NRC-94-0029, Annual Radioactive Effluent Release Rept for Period of Jan-Dec 1993
| ML20065C466 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/31/1993 |
| From: | Gipson D DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-94-0029, CON-NRC-94-29 NUDOCS 9404050168 | |
| Download: ML20065C466 (227) | |
Text
{{#Wiki_filter:_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Douglas R. Gipson Senior Wce Prescent Nuclear Generation Detroit ,e a 6400 North Dine Highway Newport, Mechigan 48166 (313) 586-5249 March 31, 1994 NRC-94-0029 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
Subject:
Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report for Fermi 2 is attached. This report is being transmitted in compli u ce with Reference 2 and Regulatory Guide 1.21, Revision 1. Ite attached report covers the period from January 1 through December 31, 1993 Please direct any questions or requests for additional information to Thomas J. VanderMey Radiological Engineer at (313) 586-1539, or Joseph M. Pendergast, Compliance Engineer, e (313) 586-1682. Sincerely, V Enclosure cc: T. G. Colburn M. P. Phillips J. B. Martin K. B. Riemer Region III
$N*RBUR Rggs eiA1 v'u.o c.c'.
fg < p,
U. S. Nuclear Rigulatory Cosmicsion March 31, 1994 NRC-94-0029 Page 2 bec: w/o Encl. J. L. Crews R. A. DeLong (w/ Encl.) R. R. Eberhardt (w/ Encl.) P. Fessler
. D. R. Gipson L. S. Goodman L. K. Layton R. McKeon W. E. Miller, Jr.
R. A. Newkirk D. O. Nordquist D. P. Ockerman W. D. Romberg R. B. Stafford W. M. Tucker
.J. G. Walker .
Information Management (140 NOC) (w/ Encl.) Secretary's Office (2412 WCL) (w/ Encl.) D. R. Hahn (Michigan Dept./Public Health) (w/ Encl.) NSRG Secretary /ISEG Coordinator (230 AIB) (w/ Encl.) UFSAR Coordinator (w/ Encl.) NRR Chron File (w/ Encl.) Routing Copy I
i DETROIT EDISON COhlPANY FERhfI 2 NUCLEAR POWER PLANT OPERATING LICENSE NO. NPF - 43 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ' for the period of January 1,1993 through December 31,1993 I _ _ _ _ _ _ _ _ - _ _ _
1993 Annual Radioactive Efiluent Release Report March 1994 PREFACE 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 for disposal. In a liquid release, a tank containing radioactive water is sampled prior to discharge. Based on the analysis of this sample, both the amount of radioactivity in the tank and the potential radiation dose to a member of the public are determined, and these figures are compared to federal limits. In calculating the radiation dose, conservative assumptions are used. For example, it is assumed that an individual eats 46 pounds of fish per year from Lake Erie directly offshore of the Fermi 2 plant. The tank may be released only after it is determined that no federal concentration limits are exceeded. As the tank is released, the contents of the tank are diluted by clean water in a ratio of approximately 400 gallons of clean water to one gallon of tank water for tanks located in the Radwaste Building basement. In the case of a Condensate Storage Tank release (a new release pathway approved in January 1994), this ratio is approximately 45 gallons of clean water to one gallon of tank water. The release is continuously monitored by radiation detectors. Fermi 2 has a water management policy which emphasizes the goal of minimizing or eliminating liquid releases, and work toward this goal continues. In 1993, there were six liquid releases. These releases contained 0 373 curies of tritium and 0.00148 curies of other radioactive material. Except for tritium, whose concentration remains fairly constant in liquid releases, the concentration of radioactive material in these liquid releases was small compared to average concentrations in releases from 1988 through 1991 (the period prior to the start of a release minimization effort). 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 radiation monitor which continuously extracts a sample from the stack effluent. Since any gaseous radioactive material is normally diluted by the building ventilation air flow, the stack concentrations are normally small. In fact, radioactive material other than naturd p roducts is not detected in most stack samples. All sample results are compared with federal dose rate limits to ensure they are not exceeded. If the amount of radioactivity in the effluent of any stack approaches a federal dose rate limit, an alarm will be activated in the Fermi 2 control room to alert operations personnel. After evaluating the situation, the operators may choose to order increased sampling, shut down building ventilation, or divert the effluent stream to a special gaseous treatment system so that federal limits are not exceeded.
2 1993 Annual Radioacthe Efiluent Release Report March 1994 In 1993, the amount of lodine-131 and particulate radionuclides with halflives greater than 8 days in gaseous releases was 0.00901 curies. This amount is comparable to levels seen in previous periods. The amount of fission and activation gases released in 1993 was 155 curies. This amount reflects increased fission and activation gas releases during the third and fourth quarters due to a small leak in a fuel assembly. The location of this assembly was identified and it was suppressed by inserting control rods around it. Estimated annual radiation doses due to effluents from Fermi 2 are included in this report. Noble gas doses to air at the site boundary in 1993 were 0.0221 mrad gamma and 0.0402 mrad beta. These doses are 0.22rk and 0.207c, respectively, of federal limits. Doses to maximally exposed individuals due to 1-131,1-133, tritium, and paniculates with halflives greater than 8 days were 0.0974 mrem (maximum organ gaseous),0.000476 mrem (total body liquid) and 0.000925 mrem (maximum organ liquid). These doses are 0.657c,0.016ck, and 0.00937c, respectively, of federal limits. 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 also complies with internal procedures. Shipment destinations are either licensed burial sites or intermediate processing facilities. Only quantities of radioactive waste shipped for disposal (as opposed to intermediate processing) are required to be listed in this repon. In 1993 Fermi 2 did not ship any radioactive waste for disposal due to the exclusion of Michigan licensees from the burial sites. 1 iii
1993 Annual Radioactive Effluent Release Report March 1994 TABLE OF CONTENTS PAGE
- 1. Introduction 1
- 2. Regulatory Limits 1
- 3. Average Energy 3
- 4. Measurements and Approximations of Total Activity 3
- 5. Abnormal Releases 7
- 6. Hatch Releases 8
- 7. Liquid Ef11uents Summary 9'
- 8. Gaseous Ef11uent Summary 11
- 9. Solid Waste and Irradiated Fuel Shipments 14
- 10. Radiological Impact on the Public 14
- 11. Radiation Instrumentation 17
- 12. Meteorological Data Summary 17
- 13. Changes to Dose Calculation and Environmental Monitoring Locations 18-
- 14. Changes to the Offsite Dose Calculation Manual (ODCM) 18
- 15. Major Changes to Radioactive Waste Systems 18
- 16. Liquid IIoldup Tanks Exceeding Limits 18 l
1 Appendix A: Meteorological Data Tables Appendix H: Revised Offsite Dose Calculation Manual iv
1993 Annual Radioactive Efiluent Release Report March 1994
- 1. INTRODUCTION The Detroit Edison Fermi 2 Nuclear Power Plant is designed and operated in a manner which strictly controls and monitors the release of radioactive material to the environment in accordance with Nuclear Regulatory Commission (NRC) and Detroit Edison Company requirements. This Annual Radioactive Effluent Release Report, for the January through December 1993 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:
- 1. Summation of the quantities of radioactive material (in the form of gases and liquids) released from the plant (Section 7 and 8)
- 2. Summation of quantities of radioactive material contained in solid waste packaged and shipped for off-site disposal (Section 9)
- 3. Changes to the Offsite Dose Calculation Manual (ODCM)(Section 14)
- 4. A list and description of any unplanned releases of radioactive materials to unrestricted areas (Section 5)
- 5. A list of any new locations for dose calculation or environmental monitoring, e.g. changes identified by the annual land use census (Section 13)
- 6. 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)
- 7. A description of events leading up to any liquid holdup tanks exceeding the limit of Technical Specification 3.11.1.4 (Section 16)
- 8. A description of any major changes to radioactive waste treatment systems (Section 15)
- 9. 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)
- 10. A summary of 1993 meteorological data (wind speed and wind direction for different stability classes) which was used in calculating gaseous dispersion factors (Section 12)
- 2. REGULATORY LIMITS The Nuclear Regulatory Commission limits on liquid and gaseous effluents are incorporated into the Fermi 2 Technical Specifications and 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 j ways to limit the overall impact on persons living near the plant. The limits are described in the following sections.
PageI
1993 Annual Radioactive Efiluent Release Report March 1994 A. Gaseous Efnuents
- 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:
- a. Noble gases Less than or equal to 500 mrem / year to the total body Less than or equal to 3000 mrem / year to the skin
- b. Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with halflives greater than 8 days Less than or equal to 1500 mrem / year to any organ.
- 2. Air dose due to noble gases released in gaseous efHuents to areas at and beyond the site boundary 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
-During any calendar quarter
- 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
- 3. Dose to a member of the public from Iodine-131, lodine-133, tritium, and all radionuclides in particulate form with halflives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited 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 Page 2
1993 Annual Radioactive Effluent Release Report
.%1 arch 1994, B. Liquid Emuents .;
- 1. 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, Colunm 2 for radionuclides -
l other than dissolved or entrained noble gases. For dissolved or entrained noble i gases, the concentration shall be limited to 2E-4 (.0002) microcuries/mi total ! activity. This limit is based on the Xe-135 air submersion dose limit converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP) Publication 2. ,
- 2. The dose or dose commitment to a member of the public from radioactive i
materials in liquid effluents released to unrestricted areas shall be limited to the values in the following sections.
- 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 l I
- 3. AVERAGE ENERGY The calculated site boundary dose rates for Fermi 2 are based on the identification of j individual isotopes and on the 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.
j 4. MEASUREMENTS ANI) APPROXIMATIONS OF TOTAL ACTIVITY As required by NRC Regulatory Guide 1.21. this section describes the rnethods 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). j
- 1 A. Gaseous Efiluents
- 1. Fission and Activation Gases l
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 exhaust points (the reactor building exhaust ! plenum). The fission and activation gases are quantified by gamma spectroscopy l analysis of periodic samples. l l l l Page 3
i 1993 Annual Radioactive Effluent Release Report March 1994 The values reported in Section 8 are the sums of all fission and activation gases quantified at all release points. Considering the inherent variability in radiation measurement, the variability in effluent stream composition, and the uncertainties in ef0uent flow rate and instrument calibration, Detroit Edison estimates that the uncertainty of the fission and activation gas total release figures is less than plus or minus 8 percent.
- 2. Radioiodines Samples are obtained from each of the seven plant radiation monitors, which continuously monitor the six ventilation exhaust points. The radiciodines 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 radiciodines. 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 radiciodines quantified at all release points. Considering the inherent variability in radiation measurements, the variability in efuuent stream composition, and the uncertainty in sample and ef0uent flow rates, Detroit Edison estimates that the uncertainty of the total radiciodine release figures is less than plus or minus 5 percent.
- 3. 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 analysis.
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 l rate of the ventilation system a rate of release can be determined. 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. I The values reported in Section 8 are the sums of all particulates quantified at all 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 Oow rates, Detroit Edison estimates that the uncertainty of the total particulate release figures is less than plus or minus 3 percent. Page 4
l 1993 Annual Radioactive ! Effluent Release Report I' March 1994
- 4. Tritium l 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 collected in the 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 l w.e is used to determine the concentration. From the flow rate of the ventilation i system a release rate can be determined. l l The values reported in Section 8 are the sums of all tritium releases quantified at all 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 uncertainty of total gaseous tritium release figures is less than j plus or minus 34 percent.
l 5. Gross Alpha The gaseous particulate 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 release points. Considering the inherent variability in radiation measurements, the variability in ! effluent stream composition, and the uncertainties in instrument calibration and f in sample and effluent flow rates, Detroit Edison estimates that the uncertainty l of the total gaseous gross alpha release figures is less than plus or minus 10 percent. l l II. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFS AR. I j l. Fission and activation products i ! 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 l establishes the rate at which the radioactive material can be discharged to the l environment. i l Page 5 1 l
1993 Annual Radioacthe Efilutnt Release Report March 1994 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 Section 7 are the pre-dilution waste volume (the total volume tank water 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). Considering the inherent variability in radiation measurement and the uncenainties in volume measurements and instrument calibration, Detroit Edison estimates that the uncertainty in total liquid fission and activation product release figures is less than plus or minus 5 percent.
- 2. 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 l 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 liquid releases. Considering the inherent variability in radiation measiirement and the uncertainties in volume measurement and instrument calibration, Detroit Edison estimates the uncertainty in total tritium release figures is less than plus or minus 15 percent.
- 3. 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 dissolved and entrained noble gases.
The values reported in Section 7 are the sums of all radioactive gases fotnd for all batch liquid releases. Page 6
1993 Annual Radioactise - Emuent Release Report Starch 1994 Considering the inherent variability in radiation measurement and the uncenainties in instrument calibration and volume measurements, Detroit Edison estim'ates that the uncertainty in total dissolved and entrained gas release figures is less than plus or minus 15 percent.
- 4. Gross Alpha Before the contents of each holding tank is discharged to the environment,i representative sample of the tank's contents is taken and retained. At the er of '
the calendar month a composite sample is made of all discharge samples tr :n 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 alpha 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 uncenainty in volume measurements and instrument calibration, Detroit Edison estimates that the uncertainty in total liquid gross alpha release figures is less than plus or minus 43 percent.
- 5. AllNORNIAL 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. On December 25,1993, a turbine incident caused a turbine building roof vent to open automatically. Fermi 2 has calculated the maximum amount of radioactivity which could have escaped through this vent during the December 25 event:
1131 2.79E+01 pCi , 1132 6.11 E+02 Ci 1-133 1.69E+02 Ci i 1134 1.50E+03 pCi 1135 4.33E+02 pCi , Kr-85m 8.86E+02 Ci l Kr-87 3.70E+03 pCi Kr-88 2.93E+03 pCi Xe-133 9.78E+02 Ci Xe-135 3.97E+03 pCi Xe 138 2.29E+04 Ci Xc-115m 7.44E+03 pCi The above amouru are included in the gaseous release totals shown in Section 8. Meteorologica! data corresponding to the time of this incident are not included in this report because a conservative UFSAR methodology was used to estimate dose resulting from this incident, and because these calculated releases are small fractions of average monthly gaseous releases. Page 7
4 1993 Annual Radioactive Efiluent Release Report '! March 1994 ! i
- 6. HATCil RELEASES As required by regulatory Guide 1.21, a summary of data for batch releases must be . ,
provided in this report. The following batch liquid releases from radwaste holding tanks to the circulating water decant line occurred between January 1,1993 and December 31, 1993 (all of these releases occurred during February and March 1993). , Number of releases: 6 Total time for all releases- '742 miautes , Alaximum time for a release: 464 minutes Average time for release: 457 minutes Minimum time for a release: 448 minutes
. 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 er s:andby 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. I s i I
- 1. \
l' age 8 i
1993 Annual Radioactive r . Ellluent Release Report i March 1994 i
. 7. LIQUID EFFLUENT
SUMMARY
A. Fission and Activation Products ' Ouarter 1 Ouarter 2 Ouarter 3 Quarter 4 '
- 1. Total Release except Tritium,
{ Gases,and Alpha (curies) 1.48E-03 0.00E+00 0.00E+00 . 0.00E+00 i
- 2. Average Diluted Concentration
- During Period (pCi/ml) 1.76E-10 0.00E+00 0.00E+00 0.00E+00
- 3. Maximum Percent of ODCM Control Limit for a Single Release (%) 1.04E-01 0.00E+00 0.00E+00 0.00E+00 H. Tritium l Ouarter 1 Ouarter 2 Ouarter 3 . Qyarter 4
- 1. Total Release (curies) 3.73E-01 0.00E+00 0.00E+00 0.00E+00
- 2. Average Diluted Concentration During Period (pCi/ml) 4.42E-08 0.00E+00 0.00E+00 0.00E+00 -l c
- 3. Percent of ODCM Control Limit (%) 7.27E-02 0.00E+00 0.00E+00 0.00E+00 i l
C. Dissolved and Entrained Gases Ouarter 1 Ouarter 2 Ouarter 3 Ouarter 4 )
- 1. Total Release (curies) 9.17E-06 0.00E+00 0.00E+00 0.00E+00 l l
- 2. Average Diluted Concentration l During Period ( Ci/ml) 1.09E-12 0.00E+00 0.00E+00 0.00E+00 1
- 3. Maximum Percent of ODCM Control Limit for a 0.00E+00 Single Release (%) 1.87E 04 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity (Note: N.D. = No activity detected)
Ouarter 1 Ouarter 2 Ouarter 3 OmEkr_4
- 1. Total Release (curies) N.D. 0.00E+00 0.00E+00 0.00E+00 E. Waste Volume Released Pre-Dilution (liters) 3.94E+05 0.00E+00 0.00E+00 0.00E+00 F. Waste Volume Released Post-Dilution (liters) 1.71 E+08 0.00E+00 0.00E+00 0.00E+00 i
G. Total Volume Dilution Discharged (liters) 8.43E+09 9.33E+09 1.20E+10 8.87E+09 Page 9 i L.__---_---____- .. - - . , . - . , . , , . .
1993 Annual Radioactive Effluent Release P.eport March 1994
- 11. Totals for Each Nuclide Released (curies)
(All are batch releases.) Nuclids Ouarter_1 Ouarter 2 Ouarter 3 Ouarter 4 11 3 3.73E-01 0.00E+fA) 0.00E+00 0.00E+00 Cr-51 1.56E-04 0.00E+00 0.00E+00 0.00E+00 Mn.54 3.51 E-04 0.00E+00 0.00E+00 0.00E+00 Co-58 6.13E-05 0.00E+00 0.00E+00 0.00E+00 Co-60 5.52E-04 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.40E-04 0.00E+00 0.00E+00 0.00E+00 Sr-89 1.89E-04 0.00E+00 0.00E+00 0.00E+00 Sh 125 1.87E-05 0.00E+00 0.00E+00 0.00E+00 Xe-133 9.17E-06 0.00E+00 0.00E+00 0.00E+00 Cs-134 *<4.2E-08 0.00E+00 0.00E+00 0.00E+00 Cs-137 8.29E-06 0.00E+00 0.00E+00 ' O.00E+00 Cc 141 *<3.7E-08 0.00E+00 0.00E+00 0.00E+00 Cc 144 *<1.5E-07 0.00E+00 0.00E+00 0.00E+00 Total 3.74E-01 0.00E+00 0.00E+00 - 0.00E+00
- Less than the Lower Limit of Detection (LLD),i.e. the maximum sensitivity of measurement, in units of microcuries per milliliter (pCi/ml).
l i l Page 10
.- ~ - . . _ . . --. - . -
1 l 1993 Annual Radioactive l Effluent Release Report i March 1994 ' )
- 8. GASEOUS EFFLUENT SUSINIARY (mixed mode releases **) l l
A. Fission and Activation Gases Ouarter i Ouarter 2 Ouarter 3 Ouarter 4 )
- 1. Total Release (curies) 2.76E+01 2.50E+01 5.61E+01 -4.66E+01 -
- 2. Average Release Rate for Period (pCi/sec) 3.55E+00 3.18E+00. - ' 7.06E+00 5.86E+00 ' '
B. Radiciodines - Ouarter 1 Ouarter 2 Ouarter 3 Ouarter 4 i
- 1. Total I-131 (curies) 5.36E-04 6.21E-04 3.82E-03 1.19E-3 '
1
- 2. Average Release Rate for Period ( Ci/sec) 6.89E-05 7.90E-05 4.81E-04 1.50E-4 l
C. Particulates Ouarter i Ouarter 2 Ouarter 3 Ouarter 4
- 1. Particulates with half-lives > 8 days (curies) 8.83E 05 1.16E-04 2.36E-03 2.76E-04
- 2. Average Release Rate for Period (pCi/sec) 1.14E-05 1.48E 05 2.97E-04 3.47E-05 ;
- 3. Gross Alpha l Radioactivity (curies) 1.03E-06 1.23E-06 1.81E-06 1.84E-06
( l l D. Tritium Ouarter 1 Ouarter 2 Ouarter 3 Ouarter 4
- 1. Total Release (curies) 2.36E+00 *<5.0E-08 *<5.0E-08 1.40E-03 i- 2. Average Release Rate
! for Period (pCi/sec) 3.03E-01 0.000E+00 0.00E+00 1.76E-04 l Less than the Lower Limit of Detection (LLD), i.e. the maximurn sensitivity of measurement in units of microcuries per milliliter (pCi/ml)
** As defined in NRC Regulatory Guide 1.11 I l Page 11 i
1993 Annual Radioactive - Efiluent Release Report March 1994
- 8. GASEOUS EFFLUENT SUhl51ARY (continued)
E. Particulates: Totals for Each Nuclide Released (curies) Nuclide Ouarter 1 Ouarter 2 Ouarter 3 - Ouarter 4 Cr-51. *<2.5 E-13 *<2.5 E-13 1.37E-03 8.18E-05 hin-54 *<4.8 E-14 '* <4.8 E-14 4.97E-04 *<4.8E-14 Co-58 *<l.4 E- 14 *<l.4E-14 1.41E-05 *<l.4E 14 Co-60 1.31 E-05 . l.64E-05 2.90E-04 2.82E 05 Zn-65 *<l .2 E-13 *<l.2E-13 8.94E-05 *<l .2 E- 13 Tc-99m 4.54E-04 2.62E-04 5.12E-04 1.45E-03 Ha 139 8.09E-02 9.24E-02 1.44E-01 1.89E-01 ! Ha-140 4.99E-05 7.14E-05 . 4.99E 05 1.23E-04 La 140 1.42E-04 1.20E-04 1.34E-04 2.28E-04 l Y-91m 1.25E-02 1.51E-02 1.81E-02 2.27E-02 Sr 91 6.68E-04 9.64E-04 9.98E 1.36E-03 Rb-88 *<6.4E-09 *<6.4E-09 1.55E-01 *<6.4 E-09 Rh-89 1.83E-02 5.00E-02 1.56E-01 1.48E-01 Cs-138 4.69E 5.30E 2.66E-01 3.47E-01 As-76 *<4.1 E-13 *<4.1 E 2.82E-04 *<4.1E-13 Ag-110m *<l.9 E-13 *< l .9 E-13 2.47E-06 *<l .9 E-13 Br-82 2.02E-05 1.42E-05 1.04E-05 2.91E Se-75 5.49E-06 *<3.0E-14 *<3.0E 14 - *<5.5 E-14 Sr-89 1.98E-05 2.65E-05 5.13E-05 4.26E-05 Sr-90 *<7.0E- 16 1.31E 06 6.66E-07 5.36E-07 , Cs-134 *<4.2 E-14 *<4.2 E- 14 *<4.2E 14 *<4.2 E-14 { Cs-137 *<5.0 E- 14 . *<5.0 E-14 *<5.0E-14 ~ *<5.0E- 14 Cc-141 *<3.9 E-14 *<3.9E-14 A3.E- e, e<3.vE-14 Ce-144 *<1.3 E-13 *<l.3E-13 *<l.3E 13 - *<l .3 E-13 Total 1.60E-01 2.12E-01 7.43E-01 7.10E-01
*Less than the Lower Limit of Detection (LLD) i.e. the maximum sensitivity of measurement in units of microcuries per milliliter (pCi/ml.)
4 b Page 12 _ - . _ , _ .._ 4 _ _ , , ,
i 1993 Annual Radioactive Efiluent Release Report March 1994
)
- 8. GASEOUS EFFLUENT
SUMMARY
(continued) l
~ F. Fission and Activation Gases: Summary for Each Nuclide Released (curies)
Quarter 1 Quarter 2 . Ouarter 3 Ouarter 4 ; Ar-41 1.14E+00 4.77E-01 *<l .9E-08 *<l.9E-08 ) Xe-131m *<3.8E-07 *<3.8E-07 1.25E-02 *<3.8E-07 Xe 133 *<4.6E-08 * <4.6E-08 1.75E+00 . 5.84E+00 Xe-133m *< l .3 E-07 *<1.3E-07 . *<l.3E-07' 8.68E-02 Xe-135 6.53E-01 *<l .5 E-08 2.45E+00 - 2.79E+00 Xe 135m 3.14E+00 2.85E+00 8.70E+00 4.69E+00 Xe-137 11.36E+01 1.51E+01 2.35E+01 - 1.97E+01 Xe 138 5.27E+00 ' 6.54E+00 1.54E+01 1.08E+01 - Kr 85 *<7.7E-06 *<7.7 E-06 8.21E-02 6.68E-02 Kr-85m 1.56E-01 *<l .2 E-08 . 6.37E-01 6.92E 01 Kr-87 *<6.0E-08 *<6.0E-08 2.26E+00 1.14E+00 I Kr-88 *<4.5E-08 *<4.5E-08 1.29E+00 - 8.31E-01 Kr-89 3.63E+00 - *<6.0E-06 *<6.0E-06 *<6.0E 06 1 Total 2.76E+01 2.50E+01 5.61 E+01. 4.66E+01 ' .j I i
'G. lodines: Summary for Each Nuclide Released (curies)'.
1 Ouarter 1 Ouarter 2 . Ouarter 3 Ouarter 4 1-131 5.36E-04 6.21E-04 3.82E-03 1.19E 1 1-132 1.33E-03 2.20E-03 1.83E-02 6.90E-03 I-133 2.89E-03 3.59E-03 9.88E-03 5.86E-03 1-134 *<l .5 E-I l 1.15E-03 2.34E-03 3.20E-03 1-135 1.19E-03 1.98E 03 ' t.54E-02 2.60E-03 I Total 5.95E-03 9.54E-03 4.97E-02 1.98E-02 1
*Less than the Lower Limit of Detection (LLD), i.e. the maximum sensitivity of measurement in units of microcuries per milliliter ( Ci/ml)
Page 13
. . . _ .~
l I. 1993 Annual Radioactive Efiluent Release Report March 1994
- 9. SOLID WASTE AND IRRADIATED FUEL SillPMENTS.
A'. Solid waste shipped offsite for burial or disposal (not irradiated fuel): No shipments in this reporting period B. Irradiated Fuel Shipments: No shipments in this reporting period.'
- 10. RADIOLOGICAL IMPACT ON TIIE PUllLIC ,
1 ( l A. Dose Due to Liould Ellluents As discussed in Section 6.5.1 of the Fermi 2 ODCM, compliance with ODCM i control 3.11.1.2, which limits dose to a member of the public to any organ and to the I 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. The individual organ and total body doses for 1993 to this hypothetical individual were calculated according to Section 6.5.1 of the ODCM and are listed below. Orfml 1993 Liould Efiluent Dose I Ilone 6.00 E-4 mrem l Liver 9.25 E-4 mrem Thyroid 1.56 E-5 mrem l Kidney 5.08 E-4 mrem Lung 4.30 E-5 mrem . GI-LLI 8.45 E-4 mrem Total body 4.76 E-4 mrem The highest organ dose,9.25 E-4 mrem to the liver, is 0.0093% of the ODCM I l Control 3.11.1.2 annual organ dose limit (10 mrem); the total body dose,4.76 E-4 i mrem, is 0.0169c' of the ODCM Control 3.11.1.2 annual total body dose limit (3 mrem). l H. Dose Due to Gascous Efiluents l I 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 I-131, I-133,113, and particulates with j half lives greater than 8 days in gaseous effluents to any organ of a member of the I 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, based on the Land Use Census, to have a garden. This child is assumed to eat food , from this garden, and to also be exposed by the inhalation and ground plane pathways. Page 14 i
1993 Annual Rxdioactive Efiluent Release Report March 1994 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. 1993 Gaseous E111uent Dose to Receptor with Ilichest Sinule Orean Dose Bone 6.36 E-3 mrem Liver 4.23 E-3 mrem Thyroid _9.74 E-2 mrem Kidney ' 4.33 E-3 mrem Lung 3.91 E-3 mrem GI-LLI 4.13 E-3 mrem Total body 4.39 E-3 mrem The highest single organ dose to the maximally exposed individual,9.74 E-2 mrem to the thyroid, is 0.63% of the ODCM Control 3.11.2.3 annual dose limit (15 mrem).- C. Dose due to Direct Radiation and compliance with 40CFR190 Title 40, Part 190 of the Code of Federal regulations requires that dose to an individual in an unrestricted area from the uranium fuel cycle be limite:d to 25 mrern/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 direct radiation. As discussed in Section 8.2 of the Fermi 2 ODCM, no other fuel cycle
' facilities contribute significantly to 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 1993 TLD readings which were consistently greater than the TLD readings at the control locations. Since other facilities and direct radiation did not contribute a significant portion of the 40 CFR 190 limits, and since the preceding sections of this report show compliance with the more restrictive requirements of 10CFR50 Appendix I, Fermi 2 was in compliance with 40CFR190 in 1993.
D. Dose to Members of the Public on Site due to Efiluents Members of the public may receive dose on site as visitors or as employes (non-radiation workers). As discussed in Section 8.0 of the Fermi 2 ODCM," visitors" to the Fenni 2 site may receive dose due to their activities within the site boundary. For purposes of this analysis, visitors are members of the public who spend time within the site boundary and who do not do work associated with the operation of Fermi 2. The ODCM considers two categories of visitors: persons ice fishing on Lake Erie and persons spending time in the Fermi 2 Visitors Center. Employes (non-radiation workers) may receive dose from various activities and at various locations (other than radiation areas) on site. Page 15
1993 Annual Radioactive j Effluent Release Report March 1994 i 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 the effluent exposure pathways which apply. A visitor is assumed to spend 240 hours per year ice fishing near the site and 4 hours per year at the Visitors Center; an employe is assumed to spend 2500 hours per year on site at various locations. Exposure by direct radiation from noble gases and by inhalation of radioactive particulates, iodines, and tritium are considered. In the case of ernployes onsite, ingestion of potable water is also considered. The doses given below do not include dose due to the pathways already l considered in Part A of this section, namely dose due to ingestion of water derived from the Monroe water intake and dose due to fish ingestion. Dose due to direct radiation from skyshine or plant structures is also not included. Based on these assumptions, the maximum dose in 1993 to a visic at the Visitors l Center is 1.18 E-5 mrem to total body and 1.99 E-5 mrem to the maximally exposed l organ (thyroid). The maximum dose in 1993 to an ice fisherman is 1.61 E-3 mrem to l the total body and 2.97 E-3 mrem to the maximally exposed organ (thyroid). The maximum dose in 1993 to an employe (non-radiation worker) on site is 4.15 E-2 to the total body and 6.63 E-2 to the maximally exposed organ (thyroid). l E. Population Dose Dose to the population within a fifty n ile radius of Fermi 2 due to 1993 gaseous and liquid effluents was calculated.
- For liquid effluents, the fish ingestion and drinking water pathways were considered.
l Since there is no significant commercial fishery in the Michigan waters of Lake Erie, the dose due to fish ingestion was assumed to be due to ingestion by the local population of the entire sport fish catch in these waters. In calculating dose dee to ; fish ingestion, parameters from Regulatory Guide 1.109_ were used, as was the USFAR dilution factor of 100. The dose due to water ingestion was determined by assuming that all residents served by the Momoe water intake drink at the average rate given by Regulatory Guide 1.109, and by using the UFSAR dilution factor to the intake of 77. The population total body dose due to drinking water was estimated to be 0.30 mrem, and the total body dose due to fish ingestion was estimated to be 0.44 mrem, for a total estimated population total body dose due to liquid effluents of 0.74 mrem. For gaseous effluents, the code MICROAIRDOS was used to estin' ate the population dose. Inputs to the code were 1993 gas tous release data, wind direction and wind speed frequencies for each stability class, population in each of 10 segments of each of 16 sectors, stack release specifications, etc. The estimated 1993 collective effective dose due to gaseous effluents is 220 mrem. The above gaseous and liquid doses are total doses to the entire population of over 5 million people living within 50 miles of Fermi 2; they are not individual doses. Page 16
1993 Annual Radioactive j Effluent Release Report March 1994 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 1993, gamma air I dose was 2.21 E-2 mrad and beta air' dose was 4.02 E-2 mrad. These doses represent 0.22% and 0.20% of the ODCM Control 3.11.2.2 gamma and beta annual air dose limits (10 mrem gamma and 20 mrem beta), respectively.
- 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. During 1993, the time specified in the action statements for these monitors was not l exceeded! !
However, on December 25,1993, the Liquid Radwaste Effluent monitor became inoperable when it was submerged as a result of a turbine incident which flooded the . Radwaste Building basement. This moniter remained submerged until February - 1 1994 due to the difficulty of removing water from the Radwaste Building basement. This monitor has since been repaired and is functioning properly, except that it does not as yet have annunciation in the Control Room and it does not have the capability to automatically terminate a release. Work is continuing to resolve these problems. : No liquid releases via the pathway associated with this monitor have taken place since the turbine incident.
- 12. METEOROLOGICAL DATA
SUMMARY
The meteorological monitoring system is described in the Fermi 2 UFSAR. In i accordance with Regulatory Guide 1.21, data recorded by that system is provided j here to' permit the NRC to assess the radiological impact of 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 l
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. 1 Page 17 i
- 1993 Annual Rtdioactive l Effluent Release Report l March 1994 l
l
- 13. CilANGES TO DOSE CALCULATION AND ENVIRONMENTAL
. MONITORING LOCATIONS During 1993, the following changes to TLD locations were made. The TLD designated T34 was moved from the east side to tiie west side of Port Creek Road, due to the removal of a utility pole. TLD locations T64 through T67 were added to the program: T64, T65, and T66 are located on the protected area fence, and T67 is located on the site boundary fence. These TLD locations were added to improve monitoring of those Detroit Edison employes who are now members of the public as defined by the revised 10 CFR Part 20 and Fermi 2 procedures. Also, the descriptions of the locations of T10 and T55 were changed, but not their actual locations.
l
- 14. CHANGES TO TIIE OFFSITE DOSE CALCULATION MANUAL (ODCM) in June 1993, sections 0.0,3.0,4.0, and 7.0 of the ODCM were revised, changing the required actions prior to venting the primary containment. In September 1993, all sections of the ODCM were revised to refer to the " Annual" effluent report, to include new dispersion and deposition factors, to fulfill commitments made to the NRC based on an NRC commissioned audit of the ODCM, to add a new gaseous release point (the auxiliary boiler stack), and to implement the revised 10 CFR Part
- 20. Due to a delay in approval of Technical Specification changes related to the 10 -
CFR 20 revision, these ODCM changes were not implemented until November 1993. Appendix B contains a copy of the entire ODCM as implemented in November 1993, together with supporting documentation for both 1993 revisions. Revision bars have been placed next to changes, and the month and year ofimplementation , are shown.
- 15. MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS l
During 1993, there were no major changes to the liquid, gaseous, or solid radioactive i waste treatment systems. However,in 1994 temporary modifications were installed l as a result of the December 1993 turbine incident. The purpose of these l modifications was to process water that had leaked into the plant during the December incident. ;
- 16. LIQUID llOLDUP 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 tritium and dissolved or entrained noble gases. During this reporting period, January through December of 1993, this activity limit for such tanks was not l exceeded. i I l. END OF TEXT Page 18 l l'
1993 Annual Radioactive Effluent Release Report Llamh 1994 APPENDIX A: METEROLOGICAL DATA TAhlES I l I l l l l l
i i l r t l t i
- I
! } f JOINT FREQUENCY DISTRIBUTION (JFD) AT THE 10-METER LEVEL i i i 1993 i 1 l t t 8 ; k 1 f i I a HALLIBURTON NUS
HALLIBURTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTMENT PAGE 1 PROGRAM: JFD VER$10N: PC-1.2 PRINTOUT OF INPUT CONTROL DATA TITLE: DECO FERM12 JFD AT 10-METERS FOR 1993 BEGIN DATE: 92 12 31 24 END DATE: 93 12 31 23 OPTION TO PRINT MONTHLY JFDS: NO OPTION TO PRINT SEASONAL JFDS: NO OPTION TO PRINT STA81LITY BY HOUR OF DAY: NO OPTION TO PLACE JFD IN FILE FORMATTED FOR PAVAM/X00000: 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 MEASUREMENTS BASED ON: WIND SPEED MEASURED AT 10.0 METERS IN MPH 8AD WIND SPEED DATA CODED: 999.90 WIND SPEED TH8ESHOLD: .75 MPH WIND DIRECTION MEASURED AT 10.0 METER 3 BAD WIND DIRECTION DATA CODED: 999.0 STABILITY BASED ON 1=A 2=8....,7=G BAD STABILITY Cr'OED: 9.0 BACK-UP MEASUREMENTS LTSED ON: NO BACKUP WIND
- PEED MEASUREMENTS NO BACKUP WIND OIRECTION MEASUREMENTS NO BACKUP STA81LITY MEASUREMENTS WIND SPEED HEIGHT TO BE USED FOR JFD: 10.00 METERS CONVERSION FACTOR TO CONVERT $1GMA RANGE TO SIGMA THETA: 6.0 FORMAT TO READ INPUT DATA: (4I2,F5.1.F3.0,T27,F1.0,T55,A6,711,A3,A3,T27,A1)
FIRST DAT4 RECORD READ: FERM12 92 12 31 24 9.4 288.0 4.0 2 ____.____________._m. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _______z_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _
HALLI90RTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTMENT PAGE 2 PROGRAM: JFD VER$!ON: PC-1.2 DECO FERMI 2 JFD AT 10-METERS FOR 1993 SITE IDENTIFIER: FERMI 2 DATA PERIOD ENJm NED: 12/31/92 - 12/31/93
*** ANNUAL ***
STA8tLITY CLASS A STABILITY BASED ON 1=A,2=8,...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 10.00 METERS SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW W NNW . TOTAL CALM 0
.76- 2.50 0 0 1 0 0 -0 0 0 1 0 0 0 0 1 0 0 3 2.51- 4.50 1 1 3 2 5 2 2 1 1 0 1 3 7 4 2 0 35 4.51- 6.50 0 3 5 9 9 15 13 7 20 0 1 5 7 7 5 6 115 6.51- 8.50 0 2 to 19 12 22 29 8 10 7 2 10 29 20 5 2 187 8.51-11.50 3 7 7 11 17 16 1 1 3 5 4 4 13 28 15 ' 9 144 11.51-14.50 5 2 6 1 8 1 0 0 2 3 8 0 6 14 0 2 58 14.51-18.50 7 1 0 1 4 0 0 'O O 1 0 0 0 0 0 3 17 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
>39.50 0 0 0 -0 0 0 0 0- 0 0 0 0 0 0 0 0 0 TOTAL 16 16 35 43 55 56 45 17 37 16 - 16 22 62 74 27 22 559 STABILITY CLASS 8 STABILITY BASED ON 1=A,2=8,...,7=G WIND MEASURED AT: 10.0 METERS WINO THRESHOLD AT: .75 MPR JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 10.00 METERS SPEED ~
(MPH) N NME NE 'ENE E ESE SE - SSE S SSW SW WSW W WNW W NNW TOTAL CALM 1
.76- 2.50 1 0 1 0 0 0 0 0 0 0 1 1 1 1 1 0 7 2.51- 4.50 3 1 1 3 1 2 3 2 2 1 2 1 9 8 4 4 47 4.51- 6.50 .2 4 3 4 2 6 16 6 13 4 5 15 15 11 .16 8 130 6.51- 8.50 0 3 8 6 6 10 8 6 19 11 12 16 19 16 11 to 161 8.51-11.50 5 6 3 3 6 8 4 0 7 11 16 11 12 15 2 to 119 11.51-14.50 7 1 9 1 7 0 0 0 2 .6 5 4 6 5 0- 3 56 14.51-18.50 0 1 1 1 1 0 0 0 0 2 0 0 1 0 0 0 7 18.51-23.50 0 1 0 0 0 0 0 .0 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
>39.50 0 0 0 0 0 0 0 0 'O O O O O 0 0 0 0 TOTAL 18 17 26 18 23 26 - 31 14 43 35 41 48 63 .56 34 35 529
HALLISURTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTMENT PAGE 3 PROGRAM: JFD VERSION: PC-1.2 DECO FERMt2 JFD AT 10-METERS FOR 1993 SITE IDENTIFIER: FERMI 2 DATA PERIOD EKAMINED: 12/31/92 - 12/31/93
*** ANNUAL ***
STA0!LITY CLASS C STABILITY BASED ON 1=A,2=9....,7=G WIND MEASURED AT: 10.0 METERS WINO THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 10.00 METERS SPEED (MPM) N NME NE ENE E ESE SE SSE $ SSW SW WSW W WWW WW WWW TOTAL CALM 1
.76- 2.50 1 0 1 0 0 0 0 0 2 0 2 0 0 4 1 1 12 2.51 4.50 6 6 3 1 1 7 3 3 5 7 4 5 16 12 6 7 92 4.51- 6.50 9 4 11 5 3 15 19 9' 9 16 17 20 29 - 17 12 15 210 6.51- 8.50 9 6 6 4 9 13 11 20 12 15 18 21 22 21 16 15 218 8.51-11.50 7 3 8 9 15 14 7 5 16 21 39 14 to 16 7 16 207 11.51-14.50 13 7 9 5 6 4 3 1 0 11 10 4 9 3 0 58 14.51-18.50 3 2 2 4 2 0 0 1 1 5 2 0 3 0 0 0 25 18.51-23.50 2 2 1 1 0 0 0 0 0 1 0 0 0 0 0 0 7 23.51-30.50 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 30.51-39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 50 31 41 29 36 53 43 39 45 76 92 64 89 73 42 57 861 STABILITT CLASS D STABILITY BASED ON 1=A,2=8,...,7=G WIND MEASURED AT: 10.0 METERS WIND TNRESMOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 10.00 METERS SPEED (MPM) N NME NE ENE E ESE SE SSE S SSW SW WSW W -WWW WW NWW TOTAL
, CALM 0 . 76- 2.50 6 6 3 3 1 3 5 4 4 5 6 15 11 9 7 5 93 -t 2.51* 4.50 17 18 20 9 9 19 19 19 29 20 34 76 69 38 35 28 459 4.51- 6.50 31 41 58 .6 31 40 62 30 55 47 74 97 81 49 52 47 833 , 6.51- 8.50 37 36 104 64 42 74 4* . 28 63 65 112 55 61 46 36 71 935 8.51-11.50- 43 37 95 67 69 59 50 26 67 104 144 53 41 43 - 20 41 959 11.51-14.50 18 29 45 17 25 29 18 6 22 72 64 16 6 19 14 21 421 4 14.51-18.50 5 11 24 11 16 7 3 5 5 39 - 27 5 2 2 1 9 172 18.51-23.50 4 0 2 0 2 0 0 0 -0 0 0 0 0 0 0 3 11 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 'O 0' 0 0 0 0 0
>39.50 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 0
- TOTAL 161 178 351 209 195 231 198 118 245 352 461 317 271 206 165 225 3583
_ . _ _ - - - ..- . _ . _ _ _ - _ _ _ . _ _ - _ _ _ _ - - - - _ = _
}
NALLIOURTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTNENT PAGE 4 PROGRAM: JFD VERSION: PC-1.2 i DECO FERMI 2 JFD AT 10-METERS FOR 1993 SITE IDENTIFIER: FERNI2 DATA PERIOD EXAMINED: 12/31/92 - 12/31/93
*** ANNUAL ***
STAOILITY CLASS E STABILITY BASED ON 1=A,2=B,...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESNOLD AT: .75 MPN JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 10.00 METERS SPEED (MPN) N NNE WE ENE E ESE SE SSE S SSW - SW WSW W WWW NW wwW TOTAL CALM 7
.76- 2.50 12 9 3 4 6 4 12 to 7 8 19 36 22 34 18 11 215 2.51- 4.50 30 25 20 9 8 11 16 19 46 35 66 89 80 81 54 49 640 4.51- 6.50 25 20 25 23 28 23 19 24 54 52 82 46 52 37 19 23 552 4 6.51- 8.50 12 7 13 17 11 26 22 20 59 57 33 to 8 8 5 6 314 - 8.51-11.50 8 0 2 6 15 15 9 13 51 53 15 3 5 9 1 2 207 11.51-14.50 0 0 3 4 0 1 7 5 14 - 38 12 2 0 0 0 0 86 14.51-18.50 0 0 0 0 0 1 3 1 1 12 7 0 0 0 0 0 25
- ' ' 0 18.51 23.50 0 0 0 0 'O O O O 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 j
^
30.51-39.50 0 0 0 0 0 0 0 0 0 0 0 0' 0 0 0 0 0
>39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 87 61 66 63 68 81 88 92 234 255 234 186 167 169 97 91 2046 STABILITY CLASS F STABILITY BASED ON 1=A,2=s,...,7=G WIND MEASURED AT: 10.0 METERS WIND TWRESNOLD AT: .75 MPN J0lNT FREQUENCY DISTRIOUTION OF WIND SPEED AND DIRECTION IN NOURS AT 10.00 METERS.
- SPEED (MPN) N NNE NE ENE E ESE LE SSE S SSW SW WSW W WNW NW NNW TOTAL -
CALM 11
.76- 2.50 5 1 3 2 3 0 2 6 12 16 17 16 24 29 17 5 158~
2.51- 4.50 8 4 2 2 6 8 3 6 7 21 35 32 36 66 41 25 302 4.51- 6.50 4 0 0 0 4 8 6 11 5 17 7 1 0 11 3 9 86
; 6.51- 8.50 5 1 2 1 4 11 11 5 5 to 0 0 0 0 0 1 56 8.51-11.50 0 0 0 0 0 4 15 8 3 10 . 0- 0 0 0 0 0 40 11.51-14.50 0 0 0 0 1 0 1 1 1 9 0 0 0 0 0 0 13
, 14.51-18.50 0 0 0 0 0 0 0 1 0 2 0 0. 0 0 0 0 3 18.51-23.50' 0 0 0 0 0 0 0 0 0 0 0 0 -0 0 0 0 0 i 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
>39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 22 6 7 5 18 31 38 38 -33 85 59 49 60 106 61 EO 669 1
4 .
, - n... - . - - .
MALLIBURTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTMENT PAGE 5 PROGRAM: JFD VERSION: PC-1.2 DECO FERMl2 JFD AT 10-METERS FOR 1993 SITE IDENTIFIER: FERMI 2 DATA PERIOD EXAMINED: 12/31/92 - 12/31/93 ee aggggt - **e STA81LITY CLASS G STABILITY BASED ON 1=A,2=B ...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 10.00 NETERS SPEED (MPH) N NME NE ENE E ESE SE SSE S SSW SW WSW W WWW NW NNW TOTAL CALM 3
.76- 2.50 1 1 0 0 0 0 0 1 1 7 0 6 13 15 9 5 59 2.51- 4.50 3 0 0 0 0 2 1 1 1 8 0 5 12 32 26 15 106 4.51- 6.50 0 0 0 1 3 2 1 2 0 1 0 0 1 8 0 1 20 6.51- 8.50 0 0 0 0 0 3 2 1 1 0 0 0 0 0 0 1 8 8.51-11.50 0 0 0 0 1 1 3 2 0 1 0 0 0 0 0 1 9 11.51-14.50 0 0 0 0 0 0 3 0 0 0 0 0 0 0 0 0 3 14.51-18.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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
>39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4 1 0 1 4 8 to 7 3 17 0 11 26 55 35 23 208 STABILITY CLASS ALL STABILITY BASED ON 1=A,2=B,...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN MOURS AT 10.00 METERS SPEED (MPM) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NU NNW TOTAL CALM 23
.76- 2.50 26 17 12 9 10 7 19 21 27 36 45 74 71 93 53 27 547 l 2.51- 4.50 68 55 49 26 30 $1 47 51 93 92- 142 211 229 241 168 128 1681 s 4.51- 6.50 71 72 105 80 80 109 136 89 156 137 186 .184 185 140 107 109 1946 6.51- 8.50 63 55 143 111 84 159 124 88 169 165 177 112 139 111 73 106 1879 8.51-11.50 66 53 115 % 123 117 89 55 147 205; 218 85 81 til 45 79 1685 11.51-14.50 43 39 72 28 47 35 32 13 41 139 99 26 . 27 41 14 29 725 6 14.51-18.50 15 15 27 17 23 3 6 8 7 61 36 5 6 2 1 12 249 18.51-23.50 6 3 3 1 2 0 0 0 0 1 0 0 0 0 0 3 19 23.51-30.50 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 30.51-39.50 0 0 0 0 0 0 0 0 '0 0 0 0 0 0 0 0 0
>39.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 358 310 526 368 399 486 453 325 640 836 903 697 738 739 461 493 8755
HALLIBURTON NUS CORPORATION AIR / RADIOLOGICAL PROGRAMS DEPARTMENT PAGE 6 PROGRAM: JFD VERSION: PC-1.2 DECO FERMI 2 JFD AT 10-METERS FOR 1993 SITE IDENTIFIER: FERMI 2 DATA PERIOD EXAMINED: 12/31/92 - 12/31/93-
*** ANNUAL ***
STABILITY SASED ON 1=A,2=8,...,7=G WIND MEASURED AT: 10.0 METERS WIND THRESHOLD AT: .75 MPH TOTAL NUMBER OF OBSERVATIONS:- 8760 TOTAL NUMBER OF VALID OBSERVATIONS: 8755 TOTAL NUMBER OF MISSING OBSERVATIONS: 5 , PERCENT DATA RECOVERY FOR THIS PERIOD: 99.9 % MEAN WIND SPEED FOR THIS PERIOD: 7.1 MPH TOTAL NUMBER OF OBSERVATIONS WITH SACKUP DATA: O PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 6.38 6.04 9.83 44.35 23.37 7.64 2.38 DISTRIBUTION OF WINO DIRECTION VS STABILITY
'8 SV W N WNE ENE E ESE SE SSE S SSW WSW WWW NW NWW CALM A 16 16 35 43 55 56 45 17 37 16 16 22 ~62 74 27 22 0 8 18 17 26 18 23 26 31 14 43 35 41 48 63 56 34 35. 1 C 50 31 41 29 36 53 43 39 45 76 92 64 89 73 42 57 1 D 161 178 351 209 195 231 198 118 245 352 461 317 271 206 165 225 0 E 87 61 66 63 68 81 88 92 234 255 234 186 167 169 97 91 7 F 22 6 7 5 18 31 38 38 33 85 59 49 60 106 61 40 11 G 4 1 0 1 4 8 10 7 3 17 0 11 26 55 35 23 3 TOTAL 358 310 526 368 399 486 453 325 640 836 903 697 738 73 9 '461 493 23
1993 Annual Radioactive Effluent Release Report March 1994 APPENDIX B: REVISED OFFSITE DOSE CALCUALTION MANUAL l 1
- . . . -. . . - ~ . . .. -- - ,.
