ML20247A173
| ML20247A173 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/31/1997 |
| From: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20247A167 | List: |
| References | |
| NUDOCS 9805050422 | |
| Download: ML20247A173 (118) | |
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ANNUAL ENVIRONMENTAL AND EFFLUENT j
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RELEASE REPORT FOR J PERRY NUCLEAR POWER PLANT
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JANUARY 1,1997 To DECEMBER 31,1997 i
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PREPARED BY:
RADWASTE, ENVIRONMENTAL, AND CilEMISTRY SECTION
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PERRY NUCLEAR POWER PLANT CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY, OHIO 1
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l APRIL 1998 l
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1997 Annual Environmental And Effluent Relene Report S U M M A R Y A N D CO N C LU S I O NS .. .. .......................... .......... . .... . .. ........................ ...... .. I
. .. I ANNUAL EFFLUENT RELEASES- -
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM- -
LAND USE CENSUS - - -- - - - - - - - -
-2 CLAM / MUSSEL MONITORING - - - - . - -- - .. ~2 IIERBICIDE USE -- - - - - - -" -- -3 SPECIAL REPORTS - - - - - -- - -
~3 I NT R O D U CT I O N .... ...... .. .... .. .. . . .... . .... ...... .. ... . ................... ............ ......... .. 4 (
RADIATION FUNDAMENTALS- - - - - - - - - .. ~4 RADIAT1ON AND RADIOACTIVITY + - - -- - - - - ~4 UNITS OF MEASURE- - - ~ ~ - - - - - ~5 LOWER LIMIT OF DETECTION - - - - - - - -
-5 BACKGROUND RADI ATION- - - - - - -6 ANNUAL EFFLUENT RELEASES. .....................................................................................7 INTRODUCTION- - - - - - - - - ~ ~ - ~7 RELEASE
SUMMARY
- -9 METEOROLOG! CAL DATA- - - - -- - - - -15 DOSE ASSESSMENT- - - -- - - - - - - -
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ABNORMAL RELEASES - - - -
PROGRAM CHANGES AND NONCOMPLIANCE-- - - - - - 17 RADIOLOGICAL ENVIRONP 1 ENTAL MONITORING PROGRAM.... ...... ................19 INTRODUCTION- - - - - - - - ~ ~ - 19 SAMPLING LOCATION 5 - - - - - - -
-19 SAMPLE ANALYSIS- - - - -- - .
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1997 SAMPLING PROGRAM- - - - - - - - - -
~26 INTERLABORATORY COMPARISON PROGRAM- - - -- ~33 CONCLUSION - - . - - - - - - -
~35 LAND USE CENSUS -_ ................................................................................................38 INTRODUCTION- - - - ~~ - - -- - - -
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DISCUSSION AND RESULTS-- - -- - - - -
~38 CLAM / MUSSEL MONITORING ...... .. . . . ....... ........................................41 INTRODUCTION- - - - - - -
-41 CORBICULA PROGRAM- . . - - - - ~41 DREISSENA PROGRAM- - - - - ~42 (
liERBIClDE USAGE ......................................... ...............................44 S P E C I A L R E PO R TS ....... .. ... .-.... . ... ..-.... ...... ..... ....................... . .... .. ... .......... .... .. 4 5 NONCOMPLIANCE -- -- - -
-45 UNREVIEWED ENVIRONMENTAL QUESTIONS - - - -
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NONROUTINE REPORTS = - - - - -
-45 APPENDIX A: 1997 R EM P D ATA SU M M A RY . ........... ... . .... ........ ... ........................ 4 6 APPENDIX H: 19 9 8 R E M P D ATA .............. .-........... ........ ..... ........ ... ...-................... ......... 4 7 APPENDIX C: CORRECTIONS TO 1995 AND 1996 DATA........ ................................ 48 (
Table of Contents -
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1997 Annual Environmental And Effiuent Release Report
SUMMARY
AND CONCLUSIONS
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The Annual Environmental and Effluent Release Report details the results of environmental and effluent monitoring programs conducted at the Perry Nuclear Power Plant (PNPP) from January I through December 31,1997. This report meets all of the requirements in PNPP Technical Specifications, Appendix B of the PNPP Operating License (the Environmental Protection Plan, or EPP), and Regulatory Guide 1.21. Report topics include Annual Effluent Releases, Radiological
) Environmemal Monitoring, Land Use Census, Clam / Mussel Monitoring, lierbicide Use, and Special Reports.
The results of the Environmental and Effluent Programs for 1997 indicate that the operation of the PNPP did not result in any significant environmental impact.
) ANNUAL EFFLUENT RELEASES During the normal operation of a nuclear power plant, small quantities of radioactivity are released to the environment in liquid and gaseous effluents. _ Radioactive materials are also released as sohd waste.
PNPP maintains a comprehensive program to control and monitor the release of all radioactive materials from the site. All releases are strictly regulated by the Nuclear Regulatory Commission
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(NRC).
l The radioactivity released in the plant's liquid and gaseous effluents was well below applicable federal regulatory limits. The dose from plant effluents to the public was also below the applicable regulatory limits. The calculated hypothetical maximum individual dose potentially received by an individual resulting from PNPP liquid efiluents was 0.002 mrem (0.07% of the applicable limit). The hypothetical
) maximum 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 1997 is equivalent to less than one percent of the dose that on 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 1997, making 12 shipments of solid radioactive waste to a licensed burial site.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
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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 cecordance 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 years before the plant became operational. This !
) preoperational 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 ;
L sediment as well as by measuring radiation directly. j Over 800 radiological environmental samples were collected in 1997 and over 1300 analyses for !
) radioactivity were performed. The results of the REMP indicate the adequacy of the control of the release of radioactivity in effluents from PNPP. These results also demonstrate that PNPP complies I'
Summary and Conclusions Page 1
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1997 Annual Environmental And Emuent Relcase Report with all applicable federal regulations. Results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring, and direct radiation monitoring.
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o Samples of air are collected to monitor the radioactivity in the atmosphere. The 1997 results are similar to those observed in both preoperational and operational programs from prior years. Only background environmental radioactivity was detected.
o Terrestrial monitoring includes analysis of milk, produce, vegetation, and soil samples. The results of the sample analyses indicate concentrations of radioactivity similar to that found in previous
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years. For example, the average concentration of cesium 137 in soil was 218.19pCi/kg in 1997, which is at the low end of the range of 208.5 to 1104.05 pCi/kg observed during the past eleven 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.
o Aquatic monitoring includes the collection and analysis of water, fish, and shore:ine sediments. The (
1997 analyses results for water and fish sample results showed normal background concentrations of radionuclides. The results of sediment sample analyses indicated concentrations of radioactivity similar to previous years. The average concentration of cesium-137 in the sediment was $85.29 pCi/kg, which is well within the range of up to 864pCi/kg established since 1981.
o Direct radiation measurements howed no change from previous years. Indicator locations averaged (
55.22 mrem / year and control locations averaged 54.70 mrem / year. This shows that, in 1997, radiation in the area of PNPP was the same as radiation at locations greater than 10 miles away from the Plant.
Based on these results, the 1997 operation of PNPP resulted in no significant increase in the concentrations of radionuclides 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 road within a five 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 C Clam and mussel shells can clog plant piping and components that use water from Lake Erie. For this 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 Erie 1989.
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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. TheDreissena 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 preventedDreissena from causing any operational problerns at PNPP in 1997. (
Summary and Conclusions Page 2
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1997 Annual Environmental And Emuent Release Report j IIERIIICIDE 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 surveillance of herbicide applications on site and weekly general site inspections, herbicide use has not had a negative impact on the environment around the plant.
SPECIAL REPORTS
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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. One special report was submitted in 1997.
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O Summary and Conclusions Page 3 j
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z 1997 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 arourd 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. The number of neutrons in the nuclei of an element may vary. Atoms with the same number of protons but different numbers of z neutrons are called isotopes. All isotopes of the same element have the same chemical properties and many are stable or nonradioactive. An unstable or radioactive isotope of an element is called.a radioisotope or radionuclides. 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, nonradioactive state through a process known as q 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 remains radioactive is defined in terms of half-life. IIalf life is the time required for a radioactive substance to lose halfits activity through the process of radioactive decay. Italf-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.
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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 decay within the nucleus occurs. This section includes a discussion on the three main fonns of radiation produced by (
radioactive decay; alpha particles, beta particles, and gamma rays.
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.
Ilowever, if alpha particles are released inside the body, they can damage the soft internal tissues because they deposit all their energy in a small area.
Beta Particles
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Beta particles are essentially electrons and usually carry a negative electrical charge. They are much smaller than alpha particles and travel at nearly the speed of light, 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 affects primarily the skin. Because of their electrical charge, beta particles can be stopped by paper, plastic or thin metals. (
Introduction Page 4 C
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J 1997 Annual Environmental And Effluent Release Report
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Gamma Rays !
) l 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.
Potassium-40 is an example of a naturally occurringradionuclide found in all humans that decays by ,
emitting a gamma ray. l
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Interaction With Matter 1 When radiation interacts with other materials, it affects the atoms of those materials principally by j knocking the negatively charged electrons out of orbit. This causes an atom to lose its electrical l neutrality and become positively charged. An atom that is charged, either positively or negatively, is j
) called an ion. l UNITS OF MEASURE 4 Some of the units of measure used in this report require explanation. ,
) l Activity 1 i
1 Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, I radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates tha rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms j
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Smaller units of the curie are often used in this report. Two common units are themicrocurie (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 curie of activity depends on the disintegration rate. For example, one gram of radium-226 is one curie of activity, but it would require about 1.5 million grams j
) of natural uranium to equal one curie since radium-226 decays more energetically than natural uranium. l I
Dose J 1
13iological damage due to alpha, beta, and gamma radiation may result from the ionization caused by these radiations. Some types of radiation, especially alpha particles, which can cause dense local
) ionizt. tion, can result in much more biological damage for the same energy imparted as do gamma or X rays. Therefore, a quality factor munt be applied to account for the different ionizing capabilities of various types ofionizing radiation. When the quality factor is multiplied by the absorbed dose, the result 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 REM (Roentgen Equivalent Man). In temis of environmental radiation, therem is a large unit. Therefore, a smaller 1 unit, the millirem (mrem) is often used. One millirem is equal to 1/1000 of a rem.
LOWER LIMIT OF DETECTION Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD is the smallest amount of radioactive material that will show a positive result for which there can be y-confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as less than the LLD, it means that no 3 radioactivity was detected and that had radioactivity been present et (or above) the stated LLD value, it :
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l Introduction Page 5 p
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1997 Annual Environmental And Ernuent Release Report statistically would have been detected. The NRC has established values for theLLDs for environmental and effluent sample analyses.
l IIACKGROUND RADIATION Background radiation includes the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space called cosmic radiation, naturally occurring radioactive isotopes in the human body like potassium-40, decay of radioisotopes used in medical procedures, man-made
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phosphate fertilizers (phosphates and uranium are often found together in nature), fallout from nucleai 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 froa sources shown in the Background Radiation Chart (Table 1) (Source: National Council on Radiation Protection and Measurements}.
