ULNRC-04021, 1998 Annual Radioactive Effluent Release Rept. with
| ML20206E772 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1998 |
| From: | Passwater A UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-04021, ULNRC-4021, NUDOCS 9905050241 | |
| Download: ML20206E772 (67) | |
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DOCKET NO. 50-483 _ . _ , _ ~ ~ _ - - . . . . - - - , _ _ . - - - _ , - _ , . ~ , - CALLAWAY PLANT 1998 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
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Union flictric One Ameren Plaza y 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149
; 314.621.3211 April 27,1999 2
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20556 Gentlemen: ULNRC-04021 MI6 41 DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT FACILITY OPERATING LICENSE NPF-30 1998 ANNUAL RADIOACTIVE EFFLUENT RE' LEASE REPORT Please find enclosed the 1998 Annual Radioactive Efiluent Release Report for the Callaway Plant. This report is submitted in accordance with section 6.9.1.7 of the Technical Specification. .- Sincerely, Alan C. Passwater Manager, Corporate Nuclear Services BFH/ Enclosure
/
.t1 a subsidinty of Amoren Corparation
I i, y l cc: M. H. Fletcher Professional Nuclear Consulting, Inc. I 19041 Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 - Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mel Gray (2) Office ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Bob Hentges Regional Administrator Department ofNaturalResources Central Regional Office P.O. Box 176 Jefferson City, MO 65102 Gerhard K. Samide ANI Account Engineer Town Center, Suite 3005 29 S. Main St. , West Hartford, CT 06107-2445 f
1 l I TABLE OF CONTENTS
1.0 INTRODUCTION
.......................................................................................................................1 - 2.0 SUPPL EM ENTAL INFO RMATION ......................... ................................................................. 2 2.1 REOULATORYIAUTS.. .. ,
. . . . . . . . . .. . . .. . . . .. . .. 2 2.2 MAXIMUM PERMISSIBLE CONCENTRAHONS.. . ... . ... . . . . . . . . . .. .. . .....3 2.3 AVERAGE ENERGY.. .. ... .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....3 2.4 MEASUREMENTS AND APPROXIMAHONS OF TOTAL RADIOACRVirY. .. . . . . ,, . . .. 4 2.5 BATCH RELEASES. .... .. . . . . . . . . . . . . . . .. .. . . . .....4 2.6 ABNORMAL RFIFASES... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 5 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS...................................................... 6 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS .......................................................... 7 5.0SOLIDWASTES...........................................................................................................................8 6.0 REL ATED INFORMATI ON ................... ................................................................................... 9 6.1 UNPLANNED RFIRASES... .. .. . . . . . . . . . .. . . . . .. ... .9 6.2 CHANGES TO Um OFFSirE DOSE CALCULATION MANUAL., , . . . . . . . .. .. 10 6.3 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS . .. . . . . . . .. . .. . . . . . . I 1 6.4 LAND USE CENSUS CHANGES . . . . . . . . . . . ... .. ... .. . . ... .I1 6.5 INOPERABILITY OF EFFLUENT MONrrORING INSTRUMENTATION . .. . . . . . . . . . . . . . 12 6.6 INSTANCES OF LIQUID HOLDUP TANKS OR WASTE GAS DECAY TANKS EXCEEDING TECHNICAL SPECIFICAHON LIMrrS. . . . . . . . . . . . . . . . . . . . . . . . ... 13 7.0 METEO RO L OG I CAL DATA .................................................................................................... 14 8.0 ASS ESSM ENT OF DOS ES........................ ............................................................................... 15 8.1 DOSE AT Tim SrrE BOUNDARY FROM GASEOUS EFFLUENTS., ... . . . ..... ... .15 8.2 DOSE TO DE MEMBER OF THE PUBLIC . .. .. . . . . . . . . . . . . .. .. .. . 15 8.3 TCTAL DOSE DUE TO Um URANIUM FUEL CYCLE . . . . . . . . . ... . .
. , .16 8.4 DOSE DUE TO LIQUID EFFLUENTS . .. ... . . . . . . . . . . .. . . . . . . .. .16 LIST OF TABLES 1A Annual Summation of Gaseous Releases IB Annual Airborne Continuous and Batch Releases ;
2A Annual Summation of Liquid Releases 2B Annual Liquid Continuous and Batch Releases 3 Solid Waste and Irradiated Fuel Shipments 4 Cumulative Joint Frequency Distributions - 5 Dose at the SITE BOUNDARY and Nearest Resident 6 Dose to the Member of the Public from Activities within the SITE BOUNDARY 7 Total Dose Due to the Uranium Fuel Cycle 8 Dose Due to Liquid Effluents ATTACHMENT . Offsite Dose Calculation Manual, Revision 9 I
l.0 INTRODUCTION , This report describes the Union Electric Co. Callaway Plant radioactive effluent releases for 1998. It is submitted in accordance with Section 6.9.1.7 of the Callaway Plant Technical Specifications. A summary of radioactivity released in liquid and gaseous effluents and solid waste shipped from the Callaway Plant during the period from January 1,1998 to December 31,1998 is presented. All liquid and gaseous effluents discharged during this reporting period were in compliance with federal regulations and the limits in the Offsite Dose Calculation Manual (ODCM). r i 1 2.0 SUPPLEMENTAL INFORMATION 2.1 REGULATORY LIMITS i The Radiological Emuent Control (REC) limits applicable to the release of I radioactive material in liquid and gaseous effluents are provided below. FISSION AND ACTIVATION GASES (NOBLE GASES) The dose rate due to radioactive noble gases released in gaseous emuents 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 gaseous emuents, from each unit, to areas at and beyond the site boundary 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: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. ;
RADIOIODINE. TRITIUM, AND PARTICULATES The dose rate due to Iodine-131 and 133, tritium and all radionuclides in particulate form with half-lives greater than eight (8) days released in gaseous emuents 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. I 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 eight (8) days in gaseous i emuents 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.
i i
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LIOUID EFFLUENTS The concentration of radioactive material released in liquid emuents to unrestricted l areas shall be limited to the concentrations specified in Appendix B, Table II, Column I 2 to 10CFR20.001 to 20.601 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/mi total activity. The dose or dose commitment to an Individual from radioactive materials in liquid emuents released to unrestricted areas shall be limited:
- a. During any calendar quarter to less than et qual 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.
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. I 2.2 MAXIMUM PERMISSIBLE CONCENTRATIONS The maximum permissible concentration values specified in Appendix B, Table II, Column 2 to 10CFR20.001 to 20.601 are used to calculate release rates and permissible concentrations ofliquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/mlis used as the limiting concentration for ' dissolved and entrained noble gases in liquid emuents. For gaseous emuents, maximum permissible concentrations are not utilized in release rate calculations since the applicable limits are based on dose rate at the site boundary. The " Percent of Tech Spec Limit" for Table lA is therefore not applicable to the Callaway Plant. 2.3 AVERAGE ENERGY This requirement is not applicable to the Callaway Plant radiological emuent monitoring program since the release rate limits for fission and activation gases in gaseous emuent are not based on the average energy of the radionuclide mixture. i 2.4 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Radionuclide concentrations in liquid and gaseous effluents were obtained by emuent ! sampling and radiological analysis in c& ordance with the requirements of Final Safety Analysis Report Table 16.11-1 and Table 16.11-4 i Gamma s.pectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration ofliquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, Fe-55, and transuranic nuclides 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 techniques, respectively. l The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged. I 2.5 BATCH RELEASES Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this year is presented below. LIOUID UNITS JAN-JUN JUL-DEC Number of batch releases: ---- 114 124 Total time period for batch releases: Minutes 64,282 54,084 Maximum time period for batch releases: Minutes 1,483 2,196 Average time period for batch releases: Minutes 564 517 Minimum time period for batch releases: Minutes 52 102 Average Missouri River flow during 8 periods of effluent release to the rivert: fl /sec 131,385 129,673 I i Letter, S. Ternes, United States Department ofInterior - Geological Survey - Water Resource Division dated March 29,1999. i
1 l l l GASEOUS UNITS JAN-JUN JUL-DEC Number of batch releases: --- 37 45 Total time period for batch releases: Minutes 6435 19043 Maximum time period for batch releases: Minutes 2510 7201 Average time period for batch releases: Minutes 174 423 Minimum time period for batch releases: Minutes 23 41 2.6 ABNORMAL RELEASES LIOUID Number of releases: 1 Total Activity released: Not Letectable l GASEOUS Number ofreleases: 1 Total Activity released: 5.56E-3 curies l l 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS The quantity of radioactive material released in gaseous effluents during the year is summarized in Tables I A and IB. During 1998 all gaseous effluents were considered as ground level releases. 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS l The quantity of radioactive material released in liquid effluents during the year is summanzed in Tables 2A and 2B. During 1998 there was no continuous release of liquid effluent from the plant.
-7 -
i j 5.0 SOLID WASTES , 1 The quantities of radioactive material released in shipments of solid waste for burial l and irradiated fuel transported from the site during the year are summarized in Table
- 3. The total quantity and radioactivity reported in Table 3 for each waste type was for waste buried and includes wastes buried by waste reprocessors aller volume ,
reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped. Those nuclides which comprise at least 1% of the total activity for a particular waste type are presented in Table 3. 3 l 1 i i l 6.0 RELATED INFORMATION 6.1 UNPLANNED RELEASES Unplanned releases are:
- 1) Inadvertent or accidental releases of radioactive material.
- 2) Releases of radioactive material via normal pathways without a release permit, proper authorization, or proper sampling and analysis.
- 3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.
AUXILIARY BOILER CONTAMINATION On April 10,1998, radioactivity was detected in the Auxiliary Boiler feed water system. The plant was performing a refueling outage. The boiler was flushed and cleaned several times in an attempt to decontaminate the unit. Small amounts of contammation still remained in the sludge. During subsequent operation of the boiler small amounts of contamination leached from the sludge and was detected in the boiler water. An investigation was performed to locate the source of the contamination. No miss-positioned valves or leaks were identified. The results of sampling different system j components were inconclusive, but may indicate a small O in the SLWE heat exchanger. During refueling operations the concentration of radioactive nuclides in , the SLWE system can be a factor of 1000 higher then normal operations. The size of the leak may be small enough to only be recognized when high these concentrations
)
are present. Increased monitoring was initiated in an attempt to identify the source of the contamination. No additional contamination was identified. A 10CFR50.59 evaluation concluded that the resulting doses to a Member of the Public from the release ofradioactive material to the environment would be a small fraction of the regulatory dose limits. Therefore, continued operation of the Auxiliary Boiler would not pose any significant safety or environmental concern. The Auxiliary Boiler was operated intermittently during the remainder of 1998. The maximum total body dose to a Member of the Public from these releases was 2.8E-04 mrem during 1998. This is negligible compared to the quarterly and annual effluent controllimits. The activity released from the Auxiliary Boiler during 1998 is included in Table I A, IB, 5, 6 and 7. A description of this event is documented in the plant Corrective Action Program l i S O S 98-1032, 98-2981, 98-3172, 98-3456, 98-3457, 98-3458, 93-3764, 98-3979 l i
a 1 i LEAK IN PLANT DISCHARGE LINE On February 19,1998, a sink hole was identified near Manhole #11 on the plant discharge pipe. It was determined that a leak of 10 - 20 gpm was coming from the l plant discharge pipe. The leak offran through the Storm Water Runoffinto Logan I Creek. l After excavation, a crack on the top and side of the discharge pipe was identified. ' The break may have been caused by negative pressure exerted in this location created when flow is decreased. To prevent future problems, a twenty foot section of the J
. damaged fiberglass pipe was replaced with carbon steel pipe. In addition, a combination vacuum breaker and air release valve was installed to prevent cyclic pressures on the discharge line.
j i The leakage to the environment from the discharge line only occurred when flow was j above 5500 gpm. The amount of time in this condition, along with the dilution of the 1 liquid effluent and the estimated leak rate from the pipe of 10 - 20 gpm, makes the I concentration of radionuclides released to the environment negligible. Surface water, sediment and soil samples were collected in the area of the leak. The 4 analytical results indicated no detectable radioactivity. Therefore there was no radiological effect of the leak on the environment. A description of this event is documented in the plants Corrective Action Program 1 6.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL Revision 9 to the ODCM was approved by ORC for issue on 3/20/1998. The
- following changes were included in this revision:
1
- Revised projected liquid and gas dose calculation to use previous 31 day 1 cumulative doses. i
- Added GL-RE-202, Laundry Decon Facility Dryer Exhaust Monitor. I e Added action to be taken when a effluent particulate and/or iodine grab sampler is not operable.
- Added setpoint calculation for GL-RE-202. l e Removed the word secular from secular equilibrium in section 3.5.
- Added Laundry Decon Facility Dryer Exhaust to Table 6.2.
A complete copy of Revision 9 to the ODCM is attached to this report as required by Section 6.14.c of the Callaway Plant Technical Specifications. I SOS 98-0258 6.3 ' MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS A Laundry Decontamination Facility was added to the plant during 1998. This work was performed under MP 97-1006. The modification was reviewed and approved by the Onsite Review Committee (ORC). (ORC meeting 1539) The Formal Safety Evaluation concluded there were no unreviewed safety questions. All liquid radioactive waste generated will be processed through the same systems used in the past. All systems required to support this facility were already located in the building and served no safety-related function. The new monitored release point for the dryer exhaust was evaluated in the Final Environmental Evaluation. This modification posed no environmental concerns and no unreviewed safety questions exist. The ALARA review concluded that this change dose not increase the potential radiation exposures beyond the exposures that already exist. l The Final Environmental Evaluation concluded that no significant adverse f enviroranental impact would result from the laundry facility. The modification will not affect concentrations, frequencies or types of efHuents being discharged from the ! plant. A particulate radiation monitor with the capability to secure dryer efBuent discharges was installed. No unreviewed environmental questions exist. { j Several piping changes were made to the Laundry and Hot Shower Tank (THB06) and Laurr ;q Water Storage Tank (THB10). This involved installation of new bag filters doustream of the laundy washers and replacement of the Laundrj and Hot Shower Fil er (FHB07) with a bag filter. The bag filters are designed to filter particulate prior to the waste water being sent to the Discharge Monitor Tanks for , final sampling and release. I The laundry dryers are equipped with a self contained HVAC system. The exhaust is passed through a pre-filter to remove lint and then through a HEPA filter to remove particulate. 1 6,4 LAND USE CENSUS CHANGES Changes identified in this years Land Use Census required a modification to the l Highest Annual Average Atmospheric Dispersion Parameters for the Nearest Resident. The nearest resident used to calculate dose is now 0.1 miles closer to the plant. I i I
r 1 6.5 INOPERABILITY OF EFFLUENT MONITORING INSTRUMENTATION During 1998 all effluent monitoring instrumentation was OPERABLE within the limits specified in FSAR Chapters 16.11.1.3 and 16.11.2.4 with the following exceptions. DMT DISCHARGE WITH EFFLUENT MONITOR ISOLATED Discharge of DMT "A" was initiated with effluent monitor HB-RE-18 valved out. The discharge lasted for 6 minutes (800 gallons) before being terminated. Appropriate sampling and analysis was performed prior to discharge including backup 1 samples and analysis. A valid permit was active and the discharged water was within ) all regulatory requirements.
)
l The cause of this event was the discharge monitor had been tagged out for maintenance and was not returned to service before initiating the discharge. No checks or valve lineups on the monitor were procedurally required until after initiation j of the release. Training and procedure revisions were among the corrective actions j taken to prevent a reoccurrence of this event. A description of this event is documented in the plant Corrective Action Programt. l UNIT VENT PARTICULATE AND IODINE SAMPLING NOT ISOKINETIC i On 2-16-98 a plant load center went out of service causing loss of flow to several ventilation units. This caused Unit Vent effluent flow to go below the isokinetic j sample range for the operable particulate and iodine monitor (GT-RE-21 A). The i effluent monitor capable of sampling under these conditions (GT-RE-21B) was out of service due to a low heat trace alarm. This condition lasted for 8 hours and 40 minutes. J Particulate and iodine samples before and after the event indicated no release of these radionuclides through the Unit Vent. These particles are normally removed by the installed filtration units. During the event a containment purge was performed for I hour and 31 minutes. This is a batch discharge and was sampled prior to release. Since the Unit Vent particulate and iodine samples were not valid, the batch sample analysis was used to determine the amount of particulate and iodine activity released during this period. t
' A description of this event is documented in tie plant Corrective Action Program 2, ~ t SOS 98-0318 3 SOS 98 0213
Fo UNIT VENT PARTICULATE AND IODINE SAMPLING HEAT TRACING NOT OPERABLE - On 10/5/1998, the Unit Vent particulate and iodine effluent monitor (GT-RE-21B) was placed out of service due to a low heat trace temperature. The backup monitor (GT-RE-21 A) was out of service for repair. This condition existed for 12 hours and 30 minutes. Auxiliary sampling equipment was used to obtain particulate and iodine samples during this period. These samples were not valid because Unit Vent flow was outside of the equipment's isokinetic sampling range and the sample line was not properly ) heated because of maintenance being performed. l An evaluation concluded no particulates or iodines were discharged during this period j based on the following: 1
+ Valid samples before and after the event indicated no activity.
+ Grab samples taken on the Condenser Air Removal System and Main Steam Enclosure indicated no activity.
+' No containment releases were performed.
+ No particulates or iodines were identified on the auxiliary sample obtained during the event. This sample is not conservative but supports the above findings.
