Text

Annual Radioactive Effluent Release Rept for Period Jan-Dec 1995
	ML20101M623
Person / Time
Site:	Fermi
Issue date:	12/31/1995
From:	Gibson D; DETROIT EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	CON-NRC-96-0025, CON-NRC-96-25 NUDOCS 9604080025
	Download: ML20101M623 (237)
	v • d • e

Doughs R. G6pson Senior Vice Pres. dent Nuclear Generat on Detroit r.-

6400 North Dive Highway Edison ~~-

~(313)586-5249 March 29,1996 NRC-96-0025 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Appendix A, Facility Operating License No.

NPF-43, Technical Specification 6.9.1.8 and 6.14.2 I

Subject:

Annual Radioactive Effluent Release Report The Annual Radioactive Efiluent Release Report for Fermi 2 is attached. This !

report is being transmitted in accordance with Reference 2 and Regulatory Guide l I

L21, Revision 1. The attached report covers the period from January 1 through December 31,1995.

Please direct any questions or requests for additional information to Lynda Craine Supervisor, Radiological Health, at (313) 586-1388.

1 Sincerely, ,

Ah7 C Enclosure ec: T. G. Colburn M. J. Jordan H. J. Miller T. Vegel Region m 9604080025 951231 PDR ADOCK 05000341 050120 h R PDR \\

l FERMI 2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 l l l l l l

l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT for the period of January 1,1995 through December 31,1995 l 1

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1995 Annual R:dicactiva Effluent Release Report TABLE OF CONTENTS TABLE OF CONTENTS 1

SUMMARY

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1. INTRODUCTION 5

2. REGULATORY LIMITS 6 A. Gaseous Effluents 6 B. Liquid Effluents 7

3. AVERAGE ENERGY 7

4. MEASUREMENTS AND APPROXIMATIONS OFTOTAL ACTIVITY 7 A. Gaseous Effluents 8

1. Fission and Activation Gases 8

11. Radioiodines 8 lli. Particulates 9 IV. Tritium 9 V. Gross Alpha 10 B. Liquid Effluents 10

1. Fission and Activation Products 10

11. Tritium 11 111. Dissolved and Entrained Gases 11 IV. Gross Alpha 12

5. ABNORMAL RELEASES 12

6. BATCH RELEASES 12

7. LIQUID EFFLUENT

SUMMARY

13

8. GASEOUS EFFLUENT

SUMMARY

13 A. Fission and Activation Gases g 13 B. Radiciodines 13 C. Particulates 13 D. Tritium 14 E. Particulates: Totals for Each Nuclide Released (curies) 14 F. Fission and Activation Gases: Total Each Nuclide Released (curies) 14 G. lodines: Summary for Each Nuclide Released (curies) 15

9. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 15 A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel): 15 B. Irradiated Fuel Shipments 19

10. RADIOLOGICAL IMPACT ON THE PUBLIC 19 A. Dose Due to Liquid Effluents 19 B. Dose Due to Gaseous Effluents 19 C. Dose Due to Direct Radiation and Compliance with 40CFR190 20 D. Dose to Members of the Public on Site due to Effluents 20 Page 1

1995 Annu21 Radi: ctiva Effluent Release Report E. Population Dose 21 F. Site Boundary Air Dose 21

11. RADIATION INSTRUMENTATION 22

12. METEOROLOGICAL DATA

SUMMARY

22

13. CHANGES TO DOSE CALCULATION AND ENVIRONMENTAL MONITORING LOCATIONS 22

14. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) 22

15. MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS 23

16. LIQUID HOLDUP TANKS EXCEEDING LIMITS 23 Appendix A: Meteorological Data Tables Appendix B: Changes to Offsite Dose Calculation Manual i

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l 1995 Annu 1 Ridinctiva Effluent Release Report

SUMMARY

The Fermi 2 Nuclear Power Plant maintains a comprehensive program of monitoring and controlling the release of radioactive material from the site. The releases covered in this report are of three types: liquid releases, gaseous releases, and radioactive waste shipments. j i

in a liquid release, a tank containing radioactive water is sampled for analysis l prior to release. Based on the results of the analysis, the amount of radioactivity '

in the tank is calculated. Then based on this amount of radioactivity, the potential ;

radiation doce to a member of the public is calculated. Conservative assumptions are used in calculating the radiation dose. For example, it is assumed that an 1 individual eats 46 pounds of fish per year from Lake Erie caught directly offshore of the Fermi 2 plant discharge point. Both the amount of radioactivity in the tank and the potential radiation dose are compared to federal limits. l l

The tank will be released only after it is determined that federal limits are not i exceeded. The contents of the tank are diluted by clean water (from the circulating water decant line) as the tank is released in a ratio of approximately 400 gallons of clean water to one gallon of tank water for tanks located in the Radwaste Building basement (the normal release pathway).

Fermi 2 is continuing to work toward minimizing or eliminating liquid releases. As a result of these efforts, there were no liquid effluent releases in 1995.

Radioactive gaseous releases occur as part of the normal operation of Fermi 2.

There are six ventilation system release points, or " stacks", each of which is monitored by a sophisticated and sensitive radiation monitor which continuously ,

extracts a sample from the stack effluent. Since any gaseous radioactive I material is diluted by the building ventilation air flow, the stack concentrations are small. In fact, radioactive material is not detected in most stack samples. All i sample results are compared with federal limits to ensure they are not exceeded. l If the amount of radioactivity in the effluent of any stack approaches a federal !

limit, an alarm will be activated in the Fermi 2 control room to alert operations i personnel. After evaluating the situation, the operators may choose to order ,

increased sampling, shut down building ventilation, or, in the case of the reactor !

building ventilation system, divert the effluent stream to a special gaseous treatment system so that federal limits are not exceeded.

l in 1995, the amount of lodine-131 and particulate radionuclides with half lives greater than 8 days in gaseous releases was 0.0026 curies. The amount of noble gases released in 1995 was 24 curies. These quantities are of the same order of magnitude as those seen in previous years of power operation.

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l 1995 Annu11 RIdiozctivs -

Effluent Release Report i

Estimated annual radiation doses due to gaseous effluents from Fermi 2 are f included in this report. Noble gas doses to air at the site boundary in 1995 were :

0.0070 mrad gamma and 0.0074 mrad beta. These doses are 0.070% and 0.037% of federallimits, respectively. Dose to the maximally exposed organ of 4 the maximally exposed individual due to 1-131,1-133, tritium, and particulates with i half lives greater than 8 days, was 0.016 mrem. This dose is 0.11% of the federal limit. ,

Radioactive shipments of solid waste from the Fermi 2 site consist of waste ;

generated during water treatment, radioactive trash, and irradiated components.

Federal regulations governing these shipments are extensive, and Fermi 2 complies with these regulations and with internal procedures. Shipment i destinations are either licensed burial sites or intermediate processing facilities. I Waste shipped to intermediate processing facilities is shipped directly from these !

facilities to licensed burial sites after processing.

In 1995, the Barnwell, S.C. burial facility was reopened to waste from Michigan ,

generators. This report provides information on shipments for final disposal i either from Fermi 2 directly to Barnwell, S.C., or shipments of Fermi 2 waste from ;

intermediate processing facilities to Bamwell, S.C. In 1995, there were 40 '

shipments from Fermi 2 to Barnwell, S.C., and 71 shipments from intermediate -{

processing facilities to Barnwell, S.C. j l

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1995 AnnuIl RIdi::ctiva !

Effluent Release Report

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1. INTRODUCTION The Detroit Edison Fermi 2 Nuclear Power Plant is designed and operated in l a manner which strictly controls and monitors the release of radioactive material to the environment in accordance with Nuclear Regulatory l Commission (NRC) and Detroit Edison Company requirements. This Annual Radioactive Effluent Release Report, for the January through December 1995 ,

period, is submitted in accordance with Fermi 2 Technical Specification '

6.9.1.8 and NRC Regulatory Guide 1.21. This report provides the following information required by those references:

A. Summation of the quantities of radioactive material (in the form of gases and liquids) released from the plant (Sections 7 and 8).

B. Summation of quantities of radioactive material contained in solid waste packaged and shipped for off-site disposal (Section 9). ;

C. Changes to the Offsite Dose Calculation Manual (ODCM) (Section 14).

D. A list and description of any unplanned releases of radioactive materials to !

unrestricted areas (Section 5). ;

E. A list of any new locations for dose calculation or environmental monitoring identified by the land use census (Section 13). j F. A list of effluent monitors which were inoperable for a period longer than ]

that specified in ODCM Controls 3.3.7.11 and 3.3.7.12, and an explanation "

of why the time limit was exceeded. (Section 11).

G. A description of events leading up to any liquid holdup tanks exceeding the I limit of Technical Specification 3.11.1.4 (Section 16).

H. A description of any major changes to radioactive waste treatment systems (Section 15).

l. An assessment of the radiological impact on the public in terms of dose due to liquid and gaseous effluents, both to the maximally exposed individual and to the population within a 50 mile radius of the plant (Section 10).

J. 'A summary of 1995 meteorological data (wind speed and wind direction for i different stability classes) which was used in calculating gaseous dispersion factors (Section 12). !

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1995 AnnuIl Ridinctivs Effluent Release Report

2. REGULATORY LIMITS The Nuclear Regulatory Commission limits on liquid and gaseous effluents are incorporated into the Fermi 2 Offsite Dose Calculation Manual. These limits prescribe the maximum doses and dose rates due to radioactive effluents resulting from normal operation of Fermi 2. The limits are defined in several ways to limit the overall impact on persons living near the plant. The limits are described in the following sections.

A. Gaseous Effluents l l

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1. Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following: I a) Noble gases i

Less than or equal to 500 mrem / year to the total body ;

Less than or equal to 3000 mrem / year to the skin :

b) lodir#131, lodine-133, tritium, and for all radionuclides in !

parthlate form with half lives greater than 8 days i Less than or equal to 1500 mrem / year to any organ. l II. Air dose due to noble gases to areas at and beyond the site boundary I shall be limited to the following: ;

a) Less than or equal to 5 mrad for gamma radiation Less than or equal to 10 mrad for beta radiation 4

- During any calendar quarter i

'l b) Less than or equal to 10 mrad for gamma radiation Less than or equal to 20 mrad for beta radiation

- During any calendar year Ill. Dose to a member of the public from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a) Less than or equal to 7.5 mrem to any organ

- During any calendar quarter b) Less than or equal to 15 mrem to any organ

- During any calendar year i

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1995 Annu;l Rrdisictiva Effluent Release Report B. Liquid Effluents l

l. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in Title 10 of the Code of Federal Regulations (10 CFR) Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by the Fermi 2 Offsite Dose Calculation Manual.

For dissolved or entrained noble gases, the concentration shall be )

limited to 2E-4 (.0002) microcuries/ml total activity. This limit is based j on the Xe-135 air submersion dose limit converted to an equivalent !

concentration in water as discussed in the International Commission on 1 Radiological Protection (ICRP) Publication 2.

II. 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:

a) Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ

- During any calendar quarter b) Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ

- During any calendar year

3. AVERAGE ENERGY The calculated site boundary dose rates for Fermi 2 are based on identification of individual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor. Average energy values are not used in these calculations, and therefore need not be reported.

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY As required by NRC Regulatory Guide 1.21, this section describes the methods used to measure the total radioactivity in effluent releases and to estimate the overall errors associated with these measurements. The effluent monitoring systems are described in Chapter 11.4 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR).

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A.~ Gaseous Effluents l

1. Fission and Activation Gases Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points and from ;

the Offgas Vent Pipe which carries the gland seal condenser exhaust, mechanical vacuum pump exhaust, and treated offgas streams. The Offgas Vent Pipe effluent is released through one of the six ventilation j exhaust points (the reactor building exhaust plenum). The fission and activation gases are quantified by gamma spectroscopy analysis of ;

periodic samples. '

The values reported in Section 8 are the sums of all fission and activation gases quantified at all monitored release points.

Considering the inherent variability in radiation measurement, the variabillty in effluent stream composition, and the uncertainties in !

effluent flow rate and instrument calibration, Detroit Edison estimates that the one sigma uncertainty of the fission and activation gas total !

release figures is plus or minus 30 percent. i l

11. Radiolodines Samples are obtained from each of the seven plant radiation monitors l which continuously monitor the six ventilation exhaust points. The .

radioiodines are entrained on charcoal and then quantified by gamma spectroscopy analysis. For each sample the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radioiodines. From the flow rate of the ventilation system a rate of release can be determined.

The values reported in Section 8 are the sums of all radioiodines quantified at all continuously monitored release points.

1 Considering the inherent variability in radiation measurements, the I variability in effluent stream composition, and the uncertainty in sample

' i and effluent flow rates, Detroit Edison estimates that the one sigma !

uncertainty of the total radioiodine release figures is plus or minus 17 percent.

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1995 Annu11 Ridimtiva Effluent Release Report lil. Particulates Samples are obtained from each of the seven plant effluent radiation monitors which continuously monitor the six ventilation exhaust points.

The particulates are collected on a filter and then quantified by gamma spectroscopy ana!ysis. For each sample, the duration of sampling and -

continuous flow rate through the filter are used in determining the concentration of particulates. From the flow rate of the ventilation ;

system a rate of release can be determined.- l Quarterly, the filters from each ventilation release point are composited and then radiochemically separated and analyzed for Strontium (Sr)- )

89/90 using various analytical methods. If found, these radionuclides are reported as total particulate activity. l The values reported in Section 8 are the sums of all particulates I quantified at all monitored release points. l Considering the inherent variability in radiation measurements, the ;

variability in effluent stream composition, and the uncertainties in instrument calibration and in sample and effluent flow rates, Detroit -

Edison estimates that the one sigma uncertainty of the total particulate !

release figures is plus or minus 16 percent.

IV. Tritium Samples are obtained for each of the seven plant effluent radiation monitors which continuously monitor the six ventilation exhaust points.

The sample is passed through a bottle containing water and the tritium is " washed" out to the collecting water. Portions of the collecting water are analyzed for tritium using liquid scintillation counting techniques.

For each sample, the duration of sample and sample flow rate is used to determine the concentration. From the flow rate of the ventilation l system a release rate can be determined.

The values reported in Section 8 are the sums of all tritium quantified at all monitored release points.

Considering the inherent variability in radiation measurement, the variability in effluent stream composition, and the uncertainties in instrument calibration, sample and effluent flow rates, and collection efficiency, Detroit Edison estimates that the one sigma uncertainty of the total gaseous tritium release figures is plus or minus 30 percent.

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1935 Annu 1 Rsdinctiva Effluent Release Report V. Gross Alpha The gaseous padiculate filters from the seven plant effluent radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters. These filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate.

The values reported in Section 8 are the sums of all alpha emitters quantified at all monitored release points.

Considering the inherent variability in radiation measurements, the variability in effluent stream composition, and the uncertainties in instrument calibration and in sample and effluent flow rates, Detroit Edison estimates that the one sigma uncertainty of the total gaseous gross alpha release figures is plus or minus 16 percent.

B. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFSAR. Since Fermi 2 released no radioactive liquid effluents in 1995, the liquid effluent monitoring activities described below were not performed in 1995.

l. Fission and Activation Products Before the contents of each holding tank are discharged to the environment, a representative sample of the tank's contents is taken and retained. The sample allows for the determination of radioactive material concentrations and establishes the rate at which the radioactive material can be discharged to the environment.

At the end of the calendar quarter a composite sample is made of all discharge samples taken during the quarter. This composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The composite sample is analyzed for Iron !

(Fe)-55 and Strontium (Sr)-89/90. Radiochemical separations and ;

various analytical methods are used to quantify the amounts of Sr-89/90 and Fe-55.

The values reported in Section 7 are the sums of all fission and activation products found in all batch releases. Also reported in Page 10

1995 Annu;l RIdiscctiva Effluent Release Report {

~ Section 7 are the pre-dilution waste volume (the total volume of liquid !

waste tanks released), the post-dilution waste volume (the total tank -

volume released plus the volume of circulating water released while the tanks were being released), and the total dilution volume discharged (the total volume of circulating water released during the reporting period). .

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Considering the inherent variability in radiation measurement and the uncertainties in volume measurements and instrument calibration, !

Detroit Edison estimates that the one sigma uncertainty in total liquid fission and activation product release figures is plus or minus 15 i percent. .

11. Tritium !

Before the contents of each holding tank are discharged to the ,

environment, a representative sample of the tank contents is taken and

- retained. At the end of the calendar _ month a composite sample is made of all discharge samples taken during the month. This composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The composite sample is analyzed for tritium by liquid scintillation counting. ,

The values reported in Section 7 are the sums of all tritium quantified from all batch releases.

Considering the inherent variability in radiation measurement and the uncertainties in volume measurement and instrument calibration, Detroit Edison estimates that the one sigma uncertainty in total tritium release figures is plus or minus 7 percent. .

111. Dissolved and Entrained Gases Prior to releasing liquid radioactive waste to the environment, a sample is taken from the radwaste holding tank. This sample is representative of the tank's contents. The sample is examined using gamma spectroscopy to determine the concentration of dissolved and entrained noble gases.

The values reported in Section 7 are the sums of all radioactive gases found for all batch releases.

Considering the inherent variability in radiation measurement and the uncertainties in instrument calibration and volume measurements, Page 11

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1995 Annual Ridl=ctiva Effluent Release Report Detroit Edison estimates that the one sigma uncertainty in total dissolved and entrained gas release figures is plus or minus 33 percent.

IV. Gross Alpha Before the contents of each holding tank are discharged to the environment, a representative sample of the tank's contents is taken and retained. At the end of the calendar month a composite sample is made of all discharge samples taken during the month. This composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The composite sample is analyzed for gross alpna radioactivity by gas proportional counting.

The values reported in Section 7 are the sums of the gross alpha radioactivity from all batch releases.

Considering the inherent variability in radiation measurement and the uncertainty in volume measurements and instrument calibration, Detroit Edison estimates that the one sigma uncertainty in total liquid gross alpha release figures is plus or minus 54 percent.

5. ABNORMAL RELEASES For the purpose of this report, an abnormal release is any release of radioactive material not performed in accordance with the Fermi 2 license and implementing procedures. No abnormal releases occurred during this ,

reporting period. ;

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6. BATCH RELEASES During this reporting period, January 1,1995, through December 31,1995, I

there were no liquid batch releases from Fermi 2. '

The only batch gaseous releases from Fermi 2 are the venting or purging of the primary containment (drywell or torus) atmosphere. These venting or purging releases pass through the reactor building ventilation or standby gas treatment system and are monitored by the final effluent monitors for these pathways. Separate data on these venting or purging releases are not reported because the associated data are already included in the gaseous effluent release data (Section 8). The amount of radioactive material released during venting and purging has been a small fraction of the amount released as continuous gaseous effluents.

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1995 Annual Radioactivo Effluent Release Report i

7. LIQUID EFFLUENT

SUMMARY

There were no liquid effluents from Fermi 2 in 1995.

8. GASEOUS EFFLUENT

SUMMARY

(Mixed mode releases as defined in NRC Regulatory Guide 1.111)

A. Fission and Activation Gases i

l Total Release l 6.24E+00 l 7.57E+00 l 3.45E+00 6.74E+00 (curies) l l l .

Average Release 8.02E-01 9.63E-01 4.34E-01 8.48E-01 !

Rate for Period (pCi/sec) i l

B. Radiolodines Total 1-131 5.48E-05 3.82E-04 3.38E-04 4.13E-04 l (curies) l Average Release 7.05E-06 4.86E-05 4.25E-05 5.20E-05 Rate for Period (pCi/sec)

C. Particulates Particulates with 1.94E-05 3.08E-04 8.12E-04 2.73E-04 half lives > 8 days (curies)

Average 2.49E-06 3.92E-05 1.02E-04 3.43E-05 l Release Rate for Period (pCi/sec)

Gross Alpha 1.02E-06 1.71 E-06 1.25E-06 1.48E-06 1 Radioactivity l (curies)

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1995 Annual Radiorctiva Effluent Release Report D. Tritium il Total Release ) *<4.2E-08 } *<4.2 E-08 ll *<4.2E-08 l *<4.2 E-08 ll E. Particulates: Totals for Each Nuclide Released (curies) l Cr-51 ll *<2.5E-13 l 2.67E-04 ll 7.89E-04 ll 2.61 E-04 l Mn-54 l *<4.8E-14 l 1.51 E-06 l 1.36E-06 l *<4.8E-14 l Co-58 l *<5.8E-14 l 6.35E-06 l 9.31 E-07 l *<5.8E-14 l Co-60 l 8.89E-06 l 1.62E-05 l 9.06E-06 l 1.17E-06 l Na 24 l *<1.2E-12 l 5.33E-05 l *<1.2E-12 l *<1.2E-12 l Tc-99m l 4.90E-05 l 5.03E-04 l 1.26E-03 l 5.48E-04 l Ba-139 l 1.29E-02 l 2.51 E-02 l 2.30E-02 l 1.31 E-02 _

l La-140 l *<4.0E-13 l 1.67E-05 l 1.75E-05 l *<4.0E-13 l Y-91 m l 9.03E-04 l 5.44E-03 l 5.74E-03 l 1.04E-03 l Sr-91 l *<2.2E-12 l 1.00E-04 l 8.52E-05 l *<2.2E-12 l Rb-89 l *<1.7E-09 l *<1.7E-09 l 3.23E-03 l *<1.7E-09 l Cs-138 l 1.12E-02 l 4.65E-03 l 1.01 E-02 l 3.00E-03 l Br-82 l *<2.4 E-13 l 8.12E-06 l 6.12E-05 l 4.73E-05 l Sr-89 l 1.05E-05 l 1.72E-05 l 1.12E-05 l 1.13E-05 l Sr-90 l *<3.0E-16 l 8.40E-08 l 1.02E-07 l *<3.0E-16 l Cs-134 l *<4.2E-14 l *<4.2E-14 l *<4.2E-14 l *<4.2E-14 l Cs-137 l *<5.0E-14 l *<5.0E-14 l *<5.0E-14 l *<5.0E-14 l Ce-141 l *<3.9E-14 l *<3.9E-14 l *<3.9E-14 l 1.38E-06 l Ce-143 l 8.33E-06 l *<2.2E-13 l *<2.2E-13 l *<2.2E-13 l Ce-144 l *<1.3E-13 l *<1.3E-13 l *<1.3E-13 l *<.1.3E-13 l Total l 2.51 E-02 l 3.62E-02 l 4.43E-02 l 1.8E-02 F. Fission and Activation Gases: Total Each Nuclide Released (curies) l Kr-87 ll *<5.3E-08 ll *<5.3E-08 ll *<5.3E-08 ll 3.02E 31 ]

l Kr-89 l *<3.2 E-07 l 3.48E+00 l *<3.2E-07 l * <3.2 E. -07 l l Xe-135 l *<3.0E-08 l *<3.0E-08 l *<3.0E-08 l 1.81 E-01 l l Xe-135m l 4.52E-01 l 5.87E-01 l 1.38E+00 l 1.68E+00 l l Xe-137 l 4.64E+00 l 2.73E+00 l *<4.3E-07 l *<4.3 E-07 l l Xe-138 l 1.15E+00 l 7.73E-01 l 2.07E+00 l 4.58E+00 l l Total l 6.24E+00 l 7.57E+00 l 3.45E+00 l 6.74E+00 l Page 14

1995 Annut! Radio:ctiva Effluent Release Report G. lodines: Summary for Each Nuclide Released (curies)

I l-131 ll 5.48E-05 0 3.82E-04 ll 3.38E-04 ll 4.13E-04 l-l l-132 l 9.64E-05 l 5.90E-04 l 1.01 E-03 l 6.33E-04 l l l-133 l 2.91 E-04 l 1.87E-03 l 2.07E-03 l 1.40E-03 l l l-134 l *<3.6E-11 l *<3.6E-11 l *<3.6E-11 l 4.07E-04 l l l-135 l *<6.4E-12 l 1.40E-03 l 2.23E-03 l 1.08E-03 l l Total l 4.42E-04 l 4.24E-03 l 5.65E-03 l 3.93E-03 l Less than the Lower Limit of Detection (LLD), i.e. the maximum sensitivity of measurement, in units of microcuries per milliliter ( Ci/ml).

9. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel):

a. Spent resins, filter sludges, etc. m" 2.85E+02 125 curies 1.02E+03

b. Dry compressible waste, l m" 4.87E+01 l 125 contaminated equipment, etc. curies 6.91 E+00 l 0 l l c. Irradiated control rods, components, etc. li l l d. Other l 0 l l

2. Estimate of major nuclide composition (by class of waste)

a. Spent resins, filter sludges, etc. (Total of Class A, Class B, and Class C waste: All waste in this category was shipped in High Integrity Containers and consisted of dewatered resins. No solidification agent or absorbent was used in processing waste in this category. All quantities were determined by measuremer't.)

ll Ag-110m ll <0.1 ll 9.01 E-02 ll l Ba-133 l <0.1 l 2.02E-01 l l Ba-140 l <0.1 l 1.58E-04 l l C-14 l 2.2 l 2.24E+01 l l Ce-144 l <0.1 l 5.48E-01 l l Co-57 l <0.1 l 3.67E-02 l Page 15

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i 1995 Annuri R dicactiva Effluent Release Report J

l Co-58 0 0.3 ll 3.24E+00 ll 1 l Co-60 l 40.9 l 4.17E+02 l l Cr-51 l 0.5 l 4.96E+00 l l

l Cs-134 l 1.6 l 1.63E+01 l l Cs-137 l 3.0 l 3.09E+01 l l Fe-55 l 36.6 l 3.73E+02 l l Fe-59 l <0.1 l 7.26E-02 l l H-3 l 0.5 l 4.64E+00 l l Hf-181 l <0.1 l 3.77E-02 l l l-129 l <0.1 l 8.47E-02 l l l-131 l <0.1 l 1.49E-04 l l Mn-54 l 4.6 l 4.71 E+01 l l Nb-95 l <0.1 l 1.64E-02 l l Ni-59 l <0.1 l 1.47E-01 l l Ni-63 l 7.3 l 7.49E+01 l l Sb-125 l 0.2 l 1.69E+00 l l Sr-90 l <0.1 l 2.54E-02 l l Tc-99 l <0.1 l 6.16E-01 l l Zn-65 l 2.1 l 2.18E+01 l Note: The following is a breakdown of the above quantities into Class A, Class B, and Class C waste.

1) Class A dewatered resin (total volume: 254 m )

L Ag-110m O <0.1 4 9.01 E-02 ll l l Ba-133 l <0.1 l 1.75E-01 l l Ba-140 l <0.1 l 1.58E-04 l l C-14 l 2.1 l 1.30E+01 l l Ce-144 l <0.1 l 5.19E-01 l l Co-57 l <0.1 l 5.10E-03 l l Co-58 l 0.5 l 3.23E+00 l l Co-60 l 43.3 l 2.62E+02 l l Cr-51 l 0.8 l 4.96E+00 l l Cs-134 l 0.7 l 4.00E+00 l l Cs-137 l 1.2 l 7.19E+00 l l Fe-55 l 40.8 l 2.47E+02 l l Fe-59 l <0.1 l 7.26E-02 l l H-3 l 0.7 l 4.21 E+00 l l l Hf-181 l <0.1 l 3.77E-02 l l l-129 l <0.1 l 5.48E-02 l l l-131 l <0.1 l 1.49E-04 l Page 16

I 1995 Annuti R:diccctivo Effluent Release Report Mn-54 { 4.7 ll 2.82E+01 h l Nb-95 l <0.1 l 1.64E-02 l l Ni-59 l <0.1 l 1.13E-01 l l Ni-63 l 3.0 l 1.83E+01 l l Sb-125 l 0.3 l 1.69E+00 l l Sr-90 l <0.1 l 1.98E-02 l l Tc-99 l <0.1 l 2.93E-01 l l Zn-65 l 1.7 l 1.02E+01 l

2) Class B dewatered resin (total volume: 21 m )

l Ag-110m ll <0.1 ll 1.38E-05 ll l Ba-133 l <0.1 l 2.70E-02 l l C-14 l 1.9 l 5.03E+00 l l Ce-144 l <0.1 l 2.85E-02 l l Co-57 l <0.1 l 1.16E-02 l l Co-58 l <0.1 l 1.21 E-02 l l Co-60 l 32.2 l 8.50E+01 l l Cs-134 l 3.6 l 9.48E+00 l l Cs-137 l 7.1 l 1.87E+01 l l Fe-55 l 28.9 l 7.62E+01 l l H-3 l <0.1 l 1.79E-01 l l l-129 l <0.1 l 1.19E-02 l l Mn-54 l 3.8 l 9.91 E +00 l l Ni-59 l <0.1 l 3.44E-02 l l Ni-63 l 20.3 l 5.37E+01 l l Sr-90 l <0.1 l 1.50E-03 l l Tc-99 l <0.1 l 1.73E-01 l l Zn-65 l 2.1 l 5.56E+00 l

3) Class C dewatered resin (total volume: 10 m )

ll Ag-110m ll <0.1 ll 1.85E-05 l C-14 l 2.9 l 4.35E+00 l Ce-144 l <0.1 l 6.73E-04 l Co-57 l <0.1 l 2.00E-02 l Co-60 l 46.6 l 7.01 E+01 -

l Cs-134 l 1.8 l 2.78E+00 l Cs-137 l 3.3 l 4.99E+00 l Fe-55 l 33.1 l 4.98E+01 l H-3 l 0.2 l 2.52E-01 Page 17

1995 Annuti Radiccctivo Effluent Release Report ll l-129 ll <0.1 k 1.80E-02 ll l Mn-54 l 6.0 l 9.02E+00 l Ni-59 l l <0.1 l 1.71 E-05 l l Ni-63 l 1.9 l 2.85E+00 l l Sr-90 l <0.1 l 4.09E-03 l l Tc-99 l <0.1 l 1.50E-01 l l Zn-65 l 4.0 l 6.01 E+00 l

b. Dry compressible waste, contaminated equipment, etc. (All waste in this category was Class A waste, was shipped in strong tight containers, and was classed as dry active waste (DAW). Some of this waste was solidified in concrete after incineration. All quantities were determined by measurement.)

il Ba-133 k <0.1 0 2.05E-04 [

l C-14 l 0.3 l 2.19E-02 l 4

l Ce-144 l <0.1 l 2.37E-05 l l Co-57 l <0.1 l 1.50E-06 l l C-58 l 0.2 l 1.32E-02 l l Co-60 l 9.5 l 6.59E-01 l l Cr-51 l 4.2 l 2.92E-01 l l Cs-134 l 5.7 l 3.92E-01 l l Cs-137 l 5.2 l 3.61 E-01 l l Fe-55 l 69.5 l 4.80E+00 l l Fe-59 l <0.1 l 1.75E-03 l l H-3 l <0.1 l 4.03E-04 l l l-129 l <0.1 l 7.15E-05 l l Mn-54 l 2.5 l 1.76E-01 l l Ni-59 l <0.1 l 1.63E-04 l l Ni-63 l 0.7 l 4.97E-02 l l Sb-124 l <0.1 l 1.89E-04 l l Sb-125 l <0.1 l 1.19E-03 l l Sr-90 l <0.1 l 5.90E-06 l l Tc-99 l <0.1 l 3.56E-04 l l Zn-65 l 2.0 l 1.37E-01 l

3. Solid Waste Disposition l Dry active waste l 71 l tractor trailor l Barnwell, SC l Page 18

1995 Annurl Ridir0tiva !

Effluent Release Report B. Irradiated Fuel Shipments No shipments in this reporting period.

10. RADIOLOGICAL IMPACT ON THE PUBLIC A. Dose Due to Liquid Effluents ;

1 As discussed in Section 6.5.1 of the Fermi 2 ODCM, compliance with l ODCM Control 3.11.1.2, which limits dose to a member of the public to any 1 organ and to the total body due to liquid effluents, is evaluated by calculating the dose to a hypothetical individual who both eats fish from Lake Erie and drinks water extracted from Lake Erie at the water intake for the city of Monroe. Conservative assumptions from Regulatory Guide 1.109 are made about the quantity of fish and water consumed. Since there were no liquid releases to Lake Erie in 1995, there was no dose due to liquid effluents in 1995.

1 B. Dose Due to Gaseous Effluents As discussed in Section 7.8.1 of the Fermi 2 ODCM, compliance with ODCM Control 3.11.2.3, which limits dose due to 1-131,1-133, H-3, and particulates with half lives greater than 8 days in gaseous effluents to any organ of a member of the public, is evaluated by calculating the dose to an individual in an age group which would receive the highest single organ dose of any member of the public. This individual is a child who is assumed to live at an offsite location which is known to have a garden based on the Land Use Census,. This child is assumed to eat food from this garden, and to also be exposed by the inhalation and ground plane pathways. The individual organ and total body doses to this individual due to 1-131,1-133, H-3, and particulates with half lives greater than 8 days were calculated according to Section 7.8.1 of the ODCM and are listed below.

Page 19

- -. . ..-- - .- - - - - - . = - - - .

! 1995 Annu 1 Ridinctiva Effluent Release Report i

i l

1 8.77E-04 mrem 3.91 E-04 mrem 1.59E-02 mrem i 4.21E-04 mrem l

3.50E-04 mrem l 3.80E-04 mrem l 3.98E-04 mrem l The highest single organ dose to the maximally exposed receptor, 1.59E-02 mrem to the thyroid, is 0.11% of the ODCM Control 3.11.2.3

annual dose limit (15 mrem).

C. Dose Due to Direct Radiation and Compliance with 40CFR190 1 Title 40, Part 190 of the Code of Federal Regulations requires that dose to j an individual in the unrestricted area from the uranium fuel cycle be limited to 25 mrem /yr to the total body and 75 mrem /yr to the thyroid. The sources of fuel cycle dose not analyzed above are due to other fuel cycle facilities and dose due to 6 rect radiation. As discussed in Section 8.2 of the Fermi 2 ODCM, no other fuel cycle facilities contribute significantly to j dose in the vicinity of Fermi 2. With respect to direct radiation, none of the

offsite TLD locations listed in Table 10.0-1 of the ODCM showed 1995 TLD l

readings which were consistently greater than the TLD readings at the control locations. Since other facilities and direct radiation did not contribute significantly to offsite dose, and since the preceding sections of i

this report show compliance with the more restrictive requirements of i

10CFR50 Appendix I, Fermi 2 was in compliance with 40CFR190 in 1995.

.? D. Dose to Members of the Public on Site due to Effluents l In 1995, members of the public received dose on site as visitors or as employees who were non-radiation workers. (In 1996, all site employees are considered to be radiation workers and none are defined as members of the public.) As discussed in Section 8.0 of the Fermi 2 ODCM, " visitors" to the Fermi 2 site may receive dose due to their activities within the site i boundary. For purposes of this analysis, visitors are members of the i public who spend time within the site boundary and who do not do work i associated with the operation of Fermi 2. The ODCM considers two categories of visitors: persons ice fishing on Lake Erie and persons Page 20

. _ _ . . _ _ . _ _ __....-_._._._.___._..______.____m 1995 Annu 1 Rr.disictiva ,

Effluent Release Report !

spending time in the Fermi 2 Visitors Center. In 1995, employees who .

were non-radiation workers were considered to have received dose as I members of the public from various activities and at various locations

.(other than radiation areas) on site.

Table 8.0-1 of the ODCM lists the maximum amount of time a member of !

the public is likely to spend on site, the likely locations of exposure, and i the effluent exposure pathways which apply. A visitor is assumed to spend : !

240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months per year ice fishing near the site or 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per year at the '

Visitors Center. In 1995, an employee was assumed to spend 2500 hours0.0289 days 0.694 hours 0.00413 weeks 9.5125e-4 months ,

per year on site at various locations. Exposure by immersion in noble i gases and by inhalation of radioactive particulates, lodines, and tritium are considered.' The doses given below do not include dose due to the pathways already considered in parts A and C of this section, namely dose ,

due to water ingestion from the Monroe water intake, fish ingestion, and ;

direct radiation. i Based on these assumptions, the maximum dose in 1995 to a visitor at the -

Visitors Center is 3.01E-06 mrem to total body and 4.10E-06 mrem to the maximally exposed organ (thyroid). The maximum dose in 1995 to an ice fisherman is 3.88E-04 mrem to the total body and 5.40E-04 mrem to the maximally exposed organ (thyroid). The maximum dose in 1995 to an employee (non-radiation worker) on site is 8.21E-03 mrem to the total body and 1.10E-02 mrem to the maximally exposed organ (thyroid).

E. Population Dose l l

Dose to the population within a fifty mile radius of Fermi 2 due to 1995 gaseous effluents was calculated.' There was no dose due to liquid effluents.

- For gaseous effluents, the code MICROAIRDOS was used to estimate the population dose. Inputs to the code were 1995 gaseous release data, wind direction and wind speed frequencies for each stability class, i population in each of 10 segments of each of 16 sectors, stack release l specifications, etc. The estimated 1995 collective effective dose due to l gaseous effluents is 300 mrem.

F. Site Boundary Air Dose ;

Gamma and beta dose to air at the site boundary due to noble gases must be calculated to evaluate compliance with ODCM Control 3.11.2.2. In 1995, gamma air dose was 6.96E-03 mrad and beta air dose was 7.44E-03 mrad. These doses represent 0.070% and 0.037% of the ODCM i

Page 21

-..m.-~ a.,y,- ,,-, .,r, ,,_,, c ,.9 - ,...g. , .-,eg9 w-- p-

1995 Annuri Ridimetivs Effluent Release Report Control 3.11.2.2 gamma and beta annual air dose limits, respectively.

(The gamma dose limit is 10 mrad and the beta dose limit is 20 mrad.)

11. RADIATION INSTRUMENTATION Fermi 2 ODCM Controls 3.3.7.11, Radioactive Liquid Effluent Monitoring Instrumentation, and 3.3.7.12, Radioactive Gaseous Effluent Monitoring Instrumentation, require that those monitors which exceed the time specified for out of service status be reported in the next Annual Effluent Release Report. In 1995, none of these monitors was out of service longer than the applicable time limit.

12. METEOROLOGICAL DATA

SUMMARY

The meteorological monitoring system is described in the Fermi 2 UFSAR.

In accordance with Regulatory Guide 1.21, data recorded by that system is l provided here to permit the NRC to assess the radiological impact of l Fermi 2 releases independently. The data format required by Regulatory '

Guide 1.21 is used. Appendix A contains the meteorological data tables.

Specifically, these are joint frequency tables of wind speed versus wind direction for each atmospheric stability class for the 10 meter monitoring .

level. These data were used to derive annual average dispersion and deposition factors.

13. CHANGES TO DOSE CALCULATION AND ENVIRONMENTAL MONITORING LOCATIONS During 1995, a drinking water sampling location at the onsite potable water plant was deleted because the site is no longer using this plant to provide potable water. Also during 1995, a new food product control location was established because the previous location dropped out of the program.

14. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

In August 1995, sections 0.0,3.0,7.0, and 10.0 of the ODCM were revised to clarify circulating water sampling requirements, synchronize actions to be taken during SPING (stationary particulate iodine noble gas) monitor inoperability, optimize sampling requirements for special plant conditions, revise environmental sampling locations, and make various minor correct:ons, in December 1995, all sections of the ODCM were revised to allow the ODCM to become part of the Technical Requirements Manual, to revise ODCM definitions to conform to 10CFR20 definition changes, to clarify actions to be taken when liquid effluent monitor flow rate devices are inoperable, to delete special dose analysis for employees previously Page 22

i l

1995 Annu 1 R:dl=ctiva '

Effluent Release Report considered to be members of the public, to delete references to an EPA environmental sample crosscheck program which has been discontinued, and to revise environmental sampling locations. Appendix B contains a ;

copy of the entire ODCM as approved in December 1995 with revision '

bars showing the August 1995 revisions and the December 1995 revisions.

These revisions were completed in accordance with Technical Specification section 6.14.2. Plant documentation supporting these revisions is also included in Appendix B.

15. MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS During 1995, there were no major changes to the liquid, gaseous, or solid radioactive waste treatment systems.

I

16. LIQUID HOLDUP TANKS EXCEEDING LIMITS l

Fermi 2 Technical Specification 3.11.1.4 requires that the quantity of radioactive material contained in any outside temporary tank shall be limited to 10 curies, excluding tritiu'm and dissolved or entrained noble gases. During this reporting period, January through December of 1995, this activity limit for such tanks was not exceeded.

End of Text I

I Page 23

1995 Annut! Radisictiva Effluent Release Report Appendix A: Meterological Data Tables

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Halliburton NUS Corporation Air / Radiological Programs Department PROGRAM: JFD VERSION: PC-1.2 PRINTOUT OF INPUT CONTROL DATA TITLE: DECO FERMI 2 JFD AT 10-METERS FOR 1995 8EGIN DATE: 95 1 1 1 END DATE: 95 12 31 24 OPit0N TO PRINT MONTHLY JFDS: NO OPTION TO PRINT SEASONAL JFDS: NO OPTION TO PRINT STABILITY BY HOUR OF DAY: NO OPil0N TO PLACE JFD IN FILE FORMATTED FOR PAVAN /XOQDOQ: YES OPTION TO USE 12 WIND SPEED CLASSES INPUTTED WIND SPEED CLASSES IN MPH : .75 2.50 4.50 6.50 8.50 11.50 14.50 18.50 23.50 30.50 39.50 .00 PRIMARY E ASUREMENTS BASED ON:

WIND SPEED E ASURED AT 10.0 METERS IN MPH SAD WIND SPEED DATA CODED: 999.90 WIND SPEED THRESHOLD: .75 MPH WIND DIRECTION MEASURED AT 10.0 METERS BAD WIND DIRECTION DATA CODED: 999.0 STABILITY 8ASED ON 1=A,2=8,...,7=G BAD STA8tLITY CODED: 9.0 8ACK-UP MEASUREMENTS BASED ON:

NO BACKUP WIND SPEED MEASUREMENTS NO BACKUP WIND DIRECTION MEASUREMENIS NO BACKUP STABILITT MEASUREMENTS WIND SPEED HEIGHT TO BE USED FOR JFD: 10.00 METERS CONVERSION FACTOR TO CONVERT SIGMA RANGE TO SIGMA THETA: 6.0 FORMAT TO READ INPUT DATA: (4I2,F5.1.F3.0,T27,F1.0,T55,A6,T11,A3 A3,T27,A1)

FIRST DATA RECORD READ: FERM12 95 1 1 1 4.1 23.0 4.0

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DATA PERIOD EXAMINED: 1/ 1/95 - 12/31/95 !

- - ANNUAL ***

STABILITY CLASS C STABILITY BASED ON 1=A,2=8,...,7=G WIIe MEASURED AT: 10.0 METERS WIND THRESNOLD AT: .75 MPM i JOINT FREGUENCY DISTRIOUTION OF WIND SPEED AND DIRECTION IN NOURS AT 10.00 METERS SPEED .

I (SPN) N NNE ME ENE E ESE SE SSE $ SSW SW WSW W WWW NW N4W TOTAL 0 [

CALM

.76- 2.50 0 0 0 0 0 1 1 2 0 1 0 2 2 0 0 0 9 2.51- 4.50 1 2 5 4 2 9 7 6 3 6 4 8 13 11 9 5 95 4.51- 6.50 12 4 8 7 4 16 19 11 18 8 17 15 31 19 to to 209 l 6.51- 8.50 8 9 11 5 13 18 30 19 11 9 14 13 18 8 7 10- 203 8.51-11.50 5 7 4 7 7 12 - 14 5 12 16 17 20 7 18 6 9 166 11.51-14.50 1 0 7 1 7 4 5 2 3 5 12 7 7 5 2 2 70 14.51-18.50 0 3 3 3 5 2 1 1 0 0 4 1 1 3 1 0 28 18.51-23.50 0 3 0 1 0 0 0 0 0 0 0 0 0 0 1 0 5 23.51-30.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,

4 30.51-39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .

e39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 27 28 38 28 38 62 77 46 47 45 68 66 79 64 36 36- 785 f i

STAOILITY CLASS D i STABILITY BASED ON 1=A,2=8,...,7=G t WIND MEASURED AT: 10.0 METERS !

WIND THRESNOLD AT: .75 MPH l JOINT FREGUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 10.00 METERS i

SPEED (MPN) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 3 !

.76- 2.50 10 4 6 8 7 1 4 5 5 5 11 12 14 17 -11 6 126 2.51- 4.50 34 31 17 20 35 18 28 16 27 23 55 64 66 50 43 27 554 5 4.51- 6.50 33 49 91 50 43 74 53 59 55 39 70 107 107 75 52 44 1001 l 6.51- 8.50 40 38 110 66 69 76 68 56 75 48 56 82 67 75 42 49 1017 :

8.51-11.50 32 35 58 73 46 56 58 56 69 80 107 105 63 41 30 39 948 !

11.51-14.50 14 14 42 20 29 14 31 23 28 34 88 17 14 13 15 20 416 14.51-18.50 8 7 2 9 21 1 to 4 7 8 48 2 2 6 2 0 137 18.51-23.50 4 0 0 0 4 0 2 2 0 2 0 0 0 0 0 0 14 23.51-30.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 30.51-39.50 0 0 0 0 0 0 0 0 -0 0 0 0 0 0 0 0 0 i e39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

'l TOTAL 175 178 326 246 254 240 254 221 266 239 435 389 333 277 195 185 4216 l

I- .- L- L _4 .s L.~ , .--s , _ , - _ _.4 .i ..