LICENSING CHANGE REQUEST LCR l l3l - l O 10 l '7 l - I OI D l At Revision O Page / of -4 7 P* ** * * * * * * * * * * * * * * * *
- P A RT 1 : UFSAR, PLAN, OR PROGRAM REVISION [ ]NA *********************" T 4 9 C OSL C(jf +1 JhrY B) Sectyn(s)k,W rAttTable (s), Figure (s), etc. Affecto.O . 3. 0 -: and . O, ad '7,6 .
' [L a,4on riw/,rt*711enY 'for CzmOHC >* r/mn/
C) Reayln fbr ChangeC@t Ta MnfW Nierfo*~ hM& M /ot d C & n V. f I MTWe / $ RW OHF %dwaf ftH& t% frude *Z 0-/. d) Reference and Source Documents (ide'ntify)
~
EDP Tech Spec PDC Procedure 2.J.4 o6 ~7W 000, /2JY, coo, O / i
/
ABN SE (Attached) i #49 POT 2.
~
DER PE (Attached) ves Test Drawing No. / Effectiveness Review (Attached) [%Ves [ ]No Other (/Ff4/2 6.2 I. 2. ,1,10, 6. ?_ ,f". 2. I" II.I. 2,V , hM ll A , T,5/,2, 9.4 f Drawings, Design Calculaiions, Correspondence, etc. ff,/, QumfM/%d/r/m Ew.(, 'f ?-og P****************************PART2: OPERATING LICENSE CHAN(IES b/.lidA * * * * * * * * * * * ** * * * * * * * * *
- l A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan B) Section(s), Table (s), Figure (s), etc. Affected C) Reference and Source Documents Attached [ ] NA [ ] Other [ ] Marked-up pages [ ] Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromental Impact / Categorical Exclusion [ ] Justification D) is change to UFSAR and/or approved plans / programs required? , [ ] Yes [ ] No LCR No(s) E) Priority [ ]NA NRC approval required by (date): Explanation - F) NRC Letter No. l G) Amendment No. , I l * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- P A RT 3 : APPROVALS *************************************************l m 4 Date SON B) Technicht'Rx t #
k u t al - p , m m s, Date bt ~3S C) Nuclear Ge e ion Unit He " l s Gr I?ll.E Date 6.- ?'t 3 D) General Dire ~ctor', Nuclear f4gipeering [dNA [ ]Att Management (Reyfew Sheet Date E) Plant Manager c, [ ]NA [ ]Att tw en eview Sheet Date ' F) Other Date
/ G) Director, Nuclear Licensing rdO [ ]Att Management Review Sheet [M Gate ((/ fj H) OSRO (Fire Protection, RERP, PCP, ODCM, SEP, TS)
[ ]NA [ lAtt Management Review Sheet /[,/27C/[m ' ' Date'/6//8M I) NSRG (OL, TS, EPP) [)(lNA [ lAtt Management Review Sheet Date Form FIP-RA2-01 Att 1 P1/1 102891 DTC: [ ] TDLCR File: [ ] 1701.03 : [ ] TCICR [ ] 1735 [ ] li ll's I.O l l 1 '1',1s i
l
. EFFECTIVENESS REVIEW Reference LCR l l)l- l0 o i9 i _
i i O i p iM i , Revision o Page 7 of I l*******************************************PART1: UFSAR D9N A * * * * * * * * * * * * * * * *
- 49*******l ,
A) Quality Assurance Program . [ ]Yes [ ]No [ ]NA Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix 0 or reduce UFSAR program commitments previously accepted by the NRC? Provide the basis for each change on Attachment 2. Page 2. ' B) Fire Protection Program [ ]Yes [ ]No [ ]NA Does the change (s) adversely affect the ability to achieve and maintain I safe shutdown in the event of a fire? ! Provide the basis for each change on Attachment 2. Page 2. , l***** PART 2: RADIOLOGICAL EMERGENCY RESPONSE PREPAREDNES PLAN (K] N A * * * * * * * * * * * * * * * *
- l A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the RERP Plan?
-[ ] Yes [ ] No Does the RERP Plan, as changed, cease to meet the standards of ;
i 10CFR50.47(b) and 10CFR50 Appendix E? l Provide the basis for each change on Attachment 2; Page 2. ! l*****************************PART3: SECURITY PLANS h(j N A * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- l A) Document B) [ ]Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR73?
I [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories ; of Informational Background, Generic Planning Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan ' prepared pursuant to 10CFR50.34(d) or 10CFR73? Provide the basis for each change on Attachment 2. Page 2. , l * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- P A RT 4 : PROCESS CONTROL PROGRAM [X 1 N # * * * * * * * * * * * * * * * * * * * * * * *
- l A) [ ]Yes [ ] No Does the change (s) reduce the overall confbrmance of the solidified l waste product to existing requirements of Federal, State, or other applicable regulations? (Technical Specification 6.13)
Provide the basis for each change on Attachment 2, Page 2. l l***************************************PART5: ODCM [ ]NA*****************************************l A) [ }Yes No Does the change (s) reduce the level of radioactive effluent control required by 10CFR20.106,40CFR Part 190,10CFR50.36a, and Appendix 1 to 10CFR Part 507 (Technical Specification 6.14) - [ ] Yes [ No Does the change (s) adversely impact the accuracy or reliability of. l effluent, dose, or setpoint calculations? (Technical Specifications 6.14) ! Provide the basis for each change on Attachment 2. Page 2. l l * * * * * * * * * * * * * * * * * * * * * * * * * * * *J P A RT 6 : A P P RO V A L 9 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- l
, Date d D B) Technical Ex r
.h Date (o-3-93 C) Quality Ass rince (Security Plans, OA Program)
Date D) OSRO (Fire Protection Program, RERP Plan, Security Plans, PCP, ODCM) i h& M Date //$/N Form FIP-RA2-01 Att 2 P1/2 060992 DTC: [ ] TDLCR File: [ ] 1701.03 [ ] TCLCR [ ] 1735 [ ] TMPLAN [ ] 1715.03 i
' i j EFFECTIVENESS REVIEW DOCUMENTATION 2 Reference LCR l l3 l- l01019l- l0 Didi I Revision O Page W" f -F 7
~'~"
**""8%;Ic Dase Glculaha- Maruis \
Listad below is each change by section and page; the reason for the change; and the basis for
-concluding that the revised plan or program continues tc satisfy the criteria for that plan or program.
Attcch all appropriate analyses or evaluations justifying the change (s), S:ctinn/Page Change l Basis 0.0/ I kdsf Wofesch sedmLl tEacl 00a*1 seeku il revisim numbers and 'Sledin R M <sa aawvaI dA remt'e Acvenfasd was i k msed sea,rk/v . ' . , 7
- 3. o/W a>J Slininde reautremed Er Oadtwrs<vcedre 23.Vo(> .
l%Ie 4. us.2.I.t-n c-shns du ,,a,u uill ~ le M G Q 1
$0f U lH1I Wf 4 fr Of t f?tAl MA i fl \
~
o110ft- I A7drGL 0 l E, 3. 1 ML NfM4 Tkaf 'n i Atef s' //11 1ZitMt r rots /Y /Ycer' Wk , ra,aL o,in d d) Yfis subs &Mer & nd #
&w'M nd durim s~ . r L _'
purc 6L. I 16 ttry N%jpg Sasstj* <t;c,
/ fW 4f r> f(AC1A 0 '2f 0
"'?tVMI lY incxWar of (2ffhC4h41 9t @ c fe O ftfC K fu sbon cn$ht. he dvvell is vtormflu oveu wA r ckonoc/ibt a h PikG. Drobc0 5 Y
~lL 'n wa disim .
IPNVkv] Sarms 4 14& fill V j f I f d fMV. fV / l l Form FIP-RA2-01 Att 2 P2/2 060992 DTC: [ ] TDLCR File: [ ] 1701.03 [ ] TCLCR [ ] 1735 1 ] TMPLAN [ ] 1715.03
EFFECTIVENESS REVIEW DOCUMENTATION Reference t,CR l l3l- l OlO l l- l O] l Revision (> Page f f [ 7 , 0 3l < 0]< Cufti l'c/M tt+10d Listad below is each change by section and page; the reason for the change; and the basis for
- cencluding that-the revised plan or program continues to satisfy the criteria for that plan or prograrn.
Attich all appropriate analyses or evaluations justifying the change (s). l S;ctirn/Page l Change Basis
$s0h1 -
hin L AJW' CDht'l/Y4
'bfa Y /t/$M4,.0 (3.1l2.2) .>m N /,2,.3 s,ue W- rlinton,L4lxmNlAesa l i y we h a e b l/e d t u wo& T since 8-e dv veil u w L.sa.,aa '
($ 0 )l tic lt RW 11ob belncL. ' 6Af&27 d,
/
, 3.0/32- Sbminak rwhenau'h Osmkmc rece$n25AOL
-(4WE'6> se,wk s4 A ad drw Jil n;/de' fin ~
( Y. u, z e i , v M #' abiuo " # ' A cs%LsLt ect krmd YII.2.h,3) nmthe wi//be wriSsfud 4LrnaAm,ondL srior b vendnf Ah
'vada ,,s L%
WimistafvN i? Y t Am/de 55'/YCeil/fk. O, l ff S- V !tL A1 95t nst r WiIl nss/M VW cfh k{ l Y'R ptt , Meef Mbak iS 0 0+tns/ r K13 s,S G TJ Form FIP-RA2-01 Att 2 P2/2 060992 SPla d. ' DTC: [ ] TDLCR File: [ ] 1701.03 [ ] TCLCR !] 1735 [ ] TMPLAN [ ] 1715.03 L____________________ _
/ EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR l 171- l Ol hl 9 l- l Ol h l Revision O Page.I~of 7 0 $l < 05< W ~
ffff/d l Listed below is each change by section and page; the reason for the change; and the basis for
-ccncluding that the revised plan or program continues to satisfy the criteria for that plan or program.
Attach all appropriate analyses or evaluations justifying the change (s). S:ction/Page Change I Sesis 0 A+ssc Slet ik di d L -ft WM) (pts (JkW l3.n. 2 f) 1; % cJiwd as M 6a4 1 d "14ett"ti % ~ e L J It n G . C lHrH l S.O 911id DViu e] ofe?22h///h J&MM 4 9 / r ". revi,emdade & N.S's ' V6' 1%_ GS fuC df /fVr9/ V
/ f :
0 $ zh rCGAsiFe71 e fY >1 arf i (Y'It.2.?,2) andm mbr& ed 042(NAr dr % bc: nkte, l/dt hC MY I CAM t 'fc
# Vit i i k Wi 0 I CW Y >
[] /0? pf %)V% , {f OLO , fgtsffs $ Mgo/Nygr MVek b oNvl0v3 v ksiiiumd r 10 /) b . k h MA/MM hcx(*grubcir110fnic M. h z.7r) ind1% 0fd /d w w & L&'m o/e, Ol1C. Pts % ibr I f/MC SVG/hC, , il VrlM _ NW - R Au }4 K M1SV& 41 1 >&tn1/ n /1S o f</t . Form FIP-RA2-01 Att 2 P2/2 060992 DTC: [ ] TOLCR File: [ ] 1701.03 [ ] TCLCR [ ] 1735 [ ] TMPLAN [ ] 1715.03 l l
. -. .. . . - - ~ . - .- .. . .-
/#
! EFFECTIVENESS REVIEW DOCUMENTATION neforence LCR 13131- l CIO 19 l- i O Didi I
RevisionO Page [of 7
"**"~"'o#r,A Dor < CA/A Aber i _
Listed below is each change by section and page; the reason for the change; and tne Desis for
-concluding that the revised plan or program continues to satisfy the criteria for that plan or program.
Attach all appropriate analyses or evaluations justifying the change (s). Soction/Page Change Basis Y.D /{ . (vbbkh prin1grv Y< OrVJ 'nwv he DN. 'n. 2. 7) hAken/" G ~Jsessr<M L d AvleJ/- N
~
"AweA " ju venNsue
.llr!n Jb/w1ef ' '
smro]efskdbaredis ntN indus/VL . l.0/2-- kevdeh6fDamc; ' ee-r/tl/idtd MD] . (% L /) b re(Ac/ lw d d Shfe '/. It,2.l,2-( ag Sec[es. Y.1I,2.81.. keui]L JWd Anacle frdmcec/bar Mcu/n
-6WWlG I"l2L JL Y f*1f v l nna %lmaA A 4 lexfr 4k f /S f RVL L4)UYu t fek (KCefY .
aka s,s anL Ahfv ~4ae ads O.ETW , /Y 11 Viry Y C v 611'kr Al[CS GPC Hi k fhtf 91oLJ 3Jh$ < ht /T C Uf++%khc '
/ 7'M C 0 VI [M1C W.
re/egfef. / f I Form FIP-RA2-01 Att 2 P2/2 060992 DTC: [ ] TDLCR File: [ ] 1701.03 [ ] TCLCR [ ] 1735 [ } TMPLAN [ ] 1715.03
.r.~, .,,t .m.9 , n.r--emy v.-- - +yW..
J
! EFFECTIVENESS REVIEW DOCUMENTATION lOlp Mi Reference LCR l l l-l O Ol}l-l Revision Y age P ~7of ~/
]4 OL cht A11(A Listed below is each change by section and page; the reason for the change; and the basis for
-concluding that the revised plan or program continues to satisfy the criteria for that plan or program.
Attach all appropriate analyses or evaluations justifying the change (s). S:ction/Page Change Basis 1.0K ck wada 4 % 7. 2.t bas u . ( 9.4. O ' ekfu/e reduww fr releeim/k c4(dm aierfs esd vedbe, v ~
- 7. o /, Ssa,c ar aG che. vi &c& /s,4 (7.
V. D Ass nwiumJ T L Arv A r A
%4 i>& aas a # & b & a /~1c cm41~vr nleer 6 atd'& 6edauf 1L nard abcL '6ek cAuns awf w
aEd lafc4 rela res. 1 2 o/7 , AA/' dLJ D Sec 7.2.1 ksu. Jadi l'i.iI,'7.VL) ' n k si r d s d .c A , J cAu/a6 is aAo " ~ ead s e ra'4
~
a lu ~ ,,, w w L wsn,v . / ack bcA fee bea, ea<e&d. Ana fau/Ast~4eraem s Ev'&dksfo 14 he PA rol And 7 0/3J Ads osrf & Heef ek Ca%s 4 uFJAG (%7.o-/) ,, sac 4 arf 9-s/93aoii u. 7, z . 2. ,7. I Form f!P-RA2-01 Att 2 P2'/2 060992 ' DTC: i]TDLCR File: [ ] 1701.03 [ ] TCLCR [ ] 1735 [ ] TMPLAN [ ] 1715.03
2 1 PRELIMINARY EVALUATION i
- ..................................................................................................M.....by Pg 1 of
.. spy
; l PART 1: DESCRIPTION OF CHANGE (Preparer) l A) Decu ent identification B) Revision if C) PlS Number i Ob 3O s Y.O,10 Approved O .A#/
D) D3scription of'Changel W ngl%2
,)(1'yflWMIMinedl
&s-ky db "
! t/ 0 l lHU12!1 . f 2
&nt WV h 4%1
}l N l; S, Y .
~ l PART 2: PRELIMINARY EVALUATION (Preparer, Approver) l A) Rsview of Commitments [ } N/A. Meets Exemption Criteria 6.1.4.5. Approved by: l V) No commitments [ ] Commitments exist (list) l 4 [ ] Commitments met - none negated [ ] Commitments need changing (explain) I j [ ] Plant Safety and/or Licensing have been contacted to make changes 4 C) Impact on License, Plans, or Programs
- o change to the Operating License (including the Technical Specifications, the Environmental
(,-l J Protection Plan, and the Technical Specification Bases), the Core Operating Limits Report (COLR), , the UFSAR, Fire Protection Program, Quality Assurance Program, Radiological Emergency Response Preparedness Plan, Physical Security Plan, Safeguards Contingency Plan, Security Personnel
- Training and Qualification Plan, Offsite Dose Calculation Manual, Process Control Program, or the Inservice inspection or Inservice Testing Programs.
f License Change Request (LCR) required: LCR h- J-lOlONl C) Effect on Environment i ff - No effect on environment [] Environment affected - contact Fermi Environmental Programs Coordinator and indicate resolution ! D) Need for Safety Evaluation (check appropriate answer) i Yes [] 1. Is this a change to the facility, including assumptions, as described in the UFSAR? ? [] ! 2. Is this a change to a procedure, including assumptions, as described in the UFSAR?
- [] l' 3. Does this change constitute a Special Test?
if any are "Yes,* initiate a Safety Evaluation. If all are *No,* provide the basis to support the determination on the continuation sheet as required by steps 6.1.7.5 and 6.1.7.6. l [ Date h[- DTC; a [5/'n l ForntTIP-SR1-0)'Att 1 P1/108306T File: f~
--- . . - - . - - . , , - -s
PRELIMINARY EVALUATION CONTINUATION SHEET l Page 7 Of E & b, g B) Revision if Appr6ve'dW I6' ! A) Document O D C t*1 identification
- 3. 0. % 0 .1. 0 0 Camments ' '
o 55 C$A41C L (MWMS Cafrid HCL. W2<d/T1Me Offcf 3 ~h of.
)u anu ul a cdmedo '
W dcili/v . I / /
- 2. ledne hinrv cm4/mnerW' is ckrcribm'iu UFJAlt
(. 2. . I?t . I 50 ae!f necuart it Ascribs/ik UPSM l.2..C2 JT h rYevinnte<ud' or rrocNcluis bJams/i> sn hc]YM' Iu he're .secb'm1. hFJAIC II,3,2. 4 $vrces bo 0,vw*ll km.Lrb%l Sbb'r &$ krywell "scburken Ca+ b-e P DnD /Ju>c J Mcs- AY LZ % @fI r r/ML
/1vochic AY f W (As ft $' & , <.
l)'V CC9M -t 64Yli Ot* AQCRC)'Y v' Y * [] frOBJech C Cwce DI)(k (#0V(Ck '?$1ain (H W ric Mervth nt Drior A/r4 Pf . AY 9ttonIkrirt L ibNa 'ru sc will be scNbbecf .bv $ oritstaru cndseWAasfe, ad,,6 C 2'z e %:u G nitilf 61 0 N G.It (5 ?ltrH(br' YMtS n A
~
i 'ti t . vfl 4 61 11441/ tr' iY Au CAlh r?tilb V KR or lh'/G lH4 GH' i '4 0, , sid 4 nd-Jn dc/Inc o', W r3 st'/M. fo &dee v'FJ/r'(dJekms w%, 4 srinrdinHcsnb~ ven G .
&t /E- (5 d~ G. HqA Anstecb r-Q , iMC scsus.,M n adeciba (A 0 /1 unx-a. '
Y l [' '/ ' l
- dh2P ttc , d1icl/111rH fblL 0 /P/iMWV ii+1 N.h hG fl/t at. COWftch N $0C2 Mf, QW $0{ShkG 5DR"i $lhjh l
r p # ' (/ ' ' (/ / i l J Form FIP-SR1-01 Att 2 P1/1 100190 i l
._. - - - .. , . . - - .. ., ~n
PRELIMINARY EVALUATION CONTINUATION SHEET
^'
'"F62'# 'Y.*h y,o, 7, o ""'*"o"^"'"**~"*
Comm.nt. G acAA k w b $ vFSAK Seebus re krowcec4 aboVe- . $wsuckX //A , ke loCF/WO Af/wenc//x 3C cowskN11ceSech%. tugs ccgu/rSc/ fo Ne"thrine W fr e VfH 8. Or f?vrei})dQ So v!Ce- 2r61 ladf dffVxtec{ }n $e c i cc 04 vS/S . ckirH '/, e o f v1/144 k of kff ((k h M0 S/ci71/ ergf fe!2Aff5 0 G o cb eS O'f~< 644' k fpn1 / 71 1 / 5
%n" ( 1hs is n tLA's im M i sf Ana #
11 Gb ll*]~l W i f ou no fr/D1ery Cm inm'k Souas ferni , ) Skou 7.e, $es $Wsedx t /R d (f. N .(f 691 0, Yu L W iY JE 2- t' /TSc r/ A U A I l'Gry by/ kq (g fggk(44 fvf ggy , & fecqhp14 9,y,f wbcL /A1a;k (Mc d,vueif colks idus. A6& WC (M 6LitMS AHL/ lHYt'C sk e aJk < Ve hq pr ftirtQjy161 Cevrc e 741 911tn fhe., f f { / 1 I Form FIP-SR1-01 Att 2 P1/1 100190
l PRELIMINARY EVALUATION CONTINUATION SHEET ,/ f/ Page'f rf 7 , Ol . , .O 7, O Y '"
' ' /
Comments Sec/icm ll of M SEil , Id ocficacAve kbr4 Planac.cwJ. war afco revievel. ,deih'er seeAw ' II.2.. k , t;a'reous kJa6 M4uodSa4m , se<Am
, , (bC W SM1 5 U61l d cG/C b rit/ r/ Ire
%&ms , n,< 9~a.M Il- E . & Easems df/'vef 0 UK A- 1. $0eCi CAlfu A /TS$ /84tk1% or 1)<jft;lHG ,
Sch, i1. 5 MWer Mk Fe,,n; 2 's W/ueW THcM l 0 ('/)4 c, _ $4f H1 1H< eb tt M ss/VC H1e Id j 8taffkb ef'/4 / f/h Osu,fdV,asasell AC 4 c%i P 1ff 8 29 J l' E. lt ?$. ' j i lCH h0 $0C $0, YnP< l'GMC Grr1f , [en 0 FC ( 6 fff' O l'h Od <- 1d lYC
$Hl//f0M M18p , Giftcf I 7/ f.Y C&MCam] 9&lc14/ r/114 -
ric60adue /reAces. A%iAfel- cerkr/iu ir ?u cNfha' W Plc #DSecf C 6%1c 2 - (GR~ 6A'i.2i a4/nces a, nib <in aa nn,& 'frhAn& < dea. anss n. b" Mt ' (%sd sui : "F;f reachs J& Le c>sier lH l'M41 en 4, QM MTGYvtTO $ GU 2 4 10 2 Cr reaecmM' camo4 VeacA s4nirec/ n4 arc stor 0 C $l d/$ e- /! FIN l t ~f 8%l 9t//)H %/ 6 L #ffrfCi1% f22& b HuC I fa$$, <- fy/20[e C Chice 4?m/um104 +?a daked bea V& ,coc4,1 r4na 4 s<&C#2 Pwb . a+4 6) drie owd "kU " rdv" Nm, I "sh II" tr v1ec9.' I I Form FIP-SR1-01 Att 2 P1/1 100190
UCENSING CHANGE REQUEST tcR 1917 i/iI17i.IoiDimi Revision O Page[of if PART 1: :11HAR, PLAN, OR PROGRAM REYJSTON C D wa N.."ened $$% 0 U Stle ]ase Cafcv/a-fim Marwor . B) Section(s), Table (s), Figure (s), etc. Affected [
}
*~* "' c"**** %/r mmMin <rfCSeccm rwuea hio A,rtfeef) cFr2 2 6 .
cbeh Wcmvat D) RefeHace and Source Documents (identify) I Tech Spec ArHvudmM 9 f EDP Procedure PDC ABN SE (Attached) PE (Attached) V C, [ DER Dravirg No. / Test I Effectiveness Review (Attached) @ Yes O No Other- (Drawings, Design Calculations, Correspondence, etc.) reifecf IO C#/? 24 A/F/4 RC i-0 / , Ajft L-9 7~oo I 7 . LC-t< '17-lot- O PL PA$tT 2: OPERAf7NG IJCENSE OTANCESIl{hiA?Jd'";IdMW.!'%9 A) Document O Operating License O Tech Specs O EnvironmentalProtectionPlan B) Section(s), Table (s), Figure (s), etc. Affected C) Reference and Source Documents Attached O NA O Other O Marked-up pages O Significant Hazards Consideration O EnvironmentalEvaluation O Environmental 1mpact/ Categorical Exclusion O Justification D) is change to UFSAR and/or approved plana / programs required? O Yes O No O LCRNo(s) E) Priority O NA NRC approval required by (date): l Explanation F) NRC Letter No. G) Amendment No.
, , PART 3: APPROVALS fus d' s Date $- l]~' u .:
- 9,,, }-l5 93 C) Responsib p ganizational Unit Head D) Plant Manager (
O NA O Atta g iew' Sheet s Date MM/~b l E) Other Date s l l [ F) Director, Nuclear Licensing O Attach Management Review Sheet Date 9lM h ' G) OSRO (Fire Protection, RERP, PCP, ODCM, SEP, O NA O Attach Management Review Sheet C
" fM~ - Date /h)
/
H) NSRG (01, TS, EPP) \ Date
/
@ NA O Attach Management Review Sheet DTC: O TDLCR File: O 1701.03 Form FIP-RA2 01 Att 1 P1/1060493 O TCLCR O 135 O TMPLAN O insa
CONTINUATION SHEET I.cn 1913 l - l / I l I 71- l 0 l D I MI isc I I I-1 I I I Revision C Page2of /f j),y (pf,],gg4 //f,y,y,,zf_, Docmnt Qff3gQ br/- / /3 ; O. O . l . o , 2..U , 2. 2A . 2.6 7 o . kcNNm III !Tble b T,7. 't2 -l . D/;/e. 3.7.'1 i1-l ^
%/,4 % 7, 7. //-/ A/dc 3' . 'Yd4 ' 7 27. r2 -l A I 4', '
v2 /, c4 7,7. /2-/ A%4 2 / 7 . i l. l / , 7 . / /. 4 . Mb/c % //,2..I; 2. - 1 . 9 44lc .7, /2 , /- / Bare '(N. II, I, / . Lr<s 3N. /I. I . z- .' lbs 7N. il. 2. I ' ikur 7N. !l . 4'. i,c/,/,'t, r, /J /cAA . T, /, / . /, 7' / ,' (. 3. 5 . l. 7.JT' W. 3 . 4 'r, f C .r,'L . 6'l , 7. I. / . 7, i 7, 7. f. / ,
- 7. 4,'2_ 7. 6' ; 7 P. 7' - . 7' i o .T#c. ~7. o -3 . P, / . 'P, 2 . .
P 2. I ! P. 2.. !2.- . P. 2 . J '. MG/e. E'. o - / . 9,'I 4, I, 2.'. '
- 9. I, 3'. 10.1 , % Al< l0'o - l T s b lc I'6 0 S '
- 7. ff. / / n l/ ,' R'. o - 2. . Fieo- lo' o -lea 7/7. /. 7.1. 2. '
/ '
f / [ 1 M,+ l C (cm4 d) : f6 #wak 6ffbere%,f: . ( kOW e h A1.eco crib 0 7tCe r . '11&o CltND*'ffb4n Gib) bt7chibh l2lLbd . W 'ftetb M1krceM1Y Sctwll 1C, heal : Elh%d of sin c ,8 ' #AC.-n.7-oon beat m s/ec M or= c.vmikeaf ma%f 0FXM fleu. 3
- ad/%m' ofauxifiarv !>ilee earea.] ^
nJese md :' ucce.saneour oded,emeof (/ / Form FIP-RA2-01 Att 5 P1/1060493 DTC: TSTSC File: 1701.02
EFFECITVENESS REVIEW
~a I C 'i 3 I - I I i l 171. Ioip la Revision O Page h / [
- PARr 2:uFsAR ENA.MD;@n M W @j @ ([kEr i Al Quality Assurance Program Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B or
- O Yes O No O NA reduce UPSAR program commitments previously accepted by the NRC7 Provide the basis for each change on Attachment 2, Page 2.
B) Fire Protection Program Does the change (s) adversely affect the ability to achieve and maintain safe O Yes O No O NA shutdown in the event of a fire? l Provide the baim for each change on Attads.ent 2, Page 2.
,' '. PART2: ~ RADIOLOGICAL DIERGENCY RESPONSEk$PAREDP$$$ hEUi&&
Does the change (s) decrease the e'!.cJveness of the RERP Plan? A) O Yes O No Does the RERP Plan, as changed, cease to meet the standards of O Yes O No 10CFR50.47(b) and 10CFR50 Appendix Et Provide the basis for each change on Attachment 2, Page 2. PART .1: SECURITY PLANS ShA Q'65%Q:+: '; ly$,$&& A) Document Does the change (s) decrease the effectiveness of the Physical Security Plan B) O Yes O No or Security Personnel Trauung and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR737 O Yts O No Does the change (s) decrease the effectiveness of the first four categories of Informational Background, Generic Plannmg Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan prepared 4 pursuant to 10CFR50.34(d) or 10CFR737 Provide the basis for each change on Attachment 2, Page 2. PART 4: PROCESS CONTROL PROGRAM Y+lk - q & f.!* 5 4f Does the change (s) reduce the overall conformance of the solidified waste 4 A) O Yes O No product to existing requirements of Federal, State, or other applicable ( regulations? (Technical Specification 6.13) I Provide the basis for each change on Attachment 2, Page 2. PART 5: ODCM O NA ' .
- *-M@Nl '
Does the change (s) reduce the level of radioactive effluent control required A) O Yes $No by 10CFR20.106,40CFR Part 190,10CFR50.36a, and Appendsx ! to 10CFRiPort 507 (Technical Specification 6.14) O Yes $-No Dees the change (s) adversely impact the accuracy or reliability of effluent, dose, or setpoint calculaticss? (Technical Specifications 6.14) Provide the basis for each change on Attachment 2, Page 2.
" ,_ .. i PART 6: APPROVALS MN; W;- kt$W.N&-
u wh , Date h/h D
' [
B) Technical f(erf C) Quality Assuranc((iecurity Plans, QA Program) Plan, Security Plans, PCP, ODCM) / D) OSRO (Fire Protection Pr am, Date hl/ h DTC: O TDLCR [ dile: O 1701.03 Form FIP RA2-01 Att 2 P1/2 060493 O TCIfR O 1735 O TMPLAN O 1715 2
EFFECTIVENESS REVIEW DOCUMENTATION en 19131 -I / I /171. Iolpina Revision o PageYofIf I < _ 0.5 e 4 Cofxhm Hud s Listed below is each change by section and page, the reason for the change, and the basis for including that the revised plan or program continues to satisfy the criteria for that plan or - program. Attach all appropriate analyses or evaluations justifyin g the change (s).
,# Section/Page 'ddMI, "dNSO;.Chmige'cC$1Q2' &%/i2&infWi$la,@d[
N l / / n J0C GW h C /1 C / E X 7j t G LS . l DTC: O TDLCR File: O 1701.03 Form FIP-RA2-01 Att 2 P2 /2 060493 O 1735 O TCLCR O TMPLAN O 1715.03 _ = _ - ,
l EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM i Revision: O Page 5 of 15 I Section/Page a j 0.0/0.0-1 Change: Update revision numbers for all sections except App A and App B, - delete App C listing. < Basis: . All sections are revised by this LCR; App C was deleted previously, l h 0.0/0.0-2, Change: Substitute " Annual" for. " Semiannual
- In section
- 0.0/0.0-4 5.9.1.7 heading; add section 7.10 to Table of Contents i
1 Basis: Effluent report will be required only annually per Technical Specification amendment 91; refers to Waste Oil incineration i section added on page 7.0-14 i j 1.0/1.0-1 Change: In first paragraph, substitute " Annual" for " Semiannual" Radioactive j Effluent Release Report. l . Basis: Effluent report will be required only annually, per Technical i
, Specification amendment 91. l i 1.0/1.0-1 Change: In third paragraph, substitute " dose limits for members of the i
public" for " concentration limits". Basis: Part II of the ODCM gives mainly dose calculation methods; also I Technical Specifications are being changed to delete reference to ) gaseous concentration limits as part of new 10 CFR 20 j implementation, and 10 times the liquid concentration limits of 10 CFR 20 are being used. i 2.21/2.0-4 Change: Revise definition of member of the public. 2 i Basis: Conforms to revised 10 CFR 20. 3 2.24/2.0-4 Change: 1 Substitute " Annual" for "Somlannual" Radioactive Effluent Reports. Basis: Effluent report will be required only annually, per Technical Specification amendment 91. i l 1 2.45/2.0-5 Change: Revise definition of Unrestricted Area. ) Basis: Conforms to Radiation Protection Manual (NPM RCI-01). This ] definition is specific to Fermi 2. d Section 3/ Change: Substitute " Annual" for
- Semiannual" Radioactive 3.0-4,9,21 Effluent Release Report i 26,35,40,46 Basis: Effluent report will be required only annually, per Technical Specification amendment 91.
4 Table Change: Add
- radioactive" prior to
- effluent release"
; 3.3.7.11-1 Action 111/ Basis: Clarifies that this action applies to waste 3.0-6 sample tank releases or contaminated circulating water 1
a.
EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM Revision: 0 Page 6 of 15 Section/Page Table Change: Add "providing alarm
- to units not so designated. t 3.3.7.12-1/
3.0-10,11,12 Basis: Satisfies commitment made to NRC in NRC-93-0017, item B.S.c. (This is the letter Fermi 2 sent to the NRC in response to the review of Revision 3 of the Fermi 2 ODCM by EG&G Idaho, Inc.) ' Table Change: Substitute " National Institute of Standards and 4.3.7.11-1, Technology
- for " National Bureau of Standards".
Note 3/ 3.0-8 Basis: The name of this agency has been changed. Table Change: Add "##* after SGTS low range noble gas activity 3.3.7.12-1, monitor in table. ' item 3.a/ 3.0-10 Basis: This symbol was inadvertently deleted when RETS were moved to ( ODCM. l Table Change: Substitute " National Institute of Standards and 4.3.7.12-1 Technology" for
- National Bureau of Standards".
Note 2/ 3.0-17 Basis: The name of this agency has been changed. 3.11.1.1/ Change: Substitute " Table 2* for " Table ll* and 3.0-18 ' substitute revised 10 CFR 20 reference (20.1001 to 20.2401). Add l
- ten times
- the concentration values.
I
- Basis: Conforms to revised 10 CFR 20 and to pending change to Technical l Specification 6.8.5.e.2 (LCR 93-105-OPL) l 3.11.4/ Change: Put " member of the public"in lower case 3.0-33 throughout. Add *(as defined in.40 CFR 190)* after " member of the public". Change ~10 CFR 20.405c" to "10 CFR 20.2203* in Action a.
Basis: " Member of the public" is defined differently in 40 CFR 190 than in 10 CFR 20. The definition in Section 2.0 is the 10 CFR 20 definition, and the terms defined in this section are indicated by upper case letters throughout the ODCM. The change in 10 CFR 20 section numbers in Action a conforms to the revised 10 CFR 20. Table Change: Add specifications for waste oil incineration. 4.11.2.1.2-1/ 3.0-25 Basis: The NRC has recently approved this type of disposal (10 CFR - 20.2004) and Formi 2 intends to burn waste oil in the auxiliary boiler following required evaluations and procedure development (see also proposed ODCM Section 7.10). Table Change: Add superscript "c" after item 2.c to refer to
- 3.12.1-1/ notation c of this table on page 3.0-40.
3.0-37 Basis: Superscript "c" does not appear in this table; notation c applies to item 2.c.
q EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM Revision: O Page 7 of 15 Section/Page Figure Change: Replace map with more legible copy. 3.0-1/ 3.0-48 Basis: Labels in blowup area could not be read. Bases Change: : Change liquid specifications as described above; 3/4.11.1.1/ change reference to 10 CFR 20.1301-- 4.0-2 Basis: Conforms to pending change to Technical Specification 6.8.5.e.2 (LCR 93-105-OPL) Bases Change: Add line 8, " water supplies that can be 3/4.11.1.2/ potentially affected~. " 4.0-3 l Basis: This line was inadvertently deleted when RETS were moved to
~ODCM. 'j Bases Change: Revise basis to reflect pending change te 3/4.11.2.1/ Technical Specification 6.8.5.e.7 and new 4.0-3,4 definition of member of the public (LCR 93-105-OPL).
Basis: The basis of gaseous effluent control is being formally changed i from MPC values at the site boundary to dose rate at the site . boundary. Dose rate is already the method for verifying compliance ! at Fermi 2 (ODCM Control 3.11.2.1), and this change conforms to Technical Specification changes already approved by the NRC for Duke Power and lilinois Power. The statement about dose to members of the public is being revised to reflect the fact that some l Fermi 2 employes will likely be classified as members of the public, ; l and will receive a higher gaseous effluent dose than persons pre */lously so classified (visitors and ic6 fishermen). Bases Change: Change reference to "10 CFR 20.2203"; change 3/4.11.4/ " member of the public" to lower case throughout.' 4.0-6 Basis: Conforms to revised 10 CFR 20 reference number. As discussed above, " member of the public* in upper case refers to the revised 10 CFR 20 definition, whereas this term is defined differently in 40 CFR 190. 5.9.1.8/ Change: 5.0-2,3,4 Substitute " Annual
- for " Semiannual" in name of effluent report.
Basis: The effluent report will be required only annually, per Technical Specification amendment 91. 5.15 Change: Substitute "UFSAR" for "FSAR" and add 10 CFR 50 footnote / reference. 5.0-4 Basis: This reflects the new name of Fermi 2's safety analysis report and provides specific guidance on updating this document.
1 EFFECTIVENESS REVIEW DOCUMENTATION- l l Reference LCR: 93-117-ODM Revision: 0 Page 8 of 15 Section/Page , i 6.1.1/6.0-2, Change: Revise liquid effluent limits to ten times values 'l 6.3.1/6.0-6, of Table 2; change Table *ll" to Table ~2*. l 6.3.2/6.0-8, ' 6.3.5/6.0-10 Basis: New liquid limits conform to pending change to Technical Specification 6.8.5.e.2 (LCR 93-105-OPL), which conforms to changes already approved by the NRC for Duke Power and Illinois Power. Change in table designation conforms to revised 10 CFR 20. 6.3/6.0-5 Change: Revise definition of CL to ten times the liquid effluent concentration limits of the revised 10 CFR 20 and incorporate the relevant section number of the revised rule. Basis: As discussed above, the new limits conform to the pending change to. Technical Specification 6.8.5.e.2 (LCR 93-105-OPL), already [ approved by the NRC for Duke Power and lilinois Power. ( 6.3/6.0-5, Change: Enhance note preceding section 6.3.1 to specify : 6.3.1/6.0-7 that DF may be used instead of DF + RR; add reference to this note in the definition of DF after Equation 6-5. Basis: The meets the commitment made to the NRC in NRC-93-0017, item C.1. (This is the letter Fermi 2 sent to the NRC in response to the review of Revision 3 of the Fermi 2 ODCM by EG&G Idaho, Inc.) < 6.3.1/6.0-6 Change: In definition of MPCl, allow separate calculation of noble gas MPCF. 1 Basis: This meets the commitment of item D.1 of NRC-93-0017. ' 6.3.1/6.0-6 Change: Revise value for BF in definition of BF and revise value for H3MPCF in definition of H3MPCF. Basis: New values for the " pure beta emitter" factors have calculated using the Table 2, Column 2 values of the revised 10 CFR 20 [ (Radiological Effluents Evaluation 93-09). l l 6.3.1/6.0-7 Change: In Equation 6-4, add summation sign. Basis: Meets commitment made in NRC-93-0017, item A.1. 6.3.1/6.0-7 Change: In equation 6-5, add safety factor to provide margin of error if individual isotope sensitivity factors are used. I Basis: Meets commitment made in NRC-93-0017, item B.I. 6.3.1/6.0-8 Change: Specify discharge with nuclides detected as basis for setpoint when 1 nuclides are not detected. . i- Basis: Realistic setpoints must be based on actual nuclide mixes present in liquid effluent samples. i
I l j EFFECTIVENESS REVIEW DOCUMENTATION l l l Reference LCR: 93-117-ODM i Revision: 0 - Page 9 of 15 ? i Section/Page c
-I 6.3.2/6.0-8 Change: Add dilution factor (DF+RR)/RR to Equation 6-7. I 1
i Basis: This corrects the MPCF term in this equation to tc. MPC fraction at
- the discharge point and meets the commitment made in -
1 NRC-93-0017, item B.3.
- 6.3.5/6.0-10 Change: Delete reference to MPCs in line 3; revise second paragraph to i
l j allow separate calculation for noble pasos using Equation 6-8. ~ i j Basis: Reference is redundant with MPCi definition on the same page;
-l separate calculation for noble gases meets commitment made in i NRC-93-0017, item D.I. ,
.i j 6.3.5/6.0-10 Change: Add the factor (1+BF)/H3F to Equation 6-8. i j Basis: -This factor accounts for the presence of
- pure beta emitters" which j
are not accounted for in Ci and thus assures that the calculation j will not indicate that the release is below the concentration limit j- when it is.over the limit due to the presence of undetected pure beta emitters. j 6.5.1/6.0-12 Change: Add sentence to specify that liquid effluent dose is to be calculated at least once per 31 days according to ODCM 4.11.1.2. j Basis: Meets commitment made in NRC-93-0017, item B.10. l 6.5.1/6.0-13 Change: Redefine Do, Ci , and DF to clarify that Equation 6-10 applies to ! a single release. ? j Basis: Meets commitment made in NRC-93-0017, item B.9. j 6.5.1/6.0-13 Change: Add parentheses in Equation 6-11. , 4 j Basis: Clarify that division and multiplication are to be performed before j addition. 1 4 6.5.2/6.0-14 Change: Specify prior to Equations 6-12 and 6-13 that they apply to the I release of a single tank, and redefine Ci and DF to clarify their application to the release of a single tank. Basis: Meets commitment made in NRC-93-0017, item B.9. j 6.6/6.0-15 Change: Substitute
- Mixed Bed Domineralizers" for "lon Exchange System".
Basis: There is no component labeled the "lon exchange system" in Figure j 6-1. This change clarifies which system Fermi 2 would use to L reduce liquid waste concentrations if a dose projection limit were
- exceeded.
1 i 4
=5- .r.
1 EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM ' Revision: O Page 10 of 15 Section/Page 7.1.1/7.0-1 Change: Delete statement that only certain SPINGs have alarm function in
' Table 3.3.7.12-1. {
Basis: Meets commitment made in NRC-93-0017, item B.S.c (see change to Table 3.3.7,12-1). 7.3.3/7.0-6 Chenge: Add sentence at the end of this section to clarify that Equations 7-4 and 7-5 may be used when analyzing routine samples as well as samples taken when an alarm setpoint is exceeded. Bar.is: Section 7.3.3 describes the situation of responding to a noble gas monitor alarm by taking and analyzing a noble gas sample, but the equations in this section can also be applied to the analysis of any
- positive noble gas sample.
7.3.1/7.0-3, Change: Substitute " primary containment" for "drywell". 7.4.1/7.0-6 7.4.2/7.0-7 _ Basis: The venting or purging analysis of this section is applicable the . either the drywell or the torus, which may be vented or purged separately. 7.6/7.0-9 Change: Revise Equation 7-9 to show summation over release points and incorporate release rate equation formerly on page 7.0-10 into Equation 7-9; in definition of RI -131 (formerly Ri ), identify this as a thyroid factor. Basis: The explicit summation over release points meets the commitment j made in NRC-93-0017, item A.2. The incorporation of the release rate equation simplifies the overall calculation since the release rate no longer needs to be calculated separately. The revised definition of RI -131 (formerly Rj) meets the commitment of item B.7 of NRC-93-0017. 1 7.6/7.0-10 Change: in discussion of alternate dose rate calculation method, include reference to meat pathway, and specify that the tritium calculation uses the alternate method. Basis: The meat pathway refer.,nce is included for completeness, even though at present the meat pathway is a minor contributor to offsite dose. The dose rate due to tritium is calculated using the alternate method because when gaseous tritium is detected, the tritium concentrations are high relative to other nuclides; if these concentrations are used with the 1-131 dose factor in Equation 7-9, unrealistically high estimates of site boundary dose rate are calculated.
EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM Revision: O' Page 11 of 15 SOction/Page 7.6/7-10 Change: Add paragraph to list requirements of Table 4.11.2.1.2-1 footnote g. l Basis: Meets commitment of NRC-93-0017, item B.8. 7.7.1/7.0-10 Change: In first paragraph, substitute "ODCM 4.11.2.2" for "ODCM 3.11.2.2" and specify an evaluation frequency of once per 31 days. Made: Meets commitment made in NRC-93-0017, item C.2. l 7.7.1/7.0-10 Change: Add statements allowing summing of air dose over 7.7.2/7.0-11 over release points. Basis: Meets commitment made in NRC-93-0017, item A.3 (air dose limit
. is for entire site).
1 l 7.8.1/7.0 11 Change: Specify ODCM 4.11.2.3 requirement for dose calculation once per 31 l days. l l Basis: Meets commitment made in NRC-93-0017, item C.4. 7.8.1/ Change: Revise Equation 7-14 to show summation over 7.0-11,12 nuclide, release point, and pathway; revise factor definitions accordingly; delete " including the total body" from the definition of Dao-Basis: Meets commitments made in NRC-93-0017, items A.3, A.4, and C.S. , 7.8.1/ Change: Revise discussion at end of section to clarify !' 7.0-12,13 how equation 7-14 is used to evaluate compliance with ODCM 3.11.2.3. Basis: This equation applies to dose assessment for the critical receptor using all identified pathways and release points. After cumulative organ doses are calculated for the quarter or year, the highest organ doses are used to evaluate compliance. 7.8.2/7.0-13 Change: Revise Equation 7-15 and definition of factors in this equation: define W and Oj for this equation, and delete SFp .- In definition of Q,i refer to cumulative release. Delete last paragraph of this section, and specify in the discussion that this equation is not to be used to calculate reported offsite dose. l
9 4 EFFECTIVENESS REVIEW DOCUMENTATION t Reference LCR: 93-117-ODM Revision: O Page 12 of 15 Section/Page 1 Basis: Since vegetable pathway is being used in this equation,'W can be specified as a D/O value readily obtainable from an ODCM table. The factor SFp equal to 0.!E, can be deleted since this is a very rough calculation which is designed to be as simple as possible so 1 ' as to provide a rapid verification of compliance. The exact . definition of Qi is specified after the equation so that the value can be rapidly obtained. The last paragraph of this section, which discussos obtaining values for the equation from the Land Use Census rather than Table 7.0-3; is inconsistent with the purpose of rapid calculation of a rough estimate: the values of Table 7.0-3 are sufficient for this estimate, given the other uncertainties and conservatisms inherent in this equation. The specification that this equation is not to be used to calculate reported dose is consistent with the above discussion of a rough rapid compliance verification method. The definition of Q ias cumulative release (not confined to a specific release point) meets the commitment made in NRC-93-0017, item A.3. 7.10/7.0-14 Change: Add section 7.10 to provide guidance on requirements for waste oil incineration if oil may contain radionuclides. Basis: This section addresses the new regulation on waste oil incineration contained on 10 CFR 20.2004, treating such incineration as a batch gaseous release. Since Fermi 2 has not yet performed all necessary evaluations or developed procedures for this activity, this section specifies that waste oli may only be incinerated according to approved plant procedures. Table 7.0-3/ Change: Update critical receptor data and dispersion and 7.0-17 deposition factors. Basis: A new critical receptor was identified as a result of the Land Use Census; this is because the infant milk pathway is no longer present at the previously identified critical receptor location, and because a child vegetation pathway was identified at the closest residence to Fermi 2, which is the new critical receptor location. New dispersion and deposition factors have been calculated for Fermi 2 by Halliburton NUS. 8.1, 8.2/ Change: Substitute " Annual" for *Semlannual' Radioactive 8.0-1 Effluent Release Report throughout. Basis: Effluent report will be required only annually, per Technical Specification amendment 91.