A description of this event is documented in the plants Corrective Action Programl. i 6.6 INSTANCES OF LIQUID HOLDUP TANKS OR WASTE GAS DECAY TANKS EXCEEDING TECHNICAL SPECIFICATION LIMITS All liquid tanks and waste gas decay tanks were within limits specified in FSAR Chapters 16.11.1 and 16.11.2 during the reporting period. , , 1 SOS 98-3547 ~ i 7.0 METEOROLOGICAL DATA The on-site meteorological data for this reporting period is presented in Table 4. The data is presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 meter tower elevations. Valid data recovery for 1998 was greater than 90% for all required parameters. 1 1 l l l i
8.0. ASSESSMENT OF DOSES Assessment of doses to the maximum exposed individual from gaseens and liquid emuents released was performed in accordance with Administrative Procedure APA-ZZ-01003 as described in the following sections. For all emuents released from the Callaway Plant during this year, the annual dose to the maximum exposed individual was less than 1% of the Radiological Emuent Control Limits presented in Section 2.1 of this report. 8.1 DOSE AT THE SITE BOUNDARY FROM GASEOUS EFFLUENTS The dose at the Site Boundary was due to plume exposure from noble gases, ground plane exposure, and inhalation. It was conservatively assumed that a hypothetical maximum exposed individual was present at the Site Boundary location with the most limiting atmospheric dispersion (based on actual meteorological conditions for the year). Dose was conservatively calculated using a child as the critical age group. The dose from gaseous emuents at the Site Boundary for 1998 is presented in Table 5. 8.2 DOSE TO THE MEMBER OF THE PUBLIC The Member of the Public was considered to be a real individual, not occupationally associated with the plant, who uses portions of the plant site for recreational or other purposes not associated with plant operation. This individual's utilization of areas both inside and outside the Site Boundary was characterized for this calculation. To evaluate total dose from the Uranium Fuel Cycle to any Member of the Public, the critical Member of the Public within the Site Boundary, and the Nearest Resident were each evaluated. DOSE AT THE NEAREST RESIDENT FROM GASEOUS EFFLUENT The dose to the Nearest Resident was due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion. Dose was calculated at the nearest actual residence with the most limiting atmospheric dispersion (based on actual meteorological conditions for the year). It was conservatively assumed that each ingestion pathway (meat, milk, and vegetation) existed at this location. Dose was conservatively calculated assuming the child as the critical age group. Dose from activities within the Site Boundary was negligible and not included in this calculation. The doses to the Nearest Resident for 1998 are presented in Table 5. DOSE To THE MEMBER OF THE PUBLic FROM ACTIVITIES WITHIN THE SITE BOUNDARY Based on the land use within the Site Boundary, the Member of the Public with the highest dose was a farmer. Dose fiom farming activities within the Site Boundary was due to direct radiation exposure, plume exposure from noble gases, ground plane exposure, and inhalation. The current tenant estimates spending 1100 hours per year working within the Site Boundary area. Dose was calculated using the adult farmer as the critical age group. Dose to the Member of the Public from activities within the Site Boundary is presented in Table 6. 8.3 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE Since there are no other Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the total dose to the most likely exposed Member of the Public resulted from direct radiation exposure and radioactive effluents from the Callaway Plant itself. The total dose to the Member of the Public (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. It was conservatively assumed that each food ingestion pathway exists at his residence and that the adult is the critical age group. The total dose from the Uranium Fuel Cycle is presented in Table 7. 8.4 DOSE DUE TO LIQUID EFFLUENTS Dose due to liquid effluents assumed contributions from the maximum exposed individual's consumption of fish and recreational activities. An adult was considered to be the maximum exposed individual in this assessment. 1 It is conservatively assumed the hypothetical maximum exposed individual obtained i his entire annual fish intake from near the plant discharge. Total dose due to liquid effluents from Callaway Plant during the year is presented in Table 8. TABLElA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS l AND 2,1998 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 6.67E +01 1.57E+02 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 8.57E+00 2.00E+01
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.28E-06 8.60E 04 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.65E 07 1.09E-04
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 1.59E-06 1.7 I E-03 30
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.(M E-07 2.I8E-04
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.62E-07 1.99E-09 D. TRITIUM
- 1. TOTAL RELEASE CURIES ! .93E+01 3.87E+01 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.49E+00 4.92E+00
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A (a) Safety Analysis Calculation 87 063-00. January 6.1988 Page 1 of 2 A
TABLElA SEMIANNUAL SUMMATION OF GASEOUS RELEASES i ALL AIRBORNE EFFLUENTS l QUARTERS 3 AND 4,1998 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 3.43E+00 7.6 iE+00 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 4.3 t E-O f 9.58E-01
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/.A B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 0.00E+00 2.01E-07 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 0.00E+00 2.53E-08
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS) f CURIES 2.04E-05 1.01 E-04 30
- 2. AVERAGE RELEASE RATE FOR PERIOD f uCi/SEC 2.57E-06 1.27E-05
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 D. TRITIUM
- l. TOTAL RELEASE CURIES 3.43E+0! 4. I 7E+01 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 4.32E+00 5.24E+00
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A (a) Safety Analysis Calculation 87-063-00, January 6,1988 Page 2 of 2
TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS l AND 2,1998 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.98 E-02 3.89E-02 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.77E-08 1.l5E-07
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM
!. TOTAL RELEASE CURIES 6.71E+02 1.68E+02 14
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.38E-04 4.98E-04
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.38E-02 3.6 t E-03 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.12E-08 1.07E-08 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 5.3 l E+06 4.98E+06 10 F. VOLUME OF DILUTION WATER USED GAL l .84E+08 8.44E+07 10 (a) Safety Analysis Calculation 87-063-00 January 6,1988 f
, Page 1 of 2 n
7 -. i i TABLE 2A I SEMIANNUAL SUMMATION OF LIQUID RELEASES l ALL LIQUID EFFLUENTS 1 l QUARTERS 3 AND 4,1998 i THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA] CURIES 1.03E-02 1.60E-02 20
- 2. AVERAGE DILUTtiD CONCENTRATION DURING PERIOD uCi/ML 3.13E-08 2.56E-08
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM
- l. TOTAL RELEASE CURIES 6.31 E+01 4.92E+02 14
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.91 E-04 7.86E-04
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES '
- l. TOTAL RELEASE CURIES 2.50E-04 2.43E-04 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.57E-10 3.88E-10 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 5.92E+06 5.27E+06 10 l F. VOLUME OF DILUTION WATER USED GAL 8.14 E+07 1.60E+08 10 (a) Safety Analysis Calculation 87-063-00. January 6,1988 Page 2 of 2
o l TABLEIB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES I QUARTERS I AND 2,1998 l CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER t, FISSION GASES AR-41 CURIES 0.00E+00 0.00E400 4.48E-02 1.42E-01 XE-133 CURIES 6.24E+01 1.44 E+02 1.72E-01 5.48E-01 XE-135 CURIES { 7.93 E-O L l.90E+00 3.00E-03 8.2SE-03 , KR-85 CURIES 0.00E+00 0.00E+00 2.68E+00 3.13 E+00 1' XE-13iM CURIES 0.00E+00 6.50E+00 I,13E 02 4.29E-02 XE 133M CURIES 5.29E-01 1.22E+00 5.40E-CM 1.25E-02 KR 85M CURIES 0.00E+00 2.65E-02 2.19E-04 0.00E+00 KR-88 CURIES 0.00E+00 0.00E+00 2.28E-04 0.00E+00 XE135M CURIES 0.00 +00 3.21 E-02 0.00E+00 0.00E+00 i i XE-138 CURIES 0.00E+00 1.12E-01 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 6.38E+01 1.54E+02 2.9 ) E+00 3.89E+00
- 2. IODINES I 131 CURIES 1.28E-06 3.01 E-05 0.00E+00 8.30E-04 I-132 CURIES l .82 E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 3.10E-06 3.0 l E-05 0.00E+00 8.30E-04 j l
l
- 3. PARTICULATES '
CO-60 CURIES 1.59E-06 0.00E+00 0.00E+00 1.17E-03 CS-134 CURIES 0.00E+00 0.00E+00 0.00E+00 1.8 l E-04 CS-136 CURIES 0.00E+00 0.00E+00 0.00E+00 4.76E-05 CS-137 CURIES 0.00E+00 0.00E+00 0.00E+00 2.3 t E 04 MN 54 CURIES 0.00E+00 0.00E+00 0.00E+00 8.17E-05 ALPHA CURIES 3.62E-07 1.99E-09 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 1.95E-06 1.99E-09 0.00E+00 1.71 E-03
- 4. TRITIUM -
H3 CURIES 1.89E+01 3.75E+0 i 4.63E-01 1.17E+00
.Page.1 of 2
TABLEIB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4,1998 CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I. FISSION GASES AR-41 CURIES 8.5 l E-01 2.67E+00 6.48E-01 7.17E-01 XE 133 CURIES 9.13E-01 2.57E+00 2.27E 01 1.74E 01 XE-135 CURIES 8.28E-02 4.77E 01 1.80E-02 9.63 E-03 KR-85 CURIES 0.00E+00 0.00E+00 6.85E-Ol 1.10E-01 XE-131M CURIES 0.00E+00 0.00E+00 2.17E-04 1.75E-03 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 1.10E 05 KR-85M CURIES 0.00E+00 2.llE-02 0.00E+00 0.00E+00 KR-88 CURIES 0.00E+00 7.49E-01 1.38E-03 0.00E+00 XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 1.12E-05 XE 138 CURIES 0.00E+00 1.0$E-01 0.00E+00 1.51 E-04 TOTAL FOR PERIOD CURIES 1.85E+00 6.60E+00 1.58E+00 1.0lE+00 2.10 DINES I-131 CURIES 0.00E+00 4.86E-08 0.00E+00 1.52E-07 I-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 0.00E+00 2.40E-11 TOTAL FOR PERIOD CURIES 0.00E+00 4.86E-08 0.00E+00 1.52E-07
- 3. PARTICULATES CO-60 CURIES 0.00E+00 0.00E+00 0.00E+00 8.89E-07 CS-134 CURIES 0.00E+00 0.00E+00 8.70E-06 3.62E-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 1.17E-05 6.41 E-05 MN-54 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 0.00E+00 2.04E-05 1.01 E-04
- l. TRITIUM I
H-3 CURIES 2.30E+0 ! 3.74E+01 1.13E+0! 4.27E+00 Page 2 of 2
7: TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS l AND 2,1998 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I. ALL NUCLIDES B E-7 CURIES 0.00E+00 0.00E+00 2.32E-05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 : ' %A) 2.27E-02 CO-60 CURIES 0.00E+00 0.00E+00 6 .i' 03 5.85E-03 H-3 CURIES 0.00E+00 0.00E+00 6.7 i U +02 1.68E+02 MN 54 CURIES 0.00E+00 0.00E+00 2.58E-03 1.22E-03 SB-125 CURIES 0.00E+00 0.00E+00 4.90E-03 4.64E-03 XE-133 CURIES 0.00E+00 0.00E+00 4.32E 02 3.52E-03 TC-99M . CURIES 0.00E+00 0.00E+00 1.94E-05 1.83E-04 I 131 CURIES 0.00E+00 0.00E+00 2,77E-03 4.06E-04 CO-57 CURIES 0.00E+00 0.00E+00 4.03E-05 5.68E-05 CS-137 CURIES 0.00E+00 0.00E+00 4.07E-04 6.74E-04 CE-141 CURIES 0.00E+00 0.00E+00 2.59E-06 0.00E+00 XE 131M CURIES 0.00E+00 0.00E+00 3.48E-04 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 3.87E-05 6.83E-04 XE-135 CURIES 0.00E+00 0.00E+00 3.83E-05 0.00E+00 1133 CURIES 0.00E+00 0.00E+00 8.76E-05 0.00E+00 CS 134 CURIES 0.00E+00 0.00E+00 8.20E-05 2.49E-04 CR-51 CURIES 0.00E+00 0.00E+00 1.18E-04 1.46E-03 ZR-95 CURIES 0.00E+00 0.00E+00 7.60E-05 4.53E-04 XE-133M CURIES 0.00E+00 0.00E+00 1.53E-04 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 0.00E+00 5.89E-06 ZR-97 CURIES 0.00E+00 0.00E+00 0.00E+00 1.38E 05 MO-99 CURIES 0.00E+00 0.00E+00 0.00E+00 7.01 E-05 SB 124 CURIES 0.00E+00 0.00E+00 0.00E+00 1.66E-04 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 3.57E-05 HF-181 CURIES 0.00E+00 0.00E+00 0.00E+00 3.02E-06 SN-il 3 CURIES 0.00E+00 0.00E+00 0.00E+00 2.57E-06 XE 137 CURIES 0.00E+00 0.00E+00 0.00E+00 8.96E-05 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 2.98E-06 TOTALS FOR PERIOD CURIES ' O.00E+00 0.00E+00 6.7 I E+02 1.68E+02 Page 1 of 2
t TABLE 2B i SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3 AND 4,1998 CONTINUOUS RELEASES B ATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER j
- 1. ALL NUCLIDES BE-7 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 5.62E-03 4.llE-03 CO-60 CURIES 0.00E+00 0.00E+00 1.3 l E-03 2.95E-03 H3 CURIES 0.00E+00 0.00E+00 6.31 E+01 4.92 E+02 1
MN-54 CURIES 0.00E+00 0.00E+00 4.8 l E-04 5.55E-04 SB 125 CURIES 0.00E+00 0.00E+00 1.53E-03 6.44E-03 XE-133 CURIES 0.00E+00 0.00E+00 3.88E-05 2.29E-04 TC-99M CURIES 0.00E+00 0.00E+00 1.77E-06 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 0.00E+00 1.09E-06 CO-57 CURIES 0.00E+00 0.00E+00 2.12E-06 2.63E 05 CS 137 CURIES 0.00E+00 0.00E+00 5.04E-04 1.25E-03 CE-141 CURIES 0.00E+00 0.00E+00 0.00E+00 3.32E-06 XE-131M CURIES 0.00E+00 0.00E+00 2.12E-04 0.00E4 00 NB-95 CURIES 0.00E+00 0.00E+00 3.85E-04 1.95E-04 XE-135 CURIES 0.00E+00 0.00E+00 0.00E+00 8.30E-07 1-133 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS 134 CURIES 0.00E+00 0.00E+00 1.54E-04 3.76E-04 CR-51 CURIES 0.00E+00 0.00E+00 5.80E-05 0.00E+00 ZR 95 CURIES 0.00E+00 0.00E+00 2.19E-04 7.52E-05 XG133M CURIES 0.00E+00 0.00E+00 0.00E+00 1.37E-05 NA-24 CURIES 0.00E+03 0.00E+00 0.00E+00 0.00E+00 2R-97 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MO-99 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 7.38 E-06 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HF-181 CURIES 0.00E+00 0.00E+00 2.82E-06 0.00E+00 SN-113 CURIES 0.00E+00 0.00E+00 3 58E-06 0.00E+00 XE 137 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 RU-106 CURIES 0.00E+00 0.00E+00 5.27E-05 2.67E-05 BA-139 CURIES 0.00E+00 0.00E+00 1.07E-05 0.00E+00 RUIO3 CURIES 0.00E+00 0.00E+00 0.00E+00 6.5lE-06 B A-140 CURIES 0.00E+00 0.00E+00 0.00E+00 7.58E-% TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 6.3 l E+01 4.92E+02 Page 2 of 2 \ ' L :
TABLE 3 SOLID WASTE & IRRADIATED FUEL SHIPMENTS 1998 A. SOLID WASTE BURIED (Does not include irradiated fuel)
- 1. TYPE OF WASTE PERIOD PERIOD EST. TOTAL UNITS JAN - JUN JUL - DEC ERROR (%)
L a. Spent resins, filter sludges m2 3.98 evaporator bottoms, etc. Ci 4.74E+01 25 %
- b. Dry compressible waste, m' 4.25 6.86 contaminated couipment, etc. Ci 4.1E-01 6.0E-01 *25%
- c. Irradiated components, m$
control rods, etc. Ci
- d. Other m2 Ci
- 2. Estimate of major nuclide composition (By type of waste)
PERIOD PERIOD JAN-JUN JUL-DEC Percent- Percent Nuclide Abundance Curies Abundance Curies
- a. Fe-55 32.64 % 1.54E+04 Co-58 22.04 % l .04E+04 Co-60 12.59 % 5.94E+03 H-3 10.11 % 4.77E+03 Ni-63 7.48 % 3.53E+03 Cr-51 4.47 % 2.l l E+03 Nb-95 2.97 % 1.40E+03 Zr-95 2.86 % 1.35E+03 Mn-54 2.59 % 1.22E+03
- b. Co-58 36.60 % 1.49E-01 36.60 % 2.19E-01 E Fe 55 35.53 % 1.45E-01 35.53 % 2.12E-01 Co-60 5.71 % 2.32E-02 5.71 % 3.41 E-02 Nb-95 5.45 % 2.22E-02 5.45 % 3.26E-02 Ni-63 5.38% 2.19E-02 5.38% 3.21 E-02 Mn-54 4.87 % 1.98E-02 4.87% 2.9] E-02 Zr-95 2.87 % 1.17E-02 2.87 % 1.71 E-02 Cr-51 1.82 % 7.41E-03 1.82 % 1.09E-02 Page1of2
( , TABLE 3
'1 SOLID WASTE & IRRADIATED FUEL SHIPMENTS l l 1998 l
- 2. Esti nate of major nuclide composition (By type of waste) l l PERIOD PERIOD
! JAN - JUN JUL - DEC Percent Percent i Nuclide Abundance Curies Abundance Curies
- c. - None l
l l d. None l l l l
- 3. Solid waste disposition l Number of Mode of Class of Solid Type of Shipments . Transportation Destination Waste Shipped Container 1* Cask GTS-Duratek A LSA 1* Cask GTS-Duratek A LSA 1 Cask Barnwell C LSA 6* Truck F. W. Hake A LSA
~2* Truck GTS-Duratek A LSA 3* Truck Allied Technologies A LSA Group l
1* Truck Molten Metals A LSA Technology- TN
., *Sent to waste processors for volume reduction before burial.
- 4. Solidification agent None used.
B., IRRADIATED FUEL SHIPMENTS (Disposition) l Number of - Mode of ! _ Shipments Transportation Destination l
- None Page 2 of 2 t . :- ._ _ _
l TABLE 4 METEOROLOGICAL DATA AVERAGES USING HOURLY AVERAGED DATA 1998
% GOOD UNITS VALUES DATA l Stability Class A-G E 99 % l Total Precipitation CM. 2.77E+02 99 % i 10 Meter Level: . Wind Speed Meter /Sec 3.64E+00 100 %
Wind Direction Degrees 1.85E+02 98 % Wind Direction Variability Degrees 1.31E+01 98 % Reference Temperature Degrees C 1.38E+01 99 % Dewpoint Degrees C 7.34E+00 99 % 60 Meter Level: Wind Speed Meter /Sec 5.58E+00 97 % Wind Direction Degrees 1.89E+02 96 % Wind Direction Variability Degrees 8.57E+00 98 % Dewpoint Degrees C NONE 0% Temperature Difference 60 - 10 Degrees C 2.16E-01 99 % l l I Page 1 of 15
TABLE 4-METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 l
. Stability Class:.A i Wind Speed at 10.00 Meter Level (MPH) -
3 4-7 8-12 13 18 19-24 >24 TOTAL N 0 1-' 1 0 0 0 2 NNE l- 0- 0 0 0 0 .1 NE 0- - 1. 0 0- -0 0 1 ENE O O- 0 0 0 0 0 E O 2- 0 0 0 0 2 ESE O 3 1 0 0 0 4 SE O 4 0 1 0 0 5 SSE- 0 8 2 -1 0 0 11 S -0, 7 2 0 0 0 9 SSM7 0 11 8 0 0 0 19 SVV - 0 6 1 0 0 0 7 WSW 0 0 0 0 0 0 0 W -0 1 3' 0 0 0 4 WNW 0 1 0 0 0 5 NW- 0- 0 4 1 0 0 5 NNW .2' 2 0 0 0 0 -4 TOT 3 50 23 3' 0 0 79
~
. Hours of Calm Data: 1'
; Hours ofInvalid Data: 0
'~ ^
Page 2 of-15 L _
p
' TABLE 4-METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION l:
l-- 1998 l
, - Stability Class: B'
_ Wind Speed at 10.00 Meter Level (MPH) . 1-3 4 8-12. 13-18 19-24 >24~ ' TOTAL' N -0 2 2 0 0 0 4 NNE 2 2 '3 -0 0 0 7 NE 0 2 1 0 .0 0- 3 ENE- 1 1-' 1 0 0 0 3-E- 0 _4 2- 0 0 0 6 ESE 0. 5 1 'O O O 6 SE- 1 10 8 0 - 0 0 19 SSE O 14 10 2 2 1 29 i S- 0' 21' 13 3 0 0 37 SSW 0' 20 18 0 1 0 39 SVV 2 9 .12 1 0 0 24 WSW 0 6- 3 1 0 0 10 W -- -0 1 7 1 0' 0 9 WNW 'l. 6 3- 0 '0 0 10 L' NW L0 4 6 0 0 0 10 NNW 0 2~ 1 1 0 0 4 TOT' 7- 109- 91 9 3 1 220 , Hours of Calm Data: 0 Hours ofInvalid Data: 7 i Page 3 of 15
TABLE 4 METEOROLOGICAL DATA 3 TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 Stabili.ty Class: C-Wind Speed at 10.00 Meter Level (MPH) - 1-3 '4-7 8 .13-18 .19-24 >24 TOTAL N~ 0 -- 9 '6 0 0 0 15 NNE 1 6,' 4 0 d- 0 11 NE- 0' 4. -1 1 0 0 6 ENE 2 6 3 2 :0. 0 13 E 0- .3 1 0 0 0 4 ESE I 10 7 0 0 0 18 SE '- 2 :18 12 0 - 0 0 32-SSE :3. 20 18 1 0 1 43 S 1: 18 18 4 1 1 43 SSW l' 23 14 0 3 0 41 SW: .1 21 10 3 -0 0 35 , WSW l 8 8 1 0 0 18 W: 1 4 .2- 0 0 0 17 WNW l~ 16 - 5 0 0 0 22 NW- 1- 19 8 1 0 0 29 NNW 3- 13 9 2' 0 0 27 TOT ^ 19 198 136 15 4 2 374 Hours of Calm Data: 0
' Hours ofInvalid Data:- 8
(-
..x.
Page h.of 15 g- ._,
TABLE'4 METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998
. Stability Class: . D .
Wind Speed at 10.00 Meter Level (MPH)
- 1-3 4-7 . 8-12 13-18 19-24 >24 TOTAL N 14 82 86 3 0 0 185 NNE 18 .71 -47 2 0 0 138 NE 24 51 36 8 0 0 119 ENE 10 56 46' 14 6 0 132 E 9 51 47- 1 1 0 109 ESE 11 65 40 11 0 0 127-SE 17 74 44 9 1 0 145 SSE 17 63 43 16 9 1 149 S 13 71 61 .46 3 1 195 SSTV 17- 96 51 20 1 0 185 SW 7 64 54 13 6 0 144 WSW 16 46 57 11 13 2 145 W. '20 83 54' 19 0' 0 176 WNW ' 16 - 68 48, 7 0 0 139 NW- 15 85 58 16- 0 0 174 NNW 21 74 87 14 0 1 197 TOT- 245 1100 859 210 41 4 2459
- Hours of Calm Data: -3 ' Hours ofInvalid Data: 34 Page 5.of 15
]
l TABLE 4 METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 Stability Class: E Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 16 79 110 50 9 0 264 NNE 18 77 50 10 0 0 155 NE 29 90 74 9 0 0 202 ENE 16 74 78 27 6 0 201 E 18 71 58 10 4 0 161 ESE 20 74 106 17 0 0 217 SE 29 87 113 25 ' 0 0 254 SSE 16 86 131 51 10 0 294 S 24 83 189 93 6 0 395 SSW 15 81 79 22 3 0 200 SVV 17 57 48 19 5 0 146 WSW 23 51 55 23 5 0 157 W 16 68 77 21 3 0 185-
'W 17 77 86 24 0 0 204 NVV 27 80 80 40 9 0 236 NNW 16 69 106 44 4 0 239 TOT 317 1204 1440 485 64 0 3510 Hours of Calm Data: 25 Hours ofInvalid Data: 25 i
f Page 6 of 15 e a
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TABLE 4 METEOROLOOICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 l l Stability Class: F Wind Speed at 10.00 Meter Level (MPH) 1 4-7 8-12 13-18 19-24 >24 TOTAL N 12 39 22 1 0 0 74 NNE 13 33 13 0 0 0 59 NE 16 35 7 0 0 0 58 l ENE 12 31 10 0 0 0 53 E 5 45 13 0 0 0 63 ESE 4 49 23 0 0 0 76 SE 9 85 93 4 0 0 191 SSE 14 82 110 3 0 0 209 S 11 63 89 7 0 0 170 SSM/ 7 41- 22 0 2 0 72 SW 11 36 13 0 0 0 60 WSW 8 21 10 0 0 0 39 W 6 31 17 0 0 0 54 WNW 13 45 17 3 0 0 78 NW 8 44 26 3 3 0 84 NNW 16 48 19 6 0 0 89 TOT 165 728 504 27 5 0 1429 i Hours of Calm Data: 19 ! Hours ofInvalid Data: 38 4' Page 7 of 15
TABLE 4 METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 j 1 Stability Class: G
. Wind Speed at 10.00 Meter Level (MPH) l 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 ' 18 6 0 0 0 36 NNE 7 11 0 .0 0 0 18 NE 2 12 4 0 0 0 18 ENE 1 4 3 0 0 0 8 E 2 4 1 0 0 0 7 ESE 3 6 1 0 0 0 10 SE 8 28 17 0 -
0 0 53 SSE 4 55 25 0 0 0 84 S 9 29 7 0 0 0 45 SSNV- 7 26 7 0 0 0 40 SW 7 15 2 0 0 0 24 WSW 2 4 0 0 0 0 6-W 0 4 5 0 0 0 9 WNW 12 23 1 0 0 0 36 NW 7- 13 9 0 0 0 29 NNW 5 .26 3 0 0 0 34 TOT 88 278 91 'O O O 457 Hours of Calm Data: 10 Hours ofInvalid Data: 11 Hours of Good Data: 8586 = 98.0% of Total Hours l L
~Page 8 of.15
TABLE 4 METEOROLOGICAL DATA
- TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 Stability Class: A Wind Speed at 60.00 Meter Level (MPH) 1-3 4 8-12 13-18 19-24 >24 TOTAL-N 0 0 1 0 0 0 1 NNE O 1 0 0 0 0 1 NE O O 0- 0 0 0 0 1
ENE 0- 2 0 0 0 0 2 E O 1 0 0 0 0 1 ESE O 2 3 0 0 0 5 SE 0 2 1 0 0 0 3 SSE O -4 7 1 0 1 13 l 1 S~ 0 4 5 1 0 0 10 { SSVV 0 7 9 3 0 0 19 SM/ 0 2 4 0 0 0 6 WSW 0 0 0 0 0 0 0 W 0 2 0 3 0 0 5 WNW 0 2 2 0 0 0 4 NW 0 0 1 4 0 0 5 NNW 0 1 0 0 0 0 1 TOT 0 30 33 12 1 0 76 Fours of Calm Data: 0 ' Hours ofInvalid Data: 4 Page 9 of 15 .
u l TABLE 4 - METEOROLOGICAL DATA ITOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 Stability Clas~ s : B Wind Speed at - 60.00 Meter Level (MPH)
.1 3 4-7~ 8-12 13-18 19-24 ' >24 TOTAL N- 0 1 3 0 0 0 4 NNE .0-1 4- Og 0 0 5-NT -0 1- '3.
0 0 0 4 ENE 1 1. 1 0 0 0 3 E -0 2- 2 0 0 0 4 ESE: 0 4 5 0 0 0 9 SE 0- 7 13 1 - 0 0 21 SSE .O. 12 5 5 0 2 24 S .0 12 23' 3 3 2 43 SSW - 0 '5- 23 8 -1 1 38 SW l 8 6 10 0 0 25 WSW 0- 4 3 2 1 0 10 W- 'O 2 0 7 .1 0 10 WNW 0 3 6. 2 0 0 11 NW' 1 2- 5 2- 0 0 10 = NNW 0 3 1 0 'O- 0 4 TOT- 3 68 103 40 6- 5 225
' Hours of Calm Data:-~- 0 Hours ofInvalid Data: 2 Page 10 of.15
i TABLE 4 ' METEOROLOGICAL DATA
- TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 Stability Class: C
'. Wind Speed at 60.00 Meter Level (MPH) 1-3 4 8-12 13-18 19-24 >24 TOTAL N- 0 '8 7' 1 0 0 16 NNE 1 5 9- 0 0- 0 15 NE 0 5 0 2 0 0 7 ENE -0 3 : 4- 3 0 0 10 E- 0 3 1 0 0 0 4 ESE' 1 5 10 0 0 0 16 SE O 13 18 2 0 0 33 SSE O- 17 15 8 1 1- 42 S 0 17 17 11 3 2 50-SSVV 1 8 21 5 0 3- 38' SVV 0 14 14 9 1 0 38 WSW 0 2 9 5 0 0 16 W. 1 3 9 7 0 0 20 WNW 0 7 15 4- 0 0 26 NW 'O 7 14 3 1- :0 25 NNW l 9 8 3 0 0 21 TOT 5 126 171- 63 6 6 377 .
- Hours of Calm Data: 0 Hours of Invalid Data: 5 Page 11 6f 15
TABLE 4 METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 l Stability Class: D Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7. 8-12. 13-18 19-24 >24 TOTAL N- -8 42 106 25 2 0 183 NNE 11 62 63 '16 0-- 0 152 NE 6 ' 48 31 8 5 0. 98 ENE 4 25 56 34 .9 4 132 E 4 29 58 18 0 0 109 ESE 5- 37 50 31 1 0 124 SE 8 50 63 27 2 1 151 l SSE 14 37 44 25 9 10 139 S 7 39 66 48 ?,7 10 207 SSW 6 41 81 51 13 7- 199 SW 7 32- 55 33 11 9 147 WSW - 8 :- 18' 43 47 6 19 141 W '
'6 41: 61 41 18 2 169 WNW 8 35 64 39 4 0 150 NW, 6 42 60 '42 13 '3 166 NNW l1- 50 70. 42 2 1- 176 TOT 119 628 971- 527 132 66 2443 Hours of Calm Data: 'O
, Hours ofInvalid Data: 53 Page 12 of 15
. TABLE 4 METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998
' Stability Class: E
. Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19 24 >24 TOTAL'- ;
i N 6 15 88 94 30 7 240 l NNE 4 28 70. 60 7 1 170 NE 6 25 92 48 2 0 173 ENE 6 - 28 ' 101' 75 22 5 237 E 4 26 72 51 5 5 163-ESE O 20 87 105 12 0 224- i l SE 2 28 62 124 14 1 231 SSE 6 -241 63 120 53 9 275 S. 4 23 72 188 83 11 381 SSNV 1 17 78 114 35 7 252 SW 4- 15 60 42 24 12 157 WSW 6 23 47 27 26 11 140 W- 4 14 66"' 79 21 3 187 WNW 4 15 92 79 18 1 209 NW ~4- 18 ' 77 81 19 18 217 3 NNW 2 18 70 86 18 2 196 l TOT 63. 337 1197 1373 389 93 3452 ,
-- Hours of Calm Data: 5 Hours ofInvalid Data: 103 Page 13 of 15 ,
l.