C:lliburton NUS Corpor6 tion Air /Rediologicci Programs Department PROGRAM: JFD VERSION: PC-1 DECO FERMt2 JFD AT 10-METERS FOR 1995 SITE IDENTIFIER: FERMI 2 -

DATA PERIOD EXAMINED: 1/ 1/95 - 12/31/95 ***

- - ANNUAL STABILITY CLASS E STABILITY BASED ON 1=A,2=8,...,7=G WIW IEASURED AT: 10.0 METERS WIW TMRESNOLD AT: .75 MPN JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECil04 IN HOURS AT 10.00 METERS SPEED (MPM) N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NWW TOTAL CALM 8

.76- 2.50 14 7 7 8 5 7 3 3 14 10 17 22 31 13 14 13 188 2.51- 4.50 31 36 20 11 20 17 17 19 40 30 90 110 73 57 70 30 671 4.51- 6.50 33 12 28 18 15 25 28 31 53 43 50 42 34 47 23 28 510 6.51- 8.50 5 9 20 7 5 14 16 34 37 50 30 22 13 17 3 8 290 8.51-11.50 0 to 4 4 10 8 17 35 34 50 18 9 9 6 2 6 222 11.51-14.50 0 2 2 4 4 0 2 5 12 11 2 2 2 1 3 3 55 14.51-18.50 0 0 0 0 1 0 0 2 0 4 1 0 0 0 0 0 8 18.51-23.50 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 23.51-30.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 30.51-39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 439.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 83 76 81 52 60 71 83 130 190 198 208 207 162 141 115 88 1953 STABILITY CLASS F STABILITY BASED ON 1=A,2=8,...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESMOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 10.00 METERS SPEED (MPN) N NME NE ENE E ESE SE SSE S SSW SV WSW W WNW NW NNW TOTAL- ,

CALM 3

.76- 2.50 9 3 2 0 1 1 1 1 4 11 7 7 14 37 23 10 131 2.51- 4.50 19 5 1 4 5 8 7 0 5 25 31 28 28 38 36 24 264 4.51- 6.50 13 1 0 0 5 4 12 8 8 16 2 4 0 8 4 7 92 6.51- 8.50 2 0 0 0 0 3 12 6 13 9 1 0 0 0 1 2 49 ,

8.51-11.50 0 0 0 0 1 1 6 10 6 9 3 1 0 0 0 0 37 11.51-14.50 0 0 0 0 0 6 1 5 6 7 0 0 0 0 0 0 25 14.51-18.50 0 0 0 0 1 0 0 0 0 1 0 0 0 0 0 0 2 18.51-23.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 23.51-30.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 30.51-39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 439.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 43 9 3 4 13 23 39 30 42 78 44 40 42 83 64 43 603

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Nelliburton NUS Corporction Air /Radittogiccl Programs Department PROGRAM: JFD VERSION: PC-1.2 DECO FERMI 2 JFD AT 10-METERS FOR 1995 SITE IDENTIFIER: FERMI 2 DATA PERIOD EXAMINED: 1/ 1/95 - 12/31/95 ***

- - ANNUAL STABILFTY BASED ON 1=A,'=8,...,7=G a

WIND 419mC *l: 10.0 METERS WIND i ncSNOLD AT: .75 MPN TOTAL NUNDER OF OBSERVATIONS: 8760 TOTAL NLMBER OF VALID OBSERVATIONS: 8759 TOTAL ul5SER OF MISSING OBSERVATIONS: 1 PERCENT DATA kECOVERY FOR THIS PERIOD: 100.0 %

MEAN WIND SPEED FOR THIS PERIOD: 6.9 MPN '

TOTAL NLMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 4.97 4.85 8.% 48.13 22.30 6.88 3.90 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW NW NNW CALM A 6 2 23 31 53 31 14 4 11 8 14 21 44 84 67 22 0 8 16 7 15 16 26 44 35 12 29 9 32 48 41 46 25 24 0 C 27 28 38 28 38 62 77 46 47 45 68 66 79 64 36 36 0 D 175 178 326 246 254 240 254 221 266 239 435 389 333 277 195 185 3 E 83 76 81 52 60 71 83 130 190 198 208 207 162 141 115 88 8 F 43 9 3 4 13 23 39 30 42 78 44 40 42 83 64 43 3 G 17 4 -4 3 10 19 38 16 11 41 13 14 31 51 25 39 6 TOTAL 367 304 490 380 454 490 540 459 596 618 814 785 732 746 527 437 20

I - - ._ . w . -.a -, e-Halliburton NUS Corporction Air /Redittogicit Programs Department PROGtAM: JFD VERSION: PC-1.2 LAST DATA RECORD READ: FERMI 2 95 12 31 24 4.8 26.0 4.0 OUTFtli FILE NAME :JFD10M95.UUT

i l

l 1995 Annual Ridicactiva Effluent Release Report l l

l l

i Appendix B: Changes to Offsite Dose Calculation Manual l

I j

EFFECTIVENESS REVIEW FOR LICENSE CHANGE REQUEST LCR 94-187-ODM ;

l EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 5 of 13

)

Document: Offsite Dose Calculation Manual Section/Page: 0.0, Page 0.0-1 Change: Change revision numbere raid approval dates for sections 0.0,3.0,7.0, and 10.0.

Basis: These sections are being revisea under this LCR.

Section/Page: Table 3.3.7.11.1, Page 3.0-6 (3.0-6 ar d 3.0-7 in reformatted version)

Change: In item "a" of Action 110 and item (1) of N. tion 113, substitute " Surveillance Requirement" for " Control".

Basis: Section 4.11.1.1.1 is a surveillance requirement.

Change: At the end ofitem "b" of Action 110, add "(one technically qualified individual can be the preparer of the calculation; the other independently reviews the release rate calculations to verify accuracy)".

Basis: This addition clarifies that only two individuals need be involved in the performance and review of release calculations under Action 110(b). It was ;

suggested by Quality Assurance and agreed to by Radiation Protection. NRC l personnel were contacted to ensure that Fermi's interpretation of this action i statement is the same as that of the NRC. See QA-94-1090 and NPRC-94-0063 (both attached).

Section/Page: Table 3.3.7.11.1, Page 3.0-6 1

Change: At the end of Action 111, add "If radioactive effluent releases are not in progress, i.e. if no Waste Sample Tank (or other tank containing radioactive liquid) is being released and the circulating water is not contaminated as shown by the most recent circulating water sample (s), this sampling requirement does not apply."

Basis: A previous revision (LCR 93-117-ODM, approved 9/21/93) added the word

" radioactive" before " effluent releases" in this action statement to clarify that it applies only when waste sample tank releases are in progress or when the circulating water is contaminated. However, there has still been confusion as to the actions required when this monitor is inoperable; this addition is a further clarification. The "most recent" sample referred to will be no more than a month old, since Chemistry procedures require monthly sampling.

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 6 of 13 l Document: Offsite Dose Calculation Manual

, Section/Page: Table 3.3.7.121, Actions 121 and 123, Page 3.0-13 (Page 3.0-12 in l reformatted version) .

Change: Change Action 121 frequency from 12 to 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and Action 123 frequency *

from 4 to 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . '

Basis: The purpose of this change is to synchronize required sample collection to i reduce the chance of enor and facilitate shift schertuling without compromising .

effluent control. The change to Action 121 increases the noble gas sample collection frequency and thus does not need furtherjustification. The change to Action 123, which reduces the flow check frequency from 4 to 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months , was discussed with Dick Hauge of Region 3 and may be justified as follows:

1) The requirement to check flow once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is inconsistent with the requirement of Action 122 that the auxiliary sampling equipment be installed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ofinoperability. If 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months are allowed without any particulate or iodine sampling (and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without noble gas sampling),

there is no need for a flow check after 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ofinoperability. This flow check requirement forces installation of the auxiliary equipment within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2) (Ming flow once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months does not add to the accuracy of effluent calculations because effluent sample volumes are based on an average of the i beginning and ending flow rate readings which are taken independently of !

the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow checks. Also, any departure from isokinetic sampling caused by variations in flow rate are small due to the small particle sizes which prevailin gaseous effluents.

3) Since 1987 flow checks on the auxiliary sampling equipment performed by Radiation Protection have never shown deviations of more than 10% either between successive checks or between checks at the beginning and end of auxiliary sampling equipment use. Thus it is unlikely that checking at a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months frequency rather than a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months frequency will provide additional information which could significantly improve the calculation of particulate and iodine releases.

4) Although the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow check requirement is found in Standard l Radiological Effluent Technical Specifications for Boiling Water Reactors '

(NUREG-0473), not all BWRs have this requirement. For example, Oyster Creek requires flow checks once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during monitor inoperability, i and Grand Gulf requires flow checks once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Duane Arnold requires flow checks only when the exhaust fan combination is changed.

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 7 of 13 Document: Offsite Dose Calculation Manual

5) Since these changes will result in flow checks and noble gas samples being I taken together every 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (or more frequently because of admmistrative requirements), scheduling will be greatly simplified and the chance of 1 personnel error and missed surveillances greatly reduced. This advantage, . l together with the added conservatism of more frequent noble gts samples, outweighs any possible negative effect of the proposed modest riecrease in flow check frequency.

6) Even considering the increased noble gas sample frequency, there is a manhour savings associated with the decreased flow check frequency and i the fact that the flow checks and noble gas samples will be done together. l (Also, because of the increased time allowed for auxiliary cart hookup, more i cases of SPING inoperability will be resolved before hookup, with its j associated manhours,is required.) The flow check surveillance was open l

for 75 days in the 5 year period 1990 through 1994. Ifit is estimated that i this surveillance will continue to be performed at this rate for 30 years of )

remaining plant life, and that I hour per day is saved at $40 per hour, the ,

estimmied savings is approximately $18,000. l Section/Page: Table 4.11.2.1.2-1, Footnote d, Pages 3.0-25 and 3.0-27 (Pages 3.0-23 and 3.0-25 in reformatted version)

Coange: Delete footnote d to eliminate the requirement for daily tritium release point i samples when the reactor well or dryer-separator storage pool is flooded. i Basis: 1) This requirement does not appear in the standard BWR effluent specifications (NUREG 0473) or in the requirements of any BWR surveyed for this change. (Ten BWRs were surveyed.) Instead,it appears in standard PWR effluent specifications (NUREG-0472). The shortest frequency of tritium sampling in the surveyed plants was I week with spent fuel in the fuel pool; Fermi also has this requirement, and it appears in NUREG-0473.

'Ibe shortest tritium sampling frequency at Grand Gulfis one month, and the Duane Arnold frequency is once per quarter and also once when the reactor head is removed.

2) Typically, when the reactor well or dryer-separator pool is flooded, the plant is in an outage of 1 month or longer, and any tritium releases from this water would be expected to be sustained rather than spike releases. Therefo're a weekly tritium sample should adequately represent the releases over the expected release period. (The only potential for spike releases is when water systems are opened, e.g. reactor head removal or opening the l condenser.) ]

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 8 of 13 Document: Offsite Dose Calculation Manual

3) To date, no tritium sample taken under this requirement has been positive at Fermi 2. The added work load of taking daily samples during already busy outage periods greatly increases the chances of personnel error and missed surveillances and has not provided information which is useful in effluent calculations.

4) The surveillance for daily tritium sampling was open for 37 days in the previous 2 fuel cycles (1994 data is excluded because of the extraordinary outage length). Assuming that this sampling would continue at this rate for 20 fuel cycles remaining in plant life, and that one hour per day is saved at

$40 per hour, the estimated savings for eliminating this surveillance is

$15,000.

Section/Page: Table 4.11.2.1.2-1, Footnote g, Page 3.0 27 (Page 3.0-25 in reformatted version)

Change: Revise footnote g to require only three additional iodine and particulate sample changeouts from the affected release point when a noble gas monitor shows a 3 times increase, and to require only three additional samples from the reactor building release point, the radwaste building release point, the turbine building release point, and the SGTS release point if SGTS is running after a 3 times increase in DEI. Allow adjustment of1.LD for shortened sample period.

Basis: 1) Currently, this footnote can be interpreted to require 7 daily samples from each release point following a 3 times increase in the noble gas reading at any SPING monitor. However, due to the separate ventilation systems at Fermi, !

increases in noble gas effluents at one release point are rarely correlated with increases at any other point. Also, experience has shown that any increases in i iodines and particulates in gaseous effluents which are associated with a 3 l times noble gas increase have peaked within 3 days following the increase, and that further daily sampling is not needed to adequately quantify the iodine i or particulate release.

)

l In the case of a 3 times DEIincrease, the current requirement is for 7 daily

{

samples from each release point. However, an increase in DEI only )

significantly increases the potential iodine and particulate releases from the teactor building, turbine building, radwaste building, and SGTS (if running) ventilation systems (since radioactive water does not circulate through the l Office Service Bt,". ding and Onsite Storage Facility). Also, experience has {

shown that any! eases in particulates and iodines associated with a 3 times DEI increase hc.e peaked within 3 days following the increase, and that further daily sampling is not needed to adequately quantify the release.

EFFECTIVENESS REVIEW DOCUMENTATION ,

Reference LCR 94-187-ODM Revision 0 Page 9 of 13 Document: Offsite Dose Calculation Manual With respect to sample accuracy, for the next sample which will be taken after the proposed 3 required daily samples, the LLD will be lower due to ;

the larger sample volume, so that the chance of detecting particulates and '

iodines will be increased.

2) Although the present requirement for 7 daily samples from each release point-appears in standard BWR effluent technical specifications (NUREG-0473),

it is not a requirement at all BWRs. For example, Duane Arnold requires only a single noble gas sample within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of a greater than 50% noble gas effluent increase after factoring out the effect of reactor power changes. )

Pilgrim requires only a single iodine and particulate sample changeout after a 50% increase in average daily rad release rate after factoring out the effect of reactor power changes. WNP-2 has a requirement similar to ours, except that only a single sample is required after a 15% power change. These practices of other plants relative to the proposed change to footnote g were discussed with Dick Hauge of NRC Region 3 on 11/1/94.

3) The practical effect of this increased sampling requirement as it stands is not beneficial to overall Radiation Protection operations or to effluent calculations: Taking daily samples for seven days from each release point at l times of startup, shutdown, or power changes-which are normally very busy l times in any case-is very burdensome and greatly increases the chances for 1 personnel error and missed surveillances while only rarely adding useful information. Also, it diverts manpower which could be used in more appropriate effluent monitoring activities. For example, after a step change noble gas increase, daily noble gas samples could be taken (only a single sample is required by footnote c for the same entry conditions as footnote g) l which may show a trend in noble gas releases and nuclide mixes, whereas daily iodine and particulate samples may show no increases above normal levels.

4) Footnote g as currently written allows LLDs for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sample periods to be 10 times higher than the normally allowed LLDs, which are used for a one week sample period. The proposed change allows LLDs to be adjusted for periods between 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and I week according to the sample volume involved relative to the normal weekly sample volume. This change does not reduce the accuracy of effluent calculations because sample periods shorter than one week are designed to quantify effluents more accurately in a period in which effluent concentrations are not stable. In this situation, a higher LLD is necessary to compensate for the smaller volume of the shorter sample periods: Sample volume is in the denominator of the LLD equation (see Table 4.11.2.1.2-1, footnote a).

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 10 of 13 Document: Offsite Dose Calculation Manual

5) The surveillance implementing this daily sampling requirement was open for 59 days in the five year period 1990 through 1994. Assuming that sampling would continue at this rate for 30 years for remammg plant life with an 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day additional manpower requirement for sampling, counting, analysis, and administrative work, at a rate of $40 per hour, the estimated savings would be $113,000.

Section/Page: Table 3.12.1-1, Jtem 1, Page 3.0 36 (3.0-35 in reformatted version)

Change: Change number of monitoring stations to 67.

1 Basis: With recently added TLD locations, the number of direct radiation monitoring I locations is 67.

Section/Page: 3.12.2, item a, Page 3.0-46 (3.0-44 in reformatted version)

Change: Substitute " Surveillance Requirement" for " Control". I I

Basis: Section 4.11.2.3 is a surveillance requirement.

Section/Page: 7J.1, Page 7.012 (7.014 in reformatted version) l Change: In definition of terms for Equation 7-14, change "Raiop" to "Raipo".

Basis: As changed, this term is written exactly as it is in Equation 7-14. This will not i change the numerical value of the term but it will avoid confusion.

Section/Page: Table 7.0-3 footnote, Page 7.0-17 (7.0-20 in reformatted version)

Change: Change "1992" to "1994".

Basis: This change reflects the fact that the values in this table have been evaluated against dispersion and deposition factors calculated from 1993 and 1994 meteorological data. (No changes in thesi; values were made.)

Section/Page: Table 7.0 4, Pages 7.0-18.-7.0-M (7.0-21--7.0-50 reformatted)

Change: Change "Rio" to "Raipo" at the top of each page.

Basis: The values in this table are used in Equation 7-14 where they are referred to as "Raipo". This change will make terminology consistent and avoid confusion; the results of past and future calculations are not affected.

1 l

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 11 of 13 Document: Offsite Dose Calculation Manual Section/Page: 7.8.2, Page 7.0-13 Change: In definition of Qi, clarify that releases are summed over all release points.

Basis: ODCM Control 3.11.2.3 applies to releases from "each reactor unit."

Section/Page: Table 10.0-1, Pages 10-4 and 10-11 (10-12 in reformatted version)

Change: Revise the description of sampling stations T7 and API 4 to " Pole at Michigan Gas substation on N. Custer Rd.,0.66 miles west of Doty Rd." and distance from 14.2 miles to 14.0 miles.

Basis: Location was moved due to vandalism. ,

Section/Page: Table 10.0-1, Page 10-7 (10-8 in reformatted version) I Change: Add direct radiation (TLD) monitoring locations T64 through T67. .

Basis: These nearby locations were added to improve quantification of skyshine dose.

Section/Page: Table 10.0-1, Page 10.0-9 (10.010 in reformatted version)

Change: Add new milk sampling location M9 to table.

Basis: Milk collection was started at this location in September 1994.

Section/Page: Figure 10.0-3, Page 10.0-18 (10.019 in reformatted version)

Change: Add new milk sampling location M9 to figure.

Basis: Milk collection was staned at this location in September 1994.

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 94-187-ODM Revision 0 Page 12 of 13 Document: Offsite Dose Calculation Manual Summary of Effectiveness Review:

The most substantive of the above changes involve effluent sampling requirements. By clarifying these requirements and making them more reasonable and less burdensome, time and manpower are saved which can be used to improve effluent monitoring and reporting or to reduce overall costs. None of the above changes involve changing effluent levels, only the monitoring of these levels. Therefore the health and safety of the public is not jeopardized by these proposed changes.

Monetary savings over the estimated 30 years of remaining plant life have been estimated !

for each proposed change to effluent sampling requirements. The total of these estimates i is approximately $150,000.

l l

i EFFECTIVENESS REVIEW l FOR LICENSE CHANGE REQUEST LCR 95-121-ODM l

l EFFECTIVENESS REVIEW DOCUMENTATION l Reference LCR 95-121-ODM Revision 0 Page 5 of 8 Section/Page: 2.21, Page 2.0-4 Change: Revise definition of Member of the Public to be any individual except when that individual is receiving an occupational dose.

Basis: This conforms to the August 1995 revision to 10 CFR 20.1003. The previous ,

definition did not define Member of the Public for the Radiologically Restricted l Area (RRA), implying that any dose in the RRA must be an recupational dose.

i Section/Page: 2.22, Page 2.0-4

]

Change: Add definition of of Occupational Dose as found in the August 1995 revision to 10 CFR 20.1003: Occupational Dose means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiadon, whether in the possession of the licensee or other person. Occupadonal dose does not include dose received from -

background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public.

Basis: This dermition is included because the definition of Member of the Public depends on the concept of Occupational Dose.

Section/Page: 2.27, Page 2.0-5 !

Change: Add definition of of Public Dose as found in the August 1995 revision to 10 CFR 20.1003: Public Dose means the dose received by a member of the public from exposure to radiation and/or radioacdve material released by a licensee, or to any other source of radiation under the control of a licensee. It does not ,

include occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs. :

Basis: This dermidon is included because it describes dose received by a Member of the Public and contrasts with Occupadonal Dose.

i I

~~

l

EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 95-121-ODM Revision 0 Page 6 of 8 Section/Page: Table 3.3.7.11.1, Action 112, Page 3.0-6 l Change: Add " radioactive" before " effluent releases" and add the followmg sentence at j the end of Action 112: "If radioactive effluent releases are not in progress, i.e., ;

if no Waste Sample Tank (or other tank containing radioactive liquid) is being i released and the circulating water is not contaminated as shown by the most recent circulating water sample (s), this requirement does not apply."

Basis: This provides the same clarification for all liquid effluent flow rate ,

measurement devices as already contained in Action 111 for the circulating water decant monitor. The grab samples required by Action 111 and the flow checks required by Action 112 are both designed to ensure that liquid effluent <

radioactivity limits are not exceeded when radioactive releases are in progress.

The grab samples check activity concentration and the flow checks ensure adequate dilution. If radioactive releases are not in progress, these requirements need not be in effect.

Section/Page: 8.1, Page 8.01 and Table 8.0-1, Page 8.0-7 Change: Delete last sentence in second paragraph and third column in Table 8.0-1.

Basis: Due to the increased dose rates anticipated with Hydrogen Water Chemistry, it has been decided to classify all individuals permanently assigned to the site as "radworkers" and none as Members of the Public. Therefore the'ODCM 5.9.1.8 requirement to assess dose to Members of the Public within the site boundary, which previously included permanently assigned workers who did not enter the l RRA, no longer applies to these workers.

Section/Page: 10.3, Page 10.0-2 Change: Delete references to the EPA and the Commission in the description of the Interlaboratory Comparison Program. Reword section to allow for upcoming changes to this program. Correct frequency of QA summary report to annual.

Basis: Earlier this year the EPA notified the NRC that it will no longer be providing )

quality assurance services to the NRC, including the Interlaboratory Comparison Program. (The EPA later agmed to extend this service till the end of 1995.) ;

Fermi 2 intends to continue to assure that an adequate program of interlaboratory comparisons involving our contract environmental laboratory is being performed. Frequency of QA Report was erroneously listed as bimonthly or quanerly because samples are received on a quanerly basis. This change does not reduce the level of effluent control because the frequency of QA reports does not affect the accuracy of analyses performed under this program.

i EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR 95-121-ODM Revision 0 Page 7 of 8 Section/Page: Table 10.0-1, Page 10.0-11 l

Change: Delete drinking water sampling location DW-3.

Basis: This is no longer an intake to an onsite potable water plant, since the site now receives its potable water from Frenchtown Township.

Section/Page: Table 10.0-1, Page 10.0-13 ,

Change: Substitute a new food product control location (FP-9) for the previous control location (FP-6).

l Basis: The previous location is no longer producing enough broadleaf vegetation for adequate samples, while the new location has a garden producing broadleaf l vegetation and has agreed to participate in the program.

Section/Page: Table 10.01, Page 10.0-4,5,11, and 13 Change: Miscellaneous minor corrections to location descriptions: a) Change description l of direct radiation station T10 to south side of Masserant and west of Chinavare, !

b) Add the word " corner" in the location of T16, c) Change SW-3 azimuth to l 160, and d) Change FP-1 distance to 3.8 miles. l Basis: This is based an a recent review of location descriptions and recalculation of distances.

Section/Page: Figure 10.0-2, Page 10.0-18 Change: Delete FP-6 from map and add FP-9. ;

I Basis: The control food product location has been changed, as discussed above. I Section/Page: Figure 10.0-4, Page 10.0-20 Change: Delete DW-3 on map.

Basis: This is no longer a drinking water location, as discussed above.

. .- - . .- . _ - . - - . . . .= - . . . . _

)

EFFECTIVENESS REVIEW DOCUMENTATION l Reference LCR 95-121-ODM Revision 0 Page 8 of 8 ,

l Section/Page: All i

Change: All sections and pages will get new revision numbers so that Information and Procedures codes can be changed to incorparate the ODCM into the Technical Requirements Manual (TRM). In conjuction with this, some new formatting and miscellaneous cosmetic changes to the ODCM will be completed.

Basis: MLS08, Licenses, Plans and Programs, requires the ODCM to be placed in the TRM. New formatting is necessitated by a change from the Macintosh to the IBM format by Information Management.

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Nuclear Production - Fermi 2 ODCM-0.0 Offsite Dose Calculation Manual Revision 10 Page 0.0-1 DETROIT EDISON - FERMI 2 OFFSITE DOSE CALCULATION MANUAL implementation Plan These revisions go into effect January 3,1996.

Current Revision Status by Section Section Number Revision Number Approval Date 0.0 10 12/12/95 1.0 6 12/12/95 2.0 6 12/12/95 3.0 10 12/12/95 4.0 7 12/12/95 5.0 6 12/12/95 6.0 7 12/12/95 7.0 8 12/12/95 8.0 6 12/12/95 9.0 6 12/12/95 10.0 7 12/12/95 Appendix A 5 12/12/95 Appendix B 5 12/12/95 Information and Procedures DSN Revision Change # DTC File #

TRM VOL 11 10 95-121-ODM TMTRM 1754 IP Code Date Approved Released By Date Recipient i 12/12/95 i

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ODCM-0.0 Revision 10 i Page 0.0-2 TABLE OF CONTENTS Pace Section 1.0-1

1.0 INTRODUCTION

PART I - R ADIOLOGICAL EFFLUENT CONTROLS 2.0-2 2.0 DEFINITIONS 3.0-1 3.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 3.0 2 3/4.0 Controls and Surveillance Requirements Applicability 3.0-4 3/4.3.7.11 Radioactive Liquid Effluent Monitoring Instrumentation 3.0-10 3/4.3.7.12 Radioactive Gaseous Effluent Monitoring Instrumentation 3.0-17 3/4.11.1.1 Liquid Effluents Concentration 3.0-21 3/4.11.1.2 Liquid Effluents Dose

3.0-22 3/4.11.1.3 Liquid Waste Treatment

, 3.0-23 3/4.11.2.1 Gaseous Effluents Dose Rate 3.0-27 3/4.11.2.2 Gsseous Effluents Dose - Noble Gases 3.0-28 3/4.11.2.3 Gaseous Effluents Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 4- 3.0-29 3/4.11.2.4 Offgas Treatment System 3.0-30 3/4.11.2.5 Ventilation Exhaust Trestment System 3.0-31 3/4.11.2.8 Venting or Purging 3.0-32 3/4.11.4 Radioactive Effluents Total Dose 3.0-33 3/4.12.1 Radiological Environmental Monitoring Program i 3.0 44 3/4.12.2 Land Use Census 3.0-45 3/4.12.3 Interlaboratory Comparison Program 4.0 1 4.0 BASES 5.0 1 5.0 ADMINISTRATIVE CONTROLS 5.0 2 5.9.1.7 Annual Radiological Environmental Operating Report 5.0 2 5.9.1.8 Annual Radioactive Effluent Release Report 5.0-4 5.15 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 4

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ODCM-0.0 Revision 10 Page 0.0-3 TABLE OF CONTENTS (continued)

Pece Section PART 11 - CALCULATIONAL METHODS 6.0-2 6.0 LIQUID EFFLUENTS 6.0-2 6.1 Radiation Monitoring instrumentation and Controls 6.0-2 6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement 6.0-3 6.1.2 Non-ODCM Required Monitor 6.0-4 6.2 Sampling and Analysis of Liquid Effluents 6.0-4 6.2.1 BATCH Releases 6.0-5 6.2.2 CONTINUOUS Releases 6.0-5 6.3 Liquid Effluent Monitor Setpoints 6.0-6 6.3.1 Tank Effluent Line Monitors 6.0-9 6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (D11-N402) 6.0-10 6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 6.0-11 6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors 6.0-11 6.3.5 Alarm Response - Evaluating Actual Release Conditions 6.0-12 6.3.6 Liquid Radwaste Setpoint Determination With Contaminated Circulating Water Reservoir 6.0-13 6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases 6.0-14 6.5 Liquid Effluent Dose Calculation - 10 CFR 50 6.0-14 6.5.1 MEMBER OF THE PUBLIC Dose - Liquid i Effluents !

6.0-16 6.5.2 Simplified Liquid Effluent Dose Calculation 6.0-17 6.5.3 Contaminated CWR System - Dose Calculation 6.0-16 6.6 Liquid Effluent Dose Projections 7.0 1 7.0 GASEOUS EFFLUENTS 7.0-1 7.1 Radiation Monitoring instrumentation and Controls 7.0 1 7.1.1 Effluent Monitoring - Ventilation System Releases 7.0-1 7.1.2 Main Condenser Offgas Monitoring 7.0-2 7.1.3 Reactor Building Ventilation Moniiors (Gulf Atomic) l

ODCM-0.0 Revision 10 Page 0.0-4

' TABLE OF CONTENTS (continued)

Pace Section 7.0-2 7.2 Sampling and Analysis of Gaseous Effluents 7.0-2 7.2.1 Containment PURGE 7.0-3 7.2.2 Ventilation System Releases 7.0-4 7.3 Gaseous Effluent Monitor Setpoint Determination 7.0 4 7.3.1 Ventilation System Monitors 7.0-6 7.3.2 Setpoint Determination with No Nuclides Detected 7.0-6 7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions 7.0-7 7.4 Primary Containment VENTING and PURGING 7.0-7 7.4.1 Release Rate Evaluation 7.0-8 7.4.2 Alarm Setpoint Evaluation 7.0-9 7.5 Quantifying Releases - Noble Gases 7.0-9 7.5.1 Sampling Protocol 7.0-10 7.5.2 Release Concentratiun Determination for Reactor Building Exhaust Plenum 7.0-10 7.5.3 Calculation of Activity Released I

7.0-11 7.6 Site Boundary Dose Rate - Radiolodine and Particulates 7.0-12 7.7 Noble Gas Effluent Dose Calculations - 10 CFR 50 7.0-12 7.7.1 UNRESTRICTED AREA Dose - Noble Gases 7.0 13 7.7.2 Simplified Dose Calculation for Noble Gases 7.0-13 7.8 Radiolodine and Particulate Dose Calculations - 10 CFR 50 7.0-13 7.8.1 UNRESTRICTED AREA Dose - Radiolodine, Particulates, and Tritium 7.0-15 7.8.2 Simplified Dose Calculation for Radiciodines and Particulates 7.016 7.9 Gaseous Effluent Dose Projection 7.0-17 7.10 Waste Oliincineration 8.0-1 8.0 SPECIAL DOSE ANALYSES 8.0-1 8.1 Doses Due to Activities inside the SITE BOUNDARY 8.0-1 8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 8.0 2 8.2.1 Effluent Dose Calculations 8.0-3 8.2.2 Direct Exposure Dose Determination 8.0-4 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data

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ODCM-0.0 Revision 10 i Page 0.0-5

TABLE OF CONTENTS (continued)

Pace Section 9.0-1 9.0 ASSESSMENT OF LAND USE CENSUS DATA 9.0-1 9.1 Land Use Census as Required by ODCM 3.12.2 9.0-3 9.2 Land Use Census to Support Realistic Dose Assessment 10.0-1 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

10.0-1 10.1 Sampling Locations 10.0-1 10.2 Reporting Levels 10.0-2 10.3 Interlaboratory Comparison Program l l

APPENDICES

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A-1 A Technical Basis for Effective Dose Factors Liquid Effluent Releases B-1 B Technical Basis for Effective Dose Factors Gaseous Radwaste Effluents TABLES 2.0-7 2.1 Surveillance Frequency Notation 2.0-8 2.2 Operational Conditions 3.0 5 3.3.7.11-1 Radioactive Liquid Effluent Monitoring instrumentation 3.0-8 4.3.7.11-1 Radioactive Liquid Effluent Monitoring Instrumentation Survelilance Requirements 3.0-11 3.3.7.12-1 Radioactive Gaseous Effluent Monitoring instrumentation 3.0-14 4.3.7.12-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3.018 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program 3.0-24 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and analysis ;

Program i 3.0 35 3.12.1-1 Radiological Environmental Monitoring Program l 3.040 3.12.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples l 3.0-41 4.12.1-1 Detection Capabilities for Environmental Sample :

Analysis

ODCM-0.0 Revision 10 Page 0.0-6 TABLE OF CONTENTS (continued)

Pace Section 6.0-20 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors, Aio 6.0-22 6.0-2 Bloaccumulation Factors (BFi) 7.0-18 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints 7.0-19 7.0-2 Dose Factors for Noble Gases 7.0-20 7.0-3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations 7.0-21 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors 8.0-7 8.0-1 Assumptions for Assessing Doses Due to Activities 1 inside SITE BOUNDARY l 8.0-8 8.0-2 Recommended Exposure Rates in Lieu of Site Specific )

Data 10.0-3 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media 10.0-15 10.0-2 Radiological Environmental Monitoring Program, Fermi 1 Sample Locations and Associated Meri!s A4 A-1 Relative Dose Significance of Radionucifdes in Liquid Effluents B-4 B-1 Effective Dose Factors - Noble Gas Effluents FIGURES 3.0-46 3.0-1 Map Defining Unrestricted Areas and Site Boundary ,

for Radioactive Gaseous and Liquid Effluents I 6.0-23 6.0-1 Liquid Radioactive Effluent Monitoring and Processing I Diagram (

7.0-51 7.0-1 Gaseous Radioactive Effluent Monitoring and l Ventilation Systems Diagram I 10.0-17 10.0-1 Radiological Environmental Monitoring Program i Sampling Locations- Site Area 10.0-18 10.0-2 Radiological Environmental Monitoring Program Sampling Locations - Greater than 10 Miles 10.0-19 10.0-3 Radiological Environmental Monitoring Program Sampling Locations - within 10 Miles !

l 10.0-20 10.0-4 Radiological Environmental Monitoring Program Sampling Locations - Site Area (Lake Erie side) 10.0-21 10.0-5 Fermi 1 Sampling Locations END OF SECTION 0.0

ODCM-1.0.

Nuclear Production - Fermi 2 Revision 6 Offsite Dose Calculation Manual Page 1.0-1 INTRODUCTION l l

1.0 INTRODUCTION

Part I of the Fermi 2 Offsite Dose Calculation Manual (ODCM), which includes Sections 2.0 through 5.0, contains the controls and surveillance requirements for radioactive effluents and radiological environmental monitoring. It also contains requirements for the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.

Part 11 of the ODCM describes the methodology and parameters used in a) determining radioactive material release rates and cumulative releases, b) calculating radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints, and c) calculating the corresponding dose rates and cumulative quarterly and yearly doses. Calculational methods different from those provided in the ODCM may be used only if they lead to more conservative results than would be obtained using ODCM methods. ODCM data for dispersion factors, receptor locations, exposure pathways, ventilation flow rates, etc. are intended to lead to conservative results. However, it is permissible to use plant procedures which implement the ODCM and which contain different data due to changes in environmental and plant conditions. ,

The methodology provided in Part 11 of this manual is acceptable for use in demonstrating compliance with the dose limits for members of the public of 10 CFR 20, the cumulative dose criteria of 10 CFR 50, Appendix I and 40 CFR 190, and the controls in Part i of this manual.

Part II, Section 6.0 of the ODCM describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 7.0 provides similar information on .

l gaseous effluorit controls, sampling, and dose evaluation. Section 8.0 describes special dose '

analyses required for compliance with Fermi 2 Offsite Dose Calculation Manual and 40 CFR 190.

Section 9.0 describes the role of the annual land use census in identifying the controlling pathways and locations of exposure for assessing potential off-site doses. Section 10.0 describes the Radiological Environmental Monitoring Program.

The ODCM will be maintained at Fermi 2 for use as a listing of radiological effluent controls and surveillance requirements, as well as a reference guide and training document for accepted methodologies and calculations. Changes to the ODCM calculational methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix 1 for demonstrating that radioactive effluents are "As ,

Low As Reasonably Achievable." l NOTE: Throughout this document words appearing all capitalized denote either definitions specified in the Fermi 2 Controls or common acronyms.

4 END OF SECTION 1.0

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Nuclear Production - Fermi 2 ODCM-2.0 {

Offsite Dose Calculation Manual Page 2.0-1 l i

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PARTI !

RADIOLOGICAL EFFLUENT CONTROLS l

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I Nuclear Production - Fermi 2 ODCM-2.0 l Offsite Dose Calculation Manual Revision 6 l Page 2.0-2 i

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SECTION 2.0 l

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.' DEFINITIONS I

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2.0 DEFINITIONS ,

t A. G Q.M 2.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION !

2.4 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the j parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass '

the entire channel including the sensor and alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST, The CHANNEL CAllBRATION may be performed ,

by any series of sequential, overlapping, or total channel steps such that the entire channelis calibrated. Calibration of instrument channels with resistance temperature detectors (RTD) or thermocouple sensors shall consist of verification of operability of the sensing element and adjustment, as necessary, of the remaining adjustable devices in the ;

channel.

CHANNEL CHECK f 2.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

l CHANNEL FUNCTIONAL TEST 2.6 A CHANNEL FUNCTIONAL TEST shall be: !

a. Analog channels - the injection of a simulated signal into the channel as close to the ]

sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

b. Bistable channels - the injection of a simulated signal into the sensor to verify )

OPERABILITY including alarm and/or trip functions.

1 The CHANNEL FUNCTIONAL TEST may be performed by any sequential, overlapping, or j total channel steps such that the entire channel is tested. !

1 DOlpE EQUIVALENTI-131 2.9 DOSE EQUlVALENT l-131 shall be that concentration of I-131 microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotop'c mixture of I-131,1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table lil of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

i ODCM-2.0 j Revision 6 1 Page 2.0-4 l 2.0 DEFINITIONS ,

FREQUENCY NOTATION 2.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 2.1.

MEMBER (S) OF THE PUBLIC 221 MEMBER (S) OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

OCCUPATIONAL DOSE 2.22 Occupational Dose means the dose received by an individualin the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive j !

material from licensed and unlicensed sources of radiation, whether in the possession of f the licensee or other person. Occupational dose does not include dose received from fl il background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a memoer of the general public.

1 OFF-GAS TREATMENT SYSTEM 2.23 An OFF-GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system offgases from the )

reactor coolant and providing for delay or holdup for the purpose of reducing the total !

radioactivity prior to release to the environment.

OFFSITE DOSE CALCULATIONAL MANUAL 2.24 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and l parameters used in the calculation of offsite doses resulting from radioactive gaseous and -

liquid effluent, 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 (1) the Radiological Effluent Controls and Radiological Environmental Monitoring Program Controls required by Technical Specification 6.8.5, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Reports required by Controls 5.9.1.7 and 5.9.1.8.

OPERABLE - OPERABILITY 2.25 A system, subsystem, train, 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, electrical power, cooling or seal water, lubrication or other auxilliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDmON - CONDITION 226 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 2.2.

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ODCM-2.0 -

Revision 6 Page 2.0-5 l

2.0 DEFINITIONS PUBLIC DOSE 2.27 Public Dose means the dose received by a member of the public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of ,

radiation under the control of a licensee. It does not include occupational dose or doses g' received from background radiation. as a patient from medical oracticea, or from voluntary participation in medical research programs. l PURGE - PURGING 2.31 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 2.32 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant equivalent to that stated in the Technical Specification definition of RATED THERMAL POWER.

REPORTABLE EVENT 2.34 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SITE BOUNDARY ;

2.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled, by the licensee.

SOURCE CHECK 2.40 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

THERMAL POWER 2.42 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. !

UNRESTRICTED AREA 2.45 The Fermi 2 Energy Center UNRESTRICTED AREA includes all areas outside the site i boundary.

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ODCM 2.0 Revision 6 Page 2.0-6 2.0 DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM 2.46 A VENTILATION EXMAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine 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) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 2.47 VENTING shall be 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.

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Nuclear Production - Fermi 2 ODCM-2.0 Offsite Dose Calculation Manual Revision 6

- Page 2.0-7 ,

TABLE 2.1 SURVEILLANCE FREQUENCY NOTATION ,

NOTATION FREQUENCY i

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , D Atleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I W At least once per 7 days.

M At least once per 31 days.

O 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 18 months (550 days). ;

S/U Prior to each reactor startup.

P Prior to each radioactive release.

N.A. Not applicable.

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Nuclear Production - Fermi 2 ODCM-2.0 Offsite Dose Calculation Manual Revision 6 Page 2.0-8 2.0 DEFINmONS TABLE 2.2 OPERATIONAL CONDmONS MODE SWITCH AVERAGE REACTOR CONDmON POSmON COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature ,

2. STARTUP Startup/ Hot Standby Any temperature

3. HOT SHUTDOWN Shutdown #, "" > 200 degrees F 4 COLD SHUTDOWN Shutdown #, ##, '" s 200 degrees F

5. REFUELING

Shutdown or refuel".# s 140 degrees F l

The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

1. The reactor mode switch may be placed in the Refuel position while a single control rod )

drive is being removed from the reactor pressure vessel per Technical Specification 3.9.10.1.

Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

See Special Test Exceptions 3.10.1 and 3.10.3 of Technical Specifications. ]

" The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.

END OF SECTION 2.0 i

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I Nuclear Production - Fermi 2 ODCM-3.0 Offsite Dose Calculation Manual Revision 10 Page 3.0-1 8

l SECTION 3.0 i CONTROLS l AND SURVEILLANCE REQUIREMENTS

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ODCM-3.0 Rsvision 10 Page 3.0-2 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the succeeding Controls is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the control, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Control shall exist when the requirements of the control and associated ACTION requirements are not met within the specified time intervals. If the Controlis restored prior to expiration of the s?ecified time intervals, completion of the Action requirements is not required.

3.0.3 When a Control is not met, except as provided in the associated ACTION l

requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the control does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual Controls.

i This Control is not applicable in OPERATIONAL CONDITIONS 4 or 5. l 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be l

made when the conditions for the Controls are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision ,

shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls.

i ODCM-3.0 Revision 10 Page 3.0-3 APPLICABILITY ,

SURVEILLANCE RECT!!REMENTS ,

4.0.1 Surveillance Reauirements shall be met during the OPERATIONAL CONDITIONS or other conditie ns specified for individual Controls unless otherwise stated in an individual Surseillance Requirement.

4.0.2 Each Survoillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance 4.0.2. shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION >

requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Control have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

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ODCM 3.0 Revision 10 Page 3.0-4 INSTRUMENTATION i RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarnvtrip 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 methodology and parameters in the OFFSITE DOSE CALCULATIONAL MANUAL (ODCM). ,

i APPLICABILITY: At all times, except as noted for Condensate Storage Tank Discharge l Monitor and Flow Rate Measurement Device.

I 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 3.3.7.11-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.11 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 4.3.7.11-1.

ODCM-3.0 Revision 10 Page 3.0-5 TABLE 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION "I"I*"" **""*" Action -

Instrument Operable

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE 1 110

a. Uquid Radwaste Effluent Line D11 N007

2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM s BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE 1 111

a. Circulating Water Reservoir Decant Line D11 N402 Condensate Storage Tank Discharge Path (1) (2) 1 113 b.

3. FLOW RATE MEASUREMENT DEVICES Liquid Radwaste Effluent Line G11 R703 1 112 a.

Circulating Water Reservoir Decant Line N71.R802 1 112 b.

Condensate Storage Tank Discharge Path (2) 1 112 c.

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! TABLE 3.3.7.11.1 (Continued) i l TABLE NOTATIONS 4

ACTION 110 - With the number of channels OPERABLE less than required by the 1 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 l3 q[

Surveillance Requirement 4.11.1.1.1, and

b. At least two technically qualified individuals independently verify the release rate calculations and discharge line valving (one l

technically qualified individual can be the preparer of the calculation, the other independently reviews the release rate

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calculations to verify accuracy); ,

Otherwise, suspend release of radioactive affluents via this pathway. -

ACTION 111 - With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue provided that grab samples are collected and analyzed at .

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie /ml, for Cs-137. Otherwise, suspend release of radioactive affluents via this pathway, if radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or '

other tank containing radioactive liquid) is being released and the 7 circulating water is not contaminated as shown by the most recent circulating water sample (s), this sampling requirement does not apply.

ACTION 112 - With the number of channels OPERABLE less than required by the /

Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue provided the flow rate is estimated at least l[

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 may be used to estimate flow. Otherwise, suspend release of radioactive effluents via this pathway. If radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or other tank containing radioactive liquid) is being released and the circulating water is not contaminated as shown by the most recent circulating water sample (s),

p this requirement does not apply.

e 4

)

l l

ODCM-3.0 Revision 10

,- , Page 3.0-7 ACTION 113 - Suspend release of radioactive effluents via this pathway j (1) --

Prior to initiating a release, a) at least two independent samples are ;qf analyzed in accordance with Surveillance Requirement 4.11.1.1.1, b) the release rate calculations are reviewed by two technically qualified lII individuals, and c) the discharge line valving is independently verified by a technically qualified !r.dividual.

In addition, the Condensate Storage Tank Discharge Monitor wi!! be continually monitored to ensure that the tank is isolated promptly if the monitor alarms.

(2) -

The Condensate Storage Tank Discharge Path Monitor and Flow Rate i Measurement Device need be OPERABLE only when the Condensate l Storage Tank discharge path is in use.

l

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I l

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ODCM-3.0 Revision 10 Page 3.0 8 TABLE 4.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source - Channel Cm ineturnent yg g mgm Funadonal Test-

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Uguid Radweste Effluent une P P R(3) O(1)(2) i

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT '

PROVIDING AUTOMATIC TERMINATION OF RELEASE l

a. Circulating Water Reservoir Decant une D M R(3) O(5)

D11 N402

b. Condensate Storage Tank Discharge P P R(3) Q(6)

Path (7)

3. FLOW RATE MEASUREMENT DEVICES (4)

a. Uguid Radweste Effluent une D(4) N.A. R -Q

b. Circulating Water Reservoir Decant une D(4) N.A. R Q

c. Condensate Storage Tank Discharge D(4) N.A. R O Path (7) i l

_. .. m . . _ . _ _ _ _ . _ _ . _ _ . - _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ . _ . _ _ _ . . _ _

ODCM 3.0 Revision 10 Page 3.0-9

]

TABLE 4.3.7.11-1 (Continued) 4 TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint.

