ML20108A551
| ML20108A551 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1995 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-96-0063, W3F1-96-63, NUDOCS 9605020298 | |
| Download: ML20108A551 (362) | |
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l W3F1-96-0063 A4.05 PR April 30,1996
- U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Annual Radioactive Effluent Release Report Gentlemen:
Attached is the Annual Radioactive Effluent Release Report for the period January 1 through December 31,1995. This report is submitted in accordance with Waterford 3 Technical Specification 6.9.1.8.
If you have any questions, please contact me at (504) 739-6242 or Don Vinci at (504)739-6370.
Very truly yours, w -
J.J. Fisicaro Director Nuclear Safety JJF/CJT/ssf Attachment l
l cc: (w/ Attachment) l L.J. Callan (NRC Region IV), NRC Resident inspectors Office
, (w/o Attachment) 02010G C.P. Patel (NRC-NRR), R.B. McGehee, N.S. Reynolds 9eoso20290 951231 PDR ADOCK 0500o382
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i Waterford 3 SES Entergy Operations, Inc.
- Docket Number 50-382 License Number NPF-38 1
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I TABLE OF CONTENTS 1 Page No. !
1.0 SCOPE 3 l i
2.0 SUPPLEMENTAL INFORMATION 4 2.1 Regulatory Limits 4 l 2.2 Maximum Permissible Concentrations 6 :
2.3 Average Energy 7 2.4 Measurements and Approximations of Total Radioactivity 7 2.5 Batch Releases l
9 2.6 Unplanned Abnormal Releases 9 3.0 GASEOUS EFFLUENTS 9 4.0 LIQUID EFFLUENTS 9 l i
5.0 SOi.lD WASTES 9 !
6.0 I METEOROLOGICAL DATA 10 j l
7.0 ASSESSMENT OF DOSES 11 7.1 Doses due to Gaseous Effluents 11 7.2 Doses due to Liquid Effluents 13 7.3 40 CFR Part 190 Dose Evaluation 13 7.4 Doses to Public Inside the Site Boundary 14 8.0 RELATED INFORMATION 15 8.1 Changes to the Process Control Program 15 8.2 Changes to the Offsite Dose Calculation Manual 15 8.3 . Unavailability of REMP Milk Sampling 15 8.4 Report of Technical Specification Required Instrument inoperability 16 8.5 Activity Released via Secondary Pathways 17 8.6 Missed Effluent Samples 19 l
8.7 Major Changes to Radioactive Waste Systems 20 ;
8.8 Additionalinformation 21 9.0 TABLES 21 10.0 ATTACHMENTS 21 i W21419HP 2 A
1.0 SCOPE i
This Annual Radioactive Effluent Release keport is submitted as required by [
Waterford 3's Technical Specification 6.9.1.8. It covers the period from
-January 1,1995 through December 31,1995. Information in this report is :
presented in the format outlined in Appendix B of Regulatory Guide 1.21.
The information contained in this report includes:
(1) A summary of the quantities of radioactive liquid and geseous l effluents and solid wastes released from the plant during the reporting !
period. !
(2) A summary of the meteorological data collected during 1995. ,
(3) Assessment of radiation doses due to liquid and gaseous '
radioactive effluents released during 1995.
(4) A submittal of changes to the Offsite Dose Calculation Manual and Process Control Program during this reporting period.
(5) A discussion of why required monitoring instrumentation was not returned to service within the time specified.
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l 2.0 SUPPLEMENTAL INFORMATION !
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2.1 Regulatorv Limits l l
The Limits applicable to the release of radioactive material in liquid and i gaseous effluents are described in the following sections. These limits are addressed in UNT-005-014, Offsite Dose Calculation Manual.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the '
site boundary shall be limited to less than or equal to l
500 mremlyr to the totalbody; and j 3000 mremlyr to the skin.
l The air dose due to noble gases released in gaseous l effluents frnm the site to areas at or beyond the site boundary shall be limited to the following:
+ During any calendar auarter: Less than or equal to 1
5 mrad forgamma radiation; and 10 mrad for beta radiation
+ During any calendar year: Less than or equal to 10 mrad forgamma radiation; and 20 mrad for beta radiation.
2.1.2 lodines
Particulates. Half Lives > 8 Days: and Tritium The dose rate due to lodine-131 and 133, tritium, and all radionuclides in particulate form with half lives greater than j eight (8) days, released in gaseous effluents from the site to W21419HP 4
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areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrom/yr to any organ.
i 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 eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
+ During any Calendar auarter: Less than or equal to i
7.5 mrem to any organ; and
+ During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents i The concentration of radioactive material released in liquid l
effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, l Table ll, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml (Total Activity). ,
The dose or dose commitment to a member of the public from I
radioactive materials in liquid effluents released to l
unrestricted areas shall be limited to the following:
+ During any calendar auarter to less than or equal to 1.5 mrem to thu total body; and 5 mrem to aruy organ, and W21419HP 5
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+ During any calendar year to less than or equal to 3 mrem to the whole body; and l 10 mrom to any organ.
2.1.4 Uranium Fuel Cycle Sources l
The dose or dose commitment to any member of the public l due to releases of radioactivity and radiation from uranium fuel cycle sources over 12 consecutive months shall be limited to less than or equal to i
1 25 mrom to the TotalBody orany organ l (except thyroid organ); and l 75 mrem to the Thyroid 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases: lodines: and Particulates.
Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the j site boundary.
l 2.2.2 Liauld Effluenta The maximum permissible concentration (MPC) values specified in 10 CFR Part 20, Appendix B, Table ll, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary.
A value of 2.0E-4 pCi/mlis used as the MPC for dissolved and entrained noble gases in liquid effluents.
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2.3 Average Energy This is not applicable to Waterford 3's Effluent Specifications. E-Bars are not required to be calculated from effluent release data. l 2.4 Measurements and Approximations of Total Badioactivitv The quarHfication of radioactivity in liquid and gaseous effluents was acconspiished by performing the sampling and radiological analysis of effluents in accordance vtith the requirements of Tables 5.3-1 and 5.4-1 of UNT-005-014 Offsite Dose Calculation Manual.
2.4.1 Fission and Activation Gases (Noble Gaans)
For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was calculated according to the following equation:
1 GR = Average Weekly Noble Gas MonitorReading MonitorReading Dunng Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior j to release to determine noble gas concentrations in the batch.
l In all cases the total radioactivity in gaseous effluents was ,
determined from measured concentrations of each radionuclide present and the total volume discharged.
l 2.4.2 lodines and Particulates l
lodines and particulates discharged were sampled using a continuous sampler which contained a charcoal cartridge and ,
a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using W21419HP 7 I i
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i gamma spectroscopy. The determined radionuclide l concentrations and effluent volume discharged were used to l calculate the previous week's activity released. The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne ;
Isotopes). Particulate gross alpha activity was measured l weekly using alpha scintillation counting techniques. The i determined activities were used to estimate effluent l concentrations in subsequent releases until the next scheduled analysis was performed.
Grab samples of continuous and batch releases were analyzed :
monthly for tritium. The determined concentrations were used to estimate tritium activity in subsequent releases until the next
- scheduled analysis was performed. l l
2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentrations were used to determine radionuclide concentrations in the following week's l releases. For batch releases, gamma analysis was performed on the sample prior to release.
For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Teledyne isotopes) for Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting techniques, respectively. For radionuclides l measured in the composite samples, the measured concentrations in the composite samples from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter.
l The total radioactivity in liquid effluent releases was I
determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent discharged.
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2.5 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 1.
2.6 Unplanned / Abnormal Releases There were no abnormal releases during this reporting period.
3.0 GASEOUS EFFLUENTS The quanSties of radioactive material released in gaseous effluents are summarized in Tables 1 A,1B, and 1C. Note that there were no elevated releases, since all Waterford 3 releases are considered to be at ground level.
The estimated total error in % is based upon several statistical uncertainties due to sample countiag, efficiency, volume, etc.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed in Table 3. For certain waste forms Waterford 3 is now using volume reduction services provided by Scientific Ecology Group, Inc. (SEG) and Alaron Corp. These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal l volumes. Final disposal volumes are reported as they become available. The l estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
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6.0 METEOROLOGICAL DATA in Table 4, the hourly meteorological data from January 1,1995 through December 31,1995, is presented in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. The Waterford-3 data recovery results by parameter are as follows-l l
Parameter Annual Data Recoverv Rate Delta T 100.0 %
Wind Speed 100.0 %
Wind Direction 100.0 %
Overall
- 100.0 %
- Simultaneous occurrence of valid data for all three parameters.
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7.0 ASSESSMENT OF DOSES 7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundarv Air doses from gaseous effluents were evaluated at the closest offsite location that could be occupied continuously !
during the term of plant operation and that would result in the highest dose. This location was determined by examining the atmospheric dispersion parameters (X/Q's) at the closest i offsite locations that could be continuously occupied during plant operation in each of the meteorological sectors currounding the plant. The location that would have the highest dose would be that location having the most restrictive (largest) x/Q value.
Based on actual metecrological data collected during 1995, this location was determined to be in the NE sector at a distance of 966 meters (0.6 miles) from the plant. I i
Doses were assessed at this location in accordance with the '
methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and gamma exposures in air due to noble gas. The results of these assessments for the year 1995 are summarized as follows:
Beta air dose: 1.191 mrad Gamma air dose: 0.431 mrad The above Beta and Gamma air doses represent the following percentage of the Annual Dose limits:
5.96 % of the Beta air dose limit (20 mrad).
l 4.31 % of the Gamma air dose limit (10 mrad).
Dose calculation results are summarized by quarters in Table 5.
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i 7.1.2 Maximum Organ Dose to the Critical Receptor The maximum organ dose to a MEMBER OF THE PUBLIC from l-131,1-133, 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 was determined for 1995.
An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was astumed to be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (x/Q) and deposition (D/Q) parameters. Furthermore, it was assumed that the receptor living at this residence consumed food products that were either raised or produced at this residence.
Using land use census and meteorological data for 1995, the residence with the highest x/Q and D/Q values was determined to be in the NE sector at a distance of 1448 meters (0.9 miles) from the plant.
t The dose calculation was performed in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering the inhalation, ground plane exposure, and ingestion pathways. The maximum organ dose to the critical receptor was determined to be l
0.558 mrom to an infant thyroid. i and represents l 3.72 % of the Annual Organ Dose limit (15 mrem).
Dose calculation results are summarized by quarters in Table 5.
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l 7.2 Doses Due to Liquid Effluents l
The annual doses to the maximum exposed individual resulting from exposure to liquid effluents released during 1995 from Waterford 3 were:
1.604 mrem to the Total Body. l 2.195 mrem to the maximum exposed organ (Liver).
The above doses represent the following percentage of the Annual i Dose limits:
53.47 % of the Total Body Dose Limit (3 mrem).
21.95 % of the Organ Dose Limit (10 mrem). 1 Dose calculation results are summarized by quarters in Table 5. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.
7.3 40 CFR Part 190 Dose Evaluation In accordance with Waterford 3 Offsite Dose Calculation Manual, Section 5.5.2, dose evaluations to demonstrate compliance with Surveillance Requirements 5.5.1.a and 5.5.1.b of the ODCM, dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases), l 10 mrem to any organ (liquid releases),10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ from radioiodines and particulates.
At no time during 1995 were any of these limits exceeded; therefore, no evaluations were required.
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i 7.4 Doses to Public Inside the Site Boundarv i l
The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at Waterford 1 and 2 fossil fuel plants, located in the NW sector at distance i
of approximately 670 meters (0.42 miles) from the plant. !
Based on an assumed occupancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week) and the fact that all employees are adults, the calculated doses were determined
! to be less than: -
1.10E-02 mrem to the maximum exposed organ i (Thyroid) i l
4.36E-02 mrem to the Total body 1.11E-01 mrem to the skin l
Doses were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only the inhalation and ground plane exposure pathways. l I
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8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There was no change to the Process Centrol Program (procedure RW-001-210, Revision 6) during the reporting pedod.
8.2 Changes to the Offsite Dose Calculation Manual There was a major change to the Offsite Dose Calculaticn Manual (ODCM) [ procedure UNT-005-014)) and is listed in Attachment 10.1 of this report. A copy of the ODCM Revision 4 is included in Attachment 10.2 of this report.
8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with ODCM Table 5.8-1. Milk is collected, when available, from the control location and two identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Attachment 6.14.
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l 8.4 Report of Required Effluent Instrument Inoperability ODCM Specification 5.6.1.b and 5.6.2.b require reporting in the Annual Radioactive Effluent Release Report of why designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the Action Statement.
l During the reporting period, there was one case when the instrument was not restored to operability within the time specified. This case is described in the following section.
8.4.1 Monitor
Waste Gas Holdup System (GWMS)
Noble Gas Monitor (PRM-IRE-0648)
Time Required by Snecifications to Restore Operabilitv:
30 Days Period of inoperabilitv: 10:00 on 03/14/1995 to 14:25 on 11/18/1995 (8 months, 4 Days,4 Hours & 25 Minutes)
Cause of lnonerability:
At 10:00 on March 14,1995, Gas Waste Holdup System (GWMS) noble gas monitor (PRM-IRE-0648) declared
! inoperable to perform the required channel calibration (WA 01132048) as per ODCM, Table 5.6-4. Due to the unavailability of the required calibration standard source, the GWMS noble gas tronitor was out of service for more than 30 i
days. It was returned to service at 14:25 on November 18, 1995.
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Reason Operability Not Restored Within Allotted Time:
As required by the Offsite Dose Calculation Manual UNT-005-014, Table 5.6-4 Notation 4, noble gas channel calibration work for the noble gas channel of GWMS monitor was delayed until a new certified standard source was ordered and received from the analytical laboratory supplier.
When the required calibration was completed, the Waste Gas Uphold System Radiation Monitor (PRM-IRE-0648) returned to service at 14:25 on November 18,1995.
8.5 Activity Released Via Secondarv Pathways 8.5.1 The following secondary release paths were continuously monitored for radioactivity:
+ The Hot Machine Shop Exhaust (AH-35),
+ Decontamination Shop Exhaust (AH-34),
+ The RAB H&V Equipment Room Ventilation system Exhaust (E-41 A and E-41B); and
+ The Switchgear/ Cable Vault Area Ventilation System (AH-25).
Continuous sampling for these areas is maintained in order to demonstrate the operability of installed treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems. Sampling for these areas was limited to continuous particulate and iodine sampling and monthly noble gas grab sampling. The activity released via these secondary pathways resulted from routine operations and remained below significant levels.
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8.5.2 On June 10,1995, the A2 Bus in the Turbine Generator Building Switchgear caught fire causing damage to the bus and surrounding cables and components. The reactor trip occurred l
1 and a radiological effluent release occurred via the Atmospheric Dump Valve (ADVs) during the plant cooldown with detectable activity in the steam generators. The release is considered a planned release via a secondary release pathway as addressed j l In the FSAR, section 11.3.2.6 and the ODCM procedure ,
UNT- 005-014, section 5.11. Conservative dose calculations for the release were performed in according to the ODCM methodology and documented in Health Physics Calculation No.
l HP-CALC-95-007, Atmospheric Dump Valve Steam Release Dose Assessment. ,
I In the referenced document, the calculated maximum dose rate at site boundary was 3.15 mromlyr to a child thyroid via inhalation pathway. (0.21% of the annuallimit).
The maximum dose was 0.196 mrom to an infant thyroid via all l receptor's pathways (1.31% of the annuallimit)
L l Thus, the calculation validated the release to be insignificant and well within the definition of a " Secondary Release Path" as ;
I defined in the FSAR and ODCM documents.
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, 8.6 Missed Effluent Samoles: '
8.6.2 No gaseous effluent samples were missed during this reporting period.
8.6.1 There was one missed liauld effluent sample for the Circulating Water Discharge-Steam Generator Blowdown Heat Exchanger Discharge (CWD-SGD) during this reporting period as documented in the Condition Report number CR-95-0021 as follows:
l Descriotion of Event:
The Offsite Dose Calculation Manual (ODCM) procedure, UNT-005-014, Table 5.3-1 Section B. Note "1" requires surveillances to be conducted on the Circulating Water Discharge-Steam Generator Blowdown Heat Exchanger l
Discharge (CWD-SGB) whenever detectable activity exists in the secondary system. Contrary to this requirement, the required surveillance's on CWD-SGB have not been conducted despite the detection of tritium and some gamma 1 emitting isotopes in the secondary plant during 1993 and 1994. This condition was discovered during the ODCM procedure revision 4 preparation. i Cause of Event: '
The cause of this event was a mistaken interpretation of the 4 ODCM's requirement to sample from this release point. It was incorrectly assumed that the sampling requirement was only needed during the release of either Steam Generator Blowdown (SGB) or Auxiliary Component Cooling Water (ACCW) to the l Circulating Water System. The primary purpose of the CWD-SGB radiation monitor is to monitor and sample the cooling i
l water outlet of the circulation water side of the Steam Generator Blowdown Heat Exchanger (SGBHX) in order to determine if SGB water is leaking into the Circulating Water System.
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Secondary purpose of this radiation monitor is to monitor the SGB and ACCW releases to the Circulating Water System.
There were several instances when gamma emitting I radionuclides were detected in the Steam Generators over the two years period. They were infrequent and resulted in very low concentrations of I-131 and 1-133. Recently, Tritium monitoring has been implemented on the Steam Generators and consistently indicates detectable H-3 activity. Since there was no activity detected (gamma emitter or H-3) in the CWD-SGB samples, assurance is provided that there has not been any leakage of SGB fluid into the circulating water system from the SGBHX.
Corrective Action:
The CWD-SGB was sampled on January 11,1995 for Gamma emitting isotopes and tritium. The analyzed sample was found to be free of any radioactivity. Also, a sampling tickler card was initiated to obtain a weekly sample from the CWD-SGB until there is no detectable activity in the secondary system.
Action to Prevent Recurrence:
The Offsite Dose Calculation Manual was reviewed and the conditional sampling requirements identified in the revision 4 of UNT-005-014 procedure. Tickler cards were generated for ,
release points having a conditional requirement and the l possibility that sampling may or may not be in place during i any instant. For some of the sampling requirements, notification that the condition exists will come from operations (i.e. >15% power change within one hour, etc.). Tickler cards j are scheduled to be weekly items except for operation notifications (daily items).
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8.7 Major Changes to Radioactive Waste Systems During the reporting period, no Major Changes were made to any Radioactive Waste Systems.
8.8 AdditionalInformation The most recent Reactor Coolant System E-Bar calculation was 0.481 MeV/ Disintegration from a sample obtained on December 4,1995.
Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.
l 9.0 TABLES :
1 Batch Release Summary. (Pages 22 & 23) 1A Annual Summation of all Releases by Quarter- All Airborne Effluents.
(Page 24) 1B Annual Airborne Continuous Elevated and Ground Level Releases. (Page 25) 1C Semiannual Airborne Batch Elevated and Ground Level Releases. (Page 26) 4 2A Annual Summation of All Releases by Quarter- All Liquid Effluents.
(Page 27) 2B Annual Liquid Continuous and Batch Releases. (Pages 28 & 29) 3 Solid Waste Shipped Offsite for Disposal. (Pages 30 to 42) 4 Joint Frequency Distribution of Meteorological Data. (Pages 43 to 46) 5 ' Dose Calculation Results for 1995. (Pages 47 & 48) 10.0 ATTACHMENTS 10.1 Changes to Offsite Dose Calculation Manual; January 1,1995 to December 31,1995. (Pages 49 to 56) 10.2 Copy of Offsite Dose Calculation Manual (ODCM) Procedure UN I-005-014, Revision 4. (153 pages)
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TABLE 1 (1 of 2) i BATCH RELEASE
SUMMARY
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Batch Release $tanary information for 1995 Report Period.
Report Catagory . Batch Release Summary Release Point . All l Type of Release . Batch Liquid and Gaseous 1
Period start Time : 01-Jan 1995 00:00:00 Period End Time 31 dec 1995 23:59:59 L.iquid Releases l
Number of Releases : 261 Total Time for All Releases : 70086.5 Minutes Maximun Time for a Release : 342.0 Minutes Average Time for a Release : 268.5 Minutes Minimun Time for a Release : 64.0 Minutes Average Stream Flcw : 776410.5 GPM Gaseous Releases l Nunber of Releases : 15 Total Time for All Releases : 4333.0 Minutes Maximum Time for a Release : 600.0 Minutes Average Time for a Release : 288.9 Minutes Minimun Time for a Release : 65.0 Minutes l
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TABLEi (2 of 2)
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BATCH RELEASE
SUMMARY
Batch Release Supmary information for 1995 by Quarter.
Repost Category . Batch Release Summary Release Point : All Type of Release : Batch Liquid and Gaseous Period Start Time : 01-Jan-1995 00:00:00 Period End Time . 31 dec-1995 23:59:59 Liquid Releases Ctr 1 otr 2 otr 3 otr 4 Number of Releases : 51 71 87 52 Total Time for All Releases : 13467.0 19016.0 23859.0 13744.5 Minutes Maxim a Time for a Release : 295.0 321.0 342.0 312.0 Minutes Average Time for a Release : 264.1 267.8 274.2 264.3 Minutes Minimtsn Time for a Release : 231.0 145.0 204.0 Average Stream Flow -
64.0 Minutes 754705.9 688926.2 952640.7 612797.4 GPM Gaseous Releases otr 1 Qtr 2 ctr 3 otr 4 Number of Releases : 2 5 4 4 Total Time for All Releases : 437.0 1705.0 969.0 1222.0 Minutes Maximan Time for a Release : 221.0 490.0 600.0 Average Time for a Release 504.0 Minutes
- 218.5 341.0 242.2 Minim e Time for a Release 305.5 Minutes
- 216.0 65.0 80.0 182.0 Minutes W21419HP 23
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TABLE 1 A (1 of 1) 1 I
ANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS l
Gaseous Release Sumary information for 1995 Report Catagory Sumation of All Releases Type of Activity All Airborne Effluents ,
Period Start ilme : 01-jan-1995 00:00:00 j Period End Time : 31-dec-1995 23:59:59
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Type of Effluent Est. Total Units otr 1 ctr 2 otr 3 Qtr 4 Error %
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A. Fission and Activation Gases
- 1. Total Release Curies 2.46e+02 5.15e+02 5.90e+02 3.93e+02 1.50e+01
- 2. Average Release Rate for Period uCi/sec 3.17e+01 6.54e+01 7.43e+01 4.95e+01
- 3. Percent of Applicable Limit % n/a n/a n/a n/a B. Radiciodines
- 1. Total lodine-131 Curies 3.12e-06 6.96e-06 1.87e-04 5.80e-04 1.50e+01
- 2. Average Release Rate for Period uCi/sec 4.02e-07
- 3. Percent of Applicaote Limit 8.85e-07 2.35e 05 7.30e-05
% n/a n/a n/a n/a C. Particulates
- 1. Particulates (Half-lives > 8 Days) Curies 1.20e-06 2.70e-06 8.61e-07
- 2. Average Release Rate for Period 9.16e-06 1.50e+01 UCI/see 1.55e-07 3.43e-07 1.08e-07 1.15e-06
- 3. Percent of Applicable Limit % n/a n/a n/a n/a
- 1. Total Release Curies 2.35e+01 7.30e+01 S.96e+00 1.66e+01 1.50e+01
- 2. Average Release Rate for Period uCf/see 3.02e+00
- 3. Percent of Applicable Limit 9.29e+00 1.13e+00 2.09e+00
% n/a n/a n/a n/a i
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TABLE 1B (1 of 1)
ANNUAL AIRBORNE CONTINUOUS ELEVATED AND GROUND LEVEL RELEASES Gaseous Release Sumary information for 1995 Report Catagory : Airborne Continuous Elevated and Ground Level Releases.
- Totals for Each Nuclide Rt. leased.
Type of Activity : Fission Gases, lodines, and Particulates Period Start Time : 01-jan-1995 00:00:00 Period End Time : 31-dec 1995 23:59:59 Elevated Releases Ground Releases Nuclide Units Qtr 1 Qtr 2 otr 3 ctr 4 ctr 1 otr 2 otr 3 atr 4 Fission and Activation Gases Kr 85m curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.07e+00 1.952+00 9.95e-01 0.00e+00 Kr-88 Cuiies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.14e-01 0.00e+00 xe-133 Curtes 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e+02 3.68e+02 4.69e+02 2.61e+02 xe 133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.91e+00 0.00e+00 xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.04e+01 2.49e+01 6.95e+00 3.44e+00 xe-135m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.10e 01 6.31e+00 7. 44 e+00 0.00e+00 Total for Period curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+02 4.02e+02 4.86e+02 2.65e+02 Radiolodines I 131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.65e-08 4.95e-07 1.87e-04 5.80e-04 1-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.0$e-06 6.46e-06 1.32e-07 0.00e+00 Total for Period curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.12e-06 6.96e-06 1.87e 04 5.80e-04 Particulates H-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.33e+01 7.30e+01 8.88e+00 1.65e+01 Cr-51 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.82e-07 Co-58 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.27e-08 3.01e-07 5.04e-06 Co-60 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.78e 07 3.22e 07 1.27e-06 Nb-95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.55e 07 Ru-103 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.89e 07 Sb-125 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.87e-07 1.24e-06 0.00e+00 0.00e+00 Cs 134 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.25e-07 2.64e-07 Cs-137 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.15e-07 1.22e-06 1.40e-08 9.49e-07 Gralpha Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.83e 06 3.68e-06 7.04e-06 6. 75 e-06 Total for Period curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.33e+01 7.30e+01 8.88e+00 1.65e+01 W21419HP 25
TABLE 1C (1 of 1) l 1
ANNUAL AIRBORNE BATCH ELEVATED AND GROUND l LEVEL RELEASES l i
1 Gaseous Release Sunnary information for 1995 i
1 Report Category : Airborne Batch Elevated and Ground Level Releases.
- Totals for Each Nuclide Released.
Type of Activity : Fission Gases, lodines, and Particulates Period Start Time : 01-jan-1995 00:00:00 Perica End Time . 31-dec 1995 23:59:59 Elevated Releases Ground Releases Nuclide Units Ctr 1 Qtr 3 Qtr 4 atr 2 ott 1 Qtr 2 Qtr 3 Qte 4 Fission and Activation Gases Ar-41 Curies 1 Kr-85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.46e 01 7.42e-02 3.02e-01 5.93e-02 '
Kr-85m 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.64e+00 8.33e+00 1.60e+00 3.79e+00 Curies xe-131m turies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.87e 04 1.92e 02 0.00e+00 Xe-133 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.65e-01 2.20e+00 1.23e+00 1.82e+00 Curies Xe-133m 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.68e+01 8.73e+01 9.95e+01 1.22e+02 Curies xe-135 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.75e-02 2.55e 01 8.43e-01 5.06e-01 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.00e-02 4.33e-02 4. A -01 3.92e 03 Xe 137 Curies Xe-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.46e+01 0.00e+00 0.00e+00 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.25e 01 0.00e+00 0.00e+00 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.02e+01 1.13e+02 1.04e+02 1.29e+02 I
Radiciodines l
None l
I Particulates M-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.87e-01 3.88e-02 8.43e-02 1.77e-01 Total for Period curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.87e 01 3.88e 02 8.43e-02 1.77e-01 l
l l
- W21419HP 26 l 1
1 l
l
[ l l
TABLE 2A (1 of 1)
ANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS Liquid Release Sumary information for 1995 Report Category : Sumation of All Releases Type of Activity : All Liquid Effluents Period Start Time : 01-Jan-1995 00:00:00 Period End lime : 31 dec-1995 23:59:59 -
Type of Efftuent Est. Total units otr 1 otr 2 Qtr 3 Ctr 4 Error %
A. Fission and Activation Products
- 1. Total Release (Not including Tritita, Cases, and Alpha curies 3.19e-01 5.79e-01 1.36e+00
- 2. Average Diluted concentration 1.51e+00 1.50e+01 During Period uC1/see B.63e-10 1.69e-09 2.84e 09 4.93e-09
- 3. Percent of Applicable Limit % n/a n/a n/a n/a B. Tritium
- 1. Total Release Curies 1.92e+02 3.20e+02 4.61e+02
- 2. Average Diluted Concentration 2.09e+01 1.50e+01 During Period uCl/sec 5.19e 07 9.35e-07 9.64e-07 6.80e-08
- 3. Percent of Applicable Limit % n/a n/a n/a n/a C. Dissolved and Entrained Cases
- 1. Total Release Curies 1.09e+00 3.49e+00 4. 76e+00 1.08e+00 1.50e+01
- 2. Average Diluted concentration During Period uCi/sec 2.95e-09 1.02e-08 9.95e 09 3.51e-09
- 3. Percent of Applicable LI.iit % n/a n/a n/a n/a D. Gross Alpha Radioactivity
- 1. Total Release Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.50e+01 E. Waste volune Released (Pre-Dilution) Liters 1.12e+07 1.39e+07 1.31e+07 9.24e+06 1.50e+01 F. Volune of Dilution Water Used Liters 3.70e+11 3.42e+11 4.78e+11 3.07e+11 1.50e+01 l
l l
W21419HP 27
- -- - . . .-- ~_ .
TABLE 2B (1 of 2)
ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES Liquid Release Sumary information for 1995 Report Category : Liquid Continuous and Batch Releases.
- Totals for Each Nuclide Released.
Type of Activity : All Radionuclides Period Start Time : 01 Jan-1995 00:00:00 l Period End Time : 31 dec 1995 23:59:59 i
Continuous Releases Batch Releases Nuclide Units otr 1 Qtr 2 ctr 3 otr 4 Qtr 1 atr 2 otr 3 otr 4 ALL Nuclides H-3 Curies 9.29e-02 1.31e 01 3.77e-02 9.66e-03 1.92e+02 3.20e+02 4.61e+02 2.09e+01 Na-24 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.64e-05 6.96e-05 1.37e-04 1.46e-04 Ar-41 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.91e 05 0.00e+00 7.20e 06 Sc-46 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e 00 4.34e-05 2.88e-05 1.97e 04 Cr-51 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.09e-04 3.07e-02 1.79e-01 1.50e-01 Mn-54 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.10e-03 1.08e 03 4.08e-03 1.82e-02 Fe 55 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.83e 01 4.40e-03 1.49e-02 5.28e-02 Fe 59 Curies 0.00e+00 0.00e+00 0.0Ce+00 0.00e+00 0.00e+00 7.56e 03 3.47e-02 1.06e-02 Co 57 Curtes 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.68e 03 Co 58 Curies 0.00e00 9.79e-06 1.02e-05 2.52e 05 6.94e-03 1.52e-01 7.18e-01 7.61e-01 Co-60 Curies 0.00e+00 5.63e 06 9.cle 07 3.86e-07 5.03e-03 5.09e-03 1.98e-02 5.73e 02 Ni-56 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.60e 04 2.85e-04 3.21e-05 Zn-65 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.85e-06 0.00e+00 Br-82 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.73e-04 1.23e-04 0.00e+00 Kr 85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.75e-02 1.05e-01 4.37e 02. 1.38e-02 Kr 85m Curies 0.00e+00 0.00e+00 0.00e+00 0.00h00 9.98e-04 2.08e 03 9.03e 04 0.00e+00 Kr-88 Curies 0.00e+00 0.00e+00 0.00e+00 0.0%+00 4.73e-04 1.05e-03 4.09e-04 0.00e+00 Rb-88 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.41e-03 3.16e-01 4.82e-02 0.00e 00 Sr 89 Curies 0.00e+00 0.00e+00 0.00e+00 0.00a+00 2.44e-04 6.10e-05 1.12e-04 0.00e+00 Sr 92 Curies 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 7.64e-05 2.89e 04 2.76e-04 l Y*91m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.29e 06 0.00e+00 0.00e+00 l Zr 95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.15e-03 1.29e-02 7.38e-02 9.81e 02 Zr 97 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.29e 05 0.00e+00 kb-95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.99e 03 1.56e 02 9.23e-02 1.60e 01 Nb-97 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.07e-04 2.22e-03 3.65e 04 l Tc-99m Curtes 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.10e 04 2.39e 05 0.00e+00 Ru-103 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.61e-05 1.00e-03 Ag 110m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.52e 04 6.38e-03 7.82e-04 Sn-113 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.21e 04 1.09e 03 8.13e 03 7.68e-03 Sb 122 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.98e 06 6.27e 05 6.40e-03 1.34e-03 Sb 124 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.15e 03 5.76e 03 1.18e-02 sb-125 Curies 6.51e-06 7.86e 06 0.00e+00 0.00e+00 3.41e-03 9.33e 03 1.60e-02 5.21e 02 sb-126 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.19e 05 6.37e-04 2.02e-04 Sb 127 Curies 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.53e 05 0.00e+00 0.00e+00 Te 132 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e 04 9.36e-05 I-131 Curies 0.00e+00 4.33e 07 1.78e 05 0.00e+00 2.32e-04 3.78e 03 6.06e-02 5.77e 02 1-132 Curies 0.00e+00 0.00e+00 0.00e+00 0.0Ce+00 0.00e+00 3.89e 05 1.86e-03 2.74e 04 1 133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.44e-04 6.35e 03 5.21e-03 5.43e 05 1 134 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.69e-04 0.00e+00 6.04e-03 7.26e 05 xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 1.00e+00 1.18e 02 5.51e-02 5.10e 02 1.70e 02 ye 133 Curies 0.00e 00 0.00e+00 4.30e-06 0.00e+00 9.95e-01 3.28e+00 4.59e+00 1.04e+00 xe 133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.24e-02 2.5de 02 3.66e-02 4.03e-03 xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.39e-02 2.14e 02 3.27e 02 2.04e-04 Cs 134 Curles 1.75 e-05 2.97e-05 3.43e 05 1.26e-05 1.95e-03 3.23e 03 1.21e-02 3.34e-02 Cs-136 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3. se-05 0.00e+00 ' 04e 03 W21419HP 28 1
l l
- 1 l
l t
! TABLE 2B l (2 of 2)
! ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES I
l l
Liquid Release Sumary information for 1995 j
Report Category : Liquid Continuous and Batch Releases.
Totals for Each Nuclide Released.
l Type of Activity All Radionuclides Period Start Time : 01 jan-1995 00:00:00 Period End Time : 31 dec-1995 23:59:59 i
Continuous Releases Batch Releases Nuclide Units otr 1 otr 2 otr 3 otr 4 otr 1 otr 2 otr 3 !
otr 4 All Nuclides (continued)
Cs-137 Curfes Cs-138 Curies 2.26e 05 6.38e-05 6.48e-05 2.48e-05 2.00e-03 3.69e-03 1.31e-02 2.97e-02 Ba-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.77e-03 0.00e+00 2.38e-02 0.00e+00 Ba-140 Curies 0,00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.24e-04 0.00e+00 0.00e+00 La-140 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.65e-05 0.00e+00 3.45e-04 Ce-141 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.10e-04 1.36e-03 1.75e 03 4.54e 03 W 187 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ce00 3.87e-05 1.50e-04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.23e-05 2.52e 05 0.00e+00 0.00e+00 Total for Period curies 9.30e-02 1.31e-01 3.79e-02 9.72e-03 1.94e+02 3.24e+02 4.67e+02 2.35e+01 l
l l
l l
K21419HP 29 i
TABLE 3 (1 of 13)
- SOODlWAS'TE SHIPPEDIDFFSITE.FDR blSPDSAk
{DURING PERIOD..OFf01/01/95 THROUGH;12/31/951 f
I....~...,......
i
- ,$/. '. j e .
- ; . . /. p? ;j '
- f. j':f. ?.;j 1 Yf.? ( . . [.; * .
Ifj[; I Ub i M}Ek,h!h.I.', } l t l (B) 2080 58.91 1.49E-01 4 -+25% !
l Non Compacted ,
Dry Activity Waste Shipped to SEG '
Corp for Volume 2.68 1.506E-01 -+25%
Reduction. . Burial Volume Burial Activity
~.
1 l
(B) 2080 58.91 3.95E-01 4 -+25% l l
Non Compacted Dry Activity Waste Shipped to SEG Corp for Volume 2.36 3.398E-01 -+25%
Reduction. . Burial Volume Burial Activity
. Waste volume shipped for volume reduction do not reflect final burial waste volume unless otherwise stated.
. A Activity determined by estimations.
1
+ Activity determined by measurements.
I l l I
W21419HP 30
TABLE 3 (2 of 13) 3DOD' VVASTElsHiPPEb.lDFFslTE fF.DR1 blSpDSXD
! DURING? PERIOD [DF-:;01/0185$THRDUGH112/3.1/951
- q. - .....,....r
. =,.
p.- .. , ,- .- . . -
, , - . +.c.
,^...
'; '* ' ' ' * ~
.". .f , _ h [ ' y.'
g - _ _ . y Ke ..
j
- *[ is^ ?
.:.'.. - _ , ' ;e. ( f ,'; l: ;- ,.~>: ._-
- : ~.
- ;. ^' f .-.' ~..y,f.y n ' W'; . > .;h(.
.?,9.:
.+.;.?.
.. .y. _;:y;,;p\ n
.a.;._
,:?' . : :..}" -[.f M; ;.n.c..25. p . .:2.3isR. ;Jscn .c
- .?.l' 'l'.;, _' ; ..'
- . Y
' .s .
^ .. _
' ,._ " . '- ,_ '. y .i,_
L:.:.,;e;,.L2;.2.::.L...;.'i;.iL,'l.;;s.%.)..
- _ I-
. .l.;:. . .
.'. .f .
(B) 2080 58.91 2.72E-01 4 -+25%
Non Compacted Dry Activity Waste Shipped to SEG Corp for Volume 0.561 1.61 E-02 -+25%
Reduction. . Burial Volume Burial Activity (B) 2080 58.91 5.61 E-01 4 -+25%
Non Compacted Dry Activity Waste Shipped to SEG Corp for Volume 2.09 2.80E-01 -+25%
Reduction. . Burial Volume Burial Activity
. Waste volume shipped for volume reduction do not reflect final burial waste volume unless otherwise stated.
4 Activity determined by estimations.
+ Activity determined by measurements..
W21419HP 31
TABLE 3 (3 of 13)
ISOOD;W4STn" SHIPPED I6FFSITEIFDR bl'SPDSnf (DURING PERIODIOFl0.1/01/95.:THROUGH!12/31/951 ;
& :; . u ; ;. - . - .- . .
{ Q:.UQlt.. ;; , M!. t kg.hp i f~ ~ j.1~ :
.7?L.. . ;:w{ ):3
...,.c
.. ; ; . . , :, y.: y n.;, ;, ' .
.o 1
- .%..;F;..g. f.y ;,89 3 - '
- . - i ;;;.
- ;.3l+k
- ? ,, ;r u .; .
. x a m .: 3. &.,w ,;nu.
.: ; . . . . . .:c : . . a ;i. . D 1. . . w. : . , ; . . a:%
(A) 174.3 4.94 6.0E+01 + -+25%
Resin Waste Management Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A) 174.3 4.94 3.18E+02 + -+25%
Resin Waste Management Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
. Waste volume shipped for volume reduction do not reflect final burial waste volume unless othenvise stated.
- Activity determined by estimations.
+ activity determined by measurements.
W21419HP 32
l
, TABLE 3 (4 of 13)
- SOLID WASTE 7 SHIPPED [OFFSITElFORlDISPOS C
~
(D.URINGlPERIODjDF 01/01/95LTHRDUdK12/31/951 i
$ i i
i i 1 1 1
1 (A) 202.1 s.72 3.g7s+oo + -+25%
\
l l
Liquid Waste Management Resin Dewatered in a
! High Integrity Container (Bead Resin) Shipped for Burial.
(A) 202.1 s.72 3.e8E+oo + _+25%
Liquid Waste Management Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
l l . Waste volume shipped for volume reduction do not reflect firia' "" rial waste volume l unless otherwise stated.
4 Activity determined by estimations.
+ Activity determined by measurements.
W21419HP 33
TABLE 3 (5 of 13)
? SDODfWASTelSHIPPeDTOFESITETFDRIblSPDSnD LD.URING PERIODTOFl01/d1/95]TAROUGN32/33/9si !
l (A) 202.1 5.72 1.56E+01 + -+25%
Liquid Waste Management Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A) 45.8 1.30 7.89E-01 + -+25%
Liquid Waste Management Resin Dewatered in a Strong Tight Container (Bead l Resin) Shipped for Burial.
. Waste volume shipped for volume reduction do not reflect final burial waste volume l
unless otherwise stated.
i
- Activity determined by estimations. 4
+ Activity determined by measurements.
W21419HP 34 l
I-________-______-______
TABLE 3 (6 of 13)
ISOOliWASTE sHIPPEDTOFFslTEIFORIDispDsX13 iDURINd, P.ER. ID. b....OI,.0,i. l01. /.9.54.T,...HR. O.., UGH..i12/31.
/95,7
,.-,~_;a_-
--;-r. .
,_ _. e;- -_ ;,_,.<_- -
<.. > . .~ 3 g
{;:'. 4 3. .
. .[ g.e. .
.,.ll, .. : . .-
,...? .;.. . ...}
y;,.;_'; ~- [ ;; }. Q
- . ..fq :
- [. . -
. %;f i; : . L.i.?.? .:n ,.L..Vh;{ ,:L.;
. . . : '. ; :i ; .. ,..:
. . ; ; .; . ./ ' . . . . ;i '.
L.
(A) 132.4 3.75 2.50E+01 + -+25%
Spent Cartridge Filters in Integrity Container Shipped for Burial.
(A) 132.4 3.75 1.03E+02 + -+25%
Spent Cartridge Filters in Integrity Container Shipped for Burial.
. Waste volume shipped for volume reduction do not reflect final burial waste volume unless otherwise stated.
- Activity determined by estimations.
+ Activity determined by measurements.
W21419HP 35
)
TABLE 3 (7 of 13) iSOOb W^'STEisHIPPEb DFFSITE!FDR 7 dlSpdS^O 1DURING PERIOD;OF;011/01/95kTHRO. UGH;12/31/951
. . . . ; . - ~ : .
.' j .] ' } : .fj{,
!"~
[u .,; . .,
.- ( [. .f -( ' [. . ,
.e
( [.l l -
..,..;.- ; ;y ,;
. .. ; ; . ..,. c. .
. ..c;., :
0.s ,r, .' ' $ ?: 1.':.,.l.~'...;..' suG .' ..,.i....s:. :.....,...'.....J,
.. .r.,.. . , --'. i.J u ; # ... . > . 6,
_ .: " '.L' nr.' . *- N ., :
(D) 270 7.64 5.59E-03 + -+25%
Waste Oil Shipped to SEG Corp for Incineration in Six Strong Tight Containers.
(D) 180 5.10 5.00E-07 + -+25%
Waste Oil Shipped to SEG Corp for Incineration in Four Strong Tight Containers.
(C) 57.4 1.625 1.24E+04 4 -+25%
Irradiated Components Shipped in Type B Container. -
. Waste volume shipped for volume reduction do not reflect final burial waste volume unless otherwise stated.
- Activity determined by estimations.
+ Activity determined by measurements.
W21419HP 36
l TABLE 3 (8 of 13)
?SOOD.WASTEISHIPPEDIDFF51TE T FDRfDispDS C J.. DURINGlPERIDD;OF 01/01/95jTHROUG H!12/31/951 '
1 i
l i,ME[ -5_s OFf,- c ss 455Q n. ,J12 p=s.sN.
,- AT40Ni .
W8HIPMENTS *, aM~ ~QE v,tP /STI@
, . - + . . .,
t ' q~9FM. s#wx t
9 Sole Use Cask Bamwell, SC 6 Sole Use Flatbed Oak Ridge, TN :
i 1
1 i
l l M.!E 3.jN4@Eug BKPQ' eg$ tog WW DISTINATION i l
[/CLAS.S,.
IS_ HIP.. ;ME.NTS_ W ' s. . _40_ .N_T...A_I.N...ER,,O
~ ._ ..
7 a M' a
I t
A 6 LSA Strong Tight Truck Oak Ridge, TN A 4 LSA Strong Tight Truck Barnwell, SC 1
>A l B 2 LSA Strong Tight Truck Barnwell, SC C 2 B Type B Truck Barnwell, SC l
>A C 1 LSA Type A Truck Barnwell, SC W21419HP 37 1
I
TABLE 3 (9 of 13)
LSOLID W STE!SHIPPEbTDFFSITn? F DRJDisPOsAC i DURINGL PERIOD ldF 01/01/95fH RdUGH j 2/31/955 s
SUMMARY
!BY MAJOR: WASTE;TYPESi (A) Spend resins, Filter Sludges, Evaporator Bottoms, ect.
(B) Dry Compressible Waste, Contaminated Equipment, etc.
(C) Irradiated Components, Control Rods, etc.
(D) Other (Waste Oili.
.WASTEITYPE TW^5TEi ETOT4k TERRORsi VOLUME? LACTIVITY?
[(M3)i l(Ci))
(A) 35.83 5.30E+02 -+ 25%
(B) 235.644 1.377E+00 -+ 25%
(C) 1.625 1.24E+04 -+ 25%
(D) 12.74 5.59E-03 -+ 25%
- 4 Includes all Type Waste Volume.
W21419HP 38
i TABLE 3 ,
(10 of 13) l 4 I SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD OF 01/01/95 THROUGH 12/31/95 L
SUMMARY
L BYiMAJOR WASTE:vTYPES (Cont'd);
LWASTE TYP5) (NUCODEN $153 [DONI'$si S ABUN NCE 1
(A)
Co-58 2.22E+02 41.95 Cs-137 1.00E+02 18.94 Cs-134 9.49E+01 17.95 Ni-63 3.92E+01 7.42 Fe-55 3.58E+01 6.76 Co-60 1.99E+01 3.76 Mn-54 7.85E+00 1.48 Cr-51 4.48E+00 0.85 Zr-95 2.02E+00 0.38 Nb-95 1.61 E+00 0.30 Fe-59 6.40E-01 0.12 Ce-144 6.40E-01 0.12 4
Ni-59 3.78E-01 0.07 Sr-90 1.28E-01 0.02 H-3 N.P. 0.00 C-14 N.P. 0.00 Tc-99 N.P. 0.00 1-129 N.P. 0.00 TOTAL 5.30E+02 Note N.P. means Not Presant.
W21419HP 39
TABLE 3 (11 of 13)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD OF 01/01/95 THROUGH 12/31/95 i
i l i
SUMMARY
BY; MAJOR 1 WASTE; TYRES;(Cont'd))
i (W4STETYP5/ [NOdUbE A M5; jlCd5tlE5i; $ciABUS hNC51 f
1 i
(B)
Fe-55 4.44E-01 32.27 1
Cs-134 1.70E-01 12.33 Ni-63 1.68E-01 12.18 j Co-60 1.62E-01 11.79 i Cs-137 1.58E-01 11.45 l
j Co-58 1.36E-01 9.85 Mn-54 7.05E-02 5.12 Ni-59 1.57E-03 0.11
) Pu-241 6.50E-04 0.05 I Cm-242 1.03E-08 0.001 i H-3 N.P. 0.00 j C-14 N.P. 0.00 1
Tc-99 N.P. 0.00
$ l-129 N.P. 0.00 TOTAL 1.377E+00 f Hole. N.P. means Not Present.
l W21419HP 40 1
3
TABLE 3 (12 of 13)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD OF 01/01/95 THROUGH 12/31/95 T
SUMMARY
BYiMAJOR; WASTE TYPES;!(Cont'd);
WASTEITIPE$ !INOCODE N MM fLdORIESl ThBbNDNUE$
(C)
Co-60 6.82E+03 55.00 Fe-55 2.06E+03 16.61 j Co-58 2.02E+03 16.29 Cr-51 1.05E+03 8.47 Ni-63 2.85E+02 2.30 Mn-54 1.88E+02 1.52 Fe-59 2.02E+01 0.16 Ni-59 1.82E+00 0.015 C-14 1.79E-01 0.001 Nb-94 1.84E-03 0.00 T-99 4.15E-04 0.00 H-3 N.P.
1-129 N.P.
TOTAL 1.24E+04 Hole N.P. means Not Present.
W21419HP 41
TABLE 3 (13 of 13)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD OF 01/01/95 THROUGH 12/31/95
~
K
SUMMARY
iBY MAJORLWASTEtTYPES::(C6nt'd)!
L: WASTE TYPEt );NOCLIDE NAMEf !.LCURIESj s*AABdND NCEs (D)
Fe-55 2.24E-03 40.07 Ni-60 1.21 E-03 21.65 Co-60 9.90E-04 17.71 Cs-137 5.70E-04 10.20 Cs-134 4.00E-04 7.16 Mn-54 1.70E-04 3.04 Ni-59 1.20E-05 0.21 Pu-241 2.24E-06 0.04 Co-58 0.00E+00 0.00 Cm-242 0.00E+00 0.00 H-3 N.P. 0.00 C-14 N.P. 0.00 l Tc-99 N.P. 0.00 1-129 N.P. 0.00 TOTAL 5.59E-03 Natt N.P. means Not Present.
i W21419HP 42
TABLE 4 (1 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA I
I I
I l Joint frequency distribution of wind speed and direction in hours 01-01-95 00:00to 12 31-95 23 59 Pasouill Class A l l
l Wind Speed (M/S) at 10 m tevel l Wind l Direction.35.50 51.75 .76-101.1 151.6 2.0 2.1-3.0 3.15.0 5.1-7.0 7.1-1010.1 1313.1 18.0 >18.0 Total l l.. .... ... . . .. . .. .... .
......l l N 0 0 0 0 2 5 27 13 0 0 1 0 48 I i NNE O O 0 0 0 4 16 6 0 0 0 0 26 l l NE O O O O 0 17 136 13 1 0 0 0 167 l l ENE O O O O 0 7 19 6 0 0 0 0 32 l l E 0 0 0 0 0 0 0 0 0 0 0 0 0 l l ESE O O O O O 1 5 3 0 0 0 0 9 l l SE O O 0 0 0 0 8 0 0 0 11 0 19 l
, l SSE O 0 0 0 0 2 'l 9 1 0 0 0 23 l l 5 0 0 0 0 0 1 16 0 0 0 0 34 l l SSW 0 0 0 0 0 2 . 3 0 0 0 0 7 {
l SW 0 0 0 0 2 4 13 21 0 0 0 0 40 l 1 WSW 0 0 0 0 0 2 8 2 0 0 0 0 12 l l W 0 0 0 0 1 2 3 0 1 0 0 0 7 l l WNW 0 0 0 0 0 0 9 1 0 0 0 0 10 l l NW 0 0 0 0 0 17 3 1 1 0 0 0 22 l l NNW 0 0 0 0 0 8 19 6 4 0 0 0 37 l
- i. .... .. . .. .. . . ... .. . ..... ... .. ... ... .... .. . .. .. ... .. .. ....
.l l Total 0 0 0 0 5 56 311 113 8 0 0 0 493 l 1
l l Nunber of calms for A Stability: 0 l l i
l l l l
l 1 l Joint frequency distribution of wind speed and direction in hours 010195 00.00to 12 3195 23.59 Pasquill Class 8 l l
l Wind Speed (M/S) at 10 m Level l
l Wind l l Direction .35 .50 .51. 75 .76101.1 1.51.6 2.0 2.13.0 3.1-5.0 5.17.0 7.1-1010.1-1313.1 18.0 >l8.0 Total l l..
l N 0 0 0 4 8
....l 1 18 7 1 0 0 0 39 l l NNE O 0 0 0 1 7 l' 10 0 0 0 0 32 l l NE O O O 1 5 31 W 3 0 0 0 0 106 l l ENE O O O O 1 10 17 2 0 0 0 0 30 l l E O O O O O O 2 1 0 0 0 0 3 l l
l ESE D 0 0 0 0 0 7 4 0 0 0 0 11 l
l SE O O O O 1 1 7 3 0 0 0 0 12 l l SSE 0 0 0 0 0 4 14 3 1 0 0 0 22 l l 5 0 0 0 0 1 3 23 13 4 0 0 0 44 l l SSW 0 0 0 0 0 6 6 5 2 0 0 0 19 l l SW D 0 0 0 1 7 15 5 0 0 0 0 28 l l WSW 0 0 0 0 0 4 6 2 0 0 0 0 12 l l W D 0 0 1 0 3 2 0 0 0 0 0 6 l l WNW 0 0 0 0 1 4 8 0 1 0 0 0 14 l l W 0 0 0 0 0 4 5 0 0 0 0 0 9 l l NNW 0 0 0 0 6 21 5 0 1 1 0 0 34 l
- j. . . . ... . . .. . . . .. . .. .. .. . . .. .. ... . .. ..
...l l lotal 0 0 0 3 21 93 231 63 10 0 0 0 421 l 1
I l Number of calms for 8 Stability: 0 l
1 I
W21419HP 43
l t
TABLE 4 (2 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA l l l l l Joint frequency distribution of wind speed and direction in nours 01-01-95 00:00to 12 3195 23:59 Pasqu111 Class C l l 1 l Wind Speed (M/S) at 10-m Level l l Wind l l Direction .35 .50 .51.75 .761.01.1 1.51.6 2.0 2.13.0 3.15.0 5.1-7.0 7.1-1010.1 1313.1 18 0 >18 0 Total l l..
N
.l l 0 0 0 0 8 12 26 8 4 0 0 0 58 l l NNE O 0 0 3 6 17 17 5 0 0 0 0 48 l l NE 0 0 0 0 12 46 62 7 0 0 0 0 127 l l ENE O O O O 2 12 27 2 0 0 0 0 43 l l E 0 0 0 0 0 0 4 2 0 0 0 0 6 l l ESE O O O 1 1 4 9 6 1 0 0 0 22 l l SE D 0 0 0 0 2 12 9 0 0 0 0 23 l l SSE O O 0 0 2 11 33 4 0 0 0 0 50 l l 5 0 0 0 0 2 12 28 9 7 0 0 0 58 [
] SSW 0 0 0 1 2 5 12 8 2 0 0 0 30 l l W 0 0 0 1 3 13 15 7 1 0 0 0 40 l l WSW 0 0 0 2 6 11 7 3 0 0 0 0 29 l 1 l W 0 0 0 0 3 12 4 0 0 0 0 0 19 l l WNW 0 0 0 0 1 3 1 0 0 0 0 0 5 l l NW D 0 0 0 0 6 7 0 0 0 0 0 13 l l NNW D 0 0 0 4 11 27 6 0 0 0 0 48 l 1 1 i l Total 0 0 0 8 52 177 291 76 15 0 0 0 619 l l i l l kJmber of calms for C Stability: 0 l l l I I I i l Joint frequency distribution of wind speed and direction in hours 01-01-95 00.00to 12-31-95 23 59 PasquillClass3l 1 I l Wind Speed (M/S) at 10 m Level l l Wind l l Direction .35 .50 51.75 .76-1.01.1 1.51.6 2.0 2.13.0 3.1 5.0 5.1 7.0 7.1 1010.1 1313.1 18.0 >18.0 Tctal l
- l. ........ ..l l N 0 2 1 5 23 57 127 121 34 0 0 0 370 l l NNE 0 0 4 7 21 40 87 62 2 0 0 3 223 l
[ NE 0 1 5 10 30 101 150 32 1 0 0 0 330 l l ENE O 0 2 8 9 33 115 27 1 0 0 0 195 l l E O 1 0 3 5 6 67 29 1 0 0 0 112 l l ESE O O 1 0 2 7 83 26 6 0 0 0 125 l l SE 0 0 2 4 6 23 74 16 5 0 0 0 130 l l SSE O O 1 1 9 29 133 45 6 0 0 0 224 l l 5 0 0 1 7 14 39 113 47 15 0 0 0 236 l l SSW 0 0 1 5 8 35 59 23 3 1 0 0 135 l SW D 0 0 7 8 22 46 20 0 0 0 0 103 l WSW D 0 0 8 12 42 24 1 1 0 0 0 88 l W D 0 2 9 12 19 32 7 0 0 0 0 81 l l WNW 0 0 1 6 5 20 17 3 0 0 0 0 52 l l W 0 0 2 5 8 13 25 3 1 0 0 0 57 l l NNW 0 0 1 6 10 33 86 58 16 0 0 0 210 l j.... . .. .... . .. . . . . .. ..... . . .. .. . .