Table 1: Background Radiation Chart (
Natural Sources hian A1ade Sources Radon 55 % Medical /X-rays i1%
Cosmic 8% Nuclear Medicine 4%
Terrestrial 8% Consumer Products 3%
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internal 11 % Other (1)
(1) - Other includes 0.3%fom occupational sources, <0.3%fomfall out, <0.1%fom the nuclear fitelcycle, and 0.1%from miscellaneous 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
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environmental samples collected in the vicinity of PNPP. Some of theradionuclides normally present include:
o beryllium 7, present as a result of the interaction of cosmic radiation with the upper atmosphere, o potassium-40, a naturally occurringradionuclide normally found in humans and throughout the environment, and
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o 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 1997 Sampling Program results. Ilowever, the data on theseradionuclides are included in Appendix B: 1997 REMP Data. (
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Introduction Page 6 C
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1997 Annual Environmental And Emuent Release Report ANNUAL EFFLUENT RELEASES
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INTRODUCTION The source of radioactive material in a nuclear power plant is fission product generation (for example, I iodines, noble gases, and particulate), or neutron activation of corrosion products and water (for
) example, cobalt and tritium). The majority of the fission products generated remain within the nuclear fuel and fuel cladding. The majority of the fission products which do escape from this fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment. ,
1 During the normal operation of a nuclear power plant, small amounts of these radioactive materials are I released as liquids, gasses, and solids. PNPP was designed ard is operated in a manner which controls
) and inonitors these ef0uent releases. Emuents are controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Ef0uent programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures ,
covering all aspects of emuent monitoring.
The main objective of controlling releases is to ensure that doses are kept As Low As Reasonably f 7
Achievable mLARA). The ALARA principle applies to reducing radiation dose both to the individuals working at PNPP and to the general public. " Reasonably achievable" means that exposure reduction is based on sound operating practices and economic decisions. By practicing ALARA, PNPP minimizes health risks and possible environmental impact, and ensures that doses are maintained well below regulatory limits. l The liqu:d and gaseous radioactive waste treatment systems at PNPP are designed to collect and
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process the wastes in order to remove most of the radioacGvity. 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 release limits. Instruments are equipped with alarms and indicators in the plant control room. The alarms are set to provide warnings to alert plant operators when radioactivity levels reach a small fraction of actual limits. In addition, waste streams are sampled and analyzed to identify and quantifyradionuclides being released. Analysis results are used with Dow
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measurements to calculate the composition and concentrations ofradionuclides in emuents.
Gaseous effluent release data is coupled with on site meteorological data in order to calculate dose to the public. In areas surrounding the plant, devices maintained for the Radiological Environmental Monitoring Program constantly sample the air in tbc surrounding environment. Frequent samples of other environmental media are also taken to de aine if any radioactive material deposition has
) occurred. This program is described in detail ir .ne 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 ornonradioactive, shredding and compacting, or incinerating waste once it is identified all help to lower the volume of radioactive solid waste. Solid waste is shipped to a licensed burial site.
REGULATORY LIMITS The Nuclear Regulatory Commission limits for liquid and gaseous ef0uents were incorporated into the PNPP Technical Specifications, and subsequently into the Offsite Dose Calculation Manual. 'Ihe limits are set to comply with 10CFR20 Appendix B,10CFR50 Appendix 1 and 40CFR190. These limits
) prescribe the maximum doses and dose rates due to radioactive ef0uents resulting from the operation of PNPP. The limits are defined in several ways to limit the overall impact on prsons living near the Annual Effluent Releases Page 7
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1997 Annual Environmental And Emuent Release Report plant. Here are no other nearby fuel cycle sources therefore,40CFR190 limits were not exceeded.
The limits are described below. None of these limits were exceeded in 1997.
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Liquid Effluents
'I. The concentration of radioactive material released in liquid emuents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations (10CFR), Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2 forradionuclides 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-4 pCi/mi total activity. These values are the maximum effluent concentrations.
II.The dose or dose commitment to a member of tFe public from radioactive materials in liquid emuents released to unrestricted areas shall be limited to the following: (
- During any calendar quarter:
Less than or equal to 1.5 mrem to the total body, and Less than or equal to 5 mrem to any organ.
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During any calendar year:
Less than or equal to 3 mrem to the total body, and Less than or equal to 10 mrem to any organ.
Gaseous Effluents (
!. Dose rate due to radioactive materials released in gaseous emuents from the site to areas at and beyond the site boundary shall oe limited to the following:
Noble gases:
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Less than or equal to 500 mrem per year to the total body, and Less than or equal to 3000 miem per year to any organ.
Iodine 131, iodine-133, tritium, and for allradionuclides in particulate form with halflives greater than eight days:
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Less than er equal to 1500 mrem per year to any organ.
II. Air dose due to noble gases to areas at and beyond the site boundary shall be limited to the following:
' During any calendar quarter:
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Less than or equal to 5 mrad for gamma radiation, and Less than or equal to 10 mrad for beta radiation.
During any calendar year:
Less than or equal to 10 mrad for gamma radiation, and
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Less than or equal to 20 mrad for beta radiation.
Annual Emuent Releases Page 8
_ - _ _ _ _ - . -m _ - - _ _ _ - - -
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1997 Annual Environmental And Emuent Release Report III. Dose to a member of the public from iodine-131, iodine-133, tritium, and allradionuclides 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.
The 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
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efauents. l l
RELEASE
SUMMARY
Efnuents are sampled and analyzed to identify both the type and quantity ofradionuclides present.
) This information is combined with emuent path now measurements to determine the radioactive composition and concentration of efnuents.
Liquid Efiluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment used for the liquid depends on its physical and chemical
) properties. It is designed to reduce the concentration of radioactive material in the liquid. Liquids are Oltered to remove suspended solids, and demineralized to remove dissolved solids.
Liquid efnuent releases may be required aller collecting water from small leaks within the plant or to reduce the volume of stored water in plant systems. In both cases, the water is first processed through a liquid radioactive waste treatment system. Dose calculations are performed prior to discharge of this
) processed water to the lake to ensure regulatory compliance and that ALARA is 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 associated with different parameters is shown in Table 2.
) Table 2: Error associated with liquid effluent processes Parameter % Error Gamma analysis 10 Tritium analysis 8 ,
Strontium 89/90 analysis 10 fron-55 analysis 10
) Gross alpha analysis 10 Dilution volume 31 Discharge volume 25 Liquid waste volume 1 Liquid effluents are released intermittently and are considered " batch" releases. Table 3 provides
) information on the number and duration of these releases for 1997.
Table 4 provides information on the nuclide composition for the liquid releases. If aradionuclide was not present at a level greater than the LLD, then the value is expre> sed as "less than (indicated by <),
LLD". In each case, LLDs were met or were below the levels required by the Technical Speci0 cations /ODCM.
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Annual Effluent Releases Page 9
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1997 Annual Environmental And Effluent Release Report Table 3: Liquid batch releases item Value Number of batch releases 29 (
Total time period for batch releases (minutes) 6244 Maximurn time for a batch release (minutes) 727 Average tim? period for a batch release (minutes) 215 1
Minimum time for a batch release (minutes)
Average stream flow during periods of release of effluent into a flowing stream 1.72E+05
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(liters / minute)
Table 4: Summation of all liquid effluent releases Unit Quarter Quarter Quarter Quarter Est.
I 2 3 4 Total Error, (
A. Fission and activation products
- 1. Total releases (not Ci Note 1 5.74 E-04 3.42E-03 2.45E-03 1.00E+1 including tritium, gases, 5
alpha)
- 2. Average diluted pCi/mi N/A 2.37E-11 1.56E-10 1.02E-10 concentration during period
- 3. Percent of applicable limit % _
NA NA NA- NA "NA "- 1his trem ts Not Applicable. lhe Techmcal Specifications %)DCM do not have a limitforfission and activation products. (
B. Tritium
- 1. Total release Ci Note 1 2.60E+0 4.28E+0 5.67E-01 1.00+El
- 2. Average diluted pCi/ml N/A 1.07E-07 1.95E-7 2.36E-08 concentration during period (
- 3. Percent of applicable limit % N/A <<1% <<l% <<!%
C. Dissolved and entrained gases
- 1. Total release Ci None 7.48E-04 1.02 E-03 <LLD 1.00E+1
- 2. Average diluted pCi/ml N/A 3.09E-I l 4.64E-Il <LLD concentration during (
period
- 3. Percent of applicable iimit % N/A <<l% <<l% <<l%
D. Gross alpha radioactivity
- 1. Total release Ci Note 1 <LLD <LLD <LLD 1.00E+1
(
E. Volume of waste released liters N/A 3.06E+05 5.13E+05 6.97E+04 1.00E+0 (prior to dilution)
F. Volume of dilution water liters 3.86E+09 2.42E+10 2.20E+ 10 2.40E+ 10 2.80E+1 used during period
(
Note 1 No releases during first quarter of 1997 Annual Effluent Releases Page 10
).
1997 AnnualEnvironmental And Emuent Release Report The total number of curies of each nuclide present in liquid efiluent releases for each quarter are shown in Table 5.
Table 5: Nuclide composition of liquid emuents
) Nuclides Released Unit Quarter I Quarter 2 Quarter 3 Quarter 4 tritium Ci Note 1 2.60E+00 4.28E+00 5.67E-01 chromium Ci Note I <LLD 3.53 E-04 2.29E-04 manganese-54 Ci Note 1 <LLD 5.94 E-05 2.08E-04 iron-55 Ci Note 1 <LLD <LLD <LLD cobalt-58 Ci Note i <LLD- 3.2S E-05 1.20E-04
). Iron- 59 Ci Note 1 <LLD 2.04 E-05 <LLD cobalt-60 Ci Note 1 1.19E-04 1.00E-03 9.14 E-04 zinc-65 Ci Note 1 4.55 E-04 1.74 E-03 9.00E-04 strontium 89 Ci Note I <LLD <LLD <LLD strontium-90 Ci Note I <LLD <LLD <LLD strontium-92 Ci Note I <LLD <LLD <LLD
)
molybdenum-99 Ci Note I <LLD -<LLD <LLD technetium-99m Ci Note I <LLD <LLD <LLD iodine 131 Ci Note i <LLD <LLD <LLD iodine-133 Ci Note 1 <LLD <LLD <LLD xenon 133 Ci Note 1 7.48 E-04 9.59E-04 <tLD
)
xenon-133m Ci Note 1 <LLD <LLD <LLD cesium-134 Ci- Note 1 <LLD <LLD <LLD xenon 135 Ci Note 1 <LLD 6.00E-05 <LLD cesium-137 Ci Note 1 <LLD <LLD <LLD lanthanum-140 Ci Note i <LLD 1.46E-04 6.2 ] E-05 cerium 141 Ci Note I <LLD <LLD 2.24 E-05
). cerium-144 Ci Note I <LLD 3.44E-05 <LLD Total for period Ci Note 1 2.60E+00 4.28E+ 00 5.70E-01 Note 1 No releases during first quarter of 1997
. Gaseous Effluents
)
Gaseous effluents are made up of noble gases, iodines and particulate. The ncble gas releases are primarily a 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 emuent vents. Each of the 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 is maintained. All gaseous emuent 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.