/-

2. Circuit failure. 1 (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

I 1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode. .

(3)

The initial CHANNEL CALIBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(5) 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. Circuit failure.

3. Instrument indicates a downscale failure.

(6)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that local alarm occurs if any of the following conditions exists: 1) instrument indicates measured levels above the alarm setpoint,2) circuit failure, or 3) instrument indicates a downscale failure.

(7) Surveillance requirements for the Condensate Storage Tank Discharge Path Monitor and the Condensate Storage Tank Discharge Path Flow Rate Measurement Device shall be met when the Condensate Storage Tank discharge path is in use.

i

ODCM-3.0 Revision 10 )

Page 3.0-10 l INSTRUMENTATION 1 1

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channe!s shown in f

Table 3.3.7.12-1 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 these channels, with the exception of the offgas monitoring system, shall be determined and adjusted in accordance with the methodology and parameters in the CDCM.

APPLICABILITY: As shown in Table 3.3.7.12-1 I

ACTION.

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably l conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.12-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.12 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.

i i

i ODCM-3.0 Revision 10 i Page 3.0-11 l I

1 TABLE 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l uwmum .

Instrument Channels. Applicability ^ Action-Operable -

1. REACTOR BUILDING EXHAUST PLENUM EFFLUENT MONITORING SYSTEM

a. Low Range Noble Gas Activity Monitor Providing 1 121

b. lodine Sampler 1 122

c. Partculate Sampler 1 122

d. Sampler Flow Rate Monitor 1 123

2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)

a. Noble Gas Acthaty Monitor Providing Alarm 1 126

3. STANDBY GAS TREATMENT SYSTEM

a. Low Range Noble Gas Activity Monrtor e# . Providing 1 # 125

b. lodine Sampier 1 # 122

c. Particulate Sampler 1 # 122 d, Sampler Flow Rate Monitor 1 # 123

4. TURBINE BLDG. VENTILATION MONITORING SYSTEM Low Range Noble Gas Activity Monitor Providing 1 121 a.

lodine Sampler 1 122 b.

Particulate Sampler 1 122 c.

Sampler Flow Rate Monitor 1 123 d.

l l

ODCM-3.0 Revision 10 Page 3.0-12 TABLE 3.3.7.12-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum-Instrument Channels - Applicability Action' Operable -

5. SERVICE BUILDING VENTILATION MONITORING SYSTEM

a. Low Range Noble Gas Activity Monitor - Providing 1 121

b. lodine Sampler 1 122

c. Particulate Sampter 1 122

d. Sampler Flow Rate Monitor 1 123

6. RADWASTE BUILDING VENTILATION MONITORING SYSTEM

a. Low Range Noble Gas Activity Monitor Providing 1 121

b. lodine Sampler 1 122

c. Particulate Sampler 1 122

d. Sampler Flow Rate Monitor 1 123

7. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR

a. . Low Range Noble Gas Activity Monitor - Provding 1- 121 !

lodine Sampier 1 122 b.

Partculate Sampler 1 122 c.

Sampler Flow Rate Monitor 1 123 d.

l ODCM-3.0 i Revision 10 Page 3.0-13 TABLE 3.3.7.12-1 (Continued)

TABLE NOTATIONS

i At all times. l Not used. I During operation of the inain condenser air ejector. !

During operation of the standby gas treatment system. l

1. Also included in Technical Specifications Table 3.3.7.5.1 Item 13.a. l

, ACTION STATEMENTS AC110N 121 - Witn the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continua provided grab samples are taken at leas hours and these samp.es are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 122 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provide:i that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.

( .

ACTION 123 - 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 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . Otherwise, suspend release of radioactive effluents via this l fl0[

pathway.

ACTION 124 - Not used.

ACTION 125 - 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 9 l hours and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, suspend release of radioactive affluents via this pathway.

ACTION 126 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via this pathway to the environment may continue for up to 7 days provided that:

a. The offgas system is not bypassed, and

b. The reactor building exhaust plenum noble gas effluent (downstream) monitoris OPERABLE; Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l ODCM-3.0 Revision 10 Page 3.0-14 1 l

l TABLE 4.3.7.12-1 l

. l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE l REQUIREMENTS l l

Channel, - Modes in -

Instrument Channel Source Channel- paneggan,g Which Check Check Calibration Teet: . Surveillance

~

Required '

1. REACTOR BUILDING EXHAUST PLENUM 1

D M

l

a. Low Range Noble Gas Activity Monitor - R(2) Q(1)

Providing Alarm I l

b. lodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A.

l

l

d. Sampler Flow Rate Monitor D N.A. R Q l

2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)

a. Noble Gas Activity Monitor D M R(2) O(1) l

3. STANDBY GAS TREATMENT MONITORING l SYSTEM

a. Low Range Noble Gas Activity Monitor D M R(2) Q(1) #

b. todine Sampler W N.A. N.A. NA #

c. Particulate Sampler W N.A. N.A. NA #

1

d. Sampler Flow Rate Monitor D N.A. R Q # l

4. TURBINE BLDG. VENTILATION MONITORING SYSTEM

a. Low Range Noble Gas Activity Monitor D M R(2) Q(4)

b. lodine Sampler W NA NA N.A. *

c. Particulate Sampler W NA NA NA *

d. Sampler Flow Rate Monitor D NA R Q

l l

ODCM-3.0 ,

Revision 10 Page 3.0-15 TABLE 4.3.7.12-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

"****I"'

r Chand' instrument - Channel Source Channel ^ Which Funcdonal

. Check Check Calibradon ' TW " ****III*"**

' ' Required ,

1

5. SERVICE BUILDING VENTILATION MONITORING SYSTEM Low Range Noble Gas Activity Monitor D M R(2) O(4)

a. ,

b. lodine Sampler W N.A. N.A. N.A.

c. Particulate Sampler W N.A. NA N.A.

D N.A. R O

d. Sampler Flow Rate Monitor l

6. RADWASTE BUILDING VENTil.ATION l' MONITORING SYSTEM Low Range Noble Gas Activity Monitor D M R(2) O(4) a.

b. todine Sampler W N.A. NA N.A.

Particulate Sampler W N.A. NA NA c.

D N.A. R O

d. Sampler Flow Rate Monitor

7. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR Low Range Noble Gas Activity Monitor D M R(2) O(1) a.

lodine Sampler W N.A. N.A. NA

b.

Particulate Sampler W NA NA NA

c.

D N.A. R O l

d. Sampler Flow Rate Monitor

ODCM-3.0 Revision 10 Page 3.0-16 TABLE 4.3.7.12-1 (Continued)

TABLE NOTATIONS At all times.

- Not used.

During operation of the main condenser air ejector.

During operation of the standby gas treatment system.

(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. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode (alarm or type).

(2)

The initial CHANNEL CAllBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CALIBRATION, sources that have' been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.

(3) Not used.

l

! (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation occurs on high level and that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoints.

2. Circuit failure.

3. Instrument indicates a downscale failure. I

! I

4. Instrument controls not set in the operate mode (alarm or type). )

j 1

4 3 _ , 4

__. _. - . _ . . m .-. . - -.

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ODCM-3.0 Revision 10 Page 3.0-17 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS - ,

CONCENTRATION CONTROLS

.3.11.1.1 The concentration of radioactive material released in liquid effluents to ;

UNRESTRICTED AREAS (see Figure 3.0-1) shall be limited to ten times the concentration values specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.- For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/r .I total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material rcleased in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. 1 SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling 3 and analysis program of Table 4.11.1.1.1-1. -l 4.11.1.1.2 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.

I i

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1 ODCM 3.0 Revision 10 l Page 3.0-18 i

i a-TABLE 4.11.1.1.1-1 ,

2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM !

i l

A Liquid Release - Sempilng

""*" Type of ActMty ' " " * '

l Type Frequency A"*EY*I*

Frequency WW Detsction (LLD)*

(uChnt)

P P Principal Gamma 5 x 10-7 ;

Each Batch Each Batch Emitterse j A. Batch Releaseb. 1131 1 x 10-6 i Waste Sample l

Tanks (3) or P M Dissolved and 1 x 10-5 Condensate One Batch /M Entrained Gases Storage Tank (Gamma Emitters)

P M H-3 1 x 10-5 Each Batch Composite d Gross Alpha 1 x 10-7 P Q St-89, Sr-90 5 x 10-8 )

I Each Batch Composite d Fe-55 1 x 10-6 i

M Principal Gamma 5 x 10-7 NA Composited Emitterse B. Continuous 1-131 1 x 104 Releasese

Circulating W M Dissolved and 1 x jo-5 Water System (if Grab Sample Entrained Gases contaminated) (Gamma Emitters)

M H-3 1 x 10-5 Composite d Gross Alpha 1 x 10-7 O Sr-89, Sr-90 5 x 10-8 Composite d Fe-55 1 x 10-6

ODCM 3.0 Revision 10 Page 3.0-19 TABLE 4.11.1.1.1-1 (Continued)

TABLE NOTATION I l

I i aThe LLD is defined, for purposes of these controls, 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 "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66. s s I LLD = I E . V .2.22 x 10' . Y.exp (At. )

Where:

1 LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass I or volume, sois 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 106is 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, and t for plant effluents is the elapsed time between the rata,noict of sainple collection and time of counting.

Typical values of E, V, Y, and t should be used in the calettation. !

It should be recognized that the LLD is defined as an a gngd (before the fact) limit representing the capability of a measurement system and not as an a costeries (after the fact) limit for a particular measurement. j bA batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. Batch liquid discharge may be made from only one tank at a time. l l

l

ODCM-3.0 R:: vision 10 Page 3.0-20 TABLE 4.11.1.1.1-1 (Continued)

TABLE NOTATION cThe principal gamma emitters for which the LLD specification applies exclusively are:

Mn-54, Fe 59, Co-58, Co-60, Zn 65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This 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 Radioactive Effluent Release Report pursuant to Control 5.9.1.8.

dAcomposite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids ieleased. This may be accomplished through composites of '

grab samples obtained prior to discharge after the tanks have been recirculated.

eA continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release.

l l

ODCMe3.0 Revision 10 !

Page 3.0-21 l

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE I CONTROLS i 3.11.1.2 The ' dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive i materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see l l Figure 3.0-1) shall be limited: ,

l

! a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and - l to less than or equal to 5 mrems to any organ, and l

b. During any calendar year to less than or equal to 3 mrems to the total body and to )

less than or equal to 10 mroms to any organ.

l APPLICABILITY: At all 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- j days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the i cause(s) for exceeding the limit (s) and defines the corrective actions that have been ]

taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This l Special Report shall also include (1) the results of radiological analyses of the ]

drinking water source and (2) the radiological impact on finished drinking water l supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act."

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. i

. ' Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge. l i

k

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ODCM-3.0 R: vision 10 Page 3.0-22 RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT CONTROLS 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of ;

the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figuro 3.0-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquiri radwaste treatment system not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report that includes the following information:

1. Explanation cf why liquid radwaste was being discharged without complete treatment, identification of any inoperable equipment or subsystems, 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.

l

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the 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.

ODCM-3.0 Revision 10 Page 3.0-23 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. For iodine-131, iodine 133. tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

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 in the ODCM.

4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all other 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 in 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.

ODCM-3.0 Revision 10

- Page 3.0 24 s

TABLE 4.11.2.1.2-1 ,

RADtOACTWE GASEOUS WASTE SAMPUNG AND ANALYSIS PROGRAM

?:24.

T "/ f;;WAgmr semparqa j -VJSeshkunn ,QgpDpe of Aosh% .q&omerLernit of yAnalyskk 4eanous eggy my nekeen u.4 & Qf2%

m , gs'iroquencylNf%

.g amu;;p&yAnalyste mpg Q .

gg,my L-@VM

, p.oje 1

AN P,I Sl Pl , Sl PrinolpelGamma 1 x 104 PURGE (Pro Each PURGE Each PURGE L;2 ."

-T m 4 Grab Sample pl H-3 1 x 104

. B. Reactor Building /l Exhaust Plenum Staney Gas ye,e ye PrincipalGamma Emittersb 1 x 104 l7h Troelmont Systemh Grab Sample ye H3 1 x 104 C. Redweste Building PrincipalGamma Turbine Building M M Emittersb 1 x 104 Service Building Grab Sample M H-3 1 x 104 On Site Storage l Factiv i I

D. AR Release Types wg I131 1 x 1012

{ asIsted in B and C atme.

Continuousf Absorbent Sample I-133 1 x 10-10 Wg PrincipalGamma Continuousf Particulate Sample Emittersb i x jo-11 0-131. others)

M Continuousf Composite Gross Alpha j x jo 11 Particulate Sample Q

Composite Sr-80, Sr go 1 x 1011 Continuousf Particulate Sample Continuoust Noble Gas Monitor Noble Gas Gross 1 x104 I Beta or Gamma i i

E. Weste Oil P PrincipalGamma i incineration by P Each Batch Weste Emitterob 5 x 10-7 I Iqestioninto Each Batch OH M Sample 1-131 1

104 AunBaryBonerFuei Stream \

(

- . , - - , ~ . . , ,, , _ . - _ ,. _ _ , . , _ . _ .

ODCM-3.0 Revision 10 Page 3.0-25 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATION aThe LLD is defined, for purposes of these controls, 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 "real" signal.

For a particular measurement system, which may include radiochemical separation: ;

b LLD = E

V

2.22 x 10'

Y

exp (-At)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, l

l 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 106is 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, and t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an A 9.[194 (before the fact) limit representing the capability of a measurement system and not as an A postenori (after the fact) limit for a particular measurement.

'bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kre88 Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Co-141, and Co 144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8.

i

! i h

ODCM 3.0 Revision 10 l Page 3.0-26 g ,-

TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATION

] cSampling and analysis shall also be performed following shutdown, startup, or a THERMAL j POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This

requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131

concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble j gas monitor shows that effluent activity has not increased more than a factor of 3.

'd Not used. l7 i

i

Tritium grab samples shall be taken at least onca rar 7 days from the ventilation exhaust from

the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

l fThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time i period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.

j 9 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 shall also be performed at least

( once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 3 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing, under the following conditions: (1) If any release point noble gas monitor shows that effluent activity has increased more than a factor of 3, sampling shall be performed at that release point. (2) If analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary coolant has increased more than a factor of 3, sampling shall be hqf performed at the reactor building, radwsste building, turbine building, and if standby gas treatment is running, the standby gas treatment system release points. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. When aamples collected for periods between 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 7 days are analyzed, the corresponding LLDs may be increased by a factor equal to the normal weekly sample volume divided by the volume of the sample in question.

hRequired when the SGTS is in operation.

l in OPERATIONAL CONDITIONS 1,2, 3, and 4, the applicable portion of primary containment shall be sampled and analyzed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any PURGING.

lin O*ERATIONAL CONDITIONS 1,2,3, and 4, when the primary containment atmosphere radiatior monitoring system is declared INOPERABLE or is in alarm condition, the appHeable '

portion ai primary containment shall be sampled and analyzed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING thmugh other than SGTS.

t 9

ODCM-3.0 Revision 10 Page 3.0-27 RADIOACTIVE EFFLUENTS i GASEOUS EFFLUENTS DOSE - NOBLE GASES CONTROLS

(

3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the followinG':

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation 4 and less than or equal to 10 mrads for beta radiation and,

b. During any. calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION: ;

)

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 '

days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

ODCM-3.0 Revision 10 Page 3.0-28 RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all i radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be l limited to the following: l

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ. i l

\

APPLICABILITY: At all times. j ACTION:

a. With the calculated dose from the rel ease of lodine-131, iodine-133, tritium, and radionuclides in particulate form with hali 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 Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

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ODCM-3.0 Rsvision 10 Page 3.0-29 RADIOACTIVE EFFLUENTS OFF-GAS TREATMENT SYSTEM CONTROLS ,

3.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be OPERABLE and shall be in operation.

APPLICABILITY: Whenever the main condenser steam jet air ejectors are in operation.

ACTION:

a. With the OFF-GAS TREATMENT SYSTEM inoperable for more than 7 days, prepare and submit to the commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information: 1

1. Identification of the inoperable equipment or subsystems and the reason i for the inoperability, l

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, !

and i

3. Summary description of action (s) taken to prevent a recurrence.

I I

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

c. The provisions of Control 4.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.2.1,3.11.2.2, and 3.11.2.3.

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1 ODCM-3.0 Revision 10 Page 3.0-30 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM CONTROLS l I

3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM as described in the ODCM shall I be OPERABLE and appropriate portions of the system shall be used to reduce radioactive {

materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site to UNRESTRICTED AREAS (see Figure 3.0-1) would exceed 0.3 mrem to any organ in any 31-day period.

l APPLICABILITY: At all times.

l ACTION: i

a. With radioactive gaseous waste being discharged in excess of the above limits and any portion of the VENTILATION EXHAUST TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report that includes the following iriformation:

1. Identification of any inoperable equipment or subsystems, 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 Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM, when any portion of the VENTILATION EXHAUST TREATMENT SYSTEM is not in use. !

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4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.2.1,3.11.2.2, and 3.11.2.3.

ODCM-3.0 Revision 10 .

Page 3.0-31 l i

RADIOACTIVE EFFLUENTS a

VENTING OR PURGING-

\

l CONTROLS l

3.11.2.8 VENTING or PURGING of the primary containment shall be through the standby gas )

treatment system or the reactor building ventilation system.

APPLICABILITY: OPERATIONAL CONDITIONS 1,2,3, and 4 I I

ACTION:

1

a. With the requirements of the above control not satisfied, suspend all VENTING or i PURGING of the primary containment.

i

b. The provision of Controls 3.0.3 and 3.0.4 are not applicable.

SURVElli ANCE REQUIREMENTS ,

4.11.2.8.1 The applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.21 of Control 3.11.2.1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any PURGING.

4.11.2.8.2 If the primary containment radiation monitoring system is INOPERABLE or is in alarm condition, the applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.2-1 of Control 3.11.2.1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of primary containment through other than the standby gas treatment system.

4.11.2.8.3 The primary containment shall be determined to be aligned for VENTING or PURGING through the standby gas treatment system or the reactor building ventilation system '

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the containment.

4.11.2.8.4 Prior to use of the vent / purge system through the standby gas treatment system assure that:

a. Both standby gas treatment system trains are OPERABLE whenever the vent / purge system is in use, and

b. Whenever the vent / purge system is in u:e during OPERATIONAL CONDITION 1 or 2 or 3, only one of the standby gas treatment system trains may be used.

4.11.2.8.5 Prior to VENTING or PURGING, assure that at least one of the following monitors is OPERABLE: the primary containment atmosphere radiation monitor, the reactor building ventilation exhaust radiation monitor (at least one division), or the SPING monitor corresponding to the release path (the reactor building exhaust plenum radiation monitor er the standby gas treatment system radiation monitor, Division 1 or 2).

ODCM-3.0 Revision 10 l Page 3.0-32

)

RADIOACTIVE EFFLUENTS

' 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 The annual (calendar year) dose or dose commitment to any member of the public (as defined in 40 CFR Part 190) due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, i except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times. 4 ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 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 should be made :

including direct radiation contributions from the reactor units 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 Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence i of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall j i

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 release (s) 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 40 CFR Part 190 has not already been corrected, the Special Report shall include a l

request for a variance in acccrdance with the provisions of 40 CFR Part 190.

Submittal 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 Controls 3.0.3 and 3.0.4 are not applicable.

1 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 Cumulative dose contributions from direct radiation from the reactor units and from outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Control 3.11.4, ACTION a.

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ODCM 3.0 R: vision 10 Page 3.0-33 i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING i

3/4.12.1 MONITORING PROGRAM i

! CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in

. Table 3.12.1-1.

APPLICABILITY: At all times.

ACTION:

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 Radiological Environmental Operating Report required by Control 5.9.1.7, 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 3.12.1-4 2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 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 PUBLIC is less than the calendar year limits of Controls 3.11.1.2,3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12.12 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ...g 1.0 reporting level (1) reporting level (2)

When radionuclides 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 from all radionuclides is equal to or greater than the calendar year limits of Controls 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 pursuant to Control 5.9.1.7.

c. With milk or fresh leafy vegetable 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 to the radiological environmental monitoring program within 30 days. The specific locations from which samples

The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

~ _- -. _ - _. . . . .- -

1 ODCM-3.0 Revision 10 Page 3.0-34 RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS (Continued) were unavailable may then be deleted from the monitoring program. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples and identify the I new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Rcport pursuant to Control 5.9.1.8 and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE 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 figure (s) 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.

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ODCM-3.0 Revision 10 Page 3.0-35 TABLE 3.12.1-1 RADIOLOGICAL. ENVIRONMENTAL MONITORING PROGRAM Nwnber of Representative Sampling and: -

Exposure Patinvey Samples and Sample: Collection ^ Type and Frequency andor Sample Locationsa - Frequency ofAnalysis 67 routine monitoring stations, Quarterly Gamma dose quarterfy.

1. DIRECT RADIATIONb with two or more dosimeters placed as follows: 1) an inner ring of stations in the general area of the SITE BOUNDARY and additional rings at approximately 2. 5 and 10 miles, j with a station in at least every 4 other meteorological sector for each ring with the exception of those sectors over Lake Erie.

The balance of the stations,8, i should be placed in special interest areas sucn as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

2. AIRBORNE Samples from 5 locations. Continuous sampler Radiolodine Canister- l Radioiodine and operation with sample 1-131 analysis weekly.

Particulates a. 3 samples from close to the collection weekly, or 3 SITE BOUNDARY more frequently if Particulate Samoler-locations. in different sectors, required by dust Gross beta radioactivity of the highest calculated loading, analysis following filter annual average ground level change:d D/O.

Gamma kotopic

b. 1 sample from the vicinity of analysiseof composite a community having the (by location) quarterly, highest calculated annual average ground level D/O.

c. 1 sample from a control l location, as for example 15 30 km distant and in the least prevalent wind direction e,

ODCM-3.0 I I

Revision 10 Page 3.0-36 l

TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

Number of Regi::::imttve Sampling and.:

Exposure Patimey Samples andSample ; Collection- Type andFrequency andfor Sample Frequency of Analysis .

Locationsa

3. WATERBORNE

a. 1 sample upstream. Composite sample Gamma isotopic

a. Surfacef

b. 1 sample downstream, over 1-month period 9 analysisemonthly.

Composite for tntium analysis quarterly,

b. Ground Samples from 1 or 2 sources only Quarterly Gammaisotopice and if likely to be affectedh, tritium analysis quarterly,

c. Drinking 1 sample of each of 1 to 3 of 1-131 analysis on each

a. Compos,te i sampie the nearest water supplies composite when the that could be affected by its over 2-week period 9 dose calculated for the discharge. when 1-131 analysis is consumption of the performed, monthly water is greater than 1 1 sample from a control composite otherwise. mrom per year.I b.

location. Composite for gross beta and gamma isotopic analyses' monthly. Composite for tritium analysis quarterly,

d. Sediment from 1 sample from cownstream area Semiannuaffy ammaisotopic with existing or potential shoreline analysisesemiannually.

recreational value.

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ODCM-3.0 Revision 10 Page 3.0-37 TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representetive Sampling and -

Exposure Patimey Samples and Sample - Collection ' Type andFrequency andforSamp6e' Y'*4****Y ~ *f A**I Y*N* '

Mons * - .

.4. INGESTION

a. Milk a. Samples from milking Semimonthly when Gamma isotopice and -

animals in 3 locations within animals are on 1-131 analysis 5 km distance having the pasture, monthly at semimonthly when highest dose potential. If other times. animals are on pasture; there are none, then,1 monthly at other times.

sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.i

b. 1 sample from milking animals at a controllocation 15-30 km distant and in the least prevalent wind l direction.

Sample in season, or Gamma isotopic

a. 1 sample of each

b. Fish and semiannuallyif they ana, g,, on oge l commercially and Invertebrates recreationally important are not seasonal.

species in vicinity of plant discharge area.

b. 1 sample of same speciesin areas not influenced by plant discharge.

a. 1 sample of each principal At time of harvestl- Gamma isotopic

c. Food Products class of food products from analysese on edible i

any area that is irrigated by portions.

water in which liquid plant wastes have been decharged.

b. Samples of 3 different kinds Monthly when Gamma isotopic' and l of broad leaf vegetation available. 1131 analysis. !

grown nearest each of two 1

different offsite locations of highest predicted annual averagelevelO/Oif milk sampling is not performed.

c. 1 sample of each of the Monthly when Gammaisotopice and similar broad leaf vegetation available. 1131 analysis' grown 15-30 km distant in the least prevalent wind directionif milksamplingis

! not performed.

1

ODCM-3.0 Revision 10 ~

Page 3.0-38 1

TABLE 3.12.1-1 (Continued) l l

TABLE NOTATIONS aspecific 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 3.12.1-1 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 hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other J legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall 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 Contol 5.9.1.7. It is recognized that, at times, it 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 altemative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the OCCM reflecting the new location (s),

bOne 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 purpose'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.

cThe purpose of this sample is to obtain background information, if it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that have valid background data may be substituted. j dAirbome 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.

eGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

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ODCM-3.0 :

RQvision 10 ;

Page 3.0-39 i l

TABLE 3.12.1-1 (Continued)

TABLE NOTATION IThe " upstream sample" shall be taken at a distance beyond significant influence of the I

discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone.

" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.

9 Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

l hGroundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

iThe dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

lif harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

s

ODCM-3.0 Rsvision 10 l Page 3.0-40 TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Fish ANIk Food Analysis : (pCV1) Particulate or- (pCMrg, wet) : (PCUI) Products-Genes (DClhrr3 j (pCMrg, wet)

H-3 20,000*

Mn-54 1,000 30.000 Fe-59 400 10.000 1 Co 58 1,000 30.000 Co-60 300 10.000 Zn-65 300 20.000 Zr Nb-95 400 1131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 l Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 l l

For drinking water samples. This is 40 CFR Part 141 value.

4 sf 1

l 1

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ODCM-3.0 l Revision 10 l l

Page 3.0-41 TABLE 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a LOWER LIMIT OF DETECTION (LLD)b,c Water Airborne Fish nfilk Food. Sediment Analysis (pCV1) Particulate or (pCUkg, wet) (pCV1) Products . (pCVkg, dty)

Gases (pCVm3) . (PCVkg, wet):

gross beta 4 0.01 H3 2000 Mn-54 15 130 Fe-59 30 260 Co 58.60 15 130 Zn-65 30 260 Zr Nb-95 15 l-131 0.07 1 60 3d Cs-134 15 0.05 130 15 60 150 Cs 137 18 0.06 150 18 80 180 Ba-La-140 15 15

dDCM-3.0 Revision 10 Page 3.0-42 1

I TABLE 4.12.1-1 (Continued) (

l TABLE NOTATIONS l l

aThis list does not mean that only these nuclides are to be considered. Other peaks that are j identifiable, together with those of the above nuclides, shall also be analyzed and reported in the

' Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.

I bRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

I cThe LLD is defined, for purposes of these Controls, 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 "real" signal.

For a particular measurement system, which may include radiochemical separation: l LLD = E

V

2.22 x 10'

Y* exp (-At)

Where: !

LLD is the "a priori" lower limit of detection as defined above, as picocuries 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 is the number of disintegrations per minute per picocurie, l Y is the fractional radiochemical yield, when applicable, i A is the radioactive decay constant for the particular radionuclide, and t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and t should be used in the calculation.

J l

ODCM-3.0 Rsvision 10 Page 3.0-43 TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS It should be recognized that the LLD is defined as an a gngri (before the fact) limit representing the capability of a measurement system and not as an a costenori (after the fact) limit for a '

particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and >

described in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.

dLLD for drinking water samples.

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1

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ODCM 3.0

ReWaion 10 l

(' Page 3.0-44

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j RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shallidentify 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 location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Surveillance Requirement 4.11.2.3, identify the new location (s) in the next Annual Radioactive gol[

Effluent Release Report, pursuant to Control 5.9.1.8.

b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add

( the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), 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. Pursuant to Control 5.9.1.8, identify the new location (s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

c. T he provisions of Control 3.0.3 and 3.0.4 are not applicalile.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the gbwing season at least once per 12 months using that information that will provide the best results, such as by a door to-door survey, visual 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 5.9.1.7. *

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/Os

( in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1, A Part 4.c, shall be followed, including analysis of control samples.

ODCM-3.0 R : vision 10 Page 3.0-45 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

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 Radiological Environmental Operating Report pursuant to Control 5.9.1.7.

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.

l Figure 3.0-1: Map Definmg Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents ODCM-3.0 l "

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END OF SECTION 3.0

Nuclear Production - Fermi 2 ODCM-4.0 Offsite Dose Calculation Manual Flevision 7 Page 4.0-1 I

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3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, l as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be i calculated and adjusted in accordance with the methodology and parameters in the ODCM l utilizing the system design flow rates as specified in the ODCM. This conservative method is used because the Fermi 2 design does not include flow rate measurement devices. This will ensure the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General !

Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50. !

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 ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2 Column 2. This l limitation provides additional assurance that the levels of radioactive materials in bodies of j water in UNRESTRICTED AREAS will result in exposures within (1) the Section ll.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to a MEMBER OF THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in intemational Commission on Radiological Protection (ICRP)

Publication 2.

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 HASL Procedure Manual, HASL-300 (revised annually),

Curne, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Cheni. 'O,586-93 (1968), and Hartwell, J. K., " Detection Limits for ,

Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-211(June 1975).

ODCM-4.0 Revision 7 Page 4.0-3 RADIOACTIVE EFFLUENTS BASES .

3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections ll.A Ill.A and IV.A of Appendix 1,10 CFR Part 50. The control implements the guides set fort in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to 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 that 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 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based cn 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 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 1," Revision 1, October 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the liquid rs.dwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to their 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 specification implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix l to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the ll quid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose to individual MEMBERS OF THE PUBLIC from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301.

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ODCM-4.0 Rsvision 7 Page 4.0-4 RADIOACTIVE EFFLUENTS l BASES -

l l 3/4.11.2.1 DOSE RATE (Continued) l Although this control applies to the SITE BOUNDARY, the occupancy and exposure pathways applicable to a MEMBER OF THE PUBLIC who may at times be within the SITE BOUNDARY l will usually be such that such an individual will not receive significantly greater dose due to I gaseous effluents than a MEMBER OF THE PUBLIC who remains outside the SITE l BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified dose rate limits restrict, at all times, the dose rates above background to a MEMBER OF THE PUBLIC at or l - beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the skin. These dose rate limits also restrict, at all times, the thyroid dose rates above background to a child via the inhalation pathway to less l than or equal to 1500 mrems/ year.

i The required detection capabilities for radioactive materials in gaseous 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 HASL Procedures Manual. HASL-300 (revised annually),

Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH SA-215 (June 1975).

3/4.11.2.2 DOSE - NOBLE GASES This control is provided to implement the requirements of Sections ll.B Ill.A, and IV.A of Appendix 1,10 CFR Part 50. The control implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I 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 Section Ill.A of Appendix l that conformance with the guides of 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 dose calculation methodology and parameters established in the ODCM l for calculating the doses due to the actual release rates of radioactive noble gases in gaseous I effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation i of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of I l Evaluating Compliance with 10 CFR Part 50, Appendix 1," 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, i July 1977. The ODCM equations provided for determining the air doses at and beyond the l SITE BOUNDARY are based upon the historical average atmospheric conditions.

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RADIOACTIVE EFFLUENTS BASES -

3/4.11.2.3 DOSE - IODINE-131. IODINE-133. TRITIUM. AND R ADIONUCLIDES IN 3 PARTICULATE FORM This control is provided to implement the requirements of Sections ll.C, Ill.A, and IV.A of

Appendix 1,10 CFR Part 50. The controla are the guides set forth in Section ll.C of Appendix 1.

l The ACTION statements provide the requitad operating flexibility and at the same time 1 implement the guides set forth in Section !V.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is l reasonably achievable." The ODCM calculational methods specified in the Surveillance 1 Requirements implement the requirements in Section Ill.A of Appendix i that conformance with l 4 the guides of Appendix l be shown by calculational procedures based on models and data, such l

that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is I unlikely to be substantially underestimated. The ODCM calculational methodology and l

, parameters for calculating the doses due to the actual release rates of the subject materials are j consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual i Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 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 based upon the historical average atmospheric conditions. The release rate controls for iodine-131, lodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the ,

5 existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The 4

pathways that were examined in the development of these calculations were: (1) individual l inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation I with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and l meat producing animals graze with consumption of the milk and meat by man, and (4) l deposition on the ground with subsequent exposure of man.

3/4.11.2.4 OFF-GAS TREATMENT SYSTEM 'l The OPERABILITY of the OFF-GAS TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of General Design Criteria 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix i to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

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3/4.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM

!- The requirement that the appropriate portions of this system be used. when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be '

kept "as low as is reasonably achievab e." 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 Sections ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

I 3/4.11.2.8 VENTING OR PURGING This control provides reasonable assurance that releases from primary containment purging '

operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. ,

s 3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits i

of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of l

Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will desc.%e a course of action that should result in the ,

limitation of the annual dose to a member of the public to within the 40 CFR Part 190 limits. For the purpose of the Special Report, it may be assumed that the dose commitment to the member of the public from other than uranium fuel cycle sources is negligible, with the 1 exception that dose contributions from other nuclear fuel cycle facilities at the same site or l 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 40 CFR Part 190, the Special Report with a request l for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in 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.

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ODCM-4.0 l

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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 pathways and for those radionuclides tha lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix l to 10 CFR Part 50 and thereby supplements the !

I radiological effluent monitoring program by verifying that the measureable 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 exposure pathways. Guidance !

for this monitoring program is provided by the Radiological Assessment Branch Technical l Position on Environmental Monitoring. The initially specified monitoring program will be l 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 the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 are considered j optimum for routine environmental measurements in industrial laboratories. It should be r

recognized that the LLD is defined as an a p_rigr!(before the fact) limit representing the capability of a measurement system an.$ not as an a costeriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968),

and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.12.2 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 monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, from visual survey or from consulting with local agricultural l authorities shall be used. This census satisfies the requirements of Section IV.B.3 of 1 Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 ,

kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. l To determine this minimum garden size, the following assumptions were made: (1) 20% of the i garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2,

ODCM-4.0 Revision 7 Page 4.0-8 u

RA0lOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the j

measurements of radioactive material in environmental sample matrices are performed as part ,

of the quality assurance program for envircnmental monitoring in order to demonstrate that the

results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

END OF SECTION 4.0 l

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Nuclear Prcducti:n - Fsrmi 2 ODCM-5.0

Offsite Dose Calculation Manual Revision 6 Page 5.0-1 J

4 SECTION 5.0 ADMINISTRATIVE CONTROLS l

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ODCM-5.0 Revision 6 l

Page 5.0-2 ADMINISTRATIVE CONTROLS i

l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

5.9.1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The initial report shall be submitted prior to May 1 of the year following initial criticality.

l l The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental l

surveillance activities for the report period, including a comparison as appropriate, with

preoperational studies, with operational controls, and with previous environmental surveillance l reports, and an assessment of the observed impacts of the plant operation on the environment.

l The reports shall also include the results of land use censuses required by Control 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, 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 some individual results are not available for inclusion with the report, l

the report shall be submitted noting and explaining the reasons for the missing results. If possible, the missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps

covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of l licensee participation in the Interlaboratory Comparison Program, required by Control 3.12.3 discussion of all deviations from the sampling schedule of Table 3.12.1-1; and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 5.9.1.8 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous year of operation shall be submitted within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

"A siregie submittal may be made for a mutiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate i radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

ODCM-5.0 Revision 6 Page 5.0-3 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Annual Radioactive Effluent Release Report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste 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 arsd Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shall include an annual 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 measureo), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability."* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same 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 (Figure 3.0-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and 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).

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. The assessment of radiation doses shall be performed in accordance with methodology and parameters in the ODCM.

The Annual Radioactive Efluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

"In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has - ,

the option of retaining this summary of required meteoro!ogical data on site in a file that shall be provided to the NRC upon request.

ODCM-5.0 Revision 6 Page 5.0-4 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE ' EFFLUENT RELEASE REPORT (Continued)

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) as described in Technical Specification 6.14.2.c, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Control 3.12.2.

The Annual Radioactive Effluent Release Reports 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 3.3.7.11 or 3.3.7.12, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 3.11.1.4.

5.15 MAJOR CHANCES TO RADIOACTIVE LIQUID. GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS

5.15.1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the OSRO. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

Licensees may choose to submit the information called for in this Control as part of the UFSAR revision in accordance with 10 CFR 50.71(e).

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! ODCM-5.0 Revision 6 Page 5.0-5 ADMINISTRATIVE CONTROLS _.

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3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4. 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;

5. An evaluation of the change, which shows the expected maximum exposures to a MEMBER 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;

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6. 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;

7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the OSRO.

b. Shall become effective upon review and acceptance by the OSRO.

END OF SECTION 5.0

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Nuclear Production - Fermi 2 ODCM-6.0 Offsite Dose Calculation Manual Page 6.0-1 D

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T ODCM-6.0 R:vilion 7 Page 6.0-2 LIQUID EFFLUENTS 6.0 LIQUID EFFLUENTS This section summarizes information on the liquid effluent radiation monitoring instrumentation and controls. More detailed information is provided in the Fermi 2 UFSAR and Fermi 2 design drawings from which this summary was derived. This section also describes the sampling and analysis required by the Offsite Dose Calculation Manual. Methods for calculating alarm setpoints for the liquid effluent monitors are presented. Also, methods for evaluating doses from liquid effluents are provided.

6.1 Radiation Monitoring Instrumentation and Controls This section summarizes the instrumentation and controls monitoring liquid effluents. This discussion focuses on the role of this equipment in assuring compliance with the Offsite Dose Calculation Manual.

6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement i

Fermi 2 ODCM 3.3.7.11 prescribes the monitoring required during liquid releases and the backup sampling required when monitors are inoperable.

The liquid effluent monitoring instrumentation for controlling and monitoring radioactive effluents in accordance with the Fermi 2 ODCM 3.3.7.11 is summarized below:

1. Radiation Alarm - Automatic Release Termination

a. Liquid Radwaste Effluent Line - The D11 N007 Radiation Monitor on the liquid radwaste effluent line provides the alarm and automatic termination of liquid radioactive material releases prior to exceeding 1 Maximum Permissible Concentration (MPC) at the discharge to Lake Erie (ten times 10 CFR 20, Appendix B Table 2, Column 2 values) required by ODCM 3.3.7.11. The monitor is located upstream of the Isolation Valve (G11-F733) on the liquid radwaste discharge line and monitors the concentration of liquid effluent before dilution by the circulating water reservoir (CWR) decant flow.

2. Radiation Alarm (only)

a. Circulating Water Reservoir (CWR) Decant Line - The CWR Decant Line Radiation Monitor (D11-N402) provides indication of the concentration of radioactive materialin the diluted radioactive liquid releases just before discharge to Lake Erie. As required by ODCM 3.3.7.11, the alarm setpoint is established to alarm (only) prior to exceeding one MPC.

I ODCM-6.0 Revision 7 Page 6.0-3 l

l b. Condensate Storage Tank (CST) Discharge Path - The CST l Discharge Monitor provides indication of the concentration of radioactive material in the CST Discharge Path prior to dilution by the l

. circulating water decant flow. As required by ODCM 3.3.7.11, the -

alarm setpoint is established to alarm (only) prior to exceeding one MPC at the discharge to Lake E ie.

3. Flow Rate Measuring Devices )

1

a. Liquid Radwaste Effluent Line - in accordance with ODCM 3.3.7.11, the !

release rate of liquid radwaste discharges is monitored by G11-R703.

l This flow rate instrumentation is located on the radwaste discharge line prior to the junction with the CWR decant line.

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b. Circulating Water Reservoir Decant Line - in accordance with ODCM 3.3.7.11, the flow rate of the CWR decant line is monitored by

' N71 R802. The flow rate instrumentation is located on the decant line downstream of the junction with the liquid radwaste effluent line. This I instrumentation measures the total discharge flow rate from Fermi 2 I to Lake Erie.

c. Condensate Storage Tank Discharge Path - In accordance with ODCM 3.3.7.11, the flow rate of this line is monitored.

6.1.2 Non-ODCM Required Monitor An additional monitor not required by Fermi 2 ODCM is provided by Detroit Edison to reduce the likelihood of an unmonitored release of radioactive liquids.

1. General Service Water - The General Service Water (GSW) Radiation Monitor (D11-N008) provides additional control of potential radioactive affluents. D11-N008 monitors the GSW System prior to discharge into the Main Condenser circulating water discharge line to the Circulating Water Reservoir. Although not an ODCM required monitor, D11-N008 monitors a primary liquid stream in the plant that also discharges to the environment (Lake Erie via the Circulating Water Reservoir). 'ndication of radioactive material contamination in the GSW System woulii also indicate potential CWR contamination and the need to control all discharges from the CWR as radioactive effluents.

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ODCM-6.0 Rsvision 7 Page 6.0-4 6.2 Sampling and Analysis of Liquid Effluents The program for sampling and analysis of liquid waste is prescribed in the Fermi 2 Offsite -

Dose Calculation Manual Table 4.11.1.1.1-1. This table distinguishes two types of liquid releases: a) BATCH releases, defined as discrete volumes, from the Waste Sample Tanks (normally after processing through the radwaste system) or from the Condensate Storage Tank, and b) CONTINUOUS releases, from the Circulating Water Reservoir l (CWR) System, if it becomes contaminated l Continuous releases from the CWR System are via the CWR decant line to Lake Erie. l The CWR System is not expected to become contaminated. Therefore, continuous i radioactive material releases are not expected. However, the General Service Water !

(GSW) and the CWR systems interface with radioactive systems in the plant. Also, the l GSW intake is within a few hundred feet of the CWR decant line discharge to Lake Erie.

For these reasons. it is prudent to consider the GSW and the CWR a potential source of i radioactive effluents and to sample them regularly.

6.2.1 BATCH Releases Fermi 2 ODCM Table 4.11.1.1.1-1 requires that a sample representative of the tank contents be obtained before it is released. The table specifies the following program:

- Prior to sampling, the tank is isolated. The tank level is determined and this value is converted to tank volume. A pump with a known recirculation flow rate is then activated to recirculate tank contents. The pump is allowed to run for at least the time required to recirculate the tank volume twice.

- Prior to each batch release, analysis for principal gamma emitters (including all peaks identified by gamma spectroscopy)

- Once per month, analysis of one batch sample for dissolved and entrained gases (gamma emitters). (See note in Section 6.2.2 below.)

- Once per month, analysis of a composite sample of all releases that month for tritium (H-3) and gross alpha activity. (The composite sample is i required to be representative of the liquids released and sample quantities of the composite are to be proportional to the quantities of liquid discharged).

- Once per quarter, analysis of a composite sample of all releases that quarter for Strontium (Sr)-89, Sr-90, and Iron (Fe)-55.

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ODCM-6.0 Revision 7 Page 6.0-5 6.2.2 CONTINUOUS Releases Fermi 2 ODCM Table 4.11.1.1.1 1 requires that composite samples be collected from the CWR System, if contaminated. The table specifies the following sample analysis:

- Once per month, analysis of a composite sample for principal gamma emitters and for 1-131.

- Once per month, analysis of a composite sample for H-3 and gross alpha.

- Once per month, analysis of weekly grab samples (composited) for dissolved and entrained gases (gamma emitters). (See note below.)

- Once per quarter, analysis for Sr-89,-90 and Fe-55.

NOTE: Identification of noble gases that are principal gamma emitting radionuclides are included in the gamma spectral analysis performed on all liquid radwaste effluents. Therefore, the ODCM Table 4.11.1.1.1-1 sampling and analysis for noble gases in batch releases (one batch per month) and continuous releases (monthly analysis of weekly grab samples) need not be performed as a separate program. The gamma spectral analysis on each batch release and on the CWR monthly composite meets the intent of this ODCM requirement.

6.3 Liquid Effluent Monitor Setpoints Offsite Dose Calculation Manual 3.11.1.1 requires that the concentration of liquid radioactive effluents not exceed the unrestricted area MPC at the discharge point to Lake Erie. Dissolved or entrained noble gases in liquid effluents are limited to a concentration of 2 E-04 pCi/ml, total noble gas activity. ODCM 3.3.7.11 requires that radiation monitor setpoints be established to alarm prior to exceeding the limits of ODCM 3.11.1.1.

To meet this specification, the alarm setpoints for liquid effluent monitors are determined in accordance with the following equation:

gg CL(DF+ RR)

RR (6-1) where:

SP = the setpoint,in pCl/mi, of the monitor measuring the radioactivity concentration in the effluent line prior to dilution. The setpoint represents a value which, if exceeded, would result in concentrations exceeding the MPC in the unrestricted area CL = the effluent concentration limit (ODCM 3.11.1.1) corresponding to ten !

times the limits of 10 CFR Part 20.1302.b.2.1 at the discharge point in pCi/ml, defined in Equation (6-4)

ODCM-6.0 Rsvision 7 Page 6.0-6 RR = the liquid effluent release rate as measured at the radiation monitor location, in volume per unit time, but in the same units as DF, below '

DF = the dilution water flow as measured prior to the release point (Lake Erie) in volume per unit time At Fermi 2 the available Dilution Water Flow (DF) is constant for a given release, and the waste tank Release Rate (RR) and monitor Setpoint (SP) are set to meet the condition of Equation (61) for a given effluent Concentration Limit, CL.

NOTE: If no dilution is provided, SP s CL. Also, when DF is large compared to RR, then (DF + RR)-DF, and DF may be used instead of (DF + RR) as a simplification, as )

in Equation (6-5).

