Text

Annual Environmental and Effluent Release Report
	ML18121A391
Person / Time
Site:	Perry
Issue date:	05/01/2018
From:	Hamilton D; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-18-127
	Download: ML18121A391 (317)
	v • d • e

FENOC Perry Nuclear Power Plant P.O. Box 97 10 Center Road Perry Ohio 44081 FirstEnergy Nuclear Operating Company David B. Hamilton 440-280-5382 Vice President May 1,2018 L-18-127 10CFR50.36(a)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP) for the period of January 1, 2017 through December 31, 2017. This document includes the radiological environmental operating report, radioactive effluent release report, and the non-radiological environmental operating report, which satisfies the requirements of the PNPP Technical Specifications (TS), the PNPP Offsite Dose Calculation Manual (ODCM), and the Environmental Protection Plan, Appendix B of the PNPP Operating License. Also enclosed is a copy of the revised Offsite Dose Calculation Manual and support documentation.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Steven Benedict, Chemistry Manager at (440) 280-5032.

David Hamilton

Enclosures:

A PNPP 2017 Annual Environmental and Effluent Release Report B Offsite Dose Calculation Manual, Revision 21 cc: NRC Project Manager NRC Resident Inspector NRC Region III

Enclosure A L-18-127 PNPP 2017 Annual Environmental and Effluent Release Report

2017 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant Prepared By:

Chemistry section Perry Nuclear Power Plant FirstEnergy Nuclear Operating Company Perry, Ohio MARCH, 2018

2017 Annual Environmental and Effluent Release Report Table of Contents EXECUTIVE

SUMMARY

\

Radioactive Effluent Releases _

Radiological Environmental Monitoring

Pre-Operational REMP 2 Operational REMP 3 Land Use Census 3 Clam/Mussel Monitoring 3 Herbicide Use 3 Special Environmental Reports INTRODUCTION \

Radiation Fundamentals 4 Radiation and Radioactivity !!

Lower Limit of Detection ft Other Sources of Radiation Dose to the U.S. Population ° Environmental Radionudides RADIOACTIVE EFFLUENT RELEASES >>

Introduction g Regulatory Limits * " " Q 40CFR190 and 10CFR72.104-Uranium Fuel Cycle Dose Assessment >>

Liquid Effluents g Gaseous Effluents

Independent Spent Fuel Storage Installation <<

Release Summary 19 Meteorological Data 19 Dose Assessment

CARBON-14 SUPPLEMENTAL INFORMATION 23 GROUNDWATER MONITORING PROGRAM J>>

RADIOLOGICAL ENVIRONMENTAL MONITORING 26 Introduction 26 Sampling Locations 32 Sample Analysis ^

Sampling Program ""^

Program Changes 33 Atmospheric Monitoring M Terrestrial Monitoring ^

Aquatic Monitoring ~&

Direct Radiation Monitoring ^

Conclusion oo Inter-Laboratory Cross-Check Comparison Program ^

Land Use Census ' 9 CLAM/MUSSEL MONITORING ^

Introduction ^2 Corbicula Program 43 Dreissena Program AA HERBICIDE APPLICATIONS Tt SPECIAL REPORTS 7?

NPDES Permit Exceedances ^

Table of Contents Pagei

2017 Annual Environmental and Effluent Release Report Environmental Protection Plan 46 Environmental Impact Evaluations 45 Appendices Appendix A: 2017 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2017 REMP Data Summary Reports Appendix C: 2017 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances Appendix G: ODCM Changes Appendix H: Changes to the Process Control Program Table of Contents Page ii

Report 2017 Annual Environmental and Effluent Release EXECUTIVE

SUMMARY

The Annual Environmental and Effluent Release ^

ments of the Annual Radioactive Effluent Release Report (ARERR),

impact.

Radioactive Effluent Releases ZSmSSxtmSL of radioactive materials from the site in accordance wrth Nuclear Regulatory Commission (NRC) release regulations.

b/an individual resulting from PNPP gaseous effluents, excluding carbon-14 (C-14) was 1.69E-03 mrem (0.03% of the regulatory limit).

Radioactivity released to the environment in the form of ggaseous C-14 was e^mated

^

ssass" made and background radiation.

radioactive waste.

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2017 Annual Environmental and Effluent Release Report Radiological Environmental Monitoring The Radiological Environmental Monitoring Program (REMP) was established in 1081 to monitor the radiological conditions in the environment around PNPP. The operational REMP was initiated in 1986 and has continued through this reporting period. The REMP is conducted in accordance with the PNPP ODCM. This program includes collection and analysis of environmental samples and evaluation of results at indicator as well as control locations. Indicator samples are collected at locations determined to be most influenced by operation of the PNPP. Control samples are collected at locations beyond the measurable influence of the PNPP for data comparison.

Pre-Operational REMP The REMP was established at PNPP six years before the plant became operational.

Between 1981 and 1986, environmental monitoring involved collection and analysis of environmental samples. This pre-operational program was designed to provide data on background radiation levels and radioactivity normally present in the area in order to establish a baseline for data comparison prior to operation of the plant. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, milk, fish, vegetation, water, and sediment, as well as by measuring radiation directly.

The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the environmental monitoring program with pre-operational data, operational data from previous years, and control location data. The results for each sample type are compared to historical data to determine whether trends or changes in concentrations are observable.

Operational REMP Results of air samples collected to monitor the radioactivity in the atmosphere revealed normal background radionuclide concentrations. Terrestrial monitoring included the analysis of milk and vegetation; the results of which indicated concentrations of radioactivity similar to those found in previous years. Analyses of vegetation samples detected only natural radioactivity, similar to those observed in previous years and indicated no radioactivity attributable to operation of the PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The analytical results of these samples showed normal background radionuclide concentrations.

Direct radiation measurements showed no significant changes from previous years. The indicator locations averaged 12.0 mrem/quarter and control locations averaged 11.4 mrem/quarter. Radiation dose in the area of PNPP was similar to the radiation dose measured at locations greater than ten miles away from PNPP.

Results from indicator samples collected during this reporting period were compared to control sample results and pre-operational data. Based on the results, the operation of the PNPP resulted in no measurable increase in the radionuclide concentrations observed in the surrounding environment. The results of the REMP indicate adequate control of radioactivity released from PNPP effluents. These results also demonstrate that PNPP complies with federal regulations.

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2017 Annual Environmental and Effluent Release Report Land Use Census In orderto estimate radiation dose attributable to t*a^*Z22&ff*

pathways through which public exposure can occur must * ^_2*'2££ pathways, an Annual Land Use Census is performed as part of the REMP. During me benW PNPP personnel travel public roads within a five mile radius of the plant tolocate te3 radioloflical^^osure pathways. These key pathways include the nearest resident oarim and milk'animal in each of the ten meteorological land sectors that surround the dart Th^nfolafioTobtained from the census is entered into a computer P"*'1J£*

toZmmSSSad dose to members of the public. The predominant land use within the census area continues to be rural and/or agricultural.

Clam/Mussel Monitoring Clam and mussel shells can clog plant piping and componentsthat<< w^ijnn Uka EriV For this reason, sampling for clams and mussels has been conducted m Lake Ene ne^r PNPP itaoTwi. The monitoring is specifically for Corticula (Asiatic dams) since S3 Modtfton into the Great Lakes in 1981. and for Dreissenaizeb<<jmussete)s.n<<

their discovery in Lake Erie in 1989. Since no Corblcula have beenfound at PNPP, routine Co^tamonltoring will provide eariy detection capability If this pert species arnves at PNPP The Dreissena program includes both monitoring and control and is directed at mVnimfeSrnplcfof theZssels on plant operation. As in past years, this program.has successfully succ prevented Dreissena from causing any sigmficant operational problems at PNPP PNPP.

Herbicide Use use of herbicides icides on on the the PNPP PNPP site site is is monitored monito to ensure compliance p with Ohio r^^

rm^^ction ^ction Agency (OEPA) PA) requirements it an andd to p^

protectihe s,^n<

areas. Based on weekly inspections, herbicide biid use hash nott had had a a negative negative impact imp on the environment around the plant.

Special Environmental Reports Signfficant environmental events (e.g. spills, releases), nonf'P"a"^

regulations (e g OEPA discharge limits), and changes in plant design or operation that SMUtelriSLtaL^mMro reported to regulatory agencies as they occur. No reports were submitted in 2017 and further details can be found on page 45.

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2017 Annual Environmental and Effluent Release Report INTRODUCTION Nuclear energy provides an alternative energy source that is readily available with a very limited impact upon the environment. To more fully understand nuclear energy as a source of generating electricity, it Is helpful to understand basic radiation concepts and the occurrence of radioactivity in nature.

Radiation Fundamentals Atoms are the basic building blocks of all matter. Simply described, atoms are made up of positively and negatively charged particles and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed together in the center of the atom called the nucleus. Orbiting around the nucleus are one or more smaller electrons. In an electrically neutral atom, the positively charged protons in the nucleus balance the negatively charged electrons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other and prevent the nucleus from breaking apart.

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 neutrons are called isotopes. All isotopes of the same element have the same chemical properties and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radionudide. Radionudides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.

Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom's nucleus through the emission of alpha and beta particles and gamma rays. Radionudides vary greatly in the rate in which they decay. The length of time an atom remains radioactive is defined in terms of its half-life. Half-life is defined as the time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

Radiation and Radioactivity Radioactive decay is a process in which the nucleus of an unstable atom becomes more stable by spontaneously emitting energy. Radiation refers to the energy that is released when radioactive decay occurs within the nudeus. This section includes a discussion on the three primary forms of radiation produced by radioactive decay.

Alpha Particles Alpha particles consist of two protons and two neutrons and have a positive charge.

Because of their charge and large size, alpha particles do not travel very far when released (less than 4 inches in air). They are unable to penetrate any solid material, such as paper or skin, to any significant depth. If alpha particles are released inside the body, however, they can damage the soft internal tissues because they deposit all their energy in a small area.

Page 4

2017 Annual Environmental and Effluent Release Report Beta Particles Beta Dartides have the same characteristics as electrons but originate from the ThevSem^h smaller than alpha particles and travel at neatly the speed of

