ML20082M613
| ML20082M613 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/30/1991 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-2474, NUDOCS 9109050284 | |
| Download: ML20082M613 (215) | |
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, UNKW ILLliCTIUC 32 August 2C, 1991 l
l l-U.S. Nuclear Regulatory Commission l Attn: Document Control Desk l
Mail Stop P1-137 Washington, D.C. 20555 ULNRC- 24 74
+ Gentlemen:
DOCFET NUMBER 50-483 CALI.AWAY PLAffr SEMI ANNUAL _ RADIOACTIVE EFFLUElfr RELEASE..REPollT l The enclosed semiannual radioactive effluent release report for the first half of 1991 is submitted pursuant to section 6,9.1.7 of the Callaway Plant.
Technical Specifications.
If there are any questions relating to thin information, please contact us. l Very truly ou s,
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)onald F. Schnell BEH/kea Enclosure 1
C50051 9109050284 910630 'h,l
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PDR ADOCK 05000483 ' / [, \ f R PDR
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, a cc: T. A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 11 gt t , I b. 20b37 )
Dr. J. O. Cermak CFA, Inc.
18225-A Flower Hill Way Gaithersburg, MD 208'9-5334 R. C. Knop Chief, Reactor Project Branch 1 U.S. !!uclear Regulatory Commission Region IIT 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 M. D. Lynch (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20851 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 William Keeler Regional Administrator Department of flatural Resourcen Centrel Regional Office P.O. Box 176 Jefferson City. MO 65102
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SEM_IA_NN_UAL RADIOACTIVE EFFLUENT REIIASE REPORT CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY - JUNE, 1991
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T_ABIJn0}iC0h]ENTS 1,0 INTRODUCTION 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 tleasurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0
SUMMARY
OF GASEOUS RADIDACTIVE EFFLUEhTS 4.0
SUMMARY
OF LIQUID RAD 10 ACTIVE EFFLUENTS 5.0 SOLID WASTE SilIPMENTS 6.0 RELATED INFORMATION 6.1 Unpinnned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 Major Changes to Radwaste Treatment Systems 6.5 land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation Table 1A Semiannual Summation of Gaseous Releases Table 1B Semiannual Airborne Continuous and Batch Releases Table 2A Semiannual Summation of Liquid Releasns Table 2B Samiannunt Liquid Continuous and Batch Releases Tchle 3 Solid Waste and Irradiated Fuel Shipments Attachment 1 APA-ZZ-01003, Offsite Dose Calculation Manual, Revision 2
1,0 INTRQDUCTION This Semiannual Radioactive Efiluent Release Report is submitted in accordance with Section 6.9.1.7 of the Callowey Plant Technical Specifications.
The report presents a summary of radioactivity relensed in liquid and gaseous effluents, and solid waste shipped trom the callaway Plant during the peric.i f rom January 1, 1991 to June 30, 1991. The information is presanted in the format outline.1 in Appendix 11 of Regulatory Guide 1 21, Revision 1, June 1974.
All liquid and gaseous effluents disenarged during this reporting period were in compliance with federal regulations and the limits of Union Electric Administrative Procedure APA-ZZ-01003.
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! 2.0 SUIPM E H AL_INFORMATI0f4 2.1 lier,ul_atory Lim _ils Specified as follows are the technical specification limits applica-ble to the release of radioactive material in liquid and gaseous effluents.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous offluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The air dose due to noble gases released in ;;aseous effluents, from each unit, to areas at and beyond the site boundsry shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: 1.es s than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad tor beta radiation.
2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to lodine 131 and 133, Tritium and all radionuclides in particulate form with half lives greater than eight (8) days released in gastuus effluents from the site to areas at and beyond the site boundary shall be. limited to less than.or equal to 1500 mrem /yr to any organ.
The dose to a member of the public from lodine 131 and 133, 3ritium, end all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid ef flu-ents to unrest ricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ml total activity.
The dose or dose commitment to an Individual from radioactive materials in liquid ef fluents released to unrestricted areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and b, During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
2.2 Maximum Permissible Concentrations 2.2.1 The maximum permissible concentrations specified in 10 CFR Part 20, t Appendix B, Table II, Column 2 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the MPC for dissolved and entrained noble aos in liquid effluents.
2.2.2 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since applicable limits are stated in terms of dose rate at the unrestricted area boundary.
2.3 Average Ene_r_gy.
This is not applicable to the Callaway Plant's radiological offluent technical specifications.
2.4 Measurements and Approximations of Total Radioactivity The quantity of radioactivity released in liquid and gaseous effluente was determined by sampling and radiological analysis of effluents in accordance with the requirements of Table 9.3-A and Table 9.6-A of APA-ZZ-01003, Offsite Dose Calculation Manual.
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Gamma " spectroscopy w a s _- thn- primary analysis technique used to determine the- radionticlide composition and concentration of- liquid and = gaseous- effluents _ _ Composite samples ware analyzed for Sr-89, IL Sr-90,1 and Fe-55 by an- independent laboratory. Tritium and Gross Alpha were. ' measured for both- liquid and gaseous _ effluents using -liquid-scintillation - counting .and gas flow proportional- counting -tech-niques, ire =oectively. 4 The . total radioactivity in effluent releases- was determined from the i measured concentration of each radionuclide present and the total effluent volume discharged. '
2.5 . Batch Releases '
2.5.1l Liquid Number of batch releases: 136 Total' time period for' batch releases: -55,303 minutes Maximum time period for a batch release: 794 minutes Average time period for batch releases: 407 minutes Minimum time period for'a' batch: release: 1 minute Average stream flow during periods of effluent release into a L flowing stream: 59,842.cfs* .
- Ref: Letter, United States Department of the Interior-Geological Survey-Missouri,-dated July 11, 1991.
'2.5.2 - Gaseous Number of batch releases: 41 Total time period for batch releases: 6,106 minutes Maximum time period for a batch release:-3,240 minutes
~ Average time period for batch releases: 149 minutes Minimum; time' period for a batch release: 42 minutes
- 2 '. 6 Abnormal-Releases 2.6.1 Liquid. R Number of releases: 0 iTotal Activity releas ed: 0- -
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) 2,6.2 Gaseous 2.6.2.1 Number of releases: 0 2.6.2.2 Total Activity released: O C1 3.0 ,SJRtMARY OF GAS _EOUS RADIOACTIVE _EF_FLUENTS 3.1 The quantity of radioactive material released in gaseous effluents is summarized in Table 1A and 1B. For this reporting period no gaseous effluents were considered elevated releases.
4.0
SUMMARY
OF L19UID RADIOACTIVE EFF 'JENTS 4.1 The quantity of radioactive material released in liquid ef fluents is summarized in Tabic 2A and 2B.
5.0 S0_ LID WASTES 5.1 The quantity of radioactive material released in shipments of solid waste and irradiated fuel during the reporting period is summarized in Table 3. The activity and fractional abundance of each nuclide was determined for each waste type by an independent laboratory based upon radiochemical analysis. The activity of each nuclide listed in Tabic 3 was determined as the product of the fractional abundance and the total activity shipped. Those nuclides which comprise at least 1% of the total activity for a particular waste type are presented in Table 3.
In April of 1991 six !ndividual fuel rods were shipped to Chalk River Nuclear Laboratory in Canada. These fuel rods are to be evaluated as part of the Westinghouse /EPRI Failed Fuel Program.
6.0 RELATED INFORMATION 6.1 Unplanned Releases Unplanned releases are inadvertent or accidental releases of radioactive material, or releases of radioactive material via normal pathways without a release permit or proper authorization, or without proper sampling and analysis, or releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.
There were no unplanned releases during the reporting period.
6.2 Changes to the Process Control Pr m .
There were no changes made to Administrative Procedure APA-ZZ-01011,
" Process Control Program Manual", during the reporting period.
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6.3 Channes To The offsite Do_se Calculation Manual Revision 2 of Administrative Procedure APA-ZZ-01003, Offsite Dose Calculation Manual was approved May 31, 1991. This revision incorporated changes in the new Callaway Plant National Pollutant Discharge Elimination System (NPDES) permit which reduced the frequency of Gross Alpha analysis f rom each batch release to monthly composite samples.
A complete copy of Administrative Procedure APA-ZZ-01003, Revision 2 is included as Attachment 1.
6.4 Maior Changes to Radwaste Treatment Systems During the reporting period, there were no changes which could be considered a major change to a Liquid, Gaseous, or Solid Radwaste Treatment System.
6.5 Land Use Census Changei kG There were no changes in critical receptor locations for dose calculations during the reporting period.
6.6 Inoperability of Effluent Monitoring Instrumentation All effluent monitoring instrumentation was OPERABLE within the limits specified by APA-ZZ-01003 Sections 9.1.1 and 9.2.1 during the reporting period.
6.7 Instances of Liquid Holdup Tanks or Vaste Gas Decay Tanks Exceeding Technical Specification Limits All liquid tanks and waste gas decay tanks were. within the limits of Specifications 3.11.1.4 and 3.11.2.6 during the reporting period.
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1 TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS
' QUARTERS 1 AND 2, 1991 UNIT FIRST SECOND EST TOTAL TYPE OF EFFLUENT QUARTER QUARTER ERROR %
A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 1.58E+00 3.47E+00 20
- 3. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.03E-01 4.42E-01
- 3. PERCENT OF TECH SPEC LIMIT %. N/A N/A B. RADIO 10 DINES
- 1. TOTAL IODINE-131 CURIES 2.29E-07 3.48E-07 23
- 3. AVERAGE RELEASE RATE OF PERIOD uCi/SEC 2.94E-08 4.42E-08 3.-PERCENT OF TECH SPEC LIMIT % N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 9.41E-07 0.00E+00 _30 3.. AVERAGE RELEASE RATE OF PERIOD uCi/SEC 1.21E-07 0.00E+00 3.-PERCENT OF TECH SPEC LIMIT % N/A N/A
. 4. GROSS ALPHA RADIOACTIVITY CURIES 6.62E-07 1.21E-06
- D. TRITIUM
- 1. TOTAL RELEASE CURIES 7.45E+00 1.10E+01 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 9.58E-01 1.40E+00
- 3. PERCNT OF TECH SPEC LIMIT % N/A N/A PAGE 1 OF 1
TABLE 1B i SEMIANNUAL AIRBORNE CONPINUOUS AND BATCH RELEASES GROUND LE'/EL RELEASES FISSION GASES, IOCINES, AND PARTICULATES QUA.RTERS 1 AND 2, 1991 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNIT QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES Kr-85 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 CURIES 1.58E-01 0.00E+00 0.00E+00 0.00E+00 Xe-131M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 CURIES 0.00E+00 2.45E+00 5.41E-02 2.19E-01 Xe-133M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 CURIES 1.28E+00 5.22E-01 2.06E-03 2.46E-03 Xo-135M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 CURIES 0.00E+00 0.00E+00 7.75E-02 2.76E-01 TOTAL FOR PERIOD CURIES 1.44'+00 2.97E+00 1.34E-01 4.98E-01
- 3. IODINES I-131 CURIES 2.18E-07 3.48E-07 1.08E-08 0.00E+00 I-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 0.00E+00 7.59E-07 0.0CE+00 8.61E-07 I-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 2.18E-07 1.11E-06 1.08E-08 8.61E-07
- 3. PARTICULATES Co-58 CURIES 4.36E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 CURIES 1.97E-07 0.00E+00 0.00E+00 0.00E+00 Rb-88 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 CURIES 1.46E-07 0.00E+00 0.00E+00 0.00E+00 Cs-137 CURIES 1.63E-07 0.00E+00 0.00E+00 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 G ALPHA CURIES 6.22E-07 1.09E-06 3.97E-08 1.15E-07 TOTAL FOR PERIOD CURIES 1.56E-06 1.09E-06 3.97E-08 1.15E-07
TABLI 2A SEMIANNUAL' SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 1 AND 2, 1991 FIRST- SECOND EST TOTAL UNIT QUARTER QUARTER ERROR %
TYPE OF EFFLUENT A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING 20 TRITIUM, GASES, ALPHA) CURIES 5.24E-03 1.59E-03
-3. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.06E-09 2.72E-09
~------------------------------------------
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM ;
l 2.29E+02 3.55E+02 i
CURIES 14
- 1. TOTAL RELEASE
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.96E-04 6.07E-04
- 3. PERCENT OF APPLICABLE. LIMIT % N/A N/A l C. DISSOLVED AND ENTRAINEL GASES
- 1. TOTAL RELEASE CURIES 2.69E-03 7.46E-03 27
- 3. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.65E-09 1.27E-08 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL-RELEASE CURIES 6.93E-04 1.60E-03 29 GAL 2.91E*06 6.46E+06 10 E. WASTE VOL RELEASED (PRE-DILUTION)
GAL 1.50E+08 1.48E+08 10 F. VOLUME OF DILUTION WATER USED PAGE 1 OF 1
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TABLE 2B
- SEMIANNUAL-LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 1 AND 2, 1991 NUCLIDE CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND ALL NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER H-3 CURIES 0.00E+00 0.00E+00 2.29E+02 3.55E+02 Na-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-88 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Cr-51 CURIES 0.00E+00 0.00E+00 9.43E-05 0.00E400 Mn-54 CURIES 0.00E+00 0.00E+00 5.49E-04 1.34E-04 Fe-55 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 CURIES 0.00E+00 0.00E+00 1.49E-05 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 3.05E-06 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+00 1.84E-03 8.13E-05 Co-60 CURIES 0.00E+00 0.00E+00 2.08E-03 1.12E-03 Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 1.63E-04 0.00E+00
.Nb-95 CURIES 0.00E+00 0.00E+00 3.51E-04 0.00E+00 Mo-99 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 CURIES 0.00E+00 0.00E+00 2.23E-05 0.00E+00 Sb-125 CURIES 0.00E+00 0.00E+00 1.93E-05 0.00E+00 Cs-134 CURIES 0.00E4 00 0. 00E+00 2.38E-05 9,19E-05 Cs-136 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 CURIES 0.00E+00 0.00E+00 6.50E-05 1.44E-04 La-140 CURIES 0.00E+00 0.00E+00 J.00E+00 0.00E+00 Ce-141 CURIES - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-144 CURIES 0.00E+00 0.00E+00 2.01E-05 0.00E+00 Ru-105 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W-187 _ CURIES 0.00E+00-0.uoE+00 0.00E+00-0.00E+00 Hf-181 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00-I-132 CURIES 0.00E+00 0.00E+00 0.00E+00 2.04E-05 I-133 -
CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 2.62E-03 7.39E-03
-Xe-133M CURIES. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 CURIES 0.00E+00 0.00E+00 6.44E-05 7.22E-05
-Xe-135M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 G ALPHA CURIES 0.00E+00 0.00E+00 6.93E-04 1.60E-03 UNIDENTIFIED CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 2.29E+02 3.55E+02 PAGE 1 OF 1 j=*-* T' g gyy yttyW+ t V" T r-mT*r m e-un+<- , -a--m--9-Hy,=q -T-7 e W m 3 p yr e 1---""--t9--+9 + MW *rgum+wT-wgr---ve--ti-ei w 1r 'vPmyy-f m- tee--w we -- e 7v"T-t-- e--w-=m- l+r--W rmy W "
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TABLE 3 y SOLID WAS1T. 5 IRRADI ATED FUEL Sil!PMENTS RUARTERS 1 & 2. 1991
TYPE-OF WASTE- 6-MONTil EST. TOTAL PERIOD _ ERROR ( R
- a. . Spent resins, filter s*udges $4.6 m' i 25%
evaporator bottoms, etc. 1.38E+3 Percent Abundance Curies Fe-55 36.766% 5.08E+2 Co 23.644% 3.26E+2 Co-58 16.494% 2.28E+2 Ni-63 11.220% 1.55E+2 Hn-54 9.124% 1.26E+2
- b. Dry compressible waste, 12.5 m' 1 25%
contaminated equipment, etc. 15.992- Ci Percent Abundance Curies Fe-55 44.810% 7.17E+0 Co-58 23.450% 3.75E+0 Co-60 13.020% 2.08E+0 Nb-95 9.340% 1.49E40 Mn 7.440% 1.19E40 Zr-95 1.920% 3.07E-1
- c. Irradiated components, control 0 m' rods, etc. O Ci
- d. Other 0 m' O Ci Solid Waste Disposition Number of Mode of- Class of Solid Type of Shipments 1 ansportation Destination Weste Shipped _
Container 4 Cask _. Richland , '..'A A LSA 4 Truck Richland, WA A LSA
-1 Cask Barnwell, SC B LSA 1_ Cask Barnwell, SC C Type B
Solidification Agent ECement'(applicable only to waste type "A" shipped to Richland, WA)
-B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Mpde of Transportation Destination 1 Cask Chalk River, Canada l'
ATTACHMENT 1 APA-22-01003, OFFBITE DOSE CALCULATION MANUAL i
APA-ZZ-01003 l 1NFORi'AATION ONil MP"*"ee1-
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ADMINISTRATIVE PROCEDURE APA-ZZ-01003 OFFSITE DOSE CALCULATION-MANUAL RESPONSIBLE DEPARTMENT
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APPROVED BY ,dex / DATE S/ '/ f/
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-DATE ISSUED ISSUED ,
JUN 041991
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This: procedure contains the fo11owing:
1 - through 191 Pages ,
' Attachments- through 1 through 12 Tables ,
4 through. 5 Figures
. Appendices
- through Checkoff Lists through-
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Table of Centents
'f Pace Number Section 1
1.0 Purpose and Scope
1 2.0 Liquid Effluents 2.1 Radioactive Effluent Controls (REC) Section 1 9.1.1.1 2 2.2 Liquid Effluent Monitors 5 2.3 Calculation of Liquid Effluent Monitor Setpoints 11 2.4 Liquid Effluent Concentration Measurements 11 2.4.1 REC ~Section 9.3.1.1 11 2.4.2 Liquid Effluent Concentration Measurements 12 2.5 Dose Due to Liquid Effluents 12 2.5.1 REC Section 9.4.1.1 12 2.5.2 The Maximum Exposed Individual 13 2.5.3 Calculation of Dose from Liquid Effluents 2.5.4 Summary, Calculation of Dose Due to 15 Liquid' Effluents 19 L 2.6 Liquid Radwaste Treatment System 19 2.6.1 REC Section 9.5.1.1 2.6.2 Operability oi the Liquid Radwaste Treatment 20 System 21 3.0 Gaseous Effluents 21 3.1 REC Section 9.2.1.1 21 3.2 REC-Section 9.6.1.1 21 3.3 Gaseous Effluent Monitors 3.4 Calculation of Gaseous Effluent Nonitor 25
-Setpoints 26 3.4.1 Total Body Dose Rate Setpoint Calculations 28 3.4.2 Skin Dose Rate Setpoint Calculations 30 3.4.3 . Gaseous Effluent Monitors Setpoint Detern.ination 3.4.4 Summary,_ Gaseous Effluent vanitors Setpoint 32-Determination 32 3.5 Calculation of Dose from Gaseous Effluents 32 3.5.1 Calculation of Dose Rate 32 3.5.1.1 Noble Gases 34 3.5.1.2 Radionuclides Other Than Noble Gases 39 3.5.2 Individual Dose Due to Noble Gases 39
,3.5.2.1 REC Section 9.7,1.1 40 3.5.2.1.1 Noble Gases 42 3.5.2.2 REC Section 9.8.1.1 42 3.5.2.2.1 Radionuclides Other Than Noble Gases 77 3.5 Gaseous Radwaste Treatment system 77 3.6.1 REC Section 9.9.1.1
AFA-ZZ-01003 Rev. X d f 5. j,y Table of Contents Section Page Number
-3.6.2 Description of the Caseous Radwaste Treatment System 77 3.6.3 Operability of the Gaseous Radwaste Treatment System 77 4.0 Dose and Dose Commitment from Uranium Fuel Cycle Sources 78 4.1. REC Section 9.10.1.1 78 4.2 Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources 78 l
-4.2.1 Identification of the MEMBER OF THE PUBLIC 80 )
.4.2.2 Total Dose to the Nearest Resident 80 i' 4.2.3 Total Dose te the Critical Receptor Within 81 the SITE SOUNDARY j i
5.0 Radiological Environmental Monitoring 86 ,
5.1 REC Section 9.11.1.1 86 '
5.2 Description of the-Radiological Environmental Monitoring Program 86 5.3 Performance Testing of Environmental Thermoluminescence Dosimeters 67 I
! 6.0 -Determinatien of Annual Average and Short Term Atmospheric Dispersion Parameters- 105 l 105 6.1. Atmospheric Dispersion Parameters 6.1.1 Long-Term Dispersion Estimates 105 6.1.2 -Determination of Long-Term Dispersion Estimates for Special Receptor Locations 106 6.-l.3 Short-Term Dispersion Estimates 106 7 . 10 Semi-Annual Radioactive Effluent Release Report 114 8.0 Implementation of CDCM Methodology. 120 "9 . 0 Radioactive Effluent Controls (REC) 121 9 .1. Radioactive Liquid Effluent Mcnitoring Instrumentation 123
-9.2 Radioactive Gaseous Effluent Monitoring Instrumentation 130 9.3. Liquid Effluents Concentration 138
- 9.4 -Dose 144
?.3- L; quid Radwaste Treatmen: Syscem 146
- 9.6 Gaseous Effluents Dose Rate 148 l -9.' Dose-Noble cas 154 I
-ii-l I
APA-2Z-01003 Rev. f) sy t 5 't 'll
- Table of Contents Section Pace Number 9.8 Dose-Iodine-131 and 133, Tritium, and Radioactive Material in Particulate Form 156 Gaseous Radwaste Treatment System 158 9.9 Total Dose 160 9.10 Radiological Environmental Monitoring Program 164 9.11 9.12 Radiological Environmental Monitoring Land Use Census 180 9.13 Radiological Environmental Monitoring Inter-laboratory Comparison Program 183 10.0 Administrative Control 184 10.1 Major Changes to Liquid and Gaseous Radwaste Treatment Systems 184 10.2 Charges to the Offsite Dose Calculation Manual 185 (ODCM) 11.0 References 186 Figure 4.1 Site Area Closed to Public Use 85 Figure 5.1A Airborne & TLD Sampling Network 100
. Eigure 5.13 Airborne & TLD Sampling Network 101 Figure 5.2A Location of Aquatic Sampling Stations 102 Figure 5.23 Location of Aquatic Sampling Stations 103 Figure 5.3 Food Products Sampling Locations 104 e
APA-ZZ-01003 Rev. XJL. ppq j f.) N x
Table of Contents 3:
Page Numbet Section-Table-1 Ingestion Dose Commitment Factor 16-17 (Ag) for Adult-A9e Group Table 2 Bioaccumulation Factor (BF1 ) Used in the Absence of Site-Specific Data 18l Table 3 Dose Eactors for Exposure to A Semi-Infinite 31 Cloud of Noble Gases Table-4 Dose Parameter (Pg) for Radionuclides Other Than Noble Cases 36 Table.5 Pathway Dose Factors (R3 ) for Radionucl. des 46-76 other Than-Moble Gases Table 6' Radiological Environmental Monitoring Program 88-95 Table 7 Reporting Levels for Radioactivity 96 Ccncentrations in-Environmental Samples Table 8 -Maximum Values for the Lower Limits of 97 Detection Table 9 Highest Annual Average Atmospheric Dispersion 110 Param'eters - Radwaste Building Vent Table 9cl-A- Radioactive Liquid Effluent Monitoring 125-127 Instrumentation-w Table 9.1-B Radioactive Liquid Effluent Monitoring 128-129 Instrumentation _ Surveillance Requirements
-Table 9.2-A Radioactive Gaseous Effluent Monitoring _
132-134 Instrumentation Table 9.2-B Radioactive Gaseous Effluent Monitoring 135-137 Instrumentation Surveillance Requirements Table 9. 3 - A Radioactive Liquid Waste Sampling and Analysis Program .
140-143 Table 9.6-A- Radioactive Gaseous Waste Sampling and Anslysis Program _150-153
-Table 9.11-A Radiological Environmental Monitoring 168-174 Program Table 9.ll-B Reporting Levels for Radioactivity 175 Concentrations In Environmental Samples Table 9.11-C Detection Capabilities for Environmental 176-179
. Sample Analysis Highest Annual Average Atmospheric Table 10- 111 Dispersion Parameters - Unit Vent 112 l
' Table 11 Short Term Dispersion Parameters j Table'12 -Application of Atmospheric Dispersi:n 113 P a rame t e r s --
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APA-ZZ-01003 Rev. Y c2 5 j cf l N
Record of Revisions Revision Reason Number Date for Revision Rev. O March 1983 Rev. 1 November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments Rev. 2 March 1984 Revised to incorporate NRC Staff comments Rev. 3 June 1985 Revised to incorporate errata identified by ULNRC-903 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land use Census.
Rev. 4 February 1987 Minor clarifications, incorporated 31-day projected dose methodology.
Change in the utilization of areas within the Site Boundary.
Rev. 5 January 1988 Minor clarifications, revised descriptions of liquid and gaseous rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose calculations for 40CFR190 requi re:aent's , Revised Table 6 and Figures 5.1A and 5.13 to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables 1, 2, 4, and 5 cc add additional nuclides, deleted redundant material from Chapter 6.
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APA-ZZ-01003 Rev. 78, 1*s r n ,-
i f' .,
') Record of Revisiens Rev. 6 May 1989 Revised methodology for calculating i
maximum permissible liquid effluent discharge rates and liquid effluent monitor setpoints, provided methodology for calculating liquid effluent monitors response correction factors, provided an enhanced description of controls on liquid monitor background limits, provided additional liquid &
gaseous dose conversion factors and bicaccumulation factors (Tables 1, 2, 4 & 5), provided description of the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added discussien of gaseous & liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Waste Gas
- Decay Tanks, revised dispersion parameters & acecmpanying description per FSAR Change Notice 88-42.
APA-ZZ-01003 August 1989 Radiological Effluent Technical Rev. O Specifications were moved from the Callaway Plant Standard Technical Specifications to Section 9.0, Radioactive Effluent Controls, of the ODCM as per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire CDCM, it was converted to APA-ZZ-01003, OFFS!TE DOSE CALCULATION MANUAL.
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APA-22-01003 Rev. J JD F-r-gi Jg a
OFFSITE DOSE CALOULATION MANUAL 1.0 PURPOSE AND SCOPE 1.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6 and 6.9.1 7. The CDCM also contains a list and description of the specific sample locations for the radiological environmental monitoring program.
?
2.0 LIQUID EFFLUENTS 2.1 RADIOACTIVE EFFLUENT CONTROLS (REC) SECTION 9.1.1.1 41838 The radioactive Ir;uid effluent monitoring instrumentation channels shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 9.3.1.1 are not exceeded. The 41840 alarm / trip setpcints of these channels shall be adjusted to the values determined in accordance with the methodeiogy and parameters in the ODCM.
1-
AFA-22-01003 Rev. P ;L l 94 y e.g f l( ,,
)
2.2 Licuid Effluent Monitors Gross radioactivity monitors which provide for automatic termination of liquid effluent releases are present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown). Setpoints, precautions, and limitations applicable to the ope > tion of the Callaway Plant liquid effluent monicors are provided in the appropriate Plant Procedures. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding the Maximum Permissible Concentration (MPC) limits in 10 CFR Part 20 atThe the calculated release point to the UNRESTRICTED AREA.
alarm and trip action setpoints for the liquid effluent line Monitors and flow measuring devices must satisfy th' following equation:
cf < C F+ f
~
(2.1) i Where:
C= the liquid effluent concentration limit (MPC) implementing Section 9.3.1.1 for the site in (uC1/ml).
c= The setpoint, in (uC1/ml), of the radioactivity monitor measuring the radioactivity concentration in tne effluent line prior to dilution and subsequent release; the setpoint, which is inversely related to the volumetric flow of the effluent line and directly related to the '
volumetric flow of the dilution stream plus the effluent stream, represents a value, which, if exceeded, would result in concentrations exceeding the limits of 10 CFR Part 20 in the UNRESTRIOTED AREA.
2 -
- . - . - .... . ~ ~- .- . .. - . . . . - - - - . ~ - - - - -
_APA-ZZ-01003 Rev. Y ,;L
)? F A i
) f =- The flow setpoint as measured 1at the .
i radiation monitor location, in volume per unit time, but in the same units as F, below.
j F= The dilution water flow setpoint as q measured prior to the release point, 1n J volume per unit time. {If (F) is large compared to (f), then F + f = F).
(Ref. 11.8.1) r-If no: dilution is provided, then c < C.
'The radioactive liquid waste stream is diluted by l the plant discharge line prior to entry into:the Missouri River. Normally, the dilution flow is
- obtained from the cooling tower blowdown, but-should this become unavailable, the plant water
- treatment facility supplies the necessary dilution flow via a bypass linu. The batch:
release limiting concentration (c) which-corresponds to the liquid radwaste effluent line monitor setpoint is to be calculated using methodology from the expression-above.
i 4
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AFA-ZZ-OlOO3
( Rev. J jL S'- I - 9 l 9.rt
--) Thus, the expression for determining the setpoint on the liquid radwaste effluent line nonitor becomes:
c; C(F + f) (uCi/ml) f (2.2)
The alarm / trip setpoint cal'culations are based on the minimum dilution flow rate (cooling tower blowdown, 5000 gpm), the maximum effluent stream Due flow rate, and the actual isotopic analysis.
to the possibility of a simulataneous release from more than o e release pathway, a portion of the total site The release limit is determination andallocated usage of to theeach pathway.
allocation factor is discussed in Section is reached, 2.3.
In the event the alarm / trip setpoint an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis to ensure that Section 9.3.1.1 3- limits were not exceeded.
2.2.1 Centinuous Licuid Effluent Monitors The rac.iation detection monitors associated with
.ontinuous liquid effluent releases are (Ref.
11.6.1, 11.6.2):
Monitor I.D. Descrintion SM-RE-52 Steam Generator Slowdown Discharge Monitor LE-RE-59 Turbine Building Frain Monitor 4
.. . . _ _ . ~ _ - . . _ _ _ ._ . . _ _ _ . _ _ . - _ . _ _ _ _ _ _ . _ . . . . _ _ .
1
.ht a se 4 t APA ZZ-01003 Rev. A'JL 9:t c-~n I-These effluent streams are not considered to be radioactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis. The sampling frequency, minimum analysis frequency, and type of a.ialysis performed are as per Table 9.3-A.
Since the Turbine Building Drain is not a designated liquid radioactive effluent discharge -1 point, its setpoint is established as a function
- of b.tekground.
2.2.2 Radioactive Licuid Batch Reisase Effluent .
Monitors The two radiation monitors which are associated with the liquid effluent batch release systems
- are (Ref. 11.6.4, 11.6.5):
MONITOR I.D., Description RB-RE-18 Liquid Radvaste Discharge !
' Monitor i
HF-RE-45 secondary Liquid Waste System Monitor 1
.' These effluent streams are normally considered to be radioactive. The sampling frequency, minimum analysis frequency, and the type of analysis
-performed _are as per Table 9.3-A. j 2.3 Cal.culation of Lieuid Effluent Monitor Setpoints
'The dependence of the setpoint (c),.on the radionuclide_ distribution,_ yields, calibratien.
and monitor parameters, requires that several variables be considered in setpoint calculations, (Ref. 11.8.1) ;
- 15 -
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APA-Z"-01003 Rev. J,2. ,
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2.3.1 Calculatien cf the MFC Sun The isotepic cancentratien of the release (s) being considered must be determined. This is obtained from the analyses required per Table 9.3-A, and is used to calculate an MFC sum (MPCSUM):
MPCSUM =
(I(C g)g/(MPC g)1)+(C /MPC,)+(C,/MPC 3 n g/MFCt)+(Cg/MFC 1) (2.3) i Where:
(Cg)g
= the concentration (C ) of each measured gamma emitting nuclide, i, observed by gamma-ray spectroscopy of the waste samplo.
) C ,' = the mearured concentration (C,) of alpha emitting nuclides cbserved by gross alpha analysis.
Ca * = the measured concentrations of Sr-89 and Sr-90 ca determined by analysis of the quarterly composite sample.
Cg * = the measared concentration of H-3 in liquid effluents.
Cf * = the measured concentration of Fe-55 in liquid waste as determined by analysis of the quarterly composite sample.
- Values for these concentrations will be based on previcus ecmposite sample analyses as required by Table 9.3-A.
s.
w~ ,
APA-ZC-01003 Rev. 2',2L
())l s -I A p MPC MPC t *- are the limiting q , MFC,, MPC,, MPC g, concentrations of the apprcpriate radienuclidos )
from 10CFR 20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases, the ;
~
concentration shall be limited to 2x10 ' uCi/mi total activity.
SF n the ssfety factor; an administrative factor used to compensate for statistical fluctuations and errors of measurements. ,
4 This factor also provides a margin of safety in the calculation of the maximum liquid effluent discharge flowrate (f,,x).
The value of SF should be $1.
For the case MPCSUM $ 1, the monitor tank effluent concentration meets the limits of Section.9.3.1.1 without dilution and the effluent may be released at any desired flow rate. If MPCSUM > 1 then dilution is required to Snsure
) compliance with Section 9.3.1.1 concentration limits. If simultaneous releases are occuring or are anticipated, an allocation fraction, N, must s be applied so that available dilution flow may be ,
i apportioned among simultaneous discharge ~
c/ pathways. The value of N may be any value between 0 and 1 for a particular discharge point, provided that the sum total allocation fractier:s for all discharge points must be $ 1.
S
J AFA-ZZ-01003 f' Rev. f,L S't-fI ,, .g I
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2.3.2 Calculation of the Maximum Permissible Liquid Effluent Discharge F1 curate The maximum permissible liquid effluent discharge flowrate is calculated by f,,x $ (F + f ) (SF) p (N) + (MPCSUM) (2.4)
Where:
f,,x = Maximum permissible liquid effluent discharge flowrate, in (gallons / minute);
f = the expected undiluted liquid effluent i P
flewrate, in gpm.
N= the allecation fraction whi< a apportions '
dilution flow among simultaneous discharge pathways (see discussion above) i 1- -
F, SF, & MPCSUM, are as previously defined. .I l
The minimum value of F is 5000 gpm, which is used :
as a default value. The dilution water supply is ,
furnished with a flow monitor which isolates the
/
i liquid _ effluent discharge if_the dilution flow rate falls below the 5000 gym minimum value. ;
In the event that f,,x i s less than f p, then the '
value of f,,x is substituted into the equation for f p and a new value of f,,x is calculated.
This substitution is performed for three iterations in order to calculate the_ correct value of f,,x.
. 9 h
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2.3.3 Calculaticn of Liquid Effluent Monitor Setpoint The 11guld effluent monitors are Ma!(Tl) based systems ar.d renp;:.d p rimarily to garma radiation.
Accordingly, their setpoint is based en the total concentration of gamma emitting nuclides in the ,
effluent:
c = BKG + (I(C )g + SF) pC1/ml (2.5) i Where:
c= the monitor setpoint as previoucly defined, in (uCi/ml);
BKG = the monitor background prior to discharge, in (pCi/ml);
C and SF are as previously defined.
g The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity.
Utilizing the methodology of ANSI N13.10-1974 4
(Ref. 11.21), the background must be maintained at a value of less than or equal to 2.23E-6 pCi/ml (relative to Cs-137) in order to detect a change of II-7 pCi/ml of I-134 (the most restrictive nuclide in Table 1 of reference 11.21).
In the event that there :.s no detectable gar.ma activity in the effluent or if the value of (I(C ,),+SF) is less .. tan the background of the v
- monitor, then the monitor setpoint will be set at twice thb current background of the monitor,
. 9 .
APA-22-01003
( Rev..Y Z j
!T-i 'il cy (
' As previously stated, the monitor's response is dependent on the garma emitting radienuct;de distribution of the effluent. Accordingly, a new database conversion factor is calculated for each release based upon the recults of the gamma spectrometric analyais of the effluent sample and the measured response of the monitor to the National Bureau of Standards (NBS) traceable calibraticn sources:
DECF g = (I(Cq)g)+(CMR) x (ECF) . (2.6)
Where:
DBCE, = the monitor data base conversion factor which converts count rate into concentration (uC1/ml);
CMR = the calculated response of the radiation monitor to the liquid effluent; ECF = the conversion factor for Cs-137 which converts count rate into concentration (uCi/ml).
C is as previously defined.
The new value of the DECE c is calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation vf the CMR is given in reference 11.14.7.
- 1C -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -- - - ~ _ _ _ _ , _
AFA-ZZ-01CO,3 Rev. ,h J tifg , g
. ~ , ,
) 2.4 Licuid Effluent Concentration Measurements 41346 2.4.1 EEC Section 9.3.1.1 4160 The concentration of radioactive material released in liquid effluents to Ut1 RESTRICTED AREAS shall be limited to the concentrations 1 specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentra:1on shall be limited to 2.0 E-04 pC1/mi total activity.
2.4.2 Licuid Effluent Concentration Measurements Liquid batch releases are discharged as a 1 discrete volume and each release is authorited based upon the sample-analysis and the dilution flow rate existing in the discharge line at time of release. To assure representative sampling, each liquid monitor tank is isolated and ,
thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyting each batch are outlined in. applicable plant procedures. The allowable release rate limit is calculated for each batch based upon the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authoritation for release.
The radvaste liquid effluent discharge is monitored prior to entering the dilutten discharge line and will automatically be terminated if the pre-selected alarm / trip setpoint is exceeded. Concentrations are determined primarily f rom the gamma isotcpic and ,
H-3, analyses of the liquid batch sample.
For cross alpha, Sr-89, Sr-90, t Fe-55, the
.. nuasured cencontration frcm the previous ccnposite analysis is used. Ccnposite sanples are collected for each batch release. !bnthly analysis for gross alpha and qturterly analyses for Sr-89, Sr-90, and Fe-55 are perfonned in accordance with
-Table 9.3-A.
APA-ZZ-01003 Rev. J S ;
f3b 3; tat I. Doses from liquids discharged as continuous releases are cal:ulated by utilizing the last measured values of samples required in accordance with Table 9.3-A.
2.5 Dese Due to Liquid Effluents +
' 41849 2.5.1 REC Section 9.4.1.1 4160
- The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid
' effluents released, to UNRESTRICTED AREAS shall be limited:
- a. During any calendar quarter to less than or equal to 1 5 mrem to the whole body and less than or equal to 5 mrem to any organ, and L
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
2.5'.2 The Maximum Exposed Individual The cumulative dose determination considers the dose contributions from the maximum exposed individual's consumption of fish and potable water, as appropriate. Normally, the adult i s l
considered to be the maximum exposed individual.