TABLE 4 - METEOROLOGICAL DATA TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998 ) Stability Class: F. Wind Speed at 60.00 Meter Level (MPH) l 3 4-7 8-12 13-18 ~ 19-24 >24 TOTAL N 1 6 28 30 3 0 68 NNE 0' 6 21 33 0 0 60 NE 'O 9 32 14 0 0 55 ENE 0. 11 29 26 0 0 66 E 1 6 31 26 0 0 64 ESE' 0 13 43 48 0 0 104 SE 3 3 36 82 , 2 0 126 SSE O 10 47- 108 9 0 174 S 1 9 62 98 '. 2 0 182 SSW '6 .39 89 10 2 146 STV. 0 7 23 40 3 0 73- ) WS'il ' O 4 17 -22 3 0 46 W 0 5 13 20 5 0 43 WNW 0 -3 30- 27 4 1 65 NW 0- 3 29- 23- 0 6 61 NNW 0 6 28 38 4 0 76-
'l TOT 6 107' 508' 724 55 9 1409 Hours of Calm Data: 0 Hours ofInvalid Data: 77 Page 14 of 15
r; TABLES DOSE AT THE SITE BOUNDARY AND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS l SITE BOUNDARY NEAREST RESIDENT LOCATION: 1.40 km SSE LOCATION: 1.93 km WSW AGE GROUP: CHILD ' AGE GROUP: CHILD . ORGAN UNITS DOSE % LIMIT (a) DOSE I
% LIMIT (b) .
- 1. GAMMA AIR DOSE
- MRAD + 3.50E-03 0.03 1.95E-03 N/A
- 2. BETA AIR DOSE
- MRAD 6.64E-03 0.03 3.70E-03 N/A
- 3. WHOLE BODY *" MREM ' 7.5 i E-03 N/A 4.18E-03 N/A
- 4. SKIN "* MREM 1.07E-02 N/A' 5.96E-03 N/A
- 5. BONE " MREM 4.41E-03 .N/A 8.52E-03 0.06
- 6. LIVER " MREM 7.64E-03 N/A 2.56E-02 0.17
- 7. TOTAL BODY " MREM 7.63E-03 - N/A 1.99E-02 0.13
- 8. THYROID " MREM 7.93E-03 N/A 8.93E-02 0.60
- 9. KIDNEY " MREM 7.63 E-03 N/A. 2.10E-02 0.14
- 10. LUNG " MREM 7.81E-03 N/A 1.93E-02 0.13 l 1 GI-LLI " MREM 7.63 E-03 N/A 1.87E-02 0.12 i
- Dose from Noble Gases only
" Dose from Tritium, Radiciodines, and Particulates only
*" Dose from Noble Gases plus Ground Plane dose (a) Annual dose limits of Offsite Dose Calculation Manual (APA ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose.
. (b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of.15 mrem to any organ from I.131,1-133. H-3 and particulate radionuclides with haltlives greater than 8 days.
i
~Page 1 of 1
TABLE 4 METEOROLOGICAL DATA
. TOTAL HOURS AT EACH WIND SPEED & DIRECTION 1998
' Stability Class: O
' Wind Speed at 60.00 Meter Level (MPH)
' l 4-7 8-12 13-18 19-24 ->24 TOTAL N- 1 2 10 4 0 0 17 .
NNE 1 2 14 10 0 0 27 NE 0- 5 17 2 0 0 24 ENE O 3 6 9 0 0 18
~
E O 5 8 5 0 0 18 ESE O 2 6 8 0 0 16 SE O l- 8 7 - 0 0 16 SSE 0 2 17 27 0 0 46 S 0 3 35 31 0 0 69 SSVV 0- 2 14 17 2 0 35 SNV O 3 17 23 0 0 43 WSW 0 4 8 8 0 0 20 W 0 0- 5 1 2 0 8 WNW 0 3- 9 12 0 0 24 NW 0- 2 6 8 0 0 16 NNW 0 1 -- 9- 8 0 0 18 TOT. 2 40 ' 189 180 4 0 415 Hours of Calm Data: O s Hours ofInvalid Data: 63
- Hours of Good Data: 8402 = 95.9% of Total Hours l
Page 15 of 15 l
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W TABLE 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY EFFLUENT DIRECT DIRECT TOTAL DOSE WITHIN RADIATION PADIATION DOSE THE SITE FROM THE FROM OUTSIDE FOR THE ORGAN- UNITS BOUNDARY UNIT TANKS . YEAR I. SKIN ~ MREM 2.13E-03 N/A N/A 2.13E-03
- 2. BONE MREM l.24E-03 8.79E 8.22E-03 1.83E-02
- 3. LIVER MREM 2.53E 8.79E-03 8.22E-03 1.95E-02
- 4. TOTAL BODY MREM 3.57E-03 8.79E 8.22E-03 2.06E-02 .
- 5. THYROID - MREM 2.60E-03 8.79E-03 8.22E-03 1.96E-02
- 6. KIDNEY MREM 2.52E-03 8.79E 8.22E-03 1.95E-02
- 7. LUNG MREM 2.58E-03 8.79E-03 8.22E-03 1.96E-02
- 8. GI-LLI MREM 2.53E-03 8.79E-03 8.22E-03 1.95E-02 i
e l l 1 Page 1 of 1
TABLE 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OF THE PUBLIC) DOSE FROM TOTAL DOSE DOSE ATTHE ACTIVITIES TO THE RESIDENCE WITHIN SITE MEMBER OF ORGAN .. UNITS LOCATION BOUNDARY THE PUBLIC % LIMITS *
- 1. SKIN MREM l.73E-03 2.13E-03 3.86E-03 0.02
- 2. BONE MREM 1.76E-03 1.83E-02 2.00E-02 0.08 '
- 3. LIVER . MREM ? 6.74E-03 1.95E-02 2.63E-02 0. l !
- 4. TOTAL BODY MREM 7.29E-03 2.06E-02 2.79E-02 0.11
- 5. THYROID MREM l.66E-02 1.96E-02 3.62E 02 0.05 '
- 6. KIDNEY MREM 6.01E-03 ~ 1.95E-02 2.55E-02 0.10
- 7. LUNG MREM 5.74E 03 1.96E-02 2.53E-02 0.10
- 8. GI-LLI MREM 5.82E-03 1.95E-02 2.54E-02 0.10
- Annual dose limits from 40CFRl90.10(a) cf 25 mrem whole body. 75 mrem to the thyroid, and 25 mrem to any other organ.
Page 1 of 1-1
- l. . . . .
l ATTACHMENT ONE 1 APA-ZZ-01003 OFFSITE DOSE CALCULATION MAMUAL REVISION 9 k ' APA-ZZ-01003, Rev 9, is not attached to the bec distribution copies. If you wish to review this revision, please contact the Callaway Plant Document Control Department. It can also be viewed on the LAN at: ! Z:/ Procedures - l l 1 I I
n i l l 1
- TABLE 8 l
DOSE DUE TO LIQUID EFFLUENTS l (MEMBER OF THE PUBLIC) 1 i 1998 OROAN UNITS DOSE LIMIT * % LIMIT i
- 1. BONE MREM 1.59E 02 10.00 1.59E-01
- 2. LIVER MREM 2.89E .10.00 2.89E-01
- 3. T'OTAL BODY'. MREM 2.14E :3.00 7.14E-01
- 4. TH YROID MREM- 6.38E-03 10.00 6.38E-02
- 5. KIDNEY MREM 1.21 E-02 10.00 1.21 E-01
- 6. LUNG MREM 6.50E-03 10.00 6.50E-02
- 7. GI LLI MREM 3.00E-02 10.00 3.00E-01 l
1 J
- Annual dose limits of APA-ZZ-010^'. Section 9.4.1.1.
l I l
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1 Page l'of 1
APA-ZZ-01003 Rev 9 bNION Ettcraic s CALLAWAY PLANT OFF-SITE DOSE CALCULATION M.ANUAL MARCH 6,1998
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APA-ZZ-01003 Revision 9 March 6,1998 t CALLAWAY PLANT i ADMINISTRATIVE PROCEDURE APA-ZZ-01003 , OFF-SITE DOSE CALCULATION MANUAL-RESPONSIBLE DEPARTMENT. HEALTH PHYSICS - I PROCEDURE OWNER - ,b. h(abaM
. WRITTEN BY
-a s l . 1/. CC ('id cA. A.3
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(J PREPARED BY ( . Y. n,) d ( ('/ Q a, d
,, , (J APPROVED BY 7[ //h5[
cfesNT isenpo MAR 201998-
/
DATE ISSUED 3 -9t> - AccOus<^ste HOLDER l%U ' This procedure contains the follor ing: Pages I through ' 63 Attachments - through Tables through Figures through Appendices ' through CheckofrLists through This procedure has checkofflist(s) maintained in the mainframe computer.
- Conversion of commitments to TRS reference / hidden text completed by Revision Number:
ITS Commitments ' Non T/S Commitments v O i:_
APA-ZZ-01003 3 Rev. 9 TABLE OF CONTENTS Section Pace Number 1.0 PURPOSE AND SCOPE.... ... ... . . . .. . . . . . . . . . . . . . . . . . .. ! 2.0 LIQUID EFFLUENTS... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..2 2.1 LIQUID EFFLUENT MONITORS ... . .. . ... . .. . . .. .. .. .. ........2 2.2 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS... ..3 2.3 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS.... .. . . . 5 2.4 DOSE DUE TO LIQUID EFFLUENTS., .. . ... .. . . .. . . . . . . . . . . =5 2.4.1 Tile MAXIMUM EXPOSED INDIVIDUAL.. .... ... .... . ............5 2.4.2 CALCULATION OF DOSE FROM LIQUID EFFLUENTS.... .. .. .. 6 2.4.3
SUMMARY
, CALCULATION OF DOSE DUE TO LIQUID EF F LU ENTS... ... ... .. . . .. . . .. . .. .. .. . . , . ...7 2.5 LIQUID RADWASTE TREATMENT SYSTEM. ... . . . . . . .7 I 2.6 DOSE FACTORS .. . .. . . . . ... . . . . . . ..7 3.0 GASEOUS EFFLUENTS., . . . . . . . . . . . ...........12 3.1 GASEOUS EFFLUENT MONITORS...... .. . . . . . . . . . . . . . . . . . . . . .12 3.2 GASEOUS EFFLUENT MONITOR SETPOINTS.. . . . . . . . ... . 13 3.2.1 TOTAL BODY DOSE RATE SETPOINT CALCULATIONS., . . .... . .14 3.2.2 SKIN DOSE RATE SETPOINT CALCULATION . .. ... . . .. . . . . . .. 1 5 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS.. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. 15 3.3.1.1 NOBLE GASES.. .. . . . . . . . . . . . .. .. . . . . ...............15 3.3.1.2 RADIONUCLlDES OTliER TliAN NOBLE GASES . .. . . . . . .16 3.3.2 DOSE DUE TO GASEOUS EFFLUENTS. . . . . . . . . . . . . . . . . . .17
)
4 3.3.2.1 NOBLE GASES... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. I 7 ; l 3.3.2.2 RADIONUCLIDES OT11ER TilAN NOBLE GASES ... . .. ..18 3.4 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . . . . .19 3.5 DOSE FACTORS .... . . . . . . . . . . . . . . . . . . . . . . .19 4.0 - DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 43 4.1 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES.. . . . . . . . . . .. . . . . . . . .43 4.1.1 IDENTIFICATION OF TiiE MEMBER OF TiiE PUBLIC.. . . . . . . . 43 4.1.2 TOTAL DOSE TO Tile NEAREST RESIDENT.. .. . . . . ...43 4.1.3 TOTAL DOSE TO T11E CRITICAL RECEPTOR WITlilN Tile SITE BOUNDARY . .. . .. .. . . . . . . . . . . . . . . . . . . . . . . . .44
.i.
APA-ZZ-01003 Rev. 9 TABLE OF CONTENTS Section Pace Number 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ..... ...........47
5.1 DESCRIPTION
OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ... . . .. . ... . ... . . . . .. . .. .. ..............47 ) 5.2 PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS... . ... .. .. . .. ... . . . .. ... . 47 6.0 -DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS.. . .. .. . . .... . .. .47 6.1 ATMOSPHERIC DISPERSION PARAMETERS .... . .... ... ... .. .. ..47 6.1.1 L.ONG-TERM DIS PERSION ESTIM ATES .. .. ...... . ... . .. . . ........ ........... 47 6.1.2 DETERMINATION OF LONG-TERM DISPERSION ESTIMATES FOR SPECIAL RECEPTOR LOCATlONS. . . . . . . . .. . . .. . . . . . . . . 4 8 6.1.3 SHORT-TERM DISPERSION ESTIMATES... . . . . . ... . ... ..48 6.2 ANNUAL METEOROLOGICAL DATA PROCESSING.. . .. .. . . .. . . 49 7.0 REPORTING REQUIREMENTS.. . . . . . . . . . . . . . . . . . . . . . . . . .. . 5 6 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (CTSN 2804).... . .. ...... .... . . . . .............................56 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (CTSN 2 8 05) .. ... ....... .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ...................56 8.0 IMPLEMENTATION OF ODCM METHODOLOGY (CTSN 2791).. . . . 57 9.0 RADIOACTIVE EFFLUENT CONTROLS (REC)......... .. . . . . . . .. . ... 5 8 10.0 ADMINISTRATIVE CONTROLS.. . . . . ... . . . . . . . . .. .. .. 5 9 10.1 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMETN SYSTEMS.. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . ... 59 10.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL' (ODCM) (CTSN 2815) ... . . .. . .. . .. .. .... ....... . . . . . . . . . . . . . . . . .59
11.0 REFERENCES
.. . .. . . . . . . . . . . . . . . . . . . . . . . .. . .. . . .. . . . . . . 6 0 FIGURES FIGURE 4.1.. . . . . . . 44
-ii-
APA-ZZ-01003 Rev. 9 TABLE OF CONTENTS I 1 Section Pace Number TABLES TABLE 2.1 ... ... ...... .... .. . . ..... ........ . ... .... 8 TABLE 2.2 .... .. ... .......... . ..... . . . .. I I TABLE 3.1 ~.. . . .. .. .._........ ... . . . . . . . . .. ....... I 9 TA B LE 3.2 .. . .. ..... . . .. . .. . - . . . . . . . . .. .. .. 2 0 TABLE 3.3 - 1NHALATION PATHWAY.. .. . ... . . . . . .22 TABLE 3.3 - MEAT PATHWAY.. . .. .. . . . . . . ....... . 24 l l TABLE 3.3 - GRASS-COW. MILK PATilWAY . ..... . . . . . . . . . . . . . . 26 l TABLE 3.3 - GRASS-GOAT-MILK PATHWAY. . . . - . . . . ....... . ... .~. 2 8 TABLE 3.3 - VEG ETATION PATHWAY .... ... .. . .... . . . . . . . . . . . . . . . . .. 30 TABLE 3.4 - 1N H A LATION PATilWAY . .... .... ...... ... - .. . ... ..... . 32 TABLE 3.4 - MEAT PATHWAY .. . . .... . . . . . . . . . - - . .... ..... . 34 TABLE 3.4 - GRASS-COW-MILK PATilWAY .. . . . . . . . . . . . . . . ... . 3 6 TABLE 3.4 - GRASS-GOAT-MILK PATilWAY... .. . . . . . . . . . . . . . . . . . . 38 TABLE 3.4 - VEGETATION PATilWAY. . . . . . .. 40 TA BLE 6.1 ...... .... ... . .. . . . . . . . . . . . . . . - - .. 49 TA B L E 6.2 . ....... ..-...... .... . ... . . . . . . . . - .............................50 TA BLE 6.3. . .. ... . .-.. . . . . . . . . . . . . - . . . . . . . . . . . . . . . . . . 5i TABLE 6.4. ...-... .. . . ............. . ... . .......................52 TA B LE 6.5. . . ..... . . . . . . . . . . . . - . . . . . . . . . . . . . . . . . ... .. 54 111-
U i l APA-ZZ-01003 I Rev. 9 RECORD OF REVISIONS
)
l l Rev. No. O Date: March 1983 l I Rev. No. I Date: November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments. l Rey, No. 2 Dete: March,1984 l Revised to incorporate NRC Staff comments Rey, No. 3 Date: June,1985 Revised to incorporate errata identified by ULNRC-803 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census.
. Rev. No. 4 Date: February,1987 Minor clarifications, incorporated 31-day projected dos: methodology. Change in the utilization of areas within the Site Boundary.
Rev. No. 5 Date: January,1988
. Minor clarifications, revised descriptions ofliquid and gasceus rad monitors, revised liquid setpoint F
methodology to incorporate monitor background, revised dose calculations for 40CFR190 requirements, Revised Table 6 and Figures 5.l A and 5.lB to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables I,2,4 and 5 to add additional nuclides, deleted redundant material from Chapter 6. Rey, No. 6 Date: May,1989 Revised methodology for calculating maximum permissible liquid effluent discharge rates and liquid emuent discharge rates and liquid emuent 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 and gaseous dose conversion factors and bioaccumulation factors (Tables 1,2,4 & 5), provided description of the use of the setpoint required by Technical Specification 1.9.4.2 during Core Alterations, added discussion of gaseous and 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 and accompanying description per FSAR Change Notice 88-42. APA ZZ-01003 Rey, No. 0 Date: August,1989 Radiological Emuent Technical Specifications were moved from the Callaway Plant Technical Specifications to Section 9.0, Radioactive Emuent Controls, of the ODCM as per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire ODCM, it was convened to APA-ZZ-01003, OFF-SITE DOSE CALCULATION MANUAL. Rev. No. I Date: October,1990 Revise Action 41 of Table 9.2-A to allow continued purging for 24 hours as per Amendment 20 to operating license, issued 4/10/87. Rev.No. 2 Date: May,1991 Section 14.2 - Changed gross alpha analysis frequency from "each batch" to a monthly composite as per Table 9.3-A, and the Callaway Plant NPDES permit (reissued March 15,1991).
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APA-ZZ-01003 Rev. 9 RECORD OF REVISIONS Rev. No. 3 Date: June,1993
' Deleted HF-RE-45 and LE-RE-59 as effluent monitors. Revised table numbering for consistency with those in Section 9.0, dele'ed redundant material, incorporated 1992 Land Use Census results, moved LLD description to
- Attachment I, moved REC Bases to Attachment 2. Deleted reporting requirements for solid radwaste, which are described in APA-ZZ-010ll, PROCESS CONTROL PROGRAM. Addressed compliance with 10 CFR 20.1301.
Revised the dilution flow rate to allow values other than 5000 gpm, based on dilution flow monitor setpoint. Revised "MPC" terminology to "ECV". Added Action 46 to REC 9.2 to clarify actlins for inoperable mid and high range WRGM Channels. Revised references to be consistent with the revised 10 CFR 20. Added Appendix A. Revised
- Action 41 of Rec 9.2 and the operability requirements of GT RE-22/33. Incorporated the revised Ri values in Tables 3.2 and 3.3. Added Section 6.2 and Table f.5.
Rev. No. 4 Date: September,1994 Increased the minimum channels OPERABLE requirement of REC 9.2 for GT-RE-22 & 23 from I channel to 2 channels. Revised Action 41 and the Bases for REC 9.2 accordingly. Incorporated the operability requirements from Tech Spec 3.9.9 into the Action statement for clarity. (Refer to SOS 941176). Rev. No. 5 Date: February,1995 Removed the REMP station locations. Removed particulate nuclides with a half-life ofless than 8 days from Tables 3.2 .~ .4 and removed C", P", Ni, Te 25", and from Tables 2.1,2.2,3.2,3.3, and 3.4. Changed the reporting frequency of the Semiannual Effluent Release Repert from semiannual to annual. Removed the meat, milk and vegetable pathway dispersion parameters from Tables 6.1,6.2, and 6.3, and clarified the applicability of the dispersion parameters and dose locations in Table 6.4. Relocated REC 9.1 and 9.2 to the FSAR. Revised footnotes 3 and 7 of Table 16.11-4 to require additional sampling of the Unit Vent in the event of a reactor power transient, only if the Unit Vent noble gas activity increases by a factor of 3 or greater. Added Section 4.1.3.1.3 for determination of dose due to the on-site storage of low level radioactive waste. Rev. No. 6 Date September,1996 Section 2: 22 2 Added dose factors (AJfor Ag"'", Np ', Pu23s, Pu '*'", Pu', Am'd', Cm242, and Cm:3v2 to Table 2.1, and Bioaccumulation Factors (Bf,) for Ag, Pu, Am, and Cm to Table 2.2 due to a change in the liquid radwaste treatment process. Revised the description of the methodology for performing the 31 day dose projection in Sectica 2.5. Revised the maximum allowable background for HB-RE-18. Section 3: Ellrainated Y"" and Tc"" from Table 3.4 (Meat Pathway) due to a half-life of < 8 days. Substituted the
- phrase " nore restrictive" in lieu of" lesser" in Section 3.2. Revised the definition of F, in equation 3.1. Added description of use of samples to verify dose rates in Section 3.3.1.2. Augmented the definition of q, in Section 3.3.2.1. Edited equations 3.13 and 3.14 and added equation 3.15 to clarify dose calculations. Revised the methodology for performing the 31 day dose projection in Section 3.4.
Section 4: Strengthened the discussion of the reevaluation of assumptions in Section 4.1.3. Section 6: Added new table 6.6 to describe the selection and use of dispersion parameters during the preparation of the Annual Effluent Release Report. Updated Tables 6.1 and 6.2 to reference the 1995 Land Use Census. There were no changes in the receptor locations. Section 8: Replaced the reference to HDP ZZ-04500 to a more generic reference to the plant operating procedures, due to change in organizational structure and responsibilities.
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c, APA-ZZ-01003 Rev. 9 RECORD OF REVISIONS Section 9: (1) Eliminated 9.0.1 and 9.0.2 due to redundancy with Technical Specifications 3.0.1 and 3.0.2; (2) Revised Table 9.3-A to incorporate sampling and analysis requirements for TRU nuclides in liquid emuents; (3) Eliminated sampling of Fuel Building Exhaust from Table 16.11-4 and the associated footnotes due to redundancy with Unit Vent sampling; revised the continuous sampling requirements for the gaseous batch release points consistent with plant design; revised the H' analysis frequency for Purges from weekly to " prior to each purge"; and, (4) Revised the air sampling station location criteria on Table 9.11-A and footnote # I, and climinated footnote #3 in order to be less generic and more descriptive of the parameters used in determining the station locations (see SOS j 95-2280). Revised the location requirements for milk and vegetables. Revised description of use of baseline samples '
. to trigger gamma isotopic analysis in footnote #4, revised requirement for location of downstream sample station in footnote #6. Revised Surveillance Requirement 9.10.2.1 to eliminate liquid emuents from the surveillance. (5)
Revised REC 9.5 and REC 9.9 to eliminate exceptions for partially tested effluents being released in excess of the 3 respective limit. - ! I Section 11s Added reference 11.14.13. j Attachment 2.; Revised the Bases for REC 9.10 to support the elimination ofliquid effluents from Surveillance 9.10.2.1i The remaining changes are editorial in nature and have no technical impact.
- (This revision implements SOS's 95-2055,96-0167,96-0961,95-2280, and 96-0986).-
Rev. No. 7 Date February,1997 Section 9: (1) REC 9.5," Liquid Radwaste Treatment System", Action statement: Eliminated reference to CTSN 1161;(2) Teble 9.11-A, items 4a (milk) and 4c (vegetation): revised to required control stations in the least prevalent wind direction. (se, SOS 97-166)
' Anoendix A: revised the discussion relative to the appropriate gross alpha Emuent Concentration Value.