SHSiSMSSSSS:<~~><<<<.~~

andthe pfcocurie (pCi), one trillionth of a curie. The mass, or wejght, ? *<<'>>>>*'*
material whi* v^uW result in one curie of activity depends on the^6I^' f"*,
example, one gram of radium-226 is equivalent to one cune of activity. It would require about 1.5 million grams of natural uranium, however, to equal one cune.
Dose
^^K, can result In much more biological damage for the same ionizing radiation. The dose equivalent is measured interms
~~quWa.em Man (rem). When discussing environmental rad<<atwn effects,~~
^ unit; therefore, a smaller unit, the milllrem (mrem) is often used. One mrem is equivalent to 1/1000 of a rem.
Page 5
2017 Annual Environmental and Effluent Release Report Lower Limit of Detection Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD for an analysis is the smallest amount of radioactive material that will show a positive result, for which there can be a 95% confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as less than the LLD (<LLD), it means that no radioactivity was detected. Had radioactivity been present at or above the stated LLD value, it statistically would have been detected. The NRC has established the required LLD values for environmental and effluent sample analyses.
Other Sources of Radiation Dose to the U.S. Population This section discusses the doses that the average American typically receives each year from naturally-occurring background radiation and all other sources of radiation. With the information presented in this section, the reader can compare the doses received from Nuclear Power Plant (NPP) effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects.
In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, Ionizing Radiation Exposure of the Population of the United States. Report No. 160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another. The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including:
Naturally-occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally-occurring radioactive materials in the food people eat and in the air people breathe; Medical sources from diagnosis and treatment of health disorders using radioactive Pharmaceuticals and radiation-producing equipment;
~~Consumer products (such as household smoke detectors);~~
Industrial processes, security devices, educational tools, and research activities; and Exposures of workers that result from their occupations.
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2017 Annual Environmental and Effluent Release Report SfMOft Radon tttoran (badqtround) 37%
<<uoratoopy (
(nwtfcal) 7%
Figure 1: Sources of Radiation Exposure to the U.S. Population Figure 1 shows the contribution of various sources of exposure to the totahj>><<ective Sfc due^effluents from NPPs are less than 0.1% of what the average person receives each year from all other sources of radiation.
Environmental Radionuclides 3S of nitrogen In the air and cosmic rays.
Program Results.
Page 7
2017 Annual Environmental and Effluent Release Report RADIOACTIVE EFFLUENT RELEASES Introduction The source of radioactive material in a nuclear power plant is the generation of fission products (e.g., noble gas, iodine, and particulate) or neutron activation of water and corrosion products (e.g., tritium and cobalt). The majority of the fission products generated remain within the nuclear fuel peliet and fuel cladding. Most fission products that escape from the fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment.
During the normal operation of a nuclear power plant, small amounts of radioactive material are released in the form of solids, liquids, and gases. PNPP was designed and is operated in such a manner as to control and monitor these effluent releases. Effluents are controlled to ensure any radioactivity released to the environment is minimal and within regulatory limits. Effluent release programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of effluent monitoring.
The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent 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. This monitoring instrumentation is 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 the limits. The waste streams are sampled and analyzed to identify and quantify the radionudides being released to the environment.
Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. Devices are maintained at various locations around PNPP to continuously sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The REMP is described in detail later in this report Generation of solid waste is controlled to identify opportunities for minimization. Limiting the amount of material taken into the plant and sorting material as radioactive or non-radioactive waste helps to lower the volume of radioactive solid waste generated. After vendor processing, solid waste is shipped to a licensed burial site.
Regulatory Limits The Nuclear Regulatory Commission has established limits for liquid and gaseous effluents that comply with:
Title 10 of the Code of Federal Regulations, Part 20, Standards for Protection Against Radiation, Appendix B; Title 10 of the Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I; Title 10 of the Code of Federal Regulations, Part 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS Title 40 of the Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations Page 8
2017 Annual Environmental and Effluent Release Report These limits were incorporated into the PNPP Technical Specification8;<<ndMs^"^
into the PNPP ODCM. The ODCM prescribes the maximum doses and dose rates due to EtaSE^U resulting from the operation of PNPP. These limits,<<.defined\m several ways and serve to limit the overall impact on persons hving near thaph^Sme thereare nb other fuel sources near the PNPP, the 40CFR190 limits descnbed below were not exceeded.
40CFR190 and 10CFR72.104- Uranium Fuel Cycle Dose Assessment The 4OCFR190 limit for whole body dose is 25 mrem. Considering f**^**1*"1 whole body dose to a member of the general public was 0.26 mrem. Tins value was KM by summing the annual whole body doses from liquid and gaseous rad.oact.ve Suenteand the annual gaseous C-14 dose. Since the direct radiation dose as
£m^brTLDw^s indistinguishable from natural ^un*f^)J'* "<*
fnduded in the calculation. More information regarding *M <<fc^ *£ and the Independent Spent Fuel Storage Installation (ISFSI), may be found on page 11.
Liquid Effluents The concentration of radioactive material released in liquid effluents to "H**^'" 9 shaYteHmited to the concentrations specified in 10CFR20, Appendix B, Table 2JColumn 2 for radionudides other than dissolved or entrained noble gases, as required by ttne ODCM.
For^rssolveo^ertrained noble gases, the concentration is limited to a concentrate of 2 OE-04 uCi/ml. These values are the maximum effluent concentrations.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
During any calendar quarter.
Less than or equal to 1.5 mrem to the whole body, and Less than or equal to 5 mrem to any organ During any calendar year:
Less than or equal to 3 mrem to the whole body, and Less than or equal to 10 mrem to any organ Gaseous Effluents the following as required by the PNPP ODCM:
~~Noble gases:~~
Less than or equal to 500 mrem per year to the whole body, and Less than or equal to 3000 mrem per year to the skin
. lodine-131, iodine-133, tritium, and all radionudides in paniculate form with half-lives greater than eight days:
Less than or equal to 1500 mrem per year to any organ Page 9
2017 Annual Environmental and Effluent Release Report Air dose due to noble gases to areas at and beyond the site boundary are governed by 10CFR50 Appendix I and shall be limited to the following:
~~During any calendar quarter:~~
~~Less than or equal to 5 mrad for gamma radiation, and Less than or equal to 10 mrad for beta radiation~~
~~During any calendar year Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation~~
Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionudides in particulate form with half-lives 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 limit for gaseous effluents. For this reason, effluent concentrations are not used to calculate maximum release rates for gaseous effluents.
Independent Spent Fuel Storage Installation During any calendar year:
Less than or equal to 25 mrem whole body dose; Less than or equal to 75 mrem thyroid dose; and Less than or equal to 25 mrem to any other critical organ.
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2017 Annual Environmental and Effluent Release Report release Summary Effluents are sampled and analyzed to identify both the type and quantity of radionuclides present This information is combined with effluent path flow measurements todetermine the composition, concentration, and dose contribution of the radioactive effluents.
40CFR190 and 10CFR72.104 Compliance Since implementation of the Independent Spent Fuel Storage Installation (ISFSI) in 2011, eight TLDs have been placed on the outer perimeter fence of the cask storage area (located within the site boundary) to monitor dose due to direct radiation from the.spent fuel source Two particular TLDs, those closest to the nearest resident, numbers 18 (NNE comer) and 19 (ENE corner) of the ISFSI pad, were used to cateuW**^*"? J0 '
barest resident to determine compliance with the 40CFR190 and 10CFR72.104 limits.
The dose calculation was performed using the location of the nearest residence, assuming they remain at the location all year, because that individual would incur the maximum potential dose from direct exposure. The TLD at REMP location 7 (refer ^Figure 3) whjch is positioned neighboring the nearest resident, was also reviewed for significant changes in readings.
To determine the dose rate to the nearest resident and demonstrate compliance, the following equation was used:
DiRi2=D2R22 Where:
Di = dose rate (mrem) at the pad perimeter D2 = dose rate (mrem) to nearest resident R, = distance (feet) of nearest TLD location to max individual R2 = distance (feet) to nearest resident The two nearest TLDs were chosen to estimate dose rates, but the higher of the two northeast corner TLDs was used for conservative estimates. The center of the pad was chosen as the highest point source.
Using the more conservative TLD result, the estimated dose to the nearest resident was 0.33 mrem/yr in 2O178 not considering vegetation and shielding from buildings\n 20 7 the calculated values were slightly lower, but statistically comparable to results of 2016. Unlike the whole body dose value of 0.26 mrem value presented on page 9, this dose rate of 0.33 mrem/yr is an estimate based on TLD readings to demonstrate (compliancei. The <calculate confirms that direct dose from the ISFSI does not exceed the 40 CFR190 limit of 25 mrem/year.
Review of the TLD results from 2017 have shown no detectable impact on dose to the public due to radiation from the ISFSI nor significant changes in results to the public since employment of the ISFSI.
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2017 Annual Environmental and Effluent Release Report Liquid Effluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the effluent from the liquid radioactive waste system is returned to plant systems. To reduce the volume of water stored in plant systems, however, the processed liquid effluents may be discharged from the plant via a controlled release. In this case, effluent activity and dose calculations are performed prior to and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principles are maintained.
Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases.
Table 1: Liquid Batch Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Number of batch releases 13 5 4 5 Total time period for batch releases, min 4.38E+03 1.97E+03 1.18E+03 1.13E+03 Maximum time for a batch release, min 4.78E+02 9.01 E+02 5.04E+02 2.31 E+02 Average time period for a batch release, min 2.30E+02 3.94E+02 2.95E+02 2.27E+02 Minimum time for a batch release, min 7.00E+00 2.19E+02 2.23E+02 2.23E+02 Average quarterly flow rate, L/min 2.18E+05 2.63E+05 2.79E+05 1.48E+05 Page 12
2017 Annual Environmental and Effluent Release Report Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. In each case, LLDs were met or below the required values. Table 2a provides information specific to radioactive effluent batch releases and Table 2b provides information specific to continuous radioactive effluent releases.
Table 2: Summation of All Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, (%)
A. FissU id Activation Products
1. Total Released, Ci 3.41 E-02 1.86E-02 8.75E-03 1.09E-03 1.00E+01 (excluding tritium, gases, alpha) 1.72E-O9 8.44E-10 2.66E-10 4.44E-11 2 Average Diluted Concentration, uCi/mL
~~2.30E-02 2.26E-02 6.31 E-03 1.40E-03~~
~~3. Pi jf Applicable Limit, %~~
~~B. Tritii 4.72E+00 1.43E+00 1.04E+00 1.24E+00 1.00E+01~~
~~1. Total Released. Cl 2.38E-07 6.49E-O8 3.18E-08 5.05E-08 0 Ai Diluted Concentration. uCi/mL 2.38E-Q2 6.49E-03 3.16E-03 5.05E-03 3, Percent of Applicable Limit, %~~
C. Dissolved and Entrained Oases 0.O0E+O0 O.OOE+00 0.00E+OO O.OOE+00 1.00E+01 1 .TotalReleased, Ci O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0 A\ Diluted Concentration, uCI/mL 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~~3. Percent of Applicable Limit, %~~
0.00E+00 0.00E+00 0.00E+O0 1.00E+01 D. Gross Alpha Activity, Cl O.OOE+00 E. Waste Volume Released, Liters (prior to 1.71E+06 7.92E+05 5.23E+05 6.80E+05 1.98E+10 2.20E+10 3.29E+10 2.46E+10 F. Dilution Water Volume Used, Liters Page 13
2017 Annual Environmental and Effluent Release Report Table 2a: Summation of Batch Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, (%)
A. Fission and Activation Products Total Released, Ci 3.41 E-02 1.85E-02 8.74E-03 1.09E-03 1.00E+01 (excluding tritium, gases, alpha)
B. Tritium Total Released, Ci 4.72E+00 1.43E+00 1.04E+00 1.24E+00 1.00E-H)1 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD <LLD 1.93E-06 <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 1.58E+06 6.54E+05 5.23E+05 6.54E+05 ** %!,/- *',
dilution)
<LLD - Less than the lower limit of detection Table 2b: Summation of Continuous Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est Total Error, (%)
A. Fission and Activation Products Total Released, Ci 4.66E-06 1.50E-04 <LLD 2.01 E-06 1.00E+01 (excluding tritium, gases, alpha}
B. Tritium Total Released, CI <LLD <LLD <LLD <LLD 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 1.36E+05 1.37E+05 O.OOE+00 2.56E+04 dilution)
<LLD - Less than the lower limit of detection Page 14
2017 Annual Environmental and Effluent Release Report TaWe 3 lists me total number of curies of each radionudide present in liquid effluent releases for each quarter. In each case, the LLDs were either met or were below the levels required by the ODCM.
Table 3: Radioactive Liquid Effluent Nucllde Composition i i i Annual Isotope Unit Quarter 1 I Quarter 2 l Quarter 3 Quarter 4 1.04E+00 1.24E-KX) 8.43E+00 Ci 4.72E+00 1.43E+00 Tritium 6.06E-04 <5,0E-07' <5.0E-07 6.51 E-03 Chromium-51 5.90E-03 3.75E-04 6.94E-05 1.84E-03 Manqanese-54 5.73E-04 8.23E-04 1.36E-03 <1,0E-061 1.35E-02 lron-55 1.21E-02 <1,0E-O61
<5.0E-07 <5.0E-07 iron-59 Ci I <5.0E <5.0E-07 '* <S.0E-07 3.54E-04 <5.0E-07 2.13E-03 9.52E-04 8.22E-04 Cobalt-58 5.53E-03 1.02E-03 3.08E-02 1.14E-02 1.28E-02 Cobalt-60 7.87E-05 <1.0E-061 7.87E-05 N/A N/A Nickel-63
^
nun ~
5.24E-04 <5.0E-07 3.03E-03 7.75E-04 1.73E-03 Zinc-65
<5E-081 <5E-081 <5E-081
<5E-08 <5E-08 Stronttum-89
<5E-08 <5E-08 ^ <5E-08 Strontium-90 <SE-08f ,
<5E-08
~~i^-~~
<5.0E-071 <5.0E-07 <5.0E-07' Motvbdenum-99 <5.0E-07 <5.0E-07 5.21E-04 <5.0E-07 4.81 E-03 Silver-110M 2.38E-03 1.71 E-03 "**
<5.0E-07 <5.0E-07 <5.0E-07 Tin-113 <5.0E-07' <6.0E-071
<5.0E-07_ 1.22E-04
<5.0E-07 1.22E-04, Tin-124
<1.0E-06 <1.0E-OB1 .OE-061
<1.0E-061 <1.0E-06' lodine-131
<5.0E-07 * <5.0E-07 <5.0E-071 <S.0E-071 I <5.0E-07 Cesium-134 - """
<5.0E-07 <5.0E-07
<5.0E-07 <5.0E-07 Ces8um-137
<5.0E-07 * <5.0E-07 <5.0E-07
~~Ceriurn-141 <5.0E-07 '~~
^^^
mum i f.mi i -
<5.0E-07 <5.0E-07 <5.0E-07
<5.0E-071 <5.0E-07 Cerium-144 MMW<<^^
<5.0E-07 <5.0E-071 <5.0E-07
<5.0E-07 <5.0E-07
<5.0E-07 <5.0E-07' <S.0E-071 <5.0E-07 <
<5.0E-07
~~1.93E-06 <1.0E 1.93E-06~~
<1.0E-071 <1,0E-07 1 - (<) Less than the ODCW-required lower limit of detection, units in uCi/mL N/A - Samples not analyzed for Ni-63 un<< third quarter, when the isotope was added to the required analyses Page 15
2017 Annual Environmental and Effluent Release Report Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine, and particulate releases. Gaseous effluents from PNPP exit the plant via one of four effluent vents. Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that the levels of radioactivity released are below regulatory limits. Samples are also collected and analyzed on a periodic basis to ensure regulatory compliance. Gaseous effluents released from PNPP are considered continuous and at ground level.
In 2013, PNPP increased the volume of air sampled for tritium in gaseous effluents, increasing the detection capability by a factor of 20, which lowered the LLD. With the increased sample volume, gaseous effluent tritium releases can be detected; whereas, in previous years the concentration was too dilute to measure. This has resulted in increased reported tritium releases over the last few years. A summation of all gaseous radioactive effluent releases is given in Table 4.
Table 4: Summation of All Gaseous Effluents Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, %
A. Fission and Activation Products
~~1. Total Released, Ci 5.55E-01 2.65E-02 O.OOE+00 3.24E-01 1.00E+01~~
~~2. Averaqe Release Rate, uCi/sec 7.14E-02 3.37E-02 0.00E+O0 4.08E-02~~
~~3. Percent of Applicable Limit, % N/A N/A N/A N/A B. Iodine~~
~~1. Total lodine-131 Released, Ci 3.26E-06 0.00E+00 O.OOE+00 O.OOE+00 1.00E+01~~
~~2. Average Release Rate. uCi/sec 4.20E-07 O.OOE+00 0.00E+00 0.00E+00~~
~~3. Percent of Applicable Limit, % N/A N/A N/A N/A C. Participates with Half-Lives > 8 days~~
~~1. Total Released, Ci 0.00E+00 0.00E+O0 O.OOE+00 O.OOE+00 1.00E+01~~
~~2. Average Release Rate, pCi/sec 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00~~
3. Percent of Applicable Limit, % N/A N/A N/A N/A D. Alpha Activity, Ci 2.76E-06 2.13E-06 4.80E-06 3.52E-06 1.00E+01 E. Tritium
~~1. Total Released, Ci 1.45E+00 2.34E-01 6.43E-01 6.31 E-01 1.00E+01~~
~~2. Average Release Rate, uCi/sec 1.87E-01 2 98E-02 6.84E-02 7.93E-02~~
3. Percent of Applicable Limit, % N/A N/A N/A N/A F. Carbon-14, Ci 2.99E+00 4.40E+00 4.75E+00 4.77E+00 1.00E+00 N/A - Not Appiicable, the ODCM does not have a release rate limit for gaseous effluents Carbon-14 activity was calculated based on power production and using the EPRI-provided spreadsheet Page 16
2017 Annual Environmental and Effluent Release Report The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. In each case, LLDs were met or were below the levels required by the ODCM.
Table 5: Radioactive Gaseous Effluent Nuclide Composition Quarter 2 Quarter 3 Quarter 4 Annual Isotope Unit Quarter 1
1. Fission and Activation Gases 2.34E-01 5.43E-01 6.31 E-01 2.86E+00 Tritium Ci 1.46E+00 2.65E-01 elOE-OB1 3.24E-01 5.89E-01 Argon-41 Ci <1.0E-061
<1.0E-061 <1.0E-06< <1.0E-06* 3.78E-01 Krypton-85m CI 3.78E-01
<1.OE-0B1 <1.0E-061 <1.0E-061 <1.0E-O61 <1.0E-061 Krypton-87 Ci
<1.0E-061 <1.0E <1.0E <1.0E Krypton-88 Ci <1.0E-061
<1.0E-06' <1.0E-061 KIOE-OS1 <1.0E-081 ^.OE-OC1 Xenon-133m Ci Ci 3.84E-02 <1.0E-061 <1.0E-O61 <1.0E-081 3.84E-02 Xenon-133
<1.0E-061 <1.0E-06* <1.0E-061 ^.OE-OS1 <1.0E-061 Xenon-135m Ci 1.38E-01 <1.0E-061 <1.0E-06' <1.0E 1.38E-01 Xenon-135 Ci
<1.0E-061 ^.OE-OS1 <1.0E-061 Xenon-138 Ci ^OE-OG1 <1.0E 4.99E-01 S.43E-01 9.55E-01 4.01 E+00 Jotal for Period Ci 2.01 E+00
~~2. Iodine/Halogens 3.26E-06 <10E.12i <10E.12,j <1.0E-12J 3.26E-06 odine-131 Ci~~
<10E-10 <1.0E-101 kLOE-IO1 <1.0E-101 odlne-133 Ci ^OE-IO1
<LLD <LLD <LLD 3.26E-06 Total for Period . Ci 3.26E-06
~~3. Partlculates~~
<1 .OE-041 <1 .OE-041 <1 .OE-04' <1 .OE-041 <1 .OE-041 Chramium-51 Ci
<1 .OE-041 <1 OE-041 <1 .OE-041 <1 .OE-04' Manqanese-54 CI <1 OE-04'
<1 .OE-04' <1 .OE-041 <1 .OE-041 <1.OE-04' ^.OE^1 lron-59 Ci
<1 .OE-04 * <1.OE-04' <1 .OE-041 <1 .OE-041 <1 .OE-041 Cobatt-58 Ci
<1 .OE-041 <1.OE-04' <1 .OE-041 <1 .OE-041 <1 .OE-041 Cobatt-60 Ci
<1 .OE-041 <1 .OE-041 <1 .OE-041 <1.OE-04
~~Zno-65 Ci <1 .OE-041~~
<10E.111 <1.0E-11 * <1.0E-111 <1.0E-111 <1.0E-11 1 Strontium-89 Ci
<1 .OE-041 <1 .OE-041 <1 .OE-04 <1 .OE-041 <1.OE-041 Molvbdenum-99 Ci
<1 .OE-041 <1 .OE-041 <1 .OE-04' <1 .OE-041 <1 .OE-041 CAsium-134 Ci
<1.OE-04' <1 .OE-041 <1 .OE-041 <1 .OE-04
~~Cesium-137 Ci <1 .OE-04'~~
<1 .OE-041 <1.0E-04' <1 .OE-041 <1 .OE-041 Certum-141 Ci <1 .OE-04'
<1 .OE-041 <1.OE-041 <1 .OE-041 <1. OE-041 <1 .OE-041 Cerium-144 Ci
<LLD <LLD <LLD <LLD Ci <LLD Total for Period 1 - (<) Less than the ODCM-required lower limit of detection, units in pCi/mL
<LLD - Less than the OCM-required lower limit of detection Page 17
2017 Annual Environmental and Effluent Release Report Solid Waste All solid radioactive waste from PNPP was processed and combined with waste from several other utilities by intermediate vendors (Energy Solutions and Erwin Resin Solutions). The final waste after processing is sent to EnergySolutfons disposal facility in Clive, Utah for burial.
Table 6: Solid Waste Shipped Offsite for Burial or Disposal
~~1. Type of Solid Waste Shipped Volume (m3) Activity (Ci) Est. Total Error (%)~~
~~a. Resins, Filters, and Evaporator Bottoms 1.35E+02 1.28E+03 +/-25~~
~~p. Dry Active Waste 1.16E+03 6.94E-01 +/-25~~
~~c. Irradiated components, control rods, etc 0.00E+0O O.0OE+00 +/-25~~
~~d. Other Waste 6.65E+00 1.95E+00 +/-25~~
2. Estimate of Major M NucMde Composition (by type Radionudide Abundance EsL Total of waste) (%) Error, (%)
~~a. Resins, Filters and Evaporator Bottoms Mn-54 4.61 +/-25 Fe-55 33.69 Cc-60 54.81 Zn-65 4.28~~
b. Dry Active Waste Cr-51 1.38 +/-25 Mn-54 5.06 Fe-56 42.06 Co-60 46.13 Zn-65 1.30
~~c. Irradiated Components, Control Rods, etc. N/A N/A N/A~~
d. Other Waste Mn-54 1.16 +/-25 Fe-55 20.55 Co-60 76.93 (1) - "Major" Is defined as any Individual radionudide Identified as >1% of the waste type abundance.
~~N/A - Not applicable due to no shipments~~
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 54 Hittman Transport Energy Solutions Bear Creek Operations 1 Hfttman Transport Energy Solutions Galfaher Operations 6 Hittman Transport Erwin ResinSolutions, LLC 151 T.C. Runnion Rd.
1 Landstar Energy Solutions Gallaher Operations Page 18
2017 Annual Environmental and Effluent 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 through separate date loggers and transmitted to a common plant computer. This program compiles the data and calculates a variety of atmospheric parameters, communicates with the Meteorological Information Dose Assessment System (MIDAS), and sends data over communication links to the plant Control Room.
A detailed report of the monthly and annual operation of the PNPP Meteorological Monitoring Program is produced as a separate document that is retained in PNPP Records and available upon request. The report substantiates the quality and quantity of meteorological data collected in accordance with applicable regulatory guidance.
Dose Assessment The maximum concentration for any radioactive release is controlled by the limits set forth in Title 10 of the Code of Federal Regulations, Part 20 (10CFR20). Sampling, analyzing, processing, and monitoring the effluent streams ensures compliance with these concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical maximum 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 individual actually meets these crtteria, 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:
~~Using data for a 360-degree radius around the plant site (land and water-based meteorological sectors); even though some of these sectors are over Lake Ene, which has no permanent residents;~~
. Considering only those sectors around the plant in which people reside (land-based meteorological sectors).
The calculated hypothetical, maximum individual dose values at the site boundary are provided in Table 7. This table considers all meteorological sectors around PNPP and provides whole body and worst-case organ-dose values.
Page 19
2017 Annual Environmental and Effluent Release Report Table 7: Maximum Yeariy Individual Site Boundaiy Dose, Considering All Sectors Type of Dose Organ Estimated Limft (mrem) % of Limit Dose, (mrem)
Liquid Effluent Whole body 1.96E-03 3.0E+00 6.5E-02 Liver 2.71 E-03 1.0E+01 2.7E-02 Noble Gas Air Dose Gamma 2.64E-03 1.0E+01 2.6E-02 (mrad)
Air Dose Beta 1.17E-03 2.0E+01 5.8E-03 (mrad)
Noble Gas Whole body 1.69E-03 5.0E+00 3.4E-02 Skin 2.71 E-03 1.5E+01 1.8E-02 Partlculate & Iodine Thyroid 1.38E-03 1.5E+01 9.0E-03 Carbon-14
~~Whole Body 2.55E-01 5.0E+00 5.1E+00~~
~~C-14 dose calculated at nearest garden.~~
The hypothetical maximum dose within a 50-mile radius of site was calculated and is presented in Table 8. This table considers all meteorological sectors around PNPP and provides whole body and worst-case organ dose values.
Table 8: Population Yearly Dose, Considering All Sectors out to 60 miles Organ Estimated Dose (persorvrem)
Liquid Effluent Whde body 2.5E-01 Thyroid 8.3E-02 Gaseous Effluent Whole body 3.1E-04 Thyroid 3.1E-04 Page 20
2017 Annual Environmental and Effluent Release Report Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors.
Table 9: Maximum Yearly Individual Site Boundary Dose (Only Land Sectors)
Umit (mrem)
Type of Dose Gamma (mrad)
~~C-14 dose calculated at nearest garden.~~
Other dose calculations are performed for a hypothetical individual assumed to be inside the site boundary for some specified amount of time. This person would receive the ma^mum dote during the timTspent inside site boundary-Because noj^onactuaHy meets the criteria established for these conservative calculations, the actual doseijeered fa^riSTttTpubRc is significantly less than what is ^f*^*"*^
individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.
The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is toTperson who is fishing on Lake Erie from the sho<< °n PN^property. The calculates assume that this person will spend 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year fishing, wtth . **
dHiSon factor of 10. The ratio of the exposure pathway to the doses calculated for offsite locations yields the dose values shown In Table 10.
Table 10: Maximum Site Pose from Liquid Effluents Whole Body Dose, Organ Dose, (mrem) (mrem) 4.6E-04 5.4E-04 First Quarter 5.4E-04 6.4E-04 iecond Quarter 2.1E-04 2.5E-04 Third Quarter 6.9E-05 8.2E-05 Fourth Quarter 1.4E-03 1.6E-03 Annual Page 21
2017 Annual Environmental and Effluent Release Report Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.
Table 11: Maximum Site Dose from Gaseous Effluents Whole Body Dose, Organ Dose, (mrem) (mrem)
First Quarter 1.2E-04 2.1E-04 Second Quarter 9.5E-05 1.5E-04 Third Quarter 2.3E-05 2.3E-05 Fourth Quarter 1.3E-04 1.9E-04 Annual 2.9E-04 1.1E-03 An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP. The dose from liquid radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP. The results of this calculation are provided in Table 12.
Table 12: Average Individual Whole Body Dose Liquid Effluents, Gaseous Effluents, (mrem) (mrem)
First Quarter 3.5E-05 4.6E-08 Second Quarter 4.6E-05 1.9E-08 Third Quarter 1.5E-05 3.8E-08 Fourth Quarter 5.0E-06 2.6E-08 Annual 1.0E-04 1.3E-07 Page 22
2017 Annual Environmental and Effluent Release Report Carbon-14 Supplemental Information Cart>on-14, with a half-life of 5730 years, is a naturally-occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuctear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the ^<*Pbere- <~'""^4 is also produced in commercial nuclear reactors, but the amounts S"^ "£**£_
lhan those produced naturally or from weapons testing. It is released pnmanhr from Bo.hng Water Reactors through the Off-flas system in the form of carbor.dioxide (CO* Tlie quantity of gaseous C-14 released to the environment can be estimated using a c-14 source term scaling factor based on power generation.
The U.S. Nuclear Regulatory Commission (NRC) requires an assessment* gaseous C-14 dose impact to a member of the public resulting from routine re eases hwhtogwl effluents Prior to 2011, the industry did not estimate the dose 'P^ * ^J^*""1 because the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates and radioiodines. At PNPP improvements over the years In effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous radionuclides released to the environment.
This report contains estimates of the gaseous C-14 radioactivity released and the resulting public dose resulting from this release. The calculation is performed ""£"**£*<<
provided by EPRI and is based on power production. This method fare^'*^,<£'
released has been endorsed by the NRC. Because the dose contnbutran of C-14 from HquS radioactive waste is much less than that contributed by gaseous radjoactwe waste, evaluation of C-14 in liquid radioactive waste at PNPP is not required. Refer to Table 4, Table 7, and Table 9 for C-14 estimated release values and doses.
Groundwater Monitoring Program Based on the Environmental Resource Management hydrogeology study, 12 monitoring wells were recommended for the site. Since most groundwater^J^.<<'*£ Lake Erie, the majority of wells are drilled north of the plant. A set of control wells were drilled south of the plant to assess a typical groundwater profile.
There are sets of three wells installed at four locations. Each set has a shallow well of Approximately 25 feet, a mid-depth well of approximately 50 feet and a deep wriI of approximately 75 feet. These three depths are designated A, B, and C, from shallowest to deepest, respectively.
PNPP has an Underdrain system to prevent groundwater hydrostatic pressure buildup on plant structures. The Underdrain system has two installed radiation monitors that assess the process stream prior to flowing into the Emergency Service Water system.
Refer to Figure 2 for locations of Groundwater Wells 1A through 4C and>>""****
Manholes 20 and 23. These wells and manholes encompass the groundwater monitonng locations at PNPP.
Page 23
2017 Annual Environmental and Effluent Release Report Manholes Piezometers QrounAmterWBlls Figure 2: Underdrain System and Groundwater Monitoring Wells Page 24
2017 Annual Environmental and Effluent Release Report The monitoring wells are sampled twice annually, in spring and fall. The samples are shipped to a vendor for gamma isotopic and tritium analysis. Any positive result less than 500 pCi/L is considered as background activity and not due to plant operations. The ODCM reporting level for tritium in an environmental water sample is 20,000 pCi/L. The tritium results of samples obtained in 2017 can be found in Table 13. There was no indication of any effluent releases via groundwater.
Table 13: Summary of Onsite Groundwater Samples Monitoring Well Spring Fall H-3. DCi/L H-3, pCi/L 1A <155 <143 1B <155 <143 1C <155 <143 2A <155 <143 2B <155 <143 2C <155 <143 3A <155 <143 3B <177 <143 3C <177 <143 4A <177 264 +/-81 4B <177 <143 4C <177 <143
(<) Less than values represent the MDA of the instrument at the time of analysis The Underdrain manholes are sampled and analyzed quarterly for principal gamma emitters and tritium by PNPP personnel in accordance with site procedures. The tritium results of samples obtained in 2017 can be found in Table 14.
Table 14: Summary of Underdrain Manhole Samples Quarter 1 Quarter 2 Quarter 3 Quarter 4 Underdrain Manhole H-3. pCi/L H-3, pCi/L H-3, pCi/L H-3. pCi/L 20 <1.0E-06 <1.0E-06 <1.0E-06 <1.0E-06 23 <1.0E-06 <1.0E-06 <1.0E-06 <1.0E-06
(<) Less than values represent the ODCM LLD value Page 25
2017 Annual Environmental and Effluent Release Report RADIOLOGICAL ENVIRONMENTAL MONITORING Introduction The REMP was established at PNPP for several reasons. First, it verifies the adequacy of plant design and operation to control radioactive materials and limit effluent releases.
Second, it assesses the radiological impact, if any, that the plant has had on the surrounding environment. Third, it ensures compliance with regulatory guidelines. The REMP is conducted in accordance with the PNPP Operating License, Appendix B, Technical Specifications, and the ODCM. The Nuclear Regulatory Commission (NRC) established the REMP requirements.
A variety of samples are collected as part of the PNPP REMP. The selection of sample types, locations, and collection frequency are based on many variables. Potential pathways for the transfer of radionuclides through the environment to humans, sample availability, local meteorology, population characteristics, land use, and NRC requirements are all factors.
To ensure that the REMP data is significant and valuable, detailed sampling methods and procedures are followed to ensure that samples are collected in the same manner and from the same locations each time. All samples are packaged on site and then shipped to an independent vendor laboratory for analysis. The vendor laboratory analyzes the samples and reports results to the PNPP Chemistry Unit staff, the Lake County General Health District and the State of Ohio Department of Health. Additionally, the Lake County General Health District obtains monthly "split" samples of milk, water, and vegetation to permit an independent verification of PNPP's REMP.
Sampling Locations REMP samples are collected at numerous locations, both on site and up to 16.2 miles away from the plant. Sampling locations are divided into two general categories: indicator and control. Indicator locations are relatively close to the plant that monitor for any environmental impact due to plant operations. Control locations are those that are unaffected by plant operation; they are a greater distance from the plant and in the least prevalent wind directions. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows naturally-occurring background radiation to be taken into account when evaluating any radiological impact PNPP may have had on the environment. Table 15, Figure 3, Figure 4, and Figure 5 identify the PNPP REMP sampling locations.
Many REMP samples are collected in addition to those required by the PNPP ODCM. The ODCM requirements for each sample type are discussed in more detail later in the report.
Page 26
2017 Annual Environmental and Effluent Release Report Table 15: REMP Sampling Locations Location # Description Miles Direction Media (1) 1 Chapel Road 3.4 ENE TLD,AIP 2 Kanda Garden 1.9 ENE Broadleaf Vegetation 3 Meteorological Tower 1.0 SE TLD.AIP 4 Site Boundary 0.7 S TLD.AIP 5 Quincy Substation 0.6 SW TLD, AIP 6 Concord Service Center 11.0 SSW TLD.AIP 7 Site Boundary 0.6 NE TLD, AIP 6 Site Boundary 0.8 E TLD 9 Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Paimly Rd. at Center Rd. 0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madlsorvon-the-Lake 4.7 ENE TLD 14 Hubbard Rd. 4.9 E TLD 15 Eagle St. Substation 5.1 ESE TLD 16 Eubank Garden 0.9 S Broadleaf Vegetation 19 Goodfield Dairy 9.2 s Milk 20 Rainbow Farms 1.9 E Broadleaf Vegetation 21 Hardy Rd. - Painesville Township Park 5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St. Clair Ave. at Mentor Substation 15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Fish 29 River Rd.at Tumey Rd. 4.3 SSE TLD 30 Lane Rd. 4.8 SSW TLD 31 Wood Rd. at River Rd. 4.8 SE TLD 32 Offshore Mentor-on-th>>-Lake 15.8 WSW Fish 33 River Rd. at Blair Rd. 4.5 s TLD 34 PNPP Intake 0.2 NW Surface Water 35 Site Boundary 0.6 E TLD. AIP 36 Lake County Water Rant 3.9 WSW TLD. Drinking Water 37 Gerlica Farm 1.5 ENE Broadleaf Vegetation 39 Painesville Purification Plant 8.3 W Drinking Water 51 Rettger Milk Farm 9.7 S Milk 53 3715ParmlyRd. 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd. behind soccer field 2.5 S TLD 56 Madison High School 4.0 ESE TLD Page 27
2017 Annual Environmental and Effluent Release Report Description NHes Direction Media (1)
Location #
1.7 S UD 57 Percy High School Antioch Rd. 0.8 ENE 1W 58 4.0 ENE Surface Water 59 Lake Shoreline at Green Rd.
1.0 wsw Surface Water 60 Lake Shoreline at Perry Park Northwest Drain Mouth 0.4 WNW Sediment 64 Lake Shore, Metropolitan Park 1.4 NE Sediment 66 16.2 ssw Broad leaf Vegetation 70 H&H Farm Stand (1) AIP = Air, Iodine and Parficulate TLD = Thermolumlnescent Dosimeter Page 28
2017 Annual Environmental and Effluent Release Report NNW NNE NW WNW ENE wsw ESE SE ssw SSE 2 MILES Figure 3: REMP Sampling Locations within Two Miles of the Plant Site Page 29
2017 Annual Environmental and Effluent Release Report
\ NNW sw ssw 0 12 3 4 5 10 MILES Figure 4: REMP Sampling Locations between Two and Eight Miles from the Piant Site Page 30
2017 Annual Environmental and Effluent Release Report Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site Page 31
2017 Annual Environmental and Effluent Release Report Sample Analysis When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation and radionuclides present.
The major analyses that are performed are discussed below.
Gross beta activity measures the total amount of beta-emitting radioactivity present in a sample and acts as a tool to identify samples that may require further analysis. Beta radiation may be released by many different radionuclides. Since beta-decay results in a continuous energy spectrum rather than the discrete energy levels, or "peaks", associated with gamma radiation, identification of specific beta-emitting nudides is more difficult.
Therefore, gross beta activity only indicates whether the sample contains normal or abnormal amounts of beta-emitting radioactivity; it does not specifically identify the radionuclides present.
Gamma spectral analysis provides more specific information than does the analysis for gross beta activity. Gamma spectral analysis identifies each radionuclide, and the amount of radioactivity, present in the sample emitting gamma radiation. Each radionuclide has a very specific "fingerprint" that allows for accurate identification and quantification.
Iodine activity analysis measures the amount of radioactive iodine present in a sample.
Some media (e.g. air sample charcoal cartridges) are analyzed directly by gamma spectral analysis. With other media (e.g. milk), the radioiodines are extracted by chemical separation before being analyzed by gamma spectral analysis.
Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample. Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally from interactions with atmospheric cosmic rays and is also man-made from the nuclear fission process.
Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This capability provides a method to measure the dose received over long periods of time. The amount of energy that was stored in the TLD as a result of interaction with radiation is released by a controlled heating process and measured in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount of light is directly proportional to the amount of radiation to which the TLD was exposed. Table 16 provides a list of the analyses performed on environmental samples collected for the PNPP REMP.
The required REMP detection limits for samples is determined by sample media and the radionuclide that is being analyzed. The NRC has established LLDs for REMP sample analysis. These LLDs are listed in the PNPP ODCM. The vendor laboratory for REMP sample analysis has complied with these LLDs.
Page 32
2017 Annual Environmental and Effluent Release Report Table 16: REMP Sample Analyses Frequency Type Airborne Gross Beta Activity &
Atmospheric Weekly & Quarterly Particulates Gamma Spectral Analysis Monitoring Airborne lodine-131 Weekly Radioiodine Monthly & Gamma Spectral Analysis &
Terrestrial Semi-Monthly when Milk lodine-131 Monitoring cows are on pasture Broadteaf Monthly during Gamma Spectral Analysis Vegetation rowing season __^____
Gross Beta Activity &
Aquatic Monitoring Water Monthly Gamma Spectral Analysis Quarterly Tritium Activity Semi-Annually Gamma Spectral Analysis Fish Semi-annuaily Gamma Spectral Analysis Sediment Quarterly &
Direct Radiation Gamma Dose TLD Monitoring Annually Sampling Program The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the environmental monitonng program with pre-operational data (he., data from before 1986), operational data from previous years, and SiSon date The results for each sample type are discussed below and compared
£hMori* d* to determine if there are any observable trends. All results are expressed rcSor^Mons. Refer to Appendix B, 2017 REMP Data Summary Reports for a detailed listing of these results. The NRC requires special reporting whenever sample analysis results exceed set limits. No values exceeded those limits.
Program Changes There were no changes to the REMP during this reporting period.
Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional two air sampling locations>above the five locations (four indicators and one control) required by the ODCM. Six oMthese locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps draw continuoussampl^a? rate °f approximately two cubic feet per minute. The air is drawn through glass fiber filters to collect Page 33
2017 Annual Environmental and Effluent Release Report particulate material and a charcoal cartridge to adsorb iodine. The samples are collected on a weekly basis, 52 weeks a year, from each of the seven air sampling stations.
Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma spectral analysis quarterly. A total of 371 air paniculate and 371 air radioiodine samples were collected and analyzed.
Gross beta activity was detected in 371 of the 371 air samples. The average gross beta activity for indicator locations was 0.023 pCi/m3 and the controls was 0.026 pCi/m3.
Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations. Figure 6 reflects the average gross beta activity for 2017 and previous years. All radioiodine samples were less than the lower limit of detection for iodine-131.
With the exception of naturally-occurring beryllium-7, no radionuclides were icientified in the quarterly gamma spectral analysis above the LLD values.
0.035 0.03 0.025 0.02 0.015 0.01 0.005 0
§ 8 I a a
©
<N a
o IN a
o f\l o
IN o
CM o
M Year Indicator >> Control Figure 6: Annual Average Gross Beta Activity, in Air Terrestrial Monitoring Collecting and analyzing samples of milk and broadleaf vegetation provides data to assess the build-up of radionuclides that may be Ingested by humans. The historical data from soil and vegetation samples provides information on atmospheric radionucJlde deposition.
Milk Samples of milk are collected once each month from November through March, and twice each month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture rather than on stored feed. The PNPP REMP includes two milk locations.
Page 34
2017 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 3
from the available locations to a Milk samples are analyzed by gamma sp ^ exception or naiuraiiy radionuclides. A total of 38 milk samples were collected occurring potassium-40, no other radionuclides were detected Broadleaf Vegetation miles SSW from PNPP.
tata SSrtWum-7 and potassium^, both ^
^
were found in the samples. No other radionuclides were detected Aquatic Monitoring these pathways.
Water samples were analyzed for tritium activity.
beta activity was detected in 42 of the 58 samples collected. The indicator average control locations. No tritium or gamma activity was detected.
Page 35
2017 Annual Environmental and Effluent Release Report 4.5 4
~~d. 3.5~~
~~g. 3 f~~
cb CO 2.5 2
§ 1.5 1
0.5 0
i-4 CN KO Sri IN 8
M 8
IN 8
CM 8 fS CM Year i Indicator m Control Figure 7: Annual Average Gross Beta Activity, In Water Sediment Sampling shoreline sediments provides an indication of the accumulation of particulate radionuclides which may lead to an external radiation source to fishermen and swimmers from shoreline exposure. Sediment was sampled from two locations.
Four sediment samples were collected and analyzed by gamma spectroscopy. The only radionuciide detected was naturally-occurring potassium-40.
Fish Fish are analyzed primarily to quantify the radionuciide intake by humans and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two locations annually during the fishing season as required by the ODCM. Important sport or commercial species are targeted, and only the fillets are sent to the laboratory for analysis.
Eleven fish samples were collected and analyzed: Five indicator and six control samples.
The species were smallmouth bass, white perch, walleye, channel catfish, freshwater drum, rainbow trout, redhorse sucker and yellow perch. Only naturally-occurring potassium-40 was detected In the samples.
Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)
Environmental radiation is measured directly at 27 locations around the PNPP site and at two control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four to five miles from the plant. The control locations are over ten miles from the plant in the two least prevalent wind directions. Each location has three TLDs, two of which are changed quarterly and one that is changed annually.
Page 36
2017 Annual Environmental and Effluent Release Report A total of 261 TLDs were collected and analyzed. This includes 232^ collected oni a quarterly basis and 29 collected annually. Annual TLDs are not required per the ODCM and are used for supplemental data only.
The annual average dose for all indicator locations was 65.8 mrem and 61.8 mrem for the control locations.
The average quarterly dose for the indicator locations was 12.0 mrem, and 11.4 mrem for the control locations. Refer to Figure 8 for the average quarterly TLD dose rates for both indicator and control locations.
18 16 14 t 12 3 io or I <<
4 2
0 to S S § OI 8
fM fM Year Indicator
Control Figure 8: Average Quarterly TLD Dose Conclusion There are no discemable trends or increase in radiological parameters when comparing cun^ montonn^sulte to pre-operational studies. Non-routine analyses were not required StK^rfing period. There is no detectabte radiological effect on the surroundmg environment due to operation of the Perry Nuclear Power Plant.
Page 37
2017 Annual Environmental and Effluent Release Report Inter-Laboratory Cross-Check Comparison Program Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures. Regulatory Guide 4.15 specifically requires that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.
The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute Standard Technology). In response to this problem, the vendor lab incorporated a program offered by Environmental Resource Associates (ERA Company), which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation as an equivalent program. In addition to comparison cross checks performed with the ERA Company, 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) and~~
~~Participating in the Department of Energy's Mixed Analyte Performance Program (MAPEP).~~
See Appendix A, for the vendor Inter-Laboratory Cross-Check Comparison Program Results.
Land Use Census Introduction Each year a Land Use Census is conducted to identify the locations of the nearest milking animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land. Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the REMP. The census is conducted by traveling all roads within a five-mile radius of the plant site and recording and mapping the locations of the nearest resident, milk animal, and vegetable garden. The Land Use Census was conducted in August, 2017. The census identified the garden, residence and milking animal locations identified in Table 17 and Table 18 and depicted in Figure 9.
Note that the W, WNW, NW, NNW, N, and NNE sectors extend over Lake Erie and are not included in the survey.
Page 38
2017 Annual Environmental and Effluent Release Report Discussions and Results In general, the predominant land use within the census area continues to be rural/
agricultural. In Vecent years, however, it has been noted that tractsnrf land once used fo farming are now being developed as ^-industrial ^
reflected in the loss of available milking animals within a five kilometer radius of PNPP to support the REMP.
There were no changes to the REMP sampling locations compared to the 2016 Land Use Census. Refer to Figure 3,4 and 5 for the map identification.
Table 17 identifies the nearest residences, by sector, to the PNPP There were no changes from the 2016 Land Use Census. Refer to Figure 9 for map identification.
Table 17: Nearest Residence, By Sector Location Address Miles from Map Locator Sector PNPP Number 4384 Lockwood 0.7 1 NE 4602 Lockwood 1.1 2 ENE 2626 Antioch 1.0 3 E
2836 Antioch 1.1 4 ESE 4495 North Ridge 1.3 5 SE 0.9 6 SSE 3119 Parmly c 3121 Center 0.9 7 0.9 8 SSW 3850 Clark 2997 Perry Park 1.2 9 SW 1.0 10 wsw 3460 Parmlv Page 39
2017 Annual Environmental and Effluent Release Report Table 18 lists the nearest gardens by sector to the PNPP consisting of at least 500 square feet. There are four changes to garden locations from the 2016 Land Use Census, which include those located fn the northeast, east-northeast, east, and south-southwest sectors.
These new locations were documented by confirming that the previous location either no longer exists or a closer location within the sector has more recently become available.
Refer to Figure 9 for map identification.
Table 18: Nearest Garden, By Sector Sector Location Address Miles from Map Locator PNPP Number NE 2348 W. Hemlock 0.9 11 ENE 2452 Antioch 1.1 12 E 2634Antioch 1.1 3 ESE 2836 Antioch 1.1 4 SE 4671 North Ridge 1.3 15 SSE 4225 Red Mill Valley 1.1 16 S 3121 Center Rd. 0.9 7 SSW 3300 Ohio St 2.3 17 SW 3021 Perry Park 1.3 13 WSW 3460Parmly 1.0 14 Page 40
2017 Annual Environmental and Effluent Release Report Figure 9: Land Use Census Map Page ^1
2017 Annual Environmental and Effluent Release Report CLAM/MUSSEL MONITORING Introduction Sampling for macro-invertebrates (clams and mussels) has been conducted in Lake Erie in the vicinity of PNPP since 1971. The dam/mussel program currently focuses on two species: Corbicula fluminea (Asiatic clam) and Dreissena polymorpha (zebra mussel).
Corbicula Program Monitoring for Corbicula was initiated in response to an NRC bulletin and concerns of the Atomic Safety and Licensing Board. The monitoring was done as part of the Environmental Protection Plan (Operating License, Appendix B). The program consists of visually inspecting the raw water systems, when they are opened for maintenance. The purpose of this program is to detect Corbicula, should it appear at PNPP.
Monitoring Samples were collected from raw water systems and examined for shells and fragments. In addition to sample collections, plant components that use raw water are inspected when opened for maintenance or repair. Sample collection/inspection dates are listed in Table 19.
Table 19: Corbicula Monitoring Date Sample Location 01/25/2017 LP Condenser "C" Outlet Waterbox 01/27/2017 HP Condenser "C 02/24/2017 P54 - Fire Protection 03/15/2017 ESW Strainer 06/09/2017 P64 - Fire Protection 07/01/2017 N34 - Turbine Lube Oil Cooler "B" 07/08/2017 N34 - Turbine Lube Oil Cooler "A" 07/31/2017 P45 - ESW "A" Discharge Strainer 08/11/2017 N34 - Turbine Lube Oil Cooler "B" 08/11/2017 N34 - Turbine Lube Oil Cooler "A" 08/11/2017 N34 - Turbine Lube Oil Cooler "B" 08/18/2017 N34 - Turbine Lube Oil Cooler "A" 09/03/2017 N34 - Turbine Lube Oil Cooler "A" 10/09/2017 N34 - Turbine Lube Oil Cooler "B" 12/21/2017 P54 - Fire Protection
2017 Annual Environmental and Effluent Release Report Conclusions Although Corblcula have been detected at the Eastlake Power Platt. rt Iim noi: been demonstrated that their presence has created any operational >>*"£""*
past, the monitoring program did not identify Corbicula in any sample collected.
Dreissena Program Dreissena, or zebra mussels, were first discovered at PNPP in September1988. Tte initial collection of 19 mussels was made as part of the Corbicula monrtonng program^ The Sena monitoring program began in 1989 with monrtonng and testing. The current control program was designed and implemented In 1990.
Monitoring In addition to visually inspecting the plant's raw water systems when they are opened for tSSSm mainienanue or S
repair monitoring or repair, monitoring methods methods include include the the use of <rc?'^"Ztf use of ^m^erc)^^^!1ndrls'?e" tf Sream monitors. Commercial divers monitor mussel infestajon WJ^P*1"^
forebays basins, and the intake and discharge structures. Divers have also beeruused to take underwater videos of the water basins and intake tunnel Side^tream monitors are flow-through containers that receive water diverted from plant systems and are set up at two in-plant locations during the mussel season.
Treatment Chemicals used for mussel control included sodium hypochlorite and a commercial molluscicide The chlorine is intermittently injected into the plant service water, emergency service water, and circulating water systems by metering sodium hypochlonte into each system'si^uent. Sodium bisulfite is added at the plant discharge structure for dechlorination prior to return into Lake Erie.
The OEPA has approved the use of a commercial molluscicide. The chemical selected for
^eatthVPN^ Treatment was applied on^> ir!. 20T1?TTieadive ingredients were detoxified by adsorption using bentonrte clay pnor to discharge into Lake Erie.
Results The effectiveness of the intermittent biocide treatment has been determined in several ways.
First visual inspections of raw water system components are conducted when systems are opTn dufS nSnance or repair. In addition, settlement monitors^were inspected for new settlement No live settlement has been found in any plant component to date.
The effectiveness of the application of the commercial molluscicide was measured by otamS^oMHy observing m ^
of mussels placed in a flow-through container installed
^.^ ^^^ The ^ ^
.n gfrt serv^e fe uttong the flow-corrtainer was 100%. To date, PNPP has had no significant problems related to zebra mussels.
2017 Annual Environmental and Effluent Release Report Conclusions PNPP 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 treatment will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels.
HERBICIDE APPLICATIONS Herbicides are used sparingly on the PNPP site. A request must be made to and approved by the PNPP Chemistry Unit prior to spraying to ensure that only approved chemicals are used, and only in approved areas. Each application was in compliance with the OEPA rules and regulations. There were no adverse environmental impacts observed during weekly site environmental inspections as a result of these applications. The herbicides used were Mojave, Glyphosate, Clipper Herbicide, and Round-Up. For each application, the type of weed to be treated dictated the herbicide and concentration to be used. Table 20 provides quantity for each chemical used. The quantity represents the amount of herbicide applied, prior to any dilution.
Table 20: Herbicide Applications Chemical Amount Mojave 1751b.
Glyphosate 520 gal.
Clipper Herbicide 1gal.
Round-Up 110oz.
2017 Annual Environmental and Effluent Release Report SPECIAL REPORTS NPDES Permit Exceedances The OEPA issues the National Pollutant Discharge Elimination System (NPDES) permit. It establishes monitoring requirements and limits for discharges from the PNPP. It also specifies the locations from which the plant is allowed to discharge.
There were no NPDES issues identified at PNPP in 2017 Environmental Protection Plan The Environmental Protection Plan (EPP), which is Appendix B of the PNPP Operating License, requires a non-radiological environmental monitoring and reporting program be established at the PNPP.
There were no non-compliance reports submitted in 2017 Environmental Impact Evaluations All proposed changes to the PNPP design or operation, as well as tests or experiments, must be evaluated for potential environmental impacts in accordance with the EPP and administrative quality assurance procedures. There were no proposed changes to the facility or programs that if performed could have resulted in an adverse environmental impact in 2017.
2017 Annual Environmental and Effluent Release Report Appendix A Inter-Laboratory Cross Check Comparison Program Results
taJ, Inc.
700 LutamhrftOKt
Nortobmak, a. B0082-2310 phom (*4Tf 69*4700 - tax 0471364-43t7 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.
January, 2017 through December, 2017
Appendix A Interlaboratorv/ Intralaboratorv Comparison Program Results Environmental, Inc., Midwest Laboratory has participated In Interfaboratory comparison (crosscheck) programs since the formulation of Ifs quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionudides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of spedfied radionudides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the Instruments or procedures used.
Results in Table A-1 were obtained through participation in the RAO PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermohiminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years avaiabte upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for trie past twelve months. Data for previous years available upon request Table A-5 lists analytical results from the In-house "duplicate" program for the past twelve months. Acceptance Is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is aet at +/-2 sigma.
Out-of-limit results are explained directly below the result.
A1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES ABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation Level for single determination Anah 5to lOOpCWiterorkg 5.0 pCMHer Gamma Emitters
>100pCI/literorkg 10% of known value 5.0 pCi/IHer Strontlum-89b 5to50pCUllterorkg
>50pCWiterorkg 10% of known value 2 to 30 pCi/iiter or kg 5.0 pCi/liter Strontiurn-BO*
>30pCWIterorkg 10% of known value 20.1 g/literorkg 10% of known value Potassium-40 s 20 pCi/Kter 5.0 pCi/IHer Gross alpha
> 20 pCi/ftter 25% of known value s100pCi/1iter S.OpCWiter Gross beta
> 100 pCi/liter 10% of known value s 4,000 pCi/liter +/-1o =
Tritium 169.85 x (known)'
> 4,000 pCi/lter 10% of known value 2 0.1 pCi/liter 15% of known value Radium-226,-228 2 0.1 pCi/liter, gram, or sample 10% of known value Plutonium s 56 pCi/liter BpCl/Uter lodine-131, 10% of known value lodine-129b > 55 pCI/lrler i 35 pCi/liter BpCWiter Uranlum-238,
>35pCi/liter 15% of known value Nickeh63b TechnetiunvSS*
50to100pCi/ltter 10 pCWiter lron-55b
> 100 pCi/liter 10% of known value 20% of known value Other Analyses From EPA publcatlon, "Environmental Radioactivity Laboratory Intercomparteon Studies Program-, Fiscal Year, 1981-19B2, EPA-800/4-81-004.
b Laboratory Umit A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8.
RAD study Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERW-95 1/9/2017 Sr-49 51.9 +/-4.6 55.5 44.3 - 63.2 Pass ERW-95 1/9/2017 Sr-90 43.6 +/- 2.4 43.1 31.8-49.5 Pass ERW-97 1/9/2017 Ba-133 78.2 +/-4.1 85.6 72.0-94.2 Pass ERW-97 1/9/2017 Cs-134 53.9 +/- 3.8 52.6 42.4 - 57,9 Pass ERW-97 1/9/2017 Cs-137 122 +/-6 112 101 -126 Pass ERW-97 1/9/2017 Co-60 117+/-4 113 102 -126 Pass ERW-97 1/9/2017 Zn-65 208 +/-13 189 170-222 Pass ERW-99 1/9/2017 Gr. Alpha 48.9 +/-2.4 52.3 27.3-65.5 Pass ERW-99 1/9/2017 Gr. Beta 37.1 +/-1.3 41.6 27.7-49.0 Pass ERW-101 1/9/2017 1-131 22.3 +/- 0.6 24.3 20.2 - 28.8 Pass ERW-103 1/9/2017 Ra-226 11.3 +/-0.4 12.7 9.5 -14.7 Pass ERW-103 1/9/2017 Ra-228 6.10 +/-0.90 6.20 3.8 - 6.1 Pass ERW-103 1/9/2017 Uranium 11.8 +/-0.8 12.6 9.9 -14.4 Pass ERW-106 1/9/2017 H-3 12,600 +/-300 12,500 10,900 -13,800 Pass ERW-3344 7/10/2017 Sr-89 29.0 +/- 10.0 26.4 18.4-32.9 Pass ERW-3344 7/10/2017 Sr-90 33.8 +/-3.3 36.0 26.4-41.5 Pass ERW-3346 7/10/2017 Ba-133 66.4 +/-4.1 66.3 55.2 - 72.9 Pass ERW-3346 7/10/2017 Cs-134 27.0 +/-4.3 24.4 18.7-27.2 Pass ERW-3346 7/10/2017 Cs-137 57.4 +/-4.5 51.6 46.4 - 59.6 Pass ERW-3346 7/10/2017 Co-60 92.6 +/-4.4 88.6 79.7-99.8 Pa6S ERW-3346 7/10/2017 Zn-65 32.4 +/-6.0 32.7 27.3-41.6 Pass ERW-3348 7/10/2017 Gr. Alpha 23.7 +/-1.9 25.7 13.0-34.1 Pass ERW-3348 7/10/2017 Gr. Beta 54.6 +/-1.6 63.0 43.5 - 69.6 Pass ERW-3350 7/10/2017 1-131 25.4 +/- 1.3 25.5 21.2-30.1 Pass ERW-3352 7/10/2017 Ra-226 1.38 +/-0.15 1.29 1.07-1.95 Pass ERW-3352 7/10/2017 Ra-228 6.70 +/-0.93 5.66 3.45 - 7.47 Pass ERW-3352 7/10/2017 Uranium 58.4 +/-0.9 66.7 54.3 - 73.9 Pass ERW-3354 7/10/2017 H-3 5,254 +/-224 5,060 4,340 - 5,570 Pass Results obtained by Environmental, Inc., Mkfwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards). '
mrem Lab Code Irradiation Delivered Reported b Performance c Date Description Dose Dose Quotient (P)
Environmental. Inc. Group 1 10/16/2017 Spike 1 59.0 49.3 -0.16 2017-1 10/16/2017 Spike 2 59.0 53.2 -0.10 2017-1 10/16/2017 Spike 3 59.0 52.7 -0.11 2017-1 10/16/2017 Spike 4 59.0 53.4 *0.09 2017-1 10/16/2017 Spike 5 59.0 51.8 -0.12 2017-1 10/16/2017 Spike 6 59.0 54.0 -0.08 2017-1 10/16/2017 Spike 7 59.0 52.0 -0.12 2017-1 2017-1 10/16/2017 Spike 6 59.0 52.6 -0.11 10/16/2017 Spike 9 59.0 54.6 -0.07 2017-1 2017-1 10/16/2017 Spike 10 59.0 50.4 0.15 10/16/2017 Spike 11 59.0 53.9 -0.09 2017-1 10/16/2017 Spike 12 59.0 55.7 -0.06 2017-1 10/16/2017 Spike 13 59.0 50.2 -0.15 2017-1 10/16/2017 Spike 14 59.0 52.4 -0.11 2017-1 2017-1 10/16/2017 Spike 15 59.0 54.3 -0.08 10/16/2017 Spike 16 59.0 53.2 -0.10 2017-1 10/16/2017 Spike 17 59.0 50.1 -0.15 2017-1 10/16/2017 Spike 18 59.0 52.3 -0.11 2017-1 10/16/2017 Spike 19 59.0 50.3 -0.15 2017-1 10/16/2017 Spike 20 59.0 50.7 -0.14 2017-1 10/16/2017 Spike 21 59.0 53.1 -0.10 2017-1 10/1672017 Spike 22 59.0 51.5 -0.13 2017-1 10/16/2017 Spike 23 59.0 54.4 -0.08 2017-1 10/16/2017 Spike 24 59.0 53.3 -0.10 2017-1 10/16/2017 Spike 25 59.0 53.7 -0.09 2017-1 10/16/2017 Spike 26 59.0 51.6 -0.13 2017-1 10/16/2017 Spike 27 59.0 51.5 -0.13 2017-1 10/16/2017 Spike 28 59.0 51.6 -0.13 2017-1 2017-1 10/16/2017 Spike 29 69.0 49.9 -0.15 10/16/2017 Spike 30 59.0 553 -0.06 2017-1 52.4 -0.11 Pass*
Mean (Spike 1-30) 1.7 0.03 Pass*
Standard Deviation (Spike 1-30) a TLD's were irradiated by the UnlvereSly of Wssoonsin-Macfison Radiation Calibration Laboratory fbflowinfl ANSI N13.37 protocol from a known air kerma rate. TLD'swereread and the results were submitted by Environmental Inc. to the University of WisconsirvMadlson Radiation CaSbration Laboratory tor comparison to the delivered dose.
b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)K, -150. mrem/cGy - 1000.
c Performance Quotient (P) is cateutated as ((reported dose - convenHaiy true value) conventlally true value) where the convenUalry true value is the deBvered dose.
d Acceptance is achieved when neitherthe absolute vahje of mean of the P values, rwrthe standard deviattoncrfth^
exceed 0.15.
A2-1
TABLE A-2. Thermoluminesoent Dosimetry, (TLD, CaS04: Dy Cards).
~~mrem Lab Code Irradiation Delivered Reported b Performance Date n Dose Dose Quotient (P)~~
Environmental. Inc. Group 2 2017-2 10/16/2017 Spike 31 186.0 164.7 -0.11 2017-2 10/16/2017 Spite 32 186.0 172.0 *O.08 2017-2 10/16/2017 Spite 33 186.0 167.3 -0.10 2017-2 10/16/2017 Spice 34 186.0 160.6 -0.14 2017-2 10/16/2017 Spite 35 186.0 171.7 *0.08 2017-2 10/16/2017 Spite 36 186.0 177.0 O.05 2017-2 10/16/2017 Spite 37 186.0 176.7 -0.05 2017-2 10/16/2017 Spite 36 186.0 165.5 -0.11 2017-2 10/16/2017 Spite 39 186.0 174.6 -0.06 2017-2 10/16/2017 Spite 40 166.0 172.7 -0.07 2017-2 10/16/2017 Spite 41 186.0 167.8 -O.10 2017-2 10/16/2017 Spite 42 186.0 161.0 0.13 2017-2 10/16/2017 Spite 43 186.0 166.3 -0.11 2017-2 10/16/2017 Spite 44 186.0 172.4 -0.07 2017-2 10/16/2017 Spite 45 186.0 173.0 -0.07 2017-2 10/16/2017 Spite 46 186.0 169.5 O.09 2017-2 10/16/2017 Spite 47 186.0 169.0 -O.09 2017-2 10/16/2017 Spite 46 186.0 166.9 -0.10 2017-2 10/16/2017 Spite 49 186.0 165.9 -0.11 2017-2 10/16/2017 Spite 50 186.0 166.7 -0.10 2017-2 10/16/2017 Spite 51 186.0 161.1 -0.13 2017-2 10/16/2017 Spite 52 186.0 173.4 0.07 2017-2 10/16/2017 Spite 53 186.0 173.1 -0.07 2017-2 10/16/2017 Spite 54 186.0 160.0 -0.14 2017-2 10/16/2017 Spike 55 186.0 166.1 -0.11 2017-2 10/16/2017 Spite 56 186.0 164.5 -0.12 2017-2 10/16/2017 Spite 57 186.0 163.8 -0.12 2017-2 10/16/2017 Spite 58 186.0 159.9 -0.14 2017-2 10/16/2017 Spice 59 186.0 165.6 -0.11 2017-2 10/16/2017 Spite 60 186.0 165.0 -0.11 Mean (Spike 31-60) 167.8 -0.10 Pass4 Standard Deviation (Spite 31-60) 5.0 0.03 Pass" a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calbration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsn-Madbon Radiation Calibration Laboratory for comparison to the delivered dose.