6.3.1 Tank Effluent Line Monitors The Liquid Radwaste Effluent Line Monitor D11-N007 provides alarm and automatic termination of releases prior to exceeding MPC. The Condensate Storage Tank Discharge Monitor provides alarm only prior to exceeding MPC.

As required by ODCM Table 4.11.1.1.1-1 and as discussed in ODCM Section 6.2.1, a sample of the liquid radwaste to be discharged is collected and analyzed by gamma spectroscopy to identify principal gamma emitting radionuclides. From the measured individual radionuclide concentrations, the allowable release rate is determined.

The allowable release rate is inversely proportional to the ratio of the radionuclide concentrations to the MPC values. The ratio of the measured concentration to MPC values is referred to as the 'MPC fraction" and is calculated by the equation:

MPCF =[ MPC i (6-2) where:

MPCF = fraction of the unrestricted area MPC for a mixture of gamma emitting radionuclides Ci = concentration cf each gamma emitting radionuclide i measured in each tank prior to release (pCi/ml)

ODCM-6.0 Revision 7 Page 6.0-7 MPCi = unrestricted area most restrictive MPC for each radionuclide 1: ten times the value from 10 CFR Part 20, Appendix B, Table 2, Column 2. For dissolved and entrained noble gases an MPC value of 2E-04 pCi/ml may be used, but noble gases need not be included in this calculation.

Including noble gases in Equation (6-2) eliminates the need for a separate evaluation of compliance with the noble gas concentration limit of ODCM 3.11.1.1. 1 Based on the MPCF, the maximum allowable release rate can be calculated by the following equation:

SF MAX RR S (MPCF * (l + BF))+ H3MPCF (6-3) where:

MAX RR = maximum acceptable waste tank discharge rate (gal / min)

(Monitor #G11-R703)

DF = dilution flow rate from the CWR as observed from the Control Room readout (gal / min) (Monitor #N71-R802)

SF = administrative safety factor to account for variations in monitor response and flow rates. A SF value of 0.5 is suggested because it provides for 100% variation caused by statistical j fluctuation and/or errors in measurements.

BF = conservative estimate of the ratio of the MPC fraction of pure beta emitters other than tritium to the gamma MPC fraction (MPCF) (The value 0.10 may be used for BF.)

MPCF = As previously defined by equation (6-2)

H3MPCF = conservative estimate of MPC fraction due to tritium (The value 0.13 may be used for H3MPCF.)

NOTE: Equation (6-3) is valid only for MPCF >1; if the MPCF s1, the waste tank concentration meets the limits of 10 CFR Part 20 without dilution, and the tank may be discharged at the maximum rate, l

if MAX RR as calculated above is greater than the maximum discharge pump capacity, the pump capacity should be used in establishing the actual Release Rate RR for the radwaste discharge. For a Waste Sample Tank, the maximum discharge rate is 50 gallons per minute. This Release Rate RR is monitored in the Radwaste Control Room by G11-R703.

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ODCM-6.0 Revision 7 Page 6.0-8

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The Concentration Limit (CL) of a liquid radwaste discharge is the same as the effective MPC for the radionuclide mixture of the discharge. Simply, the CL (or effective M.PC) represents the equivalent MPC value for a mixture of

' radionuclides evaluated collectively. The equation for determining CL is:

CL =

MPCF (6-4)

Based on the Release Rate RR and Dilution Flow DF and by substituting Equation (6-4) for CL in Equation (6-1) and introducing sensitivity factors and factors to account for the presence of pure beta emitters, the alarm setpoint is calculated by the equation:

SP s [(C,

SEN,)* DF

H 3F

SF + Bkg -

MPCF* (1 + BF)* RR (6-5) where:

SP = setpoint of the radiation monitor counts per second (eps) or counts per minute (cpm)

Ci = concentration of radionuclide i as measured by gamma spectroscopy (pCi/ml)

SENi = monitor sensitivity for radionuclide i based on calibration curve (cps /(pCl/ml) or epm /(pCi/ml)) or single conservative value for all radionuclides (see below)

RR = actual release rate of the liquid radwaste discharge (gal / min)

BF = pure beta factor as defined for Equation (6-3)

MPCF = MPC fraction as determined by Equation (6-2)

H3F = correction factor to account for estimated tritium concentration at the discharge point (The value 0.99 may be used.)

Bkg = background reading of monitor (cps)

DF = dilution flow rate of Circulating Water Decant Line as observed from Control Room readout (gal / min) monitor #N71-R802. See note preceding Section 6.3.1.

SF = 1.0 when a single conser'vative sensitivity value is used; 0.5 when individual nuclide sensitivity factors are used

ODCM-6.0 l R vision 7 Page 6.0-9 The sensitivity of Cr-51 determined from the primary calibration sensitivity curves may be used as a single conservative value for SENi above. The Cr-51 sensitivity has been determined to be conservative based on the nuclide mixes which have been seen in actual liquid discharges from Fermi 2. For the D11- l N007 monitor, a monitor sensitivity value of 1.0 E6 cps /(pCl/ml) may be used as )

the single conservative value of SENi, and for the CST Discharge monitor, a l single value of 1.6 E7 cpm /(pCi/ml) may be used. l If no radionuclides are measured by gamma spectroscopy, the alarm setpoint can be established at one half the setpoint of the most recent discharge for which radionuclides were detected by gamma spectroscopy.

l Prior to conducting any batch liquid radwaste release, Equation (6-3) is used to determine the allowable release rate in accordance with ODCM 3.11.1.1.

Equation (6-5) is used to determine the alarm setpoint in accordance with ODCM 3.3.7.11.

6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (D11-N402)

ODCM 3.3.7.11 requires that the setpoint for the CWR Decant Line Radiation l Monitor D11-N402 be estab!ished to ensure the radioactive material concentration in the decant line prior to discharge to Lake Erie does not exceed i MPC, unrestricted area (ten times 10 CFR 20, Appendix B, Table 2, Column 2 values). The approach for determining the alarm setpoint for the CWR Decant Line Radiation Monitor is the same as presented in Section 6.3.1. However, the CWR Decant Line Radiation Monitor setpoint need not be changed prior to each release. Equation (6-1) remains valid, except that, for the CWR Decant Line Monitor, the dilution flow previously assumed for diluting the BATCH liquid radwaste effluents is now the release rate. There is no additional dilution prior to discharge to Lake Erie. Thus, Equation (6-1) simplifies to:

SPs CL (6-6)

Substituting Equation (6-4) for CL and introducing a safety factor, sensitivity factors, and monitor background, the D11-N402 alarm setpoint can be calculated by the equation:

SP s -[(C,

SEN,)* SF+ Bkg MPCF (6-7)

l ODCM-6.0 i Rsvision 7 l Page 6.0-10 l where:

SP = setpoint in counts per minute (cpm) l Ci = concentration of each radionuclide i in the CWR decant line effluent (pCi/ml)

SENi = monitor sensitivity for nuclide i based on calibration curve (cpm /(pCi/ml))

MPCF = MPC fraction as determined by Equation (6-2) with Ci defined as for Equation (6-7) l SF = 0.5, administrative safety factor Bkg = background reading of monitor (cpm)

Normally, only during periods of batch liquid radwaste discharges will there exist any plant-related radioactive material in the CWR decant line.

6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 The D11-N402 setpoint could be adjusted for each BATCH release as is done l for the liquid radwaste effluent line monitor. Based on the measured levels of l radioactive material in a BATCH liquid release, the alarm setpoint fon D11-N402 could be calculated using Equation (6-7). However, during these planned releases, the concentrations will almost always be so low (due to dilution) that the D11-N402 Monitor will not indicate measurable levels. The CWR decant line l

design flow is 10,000 gpm; and the maximum liquid radwaste release rate is 50 gpm, previding a 200:1 dilution. The radioactive material concentration of l BATCH liquid releases is typically in the range of 10-7t o 104 pCl/ml. With a i nominal 200:1 dilution (actual dilution has been greater since in actual releases the decant line flow rate has been about 18,000 gpm), the CWR decant line monitor would monitor diluted activity in the range of 5 x 10-10 to 5 x 10-7 pCi/ml. D11-N402 Monitor response at these levels would be 0.1 to 100 cpm, depending on the particular radionuclide mixture and corresponding instrument response. These response levels are less than the monitor background levels.

In lieu of routinely adjusting the D11-N402 setpoints, generic, conservative setpoints have been established based on an analysis of nuclides seen in actual liquid discharges and on the primary calibration sensitivity curve.

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ODCM-6.0 R@ vision 7 Page 6.0-11 6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors Levels of radioactive material detectable above background at Radiation Monitor D11 N008 would be one of the first indicators of contamination of the General Service Water (GSW) System and the CWR. Likewise, for the Residual Heat Removal (RHR) System, the D11-N401 A and B Monitors would be one of the first indicators of contamination and subsequent contamination of the CWR.

Therefore, to provide early indication and assure prompt attention, the alarm setpoints for these monitors should be established as close to background as possible without incurring a spurious alarm due to background fluctuations. This level is typically around three times background, if the GSW System or RHR System becomes contaminated,it may become necessary to raise the radiation monitor setpoints. The alarm setpoints should be re-evaluated to provide the CR operator a timely indication of further -

increasing activity levels in the GSW or RHR System without spurious alarms.

The method for this re-evaluation is the same as described above - the alarm setpoint established at three times its current reading. No regulatory limits apply for establishing a maximum value for these alarm setpoints since these monitors are located on plant systems and do not monitor final release points to the environment. However, as a practical matter, upper limits on the alarm setpoints can be evaluated using the methods of ODCM Section 6.3.1 based on the actual system flows, dilution and release paths in effect at the time.

6.3.5 Alarm Response - Evaluating Actual Release Conditions Normally, liquid release rates are controlled and alarm setpoints are established to ensure that the release does not exceed the concentration limits of ODCM 3.11.1.1 at the discharge to Lake Erie. However,if either Monitor D11-N007 or D11-N402 or the CST Discharge Monitor alarms during a liquid release, it becomes necessary to re-evaluate the release conditions to determine compliance with ODCM 3.11.1.1 Following an alarm, the actual release conditions should be determined. Radioactive material concentrations should be evaluated by sampling the effluent stream or resampling the waste tank.

Discharge flow and dilution water flow should be redetermined.

To perform this evaluation, the following equation may be used for all nuclides, or dissolved and entrained noble gases may be evaluated separately from other nuclides using this equation:

C, ', RR , (1 + BF)

_ <MPCu DF+ RR H3F _

(6-8)

l ODCM 6.0 R vision 7 Page 6.0-12 where:

Ci = measured concentration of radionuclide i in tre sfiiuc9t

stream (pCl/ml)

MPCi = the MPC value for radionuclide i: ten times the 10 CFR 20, Appendix B, Table 2 Column 2 value (pCi/ml); 2 E-04 pCl/mi for dissolved or entrained noble gases RR = actual release rate of the liquid effluent at the time of the alarm, 9Pm DF = actual dilution circulating water flow at the time of the release alarm, gpm j H3F,BF = as previously defined NOTE: For alarm on D11-N402 (CWR decant line), the Release Rate RR is the Dilution Water Flow DF and the DF term drops out of the equation.

6.3.6 Liquid Radwaste Monitor Setpoint Determination with Contaminated Circulating Water Reservoir in the event the CWR is determined to contain radioactive material, the effective dilution capacity of the CWR is reduced as a function of the MPCF. To determine the available dilution flow capacity the MPCF for the CWR is determined using equation (6-2). The MPCF of the CWR is used to determine the available dilution flow as follows:

CWR Dilution Flow = CWR Decant Flow Rate (GPM) * (1-CWR MPCF)

(6-9)

The resulting dilution flow rate is substituted in equation (6-3) to determine the maximum allowable release rate for discharges from the radwaste system.

Substituting the available CWR dilution flow from equation (6-9), the Liquid Radwaste Monitor maximum release rate can be determined using equation (6-3).

Once the available dilution flow and maximum allowable release rate have been determined the radwaste monitor setpoint can be determined using equation (6-5),

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ODCM-6.0 Rsvision 7 ,

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6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases The GSW Radiation Monitor (D11-N008) provides an indication of contamination of this I system. The Monitors D11-N401 A and B perform this function for the RHR System. !

Also, the CWR Decant Line Radiation Monitor monitors all liquid releases from the plant and would record any release to Lake Erie from either of these systems if contaminated.-

As discussed in ODCM Section 6.2.2, sampling and analysis of the CWR System is required only if this system is contaminated, as would be indicated by D11-N402 or D11- )

N008. Nonetheless, periodic samples are collected from the CWR System to verify absence of contamination. Although not required by the ODCM, periodic sampling and l analysis of the RHR System is also performed since it also is a potential source of I contamination of the CWR and subsequent releases to Lake Erie if contamination is found, further releases from the applicable system (GSW or RHR) via the CWR decant line must be evaluated and controlled to ensure that releases are maintained ALARA.

The following actions will be considered for controlling releases.

- Sampling frequency of the applicable source (GSW or RHR System) and the CWR will be increased until the source of the contamination is found and controlled. This frequency may be relaxed after the source of contamination has been identified and isolated.

- Gamma spectral analysis will be performed on each sample.

- The measured radionuclide concentrations from the gamma spectral analysis will 1 be compared with MPC (Equation 6-2) to ensure releases are within the limits of !

ODCM 3.11.1.1. ]

- Based on the measured concentrations, the setpoint for the CWR Decant Line Radiation Monitor (D11-N402) will be determined as specified in Section 6.3.2. If i the calculated setpoint based on the measured distribution is greater than the current setpoint (see ODCM Section 6.3.3) no adjustment to the setpoint is required.

- Samples will be composited in accordance with ODCM Table 4.11.1.1.1-1 for monthly analysis for H-3 and gross alpha and for quarterly analysis for Sr-89,90 and Fe-55. ;

- Each sample will be considered representative of the releases that have l occurred since the previous sample. For each sample (and corresponding ;

release period), the volume of liquid released to the lake will be determined based on the measured CWR decant line cumulative flow.

- From the sample analysis and the calculated volume released, the total radioactive material released will be determined and considered representative of the release period. Cumulative doses will be determined in accordance with ODCM Section 6.5.

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ODCM-6.0 ,

Revision 7

Page 6.0-14 1

6.5 Liquid Effluent Dose Calculation - 10 CFR 50 l The parameters of the liquid release (or estimated parameters, for a pre-release ,

i calculation) may be used to calculate the potential dose to the public from the release (or ,

planned release). The dose calculation provides a conservative method for estimating the impact of radioactive effluents released by Fermi 2 and for comparing that impact against j limits set by the NRC in the Fermi 2 ODCM. The limits in the Fermi 2 ODCM are specified i as quarterly and calendar year limits. This assures that the average over the year is kept as low as reasonably achievable.

6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents i

l ODCM 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE

PUBLIC from radioactive materials in liquid effluents from Fermi 2 to

during any calendar quarter; i s 1.5 mrem to total body j s 5.0 mrem to any organ k

{

- during any calendar year; ,

j s 3.0 mrem to total body

< 10.0 mrem to any organ ODCM 4.11.1.2 requires that quarterly and annual cumulative dose due to liquid j effluents be determined at least once per 31 days. The calculation of the

potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive i material releases to the lake, the subsequent transport and dilution in the i exposure pathways, and the resultant individual uptake. At Fermi 2, pre-operational evaluation of radiation exposure pathways indicated that doses from j consumption of fish from Lake Erie provided the most conservative estimate of j doses from releases of radioactive liquids. However, with the proximity of the j water intake for the City of Monroe, it must be assumed that individuals will consume drinking water as well as fish that might contain radioactivity from discharges into Lake Erie.

Study of the currents in Lake Erie indicates that the current in the Lagoona Beach embayment carries liquid effluents from Fermi 2 north along the coast part of the time and south along the coast part of the time. When the current flows north, liquid effluents are carried away from the Monroe Water Intake, so only the fish consumption exposure pathway must be considered.

When the current flows south, toward the Monroe Water intake, both fish consumption and drinking water consumption exposure pathways must be considered. To ensure conservatism in the dose modeling, the combined fish and drinking water pathway is used for evaluating the maximum hypothetical dose to a MEMBER OF THE PUBLIC from liquid radioactive effluents. The following calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Fermi 2:

ODCM-6.0 R: vision 7 Page 6.0-15

[(C,*4)

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D* = ' DF*Z (6-10) where:

Do = dose or dose commitment to organ o or total body (mrem) due to ,

release of a single tank Aio = site-specific ingestion dose commitment factor to the total body or any organ o for radionuclide I (mrem /hr per pCl/ml)

Ci = concentration of radionuclide iin undiluted liquid effluent representative of the volume VOL (pCl/ml)

VOL = total volume of liquid effluent - 2d (gal)

DF = average dilution water flow (CWR decant line) during tank release (gal / min)

Z = 5, near field dilution factor (Derived from Regulatory Guide 1.109, Rev 0) 1.67 E-02 = 1 hr/60 min The site-specific ingestion dose / dose commitment factors (Aio) represents a 3 composite dose factor for the fish and drinking water pathway, The site-specific )

dose factor is based on the NRC's generic maximum individual consumption rates. Values of Aio are presented in Table 6-1. They were derived in i accordance with guidance of NUREG-0133 from the following equation:

A, = 1.14 E + 05 [(U, / D,)+(U,.

BE)[ DE (6-11)'

where:

UF = 21 kg/yr adult fish consumption UW = 730 liters /yr adult water consumption DW = 15.4, additional dilution from the near field to the water intake for the City of Monroe (Net dilution factor of 77 from discharge point to drinking water intake, Fermi 2 UFSAR, Chapter 11, Table 11.2-11)

BFi = Bloaccumulation factor for radionuclide i in fish from Table 6-2 (pCl/kg per pCI/ liter)

l ODCM-6.0 l Revision 7 l Page 6.0-16 l DF-i = dose conversion factor for nuclide i for adults in organ o from

. Table E 11 of Regulatory Guide 1.109 (mrem /pCl) 1.14 E + 05 = 10MpCi/ uCl)

10'(ml/ kg) 8760 (hr / yr)

- The radionuclides included in the periodic dose assessment required by ODCM 3.11.1.2 are those identified.by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of ODCM Table 4.11.1.1.1-1._ In keeping with the NUREG-0133 guidance, the adult age group represents the maximum exposed individual age group. Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of ODCM 3.11.1.2. The dose analysis for radionuclides requiring radiochemical analysis will be performed after receipt of results of the analysis of the composite samples. In keeping with the required analytical frequencies of ODCM Table 4.11.1.1.1-1, tritium dose analyses will be performed at least monthly; Sr-89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.

6.5.2 ' Simplified Liquid Effluent Dose Calculation In lieu of the individual radionuclide dose assessment presented in Section 6.5.1, the following simplified dose calculation may be used for demonstrating compliance with the dose limits of ODCM 3.11.1.2. (Refer to Appendix A for the derivation of this simplified method.) Equations (6-12) and (6-13) are to be applied to the release of a single tank.

Total Body D = 9.69 E + 03 *VOL QC; (6 12)

Maximum Organ D. = 1.18 E + 04

VOL , C, l (6-13)

I n-_--._-___.-_.

ODCM 6.0 Rgvision 7 l

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where:

Ci = concentration of radionuclide iin undiluted liquid effluent representative of the volume VOL ( Ci/ml)

VOL = volume of undiluted liquid effluent released (gal) l DF = average dilution water flow (CWR decant line) during tank release (gal / min) l Z = 5, near field dilution factor (derived from Regulatory Guide )

1.109, Rev 0) j 1

Db t = conservatively evaluated total body dose (mrem)

Dmax = consarvatively evaluated maximum organ dose (mrem)

9.69 E + 03 = 0.0167 (hr/ min)

5.80 E + 05 (mrem /hr per pCi/ml, Cs-134

! totc! body dose factor from Table 6.0-1) 1.18 E + 04 :- 0.0167 (hr/ min)

7.09 E + 05 (mrem /hr per pCl/mi, Cs-134 liver dose factor from Table 6.0-1) 6.5.3 Contaminated CWR System - Dose Calculation if the CWR System becomes contaminated, releases via the CWR System to Lake Erie must be included in the evaluation of the cumulative dose to a MEMBER OF THE PUBLIC as required by ODCM 3.11.1.2. ODCM Section 6.4 described the methods for quantifying and controlling releases from the CWR System.

For calculating the dose to a MEMBER OF THE PUBLIC, Equation (6-10) remains applicable for releases from the GSW System with the following assumptions:

- DF, Dilution Flow, is set equal to the average CWR decant line flow rate over the release period.

- Ci, Radionuclide Concentration, is determined as specified in ODCM Section 6.4.

- VOL, Volume Released, is set equal to the total volume of the discharges to Lake Erie via the CWR decant line as specified in Section 6.4.

l l

f ODCM-6.0 i Rsvision 7 Page 6.0-18 6.6 Liquid Effluent Dose Projections l 10 CFR 50.36a requires licensees to maintain and operate the Radwaste System to l

ensu.o rr%ses are maintained ALARA. This requirement is implemented through OD'iiO V,1.3. This section requires that the Liquid Radioactive Waste Processing l

System be used to reduce the radioactive material levels in the liquid waste prior to ,

release vehen the projected dose in any 31 day period would exceed:

l

- 0.06 mrem to the total body, or ,

l

- 0.2 mrem to any organ Whr.n the projected doses exceed either of the above limits, the waste must be processed i by the Liquid Radwaste System prior te release. This dose criteria for processing is established at one forty eighth of the design objective rate (3 mrem /yr, total body or 10 mrem /yr any organ)in any 31 day period.

The aorticable Liquid Waste Processing System for maintaining radioactive material releases ALARA is the Mixed Bed Domineralizers as delineated in Figure 6-1. Altemately, the Waste Evaporator (presented in the Fermi 2 UFSAR, Section 11.2) can be used to -

meet the NRC ALARA design requirements. It may be used in conjunction with or in lieu l of the Mixed Bed Domineralizers to meet the waste processing requirements of ODCM 3.11.1.3.

Each BATOH release of liquid radwaste is evaluated to ensure that cumulative doses are maintained ALARA. In keeping with the requirements of ODCM 3.11.1.3, dose projections are made at least once per 31 days to evaluate the need for additional radwaste j processing to ensure future releases are maintained ALARA. ;

The following equations may be used for the dose projection calculation: :

l D, = D (31/ d) ,

D., = D.(31/ d)

(6-15) ;

where:

Dtbp = the total body dose projection for the next 31 day period (mrem)

NOTE: The reference calendar quarter is normally the current calendar quarter. If there l

' have been liquid releases in the previous quarter but not in the current quarter, !

the previous quarter should be used as the reference calendar quarter.

Dtb = the cumulative total body dose for all releases to date in the reference L

! calendar quarter (normally the current quarter) as determined by equation (6-10) or (6-12) (mrom)

!l

- ,, - . - - - - - - - e .-

. . . . . . _ . _ _ . . - - - . - . ~ . _ _ . - .- . .. . . .

ODCM-6.0 -

Revision 7 ;

Page 6.0-19 !

Dmaxp = the maximum organ dose projection for the next 31 day period (mrem) ,

Dmax = the cumulative maximum organ dose for all releases to date in the reference calendar quarter as determined by Equation (6-10) or .

(6-13) (mrem) t d = the number of days from the beginning of the reference calendar quarter t to the date of the dose projection evaluation, ;

31 = the number of days in projectioq in the case of Condensate Storage Tank releases only, it may be possible to make an accurate ,

dose projection without relying entirely on releases during the reference calendar quarter. If the ,

above equations are not used for the portion of the dose projection pertaining to CST releases, the method used shall be in accordance with the dose projection procedure. !

l i

l l

i i

l

t I l

I ODCM-6.0 l Revision 7 Page 6.0-20 1

[ TABLE 6.01 ]

Fermi 2 Sit'e Specific Liquid Ingestion Dose Commitment Factors !

! Ai o (mrom/hr per uCi/ml) i l

1 l i

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-Lu l 1

l H-3 - 7.94E 1 7.94E 1 7.94E 1 7.94E-1 7.94E-1 7.94E 1 l l C 14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 l N S-24 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 i P-32 1.39E+6 8.62E+4 5.36E+4 - - -

1.56E+5 -l l

Cr51 - - 1.29E+0 7.70E-1 2.84E-1 1.71 E+0 3.24E+2 l 1

Mn-54 - 4.40E+ 3 8.40E+2 - 1.31 E+3 -

1.35E+4 Mn-56 - 1.11 E+2 1.96E+1 - 1.41 E+2 - 3.53E+3 F:-55 6.73E+2 4.65E+2 1.08E+2 - -

2.59E+2 2.67E+2 FF59 1.06E+3 2.50E+3 9.57E+2 - - 6.98E+2 8.32E+3 l- Co-57 - 2.19E+1 3.64E+1 - - -

5.55E+2 l

Co 58 - 9.32E+1 2.09E+2 - - -

1.89E+3 l Co-60 - 2.68E+2 5.90E+2 - - - 5.03E+3 Ni-63 3.18E+4 2.21 E+3 1.07E+3 - - -

4.60E+2 j Ni-65 1.29E+2 1.68E+1 7.66E+0 - - - 4.26E+2 l Cu-64 - 1.04E+1 4.89E+0 - 2.63E+1 - 8.88E+2 Zn-65 2.32E+4 7.38E+4 3.34E+4 - 4.94E+4 -

4.65E+4 Zn-69 4.94E+1 9.44E+1 6.57E+0 - 6.14E+1 - 1.42E+1 l Br-82 - - 2.28E+3 - - - 2.62E+3 Br-83 - - 4.06E+1 - - -

5.85E+1 Br-84 - - 5.27E+1 - - -

4.13E-4 l

l Br-85 - - 2.16E+0 - - -

1.01 E-15 i Rb-86 - 1.01 E+5 4.71 E+4 - - -

1.99E+4 Rb-88 - 2.90E+2 1.54E+2 - - - 4.01 E-9 Rb-89 - 1.92E+2 1.35E+2 - - -

1.12E-11 Sr 89 2.38E+4 - 6.83E+2 - - - 3.81 E+3 St-90 5.85E+5 - 1.44E+5 - - - 1.69E+4 Sr-91 4.38E+2 - 1.77E+1 - - -

2.09E+3 Sr92 1.66E+2 - 7.18E+0 - - -

3.29E+3 Y-90 6.28E 1 - 1.68E-2 - - -

6.66E+3 Y.91m 5.93E 3 - 2.30E-4 - - - 1.74E 2 Y 91 9.20E+0 - 2.46E 1 - - - 5.06E+3 Y 92 5.51 E-2 - 1.61 E-3 - - - 9.66E+2 Y 93 1.75E-1 - 4.83E-3 - - -

5.55E+3 Zr 95 4.04E 1 1.30E 1 8.78E-2 - 2.04E 1 - 4.11E+2 Zr 97 2.24E 2 4.51 E-3 2.06E 3 - 6.81 E-3 - 1.40E+3 Nb-95 4.47E+2 2.49E+2 1.34E+2 - 2.46E+2 - 1.51 E+6 Nb 97 3.75E+0 9.48E-1 3.46E-1 - 1.11 E+0 - 3.50E+3 Mo-99 - 1.26E+2 2.41 E+1 - 2.86E+2 - 2.93E+2 l

i Tc-99m 1.02E 2 2.88E-2 3.67E-1 - 4.38E 1 1.41E 2 1.71 E+1 Tc-101 1.05E-2 1.51 E-2 1.48E-1 - 2.72E-1 7.73E 3 4.54E-14 i

4 f

I

ODCM 6.0 Revision 7 Page 6.0-21 1 i

TABLE 6.0-1 i Fermi 2 Sit'e Specific Liquid Ingestion Dose Commitment Factors Ago (mrom/hr per uCl/ml) 1 1

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI :

.1 Ru-103 5.43E+0 - 2.34E+0 - 2.07E+1 - 6.34E+2 l Ru-105 4.52E-1 - 1.78E 1 - 5.84E+0. - 2.76E+2 Ru-106 8.07E+1 - 1.02E+1 - 1.56E+2 -

5.22E+3 Rh 103m - - - - - - -

Rh-106 - .

Ag 110m 1.75E+0 1.61 E+0 9.59E 1 - 3.17E+0 -

6.59E+2 i Sb 124 2.18E+1 4.13E 1 8.66E+0 5.29E 2 -

1.70E+1 6.20E+2 Sb-125 1.40E+1 1.56E-1 3.32E+0 1.42E-2 -

1.08E+1 1.54E+2 Ts 125m 2.58E+3 9.35E+2 3.46E+2 7.76E+2 1.05E+4 -

1.03E+4 TG 127m 6.52E+3 2.33E+3 7.94 E+2 1.67E+3 2.65E+4 -

2.19E+4

. To 127 1.06E+2 3.80E+1 2.29E+1 7.85E+1 4.31 E+2 -

8.36E+3 Te 129m 1.11 E+4 4.13E+3 1.75E+ 3 3.80E+3 4.62E+4 - 5.58E+4 Te-129 3.02E+1 1.14E+1 7.37E+0 2.32E+1 1.27E+2 -

2.28E+1 ;

Te-131m 1.67E+3 8.15E+2 6.79E+2 1.29E+3 3.25E+3 -

8.09E+4 Te-131 1.90E+1 7.93E+0 5.99E+0 1.56E+1 8.31 E+1 - 2.69E+0 ;

Te-132 2.43E+3 1.57E+3 1.47E+3 1.73E+3 1.51 E+4 -

7.42E+4 l-130 3.12E+1 9.21 E+1 3.64E+1 7.81 E+3 1.A4E+2 - 7.93E+1 1131 1.72E+2 2.46E+2 1.41 E+2 8.06E+4 4.21 E+2 -

6.49E+1 1-132 8.39E+0 2.24E+1 7.85E+0 7.85E+2 3.57E+1 - 4.21 E+0 1-133 5.87E+1 1.02E+2 3.11 E+1 1.50E+4 1.78E+2 - 9.17E+1 1-134 4.38E+0 1.19E+1 4.26E+0 2.06E+2 1.89E+1 - 1.04E-2 t 1135 1.83E+1 4.79E+1 1.77E+1 3.16E+3 7.68E+1 - 5.41 E+1 Cs 134 2.98E+5 7.09E+5 5.80E+5 - 2.30E+5 7.62E+4 1.24E+4 Cs-136 3.12E+4 1.23E+5 8.87E+4 - 6.85E+4 9.40E+3 1.40E+4 Cs 137 3.82E+5 5.22E+5 3.42E+5 - 1.77E+5 5.90E+4 1.01 E+4 !

Cs 138 2.65E+2 5.22E+2 2.59E+2 - 3.84E+2 3.79E+1 2.23E-3 '

Ba 139 1.45E+0 1.04E 3 4.25E 2 - 9.68E-4 5.87E-4 2.58E+0 Ba 140 3.04E+2 3.82E-1 1.99E+1 - 1.30E 1 2.19E 1 6.26E+2 Ba 141 7.06E-1 5.33E-4 2.38E 2 - 4.96E-4 3.03E-4 3.33E 10 Ba-142 3.19E-1 3.28E-4 2.01 E-2 - 2.77E-4 1.86E 4 4.49E 19 La-140 1.63E-1 8.22E-2 2.17E-2 - - - 6.04E+3 La-142 8.35E-3 3.80E-3 9.46E-4 - - -

2.77E+1 Co-141 7.30E-2 4.94E 2 5.60E-3 - 2.29E-2 - 1.89E+2 Co-143 1.29E-2 9.51 E+0 1.05E-3 - 4.19E-3 - 3.56E+2 Co 144 3.81 E+0 1.59E+0 2.04E 1 - 9.44E-1 - 1.29E+3 Pr 143 6.00E 1 2.41 E-1 2.98E-2 - 1.39E-1 -

2.63E+3 Pr144 1.96E 3 8.16E 4 9.98E-5 - 4.60E-4 - 2.83E-10 Nd-147 4.10E-1 4.74E 1 2.84E-2 -

2.77E-1 - 2.28E+3

' W 187 2.96E+2 2.48E+2 8.66E+1 - - - 8.12E+4 :

Np-239 3.49E 2 3.43E 3 1.89E-3 - 1.07E-2 - 7.04E+2

ODCM-6.0 Revision 7 Page 6.0-22 TABLE 6.0 2 Bioaccumulation Factors (BFi)

(pCi/kg per pCi/ liter)*

Element Freshwater Fish H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 3.0E+03 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 l l

Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 )

Nb 3.0E+04 i Mo 1.0E+01 l i

Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 Te 4.0E+02 l 1.5E+01 l Cs 2.0E+03 l Ba 4.0E+00 l La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W 1.2E+03 Np 1.0E+01 l

Values in this table are taken from Regulatory Guide 1.109 except for phosphorus, which is adapted from NUREG/CR-1336, and silver and antimony, which are taken from UCRL 50564, Rev 1 October 1972.

ODCM-6.0 Revision 7 l'. ige (,0- 23 FIGURE 6.0-1 Liquid Radioactive Effluent Monitoring and Processing Diagram S'".

T = ^

a

^ _

'a

= -

-@" N $

s g =

. ==

m m

^

mu , um 9 no 6 i M rp <

f Y "

1 ik

=-

^

.d. - ' '

M tTi M

=, = - >r--

a

_ . ,] 2","

u-

'm w Note: This diagram does not show the discharge path from Condensate Storage Tank.

END OF SECTION 6.0

Production - Fermi 2 ODCM-7.0 l Offsite Dose Calculation Manual Revision 8 Page 7.0-1 l

l GASEOUS EFFLUENTS l l

7.0 GASEOUS EFFLUENTS 7.1 Radiation Monitoring Instrumentation and Controls 7.1.1 Effluent Monitoring - Ventilation System Releases The gaseous effluent monitoring instrumentation required at Formi 2 for l controlling and monitoring radioactive effluents are specified in ODCM 3.3.7.12.

l The monitoring of each identified gaseous effluent release point must include the following. )

i 1

- Noble Gas Activity Monitor i - lodine Sampler (sample cartridge containing charcoal or silver zeolite) l l - Particulate Sampler (filter paper) l Sampler Flow Rate Monitor l

Meeting these requirements, a total of seven Eberline SPING Monitoring Systems are installed on the six gaseous release points (Onsite Storage Facility, Service Building, Radwaste Building, Turbine Building, Reactor Building Exhaust Plenum, and Standby Gas Treatment System Division 1 and Division 2). The l SPING Monitor outputs are recorded electronically in the CT-2B Control Terminal l in the Main Control Room.

l In general, a reading exceeding the High alarm setpoint of the SPING Monitors causes an alarm in the Control Room. Fermi 2 ODCM Table 3.3.7.12-1 identifies these alarm functions.

7.1.2 Main Condenser Offgas Monitoring ODCM Table 3.3.7.12-1 and Technical Specification Table 3.3.7.12-1 specify monitoring requirements for the Offgas System at the 2.2 minute delay line. The following monitors are required:

l f

1 l

_ _ _ _ _ _ _ _ _ _. ~ -_ _ _ . . _ __ _ _ . _ _ _ _

ODCM-7.0 Revision 8 Page 7.0-2 l Hydrogen Monitor - used to ensure the hydrogen concentration in the Offgas Treatment System is maintained less than 4% by volume as -

requited by Technical Specification 3.11.2.6.

Noble Gas Activity Monitor - used to ensure the gross activity release rate is maintained within 340 millicuries per second after 30 minute decay as l required by Technical Specification 3.11.2.7. j These two monitors perform safety functions. The Hydrogen Monitor monitors the potential explosive mixtures in the Offgas System. The Noble Gas Monitor monitors the release rate from the main condenser ensuring i doses at the exclusion area boundary will not exceed a small fraction of the !

limits of 10 CFR 100 in the event this effluent is inadvertently discharged directly to the environment bypassing the Offgas Treatment System.

7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic) ;

The Gulf Atomic Monitors (D11-N408 and 410) on the Reactor Building I

Ventilation System provide on high radiation levels (above alarm setpoint) initiation of SGTS, isolation of drywell vent / purge, isolation of the RB and Control Center Ventilation Systems and initiation of Control Center recirculation mode ventilation.' These monitors and functions are not required by Fermi 2 ODCM but are important in controlling containment venting / purging.

7.2 Sampling and Analy' sis of Gaseous Effluents The program for sampling and analysis of gaseous waste is prescribed in Fermi 2 ODCM Table 4.11.2.1.2-1. This table distinguishes two types of gaseous releases:

(1) containment PURGE, treated as BATCH releases, and (2) discharges from the Reactor Building Exhaust Plenum (including Standby Gas Treatment System (SGTS) when operating), and other building ventilation exhausts, treated as CONTINUOUS releases. ,

7.2.1 Containment PURGE l

ODCM Table 4.11.2.1.2-1 requires that samples be collected and analyzed l before each primary containment PURGE. Sampling and analysis is required within eight hours before starting a PURGE. ODCM Table 4.11.2.1.2-1 i Footnote j and ODCM 4.11.2.8.2 also require that if the purging or venting is ;

through ths Reactor Building ventilation, rather than through SGTS, and 6 the i primary containment radiation monitoring system is INOPERABLE or in alarm !

condition, sampling and analysis is required within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to and at least I

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during venting or purging of the primary containment. The l

required analyses must include principal gamma emitters and, if a pre-vent or pre-purge sample, tritium.

ODCM-7.0 Rsvision 8 Page 7.0-3 For a planned containment PURGE, the results of the samples and analyses may be used to establish the acceptable release rate and radiation monitor alarm setpoint in accordance with ODCM Section 7.3. This evaluation may be i

necessary to ensure compliance with the dose rate limits of ODCM 3.11.2.1. In practice, release flow rates are fairly constant and these calculations are necessary only if a threshold value of nuclide concentration in the primary '

containment atmosphere is reached. The alarm setpoints of the primary containment atmosphere monitor, the Reactor Building ventilation exhaust !

monitors, and the Reactor Building and SGTS SPING monitors are set to ensure that release routes are continuously monitored and controlled in accordance with l 10 CFR 20 or limits specified in the ODCM.

i 7.2.2 Ventilation System Releases ODCM Table 4.11.2.1.2-1 requires continuous samples of releases from the RB Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, ,

Turbine Building, Service Building, and Onsite Storage Facility. The table i specifies the following program:

- Once per week, analysis of an adsorbent sample of I-131 and 1-133, plus analysis of a particulate sample for principal gamma emitters.

1 1

- Once per month, analysis of a composite particulate sample of 611 releases (by release point) that month for gross alpha activity.

- Once por quarter, analysis of a composite particulate sample of all releases that quarter for Sr-89 and Sr-90.

- Once per month, analysis of a grab sample for principal gamma emitters (noble gases and tritium).

ODCM Table 4.11.2.1.2-1 also requires continuous monitoring for noble gases.

This requirement is met by the SPING Monitors on each of the plant gaseous release points.

The ODCM requires more frequent sampling and analysis following reactor startup, shutdown, or change in thermal power exceeding 15% within one hour.

The ODCM allows exceptions to this increased sampling schedule provided that neither one of the following conditions exist:

- Primary coolant dose equivalent 1-131 has increased more than a factor of l three. !

l

- Reactor Building SPING noble gas monitor has increased more than a l factorof three.

i l

i

l l

ODCM-7.0 Revision 8 Page 7.0-4 Grab samples of the Fuel Pool Ventilation Exhaust are required tritium analysis once per seven days whenever spent fuel is in the Spent Fuel Pool. Also, grab samples for tritium are required when either the reactor well or the dryer separator poolis filled. These samples are taken at the Reactor Building Exhaust Plenum and Standby Gas Treatment System (SGTS) when operating.

I 7.3 Gaseous Effluent Monitor Setpoint Determination 7 3.1 Ventilation System Monitors !

l l' Per the requirements of ODCM 3.3.7.12, alarm setpoints shall be established for l the gaseous effluent monitoring instrumentation to ensure that the release rate of j noble gases does not exceed the limits of ODCM 3.11.2.1. This section limits I releases to a dose rate at the SITE BOUNDARY of 500 mrem / year to the total body or 3000 mrem / year to the skin. From a grab sample analysis of the applicable release (i.e., grab sample of the primary containment or Ventilation System release), the radiation monitoring alarm setpoints may be established by the following calculational method. The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, limited by ODCM 3.11.2.1, by the equation:

1.67E + 01

x / O

VF * [(C,

K,)

500 (7-1) l 1.67E + 01

x / O

VF * [(C, * (L, + 1.1M,])

3000 (7-2)

Where:

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate

% /Q = annual average meteorological dispersion to the controlling site boundary location from Table 7.0-3 (sec/m3) or plant procedures VF = Ventilation System flow rate for the applicable release point and monitor (liters / minute) i Ci = concentration of noble gas radionuclide i at release point as determined by gamma spectral analysis of grab sample (pCl/cc) (If a noble gas is not detected at the reactor building release point, its concentration at this release point may be calculated by applying a dilution factor to its concentration in an Offgas Vent Pipe sample.)

l

ODCM 7.0 Ravision 8 .

Page 7.0-5

~

i Ki = total body dose conversion factor for noble gas i

radionuclide i (mrem /yr per pC1/m3, from Table 7.0-2)

~

Li = beta skin dose conversion factor for noble gas radionuclide I (mrem /yr per pCi/m3, from Table 7.0-2) ,

t Mi = gamma air dose conversion factor for noble gas radionuclide I (mradlyr per pCl/m3, from Table 7.0-2) 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) ,

500 = total body dose rate limit (mrem /yr) ,

3000 = skin dose rate limit (mrem /yr) 1.67 E + 01 = 1 E + 03 (cc/ liter) * (1/60) (min /sec)

Based on the more limiting (i.e., higher) value of FRAC as determined above, the !

alarm setpoints for the applicable monitors may be calculated by the equation: l l

SP S (AF QC,)+ Bkg FRAC (7-3)

Where.

i SP = alarm setpoint corresponding to the maximum allowable release !

rate (pCi/cc) !

Bkg = background of the monitor (pCI/cc)

AF = administrative allocation factor (Table 7.0-1) for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated ,

to the individual release points.

Ci = concentration of Noble Gas Radionuclide I as determined by gamma spectral analysis of grab sample (pCl/cc) (If a noble gas is not detected at the reactor building release point, its concentration at this release point may be calculated by applying a dilution factor to its concentration in an Offgas Vent Pipe sample.) Note: If the monitor channel in question was showing a response to the effluent at the time of the grab sample, this response minus background may be used in lieu of the summed grab sample concentrations.

.. .. _ _ . _ .. _ ._. _ __ _. _ . _ .~ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _

' ODCM-7.0 Revision 8 Page 7.0-6 The Allocation Factor (AF) is an administrative control imposed to ensure that I combined releases from all release points at Fermi 2 will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of ODCM 3.11.2.1). From the Fermi 2 design evaluation of gaseous effluents presented in the UFSAR Section 11.3, representative values have been determined for AF. These values are presented in Table 7.0-1. These values may be changed in the future as warranted by operational experience, provided the site releases comply with ODCM 3.11.2.1. In addition to the allocation factor, safety factors which have the effect of lowering the calculated setpoints may be applied. When determining the Noble Gas Monitor calibration constant, the monitor sensitivity for Xe-133 may be used in lieu of the sensitivity values for the individual radionuclides. Because of its lower gamma energy and corresponding monitor response, the Xe-133 sensitivity provides a conservative value for alarm setpoint determination. Alternatively,if the monitor channelin question frequently shows a response to a mix of isotopes whose concentrations can be determined, the calibration constant may be determined from this type of data without reference to primary calibration data.

7.3.2 Setpoint Determination with No Nuclides Detected When noble gas concentrations for a release point cannot be determined from grab samples, there are two options for setpoint determination. First, the ,

setpoint may be set slightly above monitor background (e.g. 2 to 3 times background). This approach may be used when releases are not expected from a particular release point. Second, the equations of Section 7.3.1 may be used with noble gas concentration values based either on UFSAR tables or on values from a release point for which concentrations have been determined (e.g. reactor building exhaust plenum). When this method is used, a safety factor should be used in the setpoint calculation.

7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions :

The monitor alarm setpoint is used as the primary method for ensuring and demonstrating compliance with the release rate limits of ODCM 3.11.2.1. Not exceeding alarm setpoints constitutes a demonstration that release rates have been maintained within the ODCM limits. When an effluent Noble Gas Monitor exceeds the alarm setpoint, an evaluation of compliance with the release rate limits must be performed using actual release conditions. This evaluation requires collecting a sample of the effluent to establish actual radionuclide concentrations and permit evaluating the monitor response. The following equations may be used for evaluating compliance with the release rate limit of ODCM 3.11.2.1a:

D,3 = 1.67E+ 01

x / Q

VF

1(K,

C,)

(7-4)

D, = 1.67E + 01

x / Q

VF * [$ + 1.1M,]* C,)

(7-5)

l ODCM-7.0 Revision 8 Page 7.0-7 Where:

Dtb = total body dose rate (mrem /yr)

Ds~ = skin dose rate (mrem /yr)

%/O = atmospheric dispersion to the controlling SITE BOUNDARY i

location (sec/m3)

VF = Ventilation System release rate (liters / min)

\

l Ci = concentration of radionuclide i as measured in the grab

!' sample or as correlated from the SPING Noble Gas Monitor i reading (pCl/cc)

= total body dose conversion factor for noble gas radionuclide 1 l Ki (mrem /yr per pCl/m3, from Table 7.0-2) !