-z-. -
s EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM Revision: O Page 13 of 15 Svetion/Pario
, 8.1/8.0-1 Change: At'd sentence at and of second paragraph to state implication of revised definition of member of the public; add sentence at end of 4
third paragraph to allow dose assessment based on the revised 10 CFR 20 Appendix B Table 2 concentrations, which are equivalent to 50 mram per year. Basis: Thess changes facilitate calculation of dose to persons working in the controlled area but classified as members of the public, by methods consistent with the revised 10 CFR 20. 1 8.2.1/8.0-2 Change: Specify in the second para 0raph that Equation 8-2 is not to be used for evaluation of compliance with 40 CFR 190. 4 Basis: Meets commitment made in NRC-93-0017, item D.2. 8.2.1/8.0-2 Change: Specify in second paragraph that summation over release points may have to be performed to verify compilance with 40 CFR 190. Basis: Meets commitment made in NRC-93-0017, item A.S. 8.2.1/8.0-2 Change: 'In definitions for Equations 8-1 and 8-2, delete sub-equation under l Qi and instead refer to Equation 7-8; delete definition of VF which is used in the sub-equation. Basis: The sub-equation is redundant with Equation 7-8. 4 8.2.2/8.0-3 Change: Substitute "(e.g. area TLD and survey meter data)* for phrase in 4 parentheses; add phrase at end of paragraph to require that calculational methods be included in reports. Basis: Direct exposure determinations use area TLDs and may be based on micro R meter (sodium lodida) survey meters as well as lon j chambers; last phrase meets commitment made in NRC-93-0017, item B.11. 1
EFFECTIVENESS REVIEW DOCUMENTATION Reference LCR: 93-117-ODM Revision: 0 Page 14 of 15 Section/Page 8.2.3/8.0-6 Change: Add "from noble gases" to last heading in Section 8.2.3. Add phrase to last sentence to clarify that this section deals with the detection of noble gases by TLDs and that such detection is possible under unusual conditions. Basis: This change clarifies that this section deals with direct radiation from noble gases, as opposed to direct radiation from skyshine which is discussed in Section 8.2.2. Clarify reason for checking for TLD variations in this section (direct exposure due to skyshine is covered in section 8.2.2). Table 8.0-1/ Change: Add parameters for determination of dose 8.0-7 to site personnel. Clarify in footnote that listed X/O values are examples. Basis: The addition of site personnel parameters conforms to the new definition of member of the public and the probable classification of some site personnel as members of the public. The listed X/Q values are only examples since this table also states that data for the year being evaluated are to be used. Table 8.0-2/ Change: Revise first footnote to clarify that this is 8.0-8 not a complete list of exposure rate data. Basis: Meets commitment of NRC-93-0017, item C.6. 9.1/9.0-1 Change: Add requirement in second paragraph to update plant procedures with Land Use Census results; add phrase in second paragraph to allow samples not to be taken at new location if permission cannot be obtained. Basis: Data in plant procedures must be used as well as data in Table 7.0-3; if permission of landowner cannot be obtained, samples cannot be taken. 9.1.2,9.1.3/ Change: Revise section heading and step grouping to 9.0-2 separate out dose evaluation and make it contingent on significant changes in Land Use Census. Basis: Complete dose evaluation is not necessary for minor ::hanges, but only when critical receptor may change; partial evaluation may be done if a new location yields a >20% higher pathway dose. 10.1/10.0-1 Change: Substitute " Annual
- for *Semlannual" in note in this section.
Basis: Effluent report will be required only annually per Technical Specification amendment 91.
l EFFECTIVENESS REVIEW DOCUMENTATION l f- ' Reference LCR: 93-117-ODM Revision: O Page 15 of 15 Section/Page , Table Change: Revise TLD locations T10, T34, and TSS. Delete I 10.0-1/ milk locations M3 and M7. Make SW1 a drinking ! 10.0-4,6,7, ! 9,10,12,13 water location (DW3) Add SW3 (GSW Intake). Delete FP5 and add FP7. Revise closest residence location in north sector, l Basis: The changes are periodic update due to difficulty with old TLD locations (e.g. vendalism), sale of milk animals, change in' critical receptor (FP7), ovallability of potable water (DW3), enhancement of surface water tr,onitoring (SW3), and change in cartography (north sector resident.e). Table Change: Revise Detroit raw water location. 10.0-2/ 10.0-14 Basis: The revised location is more convenient for sampling. Figures Change: Update Fermi 2 sampling location figures based 10.0-1 -- changas in Table 10.0-1 10.0-4/ 10.0-16-- Basis: Show updated sampling locations. 10.0-19 Response to questions in Part 5.A of Effectiveness Review: l The limits of 10 CFR 50 and 40 CFR 190 remain in effect in this change. The revised 10 CFR 20 section on dose to the public is Subpart D which specifies a 0.1 rem annual limit, which is lower than the 0.5 rem limit of the current 10 CFR 20. In response to comments on the revised 10 CFR 20, the NRC states ! that
- demonstration of compliance with the limits in 40 CFR part 190 or with the design objectives of appendix 1 to 10 CFR part 50 will be deemed to demonstrate compliance with the 0.1 rem dose limit ." (Federal Register vol.
56, no. 98, 5/21/91). Therefore the level of effluent control is not reduced. With respect to changes in calculations, some formulas are being changed, but only clarify their use. Several changes in ODCM formulas were recommended by EG&G Idaho, an NRC contractor, but it has been determined that these are clarifications rather than substantive changes (see NRC-93-0017). Therefore the the accuracy or reliability of ODCM calculations is not affected. l I
PRELIMINARY EVALUATION Page1of 3 PART1: DESCRIP110N OF CHANGE (Preparer) A) Documentidentification B) Revision tf Approved C) PISNum oOuH O $('w'[E a encia "o$'{fL/cfn.vueet 2 y+whc4d Iocf122p
- chmke(mN S
+4 c mef ewcA.rpay//19 e d p ' 0 Il "1 n cAct t h c>
ed - myjp yyh1h Sffn1 foCR 'htf C&Yhm h m,ad< -(c .D2C in {udC-93-ooIh bal n AMC aw(& o w[ry /%. 7 +1eov3 a&&pm Jav>aitavy ;lec p v.s ce ase
/Wn ] 751r7CE %[441Cented PART2: PRELIMINARY EVALilA110N (Preparer, Approver)
A) Review of Commitments O N/A Meets Exemption Criteria 6.1.4.5. Approvedby: 8- No commitments O Carunttmmtsexit(list) O Commitmentsmet-nonenegated 0 Ccmmitmentsneedchanging(explain) O Safety Engineering and/or Licensing have been contacted to make changes B) Impact on License, Plans, or Programs O No change to the Operating License (including the Technical Specifications, the Environmental Protection Plan, and the Technical Specification Bases), the Core Operating Limits Report (COLR), the UPSAR, Fire Protection Program, Quality Assurance Program, Radiological Emergency Response Preparedness Plan, Physical Security Plan, Safeguards Contingency Plan, Security Personnel Training and Qualification Plan, Offsite Dose Calculation Manual, Process Control Program, or the Inservice Inspection on Inservice Testing Programs.
@ License Change Request (LCR) required: LCR 3-[ / 7O P i C) Effect on Environment E No effect on environment O Environment affected - contact Fermi Environmental Engineer and indicate resolution D) Need for Safety Evaluation (check appropriate answer)
Yes No O B 1. Is this a change to the facility, including assumptions, as described in the UFSAR? O B 2. Is this a change to a procedure, including assumptions, as described in the UFSAR? O G- 3. Does this change constitute a Special Test? If any are "Yes," initiate a Safety Evaluation unless an NRC Safety Evaluation Report exists meeting the requirements of step 6.1.11. If all are "No," provide the basis to support the determination on the continuation sheet as required by steps 6.1.7.2,6.1.8.3, and 6.1.9. f Datef/J-9 ( t 7srhp { f i Form FIP-SRI-01 Att 1 P1/1052193 File: 0923.02
'1 i PRELIMINARY EVALUATION CONTINUATION SHEET Page2.of 3 B) Revision of Approved A) Document Identification ODC/1 1 a i O Comments l l. TbT revisim ofde ODCA iwolve.s cla,aes b Y Cu Y R1 YJt$nhth/2tHR VJ , 11 M16 , YK u I(Mf , ,. _2k'11o YJ t/lI C h C a tst; el i $/sh chdl1 or enldnW. As#1ucl. l ll 710hG C elme t / V Gf
- AcaiLa ,, Muswg i
! l
- I N T299C DH'th 2 i CA ) f} M I
ncKc8 uFSA(L0echm ll MJ/9/2 ( wl Cov1biln 0 Ik el O Cu h1d
- wddch wa ww 4s4dvov4esu/a4 .
1 Aes eurr k L ,w A J w a %c. _ MSCr/ bf i CJQlAf's 2/2 .ffr FMS 'M o W C 0 4 UJY r urIMc of)ern ifM
' uL A &cAKWKnal,w
. bc,6c L ,s efL A L Ku l ius- sn JinJUd;u u Ff#12 S cb m I lls $s 2 f . Uh R. ,s Gyt 410 h hao Il k, told 4 D 24 ~ La
, U Y er 'hoh f'e&>lft .
O if Nhorp i File: 0923.02 Form FIP-SR1-01 Att 2 P1/1 152193
PRELIMINARY EVALUATION CONTINUATION SHEET Page)of 3 A) Document Identification B) Revision of Approved ODCJH O l O Comments kllk vtsnec/k ke- c)maar b IOCFfl2c VWda bcNs . IO CFL 2e bow l* 2 15 c lbd l I% UFSb . tk 0 b S/cci C- VS UtG Gre e If 0 [$ nGLVIfl if % d Ce O Cr_ 7t1rvC-e b M [Cri 4l )% UYN - V
.3. k revieu ol F#1D CT I dl owr $d a hac.J c<2. be rJ h bitc, of leirfunn l li EGVn2 f) di CO2/tl VM e e pH!v _Sv$
fiY A y e-.- IMreck /n e- OD El e C U e<A /~lt bl otA 'Nrv lk r) . b O
& I,i s <e se ,1 i m d (e c m , n A n ofh{eeniAd W[ [u 91V %0& CT/C&1 f(Mf , /t 4.
~S #Mc~Q- 0 6 1t 0 /M i %cda MM.
V
\
l l l i Form FIP-SR1-01 Att 2 P1/1052193 File: 0923.02 i
Nucl:ar Pr:ductlin - F rmi 2 CDCM-0.0 ' Offsit3 DIsa Calculati:n Manual R vi lin 6 Pego 0.0-1 l l I DETROIT EDISON - FERMI 2 OFFSITE DOSE CALCULATION MANUAL
\
l l l implementation Plan I These revisions go into effect upon approval of LCR 93-105-OPl. l i Current Revision Status by Section { Section Number Revision Number Approval Date 0.0 6 09/21/93 I 1.0 5 09/21/93 2.0 5 09/21/93 3.0 6 09/21/93 4.0 6 09/21/93 $ t 5.0 6.0 5 09/21/93
\ h l
7.0 5 09/21/93 '\ l 6 09/21/93 8.0 5 09/21/93 9.0 5 09/21/93 , 10.0 5 09/21/93 l Appendix A 4 08/07/92 l Appendix B 4 08/07/92 I i ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: 93-117-ODM DSN Rev 6 Date DTC TMPLAN File 1715.02 Recipient l _.
l ODCM-0.0 q Rrvision 6 , j Pcg3 0.0-2 l ! TABLE OF CONTENTS 1
- Page Section
- 1.0-1
1.0 INTRODUCTION
i 4 j PART I - RADIOLOGICAL EFFLUENT CGNTROLS i
- 2.0-2 2.0 DEFINITIONS i
~ 3.0-1 3.0 CONTROLS AND SURVEILLANCE REQUIRgMENTS i { 3.0-2 3/4.0 Controls and Surveillance Requirements Applicability j 3.0-4 3/4.3.7.11 Radioactive Liquid Effluent Monitoring instrumentation 3.0-9 3/4.3.7.12 Radioactive Gaseous Effluent Monitoring i instrumentation
- 3.0-18 3/4.11.1.1 Liquid Effluents Concentration
- 3.0-22 3/4.11.1.2 Liquid Effluent Dose l 3.0-23 3/4.11.1.3 Liquid Waste Treatment t 3.0-24 3/4.11.2.1 Gaseous Effluents Dose Rate 4
3.0-28 3/4.11.2.2 Gaseous Effluents Dose - Noble Gases ) 3.0-29 3/4.11.2.3 Gaseous Effluents Dose - lodine-131. lodine-133,
- Tritium, and Radionuclides in Particulate Form j 3.0-30 3/4.11.2.4 Offges Treatment System j 3.0-31 3/4.11.2.5 Ventilation Exhaust Treatment System
- 3.0-32 3/4.11.2.8 Venting or Purging i 3.0-33 3/4.11.4 Radioactive Effluents Total Dose
- 3.0-34 3/4.12.1 Radiological Environmental Monitoring Program I
3.0-46 3/4.12.2 Land Use Census 3.0-47 3/4.12.3 Interlaboratory Comparison Program 4.0-1 4.0 BASES j 5.0-1 5.0 ADMINISTRATIVE CONTROLS l 5.0-2 5.9.1.7 Annual Radiological Environmental Operating Report l l l 5.0-2 5.9.1.8 Annual Effluent Release Report ] 5.0-4 5.15 Major Changes to Radioactive Liquid, Gaseous, and i Solid Waste Treatment Systems l PART 11 - CALCULATIONAL METHODS f 6.0-2 6.0 UQUID EFFLUENTS j 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 i 6.0-3 6.2 Sampling and Analysis of Liquid Effluents
! 6.0-4 6.2.1 BATCH Releases , 6.0-4 6.2.2 CONTINUOUS Releases j 6.0-5 6.3 Liquid Effluent Monitor Setpoints i 6.0-5 6.3.1 Liquid Radwaste Effluent Line Monitor (D11-N007) i j J . . _ _ - _ , , . _ _ _ _ .
j ODCM-0.0 d R:: vision 6 Paga 0.0-3 ] l TABLE OF CONTENTS (continued) Page Section ! 6.0-8 6.3.2 Circulating Water Reservoir Decant Line Radiation j Monitor (D11-N402) a 6.0-9 6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 6.0-9 6.3.4 Alarm Setpoint for GSW and RHR System Radiation j! Monitors i 6.0-10 6.3.5 Alarm Response - Evaluating Actual Release Conditions l 6.0-10 6.3.6 Liquid Radweste Setpoint Determination With ! Contaminated Circulating Water Pond j 6.0-11 6.4 Contaminated GSW or RHR System - Guantifying and Controlling ] Releases l 6.0-12 6.5 Liquid Effluent Dose Calculation - 10 CFR 50 6.0-12 6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents 3 6.0-14 6.5.2 Simplified Liquid Effluent Dose Calculation j 6.0-15 6.5.3 Contaminated GSW System - Dose Calculation j 6.0-15 6.6 Liquid Effluent Dose Projections s ~ 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 i 7.0-1 7.1.2 Main Condenser Offgas Monitoring '
7.0-2 7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic) 7.0-2 7.2 Sampling and Analysis of Gaseous Effluents 7.0-2 7.2.1 Containment PURGE i 7.0-2 7.2.2 Ventilation System Releases j 7.0-3 7.3 Gaseous Effluent Monitor Setpoint Determination i 7.0-3 7.3.1 Ventilation System Monitors 4 7.0-5 7.3.2 Setpoint Determination with No Nuclides Detected i 7.0-5 7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual j Release Conditions ! 7.0-6 7.4 Containment Drywell VENTING and PURGING 1 7.0-6 7.4.1 Release Rate Evaluation ! ! 7.0-7 7.4.2 Alarm Setpoint Evaluation ! 7.0-7 7.5 Quantifying Releases - Noble Gases ! 7.0-7 7.5.1 Sampling Protocol ! 7.0-6 7.5.2 Release Concentration Determination for Reactor l Building Exhaust Plenum j 7.0-9 7.5.3 Calculation of Activity Released > 7.0-9 7.6 Site Boundary Dose Rate - Radiolodine and Particulates 7.0-10 7.7 Noble Gas Effluent Dose Calculations - 10 CFR 50 i 7.0-10 7.7.1 UNRESTRICTED AREA Dose - Noble Gases l l i f 4 i l
ODCM-0.0 Revision 6 Paga 0.0-4 l TABLE OF CONTENTS (continued) Page Section l 7.0-11 7.7.2 Simplified Dose Calculation for Noble Gases ; 7.0-11 7.8 Radiolodine and Particulate Dose Calculations - 10 CFR 50 7.0-11 7.P.1 UNRESTRICTED AREA Dose - Radiciodine and Particulates 7.0-13 7.8.2 Simplified Dose Calculation for Radiolodines and Particulates 7.0-13 7.9 Gaseous Effluent Dose Projection 7.0-14 7.10 Waste Oil incineration 8.0-1 8.0 SPECIAL DOSE ANALYSES J 8.0-1 8.1 - Doses Due to Activities inside tho' 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 8.0-3 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data 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 10.0-1 10.1 Sampling Locations 10.0-1 10.2 Reporting Levels 10.0-2 10.3 Interlaboratory Comparison Program APPENDICES 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 2.0-6 2.1 Surveillance Frequency Notation 2.0-7 2.2 Operational Conditions 3.0-5 3.3.7.11-1 Radioactive Liquid Effluent Monitoring instrumentation 3.0-7 4.3.7.11-1 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 3.0-10 3.3.7.12-1 Radioactive Gaseous Effluent Monitoring Instrumentation l l
i ODCM-0.0 Rsvision 6 ! Pags 0.0-5 i j TABLE OF CONTENTS (continued) I l Page Section j 3.0-14 4.3.7.12-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements j , 3.0-1g 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program j 3.0-25 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and analysis Program
- 3.0-36 3.12.1-1 Radiological Environmental Monitoring Program i 3.0-42 3.12.1-2 Reporting Levels for Radioactivity Concentrations in j Environmental Samples 3.0-43 4.12.1-1 Detection Capabilities for Environmental Sample Analysis
! 6.0-17 6.0-1 Fermi 2 Site Specific Liquid ingestion Dose Commitment l Factors, Ago
- 6.0-19 6.0-2 Bioaccumulation Factors (BFi) j 7.0-15 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm j Setpoints
- 7.0-16 7.0-2 Dose Factors for Noble Gases j 7.0-17 7.0-3 Controlling Locations, Pathways and Atmospheric Dispersion j for Dose Calculations i 7.0-18 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors j 8.0-7 8.0-1 Assumptions for Assessing Doses Due to Activities inside i SITE BOUNDARY i 8.0-8 8.0-2 Recommended Exposure Rates in Lieu of Site Specific Data j 10.0-3 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 1 Sample Locations and Associated Media j 10.0-14 10.0-2 Radiological Environmental Monitoring Program, Fermi 1 i Sample Locations and Associated Media .
A-4 A-1 Relative Dose Significance of Radionuclides in Liquid I j Effluents j B-4 B-1 Effective Dose Factors - Noble Gas Effluents l FIGURES i 3.0-48 3.0-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents j 6.0-20 6.0-1 Liquid Radioactive Effluent Monitoring and Processing
- Diagram l 7.0-33 7.0-1 Gaseous Radioactive Effluent Monitoring and Ventilation !
i Systems Diagram
- 10.0-16 10.0-1 Radiological Environmental Monitoring Program Sampling
- Locations - Site Area j 10.0-17 10.0-2 Radiological Environmental Monitoring Program Sampling i Locations - Greater than 10 Miles j 10.0-18 10.0-3 Radiological Environmental Monitoring Program Sampling i Locations - within 10 Miles l 10.0-19 10.0-4 Radiological Environmental Monitoring Program Sampling i Locations - Site Area (Lake Erie side) 10.0-20 10.0-5 Fermi 1 Sampling Locations f
i ! END OF SECTION 0.0 d l
_ _ - . . - . . . - ~_.- - --. . - _ _ - . _.
; Nucl ar. Praductisn - F rmi 2 CDCM-1.0 Off<o D2co Criculatlin M nu:1. R vislin 5
{ Piga 1.0-1 j INTRODUCTION J j
1.0 INTRODUCTION
i l Part I of the Fermi 2 Offsite Dose Calculation Manual (ODCM), which includes Sections 2.0. I ! through 5.0, contains the controls and surveillance requirements for radioactive effluents ) l and radiological environmental monitoring. it also contains requirements for the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release lO (/
- Report.
I
- Part 11 of the ODCM describes the methodology and parameters used in a) determining i j radioactive material reisase rates and cumulative releases, b) calculating radioactive liquid ;
j and gaseous effluent monitoring instrumentation alarm / trip setpoints, and c) calculating the ) j corresponding dose rates and cumulative quarterly and yearly doses. Calculational 1 methods different from those provided in the ODCM may be used only if they lead to more ; j conservative results than would be obtained using ODCM methods. ' ODCM data for l j dispersion factors, roceptor locations, exposure pathways, ventilation flow rates, etc. are l j 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 3 compliance with the dose limits for members of the public of 10 CFR 20, the cumulative OpI i dose criteria of 10 CFR 50, Appendix 1 and 40 CFR Igo, and tbs controls in Part I of this manual. i I Part II, Section 6.0 of the ODCM describes equipment for monitoring and controlling liquid l effluents, sampling requirements, and dose evaluation methods. Section 7.0 provides j similar information on gaseous effluent controls, sampling, and dose evaluation. , Section 8.0 describes special dose analyses required for compliance with Fermi 2 Offsite 3 Dose Calculation Manual and 40 CFR 1g0. Section 9.0 describes the role of the annual land j use census in identifying the controlling pathways and locations of exposure for assessing j potential off-site doses. Section 10.0 describes the Radiological Environmental Monitoring j Program. 1 l The ODCM will be maintained at Fermi 2 for use as a listing of radiological effluent I controls and surveillance requirements, as well as a reference guide and training document j for accepted methodologies and calculations. Changes to the ODCM calculational j methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix i for j demonstrating that radioactive affluents are "As Low As Reasonably Achievable." l l l' NOTE: Throughout this document words appearing all capitalized denote either definitions specified in the Fermi 2 Controls or common acronyms. END OF SECTION 1.0 l' ARMS - INFORMATION SERVICES j Date approved: Release authorized by: i Change numbers incorporated: g3-117-ODM DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient f
l 1
- Nuclear Production - Fcrei 2 ODCN-2.0 l Offsite Dose Calculatien Manual- P;gs 2.0-1 t-l f.
i l 2 i ? l 1 1 i i i 1 I r e PART I RADIOLOGICAL EFFLUENT CONTROLS 1
Nuclear Production - Fcrai 2 ODCM-2.0 l l Offcito Dose Calculction Manual Rivicion 5 I Page 2.0-2 , i ! 1 l ! 1 i l l
/ SECTION 2.0 DEFINITIONS l
ARM 5 - 1150iMATICE SERVICES Date approved: Release authorized by: Change numbers incorporated: 93-117-ODN DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient
l ' Nuclear Producticn - Fcrai 2 ODCM-2.0 l Offsito Dose Calculation Manual Revicien 5 l Pags 2.0-3 i i j- 2.0 DEFINITIONS l i- 1 1~ l ,- ACTION . l l 2.1 ACTION shall be that part of a specification which prescribes remedial !' I measures required under designated conditions. i CHANNEL CALIBRATION l' 2.4 A CHANNEL CALIBRATION shall be the adjustaant, as necessary, of the l channel output such that it responds with the necessary range and accuracy ) i to known values of the parameter which the channel monitors. 1he CHANNEL 1 i CALIBRATION shall encompass the entire channel including-the sensor and l j alars and/or trip functions, and shall include the CHANNEL FUNCTIONAL' l l TEST. The CHANNEL CALIBRATION any be performed by any series of sequential, overlapping, or total channel steps such that the entire j channel is calibrated. Calibration of instrument channels with resistance j 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.
I l CHANNEL CHECK l 25 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-1 indications and/or status derived from independent instrument channels [ measuring the same parameter. CHANNEL FUNCTIONAL TEST i 2.6 A CHANNEL FUNCTIONAL TEST shall be: i a. Analog channels - the injection of a simulated signalt into the
- - channel as close to the sensor as practicable to verify OPERABILITY including alars and/or trip functions and channel failure trips.
? i b. Bistable channels - the injection of a simulated signal into the i sensor to verify OPERABILITY including alara and/or trip functions. j The CHANNEL FUNCTIONAL TEST any be performed by any sequential,
- overlapping, or total channel steps such that the entire channel is j tested.
1 ! DOSE EQUIVALENT I-131 i 2.9 DOSE EQUIVALENT I-131 shall be that concentration of_ I-131, microcuries l per gras, which alone would produce the same thyroid dose as the quantity I and isotopic mixture of I-131. I-132, I-133. I-134, and I-135 actually ) present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." l l FREQUENCY NOTATION
- 2.14 The FREQUENCY NOTATION specified for the performance of Surveillance j- Requirements shall correspond to the intervals defined in Table 2.1.
Nuclear Producticn - F4rni 2 ODCM-2.0 Offalto Dose Calculttion Manual- Revision 5 Prgs 2.0-4 2.0 DEFINITIONS 1 MEMBER (S) OF'THE PUBLIC _ 2.21 MEMBER (S) OF THE PUBLIC shall be an individual in a controlled or- ' - l UNRESTRICTED AREA. . However, an individual is not a MEMBER OF THE PUBLIC '\\ during any period in which the individual receives an occupational dose. OFF-GAS TREADIENT SYSTEM 2.23 An OFF-GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous affluents by collecting reactor coolant syst.es ; offgases from the reactor' coolant and providing'for delay or holdup for >l the purpose of reducing the total radioactivity prior to release to the environment. OFFSITE DOSE CALCULATIONAL MANUAL
- 2.24 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from ,
radioactive gaseous and liquid effluent, in the calculation of gaseous and i liquid effluent monitoring alare/ 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 Technic:1 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. l \\ N 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 l when all necessary attendant instrumentation, controls, electrical power, cooling or seal' water, lubrication or other auxilliary equipment that are required for the systes, subsystes, train, component or device.to perform its function (s) are also capable of performing their related support- , function (s). ! OPERATIONAL CONDITION - CONDITION 2.26 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. 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. _ ~ . . _ . . . _ - - _ _ _ . _ _ . .
Nuclear Production - Fcr:1 2 ODCH-2.0 .i Offaite Dose Calculatien Manual- Revicion 5 ! Paga 2.0-5 l l 2.0 DEFINITIONS
. RATED THERMAL POWER 2 32 RATED THERNAL POWER shall be a total reactor core heat' transfer rate to 4 the reactor ooolant. equivalent to that stated'in the. Technical 'i 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. l THERMAL POWER 2.42 THERNAL POWER shall1be 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' boundary. g VENTILATION EIHAUST TREATMENT SYSTEM 2.46 A VENTILATION EIHAUST TREATMENT SYSTEM shall be any systes designed and installed to' reduce' gaseous radiolodine 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 lodines or particulates.from the gaseous' exhaust strema prior to the release to the environment. Such a system is not considered to have any 4 effect on noble gas effluents. Engineered Safety Feature (ESF) { atmospheric cleanup systems are not considered to be VENTILATION EIHAUST l TREATMENT SYSTEN components. l 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 4 not provided or required during VENTING. Vent, used in system names, does ' not imply a VENTING process.
1 Nuclear Production - Fcrai 2 ODCM-2.0 Offsito Dose Calcul tien Manual Revision 5 , Pcg3 2.0-6 ' TABLE 2.1 SURVEILLANCE FREQUENCY NOTATION ) l 1 NOTATION FREQUENCY S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. Q At least once per 92 days. SA At least once per 184 days. ! A At Isast once per 366 days. R At least once per 18 months (550 days). l 1 S/U Prior to each reactor startup. ' P Prior to each radioactive release. N.A. Not applicable. l l
i Nuclear Producticn - FJrsi 2 ODCM-2.0 l ;Offaits Dose Calculcticn Manual- Re'ision v 5: i Page 2.0-7 l 1 l ~2.0 DEFINITIONS i f ' TABLE 2.2 OPERATIONAL CONDITIONS i MODE SWITCH AVERAGE REAC10R j CONDITION. POSITION COOLANT TEMPERATURE
- 1. POWER OPERATION Run .Any temperature
- 2. STARTUP, Startup/ Hot Standby- Any temperature 3 HOT SHUTDOWN Shutdown #, ### > 200 degrees F. I
- 4. COLD SIUTDOWN Shutdown #, ##, *** $ 200' degrees F 5 REFUELINGe Shutdown or refuel **,# $ 140' degrees F;
# 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.-
## The reactor _ node 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.
e 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.
EMD W SECTION 2.0 '
. Nuclear Production - Fcrai 2 ODCM-3 0 l Offsite Dose Calculation Manual Revisien 6 Pags 3 0-1 I
I l l l l t i SECTION 3.0 , CONTROLS l AND SURVEILLANCE REQUIREMENTS 1 I AmtS - IW oml& TION SERVIQts Date approved: Release authorized by: l Change numbers incorporated: 93-117-ODN DSN Rev 6 Date DTC TMPLAN File 1715.02 Recipient
i Nuclear Productica - Farsi 2 ODCN-3 0 Offcite Dose Calculcticn Manual Revision 6
- i. Paga 3 0-2 i
3. l' '; j 3/4 CONTROLS AND SURVEILLANCE REQUIRENENTS i j 3/4.0 APPLICABILITY ! CONTROLS i 1 ! 3 0.1 Comp'liance with the succeeding Controls is required during the j OPERATIONAL CONDITIONS or other conditions specified-therein; except ;
.that upon failure to meet the control, the associated ACTION requirements shall be set.
3 0.2 Noncomplie,nce with a Control shall' exist when the requirements of the ; i control and associated ACTION requirements are not met within the j specified time intervals. If the Control is restored prior to ,
- expiration of.the specified time intervals, completion of the Action- ;
- requirements is not required. ,
i j 303 Nhen a Control-is not met, except as provided in the associated ACTION-i requirements, within one hour action shall.be initiated'to place the i unit in an OPERATIONAL CONDITION in which the control does not apply j by placing it, as applicable, in: 1 i 1. At least STARTUP within the next 6 hours, 2 2. At least HDT SHUTDONN within the following 6 hours, ~ and , i 3 At least COLD SHUTDONN within the subsequent 24 hours. j i l j Where corrective measures are completed'that permit operation'under the ACTION i i requirements, the ACTION any be taken in accordance with the specified time I ! limits as measured from the time of failure to aset the Control. Exceptions to i these requirements are stated in the individual Controls. l 1 This Control is not applicable in OPERATIONAL CONDITIONS 4 or 5. i 3 0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall ! not be'made when the conditions for the Controls are not met and the
- associated ACTION requires a shutdown if they are not met within a i specified time interval. Entry into an OPERATIONAL CONDITION or other j specified condition may be made in accordanos with the ACTION i
requirements when conformanoe to then 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 j to comply with ACTION requirements. Exceptions to these requirements i are stated in the individual Controls. 4 4
Nuclear Production - Fcr:1 2 ODCM-3 0 Offaito Dose Calculation Manual Revision 6 Pcgs 3 0-3 : i APPLICABILITY ' SURVEILLANCE REQUIREMENTS , i 4.0.1 Surveillance Requirements shall be met during the' OPERATIONAL. CONDITIONS or other conditions specified for individual Controla unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed ' 25 percent of the specified surveillance interval. i 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 i' time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.. l The ACTION requirements any be delayed for up to 24 hours to permit ' the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. l Surveillance Requirements do not have to be performed on inoperable l 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. '
P - . l Nuclear Production - Fcrai 2 ODCN-3 0 j Offaite Dose Calculaticn Manual Revicion 6
~Paga 3.0-4.
INSTRUMENTATION ' 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION - CONTROLS 3 3 7 11 The radioactive 11guld effluent monitoring instrumentation ~ channels shown in Table 3 3 7.11-1 shall be OPERABLE with their alara/ trip setpoints set to ensure that the limits of Control;3 11.1.1 are not exceeded.. The alars/ trip , setpoints of these channels shall be determined and adjusted in accordance with ! the methodology and parameters-in the OFFSITE. DOSE CALCULATIONAL MANUAL (ODCN).- APPLICABILITY:- At all times. ACTION:
- a. Nith a radioactive liquid effluent monitoring instrumentation channel alara/ 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. Nith less than the ainlaus 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 - o inoperability was not corrected in a timely manner in the next Annual O Radioactive Effluent Release Report.
- c. The provisions of Controla 3 0 3 and 3 0.4 are not applicable. -
SURVEILLANCE REQUIREMENTS l 4 3 7.11 Each radioactive liquid affluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CyauvRI. CALIBRATION and NAuuP1 FUNCTIONAL TEST operations at the frequencies shown in Table 4 3 7.11-1. !
..#,. . ,4p._.-
ODCM 3.0 R'viDign 6 Page 3.0-5 TABLE 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GWOSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- m. Liquid Redweste Effluent Line D11-N007 1 110
- 2. GROSS RADIDACTIVITV MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Circulating water Reservoir Decant Line D11-N402 1 til
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Redweste Effluent Line G11-R703 1 112
- b. Circulating Water Reservoir Decent Line N71-R802 1 112
Nuclear Productica - F rai 2 ODCN-3 0 Offsite Dose Calculaticn Manual Revision 6 Pags 3 0-6 TABLE 3 3.7.11.1 (continued) TABLE NOTATIONS ACTION 110 - With'the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and
- b. At least two technically qualified individuals independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 - Vith.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 hours for gross radioactivit at least 10-y (beta or gaana) alcrocurie/al, for at a lower Cs-137. limit of detection Otherwise, suspendof ' release of radioactive effluents via this pathway. ACTION 112 - With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, effluent releases via this pathway any continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place-may be used to estimate flow. Otherwise, suspend release of radioactive affluents via this pathway.
ODC3 3.0 Ocvicisn O Pig,n 3.0-7 TABLE 4.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECM CALIBRATION TEST
- 1. GROSS RADIOAC"IVITY MONITORS PROVIDING ALARM AND AU-JMATIC TERMINATION OF RELEASE
- a. Liquid Radweete Effluent Line P P R(3) Q(1)(2)
- 2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Circulating Water Reservoir Decant Line O M R(3) Q(5)
D11-N402
- 3. FLOW RATE MEASUREMENT DEVICES (4)
- a. Liquid Radweste Effluent Line D(4) N.A. R Q
- b. Circulating Water Reservoir Decent Line D(4) N.A. R Q
________-__.._____._m. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . - __ __ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . - _ - _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ - - _ _ _ _ _ - - - _ . - _ _ _ _ _ _ _ _ _ _ _____ _ - . _ _ _ _ _ _ _ _ .
l Nuclear Productirn - Fcrai 2 ODCM-3 0 ' Offsito Doso Calculation Manual Revicion 6 Pega 3 0-8 TABLE 4.3.7.11-1 (Continued) TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic , isolation of this pathway occurs if any of the following conditions J exists: :
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. 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. 1hese 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 gg 'cg 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 hours on days on which continous, periodic, or batch releases are made. (5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alara annunciation occurs if any of the following conditions exists: j l
- 1. Instrument indicates seasured levels above the alars setpoint. l
- 2. Circuit failure.
3 Instrument indicates a downscale failure. l 1 l l
4 Nuolear Producticn - Fcrai 2 ODCM-3 0 Offa:ite Dose Calculatic) Mantal Revisicn 6 4 Page 3 0-9 INSTRUMENTATION 4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS d 3 3 7 12 The radioactive gaseous effluent monitoring instrumentation channels
- shown in Table 3 3 7 12-1 shall be OPERABLE with their alars/ 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 4 system, shall be determined and adjusted in accordance with the methodology and l
parameters in the ODCM. 1 APPLICABILITY: As shown in Table 3 3 7.12-1 ACTION: i l
- a. With a radioactive gaseous effluent monitoring instrumentation channel alars/ trip setpoint less conservative than required by the above ,
Control, immediately suspend the release of radioactive gaseous 1 effluents sonitored by the affected channel, or declare the channel l
- inoperable, or change the setpoint so it is acceptably conservative. l
)
- b. With less than the ainlaus number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in i 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 iNg Radioactive Effluent Release Report.
- c. The provisions of Controls 3.0 3 and 3 0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS l 1 4 3 7.12 Each radioactive gaseous effluent monitoring instrumentation channel i 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 12-1. i a 5 I
. ~ . . . . - _ . ~ . - ~ . .
ODCM 3.0 Ccvictcn G P!ge 3.G-10 TABLE 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION WIN! MUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. REACTOR BUILDING EXHAUST PLENUM EFFLUENT MONITORING SYSTEM
- e. Low Range Noble Gee Activity Monitor -
Providing Alarm 1
- 121
- b. Iodine 5empler 1
- 122
- c. Particulate Sampler 1
- 122 .
- d. Sampler Flow Rete Monitor
- 1 123
- 2. OFFGA5 MONITORING SYSTEM (At the 2.* minute deley piping)
- e. Noble Gee Activity Monitor - 1 *** 126 Providing Alarm
- 3. STAND 9Y GA5 TREATMENT SYSTEM
- e. Low Range Noble Gee Activity Monitor ## -
Providing Alarm . 1 # 125 g lQ
- b. Iodine sempler #
1 122
- c. Particulate Sampler 1 # 122
- d. Sempler Flow Rete Monttor #
1 123
ODCM-3.0 Ocvioisn 6 Pcce 3.0-11 TABLE 3.3.7.12-1 (Continued) RADIOACTIVITY GASEOUS EFFLUENT WONITORING INSTRUMENTATION MINIMUM CHANNEL 5 INSTRUMENT OPERABLE APPLICABILITY ACTION 4 TURBINE BLDG. VENTILATION MONITORING SYSTEM
- e. Low Range Noble Gas Activity Wonitor - 1 e 121 g\
Providing Alarm
- b. Iodine Sampler 1
- 122
- c. Particulate Sampler 1
- 122
- d. Sempler Flow Rete Monitor 1
- 123
- 5. SERVICE BUILDING VENTILATION MONITORING SYSTEM
- e. Low Range Noble Gas Activity Monitor -
Providing Alarm 1 e 121 \\
- b. Iodine Sampler 1 e 122
- c. Particulate Sampler 1 e 122
- d. Sempler Flow Rate Monitor 1
- 123
_.-..._____._m. _ _ _ _ . _ _ _ - - - - - _ . - _ - _ - _ - - _ _ - _ _ - - . _ _ _ _ _ _ _ _ _ _ _ . ._--.--.u - - - - _ _ - - -
l ODC'-3.0 Revioisn G P co 3.0-12 TABL E 3.3.7.12-1 (Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITV ACTION
- 6. RADMASTE BUILDING VENTILATION MONITORING SYSTEM
- a. Low Range Noble Gas Activity Monitor - 1 e 121 (\
Providing Alarm
= 122
- b. Iodine Sampler 1
- c. Particulate Sampler 1
- 122
- d. Sampler Flow Rate Monitor 1
- 123
- 7. ONSITE STORAGE SUILDING VENTILATION EXHAUST RADIATION MONITOR
- 121 a
- a. Low Range Noble Gas Activity Monitor - 1 OgS2 Providing Alarm
- b. Iodine Sampler 1
- 122
- c. Particulate Sampler 1
- 122
- d. Sampler Flow Rete Monitor 1
- 123
i Nuclear Producticn - F;r:li 2 l ODCH-3 0 i l Offsito Dosa Calculcticn Manual Revicion 6 l Pagli 3 0-13 l l i j TABLE 3.3.7.12-1 (Continued) : f i TABLE NOTATIONS i , l 8 At all times. l j ** Not used. i *** During operation of the main condenser air ejector. i i During operation of the standby gas treatment system. di Also included in Technical Specifications Table 3 3 7.5.1 Itos 13.a. ACTION STATEMENTS l i i l l ACTION 121 - With the number of channels OPERABLE less than required by the , Minimum Channels OPERABLE requirement, effluent releases via l this pathway any continue provided grab samples are taken at l l least once per 12 hours and these samples are analyzed for gross i i activity within 24 hours. Otherwise, suspend release of ; radioactive effluents via this pathway. ; ) ACTION 122 - With the number of channels OPERABLE one less than required by j the Minlaus Channels OPERABLE requirement, effluent releases via , t this pathway any continue provided that within 8 hours samples 1 ] are continuously collected with auxiliary sampling equipment as l j required in Table 4.11.2.1.2-1. i j ACTION 123 - With the number of channels OPERABLE-less than required by the Minimus Channels OPERABLE requirement, effluent releases via
- this pathway any continue provided the flow rate is estimated at 5
least once per 4 hours. Otherwise, suspend release of ] radioactive effluents via this pathway. l I ACTION 124 - Not used, i i ACTION 125 - With the number of channels OPERABLE less than required by the ! Minimum Channels OPERABLE requirement, effluent releases via } this pathway any continue provided grab samples are taken at l least once per 4 hours and these samples are analyzed for gross j l activity within 24 hours. Otherwise, suspend release of !
- radioactive effluents via this pathway.
4 i ACTION 126 - With the number of channels OPERABLE less than required by the ; ) Minimus Channels OPERABLE requirement, releases via this pathway j j to the environment may continue for up to 7 days provided that: 4
- a. The offgas system is not bypassed, and i b. The reactor building exhaust plenus noble gas effluent
! (downstream) monitor is OPERABLE; i Otherwise, be in at least HOT STANDBY within 12 hours. i. 4 4 i. J
I ODCM 3.0 0 victon 6 Pcco 3.0-14 TABLE 4.3.T.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECM CHECK CALIBRATION TEST REQUIRED
- 1. REACTOR SUILDING EXHAUST PLENUM
- a. Low Range Noble Gas Activity Monitor -
Providing alarm D M R(2) Q(1) *
- b. Iodine Sampler W N.A. N.A. N.A. e
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Sempler Flow Rate Monitor D N.A. R Q e
- 2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)
- e. Noble Gee Activity Monitor D M R(2) Q(1) ese
- 3. STANDBY GAS TREATMENT MONITORING SYSTEM
- a. Low Range Noble Gas Activity Monitor D M R(2) Q(1) a
- b. Iodine Sampler W N.A. N.A. N.A. a
- c. Particulats Sampler W N.A. N.A. N.A. s
- d. Sampler Flow Rate Monitor D N.A. R Q s
ODC2-3. 0 Revision S Pcee 3.0-15 TABLE 4.3.T.12-1 (Continued) RADI0 ACTIVE GASEOUS EFFLUENT MDMITORING INSTRUMENTATION SURVEILLANCE REQUIR N NTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 4 TURBINE BLOG. VENTILATION MONITORING SYSTEM
- a. Low Range Noble Gee Activity Monitor D M R(2) Q(4) e
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Porticulate Sampler W N.A. N.A. N.A. *
- d. Sampler Flow Rate Montter D N.A. R Q
- 5 .' SERVICE DUILDING VENTILATION MONITORING SYSTEM
- e. Low Range Noble Gea Activity Monitor D M R(2) Q(4) *
- b. Iodine Sampler W .N.A. M.A. N.A. e
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Sampler Flow Rate Monitor D N.A. R Q
- 4 1
i i A 1 1
ODCW-3.0 QGv101&n Q Page 3.C-10 TABLE 4.3.7.12-1 (Contipped) RADIOACTIVE GASEOUS EFFLUENT WONITORING IN$TRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECM CALIBRATION TEST REQUIRED
- 6. RADwASTE SUILDING VENTILATION MONITORING SYSTEM
- a. Low Range Noble Gas Activity Monitor D M R(2) Q(4) *
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Sampler Flo: Rete monitor D N.A. R Q *
- 7. ONSITE STORAGE SUILDING VENTILATION EXHAUST RADIATION MONITOR
- a. Low Range Noble Gas Activity Monitor D M R(2) Q(1) *
- b. Iodine Sampler W N.A. M.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Sampler Flow Rate Monitor D 'N.A. R Q
- Nuclear Produ3tien - Fcrai 'd ODCN-3 0 Offolto Dose Calculcticn Nat.st Revision 6 )
P:ga 3 0-17 i l TABLE 4.3.7.12-1 (Continued) l TABLE NOTATIONS e 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 alara setpoint.
- 2. Circuit failure.
3 Instrument indicates a downscale failure.
- 4. Instrument controls not set-in operate mode (alars or type).
(2) 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 j measurement expected during normal operation and anticipated operational 1 occurrences. For subsequent CHANNEL CALIBRATION, sources that have been i related to the initial calibration or are National Irstitute of Standards gg 'Ch and Technology traceable shall be used. (3) Not used. (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation occurs on high level and that control room alara 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.
- 4. Instrument controls not set in the operate mode (alars or type). ,
l Nuclear Producticn - Feral 2 ODCH-3 0
- Offcite Dose Calculation Manual Revicicn 6 j Pag) 3 0-18 1
2 3/4.11 RADIO 4CTIVE EFFLUENTS .l } l I 3/4.11.1 LIQUID EFFLUENTS
- CONCENTRATION-1 l CONTROLS t
t i 3 11.1.1 The concentration of radioactive material released in liquid effluents l .to UNRESTRICTED AREAS (see Figure 3 0-1) shall be limited to ten times i the concentration values specified in 10 CFR Part 20.1001-20.2401,. Appendia B, Table 2, Column 2 for radionuclides other than dissolved
\ f$ ,
\
j or entrained noble gases. For' dissolved concentrationshallbelimitedto2.I10grentrainednoblegases,the i alcrocuries/al total activity. i APPLICABILITY: At all times. ACTION: l j Nith the concentration of radioactive material released in liquid effluents to l j UNRESTRICTED AREAS exot.eding the above limits,'immediately' restore the l j concentration to within the above limits. l l 3 SURVEILLANCE REQUIREMENTS i i 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the rampling 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 i accordance with the methodology and parameters in the ODCM to assure that the I concentrations at the point of release are maintained within the limits of j Control 3 11.1.1. I i i l ) L \ i-1 i 9 s l A -
Nuclear Producticn - Fcrai 2 ODCM-3 0 Offsite Dose Calculation Manual Revicion 6 Pag 3 3 0-19 TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING'AND ANALYSIS PROGRAM Lower Limit Minimus of Detection Lir.id Release Sampling- Analysis Type of Activity (LLD)* Type Frequency Frequency Analysis (uC1/al) A. Batch y'te- P P' Release Each Batch Each Batch Principal Ganna 5 I 10-7 Sample Baitters c Tanks (3) I-131 1 I 10-6 P M Dissolved and' 1 I 10-5 One Batch /M Entrained Gases (Gamma Emitters) P M H-3 1 I 10-5 Each Batch Composite Gross Alpha 1 I 10-I P Q Sr-89. Sr-90 5 I 10-0 Each Batch Composite d Fe-55 1 1 10-6 B Continuous
' Releases
- M PrincipagGanna 5'I 10-7 '
Circulating NA Emitters Water Composited System (if I-131 1 1 10-contaminated) W M Dissolved and- 1 I 10-5 Grab Sample Entrained Gases (Gamma Emitters) M H-3 1 I 10-5 NA Composited Gross Alpha 1 I 10-7 Q Sr-89. Sr-90 5 I 10~0 Composited Fe-55 1 I 10-6
Nuclear Producticn - Fcrai 2 ODCM-3 0 Offsite Dose Calculaticn Manual Revisien 6 Pags 3 0-20 , 1 I TABLE 4.11.1.1.1-1 (Continued) l i j v TABLE NOTATION 1 } aThe LLD is defined, for purposes of these controls, as the smallest
- concentration of radioactive material in a sample that will yield a not count,
- above system background, that will be detected with 955 probability with only
- 55 probability of falsely concluding that a blank observation represents a j "real" signal.
I i For a particular measurement system, which may include radiochemical !_ separation: i 4.66 ab-LLD = E*V 2.22 x 106 . y . ,,p (, y g) j vhere: l LLD is the "a priori" lower limit of detection as defined above, as-microcuries per unit mass or volume, i 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 106 is the number of disintegrations per minute per microcurie, ] Y is the fractional radiochemical yield, when applicable, ! histheradioactivedecayconstantfortheparticularradionuclide,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 priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. 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 ODCN to assure representative sampling.
.,.- - - - . ~ , .-- .
i Nuclear Producticn - Firai 2 ODCH-3 0 Offsite Dose Calculcticn Manual Revicion 6 2 Page 3 0-21 l i TABLE 4.11.1.1.1-1 (Continued) TABLE NOTATION
- cThe principal ganna esitters for which the LLD specification applies 4
exclusively are:. Mn-54, Fe-59, Co-58, Co-60, In-65 P.o-99, Cs-134, Cs-137, Co-141, and Ce-144. h is does not mean that only these nuclides are to be i considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive l 0jg Effluent Release Report pursuant to Control 5.9.1.8. d A composite sample is one in which the quantity of liquid samples is 4 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 released. his may be accomplished through composites of grab samples obtained prior to discharge after the tanks have been recirculated. 8 A 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. i l i 1 i i s 4 4 h 4 t
Muclear Producticn - Fcr:21 2 ODCN-3 0 Offaite Dose Calculaticn Manual Revicion 6 ]! Pag) 3 0-22 i RADIOACTIVE EFFLUENTS j DOSE i i i CONTROLS I l 1 ! 3 11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC froa radioactive materials in liquid effluents released, from each reactor unit, to l UNRESTRICTED AREAS (see Figure 3 0-1) shall be limited:
. l 4
i a. During any calendar quarter to less than or equal to 1.5 areas to the j j total body and to less than or equal to 5 areas to any organ, and : 1 b. - During any calendar. year to less than or equal to 3 areas to. the ] total body and to less than or equal to 10 areas to any organ. S APPLICABILITY: At all times.