(Ref, 11.8.3)
The Callaway Plant's liquid _ effluents are discharged to the Missouri River. As there are ,
no potable water intakes within 50 miles of the discharge point (Ref. 11.7.1, 11.6.6), this pathway does not require routine evaluation.
Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from. discharges to the Missouri River. Dose from recreational activities is expected to contribute the additional 5%, which is considered to be negligible. (Ref. 11.6.7) .
I
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APA-ZZ-01003 I Rev. ? Cjat 5*/~7/
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1 2.5.3 Calculatien of Dose Frem Liquid Effluents 2.5.3.1 Calculatien of Dose Contricutions The dose contributions for the total time period m
Iat t
t=1 are calculated at least once each 31 days and a cumulative summation of the total body and individual organ doses is maintained for each calendar quarter. These dose contributions are calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref. 11.8.3) m D = I (A I at t it F]
t (2.12) i t=1 Where:
D: = the cumulativo dose commitment to the total body or any organ, t, from the liquid effluents for the total period m
I$t t
i t=1 in mrem.
- 13 -
APA-ZZ-01003 f Rev. IJA Q$ y-t-4 i
~- .
At = the length of the tth time period over t
which C "Ud I are averaged for all it t liquid releases, in hours. At t corresponds to the actual duration of the release (s).
3 C gg n the average measured concentration of radionuclide, i, in undiluted liquid j effluent during time period at t fr m any liquid release, in (vCi/ml). j l
1 A1 , = the site related ingestion dose commitment factor to the total body or any organ't for each identified principal gamma and beta
- emitter listed in Table 9.3-A, (in mrem /hr) per (uci/ml). The calculation of the-A g values is detailed in Ref. 11.14.5 and are given in Table 1.
i Ft = the near field average dilution factor for C du:ing any liquid effluent release.
it f f t= max (F + f,,x) 89.77 Whe re r !
f max
= maximum undiluted effluent flow rate during the release ;
E= average dilution flow 89.77 = site-specific applicable factor for the mixing effect of the discharge structure..(.Ref-11.5.1)
The-term C yg is the undiluted concentration of- .
- radioactive material in liquid vaste at the
- commen release point determined in accordance ,
with Section 9.3.1.1,-Table.9.3-A:, " Radioactive Liquid Wacte Sampling and Analysis Program". -All dilution factors beyond the sample point (s) are includec in the i g term.
- 14 -
APA-ZZ-01003
/
. Rev. I';c Lj,4 S~- t t !
l
}
The nearest municipal potable water intake downstream frem the liquid ef fluent discharge point into the Missouri River is located near the city of St. Lcuis, Mo., approximately 78 miles downstream. As there are currently no potable :
water intakes within 50 river miles of the discharge point, the drinking water pathway is j not included in dose estimates to the maximally L exposed individual, or in dose estimates to the l population. Should future water intakes be ;
constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates, (Ref. 11.6.6).
2.5.4 Summarv, calculation of Dese Due to Liouid Effluents ,
The dose contribution for the total time period *
- i 14t g
!=1 is determined by calculation at least once per 31 days and a-cumulative summation of the total body and organ-doses is maintained for each calendar quarter. The projected dose contribution from liquid effluents for which radionuclide concentrations are determined by periodic composite and grab sample analysis, may be approximated by using the last measured value.
Dose contributions are determined for all radionuclides-identified in liquid effluents released-to UNRESTRICTED AREAS. Nuclides which
-are not detected in the analyses are reported as ,.
"less than" the nuclida's Minimum Detectable Activity (KDA) and are not reported as being present at the Lower Level of Detection (LLD) level for that nuclide. The "less than" values are not used in the required dose calculations.
-r. .-m-s wv.,,-,..-,. ,,. ,,,-.wr--i,,m.., ,w.,,mm. ..--.,6,-+r,.,w, ,m.. -e ,,-v<- -----r-+w re= re. --v-- -
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I I I l I i l i Total i (N.cticet Ine i liver i hev 1 T% reid i U drev 1 Eet ! 0' EU !
lH3 INo Osta 12.06E 01 12.:6t 01l*. @01 I:. 6E 0112.26I 0112.26E 011
} Be 7 } 1.30E 0212.96E 02 11.45E 0:lNo Oata 13.15E 02iNo Data 15. lei +001 l l ;e 13.13 E+:a l 6 . ;t E +03 l6. 26t+0316. 26t+03 16. 26E*0 316.26 C+03 l d ,26 E+;31 i Na 24 la.07t+0:la.0*I+0: l4.07t+0 la.07E+0: la.0*E+0:la.07I+0:la.07t+C:l 1 P 31 te.6:I+0712.57t+06 11J5E+06lNo Cata INo Oata (No Data 15.19E+06l l Cr 51 JNo Osta INo Osta I L :!E+00 l f .6:E-01 12.81-01 11.69E+ 0l L *:E+):1 i Mn la INo Nta la.38E+03 18.35E+0:lNo Osta 11.30E+03(No Osta 11.);I 04l l Mn 56 INo Cata 11 1CE+0: 11.91E+011No Oata , l1.60E+C:lNo Osta 13.5 I+ 31 1 Ta 55 16.5?E*0:la.5;t+0: 11.06t+0:lNo Osta (No Data 12.5]E+2:l:.61E+ :l 1 Te 59 11.CeE+031:4 a;I+03 19.3a +E 0:lNo Osts INo Casa 16.8;I+0:16.13E631 l Co 57 INo Data l' .09 4-01 13.a8E-011No Oasa INo Osta INo Oata 15.3;I-::1 1 00 55 INo Oata 15.9aI+01 I .00E C:lNo Data INo Osta INo :sta !;.411+ 3l i Co-60 JNo Data 11.5'i+C: l$.6eE+021No Osta INo Oata (No Cata le.6 I-;31 1 Ni 63 13.11E-Oel*.15t+03 11.0et+031No Oata 1No Oata (No Data le=a9E*0:1 1 Ni 65 11.26E+00ll.6;E*01 17.a6t+00lNo tota !No Osta INo Cata 1 .16I*0:1 i Cu 6a l!.0 Data 11.0Ct+0! la 69E+00lNo Data lh5:!*011No Data .$.5:!*0:1 1 n 65 12.3:1+0alf.25t+0a 13.33E+0alNo Osta le 93E-0alNo Osta 1 .e5I.0el I n e9 le 13E*0119.--E+01 l6.561+00lNo Casa 16.1:E 41iNo Cata l1 e:I-011 i Br B: INo Oata INo Osta 12. 71-031No *ata INo Data (No Casa it e0E*031 l Br 63 INo Oata INo Cata ia.0at+01lNo Oata INo Osta INo Cata 15.8;I+]11 1 3r Aa INo Cats ;No 04ta 15.261+011No Data INo Oata INo Osta j.. 0:t-Cali
} 1r 85 INo :sta INo Osta 12.15L+0JINo Ossa lNo Osta lNo Casa 1 i Rb 86 !No Cata t i.0'.E+05 le.711+0also Oata (No Cata INo 1. Osta 0*E 09! ti.99t-:a!
! Kb t$ iso Oata 12.9:1-02 11.5at : lNo Oata INo Cata ;No Casa l 10 89 !No *sta 11.9;E+02 l:.35E+0:lNo Oata INo Data INo :sta !!.1 I 11!
l $r 89 I:.21E*CalNo Osta l6.35t+0:lNo Osta INo *ata INo Oata 12.5!I-031 1 3 r 90 15.e-E+05lNo Casa 11,3a!+05iNo Oata INo Oata iso 04:4 i;.57E- .i l 3r*91 le.0?E+0:lNo Oata 11.6at+011No Osta INo 04 4 INo Data li.1-E-031 1 $r 9: 11.3aE+0:lNo Osta 16.6&E-00lNo Data (No Oata (No sta 13,:ild 3l i Y 90 15 75E 01!No Osta !1.il-t M INo Oata INo Osta !No :sta 'd.10E*::'
i Y 91.1 13..-I 031No Oata i .10E ^elNo Oata 1No :sta INo Osta 6.E- 11.e:E 3t d 2l l Y 91 15.a3t+00iNo Cata 1;.05! 011No Oata !No Oata ;No Oata l i Y9 15.05I 02iNo Oata 11.eSI 03tNo Cata INo Oats !No 0a:4 (5.53I-::l ;
1 Y 93 11.6;E 011No Oata te,e:E 03lNo Osta INo Oata INo 04:4 15.;!1*
! lr 95 12.a E 01t? *tt 0: 15+21E 0:lNo Oata 11.:1E 011No Oata (;...E+ :l 1
r.st 1;,33t 0:12.68E 03 11. :E 03tNo :ata l..pt 03;No :sta ll.:0t*;:!
I Nb-95 le e71*0:12.-8t+0 11.3aE+02'No Data 12.a6E*0:tNo Osta i;.5;I-Ce!
l Me 99 INo Oata 11.23E*0211.96I+MINo Oata 12.3:E*0;iNo 04ta 10.29E-0 1
! 0 99".16.S!! 031:.51E 0 13.19t 011No Data 13,5;I 0111.::t ::::..t:0 4 11I j6.* ! 001
! Tc 1C;19.'.;E ::!;.31E-0; 11. 9E 011No Osta 1:.26E*
i b 103!..a:1-::!No 04:4 ii.10E+00 Wo Cata it.69E-?tiNo :sta (5. 71- ::
- Ru ;0513.6!! 011No Data ti.45E 31tNo :ata Ia.*:E-00iNo Osta ;;.:!I-::t 5.21-:: M :st: , ..?E N ; N :sta . :: - 31 L .;t : . . U -2. :.a tat s
.1d:91No Oata i! 5el-:: !;.9;I+011No :sta 15.3;I+0 tNo Oata 15.!*E-031 ,1 e913 s
in .; 15 set. il 2;I: : .::I) 19 15E: !No :Ata !No Osti 1 Sb ;;al6.6sE-00li.;tt d1 12.65E+0011.6;E 0: Iso Oata 15.MI+0011.9:I-: 1 16 -
APA*&1 0l'.03 f Rev. .V. * , j Q y? S~/119 4.c n,,
i TAB!.! 1 (Cer.tinued)
N ;37!:N 0051 J: TE'?" TACT:R ;Ag) TC R 4 0.7 A I ! :'
(trement; per U,tt/m1'
} l l l l~ l l 1 ictal }
te, i 3 t .1.1.1 J INucildel 9me I tiver i _9edy i Thytetd I rier,y i 13b 1*3 14.28t+00le.75E 02 11.0:I+0016.35E 03 INo Data 13.30E*0014.71t+01l
{Te 1*3!!!:.37t+0319. 30E+02 13. lee +0:lf .7:E+0: 11.04t+0elNo Data (1.02E+061 ITe 127!!!6.471+03 ): .3:I+03 l' .90E+0:ll .66E+03 12. 63E+041No Oata 12.17t+0al lTe 1 7 li.0!E+02l3.*8E*01 12.
- 8E+0117.8 0E+01 l .:9 E+0 lNo Cat a 16.3 *t+031 lie 1*9!111.10E+0414.11E+03 11. 74E+0313. 7tE+03 le. 60E+0alNo Oata II .3eE+0al ITe 129 13.01E+0111.1;E*01 17.33E+0012.31t+01 11.:6E+0:lNo Cata 12.27E-01l ITe 131:1l1.66t+0318.09E-02 16.75t+0:11. lt-03 16.21t*031No Osta ll.03t+0el ITe 131 11.59E+0117.181-00 ll 96E+00ll .15E+01 lo. *3E*011No Data ;2.6*t*?01 ITe 10 6 2. 41I+0 311. 3 6 t +0 3 11. 47E+ 3 311. 711+03 11.10E* 0a lNo st a 17. 3 8 E+ ;4 '
!! 130 it.71E*0116.01E+01 13.16E+0116.79E+03 11. St+0:lNo :sta 16. tit Mi l! 131 11.a9t+0:! .1.E*0: 11.::E+0:17.00E+0a 13.66E+0:lNo Data 13.6;I+011
!! 132 II.29t*00ll.93E+01 16.5:I*0016.3:E+0: 13.11E+01lNo Oata 13,6eE+001 11 133 I) .10!*0118. 6!t+01 12. 70E+01 t l . 30E*0a 11. 3 31-0* l No Da ta 17. 7 7E+011 li 13a 13.811-001'. 03E-01 l3,70E+00ll.79E+0: l1.6-I*0'INo Osta 19.01E 031 11 133 11 39E-0114.16E*01 11.SeE+0112.7!E+03 16.t 6 , O t1% Cata (a.70E+011 lCs 13a !: 9sE*031*.09E-03 13.8 E*03tNo Oats 12.09t*0)l7.6:E-Ca:1.*et*!al ICs .36 13.1:I-0;ll . 3f +03 I B. ltE+04 lNo Data lo 63E+0419.39E-??!!.e0I+?al iCn 137 13.1:1-0313.::t-03 13.4:E*03lNo Oata13. 11.77t+03!3.19E-04:
tee *0:13.79t-01; .20E*:Jl1.011-2 1 lCs 138 i: tee +;:13.2:E**2 12.39E-021No Data 134 139 19.:$E 01l6.6:I Ce 10.7:1 0:lNo Data 16.19 E 0a l 3. ?it Ca l l . 63 E-001 lla la0 11.9et+0:12. eat 01 11.07t+011No Data ll.31E 0:1;.att 01! .00E* :)
134141 te.30E 0113.-0E 0 11.5'E 0:lNo Data 13.let 0all.93E 0-i;.1:1 0 101 11a 1 2 10.0-E 0112.09E 04 11.:tt 3:lNo Oata ll.!!E 0 ell.19E*0ei l1.4 1 0 11.301 0117.33E 02 11.99E 0:lNo Dat a (No Oata INo Osta 13.32t+;31 ile le: 17.i3I 0313.att 03 14.46E 04lNo Osta INo Oats INo :sta l'.3-E 011 10e let 12.:at 0:ll.31E 01 it.7*E 03lNo Osta 17.03E 03;No Data 13,78!-011 1Ca 143 13.94L 0312.9;E+00 13.23E OelNo Oata (1.28E 038'o Osta 11.09E-:: 1 1Co lee 11.1?I*00la.86t 01 16. 6E 02lNo Data 10.49E 01(No Cata 13.94!*::l IP 1 3 13.30E 0110.21E 01 I:.*3E 0:lSo rata 11.:7E 013o Osta 10.eII-331 INd le" 13.76I 011e.35E 01 10.601 0*lSo tats I: 5-t 01 No Osta 12.:9t+031 l
I!v 134 13 67I1 1e.3:10 !).21E0 INo Osta 10.16El iNo Oata 13.**E3
!Mf 111 13.99E*;*ll.9et-01 l'. 80E 0:lNo Oasa le.17E *lNo Oata i:.21I-C:t lV 187 );.9ft-;;12.e!!+M 15.6+E 011No Osta 15o Oat a i No Osta : 5.0 91-:.1 iNp ;29 I*.6-t-0:l: 1:E 03 l1.3-t 031No Data 18.*:E*;; Ao Osta 13.7e!- 21 17 -
APA-2Z-01003
( Rev. y',2.
) y,.nj
- 3.i.01 TABLE 2 BICACCUMULATICl4 FACTCR (Erg ) USED IN THE ABSENCE OF 5
- TE-SFECIF!C CATA" (ccifka) re ucci / lit e r )
BF i
Element Fish (Freshwater) ,
H 9.0 E - 01 Be 2.0 E + 00 C 4.6 E + 03 Na 1.0 E + O2 P 1.0 E + 05 Cr 2.0 E + O2 Mn 4.0 E + O2 Fe 1.0 E + O2 Co 5.0 E + 01 Ni 1.0 E + O2 Cu 5.0 E + 01 Zn 2.0 E + 03 Br 4.2 E + O2 Rb 2.0 E + 03 Sr 3.0 E + 01 Y 2.5 E + 01 Zr 3.3 E + 00 Nb 2.0 E + 04 Mo 1.0 E + 01
) Tc 1.5 E + 01 Ru 1.0 E + 01 Rh 1.0 E + 01 Cd 2.0 E + O2 Sn 3.0 E + 03 Sb 1.0 E + 00 Te 4.0 E + O2 I 1.5 E + 01 Ca 2.0 E + 03 Ba 4.0 E + 00 La 2.5 E + 01 Ce 1.0 E + CO Pr 2.5 E + 01 Nd 2.5 E + 01 Eu 2.5 E + 01 Ef 3.3 E + 00 W 1.2 E + 03 Np 1.0 E + 01 (a). Values fr:m Regulatory Guide 1.109, Rev 1, Table A-1 ar.d References 11.14 4 ar.d 11.'.4.3.
I I
is -
I
l APA-Z"-01003 I Rev X'7. n' /. 91 C),b
..m
)
2.6 LIQUID RADWASTE TREATME!1T SYSTEM 4160 2.o.1 EEC Saction 9.5.1.1 41651 The LIQUID FADWASTE TREATME11T SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
I e
I I
l
- 19 -
)
i l
1
APA-22-01003 p,(
Rev. P .2 43 -//
r" 2.6.2 CPERASILITY Of The LICUID RADWASTE TREATMENT f- SYSTEM-The LIQUID RADWASTE TREATMENT SYSTEM is capable of varying treatment, depending on waste type and product desired. It is capable of concentrating, gas stripping, and distillation of liquid wastes through the use of the evaporator system. The demineralization system is capable of removing radioactive ions from solutions to be reused as makeup water. Filtration is performed on certain liquid wastes and it may, in some cases, be the only required treatment prior to release. The system has the ability to absorb halides through the use of charcoal filters prior to their release.
The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases of radioactive materials in liquid effluents will be kept "As Low As i Reasonably Achievable" (ALARA). !
The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for i use when liquids require treatment prior to their release to the environment. OPERABILITY is demonstrated through compliance with Sections-9.3.1.1 and 9.4.1.1.
Projected doses due to liquid releases to UNRESTRICTED AREAS.-are determined each 31 days by i dividing the cummulative annual total by the number of elapsed monthe. ;
0 0
.,_ _. ~ u. _ , _ _ _ _ . . _ . . . . _ . _ . _ _ . . _ . _ _ _ _ . _ _
AFA-ZZ-01003 f Rev. X 5 <] *,1
<t i q; l
3 2902 3.0 CASECUS EFFLUENTS 41842 3.1 REC Secticn 9.2.1.1 4160 The radioactive gasecus effluent monitoring instrumentatien channels shall be OPERAELE with their Alarm / Trip Setpoints set to ensure that the limits of Section 9.6.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be adjusted to the values determined in accordance with the methodology and parameters in the CDCM.
41853 3.2 REC Section 9.6.1.1 4160 The deso rate due to radioactive materials released in gaseous effluents frem the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For Iodine - 131 and 133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr. to any organ, from the inhalation pathway only.
3.3 Gaaecus Effluent Monitors Noble gas activity monitors are present on the containment building ventilation system, plant unit ventilation system, and radwaste building ventilation system.
The alarm / trip (41 arm & trip) setpoint for any gaseous effluent radiation menitor is determined based on the instantaneous noble gas total bcdy and skin dose rate limits of Section 9.6.1.1, at the SITE SOUNDARY location with the highest annual average X/Q value. (Figure 5.13)
APA-ZZ-01003 key . X,2 g,6 p, ,,, ,
y Each monitor channel is provided with a two level system which provides sequential alarme on increasing radioactivity levels. These sotpoints are designated as alert.setpoints end alarm / trip j setpoints. (Ref. 11.6.3) j The radiation monitor alarm / trip setpoints for i each release point are based on the radioactive l noble gases in gaseous effluents. It i s not j considered practicable to apply instantaneous i alarm / trip setpoints to integrating radiation monitors sensitive to radiciodines, radioactive materials in particulate form and radionuclides other than noble gases. Conservative assumptions
. may-be necessary in establishing setpoints to account for system variables, such as the measurement system efficiency and detection capabilities-during normal, anticipated, and unusual operating conditions, the variability in release flow and principal radionuclides, and the time lag between alarm / trip action and~the final isolation of the radioactive effluent. (Ref.
11.8.5.) Table 9.2-B provides the instrument surveillance requirements,.cuch as calibration, source checking, functional testing, and. channel y checking.
3.3.1 Continuous Release Caseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are -( Re f .
11.6.8, 11.6.9): ,
Monitor I.D. Description GT-RE Unit V-ant CH-RE-10 Radwaste Eu11 ding Vent Each of the above continuously monitors gaseous
> radioactivity concentrations downstream of the:
last foint of potential influent, and therefore measu.ms effluents and not inplant concentrations.
22 -
h T rw=- a!9m g- g sue- A -ns o w- 4 m, y-y y y y y "r=g.yity- w-we4y v%ar"wa-p'-- -
e-Kwe-y'8"w-w-'7
- g% Qi y , 9-t.-i 9. - -y wi-
APA-22-01003 Rev. J' .R d tb g;f 4 I i
Ine Unit Vent monitor continuously monitors the effluent frem the unit vent for gaseous radioactivity. The Unit Vent, via ventilaticn exhaust systems, continuously purges varicus tanks and sumps normally containing low-level radioactive aerated liquads that can potentially generate airborne activity.
The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the access centrol area, the containment purge, and the condenser air discharge.
The Unit Vent monitor provides alarm Lanctions only, and does not terminate releases from the Unit Vent.
The Radwaste Building Ventilation effluent monitor continuously monitors for gasecus radioactivity in the effluent duct downstream of the exhaust filter and fans. The flow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path for the vaste gas decay tank release line. These components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.
This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm.
- 23 -
- - - - - - - _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - ~ ~ " - - ~ - - ~-- .m__ _
AFA-Z2-01003 Rev. J .R (p g f,, ,,7 r The centinuous gaseous effluent monitor setpoints are established using the meth:dology described in Section 3.4. Since thcre are two centinueur gaseour effluent release points, a fraction of the total dose rate limitNeglecting (DRL) willthe bebatch allocated to each release point.
releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwaste Building Vent monitor has been allocated 0.3 DRL. These allocation factors may be changed as required to support plant operational needs, but Therefore, shall not bea allovted to exceed unity (i.e. 1.0).
particular monitor reaching the setpoint would not necetsarily mean the dose rate limit at the SITE BOUNDARY is C+.ing exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rato limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems.
3.3.2 Batch Release Casecus Monitors The radiation monitors associated with batch release gaseous effluents are (Fef. 11.6.9, 11.6.10, 11.6.11):
Description Monitor I.D.
GT-RE-22 Containment Furge System GT-RE-33
\
GH-RE-10 Radwaste Duilding Vent The Containment Furge system monitors continuously monitor the containment purge exhaust duct during purge cperations for gaseous radioactivity. The primary purpose of these monitors ts to isolate the contair. ment purge system on high gaseous activity via the ESFAS.
The sample points are located outside the containment between the containne.nt 1sciation l
1
- - - - - - - -- _-_ _ _ - _ _ __ _ _ _ _ _ ___ _ ~ ~ ~ ' ~ ~ ' " - ~ - - + . _ , , _ _
APA-ZZ-01003 Rev. P JL y-t.1I7;0 f ,\
dampers and the containment purge filter adsorber unit.
The Radwaste Building Vent monitor was previously l described in Section 3.3.1. !
Setpoints for the batch gaseous effluent monitors ;
are calculated using the methodology described in
- Section 3.4. :
A pre-release isotopic analysis is performed for !
each batch release to determine the identity and quantity of the principal radionuclides. The i alarm / trip setpoint(s) is adjusted accoruingly to -l
. ensure-that the-limits of Section 9.6.1.1 are not ,
exceeded. :
3.4- Determination of Caseous Effluent Monitor t setpoints !
i The alarm / trip setpoint for gaseous effluent monitors is determined based on the lesser of the .!
total body dose rate and skin dose rate, as ,
calculated for the SITE BOUNDARY. ;
i During core alterations, the setpoint for the >
b Containment Purge Monitors, CT-RE-22 and CT-RE-33 !
is set at a value of _ less than or equal to SE-3 .
pCi/ce, as required by Technical Specification , 4.9.4.2. The actual setpoint value will be '
reduced according to the Instrument Loop Uncertainty-Estimate (ILUE). This value will also be-utilized in the' event-that there is no i detectable. noble gas activity in the containment atmosphere sample analyzed in accordance with :
Section 9.6.1.1. The full derivation of this value is discussed in reference 11.14.6. .
i 1
i I
d-
.i i
e
- - , . - ,_g, y ., , , . , . .,,g ,m.p,
APA-22-01003 Rev.-1' 1 7,C r./.9 L
~~
3.4.1 Total Body Dose Rate Setpoint Calculations To ensure that the linits cf Section 9.G.1.1 are met, the alarm / trip cetpoint cased en the total body done rate is calculated according to:
S b<Dtb R b F ,F, (3.1)
Where:
S b
= the alarm / trip setpoint based on the total body dose rate (vC1/cc ) .
D tb = Section 9.6.1.1 limit of 500 mrem /yr, conservatively interpreted as a continuous release over a one year period.
F,= the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement.
(For example, F, = 0.5 correspends to a 100% variation.) Default value is F, =
1.0.
the allocation factor which will modify the F,=
required dilution f actor such that simultaneous gaseous releases may be made without exceeding the limits of Section 9.6.1.1. The default value is 1/n, where n is the number of pathways planned for
,pelease.
- ~ - - - . - - . _ - - . - _ . _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
APA-ZZ-01003 Rev. YA CJ f b~~ t 41
!- I R tb = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (uCi/cc) per (mrem /yr) to the total body, decermined according to R tb = C + { (X/Q). Ii K Qg) i (3.2)
Where C= monitor reading of a noble gas monitor corresponding to the sample radionuclide concentrations for t*.e batch to be released. Concentrations are determined in accordance with ?; ole 9,6-A. The mixture of radionuellaes determined via greb sampling of the affluent stream or source
. As correlated to a calibration The factor monitorto determine monitor response.
response is based on concentrations, not j release rate, and is in units of (yci/cc).
57Q = the highest calculated annual average relative concentration for any area at or beyond the 8
SITE BOUNDARY in (sec/m ). Refer to Tables-9, 10, and 12. ,
Kg= the total body dose factor due to gamma l emissions for each identified noble gas '
radionuclide, in (mrem /yr) per (vCi/m').
(Table 3)
Q.= rate of release of noble gas radionuclide, g
1, in (pCi/sec).
...u.. .- - ..- - . .. ._;..-.-_.-.-.-......-.--..-._.,-
i APA-02 01003 ;
- Rev. J',1 s'- t v c),f em)
'~
Q 1 in calculated as the product of the ;
ventilation path design flow rate and the f measured activity of the effluent stream an i determined by grab sampling. Flow rates ,
for the ventilation pathways can be found in references 11.6.18, 11.6.19, 11.6.20, ,
and 11.6.21.
3.4.2 skin Dose Rate setpoint calculation j To ensure that the limits of Section 9.6.1.1 are met, the alarm / trip setpoint based on the skin dose rate is calculated according tot i
l i
S,5 D,R,Eg t, (3.3) i Where F, and F, are as previously defined in Section j- 3.4.1.1.
S,= the alarm / trip setpoint based on the skin
-i dose rate.
Section 9.6.1.1 limit of 3000 mrem /yr, D, a conservatively interpreted as_a continuous ,
release over a one year period.
a i
I APA-22-01003 f Rev. 1,2 (ff : 1s
.m) R u factor used to convert dose rate to the a
effluent concentration as measured by tha effluent monitor, in (uCi/cc ) per (mrem /yr) to the skin, datormined according to:
R, a C+ [(fM) I (Lg + 1.1Mg ) Q) g (3.4) i Where Lg a the skin dose factor due to beta emissions for each identified noble gas radionuclide, 3
in (mrem /yr) per (uCi/m ), (Table 3) 1.1 = conversion factor: 1 mrad air dose = 1.1 mrem skin dose.
the air dose factor due to gamma emissions
) Mg =
for each identified noble gas radionuclide, 3
in (mrad /yr) per (uC1/m ). (Table 3)
C, (X/Q) and Q g are as previously defined.
29 - )
AFA-ZC-01003 Rev. ,l'2. cgf y. , ,yj 3,4,3 Gasecus Effluent Monitors Setteint Determination The results of Equatien (3.1) and ETaaticn (3.3) are compared. The setpoint is then selected as the lesser of the two values.
\
h 9
e
- 30 -
k L
?
94m
+-.
M -
8 s
-a O e =
hk
~. b w
4 b (d M M g M # a .9 M M N M # M M (p 63
= =a du 86 w (g (oe b C O C C C 3 3.3+3. +
++++++++ OO + O+C C++ O wwwww,.wwWwwwww 4h ***
G es# ** b C ** O M M @ M F* COD 4hO Vil @WEh C. P. O. O. m. O. C. **. J. O. M. #. N. P C. N.
wt cd s fg am me en fd .= ** an ** .e. N (q = M ei Mr t
. f
- h N W - *m O .-
bl a C
- l "5 .
w s Q '
C N D.
> - E C L e> M oo m s tv N t-J M M M M M w
,e b V *b $ QQDQ
- ++++++++++++* DOOOOOOCOD
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g bJ W A, M M M M 3 m N Py P4 N M E M M r
- e coccee e cae: 5" e e s ++++++++++++++l W W hel hmJ == he, and w ew W tse has es 6su .
4N WB $ 7
- 9 C*L Q .J 4 @ r M P= a m e @ c= c tw M o o e-X a .:
W c 6 e r. M. N. M. Q. s. e t'= 7. C. *. C. tv. =. c.
4 *= *= m f4 = P= # > M % ** = a fd E
- h O E A N 6 .
C o S b
== 0,1 L
C d E v C; ~
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- g
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- v w n D s O 6
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VO CCCCCOCOC0OOCOC wt 6
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a++++++++++++++d kes ei l.4 to was and he e emi er W nur 'em 6 e 4
Q e 'd.
C u
== w = 4 X QO ".N9.-D. N2P. c. c Oc.".
. 7e N = N MC. 4.wf J. C.
8'=
.N*g "b"" .Q:.@ .
0A h P= = = A *= = * @ f, N M ** ** Q 4 aj- N E
e 3
3 "O E -3 w
9 G9
& =
V -
~ 55 E
= Eg - M M .* r u c U M o' O N C D O M M M M M M ("* ** $*
3 C C C C C C O = * *= = a- - == 4 O a i e e e a e e I i e a e s a C 646 66 6 *J *; O O Q *J g 6
-= 14%%4%4XX(%%XX( e
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4 w C
AFA-20-OlCO3 Rev. %c9- cp b g. , .9, li, I 3.4.4 Summary, Gaseous Effluen+. Monitors Setpoint betermination The gasecus effluent monitors setpcints are calculated according to equations (3.1) and (3.3), as described in Section 3.4. However, it should be noted that a batch release will alter the flow rate characteristics at the Unit Vent and therefore the concentrat2on as sensed by the monitor. For example, in the case of a mini-purge, the setpoint for the Unit Vent monitor must be re-calculated to include both the continuous and batch sources.
3.5 Cal-ulation of Dose Fron Gasecus Effluents Dose rate calculations are performed for gaseous effluents to ensure compliance with Section 9.6.1.1.
3.5.1 Calculation of Dose Rate The following methodology is applicable to the location (SITE BOUNDARY or beyond) characterized by the values of the parameter (X/Q) which results in the maximum total body or skin dose rate. In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values. (Ref. 11.8.6)
The factors K g , L, g
and M g relate the radionuclid9 airborne concentrations to various dose rates, assuming a semi-infinite cloud model, and are tabulated in Table 3.
3.5.1.1 Noble Cases The release ratt limit for noble gases is determined according to the following general relationships (Ref, 11.8.6):
- 32 -
l APA-ZZ-01003 I Rev. Y3 p .9 f f](
)
D t3 = I [x 1 ((x/Q)Q 1)) s 500 mrem /yr (3.5) i
)
D, = I {(L 1 + 1.1 Mg)((X/Q)Q 1)] 5 3000 mrem /yr (3.6) i Where:
D = Total body dose rate, conservatively tb averaged over a period of one year.
K = Total body dose factor due to gamma 1
emissions for each identified noble gas 3
radionuclide, in (mrem /yr) per (pCi/m ).
(Table 3)
(X/Q) = The highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY. Refer to Tables 9, 10, and 12 The release rate of noble gas Q1=
radionuclides, i, in gaseous mIfluents, trom all vent releases in (pCi/sec).
Q = is calculated as the product of the ventilation path design flow rate and the measured activity of the effluent stream as determined by grab sampling. Flow rates for the ventilation pathways can be found in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21.
D -
Skin d:se rate, cenaervatively averaged s
over a period of one year.
AFA-ZZ-01003 Rev. y )
f)b 3-t 77 L
3
= Skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem /yr) per ( wCi/m ' ) (Table 3).
1.1 = Unf*' conversion factor; 1 mrad air dose =
1.1 nirem skin dose.
My = Air dose factor ?.ne to gamma emissions for each identified nob:e gas radionuclide, in (mrad /yr) per (uci/m') (Table 3).
3.5.1.2 Radionuclides Other Than Noble Cases The release rate limit for Iodine-111 and-133, for tritium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 11.8.7):
D =IP g((X/Q)Qg ] 3 1500 mren/yr (3.7) i Where:
D, = Doss rate to any critical organ, in (mrem /yr). _
P = Dose parameter for radionuclides other than 3
noble gases for the inhalation pathway for the child, based on the critical organ, in
( m r e m,'yr ) per (pCi/m'). (Table 4)
- 'ie release rate of radionuclide, 1, in Q=
gaseous effluents, from all vent releases, in (uC1/sec) . Q g is calculated as the product of the ventilation path design flow rate and the measured activity of the ,
effluent stream as determined by grab sampling. Flow rates for the ventilation pathways can be f:ur.d in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21.
~ ____---
APA-ZZ-01003 I Rev. yJ
)
7-19/
)
~
(X/Q) is as previcasly defined.
The dose parameter (? 1) includez the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age. Therefore the child age group has been selected as the limiting age group.
For the child exposure, separate values of P1 are tabulated in Table 4 for the inhalation pathway.
These values were calculated according to (Ref.
11.8.3):
1 E
g
= K' (ER) DFA g (3.8)
Where:
K' = Units conversion factor: luci = lE06 poi, BR= The breathing rate of the maximum exposed child age group, 3700 m'/yr. (Pegulatory Guide 1.109, Table E-5).
DFA = The maximum organ inhalation dose factor 3
for the child age group for the ith radionuclide, in (mrem /pCi). The total body is considered as an organ in the selection of DFA 1 (Ref. 11.11.5 cnd 11.14.4)
Note: All radiciodines are assumed to be released in elemental form. (Ref.11.8.7) u
APA-ZZ-01003 Rev. Y ch s
(jy b 7-/.9l
'~
TABLE 4 DOSE PARA >!ETER (P ) FOR RADIONUCLIDES OTHER THAS SOBLE GASES" Inhalatica Path.'ay (mrem /yr) per (uC1/m ) 3 l l l l Total l l l l l lNuclidel Bone ! Ltver i Body i Thyroid 1 Kidnev I Lung i GI-LLI l 11.12E3 'll.12E3 11.12E3 {1,12E3 11.12E3 l1.12E3 l l H-3 l ND 1 Be-7 18.47E2 l 1. R E 3 19.25E2 i ND 1 ND 16.4SE4 12.55E3 l 16.73E3 16.73E3 16.73E3 16.73E3 16,73E3 l l C-14 13.59E4 16.73E3 l Na-24 11.61E4 11.61E4 l1.61E4 11.61E4 11.61E4 11.61E4 ll.61E4 l 19.SSE4 ND 1 ND l ND 14.22E4 l l P-32 12.60E6 11.14E5 l 1 ND 11.54E2 IS.55El 12.43E1 11.70E4 11.08E3 {
l Cr-51 1 ND 11,5SE6 l Mn-54 l ND l4.29E4 19.51E3 l SD ll.00E4 12.29E4 l l Mn-56 l ND ll.66E0 13.12E-1 l SD ll.67E0 11.31E4 11.23E5 l l Fe-55 14.74Ea 12.52E4 17.72E3 I ND l ND ll.11ES (2.87E3 l l Fe-59 l2.07E4 13.34E4 11.67E4 l SD l SD 11.27E6 17.07E4 l l Co-57 1 SD 19.03E2 l1.07E3 l SD l ND 15.07E5 ll.32E4 l 13.16E3 ND ST 11.11E6 13.44E4 l i Co-58 l ST 11.77E3 1 l l ND l Co-60 l SD l1.31E4 12.26E4 i ND l7.07E6 19.26E4 1 1 Ni-63 18,21E5 14.63E4 12.SOE4 l ND l ND (2.75E5 (6.33E3 [
l Si-65 12.99E0 12.96E-1 11.64E-1 l SD l ND 18.18E3 18.40E4 l l Cu-64 l SD ll 95E0 11.07E0 l SD l6.03E0 l9.5SE3 l3.67E4 l l Zn-65 14.26E4 11.13E5 17.03E4 l SD l7.14E4 19.95ES ll.63E4 l l Zn-69 16.70E-2 19.66E-2 18.92E-3 l SD 15.85E-2 11.42E3 11.02E4 {
l Br-82 1 ND l ND 12.09E4 l ND l ND l ND l ND l l ND 0 l Br-83 l ND 1 ND la.74E2 l SD l SD l l 0
l Br-84 i ND l ND 15.4SE2 i ND l SD l ND l l 0
l Br-S5 l ND l ND 12.53E1 l ND l ND l ND ! l l Rb-86, 1 ND ll,98E5 11.14E5 l SD l ND 1 ND 17.99E3 1 1 Rb*SS l SD 15.62E2 l3.66E2 l ND l SD l ND ll.72E1 l l Rb-89 l ND 13.45E2 12.90E2 l SD. ( ND l SD 11.89E0 i l Sr-B9 15.99E5 1 ST 11.72E4 1 ND l ND l2.16E6 11.67E5 l l Sr-90 l1.01ES l ND 16.44E6 l SD l ND 11.4SE7 13.43E5 l l Sr-91 ll.21E2 l ST 14.59E0 l ST l ST 15.33E4 11.74E3 1 1 Sr-92 11.31El l ND l5.25E-1 l ND l SD 12.4CE4 12.42E5 l
!1.11E2 SD SD 12.62E5 12.6BE5 1
' APA-Z2-01003 Rev. l' A g / S~/-f/
f TABLE 4 (Cont'd.)