Rev. No. 8 Date May,1997 Section I: The Purpose and Scope was revised to describe the split of the ODCM into two sections per FSAR Change Notice 95-058. Section 2: Sections 2.2 and 2.3 were revised to clarify the use of nuclide specific alpha activity vice' gross alpha activity for setpoint determination. Section 2.5 was revised to delete the description of the Liquid Radwaste Treatment System. Section 6: Tables 6.1,6.2, and 6.3 were revised to reflect the results of the 1996
- Annual Land Use Census. Section 7: The reporting requirements for the Annual Radiological Environmental Operating Report and the Annual Emuent Release Report were relocated to the FSAR per FSAR Change Notice 95 058. Section 9: REC's and the supporting Attachments I and 2 were relocated to the FSAR per FSAR Change Notice l
' 95-058. Anoendix A: Appendix A was deleted. Editorial changes were made throughout the ODCM reflecting the I relocation of the REC's to the FSAR.
Rev. No. 9 Date March,1998 Section 2.5: Revised projected liquid dose calculation to use previous 31 day cumulative doses. Section 3.1.1: Added GL-RE-202, Laundry Decon Facility Dryer Exhaust Monitor. Added action to be taken u hen
' the particulate and/or iodine grab sampler is not operable. Section 3.2: Added setpoint calculation for GL-RE-202.
Section 3.2.1 and 3.3.2.2: Changes were made to correct typographical errors and have no technical impact. Section l$ Revised projected gas dose calculation to use previous 31 day cumulative doses. Section 3.5: Removed the word secular from " secular equilibrium" since the equilibrium mode could be secular or transient depending on the isotope. Table 6.2: Added Laundry Decon Facility Dryer Exhaust to title of table since these will be the dispersion factors used for this release point.
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i
f? l c: l L I-APA-ZZ-01003 Rev. 9 i OFF-SITE DOSE CALCULATION MANUAL
- 1. PURPOSE AND SCOPE
- The OFF-SITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the l calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the l ' Radiological Environmental Monitoring Program. The ODCM also contains the Radioactive Effluent 1 l Controls and Radiological Environmental Monitoring Program required by Technical Specification 6.8.4, and descriptions of the information that should be included in the Annual Radiological Environmental l Operating and Annual Radioactive Efiluent Release Reports required by Technical Specifications 6.9.1.6 and 6.9.1.7.
Compliance with the Radiological Elliuent Controls limits demonstrates compliance with the limits of l 10 CFR 20.1301. (Ref. I 1.1.1, i 1.2.1,11.23.3) l The ODCM consists of two parts: FSAR Section 16.1I which contains the Radiological Effluent Controls I l (REC's), and APA-ZZ-01003, which contains the methodology and parameters used to implement the REC's. , i \
\
l i i l l { l l L l l L
7 APA-ZZ-01003 Rev. 9
- 2. LIQUID EFFLUENTS -
l' 2.1 - Liquid Emuent Monitors l ' Gross radioactivity monitors which provide for automatic termination ofliquid emuent releases are j- present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines l and the discharge line (cooling tower blowdown), Setpoints, precautions, and limitations applicable to the
- operation of the Callaway Plant liquid effluent monitors are provided in the appropriate Plant Procedures.
L Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding the Emuent Concentration Values (ECV) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA. The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equation: cf sC F+f Where: C = The liquid efiluent concentration value (ECV) implementing REC 16.1 I,l.1 for the site in ( Ci/ml). j c = The setpoint, in (pCi/ml), of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely related to 4 the volumetric flow of the effluent line and directly related to the volumetric flow of the dilution stream plus the emuent steam, represents a value, which, if exceeded, would result in concentrations exceeding the values of 10 CFR Part 20 Appendix B, Table II, Column 2, in the UNRESTRICTED AREA.
~
f = The flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below. F = The dilution water flow rate setpoint as measured prior to the release point, in volume per unit time. {lf(F)is large compared to (f), then F + f a F), i
- (Ref.11.8.1)
If no dilution is provided, then c $ C. The radioactive liquid waste stream is diluted by 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 line. The limiting concentration which corresponds to the liquid radwaste emuent monitor setpoint is to be calculated using methodology from the expression above.
~
Thus, the expression for determining the setpoint of the liquid radwaste emuent line monitor becomes: c$ C(F + f) (pCi / ml) (2.2) f The alarm / trip setpoint calculations are based on the minimum dilution flow rate (corresponding to the dilution flow rate setpoint), the maximum emuent stream flow rate, and the actual isotopic analysis. Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway. The determination and usage of the allocation factor is discussed in Section 2.2. In the event the alarm / trip setpoint is reached, an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis to ensure that REC 16.11.1.1 limits were not L exceeded.: i
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l APA-ZZ-01003 Rev. 9 2.1.1 Continuous Liould Effluent Monitors The radiation detection monitor associated with continuous liquid emuent releases is (Ref. I 1.6.1,11.6.2): , Monitor I.D. Description BM-RE-52 Steam Generator Blowdown Discharge Monitor The Steam Generator Blowdown discharge is 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 analysis performed are as per FSAR Table 16.11 1.
'2.1.2 Radioactive Liauid Batch Release Emuent Monitors The radiation monitor which is associated with the liquid emuent batch release system is (Ref. I 1.6.4): j Monitor i D. DescriDtion HB-RE 18 Liquid Radwaste Discharge Monitor )
This emuent stream is normally considered to be radioactive. The sampling frequency, minimum analysis i f.equency, and the type of analysis performed are as per FSAR Table 16.11-1. 2.2 CALCULATION OF LIOUID EFFLUENT MONITOR SETPOINTS The dependence of the setpoint (c), on the radionuclide distribution, yields, calibration, and monitor parameters, requires that several variables be considered in setpoint calculations. (Ref.11.8.1) 2.2.1 Calculation of the ECV Sum j The isotopic concentration of the release (s) being considered must be determined. This is obtained from the l analyses required per Table 16.11 1, and is used to calculate an ECV sum (ECVSUM): I i ECVSUM = [(C,)/(ECV,)) l 1 = g, a , s , t, f (2.3)
.Where:
Cg = the concentration of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample. C,* = 2 2 2 2 the concentration of Np ", Pu ", Pu 'w2* Pu , Am24i, Cm242, & Cm24va** in the quarterly composite sample. C*= s the measured concentrations of Sr 89 and St-90 as determined by analysis of the quarterly composite sample. Ct = the measured concentration ofil-3 in the waste sample. Cr* = the measured concentration of Fe-55 as determined by analysis of the quarterly composite sample. ECVg, ECV 3, ECV , ECVr, ECV =t are the limiting concentrations of the appropriate radionuclides from 10 CFR 20, Appendix B, Table 11, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2x104 pCi/ml total activity. For the case ECVSUM si, the monitor tank emuent concentration meets the limits of REC 16.11.1.1 without dilution and the emuent may be released at any desired flow rate. If ECVSUM > 1 then dilution is required to ensure compliance with the concentration limits REC 16.ll.l.l. lf simultaneous releases are occurring or are anticipated, an allocation fraction, N, must be applied so that available dilution flow may
- be apportioned among simultaneous discharge pathways. The value of N may be any value between 0 and I for a particular discharge point, provided that the sum of the allocation fractions for all discharge points must be $1.
- Values for these concentrations are based on previous composite sample analyses as required by FSAR Table 16.11-1.
3-
p APA-ZZ-01003 Rev. 9 2.2.2 L Calculation of the Maximum Permissible Liould Efnuent Discharne Flowrate The maximum permissible liquid emuent discharge dowrate is calculated by: fmaxs;(F + fp)(SF)(N)+(ECVSUM) (2.4)
- Where:
fmax = maximum permissible liquid emuent discharge flowrate,(in gallons / minute);
=
.pf the expected undiluted liquid emuent flowrate, in gpm.
N.
~
=
the allocation fraction which apportions dilution now among simultaneous discharge L pathways (see discussion above) SF = the safety factor; an administrative factor used to compensate for statistical fluctuations and errors of measurements. This factor also provides a margin of safety in the calculation of the ; maximum liquid emuent discharge flowrate (fmax). The value of SF should be < l. F & ECVSUM, are previously defined. l The dilution water supply is furnished with a flow monitor which isolates the liquid efnuent discharge if l the dilution flow rate falls below its setpoint value. l In the event that fmax is less than fp, then the value of fmax is substituted into the equation for fp, and a new value of fmax is calculated. This substitution is performed for three iterations in order to calculate the . correct value of fmax-l 2.2.3 Calculation Of Liauid Efnuent Monitor Setooint l The liquid efnuent monitors are Nal(TI) based systems and respond primarily to gamma radiation. Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the emuent: c = BKG + (I(C )g + SF ) = pCi/ml (2.5) Where: c = the monitor setpoint as previously defined, in (pCi/ml); BKG = the monitor background prior to discharge, ir 'pCi/ml); ! Cgan' SF d are as prev lously defined. l
- The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity. Utilizing the methodology of ANSI N13.10-1974 (Ref.11.21), the background must be maintained at a value ofless than or equal to 9E-6 pCi/ml(relative to Cs 137) in order to detect a change of 4E-7 pCi/ml of Cs-137.
l (Ref. I1.25). l-In the event that there is no detectable gamma activity in the efnuent or if the value of(I(Cg) + SF) is less than the background of the monitor, then the monitor setpoint will be set at twice the current background of the monitor. l As previously stated, the monitor's response is dependent on the gamma emitting radionuclide distribution of the effluent. Accordingly, a new database conversion factor is calculated for each release based upon the results of the gamma spectrometric analysis of the emuent sample and the measured re'sponse of the monitor to National Institute of Standards and Technology (NIST) traceable calibration sources: DBCF c = hC + (CMR) x (ECF) (2.6) DBCFe = the monitor data base conversion factor which converts count rate into concentration (p Ci/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 (pCi/ml). Cgis as previously defined. The new value of the DBCF eis calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation of the CMR is given in reference 11.14.7. l E j
APA-ZZ-01003 Rev. 9 i 2.3- LIOUID EFFLUENT CONCENTRATION MEASUREMENTS '
' ,1 quid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at the time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mind by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyzing 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 authorization for release. 'lhe liquid effluent discharge is monitored prior to entering the dilution discharge line and will ! automatically be terminated if the pre-selected alarm / trip setpoint is exceeded. Concentrations are l determined primarily from the gamma isotopic and 11-3 analyses of the liquid batch sample. For Sr", Sr", 2 2 2 2 2 Fe", Np ", Pu ", Pu '", Pu , Am , Cm242, & Cm ",24the measured concentrations from the previous l quarterly composite analyses are used until laboratory results become available. Composite samples are collected for each batch release and analyzed in accordance with FSAR Table 16.11 1. The dose from liquids discharged as continuous releases is calculated by utilizing the last measured values of samples in accordance with FSAR Table 16.11 1, 2.4 DOSE DUE TO LIOUID EFFLUENTS 2.4.1 The Maximum Exposed Individual j The cumulative dose determination considers the dose contributions from the maximum exposed J individual's consumption of fish and potable water, as appropriate. Normally, the adult is considered to be the maximum exposed individual. (Ref. I1.8.3) 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. I l.6.7) i APA-ZZ-01003 Rev. 9 2.4.2 Calculation Of Dose From I,iauid Emuents The dose contributions for the total time period, m [ At,
/=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. Dose is calculated for all radionuclides identified in liquid emuents released to UNRESTRICTED AREAS using the following expression (Ref. I1.8.3):
" ~
m l D, =[ A,, [ At, C , F, o=, (2.12) s . . Where: D, = the cumulative dose commitment to a total body or any organ, t, from the liquid effluen'.s for the total period m [ At, (=1 in mrem. At, = the length of the Ith time period over which Cj, and F are f averaged for all liquid releases, in hours. At, corresponds to the actual duration of the release (s). C;, = the average measured concentration of radionuclide, i, in undiluted liquid emuent during time period At, from any liquid release, in (pCi/ml). Aj, = the site related ingestion dose commitment factor to the total body or any organ t for each identified principal alpha, gamma and beta emitter listed in FSAR Tab'e 16.11-1, (in mrem /hr) per spCi/ml). The calculation of the Ajr values given in Table 2.1 are detailed in Ref. I 1.14.12,11.14.13, and i 1.14.5. F, = the near field average dilution factor for Ci ,during any liquid emuent release: fmu p _ (F+ f,,)89.77 V'here:
=
fmax maximum undiluted emuent flow rate during the release F = average dilution flow 89.77 = site specific applicable factor for the mixing efTn I oi the discharge structure. (Ref. I 1.5.1) The term C;,is the undiluted concentration of radioactive mawnal in liquid waste at the common release point determined in accordance with REC 16.11.1.1, Table 16.11-1, " Radioactive Liquid Waste Sampling and Analysis Program". All dilution factors beyond the sample point (s) are included in the F, term.
'Ihe nearest municipal potable water intake downstream from the liquid effluent discharge point into the Missouri River is located near the city of St. Louis, Missouri, 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 not included in dose estimates to the maximally exposed individual, or in dose estimates to the population. Should future potable 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. l (Ref. I1.6.6).
APA-ZZ-01003 Rev,9
]
l
- 2.4.3.
Summarv. Calculation Of Dose Due To Liould Effluents 1 The dose contribution for the total time period I l
=
i [ At, j
,.i i 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 emuents 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 emuents released to UNRESTRICTED AREAS. Nuclides which are not detected in the analysis are reported as "less than" the nuclide's Minimum Detectable Activity (MDA) 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 dose calculations. -l 2.5 - LIOUID RADWASTE TREATMENT SYSTEM ' The LIQUID RADWASTE TREATMENT SYSTEM is described in Chapter 11.2 of the Callaway Plant FSAR. The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for use when liquids require treatment prior to their release to the environment. OPERABILITY i is demonstrated through compliance with REC 16.11.1.1, and 16.11.1.2. ; Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each 31 days. The
~
prior 31 day period is used to calculate compliance. This may be modified as appropriate to account for { changes in radwaste treatment which may have a significant effect on the projected doses.~ 2.6 DOSE FACTORS The dose conversion factors provided in Table 2.1 were derived from the appropriate dose conversion factors of Regulatory Guide 1.109 and other sources as necessary (Ref: 11.14.5,11.14.13 and 11.14.12) Non-gamma emitting nuclides not listed in FSAR Table 16.11-1 are not considered. l ny
' )_
- APA-ZZ-01003 Rev. 9
. TABLE 2.1 INGESTION DOSE COMMITMENT FACTOR (Ajg) FOR ADULT AGE GROUP (mrem /hr)per( Ci/ml)
N.,5flidt E9Bf jagg - Total Thyroid Kidney ggg GI-LLI ER$l H No Data 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 Be-7 ' l.30E-02 2.98E-02 1.45E-02 No Data 3.15E-02 No Data 5.16E+00 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 No Data No Data -1.27E+00 7.62E-01 2.81 E-01 1.69E+00 3.20E+02
' Mn-54 No Data 4.38E+03 8.35E+02 No Data 1.30E+03 No Data 1.34E+04 Mn-56 ' No Data 1.10E+02 1.95 E+01 No Data 1.40E+02 No Data 3.52E+03 Fe-55 6.57E+02 4.54E+02 - 1.06E+02 No Data No Data 2.53 E+02 2.61 E+02 Fe-59 1.04E+03 2.44 E+03 9.34E+02 No Data No Data 6.8 l E+02 8.13 E+03 Co-57 ' No Data 2.09E+01 3.48E+01 ~ No Data No Data No Data 5.3IE+02 Co-58 No Data 8.94E+01 2.00E+02 No Data No Data ~ No Data 1.8] E+03 Co-60 No Data 2.57E+02 5.66E+02 No Data No Data No Data 4.82E+03 Ni-65 1.26E+02 1.64E+01 7.48E+00 No Data No Data No Data 4.16E+02 Cu-64 No Data 1.00E+0! 4.69E+00 No Data 2.52E+01 No Data 8.52E+02 2n-65 2.32E+04 7.38E+041 3.33 E+04 No Data 4.93 E+04 No Data 4.65E+04 Zn-69 4.93E+01 9.44 E+01 6.56E+00 No Data 6.13E+01 No Data 1.42E+01 Br-82 No Data No Data 2.27E+03 No Data No Data No Data 2.60E+03 Br No Data - No Data 'a04E+0! No Data No Data - No Data 5.81E+01 Br-84 No Data No Data ' 5.26E+0i No Data No Data No Data 4.13 E-04 Br-85 No Data No Data 2.15E+00 No Data No Data No Data O Rb-86 No Data 1.01 E+05 4.71E+04 No Data No Data No Data 1.99E+04 Rb No Data 2.90E+02 1.54E+02 No Data No Data No Data 4.00E-09 Rb-89 No Data 1.92E+02 1.35E+02 No Data No Data No Data O Sr-89 2.21 E+04 No Data 6.35E+02 - No Data No Data No Data 3.55E+03 Sr-90 5.44 E+05 No Data 1.34E+05 No Data No Data No Data 1.57E+04 Sr-91 4.07E+02 No Data 1.64E+01 No Data No Data No Data 1.94E+03 Sr-92 1.54E+02 No Data 6.68E+00 No Data No Data ' No Data 3.06E+03 Y-90 5.75E-01 No Data 1.54E-02 No Data No Data No Data 6.10E+03 Y-91M 5.44E-03 No Data 2.10E-04 No Data No Data No Data 1.60E-02
- Y-91 8.43E+00 No Data 2.25E-01 No Data No Data No Data 4.64E+03 i Y-92 5.05E-02 No Data ' l.48E-03 No Data. - No Data No Data 8.85E+02 Y-93 1.60E-01 No Data 4.42E-03 ' No Data No Data No Data 5.08E+03
, ' Zr-95 2.40E-01 7.70E-02 5.21 E-02 No Data 1.21 E-01 No Data 2.44E+02 Zr-97 ' _ l .33 E 2.68E-03 1.22E-03 No Data 4.04E-03 No Data 8.30E+02 L Nb-95 4.47E+02 2.48E+02 1.34E+02 No Data 2.46E+02 No Data 1.51E+06 Mo-99 No Data : 1.03E+02 1.%E+0 i No Data 2.33E+02 No Data 2.39E+02 Tc-99M : 8.87E-03 2.51 E-02 3.19E-01 No Data 3.81 E-01 1.23 E-02 1.48E+01 Tc-101 ,9.1lE-03 ' l.31E 1.29E-01 No Data - 2.36E-01 6.70E-03 0
)
APA ZZ-01003 Rev. 9 TABLE 2.1 (Cont'd) INGESTION DOSE COMMITMENT FACTOR (Ajt) FOR ADULT AGE GROUP (mrem /hr) per (pCi/ml) Nuclip ggg Mgg Total Tlivroid Nidney ggg GI-LLI - M Ru-103 4.42E+00 ~ No Data 1.90E+00 No Data ' l.69E+01 No Data 5.17E r02 Ru-105 - 3.68E-01 No Data 1.45E-01 No Dats 4.76E+00 No Data 2.25E402
)
Ru-106 6.57E+0 i No Data 8.32E+00 No Data 1.27E+02 No Data 4.25E+03 ! Cd-109 No Data ~ 5.54Ed92 1.S 4 E +01 No Data 5,31E+02 No Data 5.59E+03 -l
' Ag-110m 8.83E-01 ' 8.17E-01 4.85E-01 No Data 1.61E+00 No Data 3.33E+02 ,
Sn-ll3 5.66E+04 1.61E+03 3.26E+03 9.18E+02 No Data No Data 1.69E+05 I Sb-124 6.69E+00 1.26E-01 2.65 E+00 1.62E-02 No Data 5.21 E+00 1.90E+02 Sb-125 4.28E+00 4.78E-02 1.02E+00 4.35E-03 No Data 3.30E+00 4.71E+01 1
- Te-127m 6.47E+03 2.323+03 7.90E+02 1.66E+03 2.63 E+04 No Data 2.17E+04 Te-127 1.0$E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 No Data 8.30E+03 Te-129M 1.10E+04 4. l lE+03 1.74E+03 3.78E+03 4.60E+04 No Data 5.54E+04 Te-129 3.0) E+01 1.13 E+01 - 7.33 E+00 2.31 E+01 1.26E+02 No Data 2.27E+0!
Te-131M l.66E+03 8.09E+02 6.75E+02 1.28E+03 8.21 E+03 . No Data 8.03 E+04 l Te-131 1.89E+01 7.88E+0C 5.96E+00 1.55E+01 8.25E+01 No Data 2.67E+00 Te-132 2.41 E+03 I.56E+03 1,47E+03 1.72E+03 1.50E+04 No Data 7.38E+04 1130 2.71E+01 8.01E+0i 3.16E+01 - 6.79E+03 1.25E+02 No Data 6.89E+01
.1-131 - 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.66E+02 No Data 5.64E+0!
l 132 7.29E+00 1.95E+01 6.82E+00 6.82E4 02 3.llE+01 No Data 3.66E+00 1133- 5.10E+01 8.87E+01 2.70E+0! 1.30E+04 1.55E+02 No Data 7.97E+01 1 134 3.81 E+00 1.03 E+01 - 3.70E+00 1.79E+02 1.64E+01 No Data 9.01E-03
.1-135 ~ 1.59E+01 4.16E+0i 1.54E401 2.75 E+03 6.68E+01 No Data 4.70E+0i Cs-134 2.98E+05 7.09.E+05 5.80E+05 No Data 2.29E+05 7.62E+04 1.24 E+04 Cs-136 3.12E+04 1.23 E+05 - ' 8 A6E+04 No Data 6.85 E+04 9.39E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 No Data 1.77E+05 5.89E+04 1.01 E+04 Cs-138 2.64 E+02 5.22E+02 2.59E+02 No Data 3.84E+02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 2.72E-02 No Data 6.19E-04 3.76E-04 1.65E+00 Ba-140 1.94E402 2.44E-01 1.27E+01 No Data 8.3 l E-02 1.40E-01 4.00E+02 Ba-141' ' 4.50E-01 3.40E-04 . 1.52E-02 No Data 3.16E-04 1.93 E-04 2.12E-10 Ba-142 2.04E-01 2.09E-04 1.28E-02 ' No Data 1.77 E-04 1.19E-04 0 La-140 1.50E-01 - 7.53 E-02 1.99E-02 No Data No Data No Data 5.53E+03 La-142 7.65E-03 3.48E-03 8.66E-04 No Data No Data No Data 2.54E+01 Ce-141 2.24E-02 1.51 E-02 1.72E-03 No Data 7.03 E-03 No Data 5.78E+01 Cc-143 . 3.94E-03 2.92E+00 3.23E No Data 1.28E-03 No Data 1.09E+02 Ce-144 1.17E+00 4.88E-01 6.26E-02 No Data 2.89E-01 No Data 3.94E+02 Pr-143 5.50E-01 2.21 E-01 2.73E-02 No Data 1.27E-01 No Data 2.4 I E+03 Nd-147 3.76E-01 4.35E-01 2.60E-02 No Data 2.54E-01 No Data 2.09E+03
,, ' Eu 154 3.67E+01 4.52E+00 3.21 E+00 No Data 2.16E+01 No Data 3.27E+03
.Hf181 3.99E-02 . 1.94 E-01 1.80E-02 No Data 4.17E-02 No Data 2.21 E+02 W 187 2.96E+02 2.47E+02 8.64 E+0i No Data No Data No Data 8.09E+04 t.
APA-ZZ-01003 Rev. 9 TABLE 2.1 (Cont'd) INGESTION DOSE COMMITMENT FACTOR (Air) FOR ADULT AGE GROUP
. (mrem /hr) per (pCi/ml)
Nuclidt ' Bent kJvgr Total Thyroid Kidney Lung GI-LLI
'E9d!