Li = beta skin dose conversion factor for noble gas radionuclide i ;

i (mrem /yr per pCl/m3, from Table 7.0-2) l Mi = gamma air dose conversion factor for noble gas radionuclide i j l (mradlyr per pCi/m3, from Table 7.0-2) l 1.1 = mrem skin dose per mrad gamma air dose (mram/ mrad) 1.67 E + 01 = 1 E + 03 (cc/ liter) * (1/60)(min /sec)

The above equations may also be used to verify compliance with ODCM 3.11.2.1.a when noble gases are detected in periodic (e.g. monthly) effluent ;

noble gas samples.

l 7.4 Primary Containment VENTING and PURGING 7.4.1 Release Rate Evaluation For primary containment VENTING or PURGING, an evaluation of acceptable release rate may be performed prior to the release. Based on the measured noble gas concentration in the grab sample collected per the requirements of ODCM Table 4.11.2.1.2-1, the allowable release rate from primary containment can be calculated by the following equation:

?

ODCM-7.0 Rsvision 8 Page 7.0-8 500

AF RR,* =

1.67 + 01

x / Q * { (K r

C )

3 (7-6).

or 3000

AF RR,=

1.67E + 0l

x / Q * [ ( [4 + 1.lM,]* C,)

(7-7)

Where:

RRtb = allowable release rate so as not to exceed a dose rate of 500 mrem /yr, total body (liters / minute)

RRs = allowable release rate so as not to exceed a dose rate of 3000 mrem /yr, skin (liters / minute)

AF = allocation factor for the applicable release point from Table 7.0-1 (default value is 0.5 for Reactor Building Exhaust Plenum) 500 = total body dose rate limit (mrem /yr) 3000 = skin dose rate limit (mrem /yr)

The lesser value (RRtb or RRs) as calculated above may be used for establishing the allowable release rate for primary containment PURGING or VENTING, taking into account the fraction of the allocated release limit already -

accounted for by continuous releases from the proposed release point. As discussed in section 7.2.1, this evaluation is rarely necessary.

7.4.2 Alarm Setpoint Evaluation For a primary containment VENTING or PURGING, a re-evaluation of the alarm setpoint may be needed to ensure compliance with the requirements of ODCM 3.3.7.12. For the identified release path (RB Exhaust Plenum or SGTS) and associated effluent Radiation Monitor, the alarm setpoint should be calculated using Equations (7-1), (7-2) and (7-3). In Equations (7-1) and (7-2),

the value of the Ventilation Flow VF should be established at the total release flow rate, including the contribution from the PURGE or VENT. If the calculated alarm setpoint is greater than the current setpoint, no adjustments are necessary. As discussed in section 7.2.1, this setpoint evaluation is rarely necessary.

ODCM-7.0 Ravision 8 Page 7.0-9 7.5 Quantifying Releases - Noble Gases The determination of. doses in the environment from releases is dependent on the mixture of the radioactive material. Also, NRC Regulatory Guide 1.21 requires reporting of individual radionuclides released in gaseous effluents. Therefore, Detroit Edison must determine the quantities of the individual radionuclides released. For noble gases, these quantities must be based on actual noble gas grab samples. ;

7.5.1 Sampling Protocol As required by ODCM 3.11.2.1, a gas sample is collected at least monthly from each of the six gaseous release points (Reactor Building Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, Turbine Building, Onsite Storage Facility, and Service Building). As discussed in ODCM Section 7.2.2, this gas sample is analyzed by gamma spectroscopy to identify individual radionuclides (noble gases). To date (May 1992) noble gases have been detected only in the reactor building effluent.

In addition to these monthly samples from each release point, noble gas grab samples from the Offgas Vent Pipe may be collected using the sample lines of the abandoned Offgas Vent Pipe Monitor (D11-N105 and D11-N106). Since noble gases are more concentrated at this point than at the Reactor Building

< Exhaust Plenum, a greater number of noble gases are detected at this point.

Sampling should be performed monthly at the Offgas Vent Pipe unless the ,

reactor is shut down or noble gas concentrations increase sufficiently to allow i detection of all significant noble gas nuclides at the Reactor Building Exhaust Plenum.

For Containment PURGE / VENT, samples are collected prior to the initiation of l the release and p 3riodically throughout the release (see ODCM Section 7.2.1).

These samples are evaluated using Equations (7-4) and (7-5) to ensure that the site boundary dose este limits of ODCM 3.11.2.1 are not exceeded. For an i extended PURGENENT period (e.g., longer than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ), drywell airbome activity levels will equii:brate. After equilibrium is reached, the quantification of the PURGENENT can be adequately addressed by the periodic (typically .

weekly) sample and analysis of the Reactor Building Exhaust Plenum or Standby Gas Treatment Systera.

As required by ODCM Table 4.11.2.1.2-1, special samples are required of the RB Exhaust Plenum and SGTS following shutdown, startup or a THERMAL POWER change exceeding 15% within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period. Exceptions to this special sampling are allowed as noted previously in ODCM Section 7.2.2.

ODCM-7.0 R@ vision 8 Page 7.0-10 7.5.2 Release Concentration Determination for Reactor Building Exhaust Plenum in mes where both a RB Exhaust Plenum noble gas sample and an Offgas Vent Pipe (OGVP) sample have been taken, the RB Exhaust Plenum noble gas concentrations are determined as follows: First, the RB SPING channel 1-5 readings (above background) at the times the two samples were taken are l compared, and the noble gas concentrations for the sample taken at the lower RB SPING channel 1-5 reading are normalized to the higher RB SPING channel 1-5 reading. Second, a dilution factor relating OGVP concentrations to RB i Exhaust Plenum concentrations is calculated by dividing the RB Exhaust Plenum flow rate (nominally 9.43 E4 cfm) by the OGVP flow ran as indicated in the control room (N62 R808, blue pen). Third, the OGVP noble gas concentrations are divided by this dilution factor. Fourth, the diluted OGVP noble gas concentrations are compared to the RB Exhaust Plenum noble gas concentraticns, and the higher of the two concentration values for each nuclide j is taken to be the RB Exhaust Plenum concentration for that nuclide. (For purposes of calculation, the concentrations of nuclides which are not detected are taken to be zero.) Fifth, the resulting RB Exhaust Plenum concentrations are corrected for variations during the release period by multiplying each concentration value by the average RB SPING channel 1-5 reading (above background) for the period divided by the higher of the two RB SPING channel 1-5 sample readings (above background) at time the samples were taken.

These corrected values are then used as Ciin Equation (7-8) to determine the quantity of noble gases released.

7.5.3 Calculation of Activity Released l The following equation may be used for determining the release quantities from any release point based on the grab sample analysis:

Q = 1.0E + 03

VF

T

C; i (7-8)

Where:

i Oi = total activity released of radionuclide i (pCi) l VF = Ventilation System release rate (liters / min)

T = total time of release period (min) 1.0 E + 03 = milliliters per liter Ci = concentration of radionuclide i as determined by gamma spectral analysis of grab sample (pCi/cc) corrected for variations during release period as described in Section 7.5.2 i

l l

ODCM-7.0.

Revision 8 Page 7.0-11 7.6 Site Boundary Dose Rate - Radiolodine and Particulates ODCM 3.11.2.1.b limits the dose rate to $1500 mrem /yr to any organ for 1-131,1-133, '!

tritium and particulates with half lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is pedormed at a frequency no greater than that corresponding to the sampling and analysis time period (nominally once per 7 days). The following equation may be used in the dose rate evaluation for 1-131,1-133, and particulates with half lives greater than 8 days:

DR= x / Q

R,_in

VF,

16.7

1C,

,( i s (7-9)

Where:

DR = total maximum organ dose rate for all release points (mrem /yr)

XQ=/ atmospheric dispersion factor for release point r to the controlling SITE I BOUNDARY location (sec/m3) from Table 7-3 or plant procedures Ri -in = l-131 child thyroid inhalation pathway dose factor (mrem /yr per pCl/m3) from Table 7-4 VFr = Average ventilation flow for release point r during release period (liters / min)

Cir = Concentration of radionuclide I (1-131,1-133, or particulate with half life greater than 8 days) released from release point r during the appropriate release period (pCi/cc)-usually determined by gamma spectral analysis of effluent sample i

16.7 = 1000 cc/ liter

0.0167 min /sec !

Release periods used in Equation (7-9) are the most recent periods evaluated for the different release points, and these periods may not be identical.

Alternatively, the site boundary dose rate may be evaluated using the highest individual isotopic dose factors for all age groups to calculate inhalation and ground plane exposure at the highest dispersion factor location at or beyond the site boundary, as well as vegetation, milk, and meat exposure at the garden, milk, and meat locations with the highest deposition factors. Dose rate due to tritium is currently evaluated by this method, and when tritium has been detected in gaseous effluents during the most recent release period, the tritium dose rate must be added to the result from Equation (7-9) to evaluate compliance with ODCM 3.11.2.1.b.

t ODCM 7.0 Rsvision 8 Page 7.0-12 l

l The dose rate evaluation described above may have to be performed more frequently than once per week.in order to meet the requirements of ODCM Table 4.11.2.1.2-1, footnote g: Daily sampling is required following startup, shutdown, or thermal power changes exceeding 15% in one hour if DEI has increased by a factor of 3 or if the applicable noble gas effluent monitor reading has increased by a factor of 3.

7.7 Noble Gas Effluent Dose Calculations - 10 CFR 50 7.7.1 UNRESTRICTED AREA Dose- Noble Gases l ODCM 4.11.2.2 requires that an assessment of releases of noble gases be priormed at least once per 31 days to evaluate compliance with the quarterly dose limits of 5 mrad, gamma-air and 10 mrad, beta-air and the calendar year l

limits 10 mrad, gamma-air and 20 mrad, beta-air. The following equations may be used to calculate the gamma-air and beta-air doses. If noble gases are detected at multiple release points, these equations must be performed for each such release point,' and the calculated air doses must be summed.

l Dy = 3.17E -08* X / Q * [(M,

Q )

(7-10) l and Dh = 3.17E - 08

x / Q * [(N,

Q )

(7-11)

Where:

DY = air dose due to gamma emissions for noble gas radionuclides (mrad) i l D@ = air dose due to beta emissions for noble gas radionuclides (mrad)

%Q / = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3)

Qi = cumulative release of noble gas radionuclide i over the period of interest (pCl)

Mi = air dose factor due to gamma emissions from noble gas radionuclide 1 (mrad /yr per pCi/m3, from Table 7.0-2)

Ni = air dose factor due to beta emissions from noble gas radionuclide i (mrad /yr per pCi/m3, Table 7.0-2) 3.17 E - 08 = 1/3.15 E + 07 (year /sec) 1 i '

l

. ODCM 7.0 Ravision 8 Page 7.0-13 7.7.2 Simplified Dose Calculation for Noble Gases in. lieu of the individual noble gas radionuclide dose assessment presented above, the following simplified dose calculational equations may be used for verifying compliance with the dose limits of ODCM 3.11.2.2. If noble gases are detected at multiple release points, these equations must be performed for 9ach !

. such release point, and the calculated air doses must be summed. (Refer u Appendix B for the derivation and justification of this simplified method.)

Dy = 2.0

3.17E - 08 * % / Q

M, * [Q (7-12) and g = 2.0

3.17E -08

x / Q

N, * [Q

, (7-13)

Where:

Meff = 2.7 E + 03, effective gamma-air dose factor (mrad /yr per pCi/m3)

Neff = 2.3 E + 03, effective beta-air dose factor (mrad /yr per pCl/m3) 2.0 = conservatism factor to account for potential variability in the radionuclide distribution 7.8 Radiolodine and Particulate Dose Calculations - 10 CFR 50 7.8.1 UNRESTRICTED AREA Dose - Radiolodine, Particulates, and Tritium In accordance with requirements of ODCM 4.11.2.3, a periodic assessment (at ,

least once per 31 days) is required to evaluate compliance with the quarterly l dose limit of 7.5 mrem and the calendar year limit of 15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of I-131,1-133, tritium, and particulates with half-lives greater than 8 days:

D,, = (([(W,

SF,

3.17E - 8

R,

Q,)

(7-14) l Where: !

1 Dao = dose or dose commitment to Organ o of age group a (identified in l Table 7.0-3 or plant procedures) '

m . . . __ . _ _ _ _ _ _ . . _ _ _ . _ . . _ . _ . - . _ . _ . _ _ _ _ _ _ _ . . _ . . . . . _ _

h ODCM 7.0 Rsvision B

~

Page 7.0-14

$ ,i Wr = atmospheric dispersion parameter for release point r and the residence location identified in Table 7.0 3 or plant procedures.

Either:

a) % /0, atmospheric dispersion for inhalation pathway and H-3 and C-14 dose contribution via other pathways

! (sec/m3), or b) D/O, atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2)

Raipo = dose factor (mrem /yr per pCl/m3) or (m2 - mrem /yr per pCl/sec) . l i

from Table 7.0-4 for radionuclide i, age group a, pathway p, and organ o as identified in Table 7.0-3 or plant procedures. Values [

for Raipo were derived in accordance with the methods described I in NUREG-0133. As noted in NUREG-0133 section 5.3.1.3, in the case that the milk animal is a goat, parameter values from Reg Guide 1.109 should be used. For 1-131, for example, use of the

' goat feed / forage consumption rate given in Table E-3 and the stable element transfer factor given in Table E-2 of Reg Guide 1.109 results in grass-goat-milk dose factors which are equivalent

,' to the grass-cow-milk dose factors in Table 7.0-4 multiplied -

by 1.2.

Qir = cumulative release from release point r over the period of interest (normally one month) for radionuclide 1 - I-131,1-133, tritium or radioactive material in particulate form with half-life greater than 8 days (pCl).

SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist:

1) For milk and vegetation exposure pathways:

= 0.5 (derived from Reg Guide 1.109, Rev 1. A six month fresh vegetation and grazing season (May through October) limits exposure through this pathway to half the year.

2) For inhalation and ground plane exposure pathways:

= 1.0 (derived from Reg Guide 1.109, Rev 1) 3.17 E-8 = 1/ 3.15 E7 (year /sec)

C

ODCM-7.0 RIvision 8 Page 7.0-15 This equation should be used to evaluate organ doses for the individual with the highest potential offsite dose. This calculation is performed monthly and is added to previous results for the quarter and year. The highest quarterly and annual cumulative organ dose totals for this individual should be compared with the limits of ODCM 3.11.2.3.

The residence, age group, and relevant exposure pathways for this individual are listed in Table 7.0-3 and in plant procWures. Plant procedures may provide updated information which differs from Table 7.0 3. This individual is identified from data obtained in the annual Land Use Census (ODCM 3.12.2).

7.8.2 Simplified Dose Calculation for Radiolodines and Particulates 1 l

In lieu of the individual radionuclide (1-131 and particulates) dose assessment presented above, the following simplified dose calculation may be used for verifying compliance with the dose limits of ODCM 3.11.2.3. However, the result of this calculation should not be used as the reported offsite dose.

D_ = 3.17E - 08

W

R,_33, QQ, (7-15)

Where:

Dmax = maximum organ dose (mrem) 833

= 4.76 E + 10, child thyroid 1-131 dose factor for the vegetable pathway (m2 - mrom/yr per pCi/sec)

W = highest D/O for residence listed in Table 7.0-3 (m-2)

Qi = cumulative quarterly or annual release of radionuclide i from all q(

release points- l-131,1-133, H-3, and particulates with half lives greater than 8 days (pCl)

The ground plane exposure and inhalation pathways need not be considered ,

when the above simplified calculational method is used because of the overall l negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co 60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, i especially considering that no other radionuclide has a higher dose parameter for any organ via any pathway than 1-131 for the thyroid via the vegetable or milk pathway.

(

+

ODCM 7.0 1 Rsvision 8 Page 7.0-16 !

7.9 Gaseous Effluent Dose Projection As with liquid effluents, the Fermi 2 ODCM controls on gaseous effluents require i

" processing" of gaseous effluents if the projected dose exceeds specified limits. These controls implement the requirements of 10 CFR 50.36a on maintaining and using the appropriate radwaste processing equipment to keep releases ALARA.

ODCM 3.11.2.5 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when the projected dose l exceeds 0.3 mrem to any organ in any 31 day period (i.e., one-quarter of the design !

objective rate). Figure 7.0-1 presents the gaseous effluent release points and the VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release.

Dose projection is performed at least once per 31 days using the following equation:

D , = D_ * (31/ d) l (7-16)

Where:

Dmaxp = maxirnum organ dose projection for the next 31 day period (mrem)

NOTE: The reference calendar quarter is normally the current calendar quarter, if the dose projection is done in the first month of the quarter and is to be based on dose calculated for the previous quarter, the reference calendar quarter is the previous quarter. l Dmax = the cumulative maximum organ dose from the beginning of the reference calendar quarter (normally the current quarter) to the end of the most recently evaluated release period as determined by Equation (7-14) or (7-15)(mrem) d = number of days from the beginning of the reference calendar quarter to I

the end of the most recently evaluated release period.

31 = number of days in projection I

i

i ODCM-7.0 Rsvision 8 Page 7.0-17 7.10 Waste Oilincineration As indicated in Table 4.112.1.2-1, waste oil containing radioactive material may be incinerated by injection into the Auxiliary Boiler fuel stream, but this shall only be done according to approved plant procedures. Prior to incineration of such oil, a sample of the oil must be analyzed by gamma spectroscopy to determine radionuclide concentration.

Based on the analysis results and proposed incineration rate, the proposed release must be determined to be within site beundary dose rate limits (when combined with dose rates from other release points) prior to incineration. After incineration, the activity released must be determined and recorded. The equations of this ODCM section (section 7.0) I should be used in these calculations, and the highest dispersion factors in Table 7.0-3 j may be used, unless data specific to the Auxiliary Boiler stack is available. (Since this '

stack is farther from most land receptors than other plant stacks, Table 7.0-3 dispersion i factors should be conservative for this release point.)

l 1

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ODCM-7.0 !

Ravision 8 Page 7.0-18 TABLE 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints Allocation Allocated Dose Release Point Flow Rate

Factor Rate Limit (liter / min) (AF) (mrom/ year)

Reactor Building 2.67E6 0.50 T Body = 250 Exhaust Plenum Skin = 1500 D11 P280 Organ = 750 Standby Gas 1.07E5 0.10 T Body = 50 Treatment System Skin = 300 Div i D11 P275 Organ = 150 Stanoby Gas 1.12E5 0.10 T Body = 50 Treatment System Skin = 300 Div 11 D11 P276 Organ = 150 Turbine Building 8.67E6 0.20 T Body = 100 Ventilation Skin = 600 D11 P279 Organ = 300 Service Building 9.06E5 0.01 T Body = 5 Ventilation Skin = 30 D11-P282 - Organ = 15 Radwasto Building 1.13E6 0.02 T Body = 10 Ventilation Skin = 60 011-P281 Organ = 30 Onsite Storage 3.06ES 0.02 T Body = 10 Building Skin = 60 Ventilation Organ = 30 D11 P281 l

Reactor Building 2.57E6 0.50 T Body = 125 Ventilation" Skin = 750 Gulf Atomic Monitors D11 N408, N410 Ventilation flow rate values are subject to change due to plant modifications and changing plant conditions; therefore updated values in plant procedures may be used.

D11-N408 and N410 will start the SGTS, close the Drywell Purge / Vent Valves, isolate Rx Building Ventilation System, isolate Control Center, and initiate emergency recirculation mode.

I i

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ODCM-7.0 Ravision 8 Page 7.0-19 TABLE 7.0-2 Dose Factors for Noble Gases

Total Body Skin Gamma Air Beta Air Gamma Dose Beta Dose Dose Factor Dose Factor Nuclide Factor Ki Factor Li Mi Ni a

(mrom/yr per (mrom/yr per (mradlyr per (mradlyr per pCl/m3) pCl/m3) pCl/m3) pCi/m3)

Kr-83m 7.56E-02 -- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04

. Kr 88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 l Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 l Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe 135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 1 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 1 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 l Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 NOTE: ;

Dose factors taken from NRC Regulatory Guide 1.109 l

I l

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ODCM 7.0 Revision 8 Page 7.0-20

(' TABLE 7.0 3 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations

i

)

ODCM Control Location Pathway (s) D %N A9' W (sechn3) (1hn2) 3.11.2.1a site boundary noble gases N/A RB: 1.25E 6 N/A (0.57 mi, NW) direct exposure TB: 5.71E-6 RW: 2.66E 6 3.11.2.1b site baundary inhalation child RB: 1.25E-6 N/A (0.57 rni, NW) TB: 5.71E-6 RW: 2.66E-6 3.11.2.2 site boundary gamma-air ' N/A RB: 1.25E-6 N/A (0.57 mi, NW) beta-air TB: 5.71 E-6 RW: 2.66E-6

~

11.2.3 resistance vegetation child RB: 1.10E-6 1.59E-8 (0.67 mi, inhalation, and TB: 4.02E-6 3.06E-8 WNW) ground plane RW: 1.53E-6 1.76E-8 NOTE: *The identified controlling locations and pathways are derived from land use census data and dispersion and deposition factor data tables. The dispersion and deposition factor values listed are conservative values; they represent the highest ,

annual average values seen between 1984 and 1994. When performing dose and '

dose rate evaluations for plant surveillances, the dispersion and deposition factor l9/9J' values and location and pathway information found in plant procedures should be used. These data in plant procedures should be the same as the above data unless recent information has shown the above data to be non-conservative or inaccurate.

When performing dose evaluation for the Annual Effluent Release Report, the annual ;

average dispersion and deposition factors for the year being evalueted should be i used. !

1 l

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/

\

ODCM-7.0 Revision 8 Page 7.0-21 Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT l yc[

(arem/yr per yCi/m3) auctase tees user Terreas a u ser smet Shut T. Seer

~

s-3 -

1.368 3 1.36: 3 1.M8+3 1.368+3 1.Ms+ 3 1.Ma* 3 C-14 .1.83be 3.41b3 3.418+3 3,418+3 3.41b3 3.41b3 3.41E*3 s No-34 1.02b4 1.02E+4 1.02E+4 1.02b4 1.028+4 1.02E+4 1.02E*4 P-32 . 1.325*6 7.718*4 - - - 8. M E* 4 5.01E*4 Ct-51 - -

5.955+1 3.388*1 1.44be 3.32b3 1.008+2 Ite-54 - 3. 96b4 - 9.84p3 1.408+4 7.74E+4 6.308*3 me-M - 1.348+0 -

1.30E+0 9.44b3 3.02b4 1.838-1 Fe-55 3.448+4 1.70E+4 - - 7.31t+4 6.034+3 3.94b3 Fe-59 1.188+4 2.76E+4 - - 1.025+4 1.88b5 1.06b4 Co 57 - 6.928*2 *

3.70b5 3.148+4 6.71E+2 Co-58 - 1.588+3 - - 9.388*5 1.06b5 2.078+3 Ce40 - 1.15E+4 - -

5.978+6 3.85t+5 1.44E*4 51-63 4.328*5 3.14E*4 - - 1.78b5 1.M t+4 1.45t*4 3145 1.M8+0 2.10E-1 - - 5.60E+3 1.33E+4 9.12E-2 Code - 1.44be

4.628+0 6.788+3 4.90b4 6.155-1 En-65 3.24be 1.031*5 -

6.90b4 8.648*5 5.Mt+4 4.ME4 Ea49 3.Mb2 6.51b2 -

4.228-2 9.30E+2 1.63t+1 4. 52E-3 l l

Br-42 - - - - - 1.04E+4 1.35t+4 St-43 - - - = = 3.322+2 2.41E+2 St-84 - - - = = 1.648-3 3.13E+2 St-85 - - - - - - 1.388*1 Sh-84 - 1.35E*5 - = = 1.66E*4 5.90E+4 Shte - 3.87E*2 - = = 3.34F9 1.93E*2 i g ab-89 - 2.56E*2 - - - - 1.70E*2

( 8t-89 3.e48+ 5 - - -

1.40E*6 3.50b5 4.72E+3 J i

St-90 9.928+7 - - -

9.60E+6 7.32b5 6.10b6 Sr-91 6.1 2 1 - - -

3.65t+4 1.918+5 3.50E+0 i St-92 6.74be - - - 1.658 4 4.385 4 3.918-1 '

T-90 3.095+3 - = = 1.70E+5 5.e68*5 5.61b1 Y-91e 3.618-1 l

- - - 1.92&+3 1.33s+0 1.02b3 j F91 4.638+5 - - - 1.70b6 3.85b5 1.34t+4 T-92 1.03E+1 - - -

6.575+4 7.35E+4 3.028-1 F93 9.44b t - - - 4.455+4 4.328 5 3.61B+0 Er-95 1.07b5 3.44t+4 - 5.428+4 1.778+4 1.50E+5 3.335 4 Er-97 9.688e1 1.96b t - 3.978+1 7.878+4 5.33b5 9.04be Nb-95 1.41b4 7.82t+3 - 7.74E+3 5.05B+ 5 1.e4E+5 4.21b3 N6-97 3.32b1 5.628-2 - 6.f48-2 3.40b3 3.42E+2 3.05b2 Ste-M - 1.318*2 -

3.91E*2 9.12E+4 3.48b5 3.30b1 To-9te 1.83b3 3.91b3 - 4.428-2 7.M R+2 4.Mp3 3.708-2 Te=101 4.18b5 6.085 5 - 1.088-3 3.998+3 - 5.90be Se-103 1;538+3 - -

5.83E+3 5.058+5 1.188+5 6.588+2 Su-105 7.988 1 = =

1.03E+0 1.108+4 4.828 4 3.118-1 to-106 6.915 4 - - 1.Nt* 5 9. M8+4 9.188*5 8.73E+3 Sh-103e = = = - - . . -

Sh-106 - = = = - - -

As 110e 1.888+4 1.00E+4 - 1.97b4 4.63t+4 3.838+5 5.Mp3 86-134 3.12b4 5.898*2 7.55t+1 -

3.44B+6 4.06b 5 1.ME*4 86-125 5.M be 5.958+2 5.40bt - 1.74 pe 1.018+5 1.Mt+4 Te= tale 3.428+3 1.58t*3 1.05E+3 1.NE*4 3.14E+5 7.068+4 4.67bt Te-137e 1.ht4 5.775+3 3.398+3 4.58b4 9.60E*5 1.388+5 1.578*3 fe-127 1.40see 4.438-1 1.96be 5.10E+0 6.518+3 5.74t+4 3.10b1 Te-1*te 9.768 3 4.67b3 3.44E+3 3.66b e 1.168+6 3.83s+5 1.988+3 Te-129 4.98b2 3.398 2 3.905-2 1.87bt 1.Mp3 1.578+2 1.34b2 Te-ISte 6.998+1 4.ME*1 5.508+1 3.09E*2 1.4&t+% 5.568*5 3.90E*1 Te-131 1.11b3 5.95b3 9.36b 3 4.378-3 1.398+3 1.04E+1 3.598-3

Te=132 3.808+3 3.158*3 1.90E*2 1.4b3 3.88b5 5.198+5 1.62E+2 b130 4.588+3 1.348 4 1.145+6 3.098+4 -

7.695+3 5.38b b131 3. 52b4 3.58b4 1.19E*7 6.13B+4 - 6.388+3 3.05E+4 b132 1.168+3 3. NE+3 1.14b5 5.188+3 - 4.068+3 1.168+3 b133 8.64b3 8.488 4 3.15b6 3.54b4 - 8.88b3 4.538+3

d 1

i ODCM-7.0

Revision 8

. Page 7.0-22

e

( Table 7.0 4 l Gaseous Effluent Pathway Dose Commitment Factor 3 j Raipo, Inhalation Pathway Dose Factor 8 - ADULT (cont.) l 9/O,.-

I (mremlyr per pCIIm ) 3 4

mestade toes Meer Thrteld Eideer Ama8 42-842 T. Seer l

2-1M 6.448*2 1.73E*3 2.988*4 2.75E+3 - 1.018+0 6.158+2 3-135 2. NE* 3 6.985*3 4.488+5 1.11E+4 - 5.258*3 2.57E*3

Co-134 3. 71E* 5. 8.48E*5 - 2.87E+5 9.768+4 1.e4E+4 7.288+5 Co-1H 3.90E*4 1.468*5 - 8. ME+4 1.20E+4 1.17t+4 1.10E*5 Co-137 4.78E*5 6.21E+5 - 2.23E*5 7.53E+4 8.40E*3 4.285*5 1

i Co-1H 3.31E*2 6.21E+2 - 6.80E+2 6.868+1 1.868-3 3.N E*2 Sa-139 9.36E-1 6.66E 4 - 6.22E-4 3.76E*3 8.968*2 2.748 2

- Se 140 3.90E+4 4.90E*1 - 1.67E*1 1.278+6 2.188+5 2.575+3

Se-141 1.00E-1 7.538-5 - 7.00E-5 1.945+3 1.165-7 3.368-3 Se-142 2.63E-2 2.70E-5 - 2.29E-5 1.198*3 - 1.H5-3 l

14-140 3.448*2 1.74E*2 - - 1. ME*5 4.588+5 4.588+1 La-142 6.83E-1 3.108-1 = = 6.338+3 2.11E*3 7.728-2 4

Co-141 1.998+4 1.35E+4 - 6.26E*3 3.62E*5 1.20E+5 1.53E+3 a Ce-143 1.84E*2 1.38E*2 - 6.08E*1 7.985+4 2.268+5 1.53E+1 Co-144 3.435*6 1.43E+6 - 8.48E*5 7.785+6 8.168*5 1.84t*5 i

Pr-143 9. ME*3 3.75E*3 - 2.168+3 2.81E*5 2.80E+5 4.648 2

)! Pt-144 3.01E-2 1.258 2 - 7.05E-3 1.03E*3 2.155-8 1.53E-3 Nd-147 5.27E*3 6.10E*3 - 3.MI+1 2.215+5 1.735*5 3.658*2 W 187 8.44E+0 7.08E*0 - - 2.90E+4 1.55E+5 2.488+0 up-239 2.30E+2 2.268*1 - 7.00E+1 3.765*4 1.195+5 1.24E+1 l

Y i

)

i 4

l l

1 i 1 i

i i

[

x 4

h3 ODCM-7.0 Revision 8 Page 7.0-23 l >

( Table 7.0-4 Raipo, Inhalation Pathway Do8e Factors - TEENAGER l 2/I (mrem /yr per #Ci/m3) seclide 8ese 8.tver Tbrre18 Eidney Eans83-111 T.8eer 8-3 -

1.27E*3 1.27E*) 1.27t*3 1.278+3 1.278 3 1.27E*3 C-14

2. 60E* 4 4.87E*3 4.87E*3 4.47E*3 4.875*3 4.87E*3 4.87E*3 me-24 1.38t+4 1.38E*4 1.38t*4 1. NE*4 1.M8*4 9.385*4 1.Nt*4 P-32 1.89t*6 1.10E* 5 - - - 9.28E+4 7.1E+4 Cr-SS - -

7.50E*1 3.07E*1 2.988+4 3.00E+3 1.355 2 un-54 - ~5.11t*4 -

1.275 4 1.985+6 6.68E+4 8.40E*3 Me-M - 1.70E+0 -

1.198*0 1.82E*4 5.74E+4 2.52E-1 Fe-55 3.34E*4 2.38E+4 - - 1.348*$ 6.39t*3 5. ME* 3 Fe-59 f.99E+4 3.70E*4 - -

1.53t+6 1.788*5 1.43E+4 Co-57 - 6.925*2 - -

$.NE.5 3.14t+4 9.30E*2 Co-58 -

2.875 3 - -

1.NE+6 9.52s+4 2.788 3 Co-40 - 1.$1E+4 - - 8.72E+6 2.595+5 1.988+4 mi-43 5.80Ee$,4.Nt*4 - -

3.078+5 1.428*4 1.985*4 51-65 2.18t+0 2.93E-1 - -

9.35E+3 3.67E*4 1.27E-1 Co-H - 2.03E+0 -

6.41E*0 1.11E+4 6.14E+4 8.485-1 to-65 3.86E*4 f.34 Eel -

8.64E*4 1.248+6 4.ME*4 6.24E+4 Re-49 4.83E-2 9.20E-2 -

6.025 3 1.588*3 2.85t*2 6.465-3 Sr-82 - * - = * - 1.82E+4 Sr-83 - - - = = - 3.44t.2 St 84 - - - - - - 4.33E*2 tr-85 - - - .

= = 1.83t*1 Re86 -

1.W!* 5 - - - 1.77E+4 8.40E*4 SPS8 - 5.46t*2 - = = 2.92E S 2.72E*2 ab-89 -

3.52E*2 - - - 3.38E-7 2.33E*2 Br-89 4. 34E* 5 - - -

2.428*4 3.71E*$ 1.2SE+4 i Sr-90 1.08E*8 - - -

1.658*7 7.6 H+$ 6.68t*6

\ St-91 8.80t*1 - - - 6.07E*4 2.59E*5 3.5tE+0 Sr-92 9.52E+0 - - -

2.74E+4 1.19E*$ 4.NE-1 4

T-90 2.985*3 - - - 2.93E*5 S.59E*$ 8.00E*1 T-91e 3.70E-1 - - - 3.30E*3 3.828*1 1.425-2 Y-91 6.61E*5 - - - 2.ME+6 4.99E*5 1.77t*4 Y-92 1.47E*1 - - - 2.641 4 1.65 Eel 4.29E-1 T 93 1.358*2 - - - 8.32E*4 5.795 5 3.72E*0 Er-95 1.465*$ 4.58t+4 -

6.74E*4 2.69E 6 1.49t.5 3.15E*4 Er-97 1.38E*2 2.72t*1 -

4.125*1 1.305*$ 4.30E*5 1.265 1 up95 1.NE+4 9.032 4 -

1.00t.4 7.518+l 9.68t*4 5.ME* 3 m>97 3.14E-1 7.78E-2 -

9.12E-2 3.9M* 3 2.17E*3 2.848-2 sto*99 - 1.69E*2 - 4.11E*2 1. HE* 5 2.69E*5 3.22E+1 Te-99e 1.34E-3 3.NE-3 -

8.762-2 1.158*3 6.138*3 4.99E-2 Te-101 5.923-5 8.608-5 -

1.52t-3 4.67E*2 8.723-7 8.245-4 Se-103 2.10E*3 - -

7.43E*3 7.83E*$ 1.09E* 5 8. NE* 2 Au*105 1.128+0 - -

1.41E+0 1.82t+4 9.M E*4 4.34E-1 Se-106 9.M8 4 - -

1.904*5 1.61E*7 9.40Ee$ 1.24E+4 RM 103e - - - - - -. -

Ab 106 - - - = = - -

As 110e 1.385*4 1.318+4 -

2.50E+4 4.75t+6 2.738*$ 7.99E*3 56-124 4.30E+4 7.M E*2 9.768*1 -

3.85t*6 3.98E*5 1.64t+4 SP125 7.30E*4 8.08E*2 7.NE*1 -

2.74B+6 9.92E*4 1.728 4 fe-125m 4.88t* 3 2.24E*3 1.40E*3 -

5.368 5 7.90s+4 6.675 2 fe-127e 1. 80E+4 8.168*3 4.NE* 3 6.548*4 f.668+6 1.595 5 2.18E*3 Te-127 Te-129s 2.018+0 9.125-1 1.425*4 7.20E+0 1.128+4 8.88t+4 4.428-t Te-129 t.398 4 6.585*3 4.58E*3 5.19E*4 1.985*6 4.0$2*5 2.255*3 7.105 2 3.30E 2 5.18E-2 2. NE-1 3. NE* 3 f.62E*3 f.76E-2 Te-tale 9.N E*t 6.01E*1 7.25E*1 4.39t*2 2.ME*5 6.2tE*5 4.025 1 Te-131 1.888 2 4.325-3 1.24E-2 6.188-2 2.M8+3 1.81E*1 5.NE-3 Te432 3.60E*2 2.90t*2 2.46t+2 1.95E*3 4.498 5 4.638 5 2.195 2 2-130 6. Mr*3 1.793+4 1.49g*6 2.75E*4 -

9.128*3 7.17E*3 2-131 3.5 .f *4 4.91E+4 1.46E*7 8.40E+4 - 6.49E* 3 2.N E*4 2 132 1.698 3 4.38E*3 t.lttel 6.928 3 - 1.27s*3 1.94E*3 2 133 1.228*4 2.058+4 2.92E*4 3.59E*4 -

1.038+4 6.225 3

ODCM-7.0 Revision 8

f. . Page 7.0-24

\'

Table 7.0-4 Ralpo, Inhalation Pathway Dose Fac'.ars - TEENAGER (Cont.)

(mrem /yr per #Ci/m3 )

l F/9J i

tuslide Seas Liver Thrteld Eldoey Ames41-142 f. Beer 2-134 8.88t*2 2.32E*3 3.958*4 3.Mt*3 - 2.ME*1 8.408*2 I-135 3.70t*3 9.44t*3 4.21E*5 1.498 4 - 6.958*3 3.49E*) l Co-1M 5.02E*5 1.13E+6 -

3.75E*5 1.46tel 9.76t*3 5.491 5 Co-1M 5.15E*4 1.94 t* 5 -

1.10t* 5 1.78t*4 1.09E*4 1.37tel Co 137 6.70E*5 8.48E*5 -

3.04t*5 1.21E*5 8.488 3 3.11t*5 Co-1M 4. ME* 2 8.56t*2 -

6.628*2 7.87E*1 2.708-1 4.ME*2 Se-139 1. M E+0 9.44E-4 -

8.488-4 6.46t*3 6.45t*3 3.908-2 Be-140 5.47E*4 6.70E*1 -

3.20E*1 2.03E*6 2.29E*5 3.525 3 j as-141 1.425-1 1.NE-4 -

9.M5-5 3.295 3 7.MS 4 4.74 5-3 '

8e-142 3.708-2 3.795-5 -

3. ME-5 1.918*3 -

2.37.t-3 1a-140 4.795 2 2.ME*2 - -

2.14B+5 4.87tel 6. Mt*1 14-142 9.408-1 4.25E-1 - -

1.025+4 1.30E+4 1.NE-1 Co-141 2.44E*4 1.90t*4 -

8.88t*3 6.148*5 1.368*5 2.17E*3 Co-143 2.ME*2 1.94E*2 -

8.64E*1 1.305 5 2.55t*5 2.16t*1 Co-144 4.89E*6 2.02E*e -

1.21t*6 1.348*7 8.Mtel 2.628*5 Pr-143 1.Mt+4 5.31E+3 -

3.098 3 4.83E*5 2.148*5 6.62t*2 Pr-144 4.30E-2 1.76E-2 -

1.01E-2 1.75t*3 2.358-4 2.18E-3 54-147 . 7.86E*3 8.56E*3 -

5.02E*3 3.72E*5 1.828*5 5.13t*2 W-187 1.20E*1 9.76E*0 - -

4.74t*4 1.771*5 3.4H+0 ar-239 3.34t*2 3.19E*1 -

1.00E*2 6.49E+4 1.321*5 1.77E*1

{

ODCM-7.0 Revision 8

,. Page 7.0-25 1 f

\

Table 7.0-4 Ralpo, Inhalation Pathway Dose Factor 8 - CHILD l P/[

(mrem /yr per pCi/m3) bec1He Game Lher Thrrete Riemey Lens82-411 T. Seer N-3 . 1.138+3 1.13E+3 1.128+3 1.128+3 1.138+3 1.128*3 C-14 3. 5M*4 6.738 3, 6.738*3 6.73b3 6.7H+ 3 6.7H+3 6.73t*3 me-34 1.61E+4 1.618+4 1.615+4 1.61E+4 1.618 4 1.618 4 1.615+4 F-32 3.605 4 1. M8* 5 - - - 4.32b4 9.88E4

Cr-51 - - 4.55E+1 3.435+1 1.70E+4 1.e88 3 1.548+2 gen-54 - 4.39E*4 - 1.00s+4 1.588 4 3.395+4 9.51s*3 the-M - 1.ME+0 - 1.67E*0 1.315+4 1.338*5 3.125-1 Fe-55 4.74E+4 2.522 4 - - 1.118*5 3.878+3 7.77t+3 Fe-59 3.078+4 3.Mbe = = 1.37b6 7.078*4 1.67be Co-57 - 9.03b2 - - 5.07b5 9.HS*4 1.07E*3 Co-58 - 1.775 4 - - 1.11B+6 3.44B+4 3.16b3 Co-60 - 1.315+4 - - 7.075+6 9.638+4 2.36E*4 Si-H 8.21E+5 4.63E+4 - - 2.75E+5 6.33b3 2.80E+4 81-45 2.995+0 2.ME-1 - - 8.188+3 8.40b4 1.NE-1 Cree - 1.998+0 - 6.0H+0 9.58b3 3.67be 1.07E*0 In-65 4.36E+4 1.1 H+ 5 - 7.14t*4 9.95t*5 1.H8+4 7.038+4 2n49 6.70b2 9. M E-2 - 5.85E-2 1.4'!*3 1.02E+4 8.928-3 3r-82 . = = = = = 2.09t+4 St-83 - - - = = = 4.74E*2 Gr-M - - - - - - 5.448*2 Gr-85 - - - - - - 2.53E*1 SbH = 1.98E*5 - - - 7.99E*3 1. Mb 5 Sb88 - 5.62E*2 - = = 1.72E+1 3.MD2 tha9 3.45t*2 - - - 1 898+0 2.90E*2 8,-8 S.,M.5 - - - 2.ut.6 .6Ho 1.7H.4

(

St-90 1.01E+8 - =

1.44E*7 3.43E*5 6.44E+6 er-91 1.315+2 - - - 5.338 4 1.74t*5 4.595+0 er-92 1.318+1 = = = 2.40be 3.42b 5 5.258-1 F90 4.11b 3 - - - 2.625+5 3.68b5 9.11b2 T-9te 5.075-1 - - - 3.81E*3 1.72E+3 1.448-2 T-91 9. MB+ 5 - - - 3.63E+6 1.MB+ 5 3.44E+4 bt2 3.04 b t - - - 3.395+4 3.3M+ 5 5.Sibt F93 1.86b2 - - - 7.44E+4 3.998+5 5.11bc Er-95 1.90E*5 4.188+4 - 5.965+4 3.23R+6 4.118+4 3.70E*4 i 3r-97 1.54E*2 3.72E+t - 3.89pt 1.13s+5 3.515+5 1.80E*1 ub95 3.355+4 9.188+1 - 8.62E+3 6.M8+5 3.70t+4 4.555+3 )

pbt? 4.395-1 7.70E-2 - 8.558-2 3.42E+3 2.788+4 3.60b2 I sto-99 - 1.728+2 - 3.925+2 1.358+5 1.378+5 4.368+1 Te-98s 1.788 4 3.48b3 - 5.878-2 9.515+2 4.818+3 5.77b2 Te-101 8. 90b5 8.515-5 - 1.458-3 5.85E*2 1.638+1 1.888-3 8e-803 3.798+3 - - 7.038*1 6.63E+5 4.485+4 1.078+3 Se-105 1.538+0 - - 1. M 5+0 1.59b4 9.95E+4 5.558-1 to-106 1.36b5 - - 1.84B+5 1.438+7 4.298+5 1.698+4 sh-103m = - * - = = =

Bh=106 - = = - - = =

As-190m 1.695+4 1. Mb4 - 3.128+4 5.448+6 1.80B+5 9.M8+3 abile 5.74E+4 7.40E*2 1.36b3 - 3.24E+6 1.Mb5 3.00be 86-125 9.M B+4 7.598+2 9.10E+1 - 2.328+6 4.93t+4 3.075+4 Te-tale 6.73E4 3.338 4 S.92B+3 - 4.775+5 3.385+4 9. ME*2 Te-137e 2.498+4 8.558+3 6.078+3 6.365+4 1.488+6 7. M8+4 3.038 4 Te-137 3.77be 9.515-1 1.96be 7.07be 1.00t+4 5.62E+4 6.118-1 Te-129m 1.92t+4 6.85t+3 6.33t+3 5.03t+4 1.76t+4 1.825*5 3.M E*3 Te-129 9.77bt 3.50b2 7.148-2 3.575-1 3.938+3 2.55b4 2.385-2 Te-tale 1.34B+2 5.92E+1 9.778+1 4.00t*2 2.06b5 3.08t+5 5.978+1 Te-131 3.17b2 8.448-3 1.70s-2 5.88b2 3.05b3 1.33b3 6.59E4 Te-132 4.81t+2 3.728+2 3.178+2 8.778+3 3.77b 5 t. Ht+5 3.63E+3 2 130 8.188+ 3 1.Mbe 1.852+6 2.458+4 - 5.11E+3 8.44E*3 I-131 4.81E+4 4.01E*4 1.62E+7 7.88t+4 = 3.Mb3 3.7H+4 2.12t*3 4.078+3 1.ME*5 6.35t*3 3.30t+3 1.88b3 C -

bt32 ht33 1.ME+4 3.0H+4 3.858+6 3.388+4

- 5.44t*3 7.70E*3

ODCM-7.0 Revision 8 Page 7.0-26 Table 7.0-4 Ralpo, Inhalation Pathway Dose Factors - CHILD (Cont.)