- i. ACTION:
I
- s.
j With the calculated dose from the release of rsdioactive materials in ' liquid effluents exceeding any of the above limits, prepare and j submit to the Commission within 30 days, pursuant to Technical i Specification 6.9.2, a special Report that identifies the cause(s) ! for exceeding the limit (s) and defines the corrective actions that i have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in i compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of tlne drinking ! water source and (2) the radiological impact on finished drinking
- water supplies with regard to the requirements of 40 CFR Part 141,
- . Safe Drinking Water Act.'
i
- b. The provisions of Controla 3 0 3 and 3 0.4 are not applicable.
i ! , SURVEILLANCE REQUIREMENTS a 5 4.11.1.2 Cumulative dose contributions from liquid effluents for the current ] calendar quarter and the current calendar year shall be determined in scoordance with the methodology and parameters in the ODCM at least once per 31 < days. f I ]
' Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.
i
Nuclear Producticn - Fcrai 2 ODCN-3 0 Offolte Dose Calcul0ticn Manual Revicion 6 Pag 7 3 0-23 RADIOACTIVE EFFLUENTS LIQUID WASTE TREATNENT CONTROLS 3 11.1 3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the systes 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 Figure 3 0-1) would exceed 0.06 ares to the total body or 0.2 ares to any organ in any 31-day period. APPLICABILITY: At all times. ACTION:
- a. Nith radioactive liquid waste being discharged and in excess of the above limits and cny portion of the liquid 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 of why liquid radwaste was being discharged without complete treatment, identification of any inoperable equipment or subsystems, and the reason for the inoprability.
- 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 REQUIRENENTS 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 ODCN. l 4.11.1 3 2 The installed liquid radwaste treatment systes shall be demonstrated OPERABLE by meeting Controla 3 11.1.1 and 3 11.1.2.
]
l
i f Nuclear Producticn - Fcr::12~ j Offaite Dose Calculatien Manual ~0DCM-3 Revicicn 06 j Paga 3 0-24 i RADI0 ACTIVE EFFLUENTS i 3/4.11.2 -GASEOUS EFFLUENTS l s DOSE RATE i i l CONTROLS i 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 i j 3 0-1) shall be limited to the following: i j a. For noble gases: Less than or equal to 500 aress/yr to the total l j body and less than or equal to 3000 acess/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 i equal to 1500 aress/yr to any organ.
] j APPLICABILITY: At all times. i ACTION: l 1 With the dose rate (s) exceeding the above limits, immediately restore the j release rate to within the above limit (s). i j SURVEILLANCE REQUIREMENTS I 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be I determined to be within the above limits in accordance with the methodology and l parameters in the ODCN. i
- 4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all other j radionuclides in particulate form with half-lives greater than 8 days in-j gaseous effluenta shall be determined to be within the above limits in
' accordance with'the methodology and parameters in the ODCM by obtaining s reprementative samples and performing analyses in accordance with the sampling i and analysis program specified in Table 4.11.2.1.2-1. i 1 i L i 4 i I' . __ . _ _ __ _. . _ ..
00CM 3.0 Ocvision G P:ge 3.0-25 TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM utntmum Lower Limit of Sempting Analyste Type of Detection (LLD)* Geseous Release Twee Freauency Frecuency Activity Analvete (uct/et) Pi. 53 9 9 53 A. Containment PURGE Each PURGE Each principal Gamme Emittersb 1 a 10 (Pro Treatment) Grab Sample P(URGE H-3 1 m 10 B. Reactor Building Mc.d.e uc Principal Gamma EmittersD 1m 10'* Exhaust Plenum Grab Sample MC H-3 1m 10-6 Standby Gas Tgest-ment System C. Redweste Bu11 ding M M Principal Gemme Emittersb 1 m 10~4 i 10-6 Turbine Su11 ding Grab Sample M H-3 1 a Service Building On-Site Storage Fac411tv f w9 D. All Release Types Continuous I-131 1 m 10-12 as Itsted in 9 Adeorbent I-133 1 a 10-10 and C obove. Semple Continuous f w9 Principal Gamme EmittersD 1 m 10~I1 Particulate (I-131 others) samoie Continuous # M Gross Alpha 1m 10~11 Composite Particulate Sample f Continuous Q Sr-89. Sr-90 1 m 10-13 Composite Particulate Samole Continuous f Noble Gas Noble Gas 1 a 10~8 Monitor Gross Bete or Gamme E. Weste 011 P P Principal Gamme Emitterab 5m 10'I Incineration by Each Batch Each Batch I-131 1m 10-6 Injection into Aum111ery Botter waste 041 Licuid $ ample y j Fuel Stream
1 I Nuclear Production - F rci 2 ODCH-3 0 Offsite Dose Calculation Manual Revision 6 ) P:ss 3 0-26 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 955 probability with only 55 probability of falsely concluding that a blank observation represents a "real" signal. For a particular naasurement system, which may include radiochealcal separation: 1 4.66 ab LLD
- E
- V
- 2.22 x 106.y.exp(-At)
Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, Aistheradioactivedecayconstantfortheparticularradionuclide,and l 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 priori (before the fact) limit representing the capability of a measurement system and not as an ,a,, posteriori (after the fact) limit for a particular measurement. bThe principal samma emitters for which the LLD spicification applies exclusively are the following radionuclides: Kr-C ? i -88, Ie-133, Ie-133m, Ie-135, and Ie-138 in noble gas releases and Mn-54, + 39, Co-58, co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Co-144 in . Jine and particulate releases. This list does not mean that only these nuclides are to be considered. Other ganaa peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual l \t[O Radioactive Effluent Release Report pursuant to Control 5.9.1.8.
Nuclear Production - Fcrai 2 ODCN-3 0 l Offolte Dosa Calculaticn Manual Revicion 6 Pega 3 0-27 TABLE 4.11.2.1.2-1 (Continued) , l TABLE NOTATION cSampling and analysis shall also be performed following shutdown, startup, i or a THERNAL 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 I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3 dTritius grab samples shall be taken at least once per 24 hours when either the reactor well or the dryer-separator storage pool is flooded. l
' Tritium grab samples shall be taken at least once per 7 days from the j ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
IThe ratio of the sample flow rate to the sampled strema flow rate shall be l known for the time 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 i 8Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days fullowing each shutdown, startup or THERNAL POWER change exceeding 15% of RATED i THERMAL POWER in 1 hour and analyses shall be completed within 48 hours of _ changing. When samples collected for 24 hours are analyzed, the corresponding LLDs any be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas , monitor shows that effluent activity has not increased more than a factor of 3 I hRequired when the SGTS is in operation. i In OPERATIONAL CONDITIONS 1, 2, 3, and 4, the applicable portion of primary containment shall be sampled and analyzed within 8 hours prior to the start of any PURGING. 3In OPERATIONAL CONDITIONS 1, 2, 3, and 4, when the primary containment atmosphere radiation monitoring system is declared INOPERABLE or is in alara
.h condition, the applicable portion of primary containment shall be sampled and analysed within 8 hours prior to the start of any VENTING or PURGING and at least once per 12 hours during VENTING or PURGING through other than SGTS.
i
! Nuclear Producticn - Fcrai 2 ODCN-3 0 l~ 0ffaite Dose Calculaticn Manual Revision 6 [ Paga 3 0-28 l- { RADIOACTIVE EFFLUEN"!S i
- DOSE - NOBLE GASES i
i i 1 ! 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 arads for sanaa l radiation and less than or equal to 10 mrada for beta radiation and, 1
- b. During any calendar year
- Less than or equal to'10 arads for gamma radiation and less than or equal to 20 arads for beta radiation.
i APPLICABILITY: At all times. j ACTION: 4 1 a. With the calculated air dose from radioactive noble gases in gaseous j effluents exceeding any of the above limits, prepare and submit to i the Commission within 30 days, pursuant to Technical Specification i 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 j to reduce the releases and the proposed corrective actions to be.
- taken to assure that subsequent releases will be in compliance with i the above limits, i.
j b. The provisions of Controla 3 0 3 and-3 0.4 are.not applicable.. I SURVEILLANCE REQUIREMENTS i 4.11.2.2 Cumulative dose contributions for the current calendar quarter and 4 current calendar year for noble gases shall be determined in accordance with j the methodology and parameters in the ODCN at least once per 31 days. l i i i i 4 i J } ) i
3 Nuclear Producticn - Fcr;i 2 ODCM-3 0 , Offcite Dose Calculatien Manual Ravicion 6 Pap 3 0-29 i 2 RADIOACTIVE EFFLUENTS i
- GASEOUS EFFLUENTS DOSE - IODINE-131. 10 DINE-133. TRITIUH. AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS _
1 3 11.2 3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, i tritius, and all radionuclides in particulate form with half-lives greater than l , 8 days in gaseous effluents released, from each reactor unit, to areas at and j 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 7 5 areas to any
- organ and,
- b. During any calendar year: Less than or equal to 15 areas to any l organ. l APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of iodine-131, iodine-133, tritius, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of t.he above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that l 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 I 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 tr.o current calendar quarter and current calendar year for iodine-131, iodine-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.
I Nuclear Production - Feral 2 ODCM-3 0 ! .Offeito Dose Calculaticn Manual Revicien 6 j Page 3 0-30 i 1 RADIOACTIVE EFFLUDITS l' 0FF-GAS TREA'DIENT SYSTEM CONTROLS ( i
~
! 3 11.2.4. The OFF-GAS TREATMENT SYSTEM shall be OPERABLE and shall be in ' operation. l- ! APPLICABILITY: Whenever the main condenser staan jet air ejectors are in l operation. 1 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. Identification of the 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 Controla 3 0 3 and 3 0.4 are not applicable.
- c. The provisions of Control 4.0.4 are not applicable.
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
7 ' Nuclear Productica - Fcrai 2 ODCN-3 0 . . j Offaite Dose Calculation Manual Revision 6 Paga 3 0-31 i I 'RADI0 ACTIVE EFFLUENTS j VENTILATION EIHAUST TREATMENT SYSTEM ! CONTR0tS i i ! 3 11.2.5 The VENTILATION EIHAUST TREATMENT SYSTDi as described in the ODCN l ahall be OPERABLE and appropriate 3 rtions of the system shall be used to i reduce radioactive materials in gat aus waste prior to their discharge when the , } projected doses due to gaseous affla nt releases from the site to UNRESTRICTED ! j AREAS (see Figure 3 0-1) would exceed 0 3 ares to any organ in any 31-day. ! period. j APPLICABILITY: At all times. j ACTION: > i ! j- a. Nith radioactive gassous waste _being discharged in excess of the l l 'above limits and any portion of the VF"TILATION EIHAUST TREA1NENT l SYSTEM not in operation, prepare and submit to the Commission within ;
- 30 days pursuant to Technh al Specification 6.9 2 a Special Report i j that includes the following information
- !
j 1. Identification of any inoperable equipment or subsystems, and j the reason for the inoperability, i
- 2. Action (s) taken to restore the inoperable equipment to j oeERAntE status, and i I i 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. i $ SURVEILLANCE REQUIREMENTS l i I 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at i least once per 31 days in accordance with the methodology and parameters in the ODCM, when any portion of the VENTILATION EIHAUST TREA1NENT SYSTEN is not in' 4-use.- i j 4.11.2.5.2 The VENTILATION EIHAUST TREATMENT SYSTEN shall be demonstrated OPERABLE by meeting Controls 3.11.2.1, 3 11.2.2, and 3 11.2 3 i l
- e
Nuclear Producticn - Pcrai 2 ODCM-3 0 Offalto Dose Calculatien Manual Revicion 6 Pag) 3 0-32 RADIOACTIVE EFFLUENTS VENTING OR PURGING CONTROLS 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 -(,h ACTION: a.- Nith the requirements of the above control not satisfied, suspend all. VENTING or PURGING of the primary containment. Q '}
- b. The provision of Controls 3 0 3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS , I 4.11.2.8.1 The applicable portion of primary containment shall be sampled and analysed per Table 4.11.2.1.2-1 of Control 311.2.1 within 8 hours prior to the start of any PURGING. 4.11.2.8.2 -If the primary containment radiation monitoring system is %) INOPERABLE or is in alara 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 hours prior to the start of and at least once per 12 hours during VENTING or PURGING of primary containment through other than the ; standby gas treatment system. l 4.11.2.8 3 The primary containment shall.be determined to be aligned for l VENTING or PURGING through the standby gas treatment systes or the reactor building ventilation system within 4 hours prior to start of and at least once per 12 hours 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. 1henever the vent / purge system is-in use 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 $3 one division), or the SPING monitor corresponding to the release path (the reactor building exhaust plenum radiation monitor or the standby gas treatment system radiation monitor, Division 1 or 2).
Nuclear Producticn - Farsi 2 ODCH-3 0 Offaite Dose Calculaticn Manual Revicion 6 Page 3 0-33 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE-CONTROLS 1 3 11.4 The annual (calendar year) dose or dose commitment to any member of the gs
.public (as defined in 40 CFR Part 190) due to releases of radioactivity and to radiation from uranius fuel cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.
APPLICABILITY: At all times. l ACTION:
- a. With the calculated doses from the release of radioactive materials ;
in liquid or gaseous affluents 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 l subsequent releases to prevent recurrence 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 include an analysis that estimates the radiation exposure lof ' I (dose) to a seaber of the public from uranium fuel cycle sources, pQ l 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 l radioactive material involved, and the cause of the exposure levels I or concentrations. If the estimated dose (s) exceeds the above - limits, and if the release condition resulting in violation of 40 CFR l Part 190 has not already been corrected, the Special Report shall ' include a request for a variance in accordance 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.
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 i units and from outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. ittis requirement is applicable only under conditions set forth in Control 3 11.4, ACTION a. 1 I
Nuclear Produstion - Forni 2 ODCN-3 0 Offaite Dose Calculation Manual Revisicn 6 Paga 3 0-34 3/4.12 RADIOLOGICAL ENVIRONNDITAL MONITORING 3/4.12.1 NONITORING PROGRAN CONTROLS - 3 12.1. The radiological environmental monitoring program shall be conducted aa , 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 12.1-2 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 NENBER 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 12.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (21 + ...>
~
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 doses to A M MBER 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 were unavailable any then
'The methodology used to estimate the potential annual dose to a NENBER OF THE PUBLIC shall be indicated in this report.
Nuclear Producticn - Fcrai 2 ODCM-3 0 j Offcite Dose Calculaticn Manual R vision 6 P:ge 3 0-35 RADIOLOGICAL ENVIRONMENTAL MONITORING ) I CONTROLS (Continued) be deleted from the monitoring program. Pursuant to Control 5.9.1.8, l 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 Report pursuant to Control 5.9.1.8 and l\\S$ 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 l l 4.12.1 The radiological environmental sonitoring samples shall be collected i 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.
)
1 i
DDCW 3.0 caviston 0 Prge 3.0-33 TABLE 3.12.1-1 RADIOLOGICAL ENVIROIWENTAL MONITORING PROGRAN Number of Representative Exposure Pathway $amples and Sampling and Type and Frequency and/or 5= mote Sample Locations, Collection Freauency of Analysis 1 DIRECT RADIATIOND 37 routtne monitoring stations. Quarterly Gamma dose Guarterly. with two or more dosimeters pieced as follows: 1) en inner ring of stations in the general area of the SITE BOUNDARY and additional rings at approximately 2. 5 and 10 miles, with a station in at least every other meteorological sector for each ring with the exception of those sectors over Lake Erie. The balance of the stations, 8. should be placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.
- 2. AIRDORNE Radiotodine and Samples from $ locations. Continuous sampler Radiciodine Cannisterr Particulates operation with sample 1-131 analysis weekly.
- s. 3 semples from close to collection weekly, or the 3 SITE BOUNDARY loca- more frequently if tions, in different sectors, required by dust Porticulate Samoters of the highest calculated loading. Gross beta radioactivity annual average ground- analysts following level D/Q. filter changen d
- b. 1 sample from the vicinity of Gamma isotopic analysis' a community having the highebt of composite (by calculated annual average location) quarterly.
groundlevel D/Q.
ODC3-3.0 Rovision 8 Page 3.0-37 TABLE 3.12.1-1 (Continued) RADIOLOGICAL ENVIRONMENTAL IIONITORING PROGRAas Number of Representative Emposure Pathway Samples and sempling and and/or Sample Sample Locations, Type and Pesquency Collection Frecuency of Analysis
- c. 1 sample from a control location, as for example 15-30 km distant and in the least prevalent wind
- directionC. N ( ')
- 3. WATERBORNE
- a. Surface f a. 1 semple upstream. Composite sample over
- b. 1 sample downstream.
Gemma isotopic analysis' 1-month period 9 monthly. Composite for tritium analysis quarterly
- b. Ground Samples from 1 or 2 sources Quarterly Ganwa isotopic
- and only if itkely to be tritium analysis affectedh. quarterly.
- c. Drinking a. 1 sample of each of 1 to Composite semple 1-131 enelysis on each 3 of the nearest water over 2-week period 9 composite when the dose supplies that could be when 1-131 analysis affected by its discharge. calculated for the is performed. monthly consumption of the water composite otherwise is greate 1 mrom
- b. 1 sample from a per year.y thenComposite control location for gross bete and gamma isotopic analyses
- monthly. Composite for tritium analysis cuarterly
- d. Sediment 1 semple from downstream area Semiennus11y from with existing or potential Gannia isotopic analysis' shoreline semiennually.
recreational value.
OOCW-3.0 l Covisitn 6 Pag) 3.0 . TABLE 3.12.1-1 (Continued) RADIOLOGICAL ENVIROpesENTAL MONITORING PROGRAN l
- l. Number of Representative Exposure Pothway Samples and Sempting and Type and Proovency i and/or Semolo Semote Locations
- Co11ection Freauency of Analysis 4 INGESTION Gamma isotopic
- and
- a. Milk m. Samples from milking animals Semimonthly when in 3 locations within 5 km animals are on I-131 analysts semimonthly distance having the highest pasture, monthly at when animals are on dose potential. 'If there other times pastures monthly at are none, then. I sample other times.
from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated than 1 mrom per yr to be gpeater
- b. 1 sample from milking animals at a control location 15-30 km distent and in the feest prevalent wind direction
- b. Fish and a. 1 sample of each commercially Sample in season, or Gamme isotopic analysis' Invertebrates and recreationally important semiennually if they 'on edible portions.
species in vicinity of plant are not seasonal discharge area,
- b. 1 sample of same species in areas not influenced by plant discharge,
- c. Food a. 1 sample of each principal At time of harvest 3 Gamme isotopic enelyses*
Products class of food products from on edible portions. any area that is irrigated i by water in which Itguid plant westes have been discharged.
ODC~-3.0 Ocviolen 6 Ps@o 3.0-39 TABLE 3.12.1-1 (Continued) RADIOLOGICAL ENVfRONEBENTAL IBOMITORING PROGRAM Number of Representative Exposure Pathway Samples and Sampitne and Type and Frequency and/or Sample Sample Locations" Collection Frequency of Anotysie
- c. Food b. Samples of 3 different kinds Monthly when Gamma' isotopic' and Products of broad leaf vegetation grown available 1-131 analysis.
(cont'd) nearest each of two different offsite locations of highest predicted annual average level D/Q if milk esmoling is not performed.
- c. 1 emmple of each of the similar Monthly when Gamma isotopic' and broad leaf vegetation grown available 1-131 analysis.
15-30 km distant in the least prevalent wind direction if milk sampling is not performed.
Nuclear Production - Fcrai 2 ODCM-3 0 Offaito Dose Calcul0 tion Manual Revisien 6 Pag 2 3 0-40 ! l TABLE 3.12.1-1 (continued) TABLE NOTATIONS
" Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for I each and every sample location in Table 3 12.1-1 in a table and figure (s) in !
.the ODCN. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Asma=== ant Branch Technical Position, Revision 1, November 1979. Deviations are permitted from t.he required sampling schedule if specimens are unobtainable due to hasardous conditions, seasonal unavailability, aalfunction of automatic sampling equipment and other legitimat.e reasons. If specimens are unobtainable due to sampling equipment aalfunction, every effort shall be made to complete corrective action prior to t.he end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological lDg l
Environmental Operating Report pursuant to Contol 5 9.1.7. It is recognized that, at times, it may not be possible or practicable to ecntinue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 i 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 ODCN 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 phosphers 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 optinua dose information wfth 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. d Airborne particulate sample filters shall be analysed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daught.or decay. If gross beta activity in air particulate semples is greater than 10 times the yearly mean of control samples, gnana footopic analysis shall be performed on the individual samples.
" Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides t. hat any be attributable to the affluents from the facility.
1
Nuclear Producticn - Fcrai 2 ODCM-3 0 Offolto Do o Calculcticn Manual Revision 6 P2gs 3 0-41 TABLE 3.12.1-1 (Continued) TABLE NOTATION I The 'spatream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the sizing tone. " Upstream" samples in an estuary must be ttken far enough upstream to be beyond the plant influence. 8Composite samples should be collected with equipment (or equivalent) which is capr,ble of collecting an aliquot at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly). kroundwatersamplesshallbetakenwhenthissourceistappedfordrinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. I The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. dIf harvest occurs riore than once a year, sampling shall be performed during each di.screte harvest. If harvest occurs continuously, sampling shall be sonthly. Attention shall be paid to including samples of tuberous and root food products.
I t i N l en e OCD t au
- M e ti i O e e
>0 g
- 4) e y e 0 86 **
U ** so i UB C D O
- O O O LO O O O g as e *
- q %
- N Ve OU OO l eL w m
e M O O O g % G b O l w me M
-O m *O Ew
>= a ^
, N 4 e l e,
- a g 2 e
O O O O O O- O e I g g % O O O O O O O e l r y y , fe 30 O. O. O. O. O. O. O e y p g - G O O O O O *- N
- S M O E* O " O " N 9 I 4 M Q "
s.e g e ** i i p e L . y a ! i CL t E9 l
. -E g !
g DN E l
< u ~- u l g "U i
*O O -
Lw g a @ i g &O e e ! e O O O e g to e N y Ce L $$ .e-O L DL e a to 4 a e l y g a e O O O O O O O N O O O P e a L% O O O O O O O M en O L ee O O 4 0 89 M 4 N e l 90 e e e e i eQ O e e e l Sw N B S C e-
.it O C e en 4 =-
*- O e L e 4 4 h 9 V
> T S e O an D e MM e e en en an @ @ Z M e e .J L e 49 8 0 9 0 0 0
- O I I O C 1 C e O O C L i o e o GL 4 Z S L U U N N w U U 8 e i
I I
)
Y r d 0 0 5 8 t . 1 1 nS 3 .k 64 . /
- s1
- 0. tn0 a.CD 3t 3 s(
3 Cwp 2
- 1 D0o .)
ORP tt ee vw o. o rm 0 0 0 6 6 8 Pk
* /
5 o1 I oC S oo Y r( L A t t A E L ) P p l 1 5 8 5 a C. / 1 1 1 A b k1 S ) iC O t D L A L L
"(
T ( N ) 1 E N t
- N O e 1 N I w O T 2
t 8 C . 1 1 E m
. V T k 0 0 0 0 0 0 4 N E / 3 6 3 6 3 5 E D "1 1 2 1 2 1 1 E 'C L R F ' p B O O '(
A F T T S I E M I I ' T L I L R
'5)m 1 E 'u /
8 W c1 A O iC P L t p A r( 1 7 5 6 C a 0 0 0 0 Ps N e 0 0 0 0 O es I na T rG C o E br T ro E i D A
) d 1 4 0 5 10 5 0 5 I 5 8 5 r/ 0 3 1 3 1 1 1 1 e9 0 tC 2 ao w(
a t 0 s e 0 5 4 i b 6 9 1 e - 4 7 - v s 4 9 8 5 b 1 3 3 o i s 5 5 5 6 M 3 1 1 L s o 3 - - - - - 1 - - - n r - n eF oC nZ r -Z s o e A g H u I C C S
Nuclear Producticn - Fcrai 2- ODCN-3 0 4 Offoits Dose Calculation Manual R3violon 6 ! P2gs 3 0-44 } I TABLE 4.12.1-1 (Continued) ! TABLE NOTATIONS "This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analysed-and reported in the Annual Radiological Environmental
. Operating Report pursuant to Control 5.9.1 7.
DRequired detection capabilities for thermoluminescent dosimeters used for l j environmental measurements are given in Regulatory Guide 4.13 j c1he LLD is defined, for purposes of these Controls, as the smallest { concentration of radioactive material in a sample that'will yield a not count, j above system background, that will be detected with 955 probability with only j 55 probability of falsely concluding that a blank observation represents a i "real" signal. t For a particular measurement system, which may include radiochemical separation: l 4.66 sb E*V 2.22
- Y
- exp (- A t) j Where:
! LLD is the "a priori" lower limit of detection as defined above, as
! picocuries per unit mass or volume, l
sb is the standard deviation of the background counting rate or of the l
- counting rate of a blank sample as appropriate, as counts per minute,
! E is the counting efficiency, as counts per disintegration, I I, V is the sample size in units of mass or volume, 1 I 2.22 is the number of disintegrations per minute per picocurie, 1 { Y is the fractional radiochemical yield, when applicable, i' ) Aistheradioactivedecayconstantfortheparticularradionuclide,and 1 j t for environmental samples is the elapsed time between sample
, collection, or end of the sample collection period, and time of counting l Typical values of E, V, Y, and t should be used in the calculation.
) i i i l' 1 _ -
i Nuclear _ Production - Fcr:1 2 ODCM-3 0 i Offsits Dose Calculation Manual Revision 6 Pagn 3 0-45 1 TABLE 4.12.1-1 (Continued) TABLE NOTATIONS It should be recognized that the LLD is defined as an a priori (before the i fact) limit representing the capability of a measurement system and not as an a posteriori (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 any render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual . l Radiological Environmental Operating Report pursuant to Control 5 9.1.7. ! LLD for drinking water samples. l l l l l 1 I l l l l l
! Muclear Production - F rci 2 ODCN-3.0' j' Offaite' Dose Calculaticn Manual Revision.6 P gs 3 0-46' ! l RADIOLOGICAL ENVIRONMENTAL MONI10 RING I 4 3/4.12.2 LAND USE CENSUS CONTROLS
-3 12.2 A land use census'shall be conducted and shall identify within'a i distance of 8 km _(5 miles) the location in each of the 16 meteorological
- sectors garden *ofofLthe nearest greater milk than 50 m pinal, (500 fty) nearest residence producing broad leafand the~ nearest ~
vegetation. ! APPLICABILITY: At all times.
. ACTION:
. a. With a land use census identifying a location (s) that yields a , calculated dose or dose commitment groater than the values currently being calculated in Control 4.11.2.3, identify the new location (s) in the next Annual' Radioactive 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 esposure' pathway) 20$ greater than ata location from which samples are currently,being l obtained in accordance with Control 3 12.1, add the new location (s) I to the radiological environmental monitoring prograg 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, any 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 ON report a revised figure (s) and table for the ODCN reflecting'the new location (s). l
- c. The provisions of Control 3 0 3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per.12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by 4 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 samplics of at least three different kinds of vegetation any be performed at the SITE BOUNDARY in each of two different direction sectors with the highest' predicted D/Qs in lieu of the garden oensus. Controls
.for broad leaf vegetation sampling in Table 312.1-1, Part 4.c, shall be followed, including analysis of control samples.
- Nuclear Productitn - Fcr;i 2 ODCH-3 0 L Offcits Dose Calculation. Manual Revicien 6 Pags 3 0-47 i
RADIOLOGICAL ENVIRONMENTAL MONITORING j 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ! CONTROLS ! 3 12 3 Analyses shall be performed on radioactive materials supplied as part j of an Interlaboratory Comparison Program that has been approved by the
- Commission.
i , APPLICABILITY: At all times. ACTION: l a. . With analyses not being performed as required above, report the l ' corrective actfons taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to i Control 5.9.1 7 j b. The provisions of Controls 3 0 3 and 3 0.4 are not applicable. ) i l SUHVEILLANCE REQUIREMENTS 1 l 4.12 3 The Interlaboratory Comparison Program shall be described in the ODCH. 2 A summary of the results obtained as part of the above required-Interlaboratory i Comparison Program shall be included in the Annual Radiological Environmental
- Operating Report pursuant to Control 5.9.1.7.
I i d l 1 i t 1
/
k l e f
I.
'%J . j ."
.[
.p ==
esomaal RA010t0CICAL RELEASE POIN15 A un. osw.
%. , As-.
/
- g ;g me e une t/ x nK
---- um unisiertu, D+ ~j, s Estm"s Amene &p .
, */
\-
I
,( 5 nota saueani / j h il p$
CASE 0uS RELEASE ELEva11cw5 fp/ p-
'?p g/
/ gs E **
g
- i. =ae,= sun.1=
- 1. -su
,.n.-
- is , ,,
. n, , , o y f 6 i -
E
- i. -sm s
< sennet wasu
.n . - . , ,
-- no
.n s,,s oF ,}/,f . '
/ LAKE pl s ,.
; s. - - to x .,
[
.,,, 7 g x" H N //
.4' n e
e N; U 'L
/ eme
,3 at x s y A c:
eM
/
,f f, - o _. .u.s. _.,
c3 ?Mn . -
/ -
ggg .
- 'g 3 (y.[efp ,s f stE E= . aced m .
,j) ff-
,O
- ig{ $ -
Q9 ,
- u. a'g
(
/ ~
l . I
=,=
g;-
/
ff g . , r,- - - - - - - g ae
,I lI ) /
l
; r. =~m .nor.
- s. *sm si.au unex I ~.
lI y l - in -
\
E
,I l 69 A ll lLD
'.sm uww PEnux 1 n 1 e .. _ __
ch %s%
- s%sss
(~c . - - Wl
\
. j 0-gI
' N'.*q g%%
agg y le g j s 1 es - f.%\ m s . > - -< - ENLARGED VIts re o E o.
) } . a l sf n/ u .I E i s _
_/ J ..
Muclear Producticn - Far21 2 ODCM-4.0 1 Offsito Dose Calculatien Manual Revisien 6 Pcga 4.0-1 i-I l l I l 1 SECTION 4.0 BASES i L I AIBIS - IW0ilNATIM SERVICES , Date approved: Release authorized by: Change numbers incorporated: 93-117-0DN DSN Rev 6 Date DTC TMPLAN File 1715.02 Recipient
._.__ .. = _ . . _ _ _ . . _ _ ._ ._ .
Nuclear Productica - Fer;::1 ODCN-4.0
- Offaite Dose Calculation Manual Revicien 6 P:ge 4.0-2
- INSTRUMENTATION' BASES 3/4.3 7.11 RADIOACTIVE LIQUID EFFLUENT MDNITORING IMSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to
, monitor. and control, as applicable, the releases of r/adioactive; materials in liquid effluents during actual or potential releases of liquid offluentsk The ,
alare/ trip setpoints for these instruments shall be c.alculated and adjusted in .)
- accordance with the methodology and parameters in the ODCM to' ensure that the.
. alars/ 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
)
The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous affluents during actual or potential releases of gaseous affluents. The alara/ trip setpoints for:these instruments shall be calculated and adjusted in accordance with the methodology and parameters in tJw ODCN utilizing the systen design flow rates as~specified in the ODCN. Thi.s conservative method is. used because the Fermi 2 design does not include flow rate asasurement-devloes. This will ensure the alara/ 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-if 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive 2
'I materials released in liquid unste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in-10 CFR Part gg3 20.1001-20.2401, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within'(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to a IEMBER OP THE PUBLIC. The 0 %}
concentration limit for dissolved or entrained noble gaaes is based upon the assumption that Ie-135 is the controlling radioisotope und its MPC in air (submersion) was converted to an equivalent concentration in unter-using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. The required detection capabilities for radioactive materials in liquid unste samples are tabulated in teras 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), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968)', and Hartwell, J. E.,." Detection Limit.s for Radionnalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARN-SA-215 (June 1975).
. . . . - ~ . - . -. - . _._
Nuclear Producticn - Fcr21 2 ODCM-4.0 Offaite Dose Calculaticn Manual Revision 6 , Pega 4.0-3 i , RADIOACTIVE EFFLUENTS 1 BASES , 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, l III.A, and IV.A of Appendix I, 10 CFR Part 50. The control implements the guides set forth in Section II.A of Appendir I. 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 l radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as
- -l
' low as is reasonably-achievabla." Also, for fresh water sites with drinking BSg
. water supplies that can be potentially affected by plant operations, there is 1 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 CPR Part 141. The dose calculation methodology and ,
parameters in the ODCM implement the requirements in Section III.A of Appendix l I 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 equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents -l are consistent with the methodology provided in Regulatory Guide 1.109, I
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic 1 Dispersion of Effluents from Accidental and Routine Reactor Releases'for the Purpose of Implementing Appendix I," April 1977 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid affluents require treatment prior to their release to the environment. The requirement that the appropriate portions of this systes 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 II.D of Appendix.I to 10 CFR Part 50. l The specified limits governing the use of appropriate portions of the liquid radweste treatment system were specified as a suitable fraction of the dose I design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for ; liquid effluents. 3 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 affluents from all units on the site will be within the bq') limits of 10 CFR Part 20.1301.
Nuclear Producticn - Fgrei 2 ODCM-4.0 Offsito Dose Calculatien Manual R: vision 6 Paga 4.0-4 RADI0 ACTIVE EFFLUDITS BASES 3/4.11.2.1 DOSE RATE (Continued)
-Although this control applies to the SITE BOUNDARY, the occupancy and exposure
, pathways applicable to a MEMBER OF THE PUBLIC who any at. times be within the SITE BOUNDARY vill usually be such that such an individual will not receive MI\Q
.significantly greater dose due to gaseous effluents than a MEMBER OF THE'PUBLIC who remains outside the SITE BOUNDARY. Examples'of calculations for such MEMBERS OF 11E 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 beyond the SITE BOUNDARY to less than or equal to 500 acess/ year to the. total body or to less than or equal to 3000 aress/ 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 than or equal to 1500 arems/ year.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of tho' 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. E., " 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 II.B, III. A, and IV.A of Appendix' I,10 CFR Part 50. The control implements the guides set forth in Section II.B of Appendix I. 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 laplement the requirements in Section III.A of Appendix I 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 IBMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM 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 l 1.109, " Calculation of Annual Doses-to Man from Routine Releases of Reactor I Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estinating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine ! Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. i
. - . , -,m. ..-._, - -.._.___...._e..--, , , , ,.e,_. ,-m- , , .
j- Nuclear Producticn - Fcrci 2 ODCN-4.0
- Offsito Dose Calculaticn Manual ~ R3 vision 6 l Pcgs 4.0-5 1
l
- j. RADIOACTIVE EFFLUENTS i ' BASES i
i- 3/4.11.2.3 DOSE - 10 DINE-131. 10 DINE-133. TRITIUN, AND RADIONUCLIDES IN I' PARTICULATE FORN i l This control is provided to implement the requirements of Sections II.C, III.A, j ' and IV. A of Appendix I,10 CFR Part 50. The controls are tho' guides set forth
- in Section II.C of Appendix I. The ACTION statements provide the required.
! . operating flexibility and at the same time implement the guides set forth in i Section IV.A of Appendix I to assure that' t,he releases of radioactive materials !
i in gaseous effluents to UNRESTRIC17,D AREAS will be kept "as low as is- l
- reasonably achievable." The ODCN calculational methods specified in the l Surveillance Requirements. implement the requirements in Section III.A of l Appendix I that conformance with the guides of Appendix I be shown by- ;l, i calculational procedures based on models and data, such that the actual l exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCN calculational methodology and-i parameters for calculating the doses due to the actual release rates of the i i subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of j Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, j Appendix I," Revision 1, October 1977 and Regulatory gu_ide 1.111, " Methods for j Estinating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine 1 Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These j equations.also provide for determining the actual doses based upon the i historical average atmospheric conditions. The release rate controls for
{' iodine-131, iodine-133, tritium, and radionuclides in particulate. form with i half lives greater than 8 days are dependent upon the existing radionuclide l pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways , that were examined in the development of these calculations were: (1) j individual inhalation of airborne radionuclides, (2) deposition of
- radionuclides onto green leafy vegetation with subsequent consumption by man,
' (3) deposition onto grassy areas where milk animals and meat producing animals grase with consumption of the milk and meat by man, and (4) deposition on the j ground with subsequent exposure of man. 1 ) I 3/4.11.2.4 0FF-CAS TREATMENT SYSTEN i The OPERABILITY of the OFF-GAS. TREATMENT SYSTEM ensures that the systes ! will be available for use whenever gaseous effluents require treatment prior to i release to the environment. The requirement that the appropriate portions of ; i 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 i Design Criteria 60 of Appendix A to 10 CFR Part 50, and the design objectives
- given in Section II.D of Appendix I to 10 CPR Part 50. The specified limits i governing the use of appropriate portions of the systems were specified as a
- suitable fraction of the dose design objectives set forth in Sections II.B and
! II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. l 4 i- )
Nuclear Producticn - Fcrai 2' ODCN-4.0 Offsito Dose Calculstien Manual. 'Revisien 6 , Paga 4.0-6 l l RADIOACTIVE EFFLUENTS BASES. l l
,3/4.11.2.5 VENTILATION EIHAUST TREA1 MENT SYSTEM The requirement that the appropriate portions of this systen be used,'when !
specified, provides reasonable assurance that.the releases'of radioactive
~ anterials in gaseous effluents will be kept "as low as is-reasonably -
achievable." The specified limits governing the use of appropriate portions of j the systems were specified as a suitable fraction of the dose design objectives 1 set forth in Sections II.B and II.C of Appendix I,10 WR Part 50, for gaseous affluents. 3/4.11.2.8 YENTING OR PURGING This control provides reasonable assurance that releases from primary 'l containment purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. 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 area to the total body or any organ, except-the thyroid, which shall be limited to less than or equal to 75 areas. 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 of 40 CFR Part 190 if the individual-reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the-limitation of the annual dose to a member of the public to within g the 40 CFR Part 190 limits. For the purpose of the Special Report, it may be h g3 assumed that the' dose commitment to the member of the public from other than uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the , public is estimated to exceed the requirements of 40 WR Part 190, the Special l Report with a request 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 W R Part 190.11 and 10 CFR Part 20.2203,is \\% considered to be a timely request and fulfills the requirements of 40 CFR Part i 190 until NRC staff action is completed. The variance only relates to the 4 limits of 40 WR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 TR Part 20, as addressed ir Controls 3 11.1.1 and 3 11.2.1. An individual is not considered a member c' the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
Nuclear Productica - Fcr::!i 2 ODCN-4.0 Offsite Dose Calculatien Manual R: vision 6 Page'4.0-7 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring progran required by this control
, provides representat4ve measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of BEllMBERS OF THE PUBLIC resulting from the station operv ion. This monitoring program implements Section IV.B.2 of
. Appendix I t( .2 CPR Part 50 and thereby supplements the radiological effluent
~
monitoring program by verifying that the aeasuremble concentrations.of radioactive materials and levels of radiation are not higher than' expected on the basis of.the affluent measurements and the modeling of.the environmental exposure pathways. Guidance for this monitoring program.is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective' for at-least the first 3 years of commercial operation. . Following this period, progras 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 optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is~ defined as an a priori (before the fact). limit representing the capability of a measurement system and not as an a posteriori (after the fact), limit for a particular measurement. Detailed discussion of the LLD,'and other detection limits, can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chen. 40, 586-93 (1968), and Hartwell, J. E., " Detection Limits for Radionnalytical 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 authorities shall be used.~ This census satisfies the requirements of Section IV.B.3 of Appendig I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m 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 ohild. To determine this minimum garden size, the following assumptions were made:- (1)20%ofthegardenwasusedforgrowingbroadleafvegetatgon(i.e.,similar to lettuce and embbage), and (2) a vegetation yield of 2 kg/m
Nuclear Productirn - Fgrai 2 ODCH-4.0 Offcite Dose Calculatitn Manual Revisitn 6 P;g3 4.0-8 RADIOLOGICAL 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 measurements of radioactive material in environmental sample matrices are performed a4 part of t.he quality assurance -
program for environmental 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
Nuclear Production - Fcr:1 2 ODCM-5.0 Offcito Dosa Calcul0 tion Manual Revision 5 Pcgo 5.0-1 l I l I l I I l l SECTION 5.0 ADMINISTRATIVE CONTROLS l l 1 l 9 ABIS - IN0lBl& TION SERVICES Date approved: Release authorized by: Change numbers incorporated: 93-117-ODN DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient
j Nuclear Producticn - FIrsi 2 ODCM-5.0 i' Offolte Dose Calcul tico Manual Revision 5 j Pass 5.0-2 } l $ ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT < 5917 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.
? i The Annual Radiological Environmental Operating Reports shalll include j summaries, interpretations, and an analysis of trends of the results of the j radiological environmental surveillance activities for the report period, I including's comparison as appropriate, with preoperational studies, with i operational controls,'and with previous environmental surveillance reports, and-
! an assessment of the observed ispects of the plant operation on the '
i ' environment. . The reports shall also include the results of land use censuses i required by Control 3 12.2. The Annual Radiological Environmental operating-l Reports shall include the results of analysis of all radiological environmental j samples and of all environmental radiation measurements taken during the period i pursuant to the locations specified in the Table and Figures in the ODCM, as I well as summarized and tabulated results.of~these analyses and measurments in j the format of the table in the Radiological Assessment Branch Technical j Position, Revision 1, November 1979. In the event that some individual results 1 are not available for inclusion with the report, the report shall be submitted l noting and explaining the reasons for the missing results. -If possible, the ! j 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 4 radiological environmental monitoring program; at.least two legible maps' j covering all sampling locations keyed to a table giving distances and i directions from the centerline of one reactor;-the results of licensee l participation in the Interlaboratory Comparison Program, required by Control 312 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 ** l 5.9.1.8 Routine Annual Radioactive Effluent Release Reports covering the O O ' operation of the unit during the previous year of operation shall be submitted i within 90 days after January 1 of each year. The period of the first report l i shall begin with the date of initial criticality. 4 eOne map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
##A single submittal may be made for a mutiple unit station. The submittal should combine those sections that are conson to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
! Nuclear Producticn - Firai 2 ODCM-5.0 i Offaite Dose Calculation Manual R2 vision 5 i l Page 5.0-3 l j ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) l0 The Annual Radioactive Effluent Release Reports shall include a suasary of the j \ l quantities of radioactive 11guld 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 i 'in Liquid and 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 l l of hourly meteorological data collected over the previous year. This annual y summary may be either in the form of an hour-by-hour listing on magnetic tape j of wind speed, wind direction, atmospheric stability, and precipitation (if j measured), or in the form of joint. frequency distributions of wind speed, wind j direction, and atmospheric stability.'** This same report shall include an j assessment of the radiation doses due.to the radioactive liquid and gaseous j effluents released from the anit or station during the previous calendar year. This same report shall also laclude an assessment of the radiation doses from
- i. radioactive liquid and gaseous effluents to' MEMBERS OF THE PUBLIC due to their
- activities inside the SITE BOUND.W (Figurs 3 0-1) during the report period.
j All assumptions used in making these assessments, i.e., specific activity, 1 exposure- time and location, shall be included in these reports. '!he assessment i of radiation doses shall be performed in accordance with the methodology and { parameters in the OFFSITE DOSE CALCULATION MANUAL-(ODCM).
. '!he Annual Radioactive Effluent Release Report shall also include an assessment j of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses fron
- primary effluent pathways and direct radiation, for the previous calendar year j to show conformance with 40 CFR Part 190, Environmental Radiation Protection
! Standards for Nuclear Power Operation.' The assessment of radiation doses shall j 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)
\\ 9 j shipped offsite during the report periods f a. Container volume,
, b. Total curie quantity (specify whether determined by measurement or l estimate), i } ! ***In lieu of submission with the Annual Radioactive Effluent Release Report, \\ s the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon j request. 4 I 1 l i 2
- 1 i -. -
- - .j
- Nuclear Production - Feral 2 ODCH-5.0 Offaite Dose Calculation Manual R2 Vision 5
- l P ge 5.0-4 l ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) p ih
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Source of waste and processing employed (e.g., dewatered spent resin, i
compacted dry waste, evaporator bottoms), 1 e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and 1 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 lD i radioactive materials in gaseous and liquid effluents made during the reporting period. i The Annual Radioactive Effluent Release Reports shall include any changes made , during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) as l\ 1) 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 j the land use census pursuant to Control 3 12.2. The Annual Radioactive Effluent Release Reports shall also include the j % i following: an explanation as to why the inoperability of liquid or gaseous l effluent monitoring instrumentation was not corrected within the time specified l 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 cf Technical Specification 3 11.1.4.
- 5.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREA'IMENT SYSTEMS
- l 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 p q')
Effluent Release Report for the period in which the evaluation was reviewed by the OSRO. The discussion of each change shall contain: 4
- 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). 0gcy 1
e
. ~_ . .- .. . _ . _ . - - . .. .. . _ . - . Nuclear Production - Fsrai 2 ODCN-5.0 Offcito Dora Calculction Manual Revisicn 5 Paga 5.0-5 ADMINISTRATIVE CONTROLS 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;
- 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
- Nu',leir PrIductirn - F rmi 2 - CDCM-6.0 Ctfrit3 D:s2 Cal:ul:ti:n M:nu:1 Pcg3 6.0-1 i
e l PART 11 CALCULATIONAL METHODS l 1 l l I
T l ODCM-6.0 l l R:; vision 5 j Pago 6.0-2 = LIQUID EFFLUENTS l i 4 i 6.0 ' LIOUlD EFFLUENTS t l This section summarizes information on the liquid effluent radiation monitoring ;
- Instrumentation and controls. More detailed information is provided in the Fermi 2 UFSAR i j 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.
1 Methods for calculating alarm setpoints for the liquid offluent monitors are presented. Also, li methods for evaluating doses from liquid effluents are provided. l 6.1 Radiation Monitoring instrumentation and Controls ! i l l This section summarizes the instrumentation and controls monitoring liquid effluents. l l This discussion focuses on the role of this equipment in assuring compilance with j the Offsite Dose Calculation Manual. 6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement 1 j Fermi 2 ODCM 3.3.7.11 prescribes the monitoring required during liquid l l releases and the backup sampling required when monitors are inoperable. -l i ) The liquid effluent monitoring instrumentation for controlling and monitoring ] 4 radioactive effluents in accordance with the Fermi 2 ODCM 3.3.7.11 is j summarized below: . i $ 1. Radiation Alarm - Automatic Release Termination i !- a. Liquid Radwaste Effluent Line - The D11-N007 Radiation Monitor i on the liquid radweste affluent line provides the alarm and. j automatic termination of liquid radioactive material releases prior j to exceeding 1 Maximum Permissible Concentration (MPC) (ten g 2 times 10 CFR 20, Appendix B, Table ?_, Column 2 values) required j by ODCM 3.3.7.11.- The monitor is located upstream of the
- isolation Valve (G11-F733) on the liquid redweste discharge ilne
-t , and monitors the concentration of liquid effluent before dilution j by the circulating water reservoir (CWR) decent flow. j 2. Radiation Alarm (only) l a. Circulating Water Reservoir (CWR) Decent Line - The CWR Decent l Line Radiation Monitor (D11-N402) provides indication of the j l concentration of radioactive material in the diluted radioactive i 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. l
- ARMS - INFORMATION SERVICES I Date approved
- Release authorized by:
Change numbers incorporated: g3-117-ODM DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient i i 4 e .. -* ,r- - .- ---~-,y-.m.,m -r,-,, . - , . -
ODCM-6.0 1 Revision 5 l Pago 6.0-3
]
- 3. Flow Rate Measuring Devices !
I
- a. Uguld Radwaste Effluen: Line - in accordance with ODCM 3.3.7.11, I
the release rate of liquid radweste discharges is monitored by G11-R703. This flow rate instrumentation is located on the redweste discharge line prior to the junction with the CWR decant l line. l
- b. Circulating Water Reservoir Decant Line -in accordance with j 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 decent line downstream of the junction with the liquid radweste j offluent line. This instrumentation measures the total discharge flow rate from Fermi 2 to Lake Erie.
6.1.2 Non-ODCM Required Monitor An additional monitor not required by Formi 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).
Indication of radioactive material contamination in the GSW System j would also indicate potential CWR contamination and the need to 4 control all discharges from the CWR as radioactive effluents. 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 I of liquid releases: BATCH releases, defined as discrete volumes, normally processed through the 1 radweste system to the waste sample tanks i l CONTINUOUS releases, from the Circulating Water Reservoir (CWR) System, if it becomes contaminated Continuous releases from the CWR System are via the CWR decent line to Lake Erie. The CWR System is not expected to become contaminated. Therefore, continuous radioactive material releases are not expected. However, the General Service Water 1 (GSW) and the CWR systems interface with radioactive systems in the plant. Also, the GSW Intake is within a few hundred feet of the CWR decent line discharge to Lake Erie. For these reasons, it is prudent to consider the GSW and the CWR a potential source of radioactive effluents and to sample them regularly.
. ODCM-6.0 Revisisn 5 Page 6.0-4 1
i j 6.2.1 BATCH Releases Fermi 2 ODCM Table 4.11.1.1.1-1 requires that a sample representative of i 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 l 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 l month for tritium (H-3) and gross alpha activity. (The composite - sample is required to be representative of the liquids released and-sample quantities of the composite are to be proportional to the quantitles 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. 6.2.2 CONTINUOUS Releases Fermi ? ODCM Table 4.11.1.1.1-1 requires that composite samples be collected from the CWR System, if contaminated. The table specifies the followin) 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 radweste effluents. Therefore, the ODCM Table 4.11.1.1.1-1 sampling and analysis for noble gases in batch releases (one batch por 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.