}~ Table 6: Error associated with gaseous emuent processes Parameter % Error Noble gas analysis 11 Particulate analysis - 9 lodine analysis 12 Tritium analysis . 8
) Strontium-89/90 analysis 10 Gross alpha analysis 10 Sample flow rate 4 Emuent flow rate ' 4 Annual Emuent Releases Page 11
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1997 Annual Environmental And Effluent Release Report if a radionuclides was not present at a level greater than the LLD, then the value is expressed as "less than (indicated by <), LLD". In all cases, the LLDs met or were below the levels required by the Technical Specifications /ODCM. A summation of all gaseous releases is given in Table 7. The nuclide composition of gaseous effluents is given in Table 8. (
Table 7: Summation of all gaseous effluent releases Unit Quarter Quarter Quarter Quarter Est.
I 2. 3 4 Total Error,
% (
A. Fission and activation gases Ci 2.21 E+ 1 2.22 E+ 1 3.09E+1 1.50E+ 1 1.00 E+ 1
- 1. Total release
- 2. Average release rate for pCi/sec 2.85E+0 2.83 E+ 0 3.89E+0 1.88E+0 period
- 3. Percent of Technical % NA NA NA NA Specification limit (
"NA " Ihis item is Not Apphcable. The lechnical Specifications /UDChido not have a hmstforfission and activation products.
B. Iodines
- 1. Total Iodine-131 Ci 3.97E-03 1.99E-03 2.26E-03 8.16E-04 1.00E+1
- 2. Average release rate for pCi/sec 5.1IE-04 2.53 E-04 2.84E-04 1.03 E-04 (
period
- 3. Percent of Technical % NA NA NA NA Specification limit "NA " . Ihis item is Not Apphcable, lhe lechmcal Spec {ficationMODCAf do not have a hmstforjirion and activation products.
C. Particulate
- 1. Particulate with half-lives Ci 9.83 E-03 6.32E-03 3.13 E-03 1.01E-03 1.00E+ 1
>8 days
- 2. Average release rate for pCi/sec 1.26E-03 8.04E-04 3.94 E-04 1.27E-04 period
- 3. Percent of Technical % .NA NA NA NA (
Specification limit
- 4. Gross alpha radioactivity Ci <LLD <LLD <LLD <LLD "NA "- lhes nem is Not 4pphcable. The lechnicalSpecsjicationWUDCAf do not have a hmstforfisston and activation products.
D. Tritium Ci <LLD <LLD <LLD <LLD 1.00E+1 (
- 1. Total release
- 2. Average release rate for Ci/sec NA NA NA NA period
- 3. Percent of Technical % NA NA NA NA Specification limit "NA " 1hu ttem is Not Apphcable. The TechnicalSpectPcationWODChido not have a hmetforjission andactivation products. (
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Annual Effluent Releases Page 12
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1997 Annual Environmental And Effluent Release Report i
Table 8: Nuclide composition of gaseous effluents ground level release, continuous mode j
)' Nuclides Released Unit Quarter ! Quarter 2 Quarter 3 Quarter 4 1
- 1. Fission gases tritium Ci <LLD <LLD <LLD <LLD argon-41 Ci 8.78E-02 <LLD <LLD 1.35 E-02 krypton-85 Ci <LLD <LLD <LLD <LLD
) krypton-85m Ci 1.96E-02 2.39E-01 1.17E-01 1.32E-01 krypton-87 Ci <LLD 7.88E-01 5.79E-02 2.19E-01 krypton-88 Ci <LLD 5.86E-01 1.63E-01 1.21 E-01 xenon-131m Ci <LLD <LLD <LLD <LLD xenon-133 Ci 3.16E+00 3.42E+00 3.91 E400 1.89E+00 xenon-133m Ci 8.02 E-02 1.03 E-01 <LLD 3.63 E-02
)
xenon-135 Ci 6.98 E+00 4.35 E+00 2.27E+01 6.97E+00 xenon-135m Ci 1.18E+01 4.08E+00 3.92 E+00 2.77E+00 xenon-137 Ci <LLD 3.92E-00 <LLD 1.23E+00 i xenon-138 Ci 4.70E-03 4.73 E+00 <LLD 1.58E+00 Total for period Ci 2.21 E+01 2.22 E+01 3.09E+01 1.50E+01
).
- 2. lodines iodine-131 Ci 3.97E-03 1.99E-03 2.26E-03 8.16E-04 iodine-132 Ci 1.03 E-03 6.90E-04 4.51 E-04 3.14 E-06 iodine 133 Ci 7.77E-03 4.20E-03 3.35E-03 6.55 E-04 iodine-134 Ci 9.32 E-04 5.69E-04 5.23 E-04 <LLD
) iodine-135 Ci 4.84 E-03 3.20E-03 2.35 E-03 <LLD 1 Total for period Ci 1.85E-02 1.07E-02 8 93E-03 1.47E-03
- 3. Particulate manganese-56 Ci <LLD <LLD <LLD <LLD cobalt-56 Ci <LLD <LLD <LLD <LLD
) cobalt-60 Ci <LLD 7.92 E-07 8.65 E-06 1.93 E-06 rubidium-88 Ci <LLD- <LLD <LLD <tLD rubidium-89 Ci <LLD 1.05 E-04 <LLD <LLD strontium-89 Ci 1.04 E-04 2.23 E-05 2.82E-05 8.50E-06 strontium-90 Ci 6.76E-07 1.00E-07 <LLD <LLD strontium-91 Ci 3.8~?-04 3.18 E-04 1.25 E-04 <LLD
) yttrium-91m Ci <LLD <LLD <LLD <LLD l strontium-92 Ci <LLD <LLD <LLD <LLD I I
molybdenum-99 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD technetium-104 Ci <LLD <LLD <LLD <LLD cesium-138 Ci 3.97E-03 2.57E-03 1.18E-03 9.32E-04
) barium 139 Ci 5.18E-03 3.31 E-03 1.79E-03 7.78E-05 l
_ barium-140 Ci 8.06E-05 <LLD <LLD <LLD l lanthanum 140 ' Ci- 1.17E-04 <LLD <LLD <LLD j Total for period Ci 9.83 E-03 6.32E-03 3.13E-03 1.02E )
Annual Efiluent Releases Page 13
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1997 Annual Er.vironmental And Effluent Release Report Solid Waste Twelve shipments of radioactive waste were transpwted from PNPP for disposal in 1997. Shipments were delivered to the Barnwell, South Carolina facility. In addition, PNPP waste was sent to the.
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Barnwell disposal facility from SEG/GTS Duratek in Oak Ridge as partial shipments in conjunction with other utilities. The waste total in Table 9 below includes these shipments from SEG/GTSDuratek No irradiated fuel was transported from PNPP in 1997.
Table 9: Solid waste and irradiated fuel shipments
- 1. Solid waste shipped off site for burial or disposal (
Type of Waste Unit Annual Value Est. Total Error, %
- a. Spent resins, filter sludges, evaporator bottoms, etc. m' 53.1 25 Ci 464
- b. Dry compressible waste, contaminated equipment, m' 12.7 ~+ 25
(
etc. Ci 1.7 '
- c. Irradiated components, control rods, etc. m' O 1 25 Ci 0 d.Other(describe) None m' 0 1 25 Ci 0 C
- 2. Estimate of major nuclide composition (by type of waste)
Type of Waste Radionuclides % Est. Total Error, %
- a. Spent resins, litter sludges, evaporator bottoms, etc. Cr 51 1.1 Mn-54 1.6 Fe-55 14.8 25
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Co-58 1.3 Co-60 21.3 Zn-65 $7.4 Cs-137 1.0
- b. Dry compressible we.ste, contaminated equipment, . Mn-54 1.5 etc. Fe-55 58.2
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Co-60 .9.2 1 25 Ni-63 1.0 Zn-65 6.7 Cs-137 1.0
- c. Irradiated components, control rods. etc. None
- d. Other (desenbe) None
(
- 3. Solid waste disposition Number of Shipments (1) Mode of Transportation Destination 12 Truck Barnwell, South Carolina (I) Additionalshipments were made combined with wastefrom other utthfiesfrom SEG/G15 Duratek in Oak Ridge, Tennessee.
- 4. Irradiated fuel shipments (Disposition)
Number of Shipments Mode of Transportation Destination 0 N/A N/A
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Annual Effluent Releases Page 14
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1997 Annual Environmental And Emuent Release Report 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 meter heights. The tower also has instrumentation to measure dew point and barometric pressure.
Data is logged from the tower instrumentation into the Mete" , logical Data Processing System. This system compiles the data and calculates a variety of atmospi., carameters, communicates with the Meteorological Information Dose Assessment System, and senawata over communication links to the plant control room.
All meteorological data is maintained at PNPP and is available upon request.
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). Compliance with these concentration limits is ensured by sampling, analyzing, processing, and monitoring the effluent stream. Dose limit compliance is verified through periodic dose asi,essment 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. This person, called the " maximum individual", would incur the maximum potential dose from direct 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. The second calculation is performed considering only the areas around the plant that are not over Lake Erie (land based meteorological sectors), in which people reside. Tables 10 and 11 provide the calculated hypothetical maximum site boundary dose values to either the tctal body or worst case organ considering all meteorological sectors. Table 12 provides the calculated hypothetical maximum site boundary dose values considering only the land based sectors.
If any radionuclides was not present at a level greater than the LLD, it was nct used in dose calculations.