(mrem /yr per yCi/m3) l9/V Eastide asse Liver Thytead Sidney & ass el*4JJ f.tedr I-134 1.17t+3 2.16t+3 5.075+4 3.308 3 - 9.55t+2 9.95E+2 1-135 4.92E*3 8.73E+3 7.925 5 1. ME+4 - 4.445*3 4.14E*3 Co-t u 6.51E*5 1.01E+6 - 3.30E+5 1.2fE+5 3.45s+3 2.25t*5 6 Co-136 6.51E+4 '1.71E*5 - 9.55E+4 1.#.5E+4 4.18t+3 1.16t+5 Co-137 9.07E*5 8.25E*5 - 2.82E*5 1.04E+5 3.62E*3 1.28E*5 Ce=1H 6.335 2 8.40E+2 - 6..t+:*2 6.01t+1 3.708*2 5.555+2 to-139 1.84E+0 9.845-4 - 8.625-4 5.778+3 5.778+4 5.375-2 So-MO 1.40E+4 6.485 1 - 2.115+1 1.748+6 1.02s+5 4.338*3 Se-141 1.968 1 1.095-4 - 9.475-5 3.928+3 2.758+2 6.368-3 Se-int 5.005-2 3.60E-5 - 3.918-5 1.648+3 3.748+0 2.798-3 Le-140 6.448+2 2.258+2 - - 1.835+5 2.368+5 7.55s+1 La-142 1.30E+0 4.11E-1 - - 0.7e8+3 7.598+4 1.295-1 Co-141 3.92E*4 1.955+4 - 8.55t+3 5.44t+5 5.668+4 2.905 3 Co-143 3.66E*2 1.99E+2 - 8.36E*1 1.15E+5 1.275+5 2.878+1 Co-144 6.775+6 2.12E+6 - 1.175+6 1.30E*7 3.098+5 3.618+5 Pr-143 1.85E+4 5.55E+3 - 3.00E*3 4.33E.5 9.73E+4 9.14B+2 Pr-%4 5.96E-2 1.85E-2 - 9.77E-3 1.578+3 1.975+2 3.00E-3 Ed-147 1.00 E+4 8.73E+3 - 4.815 3 3.281+5 8.21E+4 6.81E+2 W-107 1.63E*1 9.64E+0 - - 4.11E+4 9.10E+4 4.338+0 5P-239 4.66E+7 3.34E+1

9.73E+1 5.01E+4 6.40E+4 2.35E 1

ODCM-7.0 Rethion 8 Pige 7.0-27

/s

(

Table 7.0-4 Ralpo, Inhalation Pathway Dose Factors - INFANT l 9/4f~

(mrem /yr per pC1/m3) nonnae some u+er smyrou nueer sans et-u.3 s.aony 5-3 - 6.4?E*3 6.478 3 4.478+3 6:478+3 6.478+3 6.4?E*3 C-14 '3.658+4 $.31E+3 6.31E+3 5.3tE*3 5.318+3 S. Stb 3 S.3tt+3 No 34 1.NE*4 1.NE+4 f.Mbe 1.ME*4 1.065+4 1.06b4 1.M8+4 P-33 3.035+4 1.135+$ = - - 1.6tE*4 7.748+4 '

Cr 51 - - 8.758+1 1.338+1 1.388+4 3.578+3-8.958+1 No-54 - 3.$3E+4 - 4.988 3 1.008+4 7.068+3 4.985+3 the-M - 1. NE+0 =, 1.108+0 1.368+4 7.17be 3.3tbt Fe-ll 1.978+4 1.175+4 - - 8.698+4 1.098+3 3.33b3 Fe-H 1.36be 3.358+4 - - 1.tabe 3.488+4 9.40b3 Co 57 - 6.51E+3 - - 3.795+$ 4.068*3 6.41E*3 Co-88 - 1.33E+3 - - 7.77bl 1.11b4 1.838+3 Co-40 - 8.03E*3 - - 4.815+4 3.198+4 1.188+4 5143 3.398+5 3. M E+4 - - 3.095+5 3.43E+3 1.16b4 N145 3.39E+0 2.84E-1 - - 8.135+3 5.etb4 1.3M-1 Co-H = 1.8$b0 - 3.9tbo 9.30E*3 1.905+4 7.745-1 3a45 1. 9' En 4.34E+4 - 3.35E+4 6.478+5 S.145+4 3.ttt+4 Sa49 5.191 ' 675 3

- 4.03E-3 1.475+3 1.32b4 7.185-3 tr-82 - - = = = 1.31E+4 tr-83 - = = = = 3.SiE*3 tr-44 - - = = = - 4.008*3 Br-85 - - = = = - 3.Mb t a6-84 - 1.90E+5 - - - 3.04b3 S.83be l Ab-te - $.578+3 - - - 3.391+3 3.87b3 )

at-89 - 3.31E*3 - = = 6.83E+t 3.ME*3 St-89 3.98E+$ ' = - - 3.938+4 6.40E+4 1.14E+4 St-90 4.09b7 - - - 1.13E+7 1.3tb 5 3.898+6 St-91 9.54E+l - - - S.365+4 7.34E+4 3.44E+0 l St-93 1.0$b t ,

- - 3.385 4 1.408+5 3.915-l i b99 3.398+3 - - - 3.698+5 1.ME+ 5 8.83b t )

T 'sta 4.078 1 - - - 3.79E*3 3.35b3 1.395 3 T-91 S.84E+5 - - - 3.45E+6 7.93E+4 1.578+4 !

T-93 9.64E+1 - - - 3.458+4 1.37t+5 4.61bt l T-93 1.908+3 - = = 7.Mb4 1.67b 5 4.07E*0 l Es-95 1.16b5 3.798+4 - 3.11b4 1.75E4 3.175 4 3.035 4 Ar=97 1.90b3 3.ME+1 - 3.598+1 1.105+5 1.4ebl 1.178+1 sb-95 1.578+4 6.438+3 - 4.73E+3 4.798+5 1.378+4 3.788 3 Nb-97 3.438-1 7.398-3 - S.708-3 3.33E+3 3.698+4 3.638-3 1 he *9 - t.45E+3 - 3.658+3 1.35bl 4.875+4, 3.33E+1 l fc-99m 1.40b3 3.88b3 - 3.118-3 8.115+3 3.03E*3 3.73b3 i fe-101 6. Stb 5 8.3M-5 - 9.79b4 5.esb3 8.uS*3 8.135-4 au-103 3.03E+3 - - 4.34E+1 5.538+5 1.61E+4 6.79t+3 trate5 *t.338+0 - - S.995-1 1.878+4 4.048+4 4.tet-t au-106 8.648+4 - = 1.978+ 5 1.teb7 1.64bl 1.098 4 sh-telo - -

ab-146 - - - - - - -

As-ttes 9.98b3 7.33E+3 - 1.098+4 3.6?b6 3.308+4 5.808+3 86-134 3.798+4 5.568+3 1.9tb3 - 3.elbe 5.918+4 1.30E+4 36-135 S.178+4 4.77b3 6.338+1 - 1.64E+6 1.478+4 1.09E+4 to-tals 4.768+3 1.998+3 1.638+3 - 4.47b5 1.398+4 6.84E+3 Te-187a 1.675+4 6.908+3 4.87b 3 3.765 4 1.31b6 3 735+4 3.078+3 fe=127 3.338+0 9.5Sbt 1.8$be 4.06be 1.0184 3.448+4 4.09pt fe-130s 1.418+4 4.99Ee3 S.478 3 3.188 4 1.688+6 6.908+4 3.3H+3 Te-139 7.888 3 3.47b3 6.758-3 1.758-1 8.008*3 3.63E4 1.088-3 fe-131e 1.078+3 5.908+1 8.91b1 3.658+2 1.995+5 1.198+5 3.63E+1 Te-131 9.74>3 8.338-3 1. Sept 3.995-3 3.06b3 8.32b3 $.008-3 Te-133 3.738+3 3.37b3 3.798 3 1.038+3 3.40s+5 4.4tb4 1.768+3 3-130 6.34Ee3 1.39b4 1.60E+4 1.53E+4 - 1.995+3 $.578+3 3-131 3.79E+4 4.448 4 1.448+7 $.1884 - 1.ME*3 1.96be 3-133 1.49E*3 3. ME* 3 1.69E+5 3.958+3 - 1.90h3 1.Mb3 1.338+4 1.938+4 3.56b6 3.345+4 3.16b3 5.005+3 C 3-133 -

l I

1 I

ODCM-7.0 Revision 8 Page 7.0-28

{ ',

Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT (Cont.) lh/I)#

(mremlyr per pCi/m3) buslide toes Liver thrrold ENesy $ sag SI 412 f.tedr 3-1M 9.21E*2 t.84E+3 4.45E+4 3.99b3 - 1.29b3 6.65b2 2-135 3.Mb3 7.40E+1 6.NE*5 8.47b3 - 1.43E+1 3.77b3 Co-1M 3.96E+5 7.03E+ 5 - 1.90E*5 7.978 4 1.33E+3 7.45b4 ,

Co-1M 4.83E+4 - 1.35b5 - 5.ube 1.tspe 1.433*3 5.29E+4 -

Co-137 5.4 9E+ 5 6.12b5 - 1.72E+5 7.13E+4 1.385+3 4.55E+4 Co-134 5.05b2 7.81E+2 - 4.10b2 6.M E*1 8.768+2 3.98b2 So-139 1.48b0 9.04be - 5.92E 4 5.95t*3 5.105 4 4.305-2 Se-140 5 40E*4 5.40E*1 - 1.Mb t 1.60E+4 3.NE+4 2.90E+1 to-141 1.575 1 1.005 4 - 6.50b5 2.97b3 4.75b3 4.97b3 to-le2 3.908-2 3.305-5 - 1.908 5 1.55b3 6.938+2 1.Mb3 La-140 5.05E+2 2.00E+2 = = 1.68b5 8.48b e 5.15E+1 Es *42 1.03E+0 3.775-1 - - E.22b3 5.95b4 9.ME 2 Co-141 2.775 4 1.675 4 .

= 5.25E+ 3 5.175+5 3.165 4 1.99E+1 Ce 143 2.938+2 1.93E* 2 - 5.HE*1 1.16b5 4.978+4 2.21E+1 Co-164 3.19E+6 1.215+6 - 5.385+5 9.845*6 1.448*5 1.765+5 Pr-143 1.40E+4 5.345*3 - 1.975+3 4.33b 5 3.72E+4 6.99E*2 Pr-144 4.79E 2 1.05E-2 - 6.72E 3 1.61b3 4.38h3 3.41E-3 N-lef 7.ME*3 8.1SE*3 - 3.15E+3 3.22b5 3.12E+4 5.00E+2 W-187 1.50E*1 9.02E*0 - - 3.96be 3.NE+4 3.12E+0 me-239 3.71E+2 3.328*1 - 6.62E+1 5.95be 2.495+4 1.4eb t t

ODCM-7.0 Revision 8 G

Page 7.0-29 !

t Table 7.0-4 Raipo, Grass-Cow Milk Pathway Dose Factor 8 ADULT (mrem /yr per yCi/m )3 for H 3 and C-14 l P/1[

(m2 x mrem /yr per Ci/Sec) for othere seelsee Gene s.ine Tlirrets sumer smes as-u.1 T. Seer 83 . - 7.HE* 2 7.63E*2 7.6M* 2 7.63b2 7.635 2 7.63E+2 .

C-14 3.HE*5 7.36be 7.36E+4 7.368+4 7.368+4 7.36E*4 7.Mbe Se-24 2.54E+6 2.645 6 2. ME*6 3.Mb6 2.leb6 2.NE4 2. NE*6 p.32 1.71E+10 1.065+9 - * - 1.938*9 6.60E+8 Cr-51 - - 1.718+4 6.388*3 3.00b4 7.30b6 2.Mb4 see-54 - 8.4GE+4 - 2.90E+4 - 3.57b7 1.60b6 81e-56 - 4.2M-3 - 5.385-3 - 1.398-l F. 5154 Fe-5f 2.S18*7 1.7M. 7 - - 9.675+6 9.968+4 4.04E*6 Fe-59 3.98E*7 7.00E*7 - - 1.9$5+7 2.33b8 2.68E+7 Co-57 - 1.38t*6 - - - 3.25E+7 2. lM+6 Co-58 - 4.72E+6 - = = 9.575+7 1.NE*7 Ce40 - 1.M E*7 - = = 3.00E*8 3.628+7 8143 4.738+9 4. ME*8 - = = 9.735+7 2.36t+8 S&45 3.70E 1 4.81E-2 - = = 1.128+0 2.19E-2 Code - 2.4tb4 - 6.08b4 - 2.068 4 1.13E+4 8e45 f.37b9 4.Mb9 - 2.92E*9 - 3.75E*9 1.97b9 g 69 - - - - - - -

Sr-82 - - = = - 3.72b7 3.2SE*7 er-83 - - - - - 1.49b1 1.835-1 3r-34 - = = = = = -

3r.85 - - - = = - -

. Skee - 3.$95+9 - = = $.11E+8 1.21bt

gett, get - - - - - = =

8t-89 1.4$pt = = = = 2.338+8 4. ME* 7 St-90 4.688*10 - - - - 1.3SE*9 1.158*10 St-91 3.13E+4 = = = - 1.4DE*5 1.27E*3 St-92 4.89E-1 * - = = 9.68E+0 2.11E-2 T*90 7.07b t = = = = 7.90E+$ 1.90S+0 T-95e - - - = * * -

T-91 8.808*3 - - - - 4.738 4 2.30p2 T-92 5.425-5 - - - - 9.498-1 1.585-4 T-93 3.33bt - - - - 7.398*3 6.43b 3 tr-95 9.465+2 3.835 2 - 4.765+2 - 9.628*$ 2.058+2 Er-97 4.36bt 8.59E-2 - 1.30E-1 - 2.66be 3.938-2

. Sb95 8.25be 4.99b4

- 4.548+4 - 2.79b8 2.478+4 Mb-97 - - = =

5.478-9 -

Iso-99 - 3.52b7 = 5.728+7 - 5.8ss+7 4.808+6 To-90s 3.3the 9.19be - 1.4e8+2 4.30D0 $.448+3 1.178+2

= = = - -

T.o-tot e-SM 1.M +3 - - 3.8M+ 3 - 1. ,M* i 4.3M.3 )

as-tel 8.578 4 - - 1.118-2 - S.NE-1 3.385 4 '

as-106 3.MI+4 a - 3.M8+4 - 1.12b6 3.58b3

= = = = = i Sb t03. - -

- - * *

J Sbs06 -

as-110. S.83B+7 5.398*7 - 1.06be - 3.388+10 3.388+7 ablae 2.57b7 4.ME*l 6.348 4 - 3.80b7 7.398+8 1.03E*7 Sb125 3.ME*7 3.38bl 3.88be - 1.ME*7 2.2SB+8 4.86E+6 Te-126. 1.63b7 5.90E+4 4.905 4 4.63b7 - 6.90E*7 3.188+6 Te-127e 4.588+7 1.M8+7 t.17b7 1.865*8 - 1.948+8 $.SSE+6 Te-127 6.728*2 3.41b2 4.988+2 3.748 3 - S.385+4 1.45E+2 Te-129. 6.ME*7 2.25b7 2.088*7 2.528+8 - 3.MPs 9.5754

= =

ye-129 - = =

Te-131e 3.615+5 1.775*5 2.80bl 1.798+4 - 1.75b7 1.47b5

= = = = -

Te-131 ,

Te-132 3.39E*4 1.158 4 1.7tt+6 t.498+7 - 7.338+7 1.45b6 1.885 4 4.96E*l C htte F131 4.36E 5 1.26b6 1.078+8 1.M8+6 2.968+8 4.34E+8 1.39h ti 7.375+4

- 1.12b8 3 4Sb8 bili 1.ME-1 4.375-1 t.638+1 6.97bt - 8.328-2 1.838-1 bt33 3.975+6 6.90E*6 1.0tb9 1.38b7 - 4.38b6 3.188 4

ODCM-7.0 Revision 8

(~.

Page 7.0-30 Table 7.0-4 Raipo, Grass-Cow Milk Pathway Dose Factors - ADULT (CONT.) l 91/~~

/

(mrem /yr per pCi/m 3) for H 3 and C-14 (m2 x mrem /yr per yC1/sec) for other8 s s see 8 um 9mycess sumer sans es-s12 v. Seer 3-tu - - - - = = = ,

I-135 1.39t+4 3.63B+4 3.448+6 5.438+4 - 6.10S+4 1.ME*4 Co-134' 5.65E+9 1.34t*10 - 4.358+9 1.44t*9 3.358+4 1.10E*10 C -134 2.61E*8 1.03E+9 - 5.74E*4 7.47E*7 1.178+8 7.438*8 Co-137 7.38E*9 1.ett+10 - 3.438*9 1.14E+9 1.955+8 6.61E+9 Co-338 - = = = = = =

Se-139 4.70E-8 - - - - 4.MS-e 1.388-9 to-140 2.695+7 3.M8+4 - 1.1M+4 1.938+6 5.MS*7 1.768+6 an.143 - - - = = = =

= - -

Sa-142 - - - =

14-140 6.49E+0 3.368+0 - - - 1.465+5 5.978-1 La-142 - - - - - 3.038-8 -

Ce-141 4.84E+3 3.27E*3 - 1.52E*3 - 1.255+7 3.7tE*2 Co-143 4.19E*1 3.09E+4 - 1.ME*1 - 1.16E+4 3.428*0 Co-144 3.58E*$ 1.50E*5 - 8.875+4 - 1.218+8 1.928+4 Pr-143 1.59E*2 6.37E*1 - 3.685*1 - 6.968+5 7.845*0 Pr-144 - - - -

N-147 9.42E*1 1.09E+2 - 6.37E*1 - 5.23E*5 6.528+0 W-187 4.ME* 3 5.48E*3 - - - 1.40E*6 1.928+3 NP 239 3.66E+0 3.60E-1 - 1.13E+0 - 7.39E*4 1.NE-1 f

l I

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- - - . - _ . . - - - ~ . . . . - .. ...- - - - . - - - - . . . - - .-

ODCM-7.0 Revision 8 Page 7.0-31 Table 7.0 4 Raipo, Gra8S-Cow Milk Pathway Dose Factors - TEENAGER l P/fj' (mrem /yr per pCl/m 3) for H-3 and C-14 (m2 x mrem /yr per pCi/Sec) for other8 unslide Soes Meer Terrold Edmer lese $14LI T.Se87 5-3 -

9. M E* I 9.M5+2 9.Mb3 9. Mt+3 9.M8+2 9.ME*2 ble 6.708+5 1.Mb 5 9. ME* 5 1.ME+5 1.ME* 5 1.NE* 5 1.Mb 5 un-34 4.4484 ' 4.44t+6 4.44p6 4.448+6 4.44be 4.448+6 4.448+6 P-32 3.tSt+10 1.95pt - - - 3.65t*9 1.225*9 Cr=51 = = 3.788+4 1.tebe 7.1 M+4 8.4eb6 5.00be me-54 - 1.40s*7 - 4.178+6 - 3.87t+7 3.78t+6 me-M = 7.915-3 - 9.988 3 - 4.M E-1 1.H84 Fe-55 4.46t+7 3. ME* 7 - - 3.00E+7 1.378+7 7. Mt+4 i Pe-$9 5.30p? 1.31t*8 - - 3.83847 3.87b8 4.688+7 !

Co-57 - 3.25E*6 - - -- 4.198+7 3.765 4 Co-58 - 7.955+6 - - - 1.10E+8 1.838+7 Co-60 - 3.78p? - = = 3.638+8 6.365+7 51-63 1.188*l0 8.355*8 - = = 1.338+8 4.ett+8 ,

5145 6.78bt 8.64E 2 - - - 4.7ep o 3.ME-2 l Cu44 - 4.39E+4 - 3.998+5 - 3.3M+6 2.035*4 l So-65 3.11E+9 7.31E+9 - 4.688+9 -. 3.10b9 3.4tb9 3e-69 - - - - - - - ,

ar-42 - - - - - - 5.64E+7 St-83 - - = = = - 1.915-1 '

8,.u - - - - - - -

l 8,.85 - - - - - - -

Se,.te

- 4.738+9 - - -

7.008+8 3.328+9

- - - - =

g 8.

8 89M - = = = = = -

8t-89 3.678*9 - - - - 3.188*8 7.668*7 St-90 6.61E*10 - - = = 1.865+9 1.61E+10 St-91 5.768*4 - - - - 3.615*5 3.398*3 St-92 8.958-1 = = = = 3.38t+1 3.818-2 F90 1.30E+2 - - - - 1.078+6 3.50E+0 T-9te - - - - _= = -

T-91 1.588+4 - - - - 6.448*6 4.34b2 T 92 1.005 4 - = = = 3.758+0 3.905-4 T-93 4.30E 1 - - - - 1.318*4 1.188-2 Er-M 1.668+3 $.32b2 - 7.678*3 - 1.388+6 3.598*2 3r-97 7.758 1 1.338-1 - 3.338-1 - 4.158 4 7.068-2 a>95 1.618+5 7.80E+4 - 7.578+4 - 3.MB+4 '4.3004 upt7 - - - - - 6.M8-8 -

me-99 - 4.Mt*7 - 1.MB+8 - 8.168*7 8.698+6 Te-90s 5.64B+4 1.57b1 - 2.Mb3 8.7M+0 1.eM*4 3.M8+3 Te-101 - - - - - = =

Su-103 1.818+3 - - 6.408+3 - 1.538+$ 7.768*2 an-105 1.$75-3 - - 1.978-3 - 1.Mbe 6.088-4 to-106 3.75B+4 - - 7.33be - 1.888+6 4.7M+3 ab team - = = = = - -

h t06 = = = - - - -

AS-tles 9.63B+7 9.11B+7 - 1.748+4 - 3.968+10 5.M8 7 oktte 4.993+7 4.44t*5 1.Mb 5 - 4.91t*7 9.358+4 1.793*7 i SW135 . 3.668*7 3.998+5 3.49b4 - 3.3fb7 3.Mbe 8.Mb6 l To-tale 3.00B+7 1.088*7 8.395+6 - - 8.868+7 4.938+6 <

Te-187e 8.448*7 3.998*7 3.9t>7 3.43b8 - 3.188+8 1.008+7 ,

Te-137 1.M8*3 4.4tE*3 8.99b2 5.MB+ 3 - 9.61B+4 3.688*2 Te-129s 1.t tb8 4.10B+7 3.578+7 4.63E+8 - 4.158+8 1.758*7 Te-139 - - - 1.67E-9 - 3.188-9 -

Te-13te 6.578*5 3.158+5 4.74b5 3.'3906 - 3.5M*7 3.638+5 y ,.333 - - - - - - -

Te=133 4.388+6 3.718+4 3.86b6 3.80B+7 - 0.98b7 3.ll>6 3-130 7.49E*l 3.178+6 1.77t+8 3.Mb6 - 1.678+4 8.668 5 C I-131 3 138 8.385+8 7.538+8 3.308+t1 1.388+9 3.988-1 7.$98-1 3.968*1 1.3ebt 1.49E+8 4.M5+4 3.318-1 3.738-1 3-133 7.M84 1.338 7 1.73B+9 3. t t>7 - 9.388*6 3.758+6

ODCM-7.0 Revision 8 lt > Page 7.0-32

\

Table 7.0-4 Raipo, Gra88-Cow Milk Pathway Dose Factor 8 - TEENAGER (Cont.)

(mrem /yr per pCi/m 3) for H 3 and C-14 l P/'!I (m2 x mrem /yr per pCi/Sec) for othere mus!!de toes Liver Thrrold Eldeer Emm8 81-113 f.Sedr 1-114 = . - . - . .

3-135 2.47E*4 6.35t*4 4.08E+6 1.e0E*5 - 7.03E+4 2.358+4 Co-134 9.81E+9 2.31E*10 -

Co-1H 7.34E*9 2.00E*9 2.878*8 1.078*10 4.45E.8 1.75E*9 -

9.538*8 1.50E*8 1.418+8 1.188*9 Co-137 1. M 8*10 1.785*10 -

6.968+9 2.358+ 9 2.538+8 6.388*9 Co-118 = - - . = = =

Se-13/ 8.69E-8 - - - - . 7.758-7 2.538-9 Se-140 4.858*7 5.958*4 -

2.038*4 4.888*4 7.698+7 3.138+6 3.-141 - . - - . - .

3 143 - . . . .- - 14-140 8.NE*0 3.96E*0 = . . 2.378+5 1.058*0 La-142 - - - . - 2.338-7 -

Co-141 8.87E*3 . 5.925 3 - 2.79E*3 Co-143 1.698 7 6.81E*2 7.69E*1 5.60E+4 - 2.51E*1 -

1.68E+6 6.258*0 Co-144 6.58E*5 2.725*5 - 1.63E+5 -

1.665+8 2.54E+4 Pr-143 2.92E*2 1.17E*2 - 6.778+1 -

9.41E*5 1.458*1 Pr=164 - - - - . = =

Nd-147 1.81E*2 1.97E*2 - 1.168*2 -

7.118+5 1.18E*1 W-187 1.20E*4 9.78E*3 - * -

2.65Ee6 3.43E*3 NP-239 6.99E+0 6.598-1 - 2.07E*0 -

1.86845 3.665-1 l

l I

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.u.. -- . .

ODCM-7.0 Revision 8

(' Table 7.0-4 Page 7.0-33 Ralpo, Grass-Cow Milk Pathway Dose Factors - CHILD j P/V (mrem /yr per pCi/m 3) for H 3 and C-14 (m2 x mremlyr per #Ci/sec) for others Sastide asse Mwer Thytels Edme7 Imt $1413 T. Seer 8-3 - 1.57b) 1.578+3 1.678+3 1.878+3 1.57b 3 1.lfb3 ,,

0-14 1.658 4 3.398+5 3.398+5 3.398+1 3.398+5 3.398+ 5 3.39b5 as-34 9.338+6 9.338+6 9.338+6 9.338 4 9.338 4 9.338+6 9.338+6 P-H 7.77b10 3 648+9 - - - 3.158+9 3.00b9 Cr-51 = = 8.66b e 1.558+4 1.038+5 5.418+6 1.03b5 me-54 - 3.098+7 = l.878+6 - 1.768+7 S.588+4 he-56 - 1.318-3 - 1.588-3 - 1.90b0 3.958-3 Fe-$$ 1.138+8 $.938+7 - - 3.368+7 1.108+7 1.k8+7 Fe-59 1.308+8 1.958+8 - - S.658+7 3.938+8 9.718*7 Co-57 - 3.848+6 - - - 3.148+7 7.77be Co-58 - 1.215+7 - - - 7.488+7 3.738+7 Co-40 - 4.338+7 - - - 3.39bt 1.378+4 84-63 3.M8+10 1.598+9 - - 8- 1.078+8 1.015+9 81-65 1.M8+0 1. Mb t - - - 1.91b1 9.118-3 on-64 - 7.558+4 - 1.83b5 - 3.54b6 4.568+4 Se45 4.138+9 1.10b 10 - 6. Mbt - 1.938+9 6.858+9 Se-69 - - - - - 3.148-9 -

St-83 - - - - - - 1.158+8 St-83 - - - = = - 4.698-1

- = = - = = 4 Br=84 I

8,-8s

- - - 1 Sb-86 - 8.778+9 - = = $.44b8 S.398+9 i

( wu - -

- 4 89 -

St-89 6.638+9 - - - - 3.M8+8 1.098+8 Stato 1.138*11 - - - - 1.518+9 3.838*10 St-91 1.415+5 - - - - 3.138+ 5 $.338*3 Sr-93 3.198+0 - - - - 4.948*1 8.74b3 !

3.32b3 - - - - 9.1Sb5 8.61bc F,90 - - - - . - - l

9. te l b91 3.915+4 - - - - 5.318+6 1.M8*3 F92 3.46be = = = = 7 508+0 7.83b6 F93 1.068*0 - - - - 1.578+4 3.908-3 8s-95 3.M8+3 8.45b3 - 1.318+3 - 8.818+$ 7.538+ 2 St-97 1.098*0 3.738-1 - 3.9tbt - 4.138 4 1.618 1 Sk95 3.tebl 1.34bl - 1.168+5 - 3.398+4 's.M8+4

= - - 1.4Sb6 - l Sk97

No-99 - 8.39b7 - 1.778+8 - 6.06b7 3.958+7 Te-99e 1.398+1 3.568+1 - 3.etb3 1.398+1 1.u8+4 -

4.se8+3 To-let - -

- - 1.e884 - 1.115+5 1.658+3 as-tes 4.398+3 as-tel 3.838 3 - - 3.368-3 - 3.49be 1.39b3 h 106 9.M84 - - 1.35p5 - 1.44be 1.1584

- - - - =

- = . - -

.Ob.-te.ls

.. - = =

- 3.638+8 - 1.68ble 1.13b8 A4-ties 2.89b4 1.61b8 = 6.838+7 6.798+8 3.81>7 Sette 1.098+8 1.418+4 3.488+$

8bt35 0.708+7 1.41b4 8.868+4 - 4.868+ 7 3.888+8 1.438+7

- - 7.188+7 9.848+4 fe-13ts 7.38b7 3.40b7 2.078*7 - 1.488+8 3.478+7 Te-18?e 3.44b8 S.888+7 4.97b7 5.938+8

- 1.sep5 6. M8+3 Te-137 3.468+3 0.358+3 3.138+3 8.715+3 Te-139e 3.73be 7.6tb 7 8.788+7 8.00b4

- 3.338+8 4.33b7 6.188-8 -

Fe-139 - - - 3.878-9 -

Te-131e 1.8e8+6 5.538+5 1.M8+6 5 368+4

- 3.M8+1 5.89b5

= = = * -

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Te-131 1.038+1 4.138+4 6.548*4 4.308+7

- 6.nl8+7 5.468+6 Te-133 - 1.468 4 1.838+6 1.758 4 3.548+4 3.908+8 S.39b6 C bile bt31 1.308+9 1.318+9 4. MS*11 3.il>9 1.17b8 7.ub8 1.48be 5.8ebt F133 6.868-1 1. M be 5.858*1 1.93DO 1.76pf 3.188*7 4.84b9 3.638+7 - 8.778+4 8.3364 F133

... r. . . ,

)

ODCM-7.0 Revision 8

('

Page 7.0 34 Table 7.0-4 Ralpo, Grass-Cow-Milk Pathway Dose Factors - CHILD (CONT.) !NW (mrem /yr per pCi/m 3) for H.3 and C-14 '

(m2 x mrem /yr per pCi/sec) for others amessee sees user terr.se neuer ames es s&I t.emer 2-134 = . . . - - .

3-135 5.848+4 1.05E+5 9.308+6 1.618+5 - 8.00s+4 4.978+4 Co-134 2.265+10 3.718+10 - 1.158 10 4.138+9 2.005+8 7.83E+9 Co-134 1.00E+9 2.76t+9 = 1.478+9 2.19E+4 9.70E+7 1.798+9 Co-137 3.225*10 3.09E+10 . 1.01B+10 3.625+9 1.935+8 4.558+9 Co-138 - - . - = = =

Sa-139 2.148-7 - - - - 1.235-5 6.198-9 i to-140 1.175+8 1.038+5 - 3.348+4 6.125+4 8.948+7 6.848+4 l ha-141 * - * * * * - 1 Se-142 - = = = - *

l La-140 1.93t+1 4.74s+0 = . . 1.0s8 5 3.278+e 14-142 - - - = = 2.515-6 -

Co-141 2.198+4 1.09E+4 - 4.788+1 - 1.368+7 1.62s+3 Co-143 1.09E*2 1.025+5 - 4.29E+1 - 1.90E+6 1.448+1 Co-144 1.628+6 5.098+5 - 2.82s+5 - 1.33s+4 8.665+4 l pr-143 7.235 2 2.17E*2 - 1.178+2 - 7.40B+5 3.59t+1 pr-144 - - - - - - -

Ed-147 4.45t+2 3.60t+2 -

1.985 2 - $.718 5 2.79E+1 W-187 2.91E+4 1.72E+4 - - - 2.42E+6 7.73E+3 1 NP-239 1.72E+1 1.235+0 -

3.57t+0 - 9.548+4 8.688-1 l i

l l

I 1

l C

a... x.a-ODCM-7.0

(; Revision 8 t Page 7.0-35 1

Table 7.0-4 Ralpo, Gra88-Cow Milk Pathway Dose Factors - INFANT f

(mrem /yr per #Ci/m 3) for H 3 and C-14 (m2 x mrem /yr per yCi/Sec) for others amelies Seae Liver Thyroie 816eer Emes ablLI T. Soar 5-3 * -

. 3.34b3 3.M8+3 3.388*3 h.38 b 3 3.388+3 3.388*3 .

C-14 1.338+6 6.898+5 6.898+5 6.898+5 6.898+5 6.898+5 4.898+5 No-34 1.615+7 1.615+7 1.615+7 1.618*7 f.615+7 1.618+7 1.615+7 P-33 1.60 bit 9.438+9 - - - 3.178+9 6.318*9 Cr-St - - 1.058+5 3.2004 3.058+5 4.788+4 1.618+5 ane 54 - 3.89p? - 8.6H+6 - 1.438+7 8.838+6 he M - 3.31b3 - 3.768-3 - 3.9tb o 5.538-3 Fe-55 1.358+4 8.738+7 - - 4.37&*? 1.118*7 3.338+7 '

Fe-59 3.358+8 3.938+8 - - 1.16b8 1.088+8 1.558+8 Co-57 - 8.95be = = = 3.058+7 1.Mb7 Co-58 - 3.4M*7 - *

6.05p7 6.868+7 Co-60 - 8.815+7 - -+ - 3.108*8 3.888+8 51-63 3.498+10 3.168+9 - - - 1.878+4 1.218*9 54-65 3.515+0 3.978-1 - - - 3.038+1 1.018-1 Co-64 - 1.088+5 - 3.178+1 - 3.858 4 8.69b4 to-65 5.558+9 1.908+10 - 9.338+9 - 1.618+10 8.7899 Se49 - = = = - 7.368-9 -

tr-83 - - - - - - 1.M8+8 tr-83 - - - = = = 9.958-1

=

ar-84 - - - -

g - - - - - - -

( 8.r-85

-M - 3.3 M.10 - - - 5. 98 0 1.ta.ie s 8M - = = = - - -

36-39 - - - - -

St-89 1.368+10 - - - - 3.598*8 3.61b8 St-90 1.32 bit - - - - 1.53b9 3.108+10 St-91 3.M b 5 - - - - 3.488+5 1.M8+4 St-93 4.658+0 - - = = 5.01b1 1.738-1 T-90 6.008+3 - '

= = 9.398+5 1.83bt P91e -

= = - - - -

b91 7.338+4 - - - -_ 5.368+6 1.958+3 b93 5.338-4 - - - - 9.97b e 1.478-5 T-93 3.35be - - - - 1.748+4 6.188-3 Er-95 6.838+3 1.668*3 - 1.798 3 - 4.3895 1.188*3 St-97 3.99be 6.858-1 - 6.9tb1 - 4.37p4 3.135-1 sb-95 5.938+5 3.Mb5 - 1.75b5 - 3.868+8 1.415+ 5 ub-97 - - - - - 3.708-4 -

No-M = 3 138+8 - ' 3.178+8 - 6.988+7 6.13b7 fe-99e 3.698+1 5.558+1 - 5.978+3 3.98bt 1.4t>4 7.158+3 Te-let - - - - = . -

Su-103 . 8.498*1 - - 1.815+4 - 1.068+5 3.9193 me=105 8.86b3 - - 5.938-3 - 3.318*0 2.71>3 Be-106 1.908*5 - - 3.35pl - 1.648+6 3.38b4

- = = = - - i Sh-103e - '

- * - = = =

Sh-106 -

A8-110e 3.868+8 3.838*8 - 6.03b8 - 1.468+18 1.068+8 86 134 2.098+8 3.88be S.MS*5 - 1.3tb8 6.468+8 6.498+7 sb-135 1.4908 1.458+6 1.87b5 - 9.388+7 1.998+8 3.8797 fe-tale 1.518+8 5.Mb7 5.878+7 - - 7.188+7 3.M8+7 fe-137e 4.31p8 1.488+4 1.33b8 1.963+9 - 1.708+8 5.188*7 fe-137 6.308+3 3.188*3 5.398*3 1.998+4 - 1.368+5 1.488+3 Te-tate 5.59b8 1.93b8 3.16bG t.408+9 - 3.M b e 8.638+7 Te-139 3.888-9 - 1.758-9 5.188-9 - 1.Mb7 -

Te-13te 3.388+4 1.M84 3.768+6 9.358+6 - 3.39847 1.138+6 j * - - - -

- =

Te-131 Te-133 3.10B+7 1.M8+7 1.M8*7 6.51b7 - 3.858+7 9.788+6 3 12 3.6004 7.93b6 8.888+8 8.788+6 - 1.70b6 3.188+6 3-131 3.738+9 3.315+9 1.058+13 3.75bt - 1.158+8 1.41bt 3-133 1.43be 3.8990 1.358+3 3.33be - 3.Mbe 1.038*0 3-135 3.738+7 5.418+7 9.M8+9 6.M 8+7 - 9.168 4 f.888+7

u,. w.% . .

ODCM-7.0 Revision 8 Page 7.0-36 Table 7.0 4 Raipo, Grass-Cow Milk Pathway Dose Factors - INFANT (CONT.) l F/9)'

(mrem /yr per pCUm 3) for H 3 and C-14 (m2 x mrem /yr per pCusec) for others mesties Snee s.s,ar terress suser some es-u.1 f. Seer 2 tu - - 1.01 -9 - - - -

2-135 1.21b5 2.4tt+5 2.36E*7 2.698+5 - 4.74p4 8.8044 Co-1H 3.65E+10 6.80E+10 - 1.75E+10 7.188+9 1.85p3 6.87p t Co-1M t.968 9 5.775+9 - 2.308+9 4.70s+8 8.768+7 2.15E+9 Co-137 5.15t+10 6.02s+10 - 1.62p10 6.555+9 1.885+8 4.27pt

- = -

Co-tSt - - - =

Sa-139 4.558 7 - - - - 2.888-5 1.321 8 Se-140 2.41s+8 2.413 5 - 5.73s+4 1.448+5 5.93p? 1.M5+7

- - = =

an-141 - - -

3e-342 - 14-140 4.03t+1 1.598+1 - - - 1.87pl 4.9984 1,a-142 - - - - - 5.315-4 -

Co-tot 4.33t+4 2.Ht+4 - 8.15E+3 - 1.375+7 3.115+3 Ce-143 4.00E 2 1.65t+5 - 7.72E+1 - 1. 55B+6 3.02pl Ce-144 2.33E+6 9.52p5 - 3.85b5 - 1.33pe 1.3005 Pr let 1.49p3 5.59E*2 - 2.088+2 - 7.898+5 7.415+1 Pr-144 - - . - - - -

5d-147 8.82t+2 9.06t+2 - 3.498+2 - 5.74t+5 3.55t+1 ti-107 6.12E*4 4.268+4 - - = 2.50t+6 1.478+4 ,

tr-239 3.64E+1 3.25p0 - 4.498+0 - 9.40E+4 1.MB+0 I

l r

r.

e i

ODCM 7.0 Revision 8

( Page 7.0-37 Table 7.0 4 Ralpo, Gra8S-Cow-Meat Fathway Dose Factore - ADULT (mrem /yr per yCum 3) for H 3 and C-14 l 9/cif (m2 x miem/yr per pCusec) for othere amende emme u+.r Terrete neeer smee e2-u.I T. Seer 8-3 - 3.2SE*2 3.358*2 3.3Sbt 3.3Sb 2 3.258*2 3.25E 2 .

C-14 3.338+l 6.ME*4 4.ME+4 6. ME*4 6.M be 6. M8+4 6. Mt+4 ma-24 1.84E 3 1.84E-3 1.04E 3 1.Mb3 1.NE 3 1.ME4 1.84b3 P42 4.65E*9 2.89E+8 - - - 5.33S+8 1.8ug+8 Cr-51 - - 4.338+3 1.56b3 9.388+3 1.788+6 7.87t+3 me-94 - 9.155+6 - 3.72b6 - 3.08847 1.755+6 me=36 - - - - - - -

Fe-55 2.95t*8 3.03t+4 - - 1.13b8 1. ME+8 4.72B+7 i Fe-59 2.675+4 6.278+8 - - 1.758+8 3.098+9 2.40t*8 Co 57 - 5.Mbe = = = 1.435+8 9.378+6 Co-M - 1.0$t+7 - = = 3.7e8+8 4.10E*7 Co-60 - 7.53E*7 - = = 1.415+9 1.ME+8 01-63 1.89E*10 1.318*9 - - - 3.73E+4 6.33b8 84-65 - - - - = = =

co-64 - 2.95b7 - 7.458-7 - 3.538 5 1.39E-7 8.-65 3.ME+4 1.13s+9 - 7.578+4 - 7. tM+8 S.12s+8 1 go-69 - - - - - - -

Br-82 - - - - - 1.44b3 1.268+3 ar-83 - - - - - = =

gg.84 - - - - - - -

St-85 - - - - - - -

ab-M - 4.878+8 - = = 9.688+7 3.275+8 '

(' 06-88 Rb-89

=

I I

St-89 3.018+8 - - - - 4.M 5+7 8.65E*6 i St-90 1.348+10 - = = = 3.59E+4 3.0$bt St-91 - - - - - 1.38E-9 -

St-92 - - - - - = =

b90 1.078+2 - = = - 1.13E+6 3.86be )

b91e = = = = = = - !

b91 1.15E+6 - - * - 6.348 8 3.03be 3 93 - - - - - = =

b93 - - - - - 3.885-7 -

St-95 1.88b6 6.048*$ - 9.44b5 - 1.9tb9 4.995+5 l 3r-97 1.838-5 3.655-6 - 5.588-6 - 1.145+0 1.695-6 06-95 2.298+6 1.388+4 - 1. NE+6 - 7.758+9 6.NE*$

3b-97 - - - - * - -

me-99 - 1.09bl - 3.468+5 - 3.83>5 3.87b4 go. pts - - - . . . -

To-tet - - - - = = =

andel *1.068+8 - - 6.938*4 - 1.338*16 4.558+7 go.105 - = * - - - -

es SM 3.08bt - - 5.48b9 *

- 1.8tb11 3.94b8 th-team - - - - - - -

ab 106 - - - - - = *-

A8-Item 6.698 6 8.19b6 - 1.32B+7 - 3.838+9 3.67 be 8b-134 1.985+7 3.74B+5 4.988+4 - 1.548+7 5.638+8 7.858 6 St-tal 1.915+7 3.13b5 + . M B+4 - 1.478*7 3.10E+8 4.94t+6 Te-125m 3.998+8 1.30B+8 1.088+8 1.Me*9 - 1.438+9 4.015+7 fe-137e 1.138+9 3.99be 2.85b8 4.93E+9 - 3.748+9 1.36be Te-127 - - - 1.998-9 - 3.148-8 -

Te-129s 1.14pt 4.378+8 3.93p8 4.778+9 - S.768 9 1.818*8 9e-129 - - - = = = =

Te-13te 4.518+2 3.315+2 3.50S+2 3.34b3 - 3.198+4 1.84b2 Te-131 - - * * - - -

( To-132 2 130 2-131 2 132 1.48t+6 9.978+$ 1.088+4 8.73p6 3.358-6 6.NE-6 5.888-4 1.088-5 1.08b7 1.548+7 S.0$b9 3.ME*7 4.39b7 8.815+5 S.NE-6 3.74be 4.078+4 8.83be b133 6.388-1 7.478-1 1.30B+2 1.38be - 6.728 1 3.388 1

ODCM-7.0 l Revision 8 l Page 7.0-38 l

l. ,

\

\ l Table 7.0-4 i Raipo Grass Cow Meat Pathway Dose Factors - ADULT (CONT) l ['/9/' {

(mrem /yr per Cl/m 3) for H 3 and C 14 l (m2 x mrem /yr per #Ci/Sec) for othere Smensde asse La w Thrteld Kaesar taas es ad.1 T.Sedy

. . 1 2.tx . . l 2 13s . . '

C.-t u 6. 57s+8 t.us+9 . s.86:+8 t.68:+8 s.74s+7 1.38:+9 Co-1H . 1.18t+7 4.67t+1 - 2.40t+7 3. K8+6 5.30E*6 3.M E*7 Co-137 8.72E*8 1.19E+9 - 4.0M+8 1.355+8 2.315+7 7.81E*8

= = = *

l

- =

Ce=138 -

. . . . l

3. 139 . .

Se-140 2.888+7 3.61E+4 - 1.135+4 2.875+4 5.933,7 1.895+6 Se-141 -

= = " * *

. =

8e-142 3a-140 3.605-2 1.815-2 . = = 1.31B+3 4.798-3 8m-142 . . . . . . .