.. . . . .... . .l l Total 0 4 24 91 182 519 1238 520 92 1 0 0 2671 l 1 l l Nuncer of Calms for D Stability: 0 l l
l l l
W21419HP 44
l l
l l TABLE 4 (3 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA i
r l
l 1 1 l l Joint frequency distribution of wind speed and direction in hours 01-0195 00:00to 12-31-95 23.59 PasquillClassEl I I l Wind Speed (M/S) at 10-m level l l Wind l l
l Direction .35 50 .51.75 .76-1.01.1 1.51.6 2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1 1010.1 1313.1 18.0 >18.0 Total l l .l...... .... . .. . .... ... . .... . . . .. .. ..... .. . . .... . ... . .;
l l N 0 1 6 19 42 76 100 27 3 0 0 0 274 l l l NNE O 2 2 17 26 67 79 12 0 0 0 0 205 l l NE O 1 5 13 29 134 98 5 1 0 0 0 286 l l ENE O O 2 6 23 71 85 3 0 0 0 0 190 l l E O 1 4 6 12 36 60 3 0 0 0 0 122 l l ESE 1 0 0 4 15 47 85 9 1 0 0 0 162 J i l SE O 3 2 10 14 49 65 3 0 0 0 0 146 l l SSE O 1 4 14 50 127 74 5 1 0 0 0 276 l l 5 0 3 18 27 43 95 68 12 2 0 0 0 268 i 1 SSW 0 2 3 23 37 54 42 11 1 1 0 0 174 l
i SW 0 1 5 35 35 47 29 7 0 0 0 0 159 l I
l WSW 0 5 6 21 27 24 20 2 0 0 0 0 105 l i
l W 0 2 7 22 14 8 12 0 0 0 0 0 65 l t
l WNW 0 1 7 20 14 15 4 0 0 0 0 0 61 1 l l NW 1 2 6 18 15 18 9 1 1 0 0 0 71 l l NNW l D 2 0 14 27 47 43 4 1 0 0 0 138 l l
- i. .. . . .. . . . . . . . . ... .. ... . . . . ... .... .. . . . . ..
......l l l Total 2 27 77 59 423 915 873 104 11 1 0 0 2702 l l l 1 l Ntster of Calms for E Stability: 2 l l l l
l !
l l l Joint frequency distribution of wind speed and direction in hours 01-01-95 00:00to 12-31-95 23:59 Pasquill Class F l 1 1 I l
l Wind Speed (M/S) at 10-m level l l l Wind l l Direction.35-50 51.75 .76-101.1 1.51.6 2.0 2.13.0 3.1-5 0 5.1-7.0 71-1010.1 1313.1 18.0 >18.0 Total l
- l. .. .. . . . . .. .. . . .. ... . .. . .. .. . . ..
.l l N 0 5 12 13 15 29 6 0 0 0 0 0 80 l l l NNE 2 2 4 8 12 20 2 0 0 0 0 0 50 l l NE O 3 3 6 9 29 7 0 0 0 0 0 57 i i ENE 0 2 4 4 6 12 7 0 0 0 0 0 35 l i l E O 1 2 1 2 2 2 0 0 0 0 0 10 l j l l ESE 0 2 5 2 3 3 1 0 0 0 0 0 16 l i l SE 1 3 4 9 5 1 0 0 0 0 0 0 23 l !
I l SSE 1 5 9 24 28 24 2 0 0 0 0 0 93 l l 5 2 8 17 45 26 18 4 0 0 0 0 0 120 1 l SSW 5 10 43 68 19 4 0 0 0 0 0 0 146 l l SW 1 19 32 48 15 10 0 0 0 0 0 0 125 l l WSW 2 13 21 30 10 7 0 0 0 0 0 0 83 l l l W 4 8 31 46 10 1 0 0 0 0 0 0 100 l l
l WNW 0 4 16 36 14 1 1 0 0 0 0 0 72 l I l NW 0 3 6 16 9 2 0 0 0 0 0 0 36 l l NNW 2 2 8 8 10 10 6 0 J 0 0 0 46 l l l. .. . .. .. .. . ... . . .. .. .. . .. .
.l l Total 20 90 214 364 193 173 38 0 0 0 0 0 1092 l l l l Nuncer of calms for r Stae111ty: 4 l 1 l W21419HP 45
1 l
l TABLE 4 (4 of 4) l l JOINT FREQUENCY DISTRIBUTION ,
OF METEOROLOGICAL DATA I l
l l
1 I
l Joint frequency distribution of wind speed and direction in hours 01-0195 00.00to 12 31-95 23 59 Pasquill Class G l I
i l l Wind Speed (M/S) at 10 m Level l
l Wtnd l l l Direction .35 .50 .51.75 .761.01.1 1.51.6-2.0 2.13.0 3.15.0 517.0 7.1-1010.1-1313.1-18.0 >18.0 Total l
- l. . . .. . . . .. . . . . . . . . . . . . . . . . . .. . .. .. . .. ... .. .... . . . .. . ..
.l l N 3 5 6 6 1 0 0 0 0 0 0 0 21 l
} NNE O 4 4 3 2 0 0 0 0 0 0 0 13 l l NE O 2 2 7 2 1 1 0 0 0 0 0 15 l l ENE 0 2 2 0 1 0 0 0 0 0 0 0 5 l l E O 1 2 0 0 0 0 0 0 0 0 0 3 l l ESE O 1 0 2 0 0 0 0 0 0 0 0 3 l 2 l l l SE 2 5 2 0 1 0 0 0 0 0 0 12 l l l SSE 1 4 5 9 8 3 0 0 0 0 0 0 30 l l 5 4 8 15 23 7 2 0 0 0 0 0 0 59 l l
l SSW 8 35 52 12 0 0 0 0 0 0 0 108 l l l SW ' 7 38 34 32 7 1 0 0 0 0 0 0 119 l l WSW 9 40 25 12 1 0 0 0 0 0 0 0 87 l W 6 33 39 26 3 0 0 0 0 0 0 0 107 l WNW 9 19 23 26 5 0 0 0 0 0 0 0 62 1 NW I 11 14 2 7 4 0 0 0 0 0 0 39 l NNW 2 7 10 5 4 0 0 1 0 0 0 0 29 l Total 45 .)
185 221 207 59 14 1 0 0 0 0 0 732 l l l '
l l Number of calms for G Stability: 24 l
1 1
Total vaild hours for all stabilities - 8760 Total invaild hours for all stabiltties = 0 l
l i
l l W21419HP 46
TABLE 5 1
(1 of 2) 1 DOSE CALCULATION RESULTS FOR 1995 l
(DOSES DUE TO GASEOUS RADIOACTIVE EFFLUENTS) i Gaseous Effluent Oose Totals Cumulative Dose Information for 1995 Doses due to Noble Gases (mrad or mrem)
)
Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Total-body 5.2402e-02 1.2788e 01 1.2078e-01 6.8433e-02 3.6949e-01 skin 1.2263e-01 3.8100e 01 2.7082e-01 1.6427e 01 9.3872e-01 Air Beta 1.5849e-01 4.3046e-01 3.6121e-01 2.4065e-01 1.1908e+00 Air Ganvr.a 6.0998e-02 1.4662e 01 1.4175 e-01 8.1674e-02 4.3104e-01 1
1 Cumulative Dose Information for 1995 Doses due to Radiolodines/Particulates/ Tritium (mrem)
Age Group Infant organ Qtr 1 Qtr 2 otr 3 otr 4 Year Total Bone 1.8439e 05 4.6393e 05 3.0372e 04 9.6932e-04 1.3379e 03 Liver 1.8076e-02 5.6182e-02 7.2457e-03 1.3931e-02 9.5436e-02 Total-body 1.8060e-02 5.6142e-02 7.0448e-03 1.3293e 02 9.4540a 02 Thyroid 1.8124e 02 5.6480e-02 1.1988e 01 3.6389e 01 5.5837e-01 Kidney 1.8063e-02 5.6152e 02 7.2965e 03 1.4079e 02 9.5590e 62 Lung 1.8060e-02 5.6144e-02 6.8940e-03 1.2827e 02 9.3925e-02 Gi lli 1.8058e-02 5.6139e-02 6.9050e-03 1.2858e-02 9.3961e-02 skin 3.5427e-06 1.0995e-05 8.0743e 06 3.4436e-05 5.7047e-05 l
l l
W21419HP 47 i
TABLE 5 l (2 of 2) l DOSE CALCULATION RESULTS FOR 1995 l
(DOSES DUE TO LIQUID RADIOACTIVE EFFLUENTS) l l
l Liquid Effluent Dose Totals Cumulative Dose Information for 1995 (mrem)
A w Group i Adult organ otr 1 otr 2 otr 3 Qtr 4 Year Total Bone 1.8600e 01 4.4069e-01 3.0923e-01 3.4991e-01 1.2858e+00 Liver 3.3291e-01 7.3567e-01 5.0989e-01 6.1646e-01 2.1949e+00 Total-bod / 2.4774e-01 5.3213e-01 3.6729e-01 4.5644e-01 1.6036e+00 Thyroid 8.6111e-03 1.4795e 02 4.1183e 02 3.8040e-02 1.0263e 01 Kidney 1.1574e-01 2.5237e 01 1.7225e-01 2.0568e-01 7.4604e 01 Lung 4.4539e-02 9.1369e 02 5.9565e-02 1 6.9624e-02 2.6510e-01 GI lli 1.5753e-02 2.9973e-02 2.8983e-02 5.2234e-02 1.2694e 01 1
l W21419HP 48
1 i
i l
l J
J 4
1 4
1 I
4 i
l i
i 4
1 ATTACHMENT 10.1 l,
i A
e J
i l
i 1
l i
f i
4 1
5
. l i
4 a I i
4 3
1 1
4 i l 1
4 i 1 i
i 3
4 d.
i i
1 W21419HP 49
_ - . . _ . . i
a a_a_u-.4-a .e.aa---,-- 4--aa4-A-.--- .au eae4_ am m a- . _ _a- __.._m. ---- - , - - - - - - _.,___---__,________ ___ __
- d. -,- a- ~ _ __.A_-_&._.---sa-- e -_AAm.m = --
a CHANGES TO OFFSITE DOSE CALCULATION l MANUAL (ODCM)
PROCEDURE No. (UNT-005-014) ;
h a
J A
W21419HP 50
The following are the description of changes for Offsite Dose Calculation Manual (UNT-005-014. Revision 4):
1-
Purpose:
l 1.1 Format change.
1.2 & 1.3 These two steps were changed to NOTES in pages 32 and 61 prior to the calculation methodology sections 5.3.4 and 5.4.5.
2-
References:
l 2.1 All Technical Specifications that related to this manual are referenced in this step.
2.8,2.9 &2.10 Re-arranged the step numbers. ;
2.12 & 2.13 Add two new references which were only referenced in the Liquid and Gaseous effluent Bases sections 5.3.8 and 5.4.10, but were not listed in section 2 of the manual i 3- Definitions:
- Add the corresponding Technical Specification number to each definition.
- Deleted the OPERATIONAL MODE definition (step 3.8) and re-numbered the following steps.
- Defined Liquid Radwaste Treatment System, step 3.15.
- Revised the MAJOR CHANGE definition (step 3.16) to clarify that it is a Change to radioactive waste system requiring re-evaluation of the effluent l source terms.
- Deleted the LLD definition from Tables 5.3.1,5.4.1 & 5.8.3 notations and add the final LLD definition as step 3.17 in this section.
4- Responsibilities:
4.2 & 4.3 Steps were combined to reflect the new organizational change.
W21419HP 51
l 5- Procedure:
5.1 Site Characteristics Information is provided in the FSAR chapter 2 and is only referenced in this manual.
5.2.4 Administrative change 5.2.6 Add procedures titles.
l 5.3.1 Bolded some words to make it visible to the reader. l Table 5.3.1 was completely revised to be clear for the users
, the sampling and analysis requirements for each release type and avoid using the frequency abbreviation. Also, this change clearly reflects the site specific release points and numbers. The LLD limits were combined as notation a of this I
table. The Table notations were revised and stream lined with the release type to make it easier to use. The frequency of sample analysis were changed to ' prior to release' for some release type such as secondary holding tanks.
5.3.2 Format changes and add NOTE to specify the applicable condition for step 2 in ACTION for special report.
5.3.3 Format changes l
5.3.4 Add two NOTES that were listed as steps 1.2 and 1.3 in Revision 3 of this manual. I i 5.3.4.1 Add change 1 of the procedure Revision 3.
5.3.4.2 Arranged the equation 3 items to be in order and revised NOTE to reference a new attachment 6.20 which was added in this revision, for the appropriate dose factors for the other 4
liquid pathways.
4 W21419HP 52
1 5.3.5 Combined two equations (4 and 4a) into one equ2 ion (4) to calculate setpoints for any condition with or without additional dilution prior to withdrawal of the monitored fluid at the monitor location. Also revised the NOTE to state that F'= 0 if no additional dilution and defined its value for specified release types. The missing Cj definition is added.
5.3.7 Format changes
~
5.3.8 Format changes 5.4.1 Format changes
- Table 5.4.1 was completely revised to be clear for the users what is the sampling and analysis requirements for each release type and avoid using the frequency abbreviation.
Also, this change clearly reflects the site specific release points and numbers. The LLD limits were combined as ;
notation "a"of this table. The Table notations were revised l and stream lined with the release type to make it easier to use. l 5.4.2 Format changes 4 5.4.5 Add two NOTES that were listed as steps 1.2 and 1.3 in Revision 3 of this manual.
I 5.4.5.1 Administrative Arrangement of the equations 5,6&7 items to be in order and refers to Attachment 6.2 for X/Q item. Add new Attachment 6.19 from R.G.1.109 and refers to use it for Pa.
5.4.6.1 Format changes 5.4.7 Format changes 5.4.8.4 & 5.4.8.5 List effluent flow rate in CFM and use unit factor in equations 16 and 15 to convert it to cc/sec.
W21419HP 53
4 i
1 j 5.4.10 Format changes j 5.5.1 Format changes j 5.6.1 Add "daring releases to the environment" to the 5
Instrumentation Specification and Actio.7 Also, add to Action "or change the setpoint so it is acceptable conservative". This
{ change to assure that the limits of Specification 5.3.1 are met, during actual releases Tables 5.6-1 is completely revised to be clear for the users what are the applicability requirements for each release type f instrument and using the Action that represent the condition
- of the specific system. The Table notations were revised and j stream lined with the release type to make it easier for use.
3 NOTES were added for specific monitors requirements.
i Tables 5.6-2 is completely revised to be clear for the users what is the surveillance requirements for each release type ;
j- instrument and avoid using the frequency abbreviation.
Add a new column to specify the condition in which these 2
surveillance's are required. The Table notations were revised j and to make it easier for use with the specific release system.
5.6.2 Add "during releases to the environment" to the
! Instrumentation Specification and Action. Also, add to Action 1
l-t "or change the setpoint so it is acceptable conservative". This l change to assure that the limits of Specification 5.4.1 are met, j during actual releases 4
Tables 5.6-3 is completely revised to be clear for the users !
l what are the applicability requirements for each release type
- instrument and using the Action that represent the condition !
- of the specific system. The Table Actions were revised and stream lined with the specific sampler / monitor channels to
- make it easier for use. One NOTE was added for specific
- samplers requirements.
1 W21419HP 54 l
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! Tables 5.6-4 is completely revised to be clear for the users l 4
l what are the surveillance requirements for each release type j l instrument and avoid using the frequency abbreviation. i
! Add a new column to specify the condition in which these surveillances are required. The Table notations were revised i and to make it easier for use with the specific release system.
l 5.8.1 Format changes Table 5.8-1 Format changes Table 5.8-2 Format changes Table 5.8-3 Format changes and changed the LLD for Ba-140 and Zr-95 to be as specified in the Radiological Assessment Branch Technical Position Revision 1 (November 1979) document.
The LLD notation were transferred to definition section step 3.17 l'
- 5.8.3 Format change, 5.9 Technical Specification cross-references and its Attachment have been deleted. All the following section are re-numbered.
5.10 Changed to 5.9 with Format changes, 5.9.1.7 Refers to Specification 5.4.1 and Technical Specification 3.11.1.4 which were only listed in Revision 3, steps 5.10.1.7 and 5.10.1.8 without indication to the specification sources.
5.9.1.11 Combined two steps from Revision 3 (5.10.1.12 and 5.10.1.13) for Liquid and Gaseous effluent monitoring instrumentation's.
5.11 Changed to 5.10 with Format changes, step 5.10.1 Consolidated special report actions for all specification l requirements.
W21419HP 55
. . _ _ _ _ _. _ _ _ . _ _ __ _~__ _ . _ _ . _ _ _ .
Attachments:
Attachment 6.4 Format change.
Attachment 6.11 Format change for clear flow charts. !
Attachment 6.12 Format change for clear flow chart.
Attachment 6.13 Format change. Add sanitary system sample and notation 12 to indicate that it is not a REMP requirement but it represents possible environmental interface with the plant.
Attachment 6.14 Format change. Revised description for TLD sample location D-2. Add sewage sample SWR-1 and corresponding notation. l Attachment 6.16 Format change for clear map. !
Attachment 6.17 Format change for clear map.
Attachment 6.18 Format change for clear map. !
Attachment 6.19 Deleted.
Attachment 6.19 New Tablea for dose factors Pi for radionuclides other than ,
noble gases for all ages groups.
Attachment 6.20 New Tables for dose conversion factors (Inhalation and Ingestion factors) for all age groups. These Tables l were obtained from Regulatory Guide 1.109 Tables E-7 !
through E-14.
Attachment 6.21 Old Attachment 6.20 was revised. The new Attachment lists all the site specific factors that are used in Waterford 3 ,
effluent program and were obtained from Regulatory Guide 1.109.
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1 l Copy of 1
i OFFSITE DOSE CALCULATION MANUAL
) (ODCM) PROCEDURE i
UNT-005-014
- Revision 4 j (153 pages) 1 l
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PORC/PORC-SC UNT-005-014 REVISION 4 EFFECTIVE DATE SAFETY-RELATED ADMINISTRATIVE PROCEDURE OFFSITE DOSE CALCULATION MANUAL UNT-001-002 Revision 13 Attachment 6.3 (1 of 2) 48
PORC AND PORC - S/C REVIEW AND APPROVAL SHEET REVIEW 0F: UNT-005-014 - Offsite Dose PORC DD G lcylation Manual (Rev. 4) PORC - S/C O The PORC or PORC S/C has reviewed this item and determined that a Safety /
Commitment Review was performed (if applicable), that a Safety Evaluation was performed (if applicable), that an unreviewed safety question 60es not exist, and that nuclear safety is/was not adversely affected.
PORC RECOMMENDED FOR APPROVAL MEMBER MEMBER SIGNATURE YES NO Maintenance Superintendent 8W Mj0nv #
er dent Radiation Protection V '
Superintendent (./M^4 MM Y g7 E '""
hg y /
Mgmt Knowledgeable /p /
in Engineering .1 .
t W J Manager Operations &
Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member l
Meeting No.95-017 Item No. VI-D Date: 4/6/95 This item is recommended for approval? DD YES O NO This item requires SRC/NRC review prior to implementation? O YES 0D NO If yes, ensure documentation supporting review is attached.
SIGNATURE RECOMMENDED FOR APPROVAL YES NO DATE PORC-S/C Chairman PORC Chairman Alh-1,G\ V // %
O Comments:
Approved by W u % N / v Date 4lrz/(d General Manager Plant Operations UNT-001-004 Revision 14 23 Attachment 6.1 (1 of 1)
1 Check Block WATERFORD 3 SES l X l PORC PLANT OPERATING MANUAL l l PORC-S/C REQUEST / APPROVAL PAGE ;
l l DEPT.
1 Procedure No.: UNT-005-014
Title:
0FFSITE DOSE CALCULATION MANUAL j l
Effcctive Date: (If different from approval date) l COMPLETE A, B, C, and D:
A. Change No.: N/A l l Permanent l l Deviation Expiration Date:
B. Revision No.: 4 C. Deletion: l l YES l X l NO D. Temporary Procedure: l l YES l X l NO Expiration Date:
DESCRIPTION OF CHANGE, REVISION, OR DELETION:
THIS IS A MAJOR FORMAT CHANGE OF THE OFFSITE DOSE CALCULATION MANUAL (0DCM) PROCEDURE.
CHANGES TO EACH SECTION OF THE ODCM PROCEDURE IN THIS REVISION ARE LISTED IN THE ATTACHED PAGES. NO MARGIN LINES ARE USED.
.any .
REASON FOR CHANGE, REVISION, OR DELETION:
THIS REVISION IS TO MAKE THE ODCM PROCEDURE FORMAT EASIER TO USE BY ALL PERSONNEL AND TO AVOID ANY CONFUSION WHEN WE APPLY THE RADIOLOGICAL EFFLUENT AND ENVIRONMENTAL SPECIFICATIONS REQUIREMENTS. IT WILL MAINTAIN THE SAME CURRENT CONTROL LEVEL OF THE RADIOLOGCAL EFFLUENT AND ENVIORONMENTAL MONITORING PROGRAMS AT WATERFORD 3 SITE.
AUTHOR \0RIGINATOR: Samir Ramzy r/Am W AMe.ftV DATE: 3l6lW TECHNICAL REVIEW: Greg Hood b/, h DATE: 51595-GROUP HEAD REVIEW: Jerry Ridge O [ DATE: JMC/if
- TEMPORARY APPROVAL (SRO): N/A DATE:
- TEMPORARY APPROVAL: N/A DATE:
APPLICABLE CONDITIONS (Temporary procedures only):
- Refer to paragraphs 3.2.18 and 3.2.19 for tenporary approval requirements.
UNT-001-003 Revision 17 Attachment 6.5 (1 of 1)
l Administrative Procedure UNT-005-014' Offsite Dose Calculation' Manual Revision 4 i
TABLE OF CONTENTS l
1.0 PURPOSE
2.0 REFERENCES
]
l 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1 Site Characteristics )
5.2 Specifications and Surveillance Requirements j 5.3 Liquid Effluents l 5.4 Gaseous Effluents 5.5 Total Dose j 5.6 Instrumentation .
5.7 Liquid and Gaseous Radwaste. Processes 5.8 Radiological Environmental Monitoring Program Requirements 5.9 Routine Effluent Release Reports 5.10 Special Effluent Reports 5.11 Secondary Release Faths 1 6.0 ATTACHMENTS 6.1 Site Boundary for Radioactive Gaseous and Liquid Effluents 6.2 Historical Average Dispersion and Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary 6.3 Site Related Liquid Ingestion Dose Commitment Factors (Aj) for Individual Nuclides 6.4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 6.5 Inhalation Pathway Doses Due to Radionuclides Other Than Noble Gases, Ri 6.6 Ground - Plane Deposition Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Ri l
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 1
1 6.7 Cow's isilk Pathway Dose Factors Due to Radionuclides Other Than l
l Noble Gases, Ri 6.8 Meat Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R t-6.9 Leaf Vegetable Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Rj 6.10 Goat's Milk Pathway Dose Factors Due to Radionuclides Other l Than Noble Gases, Ri 6.11 Liquid Waste Management System Effluent Sources and Release l Pathways and Points l 6.12 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources and Exhaust Release Points 1
6.13 Radiological Environmental Monitoring Program '
6.14 Sample Location Table 1
6.15 Sector and Zone Designators for Radiological Sampling and l Monitoring Points
! 6.16 REMP Sampling Locations Within 2 Miles of Waterford 3 6.17 REMP Sampling Locations Within 10 Miles of Waterford 3 l 6.18 REMP Sampling Locations Within 50 Miles of Waterford 3 l 6.19 Dose Factors Due to Radionuclides other than Noble Gases, Pi ,
)
6.20 Dose Conversion Factors for All Age Groups by Nuclide l
(Inhalation and Ingestion) 6.21 Specific Factors used to Determine Aj, Pj and Rj Values for the Offsite Dose Calculation Manual i LIST OF EFFECTIVE PAGES Title Revision 4 1-301 Revision 4 l
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
1.0 PURPOSE l 1.1 The Offsite Dose Calculation Manual (0DCM) is a supporting ,
document of the Waterford 3 Technical Specifications. This document provides:
(1) The Radiological Effluent Specifications and Radiological Environmental Monitoring Program required by Technical Specification 6.8.3; (3) The detailed Radiological Environmental Monitoring Program (REMP);
(4) the description of the Radiological Environmental j Monitoring Interlaboratory Comparison Program; (5) The liquid and gaseous radwaste block flow diagram; (6) The Radioactive Liquid and Gaseous Waste Sampling and Analysis Programs; (7) The general methodology to be used to calculate dose to ;
individuals due to releases of radioactive gaseous and liquid effluents from the Waterford 3 site; (8) The general methodology to be used to calculate effluent l monitor setpoints and allowable release rates to ensure compliance with the Radiological Effluent Controls, 10CFR20, and 10CFR50 criteria; (9) The methodology to be used to ensure representative sar.pling of liquids; and (10) the methodology to be used to comply with 40CFR190 criteria.
3
Administrative Procedure UNT-005-014 :
Offsite Dose Calculation Manual Revision 4 l l
2.0 REFERENCES
2.1 Waterford 3 SES Technical Specifications (T.S.), Chapter 16 of Waterford 3 FSAR.
t i 2.1.1 T.S. 6.14, Offsite Dose Calculation Manual. ,
2.1.2 T.S. 6.9.1.7, Annual Radiological Environmental Operating Report.
2.1.3 T.S. 6.9.1.8, Annual Radioactive Effluent Release Report.
2.1.4 T.S. 3/4.11.1.4, Liquid Holdup Tanks. i l
l l 2.1.5 T.S. 3/4.11.2.6, Gas Storage Tanks.
2.1.6 T.S. 5.1.3, Map Defining Unrestricted Areas for Radioactive Gaseous and Liquid Effluents.
l t 2.1.7 T.S. 6.9.2, Special Reports l
2.1.8 T.S. 6.10.3 (d, o & p), Record Retention.
2.1.9 T.S. 6.5.2.8, (m, n & o), Audits.
l 2.2 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Gaseous-Effluents from Light-Water-Cooled Reactors, July 1977.
l 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of
- Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.
4 l
Administrative Procedure UNT-005-014
- Offsite Dose Calculation Manual Revision 4 i 2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to '
Man from Routine Releases of Reactor Effluents for the Purpose l
of Evaluating Compliance with 10CFR Part 50, Appendix I, ;
Revision 1, October, 1977. !
i 2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978, i
2.6 Code of Federal Regulations: Title 10, Parts 20, 40, 50 and 100; Title 40, Part 190. l 2.7 USNRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical I Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process .
Control Program. !
i 2.8 International Atomic Energy Agency (IAEA) Safety Series No.57, ;
Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, Exposures of Critical Groups. I 2.9 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radir activity in Solid Wastes and Releases of Radioactive Mate"ials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants, Revision 1, June, 1974.
2.10 UNT-006-010, Event Notification and Reporting 2.11 UNT-006-011, Condition Report 5
Adainistrative Procedure UNT-005-014 Offsite Dose Calculatien Manual Revision 4 2.12 HASL-300, HASL Procedures Manual; Currie, L.A., " Limits for ;
j Qualitative Detection and Quantitative Determination Application to Radiochemistry", Anal Chem. 40, 586-93, (1968).
2.13 ARH-SA-215, Hartwell, J.K.," Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hardford Company Report, (June 1975) l l
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Administrative Pracidure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
3.0 DEFINITIONS l 3.1 ACTION (T.S.1.1) shall be that part of a Specification which prescribes remedial measures required under designated l conditions.
3.2 CHANNEL CALIBRATION (T.S. 1.4) shall be the adjustment, as necessary, of the channel output such that is responds within l l
the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, and total channel steps such that the entire channel is calibrated.
3.3 CHANNEL CHECK (T.S.1.5) shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring i the same parameter. l 3.4 CHANNEL FUNCTIONAL TEST (T.S.1.6) shall be:
- a. Analog channels - the injection of a simulated signal i into channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm l
and/or trip functions.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual R: vision 4
)
l c. Digital computer channels - the exercising of the l i
l digital computer hardware using diagnostic programs and I l the injection of simulated process data into the channel l to verify OPERABILITY including alarm and/or trip l function, l i
l 3.5 The FREQUENCY NOTATION, (T.S. 1.13) specified for the performance j l
of Surveillance Requirements shall correspond to the following ;
l interval s. I l \
l NOTATI0li FREQUENCY j S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 1 l
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. !
W At least once per 7 days.
M At least once per 31 days.
j P Completed prior to each release.
Q At least once per 92 days.
SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup. I
- N.A Not appliable.
3.6 MEMBER (S) 0F THE PUBLIC (T.S.1.15) shall include all persons who are not occupational associated with the plant. This category does not include employees of the licensee, its contractors, or vendor. Also excluded from this category are persons who enter the site to service equipment or make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
8
l l' Administrative Procedure UNT-005-014' Offsite Pose Calculation Manual Revision 4 3.7 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY (T.S.1.17) when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, required l for the system, subsystem, train component, or device to l perform its function (s) are also capable of performing their related support function (s).
3.8 PURGE or PURGING (T.S.1.23) shall be the controlled process of discharging air or gas from a confinement to maintain temperature, presure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
3.9 The SITE BOUNDARY (T.S.1.29) shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
3.10 SOURCE CHECK (T.S.1.32) shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
3.11 UNRESTRICTED AREA (T.S.1.36) shall t'e any area at or beyond I the SITE B0UNDARY, access to which is not controlled by the licensee for purposes of protectiot, of individuals from exposure to radiation and radioactive materials, or any area ' I within the SITE BOUNDARY used for residential quarters or for l industrial, commercial, institutional, and/or recreation ,
purpose. This definition is applicable to areas established for effluent release limits. See Attachment 6.1.
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Administrative Procedure UNT-005-014
. Offsite Dose . Calculation Manual Revision 4 3.12 VENTILATION EXHAUST TREATMENT SYSTEM (T.S.1.37) shall be any system designed and installed to reduce gaseous radiciodine or-radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal ;
adsorbers and/or HEPA filters for the purpose of removing 1 iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not ;
considered to have any effect on noble gas effluents.
. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. j 1
.(
l 3.13 VENTING (T.S.1.38) shall be'the contro11ed process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
3.14 WASTE GAS HOLDUP SYSTEM (T.S.1.39) shall be any system designed and installed to reduce radioactive gaseous effluents by collecting coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
3.15 LIQUID RADWASTE TREATMENT SYSTEM, shall be any system designed and installed to reduce radioactive material in effluents by passing liquid waste through filters and/or absorption or exchange media (e.g. Ion Exchanger Resin, Charcoal etc) and/or other reduction processes (e.g. reverse osmosis, etc) for the purpose of removing radioactive materials from the liquid system prior to the release to the environment.
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i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 1
3.16 A MAJOR CHANGE to a radioactive waste system shall be any ;
alteration or modification to the system that causes waste characteristics (e.g. chemical composition, pH, etc.), waste form or waste activity (e.g. equipment decontamination factor !
change) in liquid, gaseous, or solid effluents to change, I thereby requiring a re-evaluation of the effluent source terms.
I 3.17 LOWER LIMITS OF DETECTION (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
It should be recognized that the LLD is defined as an a oriori !
(before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.
For a particular measurement system, which may include radiochemical separation:
4.66 s 3 l tto _
E V 2. 22 x los , y , ,-w j
Where: l LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 11
Ad inistrative Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fraction radiochemical yield, when applicable, #
A is the radioactive decay constant for the particular radionuclide,
.and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. For environmental samples it is the elapsed time between sample collection, or end of the smaple collection period, and time of counting.
Typical salues of E, V, Y, and At should be used in the calculation.
k
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Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l l
4.0 RESPONSIBILITIES l
4.1 General Manager, Plant Operations has lead responsibility for.
ensuring implementation of the Radiological Effluent j Specifications and Radiological Environmental Monitoring l l Program as required by Technical Specification 6.8.3 and as set i forth in this procedure. !
4.2 The Radiation Protection Superintendent is responsible for a) ensuring Radiological Effluent Specifications, the ;
Radiological Effluent Monitoring Program and Radiological Environmental Monitoring Program (REMP) are performed as required according to procedures and methodologies established by this document.
b) ensuring the Annual Effluent Release Report and Annual Environmental Report are performed and issued as required.
c) ensuring the Land Use Census is performed as required.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.0 PROCEDURE I 5.1 SITE CHARACTERISTICS !
Waterford 3 SES Site Characteristics is provided in Chapter 2 of Waterford 3 FSAR (Sections 2.1.1, 2.1.2 and 2.1.3).
A map of the SITE BOUNDARIES for establishing effluent release limits along with radioactive effluent release points are given in )
Attachment 6.1. The release point elevations for gaseous effluents are also provided in Attachment 6.1. The nearest distances to the boundary line are shown in Attachment 6.2 of this procedure.
The Restricted Area, defined for the purpose of controlling access for the purpose of protecting individuals against undue risks from radiation and radioactive materials, coincides with the current or future Security Protected Area fence.
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Administrative Proc: dure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.1 Compliance with the SPECIFICATIONS contained in the succeeding sections is required during the conditions specified therein; except that failure to meet the '
SPECIFICATIONS requires that the associated ACTION requirements shall be met.
5.2.2 Noncompliance with this procedure shall exist when the requirements of the SPECIFICATION and/or associated ACTION requirements are not met within the specified time intervals. If the SPECIFICATION is restored prior j to expiration of the specified time intervals, completion of the ACTION requirements is not required. l 1
5.2.3 Surveillance Requirements shall be applicable during all conditions specified for individual systems unless otherwise stated in an individual Surveillance Requirement.
5.2.4 Each Surveillance Requirement shall be performed within j the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. :
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l l Ad2inistrative Precedure UNT-005-014 Offsite Dase Calculation Manual Revision 4 l
- 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS Cont'd 1
l 5.2.5 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure -
to meet the OPERABILITY requirements for a Specific l Systen for Operation. Exceptions to these requirements ]
are stated in the individual specifications. ,
Surveillance Requirements do not have to be performed ]
on inoperable equipment. l l 5.2.6 Failure to comply with the compensatory ACTION !
requirements or failure to complete the surveillance requirements within the specified time shall be documented and evaluated in accordance with UNT-006-011, Condition Report and UNT-006-010, Event Notification and Reporting procedures.
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Administrative Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 P
P 5.3 LIQUID EFFLUENTS ,
5.3.1 Concentration Specification The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Attachment 6.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or_ entrained noble gases, the concentration shall be limited to 2 x 10-4 microcurie /m1 total activity.
APPLICABILITY: At all times ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report.
SURVEILLANCE REOUIREMENTS
- a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 5.3-1.
- b. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in section 5.3.5 to assure that the concentrations at the point of release are maintained within the limits of Specification 5.3.1.
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! Offsite Dose Calculation Manual Revision 4 l i
, TABLE 5.3-1 ,
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS IYELDE AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
BATCH RELEASES [d]
- 1. Boric Acid Grab sample from each Prior to Gamma Emitters [b]
batch to be released release I-131 Condensate Tanks prior to release Noble Gases (4 Tanks) l A Composite [c] of Monthly H-3 all grab samples Gross Alpha collected during the month for this release point.
A Composite [c] of Quarterly Sr-89 all grab samples Sr-90 collected during the Fe-55 quarter for this release point.
- 2. Liquid Waste Grab sample from each Prior to Gamma Emitters [b]
batch to be released release I-131 Management Tanks Noble Gases prior to release
[2 Waste Condensate Tanks 2 Laundry Tanks A Composite [c] of Monthly H-3 all grab samples Gross Alpha 3 Waste Tanks ] collected during the month for this )
release point. '
A Composite [c] of Quarterly Sr-89 all grab samples Sr-90 l collected during the Fe-55 l quarter for this release point.
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l j Administrative Procedure UNT-005-014 j Offsite Dose Calculation Manual Revision 4
[
~
TABLE 5.3-1 (Continued)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIOUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF
- ! AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
BATCH RELEASES [d,91 l
l \
l 3. Secondary Plant Grab sample from each Prior to Gamma Emitters [b] !
- batch to be released release I-131 Holding Tanks [f]
' prior to release Noble Gases
[ Regenerative Waste H-3 Tank and l Filter Flush Tank]
i j 4. Turbine Building Grab sample from each Prior to Gamma Emitters [b]
! batch to be released release I-131 Industrial Waste Noble Gases j prior to release Sumps (2 Sumps)
' A Composite [c] of Monthly
[TBIWS] H-3
, all grab samples Gross Alpha l For applicability, see collected during the i note [i] month for this i release point.
l A Composite [c] of Quarterly Sr-89 I
all grab samples Sr-90 l collected during the Fe-55 i quarter for this i release point.
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4 4
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! Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4
[
TABLE 5.3-1 (Continued)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
BATCH RELEASES [d,91 l
- 5. Dry Cooling Tower Grab sample from each Prior to. Gamma Emitters [b]
batch to be released release I-131 Sumps #1 and #2 prior to release Noble Gases l [DCTS] A Composite [c] of Monthly H-3 l all grab samples Gross Alpha i
For applicability, see collected during the note [j] month for this release point.
A Composite [c] of Quarterly Sr-89 all grab samples Sr-90 collected during the Fe-55 quhrter for this release point.
! 6. Steam Generator Grab sample from each Prior to Gamma Emitters [b]
batch to be released release I-131 l
Blowdown prior to release Noble Gases A Composite [c] of Monthly H-3 l
For applicability, see all grab samples Gross Alpha notes [k 11] collected during the month for this release point.
A Composite [c] of Quarterly Sr-89 all grab samples Sr-90 collected during the Fe-55 l quarter for this release point.
i 20 l
l 4
4 Administrative Procedure UNT-005-014 I f
offsite Dose Calculation Manual Revision 4
! 1 i TABLE 5.3-1 (Continued)
- RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l LI.00ID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
BATCH RELEASES Id.9) i i
! 7. Auxiliary Component Grab sample from each Prior to Gamma Emitters [b]
batch to be released release t-131 i Cooling Water prior to release Noble Gases System [ACCW]
- (2 Basins)
! A Composite [c] of Monthly H-3 For applicability, see all grab samples Gross Alpha
- note [n] collected during the i month for this i release point.
A Composite [c] of Quarterly Sr-89 l all grab samples Sr-90 l collected during the Fe-55 )!
- quarter for this l release point.
i 5
4 i
1 l 21 i
)
i
)
l Administrative Procedure UNT-005-014 offsite Dose Calculation Manual Revision 4
) TABLE 5.3-1 (Continued)'
! RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 1
- LIQUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF j AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
j CONTINU0US RELEASES [e,h]
i 4
- 1. Turbine Building Weekly grab sample Weekly Gamma Emitters [b]
l Industrial Waste $ g,,,3 j Sumps (2 Sumps)
[TBIWS] A Composite [c] of Monthly H-3
- all grab samples Gross Alpha
- For applicability, see collected during the
! note [1] month for this release point.
l A Composite [c] of Quarterly Sr-03
- all grab samples Sr-90 l collected during the Fe-55
) quarter for this 4
release point.
a i
- 2. Dry Cooling Tower Weekly grab sample Weekly GagEmitters[b]
j Sumps #1 and #2 Noble Gases l [DCTS] A Composite [c] of Monthly H-3 all grab samples Gross Alpha '
! For applicability, see collected during the j note [j] month for this release point.
4
{
A Composite [c] of Quarterly Sr-89
- all grab samples Sr-90 j collected during the Fe-55 j quarter for this
{
release point.
i' 22 4
Administrative Procedure UNT-005-014 offsite Dose Calculation Manual Revision 4 I
TABLE 5.3-1 (Continued)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PP0 GRAM LIQUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
CONTINUOUS RELEASES [e.h1 Weekly grab sample Weekly
- 3. Circulating Water g Emitters [b] l Discharge- Stream Noble Gases Generator Blowdown Heat Exchanger Discharge [CWD] A Composite [c] of Monthly H-3 all grab samples Gross Alpha For applicability, see collected during the month for this note [o] release point.
A Composite [c] of Quarterly Sr-89 l all grab samples Sr-90 collected during the Fe-55 quarter for each release point.
- 4. Auxiliary Component Weekly grab sample Weekly Ga m Emitters [b] l Cooling Water Noble Gases System [ACCW] A Composite [c] of"^ Monthly H-3 all grab samples Gross Alpha (2 Basins) collectea during the For applicability, see month for this release point.
note [nl A Composite [c] of Quarterly Sr-89 all grab samples Sr-90 collected during the Fe-55 quarter for each release point.
23
~ -. . - ., . - _ ,
i i
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.3-1 (Continued)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
CONTINU0US RELEASES [e.hl Continuous [m] sample Weekly Gamma Emitters [b]
- 5. Steam Generator I-131 collected weekly Blowdown Noble Gases A Composite [c] of Monthly H-3 For applicability, see all weekly samples Gross Alpha note [k 11] collected during the month for this release point.
A Composite [c] of Quarterly Sr-89 all weekly samples Sr-90 collected during the Fe-55 quarter for this release point.
24
i l
l l l
.)
Administrative Procedure UNT-005-014 i Offsite Dose Calculation Manual Revision 4 TABLE 5.3-1 (Continued) '
TABLE NOTATIONS I
?
l
- a. The type of analysis and their associated Lower Limits of Detection.
l (LLD) are:
Type of Analysis LLD ( C1/ml) l Gamma Emitters SE-07 I-131 IE-06 Noble Gases (Gama Emitters) 1E-05 l
H-3 IE-05 Gross Alpha IE-07 Fe-55 IE-06 Sr-89, Sr-90 5E-08 L b. The camma emitters LLD specification includes the following ,
j radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, I Cs-137, Ce-141, and Ce-144. The analysis for gama emitters shall include an analysis for I-131 and gama emitting noble gases dissolved or entrained in the sample at the LLD's specified above.
l This list does not mean that only these nuclides are to be considered. Other identifiable gama peaks, together with the above l nuclides, shall also be analyzed and reported in the Annual l Radioactive Effluent Release Report.
1 l c. A composite sample is one in which the quantity of liquid sampled is ]
i proportional to the quantity of liquid waste discharged and in which l the method of sampling employed results in a specimen that is l representative of the liquids released. Prior to analyses, all samples taken for composites are to be thoroughly mixed in order for the composite sample to be representative of the effluent release.
l .l
- d. A batch release is the discharge of liquid wastes of a discrete !
volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.
- e. A continuous release is the discharge of liquid wastes of a i non-discrete volume, e.g., a system that has input flow during the release (in service sumps, etc).
25
l l
l Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 ,
i TABLE 5.3-1 (Continued) !
l I TABLE NOTATIONS 1
1 1
- f. If the contents of the Recenerative Waste Tank or Filter Flush Tank contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA, and the contents of these tanks shall be directed to the Liquid Waste Management System.
- g. When release from this source is batch in nature.
- h. When release from this source is continuous in nature.
- 1. The Turbine Buildina Industrial Waste Si=as (TBIWS) shall be sampled and analyzed in accordance with this table if any of the folowing conditions exist, and the release has NOT been directed to the Liquid Waste Management System:
(1) Primary to Secondary leakage is occurring; or, )
(2) Activity is present in the secondary system as indicated by either the Steam Generator Blowdown (SGB) monitor or secondary sampling and analysis; or, ;
(3) Activity was present in the TBIWS during the previous FOUR Weeks.
- j. The Dry Coolina Tower SumD (DCTS) shall be sampled and analyzed in accordance with this table if any of the folowing conditions exist, and the release has NOT been directed to the Liquid Waste Management System:
(1) Primary to Component Cooling Water (CCW) leakage is occurring or, (2) Activity is present in the CCW/ACCW systems as indicated by either the CCW monitors or CCW/ACCW sampling and analysis; or, (3) Activity was present in the DCTS during the previous FOUR Weeks.
- k. Sampling and analysis of Steam Generator Blowjor will be required only when blowdown is directed to the Circulating Water System (CWS)
! or the Waterford Waste Ponds.
1 1
26
Administrative Procedure UNT-005-014 Offsite Dose. Calculation Manual Revision 4 TABLE 5.3-1 (Continued) .
TABLE NOTATIONS ,
- 1. Steam Generator Blowdown discharae to the Waste Ponds shall not be performed unless radiation monitoring and automatic isolation ~ !
capabilities are added to the Waste Ponds discharge path. Steam ;
Generator Blowdown to the Waste Ponds will be limited to situations '
requiring secondary chemistry control where the Circulating Water System is not available or the secondary chemistry is outside the requirements for Circulating Water System discharge.
Blowdown to the Waste Ponds will be terminated upon detection of sample activity greater than the LLD levels in Notation [a). l
- m. To be representative of the quantities and concentration of i radioactive raterials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent '
stream.
- n. Sampling and analysis of the Auxiliary Comoonent Coolina Water (ACCW) :
system is required when detectable activity exists in the CCW system.
Continued sampling and analysis of ACCW is required for a minimum of FOUR Weeks following non-detection of activity in CCW/ACCW l systems,
- o. Sampling and analysis of the Circulatina Water Discharoe -Steam Generator Blowdown heat exchanner discharae (CWD) is required when ,
detectable activity exists in the secondary system, or the CCW/ACCW i Systems. l t
3 27
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd) 5.3.2 Dose Soecification The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Attachment 6.1) shall be limited: l
- a. During any calendar quarter to less than or equal to 1.5 arem to the total body and to less than or equal to 5 arem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 arem to any organ.
APPLICABILITY: At all times.
i l
28
Administrative Procedure UNT-005-014 Offsite Dose Caletdation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd) l ACTION: l
- a. With the calculated dose from the release of j radioactive materials in liquid effluents exceeding j any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report. This Special 1 Report shall: l l
- 1) Identify.the cause(s) for exceeding the limit (s) and define the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
NOTE The following step is applicable only if drinking water supply is taken from the receiving water.
- 2) Include the results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.
SURVEILLANCE REOUIREMENTS: I
- a. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with methodology and parameters in l Section 5.3.7 at least once per 31 days.
29
AdJinistrative Proceduro UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd) 5.3.3 Liouid Radwaste Treatment System Specification The LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Attachment 6.1) would exceed in a 31 day period:
a) 0.06 mrem to the total body, or b) 0.2 mrem to any organ APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days pursuant j to Technical Specification 6.9.2 a Special Report l that includes the folicwing information.
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
30
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
SURVEILLANCE RE0VIREMENTS
- a. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Section 5.3.7.
- b. The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Specifications 5.3.1 and 5.3.2.
31
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd) 5.3.4 Liauid Effluent Dose Calculation l l
NOTE The Offsite Dose Calculation Manual (0DCM) follows the general models suggested by NUREG 0133 and Regulatory Guide 1.109. However, alternate calculation methods from those presented may be used provided the overall methodology is acceptable and consistent with regulation or provided the l
alternate methodology is conservative. In addition, the most up-to-date dose conversion factors and bioaccumulation factors may be substituted in lieu of Regulatory Guide 1.109 values.
NOTE Actual step-by-step dose calculations will be performed by in-plant ;
procedures which are cecistent with the methodology presented in this document.
i 5.3.4.1 The dose commitment to an individual from radioactive materials in liquid effluents
, released to unrestricted areas are calculated for I the purpose of implementing Section 5.3.2 using the following expression:
Dti = 4t t (1) l
,F k, A it C,, .
a
! D = ID t tt (2)
[
roi h
32 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 i
(
5.3 LIQUID EFFLUENTS (cont'd)
= the cumulative dose commitment to the Ott total body or any organ (t) from the '
liquid effluents for each liquid release in mrem during time period (t);
Dt =
the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for all (t) time periods; At t= the length of the tth time period over which the release is made, in hours; Cit
=
the concentration of radionuclide (i) in undiluted liquid effluent during time Period Atg from any liquid release, in
- Ci/ml; Ait = the site-related liquid ingestion dose commitment factor to the total body or any organ (t) for each identified nuclide (i) in mrem-ml/hr- #Ci (Attachment 6.3), and; l
33 1
Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
F g
= the near field average dilution factor for Cje during any liquid effluent release.
Defined as the ratio of the undiluted liquid waste flow during release to the average flow from the site discharge structure to site boundary receiving waters.
_ liquid radioactive waste flow
~
discharge structure exit flow The liquid radioactive waste flow is the maximum flow from the effluent release.
The discharge structure exit flow is the flow during disposal from the discharge structure release point into the receiving water body. For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by using a ratio of concentrations based on the previous monthly or quarterly composite analyses.
34 I
l
Adsinistrative Proc dure .UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
! 5.3 LIQUID EFFLUENTS (cont'd) 5.3.4.2 Equation (1) above for calculating the dose contributions requires the use of a dose fa. tor, Ait, f r each nuclide (1) which embodies the dose factors and dilution factors for the points of pathway origin.
The adult total body dose factor and the adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:
Af g = Ko (b + U BF,)f DCF e f (3)
Da where:
Ait - Composite dose parameter for the total body or critical organ (t) of an adult for nuclide (i) for all appropriate pathways (mrem-ml/hr-pC1);
Ko - Unit conversion factor; 6 3 Ll4e + 5 = 10 $ 10 y + 8760%
Uw
- 7301/yr adult water consumption (Reg. Guide 1.109, Table E-5);
35
Adninistrative Proc: dure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
Dw
= Dilution factor from near field area to potable water intake;
- 220 for discharges from the circulating water discharge into the Mississippi River (based on the ratio of the average Mississippi River flow to the maximum discharge flow);
- 1 for discharges into the 40 Arpent Canal (based on the assumption that dilution from the near field area to a potable water intake is negligible);
Uf = 21 kg/yr, adult fish consumption (Reg. Guide 1.109, Table E-5);
BFi- Bioaccumulation factor for nuclide (i) in fish (pci/kg per pCi/1) from Attachment 6.21 and; NOTE For other liquid pathways, the appropriate dose factors will be utilized (Regulatory Guide 1.109 Tables E-7 through E-14, or Attachment 6.20).
DCFit - Ingestion Dose conversion factor for nuclide (i) and organ (t) for adults (mrem /pC1), from Attachment 6.20.
36
l Administrative Procedure UNT-005-014 j l
Offsite Dose Calculation Manual Revision 4 l l
l l
5.3 LIQUID EFFLUENTS (cont'd) l 5.3.5 Liouid Effluent Monitor Setooint Calculation Methodoloav 1
Specifications 5.3.1 and 5.6.1 require that the liquid j j effluent monitoring instrumentation alarm / trip l l setpoints be set so that the cone'entration of l ;
- radioactive material released frr,m the site is limited i to 10CFR20, Appendix B, Table II, Column 2 for i radionuclides other than dissolved or entrained noble l gases. For dissolved or entrained noble gases, the l concentration shall be limited to 2E-4 #Ci/ml total activity. This section presents the method to be used for determining setpoints in accordance with l
Surveillance Requirements 5.3.1 and 5.6.1.
l 5.3.5.1 The calculated setpoints for the liquid effluent monitors satisfy the following equation:
l l
(SF)(RF)(F +f)f C, c= "'
(4)
(TMPC)(f +F')
l i
37 1
Adsinistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 4
5.3 LIQUID EFFLUENTS (cont'd) where; c = the Setooint, in 14Ci/m1, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to complete dilution
- and subsequent release. This setpoint represents a value which, if exceeded would result in concentrations exceeding the limits of 10CFR20, Appendix B, Table l II. Column 2, to an UNRESTRICTED AREA;
! SF = Safety Factor to ensure that the effluent 4 limit is not exceeded. Actual value is set by procedure (in the range 0.5 - 0.9);
l RF = Release Fraction allocated to this release
] (to be used only in situations of i simultaneous or concurrent release);
i f = the undiluted liouid effluents flow as
, measured at the liquid effluent monitor l location in gpm; F = the dilution water flow as determined via pump curves or other appropriate measures that determine correct plant operating configuration in gpm; 38
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 NOTE If F is large compared to f then F + f ~ F. If there is no additional dilution, F' = 0.
F' = additional dilution flow at the radiation monitor for liquid effluent radiation monitors that have additional dilution prior to actual withdrawal of the monitored fluid, in gpm.
- 1000 (maximum) for Steam Generator Blowdown or Auxiliary Component Cooling Water releases to the circulating water system.
-O for all other liquid release points.
l I
39
Adainistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
C,
= the undiluted concentration in pCi/ml for all gama emitting radionuclides (1). The value will be derived from radioanalysis of liquid effluent to be released. This value will be supplied for each liquid release;
" " Cl C'
TMPC1-1 = { MPC,,,,+ [ MPC, Cj . the undiluted concentration, in yCi/ml, for all nongama-emitting radionuclides (j). This value will be derived from radionnalysis of composite liquid effluents released. This value will be supplied for each liquid release based upon the most recent analysis results.
' - undiluted gama MPC i fraction for all gama MPC I emitting radionuclides (1);
J
- the undiluted nongama MPC) fraction for all MPC J nongama emitting radionuclides (j);
MPCj = Maximum Permissible Concentration for the applicable gama-emitting isotope (i) from 10CFR20, Appendix B, Table II, Column 2; and 1
MPCj = Maximum Permissible Concentration for the applicable nongama-emitting isotope (j) from 10CFR20, Appendix B, Table II, Column 2 40
Adainistrative Procedure UNT-005-014
! Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd) l 5.3.5.2 The values of C4 and C3 will be measured for each release as appropriate and the parameters for f, F' and F will be supplied j based on current plant operating configurations. The setpoint will be calculated in terms of pCi/ml and the liquid effluent monitor will be adjusted as necessary to ensure that liquid releases are l secured prior to exceeding limits specified in 10CFR20, Appendix B, Table II, Column 2 l to an UNRESTRICTED AREA.