b Reported dose was converted torn exposure (R) to Air Kerma (cGy) using a convention of 0.876. Conversion from afr kerma to ambient dose equivalent for Cs-T37 at the reference dose point H*(1O)K, 1.20. mrem/cQy - 1000.
c Performance Quotient (P) is calculated as ((reported dose - conventtally true value) + conventialry true value) where the conventtaHy true value is the delvered dose.
d Acceptance Is achieved when norther the absolute value of mean of the P values, northe standard deviation of the P values exceed 0.16.
A2-2
TABLE A-3. In-House "Spiked" Samples Concentration Analysis Laboratory resulte Known Control Ub Code Date 2s.n=1c Activity Limits'3 Acceptance Cs-134 38.2 +/-8.1 36.2 29.0 *43.4 W-010417 4/29/2016 Cs-137 78.0 +/-8.8 71.9 57.5 -86.3 W-010417 4/29/2016 Ra-226 18.1 +/-0.4 16.7 13.4 -20.1 SPW-306 1/4/2017 17,243 10,346 -24,140 Pass SPW-32 1/8/2017 H-3 17,849 +/-393 20.1 16.1 -24.1 Pass SPW-46 1/9/2017 Gr. Alpha 20.0 +/-0.4 28.9 23.1 -34.6 Pass SPW-46 1/9/2017 Gr.Beta 29.0 +/-0.3 17,243 10,346 -24,140 Pass SPW-92 1/11/2017 H-3 18,095 +/-397 36.6 29.3 -43.9 Pass SPW-142 1/12/2017 Sr-90 39.4 +/-2.3 17,243 10,346 -24.140 Pass SPW-155 1/19/2017 H-3 17,974 +/-400 17.243 10,346 -24.140 Pass SPW-186 1/23/2017 H-3 17,383 +/-366 17,542 +/-368 17,243 10,346 -24,140 SPW-232 1/19/2017 H-3 17,243 10,346 -24,140 Pass SPW-304 1/26/2017 H-3 17.782 +/-400 17,910 +/-406 17,243 10.346 -24,140 Pass SPW-333 1/30/2017 H-3 33.7 +/-6.1 36.2 29.0 -43.4 Pass W-020217 4/29/2016 Cs-134 71.9 57.5- -86.3 Pass W-020217 4/29/2016 Cs-137 78.4 +/-7.3 36.6 29.3
43.9 Pass SPW-412 2/6/2017 Sr-90 36.2 +/-2.4 17,243 10,346 -24,140 Pass SPW-465 2/8/2017 H-3 17,573 +/-396 17,243 10,346 -24,140 Pass SPW-661 2/15/2017 H-3 17,358 +/-395 17,243 10,346 -24,140 Pass SPW-605 2/16/2017 H-3 17,820 +/-401 17,614 +/-376 17,243 10,346 -24,140 Pass SPW-657 2/17/2017 H-3 17,243 10,346 -24.140 Pass SPW-714 2/23/2017 H-3 17,662 +/-400 17,243 10,346 - 24,140 Pass SPW-737 2/28/2017 H-3 17.196 +/-395 38.9 +/-0.1 41.5 33.2 -49.8 Pass SPAP-740 2/28/2017 Gr.Beta 0.98 0.78 -1.18 Pass SPAP-742 2/24/2017 Cs-134 1.05 +/-0.60 90.4 +/-2.5 92.9 74.3 -111.5 Pass SPAP-742 2/24/2017 Cs-137 36.6 29.3 -43.9 Pass SPW-746 2/28/2017 Sr-90 42.8 +/-2.5 4735 3788 -5682 Pass SPW-748 2/28/2017 C-14 4270 +/-17 463 +/-4 400 240 -560 Pass SPW-750 2/28/2017 Ni-63 1090 870 -1300 Pass SPF-752 2/28/2017 Cs-134 1033 +/-38 2820 2250 -3380 Pass SPF-752 2/28/2017 Cs-137 3071 +/-61 16.7 13.4 -20.1 Pass SPW-781 3/1/2017 Ra-226 18.1 +/-0.4 17,243 13,794 -20,692 Pass SPW-783 3/1/2017 H-3 17,653 +/-400 36.2 29.0 -43.4 Pass W-030517 4/29/2016 Cs-134 38.0 +/-9.0 71.9 57.5 -86.3 Pass W-O30517 4/29/2016 Cs-137 80.9 +/-9.2 17,243 13,794 -20,692 Pass SPW-1010 3/14/2017 H-3 17,312 +/-395 22.4 +/-0.5 20.1 12.0 -28.1 Pass SPW-1026 3/16/2017 Gr. Alpha 28.9 17.3 -40.4 Pass SPW-1026 3/16/2017 Gr.Beta 29.2 +/-0.3 17.243 13,794 -20,692 Pass SPW-1092 3/21/2017 H-3 17.252 +/-390 17,243 13,794 -20,692 Pass SPW-1151 3/24/2017 H-3 17,009 +/-388 36.3 29.0 -43.5 Pass SPW-1163 3/28/2017 Sr-90 39.0 +/-2.3 16.0 9.6 -22.4 Pass SPW-1178 3/29/2017 Ra-228 15.1 +/-1.9 A3-1
TABLE A-3. In-House "Spiked" Samples Concentration a Lab Codeb Date Analysis Laboratory results Known Control 2s, n=1 ° Activity Limits* Acceptance SPW-1232 3/30/2017 H-3 17,150 +/-390 17,243 13,794-20,692 Pass SPW-1246 3/31/2017 1-131 (G) 33.0 +/- 7.3 36.6 29.3-43.9 Pass SPW-1246 3/31/2017 Cs-134 28.9 +/-4.6 26.6 21.3-31.9 Pass SPW-1248 3/31/2017 Cs-137 80.6 +/- 8.2 70.4 56.3 - 84.5 Pass SPMH248 3/31/2017 H31{G) 39.8 +/- 7.0 36.6 29.3 - 43.9 Pass SPMI-1248 3/31/2017 Cs-134 26.9 +/-5.9 26.6 21.3-31.9 Pass SPMI-1248 3/31/2017 Cs-137 70.4 +/- 6.9 70.4 56.3 - 84.5 Pass SPMI-1248 3/31/2017 H31 36.2 +/-0.6 36.6 29.3-43.9 Pass SPW-1295 3/31/2017 Ra-226 17.9 +/- 0.4 16.7 13.4-20.1 Pass SPW-1304 4/4/2017 H-3 17,741 +/-398 17,243 13,794-20,692 Pass SPW-1359 4/5/2017 H31 44.3 +/- 0.5 47.6 38.1 -57.1 Pass SPW-1378 4/7/2017 H-3 17,528 +/-395 17,243 13,794-20,692 Pass SPW-1391 4/7/2017 Gr. Alpha 21.1 +/-0.4 20.1 12.0-28.1 Pass SPW-1391 4/7/2017 Gr. Beta 27.8 +/-0.3 28.2 17.3 -40.4 Pass SPW-1480 4/12/2017 H-3 17,399 +/-392 17,243 13,794 - 20,692 Pass W-041317 4/29/2016 Cs-134 34.6 +/- 5.6 36.2 29.0-43.4 Pass W-041317 4/29/2016 Cs-137 81.9 +/-8.0 71.9 57.5 - 86.3 Pass SPW-1480 4/12/2017 H-3 17,399 +/-392 17,243 13,794 - 20,692 Pass SPW-1575 4/18/2017 H-3 17,419 +/-393 17,243 13,794-20,692 Pass SPW-1626 4/20/2017 Sr-90 37.2 +/- 2.4 36.3 29.0-43.5 Pass SPW-1658 4/21/2017 H-3 17,194 +/-391 17,243 13,794-20,692 Pass SPW-1776 4/26/2017 H-3 16,609 +/-386 17,243 13,794-20,682 Pass SPW-1806 4/27/2017 H-3 17,203 +/-390 17,243 13.794-20,692 Pass SPW-1937 5/3/2017 H-3 16,690 +/- 385 17,243 13,794 - 20,692 Pass SPW-1971 5/5/2017 Sr-90 41.5 +/-2.2 36.3 29.0-43.5 Pass SPW-2033 5/8/2017 H-3 16,780 +/-386 17,243 13,794-20,692 Pass SPW-2420 5/9/2017 Ra-226 16.3 +/- 0.5 16.7 13.4-20.1 Pass W-O51517 4/29/2016 Cs-134 36.3 +/- 5.0 36.2 29.0-43.4 Pass W-051517 4/29/2016 Cs-137 68.9 +/- 6.6 71.9 57.5-86.3 Pass SPW-2284 5/22/2017 H-3 16,935 +/- 389 16.703 13.362-20,043 Pass SPW-2354 5/23/2017 H-3 17,006 +/- 390 16,700 13,360-20,040 Pass SPW-2891 5/23/2017 Ra-226 17.5 +/-0.4 16.7 13.4-20.1 Pass SPW-2418 5/23/2017 Ra-228 14.0 +/- 1.8 16.0 11.2-20.8 Pass SPW-2439 5/25/2017 Ra-228 13.0 +/-1.8 16.0 11.2-20.8 Pass SPMI-2378 5/24/2017 Sr-89 83.7 +/- 4.9 98.4 78.7-118.1 Pass SPMI-2378 5/24/2017 Sr-90 39.5 +/-1.5 36.1 26.9-43.4 Pass SPW-2468 5/2672017 H-3 17,065 +/- 391 16,692 13,354-20,031 Pass SPW-2848 5/26/2017 1-131 56.4 +/- 0.6 58.3 46.6-70.0 Pass SPW-2602 6/1/2017 H-3 17,596 +/- 396 16,677 13,342-20,012 Pass SPW-2659 6/5/2017 H-3 17,027 +/-390 16,677 13,342-20,012 Pass SPW-27B0 6/9/2017 H-3 17,101 +/-392 17,101 13,325 -19,988 Pass A3-2
TABLE A-3. In-House "Spiked" Samples Concentration
Laboratory results Known Control Lab CodeD Date Analysis 2s, n=1 ° Activity Limits* Acceptance 16,683 +/-364 16,649 13,319-19,978 Pass SPW-2798 6/12/2017 H-3 39.2 +/-2.3 36.1 28.9-43.4 Pass SPW-2943 6/19/2017 Sr-90 17.6 +/- 0.5 16.7 13.4-20.1 Pass SPW-3509 6/15/2017 Ra-226 35.0 +/-6.2 36.2 29.0-43.4 Pass W-061317 4/20/2016 Cs-134 71.9 57.5 - 86.3 Pass W-O61317 4/29/2016 Cs-137 77.4 +/-7.8 16,419 +/-378 16,620 13,296-19,945 Pass SPW-3041 8/23/2017 H-3 15.5 +/-0.6 16.7 13.4-20.1 Pass SPW-3511 6/23/2017 Ra-226 18,507 13,286 -19,929 Pass SPW-3103 6/28/2017 H-3 16,507 +/- 380 112.7 +/-1-9 107.8 86.2 -129.4 Pass SPW-3117 6/29/2017 Tc-99 17.8 +/-0.5 16.7 13.4-20.1 Pass SPW-3513 6/29/2017 Ra-226 36.1 28.9-43.4 Pass SPW-3188 7/3/2017 Sr-90 38.1 +/-2.2 16,649 13,319 -19,978 Pass SPW-3283 7/11/2017 H-3 16,057 +/- 347 17.7 +/-0.4 16.0 11.2-20.8 Pass SPW-4054 7/11/2017 Ra-226 22.3 +/-0.5 20.1 12.0-28.1 Pass SPW-3467 7/14/2017 Gr. Alpha 29.1 +/-0.3 28.2 17.3-40.4 Pass SPW-3467 7/14/2017 Or. Beta 16,507 13,286-19,929 Pass SPW-3449 7/15/2017 H-3 17,196 +/-393 16,764 +/-386 16,507 13,286 -19,929 Pass SPW-3548 7/19/2017 H-3 16,507 13,286-19,929 Pass SPW-3728 7/24/2017 H-3 16,117 +/-354 16,645 +/-384 16,507 13,286-19,929 Pass SPW-3794 7/28/2017 H-3 38.6 +/- 5.6 36.2 29.0-43.4 Pass W-072817 4/29/2016 Cs-134 71.9 57.5-86.3 Pass W-072817 4/29/2016 CS-137 76.5 +/-7.6 22.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3905 8/3/2017 Gr. Alpha 27.6 +/-0.3 28.2 17.3-40.4 Pass SPW-3906 8/3/2017 Gr. Beta 17,636 +/-403 16,507 13,286 -19,929 Pass SPW-4030 8/9/2017 H-3 16,507 13,286 -19,929 Pass SPW-4086 8/14/2017 H-3 17,472 +/-401 17,013 +/-393 16,507 13,286 -19,929 Pass SPW4207 8/17/2017 H-3 34.7 +/-6.4 36.2 29.0-43.4 Pass W-083017 4/29/2016 Cs-134 71.9 57.5-86.3 Pass W-083017 4/29/2016 Cs-137 78.2 +/- 6.7 17.222 +/-371 16.507 13,286 -19,929 Pass SPW-4241 8/19/2017 H-3 14.1 +/- 1.8 16.7 13.4-20.1 Pass SPW-4458 9/1/2017 Ra-226 22.8 +/-8.5 26.4 21.1 -31.7 Pass SPW-4466 9/6/2017 Sr-89 32.5 +/-2.1 33.8 27.0-40.6 Pass SPW-4466 9/6/2017 Sr-90 19.2 +/-0.4 20.1 10.1 -30.2 Pass SPW-4512 9/8/2017 Gr. Alpha 27.8 +/-0.3 27.9 22.3 - 33.5 Pass SPW-4512 9/8/2017 Gr. Beta 16,507 13,286 -19,929 Pass SPW-4686 9/9/2017 H-3 16,586 +/- 362 16,439 +/- 362 16.507 13.286 -19,929 Pass SPW4720 9/16/2017 H-3 16,238 +/-378 16,507 13,286 -19,929 Pass SPW-4834 9/22/2017 H-3 16,507 13,286-19,929 Pass SPW-4935 9/27/2017 H-3 16,595 +/- 381 5.6 4.1 -7.5 Pass SPW-4937 9/27/2017 Ra-228 5.7 +/- 0.9 36.2 29.0-43.4 Pass W-092717 4/29/2016 CS-134 36.0 +/- 5.9 82.6 +/- 8.5 71.9 57.5-86.3 Pass W-092717 4/29/2016 Cs-137 16,446 +/-358 16.507 13,286 -19,929 Pass SPW-5001 9/29/2017 H-3 A3-3
TABLE A-3. In-House "SpJked" Samples Concentration' i
Lab Code" Date Analysis Laboratory results Known Control 2s. n=1e Activity Limits* Acceptance SPW-5134 10/6/2017 H-3 16,128 1373 16,507 13,286-19,929 Pass SPW-5274 10/12/2017 H-3 16,108 +/-374 16,507 13,286 -19,929 Pass W-101217S 10/12/2017 Fe-55 1t491 +/-77 1,482 1,186-01,778 Pass SPW-5408 10/18/2017 Nk63 203 +/-3 199 159-238 Pass SPW-5430 10/19/2017 H-3 16,453 +/-380 16,507 13,286 -19,929 Pass W-102017 4/29/2016 Cs-134 31.3 +/-4.9 36.2 29.0-43.4 Pass W-102017 4/29/2016 Cs-137 80.4 +/- 6.9 71.9 57.5 - 86.3 Pass SPW-5674 10/2572017 H-3 16,313 +/- 380 16,507 13,286-19,929 Pass SPW-5719 10/27/2017 H-3 16,113 +/-350 16,507 13,286
19,929 Pass SPW-5730 10/31/2017 H-3 16,776 +/-387 16,507 13,266 -19,929 Pass SPW-5944 10/27/2017 Ra-226 16.4 +/-0.5 16.7 13.4-20.1 Pass SPW-5915 11/9/2017 r+3 16,930 +/-390 16,507 13,286 -19,929 Pass SPW-5989 11/11/2017 H-3 16,084 +/- 352 16,507 13,286-19,929 Pass W-111417 4/29/2016 Cs-134 38.1 +/-6.2 36.2 29.0-434 Pass W-111417 4/29/2016 Cs-137 74.0 +/- 7.5 71.9 57.5-86.3 Pass SPW-6121 11/16/2017 H-3 16,276 +/- 378 16,507 13,286-19,929 Pass SPW-6132 11/20/2017 H-3 15,897 +/- 374 16,507 13,286-19,929 Pass SPW-6249 11/30/2017 Ra-226 12.2 +/-0.4 12.3 9.8 -14.8 Pass SPW-6226 12/1/2017 H-3 16,164 +/-378 16,507 13,286-19,929 Pass SPW-6318 12/7/2017 H-3 15,779 +/-372 16.507 13,286-19,929 Pass W-120817 4/29/2016 Cs-134 29.5 +/- 5.6 362 29.0-43.4 Pass W-120817 4/29/2016 Cs-137 78.8 +/- 9.6 71.9 57.5-86.3 Pass SPW-65 12/11/2017 Ra-226 12.5 +/-0.4 12.3 9.8 -14.8 Pass SPW-6437 12/13/2017 Qr. Alpha 19.6 +/-0.4 20.1 10.1 -30.2 Pass SPW-6437 12/13/2017 Gr.Beta 28.2 +/-0.3 27.9 22.3 - 33.5 Pass SPW-6463 12/15/2017 H-3 15,560 +/-372 16,507 13,286 -19,929 Pass
" Liquid sample results are reported in pCVLter, air filters (pCVmS), charcoal (pCI/cftarcoal caratier), and solid samptes (pCi/kg).
b Laboratory codes : W (Water), Ml (mfc), AP (air filter). 80 (soil), VE (vegetation). CH (charcoal canister). F (fish), U (urine).
B Results are basedI on sinate detarmfnation*.
" Control Imits are established from the precision values listed in Attachment A of this report, adjusted to
~~2s.~~
NOTE: For fish, gelatin is used for the spice matrix. For vegetation, cabbage to used for the spike matrix.
A3-4
TABLEAU. In-House "Blank"Samples Lab Code Sample Date Type 143 71 +/-75 200 SPW-31 Water 1/6/2017 H-3 0.41 0.09 +/-0.30 2 1/9/2017 Gr. Alpha SPW-45 Water 0.74 -0.56 +/-0.50 4 SPW-45 Water 1/9/2017 Gr. Beta 151 -23 +/-71 200 SPW-91 Water 1/11/2017 H-3 0.55 0.29 +/-0.47 5 SPW-141 Water 1/12/2017 Sr-89 0.67 -0.02 +/-0.31 1 Water 1/12/2017 Sr-90 SPW-141 200 H-3 155 -17 +/-73 SPW-154 Water 1/19/2017 176 44 +/-94 200 Water 1/23/2017 H-3 SPW-185 179 26 +/-67 200 SPW-231 Water 1/19/2017 H-3 160 8+/-77 200 Water 1/26/2017 H-3 SPW-303 2 Ra-226 0.02 0.02 +/-0.01 SPW-305 Water 1/4/2017 0.21 0.01 +/-0.11 1.00 SPW-307 Water 1/27/2017 H31
-52 +/-86 200 SPW-332 Water 1/30/2017 H-3 0.14 0.00 +/-0.08 1 SPW-352 Water 2/2/2017 U-234 0.14 0.12 +/-0.15 1 Water 2/2/2017 U-238 SPW-352 0.49 0.30 +/-0.35 5 2/6/2017 Sr-89 SPW-411 Water
-0.22 +/-0.21 1 2/6/2017 Sr-90 0.52 SPW-411 Water 155 2 +/-74 200 Water 2/8/2017 H-3 SPW-464 200 2/15/2017 H-3 156 38 +/-77 SPW-560 Water 154 59 +/-77 200 Water 2/16/2017 H-3 SPW-604 200 H-3 187 28 +/-94 SPW-656 Water 2/17/2017 20 +/-81 200 2/23/2017 H-3 161 SPW-713 Water 161 -75 +/-76 200 2/28/2017 H-3 SPW-73B Water 0.002 0.004 +/-0.001 0.01 2/28/2017 Gr. Beta SPAP-739 AP 2.27 -0.95 +/-1.29 100 2/24/2017 Cs-134 SPAP-741 AP 2.65 0.17 +/-1.67 100 2/24/2017 Cs-137 SPAP-741 AP 161 -28 +/-97 200 SPW-747 Water 2/28/2017 C-14 17 -3 +/-10 200 Water 2/28/2017 NI-63 SPW-749 0.008 0.002 +/-0.004 100 2/28/2017 Cs-134 SPF-751 Flah 0.008 0.000 +/-0.005 100 Fish 2/28/2017 Ca-137 SPF-751 0.02 0.02 +/-0.01 2 Water 3/1/2017 Ra-226 SPW-780 200 H-3 154 35 +/-78 SPW-782 Water 3/1/2017 0.03 0.02 +/-0.02 2 Water 3/1/2017 Ra-226 SPW-3506 1 1-131 0.38 0.04 +/-0.18 Water 3/3/2017 SPW-836 200 H-3 154 -31 +/-72 SPW-1008 Water 3/14/2017 0.43 -0.16 +/-0.28 2 Water 3/16/2017 Gr. Alpha SPW-1025 0.75 -0.24 +/-0.52 4 3/16/2017 Gr. Beta SPW-1025 Water 145 60 +/-73 200 SPW-1091 Water 3/21/2017 H-3 152 *31 +/-71 200 Water 3/24/2017 H-3 SPW-1150 5 3/28/2017 Sr-89 0.61 -0.39 +/-0.45 SPW-1162 Water 0.52 0.18 +/-0.27 1 Water 3/28/2017 Sr-90 SPW-1162
~~Uquld sample iesulte are repwtedtopCi^^~~
~~t-131(G); HxHne-131 as analyzed by gamma spectrowopy.~~
1 AcUvtty reported is a net activity result A4-1
TABLE A-4. In-House "Blank" Samples Concentration ° Lab Code Sample Date Analysis" Laboratory results (4.66a) Acceptance Type LLD Activity0 Criteria (4.66 a)
SPW-1177 Water 3/29/2017 Ra-228 0.83 -0.14 +/-0.36 2 SPW-1231 Wafer 3/30/2017 H-3 150 24 +/-73 200 SPW-1245 Water 3/31/2017 Cs-134 3.73 0.43 +/-2.18 100 SPW-1245 Water 3/31/2017 Cs-137 3.01 -1.23 +/-2.12 100 SPW-1245 Water 3/31/2017 1-131 (G) 5.39 0.92 +/-2.15 100 SPW-1245 Water 3/31/2017 1-131 0.32 0.03 +/-0.18 1 SPMM247 Milk 3/31/2017 Cs-134 3.70 1.23 +/-1.96 100 SPMM247 Milk 3/31/2017 Cs-137 3.62 -0.84 +/-2.15 100 SPMI-1247 Milk 3/31/2017 1-131 (G) 4.42 0.39 +/-2.14 100 SPW-1294 Water 3/31/2017 Ra-226 0.02 0.18 +/-0.02 2 SPW-1303 Water 4/4/2017 H-3 151 8 +/-75 200 SPW-1377 Water 4/7/2017 H-3 150 29 +/-72 200 SPW-1390 Water 4/7/2017 Gr. Alpha 0.42 0.15 +/-0.31 2 SPW-1390 Water 4/7/2017 Gr. Beta 0.73 -0.17 +/-0.51 4 SPW-1479 Water 4/12/2017 H-3 151 89 +/-77 200 SPW-1574 Water 4/180017 H-3 144 55 +/-79 200 SPW-1625 Water 4/20/2017 Sr-89 0.59 -0.01 +/-0.50 5 SPW-1625 Water 4/20/2017 Sr-90 0.71 0.16 +/-0.35 1 SPW-1657 Water 4/21/2017 H-3 147 34 +/-73 200 SPW-1775 Water 4/26/2017 H-3 155 67 +/-80 200 SPW-1805 Water 4/27/2017 H-3 153 15 +/-74 200 SPW-1936 Water 5/3/2017 H-3 148 33 +/-71 200 SPW-1970 Water 5/5/2017 Sr-89 0.66 0.34 +/- 0.54 5 SPW-1870 Water 5/5/2017 Sr-90 0.62 -0.08 +/-0.28 1 SPW-2032 Water 5/8/2017 H-3 147 66 +/-73 200 SPW-2419 Water 5/9/2017 Ra-226 0.03 0.01 +/-0.03 2 SPW-2283 Water 5/22/2017 H-3 155 24 +/-78 200 SPW-2353 Water 5/23/2017 H-3 151 56 +/-76 200 SPW-2890 Water 5/23/2017 Ra-226 0.03 -0.01 +/-0.02 2 SPMI-2377 Milk 5/24/2017 Sr-89 0.78 0.86 +/-0.93 5 SPMK2377 Milk 5/24/2017 Sr-90 0.49 0.95 +/- 0.33 1 SPW-2438 Water 5/25/2017 Ra-228 0.90 -0.28 +/-0.38 2 SPW-2467 Water 5/26/2017 H-3 152 27 +/-77 200 SPW-2417 Water 5/26/2017 Ra-228 0.80 1.58 +/-0.54 2 SPW-2447 Water 5/26/2017 M31 0.21 -0.05 +/-0.12 1 SPW-2501 Water 671/2017 H-3 151 -23 +/-70 200 SPW-285S Water 6/5/2017 H-3 152 107 +/-78 200 SPW-2789 Water 6/9/2017 H-3 150 52 +/-77 200 SPW-2797 Water 6/12/2017 H-3 177 7 +/-93 200 SPW-2847 Water 6/14/2017 1-131 0.18 0.03 +/- 0.10 1
~~Liquid sample results are reported fn pCi/Liter, air Were (pCl/m*), charcoal (pd/charcoal canister), and solid samples (pCi/g).~~
~~1-131 (G); iodlne-131 as analyzed by gamma spectroscopy.~~
~~ActMty reported Is a net activity resul.~~
A4-2
TABLE A-4. In-House "Blank" Samples Concentration Acceptance Lab Code Sample Date Analysis" Laboratory results (4.66c)
LLD Acfivhy0 Criteria (4.66 0)
Type Ra-226 0.03 0.00 +/-0.02 2 SPW-3508 Water 6/15/2017 Sr-89 0.58 0.80 +/-0.53 5 SPW-2942 Water 6/1W2017 0.50 0.15 +/-0.25 1 SPW-2942 Water 6/19/2017 Sr-90 H-3 146 25 +/-74 200 SPW-3042 Water 6/23/2017 Ra-226 0.02 0.03 +/-0.02 2 SPW-3510 Water 6/23/2017 H-3 148 -7 +/-73 200 SPW-3102 Water 6/28/2017 6/29/2017 Tc-99 5.91 -0.38 +/-3.58 10 SPW-3116 Water 0.02 -0.01 +/-0.02 2 SPW-3512 Water 6/29/2017 Ra-226 Sr-89 0.62 0.00 +/-0.48 5 SPW-3187 Water 7/3/2017 0.48 0.07 +/-0.23 1 SPW-3187 Water 7/3/2017 Sr-90 H-3 178 -37 +/-84 200 SPW-3282 Water 7/11/2017 Ra-226 0.03 0.02 +/-0.02 2 SPW-4053 Water 7/11/2017 Gr. Alpha 0.42 -0.09 +/-0.28 2 SPW-3466 Water 7/14/2017 Gr. Beta 0.76 -0.18 +/-0.53 4 SPW-3466 Water 7/14/2017 150 54+/-77 200 SPW-3448 Water 7/15/2017 H-3 Ni-63 90 18 +/-55 200 SPW-3727 Water 7/27/2017 H-3 151 47 +/-82 200 SPW-3793 Water 7/28/2017 Gr. Alpha 0.47 -0.02 +/-0.33 2 SPW-3904 Water 8/3/2017 Gr. Beta 0.75 -0.11 +/-0.52 4 SPW-3904 Water 8/3/2017 159 11 +/-79 200 SPW-4029 Water 8/9/2017 H-3 H-3 157 55 +/-76 200 SPW-4206 Water 8/17/2017 H-3 190 61 +/-96 200 SPW-4241 Water 8/19/2017 H-3 159 -28 +/-77 200 SPW-4085 Water 8/14/2017 H-3 157 55 +/-76 200 SPW-4206 Water 8/17/2017 H-3 190 61 +/-96 200 SPW-4241 Water 8/19/2017 Ra-226 0.78 -0.02 +/-0.36 2 SPW-4457 Water 9/1/2017 Sr-89 0.51 0.30 +/-0.37 5 SPW-4465 Water 9/8/2017 Sr-90 0.46 -0.09 +/-0.20 1 SPW-4465 Water 9/6/2017 H-3 187 -66 +/-83 200 SPW-4585 Water 9/9/2017 9/13/2017 Ra-226 0.02 0.13 +/-0.02 2 SPW-5720 Water 1-131 0.17 0.10 +/-0.10 1 SPW-4703 Water 9/15/2017 H-3 184 -86 +/-93 200 SPW-4719 Water 9/16/2017 H-3 150 5 +/-72 200 SPW-4833 Water 9/22/2017 H-3 148 5 +/-70 200 SPW-4934 Water 9/27/2017 Ra-228 0.80 0.55 +/-0.44 2 SPW-4936 Water 9/27/2017 H-3 183 -13 +/-90 200 SPW-5000 Water 9/29/2017 H-3 144 64 +/-71 200 SPW-5133 Water 10/6/2017 H-3 142 106 +/-72 200 SPW-5273 Water 10/12/2017 Liquid sample results are reported in pCI/Uter, air Wen (pCi/m1). charcoal (pO/charcoal canister), and solid samples (pCI/g).
M31(G); tadine-131 as analyzed by oamma spedroscopy.
Activity reported is a net activity result.
A4-3
TABLE A-4. In-House "Blank" Samples Concentration
Lab Code Sample Date Analysis6 Laboratory results (4.66c) Acceptance Type LLD Activity6 Criteria (4.66 a)
SPW-5407 Water 10/18/2017 Ni-63 69 43 +/-43 200 SPW-5429 Water 10/19/2017 H-3 148 54+/-72 200 SPW-5603 Water 10/23/2017 Sr-69 0.57 0.16 +/-0.47 5 SPW-5603 Water 10/23/2017 Sr-80 0.70 -0.12 +/-0.31 1 SPW-6673 Water 10/25/2017 H-3 156 -36 +/-71 200 SPW-5718 Water 10/27/2017 H-3 182 45 +/-92 200 SPW-5943 Water 10/27/2017 Ra-226 0.02 0.08 +/-0.02 2 SPW-6723 Water 10/30/2017 1-131 0.10 0.03 +/-0.07 1 SPW-5914 Water 11/09/17 H-3 149 -39 +/-68 200 SPW-5988 Water 11/11/2017 H-3 183 -8 +/-88 200 SPW-6120 Water 11/16/2017 H-3 146 83 +/-75 200 SPW-6131 Water 11/20/2017 H-3 151 16 +/-72 200 SPW-6187 Water 11/29/2017 1-131 0.38 0.01 +/-0.18 1 SPW-6248 Water 11/30/2017 Ra-226 0.03 0.15 +/-0.03 2 SPW-6225 Water 12/1/2017 H-3 154 -10 +/-72 200 SPW-6317 Water 12/7/2017 H-3 148 44 +/-74 200 SPW-64 Water 12/11/2017 Ra-226 0.03 0.18 +/-0.03 2 SPW-6436 Water 12/13/2017 Gr. Alpha 0.54 -0.17 +/-0.37 2 SPW-6436 Water 12/13/2017 Gr. Beta 0.74 0.12 +/-0.52 4 SPW-6464 Water 12/15/2017 H-3 148 31 +/-75 200 1 Uquid sample results are reported In pCVUter, air flters (pCI/m*), charcoal (pCi/charcoal canister), and solid samples (pCI/g).
ActMty reported is a net activity resul.
A4-4
TABLE Ar5. In-House "Duplicate" Samples Concentration Averaged Second Result Result Acceptance Lab Code Date _Analysis First Result 0.047
0.015 0.062*0.017 0.054 +/- 0.012 Pass AP-7178,7179 1/3/2017 Be-7 Gr. Beta 1.39 +/-0.41 0.77 +/- 0.41 1.08 +/-0.29 Pass SW-6986.6987 1/3/2017 1.62 +/-0.05 1.45 +/-0.04 1.54 +/-0.11 Pass E-66,67 1/372017 Gr. Beta 128 +/-0.14 1.39 +/-0.16 1.32 +/-0.11 Pass E-68,67 1/3/2017 K-40 0.25 +/-0.11 0.30 +/- 0.12 0.28 +/- 0.08 Pass CF-87,88 1/3/2017 Be-7 6.84 +/- 0.37 7.31 +/-0.27 Pass CF-87,88 1/3/2017 K-40 7.77 +/- 0.39 0.137 +/-0.078 0.139 +/-0.082 0.138 +/-0.056 Pass AP-011217 1/12/2017 Be-7 1,515 +/-98 1,347 +/- 107 1,431 +/-73 Pass Ml-212,213 1/18/2017 K40 675 +/-118 506 +/-133 590 +/-89 Pass WW-321,322 1/18/2017 H-3 7,326 +/- 254 7,717 +/-259 7,522 +/-181 Pass WW-674.675 1/20/2017 H-3 0.034 +/-0.006 0.038 +/-0.005 0.036 +/-0.004 Pass AP-012317 1/23/2017 Gr. Beta 5,916 +/-239 5764 +/-237 5840 +/-168 Pass WW-298,299 1/2472017 H-3 0.027 +/- 0.004 0.028 +/- 0.004 0.028 +/-0.003 Pass AP-013117 1/30/2017 Gr. Beta 1,058 +/-122 1,054 +/-121 1,056 +/-86 Pass WW-500,501 1/31/2017 H-3 1.40 +/-0.56 1.62 +/-0.61 1.51 +/-0.41 Pass SW-391,392 1/31/2017 Gr. Beta 23.47 +/- 0.66 23.11 +/-0.72 23.29 +/-0.49 Pass SPS-370,371 2/1/2017 K-40 0.129 +/- 0.076 0.167 +/-0.092 0.148 +/- 0.060 Pass AP-456,457 2/2/2017 Be-7 0.021 +/-0.004 0.027 +/-0.004 0.024 +/-0.003 Pass AP-020217 2/2/2017 Gr.Beta 19.45 +/- 1.85 21.58 +/-1.99 20.52 +/- 1.36 Pass SPS-414,415 2/3/2017 K-40 0.023 +/- 0.004 0.023 +/-0.004 0.023 +/- 0.003 Pass AP-020617 2/6/2017 Gr.Beta 0.031 +/-0.004 0.030 +/-0.004 0.030 +/-0.003 Pass AP-0Z1417A 271472017 Gr.Beta 7.99 +/- 0.82 9.45+/-0.B8 8.72 +/-0.60 Pass SPW-543 2/14/2017 Gr. Beta 0.028 +/- 0.004 0.026 +/- 0.003 Pass AP-021417B 2/14/2017 Gr.Beta 0.024 +/- 0.004 643 +/-110 690 +/-79 Pass WW-718,719 2/14/2017 H-3 737 +/-113 0.018 +/-0.005 0.021 +/-0.005 0.020 +/- 0.004 Pass AP-022017 2/20/2017 Gr.Beta 3709 +/- 196 3,823 +/- 198 3,766 +/- 139 Pass WW-755,756 2/22/2017 H-3 0.021 +/-0.004 0.019 +/- 0.004 0.020 +/-0.003 Pass AP-022717 2/27/2017 Gr.Beta 7.29 +/- 0.32 6.76 +/- 0.30 7.03 +/-0.22 Pass SPOW-80011,2 3/2/2017 Ra-226 4.68 +/-0.82 6.29 +/-1.03 5.49 +/-0.66 Pass SPDW-80011,2 3/2/2017 Ra-228 12.44 +/-1.37 13.01 +/- 0.99 Pass SPDW-80013,4 3/2/2017 Gr. Alpha 13.57 +/- 1.43 249 +/-90 261 +/-66 Pass WW-845,846 3/2/2017 H-3 314 +/-93 0.022 +/-0.004 0.019 +/-0.004 0.020 +/-0.003 Pass AP-030617 3/6/2017 Gr.Beta 14,994 +/- 364 14,745 +/- 362 14,870 +/- 257 Pass WW-105071051 3/8/2017 H-3 23.30 +/-1.76 23.13 +/- 1.64 23.21 +/- 1.20 Pass SPS-920,921 3/9/2017 K-40 182 +/-80 158 +/-79 170 +/-56 Pass WW-1004,1005 3/13/2017 H-3 11.82 +/-0.68 12.01 +/-0.68 11.92 +/-0.48 Pass SPS-1029.1030 3/15/2017 K-40 0.020 +/- 0.003 0.020 +/-0.002 Pass AP-031517 3/15/2017 Gr.Beta 0.020 +/- 0.003 4.54 +/-0.82 5.29 +/-0.91 4.91 +/-0.61 Pass SPDW-80037,8 3/20/2017 Gr. Alpha 0.021 +/-0.006 0.021 +/-0.005 Pass AP-032017 3/2O/2017 Gr.Beta 0.021 +/- 0.005 1,595 +/- 138 1,583 +/-175 Pass WW-1094,1096 3/20/2017 H-3 1,571 +/-137 A5-1
TABLE A-5. IrvHouse -Dupicata" Samptos Concentration" Averaged Lab Code Date Analysis First Result Second Result Result WW-1175,1176 3/20/2017 H-3 218 +/-84 211 +/-64 214 +/- 59 Pass WW-1129,1130 3/21/2017 Gr. Bete 3.51 +/- 1.24 2.99 +/- f .17 3.25 +/- 0.85 Paw WW-1219,1220 3/22/2017 H-3 11,487 +/-322 11,516 +/-323 11,492 +/-200 Pass SPS-1152,1153 3/27/2017 Ao-228 20.39 +/- 0.75 20.43 +/- 0.88 20.41 +/- 0.58 Pass SPS-1152,1153 3/27/2017 Pfr-214 17.22 +/-0.50 16.44 +/- 0.52 16.83 10.36 Pass SPDW-80047,6 3/28/2017 R<<-226 2.06 +/- 0.23 1.60 +/- 0.32 1.83 10.20 Pats SPDW*0047,8 3/28/2017 R>>-228 0.53*0.48 0.7810.48 0.66 +/- 0.34 Past SWU-1242,1243 3/28A2017 Or. Beta 2.04 +/-0.81 2.47 +/-0.69 2.26 10.53 Pass SPS-1188,1199 3/29/2017 K-40 16.95 +/-1.85 18.33 +/- 1.71 17.64 11.26 Pass SPDW-80050,1 3/29/2017 Gr. Alpha 3.1910.80 3.39 +/- 0.78 3.29 +/- 0.56 Pass SPDW-30050,1 3/29/2017 Gr. Beta 1.58 +/-0.60 2.08 +/- 0.63 1.83 10.44 Pass AP-1706,1707 3/30/2017 Be-7 0.068 10.018 0.072 +/-0.017 0.07010.012 Pass SW-1381,1382 4/5/2017 H-3 402 +/-92 309 +/-88 356164 Pass WW-1446,1447 4/6/2017 H-3 305 +/-69 358 +/-91 332 +/-64 Pass WW-1532,1533 4/10/2017 H-3 19,124 +/-412 18,991 +/-410 19,0581291 Pass WW-1618,1619 4/12/2017 H-3 4,167 +/-203 4,305 +/-205 4,246 1144 Pass SS-1553,1554 4/13/2017 Gr. Beta 7.16 +/-0.99 6.09 +/- 0.91 6.63 +/- 0.67 Pass SS-1553,1554 4/13/2017 K40 4.60 +/- 0.32 4.64 10.34 4.72 +/-0.23 Pass SS-1553,1554 4/13/2017 TK2O6 0.038 10.016 0.03210.011 0.03510.010 Pass SS-1553,1554 4/13/2017 Pb-212 0.101 +/-0.015 0.09610.015 0.098 10.010 Pass SS-1663,1554 4/13/2017 W-214 0.094 +/-0.032 0.10910.022 0.101 +/-0.019 Pass SS-1553,1554 4/13/2017 Ao-228 0.069 +/- 0.042 0.111 +/-0.046 0.10010.031 Pass P-2015,2018 5M/2017 H-3 169 +/-80 212181 200 157 Pass WW-2336,2337 5/8/2017 H-3 422 +/-97 298191 360 +/-66 Pass AP-051117 5/11/2017 Gr. Beta 0.018 +/-0.003 0.025 +/-0.004 0.021 +/-0.002 Pass WW-2497,2498 5/23/2017 H-3 1,268 1 127 1,247 +/-126 1,257 +/-89 Pass WW-2583,2584 5/23/2017 H-3 5,159 +/-224 5,223 +/- 126 5,191 +/-129 Pass WW-2732,2733 5/23/2017 H-3 8,559 +/-282 6,5701283 8,564 +/-200 Pass XW-1218.1219 5/23/2017 H-3 11,467 +/-282 11,516 +/-283 11,492 +/-200 Pass MI-2428,2429 5/24/2017 K-40 1,752 +/- 137 1.805 1132 1,778 +/-95 Pass SO-2562,2563 5/24/2017 K-40 7.87 +/- 0.50 8.64 +/-0.49 8.25 +/- 0.35 Pass WW-3023,3024 5/24/2017 H-3 27,396 +/-466 27,733 +/- 489 27,565 +/- 344 Pass SO-2453,2454 5/25/2017 Gr. Beta 14.38 +/-0.93 15.7011.06 15.04 +/-0.70 Pass SO-2453,2464 6/25/2017 C>>-137 0.17 +/-0.03 0.18 10.03 0.1710.02 Pass SO-2453,2454 6/25/2017 K-40 9.80 10.60 9.19 10.57 9.50 +/- 0.38 Pass SO-2453,2454 5/26/2017 11208 0.09 +/- 0.02 0.1010.03 0.09 +/- 0.02 Pass SO-2453,2454 5/25/2017 Pth212 0.29 +/- 0.03 0.30 10.03 0.29 +/- 0.02 Pass SO-2453.2454 5/25/2017 Bi-214 0.24 +/-0.03 0.18 +/-0.04 0.21 +/- 0.03 Pass SO-2453,2454 5/25/2017 Ra-226 0.62 +/-0.22 0.62 +/- 0.27 0.72 +/-0.17 Pass SO-2453.2454 5/25/2017 Ac-228 0.32 +/- 0.07 0.28 +/-0.08 0.30 10.05 Pass A5-2
TABLE A-5. ln-House "Duplicate" Samples Concentration
Averaged First Result Second Result Result Lab Code Date 1.08 +/-0.55 0.86 +/-0.38 Pass SWT-2625,2626 5/30/2017 Gr. Beta 0.64 +/-0.53 0.011 +/-0.003 0.012 +/-0.002 Pass 5/31/2017 Gr. Beta 0.013 +/-0.003 AP-053117 1.06 +/-0.26 1.04 +/-0.15 Pass G-2646,2647 6/1/2017 Be-7 1.02 +/-0-17 6.55 +/- 0.51 7.03 +/-0.36 Pass 6/1/2017 K-40 7.51 +/-0.49 6-2646.2647 0.30 +/-0.06 0.32 +/-0.04 Pass 6/1/2017 Be-7 0.34 +/-0.06 SL-2669,70 4.39 +/-0.15 4.37 +/-0.10 Pass 6/1/2017 K-40 4.35 +/-0.14 SL-2669,70 2.77 +/-0.44 2.66 +/-0.27 Pass 6/2/2017 K-40 2.56 +/-0.32 F-2711.2712 0.027 +/-0.005 0.027 +/-0.004 Pass AP-060617 6/6/2017 Gr. Beta 0.026 +/-0.005 8,563 +/-279 8,371 +/-195 Pass SW-2849,50 6/8/2017 H-3 8,178 +/-273 0.027 +/-0.005 0.027 +/-0.004 Pass 6/12/2017 Gf. Beta 0.027 +/-0.005 AP-061217 8.57 +/-0.47 8.44 +/-0.33 Pass BS-3446,3447 6/12/2017 K-40 8.30 +/-0.47 3.90 +/-0.26 3.77 +/-0.18 Pass VE-2870.2B71 6/13/2017 K-40 3.65 +/-0.25 0.212 +/-0.123 0.240 +/-0.095 Pass 6/15/2017 Be-7 0.269 +/-0.146 AP-2914,5 0.328 +/-0.126 0.266 +/-0.085 Pass 6715/2017 Be-7 0.204 +/-0.113 AP-3067,8 0.019 +/-0.004 0.020 +/-0.003 Pass AP-061917 6/19/2017 Gr. Beta 0.020 +/-0.004 0.116 +/-0.021 0.111 +/-0.013 Pass 6/26/2017 Be-7 0.107 +/-0.015 AP-3610,1 0.021 +/-0.004 0.019 +/- 0.003 Pass 6/26/2017 Gr. Beta 0.017 +/-0.004 AP-062617 0.078 +/-0.008 0.083 +/-0.006 Pass AP-3673,3674 7/3/2017 Be-7 0.087 +/-0.008 0.244 +/-0.096 0.226 +/-0.074 Pass 7/B/2017 Be-7 0.207 +/-0.112 AP-3287,3288 501 +/-107 525 +/-76 Pass 7/7/2017 H-3 549 +/-108 WW-3308,3309 2.40 +/-0.16 2.36 +/-0.12 Pass 7/12/2017 K-40 2.32 +/-0.17 VE-3362,3363 4.64 +/-0.33 4.94 +/-0.23 Pass VE-3589,3590 7/16/2017 K-40 525 +/-0.33 2.97 +/-0.11 3.00 +/-0.08 Pass SG-3631,3632 7/16/2017 Pb-214 3.03 +/-0.11 2.56 +/-0.23 2.52 +/-0.16 Pass SG-3631,3632 7/18/2017 Ao-228 2.47 +/-0.22 446 +/-98 475 +/-70 WW-3846,3647 7/25/2017 H-3 505 +/-101 1.00 +/-0.25 0.93 +/-0.18 Pass 7/26/2017 K-40 0.85 +/-0.25 F-4509,4510 1.18 +/-0.03 1.18 +/-0.02 Pass F-4509,4510 7/26/2017 Gr. Beta 1.19 +/-0.03 3.47 +/-0.40 3.59 +/-0.28 Pass G-3804.3805 7/27/2017 Be-7 3.72 +/-0.39 4.46 +/- 0.52 4.34 +/-0.33 Pass 7/27/2017 K-40 4.21 +/-0.52 G-3804,3805 0.73 +/-0.07 0.75 +/-0.04 Pass 8/1/2017 Be-7 0.77 +/-0.04 SL-3868.3889 0.87 +/-0.08 0.90 +/-0.23 Pass 8/1/2017 K-40 0.94 +/-0.04 SL-3688,3889 270 +/-88 295 +/-63 Pass WW-4158,4159 8/8/2017 H-3 321 +/-90 1.84 +/-0.18 1.90 +/-0.21 1.87 +/-0.14 VE-4179,4180 8/14/2017 K-40 0.162 +/-0.080 0.187 +/-0.062 Pass 8/17/2017 Be-7 0.212 +/-0.095 AP-4289,4290 3.62 +/-0.42 3.42 +/-0.29 Pass 8/18/2017 K-40 3.22 +/-0.41 F-4333,4334 11.48 +/-0.50 11.21 +/-0.45 Pass 8/21/2017 K-40 10.94 +/-0.74 CF-4310:4311 1.19 +/-0.17 1.21 +/-0.11 Pass DW-80161.80162 8/22/2017 Ra-226 1.22 +/-0.15 0.70 +/-0.49 1.35 +/-0.40 Pass DW-80161,80162 8/22/2017 Ra-228 1.99 +/-0.63 0.13 +/- 0.08 0.13 +/-0.05 Pass 8/28/2017 Be-7 0.13 +/-0.07 VE-4398r4399 A5-3
~~TABLE A-5. In-House "Duplicate" Samples Concentration~~
Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4398,4399 8/28/2017 K-40 3.32 +/- 0.22 3.48 +/-0.25 3.40 +/-0.17 Pass SW-4463,4464 8/29/2017 H-3 495 +/-106 491 +/- 106 493 +/- 75 Pass LW-4486,4487 8/31/2017 Gr. Beta 0.425 +/- 0.471 1.358 +/-0.571 0.892 +/- 0.370 Pass VE-4561,4562 9/6/2017 Be-7 5.89 +/-0.29 5.76 +/-0.25 5.63 +/-0.19 Pass VE-4561,4562 9/6/2017 K-40 3.73 +/-0.34 3.77 +/-0.29 3.75 +/- 0.22 Pass BO-5122,5123 9/8/2017 K-40 4.50 +/- 0.36 4.50 +/-0.36 4.50 +/-0.25 Pass VE-4692,4693 9/12/2017 K-40 5.16 +/-0.13 5.31 +/-0.36 5.24 +/-0.19 Pass 88-4660,4651 9/12/2017 K-40 10.55 +/-0.51 10.41 +/-0.54 10.48 +/-0.37 Pass MM671.4672 9/13/2017 K-40 1,347 +/-115 1,283 +/-118 1,315 +/-82 Pass MI-4671,4672 9/13/2017 Sr-90 0.7 +/- 0.3 0.5 +/-0.3 0.6 +/-0.2 Pass VE4973.4974 9/17/2017 K-40 1.11 +/-0.15 1.17 +/-0.13 1.14 +/-0.10 Pass F-4928,4929 9/19/2017 K40 1.84 +/-0.31 1.68 +/-0.34 1.76 +/-0.23 Pass S-4865,4866 9/20/2017 K-40 21.07 +/-2.39 19.09 +/-2.51 20.08 +/-1.73 Pass VE-4907,4908 9/20/2017 K-40 3.83 +/- 0.44 4.28 +/-0.31 4.05 +/-0.27 Pass VE-i844,4845 9/21/2017 K-40 1.81 +/-0.22 1.88 +/-0.21 1.84 +/-0.15 Pass AP-5572,5573 9/27/2017 Be-7 0.082 +/-0.015 0.075 +/-0.014 0.078 +/-0.010 Pass LW-5145,5146 9/28/2017 Gr. Beta 0.84 +/- 0.49 1.47 +/-0.57 1.16 +/-0.38 PasB AP-092917 9/29/2017 Gr. Beta 0.038 +/- 0.004 0.031 +/-0.004 0.035 +/- 0.003 Pass WW-5080,5081 10/2/2017 H-3 208 +/-79 223 +/-80 215 +/-56 Pass AP-100217 10/2/2017 Gr. Beta 0.025 +/-0.005 0.028 +/-0.005 0.026 +/- 0.003 Pass AP-100317 10/3/2017 Gr. Bete 0.037 +/- 0.004 0.033 +/-0.004 0.035 +/-0.003 Pass S-5165,5166 10/4/2017 K-40 15.93 +/-2.30 20.34 +/-3.15 18.14 +/-1.95 Pass VE-5228,5229 10/5/2017 K-40 3.25 +/- 0.25 2.82 +/-0.24 3.04 +/-0.17 Pass AP-100917 10/9/2017 Gr. Beta 0.021 +/-0.004 0.025 +/-0.004 0.023 +/- 0.003 Pass VE-5293,5294 10/10/2017 K-40 3.89 +/- 0.30 4.08 +/- 0.34 3.99 +/-0.22 Pass DW-80184,80185 10/11/2017 Gr. Alpha 2.17 +/-0.81 2.50 +/-0.81 2.34 +/-0.57 Pass DW-80164,80185 10/11/2017 Gr. Beta 9.45 +/-0.79 10.20 +/-0.83 9.83 +/- 0.57 Pass S-5421,5422 10/12/2017 K-40 8.82 +/-1.94 7.97 +/-0.72 8.40 +/- 1.03 Pass AP-101617 10/16/2017 Gr. Beta 0.025 +/-0.005 0.022 +/-0.004 0.024 +/- 0.003 Pass F-5658,5659 10/19/2017 K-40 2.44 +/-0.41 2.57 +/-0.39 2.51 +/-0.28 Pass SO-5704,5705 10/25/2017 Cs-137 0.05 +/- 0.02 0.04 +/-0.02 0.04 +/- 0.01 Pass SO-5704,5705 10/25/2017 K-40 10.08 +/-0.51 9.57 +/-0.56 9.63 +/- 0.36 Pass SO-5704,5705 10/25/2017 TY-208 0.10 +/-0.02 0.09 +/-0.02 0.10 +/- 0.01 Pass SO-5704,5705 10/25/2017 Bl-214 0.34 +/-0.04 0.27 +/-0.04 0.30 +/- 0.03 Pass SO-5704,5705 10/25/2017 Pt>-212 0.28 +/-0.03 0.27 +/-0.03 0.27 +/- 0.02 Pass SO-5704,5705 10/25/2017 Ra-226 1.15 +/-0.52 0.59 +/-0.22 0.87 +/-0.28 Pass SO-5704,5705 10/25/2017 Ac-228 0.33 +/-0.05 0.31 +/-0,07 0.32 +/-0.04 Pass SO-5704,5705 10/25/2017 Gr. Beta 18-34 +/-1.80 16.50 +/-1.03 17.42 +/-1.04 Pass AP-5732,5733 10/26/2017 Be-7 0.139 +/-0.064 0.175 +/-0.075 0.157 +/-0.049 Pass A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration' Averaged Second Result Result Acceptance Dab Analysis First Result 279186 249160 Pass SW-5753,5754 10/31/2017 H-3 220 +/-83 2.02 11.02 1.7610.71 Pass SWU-5816,5817 10/31/2017 Gr. Beta 1.51 11.00 0.01410.004 0.01510.003 Pass 10/310017 Gr. Beta 0.015 +/-0.004 AP-103117 0.31 10.04 0.31 +/-0.03 Pass SO-5923,5924 11/1/2017 Cs-137 0.30 +/-0.04 10.5610.67 10.54 +/-0.45 Pass SO-5923,5924 11/1/2017 K-40 10.52 +/-0.61 0.14610.084 0.145 +/-0.056 Pass AP-5858.5859 11/2/2017 Be-7 0.145 +/-0.075 0.03010.004 0.028 +/-0.003 Pass AP-110717 11/7/2017 Be-7 0.026 +/-0.004 298 180 251 +/-59 Pass WW-6032,6033 11/7/2017 H-3 204 +/-86 73,0621791 72,655 +/-558 Pass WW-6074,6075 11/80017 H-3 72.247 +/-786 9.20 10.68 8.60 +/-0.46 Pass BS-6053,6054 11/13/2017 K-40 7.99 +/-0.62 0.0810.03 0.0710.02 Pass BS-6053,6054 11/13/2017 Cs-137 0.07 +/-0.03 2.3010.80 3.60 11.00 2.9510.64 DW-80211,80212 11/14/2017 Gr. Alpha 8.99 10.81 9.16 10.57 Pass DW-80211,80212 11/14/2017 Gr. Beta 9.32 +/-0.81 1.3510.15 1.35510.13 Pass DW-80214,80215 11/14/2017 Ra-226 1.36+/-0.22 0.90 10.45 1.1610.34 Pass DW-80214,80215 11/14/2017 Ra-228 1.41 +/-0.51 416194 328190 372165 WW-6152,6153 11/15/2017 H-3 1.0410.54 1.7510.58 1.39 +/-0.39 Pass SWU-6219,6220 11/28/2017 Gr. Beta 22.31 11.03 23.24 +/-0.74 Pass SS-6242,6243 11/29/2017 K-40 24.17 +/-1.05 0.0810.03 0.1010.02 Pass SS-6242,6243 11/29/2017 Cs-137 0.11 +/-0.03 14.96 10.43 15.12 10.27 Pass SG-6938,6939 11/28/2017 Pb-214 15.28 +/-0.34 19.9210.79 19.4610.49 Pass SG-6938,6939 11/28/2017 Ao-228 18.99 +/-0.59 0.03010.004 0.02810.003 Pass 11/28/2017 Gr. Beta 0.02610.004 AP-112817 60.9 16.0 65.8 14.3 Pass SQ-6286,6287 12/1/2017 Gr. Alpha 70.6 +/-6.2 48.912.7 53.7 12.8 51.3 11.9 Pass SQ-6286,6287 12/1/2017 Gr. Beta 10.710.5 11.010.3 Pass SQ-6286,6287 12/1/2017 Ra-226 11.310.4 13.2 11.0 13.410.7 Pass SQ-6286,6287 12/1/2017 Ra-228 13.510.9 5.10H.82 6.6511.53 5.8811.19 Pass SG-6286,6287 12/1/2017 K-40 0.03710.006 0.03510.005 0.036 10.004 Pass AP-120417 12/4/2017 Gr.Beta 8,604 1282 8,6161199 Pass WW-6548,6549 12/19/2017 H-3 8,4281280 0.047 10.004 0.04310.004 0.045 10.003 Pass AP-122717 12/27/2017 Gr.Beta 2.2410.82 2.34 +/-0.77 Pass XAP-6762,6763 12/31/2017 Co-60 2.43+/-1.30 4.0510.96 4.14 +/-0.73 Pass XAP-6762,6763 12/31/2017 Cs-137 4.21 11.11 Note: Duplicate analyses are performed on every twentieth sample received In-house. ResuBs are not listed for those analyses with activities that measure below the LLD.
8 Results are reported in units of pCI/L, except for air filters <pCi/F8ter or PCi/m3), food products, vegetation, soil and sediment (pCi/g).
A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration" Reference Known Control Lab Codeb Date Analysis Laboratory result Activity Limitsc Acceptance MASO-903 2/1/2017 Am-241 60.9 +/- 6.9 67.0 46.9-87.1 Pass MASO-903 2/1/2017 Cs-134 1360 +/-14 1550 1085-2015 Pass MASO-903 2/1/2017 Cs-137 678 +/- 13 611 428 - 794 Pass MASO-903 2/1/2017 Co-57 1.63 +/-1.69 0.00 NA6 Pass MASO-903 2/1/2017 Co-60 909 +/-12 891 624-1158 Pass MASO-903 2/1/2017 Mn-54 1052 +/-17 987 677 -1257 Pass MASO-903 2/1/2017 K-40 657 +/-68 607 425 - 789 Pass MASO-903 2/1/2017 Zn-65 -0.52 +/- 7.40 0.00 NA° Pass MASO-903 2/1/2017 Ni-63 3.25 +/-7.17 0.00 NAC Pass MASO-903 2/1/2017 Pu-238 0.48 +/-0.69 0.41 NA" Pass MASO-903 2/1/2017 Pu-239/240 56.8 +/-5.9 59.8 41.9-77.7 Pass MASO-903 2/1/2017 Sr-90 501 +/-17 624 437-811 Pass MASO-903 2/1/2017 Tc-99 748 +/- 16 656 459-853 Pass MAW-849 2/1/2017 1-129 -0.05 +/- 0.12 0.00 NAC Pass MAVE-905 2/1/2017 Cs-134 6.61 +/-0.16 6.95 4.87-9.04 Pass MAVE-005 2/1/2017 Cs-137 4.97 +/-0.18 4.60 3.22 - 5.98 Pass MAVE-905 2/1/2017 Co-57 -0.01 +/- 0.03 0.00 NAC Pass MAVE-905 2/1/2017 Co^O 9.51 +/-0.17 8.75 6.13-11.38 Pass MAVE-905 2/1/2017 Mn-54 3.87 +/-0.17 3.28 2.30-4.26 Pass MAVE-905 2/1/2017 Zn-65 6.12 +/- 0.44 5.39 3.77 - 7.01 Pass MAW-847 2/1/2017 Am-241 0.679 +/-0.079 0.846 0.592 -1.100 Pass MAW-847 2/1/2017 Cs-134 0.03 +/-0.10 0.00 NAC Pass MAW-847 2/1/2017 Cs-137 12.7 +/-0.4 11.1 7.8 -14.4 Pass MAW-847d 2/1/2017 Co-57 2.7 +/- 0.3 28.5 20.0-37.1 Fad MAW-847 2/1/2017 Co-60 13.5 +/- 0.3 12.3 8.6 -16.0 Pass MAW-847 2/1/2017 Mn-54 16.5 +/- 0.4 14,9 10.4 - 19.4 Pass MAW-847 2/1/2017 K-40 287 +/-6 254 178-330 Pass MAW-847 2/1/2017 Zn-65 -0.15 +/- 0.23 0.00 NA° Pass MAW-847 2/1/2017 H-3 275 +/- 10 249 174-324 Pass MAW-847 2/1/2017 Fe-55 2.4 +/- 13.6 1.7 NA1 Pass MAW-847 2/1/2017 Ni-63 10.1 +/-2.8 12.2 8.5 -15.9 Pass MAW-847 2/1/2017 Pu-238 0.729 +/-0.097 0.703 0.492 - 0.914 Pass MAW-447 2/1/2017 Pu-239/240 0.866 +/-0.102 0.934 0.654 -1.214 Pass MAW-847 2/1/2017 Ra-226 0.506 +/- 0.053 0.504 0.353 - 0.655 Pass MAW-647 2/1/2017 Sr-90 10.0 +/-0.8 10.1 7.1 -13.1 Pass A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration11 Reference Known Control Lab Codeb Date Analysis Laboratory result Activity Limits0 Acceptance Tc-99 4.77*0.62 6.25 4.38-8.13 Pass MAW-847 2/1/2017 1.19 +/-0.10 1.16 0.81 -1.51 Pass MAW-847 2/1/2017 U-234/233 U-238 1.15 +/-0.10 1.20 0.84 -1.56 Pass MAW-847 2/1/2017 0.0376 0.0263-0.0489 Fail MAAP-90/ 2/1/2017 Am-241 0.0540 +/-0.0140 Cs-134 1.31 +/-0.06 1.42 0.99-1.85 Pass MAAP-907 2/1/2017 Cfi-137 0.797 +/-0.080 0.685 0.480-0.891 Pass MAAP-907 2/1/2017 1.86 +/-0.06 1.70 1.19-2.21 Pass MAAP-907 2/1/2017 Co-57 Co-60 0.66 +/-0.05 0.78 0.55-1.01 Pass MAAP-907 2/1/2017 MAAP-907 2/1/2017 Mn-54 0.01 +/- 0.03 0.00 NAC Pass 1.62 +/-0.13 1.29 0.90-1.68 Pass MAAP-907 2/1/2017 Zn-65 Pu-238 0.0530 +/- 0.0190 0.0598 0.0419-0.0777 Pass MAAP-907 2/1/2017 Pu-239/240 0.0490 +/-0.0160 0.0460 0.0322 - 0.0598 Pass MAAP-907 2/1/2017 Sr-90 0.648 +/-0.120 0.651 0.456-0.846 Pass MAAP-907 2/1/2017 U-234/233 0.086 +/- 0.024 0.104 0.073-0.135 Pass MAAP-907 2/1/2017 0.097 +/-0.024 0.107 0.075-0.139 Pass MAAP-907 2/1/2017 U-238 Am-241 45.9 +/-7.0 58.8 412-76.4 Pass8 MASO-4515 8/1/2017 Cs-134 409 +/-7 448 314-582 Pass0 MASO-4515 8/1/2017 Cs-137 798 +/-12 722 505-939 Pass9 MASO-4515 8/1/2017 Co-57 1572 +/-10 1458 1021 -1895 Pass8 MASO-4515 8/1/2017 Co60 0.2 +/-1.4 0.00 NAC Pass8 MASO4515 8/1/2017 Mn-54 934113 825 578 -1073 Pass9 MASO4515 8/1/2017 K-40 704 +/-53 592 414-770 Pass9 MASO-4515 8/1/2017 Zn-65 667 +/-17 559 391 -727 Pass8 MASCM515 8/1/2017 Pu-238 101 +/-9 92 64-120 Pass8 MASO-4515 8/1/2017 ^ ft Pu-239/240 74.8 +/- 7.7 68.8 48.2-89.4 Pass8 MASO-4515 8/1/2017 Sr-90 252 +/-7 289 202-376 Pass8 MASO-4515 8/1/2017 1-129 2.31 +/-0.10 2.31 1.62-3.00 Pass MAW-4494 8/1/2017 Cs-134 2.40 +/- 0.10 2.32 1.62-3.02 Pass MAVE-4517 8/1/2017 MAVE-4517 8/1/2017 C8-137 -O.002 +/-0.048 0.000 NA° Pass 3.3 +/- 0.1 2.8 2.0-3.6 Pass MAVE-4517 8/1/2017 Co-57 Co-60 2.10 +/- 0.10 2.07 1.45-2.69 Pass MAVE-4517 8/1/2017 3.00 +/- 0.20 2.62 1.83-3.41 Pass MAVE-4517 8/1/2017 Mn-54 5.90 +/-0.30 5.37 3.76-6.98 Pass MAVE-4517 8/1/2017 Zn-65 A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
a Concentration Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits ° Acceptance MAW-4513 8/1/2017 Am-241 0.820 +/- 0.220 0.892 0.624 -1.160 Pass MAW-4513 8/1/2017 Cs-134 10.3 +/- 0.3 11.5 8.1 -15.0 Pass MAW-4513 8/1/2017 Cs-137 17.2 +/-0.5 16.3 11.4-21.2 Pass MAW-4513 8/1/2017 Co-57 12.7 +/- 0.4 12.1 8.5 -15.7 Pass MAW-4513 8/1/2017 Co-60 10.6 +/-0.3 10.7 7.5-13.9 Pass MAW-4513 8/1/2017 Mn-54 15.6 +/-0.4 14.9 10.4 -19.4 Pass MAW-4513 8/1/2017 Zn-65 15.9 +/-0.7 15.5 10.9 - 20.2 Pass MAW-4513 8/1/2017 H-3 255 +/-9 258 181 -335 Pass MAW-4513 8/1/2017 Fe-55 21.6 16.6 19.4 13.6-25.2 Pass MAW-4513 8/1/2017 Ni-63 -0.1 +/-2.0 0.0 NAC Pass MAW-4513 8/1/2017 Pu-238 0.590 +/-0.080 0.603 0.422 - 0.784 Pass MAW-4513 8/1/2017 Pu-239/240 0.740 +/-0.090 0.781 0,547 -1.015 Pass MAW-4513 8/1/2017 Ra-226 1.000 +/-0.100 0.858 0.601 -1.115 Pass MAW-4513 8/1/2017 Sr-90 7.80 +/- 0.60 7.77 5.44 -10.10 Pass MAW-4513 8/1/2017 Tc-99 6.70 +/- 0.40 6.73 4.71 - 8.75 Pass MAW-4513 8/1/2017 U-2344/233 0.94 +/-0.06 1.01 0.71 -1.31 Pass MAW4513 8/1/2017 U-238 0.97 +/- 0.07 1.04 0.73-1.35 Pass MAAP-4519h 8/1/2017 Am-241 0.0400 +/-0.0100 0.0612 0.0428-0.0796 Fail MAAP-4519 8/1/2017 Cs-134 0.90 +/-0.10 1.00 0.70-1.30 Pass MAAP-4519 8/1/2017 Cs-137 0.90 +/- 0.10 0.82 0.57 -1.07 Pass MAAP-4519 8/1/2017 Co-57 0.01 +/-0.01 0.00 NAC Pass MAAP-4519 8/1/2017 Cc-60 0.70 +/-0.10 0.68 0.48-0.88 Pass MAAP-4519 8/1/2017 Mn-54 1.50 +/-0.10 1.30 0.91 -1.69 Pass MAAP-4519 8/1/2017 Zn-65 1.30 +/-0.10 1.08 0.76 -1.40 Pass MAAP-4519 8/1/2017 Pu-238 0.0300 +/-0.0100 0.0298 0.0209 - 0.0387 Pass MAAP-4519 8/1/2017 Pu-239/240 0.0400 +/-0.0200 0.0468 0.0328 - 0.0608 Pass MAAP-4519 8/1/2017 Sr-90 0.800 +/-0.100 0.801 0.561 -1.041 Pass MAAP-4519 8/1/2017 U-234/233 0.070 +/- 0.010 0.084 0.059-0.109 Pass MAAP-4519 8/1/2017 U-238 0.090 +/- 0.010 0.087 0.061 -0.113 Pass
" Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soH), MAVE (vegetation).
0 MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" Indicates an analysis was included in the testing series as a "false positive11. MAPEP does not provide control limits.
11 Decimal point was misplaced while performing a unit conversion. The result is within control limits when the proper unit conversion is performed.
~~Provided in the series for "sensitivity evaluation11. MAPEP does not provide control Imite.~~
' Sample was reanalyzed In duplicate with acceptable results. Original plating was Inferior to platings obtained during reanarysls.
It is believed that isotopJc tracer was not accurately quantified due to poor resolution of its peak.
B Data were erroneously submitted In units of Bo/g. All results pass MAPEP criteria when evaluated In units of Bq/Kg.
h Laboratory is not currently offering analysis for Am-241 In Air Particulate samples.
A6-3
TABLE A-7. Interiaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*.
MRAD Study Concentration "
Laboratory ERA Control Lab Code1 Dale Analysis Result Result Limits c Acceptance 76.4 47.1 103.0 Pass 3/20/2017 Am-241 55.3 +/-2.8 ERAP-1112 1030 797 -1290 Pass ERAP-1112 3/20/2017 Co-60 1,23018 1100 700 -1360 Pass ERAP-1112 3/20/2017 Cs-134 1,110 +/-9 1,390 1.040 -1,830 Pass ERAP-1112 3/20/2017 Cs-137 1,810112 256 79.4 -500 Fall ERAP-1112 d 3/20/2017 Fe-SS 5901386
<50.0 0.00 -50.0 Pass 3/20/2017 Mn-64 <5.14 ERAP-1112 54.3 37.2 -71.4 Pass 3/20/2017 Pu-238 54.612.8 ERAP-1112 44.9 -81.0 Pass 3/20/2017 Pu-239/240 63.613.0 62.0 ERAP-1112 52.4 25.6 -78.5 Pass ERAP-1112 3/20/2017 Sr-90 55.3 18.3 73.1 45.3 -110 Pass ERAP-1112 3/20/2017 U-233/234 65.7 13.0 72.4 46.8 -100 Pass ERAP-1112 3/20/2017 U-238 67.3 13.0 984 705 -1,360 Pass ERAP-1112 3/20/2017 Zn-65 1,355116 28.6-133 Pass ERAP-1114 3/20/2017 Or. Alpha 10615 85.5 45.2 28.6 - 65.9 Fail ERAP-1114" 3/20/2017 Gr. Beta 67.613.0 448 262- 582 Pass ERSO-1116 3/20/2017 Am-241 418198 1,240 795- 1,720 Pass ERSO-1116 3/20/2017 Ao-228 1,5401260 1,240 330- 1,820 Pass 3/20/2017 BI-212 1,550190 ERSO-1116 2,750 1,660- 3,960 Pass 3/20/2017 BL-214 2,560120 ERSO-1116 4,430 3,000-* 6,100 Pass ERSO-1116 3/20/2017 Co-60 4,620 +/- 100 8,860 5,790- 10,600 Pass ERSO-1116 3/20/2017 Cs-134 6,340 1100 7,500 5,750- 9,650 Pass 3/20/2017 Cs-137 8,420 1100 ERSO-1116 10,600 7,740-* 14,200 Pass ERSO-1116 3/20/2017 K-40 13,6001900
<1000 0.00-.1,000 Pass ERSO-1116 3/20/2017 Mn-54 <68.1 1,240 812--1,730 Pass ERSO-1116 3/20/2017 Pb-212 1,060170 2,890 1,690--4,310 Pass ERSO-1116 3/20/2017 2,620 1160 648 390--894 Pass 3/20/2017 Pu-238 4241154 ERSO-1116 484 316 -669 Fall ERSO-1116f 30012017 Pu-239/240 2521112 484 316 -669 Pass ERSO-1116* 3/20/2017 Pu-239/240 4361106 9:150 3,490 -14,500 Pass 3/20/2017 Sr-90 7,930 +/-250 ERSO-1116 1,940 614 -3,650 Pass 3/20/2017 Th-234 1,8201200 ERSO-1116 1,950 1190 -2,500 Fail ERSO-1116h 3/20/2017 U-233/234 1,0301130 1,950 1,190 -2,500 Pass 1.820 +/-200 ERSO-1116' 3/20/2017 U-233/234 Pass 1,2401140 1,940 1,200 -2,460 ERSO-1116 3/20/2017 U-238 1,940 1,200 -2:460 Pass ERSO-1116! 3/2072017 U-238 1,9301200 6,090 4,850 Pass 3/20/2017 Zn-66 7,1901240 ERSO-1116 89.5 31.6 -139 Pass ERW-1122 3/20/2017 Gr. Alpha 65.312.4 61.0 34.9-90.4 Pass ERW-1122 3/20/2017 Gr.Beta 54.8 11.5 19.400 13000-27,700 Pass ERW-1124 3/20/2017 H-3 19,0001410 A7-1
TABLE A-7. Intel-laboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*
_ MRAD Study Concentration' Lab Code b Date Analysis Laboratory ERA Control Result Result Limits0 ERVE-1118 3/20/2017 Am-241 1,560 +/- 140 1.B60 1.140 -2,470 Pass ERVE-1118 3/2072017 Cm-244 530 +/-80 734 360 -1,140 Pass ERVE-1118 3/20/2017 Co-60 1,40D+/-350 1,390 959 -1,940 Pass ERVE-1118 3/20/2017 Cs-134 1,650 +/-460 1,830 1,180 -2,380 Pass ERVE-1118 3/20/2017 Cs-137 2,580 +/- 540 2,500 1,810 -3,480 Pass ERVE-1118 3/20/2017 K-40 32,100 +/- 700 30,900 22,300 -- 43,400 Pass ERVE-1118 3/20/2017 Mn-54 <27.3 <300 0.00--300 Pass ERVE-1118 3/20/2017 Zn-65 889 +/-64 853 615--1,200 Pass ERVE-1118 3/20/2017 Pu-238 3,250 +/-210 3,250 1,940--4,450 Pass ERVE-1118 3/2072017 Pu-239/240 2,1801170 2,150 1,320 --2,960 Pass ERVE-1118 3/20/2017 Sr-90 685 +/-135 726 414--963 Pass ERVE-1118 3/20/2017 U-233/234 2,640 +/-200 3,090 2,030- 3,970 Pass ERVE-1118 3/20/2017 U-238 2,990 +/- 200 3,060 2,040- 3,890 Pass ERW-1120 3/20/2017 Am-241 108+/-7 140 94.3 -188 Pass ERW-1120 3/2072017 Co-60 2,600 +/- 198 2,540 2,210 -2,970 Pass ERW-1120 3/2072017 Cs-134 2,380 +/- 250 2,510 1,840 -2880 Pass ERW-1120 3/20/2017 Cs-137 1,470 +/-243 1,400 1,190 -1,680 Pass ERW-1120 3/20/2017 Mn-54 <12.3 <100 0.00 -100 Pass ERW-1120 3/20/2017 Pu-238 117+/-4 128 94.7 -159 Pass ERW-1120 3/2072017 Pu-239/240 74.8 +/- 3.3 85.6 66.6 -108 Pass ERW-1120 3/20/2017 U-233/234 75.3 +/- 3.2 90.3 67.8 -116 Pass ERW-1120 3/20/2017 U-238 76.4 t 3J2 89.5 68.2 110 Pass ERW-1120 3/20/2017 Zn-65 2,130 +/- 378 1,960 1630 *2,470 Pass ERW-1120' 3/20/2017 Fe-55 1,400 +/-403 984 587 -1,340 Fail ERW-1120k 3/20/2017 Fe-55 1,081 +/-383 984 587 *1,340 Pass ERW-1120 3/20/2017 Sr-90 652 +/-12 714 465 -944 Pass s, serving as a replacement tor studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program <EML)
\ %£?JSS£iXS£ SKBaSBtSSaSSSf*ERVE
<< jSided STera1 M *6 kn°m W*IB8i °*pected laboratorv Preston (2 sigma. 1 determination) and control limits Fe-55 analysis result was outside the acceptable range. Recounting the sample disk tor 1000 minutes resulted In 2M +/- 364 w<<h an LLD crta<<lon of < 342. lr>>ufficlerrt^
required analyse! on the sample to quantity the activity with an uncertainty leu than the activity.
5S oratory Thia likely caused the efficency used thTcalcutatSJto to
^JJSSr *^ For comparison the in-house spike for gross beta in AP (table A-3 SPAP-740 2/28/17) was acceptable with a ratio of 0.S4 of lab reeuH to known
' Analysis result for PkJtonlum-238/240 was below the lower limit of acceptance.
1 Samples were reanalyzed in duplicate with acceptable results for each. Original analysis had poor resolution Dossibtv due to a poor elctroplating and is suspected in contributing to poor results. ^^ resojuoon possibly h Analysis result for U-233/234 was betowthe lower limit of acceptance.
' ]Jlf rea,na^'8 rB8uft for U-233<<34 was within the acceptance limits and U-23B resrar/sta result was closer to the known value.
Originai analysis had poor resolution possWy due to a poor electroplating and is Mm*S*S£Sb£lfto,£ SZ
' Fe-55 analysis result was outside acceptable range.
A7-2
2017 Annual Environmental and Effluent Release Report Appendix B 2017 REMP Data Summary Reports
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440750-441 Lake County, Ohio Reporting Period: 2017 Mean for Indicator Location with Highest Annual Mean Number of Pathway Type and Mean for All Locations Mean for Control Lower Limit Locations Non-routine Sampled Total Number Locations of Detection Detected/Collected Reported of Analyses Detected/Colected Location # Mean Detected/
Units (LLD)* Detected/Colected Measurements Performed Range Distance & Collected Range Direction Range Range 0.066 0.067 7 0.070 Air Be-7 0.074 0 N/A 28/28 24/24 0.6 pCi/m3 28 4/4 4/4 0.049 - 0.084 0.049-0.083 NE 0.051 - 0.083 0.061 - 0.084
<LLD <LLD Air Co-58 <LLD 0 N/A 0/28 0/24 0/4 pCi/m3 28
<LLD <LLD Air Co-60 <LLD 0 N/A 0/28 0/24 pCi/m3 0/4 28
<LLD <LLD Air Cs-134 <LLD 0 0.037 0/28 0/24 0/4 pCi/m3 28
<LLD <LLD Air Cs-137 <LLD 0 0.045 0/28 0/24 0/4 pCi/m3 28 0.024 0.023 7 0.025 Air Gross Beta 0.026 0 0.0075 371/371 318/318 0.6 pCl/m3 371 53/53 53/53 0.009 - 0.058 0.009-0.058 NE 0.013 - 0.058 0.013-0 057
<LLD <LLD Air 1-131 <LLD 0 0.05 0/371 0/318 pCi/m3 371 0/53
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2017 Number of Mean for Indicator Location with Highest Annual Moan Mean for Control Non-routine Type and Mean for All Locations Pathway Lower Limit Locations Locations Reported Sampled Total Number Detected/Collected Mean Detected/ Detected/Collected Measurements of Detection Detected/Collected Location #
of Analyses Collected (LLD)* Distance & Range Units Performed Range Range Direction Ranae 20 514.7 407.6 0 388.4 383.5 Broadleaf Be-7 1.9 9/12 10/14 Vegetation N/A 48/65 39/51 65 E 194-805 245-584 pCi/kgwet 115-971 0-971 20 5582.0 4751.0 0 4633.0 4600.6 Broadleaf K-40 12/12 14/14 Vegetation N/A 65/65 51/51 1.9 65 3681-9060 3141-6869 pCi/kgwet 2709-9060 2709-9060 E
<LLD 0
<LLD <LLD Broadleaf Co-58 0/14 0/51 Vegetation N/A 0/85 65 pCi/kgwet
<LLD 0
<LLD <LLD Broadleaf Co-60 0/14 Vegetation 0/65 0/51 N/A 65 pCi/kgwet
<LLD 0
<LLD <LLD Broadleaf 1-131 0/14 Vegetation 45 0/65 0/51 65 pCi/kgwet
<UJD 0
<LLD <LLD Broadleaf Cs-134 0/14 Vegetation 45 0/65 0/51 65 pCi/kgwet
<LLD 0
<LLD <LLD Broadleaf Cs-137 0/14 Vegetation 60 0/65 0/51 65 pCi/kgwet
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440750-441 Lake County, Ohio Reporting Period: 2017 Type and Mean for Indicator Location with Highest Annual Mean Number of Pathway Mean for All Locations Mean for Control Lower Limit Locations Non-routine Sampled Total Number Locations of Detection Detected/Collected Reported of Analyses Detected/Collected Location # Mean Detected/
Units (ULD)* Detected/Collected Measurements Performed Range Distance & Collected Range Direction Range Range 1473.2 1398.4 32 Fish K-40 1535.5 1535.5 0 N/A 11/11 5/5 pCi/kgwet 11 15.8 6/6 6/8 768 - 2821 1035-1745 WSW 768-2821 768 - 2821
<LLD <LLD Fish Mn-54 <LLD 0 94 0/11 0/5 0/6 pC I/kg wet 11
<U_D <LLD Fish Fe-59 <LLD 0 195 0/11 0/5 0/6 pCi/kgwet 11
<LLD <LLD Fish Co-58 <LLD 0 97 0/11 0/5 0/6 pCi/kgwet 11
<LLD <l_LD Fish co-eo <LLD 0 97 0/11 0/5 0/6 pCi/kgwet 11
<LLD <LLD Fish Zn-65 <LLD 0 195 0/11 0/5 pCi/kgwet 11 0/6
<LLD <LLD Fish Cs-134 <LLD 0 97 0/11 0/5 0/6 pCi/kgwet 11
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2017 Number of Mean for Indicator Location with Highest Annual Mean Mean for Control Non-routine Type and Mean for All Locations Locations Reported Pathway Locations Lower Limit Total Number Mean Detected/ Detected/Collected Measurements Sampled of Detection Detected/Collected Detected/Collected Location #
of Analyses Collected (LLD)* Distance & Range Units Performed Range Range Direction Range
<LLD 0
<LLD <LLD Fish Cs-137 0/6 112 0/11 0/5 pCi/kgwet 11 1489 1426.4 0 1426.4 N/A 19 Milk K-40 9.2 19/19 38/38 N/A 38/38 N/A pCi/L 38 S 1190-2546 1190-2546 1190-2546 N/A
<LLD 0
<LD N/A Milk H31 0/38 0.8 0/38 N/A pCi/L 38 N/A
<LLD 0
<LLD N/A Milk Cs-134 0738 N/A 11 0738 pCi/L 38 N/A
<LLD 0
<LLD N/A Milk Cs-137 0/38 N/A 13 0/38 pCi/L 38 N/A
<LLD 0
<LLD N/A Milk Ba-140 0738 N/A 45 0/38 pCi/L 38 N/A
<LLD 0
<LLD N/A La-140 0/38 Milk N/A 11 0/38 pCI/L 38 N/A
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50*441 Lake County, Ohio Reporting Period: 2017 Pathway Type and Mean for All Locations Mean for Indicator Location with Highest Annual Mean Number of Total Number Lower Limit Locations Mean for Control Sampled Non-routine of Analyses of Detection Detected/Collected Locations Location # Mean Detected/ Reported Unrts (LLD)* Detected/Collected Detected/Collected Performed Range Collected Measurements Distance &
Range Range Direction 10048.0 10048.0 64 Sediment K-40 12099.5 N/A N/A 4/4 4/4 pCi/kgwet 0.4 2/2 N/A 7739-15112 7739-15112 WNW 9087-15112 N/A
<LLD <LLD Sediment Co-58 N/A SO 0/4 pCi/kgwet 4 0/4 N/A N/A
<LLD <LLD Sediment Co-60 N/A 40 0/4 pCi/kgwet 4 0/4 N/A N/A
<LLD <LLD Sediment Cs-134 N/A 112 0/4 pCi/kgwet 4 0/4 N/A N/A
<LLD <LLD Sediment Ca-137 N/A 135 0/4 pCi/kgwet 4 0/4 N/A N/A
Environmental Radiological Monitoring Program Mnual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2017 Number of Location with Highest Annual Mean Mean for Control Non-routine Mean for Indicator Mean for All Locations Locations Reported Type and Locations Pathway Lower Limit Mean Detected/ Detected/Collected Measurements Total Number Detected/Collected Location #
Sampled of Detection Detected/Collected Collected of Analyses Distance &
(LLD)*
Performed Range Range Direction
Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2017 Pathway Type and Mean for All Locations Mean for Indicator Location with Highest Annual Mean Number of Lower Limit Locations Mean for Control Sampled Total Number Non-routine of Detection Detected/Collected Locations of Analyses Mean Detected/ Reported (LLD)* Detected/Collected Location # Detected/Collected Performed Range Collected Measurements Distance &
Range Direction This value is the LLD that is met by the vendor and Is lower than required by the ODCM
2017 Annual Environmental and Effluent Release Report Appendix C 2017 REMP Detailed Data Report
Environmental, Inc.
70OUn#we?v RuBj-MalhWOOft JL <<O0S? ?310 pti (M7)d6*<<lfl>>'faii(M7)fiG4-4S17 MONTHLY PROGRESS REPORT to FIRST ENERGY CORPORATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
FOR THE PERRY NUCLEAR POWER PLANT Reporting Period: January-December, 2017 Prepared and Submitted by ENVIRONMENTAL, INC.,
MIDWEST LABORATORY Project Number: 6033 Reviewed and APProved /IHf ( ,(H/^ Date Distribution- M. Baker P. Hintz, Ohio Department of Health B. Mechenbfer, Uke County Health Department
EfcBEXNUCLEAR POWERPLANX TABLE OF CONTENTS Section lit
~~1.0 INTRODUCTION~~
2.0 USTING OF MISSED ED SAMPLES SAMPLES -
- '"v 3,0 DATATWLES * '
~~lVI A Irteriaboratory Comparison Program Results , *1 8 1 B Data Reporting Conventions. ..,-. * * -~~
PERRY NUCLEAR POWER PLANT LIST OF TABLES NO. Title 1 Direct Radiation, Quarterly and Annual 1-1 2 Airborne Paniculate FUtere and Charcoal Canisters 2-1 3 Airborne Partlculate Filters 3-1 4 Lake Water , 4-1 5 Milk 5-1 7 Food Products 7-1 9 Fish 9-1 11 Sediments 11-1
PERRY NUCl E
~~1.0 INTRODUCTION~~
The following constitutes the final 2017 report for the ag f^j^ ^
Program conducted at the Perry Nuclear Power Plant In Perry, Ohio. Results of completed analyses are presented In the attached tables.
The data obtained to the program were within ranges previously encountered and to be expected in the environmental media sampled.
m concentrations, except gross bete, are decay corrected to the time of collection. Airborne Iodine is decay corrected to the midpoint of the collection period All samples were collected within the scheduled period, unless noted otherwise in Table 2.0, Listing of Missed Samples.
iv
PNPP 2.0 LISTING OF MISSED SAMPLES Expected Sample Type Location Collection Reason Date LW P-59 01-26-17 No sample sent LW P-60 01-26-17 No sample sent.
PNPP Table 1. Direct Radiation (TLDs), Quarterly Exposure.
Units. mR/91 days 2nd Qtr. 3rd Qtr, 4th Qtr.
Date Placed 01-05-16 04.05-17 07-06-17 10-10-17 Date Removed 04-07-16 07-06-17 10-10-17 01-15-18 E-1 11.7 +/-0-5 113 +/-1.4 10.6*1.1 9.8 +/-1.1 E-3 11.8*0.9 10.4 +/-1.1 11.2*1.6 8.8*1.1 E-4 13-2*06 11.6 +/-1.1 11.6*0.8 10.2*09 E-5 107 +/-0.7 8.5 +/-0.9 9.5 +/-0.8 8.6 +/-09 E-6 12,510.9 10.0+0.9 10.5*0.9 91 +/-0,7 E-7 10.1 +/-0.6 11.4*1.6 8.5 +/-0.6 9.9*1.0 E-8 105107 9.5 +/-0.9 9.2 +/-0.7 8,6*0.7 E-9 9,1 10.5 8.8*1.0 8.0
0.8 8 8 +/-0.9 E-10 13.6*0.7 9.9 +/-1.0 125*0.5 9.1 +/-0.9 E-11 13.3*1.1 13.111.0 12.6 +/-0.9 12.5 +/-0.9 E-12 12.9 +/-0.8 10.2 +/-1.2 11.9 +/-0-8 10.6 +/-1.1 E-13 10.8 +/-1.5 10.4 +/-11 97*10 101 +/-1.1 E-14 11.9*0.7 11,2 +/-09 10.7*0.8 9.9 +/-0.8 E-15 11.3 +/-0.8 10.5 +/-0.9 9,8*07 9.2 +/-0 7 E-21 12.8 +/-0.8 10.6*1.1 12,6
~~0.6 11.3 +/-0.8 E-23 13.6 +/-0.8 12.3 +/-1.0 13.0~~
1.1 11,8+0.7 E-24 13.0 +/-1.2 10,7*11 11.6*1.4 11,0*0.9 E-29 14.8*1,3 14.6 +/-11 141 +/-0.8 13,6 +/-10 E-30 14.3 +/-0.6 14.3 +/-1.0 13.1 +/-0.6 12.3 +/-0.9 E-31 14.5 +/-0.9 132 +/-1.0 13.6
~~1.2 12.6 +/- 0.9 E-33 16.6~~
10 14.5 +/-1,3 16.1 +/-0.8 14.7 +/-0.8 E-35 11.3*0.7 11.2 +/-11 10.7 +/-0.7 11.0 +/-0.9 E-36 15.6*0.7 13.8*0.8 14,6
0.5 1Z8 11.0 E-53 11.4*0.6 10,8*11 11.2 +/-0.6 10.7*1.2 E-54 12.1 +/-1.0 104*1.0 11.1 +/-07 10.0 +/-0.9 E-55 11.9*1.4 114*1.1 11.5*1,2 11.5 +/-1.1 E-56 11.3 +/-0 6 12.0
~~1.3 10.6*0.6 10.5*1.1 E-57 13.3*0.8 12.7*12 13.5 +/-0.9 11.5*1.0 E-5B 9.7*0.6 9 0 *09 7.8*1.4 8.3~~
~~0.9 Mean +/- s.d. 12.4*1.8 11.3*1,7 11.4*2.0 10.6~~
~~1.7 E-Control 1 7.0 +/-1.3 5.4*1.0 6.2*1.1 5.7 +/-1.0 E-Control 2 6.9 +/- 0.8 5.2~~
~~1.0 7.5~~
~~0,7 5.3~~
~~0 8 1-1~~
PNPP Table 1, Direct Radiation (TLOs), Quarterly Exposure.
Units: mR/91 days 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Date Placed 01-12-15 04-05-17 07-06-17 10-10-17 Date Removed 04-03-15 07-06-17 10-10-17 01-15-18 Q-1 12.7 +/-1.1 10.3 +/-1.2 12.4 +/-12 10.9 +/-1.2 Q-3 10.6 +/- 0.5 9.6 +/-1.0 10.4 +/- 0.9 9.7 +/-12 Q-4 11.9 +/-0.7 10.6 +/-0.9 12.0 +/-0.7 11.6 +/-0.9 Q-5 117 +/-0.9 10.1 +/-11 117 +/-0.6 115+/-11 Q-6 11.6 +/-0.7 11.5 +/-0.8 113 +/-0.6 116 +/-0.9 Q-7 15.6 +/- 1.1 111 +/-0.9 13.2 +/-0.6 119 +/-15 Q-8 10.8 +/-0.6 9.5 +/-0.8 11.0 +/-0.5 10.4 +/-0.9 Q-9 12.6 +/-1.0 8 5 +/-0.9 11.8 +/-10 9.5 +/-0.9 Q-10 11.3 +/-0.4 10.4 +/-0.8 115 +/-0.6 10.6 +/- 0.9 Q-11 13.3 +/-0.8 12.5 +/-0.9 13.3 +/-0.6 12.8 +/- 10 Q-12 12.1 +/- 0.8 10.5 +/-0.9 12.0 +/-0.5 10.9 +/-11 Q-13 12.2 +/- 1.0 9.6 +/-11 12.0 +/-0.6 10.1 +/-12 0-14 12.6 +/-0.7 112*1.0 12.9 +/- 0.5 11.6 +/-10 0*16 11.6 +/-0.5 9.9 +/-0.9 12.6 +/- 0.5 87 +/- 10 Q-21 14.1 +/-0.5 13.8 +/-1.3 14.9 +/-0.4 12.9 +/-1.2 Q-23 14.9 +/-1.2 13.8 +/-1.4 15.3 +/-1.0 13.3 +/-1.4 Q-24 12.7 +/-1.7 11.8 +/-1.0 114 +/-11 12.2 +/-1.0 Q-29 17.6 +/-1.2 16.0 +/-13 18.7 +/-13 15.0 +/-11 Q-30 13.6 +/-0.7 117 +/-1X3 14.0 +/- 0.5 112 +/-0.9 Q-31 16.3 +/-1.0 14.4 +/-0.9 17.6 +/-0.9 15.9 +/-11 Q-33 17.3 +/-07 17.0 +/-12 17.2 +/-0.8 16.3 +/-11 Q-35 117 +/-0.6 114 +/-0.8 13.0 +/- 0.5 10.6 +/-0.9 Q-36 15.9 +/-0.6 14.6 +/- 0.8 16.9 +/-0.4 14.0 +/-0.9 Q-53 13.2 +/-0,6 116 +/-10 13.0 +/-0.7 12.8 +/-18 Q-54 12.4 +/- 0.6 12.3 +/-0.9 12.5 +/- 0.4 116 +/-0.9 Q-55 14.7 +/-1.0 113 +/-10 15,1 +/-0.8 10.6 +/-0.9 Q-56 13.8 +/-0.8 12.1 +/-10 13.9 +/- 0 6 11.7 +/-11 Q-67 13.4 +/- 1.3 13.3 +/- 0.9 14.1 +/-1.0 12.9 +/-10 Q-58 9.5 +/-0.9 111 +/-0.9 9.9 +/- 0-9 9.9 +/- 0.9 Mean +/- s.d. 13.2 +/-2.0 11.8 +/-2.0 13.3 +/-2.2 118 +/-18 Q-ControM 6,3 +/- 0.5 6.8 +/- 0.9 6.6 +/- 0.5 6.6 +/-10 Q-Control 2 7.1 +/-0.8 6.9 +/- 0.8 7.6 +/-0.5 6.2 +/- 0.9 1-2
PNPP Table 1. Direct Radiation (TLDs), Annual Exposure.
Unite: mR/365days 2Q12 Date Placed 01-rM7 Date Removed Dt-15-18 64.4 +/-3.4 A-1 53.0*2.3 A-3 55.2 +/-2.5 A-4 A-5 64.7 +/-2.2 A-6 66.8 +/-1.9 58.0 +/-2.1 A-7 5^.7 +/-1.9 A*
A-9 56.0 +/-3.3 A-10 53.5 +/-1.8 60.8 +/-4.3 A-11 A-12 58.1 +/-2,0 A-13 566 +/-3.0 A-14 60.1 +/-3.4 A-15 50,0 +/-27 63.2 +/-3.6 A-21 A-23 70.2 +/-20 59.2 +/-3.3 A-24 716 +/-2.7 A-29 A-30 614 +/-3.0 89.6 +/-2 7 A-31 A-33 73.0 +/-3.4 A-35 51.1 +/-26 A-36 71,3 +/-4.5 60.3 +/-3.2 A-53 A-54 57.9 +/-4.1 A-55 53.1 +/-12 61.5 +/-3.0 A-57 56.5 +/-2.7 A-56 51.3 +/-2.0 59.0 +/-6.6 Mean +/- s.d.
A-ControM 27.9 +/-1.5 26.8 +/-1.6 A-Cpntrol 2 1-3
PNPP Table 2. Airborne particufates and diarcoal canisters, analyses for gross beta and iodine-131 Location: P-1 Units: pCi/m8 Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected <nV) Gross Beta M31 Collected Gross Beta H31 Reouired LLD 0.0075 0.050 0.0075 0.050 01-04-17 529 0.023 +/-0.003 < 0.006 07-05-17 576 0.01910.003 < 0.007 01-11-17 549 0.032 +/- 0.003 < 0.005 07-13-17 676 0.025 +/- 0.003 < 0.007 01-18-17 544 0.031 +/-0.003 < 0.007 07-19-17 496 0.021 +/- 0.003 < 0.007 01-25-17 537 0.01710.003 < 0.009 07-26-17 566 0.023 +/- 0.003 < 0.003 02-01-17 548 0.023 +/-0.003 < 0.008 06-02-17 578 0.021 +/- 0.003 < 0.004 02-09-17 614 0.026 +/-0.003 < 0.006 08-09-17 673 0.022 +/- 0.003 < 0.006 02-15-17 481 0.033 +/-0.004 < 0.007 08-16-17 560 0.031 +/-0.003 < 0.012 02-22-17 520 0.029 +/-0.003 < 0.007 08-23-17 582 0.034 +/- 0.003 < 0.005 03-01-17 545 0.026 +/-0.003 < 0.006 08-30-17 574 0.018 +/-0.003 < 0.014 03-06-17 540 0.024 +/- 0.003 < 0.011 09-06-17 561 0.024 +/- 0.003 < 0.007 03-16-17 609 0.022 +/- 0.003 < 0.006 09-13-17 580 0.014 +/-0.003 < 0.006 03-22-17 455 0.028 +/-0,004 < 0.009 09-20-17 591 0.037 +/- 0.003 < 0.004 03-30-17 632 0.024 +/- 0.003 < 0.005 09-27-17 549 0.050 +/- 0.004 < 0.006 1Q2017 Mean +/- s.d. 0.026 +/-0.005 < 0.011 3Q2017 Mean +/- s.d. 0.026 +/-0.010 < 0.014 04-05-17 456 0.015 +/-0-003 < 0,012 10-04-17 583 0.025 +/-0.003 < 0.007 04-12-17 541 0.015 +/-0.003 < 0.009 10-11-17 570 0.027 +/- 0.003 < 0.009 04-19-17 538 0.021 +/-0.003 < 0.012 10-18-17 567 0.021 +/- 0.003 < 0.006 04-26-17 547 0.015 +/-0,003 < 0.008 10-25-17 586 0.041 +/- 0.003 < 0.006 05-03-17 547 0.012 +/-0.003 < 0.003 11-01-17 564 0.019 +/- 0.003 < 0.008 05-10-17 531 0.014 +/-0.003 < 0.007 11-08-17 571 0.027 +/- 0.003 < 0.0O7 05-17-17 539 0.015 +/-0.003 < 0.006 11-15-17 596 0.033 +/- 0.003 < 0.008 05-24-17 532 0.018 +/-0.003 < 0.008 11-22-17 S55 0.027 +/- 0.003 < 0.007 05-31-17 633 0.010 +/-0.002 < 0.006 11-29-17 587 0.036 +/-0.003 < 0.008 06-07-17 544 0,016 +/-0.003 < 0.006 12-06-17 578 0.033 +/- 0.003 < 0.006 06-14-17 553 0.023 +/- 0.003 < 0.006 12-13-17 583 0.027 +/- 0.003 < 0.005 06-21-17 566 0.019*0.003 < 0.005 12-20-17 566 0.035 +/- 0.003 < 0.008 06-28-17 582 0.015 +/-0.003 < 0,007 12-27-17 587 0.030 +/- 0.003 < 0.007 01-03-18 566 0.024 +/- 0.003 < 0.007 2Q2017 Mean +/-s.d. 0.016 +/-0.004 < 0.012 4Q2017 Mean +/- s.d. 0.029 +/-0.006 < 0.009 Cumulative Average 0.024 2-1
PNPP Table 2. Airborne partteulates and charcoal canisters, analyses for gross beta and fodine-131 Location: P-3 Units: pCMz Coilection: Continuous, weekly exchange.
Volume Date Volume Date
<nV> Gross Beta 1-131 Collected <mJ) Gross Beta M31 Collected Reaulf&d LLC 0.0075 0,050 0.0Q7S p.05,0 01-04-17 531 0.023 +/-0.003 < 0.006 07-05-17 679 0015 +/-0,002 < 0.006 0029 +/-0.003 < 0,005 07-13-17 794 0.018 +/-0.002 < 0.006 01-11-17 544
< 0,007 07-19-17 544 0.018 +/- 0.003 < 0,007 01-1B-17 530 0 029 +/-0003 536 0.019 +/-0.003 < 0.009 07-26-17 664 0.019 +/-0.003 < 0.003 01-25-17 0.022 +/-0.003 < 0.008 08-02-17 672 0.015 +/-0.002 <0004 02-01-17 522 602 0.027 10.003 < 0.006 08-09-17 683 0022 +/-0.003 < 0.005 02-09-17 0.031 +/-0.004 < 0.007 08-16-17 590 0.030 +/-0.003 < 0.011 02-15-17 464 0.028 +/-0.003 < 0,007 08-23-17 949 0026 +/-0.003 < 0.006 02-22-17 535 03-01-17 524 0.025 +/-0.003 < 0.006 08-30-17 531 0.015 +/-0.003 < 0.015 03-08-17 532 0024 +/-0.003 < 0-012 09-06-17 541 0.021 +/-0.003 < 0,007 0.024 +/-0003 <0 006 09-13-17 532 0.012 +/- 0.003 < 0.007 03-16-17 597 03-22-17 459 0.024 +/-0.004 < 0,009 09-20-17 662 0.032 +/-0.003 <0.005 0.027 +/- 0 003 < 0.005 09-27-17 521 0,042 +/-0.004 < 0.005 03-30-17 628 Mean +/- s.d. 0.026 +/-0.003 < 0.012 3Q2017 Mean+/-sd. 0.022 +/-0.009 < 0.015 1Q2017 0 014 +/-0.003 < 0.013 10-04-17 523 0.021 +/-0.003 <0>007 04-05-17 435 523 0.015 +/-0.003 <G009 10-11-17 530 0.027 +/-0.003 < 0.010 04-12-17 0.018 +/-0.002 < 0.009 10-18-17 575 0.025 +/-0.003 < 0.006 04-19-17 673 0.011 +/-0.002 < 0.006 10-25-17 603 0.033 +/- 0.003 < 0.006 04-26-17 672 683 0.012 +/-0.002 < 0.003 11-01-17 541 0,017 +/-0.003 < 0.006 05-03-17 0.013 +/-0.002 < 0.005 11-08-17 554 0.030+0.003 < 0.007 05-10-17 650 707 0.014 +/-0.002 < 0.005 11-15-17 573 0.039 +/-0.003 < 0.008 05-17-17 652 0 014 +/- 0.002 << 0.007 11-22-17 524 0.032 +/-0,004
0.007 05-24-17 0,012 +/-0.003 < 0.007 11-29-17 705 0.032 +/- 0 003 < 0.006 05-31-17 549 0.016 +/-0.002 < 0.005 12-06-17 726 0.027 +/- 0.003 < 0.005 06-07-17 691
< 0.005 12-13-17 578 0,024 +/-0.003 < 0.005 00-14-17 681 0.021 +/- 0.003 659 0.019 +/- 0.002 < 0.004 12-20-17 564 0.026 +/-0.003 < 0.006 06-21.17 06-28-17 670 0 013 +/-0,002 <0,006 12-27-17 594 0.021 +/- 0.003 < 0.007 01-03-18 575 0.021 +/- 0.003 < 0.008 2Q2017 Meant s.d. 0.015 +/-0.003 < 0.013 4Q2017 Meant s.d. 0.027 +/-0.006 < 0.010 Cumulative Average ° 022 2-2
PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: P-4 Units: pCi/m3 Collection : Continuous, weekly exchange.
Dale Volume Date Volume Collected <ma) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 ReauiredLLD 0.0075 0.050 0.0075 0.050 01-04-17 557 0.022 10.003 < 0.006 07-05-17 568 0 017 +/-0.003 < 0.006 01-11-17 552 0 027 +/-0.003 < 0.005 07-13-17 647 0.024 +/- 0.003 < 0.007 01-18-17 529 0.027 +/- 0.003 < 0.007 07-19-17 451 0.021 +/-0.003 < 0.008 01-25-17 558 0.016 +/-0.003 < 0.008 07-26-17 543 0.022 +/-0.003 < 0,003 02-01-17 532 0.023 +/- 0.003 < 0.008 08-02-17 551 0.021 +/- 0.003 < 0.005 02-09-17 610 0.027 i 0.003 < 0.008 08-09-17 568 0.022 +/-0.003 < 0.006 02-15-17 474 0.028 +/- 0.004 < 0.007 08-18-17 532 0.032 +/- 0.003 < 0.013 02-22-17 539 0.027 +/-0.003 < 0.007 08-23-17 551 0.028 +/- 0.003 < 0.006 03-01-17 527 0.023 +/-0.003 < 0.006 08-30-17 543 0.019 +/- 0.003 < 0.015 03-06-17 540 0.023 +/-0.003 < 0.011 09-06-17 543 0.021 +/- 0.003 < 0.007 03-16-17 605 0.025 +/- 0.003 < 0.006 09-13-17 543 0.015 +/-0.003 < 0.007 03-22-17 462 0.024 +/- 0.004 < 0.009 09-20-17 670 0.041 +/- 0 003 < 0.005 03-30-17 634 0.O22 +/- 0.003 < 0.005 09-27-17 520 0.049 +/- 0.004 < 0.005 1Q 2017 Mean +/- 8.d. 0.024 +/- 0.003 < 0.011 3Q 2017 Mean +/- s.d, 0.026 +/- 0.010 < 0.015 04-05-17 446 0.013 +/-0.003 < 0.013 10-04-17 541 0.023 +/-0.003 < 0.007 04-12-17 530 0.012 10.003 < 0.009 10-11-17 545 0.028 *0.003 < 0.009 04-19-17 560 0.019 +/-0.003 < 0.011 10-18-17 558 0.023 +/- 0.003 < 0.006 04-26-17 560 0.012 +/-0.003 < 0.008 10-25-17 571 0.040 +/- 0.003 < 0.006 05-03-17 572 0.010 +/-0.003 < 0.003 11-01-17 566 0.017 +/-0.003 < 0.006 05-10-17 5S6 0.014 +/- 0.003 < 0,006 11-08-17 562 0.024 +/- 0.003 < 0.006 05-17-17 563 0.012 +/- 0.003 < Q.006 11-15-17 584 0.031 +/- 0.003 < 0.008 05-24-17 560 0.013 +/-0.003 < 0.008 11-22-17 571 0.026 +/- 0.003 < 0.007 05-31-17 565 0.010 +/-0.003 < 0.007 11-29-17 570 0.032 +/- 0.003 < 0.008 06-07-17 572 0.017 +/-0.003 < 0.006 12-06-17 588 0.036 +/- 0.003 < 0.006 06-14-17 564 0 026 +/- 0.003 < 0.006 12-13-17 566 0.025 +/- 0.003 < 0.006 06-21-17 547 0.020 +/- 0.003 < 0.005 12-20-17 545 0.036 +/- 0.003 < 0.006 06-28-17 566 0.013 +/-0.003 < 0.007 12-27-17 583 0.025 +/- 0.003 < 0.007 01-03-1B 556 0.023 +/- 0.003 < 0.007 2Q2017 Mean +/-s.d. 0.015 +/-0.005 < 0.013 4Q2017 Meant s.d. 0.028 +/-0.006 < 0.009 Cumulative Average 0.023 2-3