1 ODCM-6.0 ' R:visi::n 5 l P:gs 6.0-5 6.3 Liquid Effluent Monitor Setpoints
- Offsite Dose Calculation Manual 3.11.1.1 requires that the concentration of liquid 3
radioactive affluents 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 uCi/ml, total noble gas activity. ODCM 3.3.7.11 requires that radiation monitor setpoints be established to alarm and trip prior to exceeding the limits of ODCM 3.11.1.1. To meet this specification, the alarm / trip setpoints for liquid affluent monitors are
, determined in accordance with the following equation:
SP < RR (6-1) where: SP = the setpoint, in uCi/ml, 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 fQ uCi/ml, defined in Equation (6-4) 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 (6-1) for a given effluent Concentration Limit, CL NOTE: If no dilution is provided, SP < CL Also, when DF is large compareu 30 RR, then (DF + RR)--DF, and DF may be used instead of (DF + RR) as a p 3 i simplification, as in Equation (6-5). 6.3.1 Liquid Redwaste Effluent Line Monitor (D11-N007) Liquid Radwaste Effluent Line Monitor D11-N007 provides alarm and automatic termination of releases 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 ident8fy principal gamma emitting radionuclides. From the measured Individual radionuclide concentrati%. the allowable release rate is determined. The allowable release rate is inversely prorce:,onal to the ratio of the radionuclide concentrations to the MPC valuws. The ratio of the measured concentration to MPC values is referred to as the *MPC fraction" and is calculated by the squation:
ODCM-6.0 R:visi::n 5 Pag 3 6.0-6 l M i l (6-2) where: MPCF = fraction of the unrestricted area MPC for a mixture of gamma emitting radionuclides Ci = concentration of each gamma emitting radionuclide I measured in each tank prior to release (uCl/ml) MPCl = 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 Oh MPC value of 2E-04 uCl/mi may be used, but noble gases need lI/cg3 ) not be included in this calculation. I 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. Based on the MPCF, the maximum allowable release rate can be calculated by the following equation: I (MPCF x (1+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 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.) Dh 4 MPCF = As previously defined by equation (6-2) H3MPCF = conservative estimate of MPC fraction due to tritium (The value Iglcg 0.13 may be used for H3MPCF.) NOTE: Equation (6-3) is valid only for MPCF >1; if the MPCF $1, the waste tank concentration meets the limits of 10 CFR Part 20 without dilution, and the waste sample tank may be discharged at the maximum rate.
ODCM-6.0 R;visi:n 5 P ge 6.0-7 If MAX RR as calculated above is greater than the maximum discha ge pump capacity, the pump capacity should be used in establishing the actual Release Rate RR for the radwaste discharge. For the Waste Sample Tank, the maximum discharge rate is 50 gallons per minute. The actual Release Rate RR is monitored in the Radwaste Control Room by G11-R703. The Concentration Limit (CL) of a ilquid radweste discharge is the same as the effective MPC for the radionuclide mixture of the discharge. Simply, the CL (or effective MPC) represents the equivalent MPC value for a mixture of radionuclides evaluated collectively. The equation for determining CL is: CL = \\ (6-4) Based on the Release Rate RR and Dilution Flow DF and by substituting Equation (6-4) for CL in Equation (6-% and introducing sensitivity factors and factors to account for the presora.e of pure beta emitters, the alarm setpoint is calculated by the equation:
' ' + Bkg SP <- '
MPCF e (1+BF)
- RR (6-5) where:
SP = setpoint of the radiation monitor counts per second (cps) Cg = concentration of radionuclide i as measured by gamma spectroscopy (uCl/ml) SENj = monitor sensitivity for radionuclide i based on calibration curve (cps /(uCi/ml)) or single conservative value for all radionuclides (see below) l i RR = actual release rate of the liquid radwaste discharge (gal / min) BF = pure beta factor as defined for Equation (6-3) l 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 - O note proceding Section 6.3.1. SF = 1.0 when a single conservative sensitivity value is used; 0.5 when individual nuclide sensitivity factors are used 0 {} i l l A monitor sensitivity value of 1.0 E6 cps /(uCi/ml) may be used in lieu of sensitivity values for individual radionuclides. This value is the sensitivity of Cr-51 determined from the primary calibration sensitivity curve. It is a conservative value for the nuclide mixes which have been seen in actual liquid discharges from Fermi 2.
ODCM-6.0 R;visicn 5 Pag 3 6.0-8 ff no radionuclides are measured by gamma spectroscopy, the alarm , setpoint can be established at one half the setpoint of the most recent ,q discharge for which radionuclides were detected by gamma spectroscopy, giS/ Prior to conducting any batch liquid radwaste release. Equation (6-3) is used ' to determine the ellowable release rate in accordance with ODCM 3.11.1.1. Equation (6-5) is used to determine the D11-N007 alarm setpoint in accordance with ODCM 3.3.7.11. ; 6.3.2 Circulating Water Reservoir Decent Line Radiation Monitor (D11-N402) { l ODCM 3.3.7.11 requires that the setpoint for the CWR Decant Line Radiation Monitor D11-N402 be established to ensure the radioactive material ! concentration in the decent line prior to discharge to Lake Erie does not exceed MPC, unrestricted area (ten times 10 CFR 20, Appendix B, Table 2, Column 2 values). The approach for determining the alarm setpoint for the lg%l ;) CWR Decant une Radiation Monitor is the same as presented in Section 6.3.1 for the Liquid Radweste Effluent Line Monitor. However, the CWR Decant Line Radiation Monitor setpoint need not be changed prior to l each release. Equation (6-1) remains valid, except that, for the CWR Decant j 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) l simplifies to: j SP < 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 i calculated by the equation: l SP < [(C,
- SEN,)
- SF * (DF + RR) + Bkg g(
MPCF
- RR (6-7) where:
SP = setpoint in counts per minute (cpm) Ci = concentration of each radionuclide i in the CWR decant line affluent uCi/ml) SENg = monitor sensitivity for nuclide i based on calibration curve (cpm /(uCl/ml)) MPCF = MPC fraction as determined by Equation (6-2) SF = 0.5, administrative safety factor Bkg = background reading of monitor (cpm) DF and RR are defined for Equation (6-1) 0 () Normally, only during periods of batch liquid redwaste discharges will there exist any plant-related radioactive material in the CWR decant line.
_ .., ...m _ m.. .m ..m, .. m. _ - - , . .~.um - .;#.. ~. , ODCM-6.0 R:: vision 5 P:ge 6.0-9 i ! 6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 l The D11-N402 setpoint could be adjusted for each BATCH release as is done for the liquid radweste affluent line monitor. Based on the measured
- levels of radioactive material in a BATCH ilquid release, the alarm setpoint' for D11-N402 could be calculated using Equation (6-7). However, during j 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 decent line design flow is 10,000 gpm; and the maximum liquid redweste release rate is 50 gpm, providing a 200:1 dilution. The
. radioactive mate l the range of 10' gal to 10' concgntration uCi/ml. With of BATCH200:1 a nominal liquiddilution releases is typically in (actual dilution has been greater since in actual releases the decant line ;
i flow rate has been about 18,000 ppm), the CWyecent line ponitor would < monitor diluted activity in the range of 5 x 10- to 5 x 10' uCl/mt.- l l D11-N402 Monitor response at these levels would be 0.1 to 100 cpm, ) depending on the particular rad 9nuclide mixture and corresponding ' l Instrument response. These response levels are less than the monitor. i j background levels. i ! In lieu of routinely adjusting the D11-N402 setpoints, generic, conservative i setpoints have been established based on an analysis of nuclides seen in j actual liquid discharges and on the primary calibration sensitivity curve. ; 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 8 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 setpcints 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.
ODCM-6.0 - R:visi:n 5
. P:gs 6.0-10 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 ,g limits of ODCM 3.11.1.1 at the discharge to Lake Erie. However, if either 6 $/
Monitor D11-N007 or D11-N402 alarms during a liquid release, it becomes necessary to re-evaluate the release conditions to determine compilance 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 affluent 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:
\g\
C, RR C MPCg/) . DF + RR
. (1+BF)
H3F i 3 fy (6-8) where: Cl = measured concentration of radionuclide i in the effluent stream (uCl/ml) MPCl = the MPC value for radionuclide I: ten. times the 10 CFR 20, Appendix B, Table 2, Column 2 value (uCi/ml); 2 E-04 uCl/mi for dissolved or entrained noble gases RR = actual release rate of the liquid effluent at the time of the alarm, gpm DF = actual dilution circulating water flow at the time of the release alarm, gpm H3F.BF = as previously defined f, NOTE: For alarm on D11-N402 (CWR decent line), the Release Rate RR is the Dilution Water Flow DF and the equation simplifies to (Cg /MPCg ) 51. 6.3.6 Liquid Radweste 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 sising 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 g)
ODCM-6.0 l R visi n 5 i Pago 6.0-11 l The resulting dilution flow rate is substituted in equation (6-3) to determine ; the maximum allowable release rate for discharges from the radweste i system. Substituting the availabla 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 radweste monitor setpoint can be uetermined using equation (6-5). 6.4 Contaminated OSW or RHR System - Quantifying and Controlling Releases The OSW Radiation Monitor (D11-N008) provides an indication of contamination of this system. The Monitors D11-N401 A and 8 perform this function for the RHR System. Also, the CWR Decant Line Radiation Monitor monitors all liquid l releases from the plant and would record any release to Lake Erie from either of i 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 analysis of the RHR System is also performed since it also is a potential source of 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 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 (011-N402) will be determined as specified in Section 6.3.2. If 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 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 decent line cumulative flow.
- ODCM-6.0
- Revision 5 I Pags 6.0-12 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.
6.5 Uquid Effluent Dose Calculation - 10 CFR 50 The parameters of the liquid release (or estimated parameters, for a pre-release 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 affluents released by Fermi 2 and for comparing that impact against limits set by the NRC in the Fermi 2 ODCM The limits in the Formi 2 ODCM are specified 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 PUBUC Dese - Liquid Effluenta 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.5 mrom to total body 5 5.0 mrom to any organ during any calendar year; 5 3.0 mrom to total body
$ 10.0 mrom to any organ ODCM 4.11,1.2 requires that quarterly and annual cumulative dose due to y liquid 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 material releases to the lake, the subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Fermi 2, pre-operational evaluation of radiation exposure pathways indicated that doses from consumption of fish from Lake Erie provided the most conservative estimate of doses from releases of radioactive liquids. l However, with the proximity of the 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 l Lagoona Beach embayment carries liquid effluents from Fermi 2 north along i 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 offluents from Fermi 2:
ODCM-6.0 R:visi::n 5 P:g) 6.0-13 D, = 1,67 E-02
- VOL ,[(C, . A,,)
DF
- Z (6-10) where:
Do = dose or dose commitment to organ o or total body (mrom) g\h due to release of a single tank Ago = site-specific ingestion dose commitment factor to the total body or any organ o for radionuclide I (mrom/hr per uCl/ml) Ci = concentration of radionuclide I in undiluted liquid effluent ggQ representative of the volume VOL (uCl/ml) VOL = total volume of liquid effluent released (gal) DF = average dilution water flow (CWR decant line) during tank glQ release (gal / min) t 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 (Ago) represents a 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 Ajo are presented in ] Table 6-1. They were derived in accordance with guidance of NUREG-0133 ! from the following equation: j Ago = 1.14 E + 05 ((Uw / Dw) + (Up e BFg)] DFg [) where: Up = 21 kg/yr adult fish consumption Uw = 730 liters /yr adult water consumption i Dw 15.4, additional dilution from the near field to the water 1 intake for the City of Monroe (Not dilution factor of 77 i from discharge point to drinking water intake, Fermi 2 UFSAR, Chapter 11, Table 11.2-11) BFg = Bloaccumulation factor for radionuclide i in fish from Table 6-2 (pCi/kg per pCi/ liter) DFg = dose conversion factor for nuclide i for adults in organ o from Table E-11 of Regulatory Guide 1.109 (mram/pCl) 1.14 E + 05 = 100 (pCi/uci) .103 (ml/kg) 8760 (hr/yr)
- ODCM-6.0 l - R0 vision 5 Pago 6.0-14 i 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-go and Fe-55 dose - analyses will be performed at least quarterly. 6.5.2 Simplified Liquid Effluent Dose Calculation P in lieu of the individual radionuclide dose assessment presented in' 4 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) \gh and (6-13) are to be applied to the release of a sing!n tank. Total Body Dg = 9.69 E + 03 . VOL , [ C, DF e Z (6-12) Maximum Organ D = 1.18 E + 04 . VOL , [Cg DFeZ
. (6-13) where:
Ci = concentration of radionuclide i in undiluted liquid effluent representative of the volume VOL (uCl/mi) gy VOL = volume of undiluted liquid effluent released (gal) DF = average dilution water flow (CWR decent line) during tank release (gal / min) gg Q Z = 5, near field dilution factor (derived from Regulatory Guide 1.109, Rev 0) Dtb = conservatively evaluated total body dose (mrom)~ Dmax = conservatively evaluated maximum organ dose (mrom) 9.69 E + 03 = 0.0167 (hr/ min)
- 5.80 E + 05 (mrom/hr per uCi/ml, Cs-134 total body dose factor from Table 6.0-1) 1.18 E + 04 = 0.0167 (hr/ min)
- 7.09 E + 05 (mrom/hr per uCl/ml, Cs-134 liver dose factor from Table 6.0-1)
- ODCM-6.0 R::visisn 5 Pago 6.0-15 i
j 6.5.3 Contaminated CWR System - Dose Calculation i 1 if the CWR System becomes contaminated, releases via the CWR System to ! Lake Erle must be included in the evaluation of the cumulative dose to a i MEMBER OF THE PUBUC as required by ODCM 3.11.1.2. ODCM Section 6.4 j described the methods for quantifying and controlling releases from the
- CWR System.
4
- For calculating the dose to a MEMBER OF THE PUBUC, Equation (6-10) 4 remains applicable for releases from the GSW System with the following j assumptions
I DF, Dilution Flow, is set equal to the average'CWR decant line flow l rate over the release period. Cl, Radionuclide Concentration, is. determined as specified in ODCM j Section 6.4. } 2 - VOL, Volume Released, is set equal to the total volume of the discharges to Lake Erie via the CWR decant line as specified in j Section 6.4. 6.6 Liquid Effluent Dose Projections j 10 CFR 50.36a requires licensees to maintain and operate the Radwaste System to ] ensure releases are maintained ALARA. This requirement is implemented through { ODCM 3.11.1.3. This section requires that the Liquid Radioactive Waste Processing ; i System be used to reduce the radioactive material levels in the liquid waste prior to
- release when the projected dose in any 31 day period would exceed
,1 j - 0.06 mrom to the total body, or 0.2 mrom to any organ ] When the projected doses exceed either of the above limits, the waste must be j , processed by the Uquid Radweste System prior to release. This dose criteria for processing is established at one forty eighth of the design objective rate (3 mrom/yr,
- total body or 10 mrom/yr any organ) in any 31 day period.
l ' The appliceble Uquid Waste Processing System for maintaining radioactive material .. releases ALARA is the Mixed Bad Domineralizers as delineated in Figure 6-1. !
- Alternately, the Waste Evaporator (presented in the Fermi 2 UFSAR, Section 11.2) can l
~ be used to meet the NRC ALARA design requirements. It may be used in conjunction with or in lieu of the Mixed Bed Domineralizers to meet the wasta processing
- requirements of ODCM 3.11.1.3.
i Each BATCH release of liquid redweste 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 , radweste processing to ensure future releases are maintained ALARA. t 4 q' The following equations may be used for the dose projection calculation:
! ODCM-6.0 i R:visi::n 5 i Pago 6.0-16 1, Dthp = Dtb (31 / d) _ ] j l Dmaxp = Dmax (31/ d) j (6-15) ) where: 1 ! Dtbp = the total body dose projection for the next 31 day period (mrom) NOTE: The reference calendar quarter is normally the current calendar quarter. j if there have been liquid releases in the previous quarter but not in the l current quarter, the previous quarter should be used as the reference ;
- calendar quaner. I J
j Dtb = the cumulative total body dose for all releases to date in the reference j calendar quarter (normally the current quarter) as determined by
- equation (6-10) or (6-12) (mrom)
! Dmaxp = the maximum organ dose projection for the next 31 day period (mrom) i 1
- Dmax = the cumulative maximum organ dose for all releases to date in the reference calender quarter as determined by Equation (6-10) or
, (6-13) (mrom) J l
- d = the number of days from the beginning of the reference calendar I quarter to the date of the dose projection evaluation.
l 31 = the number of days in projection i4 l END OF SECTION G.0 i l l t ? l l. 4 3 i
ODCM-6.0 R visisn 5 j Pago 6.0-17 i 4 TABLE 6.0-1 i Formi 2 Site Specific Liquid in9estion Dose Commitment Factors 4 Ago (mrom/hr per uCl/ml) Nuclide Bone Liver T Body Thyroid Kidney Lun9 GI-LLI l I H-3 - 7.94E-1 7.94E-1 7.94E-1 7.94E-1 7.94E-1 7.94E-1 1 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 - 6.26E+3 6.26E+3 6.26E+3 NO-24 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 J P-32 1.39E+6 8.62E+4 5.36E+4 - - - 1.56E+5 4 Cr-51 - - 1.29E+0 7.70E-1. 2.84E-1 1.71E+0 3.24E+2 i l Mn-54 - 4.40E+3 8.40E+2 - 1.31E+3 - 1.35E+4
- Mn-56 -
1.11E+2 1.96E+1 - 1.41E+2 - 3.53E+3 j Fo-55 6.73E+2 4.65E+2 1.08E+2 - - 2.59E+2 . 2.67E+2 i Fa-59 1.06E+3 2.50E+3 9.57E+2 - - 6.98E+2 . 8.32E+3 3 Co-57 - 2.19E+1 3.64E+1 - - - 5.55E+2 i
- Co-58 -
9.32E+ 1 2.09E+2 - -
.- 1.89E+3 j
C3-60 - 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 4 Cu-64 - 1.04E+1 4.89E+0 - 2.63E+1 - 8.88E+2 $ \ j Zn-65 2.32E+4 7.38E+4 3.34E+4 - 4.94E+4 - 4.65E+4 1 i Zn 39 4.94E+1 9.44E+1 6.57E+0 - 6.14E+1 - 1.42E+ 1 ] Br-82 - - 2.28E+3 - - - 2.62E+3 .i Br-83 - - 4.06E+1 - - - 5.85E+1 ! Br-84 - - 5.27E+1 - - - 4.13E-4
- Br-85 - -
2.16E+0 - - - 1.01 E-15 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 l Sr-89 2.38E+4 - 6.83E+2 - - - 3.81 E+3 ! I Sr-90 5.85E+5 - 1.44E+5 - - - 1.69E+ 4 Sr-91 4.38E+2 - 1.77E+ 1 - - - 2.09E+3 Sr-92 1.66E+2 - 7.18E+0 - - - 3.29E+3 i Y-90 6.28E-1 - 1.68E-2 - - - 6.66E+3 j Y-91m 5.93E-3 - 2.30E-4 - - - 1.74E-2 i Y-91 9.20E+0 - 2.46E-1 - - - 5.06E+3 ! Y-92 5.51E-2 - 1.61E-3 - -- - 9.66E+2 ! Y-93 1.75E-1 - 4.83E-3 - - - 5.55E+3 L 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 - 6.81E-3 - 1.40E+3 ! Nb-95 4.47E+2 2.49E+2 1.34E+2 - 2.46E+2 - 1.51 E+6 i Nb-97 3.75E+0 9.48E-1 3.46E-1 - 1.11E+0 - 3.50E+3 i M2-99 - 1.26E+2 2.41E+ 1 - 2.86E+2 - 2.93E+2 Tc-99m 1.02E-2 2.88E-2 3.67E-1 - 4.38E-1 1.41 E-2 1.71E+ 1 Tc-101 1.05E-2 1.51E-2 1.48E-1 - 2.72E-1 7.73E-3 4.54E-14
ODCM-6.0 R:visi:n 5 4 Page 6.0-18
- TABLE 6.0-1
- Fermi 2 Site Specific Liquid ingestion Dose Commitment Factors
- Ago (mrom/hr per uCl/ml) 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 . 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 - - - - 1 Rh-106 - - - - - A9-110m 1.75E+0 1.61 E+0 9.59E-1 - 3.17E+0 - 6.59E+2 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 To-125m 2.58E+3 9.35E+2 3.46E+2 7.76E+2 1.05E+4 - 1.03E+ 4 Tc-127m 6.52E+3 2.33E+3 7.94E+2 1.67E+3 2.65E+4 - - 2.19E+4 Tc-127 1.06E+2 3.80E+ 1 2.29E+1 7.85E+ 1 4.31 E+2 - 8.36E+3 Tc-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 To-131m 1.67E+3 8.15E+2 6.79E+2 1.29E+3 8.25E+3 - - 8.09E+4 Te-131 1.90E+1 7.93E+0 5.99E+0 1.56E+1 8.31E+1 - 2.69E+0 To-132 2.43E+3 1.57E+3 1.47E+3 1.73E+3 1.51E+4 - 7.42 E+ 4 6-130 3.12E+ 1 9.21E+1 3.64E+1 7.81E+3 1.44E+2 - 7.93E+ 1 1-131 1.72E+2 2.46E+2 1.41E+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 3.11E+1 1.50E+4 1.78E+2 - 9.17E+ 1
! l-134 4.38E+0 1.19E+ 1 4.26E+ 0 2.06E+2 1.89E+ 1 - -
1.04E-2 l-135 1.83E+ 1 4.79E+1 1.77E+1 3.16E+3 7.68E+1 - 5.41E+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 2.01E-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 Cc-141 7.30E-2 4.94E-2 5.60E-3 - 2.29E-2 - 1.89E+2 Co-143 1.29E-2 9.51E+0 1.05E-3 - 4.19E-3 - 3.56E+2 CO-144 3.81E+0 1.59E+0 2.04E-1 - 9.44E-1 - 1.29E+3 Pr-143 6.00E-1 2.41E-1 2.98E-2 - 1.39E-1 - 2.63E+3 Pr-144 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 R, vision 5 Page 6.0-19 l TABLE 6.0-2 Bioaccumulation Factors (BFI) (pCi/kg per pCl/ liter)* Element Freshwater Fish H 9.0E-01 ! ! C 4.6E+03 l 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 l Br 4.2E+02 l Rb 2.0E+03 Sr 3.0E+01 l Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+ 04 Mo 1.0E+01 ( Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 l Ag 2.3E+00 Sb 1.0E+00 l Te 4.0E+02 1 1.5E+01 Cs 2.0E+03 i Ba 4.0E+00 l La 2.5E+01 Co 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W 1.2E+03 Np 1.0E+01
- 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.
l A
i !! 3) ih m I ! fj' . -,
,1 !
Dal 3,, a o o , a:s I o . .h . . 33; i (ii __( !! 3 ,. d 111
\ :
81 <
!a!
> >1,.
i t + 3 la
~
b
;j 1
,+
I i . C ,s a s
'T Fl18 "
- ) <:
(lI3 (111 (ID b
Nu !3cr Pr:ducti:n - F2rmi 2 CDCM-7.0 Cffetto Dosa Calculati:n M:nual R:vi:i:n 6 Pago 7.0-1 GASEOUS EFFLUENTS 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 Fermi 2 for controlling and monitoring radioactive effluents are specified in ODCM 3.3.7.12. The monitoring of each identified gaseous effluent release point must include the following: Noble Oas Activity Monitor lodine Sampler (sample cartridge containing charcoal or silver zeolite) Particulate Sampler (filter paper) Sampler Flow Rate Monitor 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 SPING Monitor outputs are recorded electronically in the CT-2B Control Terminal in the Main Control Room. In general, a reading exceeding the High alarm setpoint of the ,4 SPING Monitors causes an alarm in the Control Room. Fermi 2 ODCM \\T/ 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: Hydrogen Monitor - used to ensure the hydrogen concentration in the Offgas Treatment System is maintained less than 4% by volume as required 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 required by Technical Specification 3.11.2.7. ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: g3-117-ODM DSN Rev 6 Date DTC TMPLAN File 1715.02 Recipient
ODCM-7.0
- R
- visl2n 6
- Pags 7.0-2 i These two monitors perform safety functions. The Hydrogen Monitor
! monitors the potential explosive mixtures in the Offgas System. The Noble j' Gas Monitor monitors the release rate from the main condenser ensuring j doses at the exclusion area boundary will not exceed a small fraction of the j limits of 10 CFR 100 in the event this affluent is inadvertently discharged j }. directly to the environment bypassing the Offgas Treatment System. 1 j 7.1.3 Reactor Building Ventilation Monitors (Oulf Atomic) i The Gulf Atomic Monitors (D11-N408 and 410) on the Reactor Building Ventilation System provide on high radiation levels (above alarm setpoint) d initiation of SGTS, isolation of drywell vent / purge, isolation of the RB and ! ! Control Center Ventilation Systems and initiation of Control Center i recirculation mode ventilation. These monitors and functions are not j required by Fermi 2 ODCM but are important in controlling containment
- venting / purging.
1 j 7.2 Sampling and Analysis of Oaseous Effluents l l j The program for sampling and analysis of gaseous waste is prescribed in j i Fermi 2 ODCM Table 4.11.2.1.2-1. This table distinguishes two types of gaseous i i releases: (1) containment PURGE, treated as BATCH releases, and (2) discharges from ; the Reactor Building Exhaust Plenum (including Standby Gas Treatment l System (SGTS) when operating), and other building ventilation exhausts, treated as ! CONTINUOUS releases. l , 7.2.1 Containment PURGE i i ODCM Table 4.11.2.1.2-1 requires that samples be collected and analyzed I before each primary containment PURGE. Sampling and analysis is required within eight hours before staning a PURGE. ODCM Table 4.11.2.1.2-1 4 Footnote j and ODCM 4.11.2.8.2 also require that if the purging or venting is , l through the Reactor Building ventilation, rather than through SGTSiand if I l the primary containment radiation monitoring system is INOPERABLE or in j l alarm condition, sampling and analysis is required within 8 hours prior to and at least once per 12 hours during venting or purging of the primary i containment. The required analyses must include princial gamma emitters , j and, if a pre-vent or pre-purge sample, tritium. ' I
- For a planned containment PURGE, the results of the samples and analyses h
h j may be used to establish the acceptable release rate and radiation monitor j - alarm setpoint in accordance with ODCM Section 7.3.. This evaluation may 2 be 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 l
}' 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 10 CFR 20 or limits specified in the j ODCM. l 7.2.2 Ventilation System Releases i i i ODCM Table 4.11.2.1.2-1 requires continuous samples of releases from the l RB Exhaust Plenum, Standby Gas Treatment System, Radweste Building, t Turbine Building, Service Building, and Onsite Storage Facillity. The table l specifies the following program: 1 3
ODCM-7.0 R: vision 6 Pag) 7.0-3 l Once per week, analysis of an adsorbent sample of I-131 and 1-133, plus analysis of a particulate sample for principal gamma emitters. Once per month, analysis of a composite particulate sample of all. ! releases (by release point) that month for gross alpha activity. Once per quarter, analysis of a composite particulate sample of all releases that quarter for Sr-8g and Sr-g0. Once per month, analysis of a grab sample for principal gamma l emitters (noble gases and tritium), j l ODCM Table 4.11.2.1.2-1 also requires continuous monitoring for noble l gases. This requirement is met by the SPING Monitors on each of the plant i gaseous release points. The ODCM requires more frequent sampling and analysis following reactor - l startup, shutdown, or change in thermal power exceeding 15% within one j 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 l factor of three. j i Reactor Building SPING noble gas monitor has increased more than a factor of three. Grab samples of the Fuel Pool Ventilation Exhaust are required tritium analysis once per sevon 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 pool is filled. These samples are taken at the Reactor Building Exhaust Plenum and Standby Gas Treatment System (SGTS) when operating. 7.3 Gaseous Effluent Monitor Setpoint Determination 73.1 Ventilation System Monitors Per the requirements of ODCM 3.3.7.12, alarm setpoints shall be established for the gaseous affluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of ODCM 3.11.2.1. This section limits releases to a dose rate at the SITE BOUNDARY of 500 mrom/ year to the total body or 3000 mrom/ 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 - l @$ . alarm setpoints may be established by the following calculational method. i The measured radionuclide concentrations and release rate are used to ; calculate the fraction of the allowable release rate, limited by i ODCM 3.11.2.1, by the equation: ; FRAC = 1.67 E + 01
- X/O
- VF * [(C,
- K )
(7-1) FRAC = 1.s7 E + 01
- X/O
- VF * [(C, * [L, + 1.1 M,])
- m. . .
(7-2)
ODCM-7.0 -
. R: vision 6 P:go 7.0-4 Where:
FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate X/O = annual average meterological dispersion to the controlling site boydary location from Table 7,0-3 (sec/m ) or plant procedures VF = Ventilation System flow rate for the applicable release point and monitor (liters / minute). Cl = concentration of noble gas radionuclide I at release point as determined by gamma spectral analysis of grab ~ sample (uCi/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 Ki
= total body dose radionuclide conversion I (mrom/yr factorf,or per uCl/m from noble Table 7.0-2)' gas' Li = beta skin Jose conversion factor fgr noble gas radionuclide I (mrom/yr per uCl/m , from Table 7.0-2)
Mi = gamma air dose conversion factog for noble gas i radionuclide 1 (mrad /yr por uCl/m , from Table 7.0-2) 1.1 = mrom skin dose per mrad gamma air dose (mrom/ mrad) 500 = total body dose rate limit (mrom/yr) r 3000 = skin dose rate limit (mrom/yr) i
- 1.67 E + 01 =
1 E + 03 (cc/ liter) * (1/60) (min /sec)' I j 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 l equation:
SP $ (AF * [ CJ + Skg . l FRAC l (7-3) Where: l SP = alarm setpoint corresponding to the maximum allowable release rate (uCl/cc) Skg = _ background of the monitor (uCi/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 i administratively allocated to the individual release points. l
ODCM-7.0 R:visien 6 Pego 7.0-5 C = concentration of Noble Gas Radionuclide i as determined by gamma spectral analysis of grab sample (uCl/cc) (If a noble gas is not detected at the reactor buliding 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 affluent at the time of the grab sample, this response minus background may be used in lieu of the summed grab sample concentrations. The Allocation Factor (AF) is an administrative control imposed to ensure that 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 channel in
. 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.
73.2 Setpoint Determination with No Nuclides Detected When noble gas concentrations for a release point cannot be determined I 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 73.1 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. 733 Geseous 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 l establish actual radionuclide concentrations and permit evaluating the j monitor response. The following equations may be used for evaluating j compliance with the release rate limit of ODCM 3.11.2.1a: ' l
ODCM-7.0 RIvisicn 6 Pago 7.0-6 j Dtb = 1.67 E + 01 e X/O e VF e [(Kg e Cg) l (7-4) l Ds = 1.67 E + 01 e X/O e VF [([L i+ 1.1 M li e Cg) (7-5) Where: Dtb = total body dose rate (mram/yr) ; Ds = skin dose rate (mrom/yr) X/O
= atmospheric SITE BOUNDARY dispersion to the cqp) trolling location (sec/m VF = Ventilation System release rate (liters / min)
Ci = concentration of radionuclide i as measured in the grab sample or as correlated from the SPING Noble Gas 1 Monitor reading (uCi/cc) l Ki
= total body dose radionuclide conversion I (mrom/yr factorf,or per uCi/m from noble gas Table 7.0-2)
Li = beta skin dose conversion factor fgr noble gas radionuclide I (mrom/yr per uCi/m , from Table 7.0-2) Mi = gamma air dose conversion factog for noble gas radionuclide I (mrad /yr per uCi/m , from Table 7.0-2) 1.1 = mrom skin dose per mrad gamma air dose (mrem / mrad) 1.67 E + 01 = 1 E + 03 (cc/ liter) e (1/60) (min /sec) The above equations may also be used to verify compliance with ODCM yCd l 3.11.2.1.a when noble gases are detected in periodic (e.g. monthly) effluent noble gas samples. 7.4 Primary Containment VENTING end PURGING ! 7.4.1 Release Rate Evolustion For primary containment VENTING or PURGING, an evaluation of acceptable release rate may be performed prior to the release. Based on the measured f f cg } noble gas concentration in the grab sample collected per the requirements bl of ODCM Table 4.11.2.1.2-1, the allowable release rate from primary ' containment can be calculated by the following equation: < RRg= 500 . AF 1.67 E + 01 e X/O e {(K ei Cg) (7-6) or RR*= 3000. AF 1.67 E + 01 e X/O e {([L +i 1.1 Mg]
- Cg)
(7-7)
ODCM-7.0 - R:visi n 6 Paga 7.0-7 : Where: RRtb = allowable release rate so as not to exceed a dose rate of 500 mrom/yr, total body (liters / minute) RRs = allowable release rate so as not to. exceed a dose rate ; of 3000 mrom/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 .j Exhaust Plenum) j l 500 = total body' dose rate limit (mrom/yr) 3000- = skin dose rate limit (mrom/yr). . 1 The' lessor 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 h'Q 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 OM 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 hk SGTS) and associated offluent 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 g/qJ evaluation is rarely necessary. l f 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 l reporting of individual radionuclides released in gaseous affluents. Therefore, l Detroit Edison must determine the quantities of the individual radionuclides released. i For noble gases, these quantitles must be based on actual noble gas grab samples. ; i 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, Redweste 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 19g2) noble gases have been detected only in the reactor building effluent.
i ODCM-7.0 2 R:visicn 6' {. Pags 7.0-8 1 ] (
- in addition to these monthly camples from each release point, noble gas l grab samples from the Offgas Vent Pipe may be collected using the sample
l lines of the abandoned Offgas Vent Pipe Monitor (D11-N105 and 1 i D11-N106). Since noble gases are more concentrated at this point than at i 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 i
, concentrations increase sufficiently to allow detection of all significant 'I noble gas nuclides at the Reactor Building Exhaust Plenum. j )
- For Containment PURGENENT, samples are collected prior to the initiation of the release and periodically throughout the release (see ODCM -l Section 7.2.1). These samples are evaluated using Equations (7-4) and (7-5) to ensure that the site boundary dose rate limits of ODCM 3.11.2.1 are not i exceeded. For an extended PURGENENT period (e.g., longer than 48 hours), )
, drywell airborne activity levels will equilibrate. After equilibrium is reached, I. the quantification of the PURGENENT can be adequately addressed by the l periodic (typically weekly) sample and analysis of the Reactor Building f Exhaust Plenum or Standby Gas Treatment System. a . l i As required by ODCM Table. 4.11.2.1.2-1, special samples are required of the i RB Exhaust Plenum and SGTS following shutdown, startup or a { j THERMAL POWER change exceeding 15% within a 1 hour period. Exceptions . , l to this special sampling are allowed as noted previously in ! ]. ODCM Section 7.2.2. I t i 7.5.2 Release Concentration Determination for Reactor Building Exhaust j Monum i j in cases where both a RB Exhaust Plenum noble gas sample and an Offgas j Vent Pipe (OGVP) sample have been taken, the RB Exhaust Plenum noble gas i concentrations are determined as follows: . First, the RB SPING channel 1-5 i readings (above background) at the times the two samples were taken are ; j~ compared, and the noble gas concentrations for the sample taken at the
- l lower RB SPING channel 1-5 reading are normalized to the higher RB SPING i j channel 1-5 reading. Second, a dilution factor relating OGVP concentrations j l to RB Exhaust Plenum concentrations is calculated by dividing the RB '
] Exhaust Plenum flow rate (nominally g.43 E4 cfm) by the OGVP flow rate as j i indicated in the control room (N62-R808, blue pen). Third, the OGVP noble ! ! gas concentrations are divided by this dilution factor. Fourth,- the diluted 1 OGVP noble gas concentrations are compared to the RB Exhaust _ Plenum l } noble gas concentrations, and the higher of the the two concentration !
' values for each nuclide is taken to be the RB Exhaust Plenum concentration
! for that nuclide. (For purposes of calculation, the concentrations of nuclides j which are not detected are taken to be zero.) Fifth, the resulting RB: j Exhaust Plenum concentrations are corrected for variations during the ; i release period by multiplying each concentration value by the average RB j SPING channel 1-5 reading (above background) for the 9 L L i r l I i 4
r i ODCM-7.0 - ) R::visisn 6 i Pag 3 7.0-g period divided by the higher of the two RB SPINO channel 1-5 sample readings (above background) at time the samples were taken. These corrected values are then used as Ci in Equation (7-8) to determine the quantity of noble gases released. 7.5.3 Calculation of Activity Released The following equation may be used for determining the release quantities from any release point based on the grab sample analysis: Og = 1.0 E + 03
- VF
- T
- Cg (7-8)
Where: Og = total activity released of radionuclide I (uCl) VF = Ventilation System release rats (liters / min) T = total time of release period (min) 1.0 E + 03 = milliliters per liter Ci = concentration of radionuclido I as determined by gamma-spectral analysis of grab sample (uCi/cc) corrected for variations during release period as described in Section 7.5.2 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 performed at a frequency no greater than j that corresponding to the sampling and analysis time period (nominally once per - i 7 days). The following equation may be used in the dose rate evaluation for 1-131, ; l l-133, and particulates with half lives greater than 8 days: DR = [ (X/Or
- Rg_jgi
- VFr
- 16.7 *[ C ir) '
r i (7-g) Where: DR = total maximum organ dose rate for all release points (mrom/yr) X/Or
= atmospheric SITE BOUNDARY dispersion locationfactor (sec/mfog) fromrelease point Table 7-3 or plantr to the controlling procedures RI -131 b
= l-131 uCi/m g)hild fromthyroid inhalation pathway dose factor (mrom/yr per CG Table 7-4 VFr = Average ventilation flow for release point r during release period l (liters / min) l Cri = Concentration of radionuclide I (1-131,1-133, or particulate with half life greater than 8 days) released from release point r during the l appropriate release period (uCl/cc)--usually determined by gamma
- spectral analysis of effluent sample
ODCM-7.0
' R! vision 6 Page 7.0-10 1
16.7 = 1000 cc/litar
- 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 individualisotopic 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 g\ qk 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. 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 del has increased by a factor of 3 or if the applicable noble gas affluent 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 ODCM 4.11.2.2 requires that an assessment of releases of noble gases be performed at least once per 31 days to evaluate compilance with the quarterly dose limits of 5 mrad, gamma-air and 10 mrad, beta-air and the calendar year 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 q equations must be performed for each such release point, and the U / calculated air doses must be summed. D = 3.17 E - 08
- X/O * [(Mg
- Og) and D = 3.17 E - 08
- X/O * [(N i* Og)
N (7-11) Where: D = sir dose due to gamma emissions for noble gas I radionuclides (mrad) D = air dose due to beta emissions for noble gas radionuclides (mrad) X/O
= atmospheric SITE BOUNDARY dispersion location (socto
/m the cap) trolling Og = cumulative release of noble gas radionuclide i over the period of interest (uCl)
Mj
= air dose factor due to gamma ergssions from noble gas radionuclide I (mrad /yr per uCi/m , from Table 7.0-2)
ODCM-7.0 Revisisn 6 Pago 7.0-11 Ni = air dose factor due to beta emissgons from noble gas radionuclide I (mrad /yr per uCl/m . Table 7.0-2) 3.17 E - 08 = 1/3.15 E + 07 (year /sec) 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 i verifying compliance with the dose limits of ODCM 3.11.2.2. If noble gases
\\h}l are detected at multiple release points, these equations must be performed for each such release point, and the calculated air doses must be summed. (Refer to Appendix B for the derivation and justification of this simplified method.)
D = 2.0
- 3.17 E - 08
- X/O
- Megg * [ Og
[ and (7-12) D = 2.0
- 3.17 E - 08
- X/O
- Nett * [ Qi 8 (7-13)
. Where:
Moff
= 2.7 (mrad E+ /yr03, per effectivg) uCl/m gamma-air dose factor Nett
= 2.3 (mrad E+ /yr03, per effectivg) uCl/m beta-alr dose factor 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 pd quarterly dose limit of 7.5 mrom and the calendar year limit of 15 mram 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:
Dao "((b (Wr
- SF
- 3.17 p E-8
- Reipo
- Ogr) prI (7-14)
Where: Dao = dose or dose commitment to Organ o of age group a g\ . (identified in Table 7.0-3 or plant procedures) Wr = atmospheric dispersion parameter for release point r and the residence location identified in Table 7.0-3 or plant procedures. Either:
2 ODCM-7.0 j R:vislan 6 i Pago 7.0-12 a \ a) X/O. atmospheric dispersion for inhalation pathway l\ 1 and H-3 (sec/m pathways and C-1g), or dose contribution via other ]
- b) D/Q, atmospheric deposition for vegegation, milk and . l p 0@
J. ground plane exposure pathways (m~) l Raiop = dose factor (mrom/yr per uCl/m3 ) or (m2 - mrom/yr, por uCl/sec) from Table 7.0-4 for radionuclide I, age 3 i' group a, pathway p, and organ o as identified in j Table 7.0-3 or plant procedures. Values for Raiop were i derived in accordance with the methods described in i NUREG-0133. As noted in NUREG-0133 section 5.3.1.3, l In the case that the milk animal is a goat, parameter values from Reg Guide 1.109 should be used. For I-131, l ' for example, use of the goat feed / forage consumption i rate given in Table E-3 and the stable element transfer l factor given in Table E-2 of Reg Guide 1.109 results in i grass-goat-milk dose factors which are equivalent to i the grass-cow-milk dose factors in Table 7.0-4 I multiplied by 1.2. I Or i = cumulative release from release point r over the period i of interest (normally one month) for i radionuclide 1 -- l-131,1-133, tritium or radioactive material in particulate form with half-life greater than ! 8 days (uCl). . ! SF p = annual seasonal correction factor to account for the fraction of the year that the applicable exposure gs S} pathway does not exist: 4' 1) For milk and vegetation exposure pathways: l = 0.5 (derived from Reg Guide 1.109, Rev 1. A six 4 month fresh vegetation and grazing season (May i through October) limits exposure through this j pathway to half the year. i
- 2) For inhalation and ground plane exposure pathways
= 1.0 (derived from Reg Guide 1.109,- Rev 1) l 3.17 E-8 = 1/ 3.15 E7 (year /sec) . 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. 4 i
i ODCM-7.0 R: vision 6 Pag 3 7.0-13 The residence, age group, and relevant exposure pathways for this individual j are listed in Table 7.0-3 and in plant procedures. Plant procedures may provide updated information which differs from Table 7.0-3. This individual $ i is identified from data'obtained in the annual Land Use Census (ODCM
\\ f ;
j 3.12.2). h 7.8.2 Simplified Dese Calculation for Radiolodines and Particulates i, in lieu of the individual radionuclicQ (1-131 and particulates) dose i assessment presented above, the following simplified dose calculation may t be used for verifying compliance with the dose limits of ODCM 3.11.2.3. j However, the result of this calculation should not be used as the reported g@
- offsite dose.
Dmax = 3,17 E - OS
- W
- Rg_131 * { Og \\M (7-15)
( i Where: I g Dmax = maximum organ dose (mrom) i l RI -131'. = 4.76 E + 10, child thyrgid 1-131 dose factor for the
- vegetable pethway (m -
mrom/yr per uCl/sec) s-
- W = highest D/O for residence' listed in Table 7.0-3 (m-2) i 1
Qi = cumulative quarterly or annual release of radionuclide i j -- i-131,1-133, H-3, and particulates with half lives { greater than 8 days (uCl) The ground plane exposure and inhalation pathways need not be considered j when the above simplified calculational method is used because of the ' overall 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 l contribution than either the vegetation or milk pathway. However, use of j ! the 1-131 thyroid dose parameter for all radionuclides will maximize the ' i organ dose calculation, especially considering that no other radionuclide has { a higher dose parameter for any organ Ca any pathway than 1-131 for the j thyroid via the vegetable or milk path'way. i' i l\M J 7.9 Gaseous Effluent Dose Projection l 1 j As with liquid effluents, the Fermi 2 ODCM controls on gasecus effluents require j
- processing" of gaseous affluents if the projected dose exceeds specified limits.
i These controls implement the requirements of 10 CFR 60.36a on maintaining and j using the appropriate radwaste processing equipment to keep releases ALARA. ODCM 3.11.2.5 requires that the VENTit.ATION EXHAUST TREATMENT SYSTEM be used j to reduce radioactive material levels prior to discharge when the projected dose exceeds 0.3 mrom to any organ in any 31 day period (i.e., one quarter.of the design
! objective rate). Figure 7.0-1 presents the gaseous offluent release points and the j
VENTil.ATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior j to rolesse. 1 i w.-- -- r- _
,r-w-w v .,,pw-e -,-: i- ,-
- - Revision 6 i
- Pago 7.0-14 l Dose projection is performed at least once per 31 days using the following equation
- ;
1 i
- j. Dmaxp = Dmax * (31/ d) !
3 (7-16) e j Where: l ] Dmaxp = maximum organ dose projection for the next 31 day period (mrom) i j NOTE: The reference calender quarter is normally the current calendar . 4 quarter. If the dose projection is done in the first month of the j quarter and is to be based on dose calculated for the previous quarter, ! the reference calendar quarter is the previous quarter. i l Dmax = the cumulative maximum organ dose from the beginning of the l j reference calendar quarter (normally the current quarter) to the end 1 of the most recently evaluated release period as determined by- l l Equation (7-14) or (?-15) (mrom) l~ j d = number of days from the beginning of the reference calendar j quarter to the end of the most recently evaluated release period. }- 31 = number of days in projection i t f 7.10 Waste Oil incineration - l As indicated in Table 4.11.2.1.2-1, waste oil containing radioactive material may be 1 incinerated by injection into the Auxiliary Boiler fuel stream, but this shall only be j done 4.ccording to approved plant procedures. Prior to incineration of such oil, a t sample of the oil must be analyzed by gamma spectroscopy to determine j radionuclide concentration. Based on the analysis results and proposed incineration rate, the proposed release must be determined to be within site boudary dose rate 1 3 (\' b /
- , 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) should be used in these
- calculations, and the highest dispersion factors in Table 7.0-3 may be used, unless
- i. data specific to the Auxiliary Boiler stack is available. (Since this stack is farther from j j most land receptors than other plant stacks, Table 7.0-3 dispersion factors should be l
J conservative for this release point.) i END OF SECTION 7.0 l 4 } 1 i 3 i .i i
~
ODCM-7.0 R: vision 6 Page 7.0-15 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)
R acter Building 2.67E6 0.50 T Body = 250 Exhaust Plenum Skin = 1500 D11-P280 Organ = 750 St ndby Gas 1.07E5 0.10 T Body = 50 Trci.tment System Skin = 300 Div i D11-P275 Organ = 150 Standby Gas 1.12E5 0.10 T Body = 50 Treatment System Skin = 300 Div 11 D11-P2,0 Organ = 150 Turbine Building 8.67E6 0.23 T Body = 100 V:ntilation Skin = 600 D11-P279 Organ = 300 S:rvice Building 9.06E5 0.01 T Body = 5 V:ntilation Skin = 30 D11-P282 Organ = 15 Radwaste Building 1.13E6 0.02 T Body = 10 V:ntilation Skin = 60 D11-P281 Organ = 30 Onsit3 Storage 3.06E5 0.02 T Body = 10 Building Skin = 60 V:ntil: tion Organ = 30 D11-P281 R: actor Building 2.57E6 0.50 T Body = 125 Ventilation ** Skin = 750 Gulf Atomic M:nitcrs D11-N408,N410
- V:ntilation flow rate values are subject to change due to plant modifications and changing plant c:nditions; therefore updated values in plant procedures may be used.
- D11-N408 and N410 will start the SGTS, close the Drywell PurgeNent Valves, isolate Rx Building V:ntilation System, isolate Control Center, and initiate emergency recirculation mode.