Np-237 3.27E+04 2.84E+03 1.32E+03 No Data 9.85E+03 No Data 1.90E+03 Np-239 2.84E-02 2.80E-03 1.54E-03 No Data 8.72E-03 No Data 5.74E+02 Pu-238 5.69E+03 8.0l E+02 . l.43E+02 No Data 6.12E+02 No Data 6.1 l E+02 Pu-239' 6.58E403 8.87E+02 1.60E+02 No Data 6.78E+02 No Data 5.67E+02
~ Pu-241 1.38E+9 ,14E+00 2.78E+00 No Data 1.28E+01 No Data 1.17E+01 Am-241 4.89E+04 1.72E+04 3.23 E+03 No Data 2.43 E+04 No Data 4.43E+03 Cm-242 1.23E+03 1.25E+03 8.19E+01 No Data 3.72 E+02 No Data 4.73 E+03 Cm-243 ** 3.82E404 1.44 E+04 2.24 E+03 No Data 1.0$ E+04 No Data 4.67E+03
-
- Includes Pu-240 contribution
" Includes Cm-244 contribution
APA-ZZ-01003 - Rev. 9 TABLE 2.2 BIOACCUMULATION FACTOR (Bfg (DCi/kEl Der (DCi/ liter) l l Bfg Element Fish (Freshwater) { H 9.0 E - 01 ; Bc 2.0 E + 00 l Na 1.0 E + 02 1 Cr 2.0 E + 02 q Mn 4.0 E + O2 i Fe 1.0 E + 02 i Co 5.0 E + 01 j Ni 1.0 E + O2 - Cu 5.0 E + 01 Zn 2.0 E + 03 Br 4.2 E + 02 Rb 2.0 E + 03 Sr 3.0 E + 01 Y 2.5 E + 01 Zr 3.3 E + 00 Nb 3.0 E + 04 Mo 1.0 E + 01 Tc 1.5 E + 0! Ru 1.0 E + 01 Rh 1.0 E + 01 Ag 2.3 E + 00 Cd 2.0 E + 02 Sn 3.0 E + 03 Sb 1.0 E + 00 Te 4.0 E + 02 1 1.5 E + 01 Cs 2.0 E + 03 Ba 4.0 E + 00 La 2.5 E + 01 Ce 1.0 E + 00 Pr 2.5 E + 0i Nd 2.5 E + 01 Eu 2.5 E + 01 lif 3.3 E + 00 W l.2 E + 03 Np 1.0 E + 01 Pu 3.5 E + 00
-Am 2.5 E + 01 Cm 2.5 E + 0i '
s t W Values from Regulatory Guide 1.109. Rev.1, Table A-1 and References 11.14.4,11.14.8, and 11.14.13. 6 4 4 APA-ZZ-01003 Rev. 9 i
- 3. ' GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS Noble gas activity monitors are present on the containment building ventilation system, plant unit
' ventilation sy, tem, and radwaste building ventilation system.
The alarm / trip (alarm & trip) setpoint for any gaseous effluent radiation monitor is determined based on the 5
' instantaneous noble gas total body and skin dose rate limits of REC 16.11.2.1, at the SITE BOUNDARY '
- location with the highest annual average X/Q value.
Each monitor channel is provided with a two level system which provides sequential alarms on increasing - radioactivity levels. These setpoints are designated as alert setpoints and alarm / trip setpoints. (Ref. I 1.6.3) The radiation monitor alarm / trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. It is not considered practicable to apply instantaneous alarm / trip setpoints to integrating radiation monitors sensitive to radioiodines, 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 emciency 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 emuent. (Ref. I 1.8.5)
FSAR Table 16.11-6 provides the instrument surveillance requirements, such as calibration, source checking, functional testing, and channel checking. 3.1.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are (Ref. I 1.6.8, I 11.6.9): Monitor I.D. Description GT-RE 21 Unit Vent GH RE-10 Radwaste Building Vent GL-RE-202 Laundry Decon Facility Dryer Exhaust Monitor ! Each of the above continuously monitors gaseous radioactivity concentrations downstream of the last point of potential influent, and therefore measures effluents and not inplant concentrations. The unit vent monitor continuously monitors the effluent from the unit vent for gaseous radioactivity. The unit vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low level radioactive aerated liquids that can potentially generate airbome activity. The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the access control area, the containment purge, and the condenser air discharge.
- The unit vent monitor provides alarm functions only, and does not terminate releases from the unit vent.
The Radwaste Building ventilation effluent monitor continuously monitors for gaseous 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 waste 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 j the waste processing system.
~ This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm.
The Laundry Decon Facility Dryer Exhaust Monitor continuously monitors the effluent of the dryer exhaust for particulate radioactivity'during operation of the dryers. This emuent point is designed to release an insignificant quantity of radioactivity. The items to be placed in the dryers are typically washed before drying removing most of the radioactive material. The dryer effluent then passes through a HEPA filter before being sampled and released. i
7 i
-g APA-ZZ-01003
. Rev 9 i
- The Laundry Decon Facility Dryer Exhaust Monitor will secure the dryers and exhaust fans and isolate the -
dryer emuent upon a high radioactivity alarm or for a monitor failure. The continuous Unit Vent and Radwaste Building Vent gaseous effluent monitor setpoints are established using the methodology described in Section 3.2. Since there are two continuous gaseous effluent release ,
- points, a fraction ~of the total dose rate limit (DRL) will be allocated to each release point. Neglecting the batch releases, the plant Unit Vent mnnitor has been allocated 0.7 DRL and the Radwaste Building Vent monitor has been allocated 0.3 DRL Dese allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e.,1.0). Therefore, a particular monitor reaching the setpoint would not necessarily mean the dose rate limit at the SITE BOUNDARY is being exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the
' dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both
- systems.
' For a loss of all isokinetic sampling and/or all heat tracing for the Unit Vent or Radwaste Building Vent
- grab samplers, one hour is allowed to restore a sampler to service if sampling cannot be restored within one hour, all batch releases and ventilation not required for the operation of the plant should be secured.
The best available sampling should be maintained during this period and normal sampling returned to service as soon as possible. 3.1.2 Batch Release Gaseous Monitors ne radiation monitors associated with batch release gaseous emuents are (Ref. I1.6.9,11.6.10,11.6.11): Monitor I D. Descriotion GT-RE-22 Containment Purge System j GT-RE-33 GT RE-10 Radwaste Building Vent The Containment Purge System continuously monitors the containment purge exhaust duct during purge operations for gaseous radioactivity. The primary purpose of these monitors is to isolate the containment
; purge system on high gaseous activity via the ESFAS.'
The sample points are located outside the containment between the containment isolation dampers and the containment purge filter adsorber unit. The Radwaste Building Vent monitor was previously described. A pre-release isotopic anclysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm / trip setpoint(s)is adjusted accordingly to ensure that the limits of REC 16.11.2.1 are not exceeded. i 3.2 G ASEOUS EFFLUENT MONITOR SETPOINTS l The alarm / trip setpoint for Unit Vent and Radwaste Building Vent gaseous effluent monitors is determined based on the more restrictive of the total body dose rate (equation 3.1) and skin dose rate (equation 3.3), as calculated for the SITE BOUNDARY. He alarm trip setpoint for the Laundry Decon Facility Exhaust Monitor is set to two times equilibrium ;
~
background. During core alterations, the setpoint for the Containment Purge Monitors, GT-RE-22 and GT-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 detectable nobic gas activity in the containment atmosphere sample analyzed in accordance with REC 16.11.2.1. The full derivation of this value is discussed in reference 11.14.6. m APA-ZZ-01003 Rev. 9 3.2.1 - Total Body Dose Rate Setooint Calculations
- To ensure that the limits of REC 16.11.2.1 are met, the alarm / trip setpoint based on the total body dose rate is calculated according to:
S 5 D.R.F,F, (3.1) Where: Stb = the alarm / trip setpoint based on the total body dose rate (pCi/cc).
=
Dtb . REC 16.11.2.1 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, Fs = 0.5 corresponds to a 100% variation.) Default value is Fs = 1.0.' Fa
=
the allocation factor which will modify the required dhution factor such that simultaneous gaseous releases may be made without exceeding the limits of REC 16.11,2.1.
=
.Rtb factor used to convert dose rate to the emuent concentration as measured by the emuent monitor, in (pCi/cc) per (mrem /yr) to the total body, determined according to:
R. = C + (X/Q) [ K iO, (3.2)
. s Where:
C = monitor reading of a noble gas monitor correspo'nding to the sample radionuclide concentrations for the batch to be released. Concentrations are determined in accordance with FSAR Table 16.114. The mixture of radionuclides determined via grab sampling of tne emuent stream or source is correlated to a calibration factor to determine monitor response. The monitor response is based on concentrations, not release rate, and is in units of( Ci/cc). X/Q
=
the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY in (sec/m 3). Refer to Tables 6.1,6.2 and 6.4.
=
Ki the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem /yr) per (pCi/m3). (Table 3.1)
=
. Qi rate of release of noble gas radionuclide, i, in (pCi/sec).
Qi si calculated as the product of the ventilation path flow rate and the measured activity of the emuent
- stream as determined by sampling.-
1
>+ ,
1 APA-ZZ-01003 Rev. 9 i 3.2.2 Skin Dose Rate Setooint Calculation To ensure that the limits of REC 16.11.2.1 are met, the alarm / trip setpoint based on the skin dose rate is calculated according to: S, s D,R,F,F, (3.3) ;
' Where:
Fsand F aare as previously defined.
=
Ss the alarm / trip setpoint based on the skin dose rate. D3 =
' REC 16.11.2.1 limit of 3000 mrem /yr, conservatively interpreted as a continuous release over j a one year period.
Rs = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (pCi/cc) per (mrem /yr) to the skin, determined according to: R =C+ (X /Q) [ (L, + 1.1M,) Q 3 (3.4)
.~ \ .
Where: Lj u the skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem /yr)per(pC1/m3 ). 1.1 = conversion factor: I mrad air dose = 1.1 rr. rem skin dose.
=
Mi the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mradlyr)per(pCi/m3). C,(X/Q) and Q are previously defined.
- 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 3.3.1 Dose Rate from Gaseous Effluents 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. I 1.8.6)
The factors K;, Lj, and Mj relate the radionuclide airborne concentrations to various dose rates, assuming a semi-infinite cloud model. 3.3.1.1 Dose Rate from Noble Gases The release rate limit for noble gases is determined according to the following general relationships (Ref. I 1.8.6): D ,, = [K ((X/Q)O,) i s 500 mrem /yr (3.5) i D, = [(L + i1.1 M,)((X / Q)Q,)' s 3000 mrem / yr (3.6) i Where: Qi = , The release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in (pCi/sec). 1.1 = Units conversion factor; I mrad air dose = 1.1 mrem skin dose.
~ Li , iM , K;, (X / Q), D,3& D,are as previously identified.
APA-ZZ-01003 Rev. 9 3.3.1.2 Dose Rate from Radionuclides Other than Noble Gases The release rate limit for Iodine-131 and lodine-133, for tritium, and for all radioactive materials in particulate form with halflives greater than 8 days is determined according to (Ref.11.8.7): D = [ R,( X / Oj Q, s 1500 mrem / yr (3.7) i
. Where:
Do = Dose rate to any critical organ, in (mrem /yr).
=
-RJ Dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem /yr) per (pCi/m3 ).
.1
,Qi =
The release rate of radionuclides other than noble gases, i, in gaseous effluents, from all vent -! releases in (pCi/sec). (X / Q) is as previously defined. The dose parameter (Rj) includes the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age. The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental form (ref.11.8.7). R; values were calculated according to (Ref. I l.8.8): R, = K' (BR) DFA, (3.8) Where: X' = Units conversion factor: IE06 pCi/pCi BR = The breathing rate. (Regulatory Guide 1.109, Table E 5). DFAj = The maximum organ inhalation dose factor for the ith radionuclide, in (mren/pci). The total body is considered as an organ in the selection of DFAj. (Ref.11.11.5 and 11.14.4) The results of periodic tritium, iodine and particulate samples of the Unit Vent and Radwaste Vent are used to verify the dose rate limit was not exceeded for the period during which the samples or composite samples were obtained. l
APA-ZZ-01003 Rev. 9 3.3.2 Dose Due to Gaseous Emuents 3.3.2.1 Air Dose Due to Noble Gases The air dose at the SITE BOUNDARY due to noble gases is calculated according to the following methodology (Ref. I1.8.9): During any calendar quarter, for gamma radiation: D, = 3.17E-08 [ (M, (X/Q) q,) s 5 mrad (3.9) i During any calendar quarter, for beta radiation: D,, = 3.17E-08 [ (N, {X/Q) q,) s 10 mrad (3.10) i During any calendar year, for gamma radiation: D, = 3.17E-08 [ (M, (X / Q) q,) s 10 mrad (3.11) i During any calendar year, for beta radiation: D, = 3.17E-08 [ (N, (X / Q) q, ) s 20 mrad (3.12) Where: DE = Air d se in mrad, from gamma radiation due to noble gases released in gaseous emuent.
=
Db . Air dose in mrad, from beta radiation due to noble gases released in gaseous effluents.
=
Ni The air dose factor due to beta emissions for each identified noble gas radionuclide, i, in (mradlyr)per(pCi/m3), qi
- The releases of noble gas radionuclides, i. in gaseous effluents, for all gaseous releases in (p Cl). Releases are cumulative over the calendar quarter or year as appropriate. q, is calculated as the product of the ventilation flow rate and the measur:d activity of the effluent stream as determined by sampling.
3.17E-08 = The inverse of the number of seconds per year. X / Q & M are i as previously defined. i APA-ZZ-01003 ( Rev. 9 3.3.2.2 Dose Due to Radionuclides Other than Noble Gases The dose to a MEMBER OF THE PUBLIC from lodine-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: During any calendar quarter: I jD ys 7.5 mrem (3.13) During any calendar year: I; D ys 15 mrem (3.14) For each pathway,J, (i.e., for inhalation, ground plane, meat, cow- milk, goat- milk, and vegetation) Du is calculated according to the expression: Du= 3.17E-8 E i Roy [Wj q,] (3.15) Where: D uj = Dose in mrem, to a MEMBER OF Tile PUBLIC from radionuclides other than noble gases, from pathwayj, received by organ I (including total body). R uj = ne dose factor for each identified radionuclide, i, in m 2(mrem /yr) per (pCi/sec) or 3 (mrem /yr) per (pCi/m ) as appropriate, for the pathway 3, and exposed organ I, appropriate to the age group of the critical MEMBER OF THE PUBLIC receptor. Wj = (X / g) for the inhalation and tritium pathways, in (sec/m'). Refer to Tables 6.1,6.2, and 6.4 for applicability. Wj - (D / g) for the food and ground plane pathways, in (meters *). Refer to Tables 6.1,6.2 and 6.4 for applicability. (D/Q) = the average relative deposition of the emuent at or teyond the SITE BOUNDARY, considering depletion of the plume during transport. q; = The releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases, i, in gaseous effluents, for all gaseous releases in (pCi). Releases are cumulative over the calendar quarter or year as appropriate. q, is calculated as the product of ventilation flow rate and the measured activity of the effluent stream as determined by sampling. 3.17 E-08 = ne inverse of the number of seconds per year. X / Q is as previously defined. For the direction sectors with existing pathways within 5 miles from the site, the appropriate R uJ values are used. If no real pathway exists within 5 miles from the center of the building complex, the cow-milk RuJ 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 UJ for an existing pathway within 5 miles is less than a cow-milk R y; at 4.5 to 5.0 miles, then the value of the cow-milk R uj at 4.5 to 5.0 miles is used. (Ref. I1.8.9) i Although the annual average relative concentration (X / G)and the average relative deposition rate ! (D / Gj 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 frorn ground plane deposition is added to the dose for each individual organ. (Ref. I1.11.3)
w , APA-ZZ-01003 Rev. 9 _. 3.4 GASEOUS 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 allow for the 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. 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. The OPERABILITY of the gaseous radwaste treatment 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 REC 16.11.2.1,16.11.2.2, and 16.11.2.3. Projected doses (gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the SITE l ' BOUNDARY are determined each 31 days. The prior 31 day period is used to calculate compliance. This may be modified as appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses. 3.5 DOSE FACTORS The dose conversion factors provided in the following tables were derived from the appropriate dose conversion factors in Regulatory Guide 1.109 and other sources as necessary (Ref; 11.14.9 and l l.14.li). l Per USNRC guidance, particulate nuclides with a half-life ofless than 8 days are not considered l (Ref: 11.24). Y-90, La-140, and Pr-144 are included because the parent half-life is greater than 8 days and
-]
'l equilibrium is assumed. Non-gamma emitting nuclides not listed in FSAR Table 16.11-4 are also not -
considered. (CTSN 43121) l i i l
)
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- + + + + + + +++++++
A F BaF l ae s ie Kp y - E+EEEEEEEEEEEEE E 671 276651 421 234 E ) S t oo /y r 51 69.4651 591 8488 O TD m X.: 7 1 1 51 1 1 92231 1 88 D e r ( m L C' e L d i l c u n sa 35888mm578901mm3 88 - - - 89331 33 5 333m578 31 1 1 I 4-io - - r- r r r r1 1- e 1- e- e- - r d D r r K K K K K e- eXeXXXeA KK a XX X _ R L
APA-ZZ-01003 Rev. 9 TABLE 3.2 1 PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES l OTHER THAN NOBLE GASES Ground Plane Pathway 2 (m mrem /yr)per(pCi/sec) i NUCLIDE TOTAL, BODY SKIN Be-7 2.24 E+07 3.21 E+07 Cr-51 4,66E+06 5.51 E+06 Mn-54 1.39E+09 1.63 E+09 Fe-59 2.73 E+08 3.21 E+08 Co-57 2.98E+08 4.37E+08 Co-58 3.79E+08 4.44E+08 Co-60 2.15E+ 10 2.53 E+10 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03 E+07 Sr 89 2.16E+04 2.51 E+04 l Y-90 5.36E+06 6.32E+06 i Y-91 1.07E+06 1.21E+06 Zr-95 2.45 E+08 2.84E+08 l Nb-95 2.50E+08 2.94 E+08 l i Ru-103 1.08E+08 1.26E+08 ! Ru-106 4.22E+03 $.07E+08 . Ag-110m 3.44E+09 Cd-109 3.76E+07 4.01 E+09 1.54E+08
)
Sn-ll3 1.43E+07 4.09E+07 { Sb-124 8.74E+08 1.23 E+09 Sb-125 3.57E+09 5.19E+09 Te-127m 9.17E+04 1.08E+05 < Te-129m 1.98E+07 2.31 E+07 I l 4 l 21 i.
APA-ZZ-01003 Rey,9 TABL,E 3.2 PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE G ASES Ground Plane Pathway 2 (m mrem /yr)per(pCi/sec) 3 i NUCLIDE TOTALBODY SKIN 1130 5.5lE+06 6.69E+06 1-131 1.72E+07 2.09E+07 l-132 1.25E+06 1.47E+06 1-133 2.45 E+06 2.98E+06 1-134 4.47E+05 5.31E+05 1 135 2.53E+06 2.95E+06 Cs-134 6.85E+09 8.00E+09 Cs-136 1.51E+08 1.71E+08 Cs-137 1.03 E+ 10 1.20E+ 10 Ba-140 2.05 E+07 2.35 E+07 La-140 1.47E+08 1.66 E+08 Ce-141 -1.37E+07 1.54E+07 Cc-144 6.96E+07 8.04E+07 Pr-144 4.35 E+07 5.00E+07 Nd l47 8.39E+06 1.01 E+07 Eu-154 2.21 E+ 10 3.15E+ 10 Hf-181 1.97E+08 2.82E+08 22
APA-ZZ-01003 Rev. 9 TABLE 3.3 CHILD PATiiWAY DOSE FACTORS (R i) FOR RADIONUCLIDES OTIIER TIIAN NOBLE G ASES l Inhalation Pathway i (mrem /yr) per (pCi/m3) l ) Nuclide Bone Liver Total Thyroid Kidney Lung GI-LLI l l Brdy j 11 ND 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 l Be-7 8.47E+02 1.44E+03 9.25 E+02 ND ND 6.47E+04 2.55 E+03 l l Cr-51 ND ND 1.54E402 8.55E+0! 2.43E+01 1.70E+04 1.08E +03 l Mn-54 ND 4.29E+04 9.51 E+03 ND 1.00E404 1.58E+06 2.29E+04 l Fc-55 4.74E+04 2.52 E+04 7.77E+03 ND ND 1.llE+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 ND ND 1.27E+06 7.07E+04 Co-57 ND 9.03 E+02 1.07E+03 ND ND 5.07E+05 1.32E+04 j Co-58 ND 1.77E+03 3.16E+03 ND ND 1.llE+06 3.44 E+04 Co-60 ND 1.31E+04 2.26E+04 ND ND 7.07E+06 9.62 E+04 l Zn-65 4.25 E+04 1.13 E+05 7.03 E+04 ND 7.14E+04 9.95E+05 1.63E+04 Rb-86 ND 1.98E+05 1.14 E+05 ND ND ND 7.99E+03 Sr-89 5.99E+05 ND 1.72 E+04 ND ND 2.16E+06 1.67E+05 Sr-90 1.0lE+08 ND 6.44 E+06 ND ND 1.48E+07 3.43 E+ 05 Y-90 4. l l E+03 ND 1llE+02 ND ND 2.62E+05 2.68E405 Y 91 9.14 E+05 ND 2.44E+04 ND ND 2.63 E+06 1.84 E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 ND 5.96E404 2.23 E+06 6. l l E+04 Nb-95 2.35 E+04 9.18E+03 6.55E+03 ND 8.62 E+03 6.14 E+05 3.70E+04 Ru-103 2.79E+03 ND 1.07E+03 ND 7.03 E+03 6.62E+05 4.48 E+04 Ru-106 1.36E+05 ND 1.69E+04 ND 1.84 E+05 1.43 E+07 4.29E+05 Ag-110m 1.69E+04 1.14 E+04 9.14 E+03 ND 2.12E+04 5.48E+06 1.00E+05 Cd-109 ND 5.48E+05 2.59E+04 ND 4.96E+05 1.05E+06 2.78E+04 Sn-ll3 1.13E+05 3.12 E+03 8.62E+03 2.33E+03 ND 1.46E+06 2.26E+05 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 ND 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 ND 2.32 E+06 4.03 E+04 Te-127m 2.49E+ 04 8.55E+03 3.02 E+03 6.07E+03 6.36E+04 1.48E+06 7.14E404 Te-129m 1.92E+04 6.85E+03 3.04 E+03 6.33 E+03 5.03E+04 1.76E+06 1.82 E+05 23
APA-ZZ-01003 Rev. 9 TABLE 3.3 CillLD PATIlWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTIIER TIIAN NOBLE GASES Inhalation Pathway (mrem /yr) per (pCi/m3 ) Nuclide Bone Liver Total Thyroid Kidney latng GI-LLI Body 1130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45 E+04 ND 5. I I E+03 I-131 4.81 E+04 4.31 E+04 2.73E+04 1.62E+07 7.88E+04 ND 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94 E+05 6.25 E+03 ND 3.20E+03 I-133 1.66E+04 2.03 E+04 7.70E+03 3.85E+06 3.38E+04 ND 5.48E+03 I134 1.17E+03 2.16E+03 9.95 E+02 5.07E+04 3.30E+03 ND 9.55 E+02 1-135 4.92E+03 8.73 E+03 4.14E+03 7.92E+05 1.34E+04 ND 4.44E+03 Cs-134 6.51 E+05 1.01 E+06 2.25 E+05 ND 3.30E+05 1.21 E+05 3.85E+03 Cs-136 6.51 E+04 1.71E+05 1.16E+05 ND 9.55 E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 ND 2.82E+05 1.04 E+05 3.62E+03 Ba-140 7.40E+04 6.48E+01 4.33 E+03 ND 2.l l E+0 ! 1.74 E+06 1.02E+05 La-140 6.44 E+02 2.25 E+02 7.55E+01 ND ND 1.83 E+05 2.26E+05 Cc-141 3.92E+04 1.95E+04 2.90E+03 ND 8.55E+03 5.44E+05 5.66E+04 Ce 144 6.77E+06 2.12 E+06 3.61 E+05 ND 1.17E+06 1.20E+07 3.89E+05 Pr 143 1.85E+04 5.55E+03 9.14E+02 ND 3.00E+03 4.33 E+05 9.73 E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 ND 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73 E+03 6.81 E+02 ND 4.81 E+03 3.28E+05 8.21E+04 Eu-154 1.0lE+07 9.21 E+05 8.40E+05 ND 4.03 E+06 6.14E+06 1.10E+05 lif-181 2.78E+04 1.01E+05 1.25E+04 ND 2.05 E+04 1.06E+06 6.62E+04 24 l
APA-ZZ-01003 Rev. 9 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway (m2mrem /yr)per( Ci/sec) Nuclide Do!Le Liver Total Thyroid Kidney Lung GILLI Body H3 ND 2.34 E+02 2.34 E+02 2.34E+02 2.34E+02 2.34E+02 2.34E402 Be-7 7.38E+03 1.26E+04 8.07E+03 0.00E+00 1.23 E+04 0.00E+00 7.00E+05 Cr-51 0.00E+00 0.00E+00 8.80E+03 4.88E+03 1.33 E+03 8.92E+03 4.67E+05 Mn-54 0.00E+00 8.02E+06 2.14E+06 0.00E+00 2.25 E+06 0.00E+00 6.73 E+06 Fe-55 4.58E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.50E+07 Fe-59 3.77E+08 6.10E+08 3.04 E+08 0.00E+00 0.00E+00 1.77E+00 6.35E+08 Co 57 0.00E+00 5.92E+06 1.20E+07 0.00E+00 0.00E+00 0.00E+00 4.85E+07 Co-58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.59E+07 Co-60 0.00E+00 6.94 E+07 2.05E+08 0.00E400 0.00E+00 0.00E+00 3.84E+08 Zn-65 3.76E+08 1.00E+09 6.23 E+08 0.00E+00 6.31 E+08 0.00E+00 1.76E+08 I Rb-86 0.00E+00 5.77E408 3.55E+08 0.00E+00 0.00E+00 0.00E+00 3.7 t E+07 Sr-89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 Sr-90 1.04 E+ 10 0.00E+00 2.64 E+09 0.00E+')0 0.00E+00 0.00E+00 1.40E+08 Y 90 1.93 E+05 0.00E+00 5.16E+03 0.00E+00 0.00E+00 0.00E+00 5.49E+08 Y-91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 Zr-95 2.67E+06 5.86E+05 5.22E+05 0.00E+00 8.39E+05 0.00E+00 6. l l E+08 Nb-95 4.26E+06 1.66E+06 1.18E+06 0.00E+00 1.56E+06 0.00E+00 3.07E+09 j i Ru-103 1.55E+08 0.00E400 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01 E+09 l Ru-106 4.44 E+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00E+00 6.91 E+ 10 l Ag-110m 8.40E+06 5.67E+06 4.53E+06 0.00E+00 1.0bE+07 0.00E+00 6.75 E+08 Cd-109 0.00E+00 1.91E+06 8.84 E+04 0.00E+00 1.70E+06 0.00E+00 6.18 E+06 l l Sn-ll3 2.18E+09 4.48E+07 1.24 E+08 3.31 E+09 0.00E+00 0.00E+00 1.54 E+09 l Sb-124 2.93E+07 3.80E+05 1.03 E+07 6.46E+04 0.00E+00 1.62E+07 1.83E+08 Sb-125 2.85E+07 2.20E+05 5.97E+06 2.64E+04 0.00E+00 1.59E+07 6.81 E+07 . I Te-127m 1.78E+09 4.78E+08 2. l l E+08 4.25E+08 5.07E+09 0.00E+00 1.44 E+09 I Te129m 1.79E+09 5.00E+08 2.78E408 5.78E+08 5.26E+09 0.00E+00 2.19E+09 1 1 130 3.06E-06 6.18E-06 3.18E-06 6.80E-04 9.23 E-06 0.00E+00 2.89E-06 l 25 1
( APA-ZZ-01003 I Rev. 9 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway (m2mrem /yr)per( Ci/sec) Nuclide Bone Liver Total Thyroid Kidney Lung GI-LLI
.M- _.!