Co-141 1.40E*4 9.48E*3 . 4.40E+3 - 3.62E+7 1.888+3 Co-143 2.098-2 1.53E+1 - 6.805-3 - 5.788+2 1.718-3 Co-144 1.468+6 6.095+5 - 3.61s+5 - 4.935+8 7.8H+4 Pr-tel 2.13t+4 8. ME* 3 . 4.933 3 . 9.333+7 1.868+3 Pr=144 = . . . . . .

ud-147 7.00E+3 8.188*3 - 4.788+3 . 3.93E+7 4.90E+2 W-187 2.168 2 1.818-2 = . . 5.928+0 6.328-3 up-239 2.565-1 2.518-2 . 7.84E.2 - 3.133+3 1.395-2 j

f

\

ODCM-7.0 Revision 8 Page 7.0 39 a

Table 7.0 4 Ralpo, Grass Cow Meat Pathway Dose Factors - TEENAGER l l'/Tf" (mrem /yr per #Ci/m 3) for H 3 and C-14 (m2 x mrem /yr per yCi/Sec) for others Sec116e , Bees Liver Thyreld Eideer Ame8 81-111 T.Se6r 8-3 - 1.N E+2 1.ht*2 1.Mt+2 1.Mt+2 1.N E+2 1.Mb2

>14 3.81b5 5.62s+4 5.62E+4 5.62t+4 5.638+4 5.62E*4 5.62E+4 Se-34 ~ 1.478-3 1.478-3 1.47E-3 1.478-3 1.47b3 1.478-3 1.475-3 F-32 3.938*9 2.44E+8 - - - 3.30t+8 1.52b4 cr-51 - - 3.14t+3 1.34b3 8.978+3 9.50E+5 5.65b3 les-54 - 6.98b6 - 3.085+6 - 1.43E*7 1.38t+6 geo-56 - - = = = = =

Fe-55 3.388+8 1.6 m s - - 1.478+8 7.38E.7 3.938+7 Fe-59 3.13E+8 4.98t+4 - - 1.575+8 1.18b9 1.938+8 Co-57 - 4.53b6 - = = 8.45b7 7.59be Co-58 - 1.41E+7 - - - 1.Mb8 3.25E*7 co-60 - 5.83t+7 - - - 7.60t*8 1.31E+8 N1-43 1.528+10 1.875+9 - - - 1.715+8 5.958+4 31-65 - - - - = = =

co-H - 3.41E-7 - 6.10E-7 - 1.878-5 1.13p7 to-65 3.50E+8 8.698*8 - i.54E+8 - 3.688+8 4.058*8 go.49 - - - - - = =

St-82 - = = - = = 9.90E*2 St-83 - = = "- - = =

gr-84 - = * - - - -

Sr-85 - = = =

Sb-44 - 4.N E*8 - - - 4.StE*7 1.91E+8

86-04 - - = = =

36-89 - - = = -

8r-89 2.54L C - - - - 3.838+7 7.295+6 l 1

tr-90 8.058*9 - - - - 3.MS*8 1.99b9 )

Sr-91 - = = - - 1.10E-9 - 1 tr-92 - - = = = - -

T-90 8.90E+1 = = = - 7.486+5 3.43bo T-91s =

T-91 9.568+5 - - = = 3.92b8 3.568+4 T-92 - - - -

T-93 - - - - - 1.6 5 7 -

Er-95 1.518+4 4.768+5 - 6.99t+5 - 1.188+9 3.278+5 tr-97 1.53b5 3.028-4 - 4.582-6 - 8.188-1 1.395-6 ub-95 1.795+6 9.M R+5 - 9.MD5 - 4.35B+9 8.47b5 gb-97 - - - - - = =

see-99 - 8.988+4 - 3.e65+5 - 1.61b5 1.715+6 Te-99e - - - - - =

pe-101 = = - * - = =

Su-183 8.488+7 - - 3.83b8 - 7.185+9 3.688+7

- = = = - - -

Se=105 to-186 3.368+9 - - 4. 55B+9 - 1.1 m t1 3.978+8 th-183e - - - - - - -

= = = - = -

Sh-106 - ,

As-110e 5.868+4 4.79t+6 - 9.148+6 - 1.35bt 3.9144 86-124 1.628+7 3.98b5 3.6?p4 - 1.418+7 3.M8+8 6.31b6 86-125 1.56b7 1.118+5 1.4 W 4 - 1.375+7 1.32t+8 3.M8+4 Te-125m 3.03B+8 1.998*4 8.4?E*7 - - 8.M5+8 4.95b7 Te-127e 9.415+8 3.Mbe 3.34b8 3.83b9 - 3.3Sb9 1.13b8 Te=127 - - - - - 1.755-8 -

Te-129e 9.58b8 3.56be 3.09b8 4.91b9 - 3.68b9 1.53b8 fe-129 - = = = - - -

Te-131e 3.768+2 1.888+2 3.715+3 1.88b3 - 1.458+4 1.988+2 9 -131 * - = =

Te-132 1.15E+4 7.36b5 7. M8+5 6.978+4' - 3.388+7 6 Mb5

( 3-138 1-131 3 132 3-133 1.89E-6 5.44be 4.47E-4 8.448-6 8.95b6 1.25b7 3.ME+9 3.Mb7 1.598-1 6.185-1 8.Sth) 1.eftee 4.218-4 3.198-6 3.44 be 6.735+4 4.61>1 1.06bt

ODCM-7.0 Revision 8

,- Page 7.0-40 Table 7.0-4 Raipo, Grass Cow Meat Pathway Dose Factor 8 - TEENAGER (CONT.) f /EI (mrem /yr per pCi/m 3) for H-3 and C-14 (m2 x mrem /yr per pCi/sec) for others Sect!8e toes Liver Thrrett Eldney 8ae8 81-111 f.tedy I-134 . . . . . . .

1 138 . . . . . . .

Co-134 S.238*3 .1.238 9 . 3.91E*8 t.49E*8 1.$35*7 3.11E+8 Co-136 9.22E*6 3.63E*7 - 1.97E*7 3.11E*6 3.92E+4 2.445*7 Co-137 7.24E*8 9.63E*8 - 3.388*8 1.27E*4 1.37E*7 3.368*8 Co-138 . . . . . . .

to-139 . . . . . . .

Se=140 2.38t*7 2.91E+4 . 9.885*3 1.NE+4 3.473*7 1.l3E+4 to-141 . . . . . . .

3e-142 .

g4 140 2.968 2 1.458-2 . .

8 388'2 3*87E*3 g ,.142 - = *

Co-141 1.18E*4 7.NE*3 - 3.70E*3 .. 2.2SE*7 9.SSE*2 Ce-143 1.76E-2 1.28E*1 . 5.748-3 - 3.055*2 1.43E-3 Co-144 1.23E*6 $.08E*5 - 3.045*5 - 3.098+8 4.60E*4 Pr-143 1.798+4 7.155*3 . 4.165*3 . l.90E*7 8.928*2 Pt-144 .

M 147 6.24E*3 6.79E*3 . 3.98E*3

2.458*7 4.#E*2 W-187 1.81E-2 1.48E-2 . . . 3.995+0 S.17E 3 hp-239 2.23E-1 2.11E-2 - 6.618-2 - 3.39E*3 1.178 2 i

i

ODCM-7.0 Revision 8

-, Page 7.0-41 I '

Table 7.0-4 Ralpo, Grase-Cow-Meat Pathway Dose Factors - CHILD (mrem /yr per yCilm )3 for H-3 and C-14 l P/ V (m2 x mremlyr per pCi/sec) for others auclies Sees IJver Thyreia siemer lent SI-1LI T.Sedy 5-3 - 2.M8+2 2. M8+2 2. M842 C-14 2. M 8+2 2. M 8+2 2. M8+ 2 to-34 S.298+3 1.M8+ 5 1.868+5 1.06b 5 1.M8+ 5 1.068+5 1.068+5 P 32 2.Mb3 2.348-3 2.Mb3 7.418+9 3.478+8 -

2.Mb3 -

2.NE-3 3.Mb3 2.34b3 Cr-St' - -

2.058+8 2.868+8 4.898+3 1.348+3 8.938 4 4.678+5 8.818+3 k . 7.998+6 - 2.248+4 -

6.748+6 2.13b6

.No-54 e-M - - - - - - .

Pe-SS 4.578+8 2.428+8 . -

Pe-$9 1.378+8 6.498+7 7.615+7 3.788+8 6.12b8 - -

1.77be 6.3?b t 3.058+8 Co-57 - 5.928+4 - - -

4.858+7 f.2eb7 Co-88 - 1.6 2 7 - -

i Co-60

. 9.608+7 8.048+7

- 6.938+7 - -

.- 3.848+8 2.04b8

! N1 63 2.918*10 1.568+9 - =

1 mi-65 - - - -

=

1.068+8 9.915+8 j co-64 - 3.24b7

- 7.828-7 -

1.528-$ 1.Mb7 i so-65 i

3.?Sb e 1.808+9 , -

6.30b8 -

1.768+8 6.228+8 8 -69 - = = = - - -

a Br-82 - - - - - -

4 Br-43 - - -

1.568+3

= = - -

tr-84 - - - - - = =

2 tr-85 - - - - - - -

86-86 -

j S.768+8 - - -

3.718+7 3.548+8 Ab-84 - = = = = = -

4 86-89 - -

', I tr-89 4.023*8 -

3

\ 1.$68+7 1.388+7 sr-90 1.048+10 - - - -

3 St-91 = = -

1.408+4 2.648*9 3

1.018-9 -

St-92 - - - - - - -

Y 90 1.708+2 - = * -

y-91m . . - -

4.M8+$ 4.558+0 1

T-91 1.818+6 - - -

j y-92 - = =

2.41b8 4.838+4 y-93 - - = =

8r-95

= 1.$$8-7 -

2.688+6 S.898+$ - 8.438+5 -

4.148+8 S.Mb5 sr-97 2.84bl 4. ME-6 -

S.898-6 -

6.21b1 2.428-6

ub-95 3.098+6 1.288+4 -

1.138+4 -

ab-97 - = = =

2.23bt. 4.61b5 j = = *

, ,me ,99

- 1.258+l -

2.67b5 -

f.elbl 3.098*4 e- 9m . - - - - - -

To-tel - -

.. = = -

3e-103 1.86be - -

2.928+8 -

4.0abt S.98D7 l

3e-105 - - - * * *

3e-106 4.44D9 - -

S.998+9 -

6.988+10 S.54b8 5 Rb-103m - * - * * *

Rb-106 * * * * * *

d A8-119e 8.40b6 S.67be - 1.06b7 -

4.7tb8 4.53b6 8b-134 2.918+7 3.008+8 6. 48+ 4 -

86-12$ 1.628+7 1.838+8 1.038*7 i 2.858+7 2.198+$ 2.648+4 -

1.69b7 6.80b7 B.968+6

Te-125m S.698+8 1.548+8 9.80b8 - - S.498+8 7.598+7 1 To-12?e 1.7?b9 4.79b8 4.24b8 5.068+9 -

1.44b9 2.11b4 Te-127 - - - 1.2tb9 - 1.668-8 =

Te-129m 1.818+9 5.04b8 S.82b8 S.388+9 -

fo-129 - - -

2.208+9 2.888+8

= = = -

2 Te-tale 7.008+2 2.428+2 4.98b 2 2. M8+3 -

9.828+3 2.688+2 ge-g31 - - - - . - -

Te-132 3.09b6 9.278+5 f.3$8+6 0.608+6 -

1 3-130 9.338+6 1.128+6 3.398-6 6.858-6 7.948-4 1.028-$

( 3.308-4 3.$38-6 I-131 f.668+7 f.678+7 5.528+9 2.748+7 - 1 3-132 . . -

1.498+4 9.498+6 l J

2-133

6.68bt 8.368-1 1.$3b2 1.388+0 -

3.33bt 3.12b1 1

i l

t

l ODCM-7.0 Revision 8 Page 7.0-42

g. ,

Table 7.0-4 Ralpo, Grass Cow Meat Fathway Dose Factors - CHILD (CONT.) l 9/4T (mrem /yr per pCi/m 3) for H 3 and C-14 (m2 x mrem /yr per pCi/sec) for others Duellde Gees Liver Tierrote tideer Lees $1 5&1 T.teer I-t h ~'.~ . . . s . e

I 135 . . . . . . .

Co-1M 9.22E+4 .1.5tt+9 . 4.698+8 1.ess+4 8.15E+4 3.19E+s Co-1H l.595+7 4.375+7 - 2.33E+7 3.473+6 1.54E+6 2.s3E*7 Co-137 1.33E+9 1.388+9 . 4.16t+8 1.50E+4 7.995+6 1.88t+8 Co 138 . . . . . . .

Se-139 . . . . . . .

So-140 4.398+7 3.85s+4 . 1.363+4 3.398+4 3.338+7 3.968+4 Sa-141 . . . _. . . .

Se-143 . . . . . . .

la-140 5.415 2 1.898-2 . . . $.378+2 6.M8-3 La-142 . . .

Co-141 2.22E+4 1.11E+4 - 4.84E+3 - 1.388+7 1.ME*3 Ce-143 3.30E 2 1.79E*1 - 7.llE-3 - 3.62E+2 3.$98-3 !

Co-144 2.32E+6 7.26E*5 . 4.01E*5 . 1.89E+8 1.345+5 i Pr=143 3.39E+4 1.02E+4 - 5.51s+3 . 3.665+7 1.688+3 J Pr.144 . . .

Ed-147 1.17E+4 9.48t+3 - 5.30E*3 - 1.S88+7 7.34E+2 W-107 3.34E-2 1.99E 2 . . . 3.798+0 8.928-3 1 De-239 4.20E-1 3.025-2 . 0.732-3 . 3.23E+3 3.128-2 I

l l

l p

ODCM-7.0 Revision E Page 7.0-43

\'- Table 7.0-4 Raipo, Vegetation Pathway Dose Factore - ADULT (mrem /yr per yCi/m 3) for H 3 and C-14 l P/ff (m2 x mrem /yr per yCi/sec) for others Deellae toes Liver Thrreld . Edsey lan8 814LI T.Sedy 5-3 = 3.368+3 2.Mt+3 3.368*3 3.M8*1 3.36b3 3.Mb3 .

C-14 8.978+5 1.798 5 1.798 5 1.798+5 1.79t*$ 1.798+5 1.79b5 us-24 2.7H+ 5 2.76t*$ 2.7M+ 5 3.76b5 3.76b 5 3.768*5 2.76b5 '

P 32 1.408+9 '8.7M*7 - = = 1.588+8 5.42t+7 Cr-51 - -

2.79t+4 1.03E+4 6.19t*4 1.178*7 4.66E*4 It>H - 3.11E*8 - 9.278+7 - 9.Mb4 5.Mt+7 no-56 - 1.6tt+1 -

3.04t+t - 5.13b2 3.858+0 Fe-55 3.09t+8 1.45t+8 - - 8.06t+7 8.398+7 3.378+7 Fe-59 1.27t+8 3.998+8 - - 8.358+7 9.M 8+8 1. MD's co-57 - 1.178+7 - - - F.978+8 1.958+7 00-54 - 3.098+7 - - - 6. M8+8 6.928+7 Code - 1.678+8 - - - 3.148+9 3.69E*8 3443 1.048*10 7.2tt+8 - - - 1.50b8 3.49E*4 5145 6.158*1 7.99E+0 - - - 3.eM*2 3.65be code - 9.27b3 - 3.ME+4 - 7. gob 5 4.35b3 i

Es-65 3.178+4 1.01E*9 - 6.75t+8 - 6.M8+8 4.56t+8 '

Es49 8.758 4 1.67E-5 - 1.091-5 - 3.51E4 1.16E4 Sr-82 - - - - - 1.73E+6 1.51t+6 St-83 - - - - - 4.638+0 3.218+0 St-84 - - - - - - -

3c.85 - - - - - - -

8>84 - 2.19b8 - - - 4.328+7 1.02b8 .

. . . - - - . l s.s-as, be - - - - - - -

l 8t-89 9.968+9 - - - - 1.408+9 3.86t+8 .

{

St-90 6.058+11 - - = = 1.75b 10 1.448*11 '

Sr-91 3.30E*3 - . = = 1.528+6 1.398+4 St-92 4.278+2 - = = = 0.468 3 1.858+1 1-90 1.33be - = = = 1.41b8 3.568*2 T-9te 5.8M-9 - - - - 1.71b8 -

T-91 5.138+6 - - - - 3.828+9 1.378*5 V-92 9.018-1 - - - - 1.548+4 3.638 2 T-93 1.748+2 - - - - 5.528+6 4.888+0 Er-95 1.19b6 3.81t+5 - 5.97845 - 1.315+9 2.588+5 Er-97 3.3 M*2 6.738+1 - 1.028*2 - 3.88847 3.088+1 ab-95 1.42E*5 7.915+4 - 7.818+4 - 4.808+8 4.35b4 N>t? 3.905 4 7.M8-7 - 8.568-7 - 3.718-3 3.488-7 No-99 - 6.358*4 - 1.418+7 - 1.458+7 1.198+6 i Te=99m 3.Mbe 4.66be - 1.32b2 6.M be 3.138+3 1.108*2 '

Te-let - - - - - - -

So-103 4.008+4 - - 1.8M*7 - 5.61b8 2.078+6 Se-105 5.39E+t - - 6.M8+2 - 3.30 b e 3.138+1 Su-106 1.93b8 - - 3.738+4 - 1.35b10 3.6u+7 sh-tese - - - - - - -

Able6 - - - - = = =

As-11em 1.068+7 9.76be - 1.938+7 - 3.988+9 5.808+6 SW124 1.N E+8 1.968+6 3.538+5 - 8.088*7 3.958+9 4.11b7 SE125 1. Mt+8 1.538+6 1.398 5 - 1.058+8 1.508 9 3.358+7 Te-125e 9. M8*7 3.508+7 3.90b7 3.938+8 - 3. MS*8 1.39b7 Te-127s 3.49b8 1.25b8 8.92b7 1.428+9 - 1.178*9 4.M8+7 Te-127 5.76b3 3.078+3 4.378*3 2.M8+4 - 4.548*5 9.358+1 Te-129m 3.558+8 9.50E+7 8.758+7 1.068+9 - 1.38b9 4.038+7 Te-129 6.458 4 2.505 4 5.108 4 2.798-3 - 5.038 4 1.628-4 To-tale 9.12b 5 4.ME* 5 7.068*5 4.528+6 - 4.438*7 3.738+5 fe-131 - - - - - -

Te-132 4.39t+6 3.778+4 3.06 be 3.678+7 - 1.318+8 3.808+6 2-130 3.Mb 5 1.17b6 9.905 7 1.828+6 - 1.01b6 4.61845 I-131 0.098+7 1.168+4 3.798+10 1.988*8 - 3.058+7 6.6 M*7 2 132 5.748+1 1.M8+2 5.388+3 2.458*2 - 3.898*1 5.M8+1 '

2-133 2.128*6 3.698 4 5.428+8 6.44b6 - 3.31>6 1.128+6 l l

1

_____E

ODCM-7.0 Revision 8 :

g. , Page 7.0-44 l 1,

Table 7.0-4 Ralpc, Vegetation Pathway Dose Factor 8 - ADULT (CONT.) l P/TT (mrem /yr per yC1/m 3) for H 3 and C 14 (m2 x stremlyr per pCi/Sec) for others em:14e Gees uver Terrest satser sans Sa-8&t f. Seer 1-134 1.N E-4 2.888-4 5.008-3 4.598-4 - 2.518-7 1.038-4 3-135 4.085+4 1.07s*5 7.Mt+4 1.718*5 - 1.215+5 3.NE+4 ,

Co-1M 4.H E*9.1.11B+10 - 3.59E*9 1.19t+9 1.M8+8 9.97t+9 Ce=134 4.20E*? 1. HE*8 - 9.34E+7 1.378+7 1.89E*7 1.19E+8 Ce-137 6. ME*9 4.70E*9 - 2.958 9 9.81E+8 1.688+8 5.708+9 Co-138 - = = = = - -

Se-139 2.955-2 2.10E 5 - 1.968-5 1.195-5 5.238-2 8.64E-4 Se-140 1.295+8 1.625+5 - 5.498+4 9.258+4 2.65B+4 8.438+4 3 -141 - - - - - - -

3e-142 - - = = = = =

Le-140 1.978 3 9.92842 - = = 7.288+7 2.638+2 14-142 1.408 4 6.358-5 - - - 4.MS-1 1.5d8-5 Co-141 1.ME+5 1.33E+5 - 4.175+4 - 5.488+8 1.515*4 Co-143 1.00E*3 7.42E*5 - 3.268+2 - 2.778+7 8.21B+1 Co-144 3.29E*7 1.38E+7 - 8.168+6 - 1.11B+10 1.778+6 Pr-143 4. ME*4 2.54E+4 - 1.478+4 - 2.788+8 3.145+3 Pr-144 - - - - - - -

N -147 3.34E+4 3. NE+4 - 2.258*4 - 1.858+8 2.315+3 W-187 3.82E*4 3.19E+4 - - - 1.05E+7 1.12E+4 Mp-239 1.425 3 1.40E+2 - 4.378+2 - 2.878+7 7.72E+1

ODCM-7.0 Revision 8 l Page 7.0-45 l

(~, '

\

Table 7.0-4 Ralpo, Vegetation Fathway Dose Factors - TEENAGER lff/V l (mrem /yr per yCi/m 3) for H 3 and C 14 l (m2 x mrem /yr per pCi/sec) for others !

moslide same Liver TbrreH EWeer Imes81-112 T.8e87 )

5-3 = 3.598+3 3. S9D3 3.998+3 3.995+3 3.595+3 3.59b3

0-14 1.4Sb6 3.91t+5 3.91E*5 3.91E+5 3.91s+5 3.91E+5 3.91E*5 us-34 3.45b5 3.4$1+5 3.45b5 3.4&b5 3.45E+5 3.45E+5 3.45bl P-33 1.61B+9 9.965+7 - - - 1.3Sb8 6.33E*7 +

Cr= 51 = = 3.44E+4 1.MS*4 8.858 4 1.Mb7 6.30E*4 me-54 - 4.$35+4 - 1.35b8 - 9.37b8 8.978+7 He-M - 1.45t+1 - 1.83bt - 9.54E+3 3. NE*0 ft-55 3.35E+8 3.31b8 - - ' 1.468+8 9.98b7 5.385+7 Fe-59 1.015+4 4.23b8 - - 1.33B+8 9.98b8 1.6M*8 Co-57 - 1.79E*7 - - - 3.M8+8 3.00E*7 Co te - 4.388+7 - - - 6.04E+8 1.015+8 Co-60 - 3.495+8 - - - 3.348+9 5.60E*8 8143 1.61b10 1.1M+9 - - - 1.815+8 5.45E+8 84-65 S.7M+1 7.335*0 - - - 3.97E+3 3.33E+0 Co-64 - 8.40E+3 - 3.135+4 - 6.51E+5 3.955+3 So-65 4.34E+8 1.478+9 - 9.418+8 - 6.33b8 6.865+8 So-49 8.19b6 1. NE-5 - 1.03b5 - 3.88b5 1.09E4 Br-82 - - - = = = 1.33E+6 Br-83 - - - = = = 3.01E*0

= =

St-84 - - -

Br-85 - - - -

86-86 - 3.73E*8 - = = 4.958+7 1.285+8

= -

ab88 - - - - =

- - = =

Sb-89 -

Br*89 1.$15*10 - - - - 1.80E+9 4.33&+8 ar-90 7.51t+11 - - - - 3.11B+10 1.85E+11 tr-91 3.99E*5 - - - - 1.36b6 1.195+4 Br-92 3.975+3 - - - - 1.015+4 1.69p 1 T-90 1.34be - = = = 1.03t+8 3.348+3 T-91e 5.435 9, - - - - 3.56b7 -

T-91 7.87b6 - - - - 3.33t+9 3.11E+5 T-93 8.47bt - - - - 3.338 4 3.451-3 T-93 1.6M*3 - = * - 4.988+6 4.47be

.It-95 1.74t+( 5.498 5 - 8.075+5 - 1.375+9 3.788+$

Ar-97 3.095+!. 6.11b1 - 9.36E+t - 1.6Sb7 3.81b1 ab 95 1.938+ 5 1.068+5 - 1.e3t+5 - 4.668+8 5.86be D-97 3.695-i 4.678-7 - 7.805-7 - 1.998-3 3.442-1 me-99 - 5.748+6 - 1.31b7 - 1.8M+7 1.09E*6 Te-99n 3.798*9 7.548+0 - 1.138+3 4.198+0 4.98E+3 9.77b t

- - = = =

Te-101 - -

to-103 6.8?be - - 3.438+7 - 5.74B+8 3.MB+6 he-105 S.008+1 - - 6.315+3 - 4.M84 1.Mt+1 Re 106 3.098 8 - - S.975+4 - 1.488e10 3.90b7 Ab 103e - - - - - - -

Ab 906 - = = * * - -

AS-ties 1.S$8+7 1.44R+7 - 3.745+7 - 4.06b9 8.748*6 ab134 1.$55+8 3.05t+6 3.51bl - 1.35E+8 3.11S+9 6.038+7 8b 135 3.14E+4 3.Mb6 3.M5+$ = 1.088+4 1.86t+9 S.eete7 i To-late 1.488+8 S.Mb7 4.145+7 - - 4.378,8 1.988+7 l Te-137e 5.51b8 1.96be 1.31>8 3.348+9 - 1.378+9 6.96t+7 1 Te-137 5.438 3 1.93E+3 3.74b3 3.385 4 - 4.195+5 1.178+3 Te-189e 3.678+8 1.NE+8 1.18t+8 1.94pt - 1.388+9 S.815+7 Te-139 6.332-4 3.335-4 4.45b4 3.61>3 - 3.40E-3 1.$18-4 Te=131e 8.448+5 4.enbl 4.995+5 4.333 4 - 3.35s+7 3.3st+5

- - - - - = =

To-131 Te-133 3.90E+6 3.478+6 3.60t+6 3.378+7 - 7.83b7 3.33E+6 3-1M 3. ME*5 1.038+6 8.35E+7 1.58t+6 - 7.87b5 4.098+5 2-131 7.785*7 1.088+8 3.14E+10 1.85b8 - 3.13p? 5.79b7 C 3-133 2 133 S.188+1 1.Mt* 3 4.878+3 3.143+3 1.97p 4 3.34 b 6 4.668*8 5.86b6 5.915+1 4.875+1 3.53B+6 1.03E+6

- --_- ._. _ . _ ~ - _ . _ .

. _ - . . - - . . _ . - - . . _ = _ . - - _ _ _ . - . . - _ _ , _ . .

ODCM-7.0 Revision 8 7, Page 7.046

) Table 7.0-4 1 Ralpo, Vegetation Pathway Dose Factort - TEENAGER (CONT.)

(mrem /yr per pCi/m 3) for H-3 and C 14

[ ff$r l

(m2 x mrem /yr per pCi/sec) for others l

i Secalde Bees Liver Thrrold Eldeer 8ses s!-L&2 f.8edy l 2-1H I 9.59E-5 2. ME-4 4.24E-3 6.018-4 . 3.388-6 9.135 $

1 2-13$ 3.64E+4 9.488+4 6.10E*6 1.50E+5 . 1.958*5 3.52t+4 4 Co-th 7.09E*9 1.67E*10 . 5.NE*9 2.038+9 2.085 8 7.748+9 l Ce-1M . 4.29E*7 1.69E*8 . 9.19E*7 1.45E*7 1.36t+7 1.1H+8 Co-137 1.01E+10 1.35E+10 - 4.998+9 1.785+9 1.92E+8 4.698 9 i Co-,u . . . . . . . l 4

Se-139 2.775-2 1.96E-5 . 1.848-5 1.ME-l 2.475-1 0.885-4 Se-140 1

1. NE+4 1.698+5 . 5.758+4 1. us+f '.13E+8 8.91b6 <

Se-141 . . . . . - .

Se-142 . . . . . .

Lest'0 8.40E+3 8.848 2 . . . 5.885+7 2.358+2 Le-143 1.28E-4 5.69E-5 . . . 1.73E+0 1.425-5 Co-141 2.825*$ 1.84E+5 - 8.06E+4 . 5.385+8 2.16t+4 Co-143 9.37E*2 6.82E*5 . 3.06E*2 . 2.05t*7 7.625+1 Co-144 $.27E+7 2.185+7 . 1.30E+7 . 1.3 H+10 2.838+6 Pr-143 7.12E+4 2.84E+4 . 1.6SE*4 - 2.ME+8 3.S$5+3 I n=ue . . . . . . .

1 84-141 3.63E*4 3.94E*4 . 2.32E+4 . 1.428+8 2.36t*3 i W-187 3.55E+4 2.90E+4 . . . 7.84E+6 1.02E+4 ,

NP-239 1. NE*3 1.30E+2 . 4.095+2 - 2.108 7 7.34E*1

]

l i

(

y

ODCM-7.0 Revision 8 Page 7.0-47

/

( Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - CHILD lY (mrem /yr per yCi/m 3) for H-3 and C 14 (m2 x mrem /yr per yCi/Sec) for other8 seclide asse Liver Thrteld Eldeer 2me8 Sb1LI T.Sedy 5-3 - 4.01E*3 4.01E+3 4.01E* 3 4.018 4 4.9tb3 4.01E*3 C-14 3.50t*6 7.01E*5 7.01E*5 7.01t*5 7.018+5 7.etE*5 7.etb 5 se-24 3.83t*5 3.038 5 3.83E*5 3.83b 5 3.038+5 3.838 5 1.838*5 P-32 3.378*9 ,1.588+8 - . . 9.30s 7 1. ME*8 Cr-St = = 6.54E+4 1.798+4 1.195+5 4.355 4 1.185*5 he-54 - 6.41t+8 - 1.858*8 - 5.55E+8 1.Mt+4 No-M - 1.908*1 - 3.*S&+1 - 3.758*3 4.385+0 Fe+55 8.00t+8 4.24t*8 - - 3.40E+4 7.868+7 1.315+8 Fedt 4.81E*8 6.49t*4 - -

1.88b8 4.M8+8 3.33b8 Co-57 - 3.99E*7 - - - 3.458+8 6.Mb7 Code - 6.478 7 < - - 3.778+8 1.988+4 Co-60 - 3.78be - - . 3.10t+9 1.12t*9 ub63 3.958*10 3.11b9 - = = 1.43E*8 1. M t+ 9 8145 1.05E*2 9.09be - - - 1.21E*3 5.77t+0 Co-M - 1.118+4 - 3.MS*4 - 5.30E*$ 6.698+3 Se45 0.13E+8 3.16bt - 1. Mbt . 3.808+8 1.35E+9 to-69 1.51E-5 3.181-5 - 1.338-5 - 1.388-3 3.028 4 St-82 - - - - =

3.04E*6 Br-83 - - - - - - 5.55E+0 tr-64 - - - - - . -

St-85 - - - - - - -

86-86 - 4.52E*8 - - - 3.91E*7 3.78t+8 8b-88 - - - - . . .

86-89 - - - - - - -

St-89 3.598+10 - - - - 1.39E*9 1.0H+ 9

(

St-90 1.345 12 - = = = 1.475+10 3.15t*11 Br-91 5.50t*5 * - =

1.218+6 2.088+4 St-92 7.388*2 - - - - 1. M8+4 3.92E+1 T-90 3.Mbe * * * - 6.56b7 6.17b2 T-9ta 9.NE-9 - = *

1.958-5 -

Y-91 1.075+7 - - - - 3.49b9 5.01b5 V-92 1.56be - = * - 4.515+4 4.465-2 i T-93 3.01E*2 - - - . 4.488*6 8.25be I tr-95 3.90E*6 8.58E*5 - 1.338*6 - 8.95E+8 7.M t+5 l Er-97 5.H5* 2 8.155+t - 1.17E+2 - 1.338 7 4.018+1 ,

ub-95 4.10E*5 1.598 5 - 1.58E+5 - 3.958+8 1.14b 5 abt? 4.90E 6 8.85E-7 - 9.82b? - 3.7M-1 a.1384 No-99 - 7.8H+6 - 1.675+7 = 6.488 4 1.NE4 -

To-90s 4.65E+0 9.13E+0 - 1.3M+2 4.638+0 8.198+3 9.518+2 I Te..tet - - - - - - -

Sv-103 1.55E*? - - 3.898*7 - 3.998+8 5.Mbe Go-105 9.175*1 * - 8.06b2 - 5.988+4 3.338+1 Re-106 7.45be = = 1.4tb9 - 1. ME+40 9.30B+7 Rb tels - - - * = = -

Ab=106 - = = = = - =

A8-1 tem 3.328 7 3.17b7 - 4.elb7 - 3.588+9 1.74b7 Sb124 3.53E+4 4.578+4 7.785*5 - 1. Mt+8 3.30s+9 1.33s+8 Sht25 4.99b8 3.85t+4 4.63b 5 - 3.788*8 1.198+9 1.e58+8 se-125m 3.518*8 9.50b7 9.M8*7 - - 3.38t+8 4.67b7 fe-127e 1.32bt 3.565+8 3.Mb8 3.778+9 - 1.075+9 1.57b8 Te-127 1.00be 3.78b3 6.935*3 3.858 4

3.9tt*5 3.15E+3 fe=129e 0.54be 3.39t+8 3.758+8 3.51t+9 - 1.ME*9 1.338+8 fo-129 1.158 4 3.22t.4 8.225-4 3.378-3 - 7.173-2 3.74E-4 Te-13te 1.54b6 5.338+5 1.168 4 5.Mb6 - 3.Mt+7 5.688 5 l Te-131 = = = * - = =

Te-132 6.982 4 3.09b6 4.50t+6 3.878*7 - 3.118+7 3.7M+6 2 130 6.21b5 1.362*6 1.388*8 1.085*6 - 5.87t+5 6.47E*5 2-131 1.41E+8 1.M 8+8 4.76b 10 3.368+4

1.38E+7 8.lete?

C -

I-112 2-133 9.30E+1 1.695 2 7.M 8*3 3.598*2 1.598+6 4.44B+6 8.358+8 7.408+6 1.99b 3 7.778+1 1.798+6 1.685 4 i

1 l

I ODCM-7.0 Revision 8 Page 7.048 J

} Table 7.0-4 Ralpo, Vegetation Pathway Dose Factors - CHILD (CONT.) l /W (mrem /yr per # cum 3) for H-3 and C-14 (m2 x mrem /yr per #Cusec) for others i

mus!!ee esse Liver Thrrete tidssy Emma 88-142 f. tear 4

2-134 1.70E-4 3.16E-4 7.288-3 4.848-4 - 3.188-4 1.465-4 s 2-135 6.54E+4 1.98t+5 1.04t+7 1.01t+5 - 8.988+4 5.578+4 i Co-134 1.60E*10 2.63t*10 - 8.14t*9 2.925*9 1.43s+8 5.545*9 Cs-134 8.068+7 2.22E+8 = l.188+8 1.76E+7 7.795+6 1.438+8 4

Co-837 2.398+10 2.29E+10 - 7.468+9 2.688+9 1.43s+8 3.388+9 Co-1M - - - - - - -

8e-139 5.118-2 2.718-5 - 2.3tt-5 1.61E-5 2.95t+0 1.488-3 Se-140 2.773+8 2.43E+5 - 7.90E+4 1.45E+5 1.408+8 1.625*7 Se-141 = = = = = = -

j 8.-i42 - - - - - - - 14-140 3.238*3 1.138+3 - = = 3.158+7 3.81t+2 4

84-143 2.32E-4 7.40E-5 - - - 1.478+1 2.325-5 1

Co-141 1.23E+5 6.14E+4 - 2.695+4 - 7.M8+7 9.125*3 i co-143 1.735+3 9.ME*5 - 3.938+2 - 1.375+7 1.ME*2

Co-144 1.27E*8 3.988 7 - 2.21E+7 - 1.e4E+10 6.785+4 Pf-143 1.48E+ 5 4.468+4 - 2.41E*4 - 1.60t+8 7.378*)

Pr=144 - - - - - = =

4 IW-147 7.16t+4 5.00E+4 - 3.145+4 - 9.18E*7 4.49E*3 i

W-107 6.47E+4 3.835*4 - - - 5.388+4 1.728+4 lle-239 2.55E*3 1.835*2 - 5.30E*2 - 1.368+7 1.295+2 d

a 1

1 1

I i

't e

i

}

I

ODCM-7.0 Revision 8 Page 7.0-49 f ',

s Table 7.0-4 Raipo, Ground Plene Pathway Dose Factors l I/5J" (m2 x mrem /yr per pCl/sec) secties Aer erses 53 -

C-te -

Ne 24 1.21B+7 l P-32 - '

l I

Cr-51 6.64E+6 No-54 1.34t+9 1 no-56 9.055+ 5 i 1

Fe-55 -

Fe-59 2.75E+8 Co-M 2.82E+8 Co-60 2.168+10 Wi-63 -

N1-65 2.97t+5 Co-64 4.09t+5 so-65 7.45t+8 so-69 -

St-83 4.89t+3 Br-84 2.03E+5 Br-85 -

l Rb-86 8.98t+6 Rb-84 3.29t+4 ab-89 1.21t+5 Sr-49 2.16t+4 St-90 -

St 91 2.19t+6 St-92 7.77t+5 Y-90 4.48t*3 Y-91s 1.01t+5 T-91 1.08t+6 3 91 1.00E*5 Y-93 1.85t*5 tr-95 2.48t*4 tr-97 2.96t+6 Nb-95 1.365+8 No-99 6.05t+6 Te-99s 1.83E+5 Tc=101 2.068+4

Re-103 1.095+8 Re-105 6.36t* 5 Re-106 6.218+8

. Sh-103e Ah 106 As-lies 2.678*9 Te-125e 1.55t+6 Te-127s 9.175+4 Te=127 3.00t+3 Te-129e 2.00E*7 Te-129 2.60E+4 Te-131s 8.05t+4 Te-131 2.93t+4 Te-132 6.228+6 1 130 S.538+6 3-131 1.72t+7 I

1 132 1.248+6 3-133 2.478+6 1-134 6.698+5 i 2-135 2.568+4 '

e' Co-1M 6.758+9 i

Co-136 1.698+8 1 Co-137 1.068+10

ODCM-7.0 Revision 8 Page 7.0-50 Table 7.0-4 Raipo, Ground Plane Fathway Dose Factors (CONT.) l p/qf-(m2 x mrem /yr per pCi/sec) l Gettido der trees co-1H 3.59E+5 to-139 1.065+5 to-140 2.055*7 Be-141 4.188+4 Se-142 4.498+4 '

La-140 1.91E*7 La-142 7.ME* 5 Co-141 1.ME*7 Co 143 2.32E+4 Co-144 4.95E*7 Pr-143 .

Pr-144 1.03E*3 3d-147 8.40E+6 W-147 2.MEv 6 sp-239 1.71E+6 s

1 1

ODCM-7.0 Revision 3 l' age 7.0-51 FIGURE 7.0-1 GASEOUS RADIOACTIVE EFFLUENT MONITORING AND VENTILATION SYSTEMS DIAGRAM n

h k .ai i P Key C a. _, a i F-T U

g im EYs"os* 49i SCTS til,I I,

l w,,

WW r,-

W bg => d i j

e.mmeu e SCT's Div H E~- lAl

'129" ~

9 l -

T I ll y .'!L *- ,

OY .s -

< WM== = 0

~

U .." av l'*_" _ Q h S (Nf Ums I I

""5 MEC11 VAuroM Rn leds In limurn NOTE: 'Ihe HEPA and charcoal filters identified on the Standby Gas Treatment System (SGTS) are engineered safety features and are not considered Ventilation Exhaust Treatment Systems (VETS). No effluent reduction was credited in the UFSAR 10CFR50 Appendix I evaluation for filters installed in plant ventilation systems. Fermi 2 conforms to 10CFR50 Appendix I without filtration installed.

END OF SECTION 7.0

Nuclear Production - Fermi 2 ODCM-8.0 Offsite Dose Calculation Manual Revision 6 Page 8.0-1 l SPECIAL DOSE ANALYSIS l 8.0 SPECIAL DOSE ANALYSES l 8.1 Doses Due to Activities inside the SITE BOUNDARY In accordance with ODCM 5.9.1.8, the Annual Radioactive Effluent Release Report submitted within 90 days after January 1 of each year shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE ,

PUBLIC due to their activities inside the SITE BOUNDARY. i Two locations within the Fermi 2 SITE BOUNDARY are accessible to MEMBERS OF THE PUBLIC for activities unrelated to Detroit Edison operational and support activities. One is the over-water portion of the SITE BOUNDARY due east of the plant. Ice fishermen sometimes fish here during the winter. The other is the Fermi 2 Visitor's Center, outside the protected area (but inside the Owner Controlled Area), approximately 470 meters SSW of the Reactor Building. The Visitor's Center is open to the public and is routinely visited by MEMBERS OF THE PUBLIC, including school tour groups on a frequency of once per year. kff Conservative assumptions of locations, exposure times, and exposure pathways for assessing doses from gaseous and liquid effluents due to activities inside the SITE BOUNDARY are presented in Table 8.0-1. The calculational methods presented in ODCM Sections 7.6 and 7.7 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the above assumptions. Attematively, the effluent concentration values of Appendix B, Table 2, of the revised 10 CFR Part 20 may be used to assess dose since these concentrations, if continuously inhaled or ingested, produce a total effective dose equivalent of 50 mrem per year.

The potential dose from the fish pathway to a MEMBER OF THE PUBLIC engaged in ice l fishing within the SITE BOUNDARY is accounted for by the modeling presented in ODCM I Section 6.5. Therefore, no additional special dose analyses are required for this exposure pathway for reporting in the Annual Radioactive Effluent Release Report.

l 8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 The Annual Radioactive Effluent Release Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases i and other nearby uranium fuel cycle sources (including dose contributions from effluents l and direct radiation from onsite sources). For the likely most exposed MEMBER OF THE i PUBLIC in the vicinity of the Fermi 2 site, the sources of exposure need consider only the radioactive effluents and direct exposure contribution from Fermi 2.

, ODCM-8.0 i ReWsion 6 l Page 8.0-2 l

No other fuel cycle facilities contribute significantly to the cumulative dose to a MEMBER

l. .OF THE PUBLIC in the immediate vicinity of the site. Davis Besse is the closest fuel :

cycle facility located about 20 miles to the SSE. Due to environmental dispersion, any !

l routine releases from Davis-Besse would contribute insignificantly to the potential doses in l the vicinity of Fermi 2. l l .

l As appropriate for demonstrating / evaluating compliance with the limits of l; ODCM 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used to provide data on actual measured levels of radioactive material in the actual ;

pathways of exposure. l 8.2.1 Effluent Dose Calculations i l

For purposes of implementing the surveillance requirements of ODCM 3.11.4. !

and the reporting requirements of ODCM 5.9.1.8, dose calculations for Fermi 2 '

may be performed using the calculational methods contained within this ODCM; the conservative controlling pathways and locations of Table 7.0-3 or the actual ,

pathways and locations as identified by the land use census (ODCM 3.12.2 and )

l ODCM 9.0) may be used. Liquid pathway doses may be calculated using Equation (610). Doses due to releases of radioiodines, tritium and particulates may be calculated based on Equation (714). !

1 l The following equations may be used for calculating the doses to MEMBERS OF L THE PUBLIC from releases of noble gases. Equation (8-2)is not used for

!- evaluating compliance with 40 CFR Part 190, since this regulation does not

! address skin dose. if noble gases are being released from more than one point,

! these equations must be used to evaluate each release point separately, and j then the doses must be added to obtain the total noble gas dose.

l D g = 3.17 E-08

X / Q *hKg

Qd (8-1) i and ' i l i i

D, = 3.17 E - 08

X / Q * [ (Lg +1.1M;)

Qg (8-2) where: 4 i

Dbt = total body dose due to gamma emissions for noble gas radionuclides (mrem)

Ds = skin dose due to gamma and beta emissions for noble gas radionuclides (mrad) i

'"O = atmospheric dispersion to the offsite location (sec/m3)

{

l ODCM-8.0 Revision 6 Page 8.0-3 Qi = cumulative release of noble gas radionuclide i over the period of interest (pCi)--may be determined according to Equation (7-8)

Ci = concentration of radionuclide i as determined by gamma spectral analysis of media (pCi/mi) 1.67E + 01 = (1 E + 03 ml/ liter) * (1 min /60 sec)

Ki = total body dose factor due to gamma emissions from noble !

gas radionuclide i (mrem /yr per pCi/m3)

(from Table 7.0-2)

Li = skin dose factor due to beta emissions from noble gas radionuclide I (mrem /yr per pCl/m3) (from Table 7.0-2) )

Mi = gamma air dose factor for noble gas radionuclide I (mrad /yr per pCi/m3) (from Table 7.0-2) ,

1 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) 3.17 E - 08 = 1/3.15 E + 07 yr/sec Average annual meterological dispersion parameters or meterological conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-specific annual averages).

8.2.2 Direct Exposure Dose Determination From evaluations performed in the Fermi 2 Environmental Report, Section b.3.4, the direct exposure to the highest offsite location from the Turbine Building N-16 skyshine dose has been calculated to be approximately 3 mrem / year. This value may be used as a baseline for actual direct exposure during plant operations.

Direct exposure to offsite or onsite individuals may be evaluated based on the results of environmental measurements (e.g. area TLD and survey meter data) or by the use of a radiation transport and shielding calculational method. Only l during atypical conditions will there exist any potential for significant onsite sources at Fermi 2 that would yield potentially significant offsite doses to a MEMBER OF THE PUBLIC. However, should a situation exist whereby the direct exposure contribution is potentially significant, onsite measurements, offsite measurements and calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance. The calculational techniques will be identified, reviewed, and approved at that time, and will be included in any report on doses due to such atypical conditions.

ODCM-8.0 l Revision 6 ;

Page 8.0-4 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data i Normally, the assessment of potential doses to MEMBERS OF THE PUBLIC must be calculated based on the measured radioactive effluents at the plant. '

The resultant levels of radioactive material in the offsite environment are usually so minute as to bs undetectable. The calculational methods presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals.

The results of the radiological environmental monitoring program can provide input into the overall assessment of impact of plant operations and radioactive effluents. With measured levels of plant related radioactive materialin principal l pathways of exposure, a quantitative assessment of potential exposures can be >

perfom' ed. With the monitoring program not identifying any measurable levels, ,

the data provides a qualitative assessment - a confirmatory demonstration of the negligible impact.

Dose modeling can be simplified into three basic parameters that can be applied ,

in using environmental monitoring data for dose assessment: !

D = C U

DF l (8-3)

I where i

D = dose or dose commitment C = concentration in the exposure media, such as air concentration for the inhalation pathway, or fish, vegetation or milk concentration for the ingestion pathway U = individual exposure to the pathway, such as br/yr for direct exposure, kg/yr for Ingestion pathway DF = dose conversion factor to convert from an exposure or uptake to an individual dose or dose commitment The applicability of each of these basic modeling parameters to the use of environmental monitoring data for dose assessment is addressed below:

Concentration - C The main value of using environmental sampling data to assess potential doses to individuals is that the data represents actual measured levels of radioactive j materialin the exposure pathways. This eliminates one main uncertainty and the l modeling has been removed - the release from the plant and the transport to the )

environmental exposure medium. l l

1

ODCM 8.0 Revision 6 Page 8.0-5 ,

t l

t-Environmental samples are collected on a routine frequency per the ODCM. To .

determine the annual average concentration in the environmental medium for l use in assessing cumulative dose for the year, an average concentration should .

l be determined based on the sampling frequency and measured levels:

I l

{ = hC

t) / 365.. g (8-4) j where:

C i=

average concentration in the sampling medium for the year i Ci = concentration of each radionuclide i measured in the individual l sampling medium i

l- t = period of time that the measured concentration is considered i' representative of the sampling medium (typically equal to the sampling frequency; e.g.,7 days for weekly samples,30 days for monthly

( samples).