DOSE FARA'1ETEI! (?g) FOR EADICNC2LI2ES OTiir: ~"iAN SOBLE GASE3" Inhalation Pathway (crem/yr) per (yCi/m*)
~
l l I i Total ! l l l \
lNuclidel Bene ! Liver 1 Body l Thyroid i ILd,ey I Lung i GI-LLI l ll.84E-2 l ND 1 ND 12.81E3 l1.72E3 l l Y-91m l5.07E-1 1 ND l Y-91 19.14E5 i ND 12.44E4 l ND l ND 12.63E6 l1.84E5 l ND 12.39E4 12.39E3 l l Y-92 l2.04E1 l ND 15.81E-1 1 ND l ND l7.44E4 (3.89E5 l l Y-93 II.86E2 l ND 15.11E0 l ND l l Zr-05 11.90E5 14.18E4 13.70E4 l ND 15 06E4 l2.23E6 16.11E4 l l Zr-97 l1.88E2 12.72E1 11.60E1 i ND 13.AE1 11.13E5 13.51ES I l Nb-95 12.33E4 19,18E3 16.55E3 i ND l8.62E3 16.14E5 13.70E4 l 14.26El l ND 13.9?E2 11.35ES l1.27E5 l l Mo-99 ) ND 11.72E2 15.07E-2 19,51E2 15.77E-2 l ND 14.81E3 l l Tc-99 mil.78E-3 13.48E-3 l Tc-10118.10E-3 18.51E-5 11.06E-3 i ND ll.45E-3 15.85E2 11.63E1 l l1.0 E3 ND l7.03E3 16.62E5 14.48E4 l l Ru-10312.79E3 l ND l l9.95E4 l Ru-10511.53E0 i ND 15.55E-1 1 NT ll 34E0 11.59E4 l l Ru-10611.36ES l ND l1.69E4 l ND l1.84E5 l1.43E7 14.29E5 l lAg-110 mil.69E4 11.14E4 19.14E3 l ND (2.12E4 l5.4SE6 11.00E5 l l Cd-1091 ND l3.48E5 l. 59E4 1 SD [4.96E5 11.05E6 l2.78E4 l lS.62E3 12.33E3 l ND 11.46E6 12.26ES l l Sn-113l1.13E5 13.12E3 12.00E4 l1.26E2 i ND l3.24E6 11. 6!.E 5 )
] Sb-124l5.74E4 17.40E2 14.03E4 l Sb-125]9.84E4 17.59E2 12.07E4 19.10E1 l ND 12.32E6 l lTe-125ml6.73E3 12.33E3 19.14E2 l1.92E3 l ND 14.77E5 13.38E4 l 18.55E3 l3.02E3 16.07E3 16.36E4 11.48E6 17.14E4 l lTe-127ml2.49E4 19.51E-1 16.11E-1 11.96E0 17.07E0 11.00E6 15.62E4 l lTe-127 12.77E0 lTe-129 mil.92E4 16.55E3 13.04E3 16.33E3 15.03E4 11.76E6 l1.82E5 l 12.57E 1 12.93E3 12,55E4 [
lTe-129 19.77E 2 13.50E-2 12.38E-2 17.14E-2 15.07El l9.77El l4.00E2 12.06ES 13.0SE5 l lTe-131 mil.34E2 15.92E1 lTe-131 12.17E,2 18.44E 3 16.59E-3 11.70E-2 15.88E-2 12.05E3 11.33E3 l l2.63E2 13.17E2 l1.77E3 13.77E5 11.3SE5 l lTe-132 14.81E2 12.72E2 11-130 18.13E3 l1.64E4 1 S . I.4E 3 l1.85E6 12.45E4 l ND 15.11E3 l 12.73E4 l1.62E7 l7.S8E4 NT 12.84E3 l lI-131 l4.S154 l4.SIE4 l 12.12)3 14.07E3 11,3SE3 11.94E5 16.25E3 l 'JD 13.20E3 !11-132 j5.43E3 11.66E4 12.02E4 17 70E3 13,33E6 ;3.3dE4 i ND i (1-133 II-134 11.17E3 12.16E3 19.95E2 15.07E4 13.30E3 l ND l9.55E2 l lI-135 la.92E3 Id.73E3 l 14E3 l7.92E5 11.34E4 l ND 14.44E3 l
umisquiusummuusi um -liim gis APA-ZZ-01003 Rev. /)
b-I il
. . , TABLE 4 (Cent'd.)
\
DCSE PARAMETER 1
(? ) FOR RADICSUCLI2ES CTMER THAN SOBEE GASES
- Inhslation Pathway (mree/yr) per (uCi/m ) 8 l l l l Tctal l l l l l lNucliden Bone I Liver ! Body 1 Thyroid ! Kidney 1 Lung l GI-LLI i lCs-134 l6.51E3 11.01E6 l2.25E5 i ND 13.03E5 11.21E3 13.85E3 l lCs-136 l6.51E4 11.71E3 11.16E3 l ND 19.55E4 11.45E4 14.18E3 l lCs-137 19.07E3 l8.25E3 11.2SE3 l SD 12.82E5 11.04E5 l3.62E3 l l
lCs-138 16.33E2 18.40E2 l5.55E2 i SD l6.22E2 16.81El 12.7CE: l lBa-139 l1.84E0 19.84E-4 15.37E 2 l ND ls.62E-4 15.77E3 l5.77E4 !
lBa-140 17.40E4 16.43E1 14.33E3 l SD 12.11El 11.74E6 11.02E5 1 13a-141 l2.19E-1 l1.09E-4 16.36E-3 i SD 19.47E-5 l2.92E3 12.75E2 l lBa-142 l5.00E-2 13.60E-5 12.79E-3 1 ND 12.91E-5 l1.64E3 12.74E0 l lLa-140 16.44E2 12.25E2 17.55El l ND l ND l1.83E5 12.26E5 l lLa-142 11.30E0 14.11E-1 11.29E-1 1 ND l ND 18.70E3 l7.39E4 I (Ce-141 l3.92E4 11.95E4 12.90E3 l SD 18.53E3 l3.44E5 15.66E4 l lCe-143 13.66E2 l1.99E2 l2.8 El l SD l8.36El 11.15E5 11.27ES l lCe-144 16.77E6 12.12E6 l3.61E3 l SD 11.17E6 11.20E7 13.39E5 l lPr-143 11.83E4 15.53E3 19.14E2 l SD 13.00E3 14.33E5 19.73E4 l lPr-144 15.96E-2 11.53E 2 13.00E-3 1 ND 19.77E-3 11.37E3 11.97E2 I INd-147 11.0SE4 18.73E3 16.81E2 l SD 14.81E3 13.2SE5 IS.21E4 l lEu-154 11.01E7 19.21E5 13.40E5 i ND l4.03E6 16.14E6 l1.10E5 l lHf-131 12.7SE4 11.01E3 11.2SE4 l SD l2.05E4 11.06E6 16.62E4 l IV-187 11.63E1 l9.66E0 14.33E0 l SD l SD 14.11E4 19.1CE4 l lSp-239 l4.66E2 l3.34E1 12.35El l SD 19.73E1 15.51E4 16.40E4 I (a) The child age group; refer to reference 11.14.5.
I l
_ . . _ _ ___ ..._ m .__4 . _ _ . - _ ~ _ . . _ . _ . _ _ _ _ . . . _ _ . _ . _ .
b s
- 1 APA-ZZ-01003 Rev. y JL-S-/ -9 I pf 3'.5.2 Dose Duo To_ caseous Effluents .
413 5 3 3.5.2.1 RIC Seet,1cn 9.7.1.1
- 4160 The air dose due to noble gases released in gaseous effluents, to areas at and beyond the SITE BOUNDARY shall be limited to the followingi
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and >
less than or equal to 10 mrad for-beta radiation and,
- b. During any calendar year: Less than or equal to.10 mrad for gamma radiation and
^ less than or equal to 20 mrad for beta radiation.
i e
i 3
m O
- 39 -
m, I
r env * * * " y r - r * - '
- s'* r-er= o-- w w+v- - - - = +=*- - - - ~-- - -- - - - = - - - --
APA-ZZ-01003 j Rev..P J
)lk ri-i4I
. . -s.
I 3.5.2.1.1 Noble Cases The air dose at the SITE BOUNDARY due to noble gases released from the site is calculated according to the following methodology (Ref.
11.8.9):
1 During any calendar quarter, for garna radiation:
D = 3.17E-08 I (Mg ((X/Q) Q + (X/q) g g)) 55 mrad (3.9) 9 i
During any calendar quarter, for beta radiation:
+ (X/q) q 1)) $ 10 mrad (3.10)
D b = 3.17E-08 I [N3 ((X/Q) Q g i
During any calendar year, for gamma radiation:
= 3.17E-08 I [Mg ((.QQ) Q. + (X/q) qg )) 510 mrad (3.11)
I Dg i i
During any calendar year, for beta radiation:
Db
- 3'17E-08 1 IN i IlX/9) 9 1 + (X/q) g g)) 5 20 mrad (3.12) i
. .; c .
APA-CZ-01003 Rev, FA l);t .>' 141 1
vihere:
D = Air dose from gamma radiation due to noble gases released in gaseous effluent.
D b
= Air dose from beta radiation due to. noble gases released in gaseous effluents.
(X/q) = The relative concentration for areas at or beyond the SITE BOUNDARY for short-term releases (equal to or less than 500 hrs / year). Refer to Tables 9, 10, 11 and 12, q1
= The average release of noble gas radionuclides, i, in gaseous effluents from all vent releases for short-term releases (equal to or less than 500 hrs / year), in (vC1), Releases are cumulative over the calendar quarter or year, as appropriate.
N 1
= The air dose factor due to beta emissions for each identified noble gas radionuclide, 1, in (mrad /yr) per (vCi/m ) . (Table 3) 8 Qg = The average release of noble gas radionuclides, i, in gaseous effluents from all vent releases for long-term releases (greater than 500 hrs / year), in (pC1) ,
Releases are cumulativa over the calendar quarter or year, as appropriate, (X/Q) = The highest calculated annual average relative concentration for areas at or beyond the SITE SOUNDARY for long-term releases (greater thani500 hrs /yr). Refer to Tablec 9, 10, and 12.
3,17E-08 = The inverse of the number of seconds per year.
M is as previous'.y defined. (Refer to secti:n 3.4.1.2)
a.-
AFA-ZZ-01001 Rev. A';L S'-/1/ g., (
{ 41860 3.5.2.-2 REC Section 9.8.1.1 J - 4160 The dose to a MEMBER OF THE FUBLIC frem Iodine-131 and 133, tritium, and all-radionuclides in particulate form with half-lives greater than 8 days-in gaseous effluents releasec, to areas at and beyond the SITE BOUNDARY shall be limited to the following (Ref.
11.8.9):
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, -!
t
- b. During any calendar year Less than er equal to 15 mrem to any organ.
3.5.2.2.1 Radionuclides Other'Than Noble Cases The_ dose to a.MEMEER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, to areas at and beyond the SITE BOUNDARY, is calculated according to the
- following expressions:
Caring.any calendar quarter:
D = 3.17E-08 I R 3 (W Q 1 + w q1) $ 7.5 mrem (3.13) 3 i
- During any calendar year:
Dg - = 3.17E-08 I R g (W Q g + w g g) $ 15 mrem (3.14) 1 i
-Where:
D_=
g -Dose to a MEMBER-CE THE PUBLIC from radionuclides other than noble gases.
I l
42 -
~
i
'I 4
%
- w --- ~ . --- - -- - - - - _
_ _ . ~ . . . _.. . _ _ _ . _ . _ _ . _ . _ _ _ , _ _ . _ . . _ . . - _ _ _ _ . . _ _
APA-22-01003 Rev. 4*,2 ,
f}P J11.fj n
l Q = The releases of radiciodines, radioactive materialstin particulate form, and radionuclides other than noble gases, i, in gaseous effluents, for all long-term vent releases (greater than 500 hrs /yr), in
'(uci). Releases are-cumulative over the calendar quarter or year as appropriate.
q = -The releases of radioiodines, radioactive 1
materials in particulate form and radionuclides other than noble gases, 1, in gaseous effluents for all short-term vent releases (equal to or less than 500 hrs /yr), in (vci). Releases are cumulative over the calendar quarter.or year as appropriate.
Rg= The dose factor for each identified radionuclide, 1, in m 2(mrem /yr) per (vCi/sec) or (mrem /yr) per (uci/m'). (Table S)
W= The dispersion parameter for estimating the dose to an individual at the controlling
' location'for long-term releases (greater than 500 hrs /yr): ,
W= (X/Q) for the inhalation and tritium patnways, in(sec/m ). 8 W-= (D/Q) for the food and ground plane pathways, in(meters 2).
Refer to Tables 9, 10, and 12.
43 -
APA-ZZ-01003 Rev.-l'.2
]/ ca et w= The dispersion parameter for estimating the dose to an individual at the centrolling location for short-term releases (equal to or less than 500 hrs /yr).
w= (X/q) for the inhalation pathway, in(scc /m')
w= (D/q) for the food and ground plane pathway, in (meterc~2). Refer to Tables 9, 10, 11, and 12, 3.17 E-08 = The inverse of the number of seconds per year.
(D/Q) = the average relative deposition of the effluent at or beyond the SITE SOUNDARY, considering depletion of the plume during transport, for long term releases (greater than 500 hrs /yr), in (meters 2).
(D/q) = the relative deposition of the effluent at or beyond the SIIE SOUNDARY, considering depletion of the plume during transport, for short term releases (less than or equal to 500 hrs /yr), in (meters ~2).
I
'APA-ZZ-01003
? Rev. l'CZ l C)$ S-wn I ~ ~i - -
Note: For the direction sectors with existing pathways within 5 miles frem the site, the apprcpriate R g values are used. If no real pathway exists within 5 miles from the center of the building complex, the cow-milk R g value is used, and it is assumed that this pathway exists at the 4.5 to 5.0 mile distance in the limiting-case sector.
If the R g for an existing pathway within 5 miles is less than a cow-milk R 1 at 4.5 to 5.0 miles, then the value of the cow-milk R
1 at 4.5 to 5.0 miles is used. (Rev.
9.8.10.)
Although the annual average relative conce'ntration (X/Q) and the average relative deposition rate (D/Q) are generally considered to be at the approximate receptor location in lieu of-the SITE BOUNDARY for these calculations, it-is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value of (X/Q). (Ref, 11.8.9) The Total
. Body dose from ground plane deposition is added to the dose for each individual organ. (Ref.
11.11.3)
The cumulative critical organ doses for a
. monthly, quarterly or annual evaluation are based on the calculated dose contribution from each
.specified' time period occurring during the
. reporting period.
E
APA-ZZ-01003 Rev. r2 -
Il l
TABLE 5 "HILD PATH"4AY DOSE FACTCRS g (R ) FOR RADIONU2LIEES OTHER THAN NOBLE GASES
- Inhalation Pathway (mrem /yr) per (uC1/m')
i I I l Total l I l 1 1 INuclidel Bone l Liver 1 Bodv l Thyroid l Kidney l Lune I GI-LLI l l H-3 ) ND 11.12E3 11.12E3 11.12E3 l1.12E3 l1.12E3 11.12E3 l l Be-7 18.47E2 11.44E3 19.25E2 l ND l ND 16.48E4 12.55E3 l l C-14 13.59E4 16.73E3 16.73E3 16.73E3 l6.73E3 16.73E3 16.73E3 l l Na-24 11.61E4 11.61E4 11.61E4 11.61E4 11.61E4 l1.61E4 11.61E4 l 1 P-32 12.60E6 11.14E5 19.88E4 i ND 1 ND 1 ND 14.22E4 l 1 Cr-51 1 ND l ND ll.54E2 IS.55El 12.43E1 II.70E4 11.0SE3 l l tin-54 l ND la.29E4 19.51E3 l ND 11.00E4 11.5SE6 12.29E4 l l Hn-56 l ND 11.66E0 13.12E-1 1 ND l1.67E0 11.31E4 l1.23E5 l l Fe-55 14.74E4 ]2.52E4 17.72E3 i ND 1 ND l1.11E5 12.87E3 l l Fe-59 12.07E4 13.34E4 11.67E4 I hT l ND 11.27E6 l7.07E4 l l Co-57 l ND 19.03E2 11.07E3 l ND l SD 15.07E5 11.32E4 l l Co-58 i ND l1.77E3 13.16E3 l ND l ND 11.11E6 13.44E4 l 11,31E4 l2.26E4 l ND l NT 17.07E6 19,26E4 l 1 Co-60 l ND l2, 5E5 l Ni-63 18.21E5 14.63E4 12.80E4 1 SD l ND 16.33E3 l l Ni-65 12.99E0 12.96E-1 11.64E-1 l SD l NT 18.18E3 l8.40E4 l
[1,07E0 l ND 16.03E0 19.58E3 13.67E4 j l Cu-64 l ND l1.99E0 l Zn-65 l4.26E4 11.13E5 17.03E4 l ND 17.14E4 l9.95E5 11.63E4 l j
l Zn-69 16.70E-2 l9.66E-2 lS.92E-3 l ND 15.85E-2 l1.42E3 11.02E4 12.09E4 l ND l ND ND l 5B l j Br-82 1 ND 1 ND l l Br-83 1 ND l ND l4.74E2 l ND l ND 1 ND l 0 l l ND ND 0 l Br-84 l ND l ND 15.4SE2 l ND l l l l Br-85 l ND 1 SD 12.53E1 1 ND l ND l ND l 0 1 1 Rb-86 ) ND 11.96E5 11.14E5 l ND l ND l ND 17.99E3 l l Rb-88 l ND 15.62E2 13.66E2 l ND l ND 1 ND l1.72E1 l l Rb-B9 i ND l3.45E2 12.90E2 l SD l ND l ND ll.89E0 l l Sr-89 j5.99E5 ) ND ll.72E4 l ND l ND l2.16E6 11.67E5 l l Sr-90 11.01ES l ND 16.44E6 i ND 1 ND 11.48E7 13.43E5 l i Sr-3,l'.21E2 ! ND is.59E3 i ND 1 ND [5.33E4 ii.74E5 i l Sr-92 II.31El l ND 15.25E-1 1 ND l ND l 2 . .'.0 E4 12.42E5 l
} Y-90 la. lie 3 l St 11.11E2 l ND l NT l2.62E5 12.6SES l
APA-Z2-01003
'ev. 4 f2 7
) TABLE 5 (Cent'd.)
CHILD PATHWAY DOSE FACTCRS (R ) FOR RADIONUCLIDES OTHER THAS NOBLE GASES Inhalation Pathway (crem/yr) per (pCi/m')
I l l I Total l l l l 1
[Nuclidel Bone l Liver l Body 1 Thyroid 1 Kidney I Lung l GI-LLI l l Y-91m 15.07E-1 l ND 11.84E-2 l ND l ND [2.81E3 11.72E3 l 1 Y-91 19.14E5 1 ND l2.44E4 i SD l ND 12.63E6 11.84E5 I l Y-92 12.04E1 l ND 15.81E-1 l ND l ND 12.39E4 l2.39E5 l l Y-93 11.86E2 l ND 15.11E0 l ND l ND l7.44E4 13.89E5 l l Zr-95 11.90E5 14.18E4 l3.70E4 l SD 15.96E4 l2.23E6 16.11E4 l l Zr-97 l1.88E2 12.72E1 11.60E1 l SD 13.89El 11.13E5 13.51E5 l l Nb-95 l2.33E4 19.18E3 16.55E3 1 SD 18.62E3 l6.14E5 13.70E4 l l Mo-99 l ND 11.72E2 [4.26El l ND 13.92E2 11.35E5 11.27E5 l l Tc-99 mil.78E-3 l3.4SE-3 15.77E-2 l ND 15.0 E-2 19.51E2 14.81E3 l l Tc-10118,10E-3 IS.51E-3 11.08E-3 l SD ll.45E-3 15.85E2 11.63E1 l l Ru-10312.79E3 l ND ll.07E3 l SD 17.03E3 1 6.62E5 14.48E4 l l Ru-10511.53E0 i SD 15.55E-1 l ND 11.34E0 11.59E4 19.95E4 l l Ru-106]l.36E5 l ND 11.A9E4 l SD 11.84E5 11.43E7 l4.29E5 1 lag-110 mil.69E4 !1.14E4 [9.14E3 i ND l2.12E4 15.48E6 }1.00E5 l l Cd-1001 ND IF.48E5 12.59E4 l ND la.96E3 11.05E6 [2.78E4 l l Sn-11311.13E5 13.12E3 18.62E3 12.33E3 l ND 11.46E6 12.26E3 l l Sb-12415.74E4 17.40E2 12.00E4 11.26E2 l ND 13.24E6 ll.64E5 l l Sb-12519.84E4 17.59E2 12.'174 l9.10E1 l ND 12.32E6 14.03E4 l lTe-125ml6.73E3 12.33E3 19.1. , 1.92E3 l ND [4.77E5 l3.38E4 l lTe-127ml2.49E4 18.55E3 l3.0* 16.07E3 16.36E4 l1.48E6 l7.14E4 l
[Te-127 12.77E0 19.51E-1 16.11--1 11,96E0 17.07E0 11.00E4 l5.62E4 l iTe-129 mil.92E4 16.SSE3 13.04E3 16. 33E3 - 15.03E4 11.76E6 11.82E5 l lTe-129 19.77E-2 13.50E-2 l2.38E-2 17.14E-2 l2.57E-1 l2.93E3 12.55E4 l lTe-131 mil.34E2 15.92E1 15.07El 19.77El l4.00E2 12.06ES 13.08E5 l lTe-131 12.17E-2 18.44E-3 16.59E-3 11.70E-2 15.88E-2 12.05E3 11.33E3 l lTe-132 14.81E2 12.72E2 l2.63E2 13.17E2 11.77E3 13.77E5 11.3BE5 l II-130 18.18E3 l1.64E4 18.44E3 l1.35E6 12.45E4 l ND 15.11E3 l 1I-131 14.81E4 14.81E4 12.73E4 11.62E7 17.88E4 l ND 12.84E3 1 lI-132 j2.12E3 14.07E3 11.65E3 il.94E5 16.25E3 i SD 13.20E3 l lI-133 11.66E4 l2.03E4 17.70E3 13.55E6 13.38E4 l SD 15.48E3 l lI-134 11.17E3 12.16E3 19.95E2 !5.07E' 13.30E3 l SD l9.55E2 1
h~. APA-ZZ-01003-Rev. yQ.
4
-~
.y.
TA3LE 5 (Cont'd.)
) CHILD PATHVAY DOSE FACTORS (R,) FCR RADIONL'CLIDES OTHER THAN NOBLE GASES
- Inhalation Pathway (mrem /yr) per (uCi/m ) 3 I l I l Total l l l- l Lung i GI-LLI l l
Body i Thyroid l Kidney I lNuclidal Bone I Liver i lI-135 l4.92E3 lS.73E3- 14.14E3 17.92E5 11.34E4 i ND 14.44E3 l lCs-134 l6.51E5 l1.01E6 l2.25ES l ND l3.03E5 11.21E5 l3.S5E3 l lCs-136 16.51E4 ]1.71E5 l1.16E3 i ND 19.55E4 ,ll.45E4 14.1SE3 l 11.25E5 ND 12.82E5 l1,04E5 l3.62E3 l ll_ lCs-137 l9.07E3 l8.25E5 l lCs-138-l6.33E2 IS.40E2 l5,53E2 i ND 16.22E2 16.81El 12.70E2 ._ l -
.l3a-139 l1.84E0 19,84E-4 15.37E-2 l- ND l8.62E-4 l5.77E3 l3.77E4 i
_jBa-140 l7.40E4 l6.4SE1 l4.33E3 l ND 12.11El 11.74E6 11.02E5 l l3a-141 l2.19E-1 l1.09E-4 16.36E-3 i ND l9.47E-3 12.92E3 12.75E2 l lBa-142-l3.00E-2 l:, 60E-3 _l2.79E-3 l ND 12,91E-3 11.64E3 12.7'E0 l l La-140 -l 6. 447.2 l2.25E2- -l7.53E1 l ND l ND 11.83E5 12.26E3 l fj - lLa-142'll.30E0 14.11E-1 11.29E-1 i ND l ND l8.70E3 l7.59E4 l
./ -lCe 141 13.92E4 11.95E4 12.90E3 1 ND 'l8.55E3 l5.44E5 l5.66E4 l lCe-143 l3.66E2 il 99E2- 12.87El 1 ND 18.36El 11.15E3 11.27E5 1
- lCe-144 16.77E6 l2.12E6 l 3 '. 61E 5 l ND l1.17E6 11.20E7 13.S9E5 l lPr-143.11.85E4- 15.53E3 -l9.14E2 l ND_ 13.00E3 la.33E5 19.73E4 1 JPr-144-15.95E-2 11.85E-2.: l3.00E-3 l ND ]9.77E-3 l1.57E3 11.9"E2 l lNd-147 l1,0SE4 IS.73E3 16.81E2 ] ND l4.81E3 13.2SE5 13.21E4 l
-lEu-154 11.01E7 19.21E3 IS.40E5 i ND l4.03E6 16.14E6 11.10E5 l lHf-131 12.78E'- 11.01E5 11.25E4 l ND 12.03E4 11.06E6 16.62E4 2 lW-137 .l1.63E1 19.66E0 14.33E0 l ND -l ND 14.11E4 19.10E4 l _l lNp-239 14.66E2 13.34El- 12.35El l ND l9.73E1 15. S1E4 16.40E4 [
(3). The child age group;-refer to reference 11.I'.5s APA-ZZ-01003
-Re.v. 7 2 .p j-TABLE 5 (Cont'd.)
a
[ CHILD PATHWAY DOSE FACTORSg(R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Ground Plane Pathway (m2 mrem /yr) per (pCi/sec)
Nuclide Total Ecdv Skin 3.21E7 Be-7 2.24E7 Na-24 1.19E7 1.39E7 Cr-51 4.65E6 5.51E6 Hn-54 1.39E9 1.63E9 Hn-36 9.03E5 1.07E6 Fe-59 2.72E8 3.20Ea Co-57 2.98E8 4.37E8 Co-58 3.79E8 4.44E8 Co-60 2.15E10 2.53E10 Ni-65 2.97E5 3.45E5 Cu-64 C.07E5 6.88E5 Zn 65 7.47ES 8.59ES Br-82 3.14E7 4.49E7
)
Br-83 4.87E3 7.08E3 Br-84 2.03E5 2.36E5
-Rb-86 8.99E6 1.03E7 Rb-88 3.31E4 3.78E4 Rb-89 1.23E5 1.48E5 Sr-89 2.16E4 2.51E4 Sr-91 2.15E6 2.51E6 Sr-92 7.77E5 8.63E5 Y-90 4.49E3 5.31E3 Y-41m 1.00E5 1.16ES ,
Y-91 1.07E6 1.21E6 Y-92 1.80E5 2.14E5 Y-93 1.83E5 .2.51E5 Zr-95 2.45ES 2.84E8 Zr-97 2.96E6 3.44E6
-Nb-95 1.37ES 1.61E8 Mo-99 3.98E6 a.62E6
APA-ZZ 01003 lAS2 )f)G-t-91 I .
TABLE 5 (Cont'd.)
CHILD PATHWAY DOSE FACTORS 1 (R ) FOR RADIONUCL1 DES OTHER THAN NOBLE GASES
- Ground Plane Pathway (m2 mrem /yr) per (pCi/sec)
Nuclide Total Body Skin Tc-99m 1.84E5 2.11E5 Tc-101 2.04E4 2.26E4 tu-103 1.08E8 1.26E8 Ru-105 6.36E5 7.21E5 Ru-106 4.22EB 5.07E8 Ag-110m 3.44E9 4.01E9 rd-109 3.76E7 1.54EB Sn-113 1.43E7 4.09E7 S5-124 8.74E8 1.23E9 Sb-125 3.57E9 5.19 E9 Te-125m 1.55E6 2.13E6 Te 127m 9.16E4 1.08E5 Te-127 2.98E3 3 28E3 Te-129m 1.98E7 2.31E7 Te-129 2.62E4 3.10E4 Te-131m 8.03E6 9.46E6 Te-131 2.92E4 3.45E4 Te-132 4.23E6 4.98E6 I-130 5.51E6 6.69E6 I-131 1.72E7 2.09E7 I-132 1.23E6 1.45E6 I-133 2.45E6 2.98E6 I-134 4.47ES 5.30E5 I-135 2.51E6 2.93E6 Cs-13'4 6.86E9 8.00E9 Cs-136 1.53E8 1.74E8 Cs-137 1.03E10 1.20E10 Cs-138 3.59E5 4.10E5
!a-139 1.06E5 1.19E5 Ba-140 2.05E7 2.35E7
APA-ZZ-01003 Rev.Jp g.pg/
..~,.
} TABLE 5 (Cent ' d . )_
a l CHILDPATH'.s'AY DOSE FACTCKS (R.) TOR RADICNUCLIDES OTHER THAN N 1
Ground Plane Pathway (m mrem /yr) per (uCi/sec) 8 Total Body ,_ Shin Nuclide 4.15E4 4 .7 37.4 Ba-141 4.44E4 !.Ge:4 Ba-142 2.18E7 La-140 1.92E7 7.40ES 8.89E5 La-142 1.54E7 Ci-141 1.37E7 2.31E6 2.63E6 Ce-143 S.04E7 Ce-144 6.96E7 1.84E3 2.11E3 Pr-144 1.01E7 Nd-147 S.41E6 2.21E10 3.15E10 Eu-154 1.97ES 2.82ES Hf-181 2.74E6 V-187 2.36E6
- 1.71E6 1.98E6 Np-239 (a) Refer to reference 11.14.5 for calculational details.
9
.S 4
APA-ZZ-01003 Rev. / 4 g
[i .) TABLE 5 (Cont 'd.J
- l CHILD PATSiAY DOSE FACTCRS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" Meat Pathway (m* mrem /yr) per (uCi/sec) 1 Total l l l l \
l l l
[Nuclidel Bone l Liver l Bedy i Thyroid l Kidney l LunJ l GI LLI l lH3 l ND l2.34E2 l2.34E2 12.34E2 12.34E2- 12 34E2 12.34E2 1 1 3e-7 17.37E3 l1.26E4 l8.06E3 i ND 11.23E4 l ND 17.00E5 I 17.67E7 17.67E7 17.67E7 17.67E7 l7.67E7 17.67E7 l l C-14 l3.83ES 1 Na-24 11.7SE-3 11.78E-3 11.7BE-3 l 1.78E-3 11.78E-3 ll.78E-3 l1.78E-3 l l P-32 17.41E9 l3.47ES 12.86EB l ND l ND l ND l2.05ES l l ND 14.88E3 l1.33E3 18.91E3 14.66E5 l l Cr-51 l ND 18.79E3 l Mn-54 l ND 18.01E6 12.13E6 i ND l2.2SE6 l ND l6.72E6 l l Mn-56 i ND l 0 1 0 l ND l 0 i ND l 0 1 1 Fe-55 l4.57E8 12.42E8 l7.51E7 i ND l ND 11.37E8 l4.49E7 l l Fe-59 13.76ES 16.09ES 13.03E8 l ND l ND ll.76E8 16.34E8 l l Co-57 l ND 15,92E6 11.20E7 i ND l ND l ND 14.85E7 l l Co-53 1 ND 11,64E7 15.02E7 l ND l ND 1 ND 19.58E7 l l Co-60 ) ND [6.93E7 l2.04E8 l ND l ND l ND 13.84EE l l Ni-63 l2.91E10 11.56E9 19.91ES l ND 1 ND l ND l1.05E8 1 0 1 ND ND 1 ND l 0 1 l Ni-65 1 0 1 0 l l
] Cu-64 ) 30 12.97E-7 11.79E-7 l ND 17.17E-7 i ND ll.39E-5 l l En-65 13.75ES 11.00E9 16.22ES l ND 16.30E8 l ND {1.76ES l l Zn-69 1 0 1 0 1 0 l ND l 0 i ND l 0 l l Br-82 l ND l ND 11.52E3 i ND l ND l ND l ND l l ND l ND l ND l ND l ND 1 W l 1 Br-83 I ND l Br-84 l ND l ND 1 SD 1 ND l ND l ND l ND l l Br-85 l ND l ND l ND l ND l ND l ND l ND l l Rb-86 l ND 15.82E8 13.58E8 ] ND l ND l ND l3.74E7 l l Rb-88 1 ND l 0 1 0 l ND l ND l ND l 0 l l Rb-89 1 ND l 0 1 0 l SD l ND l ND. l 0 l l Sr-59 14.82ES l ND l1.3SE7 l ND l ND l ND ll.86E7 l l Sr-90 11.04E10 i ND 12.64E9 l ND l ND l ND l1 :.0ES l l Sr-91 12.40E-101 ND l 0 i ND 1 ND l ND 15.29E-101 l Sr-92 1 0 l SD l 0 l ND l ND l ND l 0 l l Y-90 11.71E2 ! ND !!. 59E3 i ND 1 ND i ND 14.SSES l
APA-ZZ 01003 g
Rev. y ) 'Dj3 S-l'll TABLE $ (Cont.' d . )
CHILD PATHWAY DOSE FACTORS g (R ) FOR RADICSUCL! DES OTHER THAN NOBLE GASES Meat Pathway (m* crem/yr) per (u21/sec) l l l l Total l l l l l Bone Eedv I Thyroid 1 Pidney 1 Lung 1 GI-LLI l l lNuclidel I Liver !
] Y-91m 1 0 1 ND l 0 l Y 91 11,SOE6 l ND 14.82E4 l SD l ND l SD l2.40E8 l l ND 0 l Y-92 l 0 l ND l 0 l SD l ND l l l Y-93 l 0 l SD l 0 l SD l SD l ND ll.55E-7 l l Zr-95 12.66E6 15.85ES 15.21E5 1 ht 18.38E5 l ND 16.11ES l 16.65E-6 1 ND 17.02E-1 l
\ Zr-97 13.20E-3 14.63E-6 12.73E-6 l ND (2.23E9 l Sb-95 13.09E6 11.20E6 IS.61E5 l ND {1.13E6 l ND l l1.15E5 12.84E4 l ND 12.46E5 i SD 19.51E4 l l Mo-99 i ND 0 0 0 l l Tc-99ml 0 1 0 1 0 1 ND 1 1 1 0 0 0 l l Tc-1011 0 l 0 1 0 1 ND { l l l ND 15.96E7 l SD 13.90E8 i ND 14.01E9 1
] Ru-103l1.55E8 0
. j Ru-205) O l ND ] O l SD l 0 l ND l l l Ru-10614.44E9 ] ND 15.54E8 l ND 15.99E9 l SD 16.90E10 l lag-110ml8.40E6 15.67E6 14.53E6 l SD 11.06E7 t ND 16.75E8 l 11.90E6 18.83E4 l SD ll.70E6 i SD 16.18E6 l lCd-109 l ND ll.54E9 lSn-113 12.18E9 14.48E7 l1.24E8 13.31E9 i ND l ND l lSb-124-12.93E7 13.79E5 11.02E7 16.45E4 l hT 11.62E7 11.83E8 l l2.6!E4 l ND ll.59E7 l6,80E7 l ISb-125 12.85E7 12.20E5 15.97E6 lTe-125ml5.69ES 11.54E8 17.59E7 11.60ES l SD 1 ND l5.49ES 1 l4.78E8 12.11E8 14.24E8 15.06E9 l ND !1.44E9 l ITe-127mll 77E9 (Te-127 l4.11E-1011.11E-10 l 0 .l2.85E-10 11.17E-9 i ND ll.61E-8 l lTe-129mi l . 7 9E9 l4.99E8 12.77E8 15.76E8 15,25E9 l ND 12.18E9 l 0 0 0 1 0 i UD l 0 {
lTe 129 l 0 1 l l 12.42E2 12.58E2 14.98E2 12.34E3 l ND 19.82E3 !
lTe-131ml7.00E2 lTe-131 1 0 1 0 l 0 1 0 1 0. I ND l 0 l l9.26E5 11.12E6 l1.35E6 IS.60E6 l ND [9.33E6 l lTa-132 12.09E6 lI-130- ]3.04E-6 16.13E-6 13.16E-6 16.76E-4 19.17E-6 l ND {2.87E-o 1 lo.46E6 15.50E9 12.73E7 l ND II.4SE6 l 11-131 11.66E7 11.66E7 0 0 0 0 l ND l 0 l 1I-132 ] O l 1 1 1
!!-133 16.16E-1 17.61E-1 !;.SSE 1 11.4112 11.27E0 i ND !3.07E-1 !11-134 l 0 l 0 1 0 [ 0 l 0 l ND l 0 l m
APA-ZZ 01003 b (f,) y/-9/
l TABLE 5 (Cont'dd CHILD PATWAY DOSE FACTORS (R ) FOR RADIOSUCLICES OTHER THAS SCEEE GASES
~
?! eat Pathway (m mrem /yr) per (uCi/sec) 8 i I I l Total l I I i !
Boae i Liver Bodv 1 Thyroid i Kidney l Limg l GI-LLI l INuclidel l 0 0 0 1 ND l 0 l lI-135 l 0 l 0 1 l 1 lCs-134 l9.22ES 11.51E9 13.19ES l ND 14.69ES 11.68E8 18.16E6 1 14.43E7 12.S'E7 l ND (2.36E7 13.51E6 11.56E6 l
]Cs-136 11.61E7 l7.99E6 lCs-137 11.33E9 11.2SE9 il ' .ES l SD 14.16ES 11.50E6 0
l 0 0 l bT l 0 l 0 1 l lCs-138 1 0 1 0
lBa-139 l 0 l 0 1 0 l SD l 0 l 0 1 l lBa-140 14.38E7 13.84E4 12.56E6 i ND ll.25E4 l2.29E4 12.22E7 l 0 0 lBa-141 l 0 l 0 l 0 l SD l 0 1 1 l 0 0 0 l 0 l
]Ba-142 1 0 1 0 1 l h3 1 1 lLa-140 15.69E-2 11.99E-2 16.70E-3 l SD l ND l ND l5.54E2 l 0 0 l SD l SD l ND l .0 l lLa-142 l 0 l 1
} lCe .'01 12.22E4 11.11E4 11.64E3 l SD 14.85E3 l ND ll 38E7 l 12.49E-3 l SD 17.21E-3 l ST (2.52E2 l lCe-143 l3.17E-2 11.72E1 JCe-144 12.32E6 17.26ES 11.24E5 l ST 14.02E5 i ND l1.89ES l lPr-143 13.35E4 l1.00E4 11.66E3 l ND 15.44E3 l ND (3.61E7 l l ND 0 lPr-144 l 0 1 0 1 0 l SD l 0 l l INd-147 11.17E4 l9.50E3 17.35E2 1 SD 15.21E3 l ND 11.50E7 l lEu-154 11.12E7 l1.01E6 19.20E5 l SD [4.42E6 l ST l2.34ES l 11.73E7 12.15E6 ST 13.52E6 l hT 16.40E9 l lHf-181 14.76E6 l lW-187 13.35E-2 l1.98E-2 l8.91E-3 l SD l ND l ND 12.79E0 l lNp-239 l4.20E-1 13.02E-2 12.12E-2 l SD 18.72E-2 1 ST l2.23E3 l (a) The child age group; refer to reference 11,14.5.
r, APA-ZZ-01003 Rev. Jp p ,,ry y
I' TABLE 5 (Cont'd.)