l-131 1.66E+07 1.67E+07 9.47E+06 5.51 E+09 2.74E+07 0.00E+00 1.48E+06 1132 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 133 5.70E-01 7.05 E-01 2.67E-01 1.31E+02 1.17E+00 0.00E+00 2.84E-01 1-134 0.00E+00 0.00E+ 00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 1-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 9.23 E+08 1.51E+09 3.20E+08 0.00E+00 4.69E+08 1.68E+08 8.17E+06 Cs-136 1.62E+07 4.46E+07 2.89E+07 0.00E+00 2.38E+07 3.54E+06 1.57E+06 Cs-137 1.33 E+09 1.28E409 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 Ba-140 4.39E407 3.85 E+04 2.56E+06 0.00E+00 1.25E+04 2.29E+04 2.22E+07 La-140 3.33 E+02 1.17E+02 3.93E+01 0.00E+00 0.00E+00 0.00E+00 3.25E+06 Ce-141 2.22E4 04 1.llE+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 Ce-144 2.32E+06 7.27E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08 Pr-143 3.34E+04 1.00E+04 1.66E+03 0.00E+00 5.43E+03 0.00E+00 3.6 l E+07 Pr-144 5.63E+02 1.74E +02 2.83E+01 0.00E+00 9.2 ] E+01 0.00E+00 3.75E+05 Nd-147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 Eu-154 1.12E+ 07 1.01E+06 9.20E+ 05 0.00E+00 4.43 E+06 0.00E+00 2.34E+08 Hf-l81 4.77E+06 1.74E+07 2. I 5 E+06 0.00E+00 3.53 E+06 0.00E+00 6.41 E+09 l 26
r APA-ZZ-01003 Rev. 9 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTHER THAN NOHLE GASES j Grass-Cow-Milk Pathway l 2 (m mrem /yr)per(pCi/sec) Nuclide Bone Liver Total Thyroid Kidney Lung CI-LLI Body H-3 0.00E+ 00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 Be-7 7.50E+03 1.28E+04 8.20E+03 0.00E+00 1.25 E+04 0.00E+00 7.12E+05 Cr-51 0.00E+00 0.00E+00 1.02E+05 5.66E+04 1.55E+04 1.03 E+05 5.40E+06 Mn-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 i i Fe-55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 Fe-59 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.64E+07 2.03 E+08 Co-57 0.00E+00 3.h4E+06 7.78E+06 0.00E+00 0.00E+00 0.00E+00 3.15E+07 Co-58 0.00E+00 1.21 E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 Co-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 Zn 65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95 E+09 0.00E+00 1.94 E+09 Rb-86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65 E+08 Sr-89 6.63E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.57E &08 Sr-90 1.12E+ 11 0.00E+00 2.84 E+10 0.00E+00 0.00E+00 0.00E+00 1.51 E+09 Y-90 3.38E+03 0.00E+00 9.05 E+01 0.00E+00 0.00E+00 0.00E+00 9.62E+06 Y-91 3.91 E+04 0.00E+00 1.04 E+03 0.00E+00 0.00E+00 0.00E+00 5.20E+06 Zr-95 3.84E+03 8.43 E+02 7.51 E+02 0.00E+00 1.21E+03 0.00E+00 8.80E+05 Nb-95 3.72E+05 1.45E+05 1.03E+05 0.00E+00 1.36E+05 0.00E+00 2.68E+0S Ru-103 4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.IIE+05 Ru-106 9.25 E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44 E+06 Ag-110m - 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63 E+08 0.00E+00 1.68E+10 ! Cd-109 0.00E+00 3.86E+06 1.79E+05 0.00E+00 3.45E+06 0.00E+00 1.25 E+07 Sn-l l3 6.l l E+08 1.26E+07 3.48E+07 9.29E+08 0.00E+00 0.00E+00 4.32E+08 Sb-124 1.09E+08 1.41E+06 3.81 E+07 2.40E+05 0.00E+00 6.03 E+07 6.80E+08 j Sb-125 8.71 E+07 6.72E+05 1.83E+07 8.07E+04 0.00E+00 4.86E+07 2.08E+08 I Te-127m 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94 E+08 0.00E+00 1.69E+08 l Te-129m 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98 E +08 0.00E+00 3.31 E+08 I t ! j 27 l l
APA-ZZ-01003 . Rev. 9 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTHER TH.AN NOBLE G ASES Grass-Cow-Milk Pathway 2 (m mrem /yr)per(pCi/sec) Nuclide Bone Liver Total Thyroid Kidney jgng GI-LLI Body 1-130 1.73 E+06 3.50E+06 1.80E+06 3.85E+08 5.23E+06 0.00E+00 1.64E+06 1-131 1.30E+09 1.31E+09 7.46E+08 4.34E+11 2.15E+09 0.00E+00 1.17E+08 l132 6.92E-01 1.27E+00 5.85E-01 5.90E+01 1.95E+00 0.00E+00 1.50E+00 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.54E+07 0.00E+00 8.57E+06 I-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l l-135 5.41E+04 9.74E404 4.6] E+04 8.63 E+06 1.49E+05 0.00E+00 7.42E+04 : . Cs-134 2.27E+10 3.72E+10 7.84E+09 0.00E+00 1.15E+10 4. I4E+09 2.00E+08 Cs-136 1.01 E+09 2.78 E+09 1.80E+09 0.00E+00 1.48E+09 2.21 E+08 9.78E+07 Cs-137 3.23 E+10 3.09E+ 10 4.56E+09 0.00E+00 1.0l E+10 3.62E+09 1.93 E+08 Ba-140 1.17E+08 1.03 E+0) 6.84 E+06 0.00E+00 3.34E+04 6.12E+04 5.94E+07 Ce-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 La-140 1.78E+02 6.23E+01 2.1 OE+01 0.00E+00 0.00E+00 0.00E+00 1.74E+06 Cc-144 1.62E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33 E+08 Pr 143 7.19E+02 2. I 6E+02 3.57E+01 0.00E+00 1.I7E+02 0.00E+00 7.76E+05 Pr-144 5.04 E+00 1.56E+00 2.53 F-01. 0.00E+00 8.24 E-01 0.00E+00 3.35E+03 Nd-147 4.45E+02 3.61 E+02 2.L c+01 0.00E+00 1.98E+02 0.00E+00 5.71E+05 Eu-154 9.43E+04 8.48 E+03 7.75 E+03 0.00E+00 3.73 E+04 0.00E+00 1.97E+06 Hf-I81 6.44E+02 2.35E+03 2.9 I E+02 0.00E+00 4.76E+02 0.00E+00 8.66E+05 28
g l APA-ZZ-01003 l Rev. 9 i TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTHER THAN NOHLE GASES Grass-Goat-Milk Pathway (m2 mrem /yr)per( Ci/sec) Nuclide Bone Liver Total Th_y_roid Kidn_n Lung GI-LLI Body 11-3 0.00E+00 3.20E+ 03 3.20E+03 3.20E*03 3.20E+03 3.20E+03 ' 3.20E+03 Be-7 9.00E+02 1.53 E+03 9.84E+02 0.00E+00 1.50E+03 0.00E+00 8.55 E+04 Cr-51 0.00E400 0.00E+00 1.22E+04 6.79E+03 1.85 E+03 1.24E404 6.48 E+05 Mn-54 0.00E+00 2.52E+06 6.71 E+05 0.00E+00 7.06E+05 0.00E+00 2.l l E+06 Fe-55 1.45 E+06 7.72E+05 2.39E+05 0.00E+00 0.00E+00 4.36E+ 05 1.43 E+05 i Fe-59 1.56E+06 2.53 E+06 1.26E+06 0.00E+00 0.00E+00 7.34 E+05 2.64E+06 ! Co-57 0.00E+00 4.61E+05 9.33E+05 0.00E+00 0.00E+00 0.00E+00 3.78E+06 Co-58 0.00E+00 1.46E+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.50E+06 i Co-60 0.00E+00 5.19E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 l Zn-65 4.97E+08 1.32E+09 8.23 E+08 0.00E+00 8.34E+08 0.00E+00 2.32E+08 i Rb-86 0.00E+00 1.05E+09 6.48E+08 0.00E+00 0.00E+00 0.00E+00 6.78E+07 Sr-89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 Sr-90 2.35E+ 11 0.00E+00 5.95 E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Y-90 4.06E+02 0.00E+00 1.09E+01 0.00E+00 0.00E+00 0.00E+00 1.15E406 Y-91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.25 E+05 l Zr-95 4.60E+02 1.01E+02 9.01 E+01 0.00E+ 00 1.45E+02 0.00E+00 1.06E+05 Nb-95 4.46E+04 1.74 E+04 1.24 E+04 0.00E+00 1.63 E+04 0.00E+00 3.21 E+07 Ru-103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 Ru-106 1.IIE+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73 E+05 Ag-110m 2.51 E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01 E+09 Cd-109 0.00E+00 4.64 E+05 2.15 E+04 0.00E+00 4.14 E+05 0.00E+00 1.50E+06 Sn-ll3 7.33 E+07 1.51E+06 4.18E+06 1.llE+08 0.00E+00 0.00E+00 5.18E+07 Sb-124 1.30E+07 1.69E+05 4.57E+06 2.88E+04 0.00E+00 7.24E+06 8.16E+07 Sb-125 1.05E+07 8.06E+04 2.19E+06 9.68E+03 0.00E+00 5.83E+06 2.50E+07 Te-127m 2.50E+07 6.73E+06 2.97E+06 5.98E+06 7.13 E+07 0.00E+00 2.02E+07 Te-129m 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.57E+07 0.00E+00 3.98E+07
- I130 2.08E+06 4.20E+06 2.16E+06 4.62E+08 6.27E+06 0.00E+00 1.96E+06 I-131 1.57E+09 1.57E+09 8.95 E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+0R l-132 8.30E-01 1.53E+00 7.02 E-01 7.08E+01 2.34E+00 0.00E+00 1.80E+00 29 L
r APA-ZZ-01003 Rev. 9 ( TABLE 3.3 l CHIL.D PATIIWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTHER THAN N-OBLE G ASES l Grass-Goat-Milk Pathway 2 (m mrem /yr)per(pCi/sec) Nuclide Bone Liver Total Thyroid Kidney Long GI-LLI Body 1-133 2.06E+07 2.55 E+07 9.66E+06 4.74 E+09 4.25E+07 0.00E+00 ' l .03 E+07 l134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 6.49 E+04 1.17E+05 5.53E+04 1.04E+07 1.79E+05 0.00E+00 8.90E+04 Cs-134 6.80E+10 1.12E+11 2.35 E+10 0.00E+00 3.46E+10 1.24E+ 10 6.0lE+08 Cs-136 3.04E+09 8.35E+09 5.40E+09 0.00E+00 4.45E+09 6.63 E+08 2.93E+08 Cs 137 9.68E+ 10 9.27E+ 10 1.37E+10 0.00E+00 3.02E+10 1.09E+ 10 5.80E+08 Ba-140 1.41E+07 1.23 E+04 8.21 E+05 0.00E+00 4.0l E+03 7.35E+03 7.13 E+06 La-140 2.14E+01 7.47E+00 2.52E400 0.00E+00 0.00E+00 0.00E+00 2.08E+05 Ce-141 2.63 E+03 1.3]E+03 1.95E+02 0.00E+00 5.75E+02 0.00E+00 1.63E+06 Ce-144 1.95E+05 6.l l E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 Pr 143 8.63 E+01 2.59E+0! 4.28E+00 0.00E+00 1.40E+01 0.00E+00 9.31E+04 Pr-144 6.0$E-01 1.87E-01 3.04E-02 0.00E+00 9.89E-02 0.00E+00 4.03E+02 Nd-147 5.34E+01 4.33 E+0 i 3.35 E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Eu-154 1.13 E+04 1.02E+03 9.29E+02 0.00E+00 4.47E+03 0.00E+00 2.37E+05 Hf-181 7.73E+0! 2.81 E+02 3.49E+0i 0.00E+00 5.72E+0) 0.00E+00 1.04E+05 30
=- APA-ZZ-01003 Rev. 9 TABLE 3.3 CIIILD PATHWAY DOSE FACTORS (R i ) FOR RADIONUCLIDES f OTHER THAN NOBLE GASES Vegetation Pathway 2 (m mrem /yr)per(pCi/sec) N!!.clide Bone Liver Total Thyroid Kidney lagi.g CI-LLI {
\
H-3 ND 4.0l E+03 4.0l E+03 4.01 E+03 4.01 E+03 4.01E+03 4.0l E+03 Be-7 3.38E405 5.76E+05
)
3.70E+05 0.00E+00 5.65E+05 0.00E+00 3.21 E+07 Cr-51 0.00E+ 00 0.00E+00 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21 E+06 Mn-54 0.00E+00 6.65 E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 Fe-55 8.0l E+08 4.25E+08 1.32 E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 Fe-59 3.98E+08 6.43 E+08 3.20E+08 0.00E+00 0.00E+00 1.87E+08 6.70E+08 ) Co-57 0.00E+00 2.99E+07 6.04 E+07 0.00E+00 0.00E+00 0.00E+00 2.45E+08 Co-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 Zn-65 8.13 E+08 2.17E+09 1.35 E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 Rb-86 0.00E+00 4.52 E+08 2.78 E+08 0.00E+00 0.00E+00 0.00E+00 2.91 E+07 Sr-89 3.60E+ 10 0.00E+00 1.03 E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 Sr-90 1.24E+12 0.00E+00 3.15E+ 11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y-90 3.01 E+06 0.00E+00 8.04E+04 0.00E+00 0.00E+00 0.00E+00 8.56E+09 Y-91 1.86E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.48E+09 Zr-95 3.86E+06 8.48E+05 7.55 E+05 0.00E+00 1.21E+06 0.00E+00 8.85 E+08 Nb-95 7.48E+05 2.91 E+05 2.08 E+05 0.00E+00 2.74E+05 0.00E+00 5.39E+08 Ru-103 1.53 E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 Ru-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.0lE+09 0.00E+00 1.16E+10 Ag-110m 3.21 E+07 2.17E+07 1.73 E+07 0.00E+00 4.04 E+07 0.00E+00 2.58E+09 Cd-109 0.00E+00 2.45 E+08 1.14 E+07 0.00E+00 2.18E+08 0.00E+00 7.94E+08 Sn-ll3 1.58E+09 3.25E+07 9.00E+07 2.40E+09 0.00E+00 0.00E+00 1.12E+09 Sb-124 3.52E+08 '4.57E+06 1.23 E+08 7.77E+05 0.00E+00 1.95E+08 2.20E+09 Sb-125 4.99E+08 3.85 E+06 1.05E+08 4.63 E+05 0.00E+00 2.78E+08 1.19E+09 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 Te-129m 8.4 ] E+08 2.35E+08 1.31E+08 2.7] E+08 2.47E+09 0.00E+00 1.03 E+09 l-130 6.16E+05 1.24E+06 6.4 ] E+05 1.37E+08 1.86E+06 0.00E+00 5.82E+05 l-131 1.43 E+08 1.44E+08 8.17E+07 4.76E+ 10 2.36E+08 0.00E+00 1.28E+07 31
n APA-ZZ-01003 Rev. 9 TABLE 3.3 CHILD PATIIWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER TIIAN NOBLE GASES Vegetation Pathway (m2mrem /yr)per(pCi/sec) Nuclide Bone Liver Total Thyroid Kidney Lung GI-LLI l Body ! I-132 9.23E+01 1.70E+02 7.80E+01 7.87E+03 2.60E+02 0.00E+00 2.00E+02 1133 3.53 E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 1-134 1.56E-04 2.89E-04 1.33 E-04 6.65 E-03 4.42 E-04 0.00E+00 1.92E 04 1-135 6.26E+04 1.13E+05 5.33 E+04 9.98 E+06 1.73 E+05 0.00E+00 8.59E+04 Cs-134 1.60E+ 10 2.63 E+10 5.55E+09 0.00E+00 8.15 E+09 2.93 E+09 1.42E+08 Cs-136 8.24E+07 2.27E+08 1.47E+08 0.00E+00 1.21E+08 1.80E+07 7.96E+06 Cs-137 2.39E+ 10 2.29E+ 10 3.38 E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 Ba-140 2.77E+08 2.43 E+05 1.62 E+07 0.00E+00 7.90E+04 1.45E+05 1.40E+08 La-140 3.36E+04 1.18E+04 3.96E+03 0.00E+00 0.00E+00 0.00E+00 3.28E+08 Ce-141 6.56E+05 3.27E+05 4.86E+04 0.00E+00 1.43 E+05 0.00E+00 4.08E+08 Ce-144 1.27E+08 3.98E+07 6.78E+06 0.00E+00 2.21 E+07 0.00E+00 1.04 E+ 10 Pr-143 1.46E+05 4.37E+04 7.23 E+03 0.00E+00 2.37E+04 0.00E+00 1.57E+08 Pr-144 7.88E+03 2.44 E+03 3.97E+02 0.00E+00 1.29E+03 0.00E+00 5.25E+06 Nd-147 7.15 E+04 5.79E+04 4.48 E+03 0.00E+00 3.18E+04 0.00E+00 9.17E+07 Eu-154 1.66E+08 1.50E+07 1.37E+07 0.00E+00 6.57E+07 0.00E+00 3.48E+09 Hf-181 4.90E+05 1,79E+06 2.2 ] E+05 0.00E+00 3.63 E+05 0.00E+00 6.59E+08 i 32 l i j
w APA-ZZ-01003 Rev. 9 TABLE 3.4 , ADULT PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES l Inhalation Pathway (mrem /yr) per(pCi/m3) i fluclide Bone Liver Total Thyroid Kidney Lung GI-LLI l Body ) 11-3 ND 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 Be-7 4.27E+02 9.68E+02 4.70E+02 ND ND 4.21 E+04 5.35E+03 l Cr-51 ND ND 1.00 E+02 5.95 E+0! 2.28E+01 1.44E+04 3.32E+03 Mn-54 ND 3.96E+04 6.30E+03 ND 9.84E+03 1.40E+06 7.74 E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 ND ND 7.21 E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 ND ND 1.02E+06 1.88E+05 Co-57 ND 6.92E+02 6.71 E+02 ND ND 3.70E+05 3.14E+04 Co-58 ND 1.58E+03 2.07E+03 ND ND 9.28E+05 1.06E+05 i Co-60 ND 1.15 E+04 1.48E+04 ND ND 5.97E+06 2.85E+05 Zn-65 3.24E+04 1.03 E+05 4.66E+04 ND 6.90E+04 8.64E+05 5.34E+04 Rb-86 ND 1.35 E+05 5.90E+04 ND ND ND 1.66E+04 Sr-89 3.04E+05 ND 8.72 E+03 ND ND 1.40E+06 3.50E+05 Sr-90 9.92E+07 ND 6.10E+06 ND ND 9.60E+06 7.22E+05 Y-90 2.09E+03 ND 5.61 E+01 ND ND 1.70E+05 5.06E+05 ' Y-91 4.62E+05 ND 1.24 E+04 ND ND' l.70E+06 3.85E+05 I Zr-95 1.07E+05 3.44E+04 2.33 E+04 ND 5.42E+04 1.77E+06 1.50E+05 I Nb-95 1.41E+04 7.82E+03 4.21 E+03 ND 7.74E+03 5.05E+05 1.04E+05 Ru-103 1.53 E+03 ND 6.58E402 ND 5.83E+03 5.05 E+05 1.10E+05 Ru-106 6.91 E+04 ND 8.72E+03 ND 1.34 E+05 9.36E+06 9.12E+05 Ag 110m 1.08E+04 1.00E+04 5.94 E+03 ND 1.97E+04 4.63 E+06 3.02E+05 ! Cd-109 ND 3.67E+05 1.31E+04 ND 3.57E+05 6.83E+05 5.82E+04 ' Sn-ll3 5.72E+04 2.18E+03 4.39E+03 1.24E+03 ND 9.44 E+05 1.18E F05 Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55 E+01 ND 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 ND 1.74E+06 1.01E+05 Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44 E+03 3.66E+04 1.16E+06 3.83 E+05 1-130 4.58E+03 1.34 E+04 5.28E+03 1.14 E+06 2.09E+04 ND 7.69E+03 1 131 2.52E+04 3.58E+04 2.05 E+04 1.19E+07 6.13 E+04 ND 6.28 E+03 c-33
APA-ZZ-01003 Rev. 9 l l TABLE 3.4 ADULT PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES i Inhalation Pathway (mrem /yr) per( Ci/m3) N uc_1.id_.e Bone Liver Total Thyroid Kidney lau.ng GI-LLI Body 1-132 1.16E+03 3.26E+03 1.16E+03 1.14 E+05 5.18E+03 ND 4.06E+02 1-133 8.64 E+03 1.48 E+04 4.52E+03 2.15E+06 2.58E+0i ND 8.88E+03 l-134 6.44E+02 1.73 E+03 6. I 5 E+02 2.98E+04 2.75E+93 ND 1.01 E +00 1-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.llE+04 ND 5.25E+03 Cs-134 3.73 E+05 8.48E+05 7.28E+05 ND 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 ND 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.2 ] E+05 4.28E+05 ND 2.22 E+05 7.52E+04 8.40E+03 Ba-140 3.90E+04 4.90E+01 2.57E+03 ND 1.67E+01 1.27E+06 2.18E+05 La-140 3.44E+02 1.74E+02 4.58E+01 ND ND 1.36E+05 4.58E+05 Ce-141 1.99E+04 1.35E+04 1.53E+03 ND 6.26E+03 3.62E+05 1.20E+05 i Cc-144 3.43 E+06 1.43E+06 1.84 E+05 ND 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64Ev02 ND 2.16E+03 2.81 E+05 2.00E+05 Pr-144 3.01 E-02 1.25 E-02 1.53 E-03 ND 7.0$ E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.10E+03 3.65E+02 ND 3.56E+03 2.21 E+05 1.73 E+05 Eu-154 5.92E+06 7.28E+05 5.18E+05 ND 3.49E+06 4.67E+06 2.72E+05 Hf-181 1.41E+04 6.82 E+04 6.32E+03 ND 1.48E+04 6.85E+05 1.39E+05 l 34
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway 2 (m mrem /yr)per( Ci/sec) Nuclide Bone Liver Total Thyroid Kidney n Lu._ng GI-LLI Body H-3 ND 3.25 E+02 3.25E+02 3.25E+02 3.25 E+02 3.25E+02 3.25 E+02 Be-7 4.57E+03 1.04E+04 5.07E+03 ND 1.10E+04 ND 1.81E+06 Cr-51 ND ND 7.04 E+03 4.2 ] E+03 1.55E+03 9.34 E+03 1.77E+06 Mn-54 ND 9.17E+06 1.75 E+06 ND 2.73E+06 ND 2.81E+07 Fe-55 2.93E+08 2.02 E+08 4.72E+07 ND ND 1.13 E+08 1.16E+08 I Fe 59 2.65E+08 6.24 E+08 2.39E+08 ND ND 1.74E+08 2.08E+09 Co-57 ND 5.63E+06 9.36E+06 ND ND ND 1.43E+08 Co-58 ND 1.82E+07 4.08E+07 ND ND ND 3.69E+08 Co-60 ND 7.51 E+07 1.66E+08 ND ND ND 1.41E+09 Zn-65 3.56E+08 1.13E+09 5.llE+08 ND 7.57E+08 ND 7.13E+08 Rb-86 ND 4.87E+08 2.27E+08 ND ND ND 9.60E+07 l Sr-89 3.01 E+08 ND 8.65 E+06 ND ND ND 4.83E+07 Sr-90 1.24E+ 10 ND 3.05 E+09 ND ND ND 3.59E+08 Y-90 1.21E+05 ND 3.24E+03 ND ND ND 1.28E+09 Y 91 1.13 E+06 ND 3.02E+04 ND ND ND 6.23E+08 Zr-95 1.87E+06 6.00E+05 4.06E+05 ND 9.42 E+05 ND 1.90E+09 Nb-95 3.15 E+06 1.75E+06 9.43E+05 ND 1.73E+06 ND 1.06E+10 Ru-103 1.05E+08 ND 4.53 E+07 ND 4.0 l E+08 ND 1.23 E+ 10 Ru-106 2.80E+09 ND 3.54E+08 ND 5.40E+09 ND 1.81E+11 Ag-110m 6.6&E+06 6.18E+06 3.67E+06 ND 1.21E+07 ND 2.52E+09 Cd409 ND 1.59E+06 5.55E+04 ND 1.52E+06 ND 1.60E+07 Sn-ll3 1.37E+09 3.88E+07 7.86E+07 2.22E+07 ND ND 4.09E+09 Sb-124 1.98E+07 3.74 E+05 7.84 E+06 4.79E+04 ND 1.54 E+07 5.61 E+08 Sb 125 1.91E+07 2.13E+05 4.54E+06 1.94E+04 ND 1.47E+07 2.10E+08 Te-127m 1.IlE+09 3.98E+08 1.36E+08 2.85E+08 4.53E+09 ND 3.74E+09 Te-129m 1.13E409 4.23 E+08 1.79E+08 3.89E+08 4.73 E+09 ND 5.71 E+09 l-130 2.12E-06 6.27E-06 2.47E-06 5.3 ] E-04 9.78E-06 ND 5.40E-06 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64 E+07 ND 4.06E+06 35