PNPP Table 2. Airborne participates and charcoal canisters, analyses for gross beta and iodlne-131.
Location: P-5 Unite- pCi/m3 Collection: Continuous, vyeekly exchange.
Date Volume Date Volume Deflected (m3) Gross Beta 1-131 Collected Gross Beta 1-131 Required LLD 0.0075 O.Q50 0.0075 p.oso 0.022 +/- 0.003 <0.008 07-05-17 553 0.018 +/-0 003 < 0.008 01-04-17 553 0,029 +/-0.003 < 0.005 07-13-17 626 0.02410.003 < 0.008 01-1M7 565 01-18-17 548 0.031*0.003 < 0.007 07-19-17 458 0.020 10.003 < 0.008 01-25-17 553 0,01810.003 < 0.008 . 07-26-17 526 0,02310,003 < 0.003 0.02010.003 < 0.008 08-02-17 539 0.021 +/-0.003 < 0.005 02-01-17 540 02-09-17 630 0.025 +/- 0.003 < 0.006 08-09-17 557 0.021 10.003 < 0.006 02-15-17 471 0.031 +/-0.004 < 0.007 08-16-17 516 0.030 +/-0.003 <, 0.013 0.029 +/-0.003 < 0007 08-23-17 541 0,02910.003 < 0.006 02-22-17 546 002510.003 < 0.006 08-30-17 535 0.017 +/-0 003 < 0.015 03-01-17 535 03-08-17 548 0.024 l0.003 < 0.011 09-06-17 532 0.022 10,003 < 0.008 03-16-17 637 0 024 +/- 0.003 < 0.006 09-13-17 533 0.01210.003 < 0.007 03-22-17 454 0.028 +/-0.004 < 0.009 09-20-17 560 0.039 +/-0.003 < 0005 03-30-17 630 0,02310.003 < 0.005 Oft-27-17 518 0.045 +/-0.004 < 0.005 1Q2017 Meanis.d. 0.026 +/-0.004 < 0.011 3Q2017 Mean +/- ad. 0.025 +/-0009 < 0.015 04-06^17 451 0.013 +/-0003 < 0.013 10-04-17 523 0.025 10.003 < 0.007 04-12-17 537 0 015 +/-0.003 < 0.009 10-11-17 514 0.024 +/-0.003 <O.O10 04-19^17 594 0.018 10003 < 0.011 10-18*17 561 0.024 10.003 < 0.006 04-26-17 565 0.011 +/-0.003 << 0.007 10-25-17 583 0.040 10.003 < 0.006 0.013 10.003 < 0.003 11-01*17 540 0.016 +/-0.003 < 0.006 05-03-17 596 05-10-17 571 001310003 < 0.006 11-08-17 564 0.029 +/-0.003 < 0007 05-17^17 579 0.012 +/-0.003 < 0.006 11-15-17 574 0.033 10.003 < 0.008 05-24-17 560 0.017 +/-0003 < 0.008 11-22-17 536 0.028 +/- 0.003 < 0.007 05-31-17 633 0.013 +/-0.003 < 0.007 11-29-17 542 0.029 10.003 < 0,008 06-07-17 571 0,014 10.003 < 0.006 12-06-17 543 0.035 10.003 < 0.007 567 0.022 10.003 < 0.006 12-13-17 529 0.029 10.003 <0 0O6 06-14-17 06*21*17 545 002010.003 < 0.005 12-20-17 534 0.034 1 0 003 <0 006 06-26-17 544 0015 +/-0.003 < 0.007 12-27-17 544 0.026 +/-0.003 < 0.007 01-03-18 517 0.027 10.OQ3 < 0.007 2Q2017 Meanls.d. 0.015 10.003 < 0.013 4Q2017 Meanis.d. 0.029 10.006 < 0.010 Cumulative Average 0.024 2-4
PNPP Table 2. Airborne particulates and charcoal canisters, analyses tor gross beta and iodine-131.
Location: P-6 Units: pCi/ma Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (ma) Gross Beta 1-131 Collected (m*> Gross Beta 1-131 ReaLriredLLD 0,0075 0.050 0.0075 0050 01-04-17 559 0.022 +/-0.003 < 0.006 07-05-17 546 0.020 +/- 0.003 < 0.006 01-11-17 566 0.02410.003 < 0.005 07-13-17 628 0.03210.003 < 0.008 01-18-17 538 0.027 +/-0.003 < 0.007 07-19-17 460 0.027 +/- 0.004 < 0.008 01-26-17 546 0.017 +/-0.003 < 0.009 07-26-17 533 0.028 +/-0.003 < 0.003 02-01-17 542 0.024 +/-0.003 < 0.008 08-02-17 540 0.022 +/- 0.003 < 0.005 02-09.17 615 0.027 +/- 0.003 < 0.006 08-09-17 553 0.024 +/- 0.003 < 0.006 02-16-17 476 0,03010.004 < 0.007 08-16-17 528 0.036 +/- 0.004 < 0.013 02-22-17 537 0 024 +/-0.003 < 0.007 08-23-17 535 0.036 +/- 0.004 < 0.006 03-0M7 539 0.021 +/-0.003 < 0.006 08-30-17 538 0.018 +/-0.003 < 0.015 03-08-17 547 0.02310.003 < 0.011 09-06-17 534 0.O26 +/- 0.003 < 0.008 03-16-17 624 0.024 +/- 0.003 < 0.006 09-13-17 528 0.01510.003 < 0.007 03-22-17 466 0.020 +/-0.003 < 0.009 09-20-17 547 0.042 +/- 0.004 < 0.005 03-30-17 625 0.023 +/- 0.003 < 0.005 09-27-17 513 0.057 +/- 0.004 < 0.006 1Q2017 Meanis.d. 0.024 +/-0.003 < 0.011 3Q2017 Mean +/- s.d. 0.029 +/-0.011 < 0.015 04-05-17 458 0.016 +/-0.003 < 0.012 10-04-17 525 0.032 +/- 0.003 < 0.007 04-12-17 534 0.014 +/-0.003 < 0.009 10-11-17 491 0.033 +/-0.004 < O.010 04-19-17 557 0.023 +/-0.003 < 0.011 10-18-17 551 0.027 +/- 0.003 < 0.006 04-26-17 560 0.014 10.003 < 0.008 10-25-17 556 0.043 +/- 0.004 < 0.006 05-03-17 575 0.013 +/- 0.003 < 0.003 11-01-17 515 0.019 +/- 0.003 < 0.006 05-10-17 536 0.014 +/- 0.003 < 0.006 11-08-17 640 0.029 +/- 0.003 < 0.007 05-17-17 556 0.016 +/- 0.003 < 0.006 11-15-17 538 0.036 +/- 0.004 < 0.009 05-24-17 540 0.016 +/- 0.003 < 0.008 11-22-17 519 0.028 +/- 0.003 < 0.008 05-31-17 521 0.014 +/- 0.003 < 0.007 11-29-17 520 0.031 +/- 0.003 < 0.009 08-07-17 544 0.017 +/-0.003 < 0.006 12-06-17 516 0.036 +/- 0.004 < 0.007 06-14-17 560 0.026 +/- 0.003 < 0.006 12-13-17 490 0.031 +/- 0.004 < 0.006 06-21-17 540 0.028 +/- 0.003 < 0.005 12-20-17 485 0.039 +/- 0.004 < 0.007 06-28-17 536 0.018 10.003 < 0.007 12-27-17 498 0.027 10.003 < 0.008 01-03-18 463 0.034 +/- 0.004 < 0.008 2Q2017 Meanis.d. 0.018 +/-0.005 < 0.012 4Q2017 Mean+/-s.d. 0.032 +/-0,006 < 0.010 Cumulative Average 0.026 2-5
PNPP Table 2 Airborne paniculate* *>># charcoal canisters, analyses for gross beta and todlne-131 Location: P-7 Units: pCi/m3 Collection Continuous, weekly exchange.
Date Volume Date Volume Gross Beta M31 Collected (m*) Gross Bete M31 Reauired LLD 0.0075 0.0075 Q.050 525 0.024 +/-0.003 < 0.006 07-05-17 567 0.021 +/-0.003 < 0.007 01-04-17 0.026 +/-0.003 <0 005 07-13^17 677 0.028 +/-0.003 < 0.007 01-11-17 521 0M8-17 543 0.038 +/-0.004 < 0.007 07-19-17 494 0.025 +/- 0.003 < 0.007 01-26-17 535 0.016 +/-0003 < 0,009 07-26-17 533 0.027 +/-0,003 < 0.003 O2rO1-17 524 0.023 +/-0.003 < 0.008 08-02-17 544 0 025 +/- 0.003 < 0.005 02-09-17 595 0.024 +/-0.003 < 0006 08-09-17 544 0.027 +/-0.003 < 0.006 02-15-17 463 0.028 +/-0004 < 0.007 08-10-17 526 0.036 +/-0.004 < 0.013 02-22-17 511 0 027 +/-0 003 < 0.008 08-23-17 544 0.034 +/- 0.003 < 0.008 03-01-17 535 0022 +/-0.003 < 0.006 08-30-17 537 0021 +/- 0003 < 0.015 03-08-17 518 0,021 +/-0003 < 0.012 09-06-17 516 0.025 +/-0.003 < 0.008 03-16-17 599 0.023 +/-0 003 < 0,006 09-13-17 515 0.016 +/-0.003 < 0.007 450 0.027 +/-0 004 < 0.009 09-20-17 519 0.049 +/-0 004 <0005 03-22-17 0.021 +/- 0,003 < 0.005 06-27-17 509 0.058 +/-0.004 < 0.006 03-30-17 629 0.025 +/-0.005 <;0 012 3Q2017 Mean+/-s.d. 0.030 +/-0.012 < 0.015 1Q2017 Meants.d.
04-05-17 442 0.016 +/- 0.003 < 0013 10-04-17 535 0.040 +/- 0.004 < 0,007 04-12-17 529 0 013 +/-0-003 < 0.009 10-11-17 505 0.036 +/-0.004 < 0.010 04-19-17 546 0.019 +/- 0.003 < 0.012 10-18-17 534 0 023 +/-0.003 < 0.006 0.016 +/-0.003 << 0.008 10-25-17 508 0.035 +/-0.003 < 0.006 04-26-17 540 05-03-17 545 0.014 +/-0.003 < 0 003 11-01-17 526 0.015 +/- 0.003 < 0.006 05-10-17 520 0.020 +/- 0.003 < 0.007 11-08-17 539 0.024 +/-0 003 < 0.007 05-17-17 536 0-017 +/-0.003 < 0.006 11-15-17 559 0.032 +/-0.003 < 0.008 05.24-17 518 0.019 +/-0.003 < 0,009 11-22-17 517 0.026 +/- 0.003 < 0.008 05-31-17 515 0.013*0.003 < 0.007 11-29-17 547 0.031 +/- 0.003 <o.ooe 0.019 +/- 0.003 < 0.006 12-06-17 537 0.033 +/- 0.003 < 0.007 06-07-17 538 0,027 +/- 0.003 < 0.006 12-13-17 530 0024 +/-0.003 < 0.006 06-14-17 559 06-21-17 534 0.025 +/- 0.003 < 0.005 12-20-17 520 0.029 +/-0.003 < 0.006 06-28-17 552 0.018 +/-0.003 < 0,007 12-27-17 537 0.022 +/- 0.003 < 0.007 01-03-18 517 0.027 +/- 0.003 < 0.007 2Q2017 Mean+/-s.d. 0.018 +/-0.004- < 0.013 4Q2017 Mean+/-s.d. 0.028 +/-0.007 < 0.010 Cumulative Average 0.025 2-6
PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodrne-131.
Location: P-35
.3 Units: pCi/m!
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected Gross Beta M31 Collected Gross Beta M31 Reaurred LLC> 0.0075 0.050 0.0075 0050 01-04-17 554 0.022 +/- 0.003 < 0.014 07-05-17 562 0.016 10.003 < 0.011 01-11-17 549 0.026 +/- 0.003 < 0.011 07-13-17 650 0.023 10.003 < 0.014 01-18-17 569 0.026 +/- 0.003 < 0.006 07-19-17 484 0.020 10.003 < 0.016 01-26-17 540 0.016 10.003 < 0.013 07-26-17 562 0.022 1 0.003 < 0.006 02-01-17 559 0.020 10.003 < 0.008 08-02-17 554 0.016 1 D.003 < 0.013 02-09-17 623 0.024 10,003 < 0.011 08-09-17 567 0.02610.003 < 0.010 02-15-17 505 0.027 1 0.003 < 0.013 08-16-17 544 0.034 10.003 < 0.014 02-22-17 520 0.02510.003 < 0.010 08-23-17 551 0.033 10.003 < 0.011 03-01-17 573 0.021 10.003 < 0.013 08-30-17 552 0.016 10.003 < 0.006 03-08-17 550 0.021 10.003 < 0.012 09-06-17 535 0.02210.003 < 0.015 03-16-17 614 0.02210.003 < 0.005 09-13-17 548 0.018 10.003 < 0.012 03-22-17 464 0.024 10.004 < 0.011 09-20-17 565 0.036 10.003 < 0.012 03-30-17 646 0.023 +/-0.003 < 0.010 09-27-17 540 0.049 10.004 < 0.008 1Q2017 MeantB.d. 0.02310.003 < 0.014 3Q 2017 Mean +/- s.d. 0.026 10.010 < 0.016 04-05-17 466 0.011 10.003 < 0.012 10-04-17 554 0.025 10.003 < 0.012 04-12-17 555 0.011 10.003 < 0.011 10-11-17 543 0.025 1 0.003 < 0.017 04-19-17 550 0.020 10.003 < 0.009 10-18-17 570 0.023 10.003 < 0.009 04-26-17 583 0.012 10.003 < 0.008 10-25-17 596 0.034 10.003 < 0.011 05-03-17 573 0.010 i 0.003 < 0.011 11-01-17 535 0.017 +/-0.003 < 0.015 05-10-17 534 0.013 +/-0.003 < 0.013 11-08-17 584 0 023 +/-0.003 < 0.011 05-17-17 557 0.012 10.003 < 0.011 11-15-17 584 0.033 10.003 < 0.011 05-24-17 571 0.017 1 0.003 < 0.011 11-22-17 524 0.025 10.003 < 0.009 05-31-17 542 0.009 1 0.003 < 0.013 11-29-17 551 0.029 10.003 << 0.012 06-07-17 547 0.01310.003 < 0.007 12-06-17 568 0.031 1 0.003 < 0.010 06-14-17 564 0.02210.003 < 0.011 12-13-17 540 0.023 10.003 < 0.008 06-21-17 539 0.021 1 0.003 < 0.011 12-20-17 528 0.028 +/- 0.003 < 0.009 06-28-17 563 0.015 10.003 < 0.006 12-27-17 621 0 022 +/-0 003 < 0.010 01-03-16 460 0.027 1 0.004 < 0.018 2Q2017 Mean l s.d. 0.014 10.004 < 0.013 4Q2017 Mean 1 s.d. 0.026 10.005 < 0.018 Cumulative Average 0.022 2-7
PNPP Table 3. Airborne particulates, analyses for gamma-emitting isotope*
Collection: Quarterty Composite Unite: pCi/m3 Location PE-1 2ftdQtr. 3fdQtr 4th Qtr. Req. LLD Quarter 1stQtr.
PEAP- 1725 PEAP- 3720 IPEAP- 5595 PEAP- 6831 Lab Code 8057 Vol. (m*) 710? 7111 7460 0.071 +/- 0.010 0 075 +/- 0.010 0.071 +/- 0.009 00621 0.009 -
Be-7
< 0.0004 < 0,0003 < 0,0003 < 0.0004
~~Co-58~~
< 0.0004 < 0.0004 < 0.0005 -
Co-60 < 0.0004
< 0.0604 < 0.0004 < 0.0005 0.037 Cs-134 < 0.0003
< 0.0004 < 0.0003 < 0.0003 0.045 Cb-137 < 0.0004 Location PE-3 PEAP- 3721 PEAP- 5596 PEAP- 6832 Lab Code PEAP-1720 7862 8166 Vol. (m3) 7004 6245 0,072 +/- 0008 0.060 +/- 0.009 0.049 +/- 0.007 -
Be-7 0,068 +/- 0.010
< 0.0003 < 0.0005 < 0.0003 < 0.0002 -
Co-58
< 0.0002 < 0.0002 < 0.0003 < 0.0003 -
Co-60
< 0.0004 < 0.0003 < 0.0004 0.037 Cs-134 < 00005
< 0,0004 < 0.0002 < 0.0002 0.045 Cs-137 < 0.0000 Location PE-4 PEAP- 1727 PEAP-3722 PEAP- 5597 PEAP- 6833 Lab Code 7121 7930 Vol. (m3) 7121 7163 0 072+/- 0.008 0.074 +/- 0.012 0.066 +/- 0.009 0.065 +/- 0.011 -
Be-7
< 0.0003 < 0.0004 < 00004 < 0.0006 -
Co-58
< 0.0004 < 0.0002 < 0.0004 -
Co-60 < 0.0004
< 0.0O04 < 0.0006 < 0.0003 < 0.0006 0.037 Cs-134
< 0.0004 < 0.0004 0.045 Cs-137 < 0.0003 < 0.0007 Location PE-£ PEAP- 1729 PEAP- 3723 PEAP- 5598 PEAP- 6834 Lab Code 6993 7603 Vol. (ms) 7200 7212 0.070 +/- 0.009 0.069 i 0.008 0.057 +/- 0.007 -
Be-7 0.080 +/- 0.012
< 0,0004 < 0.0005 < 0.0003 -
Co-58 < 0.0005
< 0.0003 < 0.0002 < 0.0004 < 0.0003 -
Co-60
< 0.0003 < 0.0005 < 0 0004 0,037 Cs-134 < 0 0005
< 0.0003 < 0.0002 < 0.0004 0.045 Cs-137 < 0.0003 3-1
Table 3. Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/m*
Location PE-6 3rd Qtr. 4th Qtr. Req. LLD Quarter 1st Qtr. 2nd Qtr.
PEAP- 3724 PEAP- 5599 PEAP- 6835 Lab Code PEAP- 1730 6986 7207 Vol. (m3) 7179 7016 0.082 +/- 0.013 0.084 +/- 0.010 0.061 +/- 0009 -
Be-7 0.070 +/- 0.009
< 0,0002 < 0.0003 < 0.0005
~~Co-58 < 0.0005~~
< 0.0003 < 0.0003 < 0.0004 -
Co-60 < 0.0003
< 0.0003 < 0.0004 0.037 Cs-134 < 0.0005 < 0.0006
< 0.0003 < 0.0003 0.045 Cs-137 < 0.0005 < 0.0004 Location PE-7 PEAP- 3725 PEAP- 5600 PEAP- 6836 Lab Code PEAP- 1731 6875 7025 7460 Vol. (m3) 6947 0.083 +/- 0.011 0.081 +/- 0.013 0.051 +/- 0.007 -
Be-7 0.063 +/- 0.009
< 0.0005 < 0.0007 < 0.0005 -
Co-58 < 0.0005
< 0.0005 < 0.0005 < 0.0003 -
Co-60 < 0.0003
< 0.0006 < 0.0004 0.037
< 0.0005 < 0.0005 Cs-134
< 0.0006 < 0.0003 O.045 Cs-137 < 0.0004 < 0.0003 PE-35 Location PEAP- 3726 PEAP- 5601 PEAP- 6837 Lab Code PEAP- 1732 7143 7213 7759 Vol. (m9) 7268 0.062
~~0.011 0.069 1 0.009 0.054 +/- 0.009 -~~
Be-7 0.063 +/- 0.006
< 0.0004 < 0.0006 < 0.0002 -
Co-58 < 0.0004
< 0.0004 < 0.0004 < 0.0004 -
Co-60 < 0.0003
< 0.0004 < 0.0005 0.037 Cs-134 < 0.0003 < 0.0005
< 0.0004 < 0.0005 < 0,0004 0.045 Cs-137 < 0.0003 3-2
Table 4, Lake water, analyses foi gross beta and gamma emitting isotopes.. PNPP Location: P-34 Collection: Monthly composites Units: pCi/L Lab Code PELW- 406 PELW- 785 PELW- 1306 PELW- 1902 Start Date 12-29-16 01-26-17 02-23*17 03-30-17 Req. LLD End Date 01-26-17 02-23-17 03-30-17 04^27-17 Gross beta 2.0 +/- 0 8 1.3 +/-07 2.1 +/- QJ 2.3 +/- 0.6 3.0 Mn-54 <3.2 <2.9 <2.4 < 3,0 11 Fe-S9 <3.1 <4.B <45 <8.2 22 00^8 < 1.8 <2.9 < 2.5 <3,1 11 Co-60
SL2 <2.1 < 1.8 < 2.5 11 Zn-65 < 5,7 <17 <2.0 < 6.9 22 2r-95 <6.4 < 5.1 <4.2 <2.5 22 Nb-95 <<3.8 <2.t < 32 < 2.6 11 Cb-134 <3.7 <34 < 2.8 < 3.3 11 C*-137 <<2.0 <3.4 <2.8 < 31 13 Ba-140 < 19.8 < 15.2 < 20.3 <24.0 45 La-140 <4.4 <3,2 <Z5 < 5.4 11 Lab Code PELW- 2609 PELW- 3277 PELW- 3965 PELW-4484 Start Date 04-27-17 05.26-17 06-28-17 07-24-17 Req. LLD End Date 05-26-17 06-29-17 07-24-17 08-31-17 Gross beta 11
0.5 1.4 +/- 0,6 < 0,9 1.1 +/- 0.6 3.0 Mn-54 < 15 < 2.3 <4.1 <2.9 11 Fe-59 <4.9 <3.4 <88 <5.8 22 Co-58 <<2.7 < 1.7 < 2.6 <2.9 11 Co-60 < 14 < 2.6 < 2.5 <2.3 11 Zn-65 <3J <2.1 < 3,4 < 2.6 22 Zr-95 < 3.2 < 28 < 5.0 < 5,5 22 Nb-95 <ZA < 19 <4.8 < 3.0 11 Cs-134 <2.S < 2,6 < 3.5 < 3.6 11 C*-f97 <2.3 < 3.3 <48 < 2.9 13 Ba-140 < 34.2 <239 < 38.5 < 20.4 45 La-140 <4.0 <3.2 <4.5 <6.2 11 Lab Code PELW- 5145 PELW- 5740 PELW- 6326 PELW- 6650 Start Date 08-31-17 09-28-17 10-26-17 11-30-17 Req. LLD End Date 09-28-17 10-26-17 11-30-17 12-28-17 Gross beta 1.5 4 0.6 1.0 i 0.5 1.8 +/- 0.6 1.6 +/- 0.6 3,0 Mn-54 < 2.7 <4.3 < 1,7 < 2.0 11 Fe-59 < 3.6 <4.4 <2.8 < 3.9 22 Co-58 < 2.1 <2.1 < 1.5 <4.0 11 Cp-60 <2.2 < 1.3 < 2.9 <2.9 11 Zn-65 <<6.1 <6.3 <4.0 < 6.6 22 Zr-95 <27 < 5.8 <4.4 < 5.9 22 Nb-95 <3.1 <2.6 <2.3 <27 11 C8-134 < 3.1 <3.0 <2.9 <4.3 11 Cs-137 < 3.4 <2.0 <2.8 < 3.3 13 Ba-140 < 22,4 < 16,3 < 11.7 < 25.9 45 La-140 < 3.3 < 3,0 < 3.3 <4.6 11
PNPP I able 4. Lake waiei, analyses Ioj gioss uela and gamma emitting isoiopes Location: P-36 Collection: Monthly composites Units: pCM-PELW- 407 PELW- 786 PELW- 1307 PELW- 1903 Lab Code 01-26-17 02-23-17 03-30-17 Req.LLD Start Date 12-29-16 01-26-17 02-23-17 03-30-17 04-27-17 End Date 1.3 +/-0.7 1.9 +/- 0.7 1.31 0.5 3.0 Gross beta 2.5
~~0.7~~
~~< 1.8~~
~~2.1 < 2.5 11 Mn-54 < 1.7~~
< 2.2 <4.9 < 4.2 22 Fe-59 < 7.3
< 2.2 < 3.1 < 3.2 11 Co-58 < 1.8
< 2.2 < 2.1 11 Co-60 < 2.1 <2.2
< 5.1 <4.0 < 3.1 22 Zn-65 < 3.6
< 3.8 <4.3 <4.2 22 Zr-95 < 3.5
<2.5 < 3.1 < 2.4 11 Nb-95 <2.9
<2.8 < 3.0 < 3.0 11 Cs-134 <3.0
< 3.1 < 2.2 < 2.0 <2.3 13 Cs-137
< 13.6 < 16,4 < 27.8 45 Ba-140 < 24.2
<22 < 3.0 11 La-140 <4.0 < 2.0 PELW- 2700 PELW- 3278 PELW- 3968 PELW- 4485 Lab Code 05-26-17 06-29-17 07-24-17 Req. LLD Start Date 04-27-17 05-26-17 06-29-17 07-24-17 08-31-17 Bid Date 1.2 +/- 0.5 1.3 1 0.6 < 0.8 3.0 Gross beta 0.9 +/- 0.5
< 2.1 < 4.3 < 2.2 11 Mn-54 < 2.0
< 2.6 < 5.7 < 3.5 22 Fe-59 <4.9
< 1.7 <2.5 < 1.9 11 Co-58 < 2.3
< 4.3 < 2.7 11 Co-60 < 1.9 < 1.2
~~3.6 < 3.7 < 1.8 22 Zn-65 < 1.9~~
< 3.9 < 7.7 < 3.9 22 Zr-S5 <3.8
< 4.0 < 3.0 < 2.7 11 Nb-95 < 3.9
<2.7 < 2.9 < 4.2 < 2J 11 Cs-134
< 3.0 < 1.7 < 3.2 < 1.6 13 Cs-137
< 29.1 < 19.2 < 23.1 45 Ba-140 < 43.5
< 3.4 <4.7 < 2.2 11 La-140 < 6.7 PELW- 5147 PELW- 5741 PELW-6326 PELW- 6651 Lab Code 09-28-17 10-26-17 11-30-17 Req.LLD Start Date 08-31-17 09-26-17 10-26-17 11-30-17 12-26-17 End Date 1.2 +/- 0.6 1.1 +/- 0.5 1.0*0.5 3.0 Gross beta 1.5 +/- 0.6
< 2.3 < 2.8 < 3.1 11 Mn-54 < 1.7
< 4.6 < 5.1 < 3.3 22 Fe-59 << 3.9
< 4.1 <2.8 11 Co-58 < 2.2 < 1.6
< 2.8 < 1.8 11 Co-60 < 2.1 < 2.1
< 3.2 < 2.3 22 Zn-65 < 4.4 < 3.9
< 5.8 < 6.0 < 5,9 22 Zr-95 < 6.3
< 3.6 < 3.0 < 3.3 11 Nb-95 <4.0
< 3.6 < 32 < 2,8 11 Cs-134 < 2.7
< 3.6 < 2.9 < 3.8 13 Cs-137 < 2.6
< 18.0 <22.1 < 23.9 45 Ba-140 < 25.6
< 3.1 < 3.6 < 2.8 11 La-140 < 5.6 4-2
PNpp Table 4. Lake water, analyses foi gross bete and gamma emitting isotopes.
Location: P-39 CoUedion; Monthly composites Units: pCi/L Lab Code PELW- 408 PELW- 787 PELW- 1308 PELW- 1904 Start bate 12-29-16 01-26-17 02-23,17 03-3CM7 Req. LLD End Date 01*26-17 02-23-17 03-30-17 04-27-17 Gross beta < 13 18*0.7 1,6 +/- 0,7 13 +/- 0,5 30 Mn-54 << 2.4 < 1.9 < 13 <28 11 Fe-59 < 3.7 <4.0 < 5.1 <4.6 22 Co*8 <2.7 < 2.7 < 16 <2.0 11 Co-60 < 1,2 < 2.6 < 17 <2.2 11 Zn-65 <3.9 <2.3 <2.3 << 18 22 2r-95 <4.4 <<46 <3.4 < 18 22 Nb-&5 < 1.8 < 2.7 < 2.5 <Z2 11 Cs-134 < 3.3 < 3.3 <2.1 <2.5 11 C<<-137 <3.6 <2.3 < 21 <3.4 13 Ba-140 <<? 19.3 <21,2 < 17.2 <212 45 ta-140 <20 <3.9 <2.2 <6.4 11 Lab Code PELW- 2701 PELW- 3279 PELW- 3967 PELW- 4486 Start Date 04-27-17 05-26-17 0&-2&-17 07-24-17 Req. LLD End Pate 05-26-17 06-29-17 07^24-17 08-31-17 Gross beta 1-2 +/- 0.6 <0.9 < 0.9 14 +/- 0.6 3.0 Mn-54 <2.1 <2.3 < 3,2 < 3.1 11 Fe-59 <6,0 <4,8 < 7.4 <6-7 22 Co-58 < 2.8 <2.2 <3.0 <3.3 11 Co-60 <2.1 < U < 3.0 <3.0 11 Zn-65 <53 <2.8 <28 <6.0 22 Zr-95 <3,2 < 5.1 <6.6 <5.1 22 Nb-95 <4.1 <2.4 < 5.1 <3.0 11 C8-134 <2.8 < 2.4 <<4.2 <3.4 11 Cs-137 <2,7 < 2.0 < 5,7 <2;0 13 Ba-140 <29.5 <23.2 < 25.4 < 17.6 45 ta-140 <7.6 <2.0 < 3.6 < 14 11 Lab Code PELW- 5148 PELW- 5742 PELW- 6327 PELW- 6652 start pate 08-3M7 09-28-17 10-26-17 11-30-17 Req. LLD End Date 09-28-17 10-26-17 11-30-17 12-28-17 Gross bete 1.3
0.5 < 0.9 < 0.9 13 +/- 0.6 3.0 Mn-54 <2.0 < 1.9 < 2.6 < 2.1 11 Fe-59 < 7.6 <5,0 < 4.9 <3.6 22 Co-58 < 4.0 < 1.4 < 2.6 < 3.0 11 Co-60 <3.7 <2.0 < 2.7 <2.2 11 Zn-65 < 4,3 <3.3 < 5.5 <2.7 22 Zr-95 <e.o <4.7 < 5.7 < 5.4 22 Nb-95 <2.9 < 3.9 < 3.7 <2A 11 Cs-134 < 3.7 < 3.1 < 3,2 < 2.7 11 Cs-137 <4.4 < 3.7 <2.2 <22 13 Ba-140 <29.9 < 17.0 < 172 < 18.1 45 La-140 < 5.0 <4.2 < 2.9 <3.6 11 4-3
PNP Table 4 Lake watei, analyses for gioss, beta and gamma emitting isolopes.
Location: P-59 Coftection: Monthly composites Units: pCi/L Lab Code NS' PELW- 760 PELW- 1309 PELW- 1905 Start Date 01-26-17 02-23-17 03-30-17 Req. LLD End Date 02-23-17 03-30-17 04-27-17 Gross beta 2.4 +/- 0.7 2.1 +/- 0.7 1.8 +/- 0.6 3.0 Mn-54 < 2.4
2.1 <2.9 11 Fe-59 < 5.3 <2.1 <6.8 22 Co-58 < 2.0 <2.2 <2.5 11 Co-60 <2.9 < 1.7 < 2.4 11 Zfi-65 < 2.9 < 3.9 < 4.4 22 Zr-95 < 2.4 < 4.1 <4.2 22 Nb-96 < 3.3 < 1.9 < 3.9 11 Cs-134 <2.0 < 2.0 < 3.5 11 Cs-137 -
<2.0 <2.1 < 2.5 13 Ba-140 < 23.1 < 16,2 < 23.3 45 La-140 - <4.8 <2.8 < 3.4 11 Lab Code PELW- 2702 PELW- 3280 PELW-3968 PELW- 4488 Start Date 04-27-17 05-26-17 06-29-17 07-24-17 Req. LLD End Date 06-26-17 06-29-17 07-24-17 08-31-17 Gross beta <0.9 1.0 +/- 0.5 < 0.9 1.5 +/- 0.6 3.0 Mn-54 < 2.3 < 1.9 < 3.7 < 3.0 11 Fe-59 < 6.4 <2.7 < 9.4 <4.1 22 Co-58 < 1.4 < 1.7 <4.5 < 1.6 11 Co-60 < 2.0 < 1.9 <2.4 < 3.0 11 Zn-65 < 3.7 <4.1 <5.3 < 4.3 22 Zr45 < 5.3 < 2.4 < 6.6 < 5.1 22 Nb-95 < 3.3 <3.1 <4.3 < 3.4 11 Cs-134 < 2.6 <2.7 < 3-9 < 3,1 11 Cs-137 < 2.3 < 1.8 < 2.6 < 2.9 13 Ba-140 < 38.4 < 185 < 34.6 < 180 45 La-140 < 9.0 < 4.2 < 3.5 < 3.1 11 Lab Code PELW- 5149 PELW- 5743 PELW- 6328 PELW- 6653 Start Date 08-31-17 09-28-17 10-26-17 11-30-17 Req. LLD End Date 09-28-17 10-26-17 11-30-17 12-28-17 Gross beta 1.2 +/- 0.6 1.3 +/- 0.6 1,4 +/- 0.6 1.1 +/- 0.5 3.0 Mn-54 < 2.1 < 3.1 < 2.1 < 2.2 11 Fe-59 < 5.0
~~4.8 < 3.1 <4.7 22~~
< 2.8 < 2.0 < 2.2 < 19 11 Co-58 Co-60 < 1.3 < 3.2 < 1.9 < 2.1 11 Zn-65 < 3.0 < 3.8 < 3.0 < 2.2 22 Zr-95 < 4.9 < 7.6 < 4.1 < 2.7 22
<4.1 <4.9 < 4.5 < 3.4 11 Nb-95 Cs-134 < 2.5 < 4.0 < 3.4 < 2.5 11 Cs-137 < 1.9 < 3.8 <2.7 < 2.6 13 Ba-t40 < 16.6 < 22.5 < 18.7 < 19.9 45 U-140 < 5.1 < 2.4 < 4.0 <4.2 11 "mo" > No dele; see Table 2,0, Listing of Missed Samples 4-4
PNPP Tablfc 4. Lake vvdlti, aiKiiybfcjS foi bfcta and yaiiima eniiiiitiy Location: P-60 Collection: Monthly composites Units: pCi/L Lab Code PELW- 789 PLW- 1310 PELW- 1906 Start Date 01-28-17 02-2^-17 03^0-17 Req. LLD Bid Date 02-23-17 03-30-17 04-27-17 Gros&beta - 2 3 i 0.8 2.7 +/- 0.8 1.7 +/-0.6 30 Mn-54 -
< 1.7 < 2.6 < 2.9 11 F©-59 -
<5.4 < 8$ < 5.9 22 Co-58 -
< 1.9 <2.7 < 3.3 11 Cd*60 <2.8 < 1.9 <3.5 11 Zn-eS <4.3 < 3.2 <5.8 22 Zr-95 -
<5.1 < 5.6 < 6.1 22 Nb-©5 -
< 3.4 < 1.9 <4.3 11 Ci-134 <2$ <2.7 <3.5 11 C<<-137 -
<2.5 <2.8 < 40 13 Ba-140 -
< 17.3 <283 < 39.1 45 La-140 - <<3.7 <2.6 < 3.8 11 Lab Code PELW- 2703 PELW- 3281 PELW- 3969 PELW- 4489 Start Date 04-27-17 05-26-17 06-29-17 07^4*17 Req. LLO End Date 05-26-17 Oe-29-17 07-24-1? 0*31-17 Gross beta <d.e 1 2 +/- 06 1.4 +/- 0.6 1.3 +/- 06 3.0 Mn-54 < 23 < 1,9 <4,1 < 3.4 11 Fe-59 <4.4 <04 < 7,1 <4.6 22 CO-58 < 2.1 < 1.9 <3.2 <2.1 11 Co-60 < 1.6 < 1.1 <2.0 <24 11 Zft-65 < 19 < 2.7 <4.3 <35 22 Zr-95 <4.2 < 5.1 <7.5 <6.6 22 Nb-96 <3.2 < 3.1 < 4.4 <3-2 11 C$-134 < 2.0 < 20 < 3.2 <3.4 11 Cs-137 < 2.3 <ZA <2,5 <3.3 13 Ba-140 < 32.5 < 43,6 < 25.3 c 24.7 45 La-140 <5.5 < 10.7 < 4.6 <2.7 11 Lab Code PELW, 5150 PELW- 5744 PELW- 6329 PELW- 6654 Start Date 08-31-17 09-28-17 10-26-17 11-30-17 Req. LLD End Date 09-28-17 10-26-17 11-30-17 12-28-17 Gross beta 2.2 +/- 0.6 1.2 +/- 0.6 2.0 +/- 0.6 1.7 +/- 0.6 3.0 Mn-54 < 1.8 <2.8 < 1.5 <3.3 11 Fe-59 < 5.0 <4,8 < 4.4 <4.8 22 Co-58 < 1.9 < 2.3 < 2.7 < 3.2 11 Co-80 <2.4 < 0.8 < 2-4 < 2.6 11 Zn-65 < 3,2 < 3.4 < 4.7 < 6.5 22 Zr-95 <4.2 < 5.5 < 3.7 <4.6 22 Nb-95 < 3,5 < 3.2 < 3,6 <4.2 11 Cs-134 < 2.7 <2.7 < 2.9 < 3.9 11 Gs-137 <2.7 < 2.2 < 3.1 << 3.2 13 Ba-14G < 24.9 < 17.8 < 19,3 <29.6 45 La-140 <3.3 < 3.9 < 2.5 < 7.7 11
~~"NO" = No data; see Table 2.0, Listing of Missed Ssmples.~~
4-5
PNPP Table 4. Lake Water, analysts for trnium.
Collection: Quarterly composites of monthly collection*.
Units: pCi/L Required Hmtt of detection; Location P-34 Period "IstQtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Lab Code PaW- 1332 PELW- 3408 PELW- 5523 PELW- 6696 H-3 < 150 < 149 < 157 < 152 Location P-36 Period IstQtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Lab Code PELW- 1333 PELW- 3409 PELW- 5524 PELW- B700 H-3 < 150 < 149 < 157 <152 Location P-39 Period IstQtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Lab Code PELW- 1334 PELW- 3410 PELW- 5525 PELW- 6701 H-3 < 150 < 149 < 157 < 152 Location P-59 Period IstQtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Lab Code PELW-1338 PELW- 3411 PELW- 5526 PELW- 6702 H-3 < 160 < 149 < 157 < 152 Location P-60 Period IstQtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Lab Code PELW- 1337 PELW- 3412 PELW- 5527 PELW- 6703 H-3 < 150 < 149 < 157 < 152 4-6
PNPP Table 5. Milk, analyses for kxJine-131 and gamma-emitting Isotopes, Collection Semimonthly during grazing season, monthly at otfier times.
Collection Lab Concentration (pCi/L)
Date Code 1-131 Cs-134 Cs-137 Ba-140 La-140 K-40 Required LLD (pCi/L) 0.8 11 13 45 11 01-03-17 PEMI- 35 <0J2 <3.6 <3*6 <34,4 <4 6 1477 +/-117 02-06-17 PEMI- 625 <02 <42 <<4.0 < 20,6 <4.6 1196 +/-109 03-06-17 PEMI- 923 <0.2 <2.8 <2.8 <17.0 <3.0 1191 +/-93 04-03-17 PEMI-1366 <0.2 <32 <3.7 <214 <1,6 1267 +/-103 04-17-17 PEMI- 1733 <03 <3.4 <2 9 <250 <37 1308 +/-109 05-01-17 PEMI-1931 <0.3 <3.e <19 <23.2 <3.6 1190 +/-94 05-15-17 PEMI' 2246 <0.4 <3.2 <3.9 <27.9 <3,5 1247 +/-101 064)5-17 PEMI-2745 ^0.3 <3.8 <2.5 < 144 <1.9 1286 +/-115 06-20-17 PEMI- 3063 <03 <42 <3.7 *192 <3JZ 2017 +/-131 07-05-17 PEMI- 3275 <0.4 <3.0 <2J0 < 139 <1.0 1296 +/-93 07-17-17 PEMI- 3579 <0.3 <2>6 <3.4 <34J <4.3 1356 +/-75 08-08-17 PEMI- 4047 <0.4 <1.3 <1.6 <13.6 <A2 1197 +/-42 08.21-17 PEMI- 4340 <0.5 <2M <2.9 <28.3 <3.9 1345 +/-98 09-08-17 PEMI- 4642 <0,3 <4.0 <3.1 <17.9 <3.2 1274 +/-116 09-20-17 PEMI- 4878 <03 *?3.0 <3.2 <25.5 <4.4 1367 +/-97 10-02-17 PEMI-5113 <0.3 <39 <27 <20.6 <3.2 2317 +/- 137 10-16-17 PEMI- 5613 <03 <3,3 <3.$ <15.9 <5.5 2067 +/-121 11-06-17 PEMI- 5935 <QJ3 <4.8 <3.5 <20.9 <3.4 2546 +/-152 12*04-17 PEMI- 6323 <02 <3.0 <3.5 < 11.8 <1.6 1359 +/-94 01-03-17 PEMI- 36 <0.2 <3.0 <2.9 <24^ <4.8 1367 +/-104 02-06-17 PEMI- 526 <0.2 <3.1 <3.7 < 16.9 <3.4 1391 +/-98 03-06-17 PEMI- 924 <0.5 <29 <3.3 <175 <2,9 1388 +/-98 04^3-17 PEMI- 1367 <0.2 <3.1 <3.3 <17.4 <28 1383 +/-115 04-17-17 PEMI- 1734 <0.3 <3.3 <2.1 <28,9 <4.1 1394 +/-103 05-01-17 PEMI- 1932 <0.4 <3.1 <2M <24.3 <3^ 1312 +/-99 05-15-17 PEMI- 2247 <0.4 <25 <3.0 < 19,0 <5,3 1341 +/-108 06-05-17 PEMI- 2746 <0.3 <3.3 <1.7 < 16.0 <1.0 1491 +/-117 06-20-17 PEMI- 3064 <0.3 <4.8 <4.4 <23,9 <6^ 1466 +/- 134 07-05-17 PEMI- 3276 <0.5 <3.3 <3.4 -:14.3 <3.1 1394 +/-101 07-17-17 PEMI- 3580 <0.4 <2,7 <2.8 <20.7 <A2. 1336 +/- 75 08-08-17 PEMI- 4048 <0.5 <1.3 <1.4 <270 < 3,3 1344 +/- 46 08-21-17 PEMI- 4341 <0.4 <3.2 <4.0 <38.5 <3.8 1345 +/-106 09-08-17 PEMI- 4643 *0.2 <3.5 <2.8 <11.4 <1.6 1402 +/-114 09-20-17 PEMI- 4879 <04 <3.2 <3.8 < 19.3 <6.9 1312 +/- 108 10-02-17 PEMI-6114 <<0.4 <2.8 <2.4 <15.5 <4.5 1250 +/-102 10-16-17 PEMI- 5614 <0.4 <3.3 <4.2 <27.9 <4.5 1331 +/-107 11-06-17 PEMI- 5936 <0.4 <4.0 <3.6 < 21.6 <3.6 1354 +/-118 12-04-17 PEMI- 6324 <0.3 <3.2 <3.9 <10.6 <1.9 1306 +/-104 5-1
Table 7. Food Products, analyses for gamma emitting isotopes.
Collection : Monthly Units: pCi/kg wet Location: P-2 Lab Code PEVE- 3661 PEVE- 3582 PEVE- 3583 PEVE- 4243 Date Collected 07-18-17 07-18-17 07-18-17 08-15-17 Req. LLD Sample Type Japanese greens Swiss chard Tump greens Japanese Greens Be-7 228 +/- 101.70 407 dk 102 323 +/-91 777 +/- 116 -
K-40 3392 +/- 266.60 5247 +/- 366 4012 +/-300 5755 +/- 365 -
Co-58 < 5.80 < 11.6 <5.6 <9.2 -
Co-60 < B.44 <7.8 < 8.9 < 9.7 -
1-131 < 21.46 <27.3 < 13.0 <29.7 45 Cs-134 < 9.00 < 13.5 < 8.5 <8.8 45 Cs-137 <6.19 < 13.8 < 7.0 < 11.9 60 Lab Code PEVE- 4244 PEVE- 4245 PEVE- 4246 PEVE- 4902 Dale Collected 08-15-17 08-15-17 08-15-17 09-20-17 Req. LLD Sample Type Swiss Chard Turnip Greens Collard Greens Swiss Chard Be-7 566 +/- 125 576 +/- 120 123 +/-70 245 +/- 105 K-40 5411 +/- 340 4271 +/- 335 3788 +/-225 4660 +/- 302 -
Co-58 < 10.6 < 7.7 <7.1 < 7.8 -
Co-60 < 10.1 < 7.4 < 5.7
~~9.9 -~~
1-131 <24.5 < 22.1 <21.7 < 23.8 45 Cs-134 < 10.0 < 9.5 < 6.7 < 8.6 45 Cs-137 < 10.3 < 11.0 <6.3 <8.5 60 Lab Code PEVE- 4903 PEVE-4904 PEVE-6623 PEVE- 5624 Date Collected 09-20-17 09-20-17 10-17-17 10-17-17 Req. LLD Sample Type Turnip Greens Collard Greens Collard Greens Turnip Greens Be-7 247 +/- 88 454 +/- 132 971 +/- 185 825 +/- 127 -
K-40 4671 +/- 373 5908 +/- 401 4038 +/- 391 4550 +/- 312 -
Co-58 < 10.4 < 10.2 < 13.0 < 7.6 Co-60 < 8.2 < 9.1 < 10.7 < 8.6 -
H31 <41.7 < 40.7 < 22.8 < 8.7 45 Cs-134 < 9.9 < 12.4 < 12.3 < 9.3 45 CS-137 < 11.5 < 9.5 < 7.2 < 6.9 60 7-1
PNPP Table 7. Food Products, analyses for gamma emitting isotopes.
CoHection: Monthly Units1 pCi/kgwet Location: P-16 Lab Code PEVE-3584 PEVE- 3585 PEVE* 3586 PEVE-4248 Date Collected 07-18-17 07-18-17 07-18-17 08-15-17 Req. LLD Sample Type Japanese greens Coflard greens Turnip greens Coflard Greene Be-7 166 +/-66 <86 121 +/- 58 < 54 K-40 2709 4 221 3795 +/- 244 3181 +/- 245 2742 +/- 239 -
Co-58 <7.0 <9.9 <6.3 <5.4 -
Co-60 <5.5 <61 < 5.7 <5.7 -
1-131 <<172 <24.7 <22,6 < 18.5 45 Cs-134 < 6,4 <7.8 < 7.6 <7.0 45 Cs-137 <7.1 <6.0 <6.7 < 6.5 60 Lab Code PEVE-4249 PEVE- 4250 PEVE- 4251 PEVE-4905 Pate Collected 08-15-17 08-15-17 08-15-17 09-20-17 Req. LLO Sample Type Turnip Greens Japanese Greens Swiss Chard CoJard Greens Be-7 200 +/-73 249 +/-87 327 +/- 97 <77 K-40 3105 +/- 241 2979 +/- 225 4373 +/- 245 3063 +/- 229 -
Co-58 < 59 <7,3 < 7 3 < 7.6 Co-60 <e.o <63 <7.0 <4,7 -
M31 < 15.1 < 17.6 <30.3 <26.9 45 C3-134 <6.7 <6.3 <6.7 <73 45 Cs-137 <6.8 <50 <6.5 <6.6 80 Lab Code PEVE- 4906 PEVE- 4907 PEVE- 4909 PEVE- 5625 Date Collected 09-20-17 09-2047 09-20*17 10-1747 Req. LLD Sample Type Turnip Greens Japanese Greens Swiss Chard CoJIard Greens Be-7 <99 <97 146 +/- 85 361 +/- 106 K-40 3138 +/- 255 4280 +/- 315 4525 +/- 267 3524 +/-264 Co-58 < 52 <66 < 7.2 <7.1 -
Co-60 <5.9 <9,5 < 7 5 <6.2 -
1-131 < 22 6 <29.0 < 261 <26.9 45 Cs-134 < 8.2 < 9.1 <6.5 < 7.8 45 Cs-137 <6.5 < 5,4 < 6.6 <5.7 60 Lab Code PEVE- 5626 Date Collected 10-17-17 Sample Type Turnip Greens Be-7 433 t 87 K40 4279 +/- 270 Co-58 < 7.2 Co-60 < 7.7 1-131 << 13.7 Cs-134 < 6.6 Cs-137 < 7.3 7-2
PNPP Table 7. Food Products, analyses for gamma emitting isotopes.
Collection; Monthly Units: pCi/kgwet Location: P-20 Lab Code PEVE- 3587 PEVE- 3588 PEVE-3589 PEVE- 4252 Date Collected 07-18-17 07-18-17 07-18-17 08-15-17 Req. LLD Sample Type Japanese greens Turnip greens Coflard greens Japanese Greens Be-7 429 +/- 126 548 +/- 107 < 92 805 1 164 K-40 4392 +/-307 5668 +/- 316 4642 +/- 333 7639 +/- 443 Co-58 <6.B < 7.5 < 9.6 < 12.8 -
Co-60 < 5.6 <6.7 < 7.5 < 12.4 1-131 <27.9 < 23.0 <23.9 <42.1 45 Cs-134 < 9.3 < 8.3 < 10.0 < 12.4 45 Cs-137 <8.2 < 9.4 << 9.4 < 7.6 60 Lab Code PEVE- 4253 PEVE- 4254 PEVE-4255 PEVE- 4910 Date Collected 08-15-17 08-15-17 08-15-17 09-20-17 Req. LLD Sample Type Col lard Greens Swiss Chard Turnip Greens Coilard Greens Be-7 <eo 618 +/- 133 585 +/- 107 < 135 -
K-40 3681 +/- 203 6921 +/- 420 4976 +/- 305 4498 +/- 338 -
Co-58 <5.5 < 9.9 < 9.6 < 12.1 -
Co-60 <4.4 <6.3 < 7.0 <9.1 -
M31 <23,0 < 33.4 < 37.7 <36.4 45 Cs-134 < 6.2 < 10.0 < 7.9 < 11.4 45 Cs-137 < 4.9 < 10.7 < 5.0 < 11.8 60 Lab Code PEVE-4911 PEVE- 4912 PEVE-5627 PEVE- 5628 Date Collected 09-20-17 09-20-17 10-17-17 10-17-17 Req. LLD Sample Type Swiss Chard Turnip Greens Colard Greens Turnip Greens Be-7 777 +/- 124 204 +/- 97 194 +/- 70 472 +/- 79 K-40 9060 +/- 311 4878 +/- 276 5478 +/- 291 5151 +/- 265 -
Co-58 < 7.6 < 7.7 < 7.1 < 7.4 -
Co-60 < 11.1 <4.8 <4.1 <8.0 -
1-131 < 29.2 < 23.7 < 11.7 < 13.5 45 Cs-134 <8.0 < 7.6 < 6.6 < 6.2 45 Cs-137 < 7,2 < 7.9 < 8.3 < 6.3 60 7-3
PNPP Table 7, Food Products, analyses for gamma emitting isotopes.
Collection: Monthly Unite: pCi/kgwet Location: P-37 Lab Code PEVE- 3591 PEVE-3592 PiVE- 3593 PEVE-3594 Date Collected 07-18-17 07-18-17 07-18-17 07-18-17 Req. U.D Sample Type Japanese greens Swiss chard Turnip greens Collard greens Be-7 223 +/- 88 262 +/- 146 <92 115 +/-45 K-40 5994 +/- 293 5668 4 340 3042 +/- 250 3730
~~201 -~~
~~Co-58 < 8.8 < 7 3 < 6.2~~
~~5.9 -~~
co^eo < 5.2 <8.7 < 3,6 -
1-131 < 24 5 < 39 5 < 28.1 < 23.6 45 Cs-134 < 79 <9.1 <7.3 <5.9 45 Cs-137 < 7.1 < 10 7 < ia3 <8.3 60 Lab Code PEVE- 4258 PEVE- 4257 PEVE- 4258 PEVE' 4259 Date Collected 08-15-17 08-15-17 08-16-17 08-15-17 Req.LLD Sample Type CoHard Greens Japanese Greens Swfes Chard Turnip Greens Be-7 < 83 217 +/- 82 289 +/- 90 303 +/- 101 -
K-40 4764 +/- 324 3472 +/- 252 5084 i 255 5908 +/-342 -
Co-58 <6,1 <6.4 <7.9 < 78 COh0O < 42 <4.8 <5,2 < 4.9 -
M31 < 41.2 < 21.9 < 23,0 < 35.5 45 Cs-134 < 9.0 <6.0 <6.5 < 7.4 45 C*437 < 9.4 <7.0 <6.4 <72 60 Lab Code PEVE- 4913 PEVE-4914 PEVE- 4915 PEVE- 5628 Date Collected 09-20-17 09-20-17 09-20-17 10-17-17 Req. LLD Sample Type Collard Greens Swiss Chard Turnip Greens Colard Greens Be-7 < 102 172 +/- 100 <92 211 +/- 68 -
K-40 4002 +/- 312 5140 +/- 304 4551 +/-294 3908 +/- 245 Co-58 < 10.4 <5,3 < 10.8 <3.7 -
Oo*60 < 118 < 5.8 < 7,9 <5.5 -
1-131 < 42.9 < 27.1 < 40.2 < 157 45 Cs-134 < 96 <8.2 < 8.2 < 6.7 45 Cs-137 < 7-1 <7.1 < 10.0 <6.3 60 Lab Code PEVE- 5630 PEVE- 5631 Date Collected 10-17-17 10-17-17 Sample Type Turnip Greens Swiss Chard Be-7 515 +/- 124 280 t 102 K-40 4601 +/- 318 6398 +/- 371 Co-58 < 9.3 <4.8 Co-60 < 6,8 < 6.3 1-131 < 19.5 < 17.7 Cs-134 < 9.4 < 10.0 Cs-137 << 11.7 <9.6 7-4
PNPP Table 7. Food Products, analyses for gamma emitting isotopes.
Collection: Monthly Units: pCi/kg wet Location: P-70 Lab Code PEVE- 3596 PEVE- 3596 PEVE-3597 PEVE- 3598 Date Collected 07-1B-17 07-18-17 07-18-17 07-16-17 Req.LLD Sample Type Collafd greens Turnip greens Japanese greens Swiss chard Be-7 < 55 444 +/- 114 < 59 427 +/- 116 K-40 4655 +/- 239 6397 +/- 371 3969 1299 5191 +/- 287 -
Co-58 << 7.3 < 8.3 <6.8 < 9.6 -
Co-60 < 8.5 <6.1 <6.6 < 5.3 -
H31 < 16.8 < 37.0 < 18.6 <29.9 45 Cs-134 < 6.8 < 9.2 < 5.4 < 8.3 45 Cs-137 < 7.4 < 11.2 <6.6 < 4.5 60 Lab Code PEVE- 4260 PEVE- 4261 PEVE- 4262 PEVE-4263 Date Collected 08-15-17 08-15-17 08-15-17 08-15-17 Req. LLD Sample Type Coflard Greens Turnip Greens Japanese Greens Swiss Chard Be-7 < 81 382 +/- 104 278 +/- 120 364 +/- 97 K-40 3554 i 242 3943 +/- 236 4218 +/- 325 3979 +/- 255 Co-58 < 8.8 <6.4 < 7.9 <6.6 Co-60 < 6,8 < 5.1 < 8.7 < 7.3 1-131 <24.7 < 18-0 < 41.8 < 24,7 45 Cs-134 < 7.3 < 7.1 < 9.8 < 72 45 Cs-137 <8.3 < 7.7 < 13.0 < 8,3 60 Lab Code PEVE- 4916 PEVE- 4917 PEVE- 4918 PEVE-5632 Date Collected 09-20-17 00-20-17 09-20-17 10-17-17 Req. LLD Sample Type Collard Greens Turnip Greens Swiss Chard Collard Greens Be-7 < 117 344 +/- 103 485 +/- 144 245 +/- 112 >>
K-40 3141 +/- 296 6120 +/- 353 6669*458 3532 +/- 293 -
Co-58 <9.8 < 8.8 < 17.7 < 8.7 Co-60 < 3-6 < 10-0 < 10.5 <6.3 _
1-131 < 38.4 < 30.9 < 29.2 < 22.8 45 Cs-134 < 8.0 < 9.5 < 11.8 < 9.1 45 Cs-137 <8.2 < 11.9 < 11.8 < 8.9 60 Lab Code PEVE- 5633 PEVE- 5634 Date Collected 10-17-17 10-17-17 Sample Type Turnip Greens Swiss Chard Be-7 584 +/- 113 543 +/- 122 K-40 5937 +/- 343 6009 +/- 378 Co-58 < 6.3 < 9.0 Co-60 < 6.5 < 9.6 1-131 < 15.8 < 26.3 Cs-134 < 9.7 < 10.3 CS-137 < B.5 < 9.4 7-5
PNPP Table 8. Fish, analyses for gamma emitting isotopes.
Collection: Annually* Units. pCt/kgwet Location P-25 Lab Code PEF- 4921 PEF- 4922 PEF- 4923 PEF- 4924 Date Collected 09-19-17 09-19-17 09-19-17 09-19-17 R<<q LID Sample Type Smallmouth Bass Walleye Yellow Perch Channel Catfish MO 1035 1 269 1643
~~314 1172 +/- 194 1397 +/- 275 j.~~
Mrt-54 <5.7 < 19.8 < 8.7 < 11.6 94 Fe-59 <27.2 <20;4 < 20.0 < 32.2 195 Co-58 < 14.1 < 10.5 < 11-6 < 134 97 00-60 < 10.2 < 15,0 < 77 < 19.3 97 Zn-65 <7.5 < 34.8 < 21 2 <32.9 195 Cs-134 < 10.0 < 15.7 <8.9 < 18.3 97 C<<-137 < 11.9 < 193 <9.7 < 14.8 112 Location P-25 Lab Code PEF- 4925 Dale Collected 09-19-17 Req LLD Sample Type White Perch K40 1745
303 Mn-54 < 12 4 94 Fe-59 < 35.4 195 Co-68 <8.2 97 Co-60 < 12,5 97 Zn-65 < 15,4 195 C8-134 < 13.1 97 CM37 < 13.3 112 Location P-25 a Delivery problems with fish collected 05-31-17; fish arrived very late. Unable to analyze due to overwhelming toxic odor from liquified samples.
9-1
Table 9. Fish, analyses for gamma emitting isotopes.
Collection: Annually* Unite: pCi/kg wet Location P-32 Lab Code PEF-4927 PEF- 4928 PEF- 4930 PEF- 4931 Date Collected 09-19-17 09-19-17 09-19-17 09-19-17 Req. LLD Sample Type Rainbow Trout Smallmouth Bass Freshwater Drum White Perch K-40 15541211 1660 +/- 341 768 t 254 668 +/- 160 Mn-M <5.B < 15.1 <20.8 < 8.5 94 re-59 <27.2 << 42.3 < 45.9 < 20.6 195 Co-56 < 9.6 < 13.4 < 18.7 < 9.4 97 Co-60 <8.3 < 11.5
7.1 < 9.4 97 Zn-65 < 19.2 < 30.8 < 35.6 < 22.7 195 Cft-134 <<9.5 < 16.3 < 16.0 < 11,9 >>7 Ct-137 < 10.1 < 11.6 < 14.6 < 11.8 112 Location P-32 Lab Code PEF- 4932 PEF- 4933 Date Collected 09-19-17 09-19-17 Req. LLD Sample Type Redhoree Sucker YeHow Perch
&40 1522 +/- 244 2821 1 339 Mn-54 < 13.8 < 26.6 94 Fe-59 < 51.8 < 65.0 195 Co-58 < 10.0 << 26.3 97 Co-60 < S.3 < 24.4 97 Zn-65 << 33.0 < 52.0 195 Cs-134 < 12.9 < 34.6 97 Cs-137 < 12.1 < 22.0 112 Location P-32 8 Delivery problems with fish collected 05-31 -17; fish arrived very late. Unable to analyze due to overwhelming toxic odor from liquified samples.
9-2
PMPP Table 11. Sediments, analyses for gamma emitting isotopes.
Collection: Semiannual Units' pCi/kgdry Location P-64 ...
Lab Code PE8S- 1938 PEBS- 4919 Date Collected 04-27-17 09-2O-17 Req. LLD K-40 15112 +/- 663 9087 +/- 484 Co-58 < 19.6 < 13.3 50 Co-$0 < 14.3 < 77 40 Cs-134 < 17,3 < 0.0 112 Cs-137 < 10.8 < 0.0 135 Location ( i P-8S Lab Code PEBS- 1939 PEBS- 4920 Date Collected 04-27-17 09-20>t7 09-20>f7 Req.aD K-40 8254 1 440 7739* 437 Co-58 < 16.1 < 125
.< 122 50 Co-60 < 11.0 < 13.0
< 40 Cfi-134 < 138 < 0.0
< 112 Cs-137 < 9.1 < 0.0
< 135 11-1
2017 Annual Environmental and Effluent Release Report Appendix D Corrections to Previous Annual Environmental and Effluent Release Reports
2017 Annual Environmental and Effluent Release Report APPENDIX D Corrections to Previous Annual Environmental and Effluent Release Reports There is one correction to the annual reports from 2013,2014,2015, and 2016, which reference "Great Lakes Nuclear Services" as a REMP-sampled location in Table 15, location
~~53. The title is not correct for the company that has resided at this location in recent years.~~
The reference of the REMP location was corrected in the latest revision of the ODCM and was changed to list the address rather than a company title, which can change frequently.
D-1
2017 Annual Environmental and Effluent Release Report Appendix E Abnormal Releases
2017 Annual Environmental and Effluent Release Report APPENDIX E Abnormal Releases In November 2011, radioactivity was detected in the Nuclear Closed Cooling (NCC) system.
The source of this activity is the primary coolant. There is some leakage from the NCC system to Service Water and from there to the environment. Residual activity remains in the NCC system and it is being tracked as a continuous abnormal release.
The calculated annual doses for the NCC abnormal releases were 7.10E-06 mrem whole body and 1.27E-05 mrem organ.
Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total time period for continuous release, min 4.46E+04* 4.32E+04* NA 8.78E+04 Total volume released, liters 1.36E+05* 1.38E+05* NA 2.57E+04 Average quarterly flow rate, L/min 1.28E+05* 8.71 E+04* NA 2.97E+05
'Release continued, however, no activity was detected In January, February, May, June, nor October; these monthly volumes were omitted from aU calculations NA - no activity was detected during the quarter Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Fission and Activation Products (Ci)
Mn-54 <LLD 2.06E-05 <LLD <LLD 2.06E-05 Co-58 <LLD 1.12E-05 <LLD <LLD 1.12E-05 Co-60 4.66E-06 1.18E-04 <LLD 1.01E-06 1.23E-04 Total Released 4.66E-06 1.49E-04 <LLD 1.01 E-06 1.55E-04 B. Tritium (Ci) <LLD <LLD <LLD <LLD <LLD
<LLD <LLD <LLD <LLD <LLD C. Noble Gases (CD D. Gross Alpha (Ci) <LLD <LLD <LLD <LLD <LLD There were no abnormal gaseous releases.
E-1
2017 Annual Environmental and Effluent Release Report Appendix F ODCM Non-Compliances
2017 Annual Environmental and Effluent Release Report appendix f ODCM Non-Compllances Effluent Monitoring On 2/17/2017, the Service Water Discharge Header Flow was declared inoperable, and remained inoperable until 5/05/2017. TTie sensing tube had deteriorated and needed to be replaced. This also required excavation of the work site to replace the piping.
This instrument is the only channel meeting the minimum channels operable requirement.
Per the ODCM and Technical Specifications, a notification is required to be made in this report for ODCM-equipment that is out of service for greater than 30 days. All contingency actions were taken in accordance with the ODCM, which requires recording flow rates every four hours.
Environmental Monitoring On 05/30/17 semi-annual fish sampling was performed. The following species were obtained on May 31 at location 32: smallmouth bass, red horse sucker yellow perch, walleye, fresh water drum and white perch. The following species were obtained the same day at location 25- Walleye, channel catfish, sheep head, small mouth bass, and white perch. Samples were prepared, labeled, and shipped to the vendor; however, a different location received the boxes Once the issue had been identified, it was promptly corrected, and the samples shipped to the correct location. Upon receipt at the vendor lab, It was determined that analysis could not be performed due to the condition of the samples. Semi-annual fish sampling is required by the ODCM, Table 3.12.1-1 Ab and to analyze edible portions for gamma isotopic. Annually, fish sampling is arranged in the spring and fall, typically May and September, weather dependent. Sampling was performed in the fall as expected and all samples analyzed.
Failed to capture Walleye at the indicator location during fall fish sampling. However, six species from this location were sent for analysis, including the other required species, yeyow perch.
Water Shoreline samples (location #59 and #60) were not sampled for the month of January due to frozen shoreline conditions.
F-1
2017 Annual Environmental and Effluent Release Report Appendix G ODCM Changes
2017 Annual Environmental and Effluent Release Report APPENDIX G ODCM Changes The scope of changes to the ODCM during this reporting period are listed as follows:
~~1. Commitment L02211 was closed and removed from;~~
~~a. Introduction, paragraph 6~~
~~b. Table 3.3.7.9-1.3.C.2~~
~~c. Table 3.3.7.10-1.2.a~~
~~d. Table 3.3.7.10-1.4.a e Table 3.3.7.10-1, action note 122 f Controls section 3.11.2.4 under the description and footnote~~
~~2. Commitment R00449 was closed and removed from Table 4.11.1.1.1-1.B under the grab sample composite 3 Added clarification of a valid alert alarm in 3.1 note a~~
4. CombinedSole in calculation 3.1*4 with the definition Y and added note to reference table 5 Focalized table of Effluent Release Path flow rates listed under section 3.1.4 equation quarterly and annually. Now section contains a reference to Table 3.12-1, 7 Secton 5*1: Removed reference to site-specific environmental monitoring P^"^.
I] TaWe 5.1-1: shortened titie; renamed location 53 to reflect current £<<£**£ SflSKE 16 20 39, 57and66; removed locations 18,28and65; indjcatedthat tocatons36 and 39are drinking water and locations 59 and 60 are surface water samples; changed "Food Products to "Broadleaf Vegetation" at locations 2, 37, and 70 9 Figures 5 1-1, 5/1-2, and 5.1-3: Updated maps to reflect changed sample locations 10 Revised Table A-2: Added a new column showing distance in meters 11 TableT3.3.7.10-1 and 4.3.7.10-1: Table Notations, Removed "^unng main condenser off-
' gas treatment system operation." There are no double astensks In the tables 12 Table 3 3 7 10-1 Addeclaction 124 to Unit 1 Vent noble gas channel during modes 4 and 5 13 Table IIj.IO-I: Sed footnote (1) from each page and added it to the notations port.on 14 Table 3.12.1-1: Updated number of TLDs to 29 15 Table 312 1-V modified wording to state that one sample of each commercially or reTre^onally important fish species will be collected; changed samplmg frequency to sem.-
annually in section 3. b l?^s^^
the meteorological report separate from the Annual Report into paragraph b; spirt the paragraph into two for clarity purposes.
~~18. Removed asterisk and footnote from section 6.9.1.7 19 Added new section for commitments~~
~~20. Minor editorial and grammatical corrections, revision bars not usea G-1~~
2017 Annual Environmental and Effluent Release Report Appendix H Changes to Process Control Program
2017 Annual Environmental and Effluent Release Report APPENDIX H Process Control Program Changes There were no changes to the Process Control Program during this reporting period.
H-1
Enclosure B L-18-127 Offsite Dose Calculation Manual, Revision 21
ODCM Page: i Rev.: 21 Offsite Dose Calculation Manual Effective Date: 10-10-17 Preparer: Melanie Baker Approver: Steve Benedict Program Manager
ODCM Page: ii Rev.: 21 TABLE OF CONTENTS
~~1.0 INTRODUCTION~~
1 2.0 LIQUID EFFLUENTS 2 2.1 Batch Releases , 2 2.1.1 Monitor Alarm Setpoint Determination 3 2.1.2 10CFR20 Compliance - Liquid Effluent Concentration 5 2.2 Continuous Releases 8 2.2.1 Monitor Alarm Setpoint Determination 9 2.3 10CFR50, Appendix I Compliance - Liquid Effluent Dose 10 2.3.1 Dose Calculations 10 2.3.2 Cumulation of Doses 12 2.3.3 Projection of Doses 12 2.3.4 Population Dose 12 3.0 GASEOUS EFFLUENTS 30 3.0.1 Batch Releases 30 3.0.2 Continuous Releases 30 3.1 Monitor Alarm Setpoint Determination 32 3.1.1 Determination of "Mix" (Noble Gas Radtonuclide Composition) of Gaseous Effluents 33 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 33 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limft 34 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent 35 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides 36 3.2 10CFR20 Compliance - Gaseous Effluent Dose Rate 37 3.2.1 Noble Gases 37 3.2.2 Radtoiodines, Particulates, and Other Radionuclides 37 3.2.3 Dose Rate Calculations 37 3.3 10CFR50, Appendix I Compliance - Gaseous Effluent Dose 64 3.3.1 Noble Gases w 3.3.2 Radioiodines, Particulates, and Other Radionuclides 64 3.3.3 Dose Calculations 65 3.3.4 Cumulation of Doses 66 3.3.5 Projection of Doses 67 3.4 Population Dose 67 4.0 TOTAL DOSE M 4.1 40CFR190 and 10CFR72.104 Compliance - Uranium Fuel Cycle Dose 68 4.2 Direct Radiation Dose from PNPP (including the ISFSI) 69 4.3 Dose to Members of the Public While Onsite 69 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 71 5.1 Monitoring Program 71 5.2 Land Use Census Program '*
5.3 Inter-Laboratory Comparison Program 72 AppendixA 77 Appendix B J1 Appendix C >>
Records ]J>>
Commitments 1fJ[
REFERENCES 169
ODCM Page: iii Rev.: 21 List of Tables lable JJS ESOS.
2.3-1 Organs Used for Liquid Effluent Dose Calculations 13 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 13 2.3-3 Liquid Effluent Dose Pathways 13 2.3-4 Bio-Accumulation Factors (&P) (pCi/kg per pCi/ltter) 14 2.3-5 Ingestion Dose Factors for Adult (mrem/pCi ingested) 15 2.3-6 Ingestion Dose Factors for Teenager (mrem/pCi ingested) 17 2.3-7 Ingestion Dose Factors for Child (mrem/pCi ingested) 19 2.3-8 Ingestion Dose Factors for Infant (mrem/pCi ingested) 21 2.3-9 External Dose Factors for Standing on Contaminated Ground 23 2.3-10 Liquid Effluent Dilution Factors (Mp) 25 2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (tp) 25 2.3-12 Usage Factors <IW) 26 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP 27 2.3-14 Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations 28 2.3-15 Dilution Factors for the Shore Exposure Pathway 29 3.1-1 Whole Body and Skin Dose Factors 34 ^^, - n 3.1-2 Flow Rates and Effluent Monitor Efficiencies 35 l >><**>>*- <<*
3.2-1 Organs Used for Gaseous Effluent Dose Calculations 42 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 42 3.2-3 Gaseous Effluent Dose Pathways 42 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 43 3.2-5 External Dose Factors for Standing on Contaminated Ground 44 3.2-6 Inhalation Dose Factors for Adult (mrem/pCi inhaled) 46 3.2-7 Inhalation Dose Factors for Teenager (mrem/pCi inhaled) 48 3.2-8 Inhalation Dose Factors for Child (mrem/pCi inhaled) 50 3.2-9 Inhalation Dose Factors for Infant (mrem/pCi inhaled) 52 3.2-10 Ingestion Dose Factors for Adult (mrem/pCi ingested) 54 3.2-11 Ingestion Dose Factors for Teenager (mrem/pCi ingested) 56 3.2-12 Ingestion Dose Factors for Child (mrem/pCi ingested) 58 3.2-13 Ingestion Dose Factors for Infant (mrem/pCi ingested) 60 3.2-14 Annual Usage Factors for the Maximum Exposed Individual 62 3.2-15 Annual Usage Factors for the Average Individual 62 3.3-1 Gamma and Bete Air Dose Factors for Semi-Infinite Plume 66 5.1-1 ODCM REMP Sample Locations 73 A-1 Atmospheric Depletion and Deposition Factors 79 A-2 Site Boundary Atmospheric Dispersion (x/Q) and Deposition Parameters (D/Q) for PNPP Unit 1 80 A-3 Atmospheric Dispersion (x/Q) as a Function of Distance (s/m3) 81 A-4 Atmospheric Dispersion (D/Q) as a Function of Distance (rrv2) 86
ODCM Page: iv Rev.: 21 List of Figures Figures B!s 2.1-1 Liquid Radioactive Waste (LRW) Discharge System 2 3.0-1 Gaseous Effluent System Flow Diagram 31 3 2-1 PNPP Site Boundary and Unrestricted Area 63 51-1 Technicai Specification Required REMP Sampling Locations Within Two Miles of the Plant Site 74 5.1-2 Technical Specification Required REMP Sampling Locations Between Two and Eight Miles from the Plant Site 75 5.1-3 Technical Specification Required REMP Sampling Locations Greater Than Eight Miles from the Plant Site 76
ODCM Page: v Rev.: 21 SCOPE OF REVISION:
Rev. 21:
~~1. Commitment L02211 was closed and removed from:~~
~~Introduction, paragraph 6 Table 3.3,7.9-1.3.C.2 Table 3.3.7.10-1,2.a Table 3.3.7.10-1.4.a Table 3.3.7.10-1, action note 122 Controls section 3.11.2.4 under the description and footnote~~
~~2. Commitment R00449 was closed and removed from Table4.11.1.1.1-1.B under the grab sample composite~~
~~3. Added clarification of a valid alert alarm in 3.1 note a~~
~~4. Combined the note in calculation 3.1-4 with the definition T and added note to reference table 3.1-2~~
~~5. Formalized table of Effluent Release Path flow rates listed under section 3.1.4 equation definitions, creating Table 3.1-2 and added table to List of Tables~~
6. Section 4.2: Removed requirement that specified that environmental TLDs will be changed out quarterly and annually. Now section contains a reference to Table 3.12-1, Radiological Environmental Monitoring Program
7. Section 5.1: Removed reference to site-specific environmental monitoring procedures 8 Table 5.1-1: shortened title; renamed location 53 to reflect current status; added new locations 16,20, 39,57 and 66; removed locations 18,28 and 65; indicated that locations 36 and 39 are drinking water and locations 59 and 60 are surface water samples; changed "Food Products" to "Broadleaf Vegetation" at locations 2,37, and 70
~~9. Figures 5.1-1,5.1-2, and 5.1-3: Updated maps to reflect changed sample locations~~
~~10. Revised Table A-2: Added a new column showing distance in meters~~
~~11. Tables 3.3.7.10-1 and 4.3.7.10-1: Table Notations, Removed "**During main condenser off-gas treatment system operation." There are no double asterisks in the tables~~
~~12. Table 3.3.7.10-1: Added action 124 to Unit 1 Vent noble gas channel during modes 4 and 5~~
~~13. Table 3.3.7.10-1: Removed footnote (1) from each page and added it to the notations portion~~
~~14. Table 3.12.1-1: Updated number of TLDs to 29~~
15. Table 3.12.1-1: modified wording to state that one sample of each commercially or recreationally important fish species will be collected; changed sampling frequency to semi-annually in section 3.b
~~16. Table 4.3.7.9-1.3: Updated NBS reference to NIST~~
17. Revised Section 6.9.1.7: moved the information denoted by an asterisk regarding maintaining the meteorological report separate from the Annual Report into paragraph b; split the paragraph into two for clarity purposes.
~~18. Removed asterisk and footnote from section 6.9.1.7~~
~~19. Added new section for commitments~~
~~20. Minor editorial and grammatical corrections, revision bars not used~~
~~ODCM Page: 1 Rev.: 21~~
~~1.0 INTRODUCTION~~
This Offsite Dose Calculation Manual (ODCM) contains information and methodologies to be used by the Perry Nuclear Power Plant (PNPP), Unit 1, to ensure compliance with PNPP Radiological Effluent Technical Specifications. The Technical Specifications and this ODCM are written to satisfy 10CFR20 10CFR50.36 and Appendix 1,40CFR190 and 10CFR72.104 requiremente. This ODCM applies to doses from radioactivity and radiation from the Perry Nuclear Power Plant, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI).
Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively.
Each of these sections contain alarm setpoint determination, radiation dose and dose rate calculation methodologies, as well as limits and requirements. Section 4 covers uranium fuel cycte related radiation dose limits including direct dose from the Perry Nuclear Power Plant, including the ISFSI.
Also included in this manual, in Section 5. is information relating to the Radiological Environmental Monitoring Program (REMP). The figures and tables contained therein designate specific sample types and locations currently used to satisfy the Technical Specification requirements for the REMP as weH as sampling reporting and detection capability limits. The sample types and locations are subject to change based on factors including the results of the annual Land Use Census.
The ODCM has been prepared, as generally as possible, in order to minimize future revisions.
However, any such changes will be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications.
Supplemental information needed to support calculations is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters and Appendix B presents the methodology for determining the tower limit of detection (LLD).
Appendix C of the ODCM was prepared based on guidance of NUREG-1302, *Offsite Dose ^
Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1. This appendix along with plant procedures win be used by plant personnel to demonstrate compliance with Specification 5.5.4 (Radioactive Effluent Controls Program) of the PNPP Technical Specifications.
ODCM Page: 2 Rev.: 21 2.0 MQUID EFFLUENTS 2.1 Batch Releases A batch release is the discharge liquid radioactive waste of a discrete volume. Batch releases from the liquid radwaste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank (see Figure 2.1-1). The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tanks, which have a maximum release rate of 50 galbns per minute. All of the above liquid radwaste releases go to the Emergency Service Water discharge which is then released through the discharge tunnel after mixing with Service Water effluent and/or and blowdown from Circulating Water system, if present.
Figure 2.1-1 LJaukl Radioactive Waste fLRW) Discharge System
ODCM Page: 3 Rev.: 21 The type and frequency of sampling and analysis required by the ODCM is given in Appendix C, Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. Recycle lines are provided with one or more mixing eductore located near the bottom of the tanks to promote better mixing as well as reducing recirculation time. This ensures that the water in the tank will be mixed and will be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents.
Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to release in accordance with ODCM. Appendix C, Table 4.11.1.1.1-1. Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined in the previous month/quarter. If there are no tritium results from the most recent month the most recent steam cycle value may be used as this will be a conservative number used for calculating batch releases. If there is sufficient time prior to a planned release, a composite of samples that are expected to be representative of the release may be analyzed for the tritium and other non-gamma emitting isotope values.
2.1.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints for the Radwaste Discharge Radiation Monitor - ESW Discharge and Liquid Radwaste Adjustable High Flow Trip Unit to ensure that liquid radwaste effluent releases from the site to unrestricted areas are below the limiting effluent concentrations (EC) specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases. An EC of 2.0E-4 uCiftnl has been established for dissolved and entrained noble gases. The Radwaste Discharge Radiation Monitor - ESW Discharge provides alarm and automatic termination of releases prior to exceeding these limits.
NOTE: Liquid radwaste discharge flow rate shall be verified at least once per four hours, whenever the flow rate measuring device(s) is inoperable during actual releases.
2.1.1.1 Minimum Acceptable Dilution Factor Determination:
Jeco Where:
DF0 = the minimum acceptable dilution factor determined from analysis of the liquid effluent to be released; Ci = the concentration of radionuclide T in the batch to be released, nCi/ml. If the concentration of a radionuclide is below the lower limit of detection, the radionuclide shall not be included as a source term in the setpoint calculation.
ECi = the effluent concentration of radionuclide 'i', from 10CFR20, Appendix B, Table 2, Column 2, in uCVml. (2.0E-4 uCi/ml for noble gases).
DF = lODFo (21-2)
Where:
DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure compliance with 10CFR20; dfc = the minimum acceptable dilution factor, as per equation 2.1-1; 10 = a factor of ten less than 10CFR20, Appendix B, Table 2, Column 2, limits; which represents an order of magnitude of conservatism for liquid radwaste releases from PNPP.
ODCM Page: 4 Rev.: 21 2.1.1.2 Maximum Allowable Radwaste Tank Discharge Flow Rate
__ (o.64)mdf Where:
Fmax = the maximum allowable radwaste tank discharge flow rate for the batch to be released, gpm; DF = the conservative dilution factor, per equation 2.1-2; MDF = the minimum dilution flow - supplied by the Service Water system, Emergency Service Water system, or Circulating Water system blowdown, gpm; 0.64 = an engineering factor to prevent spurious alarms 2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint <L00434>
Monitor alarm setpoints are determined to ensure that the concentration of radionucHdes in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table 2, Column 2, for radionudides other than dissolved and entrained noble gases. A limiting effluent concentration of 2.0E-4 uCi/ml has been established for dissolved and entrained noble gases in liquid effluents.
SPf= 1.25 (Fact) (2.1-4)
Where:
SPr = liquid radwaste adjustable high flow trip Unit (G50-K805A/B or G50-K926/7) alarm setpoint, gpm; Fact = actual allowable radwaste tank discharge flow rate for the batch to be released, not to exceed the maximum allowable radwaste discharge flow rate Fmax as defined in equation 2.1-3, gpm; 1.25 = an engineering safely factor to prevent spurious alarms The liquid radwaste tank discharge flow should be maintained at or below this Fact value by proper regulation of the high or low volume discharge throttle valves (G50-F153 or G50-F155, respectively).
2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm/Trip Setpoint Monitor alarm/trip setpoints are determined to ensure that the concentration of radionudides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table 2, Column 2 for radionudides other than dissolved or entrained noble gases. A limiting effluent concentration of 2.0E-4 uCi/ml has been established for dissolved and entrained noble gases in liquid effluents.
= Z(Ci)(Ef) (2.1-5)
Where:
CRe = the calculated monitor count rate above background, cpm; Ci = the concentration of radionudide Y in the batch to be released, uCi/ml; Ei = the detector efficiency of the monitor for radlonucllde 1", cpm/uCi/ml.
OR
ODCM Page: 5 Rev.: 21 CRx = (R.) (Fx) (Id) (2.1-8)
Where:
CRx = the cross-calibrated monitor count rate above background, cpm; Fx = the cross-calibration factor is used to ratio the Hquid redwaste discharge radiation monitor actual response to the Cs-137 calibrated response; R, = the response of the Liquid Radwaste Discharge Radiation Monitor to a Cs-137 calibrated standard, cprr%Ci/ml).
SPr = 1.25 (~z)CRn + BG (2.1-7)
Where:
SPr = the Radwaste Discharge Radiation Monitor - ESW Discharge alarm/trip setpoint, in cpm; BG = background count rate due to internal contamination and radiation levels in the area of the monitor, cpm; CRn = monitor net count rate, either CRc or CRx. per equation 2.1-6 or 2.1-6, cpm; 1.25 = an engineering factor to prevent spurious alarms; Fmn/Fict - an adjustment factor (to account for the difference between an actual radwaste discharge flow rate to be used for the discharge and maximum allowable radwaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; Where:
F.* = actual radwaste discharge flow rate, this value must always be less than or equal to Firm, gpm; Fimx = maximum allowable radwaste discharge flow rate, per equation 2.1-3, gpm.
2.1.2 10CFR20 Compliance - Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radtonuclides in liquid effluents will be determined and compared with the limiting effluent concentrations as defined in 10CFR20, Appendix B, Table 2, Column 2, (2.0E-4 uCiftnl for dissolved and entrained noble gases). Concentrations of radioactivity in effluents prior to dilution will be determined.
Concentration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release.
2.1.2.1 Concentration of Radionuclides in Prerelease The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with 10CFR20 in the following manner The concentration of the various radionuclides in batch releases prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
ODCM Page: 6 Rev.: 21 Cone , >> ^i)W (2.1-8)
' MDF Where:
= the concentration of radionudide T at the unrestricted area, nCi/ml; C{ = the concentration of radionuclkfe T in the batch to be released, uCi/ml; f = the radwaste tank discharge flow rate for the batch to be released, gpm; MDF - the minimum dilution flow, per equation 2.1-3, gpm.
The projected radionuclide concentrations in the unrestricted area are compared to the limiting effluent concentrations In 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 uCi/ml for dissolved and entrained noble gases) In order to give a final 10CFR20 compliance check, I.e., the following equation must be met:
^ Cone, S^<1 (2.1*)
Where:
Cofif = the concentration of radionuclide T at the unrestricted area, jiCi/ml; EQ = the limiting effluent concentration of radionuclide "i", from 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 ^Ci/ml for dissolved and entrained noble gases), uCi/ml.
2.1.2.2 Post Release The actual radioactivity content of each batch release will be determined following release to show final compliance with 10CFR20.
The concentration of the various radionuclides in batch releases prior to dilution is divided by the actual dilution to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
(2.1-10)
Where:
Corif = the actual concentration of radionuclide V at the unrestricted area for the release, pCi/ml; Cf = the concentration of radionuclide T in the batch released, pCi/mi; Vdij = the actual volume of dilution water during the release (total plant discharge flow, including Service Water, Emergency Service Water, and cooling tower Wowdown), in gallons; Vlr( = the actual volume of the liquid radwaste tank discharged for the batch, gal.
ODCM Page: 7 Rev.: 21
ODCM Page: 8 Rev.; 21 The concentrations in the unrestricted area are compared to the limiting effluent concentrations in 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 uCi/ml for dissolved and entrained noble gases). In order to demonstrate final compliance with 10CFR20, the following equation must be met:
__ Conei Where:
Conf - concentration of radionuclide "i" at the unrestricted area, EQ = limiting effluent concentration of radionuclide "i", from 10CFR20, Appendix B, Table 2, Column 2, 2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a non-discrete volume, i.e., from a volume or system that has an input flow during the continuous release. Potential sources for a continuous release at Perry are RHR heat exchanger leakage into the Emergency Service Water system, tritium activity in the M35 Supply Plenum drain into storm drains, and Alternate Decay Heat Removal (ADHR) heat exchanger leakage into Service Water.
Potentially contaminated discharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment In Emergency Service Water System Loop A and the other for Emergency Service Water Loop B. If radiation is detected, the affected Emergency Service Water line can be manually isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.
The Emergency Service Water discharged will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1. To show compliance with 10CFR20, the sum of the concentrations of radionuclide T in unrestricted areas due to both continuous and batch releases divided by that isotope's limiting effluent concentration must be less than 1.
During the summer months, the Turbine Building Supply Plenums (1M35B0001 A, B, C) are used as a cooling source; condensation from the cooling coils is collected in the M35 plenum drain pans.
Moisture from the outside air Is condensed and flows into the drain pan. The potential exists Ibr the outside air to contain tritium from the plant vents, thus the M35 Turbine Building Supply Plenums could also contain tritium. During the summer months, the M35 drains are routed to storm drains due to the large quantity of condensation. Grab samples are obtained in accordance with ODCM Appendix C Table 4.11.1.1.1-1.
The ADHR system has an installed radiation monitor on the Service Water line ttiat provides cooling to the AHDR heat exchanger. The Service Water (ADHR) system will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1. If radiation is detected, the ADHR system can be isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.
ODCM Page: 9 Rev.: 21 2.2.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the alarm setpoints for the Emergency Service Water loops A & B and Service Water (ADHR) Radiation Monitors. This methodology ensures an alarm will be received prior to exceeding the limiting effluent concentration listed in 10CFR20, Appendix B, Table 2, Column 2.
2.2.1.1. Alarm Setpoint CRc = (BG + MR)(0.75)
Where:
CRc = the calculated monitor count rate in cpm; BG = the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm; MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix; 0.75 engineering safety factor 2.2.1.2 Minimum Allowable Backgrounds BGnHn-CRc-MR Where:
BCrtn minimum allowable background to ensure monitor wiH alarm prior to exceeding 1.0 EC; CRc - the calculated monitor count rate in cpm; MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix; NOTE: If calculated value is negative, then 0 cpm will be used as the minimum allowable background.
2.2.1.3. Expected Monitor Response Based on the Reactor Water Source Term MR = I(ECiX%rxEffi)
Where:
MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix;
%, = percent of isotope (i) in a typical reactor water isotopic mixture; Eff, = radiation monitor detector efficiency for isotope (i);
ECi = Effluent concentration value for isotope (0, Appendix B, Table 2, Column 2,10CFR20.
2.2.1.4. Minimum Allowable Setpoint Based on Monitor Background
= 3G+
Where:
ODCM Page: 10 Rev.: 21 CRmin = Minimum allowable setpoint for a given monitor background (BG);
BG = the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm; 2 = 95% confidence level; 2TC = two times the instrument time constant where (Log 10BG - Log 10Locpm ) (TChicpin - TCiocpm J TC j c
{LogioHicpm -
Time Constants:
Hi/Lo cpm TC Hi/Lo cpm 10 cpm 1.25 min 100 cpm 1.25 min 1,000 cpm 1.25 min 10,000 cpm 0.2 min 100,000 cpm 0.042 min 1,000,000 cpm 0.0033 min For Backgrounds less than 400 cpm, the following values will be used:
Locpm = 100 cpm TClocpm = 1 -25 min Hicpm = 1000 cpm TCmcpm = 1 -25 m'n For Backgrounds £ 400 cpm and less than 1,000 cpm, the following values will be used:
Locpm = 1,000 cpm TClocpm = 1 -25 min Hicpm = 10,000 cpm TCHicpm = °-2 mln 2.3 10CFR50. Appendix I Compliance - Liquid Effluent Dose Doses resulting from liquid effluents will be calculated at least monthly to show compliance with 10CFR50, Appendix I. A cumulative summation of whole body and organ doses for the current quarter and year will be maintained. Additionally, doses due to liquid releases are projected monthly.
2.3.1 Dose Calculations Radiation doses due to liquid radioactive effluents from PNPP are calculated based on three main dose pathways: potable water, aquatic foods (namely fresh water fish ingestion), and exposure to shoreline deposits. Irrigated food pathways, as discussed in Regulatory Guide 1.109, will not be of concern at PNPP as little or no water from Lake Erie is used for irrigation in the nearby Ohio counties of Lake, Ashtabufa, Cuyahoga and Lorain. Nursery businesses and other agricultural activities that require supplemental water generally rely on water drawn from smal ponds and streams.
Radiation dose to members of the public for liquid radioactive releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:
ODCM Page: 11 Rev.: 21 Potable Water uap ^ . ., (2 3-1) a-p (Mp) (F)
Aquatic Foods
,xc i-i, t.>> (2-3-2)
(F)
Shoreline Deposits R . 11MO0 iHffi^ z (Q1) w (Dalpj, (Mp)(F; Where:
R . the dose to individuals of age group "a" to organ "f from all the radionuclides in
- ajp pathway "p".ln mrem; 5ic = the equilibrium bioaccumulation factor for radionudide Tin pathway p, expressed as the ratio of the concentration in biota (pCi/kg) to the radionudide concentration in water (pCi/l), from Table 2.3-4, I/kg;
= the dose factor, specific to a given age group "a", radionuclide i, pathway p.and organ "j", which can be used to calculate the radiation dose from an intake of a radionuclide (mrem/pCI); or from exposure to a given concentration of a radio nuclide in sediment, expressed as a ratio of the dose rate (mrem/h), and the areal radionuclide concentration, (pCi/m2), from Tables 2.3-6 through 2.3-9; F = the flow rate of the liquid effluent, fP/sec; NOTE: The normal minimum dilution flow will be 30,000 gpm (USAR 11.2.3.2).
,: - the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water, point of harvest of aquatic food or shoreline), from Table 2.3-10, dimensionless; Qi = the release of radionudide T.Ci; Tb = the period of time for which the sediment or soil is exposed to the contaminated water, 1.75 x 105 hr (20 yrs);
Ti = the half-fife of radionudide T, days; t* = the average transit time required for radionuclides to reach the point of exposure, from Table 2.3-11; for internal dose, tp >>the total time elapsed between release of the radionuclides and the ingestion of food or water, hr, o = the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway "p", from Table 2.3-12, hr/yr, 1/yr, or kgfyr; W = me shoreline width factor, 0.3 (from Regulatory Guide 1.109);
xL - radioactive decay constant of radionudide T.hr1; 1100 = a factor to convert from (CityrMrWs) to pCi/l; 110,000 = a factor to convert from (Ci/yry(ftVs) to pCi/l and to account for the proportionality constant used in the sediment radioactivity model.
ODCM Page: 12 Rev.: 21 2.3.2 Cumulation of Doses The dose contribution from liquid effluents will be calculated at least monthly. Calculations will be performed to determine the maxfmum whole body as well as the maxfmum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results will be summed with the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR50, Appendix I the following relationships shall hold:
for the quarter Dose < 1.5 mrem whole body; Dose < 5 mrem any organ; for the year Dose < 3 mrem whole body; Dose < 10 mrem any organ.
The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with ODCM Appendix C controls, stating the reason and corrective action to be taken.
2.3.3 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.
If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the whole body or 0.2 mrem to any organ, the liquid radwaste system wil be used to process waste. The values for the projected dose impact levels correspond to approximately one forty-eighth of the 10CFR50, Appendix I design objective. If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the 10CFR50, Appendix I limit.
The projected doses will be calculated using equations 2.3-1,2.3-2, and 2.3-3.
In this case, the source term will be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month.
2.3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses will be calculated using average individual transit times and usage factors, Table 2.3-12, (as compared to maximum exposed individual factors used for Individual doses). The total population dose will be calculated by dose pathway and organ, with pathway doses being corrected for the fraction of the population assumed to be in each age group (adult, teen, child and infant 0.71, 0.11,0.18,0.0 respectively).
ODCM Page: 13 Rev.; 21 Table 2.3-1
~~1. Bone~~
~~2. Gl Tract~~
~~3. Kidney~~
~~4. Liver~~
~~5. Lung~~
~~6. Thyroid~~
~~7. Whole Body~~
~~8. Skin Table 2.3-2 An<< Grauus Used for Liauid Effluent Dose Calculations~~
~~1. Adult (17 yrs. and older)~~
~~2. Teen(11-17yrs)~~
~~3. Child (1-11 yrs)~~
~~4. Infant (O-1yr)~~
~~Table 2.3-3 l inuid Effluent Dose Pathways~~
~~1. Water Ingestion~~
~~2. Shore Exposure~~
~~3. Fresh Water Fish Ingestion~~
ODCM Page: 14 Rev.: 21 Table 2.3-4 BkWtecumulation Factors (B*) fpCi/ko per pCi/lter)
Element Fish H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 1.0E+05 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo LOE+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Sb 1.0E+00 Te 4.0E+02 l 1.5E+01 Cs 2.0E+03 Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 Ta 1.0E+00 W 1.2E+03 Re 1.0E+00 Au 1.0E+00 Np 1.0E+01
ODCM Page: 15 Rev.: 21 Table 2.3-5 Inaestion Dose Factors for Adult (mrem/pCi ingested)
WHOLE BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER O.OOE+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 H-3 2.84E-08 5.68E-07 5.68E-O7 5.68E-07 5.68E-07 5.68E-07 5.68E-07 C-14 Na-24 1.70E-0e 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-O4 1.20E-05 7.46E-06 O.OOE+00 0.00E+00 0.00E+00 2.17E-05 O.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-O9 6.69E-07 Cr-51 O.OOE+00 4.57E-06 8.72E-07 O.OOE+00 1.36E-06 0.00E+00 1.40E-05 Mn-54 O.OOE+00 Mn-56 O.OOE+00 1.15E-07 2.04E-08 O.OOE+00 1.46E-07 0.00E+00 3.67E-06 1.90E-06 4.43E-07 O.OOE+00 O.OOE+00 1.06E-06 1.09E-06 Fe-55 2.75E-06 4.34E-06 102E-Q5 3.91 E-06 O.OOE+00 0.00E+00 2.85E-06 3.40E-05 Fe-59 Co-58 0.00E+O0 7.45E-07 1.67E-O6 O.OOE+00 0.00E+00 0.00E+00 1.51E-05 Co-60 O.OOE+00 2.14E-06 4.72E-06 O.OOE+00 0.00E+00 0.00E+00 4.02E-05 1.30E-04 9.01 E-06 4.36E-06 0.00E+00 0.00E+00 O.OOE+00 1.88E-06 Ni-63 Ni-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+00 O.OOE+00 O.COE+00 1.74E-06 Cu-64 O.OOE+00 8.33E-08 3.91 E-08 O.OOE+00 2.10E-07 0.00E+00 7.10E-06 Cu-67 2.95E-07 8.41 E-07 O.00E+O0 2.24E-07 2.62E-07 2.27E-07 1.07E-05 4.84E-06 1.54E-05 6.96E-06 O.OOE+00 1.03E-05 0.00E+00 9.70E-06 Zrn65 2n-69 1.03E-O8 1.97E-08 1.37E-09 O.OOE+00 1.28E-08 0.00E+00 2.96E-09 Br-83 O.OOE+00 0.00E+00 4.02E-08 0.00E+O0 O.OOE+00 O.OOE+00 5.79E-08 Br-84 O.OOE+00 0.00E+O0 5.21 E-08 O.OOE+00 0.00E+00 0.00E+00 4.09E-13 O.OOE+00 O.OOE+00 2.14E-09 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Br-85 Rd-86 O.OOE+00 2.11E-05 9.83E-O6 O.OOE+00 O.OOE+00 O.OOE+00 4.16E-06 Rb-88 0.00E+O0 6.05E-O8 3.21 E-08 O.OOE+00 0.00E+00 0.00E+00 8.36E-19 4.01 E-08 2.82E-08 O.OOE+00 O.OOE+00 0.00E+00 2.33E-21 Rb-89 O.OOE+00 Sr-87M 1.52E-08 1.77E-08 0.00E+O0 2.96E-09 2.58E-08 6.92E-O9 2.15E-07 O.OOE+00 8.84E-06 O.OOE+00 0.00E+00 0.00E+00 4.94E-05 Sr-89 3.08E-04 0.00E+00 1.86E-03 O.OOE+00 O.OOE+00 0.00E+00 2.19E-04 Sr-90 7.58E-03 5.67E-06 O.OOE+00 2.29E-O7 O.OOE+00 O.OOE+00 0.00E+00 2.70E-05 Sr-91 O.OOE+00 9.30E-08 0.00E+00 0.00E+00 0.00E+O0 4.26E-05 Sr-92 2.15E-06 9.62E-09 O.OOE+00 2.58E-10 O.OOE+00 O.OOE+00 0.00E+O0 1.02E-04 Y-90 Y-91M 9.09E-11 O.OOE+00 3.52E-12 O.OOE+00 0.00E+O0 O.OOE+00 2.67E-10 Y-91 1.41E-07 O.OOE+00 3.77E-09 0.00E+00 O.OOE+00 O.OOE+00 7.67E-05 Y-92 8.45E-10 O.OOE+00 2.47E-11 0.00E+00 O.OOE+00 O.OOE+00 1.48E-05 2.68E-09 O.OOE+00 7.40E-11 0.00E+00 0.00E+OO 0.00E+00 8.50E-05 Y-93 3.04E-08 9.75E-09 6.60E-O9 O.OOE+00 1.53E-08 O.OOE+00 3.09E-05 Zr-95 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 O.OOE+00 1.05E-04 Zr-97 Nb-95 6.22E-09 3.46E-09 1.86E-O9 0.00E+00 3.42E-09 O.OOE+00 2.10E-05 Mo-99 O.OOE+00 4.31 E-06 8.20E-07 0.00E+00 9.76E-06 O.OOE+00 9.99E-06 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-O8 3.42E-10 4.13E-07 TC-99M
ODCM Page: 16 Rev.: 21 Table 2.3-5 (Cont.)
Irraestion Dose Factors for Adult (mrem/bCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 O.OOE+00 2.16E-O5 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-O7 0.00E+00 9.42E-06 Ru-106 2.75E-06 O.OOE+00 3.48E-07 0.00E+O0 5.31 E-06 0.00E+00 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91 E-O7 O.OOE+00 6.04E-05 Te-125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-O6 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-O8 4.48E-07 0.00E+00 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-08 118E-48 7.65E-09 2.41 E-08 1.32E-O7 0.00E+00 2.37E-08 Te-131M 1.73E-06 8.46E-O7 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-O8 O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-O5 O.OOE+00 7.71 E-05 i-130 7.56E-07 Z23E-06 8.80E-07 1.89E-04 3.48E-O6 0.00E+00 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 O.OOE+00 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-O7 0.00E+00 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 O.OOE+00 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51 E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.66E-05 1.86E-O6 0.00E+00 1.31 E-06 Cfi-134 6.22E-05 1.48E-04 1.21 E-04 0.00E+O0 4.7BE-05 1.59E-05 2.59E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cfr-136 6.51 E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-O5 1.23E-05 2.11 E-06 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01 E-08 7.91 E-09 4.65E-13 Cs-138 Ba-139 9.70E-08 6.91 E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-O7 Ba-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+00 8.67E-O9 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 O.OOE+00 3.31 E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 O.OOE+00 1.85E-11 1.24E-11 3.00E-26 2.50E-O9 1.26E-09 3.33E-10 O.OOE+OO 0.00E+00 0.00E+00 9.25E-05 La-140 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 0.00E+00 O.OOE+00 4.25E-07 Ce-141 9.36E-09 6.33E-O9 7.18E-10 O.OOE+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22 E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ca-144 4.88E-07 2.04E-07 2.62E-08 0.00E+O0 1.21E-07 O.OOE+00 1.65E-04 Pr-143 9.20E-09 3.69E-O9 4.56E-10 0.00E+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.01 E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 O.OOE+00 4.25E-09 0.00E+O0 3.49E-05 Ta-183 4.77E-11 2.92E-10 2.39E-11 0.00E+00 1.66E-10 0.00E+00 1.76E-04 V\M87 1.03E-07 8.61E-O8 3.01 E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.82E-05 Re-188 2.42E-07 1.90E-07 5.37E-07 1.26E-05 0.00E+00 0.00E+00 1.56E-O5 Au-198 0.00E+00 1.12E-08 1.90E-08 0.00E+00 3.42E-08 O.OOE+00 8.67E-06 Au-199 0.00E+O0 7.00E-08 5.89E-08 O.OOE+00 2.74E-07 0.00E+00 1.13E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 O.OOE+00 2.40E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E+00 2.18E-06 7.95E-05 St>-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE+00 1.38E-06 1.97E-05
ODCM Page: 17 Rev.: 21 Table 2.3-6 Inoestion Dose Factors for Taenaoer (mrem/pCi ingested)
WHOLE BODY THYROID KIDNEY LUNG GH-LJ SOTOPE BONE LIVER 1.06E-07 1.06E-07 1.08E-07 0.00E+00 1.06E-07 1.08E-07 1.06E-07 H-3 8.12E-07 8.12E-O7 8.12E-07 8.12E-07 4.06E-06 8.12E-07 8.12E-07 C-14 2.30E-06 2.30E-06 2.30E-06 2.30E-O6 Na-24 2.30E-C6 2.30E-06 2.30E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-05 P-32 2.76E-O4 1.71E-05 1.07E-05 7.89E-10 5.14E-09 6.05E-07 O.OOE+00 O.OOE+00 3.60E-09 2.00E-09 Cr-51 O.OOE+00 1.76E-O6 O.OOE+00 1.21 E-05 Mn-54 0.00E+00 5.90E-06 1.17E-06 O.OOE+00 2.00E-07 O.OOE+00 1.04E-05 O.OOE+00 1.58E-07 2.81 E-08 Mn-56 O.OOE+00 O.OOE+00 1.70E-06 1.16E-06 Fe-55 3.78E-06 2.68E-06 8.25E-07 O.OOE+00 4.32E-06 3.24E-05 5.87E-06 1.37E-05 5.29E-06 O.OOE+00 Fe-59 2.24E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.34E-05 Co-58 O.OOE+00 9.72E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-05 O.OOE+00 2.81 E-06 6.33E-06 Co-60 O.OOE+00 O.OOE+00 O.OOE+00 1.99E-06 1.77E-O4 1.25E-05 6.00E-06 Ni-63 O.OOE+00 O.OOE+00 5.19E-06 7.49E-07 9.57E-08 4.36E-08 O.OOE+00 Ni-65 3.19E-7 2.81 E-07 1.32E-05 3.54E-07 1.07E-06 O.OOE+00 2.74E-07 Cu-64 O.OOE+00 2.91 E-07 O.OOE+00 8.92E-06 O.OOE+00 1.15E-07 5.41 E-08 Cu-67 1.28E-05 O.OOE+00 8.47E-O6 5.76E-06 2.00E-05 9.33E-06 O.OOE+00 Zn-65 O.OOE+00 1.83E-08 O.OOE+00 5.16E-08 Zn-69 1.47E-08 2.80E-08 1.96E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.74E-08 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.22E-08 Br-84 3.05E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 1.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.41 E-06 Rb-86 O.OOE+00 2.98E-05 O.OOE+00 O.OOE+00 O.OOE+00 7.30E-15 Rb-88 O.OOE+00 8.52E-08 4.54E-08 3.89E-08 O.OOE+00 O.OOE+00 O.COE+00 8.43E-17 Rb-89 O.OOE+00 5.50E-C8 4.40E-9 3.00E-08 9.91 E-09 2.42E-07 Sr-87M 2.81 E-8 2.18E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.24E-05 Sr-89 4.40E44 O.OOE+00 1.28E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-04 8.30E-03 O.OOE+00 2.05E-03 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 3.68E-06 8.07E-06 O.OOE+00 3.21 E-07 O.OOE+00 Sr-91 1.30E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.77E-05 Sr-92 3.05E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-04 Y-90 1.37E-08 O.OOE+00 3.69E-10 O.OOE+00 O.OOE+00 6.09E-09 1.29E-10 O.OOE+00 4.93E-12 O.OOE+00 Y-91M 5.39E-09 O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 Y-91 2.01 E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.32E-05 Y-92 1.21E-09 O.OOE+00 3.50E-11 O.OOE+00 O.OOE+00 O.OOE+CO 1.17E-04 Y-93 3.83E-09 O.OOE+00 1.05E-10 O.OOE+00 1.91 E-08 O.OOE+00 3.00E-05 Zr-95 4.12E-08 1.30E-08 8.94E-09 7.11E-10 O.OOE+00 1.27E-04 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 Zr-97 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-95 8.22E-09 4.56E-09 2.51 E-09 O.OOE+00 1.38E-05 O.OOE+00 1.08E-05 O.OOE+00 6.03E-06 1.15E-06 Mo-99 O.OOE+00 1.38E-08 5.14E-10 6.08E-07 3.32E-10 9.26E-10 1.20E-08
ODCM Page: 18 Rev.: 21 Table 2.3-6 (Cont.)
Inoestion Dose Factors for Teenager imrem/pCi ingested")
WHOLE BODY THYROID KIDNEY LUNG GI-LU ISOTOPE BONE LIVER 5.O3E-09 0.00E+O0 9.26E-09 3.12E-10 8.75E-17 To-101 3.60E-10 5.12E-10 O.OOE+00 1.09E-07 0.00E+OO 8.99E-07 O.OOE+00 2.13E-05 Ru-103 2.55E-07 O.00E-KK) 8.46E-09 0.00E+OO i75E-O7 0.00E+O0 1.76E-05 Ru-105 2.18E-08 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ru-106 3.92E-06 O.OOE+00 1.18E-07 0.O0E+00 3.70E-O7 0.00E+00 5.45E-O5 Ag-HDM 2.05E-07 1.94E-O7 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-125M 3.83E-06 1.38E-O6 3.43E-06 1.15E-06 2.30E-06 3.92E-O5 0.00E+00 2.41 E-05 Te-127M 9.67E-06 1.09E-07 6.40E-07 0.00E+00 1.22E-O5 Te-127 1.58E-07 5.60E-08 3.40E-08 6.05E-06 2.58E-06 5.26E-O6 6.82E-05 0.00E+O0 6.12E-O5 Te-129M 1.63E-05 1.09E-08 3.20E-08 1.88E-O7 0.00E+00 2.45E-07 Te-129 4.48E-08 167E-O8 9.76E-O7 1.76E-06 122E-05 0.00E+00 9.39E-O5 Te-131M 2.44E-06 1.17E-06 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-131 2.79E-08 1.15E-08 8.72E-09 2.08E-06 2.33E-06 2.12E^)5 0.00E+O0 7.00E-05 Te-132 3.49E-06 2.21 E-06 Z98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-O6 1-130 1.03E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-O6 1-131 5.85E-O6 8.19E-O6 2.62E-07 2.46E-05 1.15E-O6 O.OOE+00 3.18E-07 1-132 2.79E-07 7.30E-07 4.76E-04 5.98E-06 O.OOE+00 2.58E-O6 1-133 2.01 E-06 3.41 E-06 1.04E-06 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-O9 1-134 1.46E-07 3.87E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0.00E+O0 1.74E-06 M35 6.10E-07 O.O0E+00 6^6E-05 2.39E-05 2.45E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 1.B4E-O5 2.90E-06 2.72E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 5.19E-05 0.00E+O0 5.07E-O5 1.97E-05 2.12E-06 Cs-137 1.12E-04 1.49E-04 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Cs-138 7.76E-08 1.49E-07 O.00E+O0 9.22E-11 6.74E-11 1.24E-06 Ba-139 1.39E-07 9.78E-11 4.05E-09 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-O5 Ba-140 2.84E-05 3.48E-08 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-141 6.71 E-08 5.01 E-11 2.24E-O9 0.00E+00 Z53E-11 1.99E-11 9.18E-20 Ba-142 2.99E-08 299E-11 1.84E-09 O.OOE+00 0.00E+00 0.00E+00 9.82E-O5 La-140 3.48E-09 171E-09 4.55E-10 0.O0E+O0 O.OOE+00 0.00E+00 2.42E-06 La-142 1.79E-10 7.95E-11 1.98E-11 0.OOE+00 4.18E-09 0.00E+00 2.54E-05 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-143 2.35E-09 1.71 E-08 1.91E-10 2.88E-07 3.74E-08 O.OOE+00 1.72E-07 0.00E+00 1.75E-04 Ca-144 6.96E-07 6.52E-10 0.00E+00 3.04E-O9 O.OOE+00 4.31 E-05 Pr-143 1.31 E-08 5.23E-09 0.00E+00 1.01 E-11 O.OOE+00 4.74E-14 Pr-144 4.30E-11 1.76E-11 2.1BE-12 6.11E-10 0.00E+O0 5.99E-09 O.OOE+00 3.68E-05 Nd-147 9.38E-09 1.02E-08 3.42E-11 0.00E+00 2.37E-10 O.OOE+00 1.86E-04 Ta-183 6.81 E-11 4.15E-10 0.00E+00 0.00E+00 O.OOE+00 3.22E-O5 W-187 1.46E-07 119E-07 4.17E-08 7.66E-07 1.68E-05 O.OOE+00 O.OOE+00 2.33E-05 Re-188 3.45E-07 2.70E-07 2.72E-08 0.O0E+00 4.88E-08 0.00E+O0 9.84E-06 Au-198 0.00E+00 1.60E-08 O.OOE+00 3.92E-07 0.00E+00 1.17E-05 Au-199 0.00E+00 9.92E-08 8.41 E-08 9.22E-11 O.OOE+00 5.21 E-10 O.OOE+00 2.67E-05 Np-239 1.76E-09 1.66E-10 1.51 E-06 8.78E-09 0.00E+00 3.38E-06 7.80E-05 Sb-124 3.87E-0B 7.13E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 193E-05 Sb-125 2.46E-06 Z71E-08
ODCM Page: 19 Rev.: 21 Table 2.3-7 Inaestion Dose Factors for Child (mrem/oCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LU O.OOE+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 H-3 2.42E-06 2.42E-06 2.42E-O6 2.42E-08 2.42E-06 2.42E-06 C-14 1.21E-05 5.80E-O6 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 Na-24 5.80E-06 8.25E-04 3.86E-O5 3.18E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.28E-05 P-32 O.OOE+00 O.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Cr-51 1.07E-05 2.85E-08 O.OOE+00 3.00E-06 O.OOE+00 8.98E-06 Mn-54 O.OOE+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-05 Mn-56 O.OOE+00 6.10E-06 1.89E-06 O.OOE+00 O.OOE+00 3.45E-06 1.13E-06 Fe-55 1.15E-05 1.65E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7.74E-06 2.78E-05 Fe-59 Co-58 O.OOE+00 1.80E-06 5.51 E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.05E-05 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-05 Co-60 Ni^3 5.38E-04 2.88E-05 1.83E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-06 2.09E-07 1.22E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 Ni-65 2.22E-06 2.52E-06 O.OOE+00 7.83E-07 8.74E-07 7.81 E-07 3.89E-05 Cu-64 9.21 E-07 Cu-67 O.OOE+00 2.45E-07 1.48E-07 O.OOE+00 5.92E-07 O.OOE+00 1.15E-05 1.37E-05 3.65E-05 2.27E-05 O.OOE+00 2.30E-05 O.OOE+00 6.41 E-06 Zn-65 6.33E-O8 5.85E-09 O.OOE+00 3.84E-08 O.OOE+00 3.99E-06 Zn-69 4.38E-08 Br-83 O.OOE+00 O.OOE+00 1.71 E-07 0.00E+O0 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.98E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+00 O.OOE+00 0.0OE+OC O.OOE+00 O.OOE+00 6.70E-05 4.12E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.31 E-06 Rb-86 1.9OE-O7 1.32E-Q7 O.OOE+00 O.OOE+00 O.OOE+00 9.32E-09 Rb-88 O.OOE+00 O.OOE+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-09 Rb-89 Sr-87M 5.47E-08 6.78E-08 O.OOE+00 1.34E-08 6.65E-08 2.57E-O8 6.66E-07 1.32E-03 O.OOE+00 3.77E-O5 O.OOE+00 O.OOE+00 O.OOE+00 5.11E-05 Sr-89 4.31 E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.29E-04 Sr-90 170E-02 O.OOE+00 O.OOE+00 9.06E-O7 O.OOE+00 O.OOE+00 O.OOE+00 5.30E-05 Sr-91 2.40E-05 O.OOE+00 3.62E-O7 O.OOE+00 O.OOE+00 O.OOE+00 1.71E-04 Sr-92 9.03E-06 4.11E-08 O.OOE+00 1.10E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-04 Y-90 Y-91M 3.82E-10 O.OOE+00 1.39E-11 O.OOE+00 O.OCE+00 O.OOE+00 7.48E-O7 6.02E-07 O.OOE+00 1.61E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.02E-05 Y-91 3.60E-09 O.OOE+00 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.04E-04 Y-92 1.14E-08 O.OOE+00 3.13E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.70E-04 Y-93 2.55E-08 2.27E-08 O.OOE+00 3.65E-08 O.OOE+00 2.66E-05 Zr-95 1.16E-07 6.99E-09 1.01E-09 5.96E-10 O.OOE+00 1.45E-09 O.OOE+00 1.53E-04 Zr-97 8.76E-09 6.26E-09 O.OOE+00 8.23E-09 O.OOE+00 1.62E-05 Nb-95 2.25E-08 1.33E-05 3.29E-06 O.OOE+00 2.84E-05 O.OOE+00 1.10E-05 Mo-99 O.OOE+00 9.23E-10 1.81E-09 3.00E-08 O.OOE+00 2.63E-08 9.19E-10 1.03E-06 T0-99M
ODCM Page: 20 Rev.: 21 Table 2.3-7 (Cont.)
Inaestion Dose Factors for Child (mrem/pCi ingested)
WHOLE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE 1.12E-09 1.42E-O8 O.OOE+00 1.91 E-08 5.92E-10 3.56E-09 To-101 1.07E-09 Ru-103 7.31 E-07 O.OOE+00 2.81 E-07 0.00E+00 1.84E-06 O.OOE+00 1.89E-05 Ru-105 6.45E-08 O.OOE+00 2.34E-08 0.00E+00 5.67E-07 O.OOE+00 4.21 E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 0.00E+00 1.58E-05 O.OOE+00 1.82E-04 3.64E-07 2.91 E-07 O.OOE+00 6.78E-07 0.00E+D0 4.33E-05 Ag-110M 5.39E-07 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 O.OOE+00 1.10E-O5 Te-127M 2.89E-05 7.78E-08 3.43E-06 6.91 E-06 8.24E-05 O.OOE+00 2.34E-05 4.71 E-07 1.27E-07 1.01 E-07 3.28E-07 1.34E-06 0.00E+O0 1.84E-O5 Te-127 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131M 7.20E-06 2.49E-O6 2.65E-06 5.12E-06 2.41 E-05 O.OOE+00 1.01E-04 8.30E-08 2.53E-08 2.47E-O8 6.35E-08 2.51 E-07 0.00E+00 4.36E-07 Te-131 1.01E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-O5 O.OOE+00 4.50E-05 Te-132 M30 2.92E-06 5.9OE-O6 3.04E-06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 1.72E-05 1.73E-0S 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-O6 H31 H32 8.00EO7 1.47E-06 6.76E-07 6.82E-05 2.25BO6 0.00E+00 1.73E-06 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-O5 0.00E+00 2.95E-06 M33 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 M34 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-O6 1-135 2.34E-04 3.84E-04 8.10E-05 O.OOE+00 1.19E-O4 4.27BO5 2.07E-08 Cs-134 2.35E-05 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E-06 2.27E-06 Cs-136 3.27E-04 3.13E-04 4.62E-05 O.OOE+00 1.02E-O4 3.67E-05 1.96E-06 Cs-137 C&-138 2.28E-07 3.17E-07 2.01 E-07 0.00E+00 2.23E-07 2.40E-O8 1.46E-07 Ba-139 4.14E-O7 2.21 E-10 1.20E-08 O.OOE+00 1.93E-10 1.30E-10 2.39E-05 7.28E-08 4.85E-06 O.OOE+00 2.37E-08 4.34E-08 4.21 E-05 Ba-140 8.31 E-05 Ba-141 2.00E-07 1.12E-10 6.51 E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+00 5.09E-11 3.70E-11 1.14E-09 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-140 5.24E-10 1.67E-10 5.23E-11 O.OOE+00 O.OOE+00 0.00E+00 3.31 E-05 La-142 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-O9 0.00E+00 2.47E-05 Ce-141 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-143 2.08E-06 6.52E-07 1.11E-07 0.00E+O0 3.61E-07 0.00E+00 1.70E-04 Ce-144 Pr-143 3.93E-08 1.18E-O8 1.95E-09 O.OOE+00 6.39E-09 0.00E+00 4.24E-05 3.99E-11 6.49E-12 0.00E+00 2.11E-11 O.OOE+00 8.59E-08 Pr-144 1.29E-10 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 Nd-147 2.79E-08 Z26E-08 2.04E-10 9.40E-10 1.02E-10 O.OOE+00 4.98E-10 O.OOE+00 2.07E-04 Ta-183 4.29E-07 2.54E-07 1.14E-07 O.OOE+00 O.OOE+00 0.00E+00 3.57E-05 W-187 Re-188 1.03E-06 6.12E-07 2.29E-06 5.03E-O5 O.OOE+00 O.OOE+00 4.12E-05 Au-198 O.OOE+00 3.61 E-08 8.12E-08 O.OOE+00 1.02E-07 0.00E+00 1.20E-05 Au-199 O.OOE+00 2.25E-07 2.51 E-07 O.OOE+00 8.23E-07 0.00E+00 1.27E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 O.OOE+00 2.79E-05 1.44E-07 3.89E-06 2.45E-08 O.OOE+00 6.16E-06 6.94E-O6 St>124 1.11 E-05 Sb-125 7.18E-08 5.52E-06 1.50E-06 6.63E-09 O.OOE+00 3.99E-06 1.71 E-06
ODCM Page: 21 Rev.: 21 Table 2.3-8 WHOLE BODY THYROID KIDNEY LUNG GI-LU ISOTOPE BONE UVER 3.08E-07 3.08E-07 3.08E-07 3.08E-07 H-3 O.OOE+00 3.08E-07 3.08E-07 5.06E-06 5.06E-06 5.06E-06 5.06E-06 C-14 2.37E-45 5.06E-06 5.06E-06 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 Na-24 1.01E-05 1.01 E-05 1.01 E-05 6.59E-05 0.00E+00 O.OOE+00 O.OOE+00 2.30E-05 P-32 1.70E-03 1.00E-04 141E-08 9.20E-09 2.01 E-09 1.79E-08 4.11E-07 Cr-61 O.OOE+00 O.OOE+00 1.99E-05 4.51 E-06 0.00E+00 4.41 E-06 O.OOE+00 7.31 E-06 Mn-54 O.OOE+00 1.41E-07 O.OOE+00 7.03E-07 O.OOE+00 7.43E-05 Mn-56 0.00E+O0 8.18E-07 2.40E-06 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 Fe-55 1.39E-05 8.98E-06 0.00E+00 O.OOE+00 1.59E-05 2.57E-05 Fe-59 3.08E-O5 5.38E-05 2.12E-05 O.OOE+00 O.OOE+00 8.97E-06 Co-58 O.OCE+OO 3.60E-06 8.98E-06 O.OOE+00 2.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.57E-05 Co-60 O.OOE+00 1.08E-05 0.00E+00 O.OOE+00 O.OOE+00 1.95E-06 Ni-63 6.34E-04 3.92E-05 2.20E-05 2.42E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.05E-05 Ni-65 4.70E-06 5.32E-O7 O.OOE+00 4.93E-06 4.98E-06 4.87E-O6 1.36E-05 Cu-64 5.26E-06 1.42E-05 2.82E-07 0.00E+00 1.03E-06 O.OOE+00 1.25E-05 Cu-87 0.00E+O0 6.09E-07 2.91 E-05 0.00E+00 3.06E-05 O.OOE+00 5.33E-05 Zn-65 1.84E-05 6.31 E-05 1.25E-08 O.OOE+00 6.98E-08 O.OOE+00 1.37E-O5 Zn-69 9.33E-0B 1.68E-07 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 3.63E-07 3.62E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 0.00E+00 1.94E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 8.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.35E-06 Rb-86 O.OOE+00 1.70E-O4 2.73E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.85E-07 Rb-88 O.OOE+00 4.98E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.74E-08 Rb-89 O.OOE+00 2.86E-07 1.97E-O7 4.70E-08 1.37E-07 7.71 E-08 1.49E-06 Sr-87M 2.22E-07 1.56E-07 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 5.16E-O5 Sr-89 2.51 E-03 O.OOE+00 7.20E-05 4.71 E-03 0.00E+00 O.OOE+00 O.OOE+00 2.31 E-04 Sr-90 1.85E-02 O.OOE+00 1.81 E-06 0.00E+00 O.OOE+00 O.OOE+00 5.92E-05 Sr-91 5.OOE-05 O.OOE+CO 7.13E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Sr-92 1.92E-05 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1.20E-04 Y-90 8.69E-08 O.OOE+00 2.33E-C9 O.OOE+00 2.76E-11 O.OOE+00 O.OOE+00 O.OOE+00 2.70E-06 Y-91M 8.10E-10 3.01 E-08 0.00E+00 O.OOE+00 O.OOE+00 8.10E-06 Y-91 1.13E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.46E-04 Y-02 7.65E-09 O.OOE+00 2.15E-10 6.62E-10 0.OOE+O0 O.OOE+00 O.OOE+00 1.92E-04 Y-93 2.43E-08 O.OOE+00 3.56E-08 0.00E+O0 5.41 E-08 O.OOE+00 2.50E-05 Zr-95 2.06E-G7 5.02E-08 O.OOE+00 2.56E-09 O.OOE+00 1.62E-04 Zr-97 1.48E-08 2.54E-09 1.16E-09 1.00E-08 O.OOE+00 1.24E-08 O.OOE+00 1.46E-05 Nb-95 4.20E-08 1.73E-08 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 O.OOE+00 112E-O5 Mo-99 O.OOE+00 5.10E-08 O.OOE+00 4.26E-08 2.07E-09 1.15E-06 To99M 1.92E-Q9 3.96E-09
ODCM Page: 22 Rev.: 21 Table 2.3-8 (Cont.)
Inaestion Dose Factors for Infant fmrem/pCi Ingested)
WHOLE LIVER BODY THYROID KIDNEY LUNG GI-LLJ ISOTOPE BONE 2.86E-09 2.83E-08 O.OOE+00 3.40E-48 1.56E-09 4.86E-O7 Tc-101 2.27E-09 0.00E-KX3 4.95E-07 O.OOE+00 3.08E-06 O.OOE+00 1.80E-05 Ru-103 1.48E-06 0.00E+O0 4.58E-08 O.OOE+00 1.00E-06 O.OOE+00 5.41E-05 Ru-105 1.36E-07 2.41 E-05 0.00E+O0 3.01 E-06 O.OOE+00 Z85E-05 O.OOE+00 1.83E-O4 Ru-106 9.96E-07 7.27E-07 4.81 E-07 O.OOE+00 1.04E-06 O.OOE+00 3.77E-05 AQ-110M Te-125M 2.33E-05 7.79E-06 3.15 E-06 7.84E-06 O.OOE+00 O.OOE+00 1.11E-05 5.85E-05 1.94E-05 7.08E-06 189E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127M 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-127 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+00 5.97E-05 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+00 2.27E-O5 Te-129 1.52E-O5 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 1.03E-O4 Te-131M 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+00 7.11E-06 Te-131 2.08E-05 1.03E-0S 9.61 E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 Te-132 5.30E-06 1.48E-03 1.45E-05 O.OOE+00 2.83E-O6 H30 6.00E-06 1.32E-05 3.59E-05 4.23E-O5 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 H31 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-O6 H32 1.66E-06 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 O.OOE+00 3.08E-06 1-133 1.25E-05 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 1-134 8.69E-07 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 1-135 3.64E-06 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91 E-06 Cs-134 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.10E-05 2.05E-06 Cs-136 5.22E-04 6.11E-04 4.33E-05 O.OOE+00 1.64E-04 6.64E-05 1.91 E-06 Cs-137 Cs-138 4.81 E-07 7.82E-07 3.79E-07 O.OOE+00 3.90E-07 6.09E-08 1.25E-08 5.84E-10 2.55E-08 O.OOE+00 3.51 E-10 3.54E-10 5.58E-05 Ba-139 8.81 E-07 1.71 E-07 8.81 E-06 O.OOE+00 4.06E-08 1.05E-07 4.20E-05 Ba-140 1.71 E-04 4.25E-07 2.91 E-10 1.34E-08 O.OOE+00 1.75E-10 1.77E-10 5.19E-O6 Ba-141 Ba-142 1.84E-07 153E-10 9.06E-09 O.OOE+00 8.81 E-11 9.26E-11 7.59E-07 8.32E-09 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.77E-05 La-140 2.11E-08 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.86E-O5 La-142 1.10E-09 4.80E-08 5.65E-09 O.OOE+00 1.48E-08 O.OOE+00 2.48E-06 Cfr-141 7.87E-08 Ce-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 O.OOE+00 5.73E-05 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E^)4 Ce-144 2.98E-06 3.04E-08 4.03E-09 O.OOE+00 1.13E-O8 O.OOE+00 4.29E-05 Pr-143 8.13E-08 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-11 O.OOE+00 4.93E-06 Pr-144 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-O5 Nd-147 5.53E-08 5.68E-08 2.49E-09 2.17E-10 O.OOE+00 9.05E-10 O.OOE+00 2.10E-O4 Ta-183 4.33E-10 6.28E-07 2.17E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.69E-05 W-187 9.03E-07 1.62E-06 4.86E-06 1.25E-04 O.OOE+00 O.OOE+00 4J2E-05 Re-188 2.20E-06 Au-198 0.00E-KK) 9.56E-08 1.73E-07 O.OOE+00 1.B6E-07 O.OOE+00 1.25E-05 5.32E-07 O.OOE+00 1.49E-06 O.OOE+00 1.28E-05 Au-199 O.OOE+00 5.91 E-07 9.93E-10 5.61 E-10 O.OOE+00 1.98E-09 O.OOE+00 2.67E-05 Np-239 1.11E-08 3.15E-07 6.63E-06 5.08E-08 O.OOE+00 1.34E-05 6.60E-05 Sb-124 2.14E-05 2.53E-06 1.54E-08 O.OOE+00 7.72E-06 1.64E-05 Sb-125 1.23E-05 1.19E-O7
ODCM Page: 23 Rev.: 21 Table 2.3-9 (mrem/h per pCi/m2)
Element Whole Bodv Skin H-3 0.0 0.0 O14 0.0 0.0 Na-24 2.50E-08 2.9OE-O8 P-32 0.0 0.0 2.20E-10 2.60E-10 Cr-51 Mn-54 5.80E-09 6.80E-O9 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 8.00E-09 9.40E-09 Fe-59 7.00E-09 8.20E-09 Co-58 1.70E-08 2.00E-O8 Co^O Nh63 0.0 0.0 3J0E-09 4.30E-09 Nr-65 Cu-64 1.50E-09 1.70E-09 Cu-67 1.40E-09 2.14E-9 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 1.20E-08 1.40E-08 Br-84 Br-85 0.0 0.0 6.30E-10 7.20E-10 Rb-86 Rb-88 3.50E-09 4.00E-09 1.50E-08 1.80E-08 Rb-89 4.05E-09 5.36E-09 Sr-87M 5.60E-13 6.50E-13 Sr-89 7.10E-09 8.30E-09 Sr-91 9.00E-09 1.00E-08 Sr-92 Y-9O 2.20E-12 2.60E-12 3.80E-09 4.40E-09 Y-91M Y-91 2.40E-11 2.70E-11 1.60E-09 1.90E-09 Y-92 5.70E-10 7.80E-10 Y-93 5.00E-09 5.80E-09 Zr-95 5.50E-09 6.40E-09 Zr-97 5.10E-09 6.00E-09 Mo-95 1.90E-09 2.20E-09 Mo-99 TC-99M 9.60E-10 1.10E-09 2.70E-09 3.00E-09 To101 3.60E-09 4.20E-09 Ru-103 4.50E-09 5.10E-09 Ru-105 1.50E-09 1.80E-09 Ru-106
ODCM Page: 24 Rev.: 21 Table 2.3-9 (Cont)
(mrem/h per pCi/m2)
Element Whole Bodv Skin Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 T6-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 Sb-124 2.28E-08 6.93E-08 Sb-125 5.67E-09 7.96E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-O8 Cs-137 4.20E-09 4.90E49 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00E+OO 0.00E+00 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 Ta-183 3.76E-09 7.30E-09 W-187 3.10E-09 3.60E-09 Re-188 7.86E-10 1.18E-07 Au-198 5.33E-09 3.36E-08 Au-199 1.13E-9 1.39E-09 Np-239 9.50E-10 1.10E-09
ODCM Page: 25 Rev.: 21 Table 2.3-10 Liquid Effluent Dilution Factors (fA>)
Maximum Individual Dilution Factors Pathway Location Mp Potable Water Ingestion 3.9 miles WSW of site 32.2 Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 miles ENE of Site 14.5 Population Dose Dilution Factors*
Pathway Location Mp Potable Water Ingestion Population Weighted Average 314 Fresh Water Fish Ingestion Catch Weighted Average 77.4 Shoreline Exposure 7.7 miles WSW of site 162
~~for total population and average individual dose calculations Table 2.3-11 Transit Times Reauired for Nuclides to Reach the Point of Exposure (\b)~~
Maximum Average Exposed Exposed Individual Individual*
Eventual transit time for water ingestion 12 h 24 h Eventual transit time for fish ingestion 24 h 168 h Eventual transit time for shore exposure Oh Oh
~~for total population and average individual dose calculations~~
ODCM Page: 26 Rev.: 21 Table 2.3-12 Llsffpa Factors IU<<>>)
Maximum Average Exposed Exposed Individual Individual*
Water ingestion (L/yr) Adult 730 370 Water ingestion (L/yr) Teen 510 260 Water ingestion (L/yr) Child 510 260 Water ingestion (L/yr) Infant 330 -
Fresh water fish ingestion (kg/yr) Adult 21 6.9 Fresh water fish ingestion (kg/yr) Teen 16 5.2 Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant Shore exposure (h/yr) Adult 12 8.3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 Shore exposure (h/yr) Infant -
~~for total population and average individual dose calculations~~
ODCM Page: 27 Rev.: 21 Table 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP The total population dilution factor of 314 is population weighted using dilution factors for each of the potable water intakes within 50 miles of PNPP.
Weighted Dist Fraction of Dilution Dilution Pooulation PoDulatlon Factor Factor Intake (Mil PJE Ohio American 20 ENE 38.500 2.12E-O2 187.7 3.98E+00 Water Serv. Co.
33 ENE 13,500 7.43E-03 238.2 1.77E+00 Conneaut Avon Lake 50 WSW 99,500 5.48E42 388.5 2.13E+O1 35 SW 1,437.000 7.92E-01 326.7 2.59E+02 Cleveland Fairport Harbor 7 WSW 3,200 1.76E-03 154.2 2.71&O1 3.5 WSW 10,258 5.65E-03 107.4 6.07E-01 Lake County East Lake County West 15 WSW 85,000 4.68E-02 220.0 1.03E+01 WSW 60,000 3.30E-02 181.9 6.00E+00 Ohio Water Serv. 10 7.5 WSW 27,000 1.49E-02 159.3 2.37E+00 Painesville Kent County Water 50 NW 42000 2.31 E-02 388.5 8.97E+00 Supply TOTALS 1,815,958 1.00E+0 TOTAL DF 3.14E+02 Dist Dir Population = distance, direction, and population values obtained from the 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP" (Ref. SO-11552 "E").
Fraction of Population The ratio of the population receiving drinking water from that intake to the total population number for all drinking water intakes located within 50 mites of PNPP.
Dilution Factor = Values obtained from the Perry Environmental Report - Operating License Stage:
Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" and Q&R Page 2.1-2. Lake County West dilution factor per interpolation. Kent County Water Supply dilution factor was estimated.
The Weighted Dilution Factor (Fraction of Population) x (Dilution Factor), based on the population for each drinking water intake; the sum of which is to be used as the potable water total population dilution factor for radioactive liquid effluent releases from PNPP.
ODCM Page: 28 Rev.: 21 Table 2.3-14 nn.ittnn Factors for the Fi<<h inoestion Pathway Individual Grid Locations The total population dilution factor ofJJA is catch distance and volume weighted using dilution factors at thoseSins. Fish harvest is based on Ohio Department of Natural Resources the total angler catch (1987 annual) values for Lake Erie within 50 mile of PNPP.
Fraction Distance (Frac Fish)x Grid No. of (mi) (Dil Factor)
Fish of Fish 29 3.60E+00 617 52823 3.91 E-02 5.63E+00 618 76004 5.63E-02 36 3.96E+00 714 102522 7.59E-02 9 7.95E-03 9 4.13E-01 715 10743 11 8.21 E-01 716 19817 1.47E-02 24 4.51 E+00 717 73401 5.43E-02 33 8.34E+00 718 118676 8.78E-02 48 0.00E+00 809 0 0.00E+00 39 3.07E-01 810 3953 2.93E-03 30 9.29E-01 811 13648 1.01 E-02 22 1.96E+00 812 33923 2.51 E-02 13 8.25E+00 813 182663 1.35E-01 4 4.14E+00 814 164369 1.22E-01 50 6.93E+00 909 80753 5.98E-02 3.24E-02 42 3.57E+00 910 43800 33 8.26E+00 911 117430 8.69E-02 24 1.S8E+01 912 ?56529 1.90E-01 1.00E+00 7.74E+01 TOTAL 1351054 Grid No and No of Fish = Total angler catch (1987 annual) for each grid location; per letter from
£IrC Fairport Fisheries Research Station, Ohio Department of Natural Resources to Rktad oftflbN). Commercial harvest data were not used as they were drfTerent.ated by harbor location only, not by geographical grid location.
Fraction of Fish = The ratio of the fish caught in that grid to the total number of fish caught in all grids located within 50 miles of PNPP.
Distance = Distance to the center of that grid from PNPP, In miles.
Dilution Factor = Derived, for the appropriate distance (centerofeach grid), from an'al average dilution factor data (non-adjusted), per Perry Environmental Report - Operating License Stage, Table 5.1-10
-Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP.
(Fraction of Fish) x (Dilution Factor) - The weighted dilution factor, based on catch, for eachi grid; thesum ofXh isto be used as the fish ingestion total population dilution factorfbr radioactive liquid effluent releases from PNPP.
ODCM Page: 29 Rev.: 21 Table 2.3-15 Dilution Factors for the Shore Exposure Pathway MAXIMUM EXPOSED INDIVIDUAL DILUTION FACTOR TTie point of exposure assumed for this pathway is the shoreline at the PNPP site boundary 0.7 mites down shore from the plant discharge structure. Interpolation of the data presented in the Perry Environmental Report - Operating License Stage, Table 5.1-10, "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" yields a maximum individual dose dilution factor of 14.5 (dilution factor unadjusted for current frequency).
TOTAL POPULATION DILUTION FACTOR The total population dilution factor of 162 is that of the Headlands Beach State Park, 7.7 miles WSW of PNPP (interpolated, adjusted WSW dilution factor). This location was selected because of its lake site location and it has, by far, the highest attendance of any park located in vicinity of PNPP (Perry Environmental Report - Operating License State, Table 2.1-2 "Major Camps and Parks within 10 Miles of the PNPP").
ODCM Page: 30 Rev.: 21 3.0 GASEOUS EFFLUENTS 3.0.1 Batch Releases A batch release is the discontinuous discharge of gaseous radioactive effluents of known radionudide concentration(s) and flowrate taking place over a finite period of time, usually hours or days. A batch release to the environment may occur as a result of an effluent flowpath that bypasses treatment or monitoring. Since radioactive releases approaching 10CFR20 limits are not anticipated, an ODCM Control is not entered for batch releases.
Every reasonable effort will be made to maintain the levels of radioactive matenal in the gaseous effluents ALARA.
The radioactive gaseous effluent release flowpath is monitored for principal gamma emitters (noble gases, particulatos, and halogens) as if the inoperable radioactive effluent monitor requirements of Table 3.3.7.10-1 had been entered. This action ensures the dose to a member of the general public is within the limits of Controls 3.11.2.2 and 3.11.2.3. If radioactivity is detected, the radionuclide concentration(s) is added to the dose calculations for the appropriate radioactive gaseous effluent continuous release point. Administrative instructions are employed to establish minimum monitoring requirements for these batch releases to ensure compliance with all regulatory requirements. The administrative instructions shall also ensure that the specific activity that will cause a batch release has been reviewed for the requirements of 10 CFR 50.59.
3.0.2 Continuous Releases There are four environmental release points for gaseous effluents used for Unit 1 operation of the Perry Nuclear Power Plant: Turbine BWg/Heater Bay Vent, Off-Gas Vent, Unit 1 Vent, and Unit 2 Vent (see Figure 3.0-1). The Unit 1 and Unlt2 Vents are located on the top of the Intermediate Building, Elevation 753'9". The Turbine Bldg/Heater Bay Vent is located on the top of the Heater Bay Building, Elevation 722*0". The Off-Gas Vent is located on the top of the Off-Gas Building, Elevation 723'0". Site ground level elevation is 620'0". Radiological releases from each vent are monitored by a noble gas radiation monitor.
All gaseous effluent releases from PNPP via these vents will be continuous releases, and are considered to be long-term (i.e., greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year) and ground level.
Containment/drywell purges and vents will be considered periods of increased radiological release as they are vented through the Unit 1 Vent, concurrent with normal, continuous releases.
ODCM Page: 32 Rev.: 21 3.1 Monitor Alarm Setpoint Determination The following calculation methods provide a means of determining the High Alarm Setpoint (HSP) and the Alert Setpoint (ASP) to ensure compliance with the regulatory dose rate limit to areas at or beyond the site boundary of 500 mrem/yr for the following noble gas monitors:
~~1. Unit 1 Vent radiation monitor (1D17K0786)~~
~~2. Unit 2 Vent radiation monitor (2D17K0786)~~
~~3. Off-Gas Vent radiation monitor (1D17K0836)~~
~~4. Turbine Building/Heater Bay Vent radiation monitor (1D17K0856)~~
The Unit 2 Vent radiation monitor is included for the operation of Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate Building ventilations are exhausted through the Unit 2 Vent.
The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70% of the annual dose rate limit (350 mrem/yr) and the Alert Setpoint (ASP) will be at 10% of the annual dose rate limit (50 mrem/yr).
NOTE: These values are set as a small fraction of the total activity that may be released via the monitored pathways to ensure that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without exceeding the 500 mrem/yr dose rate limit.
a. Upon receipt of a valid alert alarm, a sample from the alarming effluent path will be obtained and analyzed. If two or more effluent monitors exceed the ASP or if any one effluent monitor exceeds the HSP, the potential exists that the 500 mrem/yr dose rate limit may be exceeded.
~~In this case, all four effluent paths will be sampled and analyzed with the appropriate actions initiated to limit gaseous releases to below the annual dose rate limit~~
b. If a single high alarm setpoint continues to be exceeded, verification shall be made at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , via the gaseous effluent radiation monitors, that plant releases are below the ODCM Appendix C 3.11.2.1 dose rate limits. Sampling and analysis shall be performed on the four gaseous effluent release points at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
This procedure determines the monitor alarm setpoints that Indicate if the dose rate beyond the site boundary due to noble gas radionuclides in gaseous effluent released from the site exceeds 500 mrem/year to the whole body, or 3000 mrem/year to the skin.
ODCM Page: 33 Rev.: 21 3.1.1 Determination of "Mix" (Noble Gas Radionuclide Composition) of Gaseous Effluents
a. The gaseous source terms that are representative of the "mix" of the gaseous effluent are determined. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms will be those generated by the GALE code, Revision 0 for PNPP (FSAR Tables 11.3-9 and 11.3-10).
~~b. Determination of the fraction of the total radioactivity in the gaseous effluent for each noble gas radionuclide in the gaseous effluent.~~
£ (3.1-1)
Where:
Si = the fraction of the total for radionuclide "I" in the effluent; Ai = the activity of radionuclide T in the gaseous effluent.
NOTE: If the activity of a noble gas radionuclide is below the lower limit of detection the noble gas radionuclide is not included as a source term in this setpoint calculation.
3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit Qb = / a5? w \ (3-1-2)
Where:
Ob = the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for whole body exposure), nCi/s; kl = the whole body dose factor for a semMnfinlte cloud of radionuclide "i" (includes Sg/cm2 tissue attenuation) from Table 3.1-1, (mrem/yr)/(^Ci/m3);
si = the fraction of the total for radionuclide T, as per equation 3.1.1; yJQ = the annual average dispersion factor in s/m3 (see Appendix A);
NOTE: The dispersion parameters (x/Q) used in these calculations are the highest calculated site boundary values for any of the land-based sectors only. At PNPP the site boundary locations in the following sectors are totally over water N, NNE. NNW, NW, W, WNW.
500 = the whole body dose rate limit, in mrem/yr.
ODCM Page: 34 Rev.: 21 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 3000 Qs = (3-1-3)
Where:
qs the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in iiCi/s; the beta skin dose factor for a semHrrflntte cloud of radionudide "i" (includes attenuation by the outer "dead" layer of skin), in (mrem/yr)/(uCi/m3);
the gamma air dose factor for a uniform semi-infinite cloud of radionudide T, in (mrad/yr)/OiCi/m3);
the fraction of the total for radionudide T, per equation 3.1.1; the annual average dispersion factor in s/m3 (see Appendix A);
1.11 = the air dose to tissue dose equivalent conversion factor, in mrem/mrad; 3000 = the skin dose rate limit, in mrem/yr.
+ i . h Mi) values are shown in Table 3.1-1.
Table 3.1-1 Whole Bodv and Skin Dose Factors Whole Body Dose Factor (Ki) Skin Dose Factor Radionudide (b+1.11 Mi)
(mrem/yr/nCi/m3) (mrem/yr/uCi/m3) 7.56E-02 2.14E+01 Kr-83m 1.17E+03 2.83E+03 Kr-85m 1.61E+01 1.36E+03 Kr-85 5.92E+03 1.66E+04 Kr-87 1.47E+04 1.92E+04 Kr-88 1.66E+04 2.93E+04 Kr-89 9.15E+01 6.49E+02 Xe-131m 2.51 E+02 1.36E+03 Xe-133m 2.94E+02 6.97E+02 Xe-133 181E+03 3.99E+03 Xe-135 3.12E+03 4.44E+03 Xe-135m 1.42E+03 1.39E+04 Xe-137 8.83E+03 1.44E+04 Xe-13B 8.84E+03 1.30E+04 Ar-41
ODCM Page: 35 Rev.: 21 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent l2.12xlO"3l(Qt)
(3.1-4)
Where:
ct = the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the effluent, in jiCi/cc; f = the flow rate for the release point from the respective flow rate recorders, m tWmin; design flow rates, which incorporate a 10% flow rate inaccuracy correction, may be used in lieu of actual flow rates (refer to flow rates in Table 3.1-2).
Qt = the smaller of 2b and qs , calculated in equations 3.1-2 and 3.1-3, respectively, nCi/s; 2.12E-03 = the conversion factor to convert (nCi/sXfP/min), jiCi/cc.
Table 3.1-2 Flaw Rates and Effluent Monitor Efficiencies
~~r,<<*u.~~
Effluent Pathway Flow Rate (dm)
Ij Unit 1 Plant Vent i4Q,uuu Unit 2 Plant Vent 60>000 Off Gas Vent Pipe 16'700 400.000 (summer)
Turbine Building/Heater Bay 220.000 (winter/reduced summer)
ODCM Page: 36 Rev.: 21 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides Where:
au = the calculated monitor count rate above background attributed to noble gas radionuclides, in cpm; ct = the maximum acceptable radioactivity concentration, per equation 3.1-4, uCi/cc; _,. _.
E^ << the detector efficiency of the monitor for the "mix" of noble gas radionucfldes in the effluent, in cpm/(nCi/cc);
= the total uCi/cc concentration divided Into the net monitor count rate taken at the time the sample was taken; during the early period of operation, before a sufficient operational effluent source term data base has been obtained, the value will be calculated using monitor calibration data; 0.8 = an engineering safety factor.
3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP - (O.7O)(CRC)+BG (3-1"6)
Where:
HSP = the high alarm setpoint (including background), In cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm; crc = the calculated monitor net count rate, per equation 3.1-5, in cpm; 0 70 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.
3.1.5.2 Determination of the Monitor Alert Setpoint asp = (o.io)(crc)+ bg <3<1"7>
Where:
ASP = the alert setpoint (including background), in cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, In cpm; crc = the calculated monitor net count rate, per equation 3.1-5, cpm; 010 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.
ODCM Page: 37 Rev.: 21 3.2 10CFR20 Compliance - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied for the release period at the controlling location.
3.2.1 Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents is limited, by ODCM Appendix C controls, to 500 mrem/yr to the whole body and 3000 mrem/yr to the skin. Only the external dose pathway will be considered for noble gases. Because all gaseous effluent releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site boundary location (see Figure 3.3-1) with the highest relative dispersion factor (x/Q). (See Appendix A for elaboration on atmospheric dispersion.)
The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the ODCM, Appendix C, CONTROLS.
3.2.2 Radioiodines, Particuiates, and Other Radionuclides The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days is limited, by ODCM Appendix C controls, to 1500 mrem/yr to any organ. The calculation of dose rate from these radionuclides win be performed based on results of analyses obtained pursuant to those Appendix C controls. The controlling location for this limit is the location of the highest relative deposition (D/Q) for the period of release as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm animal locations In each sector.
3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseous effluents to areas at or beyond the site boundary for the purpose of showing compliance with ODCM Appendix C controls as related to 10CFR20.
-*a]p ~ i <<>.--*rt-i.v ii zr- *>*- /r-1 a- v-anci vu (3.2-1)
Where:
Dajp = the organ "j" dose rate as a function of age group "a" and pathway V. mrem/yr; DFai^ - the dose factor for organ type "j", age group "a", pathway "p" for isotope "i" (see Tables 3.2-1 through 3.2-3); units and equations used (equations 3.2-2 through 3.2-6) are provided later in this section; x/Q or D/Q = the normal or depleted relative dispersion factor (x/Q) in s/m3, or relative deposition (D/Q) in nr2, at the receptor distance (see Appendix A);
ODCM Page: 38 Rev.: 21 3.15x1 o1 = conversion factor to convert (mremVCi)/{Ci*s) to mram/yr; Qi = release rate of Isotope T (annualized), uCi/s
- (472)(Ci)(f)
Where:
Ci - the concentration of radionuclide T in the gaseous effluent, in nCi/cc; f = the gaseous effluent flow rate during the release, fP/min; 472 = conversion factor, PPM/i)
The following relationships are used to derive the dose factors (Df<<up)for noble gases, tritium, radioiodines and particulates used in equation 3.2-1.
~~a. Whole Body Dose Factors from Exposure to a SemMnflnite Plume Where:~~
~~DF. = the whole body factor due to immersion in a semi-infinite cloud of radionuclide "I", (mrem~~
~~m3)/(Ci~~
~~s);~~
= the whole body gamma dose factor for a semi-infinite cloud of radionuclide "i" which includes the attenuation of 5 g/cm2 of tissue from Table 3.2-4, mrem/yr per pCi/m3; sF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:
maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose rate = 1.0; Xi = the annual average concentration of radionuclide T in air (pCi/m3), for a unit release rate (Ci/yr) and a unit %/Q (s/m3), (pCi/rrr^Ci/yrXs/m3).
~~b. Skin Dose Factors for Exposure to a SemMnfinite Plume Where:~~
~~DF. = the skin dose factor due to immersion in a semi-infinite cloud of radionuclide T, (mrem~~
~~m3)/(Ci~~
~~s);~~
DfT = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "I", from Table 3.2-4, mraoTyr per pCi/m3; DSF i = the beta skin dose factor for a semi-infinite cloud of radionuclide T (includes attenuation by the outer "dead" layer of skin), from Table 3.2-4. mrem/yr per pCi/m3;
ODCM Page: 39 Rev.: 21 3t = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:
= maximum exposed individual 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose fate = 1.0, Xi = the annual average concentration of radionuclide Tin air (pCirni3), for a unit release rate (Ci/yr) and a unit x/Q (s/m9), (pCi/rrrWityrKs/m3);
1.11= the air dose to tissue dose equivalent conversion factor, mrem/mrad.
Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface DF,S..= (8760) (cfi ipFGin) fep)
Where:
/->
DF^_. = the dose factor for radionuclide T to organ f resulting from exposure to radionuclides deposited onto the ground surface, (mrem
~~m*)/Ci; C i = the ground plane concentration (pCi/m2) of radbnuclkJe "i" for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (nr2),~~
(pCirni^Ci/yrHrrr2);
D7G i, = the open field ground plane dose conversion factor for organ "j" from radionuclide T, from Table 3.2*6, mrem/yr per pCi/m2; sF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:
= maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose rate = 1.0; 8760 the number of hours per year.
~~d. Dose Factors from Inhalation of Radionuclides in Air CF A 4FAaij) (-a) fei)~~
Where:
DF .j, = the dose factor for radionuclide T to organ "j" of an individual in age group "a" due to inhalation, (mrem m3)/(Ci s) [equivalent to (mrem/yr)(yr/Ci)(m3/s)];
dfa aii = the inhalation dose factor for radionuclide T, organ T. and age group "a" (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-8, mrem/pCi; r- = the annual air intake for individuals in age group "a", from Table 3.2-14, m3/yr.
ODCM Page: 40 Rev.: 21 X = the annual average concentration of radionudide T in air (pCi/m3),
for a unit release rate (Ci/yr) and a unit %/Q (s/m3),
~~e. Dose Factors from the Ingestion of Atmosphericaly Released Radionuclides in Food D (3.2-6)~~
DF ai, = DFIaij Where:
DF D. . e the dose factor for radionudide T to organ T of an individual in age group "a* from the ingestion of meat, leafy vegetables, milk, and produce (non-leafy vegetables, fruits, and grains) in (mrem
~~m2; or in the cases of H-3 and C-14 in (mrem~~
~~m^Ci~~
~~s);~~
cF cP C ? C Y = the concentrations of radionudide "i" in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or pCi/L) for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (nrr2), or in cases of hf3 and C"14, a unit yJQ, relative ground-level concentration (s/m3), in (pCi/kg)(Ci/yr)(m-2) or (pCI/kg)/(Ci/yr)(s/m3) or (pCi/LMCi/yrHm-2) or (pCi/L)(yr/Ci)(s/m3);
DFi ai j = the ingestion dose factor for radionuclide "I", organ "j", and age group "a", from Tables 3.2-10 through 3.2-13, mrem/pCi; fl # *v = *ne respective fractions of the ingestion rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (Regulatory Guide 1.109);
UFULUMU^ = the annual intake (usage) of meat, leafy vegetables, milk, and produce respectively, for individuals in age group "a", from Table 3.2-14, kg/yr or l/yr.
~~f. Dose rate example problem:~~
1) For the purpose of this sample problem, the following assumptions are utilized: a release of Xe-133 at 1 .OE-5 uCi/cc, a flow rate of 1.0E5 tf/min, and a whole body dose factor of 2.94E-4 mrem/yr per pCi/m3. Dose rate and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cumulative dose are calculated.
~~2) Whde Body Dose Factor per ODCM equation 3.2-2.~~
For final dose calculation:
. .( mrem/yrif lE + 12pCi/m3 ^ mremV_
uri -\V'/ ^lJ . / 3 (ri /.,J\ h -I cp . n-j epr/m3IJ Ci SeC
ODCM Page: 41 Rev.: 21 For dose rate:
IE -r 12pCi/:r? ] _ a -.<< Hirera:!0 HF7 = (l.O) 2.94E- 04 Ci sec
~~3) Dose Rate per ODCM equation 3.2-1.~~
For final dose calculation:
For dose rate:
Final dose calculation:
yr y \8760hr
ODCM Page: 42 Rev.: 21 Table 3.2-1 Oman Used for Gaseous Effluent Dose Calculations
~~1. Bone~~
~~2. Gl Tract~~
~~3. Kidney~~
~~4. Liver~~
~~5. Lung~~
~~6. Thyroid~~
~~7. Whole Body~~
~~8. Skin Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations~~
~~1. Adult (17 yr and older)~~
~~2. Teen (11-17 yr)~~
~~3. Child (1-11 yr)~~
~~4. Infant (0-1 yr)~~
~~Table 3.2-3 Gaseous Effluent Dose Pathways~~
~~1. Plume~~
~~2. Ground Shine~~
~~3. Vegetables~~
~~4. Meat~~
~~5. Cow Milk~~
~~6. Goat Milk~~
~~7. Inhalation~~
ODCM Page: 43 Rev.; 21 Table 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Gamma Air**
Whole Body* Beta Skin* Dose Factor Gamma Dose Dose Factor Nuclide Factor (DFB() (DFS,) fDF,)
Kr-83m 7.56E-08 .
1.93E-05 Kr-85m 1.17E-03 1.46E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 1.56E-04 Xe-133m 2.51 E-04 9.94E-04 3.27E-04 Xe-133 2.94E-04 3.06E-04 3.53E-04 Xe-135m 3.12E-03 7.11 E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.51E-O3 Xe-138 8.83E-03 4.13E-03 9.21 E-03 Ar-41 8.84E-O3 2.69E-03 9.30E-03
~~mrem/yrperpCi/m8~~
~~mrad/yr per pCi/m3~~
ODCM Page: 44 Rev.: 21 Table 3.2-5 External Dose p^rtors for Standlna on Contaminated.
Ground (mrem/h per pCi/m2)
\A/hole Bodv Skin Element O.OOE+00 O.OOE+00 H-3 O.OOE+00 O.OOE+00 C-14 2.50E-08 2.90E-08 Na-24 O.OOE+00 O.OOE+00 P-32 2.20E-10 2.60E-10 Cr-51 5.80E-09 6.80E-09 Mn-54 1.10E-08 1.30E-08 Mn-56 O.OOE+00 O.OOE+00 Fe-55 8.00E-09 9.40E-09 Fe-59 7.00E-09 8.20E-09 Co-58 1.70E-08 2.00E-08 Co-60 O.OOE+00 O.OOE+00 Ni-63 3.70E-09 4.30E-09 Nr-65 1.50E-09 1.70E-09 Cu-64 4.00E-09 4.60E-09 Zn-65 O.OOE+00 O.OOE+00 Zn-69 6.40E-11 9.30E-11 Br-83 1.20E-O8 1.40E-0B Br-84 O.OOE+00 O.0OE+O0 Br-85 6.30E-10 7.20E-10 Rb-86 3.50E-09 4.00E-09 Rb-88 1.50E-08 1.80E-08 Rb-89 5.60E-13 6.50E-13 Sr-89 7.10E-09 8.30E-09 Sr-91 9.00E-09 1.00E-08 Sr-92 2.20E-12 2.60E-12 Y-90 3.80E-09 4.40E-09 Y-81M 2.40E-11 2.70E-11 Y-91 1.60E-09 1.90E-09 Y-92 5.70E-10 7.80E-10 Y-93 5.00E-09 5.8DE-09 Zr-95 5.50E-09 6.40E-09 Zr-97 5.10E-09 6.00E-09 Mo-95 1.90E-09 2.20E-09 Mo-99 9.60E-10 1.10E-09 TC-99M 2.70E-09 3.00E-09 To101 3.60E-09 4.20E-09 Ru-103 4.50E-09 5.10E-09 Ru-105 1.50E-09 1.80E-09 Ru-106 1.80E-08 2.10E-08 Ag-110M
ODCM Page: 45 Rev.: 21 Table 3.2-5 (Coni)
External Dose Factors for Standina on Contaminatad Ground (mnem/h per pCi/m2)
Element Whole Bodv Skin T&-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 110E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-O8 1-131 2.80E-09 3.40E-09 M32 1.70E-08 2.00E-08 M33 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-O8 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-O9 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-O8 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-O9 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00E+00 0.00E+00 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
ODCM Page: 46 Rev.: 21 Table 3.2-6 Fartors for Adi# ^jmrntoCl inhaled)
WHOLE THYROID KIDNEY LUNG G1-LU BONE LIVER BODY NUCLIDE 1.58E-07 1.58E-07 1.58E-07 1.58E-O7 NO DATA 1.58E-07 1.58E-07 H-3 4.26E-O7 4.26E-O7 4.28E-07 4.26E-07 2.27E-06 4.26E-07 4.26E-07 C-14 1.28&-06 1.28E-06 1.28 E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 Na-24 1.08E-O5 6.26E-06 NO DATA NO DATA NO DATA P-32 L65E-04 9.64E-06 2.85E-09 1.80E-06 4.15E-07 NO DATA 1.25E-08 7.44E-09 Cr-51 NO DATA 1.23E-O6 1.75E-04 9.67E-O6 4.95E-06 7.87E-O7 NO DATA Mn-54 NO DATA 2.53E-06 1.63E-10 1.18E-06 1.55E-10 2.29E-11 NO DATA Mrv-56 NO DATA 7.54E-07 4.23E-07 NO DATA NO DATA 9.01 E-06 3.07E-06 2.12E-06 Fe-55 1.27E-04 2.35E-05 1.32E-06 NO DATA NO DATA Fe~59 1.47E-06 3.47E-06 NO DATA 1.16E-04 1.33E-05 1.98E-07 2.59E-07 NO DATA Co-58 NO DATA 3.56E-05 NO DATA NO DATA 7.46E-05 NO DATA 1.44E-06 1.85E-06 Co-60 1.67E-06 NO DATA NO DATA 2.23E-05 5.40E-05 3.93E-06 1.81 E-06 Ni-63 NO DATA 7.00E-07 1.54E-06 2.62E-11 1.14E-11 NO DATA Nh65 1.92E-10 5.78E-10 8.48E-07 6.12E-06 NO DATA 1.83E-10 7.69E-11 NO DATA Cu-64 6.68E-06 NO DATA 8.62E-06 1.08E-04 4.05E-06 1.29E-05 5.82E-06 Zn-65 2.04E-09 5.27E-12 1.15E-07 4.23E-12 8.14E-12 5.65E-13 NO DATA Zrv69 2.90E-08 3.01 E-08 NO DATA NO DATA NO DATA Br-83 NO DATA NO DATA NO DATA NO DATA 2.05E-13 NO DATA 3.91 E-08 NO DATA Br-84 NO DATA NO DATA NO DATA LT E-24 NO DATA 1.60E-09 NO DATA Br-85 NO DATA 2.08E-O6 7.37E-06 NO DATA NO DATA NO DATA Rb-86 NO DATA 1.69E-06 NO DATA 4.18E-19 2.41 E-08 NO DATA NO DATA Rb-88 NO DATA 4.84E-O8 NO DATA NO DATA 1.16E-21 3.20E-O8 2.12E-08 NO DATA Rb-89 NO DATA 4.37E-05 NO DATA NO DATA 1.75E-04 3.80E-05 NO DATA 1.09E-06 Sr-B9 9.02E-05 NO DATA NO DATA 1.20E-03 1.24E-02 NO DATA 7.62E-04 Sr-90 4.56E-06 NO DATA 3.13E-10 NO DATA NO DATA Sr-91 7.74E-09 NO DATA 2.06E-06 5.38E-0B NO DATA 3.64E-11 NO DATA Sr-92 8.43E-10 2.12E-05 6.32E-05 7.01 E-09 NO DATA NO DATA Y-90 2.61 E-07 NO DATA NO DATA 2.40E-07 1.66E-10 NO DATA 1.27E-12 NO DATA Y-81M 3.26E-11 4.81 E-05 NO DATA NO DATA 2.13E-04 5.78E-05 NO DATA 1.55E-O6 Y-91 1.96E-06 9.19E-06 NO DATA 3.77E-11 NO DATA NO DATA Y-92 1.29E-09 NO DATA 6.06E-08 5.27E-05 NO DATA 3.26E-10 NO DATA Y-93 1.18E-08 6.77E-06 2.21 E-04 1.88E-05 4.30E-06 2.91 E-06 NO DATA Zr-95 1.34E-05 6.54E-05 NO DATA 3.71 E-09 9.84E-06 1.21 E-08 2.45E-09 1.13E-09 Zr-97 1.30E-05 5.26E-07 NO DATA 9.67E-07 6.31 E-05 Nb-95 1.76E-06 9.77E-07 3.64E-06 1.14E-05 3.10E-05 1.51 E-08 2.87E-09 NO DATA Mo-99 NO DATA 5.20E-07 NO DATA 5.52E-12 9.55E-08 1.29E-13 3.64E-13 4.63E-12 Tc-99M
ODCM Page: 47 Rev.: 21 Table 3.2-6 (Cont)
Inhalation Dose Factors for Adult fmrem/oCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LU To-101 5.22E-15 7.52E-1S 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-O6 6.02E-06 Ru-106 8.64E-06 NO DATA 1.00E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AQ-110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 T6-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-05 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-06 Te-127 1.75E-10 8.00E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 T6-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-C6 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-O9 6.88E-09 3.86E-08 1.82E-05 6.06E-O5 Te-131 1.39E-12 7.44E-13 4.49E-13 117E-12 5.46E-12 1.74E-07 2.30E-09 T&-132 3.25E-08 2.69E-C8 2.02E-08 2.37E-OB 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 NO DATA 9.61 E-07 H31 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-0B NO DATA 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11 E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 H35 3.35E-07 B.73E-07 3.21 E-07 5.60E-O5 1.39E-06 NO DATA 6.56E-O7 Cs-134 4.86E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-O6 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-1S 2.07E-13 NO DATA 2.86E-15 1.49E-O7 1.96E-26 La-140 4.30E-08 2.17E-O8 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-C6 1.91 E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91 E-13 NO DATA 8.81 E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-O7 4.56E-08 NO DATA 4.45E-07 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-O5 Np-239 2.37E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05
ODCM Page: 48 Rev.: 21 Table 3.2-7