1 l
l l
i l
I 41
l Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
l 5.3 LIQUID EFFLUENTS (cont'd) 5.3.6 Representative Liauid Samolina Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling.
Large volumes of liquid waste shculd be mixed in as short a time as possible and uniformly distributed prior to sampling. To determine the minimum mixing time for tanks from which releases are made, the following tests were performed prior to initial use for release purposes.
- a. The tank was filled to a known volume.
- b. A specific quantity of a selected chemical and/or sediments was added to the tank.
- c. Recirculstion was initiated through the normal path.
l
- d. Periodic samples were taken until equilibrium was reached.
i
- e. The time observed to completely mix the tank is used as a minimum recirculation time prior to 1
effluent sampling. Records of the test will be maintained.
i
- 42
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQ'JID EFFLUENTS (cont'd) 5.3.7 Dose Proiection for Liauid Effluents Specification 5.3.3 requires that apprcpriate subsystems of the LIQUID Rt.DWASTE TREATMENT SYSTEM be j used to reduce releases of radioactivity when the l projected doses due to the liquid effluent from each l reactor unit to UNRESTRICTED AREAS would exceed in a 31 ;
day period I a) 0.06 arem total body, or b) 0.2 arem to any organ j i
The following calculational method is provided for performing this dose projection. !
At least once every 31 days, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, and the LIQUID RADWASTE TREATMENT SYSTEM has not been operating, it shall be operated, if operation would reduce the monthly projected doses below 0.06 mrem total body or 0.2 mrem any organ. (This is performed in accordance with the Surveillance Requirements of 5.3.3.)
43
Ad2inistrativa Pr cedure .'UNT-005-014 1 Offsite Dose Calculation Manual Revision 4 i
5.3 LIQUID EFFLUENTS (cont'd) ;
< 5.3.8 Liouid Effluent Bases
)
a.: CONfENTRATIQN (Section 5.3.1) l This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR l Part 20, Appendix B, Table II, Column 2. This :
j limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within .:
(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and i l
l (2) the limits of 10 CFR Part 20.106(e) to the
, population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Cownission on Radiological Protection (ICRP)
Publication 2.
j 4
1 44
l Administrative Pr:cedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 l
l 5.3 LIQUID EFFLUENTS (cont'd) j I
The sampling and analysis of the contents of the regenerative waste tank and the filter flush tank is performed if primary to secondary leakage occurs in a steam generator. The contents of these tanks cannot be discharged to the UNRESTRICTED AREA if any radioactivity is detected in these tanks since the ,
discharge from these tanks is unmonitored. When l
radioactivity is detected in these tanks, the l contents from these tanks must be discharged to the l liquid radwaste system where the contents may then l be monitored upon discharge. l The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the LOWER LIMITS of DETECTION (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (Reference 2.12) and Report ARH-SA-215 (Reference 2.13).
,)
i 45 l
Administrative Precedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
- b. IEEE (Section 5.3.2)
This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to a.ssure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.16.
46
Ad2inistrative Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 4
5.3 LIQUID EFFLUENTS (cont'd) l
- b. DQ1E (Section 5.3.2) (cont'd)
The dose calculation methodology and parameters implement the requirement in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures bared on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The l equations specified for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, (Reference 2.4)
! and Regulatory Guide 1.113, (Reference 2.3).
1 l
l l l
s a
4 J 47
- Administrative Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.3 LIQUID EFFLUENTS (cont'd)
- c. LIOUID RADWASTE TREATMENT SYSTEM (Section 5.3.3)
The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."
This specification implements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix A 10 CFR Pcrt 50 and the design objective given in Sectior. II.D of Appendix I to 10 CFR Part
- 50. The specified limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT SYSTEM were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
t 48
l Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 !
l l
5.4 GASE0US EFFLUENTS l
5.4.1 Dose Rate Specification The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE B0UNDARY (see Attachment 6.1) shall be limited to the following:
- a. For Noble Gases: Less than or equal to
- 1) 500 mres/yr to the total body; and
- 11) 3000 mres/yr to the skin. l and i
- b. For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives i greater than 8 days: Less than or equal to
- 1) 1500 ares /yr to any organ.
1 49 1
Ad:inistrativa Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASE0US EFFLUENTS (continued)
APPLICABILITY: At all times ACTION:
With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to.this condition in the next Annual Radioactive Effluent Release Report.
SURVEILLANCE REQUIREMENTS:
- a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 5.4.5.
- b. Representative samples and analysis of gaseous effluents shall be obtained in accordance with the sampling and analyses program specified in Table 5.4-1.
- c. Based upon the sampling and analysis performed in Table 5.4-1 the dose rate due to I-131, I-133, H-3, and all other radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology and parameters in Section 5.4.5.
50
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Administrative Procedure UNT-005-014 offsite Dose Calculation Manual Revision 4 i
TABLE 5.4-1 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM fd}iQiL4_ ELE 831_ TIPI SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
- 1. Waste Gas Decay Grab sample from each Prior to Noble Gas tank to be released Release Gamma Emitters [b]
prior to release
- 2. Containment Purge Grab sample from each Prior to Noble Gas P " ' "" ' "
(Plant Stack) Pbese r
Grab sample prior to Monthlyli 9] H-3 purge Continuous noble gas Continuous Noble Gases monitor Gross Beta or Gamrrg
- 3. Plant Stack Monthly grab sample Monthlyl93 Noble Gas Gamma Emitters [b] l Monthlylfe91 H-3 Continuous Charcoal Weekly th] I-131 l Cartridge Sample [c] I-133 i Continuous Weekly [h] Particulate !
Particulate Sample Gamma Emitters [b], j
[c] Gross Alpha '
Composite of all Quarterly Sr-89 continuous Sr-90 particulate filters collected during the Quarter Continuous noble gas Continuous Noble Gases monitor Gross Beta or Gamma 51
1 Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 I l
TABLE 5.4-1 (Continued)
RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE TYPE SAMPLE TYPE AND ANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
- 4. Fuel Handling M nthly grab sample Monthly Noble Gas Gamma Emitters [b]
Building Weekly grab sample Weekly H-3 Ventilation Continuous Charcoal Weekly I-131 Cartridge Sample [c] I-133 (Normal Exhaust)
Continuous Particulate Weekly Particulate Sample [c] Gamma Emitters (b),
Gross Alpha
- Whenever irradiated Composite of all Quarterly Sr-89 fuel is in the continuous particulate Sr-90 storage pool,see filters collected during note [e]. the Quarter Continuous noble gas Continuous Noble Gases monitor Gross Beta or Gamma
- 5. Main Condenser Monthly grab sample Monthlyl93 Noble Gas Evacuation and Gamma Emitters (b)
Turbine Gland Monthlyl93 H-3 Sealing System Continuous Charcoal Weekly [h] I-131 Cartridge Sample [c] I-133 (HCES)
Continuous Particulate Weekly [h] Particulate For applicability Sample [c] Gamma Emitters (b),
see note [d]. Gross Alpha Composite of all Quarterly Sr-89 continuous particulate Sr-90 filters collected during the Quarter Continuous noble gas Continuous Noble Gases monitor Gross Beta or Gamma 52
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.4-1 (Continued)
TABLE NOTATIONS
- a. The LLD values for the following types of analysis are:
Type of Analysis LLD (pCi/cc)
Noblu Gas Gamma Emitters IE-04 H-3 IE-06 I-131 1E-12 I-133 1E-10 Particulate Gamma Emitters 1E-11 Gross Alpha 1E-11 Sr-89, Sr-90 1E-11 Gross Beta or Gamma Noble Gas Monitor 1E-06 b- The principal gamma emitters for which the LLD Specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases, and Mn-54, Fe-59, C0-58, ,
Co-60, Zn-65, Mo-99, ? 'H , I-133, Cs-134, Cs-137, Ce-141, and Ce-144 i in iodine and particulm celeases. This list does not mean that only these nuclides are in Le considered. Other gamma peaks that are identifiable, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
c- Samples shall be changed at least once per seven days and analyses i shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. The ratis of the sample flow rate to the sampled stream (effluent stream) flow shall be known for the time period '
covered by each dose or dose rate calculation.
s d- If no primary to secondary leakage exists, then only the gross beta l or gamma analysis (installed radiation monitors) needs to be performed for the Main Condenser Evacuation and Turbine Gland Sealing System (MCES). Sampling and analysis shall be performed when a primary to secondary leak exists and the releases from the MCES have not been directed to the Plant Stack.
e- Fuel Handling Building sampling is required whenever irradiated fuel is in the storage pool.
53
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Administrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 l TABLE 5.4-1 (Continued) !
TABLE NOTATIONS f- Tritium grab samples for the Plant Stack shall be taken at least once ,
per 24 houn if purging containment with the refueling canal flooded. l g- Sampling sull also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL !
l POWER within a 1-hour period. Analysis for radionuclides shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sampling. This sampling is not applicable if the noble gas monitor shows that effluent activity ;
has not increased by a factor of 3. This sampling is not !
applicable to the McES WRGM if the release has been directed to the Plant Stack, or no primary to secondary leakage exists. i h- Samples shall be chanced at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least Seven days following each Shutdown, Startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1-hour, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:
- 1) Primary Coolant Dose Equivalent Iodine-131 concentration has increased by more than a factor of 3; AND
- 2) The noble gas monitor shows that effluent activity has increased by more than a factor of 3.
i- Sampling and analysis are required prior to first purge and monthly l thereafter.
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Administrative Procedure UNT-005-014 Offsite Dose Calculatien Manual Revision 4
- 5. 4- GASEOUS EFFLUENTS (cont'd) 5.4.2 Dose-Noble Gas Specification The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE B0UNDARY (see Attachment 6.1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 1
i) 5 mrad for gamma radiation, and
- 11) 10 mrad for beta radiation and,
- b. During any calendar year: Less than or equal to
- 1) 10 mrad for ganna radiation, and
- 11) 20 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report.
This Special Report shall identify the cause(s) for exceeding the limit (s) and define the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that !
subsequent releases will be in compliance with the above limits.
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Administrative Procedure UNT-005-014 Offsite Dose Calculatien Manual Revisien 4 5.4 GASE0US EFFLUENTS (cont'd)
SURVEILLANCE REQUIREMENTS:
Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Section 5.4.6 at least once per 31 days.
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Ad inistrative Precedure UNT-005-014 ,
Offsite Dose Calculation Manual Revision 4 t
5.4 GASEOUS EFFLUENTS (cont'd) 5.4.3 Dose - Iodine-131. Iodine-133. Tritium. and Radionuclides in Particulate Form Specification j
The dose to MEMBER OF THE PUBLIC from iodine-131, ;
iodine-133, tritium, and all radionuclides in l
particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE B0UNDARY (see Attachment 6.1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrom to any organ and,
- b. During any calendar year: Less than or equal to 15 mrom to any organ.
i APPLICABILITY: At all times !
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1 Administrative Prscedure UNT-005-014 Offsite Dose Calculatien Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd) l ACTION:
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous l effluents exceeding any of the above limits, prepare and l submit to the Commission within 30 days, pursuant to l Technical Specification 6.9.2, a Special Report. . This Special Report shall identify the cause(s) for exceeding the limit and define the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
l l SURVEILLANCE REQUIREMENTS:
Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in Section 5.4.7 at least once per 31 days.
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AdJinistrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.4 Gaseous Radwaste Treatment Specification The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE B0UNDARY (see Attachment 6.1) would exceed either:
- a. 0.2 mrad to air from gannia radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrom to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
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Ad;inistrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 i
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5.4 GASE0US EFFLUENTS (cont'd) i ACTION:
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report.
This Special Report shall include the following information:
- a. Identif' cation of any inoperable equipment or
- "bsystems, and the reason for the inoperability,
- b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and l
l
- c. Summary description of action (s) taken to prevent a recurrence.
SURVEILLANCE RE0VIREMENTS: l l
- a. Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and
! parameters in Section 5.4.9.
- b. The installed Gaseous Radwaste Treatment System shall be demonstrated operable by meeting Specifications 5.4.1, 5.4.2 and 5.4.3.
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l Ad31nistrative Precedure UNT-005-014 l Offsite Dose Calculation Manual Revisicn 4 5.4 GASE0US EFFLUENTS (cont'd)
NOTE The Offsite Dose Calculation Manual (0DCM) follows the general models suggested by NUREG 0133 and Regulatory Guide 1.109. Howrear, alternate calculation methods from those presented may be used provided the overall methodology is acceptable and consistent with regulation or provided the alternate methodology is conservative. In addition', the most up-to-date dose conversion factors and bioaccumulation factors may be substituted in lieu of Regulatory Guide 1.109 values.
NOTE Actual step-by-step dose calculations will be performed by in-plant procedures which are consistent with the methodology presented in this document.
5.4.5 Calculational Methodoloav for Gaseous Effluent Dose Rate This section presents the calculational methods used for calculating gaseous effluent doses in fulfillment of Specification 5.4.1.
5.4.5.1 The dose rate due the radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE B0UNDARY shall be limited to the following values and expressions:
i 61 1
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd)
Release rate limit for Noble Gases:
"" total body K' (%), K, Q,, s 500 (5) 1.i K'(%), (L, + 1.1#,)0,y s 3000 '"7 skin (6) s.
Release rate limit for Iodine-131, Iodine-133, Tritium and for all radionuclides in particulate form with half-lives greater than 8 days: l
(%),fP,tQ,, s 1500 y any organ (7) 11 Where:
K' =
a constant of unit conversion, IE6 pCi/ #Ci; (X/Q)v = 1.1E-5 sec/m3 in the ESE sector at 0.6 mile for all vent releases (v)
(the highest calculated annual average dispersion factor at the SITE BOUNDARY based on historical data Attachment 6.2).
The actual X/Q for the time of release may be determined and used under certain circumstances; f = summation for all identified fel radionuclides; 62
Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 1
5.4- GASE0US EFFLUENTS'(cont'd)
Ki = the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of mrem /yr per pCi/m3 (Attachment 6.4);
Lj = the skin dose factor due to beta emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m3 (Attachment 6.4);
Mj = the air dose factor due to gamma emissions for each identified radionuclide (i) in units of mrad /yr per pC1/m8 (Attachment 6.4). The constant 1.1 converts air dose to skin dose; Pit = the thyroid dose parameter for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days (i) for the inhalation ;
pathway only, in mrem /yr per )
pC1/m3 (Attachment 6.19). The dose factor is based on the most restrictive age group (child) and most restrictive organ at the SITE BOUNDARY; and i
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Administrative Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 j i
5.4 GASEOUS EFFLUENTS (cont'd)
NOTE All radiciodines are assumed to be released in elemental form.
Qiy - the average release rate of )
radionuclides (i) (either noble gas or Iodine-131, Iodine-133, tritium, and radionuclides in the particulate form with half-lives greater than 8 days, as appropriate) during the time of release from all vent releases (v). Value is averaged over one hour and is in units of pCi/sec. l 64
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASE0US-EFFLUENTS (cont'd) 5.4.6 Calculational Methodology for Noble Gas Doses This section presents the calculational methods used for ,
calculating noble gas effluent dose in air in accordance with Surveillance Requirement 5.4.2.
5.4.6.1 .The air dose due to noble gases released in gaseous effluents to areas at or beyond the SITE B0UNDARY will be determined by the following expressions:
- a. During any calendar quarter, for gama '
radiation:
I n m \
D7 = (1.14e + 2)(%),[ #,[ Atj 0,j, (8) I r=1 )=1 and for beta radiation:
Of = (1.14e + 2)(%),f N,f Atj 0,j, (9) i=1 J=1
- b. During any calendar year, for gamma l radiation:
D7 = (1.14e + 2)(%),f #,f Atj Q,y, (10)
-i ;-i and for beta radiation: .
Dj = (1.14e + 2)(%),f N,f Atj Q,y, (11)
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l AdJinistrative Procedure UNT-005-014 l l Offsite Dose Calculation Manual Revision 4 j j
, 5.4 GASEOUS EFFLUENTS (cont'd)
Where:
1 D-y
= the total gamma (y) air dose from gaseous j efflitents for the total time period and I not to exceed 5 mrad quarterly and 10 mrad yescly;
, D 8
= the total beta (8) air dose from gaseous 1 effluents for the total time period and not to exceed 10 mrad quarterly and 20
, mrad yearly;. l
- 1.14E+02 = a constant of (1 yr/8760 hr) (IE+6 pCi/ Ci); I 1
- ( %), =
1.1E-5 sec/m8 in the ESE sector at 0.6 mile i i
for all vent releases (v). The actual X/Q for the time of release may be
- determined and used under certain circumstances; )
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Administrative Procedure UNT-005-014 i Offsite Dose Calculatien Manual Revision 4 5.4 GASE0US EFFLUENTS (cont'd)
Mi and Ni - the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (1) in mrad /yr per pCi/m3 (Attachment 6.4);
Atj = the length of the jth time period over l
which Qjjy are accumulated for all gaseous releases in hours; and j Qijy - the average release rate of radionuclides (1) in gaseous effluent from all vent releases (v) in pCi/sec during the time I period Atj, 1
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1 Administrative Procedure UNT-005-014 )
Offsite Dose Calculation Manual Revision 4 l
5.4 GASEOUS EFFLUENTS (cont'd) 5.4.7 Calculational Methodology for Doses Due to j Radiciodines, Tritium, and Radioactive Materials in Particulate Form i I
l This section presents the calculational methods used for j calculating doses due to iodine-131, iodine-133, l tritium, and radionuclides in particulate form in accordance with Surveillance Requirement 5.4.3.
5.4.7.1 The dose to an individual from iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to !
areas at and beyond the SITE BOUNDARY will l be determined by the following expressions:
During any s.glgpdar auartgr:
D,t, = 1.14e - 4 Atf R , W eQ,,
ft (12) 1-1 !
I During any calendar year:
Dft , = 1.14e - 4 Atf R ft, F, Q,, (13) 1=1 68
l AdJinistrative Procedure UNT-005-014 1 Offsite Dose Calculation Manual Revision 4 l l
5.4 GASEOUS EFFLUENTS (cont'd)
Where:
l l
the cumulative dose to an organ (t), age
=
Dita group (a), due to radionuclides (i) in gaseous effluents; not to exceed 7.5 mrem quarterly or 15 mrem yearly; 1.14E a constant of unit conversion
= 1 yr/8760 hr; t
At - the time required for the release in I
hours for all releases per quarter or per )
year.
Wy - the dispersion parameter for estimating the dose to an individual at the controlling location for long term vent releases (v);
=(#/g),
for the inhalation pathway from vent releases (v) in sec/m8, from historical data, at the location of the critical receptor (Attachment 6.2);
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revisien 4 l 5.4 GASE0US EFFLUENTS (cont'd) j - (yg),
for the food and ground plane pathways l
from vent releases (v) in 1/m2, from
, historical data at the location of the I
critical receptor (Attachment 6.2),
with the exception of tritium, which shall use Wv = (%)v.
Rita -
the dose factor from each identified radionuclide (i), for each applicable organ (t), and age group (a), in l ares /yr per uC1/m3 for the inhalation pathway (Attachment 6.5) and in eres/yr per uCi/mt-sec for the food and ground ,
plane pathways (Attachments 6.6, 6.7, 6.8, 6.9, and 6.10). For sectors with real pathways within 5 miles of the l plant, the values of Rj are used based on these real pathways; for sectors with no real pathways within 5 miles from the plant, Rj is used assuming that the cow-grass-milk pathway exists at the 5-mile distance. (Rj's were calculated using the methodology found in NUREG 0133, Reference 2.5, pages 31-36.); and Qiy - the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec.
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l Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.8 Gaseous Effluent Monitor Setqgint Calculational Methodoloav i l- !
5.4.8.1 Specification 5.6.2 requires that the -
radioactive gaseous effluent monitoring instrumentation alarm / trip setpoints be set to ensure the limits of Specification 5.4.1 ;
j are not exceeded.
5.4.8.2 The calculated high alarm / flow termination setpoint is the maximum value for that l particular release. For conservatism, an administra.ive r safety factor (SF) of usually 10% will be utilized in the setpoint calculation. To allow for simultaneous l releases from common or different release points a Release Fraction (RF) may be used to_ allocate percentages of the total ,
l allowable release.
l ,
I l 5.4.8.3 Since the noble gas dose rates are more limiting than the radiciodine dose rate, gaseous setpoints will be based on noble gas dose rates (less than or equal to 500 mrem /yr total body, and less than or equal to 3000 mrem /yr skin). Specifically, gaseous setpoints will be based on the most limiting of the following equations:
71
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd)
- a. Total body (Qtb)
(500TfXRFXSF)
Ow =
.i
__ IK 0n i
(xf), (1.0e + 6 @) ' ;
10iv kl Where:
Qtb - maximum release rate allowed to give a limiting total body dose rate of 500 mrem /yr in / sci /sec; f -summation of all nuclides considered; r-1 Ki - the total body dose factor due to gamma emissions for each identified radionuclide (1) in units of ares /yr per pCi/m3 (Attachment 6.4);
72 l l
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Administrative ProcGdure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd)
Qiy = average release rate of isotope (i) from i the release point (v) in #Ci/sec;
%), = 1.lE-5 sec/m3 (in the ESE sector at 0.6 mile). The sector with highest value of annual average atmospheric dispersion factor at the site boundary for the release point (v) in question; RF - release fraction allotted to release point in consideration; and l
SF - administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.). Usually, the l SF takes on a value of 0.9. !
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd)
- b. For Skin (Q skin):
(3000225XRFXSF)
Osn, = ", (15)
I(L +i 1.1Mii)0, Gi[),(L0e+ 6js) *' ,
I0,i ml Where:
'all terms are as defined in Step (a) for Qth, except:
Qskin - maximum release rate allowed to give a limiting skin dose of 3000 mrem /yr in pCi/sec; Li = skin dose factor due to beta emissions for each identified radionuclide (1) in units of mrem /yr per pCi/m3 (Attachment 6.4);
1.1 = conversion factor to convert from air to skin dose; and Mi
- air dose factor due to gamma emissions for identified noble gas isotope (1) in units of mrad /yr per pCi/m3 (Attachment 6.4).
74 1
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Ad2inistrative Procedure UNT-005-014 l
Offsite Doss Calculation Manual Revision 4 l
! 5.4 GASE0US EFFLUENTS (cont'd) 1 5.4.8.4 The monitor setpoint is calculated is the following manner:
0 (16)
SN = (F )(472) ,
Where:
SN - maximum monitor setpoint in gC1/cm3; Q - Minimum value of Qtb or Qskin (gCi/sec).
Faax = maximum effluent flow rate (cfa); and l
l 472 = Unit conversion, CFM to cm3/sec 5.4.8.5 Since Kr-88 is the noble gas with the highest dose rate conversion factors, for
- conservatism, the preceeding calculations may be computed using Kr-88 only. Total l body dose becomes more limiting than skin and the release limit is
i i Q,,_,, = (500==)(RF)(SF) (17)
(#/g),(Kr, :) (1.0e + 6 g) 75
Ad2inistrative Procedure UNT-005-014
~ Offsite Dose Calculation Manual Revision 4 I
5.4 GASE0US EFFLUENTS (cont'd) !
where:
QKr-88 = the maximum release rate, based on Kr-88, I allowed to give a limiting total body dose rate of 500 mrem /yr in yci/sec; and i l
KK r the total body dose factor due to Kr-88 in units of mrem /yr per pC1/m3 (Attachment 6.4); and.
All other terms are as previously defined.
The monitor setpoint can be calculated as:
0"'-
SN = (F,)(472) (18) 1 l
All terms are previously defined
]
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Offsite Dose Calculation Manual Revision 4 5.4 GASE0US EFFLUENTS (cont'd) 5.4.9 Dose Proiection due to Gaseous Effluents 5.4.9.1 Specification 5.4.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment System be'used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE B0UNDARY would
)
exceed, in a 31-day period, any of the !
following:
0.2 mrad to air from gamma radiation; or 1 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. ,
5.4.9.2 The following calculational method is provided i for performing this dose projection. l At least once every 31 days the gamma air dose, I beta air dose and the maximum organ dose for the month-to-quarter will be divided by the number of l days into the quarter and multiplied by 31. If j these projected doses exceed any of the values listed above and the VENTILATION EXHAUST TREATMENT SYSTEM OR WASTE GAS HOLDUP SYSTEM has not been operating, it shall be operated to reduce radioactivity levels prior to release. l (This is performed in accordance with the Surveillance Requirements of Specification 5.4.4.)
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.10 Gaseous Effluent Bases
- a. DOSE RATE (Section 5.4.1)
This specification is provided to ensure that the dose at any time at and beyond the SITE B0UNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER 0F THE PUBLIC in a UNRESTRICTED AREA, either within or outside the SITE B0UNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE B0UNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in this manual. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the total body and 3000 mrem /yr to the skin.
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i Administrative Procedure UNT-005-014 0.'fsite Dose Calculation Manual Revision 4 l
5.4 GASEOUS EFFLUENTS (cont'd)
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (Reference 2.12) and Report ARH-SA-215 (Reference 2.13).
- b. DOSE - N0BLE GASES (Section 5.4.2)
The Specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I, 10 CFR Part 50. It implements the l guides set forth in Section II.B of Appendix I.
1 i
l 79
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Administrative Procedure UNT-005-014 Offsite D5se Calculaticn Manual Revision 4 5.4 GASE0US EFFLUENTS (cont'd)
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to assure ;
that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable".
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 2.4) and Regulatory Guide 1.111 (Reference 2.2). I l
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Administrative Procedure UNT-005-014 i
Offsite Dose Calculation Manual Revision 4 '
5.4 GASEOUS EFFLUENTS (cont'd)
Sections 5.4.2 and 5.4.3 equations provided for l
determining the air doses at and beyond the SITE j BOUNDARY are based upon the historical average atmospheric conditions.
l Grab sampling of effluents from the main condenser l evacuation and turbine gland sealing system is not l required when this source has been continuously l
discharging to the plant stack.
l t
l l If no primary to secondary leakage in the steam l generator exists, then there should be no radioactive release from the main condenser evacuation and turbine gland sealing system and the gross beta or gamma monitoring for noble gases will be sufficient to determine if any radioactivity is preser t in the release.
If a primary to secondary leak exists, then the release from the main condenser evacuation and turbine gland sealing systems will be sampled and
[ analyzed in accordance with Table 5.4-1. ;
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLUENTS (cont'd)
- c. 10 DINE-131. 10 DINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM (Section 5.4.3)
This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of l Appendix I, 10 CFR Part 50. The Specifications are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable.
"The calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
82
Administrative Prccedurc UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.4 GASEOUS EFFLb'iNTS (cont'd)
The calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Reference 2.4 and Regulatory Guide 1.111, Reference 2.2. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in l particulate form with half-lives greater than 8 I days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were:
(1) Individual inhalation of airborne radionuclides, (2) Deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) Deposition onto grassy areas where milk animals i and meat-producing animals grare with consumption of the milk and meat by man, and (4) Deposition on the ground with subsequent exposure of man.
I i
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l Administrative Precedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 1
i 5.4 GASEOUS EFFLUENTS (cont'd)
- d. GASEOUS RADWASTE TREATMENT (Section 5.4.4)
I The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and ,
the VENTILATION EXHAUST TREATMENT SYSTEM ensures i that the systems will be available for use whenever gaseous effluents require treatment prior to i release to the environment. The requirement that the appropriate portions of these systems be used,
)
when specified, provides reasonable assurance that l the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably i achievable".
This specification implements the requirements of
]
10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to l 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.
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Ad31nistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4
)
5.5 TOTAL DOSE 5.5.1 TOTAL DOSE SPECIFICATION I
The annual (calander year) dose or dose commitment to any MEMBER OF THE PUBLIC due to release of radioactivity l and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 aren to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
APPLICABILITY: At all times.
ACTION:
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 5.3.2.a.
5.3.2.b, 5.4.2.a, 5.4.2.b, 5.4.3.a, or 5.4.3.b calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 5.5.1 have been exceeded. This evaluation should be done in accordance with guidance in Section 5.5.2. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2 a Special Report.
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I Administrative Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.5 TOTAL DOSE (cont'd)
This Special Report shall:
a) Define corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
b) As defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.
c) Describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
d) If the estimated dose (s) exceeds the specification 5.5.1 limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisie,m; of 40 CFR Part 190. Submittal of the report ;., considered a timely request, and a variance is granted until staff action on the request is complete.
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Administrative Proc: dure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.5 TOTAL DOSE (cont'd)
SURVEILLANCE REQUIREMENTS:
- a. Cumulative dose contributions from liquid and j gaseous effluents shall be determined in accordance with Specification 5.3.2, 5.4.2, and 5.4.3 and in accordance with the methodology and parameters in this manual.
- b. Cumulative dose contributions from direct j radiation from the reactor units and from radwaste j storage tanks shall be determined in accordance with the methodology and parameters in this manual . This requirements is applicable only ;
under condition set forth in Specification 5.5.1.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.5 TOTAL DOSE (cont'd) 5.5.2 40 CFR 90 DOSE EVALUATION This section demonstrates compliance with Specification 5.5.1 Surveillance Requirements. Specifically, the dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 ares to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 aren) over 12 consecutive months.
Dose evaluations to demonstrate compliance with the above dose limits need to be performed only if quarterly doses exceed:
(1) 3 aren to the total body (liquid releases).
(2) 10 mres to any organ (liquid releases).
(3) 15 ares to the thyroid or any organ from radioiodines and particulates (gaseous rele n as).
otherwise no evaluations are required.
For the evaluation of doses to real individuals from liquid releases, the same calculational methods as employed in Section 5.3.4 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion ~of radionuclides by individuals who live and fish in the Waterford 3 area.
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Administrative Procedure UNT-005-014 t Offsite Dose Calculation Manual Revision 4 l
5.5 TOTAL DOSE (cont'd)
The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentrations.
For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as i employed in sections 5.4.6 and 5.4.7 will be used. The total body dose factor should be substituted for the gamma air dose factor (Mj) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the '
meteorological conditions, and the consumption of food.
Data obtained from the latest land use census should be l
used to determine locations for evaluating doses. The )
results of the Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations.
Cumulative dose contributions from direct radiation, from the reactor unit, and from Radwaste Storage Tanks shall be determined utilizing the results of routine plant perimeter surveys, TLD data, or a combination of both when necessary.
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Adainistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases The specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 Federal Register 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.
90
Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 5.3.1 and 5.4.1. An individual is not considered a MEMBER OF THE PUBLIC during in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
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Administrative Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.6 INSTRUMENTATION !
5.6.1 Radioactive Liauid Effluent Monitorina Instrumentation Specification
]
l The radioactive liquid effluent monitoring j instrumentation channels shown in Table 5.6-1 shall be l OPERABLE with their alarm / trip setpoints set to ensure l that the limits of Specification 5.3.1 are not exceeded i
during releases to the environment. The alarm / trip ;
setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 5.3.5.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid effluent monitoring i instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend release to the j environment of radioactive liquid effluents j monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
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Administrative Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.6 INSTRUMENTATION (Cont'd) l l
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-1.
! Restore the inoperable instrumentation to OPERABLE l status within 30 days if release to the environment are in progress or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why
. this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.
l SURVEILLANCE RE0VIREMENT Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, S0.URCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 5.6-2.
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Administrative Procedure UNT-005-014
- Offsite Dose Calculation Manual Revision 4 i
TABLE 5.6-1 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION ;
6 HINIMUM APPLICABILITY ACTION
- CHANNELS INSTRUMENT OPERABLE l
I- BORIC ACID CONDENSATE DISCHARGE (BWMS):
- a. Radioactivity Monitor Providing Alarm 1 During Batch I l and Automatic Termination of Release Release of ;
l (PRM-IRE-0627) Boric Acid
- b. Waste (Process) Flow Rate Measurement 1 Condensate 2 Device (PRM-IFT-0627) Tanks j II- WASTE, WASTE cow ENSATE and LAUNDRY : ,
i DISCHARGE (LWMS)
- a. Radioactivity Monitor Providing Alarm 1 During Batch 1 and Automatic Termination of Release Release of (PRM-IRE-0647) Liquid Waste
- b. Waste (Process) Flow Rate Measurement 1 Management 2 i Device (PRM-IFT-0647) Tanks III- DRY COOLING TOWER SUMPS (DCTS): Detectable (Note I
- a. Radioactivity Monitor Providing Alarm 1/ sump #2) Activity in 3 and Automatic Termination of Release CCW/ACCW Systems
[PRM-IRE-6775(DCTSf1) and and Release [
PRM-IRE-6776(DCTSf2)] Path NOT Aligned ;
- b. Waste (Process) Flow Rate Measurement N/A to LWMS N/A l Device (See Table Note. #1) .
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UNT-005-014 ,
Administrativa Proceduro R2 vision 4 i Offsite Dose Calculation Manual I TABLE 5.6-1 (Continued) pani 0 ACTIVE LIOUID EFFLUENT NONITORING INSTRUNENTATION i
i MINIPUi APPLICABILITY ACTION INSTRIE NT CHANNELS OPERABLE IV- TURBINE BUILDING IM USTRIAL WASTE l Detectable (Note #2)
SWP (TBIWS):
Radioactivity Monitor Providing Alare 1 Activity in 3 a.
and Automatic Termination of Release Secondary Plant and Release i (PRN-IRE-6778)
- b. Waste (Process) Flow Rate Measurement N/A Path NOT A'igned N/A Device (See Table Note. #1) to LWMS
- 1. Detectable V- CIRCULATING WATER DISCHARGE- BLOWDO W Activity in NEAT EXCHANGER DISCHARGE AW l Secondary Plant. 4 I
AUXILIARY COOLING WATER PUNPS (CWD): 2. During Blowdown j
- a. Radioactivity Monitor Providing Alarm 0F Steam Generators I
and Automatic Reduction of Blowdown to CW System. ,
Discharge Flow Rate. (PRN-IRE-1900) 3. During Discharge
- b. Waste (Process) Flow Rate Measurement N/A of ACCW Basins N/A i
! Device (See Table Note. #1) to CW System.
t During Blowdown VI- STEAN GENERATOR BLOW OWN EFFLUENT LINE (Note #3) of S/Gs ,
- a. Continuous Composite Sampler 1 to CW System or 4
- Waste Ponds. -
95
i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l TABLE 5.6-1 (Continued) l I
TABLE NOTATIONS NOTE #1 - Waste (process) Flow Measurement Devices are not installed on ;
the release paths for the DCTS. TBIWS or CWD monitors. For l these release paths, pump performance curves generated in ;
place or some form of volumetric estimate or measurement device may be used for effluent flow rate estimates.
NOTE #2 - DCTS and TBIWS monitor operation should be maximized during releases to the environment, even when detectable activity is not present in the CCW/ACCW or secondary systems,.to provide capability for release termination in the event that Primary-to-Secondary or Primary-to-CCW 1eakage occurs.
l NOTE #3 - The Steam Generator Blowdown Composite Sampler is capable of l sampling blowdown discharge to either the CW System or Waste )
Ponds. Blowdown to the Waste Ponds is not allowed unless radiation monitoring capable of release termination is added to the release path.
ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 5.3.1, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; ACTION 2 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per FOUR hours during actual releases. Pump performance curves generated in place may be used to estimate fl ow.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 I
l' TABLE 5.6-1 (Continued)
TABLE NOTATIONS ACTION 3 - With the number of channels OPERABLE 1ess than required by -j
! the Minimum Channels OPERABLE requirement, effluent releases 1 i via this pathway may continue provided best efforts are made e to repair the instrument and that grab samples are collected l' and are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection time for radioactivity at a lower limit of detection of at least 5 E-07 microcurie /m1. Sample collection and analysis is NOT 4
required if the release path for the DCTS/TBIWS is aligned to l the LWMS. The sample collection frequency is:
i
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity l l of the secondary coolant is greater than i 0.01 microcurie / gram DOSE EQUIVALENT I-131, or )
l b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity !
l of the secondary coolant is less than or equal to j i 0.01 microcurie / gram DOSE EQUIVALENT I-151. '
j ACTION 4 - With the number of channels OPERABLE less than required by j the Minimum t,hannels OPERABLE requirement, effluent releases
! via this pathway may continue provided best efforts are made i to repair the instrument and that grab samples are collected l and are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection time for
- radioactivity at a lower limit of detection of at least
) 5 E-07 microcurie /ml. Sample collection and analysis is NOT :
i required if no detectable activity exists in either the
! secondary plant or CCW/ACCW systems. Sampling of Steam l Generator Blowdown is required during blowdown to the CW i System or Waste Ponds. The sample coliection frequency is:
l 5 a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity 3
of the secondary coolant is greater than
! 0.01 microcurie / gram DOSE EQUIVALENT I-131, or i
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to.
J 0.01 microcurie / gram DOSE EQUIVALENT I-131.
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Administrativa Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-2 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL CHANNEL CHANNEL FUNCTIONAL CONDITIONS CHECK SOURCE CALIBRATION TEST IN WHICH CHECK REQUIRED I- BORIC ACID CONDENSATE DISCHARGE (BWMS): During Batch
- a. Radioactivity Monitor Providing Alarm Prior to Prior to 18 Months (3) Quarterly (l) Release of and Automatic Termination of Release Release Release soric Acid condensate (PRM-IRE-0627)
- b. Waste (Process) Flow Rate Measurement Daily (4) N/A 18 Months Quarterly Tanks Device (PRM-IFT-0627) .
t II- WASTE, WASTE CONDENSATE and LAUNDRY DISCHARGE (LWMS): During Batch
- a. Radioactivity Monitor Providing Alarm Prior to Prior to 18 Months (3) Quarterly (l) Release of and Automatic Termination of Release Release Release Liquid weste (PRM-IRE-0647) Management
- b. Waste (Process) Flow Rate Measurement Daily (4) N/A 18 Months Quarterly Tanks Device (PRM-IFT-0647)
Detectable III- DRY COOLING TOWER SUMPS (DCTS): Activity in
- a. Radioactivity Monitor Providing Alarm Daily Monthly 18 Months (3) Quarterly (2) ccw/Accw and Automatic Termination of Release systems and ,
(PRM-IRE-6775 and PRM-IRE-6776) Release Path
- b. Waste (Process) Flow Rate Measurement N/A N/A N/A N/A nor Aiianed to LWMs 98
Admiinistrativa Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-2 (Continued) '
Mp!0 ACTIVE LIOUID EFFLUENT NONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS INSTRWENT CHANNEL CHANNEL CHANNEL FUNCTIONAL CONDITIONS i CHECK SOURCE CALIBRATION IESI IN le(ICH CHECK REQUIRED ;
Detectable IV- TURBINE BUILDING IWUSTRIAL MASTE Activity in SUMP (TRIWS): secondary ;
- a. Radioactivity Monitor Pro,: :..g Alarm Daily Monthly 18 Months (3) Quarterly (2) Piant end and Automatic Termination of Release Release Path (PRM-IRE-6778) nor Aiianed
- b. Waste (Process) Flow Rate Measurement N/A N/A N/A N/A to tas ;
I
-Detectable V- CIRCULATING MATER DISCHARGE- BLOWDol#1 Activity in HEAT EXCHANGER DISCHARGE Als secondary AUXILIARY C0OLING WATER PW PS (C W): Plant.
(TERMINATION OF BLOWDOWN DISCHARGE ONLY) -ouring aio or
- a. Radioactivity Monitor Providing Alarm Daily Monthly 18 Months (3) Quarterly (2) sia to cu system and Automatic Reduction of Blowdown During otschg.
Discharge Flow Rate (PRM-IRE-1900) or accu sasins
- b. Waste (Process) Flow Rate Measurement N/A N/A N/A N/A to cv syste .
During bid VI- STEAM GENERATOR BLOWDOWN EFFLUENT LINE: Daily (5) N/A 18 Months Quarterly or sics to
- a. Continuous Conposite Sanpler cv system or vaste Ponds.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-2 (Continued)
TABLE NOTATION
- 1. The CHANNEL FUNCTIONAL TEST for BWM and LWM shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists.
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure
- 3. Instrument indicates a downscale failure.
- 2. The CHANNEL FUNCTIONAL TEST for DCTS. TBIWS and CWD shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels.above the alarm setpoint. :
- 2. Circuit failure.
- 3. Instrument controls not set in operate mode. ,
- 3. The initial CHANNEL CALIBRATION shall be performed using one or more of ,
the reference standards certified by the National Institute of Standards !
and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system for over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
- 4. CHANNEL CHECK for BWM and LWM shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
- 5. CHANNEL CHECK for Steam Generator Blowdown Composite Sampler shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which releases are made to the Circulating Water System or Waterford 3 waste pond.
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Administrative Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 ,
i l 5.6 INSTRUMENTATION (cont'd)
! 5.6.2 Radioactive Gaseous Effluent Monitorina Instrumentation l Specifications i
j The radioactive gaseous effluent monitoring l instrumentation channels shown in Table 5.6.3 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 5.4.1 are not exceeded during releases to the environment. .The alarm / trip-l setpoints of these channels shall be determined and 1
adjusted in accordance with the methodology and parameters in Section 5.4.8.
APPLICABILITY: As shown in Table 5.6-3 i
ACTION:
i- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less j conservative than required by the above l Specification, immediately suspend release to the j environment of radioactive gaseous effluents I l monitored by the affected channel, or declare the l j channel inoperable, or change the setpoint so it i is acceptably conservative.
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Administrative Precedure UNT-005-014 Offsite Dose Calculation Manual Revisicn 4 5.6 INSTRUMENTATION (cont'd)
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-3. Restore the inoperable instrumentation to OPERABLE status within 30 days if releases to the environment are in progress or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.
SURVEILLANCE REQUIREMENTS:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown l in Table 5.6-4.
102
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Adsinistrativa Pr:cedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTR _UtiENTATION
.' l INSTRUMENT MINIMUM APPLICABILITY ACTION i
CHANNELS OPERABLE l
I- WASTE GAS HOLDUP SYSTEM (GWMS): I
- a. Noble Gas Activity Honitor Providing Alarm 1 During Waste 1 i
and Automatic Termination of Release Gas Decay Tank !
(PRM-IRE-0648) Discharge
- b. Waste (Process) Flow Rate Measurement 1 5 Device (GWM-IFIT-0648)
II- MAIN CONDENSER EVACUATION AND TURBINE j
GLAW SEALING SYSTEM (MCES): When Main
- a. Noble Gas Activity Monitor 1 Condenser is 3 (PRM-IRE-0002) Under a vacuum i
- b. Iodine Sampler (see NOTE 1) I and Release 4
- c. Particulate Sampler (see NOTE 1) I has not been 4 i
- d. Sampler Flow Rate Monitor (see NOTE 1) I directed to the 6 Plant Stack i
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-3 Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION J INSTRUMENT MINIMUM APPLICABILITY ACTION CHANNELS OPERABLE III- REACTOR AUXILIARY BUILDING VENTILATION SYSTEM (PLANT STACK): f' al. Noble Gas Activity Monitor Providing Alarm 1 During 2 and Automatic Termination of Containment Containment Purge (PRM-IRE-0100.lS & 25) Purge a2. Noble Gas Activity Monitor 1 3 (PRM-IRE-0100.lS , 2S or 0110) At
- b. Iodine Sampler (see NOTE 1) 1 All 4
- c. Particulate Sampler (see NOTE 1) 1 Times 4
- d. Sampler Flow Rate Monitor (see NOTE 1) 1 6
- e. Waste (Process) Flow Rate Monitor 1 5 (PRM-IFT-0100-12/22)
IV- FUEL HAELING BUILDING VENTILATION SYSTEM - (NORMAL ):
- a. Noble Gas Activity Monitor 1 With 3 (PRM-IRE-5107 A or B) Irradiated
- b. Iodine Sampler (see NOTE 1) 1 Fuel in 4
- c. Particulate Sampler (see NOTE 1) I the Storage 4
- d. Sampler Flow Rate Monitor (see NOTE 1) 1 Pool 6
- e. Waste (Process) Flow Rate Monitor 1 5 (PRM-IFT-5107 A or B) 104 ,
t
. . _ . . . _ _ . . _ . . . _ ~ _ _ _ _ _ _ _._ . __ .. -. __ _ _ . .
l
[ Administrative Procedure UNT-005-014 l
Offsite Dose Calculation Manual Revision 4 TABLE 5.6-3 (Continued)
TABLE NOTATIONS l NOTE 1 - The sampler flow rate monitor operability also satisfies the i
particulate and iodine sampler requirements as long as the l filter media for the applicable sample pump is installed.
! For the MCES and Plant Stack WRGM's, the low range detector
! sample pump is normally used to satisfy these requirements.
l' For the Plant Stack and Fuel Handling Building PIG's, the filter media necessary to satisfy the particulate and iodine sampler is normally applicable to the iodine / gas channel sample pump. 1 l
ACTION STATEMENTS i I ACTION 1 - With the number of channels OPERABLE less thar. required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best efforts are made to repair the instrument and that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; ACTION 2 - With the number of channels operable less than required, containment purging of radioactive effluents must be immediately suspended. This ACTION only applies to the l noble gas channels of the Plant Stack PIG's (PRM-IRE-0100.15 and PRM-IRM-0100.2S).
l 105
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.6-3 (Continued) j TABLE NOTATIONS j ACTION STATEMENTS j ACTION 3 - With the number of Noble Gas activity monitor Channels OPERABLE less than the minimum channels OPERABLE requirement, i effluent releases via this pathway may continue provided best
! efforts are made to repair the instrument and that grab
- samples are taken at least once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these i samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l For the Main Condenser Evacuation and Turbine Gland Sealing l Systems (MCES), this ACTION only applies during releases ll9I directed to the Plant Stack with Turbine Gland Sealing
- System or Condenser Vacuum Pumps in OPERATION.
ACTION 4 - With the number of Particulate / Iodine samoler Channels
! OPERABLE less than the minimum channels OPERABLE requirement, i effluent releases via this pathway may continue provided best
- efforts are made to repair the instrument and that samples
- are continuously collected with auxiliary sampling equipment
- as required in Table 5.4-1. For the MCES WRGM, this ACTION l only applies during periods of Primary to Secondary leakage l and the release has llQI been directed to the Plant Stack.
ACTION 5 - With the number of Waste (Process) flow rate monitor channels
- OPERABLE less than the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided best l efforts are made to repair the instrument and that flow rate
! is estimated at least once _every four hours. Waste (Process) flow rate estimates may be in the form of a log of running l ventilation equipment which is updated at four hour 1
intervals. For the waste gas holdup tank, this ACTION is j applicable only during periods of release.
i ACTION 6 - With the number of Samoler Flow Rate Monitor Channels
{' OPERABLE less than the minimum channels OPERABLE requirement, 4
effluent releases via this pathway may continue provided best efforts are made to repair the instrument and flow rate is
- estimated at least once every four hours. For the MCES j WRGM, this ACTION only applies during periods of Primary to l Secondary leakage and the release has MI been directed to the Plant Stack.
i 106 l
i L__--_ _ __________ _ _ - _ _.
UNT-005-014 3 Administrative Procedure Revision 4 :
Offsite Dose Calculation Manual TABLE 5.6-4
- i RADI0 ACTIVE GASEOUS EFFLUENT MONITOPING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL CONDITIONS p INSTRUMENT CHANNEL CHECK SOURCE CALIBRATION FUNCTIONAL IN WICH CHECK E LE_SI REQUIRED ,
I- WASTE GAS HOLDUP SYSTEM (GWMS):
- a. Noble Gas Activity Monitor Providing Alarm Prior to Pric+' tc 18 Months (4) Quarterly (1) ouring Waste Gas i and Automatic Termination of Release Release ReleO Decay Tank (PRM-IRE-0648)
Daily (5) N/A 18 Months Quarterly otscharge
- b. Waste (Process) Flow Rate Measurement ,
Device (GNM-IFIT-0648) unen nain i II- MAIN CONDENSER EVACUATION Alm TURBINE condenser GLAND SEALING SYSTEM (MCES):
- a. Noble Gas Activity Monitor Daily Monthly 18 Months (4) Quarterly (2) is under a vac = and (PRM-IRE-0002)
- b. Iodine Sampler Weekly N/A N/A N/A Release has ;
- c. Particulate Sampler Weekly N/A N/A N/A not been
- d. Sampler Flow Rate Monitor Daily N/A 18 Months Quarterly directed to Plant Stack l 107 i
Administrativa Prccedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 ,
TABLE 5.6-4 (Continuedi RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEWTATION S!IRVEILLANCE REQUIREME'dTS INSTRUMENT CHANNEL 5]EL CHANNEL CHANNEL CONDITIONS CHECK SOURCE CALIBRATION FUNCTIONAL IN WHICH CHECK TEST REQUIRED !
III- REACTOR AUXILIARY BUILDING VENTILATION SYSTEM (PLANT STACK):
- a. Noble Gas Activity Honitor Providing Alarm Daily Monthly 18 Months (4) QuarterlyQi At and Automatic Terminaticn of Release (PRM-IRE-0100.IS or 25 ) All
- b. lodine Sampler Weekly N/A N/A N/A ;
- c. Particulate Sampler Weekly N/A N/A N/A Times
- d. Sampler Flow Rate Monitor Daily N/A 18 Months Quarterly
- e. Waste (Process) Flow Rate Monitor Daily N/A 18 Months Quarterly (PRM-IFT-0100-I2/22)
IV- FUEL HAM) LING BUILDING VENTILATION SYSTEM - (NORMAL ):
- a. Noble Gas Activity Monitor Daily Monthly 18 Months (4) Quarterly (2) With (PRM-IRE-5IO7 A or B) Irradiated
- b. Iodine Sa@ler Weekly N/A N/A N/A ruel in
- c. Particulate Sampler Weekly N/A N/A N/A the storage
- d. Sagler Flow Rate Monitor Daily N/A 18 Months Quarterly rool !
- e. Waste (Process) Flow Rate P;.itor ' Daily N/A 18 Months Quarterly (PRM-IFT-5IO7 A or B) 108
Administrative ProcGdure 'UNT-005-014 i
Offsite Dose Calculation Manual Revision 4 i
TABLE 5.6-4 (Continued)
TABLE NOTATIONS
- l. The CHANNEL FUNCTIONAL TEST for Waste Gas Holduo System shall also
- demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists
l 1. Instrument indicates measured levels above the alarm / trip setpoint.
Circuit failure.
2.
- 3. Instrument indicates a downscale failure.
- 2. The CHANNEL FUNCTIONAL TEST for MCES and Fuel Handlina Buildina shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
i
- 1. Instrument indicates measured levels above the alarm setpoint.
I
- 2. Circuit failure.
- 3. The CHANNEL FUNCT!0N TEST shall for Plant Stack also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:
i
- 1. Instrument indicates measured levels above the alarm set.
- 2. Circuit failure.
- 3. Instrument controls not set in operate mode.
- 4. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its
, intended range of energy and measurement range. For subsequent CHANNEL l CALIBRATION, sources that have been related to the initial calibration shall be used.
- 5. CHANNEL CHECK for fdtE shall consist of verifying indication of flow during periods of r31 ease. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on day:. on which continuous, periodic, or batch releases are made.
i 4
l 109 1
i
Administrative Pr:ccdure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.6 INSTRUMENTATION (Cont'd) 5.6.3 Instrumentatioa Bases
- a. RADI0ACTIVLLIOUID EFFLUENT MONITORING ]
INSTRUMENTATION (5.6.1) '
The radioactive liquid effluent instrumentation is !
provided to monitor and control, as applicable, the releases of radioactive materials in liquid ,
effluents during actual or potential releases of l liquid effluents. The alarm / trip setpoints for '
these instruments shall be calculateo and adjusted in accordance with the methodology and parameters in Section 5.3.5 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part
- 20. The OPERABILITY and use of this instrumentation is consistent with the requirements J of General Design Criteria 60, 63, and 64 of l Appendix A to 10 CFR Part 50.
110
. - _ . . . . -. . - . - ~ - . . .
- Ad2inistrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Revision 4 l
l 5.6 INSTRUMENTATION (Cont'd)
- b. RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION (5.6.3) l The radioactive gaseous effluent instrumentation is provided to m)nitor and control, as applicable, the releases of radioactive materials in gaseous
- effluents during actual or potential releases of gaseous effluents. iiis alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 5.4.8 to ensure that the alarm / trip will ;
occur prior to exceeding the limits of 10 CFR Part I
- 20. This instrumentation also include provisions :
for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE l GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consis'ent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
l f d l
111
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.7 LIQUID AND GASE0US RADWASTE PROCESSES The block flow diagrams of the radwaste systems are'shown in Attachments 6.11 and 6.12. In order to obtaii a more detailed description, see the appropriate sections of the FSAR.
112
Administrative Procedure UNT-005-014 Offsite' Dose Calculation Manual Revision 4 i
5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS ,
5.8.1 Radioloaical Environmental Proaram Specification
- The radiological environmental monitoring program shall l be conducted as specified in Table 5.8-1.
l APPLICABILITY: At all times.
ACTION: l 1
- a. With the radiological environmental monitoring j program not being conducted as specified in Table :
! 5.8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating l Report required by Technical Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
j b. With the level of radioactivity as the result of l plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 5.8-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report.
l e
l 113
Administrative Prcctdure UNT-005-014 4 Offsite Dose Calculation Manual Revision 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
This Special Report identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be.taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 5.3.2, 5.4.2, and 5.4.3.
When more than one of the radionuclides in Table 5.8-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) .i. concentration (2) + .. 1 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 5.8-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 5.3.2, 5.4.2, and 5.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential annual dose to A MEMBER OF THE PUBLIC shall be indicated in this report.
I14
AdDinistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
l 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 5.8-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification l
6.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Annual l Radioactive Effluent Release Report and 7.lso l include in the report revisions of Attachments
! 6.13, 6.14, 6.16, 6.17 and 6.18 reflecting the new location (s).
l t
115
Administrative Proczdure UNT-005-014 Offsite Dose Calculation Manual Revisien 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
SURVEILLANCE RE0VIREMENTS:
The radiological environmental monitoring samples shall be collected pursuant to Table 5.8-1 from the specific locations given in Attachments 6.13 and 6.14, and shall be analyzed pursuant to the requirements of Table 5.8-1 and the detection capabilities required by Table 5.8-3.
116 l
Administrativa Procedure UNT-005-014 Offsite Dose Calculaticn Manual R:visicn 4 TABLE 5.8-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF EXPOSURE PATHWAY REPRESENTATIVE SAMPLING Alm TYPE AND FRQUENCY AND/OR SAMPLE SAMPLES AMD SAMPLE LOCATIONS 1 COLLECTION FREQUENCY OF ANALYSIS I. DIRECT RADIATION 2 31 routine monitoring stations either Quarterly Gamma dose quarterly.
with 2 or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY An outer ring stations, 1 in 10 of the meteorological sectors in the 6-to 8-km range from the site, The balance of the stations to be in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations 117
Administrative Prccedure UNT-005-014 l Offsite Doss Calculaticn Manual Rivisien 4 TABLE 5.8-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF EXPOSURE PATHWAY REPRESENTATIVE SAMPLING Als TYPE A15 FRQUENCY AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS 1 COLLECTION FREQUENCY OF ANALYSIS II. AIRBORNE Radiciodine and Samples from five locations Continuous sampler. Radiciodine Canister ,
Particulates operation with I-131 analysis Three samples from close to the sample collection weekly.
three SITE BOUNDARY locations, in weekly, or more !
different sectors, of the highest frequently if Particulate Samoler: i calculated annual average ground-level required by dust Gross beta D/Q loading. radiaactivity analysis ,
follo.ving filter One sample from the vicinity of a community change 4: Gamma isotopic having the highest calculated annual analysis of composite 5 average ground-level D/Q (by location) quarterly.