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTIIER TIIAN NOBLE GASES Meat Pathway 2 (m mrem /yr) per( Ci/sec) Nuclide Hone Liver Total Thyroid Kidney Lung GI-LLI Bj_.y d 1-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 1-133 3.67E- 01 6.39E-01 1.95E-01 9.38E+01 1.1 I E+00 ND 5.74E-01 1-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 1-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 Cs-134 6.57E+08 1.56E+09 1.28E+09 ND 5.06E+08 1.68E+08 2.74 E+07 Cs-136 1.20E+07 4.76E+07 3.42E+07 ND 2.65E+07 3.63E+06 5.40E+06 Cs-137 8.71 E +08 1.19E+09 7.81 E+08 ND 4.04E+08 1.34E+08 2.31 E+07 Ba-140 2.87E+07 3.61 E+04 1.88E+06 ND 1.23 E+04 2.07E+04 5.91 E+07 La-140 2.21 E+02 1.llE+02 2.94E+0 ! ND ND ND 8.18E+06 Ce-141 1.40E+04 9.49E+03 1.08E+03 ND 4.41 E+03 ND 3.63 E+07 Cc-144 1.46E+06 6.09E+05 7.82E+04 ND 3.61 E+05 ND 4.92E+08 Pr-143 2.10E+04 8.40E+03 1.04 E+03 ND 4.85E+03 ND 9.18E+07 Pr-144 3.52E+02 1.46E+02 1.79E+01 ND 8.24E+01 ND 5.06E-05 Nd-147 7.07E+03 8.17E+03 4.89E+02 ND 4.77E+03 ND 3.92E+07 Eu-154 8.02E+06 9.86E+05 7.01E+05 ND 4.72E+06 ND 7.14 E+08 Hf-181 3.0l E+06 1.46E+07 1.35E+06 ND 3.14E+06 ND 1.66E+10 l 36
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATIIWAY DOSE FACTORS (R i ) FOR RADIONUCLIDES OTIIER TIIAN NOHLE GASES Grass-Cow-Milk Pathway I 2 (m mrem /yr) per (pCi/sec) Nuclide Bone Liver Total Thyroid Kidney Lunf, GI-LLI Body
}{-3 ND 7.63 E+02 7.63 E+ 02 7.63 E+02 7.63E+02 7.63 E+02 7.63 E+02 Be-7 1.63 E+03 3.72 E+03 1.8tE+03 ND 3.93E+03 ND 6.45 E+05 Cr-51 ND ND 2.86E+04 1.7]E+04 6.30E+03 3.79E+04 7.19E+06 Mn-54 ND 8.42E+06 1.61E+06 ND 2.50E+06 ND 2.58E+07 Fe-55 2.51 E+07 1.74E+07 4.05 E+06 ND ND 9.68 E+06 9.96E+06 Fe-59 2.97E+07 6.98E+07 2.68E+07 ND ND 1.95E+07 2.33E+08 Co-57 ND 1.28 E+06 2.13E+06 ND ND ND 3.25E+07 Co-58 ND 4.72 E+06 1.06E+07 ND ND ND 9.56E+07 Co-60 ND 1.64 E+07 3.62E+07 ND ND ND 3.08E+08 Zn-65 1.37E+09 4.37E+09 1.97E+09 ND 2.92 E+09 ND 2.75E+09 Rb-86 ND 2.60E+09 1.2]E+09 ND ND ND 5.12E+08 Sr-89 1.45E+09 ND 4.17E+07 ND ND ND 2.33E+08 Sr-90 4.68 E+ 10 ND 1.15E+10 ND ND ND 1.35E+09 Y-90 7.43 E+02 ND 1.99E+01 ND ND ND 7.87E+06 Y-91 8.59E+03 ND 2.30E+02 ND ND ND 4.73 E+06 Zr-95 9.44E+02 3.03 E+02 2.05 E+02 ND 4.75E+02 ND 9.59E+05 Nb-95 9.65 E+04 5.37E+04 2.89E+04 ND 5.31 E+04 ND 3.26E+08 Ru 103 1.02E+03 ND 4.39E+02 ND 3.89E+03 ND 1.19E+05 Ru-106 2.04E+04 ND 2.58E+03 ND 3.94E+04 ND 1.32E+06 Ag l10m 5.82E+07 5.39E+07 3.20E+07 ND 1.06E+08 ND 2.20E+ 10 Cd-109 ND 1.13E+06 3.95 E+04 ND 1.08E+06 ND 1.14E+07 Sn-ll3 1.34E+08 3.81E+06 7.73E+06 2.18E+06 ND ND 4.02E+08 Sb-124 2.57E+07 4.86E+05 1.02E+07 6.24 E+04 ND 2.00E+07 7.31 E+08 Sb-125 2.04 E+07 2.28E+05 4.87E+06 2.08E+04 ND 1.58E+07 2.25 E+08 Te 127m 4.58E+07 1.64 E+07 5.58E+06 1.17E+07 1.86E+08 ND 1.54 E+ 08 Te 129m 6.02E+07 2.25E+07 9.53 E+06 2.07E+07 2.5 ] E+08 ND 3.03E+08 1-130 4.21 E+05 1.24 E+06 4.91 E+05 1.05E+08 1.94E+06 ND 1.07E+06 1-131 2.97E+08 4.25E+08 2.43 E+08 1.39E+11 7.28E+08 ND 1.12E+08 37
y APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATIIWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTIIER TIIAN NOHLE G ASES 4 Grass-Cow-Milk Pathway 2 (m mrem /yr)per(pCi/sec) Nyellde Bone Liver Total Thyroid Kidney Lung GI-LLI Body I-132 1.65 E-01 4.42E-01 1.55E-01 1.55E+01 7.04E 01 ND 8.30E-02 1 133 3.88E+06 6.75 E+06 2.06E+06 9.92E+08 1.18E+07 ND 6.07E+06 1-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 I 135 1.29E+04 3.37E+04 1.25E+04 2.23E+06 5.41E+04 ND 3.81 E+04 Cs-134 5.65E+09 1.35E+10 1.10E+ 10 ND 4.35 E+09 1.45E+09 2.35 E+08 Cs-136 2.63 E+08 1.04 E+09 7.48E+08 ND 5.79E+08 7.93 E+07 1.18E+08 Cs-137 7.38E+09 1.0lE+10 6.61 E+09 ND 3.43E+09 1.14 E+09 1.95 E+08 Ba-140 2.69E+07 3.38E+04 1.76E+06 ND 1.15E+04 1.93 E+04 5.54 E+07 La-140 4.14 E+0! 2.09E+01 5.5]E+00 ND ND ND 1.53 E+06 Cc-141 4.85E+03 3.28E+03 3.72E+02 ND 1.52E+03 ND 1.25E+07 Cc-144 3.58E+05 1.50E+05 1.92E+04 ND 8.87E+04 ND 1.21E+08 Pr-143 1.58E+02 6.34 E+01 7.83 E+00 ND 3.66E+01 ND 6.92 E+05 Pr-144 1.10E+00 4.58 E-01 5.61E-02 ND 2.58E-01 ND 1.59E-07 Nd-147 9.42E+0 ! 1.09E+02 6.51 E+00 ND 6.36E+01 ND 5.23E+05 Eu-154 2.37E+04 2.9 I E+03 2.07E+03 ND 1.39E+04 ND 2.1 I E+06 Hf-181 1.42E+02 6.92E+02 6.41 E+01 ND 1.49E+02 ND 7.87E+05 38
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATIIWAY DOSE FACTORS (R i ) FOR RADIONUCLIDES
, OTIIER TIIAN NOBLE G ASES Grass-Goat-Milk Pathway 2
(m mrem /yr)per(pCi/sec) Nuclide jlgne Jiver Total Thyroid Kidney Lung GI-LLI Body 11-3 ND 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 Be-7 1.96E+02 4.47E+02 2.17E+02 ND 4.72E+02 ND 7.74E+04 Cr-51 ND ND 3.43E+03 2.0$E403 7.56E+02 4.56E+03 8.63 E+05 Mn-54 ND 1.0!E+06 1.93 E+05 ND 3.0l E+05 ND 3.10E+06 Fe-55 3.27E+05 2.26E+05 5.26E+04 ND ND 1.26E+05 1.30E+05 Fe-59 3.87E+05 9.08E+05 3.48 E+05 ND ND 2.54E+05 3.03 E+06 Co-57 ND 1.54E+05 2.56E+05 ND ND ND 3.90E+06 Co-58 ND 5.66E+05 1.27E+06 ND ND ND 1.15E+07 Co-60 ND 1.97E+06 4.35E+06 ND ND ND 3.70E+07 Zn-65 1.65E+08 5.24E+08 2.37E+08 ND 3.51 E+08 ND 3.30E+08 Rb-86 ND 3.12E+08 1.45E+08 ND ND ND 6.15 E+07 Sr-89 3.05E+09 ND 8.75E+07 ND ND ND 4.89E+08 Sr-90 9.84E+10 ND 2.4 ] E+ 10 ND ND ND 2.84E+09 Y-90 8.92 E+0! ND 2.39E+00 ND ND ND 9.46E+05 Y-91 1.03 E+03 ND 2.76E+01 ND ND ND 5.68E+05 Zr-95 1.13 E+02 3.63 E+01 2.46E+0 ! ND 5.70E+01 ND 1.15E+05 Nb-95 1.16E+04 6.45E+03 3.47E+03 ND 6.37E+03 ND 3.91 E+07 Ru 103 1.22E+02 ND 5.27E+0! ND 4.67E+02 ND 1.43E+04 Ru-106 2.45 E+03 ND 3.10E+02 ND 4.73 E+03 ND 1.59E+05 Ag 110m 6.99E+06 6.47E+06 3.84 E+06 ND 1.27E+07 ND 2.64 E+09 Cd-109 ND 1.36E+05 4.74E+03 ND 1.30E+05 ND 1.37E+06 Sn-ll3 1.61E+07 4.58E+05 9.28 E+05 2.62E+05 ND ND 4.83 E+07 Sb-124 3.09E+06 5.84E+04 1.23 E+06 7.50E403 ND 2.41 E+06 8.78E+07 Sb-125 2.46E+06 2.74E+04 5.84E+05 2.50E+03 ND 1.89E+06 2.70E+07 Te 127m 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23 E+07 ND 1.84E+07 Te-129m 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 ND 3.64E+07 1-130 5.05 E+05 1.49E+06 5.88E+05 1.26E+08 2.32 F+06 ND 1.28E+06 1-131 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.72 E+08 ND 1.34 E+08 1 132 1.98E-01 5.29E-01 1.85E-01 1.85E+01 8.43 E-01 ND 9.95E-02 39
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway 2 (m mrem /yr)per(pCi/sec) Muclide Bone Liver Total Thyroid Kidney Lung GI-LLI Body 1-133 4.65 E+06 8.09E+06 2.47E406 1.19E+09 1.41E+07 ND 7.27E+06 1-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND 0.00E+00 1-135 1.54 E+04 4.04 E+04 1.49E+04 2.67E+06 6.48E+04 ND 4.57E+04 Cs-134 1.70E+10 4.04E+10 3.30E+10 ND 1.3lE+10 4.34 E+09 7.07E+08 Cs-136 7.91 E+08 3.12E+09 2.25E+09 ND 1.74E+09 2.38E+08 3.55E+08 Cs-137 2.22E+10 3.03E+ 10 1.99E+10 ND 1.03E+10 3.42E+09 5.87E+08 Ba-140 3.23 E+06 4.06E+03 2.12E+05 ND 1.38 E+03 2.32E+03 6.65E+06 La-140 4.97E+00 2.51 E+00 6.62E-01 ND ND ND 1.84 E+05 Ce-141 5.82E+02 3.94 E+02 4.46E+01 ND 1.83 E+02 ND 1.50E+06 Cc-144 4.30E+04 1.80E+04 2.31 E+03 ND 1.07E+04 ND 1.45E+07 Pr-143 1.90E+01 7.61 E+00 9.40E-01 ND 4.39E+00 ND 8.31 E+04 Pr-144 1.33 E-01 5.50E-02 6.74 E-03 ND 3.10E-02 ND 1.91 E-08 Nd-147 1.13E+01 1.31 E+01 7.82E-01 ND 7.64 E+00 ND 6.28E+04 Eu-154 2.84E+03 3.49E402 2.49E+02 ND 1.67E+03 ND 2.53E+05 Hf 181 1.7lE+01 8.31 E+01 7.70E+00 ND 1.79E+01 ND 9.46E+04 40 l
l APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway (m2 mrcm/yr)per( Ci/sec) Nuclide Bone Liver Total Thyroid Kidny Lung Body GI-QI 11-3 ND 2.26E+03 2.26E+03 2.26E+03 2.26E+ 03 2.26E+03 2.26E+03 Be-7 9.24E+04 2.l l E+05 ND 1.03 E+ 05 2.23E+05 ND 3.66E+07 Cr-51 ND ND 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 ND 3.13E+08 5.97E+07 ND 9.31 E+07 ND 9.59E+08 Fe 55 2.10E+08 1.45 E+08 3.38E+07 ND ND 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.14E+08 ND ND 8.28 E+07 9.88E+08 Co-57 ND 1.17E+07 1.95E+07 ND ND ND 2.97E+08 Co-58 ND 3.07E+07 6.89E+07 ND ND ND 6.23 E+08 Co-60 ND 1.67E+08 3.69E+08 ND ND ND 3.14 E+09 Zn-65 3.17E+08 1.0lE+09 4.56E+08 ND 6.75E+08 ND 6.36E+08 Rb-86 ND 2.19E+08 1.02E+08 ND ND ND 4.33 E+07 Sr-89 9.97E+09 ND 2.86E+08 ND ND ND 1.60E+09 Sr-90 6.0S E+ 11 ND 1.48E+11 ND ND ND 1.75 E+10 Y-90 7.67E+05 ND 2.06E+04 ND ND ND 8.14 E+09 Y-91 5.llEdO6 ND 1.37E+05 ND ND ND 2.81 E+09 Zr-95 1.17E+06 3.77E+05 2.55E+05 ND 5.9] E+05 ND 1.19E+09 Nb-95 2.40E+05 1.34 E+05 7.19E+04 ND 1.32E+05 ND 8.l l E+08 Ru-103 4.77E+06 ND 2.06E+06 ND 1.82E+07 ND 5.57E+08 Ru 106 1.93 E+08 ND 2.44E+07 ND 3.72E+08 ND 1.25E+10 AgIl0m 1.05E+07 9.75 E+06 5.79E+06 ND 1.92E+07 ND 3.98E+09 Cd-109 0.00E+00 8.36E+ 07 2.92E+06 ND 8.00E+07 ND 8.43 E+08 Sn-ll3 4.16E+08 1.18E+07 2.40E+07 6.75 E+06 ND ND 1.25E+09 Sb-124 1.04E+08 1.96E+06 4. l lE+07 2.5 ] E+05 ND 8.07E+07 2.94 E+09 Sb-125 1.37E+08 1.53 E+06 3.25E+07 1.39E+05 ND 1.05E+08 1.50E+09 Te-127m 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 ND 1.17E+09 Ts-129m 2.5 l E+08 9.38E+07 3.98E+07 8.64E+07 1.05E+09 ND 1.27E+09 l-130 3.93 E+05 1.16E+06 4.57E+05 9.81 E+07 1.81E+06 ND 9.97E+05 1 131 8.08E+07 1.16E+ 08 6.62E+07 3.79E+ 10 1.98E+08 ND 3.05 E+07 41 l . . .
APA-ZZ-01003 Rev. 9 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (R,) FOR RADIONUCLIDES OTIIER TIIAN NOBLE GASES Vegetation Pathway 2 (m mrem /yr) per(pCi/sec) Nuclide Bone Liver Total Thyrold Kidney Lung GI-LLI Body 1132 5.77E+0! l .54E+02 5.40E+01 5.40E+03 2.46E+02 ND 2.90E+01 1-133 2.09E+ 06 3.63 E+06 1.llE+06 5.33E+08 6.33E+06 ND 3.26E+06 I-134 9.69E-05 2.63 E-04 9.42E-05 4.56E-03 4.19E-04 ND 2.30E-07 l-135 3.90E+04 1.02E+05 3.77E+04 6.74 E+06 1.64 E+05 ND 1.15E+05 Cs 134 4.67E+09 1.llE+10 9.08E+09 ND 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.27E+07 1.69E+08 1.21E+08 ND 9.38E+07 1.29E+07 1.91E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 ND 2.95E+09 9.81 E+0d 1.68E+08 Ba-140 1.29E+08 1.61E+05 8.42E+06 ND 5.49E+04 9.24 E+04 2.65E+08 La-140 1.58E+04 7.98E+03 2.llE+03 ND ND ND 5.86E+08 Cc-141 1.97E+05 1.33 E+05 1.51E+04 ND 6.19E+04 ND 5.10E+08 Ce-144 3.29E+07 1.38 E+07 1.77E+06 ND 8.16E+06 ND 1.llE+10 Pr-143 6.26E+04 2.51 E+04 3.10E+03 ND 1.45E+04 ND 2.74 E+08 Pr-144 2.03 E+03 8.43 E+02 1.03E+02 ND 4.75E+02 ND 2.92E-04 Nd-147 3.33 E+04 3.85E+04 2.31 E+03 ND 2.25E+04 ND 1.85E+08 Eu-154 4.85E+07 5.97E+06 4.25E+06 ND 2.86E+07 ND 4.32E+09 Hf-181 1.40E+05 6.82E+05 6.32 E+04 ND 1.47E+05 ND 7.76E+08 42
m 3 APA-ZZ-01003 Rev. 9 4, DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 1
- 4.1 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) . Dose to the total body and internal organs due to gamma ray exposure from submersion in a cloud of j radioactive noble gases, ground plane exposure, and direct radiation from the Unit , onsite storage of low level radioactive waste, and outside storage tanks; ]' b). Dose to skin due to beta radiation from submersion in a could of radioactive noble gases, and ground plane exposure; c) - Thyroid dose due ' to inhalation and ingestion of radioiodines; an'd i d) Organ dose due to inh 9ation 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. I 1.12.5) { The dose from gaseous effluents is considered to be the summation of the dose at the individuars residence and the dose to the individual from activities within the SITE BOUNDARY. Smce 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. I1.12.3). There are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant. 4.1.1- Identification of the MEMBER OF THE PUBLIC 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. I 1.4 and 11.8.10). Accordingly, it is necessary to characterize this individual with respect to his utilization of areas both within and at or beyond
- the SITE 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 realistic j assumptions (Ref.11.12.3 and i 1.12.4).
- 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 Critical Receptor within the SITE BOUNDARY.
. 4.1.2 . ' Total Dose to the Nea,rgst r Resident The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure, and !
inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, j 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 i gaseous effluents due to activities within the SITE BOUNDARY, 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 ofX/Q. The location of the Nearest Resident in each meteorological sector is determined from the Annual Land
- Use Census conducted in accordance with the Requirements of REC 16.11.4.2.
APA-ZZ-01003 Rev. 9 4.1.3 Total Dose to the Critical Receptor Within the SITE 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. Under 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 immediately surrounding the plant site (refer to Figure 4.1). Much of the residual lands within the SITE BOUNDARY are leased to area farmers by the Department of Conservation to provide income to support management and oevelopment costs. Activities conducted under these leases are primarily comprised of farming (animal feed), grazing, and forestry (Ref. I 1.7.2,11.7.3,11.13, and 11.13.1). Based on the utilization of areas within the SITE BOUNDARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities u ithin the SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The current tenant has estimated that he spends approximately 1100 hours per year working in this area (Ref.11.5.5). Occupancy of areas within the SITE BOUNDARY is assumed to be averaged over a period of one year. Any reevaluation of assumptions should consider only real receptors and real pathways using realistic assumption, and 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). 4.1.3.1 Total Dose to the Farmer from Gaseous Effluents The Total Dose to the farmer from gaseous effluents is calculated for the adult age group using the methodology discussed in Section 3, utilizing concurrent meteorological data at the farmer's residence and historical meteorological data from Table 6.1 for activities within the SITE BOUNDARY. These dispersion parameters were calculated by assuming that the farmer's time i equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of i 100 hours / year factored into their value (Ref. I 1.5.6). The residence of the current tenant is located at a distance of 3830 meters in the SE sector, ne gaseous effluents dose at the farmer's residence is due to plume exposure from Noble Gases and the ground plane, inhalation, and ingestion pathways. For conservatism, it is acceptable to assume that all of the ingestion pathways exist at this location. It is assumed that food ingestion 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. 4.1.3.1.1 Direct Radiation Dose from Outside Storace Tanks ne 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 radiation dose from outside storage tanks to a MEMBER OF THE PUBLIC (Ref. I1.6.14,11.6.15,11.6.16 and i1.6.17). Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures, which is 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. I l.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. I 1.17). The computer program ISOSHLD (Ref. I1.18, Il.19 and i1.20) will normally be utilized to perform this c.Jeulation. ! 44 1
APA-ZZ-01003 Rev. 9 - ! -4.1.3.1.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined 1 to be 7E 2 iarads/ calendar year, based on a point source of primary coolant N-16 in the steam generators. f This source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the containment dome and for distance attenuation. No credit was allowed for shielding by other structures or components within the Containment Building.The number of gammas per i' second was generated and then converted to a 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 is based 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 obscured by significant plant structures (Ref. I1.14.3).