tors for Ti WHOLE KIDNEY LUNG GI-LU LIVER BODY THYROID NUCLIDE BONE 1.59E-07 1.59E-07 1.59E-07 1.59E-07 NO DATA 1.59E-O7 1.59E-O7 H-3 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-O7 C-14 3.25E-06 6.09E-07 1.72E-06 1.72E-06 1.72E-06 1.72E-O6 1.72E-06 Na~24 1.72E-06 1.72E-06 NO DATA NO DATA 1.16E-05 1.37E-05 8.95E-06 NO DATA P-32 2.36E-04 3.75E-07 9.37E-09 3.84E-09 2.62E-06 NO DATA NO DATA 1.69E-08 Cr-51 1.59E-06 2.48E-04 8.35E-06 6.32E-06 1.05E-O8 NO DATA Mi>54 NO DATA 7.18E-06 2.24E-10 1.90E-06 2.12E-10 3.15E-11 NO DATA Mn-56 NO DATA 7.99E-07 NO DATA NO DATA 1.55E-05 4.18E-06 2.98E-06 6.93E-07 Fe-55 1.91E-04 2.23E-05 1J9E-06 NO DATA NO DATA 1.29E-06 4.62E-06 Fe-59 1.68E-04 1.19E-05 3.47E-07 NO DATA NO DATA NO DATA 2.59E-07 Co-58 1.09E-O3 3.24E-O5 2.48E-06 NO DATA NO DATA Co-60 NO DATA 1.89E-06 NO DATA 3.84E-05 1.77E-O6 5.43E-06 2.47E-06 NO DATA Ni-63 7.25E-05 4.59E-06 NO DATA NO DATA 1.17E-06 2.73E-10 3.66E-11 1.59E-11 NI-65 1.39E-06 7.68E-06 1.06E-10 NO DATA 8.01 E-10 Cu-64 NO DATA 2.54E-10 1.08E-0S 1.55E-04 5.83E-Q6 1.67E-05 7.80E-06 NO DATA Zn-65 4.82E-06 3.56E-06 7.53E-12 1.98E-07 1.15E-11 8.07E-13 NO DATA Zn-69 6.04E-12 LT E-24 NO DATA NO DATA NO DATA NO DATA NO DATA 4.30E-08 Br-83 NO DATA LTE-24 5.41 E-08 NO DATA NO DATA Br~84 NO DATA NO DATA NO DATA NO DATA LT E-24 NO DATA 2.29E-09 NO DATA Br-85 NO DATA 2.21 E-06 NO DATA NO DATA NO DATA NO DATA 2.38E-05 1.05E-05 Rb-86 NO DATA 3.65E-15 3.40E-O8 NO DATA NO DATA NO DATA 6.82E-08 Rb-88 NO DATA 4.22E-17 2.91 E-08 NO DATA NO DATA Rb-89 NO DATA 4.40E-08 4.64E-05 NO DATA 3.02E-04 NO DATA 1.56E-06 NO DATA Sr-89 5.43E-05 2.08E-O3 9.56E-05 8.35E-04 NO DATA NO DATA Sr-90 1.3SE42 NO DATA NO DATA 7.59E-06 3.24E^05 NO DATA 4.39E-10 NO DATA Sr-91 1.10E-08 3.43E-08 1.49E-05 5.08E-11 NO DATA NO DATA Sr-92 1.19E-09 NO DATA 6.99E-05 NO DATA 3.66E-05 NO DATA 1.00E-08 NO DATA Y-90 3.73E-07 3.77E-09 NO DATA NO DATA 4.00E-07 4.63E-11 NO DATA 1.77E-12 Y-91M 3.67E-04 5.11E-05 2.21 E-06 NO DATA NO DATA 8.26E-05 NO DATA Y-91 NO DATA 3.35E-06 2.06E-05 NO DATA 5.36E-11 NO DATA Y-92 1.84E-09 NO DATA 1.04E-05 7.24E-05 NO DATA 4.65E-10 NO DATA Y-93 1.69E-Q8 1.86E-05 NO DATA 8.42E-06 3.36E-04 5.73E-06 3.94E-06 2>95 5.15E-09 1.62E-05 7.88E-O5 3.40E-09 1.57E*09 NO DATA Zr-S7 1.72E-08 1.21E-05 NO DATA 1.25E-O6 8.39E-05 2.32E-06 1.29E-06 7.08E-07 Nb-95 1.92E-05 3.36E-05 4.03E-09 NO DATA 6.14E-08 NO DATA 2.11E-08 Mo-99 7.20E-12 1.44E-07 7.66E-O7 4.83E-13 6.24E-12 NO DATA TO-99M 1.73E-13
ODCM Page: 49 Rev.: 21 Table 3.2-7 (Cont)
Inhalation Dose Factors for Teenaoer imrem/DCi inhaledi WHOLE NUCLIDE BONE UVER BODY THYROID KIDNEY LUNG GI-LLI To-101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 NO DATA 1.55E-08 NO DATA 2.38E-O5 2.01 E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-08 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41 E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-O7 8.17E-06 2.07E-O4 1.99E-05 Te-127 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-O7 6.49E-06 2.47E-04 5.06E-05 Te-129 8.B7E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7J2E-12 2.97E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5J9E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11 E-07 M32 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 1-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-O6 NO DATA 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11 E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 La-142 1.20E-10 5.31 E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71 E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-C6 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.C4E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41 E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21 E-05 Np-239 4.23E-08 3.99E-09 2.21 E-09 NO DATA 1.75E-08 8.11E-06 1.65E-05
ODCM Page: 50 Rev.: 21 Table 3.2-8 Inhalation Dose Factors for Child fmramfoCI inhaled)
WHOLE NUCUDE BONE UVER BODY THYROID KIDNEY LUNG GI-LLJ H-3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.O4E-07 3.04E-O7 3.04E-O7 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-O6 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 Z67E-05 NO DATA NO DATA NO DATA 1.14E-05 Cr-51 NO DATA NO DATA 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 NO DATA 1.16E-O5 2.57E-06 NO DATA 2.71 E-06 4.26E-04 6.19E-08 Mn-56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 NO DATA NO DATA 3.43E-04 1.91 E-05 Co-58 NO DATA 4.70E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 Co-60 NO DATA 3.55E-06 6.12 E-06 NO DATA NO DATA 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21 E-06 2.27E-05 Cu-64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-O5 1.90E-05 NO DATA 1.93E-05 2.69E-O4 4.41 E-06 Zn-69 1.81E-11 2.61 E-11 2.41 E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 Br-83 NO DATA NO DATA 1.28E-O7 NO DATA NO DATA NO DATA LTE-24 Br-84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LTE-24 Br-85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LTE-24 Rb-86 NO DATA 5.36E-05 3.09E-O5 NO DATA NO DATA NO DATA 2.16E-06 Rb-88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-O9 Rb-B9 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.11E-10 Sr-89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 Sr-90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 Sr-81 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-OS Sr-92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y-90 1.11E-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y-91M 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y-91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-0S Y-S2 5.50E-09 NO DATA 1.67E-10 NO DATA NO DATA 6.46E-06 6.46E-O5 Y-93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01 E-05 1.05E-04 Zr-95 5.13E-06 1.13E-05 1.00E-O5 NO DATA 1.61 E-06 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-O8 3.06E-05 9.49E-06 Nb-95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-O5 Mo-99 NO DATA 4.66E-O8 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-0S TC-99M 4.81 E-13 9.41 E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06
ODCM Page: 51 Rev.: 21 Table 3.2-8 (Cont)
Inhalation Dose Factors for Child (mffp/oCi inhaled)
WHOLE THYROID KIDNEY LUNG Gl-LLl JCL1DE BONE LIVER BODY 2.91 E-13 NO DATA 3.92E-13 1.58E-07 4.41 E-09 To-101 2.19E-14 2.30E-14 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 Ru-103 7.55E-07 NO DATA NO DATA 3.63E-10 4.30E-06 2.69E-05 Ru-105 4.13E-10 NO DATA 1.50E-10 NO DATA 4.97E-05 3.87E-03 1.16E-04 Ru-106 3.68E-05 NO DATA 4.57E-06 NO DATA 5.74E-06 1.48E-03 2.71 E-05 Ag-110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 1.29E-04 9.13E-06 1.82E-06 6.29E-07 2.47E-07 5.20E-07 Te-125M 1.64E-06 1.72E-05 4.00E-04 1.93E-05 T©-127M 6.72E-06 2.31 E-06 B.18E-07 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 Te-127 7.49E-10 2.57E-10 8.22E-07 1.71E-06 1.36E-05 4.76E-O4 4.91 E-05 T0-129M 5.19E-06 1.85E-06 6.94E-11 7.93E-07 6.89E-06 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131M 3.63E-08 1.60E-08 1.37E-08 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-131 5.87E-12 2.28E-12 1.78E-12 8.58E-08 4.79E-O7 1.02E-O4 3.72E-05 Te-132 1.30E-07 7.36E-08 7.12E-O8 2.28E-06 4.99E-04 6.61 E-06 NO DATA 1.38E-06 1-130 Z21E-06 4.43E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 1-131 1.30E-05 1.30E-O5 7.37E-06 5.23E-O5 1.69E-06 NO DATA 8.65E-07 M32 5.72E-07 1.10E-06 5.07E-O7 2.08E-O6 1.04E-03 9.13E-06 NO DATA 1.48E-06 1-133 4.48E-06 5.49E-06 1.37E-05 8.92E-07 NO DATA 2.58E-07 3.17E-07 5.84E-07 2.09E-07 1-134 2.14E-04 3.62E-06 NO DATA 1.20E-06 1-135 1.33E-06 2.36E-06 1.12E-06 NO DATA 8.93E-05 3.27E-05 1.04E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 Cs-136 1J6E-05 4.62E-05 NO DATA 7.63E-05 2.81 E-05 9.78E-07 Cs-137 2.45E-04 2.23E-04 3.47E-C5 NO DATA 1.68E-07 1.84E-08 7.29E-O8 Cs-138 1.71E-07 2.27E-07 1.50E-07 2.33E-13 1.56E-Q6 1.56E-05 Ba-139 4.98E-10 2.66E-13 1.45E-11 NO DATA NO DATA 5.71 E-09 4.71 E-04 2.75E-05 Ba-140 2.00E-05 1.75E-08 1.17E-Q6 2.56E-14 7.89E-07 7.44E-08 Ba-141 5.29E-11 2.95E-14 1.72E-12 NO DATA 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 Ba-142 1.35E-11 2.73E-15 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 La-140 1.74E-07 6.08E-08 NO DATA NO DATA 2.35E-06 2.05E-05 La-142 3.50E-10 1.11E-10 3.49E-11 NO DATA 2.31 E-06 1.47E-05 1.53E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.26E-08 3.12E-05 3.44E-05 Ce-143 9.89E-D8 5.37E-08 7.77E-09 3.17E-04 3.23E-03 1.05E-04 Ce-144 1.83E-03 5.72E-O4 9.77E-05 NO DATA NO DATA 8.11E-07 1.17E-04 2.63E-05 Pr-143 4.99E-06 1.50E-O6 2.47EXJ7 NO DATA 2.64E-12 4.23E-07 5.32E-08 Pr-144 1.61E-11 4.99E-12 8.10E-13 NO DATA 1.30E-06 8.87E-05 2.22E-05 Nd-147 2.92E-OB 2.36E-06 1.84E-07 NO DATA NO DATA 1.11 E-05 2.46E-05 W-187 .41 E-09 2.61 E-09 1.17E-09 Np-239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 t57E-05 1.73E-05
ODCM Page: 52 Rev.: 21 Table 3.2-9 Inhalation Dose Factors for Infant Jmrem/pCi inhaled)
WHOLE THYROID KIDNEY LUNG GI-LLI NUCLIDE BONE LIVER BODY 4.62E-07 4.62E-07 4.62E-07 4.62E-07 H-3 NO DATA 4.62E-07 4.62E-O7 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 C-14 1.89E-05 179E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 Na-24 7.54E-06 7.54E-06 NO DATA NO DATA NO DATA 1.15E-05 P-32 1.45E-03 8.03E-05 5.53E-O5 4.11E-08 9.45E-O9 9.17E-06 2.55E-07 Cr-51 NO DATA NO DATA 6.37E-08 NO DATA 3.56E-06 7.14E-04 5.04E-06 Mn-54 NO DATA 1.81E-05 3.56E-06 NO DATA 7.86E-10 8.95E-O6 5.12E-05 Mn-56 NO DATA 1.10E-09 1.58E-10 2.38E-06 NO DATA NO DATA 6.21 E-05 7.82E-07 Fe-55 1.41E-05 8.39E-06 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 Fe-59 9.69E-06 1.68E-05 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 Co-58 NO DATA B.71E-07 8.41 E-06 NO DATA NO DATA 3.22E-03 2.28E-05 Co-60 NO DATA 5.73E-06 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 Nl-63 2.42E-04 1.46E-05 NO DATA NO DATA 5.80E-06 3.58E-05 Ni-65 1.71 E-09 2.03E-10 8.79E-11 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 Cu-64 NO DATA 1.34E-09 2.22E-06 NO DATA 2.32E-05 4.62E-04 3.67E-05 Zn-65 1.38E-05 4.47E-05 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 Zn-69 3.85E-11 6.91 E-11 2.72E-07 NO DATA NO DATA NO DATA LT E-24 Br-83 NO DATA NO DATA 2.86E-O7 NO DATA NO DATA NO DATA LT E-24 Br-84 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LTE-24 Br-85 NO DATA NO DATA 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 Rb-66 NO DATA 1.36E-04 NO DATA NO DATA NO DATA 2.42E-07 Rb-88 NO DATA 3.98E-07 2.03E-07 NO DATA NO DATA NO DATA 4.87E-08 Rb-89 NO DATA 2.29E-07 1.47E-07 8.15E-06 NO DATA NO DATA 1.45E-O3 4.57E-05 Sr-<<9 2.84E-04 NO DATA NO DATA NO DATA 8.03E-O3 9.36E-05 Sr-90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 3.76E-O5 5.24E-05 Sr-91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 1.70E-05 1.00E-O4 Sr-92 7.50E-09 NO DATA 2.79E-10 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y-90 2.35E-06 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y-91M 2.91 E-10 NO DATA NO DATA NO DATA 1.75E-03 5.02E-05 Y-91 4.20E-04 NO DATA 1.12E-05 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y-92 1.17E-O8 NO DATA NO DATA NO DATA 5.46E-05 1.19E-04 Y-93 1.07E-07 NO DATA 2.91 E-09 NO DATA 2.22E-05 1.2SE-03 1.55E-05 Zr-95 8.24E-05 1.99E-05 1.45E-06 NO DATA 1.85E-08 7.88E-05 1.00E-04 1.07E-07 1.83E-08 8.3SE-O9 Zr-97 NO DATA 3.37E-06 3.42E-04 9.05E-06 Nb-95 1.12E-05 4.59E-06 2.70E-06 NO DATA 1.89E-07 9.63E-05 3.48E-05 Mo-99 NO DATA 1.18E-07 2.31 E-08 NO DATA 2.22E-11 5.79E-07 1.45E-06 TC-99M 9.98E-13 2.06E-12 2.66E-11
ODCM Page: 53 Rev.: 21 Table 3.2-9 (Cont.)
Inhalation Dose Factors for Infant (mrem/pCi inhaled)
WHOLE NUCLIDE BONE UVER BODY THYROID KIDNEY LUNG GI-LLi Tc-101 4.65E-14 5.58E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.1SE-05 Ru-105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61 E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-O6 NO DATA 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.4OE-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-O7 2.43E-04 3.15E-05 1-130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 1-131 1.71E-G5 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 1-132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 NO DATA 1.36E-06 U33 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-O6 M34 6.5BE-07 1.34E-06 4.75E-O7 3.18E-05 1.49E-06 NO DATA 9.21 E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.C5E-06 NO DATA 1.31 E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61 E-05 3J8E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61 E-07 5.58E-O7 2.84E-07 NO DATA 2.93EO7 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.D7E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 3.48E-11 NO DATA NO DATA 5.87E-O6 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-O4 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-O6 Nd-147 5.67E-06 5.81 E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-O5 Np-239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05
ODCM Page: 54 Rev.: 21 Table 3.2-10 Indian Dose f^om for AcKJ (mr?'*^1i"<<*tecn WHOLE THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER BODY 1.05E-07 1.05E-07 1.05E-07 1.05E-O7 H-3 0.OOE+0O 1.05E-07 1.05E-07 5.68E-07 5.68E-O7 5.68E-07 5.68E-07 C-14 2.84E-06 5.68E-07 5.88E-07 1.70E-06 1.70E-06 1.70E-06 1.70E-06 Na-24 1.70E-06 1.70E-06 1.70E-06 0.00E+00 0.00E+00 O.OOE+00 2.17E-O5 P-32 1.93E-04 1.20E-05 7.46E-06 5.86E-10 3.53E-09 6.69E-07 O.OOE+00 O.OOE+00 2.66E-09 1.59E-09 Cr-51 O.OOE+00 1.38E-06 O.OOE+00 1.40E-05 Mn-54 0.00E+O0 4.57E-06 8.72E-07 2.04E-08 0.00E+00 1.48E-O7 O.OOE+00 3.67E-06 Mrv56 0.00E+00 1.15E-07 4.43E-07 O.OOE+00 O.OOE+00 1.06E-06 1.09E-06 Fe-55 2.75E-06 1.90E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Fe-59 4.34E-06 1.02E-05 3.91 E-06 O.OOE+00 0.00E+00 0.00E+00 1.51E-05 Co-58 0.O0E+O0 7.45E-07 1.67E-06 O.OOE+00 0.00E+00 4.02E-05 O.0OE+O0 2.14E-06 4.72E-06 0.00E+00 Co-60 4.36E-06 O.OOE+00 0.00E+00 0.00E+00 1.88E-O6 Ni-63 1.30E-04 9.01 E-O6 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+00 2.10E-07 O.OOE+00 7.10E-06 Cu-64 O.OOE+00 8.33E-08 3.91 E-08 O.OOE+00 1.O3E-O5 O.OOE+00 9.70E-O6 Zn-65 4.84E-06 1.54E-05 6.96E-06 1.28E-08 O.OOE+00 2.96E-09 1.03E-08 1.97E-O8 1.37E-09 O.OOE+00 Zn-69 O.OOE+00 O.OOE+00 0.00E+00 5.79E-08 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 O.OOE+00 0.00E+00 4.09E-13 Br-84 O.OOE+00 O.OOE+00 5.21 E-08 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-85 0.00E+00 O.OOE+00 2.14E-09 O.OOE+00 O.OOE+00 4.16E-O6 O.OOE+00 2.11E-O5 9.83E-06 O.OOE+00 Rb-66 O.OOE+00 0.00E+00 O.OOE+00 8.36E-19 Rb-88 0.00E+00 6.05E-O8 3.21 E-08 2.82E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-21 Rb-89 0.00E+00 4.01 E-O8 O.OOE+00 0.00E+00 O.OOE+00 4.94E-05 3.08E-04 0.00E+00 8.84E-06 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 2.19E-04 Sr-90 7.58E-03 0.00E+00 1.86E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-91 5.67E-06 O.OOE+00 2.29E-07 0.00E+0O 0.00E+00 0.00E+O0 4.26E-05 Sr-92 2.15E-06 O.OOE+00 9.30E-08 0.00E+00 O.OOE+00 O.OOE+00 1.02E-04 Y-SO O.OOE+00 2.58E-10 O.OOE+00 O.OOE+00 O.OOE+00 2.67E-10 Y-81M 9.09E-11 O.OOE+00 3.52E-12 0.00E+OO O.OOE+00 0.00E+00 7.67E-05 Y-91 1.41E-07 O.OOE+00 3.77E-O9 0.00E+OO O.OOE+00 0.00E+00 1.48E-05 Y-92 8.45E-10 O.OOE+00 2.47E-11 0.00E+00 0.00E+00 O.OOE+00 8.50E-05 Y-93 2.68E-09 O.OOE+00 7.40E-11 1.53E-08 O.OOE+00 3.09E-O5 3.04E-08 9.75E-O9 6.60E-09 O.OOE+00 Zr-95 5.12E-10 O.OOE+00 1.05E-O4 1.68E-09 3.39E-10 1.55E-10 0.00E+00 Zr-97 3.42E-09 O.OOE+00 2.10E-O5 Nb-95 6.22E-O9 3.46E-09 1.86E-09 0.00E+00 0.00E+00 9.76E-O6 0.00E+00 9.99E-O6 Mo-99 O.OOE+00 4.31 E-06 8.20E-07 0.00E+00 1.06E-08 3.42E-10 4.13E-07 2.47E-10 6.98E-10 8.89E-09
ODCM Page: 55 Rev.: 21 Table 3.2-10 (Cont)
Inaestion Dose Factors for Adult (mrem/pCi ingested!
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GE-LLI To-101 2.54E-10 3.66E-10 3.59E-09 0.00E+O0 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-O7 O.OOE+00 7.97E-08 O.OOE+00 7.06E-07 O.OOE+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 O.OOE+00 1.99E-07 O.OOE+00 9.42E-06 Ru-106 2.75E-06 0.00E+O0 3.48E-07 0.00E+00 5.31 E-06 0.00E+00 1.78E-04 A0-11OM 1.60E-07 1.48E-07 8.79E-08 O.OOE+00 2.91 E-07 0.00E+00 6.04E-O5 Te-125M 2.88E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 T&-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+OO 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 0.00E+00 2.37E-08 Te-131M 1.73E-06 8.46E-O7 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-0S 0.00E+00 7.71 E-05 1-130 7.56E-O7 2.23E-06 8.80E-O7 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 O.00E+00 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E47 0.00E+00 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0.00E+00 2.22E-06 M34 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51 E-10 M35 4.43E-07 1.16E-06 4.28E-07 7.66E-05 1.86E-06 0.00E+OO 1.31 E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51 E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.C9E-07 5.40E-08 O.OOE+00 8.01 E-06 7.91 E-09 4.66E-13 Ba-139 9.70E-08 6.91 E-11 2.84E-09 O.OOE+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-C9 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 0.00E+00 3.31 E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.B5E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 O.OOE+00 0.00E+00 9.2SE-05 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 O.OOE+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+00 2.94E-09 0.00E+OO 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21 E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-O5 Pr-144 3.01 E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.O0E+0O 3.49E-05 W-187 1.03E-07 8.61 E-08 3.01 E-08 O.OOE+00 0.O0E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05
ODCM Page: 56 Rev.: 21 Table 3.2-11 Inaestion Dose Factors for Teenager fmrenVpCi ingested)
WHOLE UVER BODY THYROID KIDNEY LUNG GM-LI ISOTOPE BONE 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.08E-07 1.06E-07 H-3 0.00E+00 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 C-14 2.30E-06 Z30E-06 2.30E-06 2.30E-08 2.30E-O6 2.30E-O6 2.3OE-06 Na-24 1.71E-05 1.07E-05 O.OOE+00 0.00E+00 O.OOE+00 2.32E-05 P-32 2.76E-04 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Cr-51 0.00E+00 1.17E-06 0.00E+00 1.76E-O6 O.OOE+00 1.21E-05 Mn-54 O.OOE+00 S.SOE-06 Mn-56 O.OOE+00 1.58E-07 2.81 E-08 0.00E+00 2.00E-07 O.OOE+00 1.04E-05 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-O6 1.16E-06 Fb-55 3.78E-06 5.87E-06 1.37E-05 5.29E-06 0.00E+00 O.OOE+00 4.32E-06 3.24E-05 Fa-59 9.72E-07 2.24E-06 0.00E+00 O.OOE+00 0.00E+00 1.34E-05 Co-58 O.OOE+00 2.81E-06 6.33E-06 0.00E+00 O.OOE+00 0.00E+00 3.66E-05 Co-SO O.OOE+00 1.25E-05 6.00E-06 0.00E+00 O.OOE+00 O.OOE+00 1.99E-06 NI-63 1.77E-04 7.49E-07 9.57E-08 4.36E-08 0.00E+00 O.OOE+00 0.00E+00 5.19E-06 Ni-65 5.41 E-08 0.00E+00 2.91 E-07 0.00E+00 8.92E-06 Cu-64 O.OOE+00 1.15E-07 9.33E-O6 0.00E+O0 1.28E-05 0.00E+00 8.47E-06 Zn-65 5.76E-06 Z00E-05 Z80E-08 196E-O9 0.00E+O0 1.83E-08 0.00E+00 5.16E-O8 Zn-69 1.47E-08 O.OOE+00 5.74E-08 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 7.22E-08 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 1.40E-05 O.OOE+00 O.OOE+00 0.00E+00 4.41 E-06 Rb-86 O.OOE+00 2.98E-05 O.OOE+00 8.52E-08 4.54E-08 0.00E+00 O.OOE+00 O.OOE+00 7.30E-15 Rb-88 O.OOE+00 5.50E-08 3.89E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.43E-17 Rb-89 O.OOE+00 1.26E-O5 O.OOE+00 O.OOE+00 O.OOE+00 5.24E-05 Sr-89 4.40E-04 O.OOE+00 2.05E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-04 Sr-90 8.30E-03 3.21 E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-O5 Sr-91 8.07E-06 O.OOE+00 O.OOE+00 1.30E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.77E-05 Sr-92 3.06E-06 O.OOE+00 3.69E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-04 Y-90 1.37E-08 4.93E-12 0.00E+00 O.OOE+00 O.OOE+00 6.09E-09 Y-91M 1.29E-10 0.00E+00 5.39E-09 O.OOE+00 O.OOE+00 O.OOE+00 8.24E-O5 Y-01 2.01 E-07 O.OOE+00 0.00E+O0 O.OOE+00 O.OOE+00 3.32E-O5 Y-82 1.21E-09 O.OOE+00 3.50E-11 O.OOE+00 1.05E-10 0.00E+O0 O.OOE+00 O.OOE+00 1.17E-04 Y-93 3.B3E-O9 1.30E-08 8.94E-09 O.OOE+00 1.91 E-08 O.OOE+00 3.00E-O5 Zr-95 4.12E-06 4.69E-10 2.16E-10 0.00E+00 7.11E-10 O.OOE+00 1.27E4J4 Zr-97 2.37E-09 4.56E-09 2.51 E-09 O.OOE+00 4.42E-O9 0.00E+00 1.95E-05 Nb-95 8.22E-09 O.OOE+00 6.03E-O6 1.15E-06 O.OOE+00 1.38E-06 0.00E+00 1.08E-05 Mo-99 9.26E-10 1.20E-08 O.OOE+00 1.38E-O8 5.14E-10 6.08E-07 TQ-89M 3.32E-10
ODCM Page: 57 Rev.: 21 Table 3.2-11 (Cont.)
Inaestion Dose Factor for Teenager (mrem/DCi ingested)
WHOLE BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER 5.12E-10 5.03E-09 O.OOE+00 9.26E-09 3.12E-10 8.75E-17 To-101 3.60E-10 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 O.OOE+00 2.13E-05 Ru-103 2.18E-08 0.O0E+O0 8.46E-09 0.00E+00 2.75E-07 O.OOE+00 1.76E-05 Ru-105 0.0OE+O0 4.94E-07 0.00E+00 7.56E-06 O.OOE+00 1.88E-04 Ru-106 3.92E-O6 1.94E-07 1.18E-07 O.00E+00 3.70E-07 O.OOE+00 5.45E-05 Ag-HOM 2.05E-07 T6-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+O0 1.13E-05 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.O0E+O0 2.41E-05 Te-127M 1.58E-07 5.60E-08 3.40E-06 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-127 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129M 1.63E-05 4.4BE-O8 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-129 2.44E-06 1.17E-06 9.76E-07 1.76E46 1.22E-05 O.00E+O0 9.39E-05 Te-131M 2.79E-08 1.15E-08 8.72E-09 2.15E-O8 1.22E-07 0.00E+O0 2.29E-09 Te-131 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 0.O0E+O0 7.00E-05 Te-132 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 2.29E-06 1-130 5.85E-O8 8.19E-06 4.40E-06 2.39E-O3 1.41E-05 O.00E+O0 1.62E-06 1-131 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-07 1-132 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+00 2.58E-06 1-133 1.46E-O7 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 1-134 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 1-135 8.37E-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-134 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2.72E-06 Cs-136 1.49E-04 5.19E-05 O.OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-137 1.12E-04 7.76E-08 1.49E-07 7.45E-08 O.OOE+00 1.10E-07 1.28E-08 6.76E-11 Cs-138 1.39E-07 9.78E-11 4.05E-09 O.OOE+00 9.22E-11 6.74E-11 1.24E-06 Ba-139 2.B4E-05 3.4BE-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-140 5.01 E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-141 6.71 E-08 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 Ba-142 1.71E-09 4.55E-10 0.00E+00 0.00E+00 O.OOE+00 9.82E-05 La-140 3.48E-09 179E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 O.OOE+00 2.42E-06 La-142 1.02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05 Ce-141 1.33E-08 8.88E-C9 2.35E-OG 1.71 E-06 1.91E-10 O.OOE+00 7.67E-10 0.00E+00 5.14E-05 Ce-143 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Ce-144 1.31E-08 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 0.00E+00 4.31 E-05 Pr-143 1.76E-11 2.18E-12 0.00E+00 1.01 E-11 0.00E+00 4.74E-14 Pr-144 4.30E-11 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-O5 Nd-147 9.38E-09 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 O.OOE+00 3.22E-05 V\M87 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21 E-10 0.00E+00 2.67E-05 Np-239
ODCM Page: 58 Rev.: 21 Table 3.2-12 Inaestion Dose Factors for Child (mrem/bCi ingested)
WHOLE BONE LIVER BODY THYROID KIDNEY LUNG GM-LI ISOTOPE 2.03E-07 2.03E-07 2.03E-07 Z03E-07 2.03E-07 2.03E-07 O.OOE+00 1.21 E-05 2.42E-O6 2.42E-06 2.42E-06 Z42E-06 2.42E-06 2.42E-06 C-14 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 8.25E-04 3.86E-O5 3.18E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.28E-05 P-32 O.OOE+00 O.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-O9 4.72E-07 Cr-51 1.07E-05 2.85E-06 O.OOE+00 3.00E-O6 O.OOE+00 8.98E-06 Mn-54 O.OOE+00 Mn-56 O.OOE+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-05 F<<-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+00 O.OOE+00 3.45E-06 1.13E-06 Fe-59 165E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7.74E-06 2.78E-O5 Co-58 O.OOE+00 1.80E-06 5.51 E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.05E-05 Co-60 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-05 5.38E-04 2.88E-05 1.83E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-06 NI-63 NI-65 2.22E-06 2.09E-07 1.22E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 Cu-64 O.OOE+00 2.45E-07 1.48E-07 O.OOE+00 5.92E-07 O.OOE+00 1.15E-05 1.37E-05 3.65E-05 2.27E-05 O.OOE+00 2.30E-05 O.OOE+00 6.41 E-06 Zn-65 4.38E-08 6.33E-08 5.85E-09 O.OOE+00 3.84E-08 O.OOE+00 3.99E-06 Zn-69 O.OOE+00 O.OOE+00 1.71E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 Br-64 O.OOE+00 O.OOE+00 1.98E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.70E-05 4.12E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.31 E-06 Rb-86 1.90E-07 1.32E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.32E-09 Rb-88 O.OOE+00 Rb-89 O.OOE+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-09 O.OOE+00 3.77E-05 O.OOE+00 O.OOE+00 O.OOE+00 5.11 E-05 Sr-69 1.32E-03 O.OOE+00 4.31 E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.29E-O4 Sr-90 1J0E-02 Sr-91 2.40E-05 O.OOE+00 9.06E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.30E-O5 Sr-92 9.03E-06 O.OOE+00 3.62E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.71E-O4 4.11E-08 O.OOE+00 1.10E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-04 Y-90 Y-91M 3.82E-10 O.OOE+00 1.39E-11 O.OOE+00 O.OOE+00 O.OOE+00 7.48E-O7 6.02E-07 O.OOE+00 1.61E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.02E-O5 Y-91 3.60E-09 O.OOE+00 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.04E-O4 Y-92 1.14E-0B O.OOE+00 3.13E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.70E-04 Y-93 Zr-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+00 3.65E-08 O.OOE+00 2.66E-05 6.99E-09 1.01E-09 5.96E-10 O.OOE+00 1.45E-09 O.OOE+00 1.53E-04 Zr-97 8.76E-09 6.26E-09 O.OOE+00 B-23E-09 O.OOE+00 1.62E-05 Nb-95 2.25E-08 1.33E-06 3.29E-06 O.OOE+00 2.84E-O5 O.OOE+00 1.10E-05 Mo-99 O.OOE+00 9.23E-10 1.81E-09 3.0OE-O6 O.OOE+00 2.63E-08 9.19E-10 1.03E-06 TC-99M
ODCM Page: 59 Rev.: 21 Table 3.2-12 (Cont)
Inaastion Dose Factors for Child (mram/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI To-101 1.07E-09 1.12E-09 1.42E-08 O.OOE+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31 E-07 0.00E+00 2.81 E-07 O.OOE+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 O.OOE+00 2.34E-08 O.OOE+00 5.67E-07 O.OOE+00 4.21 E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 0.00E+00 1.58E-05 O.OOE+00 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91 E-07 O.OOE+00 6.78E-07 0.00E+00 4.33E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-O5 1.43E-O4 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 O.OOE+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 0.00E+00 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-O5 0.00E+00 1.54E-06 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+O0 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2.95E-O6 1-134 4.19E-07 7.78E-O7 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 1-136 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01 E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21 E-10 1.20E-08 O.OOE+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 O.OOE+00 2.37E-08 4.34E-08 4.21 E-05 Ba-141 2.00E-07 1.12E-10 6.51 E-09 O.OOE+00 9.69E-11 6.58E-10 1.14E-O7 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 O.OOE+00 0.00E+00 3.31 E-05 Ce-141 3.97E-08 1.98E-O8 2.94E-09 0.00E+00 8.68E-O9 0.00E+00 2.47E-05 Ce-143 8.99E-09 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 0.00E+00 5.55E-05 I Ce-144 2.08E-06 8.52E-07 1.11E-07 O.OOE+00 3.61 E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+00 2.11E-11 O.OOE+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 O.OOE+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-O7 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-1G O.OOE+00 1.09E-09 0.00E+00 2.79E-05
ODCM Page: 60 Rev.: 21 Table 3.2-13 Dose Factors for Infant fmrem/pCj jnqegtefl WHOLE THYROID KIDNEY LUNG GI-LLI SOTOPE BONE UVER BODY 3.08&07 3.08E-07 3.08E-07 3.08E-07 3.0BE-07 3.08E-07 H-3 0.00E+00 5.06E-06 5.06E-O6 5.06E-O6 5.06E-06 5.06E-06 5.08E-O6 C-14 2.37E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-O5 1.01 E-05 1.01 E-05 Na-24 1.01E-05 O.OOE+00 0.00E+00 0.00E+00 2.30E-05 1.70E-03 1.00E-04 6.59E-05 P-32 9.20E-09 2.01 E-09 1.79E-08 4.11E-07 Cr-51 O.OOE+00 O.OOE+00 1.41E-08 0.00E+00 4.41 E-06 0.00E+00 7.31E-O6 0.00E+00 199E-05 4.51 E-06 Mn-54 7.03E-07 0.00E+00 7.43E-05 0.00E+O0 8.18E-07 1.41E-07 0.00E+00 Mn-56 O.OOE+00 0.00E+O0 4.39E-06 1.14E-06 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+OO 0.00E+O0 1.59E-05 2.57E-05 Fe-59 3.08E-05 5.3BE-O5 2.12E-05 O.OOE+00 O.OOE+00 8.97E-06 O.OOE+00 3.60E-O6 8.98E-06 0.00E+OO Co-58 O.OOE+00 0.O0E+O0 2.57E-05 1.08E-05 2.55E-05 0.00E+OO Co^O 0.00E+00 O.OOE+00 0.00E+O0 1.95E-06 3.92E-05 2.20E-05 0.00E+00 Nh63 6.34E-04 0.00E+O0 0.00E+00 0.00E+O0 4.05E-05 Ni-65 4.70E-06 5.32E-07 2.42E-07 1.03E-O6 0.00E+00 1.25E-O5 0.00E+00 8.09E-07 2.82E-07 0.00E+00 Cu-64 O.OOE+00 3.06E-05 0.00E+00 5.33E-05 Zn-65 1.84E-05 6.31 E-05 2.91E-05 6.98E-06 0.00E+00 1.37E-05 9.33E-08 1.68E-07 1.25E-08 O.OOE+00 Zn-69 O.OOE+00 0.0OE+O0 0.00E+0O O.OOE+00 O.OOE+00 3.63E-07 O.OOE+00 Br-83 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 3.82E-07 Br-84 0.00E+00 1.B4E-0B 0.00E+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 4.35&O6 0.00E+00 1.70E-04 8.40E-05 Rb-86 4.85E-07 2.73E-07 O.OOE+00 0.O0E+00 0.00E+00 Rb-88 0.00E+0O 4.96E-O7 O.OOE+00 0.O0E+00 0.00E+00 9.74E-08 O.OOE+00 2.86E-07 1.97E-07 Rb-89 5.16E-05 7.20E-05 0.00E+00 O.OOE+00 O.OOE+00 Sr-89 2.51 E-03 O.OOE+00 O.OOE+00 O.OOE+00 0.O0E+O0 2.31 E-04 Sr-90 1.85E-02 O.OOE+00 4.71 E-03 O.OOE+00 0.00E+00 0.O0E+00 5.92E-O5 Sr-91 5.00E-05 O.OOE+00 1.81 E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Sr-92 1.92E-05 O.OOE+00 7.13E-07 O.OOE+00 0.0OE+O0 O.OOE+00 1.20E-04 8.69E-08 O.OOE+00 2.33E-09 Y-90 2.70E-O6 O.00E+00 0.00E+00 0.00E+O0 Y-S1M 8.10E-10 O.OOE+00 2J6E-11 O.OOE+00 O.OOE+00 O.OOE+00 8.10E-05 Y-81 1.13E-06 O.OOE+00 3.01 E-08 0.O0E+O0 0.00E+O0 1.46E-04 O.OOE+00 2.15E-10 0.00E+00 Y-92 7.65E-09 0.00E+00 0.00E+00 1.92E-O4 O.OOE+00 6.62E-10 0.00E+00 2.43E-08 5.41 E-O8 0.00E+O0 2.50E-05 5.02E-08 3.56E-08 0.00E+00 Zr-05 2.06E-07 0.00E+00 2.56E-O9 0.00E+O0 1.62E-04 1.48E-08 2.54E-09 1.16E-O9 Zr-87 1.46E-O5 1.00E-O8 O.OOE+00 1.24E-08 0.00E+O0 Nb-85 4.20E-08 1.73E-08 0.00E+00 5.08E-05 0.00E+O0 1.12E-O5 O.OOE+00 3.40E-O5 6.63E-06 Mo-99 1.15E-06 O.OOE+00 4.26E-O8 2.07E-09 1.92E-09 3.96E-09 5.10E-08 T&-99M
ODCM Page: 61 Rev.: 21 Table 3.2-13 (Cont.)
Inaestion Dose Factors for Infant WHOLE ISOTOPE BONE UVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 2.27E-09 2.86E-O9 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-O7 Ru-103 1.48E-06 O.OOE+00 4.95E-07 O.OOE+00 3.08E-06 O.OOE+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 O.OOE+00 5.41 E-05 Ru-106 2.41 E-05 O.OOE+00 3.01 E-06 0.00E+00 2.85E-05 O.OOE+00 1.83E-04 Ag-HOM 9.96E-07 7.27E-07 4.81 E-07 O.OOE+00 104E-06 0.00E+00 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 O.OOE+00 0.0OE+O0 1.11E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E-O6 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.60E-O4 0.00E+O0 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.O7E-07 O.OOE+00 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+00 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 O.OOE+00 3.81 E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-O5 0.00E+00 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-O5 0.00E+00 1.51 E-06 1-132 1.66E-O6 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 O.OOE+00 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-O7 4.15E-05 1.98E-06 O.OOE+00 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Ce-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-O7 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81 E-07 5.84E-10 2.55E-08 O.OOE+00 3.51 E-10 3.54E-1C 5.58E-05 Ba-140 1.71E-04 1.71 E-07 8.81 E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+0G 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.63E-10 9.06E-09 O.OOE+00 8.81 E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 O.OOE+00 0.00E+00 O.OOE+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+00 1.48E-08 O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-O9 O.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E^)4 Pr-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+00 1.13E-08 O.OOE+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-08 5.68E-O8 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-O5 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61 E-10 0.00E+00 1.98E-09 O.OOE+00 2.87E-05
ODCM Page: 62 Rev.: 21 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables & 520 630 520 grain (kgfyr)*
Leafy - 26 42 64 vegetabtes(kg/yr)
Milk(Uyr) 330 330 400 310 Meat & poultry 41 65 110 Inhalation (rrrVyr) 1400 3700 8000 8000 Consists of the following (on a mass basis): 22% fruit 54% vegetables (including leafy vegetables), and 24% grain.
Table 3.2-15 Annual Usaae Factors for the Averaae Individual**
Pathway Infarrt Child Teen Adult Fruits, vegetables & 200 240 190 grain (kg/yr)*
Milk (L/yr) 170 200 110 Meat & poultry 37 59 95 Inhalation (m3/yr) - 3700 8000 8000 Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.
For total population and average individual dose calculations.
Rev.: 21 Page: 63 ODCM Figure 3.2-1 PNPP Site Boundary and Unrestricted Area t -ma haamOmrj Hob tfca Ufe>> abac* apqpltea oaly to Uqpli <<fflMacs trlcted <<re* konduy.
UNRESTRICTED AREA
ODCM Page: 64 Rev.: 21 33 mr.FRS0. Add?ptifr I Complia"' - ^^ou>> Effluent Pose
' sraassR52 ta performed at teas. monthly for all 3.3.1 Noble Gases ixl Section II.B.1, limits the releases of gaseous effluents from each the nearest site boundary location for the period of retease.
ODCM Appendix C controls limit the dose resulting from the release of noble gas radionudides in gaseous effluents to the following:
~~a. For gamma radiation, during the current quarter~~
~~_ £ 5 mrad, uair~~
~~b. For beta radiation, during the current quarter Dair ^10 mrad,~~
~~c. For gamma radiation, during the current year:~~
~~n 110 mrad, Dair~~
~~d. For beta radiation, during the current year.~~
<, 20 mrad.
3 3.2 Radioiodines, Particulates, and Other Radionuclides Census each sector.
ODCM Page: 65 Rev.: 21 ODCM, Appendix C, CONTROLS limit the dose resultant from the release of todine-131, iodine-133. tritium, and all radionuclides in particulate form with half-lives greater than eight days to the foiiowing:
~~a. During the current quarter Dose to Any Organ £ 7.5 mrem~~
b. During the current year Dose to Any Organ £ 15 mrem 3.3.3 Dose Calculations The following calculations are used to determine gamma and beta air doses resultant from with 10CFR50, Appendix I. The equations used to calculate organ doses resultant from the release of todine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days are those found In Section 3.2.3.
~~Dose values are obtained by applying the dose rates over the appropriate surveillance or sampling time period.~~
~~a. Gamma Air Dose from Noble Gas Releases Where:~~
y D air = th8 annual gamma air dose due to noble gas radionuclides, mrad/yn y
i = the gamma air dose factor for a uniform semMnfinlte cloud of radionuclide "i", from Table 3.3-1, (mrad m^s Ci);
- the release rate of radionuclide T^Ci/s;
= the annual average dispersion factor (see Appendix A), s/m3; 3.15 x 1 fr = the conversion factor to convert (mrad*^iCi)/(Ci*B) to mrad/yr.
ODCM Page: 66 Rev.: 21
~~b. Beta Air dose from Noble Gas Releases Where:~~
D \ = the annual beta air dose due to noble gas radionuclides, mraoTyr, 3H DF? s the beta air dose factor for a uniform semi-infinite cloud of radionuclide T, from Table 3.3-1, (mrad m8)/(Ci s);
Qi = the release rate of radionuclide T, jiCi/s; x/Q = the annual average dispersion factor (see Appendix A), s/m3; 3.15 x 1 (f- = the conversion factor to convert (mrad*uCi)/(Ci*s) to mrad/yr.
3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly.
Calculations will be performed to determine the maximum air dose as well as the maximum organ dose to an individual. These dose calculations win be summed for comparison with quarterly and annual limits. To assure compliance with 10CFR50, Appendix I, the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2, respectively. The quarterly limits specified in those sections represent one half of the annual design objectives.
If these limits are exceeded, a special report will be submitted to the NRC in accordance with ODCM Appendix C controls.
Table 3.3-1 (mrad/s per Ci/m3)
Gamma Air Beta Air Dose Factor Dose Factor H H)
Ar-41 2.95E+02 1.04E+02 6.12E-01 9.13E+00 Kr-83m Kr-85m 3.90E+01 6.24E+01 Kr-85 5.45E-01 6.18E+01 Kr-87 1.96E+02 3.27E+02 Kr-88 4.82E+02 9.29E+01 Kr-89 5.48E+02 3.36E+02 Kr-90 5.14E+02 2.48E+02 Xe-131m 4.95E+00 3.53E+01 Xe-133m 1.04E+01 4.69E+01 Xe-133 1.12E+01 3.33E+01 Xe-135m 1.07E+02 2.34E+01 Xe-135 6.09E+01 7.80E+01 Xe-137 4.79E+01 4.03E+02 Xe-138 2.92E+02 1.51 E+02
ODCM Page: 67 Rev.: 21 3.3.5 Projection of Doses Anticipated doses resulting from the release of gaseous effluents will be projected monthly.
The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.
In this case the source term will be adjusted to reflect this information and the justification for the adjustment noted.
If the sum of the projected doses for the 31-day period exceeds 0.3 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will be operated to reduce releases. The values for the projected dose impact levels correspond to about one forty-eighth of the 10CFR50, Appendix I dose limits, tf continued for a year, these values would correspond to less than one-fourth of the 10CFR50, Appendix I dose limits.
3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose and average individual dose will be computed, taking into account geographical population distribution and pathway(s) using the equations in Section 3.2.
However, the dose factors. DF^p, differ, total population and average individual doses are calculated in a manner similar to that used for maximum individuals except that Regulatory Guide 1.109. Revision 1, assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all age groups after weighting by the fraction of population in each age group.
ODCM Page: 68 Rev.: 21 4.0 TOTAL DOSE 4.1 40CFR190 and 10CFR72.104 Compliance - Uranium Fuel Cycle Dose Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 and 10CFR72.104 annual limit of 25 mrem whole body or any organ (except the thyroid, which is 75 mrem).
PNPP does not intend to exceed 40CFR190 or 10CFR72.104 limits during normal operation.
However, if such a situation should occur, violations would be handled as per ODCM Appendix C Control 3/4.11.4a. which requires the following:
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a. or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units, from the ISFSI and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above Bmits. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190.
Submlttal of the report Is considered a timely request, and a variance Is granted until staff action on the request is complete.
This Special Report shall contain:
~~1. A determination of which fuel cycle facilities or operations, in addition to the nuclear power reactor unit(s) at the site, contribute to the annual dose to the maximum exposed individual.~~
~~Nuclear fuel facilities over five miles from PNPP need not be considered in this determination.~~
~~2. A determination of the maximum exposed individual.~~
3. A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described In this ODCM. Where addrtiona! information on pathways and nuclides is needed, the best available information will be used and documented.
~~4. A determination of the dose resulting from direct radiation from the plant and storage facilities, including the ISFSI.~~
The whole body and organ doses resulting from liquid effluents from the PNPP will be summed with the doses resulting from gaseous releases of noble gases, radiotodines, tritium, and particulates with half-lines greater than eight days when any of the dose limits outlined in Sections 2.3.2,3.3.1 or 3.3.2 are exceeded by a factor of two. The doses from the PNPP will be summed with the dose to the maximum exposed individual contributed from other operations of the uranium fuel cycle.
ODCM Page: 69 Rev.: 21 4.2 Direct Radiation Dose from PNPP (including the 1SFSI)
Potential direct radiation dose to individuals outside PNPP will arise from (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and (c) direct dose from stored radwaste.
Coolant activation by high energy neutrons, the O18(n,p)N16 reaction, is of interest in boiling water reactors Ike PNPP, because it can result in turbine skyshine and direct dose. Tne N-16 present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separators, and associated equipment Although N-16 has a half-life of 7.13 seconds, its gamma emission can present a radiation dose problem to the site boundary as a result of the high energy gamma scatter from structures and the atmosphere.
All external walls of buildings at PNPP have been designed to attenuate radiation sources from within the plant to maximum of 0.5 mrem/h outside, with an expected radiation dose not to exceed 0.25 mrem/h.
Projected direct radiation dose assessment for normal operations was performed, based on 80%
load factor and 100% occupancy, for the closest site boundary location (WSW sectary. Direct dose from turbine skyshine was calculated to be 1.3 mrem/yr and direct dose from the surface of buildings was calculated to be 2.2 E-3 mrem/yr.
Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with monitoring performed per Table 3.12.1-1, Radiological Environmental Monitoring Program.
4.3 Dose to Members of the Public While Onsite ODCM Appendix C Control 6.9.1.7 requires "assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary.' This assessment is included in Annual Radioactive Effluent Release Reporting.
A member of the public is defined in ODCM Appendix C to include anyone who Is not occupationally associated with the plant, i.e., not a utility employee, contractor or vendor. Also excluded from this category is any person who enters the site to service equipment or make deliveries.
Maximum dose to member of the public while onsite is conservatively assessed relative to oflsite dose values. The assessment methodology incorporates use of appropriate dilution, dispersion, and occupancy factors for onsite activities.
The only liquid effluent dose pathway affecting members of the public while onsite is shore exposure, which is assumed to be fishing on the Lake Erie shoreline. Onsite dose assessment is made via ratio to the maximum calculated oflsite shore exposure dose, using adjustments for occupancy factor and liquid effluent dilution.
ODCM Page: 70 Rev.: 21 Several cases are J^R onsite Including: traversing a public road *>>?"** ^
related training session, at ^Jra^gand Educrt^ ?££ g ^.Z*9 Contml Point (PACP) parking lot, ^vi*^jS^J^ are me product of the highest
relative X/Q' (atmospheric dispersion) values.J*"£W°sSoMbrme ease. The ratio of the annual average x/Q forthe P<**of concern,^gJ^K^Sf s used as an adjustment hfchest onste 'relative xW to the ^ * *22£LSm3^~highest site boundary "relative factor. (A unity occupancy factor <<'>T^^XSSm\Tw"^ *e "relative yJV adjustment dose.
ODCM Page: 71 Rev.: 21 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1 Monitoring Program Environmental samples shall be collected and analyzed according to Table 3.12.1-1 at locations shown in Figures 5.1-1,5.1-2 and 5.1-3. Analytical techniques used shall ensure that the detection capabilities in Table 4.12.1-1 are achieved.
Ground water sampling will not be conducted as part of PNPP's REMP because this source is not tapped for dnnking or irrigation purposes in the area of the plant The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain system will flow north towards Lake Erie. Local domestic wells outside the exclusion area boundary are up-gradierrt from the plant As part of the REMP, samples will be routinely collected from the closest potable water intakes on Lake Erie.
The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monltonng program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. The initial radiological environmental monitoring program was conducted for the first three years of commercial operation-program changes may now be proposed based on operational experience 5.2 Land Use Census Program A Land Use Census shall be conducted annually to identify, within a distance of 8 km (5 miles) the tocation in each of the meteorological sectors of the nearest residence, the nearest garden1 greater than 50m2 (500 ft2) and the nearest milk-producing animal.
tf a Land Use Census identifies a locations) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently being obtained the new location(s) will be added to the radiological environmental monitoring program within 30 days. The sampling locations), excluding the control station location, having the lowest calculated dose or dose commitment^), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.
The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey aerial survey, general observations, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
Broad leaf vegetation sampling of at least three different types of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.
ODCM Page: 72 Rev.: 21 5.3 Inter-Laboratory Cnnnparispn P""iam The laboratories of the licensee and/or licensee'.
Environmental Operating Report.
ODCM Page: 73 Rev.: 21 Table 5.1-1 ODCM REMP SamDie Locations Location # Description Miles Direction Media")
1 Chapel Road 3.4 ENE TL0, AIP 2 Kanda Garden 1.9 ENE Broadleaf Vegetation 3 Meteorological Tower 1.0 SE TLD 4 Site Boundary 0.7 S TLD, AIP 5 Quincv Substation 0.6 SW TLD 6 Concord Service Center 11.0 SSW TLD. AIP 7 Site Boundary 0.6 NE TLD, AIP 8 Site Boundary 0.8 E TLD 9 Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Parmrv Rd. 0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madison-on-the-Lake 4.7 ENE TLD 14 Hubbard Rd. 4.9 E TLD 15 Eagle St Substation 5.1 ESE TLD 16 Eubank Garden 0.9 S Broadleaf Vegetation 20 Rainbow Farms 1.9 E Broadleaf Vegetation 21 Hardy Rd. 5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St ClairAve. 15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Fish 29 River Rd. 4.3 SSE TLD 30 LaneRd. 4.8 SSW TLD 31 Wood and River Rd. 4.8 SE TLD 32 Offshore - Mentor 15.8 WSW Fish 33 River Rd. 4.5 S TLD 35 Site Boundary 0.6 E TLD, AIP 36 Lake County Water Plant 3.9 WSW TLD, Drinking Water 37 Gerlica Farm 1.5 ENE Broadleaf Vegetation 39 Painesville Purification Plant 8.3 W Drinking Water 53 3715 Parmly Rd. 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd. 2.5 S TLD 56 Madison High School 4.0 ESE TLD 57 Perry High School 1.7 S TLD j I o<<.-ww z>>n 58 Antioch Rd. 0.8 ENE TLD 59 Lake Shoreline at Green Rd. 4.0 ENE Surface Water 60 Lake Shoreline at Perry Park 1.0 WSW Surface Water 66 Lake Shore Metropolitan Park 1.4 NE Sediment 70 H&H Farm Stand 16.2 SSW Broadleaf Vegetation (1) AIP* Air, Iodine and Particulate TLD = Themokimineacent Dosimeter
ODCM Page: 74 Rev.: 21 Figure 5.1-1 ODCM REMP sample locations within two mites of PNPP NNW NNE NW WNW ESE wsw SE SSE SSW
ODCM Page: 75 Rev.: 21 Figure 5.1-2 ODCM required REMP sample locations between two and eight miles of PNPP SW SSW ZoCl
Rev.: 21 Page: 76 ODCM Figure 5.1-3 ODCM required REMP sample locations greater than eight mites from PNPP
ODCM Page: 77 Rev.: 21 APPENDIX A ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS
ODCM Page; 78 Rev.: 21 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations. Dose calculations will be performed using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or using historical average atmospheric conditions. All atmospheric releases at PNPP are considered to be ground-level releases.
Constant Mean Wind Direction Relative Dispersion Factor r/ (2032 XTf)
AT T (u)(x)(<<)
Where:
x/Q = the annual average dispersion factor, s/m3; Tf
the terrain correction factor, from FSAR Table 2.3-26, dimensionless; u = the wind speed (measured at 10m), in m/s; X = the distance of calculation, in m; 2.032 = (2/tc)* divided by the width in radians of a 22.5°sector
= the Jesser of <r£ + -£ or (oz) (:
2n V Where:
% = the building height (44.8m);
az = the vertical dispersion coefficient, per Regulatory Guide 1.111, in m.
~~b. Depleted Relative Dispersion Factor Where:~~
X/Qd = the depleted relative dispersion factor (for airborne halogens and particulates), in s/m3; DPL j = the ground depletion factor for the "j"th distance, interpolated from Table A-1, dimensionless; x/Q = the annual average dispersion factor per equation A-1, s/m3.
~~c. Ground Deposition (A-3)~~
(o.3927)(x)
Where:
D/Q = the relative deposition per unit area (for halogens and particulates), nr2; DEP. = the ground deposition factor for the "fth distance, interpolated from Table A-1, irr1; Tf = terrain correction factor, from FSAR Table 2.3-26, dimensionless; x = the "jth distance, m; 0.3927 = radians per 22.5° sector
ODCM Page: 79 Rev.: 21 Table A-1 Atmospheric DeDletion and Deoosition Factors Depletion Deposition Factors Factors (DPLj) (DEPj, nr1)
Pasquill Stability Class All All 200 0.970 1.25E-04 Distance (meters) 500 0.936 8.0E-05 1,000 0.900 5.4E-05 2,000 0.860 3.2E-05 3,000 0.832 2.6E-05 6,000 0.770 1.5E-05 10,000 0.714 9.9E-06 30.000 0.590 4.5E-06 50,000 0.517 3.0E-06 80,000 0.440 2.0E-06 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP. Long-term releases are those that occur greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year.
The highest annual average relative concentration (x/Q) value at the site boundary for sectors over land shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was XOQDOQ, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on seven years of meteorological data (May 1,1972 through April 30,1974 and September 1,1977 through August 31,1982), ground-level releases, sector spread for purge calculations, and twelve wind speed classes.
ODCM Page: 80 Rev.: 21 Table A-2
{WQ} and Deposition Site Boundary AtmoSD h^rjc piapersion Paramete^D/QHorPNP*P Unit 1 Distance Distance x/Q D/Q (meters) (sec/m3) (perm2)
Sector (miles) 294 5.7E-05* 1.6E-07 N 0.18 1.8E-O5* 7.9E-08 NNE 0.25 402 5.8E-06* 3.1E-08 NE 0.42 678 2.1E-06* 1.6E-08 ENE 0.67 1079 2.2E-06 1.8E-08 E 0.67 1079 1.6E-06 1.3E-08 ESE 0.67 1079 1.4E-06 1.1E-08 SE 0.79 1271 2.2E-06 1.4E-08 SSE 0.82 1320 2.7E-06 1.6E-08 s 0.81 1304 1.3E-06 6.8E-09 ssw 0.80 1287 2.3E-06* 1.1E-08 sw 0.65 1047 4.2E-06* 1.5E-08 wsw 0.56 900 2.5E-05* 4.6E-08 w 0.27 430 5.9E-05* 8.4E-08 WNW 0.18 283 6.6E-05* 1.1E-07 NW 0.17 273 5.9E-05* 1.2E-07 NNW 0.17 280 All x/Q and D/Q values are taken from the Updated Safety Analysis Report (USAR)
Tabte 2 3-27. All marked values (*) are from Unit 1 USAR values and the balance are Un.t 2 values. In each case, the most conservative x/Q value >> utilized.
ODCM Page: 81 Rev.: 21 TabteA-3 AtmosDheric DisDersion h/Q) as a Function of Distance (s/mfa SECTOR 0.2 0.3 0.4 0.5 0.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4.904E-05 2.453E-05 1.525E-05 1.057E-05 7.918E-06 NNE 2.656E-05 1.360E-05 8.640E-06 6.082E-06 4.612E-06 NE 1.859E-05 9.760E-06 6.293E-06 4.460E-O6 3.383E-06 ENE 1.327E-05 7.129E-06 4.636E-06 3.293E-06 2.490E-06 E 1.363E-05 7.362E-06 4.760E-06 3.367E-06 2.538E-06 ESE 1.025E-05 5.566E-06 3.602E-06 2.547E-06 1.916E-06 SE 1.113E-O5 6.061 E-06 3.935E-06 2.788E-06 2.100E-06 SSE 1.894E-05 1.022E-05 6.647E-06 4.718E-06 3.560E-06 S 2.283E-05 1.227E-05 7.932E-06 5.615E-05 4.238E-06 SSW 1.142E-05 6.079E-06 3.925E-06 2.777E-06 2.097E-06 SW 1.449E-05 7.663E-06 4.928E-06 3.479E-06 2.622E-06 WSW 2.151 E-05 1.111E-05 7.031 E-06 4.934E-06 3.733E-06 W 4.184E-05 2.081 E-05 1.281E-05 8.833E-06 6.606E-06 WNW 4.669E-05 2.298E-05 1.401E-05 9.573E-06 7.093E-06 NW 4.908E-05 2.423E-05 1.482E-05 1.015E-05 7.521 E-06 NNW 4.580E-05 2.266E-05 1.390E-05 9.541 E-06 7.083E-06 SECTOR 0.7 0.8 0.9 10 1.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 6.138E-06 4.968E-06 4.203E-06 3.636E-06 1.949E-06 NNE 3.622E-06 2.947E-06 2.481 E-06 2.132E-06 1.278E-06 NE 2.662E-06 2.165E-06 1.815E-06 1.552E-06 9.269E-07 ENE 1.957E-06 1.588E-06 1.325E-06 1.129E-06 6.710E-07 E 1.991 E-06 1.613E-06 1.343E-06 1.141 E-06 6.768E-07 ESE 1.501 E-06 1.215E-06 1.010E-06 8.571 E-07 5.080E-07 SE 1.647E-06 1.334E-06 1.108E-06 9.402E-07 4.456E-07 SSE 2.796E-06 2.266E-06 1.885E-06 1.601 E-06 5.524E-07 S 3.327E-06 2.697E-06 2.247E-06 1.911 E-06 7.340E-07 SSW 1.646E-06 1.335E-06 1.114E-06 9.486E-07 5.223E-07 SW 2.053E-06 1.664E-06 1.391 E-06 1.188E-06 5.667E-07 WSW 2.927E-06 2.380E-06 2.002E-06 1.719E-06 8.671 E-07 W 5.110E-06 4.135E-06 3.504E-06 3.036E-06 1.630E-06 WNW 5.434E-06 4.378E-06 3.719E-06 3.235E-06 1.845E-06 NW 5.764E-06 4.643E-06 3.941 E-06 3.425E-06 1.952E-06 NNW 5.439E-06 4.385E-06 3.720E-06 3.230E-06 1.839E-06
ODCM Page: 82 Rev.: 21 Table A-3(Cont)
Atmosnl ierie DisDarsion fa/C3) ?R a Function of Distance (s/m°>
1.4 1.5 1.6 SECTOR 1.2 1.3 (MILES) (MILES)
(MILES) (MILES)
(MILES) 1.399E-06 1.273E-06 1.166E-06 1.729E-06 1.549E-06 N 8.202E-07 7.485E-07 1.006E-06 9.050E-07 NNE 1.128E-06 6.494E-07 5.867E-07 5.340E-07 8.150E-07 7.243E-07 NE 4.190E-07 3.803E-07 5.205E-07 4.652E-07 ENE 5.878E-07 4.197E-07 3.804E-07 5.230E-07 4.667E-07 E 5.917E-O7 3.494E-07 3.140E-07 2.843E-07 4.437E-07 3.919E-07 ESE 2.491 E-07 3.436E-07 3.062E-07 2.751 E-07 SE 3.891 E-07 3.102E-07 4.267E-07 3.807E-07 3.423E-07 SSE 4.829E-07 5.076E-07 4.569E-07 4.145E-07 S 6.424E-07 5.684E-07 3.266E-07 2.965E-07 4.054E-07 3.624E-07 SSW 4.576E-07 3.570E-07 3.246E-07 4.976E-07 4.417E-07 3.955E-07 SW 5.547E-07 5.060E-07 7.648E-07 6.814E-07 6.125E-07 WSW 1.070E-06 9.809E-07 1.448E-06 1.299E-06 1.175E-06 W 1.224E-06 1.124E-06 1.479E-06 1.341E-06 WNW 1.644E-06 1.292E-06 1.186E-06 1.563E-06 1.416E-06 NW 1.733E-06 1.332E-06 1.214E-06 1.115E-06 1.637E-06 1.471E-06 NNW 1.9 2.0 2.1 SECTOR 1.7 1.8 (MILES) (MILES)
(MILES) (MILES) (MILES) 9.226E-07 8.604E-07 8.052E-07 1.074E-06 9.931 E-07 N 5.090E-07 5.B64E-07 5.453E-07 6.867E-07 6.331 E-07 NNE 3.854E-07 3.263E-07 4.494E-07 4.153E-07 NE 4.886E-07 2.526E-07 2.936E-07 2.718E-O7 3.471E-07 3.184E-07 ENE 2.705E-07 2.283E-07 3.467E-07 3.177E-07 2.925E-07 E 1.871 E-07 2.371 E-07 2.182E-07 ESE 2.590E-07 1.637E-07 2.076E-07 1.910E-07 1.765E-07 SE 2.268E-07 2.205E-07 1.407E-07 2.590E-07 2.384E-07 SSE 2.827E-07 3.194E-07 2.955E-07 1.373E-07 3.780E-07 3.466E-07 S 2.121 E-07 1.409E-O7 2.484E-07 2.290E-07 SSW 2.706E-07 2.173E-07 2.518E-O7 2.335E-07 SW 2.968E-07 2.727E-07 3.678E-07 5.303E-07 4.275E-07 3.957E-07 WSW 4.639E-07 1.050E-06 7.777E-07 7.258E-07 9.037E-07 8.365E-07 W 8.375E-07 1.142E-06 9.622E-07 8.960E-07 WNW 1.038E-06 8.275E-07 9.445E-07 8.826E-07 1.095E-06 1.015E-06 NW 8.281 E-07 7.761 E-07 9.527E-07 8.865E-07 NNW 1.028E-06
ODCM Page: 83 Rev.: 21 Table A-3(Cont.)
Atmospheric Dispersion MQ) as a Function of Distance (&fm*\
SECTOR 2.2 2.3 2.4 2.5 2.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 7.560E-O7 7.118E-07 6.720E-O7 6.359E-07 6.033E-07 NNE 4.766E-07 4.477E-07 4.217E-07 3.982E-O7 3.770E-07 NE 3.050E-O7 2.859E-07 2.688E-07 2.534E-07 2.395E-07 ENE 2.356E-07 2.205E-07 2.069E-07 1.947E-07 1.837E-07 E 2.127E-07 1.988E-07 1.864E-07 1.752E-07 1.652E-07 ESE 1.743E-07 1.628E-07 1.525E-07 1.433E-07 1.351 E-07 SE 1.524E-07 1.424E-07 1.334E-07 1.253E-07 1.181E-07 SSE 1.311E-O7 1.225E-07 1.149E-07 1.080E-07 1.018E-07 S 1.280E-07 1.197E-07 1.123E-07 1.056E-07 9.963E-08 SSW 1.314E-07 1.230E-07 1.154E-07 1.087E-07 1.025E-07 SW 2.030E-07 1.902E-07 1.787E-07 1.683E-07 1.590E-07 WSW 4.964E-07 4.661E-07 4.388E-07 4.142E-07 3.920E-07 W 9.867E-07 9.296E-07 8.780E-07 8.313E-07 7.891 E-07 WNW 1.075E-06 1.014E-06 9.587E-07 9.088E-07 8.636E-07 NW 7.782E-07 7.339E-07 6.939E-D7 6.576E-07 6.247E-07 NNW 7.297E-07 6.879E-07 6.502E-07 6.161 E-07 5.852E-07 SECTOR 2.7 2.8 2.9 3.0 3.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 5.734E-07 5.460E-07 5.208E-07 4.976E-07 4.762E-07 NNE 3.576E-07 3.398E-07 3.235E-07 3.086E-07 2.948E-07 NE 2.268E-07 2.152E-07 2.046E-07 1.949E-07 1.859E-07 ENE 1.737E-07 1.645E-07 1.562E-07 1.485E-07 1.415E-07 E 1.560E-07 1.477E-07 1.401E-07 1.331 E-07 1.267E-07 ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-08 SE 1.115E-07 1.054E-07 9.996E-08 9.493E-08 9.031 E-08 SSE 9.613E-06 9.099E-08 8.630E-08 8.200E-08 7.805E-08 S 9.415E-08 8.917E-08 8.462E-08 8.044E-08 7.661 E-08 SSW 9.697E-08 9.189E-08 8.725E-08 8.299E-08 7.907E^)8 SW 1.505E-07 1.428E-07 1.357E-07 1.291E-07 1.231 E-07 WSW 3.716E-07 3.531E-07 3.360E-07 3.204E-07 2.520E-O7 w 7.503E-07 7.147E-07 6.820E-07 6.519E-07 5.874E-07 WNW 8.220E-07 7.838E-07 7.487E-07 7.164E^)7 7.722E-07 NW 5.945E-07 5.668E-07 5.413E-07 5.178E-07 5.412E-07 NNW 5.567E-O7 5.307E-07 5.067E-07 4.846E-07 4.642E-07
ODCM Page: 84 Rev.: 21 Table A-3 (Cont.)
AtmosDheric Dispersion fy/Q} as a Fun^Hon of Distance Mm*)
3.3 3.4 3.5 3.6 SECTOR 3.2 (MILES) (MILES) (MILES) (MILES)
(MILES) 4.208E-07 4.047E-07 3899E-07 N 4.563E-07 4.379E-07 2.702E-07 2.592E-07 2.489E-07 2.395E-07 NNE 2.820E-07 1.700E-07 1.629E-07 1.562E-07 1.501 E-07 NE 1.777E-07 1.290E-07 1.234E-07 1.182E-07 1.135E-07 ENE 1.350E-O7 1.154E-07 1.103E-07 1.056E-07 1.013E-07 E 1.208E-07 8.550E-08 8.173E-08 7.821 E-08 7.499E-08 ESE 8.958E-08 8.213E-08 7.849E-08 7.510E-O8 7.200E-O8 SE 8.606E-08 7.105E-08 6.794E-08 6.503E-08 6.237E-08 SSE 7.441 E-OB 6.980E-08 6.678E-0S 6.395E-08 6.136E-08 s 7.307E-08 7.212E-08 6.902E-08 6.613E-08 6.348E-08 SSW 7.546E-08 1.125E-07 1.077E-07 1.033E-07 9.922E-08 SW 1.176E-07 2.308E-07 2.214E-07 2.125E-07 2.044E-07 wsw 2.410E-07 5.406E-07 5.196E-07 4.999E-07 4.818E-07 w 5.631 E-07 7.118E-O7 6.848E-07 6.593E-07 6.359E-07 WNW 7.409E-07 4.987E-07 4.797E-07 4.618E-07 4.454E-07 NW 5.192E-07 4.276E-07 4.112E-07 3.958E-07 3,817E^07 NNW 4.452E-07 3.8 3.9 4.0 4.1 SECTOR 3.7 (MILES) (MILES) (MILES) (MILES)
(MILES) 3.628E-07 3.504E-07 3.388E-07 2.981 E-07 N 3.759E-07 2.222E-07 2.144E-07 2.070E-07 1.819E-07 NNE 2.306E-07 1.390E-07 1.339E-07 1.292E-07 1.247E-07 NE 1.444E-07 1.048E-07 1.009E-07 9.718E-08 9.373E-08 ENE 1.090E-07 9.342E-08 8.987E-08 8.653E-08 8.341 E-08 E 9.722E-08 6.912E-08 6.647E-08 6.399E-08 6.166E-O8 ESE 7.196E-08 6.635E-08 6.380E-08 6.140E-08 5.378E-08 SE 6.908E-08 5.753E-08 5.533E-08 5.328E-08 5.135E-O8 SSE 5.987E-0B 5.451 E-08 5.251 E-08 5.063E-08 s 5.892E-08 5.664E-08 5.865E-08 5.646E-08 5.441 E-08 5.248E-08 SSW 6.09BE-08 9.537E-08 9.178E-08 8.841 E-08 8.525E-08 8.228E-08 SW 1.896E-07 1.828E-07 1.765E-07 1.462E-07 wsw 1.967E-07 4.485E-07 4.334E-07 4.191 E-07 3.043E-07 w 4.646E-07 6.929E-07 5.733E-07 5.548E-07 4.180E-07 WNW 6.137E-07 4.151 E-07 4.013E-07 3.883E-07 3.761 E-07 NW 4.298E-07 3.556E-07 3.438E-07 3.326E-07 2.928E-07 NNW 3.682E-07
ODCM Page: 85 Rev.: 21 Table A-3(Cont)
AtmosDheric Disoersion MQ) as a Function of Distance isfm3)
SECTOR 4.2 4.3 4.4 4.5 4.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 NNE 1.759E-07 1.703E-07 1.650E-07 1.599E-07 1.552E-07 NE 1.205E-07 1.166E-07 1.128E-07 1.093E-07 1.059E-07 ENE 9.047E-08 8.740E-O8 8.451E-08 8.176E-08 7.921 E-08 E 8.046E-08 7J69E-08 7.508E-08 7.260E-O8 7.030E-08 ESE 5.946E-08 5.740E-08 5.545E-08 5.361 E-08 5.189E-08 SE 5.186E-08 5.005E-08 4.835E-08 4.673E-08 4.523E-08 SSE 4.954E-08 4.783E-08 4.622E-08 4.469E-08 4.327E-08 S 4.886E-08 4.719E-08 4.562E-08 4.413E-08 4.274E-O8 SSW 5.067E-08 4.896E-08 4.735E-08 4.581 E-08 4.439E-O8 SW 7.948E-08 7.684E-08 7.435E-08 7.198E-08 6.978E-08 WSW 1.413E-07 1.368E-07 1.325E-07 1.284E-07 1.246E-07 W 2.948E-07 2.858E-07 2.773E-07 2.691 E-07 2.616E-07 WNW 4.051 E-07 3.930E-07 3.815E-07 3.706E-07 3.603E-07 NW 3.645E-07 3.536E-07 3.432E-07 3.333E-07 3.241 E-07 NNW 2.837E-07 2.752E-07 2.671 E-07 2.593E-07 2.521 E-07 SECTOR 4.7 4.8 4.9 5.0 (MILES) (MILES) (MILES) (MILES)
N 2.487E-07 2.419E-07 2.354E-07 2.292E-07 NNE 1.507E-07 1.464E-07 1.423E-07 1.384E-07 NE 1.028E-07 9.975E-08 9.689E-08 9.416E-08 ENE 7.676E-08 7.443E-08 7.223E-08 7.014E-08 E 6.809E-08 6.600E-08 6.402E-08 6.214E-08 ESE 5.025E-08 4.869E-08 4.722E-08 4.582E-08 SE 4.379E-08 4.244E-08 4.115E-08 3.992E-08 SSE 4.191 E-08 4.063E-08 3.941 E-08 3.825E-08 S 4.141E-08 4.015E-08 3.896E-08 3.782E-08 SSW 4.302E-08 4.173E-08 4.050E-08 3.934E-08 SW 6.767E-O8 6.567E-08 6.377E-08 6.196E-08 WSW 1.210E-O7 1.175E-07 1.142E-07 1.110E-07 W 2.543E-07 2.474E-07 2.408E-07 2.345E-07 WNW 3.505E-07 3.411 E-07 3.322E-07 3.237E-07 NW 3.152E-07 3.068E-07 2.987E-07 2.910E-07 NNW 2.452E-07 2.336E-07 2.323E-07 2.263E-07
ODCM Page: 86 Rev.: 21 Table A-4
-Z\
Atmospheric Dispersion (DIQ\ as a Function of Distance (m')
0.4 0.5 0.6 SECTOR 0.2 0.3 (MILES) (MILES) (MILES)
(MILES) (MILES) 4.836E-08 3.383E-08 2.516E-08 N 1.396E-07 7.578E-08 3.834E-Q8 2.682E-08 1.995E-08 NNE 1.107E-07 6.008E-08 3.372E-08 2.359E-08 1.755E-O8 NE 9.733E-08 5.284E-08 3.698E-08 2.587E-08 1.924E-08 ENE 1.067E-07 5.795E-08 4.103E-08 2.870E-08 2.135E-08 E 1.184E-07 6.429E-08 3.071 E-08 2.149E-08 1.598E-08 ESE 8.865E-08 4.813E-08 3.258E-08 2.279E-08 1.695E-O8 SE 9.402E-08 5.105E-08 4.637E-08 3.244E-08 2.413E-08 SSE 1.338E-07 7.266E-08 4.951 E-08 3.463E-08 2.576E-08 S 1.429E-07 7.757E-08 2.111 E-08 1.477E-08 1.099E-0B SSW 6.094E-08 3.309E-08 2.518E-08 1.761 E-08 1.310E-08 SW 7.267E-08 3.945E-08 2.466E-08 1.725E-08 1.283E-08 WSW 7.117E-08 3.864E-08 2.47OE-08 1J28E-08 1.285E-08 W 7.129E-08 3.870E-08 2.415E-08 1.689E-08 1.256E-08 WNW 6.970E-08 3J84E-08 3.085E-08 2.158E-08 1.605E-08 NW 8.904E-08 4.834E-08 3.334E-08 2.332E-08 1.735E-08 NNW 9.623E-08 5.225E-08 0.9 1.0 1.1 SECTOR 0.7 0.8 (MILES) (MILES) (MILES)
(MILES) (MILES) 1.560E-08 1.277E-08 1.068E-08 5.545E-O9 N 1.954E-08 1.013E-08 8.465E-09 4.945E-09 NNE 1.549E-08 8.907E-09 7.445E-09 4.350E-O9 NE 1.362E-08 1.088E-08 9.768E-09 8.164E-09 4.770E-09 ENE 1.494E-08 1.193E-08 1.084E-08 9.058E-O9 5.292E-09 E 1.658E-08 1.323E-08 9.905E-09 8.112E-09 6.781 E-09 3.961 E-09 ESE 1.241E-08 8.605E-09 7.192E-09 3.361 E-09 SE 1.316E-08 1.051 E-08 1.225E-08 1.024E-08 3.480E-09 SSE 1.874E-08 1.496E-08 1.308E-08 1.093E-08 4.128E-09 S 2.000E-08 1.597E-08 5.577E-09 4.662E-09 2.521 E-09 SSW 8.531 E-09 6.810 E-09 6.651 E-09 5.559E-09 2.598E-09 SW 1.017E-08 8.120E-09 6.513E-09 5.444E-09 2.678E-09 WSW 9.963E-09 7.953E-09 6.524E-O9 5.453E-09 2.832E4)9 9.980E-09 7.966E-09 w
6.379E-09 5.332E-09 2.932E-09 WNW 9.757E-09 7.788E-09 9.949E-09 8.148E-09 6.811 E-09 3J45E-09 NW 1.246E-08 8.807E-09 7.361 E-09 4.047E-09 NNW 1.347E-08 1.075E-08
ODCM Page: 87 Rev.: 21 Table A-4 (Cont)
AtmosDheric Deoosition iD/Q) as a Function of Distance (m~2)
SECTOR 1.2 1.3 1.4 1.5 1.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4.777E-09 4.163E-09 3.664E-09 3.252E-09 2.910E-09 NNE 4.260E-09 3.713E-09 3.268E-09 2.900E-09 2.595E-09 NE 3.747E-09 3.265E-09 2.874E-09 2.551 E-09 2.283E-09 ENE 4.109E-09 3.581 E-09 3.151 E-09 2.797E-09 2.503E-09 E 4.559E-09 3.973E-09 3.497E-09 3.104E-09 2.777E-09 3.413E-09 2.974E-09 2.617E-09 2.323E-09 2.079E-09 SE 2.896E-09 2.524E-09 2.221E-09 1.971 E-09 1.764E-09 SSE 2.998E-09 2.612E-09 2.299E-09 2.041 E-09 1.826E-09 S 3.556E-O9 3.099E-09 2.727E-09 2.421 E-09 2.166E-09 SSW 2.172E-09 1.892E-09 1.666E-09 1.478E-09 1.323E-09 SW 2.238E-09 1.950E-O9 1.717E-O9 1.524E-09 1.363E-09 WSW 2.307E-09 2.011 E-09 1.770E-09 1.571 E-09 1.406E-09 W 2.440E-09 2.126E-09 1.871 E-09 1.661 E-09 1.486E-09 WNW 2.525E-09 2.201 E-09 1.937E-09 1.719E-09 1.538E-09 NW 3.226E-09 2.811 E-09 2.474E-09 2.196E-09 1.965E-09 NNW 3.487E-09 3.039E-09 2.674E-09 2.374E-09 2.124E-09 SECTOR 1.7 1.8 1.9 2.0 2.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 2.619E-09 2.371 E-09 2.158E-O9 1.973E-09 1.812E-09 NNE 2.336E-09 2.115E-09 1.925E-09 1.760E-09 1.616E-09 NE 2.055E-09 1.860E-09 1.693E-09 1.548E-09 1.292E-09 ENE 2.253E-09 2.040E-09 1.856E-09 1.697E-09 1.558E-09 E 2.500E-09 2.263E-09 2.059E-09 1.883E-09 1.572E-09 ESE 1.871E-09 1.694E-09 1.542E-09 1.410E-09 1.294E-09 SE 1.583E-09 1.437E-O9 1.308E-09 1.196E-09 1.098E-09 SSE 1.644E-09 1.488E-09 1.354E-09 1.238E-09 7.816E-10 S 1.950E-09 1.765E-09 1.606E-09 1.469E-09 6.743E-10 SSW 1.191E-09 1.078E-09 9.810E-10 8.969E-10 5.883E-10 SW 1.227E-09 1.111E-09 1.011 E-09 9.244E-10 8.488E-10 WSW 1.265E-09 1.145E-O9 1.042E-09 9.530E-10 1.352E-09 W 1.338E-09 1.211 E-09 1.102E-O9 1.008E-09 1.430E-09 WNW 1.385E-09 1.254E-09 1.141E-09 1.043E-09 1.393 E-09 NW 1.769E-09 1.601E-09 1.457E-09 1.333E-09 1.223E-09 NNW 1.912E-09 1.731 E-09 1.575E-09 1.440E-09 1.322E-09
ODCM Page: 88 Rev.: 21 Table A-4(Cont)
AtmosDheric DeDosition (D!Q\ as a Function of Distance (m"2)
SECTOR 2.2 2.3 2.4 2.5 2.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.670E-09 1.544E-09 1.433E-09 1.334E-09 1.245E-09 NNE 1.489E-09 1.377E-09 1.278E-09 1.189E-O9 1.110E-09 NE 1.191E-09 1.101 E-09 1.022E-09 9.511E-10 8.879E-10 ENE 1.436E-09 1.328E-09 1.233E-09 1.147E-09 1.071 E-09 E 1.449E-09 1.340E-09 1.243E-09 1.157E-09 1.080E-09 ESE 1.193E-09 1.103E-09 1.O24E-09 9.528E-10 8.895E-10 SE 1.012E-O9 9.362E-10 8.687E-10 8.085E-10 7.548E-10 SSE 7.204E-10 6.663E-10 6.183E-10 5.754E-10 5.372E-10 S 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 SSW 5.422E-10 5.015E-10 4.653E-10 4.331 E-10 4.043E-10 SW 7.823E-10 7.236E-10 6.714E-10 6.249E-10 5.834E-10 wsw 1.246E-09 1.153E-09 1.070E-09 9.956E-10 9.294E-10 w 1.318E-09 1.219E-09 1.131E-09 1.053E-09 9.827E-10 WNW 1.284E-09 1.188E-09 1.102E-09 1.026E-09 9.575E-10 NW 1.128E-09 1.043E-09 9.678E-10 9.007E-10 8.409E-10 NNW 1.219E-09 1.127E-09 1.046E-09 9.735E-10 9.089E-10 SECTOR 2.7 2.8 2.9 3.0 3.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.165E-09 1.092E-09 1.026E-09 9.666E-10 9.120E-10 NNE 1.039E-09 9.742E-10 9.155E-10 8.621 E-10 8.134E-10 NE 8.307E-10 7.789E-10 7.320E-10 6.893E-10 6.504E-10 ENE 1.002E-09 9.396E-10 8.830E-10 8.315E-10 7.845E-10 E 1.011 E-09 9.477E-10 8.906E-10 8.387E-10 7.913E-10 ESE 8.322E-10 7.804E-10 7.334E-10 6.906E-10 5.923E-10 SE 7.061 E-10 6.622E-10 6.223E-10 5.860E-10 5.529E-10 SSE 5.026E-10 4.713E-10 4.429E-10 4.171 E-10 3.935E-10 S 4.336E-10 4.066E-10 3.821E-10 3.598E-10 3.395E-10 3.782E-10 3.647E-10 3.333E-10 3.139E-10 2.961 E-10 SSW SW 5.458E-10 5.118E-10 4.810E-10 4.529E-10 4.273E-10 WSW 8.695E-10 8.154E-10 7.663E-10 7.216E-10 5.607E-10 w 9.194E-10 8.621 E-10 8.102E-10 7.630E-10 6.775E-10 WNW 8.958E-10 8.400E-10 7.894E-10 7.434E-10 7.890E-10 NW 7.867E-10 7.377E-10 6.933E-10 6.528E-10 6.719E-10 NNW 8.503E-10 7.973E-10 7.493E-10 7.056E-10 6.657E-10