One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction. 3 ;
I f
118
Administrative Procedure UNT-005-014 Offsite Dose Calculatisn Manual R:visicn 4 TABLE 5.8-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF EXPOSURE PATHWAY REPRESENTATIVE SAMPLING AND TYPE AW FREQUENCY AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS 1 COLLECTION FREQUENCY OF ANALYSIS III. WATERBORNE
- a. Surface 6 One sample upstream Composite sample Gama isotopic analysis One sample downstream over one month monthly 5.11, period 7 11 Composite for tritium analysis quarterly.
- b. Ground Samples from one or two sources Quarterly Gama isotopic 5 and only if likely to be affected 8 tritium analysis quarterly.
- c. Drinking One sample of each of one of the three Composite sample I-131 analysis on nearest water supplies that could over two week each composite when be affected by its discharge. period 7 when I-131 the dose calculated analysis is for the consumption of performed, monthly 11 the water is greater composite than one mrem per year otherwise 9 Composite for gross beta and gama isotopic analyses 5 monthly 11 Composite for tritium analysis quarterly.
- d. Sediment from One sample from downstream area with Semiannually Gama isotopic shoreline existing or potential recreational value. analysis 5 semiannally.
119
-Administrative Procedura UNT-005-014 Offsite Dose Calculatten Manual R:visien 4 TABLE 5.8-1 (Continued)
RADIOLOGICAL ENVIROMENTAL MGNITORING PROGRAM
- NUMBER OF EXPOSURE PATHWAY REPRESENTATIVE SARPLING Am TYPE AW FREQUENCY AN/0R SAMPLE SAMPLES AM SAMPLE LOCATIONS I COLLECTION FREQUENCY OF ANALYSIS IV. INGESTION Samples from milking animals I
- a. Milk in the three locations within 5 km Semimonthly when Gamma isotopics and distance having the highest animals are on I-131 analysis dose potential. If there are pasture; monthly at semimonthly when i none, then, one sample from milking other times. animals are on pasture; animals in each of the three areas between monthly at other times 5 to 8 km distant where doses are calculated to be greater than i 1 mrem per yr.9 One sample from milking animals I at a control location 15-10 km ,
distant and ir the least prevalent wind direction.3
- b. Fish and One sample of each commercially Sample in season, or Gamma isotopic Invertebrates and recreational important semiannually if they analysis 5 on edible species in vicinity of plant are not seasonal- portions.
discharge area. ;
One sample of same species in areas not I influenced by plant _ discharge. -
i 120
Administrative Prccedura UNT-005-014 Offsite Dose Calculation Manual Rivisicn 4 TABLE 5.8-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUNBER OF EXPOSURE PATHWAY REPRESENTATIVE SANPLING Als TYPE A m FREQUENCY AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS 1 COLLECTION FREQUENCY OF ANALYSIS
- c. Food Products One sample of each principal class of food At time of harvest 10 Gamma isotopic products from any area that is irrigated analysis 5 on edible by water in which liquid plant wastes have portion discharged.
Samples of one to three different kinds Monthly when Garuna isotopic 5 and ,
of broad leaf vegetation grown nearest each available I-131 analysis.
of two different offsite locations of highest predicted annual average groundlevel D/Q if milk sampling is not perfomed.
One sample of each of the similar broad leaf Monthly when Gamma isotopic 5 and vegetation grown 15-30 km distant in the available I-131 analysis least prevalent wind direction if milk sampling is not performed. -
1 121 ,
_ _ - _ - _ - 'T C_ - - . - _ _ - __m - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_ - -
- _ _ -
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.8-1 (Continued)
TABLE NOTATIONS
- The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included 'r.
the sampling program.
1 Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Attachments 6.14, 6.16, 6.17 and 6.18. Refer to NUREG-0133 (Reference 2.5) and to Radiologic 01 Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, corrective action shall be completed prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table reflecting the new location (s).
122
Administrative Procedure -UNT-005-014 Offsite Dose Calculation Manual Revisien 4 ,
I TABLE 5.8-1 (Continued)
TABLE NOTATIONS 2
One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of. this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
t
.3 The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance wf th the ;
distance and wind direction criteria, other sites that provide valid background data may be substituted.
4 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
5 Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that n.::y be attributable to the effluents from the facility.
123
Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 1
l i
TABLE 5.8-1 (Continued) !
TABLE NOTATIONS 6 The " upstream sample" shall be taken at a distance beyond significant
-influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities. .
7 A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method j of sampling employed results in a specimen that is representative of the l liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
l 8 Groundwater samples shall be taken when this source is tapped for drinking i or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
9 The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in this document.
10 If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.
11 Composite samples for surface and/or Drinking Water gross beta and gamma isotopic analysis should be performed every four weeks. The maximum frequency is monthly.
124 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.8-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels WATER AIRBORNE FISH MILK FOOD ANALYSIS PARTICULATE PRODUCTS OR GASES (pci/kg , (pC1/kg, (pCi/1) (pci/M3 ) wet) (pci/1) wet)
H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300 ;
l 125
i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 TABLE 5.8-3 i DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 1
Lower Limits of Detection (LLD) abc l
WATER AIRBORNE FISH MILK FOOD SEDIMENT ANALYSIS PARTICULATE PRODUCTS OR AASES (pci/kg, (pci/kg, (pci/kg, (pCi/1) 1 (pCi/M3 ) wet) (pCi/1) wet) dry)
Gross 4 0.01 Beta H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1d 0.07 1 60 I Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 126
Administrative Proc: dure UNT-005-014 Offsite Dose Calculation Manual Revision 4 JAB.LE 5.8-3 (continued)
TABLE NOTATIONS a This list does not mean that only these nuclides are to be considered.
I Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and repc.rted in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
l l c Analyses shall be performed in such a manner that the stated LLDs will l be achieved under routine conditions. Occasionally background I
fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors j shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
d LLD for drinking water samples. If no drinking water pathway exists, l
l the Li.0 of gamma isotopic analysis may be used.
l l
l l
I 127
Adainistrative Procedure UNT-005-014 Offsite Dase Calculation Manual Revision 4 i
5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.2 Interlaboratory Comoarison Procram Specification Analyses shall be performed on all radioactive materials supplied as part of an Interlaboratory Comparison l
Program that has been approved by the Connission.
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Connission in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
SURVEILLANCE RE0VIREMENTS l
The Interlaboratory comparison Program shall be ,
l described in Section 5.8.5. A summary of the results obtained as part of the above required Interlaboratory Comparison Program sSall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
1 3
128
l Administrative Proccdure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.3 Land Use Census Specification !
A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk I animal, the nearest residence, and the nearest garden
- of greater than 50 m2 (500 ft2) producing broad leaf l vegetation. l APPLICABILITY: At all times.
ACTION:
- a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 5.4.3, identify the new location (s) in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8. !
l
- Broad leaf vegetation sampling of different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.
Specifications for broad leaf vegetation sampling in Table 5.8-1 Part 4.c. shall be followed, including analysis of control samples.
129
Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
- b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently :
being obtained in accordance with Specification 5.8.1, add the new location (s) to the radiological environmental monitoring program within 30 days.
The sampling location (s), excluding the control !
station location, having the lowest calculated dose or dose commitment (s), via the same exposure i pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to l Technical Specification 6.9.1.8 identify the new I location (s) in the next Annual Radioactive Effluent Release Report and also include in the report revision of Attachments 6.13, 6.14, 6.16, 6.17, and 6.18 reflecting the new locations (s). I SURVEILLANCE REQUIREMENTS The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological f.nvironmental Operating Report pursuant to Technical Specification 6.9.1.7.
130 i
Administ'rative Procedure UNT-005-014 i
Offsite Dose Calculation Manual Revision 4- l i
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5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
I 5.8.4 Descriotion of the Radioloaical Environmental Monitorina
- Proaram i The Radiological Environmental Monitoring Program (REMP) ;
l is expounded on in Attachment 6.13, and the Sample
. Location Table, Attachment 6.14. Attachment 6.15 explains the sector and zone designations for the sample
- locations. Attachments 6.16, 6.17 and 6.18 show the
- sample locations within the 2,10, and 50 mile radius of
- Waterford 3.
i Deviations are permitted from the required sampling j schedule if specimens are unobtainable due to hazardous f conditions, seasonal unavailability, malfunction of l . automatic sampling equipment and other legitimate 2
reasons. If specimens are unobtainable due to sampling i equipment malfunction, every effort shall be made to
- j. complete corrective action prior to the end of the next j sampling period. All deviations from the sampling i schedule shall be documented in the Annual Radiological-
- Environmental Operating Report. It is recognized that, i
{ at times, it may not be possible or practical continue l to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Programs.
]
131
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.5 Descriotion of the Interlaboratory Comoarison Proaram I l
As described in Section 5.8.2 the quality assurance in l radiological environmental sampling will be maintained 1 through participation in the Environmental Protection .
Agency's Radiological Laboratory Quality Assurance Program. The summary of results will be presented in tabular form and will include the type of analysis, the ,
preparation (collection) date, the date the results are ;
returned, the mean of the analyses (usually triplicate),
the standard deviation, the date the values are released ,
for information, the known value, the three standard deviation limit, and a two standard deviation /three standard deviation warning / action flag. If the sample analysis indicates results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report is submitted.
132
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 l
5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.6 Dispersion Parameters For Critical Locations As per Requirements 5.8.3, the dispersion parameters for the site boundary and where necessary, as identified by the Annual Land Use Census, are listed in Attachment 6.2. This table will be subject to changes based on the Annual Land Use Census and historical data.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.7 Radioloaical Environmental Monitorina Bases
- a. INTERLABORATORY COMPARIS0N PROGRAM (Section 5.8.2)
The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
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Administrative Proccdure UNT-005-014 Offsite Dose Calculatien Manual Revisien 4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
- b. LAND USE CENSUf (Section 5.8.3) j l
This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.
The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be use1. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 me provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for '
consumption by a child. To determine this minimum garden size, the following assumptions were made:
(1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 135
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS 5.9.1 Annual Radioactive Effluent Release Report A routine radioactive effluent release report covering the operation of the unit during the previous Twelve months shall be submitted as specified in Waterford 3 SES, Technical Specification 6.9.1.8.
5.9.1.1 The radioactive effluent release report shall include a summary of the quantities of radioactive liqid and gaseous effluents and solid waste released from the units as outlined in Regulatory Guide 1.21, Reference 2.10, with data summarized on a quarterly basis following the format of Appendix B thereof.
5.9.1.2 The Annual Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on ma3netic tape, or in the form 1 of joint frequency distributions of wind ;
speed, wind direction, and atmospheric stability.
4 136
Administrative Procedure UNT-005-014 Offsits Dose Calculation Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) l
( In lieu of submission with the i
Radioactive Effluent Release Report, the summary of required meteorological data may f
be filed on sitc and provided to the NRC when requested. This same report shall '
include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive !
liquid and gaseous effluents to members of !
the public due to their activities inside the site boundary during the report period.
I All assumptions used in making these l assessments (i.e., specific activity, l exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses ]
shall be performed in accordance with the !
methodology and parameters in this manual. l l
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Administrative Procrdure UNT-005-014 Offsite Dose Calculation Manual Revisien 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) b.9.1.3 The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed member of the public from reacter releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40CFR190, Environmental Radiation Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
5.9.1.4 The Annual Radioactive Effluent Release Report shall include the foilowing information for each class of solid waste (as defined by 10CFR 61) shipped off site during the report period:
A. Container volume B. Total curie quantity (specify whether determined by measurement or estimate),
C. Principal radionuclides (specify whether determined by measurement or estimate),
138 j
Ad:inistrative Procedure UNT-005-014 Offsite D:se Calculation Manual Revision 4 1
5.9 ROUTINE EFFLUENT R LEASE REPORTS (cont'd)
D. Source of waste and processing i employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
E. Type of container (e.g., Type A, Type B),and F. Solidificttion agent or absorbent (e.g., cement, urea formaldehyde).
5.9.1.5 The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. l 5.9.1.6 The Annual Radioactive Effluent Release Report shall include any changes to the Process Control Proaram (PCP) or the Offsite Dose Calculation Manual (0DCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to 0DCM Specification 5.8.3. The Annual Radioactive Release Report shall include information of Major Changes to Radioactive Waste Systems if the information is not submitted as part of the annual FSAR update.
139
Administrative Procedure UNT-005-014 0ffsite Dose Calculation Manual Revision 4 5.9- ROUTINE EFFLUENT RELEASE REPORTS (cont'd)
A. The submittal providing information on ODCM changes shall contain:
- 1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a complete legible copy of the ODCM together with appropriate analyses or evaluations justifying the change (s), if applicable.
- 2. A determination that the change did not reduce the accuracy or reliability of dose calculations or setpoint determinations.
- 3. Documentation of the fact that the change has been reviewed and found acceptable by the Plant Operations Review Committee (PORC).
140
Administrative Precedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.9 ROVIINE EFFLUENT RELEASE REPORTS (cont'd)
- 8. The submittal providing information on PCP changes shall contain:
- 1. Information submitted should consist of a complete legible copy of the PCP, together with appropriate analyses or evaluations, justifying the changes (s), if applicable.
- 2. Documentation of the fact that the change has been reviewed and found acceptable by the Plant Operations Review Committee (PORC).
NOTE Radioactive Was.s System change information may be submitted as part of the annual FSAR update in lieu of the Annual Radioactive Effluent Release Report.
C. The submittal providing information on licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) shall contain:
- 1. A summary of the evaluation that led to the the determination that the change could be made in accordance with 10CFR50.59 141
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd)
- 2. Sufficient detailed informatun to totally support the reason for the change without benefit of additional or supplemental information.
- 3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems.
- 4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.
- 5. An evaluation of the change which shows the expected maximum exposures 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.
142 l
Administrative Proc: dure UNT-005-014 Offsite Dose Calculation Manual Revisien 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd)
- 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period before the changes are to be made.
- 7. An estimate of the exposure to plant operating personnel as a result of the change.
- 8. Documentation of the fact that the change was reviewed and found acceptable by the Plant Operating Review Committee.
- 9. Changes to Radioactive Waste Systems performed using the plant design change process will be reported as per design change procedures.
5.9.1.7 The Annual Radioactive Effluent Release Report shall include, if applicable, a description of events which led to exceeding the following limiting condition for operation:
143
Ad;inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd)
A. The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to specification 5.4.1.
B. The quantity of radioactive material contained in each unprotected tank I shall be limited to Technical Specification 3.11.1.4.
5.9.1.8 The Annual Radioactive Effluent Release Report shall, if applicable, identify the cause of the unavailability of milk or fresh leafy I vegetable samples at locations required by 0DCM Spec. Table 5.8.1. The new location (s) for obtaining replacement samples shall be identified. Revised figure (s) and table for the ODCM reflecting the new locations shall be included in the report.
144
Ad;inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) :
5.9.1.9 . The Annual Radioactive Effluent Release ;
Report shall identify the new location (s), !
if a land use census pursuant to 00CM -
Specification 5.8.3 identifies an environmental sampling location that yields ;
a calculated dose or dose commitment greater than the values currently being calculated pursuant to DDCM Specification 5.4.3.
r 5.9.1.10 The Annual Radioactive Effluent Release Report shall identify the new location (s),
and include a revised figure (s) and table for the ODCM reflecting the new location (s) ;
if a land use census identifies an environmental sampling location (s) that yield a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained pursuant to ODCM Specification 5.7.1.
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i Administrative Procedure UNT-005-014 q Offsite Dose Calculatien Manual Revision 4 5.9 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) l 5.9.1.11 With less than the minimum number of radioactive liquid or gaseous effluent monitoring instrumentation channels operable for 30 days or longer, as required by ODCM Specification Table 5.6-3 or 5.6-1, explain in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified.
NOTE The Shift Supervisor shall be immediately notified and a Condition Report promptly initiated whenever an effluent sample is late or missing in accordance with applicable Specifications.
5.9.1.12 The Annual Radioactive Effluent Release Report shall identify any missing or late analysis results for radioactive effluent samples collected during the reporting period.
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Ad2inistrative Prccedure UNT-005-014 l Offsite Dose Calculaticn Manual Revision 4 5.10 SPECIAL EFFLUENT REPORTS 5.10.1 The Shift Supervisor shall be immediately notified and a Condition Report promptly initiated whenever any of l the following specifications have been exceeded. A Special Report shall be prepared for submittal to the NRC within 30 day period, as per the ACTION requirement of the specification that has been exceeded.
5.10.1.1 Radioactive Liquid Effluent Dose l Specification 5.3.2 l
5.10.1.2 Radioactive Liquid Waste Treatment System Specification 5.3.3 l
5.10.1.3 Radioactive Gaseous Ef fluent Dose, Noble Gas Specification 5.4.2 5.10.1.4 Radioactive Gaseous Effluent Dose, Iodine 131, I-133, Tritium, and Radionuclides in
, Particulate Form Specification 5.4.3 l
5.10.1.5 Radioactive Gaseous Waste Treatment System Specification 5.4.4 5.10.1.6 Radioactive Effluent Total Dose Specification 5.5.1 147 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.10 SPECIAL EFFLUENT REPORTS (cont'd) 5.10.2 Environmental Protection Aaency ReDortable Ouantities 5.10.2.1 If any of ODCM specifications, 5.3.1, 5.3.2, 5.4.1, 5.4.2, or 5.4.3 have been exceeded, an evaluation of the Radioactivity released verses EPA Reportable Quantities (RQ's) shall be performed as soon as practical.
The Shift Supervisor shall be immediately notified and a Condition Report promptly J
initiated whenever any radionuclide released ;
over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is greater than or equal to the EPA RQ. Notification requirements shall be performed as per UNT-006-010, Event Evaluation and Reporting.
Recipients of notification are: The National Response Center, the State Emergency Response Commission, and the Local l
Emergency Planning Committee. Methods for determination of reportability and the ,
Reportable Quantities values for radionuclides are contained within 40CFR302.
148
r Ad:inistrative Prec: dure UNT-005-014 Offsite Dose Calculation Manual Revision 4 5.11 SECONDARY RELEASE PATHS 5.11.1 This section addresses potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. The ODCM methodology for calculation of doses will be applied to an applicable
- release path if a likely potential arises for
! contributing more than 10% of the doses evaluated in i this manual.
l 5.11.2 Secondary Release Paths are expected to release trivial quantities of radionuclides. Some examples of Secondary Release Paths are listed below:
- Unmonitored Secondary System Steam Vents / Reliefs e Decon Shop / Hot Machine Shop Exhaust j
. Turbine Building Ventilation Exhaust e Unmonitored Tank Atmospheric Vents
- Radioactive Waste Compactor Building e Radioactive Waste Solidification Building
- Cooling Tower Atmospheric Entrainment 6.0 ATTACHMENTS Refer to Table of Contents 149 I
SITE B0UNDARY FOR RADIDACTIVE GASEOUS AND L1001D EFFLUENTS s i l tisu. % m3 j
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UNT-005-014 Revision 4 150
. ~ . - _ _
.- ~ , - - . . - - _ _ . . .. - , . - - . ~ . ~ . - . . .. . . - . _ . . . .
HISTORICAL AVERAGE DISPERSION AND DEPOSITION PARAMETERS FOR AREAS AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY 1
,! " " AVERAGE AIMOSPNERIC DISPERSION AND DEPOSITION PARAMETERS BASE 0 ON NISTORICAL METEOROLOGICAL DATA AND CURRENT LAND USE CENSUS l
Recepter i me er Direction sector Oletence Location X/e 0/4 from Site Location from site No Decay undepleted !
(sites) (meters) (sec/m3) (1/m2) site Soundary Me A 0.8 1287 1.0e 05 2.4e-08 NNE8 s 0.6 9M 1.6e-05 3.4e-08 nee C 0.6 9M 1.5e 05 2.Be-08 ENE8 D 0.6 9M 1.6e-05 2.5e-08 E E 0.8 1287 6.9e-06 1.3e-00 ESE F 0.6 9M 1.1e-05 2.3e-08 SE C 0.6 96 1.1e-05 3.1e 06
' sSE N 0.8 1287 6.3e-06 ' 2.4e-08 s J 1.6 2575 8.9e-07 2.7e-09
$W K 3.1 4909 3.0s-07 7.9e-10 SW L 3.4 5472 3.3e-07 9.1e 10 1
WsW M 1.5 2414 1.7e-06 4.9e-09 W W 1.0 1609 2.3e-06 7.3e 09 WW P 0.8 1287 7.5e-06 2.7e 08 W e 0.8 1287 1.De-05 3.2e-08 NW R 0.9 1648 9.4e-06 2.4e-08
- Residence N A 0.9 1448 7.Se 06 1.8e-08 NME 8 1.3 2092 3.0e-06 5.Se-09 NE C 0.9 1448 6.3e-06 1.2e-08 ENE D 0.9 1648 6.So 06 1.te-08 E E 2.2 3541 7.4e-07 1.0s-09 ESE F 3.1 4909 3.7e 07 4.8e 10 SE C 4.0 6437 2.3e-07 3.6e 10 W N 1.0 1609 2.3e-06 7.3e 09 nRAf P 0.9 1648 5.6e 06 2.0s 08 W G 0.9 1448 7.7e 06 2.3e-08 l NNW R 3.0 4828 7.7e 07 1.3e-09 l t
Milk Cow wb e 0.9 1448 7.7e 06 2.3e 08 W G 4.9 7506 2.6e-07 4.le 10 Vegetable Garden N 1.0 A 1609 6.le 06 1.4e 08 NME B 1.3 2092 3.0e 06 5.Be 09 4
NE C 0.9 1448 6.3e 06 1.2e 08 ENE D 0.9 1648 6.Se-06 1.1e 08 E E 2.2 3541 7.4e-07 1.0s 09 ESE F J.2 3541 7.0e 07 1.1e 09 SE G 2.3 -3701 6.2e-07 1.3e 09 WW M 1.5 2414 1.7e-06 4.9e 09 W N b1 1770 1.9e-M 5.7e 09 WW P 0.9 1544 5.6e 06 2.0s-08 W e 0.9 1648 7.7e 06 2.3e 08 NW R 3.0 4828 7.7e-06 1.3e 09 Seef Cow E 3.2 E 5150 3.7e 07 4.2e 10 ESE 3.5 F 5633 3.0e-07 3.6e 10 SE G 4.5 7242 1.9e 07 2.8e 10 WOW N 1.2 1931 2.7e 06 8.6e 09 nani P 0.9 1648 5.6e-06 2.0e-00 W e 0.9 1448 7.7e-06 2.3e-08 NW R 2.3 3701 1.3e-06 2.4e 09 Notest e The alte benadery in thle oester le Located ever unter. The Lacetion connet be scensied continueuely for the Life of the plant.
b the animate et thle locetten de not preesce milk for h6mmn canonsytten.
UNT-005-014 Revision 4 Attachment 6.2 (1 of 1) 151
SITE RELATED LIOUID INGEST 10N 00SE FACTORS (Aj) FOR INDIVIDUAL NUCLIDES I
Al factors for Adult age group Dy nuclide. .
Waterford Steam Electric Station Unit !!! I Discharge point : Circulating Water Disenarse to Mississippi River '
l Dilution Factor DW = 220.0 Nuctide Orgen Dose Conversion factors Bone Liver T. Body Thyroid Kidwy Lung Cl*LLI H3 0.00e00 2.66e 01 2. W -01 2. W 01 2. W 01 2.66e 01 2.66e-01 C 14 3.13e+04 6.26e+03 6.26e+03 6.26e+03 6.26e+03 6.26e+03 6.26e+03 Na 24 4.08e+02 4.08e+02 4.08e+02 4.08e02 4.08e+02 4.08e+02 4.08e+02 P-32 4.62e+07 2.87e+06 1.79e+c6 0.00e+00 0.00e+00 0.00e+00 5.19e+06 cc 51 0.00e+00 0.00c00 1.27e+00 7.62e 01 2.81e 01 1.69e+00 3.21e+02 Mn 54 0.00e+00 4.38e+03 8.35e+02 0.00e+00 1.30e+03 0.00e+00 1.34e+04 Mn-56 0.00e+00 1.10e+02 1.95e01 0.00e+00 1.40c02 0.00e+00 3.52e+03 Fe 55 6.59e+02 4.56e+02 1.06e+02 0.00e+00 0.00e+00 2.54e+02 2.61e+02 Fe*59 1.04e+03 2.45e+03 9.38e+02 0.00e00 0.00e00 6.83e+02 8.15e03 Co 58 0.00e+00 8.95e+01 2.01e*02 0.00e*00 0.00e+00 0.00e+00 1.81e+03 Co-60 0.00e+00 2.57e02 5.67e+02 0.00e+00 0.00e+00 0.00e+00 4.83e+03 Ni.63 3.12e06 2.16e+03 1.05e*03 0.00e+00 0.00e+00 0.00e+00 4.51e+02 Ni 65 1.27e+02 1.64e+01 7.51e+00 0.00e+00 0.00e+00 0.00e00 4.17e+02 Cu 66 0.00e+00 1.00e+01 4.70e+00 0.00e+00 2.52e01 0.00e+00 8.53e+02 Zn-65 2.32e+06 7.37e06 3.33e+06 0.00e*00 4.93e+06 0.00e+00 4.64e+06 In 69 4.93e+01 9.43e+01 6.56e+00 0.00e+00 6.13e+01 0.00e+00 1.42e+01 Br 83 0.00e+00 0.00e+00 4.06e+01 0.00e+00 0.00e+00 0.00e*00 5.82e+01 Br 86 0.00e+00 0.00e+00 5.24c01 0.00e+00 0.00e+00 0.00e+00 4.11e 06
............................................................................... l Br 85 0.00e+00 0.00e00 2.15e*00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 )
Rb 86 0.00e+00 1.01e+05 4.71e+06 0.00e+00 0.00e*00 0.00e+00 1.99e+06 i Rb 88 0.00e00 2.90e+02 1.54e*02 0.00e+00 0.00e+00 0.00e+00 4.00e 09 Ab 89 0.00e+00 1.92e+02 1.35e+02 0.00e+00 0.00e+00 0.00e+00 1.12e 11 Sr-89 2.22e+06 0.00e00 6.38e+02 0.00e+00 0.00e00 0.00e+00 3.57e+03 l tr 90 5.47e+05 0.00e+00 1.34e+05 0.00p00 0.00e+00 0.00e+00 1.58e+06 Sr.91 4.09e+02 0.00e+00 1.65e+01 0.00e*00 0.00e+00 0.00e+00 1.95e+03 sr 92 1.55e+02 0.00e+00 6.71e+00 0.00e+00 0.00e+00 0.00c00 3.08c03 Y 90 5.79e-01 0.00e*00 1.55e 02 0.00e+00 0.00e+00 0.00e00 6.14e+03 Y 91 8.49e+00 0.00e+00 2.27e 01 0.00e+00 0.00e+00 0.00e+00 4.67e+03 Y 91e 5.47e 03 0.00e+00 2.12e 06 0.00e+00 0.00e+00 0.00e+00 1.61e 02 Y 92 5.09e-02 0.00e00- 1.69e 03 0.00e+00 0.00e+00 0.00e+00 8.91e02 Conversion factors are in units of aram/hr per uCl/ml.
UNT-005-014 Revision 4 Attachment 6.3 (1 of 6) 152
SITE RELATED LIOUID INGEST 10N DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL NUCLIDES Al f actors for Adult age grote by nuclide.
Waterforts Steam Electric Station Unit I!!
Discharge point : Circulating Water Discr.2rge to Mississippi River Ollution Factor DW = 220.0 t-l Nuclide Organ Dose conversten Facters Sone Liver T. Body Thyroid Kidney Lung GI LLI Y 93 I
Zr 95 1.61e 01 0.00e+00 4.44e-03 0.00e+00 0.00c00 0.00e+00 5.12e03 i
Zr 97 2.52e 01 8.07e 02 5.46e-02 0.00e+00 1.2Te 01 0.00e+00 2.56e02 1.39e 02 2.81e 03 1.28e 03 0.00e+00 4.24e 03 0.00e+
Nb 95 00 8.69c02 Mo 99 4.47e+00 2.49e*00 1.34e+00 0.00e+00 2.46e*00 0.00e+00 1.51e+06 j Tc-101 0.00e+00 1.05e+02 1.99e+01 0.00e+00 2.37e+02 0.00e+00 2.43c02 9.22e 03 1.33e 02 1.30e-01 0.00e*00 2.39e 01 6.79e-0 3.99e 14
- l. ...................................................................
Tc 99m 3...........
- Ru-103 8.96e 03 2.53e-02 3.23e 01 0.00e+00 3.85e 01 1.24e 02 1.50e+01
! Ru-105 4.50e+00 0.00e+00 1.94e+00 0.00e*00 1.72e+01 0.00e+00 5.25e+02
- 3.75e-01 0.00e+00 1.48e.01 0.00e+00 4.84e+0 0.00e00 2.29e02 Ru.106 0.....................
6.69e*01 0.00e+00 8.44e*00 0.00e*00 1.29e*02 0.00e+00 4.33e+03
, As 110m 8.27e 01 7.65e 01 4.54e.01 0.00e+00 1.50e+00 0.00e+00 3.12e W Te 125m 2.57e+03 9.30e*02 3.44e*02 7.72e*0 1. % +06
............................................... 2 1.04e+06 0.00e*00 Te-127
! To.127m 1.05s+02 3.78e*01 2.28e+01 7.81e+01 4.29e02 0.00e+00 8.32e+03 3
T**129 6.69e+03 2.32e+03 7.90e*02 1.66e+03 2.63e*06 0.00e+00 2.17e+06 3.01e+01 1.13e+01 7.33e+00 2.31c0 1.26e+02 0.00e+00 2.27e+01 t
................................................1 To 129m
.............................. 4 j
To.131 1.10e+06 4.11e+03 1.74e*03 3.78e+03 4.60e*06 0.00e*00 5.55e+04 '
Te.131a 1.89e*01 7.88e*00 5.96e 00 '1.55e+01 8.27e+01 0.00e*00 2.67e+00 1.66e*03 8.10e+02 6.75e*02 1 ,
.......................................... 28e+03 8.21e*03 0.00e+00 8.05e+06 Te-132 ;
l 130 2.41e+03 1.56e+03 1.47e*05 1.72e+03 1.50e+06 0.00e+00 7.39e+06 ;
1-131 2.74e*01 8.09e*01 3.19e+01 6.86e+03 1.26e*02 0.00e+00 6.97e+01 1.51e+02 2.16e+02 1.24e+02 7
.......................................... 08e+06 ....................................
3.70e+02 0.00e+00 5.70e01 1 132 1 133 7.37e+00 1.97e+01 6.89e+00 6.89e+02 3.14e01 0.00e+00 3.70e+00 1 134 5.15e*01 8.96e*01 2.73e01 1.32e+06 1.56e*02 0.00e+00 8.06e+01 3.85e+00 1.05e+01 3.74e+00 1
.......................................... 81e+02 ....................................
1.66e+01 0.00e+00 9.11e 03 1 135 Cs-134 1.61e+01 4.21e+01 1.55e+01 2.78e+03 6.75e+01 0.00e+00 4.75e+01 Ca 136 2.98e+05 7.09e+05 5.79e+05 0.00e+00 2.29e+05 7.61e+06 1.26e+06 3.12e+06 1.23e05 8.86e+06 0.0
................................. ........ 0e+00 6.85e+06 9.39e+03 1.40e+06 Cs.137 Cs 138 3.82e+05 5.22e+05 3.42e+05 0.00e+00 1.TTe05 5.89e+06 1.01e+06 8e 139 2.64e+02 5.22e+02 2.59e*02 0.00e+00 3.86e02 3.79e+01 2.23e-03 9.66e 01 6.88e.06 2.835 02 0.00e+00 6.43e 04 3.90e-04 1.71p00 Conversion facters are in units of aremi/hr pe. uct/st.
UNT-005-014 Revision 4 Attachment 6.3 (2 of 6) 153
SITE RELATED LIOUID INGESTTON DOSE COMMITMENT l
FACTORS (Ai ) FOR INDIVIDUAL NUCLIDES !
Ai factors for Adult age group by nuclide. j Waterford Steam Electric Station unit 111 i Olscharge point : Circulating Water Discharge to Mississippi River I Dilution factor DW = 220.0 I l
Nuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kickiey Lung 01 LLI Ba 140 2.02e+02 2.54e 01 1.32e+01 0.00e+00 8.63e 02 1.45e 01 4.16e+02 Ba 141 4.69e 01 3.54e 04 1.58e 02 0.00e+00 3.29e 04 2.01e 04 2.21e 10 1 Ba 142 2.12e 01 2.18e 04 1.33e-02 0.00e+00 1.84e 04 1.23e 04 2.99e 19 l La 140 1.51e-01 7.59e 02 2.01e 02 0.00e+00 0.00e+00 0.00e+00 5.57e+03 La 142 7.71e 03 3.51e 03 8.73e 04 0.00e+00 0.00e+00 0.00e+00 2.56e+01 Co 141 2.59e-02 1.75e 02 1.99e 03 0.00e+00 8.15e 03 0.00e+00 6.71e+01 Co-143 4.57e 03 3.38e+00 3.74e 04 0.00e+00 1.49e-03 0.00e+00 1.26e+02 Ce 144 1.35e+00 5.66e-01 7.26e 02 0.00e+00 3.35e 01 0.00e+00 4.57e+02 Pr 143 5.54e-01 2.22e-01 2.75e 02 0.00e+00 1.28e 01 0.00e+00 2.43e+03 Pr-144 1.81e 03 7.53e 04 9.21e 05 0.00e+00 4.25e-04 0.00e+00 2.61e.10 Nd-147 3.79e 01 4.38e-01 2.62e 02 0.00e+00 2.56e 01 0.00e+00 2.10e+03 W 187 2.96e+02 2.47e+02 8.65e+01 0.00e+00 0.00e+00 0.00e+00 8.10e+04 Np*239 2.89e 02 2.85e 03 1.57e 03 0.00e+00 8.88e 03 0.00e+00 5.84e+02 Corwersion f actors are in mits of arsavhr per uti/st.
l l
UNT-005-014 Revision 4 Attachment 6.3 (3 of 6) 154
SITE RELATED LIQUID INGESTf0N DOSE COMMITMENT FACTORS (Ai ) FOR INDIVIDUAL NUCLIDES Al f actors for Adult age group by nuclide.
Waterford Steam Electric Station unit !!!
Discherge point : 40 Arpent Canet Dilution Factor 0W = 1.0 Nuclide Organ Dose Conversion factors Sone Liver T. Body Thyroid Kidney Lung GI LLI M3 C 14 0.00e+00 8.96e+00 8.96e+00 8.96e+00 8.96e+00 8.96e*00 8.96e+00 Ne*24 3.15e+06 6.30e+03 5.48e+02 5.48e+02 6.30e+03 6.30e+03 6.30e+03 6.30e+03 6.30e+03 5.48e*0
..................................... 2 5.48e*02 5.48e+02 5.48e+02 5.48e+02 P 32 Cr 51 4.62e+07 2.87e+06 1.79e+06 0.00e+00 0.00e+00 0.00e+00 5.20e+06 Mn*54 0.00e+004.76e+03 0.00e+00 0.00e+00 9.01.49e+00 8.96e-01 3.29e 01 1.98e+00 3.76e+02
................................. 8e+02 0.00e+00 1.42e+03 0.00e+00 1.46e+06 Mn.56 Fe 55 0.00e*00 1.20e+02 2.12e+01 0.00e*00 1.52e*02 0.00e+00 3.82e+03 Fe 59 8.87e+02 6.13e+02 1.40e+03 3.79e*03 1.2 1.43e+02 0.00e*00 0.00e*00 3.42e+02 3.52e+02
................................. 6e+03 0.00e+00 0.00e+00 9.19e*02 1.10e+06 Co 58 Co 60 0.00e+00 1.51e+02 3.39e+02 0.00e*00 0.00e+00 0.00e+00 3.06e+03 NI 63 0.00e+00 4.34e*02 4.19e*06 2.91e+03 1.419.58e+02 0.00e+00 0.00e+00 0.00e+00 8.16e+03
...................................e+03 0.00e+00 0.00e+00 0.00e+00 6.07e+02 kl.65 Cu 66 1.70e+02 2.21e+01 1.01e+01 0.00e+00 0.00e*00 c.00e+00 5.61e*02 2n-65 0.00e*007.50e+06 2.36e+06 1.69e+01 3 7.93e+00 0.00e+00 4.26e+01 0.00e+00 1.44e*03
................................ 39e+04 ..............................................
0.00e+00 5.02e+06 0.00e+00 4.73e+06 2n 69 Br.83 5.02e+01 9.60e*01 6.67e+00 0.00e*00 6.24e+01 0.00e+00 1.44e+01 Br.84 0.00e*00 0.00e+00 4.38e*01 0.00e+00 0.00e+00 0.00e+00 6.30e+01 0.00e+00 0.00e+00
.............................. 5.67e+01.............................................
0.00e+00 0.00e+00 0.00e+00 4.65e. 06 Br*05 ..
ab 86 0.00e+00 0.00e+00 2.33e+00 0.00e+00 0.00e+00 0.00s+00 0.00e+00 ab 88 0.00e+00 0.00e+00 1.03e*05 4.79e*06 0.00e+00 0.00e+00 0.00e+00 2.03e+06 2.95e+0
........................... 2............................................
1.56e+02 0.00e*00 0.00e+00 0.00e+03 4. 07e 09 Ab 89 ......
sr.89 0.00e+00 1.95e+02 1.37e+02 0.00e+00 0.00e+00 0.00e+00 1.13e.11
$r.90 4.78e+06 1.18e+06 0.00e+00.00e+00 1.37e*03 0.00e*00 0.00e+00 0.00e+00 7.66e+03
........................... 0..........................................
2.8Be+05 0.00e+00 0.00e+00 0.00e+00 3.40e+04 Sr 91 ........
Sr 92 8.79e+02 0.00e+00 3.55e+01 0.00e*00 0.00e+00 0.00e+00 ?.19e*03 Y 90 3.33e+02 1.38e+00 0.00e+000.00edW 1.44e+01 0.00e+00 0.00e+00 0.00e+00 6.60e+03 0.00e+00 0.00e+00 1.46e*0 6 Y 91 3.69e 02 0.00e*00..............................................
7 91m 2.02e*01 0.00e+00 5.39e.01 0.00e+00 0.00e+00 0.00e+00 1.11e+06 T 92 1.30e.02 0.00e+00 5.06e-06 0.00e*00 0.00e+00 0.00e+00 3.82e 02 1.21e.01 0.00e+00 3.53e.03 0.00e*00 0.00e+00 0.00e+00 2.12e+03 Conversten facters are in m its of area /hr per uC1/st.
UNT-005-014 Revision 4 Attachment 6.3 (4 of 6) l 155 l
l l
SITE RELATED LIOUID INGESTION DOSE COMMITMENT j FACTORS (Aj) FOR INDIVIDUAL NUCLIDES i l
l l
Al factors for Adult age group by nuclide. l Waterford Steam Electric Station Unit !!! )
Discharge point 40 Arpent Canal Dilution Factor DW = 1.0 Nuclide Organ Dose Conversion Factors Bone Liver T. Sody Thyroid Kidney Lung Gl LLI f 93 3.83e 01 0.00e00 1.06e 02 0.00e+00 0.00e+00 0.00e+00 1.22e+06 Zr-95 2.77e+00 8.88e 01 6.01e 01 0.00e+00 1.39e+00 0.00e+00 2.82e+03 Zr.97 1.53e.01 3.09e.02 1.41e.02 0.00e+00 4.67e-02 0.00e+00 9.57e+03 Ntr95 4.98e+00 2.77e+00 1.69e+00 0.00e+00 2.74e+00 0.00e+00 1.68e+06 Mo.99 0.00e+00 4.62e+02 8.79e+01 0.00e+00 1.05e+03 0.00e+00 1.07e+03 Tc.101 3.03e-02 4.36e-02 4.28e 01 0.00e*00 7.85e-01 2.23e-02 1.31e-13 Tc.99m 2.94e.02 8.32e.02 1.06e+00 0.00e*00 1.26e*00 4.07e.02 4.92e*01 Ru.103 1.90e+01 0.00e+00 8.56e+00 0.00e+00 7.57e+01 0.00e+00 2.31e*03 Ru-105 1.65e+00 0.00e+00 6.52e 01 0.00e+00 2.13e+01 0.00e+00 1.01e*03 Ru.106 2.95e*02 0.00e+00 3.73e+01 0.00e+00 5.69e+02 0.00e+00 1.91e+06 As.110m 1.41e+01 1.30e+01 7.74e*00 0.00e+00 2.56e+01 0.00e+00 5.32e+03 Te.125m 2.79e+03 1.01e*03 3.74e+02 8.39e+02 1.13e+04 0.00e+00 1.11e+06 Te.127 1.14e+02 6.11e+01 2.48e*01 8.48e+01 4.66e+02 0.00e+00 9.03e+03 Te-127m 7.05e*03 2.52e+03 8.59e+02 1.80e*03 2.86e+06 0.00e+00 2.36e+04 Te-129 3.27e+01 1.23e+01 7.96e+00 2.51e+01 1.37ee32 0.00e+00 2.47e+01 Te.129m 1.20e+06 4.47e+03 1.89e+03 4.11e+03 5.00e+06 0.00e*00 6.03e+04 Te 131 2.05e+01 8.57e+00 6.67e+00 1.69e*01 8.98edel 0.00e+00 2.90e+00 Te.131m 1.80e+03 8.81e+02 7.34e+02 1.39e*03 8.92e.43 0.00e+00 8.74e+06 Te 132 2.62e+03 1.70e+03 1.59e+03 1.87e+03 1.63e*06 0.00e+00 8.02e+04 I 130 9.01e+01 2.66e+02 1.05e+02 2.25e+06 4.15e*02 0.00e+00 2.29e+02 1 131 4.96e+02 7.09e*02 4.06e+02 2.32e+05 1.22s+03 0.00e+00 1.87e+02 1 132 2.42e+01 6.6Te+01 2.26e+01 2.26e*03 1.03e*02 0.00e+00 1.22e*01 I.133 1.69e*02 2.96e+02 8.97e+01 4.32e+06 5.13e02 0.00e+00 2.66e+02 I 134 1.26e+01 3.43e+01 1.23e+01 5.96e+02 5.66e+01 0.00e+00 2.99e-02 I.135
) '
5.28e*01 1.38e+02 5.10e*01 9.11e+03 2.2Re*02 0.00e+00 1.54e*02 Cs 134 3.03e*05 7.21e*05 5:09e+05 0.00e+00 2.31e+05 7.75e+06 1.26e+06 Cs 134 3.17e+06 1.25e+05 9.01o*06 0.00e*00 6.97e*06 9.55e+03 1.42e+06 Ca.137 3.88e+05 5.31e+05 3.68e+05 0.00e+00 1J0e*05 5.99e+06 1.03e+06 Ca.138 2.69e+02 5.31e*02 2.63e+02 0.00e+00 3.90e+02 3.85e*01 2.27e.03 8e-139 9.00e*00 6.41e-03 2.64e.01 0.00e+00 5.P9e.03 3.64e-03 1.60e+01 Conversion facters are in mits of aren/hr per uct/s!. !
l l
1 1
UNT-005-014 Revision 4 Attachment 6.3 (5 of 6) 156 l
l
1 - . _ . . _ __ _ _ . _ _ . _ . . . . . . . . _ . _ .
SITE RELATED L10UID lilGESTION DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL tlUCLIDES Al f actors for Adult age group by nuclide.
Waterford steam Electric station unit !!!
Discharge point 40 Arpent Canet Oltution Factor DW = 1.0 Nuctide Organ Dose conversion factors i
Bone Liver T. Body Thyroid Kitey Lung Cl-LLI Sa 140 Ba 141 1.88e+03 2.37e+00 1.23e+02 0.00e+00 8.05e 01 1.35e+00 3.88e+03 Ba 142 4.37e+00 3.30e0303 1.98e+00 2.03e 1.48e 01 0.00e+00 3.07e 03 1.87e 03 2.06e 09 1.24e-
.................................... 01 0.00e+00 1.72e 03 1.15e 03 2.78e-18 La-140 La-142 3.58e 01 1.80e 01 4.76e-02 0.00e+00 0.00e+00 0.00e+00 1.32e+04 Co-141 1.83e01 8.01e 025.42e-01 8.33e 03 6.12.07e 03 0.00e+00 0.00e+00 0.00e+00 6.08e+01
................................. 5e 02 0.00e+00 2.52e-01 0.00e+00 2.07e*03
.......c.....................................
Co 143 Co 144 1.41e-01 1.04e+02 1.16e-02 0.00e+00 4.60e-02 0.00e+00 3.90e+03 Pr-143 4.18e+01 1.75e+01 2.24e+00 0.00e+00 1.04e+01 0.00e+00 1.41e+04 1.32e+00 5.28e.01 0.00e+00 3.05e-01 0.00e+00 5 77e+03 Pr-144 6.52e 02......................................... ......
Nd 147 4.31e 03 1.79e.03 2.19e 04 0.00e+00 1.01e.03 0.00e+00 6.19e.10 W 187 9.00e-01 1.04e+00 6.22e 02 0.00e+00 6.00e-01 0.00e+00 4.99e+03 3.04e+02 2.55e+02 Np-239 0.00e+00 0.00e+00 0.00e+00 8 34e+04 8.90e+01...............................................
1.28e-01 1.25e 02 6.91e 03 0.00e+00 3.91e 02 0.00e+00 2.57e+03 Conversion factors are in units of arenvhr per uCl/st.
UNT-005-014 Revision 4 Attachment 6.3 (6 of 6) 157
DOSE FACTORS FOR EXPOSURE TO A SEMI- INFINITE CLOUD OF N0BLE GASES Nuclide (Nj) (l.i) (Mi ) (Ki )
p-Air
- S-Skin ** y-Air
- y-Body **
Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9. 73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1. 73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4. 76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E 03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe138 4. 75E-03 4.13E-03 9.21E-03 8.83E-03 mrad- m3
- pCl- yr miem- m3
- pCl- yr Extracted from Table B-1 of Regulatory Guide 1.109, Revision 1,1977.
UNT-005-014 Revision 4 Attachment 6.4 (1 of 1) 158
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri l Ri factors for Adult age group DY nuctide.
Waterford Steen Electric Stetton Pathway : Geseous setease inhetetton Pathway al Nuctice organ Dose conversion factors l
Bone Liver T. Body Thyroid Ki@ey Lung GI.LLI H3 C 16 0.00e+00 1.26e+03 1.26e*03 1.26e+03 1.26e+03 1.26e+03 1.26e+03 Wa 24 1.82e+06 3.41e+03 1.02e+06 1.02e+06 1.0 3.61e+03 3.61e+03 3.41e+03 3.41e+03 3.41e+03
................................. 2e+06 1.02e+04 1.02e+06 1.02e+04 1.02e+04 P-32 Cc-51 1.32e+06 7.71e+06 5.01e+06 0.00e+00 0.00e+00 0.00e+00 8.6(e+04 Mn*54 0.00e+00 0.00e+00 1.00e+02 5.95e+01 .28e01 1.64e+04 3.32e+03 0.00e+00 3.96e+06 6.
................................ 30e+03 0.00e+00 9.84e+03 1.40e+06 7.74e+M Mn*56 Fe 55 0.00e+00 1.26e+00 1.83e.01 0.00e+00 1.30e+00 9.46e+03 2.02e+06 Fe.59 2.46e+06 1.70e+06 1.18e*06 2.78e+06 1 3.94e+03 0.00e+00 0.00e+00 7.21e+M 6.03e+03 I ................................ 06e+06 ..............................................
0.00e+00 0.00e 00 1.02e+06 1.88e+05 co 58 Co.60 0.00e+00 1.5Be+03 2.07e+03 0.00e+00 0.00e+00 9.28e+05 1.06e+05 Ni 63 0.00e+00 4.32e*05 1.15e+06 1.68e+06 0.00e+00 0.00e+00 5.97e+06 2.aSe+05 3.16e+06-
- ...............................1.65e+06 0.00e+00 0.00e+00 1.78e+05 1.34e+06 Ni 65 Cu-64 1.56e+00 2.10e.01 9.12e-02 0.00e00 0.00e00 5.60e*03 1.23e06 j
Zn-65 0.00e+001.03c05 3.26e+04 1.66e+006 6.15e 01 0.00e+00 4.62e+00 6.78e+03 4.90e+M i
................................ 66e 06 0.00e+00 6.90e06 8.66e+0! 5.34e+06 Zn-69 ..............................................
- Br-83 3.46e-02 6.51e-02 4.52e 03 0.00e00 4.22e-02 9.20e+02 1.63e+01 Br 86 0.00e*00 0.00e00 0.00e+00 2.61e+02 0.00e+00 0.00e+00 0.00e+00 2.32e+02 0.00e+00 Br 85 0.00e+00 0.00e*00 0.00e+00 1.6&
3.13e02............................................e.03 ab 86 0.00e+00 0.00e+00 1.28e+01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3
ab 88 0.00e+00 0.00e+00 3.87e+01.35e05 5.90e+04 0.00e+00 0.00e+00 0.00e+00 1.66e+04 1.93e02 0.00e00 0.00e+00 0.00e+00 3.34e.09 Rb 89 2.......................................... ........
sr 89 0.00e00 2.56e+02 1.70e+02 0.00e+00 0.00e+00 0.00e+00 9.28e.12 sr 90 3.06e+05 9.92e+07 0.00e+0 0.00e+00 8.72e+03 0.00e00 0.00e 00 1.60e+06 3.50*05 Sr.91 6.10c06 0.00e+00 0.00e+00 9.60e+06 7 0............................................ 22e+05 sr 92 6.19e+01 0.00e+00 2.50e+00 0.00e+00 0.00e+00 3.65cM 1.91e+05 Y 90 6.74e+00 2.09e*03 0.00e+00 2.91e 01 0.00e00 0.00e+00 1.65cM 4.30e+M 0.00e0 7 91 5.61e+01 0.00e+00 0.00e+00 1.70e+05 5.06c 05 0.......................................... ........
Y-91m 4.62e+05 0.00e+00 1.2'4e+04 0.00e+00 0.00e+00 1.70e+06 3.85e+05 Y-92 2.61e-01 0.00e*00 1.02e 02 0.00e*00 0.00e+00 1.92e+03 1.33e+00 1.03e+01 0.00e+00 3.02e 01 0.00e+00 0.00e+00 1.57e+M 7.35e+M Conversion factors are in mits of erenVyr per uCi/c@ic ester.
i i
UNT-005-014 Revision 4 Attachment 6.5 (1 of 12) 4 159
.- . - - - .~ . . . - - - . ~ -. .. - - - .. . .. . . _ _ - . -- . . .
INHALAT10N PATHWAY 00SES DUE TO l
RADIONUCLIDES OTHER THAN N0BLE GASES. Rj l
l I
i Ri factors for Adult age group by nuclide.
Waterford steen Electric Stetton '
Pathway : Caseous Release inh 6Lation Pathway Ri
)
Nuclide organ Oose Conversion Factors 1
Sone Liver T. Sody Thyreld Kidmy Lung GI LLI ]
I f 93 9.44e+01 0.00e+00 2.61e+00 0.00e+00 0.00e+00 4.85e+06 4.22e+05 ;
Zr 95 1.07e+05 3.44e+06 2.33e+06 0.00e+00 5.42e+06 1.77e+06 1.50e+05 i Zr 97 9.68e+01 1.96e+01 9.04e+00 0.00e+00 2.97e+01 7.87e+04 5.23e+05
............................................................................... )
Nb-95 1.41e+06 7.82e+03 4.21e+03 0.00e+00 7.74e+03 5.05e+05 1.04e+05 '
Mo-99 0.00e+00 1.21e+02 2.30e+01 0.00e+00 2.91e+02 9.12e+06 2.48e+05 ;
Tc 101 4.18e.05 6.02e 05 5.90e-M 0.00e+00 1.08e 03 3.99e+02 1.09e.11
............................................................................... l Tc.99m 1.03e-03 2.91e-03 3.70e.02 0.00e+00 4.42e.02 7.64e*02 4.16e*03 Ru.103 1.53e*03 0.00e+00 6.58e+02 0.00e+00 5.83e+03 5.05e+05 1.10e+05 Ru-105 7.90e.01 0.00e+00 3.11e.01 0.00e+00 ,1.02e+00 1.10e+06 4.82e+06 )
Ru.106 . 6.91e+06 0.00e+00 8.72e+03 0.00e*00 1.34e+05 9.36e*06 9.12e*05 ,
Ag-110m 1.08e+06 1.00e*06 5.96e+03 0.00e+00 1.97e+06 4.63e+06 3.02e+05 !
Te.125e 3.42e+03 1.58e+03 '4.67e+02 1.05e+03 1.24e+06 3.14e+05 7.06e+06
............................................................................... l To.127 1.40e*00 6.42e 01 3.10e.01 1.06e+00 5.10e*00 6.51e+03 5.74e+06 i Te.127m 1.26e+06 5.77e*03 1.57e*05 3.29e*03 4.58e+06 9.60e+05 1.50e+05 l To.129 4.98e-02 2.39e-02 1.24e.02 3.90e-02 1.87e.01 1.96e*03 1.57e+02 '
Te-129m 9.76e+03 4.67e+03 1.58e+03 3.44e*03 3.66e+06 1.16e+06 3.83e*05 !