The maximum direct radiation dose from the Unit to the farmer is thus approximately 9E 3 mrads per year, assuming a maximum occupancy of 1100 hours per year. 4.1.3.1.3 Direct Radiation Dose From On Site Storace Of Low Level Radioactive Waste The on-site storage area for radioactive wastes is located Plant Southwest of the radwaste building and consists of a concrete pad enclosed by a fence. 'Ihe storage area is bounded on two sides by the radwaste building. The area is also partially bounded on a third side by the Discharge monitoring tanks dike system. 4 The radioactive wastes are stored in this area using high integrity containers (HIC) inside Onsite Storage Containers (OSC) and LSA type storage containers. The HIC has the highest potential for containing significant amounts of radioactive material, and constitutes the only potentially significant source of direct radiation from on-site radioactive waste storage. Direct radiation dose from the HICs to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures. The HICs typically are right circular cylinders approximately 1.7 meters in diameter and 1.8 meters in height. The HICs are stored inside Ot'Cs which typically are constructed of concrete with additional shielding as necessary to minimize external doses. The individual parameters (e.g., dimensions, shielding material, etc.) for each OSC will be accounted for in the calculations. 1 i The direct radiation dose from the On-Site Storage area is the summation of the individual calcui9ed HIC doses based on the HIC isotopic contents and the OSC design parameters, considering buildup, attenuation, and shielding. Appropriate methodology for calculating the dose rate is given in Safety Analysis Calculations ZZ-293 and ZZ 310. The computer program MICROSHIELD (Ref. I 1.24) will normally be utilized to perform this calculation. 1 J i 1 E 0 " lI ll At , lll l
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APA-ZZ-01003 Rev. 9
- 5. RADIOLOGICAL ENVIRONMENTAL MONITORING a
5.1 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 exposure 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, hazardous conditions, or other legitimate reasons. EfTorts are made to obtain all required samples within the required time frame. ' Any deviation (s) in sampling frequency or location is documented in the Annual Radiological Environmental Operating Report.
' Sampling, reporting, and analytical requirements are given in FSAR Tables 16.117,16.118, and 16.119.
Airborne, waterborne, 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 Intercomparison 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. 5.2 ' PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS Thermoluminescence Detectors (TLD's) used in the Er.rironmental 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 Gases (80,160,200 kev), Cs-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. (Ref. I 1.14.10)
- 6. -
DETERMINATION OF ANNUAL AVERAGE AND SHORTTERM ATMOSPHERIC DISPERSION
- PARAMETERS 6.1 i ATMOSPHERIC DISPERSION PARAMETERS
- The values presented in Table 6.1 and Table 6.2 were determined through the analysis of on-site meteorological data collected during the three year period of May 4, !?73 to May 5,1975 and March 16, 1978 to March 16,1979.
- 6.1.1 - Lona-Term Dispersion Estimates The variable trajectory plume segment atmospheric transport model MESODIF-II (NUREG/-CR-0523) and the straight-line Gaussian dispersion model XOQDOQ (NUREG/CR2919) were used for determination of the long-term atmospheric dispersion parameters. A more detailed discussion of the methodology and data utilized to calculate these parameters can be found elsewhere (Ref. I1.6.12).
The Unit Vent and Radwaste Building Vent releases are at elevations of 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 eliminates the possibility of the exit velocity exceeding five times the horizontal wind speed. All gaseous 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). i
E APA-ZZ-01003 Rev. 9 6.1.2 Determination of Lonn-Term Disnersion Estimates for Special Receptor Locations Calculations utilidng *he PUFF model were performed for 22 standard distances to obtain the desired dispersion pmmeters. Dispersion parameters at the SITE BOUNDARY and at special receptor locations were estim. . iy logarithmic interpolation according to (Ref. I 1.6.13): X=X,(d/d,)* .(6.1) l Where: B =In (X2 /X,)/In (d2/di ). X3 , X2= Atmospheric dispersion parameters at distance d 3and d ,2 respectively, from the source. The distances d3and d 2were selected such that they satisfy the relationship. - d<d<d2 i 6.l.3 Short Term Dispersion Estimates Airborne releases are classified as short term if they are less than or equal to 500 hours during a calendar year and not more than 150 hours in any quarter. Short term dispersion estimates are determined by - multiplying the appropri; te long term dispersion estimate by a correction factor (Ref. I 1.9.1 and i 1.15.1): F = (T, / T,)* (6.2) Where: Ts The total number of hours of the short term release.
=
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 6.3. Short term dispersion estimates are not applicable to short term releases which are 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. I 1.8.1). 6.l.3.1 The Determination of the Slooe Factor (S) The general approach employed by subroutine PURGE of XOQDOQ (Ref.11.15.1) was utilized to - produce values of the slope of the (X/Q) curves for both the Radwaste Building Vent and the Unit Vent. However, instead of using approximation procedures to produce the 15 percentile (X/Q) values, the 15 percentile (X/Q) value for each release and at each location was determined by ranking all the l-hour ((X/Q)t) values for that release and at that location in descending order. The (X/Q) 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. The intermittent release (X/Q) curve was constructed using the calculated 15 percentile (X/Q) aad its corresponding annual average (X/Q)a. 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) values for intermittent releases, ranging in duration from one hour to 8760 hours. The slope (S) of the curve is expressed as:
-log ((X/o), /(X/0) )
S= (6.3) log (T, / T,) or
-(log (X / o), - log (x / o),)
S= (6.4) log T, - log T, r_ _ - - _ _ . - . _ _ _ _ _ - _ _ _ APA-ZZ-01003 Rev. 9
' 6.1.4 ' Atmospheric Dispersion Parameters for Farming Areas within the SITE BOUNDARY The dispersion parameters for farming areas within the SITE BOUNDARY are intended for a narrow
. scope application: That of calculating the dose to the current farmer from gaseous effluents while he conducts farming activities within the SITE BOUNDARY.
For the purpose of these calculations, it was assumed that all of the farmer's time, approximately 1100 hours 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 dispersion parameters which are presented in Tables 6.1 and 6.2. These dispersion parameters therefore represent the distributed activities of the 7 amer within the SITE BOUNDARY and his estimated occupancy period. 6.2 ANNUAL METEOROLOGICAL DATA PROCESSING The annual atmospheric dispersion parameters utilized in the calculation of doses for demonstration of compliance with the numerical dose objectives of 10 CFR 50, Appendix I, are determined using computer codes and models consistent with XOQDOQ (Ref. I 1.15). These codes have been validated and verified by a qualified meteorologist prior to implementation. Multiple sensors are utilized to ensure 90% valid data recovery for the wind speed, wind direction, and ambient air temperature parameters as required by Regulatory Guide 1.23. The selection hierarchy is presented in Table 6.5. i I. I
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c I S X ED CE ( es 9 9 2 6 5 2 1 2 f. R e d w R DN ( e s E U ) 1 icr P 6 e S ( x I n e D io t b e a C I u q d lu R ) E o 1 E T Q 3 m 6- 7- 7- 7-n h s 6 H N / X /c E 0 2 E E 5 E i d n o E 1 P e e E V ( s 1 6 2 2 t n i t u L S e t n a B O T I s e r id e c e 3
)
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, l c s )
=
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/
N R C o f ( B E E N N A e R d t d 5 t n S S A e H F U s S e m v 0 e c G F i r = a m d u e ) j I o n m s d C d H fr a o s a e ( A e L f r e r r t s r 6 r e e e a 9 d a w t e h n 9 e s s u ig
) e e v y e
)
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/AP N Y X ED CE 3 1
9 7 0 3 2 9 g O R DN in I S D U in m R Y r e E T ) 6 t e P I 5 d S L I 1 n I e D C I h C A 6- 7- 7- 7-f. e w I F Q R d e
/ E E E E ( s R N X 3 9 0 9 )
1 i c 2 E O 1 7 3 2 6 r e 6 H C ( n x e E P E o e L S D i t b O a B u ld A M Y E q u o T T R n h A D E) i s n 1 5 N CS d e o E U NR E 0 2 0 t n it u A G A AE T 0 4 3 / e s t n a A L T S 2 2 0 3 8 3 N e r d e c e
)
3 R D I D( M p y i s e m 5 E N g r e r 1 V t t I A lo s e x f. A o r E e T d a R L o e n ( A N ht n e io s r U E e ht t a e N V R m e f o ic t e m E O ht lp N T T W W E A g n p a 6 A S C N N S
/
N n io e 9 E N N t a p 9 T A S is u, c o o 1 S 4 c = E W 8
- 1 l
e s ) ) V H D 3 2 8 3
- ht w o
3 5 ( G A le 2 t a r r 1 g I R b s u e t a n I in H T a s n l b a is x a f. e l i d e e r R u R T o o B A C R t f ( t e d d 5 n
) S s A e e 0 e
) d ) n F U S v c a ( c F m i r = a
( ) ( i )e m d u e j
)
b Y ( c e c ih( t o n m s d C
) d
( R n f r a o a s ( A N A e c e W )(c e L f r e e r e r t s D n id s y r 6 r e e O e s a r ea a 9 d a w t e h I T N d e rd n 9 e v s s m ig U is R An u e 1 y e a A O e s g v i r e a u r l f C B R 're n o i g m o d w l a a f O t s iB s r s ht v P o L E T e r m r me r t e u f a e u a p e s e p h t a a e a ig Fai S l t l I S e F a a a l h h e N V D V lA T S i l g l in a d i c l t
) ) ) )
i r
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APA-ZZ-01003 Rev. 9 TABLE 6.3 SHORT DISPERSION PARAMETERS (s)(c) Slope Factor (s) Location (b) Sector Distance Unit Vent Radwaste Building Vent Site Boundary S 1300 .328 .320 Nearest Residence (d) NNW 3042 .264 .268 (a) Reference 11.5.3 (b) Data from 1996 Land Use Census (c) Recirculation Factor = 1.0 (d) All pathways are assumed to exist at the location of the nearest resident. 52
ijl ji{lI !llll il'IIi 1 . n 3 o t t t 0 0 i t a y r y r ny e r n e n e c a d a d d 1 o d A isd i s is 0- L n m e n e e e u Ru o R R Z in B o m Z9 l B sBu t s e t s
- l e e e A ev.
o r t iS t miet a r e r a t iS e P n o NoS N N AR C 2 1 1 3 3 3 S c 2 2 2. 2 2 2 R R e 1 1 1 1 1 1 1 1 1 1 E 6 6 66 1 6 1 6 T 1 1 1 1 1 1 E M A R A P p N u o r OI G S e g R A A A d l A d l E e / N
/ i h /
i P i n N C N h C S l 4 I lor D t n 6 o E C I C L R 3 B E 5 A I I ) T P I S 1 1 O 1 I M f. T r d e d e d R e A t e e l t e )e pf l t e )e t e e) ( pf F m eli el i lpfi e Q
/
O a r dnlf- dnlf- el D a ua ua d
/ f- f N P /h de
/h de dl a e Q Q o
O n y y y h / d I o ya ya a y D D
/
a i s ad ad c a e T r e c6 e c6 e ed t s A p s d, 2 2 d, 22 d
,8 i n
C I i D Q( Q( Q(
/
d e
/ / x s u
L x x P is P d A t e e lp e d
/
d r n e y iA io a a n t s y c y i is a e a ,m ,S k o p d, s s n w w am a& io e ht Q ht GaG G y t D a / a e a p x, P l e.. e lb& bled o a a o n 3 s o oB h n l H o Ni r Nl a I P it s r D A t o d n e g o a T u n F t e o r I B G 1
APA-ZZ-01003 . Rev.8 TABLE 6.5 METEOROLOGICAL DATA SELECTION HIEARCHY Parameter Primary First Second Third Alternate Alternate Alternate Wind Speed 10m Pri 10m Sec 60m Pri 90m Pri Wind Direction 10m Pri 10m Sec 60m Pri 90m Pri Air Temperature 10m Pri 10m Sec Wind Variability 10m Pri 10m Sec 60m Pri 90m Pri Temp Different - 60-10m Pri 90-10m Pri 90-60 Pri Dew Point 10m Pri Precipitation im Pri (a) Pri indicates primary tower (b) Sec indicates secondary tower h-
3 0 0 1 0-Z Z 8 A v. P e AR - n ey ey e y eyr o r r r n yen c a n c a n c a i t ye t t nd ye t t yn t c a a e n nd e n ye nd nd c r ad r ad d r ad d u r ad e d n u r e ad d e nu o d is d is is u d i di L ne ne eBo ne ieBo ne iseBo neiss s s d is eB o g n uR uR R o o e uR R o e o uR R uR e o t R e t t
'srSi i
l Bs e Bs e 's t i Bs te s it Bs t st i Bs e t _ l o e r ter rS e e r 'r e S e re 'r e S e r _ r t i a ia e t ia e a e ia e e _ S e S e md t t S e md S e mi S e md _ t i - n N N as ri N as ri N rf a N ri a s o F nI F nI F rI F nI C t r o p e s R e . e l u - s a t t t t t a n n enl ac ren nl a t n t nl t n t nl l e V e r e r r e r c e r er ac e r e r ac _ e n r r r ir r ri r r ri r r ri r R i o u c u c u o cu ct u ct o u c u ct o c u u ct o t s n n ns n ns n ns n ns . n e r e o o oH Co i oI i o oH Co i oI i m p C C C CI C C CI s . m i D _ E . l a u n gp n n uo . A i l t - l o r A A A ld lt u d l l u - s rG / / / i h d i h d 5 r e t ne N N N C A C A 5 t e og _ 6 6 m CA e a r l b a _ a P ) T n 1 _ o r d e d e 1 i s e t d 1 r t e e t e l e )e e pi f l pf
)e t e) 1 I
p m el el i lpfe i s a r d f- d f- el i f. e D a nl ua nl a d f- R e P /h de
/u h d Q
/
dl a e Q ( i r e n ya y ey ya
/
D yh / Q b i o ad ad ay c a D / D o s s r c6 e c6 e ed f o e d, 8 o m p s d, 22 d, 22 Q( d t i Q( Q( / a e A D / x
/
x x t s f n o i n d o e s i t u a s c e i i l e s d e s o o e D e D s t e A D s o y a lp n y ir D o e w d e a ,A n i i t s o ht a
/
w s a sk ,i s o d e h_ am a S p D P y t a Gm G e n e s a P l bG e a le& b y D io t D o c e e o od e n l a d, s o N&r NoB l a h a n o Q D i l P i n it s
/
x, A a d e t n g 3 a o u n t e T o I 1 1 r r B G o F
APA-ZZ-01003 Rev. 9
- 7. REPORTING REOUIREMENTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (CTSN 2804)
The reporting requirements for the Annual Radiological Environmental Operating Report have been l relocated to FSAR Section 16.11.5.1. I 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (CTSN 2805) The reporting requirements for the Annual Radioactive Effluent Release Report have been relocated to FSAR Section 16.11.5.2.
h, APA-ZZ-01003 Rev. 9 -
- 8. IMPLEMENTATION OF ODCM METHODOLOGY (CTSN 2791)
The ODCM provides the mathematical relationships used to implement the Radioactive Effluent Controls. For routine effluent release and dose assessment, computer codes are utilized to implement the ODCM methodologies. These codes are evaluated in accordance with the requirements of plant operating procedures to ensure that they produce results consistent with the methodologies presented in the ODCM. Procedures which implement the ODCM methodology are contained in the Plant Operating Manual. I l APA-ZZ-01003 Rev. 9 i
- 9. RADIOACTIVE EFFLUENT CONTROLS (REC)
The Radioactive Effluent Controls have been relocated to FSAR Section 16,11, "Offsite Dose Calculation Manual Radioactive Effluent Controls". The former ODCM REC numbers appear on each of the REC's in the FSAR, and may be used as a cross- reference between the previous and the current numbering system if necessary. I APA-ZZ-01003 Rev. 9 10 ADMINISTRATIVE CONTROLS 10.1 MAJOR CHANGES TO LIOUID AND GASEOUS 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 Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). The discuss!on of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- 3) A detailed description of the equipment, components and process involved and the interfaces with other plant systems;
- 4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;
- 5) . An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general
-- population that differ from those previously estimated in the License application and amendments thereto;
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by the ORC,
- b. Shall become effective upon review and approval by the ORC and in accordance with Technical Specification 6.53.1.
-10.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)(CTSN 2815) 10.2.1 All changes to the ODCM shall be completed pursuant to Technical Specification 6.14 and approved as per APA-ZZ-00101, " Preparation, Review, Approval and Control of Procedures".
10.2.1.1 All changes shall be approved by the ORC prior to implementation. 10.2.2 Cross Disciplinary Review for each revision of the ODCM must include, as a minimum, the Health Physics, Quality Assurance, and Licensing and Fuels Radiological Engineering Departments. 10.2 3 A complete and legible copy of each revision of the ODCM that became effective during the last annual period shall be submitted as a part of, or concurrent with that years Annual Radioactive Effluent Release Report pursuant to Technical Specification 6.14.
/'
m APA-ZZ-01003 Rev,9
- II. REFERENCES I11.1 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402, 11.1.1 Statements of Consideration, Federal Register, Vol. 56, No. 98, Tuesday, May 21,1991, Subpart D, page 23374.
I 1.2 - Title 10 " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S. Government Printing Office, Washington, D.C. 20402. I1.2.1 10 CFR 5036 a (b) 113 Title 40, " Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S. Government Print Office, Washington, D.C. 20402. I1.4- ~ U.S. Nuclear Regulatory Commission, " Technical Specifications Callaway Plant, Unit NO.1", NUREG. 1058 (Rev.1), October 1984. I1.4.1 Section 6.8.1 11.4.2 Section 6.8.4f - 11.5 COMMUNICATIONS { l1.5.1 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. I1.53 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Electric Co.), dated February 9,1984. I 1.5.4 : Reference Deleted l 11.5.5 , Private Communication, H. C Lindeman & B.F. Holderness, August 6,1986 11.5.6 Calculation ZZ-67," Annual Average Atmospheric Dispersion Parameters", April 1989. I 1.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report. I1.6.1 Section 11.5.2.23.1 11.6.2 Section 11.5.2.23.4
-11.6 3 Section 11.5.2.1.2 11.6.4 Section 11.5.2.2 3.2 -11.6.5 Section 11.5.2.233 11.6.6 Section 11.23 3.4 11.6.7 Section 11.23.43 11.6.8 Section 11.5.233.1 .I1.6.9 Section 11.5.233.2 '11.6.10: Section i1.5.23.23 - ' i1.6.11 Section i1.5.23.2.2 11.6.12 Section 23.5 11.6.13 Section 23.5.2.1.2 11.6.14 Section 9.2.6 11.6.15.. Section 9.2.7.2.1 '11.6.16 - Section 63.2.2 APA-ZZ-01003 Rev. 9 ?I1.6.17: Table 11.1-6 .I1.6.18 Deleted 11.6.19 Deleted 11.6.20 ' Deleted '
11.6.21 Deleted -
.I1.6.22 Table 2.3-68 m 11.7 Union Electric Company Callaway Plant Environmental Report, Operating License Stage.
I 1.7.1 ' Table 2.1-19 11.7.2 Section 2.1.2.3 11.7.3 Section 2.1.3.3.4
.11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19.
I 1.8 U.S. Nuclear Regulatory Commission, Preparation of Radiological Efiluent Technical Specification 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
.I1.8.5 Section 5.1.1 11.8.6 . Section 5.1.2 11.8.7 L Section 5.2.1 11.8.8 Section 5.2.1.1 11.8.9 Section 5.3.1 11.8.10 Section 3.8 11.8.11 Section 3.3 11.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, Program For the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG-0324, Washington, D. C. 20555.
11.9.1 Pages 19-20 Subroutine PURGE 11.10 Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Efiluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, U. S. Nuclear Regulatory Commission, Washington, D. D. 20555, July,1977. I1.10.1 Section c.l.b ' i1.10.2 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 Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, October 1977. I1.11.1 Appendix C, Section 3.a 11.11.2 . Appendix E, Table E-15 11.11.3- Appendix C, Section 1 APA-ZZ-01003 Rev. 9 , 1 I1.11.4' Appendix E, Table E-Il l 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.
' i1.12.1 Section I, Page 2 11.12.2 - Section IV, Page 8 11.12.3 Se: tion IV, Page 9 11.12.4 Section III, Page 6 11.12.5 Section ill, Page 8 11.13 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 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) 11.14.3 UE Safety Analysis Calculation 87 001-00
.I1.14.4 Calculation ZZ-48, " Calculation ofinhalation and Ingestion Dose 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 Limiting Setpoint for the Containment Purge Exhaust Monitors, GT RE-22 and GT RE-33", March,1987 11.14.7 HPCI 88-10 " Methodology for Calculating the Response of Gross Nal(TI) Monitors to Liquid Effluent Streams", June,1988 11.14.8 Calculation ZZ-57, " Dose Factors for Eu-154", January,1989 11.14.9 Calculation ZZ-78, Rev. 2, "ODCM Gaseous Pathway Dose Factors for Adult Age Group", July,1992.
11.14.10 HPCI 88-08, " Performance Testing of the Environment TLD System at Callaway Plant", August,1980 I1.14.11 Calculation ZZ-250, Rev. O, "ODCM Gaseous Pathway Dose Factors for Child Age Group and Grous.: Plane Dose Factors", September,1992.' 11.14.12 UOTH 83-58," Documentation of ODCM Dose Factors and Parameters",. February,1983. I1.14.13 Calculation HPCI 95-004 (Rev. 0)," Calculation of Liquid Emuent Dose Commitment factors (Aa ) for the Adult Age Group", June,1996. 11.15 . U. S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Emuent Releases at Nuclear Power Stations", USNRC NUREG/CR-2919, September 1982,
. Washington D. C. 20555 ~
11.15.1 ' Section 4, " Subroutine 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 - TID-7004, " Reactor Shielding Design Manual", Rockwell, Theodore, Ed; March 1956. 'i1.18 ' BNWL-236, "ISOSHLD - A computer code for General Purpose Isotope Shielding Analysis", Engel, R. C.,
Greenberg, J., Hendrichson, M. M.; June 1966 r APA-ZZ-01003 Rev. 9 11.19 - . BNWL-236, Supplement I,"I'SOSHLD- IL Code Revision to include calculation of Dose Rate from Shielded Bremstrahlung Sources", Simmons, G. L., et al; March 1%7 11.20 BNWL-236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD- 111", Mansius, C. A.; April 1%9. I1.21; 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 Administrative Controls Section of Technical Specifications and the Relocation or w . edural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Pu m .m", January 1989 11.23 f.RC Answers to 10 CFR 20 Implementation Questions ! I1.23.1 Letter, F. J. Congel to J. F. Schmidt, dated December 9,1991. j .I1.23.2 Internal USNRC memo, F. J. Congel to V. L. Miller, et al, dated April 17,1992. j 11.23.3 Letter, F. J. Congel to J. F. Schmidt, dated April 23,1992. 11.23.4 Letter, F. J. Conget to J. F. Schmidt, dated September 14,1992. I1.23.5 Letter, F. J. Congel to J. F. Schmidt, dated June 8,1993. Il.24 USNRC Inspection Report 50-483/92002(DRSS) Section 5, page 5. j 11.25 HPCI 96-005," Calculation of Maximum Background Value for HB RE-18". I1.26 EGG-PilY-9703," Technical Evaluation Report for the evaluation of ODCM Revision 0 (May,1990) Callaway Plant, Unit 1", transmitted via letter, Sam' sal J. Collins (USNRC) to D. F. Schnell (UE), dated July 12,1996. ! I l I
- }}