CHILD PATINAY DOSE FACTORS g (R ) FOR RADIONUCLIDES OTHER THAN NOBLE Grass-Cow-Hilk Pathway (m1 mrem /yr) per (pCi/sec)
-l l l l Total l l l l l lNuclidel Bone i Liver 1 Body l Thyroid 1 Kidney l Lung I GI-LLI I
-l H-3 l ND- l1.57E3 l1.57E3 l1.57E3 11.57E3 11.57E3 11.57E3 l l Be-7 17.49E3 l1.28E4 l8.19E3 l ND ]1.25E4 l ND l7.11E5 l l2.39E8 12.39ES 12.39E8 l2.39ES~12.39E8 12.39E8 l l C 14 l1.19E9 l Na-24 18.89E6 18.89E6 l8,89E6 l8.89E6 IS.89E6- 18.89E6 18.89E6 l
_l P-32 17.77E10 13.64E9 {3.00E9 l ND l ND l ND l 2.15 E9 l l Cr-51 l hT l ND l1.03E5 l5.65E4 11.56E4 11.04E5 15.40E6 l l 2.- 10E 7 15.59E6 l ND 15.88E6 l ND l1.76E7 l
_.! Mn-54 l ND
-l Mn-56 l ND l1.29E-2 l2.90E-3 l ND ll.56E-2 l ND 11.86E0- l l Fe-55 l1.12ES -15.93E7- li.84E7 l ND l ND l3.35E7 11.10E7 l l Fe-59 11.20E8 l1.94E8 l9.69E7 l ND l ND 15.64E7 l2.02E8 l l Co-57 l ND 13.84E6 17.76E6 l ND l ND l ND 15.15E7 l
'; I Co-58 l_ ND -11.21E7 13.71E7 l ND l ND l ND [7.07E7 l l Co-60 l ND 14.32E7 l1.27ES l ND l--ND l ND 12.39E8 l l Ni-63 12.96E10 11.59E9 11.01E9 -l ND l ht l ND l1.07ES l l Ni-65 l1.66EO- 11.56E-1 19.01E-2 l ND l ND l ND l1.91El l
[7.46E4 l4.51E4 l ND 11.80E5 l ND l3.50E6 l l Cu-64-1 ~ ND l Zn-65 14.13E9 l1.10E10 16.85E9 i ND 16.94E9 l ND l1.93E9 l
-l 2n-69 l 0 } O l 0 l ND l 0 l ND l1.12E-9 l
.} Br-82 i ND , -l ND ll.15E8 l ND l ND l ND :l ND l
.l 3r-83 l ND l ND . I ND l ND l ND l ND- l ND l 1.3r-84 l ND l ND l ND l ND l ND l ND l ND l
-l Br-85 l' ND- l ND -l ND i ND l - ND l ND l ND l l Rb-86 l ND 18.80E9 15.41E9_ l ND l ND l ND 15.66E8 l 0
lLRb-83 i ND l 0 i O_ l ND 1. ND l ND l l
_l Rb-89 l ND' l 0 l 0 ) ND l ND -l ND l 0 l l Sr-89 l6.62E9 l ND l1.89E8 l ND l ND l ND l2.56E8 l l Sr-90 l1.12E11 1 ND 12.83E10 1 ND l ND l - ND fl.51E9 I 14.92E3 l ND. 1 ND l ND 12.88E5 l l Sr-91 l1.30E5 i ND -
l Sr-92 12.18E0 l ND l8.75E-2 i ND l ND l ND (4.13E1 l I Y-90 13.22E2 ! ND 18.62E3 ! c
. 1 ND i ND 19.17E5 I
... . _- . ~ _ . _ _ - - . . - - - . . _-
APA-ZZ-01003 Rev. /g _
TABLE 5 (Cont'd.)
CHILD PAThVAY DOSE FACTORS g (R ) TCR RADIONUCLIDES OTHER THAN NOBLE GASES" ,
Grass-Cow-Milk Pathway (m8 mrem /yr) per (pCi/sec) l l 1. l Total l l l l l lNuclidel Bene- I Liver i Body 1 Thyroid i Kidney i Lung l GI-LLI l l Y-91m l- 0 l ND - l _0 l' ND. I ND l . ND l 0 l
-) Y-91 J3.90E4 l ND l1.04E3 l ND l ND l ND 15.20E6 l l Y-92 l2.53E-4 l ND 17.24E-6 l _ND l ND l ND [7.31E0- l-l Y-93 l1,05E0 l ND l2.90E-2 l ND l ND l ND l1.57E4 l
~l Zr-95-l3.83E3 l8.42E2 'l7.50E2 1 ND l1.21E3 l ND l8.79ES l l-Zr-97 11.92E0 l2.77E-1 l1.64E-1 l ND l3.98E-1 l ND 'l4.20E4 l
') Nb-95-l3.18E5- ll_.24E5 l8.84E4 l ND l1.16E5 l .ND l2.29EB l l'Mo-99 l ND 18.14E7 l2.01E7 l _ ND l1.74EB l ND l6.73E7 l l Tc-99ml1.32E1 l2.59El l4.29E2 l ND '3.76E2
, l1.32E1 11.47E4 l 0 l ND 0 l 0 l 0 l l Tc-101l 0 l _0 l l l Ru-103l4.28E3 -l - ND l1.65E3 l ND l1.08E4 l ND l1.11E5 l l Ru-105l3.82E-3 l ND- l1.39E-3 l ND l3.36E-2 l' ND l2.49E0 l lTRu-106l9.24E4 l ND_ l1.15E4 l Sp l1.25ES l ND l1.44E6 l
[Ag-110ml2.09E8 l1.41ES ll.13E8 l ND l2.63E8- l ND l1.68E10 l ,
l l1.2 E7 l lCd-109 l' SD 13.86E6'- l1.79E5 l ND l3.45E6 _l ND
_l5n-li3 l6.10E8 l1.25E7 l3.48E7 19.27E8 l ND 1 ND l4.31E8 l
- l Sb-124 -ll'.08E8 = ;ll.41E6 .l3.81E7' l2.40E5 l ND l6.03E7 16.79ES l
-lSb-125 l 8.70E7 -l6.71ES ;[1.83E7 _l8.06E4- l .ND [4.85E7 l2.08E8 l-
[Te-125ml7.38E7 'l2.00E7 19.84E6' j2.07E7 l ND l - ND 'l7.32E7 l
-lTe-127ml2.08ES -l5.60E7 l2.47E7 14.97E7- 15.93E8 _l -ND ll.68E8 l lTe-127 l3.05E3 18.22E2 [6,54E2 l2.11E3 l8.67E3 l ND lI.19E5 l
~
-lTe-129ml2.71E8 l7.57E7 l4.21E7 l8.74E7 l7.96E8 l' ND l3.31E8 l
'lTe-129-lc .0 1 l -0 l 0 12.90E-9 --l _ ND l6.17E-8 l lTe-131 mil.60E6 'l5.53E5 0. -l5.89E5 {1.14E6 l5.35E6 l- ND l2.24E7 l' '
0 .0 0 l ND l 0 j-lTe-131 l 0 l_ 0 l l l
.lTe-132-II.02E7 -l4.52E6 l5.46E6_ l6.58E6 l4.20E7 l ND 14.53E7 l.
lI-130 jl 73E6 13.49E6 11.80E6 l3.84E8 l5.22E6 l ND l1.63E6 l JI-131 jl.3CE9 11.31E9 l7.45E8 14.33E11 l 2.15E9 l ND l1.17E8 l
-lI-132 16.02E-1 l1.11E0 15.08E-1 15.13E1 l1.69E0 l hT ll.30E0 l l'
'j!-133 il.7eE7- l2.1527 IS.13E6._l3.99E9 13.3aE7 l ND [8.66E6 lI-134 1 0 l 0 l 0 l 0 l 0 l ND l 0 l 56
APA-ZZ 01003 Rev. /) .g g 3
TABLE 5 (Cont'd.)
CHILD PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m m em/yr) per (pCi/sec) 2 l l
[ [ l l Total l 1 Thyroid l Kidney l l l Luns: 1 GI-LLI l Bone ! Liver ! Body lNuclidel ll.49E5 i hT (7.40E4 l II-135 (5.40E4 19.72E4 14.60E4 IS.61E6 12.00E8 l lCs-134 {2.26E10 13.72E10 l7.84E9 l ND 11.15E10 14.13E9 l ND l1.48E9 12.20E8 19.74E7 l lCs-136 11.01E9 12.77E9 11.79E9 i ND l1.01E10 13.62E9 l1.93E8 l lCs-137 {3.22E10 13.09E10 14.56E9 0 ND { 0 l 0 l 0 l 0 0 1 l lCs-138 1 1 ~
0 (5.46E-9 { ND l 0 l 0 l1.09E-5 1 lBa-139 }1.89E-7 l [3.34E4 l6.12E4 15.93E7 l IBa-140 11.17ES 11.03E5 l6.84E6 i SD 0 0 1 0 l 0 0 i h3 1 l lBa-141 1 0 l l O
0 [
lBa-142 1 0 1 0 [ 0 l ND l 0 l }
l2.29E0 i ND l . ') l ND l1.90E5 l lla-140 ll.95El 16.SOE0 0 l 0 } ND l ND 1 ND 12.90E-6 (
lLa-142 l 0 1 ll.62E3 l ND 14.7BE3 l ND ll.36E7 l lCe-141 12.19E4 {1.09E4 (4.26El ND 11.49E6 l lCe-143 ll.87E2 l1.02E5 11.47El i ND l IS.66E4 l ND 12.82E5 l ND ll.33E8 l lCe-144 11.62E6 15.09E5 !1.17E2 ND l7.75E5 l l P r-143 17.19 E2 12.16E2 13.57El l ND l ND 0 l lPr-144 1 0 1 0 1 0 i ND [ 0 1 l 12.79El l ND l1.9SE2 i ND l5.71E5 l lNd-147 {4.45E2 l3.61E2 ND ll 97E6 )
leu-154 [9.41E4 {8.47E3 17.73E3 l ND 13.72E4 l ND 14.75E2 l ND 18.65E5 l lHf-181 16.43E2 l2.35E3 l2.90E2 l 17.73E3 l ND h3 l ND (2.42E6 l lW-187 12,91E4 {1.73E4 l ND 19.14E4 1 lNp-239 l1.72E1 l1.23E0 IS.6SE-1 1 ND l3.57E0 i (a) The child ye group; refer to referen:e 11.14.5.
- 57 -
APA-ZZ-01003 Rev. If) , _
\
TABLE 5 (Contd.)
CHILD PATHWAY DOSE gFACTORS (R ) FOR PJOIONCCLIDES OTHER THAN NCBLE GAS Grass-Goat-tlilk Pathway (m2 mrem /yr) per (pCi/sec)
I I l i ! l Total I I I Lung I GI-LLI i Liver l Body ! Thyroid i Kidney I lNuclidel Bene l l3.20E3 13.20E3 13 . 20E'.> 13.20E3 (3.20E3 l 1 H-3 l ND 13.2CE3 11.50E3 l ND [8.53E4 l l Be-7 18.98E2 11.53E3 19.82E2 1 ND 12.39ES 12.39ES 12.39ES 12.39EB l2.39ES I l C-14 l1.19E9 l2.39ES 11.07E6 l1,07E6 11.07E6 l 11.07E6 11.07E6 i Na-24 11.07E6 11.07E6 l ND ND l2.58E9 l l P-32 (9.33E10 I4.37E9 13.60E9 [ ND l 16.75E3 {1.S7E3 11.25E4 16.48E5 l l Cr-51 1 ND l ND l1.23E4 l ND 17.06ES l ND 12.11E6 l l Mn-54 l ND l2.52E6 l6.70E5 13.49E-4 l ND 11.87E-3 l ND 12.24E-1 1 l Mn-56 l ND l1.54E-3 17,71ES l2.39ES l ND l ND 14.36E5 11.43E5 l
] Fe-55 11.45E6 l ND l7.33E5 l2.63E6 l l Fe-59 11.56E6 12.53E6 11.26E6 i ND 19.31E5 l ND l ND l ND l3.77E6 l l Co-57 i ND lt.60E5 11.45E6 14.45E6 l ST l ND l ND 18.49E6 1 l Co-58 l ND
] ND ] ND l SD l2.87E7 l l Co-60 l ND 15.18E6 11.53E7 1 ND ND 11.2SE7 l l Ni-63 13.56E9 11.90E8 11.21ES l ND l l2.29E0 l 1 Ni-65 11.99E-1 11.87E-2 11.09E-2 i ND l ND l ND ND (2.01E4 l ND 13.90E5 l
] Cu-64 1 ND 18.31E3 15.02E3 l lS.22E3 1 SD 18.33E8 l ND [2.32ES l l Zn-65 l4.96ES 11.32E9 0 0 0 1 ND i 0 l ND l1.35E-101 l Zn-69 l 1 1 i SD l ND l ND l ND l l 3r-82 l ND l ND 11.3SE7 ND l Br-83 l ND l ND l ND 1 ND l ND i SD l l l SD l ND l ND l ND 1 ND l l 3r-84 l ND l ND l ND l ND l ND ND 1 ND l ND l l 3r-85 l ND 1 l ND ] ND l ND (6.80E7 l l Rb-S6 l ND 11.06E9 16.50ES 0
} Rb-88 l ND } O 1 0 [ ND l ND l ND l 0
l l Rb-89 i ND l 0 1 0 l ND l ND l ND l l ND l ND l SD 15.38ES l l Sr-69 ll.39E10 1 ND }3.97ES l 15.95E10 l SD l ND l ND 13.16E9 l l Sr-90 12.35E11 1 ND l ND l ND 16.04E5 l l Sr-91 12.74E5 1 ND ll.03E4 ] ND
l APA-ZZ-01003 J
Rev. yaygpg3.j,qg i
TABLE 5 (Contd.)
CllII.D PATir, LAY CCSE FACT 2KS (R ) FCR RADIONUCLIEES OTFER THJ.h N05I.E GASIS "
Grass-Goat-Milk Pathway (m2 mrem /yr; per (pCi/sec) i ) l l Total I l l l l lNuclidel Bene i Liver l Body l Thyroid i Kidney 1 Lung l GI-LLI l l Sr-92 14.58E0 l SD 11.84E-1 1 ND l SD l SD l8.68E1 l l Y-90 13.87El l ND 11.03E0 i ND l ND l ND 11.10E5 l l Y-91m l 0 l ND i 0 l ND l SD l ND l 0 l l Y-91 14.68E3 I ND ll.25E2 1 SD l SD l ND l6.24E-5 l l Y-92 13.04E-5 l ND 18.69E-7 l ND l ND l ND 18.77E-1 l ---
l Y-93 l1.27E-1 1 ND 13.48E-3 l ND 1 ND l ND l1.89E3 l l Zr-95 14.60E2 11.01E2 19,00E1 i ND ll.43E2 l ND ll.05E5 l l Zr-97 12.30E-1 13.33E-2 l1.96E-2 1 ND l4.78E-2 1 ND 15.04E3 l l Nb-95 13.81E4 11.48E4 11.06E4 l ND ll.39E4 l ND 12.75E7 l l Mo-99 l ND 19,76E6 l2.42E6 l ND 12.09E7 i ND 18.0SE6 l l Tc-99mll.59E0 13.11E0 15.15El l ND 14.52E1 l1.5SE0 11.77E3 l l Tc-1011 0 1 0 1 0 l SD l 0 l 0 l 0 l l Ru-10315.14E2 1 ND l1.98E2 l ND ll.29E3 l ND 11.33E4 l 1 Ru-10514.3SE-4 l SD ll.66E-4 l ND 14.03E-3 l ND 12.99E-1 l i Ru-106l1.11E4 l SD 11.38E3 l SD 11.50E4 1 SD l1.72E5 l lAg-110ml2.51E7 11.69E7 l1.35E7 l ND !3.15E7 1 ND l2.01E9 l lCd-109 ) ND 14.63E5 12.15E4 l ND 14.13E5 i ND ll.50E6 l lSn-113 17.32E7 11.50E6 14.17E6 l1.11E8 i ND 1 ND 15.17E7 1 ISb-124 l1.30E7 11.69E5 14.56E6 l2.87E4 l ND l7.22E6 l8.14E7 l 155-125 11.04E7 l8.04E4 12.19E6 l9.66E3 i ND l5.81E6 l2.49E7 l ITe-125ml8.85E6 12.40E6 11.18E6 12.48E6 l SD l ND 18.54E6 l lTe-127ml2.50E7 16.72E6 12.96E6 15.97E6 l7.12E7 i ND 12.02E7 l lTe-127 13.66E2, 19.86El 17.85El l2.53E2 11.04E3 l ND ll.43E4 l lTe-129ml3.25E7 19.09E6 15.05E6 11.05E7 19.53E7 l ND l3.97E7 l ITe-129 1 0 1 0 [ 0 l 0 1 0 i SD 17.40E-9 l iTe-131 mil.92E5 l6.64E4 17.07E4 11.37E5 16.43E5 l ND 12.69E6 1 0 0 0 0 0 ND 0 l ITe-131 1 1 1 [ 1 l l lTe 132 11.23E6 15.42E5 l6.55F5 17.90E5 l5.04E6 i ND 15.46E6 l lI-130 12.07E6 14.19E6 12.16E6 14.61ES 16.26E6 l SD 11.96E6 1
APA-ZZ-01003 f
Rev /,Q TABLE 5 (Contd.)
CHILD pg7aiAY DOSE FACTCES (h ) FOR RADICN'JCLIDf 5 OTHER THAN SCBLE GASES Grass-Goat-Milk Pathway (m mrem /yr) per (tici/sec) 8 j j j Total l l l l l l
lNuclidel Bone I Liver i Body 1 Thyroid 1 Kidney l Lung i GI-LLI l i:-131 l1.56E9 11.57E9 18.94ES l5.20E11 12.55E9 i ND l1.40E8 1 1I-132 17.22E-1 11.33E0 16.10E-1 16.15El 12.03E0 l ND ll.56E0 l 11-133 l2.09E7 12.58E7 19.76E6 14.79E9 14.30E7 1 ND 11.04E7 l lI-134 l 0 ) 0 1 0 1 0 1 0 i ND 1 0 l 1I-135 l6.4SE4 11.17E5 15.52E4 11.03E7 11.79E5 l ND IS.SSE4 l ICs-134 16.79E10 11.11E11 12.35E10 i ND 13.45E10 ll.24E10 16.01ES l lCs-136 l 3.03E9 18.32E9 15.38E9 i ND 14.43E9 16.61E8 l2.92ES l lCs-137 19.67E10 19.26E10 ll.37E10 i ND l3.02E10 11.09E10 15.80ES l 0 0 0 l ST I 0 l 0 1 0 l lCs-138 1 l l IBa-139 12.27E-8 1 0 1 0 l ND l 0 1 0 ]1.31E-6 l lBa-140 l1.4157 l1.23E4 IS.20E5 ) h3 l4.01E3 17.3'E3 17.12E6 0
l 0 0 0 ND l 0 1 0 l l lBa-141 1 1 l l 0
13a-142 l 0 l 0 1 0 l ST l 0 1 0 1 l lLa-140 12.34E0 IS.17E-1 12.75E-1 l NE l ND l ND l2.28E4 l lLa-140 1- 0 l 0 l 0 l ND l ND l ND l3.49E-7 l lCe-141 12.62E3 l1.31E3 11.94E2 1 ND 15.74E2 l St 11.63E6 l lCe-143 12.25El 11.22E4 11.77E0 l ND l5.12E0 l ND ll.79E5 l 1Ce-144 l1.95ES 16.11E4 11.04E4 l ND 13.35E4 l ND ll.59E7 l lPr-143 18.62E1 12.59El 14.28E0 i ND ll.40E1 1 ND 19.30E4 l lPr-144 l 0 1 0 1 0 l 53 1 0 l ND l 0 l lNd-147 15.34E1 la.33E1 13.35E0 l NT 12.37El i ND l6.85E4 l lEu 151- l1,13E4 11.02E3 19.27E2 l ND 14.46E3 1 ND 12.36E5 l lHf-181 l7.71El 12.81E2 13.4SE1 l ND 15.70E1 1 ND 11.04E5 l lW-187 13.49E3 l2.07E3 19,27E2 l ND l ND l ND 12.90E5 1 lSp-239 12.06E0 11.48E-1 11.04E-1 l ND 14.28E-1 l ND 11.10E4 1 (a) The child age group; refer to reference 11.14.5. - ,
60 -
APA Z2 01003 ,
8*/\Q$.)-9l
- n p*i TAPEE 5 (Centd.)
J' CHILD PATINAY DCSE FACTORS- (R ) TOR RADIONt'CLI;ES OTt!ER TMAN NO3LE GASES" g
I Veptation Pathway l
{
(m8 srem/yr) per (uC1/sec) l l l l Total l l l l l lNuc1: 'el Bene I Liver i Body 1 Thy:old 1 Kidney I Lung l GI LLI l l H-3 l ND 14.01E3 l4.01E3 l4.01E3 l4.01E3 14.01E3 14.01E3 l
) Be-7 l3.38E5 15.76E3 13.70E5 .] ND 15.64E5 l ND l3.21E7 l l-l C-14 l8.89E8 l1.78E8 ll.78E8 l1.78E8 11.76E8 l1.7BE8 l1.78E8 l l Na 24 13.75E3 _13.75E5 _ l3.75E3 l3.75ES 13.75E5 13.75E3 l3.75E5 l
!' l P-32 l3.37E9 li 37E8 l1.30E8 l ND l ND l ND 19. JOE 7 l l Cr-51 j ND- l _ ND l1.17E5 l6.50E4- -l1.78E4 l1.19E3 l6.21E6 l l tin 54 l - ND 16.65ES l1.77E6 l ND l1.86E8 l ND l5.58E8 l l tin-56 -l ND 11.88E1 14.24E0 l ND 12.27El l ND l2.72E3 l l Te-55 j8.01E8 14.25E8 l1.32E8 l ND l ND l2.40E8 l7.87E7 l l To 5" l3.a7ES 16.43E8 l3.20E8 l ND l ND l1.86E8 l6.69E8 l l ND
_j Co-57 l ND l2.98E7 l6.04E7 l ND ND l2.45ES l ,
-l.Co 58-l ND -l6.44E7 il.97E8 l ND l ND ND l3.76E8 l l
[
] Co 60 l ND l3.78E8 l1.12E9 l ND l ND ND l2.10E9 l Ni 63 J3.95E10 !?. 11E9 11.34E9 l ND l ND L ND l1.42E8 1 Ni 65 l1.05E2 19.89E0 15.77E0 l ND l ND l ND l1.21E3 l l Cu-64 l ND ll.10E4 l6.64E3 l ND- l2.66E4 l _ ND 15.16E5 l l' Zn-65 l8.12E8 12.16E9 l1.35E9 l ND 11.36E9 l ND l3.80E8 l
. Zn 69 l1.09E 5 11.57E-5 11.45E 6 l ND l9.52E-6 l ND l9.11E 4 l ;
l Br 82 l ND l ND- l2.04E6 l ND l ND l _ND l ND l l Br-83 l_ ND l ND 15.37EO- l ND l ND l ND l 0 l i l Br-84 l ND l ND l 0 I ND l ND- l ND l 0 l
.. ,l Br 85 l ND 0 l ND 1 0 l N*d .l ND l ND l _l l Rb 86 l ND - l4.58E8 12.82E8 l ND l ND l ND l2.94E7 l l Rb-86 l ND l 0- l 0 .
I ND l ND l ND l 0 l 0- l ND ND ND 1 0- l 1.Rb-89 l ND l l _0 l l l Sr 89 l3.59E10 i ND- l1,03E9 -l ND l ND l ND 11.39E9 l ,
1 Sr+90 l1,24E12 l ND 13.'.5E11 l ND -l ND l ND ,11.67E10 I i Sr-91 15.24E5 i ND ll.9BE4- l ND l ND 1 ND ll.16E6 l ,
l Sr 92 17.2SE2_ l ND 12.92E1 l ND l ND l ND 11.38E4 'l l Y 12. 31E!. i ND 15.1SE2 1 ND 1. ND l ND l 6.57E7 ]
APA ZZ 01003 Rev.- g _gp g,I,l ,
m).
TABl.E $ (Contd.)
9- CHILD PAT &'AY DOSE EACTORS g (R ) FOR RADIONUCLIDES OTHER THAN N0PLE GASE5" )
Vegetation Pathway f '
(m' mrem /yr) per (WC1/sec) j Total j l l l l !
}- l l l lNuclidel Bone i Elver l Body i Thyroid l Kidney l Lun r, l 01 LLI i 1 4
l Y-91m l8.87E-9 l ND l3.23E 10l ND .l ND l ND l1.74E-3 l 14.99E3 [ ND l ND l2.48E9 l Y 91 l1.86E7 .l.ND. l ND l l Y-92 l1.58E0 l ND la.53E 2 l ND l ND l ND l4.58E4 l l Y-93 l3.01E2 l ND l8.2SE0 l ND l ND l ND 14.48E6 l l Zr 95 l3.86E6 18 . '.5 E 5 l7.55E5 l ND l1.21E6 l ND 18.84E8 l
! Zr 97 l5.70E2 18.24E1 l4.86El l ND l1.18E2 l ND l1.25E7 l 7 j Nb 95 l4.10E5 l1.59E5 l1.14E5 l ND l1.50E5 l ND l2.95E8 l l Mo-99 l ND l7.71E6 l1.91E6 l ND l1.65E7 l ND l6.3BE6 l i l Tc-9)ml4.71E0 l9.24E0 l1.53E2 l ND l1.34E2 l4.69E0 l5.26E3 [
-l Tc-1011 0 l 0 l 0 l ND l 0 l 0 l 0 l l Ru-103l1.54E7 l ND 15.90E6 l ND l3.87E7 l ND l3.97E8 l
, l Ru 10$l9.16El l ND l3.32E1 l ND l 8 . 05 't l ND l5.98E4 l l Ru-106l7.45E8 l- ND l9.30E7 i ND l1.01E9 l ND l1.16E10 l lAg-110ml3.22E7 l2.17E7 l1.74E7 l ND 14.05E7 l ND 12.58E9 l lCd-109 j ND l2.45E8 l1.13E7 l- ND l2.18E8 l ND 17.94E8 l lSn-113 11.58E9 l3.25E7 l9.00E7 l2.40E9 l ND l ND l1.12E9 -l lSb-124 13.52E8 l4.56E6 l1.23E8 ]7.76ES l ND l1.95ES l2.20E9 l lSb 125 l4.99E8 l3.85E6 11.05E8 l4.62E5 l ND l2.78E8 l1 19E9 l lTe-125ml3.51E8 l9.50E7 14.67E7 l9.84E7 l ND l ND l3.38E8 l lTe-127ml1.32E9 13.56E8 .l1.57E8 13.16ES 13.77E9 l ND l1,07E9 l lTe-127 11.00E4 l2.69E3 l2.14E3 l6,91E3 l2.84E4 l ND 13.90E5 l lTe 129ml8.38E8 l 2. 34E8 . . l1,30E8 l2.70E8 l2.46E9 l ND l 1,02E9 l lTu-129 l1.16E 3 l3.23E-4 . l 2.75E 4 l8.26E-4 13.39E-3 l ND. 17.20E-2 l lTo-131m l 1.54E6 l5.33E5 !5.68E5 11.10E6 l$.16E6 l ND l2.16E7 l 0 0 0 0 ND 0 l ;
lTe-131-l 1 0 l l l l l lTe-132 l6.98E6 13.09E6 l3.73E6 l4.50E6 12.87E7 l ND l3.11E7 l
. lI-130 16.16E5_.[1.24E6 l6.38E5 11.37ES __l1_.86E6 l ND 15.79!5 l lI-131 l1.43E8 11.4.E8 l8.17E7 la.75E10 12.36E8 l ND l1.2SE7 l lI-132 l8.58E1 l1.58E2 l7.25El -l7.31E3 l2.41E2 l ND l1.86E2 l' '
113 13.56E6 14..0E6 l1.6?E6 l8.15E3 .17.34E6 l ND 11.77E6 1 l1-134 l1.55E 4 l2.88E-4 11.32E-4 l6.62E-3 l4.40E-4 l ND l 1. 91E
- 4 - l 1I 135 16.62E4 11.13E5 15.33E4 l9.97E6 J1.70E5 l ND 15.56E4 l 4
62 - .
i i
-,,_:.__..._.uu....__ .._....__.._.._._._.__.___,._,_.-_.,_,...__,_....m.,_-.,, .,~m_.__.
' APA-22 01003 R e v . .r0c f fp e'll
- s. .
TAPLE 5 (Cened.)
CHILD PATINAY DOSE TACTCRS (R p FOR RADICTCE: DES OTHER TH AN NDBLE GAS)
I Vegetation Pathway (m8 mram/yr) per (LO1/sec) l l l l Total l l l l l lNuclide! Pene l Liter 1 Body 1 Thyroid 1 Kidney I Lug l GI-LLI I l ND l3.15E9 (2.93E9 11.42ES l lCs-134 l1.60E10 12.63E10 15.55E9 l7.90E6 lCs-136 18.17E7 10.2SES 11.45ES l ND ll 20E8 11.75E7 l l3.38E9 1 ND l7.46E9 12.68E9 11.43E8 l
}Cn-137 J2.39E10 12.29E10 0 0 lCs-138 l 0 l 0 1 0 l ND l 0 1 l l lBa-139 14.60E-2 l2.56E-5 11.39E-3 l ND l2.24E-5 11.51E-5 12.77E0 l 11.62E7 1 hT 17.89E4 11.45E5 11.40E8 l lSa 140 12.77E8 12.42E5 0 0 0 l ND i 0 1 0 l l lBa-141 1 0 1 1 0
lBa 142 l 0 1 0 1 0 i ND 1 0 1 0 l l 13.55E2 1 ND I ND 1 ND 13.17E7 l lLa-140 13.25E3 11.14E3 lLa-142 12.50E-4 17.98E-5 12.50E-5 l ND l ND i SD l1.58E1 l 14.86E4 l ND ll.43E5 l ND 14.08ES l lCe-141 16.56E5 l3.27E5 11.35E2 1 bT 13.91E2 l ND 11.36E7 l
) lCe-143 11.72E3 19.31E5 lCe-144 11.27EB 13.98E7 l6.7BE6 l ND 12.21E7 i ND ll.04E10 l ipr-143 11.46E5 14,38E4 17.25E3 1 SD l2.37E4 l ND l1.5EES l 0
lPr-)44 l 0 1 0 1 0 i ND 1 0 1 ND 1 l lNd-147 17,17E4 15.81E4 14.50E3 l ND l3.19E4 I ht 19.20E7 l 11.50E7 11.37E7 ) ND 16.57E7 l ht 13.46E9 l lEu-154 l1.66ES lHf-181 14.90E5 l1.79E6 12.21ES l ND 13.62E5 l ND l6.59ES l 13.83E4 11.72E. l ND 1 ND 1 SD 15.38E6 l lW-187 16.47E4 lNp-239 12.55E3 l1.83E2 11.29E2 1 ND l3.30E2 1 ND li.36E7 l (a) The child age group; refer t reference 11.14.5, I
e
APA ZZ 01003 !
Rev.[^Ilu l.11 .I TABLE 5 (Contd.) ;
ADULT PATWAY DOSE TACTORS (R ) FOR RADIONUCLIDES OTHER THAN NDPLE GASES
~
Intalation Pathway (mrem /yr) per (VCi/m') ,.
~
l l l l l l Total l l l lung l
I GI LLI [
Bone I Liver Body l Thyroid i Kidnev i ,
lNuclidel l '
l lH-3 l ND l1.26E+03 11.26E+03 l1.26E+03 li.26E+03 11.26E+03 l1.26E+03 l '
lBe 7- l4.27E+02 l9.68E+02 l4.70E+02 { ND l ND l4.21E+04 15.35E+03 l lC 14 1.82E+04 l3.41E+03 l3.41E+03 l3.41E+03 l3.41E+03 13.41Ee03 13.41E+03 l t
lNa-24 1.02E+04 l1.02E+04 11.02E+04 l1.02E404 l1.02E+04 l1.02E+04 l1.02E+04 l !
l: l1,32E+06 l7.71E+04 15.01E+04 l ND l ND l 'ND lo.64E+04 l lP-32 j ND l1,00E+02 l 5.95E+01 12.28E+01 11.44E+01 13.32E+03 l lCr-51 -l ND l9.84E+03 l1.40E+06 l7.74E+04 l lMn-54 l ND l3,96E+04 l6.30E+03 l ND l Mn-5 6 -- l ND ll.24E+00 l1.83E 01 l ND l1.30E+00 l9.44E+03 l2.02E+04 l '
ND l ND l7.21E+04 16.03E+03 l lFe-55 J2.46E+04 11.70E+04 13.94E+03 l
, lFe-59 l1.18E+04 l2.78E+04 l1.06E+04 l ND l ND l1.02E+06 11.88E+05 l ND l6.92E+02 l6.71E+02 1 ND l ND l3.70E+05 l3.14E+04 l lCo-57 l ND l9.28E+05 l1,06E+05 1 lCo 58 l ND l1.58E+03 l2.07E+03 l .ND l l1.15E+04 ll.48E+04 l ND l ND (5.97E+06 12.85E+05 l lCo 60 l ND ND ,1.78E+05 l1.34E+04 l- 4 lNi l4.32E+05 13,14E+04 .1.45E+04 l ND l lNi 65 11.54E+00 l2.10E-01 9.12E 02 l !
ND 1 ND l5.60E+03 l1.23E+04-l s lCu 64 l ND ll.46E+00 16.15E-01 l ND 14.62E+00 16.78E+03 14.90E+04 l lZn-65 'l3.24E+04 11.03E+05 14.66Ef04 l ND 16.90E+04 l8.64E+05 l5.34E+04 l lZn 69 l3.38E 02 16.51E-02 14.52E-03 l ND l4.22E 02 19.20E+02 l1.63E+01 l-ND ND 11.35E+04 i ND l ND l ND l1.04E+04 l lBr-82 l l ND l FD l2.32E+02 l ND ND l2.41E+02 l ND l lBr-83 l l-ED 13.13E+02 l ND l ND l ND l1.64E 03 l lBr-84 l ND l ND ND 10.00E+00 l lBr-85 l ND l ND 11.28E+01 l ND i l ND 11.35E+05-15.90E+04 l ND 1 ND l ND l1.66E+04.l lRb 86 l ND 13.87E+02 11.93E+02 l ND 1 ND l ND l3.34E 09 l JRb 88 l ND ND l0.00E+00 l ND l2.56E+02'lI.70E+02 l ND l l ,
lRb-89 l 18.72E+03 l ND l ND {1.40E+06 l3,50E+05 l ISr 89. 13.04E+05 l ND lSr-90 19.92E+07 l ND 16.10E+06 i ND _l ND 19.60E+06 (7.22E+05 l l lSr-91 16,19E+01 l ND l2.50E+00 l ND l ND [3.65E+04 11.91E+05 l lSr 92 l6.74E+00 l ND 12.91E-01 i ND l ND. l1.65E+04 l4.30E+04 I lY-90 l2.09E+03 l ND 15.61E+01 l ND 1 ND l1.70E+05 15.06E+05 1
, f4 -
. . . - , . - _ . . - . _ , - - . . . _ _ _ _ - . - _ . _ . - . . - . . _ . ~ , _ , _ _ _ _ _ . . _ . . _ . .
i APA ZZ.01003 Rev % 2 l Ne gn TABLE 5 (Contd.)