ODCM Page: 89 Rev.: 21 Table A-4(Cont.)
AtmosDheric Deoosition IDIQ) as a Function of Distance (m'2)
SECTOR 3.2 3.3 3.4 3.5 3.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 8.620E-10 8.161 E-10 7.739E-10 7.347E-10 6.991 E-10 NNE 7.688E-10 7.279E-10 6.902E-10 6.552E-10 6.235E-10 NE 6.147E-10 5.820E-10 5.518E-10 5.239E-10 4.985E-10 ENE 7.415E-10 7.020E-10 6.657E-10 6.320E-10 6.014E-10 E 7.479E-10 7.081E-10 6.714E-10 6.374E-10 6.066E-10 ESE 5.598E-10 5.300E-10 5.026E-10 4771E-10 4.541 E-10 SE 5.225E-10 4.947E-10 4.691E-10 4.454E-10 4.238E-10 SSE 3.719E-10 3.521E-10 3.339E-10 3.170E-10 3.016E-10 S 3.209E-10 3.038E-10 2.880E-10 2.735E-10 2.602E-10 SSW 2.799E-10 2.650E-10 2.513E-10 2.386E-10 2.270E-10 SW 4.039E-10 3.824E-10 3.626E-10 3.442E-10 3.276E-10 WSW 5.299E-10 5.017E-10 4.757E-10 4.516E-10 4.298E-10 W 6.403E-10 6.062E-10 5.749E-10 5.458E-10 5.193E-10 WNW 7.457E-10 7.060E-10 6.695E-10 6.356E-10 6.048E-10 NW 6.351E-10 6.013E-10 5.702E-10 5.413E-10 5.151E-10 NNW 6.292E-10 5.957E-10 5.649E-10 5.363E-10 5.103E-10 SECTOR 3.7 3.8 3.9 4.0 4.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 6.657E-10 6.347E-10 6.059E-10 5.791 E-10 5.036E-10 NNE 5.937E-10 5.661E-10 5.404E-10 5.165E-10 4.492E-10 NE 4.747E-10 4.526E-10 4.321E-10 4.129E-10 3.951E-10 ENE 5.727E-10 5.460E-10 5.212E-10 4.981 E-10 4.766E-10 E 5.776E-10 5.507E-10 5.257E-10 5.024E-10 4.807E-10 ESE 4.324E-10 4.122E-10 3.935E-10 3.761 E-10 3.598E-10 SE 4.036E-10 3.848E-10 3.673E-10 3.510E-10 3.053E-10 SSE 2.872E-10 2.739E-10 2.614E-10 2.498E-10 2.390E-10 S 2.478E-10 2.363E-10 2.255E-10 2.155E-10 2.062E-10 SSW 2.162E-10 2.061 E-10 1.968E-10 1.880E-10 1.799E-10 SW 3.119E-10 2.974E-10 2.839E-10 2.713E-10 2.596E-10 4.093E-10 3.902E-10 3.725E-10 3.560E-10 2.919E-10 WSW W 4.945E-10 4.715E-10 4.501E-10 4.302E-10 3.087E-10 WNW 5.759E-10 5.491 E-10 5.242E-10 5.010E-10 3.728E-10 4.905E-10 4.677E-10 4.464E-10 4.266E-10 4.082E-10 NW NNW 4.895E-10 4.633E-10 4.423E-10 4.227E-10 3.676E-10
ODCM Page: 90 Rev.: 21 Table A-4 (Cont.)
At heric Position (DIQ)<<<< a Function of Distance (pn')
4.4 4.5 4.6 SECTOR 4.2 4.3 (MILES) (MILES)
(MILES) (MILES) (MILES) 4.260E-10 4.097E-10 4.823E-10 4.624E-10 4.437E-10 N 3.800E-10 3.654E-10 4.302E-10 4.124E-10 3.957E-10 NNE 3.342E-10 3.214E-10 3.627E-10 3.480E-10 NE 3.784E-10 4.198E-10 4.031 E-10 3.877E-10 ENE 4.564E-10 4.375E-10 4.234E-10 4.066E-10 3.910E-10 4.603E-10 4.413E-10 E 3.044E-10 2.927E-10 3.303E-10 3.170E-10 ESE 3.446E-10 2.484E-10 2.803E-10 2.690E-10 2.583E-10 SE 2.924E-10 1.944E-10 2.195E-10 2.106E-10 2.022E-10 SSE 2.289E-10 1.744E-10 1.677E-10 1.975E-10 1.893E-10 1.817E-10 S 1.522E-10 1.463E-10 1.723E-10 1.652E-10 1.585E-10 SSW 2.196E-10 2.112E-10 2.486E-10 2.383E-10 2.287E-10 SW 2.375E-10 2.572E-10 2.469E-10 2.796E-10 2.680E-10 wsw 2.611 E-10 2.511 E-10 2.956E-10 2.834E-10 2.719E-10 w 3.153E-10 3.032E-10 3.422E-10 3.284E-10 WNW 3.570E-10 3.453E-10 3.320E-10 3.909E-10 3.747E-10 3.596E-10 NW 2.991 E-10 3.239E-10 3.110E-10 NNW 3.521 E-10 3.375E-10 4.9 5.0 SECTOR 4.7 4.8 (MILES) (MILES) (MILES)
(MILES) 3.795E-10 3.656E-10 3.525E-10 N 3.941 E-10 3.384E-10 3.261 E-10 3.144E-10 NNE 3.515E-10 2.977E-10 2.868E-10 2.765E-10 NE 3.092E-10 3.591 E-10 3.460E-10 3.336E-10 ENE 3.729E-10 3.622E-10 3.489E-10 3.364E-10 E 3.762E-10 2.711 E-10 2.612E-10 2.519E-10 ESE 2.816E-10 2.300E-10 2.216E-10 2.137E-10 SE 2.389E-10 1.801E-10 1.735E-10 1.673E-10 SSE 1.871 E-10 1.497E-10 1.443E-10 1.614E-10 1.554E-10 S 1.259E-10 1.408E-10 1.355E-10 1.306E-10 SSW 1.817E-10 2.031 E-10 1.956E-10 1.884E-10 SW 2.199E-10 2.119E-10 2.043E-10 WSW 2.285E-10 2.241 E-10 2.160E-10 2.415E-10 2.326E-10 W 2.609E-10 2.809E-10 2.706E-10 WNW 2.917E-10 2.963E-10 2.857E-10 3.194E-10 3.075E-10 NW 2.573E-10 2.877E-10 2.770E-10 2.669E-10 NNW
ODCM Page: 91 Rev.: 21 APPENDIX B LOWER LIMIT OF DETECTION
ODCM Page: 92 Rev.: 21 The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with a 95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an *a posteriori" (after the fact) limit for a particular measurement.
For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha liquid scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity:
( v/2 Us tbj t
Where:
LLD = the "a priori" tower limit of detection, as defined above; C = the conversion factor of transformations per unit time per yCi or pCi; E = the detector efficiency; rfo = the background count rate in units of transformations per unit time; tb the counting time of background; ts = the counting time of the sample; V - the sample size, in units of mass or volume; yc = the fractional radiochemical sample collection or concentration yield (when applicable);
At = for plant effluents, the elapsed time between the midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and time of counting; X = the radioactive decay constant for the radionudide in question.
For the purpose of routine analyses, count times for both the sampled) and background(s) are equal.
This satisfies the given ODCM Appendix C control for lower limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 Sb, where Sb is the standard deviation of the background count rate or the count rate of a blank sample, as appropriate.
For gamma ray spectroscopy analyses:
LD exp
( 0.693-^2"At 1 (B-2)
(c)(E)(t)(v)(Yc)(Yy)
Where:
LLD = the lower limit of detection, in uCi or pCi per unit mass or volume; C = the conversion factor of transformations per unit time per \iC\ or pCi; E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; ti/2 - the half-life ofthe radionudide in question; V = the sample size, In units of mass or volume;
ODCM Page: 93 Rev.: 21 yc = the fractional radiochemicai, sample collection, or concentration yield (when applicable);
y>, = the yield of the gamma ray in question; At = for plant effluents the elapsed time between midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and the time of counting; Lei = the detection limit 2k(iL (i+_Lv(3l.B2)-i-^
2n, (B-3)
Where:
Bi = the number of counts in V background channels below the peak due to Compton scattering, etc., determined at the same time a photopeak Is measured; B2 = the number of counts in the V background channels above the peak; k = an abscissa of the normal distribution corresponding to confidence level,
= 1.645 at a confidence level of 95%;
I = the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc., determined by a separate measurement with no sample; N - the number of channels in the photopeak of interest; n = the number of background channels on each side of the photopeak of interest; ot = the standard deviation of I.
Typical values of E. V, Y, and At shall be used in the calculation.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g.,
potassium-40 in milk samples).
Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1.4.11.2.1.2-1, and 4.12.1-1 of the ODCM Appendix C controls for the Perry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nudWes, or other uncontrollable circumstances may render these LJLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
ODCM Page: 94 Rev.: 21 APPENDIX C CONTROLS
ODCM Page: 95 Rev.: 21 INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 97 Table 1.1, Surveillance Frequency Notation 101 Table 1.2, MODES 102 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY. 104 3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumentation 106 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation 107 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 109 Radioactive Gaseous Effluent Monitoring Instrumentation 111 Table 3.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation 112 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitoring instrumentation Surveillance Requirements 115 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration 118 Table 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program 119 Dose 122 Liquid Radwaste Treatment System 123 3/4.11.2 GASEOUS EFFLUENTS Dose Rate 124 Table 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and Analysis Program 125 Dose-Noble Gases 128 Dose - lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form 129 Gaseous Radwaste (Off-Gas) Treatment 130 Ventilation Exhaust Treatment Systems 131 3/4.11.4 TOTAL DOSE 132 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 133 Table 3.12.1-1 Radiological Environmental Monitoring Program 135 Table 3.12.1 -2 Reporting Levels for Radioactivity Concentrations In Environmental Samples 140 Table 4.12.1-1 Maximum Values for the Lower Limits of Detection (LLD) In Environmental Samples 141 PERRY - UNIT i
ODCM Page: 96 Rev.: 21 CONTROLS ANH RURVFILLAMrF REQUIREMENTS SECTION PAGE 3/4.12.2 LAND USE CENSUS 144 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 145 BASES _<<__-__- __
3/40 APPLICABILITY 147 3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumentation 155 Radioactive Gaseous Effluent Monitoring Instrumentation 155 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration '
Dose Liquid Radwaste Treatment System 3/4.11.2 GASEOUS EFFLUENTS Dose Rate Dose - Noble Gases 158 Dose - lodine-131, lodine-133, Tritium and Radionuclides in Paniculate Form 159 Gaseous Radwaste Treatment (Offgas) System and Ventilation Exhaust Treatment Systems 16° 3/4.11.4 TOTAL DOSE 160 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 161 3/4.12.2 LAND USE CENSUS 161 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 161 ADMINISTRATIVE CONTROLS __ _
6.9 REPORTING REQUIREMENTS 6.9.1.6 Annual Radiological Environmental Operating Report 163 6.9.1.7 Annual Radioactive Effluent Release Report 164 6.9.2 SPECIAL REPORTS 165 6.10 RECORD RETENTION. 165 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 166 PERRY - UNIT 1 ii
ODCM Page: 97 Rev.: 21 SECTION 1.0 DEFINITIONS
ODCM Page: 98 Rev.: 21 ACTIONS be taken under designated ACTIONS shall be conditions.
CALIBRATION channel steps so that the entire channel is calibrated.
r.HAKllMEL CHECK parameter.
fflANNEL FUNCTIONAL TEST ACHANNELRMAL^sh^
dose to the sensor as P"*aHafe"5* ^<< CWNNEL FUNCTONAL TEST may be performed by BE EQUIVALENT 1-131 PERRY - UNIT 1 1"1
ODCM Page: 99 Rev.: 21 DEFINITIONS FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE TREATMENT (QFF-GAS1 SYSTEM The GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gasses from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is any process or control equipment used to reduce the amount or concentration of liquid radioactive materials prior to their discharge to UNRESTRICTED AREAS It involves all the installed and available liquid radwaste management system equipment, as well as their controls, power instrumentation, and services that make the system functional.
MEMBER OF THE PUBLIC OCCUPATIONAL DOSE0 "^^ "*lndMdUal eXC8pt *hifl **lndividuaJ>> receiving an MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.2 with fuel in the reactor vessel.
OCCUPATIONAL DOSE 2the ?Jf^^ ? ?.meanS ** d08e *"**""*by an lndividual rn ** t"11'
employment in which individual s assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuate administered radioactive material and released under § 35.75, from voluntary participation In medical research programs, or as a member of the public PERRY - UNIT I
ODCM Page: 100 Rev.: 21 DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM)
The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsfte doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain the Radioactive Effluent Controls Program required by Technical Specification 5.5.4, the Radiological Environmental Monitoring Programs and descriptions of the information that should be included in the Annual Radioactive Effluent Release Report required by Technical Specifications 5.6.2 and 5.6.3.
OPERABLE - OPERABILITY A system, subsystem, division, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its specified safety function(s) are also capable of performing their related support function(s).
PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3758 MWT.
REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73.
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
PERRY - UNIT 1 1-3
ODCM Page: 101 Rev.: 21 DEFINITIONS , _ _ _ =_ =_
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEMS A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radlolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system Is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmosphenc cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components provided the ESF system is not utilized to treat normal releases.
VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
PERRY UNIT 1
ODCM Page: 102 Rev.: 21 TABLE 1.1 NOTATION FEEQUENSZ s At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
w At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
A At least once per 366 days.
R At least once per 24 months.
s/u Prior to each reactor startup, p Completed prior to each release.
4H Every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when required.
NA Not applicable.
PERRY - UNIT 1 1 5
ODCM Page: 103 Rev.: 21 TABLE 1.2 MODE?
REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE 1 POWER OPERATION Run MA 2 STARTUP Refuel (a) or Startup/Hot NA Standby HOT SHUTDOWN (a) Shutdown >200°F COLD SHUTDOWN (a) Shutdown REFUELING (b) Shutdown or Refuel NA (a) AM reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensfoned.
PERRY UNIT I 1-6
ODCM Page: 104 Rev.: 21 SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS
ODCM Page: 105 Rev.: 21 3/4.0 APPLICABILITY CONTROLS 3.0.1 Controls shall be met during the MODES or other conditions specified in the Applicability except as provided in Control 3.0.2.
3.0.2 Upon discovery of a failure to meet a Control, the requirements of the Actions shall be met except as provided in Control 3.0.5. If the Control is met or is no longer applicable prior to expiration of the specified time interval^), completion of the Action(s) is not required, unless otherwise stated.
3.0.3 When a Control is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the Control is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit as applicable, in:
~~a. MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;~~
~~b. MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and~~
~~c. MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .~~
Exceptions to this Control are stated in the individual Controls.
Where corrective measures are completed that permit operation in accordance with the Control or ACTIONS, completion of the actions required by Control 3.0.3 is not required.
Control 3.0.3 is only applicable in MODES 1,2, and 3.
3.0.4 When a Control is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
~~a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;~~
b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Control are stated in the individual Controls, or
~~c. When an allowance is stated in the individual value, parameter, or other Control.~~
This Control shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS, or that are part of a shutdown of the unit.
UNIT 1 3/4 0-i
ODCM Page: 106 Rev.: 21 3/4.0 APPLICABILITY (Continued) 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABIUTY or the OPERABIUTY of other equipment. This is an exception to Control 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
fiipVRI 1 AKICF RFQUIREMENT <SR) __ _ _
4.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual Controls, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the surveillance or between performances of the Surveillance, shal be failure to meet the Control. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Control except as provided in SR 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 The specified frequency for each SR is met if the SurveiHance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met If a completion time for an action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance after the initial performance.
Exceptions to this SR are stated in the individual SR's.
4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Control not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.
If the Surveillance is not performed within the delay period, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered.
4 0.4 Entry into a MODE or other specified condition in the Applicability of a Control shall only be made when the Control's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When a control is not met due to Surveillances not having been met, entry into a MODE or other specified Condition in the ApplicabiWy shall only be made in accordance with Control 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
PERRY - UNIT 1 3/4 0-2
ODCM Page: 107 Rev.: 21 3/4.3 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.9 In accordance with Perry Nuclear Power Plant Unit 1TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
~~b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1.~~
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperabilrty was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report
~~c. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.
FERRY - UNIT 1 3/4 1-1
Rev.: 21 Page: 108 ODCM TABLE 3.3.7.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE ACTION INSTRUMENT
~~1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE~~
~~a. Liquid Radwaste Discharge Radiation Monitor - 110 ESW Discharge~~
~~2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE~~
~~a. Emergency Service Water Loop A Radiation Monitor 111~~
~~b. Emergency Service Water Loop B Radiation Monitor 111 c Service Water Radiation Monitor (ADHR) 111~~
~~3. FLOW RATE MEASUREMENT DEVICES~~
~~a. Radwaste High-Flow Discharge Header Flow 112~~
~~b. Service Water Discharge Header Flow Monitor 113~~
~~c. Unit 1 Emergency Service Water Header Flow Monitor or 113 individual ESW HX Monitors~~
~~1) Emergency Service Water Flow Monitor, or~~
~~2) Individual RHR, ECC and DG HX Flow Monitors PERRY UNIT 1 3/4 1-2~~
ODCM Page: 109 Rev.: 21 TABLE 3.3.7.9-1 (Continued)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
~~a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and~~
b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channeb OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10"7 uCMnl.
ACTION 112 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the discharge valve position is verified to be consistent with the flow rate provisions of the release permit at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Prior to initiating another release, at least two technically qualified members of the Facility Staff shall independently verify the discharge line valve lineup and that the discharge valve position corresponds to the desired flow rate. Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place as well as other curves generated using pump performance may be used to estimate flow.
FERRY - UNIT 1 3/4 1-3
ODCM Rev.: 21 Page: 110 TABLE 4.3.7.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FLOW SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CHECK CALIBRATION TEST
~~1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE~~
~~a. Liquid Radwaste Discharge Radiation N.A. R(3)~~
~~Monitor - ESW Discharge~~
~~2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE~~
~~a. Emergency Service Water Loop A Radiation Monitor D N.A. M R(3) Q(2)~~
~~b. Emergency Service Water Loop B Radiation Monitor D NA M R(3) Q(2)~~
~~c. Service Water Radiation Monitor (ADHR)(6) D NA M R(3) Q(2)~~
~~3. FLOW RATE MEASUREMENT DEVICES~~
~~a. Radwaste High-Flow Discharge Header Flow D(4) NA NA R Q~~
~~b. Service Water Discharge Header Flow D(4) N.A. NA R Q~~
~~c. Unit 1 Emergency Service Water Header Flow~~
~~1) Emergency Service Water Flow, or D(4) NA NA R Q~~
~~2) Combination of Individual RHR, ECC & D(4) 4H(5) NA NA NA DG HX Flows~~
~~3) Individual RHR, ECC, & DG HX Flows NA NA NA PERRY - UNIT 1 3/4 1-4~~
ODCM Page: 111 Rev.: 21 TABLE 4.3.7.9-1 (Continued)
RADIOACTIVE LiQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm/trip setpoint~~
~~2. Instrument indicates a downscale failure.~~
~~3. Instrument controls not set in operate mode except in high voltage position.~~
~~(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:~~
~~1. Instrument indicates measured levels above the alarm setpoint~~
~~2. Instrument indicates a downscale failure.~~
~~3. Instrument controls not set in operate mode, except in high voltage position.~~
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been rotated to the initial calibration shad be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow. A CHANNEL CHECK shall be made initially and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days when continuous, periodic or batch releases occurs.
Pump performance curves may be used to verify the indication of flow from flow instrumentation.
(5) FLOW CHECK shall consist of verifying indication of flow by summing the individual RHR, ECC and DG heat exchanger flows. A FLOW CHECK shall be made initially, prior to securing ESW pumps, at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during a Uquid Radwaste discharge, and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during operation of ESW pumps.
(6) Surveillance requirements are in effect only when the system is in service.
PERRY - UNIT I 3/4 1-5
ODCM Rev.: 21 Page: 113 TABLE 3.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION INSTRUMENT
~~1. OFF-GAS VENT RADIATION MONITOR~~
~~a. Noble Gas Activity Monitor 121,124 122~~
~~b. Iodine Sampler <1>~~
~~c. Participate Sampler(1) 122~~
~~d. Effluent System Flow Rate Monitor 123~~
~~e. Sampler Flow Rate Monitor (Victoreen Flow Monitor) 1 123~~
~~2. UNIT 1 VENT RADIATION MONITOR 1,2,3 121,124,125~~
~~a. Noble Gas Activity Monitor t 4,5 121,124~~
~~b. Iodine Sampler(1) 122~~
~~122~~
~~c. Particulate Sampler(1)~~
~~d. Effluent System Flow Rate Monitor 123~~
~~e. Sampter Flow Rate Monitor {Victoreen Flow Monitor) 1 123 PERRY - ONIT 1 3/4 1-7~~
ODCM Page: 112 Rev.: 21 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS ___ __
3.3.7.10 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm/trip setpoints of applicable channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 3.3.7.10-1 ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperabiKty was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.
c The provisions of Control 3.0.3 are not applicable.
IP\/PII I AWP.P Rpni IIRFMFNTS 4.3.7.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown In Table 4.3.7.10-1.
PERRY UNIT I 3/4 1-6
ODCM Rev.: 21 Page: 114 TABLE 3.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY
~~3. UNIT 2 VENT RADIATION MONITOR~~
~~a. Noble Gas Activity Monitor 121,124~~
~~b. Iodine Sampler(1) 122~~
~~c. Paniculate Sampler <1> 122~~
~~d. Effluent System Flow Rate Monitor 123~~
~~e. Sampler Flow Rate Monitor (Victoreen Ftow Monitor) 1 123 TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR~~
~~a. Noble Gas Activity Monitor 121,124~~
~~b. Iodine Sampler(1) 122~~
~~c. Particulate Sampler <1> 122~~
~~d. Effluent System Flow Rate Monitor 123~~
~~e. Sampler Flow Rate Monitor (Victoreen Flow Monitor) 1 123 PERRY UNIT 1 3/4 1-8~~
ODCM Page: 115 Rev.: 21 TABLE 3.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION (1) This encompasses the isokinetic and Victoreen photohellcs At all times ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for principal gamma emitters as required by Table 4.11.2.1.2-1.
ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with auxiliary sampling equipment as required by Table 4.11.2.1.2-1. If the inoperability is due to failure of the AMC skid, the victoreen skid alone can be used as the auxiliary sampling equipment for a maximum of 30 consecutive days. Loss of the isokinetic flow monitor constitutes inoperability of particulate and iodine channels (b, c).
ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent release via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . This action applies to both the effluent system flow and Victoreen sample flow (d, e).
ACTION 124 - With the 1H13-P680 panel annunciator for noble gas channels locked in due to a downscale condition on the radiation monitoring panel, the affected noble gas monitor channels shall be verified in the Control Room at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to ensure that no unmonitored high or alert level alarms are present ACTION 125 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement except as a result of a non-conservative setpoint or within the criteria specified in Action 126, immediately suspend operation of the Containment Vessel and Drywell Purge (M14) system. Prior to resuming M14 System operation, ensure compliance with Control 3.11.2.1 requirements. If Control 3.11.2.1 compliance is met, operation of the M14 System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for principal gamma emitters, as required by Table 4.11.2.1.2-1.
ACTION 126 - For periods of planned maintenance or performance of surveillance requirements in support of the requirements listed in Table 4.3.7.10-1, which wilt reduce the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, compliance with Control 3.11.2.1 may be verified prior to reducing the number of OPERABLE channels below the requirement. If Control 3.11.2.1 compliance is met, operation of the M14 System need not be suspended for the channel provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for principal gamma emitters, as required by Table 4.11.2.1.2-1.
PERRY UNIT 1 3/4 1-9
ODCM Rev.: 21 Page: 116 TABLE 4.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
~~1. OFFGAS VENT RADIATION MONITOR M RW Qd)~~
~~a. Noble Gas Activity Monitor D~~
~~b. Iodine Sampler W^ NA NA NA~~
~~c. Participate Sampler Vf NA. NA NA.~~
~~d. Effluent System Flow Rate Monitor D NA. R Q~~
~~e. Sampler Flow Rate Monitor D NA R Q~~
~~2. UNIT 1 VENT RADIATION MONITOR R Qd)~~
~~a. Noble Gas Activity Monitor D M~~
~~b. Iodine Sampler W> NA. NA NA~~
~~c. Paniculate Sampler W>> NA. NA. NA~~
~~d. Effluent System Flow Rate Monitor D NA. R Q~~
~~e. Sampler Flow Rate Monitor D NA R Q PERRY - UNIT 1 3/4 1-10~~
ODCM Rev.: 21 Pago:
TABLE 4.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
~~3. UNIT 2 VENT RADIATION MONITOR D M R Qd)~~
~~a. Noble Gas Activity Monitor~~
~~b. Iodine Sampler WP) N.A. N.A. NA~~
~~c. Participate Sampler WO) N.A. NA NA~~
~~d. Effluent System Flow Rate Monitor D N.A. R Q~~
~~e. Sampler Flow Rate Monitor D N.A. R Q~~
~~4. TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR RW Qd)~~
~~a. Noble Gas Activity Monitor D M~~
~~b. Iodine Sampler NA NA NA~~
~~c. Paniculate Sampler wo NA NA N.A.~~
~~d. Effluent System Flow Rate Monitor D NA R Q~~
~~e. Sampler Flow Rate Monitor D NA R Q PERRY - UNTT I 3/4 1-11~~
ODCM Page: 118 Rev.: 21 TABLE 4.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVE<l 1ANCE REQUIREMENTS TABLE NOTATION At all times (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm setpoint~~
~~2. Instrument indicates a downscale failure.~~
~~3. Instrument controls not set in operate mode.~~
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST These standards shall permit calibrating the system over its intended energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(3) The iodine cartridges and particulate filters will be changed at least once per 7 days. Performance of this CHANNEL CHECK does not render the system inoperable, and the applicable ACTION statements need not be entered.
PERRY - UNIT 1 3/4 1-12
ODCM Page: 119 Rev.: 21 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with Perry Nuclear Power Plant TS 5.5.4.b and c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, for radlonuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the concentration shall be limited to 2 x 1O4 ud/rnl total activity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11.1.1.1-1. The results of pre-release analyses shaH be used with the calculationaJ methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 3.11.1.1.
4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
4.11.1.1.3 Continuous releases of radioactive liquid effluents shall be sampled and analyzed In accordance with Table 4.11.1.1.1-1. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
FERRY UNIT I 3/4 2-1
ODCM Page: 120 Rev.: 21 TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPUNG ANn ANALYSIS PROGRAM Minimum Type of Lower Limit Sampling Analysis Activity of Detection Liquid Release Type Frequency Frequency Analysis (LLD)
Batch Waste P P Principal Gamma 5x10"7 A.
Release Tanks' Each batch Each batch Emitters
1-131 1x10*
p M Dissolved and 1x10*
OneBatch/M Entrained Gases (Gamma emitters)
P M H-3 1x10*
Each Batch Composite" Gross Alpha 1x1 Or7 P Q Sr-89, Sr-90 5x10*
Each Batch Composite" Fe-55 1x10*
B. Continuous D W Principal Gamma Releases* RHR Grab Composite"'* Emitters'1 Heat Sample*"-
Exchanger ESWOuUet, 1-131 1x10*
M35 Drains, or Service Waters M* M Dissolved and 1x10*
Grab Sample Entrained Gases (Gamma emitters)
D M H-3 1x10*
Grab Sample8' Composite" Gross Alpha 1x10-7 D Q Sr-89, Sr-90 5x10*
Grab Sample9- Composite" Fe-55 1x10*
PERRY - UNIT 1 3/4 2-2
ODCM Page: 121 Rev.: 21 TABLE 4.11.1-1.1-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
For a particular measurement system (which may include radtochemical separation):
4.66Sb LLD =
- XAt)
Where:
LLD is the "a priori" lower limit of detection as defined above (as yCi per unit mass or volume).
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 x 109 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
X is the radioactive decay constant for the particular radionuclide (sec-1)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V: Y and At should be used in the calculation.
PERRY - UNIT i 3/4 2-3
ODCM Page: 122 Rev.: 21 TABLE 4.11.1.1.1-1 (Continued)
RAniQAHTTVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TA.BL.E NOTATION (Continued) b A composite sample is one in which the quantity of liquid sampled is proportional to the
' quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. A composite sample mayateo be obtained from liquid batches of similar origin that are not discharged as these liquid batches are expected to be representative of samples that could be discharged. Composite samples for batch liquids that were not released is performed to provide non-gamma emitting isotopic values to verify other batches are within limits prior to release when recent non-gamma emitting isotopic values for discharged liquids are not available.
c.
A batch release is the discharge of liquid wastes of a discrete volume. .
analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
d The principal gamma emitters for which the LLD specification applies exclusively are the flowing radionudkles: Mn-54, Fe-59, Co-58. Co*0, 2^65, McM>>, Cs-134 Cs-W and Ce-141 Ce-144 shall also be measured, but with an LLD of 5x10* This list does not mean that only these nudides are to be detected and reported. Other peaks which are '*surable and identifiable, together with the above nuclides, shal also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
e. A continuous release is the discharge of liquid wastes of a non-discrete volume <e.g. froma volume of a system that has an input flow during the continuous release. Samphng/Analysls of RHR Heat Exchanger is only applicable when there is ESW flow through the RHR Heat Exchanger.
f. Sampling and analysis is required of the RHR heat exchanger ESW outlet every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the samples indicate levels greater than LLD.
g Sampling is only required for M35 drains, when the M35 drains have been lined up to storm drains. If activity other than tritium or naturally occurring isotopes is detected in the M35 drains, then these drains shall be lined up to radwaste
~~h. Sampling/Analysis of Service Water is only applicable when there is Service Water flow through the ADHR Heat Exchanger.~~
PERRY ~ UNIT 1 3//4 2"4
ODCM Page: 123 Rev.: 21 RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.d and e, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited:
~~a. During the current quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and~~
~~b. During the current year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.~~
APPLICABILITY: At aH times.
ACTION:
a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the causes) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the corrective actions to be taken to ensure that future releases will be in compliance with the above limits.
~~b. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current quarter and the current year shall be determined in accordance with the methodology and parameters of the ODCM at least once per 31 days.
PERRY UNIT ! 3/4 2-5
ODCM Page: 124 Rev.: 21 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM 3.11.1.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5Af, the LIQUID TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the qgtom thai <<* "f***
reduce the release of radioactivity when the projected doses due to the liquid fuentfrom each reactor unit to UNRESTRICTED AREAS (see Figure 3.2-1) would exceed 0.06 mrem to the whole body or 02 mrem to any organ, in a 31-day period.
APPLICABILITY: At all times.
ACTION:
a With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation prepare and submit to the Commission, within 30 days pursuant to Control 6.9.2, a Special Report which includes the following information:
1 Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperabilKy, and
~~2. Adion(s) token to restore the inoperable equipment to OPERABLE status, and~~
~~3. Summary description of actlon(s) taken to prevent a recurrence,~~
~~b. The provisions of Control 3.0.3 are not applicable.~~
411 1 3 1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with methodology and parameters in the ODCM.
4.11.1.3.2 The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
PERRY - UNIT 1 3/4 2~6
ODCM Page: 125 Rev.: 21 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.C and g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
a For noble gases: Less than or equal to 500 mrem/yr to the whole body and less than or equal to 3000 mrem/yr to the skin, and
~~b. For all iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.~~
APPLICABILITY: At all times.
ACTION:
With the dose rate(s} exceeding the above limits, immediately decrease the release rate(s) to within the above limit(8).
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM.
4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium and to radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.
PERRY - UNIT i 3/4 2-7
ODCM Rev.: 21 Page: 126 TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD)<*
GASEOUS RELEASE PATH FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCt/mL)
A. Containment Vessel and Each PURGE Each PURGE Principal Gamma 1x10" Drywell Purge (M14) and VENT and VENT Emitters <<
System, and Combustible Grab Sample Gas Control (M51) System M M H-3 1x10" Grab Sample B. Offgas Vent, Unit 1 Vent, M<"> Principal Gamma 1x10" Unit 2 Vent, and Turbine Grab Sample Emitters **
Bldg/Heater Bay Vent H-3 1x10 All Release Paths as listed Continuous 1-131 -12 1x10 in B above Charcoal Sample -10 1-133 1x10 Continuous(d) Principal Gamma ,-11 1x10 Particulate Sample Emitters^
Continuous <d) M Gross Alpha -11 1x10 Composite Particulate Filter Continuous<d} Q Sr-89, Sr-90 -11 1x10 Composite Particulate Filter Continuous<d) Noble Gas Noble Gases 1x10"° Monitor Gross Beta or Gamma (Xe-133 equivalent)
PERRY UNIT 1 3/4 2-8
ODCM Page: 127 Rev.: 21 TABLE 4.11.2.1.2-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
a. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "rear signal.
It should be recognized that the LLD is defined as an "a priori" (before the tact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
For a particular measurement system (which may include radiochemical separation):
x TT\_
4.66Sh *"
(e) (v) (2.22X1GP] (y) exp(- >.At)
Where:
LLD is the "a priori" lower limit of detection as defined above (as nCi per unit mass or volume).
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 x 108 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) a is the radioactive decay constant for the particular radionuclide (sec-1)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V. Y and At should be used in the calculation.
PERRY - UNIT
~~3/4 2-9~~
ODCM Page: 128 Rev.: 21 TABLE 4.11.2.1.2-1 (Continued)
RADIOACTIVE GASFOUS WASTE SAMPLING AND ANAIYSIS PROGRAM tari E NOTATION (Continued) b Analyses shall also be performed following startup, shutdown, ora THERMAL POWER change
' exceedina 15 percent of the RATED THERMAL POWER within a one hour period. This Z^SKot app* if (1) anafysis shows that the DOSE ^S^^^S^
in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
c Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler. Sampling and analyses shall also be performed at least daily (* 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) for at least 7 days following each shutdown startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply If:
(1) Analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) The noble gas monitor shows that effluent activity has not increased more than a factorof 3.
If the noble gas monitor is not operable, then a grab sample may be used to demonstrate that activity has not increased by a factor of 3.
~~d. The ratio of the sample flow rate to the sampled ,....,~~
covered by each dose or dose rate calculation made In accordance with Control 3 ,
and 3.11.2.3.
e The principal gamma emitters for which the LLD specification applies exclusively are the following radfonuclides: Kr-87,1MB. Xe-133, Xe-133m, Xe-135, and Xe-138 f* gaseous emissions and Mn-54, Fe-59.Cc-58. Co-60,Zrv65, Mo-99,1-131, Cs-134,Cs-137,Ce-141 andICe-144for particulate emissions. This 1st does not mean that only these nuclides are to be detected and FeVorteTother peaks which are measurable and identifiable, together wKh the above nucHdes shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuarrt to Control 6 9 1 7 in the formatOutlined in Regulatory Guide 1.21. Appendix B, Revision 1, June 1974.
f Sampling and analysis of gaseous release points shall be performed initially ^f?9^^
setpoint is exceeded or whenever two or more of the alert setpointe are exceeded Ifihelh*h sejoint or two or more of the alert setpoints continue to be exceeded, verify at^least once per Hours via the radiation monitors that plant releases are below the Control 3.11.2.1 dose rate limits and sampling and analysis shall be performed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
PERRY UNIT 1 3/4 2"10
ODCM Page: 129 Rev.: 21 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.e and h, the air dose due to noble gases released in gaseous effluents, from each reactor unit from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
~~a. During the current quarter. Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation; and~~
~~b. During the current year Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation, APPLICABILITY: At all times.~~
~~ACTION:~~
a. With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to ensure that future releases win be in compliance with Control 3.11.2.2.
~~b. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PERRY - UNIT 1 3/4 2-1!
ODCM Page: 130 Rev.: 21 RADIOACTIVE EFFLUENTS DOSE - IOD1NE-131. IODINE-133. TRITIUM AND RADIONUCUDES IN PARTICULATE FORM QQNTRQ1S . __ :
3.11.2.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.e and i, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionudides in partlculate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
~~a. During the current quarter Less than or equal to 7.5 mrem to any organ; and~~
~~b. During the current year: Less than or equal to 15 mrem to any organ.~~
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of iodine-131, bdine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.3.
~~b. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCF RFOUIREMENTS __
4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PERRY - UNIT 1 3/4 2-12
ODCM Page: 131 Rev.: 21 RADIOACTIVE EFFLUENTS GASEOUS RAPWASTE (OFF-GAS^ TREATMENT 3.11.2.4 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM shall be in operation*. The OcWW*r Charcoal bypass mode shall not be used unless the off-gas posMreatment radiation monitor is OPERABLE.
APPLICABILITY: Whenever the main condenser air ejector evacuation system is in operation.
ACTION:
a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:
1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability.
~~2. Adion(s) taken to restore the inoperable equipment to OPERABLE status, and~~
~~3. Summary description of action(s) taken to prevent a recurrence.~~
~~b. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS . __ ____
4.11.2.4 The readings of relevant instrumentation shall be checked at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.
~~Flow directed through the adsorber beds.~~
PERRY - UNI? : 3/4 2~13
ODCM Page: 132 Rev.: 21 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEMS 311 2 5 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when thejfgf^J"? ** to gaseous effluent releases from each reactor unit to areas at and beyond the S TE^BOUNDARY (see Figure 3.2-1) in a 31 day period would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
ACTION:
a With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:
1 Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability,
~~2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and~~
~~3. Summary description of action(s) taken to prevent a recurrence,~~
~~b. The provisions of Control 3.0.3 are not applicable.~~
RURVEILLANCF RFOHIR^MENTS _ _ _ =
4112 51 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS shall be demonstrated OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.3.
PERRY - UNIT 1 3/4 2"14
ODCM Page: 133 Rev.: 21 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Perry Nuclear Power Plant Unit 1TS 5.5.4.J, the current year dose or dose commitment to any MEMBER of THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
APPLICABILITY: At all times.
ACTION:
~~a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a.. 3.11.2.2b.,~~
3.11.2.3a, or 3.11.2.3bM calculations shall be made including direct radiation contributions from the reactor units, from the ISFSI and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded.
1. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
2. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the current year that includes the releases) covered by this report It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
3. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190.
~~Submrttai of the report is considered a timely request, and a variance is granted until staff action on the request is complete.~~
~~b. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2,4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.
4.11.4.2 If the cumulative dose contributions exceed the limits defined in 3.11.4, ACTION a, cumulative dose contributions from direct radiation from unit operation including from the ISFSI and outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.
PERRY UNIT i 3/4 2-15
ODCM Page; 134 Rev.: 21 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM nnKTTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.
APPLICABILITY: At all times.
a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Environmental and Effluent Release Report per Control 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over the current quarter, prepare and submit to the Commission within 30 days pursuant to Control 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBUC is less than the current year limits of Control 3.11.1.2,3.11.2.2 and 3.11.2.3. When more than one of the radtonuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if concentration (1) + concentration (2) +... *1.0 reporting level (1) reporting level (2)
When radtonuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC is equal to or greater than the current year limits of Control 3.11.1.2,3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual Radiological Environmental Operating Report required by Control 6.9.1.6.
~~The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.~~
PERRY - UNIT 1 3/4 3-1
ODCM Page: 135 Rev.: 21 RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS
c. With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Control 6.9.1.7, submit in the next Annual Radiological Effluent Release Report documentation for a change in the ODCM including a revised figure^) and table for the ODCM reflecting the new kxation(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new locations) for obtaining samples.
~~d. The provisions of Control 3.0.3 are not applicable.~~
RURVFH I ANCE REQUIREMENTS =__
4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.
FERRY UNIT I 3/4 3-2
ODCM Rev.: 21 Page: 136 TABLE 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*
Number of Samples Exposure Pathway and <1> Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
1. Direction Twenty-nine routine monitoring stations Quarterly Gamma dose quarterly OcVoWr Radiation*2* either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as folows:
An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NNE, NNW, NW, W, WNW), in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NE, NNE, NNW, NW, W, WNW), in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations PERRY UNIT 1 3/4 3-3
Rev.: 21 Page: 137 ODCM TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Sampling and Type and Frequency Exposure Pathway and<1>
Collection Freauencv of Analysis and/or Sample Sample Locations
~~2. Airborne Continuous sampler operation Radioiodine Canister Radioiodine and Samples from five locations:~~
with sample collection weekly, 1-131 analysis weekly Participate Three samples from close to the three SITE or more frequently if required by BOUNDARY locations, in different sectors, dust loading Particulate Sampler of the highest calculated annual average Gross beta radioactivity analysis ground-level D/Q; following filter replacement &;
and gamma isotopic analysis <4>
One sample from the vicinity of a of composite (by location) community having the highest calculated quarterly annual average ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction
~~3. Waterborne Composite sample over a Gamma isotopic analysis(4)~~
~~a. Surface Two samples 1-month period <*> monthly. Composite for tritium analysis quarterly~~
~~V4 3-4 PERRY UNIT 1~~
Rev.: 21 Page: 138 ODCM TABLE 3 12 1-1 {Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Sampling and Type and Frequency Exposure Pathway and <1>
SamDle Locations Collection Frequency of Analysis and/or Sample
~~3. Waterbome (Continued)~~
~~One sample of each of one to three of the Composite sample over 2-week 1-131 analysis on each~~
b. Drinking nearest water supplies that could be period(5) when 1-131 analysts is composite when the dose affected by its discharge performed; monthly composite calculated from the consumption otherwise of the water is greater than One sample from a control location 1 mrem per year>>. Composite for gross beta and gamma isotopic analyses(4) monthly.
Composite for tritium analysis quarterly One sample from area with existing or Semi-annually Gamma isotopic analysis(4)
Sediment semi-annualy from potential recreational value shoreline
~~4. Ingestion Samples from milking animals in three Semi-monthly when animals are Gamma Isotopic analysis w and~~
a. Milk on pasture; monthly at other 1-131 analysis semi-monthly, locations within 5 km distance having the highest dose potential. If there are none, times when animals are on pasture; then one sample from milking animals in monthly at other times each of between 5 to B km distant where doses are three areas calculated to be greater than 1 mrem per yr(6). One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.
PERRY UNIT 1 3/4 3-5
ODCM Rev.: 21 : 139 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and <1> Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
~~4. Ingestion (Continued)~~
b. Fish and One sample of each commercially and One sample in season or Gamma isotopic analysis{4) on Invertebrates recreationally important species (if seasonal) in semiannualry if they are not edible portions vicinity of plant discharge area seasonal One sample of same species in areas not influenced by plant discharge
c. Food Sample of three different kinds of broad leaf Monthly during growing season Gamma isotopic analysis << and Products vegetation grown nearest each of two different 1-131 analysis offeite locations of highest predicted annual average ground level D/Q if milk sampling is not performed One sample of each of the similar broad leaf Monthly during growing season Gamma isotopic analysis(4) and vegetation grown 15 to 30 km distant in the least 1-131 analysis prevalent wind direction if milk sampling is not performed PERRY - UNIT 1 3/4 3-6
ODCM Page: 140 Rev.: 21 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS Sample locations are given on the figure and the table in the ODCM.
(1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic samplng equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shad be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. It is recognized that, at times, Ft may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Control 6.9.1.7, submit in the next annual Radioactive Effluent Release Report documentation for a change in the ODCM, including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new tocation(s) for obtaining samples.
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) Is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. (The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)
(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(5) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
PERRY - UNIT 1 3/4 3-7
Rev.: 21 Page: 141 ODCM TABLE 3.12.1-2 REPORTING ILEVELS FOR RADIOACTIVrTY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Fish Milk Broadleaf Vegetation Water Airborne Paniculate (pCi/kg, wet) (pCi/L) (pCi/kg, wet)
Analysis <pCi/L) or Gases (pCi/ms)
NA NA NA NA H-3 2x10*"
N.A. 3x104 N.A. NA Mn-54 1x103 NA 1x10* N.A. NA Fe-59 4x10*
3x10* N.A. N.A Co-58 1x103 NA NA 1x10* N.A. N.A.
Co-60 3X102 NA 2x10* NA N.A Zn-65 3X102 N.A. NA N.A. NA Zr-Nb-95 4X102 0.9 NA 3 1x10*
1-131 2" 10 1x103 60 . 1X103 Cs-134 30 2X103 70 2X103 Cs-137 50 20 NA NA 3X102 HA Ba-La-140 2x102 For drinking water samples. This is a 40CFR141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.
blf no drinking water pathway exists, a value of 20 pCi/L may be used.
PERRY - UNIT 1 3/4 3-8
Rev.: 21 Kagib: 14Z ODCM TABLE 4 12.1-1 (a),(b),(c)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 1 ENVIRONMENTAL SAMPLES Airborne Particulate Broad Leaf or Gases Fish Milk Vegetation Sediment Analysis Water (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/kg,wet) (pCi/kg.wet)
(pCW) 4 1x10-2 NA NA N.A. NA Gross beta NA NA NA N.A. N.A.
H-3 2000*
15 N.A. 130 NA NA NA Mn-54 NA 260 NA NA NA Fe-59 30 NA 130 NA N.A. NA Co-58,60 15 NA 260 NA NA NA Zn-65 30 N.A. NA NA NA NA Zr-85 30 NA NA NA N.A. NA Nb-95 15 7X10-2 NA 1 60 NA 1-131 1-5X10"3 130 15 60 150 Cs-134 15 6x10-2 150 16 80 180 Cs-137 18 NA NA 60 NA NA Ba-140 60 NA N.A. 15 NA NA La-140 15
~~lf no drinking water pathway exists, a value of 3000 pCifl may be used.~~
~~lf no drinking water pathway exists, a value of 15 pCi/l may be used.~~
PERRY - UNIT 1 3/4 3-9
ODCM Page: 143 Rev.: 21 TABLE 4.12.1-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
TABLE NOTATION Acceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
bTable 4.12-1 indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'rear signal.
For a particular measurement system (which may include radiochemical separation):
4.66Sb LLD=
(e ) (v) f2.22x!CPj (y) exp(- X At)
Where:
LLD is the "a priori" lower limit of detection as defined above (as yCi per unit mass or volume).
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2,22 x 108 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionudide (sec-1)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V, Y and At should be used in the calculation.
PERRY UNIT 3/4 3-10
ODCM Page: 144 Rev.; 21 TABLE 4.12.1-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (UP)
TABLE NOTATION (continued)
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement Occasionally background fluctuations, unavoidable small sample size, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors should be identified and described in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
The value of sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
°Thjs list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.16.
PERRY - UNIT 1 3/4 3-11
ODCM Page: 145 Rev.: 21 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS QPNTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
APPLICABILITY: At all times.
ACTION:
a. With a land use census identifying a locations) which yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, identify the new locations)'
~~in the next Annual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7.~~
b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which milk and/or broad leaf vegetation samples are currently being obtained in accordance with Control 3.12.1, add the new locations) to the radiological environmental monitoring program within 30 days. If no milk and/or broad leaf vegetation samples are identified in the new sector with the highest D/Q value, then the next sector with the highest D/Q value will be considered and so on until a sampling location can be established. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitments), via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.* Identify the new locations) in the next annual Radioactive Effluent Release Report and also include in the report a revised figures) and tables) for the ODCM reflecting the new location(s).
~~c. The provisions of Control 3.0.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS -____-___
4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a doorto-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
"Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.
PERRY UNIT i 3/4 3-12
ODCM Page: 146 Rev.: 21 RADIOLOGICAI ENVIRONMENTAL MONITORING a/4 12.3 INTER! ABORATORY COMPARISON PROGRAM 312 3 Analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1. These materials are supplied as part of an Inter-teboratory Comparison Program.
APPLICABILITY: At all times.
ACTION:
a With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Environmental and Effluent Release Report pursuant to Control 6.9.1.6.
~~b. The provisions of Control 3.0.3 are not applicable.~~
Rl 1RVFII LANCF RFQUIREMENTS _ __= _==_
412 3 A summary of the results obtained as part of the above required Inter-Laboratory Comparison Program shall be included in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
PERRY - UNIT 1 3/4 3~13
ODCM Page: 147 Rev.: 21 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE: The BASES contained in succeeding pages summarize the reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.
ODCM Page: 148 Rev.: 21 3/4 CONTROLS AND SURVEIU ANCE REQUIREMENTS 3/4.0 APPLICABILITY Controls 3.0.1 through 3.0.5 establish the general requirements applicable to Appendix C Controls and apply at all times, unless otherwise stated.
Control 3 01 establishes the Applicability statement within each individual control as the requirement for when the Control is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Control).
Control 3.0.2 establishes that upon discovery of a failure to meet a Control, the associated ACTIONS shall be met. The Completion Time of each ACTION condition is applicable from the point in time that an ACTIONS condition is entered. The ACTIONS establish those remedial measures that must be taken within specified times when the requirements of a Control are not met This Control establishes that
~~a. Completion of the ACTIONS within the specified times constitutes compliance with a Control; and~~
~~b. Completion of the ACTIONS is not required when a Control is met within the specified time, unless otherwise specified.~~
There are two basic types of ACTION requirements. The first type of ACTIONS specifies a time limit in which the Control must be met This time limit is the time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of ACTION is not completed within the specified completion time, a shutdown may be required to place the unit in a MODE or condition in which the Control is not applicable. (Whether stated as an ACTION or not, correction of the entered condition is an action that may always be considered upon entering ACTIONS.) The second type of ACTION specifies the remedial measures that permit continued operation of the unit that is not further restricted by the completion time. In this case, compliance with the ACTIONS provides an acceptable level of safety for continued operation.
Completing the ACTIONS is not required when a Control is met or is no longer applicable, unless otherwise stated in the individual Control.
The nature of some ACTIONS of some conditions necessitates that, once the condition is entered, the ACTIONS must be completed even though the associated condition no longer exists. The Individual Control's ACTIONS specify where this is the case.
PERRY - UNIT 1 B 3/4 0-1
ODCM Page: 149 Rev.: 21 3/4.0 APPLICABILITY BASES (Continued!
The completion times of the ACTIONS are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience.
Alternatives that would not result in redundant equipment being inoperable should be used instead.
Doing so limits the time both subsystems/divisions of a safety function are inoperable and limits the time other conditions exist which result in Control 3.0.3 being entered. Individual Controls may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the completion times of ACTIONS are applicable when this time limit expires, if the equipment remains removed from service or bypassed.
When a change in MODE or other specified condition is required to comply with an ACTION, the unit may enter a MODE or other specified condition in which another Control becomes applicable. In this case, the completion times of the associated ACTIONS would apply from the point in time that the new Control becomes applicable and the ACTIONS conditions) are entered.
Control 3.0.3 establishes the actions that must be implemented when a Control is not met and:
~~a. An associated ACTION and completion time is not met and no other condition applies; or~~
b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of conditions are such that entering Control 3.0.3 is warranted; in such cases, the ACTIONS specifically state a condition corresponding to such combinations and also that Control 3.0.3 be entered immediately.
This Control delineates the time limits for placing the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the Control and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.
?2RRY - UNIT 1 3 3/4 0-2
ODCM Page: 150 Rev.: 21 3/4.0 APPLICABILITY Upon entering Control 3.0.3,1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Control applies.
A unit shutdown required in accordance with Control 3.0.3 may be terminated and Control 3.0.3 exited if any of the following occurs:
~~a. The Control is met~~
~~b. A condition exists for which the ACTIONS have now been performed.~~
c. ACTIONS exist that do not have expired completion times. These completion times are applicable from the point in time that the condition is initially entered and not from the time Control 3.0.3 is exited.
The time limits of Control 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown Is required, the time limit for reaching the next lower MODE applies. If a lower MODE of operation is reached In less time than allowed, however, the total allowable time to reach MODE 4, or other applicable MODE, is not reduced. For example, If MODE 2 is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.
In MODES 1 2, and 3, Control 3.0.3 provides actions for conditions not covered in other Controls. The requirements' of Control 3.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive condition required by Control 3.0.3. The requirements of Control 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1,2, or 3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.
Exceptions to Control 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with Control 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit.
These exceptions are addressed in the individual Controls.
PERRY -- UNIT 1 B 3/4 0-3
ODCM Page: 151 Rev.: 21 3/4.0 APPLICABILITY BASES /Continued^
Control 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when a Control is not met. It allows placing the Unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with Control 3.0.4.a, 3.0.4.b, or 3.O.4.C.
Per Control 3.0.4.8, compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the plant before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the ACTION requirements.
Per Control 3.0.4.b, changes in MODE may be made even if the ACTION requirements include a requirement to exit the Applicability, PROVIDED a risk assessment is performed (and is determined to be acceptable) which addresses the inoperable systems/components, and any appropriate risk management actions are put in place.
The provisions of this control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before Unit startup.
The provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE associated with transitioning from MODE 1 to MODE 2 or 3, MODE 2 to 3, and MODE 3 to 4.
Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, utilizing Control 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment.
However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected Control.
PERRY UNIT I B 3/4 0-4
ODCM Page: 152 Rev.: 21 3/4.0 APPLICABILITY Control 3.0.5 establishes the allowance for restoring equipment to servrce ^*!'*^'!*
when it has been removed from service or declared inoperable to comply with ACTIONS The sote purpose of this Control is to provide an exception to Control 3.0.2 (e.g., to not comply with the applicable ACTION(s)) to allow the performance of SRs to demonstrate:
a, The OPERABILITY of the equipment being returned to service; or
~~b. The OPERABILITY of other equipment.~~
The administrative controls ensure the time the equipment Is returned to f"1^0?**"** <<<. This requirements of the ACTIONS is limited to the time absolutely necessary to perform the allows SRs. This Control does not provide time to perform any other preventative or corrective maintenance.
rr 40.1 through 4.0.5 establish the general requirements applicable to all Controls and apply at all times, unless otherwise stated.
SR 4 01 establishes the requirement that SRs must be met during the MODES or other specified Sndlttons in the Applicability for which the requirements of the Control apply, unless otherwise specrfied in the individual SRs. This Control is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits Failure tomeet a SurveSance wrttiin the specrfied frequency, in accordance with SR 4.0.2, constitutes a fa,lure to meet a Control.
Systems and components are assumed to be OPERABLE when the associated SRs have been met Nothing in this Control, however, is to be construed as implying that systems or components are OPERABLE when:
~~a. The systems or components are known to be inoperable, although still meeting the SRs; or~~
~~b. The requirements of the Surveillances) are known to be not met between required Surveillance performances.~~
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which he requirements of the associated Control are not applicable, unless otherw.se specrfied The M <<MdSSI with a Special Operations Control are only applicable when the Special Operates Control is used as an allowable exception to the requirements of a Control.