Te.131 1.11e.02 5.95e-03 3.59e-03 9.36e-03 4.37e.02 1.39e+03 1.84e+01 l Te.131e 6.99e+01 4.36e+01 2.90e+01 5.50e+01 3.09e+02 1.46e+05 5.56e+05 j Te-132 2.60e+02 2.15e+02 1.62e+02 1.90e+02 1.46e+03 2.80e+05 5.10e+05 1-130 4.58e+03 1.34e+06 5.28e+03 1.14e+06 2.09e+04 0.00e*00 7.69e+03 I-131 2.52e+06 3.58e+06 2.05e+06 1.19e+07 6.13e+06 0.00e+00 6.28e*03 1 132 1.16e+03 3.26e+03 1.16e+03 1.14e+05 5.18e+03 0.00e+00 4.06e+02 1 133 8.66e*03 1.48e+06 4.52e+03 2.15e+06 2.58e+06 0.00e+00 8.88e+03 1 136 6.46e*02 1.73e+03 6.15e*02 2.98e+06 2.75e+03 0.00e+00 1.01e+00 1 135 2.60e+03 6.98e+03 2.47e+03 4.48e+05 1.11e+06 0.00e+00 5.25e+03 Cs 134 3.73e+05 8.48e+05 7.28e+05 0.00e+00 2.80e+05 9.76e+06 1.04e+06 Ca.136 3.90e+06 1.46e+05 1.10e+05 0.00e+00 8.56e+06 1.20e+06 1.17e+06 Cs.137 4.78e+05 6.21e+05 4.28e*05 0.00e+00 2.22e*05 7.52e+06 8.40e+03 i Co 138 3.31e+02 6.21e*02 3.24e*02 0.00e+00 4.80e+02 4.86e+01 t.86e-03 1 Se.139 9.36e-01 6.66e 06 2.76e-02 0.00e+00 6.22e 06 3.76e+03 8.96e+02 Conversion facters ere in mits of arearyr per uti/cthic meter. !
UNT-005-014 Revision 4 Attachment 6.5 (2 of 12) 160
p.
j INHALAT10N PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Rj 1
t l Ri factors for Acult age group by nuclide.
l Watertore Steam f,tectric station Pathway Caseous Aeteese inhetetton Pathway Al 1
7 I Nuclide Organ Dose Conversion Factors Sone Liver T. Body Thyroid Kishey Les GI LLI a
l Be 140 3.90e+06 4.90e+01 2.57e+03 0.00e+00 1.67e+01 1.27e+06 2.18e+05 Be-141 1.00e 01 7.53e 05 3.36e-03 0.00e+00 7.00e-05 1.94e+03 1.16e 07 Be 142 2.63e 02 2.70e 05 1.66e.03 0.00e+00 2.29e 05 ' 1.19e+03 1.57e 16 l La 140 3.44e+02 1.74e*02 4.58e+01 0.00e+00 0.00e+00 1.36e+05 4.58e+05
- La 142 6.83e 01 3.10e 01 7.72e 02 0.00e+00 0.00e+00 6.33e+03 2.11e+03
- Co.1;.1 1.99e+04 1.35e+M 1.53e+03 0.00e+00 6.26e+03 3.62e+05 1.20e+05
. Co 143 1.86e+02 1.38e+02 1.53e+01 0.00e+00 6.08e+01 7.90e+04 2.26e+05 f Ce 144
' 3.43e+06 1.43e+06 1.86e+05 0.00e+00 0.00e+00 7.7Be+06 8.16e*05
, Pr*143 9.36e+03 3.75e+03 4.64e+02 0.00e+00 2.16e*03 2.81e+05 2.00e+05
- Pr 144 3.01e 02 1.25e 02 1.53e 03 0.00e*00 7.05e.03 1.02e*03 2.15e-08 Nd-147 5.27e*03 6.10e+03 3.65e+02 0.00e+00 3.56e*03 2.21e+05 1.73e+05 j W 187 8.48e+00 7.0Be*00 2.48e+00 0.00e+00 0.00e+00 2.90e+04 1.55e*05 3 ...............................................................................
i Mp 239 2.30e+02 2.24e+01 1.24e+01 0.00e+00 7.00e+01 3.76e+04 1.19e+05 F
convereien f acters are in mits of areatyr per uct/ cubic meter.
3 I
3 i
t UNT-005-014 Revision 4 Attachment 6.5 (3 of 12) 161
i INHALAT10N PATHWAY DOSES DUE TO I
RAD 10NUCL1 DES OTHER THAN NOBLE GASES. Rj l i
l i
Ri f actors for Teen age grote by nuclide.
Watertora Steen Electric Station Pathway Geseous Release inhalation Pathway Ri '
Nuclide Organ 00se Conversion Factors l
Bone Liver T. Body thyroid Kidney Lung cl LLI N3 C 14 0.00e+00 1.27e+03 1.27e*03 1.27e+03 1.27e+03 1.27e+03 1.27e+03 No 24 2.60e+06 6.87e+03 1.38e+04 1.38e+06 1.384.87e+03 4.87e+03 4.87e+03 4.47e*03 4.87e+03
...................................e+06 P 32 1.38e+06 1.38e+06 1.38e+06 1.38e*06
............................................ )
Cr-51 1.89e*06 1.10e+05 7.16e+06 0.00e+00 0.00e+00 0.00e+00 9.28e+06 Mn 54 0.00e+00 0.00e+00 0.00e+00 5.11e+04 8.41.35e+02 7.50e+01 3.07e+01 2.10e*06 3.00e+03
................................. 0e+03 0.00e+00 1.27e+06 1.98e+06 6.68e+06 Mn.56 Fe 55 0.00e+00 1.70e+00 2.52e 01 0.00e+00 1.79e+00 1.52e+04 5.74e+04 Fe.59 3.34e+06 2.38e+04 1.59e*01 3.70e+06 1 5.54e+03 0.00e+00 0.00e+00 1.24e+05 6.39e+03
................................ 43e*06............................................
0.00e*00 0.00e+00 1.53e+06 1.78e+05 co 58 .
Co 60 0.00e+00 2.07e+03 2.78e+03 0.00e+00 0.00e+00 1.34e+06 9.52e+04 i Nl.63 0.00e+00 1.51e+06 1.98e+06 0.00e+00 0.00e+00 8.72e+06 2.59e+05 5.80e+05 4.34e+06
...............................1.98e+06 0.00e+00 0.00e+00 3.07e+05 1.42e+06 N(.65 Cu-64 2.18e+00 2.93e-01 1.27e.01 0.00e*00 0.00e+00 9.36e+03 3.67e+06 Zn.65 0.00e+00 2.03e+00 3.86e+06 1.34e+05 6 8.68e.01 0.00e+00 6.41e+00 1.11e+06 6.14e*06
................................ 24e*46 ..............................................
0.00e+00 8.66e+06 1.24e*06 4.66e+06 In*09 Br.83 4.85e.02 9.20e-02 6.66e.03 0.00e+00 6.02e.02 1.58ee03 2.85e*02 Br*84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4. 3.44e+02 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Br*85 0.00e*00 0.00e+00 0.00e+00 0.00e+0 0 33e+02............................................ .
Rb 86 0.00e+00 0.00e+00 1.83e+01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb 88 0.00e+00 0.00e+00 1.90e+05 8.60e+06 0.00e*00 0.00e+00 0.00e+00 1.77e+06 5.46e+02 Ab.89 0.00e+00 0.00e+00 0.00e+00 2.92e.05 2.72e+02.............................................. .
Sr.89 0.00e+00 3.52e+02 2.33e+02 0.00e+00 0.00e*00 0.00e+00 3.38e.07 3r*90 6.34e+05 0.00e+00 1.00e+0s 0.00e*00 6 1.25e+06 0.00e+00 0.00e+00 2.42e+06 3.71e+05
................................ 68e+06 0.00e+00 0.00e+00 1.65e+07 7.65e+05 Sr*91 Sr 92 8.80e+01 0.00e+00 3.51e+00 0.00e+00 0.00e+00 6.07e+06 2.59e+05 Y40 9.52e+00 2.90e+03 0.00e+00 4.06e.01 0.00e+00 0.00e+00 2.76e+06 1.19e+05 0.00e*00
.............................. 8.00e+01 .. 0.00e+00 0.00e+00 2.93e+05 5.59e+05 f41 Y 91e 6.61e+05 0.00e+00 1.77e+06 0.00e+00 0.00e+00 2.96e*06 4.09e+05 Y 92 3.70e.01 0.00e+00 1.42e-02 0.00e+00 0.00e+00 3.20e+03 3.02e+01 1.47e+01 0.00e+00 4.29e.01 0.00e+00 0.00e+00 2.68e+04 1.65e+05 Corwersion facters are in units of aren/yr per utf/c4fc meter.
UNT-005-014 Revision 4 Attachment 6.5 (4 of 12) 162
l INHALATION PATHWAY DOSES DUE TO '
RADIONUCLIDES OTHER THAN NOBLE GASES. Rj l
l l
i l
i l
Ri f actors f or Teen age group Dy ruclide.
Waterford Steen Electric Station Pathway : Caseous Release irttelstion Pathway Al Nuclide Orson Dose Conversion factors Bone Liver T. Body Thyroid Kichey Lung GI LLI l
l Y 93 1.35e+02 0.00e+00 3.72e+00 0.00e+00 0.00e+00 8.32.+04 5.79e+05 l Zr-95 1.46e+05 4.58eM 3.15e+04 0.00c00 6. 74e+M 2.69e+06 1.49e05 Zr 97 1.38e+02 2.72e+01 1.26e+01 0.00e+00 4.12e+01 1.30e+05 6.30e+05 Nb-95 1.86e+06 1.03e+04 5.66e+03 0.00e+00 1.00e+M 7.51e+05 9.68e+06 Mo 99 0.00e+00 1.69e+02 3.22e+01 0.00e+00 4.11e+02 1.54e+05 2.69*05 Tc-101 5.92e 05 8.60e 05 8.24e-04 0.00*00 1.52e 03 6.67e+02 8.72e 07 j
............................................................................... I Tc 99m 1.38e 03 3.86e 03 4.99e-02 0.00e00 5.76e 02 1.15e+03 6.13e+03 )
Ru 103 2.10e+03 0.00e+00 8.96e+02 0.00e+00 7.43e+03 7.83c05 1.09e+05 Ru 105 1.12e+00 0.00e+00 4.34e-01 0.00e*00 1.61e+00 1.82e+06 9.06e+04 Ru-106 9.84e+06 0.00e+00 1.24e+06 0.00e+00 1.90e+05 1.61e+07 9.60e+05 As 110e 1.38e+06 1.31e*06 7.99e*03 0.00e+00 2.50eM 6.75e+06 2.73e+05 Te-125m 4.88e+03 2.24e+03 6.67e+02 1.60e+03 0.00e+00 5.36e+05 7.50e06 Te-127 2.01e+00 9.12e-01 4.42e-01 1.42e+00 7.28p00 1.12c04 8.00ce6 Te 127m 1.80e+04 8.16e+03 2.18e+03 4.38e+03 6.56e+06 1.66e+M 1.59e05 Te 129 7.10e 02 3.38e-02 1.76e.02 5.18e 02 2.66e-01 3.30e*03 1.62e+03 Te.129m 1.39e+06 6.58e+03 2.25e+03 4.58e+03 5.19e06 1.98e+06 4.05c05 Te-131 1.58e-02 8.32e-03 5.06e-03 1.24e-02 6.18e-02 2.s 3+03 1.51e+31 Te.131s 9.84e+01 6.01e+01 4.02e+01 7.25e+01 4.39e+02 2.3aes05 6.21e+05 Te-132 3.60e+02 2.90e02 2.19e+02 2.66e+02 1.95e+03 4.49e+05 4.63e+05 I 130 6.24e+03 1.79e+04 7.17e+03 1.49e*06 2.75e+06 0.00e+00 9.12e+03 I-131 3.54e+06 4.91e+06 2.64e+06 1.46e+07 8.40e06 0.00c00 6.49e03 1 132 1.59e+03 4.38e*03 1.58e*03 1.51e+05 6.92e+03 0.00e+00 1.27e+03 1*133 1.22e+06 2.05e+06 6.22e+03 2.92e+06 3.59c06 0.00e+00 1.03e+M I-134 8.88e+02 2.32e+03 8.40e+02 3.95e+M 3.66e+03 0.00e+00 2.06e+01 1 135 3.70e+03 9.44e03 3.49e+03 6.21e+05 1.49e*06 0.00e+00 6.95e+03 Cs 134 5.02e+05 1.13e+06 5.69e+05 0.00e+00 3.75e+05 1.46e+05 9.76e+03 Cs 136 5.15e+M 1.94e+05 1.37e+05 0.00e00 1.10e05 1.78e+04 1.09e M Cs 137 6.70e+05 8.68e+05 3.11e+05 0.00e+00 3.04e05 1.21e*05 8.48e*03 Cs 138 4.66e+02 8.56e+02 4.46e+02 0.00e+00 6.62e+02 7.87e+01 2.70e 01 8e.139 f 1.34e+00 9.44e.06 3.90e.02 0.00e+00 8.88e 06 6.46e03 6.45e+03 '
Conversion f actors are in tsdts of areWyr per uct/ ethic seter.
UNT-005-014 Revision 4 Attachment 6.5 (5 of 12) 163 t
I
INHALAT10ft PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Rj Ri factors for Teen age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release inhetetton Pathway al Nuclide Organ Dose Conversion factors Bone Liver T. Body thyroid Kichey Lme GI LLI Ba 140 5.47e+04 6.70e+01 3.52e+03 0.00e+00 2.28e+01 2.03e+06 2.29e+05 Be 141 1.42e 01 1.06e 04 4.74e 03 0.00e+00 9.84e 05 3.29e*03 7. W -04 Be 142 3.70e 02 3.70e 05 2.27e 03 0.00e+00 3.14e-05 1.91e+03 4.79e-10 La 140 4.79e+02 2.36e+02 6.26e+01 0.00e+00 0.00e+00 2.14e+05 4.87e+05 La 142 9.60e 01 4.25e-01 1.06e 01 0.00e+00 0.00e+00 1.02e+04 1.20e+04 co-141 2.84e+04 1.90e+04 2.17e+03 0.00e+00 8.88e+03 6.14e+05 1.26e+05 co 143 2.66e+02 1.94e+02 2.16e+01 0.00e+00 8.64e+01 1.30e+05 2.55e+05 Co.144 4.89e+06 2.02e+06 2.62e+05 0.00e+00 1.21e+06 1.34e+07 8.64e+05 Pr 143 1.34e+04 5.31e+03 6.62e+02 0.00e+00 3.09e+03 4.83e+05 2.14e+05 Pr-144 4.30e 02 1.76e 02 2.18e 03 0.00e+00 1.01e 02 1.75e+03 2.35e 04 Nd 147 7.86e*43 8.56e+03 5.13e+02 0.00e+00 5.02e+03 3.72e+05 1.82e+05 l W 187 1.20e+01 9.76e+00 3.43e+00 0.00e+00 0.00e+00 4.74e+04 1.77e+05 l ............................................................................... j hp 239 3.38e+02 3.19e+01 1.77e+01 0.00e+00 1.00e+02 6.49e*04 1.32e*05 l
l l
l Convereton factors are in mite of arewyr per uct/ cubic enter.
l l t ,
l l
l l
i
\
l UNT-005-014 Revision 4 Attachment 6.5 (6 of 12) 164 4
INHALATION PATHWAY DOSES DUE TO RADIONUCL1 DES OTHER'THAN N0BLE GASES. Rt Ri factere for Child age group by nuclide.
Waterford Stees Electric Station Pathway Gemeeue Release Inhalation Pathuey Al Nuclide Organ Dese Conversion factere Bone Liver T. Body Thyroid Klehey Lee GI.LLI H.3 C 14 0.00e+00 1.12e+03 1.12e*03 1.12e*03 1.12e+03 1.12e+03 1.12e+03 No-24 3.59e+06 6.73e+03 6.73e+03 6.73e+03 6.73e+03 6.73e+03 6.73e+03 1.61e+06 1.61e+06 1.61e*06 1.61e*06 1.61 1.61e+06 1.61e+06
.......................................................e+06 P 32
! cr 51 2.60e*06 1.14e+05 9.88e+06 0.00e+00 0.00e+00 0.00e+00 6.22e+06 l Mm56 0.00e+00 0.00e+00 1.54e+02 8.55e+01 2.43e+01 1.70e+06 1.08e+03 0.00e+00 4.29e+06 9.51e*03 0.00e+00 1.00 1.58e*06 2.29e+06 I .......................................................e+06 Mn46 l
Fe 55 0.00e*00 1.66e*00 3.12e-01 0.00e+00 1.67e+00 1.31e+06 1.23e+05 Fe 59 6.74e+06 2.52e*06 7.77e+03 0.00e+00 0.00e+00 1.11e+05 2.87e+03 2.07e+06 3.3&o+06 1.67e+06 0.00e+00 0
.................................................... 00e+00..........................
1.27e*M 7.07e+06 Co.58 Co 60 0.00e+00 1.77e+03 3.16e*05 0.00e*00 0.00e+00 1.11e+06 3.44e+06 Nl.63 0.00e+00 1.31e*06 2.26e*06 0.00e+00 0.00e+00 7.07e*06 9.62e*06 8.21e+05 4.62e*06 2.80e+06 0.00e*00 0
.................................................... 00e+00 ..........................
2.75e+05 6.33e+03 ul 65 Cu-66 2.99e*00 2.96e-01 1.46e 01 0.00e+00 0.00e+00 8.18e+03 8.40e*06 Zn.65 0.00e*W 1.99e*00 1.07e+00 0.00e+00 6.03e+00 9.58e*03 3.67e+06 4.26e+06 1.13e+05 7.03e+06 0.00e+00
.................................................. 7.14e+06 9.95e+05 1.63e+06 2n.49 l Br.83 6.70s-02 9.64e.02 8.92ea03 0.00e*00 5.85e-02 1.42e*03 1.02e*06 Br 86 0.00e+00 0.00e+00 4.74e+02 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e*00 0.00e*00 5.48e+02 0.00e*00
.................................................. 0.00e+00 0.00e+00 0.00e+00 Br.85 ab.86 0.00e*00 0.00e+00 2.53e+01 0.00e*00 0.00e+00 0.00e+00 0.00e+00 Rb.88 0.00e+00 1.98e+05 1.14e+05 0.00e+00 0.00e+00 0.00e+00 7.99e*03 0.'00e+00 5.62e+02 3.66e+02 0
.......................................... 00e*00 0.00e+00 0.00e+00 1.72e*01 Rb.89 sr.89 0.00e+00 3.45e*02 2.90e+02 0.00e+00 0.00e+00 0.00e+00 1.89e+00 Sr.90 5.99e*05 0.00e+00 1.72e+06 0.00e*00 0.00e+00 2.16e+06 1.67e*05 1.01e+08 0.00e+00 6.64e+06 0.00e+
.............................................. 00 0.00e+00 1.48e*0T
............... 3.43e*05 Sr.91 St-92 1.21e*02 0.00e+00 4.59e+00 0.00e+00 0.00e+00 5.33e+0A 1.74e+05 l Y-90 1.31e+01 0.00e+00 5.25e.01 0.00e*00 0.00e*00 2.40e+06 2.42e+05 4.11 e* a.00e+00 1.11e+02 0.00e+0 0.00e+00 2.62e+05 2.68e+05 l
l Y 91
..............3..............................
Y-91a 9.14e+05 0.00e*NI 2.44e+06 0.00e+00 0.00e+00 2.63e+06 1.86e*05 Y 92 5.07e.01 0.00e+00 1.86e.02 0.00e+00 0.00e+00 2.81e*03 1.72e+03 2.03e+01 0.00e+00 5.81e.01 0.00e+00 0.00e+00 2.39e+06 2.39e+05 Conversten factors are in w its of eremryr per uct/c ele meter.
4 N
I.
v UNT-005-014 Revision 4 l Attachment 6.5 (7 cf 12) 165
7NHALAT10N PATHWAY DOSES DUE T0 i RADIONUCLIDES OTHER THAN NOBLE GASES. R i f
J i
Ri factors for Child age group Dy nuclide.
Waterford $ team Electrte Station Pathway : Gaseous Seteese inhalation Pathway Ri Wuctide Organ Dose Conversion factors Bone Liver T. Boey Thyroid Kidrwy Lms Cl LLI {
l l
T 93 1.86e+02 0.00e+00 5.11e+00 0.00e+00 0.00e00 7.44e+04 3.88e+05 Zr 95 :
1.90e+05 4.18e+06 3.70e+06 0.00e+00 5.96e+06 2.23e+06 6.11e+06 Zr 97 1.88e+02 2.72e+01 1.60e*01 0.00e+00 3.89e+01 1.13e05 3.51e05 Nb-95 2.35e+04 9.18e+03 6.55e+03 0.00e+00 8.62e03 6.16e+05 3.70e+06 Mo-99 0.00e+00 1.72e+02 4.26e+01 0.00e00 3.92e+02 1.35e+05 1.27e+05 l Tc 101 8.10e.05 8.51e 05 1.08e-03 0.00c 00 1.45e 03 5.85e+02 1.63e*01
............................................................................... l Tc 99m 1.78e.03 3.48e 03 5.7Te 02 0.00c00 5.07e 02 9.51e+02 4.81e+03 Ru.103 2.79e+03 0.00e+00 1.07e+03 0.00e00 7.03e+03 6.62e+05 4.48e*04 Ru 105 1.53e*00 0.00e+00 5.55e-01 0.00e+00 1.34e00 1.59e+06 9.95e+06 Ru 106 1.36e+05 0.00e+00 1.69e+06 0.00c00 1.84e+05 1.43e+07 4.29e05 As-110e 1.69e*06 1.14e+04 9.14c03 0.00e+00 2.12e+06 5.48e+06 1.00e+05 Te 125e 6.73e+03 2.33e+03 9.14e+02 1.92e+03 0.00e+00 4.77e+05 3.38e*06 Te 127 2.7Te+00 9.51e-01 6.11e-01 1.96e+00 7.07e+00 1.00e*06 5.62e+04
% 127m 2.49c06 8.55e*03 3.02e+03 6.07e+03 6.36e04 1.68e+06 7.14e*06 Te 129 9.7Te 02 3.50e 02 2.38e.02 7.16e 02 2.57e 01 2.93e03 2.55e+06 To.129m 1.92e+04 6.86e+03 3.06e+03 6.33e+03 5.03e+06 1.76e+06 1.82e05 fe-131 2.17e-02 8.44e-03 6.59e.03 1.70e.02 5.18e.02 2.05e+03 1.33e+03 Te.131m ,
1.34e+02 5.92e*01 5.07e*01 9.TTe+01 4.L0e*02 2.06e+05 3.00e+05 Te 132 4.81e+02 2.72e+02 2.63e+02 3.17e02 1.7Te+03 3.77e+05 1.38e+05 1-130 8.18e+03 1.64e+06 8.64e+03 1.85e+06 2.45e+06 0.00e+00 5.11e+03 1-131 4.81e*06 4.81e+04 2.73e+06 1.62e+07 7.88e+04 0.00p00 2.84e+03 1 132 2.12e+03 4.07e+03 1.88e*03 1.94e+05 6.25e*03 0.00e+00 3.20e+03 ;
1 133 1 134 1.66e+06 2.03e+04 7.70c43 3.85e06 3.38e06 0.00e00 5.68e+03 j 1.17e+03 2.16e+03 9.95e+02 5.07e06 3.30e03 0.00e+00 9.55e+02
............................................................................... j I.135 4.92e+03 8.73e+03 4.14e+03 7.92e+05 1.34e+04 0.00c00 4.44e+03 Cs 134 6.51e+05 1.01e+06 2.25e+05 0.00e00 3.30e05 1.21e+05 3.85e+03 Cs 136 6.51e+06 1.71e*05 1.16e+05 0.00e+00 9.55e*06 1.65e+06 4.18e+03 Co.137 9.06e+05 8.25e+05 1 28e+05 0.00e+00 2.82e+05 1.0&o+05 3.62e+03 Ca 138 6.33e*02 8.60e+02 5.55e+02 0.00e+00 6.22e+02 6.81e+01 2.70e02 se.139 1.84e+00 9.84e46 5.37e.02 0.00e+00 8.62e.06 5.77e03 5.77e+06 Conversion factors are in mite of area /yr per uCl/ ethic meter.
UNT-005-014 Revision 4 Attachment 6.5 (8 of 12) 166
INHALATTON PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i l
l l
I Ri factors for Child age group cy nuctide.
Waterford Steam Electric Station Pathway : Caseous delease inhalation Pathway Ri Nuclide Organ Dose Conversion f actors Bone Liver T. Body Thyroid Kichey Lms Cl LLI Ba.140 7.40e+04 6.48e+01 4.33e+03 0.00e+00 2.11s+01 1.74e+06 1.02e+05 sa 141 1.96e 01 1.09e 04 6.36e.03 0.00e+00 9.47e 05 2.92e+03 2.75e+02 Be 142 5,00e 02 3.60e 05 2.79e 03 0.00e+00 2.91e 05 1.64e+03 2.74e+00 La 140 6.44e+02 2.25e+02 7.55e+01 0.00e+00 0.00e+00 1.83e+05 2.26e+05 La 142 1.29e+00 4.11e 01 1.29e-01 0.00e+00 0.00e+00 8.70e+03 7.58e+04 Ce 141 3.92e+04 1.95e+04 2.90e+03 0.00e+00 8.55e+03 5.44e+05 5.66e*04 )
............................................................................... i Co-143 3.66e*02 1.99e+02 2.87e+01 0.00e+00 8.36e+01 1.15e+05 1.27e+05 I Co 144 6.77e*06 2.12e+06 3.61e+05 0.00e+00 1.17e+06 1.20e*07 3.88e+05 Pr.143 1.85e+04 5.55e+03 9.14e*02 0.00e+00 3.00e+03 4.33e*05 9.73e*06
............................................................................... j Pr-144 5.96e 02 1.85*.02 3.00e 03 0.00e+00 9.77e-03 1.57e+03 1.97e+02 Nd-147 1.08e+04 8.73e*03 6.81e+02 0.00e+00 4.81e+03 3.28e+05 8.21e+04 l W-187 1.63e+01 9.66e+00 4.33e+00 0.00e+00 0.00e+00 4.11e+04 9.10e+04 i up 239 4.66e+02 3.34e+01 2.35e+01 0.00e+00 9.73e+01 5.81e+04 6.40e*04 Corwersion f actors are in units of area /yr per uct/ceic meter.
UNT-005-014 Revision 4 l Attachment 6.5 (9 of 12) 167 l
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri i
l at factors for Infant age group cy nucitae.
watertora steam Electrte station I Pathway : Gaseous Release inhetstion Pathway Ri Nuclide !
Organ Dose Conversion factors i
Bone Liver T. Body Thyroid Kichey Lung GI.LLI l H3 0.00e+00 6.47e+02 6.47e+02 6.47e*02 6.4Te+02 6.4Te02 6.47e+02 C 14 j 2.65e+04 5.31e+03 5.31e+03 5.31e+03 5.31c03 5.31e+03 5.31e+03 .
Na 24 1.06e+M 1.06e+04 1.06e+M 1.06e+04 1.06e+04 1.06e+04 1.06e+04 !
P 32 2.03e+06 1.12e+05 7.74e+04 0.00e+00 0.00e+00 0.00e+00 1.61e+04 Cr 51 0.00e+00 0.00e+00 8.95e+01 5.75 c 01 1.32e+01 1.28e+M 3.57e02 Mn 54 0.00e+00 2.53e+04 4.98e03 0.00e00 4.98e+03 1.00e+06 7.06e+03 Mn 56 0.00e00 1.54e+00 2.21e 01 0.00e*00 1.10e+00 1.25e+M 7.17e+04 Fe.55 1.97e+04 1.17e+M 3.33e+03 0.00e+00 0.00e+00 8.69e+04 1.09e+03 1 Fe-59 1.36e+04 2.35e04 9.48e+03 0.00e+00 0.00e+00 1.01e06 2.48e+04 I
............................................................................... l Co 58 0.00e+00 1.22e+03 1.82e+03 0.00e 00 0.00e+00 7.77e+05 1.11e+04 l Co 60 0.00e+00 8.02e+03 1.18e 04 0.00e+00 0.00e+00 4.51e+06 3.19e+04 Ni 63 3.39e+05 2.04e+04 1.16e+04 0.00e+00 0.00e+00 2.09e+05 2.42e+03 Ni 65 2.39e00 2.84e-01 1.23e 01 0.00e+00 0.00e+00 8.12e+03 5.01e+04 Cu-64 0.00e 00 1.88e+00 7.74e-01 0.00e+00 3.98e+00 9.30e+03 1.50e+04 In-65 1.93e+44 6.26e+M 3.11e+04 0.00e+00 3.25c04 6.47e+05 5.14e04 Za-69 5.39e.02 9.67e-02 7.18e.03 0.00e+00 4.02e.02 1.47e+03 1.32e+04 Br 83 0.00e00 0.00e+00 3.81e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br 84 0.00e+00 0.00e+00 4.00e+02 0.00e+00 0.00e+00 0.00e+00 0.00*00 Br-85 0.00e+00 0.00e+00 2.04e*01 0.00e00 0.00e+00 0.00e+00 0.00e+00 Rb 86 0.00e 00 1.90e05 8.82e 06 0.00e+00 0.00e+00 0.00e+00 3.04e+03 Rb-88 0.00e+00 5.57e+02 2.87e+02 0.00e+00 0.00e+00 0.00e+00 3.39e+02 Ab 89 3r*09 0.00c00 3.21e+02 2.06e02 0.00e00 0.00e*00 0.00e+00 6.82e+01 3.98e+05 0.00e+00 1.14e+M 0.00e00 0.00e+00 2.03e06 6.40e+M tr.90 4.09e+07 0.00e+00 2.59e+06 0.00e+00 0.00e+00 1.12e+07 1.31e+05 sr-91 9.56e01 0.00e+00 3.46e00 0.00e00 0.00e+00 5.26e+04 7.34e+M sr.92 1.05c01 0.00e+00 3.91e-01 0.00e+00 0.00e+00 2.38e+04 1.40e+05 Y-90 3.29e*03 0.00e+00 8.82e+01 0.00e+00 0.00e+00 2.69c05 1.04e+0
.................................,,........................................... 5 i Y 91 5.88e+05 0.00e+00 1.57e06 0.00e+00 0.00e+00 2.45e+06 7.03e+04 Y 91m 4.07e.01 0.00e+00 1.39e.02 0.00s+00 0.00e+00 2.79e+03 2.35e03 Y 92 1.64e+01 0.00e+00 4.41e 01 0.00e+00 0.00e+00 2.45e+04 1.27e+05 Corwersion f actors are in units of mresvyr per uCl/ cubic enter.
UNT-005-014 Revision 4 Attachment 6.5 (10 of 12) 168
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri i
i I
Ri factors for Infant age group Dy nuclide.
waterford Steen Electric Station Pathway : Caseous Reteese inhetetton Pathway Ri Nuclide Organ Oose Conversion factors l I
I Bone Liver T. Body Thyroid Kidney Lms Gl*LLI l Y 93 1.30e+02 0.00e+00 4.07e+00 0.00e+00 0.00e+00 7.64e+04 1.67e+05 Zr 95 1.15e+05 2.79e+M 2.03e+04 0.00e+00 3.11e+04 1.75e+06 2.17e+06 Zr 97 1.50e+02 2.56e+01 1.17e+01 0.00e+00 2.59e+01 1.10e+05 1.40e+05 Nb-95 1.57e+M 6.43e+03 3.78e+03 0.00e+00 4.72e+03 4.79e+05 1.27e+06 Mo 99 0.00e+00 1.65e+02 3.23e+01 0.00e+00 2.65e+02 1.35e+05 4.87e+04 Tc 101 6.51e 05 8.23e 05 8.12e M C.00e+00 9.79e M 5.84e*02 8.44e+02 Tc 99m 1.60e 03 2.88e 03 3.72e.02 0.00e+00 3.11e 02 8.11e*02 2.03e*03 Ru 103 2.02e+03 0.00e+00 6.79e+02 0.00e*00 4.24e+03 5.52e+05 1.61e+06 Ru 105 1.22e*00 0.00e+00 4.10e 01 0.00e*00 8.99e-01 1.57e+04 4.86e+06 Ru 106 8.68e+M 0.00e+00 1.09e+04 0.00e+00 1.07e+05 1.16e+07 1.64e+05 As 110m 9.98e+03 7.22e+03 5.00e+03 0.00e+00 1.09e+06 3.67e+06 3.30e+06 Te 125m 4.76e+03 1.99e*03 6.58e+02 1.62e+03 0.00e+00 4.47e+05 1.29e+06 Te 127 2.23e+00 9.53e 01 4.89e.01 1.85e*00 4.86e+00 1.03e+06 2.64e+06 Te 127m 1.67e*M 6.90e*03 2.07e+03 4.87e*03 3.75e+04 1.31e+06 2.73e+06 Te 129 7.88e.02 3.47e-02 1.88e.02 6.75e-02 1.75e-01 3.00e+03 2.63e+06 Te 129m 1.61e+06 6.09e+03 2.23e+03 5.67e+03 3.18e*06 1.68e+06 6.90e+06 Te 131 1.74e 02 8.22e.03 5.00e.03 1.58e-02 3.99e.02 2.06e*03 8.22e+03 Te.131m 1.07e*02 5.50e+01 3.63e+01 8.95e+01 2.65e+02 1.99e+05 1.19e+05 Te 132 3.72e+02 2.37e+02 1.76e+02 2.79e+02 1.03e+03 3.40e+05 4.41e+06 I DO 6.36e+03 1.39e+04 5.57e+03 1.60e+06 1.53e+M 0.00e+00 1.99e+03 I 131 3.79e+04 4.46e+06 1.96e+04 1.68e+07 5.18e+06 0.00e+00 1.06e+03
! 132 1.69e+03 3.54e+03 1.26e+03 1.69e+05 3.95e*03 0.00e+00 1.90e+03
!*133 1.32e+06 1.92e*06 5.60e+03 3.56e*06 2.24e+06 0.00e+00 2.16e+03 3-134 9.21e+02 1.88e+03 6.65e+02 4.45e+06 2.09e+03 0.00e+00 1.29e+03 l'135 3.86e+03 7.60e+03 2.77e+03 6.96e+05 8.67e+03 0.00e*00 1.83e+03 Cs 134 3.96e+05 7.03e+05 7.45e+04 0.00e+00 1.90e+05 7.97e+06 1.33e+03 Co 136 4.83e+06 1.35e+05 5.29e 06 0.00e+00 5.66e+% 1.18e+06 1.43e+03 Cs 137 5.49e+05 6.12e+05 4755e+06 0.00e+00 1.72e+05 7.13e+06 1.33e+03 Co 138 5.0$e+02 7.81e+02 3.98e+02 0.00e+00 4.10e*02 6.54e+01 8.76e+02 Be 139 1.48 *00 9.86e.04 4.30e-02 0.00e+00 5.V2e-04 5.95e+03 5.10e+06 Conversion factors are in mits of aree/yr per uct/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.5 (11 of 12) 169
1 IrlHALAT10tl PATHWAY DOSES DUE TO RAD 10tiUCLIDES OTHER THAN f40BLE GASES Ri l
l El factors for Infant age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release innalation Pathway di kuctide Organ Dose Conversion factors T. Body Thyroid Kidney Lme GI*LLI Bone Liver Ba 140 5.60eM 5.60e+01 2.90e+03 0.00e+00 1.34e+01 1.60e+06 3.84e+04 sa 141 1.57e 01 1.08e-M 4.9Te 03 0.00e+00 6.50e 05 2.97e03 4.75e+03 Ba 142 3.98e-02 3.30e 05 1.96e 03 0.00e+00 1.90e-05 1.55p03 6.93e+02 ta 140 5.05e+02 2.00e+02 5.15e+01 0.00e+00 0.00e+00 1.68e+05 8.48e+04 La 142 1.03e+00 3.77e 01 9.04e 02 0.00e+00 0.00e+00 8.22e+03 5.95e+04 Co 141 2.77e+04 1.67e+M 1.99e+03 0.00e+00 5.25e+03 5.17e+05 2.16e+04 2.93e+02 1.93e+02 2.21p01 0.00c00 5.64c01 1.16e05 4.97e+M Co 143 Ce 144 3.19e+06 1.21e+06 1.76e+05 0.00e+00 5.38e+05 9.84e+06 1.48e+05 Pr.143 1.40e+M 5.24e+03 6.99e+02 0.00e00 1.97e+03 4.33e+05 3.72e+04 Pr.144 4.79e.02 1.85e 02 2.41e 03 0.00e+00 6.72e.03 1.61e+03 4.28e03 Nd 147 7.94e+03 8.13e+03 5.00e+02 0.00e00 3.15e+03 3.22e+05 3.12e+M W 187 1.30p01 9.02e+00 3.12e*00 0.00e00 0.00e+00 3.96eM 3.56e04 NP-239 3.71e+02 3.32 e01 1.88e+01 0.00e+00 6.62e+01 5.95e+04 2.49e+M Corwersion f actors are in units of erem/yr per uCl/ cubic meter. l l
4 Attachment 6.5 (12 of 12)
UNT-005-014 Revision 4 170
GROUND - PLANE DEPOS!TTON PATHSAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Rj Ri factors for alt age groups by nuclide.
Waterford steen Electric Stetton Pathway Geseous Release Ground Plane Exposure Pathway Ri Nuclide Organ Oose Conversion factors T. Body Skin H3 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 Ns*24 1.19e+07 1.39e+07 P 32 0.00e+00 0.00e+00 Cr 51 4.66e+06 5.51e+06 Mn 54 1.39e+09 1.63e+09 Mn 56 9.02e+05 1.07e+06 Fe-55 0.00e00 0.00e+00 Fe-59 2.73e+08 3.21e+08 Co-58 3.79e+08 4.44e 08 Co 60 2.15e+10 2.53e+10 Ni 63 0.00e+00 0.00e+00 NI 65 2.97e+05 3.45e+05 Cu-64 6.07e+05 6.88e+05 Zn 65 7.47e+08 8.59e+08 Zn-69 0.00e00 0.00e+00 Br-83 4.87e+03 7.08e+03 Br 84 2.03e+05 2.36e+05 fir 85 0.00e00 0.00e+00 Rb 86 8.99e+06 1.03e+07 Rb 88 3.31e+04 3.78e+04 Rb-89 1.23e+05 1.48e+05 Sr 89 2.16e+04 2.51e+04 Sr-90 0.00e+00 0.00e+00 )
Sr 91 2,15e+06 2.51e+06 Sr 92 7.77e+05 8.63e+05 Y 90 4.49e+03 5.31e+03 Y-91 1.07e+06 1.21e+06 Y-91m 1.00e+05 1.16e+05 Y 92 1.80e+05 2.14e+05 Conversion factors are in units of square meter mram/yr per uCi/sec.
UNT-005-014 Revision 4 Attachment 6.6 (1 Of 3) 171
l t
GROUND - PLANE DEPOSfTTON PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri i
(
l l
l Ri factors for all age groups Dy nuclide.
Waterford Steam Electric Station Pathway : Caseous Release Ground Plane Exposure Pathway Ri Nuclide Organ Dose Conversion Factors T. Body Skin Y 93 1.83e+05 2.51e+05 2r 95 2.45e+08 2.84e+08 Zr-97 2.96e+06 3.44e+06 Nb-95 1.37e+08 1.61e+08 Mo 99 3.99e+06 4.63e+06 Tc-101 2.04e+04 2.26e+04 Tc 99m 1.84e+05 2.11e+05 Ru-103 1.08e+08 1.26e+08 Ru-105 6.36e+05 7.21e+05 Ru 106 4.22e+08 5.07e+08 Ag-110m 3.44e+09 4.01e+09 Te 125m 1.55e+06 2.13e+06 Te-127 2.98e+03 3.28e+03 Te 127m 9.16e+04 1.08e+05 Te 129 2.62e+04 3.10e+04 Te 129m 1.98e+07 2.31e+07 Te 131 2.92e+04 3.45e+07 Te 131a 8.03e+06 9.46e+06 Te 132 4.23e+06 4.98e+06 l 1 130 5.51e+06 6.69e+06 1-131 1.72e+07 2.09e+07 )
............................. )
1 132 1.25e+06 1.46e+06 I 133 2.45e+06 2.98e+06 1-134 4.47e+05 5.30e+05 I 135 2.53e+06 2.55e+06 Cs 134 6'.86e+09 8.00e+09 Cs-136 1.51e+08 1.71e+08 Cs 137 133e+10 1.20e+10 Cs 138 3.59e+05 4.10e+05 Ba 139 1.06e+05 1.19e+05 Conversion factors are in units of square meter mrenvyr per uCi/se .
I r
i l I
I
- UNT-005-014 Revision 4 Attachment 6.6 (2 of 3) 1 172 i 1 l
l l
GROUND - PLANE DEPOSIT 10N PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i
Ri factors for all age pro p by nuclide.
Waterford Steam Electric Station Pathway : Gaseous Release Grome Plane Exposure Pathway Ri Nuclide OrBan Dose Conversion Factors T. Body Skin Ba 140 2.05e+07 2.35e+07 Be 141 4.17e+04 4.75e+04 Ba 142 4.49e+04 5.11e+04 La 140 1.92e+07 2.18e+07 La 142 7.60e+05 9.11e+05 Ce 141 1.37e+07 1.54e+07 ,
Ce 143 2.31e+06 2.63e+06 Co 144 6.95e+07 8.04e*07 Pr 143 0.00e+00 0.00e+00 Pr=144 1.83e+03 2.11e+03 Nd 147 8.39e+06 1.01e+07 W-187 2.35e+06 2.73e+06 Np 239 1.71e+06 1.98e+06 Convers{on f actors are in units of square meter-mrom/yr per uCl/sec.
l l
l
[
- l l
l l
UNT-005-014 Revision 4 Attachment 6.6 (3 of 3)
! 173 1
C0W's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Rj l
1 l
l Ri factors for Adult age group Oy nuclide.
Waterford Steam Electric station l Pathway Gaseous Release Cow's Milk Pathway Ri Wuctide organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung Cl LLI H3 0.00e+00 7.63e+02 7.63e+02 7.63p02 7.63e02 7.63e+02 7.63e+02 C 14 2.63e+08 5.27e07 ' 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+07 Na*24 2.44e+06 2.44e+06 2.44*06 2.44e+06 2.44e+06 2.44e+06 2.44e+06 i
............................................................................... 1 P 32 1.71e+10 1.06e+09 6.61e+08 0.00e+00 0.00e+00 0.00e+00 1.92e+09 Cr 51 3.00e+00 0.00e+00 2.86e+04 1.71e+04 6.30e+03 3.79e+04 7.19e+06 Mn 54 0.00e+00 8.41e+06 1.61e+06 0.00e+00 2.50e+06 0.00e+00 2.58e+07 Mn 56 0.00e+00 4.15e 03 7.37e 04 0.00e 00 5.27e 03 0.00e+00 1.33e-01 i Fe 55 2.51e+07 1.73e+07 4.05e06 0.00e+00 0.00e+00 9.68e+06 9.95e+06 Fe 59 l 2.97e+07 6.98e*07 2.68e*07 0.00e00 0.00e00 1.95e+07 2.33e+08 Co 58 0.00e+00 4.71e+06 1.06c07 0.00e+00 0.00e+00 0.00e+00 9.55e+07 Co-60 0.00e+00 1.64e07 3.62e*07 0.00e+00 0.00e*00 0.00e00 3.08e+08 Ni 63 6.73e+09 4.66e+08 2.26e+08 0.00e00 0.00e 00 0.00e+00 9.73e07 NI-65 3.76e-01 4.88e 02 2.23e-02 0.00e+00 0.00e+00 0.00e+00 1.24e+00 cu-64 0.00e+00 2.39c04 1.12e+04 0.00e+00 6.03e+04 0.00e+00 2.04e+06 Zn-65 1.37e+09 4.37e+09 1.97e+09 0.00p00 2.92e+09 0.00e+00 2.75e+09 2n-69 2.18e 12 4.17e 12 2.90e.13 0.00c00 2.71e.12 0.00e+00 6.26e.13 Br 83 0.00e+00 0.00e+00 1.18e 02 0.00e+00 0.00e*00 0.00e00 1.71e.02 Br-84 0.00e+00 0.00e+00 2.08e 24 0.00e00 0.00e+00 0.00e+00 1.63e 29 Br 85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb-86 i 0.00e+00 2.59e+09 1.21e+09 0.00e+00 0.00e+00 0.00e+00 5.12e+08 1 Rb 88 0.00e00 0.00e+00 0.00e+00 0.00p00 0.00e+00 0.00e+00 0.00e+00 !
............................................................................... i Rb 89 0.00e+00 0.00e+00 0.00e00 0.00e*00 0.00 e00 0.00e+00 0.00e+00
$r-89 1.45e+09 0.00c 00 4.16e+07 0.00e00 0.00e+00 0.00e+00 2.33e+08 Sr 90 4.68e+10 0.00e00 1.15e+10 0.00e00 0.00e+00 0.00e+00 1.35e+09 Sr 91 2.90e+04 0.00e+00 1.17e+03 0.00* 00 0.00e+00 0.00e+00 1.38e+05 Sr*92 4.95e-01 0.00e+00 2.14e 02 0.00e*00 0.00e+00 0.00e00 9.81e+00 T 90 7.09e+01 0.00e+00 1J0e+00 0.00e00 0.00e00 0.00e00 7.52e+05 Y.91 8.59e+03 0.00e+00 2.30e02 0.00e+00 0.00e00 0.00e00 4.73e+06 Y 91m 6.27e 20 0.00e00 2.43e 21 0.00e+00 0.00p00 0.00e+00 1.84e 19 T 92 5.64e-05 0.00e00 1.65e 06 0.00e+00 0.00c00 0.00e+00 9.88e.01 Conversion factors are in units of square meter.arem/yr per uCi/sec for att nucLtdes except H 3, which is in teilte of aram/yr per uti/ cubic seter.
i l
l
( UNT-005-014 Revision 4 Attachment 6.7 (1 of 12) i 174 1
4 COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i 6
Ri factors for Adult age group Dy nuclide.
Waterfore steam Electric Station P?thway : Caseous selease Cow's Milk Pathway Ri WucLtde Organ Oose Conversion factors Bone Liver T. Body Thyroid tidwy Lung Gl.LLt i
Y 93 Zr 95 2.24e 01 0.00e+00 6.19e.03 0.00e+00 0.00e+00 0.00e+00 7.11e+03 Zr 97 9.43e+02 4.34e.01 3.03e02 2.05e+02 0.00e+00 4.75e+02 0.00e+00 9.59e+05 8.76e.0
........................... 4.01e 02 0.00e+00 1.32e.01 0.00e+00 2.71e+ 04 2................................................
Nb-95 ..
Mo 99 8.26e04 4.59e04 2.47e+04 0.00e00 4.54e04 0.00e+00 2.79e+08 Tc 101 0.00e+00 0.00e+00 2.48e+07 4.72e+06 0.00e+00 5.61e+07 0.00e+00 5.74e+07 0.00c00 0.00e+00 0.00e+00 0.00e+00 0.00 Tc 99m 0.00c 00............................................e+00 ....
Ru.103 3.34e+00 9.44e+00 1.20e+02 0.00e+00 1.43e+02 4.63e+00 5.59e+03 Ru 105 1.02e+03 8.64e 0.00e+00 04 0.00e+00 4.39e+02 0.00e+00 3.89e+03 0.00e+00 1.19e+05 Ru 106 0.00e+00 1.12e 02 0.00e+00 5.29e 0 3.41e-04...............................................1 Ag 110m 2.04e+04 0.00e+00 2.58e+03 0.00e+00 3.94e+04 0.00e+00 1.32e+06 Te.125m 5.82e*07 5.39e+07 3.20e+07 0.00e+00 1.06e*08 0.00e+00 2.20e+10 1.63e+07 5.90e+
4.90e*06 6.63e+07 0.00e+00 6 Te 127 M 2.18e+06.............................................50e+07 6.56e+02 2.35e+02 1.42e+02 4.86e02 2.67e+03 0.00p00 5.17e+04 Te.127m To.129 4.58e07 2.92e.10 1.W.11.64e+07 5.58e*06 1.17e+07 1.86e+08 0.00e+00 1.53
........................... 0..........................................
7.11o.11 2.24e.10 1.23e-09 0.00e*00 2.20e.10 Te 129m Te*131 6.02e+07 2.25e*07 9.53e06 2.07e+07 2.51e+08 0.00e+00 3.03e08 Te 131m 3.95e 331.77e+0 3.62e+05 1.65e33 1.25e33 3.25e-33 1.73e 32 0.00e+00 5.60s.34
........................... 5...............................................e+07 1.47e+05 2.80e+05 1.79e06 0.00e00 1.76 )
i Te 132 ....
l 130 2.40e+06 1.55e+M 1.44e+06 1.72e+06 1.50e07 0.00e+00 7.35e+07 l 1 131 4.21e+05 2.96e08 1.24e*M 4.90e+05 1.05e+08 1.94e+M 0.00e+00 4.24e+0 1.07e*06 !
........................... 2.43e*08 1.39e11 7.26e+08 0.00e+00 1.12e*08 8................................................
1 132 ..
1 133 1.67e.01 4.47e 01 1.56e.01 1.56e*01 7.12e.01 0.00e+00 8.39e.02 I 134 3.88e+M 2.11e.12 6.76e+06 2.06e+06 9.91e+08 1.18e*07 0.00e+00 6.06e*06 5.72e.
2.05e.12 9.92e.11 9.10e.12 0.00e+00 4.99
...........................12.....,..........................................e.15 I 135 ...
Ca.134 1.29e+M 3.38e+04 1.25e+04 2.23eG4 5.42c06 0.00e 00 3.82e+06 Co.136 5.65e*09 2.63e+08 1.34e10 1.04e+0 1.10e10 0.00c00 4.35e09 1.44c09 2.35e+08
........................... 9................................................
7.48e+08 0.00e*00 5.78e+08 7.93e+07 1.18e08 Ca.137 ..
Cs 138 7.38e*09 1.01e10 6.61c 09 0.00e*00 3.43e+09 1.14e+09 1.95e+08 Se-139 9.72e.24 1.92e.23 9.50e.24 0.00e+00 1.41e 23 1.39e 24 8.18e 29 4.54e.08 3.24e.11 1.33e 09 0.00e+00 3.03e.11 1.84e.11 8.06e 08 Conversion factors are in units of swore meter.oremfyr per uCf/sec for all nuclidee except H 3, which is in mits of arasvyr per uCl/ciefc meter.
UNT-005-014 Revision 4 Attachment 6.7 (2 of 12) 175
COB's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. R i Ri factors for Adult age group by nuclide.
.iatertora steam Electric Station Pathway a caseous Release Cow's Milk Pathway al Nuctice Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidrwy Lun8 C! LLI 8e*140 A* Jt 2.69e+07 3.38e+04 1.76e+06 0.00e+00 1.15e+04 1.93e+04 5.54e07 L 0.00e+00 3.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e 00 0.00e+00
... "..w.... ............................................e+00 0.00e+00 0.00e+00 0.00e+00 0.00 0.00e+00 0.00e+00 La 140 ........................
La 142 4.52e+00 2.28e+00 6.01e 01 0.00e+00 0.00e+00 0.00e+00 1.67e05 te 141 1.90e.11 8.66e.12 2.16e 12 0.00e+00 0.00e+00 0.00e+00 6.32e 08 4.84e+03 3.28e+03 3
................................ 72e+02 ..............................................
0.00e+00 1.52e+03 0.00e+00 1.25e+07 Co 143 co 144 4.16e+01 3.08e+04 3.40e00 0.00e+00 1.35e+01 0.00e00 1.15e+06 Pr-143 3.58e+05 1.50e05 1.92e*04 0.00e+00 8.87e+04 0.00e+00 1.21e+08 1.58e+02 6.33e+01 7.83
...................................e+00 Pr-144 0.00e+00 3.66e+01 0.00e+00 6.92e+05 Nd 147 0.00e+00 0.00s+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 W 187 9.42e+01 1.09e02 6.51e+00 0.00e+00 6.36e+01 0.00e+00 5.22e+05 6.52e+03 5.45e+03 1
................................ 91e+03..............................................
0.00e+00 0.00e00 0.00e+00 1.79e+06 Np*239 3.68e+00 3.61e*01 1.99e*01 0.00e+00 1.13e+00 0.00e+00 7.41e+04 Conversion factors are in units of square meter.arenvyr per uCi/see for all nuclides except H 3, dich is in mits of scan /yr per uCf/csic meter.
UNT-005-014 Revision 4 Attachment 6.7 (3 of 12) 176
I COS's MILK PATHBAY DOSE FACTORS DUE TO
! RADIONUCLIDES OTHER THAN N0BLE GASES. R i l
l l
l El factors for Teen age group cy nuclide.
! Watsrtord Steen Electric Station Pethway : Gaseous Release Cowe s Milk Pathway Ri
! Nuclide i Or9en 00se Conversion Factors Bone Liver T. Sody Thyroid Kichey Lune GI.LLI W.3 l
C 14 0.00e+00 9.94e+02 9.94e*02 9.94e+02 9.94e*02 9.94e+02 9.94e+02 No 24 4.86e+08 9.72e+074 9.72e+07 9.72e+07 9.72e+07 9.72e+07 9.72e+07 4.2Te+06 4.27e+06
................................ 27e+06 ..............................................
4.27e+06 4.27e*06 4.27e+06 4.27e+06 P 52 Cr 51 3.15e+10 1.95e+09 1.22e+09 0.00e+00 0.00e+00 .0.00e*00 2.65e+09 0.00e+00 0.00e+00 4.99e+04 Mn-54 2. 77e+04 1.09e+04 7.13e+04 8.39e+06 i 0.00e+00 1.40e+07 2.78e+0
..................................... 6 0.00e*00 4.18e+06 0.00e+00 2.87e+07 Mn.56 Fe 55 0.00e+00 7.36e.03 1.31e.03 0.00e+00 9.32e 03 0.00e+00 4.85e.01 Fe 59 4.45e+0F 3.16e+07 7.36e*06 0.00e+00 0.00e+00 2.00e+07 1.37e+07 5.18e+0F 1.21e*08 4.67
...................................e+07 0.00e+00 0.00e+00 3.81e*07 2.86e+08 Co 58 Co 60 0.00e+00 7.94e+06 1.83e+07 0.00e*00 0.00e+00 0.00e+00 1.09e*08 ut.63 0.00e*00 1.18e+10 8.35e+082.78e+074.06.26e*07 0.00e+00 0.00e+00 0.00e*00 3.62e+08
..................................1e*08 0.00e+00 0.00e*00 0.00e*00 1.33e+08 Mt.65 cu 64 6.87e.01 8.78e-02 4.00e.02 0.00e+00 0.00e*00 0.00e+00 4.76e+00 2n-65 0.00e+00 2.11e*09 7.32e+094.26e+04 3 2.00e*04 0.00e+00 1.08e*05 0.00e*00 3.30e+06
................................ 41e+09 ..............................................
0.00e+00 4.60e+09 0.00e+00 3.10e*09 Zn49 Gr*83 4.01e.12 7.65e.12 5.35e.13 0.00e*00 5.00s.12 0.00e+00 1.41e.11 Or 84 0.00e+00 0.00e+00 0.00e*00 0.00e+00 2.18e.02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 i
.............................. 3.71e.24 0.00e+00 0.00e+00 0.00e+00 0.00e*00 I
Br 85 R>S6 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 R>88 0.00e+00 0.00e+00 0.00e+00 4.73e+09 0 2.22e+09 0.00e+00 0.00e+00 0.00e+00 7.00e+08
! ................................ 00e+00 ..............................................