ODCM-7.0 R: vision 6
. Pags 7.0-16 i
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 (mrom/yg)per uCl/m (mrom/yg)per uCi/m (mrad uCi/m /yrg)er (mrad uCi/m /yrg)er 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 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 j Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+ 03 4 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 XO-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 X3-133m 2.51 E+02 9.94E+ 02 3.27E+02 1.48E+03 X3-133 2.94 E+02 3.06E+02 3.53E+02 1.05E+03 , X0-135m 3.12E+ 03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 XO-137 1.42E+03 1.22E+04 1.51E +03 1.27E+ 04 Xa-138 8.83E+ 03 4.13E+03 9.21 E+ 03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 4 4
- N&TE
i
- Dose factors taken from NRC Regulatory Guide 1.109 l l
l i I l I 1 3 s 6 k +
ODCM-7.0 RIvlsisn 6 f Pago 7.0-17 1 i , TABLE 7.0-3 Controlling Locations, Pathways, and Atmospheric , Dispersion for Dose Calculations
- Atmospheric Dispersion Factor CDCM Location Pathway (s) Controlling X/O D/O Control 3 Age Group (sec/m ) (1/m2) 3.11.2.1 a site boundary noble gase N/A RB: 1.25E-6 N/A (0.57 mi, NW) direct TB: 5.71E-6
{ exposure RW: 2.66E-6 3.11.2.1 b site boundary inhalation child RB: 1.25E-6 N/A (0.57 mi, NW) l TB:5.71E-6 , RW: 2.66E-6 3.11.2.2 site boundary gamma-air N/A RB: 1.25E-6 N/A i (0.57 mi, NW) beta-air TB: 5.71E-6 { RW: 2.66E-6 3.11.2.3 residence vegetation child RB: 1.10E-6 1.59E-8 (0.67 mi, WNW) inhalation, and TB: 4.02E-6 3.06E-8 ground plane RW: 1.53E-6 1.76E-8 l 1 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 1992. When performing dose and dose rate evaluations for plant surveillances, the dispersion and \ deposition factor 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 dispers!on and deposition factors for the year being evaluated should be used. 0h I l l l I l i
am g feweeve Elf twest P:thver Doet Cassiteert Tectors . 4*ee 2ehetstsee r:twe7 Sees rutee. = esas ODCM-7.0 4 (arentyr per stuW Revision 6
' P gs 7.0-18
} 8= sk Sees user terrese t uner tems 8 -ua t. Seer S 5-3 - 1.368*3 t.Mtel ' t.36b3 1.36b 3 1.Mte3 f.36tel
- '. C- H .1.82b4 3.415 3 3.4tt*3 3.41t*3 3.41t*3 3.41b3 3.41Ee3
, So-24 1.02t*4 1.02t*4 1.821*4 1.02E+4 1.02t+4 1.02b4 1.025 4 i b33 1.32t+6 7.718 4 . -
- 8.Hb4 5.01t+4 Ca-51 -
- 5.958*1 2.38b t 1.445*4 3.338*3 1.80t*2 no-54 - 3.ME*4 .. 9.84t*3 1.4044 7.74t+4 6.30Ee3 me-54 . 1.34be .- 1.30t+0 9.44t*3 2.02t*4 t.838 1 Fe-ll 3.ut*4 1.70t*4 - - 7.318 4 6.03D) 3.948*3 Fe-19 1.18b4 2.78t+4 . . 1.02t*6 1.88t*5 1.86t+4 Co-57 - 6.93ba . - 3.70t*$ 3.H8+4 6.718*2
- Co-58 - 1.58t*3 . - 9.38tel 1.86bl 2.07b 3 4 Ce40 - 1.1$5+4 - - 5.97t*6 3.855*5 l.48b4 84-63 4.328*5 3.14t+4 - 1.788*5 1.348+4 1.458 4 8845 1.54be 3.10bt .- - S.488 3 1.25t*4 9.128-2 On-44 = 1.66 be - 4.62b8 6.788*3 4.908+4 6.15b t Se45 3.24t+4 1.0M
- S = 6.905 4 8.MDS S.34t+4 4.66be as-69 3.38b3 6. 51b2
- 4.22b2 9.30B+3 1.638*1 4.521-3 St-83 . . . . . 1.ME*4 1.35b4 Sr.43 . - . . . 3.328 3 3.41E*2 Br-84 * - = = * ' 1.Mb3 3.13p2 tr-85 * = = = = = 1.388*1 ab-M - 1.358+5 * -
- 9.668+4 S.90b4 86-88 - 3.87t*2 = . . 3.345-9 4.93D2 80-89 . 3.56t*2 - - = = 1.70E*3 St*89 3.MBe l - - - 1.40b6 3.50bl 4.72b3 Gr-90 9.92b7 - - = 9.60te6 7.228*5 6.10b6 er-91 6.19t+1 = = = 3.658*4 1.9ttel 3.50be Br-92 6.74b0 - - = 1.668*4 4.30t+4 2.918 1 F90 2.99E*3 - - - 1.70E*5 5.Mb $ S.41bt F91e 3.6thi - - - 1.915+3 1.33t+0 1.028-2 1-91 4.625*$ = = = 1.70t+6 3.tSt+5 1.34t+4 T 92 1.035*t - - - 1.57t+4 7.35E+4 3.02E l b93 9.448 1 . . - 4.858+4 4.328*$ 2.6tbo St-9$ 1.87t*5 3.44t+4 - 5.42t+4 1.77be 1.50bl 2.33b4 te-97 9.688*1 1. ht+1 - 2.97b t 7.875+4 5.338+l 9.Mbe ub-95 1.4 t b4 7.82t*3 - 7.74tel 5.058*5 1.m tes 4.21t*3 gb-97 3.238-1 S.62t-2
- 4.548 2 2.40te3 2.42b2 3.05b2 So-99 - 1.31E*3 - 3.91Ee2 9.13t+4 3.48t*5 3.30t*1 te-91e 1.8M-3 2.91b3
- 4.425-2 7.M8+2 4. ME*3 3.70E-2 te-101 4.10b$ 6.02D 5 - 1.085 3 3.99t*2
- 5.90E-4 So-103 1:53E+3 - - S.838 3 5.05t+5 1.10E*5 6.18b 2 to-105 7.90E 1 = = 1.02t+0 1.10t+4 4.838 4 3.115-1 to-104 6.9tb4 - - 1.ME*5 9.Mb6 9. tate $ 8.72t+3 th-103e = - = . - = =
Sb-104 = = = = * = = es-110s 1.08t+4 1.00t+4 = 1.97 b e 4.63t+4 3.02tel 5.948*3 86-134 3.12E+4 8.89t+2 7.55t*1 - 2.488+6 4.868+1 1.34E+4 ab-125 S.ME*4 5.95b2 5.40t*1 - 1.74E+6 1.018*$ 1.ht*4 Te-12$e 3.43t%3 1.98t*3 1.05t+3 1.34E+4 3.Mtel 7.968+4 4.6?b2 fe-127e 1.Mb4 5.77Be3 3.29b3 4.Seb4 9.80B+5 t.tetel 1.87b3 fe-127 1.48844 6.625-1 f .Nt*0 $.10t+0 6.51t*3 S.74b4 3. %t-1 te-129s 9.768*3 4.678 3 3.448 3 3.Mt+4 1. M8+6 3.88tel 1.588*3 fe-129 4.9BF2 3.39b2 3.908 3 1.87bt 1. M8* 3 1.57E*3 1.345-3 Te-131e 6.99p 1 4.Mte t 6.90tel 3.995 2 1.4f.t* % 5.56pl 3.90b t fe-131 1.11b3 $.958-3 9. ht-3 4.37b2 1.398*3 1.M8*1 3.59b3 fe-132 2.40b2 2.15p2 1.905 3 9.46t+3 3.84tel 5.tebl 1.62p3 bl30 4.58tel 1. M8+4 1. h t +6 2.00E*4 - 7.698+3 S.38t*3 F131 2.528+4 3.58be 5.19te? 6.1M*4 = 6.388*3 2.05be b132 1. Mt+ 3 3.Mb 3 1.14tel 5.188+3 . 4.068*2 1.Mte3 b133 8.ME*3 1.448 4 3.15t*6 2.585*4 - 8.88b3 4.53b3 J b1M 6.448 2 1.738*3 2.98t4 2.7$2+3 a 1.018 0 6.1Sb2 l b135 2.48Ee3 6.988*3 4.44bl 1.118 4 = $.253*3 3.57b3 1
$s-1M 3.7M* 5 8.44tel - 2.87E*$ 9.768+4 1.e48+4 7.38b t I Co-1M 3.905 4 1.46b5 - 8.M84 1.30t+4 1.178+4 1.18tel J es-137 4.788+1 6.31b5 - 3.32bl 7.538+4 8.40t* 3 4.Mb5 ]
i Co.1M 1.318*2 6.218e3 - 4.80t*2 4.868*1 9.868-3 3.34te2 ' So-139 9. ME-1 6.668-4 - 4.33t-4 3.768+3 8.96tet 2.745-3 I Be-He 3.90t+4 4.90t*1 - 1.678+1 1.37b e 3.94t*5 3.578+3 Se-141 1.008-1 7. SM-5 - 7.00t 5 1. ME* 3 1. M8-7 3.ME-3 So-M3 2.635-2 3.7ebl - 3.29b$ 1.19b3 = l.Mb3 1 Ia-He 3.44t** 1.745*3 -
- 1.Mtel 4.988*5 4.ME+ t ta-M2 6.83E-t 3.lebt - - 6.3M*3 3.118*3 7.7203 Me-let 1.99b4 1.358+4 = 6.Mt+ 3 3.628*$ 1.30t+5 1.SM*3 I Co-M3 1.NE+2 1.388+2 - 6.08t+1 7.988+4 2.NE* 5 1.53bt Co-ne 3.63be 1.43be - 4,48b5 7.785+6 4.16bl 1.84tel Pr-M3 9.MBe3 3.768 3 - 2.16te3 2.S t b 5 2. cat *5 4.Mb2 Pr-H4 3.018-2 1.258-2 - 7.058 3 1.02E+3 3.158-8 1.53b1 SbM7 5.37h3 6.tet+3 - 3. ME*3 3.21t+1 1.738*5 3.65t+3 W.187 8.48be 7.08be = = 2.90E*4 1.5SD S 3.48be l 8p-239 2.30b2 2.262 1 -
7.00t+1 3.76t*4 1.19b 5 1.24b t
j Towe 7.o-4 usettece ODCM-7.0 See* Sassan ho pel8mer See tesist - 2:8sessa l Ravision 6
- terwyr per scuW Psg3 7.0-19 Sect &4e Sean Liver Thrreld Slese7 Lens - Sbll! - T. Seer b3 - - 1.3Pb3 1.3?b3 1.37b 3' t.178 3 1.3?b3 1.37t*3 J C-te- '3.60t+4 4.878*3 4.878 3 4.87t*3 4.87b3 4.878 4 4.87E*3 1 Sa 34 1.38t*4 1.3854 - 1.MS*4 1. M8*4 1.348 4 1.34be 1.Mt*4 : '
d P-33 ' t.89b6 1.188*5 . = = 9.385*4 7.Mb4 Ct=51 - - 7.50bt 3.0?!*1 2.105 4 3.888 3 1.358 3 1 No-54 = 5.118+4 - 1.278+4 1.988+6 6.64t+4 8.688 4 - { me-54 =. 1.70E+0 - -1.79E+0 1.$38+4 5.74E+4 ' 2.53b1 - l 1 Fe-55 3. ME*4 3.385+4 - - 1.348*l 6.39b 3 5.545*3 j Fe-59 1.S98+4 3.78E4 -
- 1.538+6 t.788 5 1.43be i A Co-57 - 6.938*3 - - 5.865+$ 3.148 4 9.38b3 l 3 l 1 Co-le - 2.878 3 - . l.Mb6 9.528*4 3.78b3 l Co-48 - 1.ltt+4 - - 8.738+6 3.H b 5' t.90s*4 ;
8143 5.88tel. 4.Mt+4 - = =- 3.878*1 1.438*4 1.988+4 1 8145 3.188+e 3.93t-t - - 9.368 3 3.67t*4 1.378-1 l j on-M = 3.8M+8 - 6.etbe . t.118+4 6.148+4. 8.44bt 3e-65 3.868+4 1.34tel - 8.Mbe 1.348+6 4.M8+4 6.34E+4 - Re-69 4.83>3 9.388 3 - 6.025 3 1.588*3 3.Sibt 6.448-3 St-42 = = = - - - 1.828+4 l St-83 - = = . - .
. 3.448*3 St=84 . = = = = = 4.HE*3 i
St-85 - = . .
. . t.8' le t B>S6 = . t.90bl -- . . l.778*4 8.488 4 Shte - 5.468*2 - - - 3.9tb5 2.73bt i 8689 - 3.528+2 - - - 3.38b7 2.Hp2 ~
i St-89 4. Ms+ 5 -- - - 3.438+6 3.7tE*l 1.2684 1 i St-90 1.883*4 - - . 1.653*7 f.65 Eel 6.68t+6 j . St-91 8.80E*1 - - - 6.07t+4 2.$98+$ 1.51 b4
- St-92 9.528+0 = '. - 3.74t+4= 1.198*5 4.861-1 i
T-90 2.988+3 - = = - 2.9H+ 5 5.59E* 5 8.80p t
- b91e 3.788-1 = = - 3.30b3 3.838*1 1.435-3 f b91 = 6.6tE*S - * - - 3.Mt+6 4.89E*$ 1.778+4
'T-92 1.47b t = = = 3.68 be 1.6Sb 5 4.298-1 l b93 1.38t*2 - = = 8.33 tee 5.79tel 3.728*0 -
4 Et-95 1.448*5 4.54t+4 - 6.74E+4- 2.698+6 1.49E*5 3.t Sbe l *t-97 1.388+3 2.728*1 - 4.12 set 1.38t*5.6.30E*5 1.NE* t $ Skt$ 1.865+4 1.8M4 - 1.008+4 - 7.Stbl 9.642 4 5.ME4 4 Obt? 3. Mbt 7.78b2
- 9.12b2 3. 9M* 3 2.17b 3 .3.84E 3 ii No-99 - 1.698*2 = 4.11p3 1.948*$ 3.69b 5 3.338,1 fe-99u 1.30F3 3.848-3 - 5.ht-2 1.158*3 6.13b 3 4.998 Te-101 5.93b5 8.488-S
- 1.125 4 6.67E*2 8.738 4 8.348-4
- ! Be-103 2.10E+3 - - 7.43E+3 7.8 H+ 5 1.89t+$ 8. Mbt
} Su-105 1.128+0 - - 1.41E+0 1.82E+4 9.N E+4 4. Mbt An-146 9.448+4 - - 1.90E*5 1.6tt*7 9.60t*5 1.34b4
- M.t . - - . . - -
- M -,els M - - - - - .. .
l As-Sten 1.Mbe 1.318+4 - 2.905 4 6.758+6 3.73bl . 7.998 3 . Set 24 4.30b4 7.ME*2 9.768+t - 3.85be 3.988*$ t.488*4 ! 89125 7.388+4 8.888*3 f.hte t - 3. M8+6 9.938 4 t.738*4
-Te-tale 4.888*3 3.248*3 1.4e8*3 - 5.368*8 7.9804 6.67p3 f fe-127e 1.80t+4 8.168*3 4.3Pp3 6.545 4 1. M 8+6 1.59b 5 3.18p 3
. fe-137 2.018+8 9.13bt 1.438 0 7.38E+0 1.128+4 8.888+4 4.428 t I fe-129e 1.39b4 6.588*3 4.98b3 1.19E*4 1.98 b6 4.858+l 3.2$b3 4 fe-129 7.185 2 3.NE-2 S.182-3 2.668 1 3.30t*3 1.62b3 1.768-3 I ii ' fe-13te 9.848*1 6.Sitet 7.25pt 4.39E** 2.Mtel 6.3ttel 4.828 1 i fe-131 1.548-2 8.328-3 1.348 2 6.188-3 3.ME* 3 1.51p t 8.Mb3 1 3 fe-133 3.88842 2.90t*3 3.46t*3 1.958*3 4.49b5 4.438*3 2.19t*3 1 I 138 '6.34t*3 1.798+4 1.498+6 3.758+4 - 9.13t*3 7.17p3 l I bl31 3.548*4 4.918+4 1.468*7 8.448 4 - 6.49b3't.Mid l F132 1. 99b 3 4.38b3 t.$1b5 6.93p 3 - 1.27b3 1.588*3 bs33 -1.238+4 3.858+4 3.928+6 3.59b4
- 1.8M*4 4.32h3 j I-t h 8.88E*3 2.338*3 3.95t+4' 3. M t+3 - 2.ht*1 8.40t*2
- I-135 3.788*3 9.44b 3 6.3ttel 1.49b4 - 6.958*3 3.49b3 Co-S M $.838*5 1.138*6 - 3.768*$ t .ME* $ 9.76b 3 5.498*$
1 Co-1M 5.158*4 1.ME* 5 - 1.18tel 1.788+4 f.8984 1.378*5 j Co-837 6.788*$ 8.48t*S - 3.Mb 5 1.21E*5 8.48b3 3.11E*S Co-l38 4.MS*3 8.568+3 - 6.62b3 7.878*t 3.78t-1 4.46t*2 l Sa-139 1. ME+0 9.448-4 - 8.00p4 6. ME* 3 4.468*3 3.908-2
- So-M8 8.478+4 6.185+1 = 3.M8*1 3.838+6 2.39t*5 3.538 3 1 an-let 1.438-t 1.865-4 - 9.Mt 5 3.398*3 7.468-4 4.74b3 Re-lea 3.78b3 3.788-5 . 3.Mb5 1.918*3 - 3.37b3 i Le 148 4.798*3 3.368*2 - - 3.M8+l 4.878+5 6. Mbt
, La-M2 9.888 1 4.358-1 . -
1.838+4 1.38be 1.M8-t-i co-141 3. M8+4 1.988+4
- 8.888 4 6.148+l 1.M8+l 3.17B*3 co-MS 3.668+3 1.948*2 -
- 8. Mbt 1.30tel 2.558*5 3. Mbt Co- M4 4.89b6 2.03be
- 1.31E+6 1.M b7 8.M8*$ 3.638*$
s Pr-M3 1.34b4 5.31t*3 - 3.89b3 4.8M* 5 2. M8* $ 6.62p3 f Pr-M4 4.385 2 1.768-2 - 1.81b2 1.75E*3 2.355-4 2.185-3 1 86-147 7.86b3 8.56b 3 - S.828 4 3.72b5 5.82b5 S.138*2 } W-187 f.30E*1 9.76be = = 4.74t+4 f.77b 5 3.43p0
- SP 239 3.Ma*3 3.198+1 -
1.80t*2 6.49E*4 1.33DS .1.77bt _- ~
~ ~
j Teolo 7.0-4 " (seet t'n kid) l Rae, 2ehoitties Psehser Se*e facters - Cults ODCM-7.0 ' f f (aree/yr Per pC1/2 ) 8 Rovision 6 m.ca ue neue ' user Terrou asteer f.es s -u.2 f.neer Pags 7.0-20 l l P B-3 . 1.12b 3 1.13b 3 1.138 4 1.128*3 1.121*3 1.128*) i C-14 3.598+4 6.7M4 6.7M* 3 6. 7 M* 3 6.73t*3 4.7Mel 6.7M+ 3 l so 24 1.618+4 t.6184 1.61t*4 1.61t*4 1.61E+4 1.6tb4 1.61t*4 P-32 2.tobe 1.H8+l = = = 4.22t+4 9.888 4 Cr-51 = = 8.55Dt 3.43b t 1.70E+4 1.08t*3 1.54b t me-54
- 4.29t+4 = 1.00b4 4.Mtd 2.298+4 9.518+3 No-$4 = 1. Ht+0 - 1.6?E*0 1.3tt+4 1.21bl 3.128-t Fe 55 4.74t+4 3.52t+4 - - 1.lttel 2.87b3 7.77h 3 J i
Fe-59 2.078+4 3.34E+4 = = 1.275+6 7.07t*4 9.67be j Co-57 - 9.tM*2 - = 5.07t*5 1.328 4 1.07b 3 i Co SS - 1.77b3 - - 1. t tb4 3.Mbe 3.ME*3 Co-60 - 1.3tt+4 - - 7.07t+4 9.628 4 2.ME*4 si-63 8.2t b l 4.63t+4 - - 2.75 Bel 6.338*3 2.80E+4 5145 2.998+0 3.NE-1 = = 0.188*3 8.4ebe 1.M8-1 Co4e = 1.99he - 6.03be 9.588*3 3.67b4 1.07be Re-65 4.368+4 ' 1.138*5 - 7.148 4 9.95t+$ 1.6M+4 7.03t+4 8e49 6.70s 3 9.ME-3 - 5.858-2 1.42t+3 1.02t+4 8.928-3 St-82 - = = = = = 2.99E4 Sr-83 - - = = = = 4.748*2 tr-84 - = = - - - 5.48s*2 tr-45 - - = = * = 2.538*1
' B>44 = t.98tel - = = 7.99E*3 1.Mbl Rb88 - S.62t*2 - - - 1.72bt 3. Mbt RF89 - 3.458*2 - = = 1.09pe 2.90b3 -l St-49 5.998 5 - = = 2.ME+6 ~ 1.67bl 1.728 4 i i
St=90 1.018*4 = = = 1.44te? 3.438*$ 6.MD6 - St-91 1.2ftet = = = 5.338+4 1.74tel 4.59pt ' St-92 1.318*1 = = = 2. 40b4 2.42bl S.2Sbt i bt0 4. t t b 3 - = = 2.62E+1 2.685+5 1.11E*2 l b9le 5.07bt - = = 2.81E*3 1.73b3 1.MS-2 ' t 91 9.Mt+5 = = = 2.63b6 1. M8* 5 3.MB+4 b92 2.Mb t = = - 3.39t+4 2.39t*5 5.815 1 bt3 1.04t*2 = = = 7.44E*4 3.898*5 $.11b6 3r-95 1.90bl 4.188+4 = S. Mt+4 2.238,4 6.11b4 3.70b4 , j 2r-97 1.88t*2 2.728*t = 3. 89D1 1. t M* $ 3.$15+5 1.40B+1 ' ! s>95 2.35E+4 9.165*3 - 8.62t+3 4. Htel 3.70t+4 6.$58*3 p>97 4.298-1 7.708-2 = 0.5$E-2 3.425*3 2.785+4 3.408-2 Me-99 - 1.72E*2 - 3. 92b2 1.355*5 1.27bl 4.368*1 fe=99e 1.788-3 3.448-3 - $.078-2 9.51b2 4.8tb3 5.778 2 fe-101 0.108 5 0.515-5 - 1.458 3 S.8Sb t- 1.638+t 1.088 3 Se-103 2.79t*3 - . .7.038 3 6.625*5 '4.488+4 1.07E*3 Be-105 1.53bo = = 1.34t+0 1.$98+4 9.958+4 5.558 1 Re-106 1.ME* 5 - - 1.045*5 1.43t*7 4.29t*5 1.69t+4 Rb-103e = = = = = =* - gh.106 = = = . - -. - es-ttes 1.691+4 1.14t*4 - 2.12b4 S.488+6 1.00b5 9. ME*3 Bette 5.74t+4 7.40tet 1.26t*2 - 3.24t+6 1.64b5 2.00E*4 Set 25 9.84p4 7. 59b2 9.10E*1 - 2.32t+6 4.038+4 2.07be fe-125e 6.738+3 2.3M* 3 t.92E 3 - 4.77bl 3.38be 9. H E*2 fe-127e 2.498+4 4.55b3 6.078+3 6. 36b4 1.44s+6 7.14b4 3.028*3 fe-127 2.778+0 9.51E-t 1.96t+0 7.07be 1.eebe S.62b4 6. t tbt fe-129e 1.92E+4 6.85E*3 6.338*3 S.03b4 9.76t+6 1.025+l 3.N t* 3 fe-129 9.778 2 3.508 2 7.142-2 2.575-1 3.935*3 2.555 4 2.385 2 fe=13te 1.34B+2 5.92b1 9.778+1 4.00E*2 2.86t*$ 3.estel 5.07b t fe-131 2.175-2 8.448-3 1.70E-2 S.8Sb2 2.05t*3 1.338*$ 6.59b3 I fe=132 4.818*2 2.728*2 3.171*2 f.775+3 3.778+$ t.NEel 2.638,3 2-130 8.188*3 1. M t+4 1.85E+6 2.45t+4 = $.11t*3 8.MS* 3 bl31 4.81B*4 4.815+4 1.62t+7 7.088+4 = 2.Nt*3 3. 7M+4 i 2-132 2.128*3 4.978*3 1.M B+ 5 5.25t*3 - 3.20E*3 f.88t*3 2-133 1.M8+4 2.038+4 3.85t*6 3.Ma*4 - S.488*3 7.7et*3 SalM t.17t*3 2.16t+3 $.07E+4 3.30t+3 - 9.558 2 9.95E+2 2-135 4.92b3 8.7He3 7.928*5 1.34t*4 - 4.ut* 3 4. ME* 3 Co-1M 6.51bl I.01t+6 - 3.3005 1.21bl 3.45t*3 3.258*5 Co 1M 6.$18+4 1.718*l - 9.55be 1.45t+4 4.188*3 1.1645 l Co-137 9.075*$ 8.25s+5 - 2.828*5 1.ME* 5 3.62b3 1.388*5 l Co-t M 4.33b2 0.40t*2 = 6.22b2 6.8ttet 2.10B+2 S.558+2 to-139 1.M8+0 9. MS-4 - 8.628-4 8.775+3 $.775+4 5.37b3 ' Be-Me 7.485+4 4.488+1 = 3.11B+1 1.748+6 1.038+$ 4.338 3 Be-141 1.96>1 1.998-4 - 9.47b5 2.928+3 2.755*2 6.368-3 Be M2 S.005-2 3.408-5 - 2.918-5 1.Mb 3 2.748 0 2.79>3 I Le=140 4.ubt 2.25b3 - - 1.83t+5 2.M8+5 7.598*1 l Le-M2 1.3eb6 4.118-9 - - 8.7eE*3 7.59b4 1.395-1 co-Ht 3.98b4 1.958+4 = S.SSE*3 5.44t*S $.44be 2.90h3 Co-H 3 3.MB+2 1.99t*2 -
- 4. ME* 1 1.15t*5 1.27bl 2.87B+1 Ce-M4 6.77be 3.128+6 =
1.173+6 1.30t*7 3.89b 5 3.618+5 Pr 143 1.058+4 5.55b3 - 3.o0t*3 4.31sel 9.738+4 9.ut+2 Pr=M4 5.965-2 1.05E-2 - 9.77b3 1.57b3 9.97b2 3.008-3 ed-M7 1.088+4 8.735*3 - 4.8tb3 3.38t+5 8.21t+4 6. Sit *2 If-107 1.638*1 9.Hb4 - - 4.11E+4 9.10E+4 4.33DO NP 339 4.448*2 3.34 Ret
- 9.73bt 5.81b4 6.40t*4 2.35b t
- = m
- .- . . . .. .- - . - . - . - - _ _ _ _ ~ _ _
?.we 74-4 woe bm ODCM-7 0 an.* seheinses panser son ruute = inras?
Revision 6 Pcga 7.0-21 < (area /7r por WC&h8) l pectide tone Elver thyroid Elener laas SI-tal f.Sedy 5-3 - 6.47tet 6.47b2 6.47t*2 4:478*2 6.47t*2 6.47b2 C-14 ' 3.65be 5.31t*3 5.388*3 5.3tE*3 5.31t*3 8.38t*3 5. 31b3 R4-24 t.Nt*4 1.Mt+4 1.Nt*4 9.Nt*4 1.9H+4 1.06t+4 1.06t+4 i P-32 2.0M*6 1.128*5 - -
- 1.61t+4 7.74 t+4 l Cr-51 - -
5.75Eet 1.325*1 1.38b4 3.57b2 8.95Eet - l see-54 - 2.53t+4 - 4.Mb3 1.00b e 7. M t*3- 4. M t*3 lan-56 - 1.54t*0 . . 1.10 be 1.25b 4 7.1?b4 3.218 1 , Fe-55 1.97E*4 1.178+4 - - 8.698 4 1.098+3 3. 3M* 3 ' Fe-59 9. M b e 2.35t+4 - - 1.02b6 2.48E4 9.48t*3 Co 57 - 4.518*2 - - 3.79t*5 4.Mb3 6.41t*2 1 Co-58 - 1.32t*3 - - 7.778+5 1.ttt+4 t.828*3 Co-40 - 8.82b 3 - - 4. 51b6 3. t M*4 1.18t+4 5443 3.39t*5 a.mbe -. - 2.e9t*5 3.428*3 1.48+4 l si-65 3.39p e 3.84E-1 = = 0.13b3 5.01h4 1.338-1 Co-H - 1.88be - 3.98t+0 9.308*3 1.308 4 7.748 1 ,
-En-45 ~ 1.9M*4 6.36t*4 - 3.25t*4 6.4?b5 5.148 4 3.1tE*4 '
3e-49 5.398 2 9.67b2 - - 4.028-2 1.47b3 1.32E+4 7.18b3 I tr-82 - - = ,= = - 1.3M4 ' St-83 - - - - - - 3.015+2 ar - - - - - - 4.get*3 tr-85 - = = = = = 2.Nb t 1 R>Se - 1.90t*5 - - - 3.Mp 3 8.828+4 l akte - 5.57E*2 - - - 3.39b2 3.47E*3 1 Ree9 - 3.21s+2 - - -- 6.828*1 3.86t*2 Br-89 3.98t+5 - = = = 2.03b6 6.40t+4 1.548+4 St-90 4.09te? - - - 1.12E+7 9.3ttel 3.598 4 -l St-91 9.548*1 - - - 5.36b4 7.H b4 3.44be i St-92 1.05tet ,
= = 2.38b4 1.40b 5 3.918-l T-90 3. 29b 3 - - - 3.69tel 1.048*5 8.82b t T-9te 4.078-9 - - - 2.798:3 2.35b3 1.398-2 Y-91 5.88t*5 - - - 2.45t+6 7.03t*4 1.57t+4 i bt2 1.Hs+1 - - -- 2.45b4 1.27b 5 4.6tbt j 7-93 1.50t*2 - - - 7.64t*4 1.67t*5 4.87 tee '
tr-95 1.158+5 2.79b4 - 3.11t+4 1.75b e 3.178+4 2.0M+4 Er-97 1.50t*2 2.Mte l - 2.598+1 1.10E*5 1.4ebl 3.17s*1 sk95 1.57be 6.45t*3 - 4.728*3 4.79t*5 1.27t+4 3.78t*3 set? 3.425-1 7.29b2 - 5.7002 3.328*3 2.69b4 2.638-3 Ite-99 - 1.658*2 - 2.65t*2 . 1.35b 5 4.878+4 3.238*1 fe-99n 1.408-3 2.888-3 - 3.118-2 8.118*2 3.05t*3 3.728 3 fe-let 6.518-5 0.33b5 - 9.791-4 5.848*2 8.44t*2 8.128-4 Au-103 3.02b3 - - 4.24t*3 5.52t*5 1.61E*4 6.798 2 Ru-105 ' t.22bc - - 8.995 1 1.57b4 4.84t*4 4.105-1 Su-106 8.68t+4 - - 1.07b5 1.16t*7 t.HE*5 1.09t+4 Rh-103e - = = = = - * - g6-104 - . . - . - - - as ties 9.98t+3 7.22843 -
.l.09be.3.67t*6 3.30b e 5.00t*3 sut24 3.79t+4 5. Mbt 1.01**2 - 2.65t*6 5.915+4 1.30E+4 S E125 5.17b e 4.77t*2 6.33t*1 - 1. H t+6 1.47t*4 1.09t+4 Te-125e 4. 7He 3 1.99b3 9.62b3 - 4.478*5 1.29t*4 6.58t*2 fe-127e 1.67t+4 6.9et*3 4.87E*3 3.75b4't.3tt*6 3.7M*4 3.97t*3 fe-127 3.33be 9.53bt 1.85t+0 4.86t*0 1.038*4 2.44 b e 4.095 1 fe-129e 1.418*4 6.99t*3 5.47t*3 3.188 4 1.688+6 6.9eB+4 3.33t*3 fe-129 7.888-2 3.47bt 6.75t 2 1.758-1 3.00t*3 3.6M4 1.088 3 Te-13te 1.07b2 5.908+1 8.93tet 2.658 2 1.99b 5 1.19s*5 3.638*1 fe-131 9.74b2 8.328-3 1.588-3 3.998-3 3.06b3 8.338*3 5.008 3 fe-132 3.738 2 3.3?bt 2.79b2 1.03t*3 3.4eb5 4.4tt+4 1.768*3 bile 6. ME* 3 1.398+4 1.60t+6 1.53E+4 . - 1.99t*3 5.57s*3 2 131 3.795 4 4.44pe t.48t*7 5.188+4 - 1.06t*3 1.96t+4 2-132 1.69t*3 3.54t*3 1.69t*5 3.95t*3 - 1.90E*3 1.368*3 bl33 l.12E+4 1.928*4 3.Mt+6 3.34t+4 - 3. ns*3 5.6eE*3 b1M 9.31E*2 1.88t*3 4.45t*4 3.09t*3 - 1.298*3 6.658*3 bt35 3.a68*3 7.60b 3 6.Mb 5 8.47t*3 - 1.8M* 3 2.77s*3 i Co-tM 3.96t*5 7.03t+5 - 1.90t*5 7.97t*4 1.3M*3 7.45b4 l Co 134 4.838 4 1.35t*5 - 5.Ht+4 1.18t+4 1.438*3 5.798+4 Co-137 5.49b5 6.13b 5 - 1.728 5 7.1 M+4 1.3M*3 4.55t*4 Co-138 5.95t*2 7.81t** - 4.10t*2 6.548*1 8.768*2 3.988 3 Se-1H 1.48 b e 9.N E-4 - 5.938-4 5.95t*3 5.90E*4 4.30>3 to-140 5.60t+4 5.40t*1 - 1. M E* 1 1. Set *4 3.Mtd 3.988*3 -
Be-set 1.57B-9 1.esb4 - 6.50E-5 2.978+3 4.75b3 4.978-3 to-M2 3.905-3 3.30>5 - 1.908-5 1.55b3 6.935+3 1.968-3 to-148 5.058*3 3.00b2 - - 1.68b5 8.488+4 5.158+1 la-le2 1.93DO 3.778-1 - - 8.338*3 5.958*4 9.m s-2 to-let 3.77p4 f.67t+4 - 5.258*3 5.17t*5 3.168+4 1.99t*3 Co-M3 2.938*2 1.93t*2 - 5.M E*1 1.48*5 4.978+4 3.31E*1 Co-144 3.19t+4 1.21E+6 - 5.38t+5 9.848 4 1.488 5 1.76b5 Pr-143 1.4ebe 5.34t*3 - 1.97s*3 4.3M*5 3.73b e 6.995 2 Pr-M4 4.798-2 1.85b3 - 6.728-3 1.61s*3 4.38t*3 3.41E 3
- Bd-147 7.Mb3 8.1 M* 3 - 3.15t*3 3.228*5 3.138*4 5.008*2 W 107 1.30tet 9.02t+0 - - 3.96b4 3.568 4 3.12t+0 sp-239 3.71t*2 3.32b t - 6.62b t 5.95t+4 2.49t*4 1.88t*1
1.ie 74-4 u.etee.n l 8.e* stu.-Coe.ana came., s . ruu,. . asutt ODCM-7.0 l
. (areefyr per pC1/es) 5:t 5 3 ama C-14 ROVi$lOn 6 (is a eres/rr per aCU.ec) 5:t cthers Pags 7.0-22 muellee sees Liver Thyroid Eldeer tens 81 IJ.2 T. Sear .
5-3 . . 1.638*2 7.63t*2 7.63t*2 7.635 2 7.638*2 7.638*2 C-14 3.63t+5 7.268+4 7.26t+4 7.268+4 7.26t+4 7.26t*4 7.265*4 Ba-24 2.54t+4 2.542 4 2.54t*6 2.54t*6 2.54t+6 2.545 4 2. 54 t*4 P-32 1.78t*10 1.068*9 * * . 1.921*9 6.60E*6 Cr SI = = 1.718*4 4.30t*3 3.605 4 7.20E*6 2. Mt+4 No-54 . 8.40t+6 - 2.50t+6 - 2.57t*7 1.60t*6 Me-56 . 4.238-3 = 5.ME- s - 1.358-3 7.518-4 . Ft-55 2.51t*7 1.73b7 - . 9.671 4 9.95t+6 4.048+6 l Fe-59 2. ME*7 7.00t*7 . - 1.95t*7 2.35t+8 2.688*7 Co 57 - 1.245*6 - - . 3.258 7 2.134+4 .J i Ce-58 - 4.72t+6 - = = 9.57t*7 1.M8+7 Ce40 - 1.64t*7 . - - 3.085 8 3.628*7 3143 6.73t+9 4.668*8 - =
- 9.73t*7 2. ME*8 8145 3.708 1 4.811-2 . . .
1.22t*0 2.198-2 C e64 - 2.411+4 . 6.085 4 = 2.058+6 1.131*4 to-65 1.37E*9 4.368+9 . 2.928*9 - 2.75t*9 1.97t+9 to-69 - . - - . . . I Br-82 - - . . . 3.72t+7 3.25t*7 tr-83 - . - - . 1.491 1 1.83t-1 ) St-te . . . - - . - l tr-85 - . . . . - - 26-86 . 2.59fet . . - 5.11t+8 1.21t+9 A6-88 - . . . . . - Reat . - - . . . - St-89 1.455*9 - - - - 3.33E+4 4.168*7 Br*10 4. W E*10 - = = = .1.358*9 1.158*10 St-91 3.131 4 = = = . 1.49tel 1.27t*3 St-92 4.895-3 . . . = 9.68t+0 2.118-2 T-90 7.07t*1 . . . - 7.50tel 1.90E+0 y-91. . - . . - . . T-91 8.60t*3 - - . - 4.73t*6 2.30E*2 T 92 5.421-5 . . . . 9.4 9E.1 1.545-6 T-93 2.33E-t - - - = 7.39t*3 6.438-3 tr-95 9.462+2 3.03t*2 . 4.76t*2 - 9.62t*5 2.05D2 tr-97 4.8E-1 8.598-2 . 1.308-1 = 2.HE*4 3.938-2 Nb-95 8.231 4 4.59D4 4.$48*4 . 2.79g+4 2.47t+4 pkt? = - = . . 5.473 9 . he-99 - 2.52t+7 - 5.72t*7 - 5.a5E*7 4.80b6 i Te-99e 3.25E+0 9.198 0 - 1.60t+2 4.50t+0 5.448*3 1.17b2 I fe-101 = = - . . . . ' Re-103 1.028*3 . . 3.898 3 - 1.19E*5 4. 39b 2 au-105 8.578-4 = - 1.111-2 - 5.24bt 3. N E-4 p.-106 2.048*4 . - 3.945 4 - 1.12t*6 3.58b3 R b103e - = . . . . . 36-106 . . - . . . . As 110e 5.838*7 5.39b7 . 1.06t*8 - 2.20t*10 3.20t*7 sette 2. 57p ? 4.84t*5 4.24E+4 = 2.00t*7 7.31t*8 1.02t*7 se125 2.04t*7 2.28t+5 2.04t*4 . 1.58t*7 2.258*8 4.h t*6 Te-125e 1.63t*7 5.902 4 4.90t+6 6.63t*7 = 6.50t*7 2.18b6 fe-127e 4.56t*7 1.64t*7 1.171*7 1.86b8 - 1. 54D8 5.54t*6 Te-127 6.72t*2 2.41t*2 4.98b2 2.74t*3 - 5.30be 1.45t*2 fe-129e 6.048*7 3.25t*7 2.08t*7 2.521*8 . 3.04p3 9.57b4 Te-129 . - . . - . . fe-131e 3.61t*5 1.77b5 2.80t+5 1.795e6 . 1.758*7 1.47t*5 fe-131 . . . . - .
- Te-132 2.39t*4 1.55t.6 1.71t+6 1.495 7 - 7.328 7 1.45t*6 7-1M 4.26t*5 1.26b6 1.07t+4 1.Mt+4 = 1.04t*6 4.96t*5 F131 2.M E*8 4.24t*8 1.391*11 7.278+8 - 1.12p3 2.43b8 2-132 1.H E-1 4.37bt 1.53b t 6.978-1 . 8.228 2 1.53E-1 2-133 3.97t+6 6.90D4 1.01t+9 1.20t*7 = 6.308*6 2.308 6 3-134 . . . . . - .
b135 1.39b4 3.63t+4 2.40E+6 5. 83b4 . 4.10t+4 1.Mbe Ca-1M 5.65bt 1.ME*10
- 4.35t*9 1.44b9 2.35b8 1.10t*10 Co-1M 2.61b8 1.03t*9 . 5.74t*8 7.87t*7 1.1?b8 7.42t*8 Ca-137 7. ME*9 1.81t+t0 - 3.43t+9 1.14t*9 1.95bt 6.41bt Co-1M . . . . . - .
So-139 4.708-4 = = = = 8. MS-8 1. MS-9 Se-140 2.698*7 3.388+4 = 1.15t+4 1.9M+4 5.548*7 1.76be as-141 . . . . . - . go-142 . . . - . . . 54-140 6.49t*0 2.36be . . - 1.64t*5 5.978-1 te-142 = = = = . 3.0M-8 - Ce-141 4.84t* 3 3.27t*3 - 1.52t*3 - 1.25pf 3.71b2 Ce-143 4.19t*1 3.09b4 - 1.ME*1 - 1. ME*4 3.42b6 Ce-44 3.58t+5 1.50E*5 - 8.87t*4 - 1.21b8 1.928+4 Pr-143 1.59E*2 6.378+1 - 3.688 1 - 6.Mb 5 7.88be Pr=144 - = * * = *
- 56-147 9.428*1 1.09E*2 - 6.37t*1 . 5.232 5 6.52bo W-187 6.56t*3 5.68b3 . . . 1.a084 1.92E+3 5p-239 3.HE*0 3.60E 1 .- 1.128*0 -
7.39t*4 1.MF1
Ssa. Greae-Coe-milk Pathway Dese Tactits . 71 Des s ODCM- 7.0 c.rantre Per scum E:t s-3 e.s e-se Revision 6 (e8 a aren/rr ser pCueec) ter cthere Pago 7 0-23 Decties tems Lher thyteld Eldaer laas $1422 f.8edy 5-3 - 9.94t*) 9.94te! 9.94t*2 9.94t+2 9.Mb2 9.M E*2 C-te 6.70tel 1.htel 1.34t*5 1. Mt* 5 1.34tel 1.Mb5 1.MEe 5 54-24 4.44E4 4.44t+4 4.44t*6 4.44t*6 4.448*6 4.44b6 4.64te6 P-32 3.15teto 1.95E+9 - - - 2.65tet 1.22t+9 Cr-St = = 2.788 4 1.102 4 7.131 4 8.40t+6 5.002e4 No-54
- 1.40b7 = 4.17t*6 - 2.875*7 2.78t+6 me-56 = 7.518-3 - 9.508-3 - 4.M8-1 1.338 4 Fe-55 4.4 5t+7 3.16t*7 * - 2.00t+7 1.37b7 7.Mt+6 Fe-59 5.20b7 1.2tt+8 - - 3.82t+7 2.878+8 4.68t*7 Co-57 - 3.258*6 - = = 4.198 7' 3.76b6 Co-58 = 7.958 4 - - -
1.10t+8 1.838*7 Co-60 - 2.78b7 - - - 3.62t+8 6.36t*7 51-63 1.18t*10 8.351 8 - = = 1.33t+8 4.01t*8 8145 6.788-1 8. ME-2 * . - 4.70D0 3.ME 2 Co-64
- 4.298 4 - 1.095 5 - 3.338 6 2.02t+4 2a-65 2.1t!*9 7.3ttet . 4.68b9 = a 3.10E*9 3.41t*9 to-69 . . . . . . .
St-82 Br-83
- . - - - - 5.64te? )
- . - . . - 1.91t-1 St-84 - - . . . . . !
Sr 85 - - . - - - - 8b-86 - 4.73t+9 - = = 7.00t+8 2.22t*9 8b-88 - - - . . . . 86-89 - . . . . - = Sr-89 2.678+9 - = = = 3.18b8 7.Mb? St-90 4.618e10 - - - - 1.868 9 1.63t*10 tr-91 5.75t+4 - = = = 2.61t+ 5 2.295*3 St-92 8.958-1 - . . - 2.24t+1 3.811 2 T 90 1.30t+2 = - - - 1.87be 3.30t+0 T-91a = = = = = = = F91 1. 54b4 = = - - 6.48t+6 4.248 2 T-92 1.00E4 - = = . 2.75E.0 2.908-6 T-93 4.305-1 - - = = 1.3tt+4 1.188-2 tr-95 1.655 3 5.221 2 - 7.47bt - 1.20t+6 3.598 2 tr-97 7.751 1 1.538-1 -- 2.32bt . 4.15t+4 7.06t-2 Eb-95 1.41E*5 7.80t+4 - 7.57t+4 - 3.348*8 4.302*4 Nb = = = = = 6.ME-8 = me-99 - 4.56t+7 - 1.MEe8 . 8.14t*7 8.69be Ye-99m 5.64be 1.57bt - 2.34b2 8.73t+0 1.838 4 2.Nt* 2 fr-101 = = = * - .
- Be-103 1.818+3 - = 6.40Ee3 - 1.52t+5 7.75t*2 l Se-105 1.57b3 - -
1.97b2
- 1.26t+0 6.088-4 '
So-104 3.75b4 - - 7.23b4 = 1.008 4 4.731*3 th-103e = = = = = *
- Sh-106 = = = = = * =
Aa-110m 9.43t+7 9.11t*7 = 1.74E+8 = 2.56H10 5.54t*7 I 8b-124 4.59E*7 8.46t+5 1.04t+5 - 4.018+7 9.25b8 1.79b 7 Sb-125 3.65b7 3.99E* 5 3.493 4 = 3.211+7 2.848 8 8.54t+4 fe-125e 3.60 4 7 1.088 7 8.39b 6 = = 8.Nt*7 4.02t*6 fe-127e 8.64t*7 2.99E*7 2.01t*7 3.42t*8 = 2.108+8 1.00t*7 fe-127 t.24e+3 4.41t*2 8.59t*2 5.M t+ 3 - 9.61t*4 2.68b2 fe-129e 1.ttb8 4.908 7 3.37Ee7 4.63t+8 - 4.158 8 1.75t*7 fe-129 - = = 1.67t-9 - 2.188-9 - Te-131e 6.578*5 3.15tel 4.74t*5 3.'29t*6 - 2.53te? 2.43b5 f ,.131 . - - . . - . fe-132 4.285 6 2.7tb4 2.NE*6 2.608 7 = . 8.58b7 2.55t+6 b1M 7.498+5 2.17b6 1.771 8 3. 34 t+6 - 1.67b6 8.utel 2-131 5.38t+8 7.53t*8 2.30t*11 t.Sete9 - 1.49tet 4.Mt+8 b132 2.90E-1 7.598-1 2. Mte t 1.20po . 3.31b1 2.728-1 b133 7.24b6 1.238*7 1.728+9 2.158 7 . 9.30t+4 3.75t+6 1-134 = - - - = . . b135 2.67t+4 6.35t+4 4.84t+4 1.00b 5
- 7.03b4 2.35b4 Co 134 9.01E*9 2.31t*10 = 1.34E+9 2.80t*9 3.87t+8 1.07t*10 Co-1M 4.4 5t+8 1.758*9 a 9.53t+8 1.50Ee8 1.4tt+8 1.18b t Co-137 1.34Eete 1.788*10 -
6.06t*9 2.35t*9 2.53bt 6.30b 9 Co-138 - = = = = = = Se-139 4.498-8 . = = =. 7.758-7 2.53E-9 Be-140 4.858+7 S.958+4
- 2.02b4 4.00t+4 7.49t*7 3.13b6 he-141 * * - - = = -
Be-142 - * = . . . = 14-140 8.06be 3.Mt*0 * = = 2.278*5 1.05 tee Le-142 - = = = . 2.238-7 - Co-141 8.E7B*3 5.92b3 - 2.79b3 = 1.69t*7 6.81t+2 Co-143 7.69t*1 5.60be - 2.StE*1 - 1.68t4 6.25t+0 Co-144 6.58b5 2.728+5 - 1.63t*5 - 1.Mba 3.Mb4 Pr-143 2.92b2 1.178*2 - 6.77E*1 - 9.41t*5 1.45b t Pr-144 - . . = = . - Ad-147 1.01b3 1.978+2 - 1.168*2 - 7.11t+5 1.18t+1 W-187 1. 30E4 9.788+3 - - = 2.458+6 3.43E+3 sp-239 6.998+0 6.598-1 - 2.07t+0 - 1.Mt+5 3.ME 1
. temo 7.o-4 usetsomeo ODCM-7.0 Rae. Greae-Coe Stilk Pothese Base Facters . CEILD 4 2 Rsvision 6 (aree/rr per scuw for s-3 esa C 14 (e8 a aren/rr per pCunee) fee (there Page 7.0-24 sus!!6e seen 8.iver Thrrold 518eer less 81-111 T.Sedr 34 .- 1.lf p 3 1.575 4 1.575 3 1.575 4 1.lis4 1.575 0 ( C-14 1.65 be 3.29b 6 3.29 Eel 3.298*5 3.29bl 3.29b 5 3.29t*5 Be-24 9.23E+6 9.23t+6 9.2H+6 9.23t*4 9.2M+6 9. 2M+4 9.2M+4 P-32 7.77E*10 2.64bt = = - 2.15b9 3.008 9 Ct=51 . - 5.ut*4 1.55b4 t.03pl 5.415 4 1.028 5 I he-54 = 2.09t+7 - 'l.878 6 = 1.76t*7 5.588+6 ! Me-56 . 1.312-2 = 1.548 2 = 1.90E+0 2.95E4 Fe-55 1.t28 8 5.9H+7 - - 3.358e7 1.50b7 1. M t+7 , Fe-59 1.20t*8 1. 958*8 - - 5. 65s+ 7 2.93s+8 9.715+7 j Co-57 - 3.ME+6 - = = 3.14B+7 7.77be co-50 - 1.21t+7 - - = 7.84E+7 3.728 7 Co-40 . 4.338*7 . . . 2.39b8 1.275+8 Ob63 2.ME*10 1. 59pt * = b 1.078+8 1.01t+9 5145 1.us.O 1.Mb t = = = 1.918*1 9.11E-2 Co-H = 7.558 4 . 1.828*5 - 3.54be 4.M5+4 , te45 4.13t+9 1.10E*10
- 6.ME+9 - 1.9M*9 4.85t*9 En-49 - = = = = 2.148-9 =
! St . * * * = = 1.155+8 Br+03 = = = = = = 4.698-1 3r-84 . . . . . . . j -br-85 - * =- = = =
- 4 a6-86 = 8.77bt . - - 5.64t+8 5.398+9 4
ab-88 - . . . = = . . ab-89 = . . . - - - - St-89 6.628*9 = = = - 2.54E+8 1.89b8 ' St-90 1.128 11 . = = = 1.51t+9 2.83t*10 St-91 1.41bl = . . - 3.11bl S.3Me3 St-92 2.195+0 - = = = 4.14 Eel 4.76b2 F90 3.22E+2 . = = = 9. 85bl 8.6tbo 7-91e . = = = = . - F91 S.918+4 * = = = ' $.21546 1.048*3 T-92 2.45-4 = = = .- 7.10s+0 7.eu-6 1 7-93 1.068+0 . - = = 1.57t+4 2.908-2 i tr-95 S.B4tel 8.458 2 = 1.218*3 - 8.sts*5 7.525 2 l Er-97 1.09E*0 2.728-1 . 3.915-1 . 4.1M+4 1.618-1 ] 4 Ekt5 - 3.181*5 1.34b5 - 1.168 5 - 2.29b8 8.848+4 i gb-97 = . . . . l.458-6 = ! 4 No-99 - 8.29te? - . 1.77t*8 - 6.8Me7 2.055*? i fe-99e 1.29E*1 2.548e1 - 3.688 2 1.298 1 1.445+4 4.308+2 l' 9 te-101 = = . . . . . br103 4.298+3 . = 1.088+4 = 1.11E*5 1.6St+3 to-105 3.821-3 . = 3. ME-2 = 2.49be 1.198 3 au-106 9.24be - - 1.25tel = 1.44E+4 1.15t+4 Ab-103e = = = = = =
- j Sh-106 = * = = = = =
l As-lies 2.098+8 1.41b8 = 2.63t+8 = 1.68te10 1.1M+4 l
$b-124 1.095+8 1.41b8 2.448+1 = 6.83E+7 6.79b8 3.81b7 Sb-135 8.70t*7 1.415e6 8.Mb4 - 4.458e 7 2.88b8 1.828*7 Te-tale 7.ME*7 2.80b7 2.07b7 = = 7.13b7 9.N E+4 fe-121e 2.88b8 5.60t*7 4.975+7 5.9M+8 - 1.648+4 2.47b7 Te-127 3.06Ee3 8.25te! 2.128e3 8.718e3 + - 1.34b 5 6.968+2 fe-129s .2.71E*8 7.618*7 8.74t*7 8.80b8 . 3.32s+8 4.23t*7 fe-129 = * . 2.875 9 = 6.128-8
- Te-131e 1.60t+6 5.538+5 1.1446 5.35t*6 = 2.34b7 8.89E*$
te-131 . = . . . . . Te-132 1.ette? 4.52b4 6.988+4 4.30E*7 - 4.558*7 5.46t*6 21M 1.75t+6 3.548+6 3.90b e $.29t+6 - 1.ub6 1.82t+6 2-131 1.308*9 1.31t+9 4.34t+11 2.158+9 = 1.17b8 7.Mb8
, b132 6.86b t 1.26be 5.858e1 1.938 0 - 1.48be S. Sept F133 1.76te? 2.188+7 4.ME*9 3.63b7 . 8.778+6 8.23E+6 2-th - = = . = * =
2-135 5. M8+4 1.elb5 9.30be 1.618el . 8.00b4 4.97be Co 1M 2.36b10 3.71b10 = 1.158+10 4.13E*9 2.80E+8 7.838*9 Co-1M 1.00t+9 2.768+9 - 1.478+9 2.19t+8 9.788*7 1.79E*9 Co-137 3.228*10 3.89t*10 = 1.018*10 3.62b9 t.93b8 4.S$8*9 go.tw . = . . . . -
; So-139 2.148-7 = = - - '= 1.238-5 6.195-9 1.17be 1.83b5 S.348+4 6.128*4 5.MS*7 8.84be an=540 .
go.141 . . . . . = . 3 142 . . . . . = = la-40 1.93t*1 6.74be . = = 1.888+l 2.27be La-142 . . = = . 2.513-6 - Co-141 2.198+4 1.995+4 - 4.788+3 . 1.368+7 1.62b3 Co-143 1.09E*2 1.03t+$ = 4.29t+1 - 1.50t+6 1.48b t Co-tee 1.62t+6 5.99b5 - 2.82b5 - 1.338+8 8.Mb4 Pr-143 7.238*2 2.175+2 - 1.17b2 - 7.80pl 3.59b1 Pr=144 . . . . . = = Sbl47 4.45t*2 3.80t*2 - 1.981+2 . 5.7tb 5 2.79t+1 W-107 2.9tb4 1.728+4 - = = 2.42b6 7.73t+3 tr-239 1.72E+1 1.238+0 = 3.57be - 9.14t+4 8.681-1 4
N 1 Sue Gree -Coe-sta pet 8eer sees rattre - sten? ODCM-7.0 i (aremtre 9er Scuen ser 81 and C-14 R:: vision 6 (es a erantre per aCuned for camer. Pagn 7.0-25 1 1 Declide some Liver thyrelt Eldeer last 8bLLI f.tedy n '
- 2. Mt
- 3 2. ME* 3 2.38b3 k.ME*3 2. ME
- 3 2.38t*3 C-14 3. 2 H+ 6 6.89t* 5 6.89E*5 4.49t*5 6.89b 5 6.89b 5 6.89t*5 i se-24 1.61t*7 1.61t*7 t.61t*7 1.etE*7 1.61t*7 1.61b7 1.61E*7 l P-32 1.60t*11 9.42b9 . . = 2.17b9 6.21t*9 Cr-51 . -
1.05b 5 2. ME* 4 2.0$b 5 4.7tb6 1.61b 5 No-54 . 3.89E*7 - E.638*4 = 1.43t*7 8.83t*6 he-56 = 3.21b2 . 2.765-2 = 2.9tt+0 5.538 3 Fe-55 1.358*8 8.721 7 = . 4.27b7 1.19t*7 2.33t*7 Fe-59 2.258*8 3.93b8 = = 1.16t+8 t.888*8 1.55t*8 Co-57 - 8.95t+4 = . - 3.05b7 1.Nt*7 Co-50 = 2.43t*7 . = = 4.858*7 6.06b7 i Co-60 - 8.81E*7 - =
- 2.10E*8 2.88b8 l 51-43 3.49t*10 2.Mb9 - = .