Table 10: 1997 Site boundary dose to maximum individual considering all sectors Effluent Organ Estimated dose (mrem) Limit % oflimit Liquid Total body 2.15E-03 3.0E+0 7.20E-02 Liquid Liver 3.86E-03 1.0E+ 1 3.90E-02 Noble gas gamma NA 6.44 E-01 1.0E+1 6.40E+00 Noble gas - beta NA 7.05E-01 2.0E+ 1 3.50E+00 Noble gas Total body 3.90E-01 5.0E+0 7.80E+00 Nobb gas Skin 9.94E-01 1.5 E+ 1 6.60E+00 lodine & particulate Thyroid 4.31 E-01 1.5 E+ 1 2.90E+00 Annual Efiluent Releases Page 15
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1997 Annual Environmental And Efnuent Release Report Table 11: 1997 Population dose considering all sectors Efiluent Organ Estimated Population Dose (person-rem)
Total body 1.40E-01 (
Liquid Liquid Thyroid 3.30E-02 Gaseous Total body 1.30E-02 Gaseous Thyroid 1.800-01 Table 12: 1997 Site boundary dose to maximum individual considering sectors on land Organ Limit % oflimit (
Effluent Estimated dose (mrem)
Liquid Total body 2.15E-03 3.0E+0 7.2 E-02 Liquid Liver 3.86E-03 1.0E+ 1 3.90E-02 Noble gas - gamma NA 6.60E-02 1.0E+1 6.60E-01 Noble gas - beta NA 6.24E-02 2.0E+1 3.10E-01 Noble gas Total body 3.69E-02 5.0E+0 7.40E-0 i Noble gas Skin 8.70E-02 1.5E+1 5.80E-01 (
lodine & particulate Thyroid 9.99E-02 1.5 E+ 1 6.7 E-01 Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time 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 it.dividual. This dose is assessed relative to theoffsite dose, and considers dilution, dispersion, and occupancy factors.
The highest hypothetical dose from liquid efnuents 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. Ratioing this exposure (
pathway to doses calculated foroffsite locations yields the dose values shown in Table 13, below.
I Table 13: Maximum dose from liquid efauents inside site boundary Quarter / Annual Total Body Dose (mrem) Organ Dose (mrem)
First Quarter 0.00E+00 0.00E+00 Second Quarter 1.84E-04 2.84E-04 (
Third Quarter 1.29E-03 2.27E-03 Fourth Quarter 6.89E-04 1.34E-03 Annual 2.15E-03 3.86E-03 Although several cases were evaluated to determine the highest hypothetical dose from gaseous efuuents to 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 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). The calculations account for this and the difference between annual average dispersion values for the on site point of concern,6.6E-5 s/m3. The maximum on site dose values generated are shown in Table 14.
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l Table 14: Maximum dose from gaseous efnuents inside site boundary Quarter / Annual Total Body Dose (mrem) Organ Dose (mrem) f 2.89E-03 8.66E-03 l First Quarter Second Quarter 3.50E-03 2.69E-02 l
Third Quarter 1.56E-02 6.12E-02 Fourth Quacter 2.40E-02 8.55E-03 (
Annual 9.99E-02 3.69E-02 Annual Effluent Releases Page 16
1 1997 AnnualEnvironmental And Ef0uent Release Report Av -tal body dose to individual members of the public is determined by combining the dose from gasew;, efHuents to the population that lives within 50 miles of PNPP (2,420,000 people), with the
) dose from liquid ef0uents to the population that receives drinking water from intakes within 50 miles "
of PNPP (18,200,00 people). The results are shown in Table 15.
Table 15: Average individuai total body dose (mrem)
Quarter /t.nnual From Gaseous Ef0uents From Liquid Ef0uents First Quarter 4.13 E-07 0.00E+00
) Second Quarter 4.58E-07 6.58E-06 Third Quarter 2.27E-06 4.73 E-05 Fourth Quarter 3.47E-06 2.42E-05 )
Annual 5.37E-06 7.69E-05 t ABNORMAL RELEASES
}
There were no abnormal releases in 1997.
PROGRAM CHANGES AND NONCOMPLIANCE Pn, gram Changes )
)
No changes were made to the Offsite Dose Calculation Manual or the Process Control Program in 1997 l 1
There was one change to the radwaste treatment system which involved revision 2 to Design Change l
Package 910155. Revision 0 and I of this design change deleted the low trip / alarm function associated with the Solid Radwaste Feed and Dewatering pump pressure switches OG51 N0035A/B and ,
) OG51N0055A/B. Revision 2 of this design change deletes the high trip / alarm associated with the Solid Radwaste Feed and Dewatering pump pressure switches OG51N0035A/B and 0G51N0055A/B. The revision of this DCP has not changed the function of the solidradwaste system.
Nonco; elbnces
)
There were three incidents when effluent monitoring instruments were inoperable for greater than the 30 day limit:
i
- 1. The Emergency Service Water Loop B radiation monitor , ID17-K0605, was out-of service from June 4,1997 until July 14,1997 which was a total of 40 days. The sample pump for this monitor 1'
) had tripped and would not reset. The pump was inspected and no problems were discovered. The pump was then reset and no further problems have been encountered. During this period of time the plant was in a forced outage which delayed the initial attention to resolving this problem.
Compensatory sampling was performed during the period of time in which the radiation monitor was out of service.
) I
- 2. The Radwaste to Emergency Service Water radiation monitor, ODl7 K606, was out of service from 7/18/97 through the end of 1997 for a total of 166 days. The monitor was taken out of service 1 due to spiking signals in the electronics of the monitor causing nuisance trips. A detailed investigation into this problem identified a problem with the ground on this instrument. The problem was corrected and the monitor has been returned to service.
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Radiological Environmental Monitoring Program Page 17
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1997 Annual Environmental And Effluent Release Report
- 3. The Radwaste High Flow Discharge Header flow Monitoi, G50-N0445, was inoperable from November 25,1997 through the end of 1997 for a total of 37 days. This monitor was originally taken out of service for a calibration surveillance however hisufficient parts were available to perform the task. Once the parts were available to replace the turbine meter the power supply transformer failed which delayed restoring the monitor to service. All maintenance activities with this monitor have now been completed and the monitor has been returned to service.
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Tnere was one situation in which information and records were not maintained as required by the Environmental Protection Plan
- 1. The Environmental Protection Plan requires that if herbicides are used on site, their use shall conform to the U. S. EPA regulations and records of applications should be made available to the NRC for a period of five years. During 1997 there were five permits issued however, only
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L information for two of these permits was submitted for closure. The information on the permits submitted for closure was incomplete and did not contain the application area or quantity of chemical used. Through conversations with individuals involved, the applications did take place.
Corrective actions are being taken to improve this program to ensure this information is properly documented with future applications.
(
Corrections to 1995 and 1996 Data The 1996 report did not contain information that demonstrated compliance with 40CFR190. There were no other nearby fuel cycle sources, therefore,40CFR190 limits were not exceeded.
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- The 1995 and 1996 reports did not contain information for total flow during periods ofliquidradwaste discharges. The amended information for the tables for 1995 and 1996 are contained in appendix C.
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Radiological Environmental Monitoring Program Page 18
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) l 1997 Annual Environmental And Effluent Release Report l
l l.
) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM INTRODUCTION
) The Radiological Environmental Monitoring Program (REMP) was established at PNPP for several l reasons. First, it verifies the adequacy of plant design and operation to control radioactive materials l
and limit effluent releases. Second, it assesses the radiological impact, if any, that the plant has had on -
the surrounding environment. %!rd, it ensures compliance with regulatory guidelines. The REMP is conducted in accordance with the PNPP Operating License, Appendix B, Technical Specifications and the ODCM. REMP requirements were established by the Nuclear Regulatory Commission (NRC).
A wide variety of samples is collected as part of the PNPP REMP. The selection of sample types, i sampling locations, and sample collection frequency are based on many things. Potential pathways for j the transfer of radionuclides through the environment to humans, sample availability, local
)
meteorology, population characteristics, land use and NRC requirements are all considered. f
) 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 time. All samples are packaged on site, then shipped to an independent vendor laboratory for analysis. The vendor laboratory analyzes the samples and reports results to the PNPP Environmental Unit staff, the Lake County General llealth District, and the State of Ohio Department ofitealth.
) 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 these last two media were not required by the NRC, 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 same 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 future samples are desired. Also in 1995, the frequency for collecting soil samples was changed from quarterly to biannually.
SAMPLING LOCATIONS
) REMP samples are collected at numerous locations, both on site and up 10.22 miles away from the plant. 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. His
) comparison allows naturally occurring background radiation to be taken into account when evaluating any radiological impact PNPP 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 Technical Specifications and 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 Radiological Environmental Monitoring Program Page19
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1997 Annual Environmental And Emuent Release Report are discussed in more detail below. Sample types and beations that are required by the Technical Specifications and ODCM are shown in BOLD in Table 16.
Table 16: REMP sampling locations
- Description Miles Direction Media (l)
I liaines Rd. 3.4 ENE TLD, AIR 2 Site Boundary 0.7 E TLD 3 Meteorological Tower 1.0 SE TLD, AIR, SOIL (
4 Site Boundary 0.7 S TLD, AIR, SOIL 5 Quincy Substation 0.6 SW TLD, AIR 6 Concord Service Center 11.0- SSW TLD, AIR, SOIL, VG 7 Site Boundary 0.6 NE TLD, AIR, SOIL, VG 8 Site Boundary 0.8 E TLD 9 Site Boundary 0.7 ESE TLD, SOlL 10 Parmly Rd. 0.8 SSE TLD 11 Parmly Rd. 0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD, SOIL 13 Madison-on-the-Lake 4.7 ENE TLD 14 Ilubbard Rd. 4.9 E TLD (
15 Eagle Substation 5.1 ESE TLD 16 Dayton Rd. 5.0 SE TLD 17 Chadwick Rd. 5.2 SSE TLD 18 Blair Rd. 5.0 S TLD 19 Lane Rd. 5.3 SSW TLD 20 Nursery Rd. 5.3 SW TLD (
21 liardy Rd. 5.1 WSW TLD 22 Main St. 6.9 SW TLD 23 liigh St. 7.9 WSW TLD 24 St. Clair Ave. 15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW SEDIMENT, FISil
(
26 OtTshore Redbird 4.2 ENE SEDIMENT 27 Offshore - Fairport Harbor 7.9 WSW SEDIMENT 28 CEI Ashtabula Plant Intake 22.0 ENE WATER 29 River Rd. 4.3 SSE TLD 30 Lane Rd. 4.8 SSW TLD 31 Wood and River Rd. 4.8 SE TLD (
32 Offshore - Mentor 15.8 WSW SEDIMENT, FISil 33 River Rd. 4.5 S TLD 34 PNPP Intake 0.7 NW WATER 35 Site Boundary 0.6 E TLD, AIR, SOIL, VG 36 Lake County Water Plant 3.9 WSW TLD, WATER 37 Gerlica Farm 1.5 ENE FOOD PRODUCTS (
41 Clark Rd. 1.1 SW TLD 42 Parmly Rd. 0.8 S TLD, VG 43 Parmly Rd. 1.0 SSE TLD 45 Clark Rd. 0.9 SSW TLD 51 Retteer Milk Farm 9.6 S MILK 53 Neff Perkins 0.5 WSW TLD (
$4 Itale Rd. School 4.6 SW TLD Radiological Environmental Monitoring Program Page20
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_ - - . - - , - - - - - . - - - - _ - - - . - - - . - , - . , - - . - - - - - - - - - - - , . - - - - - - - - - - - - - , - - - - - - - - - - . , - - _ - - - - , - . - - - - , - - - . - - - - , . - - - - - , - - - - - , - - - - - . - . - - - - - - - - - - - - - - . - . - - - - . - - ~ - - . - - - - - .