ADULT PATWAY DOSE TACTORS (R ) TOR RADIONUCLIDES OTHER THAN NOBLE GASE
~ '
Inhalation Pathway (mree/yr) per (pCJ/m ) 8
^ '
l l l j- l Total l l l Lung l
1 GI-Ltd I Liver l Body l Thyroid i Kidney I 1 lNuclidel J one ND l1.02E 02 l ND l ND 11.92E+03 l1.33E+00 l lY-91's l2.61E 01 l ND ND l1.70E+06 13.85E+05 l JY 91 ' l4.62E+05 l ND l1.24E+04 l l
. li.03E+01 1 ND 13.02E 01 i ND l ND l1.57E+04 l7.35E+04 l lY-92
[Y-93 l9.44E+01 l ND l2.61E+00 1 - ND l ND . l4.85E+04 l4.22E+05 l-
. lZr-95 l1.0'E+05 l3.44E+04 l2.33E+04 l ND 15.42E+04 l1.77E+06 11.50E+05 l lZr-97 l9.68E+01 l1.96E+01 19.04E+00 l -ND 12.97E+01 l7.87E+04 l5.23E+05 l lNb 95 l1.41E+04 17.82E+03 14.21E+03 l ND l7.74E+03 l5.05E+05 l1.04E+05 l '
lMo l ND l1.21E+02 l2.30E+01 l ND l2.91E+02 l9.12E+04 l2.48E+05 1 ND :4.42E 02 l7.64E+02 l4.16E+03 l lTc 99m l1.03E-03 l2.91E 03 l3.70E 02 l ND ti.08E-03 13.99E+02 l0.00E+00 l
- lTc-101 l4.18E 05.16.02E 05 15.90E 04 l '
- lRu-103 l1 53E+03 l ND l6.58E+02 i ND - 15.83E+03 l5.05E+05 l1.10E+05 l- '
iku-105 l7.90E-01 ND 13.11E 01 l ND l1.02E+00 l1.10E+04 l4.82E+04 l 1Ru-106 l6.91E+04 ND l8.72E+03 l ND l1.34E+05 l9.36E+06 19.12E+05 l
- lag-110ml1.08E+04 l1,00E+04 15.94E+03 i ND l1.97E+04 l4.63E+06 l3.02E+05 l lCd 100 j ND l3.67E'05 l1.31E+04 l -ND 13.57E+05 16.83E+05 15.82E+04 l N'O 19.44E+05 11.18E+05 l lSn-113 15.72E+04 12.18E+03-l4.39E+03 l1.24E+03 l ND 12.48E+06 l4.06E+05 l '
lSb-124 l3.12E+04 15.89E+02 11.24E+04 l7.55E+01 1 lSb-125 15.34E+04 15.95E+02 11.26E+04 15.40E+01 l ND. l1.74E+06 l1.01E+05 l lTe-125ml3.42E+03 l1.58E+03 14.67E+02 ll.0$E+03 l1.24E+04 l3.14E+05 - l 7 06E+04 lTe-127ml1.26E+04 15.77E+03 11.57E+03 - 13.29E+03 14.58E+04 l 9.60E+05 l 1.50 lTe-127_l1.40E+00 16.42E 01 l3.10E 01 l1.06E+00 15.10E+00 l6.51E+03 15.74E+
JTe-129ml9.75E+03 14.67E+03 11.38E+03 l3.44E+03 13.66E+04 l1.16E+06 l3.83E
-lTe-129 14.98E-02--12.39E 02 l1.24E 02 l3.90E-02 11.87E 01 l1.94E+03 l1.57E+02 l lTe-131ml6.99E+01 14.36E+01 l2.90E+01 l5,50E+01 13.09E+02_l1.46E+05-l5.56E+05 l
~lTe-131'l1.11E-02 l5.95E 03-l3.59E-03 l9.36E-03 14.37E-02 11.39E+03 [1,84E+0'1 l >
lTe-132 12.60E+02 12.15E+02 li.62E+02 l1.90E+02. l1.46E+03 12,88E+05 l5.10E+05 l- <
ND l7.69E+03 l 11-130 l4.58E+03 l1.34E+04 13.2SE+03 11.14E+06 12.09E+04 i ND l6.2SE+03 l lI131 12.52E+04.13.58E+04 l2.0$E+04 11.19E+07Ll6.13E+04 l; ND - - l 4 . 06E+0 2 -- l lI-132 11.16E+03-l3.26E+03 11.16E+03 11.14E+05 15.18E+03-l ND lS.88E+03 l lI-133 lS.64E+03 l1.48E+04 14.32E+03 12.15E+06 12.58E+04 i ND ll.01E+00 i
!!-134 :!6 J4E+02 11.73E+03 16.15E+02 12.98E*04 !2.75E+03 l r l
63
- 4 ^7 e gp---g-i ---w'N,+a +m.? gym,W'+-Mh-igi %g.g'g=.,,.re--3-=4--ed- --.h-.w-rw+, e .aw re - t--n+d e(yi*w.edhwn--g----wy__.m-ie* re - e y wwgw -wee ums.or-se9 tam-aerND+er'*--='m'-w'elw-+unmwe e--e m--unm'wb w-e e '*-
I APA 22 01003 )
2 J Rev./'obiqj TABLE 5 (Centd.)
ADULT PATKWAY COSE TACTORS g(R ) FOR RADIONUCLIDES OTHER Tu^N NOBLE GASES Inhalation Pathway (mram/y:) per (uCi/m')
f-l l l l Total l l l l l '
lNuclidol Bone i Liver 1 Body i Thyroid i Kidney I Lung i GI LLI l lI-135 J2.68E+03 l6.98E+03 12.57E+03 14.48E+05 11.11E+04 l ND l$.2SE+03 l lCs 134 l3.73E+05 18.48E*05 17.28E+05 l ND l2.87E+05 l9.76E+04 11.04E+04 l lCs-136 l3.90E+04 l1.46E+05 l1.10E+05 l ND 18.56E+04 11.20E+04 l1.17E+04 l ;
lCs 137 l4.78E+05 16.21E+05 14.2SE+05 l ND 12.22E+05 l7.52E+04 l3.40E+03 l lCs-138 l3.31E+02 16.21E+02 l3.24E+02 l ND 14.80E+02 la.86E+01 11.86E-03 l
- lBa 139 l9.36E-01 16.66E 04 l2.74E-02 i ND 16.22E-04 l3.76E+03 18.96E+02 l lBa 140 l3.90E+04 14.90E+01-l2.57E+03 i ND 11.67E+01 l1.27E+06 l2.18E+05 l lBa-141 l1.00E-01 17.53E-05 13.36E 03 l ND l7.00E-05 l1.94E+03 l1.16E-07 l
- JBa-142 l2.63E 02 l2.70E-05_l1.66E-03 l ND l2.29E-05 l1.19E+03 l0.00E+00 l
[La-140 l3.44E+02 11.74E+02 l4.58E+01 l ND l ND l1.36E+05 14.58E+05 l ND l ND [6.33E+03 j2.11E+03 l lLa-142 l6.83E-01 13.10E 01 l7.72E-02 l 16.26E+03 l3,62E+05 l1.20E+05 l ND lCe 141 11.99E+04 11.35E+04 11.53E+03 l
- )Ce-143 l1.86E+02 l1.38E+02 11.53E+01 1- ND l6.08E+01 l7.9CE+04 l2.26E+05 l lCe-144 l3.43E+06 l1.43E+06 l1.84E+05 i ND 18.48E+05 17.78E+06 18.16E+05 l ,
ipr 143 l9.36E+03 13.75E+03 14.64E+02 i ND 12.16E+03 12.81E405 l2.00E+05 l lPr-144 l3.01E-02 l1.25E-02 l1.53E-03 i ND l7.05E-03 l1.02E+03 12.15E-08 l lNd-147-15.27E+03 16.10E+03 l3.65E+03 I ND 1'.56E+03 12.21E+05 11.73E+05 l leu-154 15.92E+06 l7.28E+05 l5.18E+05 l ND l3.49E+06 l4.67E+06 12.72E+05 l lHf-181 l1.41E+04 lo.82E+04 l6.32E+03 l ND l1.48E+04 l6.85E+05 11.39E+05 l j8i48E+00'l7.08E+00 12.48E+00 i ND 1 KD 12.90E+04 l1,55E+05 l lW-187 lNp-239-l2.33E+02 12.26E+01 l1.24E+01 1 ND 17,00E+01 13.76E+04 11.19E405 l
,O I
t 66 -
e-+--+r--.-+ y-vw-.w.r, , -4,n,rw*,u--,,n-- - - , - - -
VdY 22 ot00C '
MM' &
iyg13[ .ygoutp-( l t'
YOSI'l dY1HMYA 00S3 JY0103S )Hd J03 3VGIQNS011G3S 01H331HYN NOE13 DYS3S tu['vissiou dv lo h i t
)n am/A2( det. )tr3y/y(
l 1o291 __ , J I I I l l._ l l lsnotypp goua l 1yao t. l gopA~ l 1y4,roip l xypuoA l 1num l 01-ITI I lI-tCS !0'003+00 10'003+00 lO'003+00 10'003+00 10'003+00 l NC 10'003+00 l l35 icv 19'f43+09 lt*f93+06 11't93+06 l NC lf*093+09L11'993+09 it*t73+04-l los tC9 !t*t03+OL 11'493+04 lC'tt3+OL l NC lZ'953+OL lC'9C3+09 15'702+09 l IDS tCL 19'tt3+09-11't63+06 ll'913+09 l NC 17*013+09 li'C?3+09 lZ'Ct3t04 l l0s-tC9 lO*003+00 lO*003+00 10'003+00 l NC l0'003+00 lO*003+00 l0*003+00 I lE# IC6 !0'003+00 l0'003+00 !0'003+00 l NC 10'003+00 i0'003+00 10'003+00 l -
n l
- 168 110 lE'943+OL,lC'913+Oi-li'993+09 l NG lt*EC3+07 lI'043+01 lf'613+OL l- ,
its-tyt 10'003+00 10'003+00 10'003+00 l Nc 10 003+00 10'003+00 10'003+00 1 lEs tnI 10'003+00 10 003+00 10 003+00 I Nc 10 003+00 10 003+00 10'003+00 1 118-170 lC'tt3 OZ 11'9L3 07 li'653 0C l NC l NQ I Nc lt*C43+0C l 118-t77 10'003+00'10'003+00 10*003+00 l NQ l Na I Nc 10'003+00 l 13*-171 11'703+07 16*763+0C lt*093+0C l NC 14*?t3+0C I NG lC'9C3+OL l NG 19'573 0C l NQ 15'553+02 l
)08-11C lI*0I3 OZ 11'763+01 lI'973-OC 1 10*-tiv 11'793+09 19'063+05 ll'973+07 l NC lC'913+OS l NQ 11'6t3+09 I ld2-17C lZ*103+07 I9'103+0C lt'073t0C l NC l1*953+0C l NQ l6'I93+0L l l Nc 10 003+00 ! ;
laJ-tit 10'003+00 10 003+00 10'003,00 I NO 10'003+00 I i NC lt*Lt3+0C l NG lC*6t3+OL !
INP 17L lL*043+0C 19't43+0C li'963+ot l' NQ iL*t;3+OW l 13n-tgv 19*0I3+09 16*993+05 lL*013+05 I NC 17*Lt3+09 l 1HJ 191 lC'013+09 11'793+04 lI"C53+09 l NG lC*t93+09 l NQ- li'993+tO l ,
iM-194 lZ'043_OZ lI'LC3-07 19'053-OC l NC l NQ. l NG lS'943+00 ( ,
NG 19*013-02 I NC !S'C03+0C !
lNd EC6 it*9C3 01 lE'563 ot ll'7C3 07 l f
?! -
l APA 22 01003 Hev. /;?
'.M A y TABLE 5 (Contd.)
- ADULT PATWAY DOSE TACTORS (Rf ) TCR FADICNUCLIDES OTHER THAN NOBLE GA!tS l Grass-Cow M1 A Pathway l
- (m* mrrm/yt) per (uCi/sec) l l l- l Total l l _ l Lung l l lNuclidel Bone l Liver l- Body l Thyroid l Kidney l l GI-LLi j, lH-3 l ND l7.63E+02 l7.'63E+02 l7.63E+02 l7.63E+02 l7.63E+02 l7.63E'02 l ,
lBe-7 jl.63E+03 l3,72E+03 l1.81E+03 l ND -l3.93E+03 l ND -l6.45E+05 l lC-14 _ -l2.63E+08 l5.27E+07 15.27E+07 l5.27E+07 15.27E+07 l5.27E+07 l5.27E+07 l lNa 24: l2.44E+06 l2.44E+06 12.44E+06 12.44E+06 l2.44E+06 l2.44E+06 12.44E+06 l ,
lP-32 11.71E+10 l1.06E+09 l6.61E+08 l ND l ND l ND li.92E+09 l 3 (Cr-51 l- ND:- l- ND l2.86E+04 l1.71E+04 l6.30E+03 l3.79E+04 l7.19E+06 l ,
lMn-54 l_ ND 18.42E+06 l1.61E+06 l ND l2.50E+06 l ND l2.58E+07 l lMn-56 1 ND 14.20E 03:l7.45E 04 1 ND l5.33E-03 l ND l1.34E-01 l lFe-55 12.51E+07 ji.74E+07 l4.03E+06 l ND l ND 19.68E+06 19.96E+06 l
[Fe-59 l2.97E+07 l6.98E+07 l2.68E+07 l ND l ND. l1.95E+07 12.33E+08 l-lCo-57 l- -ND l1.28E+06 12.13E+06 l ND l ND l: ND l3.25E+07 l lCo-58 l- ND 14.72E+06 l1.06E+07 l ND l ND l ND_ l9.56E+07 l lCo*60 l -ND l1.64E+07 13.62E+07 l ND l ND l ND 13 08E+08 l lNi-63 16.73E+09 l4.76E+08 l2.26E+08 l ND l ND l MD l9'.73E+07 l lNi-65 l3.71E-01 l4.82E-02 l2.20E 02 l ND l ND l ND l1.22E+00 l lCu 64 l ND l2.39E404 !1.12E+04 l ND 16.01E+04 l ND 12.03E+06 l lZn-65 l1.37E+09 l4.37E+09 l1.97E+09-l. ND l2.92E+09 l ND l2.75E+09 l lZn-69 l0.00E+00 10.00E+00'l0.00E+00 l ND l0.00E+00 l -ND l0.00E+00 l lBr-82 j ND l ND 13.23E+07 l ND l ND l ND 13.71E+07 l !
lBr-83 l- ND l ND 19.75E-02 l ND- l ND l ND ll.40E-01 l lBr l ND l ND l0.00E+00 l - ND l ND l ND (0.00E+00 l lBr-85. l ND _l_ ND l0.00E+00 l ND i ND l ND l0.00E+00 l lRb-86 1 ND, l2.60E+09 l1.21E+09_l ND l ND l ND l5.12E+08 l lRb-88 l ND l0.00E+00 l0.00E+00 l ND l. ND l ND 10.00E+00 l lRb-89 -l . ND ' l0.00E+00 l0.00E+00 l- ND l ND l ND l0.00E+00 l-lSr 89 l1.45E49 l ND- l4.17E+07 l _ND l_ SD -l ND l2.33E+08 l JSr-90 14.68E+10-l ND- ll.15E+10 l ND l 'ND l ND ll.35E+09 l lSr l2.90E+04 l ND. 'll.17E+03 l ND l ND l ND l143GE+05 l
-lSr-92 l4.90E-01 l- ND l2.12E-02 l ND l ND l ND l9.71E+00 l~
lY-90__ [7-09E+01 l_
. ND ll.90E+00 i ND l ND l ND l7.52E+03 l .;
._ _ . _ _ . . _ ,_ _ . _ . . ._ _ . . . . _ . . _ _ _ _ . - _ _ _ . . . . _: ____,__.w. -
APA 22 01003 Rev /2
'ywn
(
TAtLE 5 (Centd.)
ADULT PATINAY DOSE FACT 0".5 (R ) FOR RAD:GNUCLCES OThER TRAN MLE CASES
~~
Grass-Cow Hilk Pathway (m8 mrem /yr) per ('.:C1/sec) l l l l l Total I l l l Bene Liver Body 1 Thyroid 1 Kidney i Lung i GI-LLI I lSuclidel ! i ND l0.00E+00 l ND 1 ND l ND 10.00E+00 l lY-91m 10.00E+00 l 18.59E+03 i ND 12.30E+02 i ND l ND l ND I4.73E+06 l lY 91 ND ND 19.80E-01 l lY-92 l5.59E 05 l ND l1.63E-06 i ND l 1 ND l6.18E 03 i ND 1 ND l ND 17.09E+03 l lY-93 12.24E 01 l 19.44t+02 13.03E+02 12.0$E+02 1 SD 14.75E+02 i ND l9.59E+05 i
!Zr 95 14.34E-01 18.75E-02 14.00E-02 l 11.32E-01 1 ND 12.71E404 l lZr-97 12.79E+08 {
lNb 95 18.25E+04 14.59E+04 12.47E+04 1 .iD l4.54E+04 l ND jHo-99 ND 12.48E+07 14.72E+06 i ND [5.61E+07 l ND 15.74E&O7 l i
lTc-99m 13.33E+00 19.40E+00 11.20E+02 i ND ll.43E+02 14.61E+00 {5.'6E+0? l lTc-101 10.00E+00 10.00E-00 10.00E+00 1 ND l0.00E+00 10.00E+00 10.00E+0) l ND la.39E+02 l ND 13.59E+03 I ND 1 1.19E+d5 l lRu-103 11.02E+03 i 15.25E-01 1 lRu-105 18.5BE-04 l ND 13.39E-04 l ND 11.11E 02 l ND l2.58E+03 i ND 13.94E+04 1 11.32E+06 l 1Ru-106 12.04E+04 i 12.20E410 )
lAg-110ml5.82E+07,15.39E+07 l3.20E+07 l ND ll.06E+08 l ND lCd-109 i ND l1.13E+06 l3.95E*04 I ND l 1.08E+06 l ND ll.14E+07 l ST I ND 14.02E+08 1 lSn 113 l1.34E+0S 13.81E+06 17.73E+06 12.18E+06 l iSb-124 l2.57E+07 14,86E+05 l1.02E+07 16.24E+04 i ND I2.00E+07 17.31E'73 l lSb 125 12.04E+07 12.28E+05 l4.87E+06 12.0SE+04 l ND l1.5BE+07 (2.25E+08 l
- ND l6.51E+07 l lTe-125 mil.63E+07 15.90E+06 12.18E+06 14.90E+06 16.63E+07 i ND l1.54E+08 i ITe-127 mis.5EE+07 11.64E+07 (5.58E+06 11.17E+07 11.86E+08 l ND l5.16E+04 l iTe 127 16.5;E+02 12.35E+02 11.41E+02 14.84E+02 12.66E+03 i ND 13.03E+08 l lTe 129m16.02E*07 12.25E+07 19.53E+06 12.07E+07 12.51E+08 l ND (2.15E-10 l lTe 129 12.84E-10 11.07E-10 10.00E+00 12.18E-10 l1.19E-09 i ND (1.75t+07 I JTe-171ml3.61E+05 11.77E+05 ll.47E+05 12.80E+0! ll.79E+56 ND i 10.p0E+00 l ITe-131 10.CCE+00 10.00E+00 10.00E+00 10.00E+00 10.00E+00 l ND 17.35E+07 l ;
lTe-132 12.40E+06 11.55E+06 11.46E+06 l1.7;E+06 11.50E+07 l 14.21E+05 11.24E+06 l4.91E+05 11.05E+0B ll.94E+06 i ND 11.07E+06 1 11-130 11-131 12.97E+0S 14.25E+08 12.43E+0B 11.39E+11 17.2BE+0S I ST ll.12E+08 l 11 65E-01 14.42E-01 11.55E-01 11.53E+01 17.04E-01 i ND (S.30E-02 l lI-132 ND 16.07E*06 l
!7-133 13.SSE+06 16.75E+06 12.06E+06 19.92E*08 11.18E+07 i 10.00E+00 [0.00E+00 10.00E+00 l0.00E+00 10.00E+00 l SD 10.00E+00 1 11-134 l
APA-2Z 01003 Rev. [2
' Gi w TABLE $ (Contd.)
ADULT PATHk'AY DOSE TAC *CRS (R ) TCR RADIONUCLTDES OTHER THAN NDELE CASES Grad Ccw hilk Pathway (m8 mrem /'fr) per (VCi/sec) 1 Total l l l l l l l l lNuclidel Pene l Liver i Body 1 Thyroid ! Kidney I Lung l GI-LLI l lI 135 li.29E+04 13.37E+04 11.25E+04 12.23E+06 15.41E+04 l ND 13.81E+04 l lCs-134 l5.65E+09 11.35E+10 11.10E+10 l ND 14.35E+09 11.45E+09 12.35E+08 l lCs 136 12.63E+08 11.04E+09 17.48E+08 i ND 15.79E+08 17.93E+07 11.18E+08 l lCs-137 17.35E+09 11.01E+10 16.61E+09 i ND 13.43E+09 11.14E+09 11.95E+06 l lCs-138 10.00E+00 10.00E+00 10.0CE+00 l ND 10.00E+00 10.00E+00 l0.00E+00 [
13a 139 14.44E-08 l0.00E+0n 11.30E-09 l ND 10.00E+00 10.00E+00 17.88E-08 l lBa-140 12.69E+07 13.3Ei.+04 11.76E+06 i ND 11.15E+04 11.93E+04 l5.54E+07 l lBa-141 10.00E+00 10.00E+00 l0.00E+00 l NT 10.00E+00 10.00E+00 10.00E+00 l lBa 142 10.00E+00 10.00E+00 10.00E+00 l ND l0.00E+00 10.00E+00 10.00E+00 l lLa 140 14.51E+00 12.28E+00 16.01E-01 1 ND l ND l ND (1.67t+05 l lLa-142 11. 87E-11 18.49E-12 12.12E-12 l ND l ND l ND 16.20E 08 l lCe 141 14.85E+03 13.28E+03 13.72E+02 l ND 11.52E+03 l ST 11.25E+07 l lCo 143 l4.16E+01 13.0SE+04 13.40E+00 l ND 11.35E+01 l ND l1.15E+06 l lCo-144 l3.58E+05 11.50E+05 11.92E+04 l ST 18.87E+04 l ND ll.21E+08 l ND 13.66E+01 l hT 16.92E+05 l lPr 143 11.58E+02 (6.34E+01 17.83E+00 i lP:-144 10.00E+00 10.00E+00 10.00E+00 1 ND 10.00E+00 1 ND 10.00E+00 l lNd-147 19.42E+01 l1.09E+02 16.51E+00 l ST 16.36E+01 1 ST l5.23E+05 l lEu-154 12.37E+04 12.91E+03 12.07E+03 l ND 11.39E+04 1 ND l2.11E+06 1 lHf 181 11.42E+02 16.92E+02 16.41E+01 1 ND 11.49E+02 i ND [7.87E+05 I ik'-187 16.52E+03 15.45E+03 11.91E+03 i ND l ND l ND ll.78E+06 l lSp-239 13.69E+00 13.62E-01 12.00E-01 1 ND 11.13E400 1 ND 17.43E+04 1
. ~n .
1 APA ZZ 01003 4 Rev./'2_ l j
Yhf/
[ TMLE 5_ (Centd. ) ,
l,,-
ADULT PATHVAY DOSE TACTCF.S 3 (2 ) FOR RADIONUCLICES OTHER THAN NOBLE GASES Grt.ss A G oat Milk Pathway (m8 mrem /yr) per (11Ci/sec) i-l l l Total l l l l l Bene Liver Body l Thyroid 1 Kidney i Lung l GI-LLI I ;
-lNuclidel l lH-3 l ND 11.56E403 l1.56E+03 11.56E+03 l1.56E+03 11.56E+03 l1.56E+03 l l1,96E+02'l4.47E+02 l2.17E402 l ND l4.72E+02 l - ND l7.74E+04_l lBa-7 >
lC-14 12.64E+08-l5.27E+07 l5.27E+07 15.27E+07 l5.27E+07 15.27E+07 l5.27E+07 l lNa-24 l2.93E+05 12.93E+05 l2.93E+05 ]2.93E+05 ND l2.93E+05 ND l ND12.93E+05 l2.31E+09 l2.93E+05 l l ,
l lP l2.0$E+10 11.28E+09 l7.94E+08 }
lCr-51--l ND l ND- 13.43E+03 l2.05E+03 17.56E+02 14.56E+03 18.63E+05 l ND -11.01E+06 l1.93E+05-l. ND _l 3.01E+05 i ND l3.10E+06 l lMn-54 l l1.61E 02 l lMn-56 i ND . 15.04E-04 l8.94E-05 l ND -l6.40E-04 l ND lFe-55 13.27E+05 ]2.26E+05 15.26E+04 l ND l ND (1.26E+05 l1.30E+05 l ND l ND 12.54E+05 13.03E+06 l
-lFe-59 13.87E+05 19.08E+05 l3.48E+05 l_
l1.54E+05 12.56E+05 l ND l ND l ND l3.90E+06 l lCo-57 -l- ND ND ND l1.15E+07'l ND l l 4
lCo-58 l .ND 15.66E+05 11.27E+06 l ND l ND l ND 13.70E+07 l lCo 60 l ND l1.97E+06 14.35E+06 l ND l ND l ND l1.17E+07-l lNi 63 18.0SE+08-l5.60E+07 12.71E+07 l ND ND l ND l1.47E-01 l l
lNi-65 l4.46E-02 l5.79E-03 l2.64E-03 l 12.66E+03 li.25E+03 i ND 16.71E+03 i ND 12.27E+05 l lCu-64 i ND
.ND l3.51E+08 l ND l3.30E+08 l lZn-65 -l1.65E+08-15.24E+08 12.37E+08 l ND - l 0. 00E+00_ _ l lZn-69 10.00E+00 l0.00E+00 l0.00E+00 i ND .10.00E+00 i ND i3.88E+06 l' ND l ND l ND l4.45E+06 l lBr-82 l _ND l ND ND ND l1.69E-02 l_
lBr-83 1 ND l- ND l1.17E-02 l l l ND l' ND 10.00E+00 l .ND l ND l ND l0.00E+00 l lBr-84 l- ND ND l ND lo.00E+00 l
-lBr-85 _I ND l ND _ _ l0.00E+00 i l ND l3.12E+08 11.45E+08 i ND i ND l ND l6.15E+07 l lRb-86 -l_
ND ND 10.00E+00 l lRb-88 l- ND l0.00E+00 l0,00E+00 l ND l l
_0.00E+00 10.00E+00 l ND l ND 1 ND l0.00E+00 l lRb-89. I ND l ND 18.75E+07 l ND 1 ND i ND l4.89E+08-l ISr-89 l3.05E+09 l l2.84E+09 l lSr-90 19;84E+10-l ND l 2. 41E+10 1. ND l ND - -l- ND ND l2.46E+03 l- ND l ND l ND l2.90E+05 l
- l S r-91' l6.09E+04-l- ND ND l2.04E+01 l lSr-92 -l1,03E+00 l ND 14.45E-02 l- ND i l-ND l2.2SE 01 l ND j ND l ND l9.03E+04 l lY 90 16.51E+00 1 -
?
_..u._--.-__._.-.__._._.
~ - _ _ _ _ _ _ - - - - - - _ _ _ - . _
k APA ZZ 01003 Rev. / i?
0.'b/Of TABLE 5 (Centd.)
)
ADULT pan"a'AY DOSE FACTORS g(R ) FOR RADICNUCLIDES CTHER THAN NOBLE GASES Grass-Gost-Milk Pathway (m* mram/yr) per (pCi/sec) f l l l l l J l Total l l l Thyroid l Kidney I Lung i GI-LLI l i Liver l Body lNuclidel Pone ND 10.00E+00 l ND l ND 1 ND l0.00E+00 l lY-91m 10.00E+00 i ND l ND l ND l5.68E+05 l
)Y-91 l1.03E+03 i ND 12.76E+01 1 SD l1.96E 07 i ND l ND l ND l1.18E-01 l lY-92 16.72E 06 i ND ND l ND l8.52E+02 l lY-93 12.69E-02 l ND 17.42E-04 l l ND 15.70E+01 i ND l1.15E+05_l lZr 95 11.13E+02 13.63E+01 12.46E+01 1 ND l1.59E-02 l ND l3.25E+03 l lZr-97 15.21E-02 ll.05E 02 l4.80E-03 l ND l3.35E+07 l ND l5.45E+03 l
-lNb 95 19.92E+03 15.52E+03 12.97E+03 l ND l6.74E+06 l- ND l6.90E+06 l lHo 99 l ND 12.98E+06 l5.66E+05 l ND l1.71E+01 15.53E-01 l6.68E+02 l lTc-99m: 13.99E-01 11.13E+00 11.44E+01 1 ND 10.00E+00 l0.00E+00 l0.00E+09 l.
lTc-101 10.00E+00 l0.00E+00 10.00E+00 l ND 15.27E+01 l ND 14.67E+02 l ND l1.43E+04 l lRu-103 l1.22E+02 l ND l1.33E-03 l ND 16.31E-02 l lRu-105 11.03E-04 l ND (4.07E-05 l ND l3.10E+02 i ND l4.73E+03 l ND l1.59E+05 l
- lRu-106 12.,CSE+03 l ND l2.64E+09 l lAg-110ml6.99E+06 l6.47E+06 l3.84E+06 l- ND l1.27E+07 l ND (1,30E+05 l ND l1.37E+06 l lCd-109 l' ND ll.36E+05 l4.74E+03 l ND ND [4.83E+07 I l
lSn-113 11.61E+07 l4.5BE+05 19.28E+05 12.62E+05 l ND l2.41E+06 l8.78E+07 l
- lSb-124 13.09E+06 15.84E+04 11.23E+06 l7.50E+03 lht 11.89E+06 l2.70E+07 l lSb-125 l2.46E+06 12.74E+04 l5.84E+05 l2.50E+03 l ND l7.81E+06 l lTe-125ml1.96E+06 l7.09E+05 l2.62E+05 15.89E+05 17.96E+06 ND l l1.84E+07 l lTe-127ml5.50E+06 11.97E+06 16.70E+05 11.41E+06 l2.23E+07 ND i l6.19E+03 l lTe-127 17.85E+01 12.82E+01 11.70E+01 15.82E+01 13.20E+02 l ND l3.64E+07 l ,
lTe-129ml7.23E+06 12.70E+06 l1.14E+06 12.48E+06 l3.02E+07 ND l 10.00E+00 l lTe-129 10.00E+00 10.00E+00 10.00E+00 [0.00E+00 11.43E-10 NDl l2.11E+06 l ,
lTe-131ml4.34E+04 12.12E+04 l1.77E+04 13.36E+04 12.15E+05 ND l l0.00E+00 l jTe-131 l0.00E+00 l0.00E+00 10.00E+00 (0.00E+00 10.00E+00 l ND l8.83E+06 l lTe-132 12.89E+05 11.87E+05 11.75E+05 12.06E+05 l1.80E+06 l ND l1.28E+06 l 11-130 l5.05E+05 l1.49t+06 15.88E+05 11.26E+08 12.32E+06 l ND l1.34E+08 l lI-131 13.56E+08 15.09E+08 l2.92E+08 11.67E+11 l8.72E+08 lND l9.95E-02 l
- 11-132 11.9BE-01 15.29E-01 11.85E-01 11.85E+01 l8.43E-01 i ND l7.27E+06-l 11-133- 14.65E+06 18.09E+06-l2.47E+06 11.19E+09 11.41E+07-l ND 10.00E+00 1
!! 134 10.00E*00 10.00E-00 l0.00E+00 11.15E *0 l0.00E+00 i
APA-2t 01003 Rev / 2 W/ VI T,}_Q 5 (Contdd ADUL'I PATHWAY DOSE TACTORS (Rj ) TOR RADIONUCLIDES C-TMR THAN NOBLE GASES
'~
k Grass-Gon Milk Patd6 (m8 mrem /yr) per (11Ci/sec) l l l l Total l "l l 1 lNuclidel Bone 1 Liver i Body _ _@rMd 'l _ K idnav,_[ Lung i GI LLI 1 11-135 l1.54E+04 l4.04E+04'll.49E+04 12.67E+06 16.4aE+04 ! ND 14.57E+04 l lCs-134 l1.70E+10 l4.04E+10 13.30E+10-l ND l1.31E+10 l4.34E+09 l7.07E+08 l lCs 136 l7.91E+06 l3.12E+09 12.25E+09 j ND l1474E+09 12.3SE+08 13.55E+08 l lCs 137_J2.22E+10 13.03E+10 li.99E+10 l ht 11.03E+10 13.42E+09_l5.87E+08 l lCs-138.l0 00E+00=l0.00E+00 l0.00E+00-1 ND 10s00E+00 l0.~00E+00 l0.00E+00 l-lBa-139 l$.34E-09 l3.08E 12 l1.55E 10 l ND 13.55E-12 l2.16E-12-l9.46E 09 l lBa-140-13.23E+06-l4.06E+03 l2.12E+05 l ND 11.3BE+03 l2.32E+03 l6.65E+06-1 IBa-141 l0.00E+00 10.00E+00 (0.00E+00 l KD iO.00E+00 l0.00E+00-l0.00E+00 l lBa-142-l0.00E+00 l0.00E+00 l0.00E+00 l ND 10.00E+00 l0.00E+00 l0.00E+00 l
, _ lLa-140 15.42E-01 l2.73E 01 17.22E 02 l ND l ND l ND l2.01E+04 l lLa-142 l0.00E+00 l0.00E+00=l0.00E400 l ND l ND l ND l7.45E-09 ND l1.83E+02 l ND 11. 50E+06 lCo 141^l5.82E+02 l3.94E+02 14.46E+01 l
.JCe-143 j4.99E+00 l3.69E+03 14.09E-01 l ND l1.43E+00 l ND ll.38E+05 l lCo 144 ja.30E+04 l1.60E+04 l2.31E+03 l ND _{1.07E+04 l ND l1.45E+07 l lPr-143 l1.90E+01=17.61E+00-19.40E-01 l ND 14.39E+00-l . ND l8.31E+04 1
'lPr-144 l0.00E+00-l0.00E+00 10.00E+00 l ND l0.00E+00 l ND l0.00E+00 l lNd-147 l1.13E+01 l1.31E+01 17.82E-01 i ND '.7.64E+00 l ND 16.2SE+04-!
lEu-154 l2.84E+03 l3.49E+02 l2.49E+02-l_ ND _ ll.67E+03 l ND l2.53E+05 l lHf-181 ll.71E+01 lS.31E+01 17.70E+00-l ND l1.79E+01-l- ND 19.46E+04 l lW 187 l7.83E+02 16.54E+02.l2.29E+02 l ND l ND- l ND l2.14E+05 l lNp-239 l4.43E-01 14.35E-02 12.40E-02 l ND l1.36E-01 1 ND IB.93E+03 1
. ?j e I
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- ld-CU lt*t03+06 1s't13+04 lf*1C3+ot l NQ l NG l NG lI'ts3+os !
-102 51 l- NQ l NC li'973+01 ]t'4s3+07 lI'ot3+ov 19't93+ov ll't43+ot I l luu-sv I xa lC tC3+os-IS*st3+ot l- xa tt3+ot I - Nc 16 563+09 i luu-59 I Nc- li'903+ot 1t'ev3+00 l- Nc ls'oC3+ot I sa 15 t03+02 ll*-ss lt't03+os li'vf3+os lC'ts3+ot I Nc lc' I sa 1s 083+0t le'tt3+ot.I 1-138-76 -11'393+09 lZ'693+os 11't73+08 l NQ l NG le'ts3+ot 16*ss3+os l l30-54 l NQ- lI'tt3 tot 11'6f3+04 l NC l NQ l NG U*643+os I l30 58 l NG lC'043+ot 19's63+oL l NQ l Na l NG 9'EC3+08 l
- loo 90 I Na lt 9t3+os lC 963+os I Nc I sa 1 Na lC*t73+06 1 INT-9C 11 013+t0 lt*tt3+os lC'v63+os I Na I sa I Nc 11's03+09 I INT-95 19't93+ot 19*003+0o lC'9f3+oO l NQ l NC- l NG lc'oC3+ot I ton 9v I Nc 16 303+oC le C33voC I Nc lt'tt3+ov I sc 1t 9v3+05 I lgu-95 lC*tt3+os 1t'013+06 11'f93+09 l NQ 19*453+09 l Nc C93+os I 12u 96 C NQ 19's53-09 l NC 19'ssi It' 09 1 ls2 er l$'it3-09 I Nc III*053-05 na li' l4's?3-ot 03+09 l -INc I sa I sa tt3+09 I la2-sC I Na I Nc~ lC*tt3+oc I Na I sa I sa lI'vs3+co lv' I
-is2-ev i sa I sa 1o'003+a0 I Na- -l sa 1- Nc 1o'003+00 I las si l- Nc l- sa lo'oc3+oc I sc l Nc I Nc 10 003+00 l luq-89 l NQ it*t63+os lt'ot3+os I sa -1 Nc I sa lv CC3+ot I.
189-88 I Na 1o4 003+00 1o 003+0o I Nc I- Nc 1- Na 10 003+00 l iuq-96 l sa 10 003+00 1o003+0o I Nc I Na 1 xc 10 003+00 I 1151-86 6t3+06 l NC li's93+os l NQ l NG l NG 11*903+06 !
lS2-60 -16'of3+II 19' 1 NG it*183+tI l- NC 1- NQ l NQ it*ts3+to I lt*1$3+09 l-
!t'tC3+ov l NQ NG NG IS2 61 lC of3+oS l NQ l l .
lS2-6t= ivttirot l-- NG li'sf3+ot l NC I .NQ I NG le'793+oC~1 11-60 li'CC3+Oi l NC lC'it3+ot l NG l NC l NC ll'tt3+os I
- i- -
l i APA ZZ 01003 Pev. /2 QTWll TABLE 5 (Contd.)