0.00e+00 0.00e+00 0.00e+00 0.00e+00 R>a9 l
Sr 89 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 l
- $r.90 2.67e+09 6.61e*10 0.00e+00 0.00e+00 7.66e+07 0.00e*00 0.00e+00 0.00e+00 3.19e*08
.............................. 1.63e+10 0.00e+00 0.00e+00 0.00ee00 1.86e+09 Sr*91 t
i Sr*92 5.33e+04 0.00e+00 2.12e+03 0.00e+00 0.00e+00 0.00e+00 2.42e+05 Y 90 9.07e.01 1.30e+02 0.00e+000.00e*00 -3.86e.02 0.00e+00 0.00e+00 0.00e+00 2.31e+01
.............................. 3.51e+00 0.00e+00 0.00e+00 0.00e+00 1.07e+06 Y41 Y 91m 1.58e*04 0.00e+00 4 24e*02 0.00e*00 0.00e+00 0.00e+00 6.48e+06 Y42 1.15e.19 0.00e+00 4.39e.21 0.03e+00 0.00e+00 0.00e+00 5.42e.18 1.04e.04 0.00e+00 3.01e.06 0.00e+00 0.00e*00 0.00e+00 2.86e+00 Conversion facters are in wilts of square meter.arem/yr per uct/see for ett nustidos except u.3, which is in units of area /yr per uC1/c eic meter.
i
+
- UNT-005-014 Revision 4
,I Attachment 6.7 (4 of 12) i 177 P
i t
COS's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i Ri factors for Teen age group Dy nuclide.
Waterford Steam Electric Stetton Pathway : Geseous Release f.ow's Milk Pathway Ri l
l Nuclide Organ Oose Conversion factors l l
sone Liver T. sody Thyroid tihey Luns ct.LLI I
Y.93 4.13e.01 0.00e+00 1.13e.02 0.00e00 0.00e00 0.00c00 1.26e+06 Zr.95 1.65e03 5.20e+02 3.58e+02 0.00c00 7.65e+02 0.00e+00 1.20e+06 2r 97 7.90e 01 1.56e 01 7.20e 02 0.00e00 2.37e 01 0.00e+00 4.23e+06 Nb-95 1.41e+05 7.81e+06 4.30e+04 0.00e+00 7.57c06 0.00e*00 3.34e+08 Mo.99 0.00e+00 4.47e+07 8.53e+06 0.00e+00 1.02e+08 0.00e+00 8.01e+07 Tc 101 0.00e+00 0.00e*00 0.00e+00 0.00p 00 0.00e00 0.00e*00 0.00e+00 Tc 9% 5.80e+00 1.62e+01 2.10e+02 0.00e+00 2.41e+02 8.97e+00 1.06e+06 Ru-103 .,91e*03 0.00e*00 7.74e*02 0.00e*00 6.34e+03 0.00e+00 1.51e+05 Ru 105 1.5w M 0.00e+00 6.13e.06 0.00e+00 1.99e.02 0.00e*00 1.27e+00 Ru-106 2.89e*06 0.N00 4.73e+03 0.00e*00 7.24e+06 0.00e+00 1.80e+06 As.110m 9.63e+07 9.11ed ? 5.54e+07 0.00e+00 1.74e+0s 0.00e+00 2.56e+10 To.125m 3.00e+07 1.08e+07 4.02e+06 8.39e+06 0.00e+00 0.00e+00 8.N+07 Te.127 1.22e+03 4.31e*02 2.61e+02 8.38e+02 4.92e*03 0.00e+00 9.38e+06 To.127m 8.64e+07 2.99e+07 1.00p07 2.01e+07 3.42e+08 0.00e+00 2.10e*08 To.129 5.37e.10 2.00e 10 1.20e.10 3.86e.10 2.25e-09 0.00e+00 2.96e.09 To.129s l 1.10e+0S 4.09e+07 1.Ne07 3.55e+07 4.61e+0S 0.00e+00 4.13e+0S To.131 7.22e 33 2.90e.33 2.26e.33 5.57e.33 3.16e.32 0.00e+00 5.93e.34 .-
Te.131m 6.58e+05 3.15e*05 2.63e+05 4.75e+05 3.29e+06 0.00e+00 2.53e+07 l
............................................................................... l Te 132 4.29e+06 2.72e+06 2.56e+06 2.87e+06 2.61e+07 0.00e+00 8.61e*07 I.130 7.41e+05 2.14e*06 8.56e+05 1.75e+0s 3.30e+06 0.00e+00 1.65e+06 3 131 5.37e+0S 7.52e+0S 4.06e*05 2.20e+11 1.30p09 0.00e00 1.69e+0s 1-132 2. 5 -01 7.75e.01 2.78e-01 2.61e+01 1.22e+00 0.00e+00 3.38e 01 1 133 7.00 e 06 1.20e*07 3.66e*06 1.68e*09 2.11e*07 0.00e*00 9.09e*06 I 134 3.74e.12 9.92e.12 3.56e.12 1.65e.10 1 N 11 0.00e+00 1.31e.13 1 135 2.29e+06 5.90e+04 2.19e+06 3.80e*06 9.33e+06 0.00e+00 6.54e*06 Cs.134 9.81ea09 2.31e+10 1.07e+10 0.00e+00 7.34e+09 2.80e+09 2.87e+0S Cs 136 4.48e+08 1.76e+09 1.18e+09 0.00e+00 9.60e*08 1.51e+08 1.42e+08 Cs.137 1.34e+10 1.78e+10 6.20e+09 0.00e+00 6.06e*09 2.35e*09 2.53e08 Ca.138 1 N .23 3.38e-23 1.69e.23 0.00e+00 2.50e.23 2.91e-24 1.54e-26 Be.139 8.40e.08 5.91e 11 2.45e.09 0.00e*00 5.57e.11 4.07e.11 7.50e-07 Convereien facters are in mits of square meter.oren/yr per ucl/sec for ett nuclides except N 3, which is in mits of aram/yr per UCl/ cubic meter.
1 i
i UNT-005-014 Revision 4 Attachment 6.7 (5 of 12) 178
- . ~ . - - - . . ~- -- - - -- .
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri l
l l
i Al factors for Teen age group cy nuclice.
Waterford Steen Electric Station Pathway Gaseous selease Cow's Milk Pathway Ri Nuclide Organ Oose Conversion Factors Sone Liver T. Body Thyroid Kidwy Lung GI LLI Ba 140 4.85e+07 5.95e04 3.13e+06 0.00e 00 2.02e+04 4.00e+04 7.48e+07 Ba 141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Ba 142 0.00e+00 0.00e+00 0.00e 00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 La 142 8.11e+00 3.99e+00 1.06c00 0.00e+00 0.00e00 0.00e00 2.29e05
-3.43e 11 1.53e 11 3.80e 12 0.00e+00 0.00e 00 0.00e+00 4.64e.07 Ce 141 8.88e+03 5.93e+03 6.81e+02 0.00e+00 2.79e+03 0.00e+00 1.70e+07 Co 143 7.65e+01 5.56e+04 6.21e+00 0.00e+00 2.50e01 0.00e+00 1.67e+06 co-144 6.58e+05 2.72e+05 3.54e+04 0.00e+00 1.63e+05 0.00e+00 1.66e+08 Pr-143 2.90e+02 1.16e+02 1.44e*01 0.00e+00 6.73e+01 0.00c00 9.55e+05 Pr.144 0.00e+00 0.00e+00 0.00e 00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Nd-147 1.81e+02 1.97e+02 1.18e+01 0.00e+00 1.16e+02 0.00e+00 7.11e+05 W 187 1.19e+04 9.73e+03 3.41e+03 0.00e+00 0.00e+00 0.00e+00 2.63e+06 kp 239 7.01e+00 6.62e.01 3.67e 01 0.00e+00 2.08e*00 0.00e+00 1.06e+05 Conversion facters are in units of sedere meter-erea/yr per uct/sec for ELL nuntidos eacept u.3, which is in waits of aremryr per uct/ceic meter.
i c
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! UNT-005-014 Revision 4 '
l Attachment 6.7 (6 of 12) 179
COB's MILK PATHSAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri Rt factors for Child age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release Cow's Milk Pathway Ri Nuclide Organ 00se Conversion factors Bone Liver T. Body Thyroid Kidrwy Lung GI.LLI H-3 C-14 0.00e+00 1.57e+03 1.57e03 1.57e+03 1.57e+03 1.57e+03 1.57e+03 No 24 1.19e+09 2.39e+08 2.39e+08 2.39e+08 2.39e+08 2.39e+08 2.39e+08 8.88e+06 8.88e+07 B.88e+06
........................................ 8.88e+06 8.88e+06 8.88 e06 8.88e+06 P-32 Cr 51 7.78e+10 3.64e+09 3.00e+09 0.00e+00 0.00e+00 0.00e 00 2.15e+09 Mn 54 0.00e+00 0.00e+00 1.02e+05 5.65e+04 1.54e+04 1.03e+05 5.40e06 0.00e+00 2.10e+07 5.59e+0
..................................... 6 0.00e+00 5.88e+06 0.00e+00 1.76e+07 Mn 56 Fe 55 0.00e+00 1.28e.02 2.90e 03 0.00e00 1.55e 02 0.00e+00 1.86e00 Fe 59 1.12e+08 5.93e+07 1.84e+07 0.00e+00 0.00e+00 3.35e07 1.10e+07 1.20e+08 1.95e+08 9.69e+07
........................................ 0.00e+00 0.00e 00 5.64e+07 2.03e+08 Co 58 Co 60 0.00e+00 1.21e+07 3.71e+07 0.00e+00 0.00e+00 0.00e+00 7.07e+07 Ni+63 0.00e+00 4.32e+07 2.96e+10 1.59e09 1.27e+08 0.00e+00 0.00e+00 0.00e+00 2.39e+08 1.04
...................................c09 Ni 65 0.00e+00 0.00e+00 0.00e+00 1.07e+08 Cu 64 1.68e+00 1.58e-01 9.24e 02 0.00e+00 0.00e+00 0.00e+00 1.94e+01 2n.65 0.00e 00 7.49e+04 4.52e*04 0.00e+00 1.81e+05 0.00e+00 3.51e+06 4.13e+09 1.10e+10 6.80.00e+00 6.94e+09 0.00p00 1.93e+09
................................. 5e+09 2n-69 .............................................
Br*83 9.87e.12 1.43e.11 1.32e.12 0.00e+00 8.65e.12 0.00e+00 8.99e.10 Br*84 0.00e*00 0.00e*00 5.36e.02 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 8.40
...................................e.24 Br 85 0.00e+00 0.00e+00 0.00e*00 0.00e+00 Rb 86 0.00e+00 0.00e+00 0.00e+00 0.00c00 0.00e+00 0.00e+00 0.00e+00 Ab-88 0.00e+00 8.TTe+09 5.39e+09 0.00e00 0.00e+00 0.00e+00 5.64e+08 0.00e+00 0.00e+00 0.00
...................................e+00 Rb 89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Sr 89 0.00e+00 0.00e+00 0.00e00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 sr.90 6.62e+09 0.00e+00 1.89c08 0.00e00 0.00e+00 0.00e+00 2.56c08 1.12e+11 0.00e*00
.............................. 2.83e+10 0.00e+00 0.00e+00 0.00e+00 1.50e+09 Sr-91 sr.92 1.31e05 0.00*00 4.94e+03 0.00e00 0.00e+00 0.00e+00 2.89e05 Y 90 2.21e+00 0.00e*00 8.88e.02 0.00e00 0.00e00 0.00e+00 4.19e+01 3.22e+02 0.00e+0C 8.63 0.00e+00 0.00p00 0.00e+00 9.18e05
...................................e+00 Y 91 ............................................
Y 91m 3.90**04 0.00e*00 1704e+03 0.00e+00 0.00e+00 0.00e+00 5.20e06 Y-92 2.80e.19 0.00e+00 1.02e 20 0.00e+00 0.00e+00 0.00c00 5.49e.16
- 2. k .04 0.00e+00 7.32e 06 0.00e00 0.00e+00 0.00e+00 7.39e+00 Corwersion factors are in units of somre seter aree/yr per uCf/sec for att nuclides except N 3, which is in tatits of arem/yr per uCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.7 (7 of 12) 180
C0W's MILK PATHWAY DOSE FACTORS DUE TO
- RADIONUCLIDES OTHER THAN N0BLE GASES. Rj Ri f actors for Chlid age group cy nuctide.
waterforo Steam Electric station Pathway : Caseous Release Cow's Milk Pathway Ri Wuclide Organ Dose Conversion Factors Sone Liver T. Body Thyroid Kichey Lung Cl LLI Y 93 Zr 95 1.02e00 0.00e+00 2.79e.02 0.00e+00 0.00e+00 0.00e+00 1.51e+04 Zr 97 3.83e+03 8.42e+02 7.50e+02 0.00e+00 1.21e+03 0.00e00 8.79e05 1.92e.00 2.78e 01 1.64e 01 0.00e+00
.................................................. 3.99e-01 0.00e+00 4.21e+04 Nb 95 Mo 99 3.18e+05 1.24e+05 8.84e+04 0.00e+00 1.16e+05 0.00e+00 2.29e+08 Tc-101 0.00e+00 8.14e+07 2.01e+07 0.00e00 1.74e+08 0.00e+00 6.73e+07 0.00e+00 0.00e+00 0.00e+00 0.00e+0
............................................... 0 0.00e+00 0.00e+00 0.00e+00 Tc 99m Ru.103 1.33e+01 2.61e+01 4.32e+02 0.00e+00 3.79e*02 1.32e+01 1.48e+04 Ru.105 4.28e+03 0.00e+00 1.65e+03 0.00e+00 1.08e04 0.00e+00 1.11e+05 3.85e 03 0.00e+00 1.40e 03 0.00e+0
............................................... 0 3.39e.02 0.00e+00 2.51e+00 Ru 106 Ag.110m 9.24e+04 0.00e+00 1.15e+04 0.00e00 1.25e+05 0.00e+00 1.44e06 Te*125m 2.09e+08 1.41e+08 1.13e+08 0.00e+00 2.63e+08 0.00e+00 1.68e+10 2 7.38e+07 2.00e+07 9.84e+06
........................................ 2.07e07......................................
0.00e+00 0.00c 00 7.12e+07 Te*127 2.99e03 8.06e+02 6.41e+02 2.07e+03 8.50e+03 0.00e00 1.17e+05
- Te.127m Te.129 2.08e08 5.60e+07 2.47e+07 4.97e+07 5.95e+08 0.00e+00 1.68e+08 1.33e 09 3.70e.10 3.15e.10
........................................ 9.46e 10 3.88e.09 0.00e 00 8.25e.08 i Te*129m 2.71e+08 7.58e+07 4.21e+07 8.75e+07 7.97e*08 0.00e+00 3.31e+08 Te.131 Te.131m 1.77e-32 5.40e.33 5.27e.33 1.36e.32 5.36e-32 0.00e+00 9.31e.32 1.60e+06 5.54e*05 5.89e+0
..................................... 5 1.14e+06 5.36e+06 0.00e+00 2.25e+07 Te 132 1 130 1.03e+07 4.54e06 5.48*06 6.61e+06 4.21e+07 0.00e00 4.57e+07 3
1 131 1.73e+06 3.50e+06 1.80e+06 3.86e*08 5.23e+06 0.00c00 1.64e+06 1.30e+09 1.31e+09 7.4
.................................5c08 1-132 4.33e+11 2.15e+09 0.00e+00 1.17e+08 1-133 7.01e.01 1.29e+00 5.92e-01 5.97e+01 1.97e+00 0.00e+00 1.52e+00 l 134 1.72e+07 2.13e+07 8.05e+06 3.95e+09 3.55e+07 0.00e+00 8.57e*06 8.87e.12 1.65e 11 7.
. . 5 7e 12 3. 79c 10 2.52e 11 0.00e00 1.09e-11 1 135 Cs.134 5.43e04 9.77e+04 4.62e+04 8.66e+06 1.50c05 0.00e+00 7.45e+04 Cs 136 2.26e10 3.71e+10 7.84c09 0.00e+00 1.15e+10 4.13e09 2.00e+08 1.01e+09 2.86e+09 1.80e*0 0.00e+00 1.48e+09 2.21e+08 9.77e+07
..................................r..9 Ca.137 Cs.138 3.22e10 3.09e+10 4.55e+09 0.00c00 1.01e+10 3.62e+09 1.93e+48 Se.139 4.27e.23 5.94e23 3.77c23 0.00e00 4.18e.23 4.50c24 2.74e.23 2.06e-07 1.10e 10 5.98e.09 0.00e+00 9.62e.11 6.48e 11 1.19e.05 conversion factors are in units of square meter mrom/yr per uCl/sec for all nuclideo except H'3, which is in units of arem/yr per uCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.7 (8 of 12) 181
C0W's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri l
l l
Ri f actors f or Child age grow Dy nuctice.
l Waterford steam Electric Station Pathway Caseous Release Cow's Milk Pathway Ri I
l Wuclide Organ 00se Conversion factors .
I Bone Liver T. Body thyroid Kidney Lung 01.LLI Ba.140 Ba 141 1.17e+08 1.03e+05 6.84e+06 0.00e+00 3.34e+04 6.12e+04 5.93e+07 Ba 142 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e 00 0.00e+00 0.00e00 0.00e+00 0.00e00 0
.......................................... 00e+00 0.0Ce+00 0.00e+00 0.00e+00 La 140 La 142 1.94e+01 6.79e+00 2.12e+00 0.00e+00 0.00e+00 0.00e+00 1.89e+05 Ce 141 8.30e.11 2.64e.11 8.28e 12 0.00e+00 0.00e+00 0.00e+00 5.24e.06 2.19e+04 1.09e+04 1.62e+03
........................................ 0.00e+00......................................
4.78e+04 0.00e+00 1.36e+07 i 1
Ca.143 Co.144 1.88e02 1.02e+05 1.47e01 0.00e+00 4.27e+01 0.00e+00 1.49e+06 1.62e+06 5.09c05 8.66e+04 0.00e+00 2.82e+05 0.00e+00 1.33e+08 Pr.143 7.18e02 2.16e+02 3.56e+01 0 l
.......................................... 00e+00 1.17e+02 0.00e+00 7.75e+05 Pr.144 Nd 147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.0 h *00 t W 187 4.45e+02 3.60e+02 2.79*01 0.00e+00 1.98e02 0.00e+00 5.71e+05 l 2.89*04 1.71e+04 7.69e+0
..................................... 3 0.00e+00 0.00e+00 0.00 e00 2.41e+06 Np 239 1.73e+01 1.24e+00 8.71e 01 0.00e+00 3.58e+00 0.00e+00 9.17e+04 Corwersion f actors are in mits of assare meter.orea/yr per uC1/sec for att nuttidos except M.3, which is in mits of aren/yr per uct/cielu meter.
l l
l l
UNT-005-014 Revision 4 Attachment 6.7 (9 of 12) 182
COB's MILK PATWM O*)SE FACTORS DUE TO RADIONUCLIDES GitiER THAN NOBLE GASES. Ri l
Ri factors for Inf ant age group ty nuclide.
Waterford steen Electric station Pathway : Caseous Release Cou's Milk Pathway RI huclide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kidney Lung G!.LLI H3 C 16 0.00e00 2.38e03 2.38e03 2.38e03 2.38e03 2.38e+03 2.38e03 No 24 2.34e09 5.00c08 5.00e+08 5.00 e os 5.00e+0s 5.00e+0s 5.03c os 1.55e*07 1.55e+07 1.55e+07 1.55e07 1 1.55e+07 1.55e+07
....................................................55e07 P.32 Cr.51 1.60e+11 9.43e09 6.21e+09 0.00e*00 0.00e+00 0.00e+00 2.17e+09 Mn 54 0.00e+00 0.00 c00 1.61e+05 1.05 e05 2.30e+06 2.05e+05 4.70e+06 0.00e+00 3.90c07 8.84c06 0.00e+0
............................................... 0 8.64e+06 0.00e+00 1.43e07 Mn.56 Fe.55 0.00e+00 3.14e.02 5.42e.03 0.00e00 2.70s.02 0.00e+00 2.86e00 Fe.59 1.35e*08 8.73e*07 2.33e+0F 0.00e+00 0.00c00 4.2Te*07 1.11e+0F 2.26e+08 3.92e+08 1.54e+0S
........................................ 0.00e+00......................................
0.00e+00 1.16e+08 1.87e+0S Co 58 Co 60 0.00e+00 2.42e+0F 6.05e+07 0.00e*00 0.00e*00 0.00e*00 6.06e*07 ul.63 0.00e+00 8.81e*07 2.08e*00 0.00e+00 0.00e+00 0.00e*00 2.10e08 3.49e+10 2.16e+09 1.21e+09
............ ........................... 0.00e+00 0.00e+00 0.00e*00 1.0Te+08 Ni 65 Cu 66 3.56e+00 4.03e.01 1.83e.01 0.00e*00 0.00e*00 0.00e*00 3.0Te+01 2n-65 0.00p00 1.86e+05 8.62e+06 0.00e+00 3.15e05 0.00e+00 3.82e*06 5.55e+09 1.90e+10 8
................................ 78e+09..............................................
0.00e+00 9.23e09 0.00e+00 1.61e+10 2n.49 Br*43 2.10e.11 3.7pe.11 2.82e.12 0.00e*00 1.57e.11 0.00p00 3.09e-09 tr*S6 0.00e*00 0.00e+00 1.14e.01 0.00rs00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 1.6
................................. 2e.23 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br.05 AkS6 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e00 ,
R>as 0.00e+00 2.23e*10 1.10e+10 0.00e+00 0.00e00 0.00e+00 5.69e+0S I 0.00e+00 0.00e+00 0
................................ 00e+00 ..............................................
0.00e+00 0.00e+00 0.00e+00 0.00e*00 l R&89 tr*89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 1.26e*10 0.00e+00 3.61o+0S 0.00e+00 0.00e*00 0.00e+00 2.59e+08 )
sr.90 1.22e+11 0.00e+00 3 :
................................ 10e+10 ..............................................
0.00e+00 0.00e+00 0.00e+00 1.52e+09 !
Sr.91 j tr 92 2.73e+05 0.00e+00 9.97e+03 0.00e+00 0.00e*00 0.00e+00 3.23e+05 l Y 90 4.71e+00 0.00e+00 1.75e-01 0.00e+00 0.00p00 0.00e*00 5.00w01 6.82e+02 0.00e+00 1.
................................ 53e+01 .er...........................................
0.00e+00 0.00e+00 0.00e*00 9.41e+05 T 91 Y.91m 7.33e+44 0.00e+00 1.95e+03 0.00e+00 0.00e+00 0.00e+00 5.25e+06 f.92 5.96e.19 0.00e+00 2.03e.20 0.00e+00 0.00e+00 0.00e+00 1.90e.15 5.44e-06 0.00e+00 1.53e.05 0.00e+00 0.00e+00 0.00c00 1.06e01 Conversten factere are in units of equore meter.aremryr per uCf/see for ELL nucLtdes except M 3, which is in units of aremryr per uCf/cible meter.
UNT-005-014 Revision 4 Attachment 6.7 (10 of 12) 183
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i Ri factors for Infant age groue ey nuclide.
Watertoro Steam Electric station Pathway 2 Caseous selease Cow's Milk Pathway Al Nuclide Organ 00su Conversion Factors Bone Liver T. Sody Thyroid Kichey Lung CI LLI Y 93 Zr 95 2.16e+00 0.00e 00 5.90e 02 0.00e00 0.00e00 0.00e+00 1.71e04 Zr-97 6.80e+03 1.66e03 1.18e+03 0.00e+00 1.79c03 0.00e+00 8.26e+05 4.07e+00 6.99e.01 3.19e 01 0
.......................................... 00e+00 ....................................
7.04e 01 0.00e*00 4.46e+04 Nb 95 Mo W 5.93e+05 2.44e+05 1.41e+05 0.00e+00 1.75e+05 0.00e+00 2.06e+08 Tc 101 3.00e+00 2.08e+08 4.06e+07 0.00e+00 3.11e+08 0.00e+00 6.86e+0T 3.00e+00 0.00e+00 0.00
...................................e+00 0.00e00 0.00e00 0.00e+00 0.00e+00 Tc 99m Ru 103 2.7Te*01 5.70e*01 7.35e*02 0.00e+00 6.14e02 2.95e+01 1.66e+04 Ru 105 8.67e+03 0.00e*00 2. h *03 0.00e+00 1.80e+04 0.00e+00 1.05e+05 8.12e-03 0.00e+00 2.
................................ 74e 03 0.00e+00 5.97e 02 0.00e+00 3.23e+00 Ru-106 Ag*110m 1.90e*05 0.00e*00 2.38e+04 0.00e+00 2.25e+05 0.00e*00 1.44e+06 3.86e+08 2.82e+08 fe.125m 1. Gee +08 0.00e+00 4.03e+08 0.00e*00 1.46e+10 1.51e+08 5.04e+07 2.04e+0 5.07e+07 0.00e00 0.00e00 7.18e07
......................................7 Te 127 ........................................
Te*127m 6.34e+03 2.13e+03 1.36e+03 5.16e+03 1.55e+04 0.00e*00 1.33e05 Te.129 4.21e+08 1.40e+08 5.10e*07 1.22e+08 1.04e+09 0.00e+00 1.70e*08 2.81e.09 9.60e-10 6.54e- 2.34e-09 7.00e-09 0.00e+00 2.25e 07
.....................................10.........................................
Te*129e+ 5.57e+08 1.91e+08 8.58e+0T 2.14e*08 1.39e+0p 0.00e+00 3.33e+08 fe 131 3.76e.32 1.39e 32 1.05e 32 3.35e.32 9.61e 32 0.00e+00 1.52e 30 To.131m 3.38e*06 1.36e*06 1.1
................................. 2e+06 2.76e*06 9.36e+06 0.00e+00 2.29c07 Te-132 1 130 2.11e+07 1.05e+07 9.75e+06 1.54e+07 6.54e*07 0.00e00 3.87e+07
!*131 3.56e*06 7.83e+06 3.14e+06 8.78e*08 8.60e+06 0.00e+00 1.68e+06 2.72e*09 3.21e+00 1
................................ 41e*09 1.05e+12 3.74e+09 0.00e+00 1.14e+08 1 132 1 133 1.45e+00 2.95eefe 1.05e*00 1.38e+02 3.29e+00 0.00e*00 2.39e+00 I 134 3.63e+0T 5.29e+07 1.55e+07 9.62e+09 6.22e+07 0.00e+00 8.95e+06 1.84e 11 3.77e.11 1.34e. 8.78e.10 4.21e.11 0.00e+00 3.89e-11
.......................... ..........11.........................................
l.135 Ca 134 L13e05 2.25e*05 8.19e+04 2.01e+07 2.50e*05 0.00e*00 8.13c04 Cs 136 3.65e+10 6.80e+10 6.87e309 0.00e+00 1.75e+10 7.18e+09 1.85e+08 1.95e09 5.81e+09 2.17e+
.................................... 09 0.00e+00 2.32e+09 4.74e+08 8.83e+07 Cs 137 Ca*138 5.15e+10 6.0te+10 4.27ed9 0.00e+00 1.62e+10 6.55e09 1.8Be+08 8e 139 9.01e 23 1.47e.22 7.noe.23 0.00e+00 7.31e.23 1.14e 23 2.34e 22 4.39e-07 2.91e.10 1.27e.08 0.00e+00 1.75e.10 1.77e.10 2.78e*05 Corwersion factere are in mits of equere meter-aren/yr per uCl/see for ett nuclidee except N 3, unich is in mits of aremryr per uCf/ceic meter.
UNT-005-014 Revision 4 Attachment 6.7 (11 of 12) 184
I t
- C0W's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri i
l l
R1 factors for infant age group Dy nuclide.
Waterford Steam Electric Station Pathway 1 Caseous Aelease Cow's Milk Pathway Ri Nuclide Organ Oose Conversion factors l
Bone Liver T. Body Thyroid KIM Lung GI LL1 Ba 140 2.41e+08 2.41e+05 1.24e+07 0.00e+00 5.72e04 1.48e+05 5.92e+07 Ba 141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Ba 142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 4.06e+01 1.60e+01 4.11e+00 0.00e+00 0.00e+00 0.00e+00 1.88e+05 La 142 Ce 141 1.74e 10 6.40e-11 1.53e 11 0.00e+00 0.00e+00 0.00e+00 1.09e 05 4.34e+04 2.64e+04 3.11e+03 0.00e+00 8.15e+03 0.00e+00 1.37e+07 Ce.143 Ce 144 3.97e+02 2.64e+05 3.01e+01 0.00e+00 7.68e+01 0.00e+00 1.54e+06 Pr.143 2.33e+06 1.49 ,+03 9.52e+05 1.30e+05 0.00e+00 3.85e+05 0.00e+00 1.33e+08 5.55e+02 7.36e01 0.00e+00 2.06e02 0.00e*00 7.84e+0
..............................................................................5 Pr 144 Nd-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 .
W 187 8.81e+02 9.05e+02 5.55e+01 0.00e00 3.49e*02 0.00e+00 5.74e+05 I 6.09e+04 4.23e+04 1.46e+04 0.00e+00 0.00e*00 0.00e+00 2.49e0 hp 239
- 6. !
3.65e+01 3.26e+00 1.84e+00 0.00e+00 6.51e*00 0.00e+00 9.44e 04 !
Conversion f actors are in mits of square meter.oremryr per uti/sec for att nuclides except N*3, which is in mits of arem/yr per uCi/ceic meter.
l l
i 1
UNT-005-014 Revision 4 Attachment 6.7 (12 of 12) 185 l
_ .. ~. .. - .. . - -- _ . - - - . - - - .. . ~_ -
i MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri i
at f actors for aault age groim ey nuctice.
Watertoro Steam Electric Station Pathway : Caseous Aeteese Meet & Poultry Pethway Ri l Nuctice Organ Dose Conversion Factors i
Bone Liver T. Body Thyreid KlWiey Lung GI LLI N3 C 14 0.00e+00 3.25e+02 3.25e+02 3.25e+02 3.25e+02 3.25e+02 3.25e+02 Wa 24 2.41e*08 4.83e+07 4.83e+0F 4.83e+07 4.83e+07 4.83e+07 4.83e+07 1.39e 03 1.39e.03 1.39e-03 1.39e-03 1
.................................................... 39e.03..........................
1.39e-03 1.39e-03 P 32 ,
Cr 51 4.66e+09 2.90e*08 1.80e+0s 0.00e+00 0.00e+00 0.00e+00 5.24e+08 i Mn*54 0.00e+00 0.00e+00 7.05e+03 4.21e+03 1.55e+03 9.36e+03 1.77e+06 0.00e+00 9.18e+06 1.75e+06 0.00e*00 0.00e+00 2.81e+0T
..................................................2.73e*06 ............................
Mn-56 Fe.55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 Fe 59 2.93e+04 2.03e+0s 4.72e+07 0.00e+00 0.00e+00 1.13e+0s 1.16e+08 2.66e*08 6.24e+0S 2.39e+0S 0.00e*0
............................................... 0 0.00e+00 1.76e*08 2.00e*09 Co 54 Co 60 0.00e*00 1.82e+07 4.09e+07 0.00e*00 0.00e*00 0.00e*00 3.70e+0S Ni+63 0.00e*00 7.52e+07 1.66e*05 0.00e*00 0.00e*00 0.00e+00 1.41e+09 1.89e*10 1.31e*09 6.33e*00 0.00e+0
............................................... 0 0.00e+00 0.00e+00 2.73e*08 Nl.65 Cu 64 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 Zn.65 0.00e+00 2.80e.07 1.31e.0T 0.00e*00 T.05e.0T 0.00e+00 2.38e 05 3.56e+0B 1.13e*09 5.12e+08 0
.......................................... 00e+00 ....................................
7.57e*08 0.00e*00 7.13e+08 2n.69 Br.83 0.00e+00 0.00e*00 0.00e*00 0.00se00 0.00e*00 0.00e+00 0.00se00 Br.44 0.00e+00 0.00e+00 0.00e*00 0.00ee00 0.00e*00 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e*00 0
.......................................... 00e+00 ....................................
0.00e*00 0.00e+00 0.00e*00 Sr.85 ab.86 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 Ab-88 0.00e+00 4.8Be*05 2.27e*08 0.00e+00 0.00e+00 0.00e+00 9.61e+0F 0.00e+00 0.00e+00 0.00e+00 0
.......................................... 00e+00 ....................................
0.00e+00 0.00e*00 0.00e+00 ab.09 Sr 49 0.00ea00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 sr.90 3.02e*08 1.24e*10 0.00e*00 8.66e+06 0.00e+00 0.00e*00 0.00e+00 4.84e+07
........ 0.00e*00 3.05e+09 0.00e+00 0.00e+00 0 Sr.91
................................................... 00e+00 3.59e+0S
$r 92 .58e.10 0.00e+00 6.39e.12 0.00e+00 0.00e+00 0.00e+00 7.53e.10 Y 90 00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.08e*02 0.00e+00 ~2.90e+00 0
.......................................... 00e+00 0.00e+00 0.00e+00 1.15e+06 Y*91 Y.91s 1.13e*06 0.00e*00 3.D1e*04 0.00e+00 0.00e+00 0.00e+00 6.23e*08 Y 92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.69e 39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.96e.35 Conversion factors are in units of equere motor area /yr per uCl/sec for all nustidos oncept N 3, which is in teitts of mram/yr per uCl/ciale meter.
i UNT-005-014 Revision 4 Attachment 6.8 (1 of 9) 186
MEAT PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri l
Ri factors for Adult age group by nuctice. 1 1
Watertora Steam Electric Station )
Pathway : Gaseous Release Meet & Poultry Pathway Ri Nuclide Organ Dose Conversion factors Bone Liver T. Sody thyroid Kidney Lung GI.LLI Y 93 4.87e 12 0.00e00 1.35e 13 0.00e00 0.00e00 0.00e 00 1.55e 07 Zr-95 1.87e+06 6.01e+05 4.07e+05 0.00e+00 9.43e+05 0.00e+00 1.90e+09 Zr 97 2.11e 05 4.27e 06 1.95e 06 0.00e+00 6.44e.06 0.00c00 1.32e+00 Nb-95 2.30e+06 1.28e+06 6.87e+05 0.00e+00 1.26e+06 0.00e+00 7.76e+09 Mo 99 0.00e+00 1.01e+05 1.91e+04 0.00e+00 2.28e+05 0.00e+00 2.33e+05 Tc 101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Tc 99m 4.74e.21 1.34e.20 1.71e 19 0.00e+00 2.04e.19 6.57e 21 7.93e.18 Ru-103 1.05e+08 0.00e+00 4.53e+07 0.00e+00 4.02e+08 0.00e+00 1.23e+10 Ru 105 6.30e 28 0.00e+00 2.49e 28 0.00e+00 8.14e 27 0.00e+00 3.85e 25 Ru 106 2.80e09 0.00e00 3.54e+08 0.00e+00 5.40e+09 0.00e00 1.81e11 As 110m 6.68e06 6.18e+06 3.67e+06 0.00e00 1.22e+07 0.00e00 2.52e+09 Te.125m 3.59e+38 1.30c08 4.81e+07 1.08e+08 1.46e+09 0.00e+00 1.43e09 Te.127 2.21e 10 7.94e 11 4.78e 11 1.64e.10 9.01e 10 0.00e+00 1.74e 06 Te 127m 1.12ee09 3.99e+08 1.36e+08 2.85e+08 4.53e+09 0.00e 00 3.74e+09 i Te.129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Te.129m 1.13e+09 4.23e+08 1.00e+08 3.90e+08 4.74e+09 0.00e+00 5.71e+09 Te.131 0.00e+00 0.00e+00 0.00p00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Te 131m 4.57e+02 2.23e+02 1.86e+02 3.54e+02 2.26e03 0.00e+00 2.22e+04 Te 132 1.43e+06 9.23e+05 8.66e+05 1.02e+06 8.89e+06 0.00e+00 4.36e+07 1 130 2.18e-06 6.42e 06 2.53e.06 5.44e 04 1.00e 05 0.00e+00 5.52e-06 1 131 1.08e+07 1.54e+07 8.82e+06 5.04e09 2.64e+07 0.00e+00 4.06e+06 1 132 0.00e 00 0.00e00 0.00e+00 0.00e+00 0.00e00 0.00e+00 0.00e+00 1 133 3.72e 01 6.47e 01 1.97e-01 9.51e+01 1.13e+00 0.00e+00 5.82e-01 1 134 0.00e00 0.nDe+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 1 135 4.69e17 1.23e.16 4.53e.17 8.10e 15 1.97e.16 0.00e+00 1.39e.16 Cs 134 6.58e+08 1.56e+0c 1.28e+09 0.00e+00 5.06p00 1.68c08 2.74e+07 Cs.136 1.21e+07 4.76e+07 3.43e+07 0.00e00 2.65e+07 3.63c06 5.41e+06 Cs.137 8.72e+08 1.19en
- 7.81e+08 0.00e+00 4.0$e+08 1.35c08 2.31e+07 Cs 138 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e00 Se*139 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Conversion f actors are in tsilts of square meter mrom/yr per uCf/sec for all metidos except M 3, which is in units of mram/yr per uCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.8 (2 of 9) 187
MEAT PATHWAY DOSE FACTORS DUE TO RADI0flVCLIDES OTHER THAN fl0BLE GASES. Ri iti factors for Acult age group by nuctice.
Watertora steam Electric station Pathway : Caseous Reteese Meet & Poultry Pathway Al Nuclide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung GI LLI Ba 140 Ba 141 2.88e07 3.61e+04 1.88e+06 0.00e+00 1.23e+04 2.07e+04 5.92e+07 Sa 142 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+
.................................... 00 0.00e+00 0.00e+00 0.00e00 0.00e+00 La 140 La.142 3.75e 02 1.89e 02 4.99e.05 0.00e+00 0.00e+00 0.00e+00 1.39e+03 ca.141 0.00e+00 0.00e+00 1.41e+04 9.50e+03 1.080.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00
...................................e+03 0.00e+00 4.41e+03 0.00e+00 3.63e+07 ca.143 te.144 2.03e-02 1.50e+01 1.66e 03 0.00e00 6.61e 03 0.00e+00 5.61e+02 Pr.143 1.46e+06 2.10a+04 6.09e+05 8.42e+03 1 7.83e+04 0.00e+00 3.6te+05 0.00e+00 4.93e+08
................................ 04e+03..............................................
0.00e*00 4.86e+03 0.00e 00 9.19e+07 Pr.144 Nd.147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00c00 0.00c00 0.00e+00 '
W 187 7.08e+031.76e.02 2.10e.02 8.18e+03 6 4.90e+02 0.00e+00 4.78e+03 0.00e+00 3.93e+07
................................ 14e.03-..............................................
0.00e 00 0.00e+00 0.00c 00 5.75e+00 Nr239 2.61e.01 2.57e.02 1.41e.02 0.00e+00 8.00e.02 0.00e+00 5.26e+03 Corwersion festere are in unite of egare meter-eremryr por uct/ses for ett nuttidae except M.3, which is in tasite of oremryr per uct/ceic meter.
i UNT-005-014 Revision 4 Attachment 6.8 (3 of 9) 188
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri l
i I
RI factors for Teen age group cy nuctide.
Watertora $ teen Electric Station Pathway Caseous Aelease Meet & Poultry Pathuey Ri l
!' NUCLide Organ Dose Conversion Factors 1
l Bone Liver T. Sody Thyroid Kidney Lms GI LLI 1
M*3 0.00e+00 1.94e+02 1.94e02 1.94e+02 1.94ee02 1.94e+02 1.94e02 C 14 2.04e+08 4.08e+07 4.08e+07 4.08c07 4.08e*07 4.08e+07 4.08e+07 No 24 1.11e-03 1.11e.03 1.11e 03 1.11e*03 1.11e 03 1.11e 03 1.11e 03 P 32 3.94e+09 2.44e+08 1.53e+08 0.00e+00 0.00e+00 0.00e+00 3.31e+06 Cr 51 0.00e+00 0.00e00 5.64e*03 3.13e03 1.24e+03 8.05e+03 9.48e+05 Mn 54 0.00e+00 7.00e+06 1.39e+06 0.00e+00 2.09e+06 0.00e+00 1.44e+07 Mn-56 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 i Fe 55 2.38e+08 1.69e*08 3.94e+07 0.00e+00 0.00e+00 1.07e*08 7.31e+07 l
Fe 59 2.12e+08 4.95e*08 1.91e+08 0.00e+00 0.00e+00 1.56e+08 1.17e+09 Co 58 0.00e+00 1.41e+07 3.24e+07 0.00e+00 0.00e+00 0.00e+00 1.94e*08 Co 60 0.00e*00 5.83e+07 1.31e+08 0.00e+00 0.00e00 0.00e+00 7.60w+08 Ni 63 1.52e+10 1.07e+09 5.15e+08 0.00e+00 0.00e+00 0.00e+00 1.71e+08 Ni.65 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 Cu-64 0.00e00 2.28e.07 1.07e-07 0.00e+00 5.77e-07 0.00e+00 1.7Fe.05 Zn 65 2.50e*08 8.69e+08 4.05e*08 0.00e+00 5.56e+08 0.00c 00 3.68e+08 2n.69 0.00e*00 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00ee00 Gr*83 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e*00 Br-84 0.00e+00 0.00e+00 0.00e 00 0.00e*00 0.00e*00 0.00e+00 0.00e*00 l ...............................................................................
Br 85 0.00e*00 0.00e*00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 -
i Rb 86 0.00e+00 4.07e+08 1.91e*08 0.00e+00 0.00e*00 0.00e+00 6.02e+07 l l Rb 88 0.00e+00 0.00e*00 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 i Rb-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e00 0.00p00 0.00e+00 Sr*89 2.55e*06 0.00c00 7.29e+06 0.00e+00 0.00e00 0.00e00 3.03e07 Sr-90 8.05e+09 0.00e*00 1.99e+09 0.00e+00 0.00e00 0.00e*00 2.26e+08 Sr.91 1.33e.10 0.00e+00 5.29e.12 0.00e+00 0.00e*00 0.00e+00 6.03e.10 b' e2 0.00e+00 0.00e00 - 0.00e+00 0.00e+00 0.00p00 0.00e00 0.00e+00 Y 90 9.11e*01 0.00e+00 2.45e00 0.00e00 0.00w 00 0.00e+00 7.52e*05 Y 91 9.54c05 0.00e+00 t.56e*04 0.00e*00 0.00e+00 0.00e+00 3.91e08 l
Y 91m 0.00e*00 0.00e00 0.00e00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Y 92 1.43e 39 0.00e+00 0.00e+00 0.00e+00 0.00c00 0.00e+00 3.93e 35 Conversion factors are in units of swore meter.orem/yr per uCf/sec for all twelfdee except M*3, which is in mits of aren/yr per UCi/cthic meter.
l t
UNT-005-014 Revision 4 Attachment 6.8 (4 of 9) 189
MEAT PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri Ri factors for Teen age group by nuclide.
Waterford Steam Electric station Pathway : Caseous Aelease Meet & Poultry Pathway Ai I
Nuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung Gl*LLI Y 93 4.11e.12 0.00e+00 1.13e.13 0.00e+00 0.00e+00 0.00 e00 1.26e-07 Zr 95 1.50e+06 4.73 e05 3.25e+05 0.00e+00 6.95e*05 0.00e+00 1.09e+09 Zr 97 1.76e.05 3.49e.06 1.61e.06 0.00e+00 5.29e-06 0.00e+00 9.44e.01 Nb-95 1.79e+06 9.96e+05 5.48e+05 0.00e+00 9.65e+05 0.00e+00 4.26e+09 l Mo 99 0.00e+00 8.31e04 1.59e+04 0.00e+00 1.90e+05 0.00e+00 1.49e+05 l Tc 101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e 00 0.00e+00 0.00e+00 Tc 99m 3.77e 21 1.05e.20 1.34e.19 0.00e+00 1.57e.19 5.83e.21 6.90e.18 Ru.103 8.57e+07 0.00e+00 3.66e+07 0.00e+00 3.02e+08 0.00e+00 7.16e+09 3
Ru.105 l 5.27e.28 0.00e+00 2.04e.28 0.00e*00 6.65e.27 0.00e*00 4.25e.25 !
J au.106 1.82e+09 0.00e+00 2.97e+0S 0.00e+00 4.55e+09 0.00e+00 1.13e+11 I Ag.110m 5.06e+06 4.79e*06 2.91e+06 0.00e00 9.13e*06 0.00 e00 1.34e+09 1 Te.125m 3.03e+08 1.09e+08 4.05e+0T 8.47e+07 0.00e*00 0.00e00 8.94e+06 !
1 Te.127 1.88e.10 6.65e.11 4.04e.11 1.29e.10 7.60s.10 0.00e 00 1.45e.08 l Te.127m 9.42e*04 3.34e+08 1.12e*08 2.24e+08 3.82e+09 0.00e00 2.35e+09 '
Te.129 0.00e00 0.00e00 0.00e 00 0.00e00 0.00e+00 0.00e+00 0.00e+00 Te-129ts 9.50e+0S 3.53e+08 1.50e+08 3.07e*0s
- 3.90e+09- 0.00e+00 3.57e+09 Te.131 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Te.131m 3.81e+02 1.83e+02 1.52e+02 2.75e+02 1.90e+03 0.00e+00 1.47e+04
............................................................................... i l
Te.132 1.17e+06 7.39e+05 6.96e+05 7.79e+05 7.09e06 0.00e+00 2.34e+07 1 130 1.75e 06 5.07e 06 2.02e-06 4.13e-04 7.80e.06 0.00e+00 3.89e.06 I 131 8.94c06 1.25e+07 6.72e+06 3.65e+09 2.15e+07 0.00e+00 2.48e+06 1 132 0.00e+00 0.00e+00 0.00e+00 0.00c00 0.00e+00 0.00e+00 0.00e+00 1-133 3.11e-01 5.28e.01 1.61e-01 7.37e+01 9.26e.01 0.00e+00 3.99e.01 1 134 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e00 1-135 3.82e.t7 9.82e 17 3.64e.17 6.32e 15 1.55e.16 0.00e+00 1.09e.16 Cs.134 5.23e08 1.23e+09 5.71e+08 0.00c00 3.91e+0s 1.49c08 1.53e+07 Ca.136 9.41e+06 3.70e+07 2.49e+07 0.00e+00 2.02e+07 3.18e+06 2.98e+06 Ca.137 7.24e+0S 9.63e+08 3.3&o+0S 0.00e+00 3.28e+06 1.27e+08 1.37e+07 Cs-138 0.00e+00 0.00e+00 0.00e+00 0.00e00 0.00e00 0.00e+00 0.00e+00 Ba 139 0.00 e00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 conversion factors are in units of square meter eres/yr per uti/see for att nuclidee except N.3, iAlch is in units of arouvyr per uCf/ctmic meter.
UNT-005-014 Revision 4 Attachment 6.8 (5 of 9) 190
'1 EAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAtit10BLE GASES. Ri 1
i i
Ri factors for Teen age group cy nuctice. '
I Waterford Steam Electric Station Pathway : Gaseous Release Meet & Poultry Pathway Ri Nuclide Organ 00se Conversion factors !
Bone Liver T. Body Thyr?id Kichey Leg GI LLI Ba 140 Ba 14 :
2.33e07 2.91e+04 1.53e+06 0.00e*00 9.88e+03 1.96e+04 3.67c07 Ba 142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0 La 140 00e+00......
La-142 3.08e 02 1.51e 02 4.03e 03 0.00e+00 0.00e+00 0.00e+00 8.69e+02 Ce 141 0.00e+00 0.00e 00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.18e+04 7.88e+03 9.05e+02 0.00e+00 3.71e+03 0.00e+00 2
.......................................................................25e+07 Ce 143 Co 144 1.71e 02 1.24e+01 1.39e 03 0.00e+00 5.58e 03 0.00e00 3.74e+02 Pr=143 1.23e+06 5.08e+05 6.60*04 0.00e+00 3.04e+05 0.00e+00 3.09e+08 1.77e+04 7.05e+03 8.79 e02 0.00e+00 4.10e+03 0.00e+00- 5 Pr 144 81e+07......
Nd 147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 W-187 6.24e+03 6.78 e03 4.06e+02 0.00e00 3.98e+03 0.00e+00 2.45e+07 1.76e 02 1.43e-02 5.03e-03 0.00e00 0.00e+00 0.00e+0 Np 239 0 3.88e00 2.28e 01 2.15e 02 1.19e 02 0.00e+00 6.75e 02 0.00e+00- 3.46e+03 Conversion facto.s are in mits of square meter-aremVyr per uCf/sec for all
{
nuclides except H 3, Which is in mits of presVyr per UCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.8 (6 of 9) 191
..- - - - - . _ _ _ ---~ - - . - - .. .-- - . _ . - -_ - - - . - -.
i MEAT PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Rj t 1
l l
l l
l l
j l
Ri factors for Child age group by nuctice.
! Waterford Steen Electric Station Pathway : Caseous Reteese Meet & Poultry Pathway Ri l
l Nuctide Organ Dose Conversion Factors l
l Bone Liver T. Sody Thyroid Kichey Lunt GI.LLI l
l H3 0.00e*00 2.34e+02 2.34e+02 2.34e+02 2.34e+02 2.34e+02 2.34e+02 C 14 3.83e+08 7.67e+07 7.67e*07 7.67e*07 7.67e+0T 7.67e+07 7.67e*07 Ne*24 1.77e.03 1.77e.02 1.77e 03 1.77e 03 1.77e-03 1.77e.03 1.77e 03 P 32 l 7.43e+09 3.47e+08 2.86e*08 0.00e+00 0.00e+00 0.00e+00 2.05e+0S Cr 51 j 0.00e+00 0.00e+00 8.79e*03 4.88e+03 1.33e+03 8.91e+03 4.66e+05 Mn 54 0.00e+00 8.01e+06 2.13e+06 0.00e+00 2.25e+06 0.00e+00 6.72e+06 Mn.56 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 l
Fe 55 Fe 59 4.57e+08 2.62e+08 7.51e+07 0.00e+00 0.00e+00 1.37e*08 4.49e*07 3.76e+08 6.09e*08 3.03e+08 0.00e+00 0.00e+00 1.TTe+08 6.34e*08 Co 58 Co 60 0.00e+00 1.Me+07 5.03e*07 0.00e*00 0.00e*00 0.00e+00 9.58e+07 Wl.63 0.00e+00 6.93e+07 2.06e+08 0.00e*00 0.00e+00 0.00e+00 3.86e*08 2.91e+10 1.56e+09 1.02e*09 0.00e+00 0.00e*00 0.00e+00 1.05e+
l NI+65 08 ..
1 l
Cu 64 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e*00 0.00e*00 0.00e*00 !
Zn 65 0.00e+00 3.07e.07 1.85e.07 0.00e+00 7.41e.07 0.00e+00 1.64e.05 3.75e*08 1.00e+09 6.22e+08 0.00e+00 6.30e+08 0.00e+00 1 2n-69 76e+08......
Br 83 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 Br.86 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+0 0.00e+00 Br 85 0...........
RD 86 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Ab 88 0.00e+00 5.77e+08 3.55e+08 0.00e+00 0.00e+00 0.00e*00 3.71e+0F l
0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0 ab 89 00e+00 ......
Sr 89 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Sr.90 4.82e+08 0.00e*00 1.38e+0F 0.00e+00 0.00e+00 0.00e+00 1.87e+07 1.0&o+10 0.00e+00 2.66e*09 0.00e+00 0.00e*0C 0 1.60e*08 Sr 91 00e+00 ................
Sr 92 2.50s.10 0.00e*00 9.42e.12 0.00e+00 0.00e+00 0.00e+00 5.51e.10 Y*90 0.00e+00 0.00e+00 'O.00e+00 0.00e+40 0.00e+00 0.00e*00 0.00e+00 1.72e*02 0.00e*00 4.61e*00 0.00e+00 0.00e*0G 0.00e*0 T-91 0 4.91e+05 Y-91m 1.80e+06 0.00e+00 4$42e+06 0.00e*00 0.00e+00 0.00e+00 2.60e+08 Y-92 0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00e*00 2.69e 39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 7.76e.35 Conversion factors are in tssits of sguere meter arsevyr per uCf/sec for ett ruslides emcept N 3, which is in units of aremvyr per uCi/ cubic meter.
l
- L.57-005-014 Revision 4 i Attachment 6.8 (7 of 9) i 192
MEAT PATHWAY 00SE FACTORS DUE TO RAD 10NUtt. IDES OTHER THAN NOBLE GASES. Rj Ri factors for Child age group Oy nuclice.
Waterford Steen Electric Station Pathway : Gaseous Release Meet & Poultry Pathway Ri Nuclide Organ Dose Conversion factors Bone Liver T. Sody Thyroid Kieey Les GI LLI T 93 7.73e 12 0.00e+00 2.12e.13 0.00e+00 0.00e+00 0.00e+00 1.15e.07 Zr.95 2.66e+06 5.86e+05 5.21e+05 0.00e+00 8.38e+05 0.00e+00 6.11e+08 Zr.97 3.28e.05 4.74e.06 2.80e.06 0.00e+00 6.80e.06 0.00e+00 7.18e 01 Nb-95 3.10e+06 1.21e+06 8.62e+05 0.00e*00 1.13e+06 0.00e+00 2.23e+09 Mo-99 0.00e+00 1.16e+05 2.86e+04 0.00e+00 2.47e+05 0.00e+00 9.57e+M Tc 101 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Tc.99m 6.61e-21 1.30e 20 2.15e.19 0.00e+00 1.88e.19 6.58e.21 7.37e.18 Ru.103 1.55e*08 0.00e+00 5.96e+07 0.00e+00 3.90e+08 0.00e+00 4.01e+09 Ru-105 9.83e-28 0.00e*00 3.57e.28 0.00e+00 8.64e.27 0.00e+00 ' 6.42e.25 Ru-106 4.44e+09 0.00e+00 5.54e+08 0.00e+00 5.99e*09 0.00e+00 6.90e+10 As.110m 8.39e+06 5.67e+06 4.53e+06 0.00e+00 1.06e+07 0.00e+00 6.74e+08 Te.125m 5.69e+08 1.54e+08 7.59e+07 1.60e+08 0.00e+00 0.00e+00 5.49e+48 Te-127 3.53e.10 9.51e 11 7.57e.11 2.44e-10 1.00e-09 0.00e+00 1.38e.08 Te.127m 1.77e+09 4.78e+08 2.11e+08 4.24e+08 5.06e+09 0.00e*00 1.4e+09 Te.129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 To.129m 1.79e+09 5.00e+08 2.7Be+08 5.77e+08 5.26e+09 0.00e+00 2.18e+09 Te.131 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 Te.131m 7.09,+02 2.45e+02 2.61e+02 5.04e+02 2.37e+03 0.00e+00 9.94e+03 Te 132 2.13e+06 9.43e+05 1.14e+06 1.37e+M 8.76e+06 0.00e+00 9.49e+06 1-130 3.13e.M 6.33e.06 3.26e.06 6.97e 04 9.46e M 0.00e+00 2.96e 06 1 131 1.66e*07 1.67e+07 9.48e+06 5.51e*09 2.74e+07 0.00e*00 1.48e+06 3 132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1 133 I 134 5.78e.01 7.15e-01 2.70s.01 1.33e+02 1.19e+00 0.00e+00 2.88e 01 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3*135 6.91e.17 1.24e.16 ~5.88e.17 1.10e.14 1.91e.16 0.00e+00 9.47e.17 Cs 134 9.22e+08 1.51e+09 3.19e+08 0.00e+00 4.69e+08 1.68e+08 8.16e*06 Cs 136 1.62e+07 4.59e+07 2.89e+07 0.00e+00 2.38e+07 3.54e+06 1.57e+06
.............................. 3...............................................