) I 1997 Annual Environmental And Ernuent Release Report i
- Description Miles Direction Media (1) 55 Center Rd. 2.5 S TLD l
) 56 Madison High School 4.0 ESE TLD l 58 Antioch Rd. 0.8 ENE TLD 59 Lake Shoreline at Green Rd. 4.0 ENE WATER 60 Lake Shoreline at Perry Park 1.0 WSW WATER 61 Keller Milk Farm 7.4 SE MILK ;
63 Minor Stream Mouth 0.08 NNE SEDIMENT j
)- 64 Northwest Drain Mouth 0.09 NW SEDIMENT l 65 Major Stream Mouth 0.18 W SEDIMENT 70 II&ll Farm Stand 16.2 SSW FOOD PRODUCTS 71 Mosley Farm 7.9 SE MILK S 77 Orosz Farm 1.2 E FOOD PRODUCTS
} VG = Vegetation (1) AIR = Air Iodine and Particulate TLD = Thermoluminescent Dosimeters (2) Sample location 62 was removed since the farmer was nu lager growing produce. Sample I location 37 was then added as the required ODCM locatica. The change to the ODCM was effective 1/5/98 and therefore is not a listed ODCM change for 1997. 1
) SAMPLE ANALYSIS l
When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation andradionuclides present. The major analyses that are perfonned are discussed below.
)
Gross beta analysis measures the total amount of beta emitting radioactivity present in a sample. Beta .
radiation may be released by many differr ntradionuclides. Since beta decay results in a continuous )
energy spectrum rather than the discrete energy levels or " peaks" associated with gamma radiation, . j 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 specifieradionuclides. Gross beta analysis primarily acts as a tool to l
) identify samples that may require further analysis. I i
Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma i spectral analysis identifies each radionuclides present in the sample that emits gamma radiation, and the }
amount of radioactivity associated with it. Each radionuclides has a very specific " fingerprint" that )
allows for accurate identification.
{
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 separation. I l
Tritium analysis measures the amount of theradionuclide tritium (H-3) present in a sample. Tritium is i
) an isotope of hydrogen that emits low energy beta particles. Tritium occurs naturally and is also man- i made, j 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 1 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 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 Radiological Environmental Monitoring Program Page21
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(
1997 Annual Environmental And Eruuent Release Report the TLD is heated, the phosphor releases the stored energy as light. The amount of light 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. (
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) l REMP sampling locations between two and eight miles from the plant site.
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Radiological Emironmental Monitoring Program Page 25
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r_ _ . _ _ _ ._. __ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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1997 Annual Environmental And Effiuent. Release Report Table 17 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 1997.
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Table 17: Analyses performed on REMP samples.
Sample Type Frequency Analyses Performed Atmospheric Monitoring Airborne Particulate Weekly Gross Beta Quarterly Gamma Spectral Airborne Radiciodine Weekly Iodine-131 (
Terrestrial Monitoring Milk Bi/ Monthly Gamma Spectral, Iodine-13 i Food Products Monthly Gamma Spectral Vegetation Monthly Gamma Spectral Soil Biannually Gamma Spectral Aquatic Monitoring (
Water Monthly Gross Beta, Gamma Spectral Quarterly Tritium Fish Biannually Gamma Spectral Sediment Biannually Gamma Spectral Direct Radiation Monitoring Gamma Dose (
TLD Quarterly Annually Gamma Dose Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD is 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 C
of a sample 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 ODCM table values. The NRC has
! established the values for the LLDs for REMP sample analysis. The vendor laboratory was able to comply with those values in 1997.
C 1997 SAMPLING PROGRAM 1
l The contribution ofradionuclides to the environment resulting from the operation of PNPP is assessed by comparing results from the 1997 program withpreoperational data (i.e., data from before 1986),
operational data from previous years, and control location data. The 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: 1997 REMP Data Summary and j Appendix B: 1997 REMP Data, for detailed results. The NRC requires special reporting if sample l analysis results exceed set limits. No values exceeded these reporting levels in 1997.
i Program Changes
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The following program change occurred in 1997.
July Food product sample location # 62 was withdrawn from the program since thefarmer decided to no longer grow produce. Backup location # 37 now replaces # 62 and meets ODCM requirements.
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l Radiological Environmental Monitoring Program Page26 ,
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1997 Annual Environmental And Effluent Release Report Missed Samples On occasicn, samples cannot be collected. This can be due to a variety of events, including equipment malfunction, animal husbandry practices, lost shipments, or vandalism. Table 18 provides information on samples missed in 1997, Table 18: Missed REMP samples.1997 Media Location Date Reason Missed Food Products All April-July Vegetables not ready for harvest Food Products # 62 May Farm withdrew from program Food Products # 37 August Crop died due to lack of rain Grass All April Insufficient growth Grass #6 May, June, September Insufficient growth Grass # 42 August Insufficient growth Lake Water # 59,# 60 January Lake shoreline covered with ice Milk # 61 January, February, March, Drying period for goats (1)
October, November, December Sediment # 63 May, October High take level, no access Sediment # 65 October High lake level, no access TLD # 23 Annual Lost in field (2)
TLD # 23 First Quarter Lost in field (2)
(1) The dryingperiodfor goats is an annual occurrence. Goats, unlike cows, cannotproduce milk allyear.
(2) Missing TLDs can be the result ofvandalism. At locations where vandalism has been idennfied as a recurringproblem, the TLO is relocated Loss of the TLDs listedabove was unusual; thq were not relocatedas a result of this sir.gle event. The loss oftwo TLD 's at location 23 was classified as a single event since they were located together andlost at the same time.
Events may also occur which prevent a sample from being collected in the normal way, or prevent a complete sample from being collected. The following is a discussion of these events for 1997.
Food There were no food products collected during the months of April through July because the local vegetable crop was not ready to harvest. Sample point number 62, which was a required sample point in the ODCM, withdrew from the program by deciding not to grow produce. The alternate point, for location number 62, was location number 37 which lost all crops due to lack of rain. This problem was not discovered until the growing season was past, preventing alternative locations to be established in the 1997 season. The ODCM has since been revised to establish location number 37 as the required point, and an additional backup location has been chosen to ensure samples are available in the 1998 growing season.
Water The weekly grab samples could not be collect:d from locations 59 and 60 during January due to ice on shoreline.
Grass The grass for all of the sample locations could not be collected during April due to lack of growth. In addition, grass samples were not collected for Location 6 during (May, June, September) and location 42 (August) due to grounds personnel inadvertently mowing area set aside for sampling.
Sediment Recent years has seen the lake level rise causing the access to locations 63 and 65 to be unsafe.
Radiolt.'ical Environmental Monitoring Program Page27
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1997 Annual Environmental And Ernuent Release Report Atmospheric Monitoring
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AIR Air sampling is conducted to detect any increase in the concentration of airborneradionuclides. Five locations (four indicator and one control), are required by the PNPP Technical Specifications /ODCM.
Air 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 collectparticulates, and charcoal cartridges, to adsorb iodine. The saraples are collected on a weekly basis,52 weeks a year, from each of seven air sampling stations. Six of the locations are within four miles of the plant site; the seventh is used as a (
control location and is eleven miles from PNPP.
Air samples are analyzed weekly for gross beta, iodine, and by gamma spectral analysis (quarterly). A total of 364 of each type of air sample (particulate and iodine) was collected in 1997.
Gross beta activity was detected in all air samples and ranged up to 0.05 pCi/m3. The annual average (
concentration of gross bets at both indicator and control locations was 0.02 pCi/m3. Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations, as shown in Figure 5.
Except for naturally occurring beryllium-7, noradionuclide was identified in the gamma spectral analysis above the LLD. Iodice-131 was not detected in any sample above the LLD of 0.05 pCi/m3. (
0.03 fulndicator
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Terrestrial Monitoring
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Collecting and analyzing samples of milk, food products and vegetation provides data to assess the build-up of radionuclides that may be ingested by humans. The data from soil samples provides information on the deposition ofradionuclides from the atmosphere. Neither vegetation nor soil samples are required by the PNPP Technical Specifications /ODCM.
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Radiological Environmental Monitoring Program Page28
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1997 Annual Environmental And Efauent Release Report .
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MILK l Samples of milk are collected once each month from November through March, and twice each month 1
) from April through October. Sampling is increased during the summer because animals usually feed j outside on pasture and not on stored feed. The PNPP REMP includes three 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, food product sampling (discussed below) was i 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.
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Milk samples are analyzed for iodine and by gamma spectral analysis. A total of 49 milk samples were 1 collected in 1997. 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 belowLLDs in all samples collected. The results for potassium-40 were similar at indicator and control locations, as expected.
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FOOD PRODUCTS )
Food products can provide a direct pathway to humans by ingestion. They can absorbradionuclides j from atmospheric deposition on soil or from irrigation water drawn from a lake or pond receiving i
airborne or liquid eftiuents. Also, radionuclides in the soil may be absorbed by the roots of the plants I and become incorporated into the edible portions. Because there is not a sufficient number of milk l
) sampling locations, the PNPP f.LMP is required to include two food product indicator locations and one control location. Food poducts are collected monthly during the growing season from three farms in the vicinity of PNPP. The control location for food products is 16.2 miles from PNPP, A total of 9 food product samples were collected in 1997 and analyzed by gamma spectral analysis.
Seven food products were collected which included: cabbage, broccoli, caulitiower, dill, beet greens,
) and turnip greens. Beryllium-7 and potassium-40, naturally occurringradionuclides, were found in several samples, as expected. No other radionuclides were detected above the LLDs.
VEGETATION Vegetation (grass) was collected monthly during the growing season from four locations (three indicator and one control) in 1997. Grass is clipped from open areas using standard lawn trimming
) equipment. The control location for vegetation is eleven miles away. A total of 20 grass samples were collected in 1997 and analyzed by gamma spectral analysis. Two naturally occurringradionuclides were detected: beryllium-7 and potassium-40. No otherradionuclides were detected above the LLDs.
SOIL Soil samples are collected biannually from seven locations (six locations and one control). The control
) location is eleven miles away. Only the top inch of soil is sampled in an effort to identify possible trends in the local environmentalradionuclide concentrations.
Fourteen soil samples were collected in 1997 and analyzed by gamma spectral analysis. One naturally occurring radionuclides, potassium-40 was detected in the samples, as expected. Cesium-137 activity was detected in all samples and ranged from 152.76 - 405.96pCi/kg. The annual average concentration of cesium 137 was 230.20pCi/kg at the indicator locations and 158.11 pCi/kg at the
).
control location. For all sample sites, the annual average concentrations were similar to those measured in previous years (Figure 6). The downward trend apparent in the figure represents the decrease in cesium-137 deposition from atmospheric weapons testing in the 1960's and '70's.