)
ADULT PATH".'AY DOSE TACTORS g (R ) FOR RADIOSUCLIDES OTHER THAN N0 ELE GASES Vegetation Pathway (m mrem /yr) per (pCi/sec) 8 l
[ l l l Total l 1 l l i GI-LLI 1 Liver- 1 Body i Thyroid 1 Kidney I Lunt l lNuclidel Pone i jY 91m 15.24E 09 l ND l2.03E 10 1 ND l ND l ND l1.54E-08 l N'D l1.37E+05 l ND l ND l- ND l2.81E+09 l l lY 91 'l5.11E+06 i ND ND l1.60E+04 l ND 12.68E 02 ] ND l l lY 92 _l9.16E 01 l ND ND l5.38E+06 l ND 14.68E+00 l ND l l lY 93 l1.70E+02 l ND l1.19E+09 l lZr 95 l1.17E+06 l3.77E+05 l2.55E+05 l ND l5.91E+05 l ND . l1,03E+02 l ND 12.11E+07 l l
_ lZr 97 13.37E+02 l6.81E+01 13.11E+01-l ND 17.83E+04 l ND l4.81E+08-l lNb 95 11.42E+05 17.92E+04 14.26E+04 ' ND l1.43E+07 l lMo-99 10.00E+00 16.15E+06 11.17E+06 ND l1.39E+07 i ,
lTc-99m-l3.10E+00_l8.77E+00 jl.12E+02 L ND l1.33E+02 (4.30E+00 l5.19E+03 l-l lTc 101 l0.00E+00 10.00E400 10.00E+00 l ND l0.00E+00 l0.00E+00 10.00E+00 l I ND 12.06E+06 l ND l1.82E+07 1 ND l5.57E+08 l
- 1Ru 103.l4.77E+06 i ND 13.30E+04 l t lRu-105 15.39E+01 l ND l2.13E+01 l ND 16.97E+02 l
' ND (2.44E+07 l ND l3.72E+08 l ND l1.25E+10 l lRu-106 l1.93E+08 i ND l3.98E+09 l lAg-110mit.05E+07 l9.75E+06 l5.79E+06 l ND l1.92E+07 l ND -l8.00E+07 l ND l8.43E+08 l '
lCd-109'l0.00E+00 l8.36E+07 l2.92E+06 l ND l ND l1.2SE+09 l l$n 113 l4.16E+08 11.18E+07 12.40E+07_l6.75E+06 l
- jSb 124 11.04E+08 11.96E+06 l4.11E+07 l2451E+05.I ND 16.07E+07 l2.94E+09 l lSb-125 11.37E+08 l1.53E+06 13.25E+07-11.39E+05 l ND l1.05E+08 l1.50E409 l ND l3,86E+08 l lTe-125ml9.66E+07 13.50Ev07 l1.29E+07'l2.90E+07 13.93E+08 lND li.17E+09 l 4 lTe 127ml3.49E+08 11.25E+08 14.26E+07 l8.92E+07 11.42E+09 i ND 14.47E+05 1 lTe-127 .15.66E+03 12.03E+03 l1.23E+03 l4.20E+03_12.31E+04 l lTe 129ml2.51E+08 l9.38E+0' 13.98E+07_l8.64E+07 l1,05E+09 i ND l1.27E+09 l NP 15.77E 04 l lTe 129'17.65E 04 12.87E-04 11.86E 04-15.87E-04 l3.22E 03 I ND _,14.43E+07-l i
_lTe-131ml9.12E+05 l4.46E+05 13.72E+05 l7.07E+05 14.52E+06 ND i 10.00E+00 l ITe-131 l0.00E+00-10.00E+00 10.00E+00 l0.00E+00 10.00E+00 l ND 11.32E+08-! .
lTe 132;i4.30E+06 l2.7BE+06 l2.61E+06 l3.07E+06 l2.68E+07 l ND 19.97E+05-l >
lI-130 - - l3.93E+05 11.16E+06 - 14.57E+05 l9181E+07 l1.81E+06 i ND (3.05E+07--
_lI-131 }$.08E-07 l1.16E+08 l6.62E+07 13.79E+10 11.98E+08 l ND 12.90E+01 l' l
!!-132- -15.77E+01 11.54E+02 15.40E+01 l5.40E+03 12.46E+02 l ND
~
13.26E+06 l lI-133 -12.09E+06 13.63E+06 11.11E+06 15.33E+08 16.33E+06 l .ND 12.3CE 07 1 11-134 19.69E-C5.12.63E 04 [9.a:E 05 14.56E-03 la 19E 04.l F
f
- 73 * ,
I
APA-ZZ 01003- l Rev. /2 ;
' O f ff 5
TABLE 5 (Centd.)
i ADULT PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Patt.way f
(m8 mrem /yr) per (vCi/sec) 1 l l l Total l l l l l Bone Liver Body 1 Thyroid l Kidney Lung 1 GI-LLI I lNuclidel I 1 1 l1-135 l3.90E+04 l1,02E+05 13.77E+04 l6.74E+06 l1.64E+05 l ND ll.15 M 5 l lCs-134 l4.67E+09 l1.11E+10 19.08E+09 l ND 13.59E+09 11.19E+09 l1.94E+08 l lCs 136 l4.27E+07 11.49E+08 l1.21E+08 l ND l9.38E+07 l1.29E+07 l1.91E+07 l
'JCs-137 l6.36E+09 l8.70E+09 15.70E+09 l ND l2.95E+09 19.81E+08-11.68E+08 1 (Cs-138-l0.00E+00 l0.00E+00 l0.00E+00 l ND 10.00E+00 10.00E+00 l0.00E+00 l lBa-139 12.86E-02 12.04E 05 l8.39E 04 l ND 11.91E-05 11.16E 05 l5.0$E-02 l lBa-140 ll.29E+08 l1.61E+05 18.42E+06 l ND- 15.49E+04 l9.24E+04 l2.65E+08 l lBa-141 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 10.00E+00 l_
JBa-142 10.00E+00 l0.00E+00 l0.00E400 l ND l0.00E+00 l0.00E+00 l0.00E+00 l '
lLa-140 11.98E+03 l9.97E+02 l2.63E+02 l ND l ND l rid 17.32E+07 l lLa-142 l2.03E-04 l9.21E 05 l2.29E-05 l ND l ND l ND l6.725-01 l JCo-141'll 97E+05-ll.33E+0/ l1.51E+04 l ND l6.19E+04 l ND 15.10E+08 l lCe-143 l9.98E+02 l7.38E+05 l8.17E+01 l hD 13.25E+02 l FD l2.76E+07 l I lCo-144~j3.29E+07 l1.38E+07 l1.77E+06 l ND 18.16E+06 l ND l1.11E+10 l- .
lPr-143 l6.26E+04 l2.31E+04 l3.10E+03 l ND l1.45E+04 l ND l2.74E+08 l lPr-144 l0.00E+00 l0.00E+00 lo.00E+00 l hT l0.00E+00 l' ND l0.00E+00 l ,
INd 147 13.33E+04 l3.85E+04 12,31E403 l ND l2.25E+04 l ND l1.85E+08 l lEu 154 l4.85E+07 l5.97E+06 14.25E+06 l ND l2.86E+07 l ND l4.32E+09 l lHf-181 li.40E+05 16.32E+05 16.32E+04 l ND ll.47E+05 [ ND 17.76E+08 l lW-187 l3.80E+04 l3.18E+04 l1.11E+04 l ND l ND l ND ll.04E+07 l lNp-239 l1.43E+03 11 41E+02 l7.76E+01 l ND 14.39E+02 1 ND l2.89E+07 l t
- '6 -
i APA-22-01003 Kev.. gf 2 (25/1/
I- 3.6 Casecus Radwaste Treatment System i
41862 3.6.1- REC 9.9.1.1 f 4160 '
l The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE OAS HOLDUP SYSTEM shall be OPERABLE and ?
appropriate portions of these systems shall be
[ used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY would exceed: ,
- a. O.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or c.-0.3 mrem to any organ of an Individual 3.6.2 Description of the Caseous Radwaste Treatment >
System The gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gaseous. effluents require treatment ,
prior to-being released-to the environment. The ,
- gaseous radwaste treatment system is designed to ;
e , allow for tne retention of all gaseous fission products to be discharged from the reactor coolant system. The retention system consists of eight (8) waste gas decay tanks, six (6) for use during normal operations.and two (2) for use
.during shutdown conditions. Normally, waste gases:.will be retained-for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials-in gaseous effluents will be kept ALARA.
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AFA-ZZ-01003 Rev. .
'h.6/ 9/
i
- 3.6.3 Ocerability of the Gaseous Radwaste Treatment
- System i The OPERASILITY of the gaseous radwaste treatment :
f system ensures this system will be available for ;
use when gases require treatment prior to their release to the environment. OPERABILITY is ;
[ demonstrated through compliance with Sections 9.6.1.1,-9.7.1.1, and 9.8.1.1. i b Projected doses (' gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the SITE BOUNDARY are determined each 31 days by ;
dividing the cumulative annual total by the f" number of elapced months.
4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE' SOURCES.
41864 4.1 REC Section 9.10.1.1 4160 _
The annual-(calendar year) dose or dose
= commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body -
or any organ, except the thyroid, which shall be limited to less than or. equal to 75 mrem.
4.2 Calculation of Dose and Dose Commitment from '
Uranium Fuel Cycle Sources The annual dose or dose commitment to a MEMBER OF THE'PUBLIC for Uranium Fuel Cycle Sources is determined as ,
a).Do'se to the total body and internal organs due ;
to gamma ray expc'scre from submersion in a cloud of radioactive noble gases, ground plane-exposure, .and direct radiation from the Unit and outside sto, rage tanks; ;
e
- 78 -
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APA-ZZ-01003 l Rev g2
'.*f h f/
b) Dose to the skin due to beta radiation from submersien in a cicud of radicactive noble gases, and greund plane exposure; c) Thyroid dose due to inhalation and ingestion of radiolodines; and d) Organ dose due to inhalation and ingestion of radioactive material.
It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate. (Ref. 11.12.5)
The dose from gaseous effluents is considered to be the summation of the dose at the individual's residence and the dose to the individual from activities within the SITE SOUNDARY.
Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190. (Ref. 11.12.3)
It should be noted that there are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant.
79 -
APA-20-01003 Rev.gC2 ,
'lD/4/
l
-.t~
Identification of the MEMBER OF THE PUBLIC 4.2.1 The MEMBER OF THE PUBLIC is considered to be a real individual, including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant. (Ref, 11.4 and 11.6.10.)
Accordingly, it is necessary to characterize.this j individual with respect to his utilization of '
areas both within and at or beyond the SITE h BOUNDARY and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CFR 190 through the use of more realfstic assumptions. (Ref. 11.12.3 and 11.12.4)
The evaluation of Total Dose from the Uranium .
Fuel Cycle should consider the dose to two Critical Receptors: a) The' Nearest Resident, and b) The Cr1tical Receptor within the SITE BOUNDARY.
4.2.2 Total'Doso,to the Nearest Resident The dose to the Hearent Resident is due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestien :
pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.
It is assumed that direct radiation dose from operation of the-Unit and outside storage _ tanks, and dose from gaseous effluents due to activities-within the SITE SOUNDARY,_is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the .
-highest value of X/Q.
, _ .- -. .__-.-. - . - - , . - - _ . ~ . . - _ - _ - - - ... . - . -
(J A- 7,'Z - 0100 3 i
i Rev. Y 2 Q&t f/
i The location of the Nearest Resident in each meteorolagt:al sector is determined frem the Annual Land Use Census conducted in accordance with th<e Requirements of Section 9.12.1.1 4.2.3 Total Dose to the Critical Recentor Within the EITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for management of the residual lands surrounding the Callaway Plant, including some areas within the SITE BOUNDARY. Urder the terms of this agreement certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing, etc.) but recreational use is excluded in an area immedintely surrounding the plant site (Refer to Figure 4.1) . Much of the residual lands within the SITE SOUNDARY are leased to area farmers by the Department of Contervation to provide income to support management and development costs.
Activities conducted under these leases are primarily comprised of farming (animal feed),
grazing, and farestry. (Ref 11.7.2, 11.7.3, 11.13, 11.13.1).
Based on the utilization of areas within the SITE BOUNDARY, it is reasenable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The current tenant has estimated that he spends approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in this area (Ref 11.5.5). Occupancy of areas within the SITE BOUNDARY is assumed to he' averaged over a period of one year.
Any reevaluation of assumptions should include a reevaluation of the occupancy period at the locations of real exposure (e.g. a real individual would not simultaneously exist at each point of maximum exposure). ,
i 1
'- - - " " - ~---,..___.m
AFA-ZZ-01003 Rev. ??2 I.SS] <//
! 4.2.3.1 Total Dese to the Farmer from Gasecus Effluents The Total Dose to the farmer frem gaseous effluents is calculated using the methodology discussed in Secticn 3, utilizing concurrent meteorological data at the farmer's residence and historical meteorlogical data from Table 10 for activities within the S!TE BOUNDARY. These dispersion parameters were calculated by assuming that the f armer's time is equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> / year factored into their value (Ref.
11.5.6).
The residence of the current tenant is located at a distance of 3830 meters in the SC setter. No meat or milk animals or vegetable gr.rdens were l
identified by the 1987 Land Use Ce sus for this location, therefore, the gaseous effluents dose at the farmer's residence is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.
It is assumed that food ingestien pathways do not exist within the SITE BOUNDARY, therefore the gaseous effluents dose within the SITE BOUNDARY is due to plume exposure from Noble Gases and the ground plane and inhalation pathways 4.2.3.2 Total Dose from Direct Radiation 4.2.3.2.1 Direct Radiation Dese frem Outside Storage Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioactive materials, and constitutes the only potentially significant source of direct l radiation dose from outside storage tanks to a MEMBER OF THE FUBLIC. (Ref. 11.6.14, 11.6.15, 11.6.16, and 11.6.17.)
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APA-ZZ-OlLO3
[ Rev. X2 6]D/4/
s i
Direct radiation dose frem the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Centrolled Area fence which isThis not obscured by significant plant structures.
has been determined to be 450 meters from the RWST.
The RWST is a right circular cylinder approximately 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters. (Ref. 11.6.17.) The walls are of type 304 stainless steel and have an average thickness of .87 cm. (Ref. 11.14.1.)
The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and attenuation within the volume source. Appropriate methodology for calculating the dose rate from a volume source is given in TID-7004, " Reactor Shielding Design Manual" (Ref. 11.17). The computer program ISOSHLD (Ref. 11.18, 11.19, 11.20) will normally be utill:ed to perform this calculation.
p
- $3 -
P APA-EE-01003 R iv '15Fil
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t 4.2.3.2.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined to be 7E-2 mrads/ calendar year, based on a point source of primary coolant N-16 in the steam generators. This source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the i containment dome and for distance attenuation.
No credit was allowed for shielding by other structures or components. The number of gammas per second was generated and then converted to a f dose rate at the given distance by use.of ANSI /ANS-6.6.1, " Calculation and Measurement of Direct and : Scattered Gamma Radiation from LWR Nuclear Power Plant 1979", which considers attenuation and buildup in air. The final value isLbased on one unit operating at 100% Power.
The distance was determined to be 367 meters, ,
which is approximately the closest point of the
~
boundary of the owner Controlled Area fence which is not obscurred by significant plant structures. ;
.(Ref. 11.14.3.)
The maximum direct radiation dose from the Unit-to a MEMBER OF THE PUBLIC due to activities within-the SITE BOUNDARY is thus approximately 9E-3 mrads per year, assuming a maximum occupancy '
of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year.
1 4-4
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i 41835 5.0 RADIOLOGICAL ENVIRCt MEMTAL M0!!IT0_RI?]2 3535 41866 5.1 REC Section 9.11.1.1 The radiological environmental menitoring program shall be conducted as specified in Table 9.11-A.
5.2 Description of the Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program is intended to act as a background data base for preoperation and to supplement the radiological effluent release monitoring program during plant operation. Radiation expecure to the public from the various specific pathways and direct radiation can be adequately evaluated by this program.
Some deviations from the sampling frequency may be necessary due to seasonal unavailability, hasardous conditions, or other legitimate bases.
Efforts are made to obtain all required samples within time frame cutlines. Any deviation (s) in campling frequency or location is documented in
' the Annual Radiological Environmental Operating Report.
The Environmental samples are collected and analyzed at the frequency outlined in Table 6.
Reporting levels and lower limits of detection (LLD) are given in Tables 7 and B.
e I
APA-ZZ-01003
{ Rev. /2
' 035/ 4/
i Airborne, waterbore, and ingestion samples collected under the monitoring program are analyzed by an independent, third-party laboratory. This laboratory is required to participate in the Environmental Protection Agency's (EPA) Environmental Radioactivity Laboratory Interccmparison Studies (Crosscheck)
Program or an equivalent program. Participation includes all of the determinations (sample medium
- radionuclide combination) that are offered by the EPA and that are also included in the monitoring program.
5.3 Performance Testing of_ Environmental Thermoluminescence Dosimeters Thermoluminescence Detectors (TLD's) used in the Environmental Monitoring Program are tested for accuracy and precision to demonstrate compliance with Regulatory Guide 4.13. (Ref. 11.16).
Energy dependence is tested at several energies between 30 kev and 3MeV corresponding.to the approximate energies of the predominant Noble Cases (80, 160, 200 kev), C s- 137 (662 kev), Co-60 (1225 kev), and at least one energy less than 80
> kev. Other testing is performed relative to either Cs-137 or Co-60.
57 -
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- - /2
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-RADI01OCICAt EffVIRotiMtJT_At MONITOHIttG PfmJ SAMPLING AND TYPE AND FREQUENCY f nt*050Ht! Pall 6WAY NUMilfH OF ftt ritt SE NT AT 8VE SAMP115 COLLECT IOtt FR(90EN_Cy OF AftAMSIS Alip SAMPil_IOCAlf0NS 4,yrjD/1Mt sal'Pl [_,
At least once per 92 days Camma Dose
- l. Dire:ct Radiation 40 routine monitorin9 stations eittier with two or more dosimoters or Witts one instrument l'or measuring and recording dose rate continuously, placed as foltows:
An inner ring of saxteen stations, one in each meteorological sector in tise general a rea or the S:1E couMDARY.
Station tocg ion Gd39 I*eCLo_r Si,t e_Degg rif(ion- 1.9 mi. O 349' ft 04 A D.3 Miles East or llwy O avut CC Junction, Callaway Electric Cowp. Utility role No. 18892 B County fload 448 0.9 Miles Soutte or guy O. Castaway 0.9 mi. 9 17' NME 47 Electric Coop. Utility Pole No. 20151 C County Road 448, 1.5 Miles South or lawy 0,. Plant 0.4 ml. # 45' NE 48 Security Area Sign Post 3 Primary Meteorological lower 1.3 mi. 6 78* ENC OS E County fload 448, Catlaway Electric Coop UtillP-. 1.7 al. 6 93* E 49 Pete No. 06959. Reform Wildlife Management king Area r Light Pole Near East Plant Security Fence 0.4 mi. 0 114* ESE 52 C Located in time "Y" of the atsandoned Rail road spur, 0.7 mi. # 137' SE St northwest or sludge lagoon So si County Road 459, 3.3 Mitos Nortia or liwy 94, Callaway 0.9 mi. 4 163* SSE Electric Coop. Utility Pule No. 35086 ,
07 J County Road 459, 2.6 Miles North of'towy 9fa, Cattavey 1.3 mi. 9 181* 5 Electric Coo.. Utility role No. 3509T 37 K County Road 459, 0.9 Miles South or itwy CC, Callaway 0.7 mi # 202* SSW Electric Coop. Utility Pole No. 3507T 43 L County Road 459, 0.7 Miles South of Itwy CC, Callaway 0.5 mi. # 230' SW Electric Coop util8ty role No. 35073 liigtn.tay CC, 1.0 Mi ses South or County Road 459, 1.7 mi. e 257* WSW 44 M Cattaway Electric Coop. Utility role No. 18769 N County Road 428, 1.2 Miles West or IMy CC, Callaway 2.0 mi. 8 21F* W 06 Electric Coop. totility Pole fio. 18609 l
APA-zt-u Itev. f 2 ~~
$/r/
I A!!LE 6 109t!L i nstedj RAnf or oCICAljyyggotLMULI Al_MOffl10HINC PHOCMAM location Station pector Si m puscri.jil.og 1.0 mi. # 290* WNW
[tpfe Cal'.away ad 42J, 0.1 Milos Vest of stwy CC, op. Utility Pole No. 18580 P Couu.)
ha [ a ct. t r t e.
- 1. 3 el . U 30f' IN 0.1 v ' n t of liwy CC on Cravel Road 0.8 Miles Utility Pole n) Q Sout ti . J. Callaway Electric Coop.
No. 18M9 1.5 mi 0 333' NNW flortit-Cast side of lisy CC and County Road 146 6
8s 6 ft Intersection Ca'laway Electric Coop.
- Utiiity Pole flu. 262*:2 statiotss, one An buter riteg of sixteensector in tite 6-in eacts motoorologica l to 8-Fm ra nge f' rote tiie s i te . 4 132, 5.2 mi. # 7' N County stoad 1%, 0.8 MilesUtility Soutta of County Pole No. 19137 Hoa.
A 36 Callaway Cloctric Coop. 4.0 mi O 23* ANC Il County Hoad 155, 1.9 miles siotti 1r ifvy 0, Callaway Utility r3ic no. 19100 21 [lectric Coop.
Callaway 4.D mi. #1 47' flE 0 Ifigirway D, O.fs Utility Miles Nortin of alwy12830 role No.
K, 20 Electr c Coop.
a Callaeay 3.8 mi O 63* ENE 0 Higirway D, ts.4 Mi 6 as Soutti o f Ilwy O.
Utility Potu No. 129$2 18 Flectree Coop.
K inty!om 4.0 mi. tl C9' E
[
County Ituad 40$3, 0.3 Miles 3East X 12of Hwy D, Il Teleptione Comt.any Pole ria.
5.0 ml 0 121* ESC Side of Itwy 98s and Hwy D Intersectiors Its I South-fast Callaway Itectric Coop.
Utility Pole No. 18940 Utility 4.0 mi. O 139' SE G
City of Portland, Callaway Liectric Coop.
11 Pole Ho. 12112 es.O ml. 4 1$7* SSE I*ighway 94, 1.8 Miles f ast of County ftnad 4$9 Utility Pole fio. 12182 10 11 Callaway Electric Coop.
3.7 mi. @ 183* 5 Side of Ifwy 94 an<j County Road r459 09 J tiorth-West Callaway Electric Coop. Utility role J unc t i on, tio . 06754 4.6 ml. 0 208' SSW K West Side of County Hoad 447 at tse Junction 30 we tte County Road 463, Kingdom Ieleptione Company Polo No. 2K1 8
.s . fi mi. # 233 SW L Cour:ty Itoad '84 7 2.6 Miles Nortis of County Hoad 463, Utflity Pole No. 06326 f2 6 Callaway Electric Coop.
i _
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,s APA-ZL-010Ch nev. /2
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JANtE ( (Cc .inuedl It AD int OGICALI Nyil!OfiHt_tji At MO3fTORtNG PflOGRM
/
Station
_focation I Setito r site Descripuun 0011! $.4 mi. 4 251' V5W H tligf >wity W, 0.6 Hitos West. of County ftnat.f 44 7, 32 Callaway Electric Coop. Uti4ity Pole No. 2 t'8 3 I 4.8 mi. 0 279* W N liigway AD, 2.8 Miles fast or ifwy C, Callaway t; I Liectric Coop. Utility Pole No. 18239 8.2 mi. 4 294* WNW 8
P North-Last Side of County fload 112Utility and Itwy I' O ole 40 Junction Callaway Electric Coop.
No. 06326 5.4 mi. 6 31$" NW Q Consetty Foad 112, 0. 7 Piles Ea st of County fload 111 39 Callaway Efectric Coop. Utility Pole No. 17$16 j 4.8 mi. G 337' NPfW '
County atoad 133, 1.'> Miles Soutti or stwy UU 30 81 Callaway Etelctric Coon. Utility Polo No. 3'e705 l in special
[iglet Stations to be placed areas suele as population interest centers, nearby residences. scfico l s ,
and .n 1 or 2 a reus to serve as control stations. 7.4 mi. @ 273* W 33 N City of flams Prairie, South-East of the ilsy C and llwy AD Junction Callaway Electric Coop. Utiftty 7.ts mi. H 218' SW
- 1. City or Hokano, 38 Pole No. 06039 Utility 12.1 mi. 4 02' E T own of Ame ricu s, Ca l l a wa y E l ec t r i c Coop.
26 E Pole No, Ills 9 Callaway Electric Coop. Utility 9.6 mi. 4 110' ESE J
lown or Bluffton, 21 Pole No. 117816 5.8 mi. 0 342 3 Ners N Csty of Toledo, Callaway Electric Coop, Utility 3$
Pcle No. 1766f4 Callaway Electric Coop. Utility 6.6 mi. 0 16' NNE 8 City of Yucatan, 23 Pole N>. 12370 4.8 mi. 4 139' SE tl C City of Portland, Cattaway Electric Coop. Utility Pole No. 12112 it . 8 m i . O ra7* NE 20 C Ci ty of ficadsvi l le, Callaway Liectric Coop. Utility Pole No. 17030 ide of Inwy C and Conanty Read 108 4 9.7 al. 4 293* WttW P tiorth-East 34 Junction (P-Cont ut)
N
~APA-ZZ-01003
- Rev. Q
- p -
J^llLL6_LG9LrtijfitJgdj RADIOlhC1 CAL fl{ViItOyM[tif AL MOtR10RIljC PROGRAtt .
Station tocation Gode Secjo r site Descriplign of Q .llighway Z, 0.8 Miles East or Husiness $1s, Callaway 11.0 mi. 6 312* NW (Q-Control) E lectric Coop. Uti l i ty. l' ale flo. 21$8 8a o 3g
- 2. Ai e Amrne Contisitiones opera tions of Analyze at least Itaal salud Ine asid S.amples rrtsa rive
- l oca t l osis sampler witta sample once per 7. daya Pa r t i cula te s collect ion as requi red for 1-131 .
by dtast loading, but at least once ,
- per 7 days.
Ihree samples from close to the * ; Particulate Samdel thren 5110 BOUtIDAllY locations, in different sectors, of the Analyze for gross Isighest calculated annual average beta rad ioac tiv i ty gsound levul D/Q. > 24 isoners Tollowing ritter change. Perform
. gamma asutopic asia lys i sd on those samples for-wlilch Late gross
' beta activity is >10 t ime s the yea rly smean of' cont rol sampics. Perform gamma isotopic analysis 8 i on compt.si te samp les l (by location) at Icast once per 92 days.
Al D Primary Meteorotocical Tower 1.3 mi. H 78* LtiE B County Road fat:8, l.0 Miles South or Ilwy 0 0.6 mi 8 21s* t!NE AS
- 0. 3 M i l e s Ea s t o r alwy 0 a nd I'.'sy CC J enc t i on ,1.9 mi . 0 3ts9' tt H3 A ono sample from the community with the lii g he s t D/Q.
R Communi ty ol' Iterorm 1.7 mi. O 338' ffNW A9 t
APA-ZZ-01003 Itsv. / 2 j
.. Qfp TAfil0 6-(Con dnueJ1
{tADIOl OCICAL f t{ylR0fifjLNI AL MOH110RiflG PROCftAM S ta t iott Loca t iors Code Sector Mtre Descrigt i,or)
Osin sample from a coritrol location, as for exaatple 1*>- 30 km d i starit a rid in tise least pe eva lorit vised di rection.
A7 Q .C. l)articy farm 9.5 mi. 4 312' fM
- 3. Watustiorno Composite samptef Casnma isotopic analysis d
- n. Surface
- One sample upstroasa over a period or eacle sample, or less than or Tritium analysis or equal'to 31 days, composite sample at least once per 92 days.
II ass reot tspstream of discharge, north basik 81 . 6 sei . U 184 8s' SE Sul One samplo dowfistream 1,1 miles downstream or disclearge, north bank 5.2 mi .,6 133' SE 502 C Composite sample over 5-131 analysis on
- b. D r i s.k i ng One sample or eacl: each composite when 2-week period when one to tisscu of the 1-131 assalysis is the dose calculated nearest water supplies for the consurapt ion wi thin 10 salles downstrea, performed, amnthly composite othervi se. of the water is that could be aff ected by greater than 1 arem its dischargo, per year. Composite for grcss beta and gr ama isotopic One saspple Frcna a control analyals monthly.
location. . Composite for tritium analysis qua rte rly.
the As there a re no . drinkin'J wa ter intakes wi thin 10 miles downst ream or the discha r ge point, drinking wa ter pa thway is currently not included as part or the Callaway Plant Radiological tuvironmental Horsi toring Program. Should ruture water intakes be constructed within 10 river miles downstream of the discharge point, then the program will be revised to include this gaa thwa y. (iter 11.6.6)
Semia nnua l ly Camma isotopic
- c. Sedsment One sasople from dowrestream analysis (d) from a rea vi tti exist ing or semianrually.
Shoseline potential recreational value.
1.0 river mile downstream or dischargo, north bank 5,1 mi. 0 13$' SL C G
~ '
~
Al'A-LZ-01003 nov. 72 -
')
l}3579, 160! C 6 jger!LLniscill PaoGHAM HAD10 W 98G^t F Wilio.tLHOf L^L_U9ftU oM i r8G station Mcation 8
OE 18 Sec er She Descrin@29 is . Ingestion Camma isotopied and Semimonthly vtieri 8-131 analysis
- a. tiilk Samples from milking animals anima l s a re on sem! monthly vtico in ttis ce location wittiis pasture, conthly a t animals are on
$ km distance fiaving the otlier times. pasture; monthly at folgteost dose potesitia19 other times, ir thoru are nono, then one sampia from milking animals in cacle ur thren areas between 5 to 0 km distant whero doses are calculated to be gr ea tor tisari 1 mrem per year the milk pattrway is currently Duc to a lack of milk animals whicts satisfy these flad reqirements, io log ica l Environmental Moni toring Prog ram.
not included a:6 a part of the Callaway Pfant identify the existence of milking an!mals in locations whicia Should satisfy tiec Anrusa these l land Use Census requirements, tieen the program will be revised to incleide Lt:Is pathway, Camma isotopic Samplo i ts season, or atta f ys i s d on f One sample nr each semiannylally if they edible portions. (
- b. Iish ,l commercially and are riot seasonal.
recreationally important species in vicinity or plant discliarge area.
location Station Sijo Descriptfor)
Codo Sector north bank 5.I al . # 135' Si~
C C 1.0 river mile dovrest reae or discha rgo, Ono samplo or same species in a reas riot intr auenced by plant disclia rge.
north bank 8.9 al. & 158
- SSE 8 4 A il 0.6 river miles espstream or discharge, j
i
" ' ~~
.APA-ZZ-01003 Rev../2- -
Tant E 6 iContintseQ
- RAJ110l OCICAl. ENVillOtttjf tlT At_ HORTORING PitOGl!AM .
Station d Es te l)escrijttion tocallo_g fji_q 1eciol Orte sample ' or each At t ime o f ha rve s t (h) Camma isotopic
- c. food Products anafysisd on p r i tic i pa l class of prottucts f rom any a rea edible portion, that is irrigated Isy water : In viilcle - t iqisid plant. wastes have tseen
' d i sclea rged.
As thore are no a reas . i rrigated by wa ter in wisich liquid plant vastes have been dischargad wi tteiss 50 river miles downstrease of the discitarge point, this sample type is snot cu rrent ly isscludet' . a s pa rt or Llio Ca llaway Plant Stad io l og ica l Environmental 14oni toring Program. Sitould itettes e it rigatiots water irstakes be constructed within 10 river miles downstream or the discleas ge poirst, tliers the p rog ra m w i l l be revised to include this sample type. ( He r. 11.7.ts and ll.7.$)
Samples of Liaree Monthly wisen available Gamma isotopic d and diffs:sont kisists or 1-131 analysis, tsroad lear vegatation growra nea rest eacle or two different offsite locations of' liighest predicterd anrusa l average ground-level D/Q if anilk sampling is not performed.
Station Location Cmio se_c,lo r Si te Desc rip _t ion V6 It Dectie r's ra ra 1.6 mi. 0 3f6* tstew VI A Heelian's f a rm 1.8 al. 0 3%* te One sample or.ench of Monthly witen available Gamma Isotopicd simila r Isroad lear analysis.
vegetation grown 15 to ,
30 km distant in tho least prevalent wind direction (ir milk sampfing is not pc rro rmed ) .-
Station Code Sec to_r $11e Descriptiog l_ocation V3 t. - Beazley's Fa ris 15.0 al. 0 227' SW 4
~
ACTA QPIRsAAslChr v
stiv. p g g ,
v(
' LAlH r 6 [GrJ!.!tiputd) ;
T Allt.E NOT Ai t otl (a) Deviations are permitted f rom the regtelred sampling scliedule if specimens are unobtainable due to haza rdous
. conditions, so.a bona l unava i labi l i ty,' aus t runct ion of automa t ic sampl ing equipmesit, and ottier legi tima be made te reasons, to complett, if specimens a re.unohta issable due to' sampling equipment ma t ronctions, every cf rort . shall correctivo action prior to the end of the next samplitig period. All deviations'from the sampling scheduet shalt
.be documented Ise the Arenua l ' Itad iolog ica l Environmental Opera ting Report. It is recognized that, at' times,.it may not be possible or practical to continuo to obtain samples of' the media or citoice at the most desired loca tion or timo, in tito se . i ns tances. su i tab le a f t erna t i ve med i a a nd locat iosss may he chosen for the pa rticula r pathway les quest ion and appropria tu 'substi tutions made wi thin ,3D days in the fladiological invironmental Honi toring Program, idusstif y tins casase of the unavailability or samples for that pathway ased identify.thu new locatiot*{s) for' obtainsng soplacenent samples in tfie next Semi-Annenal Itadioactive Errluent fielease Ileport ' and" also include its the report a complete and tugible' copy of the entire ODCH, including the revised figure ( s ) and table reflecting thu new IocaLlon(s).
(b) One o r mo r u l et s t rumen t s, sueli as a presstarized ion cfiamber, f or meastering used recording dose rate continuously may be used in place or, or,in additson to, Integrating dosimeters. for the purpose of this table, a 4
t he rmu l tim i sse scen t dosimotor (ILD) is considered to be one pliosphort two or more phosphors in a paci ct a re J
i consistered as - two or mor e elusimeters. rism tadges shall Ihn not be used as dosis.cters for measuring direct reumber of di rect radiastion monitoring stations may be rad i a t s on. tho 40 stations i s - no t a n . abso l u te . ruimbe r.
s edisced accordiseg to geograptilca l limitations; c.9.,.atIhc an frequency ocean site,ofsome sectors analysis vill be ove or readout forr 110 wa tesystems r se tha will t--
the number of slosimoters may- be reduced accordingly.
deposed upon the characteristics of the specific system used and should be selected'to obtain optimum dose 1
< information wittimainimal rading.
(c) Ihis purpose of this sampio is to obtain Isackground information. .3r it i s not ' pract ica l to establish control l oc a t i ust s ist accordance with the distance and wind direction criteria, other si tes tisa t provide va l id backgrousul stata may be substituted.
id)
Camma e sotupic analysig is deristed as the ident i fica tion and quanti fica tion of gamma-emi tting radionucl ides tha t
' may be attaibutablo to the erriuents room tho' facility.
Ti e (c) The " upstream" sample shall be taken at a di stance tseyond signi f icant influence of the discharge.
i
" downstream"' sample shall be talen in an a rea beyond, but near the mixing zone.
(r) i st titis g N9 ram, con s ta n t volume sample .a t iquote a re collected 'at short time intervals (e.g., monthly).
(g) Yhn do:.u; sha l l be calculated for the maximum organ and age group, using the methodology and parameters in the ODCH, If ha rve st occurs more than once a year, sampling shall be performed during each discrete harvest. I f ha rvre s t ib) occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and runt i uod p roduc t s .
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IMILf_A ttAxJtiyM,yALurs ron reil ourn LLM f s or sg rtGuoff_1LLO)*,*. l food Product Sediment l Hlik (pCi/kg, vet) (pCl/kg, d ry )
__ fish (pCl/8) l Ai rtsorno Pa rticulate ( pC i / kg ), wa t Water or Ga ses (pCl/m3) I l (pCl/l) i I An.i t y s i s .
I
-01 l _ _ ...._.,___ ._4_ _ . i inross ceta I i 2000
- I l it- 3 130 I t 15 I i fe-5ti 260 1 t I Fe *;9 30 i 130 i I !$ I I co-So,60 i I 15 a* 1 60 i i 1 r- en,-95 . 1 07 60 150 I f(d) 35 l l t-131 13e 1
,oS 80 180 I 35 18 I I e s- 13ri 150 I
.06 _1 I tt Q**
l Cs-13T 1
i to - t f ,1go___ _Q *
- a value of 3000 pCi/t is used.
- s ur surface wa te r samples,
- fotal activity, parent plus daugf ator activi ty.
l 4
4
APA-2Z-01003 Rev..P A. rj)E f;u l P TABLE _8 (CONTINUED)
T AB L E.~NO. TAT.
-- ! C:4 (a) The LLD is defined for purposes of compliance with the Radioactive Effluent Controls as the smallest concentration of radios.ctive material in a sample that will yield a not count, above system background, that will bo detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.56 S b E
V 2.22 'Y exp (-kat)
Where:
LLD = The lower limit of detection as defined
- above (as picocurie per unit mass or volume).
The standard deviation of'the background Sb=
counting rate or of the counting rate of a blank ai pie as appropriate (as counts per mir.ute).
E= The counting efficiency (as counts per disintegration).
V= The sample size (in units of mass or volume).
2.22 = The number of disintegrations per minute per picocurie.
Y= The fractional radiochemical yield (when applicable).
.APA-22-01003 Rev. d'2. fc-l 1= The radioactive decay constant for the particular radionuclide and, at = the elapsed time between sample collection (or end of the smaple collection period) and time of counting (for environmental !
samples, not plant effluent samples). l
~
Typical values of E, V, Y and at shall be used in the calculations.
It should be recognized that the LLD is defined 1 as a 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. '
Analyses are performed in such a manner that the stated LLDs are achieved under routine conditions. Occassionally background j fluctuations, unavoidable small sample sines, the !
presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
(b) 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 analyzed and reported in the Annual Radiological Environmental Operating Report.
(c) Required detection. capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Revision 1, July
. 1977. (Refer to-Section 5.3) l
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- -INTEAMITTENT STAE AMS CONTINUCUS ST AE AMS S ACU ATIC S AMPt.ING STATIONS i i o
0 CCMPCSITE SUAFACE WATEA ,,
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C ALL AWAY PLANT LOC ATION OF AQU ATIC S AMPLING STATIONS l FIG UR E 3. A REY 6 l
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<e%Mst4h Rev . - 1 'A . Q) 5 -8 .'l 8 j; 6.0 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC-DISPERSION PARAMETERS
- j. 6.1 Atmoseheric_ Dispersion Farameters The values presented in Table 9 and Table 10 were determined _through the analysis of on-site meteorological data collected during the three !
year period of May 4, 1973 to May 5, 1975 and March 16, 1978 to March 16, 1979, 6.1.1 L5ng-Term Dispersion Estimates The variable trajectory plume segment atmospheric transport model MESODIF-II (NUREG/CR-0523) and the straight-line Gaussian dispersion model XOQDOQ'(NUREC/CR2919) were used for determination of the long-term atmospheric dispersion parameteru. A more detailed discussion-of the methodology and data utilized to calculate these parameters can be found elsewhere (Ref. 11.6.12).
The Unit Vent and Radwaste Building Vent releases are at elevations 66.5 meters and 20 meters above grade, respectively. Both release points are within the-building wake of the structures on which they are located, and the Unit Vent is equipped with a rain cover which effectively 1 eliminates the possibility of the exit velocity exceeding five times the horizontal wind speed.
All-vasecus releases-are thus considered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined.- (Ref. 11.5.2) j i
l 1
- 105 -
1 J
APA-ZZ-01003
( ,. . f g 6.1.2 Determination of Long-Term Dispersion Estimates, for-Soecial Receptor Locations Calculations utilicing the FUFF model were performed for 22 standard distances to obtain the desired dispersion parameters. Dispersion parameters at- the SITE BOUhTARY and at special receptor locations were estimated by logarithmic interpolation according to--(Ref. 11.6.13):
X=X y d)B (6.1) dy L
Where:
l B= .ln (X2 /X1 )/ n.(d /d 2 ).
y i
! X,X y
= Atmospheric concentrations at distances 2
d y and d , respectively, from the source 2
(in C1/m ).