Co.137 1.33e+09 1.28e*09 1.88e+0F 0.00e+00 4.16e+08 1.50e+08 7.99e*06 Cs*138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+0c 0.00e*00 0.00e*00 Se.139 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Conversten facters are in mits of egasre meter.oren/yr per uCl/sec for all nuclides except N.3, which is in mits of armaryr per WCl/c@lc meter.
UNT-005-014 Revision 4 Attachment 6.8 (8 of 9) 193
- . - -. . -- --. - . - - - -- ~. . _ _ _ - _ _ _ _ . .
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES 1 OTHER THAN N0BLE GASES Rj li l
l i
l Ri factors for Child age group by nuclide.
Waterford Steam Electric station Pathway Gaseous Release Meet & Poultry Pathway Ri I
Nuclide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kichey Lung GI LLI l 1
Be 140 4.39e+07 3.85e+04 2.56e+06 0.00e+00 1.25e+04 2.29e+04 2.22e+07 ,
Be 141 0.00e+00 0.00e+00 0.00e+00 0.00ee00 0.00e*00 0.00e*00 0.00e+00 i Ba 142 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e40 0.00e+00 0.00e+00 1 La 140 5.64e 02 1.97e 02 6.14e 03 0.00e+00 0.00e+00 0.00e+00 5.49e+02 La 142 0.00e+00 0.00e*00 0.00e*00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 Co 141 2.22e+04 1.11e+04 1.65e+03 0.00e+00 4.86e+04 0.00e+00 1.38e+07 Co 143 3.21e.02 1.76e+01 2.52e 03 0.00e+00 7.29e-03 0.00e+00 2.55e+02 Co 144 2.32e+06 7.26e+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 3.61e+07 Pr 144 0.00e+00 0.00e+00 0.00e 40 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Nd.147 1.17e*04 9.48e+03 7.34e+02 0.00e*00 5.20e+03 0.00e*00 1.50e+07 W-187 3.26e-02 1.93e 02 8.67e 03 0.00e+00 0.00e+00 0.00e+00 2.71e+00 Np 239 4.29e-01 3.08e-02 2.17e 02- 0.00e*00 8.91e-02 0.00e+00 2.28e+03 i
Conversion factors are in mits of square meter-eren/yr per uCl/sec for all I nustidos eacept N 3, which is in mits of area /yr por uCl/c@ic meter. 1 1
UNT-005-014 Revision 4 Attachment 6.8 (9 of 9) 194
-- - ~ . - . .. . - - - _ . . . - .- - - -. -. . - . _ --- -.
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i t
Ri f actors for Acult age group Oy nuclide.
e
(
Waterford Steen EL6ctric Station Pathway : Geseous Release Leefy/ Produce Vegetation Pathway Ri Nuclide Orgen Dose Conversion factors Bone Liver T. Sody Thyroid Kleey Lung GI-LLI H3 0.00e+00 2.26e*03 2.26e+03 2.26e+03 2.26e+03 2.26e+03 2.26e*03 C-14 2.28e+08 4.55e+07 4.55e*07 4.55e*07 4.55e+07 4.55e+07 4.55e+07 Ne*24 2.68e+05 2.68e+05 2.68e+05 2.68e+05 2.68e+05 2.68e+05 2.68e+05 P 32 1.40e+09 8.73e+07 5.42e+07 0.00e+00 0.00e*00 0.00e+00 1.58e+08 Cr 51 0.00e+00 0.00e+00 4.Me+04 1.77e+04 1.02e+04 6.16e+04 1.17e+07 Mn 54 0.00e+00 3.13e+08 5.97e+07 0.00e+00 9.31e+07 0.00e+00 9.58e+08 Mn-56 0.00e+00 1.53e+01 2.72e+00 0.00e+00 1.94e*01 0.00e+00 4.89e*02 Fe 55 2.10e+08 1.45e*08 3.38e+07 0.00e+00 0.00e+00 8.00e+07 8.31e+07 Fe-59 1.26e+08 2.96e+08 1.14e+08 0.00e+do 0.00e+00 8.28e+07 9.80e+08 '
Co-58 0.00e+00 3.07e+07 6.89e+07 0.00e+00 0.00e*00 0.00e+00 6.23e+08 Co-60 0.00e+00 1.67e+08 3.69e+08 0.00e*00 0.00e*00 0.00e+00 3.14e+09 Ni.63 1.04e+10 7.21e+08 3.49e*08 0.00e+00 0.00e*00 0.00e*00 1.50e+08 Ni 65 5.96e+01 7.75e+00 3.54e+00 0.00e+00 0.00e+00 0.00e+00 1.97e+02 Cu-64 0.00e+00 9.15e+03 4.29e+03 0.00e+00 2.31e*04 0.00e+00 7.79e*05 Zn 65 3.17e+08 1.01e+09 4.56e+08 0.00e+00 6.75e*08 0.00e+00 6.36e*08 2n-69 5.06e.06 9.67e 06 6.72e-07 0.00e+00 6.28e-06 0.00e+00 1.45e 06 Sr 83 0.00e+00 0.00e+00 3.01e*00 0.00e+00 0.00e+00 0.00e+00 4.33e+00 Gr*84 0.00e+00 0.00e+00 2.14e.11 0.00e+00 0.00e+00 0.00e+00 1.68e 16 Br 85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 Rb 86 0.00e+00 2.19e+08 1.02e+08 0.00e+00 0.00e+00 0.00e+00 4.32e+07 Rb-88 0.00e+00 2.64e-22 1.40e 22 0.00e+00 0.00e+00 0.00e+00 3.65e 33 Ab 89 0.00e+00 2.80e.26 2.03e-26 0.00e+00 0.00e+00 0.00e+00 1.67e 39 Sr.89 9.96e*09 0.00e+00 2.86e+08 0.00e*00 0.00e+00 0.00e*00 1.60e*09 Br-90 6.05e+11 0.00e+00 1.48e+11 0.00e+00 0.00e*00 0.00e+00 1.75e+10 Sr-91 3.02e*05 0.00e+00- 1.22e+04 0.00e+00 0.00e+00 0.00e+00 1.44e+06 '
Sr.92 4.15e+02 0.00e+00 1.79e+01 0.00e+00 0.00e+00 0.00e+00 8.21e+03 Y 90 1.33e+04 0.00e+00 3.56e*02 0.00e+00 0.00e+00 0.00e+00 1.41e+08
..............................s................................................
Y 91 5.11e+06 0.00e+00 1.37e+05 0.00e+00 0.00e+00 0.00e+00 2.81e+09 Y*91m 4.76e.09 0.00e*00 1.84e-10 0.00e+00 0.00e+00 0.00e+00 1.40e 08 Y 92 8.96e-01 0.00e*00 2.62e 02 0.00e+00 0.00e+00 0.00e+00 1.57e+04 Conversion facters are in units of equere meter-aren/yr per uC1/sec for ett nuslidos oncept N.3, which is in units of aremryr per uct/ceic ester.
UNT-005-014 Revision 4 Attachment 6.9 (1 of 9) 195
i I
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADf0NUCLlDES OTHER THAN N0BLE GASES. Rj l
i I
at factors for Adult age group cy nuclide. i Waterford steen Electric Station Pathway : Caseous Release Leafy / Produce vegetation Pathway Ri
]
Nuclide Organ Oose Conversion factors l l
Bone Liver 1. f.ody Thyreid Kidiey Lung GI.LLI Y-93 1.68e 32 0.00e+00 4.45e*00 0.00e+00 0.00e+00 0.00e+00 5.34e*06 !
Zr 95 1.17e,06 3.7Te+05 2.5f e05 0.00e+00 5.91e+05 0.00e+00 1.19e+09 !
Zr 97 3.36e02 6.7fse+01 3.10e+01 0.00e+00 1.02e+02 0.00e+00 2.10e+07
............................................................................... l NO-95 1.42e+05 7.91e+06 4.25e+04 0.00e+00 7.82e+06 0.00e+00 4.80e+08 Mo 99 0.00e*00 6.14e+06 1.17e+06 0.00e+00 1.39e+0T 0.00e00 1.42e+07
)
1 Tc.101 5.93e.31 8.55e.31 8.39e-30 0.00e+00 1.54e-29 4.37e.31 0.00e+00
............................................................................... )
Tc 99m 3.06e+00 8.66e+00 1.10e+02 0.00e*00 1.31e+02 4.24e00 5.12e+03 Ru-103 4.TTe+06 0.00e+00 2.05e+06 0.00e*00 1.82e+07 0.00e+00 5.57e+0B Ru.105 5.29e+01 0.00e+00 2.09e+01 0.00e+00 6.84e+02 0.00e+00 '3.24e+04 Ru-106 1.93c08 0.00e+00 2.44e+07 0.00e+00 3.72e+08 0.00e00 1.25e+10 Ag.110m 1.05e+07 9.74e+06 5.79e*06 0.00e+00 1.92e*07 0.00e+00 3.90e*09 Te-125m 9.65e07 3.50e+07 1.29e+07 2.90e+07 3.93e+08 0.00e+00 3.85e+0S Te-127 5.61e+03 2.02e+03 1.21e+03 4.16e+03 2.29c04 0.00e+00 4.43e+05 Te.127m 3.49e+08 1.25e+08 4.25e+07 8.92e+07 1.62e+09 0.00e 00 1.17e+09 Te-129 7.13e.04 2.68e-06 1.76e.06 5.48e-06 3.00e.03 0.00e*00 5.38e-06 Te 129m 2.51e+0s 9.37c 07 3. gee +07 8.63e*0T 1.05e*09 0.00e+00 1.2&e09 Te.131 1.25e 15 5.21s.16 3.9&e.16 1.03e.15 5.67e 15 0.00e+00 1.7Te.16 Te.131m 9.10e+05 4.45e+05 3.71e05 7.05e+05 4.51e+06 0.00e+00 4.42e+0T Te 132 4.30e+06 2.78e+06 2.61e+06 3.07e+06 2.68e*07 0.00e+00 1.31e+08 I 130 3.90e+05 1.15e+06 4.54e*05 9.75e+07 1.79c06 0.00e+00 9.90e+05 I 131 8.07e+07 1.15e+08 6.62e+07 3.78e+10 1.98e+0S 0.00c00 3.05e07 3 132 5.57e+01 1.49e+02 5.21e+01 5.21e03 2.37e02 0.00e00 2.80e+01 I.133 2.0Be+06 3.61e+06 %.10e+06 5.31 e os 6.31e*06 0.00e+00 3.25e+06 I 134 8.84e.05 2.40e 06 2.59e.05 4.16e.03 3.82e 06 0.00p00 2.09e-07 I 135 3.85e+06 1.01e+05 3.72e+06 6.65e*06 1.62e+05 0.00e+00 1.14e+05 Cs.134 4.67e+09 1.11e+10 9.08e+09 0.00e*00 3.59e+09 1.19e+09 1.94c08 Cs 136 4.2&o+07 1.68e*08 1.21e+08 0.00e+00 9.37p0T 1.28e*07 1.91e+07 Co.137 6.36e+09 8.70e+09 5.70e+09 0.00e+00 2.95p09 9.81e*08 1.68e+08 Ca.135 3.39e 11 6.?Oe.11 3.32e.11 0.00e+00 4.92e.11 4.86e.12 2.86e 16 Be 139 2.70e 02 1.92e-05 7.91e.04 0.00e*00 1.80e.05 1.09e.05 4.79e-02 Conversten factors are in mits of sesre meter-aram/yr per utt/sec for all nustidos eacept N.3, which is in mits of area /yr por uCl/ceic meter.
UNT-005-014 Revision 4 Attachment 6.9 (2 of 9) 196
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO 1
RAD 10NUCLlDES OTHER THAN NOBLE GASES. Ri Ri f actors for Adult age grote Dy nuclide.
Waterford Steee Electric $tation Pathway : Caseous Release Leafy / Produce Vegetation Pathuey Ri Nuctide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kichiey Lime GI LLI Be 140 Be-141 1.28e+08 8.94e-22 1.61e+05 8.41e+06 0.00e+00 5.48e+04 9.23e+04 2.64e+08 Be-142 6. N 25 3.02e 23 0.00e+00 6.28e 25 3.83e-25 4.21e 31 3.88e 39 0.00e*00 2.44e 40 0
.......................................... 00e+00 ....................................
0.00e+00 0.00e+00 0.00e+00 La-140 Le 142 1.97e+03 9.95e+02 2.63e+02 0.00e+00 0.00e+00 0.00e+00 7.30e+07 Co 141 1.92e 04 8.75e 05 2.18e 05 0.00e+00 0.00e+00 0.00e+00 6.39e 01 1.97e+05 1.33e+05 1.51e+04 0
.......................................... 00e+00 ....................................
6.19e+06 0.00e+00 5.09e+08 Co 143 Co 144 9.95e+02 7.36e+05 8.14e+01 0.00e+00 3.24e+02 0.00e+00 2.75e+07 Pr.143 3.29e+07 1.38e+0T 1.77e+06 0.00e+00 8.16e+06 0.00e+00 1.11e+10 6.2&o+04 2.51e+04 3.10e+03
........................................ 0.00e+00 1.45e+06 0.00e+00 2.74e+08 Pr.144 Nd-147 2.36e-26 9.81e 27 1.20e 27 0.00e+00 5.53e 27 0.00e+00 3.40e-33 W 187 3.33e+043.17e+04 3.79e+04 3.85e+04 1.112.30e+03 0.00e+00 2.25e+04 0.00e+00 1.85e+08
...................................e+04 Np 239 0.00e+00 0.00e+00 0.00e+00 1.04e+07 1.43e+03 1.40e+02 7.73e+01 0.00e+00 4.37e+02 0.00e+00 2.88e*07 Corwersion factors are in mits of square meter area /yr per uCi/see for all nuctidee except N 3, which is in mits of aremryr per uCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.9 (3 of 9) 197
LEAFV VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri Ri factors for teen age group ey nuclide.
Waterford Steen Electric Station Pathway Geseous Roleese Leefy/ Produce Vegetation Pathway Al Nuclide Or9en Dose Conversion factors Bone Liver T. Body Thyroid Kichey Lung GI.LLI H3 C 14 0.00e00 2.59e+03 2.59e+03 2.59e+03 2.59e+03 2.59e+03 2.59c03 Ne*24 3.69c08 7.38e07 7.38c07 7.38e07 7.38e+0F 7.38e+07 7.38e07 2.38e05 2.38e05 2.38e+05 2.38c05 2.38e05 2.38e+05 2.
P.32 38c05 Cr.51 1.61e+09 9.96e+07 6.23e+07 0.00e+00 0.00e+00 0.00e+00 1.35e+08 Mn-54 0.00e+00 0.00e+00 6.16e+04 3.42e04 1.35e+04 8.80e+04 1.04e+0T 0.00e00 4.54ces 9.01c 07 0.00e+00 1.36e00 0.00e*00 9 Mn.56 32e+0s Fe.55 0.00e+00 1.38e+01 2.46e+00 0.00e+00 1.75e+01 0.00e+00 9.09e*02 Fe-59 3.24e+08 2.31e*08 5.39e+0T 0.00e00 0.00e+00 1.47e+08 1.00e+0S 1.79e*08 4.18e+08 1.62e+08 0.00e*00 0.00e+00 1.32e+
Co 58 0S 9.90e+08 0.00e+00 4.36e+07 1.00e+0s 0.00e+00 0.00p00 0.00e+00 6.01e+0s co-60 Ni.63 0.00e+00 2.49e+0S 5.60e08 0.00e+00 0.00e00 0.00e+00 3.24e*09 1.61e+10 1.13e+09 5.45e+08 0.00e*00 0.00e+00 0.00e Nl.65 00 1.81e*08 Cu 64 5.55e+01 7.09e+00 3.23e*00 0.00e*00 0.00e*00 0.00e+00 3.85e+02 Zn.65 0.00e*00 8.29e+03 3.90e+03 0.00e+00 2.10e*04 0.00e+00 6.43e+05 4.24e+0B 1.47e+09 6.86e+0S 0.00e+00 9.42e+08 0
.............................................................. 00e+00 6.23e+08 2n 69 tr.83 4.73e.06 9.02e.06 6.31e.07 0.00e+00 5.89e.06 0.00e+00 1.66e.05 Br*84 0.00e00 0.00e+00 2.82e+00 0.00e+00 0.00e00 ?.00e+00 0.00e+00 0.00e+00 0.00e+00 1.95e.11 0.00e+00 0.00e+00 0 Br.85 00e+00 0.00e+00 aba6 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Rb88 0.00e*00 2.73e+08 1.28e+08 0.00e+00 0.00e+00 0.00e+00 4.05e+07 0.00e+00 2.44e.22 1.30e.22 0.00e+0
............................................... 0 0.00e*00 0.00c00 2.09e.29 RFP9 Sr.89 0.00e+00 2.59e.26 1.83e 26 0.00e+00 0.00e+00 0.00e00 3.90e.35 tr.90 1.51e+10 0.00e+00 4.33e+08 0.00e+00 0.00e+00 0.00e+00 1.80e+09 7.51e+11 0.00e+00 1.85e+11 0
.......................................... 00e+00 0.00e*00 0.00e+00 2.11e+10 tr*91 Sr.92 2.82s*05 0.00e+00 1.12e+04 0.00e+00 0.00e+00 0.00c00 1.28e+06 Y 90 3.86e+02 0.00e+00 1.65e+01 0.00e+00 0.00e+00 0.00e+00 9.83e+03 1.24e+04 0.00e*00 3.3Ae+02 0
................................ ........ 00e+00 0.00e+00 0.00e*00 1.02e+0S Y-91 Y-91m 7.83e*06 0.00e+00 2.10 C a "3e00 0.00e00 0.00e+00 3.21e+09 4.43e.09 0.00e+00 1.69e.10 0.00e+00 0.00p00 0.00e+00 2.09e.07 Y 92 S.42e.01 0.00e*00 2.43e.02 0.00e+00 0.00e+00 0.00e00 2.31e+04 Conversten festers are in units of espare aster.aremfyr per uCf/sec for oli nuttidos eseept N.3, which is in knite of aremfyr per WCi/s e ls ester.
UNT-005-014 Revision 4 Attachment 6.9 (4 of 9) 198
1 l
1 LEAFY UEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Rj l
Ri factors for Teen age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release Leafy / Produce vegetation Pathuey Ri Nuclide Organ Dose Conversion factors Bone Liver T. Sody Thyroid Cleey Lung GI LLI Y 93 1.58e02 0.00e+00 4.33e+00 0.00e+00 0.00e+00 0.00e+00 4.82e+06 Zr 95 1.72e+06 5.43e+05 3.73e+05 0.00e+00 7.98e+05 0.00e+00 1.25e+09 Zr 97 3.11e+02 6.15e+01 2.83e+01 0.00e+00 9.33e+01 0.00e+00 1.67e+07 Nb-95 1.92e+05 1.07e+05 5.87e+04 0.00e+00 1.03e+05 0.00e+00 4.56e+08 Mo-99 0.00e+00 5.64e+06 1.08e+06 0.00e+00 1.29e+07 0.00e+00 1.01e+07 Tc.101 5.52e 31. 7.85e.31 7.71e 30 0.00e+00 1.42e 29 4.78e 31 1.34e 37 Tc 99m 2.70e+00 7.54e+00 9.77e+01 0.00e+00 1.12e+02 4.18e+00 4.95e*03 Ru.103 6.82e+06 0.00e+00 2.91e+06 0.00e+00 2.40e+07 0.00e+00 5.69e+08 Ru.105 4.92e+01 0.00e+00 1.91e+01 0.00e+00 6.20e+02 0.00e+00 I.97e+04 Ru.106 2.38e+08 0.00e+00 3.90e+07 0.00e 00 5.97e+08 0.00e+00 1.44e 10 As-1 ar .' 1.52e+07 1.43e+07 8.72e+06 0.00e+00 2.73c07 0.00e*00 4.03e+09 Te.12im 1.48e+08 5.34e+07 1.98e*07 4.14e*07 0.00e00 0.00e+00 4.37e+08 Te 127 5.29e+03 1.88e*03 1.14e+03 3.65e+03 2.14e64 0.00e+00 4.09c05 Te 127m 5.51e+08 1.96e+08 6.56e+07 1.31e+08 2.23e+09 0.00e+00 1.37e+09 Te 129 6.68e-04 2.49e.M 1.49e.04 4.77e.04 2.80s.03 0.00e00 3.65e-03 Te 129m 3.61e+08 1.34e+08 5.72e+07 1.17e+08 1.51e+09 0.00e00 1.36e+09 Te.131 1.16e-15 4.78e-16 3.62e.16 8.93e 16 5.07e-15 0.00e+00 9.52e 17 To.131m 8.42e+05 4.04e+05 3.37e05 6.07e+05 4.21e+06 0.00e+00 3.24e+07 Te.132 3.90e+06 2.47e+06 2.33e+06-2.61e+06 2.37e+07 0.00e+00 7.83e+07 1 130 3.49e+05 1.01e+06 4.03e+05 8.22e+07 1.55e+06 0.00e+00 7.75e+05 1 131 7.68e07 1.08e+08 5.78e+07 3.14e+10 1.85e+08 0.00e+00 2.13e+07 1 132 5.02e+01 1.31e+02 4.72e+01 4.43e+03 2.07e+02 0.00e+00 5.72e+01 :
1 133 1.93e+06 3.27e+06 9.99e+05 4.57e+08 5.76e*06 0.00e+00 2.48e06 '
l 134 7.99e-05 2.12e.04 7.61e-05 3.53e 03 3.34e-04 0.00e 00 2.79e 06 1 135 3.48e+04 8.96 e 04 .3.32e+04 5.76e+06 1.42e+05 0.00e+00 9.93e+04 Cs 134 7.10e+09 1.67e+10 7.75e+09 0.00e+00 5.31e09 2.03e+09 2.08e+08 Cs 136 4.37e+07 1.72e08 1.15e*08 0.00e+00 9.36e07 1.44e+07 1.38e*07 Cs 137 1.01e+10 1.35e+10 4.69e+09 0.00e+00 4.59e+09 1.75e*09 1.92e 08 Cs.138 3.13e.11 6.01e.11 3.00e.11 0.00e+00 4.44e 11 5.16e 12 2.73e 14 Sa 139 2.54e 02 1.79e 05 7.40e 06 0.00e+00 1.69e.05 1.23e-05 2.27e-01 Conversion f actors are in urnits of square meter.oren/yr per uCl/see for all nustidos except u.3, editch is in units of aremryr per uti/ceic mete .
UNT-005-014 Revision 4 Attachment 6.9 (5 of 9) 199 i
J
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RAD 10NUCLlDES OTHER THAN NOBLE GASES. Rj l
Ri factors for Teen age group Dy nuclide.
Waterforc steam Electric Station Pathway : Gaseous Release Leaty/ Produce Vegetation Pathway Al Nuctice Organ Dose Conversion Factors l
Bone Liver T. Body Thyroid Kidney Lung 01-LLI I l
Ba 140 1.38e+08 1.69e+05 8.89e+06 0.00e+00 5.73e+04 1.14e+05 2.13e+08 Ba-141 8.36e-22 6.24e 25 2.79e 23 0.00e+00 5.79e-25 4.27e 25 1.78e-27 sa 142 3.57e 39 0.00e+00 2.20e-40 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 1.80e+03 8.86e+02 2.36e+02 0.00e+00 0.00e+00 0.00e+00 5.09e+07 La-142 1.77e 04 7.84e 05 1.95e-05 0.00e+00 0.00e+00 0.00e+00 2.39e+00 Ce 141 2.83e+05 1.89e+05 2.17e+04 0.00e+00 8.89e+04 0.00e+00 5.40e+08 Co 143 9.30e+02 6.77e+05 7.56e+01 0.00e+00 3.04e+02 0.00e+00 2.04e+07 Ce 144 5.27e+07 2.18e+07 2.83e+06 0.00e+00 1.30e+07 0.00e+00 1.33e+10 Pr.143 7.00e+04 2.79e+04 3.48e+03 0.00e+00 1.62e+04 0.00e+00 2.30e+08 Pr 144 2.22e 26 9.07e 27 1.12e-27 0.00e+00 5.20e 27 0.00e+00 2.44e-29 Nd-147 3.62e+04 3.93e+04 2.36e+03 0.00e+00 2.31e+04 0.00e+00 1.42e+08 W-187 3.53e+04 2.87e+04 1.01e+04 0.00e+00 0.00e+00 0.00e+00 7.78e+06 Np*239 1.38e+03 1.31e+02 7.25e+01 0.00e+00 4.10e+02 0.00e+00 2.10e+07 Conversion factors are in units of square meter-erem/yr per uCf/sec foi M nuctides except H 3, which is in units of aram/yr per UCl/c@lc meter.
UNT-005-014 Revision 4 Attachment 6.9 (6 of 9) 200
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO l RADIONUCLIDES OTHER THAN N0BLE GASES. i R !
l i
l i Ri factors for Child age group by nuclide.
Waterford Steam Electric station Pathway :
Caseous Release Leafy / Produce vegetation Pathway Ri Nuctide Organ Oose Conversion factors l
l Sone Liver T. Sody Thyroid Kidiey Lung GI LLI I
! i H3 l C 14 0.00e+00 4.01e+03 4.01e03 4.01e+03 4.01e+03 4.01e+03 4.01e+03 Ne*24 6.89e+08 1.78e+08 1.7Be+08 1.78e+08 1.78e+08 1.78e*08 1. 78e+08 3.71e+05 3.71e+06 3.71e+0
..................................... 5 3.71e+05 3.71e+05 3.71e+05 3.71e+05 i
P 32 {
Cr 51 3.37c09 1.58e 08 1.30e+08 0.00e+00 0.00e+00 0.00e+00 9.30e+07 l Mn-54 0.00e+00 0.00e001.7 0.00e*00 6.65e*08 1.17e05 6.50e+04 1.78e+04 1.19e+05 6.21e+06 t
................................. 7e+08 0.00e+00 1.86e+08 0.00e+00 5.58e+08 Mn.56 i
Fe 55 0.00e+00 1.81e+01 4.08e+00 0.00e+00 2.19e+01 0.00e+00 2.6Pe+03 Fe.59 8.01e+08 3.97e*08 4.25e*04 6.43e+08 3.
1.32e*08 0.00e+00 0.00e+00 2.40e*08 7.87e+07 ,
l
................................ 20e+08..............................................
0.00e*00 0.00e+00 1.86e+08 6.69c08 !
Co 54 i
' Co 60 0.00e+00 6.44e*07 1.97e*08 0.00e*00 0.00e 00 0.00e+00 3.75e+08 Ni 0.00e+00 3.7Be+08 1.12e+09 0.00e+00 0.00e+00 0.00e00 2.10e+09 3.95e+10 2.11e*09 1.38e+
t
....'63
......'.......................... 09 Ni 65 0.00e00 0.00e+00 0.00e+00 1.42e+08 Cu 64 1.02e+02 9.59e00 5.60e+00 0.00e+00 0.00c00 0.00c00 1.17e+03 Zn-65 0.00e+00 1.09e*04 6.60e+03 0.00c00 2.64e+04 0.00e+00 5.13e05 8.12e+08 2.16e+09 l
i .............................. 1.35e+09 0.00e+00 1.36e+09 0.00e+00 3.80e*08 Zn-69 Br.83 8.73e.06 1.26e.05 1.17e-06 0.00e+00 -7.66e.06 0.00e00 7.96e.04 Br.84 0.00e+00 0.00e+00 0.00e+00 5.20e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00
......... ................... 3.30s 11................................................
0.00e+00 0.00e 00 0.00e+00 0.00e+00 Br 85 Rb 86 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 i
' Ab-88 0.00e+00 4.52e*08 2.78e+08 0.00e+00 0.00e00 0.00p00 2.90e+07 0.00e+00 3.37e-22 0.00e*00 0.00e+00 0.00e*00 1.65e-2 ab 89 2.34e 22...............................................3 sr 89 0.00 p00 3.42e 26 3.04e.26 0.00e+00 0.00e+00 0.00e+00 2.98e 28 sr-90 3.59e+10 0.00e+00 1.03e*09 0.00e00 0.00p00 0.00e+00 1.39e+09 1.24e+12 0.00e+0 i
........................... 3.15e11 0.00e*00 0.00e+00 0.00e+00 1.67e+
0.................................................10 sr 91 .
sr-92 5.20e05 0.00e*00 1.96e*04 0.00e*00 0.00e*00 0.00e+00 1.15e+06 j
T 90 7.07e+02 2.30e+04 0.00e*00 2.84e+01 0.00e+00 0.00e*00 0.00e+00 1.34e+04 0.00e+00
.............................. 6.17e+02 ...0.00e+00 0.00e+00 0.00e+00 6.56e+07 Y 91 T 91e 1.86e*07 0.00e*00 4.98e+05 0.00e+00 0.00e+00 0.00e+00 2.48p09 T*92 8.12e-09 0.00e*00 2.95e.10 0.00e+00 0.00e*00 0.00e*00 1.59e.05 1,55e+00 0.00e+00 4.43e.02 0.00e+00 0.00p00 0.00c00 4.48e 04 Conversion facters are in mits of square meter erea/yr per uti/see for att nustidos except u.3, telch is in unite of areatyr per sci /c@ic meter.
l l
l
, UNT-005-014 Revision 4 I
Attachment 6.9 (7 of 9) i 201
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO '
RADIONUCLIDES OTHER THAN NOBLE GASES.i R Ri factors for Child age group by nuclide.
Waterford Steen Electric Station Pathway : Caseous Aeteese Leafy / Produce Vegetation Pathway Ri Wuctide Organ Dose Conversion Factors Bone Liver T. Rody Thyroid Kidrwy Lung GI-LLI Y 93 Zr 95 2.91e+02 0.00e+00 7.98e+00 0.00e+00 0.00e+00 0.00e+00 4.34e+06 Zr-97 3.86e+06 8.48e+05 7.54e+05 0.00e+00 1.21e+M 0.00e+00 8.84e+08 5.68e+02 8.20e+01 4.84e*01 0.00e+00 1.18e+02 0.00e+00
.......................................................................1.24e+07 hb 95 .......
No 99 4.10e+05 1.60e+05 1.14e+05 0.00e+00 1.50e+05 0.00e+00 2.95e+08 Tc 101 0.00e+00 7.70e+M 1.91e+06 0.00e+00 1.64e+07 0.00e+00 6.37e+M 1.02e 30 1.06e-30 1.35e 29 0.00e+00 29 5.62e 31 3.38e 30
...................................................1.81e Tc 99m Ru 103 4.65e+00 9.12e+00 1.51e+02 0.00e+00 1.32e+02 4.63e+00 5.19e+03 Au-105 1.53e*07 0.00e+00 5.89e+06 0.00e+00 3.86e+07 0.00e+00 3.96e+08 9.01e+01 0.00e*00 3.27e+01 0.0
........................................... 0e+00 7.92e+02 0.00e*00 5.88e+04 Ru-106 Ag 110m 7.45e+08 0.00e+00 9.30e+0F 0.00e*00 1.01e+09 0.00e+00 1.16e+10 Te 125m 3.21e+07 2.17e+07 1.73e*07 0.00e+00 4.04e+07 0.00e+00 2.58e+09 3.50e+08 9.50e+07 4.67e+07 9.8
........................................... 3e+07 0.00e+00 0.00e+00 3.38e+08 Te 127 Te 127m 9.76e+03 2.63e+03 2.09e+03 6.76e+03 2.78e+04 0.00e+00 3.81e+05 Te 129 1.32e+09 3.56e+08 1.57e+08 3.16e+08 3.77e+09 0.00e+00 1.07e+09 1.24e-03 3.45e 04 2.94e 04
........................................ 8.82e.04 3.62e 03 0.00e+00 7.70e-02 Te 129m Te 131 8.40e+08 2.35e+08 1.30e+08 2.71e+08 2.47e*09 0.00e+00 1.03e+09 Te.131m 2.14e 15 6.51e-16 6.35e 16 1.63e 15 6.46e 15 0.00e+00 1.12e 14 1.54e*M 5.32e+05 5.66e+05 5.15e+06 0.00e+00 2.16e+07
.........................................1.09e+06 Te 132 ..................................... ;
i l 130 6.99e*M 3.10e+06 3.74e+06 4.51e+06 2.87e+07 0.00e+00 3.12e+07 !
1 131 6.12e+05 1.24e+M 6.37e+05 1.36e+08 1.85e+06 0.00e+00 5.78e+05 l 1.43e+08 1.44e+08 8.16e+07 4
.......................................... 75e+10 ....................................
2.36e*08 0.00e+00 1.28e+07 !
1 132 1 133 8.91e+01 1.64e+02 7.53e+01 7.60e+03 2.51e+02 0.00e+00 1.93e+02 l 134 3.52e+06 4.35e+06 1.65e+06 8.00e+08 7.25e+06 0.00e+00 1.75e+06 1.42e-04 2.64e-04 1.21e 04
........................................ 6.07e 03 4.03e 06 0.00e+00 1.75e 04 1 135 Cs 134 6.18e+04 1.11e+05 5.2&e+04 9.86e+0m 1.71e+05 0.00e+00 8.48e+04 Cs 136 1.60e+10 2.63e+10 5.55e+09 0.00e+00 8.15e+09 2.93e+09 1.42e+08 8.23e+07 2.33e+48 1.46e+08
..................................:..... 0.00e*00......................................
1.21e+08 1.80e+07 7.95e+06 Cs 137 Cs 138 2.39e+10 2.29e+10 3.38e+09 0.00e+00 7.4&o+09 2.68e+09 1.43e+08 8e 139 5.69e-11 7.91e 11 5.02e 11 0.00e+00 5.57e.11 5.99e-12 3.64e 11 4.69e 02 2.50e-05 1.36e-03 0.00e+00 2.18e 05 1.47e 05 2.70e+00 Corwersion facters are in mits of square meter aremvyr per uC1/ses for att nuntidos eacept N 3, e lch is in units of aremryr per uCi/c eic ester.
UNT-005-014 Revision 4 Attachment 6.9 (8 of 9) 202 4
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. R i Ri factors for Child age group by nuctide.
Waterfore Steam Electric Station l l
Pathway : Caseous AeLeese Leafy / Produce Vegetation Pathway Ri Wuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kidwy Lung GI LLI l
Ba 140 Ba.161 2.76e+08 2.42e+05 1.61e+07 0.00e+00 7.88e+06 1.44e+05 1.40e+08 Sa 142 1.56e 21 8.64e 25 5.02e-23 0.00e+00 7.47e 25 5.07e 24 8.79e 22 6.66e-39 0.00e+00 3.61e 40 0.00e+00 0.00e+00 0.00e+00 l
i ......................................................................
La 140 0.00e+00 ........
La.142 3.24e+03 1.13e+03 3.53e+02 0.00e+00 0.00e+00 0.00e+00 3.16e*07 Co.161 3.20e-04 1.02e 04 3.19e-05 0.00e*00 0.00e*00 0.00e+00 2.02e+01 6.55e+05 3.27e+05 4.aSe+06 0.00e+00 1.43e+06 0
.............................................................. 00e+00 4.08e+08 Co 143 Co 144 1.71e+03 9.29e+05 1.35e+02 0.00e+00 3.90e+02 0.00e+00 1.36e*07 Pr.163 1.27e+0S 3.90e+07 6.75e+06 0.00e+00 2.21e+07 0.00e+00 1.04e*10 1.45e*05 4.37e+06 7.22e+03 0.00e+00 2.36e+06 0 Pr.144 00e+00 1.57e+08 Nd-167 4.11e.26 1.27e 26 2.07e 27 0.00e+00 6.73e.27 0.00e+00 2.74e 23 W 187 7.14e+06 5.78e+06 4.48e+03 0.00e+00 3.17e+06 0.00e+00 9.16e*07 6.41e+04 3.80e+06 1.70e+06 0.00e+00 0.00e+00 0.00 5.34e+06
.................................................................e+00 Np 239 2.56e+03 1.56,+4 1.29e+02 1.00e+00 5.31e+02 0.00e+00 1.36e+07 Conversion facters are in mits of square meter. area /yr por uCi/sec for all nustidos eacept N 3, which is in mits of area /yr per uCi/c4fc meter.
l UNT-005-014 Revision 4 l- Attachment 6.9 (9 of 9) 203
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. i R !
l i
Rt factors for Adult age grote by nuclide.
Waterford Steen Electric Station Pathway : Geseous Reteese Goet's Milk Pathway Ri Nuctide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kichey Lung GI.LLI M3 C 14 0.00e+00 1.56e*03 1.56e+03 1.56e+03 1.56e*03 1.56e*03 1.56e+
No.26 2.63e+08 2.93e+05 5.27e+07 2.93e+05 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+
P.32 2.93e+05 2.93e+05 2.93e+05 2.93 2.93e+05............................................e+05 ....
Cr 51 2.05e+10 1.28e+09 7.93e+08 0.00e*00 0.00e+00 0.00e+00 2.31e+
Mn.54 0.00e+00 0.00e+00 0.00e*00 3.63e+03 2.05e+03 7.55e+02 4.55e+03 8.62e+0 1.01e+0
........................... 1.93e+05 0.00e+00 3.00e+05 0.00e+00 3 09e+06 6............................................
Mn-56 ......
Fe.55 0.00e*00 4.98e-04 8.8&e+05 0.00e+00 6.33e.04 0.00e*00 1.59e-0 Fe.59 3.26e+05 2.2&o+05 5.2&o*06 0.00e+00 0.00e*00 1.26e+05 1.29e 3.86e+05 9.07e+0
........................... 3.68e+05 0.00e+00 0.00e+00 2.54e+05 3 5............................................ 02e+06 Co.58 ......
Co 60 0.00e+00 5.66e*05 1.27e+06 0.00e+00 0.00e+00 0.00e+00 1.15e*
Ni.63 0.00e+00 8.07e+08 1.97e+06 4.34e+06 0.00e+00 0.00e+00 0.00e+00 3.70e*
5.60e+
.......................... 07 2.71e+07 0.00e+00 0.006 J0 0.00e+0 1.17e+07
........................................ 0...........
Ni 65 Cu.66 6.51e-02 5.86e.03 2.67e-05 0.00e+00 0.00e+00 0.00e+00 1.49e-01 Zn 65 0.00e+00 2.66e+03 1.25e+03 0.00e+00 6.72e+03 0.00e+00 2.27e+0 1.65e*08 5.26e+0
........................... 8..........................................
2.37e*08 0.00e+00 3.50e+08 0.00e+00 3.30e*08 2n 69 ........
Br 83 2.62e.13 5.00e.13 3.68e.14 0.00e*00 3.25e.13 0.00e+00 7.52e.14 Br.84 0.00e+00 0.00e+00 0.00e+00 1.62e.03 0.00e+00 0.00e+00 0.00e+00 2.05e 0 0.00e+0 Br.85 2.69e-25 0.00e+00 0.00e+00 0.00e*00 0...........................................1.96e.30- .......
Rb 86 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 ab.48 0.00e+00 0.00e+00 3.11e*08 1.65e+08 0.00e+00 0.00e+00 0.00e+00 0.00e+ 6.14e+
Rb.89 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 00....................................... ............
sr.89 0.00e+00 0.00e+00 0.00e*00.0.00e+00 0.00e+00 0.00e+00 0.00e+0 Sr.90 3.05e*09 9.83e+10 0.00.00e+00 8.76e+07 0.00e+00 0.00e+00 0.00e+00 4.49eI 2.41e+10 0.00e+00 0.00e*00 0.00e*00 2.84ee09
........................0e+00.........................................
Sr.91 ............
Sr.92 6.10e+06 0.00e+00~ 2.66e+03 0.00e+00 0.00e+00 0.00e*00 2.90e+
Y.90 1.06e+00 8.51e*00 0.000.00e+00 6.50e 02 0.00e+00 0.00e+00 0.00e+00 2.06e+
.........................e+00 0.00e+00 0.00e+00 9 02e+06
......,J. 28e-01. 0.00e+00.......................................
T 91 ......
7 91e 1.03e+03 0.00e+00 2.76e+01 0.00e+00 0.00e+00 0.00e+00 5.67 Y.92 7.52e.21 0.00e*00 2.91e.22 0.00e*00 0.00e+00 0.00e+00 2.21e 6.77e-06 0.00e+00 1.98e 07 0.00e+00 0.00e*00 0.00e+00 1.19e-0j nustideo emcept N-3, which is in units of aree/yr per uCf/ct UNT-005-014 Revision 4 Attachment 6.10 (1 of 12) 204
GOAT'5 MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. i R Ri f actors for Adult age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release Goat's Milk Pathway Ri Nuclide Organ Dose Conversiore Factors Bone Liver T. Body Thyroid KiMey Lung GI.LLI Y 93
' Zr-95 2.69e 02 0.00e+00 7.43e 04 0.00e+00 0.00e+00 0.00*00 8.53e02 1.13e+02 3.63e+01 2.46e*01 0.00e+00 5. 70e*01 0.00e+00 1.15e+05 Zr 97 5.21e 02 .1.05e-02 4.
0.00e*00 1.59e 02 0.00e+00 3. 26e+03 Nb*95 81e 03....................................... ......
i Mo.99 7.91e03 5.51e+03 2.96e+03 0.00e+00 5.45e+03 0.00e+00 3.34e+07 l Tc 101 0.00e+00 0.00e00 2.97e+06 0.00e+00 0. 5.66e 05 0.00e00 6.73e+06 0.00e+00 6.89e06
................................ 00e+00........................................
0.00e+00 0.00e+00 0.00e+GO 0.0 0e+00 Tc-99m .....
i Ru.103 4.01e.01 1.13e+00 1.44e+01 0.00e+00 1.72e+01 5.55e.01 6.71e+02 Ru.105 1.22e+02 0.00e+00 1.04e.04 0.00e+00 4 5.26e+01 0.00e+00 4.66e+02 0.00e+00 1.43e+04 0.00e+00 1.34e-03 0.00e+00 6.34 02 Ru-106 09e 05..........................................e ....
As.110m 2.45e+03 0.00e+00 3.10e02 0.00e+00 4.73c03 0.00e+00 1.58e+05 Te.125m 6.99e+06 6.46e+06 3.84e+06 0.00e+00 1.27e*07 0.00e+00 2.64e+09 1.95e+06 7.08e+05 To.127 5.88e+05 7.95e+06 0.00e+00 7 80e+06 2.62e+05......................................... ......
l 7.87e+01 2.82e+01 1.70e+01 5.83e+01 3.20ce2 0.00e+00 6.21e+03
- Te.127m Te.129 3. W 5.49c06 11 1.32e-11 1.96e+06 6.69e+05 1.40e+06 2.23e+07 0.00e+00 1.84 2.69e.11 1.47e 10 0.00e+00 2.64e.11
.Te.129m
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 . 5 3c 12................................
Te.131 7.22e+06 2.69e+06 1.14e+06 2.44e*06 3.02e+07 0.00e+00 3.64e+07 Te.131m 4.74e.34 4.34.*04 1.98e.34 2.12e*04 1 1.h34 3.h34 2.08e 33 0.00e+00 6.72e.35 Te.132 3.36e+04 2.15e*05 0.00e00 2 11e+06 77e+04....................................... ......
1-130 2.88e+05 1.86e+05 1.75e*05 2.06e*05 1.80e+06 0.00e+00 8.82e+06 I-131 5.06e*05 3.55e+08 1.49e*06 5.89e+05 1.26e+08 2.33e+06 0.00e+00 1.28e+06 5.08e*08 1.67e+11 8.71e+08 0.00e+00 1 34e+08
...............................2.91e+08........................................
1 132 ......
1 133 2.00e 01 5.36e.01 1.88e.01 1.88p01 8.54e.01 0.00e+00 1.01e 01 I 134 4.65e+06 8.09e+06 2.47e+06 1.19e+09 1.41p07 0.00e+00 7.27e+06 2.53e*12 6.87e.1
........................... 2.46e.12 1.19e.10 1.09e.11 0.00e+00 2................... ...................... 5.99e 15 3*135 ........
Ca*134 1.55e+04 4.06e+04 h50e+04 2.68e+06 6.ble+06 0.00e+00 4.58e+04 Cs.136 1.70e+10 7.90e+08 3.12e+094.03e+10 3.30e+10 0.00e00 1.31e+10 4.33e*09 7.06e+04 Cs 137 0.00e+00 1.73e+09 2.38e+04 3.54e+08 2.24e+09..r............................................
Cs.138 2.21e+10 3.03e+10 1.90e+10 0.00e+00 1.03e+10 3.42e+09 5.86e+08 8e 139 2.91e.23 5.76e.23 2.85e.23 0.00e00 4.23e-23 4.18e.24 2.46e 28 5.45e-09 3.88e.12 1.60e.10 0.00e+00 3.63e.12 2.20e-12 9.67e-09
, Comoreien f acters are in units of agaare meter.oremryr per uti/ses for att i
! nustidos except N.3, which is in mits of aremryr per utt/ceic meter.
i i
i f UNT-005-014 Revision 4 Attachment 6.10 (2 of-12) 205 l
( __ - . _ - -- -
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLlDES OTHER THAN N0BLE GASES. Ri Ri f actors for Adult age group cy nuclide.
Waterford Steam Electric Station Pathway : Gaseous Release Goat's Milk Pathway Ri Wuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung GI-LLI l
Ba-140 1 Ba.141 3.23e+06 4.05e+03 2.11e+05 0.00e+00 1.38e+03 2.32e+03 6.64e+06 '
Ba-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00 0.00e+00 0.00e+00
.......................................................e+00 La.140 La.142 5.42e.01 2.73e.01 7.22e.02 0.00e+00 0.00e+00 0.00e+00 2.00e+06 Co.141 2.28e.12 1.04e 12 2.59e.13 0.00e+00 0.00e+00 0.00e+00 7.58e.09 5.81e+02 3.93e+02 4.46e+01 0.00e+00 1
.................................................... 83e+02..........................
0.00e+00 1.50e+06 l Co.143 Co.144 4.99e+00 3.69e+03 4.09e.01 0.00e+00 1.63e+00 0.00e+00 1.38e+05 j Pr.143 4.29e+04 1.79e+04 2.30e+03 0.00e+00 1.06e+04 0.00e+00 1.45e+07 i 1.89e*01 7.60e+00 9.39e-01 0.00e+00 4 0.00e+00 8.30e+04
.................................................... 39e+00 Pr.144 ud.147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 W 187 1.13e+01 1.31e*01 7.31. 01 0.00e+00 7.63e+00 0.00e+00 6.2Te+04 7.83e+02 6.54e+02 2.29e+02
........................................ 0.00e+00 0.00e+00 0.00e*00 2.14e+05 Np 239 i 4.41e.01 4.34 02 2.39e.02 0.00e+00 1.35e.01 0.00e+00 8.89e+03 Conversion f actors are in mits of square meter-erem/yr per uCf/see for all nuclides except H 3, which is in mits of mree/yr per uCf/ctbic meter.
UNT-005-014 Revision 4 Attachment 6.10 (3 of 12) 206
i i
1 l
GOAT's MILK PATHWAY DOSE FACTORS DUE TO j
RADIONUCLIDES OTHER THAN NOBLE GASES. Rj l l
I Ri factors for feen age group Oy nuctice.
waterford Pathway : Steam Electric station I
Caseous Reteese Goet's Milk Pathway Ri Nuctide __
Orgen Dose Conversion Factors Bone Liver T. Sody Thyroid Kidney Lung GI.U I H-3 C 14 0.00e+00 2.03e+03 2.03e+03 2.03e+03 2.03e+03 2.03e+03 No 26 4.86e+08 5.12e+05 9.72e+07 5.12e+0 9.72e+07 9.72e+07 9.72e+07 5.12e+05 5.12e+05 5.12e+05 5 12e+05 5.12e+05 9.72e+07 ' 9
............................5.................................
P 32 ................
Cr-51 3.79e+10 2.35e+09 1.47e+09 0.00e+00 0.00e+00 0.00e+00 3 Mn.54 0.00e+00 0.00e+00 1.68e+0.00e+00 5.99e+03 3.33e+03 1.31e+03 8.55e*05 1 Mn 56 3.34e+05 0.00e+00 5.02e+05 0.00e+00 3.45e+06 06...................................................
7e-55 0.00e+00 8.83e.06 1.57e 04 0.00e+00 1.12e.03 0.00e+00 5.8 Fe.59 5.79e+05 6.74e+05 1.5 4.10e+05 9.57e+04 0.00e+00 0.00e+00 2.60e+45 1 6.07e+05 0.00e+00 0.00e+00 4
........................7e+06.....................................
Co*54 96e+05 3.72e+06 Co 60 0.00e+00 9.52e+05 2.19e+06 0.00e+00 0.00e+00 0.00e+00 1.
Ni-63 0.00e+00 1.42e+09 1 3.34e+06 7.51e+06 0.00e+00 0.00e+00 0.00e+00 4.3
...................... 00e+08 4.81e+07 0.00e+00 0
............................. 00e+00 0.00e+00 1.59e+07 NI.65 ..........................
Cu-64 8.25e 02 1.05e.02 4.80s.03 0.00e+00 0.00e+00 0.00e+00 5.72 2n 65 0.00e+00 4.75e+03 2.23e+03 0.00e+00 1.20e+06 0.00e+00 3
.......................8.78e*08............................
2.53e+08 4.09e*08 0.00e+00 5. 62e+08 0.00e*00 3.72e+08 2n-69 ..........................
Br.83 4.82e.t3 9.14e.13 6.62e.14 0.00e+00 6.00e.13 0.00e+00 1.6 Br.84 0.00e+00 0.00e+00 0.0 0.00e+00 2.62e.03 0.00e*00 0.00e+00 0.00e+00 0.
4.45e.25 0.00e+00 0.00e+ 00 0.00e+00 0.00e+00
........................0e+00...............................
ar.85 ......................
Rb 86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0 Ab 88 0.00e+00 0.00e+00 0 5.67e+08 2.67e+08 0.00e*00 0.00e+00 0.00e*00 8.
...................... 00e+00.............................
0.00e+00 0.00e+00 0 00e+00 0.00e+00 0.00e+00 Rb.89 ..........................
$r 89 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0 Sr*90 5.62e+09 1.39e*11 0.00e+00 1.61o+08 0.00e+00 0.00e+00 0.00e+00 6
.................... 0.00e+00 3.43e+10 0.00e*00
............................. 0.00e+00 0.00e+00 3.90e+09 Sr.91 ............................
Sr.92 1.12e+05 0.00e*00 4.46e+03 0.00e+00 0.00e+00 0.00e+00 5.
Y-90 1.90e+00 0.00e+00 8.11e.02 0.00e+00 0.00e+00 0.00e+00 4.
1.56e+01 T 91 0.00e+00. . 0.00e+00
. . . . ... 0.00e+00 0.00e+00 1.29e+05
.4J. . .t e.01.........................
7 918 1.90e+03 0.00e+00 5.08e+01 0.00e+00 0.00e+00 0.00e+00 7 Y"92 1.38e.20 0.00e+00 5.26e.22 0.00e+00 0.00e+00 0.00e+00 6.5 1.25e.05 0.00e+00 3.62e.07 0.00e+00 0.00e+00 0.00e+00 3.4 nuslides except N 3, which is in mits of aremryr per uct/
UNT-005-014 Revision 4 Attachment 6.10 (4 of 12) 207
~~ . . _ - .-- -. - - - - - - _
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. Ri l
l l
Al f actors for teen age grote by nuclide.
Waterford Steen Electric Station Pathway : Geseous Reteese Goet's Milk Pethway Ri Nuclide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidwy Lung GI LLI Y 93 Zr 95 4.96e-02 0.00e+00 1.36e-03 0.00e+00 0.00e+00 0.00e+00 1.52e+03 Zr 97 1.98e+02 6.25 e+01 4.30e+01 0.0ce<0 9.18e+01 0.00e+00 1.44e+05 s 9.48e-02 1.88e-02 8.64e-03 0.00e+00
.................................................. 2.84e 02 0.00e+00 5.08e+03 l
Nb 95 Mo-99 1.69e+04 9.37e+03 5.16e+03 0.00e+00 9.08e+03 0.00e+00 4.01e+07 Tc 101 0.00e+00 5.37e+06 1.02e+06 0.00e00 1.23e+07 0.00e+00 9.62e+06 0.00e00 0.00e+00 0.00e+00 0.00e00
.................................................. 0.00e+00 0.00e+00 0.00e+00 Tc 99m Ru 103 6.96e-01 1.94e+00 2.51e+01 0.00e*00 2.89e+01 1.08e+00 1.27e+03 Ru-105 2.17e+02 0.00e+00 9.29e+01 0.00e+00 7.66e+02 0.00e+00 1.81e+04 1.89e-04 0.00e+00 7.35e-05 0.00e+
.............................................. 00 2.39e-03 0.00e+00 1.53e 01 Ru-106 As 110m 3.47e+03 0.00e+00 5.67e+02 0.00e+00 8.68e+03 0.00e+00 2.16e05 Te 125m 1.16e+07 1.09e+07 6.65e+L 0.00e+00 2.08e+07 0.00e*00 3.07e+09 3.60e+06 1.30e+06 4.82e+05 1.0
............................................1e+06 0.00e+00 0.00e00 1.06e+07 Te 127 ..................................
Te 127m 1.46e+02 5.17e+01 3.14e+01 1.01e+02 5.91e+02 0.00e+00 1.13e+44 Te 129 1.01e+07 3.59e+06 1.20e+06 2.41e06 4.10e+07 0.00c00 2.52e+07 6.45e.11 2.40e.11 1.44e.11 4
.......................................... 61e.11 ....................................