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Radiological Environmental Monitoring Program Page29
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1997 Annual Environmental And Efnuent Release Report 1200 1 1000 S
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Figure 6: Annual average concentration of cesium-137 in soil The difference between indicator and ~ontrol location results is not surprising since the presence of radionuclides in soil is so dependent on site-specific factors such as soil type and drainage. These 4 factors determine the ability of the soil to attract ions. For example, differences in soil types at the six indicator locations in 1997 resulted in cesium.137 concentrations ranging from 162.07pCi/kg to 405.96 pCi/kg.
Aquatic Monitoring O
Radionuclides may be present in Lake Erie from many sources (other than PNPP) including atmospheric deposition, run-off/ soil erosicm, and releases of radioactivity in liquid efauents from hospitals, universities or other industrial facilities. These sources provide two forms of potential radiation exposure, external and internal. External exposure can occur from contact with water or shoreline sediments. Intemal exposure can occur from ingestion ofradionuclides, either directly from drinking the water, or as a result of the transfer ofradionuclides through the aquatic food chain to the S eventual consumption of aquatic organisms, such as Osh. To monitor these pathways, PNPP samples water, shoreline sediments, and fish.
WATER Water is sampled from five locations along Lake Erie in the vicinity of the PNPP as required by the PNPP Technical Specifications /ODCM. Samples from three locations are collected using composite G sample pumps. The pumps are designed to collect water at regular intervals and composite it in a sample 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.
Fifty-eight water samples were collected and analyzed for gross beta activity and by gamma spectral O analysis in 1997. From these, monthly samples werecomposited into quarterly samples and analyzed for tritium. Gross beta activity was detected in 6 of 58 samples collected (for all locations) and 1 of 11 samples for control locations. The concentration range for samples with detectable activity (i.e., above ODCM LLD) ranged from 3.39 - 6.81 pCi/l. The annual average concentration of gross beta was 4.39 pCi/l at the indicator locations and 6.81 pCill at the control location using the mean of values > LLD.
The mean using the LLD value for samples with activity less than the LLD resulted in the annual g average concentration of gross beta at 3.14 pCill at the in&cator location and 3.35 pCi/l at the control location. (Figure 7).
Radiological Environmental Monitoring Program Page30 C
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1997 Annual Environmental And Effluent Release Report The signincant difference between pre-1988 data and post-1988 data has been attributed to a change in vendor laboratories in 1987/1988. A comprehensive explanation is provided in the 1988 Annual
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Environmental Operating Repcrt.
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) No radionuclides were detected by gamma spectral analysis above the LLD. Tritium was not detected in any of the 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 2,200pCill.
SEDIMENT Sampling lake bottom sediments can provide an indication of the accumulation ofundissolved
) radionuclides which may lead to internal exposure to humans through the ingestion of fish, through resuspension into drinking water, or as an external radiation source from shoreline exposure to fishermen and swimmers. Although only one location is required by the PNPP Technical Specification
/ ODCM, sediment is sampled twice each year from seven locations, two 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. Eleven sediment samples were collected in 1997 and analyzed by
) gamma spectrometry. The predominantradionuclide 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 six samples and ranged from 218.57 - 1,203.30 pCi/kg. The annual average concentration was 394.12 pCi/kg at the indicator locations and 967.64 pCi/kg at the control location. These are within the range of concentrations measured in previous years (Figure 8).
)
The changes in cesium-137 concentration from year to year may be related to the moven ent of sediment on the lake bottom. Wave action and currents can cause signincant sediment rnovement 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, as Figure 8 demonstrates.
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Radiological Environmental Monitoring Program Page31
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Figure 8: Annual average concentration of cesium 137 in sediment
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FISil Fish are analyzed primarily te quantify the dietaryradionuclide intake by humans, and secondarily to serve as indicators of radioactivlty in the aquatic ecosystem. Fish are collected from two locations, twice each year as required by the Technical Specifications /ODCM Important 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-seven fish samples were collected in 1997 and analyzed by gamma spectral analysis. Eleven species of fish were represented, including walleye, drum,smallmouth bass, carp, white sucker, white perch, yellow perch, redhorse sucker, white bass, rainbow trout,sheephead, and gizzard shad. As expected, naturally occurring potassium-40 was found in all samples. No otherradionuclides were detected above the LLD. (
Direct Radiation Monitoring THERMOLUMINESCENT DOSIMETERS 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 plani. 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 annually.
A total ot'250 TLDs were collected and analyzed in 1997. This includes 222 collected on a quarterly (
basis, and 28 collected annually, in 1997, the annual average dose for all indicator locations was 55.22 mR, and 57.40 mR for all control locations. The TLD results are higher prior to 1988 due to a change in vendor laboratory services. A comprehensive explanation of the difference is provided in the 1988 Annual Environmental Operating Report.
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Radiological Environmental Monitoring Program Page32
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. I 1997 Annual Environmental And Erliuent Release Report 1
25
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Figure 9: Average dose per quarter l
INTERL.A13 ORATORY COMPARISON PROGRAM l
The purpose of the interlaboratory Cross-Check Comparison Program is to provide an independent
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check on the vendor laboratory's analytical procedures. Samples with a known concentration of necific 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 results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures.
) In 1997, the vendor laboratory analyzed 42 samples of water for this program. All results were within the 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 Interlaboratory Comparison Program, the vendor laboratory periodically conducts an intemal cross-check program for dosimeters. The Eleventh
) Internationalintercomparison of Environmental Dosimeters was conducted in 1997 and wasoragnized by the Department of Energy's Environmental Measurements Laboratory in collaboration with 13rookhaven National Laboratory and the National Institute of Standards and Technology. Results for the Eleventh Internationalintercomparison were originally reported in error. The results are being re-cvaluated and will be reported in 1998 report.
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Radiological Environmental Monitoring Program Page33
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1997 Annual Environmental And Emuent Release Report 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 quantity is not known by the sample analyst). Table 20 shows the results of this nrogram for 1997. No samples were outside the g acceptable range. All results are expressed in pCi/l excs< air filter results, which are in pCi/ filter.
Table 19: 1997 EPA Cross-Check Intercomparison Program resu,'s.
Date Sample Analysis Vendor Result EPA Value Acceptable Range
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Type Jan. Water Sr-89 9.7 t 0.6 12.0 5.0 3.3 -20.7 Sr-90 24.0 1.0 25.0 5.0 16.3-33.7 Gross Alpha 10.0 1.4 5.2 5.0 0.0 - 13.9 Gross Beta 15.8 2.0 14.7 5.0 6.0 -23.4 Feb. Water I 131 86.0 2.0 86.0 9.0 70.4 -101.6 (
I-131 79.3 2.0 86.0 9.0 70.4 - 101.6 Ra-226 6.7 0.2 5.9 0.9 4.3-7.5 Ra 228 8.4 t 1.1 8.2 ! 2.I 4.6 - 11.8 Uranium 26.5 1.3 27.0 3.0 21.8 -32.3 Mar. Water H-3 7,594.0 279.7 7900.0 790.0 6529.4 - 9270.6 Apr. Water Gross Alpha 44.3 1.6 48.0 12.0 27.2 - 68.8 (
Ra-226 10.7 0.9 13.0 2.0 9.5 - 16.5 Ra 228 4.7 0.4 3.1 0.8 1.7 - 4.5 Note 1 Uranium 26.8 0.3 24.0 3.0 18.8 - 29.2 Co-60 21.7 0.6 21.0 5.0 12.3 - 29.7 Cs-134 27.3 1.2 31.0 5.0 22.3 - 39.7 Cs-137 21.7 1.5 22.0 5.0 13.3 30.7 (
Gross Beta 98.2 2.1 102.1 15.3 75.6 - 128.6 Sr-89 21.3 1.2 24.0 5.0 15.3 - 32.7 Sr-90 12.7 0.6 13.0 5.0 4.3 21.7 Jun. Water Ba-133 24.7 t 1.2 25.0 5.0 16.3 - 33.7 Co-60 18.7 0.6 18.0 5.0 9.3 -26.7
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Cs-134 19.7 0.6 22.0 5.0 13.3 - 30.7 Cs-137 52.0 2.0 49.0 5.0 40.3 -57.7 Zn-65 101.0 2.0 100.0 10.0 82.7 I17.3 Ra 226 2.7 0.1 3.0 0.5 2.1 - 3.9 Ra-228 2.3 0.3 3.1 0.8 1.7 - 4.5 Uranium 38.1 1.0 40.3 4.0 33.4 - 47.2 (
Jul Water Sr-89 37.7 3.2 44.0 5.0 35.3 - 52.7 Sr-90 16.0 t 1.0 16.0 5.0 7.3 - 24.7 I-131 10.7 1.2 10.0 6.0 0.0- 20.4 Gross Alpha 3.1 0.3 - 3.1 5.0 0.0 - 11.8 Gross Beta 13.9 0.2 15.1 5.0 6.4 -23.8 Aug. Water H-3 11,348.7 1 241.4 11,010.0 1 9,099.8-12,920.2 (
l.101.0 Sept. Water Ra-226 20.0 t 0.8 20.0 3.0 14.8 - 25.2 Ra 228 7.0 0.1 8.0 2.0 4.5 - 11.5 Uranium 5.0 0.1 5.1 3.0 0.0 - 10.3 Nov. Water Ba-133 97.3 5.0 99.0 10.0 81.7 - 116.3
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Co-60 28.3 t 1.7 27.0 5.0 18.3 - 35.7 Cs 134 9.7 1.0 10.0 5.0 1.3 - 18.7 Radiological Environmental Monitoring Program Page34
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1997 Annual Environmental And Eftluent Release Report Date Sample Analysis Vendor Result EPA Value Acceptable Range Type
)- Nov. Water Cs-137 78.0 3.5 74.0 5.0 65.3 - 82.7 f
Zn-65 76.7 2.1 75.0 8.0 61.1 - 88.9 i Note i This analysis uns repeated with the technician under observation of the Lab Supenhor. The results of the reanalysis
. was 3.1 + 0.3 which uas within the acceptable range.
) CONCLUSION !
l No unusual radionuclides concentrations or exposure levels were detected during 1997. Atmospheric monitoring results were consistent with past results. The prevalentradionuclide in air was beryllium-7 which is naturally occurring. Naturally occurring potassium-40 was detected in all terrestrial samples, as expected. Cesium-137 was detected in soil and is the result of fallout from weapons testing. The
) concentrations were similar to those measured in previous years and are not related to plant operation.
There was no significan' change in radionuclides concentrations at indicator locations for aquatic samples in 1997. Cesium 137 was detected in sediment. Results were within the range of past data.
Finally, direct radiation measurements are consistent with past data.