If the concentration in the sampling medium is below the detection capabilities -

(i.e., less than Lower Limits of Detection (LLD), a value of zero should be used for Ci (Ci = 0).

Exposure - U l Default Exposure Values (U) as recommended in Regulatory Guide 1.109 are presented in Table 8.0-2. These values should be used only when specific data applicable to the environmental pathway being evaluated is unavailable.

Also, the routine radiological environmental monitoring program is designed to sample / monitor the environmental media that would provide early indications of -

any measurable levels in the environment but .1ot necessarily levels to which any individual is exposed. For example, sediment samples are collected in the area of the liquid discharge: typically, no individuah are directly exposed. To apply the measured levels of radioactivity in samplea that are not directly applicable to exposure to real individuals, the approach recommended is to correlate the location and measured levels to actual locations of exposure.

Hydrological or atmospheric dilution factors can be used to provide reasonable correlations of concentrations (and doses) at other locations. The other ,

[ altemative is to conservatively assume a hypothetical individual at the sampling l j location.- Doses that are calculated in this manner should be presented as '

hypothetical and very conservatively determined - actual exposure would be

much less. Samples collected from the Monroe water supply intake should be used for estimating the potential drinking water doses. Other water samples l

! collected, such as near field dilution area, are not applicable to this pathway.

l 1

f ~ ..

ODCM-8.0 l Revision 6 l Page 8.0-6 l l

Dose Factors - DF !

The dose factors are used to convert the intake of the radioactive material to an l individual dose commitment. Values of the dose factors are presented in l NRC Regulatory Guide 1.109. The use of the RG 1.109 values applicable to the 1 exposure pathway and maximum exposed individualis referenced in Table 8.0-2.

Assessment of Direct Exposure Doses from Noble Gases i

Thermoluminescent Desimeters (TLD) are routinely used to assess the direct l exposure component of radiation doses in the environment. However, because l routine releases of radioactive material (noble gases) are so low, the resultant '

direct exposure doses are also very low. A study

performed for the NRC concluded that it was generally impractical to distinguish any plant contribution to the natural background radiation levels (direct exposure) below around 10 mrem per year. Therefore, for routine releases from nuclear power plants the use of TLD is mainly confirmatory - ensuring actual exposures are within the expected natural background variation.

For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in ODCM Sections 7.6 and 8.2.1 represents the best method of assessing potential environmental doses. However, under unusual conditions, direct radiation from noble gas I concentrations could be sufficient to cause significant increases in TLD readings; any observed variations in TLD measurements outside the norm should be I

evaluated.

l NUREG/CR-0711. Evaluation of Methods for the Determination of X- and Gamma-Ray Exposure Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gail dePlanque, June 1979, USNRC.

END OF SECTION 8.0

t ODCM-8.0 ,

Revision 6 Page 8.0-7 TABLE 8.0-1 ,

Assumptions for Assessing Doses Due to Activities inside SITE BOUNDARY ice Fishing Visitor's Center Distance / 470 meters / E 470 meters / SSW Direction:

Estimated 240 hr/yr 4 hr/yr Exposure (20 hr/ week over (4 hr/ visit,1 visit Time: 3 month period) per year)

Exposure direct exposure direct exposure k !

from noble gases

'g5 Pathways: from noble gases l inhalation of inhalation of tritium, lodin6s. tritium, iodines .

l particulates particulates Meteorological annual average annual average Dispersion: (as determined (as determined for year being for year being evaluated) evaluated) 6.48E-6 sec/m3* 2.54E-6 sec/m3-Annual average X/O values for 1991. These values are shown as examples of the range of values to be expected.

- _ . - _ _ . ._. . . - . . =. -. .

ODCM-8.0 Revision 6 Page 8.0-8 TABLE 8.0-2 i Recommended Exposure Rates in Lieu of Site Specific Data' Table Reference Exposure Pathway Maximum Exposed Exposure Rates for Dose Factor Age Group from RG 1.109 Liquid Releases Fish Adult 21 kg/y E-11 Drinking Water Adult 7301/y E-11 Bottom Sediment Teen 67 h/y E-6 Atmospheric Releases Inhalation' Teen 8,000 m3/y E-8 Direct Exposure All 6,100 h/y" N/A Leafy Vegetables Child 26 kg/y E-13 Fruits, Vegetables Teen 630 kg/y E-12 and Grain )

Milk Infant 3301/y E-14 Adapted from Regulatory Guide 1.109, Table E-5. This table is not a complete list of exposure rates; other applicable values may be found in Regulatory Guide 1.109.

Net exposure of 6,100 h/y is based on the total 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year adjusted by a 0.7 shielding factor as recommended in Regulatory Guide 1.100.

l END OF SECTION 8.0

4 Nuclear Production - Fermi 2 ODCM-9.0 Offsite Dose Calculation Manual Revision 6 Page 9.0-1 j

_l ASSESSMENT OF LAND USE CENSUS DATA l 9.0 ASSESSMENT OF LAND USE CENSUS DATA A Land Use Census (LUC) is conducted annually in the vicinity of the Fermi 2 site. This census fulfills two main purposes: 1) Meet requirements of ODCM 3.12.2 for identifying controlling location / pathway for dose assessment of ODCM 3.11.2.3; and 2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC.

9.1 Land Use Census as Required by ODCM 3.12.2 As required by ODCM 3.12.2, a land use census shall be conducted during the growing season at least once per twelve months. The purpose of the census is to identify within a 5 mile distance the location in each of the 16 meterological sectors of all milk producing animals, all meat producing animals, all gardens larger than 500 ft2 producing broadleaf vegetation, and the closest residence to the plant. The data from the LUC is used for updating the location / pathway for dose assessment and for updating the Radiological Environmental Monitoring Program.

If the census identifies a location / pathway (s) yielding a higher potential dose to a MEMBER OF THE PUBLIC than currently being assessed as required by ODCM 3.11.2.3 (and ODCM Section 7.7 and Table 7.0-3), this new location pathway (s) shall be used for dose assessment.

Table 7.0-3 and plant procedures shall be updated to include the currently identified controlling location / pathway (s). Also, if the census identifies a location (s) that yields a calculated potential dose (via the same exposure pathway) 20% greater than a location currently included in the Radiological Environmental Monitoring Program, the new location (s) shall be added to the program within 30 days, unless permission to take samples cannot be obtained from the affected landowner. The sampling location (s), excluding control locations, having the lowest ]

calculated dose may be deleted from the program after October 31 following the current i census. As required by ODCM 3.12.2 and 5.9.1.8, the new location / pathway (s) shall be Identified in the next Annual Radioactive Effluent Release Report. The following guideline ]

shall be used for assessing the results from the land use census to ensure compliance with ODCM 3.12.2.

9.1.1 Data Compilation I

1. Compile all locations and pathways of exposure as identified by the land use census.

2. From this compiled data, identify any changes from the previous year's census. Identify the current controlling location / pathway (critical receptor) used in ODCM Table 7.0-3. Also, identify any location currently included in the REMP (Table 10-1).

ODCM-9.0 Revision 6 Page 9.0-2 ,

9.1.2 Evaluation of Relative Dose Significance if any identified changes are likely to change the identity of the critical receptor or to result in a potential dose via a particular pathway which is at least 20% greater ,

than the current maximum dose for that pathway, perform the following:

1. Determine the historical, annual average meterological dispersion and deposition parameters (X /O, D/Q) for any location to be evaluated for dose significance. Alllocations should be evaluated against the same historical meterological data set.

2. Perform relative dose calculations based on actual Fermi 2 gaseous effluent releases for a recent period of reactor operation, using the pathway dose equations of the ODCM. In identifying the critical receptor for Table ,

7.0-3, all age groups and all pathways relevant to ODCM 3.11.2.3 that may i be present at each evaluated location are considered. The critical receptor is assumed to be a member of the age group with the highest calculated dose to the maximally exposed organ due to 1-131,1-133, tritium, and particulates with half lives greater than 8 days. Other receptors may have ;

higher doses to other organs than the critical receptor has to those organs. ,

3. Formulate a listing of locations of high dose significance in descending order of relative dose significance. Include the relative dose significance in i the listing.

9.1.3 Program Updates *

1. If any receptor is identified with a higher relative dose than the current critical receptor in ODCM Table 7.0-3, this receptor and its associated -

location and pathways should replace the previously identified critical ,

receptor information in Table 7.0-3.

2. The Land Use Census data should be used to revise the REMP and Section 10.0 of the ODCM in accordance with ODCM 3.12.2, Action item b.

l

3. Any changes in either the controlling location / pathway (s) (critical receptor) for the ODCM dose calculations (Section 7.7 and Table 7.0-3) or the REMP (ODCM Section 10.0 and Table 10-1) shall be reported to NRC in accordance with ODCM 3.12.2, Action items a. and b. and ODCM 5.9.1.8.

ODCM-9.0 Revision 6 Page 9.0-3 NOTE: As permitted by footnote to ODCM 3.12.2, broadleaf vegetation

- sampling may be performed at the SITE BOUNDARY in two locations, in different sectors with highest predicted D/Os, in lieu of the garden census.

Also, for conservatism in dose assessment for compliance with ODCM 3.11.2.3 (see also ODCM Section 7.7 and Table 7.0-3), hypothetical exposure location / pathway (s) and conservative dispersion factors may be assumed (e.g., milk cow at 5 mile location or garden at SITE BOUNDARY in highest D/O sector). By this approach, the ODCM is not subject to frequent revision as pathways and locations change from year to year. A verification that the hypothetical pathway remains conservative and valid is still required. Also, for NRC reporting, the actual pathways and doses should be reported along with the hypothetical. The reporting of the actual pathway and doses provides a formal documentation of the more realistic dose impact.

9.2 Land Use Census to Support Realistic Dose Assessment The LUC provides data needed to support the special dose analyses of the ODCM -

' Section 8.0 Activities inside the SITE BOUNDARY should be periodically reviewed for dose assessment as required by ODCM 5.9.1.8 (see also ODCM Section 8.1).

' Assessment of realistic doses to MEMBERS OF THE PUBLIC is required by-ODCM 3.11.4 for demonstrating compliance with the_ EPA Environmental Dose Standard, 40 CFR 190 (ODCM Section 8.2).

To support these dose assessments, the LUC shall include use of Lake Erie water on and near the site. The LUC shall include data on Lake Erie use obtained from local and state officials. Reasonable efforts shall be made to identify individual irrigation and potable water users, and industrial and commercial water users whose source is Lake Erie. This data is used to verify the pathways of exposure used in ODCM Section 6.5.

END OF SECTION 9.0 l

l

.- --_ - - - - - - _- - -~ --.-. - .- - - - . .. -

Nuclear Production Fermi 2 ODCM 10.0 Offsite Dose Calculation Manual Revision 7 Page 10.0-1 l l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of ODCM 3.12.1. The sampling and analysis program described herein was developed to provide representative measurements of radiation and radioactive materials resulting from station operation in the principal pathways of exposure of MEMBERS OF THE PUBLIC. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent control 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 exposure pathways. Guidance for the development of this monitoring program is provided by the NRC Radiological Assessment Branch ;

Technical Position on Environmental Monitoring, Revision 1, November 1979.

10.1 Sampling Locations 1 Sampling locations as required by ODCM 3.12.1 are described in Table 10.0-1 and shown on the maps in Figures 10.0-1,10.0-2,10.0-3, and 10.0-4. Fermi 1 sampling locations are described in Table 10.0-2 and shown on the map in Figure 10.0-5.

NOTE: For purposes of implementing ODCM 3.12.2, sampling locations will be modified as required to reflect the findings of the annual land use census as described in ODCM Section 9.1 and as required by other contingencies (e.g. unavailability of milk from a listed location). Such changes will be documented in plant records and reflected in the next ODCM revision, the next Annual Effluent Release Report, and the next Annual Radiological Environmental Operating Report. Also, if the circumstances of such changes involve a possible change in the maximally exposed individual evaluated for ODCM Control 3.11.2.3, the identity of this individual will be reevaluated.

10.2 Reporting Levels ODCM 3.12.1, Action b, describes criteria for a Special Report to the NRC if levels of plant-related radioactive material, when averaged over a calendar quarter, exceed the prescribed levels of ODCM Table 3.12.1-2. The reporting levels are based on the design objective doses of 10 CFR 50, Appendix 1 (i.e., the annuallimits of ODCM 3.11.1.2,3.11.2.2 and 3.11.2.3). In other words, levels of radioactive material in the respective sampling medium equal to the prescribed reporting levels are representative of potential annual doses of 3 mrem, total body or 10 mrem, maximum organ from liquid pathways; or 5 mrem, total body, or 15 mrem, maximum organ for the gaseous effluent pathway. These potential doses are modeled on the maximum individual exposure or consumption rates of NRC Regulatory Guide 1.109.

l ODCM 10.0 l Revision 7 l Page 10.0-2 j 1

The evaluation of potential doses should be based solely on radioactive material resulting from plant operation, As stated in ODCM 3.12.1, Action b, the report shall also be ,

submitted if radionuclides other than those in ODCM Table 3.12.1-2 are detected (and are a result of plant effluents) and the potential dose exceeds the above annual design objectives. The method described in ODCM Section 8.2.3 may be used for assessing the potential dose and required reporting for radionuclides other than those in ODCM Table 3.12.12.

10.3 Interlaboratory Comparison Program A major objective of this program is to assist laboratories involved in environmental i radiation measurements to develop and maintain both an intrataboratory and an !

interlaboratory quality control program. This is accomplished through a laboratory intercomparison study (" cross-check") program involving environmental media and a

/afI

/

variety of radionuclides with activities at or near environmental levels. ,

I Simulated environmental samples. containing known amounts of one or more i radionuclides, are prepared and routinely distributed to Detroit Edison's contract environmentallaboratory, which performs the required analyses. The analysis results are then compared to the known concentrations in the samples. The program thus enables the laboratory to document the precision and accuracy of its radiation data, and identify j2 ;

instrument and procedural problems. .//g The environmental laboratory is required to participate in an interlaboratory Comparison Program and to submit QA Program Progress Summary Reports to Detroit Edison on an l annual basis. These reports contain performance data summaries on blind spiked analyses, and explanations of deviations from expected results. A summary of the Interlaboratory Comparison Program results obtained is required to be included in the Annual Radiological Environmental Operating Report pursuant to ODCM 5.9.1.7, Participation in an interlaboratory Comparison Program ensures that an independent check on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices is performed as part of the QA Program for environmental monitoring in order to demonstrate that the results are valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR Part 50.

)

I i

ODCM-10.0 Revision 7 !

Page 10.0-3 J TABLE 10.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FERMI 2 SAMPLE LOCATIONS AND ASSOCIATED MEDIA KEY 1- T TLD Locations (Pg.10.0-4 through 10.0-8) 2- S Sediments Locations (Pg.10.0 9) 3- F Fish Locations (Pg.10.0-9) 4- M Milk Locations (Pg.10.0-10) )

5- DW Drinking Water Locations (Pg.10.0-11)

]

6- SW Surface Water Locations (Pg.10.0-11) 7- GW Ground Water Locations (Pg.10.0-11) 8- API Air Particulate / lodine Locations (Pg.10.0-12) 9- FP Food Products Locations (Pg.10.0-13) l i

~

ODCM-10.0 Revlolon 7 Page 10.0-4 TABLE 10.0-1 Redelegleel Esevironmental IIonnering Progreen, Fermi 2 Seenple LoceSono and 7.wooelsted Mose Derect Reemmen T _ _ _ lg _ _ J NWN t;;;,ntNM r e %, g" . ' g - % 3+ : M 'y -

e. .

3 h4 '. Descr$dfon NQ ~ ,'@d:

qs G~ N - 'Q80sesi(; Q /W 1- sp' W s

AfWienterq{7"ObseMsn4*w_ _ AseneWaftssetor$4pprest),

wN:1 N- &# ' - - "c- -* ' -

' j@" ; y ;;3(

' ~ " - -

'L4-N

' ' - ~

T1 NEfJIf 1.3 ml Estral Booch Pole on Lahoshore,23 Poles S of Lakeview Direct Re:Seilon o (Special Area)

T2 NNE4!2' 1.2 ml East of terminellon of Branchoeu St. on poet Direct R=re= sing Q (Special Area)

T3 Naf 1.1 mi Pole, NW Comer of Swan Boot Club Fence Dired R=amaann o

('e=ri=8 Area)

T4 NNW/33f 0.6 mi Sile Boundary and Tog Rd, on Slie Fence by API #2 Direct pare = sing o

', T5 NW/313" 0.6 rni S11e Boundary and Tag Rd, on Sne Fence by API #3 Dired Raressing Q T6 WNW/293* 0.6 ml Pole, NE Comer of Bddne over Toll Rd. Direct Raramann o TT W/27tf 14.0 mi Pole, et Michigen Gas =d=tation on N. Cueler Rd.,0.06 mges W of Doty Rd. (Contro0 Olvect R=remainn o N T6 NW/305' 1.9 mi Pole on Post Rd. near NE Comer of Dhde Hwy. and Post Rd. Direct R=re= sing o T9 NNW/334* 1.5 mi Pole, NW Comer of Trombioy and thuen View Road Direct Reageson O T10 NAl" 2.1 ml Pole, S Side of Messeront - 2 Pohs W cd Chinevere Direct parassing o N T11 NNE/23' 6.2 mi Pole, NE Comer of Mimmen and Joserman Direct R=remenn O T12 NNE4!If 6.3 mi Poinie Moumee Game Area - Field Ollice, Pole near Tree N Area of Direct Raressing o Paddne Lot T13 N/351f 4.1 ml Lobo end Dbde Hwy - Pole on SW Comer wilh Light Direct paramaan Q T14 NNW/337' 4.4 mi Lobo arv Brandon - Pole on SE Comer neer RR e

Direct Re:Sation O T15 NW/315' 3.9 mi Pole, behina Newport Post Ollice Direct RadleNon O T16 WNW/283* 4.9 mi Pole, SE comer of War and Post Rds. Direct Radiation O

. - . - - ._ _. - _~

ODCM-10 0 Revision 7 Page 10.0-5 TABLE 10.61 Radiological Environmental Monitoring Program, Fermi 2 tL9 Locations and Associated Media Direct Radsstion Steffen afsteorofogicef Disemece free Nuentner 9scenefAninnogh Reector(Approir.)

^

' CL _ , _ ; 40ede Frequency v w,

.m. n. - ; -

i T17 W/271* 4.9 mi Pole, NE Comer of Nadeau and LaPrad near Mobile Home Park Direct Radiation O T18 WSW/24f 4.8 mi Pole, NE Corner of Mentel and Hurd Direct Radiation O T19 SW/236* 5.2 mi 1st Pole E. of Fermi Siren on Waterworks Rd. NE comer of Direct Radiation O intersection - Sterung State Park Rd. Entrance Drive / Waterworks (in Sterling State Park)

T20 WSW/25f 2.7 mi Pole, S Side of Williams Rd. - 8 Poles W of Dixie Hwy. (Special Area) Direct Radiation O T21 WSW/239' 2.7 mi Pole, N Side of Pearl at Parkview - Woodland Beach (Special Area) Direct Radiation O T22 S/172* 1.2 mi Pole, N Side of Pointe Aux Peaux 2 Poles W of Long - Site Boundary Direct Radiation O I T23 SSW/195* 1.1 mi Pole, S Side of Pointe Aux Peaux - 1 Pole W of Huron next to Vent Direct Radiation O Pipe - Site Boundary T24 SW/225* 1.2 mi Fermi Gate along Pointe Aux Peaux Rd.- on fence wire W of Gate - Direct Radiation O Site Boundary T25 WSW/251* 1.5 mi Pole, Tou Rd. - 13 Poles S of Fermi Dr. Direct Radial _ ion O T26 WSW/259" 1.1 mi Pole. Toll Rd. - 6 Poles S of Fermi Dr. Direct F',adiation O T27 SW/225" 6.8 mi Pole NE Comer of McMi,1an and East Front St. (Special Area) Direct Radiation O

(

T28 SW/229* 10.7 mi Pole, SE Comer of Mortar Creek and LaPlaisance (Control) Direct Radiation O T29 WSW/23f 10.3 mi Pole, E Side of S Dixie,1 Pole S of Albain (Control) Direct Radiation O T30 WSW/24f 7.8 mi Pole, St. Mary's Park Comer of Elm and Monroe St. S side of parking Direct Radiation O lot next to river (Special Area)

T31 WSW/255' 9.6 mi 1st Pole W of Entrance Drive Milton

Pat" Munson Recreational Dirse! Rr.diation O '

Reserve - N. Custer Rd. (Control)

ODCM-10 0 Revision 7 Page 10.0-6 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station Noenorologicat. Dieterse from Number SectorfAllmtoilt R, eector(Approir.) Descriptfon Media Frequency T32 WNW/295* 10.3 mi Pole, Comer of Stony Creek and Finzel Rds. Direct Radiation O T33 NW/317' 9.2 mi Pole W Side of Grafton Rd.1 Pole N of Ash /Grafton Intersection Direct Radiation O T34 NNW/338' 9.7 mi Pole W Side of Port Creek,1 pole S of Will Carleton Rd. Direct Radiation O T35 N/359' 6.9 mi Pole, S Side of S. Huron River Dr. across from Race St. (Special Direct Radiation O Area)

T36 N/358* 9.1 mi Pole, NE Comer of Gibraltar and Cahill Rds. Direct Radiation O T37 NNE/21' 9.8 mi Pole, S Comer of Adams and Gibraltar (across f rom Humbug Marina) Direct Radiation O T38 WNW/294* 1.7 mi Residence - 6594 N. Dixie Hwy. Direct Radiation O T39 S/176* 0.3 mi SE Comer of Protected Area Fence (PAF) Direct Radiation O T40 S/170* 0.3 mi Midway along OBA - PAF Direct Radiation O SSE/161* 0.2 mi Midway between OBA and Shield Wall - PAF Direct Radiation O T41 T42 SSE/149" 0.2 mi Midway along Shield Wall- PAF Direct Radiation O T43 SE/131' O.1 mi Midway between Shield Wall and Aux Boilers - PAF Direct Radiation O T44 ESE/109' O.1 mi Opposite OSSF Door - PAF Direct Radiation O T45 E/86* 0.1 mi NE Comer - PAF T46 ENE/67* 0.2 mi NE Side Barge Slip - on Fence Direct Radiation O T47 S/185* 0.1 mi South of Turbine Bldg. rollup door on PAF Direct Radiation O T48 SW/235* 0.2 mi 30 ft. from comer of AAP on PAF

ODCM-10.0 Revision 7 Page 10.0-7 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station A0sesorofogical . Dietence froen Reector(Approt) DescrQation niedia Frequency Sector /Azinnotts N.m narntner % n. no <.t.. +

1.1 mi Corner of site boundary fence north of NOC along Critical Path Rd. Direct Radiation O T49 WSW/251" 0.9 mi Site boundary fence near main gate by the south Bullit St. sign Direct Radiation O T50 W/270*

TS1 N/3" 0.4 mi Site boundary fence north of North Cooling Tower Direct Radiation C.

O.4 mi Site boundary fence at the comer of Arson and Tower Direct Radiation O T52 NNE/20' O.2 mi Site boundary fence east of South Cooling Tower Direct Radiation O T53 NE/55' 0.3 mi Pole, next to Fermi 2 Visitors Center Direct Radiation O T54 S/189*

3.3 mi First pole east of Frenchtown Fire Glation entrance, across from Sodt Direct Radetion O T55 WSW/251*

Elementary School 4.9 mi Pole, entrance to Jefferson Middle School on Stony Creek Rd. Direct Radiation O T56 WSW/255' 2.7 mi Pole, north side of Williams Rd. across from Jellerson High School Direct Radiation O T57 W/260*

entrance WSW/249' 4.9 ml Pole, west of Hurd Elementary School Marquee Direct Radiation O T58 2.6 mi Pole, north of St. Charles Church entrance on Dixie Hwy. Direct Radiation O T59 NW/325*

NNW/341" 2.5 mi 1st pole north of North Elementary School entrance on Dixie Hwy. Direct Radiation O T60 W/268* 10.1 mi Pole, SW Comer of Stewart and Raisinville Rds. Direct Radiation O T61 SW/232" 9.7 mi Pole, NW Comer of Albain and Hull Rds. Direct Radiation O T62 WSW/245" 9.6 mi Pole, Comer of Dunbar and Telegraph Rds. Direct Radiation O T63 T64 WNW/286* 0.2 mi W of switchgear yard on PAF Direct Radiation O ,

T65 NW/322" 0.1 mi PAF switchgear yard area NW of RHR complex Direct Radiation O

ODCM-10 0 Revision 7 Page 10.0-8 TABLE 10.0-1 Radiological Envkonmental Monitoring Program, Fermi 2 Sample Locations and Associated Medea Direct Radiation Staffors Atetsorofogical Dietersee flrom Numtrer Socior/Asimutts Reactor (Approt) Descr>tions A0edia frequency

4 t-f* *5 t T66 NE/50' O.1 mi Behind Bldg. 42 on PAF Direct Radiation O f T67 NNW/388* 0.2 mi Site boundary fence W of S cooling tower Direct Radiatbn O

_ . . _ . _ _ _ _ _ . . _ _ _ . . - _ _ _ _ _.____m__.___-___m____ _ _ _ _ _ _ . _ _ _ _ _ - . _ -e - -- m__ __a__

ODCM-10.0 Revision 7 Page 10.0-9 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Fish and Sediment Ste#pri Afossorofopicat , Distance firem Nurniser Sector (Animuth Reactor (Agiprok.) Descr4ption n0edia Frequency m '

SEDitAENTS S-1 SSE/165* 0.9 mi Pointe Aux Peaux, Shoreline to 500 ft. offshore sighting directly to Sediment SA Land Base Water Tower E/81* 0.2 mi Fermi 2 Discharge, approx. 200 ft. offshore Sediment SA S-2 NE/39* 1.1 mi Estral Beach, approx. 200 ft. offshore, off North shoreline where Sediment SA S-3 Swan Creek and Lake Erie meet 3.0 mi Indian Trails Community Beach Sediment SA S-4 WSW/241' 11.7 mi DECO *s Trenton Channel Power Plant intake area (Control) Sediment SA S-5 NNE/20*

FISH NNE/31' 9.5 mi Celeron Island (Control) Fish SA F-1

[pmi 2 Dischg!go @gmx 12M 11 offsim) , _ [h!! SA E:2 [/87 _ ,_ 9:3 m,j _

F-3 WSW/238* 4.8 mi Breast Bay Marina Area (Control) Fish SA

ODCM-10 0 Revision ?

Page 10.0-10 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 r@ Locations and Associated Media Milk / Grass Station NoteoroCogical Distance from Peactor(Approt) Descr& tion Media Frequency Number Sector /Asimuth

,e t-Reaume Farm -2705 E. Labo Milk M-SM M-2 NW/319" 5.4 mi Calder Dairy - 9334 Finzel Rd. Mdk M-SM M-8 WNW/289* 9.9 mi

/

N/6* 4.2 mi Bourasso Farm - 6658 Labo Rd. Mdk M-SM $'h

._ M-9 __

ODCM-10 0 Revision 7 Page 10 0-11 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Water Sta0\on 80eenerological Distance fimm Nuinber Sector /Asinutfn Renchw(Approx.) DescrQtion n0edte Frequency

3. -

DRINKING WATER S/174* 1.1 mi Monroe Water Station N Side of Pointe Aux Peaux 1/2 Block W of Drinking Water M DW-1 Long Rd.

Detroit Water Station,14700 Moran Rd. Allen Park (Control) Drinking Water M I,I DW-2 N/8* 18.5 mi SURFACE WATER NNE/20* 11.7 mi DECO's Trenton Channel Power Plant intake Structure (Screenhouse Surface Water M SW-2

1)(Control)

SW-3 SSE/160* 0.2 mi DECO's Fermi 2 General Service Water intake Structure Surface Water M f SITE WELLS GW-1 S/175* 0.4 mi Approx.100 ft. W of Lake Erie EF-1 Parking lot Groundwater near Groundwater O gas fired peakers GW-2 SSW/208* 1.0 mi 4 ft. S of Pointe Aux Peaux (PAP) Rd. Fence 427 ft. W of where PAP Groundwater O crosses over Stony Point's Westem Dike GW-3 SW/226* 1.0 mi 143 ft. W of PAP Rd Gate,62 ft. N of PAP Rd. Fence Groundwater O GW-4 WNW/299" 0.6 mi 42 ft. S of Langton Rd.,8 ft. E of Toll Rd. Fence Groundwater O

ODCM-10.0 Revision 7 Page 10 0-12 TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Air Particulate Air lodine Station Meenannogical LNetance kom Number SectorfAtimutts DescrQtion Media Fi m z y R..eact,or(Approx.)

NE/39* 1.4 mi Estral Beach Pole on Lakeshore,18 Poles S of Lakeview (Nearest Radioiodine W API-1 Community with highest X /O) Particulates W NNW/337' O.6 mi Site Boundary and Toll Road, on Site Fence by T-4 Radioeodine W API-2 Particulates W NW/313' O.6 mi Site Boundary and Toll Road, on Site Fence by T-5 Radiciodene W API-3 Particulates W API-4 W/270* 14.0 mi Pole, at Michigan Gas substation on N. Custer Rd ,0 66 miles W of Radioiodine W j[

Doty Rd. (control) Particulates W S/191* 1.2 mi One pole south of Pointe Aux Peaux Rd. on Erie St. Radioiodine W API-5 Particulates W

ODCM-10.0 Revision 7 Page 10.0-13 TABLE 10.0-1 Radiologk:al Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Food Products Staffon W Diesence from Description needia Frequency SectorfAsimuth Re.

N,,uminr

o. e s

%r n. a,ct.or(Approx.)

FP-1 NNE/21' 3.8 mi 9501 Turnpike Highway Food Products M (when y available)

FP-3 NNFJ12* 1.1 mi 6441 Brancheau Food Products M (wten available) l/ _

FP-7 WNW/302" 0.7 mi 6200 Langton* Food Products M (when available)

FP-9 W/261* 10.9 mi 4074 North Custer Road Food Products M (when f'[

available)

Calculated critical receptor

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ODCM-10.0 R&idon 7 Page 10 0-15 TABLE 10.0-2 Radiological Environmental Monitoring Program, Fermi 1 Sample Locations and Associated Media Water Station Z.:_2t-F M Number Sector / Azimuth Distance from Direction Reactor (approx.) Description Media Frequency Surface Water South Lagoon S/1900 0.5 rni Shoreline behind fuel oil storage tank SW SA Swan Creek NW/560 1.9 mi Area below bndge N of Dixie Hwy and Swan SW SA Creek Rd. (Public Access area)

Reactor NE/00 0.4 mi Area where overflow canal meets Swan Creek SW SA Channel Lake Water SSE/1590 0.4 mi Fermi 1 inlet E of pumphouse SW SA

3 Raw City Water City of S/1690 1.2 mi Monroe Water Station, N side of Point Aux RW SA Monroe Peaux,1/2 block W of Long Rd.

Fermi 1 SSE/1590 0.4 mi Fermi Unit 1 Raw Lake water intake structure RW SA City of NNE/280 29.5 mi Detroit Water Treatment Plant Detroit 14700 Moran Rd., Allen Park RW SA Note: Distances were taken from Fermi 2 Reactor Center Line.

ODCM-10 0 Revision 7 Page 10.0-16 TABLE 10.0-2 Radiological Environmental Monitoring Program, Fermi 1 Sample Locations and Associated Media Sediments Station 1 2 ,4---j 2 Number Sector / Azimuth Distance from Direction Reactor (approx) Description Media Frequency South Lagoon S/1900 0.5 mi Shoreline behind fuel oil storage tank Sediment SA Reactor Channel N/00 0.4 mi Area where overflow canal meets Swan Creek Sediment SA Swan Creek NW/560 1.9 mi Area below bndge N of Dixie Hwy. and Swan Creek Rd. (public access area) Sediment SA i

w, .

l f,, l 1

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l l Nuclear Production - Fermi 2 ODCM-APP-A Offsite Dose Calculation Manual Revision 5 Page A-1 APPENDIX A: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS l LIQUID EFFLUENT RELEASES Overview To simplify the dose calculation process, it is conservative to identify a controlling, dose-significant radionuclide and to use its dose conversion factor in the dose calculations. Using the total release

, (i.e., the cumulative activity of all radionuclides) and this single dose conversion factor as inputs to a j one-step dose assessment yields a dose calculafon method which is both simple and conservative.

I' Fermi 2 does not have a large data base of previous reibses of radioactive liquid effluents upon which to base the determination of the controlling, dose-significant isotope. The Fermi 2 UFSAR, Table 11.2-9 presents the estimated annual releases from liquid effluents as calculated using the l

NRC GALE computer code, (NUREG-0016. Revision 1). Site specific dose conversion factors (Aio) from ODCM Table 6.01 were multiplied by the UFSAR estimated annual release quantity to determine a relative dose significance. Table A-1 presents the results of this relative dose evaluation.

Because Cs-134 is the controlling nuclide for the total body dose and has the highest dose conversion factor among the nuclides evaluated for that dose, the use of its dose conversion factor in the simplified dose assessment method for evaluating the total body dose is demonstrably

conservative.

l Ssiection of the appropriate dose conversion factor for the maximum organ dose is not so straightforward. Inspection of Table A-1 shows that the thyroid dose is the controlling organ dose, and it follows that the iodines are the controlling radionuclides. However, this identification is based upon the FSAR estimate of annual releases. To be adequately conservative when using this simplified method, it is appropriate to select the largest dose conversion factor from among all the radionuclides evaluated to assure that offsite doses are not mistakenly underestimated.

For the UFSAR Table 11.2-9 isotopes evaluated, there are a few radionuclides with a higher dose conversion factor than 1-133 for the thyroid dose. Further inspection of Table A-1 shows that P-32 is the major contributor to the dose to the bone, which is the second highest organ dose. P-32 has a high dose conversion factor (1.39 E + 06 mrem /hr per UCi/ml) and would provide additional conservatism if used as the simplifying dose conversion factor. However, analysis for P-32 is not required. P-32 decays by beta emission without any accompanying characteristic gammas.

Use of the P-32 dose conversion factor is therefore inappropriate. The next largest dose conversion factor of the evaluated radionuclides is Cs-134 for the dose to the liver at 7.09 E + 05 mrem /hr per uCi/ml. (The dose to the livar is the third largest organ dose.) As Cs-134 is easily measured with

. gamma spectroscopy, has a long half-life, and a high organ dose conversion factor, it is used as the controlling radionuclide for the simplified maximum organ dose assessment.

I t

i

{ l

i ODCM APP-A l Revision 5 I Page A-2 Simplified Method For evaluation of compliance with the dose limits ODCM 3.11.1.2, the following simplified equations may be used: 1 l

Total Body l

1.67E - 02

VOL A Dtb = * (Cs - 134,tb)

1C, DF*Z (A-1) where:

l Dbt = dose to the total body (mrem)

VOL = volume of liquid effluents released (gal) l l

DF = average circulating water reservoir decant line flow (gal / min) !

Z = 5, near field dilution factor (derived from Regulatory Guide 1.109)

A(Cs-134,tb) = 5.80 E + 05 mrem /hr per pCi/ml, the total body ingestion dose factor for Cs-134 Ci = total concentration of all radionuclides (pCi/ml) 1,67 E - 02 = 1 hr/60 min Substituting the value for the Cs-134 total body dose conversion factor, the equation simplifies to: ,

9.69E +03

VOL !

Dtb " op*z

IC; (A2)

Maximum Organ D"" = 1.67E-02

VOL

A(Cs -134, liver)* IQ DF*Z (A3) where:

Dmax = maximum organ dose (mrem)

A(Cs-134, liver) = 7.09 E + 05 mrem /hr per pCi/ml, the liver ingestion dose factor for Cs-134

ODCM-APP A Revision 5 Page A-3 Substituting the value for the Cs-134 liver dose conversion factor, the equation simplifies to:

l 1.18E +04

VOL Dmax =

DF*Z 3 (A-4)

Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible. Furthermore, the release of tritium is a function of operating history and is essentially unrelated to radwaste system operations.

l l

l' l

l l

l I

l 1

i l

l 1

ODCM-APP-A Revision 5 Page A-4

, TABLE A-1 ,

Relative Dose Significance of Radionuclides in Liquid Effluents Estimated Annual Relative Dose Significance Ag

Curies Percent Dose Contribution (% total)

Releases ,

W* Centee Bone Uwer T. Body 7hyroM MGney Lung G H.LI Bone ther TBody 7hyroM Mdney Lung GI-LLI Na-24 .00440 1.87 1.87 1.87 1.87 1.87 1.87 1.87 .69 .72 .98 .27 1.71 7.26 1.42 P-32 .00011 152.70 9.49 5.90 0 0 0 17.17 56.37 3 63 3.10 0 0 0 13.06 Mn-56 .00970 0 1.08 .19 0 1.37 0 34.47 0 .41 .10 0 1.25 0 26.23 ,

Cu-64 .01300 0 .14 .07 0 .36 0 12.05 0 .05 .03 0 .33 0 9.17 Zn-65 .00011 2.55 8.13 3.67 0 5.44 0 5.12 .94 3 11 1.93 0 4.97 0 3 90 Sr-91 .00160 .75 0 .03 0 0 0 3.57 .28 0 .02 0 0 0 2.72 SR-92 .00200 .36 0 .02 0 0 0 7.04 .13 0 .01 0 0 0 5.36 V-92 .00270 .00 0 .00 0 0 0 2.82 .00 0 .00 0 0 0 2.15 V-93 .00160 .00 0 .00 0 0 0 9.61 .00 0 .00 0 0 0 7.31 Te-131m .00005 .08 .04 .03 .06 .41 0 4.07 .03 .02 .02 .01 .38 0 3.09 l-131 .00220 .43 .61 .35 200.42 1.05 0 .16 .16 .23 .18 28.54 .96 0 .12 1-132 .01100 .10 .28 .10 9.76 .44 0 .05 .04 11 .05 1.39 .41 0 .04 l-133 .02500 1.66 2.88 .88 423.96 5.03 0 2.59 .61 1.10 .46 60.38 4.60 0 1.97 l-135 .01800 .37 .98 .36 64.33 1.56 0 1.10 .14 .37 .19 9.16 1.43 0 .84 Cs-134 .00017 50.74 120.74 98.71 0 39.08 12.97 2.11 18.73 46.20 51.79 0 35.70 50.29 1.61 Cs-136 .00044 13.75 54.26 39.06 0 30.19 4.14 6.17 5.07- 20 76 20.49 0 27.59 16 04 4.69 Cs-137 .00011 42.07 57.54 37.69 0 19.53 6.49 1.11 15.53 22.02 19.77 0 17.85 25.17 .85 Cs-138 .00400 1.06 2.09 1.04 0 1.54 .15 .00 .39 .80 .54 0 1.40 .59 .00 W-187 .00014 .04 .03 .01 0 0 0 11.38 .02 .01 .01 0 0 0 8.66 Np-239 .00360 .00 .00 .00 0 .00 0 3.00 .00 .00 .00 0 .00 0 2.28 TOTAL 288.53 260.16 189.98 700.40 107.87 25.62 125.46 99.13 99.54 99.67 99.75 98.58 99 35 95 47 Radionuclide distribution from Fermi 2 UFSAR, Section 11.2, Table 11.2-9. Radionuclides contributing less than 1% of the total relative dose

' for any organ have been deleted. ,

END OF APPENDIX A '

Nuclear Production - Fermi 2 ODCM-APP-B Offsite Dose Calculation Manual Revision 5 Page B-1 APPENDIX B: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADWASTE EFFLUENTS I

Overview '

Dose evaluations for releases of gaseous radioactive effluents may be simplified by the use of an effective dose factor rather than radionuclide-specific dose factors. These effective dose factors are applied to the total radioactive release to approximate the various doses in the I environment;i.e., the total body, gamma air, and beta-air doses. The effective dose factors are based on the typical radionuclide distribution in the gaseous radioactive effluents. This approach reduces the analyses to a single multiplication (Keff, Meff. or Neff) times the quantity of radioactive gases released, rather than individual analyses for each radionuclide and summing the results to determine the dose. Yet the approach provides a reasonable estimate of the actual doses since under normal operating conditions there is relatively little variation in the radionuclide distribution.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

K,gg=1(Kg*f) g (B-1) where:

Keff = the effective total body dose factor due to gamma emissions from all noble gases released (mrem /yr per pCl/m3, effective)

Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released (mrem /yr per pCl/m3, from Table 7.0-2) fi = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity (L + 1.1 M)eff = 1 Lg + 1.1 Mh *g f (B-2)

)

ODCM-APP B Revision 5 Page B-2 where:

(L + 1.1 M)eff = the effective skin ciose factor due to beta and gamma emissions from all noble gases released (mrem /yr per uCl/m3, effective)

(Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released (mrem /yr per uC1/m3, from Table 7.0-2)

M,,7 = Eht;

f g)

(B-3) where:

Meff = the effective air dose factor due to gamma emissions from all noble gases I released (mrad /yr per UCi/m3, effective)

Mi = the air dose factor due to gamma emissions from each noble gas radionuclide i released (mrad /yr per uCl/m3, from Table 7.0-2) 1 N,g = E(Ng

f g)

(B-4) where:

Neff = the effective air dose factor due to beta emissions from all noble gases released (mrad /yr per uCl/m3, effective)

Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released (mrad /yr per uC1/m3, from Table 7.0-2)

Normally, past radioactive effluent data would be used for the determination of the effective dose factors. Fermi 2, however, does not have a sufficient operating history at or near full power to prc'/de a reasonable data base for determination of the typical radionuclide distribution in gaseous effluents. Therefore, the UFSAR estimate of radionuclide concentrations at the site boundary is used as the initial typical distribution. The effective dose factors derived from this distribution are presented in Table B-1.

l

ODCM APP-B l Revision 5 l

Page B 3 Application l

l To provide an additional degree of conservatism, a factor of 2.0 is introduced into the dose calculation when the effective dose factor is used. This conservatism provides additional l

assurance that the evaluation of doses by the use of a single effective dose factor will not significantly underestimate any actual doses in the environment.

For evaluating compliance with the dose limits of ODCM 3.11.2.2 the following simplified equations may be used:

D = 2.0

3.17 E- 08

x / Q

M,ff *1Qg ;

(B5) and Dp = 2.0

3.17 E -08

x /Q

N,ff *1 Q; (B-6) where:

D I Y = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)

D 0 = air dose due to beta emissions for the cumulative release of all noble gases (mrad) l 1

%/Q = atmospheric dispersion to the controlling site boundary (sec/m3) !

Mett = 2.7 E + 03, effective gamma-air dose factor (mrad /yr per pCl/m3)

Neff = 2.3 E + 03, effective beta air dose factor (mrad /yr per pCi/m3)

Oi = cumulative release for all noble gas radionuclides (pCi) 3.17 E - 08 = conversion factor (yr/sec) 2.0 - conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculation equations simplify to:

Dy = 1.71 E-04 *X / Q * [Qi (B-7) and D p = 1.46 E- 04

X / Q *[Qi (B-8)

The effective dose factors are used for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods when the computer or ODCM software

! may be unavailable to perform a detailed dose assessment.

ODCM-APP B Revision 5 Page B-4 TABLE B-1 Effective Dose Factors - Noble Gas Effiluents Total Body Skin Dose Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Isotope Fractional

Dose Factor Koff (L + 1.1 Moff) Moff Nett Abundance' (mrom/yr (mrom/yr per (mrad /yr per (mradlyr per uCVm3) uCi/m3) (uCl/m3) uCi/m3)

Kr-85m 0.10 1.2E+02 2.8E+02 1.2E+02 2.0E+02 Kr85 0.01 1.6E-01 1.4E+01 1.7E-01 2.0E+01 Kr 88 0.04 5.9E+02 7.6E+02 6.1E+02 1.2E+02 Kr-89 0.06 1.0E+03 1.7E+03 1.0E+03 6.4E+02 Xe 133 0.67 2.0E+02 4.7E+02 2.4E+02 7.0E+02 Xe-135 0.02 3.6E+01 7.9E+01 3.8E+01 4.9E+01 Xe 137 0.02 2.8E+01 2.8E+02 3.0E+01 2.5E+02 Xe-138 0.07 6.2E+02 1.0E+03 6.4E+02 3.3E+02 TOTAL 2.6E+03 4.6E+03 2.7E+03 2.3E+03 Radionuclide distribution derived from Fermi 2 UFSAR, Section 11.3, Table 11.3-6, Kr 90, Kr-91, Xe-139, and Xe-140 have been excluded from the UFSAR distribution because of short half-lives and subsequent decay during environmental transport. Kr-87, Xe-131m, and Xe-133m have been excluded because of their negligible fractional abundance.

END OF APPENDIX B

. . . _ , . _

NRC-96-0025, Annual Radioactive Effluent Release Rept for Period Jan-Dec 1995

Contents

Text

References:

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

s g =

= =

= = = = -

- - - - =

= - - 1.4Sb6 - l Sk97

=

= =

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NRC-96-0025, Annual Radioactive Effluent Release Rept for Period Jan-Dec 1995

Text

References:

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

s g =

= =

= = = = -

- - - - =

= - - 1.4Sb6 - l Sk97

=

= =

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