1.07E*4 1.21869 5145 3.5tb o 3.978 1 . - - 3.028*1 1.81bt 0,44 - 1.488 5 - 3.t Fb 5 - 3.858*6 8.69E*4 te45 5.55t*9 1.90b le - 9.23t*9 . 1.6tE*10 0.78t*9 te49. - . . . . 7.MS-9 . 3r-82 - = . '. . . 1.948 8 Br-83 - = . = =
- 9.95b t Br-te - - - - = . .
3r-85 . . .- . . . . REN = 2.228*10 = . . 5.69t*8 1.10 tete 36-48 . . . . . . . 8b-89 = = = = = . . i St-89 1.268*10 - = . - 2.59E*8.3.6tb8 l l St-90 1.228*11 . . . . 1.52t+9 3.18t*10 St-91 2.94t*5 . . . . 3.488*5 1. 96b4 St-92 4.65t*0 - * - - 5.0tE*1 1.71b t Y-90 3-9te 6.80E*2
- =
=
9.39t*5 1.821*t 7-91 7.33t*4 . - . - 5.26t+6 t.95t*3 f.92 5.221-4 - - . = 9.97b e 1.471-5 T 93 2.253*0 - . - - 1.78t*4 6.13E-2 tr-95 6.83t*3 1.Mb 3 - 1.79t*3 - 4.28b5 1.18t*3 tr-97 3.99b0 6.851 1 - 6.91b1 - 4.37t*4 3.13F1 5995 5.938*5 2.448*5 - 1.75t* 5 - 2.068*8 1.4 tb5 5997 - - . . . 3.708 4 . me-99 - 2.12t*8 - 3.17b8 - 6.98t*7 4.138*7 fe-99e 2.69tet 5.55t*1 . 5.97t*2 2.90t*1 1.61E+4 7.158*2 te.101 . . . . . .
- Re-103 8.69t*3 . - 1.81t*4 - t.Nt* 5 2.9tE*3 to-105 8.06F3 = . 5.921 2 . 3.3tt*0 2.?tt-1 Re-106 1.90b 5 . - 3.25t*5 - 1.44t*6 2.ME*4 aptose . . . . . . -
3ktM . . . . . . . As-110m 3.86t*4 2.82t*8 . 4.0M*8 - 1.46t*10 1.Nf *8 SW124 2.89t*8 3.86t*6 5.548*5 - 1.StE*8 6.468*8 6.49t*7 SW125 f.49t+8 1.45t*4 1.87E*5 - 9.Mb7 1.99b4 3.07b7 l Te-125e 1. 51D S 5.04t*7 5.87t*7 = =- 7.188*7 2.04b7 l Te-127e 4.21b8 1.40t*8 1.228*4 1.04b9 . 1.70b8 5.10E*7 j i Te-127 6.50t*3 2.18b3 5.29t*3 1.59t+4 - 1.Mb 5 1.40t*3 Te-129e 5.59E*8 1.92t*8 3.45t*8 1.40t*9 - 3.34E+8 8.62t*7 fe-129 2.08t-9 . 1.755-9 5.188-9 a 1.ME-7 - Te-13te 3.M b6 1.Mb6 2.76be 9.3554 . 2.29b7 1.121*6
= = . * -
- Te-131 =
To.132 2.9007 1.04Ee? 1.54t*7 4.51E47 . 3.85b? 9.72b6 blM 3.60t+6 7.92b4 8.88t*8 8.70f*6 = 1.70t+6 3.18be bt31 2.728*9 3.21b 9 1.058*12 3.75t*9 - 1.151*8 1.41t*9 b132 1.42b4 2.89E*0 1.35t*2 3.22t*0 - 2.34be 1.03DO bt33 3.72b7 5.4tte? 9.44b9 6. ME*7 - 9.Mbe 1.58b7 bile . . 1.011-9 - = = = bt35 9.21E*5 2.41t*5 2.16b 7 2.69t*5 . 8.74t*4 8.00E*4 Co-134 3.65t*l0 6.00E*10 = 1.75t*10 f.teht 1.85t+8 4.87bt Co-lM 1.968*9 5.77b9 - 3.30t*9 4.1JE*8 8.76t*7 3.15b 9 Co.137 5.tSE*10 6.02telo - 1.621*t0 6.55b t 1.88t*8 4.278*9 Co-tM - - . = = . . De-139 4.55t-7 - - . . 2.885-5 1.128-8 be-140 2.41E+8 2.41E*5 . 5.7M+4 1.488 5 5.928*7 1.348*7
. =
to-141 = = = . . 8e-142 . . . . . . la-140 4.838*1 1.59tet . . - 1.87t*5 6.09t*0 5m-142 * - . . = 5.215 4 . Co-141 4.35t+4 2.64t+4 . 8.tSE*3 - 1.37t*7 3.titel Co-143 4.80t*2 2.65b5 - 7.721*1 - 1.558 4 3.02b t Ce-144- 2.3He6 9.52b 5 .- 3.85b5 - 1.338*8 1.3005 pr-143 1.49b3 5.59b2 - 2.08t*2 - 7.898 5 7.41b1 pr-144 . . . . . . . 36-147 8.82t*2 9.M a*2 - 3.49E* 2 - 5.74b5 5.55t*1 W-187 6.12t+4 4. Nt*4 - = . 2. 50b6 1.47E*4 pr-239 3.64tel 3.25be . 6.49b o . 9.40 be 1.84t*0
- - ~
~'ODCM-7 d m u. Seese-Cov east eetwer Saee teet:re - autt Rsvision 6 (aree/rr per acuen for 8 3 and C-14
* ('8 a aree/yr per ac uore) for gthers Pa0e 7 0-26 Nectide Sees Liver Thrrold Eldeer last 81 111 f.Sedy 5-3 - 3.2SE*2 3.258*2 3.255 2 3.25t.2 3.25tet 3.25te!
C-14 3.33tel 6. Ht+4 6. 4t +4 6.u t+4 6.Ht+4 6. M t+4 6.MEe4 me 24 1.84E 3 1. N E- 3 1.848 3 1.84t 3 1.848-3 1.648-3 1.ht 3 P-32 4.65t*9 2.898+8 - - - 5.23t+8 1.8vs+8 Cr-51 - - 4.221 3 1.541 3 9.ME*3 1.785 6 7.07te) No-54 - 9.1$t+6 - 2.72t+6 - 2.80E*7 1.75t+6 no-54 - * = = = = . Fe-51 2.938*8 2.02E+4 . . 1.13t*8 1.16t*8 4.721e7 Fe-59 2.678+8 6.27E*8 -
- 1.75E+8 2.891 9 2.40E 8 Ce-57 - 5.Mtd = = = 1.4 M* 8 9.37t+6 Co-58 - 1.03t.7 - - - 3.70t*8 4.10te?
Co-40 = ?.52t*7 - =
- 1.41t*9 1.ht+8 51-43 1.89t.10 1.318e9 - = = 2.7M*8 6.338*8 3 31-65 - - - - - - .
j Co-H - 2.95t 7 - 7.4 5E - 3.$28-5 1.391 7 1 i 2 45 3.568*8 1.138 9 - 7.57t+8 - 7.13t+8 $.128 8 i to-49 = = = = = = = i St-82 = = = = = 1.44t*3 1.26t*3 2 tr-83 . - . . . . . St-84 = = = . . = = St-85 - - = . . - - j REN
- 4.87E*8 = = = 9.60t*7 2.27t+4 ah-84 - - - - - - =
gett . . . . . . - Sr-89 1.01E*6 . . - - 4.84E+1 8.658 4 . St-90 1.24t+10 - . . - 3.198+8 3.011 9 St-91 - - - = = 1.381-9
- Sr-92 = = . = = =
- T-90 1.07E*2 - . *
- 1.13t+6 2.86t+0 y-9te - . . . . . .
1 91 1.138*6 - - - - 6.24E+4 3.03t+4 y 92 . . . - - . - Y-93 - - - = = 2.088 7 - 1r-95 1.881+6 6.04t+5 - 9.46tel = 1.915+9 4.098+1 tr-97 1.831-$ 3.69E-6 - 5.585 4 - 1.14t+0 1.698-6 metl 2.29t*6 1.28t+6 - 1.26t+6 - 7.7$3*9 6.86tel sp97 - . . . . . . Me-99 - 1.09t*5 - 2. HE* 5 - 2.528el 2.078+4 Te-99e = * - = = * -' Te-101 - - - - - - - Ae-103 *1.06t*8 . . 4.03t+4 .. 1.2M+10 4.S$t+7 Se-10$ . = = = = = . Re-1M 2.80t+9 - - $.40t+9 *
- 1.81t+11 3. 54 t*8 ag-103e = - - - . - -
gh-1H = = = = = = = As-110e 6.69E*6 6.19 tee - 1.228 7 - 2.52t+9 3.678+6 SE124 1.98t*7 3.748 5 4.80E+4 - 1.54t*7 8.628 8 7.01E+4 SE125 1.91t*7 2.1 M
- 5 1. M I+4 = 1.478 7 2.10t+8 4.54t+4 fe-125e 3.59t+8 1.30E*8 1.08t*8 1.468+9 . 1. 4 M+9 4.818+7 fe-127e 1.121 9 3.998 8 2.85t*8 4.5M*9 - 3.74Ee9 1.54t+8 fe-127 - = = 1.091-9 - 2.108-8 =
Te-129s 1.14t*9 4.27t*8 3.938 8 4.778+9 - $.76t+9 1.41t*4 Te-129 - = = = - - - Te 131e 4.51E*2 2.21E*2 3.50 set 2.241 2 = 2.198+4 1.848 2 f -131 - . . . . . . fe-132 1.40t+6 9.07E*5 1.005 6 8.73t+6 - 4.29t*7 8.lltel 2-130 2.358 4 6.MI4 S.888-4 1.088-5 - S.988-4 2.743 4 2-131 1.088+7 1.541*7 S.05t+9 2.64te7 - 4.07E*6 8.031*6 2 132 . . . . . . . 3-133 4.304-1 7.478 1 1.10t*2 1.30t+0 - 6.721-1 2.38t-1 2-134 . . . . . . . 3-13$ . . . . . . . Co-134 6.57t+8 1.let+9 - 5.068 8 1. ME
- 8 2.74t+! 1.asht Co-1H 1.188+7 4.67t*7 - 2.60t*7 3. Set +6 5.30E4 3.Mte?
Co-137 0.725*8 1.19E*9 - 4.05t*8 1.35t*8 2.311 7 7.811+8 Co-138 - = = - . . . 8 139 . . . . . . . Se-140 2.888+7 3.618+4 - 1.238+4 2.878+4 S.921*7 1.891 4 8.-141 . . - - . . . Se-142 . . . . . - . 14-140 3.60s 2 1.813-2 - - - 1.333 3 4.798-3 3,s.142 - . . . . . . Ce=141 1.40E+4 9.68t+3 - 4.40t+3 - 3.622 7 1.085*3 Co 143 2.098-2 1.558*1 - 6.00E-3 - S.788*2 1.718-3 Co-144 1.468+6 6.09t*5 - 3.618*5 - 4.938 8 7.83t+4 Pr-143 2.138 4 8.548+3 - 4.931*3 - 9.3He7 1.865+3 Pr-144 - - - - - - - 34-147 7.08t+3 8.18te) = 4.78t*3 . 3. 9M* 7 4.90t+2 W-187 2.16t-2 1.818-2 - - - S.925 0 6.328-3 me 239 2.54E 1 2.518-2 . 7.848-2 - 5.15t*3 1.395-2
Tamae 74-4 (eesti - 4) l ~ODCM-7 0 l ane true-earesas Petaner Snee rectors - ftanatta Rovision 6 j
. (ares /rr per acus') r:r 84 ene C-14 P:gs 7 0-27 '
(18 a ernstyr per ett/su) for sthere sectise ,8eme Liver Thyroid tiener Imes $14LI T.Sedy i I 8-3 - 1.Mb t 1.948 2 1. M E* 2 1.94b2 1.M t*2 1.948 2 C-14 2.81E*5 5.628 4 S.62t+4 5.62t*4 S.628+4 5.628*4 $.628 4 me 24 1.471 3 1.475 3 1.471-3 1.47t-3 1.471 3 1.47E-3 1.471 3 P-32 3.93bt 2.44b8 . . .. 3. M t+ 8 1.52t+8 l Cr-51 . - 3.14E*3 1.24td 8.07Ee3 9. Mt + 5 5.65t+3 me-54 - 6.N E*6 - 2.06t+4 . l.63b7 1.381*6 Me-56 . . - - - . . Fe-55 2.38t+8 1.69t+8 - . 1.07t*8 7.30b 7 3.938*7 Fe-59 2.115+6 4.98t+8 . - 1.57t+8 1.18t*9 1.928,8 , Co-57 . 4.53t+6 - . . 4.45t*7 7.59t+6 i l Co-58 - 1.41847 . . - 1.M E*8 3.258*7 Ce40 = $.83te? - - - 7.60E+8 1.31t+8 l- 31-63 1.82E+10 1.07t+9 - . . 1.7 tee 8 S.15t+8 31-65 = . . . . . . l Co-H . 2.415-7 - 6.10E-7 - 1.878-5 1.138-7 to-65 2.50b 8 8.69b8 . $.56b8 - 3.68b4 4.05t*4 to-69 . . - . . . . Br-82 . . - . . . 9.98Ee2 Sr.f3 - - . *- = = . Br-84 . - = = - . - St-85 . . . . . . . SkS6 - 4.06t+8 . - . 6.01E*7 1.91t+8 I SbH . . . . . . . gb-89 . - . . . . . Sr-89 2.546+8 . - - - 3.03t+7 7.29te6 St 90 8.05E+9 . . .
- 2.268 8 1.99t+9 St-91 . . - - . 1.10g-9 .
St-92 - - - - . . . T-90 8.MEe t . - - . 7.60E+$ 2.42E+0 T-91e , T-91 9.Mt+5 . - - . 3.925*8 2.Mb4 T-92 . . . - - . - T-93 . . - - = 1.698-7 . Er-95 1. 51b 6 4.761 5 . 6.991 5 - 1.10b t 3.27b5 j tr-97 1.53b5 3.825-6 . 4.583-4 - 8.185 1 1.395-6 ! ubts t.79b6 9.94t+5 . 9.64tel - 4.25t+9 5.478+5 t ypgy - . . . . . . Me-99 . 8.Mt+4 - 2.06b$
- 1.618e$ 1.71t+4 l Te-99e . . . . = = =
[ Te-101 . . - . . - - Su-103 8.60t*7 - - 3.031 8 - 7.188*9 3.Hbf l I no-iol . . . . - . . Re-106 3.36t+9 . - 4.55bt . 1.13Eett 2.97b8 a -103e - - . . . . . Rbl06 = = = . * = . As-110m 5.06t*6 4.79t+6 - 9.14b6 - 1.35t+9 2.91b6 89124 1.62b7 2.988*5 3.67t*4 .- 1.4tt+7 3.36:+8 6.31t+6 l SW125 1.ME*7 1.71b5 1.49b4 - 1.37t*7 1.22t+8 3.ME+6 ' Te-125e 3.03b8 1.09E*8 8.47b7 - . 8. Mtet 4.05E+7 Te-127e 9.41E*4 3.34t+8 2.24b8 3.82b9 . 2.35bt 1.13E+8 Te-127 = . . - - 1.75E-8 . Te-129s 9.58t+8 3.56be 3.09b8 4.ettet . 3.608 9 1.54;;2 Te-129 . . . . . . . Te-131e 3.7M* 2 1.80E*2 2.718e2 1.88t*3 . 1.455 4 1.50E*2 Te-131 . - . . . . . Te*l32 1.15E+4 7.268*$ 7.66b5 4.97t+6 *
- 2.305 7 6.84 Eel 1 2 130 1.89E4 $.4884 4.475-4 8.448 4 . 4.218-6 2.198 4 !
2 131 8.95b6 1.258*7 3. ME*9 3.168+7 . 2.64E+6 6.738*6 2-132 . . - . . . - bt33 3.598-1 6.108 1 8.5tE*1 1.87be - 4.618-1 1.86t-1 1 2 134 . . . . . . . 3-135 - . . . . . . Co-134 S.23t*8 1.238*9 . 3,913 8 1.493 8 1.538 7 $.718 8 , Co 1H 9.12E+6 3.63bt
- 1.97t+1 3.11t+6 2.92b6 2.645*7 Co-137 7.34t+8 9.63t+8 . 3.28tet 1.27b8 1.37Ee7 3.M3 8 Co-138 - . . . . . .
Se-139 . . . . . . . Se-140 2.388*7 3.91t+4 . 9.888*3 1.968*4 3.678 4 1.53E+4 Se-141 . . . . . . . Se-142 . g,-%0 2.968-2 1.45t-2 . . - 8.35b2 3.875-3 g,.g3 . . Co.141 1.188+4 7.868+3 . 3.788+3 .. 2.25t+7 9.038*2 Co-143 1.?M-2 1.28t+1
- 5.748-3 - 3.85t* 2 1.43b3 Co-M4 1.21E*6 5.08t+5
- 3.045 5 . 3.09b8 6.60be Pr-143 1.79E*4 7.15t*3 . 6.Mtd - 5.90E+7 8.92142 Pr- 44 - .
nd-147 6.24h3 6.798+3 - 3.98b3 . 2.alte? 4.068+2 w-187 1.815-2 1.682 2 - - . 3.99po 5.178 3 8p-239 2.23bt 2.11F2
- 6.618-2 - 3.39b 3 1.17b2 l
i
Yetne 7.o-4 ti.ncisee4 .I nue cease eee. ness resvy neee 7eente - Caus ODCM-7 0 I Rovision 6 i
* (area /rf Det set /e83 for 5-3 med C 14 I (es a eren/yr pge act/ses) for nhere Pa9a
" 7 0-28 '
Bec316e toes Liver Thyteld Klesey lae8 83-11J f. Seer 5-3 '
- 2.ME*2 2.ME*2 2. h t*2 2.ht*2 2.ht*2 2.ht*2 !
C-14 5.29tel 1.Mtel 1.Mtel 1.NE* $ 1.86t*5 1.M!*l 1.Mtel Ro 24 2.ME 3 2.34E 3 2. h t- 3 2.M E-3 2.Mt 3 2.Mt 1 2.ht 3 J P 32 7.41t*9 3.47t*8 - = . 2.05t+8 2.648 8 Cr-$1 * - 4.89E* 3 1.34 E.3 8.93t 3 4.678*5 8.81t+3 she-54 - 7.998+4 - 2.24E+6 - 6.70E*6 2.138 4 see-56 - - - = . . . Fe-55 4.57t+8 2.42t+8 * - 1.378+8 4.49E*7 7.$18+1 ye-59 3.78t+8 6.125*4 -
- 1.77E*8 6.378*8 3.0$t*8 Co-57 - S.928 4 - - - 4.8$8*7 1.30t*7 Co-SS = 1.658*7 - = = 0.00t*7 S.NE*7 !
Ce48
- 6.938*7 = *
.== 3.84t*8 2.048*8 '
51-43 2.91t+10 1.562*9 - = 1.05t*8 9.91E*8 51-45 - = = * - *
- Code - 3.248 7 - 7.428 7 - 1.521-5 1.ME-?
te45 3.758+8 1.00t+9
- 6.304+8 = 1.76t*8 4.21t*4 to-69 . . . . - - .
St-82 = . . - -
- 1. ME* 3 gr-83 . . . . . . .
3r.e4 . . . . . . . k4$ . . . . - . . B>S6 - $.768+8 - = = 3.71E*7 1.548*8 apS8 . . . . . . . 36-39 . . . . St-89 4.82t+8 - = . - 1.86t*7 1. ME+ 7 Er-90 1.04t*10 . . . . 1.40E+8 2.M1+9 sr-91 - - - - - 1.018-9 - St-92 - = = = * - 1 90 1.70t*2 - . = = 4.84E+$ 4.S$t*0 T-91e = = = = - =
- T-91 1.815+6 - = = = 2.41E*8 4.83t+4 1-92 . . . . . . .
7 93 = . = . . 1.558 7 - 2r-95 2.688 6 $.89t+$ - 8.43tel - 4.141+8 S.24E+5 tr-97 2.84t 5 4.10E4 - 5.898 4 - 6.218-$ 2.422 4 s>95 3.095 4 1.30E+6 - 1.13t+6 - 2.23t+9 8.618e5 p>97 . . . . . no-99 - 1.25tel - -2.678+$ = 1.031*l 3.095+4 sette . . . . . . . fe-101 = = =. . . = = to-103 1.568+8 - - 3.925 0
- 4.041 9 5.988*7 ge-105 . . . . . - .
As-1M 4.448*9 - - 5.995 9 - 6.90t*10 5.54t*8 sh-103e . . . = = = = th-106 a = =
,= - = =
As-190s 8.40t+6 5.67E*6 = 1.061 7 - 6.75t*8 4.53t+6 89124 2.93t*7 3.00Ee5 6.46t+4
- 1.628 7 1.83t+8 1.038 7 SW125 2.85t*7 2.19E*5 2.648 4 - 1.59t+7 6.80t*7 5.ME*6 Te-125e 5.69t*8 1.54E+8 1.60t*8 = = S.49t+8 7.69E*7 fe-127e 1.778+9 4.78t*8 4.24E+8 5.068+9 - 1.44t+ 9 2.115+4 fe-127 - - - 1.21E-9 - 1.Mt 8 =
Te-129e 1.81E*9 5.06t+8 5.821 8 5.308+9 - 2.308 9 2.00t+8 f ,-129 . . . . . . . Te-131. 7.80t+2 2.42t+2 4.98t*2 2.MEe3 - 9.021*3 2.582*2 te-131 . . . . . . . Te-132 2.09t*6 9.27E*$ l.35t*6 8.60E4 . 9.338 4 1.128+6 I 130 3.398 4 6.858 4 7.ME-4 1.025 5 - 2.308-6 3.538 4 1 131 1. HE*7 1.67t*7 S.528*9 2.74E+7 - 1.498 4 9.49t*6 2 332 . . . 2 133 6. M E-1 8.268-1 1.53t*2 1. ME*0 - 3.33t-1 3.128 t 2 114 . . . . . . . 2-135 - = = - = =
= .
Co-1M 9.228+8 1.51t+9 - 4.698+8 1.6st+4 8.15E+6 3.198 8 Co 1M 1.99t*7 4.378 7 - 2.33E+7 3.47t+6 1.54E+4 2.83t*7 Co-137 f.33t*9 1.288*9
- 4.16t+t 1.50t+4 7.998 4 1.88t+8 Co-138 - = * * - = =
3e.139 . . . . . . . Be-140 4.39t*7 3.8St+4 = 1.258 4 3.29E*4 2.228 7 2.M84 Be-141 = = = = = * *
* = =
So M2 - = = - ga.Mo $ 613-2 1.895-2 - - - A.27&*2 6.38E-3 g,.M3 . . . - . . . Co.141 2.22t+4 1.118 4 - 4.64t*3 - 1.38t*7 1.Mt+3 Co-143 3.305-2 1.79t*1 - 7.518 3 - 2.62t*2 2.598-3 Co-144 2.32t+6 7.268+5 - 4.03t*5 - 1.89t*8 1.341 5 Pr=143 3.398+4 1.028 4
- 5. Sit *3 - 3.ht*7 1.ME* 3 pr.144 34-147 1.17E*4 9.688 3
- 5.305 3 - 1.$0E*7 7.ME*2 s 187 3.ME-2 1.995 2 - - - 2.798+0 8.928-3 5p-239 4.308 1 3.025 2 - 8.738-2 - 2.23t.3 2.428 2
So* sesamtles pe4Mer Sm.e Factus - 48us.t . . ODCM-7.0 teree/rr po, acuan for 8-3 ee8 C-te Revision 6 W s eree/r, por acutees ter c46ers Peps 7.0-29 Seclide Sees Liver thrreia. Eldeer Lees $3-11! T.8may 5-3 *- 2.36t*3 2.268*3 2.368*3 2.Mb3 2.34t*3 2.268,3 l C-14 8.978,5 1.79D 5 1.79E*5 1.79E*5 1.79t.5 1.79b 5 1.792 5 i So-to 2.76t.5 2.76D5 2.76t+5 2.768 5 2.76t*5 2.761 5 2.76t*5 P 32 1.40t*9 8.73b7 - - - 1. 58 b t 5.42b7 Cr 51 - - 2.79b4 1.03E+4 6.19be 1.17D7 4.ME+4 ha-54 -- 3.11t*8 -- 9.27t*7 - 9.54E+8 5.94t*7 ha-M - 1.6tE*1 - 2.04t*1 - 5.13b2 2.858*0 Fe-55 2.99t*8 1.4 5t*8 - - 8 MB+7 8.298 7 3.378*7 Fe-59 1.27t*8 2.99b8 - - 8.35t*7 9.MS*8 1.148 8 Co-57 - 1.171*7 - - - 2.97t*4 1.958 7 ee-58 - 3.09t*7 - - - 6. M8+8 6.9tb7 Co-40 .
- 1.67D8 = - - 3.let+9 3.69b8 41-43 1.M E*10 1.2tt+8 - - - 1.588*8 3.49b8 81-45 6.15t*1 7.998+0 * - - 2.83b2 3.654+0 "
Co-M - 9.27t*3 - 2.34t*4 - 7.90E+5 4.35p3 Re-65 3.t?t+8 1.01b9 - 6.75t*8- - 6. MS*8 4.Mbs l So-69 8.75t-6 1.671-5 - 1.098-5 - 2.518-6 1.168-6 ! St-82 - = = - - 1.73t*6 1.588*6 I tr-83 - - - - - 4.63be 3.21b c ) Sg-44 = . - - - - - St-85 - = = - - - . . SbH - 2.1H+8 - - - 4.325*7 1.02b8 SpSS . - - - - - - Sp09 - - - - = = = ar-89 9.Mt*9 - - -~ - 1.60t*9 2.Mb8 Sr-90 4.05t*11 = = = = 1.75t*10 1.44t*11 i ( Sr-91 3.20tel - - - - 1.52t+6 1.29t*4 I i St-92 4.273+2 - - - - 4.468*3 f.858*1 1 l T-90 1.33t*4 - = = = 1.41b8 3.MS*2 l b91s 5.838-9 , - - = = 1.718-8 - } T-91 5.13t*4 - - - - 2.82t+9 9.37b5 ! F92 9.018-1 - - - - 1.54t*4 2.63b2 i ht) 1.74t*2 - - '- - 5.528*6 4.80tes ! tr-95 1.19t*6 3.81t*5 - 5.97t*5 - 1.2tt*9 2.58b5 8t-97 3.33b2 6.73tet - 1.02t*2 - 2.08t*7 3.988+t 8>95 1.421,5 7.91t+4 - 7.81E*4 ' - 4.80t*8 4.25E+4 8>97 2.908-6 7.348-7 - 4. MS-? - 2.7tb3 2.688-7 he-99 - 6.25t*6 - 1.41t*7 - 1.458 7 1.198*6 fc-99m 3.06be 8.668+0 - 1.328*2 4.24p o 5.128*3 1.10E*2 fr-101 . = = = = * - Be-103 4.80E+6 - - 1.83t*7 - 5.61E*8 2.07t*6 Su-105 5.39b t - - 6.ME*2 - 3.Mt*4 2.13t*1 Se=106 1.93t*8 - - 3.72t*8 - 1.25ble 2.44b7 4>103e = = - = = = = ' 8>106 - - - . = = = I es 110m 1.ME*7 9.76t*6 - 1.92b7 - 3.Mb9 5.80E*6 8>124 1.04t*8 1. ME* 6 2.52t*5 - 8.08b7 2.95bt 4.118*7 t 8>125 1.36t*4 1.528*6 1.39tel - 1.05t*8 1. 50b9 3.25b7 - i fe-125e 9. M E*7 3.50t*7 2.90t*7 3.938*8 - 3.46t+8 1.29E*7 fe-127e 3.49t+8 1.25b8 8.928*7 1.428*9 - 1.17b9 4.N8*7 l Te-127 5.76t*3 2.07E*3 4.27E*3 2.35t*4 = 4.54b5 1.258*3 fe-129s 2.551 8 9.50E*7 8.75t*7 f.86t*9 - 1.28b9 4.89E*7 Ye 129. 6.65b4 2.50 be- 5.108-4 2.792-3 - 5.028 4 1.62E-4 fe-131e 9.125*5 4.46t*5 7.86t*5 4.52 b6 - Te-131 = = = - - 4.438*7
- 3.728.*$
Te-132 4.29t*6 2.77E*6 3.06t+4 2.67t*7 - 1.31t*8 2.Se' 6 b1M 3.Mtel 1.171*6 9.90b7 1.82b6
- 1.01E*6 4 'd .
1 131 0.09E*7 1.168*8 3.79 tete 1.98be - 3.05t*7 4.u t*? ht32 5.745*1 1.545 2 5.38t*3 2.458 2 - 2.89E*1 5.388*t 2-133 2.123*6 3.698,6 5.428*8 6.44b6 - 3.31b6 1.125*4 2-134 1.868-4 3.888-4 5.00b3 4.598 4 - 2.51b7 1.838-4 bill 4.888*4 f.etb5 - 7.04b6 1.?tt*5 - 1.21E*5 3.ME4 < Co-134 4. ME*9 1.11 b 10 - 3.59t*9 1.19t*9 1.948*8 9.87E*9 l Co-136 4.28Ee? 1.Mba - 9.24b7 1.2?E*7 1.89E*7 .1.19b 8 Co-137 6.Mb9 8.70E*9 - 2.95t*9 9.81E+8 1.Mt+8 5.70E*9 I Co-138 - - = = = - . Be-139 2.958-2 2. *8b5 - 1. ME-5 1.19b5 5.238-2 8.648-4 Be-148 1.298+8 1. 62> 5 - 5.495+4 9.258*4 2.45b4 4.438+6 8 -441 . - - - - - - So-342 - - = = - . - te-148 1.978*3 9.928*2 - - - 7.385*7 2.62b2 Se-142 1.48be 6.358-5 - - - 4.648-1 1.588-5 Co-141 1.968*$ 1.33t*5 - 6.17t*4 - 5.883*8 1.ptp4 Co-143 1.088*3 7.42t*5 = 3.368*2 - 2.77t*7 8.218*1 Co-144 3.29b7 1.38t+7 = 0.16b6 - 1.11E*10 1.77E4 Pr-143 4.34t*4 2. ME*4 - 1.47t+4 - 2.78t+8 3.16b 3 Pr-144 - - - - - - - M-147 3.34 pe S. Mt+4 - 2.25b4 - 1.85be 2.31t*3 W-187 3.82b4 3.19E*4 - - - 1.05t*7. 1.12t*4 St-239 1.42b 3 1.40E*2 - 4.37b2
- 2.87E*7 7.72t*1
I ace, te8mune enneer so.e rtentre - 188mtsa . ODCM-7.0 ' terenver per acuen 2.,8 3 see C u - R: vision 6 m a armarre per Cueec) Str onore . Pags 7.0 Nuclide sees Liver Thrt:18 sideer Esse 8bLLI ?. Seer B-3 = C- H 2.598 3 2.89t*3 2.59t*3 2.59t*3 3.59E*3 3.598 3 Es-34 1.458*6 2.91bl 3.91bl 2.91bl 2.9tbl 3.91t*5 2.9ttel ) 2.45 Eel 2.458 5 3.45b5 2.41E*l 2.455*5 2.45bl 3.468* $ P 12 1.6tI*9 9.ME*7 = * = 1.35b8 4.238*7 i Cr-$1 - - 3.44t*4 1.ME*4 8.85E+4 1.04 b 7 6.301 4 No-54 - 4.525*8 1.31t+8 no-M
- 9.378e8 8.97t*7
. 1.45t*1 t.88 1 - 9.54t*2 2.58t*0 Fe-55 3.25b8 2.3tb8 - =
- 1.46t*8 9.98t*7 5. ME* 7 Fe-59 1. Stb 8 4.22t*8 =~ =
1.33t*8 9.988*8 1.63t*4 co-57 - 1.7 m f - - - 3.ht*8 3.80E*7 Co-58 - 4.38b7 - -- - 6.84b8 1.01t*4
. Code - 2.498+4 - = = - 3.34t*9 S.488+8 5143 f.41t*10 1.13t+9 - = = 1.StE*8 5.45E+8 3145 5.7Me t 7.328*0 -- - - 3.97t*2 3.338 4 Code . = 8.40t*3 - 2.128+4 -
6.$ltel 3.9SE*3 j 8e-45 ' 4.34b8 1.47t+9 - 9.41E*4 Se49 6.238+4 6.46t*4 . 8.198-6 1.568-5 - 1.828-5 - 3.888-5 1.098-6 ar-82 . .. - . - - 1.3M*6
, Dr-83 -
= = - - - 3.01t*0 St - - - = = = =
St-85 - - - . . - - Rb-86 - 2.738*8 - . ab-88 - = 4.058*7 1.388+8
= . . - -
36-8, . - - - . . - 8t-49 1.$1E*10 = = = = 1.80E*9 4.338*8 8t-90 7.51t+11 - - - - 2.11t*10 1.85tett St-91 2.998 5 - - = =' l . ME*6 1.198 4 er-92 3.97t*2 . = = - 1.015+4 1.698+t 1-90 1.248 4 - - - - ' = 1.02t+8 3.ht*2 '
,j T-91e S.43b9, - * - - 3.Mt-7
- e b91 7.87E*6 - - = = 3.2 H*9 2.11t*5 b93 8.478-1 = = = =
2.328+4 2.458-2 T-93 1.638 2 - = = = 4.98t+4; 4.47t*0
.1r-95 1.74E+6 5.49t*5 -
4.078*5 - 1.27bt 3.748*$ l Er-97 3.09b2 6.118+1 - 9.368*1 = 1.65t*7 3.41t*1 l ub-95 9.92b$ 1.86t*$ 1.03t+l ab-97 4.S$be $.Mbe l 2.698-4 6.678-7
- 7.808-7 -
1.598-2 2.44b7 l to-99 - 5.743*6 - ' t.3tE*7 Te-99e 1.03t*7 1.098 6 2.708 4 7.548 4 - 1.128*2 4.198 4 4.95b 3 9.77D I Te-101 - - . - - *
- Su-103 6.87E*6 - -
3.42b7 Re-105 5.00t*1 = = S.74t+8 2.94t+4 6.31E*2 - - 4.M a*4 1.94t*1 Re-106 3.09b8 . - 3.97E*8 ab-103e - - = = 1.48t*10 3.90s 7
= = -
Ah-106 * = = = = = = AS-ties 1.528*7 t.44t*7 . 2.74t*7
$> t 24 4.84t*9 8.74E4 1.55t*8 3.858*6 3.518*5 -
1.35D8 3.ltb9 6.838*7 Sk125 3.14t*8 2.345 4 2.848*l - Te-125e 1.8848 1. Mbt $.80t*7 1.488+8 S.34t*7 4.148*7 * - 4.178+8 1.98t*7 Te-127e 5.51b8 1. ME* 8 1.3 tb8 2.24t*9 - 1.37t*9 4.Mbf Te-127 S.4M*3 l.928*3 3.748*3 2.388+4 Te-129e 4.19 Eel 1.17tel Te-129 3.67t*8 1.ME+8 1.18t+8 1.$4b9 - 1.38t*9 l.818*7 Te-13te 6.228-4 3.328-4 4.458-4 2.61b3 - 3.488-3 1.5 t b4 8.448*5 4.058*5 6.09E* 5 4.228*6 - 3.258*7 3.ME* 5 Te-131 = = = = = = = Te-133 S.98b6 3.47b6 3.80B+6 2.37t*7 21M
. 7.838*7 3.32t+6
- 3. ht* $ 1.82t+6 8.358*7 1.98t*6 =
7.87E*5 4.09tel b131 7.70b7 1.888+8 3. utete 1.058+4 2-132 5.188*1 2.138*7 S.79t*7 f.36t** 4.8?b3 3.14t*2 - S.91t*1 4.87E*1 2-133 1.97be 3.M84 4.668+4 $.868,6 - 2.$3b6 1.82b6 2-1M 9.598-5 2.348-4 4.24b3 4.013-4 2 135
=
3.t.z-6 9.118-l 3.688 4 9.488 4 6.10be 1.50 Eel . 1.058*l 3.58t+4 Co-th 7.9pt*9 1.67b10 - Co-t M 4.29b 7 1.49b8 = 5.388*9 f.estet 3.88b8 7.748*9 Co-137 1.01b 10 1.35t*10 - 9.19t*7 1.458 7 f.368*7 1.1M+4 4.59E*9 1.788+9 9.92b8 4.69t*9 Co-138 - - = = = = - 8e-139 2.778-2 1.988-8 = So-Me 1.30p4 1.698*5 t.84b5 9.MB-S 2.47bt 8.888 4
- 5.758 4 1. M8+5 2.138*8 8.918 4 8e=141 - = * = = = =
go-u2 - - - . - . . La-M0 1.88b3 8.84b2 - - Le-143 1.388-4 5.69b5 - = 5.98t*7 3.368*2 Co-let 2.82b 5 1.888+5 -
. 1.738 4 1.42b5 8.86t+4 -
5.Mb8 3.1't+4 Co-M3 9.37E*2 6.82B+$ = 3.868*2 Co-M4 5.378+7 2.188*7 -
- 2.05t* 7 7.62t*1 1.388*7 -
1.338*10 2.83t+4 Pr-143 7.128 4 2.844 4 - 1.65E+4 Pr- M4 - * - - 2.M8+4 3.$54*3
- - =
abt47 3.438*4 3. M8+4 - 3.32b4 - W-187 3.85be 2.98be - 1.43 & S 2.ME* 3 ar-239 1.38b3 1.30b2 - 7.84b6 1.928 4 4.09t*2 - 2.10D 7 7.248e1 v
_7
; tae teenaue P4wer tus recur - cant - ODCM-7 0 (aremtre per acus ) for e-3 est C-14 s Revision 6
' (18 a eree/rr per pCuen) ser unere Pa g 2_7.0-31 Seclide tone Lieet - Thrtela Stener imme 81-LL1 f.8eay a-3 -
4.01E*3 4.91t+3 4.91E*3 4.81E*3 4.918e3 4.01E*3 C 14 3.50t+4 7.01t*5 7.018+5 7.81t*5 7.018*5 7.01t*5 7.018+5 Be-24 3.83tel 3.83t+5 3.838+5 3.838+5 3.438*5 3.8H+5 3.83t*5 b32 3.378+9 1. 58 b8 - - - 9.302 7 1.30be Ct-11 . - 6.548*4 1.798 4 1.19t+5 6.25b6 1.188 5 Ne 54 - 6.61t+8 - 1.85t+8 - 1.55t+4 1.768+8 :
' l No-M . 1.908 1 - 2.29te t - 2.75t*3 4.28be -l re-55 8.00E+4 4.24t+8 - - 2.40s 8 7.Ht+7 1.318+8 Fe 59 4,91t+4 6.498+8
-I
- - 1.888*8 6.768+8 3.23b4 Co-57 . 2.998+7 = .. . 2.45E+8 6.Nt*7 Co-58 - 6.478+7 - -
- 3.778+8 1.988+8 '
Co-40 - 3.788+8 - . - 2.18t+9 1.128,9 N143 ~ 3.958*10 2.11E*9 - = = 1.43t+8 1.ME*9 5145 1.058*2 9.89 tee - = = 1.21E*3 5.77be co-H . 1.115+4 - 3.utee - 5.20b5 6.698*3 2e-45 8.12t+8 2.16b9 - 1.36t+9 = 3.00t+8 1.35E+9 to-49 1.518-5 3.18 b 5 - 1.328-5 - 1.385-3 2.028-6 tr-82 . . . . . .- 2.04t*6 ' tr-43 - - - - - - 5.55be Sr.84 - - - . . . . tr-85 . . . . . . . 56-86 - 4.52t*8 - - - 3.915+7 2.78b8 86-88 . . . . . . . 86-49 . 3 . . . . . St-49 3.598*10 - * = -- 1.39E*9 1.035 9 St-90 .1.24t+12 - = = = 1.678+10 3.15bt1 St-91 5. 50b 5 - = = = 1.218 4 2.88be St-92 7.288*2 - - - - 1.388+4 2.92h1 b90 2.30$+4 - - - - 6.568*7 6.178+2 F91e 9.948-9 - = =
- 1.958-5 =
F91 1.87b7 . . = = 2.493*9 5.01t*5 F92 1.568*0 - - - = 4.51t+4 4.468-2 b93 3.01t+2 '= - - - 4.48t+4 4.252 0 tr-95 3.90t+6 8.54E+5 - 1.238*6 = 8.95t+8 7.Mtel 1t-97 5.H8*2 8.158*1 - 1.17t** = 1.2M* 7 4.81E*1 56-95 4.10E+5 1.598+5 - 1.50t*5 - 2.95t+8 1.14b 5 N>t? 4.988-6 8.858-7 - 9.822-7 . 2.73bt 4.138-7 Ito-99 - 7.8M*6 - 1.678+7
- 6.488+6 1.94t+6 Te-99e 4.65be 9.1200 -
1.33b3 4.6 M +0 -5.19b 3- 1.51b 2 i j fe-101 = = = = . . = ' Su-103 1.55t*7 - - 3.09Ee7 - 3.998+8 5. Mt+6 l So-105 9.17b t - -. 8.06b2 - - 5.98 b e 3.33t*1 Su-106 7.45t*8 - - 1.01t+9 -- 1.16t*10 " . 30b 7 Sh-103e
= = = - - -
- Sh-106 - - - . - .
A8 118e 3.22t*7 2.17b7 - 4.05b7 - 4.588*9 1.74t*7 l D 124 3.52t+8 4.578+6 7.788*5 - 1. Mt+8 2.20bt 1.2M+8 SW125 4. 99E*4 3.858*6 4.6JE*5 - 2.788+4 1.198+9 1.elb8 Te-125e 3.51b8 9.50te? 9.N t*7 - - 3.388+4 4.67b7 fe-137e 1.32bt 3.56b8 3.168+8 3.77t+9 - 1.87bt 1.57t+8 fe-127 1.00t+4 2.70t*3 6.93te3 2.85t*4 - 3.918*5 2.15b3 fe-129s 8. 54b8 2.398 8 2.758*8 2.51t+9 . 1.84t+9 1.3M*8 fe-129 t.15b3 3.228 4 8.228-4 3.37b3 = 1.178-2 2.74b4 Te-131s 1.54 be 5. H E*5 1.10$+4 5.1M+6 = 2. 4t* 7 5.ut*5 - 7,-133 . . . . . . . Te-132 6.98b6 3.098+6 4.50t+6 3.87E*7 = 3.11t+7 3.?M*6 btM 6.218e5 1.268+6 1. Mt+8 1.882 6 - 5.87t*5 6.47t*5 b131 1.438+8 1.44t+8 4.7 Melo 2.36t+8 - 1.28t*7 8.188*7 2-132 9.30t*1 1.69t*2 7.Mt* 3 2.598 2 ~ 1.99t+2 7.77bt b133 3.598+6 4.448*6 8.25E+4 7.40b6 - 1.79t+6 1.688 4 2 1M t.708-4 3.1M-4 7.28b 3 4. N E-4
- 2.188-4 1.48 4 b135 6.548+4 1.18t*5 1.Mb7 1.81t+5 ,- 8.98be 5.5754 Co-1M 1.80t*18 2.63t+10
- 8.148*9 2.92E+9 1.42t+8 S.548*9 Co-1M 8.868*7 2.22b8 = 1.188+8 1.76t+7 7.798+6 1.43b8 Co-137 2.39b le 2.298*10 -
7.468+9 2.ME*9 1.438+8 3. Mbt Co-138 . . . . . . . Se-t H 5.118-2 2.73b5 = 2.385-5 1.61b5 2.95b e 1.488-3 Se-140 2.778+8 2.438+5 - 7.988+4 1.45E+5 1.488+8 1.63847 Se-141 . . = . . . . So-M2 . . . . . . .