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Radiological Environmental Monitoring Program Page35 y
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1997 Annual Enviroenental And Emuent Release Report Table 20: 1997 Vendor " spiked" sample results Date Sample Analysis Result Known Value Acceptable Range
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Jan. Water Th-230 3.120 0.104 3.070 1.842 - 4.298 Th-232 3.355 0.108 3.070 1.842 - 4.298 Feb. Water Gross Beta 43.881 1.305 41.860 31.860 -51.860 Milk Cs-134 48.649 4.940 56.400 46.400 - 66.400 Cs-137 54.700 8.450 52.300 42.300 - 62.300 Sr-89 49.849 7.940 40.030 30.030 -50.030 (
Sr-90 48.856 1.740 50.300 40.240 - 60.360 Water H-3 27229.744 1 28234.000 22587.200 -
452.056 33880.800-Co-60 65.219 8.790 62.950 $2.950 - 72.950 Cs 134 52.996 8.000 56.430 46.430 - 66.430 Cs-137 60.419 12.900 52.320 42.320 - 62.320 (
I-131 72.182 1.009 66.300 53.040 - 79.560 1-131(g) 68.816 14.800 66.300 -39.780 - 76.300 Charcoal Canister 1-131(g) 1.171 0.023 1.080 0.648 - 1.512 Air Filter Gross Beta 6.320 0.041 5.740 0.000- 15.740 Water Ra-226 19.770 0.189 17.300 12.110 -22.490 Ra-228 36.784 2.571 3!.300 21.910- 40.690 (
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Sr-90 35.822 2.020 33.520 26.816 - 40.224 1129 15.525 0.854 14.942 2.942 - 26.942 Fe-55 1.418 0.530 1.535 0.000 - 21.535 Mar. Air Filter Cs-137 2.151 0.025 1.900 1.140 -2.660 Apr. Milk Cs-134 50.282 8.920 53.600 43.600 - 63.600 Cs-137 56.090 14.900 52.100 42.100 - 62.100 Water Co-60 54.077 4.280 51.300 41.300- 61.300 Cs-134 47.636 4.150 53.200 43.200 - 63.200 Cs-137 60.688 2 5.760 52.100 42.100 - 62.100 Gross Alpha 34.554 2.677 41.300 20.650 - 61.950 Gross Beta 38.729 1.658 41.700 31.700 - 51.700 (
H-3 25445.478 1 26257.000 21005.600 -
428.384 31508.400 May Fish Cs-134 0.199 0.020 0.222 0.133 - 0.311 Cs-137 0.234 0.037 0.227 0.136- 0.318 Jun Water 1-131 76.174 0.776 71.800 57.440 - 86.160 1131(g) 66.587 8.750 71.800 43.080 - 81.800 (
Milk I 131 79.851 0.833 71.800 57.440 - 86.160 1131(g) 78.887 7.750 71.800 43.080 - 81.800 Charcoal Canister I-131(g) 81.869 0.317 76.600 45.960 - 86.600-July Milk Cs-134 38.265 5.450 39.500 29.500 -49.500 Cs-137 46.472 10.600 41.500 31.500 - 51.500 1-131 75.247 0.831 83.230 66.584 - 99.876 (
I-131(g) 84.872 7.010 83.230 49.938 - 93.230 Sr-90 33.610 1.430 33.210 26.568-39.852 Water Co-60 26.270 4.360 24.900 14.900 - 34.900 Cs-134 36.591 5.040 39.540 29.540-49.540 Cs-137 45.552 7.770 41.480 31.480 - 51.480 1131(g) 85.221 9.660 83.230 49.938 - 93.230 (
Sr-90 36 285 1.629 33.210 26.569 - 39.852 Radiological Environmental Monitoring Program Page36
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1997 Annual Environmental And Emuent Release Report I Date Sample Analysis Result Known Value Acceptable Range July Milk I-131(g) 84.870 7.010 83.230 49.938 - 93.230
) Water Fe-55 4.548 0.640 5.477 0.000 -25.477 f
11-3 ' 41026.000 1 41578.000 33262.400 -
329.000 49893.600- j Gross Alpha 49.266 2.081 41.305 20.653 - 61.958 l Gross Beta 44.450 1.334 41.406 31.406 - 51.406 )
Fish Cs-134 0.641 0.030 0.700 0.420 - 0.980
) Cs-137 0.632 0.042 0.527 0.316 - 0.738-Oct. Water Co-60 30.424 7.530 33.642 23.642 - 43.642 l Cs-134 37.410 6.690 - 36.086 26.086 -46.086 Cs 137 52.845 1 11.300 41.221 31.221 - 51.221 Note 1 1-131 78.126 1.201 78.302 62.642 - 93.962
) Milk Cs-134 15.166 3.250 18.043 8.042-28.043 Cs-137 91.110 8.370 82.440 72.440 - 92.440 I-131 73.529 1.253 78.320 62.642 - 93.962 1-131(g) 74.613 8.810 78.302 46.981- 88.302 Sr-89 31.281 4.601 39.490 29.490 -49.490 Charcoal Canister 1-131(g) 0.450 0.050 0.440 0.264 - 0.616
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Air Filter Gross Beta 3.080 0.030 3.040 1.824 - 4.256 (ss)
Nov. Fish Cs-134 0.306 0.025 0.318 0.191 - 0.445 l Cs-137 0.738 0.049 0.649 0.389 - 0.909 ,
Water Gross Alpha 51.420 6.385 41.280 20.640 - 61.920 l
) Gross Beta 48.938 3.735 43.164 33.164 - 53.164 ;
Dec. Water Gross Alpha 40.480 4.598 41.280 20.640 - 61.920 Co-60 44.900 8.290 42.080 32.080-52.080 Cs-134 40.010 7.010 37.850 27.850 - 47.850 (1) The Cs-137 spike is suspect. No errors werefound in the spectroscopyprogram and the Cs-
) 134 and Co-60 test results on the same sample were very good. Sample restdts prepared with a newstandardare acceptable.
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Radiological Environmental Mor.itoring Program Page37
1997 Annual Environmental And Effluent Release Report LAND ~USE CENSUS
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INTRODUCTION Each year a land use census is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land. The Land Use Census is required by tne PNPP Off Site Dose Calculation Manual, Section 3/4.12.2. The (
information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological 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 mappirg the location of the nearest resident, milk animal, and vegetable garden in each of the meteorological sectors that is over land. The 1997 Census was conducted August 12 - 14.
The information has been tabulated below; garden, residence and milk animal locations are plotted on the map on page 38. Note that the W, WNW, NNW, NW N, and NNE sectors extend over Lake Erie, and therefore, were not included in the survey.
DISCUSSION AND RESULTS (
In general, the predominant land use within the census area continues to be rural! agricultural.
There was no change in nearest residences within five miles of the plant in 1997. Table 21 lists the nearest residence by sector. There were no changes tc. the nearest milk animal location in 1997.
Information on the milk animal is shown in Table 22. There were no changes to nearest gardens (
recorded during the 1997 census. Table 23 lists the nearest gardens that occupy at least 500 square feet.
Table 21: Nearest residence by sector Sector Location Address Miles from PNPP X/Q Value Map (Sec/m3) Locator #
NE 4385 Lockwood 0.8 2.17E-6 I
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ENE 4585 Lockwood 1.0 1.13 E-6 2 E 2684 Antioch 1.1 6.77E-7 3 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 1.11 E-6 8 SW 3440 Clark 1.2 4.98 E-7 9 WSW 2815 Perry Park 1.0 1.72E-6 10
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Land Use Census Page 38
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1997 Annual Environmental And Emuent Release Report Table 22: Milk animal Sector Location Address Miles from PNPP Map
). Locator #
S 3588 River 4.8 18 l
l Table 23: Nearest garden by sector
) Sector Location Address Miles from D/Q Value per m2 Map PNPP Locator #
NE 4398 Lockwood 0.8 1.09E-8 11 ENE 4630 Lockwood 1.2 4.11E-9 12 ;
E 2656 Antioch 1.2 4.56E-9 13 i
) ESE 2774 Antioch 1.2 3.41E-9 4 SE 4679 Middle Ridge 1.9 1.31 E-9 14 SSE 3119 Parmly 0.9 2.30E-9 15 S 3121 Center 0.9 1.31 E-8 7 SSW 3515 N. Ridge 1.7 1.19 E-9 16 SW 3440 Clark 1.2 2.24 E-9 9 )
)' WSW 2975 Perry Park 1.2 2.31 E-9 17
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~ Land Use Census Page 39
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1997 Annual Environmental And Efnuent Release Report l CLAM / MUSSEL MONITORING
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INTRODUCTION Sampling for benthic macroinvertebrates (clams and mussels) has been conducted in Lake Erie in the vicinity of PNPP since 1971. The clam / mussel program currently focuses on two species: Corbicula
) fluminea (Asiatic clam) and Dreissena polymorpha (zebra mussel).
CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to an NRC bulletin and concerns of the Atomic Safety and Licensing Board. The current monitoring is part of the Environmental Protection
- f. Plan (Operating License, Appendix D). The program consists of periodic sampling of areas at both the PNPP and Eastlake Power Plants. Its purpose is to detect Corbicula, should l' 2ppear in the study area.
No Corbicula have ever been found in any sample collected from PNPP or from Lake Erie in the vicinity of PNPP. Two Corbicula were found in a s unple collected from the Eastlake plant in June, 1987. No Corbicula have been found in any other sample collected since that time. A more detailed
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program history can be found in the 1986 and 1987 PNPP Annual Environmental Operating Reports.
Monitoring Samples were collected quarterly in 1997 from the service water and emergency service water pump
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houses at PNPP, and semiannually from Lake Erie in the vicinity of the Eastlake Power Plant. Sample collection dates are listed in T:ble 24.
Table 24: 1997 Corbicula sampling dates and locations Date Sample Location 1/24 Service Water (SW) and Emergency Service Water (ESW) Forebays and trash baskets
) 4/28 SW and ESW Forebays and trash baskets 6/l1 Lake Erie in the vicinity of the Eastlake Plant 7/10 SW and ESW Forebays and trash baskets 9/2 Lake Erie in the vicinity of the Eastlake Plant 10/13 SW and ESW Forebays and trash baskets
., Weekly inspections of PNPP property shoreline, weather permitting 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 whenever opened for maintenance or repair. Internet environmental sites have been utilized specifically for the purpose k of obtaining information on bivalves.
Results No Corbicula were found in any sample collected during the 1997 monitoring program. All bivalves
- collected are listed in Table 25.
Clam /MusselMontioring Page 41 L
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1997 Annual Environmental And Emuent Release Report Table 25i Bivalves collected during the 1997 Corbicula monitoring program Species / Location PNPP Eastlake Ancylldoe X (
Dreissena polymorpha X X Dreissena bugensis X X Gastropod X
' Limpets X X Pelecypoda X X X (
Physa sp.