Surveillances, including Surveillances invoked by ACTIONS donoUiaveto >>£*^££^
equipment because the ACTIONS define the remedial measures that apply. SurvaHances MWBDa met and performed in accordance with SR 4.0.2, prior to returning equipment to OPERABLE status.
PERRY UNIT 1 B 3/4 °~5
ODCM Page: 153 Rev.: 21 3/4.0 APPLICABILITY BASES (Continued)
Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 4.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
SR 4.0.2 establishes the requirements for meeting the specified frequency for Surveillances and any ACTIONS with a completion time that requires the periodic performance of the ACTION on a "once per..."
interval.
SR 4.0.2 permits a 25% extension of the interval specified in the frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 4.0.2 are those Surveillances for which the 25% extension of the interval specified in the frequency does not apply. These exceptions are stated in the individual Controls.
As stated in SR 4.0.2, the 25% extension also does not apply to the initial portion of a periodic completion time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the ACTION, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single completion time. One reason for not allowing the 25% extension to this completion time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.
The provisions of SR 4.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic completion time intervals beyond those specified.
PERRY - UNIT 1 B 3/4 0-6
ODCM Page: 154 Rev.: 21 3/4.0 APPLICABILITY RASFR {Continued!
SR 4.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified Bmits when a Surveillance has not been completed within the specified frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is less, applies from the point in time that it is discovered that the Surveilance has not been performed in accordance with SR 4.0.2, and not at the time that the specified frequency was not met. This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with ACTIONS or other remedial measures that might preclude completion of the Surveillance.
The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.
When a Surveillance with a frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, SR 4.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the Surveillance.
SR 4.0.3 also provides a time limit for completion of Surveillances that become applicable as a consequence of MODE changes imposed by ACTIONS.
Failure to comply with specified frequencies for Surveillance Requirements is expected to be an infrequent occurrence. Use of the delay period established by SR 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.
If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable then is considered outside the specified limits and the completion times of the ACTIONS for the applicable Control conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the completion times of the required ACTIONS for the applicable Control conditions begin immediately upon failure of the Surveillance.
Completion of the Surveillance within the delay period allowed by this Control, or within the completion time of the ACTIONS, restores compliance with SR 4.0.1.
SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability, with two exceptions as described in SR 4.0.4.
PERRY UNIT 1 B 3/4 0-7
ODCM Page: 155 Rev.: 21 3/4.0 APPLICABILITY BASES (Continued)
This Control ensures that system and component OPERABILJTY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment or variables outside specified limits. When equipment is inoperable, or variables are outside their specified limte, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance^) within the specified frequency, on equipment that is inoperable, or on variables that are outside specified limits, does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions in the Applicability.
However, since the Control is not met in this instance, Control 3.0.4 wiH govern any restrictions that may (or may not) apply to MODE or other specified condition changes.
The provisions of this Control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
The provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context a unit shutdown is defined as a change in MODE associated with transitioning from MODE 1 to MODE 2 or 3, MODE 2 to 3, and MODE 3 to 4.
The precise requirements for performance of SRs are specified such that exceptions to SR 4.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition^) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated Control prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the Control's Applicability would have its frequency specified such that it is not "due" until the specific conditions needed are met Alternately, the Surveillance may be stated in the form of a note as not required (to be met or performed) until a particular event, condition, or time has been reached.
?ERRY UNIT 1 B 3/4 0-8
ODCM Page: 156 Rev.: 21 INSTRUMENTATION 3/4 3 7 MONITORING INSTRUMENTATION 3/4 3 7 9 RADIQAn-nVF LIQUID FFFI LJENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor andcontrol, as releases of radioactive materials in liquid effluents during actual or potential -<<-
The alarm/trip setpoints for these instruments shall be calculated in accords the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits ofJ^FRiW. "e OPErSjtY and use of this instrumentation is consistent wrth the requirements of 10CFR50, Appendix A, General Design Criteria 60, 63, and 64.
?M 3 7 10 RADIOACTIVE QASFQW PFFLUEN.T MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided *J^JZ*JS*££*i of radioactive g StaS TnValarm setpoints for these instruments shall be ^^^^
procedures in the ODCM to ensure that the alarm will occur ^^^SS^d The OPERABILITY and use of this instrumentation is consistent with the requirements of Appendix A, General Design Criteria 60,63, and 64.
PERRY - UNIT 1 B 3/4 1-1
ODCM Page: 157 Rev.: 21 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section HA design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20 to the population. The concentration limit for dissolved and entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its limiting effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
This Control applies to the release of radioactive materials in liquid effluents from all units at the site.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in:
(1) Currie, L. A.., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4Q07 (September. 1984).
(2) HASL Procedures Manual HASL-300 (revised annually).
3/4.11.1.2 DOSE This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections IIA Hl-A and IVA The Control implements the guides set forth In of 10CFR50, Appendix I, Section IIA The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in of 10CFR50, Appendix I, Section IV.A which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculations in the ODCM implement the requirements in 10CFR50, Appendix I, Section IILA that confomnance with the guides of 10CFR50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive PERRY UNIT I 3 3/4 2-'.
ODCM Page: 158 Rev.: 21 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.2 DOSE (Continued) materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1", October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
3/4.11.1.3 LIQUID RADWASTF TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion 60; and the design objective given in 10CFR50, Appendix I, Section II.D. The specified limit governing the use of appropriate portions of the Iiquld radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in 10CFR50, Appendix I, Section IIA, for iquid effluents.
This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing the system.
PERRY - UNIT 1 B 3/4 2-2
ODCM Page: 159 Rev.: 21 RADIOACTIVE EFFLUENTS RASPS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the dose any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 for UNRESTRICTED AREAS. The annual dose rate limits are those associated with the concentrations of those limiting effluent concentrations, as described in Regulatory Guide 1.109. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC In an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in 10CFR20, Appendix B, Table II. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict at all times, the corresponding gamma and bete dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body or to less than or equal to 3000 mrem/year to the skin.
These release rate limits also restrict, at aH times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.
This Control applies to the release of radioactive materials in gaseous effluents from all reactors at the site. The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limit of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in:
(1) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984).
(2) HASL Procedures Manual, HASL-300 (revised annually).
3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.B. 111.A and IV.A. The Control implements the guides set forth in 10CFR50, Appendix I, Section II.B. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50, Appendix I, Section NA to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section IILA that conformance with the guides of 10CFR50, Appendix I, be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
PERRY UNIT 1 3 3/4 2-3
ODCM Page: 160 Rev.; 21 RADIOACTIVE EFFLUENTS BASES ,
3/4.11.2.2 DOSE - NOBLE GASES (Continued)
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Revision 1",
October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are made using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.3 DOSE - IODINE-131. IODINE-133. TRITIUM AND FjApiONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.C, IIIA and IVA The Controls are the guides set forth in 10CFR50, Appendix I, Section II.C. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50, Appendix I, Section IVA, to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculation^ methods specified in the Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section IIIA, that conformance with the guides of 10CFR50, Appendix I be shown by calculation^ procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculation^ methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium and radionudides in particulate form are dependent on the existing radionucfide pathway to man in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne radionudides, (2) deposition of radionudides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
PERRY - UNIT 1 B 3/4 2-4
ODCM Page: 161 Rev.: 21 RADIOACTIVE EFFLUENTS 3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTF TREATMENT fOFFGASl SYSTEM AND VENTILATION EXHAUST TREATMENT SYSTEMS The OPERABILITY of the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment The requirement that the appropriate portions of the systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as tow as is reasonably achievable."
This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion; and the design objectives given in 10CFR50, Appendix I, Section II.D. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in 10CFR50, Appendix I, Sections II.B and II.C, for gaseous effluents.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units sharing that system.
3/4.11.4 TOTAL DOSE This Control is provided to meet the dose limitations of 40CFR190 that have been incorporated into 10CFR20 by 46 FR18525 and the dose limitations of 10CFR72.104. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the whole body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40CFR190, if the individual reactors remain within twice the dose design objectives of 10CFR50, Appendix I, and if direct radiation doses from the units including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40CFR190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR190 have not already been corrected), in accordance with the provisions of 40CFR190.11 and 10CFR20.405C, is considered to be a timely request and fulfills the requirements of 40CFR190 until NRC staff action is completed. The variance only relates to the Hmits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20, as addressed in ODCM Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
?SRRY UNIT i B 3/4 2-5
ODCM Page: 162 Rev.: 21 a/412 RADIOLOGICAL EhMRQNMFNTAL MONITORING 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure ££^!^FJ!£U radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE public resulting from the plant operation. This monitoring program implements 10CFR50, Appendix I Section IV B 2 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental e*P°*ut*
pathways. Guidance for this monitoring program is provided by the RadWogicaLMnwm^Bf' Technical Position on Environmental Monitoring, Revision 1, November 1979. 'e^rtia%8^"*
monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of^he tower limrts of detection (LLDs). The LLDs required by ODCM Table 4.12-1 are eonsMtaradI opt.mum for routme environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in:
(1) Currie, L. A. "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984).
(2) HASL Procedure Manual, HASL-300 (revised annually).
3/412.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitonngprogram given in me ODCM are made If required by the results of the census. The best informat.on from door-to-door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census Xfies the requirements of 10CFR50, Appendix I, Section ^B-3^estrict.ng the census togardens of greater than 50 ma provides assurance that significant exposure pathways via leafy vegetables wiH be identified and monitored since a garden of this size is the minimum required to produce the quantify 26kgtoar) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child To
£KS£minimum garden size, the following assumptions were made: (1) 20% o^he garderrws used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2.
3/4 12.3 INTFRIABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratoiy Comparison Program is ensurethat independent checks on the precision and accuracy of the measurements of material in environmental sample matrices are performed as part of the ^^
environmental monitoring In order to demonstrate that the results are valid for the pur Appendix I,Section IV.B.2.
PERRY - UNIT 1 B 3/4 3"1
ODCM Page: 163 Rev.: 21 6.0 ADMINISTRATIVE CONTROLS
ODCM Page: 164 Rev.: 21 ANNUAL REPORTS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous year shall be submitted by May 1 of each year.
The annual Radiological Environmental Operating Report shall include:
a Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, Including a comparison wrtti pre-operational studies, operational controls (as appropriate), and previous environmental survelltance reports and an assessment of the observed impacts of the plant operation on the environment;
b. The results of land use censuses required by Control 3.12.2; c The results of analysis of all radiological environmental samples and of all locations specifledin the table and figures in the Offeite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that *°'
individual results are not available for inclusion with the report the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report; d A summary description of the Radiological Environmental Monitoring Program; atleast two legible maps* covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Inter-laboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3 12 3; reasons for not conducting the Radiological Environmental Monitonng Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3 12.1-1; discussion of environmental sample measurements that exceed the reportins(levels of Table 3121-2 but are not the result of plant effluents, pursuant to ACTION b of Control 3.12.1, and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.
One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
PERRY - UNIT 1 4~1
ODCM Page: 165 Rev.: 21 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 Routine radioactive release reports covering the operation of the unit during the previous year shall be submitted annually. The Report shall be submitted by May 1 of each year.
The Annual Radioactive Effluent Release Report shall include:
a. A summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, 'Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from IJght-Water-Cooied Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
b. A summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
c. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous year. This report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (see Figure 3.2-1) during the report period. Ail assumptions used in making these assessments, i.e., specific activity, exposure time, arid location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
d. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cyde sources, induding doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40CFR190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
~~e. A list and description of unplanned releases from the site to UNRESTRICTED AREAS (see Figure 3.2-1) of radioactive materials in gaseous and liquid effluents made during the reporting period.~~
f. Any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to PNPP Technical Specification 5.5.1 as well as any major change to Liquid or Gaseous Treatment Systems pursuant to Control 6.15. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.
g. The report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 3.3.7.9 or 3.3.7.10, respectively; and description of the events leading to liquid holdup tanks exceeding total curie limits PERRY - UNIT 1 4-2
ODCM Page: 166 Rev.; 21 SPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10CFR50.4 within the time penod specified for each report 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.2 Records of surveillance activities, inspections, and calibratbns required by these Controls shall be retained for at least 5 years.
PERRY - UNIT 1 4-3
ODCM Page: 167 Rev.: 21 ADMINISTRATIVE CONTROLS 615 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS*
6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:
1. Shall be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain:
~~a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;~~
~~b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;~~
~~c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems~~
d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e An evaluation of the change which shows the expected maximum exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;
f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
~~g. An estimate of the exposure to plant operating personnel as a result of the change; and~~
~~2. Shall become effective upon review and approval by the Plant Manager.~~
Licensee may choose to submit the information called for in this Control as part of the annual USAR update.
PERRY - UNIT I 4-4
ODCM Page: 168 Rev.: 21 RECORDS The following records are completed/generated by this document:
Quality Records Annual Radioactive Effluent Release Report Non-Qualitv Records None Commitments
ODCM Page: 169 Rev.: 21 REFERENCES
~~1. Title 10, "Energy," Chapter 1, Code of Federal Regulations: Part 20, U.S. Government Printing Office, Washington, D.C. 20402, May 21,1991.~~
~~2. Title 10, "Energy," Chapter 1, Code of Federal Regulations: Part 50; U.S. Government Printing Office, Washington, D.C. 20402, January 1,1984.~~
~~3. Title 40, "Protection of Environment," Chapter 1, Code of Federal Regulations. Part 190, Federal Register, Vol. 42, Washington, D.C. 20402, January 13,1977.~~
~~4 U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Washington, D.C. 20555, October, 1981.~~
~~5. U.S. Nuclear Regulatory Commission, 'Draft Radiological Effluent Technical Specifications for PWR's." USNRC NUREG-0473, Revision 2, Washington, D.C. 20555, February, 1980.~~
6. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity In Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.
~~20555, June 1974.~~
~~7. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I," Revision 0, U.S.~~
~~Nuclear Regulatory Commission, Washington, D.C. 20555, March 1976.~~
8. Regulatory Guide 1.109. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix L* Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1977.
~~9. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, U.S.~~
~~Nuclear Regulatory Commission: Washington, D.C. 20555, July 1977.~~
10. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision i. U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, April 1977.
11. Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment," U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, February 1979.
~~12. U.S. Nuclear Regulatory Commission, "Branch Technical Position," Revision 1 Washington, D.C.~~
~~20555, November 1979.~~
~~13. Perry Nuclear Power Plant, Unit 1 and 2, "Final Safety Analysis Report," Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.~~
14 Perry Nuclear Power Plant, Units 1 and 2, "Environmental Report, Operating License Stage,"
Supplement 3, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November 1981.
~~15. Perry Nuclear Power Plant, Units 1 and 2, "Radiological Environmental Monitoring Program Manual," The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February 1985.~~
~~ODCM Page: 170 Rev.: 21 REFERENCES fConU~~
~~16. "Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Lowe and Garrick, Washington, D.C. 20036, July 1983.~~
~~17. Kocher, D.C., "Radioactive Decay Data Tables," Technical Information Center, U.S. Department of Energy, Springfield, Virginia 22161, September 1985.~~
~~18. 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP, (Ref.SO-11552"E").~~
~~19. Perry Environmental Report Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP and Q&R Page 2.1-2.~~
~~20. PNPP Ohio Power Siting Commission application of August 1974, Appendix 1304-C-2, Table IV-A-2.~~
~~21. Total Angler Catch (1987 annual) for Each Grid Location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources (6-20-88).~~
~~22. Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors; Generic Letter 89-01, Supplement No. 1.~~
~~23. Federal Guidance Report 13 CD Supplement: Cancer Risk Coefficients for Environmental Exposure to RadbnucHdes.~~
REGULATORY APPLICABILITY DETERMINATION N° A -A A RW. 00 NOP-LP-4003-01 Rev. 04 Page 1 of 8 Initiating Activity NO.
Procedure CHI-ODCM m9m DBVPS1 DBVPS2 DDBNP8 EPNPP
~~Title:~~
~~Offslte Dose Calculation Manual Brief description of activity {what la batng changed and why):~~
1. References to cloaad commitment L02211 ware removed Administrative change to the remove reference to a closed commitment L02211 tracked changes nacaaaaiy wNh Icanaa amendment 72 to Technical SpecMcationa - RETS. Coimnttmant text reads aa follow*: The Commlaalon has Isauad the encloaed Amendment no. 72 to Faculty Operating Ucanaa No. NPf-58 for the Peny Nuclear Powar Plant, Unit No. 1. Amendment 72 revises the Technical Speclteatlon* conalatant with Generic Letter 89-01. Implementation of programmatic controls for Radiological Effluent Technical Specifications In the Administrative Controls section of Technical Specifications and the relocation of procedural details of RETS to the Offslte Dose Calculation Manual or to the Process Control Program." Compliance with Tfi 5.5.1 and 5.6.4 la nwfntainad.
~~2. Reference to closed commitment R00449 was removed from Table 4.11.1.1.1-1.B under the grab sample composite.~~
Administrative change to remove reference to closed commitment ROOMS required a quarterly analysis for Sr-89 and Sr-90 on a composite mads on paniculate filters from each aamplng location collected. This requirements la contained In Table 4.11.1.1.1-1 .B of the ODCM.
~~3. Section 3.1 .a: Clarified that the alert alarm received must be valid.~~
~~4. Created formal Table 3.1-2 from table of Effluent Release Path flow rates listed under section 3.1.4 aquation deflnltlone.~~
~~Administrative change to give table an official table title for easier reference.~~
~~5. Added new Table 3.1-2 to flat of Tables on page III.~~
~~Administrative change to update List of Tablaa to Include new TaWe 3.1-2.~~
~~6. Combined the note In atop 3.1.4 with the definition of "f' and addsd note to reference table 3.1 -2.~~
~~Editorial change for clarity.~~
7. Section 5.1: Removed reference to alto-specific environmental monitoring procedure REMP-0013. Editorial change to remove unnecessary Information. The site-specific REMP4013 procedure lists location* in addition to those required by the ODCM. It should not be referenced In the ODCM as a required Hat
~~8. Table 5.1-1: Shortened title of TaMe to remove extra unnecessary Information.~~
~~Editorial change to remove extraneous material from Table title.~~
~~0. Table 5.1-1: Renamed location 53 to reflect location's address Instead of name of company In business at that location.~~
Editorial change to reflect location's address instead of name of company In business at that location. TLD location doss not change, no matter what the name of the company In business at this location at a given time.
~~10. Table 5.1-1: Clarified that locations 36 and 39 are drinking water.~~
~~Clarification aa to which type of water sample Is taken at these locations. As both are municipal water purification plants, drinking water was Implied, but not clearly stated.~~
~~11. Table 5.1-1: Clarified that locations 59 and 60 are surface water eampte locations. -~~
~~Clarification aa to which type of water sample is taken at these locations. Aa both are shoreline locations, surface water was Implied, but not dearly stated.~~
~~12. TaMe 5,1-1: Changad "Pood Products" to "Broadleaf Vegetation- at locations 2,37, and 70.~~
~~Clarification to specify the typs of Food Products (broadleaf vegetation) as required by Table 3.12.1-1.~~
~~13. Figures 5.1-1,6.1-2, and 5.1-3: Updated maps to reflect changad aampla locations.~~
Administrative update of maps related to changes 23 through 28.
REGULATORY APPLICABILITY DETERMINATION N° NOP-LP-4003-01 R<<v. 04 Page 2 of 8 moating Activity No.
Rbv. 21 Procedure CHI-ODC*
DBVPS1 DBVPS2 DpBNPS 0PNPP
~~14. Revised Table A-2 to add a new column showing distance in mster*.~~
Clarification to provide conversion of mile* (previously In the table) to rnefem from UFSAR Table 2.3-27.
Distance in meters it used In calculations In Appendix A.
15. Tablet 3.3.7.10-1 and 44.7.10-1 Table Notations; Removed *""During main condenser off-flas treatment system operation.*1 Editorial correction to remove footnote that doee not apply In Table 3.3.7.10-1 and 4,3.7,10-1 In the Perry ODCM.
~~The Perry ODCM contains only tingle aeterlaka which algnlfy "at all times" for a mode of applicability.~~
~~16. Table 3.3.7.10-1: Removed footnote (1) from each page and added It to the table notation*.~~
~~Editorial change to remove the footnote from each page of the table and mate It a table endnote for formatting consistency in the document~~
~~17. Table 3.3.7.10-1: Added action 124 to Unit 1 Vent noble gae channel during modes 4 and S.~~
Procedure correction. When the original change was drafted Into the OOCM, the fact that the Unit 1 Vent has a potential source term during modes 4 and 6 from the spent fuel pool was overlooked and Action 124 was omitted for Unit 1 Plant Vent for Modee 4 and 6.
~~18. Table 3.12.1-1: Changed number of TLDe to 29.~~
~~Editorial change to update number of TLDs listed In table to reflect change made In Item 22.~~
~~19. Table 4.3.7.9-1 Table Notation 3: Updated NBS reference to NtST.~~
~~Administrative change to change title of department The National Bureau of Standards, or NBS, became the National Institute of Standards and Technology, or NiST, In 1988.~~
20. Revised Section 6.9.1.7 to move the Information denoted by an asterisk regarding maintaining the meteorological report separate from the Annual Report Into paragraph b; spilt the paragraph Into two for clarity purposes.
~~Editorial change for clarity to bring pertinent Information Into the text, rather than a note.~~
21. Removed asterisk footnote contained In ODCM revision 20 page 179 which contains a continuation of Section 9.9.1.7 and Sections 6.9.2 and 8.10. This page contains no asterisks. Asterisk footnote discussed the option of submlttal as part of the annual USAR update.
Editorial correction to remove asterisk footnote that Is not applicable to the page on which tt was located. The asterisk applies to Section 6.16, Major Changes to Radioactive Waste Treatment Systems, where the "Licensee may choose to submit the Information esllsd for in this Control ss part of the annual USAR update*. The footnote appears eorrectiy for Section 6.15. In revision 19. Section 6.15 started on the same page as the end of section 6.9.1.7. WHh ODCM revision 20, pagination was changed to start section 6.16 on a separate page. The footnote waa Inadvertently left on the previous page WHh the remainder of Section 9.9.1.7, Section 9.9.2, and 9.10 In revision 20.
~~22. Added new section for commitments.~~
~~Administrative change for clarification by adding list of commitments Implemented In this document.~~
~~23. Minor editorial and grammatical corrections.~~
~~Editorial changes.~~
24. Section 4.2: Removed requirement that specified that environmental TLDs will be changed out quarterly and annually and replaced with a reference to Table 3.12.1-1, Radiological Environmental Monitoring Program.
This change ensures there is only one location In the ODCM that specifies monitoring frequency and directs to the appropriate table. The additional administrative burden of collecting TLDs annually as well as quarterly was removed by this change. Only quarterly TLD collection Is required by NUREG-1302. Each TLD location contains at least two TLDs as required which are collected and analyzed quarterly,
25. Table 6.1-1: Added new TLD location 57. The TLD at Location 67, Perry High School, was added when the old school on Center Road was demolished and a school waa built at the new location. According to ODCM
No 17-02381 REGULATORY APPLICABILITY DETERMINATION NOP-LP-4Q03-01 Rev. 04 Page 3 of 6 Mllating Activity No. Rev. 21 Procedure CHI-ODCM DBVP81 DBVP82 DDBNPS B PNPP Table 3.12.1-1, Exposure Pathway/Sample 1, Direct Radiation, TLDa should bt placsd "In special Interest areas... such as schools." Ths TLO In Location 68 at the previous school location remains In place due to Ins location remaining a special Interest area as a public soccer field.
26. Table S.1-1: Removed location 18 for milk sampling due to death of the goat The goat was not replaced by the owner. There are no additional milking, animals within the prescribed distance from the plant whose owner*
wish to participate In the Peny Nuclear Power Plant Radiological Environmental Monitoring Program. PNPP performs broad leaf vegetation as required by Table 3.12-1, Radiological Environmental Monitoring Program, Section 4.c Food Products when milk sampling Is not performed.
27. Table 6.1-1: Removed location 18 bi the East sector for broadleef vegetation sampling as owners chose not to continue participation in the PNPP REMP. This location was replaced with location 20, also In the East sector (sse change 26). Table 3.12.1-1 Ac requires two different offstte locations for broadteaf vegetation sampling. The REMP as outlined In Table 5.1-1 contains more than two Indicator locations (2,16,20, and 3T) as we* as a control (70).
~~28. Table 6.1-1: Added new broadleaf vegetation sampling locations 16 and 20.~~
With no milking animals within the required five km distance from the PMPP, the ODCM requires that food product sampling Is performed at two locations of the highest D/Q sectors. Locations 16 and 20 hava participated In the broadleaf vegetation sampling program for yearn and aatlafy the requirements of the ODCM because they lie In two of the three highest D/Q sectors: location 20 in tlie East ami kxjai^ 16 in the South.
The addition of food product sampling locations In the East and South sector* aligns ODCM Table fci-1 impHng locations to compliance with the environmental monitoring requirements contained In NUREG-isoz and ODCM Table 13.12.1-1.
i <<%pfcj%u v_kla* I4I4J 4
29. Table 8.1-1: Removed location 28 (Aahtabula Plant that closed) and added nsw location 39 (P<<>>*<wlHe Water Plant). When the control drinking/surface water location, Aahtabula Plant, closed, It wit replaced with the Painesville Purification Plant, which Is outside of the Influence of PNPP. A Control location Is onethat could not be affected and/or Influenced by plant discharge. The new water control location at the Painesville Purification Plant to located 8J miles west of the plent The current In Lake Erie flows In the easterly direction toward Niagara Falls. Additionally, the Grand River discharges to ths take between the plant and the new location, further limiting any Influence the plant may have on this new Control location.
30. Table 5.1-1: removed location 65 (Major Stream Mouth) and added new location 66 (Lakeshore Metroparic Reservation) due to loss of sampling location due to erosion. Location 65, Major Stream Mouth, for sediment collection became inaccessible In July of 2014 due to shoreline erosion. Location 66, UkeahoreMetropark Reservation, waa Identified as a replacement location for the major stream sediment location after It became Inaccessible Table 3.12.1-1 3.C requires one sample from an area with existing or potential recreational value for shoreline sediment The Lakashore Mstropark Reservation is downstream of the Influence of the plant and has recreational significance because It Is a public beach.
~~31. Tabto 3.12.1-1: reduced numbereemptoa offleh species requto^~~
Important species from two samples of each species to ons sample of each species In both '<<'CT*'
unaffected by the plant discharge. Updated to be consistent with wording In NUREG-1302, which states, One sample of each commercially and recreaflonally important apeclee In vicinity of plant discharge area and one sample of eame species In areas not Influenced by plant discharge". Reduces extra sampling that Is not required.
~~32. Table 3.12.1-1 Section 4.b: revised sampling frequency from "one sampielln *ewon"lto -<<"**<<*&"~~
season or semlannually If they are not seasonal." Updated to be consistent with wording In NUREG-1302 which states, "Sample in season, or semlannually If they are not seasonal.
No. 17-02381 REGULATORY APPLICABILITY DETERMINATION Rev. 00 NOP-LP-4003-01 Rev. 04 Page 4 of 8 Initiating Activity No.
Procedure CHI-ODCM Rev. 21 D BVPS1 QBVPS2 D DBNPS 0PNPP
~~1. EXEMPTIONS Is the scope of the entire activity exempt from the 10CFR50.69 process because ft la limited to:~~
1.1 Managerial or administrative change*.. , ..>,.........,.,. _, .,. YES NO 1.2 UFSAR changes (or equivalent information) excluded from the requirement to perform a 10CFR50.59 Screen and Evaluation by NEI86-07 or NEI98-03?... YES 0 NO 1.3 Maintenance activities and temporary alterations In support of maintenance planned for 90 days or less while at power ,...,.........,,. ,. .,.. >........ .,,,.,. DYES S2N0 1A Changes evaluated under another program that included a 10CFR50.59 Scnien. YES 0 NO
~~2. OTHER REGULATIONS 2.1 DoesHie activity require a Deense amendment?~~
2.1.1 Operating License..... ., YES 53 NO 2.1.2 Technical Spedlkatlons.... , ...,..,......,...,,., >.,.. DYES- 0NO 2.1.3 Environmental Protection Plan (BVPS and PNPP only)- ,.... ._.....,... n YES 0 NO 2.2 IS the activity or any portion of the activity governed by one or more of the following regulations:
2.2.1 Quality Assurance Program (10CFR80.54(a>> ..., ..., .> YES B NO 222 Security Plans (10CFR50,54(p)).,.,... , .,.,.... .^ YES H NO 2.2.3 Emergency Pton (10CFR50.54{q)) .._ .,>,. D YES S NO 2.2.4 1ST Progwm Plan (10CFR50.55(aKD)>>. .. D YES H NO 2.2.5 ISI Program Plan (10CFR5D.35(a)(g)) ^ D YES 0 NO 2*2.8 Flie Protection Pnjgram (10CFR50^8) ,.,.,...,..., , YES NO 2.2.7 Independent Spent Fuel Storage Facility (10CFR72.49)...... ..<........, D YES S NO 2.2.8 Another regMation:
Standard* For Protection Against Radiation (10 CFR 20 including ODCM).. El YES D NO Specfflo Exemptions (10 CFR 50.12) ..., YES 0 NO ECCS Acceptance Criteria (10 CFR 5046),. .,...... ..,.. D YES S NO Environmental Protection (PBNPSonly).., ,... D YES B NO Other- fat the regulation^): <<f<< below BYES D NO
No. 17-02361 REGULATORY APPLICABILITY DETERMINATION NOP-UM003-01 Rev.04 PagaSof 6 Initiating Activity No. Rev. 21 Procedure CM-ODCM DBVPS1 DBVP82 DDBNP8 CONCLUSION 3.1 Does 10CFR50.59apply7 LJ YES M NO 3.2 Does this activity require a change to the UFSAR? Change Request No: U YES bfl NO 3.3 Summarize the bases for responses: Include Keywords used to search documents.
Keywords: Radiological Environmental Monitoring Program, RBf, fish, TLD, drinking water, milk, sediment, downscsls, gaseous effluent, radiation monitor, ODCM, Offsrte Dose Calculation Manual, NURE01302,89-01, Reg Guide 1.21 The UFSAR wonl search for toe keywords above revealed no results which would require changes to the UFSAR. Changes made maintain compliance wtth UFSAR Table 1.8-1: Conformant* to NRC Regulatory Guides; 3.1.2.6.5: Criterion 84 - Monitoring Radioactivity Releases; 11.3 Osseous Waste Management Systems; and 11.6 Process And Effluent Radiological Monitoring And BampHng Systems.
A review of the regulations Hated in section 2.1 was performed and K was concluded that this change to the ODCM neither directly nor Indirectly affects the Operating License, Technlcsl Specifications (specifically 5.i.1 and 6.&4J, or the Environmental Protection Plan. The proposed procedure change does not change any part of these documents such that a license amendment Is required.
Technical Specifications fi.0, Administrative Controls, Section 6.6 Programs and Manuals requires that the following programs and manuals shall be established, Implemented, and maintained for the Offstte Doss Calculation Manual (ODCM).
ki Section 8.6.1: Licensee Initiated changes to the ODCM:
~~a. Shall be documented and records of reviews performed shall be retained. Thle documentation shall contain:~~
1. sufficient Information to support the change(s) together with the appropriate analyaea or evaluations Justifying the changers), and _*.*, j~mu* *n
2. a determination that the changes) maintain the levels of radloactivs effluent control required by 10 CFR 20.1302,40 CFR 100,10 CFR 60.36a, and 10 CPU SO Appendix I, and not adversely Impact ths accuracy or reDsblllty of effluent, doss, or setpolnt calculations dluMl.
~~b. Shall become effective after review and acceptance Including approval by the proceduraUy authorized Individual.~~
This change to the ODCM Is documented In accordance with REC-0107, Control of the Offer* Dose Calculation Manual. The REC-0107 evaluation determined that the change maintains the level of radioactive effluent control required by 10 CFR 20,1302,40 CFR100,10 CFR 50.36a, and 10 CFR 50 Appendix I. The REC-0107 evaluation determined that the proposed changes do not adversary Impact the accuracy or reliability of effluent calculations, doss calculations, or setpolnt calculations. The P'e<<[u^l*2>>fc package, Including REC-0107 Attachment 1, Is retained as a quality record and documents the Information required In 8ectk>n 8.5.1 a.1 and a.2 for ucenaee-lnitlated changes. Ths ODCM becomes effectrvs after reviews and acceptance In accordance with the process outlined In NOP-SS-3001. Procedure Review and Approval.
A review of the section 2A1 through 2.2.7 regulations waa performed and It waa concluded that this change to the ODCM doea not result In a change or deviation from any of the program requirements referenced In section 2.2 of this form. The Quality Assurance <QA) Program la unaffected by this change.
This procedure change doea not Impact the Fire Protection Program, the Security Plan or the Emergency Plan. There la no effect on the In-Servlce Test Program Plan, the ln-8eivlce Inspection Program Plan and is not related to an Independent Spent Fuel Storage Facilty.
Other Regulations which apply per section 2.2.8:
-10 CFR 20, Standards for r^rotection Against Radiation, Including 10 CFR 20.1302
- 40 CFR Part 190, Envlronmsntsl Radiation Protection Standards for Nuclear Power Operations
-10 CFR 50.36a, Technical Specifications on Effluents from Huclsar Power Reactors.
-10 CFR 50 Appendix lf Numerical Guide, for Dsskjn Objsctlvss_andjf"^^1^' ^°#JS^
Meet ths Criterion -As Low as Is Reasonably Achievable" for Radloactlva Material In Ught-Water-Cooted
- Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactivity In Solid Wastesand Release of Radioactivity In Liquid and Gaseous Effluents from Lkjht-Wster Coded Nuclear Power Plants
No. 17-02381 REGULATORY APPLICABILITY DETERMINATION NOP-LP-4003-01 RtV. 04 Rev. 00 Page 6 of 8 Initiating Activity No.
Procedure CHMODCM Rev. 21 D BVP81 D BVPS 2 dbnps gjPNPP
- Generic Utter 89-01, Supplement No. 1, Implementation for Programmatic Controls for Radiological Effluent Technical Specification In the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offelte Doee Calculation Manual or to the Process Control Program.
- NUREO-1302, Offelte Doee Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors
- Perry Nuclear Power Plant Units 1 and 2 Environmental Report, Operating License Stage. Sections 5.2.4 and 6.2.5 The first 23 Items described In the "Brltf Description Of Activity" above fall under the administrative definition In section 1.1 and do not need to be evaluated under 50.59. These Kerns are editorial or clarifying In nature and move, add, or delete Information throughout the ODCM. No changes will occur ae a result of the first 23 Hems In the ODCM change that would Impact compliance with Technical Specifications 6.6.1 or 5.5.4,10 CFR 20 (Including 10 CFR 20.1302), 40 CFR Part 190,10 CFR 50.36a, 10 CFR 60 Appendix I. Reg.
Quids IK, Generic Letter 8941, Supplement No. 1, NUREO-1302, or the Environmental Report Items 24 through 32 In the "Brief Description of Activity" involve changes to the Radiological Environmental Monitoring Program (REMP) sampling locations and frequency of collection. The Radiological Environmental Monitoring Program (REMP) Is not discussed In the UFSAR. these changes to the REMP do not constitute modifications or additions to, or removal from, the facility or procedures that affect a design function, method of performing or controlling the function, or an evaluation that demonstrates that Intended functions will be accomplished. The REMP is conducted outside the facility and Is a monitoring program to evaluate the environmental Impact of site radiological releases. As such, K doss not affect the Facility as Described in the UFSAR (The structures, systems and components that ire described in the UFSAR, the design and performance requirements for such SSCs described In the UFSAR, and the evaluations or methods of evaluation Included In the UFSAR to demonstrate that the Intended function(B) of such SSCs win be accomplished.) The REMP has no adverse Impact on 8SC operation or function and 50.59 doss not apply. These changes require evaluation to the other regulations which apply per section 2.2.8,
24. Section 4.2: Removed requirement that specified that environmental TLDs win* be changed out quarterly and annually and replaced with a reference to Table 3.12.1 -1, Radiological Environmental Monitoring Program.
This change ensures there Is only one location In the ODCM that specifies monitoring frequency and directs to the appropriate table- Annual collection of TLDs hi over and above the requirements set forth in NUREG-1302. The additional administrative burden of collecting TLDs annualry as well as quarterly was removed by this change. NUREG-1302 does not require annual TLDs. Only quarterly TLD collection is required by the NllREG.
For the purposes of ODCM Table 13.12.1-1, a thermolumlnescerrt dosimeter (TLD) is considered to be one phosphor; two or more phosphors In a packet are considered as two or more dosimeters (see table I note 2). Each quarterly TLD contains two or more phosphors and, therefore, meets the requirement of i NUREO-1302.
Quarterly TLD collection to more restrictive than annual coRectlon. As quarterly TLD collection remains a I requirement In the ODCM, this change does not affect PNPP's compliance with the environmental l monitoring requirements contained In Reg. Guide 1.21, NUREG-1302 (GL 09-01), or the Environmental I Report. This change has no adverse effect on compliance with Technical Specifications 6.5.1 or 5.5.4.
~~[ 28. Table 5.1-1: added new location 57~~
The TLD at Location 57, Perry High School, was added when the Old school on Center Rd. was demolished j and a school was built at the new location. According to ODCM Table 3.12,1-1, Exposure Pathway/Sample l 1, Direct Radiation, TLDs should be placed "In special Interest areas., such as schools." The TLD In Location 59 at the previous school location remains In place due to the land being repurposed as a special interest area as a public soccer field. Addition of another TLD to the ODCM Increases the monitoring j performed and monitors offslte dose at an additional location. Addition of new location 57 maintains pvipp In compliance with the environmental monitoring requirement* contained In Reg. Guide 1.21, NUREG-1302 (GL 89-01), the Environmental Report, and the ODCM. This change has no adverse effect on compliance with Technical Specifications 5.5.1 or 5.5A
7-02381 REGULATORY APPLICABILITY DETERMINATION Rev. 00 NOP-LJM0Q3-01 Rev. 04 Page 7 of 8 Initiating Activity No.
Rev. 21 Procedure CHI-ODCM BVPS1 DBVPS2 D DBNPS 0 I>NPP
~~26. Table 8.1-1: removed location 18 for milk sampling.~~
MHt sampling at location 18 was lost due to the death of the goat The goat was not replaced. Them are no additional milking animals within the prescribed distance from the plant whose owners wish to participate in the Peny Nuclear Power Plant Radiological Environmental Monitoring Program. (Documented In Chemistry Technical Assignment File 15-009.)
ODCM Table 3.12-1, Radiological Environmental Monitoring Program, Section 4.c Food Products requires sampling of broadleaf vegetation if milk sampling la not performed. PNPP performs broadleaf vegetation sampling in accordance with ODCM Table 3.12-1 requirements and has been doing so for many yean. With removal of location 18 for milk sampling, PNPP remains In compliance with the environmental monitoring requirements contained In Reg. Oulde 1.21, NUREO-1302 (OL 89-01), the Environmental Report, and the ODCM. This change has no adverse effect on compHanee with Technical Specifications 5.6.1 or 6.SA
27. Table 5.1 -1: Removed location 18 in the East sector for broadleaf vegetation sampling as owners chose not to continue participation In the PNPP REMP. This location was replaced with location 20, also In the East sector (see change 26). Table 3.12.1-1 Ac requires two different offstte locations for broadteaf vegetation sampling in the highest D/Q sector*. The REMP as outlined In ODCM Table 6.1-1 contains more than two indicator locations (2,16,20, and 37) In the highest Dtt sectors as well as a control (70) in the least prevalent D/Q sector. WHh the removal of location 18 and concurrent addition of location* 18 and 20, PNPP remains In compliance with the environmental monitoring requirements contained In Reg. Guide 1.21, NUREG-1302 (GL 89-01), the Environmental Report, and the ODCM. This change has no adverse effect on compliance with Technical Specifications 6.5.1 or 5.5.4.
~~28. TaMs $.1-1: Added new broadleaf vegetation sampling locations 18 and 20.~~
With no milking animate wtthtn the required five km distance from the PNPP, the ODCM requires that food product sampling la performed at two locations of the highest D/Q sector*. Using ODCM TaWe A-2, the highest D/Q sector on land Is the East (with a D/Q of 1JE48 per square meter). The second highest sector Is a tie between the South and the East Northeast (ENE) (with a WQ of 1.6E-08 per square meter).
ODCM Table 1.12.1-1, Radiological Environmental Monitoring Program, Section 4.c Food Products requires "Sample of three different kinds of broad leaf vegetation grown nearest each of two different offslte locations of highest predicted snnual average ground level D/Q if milk sampling Is not performed" and "One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant In the least prevalent wind direction If milk sampling Is not performed."
The two broadleaf vegetation collection locations listed m revision 20 of the ODCM (locations 2 and 37) are In one of the three highest D/Q sectors (ENE). Two other locations are being sampled In addition to the ODCM-requlred locations. Locations 16 and 20 have participated In the broadleaf vegetation MmpUno program for years and satisfy the requirements of the ODCM because they lie in other two highest DfQ sectors: location 20 In the East and location 16 In the South. These changes maintain the PNPP REMP m line with historically-sampled sectors. Location 70 remains unchanged as the control location in the least prevalent SSW D/Q sector. (Documented In Chemistry Technical Assignment File 17-004.)
The addition of food product sampling locations In the East and South sectors aligns ODCM Table 5.1-1 sampling locations to compliance with the environmental monitoring requirements contained In NUREO-1302 and ODCM Table 13.12.1-1. WHh this change, PNPP le In compliance with the environmental monitoring requirements contained in Reg. Guide 1.21, NUREO-1302 (GL 89-01), the Environmental Report, and the ODCM. This change has no adverse effect on compliance with Technical Specifications 5.6.1 or 5.5.4.
~~29. Table 5.1-1: removed location 28 and added new location 39.~~
Location 28, Ashtabula Plant, was closed In 2019, at which time water collection was no longer avalable.
Location 36: PaJnesvIlle Plant: When the control drinking/surface water location, Ashtabula Plant, closed, It was replaced with the Pameevilie Purification Plant which Is outside of the Influence of PNPP.
(Documented In Chemistry Technical Assignment File 16-004.)
In the ODCM Table 3.12-1, the Waterbome - Drinking section contain* a requirement for a control
ample but does not specify Its location. A control location la one that could not be affected or Influenced by plant discharge. The new water control location at the Palneavaie Purification Plant la located 8,6 miles west of the plant Ths current In Lake Erie flows in the easterly direction toward Niagara Falls. Additionally, the Grand River discharges to the lake between the plant and the new location, further limiting any Influence the plant may have on this new control location. The new water control location meets the
No. 17-02381 REGULATORY APPLICABILITY DETERMINATION Ray. 00 NOP-LP-40034)1 Rev. 04 Page 6 of 6 Initiating Activity No.
Procedure CHKJDCM Rev. 21 D BVPS1 DBVP82 DDBNPS PNPP requirements of Rag. GuWe 121, NUREG-1302 (GL 89-01), the Environmental Rtport, and tha ODCM. This change haa no adverae effect on compliance with Technical Speciflcatlona 6.6.1 or 6,6.4.
~~30. Table 5.1 -1: removed location 6$ and added new location 66.~~
Location 66, Major Stream Mouth, for sediment collection became Inaccessible In July of 2014 due to shoreline erosion.
Location 66, Laksshore Metropark Reservation, was Identified aa a replacement location for tha Major Stream sediment location after It became Inaccessible. The Lakeshore Metropatfc Reservation location to an acceptable replacement for the lost Major Stream sediment sampling location. Table 3.12.1-13.0 requires one sample from an area with existing or potential recreational value for shoreline sedlmsnt The Lakeshore Mstropark Reservstion la downstream of the influence of the plant and haa recreational significance because It is a public beach.
The now Sediment location meets tha requirements of Reg. Guide 1.21, NUREG-1302 (GL 89-01), tha Environmental Report, and the ODCM. This change haa no adverse affect on compliance with Technical Specifications 5.6.1 or 8,64.
31. Table 3.12.1-1: reduced number samples of fish species required for commercially and recreatlonalry Important species from two samples of aach species to one sample of each species In both areaa affected and unaffected by the plant discharge.
Updated to be consistent with wording In NUREG-1302, which states, "One sample of each commercially and recreationalty important species In vicinity of plant discharge area" and "One aampla of same species In areaa not Influenced by plant discharge**. Thla change removes an administrative burden which required two samples of aach speciee. One sample of aach commercially and recreanonally Important fish species Is an adequate sample stae for performance of required laboratory analyses. This change removes extra sampling that Is not required to comply with NUREG-1302. This change haa no adverse effect on compliance with Rag, Guide 1.21, NUREG-1302 (GL 89-01), 10 CFR 20.1302,40 CFR Part 190,10 CFR 60.36a, the Environmental Report, or 10 CFR 60 Appendix I. Thla change haa no adverse effect on compliance with Technical Specifications 8.6.1 or 5.5.4.
~~32. Table 3.12.1-1 Section 3.b; revised sampling frequency from "one sample in season" to "One sample In season or eemlannually If they art not seasonal."~~
Updated to be consistent wtth wording In NUREG-1302, which states, "Sample In season, or semlannually If they are not seasonal". The fish which follow seasonal migratory patterns In the lake are not always present and can only be caught when in season, hence em aampla In season, Thla change Imposes more restrictive requirements for obtaining samples eemfannuafly for flsh which are not seasonal. This change has no advene effect on compliance wtth Reg. Guide 1.21, NUREG-1302 (GL 69-01), 10 CFR 20.1302,40 CFR Part 190,10 CFR 60.36a, tha Environmental Report, or 10 CFR 60 Appendix I. This change haa no adverse effect on compliance with Technical Specifications 8.6.1 or 6.6.4.
items 24 through 32 described in the "Brief Description Of Activity" have been reviewed against tha Other Regulations listed above and are in complleance with the requrelments of those regulations. No further evaluation Is necessary for these changes Preparer (Print name) Date Gehring-Ohrablo, Krtstlne M. 10/9/2017 Reviewer (Print name) Date Bates, Carl Signature Date Database updated
Procedure Number PERRY NUCLEAR POWER PLANT REC-0107 rule: Use Category:
Control of the Offsite Dose Calculation Manual General Skill Reference Revision: Page:
2 8of9 ATTACHMENT 1: ODCM CHANGE DETERMINATION Page 1 of2 Description of Changes:
Provide a description of each change with sufficient information to support each change together with appropriate analyses or evaluations Justifying the change(s)
Description of Change see Justification for Change Description of Change Justification for Change (Add additional as necessary to address each change.)
Change Determination:
For each question, provide sufficient information for an informed reviewer to arrive at the same conclusion. W\ tfUd Does the proposed change maintain the level of radioactive effluent control reouired bv 10 CFR 20.1302? (Compliance with dose Bmrts for individual members of the public, where annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the unrestricted area do not exceed the values specified in Table 2 of Appendix B Part 20.)
ElYes No B. Does the proposed change maintain the level of radioactive effluent control required bv 40 CFR 190? (Total dose uranium fuel cycle - less than or equal to 25 mrem total body or any organ, or less than or equal to 75 mrem thyroid.)
Yes No Does the proposed chanae maintain the level of radioactive effluent control required bv 10 CFR 50.36a? (Technical Specifications on effluents from nuclear power reactors, where the Offsite Dose Calculation Manual is the document where the effluent controls are specified, and all the requirements of this regulation are demonstrated.)
Yes No
Procedure Number PERRY NUCLEAR POWER PLANT REC-0107 Tffle: Use Category:
Control of the Offsite Dose Calculation Manual General Skill Reference Revision: Pipe 2 9of9 ATTACHMENT A: ODCM CHANGE DETERMINATION Page 2 of 2 D. Doaa the proposed chanoe maintain the level of radioactive effluent control required by 10 CFR 50. Appendix I? (Numerical guides for design objectives and limiting conditions for operation to meet the criterion "as low as reasonably achievable," for radioactive material in llght-¥rateH>>oJed nuclear power reactor effluents, fists the annual dose commitments to unrestricted areas for liquid and gaseous effluents.)
Yes No calculations?
Yes No F.
calculations?
The changes have no effect on the accuracy or reliability of dose calculations. TherefoiB they do not adversely impact the accuracy or reliability of effluent calculations.
G.
calculations?
Yes No
~~Conclusion:~~
Will the change(8) to the ODCM maintain the level of radioactive effluent control raqulr by regulation as required by of Technical Specification 5.5.1(a)?
Yes No MfxaUv- Date: f&Uy?-l H
ODCM Rev. 21 Justification of Changes:
~~1. Commitment L02211 was dosed and removed from:~~
Introduction, paragraph 6 Table 3.3.7.9-1.3.C.2 Table 3.3.7.10-15.8 Table 3.3.7.10-1.4.a Table 3.3.7.10-1, action note 122 Controls section 3.112.4 under the description and footnote Commitment was closed
~~2. Commitment R00449 was closed and removed from Table 4.11.1.1.1-1 .B under the grab sample composite Commitment was closed~~
~~3. Added clarification of a vaM alert alarm in 3.1 note a Added clarification of need for a valid alert alarm before sampling~~
4. Combined note in calculation 3.1-4 with the definition T and added note to reference table 3.1-2 Editorial change for clarity 5 Formalized table of Effluent Release Path flow rates listed under section 3.1.4 equation definitions, creating Table 3.1-2 and added table to List of Tables Administrative change to give table official table title for easier reference.
6 Section 4.2: Removed requirement that specified that environmental TLDs will be changed out quarterly and annually. Now section contains a reference to Table 3.12-1, Radiological Environmental Change ensures only one location in the ODCM that specifies monitoring frequency; removes annual TLD replacement (not required per Table 3.12-1). Per NUREG-1302, only the quarterly TLD analysis is required.
7 Section 5.1: Removed reference to site-specific environmental monitoring procedures.
REMP-0013 should reference the ODCM as the governing document. The procedure lists locations in addition to those required by the ODCM and therefore, should not be referenced in the ODCM as a required list.
8 Table S1-1: shortened title; renamed location 53 to reflect current status; added new locations 16,20, 39,57 and 66; removed locations 18,28 and 65; Indicated that locations 36 and 3© are drinking water and locations 50 and 60 are surface water samples; changed "Food Products" to "Broadleaf Updated to reflect current'locatlons (location 53 lists address rather than facility name); title changes made to better specify water and food types Removed locations:
18 Kijauskas Farm: milking goat died (refer to TAF 15-009), owners also chose to discontinue participation in the broadleaf vegetable portion of the program. This location was not replaced. Table 3.12.1-1 Ac states that only two different offslte locations are required. Tnere are still two indicator locations as well as a control.
~~28 Ashtabula Plant: plant was closed in 2015, at which time water collection was terminated (refer to TAF 15-004)~~
~~65 Major Stream: The access point for sediment collection became inaccessible in July ot 2014 as the shoreline eroded. This issue is documented in REMP-0013.~~
~~New locations:~~
~~16 Eubank Garden: Food product sampling required In south sector, which is the second-highest D/Q sector, per Table 3.12,1-1 section 4c Refer to TAF17-004~~
~~20 Rainbow Farms: Food product sampling required in east sector, which is flu* highest D/Q sector, per Table 3.12.1-1 section 4.0, Refer to TAF 17-054~~
39 Painesville Plant When the control drinking/surface water location, Ashtabula Plant, ctosedt ft was replaced with the Painesville Purification Plant which is outside of the Influence of PNPP (refer to TAF 1S-004).
~~57 Perry High School: The TLD at this location was added when the old school on Center Rd.~~
was demolished and new school established. TLDs should be placed 'in special Interest areas" .'such as schools11 according to Table 3.12.1-11. The TLD at on Center Rd. remains in the program (location 55) due to historical data collection and it is still recreatiooally significant since there is now a football and soccer field in the vidnrty. Location 57 was inadvertently never added to the ODCM, but is documented in REMP-0013.
66 Lakeshore Reservation: When the major stream sediment location became inaccessible, it was replaced with the Lakeshore Metropark location, which is sufficient because it is also downstream of the influence of the plant and has recreational significance (as required by Table 3.12.1-1.3.C) because ft is a pubfc beach.
~~9. Figures 6.1-1, 5.1-2, and 5.1-3: Updated maps to reflect changed sample locations Reference change #8~~
~~10. Revised Table A-2: added a new column showing distance in meters The column displaying distance in meters was added because the dispersion and deposition calculations use meter unite~~
~~11. Tables &&7.1CM and 4.3.7.10: Table Notations. Removed ""During main condenser off-gas treatment system operation."There are no double asterisks In the tables.~~
Correction not previously changed; Previous revisions show no double asterisk notation in the table either. Thismay have been inadvertently copied from NUREQ-13G2, which also lists the footnote without any notations in the tables.
12. Table 3.3.7.10-1: Added action 124 to Unit 1 Vent noble gas channel during modes 4 and 5 Correction to table not previously changed; Unit 1 vent still has a source term during modes 4 and § from the spent fuel pool. If the annunciator downscale alarm locks in, action 124 is applicable in all modes, not just 1,2, and 3.
~~13. table 3.3X10-1: Removed footnote (1) from each page and added it to the notations portion Editorial correction~~
~~14. Table 3.12.1-1: Changed numberof TLDs to 29.~~
~~Reference change #8, added TLD at Perry High School~~
15. Table 3.12.1-1: modified wording to state that one species of each commerdaly or recreationalty important fish win be collected; changed sampling frequency to semtannuaHy In section 3.b Updated for consistency with wording in NUREG 1302, which states, "One sample of each commercially and recreationally important species in vicinity of plant discharge area* and "One sample of same species in areas not influenced by plant discharge"
~~16. Table 4.3.7.9-1.3: Updated NBS reference to NIST Correction not previously changed~~
17. Revised Section 6.9.1.7: moved the information denoted by an asterisk regarding maintaining the meteorological report separate from the Annual Report (nto paragraph b; spilt the paragraph into two for clarity purposes.
Changed for clarification of how the met report will be distributed, it was requested to be changed by the NRC to clarify that we will retain the met data report and distribute as requested, but it will not be submitted each year.
18. Removed asterisk and footnote from second page of section 6.9.1.7 When table was updated in previous revisions, the asterisk was not removed. The asterisk on the second page, "Licensee may choose to submit the information called for in this Control as part of the annual USAR update", applied to section 6.15 Major Changes to Radioactive Waste Treatment System. In revision 19, section 6.15 stared on the same page as the end of section 6.9.1.7. With revision 20, pagination was changed to start section 6.15 on a separate page. The footnote was inadvertently not removed from the previous page, but was correctly carried on with section 6.15.
~~19. Added new section for commitments Section was previously missing~~
~~20. Minor editorial and grammatical corrections, revision bars not used Editorial corrections~~

L-18-127, Annual Environmental and Effluent Release Report

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L-18-127, Annual Environmental and Effluent Release Report

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