The diatances d y and d 2 were selected such that
- dy <d<d2 '
6 . .l . 3 Short Term Discersion Estimates i Airborne releases are classified as short term if they are less than or equal to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during a calendar year and not more than ISO-hours in any quarter._ Short term dispersion estimates are determined by multiplying the appropriate long term dispersion estimate by a correction factor i (Ref. 11.9.1 and 11.15.1):
(-
? = (T s/T a) (6.2) i - 106 -
i
, _ , _ _ - - - - . . , ,4
I APA-ZZ-01003 Rev. %'). c36f~-l h f l-Where:
4 Tg = The total number of hours of the short term release, p
}.
Ta = The total number of hours in the data collection period from which the'long term diffusion estimate was determined (Refer to Section 6.1).
Values of-the slope factor (S), are presented in TABLE 11.
Short term dispersion estimates are applicable to short term releases which are not sufficiently
-random in-both time of day and duration (e.g.,
the short term release periods are not dependent solely on atmospheric conditions or time of day) to be represented by the annual average dispersion conditions. (Ref. 11,8.11.)
6 .1. 3 .1 ' The Deter:aination of the Slope Factor (S) .
The general approach employed by subroutine PURGE of XOQD0Q (Ref. 11.15 1) was utilized to produce values of the slope of the (X/Q) curves (Slope
_) Factor (S)) for both the Radwaste Building Vent and the Unit Vent. However, instead of using approximation procedures-to produce the 15 precentile (X/Q) values, the 15 percentile (X/Q) value for each release.and atEeach location was determined by ranking all the 1-hour (X/Q)y values for that release and at the location in descending order. The (X/Q)y value which corresponded to the 15 percentile'of all the calculated (X/Q) values within a sector was extracted for use in the intermittent release
. .(X/Q) calculation. .
- 107 -
-m -- -- _______ ___ _____ ___ _-- >
APA-ZZ-01003-Rev. 17- g'g6 ,
ry
The intermittent release (X/Q) curve was constructed using the calculated 1-hour 15 f; percentile (X/Q)y and its corresponding annual average 1(X/Q),. A graphic representation, of how the computational procedure works is illustrated by Figure 4.8 of reference 11.15.1. The straight line connecting these points represents (X/Q)y values for intermittent releases, ranging in duration from one (1) hour to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />. The slope (S) of the curve is expressed as:
W
- -log ( (X/Q)1/ (X/0),1 (6.3)
S= ~
log (Ta/T y) or (log (X/0)y - log (X/Q),1 (6.4)
S=
log Ta - log T 1.
6.2 Atmoscheric Discersion Parameters for Farming Areas Within The SITE BOUNDARY The dispersion parameters for farming areas ~
within the SITE-BOUNDARY:are intended for a narrow scope _ applications That of calculating the
' doser to the1 current tennant farmer from gaseous-
.effluentsLwhile he conducts. farming activities within-the SITE BOUNDARY.
1 e
4
- 108 -
+-m:-mm g - - , , rym - w
APA-ZZ-01003 Rev. Y A gg ,,,
i For the purpose of these criculations, it was assumed that all of the f armer's time, approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year, is spent on croplands within the SITE BOUNDARY, and that his time is divided evenly over all of the croplands.
Fractional acreage / time - weighted dispersion parameters were calculated for each plot as described in reference 11.5.6. The weighted dispersion parameters for each plot were then summed (according to type) in order to produce a composite value of the dispe.sion parameters.
The dispersion parameters presented in Tables 9 &
10 therefore represent the distributed activities of the farmer within the SITE BOUNDARY and his estimated occupancy period.
109 -
~
Am-ww-u
! nov. .L 4 cj d 'i-M/,i n- 1)
[]j
/ . /
pne E 9 fflCetrST AffilHAL AVf ftAG[ AIMOSP110 tlc DISPGS(.ON PARAM([ERS (gj f t AD4/AS T[__D3J119J 81Q _yf_tjl X/Q X/4 DISTANGC DM?ygd/U!!dSE ited l imca,yed/lD eght gd p/J StCIOR (M11ljis) 3/9 l lOCAIIOtt[h1 (sec/ml) (m 2)
(sec/m2) (sec/m3) 1.10-6 8.3E-9 4
2200 !.3t-6 1.30-6 NtiW Slit 000NDARY is . 9 E-7 1.6E-9 4/SW 2372 5.7[-7 $.7E-7 Nea s est Cow (c) se.9E-7 1.60-9 t/SW 2372 5.7E-7 5.7E-7 Heaanst Goat (c) 7.20*7 2.0E*9 2868 8.7E-7 8.7E-7 taea s e st ticat Animal (d) Ntn/
7.20-1 P.6E-9 ttuasust Vegtalste (c) 2068: 8.7t-7 8.7E-7 car, ten NtfW 8.7E-7 7.2E-7 2.6E-9 NttW 2S68s 8.70-7 Neasest Hesidence(c) 2.6E-7 1.10-9 2.9E-7 2.9E-7 I a rm e ng Areas 1/i tisin N/A N/A Site ununda ry (c )(u )
1 (a) Valuus given are rrum ISAR Isble 2.3-88s (b) Data from 1908 t.and Use Census in Equa tiott (6.1)
(c) Va lues de rived i' rom i SAR lable 2.3-83, using the methodology presented
( f to f . 11.5.6)
(d) the nea res t a ca t animal is assumed to exist at the locatior af the nearest resident.
for a narrow scope application. E xtr. me caution sliould be exerci sed (e) 1 when hose va lues were derived in other applications.
dutosmining their suitability f~or use nullding shapo Pa rameter (c) = 0.5 (nor. 11.5.3) 11.5. 3 )
vertical sle iyht or itighest Adjacent nul ldirig (v) = 19.9e> me te rs ( ne r.
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APA-22-blUU3 g1-j y,,
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et:,v. 4.z 3
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T AI)I E 10 UICilGT ANNUAt_ fyj_RAGI All4051*llf R IC Ol Sf(RSIOti P6ARAMrfrRS [aj
!)til!_ Ytt11 DESIANCE X/Q X/Q ljfr^ l l 8]tL_I t' ) SIC 10R liiE._lMEl 5/9 D0cfY"i l.U l Heje;gd e ty! pgcaygiQDefniglgd I!/3 (sec/ml) {sec/m3) (6ec/ml) (m 2) 2200 1.00-6 9.90-7 8.50-1 8s.30-9 Stil. Isout40Af tY NNW 2172 es s,sE-7 8a . 8t E- 7 3.80-1 1.6E-9 fica r e t. t Cow (c) USW 21/2 86 . 8s E - 7 3.00-1 1.60-9 ric a re :. t Goat (c) U5W is . 8e E - 1 2t368: 6.8E-7 6.80-7 5.7t-1 2.60-9 No.s r e :. t Heat Animal (d) titni tie.a r et s t Veg t.dts t e (c ) $.70-7 2.6E-9 Ga rden fit;W 2n68: 6. r, t'- 7 6.8E-7 28681 ti . 8 0- 7 6.80-7 S.70-1 2.6E-9 Neare.t Posidence(c) titol f a r m s s..g A rc.s s Wi t tii si tlau 1.90-1 1.1E-9 Site Itounda ry( c )( e ) ti/A N/A 2.10-7 2.10-7 (a) V lues given are from ISAR Table 2.3-82 (b) ti.s ta from 1988 tand tJso Census (c) v.s t ues derived f rom f SAft Table 2.3-83, using the methodology presented in Equation (6.1)
( ite r . 11.5.6)
(d) llee nearest meat animal i s a s sumed to exist at the locationExtreme of the nearest resident.
caution sisou l d tse exerci sed (e) these vatuos weses du r i ved for a na rrow scope app l ica t ion.
wisen determining tieei r suitability f or use in ottier appl icat iores.
f t si id leig Shapo Pa ra me t e r ( C ) = 0. 5 ( Re r. 11.5. 3 )
V e r t i c.s i lic a gh t of liigliest Adjacent fus i l d ing (V) = 66.6 meters (Her. 18.$.3)
-111-
APA-ZZ-01003 .
Rev. 2" 7. L I~' '# I f
') TABLE 11 SHORT TER*4 DISPERSION PARAMETERS (a) (cl Slope Factor (S)
Location (b) Sector Distance Unit Vent Radwaste (meters) Building Vent Site Boundary S 1300 .328 .320 Nearest Cow NW 5053 .263 .266 Nearest Goat NW 5053 .263 .266 Nearest Meat NNW 2736 .262 .268 Animal Nearest Vegetable NSW 2865 .264 .268 Garden Nearest Residence NhW 2865 .264 .268 i
(a) Reference 11.5.3 (b) Data from 1987 Land Use Census (c) Recirculation Factor = 1.0 112 -
Aas-LL-Unovp
[ . sf_g / - ', - -
fiev. f .4 LA!!LE 1R T
APPt.lCAT IOtt Of A1. H OSrit[ftlC DISPf ftSIOff FARAM[mURS CON I HOI..t I NG Cott litOt_i_ t t4G DISPfitsION AGE GitOUP LOCAT!O'(
OD(.f4 Hl. I I It! tiCI: PAftAHf i t 14 DO5f t- A l ltWA Y -- Site Boundary X/Q, decayett/usalepleted Nutste G.as,_lieta Air 3.5.2.I ( 2. ?(. day liairlife)
-- Si te bounda ry X/Q, . decayed /ustifep le ted Noble Gas, Comma A l r- 3.5.2.I (2.26 day tiaiflife)
Si te Bounda ry X/Q, decayed /undepleted Huble Gas, lutal Budy 3.88.1 & 3.5.1.1 (2.26 t!ay lis t f t i f c)
- Site Doundary 1/Q, decayeif / undeple ted t<util e Ga s , Skin 3.8a.2 & 3.5.3.8 (2.26 day fiaif4 ire)
-- Nea rest ?tes ident 3.5.2.2
)/Q Ground Plane Deposition Hearest fle s iden t Cal 3d 1/Q, deca'ed/deptete:1 tutnesatson 3.5.2.2 [c day fialflifc}
C7:3 sd itearest fle sident D/Q*
l Veeje t a t i on 3.$.2.2 tsca res t fle s i den t C2ii ld D/4' f 3.5.2.2 l t4 i I k Ciel Id Nearest ite s i den s 3.5.2.2 D/Q*
McaL
.. o f D/O ( fle f =1 rerm e it.71.1).
"f or la- 3 and C- 1fs , lt /Q, decayed /dripleted is usti:0 O
-f13-
APA-ZZ-01003
- (
Rev '5. X , ,9 l
_7 . 0 REPORT.90 REQUIREtiENTS
-7,1 ANNUAL RADICLOGICAL ENV:RONMEMTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Repcrts covering the. operation of the E unit during the previous calendar year shall be submitted prior to May 1 of each year,- The initial rey shall be submitted-prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previour, environmental surveillance reports, and an assessment of the observed impacts of the. plant operation on the environment. The reports shall also include the results of Land Use Censtses required by Section 9.12.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological envi'rnnmental samples and of hil environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the CDCM, as well as summarized the tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Eranch Technical Position, Revision 1,-November 1979.
In the event that some individual results are-not available for inclusion ~with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall-be submitted as soon as possible in a supplementary report.
114 -
AFA-ZZ-01003 Rev. % %
(3 )k >_ A l
)
The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action.
being taken if the specified program is not being performed as required by Section 9.13.1; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 9.11.1 and discussion of a 1 deviations from the sampling schedule of Table 9.11-A, discussion of environmental sample measurements that exceed the reporting leve)* ,f Table 9.11-B, but are not the result of the piant effluents, pursuant to Section 9.11.1; and discussion of all analyses in which the LLD required by Table 9.11-C was not achievable.
i
- Cne map shall cover stations near the SITE BOUNDARY: a second shall include the more distant stations.
-115-
~ _. - -
Rev. J.% (- y-f i l ]
4 7.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE PEPORT g.
Routine Semiannual Radioactive' Effluent Release during Reports covering _the operation of the unit i
the previous 6 months of operation shall be submitted within 60 days after January 1 and July
} 1 of each year. The period of the first report
}. shall begin with the date of initial criticality, The Semiannual Radioactive shall include Effluent a summary of Releass the quantities f- Reports of radioactive liquid and gaseous effluents and solid waste released - from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity-in Solid Wastes and Releases of Radioactive Materials in Liquid and Gasecut Effluents from. Light-Water-Cooled Nuclear Power Plants, " Revision 1, June 1974, with data summarized on a quarterly basisFor following the solid wastes, format of Appendix B thereof.
the format for Table 3 in Appendix B shall be supplemented with three additional categories:
class-of solid waste (as defined by 10 CFR Part LSA, Type A, Type 60), type of container (e.g.,
B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).
-115-
AFA-00-J1003~, , i gey 4p g 0 < P </ 1 l' \
i The Semiannual Radioacti"e Effluent Release !
Report to be submitted within 60 days after January 1 of each year Jhall include an annual i aummary of hourly meteorological data collected l' over the previous year. This annual summary u.ay be either in the form of an hour-by-hour listing l en magnetic tape of wind speed, wind direction, l atmospheric stability, and precipitation (if '
measured), or in the form of joint frequency and distributions of wind speed, wind direction atmospheric stability *. This same report shall include an assessment of the' radiation doses due ,
to the radioactive liquid and gaseous off14ents !
released from the unit orThis station same during report the shall previous calendar year.
also-include an assessment of the radiation doses from radioactive liquid and gaseous effluents to !
MEMBERS OF THE PUBLIC due to their activities l inside'the SITE-BOUNDARY (Technical .
Specifications, Figures 5.1-3 and 5.1-4) during the report period using historical All assumptions used in average ;
atmospheric condit$ons.
making these assessments, i.e., specific activity,. exposure time andThe location, meteorological shall be ;
i included in these-reports.
i conditions concurrent with the time of release of radioactive esterials in gaseous effluents, as ;
l s
- -determined by simpiing frequency and measurement, shall be used for determining the elseous pathway !
doses. The assessment of racia*,vn dosos shall be performed in accordance wit'. the methodology ;
and parameters in the OFFSITE DOSE CALCULATION '
MANUAL (ODCM). i i
I
. t Ef fluent Release i
. i
- In lieu of submission with ths Semiannual Radioact ve j Report, Union. Electric has the option of retaining this summary of required meteorological data-en site in a file that shall-be-provided-4 to the NRC upon request.
' - 117- ,
i
-y e ,, , , . ,,w ,_y, ,. ,, ,4,'%.. . , , , , , . . . ,mm..,,,,.__,...,-. __ i m , ,_....,, _.,._., m.. _ , , . , ,..,.___......m,,_,,...__...m_ _
9 g3 Rev..P ; ...,M' q&
i The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doces to the likely near exposed MEP.3ER ;F THE 7"dLIC frem Reacter releases and other nearby uranium fuel cycle sources, including doses f rc.n primary ef fluent pathways and direce radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Fower Operation."
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1,109, Rev. 1, October 1977.
The Semiannual Radioactive Effluent Release of Reports shall include a list and description unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid offluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports shall include any major changes made during the reporting period to any Liquid or Gaseous Treatment Systems, pursuant to Section 10.1. It shall aise include a listing Of new locations for dose calculatiens and/or environmental monitoring identified by the Land Use Census pursus t to Section 9.12.1.
The Semiannual Radioactive Effluent Release Reports shall also include the following information: An explsnation as to why the inoperability of liquid er gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 9.1.1 or 9.2.1, respectively; .snd description of the events leading to liquid holdup tanks or gas storage ta'nks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively.
.15-l
- - - - --_m_____ _ _
APA-ZZ-01003 Rev . 1- JJ c ,< y , f . y 7'j 2815 The Semiannual Radioactive Effluent Release-Reports shall also include as a part of or submitted concurrent with, a complete and legible ccpy of all revisions of the CDCM that occurred during the reporting period pursuant. to Specification 6.14.2.
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-119-c
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APA-23-01003 j 1
Rev. V A
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- s 8.0 IMPLEMENTATION OF CDCM METHODOLCOY The CDCM provides the mathematical relationshipo :
used to implement the Radicactivo Effluent :
Controls. l For routine effluent release and dose assessment, i computer codes are utilized to implement the ODCM methodologies. - These codes have been evaluated by a qualified independent reviewer to ensure that they produce results consistent with the .
methodologies presented in the CDCM. (Ref. lt 11.5.4.)
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-120-
APA-Z"-01003 Rev.,l'.ggl. f / il
- % 9.0 RADI0 ACTIVE EFFLUENT CONTROLS (REC)
. 1~
NOTE 1. The terms in this section that
~~~~
appear in CAPITALIZED TYPE aro !
defined in Technical Specifications.
- 2. All f requency notations are per .
Table 1.1 of Technical Specifications.
9.0.1 Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION-requirements shall be met.
9.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified I
time intervals. If the Control is restored prior i to expiration of the specified time intervals, i completion of the ACTION requirements is not required.
9.O.3 When a control is not met, except as provided in the associated ACTION requirements, within i hour ACTION-shall be= initiated to place the unit in a 1
' MODE.in which the Control does not apply by placing it, as applicable, ini l l
- a. At least HOT STANDBY within'the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, ;
- b. At least HOT SHUTDOWN within the following ,
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- c. At.least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that j permit operation under the. ACTION requirements,. -e the action may be taken in accordance with the '
specified time limits as measured-from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual Controls,' .
This Contbol is not applicable in MODE-5 or-6. .
I
-121 T 9
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N i Rev. P.; l f f _~ g. j.*) u i 9.0.4 Entry into an OPERATICNAL MODE or other specified condition 4, hall not be made unless the conditions for the Control are met without reliance on provisions contained in the ACTION requirements.
This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual j Controls. ;
9,0.5 Operability of equipment included in Section 9.0 must be tracked in the Equipment Out-of-Service Log 'EOSL) as per ODP-ZZ-00002, Equipment Status isd.co1.
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-122-
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'.!l 9.1 RADIOACTIVE LIgUID EFFLUENT MONITORING INSTEUMENTATICN 41838 9.1.1 Controls 9.1.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 9.1-A shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that The the limits Alarm of Section
/ Trip 9.3.1.1 Setpoints of are not exceeded.
these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MA!UJAL (CDCM).
APPLICABILITY: At all times ACTION:
- a. With a radioactive liquid affluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable,
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 9.1-A, Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Section 7.2, why this inoperability was not corrected within the time specified.
- c. The provisions .o( Sections 9.0.3 and 9.O.4 are not applicable.
41839 9.1.2 Surveillance Requirements 9.1.2.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated CPERAELE by the performance of the CEANNEL CHECK, SCUECE CHECX, CHAN"EL CALI2 RAT!ON and ANALOG CEANNEL OPERATIONAL TEST at the frequencies shown in Table 9.1-3.
.23- l
- - - _ ~ - _ _ _ _ _ _ _ _-
APA-ZZ-01003 Rev . -l' ,2 i
Cf l 5-l 'It 41340 9.1.3 Bases 9.1.3.1 Eadioactive L qu:d Efiluen: Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential The Alarm / Trip releases of liquid effluents.
Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to ev.ceeding 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.
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'APA-ZI-01003 i'
Rev. 4 1 yf /-
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T Anti 9.1-A l'
fyQ[OACT 1VE t.IQti!D EF FLUtNT MOWI TORING lN5ittUMENTATIOtt MittIMUM CitAftNt LS OPf RABt C ACT104 I NS l H4ftil N T j
i
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1 fladioactivity Mornitors Providing Alarm and
- j. Automatic terminatiosa or Release t 31
- a. t equid Itadwaste Di sclia s'Je Monitor (tttt-RE-18) 1 32 -
i
- b. Steam Cerverator Ulowdows: Discliarge Moni tor (DM-RE-$2) 1 32 c.. Turbine Deel 8diswJ Crain Moni tor (LC-RE-$9) 1 33
- d. -Secorada ry t,igtsid 6ta ste System Moni to r (HF-RE-8t$)
l'
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! 2. I tus ftate Mcasureseerit Devices i
- a. t_6guld RaJwaste Discrearge Line
}
1 34 1
t) Wa s te Mors i to r T a rik A D i sctie rtje L i ne i 1 34 i
- 2) Waste Monitor Tank El Discharge Line
- 1 388 j b. Steam Getierator titowlown Discharoc Line 1 34 c ., Secondary t_lquid Waste Systen Discharge Lisee l .
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' Table 9.1-A (Continued)
ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior _to initiating a release: ;
- a. At least two independent samples are analyzed in accordance with Section 9.3.2.1, and
-b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 - With the number of channels OPERABLE Less than required by the Minimum Channels OPERABLE-requirement, effluent releases via this pathway may continue for up to 30 days provided-grab ,
samples are analyzed for principal gamma emitters and I-131 at a lower limit of detection as specified in Table 9.3-At .
- a. At least once per_12 hours when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or t
- b. At least once per 24. hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE
. EQUIVALENT I-131. , ,
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RM Rev. &';L kJ6g j ,9 f Tcble 9.1-A (Continued) 1 ACTION STATEMENTS ACTION 33 - With the number of channela OPERABLE Less than required by the Minimum Channals OPERABLE requirerent, effluent releases via this pathway may continue for up to 30 days provided that prior to-initiating a release
- a. At least two independent samples are analyzed j in accordance with Section 9.3.2.1, and l
' b. At least two technically qualified members of !
the facility' staff independently verify the ;
release rate calculations and_ discharge line valving.
otherwise, suspend release of radioactive effluents via this pathway.
ACTION 34 - With'the number of channels OPERABLE less than required by the Minimum Channels OPERABLE-requirement, effluent releases via this pathway may continue for up to 30 days'provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves-
' generated in place may be used to estimate flow, t
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0 t,' l ",'t "m TABLE 9,1-B (Continued) 4 TABLE NOTATIONS 41841 (1) The ANALCG CHANUEL CPERATICNAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions existas
- a. Instrument indicates measured levels above the or Alarm / Trip Setpoint (isolation and alarm),
- b. Circuit failure (alarm only),. or
- c. Instrument indicates a downscale f ailure (alarm only), or
- d. Instrument _centrola not set in operate mode
- (alarm only).
(2). The initial CHANNEL CALIBRATICM shall'be (gas performed using one or more of the reference ~ L or liquid and solid) standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NES. These standards shall I permit calibrating the system over its-intended
~
range of energy, measurement rar.ge, and establish monitor response to a solid calibration source. For.. subsequent CHANNEL CALIBRATION, NES traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the se.me geometry and type of source standard traceable to NES.
-CHANNEL CHECK shall consist of verifying (3) indication'of flow during periods of release.
CRANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic,
-or batch releases are made.
-129-
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/ 9.2 RADICACTIVE CASECUS EFFLUENT MONITORING
) INSTRUMENTATION 41872 9.2.1 Controls monitoring 9.2.1.1 The radioactive gaseous effluent instrumentation channels shown in Table 9.2-A
- shall be OPERABLE with their Alarm / Trip Setpoints set and to ensure that Technical Specification the limits3.11.2.5 of Section are 9.6.1.1 not exceeded. The Alarm / Trip Sotpoints of these channels meeting Section 9.6.1.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM, APPLICABILITY: As shown in Table 9.2-A.
ACTION:
- a. With a radioactive gaseous effluent monitoring i instrumentation channel Alarm / Trip Setpoint less conservative than required by the above t specification, immediately suspend the release of radioactive gaseous effluents monitored by ,
the affected channel, or declare the channel inoperable. !
) b. With less than radioactive gaseousthe minimum effluentnumber of monitoring l instrumentation channels OPERABLE, take the Restore the ACTION shown in Table 9.2-A.
inoperable instrumentation.to 0FERABLE status within the time specified in the ACTION, or ' explain Effluent in the next Release Semiannual Radioactivepursuant to Report, Specification 6.9.1.7, why this inoperabilit . was not corrected within the time specified. 1: . The provisions of Sections 9.0.3 and 9.0.4 are not applicable. 9.2,2_ Surveillance Requirements t 41843 4 9.2.2.1 Each radioactive gaseous effluent menitoring , instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL. CHECK, t SOURCE CHECK, CHANNEL-CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 9.2-3.
-130- ,
. . . . _ _ _ _ _ _ .,____..._...,,,-__,__a.,_-..
APA-20-U.LUJ Rev.,P,/ fi-/. s/ / 9 >& 1 l 9.2.3 Bases l Effluent Monitorin, 41S44 9.2.3.1 Radioactive Garecua Instrurentat;gn The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual Theor potential releases of gaseous effluents. Alarm / Trip Setpo be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior Theto exceeding the limits of 10 CFR Part 20. OPERASILITY and use of this instrumentation is consistent with the requirements 63, and 64 ofofAppendix General A to Design Criteria 60,The sensitivity of any noble 10 CFR Part 50. gas activity monitor used to show ccmpliance with the gaseous effluent release requirements of Section 9.7.1.1 shall be such that concentrations as low as 1 x 10 8 uCi/cc are measurable.
-131-
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- t S
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'l)$'Stil TABLE 9.2-A ICentinuedl l TA3tE MCTAT!CJ'S i
- At all times. ,
ACTION STATEMENTS ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE , requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the releases
- a. At least two independent samples of the tank's contents are analy:ed, and
- b. At least two technically qualified members ef the facility staff independently verify the release rate calculations and discharge valve lineup.
! Otherwise, suspend release of radioactive ; affluents via this pathway. ACTION 39 - With the number of channels OPERABLE less than
)' required by the Minimum Channels OPERABf,E requirement, effluent releases via tnis pathway may continue provided the flow rate is estinated based en fan status and operating curves or actual measurements at least once per 4 hours.
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab - samples are taken at least once per 12 hours and these samples are analysed for radioactivity within 24 hours. ACTICN 41 - With the number of channels OPERAELE one less than required by 'the Minimum Channels CPERA5LE requirement, PURGING of radioactive effluents via this pathway may continue for 24 hours. With
-both channels inoperable, immediately suspend PURGING of radioactive effluents via this pathway.
3
-133-
-I
. - , - , , , , - - - - - - . - - , , , - - - - - - - ~ - - - - - - - - - - - - - - -
Re v . X ,4 Q) ,l 4. I f-p.B_L_E 9.2-A (Centinuedl TABLE NOTATIONS ACTION 43 required - With the by thenumber tiinimum of Channels channelsOPEPIDLE OPERABLE loss than l requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary i sampling equipment as required in Table 9.6-A. : l ACTIo!4 45 - Flow rate for this system shall be based on fan - j status and operating curves or actual i measurements. r t r i 6 L
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SUttV[ittANCE PEm7fREMfNf3 RAflinACi t Vi GA5f 005 f fi t tif MT MONf f 0F f MG f MSTHtWLP!T AT ION ANALOG CriANNi t_ MOfR S F Oft uit i Cst OP[flA T I Ot4AL SUtivif f I ANCE SOtiftCf CitANNFL 15 fil 918 8149 O CilANtil l CA_I l lM( Al l O'j TQI CettCK C111CM I N}l topil. t! I
!. Urs i t Venit System It(3) O(2)
D M a, thab le Ga s Ac t a v i t y Phuo l to
- P rov id i sp) A l a r se ( 0 f - ftf -21 ) fl . A .
N.A. W N.A.
- 13 t od i e e Sampfer N.A.
N.A. W N.A.
- t'artsculate Sa ms. t e r O
- c. N(88)
N.A. N.A. *
- d. Ilow ilate R Q D N.A.
- r. Samp l e r i I ow Rate M,oteitor 2.
Caen t a i t.me:n t f*u rtre System a. flob i c Ca s Ar: t i v i ty Mans i to r - R(3) Q(1
- P suv i d i sp; Alasms and Aestomatic D f*
t er misia t loss of' lte lea se
- t c i-nt. -22, CT -itt - 3 3 3 N.A.
N.' W N.A. *
- h. Bodine Sampler M.A. N.A.
W N.A.
- Pa r t i cu l a t e Samag f e r N.A.
c. M.A. R(4) N.A. *
- d. 6 low fla te M N.A.
D N.A.
- e.
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- 3. Hadweste thsildisp) Vcsit System Ht3) 4(1)
P M. P D,
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rs ow i d i enj Alarm aswl Atitoes.s t i c
- termina tices of heicase ( Gil-ft t- 10 ) N.A.
N.A. W N.A.
- is , lodiere Sampler N.A. N.A.
W N.A. *
- c. Pa rt iccola te Samgele r R ( 83 )
ff . A . N.A. N.A. *
- d. tlow Hate H tt . A .
D N . f.. e, sa pier t rov Ita te Moni tor
- 13 '>- E
APA-ZZ-01003 i l R e v . W'2- .js .'t.' g t sll TABLE 9.2-B (Continued) TABLE NOTATIONS l 41845 ;
- At all times. .
The ANALOG CHANNEL OPERATIONAL TEST shall also : (1) ; demonstrate that automatie isolation of this ! pathway and control roem alarm annunciation occur as appropriate if any of the following conditions i exists: ,
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), lor la. Circuit failure (alarm only), or-i
- c. Instrument indicates-a downscale failure (alarm only), or ,
- d. Instrument controls not set in operate mode (alarm only).
(h The ANALOG CHANNEL OPERATIONAL TEST shall also I demonstrats that control room alarm annunciation occurs if any of_the following conditions exists: i a, _ Instrument indicates measured levels _above the ' Alarm Setpoint, or b, circuit-failure, or
- c. Instrument indicates a downscale failure, or
- d. Instrument controls not set in operate mode, ,
4 9 J
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-136- ,
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TABLE 9.2-B (Continued 1 TABLE NOTATIONS (3) The initial CHANNEL CALIBRATION shall be reference (gas l performed using one or more of the l or liquid and solid) standards certified by the l National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source. j For subsequent CHANNEL CALIBRATION, NBS traceable standard (gas, liquid, or solid) may be usedt ei a gas, liquid, or solid source that has bosr. calibrated by relating it to equipment that veo previously (within 30 days) by the same gec.rresy and type of source traceable to NBS. (4) If flow rate is determined by exhaust fan status i i and fan performance curves, the folleving surveillance operations shall be performed at 1 east once per 18 months a The specific vent flows by direct measurement, or
- b. The differential pressure across the exhaust
~
fan and vent flow established by the fan's
" flow-AP" curve, or
- c. The fan motor horsepower measured and vent flow established by the fan's
" flow-horsepower" curve.
e ( s h i
-137-
&#F-Yif;V'NtD t Rev. l' )
p est 9 ,t L [~) 2881 9.3 LIQUID EFFLUENTS CONCENTRATION , 41846 9.3.1 Controls 4160 9.3.1.1 The concentration of radicactive material released in 11guid effluents to UNRESTRICTED ! AREAS (see Technical Specification's Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides ' other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the , concentration shall be limited to 2 x 10-
- microcurie /mi total accivity.
i APPLICABILITY: At all times. ; ACTION:
- a. With the concentration of radioactive material released in liquid effluents-to UNRESTRICTED-AREAS exceeding the above limits, immediately restore the concentration to within the above
-limits,
- b. The provisions of Sections 9.0.3 and 9.0.4 are '
not applicable. 41847 9.3.2 Surveillance Recuirements 4 2895 9.3.2.1 Radioactive liquid wastes shall be sampled and analyced according to the sampling and analysis , program of Table 9.3-A. 9.3 2.2 The results of the radioactivity analysis shall-be used in accordance with the methodology and parameters in the CDCM to' assure that the . concentrations at the point of release are maintained within the limits of Section 9.3.1.1. . 5 g
-138-
. . . , , , , . . . . - . . . . . . . . , . . . - . , _ . . . . . . , . . _ . - , . - , . . - , . . ~ . . _ . - , . . . _ . . . _ . . . . _ _ . , . . . . , . . . _ . . _ . . . _ . , _ . . . - - . . . . . . . . - . . . , - ~ , . . . . . , .
APA-02-01003 Rev. P / C)>f f-/ 'l/ 9.3.3 Bases 9.3 3.1 This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures withini (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 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent-concentration in water using the. methods described in International Commission on Radiological Protection (ICRP) Publication 2. 9.3.3.2- The required detection capabilities for radioactive materials in liquid waste samples are tabulated-in terms of the lower limits of detection (LLDs). Detailed discussion of the r LLD, and other detection limits can be found in EASL Procedures Manual, MASL-300 (revised annually), Currie, L. A., Limits for Qualitative Detection-and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93~(1968), and Hartwell, J. K., " Detection Limits f or Radioanalytical~ Counting -Techniques", Atlantic Richfield Hanford Company Report ARM-SA-215 (June 1975). l
- 139-T457s 4f a.
-&3<,ep% g p ..--y,wcpey e,y9,.yy,.wegy.- m yypg, 9..9,yan_y yg,,,_g.,%,,_g. -
my- - wm-enw-w--
APA-Z: 01003 l_ Rev. t .a J' TABLE 9.3 A {// p / <// RADIVACTIVE LIQUID VAtTE SA"dI3G AND ANALYSIS PROGRAM j~ l l l l LOVER LIMIT l I j l 1 HINIMUM i l OF DETECTION l ITYPE OF ACTIVITY l (LL'.))I ) l LIQUID TsELEASE l SAMPLING l ANALYSIS TYPE l TREQUENCY l TREOUENCY l ANALYSIS l_ (vC1/ml) l I l l l l l l_ l l P l l l 1. Batch Vaste l P leach Batch lEach Batch l Principal Gamma l 5x10"# l l Release I3) l Tanks (2) l l l Emitters l l I I -l 1 1 l l 6 1x10 g l~ l l l I-131 l l l J l a. Vaste l l l , l l Monitor { l l M l Dissolved and l 1x10 l
]_ Tank l P 1 l
-l lone Batch /Hj l Entrained Gases l l
l l l l(Gamma Emitters) l 1 1 -l
- l. - b. Secondaryl_ l l
l l- Liquid l l l
*I H l H3 l 1x10 l l- Vaste l P \
Monitor -lEach Batch ICompositeI ')l 1 _ l l *7 l Gross Alpha l 1x10 l l l Tank .l ') l l l 1 l l *8 lSr-89, Sr 90 1 5x10 l ; l c. Discharge l .P .1 Q
~0 1x10 1.
'l Monitor leach Batch l Composite (')1 Fe 55 l I l I
.l Tank I I l
1 l l 1 1 V l Principal Gamma l 3x10"I l l 2. Continuous l l
- Releases ( )'lDaily(0) l Composite ( )l Emitters (3) l l
-l l l l
l Grab Samplel- l __ 6 g l l l I-131 l 1x10 l I l I I j Steam l l l Generator 1. l l ' l M iDissolved and l 1x10 l
.) Blowdown l M_
l
)
l l Grab Sampiel (Entrained Gases l l
- l l l l(Gamma Emitters) l l I 1 -
l l I l ~3 M l H-3 l 1x10 i l' l l I l (Daily (0) ICompositab)l t _l iGrab Sampiel IGrJss Alpha l 1x10' l l- I i 1 I
-l l
! Q ISr B9, Se 90 1 3x10'8 I 1: !
IDaily(6) (Composite (')l_ i _l l' IGrab Samplel ITe 55 1 1x10
- I 1 l l 1 ! I i
. iso-
'i
(pt,.gf TABLE 9.3-A (Continued) TABLE NOTATIONS , 'i I (1) The 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 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. , For a particular measurement system, which may include radiochemical separation: { 4.66 s b LLD = E
- V + 2.22 x 10' + Y
- exp (- Aat)
Where LLD a the "a priori" lower limit of detection (microcuries per unit mass of volume), ; s a the standard deviation of the background 3 counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per , disintegration), V = the sample si:e (units of mass or volume), 2.22 x 10 = the number-of disintegrations per 8 minute per microcurie, Y = the fractional radiochemical yield, when applicable, 1 = the radioactive decay constant for the particular radionuclide (s 8), and t at = the elapsed time between the midpoint of : sample collection and the. time of counting (s). Typical values of E, V, Y, and at should be used in the calculation.
-141-
n.m- -.___ Rev. 1 cl C)'f ; . j .9 1 ! ABLE_9 3-A (Continued) TAELE NOTATIOMS 4184B should be recognized that the LLD is defined It as a _a_pripp; (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. (2) A batch release is the discharge of liquid wastes Prior to sampling for of a discrete volume. analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the CDCM to assure representative sampling. (3) The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn-54, Fe-59, Co-50, co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Seminannual Radioactive Effluent Release Report pursuant to Technicalin the format outlined in Specification 6.9.1.7, Revision 1, Regulatory Guide 1.21, Appendix B,
' June 1974.
(4) A composite sample is one in which the quantity of liquid sampled is preportional 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. Prior to analysis, all samples taken for the cemposite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release. (5) A centinuous release is the dischargefrom of liquid a wt.tes of a nondiscrete volume, e.g., flow during 741sme of a system that has ar. input tso sentinucun release.
-142-
APA-ZZ-010Q3 Rev. E t j i= g. 4I TABLE 9.3-A (Continued) -s-1 TABLE NOTATIONS (6) Samples shall be taken-at the initiation of effluent flew and at least once per 24 hours thereafter while the release is occurring. To-be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shal.'. be , maintained constant for all-samples taken for the J composite sample. i
, 4 I
t 4 r
) -143- - _ _ . _ ___ .___.-.__._.._._.._.a_.-_. . _ _ - ._..._ . .2.____..._.___.......,~~
- ~~-- - -- - . _ - ______ -______. APA-ZZ-01003
+
Rev. Pa ti t~ g t il
' 9.4 DOSE 41849 9.4.1 Centrols 4160 9.4.1.1 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, frcm each unit, to UNRESTRICTED AREAS (see Technical Specification's Figure 5.1-4) shall be limited:
- a. During any calendar quarter to lens than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report
- hat identifies the cause(s) ,
for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releasec will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished 7 drinking water supplios with regard to the f requirements of 40 CFR Part 141, Clean Drinking Water Act.*
- b. The provisions of Sections 9.0.3 and 9.0.4 are '
not applicable.