Pisidium amnicum X X Pisidium sp. X X Pisidium cascrtanum X X Pisidium compressum X X Pisidium equilateral X X Pisidiumferrugineum X Pisidium tilljeborgi X X Pisidium nitidum X X Pisidium subtruncatum X X Pisidium vanabile X X Sphaeridae X ~{
Sphaerium corneum X Sphaerium nitidium X Sphaerium striatinum X Sphaerium transversum X X
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Conclusions The collection in June 1987 was the only indication ofCorbicula in the vicinity of PNPP. Ilowever, it has not been demonstrated that the presence of these clams is creating any operational problems at the Eastlake Power Plant or at PNPP.
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DREISSENA PROGRAM Zebra mussels were first discovered at PNPP in September 1988. The initial co!!ection of 19 mussels was made as part of the Corbicula monitoring program. The Dreissena program began in 1989 with monitoring and testing. The current control program was designed and implemented in 1990.
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! Monitoring l
In addition to visually inspecting plant raw water systems when they are opened for maintenance or l
repair, monitoring methods include the use of commercial divers, artificial substrates,sidestream monitors, and plankton nets.
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Commercial divers monitor mussel infestation when they are inspectingforehays, basins, and the intake and discharge structures. They have also been used to take underwater videotapes of the water basins and intake tunnel. Artificial substrates include concrete blocks suspended by rope into the plant service water basm. He substrate is removed weekly for inspection for settlement.
Sidestream monitors are flow-through containers that receive water diverted from plant systems, and (
are normally used in three in-plant locations during the mussel season. They are fitted with slides and inspected weekly for veliger settlement. A plankton net was used on a limited basis in 1997 Clam / Mussel Montioring Page 42
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1997 Annual Environmental And Ernuent Release Report Treatment
) Chemicals used for mussel control in 1997 included chlorine and a commercialmolluscicide. The system provides chlorine to plant service water, emergency service water, and circulating water systems. Sodium sulfite is added to plant discharge water todechlorinate it before discharge to Lake Erie.
The use of commercial molluscicide requires approval of the Ohio Environmental Protection Agency
) (OEPA). The chemical selected for use at Perry Nuclear Power Plant in 1997 was N-alkyl, dimethylbenzyl ammonium chloride. One treatment was applied near the end of cycle 6, prior to shutdown for refueling. The active ingredients were detoxified by adsorption ontobentonite clay prior to discharge into Lake Erie.
l Results
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The effectiveness of the intermittentchlorination 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 f%nd in any plant component to date.
) The effectiveness of the application of the commercialmolluscicide was measured by observing mortality of mussels placed in a flow-through container placed in plant service water and subjected to I the chemical treatment. Mortality observed in the flow-through container was 100%. To date, PNPP ;
has had no problems related to zebra mussels. j Conclusions I
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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. The current program of monitoring and chemical treatments will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels.
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' 1997 Annual Environmental And Effluent Release Report -
- HERBICIDE USAGE
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Herbicides are used sparingly on the PNPP site. An application must benade to the PNPP Chemistry Unit prior to spraying to ensure that only approved chemicals are used, and only in approved areas.
s in 1997 there were five herbicide applications initiated for spraying purposes. Of these five only the information for two was submitted for closure and the information that was submitted was not complete. Three of the permits were misplaced by the handler of the herbicides, preventing a complete (
compilation of herbicide usage.- All usage was in compliance with Ohio Environmental Protection Agency regulations. No adverse environmental impacts as a result of this usage were noted during
- weekly site environmentalinspectionc. Surfian AS and Round Up were used in equal portions at 2%
concentration for all locations except the E field perimeter, where Prametol was used at a maximum of
,20% concentration. The data available is provided below,
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Table 26: Documented Herbicide Usage Date Applied Location Acres Gallons Chemical Conc. %
6/10/97 Inside Protected unknown unknown 2 Area 6/11/97 Inside Protected unknown unknown 2 Area (
Table 26a shows the areas for which approval was given to use herbicides but the documentation was - (
not returned. Through conversations with the involved individuals it has been detennined that the herbicide application did take place in these areas however, efforts to retrieve of the documentation
.w ere unsuccessful. Corrective actions are being taken to improve this program to ensure this
- information is properly documented with future applications.
Table 26a: Undocumented Herbicide Use (
Date Applied Location Acres Gallons Chemical Conc. %
unknown Perimeter of E Field unknown unknown 20 unknown ' Owner Controlled unknown unknown 2 Area
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Herbicide Usage Page 44
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1997 Annual Environmental And Effiuent Release Report SPECIAL REPORTS
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NONCOMPLIANCE NPDES Permit Noncompliance
) The National Pollutant Discharge Elimination System, or 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.
There was one notification made to the OEPA in 1997.
I On 8/6/97 it was discovered that the service water system, automatic strainer backwash drains directly
) to Lake Erie via the storm drain system. Since thebackflush water could potentially be chlorinated I during the backwash evolution, there was a potential to route chlorinated water directly to Lake Erie via a non-permitted point source. This situation was reported to the Ohio Environmental Protection Agency (OEPA) on 9/12/97, Report # 97-09-43-3749 was assigned by the OEPA. To date the situation has been corrected by disabling the backwash duringchlorination.
) EPP Noncompliance The Environmental Protection Plan, or EPP, is a part of the PNPP Operating License. It requires non-radiological environmental monitoring programs and reporting. There were no EPPnoncompliances identified in 1997.
)
UNREVIEWED ENVIRONMENTAL QUESTIONS All proposed changes in plant design or operation, as well as tests or experiments conducted during 1997 were reviewed for potential environmental impact in accordance with the EPP and administrative
) quality assurance procedures. The reviews ensured that no changes were performed which could cause j an adverse environmental impact. Therefore, there were no potentially significantunreviewed j environmental questions in 1997.
NONROUTINE REPORTS
) There was no nonroutine reports in 1997.
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Appendix A: 1997 REMP Data Summary Page45
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o 1997 Annual Environmental And Emuent Release Repon APPENDIX A: 1997 REMP DATA
SUMMARY
O O
O O
O O
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Appendix A: 1997 REMP Data Summary Page46 g
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1997 Annual Emironmental And Emuent Release Report APPENDIX C : CORRECTIONS TO 1995 AND 1996 DATA
\
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Appendix C: 1997 IEMP Data Page 48 g
).
i 1995 Annual Emironmental and Efiluent Release Report i j
) Table 3: Liquid batch releases !
Item Value Number of batch releases 97 Total time period for batch releases (minutes) 1.965E+4 Maximum time for a batch release (minutes) 434 j Average time period for a batch release (minutes) 202.6
)' Minimum time for a batch release (minutes) 2 Average stream flow during periods of release of efIluent into a flowing stream 2.09E+05 (liters / minute)
Table 4: Summation of all liquid effluent releases Unit Quarter Quarter Quarter Quarter Est.
1 2 3 4 Total Error, A. Fission and activation products
)
- 1. Total releases (not Ci 4.63E-3 4.53E-3 5.68E-3 1.50E-2 1.00E+1 including tritium, gases, alpha)
- 2. Average diluted Ci/ml 1.42E-9 6.72E-10 2.09E 10 1.77E-9 concentration during
) period
- 3. Percent of applicable limit . % NA NA NA NA "NA "- This item is Not Applicable. ."
- Techmcal SpectficationsCDCM u'o not have a limitforfission and activatton products.
B. Tritium
- 1. Total release Ci 1.55E+0 2.31E+0 3.03E+0 3.53E+0 1.00+El
) 2. Average diluted uCi/ml 4.76E-7 3.43E-07 1.1 IE-7 4.16E-07 concentration du.iag period
- 3. Percent of applicable limit % <<l% <<l% <<l% <<1%-
C. Dissolved and entrained gases
) 1. Total release Ci - 8.18E-4 3.49E-3 7.07E-03 6.86E-3 1.00E+1
- 2. Average diluted Ci/ml. 2.51E-10 5.18E-10 2.60E-10 8.09E-10 concentration during period
- 3. Percent of applicable limit % <<1% <<l% <<1% <<1%
) D. Gross alpha radioactivity
- 1. Total release ' Ci 4.58E-5 <LLD <LLD <LLD 1.00E+1 E. Volume of waste released liters 1.59E+6 2.30E+0 4.25E+0 3.05E+0 1.00E+0 (prior to dilution) 6 6 6
- y. .
F. Volume of dilution water liters 3.26E+0 6.74E+9 2.72E+1 8.48E+9 2.80E+ 1 used during period 9 0 y
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1996 Annual Emironmental and EIT!uent Rc! case Report Table 3: Liquid batch releases Item Value (
Number of batch releases 85 Total time period for batch releases (minutes) 17560 Maximum time for a batch release (minutes) 246 Average time period for a batch release (minutes) 207 1
Minimum time for a batch release (minutes) 1.78E+05 (
Average stream flow during periods of release of effluent into a flowing stream (liters / minute)
Table 4: Summation of all liquid effluent releases Unit Quarter Quarter Quarter Quarter Est.
I 2 3 4 Total Error, A. Fission and activation products
.1. Total releases (not Ci 2.42E-02 8.52E-03 1.97E-03 Note 1 1.00E+1 (
including tritium, gases, alpha)
- 2. Average diluted Ci/ml 2.02E-9 5.61E-10 6.20E Il N/A concentration during period
- 3. Percent of applicable limit % NA NA NA NA (
"NA "- This stem Is Not Apphcable. The Techmcal SpecnficarnonsK)DCM do not have a hmstforfission and activation products.
B. Tritium
- 1. Total release Ci 4.77E+0 2.02E+0 1.29E+0 <LLD 1.00+El
- 2. Average diluted Ci/ml 3.98E-07 1.33E-07 4.06E-8 N/A concentration during (
period
- 3. Percent of applicable limit % <<1% <<!% <<1% N/A C. Dissolved and entrained gases
- 1. Total release Ci - 4.46E-03 7.30E-05 ' 2.75E-05 N/A 1.00E+1
- 2. Average diluted Ci/ml 3.72E 10 4.80E-12 8.65E-13 N/A (
concentration during period
- 3. Percent of applicable limit % <<1% <<1% <<1% N/A l
D. Gross alpha radioactivity
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- 1. Total release Ci 7.03E-05 2.10E-04 <LLD <LLD 1.00E+1 E. Volume of waste reicased liters 5.40E+0 2.70E+0 2.21E+0 0.00E+0 1.00E+0 (prior to dilution) 6 6 6 0 F. Volume of dilution water liters 1.20E+ 1 1.52E+1 - 3.18E+ 1 3.11E+0 2.80E+ 1 (
used during period 0 0 0 9 Note 1 No releases in fourth quarter l
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Perry Nuclear Power Plant Radwaste, Environmental and Chemistry Section 10 North Center Road P.O Box 97 (
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