. Le-140 3.23b3 1.13E+3 - = . 3.15b? 3.81t+2 1e-143 3.328-4 7.4eb5 - = = 1.478+1 2.328-5 Co-141 1.23b 5 6.148 4 - 2.698 4 - 7.H3+7 9.138+3 Co-143 1.7M*3 9.36t*5 - 3.93b2 - 1.378+1 1.36t*2 Co- M4 ' 1.27b8 3.98b7 - 2.21t*7 . 1.e4E+10 4.78be Pr-143 1.48b 5 4.44t+4 - 2.4tt+4 - 1.Seb8 7.37b3 Pr-164 - = = - . . -
58 147 7. 4E+4 5.80t+4 - 3.18t+4 . 9.18t*7 4.49b3 W-107 6.478 4 3.838+4 - . . 5.388+4 1.728+4 5p 239 2.55t+3 1.83b2 a 5.30E+2 - 1.368+7 1.29b2 e-- r,- W w*w,erm-
I Tebte 7.0-2 (eastiou*d) ODCM-7.0 i Ras. Stened Pleae Patheer Dese Facters R: vision 6 i Pag 3 7.0-32 (et a eram/yr per WC1/***) meel16e Any Ortes ! s.3 - C-14 = me-24 1.2tt+7 P-32 - Cr-51 4.64t+6 Me-54 1.34t+9 he-56 9.05t+5 Fe-55 - Pe-59 2.75t+8 Co-54 3.83E+8 Co-60 2.163+t0 N1-63 . 51-65 2.97t+5 Ce 64 6.09t+5 . to-65 7.45t*4 3e-69 . St-83 4.89t+3 Br-64 2.03t+5 Br-45 - Rb-46 8.Det+6
)
R >- 64 2.29t+4 RD-89 1.2tE*5 St-89 2.16t+4 St-90 - Sr-91 2.19t+6 3r-92 7.773+5 T-90 4.44t+3 T 91e 1.01t+5 T 91 1.08t+6 T-92 1.60te$ T-93 1.85t+5 l Er 95 2.44t+4 1 Er-97 2. 94 t+ 6 N>-95 1.34t+8 No-99 4.05E+6 Te-99m 1.83t+5 fr-101 2.04E+4 Re-103 1.09E*8 Re-105 6.36t+5 ke-104 4.2tt+8 Rh-101e . R&-104 - As-110e 3.47t+9 fe-125e 1.55t+6 Te-127s 9.17t+4 Te-127 3.00E+3 Te-129m 2.00t+7 Te-129 2.60t+4 Te-131s 8.03t*6 Te-131 2.91t+4 Te-132 4.22t+6 1-130 5.53t*6 1 131 1.72t+7 2-132 1.34t*6 2-133 2.47t+6 2 154 , 4.49t+5 1 135 2.56t*6 Co-15# 6.75t+9 Co-13 a 1.69t+8 Co-137 1.04t+10 Co-154 3.59t+5 Se-139 1.06t+5 Be-140 2.05t+7 Se-let 4.18t+4 Se-142 4.49E*4 La-160 1.91t+7 La-142 7.36t+5 Ce-141 1.36t+7 Ce-143 2.32E+6 se-144 6.95t+7 Pr-143 - Pr-144 1.83E+3 5d-147 8.60E+6 W-147 2.56t+6 by-239 1.71t+6
qf qa e s N t M . y . e . K M n e e 3 a s 03 n y n0
- 0. o
- J e
m t ea f ws
- s. _
7i7 N a sne m Cio s n ot Cvg dis Dec et y _ Ofl P rcs eu edn neo i ri g t nt s - eni et eut uM rl n af e f v
) e _
S t _ Ton _ N
, - GNa .
O S l . I ! ( p _ T ' m) n _ A b L ~
-_
- eSi tT
=M" I -
sed T V N E
" yVe S(l l
sa.
't _
t _ D 40 nmt N eesd _ A I . - {A u0 mt ne t sil G N I R l S r
.. d. a sI ay essa r
Tt es rt l OW T nt n A sel i 1 T R G ami g_
- I G 3 Gtfn 0 N A
_Wnu a o O I _ yeri 7 M D u brot D c M E T S dTf a E n r R N U E M w at nt G U ET t sol I F L F S ' n S uii atf F Y r_ eha E S l ll m hnut tEl u E ao V I T _l
- ee
.e s r me nnvh ooet i i sv dtI w C
A O l -smn a e ea t iaI I . fti _ D l tda A } j I.i. t nni R n o s need
. eVpn S
U 2
- .m d
idAp pe O := e p E :n= sr0A 5 A G M re5 edR0 tiF5 l sCR in0F y l
- M lE f o1 C l
atA oo$o c 0 R1 A cnFt 1
.v t
" Y. r U ae s 1
t hrem cahr r Wdd nnnn t o f nA9 r e aaio Asd Pee 2 Ert c i.l I[ l l v: n= eaer H uit tdm t f n e w o t l :
~ :.. Y.v hero TfcF P
S eM i T -[l . n E T O N
Null:cr Producti:n - F rmi 2 CDCM-8.0 } Cffsit3 Dosa C lcut:tiin M:nual Rivizian 5 j P:gs 8.0-1 ) SPECIAL DOSE ANALYSIS i
)
j s.0 SPECIAL DOSE ANALYSES i 8.1 Doses Due to Activities inside the SITE BOUNDARY in accordance with ODCM 5.g.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 affluents to MEMBERS OF THE j PUBLIC due to their activities inside the SITE BOUNDARY. l Two locations within the Formi 2 SITE BOUNDARY are accessible to MEMBERS OF THE j PUBLIC for activities unrelated to Detroit Edison operational and support activities. 4 One is the over-water portion of the SITE BOUNDARY due east of the plant. Ice l fishermen sometimes fish here during the winter. The other is the Fermi 2 i Visitor's Center, outside the protected area (but inside the Owner Controlled Area), j approximately 470 meters SSW of the Reactor Building. The Visitor's Center is open j to the public and is routinely visited by MEMBERS OF THE PUBLIC, including school i tour groups on a frequency of once per year. Also, due to a change in the definition 4 j of MEMBER OF THE PUBUC in the revised 10 CFR Part 20, some individuals working O $/ j within the SITE BOUNDARY may be considered MEMBERS OF THE PUBLIC. Conservative assumptions of locations, exposure times, and exposure pathways for
] assessing doses from gaseous and liquid effluents due to activities inside the j ' SITE BOUNDARY are presented in Table 8.0-1. The calculational methods presented j 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. Alternatively, I
the affluent concentration values of Appendix B, Table 2, of the revised 10 CFR Part 6%9 { 20 may be used to assess dose since these concentrations, if continuously inhaled or I i ingested, produce a total effective dose equivalent of 50 mrom per year. l 1 The potential dose from the fish pathway to a MEMBER OF THE PUBUC engaged in i ice fishing within the SITE BOUNDARY is accounted for by the modeling presented in i~ ODCM Section 6.5. Therefore, no additional special dose analyses are required for this exposure pathway for reponting in the Annual Radioactive Effluent Release Report. l l 8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 The Annual Radioactive Effluent Release Report shall also include an assessment of l
! the radiation dose to the likely most exposed MEMBER OF THE PUBUC for reactor lYN '
l: releases and other nearby uranium fuel cycle sources (including dose contributions-from effluents and direct radiation from onsite sources). For the likely most exposed l
! MEMBER OF THE PUBUC in the vicinity of the Fermi 2 site, the sources of exposure I
! need consider only the radioactive effluents and direct exposure contribution from l Formi 2. I ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: LCR g3-117-ODM DSN Rev 5 Date f j DTC TMPLAN File 1715.02 Recipient i i l i_, . - - . -
j ODCM-8.0 l-Revision 5 Page 8.0-2 i , No other fuel cycle facilities contribute significantly to the cumulative dose to a I , MEMBER OF THE PUBLIC in the immediate vicinity of the site. Davis-Besse is the ; j closest fuel cycle. facility located about 20 miles to the SSE. Due to environmental i
- dispersion, any routine releases from Davis-Besse would contribute insignificantly to
- the potential doses in the vicinity of Fermi 2.
As appropriate for demonstrating / evaluating compliance with the limits of ODCM ! . 3.11.4 (40 CFR 190), the results of the environmental monitoring program.may be { l used to provide data on actual measured levels of radioactive material in the actual pathways of exposure. ] 8.2.1 Effluent Dose Calculations 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 ODCM g.0) may be used. Liquid pathway ) doses may be calculated using Equation (6-10). Doses due to releases of radiolodines, tritium and particulates may be calculated based on Equation (7-14). The following equations may be used for calculating the doses to MEMBERS OF THE PUBLIC from releases of noble gases. Equation (8-2) is not used for evaluating compliance.w!th.40 CFR Part 190, since this regulation does not address skin dose. If noble gases are being released from more than one 0N< point, these equations must be used to evaluate each release point separately, and then the doses must be added to obtain the total noble gas dose. Dtb = 3.17 E - 08
- X/O * [(Kg
- Og)
(8-1) and Ds = 3.17 E - 08
- X/O * [([L; + 1.1 M li
- Og)
(8-2) where: Dtb = total body dose due to gamma emissions for noble gas radionuclides (mrom) Ds = skin dose due to gamma and beta emissions for noble gas radionuclides (mrad) X/O = atmospheric dispersion to the offsite location (sec/m3 ) Og = cumulative release of noble gas radionuclide i over the period of interest (uCl)--may be determined according 0 to Equation (7-8) Cg = concentration of radionuclide i as determined by gamma spectral analysis of media (uCl/ml) b
, ODCM-8.0 j R;vislan 5 g Pago 8.0-3 4 f 1.67E + 01 = (1E + 03 ml/ liter) * (1 min /60 sec) Ki
= total noblebody dose factor gas radionuclide due to gamma I (mrom/yr per uCl/memissig)ns (from from
. Table 7.0-2) i j Li = skin dose factor due to beta emisglons from noble gas j radionuclide 1 (mrom/yr per uCl/m ) (from Table 7.0-2)
- Mi = gamma air dose fagtor for noble gas radionuclide I i (mrad /yr per uCi/m ) (from Table 7.0-2)'
1.1 = mrom skin dose per mrad gamma air dose (mrom/ mrad) 3.17 E - 08 = 1/3.15 E + 07 yr/sec j Average annual meterological dispersion parameters or meterological conditions concurrent with the release period under evaluation may be used j (e.g., quarterly averages or year-specific annual averages). 8.2.2 Direct Exposure Dose Determination 3 From evaluations performed in the Fermi 2 Environmental Report, Section 5.3.4, the direct exposure to the highest offsite location from the
! Turbine Building N-16 skyshine dose has been calculated to be j approximately 3 mrom/ year. This value may be used as a baseline for i actual direct exposure during plant operations. Direct exposure to offsite or
- onsite individuals may be evaluated based on the results of environmental i
i measurements (e.g. area TLD and survey meter data) or by the use of a radiation transport and shielding calculational method. Only during atypical l "jd conditions will there exist any potential for algnificant onsite sources at
- Fermi 2 that would yield potentially significant offsite doses to a MEMBER I 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 i of dose for assessing 40 CFR igg compliance. The calculational techniques j will be identified, reviewed, and approved at that time, and will be included Oi 1 in any report on doses due to such atypical conditions. i 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data 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 be undetectable. The calculational methods presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals.
. ODCM-8.0 ;
R:visisn 5 P:g2 8.0-4 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 material in 5,rincipal pathways of exposure, a quantitative assessment of ' potential exposures can be performed. With the monitoring program not identifying any measurable levels, the data provides a qualitative , assessment - a confirmatory demonstration of the negligible impact. a Dose modeling can be simplified into three basic parameters that can be applied in using environmental monitoring data for dose assessment: D a C
- U
- DF !
(8-3) where: D = dose or doss 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 hr/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 l
The applicability of each of these basic modeling parameters to the use of environmental monitoring data for dose assessment is addressed below: e 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 material in the exposure pathways. This eliminates one main uncertainty and the modeling has been removed - the release from the plant and the transport to the environmental exposure medium. Environmental samples are collected on a routine frequency per the ODCM. To determine the annual average concentration in the environmental medium for use in assessing cumulative dose for the year, an average concentration should be determined based on the sampling frequency and measured levels: k = [(Cg
- t)/365 (8-4) where:
Cg = average concentration in the sampling medium for the year Cj = concentration of each radionuclide i measured in the individual sampling medium
l ' ODCM-8.0 R3 vision 5 l - Page 8.0-5 t = period of time that the measured concentration is considered 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 C i(Cg = 0). Exposure - U 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 not necessarily levels to which any individual is exposed. For example, sediment samples are collected in the area of the liquid discharge: typically, no individuals .
. are directly exposed. To apply the measured levels of radioactivity in -
samples 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 alternative is to conservatively assume a hypothetical individual at the sampling 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 collected, such as near field dilution area, are not applicable to this pathway. Dose Factore - DF The dose factors are used to convert the intake of the radioactive materian to en individual dose commitment. ' Values of the dose factors are presented in NRC Regulatory Guide 1.109. The use of the RO 1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 8.0-2.
_ _~ _. ODCM-8.0 Revislan 5 Pago 8.0-6 Assessment of Direct Exposure Doses from Noble Gases B Thermoluminescent Dosimeters (TLD) are routinely used to assess the direct exposure component of radiation doses in the environment. . However, because routine releases of radioactive matenal (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 mrom per year. Therefore, for routine releases from nuclear power plants the use of TLD b 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 concentrations could be sufficient to cause significant increases in TLD readings; any observed variations'in TLD measurements
\\h\
outside the norm should be evaluated.
- NUREG/CR-0711, Evaluation of Methods for the Determination of X- and Gamma-Ray Exposure Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gall dePlanque, June 197g. USNRC.
END OF SECTION 8.0
ODCM-8.0 R;vislan 5 j . Page 8.0-7 TABLE 8.0-1 Assumptions for Assessing Doses Due to Activities inside SITE BOUNDARY ice Fishing Visitor's Center Site Personnel Distance / ' 470 meters / E 470 meters / SSW' various Direction: Estimated 240 hr/yr 4 hr/yr . . 2500 hr/yr Exposure (20 hr/ week over (4 hr/ visit,1 visit Time: 3 month period) per year) F Exposure direct exposure direct exposure direct exposure Pathways: from noble gases from noble gases from noble gases inhalation of inhalation of inhalation of tritium, lodines, tritium, lodines tritium, lodines particulates particulates particulates ingestion of O potable water direct exposure from skyshine Meteorological annual average annual average annual average Dispersion: (as determined (as determined (as determined for year being for year being for year being evaluated) evaluated) evaluated) 6.48E-6 sec/m3
- 2.54E-6 sec/m3
- various depending on location of personnel being evaluated
- Annual average X/Q values for 1991. These values are shown as examples of the range of values to be expected.
l ODCM-8.0 . R: vision 5 Pago 8.0-8 , TABLE 8.0-2 I Recommended Exposure Rates in Lieu of Site Specific Data
- j 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 Sedimont Toen 67 h/y E-6 i
i 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 1
Fruits, Vegetables Teen 630 kg/y E-12 and Grain ) Milk Infant - 3301/y E-14 l 2 1 Adapted from Regulatory Guide 1.IO9, Table E-5. This table is not a complete list of ggy 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 hours per year adjusted by a 0.7
- shielding factor as recommended in Regulatory Guide 1.109.
END i 4 i s 4 4 M 4 J
Nuciscr Pr:ductirn - F:rmi 2 ODCM-9.0 Off:lto D:co Criculatirn Manu:1 R:virian 5 P g3 9.0-1 ASSESSMENT OF LAND USE CENSUS DATA 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 pilk producing animals, all meat producing animals, all gardens larger than 500 ft 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. I ff the census identifies a location / pathway (s) yielding a higher potential dose to a l 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 cens location (s) that yleIds 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 kgi 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 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 fo!!owing 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
- 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).
ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: LCR 93-117-ODM DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient
- .- . _. . - . . ~ . .
- ODCM-g.0 R:vislan 5 Page g.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 motorological dispersion and deposition parameters (X/0, D/Q) for any location to be evaluated for dose significance. All locations 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 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 h descending order of relative dose significance, include the relative dose significance in the listing.
g.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.
- 2. 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.
.; w
ODCM-9.0 Revisisn 5 Pago 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/Qs, 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 SI'IE 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 efficials. 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
Nuciscr Pr:ducti:n - F:rmi 2 CDCM-10.0 i Offsita Daso C:lculatian M:nu:1 Revi2isn 5 j P ga 10.0-1 ! RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i i 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 j PUBLIC. This monitoring program implements Section IV.B.2 of Appendix 1 to 10 CFR Part 50 i and thereby supplements the radiological effluent control program by verifying that the j measurable concentrations of radioactive materials and levels of radiation are not higher j 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 l Environmental Monitoring, Revision 1, November 197g. i 10.1 Sampling Locations
- 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 l 4 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 j modified as required to reflect the findings of the annual land use census i 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 j documented in plant records and reflected in the next ODCM revision, the l j next Annual Effluent Release Report, and the next Annual Radiological j Environmental Operating Report. Also, if the circumstances of such l0V I j 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 j reevaluated.
10.2 Reporting Levels l ! ODCM 3.12.1, Action b, describes criteria for a Special Report to the NRC if levels of j plant-related radioactive material, when averaged over a calendar quarter, exceed the 4 prescribed levels of ODCM Table 3.12.1-2. The reporting levels are based on the I j design objective doses of 10 CFR 50, Appendix I (i.e., the annual limits 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 mrom, total body or 10 mrom, maximum i organ from liquid pathways; or 5 mrom, total body, or 15 mrom, maximum organ for j the gaseous effluent pathway. These potential doses are modeled on the maximum individual exposure or consumption rates of NRC Regulatory Guide 1.10g.
ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: LCR 93-117-ODM , DSN Rev 5 Date DTC TMPLAN File 1715.02 Recipient
-.-,n-- m - - ~ --
. ODCM-10.0 Revision 5 P:gs 10.0-2 The evaluation of potential doses should be based solely on rrdioactive 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 3.12.1-2.
10.3 interleboratory Comparison Program A major objective of this program is to assist laboratories involved in environmental radiation measurements to develop and mairstein both an intralaboratory and an interlaboratory quality control program. This is accomplished through an extensive laboratory intercomparison study (" cross-check") program involving environmental media (milk, water, air, food, soll, and gases) and a variety of radionuclides with activities at or near environmental levels. Simulated environmental samples, containing known amounts of one or more radionuclides, are prepared and routinely distributed to all laboratories upon request. These laboratories perform the required analyses and return their data to the Quality Assurance Branch of the Environmental Protection Agency (EPA). The EPA performs statistical analysis and comparison with known values and analytical values obtained' from other participating laboratories. A report and control chart are returned to each participant. The program thus enables each laboratory to document the precision and accuracy of its radiation data, identify Instrument and procedural problems, and compare its performance with that of other laboratories. The environmental laboratory is required to participate in a Commission-approved Interlaboratory Comparison Program and to submit GA Program Progress Summary Reports to Detroit Edison on a bimonthly or quarterly basis. These reports contain summary descriptions and performance data summaries on reference standards, blank, blind, spiked, and duplicate analyses, as well as the USEPA and other Laboratory intercommission Programs, as applicable. 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.g.1.7. Participation in an approved interleboratory Comparison Program onsures that an independent check on the precision and accuracy of the measurements of radioactive material in 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.8.2 of Appendix 1 to 10 CFR Part 50. END OF SECTION 10.0
l ODCM-10.0 l R:visinn 5 Page 10.0-3 TABLE 10.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FERMI 2 SAMPLE LOCATIONS AND ASSOCIATED MEDIA KEY 1- T TLD Locations (Pg.10.0-4 to 10.0-6) 2- S Sediments Locations (Pg.10.0-7) 3- F Fish Locations (Pg.10.0-7) 4- M Milk Locations (Pg.10.0-8) 5- DW Drinking Water Locations (Pg.10.0-9) 6- SW Surface Water Locations (Pg.10.0-9) 7- OW Ground Water Locations (Pg.10.0-9) 8- APl Air Particulate / lodine Locations (Pg.10.0-10) 9- FP Food Products Locations (Pg.10.0-11)
ODC'.*- 10 . 0 nov101sn 5 Page 10.0-4 TABLE 10.0-1 Radiological Environmental Isonttoring Program. Fermi 2 Sample Locations and Associated Nedle Direct Radiation Noteorological Station Sector / Azimuth Distance from leunber Direction Reactor (Appron) Description Bedia Frequency T1 NE/38 8 1.3 at Estral Beach Pole on Lakeshore. Direct Radiation Q 23 Poles S of Lakeview (Special Area) T2 NNE/228 1.2 mi East of termination of Branchoeu St on post Direct Radiation Q (Special Area) T3 N/90 1.1 mi Pole. NW Corner of Swan Boat Club Fence Direct Radiation Q (Special Area) T4 NNW/337' O.6 mi Site Boundary and Toll Rd. on Site Fence by Direct Radiation Q API #2 T5 MW/313 0 0.6 mi Site Soundary and Toll Rd. on Site Fence by Direct Radiation Q API #3 T6 WNW/293 8 0.6 mi Pole. NE Corner of Bridge over Toll Rd Direct Radiation Q T7 W/270 8 14.2 mt Pole. behind Doty Farm. 7512 N Custer Rd Direct Radiation Q (Control) 78 NW/3058 1.9 mi Pole on Post Rd near NE Corner of Diste Hwy Direct Radiation Q and Post Rd 79 NNW/334' 1.5 mi Pole. NW Corner of Trombley and Swan View Rd Direct Radiation Q T10 N/6 8 2.1 mi Pole. E Side of Masserant - 2 Poles S Direct Radiation Q gg of Chinavarre T11 NNE/23' 6.2 et Pole. NE Corner of M1111 men and Jefferson Direct Radiation Q T12 NNE/29' 6.3 mi Pointe Mou111ee Game Area - Field Office. Pole Direct Radiation Q near Tree. N Area of' Parking Lot T13 N/356' 4.1 mt Labo and Diate Hwy - Pole on SW Corner Direct Radiation Q with Light T14 NNW/337 8 4.4 mi Lobo and Brandon - Pole on SE Corner near RR Ot oct Radiation Q T15 NW/315' 3.9 mi Pole. behind Newport Post Office Direct Radiation Q
DDCM-10.0 Ocviolan 5 P 9e 10.0-5 TABLE 13.0-1 Radielegical Enytrennental Monitoring Program. Formt 2 Sample Locations and Aeoeciated Media Direct Radiation Meteorelegical Station Secter/Artmuth Distance from Museer Direction Reactor (Approm) Description Media Frequency T16 WNW/283 8 4.9 mi Pole. SE of War and Post Rds Direct Radiation Q T17 W/2710 4.9 mi Pole. NE Corner of Nadeau and Laprad near Direct Radiation Q Mobile Home Park T18 WSW/247 8 4.8 mi Pole. NE Corner of Montet and Hurd Direct Radiation Q T19 SW/236' 5.2 mi 1st Pole E of Formt Siren on Waterworks Rd. Direct Radiation Q NE corner of intersection - Storitng State Park Rd Entrance Detve/ Waterworks (in Sterling State Park) T20 WSW/2578 2.7 mi Pole. S Side of W1111ams Rd - 8 Poles W of Direct Radiatit Q Diate Hwy (Special Area) T21 WSW/239' 2.7 mi Pole. N Side of Pearl at Parkview - Woodland Direct Radiation Q Beach (Special Area) T22 S/172 0 1.2 mi Pole. N Side of Pointe Aux Peaux 2 Poles W of Direct Radiation Q Long - Site Boundary 723 $$W/195 8 1.1 mi Pole. S Side of Pointe Aus Peaux - 1 Pole W of Direct Radiation Q Huron next to Vent Pipe - Site Boundary T24 SW/225' 1.2 mi Fermt Gate along Pointe Aux Peaux Rd'- on' Direct Radiation Q fence wire W of Gate - Site Boundary T25 WSW/251' 1.5 mi Pole. Toll Rd - 13 Poles 5 of Fermi Dr Direct Radiation Q T26 WSW/259 8 1.1 mi Pole. Tott Rd. 6 Poles 5 of Formt Dr Direct Radiation Q T27 SW/225' 6.8 mi Pole. NE Corner of McM111an and East Front St Direct Radiation Q (Special Area) T28 SW/229 8 10.7 mi Pole. SE Corner of Nortar Creek and Direct Radiation -Q LaPlaisance (Control) T29 WSW/237 8 10.3 mi Pole. E Side of S Dixie. 1 Pole 5 of Albain Direct Radiation Q (Control) T30 WSW/247 8 7.8 mi Pole. St. Mary's Park Corner of Direct Radiation Q Elm and monroe St. 5 side of perking tot next to river (Special Area)
ODCW-10.0 Qev1oton 5 P ge 10.0-0 TABLE 10.0-1 Radiological Enytronmental IBonitoring Program. Fermi 2 Segle Locations and Associated IBodta Direct Radiation tBeteorelegical Station Sector /Artmuth Distance from Muaber Direction Reactor (Approm) Description IBedia Frequency T31 WSW/255' 9.6 mi ist Pole W of Entrance Drive Mtiton " Pat" Direct Radiation Q hanson Recreational Reserve - N Custer Rd (Control) T32 WNW/295' 10.3 mi Pole. Corner of Stony Creek and Finzel Rds Direct Radiation Q T33 NW/317' 9.2 mi Pole. W Side of Grafton Rd. 1 Pole N of Direct Radiation Q Ash /Grafton Intersection T34 NNW/3380 9.7 mi Pole. W Side of Port Creek. 1 Pole S of Will-Carleton Rd Direct Radiation Q }\/h [ T35 N/359' 6.9 mi Pole. S Stde of S Huron River Dr across from Direct Radiation Q Race St (Special Area) T36 N/3580 9.1 mi Pole. NE Corner of Gibraltar and Cahill Rds Direct Radiation Q T37 NME/21 0 9.8 mi Pole. S Corner of Adams and Gibraltar (across Direct Radiation Q from Humbug Marina) T38 WNW/2940 1.7 mi Residence - 6594 N. Dixie Hay. Direct Radiation Q T39 S/176' O.3 m1 SE Corner of Protected Area Fence (PAF) Otreet Radiation Q T40 S/1700 0.3 mi Midway along OBA - PAF Direct Radiation Q T41 SSE/1610 0.2 mi Midway between OBA and Shield Wall - PAF Direct Radiation Q T42 SSE/149 8 0.2 mi Midway along Shield Wall - PAF Direct Radiation Q T43 SE/131' O.1 mt Midway between Shield Wall and Aus Boilers - Direct Radiation Q PAF T44 ESE/109' 0.1 m1 Opposite OS$F Door - PAF Direct Radiation Q T45 E/86' O.1 mi NE Corner - PAF T46 ENE/67 0 0.2 mi NE Side Berge Slip - on Fence Direct Radiation Q
I ODCW-10.0' < Rsvision 5 Pe9e 10.0-7 TABt.E 10.0-1 Redlological Environamental Monitoring Program. Formt 2 Sample Locations and Aseectated Media Direct Radiation Meteorological Stetten Sector /Aztenuth Distance frone Mustar Directlen Reactor (Approm) Descript1'on Medte Frequency . 747 $/185 0.1 mt South of Turbine sido, rottup door on PAF Direct Radiation Q l T48 SW/235 0.2 mi 30 ft. f rom corner of AAP on PAF T49 WSW/251 1.1 mi Corner of site boundary fence north of NOC~ Direct Radtetion Q along Critical Path Rd. T50 W/270 0.9 mt Site boundary fence near mein gate by the Direct Radiation Q south Bullit St. sign T51 N/3 0.4 mi Site boundary fence north of North Direct Radiation Q Cooling Tower T52 NME/20 0.4 mt Site boundary fence at the corner of Direct Radiation Q Arson and Tower T53 NE/55 0.2 mi Site boundary fence east of South Direct Radiation Q Cooling Tower T54 S/199- 0.3 mi Pole, next to Fermi 2 viattors Center Direct Radiation Q 755 WSW/251 3.3 mt First pole east.of Frenchtown Fire Station Direct Radiation Q g (A entrance, across from Sodt Elementary School i/ T56 WSW/255 4.9 mi Pole, entrance to Jefferson Middle School on Direct Radiation- Q Stoney Creek Rd. T57 W/260 2.7 mi Pole. north side of W1111ans Rd. across from Direct Radiation Q Jefferson High School entrance T58 WSW/249 4.9 mi Pole. west of Hurd Elementary School Marquee Direct Radiation Q T59 NW/325 2.6 mi Pole. north of St. Charles Church Direct Radiation Q entrance on Dixie Hwy. T60 NNW/341 2.5 et 1st pole north of North Elementary School Direct Radiation Q entrance on Dixie Hwy. t T61 W/268 10.1 mt Pole. SW Corner of Stewart and Direct Radiation Q Raisinville Rds. T62 SW/232 9.7 mi Pole. NW Corner of Albein and Hull Rds. Direct Radiation Q T63 WSW/245 9.6 mi Pole. Corner of Dunbar and Telegraph Rds. Direct Radiation Q _ _ _ _ _ . _ - . _ _ _ _ - _ _ - _ _ _ - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - - _ - _ _ _ _ _ . _ - _ _ _ _ - _ .- __- - --- _ .- - _ _ _ ___-_____ _ ~ _____.
DOCW10.0
- R wistEn 5 Prge 10.0-8 TABLE 10.0-1 Radiological Environmental Isonttoring Program. Formt 2 Seaple Locations and Associated Wodie Fish and Sediment IIeteorological Station Sector /Aximuth Distance from Number Direction Reactor (Appron) Description media Frequency SE0!MENTS S-1 $$E/185' O.9 mi Pointe Aux Peaux. Shoreline to 500 ft Sediment SA offshore sighting directly to Land Base water Tower ,
5-2 E/818 0.2 m1 Fermi 2 Discharge. approm 200 ft offshore Sediment SA S-3 NE/39' 1.1 mi Estral Beach. approx 200 ft offshore. off Sediment SA North shoreline where Swan Creek and Lake Erie meet S-4 WSw/241' 3.0 mt Indten Traits Community Beach Sediment SA S-S NNE/208 11.7 mi DECO *s Trenton Channel Power Plant intake Sediment SA ares (Control) FISH F-1 NNE/31' g.5 mi Celeron Island (Control) Fish SA F-2 E/86 0 0.4 mi Feret 2 Discharge (approm 1200 ft offshore) Fish SA F-3 WSw/238' 4.8 nt Brest Bay Marina Area (Control) Fish SA
- =. .~. . . . . .
00CM-10.0 Qcvioicn 5 Pree 10.0-3 TigLE 13.0-1 Radiological Environmental Monitoring Program. Formt 2 Semple Locations and Associated Media Milk / Gross Weteorelegical Stetton Sector / Azimuth Distance from Number Direction Reactor (Approx) Description Media Frequency l M-2 NW/319' 5.4 mi Resume Farm - 2705 E Lobo Milk M-SM M-8 WNW/200 0 9.9 mi Calder Dairy - 9334 Finzel Rd Milk M-SM
ODCM-10.0 Qcviottin 5 Page 10.0-10 TABLE 10.D-1 Redfelogical Environmental penitoring Program. Feret 2 Sample Locatione and Associated Modta Water IBeteorological Stetten Sector / Azimuth Distance fross Number Direction Reacter (Approm) Description Modte Frequency DRINKING WATER OW-1 $/174' 1.1 mi Monroe Water Station N Side of Pointe Aux Drinking Water M Peaux 1/2 Block W of Long Rd DW-2 N/8' 18.5 mi Detroit Water Station Drinking Water M 14700 Moran Rd. Allen Park (Control) DW-3 SSE/100 0 0.3 mi Formt 1 Row Lake Water Intake Structure Drinking Water M SURFACE WATER SW-2 NNE/20 0 11.7 mt DECO's Trenton Channel Power Plant Intake Surface Water M Structure (Screenhouse al) (Control) SW-3 SSE/157 0 0.2 mt DECO *s Fermi 2 General Service Water Surface Water M lk ] Intake Structure SITE WELLS GW-1 $/175' O.4 mi Approm 100 ft W of Lake Erie. EF-1 Parking lot Groundwater Q near gas fired peakers GW-2 SSW/208' 1.0 mi 4 ft S of Pointe Aus Peaux (PAP) Rd Fence Groundwater O 427 ft W of where PAP crosses over Stoney Point's Western Dike GW-3 SW/228' 1.0 mi 143 ft W of PAP Rd Gate. 62 ft N of Groundwater Q PAP Rd Fence GW-4 WNW/299 0 3.6 mi 42 ft 5 of Langton Rd. 8 ft E of Groundwater O Toll Rd Fence
ODCM-10.0 Q:visttn 5 Poco 10.0-11 TABt.E 13.0-1 Radielegical Enytrermeental IBonitoring Program. Ferent 2 Sample Location? and Aseectated Wodte Air Particulate Air Iodine Meteorelegical Statten Secter/ Azimuth Distance frem Number Directten Reacter (Apprem) Description Itedte Frequency API-1 NE/398 1.4 mt Estral Beech Pole on Lakeshore. 15 Poles S of Mediotodine W Lakeview (Nearest Community with highest X/Q) Particulates W API-2 NNW/337' O.6 mt Site Boundry and Toll Road, on Site Fence by Radiotodine W T-4 Particulates W API-3 NW/313 8 0.6 mi Site Boundry and To11 Road, on Site Fence by Radictodine W T-5 Particulates W API-4 W/270' 14.2 mi Pole, behind Doty Form - 7512 N Custer Road Radiolodine- W (Control) Particulates W API-5 S/1910 1.2 et one pole south of Potnte Aux Pesum Rd on Radiciodine W Erie St Particulates W
ooc >10.0 QOvicton 5 P ge 10.0-12 ' TABLE 10.0-1 Radiological Environmental Isonttoring Program. Feral 2 Sample Locations and Associated Wedte Food Products Meteoretosical Stetten Sector / Azimuth Distance from Mundwr Ofrection Reactor (Appron) Description media Frequency , FP-1 NNE/21' 3.9 mt 9501 Turnpike Highway Food Products M (when available) FP-3 NNE/128 1.1 mt 8441 Brancheau Food Products W (when FP-6 WNW/290' 14.5 at 8200 Geirman (Control) Food Products
.. 11.bt.)
M (when
,gg eve 11able)
FP-7 WNW/302' O.7 mi 6200 Langton* Food Products M (when ! 4 available) N /
- calculated critical receptor
ODCW-10.0 Ocviolan 5 P;ge 10.0-13 TABLE 10.2-1 Radielegical Envirorumental Monitoring Program. Formt 2 Sample Locations and Assectated Medle Land Use Census Closest Reeldences 1Beteorelegical Dietence from Sector Reactor (Appron) Description , NE 1.1 mt 6760 Lakeshore NME 1.1 mi 6460 Branchesu N 1.1 mi 6362 Branchesu g\%) NMW 1.1 mi 5701 Pcat NW 1.0 mt 6577 Leroux WNW ~ 0.7 mi 6200 Langton W 1.1 at 6001 Toll WSW 1.4 mt 4981 Pointo Aux Peaux SW 1.3 mi 5194 pointe Aus Peaux SSW 1.1 mt 5820 Pointe Aun Peaux f S 1.0 mt 4834 Long ESE-SSE Lake Erie
ODCG-10.0 Q:vicitn 5 Pr@o 10.0-14 TABLE 10.0-2 Radiological Environmental ISonttoring Program, Feral 1 Sample Locations and Associated Isodta Water Station Weteerlogical Number Sector /Ar*muth Distance from Direction Reactor (approm.) Description Wodle Frequency Surface Water South Lagoon S/1900 0.5 mt Shore 11ne behind fuel ott storage tank SW SA Swan Creek NW/56' 1.9 mi Area below bridge N. of Dixie Hwy end Swan SW SA Creek Rd. (Public Access area) Reactor NE/O' O.4 mi Area where overflow canal meets Swan Creek SW SA
^
Channet Lake Water SSE/159' O.4 mt Fermt 1 intet E. of pumphouse SW SA
#3 Row City Water City of 5/189' 1.2 mi Monroe Water Station, N. Side of Point Aun RW SA Monroe Peaux, 1/2 block W. of Long Rd.
Fermi 1 SSE/159' O.4 mt Fermi Unit 1 Raw Lake water intake structure RW SA City of NNE/28' 29.5 mi Detroit Detroit Water Treatment Plant 14700 Moran Rd., Allen Park RW SA gg. g i / I Note: Distances were taken from Formt 2 Reactor Center Line.
ODCD-10.0 Rovtsten 5 P".g> 10.0-15 TABLE 10.0-2 Redfological Environmental Monitoring Program. Formt 1 Semple Locatione and Associated Media Sedimente Station meteorlogical Number Sector / Azimuth Dietence from Direction Reactor (appron) Deecription medle Frequency South Lagoon S/1908 0.5 mi Shoreline behind fuel att storage tank Sediment SA Reactor Channel N/0 0 0.4 mt Area where overflow canal moote Swan Creek Sediment SA Swan Creek N/W/560 1.9 mi Aree below bridge H. of Dixie Hwy. and Swan Creek Rd. (public accese area) Sedtoont SA
_ : ; S
<l l11 l i
' f - < ;
_ E T i E A N C t I D E O C I A F R R 1 S I U ,s E A S L / / , I M o S E R E g s 1 n N! TA gR N g!O A. i - I o 1t A W R ' S Rt 0 0 1 M
- i 5
n o. 10 oo t e s i e u C v g g 0 r 0 NE L A C S e AC II NT t DT IA ARSKW RATN GE "' PNID " T ERN CRMDU EII O *8 u ig g , s D e a i ? O R p r RAD I EWGt D SS I / R'd u-P WW " TA5DGul- - E E E e0AA N w 12or S E 'c I-wS E
- 4 E
E S 3g I. V " sm a E T I S -
~
, F O -
s E L4 E R S I. A TG N T S , E I S EI eDF _ N A E , g s =r m E R E E RE . K \ OOE
~ I>
L i
'T 3 A
L
\
\
\
\ NFS .
I !.
\
/ ,
x ,
\g I ,
y N .I A y I ~
* ~
~
~ "
k e I A. =
=
. 1 f g
/
^
r x S W a J n. ~- S
. > I. f
/ .r /
/ I ' W S
N I i Fi
^ S 8 / / I f
W S' W w W
ODCM - 10.0 Revision 5 1
. umerA
@--W N o
** a**
* * =s. .
Page 10.0 - 17 imNN "T- " Figure 10.0 - 2 l o ' " i? ,
=
- ~
W. y --
/- ,-
. av '
NE m 1_2
=- v
- = , S41
~
t , . WNW ! ,,- d 5 Y-6 E 0g
-.,. h - ,_ -
m 17.,'~
~' i s
c xAoA Q 3 .I f [ #
. . - 3 2*, -@
% m2 r- " 1-t ,, E T,
&%mmser Q y 10
. f M -
N
- 5 0 5 10
=
T. 1 T T ME g SCALE IN MILES
+ =
i ears Vd5W @ - m . w ;,. , i'ESE LEGEND
's 0 -T- DIRECT RADIATION i co. .s N moerar sawen *. O -API- AIR PARTICULATES OR AIR IODINE-
. 1. -p .--
k* m Q N. A -S- SEDIMENTS
- A -DW/SW- DRINKING WATER / SURFACE WATER syrsam4[y I as,, ,
C E-
-GW- GROUND WATER a m_
- J F= -M- MILK o o
/ .f
-FP- FOOO PRODUCTS
-F- FISH
& , .. -. . novrst maan s
. m o
cJ s. SE
%I'W((.
e rIGuRE z SAMPLING LOCATIONS l g
$ t BY STATION NUMBER (CREATER THAN 10 MILES)
.g* i I ODCM - 10.0 N aevision s MNW NE Page 10.0 - 18 h , ,
' 2 Figure 10.0 - 3
= 1M WM
~
y_s ; u - m, ri, /. kJ'g. '! 7 ~
- w. ems a ;c
,__ o s m ,
; - 2 a sv/ ,,_ ~viim, s
s - j ,n ave yx yy N <l . . . I , l W , I d i E f*D ' p III / *^ . w a i o i 2 s / - . SCALE IN WILES 1 # ' - c' - i* 2 / \ g>' .? W, - \ -o ESE 4 LAKE . LEGEND \ ./ \ : *y . e-T- DIRECT RADIATION \ ERAF O-API- AIR PARTICULATES/ AIR IODINE i * \ A SEDIMENTS ' \ a-DW/5W- DRINKING WATER / SURFACE WATER / \ SE )N -GW- CRWND WATER -M- MILK + / \ I -FP- FOOO PRODUCTS -F- FISH \ / f SSW NSSE s,M,Ligt!Cir10NS i' $ rnoTEi- - - ~ s -----1 BY STATION NUMBER (LESS THAN 10 MILES) ll5 N!!'!El/d!r0$$cPh2!:"-l _ oc,,,en o. ,,.,.e . . . . . . . .. ODCM - 10.0 Revision 5 N Page 10.0 - 19 Figure 10.0 - 4 r E NW T4 ( A - r ' T5 ENE T ' / T52 - WNW pp_7 p1_3 J LAKE ' T6 c 4 g \, 5 3 -_ T46 n 6g og TSO 4F-2 ERIE mE = W , ; o .s 4 / T[ , $, SCALE IN MILES i - 749 w J c4_i e ESE teceno ggg , "" I CU ES/ AIR IODINE ,# l _ A /S - N WATER / SURFACE WATER SE :g_u,1gyooucrs =j - 3 1 s-i ) "T y_ E gy, p,### SSE r s,,ty,uRt,c,4,,,,, s S s??t AMAT, Mar t S . 3 o . N d*k 5 'S 5 g : I g - d *O il 3$ B d5 k". k g i S d i. g# " G -{ B a 9-el - 3 1 o 1 g U z S W 5 u W #4 e. Z I g w w J %,, % w 1 4 g# .- y ~ [' ^ ( , ..s 4 # ) - ' *~ k\ .- - w 5 5 7 8 2 3 . "- 5 +
- 3. i i ,
' Zye % (1 t g - \ \ ) 1 y g 3 \
- Z *r,, -
2 i o f . /i - \ i { a t 5 i * :. 1 ? ; ] \ \ v A genuen uelasinogeo esoo entsuo g twJ8d - uoponpoJd JeolonN E ~ { , Nurl: r Pr:ductirn - F rmi 2 ODCM-APP-A Offsita D:s3 C:lcul:tiin M:nu:1 R;visi:n 4 Page A-1 APPENDIX A: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS ( 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 one-step dose assessment yields a dose calculation method which is both simple and conservative. Fermi 2 does not have a large data base of previous releases 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 NRC GALE computer code, (NUREG-0016, Revision 1). Site specific dose conversion factors (Ajo) from ODCM Table 6.0-1 were multiplied by the UFSAR estimated annual release quantity to determine a relative dose significance. Table A 'i 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. Selection 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 i 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 simpilfied 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 liver 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. ARMS - INFORMATION SERVICES Date approved: 7- 3c, -9 2. Release authorized by: 7,/d%[ C tlwteww_ - vi g Change numbers incorporated: LCR 91-104-ODM , DSN 0A CK -/)//- A Rev 4 Date Ausers t 9,M% DTC TMPLAN File 1715.02 Recipient /d D R G O ___. ODCM-APP-A Rsvision 4 Page A-2 I Simplified Method For evaluation of compilance with the dose limits ODCM 3.11.1.2, the following simplified equations may be used: Total Body D 1.67 E - 02
- VOL , A(Cs-134,th)
- O i
tb = DF
- Z (A-1) where:
Dtb = dose to the total body (mrem) VOL = volume of liquid effluents released (gal) 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 uCi/ml, the total body ingestion dose factor for Cs-134 Ci = total concentration of all radionuclides (uCi/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: D tb = 9.69 E + 03 . VOL DF = Z . [C y l (A-2) l l Maximum Organ D = 1.67 E - 02 . VOL , A(Cs-134, liver)
- i DF
- Z (A-3) where:
Dmax = maximum organ dose (mrem) ) A(Cs-134, liver) = 7.09 E + 05 mrem /hr per uCl/ml, the liver ingestion dose factor for Cs-134 I l ODCM-APP-A Revision 4 Page A
- 1 .
Substituting the value for the Cs-134 liver dose conversion factor, the equation simplifies to: D = - 1.18E + 04 . VOL . [C, DF a 2 (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 relethicly negligible. Furthermore, the release of tritium is a function of operating h: 4c.y and is essentially unrelated to radweste system operations, i 4 ( l s - - . - - , - m c - , , , % ^ .'~ . 00CM-APP-A Revision 4 page A-4 TABLE A-1 Relative Dose Significance of Radionuclides in Liquid Effluents Estimated Relative Dose Stentficance Percent Dose Contritpution Annual Ago
- Curies (% total)
Releases Muclide* Curtes Bone Liver T Body Thyroid Kidney Lung GI-LLI Bone Liver T Body Thyroid Kidney 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 0-32 .00011 152.70 9.49 5.90 0 0 0 17.17 56.37' 3.63 3.10 0 0 0 13.06 En-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 O .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 Y-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 I-131 00220 43 .61 .35 200.42 1.05 0 .16 16 .23 .18 28.54 .96 0 .12 3-130 .01100 .10 .28 .10' 9.76 44 0 .05 .04 11- .05 1.39 41 0 .04 1-133 .02500 1.66 2.88 .88 423.96 5.03 0 .2.59 .61 1.10 46 60.38 4.60 0 1.97 I-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 No-239 .00360 .00 .00 .00 0 .00 0 3.00 .00 .00. .00. 0 .00 0 2.28 , TOTAL 268.53 260.16.109.98 700.40 107.87 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. 1 + _ , _ - . _ . _ - _ . _ _ _ _ m _. _m--__ _ _ _ _ _ _ _ _ _ _ _ . _ Ih i Nuclo:r Praduttisn - Fcrmi 2 - C DCM-APP-3 , Offsita D:ss C Iculatian Mtnuni R;visi:n 4 Page B-1 , APPENDIX B: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS ! GASEOUS RADWASTE EFFLUENTS l l Overview Dose evaluations for releases of gaseous radioactive effluents may be simplified by the use 'I 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 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, Moff, or Neff) times the quantity of radioactive gases released, rather than ) individual analyses for each radionuclide and summing the results to determine the dose, l 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. l l Determination of Effective Dose Factors ' Effective dose transfer factors are calculated by the following equations: ] ' Keff = { Kg
- fg )
(B-1) where: , Keff = the effective total body dose factor due to gamma emissions from all noble gases released (mrem /yr per uCl/m , effective) ' = Ki the total body dose factor due to gamma epissions from each noble gas radionuclide i released (mrem /yr per uCi/m , from Table 7.0-2) fi = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity I (L + 1.1 M)eff = [((L + i 1.1 M i)
- f i) l (B-2) i i
where: (L + 1.1 M)eff = the effective skin dose factor due to beta and gagma emissions from all noble gases released (mrem /yr per uCl/m , effective) (Li + 1.1 Mj) = the skin dose factor due to beta and gamma emissions frog each noble gas radionuclide i released (mrem /yr per uCi/m , from Table 7.0-2) ARMS - INFORMATION SERVICES Date approved: 7 36-92 Release authorized by: '2T h[r '7 64rwm Change numbers incorporated: LCR 91-104-ODM I ( DSN D Al' N - k ll-h Rev 4 Date kV6VS T lhjfW DTC TMPLAN File 1715.02 Recipient /dh ccNTncLL:= 4 ODCM-APP-B l Revision 4 l Page B-2 l ( Mett = [(Mef) i i -. where: Megg = the effective air dose factorgue' to gamma emissions from all noble gases released (mrad /yr per uCi/m , effective) l l = Mi the air dose factor due to ggmma emissions from each noble gas radionuclide i ) released (mrad /yr per uCi/m , from Table 7.0-2) N egg = [(N i* f i) (B-4) where: = Neff the effective air dose factorgue to beta emissions from all noble gases released (mrad /yr per uCi/m , effective) 1 Ni = the air dose factor due to bqta emissions from each noble gas radionuclide i released (mrad /yr per uCi/m , from Table 7.0-2) l 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 provide a reasonable data base for determination of the typical radionuclide l distribution in gaseous effluents. Therefore, the UFSAR estimate of radionuclide l 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. Application 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 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 lirnits of ODCM 3.11.2.2 the following simplified equations may be used: D = 2.0
- 3.17 E - 08 a X/O
- eM gg * [Qi (B-5) and D = 2.0 a 3.17 E - 08
- X/O
- Negg a [Q i (B-6) where:
D = air dose due to gamma emissions for the cumulative release of all noble gases (mrad) ; D = air dose due to beta emissions for the cumulative release of all noble gases (mrad) - ODCM-APP-B Revision 4 ' Page B-3 k X/O = atmospheric dispersion to the controlling site boundary (sec/m3) fAett = 2.7 E + 03, effective gamma-air dose factor (mrad /yr per uCi/m3) Nett = 2.3 E + 03, effective beta-air dose factor (mrad /yr per uCl/m3) Oi = cumulative release for all noble gas radionuclides (uCl) 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: D 7 = 1.71 E - 04
- X/O * [Oi and D =
1.46 E - 04
- X/O * [O i (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. e 1 i i i 1 6 4 m ]}}