'The requirements of ACTION a. (1) and (2) are applicable only if drinking water supply is taken from the receiving water bcdy within 3 miles of the plant discharge. In tne case of river-sited plants this is 3 miles downstream only. '
.44-
ara-oc-vavva Rev. l' L . i{ . gal
^'
9.4.2 Surveillance Recuirements 9.4.2.1 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. 41850 9 4.3 Bases 9.4.3.1 This section is provided to implement the requirements of Sections II.A, III.A and IV.A of The Limiting Appendix I, 10 CER Part 50. Cc. dition for Operation implements the guides set fo, th in Section II . A 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 radioaccive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will net result in radionuclide concentrations in the finished drinking water that are in excess of the
; requirements of 40 CFR part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I which specify that conformance with the cuides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMEER OF THE FUELIC through appropriate pathways is unlikely to be substantially underestimated. The equations spic 'ied in the CDCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in
.. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine eleases of Reactor Effluents for the Purpose .: Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision 1, Octcher 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents frem .\ccidental and Reutine Reactor Releases for the Purpose of Implementing Appendix I", April 1977
-145-
APA-ZZ-01003 Rev. J'$ Jfq-qt 9.5 LIQUID RADWASIE TRE7(.;"PT SYSTE!1 41851 9.5.1 Cont-ols 4160 9.5.1.1 The Liquid Radwaste Treatment System chall be OPERABLE and appropriate pcrtions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Technical Specification's Figure 5.1-4) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period. APPLICABILITY: At all times. ACTION:
- a. With radioactive liquid waste being discharged without treatment a d in excess of the above limits and any porticr. of the Liquid Radwaste Treatment System not in operati.on, prepare and submit to the Ccmmission 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 treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Sammary description of action (s) taken to prevent a recurrence.
- b. The prc .sions of Sections 9.O.3 and 9.0.4 are not applicable.
41852 9.5.2 surveillance Requirements 9.5.2.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized. s
.k$*
APA-ZZ-01003 ( I Rev. Eg d...qi i }s 9.5.2.2 The installed Liquid Radwaste Treatment System shall be considered OPERAELE by meeting Sections 9.3.1.1 and 9.4.1.1. 9,5.3 Bases 9.5.3.1 The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the envir'onment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releasos of radioactive materiala in liquid effluents will be kept "as low as is reasonabley achievable". This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D cf Appendix ! to 10 CFR Part 50. The specified limits governing the use of appropriate portione of the Liquid Radwaste Treatment System were specified as a suitable fraction of the ccse design objectives set forth in Section 11.A of Appendix I, 10 CFR Part 50, for liquid effluents.
)
1
. .. .- - .~ .- = - . . - - _ = . . _ ~ _ . - -. - . _ ~ . - . ~ .-
APA-ZZ-01003 Rev, g) Pl' , .y I 96 GASECUS EFFLUENTS DOSE RATE 41853 9.6.1 Centrols
.4160' 9.6.1.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas -at and beyond the SITE BOUNDARY (see_
Technical Specification's. Figure 5.1-3) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and.
- b. For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives areater than 8 days: Less than or equal to 15 0 mrems/yr to any organ.
^
APPLICA3ILITY: At all times. ACTION:
- a. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).
- b. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41854- 9.6.2 Surveillance Requirements 9.6.2.1 The dose rate due to noble gases in gaseour effluents shall be determined to be within the above limits in accordance with the methodology - and parameters in the CDCM. 9.6.2,2 The dose rate due to Iodine-131.and 133, tritium, and all radionu.clides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the , above limits in accordance with the methodology and parameters in the CDCM by obtaining. representative samples and performing analyses in accordance with the sampling and analysis program spe-ified in Table 9.6-A.
-148-
.c - - , + + . , - ., - .y-. y..- -,
-Rev.XpMj;..g 19.6.3 Eases 41855 9.6.3,1 This section is provided to ensure that the dose at any time at and beyond the SITE SCUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, .
Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous _ effluents will not result in the' exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, 14 annual average concentrations i
-exceeding the list.its specified in Appendix B, l
Table II of 10 CFR Part 20 (10 CFR 20.106(b)). For~ MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER 0F THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the
' SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate
. occupancy factors, shall-be given in the ODCM.
The speci 'ed release rate limits restrict,-at all-times, '.e corresponding gamma and beta dose i rates above backgrcund to a MEMBER OF THE PUBLIC at- or beyond SITE BOUNDARY to _less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin. These release rate-limits also-restrict, at all times, the corresponding thyroid dose rate above , background to a child via_the inhalation pathway to less.than or equal to 1500 mrems/ year. 9.6.3.2 The required detection capabilities for radioactive materials in1 gaseous waste samples are tabulated in terms of the lower limits of-detection (LLDs). Detailed.discussicn of the LLD,. and other detection limits can be found in
- EASL Procedures Manual,EHASL-300 (revised annually), Currie, L. A., " Limits for Qualitative
-Detection and Quantitative Determination --
Application to Radiochemistry", Anal. Chem. 40, 586-93-(1968),. and Hartwell,-J.'K., " Detection Limits for Radicanalytical Counting Techniques", Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
-149-
~
,l
.)
APA-ZZ-01003 Rev.J'] y5 i si 1Alli.E 9.6-A ftADl0ACi lV1: CASEOUS tlAS10 SAMPl.fMG AND ANAL.YSIS PROGRAM l l 1 owtit LIHsI or l l I lat t n : Hun l Att Al YS I S l lYPE Of I DETECilott (4.tD) -('ll .I l$AMPl.lHG j f HL4t_ff3CY lACTIVliY ANAL.YSIS l (DC4/ml] .1 ICASLOtlS ItL Q M C 1YPE ll_It(gu_jyCY P i (2) 4 -4 l
- P. I l 1 .
l Facts fank iPrincipal Camma [mitters i 1x10 l1. Waste'Cas Decay I fach lank i l I lagk, l Grals Sample l _ _l_ I I I l P i P 1
-4 l l (3) I -(3) I .
(21 1 l .Camma Emitters I 1x10 l
- 12. Containment f* urge Itact PultCE l[agli PUlIGC l Principal
-6 l I 1 I . (31 IGrab I .
jli-) (y W e_) l 1x10 l 1 o r _Ya;!!L l H (2) -4 i I lSamele ( 3 ),(4 ) ' 1 (3) I { Principal Ca_smaa teltters 0 l 1x10 $
- 13. tinit verit lH l _!i _ ! -6 i l
l Grab Sample 1 (4) l 1 1x10 1 l l H l!I-J_[ o x i de ) l t, (5) I i (2) 1 -4 I I Spent luul fluilding l H
- I H l Principal Camma imitters [ 1x10 1 l 84 -6 i I [)tlia n s t . l Grab Sample I (5)_ l 1 i 1xio l
! l H 118- 3 (o_x t ee l i - I (2) 1 -4 I 1
l . 1 lPrincipaI Camraa Emitters 1 1x10 i l$. Radwaste bolIding i H I l l H,_ l l l, J ent l Crab Sac *nfo i -12 l 1 I .
- 6) (a) 1 (7) 1 i 1x10 I
- 16. All ite l ea se types l Continuous i W lj .lj t
-10 I i as listed in 1., I (Clia rcoa l i 1 1)< 10 l l 2., 3., 4., and l lSy nto ll-133 l
-ti i I (6) (a) 1- (7) 1 12) 1 l S. above u irrincipal Camma Emitters i 1x10 I i IContinuous l l 1 l l l Pa rt icula te l I l I i isjmpic ~
1
-11 l H l 1 I i (6) (8) l ICross Alpha i 1x10 l l Continuous l Composite l i l 1 l l Pa rt i cula te 1 I
1 i i IMmelo I -11 l i I (6).(a) i 4 1x10 i l Continuous l Composite ll Sr-89, Sr-90 1 l j j l l Particulate I l I i ! i i Isam2 e
-150-
e ,E , .s ; l L
- TABLE 9.6-A (Continued)
TABLE NOTATICMS (Continued) (1) The LLD is defined, for purposes of these centrols, as the smallest concentration of radioactive mater.4al in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: Nl 4' LLD = "b E*V* 2. 22 x 10'
- Y
- exp (-Xat) 1 Where:
LLD = the "a priori" lower limit of detection (microCuries per unit mass of volume), s b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
) E = the counting efficiency (counts per disintegration),
V = the sample sice (units of mass or volume), 2.22 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (s 1), and o at = the elapsed time between the midpoint of I sample collection and the time of counting (s). Typical values of E, V, Y, and at should be used in the calculatien.
-151-
Rev.fl' ) M.7, Al 1 i TABLE 9.6-A (Continued 1 TABLE NOTAT! CMS (Continuedl b 41857 It should be recognized that the LLD is defined as a 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. (2) The principal gamma emitters for which following the LLD specification applies Kr-87,include the Kr-88, Xe-133, Xe-133m, radionuclides: Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Section 7.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL FOWER change exceeding 15% of RATED THERMAL F0WER within 1 hour period. Tritium grab samples shall be taken and analyzed (4) at least once per 24 hours when the refueling canal is flooded. Tritium grab samples shall be taken and analy ed (5) at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever Grab spent fuel is in the spent fuel pool. fuel is samples need to be taken only when spent in the spent fuel pool. The ratio of the sample flow rate to the sampled (6) stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in9.7.1.1, accordance and with 9.8.1.1. Sections 9.6.1.1,
-152-
Rev.j'S Ph A1 ) TA3LE 9.6-A (Continu_eg TABLE UCTATIONS (Centinued) least once per 7 days (7) Samples shall be changed at and analyseu shall be completed within 49 heurs after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, STARTUP or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shallWhen be completed within 48 hours of changing. analyzed, the samples collected for 24 hours are corresponding LLDs may be ine-eased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolantand has(2) notthe increased more than a facter effluent of 3, activity noble gas monitor shows that has not increased more than a factor of 3. Continuous sampling of the spent fuel building (8) exhaust needs to be performed only when spent fuel is in the spent fuel pool. t 0 1
-153-
9.7 DOSE - NOBLE CASES 41858 9.7.1 Cpntrols The-air dose due.to noble gases _ released in gaseous effluents, from each unit, to areas at 9,7.1.1 4160 and beyond the SITE SOUNDARy (see Technical Specification's Figure 5.1-3 ) shall be limited to the following:
- a. During any calendar quarter: Less than or l' equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times. ACTION: J
- a. With the calculated air dose from radioactive noble gases in gaseous effluetns exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to a Special Technical Specification 6.9.2,
,,N Report that identifies th'e cause(s) for J-exceeding the - litait( s ) and defines the
. corrective actions that have been.taken to reduce the releases and the proposed corrective actions to be taken to assure that subsegaent releases will be in compliance with the above limits,
- b. The-provisiens of Sections 9.O.3 and 9.0.4 are not applicable.
41859 9.7.2 Surveillance Recuirements
'9.7.2.1 Cumulative dose contributions for the current-cal'endar quarter and current calen,dar year for noble gases shall be determined in accordance
, with the methodology and parameters in the ODCM at least onca cer 31 days.
-154-
, 4
*~ ~ r ,
Rev. J'm al g, , .o 1 l 9.7.3 Bases 9.7.3.1 This section is providet'_ to implement the requirements of Sections II.B, III.A, and IV.A of The Limiting Appendix I, 10 CFR Part 50. Conditions for Cperation implements the guides The set forth in Section II.B of Appendix I. ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section 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 MEMBER OF THE FUBLIC 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 effluents are 'cor.sistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for 4 the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases frem 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.
-155-
Rev. 7 3 %,,.C 3 9 / 9.8 DOSE - ICDIME-131 AND 133, TRITIUM, AND "h-
- RADICACTIVE MATERIAL IN PARTICULATE FORM 41860 9.8.1 Controls 4160- - 9.8.1.'1 The. dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 6 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Technical Specification's f Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or f equal to 7.5 mrems to an'y organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
f APPLICASILITY: At all times. ACTION:
- a. With the calculated dose from the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives grea*$r
.than 8 days, in gaseous effluents exceec ug s
.) any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions.to be taken to assure that subsequent releases will be in compliance with the abcVe limits.
- b. The provisions of Sections 9.0.3 and 9 O.4 are not applicable.
41861 9. 8. 2' Surveillance Recuirece' hts 9.8.2.1 Cumulative dose contributions for the current calendar quarter and current-calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days.shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
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APA-ZZ-01003 Rev.,% } 'y A l } 9.8.3 Bases 9.S.3.1 This section is prcvided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CER Part SC. The Limiting Conditions for Operation are the 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 Sectdon IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The Surveillance Requirements implement 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 MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the CDCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent
.. upon the existing radionuclide pathways to man, in the areas at and beyond the SITE SOUNDARY.
The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuc] ides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) desposition of radionuclides onto grassy areas where ?. ilk animals and meat-producing animals grace with consumption of the milk and meat by man, and (4) deposition en the ground with subsequent exposure of man.
APA-ZZ-01003 j Rev. .y [ } 9.9 CASEOUS RADWASTE TREATMENT SYSTEM 41862 9.9.1 Controls 4160 9.9.1.1 The VENTILATION EXHAUET TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure Technical Specification's 5.1-3 ) would exceed:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. O.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times. ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6t 9.2, a Special Report that includes the following information:
- 1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to preve.t 7 a recurrence.
- b. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
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APA-ZZ-01003 Yt .p l Rev./ e) k}L,i' 2 l 9,9.2 Surveillance Recuirements i 41863 9.9.2.1 Do es due to gaseous releases from each unit to areas at and beyond the SITE SOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utill:ed. 9.9.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE CAS HOLDUP SYSTEMS shall be considered OPERABLE by meeting Sections 9.6.1.1 and 9.7.1.1 or 9.8.1.1. 9.9.3 Bases 9.9.3.1 The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gasecus effluents will be kept "as low as is reasonably achievable" . This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limith governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections I1.3 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
-15?-
APA-22-01003 i Rev fj jI ,i.i' l
~
9.10 TOTAL DOSE 41864 9.10.1 Controls 9.10.1.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. APPLICABILITY: At all times. e
APA-ZZ-01003 Rev. y 3 1 y 5 i ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 9.4.1.la., 9.4.1.lb, 9.7.1.la.,
9 . 7 .1.1b . , 9.8.1.la., or 9.8.1.1b., calculatiens should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 9.10.1.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 0FR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMEER OF THE PUBLIC from uranium fuel cycle scurces, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance witn 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 Sections 9.0.3 and 9.0.4 are not applicalbe.
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APA-ZZ-01003 j\L,c'O Rev.)] j
.j 41865 9.10.2 surveillance Recuirements 9.10.2.1 Cumulative dose contributions from liquid and gasecus effluents shall be determined in accordance with Sections 9.4.2.1, 9.7.2.1 and 9.8.2.1, and in accordance with the methodology and parameters in the CDCM.
9.10.2.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the CDCM. This requirement is applicable only under conditions set forth in ACTION a. of Section 9.10.1.1 1
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xev, j g y v ) y, 3, 9.10.3 Bases ' 9.10.3.1 This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 16525. The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and the radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 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 from 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 For theto within the 40 CFR Part 190 limits. purposes of the Special Report, it may be assumed that the dose commitment to the MEMSERsources OF THE is PUBLIC from other uranium fuel cycle negligible, with the exception that dose
, contribution from other nuclear fuel cycle facilities at the same siteIforthe within dose a toradius any of 8 km must be considered.
MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFRfor Part 190, the (provided a variance Special Report with a request the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFRThe 190 until NRC staff Partvariance action is ccmpleted. only relates to the limits of 40 CFR Part 190, and does not apply in any way to the othbr requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 9.3.1.1 and 9.6.1.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
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- - - - - - ~ _ . _ _ _ _ _ _ _ _ _
~
APA-ZZ-@l0UW-~- -~~
,O Rev. )]- ji 9.11- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
-41866 9.11.1 Controls 9.11.1.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 9.11-A, -
APPLICABILITY: At all times. ACTION: a._With the Radiological Environmental Monitoring Program not being conducted as specified in
- Table 9.4-A, prepare and submit to the :
Commission, in the Annual Radiological
~
-Environmental. Operating Report required by Section 7.1, a description of.the reasons for
- not conducting the program as required and the plans for preventing a recurrence.
f, n 4
- 164-b
Rev.,1Q< rc y6
- 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 cf Table 9.ll-A when averaged over any calendar quarter, prepare and submit to the Ccemission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 9.4.1.1, 9.7.1.1, or 9.8.1.1. When more than one of the radiocuelides in Table 9.11-B are detected in the sampling medium, this report shall be submitted if:
concentration (21 + ...> 1.0 concentratien (1) + reporting reporting level (1) level (2) When radionuclides other than those in Table 9.11-3 are detected and are this report the be shall result of plant effluents, submitted if the potential annual dose
- to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the 9.7.1.1 calendaroryear limits of Sections 9.4.1,1, 9.8.1.1. This report is not required if the the measured level of radioactivity was not result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report, required by Section 7.1.
*The methcdolcgy and parameters used to indicatedestimate the in potential this repcrt. annual dose to a MEMEER OF THE FU3LIC shall be
-165-l
I APA-ZZ-01003 i,
-Rev.
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by the Table 9.11-A, identify specific iccations for obtaining replacement samples and ' add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.** The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical
-Specification 6.14, submit as part of, or concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible' copy ofLthe entire ODCM, including the revised figure (s) and table reflecting the
- new location (s) with supporting inforn.ation identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples,
- d. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41867 9.11.2 Surveillance Recuirements 9.11.2.1 The radiological environmental monitoring samples shall be collected pursuant to Table 9.11-A from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 9.11-A and the detection capabilities required by Table 9.11-c. 9.11.3 Bases-9.11.3.1 The Radiological Enviornmenta1' Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest .. potential radiation exposures of MEMBERS OF THE-PUBLIC resulting-from the' station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR;Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations-of radioactive materials and levels of radiation are not higher than expected-en the basis of the effluent measurements and the
** Excluding short term or temporary unavailability.
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a r.s - c c - v i v v a Rev. J') lV modeling of the environmental exposure pathways. Cuidance for this monitor 4.ng program is provided J by the Radiological Assessment Branch Technical Position on Environmental Monitoting, Revision 1, November 1979. The initially specified least monitoring program will be effective for at the first 3 years of commercial operation. Following this period, procram 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 9.ll-C are considered optimum for routine environmental measurements It should be recognized in industrial laboratories. that the LLD is defined as 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 Procedures Manual, MASL-3OO (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1986), and Hartwell, J. K., " Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). t
-167-
. .. ....y J,. . - l "
APA-ZZ-01003 Rev. / ff 1r , .j, i_A,Ill E 9.11- A RADIOt.OGICAL fMVis(ONMfHT AL HOgiCHitlG PHOCRM NtlHilf11 OF lt[PitESENT AllVE - TYPE AND FREQUENCY SAMPLES Af4D SAMPLING AND Of ANAL,Y$1S E Xf'OSUR E - l'AllfWAY cot I (CT 10N f f4[QUCttC_Y AND/C M AMPti . . SAf1Pt [ l OCAT lOfG( 8 ) ' _ (2) Quarterly. Camma dose qua rterly.
- 1. Direct Radiation forty roastine moni torisig ' stations ui t, tier vi tti two o r eso re dosimeters or witta one ins t ruracn t for measuritig and .I recordirig dose ra te continatously, placed as foltows:
Art inner ring of sixteen s ta t ions, otte in eacts - inc teo ro log ica l sector in (fee general area of tise SilE DOUf40ARY; Asl oestor ring of stations,'one in atacto smeteorologica l sector its tfie 6- to 8-km (3 to 5 mile) range from tite si te; and E i gtit stations to tie placed in special interest areas sucts as populatiori centers, neartsy residences, scitoo l s, and in one or two. areas to serve as control stations. i
-166-4 ar-
- ud e--e -_____ ' _-_ _ . _ _ _ _ __-_ _ _ _ _ _ . . _ _ - _ _ _ _ - _ _ . _ _ _ _ . - _ _ . _ _ . _ . _ _ _ _ _ _ _ _ - _ - - _ _ _ _ - - . _ _ _ _ _
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Itev. j f4 G - r - y, 1 Allt l' 9.11-Af Cont inue_d.Q ltADlul OGICAt. It(yJftONMf ff f Af f403110ftlNG PftOCftAM HUMilEft Of itEl*ltESENI AT IVE ' TYPE AND fpEQULNCY SAMPIES AND SAMPLING AND EXPnsuflf PAllWAY cot t ECTION Fit [Qtyf(CJ Of ANAL.YSIS ANDf_ Oft SAMPt!~ SAMPtt LOCAT IOfLS( 8 ) l P. Al rtio rnu Continunus sampler i t,e r: Bad. lo ind i ne Cantt _s Samples from five locations; Radiciodino and 8-131 analysis veckly. j operation with sample Particulates collection wechly, or 1hree samples from close to thrs
. tlerec Si1E ilotfNDAftY tocations, more f renteen t ly if in dirrorent sectors, of the regesi red by desst G rM gulate_ Sampler; loading. Gross beta radioactivity highest calctilated antnsal analysis rollowing ave rage g r ouruf leve l - D/Q. filter change; (*) and. .
gamma isotopic analysis (S) l One sampic f rom the vicini ty or composite (by of a 4:ommunity having the leighest loca t ion) qua rt e rly. ca lculate:d annual ave rago - g routed level D/Q. One sasaple from a control location, as for exampic .I'> Lo 30 km (10:to 20 mile) distant and in the least prevalent vind [ direction.(3)
- 3. Waterbortie Composite sample over Gamma isotopic analysis (S) ,
a, Su r t . ice ( 6 ) One sample upstream. I-mototh period ( 7 ). monthly. Composeto for One sample downstream. tritium analysis or composite sample (by I locatiot.) qua rterly. ; Composite sample 1-131 an lysis on each ,
- b. Drinking One sample of each of' one to over 2-week period ( 7) composite vlien the dose >
three or the nearest water when 1-131 analysis ca lcula ted for the consump- E f ' supplios within 10 miles tion or the water is downstream that could be is performed, monthly i composite othervise. greater than 1 mrem per a f'rected by i ts discharge, yea r. ( s ) Composite { for gross beta atu! 3. gamma isotopic artalyses(S) f One sample f' rom a controf monthly. Composite for location. tritium analysis quarterly. i l l i
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d e u n i t n o C o s ( n t Y t i c Ai e n f n Mt n e n t l P r c. m m r s oo j o h s du i l 4 f o s t ts or AA b drr t i i oP PS r ef s s H f f e S e 1 t t g Hy l a i r . b c. Uf K SD
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%~t -;j f Alst.I' 9.11- Af_Co_rit i ntied 1 bat >lOf OCICJtJJVil10f4ti[ Nil Al. Mot (UO[11NG PitOCHAM Htif411[R Of HEPHESti4TAltVE SAMPLfNG AP80-TYPE AND TREQUfHCY-SAMP1ES AND C_OLMCi f Off FHEQ12Lt g CF ANALY5tS'
[XPOStiftC PAllNAY SAMPI[ I OCAT l ON S( '8 ) _ ylH/(j!! SAMPLC. It . - l engu s t ion - ( Cont i nued ) Gamma i sotopic(5 ) and ' f4onthly when 1-131 ana lysi s. ' food Samples of tierce dit 'erent avaliablu,
.c.
Prodsec t s' kinds 'or broad lear vegetation ir available grown nearest each ( cont inwed ) or two diff erent ofTsito locations or highest predicted annual average ground-Invet 0/Q ir milk sampling is not pe r fo rmed . Morithly when Camma isotopic (5) a ru.f . One sample or eacts or the a va i la b i c, 1-131 analysis. similar broad tear vegetation - g rown 15 to 30 km (10 to 20 saile) distant in the Icast prevaleset wind di rection ir mith samplisig is not performed. -) {
-171-
hYd"44"U1VVJ l- Rev . ,l'M gl A\ 5 TABLE 9.11-A (Continued) TABLE NOTATIONS 41868 (1) Specific parameters of distance and direction aector from the centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in Table 9.11- A in a table and figure ( s) in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic campling equipment, and other legitimate reasons. Il specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section 7.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of chedce at the most desired location or time- :n these instances suitable specific alternative menia and locatione may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Invironmental Monitoring Program given in the CDCM. Pursuant to Technical Specification 6.14, submit as part of, or concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible copy of the entire CDCM including the revised figure ( s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justify ng the - selection of the new location (s) for obtaining samples. I
-172-
OV Y]
)Y, .1 '
5 TABLE 9.11-A (Centinued) f TABLE NCTATICMS (2) One er m0re instruments, such as a pressuriced ion chamber, fcr measuring and recording doce rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent 4 dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosi7eters for measuring direct radiation. The 40 stations is not an absolute number. Thu number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, { scme sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose informat$on with minimal - fading. (3) The purpose of this cample is to obtain background information. If it is not practical i to establish control locatiens in accordance with the distance a.sd wind direction criterie, other sites that provide valid background data may be subs:ituted. (4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of centrol samples, gamma isotepic analysis shall be performed on the individual samples. (5) Gamma isetopic analysis means the identification and quantification of gamma-emitting , radionuclides that may be attributable to the effluents from the facility. (6) The " upstream sample" shall be taken at a distance beycnd significant influence of the discharge. The "devnstream" sample shall be taken in an are.x beyonc but near the mixing :ene.
-173-
Rev, 1'f ) )F g ' V TABLE 9,ll-A (Continued) J BLE_NOTAT!CNS l I (7) In this program composite sample aliquets shall be collected a*. time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. (8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitabic for contamination. (9) The dose shall be calculated for the maximum crgan and age group, using the methodology and parametars in the CDCM. (10) If harvest occurs more than once a year, sampling shall be perfcrmed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. 4
-l~4-
i APA-ZZ-OlOO3 0'*- $y yx f i - f. T Af11.EEid gl POft f 7 NG I C_Yf t S TOfLitADibaOi.lyl TY CgNgfJiftAT f 0NS_JMlNM9?I_4!_A.L 9.PtB . ett roa f inc t tvt t.s 1000 P110tMfGIS l' ARI ICUt All i I Sit til t h (pCifkg, Let) WAf ttt A l f2 DOllNL ( pCi / htj , vet) (pCiff) (pCi/l) Oft GAS [S (pCI/ml) Af4AlYS15 ll- 3 20.000* 30,000 tan-S ea 1,000
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inOO l 0 *>') 30,0W Co-SS 1,00o l 10, WO Ge n - (.O 300 . l Ir-nh-9', aoo** n 3 too 2 0.9 i-33i 60 3.000 1,000 3tl 10 Cs-13:3 _ 70 2,OW 2,000 50 20 c3_13y 300** fla-1 a- lie;l 200** f ar scarf ace water samples, a value T o r d r inki rvy w a te r san *p le s . Ita l s is 80 CfM Pa rt. 18e1 va lue. 1 of 30,000 pCi/E may t>e used.
** Iutal activity, pa ren t plus daughter act e vi ty.
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I a b b & C m * '- =* I 4 5 ( } Om I l I 6 " i e 1 e 8 Z 6 i g : 6 i d ( 'J " E = U N = U U E 8 _ _ _ . . . - - - .-_.___-_._______-__~____!____________
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Rev.J'l l TABLE 9.11-C (Continuedl TAELE NOTATICMS 41369 (1) 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 analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Section 7.1. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Revisien 1, July 1977.
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APA-LE*0 LOU 3 ReV . ) TABLE 9.11-C (Continued) TABLE NOTATICMS (3) The 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, tha*. will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 s b LLD = E
- V + 2.22
- Y
- exp (-kat)
Where: LLD = the "a priori" lower limit of detection (microcuries per unit mass or volume), s = the standard deviation of the background b counting rate or of the ccunting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, 1 = the radioactive decay constant for the
- particular radienuclide (s-9 , and at = the elapsed time between the sample collection, or end of the sample collection period, and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
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APA-CZ-01003 AI Rev.f) )) 1 TABLE 9.11-C (Centinued) TABLE !20TATICt15 It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capability of a measurement system and not as an a_pasteriori (after the fact) limit for a particular meamtrement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Envireraental Operating Report pursuant to Section 7.1. LLD for drinking water samples. For surface (4) water samples, the LLD of gamma isotopic analysis may be used.
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APA-ZZ-01003 A\ Rev.,Y c_ 9.12 RADIOLOGICAL EINIRONMENTAL MCNITORING LAMD USE CENSUS 41870 9.12.1 controls 9.12.1.1 A Land Use Census shall be conducted and shall idcntify within a distance of 8 km (5 miles) the location in each of the 16 muteorological sectors of the nearest milk animal, the nearest residence 8 and the nearest garden
- of greater than 50 m (500 f t ) producing broad leaf vegetation.
8 APPLICALILITY: At all times. ACTIO!4:
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being ce,1culated in Section 9.8.2.1, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Section 7.2.
*Srcad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE SOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 9.ll-A, Part 4.c. shall be followed, including analysis of control samples. I
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APA-ZZ-01003 Rev.fi (L A
- b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose ecmmitment (via the same exposure f pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 9.11.1.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODOM. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after october 31 of the year in which this Land Use Census was conducted. Pursuant to Technical Specificatien 6.14, submit as part of, or concurrent with, the next Sem! annual Radioactive Effluent Release Report a complete and legible copy of the entire COCM, including D the revised figure (s) and table (s) reflecting the new location (s) with information supporting the change in sampling locations.
- c. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41871 9.12.2 Surveillance Recuirements 9.12.2.1 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results c.i the Land Use Census sha*1 be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.
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APA-2Z-01003 Rev. g4 r 3b '[ 9 41872 9.12.3 Bases This section is provided to ensure that changes 9.12.3.1 in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. Information that will provide the best results, such as door-to-door survey, aerial survey, or consulting with local agricultural authorities, shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the cenLus to gardens of greater than 50 m provides assurance that significant 8 exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made (1) 20% of the garden wac used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m . 8
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APA-ZZ-01003 Rev. )\ , g 8 9.13 RADIOLOGICAL __ ENVIRONMENTAL MONITORING
- INTERLABORATORY COMPARISON PROGRAM 41873 9.13.1 Controls 9.13.1.1 Analyses shall be performed on rodioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.
APPLICABILITY: At all times. ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.
- b. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41874 9.13.2 Surveillance Requirements 9.13.2.1 The Interlaboratory Comparison Program shall be
' described in this procedure. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.
9.13.3 Bases 9.13.3.1 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 as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the
- purposes of Section IV.3.2 of Appendix ! to 10 CFR Part 50.
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AFA-EL-U;Uva
'b Rev.??R v
)\',h' o
) 10.0 ADMIMISTRATIVE CCNTROLS 10.1 MAJOR CHAjjCES TO__ LIQUID AND CASECUS RADWASTE TREATMENT SYSTEMS" 10.1.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous),
- a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). The discussion .' each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CER S0.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- 3) A detailed description of the equipment, components and processes involved and the interfr.ces 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 maxinum 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 ccmparison 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;
" Union Electric Co. may choose to submit the information called for in this specification as part of the annual FSAR update.
' -184-
APA-ZZ-01003 A' Rev.,1'} .s
- 7) An estimate of the exposure to plant L
operating personnel as a result of the change; and
- 8) Documeatation of the fact that the change was reviewed and found acceptable by the ORC.
- b. Shall become effective upon review and approval by the ORC an in accordance with Technical Specification 6.5.3.1.
10.2 CRANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)_ 2815 10.2.1 All changes in the CDCM shall be completed pursuant to Technical Specification 6.14.2 and approved as per APA-ZO-00101, Preparation, Review, Approval And Control of Procedures. 2815 10.2.1.1 All changes shall be approved by the CRC PRIOR to implementation. 10.2.2 Cross Disciplinary Review for each revision of the ODCM must include, as a minimum, Health Physics, Quality Assurance, and Radiological Engineering. 2815 10.2.3 A complete and legible copy of each revision of the CDCM that became effective during the last semiannual period shall be submitted as a part of, or concurrent with that periods Semiannual Radioactive Effluent Release Report pursuant to Technical Specification 6.14.2.
~
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P Rev. fiQ e g hv.O
11.0 REFERENCES
- 11.1 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 2r
- U.S. Government Printing Office, Washington, D.C. 204C2.
11.2 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S. Government Printing Office, Washington, D.C. 20402. 11.3 Title 40, " Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S. Government Printing Office, Washington, D.C. 20402. 11.4 U.S. Nuclear Regulatory Commission, " Technical Specifications Callaway Plant, Unit No. 1", NUREG-1058 (Rev. 1), October A984. 11.4.1 Section 6.8.1 (2791) 11.4.2 Section 6.8.4f (41834) 11.5 Communications 11.5.1 Letter NEO-54, D.W. Capone to S.E. Miltenberger, dated January 5, 1983; Union Electric Company correspondence. . 11.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27, 1984. 11.5.3 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Elecetric Co.), dated February 9, 1984. 11.5.4 Letter BLUE 1358, " Comparison of Callaway Plant offsite Dose Calculations for Routine Effluents", J,H. Smith (Bechtel Power Corporation) to D,W. Capone (Union Electric Company), dated March 22, 1984. 11.5.5 Private Ccmmunication, H.C. Lindeman & B.F. Holderness, August 6, 1986 11.5.6 Calculation 22-67, " Annual Average Atmospheric Dispersion Paramecers", April 1969.
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Rev.1} g , 3 ,,i, p I Union Electric Ccr.pany Callaway Plant, Unit 1, 11.6
! Final Safety Analysis Report.
11.6.1 Section 11.5.2.2.3.1 11.6.2 Section 11.5.2.2.3.4 11.6.3 Section 11.5.2.1.2 11.6.4 Section 11.5.2.2.3.2 11.6.5 Section 11.5.2.2.3.3 11.6.6 Section 11.2.3.3.4 11.6.7 Section 11.2.3.4.3 11.6.8 Section 11.5.2.?.3.1 11.6.9 Section 11.5.2.3.3.2 11.6.10 Section 11.5.2.3.2.3 11.6.11 Section 11.5.2.3.2.2 11.6.12 Section 2.3.5
, 11.6.13 Section 2.3.5.2.1.2 11.6.14 Section 9.2.6 11.6.15 Section 9.2.7.2.1 11.6.16 Section 6.3.2.2 11.6.17 Table 11.1-6 11.6.18 Tabl, 9.4-6 11.6.19 Table 9.4-8 11'6.20 Table 9.4-11 11.6.21 Table 9.4-12 11.6.22 Table 2.3-68
-187-s
,,, j
APA-Z2-01003 Rev.JJ 'h .4 % 4
\ 11.7 Unior. Electric Company Callaway Plant Environmental Report, Operating License Stage.
11.7.1 Table 2.1-19 1 ' Section 2.1.2.3 11.7.2 11.7.3 Section 2.1.3.3.4 11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19 11.8 U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Technical Specificatien For Nuclear Power Plants", USNRC NUREG-0133, Washington, D.C. 20555, October 1978, 11.8.1 Pages AA-1 through AA-3 11.8.2 Section 5.3.1.3 11.8.3 Section 4.3 11.8.4 Section 5.3.1.5
)
11.8.5 Section 5.1.1 11.8.6 Section 5.1.2 11.8.7 Section 5.2.1 11.8.8 Section 5.2.1.1 11.8.9 Section 5.3.1 l'.8.10 Section 3.8 11.8.11 Section 3.3 11.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, Program For the Meterological Evaluation of Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington. D.C. 20555, 11.9.1 Pages 19-20 Subroutine PURGE
._ , f
-188-
APA-ZZ-01003 g y'U Rev, f[ i 11.10 Regulatory Guide 1.111, " Methods For Estimating ' Atmospheric Transport And Dispersion of Gaseous Effluents In Rcutine Releases Frcm Light-Water-I Ccoled Reactors", Revision 1, U.S. Muclear 20555, L Regulatory Commissien, Washington, D.C. July, 1977. 11.10.1 Section c.1.b 11.10.2 Figures 7 through 10 11.10.3 Section c.4 11.11 Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases Of Reactor Effluents For the Purpose of Evaluating I", Compliance With 10 CFR Part 50, Appendix Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1977. 11.11.1 Appendix C, Section 3.a 11.11.2 Appendix E, Table E-15 11.11.3 Appendix C, Section 1 11.11.4 Appendix E, Table E-11 11.11.5 Appendix E, Table E-9 11.12 U.S. Nuclear Regulatory Commission, " Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C. 20555, January 1980. 11.12.1 Section I, Page 2 11.12.2 Section IV, Page 8 11.12.3 Section IV, Page 9 11.12.4 Sectian III, Page 6 11.12.5 Section III, Page 8
-189-
APA-ZZ-01003[f,ql Rev.f1'6 6 1 > 3 11.13 Management Agreement for the Public Use of Lands, ' Union Electric Company and the State of Missouri Department of Ccncervation, Decetrer 21, 1982. 11.13.1 Exhibit A 11.14 Miscellaneous References 11.14.1 Drawing Number M-109-0007-06, Revision 5. 11.14.2 Callaway Plant Annual Environmental Operating ( Report (updated annually). I 11.14.3 UE Safety Analysis Calculation 87-001-00. 11.14.4 Calculation Z2-48, " Calculation of inhalation and Ingestion Doce Commitment Factors for the Adult and Child", January, 1988. 11.14.5 HPCI 89-02, " Calculation of ODCM Dose Commitment Factors", March, 1989. 11.14.6 HPCI 87-04, " Calculation of the Liniiting Setpoint for the Containment Purge Exhaust Monitors, GT-RE-22 and GT-RE-33", March, 1987, 11.14.7 HPO! 88-10, " Methodology for Calculating the Response of Gross NaI(Tt) Monitors to Liquid Effluent Streams", June, 1988, 11.14.8 Calculation ZZ-57, "Dese Factors for Eu-154", January, 1989. 11.15 U.S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meterological Evaluati.on of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2929, September, 1982, Washington, D.C. 20555. 11.15.1 Section 4, "Sub:cutine PURGE", pages 27 and 28. 11.16 Regulatory Guide 4.13, " Performance, Testing, and procedural specifications for Thermoluminiscence Dosimetry: Environmental Applications
"(Revision 1), July 1977; USNRC, Washington, D.C. 20555 11.17 !!D-7004, " React r Shielding Design Manual" Rockwell, Theodore, ed; March 1956.
-190-
AFA-ZZ-01003 Rev /' l j A' 11.38 ENWL-236, "ISOSHLD - A computer code for General R.C., Purpose Isotepe Shielding Ant.Iysis", Engel, Greenberg, J., Hendrichten, M.M.; June 1963. Em!L-236, Supplement 1, "lSOSHLD-II: Code 11.19 Revision to include calculation of Dose RateG.L., from Shielded Bremnotrahlung Sources", Simmons, et al; March 1967. 11.20 BNWL-236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD-III", Mansius, C.A.; April 1969. 11.21 ANSI N13.10-1974, " Specification & Performance of on-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents"; September, 1974. 11.22 Nuclear Regulatory Commission Generic Letter 89-01, " Guidance for the Implementation of Programmatic Controls for RETS in the Ad:ninistrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989. . 11.23 ODP-ZZ-00002, ETaipment Status Control.
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