2.71e*10 0.00e+00 3.53e.10 Te-129m ;
Te 131 1.32e+07 4.90e+06 2.09e+06 4.26e+06 5.53e07 0.00e00 4.96e07 Te.131m 8.67e*34 3.57e 34 2.71e-34 6.68e.34 3.79e.33 0.00e+00 7.11e 35 7.89e+04 3.79e+04 3.16e+04
........................................ 5.69e+04 3.95e+05 0.00e+00 3.04e+06 T* 132 t 130 5.15e+05 3.26e+05 3.07e+05 3.44e+05 3.13a+06 0.00e+00 1.03e+07 t-131 8.89e+05 2.57e+06 1.03e+06 2.10e+08 3.96e+06 0.00e00 1.98e+06 6.45e+08 9.03e+08 4.85e+0
..................................... 8 2.63e+11 1.55e+09 0.00e+00 1.79e+08 1 132 1 133 3.55e.01 9.30e 01 3.34e 01 3.13e+01 1.47e+00 0.00e+00 4.05e 01 l 134 8.50e+06 1.44e+07 4.40e+06 2.01e+09 2.53e+07 0.00e00 1.09c07 4.49e-12 1.19e.11 4.28e.1
..................................... 2 1.90e.10 1.88e.11 0.00e+00 1.57e.13
!*135 Cs 134 2.75e+04 7.09e+04 1!.63e+04 4.56e+06 1.12e+05 0.00e+00 7.85e+04 Cs 136 2.94e+10 6.93c10 3.22e+10 0.00e+00 2.20e+10 8.41e+09 8.62e+08 1.34e+09 5.29c09 3.55e+0
............................... :.... 9 0.00e00 2.88e09 4.54e+08 4.26e08 Cs 137 Cs 138 4.02e+10 5.34e10 1.86e+10 0.00e+00 1.82e*10 7.06e+09 7.60e+08 8e 139 5.29e 23 1.02e.22 5.08e 23 0.00e+00 7.49e.23 8.72e 24 4.61e 26 1.01e 08 7.09e 12 2.94e 10 0.00e+00 6.69e.12 4.89e.12 8.99e-06 Conversion f actors are in mits of square meter-aremryr per uct/sec for ELL nustidee except N 3, nAich is in units of areatyr per uct/ceic meter.
UNT-005-014 Revision 4 Attachment 6.10 (5 of 12) 208
GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. i R R1 f actors for feen age group try nuclide.
Waterford Steen Electric Station pathway
- Caseous Reteese Goat's Milk Pathway Ri Wuclide Organ Dose Conversion Factors sono Liver T. Sody Thyroid Kfdney Lime G! LLI Be-140 sa 141 5.82e+06 7.14e+03 3.75e+05 0.00e+00 2.42e+03 4.30e+03 8.98e+06 Be 142 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+ 0.00e+00
.......................... 00.......................................
0.00e+00 0.00e+00 0.00e+00 0.00e+ 00 0.00e+00 La 140 ............
La 142 9.73e1201 4.12e 4.78e.01 1.27e-01 0.00e+00 0.00e+00 0.00e+00 2.75e+04 1.83e.12 Co-141 1.07e+03 7.1 4. m .13 0.00e+00 0.00e+00 0.00e+00 5.57e 08 0.00e+00 3.35e+02 0.00e*00 2.04e+06
.Co.143
..... . . . . . . . . . . ... . . . . 2e+02 8.17e+01................................. .....................
Ce*144 9.18e+00 6.68e+03 7.46e.01 0.00e+00 2.99e+00 0,00e+00 2.01e+05 Pr*143 7.90e+04 3.48e*01 1. 3.27e+04 4.24e+03 0.00e+00 1.95e+04 0.00e+00 1.99e*07 1.73e+00 0.00e+00 8.08e*00 0.00e+00 1.15e+05
.......................39e+01....................................
Pr.144 ..................
Nd.147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 W 187 2.17e+01 1.43e+03 1 2.36e+01 1.42e+00 0.00e+00 1.39e+01 0.00e+00 8.53e+04
...................... 17e+03..................................
Np.239 4.09e+02 0.00e+00 0.00e+0 0' O.00e+00 3.16e+05 8.42e.01 7.94e-02 4.41e-02 0.00e+00 2.49e.01 0.00e+00 1.28e+04 nuctIdee except N 3, which is in units of arem/yr per uCf/cLeic UNT-005-014 Revision 4 Attachment 6.10 (6 of 12) 209
GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. Ri Ri factors for Child age group by nuclide.
Waterford Steam Electric Station Pathway : Caseous Release Goat's Milk Pathway Ri Nuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kichey Lung CI LLI H-3 0.00e+00 3.20e+03 3.20e+03 3.20e+03 3.20e+03 3.20e+03 3.20e+03 C-14 1.19e+09 2.39e+08 2.39e+08 2.39e08 2.39e*06 2.39e+08 2.39e+08 Na 24 1.07e+06 1.07e+07 1.07e+06 1.07e+06 1.07e+06 1.07e+06 1.07e+06 P 32 9.33e+10 4.37e+09 3.60e+09 0.00e+00 0.00e+00 0.00e00 2.58e+09 Cr 51 0.00e+00 0.00e00 1.22e+06 6.78e*03 1.85e+03 1.24e04 6.48e+05 Mn 54 0.00e+00 2.52e+06 6.70e+05 0.00e 00 7.06e+05 0.00e+00 2.11e+06 Mn.56 0.00e+00 1.54e.03 3.48e-04 0.00e+00 1.86e.03 0.00e+00 2.23e-01 Fe.55 1.45e+06 7.71e*05 2.39e+05 0.00e+00 0.00e+00 4.36e+05 1.43e+05 Fe-59 1.56e*06 2.53e+06 1.26e*06 0.00e+00 0.00e+00 7.33e+05 2.63e*46 Co.58 0.00e+00 1.45e+06 4.45e+06 0.00e+00 0.00e*00 0.00e+00 8.49e+06 Co 60 0.00e+00 5.18e+06 1.53c07 0.00e+00 0.00e+00 0.00e+00 2.87e+07 N1 63 3.56e+09 1.90e+08 1.24e+08 0.00e+00 0.00e+00 0.00e00 1.28e+07 Ni-65 2.02e-01 1.90e.02 1.11e 02 0.00e+00 0.00e+00 0.00e+00 2.33e00 Cu-64 0.00e+00 8.34e+03 5.04e+03 0.00e+00 2.02e+04 0.00c00 3.92e+05 Zn 65 4.96e+08 1.32e+09 8.22e08 0.00e+00 8.33e+08 0.00e+00 2.32e+08 Zn-69 1.18e.12 1.71e.12 1.58e-13 0.00e+00 1.04e.12 0.00e+00 1.08e.10 Br-83 0.00e*00 0.00e+00 6.44e-03 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br 84 0.00e+00 0.00e00 1.01e 24 0.00e+00 0.00e*00 0.00c+00 0.00e+00 Sr.85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 R&86 0.00e+00 1.05e+09 6.47e*06 0.00e+00 0.00e+00 0.00e+00 6.77e+07 Rb88 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 Ab-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Sr 89 1.39e+10 0.00e+00 3.97e+08 0.00e+00 0.00e+00 0.00e+00 5.38e+08 Sr 90 2.35e11 0.00e+00. 5.95e+10 0.00c00 0.00e+00 0.00e+00 3.16e+09 Sr-91 2.75e+05 0.00e+00 1.04e+04 0.00e+00 0.00e*00 0.00e+00 6.07e+05 sr 92 4.65e*00 0.00e*00 1.86e-01 0.00e*00 0.00e+00 0.00e+00 8.81e+01 Y 90 3.87e+01 0.00e+00 1.04e+90 0.00e+00 0.00e+00 0.00e00 1.10e+05 Y 91 4.68e+03 0.00e+00 1.25e+02 0.00e+00 0.00e+00 0.00e00 6.24e+05 Y 91m 3.36e.20 0.00e*00 1.22e 21 0.00e00 0.00e*00 0.00e00 6.59e.17 Y 92 3.07e-05 0.00e+00 8.78e 07 0.00e+00 0.00e00 0.00e+00 8.87e.01 Conversion factors are in mits of square aster area /yr per uCI/sec for aLL nuclides except N-3, which is in units of aram/yr per UCl/cthic meter.
UNT-005-014 Revision 4 Attachment 6.10 (7 of 12) 210
GOAT's MILK PATHWAY DOSE FACTORS DUE TO MDIONUCLlDES OTHER THAN N0BLE GASES. i R, i
i l
Ri factors for Child age group by nuctide.
Waterford Steen Electric station Pathway : Caseous Aeteese Goet's Milk Pathuey Al Nuclide i
Organ Dose Conversion Factors Bone Liver T. Sody Thyroid Kidrwy Lung l GI LLI l
Y-93
' Zr 95 1.22e 01 0.00e+00 3.35e 03 0.00e+00 0.00e 00 0.00e+00 1.82e+03 Zr 97 4.60e+02 2.31e 01 3.33e 1.01e+02 9.00e+01 0.00e+00 1.45e+02 0.00e+00 1.05e+05 02 1.97e-
.................................... 02 0.00e+00 4.79e 02 0.00e+00 5.05e+03 Nb 95 Mo-99 3.81e+04 1.49e+04 1.06e+04 0.00e+00 1.40e+04 0.00e+00 2.75e+07 Tc 101 0.00e+00 9.77e+06 2.42e+M 0.00e00 2.09e+07 0.00e+00 8.08e+06 0.00e+00 0.00e+00 0.00e+0
..................................... 0 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Tc-99m Ru-103 1.60e+00 3.13e+00 5.19e+01 0.00e+00 4.55e+01 1.59e+00 1.78e+03 Ru 105 5.14e+02 4.62e-04 0.00e+00 0.00e+00 1.98e+02 0.00e+00 1.29e+03 0.00e+00 1.33e+04 1.68e.
.................................... 04 0.00e*00 4.06e-03 0.00e+00 3.02e 01 Ru-106 1.11e+04 0.00e+00 1.38e+03 0.00e+00 1.50e+04 0.00e00 1.72e+05 Ag-110m Te-125m 2.51e+07 1.69e+07 1.35e+07 0.00e+00 3.15e+07 0.00e+00 2.01e+09 8.85e+06 2.40e+06 1.18
...................................e+06 2.48e+06 0.00e+00 0.00c00 8.54e+06 Te 127 Te 127m 3.59e+02 9.67e+01 7.69e+01 2.48e+02 1.02e+03 0.00e+00 1.40e+04 Te 129 2.50e+07 1.59e 10 4.44e.116.72e*06 3 2.96e+06 5.97e*06 7.12e+07 0.00e+00 2.02e+07
................................ 78e 11..............................................
1.14e 10 4.65e.10 0.00e 00 9.90e 09 Te*129m 3.26e+07 9.09e 06 5.06e*06 1.05e*07 9.54e+07 0.00e+00 3.97e+07 fe.131 I Te*131m 2.13e.33 6.48e 34 1.92e+05 6.65e+04 6.33e.34 1.63e.33 6.43e 33 0.00e+00 1.12e 32 7.07
...................................e+04 1.37e+05 6.43e+05 0.00e+00 2.70e*06 Te 132
! 130 1.23e+06 5.44c05 6.58e+05 7.93e05 5.05e06 0.00e+00 5.48e+06 l 131 2.08e+06 1.56e+09 1.57e09 4.20e+068 2.16e+06 4.63e+08 6.28e+06 0.00e+00 1.97e+06
................................94e08 1 132 5.20e+11 2.58e+09 0.00e+00 1.40e+08 1 133 8.41e-01 1.54e+00 7.10e 01 7.17e+01 2.36e*00 0.00e+00 1.82e+00 1 134 2.06c07 2.55e+07 1.06e.11 1.98e-11 9 9.66e+M 4.74e+09 4.25e+07 0.00e+00 1.03e+07 1 135 4.54e 10 3.02e 11 0.00e+00 1.31 09e.12..........................................e ....
11 cs 134 6.52e+M 1.17e+05 5.55e+04 1.04e+07 1.80e05 0.00e+00 8.94e04 cs 136 6.79e+10 3.04e+09 1.11e+11 8.58e+09 2.35e+10 0.00e+00 3.45e+10 1.24e+10 6.01e+08
.............................. 5.40e+09 0.00e+00 4.44e+09 6.63e+08 2.93e+08 Cs 137 ................................................
cs 138 9.67e+10 9.26e+10 1.We+10 0.00e+00 3.02e+10 1.09p10 5.80e+08 Sa*139 1.28e 22 1.78e 22 1.13e.22 0.00e+00 1.25e 22 1.35e-23 8.21e 23 2.48e-08 1.32e.11 7.18e 10 0.00e+00 1.15e.11 7.78e 12 1.43e-06 Conversion facters are in mits of squere meter erem/yr per uCf/sec for all nuclideo except N 3, which is in mits of arem/yr per ucl/ cubic meter.
l l
k i
UNT-005-014 Revision 4 Attachment 6.10 (8 of 12) 211
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. i R Ri fcetors for Child age gro m Oy nuclide.
Watertoro steso Electric Station Pathway : Caseous Release Goet's Milk Pathway Ri l Nuclice organ Dose Conversion Factors i
Bone Liver 7. Body Thyroid Kichey Lme GI.LLI Be.140 Be.141 1.41e+07 1.23e+04 8.20e*05 0.00e+00 4.01e+03 7.34e+03 7.12e+06 i Be.142 0.00e+000.00e+00 0.00e+00 0.00e+00 0 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1
................................ 00e+00 ..............................................
0.00e+00 0.00e+00 0.00e+00 0.00e+00 La.140 La.142 2.33e+00 8.15e.01' 2.54e.01 0.00e+00 0.00e+00 0.00e+00 2.27e+04 i Co.141 9.95e.12 3.17e.12 9.94e.13 0.00e+00 0.00e+00 0.00e+00 6.29e.07 2.62e+03 1.31e+03
.............................. 1.94e+02 0.00e+00 5.74e+03 0.00e+00 1.63e+06 Co.143 Co.144 2.25e+01 1.22e+04 1.77e+00 0.00e+00 5.12e+00 0.00e+00 1.79e+05 Pr.143 1.95e+05 8.62e+01 6.10e+04 1.04e+04 0.00e+00 3.38e*04 0.00e+00 1.59e+07 2.59e+0
............................1 Pr.144 4.28e+00 0.00e+00 1.40s+01 0.00e+00 9.30e+04 I
Nd-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 '
W.187 5.34e+01 3.47e+03 4.32e+01 3.35e+00 0.00e+00 2.37e+01 0.00e+00 6.85e+04 2.06e+ !
up-239 9.22e+02 0.00e+00 0.00e+00 0.00e+00 2.89 03................................................e+05 2.0Te+00 1.49e.01 1.0$e 01 0.00e+00 4.30e.01 0.00e+00 1.10e+04 l Corwersion factors are in units of square ester. area /yr per uCf/sec for all nuctidee except H.3, which is in mits of arem/yr per UCf/c@lc meter.
UNT-005-014 Revision 4 Attachment 6.10 (9 of 12) 212
l 1
GOAT's MILK PATHL4AY DOSE FACTORS DUE TO ;
RADIONUCLIDES OTHER THAN NOBLE GASES. i R Ri factors for infant age group cy nuclide.
Waterforo Steam Electric Station Pathway Caseous Release Goet's Milk Pathway Ri Nuclide Organ Dose Conversion Factors sono Liver l
T. Body Thyroid Kichey Lung G! LLI
}
1 H-3 i
', c 14 0.00e+00 4.86e+03 4.86e*03 4.86e*03 4.86e+03 4.86e*03 4.86e+03 I Na*24 2.34e09 5.00e+08 1.85e+06 1.85e+06 5.00e+08 5.00e+08 5.00c08 5.00e08 5.00e08 1.85e+06 l
{ ........................................1.85e+06 Pa32 1.85e*06 1.85e+06 1.85e+06 q
cr 51 1.92e+11 1.13e+10 7.44e+09 0.00e+00 0.00e+00 0.00e*00 2.60e*09
- Mn-54 0.00 0.00e+00e004.68e+06 0.00e+00 1.94e*04 1.26e*04 2.76e*03 2.46e+06 5.64e*05 1.06e*
.................................... 06 i
0.00e*00 1.04e+06 0.00e+00 1.72e*06 I
Mn-56 .......................................... l Fe.55 0.00e+00 3.77e-03 6.50e.04 0.00e+00 3.24e 03 0.00e+00 3.43e 01 Fe-59 1.76e+06 2.92e*M 1.13e+06 5.10e+M 2.013.03e05 0.00e*00 0.00e00 5.55e*05 1.44e+05
...................................e+06 Co 58 0.00e+00 0.00e+00 1.51e+06 2.43e+06 i co-60 0.00e*00 2.91e+06 7.26e*06 0.00c00 0.00e+00 0.00e+00 7.25e+06 Ni 63 0.00e+00 1.06e+07 4.19e+09 2.59e+08 1 2.50e+07 0.00e 00 0.00*00 0.00e+00 2.52e07 i
................................ 45e+08 ..............................................
0.00e+00 0.00e+00 0.00e+00 1.29e+07 Ni 65 cu 64 4.27e 01 4.83e-02 2.20e 02 0.00e00 0.00e+00 0.00e+00 3.68e+00 9
Zn-65 0.00e+002.28c09 6.66e+08 2.07e+04 1 9.60e03 0.00e+00 3.51c06 0.00e 00 4.26e05 j ................................ 05e+09..............................................
0.00e+00 1.11e*09 0.00c00 1.93e+09 (
i Zn 69 gr 83 2.52e 12 4.54e.12 3.38e.13 0.00e+00 1.89e.12 0.00e*00 3.70e-10 l 0.00e+000.00e+000.00e+00 Br 84 0.00e+00 1 1.37e-02 0.00e+00 0.00e+00 0.00e+00 0.00e+00
................................ 94e.24 0.00e+00 0.00e*00 0.00e+00 0.00e+00
- Br 85
' Rb-86 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb-88 0.00e+00 0.00e*00 2.67e+09 1.32e*09 0.00e*00 0.00e+00 0.00e00 6.83e*07 0.00e+00
.............................. 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 Rb 89 St 89 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Sr.90 2.64e+10 0.00e+00 7.58e+08 0.00e+00 0.00p40 0.00e00 5.43e+08 2.55e+11 0.00e+00
.............................. 6.50e*10 0.00e+00 0.00p00 0.00e+00 3.19e09 Sr-91 ................................................
Sr-92 5.73e+05 0.00e+6 2.07e+04 0.00e+00 0.00p00 0.00e+00 6.78e+05 Y 90 9.89e+000.00e+00 8.18e+01 0.00e+002 3.67e 01 0.00e+00 0.00e+00 0.00e*00 1.07e+02
................................ 19e*00 ..............................................
0.00e+00 0.00e+00 0.00e+00 1.13e05 b91 Y 91m 6.79e+03 0.00e+00 2.34e*02 0.00e+00 0.00e+00 0.00e+00 6.30e05 Y 92 7.13e.20 0.00e*00 2.43e 21 0.00e+00 0.00e+00 0.00e+00 2.38e.16 6.52e 05 0.00e+00 1.83e.06 0.00e+00 0.00e*00 0.00e+00 1.24e*00 Convereien festers are in mite of equere meter-eres/yr per ucl/sec for all nustidae except M 3, dich is in mite of ares /yr per uCi/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.10 (10 of 12) 213
G0AT's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. R i Ri factors for Infant age group by nuctide.
Waterford Steen Electric station Pathway : Gaseous Reteese Goet's Milk Pathway Ri Nuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kidney Lung Gl*LLI Y 93 Zr 95 2.60e 01 0.00 e00 7.08e 03 0.00e+00 0.00e00 0.C0e00 2.05e+03 Zr 97 8.16e+02 1.99e+02 1.41e+02 0.00e+00 2.14e+02 0.00e+00 9.91e+04 4.89e.01 8.38. 02 3.83e 02 0.00e+00
.................................................. 8.45e.02 0.00e+00 5.35e*03 Nb-95 Mo-99 7.12e+04 2.93e+04 1.70e+04 0.00e+00 2.10e+04 0.00e+00 2.48e+07 Tc.101 0.00e00 2.50e+07 4.87e+06 0.00e+00 3.73e+07 0.00e+00 8.23e+06 0.00e+00 0.00e+00 0.00e+00 0.00e+00
.................................................. 0.00e+00 0.00e+00 0.00e+00 Tc 99m Ru-103 3.32e+00 6.84e+00 8.82e+01 0.00e+00 7.36e+01 3.58e00 1.99e+03 Ru 105 1.04e+03 0.00e+00 3.48e*02 0.00e+00 2.17e+03 0.00e+00 1.27e+04 9.75e-04 0.00e+00 3.28e-04
........................................ 0.00e+00 7.17e-03 0.00e+00 3.88e.01 Ru-106 As 110m 2.28e+04 0.00e+00 2.85e+03 0.00e*00 2.70e+04 0.00e+00 1.73e+05 Te.125m 4.63e+07 3.38e+07 2.24e+07 0.00e+00 4.83e+07 0.00e+00 1.75e+09 1.81e+07 6.05e+06 2.45e+06
........................................ 6.09e+06......................................
0.00e+00 0.00e+00 8.62e+06 To.127 {
To.127m 7.61e+02 2.55e*02 1.64e+02 6.20e+02 1.86e+03 0.00e+00 1.60e 04 Te.129 5.05e+07 1.68e+07 6.12e+06 1.46e+07 1.24e+08 0.00e+00 2.04e+07 3.37e.10 1.16e.10 7.87e. 2.83e.10 8.40e.10 0.00e+00 2.70e-08
.....................................11 T e129m .........................................
Te 131 6.69e+07 2.29e+07 1.03e+07 2.57e+07 1.67e+08 0.00e+00 3.99e+07 Te-131m 4.51e.33 1.67e.33 1.27e.33 4.02e 33 1.15e.32 0.00e+00 1.82e 31 4.06e+05 1.63e+05 1.35e+05
........................................ 3.31e+05......................................
1.12e+06 0.00e+00 2.75e+06 Te-132 I 130 2.53e+06 1.25e+06 1.17e+06 1.85e+06 7.84e+06 0.00c00 4.64e+06 I 131 4.27e+06 9.40e+06 3.TTe+06 1.05e+09 1.03e+07 0.00e00 2.01e+06 3.26e+09 3.85e+09 1.69e+
.................................... 09 1.26e+12 4.49e+09 0.00e+00 1.37e+08 1*132 1 133 1.74c00 3.54e+00 1.26e+00 1.66e+02 3.95e+00 0.00e+00 2.87e+00 I 134 4.36e+07 6.35e+07 1.86e+07 1.15e*10 7.46e+07 0.00e+00 1.07e+07 2.21e-11 4.52e 11 1.61e. 1.05e-09 5.0$e.11 0.00e+00 4.67e.11
.............................. .....11.........................................
1 135 Cs.134 1.36e+05 2.70e+05 9.83e+04 2.42e+07 3.00e+05 0.00e+00 9.76e+04 Cs 136 1.09e+11 2.04e+11 2.06e+10 0.00e+00 5.25e+10 2.15e+10 5.54ces 5.95e+09 1.74*10 f.51
....................................e+09 0.00e+00 6.95c09 1.42e+09 2.65e+08 Cs 137 Co 138 1.54e+11 1.81e+11 1.28e+10 0.00e+00 4.85e10 1.96e+10 5.65c08 Be 139 2.70e.22 4.40e.22 2.13e.22 0.00e+00 2.19e22 3.42e.23 7.03e.22 5.27e-04 3.49e.11 1.53e.09 0.00e00 2.10e.11 2.12e.11 3.34e 06 Corwersion factors are in units of agaare aster.oremryr per uCl/see for ett nustidos eseept l1 3, e lch is in tmits of aremryr por uCl/c eis meter.
UNT-005-014 Revision 4 Attachment 6.10 (11 of 12) 214
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES. iR Ri factors for Infant age group by nuclide.
Waterford steam Electric stattori Pathway : Caseous Reless0 Goates Milk Pathway Ri Nuclide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kichey Lung GI.LLI Ba.140 Ba 141 2.89e+07 2.89e+04 1.49e+06 0.00e+00 6.87e03 1.78e+06 7.10e+06 Ba 142 0.00e+000.00e+00 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+
.................................... 00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 La 142 4.87e+00 1.92e+00 4.94e 01 0.00e+00 0.00e+00 0.00e+00 2.25e+04 Co 141 2.09e 11 5.20e03 7.67e 12 3.17e+03 1.84e.12 0.00e+00 0.00e+00 0.00e+00 1.30e.06 3.74e+
.................................... 02 0.00e+00 9.79e+02 0.00e+00 1.64e+06 Co-143 C8 144 4.77e+01 3.16e+06 3.61e00 0.00e+00 9.21e+00 0.00e+00 1.85e+05 Pr*143 2.79e+05 1.14e+05 1.78e*02 6.67e+01 8 1.56e+04 0.00e+00 4.62e+04 0.00e+00 1.60e+07
................................ 84e+00 ..............................................
0.00e*00 2.48e+01 0.00e+00 9.41e+04 Pr.144 Nd-147 0.00e+00 0.00e+00 0.00e+00 0.00w+00 0.00e+00 0.00e+00 0.00e+00 W.187 1.06e02 1.09e+02 6.65e+00 0.00e+40 4.19e+01 0.00e+00 6.88e*04 7.31e+03 5.08e+0
........................... 1.76e+03 0.00e 00 0.00e+00 0.00e+00 2 3............................................ 99e+05 NP-239 4.38e+00 3.92e.01 2.21e.01 0.00e+00 7.81e 01 0.00e+00 1.13e+06 Corwoesten factors are in isiits of emance meter.aren/yr per uct/see for ett nuclides except u.3, which is in istits of aren/yr per uCf/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.10 (12 of 12) 215
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UNT-005-014 Revision 4 Attachment 6.12 (1 of I)
, n.- --. ~. ~.-.-. _ ..- - - - - - . . - . - - . - - . - . . . - - - ~ . - - - - . - - . . . ~ .
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM L
SAMPLE LOCATION ANALYSIS FREQUENCY VOLUME A-2, B-1. C-1, D-2. E-1, TLD (1) ouerterly N/A !
F-2, G-2, H-2, J-2, K-1, TLD L-1, M-1, N-1, P-1, Q-1, R-1, A-5, 84, D-5, E-5, F4, G4, H-6, P-6, Q-5, R-6, F-9, G-9, E-15,J-15, !
E-30 Radioiodine and APP-1, APQ-1, APG-1, Gross Este.1-131 w kiy 285 m3/wk Particulates APC-1. APE-30 Gamme isotopic (2) ouert riy composite 3700 maiort !
Ground Water (6) GWK-1 Gamma Isotopic , H-3 overterty 4 uter. _ _ _ _
P H-3 Quarterly Composite y Hwnogeneous 4 Uters t Drinking Water (3) DWG-2, DWE-5 (4) DWP-7 Gross Beta, Gamma Isotopic Monthly composit (111 1-131 (7) s.mi-monthey composite rface V er (3) SWG-2. SWE-5 (4) ,SWP-7 H-3 ouert.ety Composite Homogeneous 4 Utere i
\l Gamma Isotopic Montwy compoce (11 ;
Shoreline Sediment SHWE-3, SHWK-1 Gamma Isotopic semi-Annueny 2 Kisograme Milk MKO-5, MKQ45, MKO-1 Gamma Isotopic,1-131 semi-montwy t uontwy tel 4 ut.re Fish FH-1, FH-2 l Gamma Isotopic in s eon or semi-AnnueNy (9) 500 Grams Food products
- FPP-1, FPG-1 I Gamma Isotopic At H.rvest Time 110) 500 Grorm Broad Leaf BLQ-1, BLB-1, BLK-15 Gamma Isotopic,1-131 montwy (when mak e.mpi.e 500 Gr,m.
are not conectedi Sanitary System (12) SWR-1 Gamma Isotopic Montwy composite (11) Homogeneous 4 Utere
- lerigated Food Pathway do.e not Exist However, Food Products grown within the alte boundary are sempted and analyzed.
UNT-005-014 Revision 4 Attachment 6.13 (1 of 3) r 219
RADIOLOGICAL ENVIR0fMENTAL MONITORING PROGRAM (Continued)
- 1. One or more instrument, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. A TLD is considered one phosphor, two or [
more phosphors in a packet are considered two or more dosimeters. Geographical limitations affect siting of dosimeters.
r
- 2. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after ;
sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is i greater than ten times the yearly mean of control samples, gamma isotopes analysis shall be performed on the individual samples. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
- 3. Drinking Water and Surface Water samples are identical samples.
- 4. The downstream sample is beyond the mixing zone.
- 5. A composite sample will contain aliquots of sarple taken proportional to the quantity of flowing liquid that i results in a specimen representative of the liquid flow.
- 6. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for coatamination.
- 7. This analysis will be performed when the dose calculated for tha consumption of water is greater than 1 arem per year as calculated for maximum organ and age group.
- 8. Milk will be collected semimonthly %en animals are on pasture, monthly otherwise. If milk sampling is not performed, broad leafy vegetation will be sampled.
- 9. Striped mullet, gizzard shad, freshwater drum, and catfish will be collected. If they are not available, substitute species will be collect =d and identified in reporting.
UNT-005-014 Revision 4 Attachment 6.13 (2 of 3) 220 ,
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)
- 10. One sample of each principal class of food products will be sampled in an area irrigated by water in which plant wastes have been inadvertently discharged. If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvesting occurs continuously, sampling shall be monthly.
Tuberous and root products will be sampled when available.
- 11. An anaylsis frequency of Every 4 Weeks satisfies this requirement. The maximum frequency is monthly.
- 12. Sanitary System Sampling and analysis performed additionally for this location. This sampling requirement is not derived directly from REMP requirements, but it represents another possible environmental interface with the plant. Information from this sample location will not normally be included in the Annual Radiological Environmental Operating Report.
UNT-005-014 Revision 4 Attachment 6.13 (3 of 3) 221
l SAMPLE LOCATION TABLE LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD) l A-2 (Eastbank) Located on a utility pole on 1.1 N
! River P nd (La. 628) at the south corner of
! the i gnrin L. Perriloux Fire Station i
(Station 5) in Montz, La.
B-1 (Eastbank) On fence enclosing the 0.8 NNE transmission tower 0.3 miles west (up river) from Little Gyspy. Access from River Road (LA 628). TLD's are located at SW corner of fence enclosure.
C-1 (Eastbank) On fence enclosing the Little 0.8 NE l
Gyspy Cooling Water Intake. Access is from River Road (LA 628) across from Little Gypsy Power Station entrance. TLD's are on the south side (inside) of the Cooling Water Intake fence enclosure, directly opposite the entrance gate.
D* (Eastbank) Located approximately 0.3 miles 1.1 ENE east of Little Gypsy Power Station.
Access from River Road (LA 628). TLD's are attached to a stop sign post located at the peak of the levee on the west entrance road through the Bonne Carre Spillway.
l I
l l UNT-005-014 Revision 4 Attachment 6.14 (1 of 12) 222 l
1
SAMPLE LOCATION TABLE (Continued) l LOCATION LOCATION MILES FROM SECTOR NUMBER D/SCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD) (continued) i E-1 (Westbank) located on utility pole along 0.2 E l
River Road (LA 18) approximately 0.3 miles east of Waterford 3 plant entrance. Access I from LA 18. TLD's are on the third utility l
pole east of the constr_uction entrance road. '
F-2 (Westbank) located on fence enclosure 1.1 ESE surrounding the LP&L substation on LA 3142.
j Access from LA 3142 approximately 0.2 miles south of LA 18. TLD's are on the southeast corner of the fence enclosure.
G-2 (Westbank) Located on fence near 1.2 SE
- utility pole on East side of LA 3142 1 (Next to Union Carbide Star Plant Gate 3).
Access from LA 3142 approximately 0.2 miles north of railroad overpass.
1 i
H (Westbank) Located on fence enclosure 1.2 SSE to shell road off of LA 3142. Access from LA 3142 south of railroad overpass l
on east side of LA 3142. .TLD's are on the south side of the gate for shell road.
j (Just south of Texaco pipeTine station).
l l
't UNT-005-014 Revision 4 Attachment 6.14 (2 of 12) 223
l i
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION fTLD) (continued)
J-2 (Westbank) Located on northeast corner 1.3 S of fence enclosing Texaco valve station south of LA 3127. Access from LA 3127, approxmiately 0.6 miles west of LA 3127/3142 intersection.
K-1 (Westbank} Located on fence at Gate 92 1.0 SSW entrance off of LA 3127. Access from LA 3127, approximately 1.3 miles west i
of LA 3127/3142 intersection. (Gate 92 is the access to the Waterford 3 switchyard station and Training Center).
L-1 (Westbank) located next to " Private Road" 1.0 SW sign at Gate 97 entrance off of LA 3127, approximtely 1.6 miles west of LA 3127/3142 intersection. (Gate 97.
is an access road for Waterford 3).
M-1 (Westbank) located on south gate of 0.7 WSW the Waterford I and 2 fuel oil storage tank enclosure. Access is either thru LP&L Gate 92, Gate 97 off of LA 3127, the shell access road from LA 18 betw'een Waterford 3, i or thru the Waterford 1 and 2 access road.
N-1 (Westbank) located behind the "No Trespassing 0.9 W l
1 sign off on Short Street, in K111ona just south of the Killona Elementary School.
l UNT-005-014 Revision 4 Attachment 6.14 (3 of 12) 224
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT- DIRECTION DIRECT RADIATION (TLD) (continued)
P-1 (Westbank) located on Short Street, TLD 0.8 WNW is inside fence at air sample station APP-1 Q-1 (Westbank) Located on fence enclosing air. 0.8 NW sample station approximately 0.5 miles-west of Waterford 1 and 2 on River Road (LA 18). !
R-1 (Westbank) locateu on fence enclosure for- 0.5 NNW Waterford 1 and 2 Cooling Water Intake Structure. Access is from River Road !
(LA 18) opposite Waterford I and 2.
TLD's are on the southwest corner of fence.
A-5 (Eastbank) located on utility pole just 4.5 N east of the Shady Nook Trailer Park on Hwy 61 in Laplace. TLD's are on second utility pole east of trailer park on north side of Hwy 61 (eastern end of Laplace)
B-4 (Eastbank) Located on utility pole guidewire 3.8 NNE west of shell access road to South Central Bell transmission tower on south side of Hwy 61. Transmission tower is just east of Weigh Station at St. John /St. Charles Parish line.
TLD's are on first utility pole west of access road.
l UNT-005-014 Revision 4 Attachment 6.14 (4 of 12) 225 1
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM~ SECTOR NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD) (continued)
D-5 (Eastbank) Located on fence gate on shell 4.2 ENE l access road to Big 3 Chemical Plant.
Shell access road is approximately 0.1 miles west of Hwy 61/48 intersection (at black and yellow gate). TLD's are ,
on fence gate 0.1 miles north on shell ;
access road from Hwy 61.
E-5 (Eastbank) Located on the Norco Substation 4.2 E fence enclosure. Access from River Road (LA 48) onto Wesco St. (adjacent to Norco Shell Chemical Plant), take Wesco St.
j to the dead end. TLD's are located on l fence beside of the north substation gate.
F-4 (Westbank) Located on utility pole behind 3.5 ESE blonde brick Lause on Aquarius St. in Hahnville. Access from River Road (LA 18) and turn onto Oak St. Follow Oak St. to Hickory St., turn right on Hickory St. and follow to Aquarius St. and turn left. Blonde
{
brick house is second house on right (west) I side of Aquarius St. heading south.
G-4 (Westbank) Located on rail. road sign 3.2 SE northwest side of LA 3160/ railroad track intersection. Access from either LA 3127 or River Road (LA 18) onto LA 3160.
UNT-005-014 Revision 4 Attachment 6.14 (5 of 12) 226
J SAMPLE LOCATION TABLE (Continued) I l
l LOCATION LOCATION MILES FROM SECTOR l
NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD) (continued)
H-6 (Westbank) located on a road 5.7 SSE l sign on the Northwest side of the second I
canal bridge east of LA 3160 along LA 3127.
P-6 (Westbank) Located on a fence surrounding 5.5 WNW the Union Pacific communications tower at the LA 640/ railroad track intersection.
Tower is located approximately 500 feet west of LA 640.
l l Q-5 (Westbank) located on fence l 5.0 hW surrounding (green) ri'ter marker on lavee just east of Edgard. Fence post is located along River Road (LA 18) across from the Webre's house.
l R-6 (Eastbank) located on fence enclosing 5.3 NNW l
LP&L Laydown Yard on LA 3223 in Laplace.
Access from Hwy 61 onto Elm St. (LA 3223),
take Elm St. to the northeast corner of LA 3223/ railroad intersection. TLD's are located ac the entrance of the fence enclosure.
F-9 (Eastbank) located on entrance gate 8.2 ESE to Destrehan Substation. Access from i
River Road (LA 48), approximate 1.5 miles east of Luling-Destrehan Bridge, onto Jonathan Street (west of Bunge Corp.
Grain Elevator), and proceed to substation gate.
UNT-005-014 Revision 4 Attachment 6.14 (6 of 12) 227 l
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD)-(continued)
I l l G-9 (Westbank) located on back fence of 8.1 SE LP&L District Office in Luling. Access I
via Ellington St. from either River Road l
(LA 18); or Second or Third S. from Paul Mallard Rd. (LA 52) to Ellington St.
i E-15 (Eastbank) located on Kenner Substation 11.8 E fence enclosure. Access from either River Road (LA 48) or Hwy 61, turn onto Alliance Ave. TLD's are located at the entrance of the fence enclosure.
1 J-15 (Westbank) located on fence enclosure 12.0 S surrcunding LP&L switchyard at LA 631/ Hwy 90 intersection in Des Allemands.
\
TLD's are on the northwest corner of i fence. Access from LA 631 via shell road.
i E-30* (Westbank) Located at LP&L General 27.0 E l Office or Delaronde St. in Algiers. TLD's are on a tree in the courtyard at the south entrance to the building.
i
- DENOTES CONTROL LOCATIONS l
UNT-005-014 Revision 4 Attachment 6.14 (7 of 12) 228
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION AIRBORNE l APP-1 (Westbank) located in soybean / sugarcane 0.8 WNW field at northwest corner of Short St.
in Killona. !
l APQ (Westbank) Located at northwest corner 0.8 NW of soybean / sugarcane field on east side of Killona Access from River Road (LA 18) approximately 0.6 miles east of LA 18/3141 intersection.
APG-1 (Westbank) Located at the north side 0.5 SE of the Secondary Meteorological Tower.
APC-1 (Eastbank) Located inside the Little Gypsy 0.8 NE Cooling Water Intake Structure fence enclosure.
APE-30* (Westbank) Located on the roof of the 27.0 E LP&L General Office building on Delaronde St. in Algiers.
- DENOTES CONTROL LOCATIONS UNT-005-014 Revision 4 Attachment 6.14 (8 of 12) 229
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR
, NUMBER DESCRIPTION PLANT DIRECTION FOOD PRODUCTS i
FPP-1 (Westbank) located in field on eastern edge 0.8 WNW of Killona, between air sample stations APP-1 and APQ-1. The crops grown alternate between soybeans and sugar cane.
FPG-1 (Westbank) located in field east of Water- 0.4 SE ford 3 near the Back-up Meteorological l
Tower and air sample station APG-1.
The crops grown alternate between soybeans and sugar-cane.
BROAD LEAF BLQ-1 (Westbank) located between LA 18 and 0.8 NW soybean field on eastern edge Killona, near air sample station APQ-1.
BLB-1 (Eastbank) located at wooded area at the 0.8 NNE southwestern corner of the LP&L Little Gypsy plant along River Road.
BLK-15* (Westbank) Located 3.5 miles SSW of 15.0 SSW Des Allemands on Hwy. 90.
- DENOTES CONTROL LOCATIONS UNT-005-014 Revision 4 Attachment 6.14 (9 of 12) 230
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION INGESTION MILK MKQ-5 (Westbank) located at the Webre's house, 5.0 NW just across LA 18 from river marker, at the eastern end of Edgard.
MKQ-45* (Eastbank) located off of I-12 in Denham 42 NW ,
Springs. Take LA 3002 south of LA 1034 I then right to LA 1032. Turn left and go to farm 1 mile on the right.
1 MKQ-1 (Westbank) 1.0 miles west of Watertwd 3 1.0 NW !
at the corner of River Road and l Post Street in Killona.
l EISH FH-1* Upstream of the plant intake structure. N/A N/A FH-2 Downstream of the plant discharge structure. N/A N/A
- DENOTES CONTROL LOCATIONS N/A - Not Applicable for this sampling location.
l l
UNT-005-014 Revision 4 Attachment 6.14 (10 of 12) 231
SAMPLE LOCATION TABLE (Continued) l l
LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION ,
l WATERBORNE GWK-1 (Westbank) Located at 40 Arpent Canal 0.5 SSW south of the plant. Access from LA 3127 i through LP&L Gate 92 which is at the l Waterford-3 Training Center. The canal is northwest of the shell access road / l railroad track intersection. I DWG-2 (Westbank) Located at the Union Carbide 2.0 SE SWG-2 drinking water canal. Access from LA 3142 through Gate 28.
SHWE-3 (Westbank) Located at the Foot Ferry 3.0 E Landing off of LA 18 in Taft.
SHWK-1 (Westbank) Located at 40 arpent canal 0.5 SSW south of plant. Access thru LP&L gate 92 off of LA 3127.
DWE-5 (Eastbank) Located at the St. Charles 4.5 E SWE-5 Parish Waterworks off of River Road (LA 48) near New Sarpy.
DWP-7* (Westbank) Located at the St. John Parish 6.5 WNW SWP-7* Waterworks off of LA 18 in Edgard. _
- DEN 0TES CONTROL LOCATIONS i
UNT-005-014 Revision 4 Attachment 6.14 (11 of 12) 232
SAMPLE LOCATION TABLE (Continued)
LOCATION LOCATION MILES FROM SECTOR I NUMBER DESCRIPTION PLANT DIRECTION I SANITARY SYSTEM SWR-1** Sewage lift station NW of MSB between 0.1 R Protected Area Fence and the river road i 0.1 miles from the plant
- Sampling requirements is not derived directly from REMP requirements therefore results will not appear in the annual report however; it represents another possible environmental interface with the plant.
1 UNT-005-014 Revision 4 Attachment 6.14 (12 of 12) 233
. . . . - - . . . . ~
SECTOR AND ZONE DESIGNATORS FOR RADIOLOGICAL SAMPLING AND MONITORING POINTS SECTOR NOMENCLATURE ZONE NOMENCLATURE CENTERLINE OF SECTOR IN DEGREES TRUE NORTH 22 1/2 NILES FROM FRON FACILITY SECTOR FACILITY ZONE O & 360 *A N 0-1 1 22 1/2 B NNE l-2 2 45 C NE 2-3 3 67 1/2 D ENE 3-4 4 90 E E 4-5 5 112 1/2 F ESE 5-6 6 135 G SE 6-7 7 157 1/2 H OR SSE 7-8 8 180 J S 8-9 9 202 1/2 K SSW 9-10 10 225 , L SW 10-15 15 247 1/2 M WSW 15-20 20 270 N W 20-25 25 292 1/2 P WNW 25-30 30 315 Q NW 30-35 35 337 1/2 R NNW 35-40 40 40-45 45 45-50 50 AREA SEGMENT - An area is identified by a Sector and Zone designator. Thus, area N-1 is that area which lies between 348 3/4 and 11% degrees.true north from the facility out to a radius of I mile. Area G-4 would be that area between 123 3/4 to 146% degrees and the 3- and 4-mile arcs from the facility. For Airborne, Ingestion (milk), ~
and Food Products pathways, the sector designator will be preceded by acronyms AP, NK, and FP, respectively.
- The letters I and 0 have been omitted from these sector designators so as to eliminate possible confusion between letters and numbers.
UNT-005-014 Revision 4 Attachment 6.15 (1 of 1) 234
l REMP SAMPLES WITHIN 2 MILES OF WATERFORD 3
,mmnrmn.v. i 9g. &R Raniksippihk ..]; ~~~~'~.... ..-- W9 .h/kg
- . . ga gw -s .M e 30 .
9 g.$$
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. AP AIR PARTICLE. LODINE
. ~ b?p , 'i ' ! /F DW DRINKING / SURFACE WATER K-1
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/ GW FH GROUND WATER FISH DW42
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/ FP
-- PARISH BOUNDRIES FOOD PRODUCT
./
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H J HAHNVILLE UNT-005-014 Revision 4 Attachment 6.16 (1 of 1) 235
l REMP SAMPLES WITHIN 10 MILES OF WATERFORD 3l s s.
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.m .eedam UNT-005-014 Revision 4 Attachment 6.18 (1 of 1) 237
JOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi f actors f or Acult age grouD Oy nuclide.
watertoro Steam Electric Station Pathway : Inhalation Pathway for Pi Nuclide Organ Oose Conversion factors i
Bone Liver T. Body Thyroid Kidney Lung Cl*LLI H3 0.00e+00 1.26e+03 1.26e+03 1.26e+03 1.26e+03 1.26e+03 1.26c03 C 14 1.82e+04 3.41e+03 3.41e+03 3.41e+03 3.41e+03 3.41e+03 3.41e+03 Na 24 1.02e+04 1.02e+04 1.02e+04 1.02e+04 1.02e+04 1.02e*04 1.02e+04 P 32 1.32e+06 7.71e+04 5.01e+04 0.00e+00 0.00e+00 0.00e+00 8.64e+04 ;
Cr 51 0.00e+00 0.00e+00 1.00e+02 5.95e+01 2.28e+01 1.44e+04 3.32e+03 i Mn 54 0.00e+00 3.96e+04 6.30e+03 0.00e+00 9.84e+03 1.40e+06 7.74e+04 ;
Mn-56 0.00e+00 1.24e+00 1.83e 01 0.00e+00 1.30e+00 9.44e03 2.02e+04 i Fe 55 2.46e+04 1.70e+04 3.94p03 0.00e+00 0.00e+00 7.21e+04 6.03e03 I Fe-59 1.18e+04 2.78e+04 1.06e+04 0.00e+00 0.00e+00 1.02e+06 1.88e+05 :
Co-58 0.00e+00 1.58e+03 2.07e+03 0.00e*00 0.00e+00 9.28e+05 1.06e+05 I co 60 0.00e+00 1.15e+04 1.48e+04 0.00e+00 0.00e+00 5.97e+06 2.85e+05 N1 63 I 4.32e+05 3.14e*04 1.45e*04 0.00e+00 0.00e00 1.78e+05 1.34e+04 1 Ni+65 1.54e+00 2.10e-01 9.12e 02 0.00e+00 0.00e+00 5.60e+03 1.23e+04 Cu-64 0.00e+00 1.46e+00 6.15e 01 0.00e+00 4.62e+00 6.78e+03 4.90e+04 Zn 65 3.24e04 1.03e+05 4.66e+04 0.00e+00 6.90e+04 8.64e+05 5.34e04 )
............................................................................... 1 Zn 69 3.46e-02 6.51e 02 4.52e-03 0.00e+00 4.22e-02 9.20e+02 1.63e+01 Br 83 0.00e+00 0.00e+00 2.41e*02 0.00e+00 0.00e+00 0.00e+00 2.32e+02 tr 84 0.00e+00 0.00e+00 3.13e+02 0.00e+00 0.00e+00 0.00e+00 1.64e 03 Br.85 0.00e+00 0.00e+00 1.28e01 0.DCe+00 0.00e+00 0.00e+00 0.00e+00 Rb 86 0.00e+00 1.35e+05 5.90e+04 0.00e+00 0.00e+00 0.00e 00 1.66e+04 Rb 88 0.00e+00 3.87e+02 1.93e02 0.00e+00 0.00e+00 0.00e+00 3.34e 09 Ab-89 0.00e+00 2.56e02 1.70e+02 0.00e+00 0.00e+00 0.00e+00 9.28e 12
$r-89 3.04e+u5 0.00e+00 8.72e+03 0.00e+00 0.00e+00 1.40c 06 3.50e+05 Sr 90 9.92e+07 0.00e+00 6.10e+06 0.00e+00 0.00e+00 9.60e+06 7.22e+05 Sr 91 6.19*01 0.00e+00 2.50e00 0.00e+00 0.00e+00 3.65e+04 1.91e+05 Sr 92 l 6.74e+00 0.00e+00 2.9ta 01 0.00e+00 0.00e00 1.65e+04 4.30e+04 Y 90 2.09e+03 0.00e+00 5.61e+01 0.00e+00 0.00e+00 1.70e+05 5.06e05 Y 91 4.62e+05 0.00e+00 1.24e+04 0.00e+00 0.00e+00 1.70e+06 3.85e+05 Y 91m 2.61e.01 0.00e+00 1.02e 02 0.00e+00 0.00e+00 1.92e+03 1.33e+00 Y 92 1.03e+01 0.00e+00 3.02e 01 0.00e+00 0.00e+00 1.57e+04 7.35e+04 Conversion f actors are in units of area /yr per uCl/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.19 (1 of 27) 238
l l
00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi f actors for Adult age group cy nuclide.
Waterford Steam Electric Station.
Pathway : Inhaletion Pathway for Pi Nuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kieey Lung GI LLI Y 93 Zr 95 9.44 e01 0.00e+00 2.61e+00 0.00e+00 0.00e+00 4.85e+04 4.22e+05 Zr 97 1.07e+05 3.44e+06 2.33e+04 0.00c00 5.42e+06 1.77e 06 1.50e+05 9.68e+01 1.96e+01 9.04e*00 0
.......................................... 00e+00 2.97e+01 7.87e+04 5.23e+05 Nb 95 Mo 99 1.41e+06 7.82e*03 4.21e+03 0.00e+00 7. 74e+03 5.05c05 1.04e+05 ic 101 0.00e+00 1.21e+02 2.30e+01 0.00e+00 2.91e+02 9.12e+04 2.48e+05 4.18e.05 6.02e 05 5.90e M
........................................ 0.00e+00 1.08e-03 3.99e*02 1.09e 11 Tc-99m Ru 103 1.03e 03 2.91e 03 3.70e-02 0.00e+00 4.42e 02 7.64e02 4.16e+03 Ru 105 1.53e+03 0.00e+00 6.58e+02 0.00e+00 5.83e+03 5.05e+05 1.10e+05 7.90e 01 0.00e 00 3.11e 0 0.00e00 1.02e+00 1.10e+06 4.82e+06
......................................1 Au-106 ........................................
As 110m 6.91e+06 0.00e+00 8.72e+03 0.00e+00 1.34e+05 9.36e+06 9.12e+05 !
1.08e+04 1.00e+06 5.94e*03"0.00e+00 1.97e+06 4.63e+06 3.02e+05 Te 125m 3.42e+03 1.58e+03 4.67e+0
..................................... 2 1.05e+03 1.24e06 3.14e+05 7.06e+06 Te 127 Te*127m 1.40e+00 6.42e 01 3.10e-01 1.06e+00 5.10e+00 6.51e+03 5.74e+06 Te 129 1.26e*M 5.77e+03 1.57e+03 3.29e03 4.58e+06 9.60e+05 1.50e+05 4.98e.02 2.39e*02 1.24
...................................e-02 3.90e 02 1.87e 01 1.94e+03 1.57e+02 Te*129m Te*131 9.76e+03 4.67e+03 1.58e*03 3.44e+03 3.66e*06 1.16e+06 3.83e+05 Te 131m _1.11e*02 5.95e-03 3.59e 03 9.36e*03 4.37e.02 1.39e*03 1.84e+01 6.99e+01 4.36e+01 2.90e+
.................................... 01 5.50e+01 3.09c02 1.46e*05 5.56e*05 Te-132 1 130 2.60e+02 . 15e+02 1.62e+02 1.90e+02 1.46e+03 2.88e+05 5.10e+05 1 131 4.58e03 1.34e06 5.28e+03 1.14e+06 2.09e*06 0.00e+00 7.69e+03 2.52e+06 3.58e06 2.05e+06 6.13e+06 0.00e+00 6.28e+03
.........................................1.19e+07 1 132 .....................................
1 133 1.16e+03 3.26e+03 1.16e*03 1.14e+05 5.18e03 0.00e 00 4.06e02 t 134 8.64e+03 1.48e+06 4.52e+03 2.15e+06 2.58e+06 0.00e+00 8.88e+03 i 6.64e+02 1.73e*03 6 2.98e+06 2.75e+03 0.00e00 1.01e+00
! ................................ 15e+02 ..............................................
l 135 Ca*134 2.68e+03 6.98e03 2'57e+03 4.48e+05 1.11e+06 0.00e00 5.25e+03 Ca.136 3.73e+05 8.48e*05 7.28e+05 0.00e+00 2.80e+05 9.76e+06 1.04e+06 3.90e06 1.46e+05 1.
l
................................ 1De+05 0.00e+00 8.56ce4 1.20e06 1.17e04 Ca.137 Ca*138 4.78e+05 6.21e+05 4.28e+05 0.00e+00 2.22e+05 7.52e+06 8.40e+03 8e.139 3.31e+02 6.21e+02 3.24e*02 0.00e+00 4.80e+02 4.86e+01 1.86e 03 l
9.36e 01 6.66e-M 2.74e 02 0.00e+00 6.22e M 3.76e+03 8.96e+02 Conversion factors are in units of aremvyr per uct/ cele meter.
i i
UNT-005-014 Revision 4 Attachment 6.19 (2 of 27) 239 1
l 1
DOSE FACTORS DUE TO RADIONUCLIDES l OTHER THAN N0BLE GASES: P j
l I l
d 4
Pi factors for Adult age group by tuclice.
Watertora steam Electric Station Pathway 3 inhalation Pathway for Pi i
i i
- Nuclide Organ Oose Conversion factors i i
d Bone Liver T. Body Thyroid Kidney Lme GI LLI l
3 Ba 140 3.90e+04 4.90e+01 2.57e+03 0.00e+00 1.67e+01 1.27e+06 2.18e+05--
Ba 141 l
- 1.00e 01 7.53e 05 3.36e 03 0.00e00 7.00e 05 1.94e+03 1.16e 07 i Ba 142 2.63e 02 2.70e 05 1.66e 03 0.00e+00 2.29e 05 1.19e+03 1.57e 16 La-140 3.44e+02 1.74e+02 4.58e+01 0.00e+00 0.00e+00 1.36e+05 4.58e+05 La 142 6.83e 01 3.10e 01 7.72e-02 0.00e+00 0.00e+00 6.33e+03 2.11e+03 Co 141 1.99e+04 1.35e+04 1.53e+03 0.00e 00 6.26e03 3.62e+05 1.20e+05 1
............................................................................... 1 Co 143 1.86e+02 1.18e+02 1.53e+01 0.00e+00 6.08e*01 7.98e 04 2.26e+05 l Co-144 3.43e+06 1.43e+06 1.84e+05 0.00e+00 0.00e+00 7.78e+06 8.16e+05 Pr 143 9.36e+03 3.75e+03 4.64e+02 0.00e00 2.16e+03 2.81e+05 2.00e+05 Pr 144 3.01e 02 1.25e 02 1.53e-03 0.00e*00 7.05e-03 1.02e+03 2.15e 08 Wd 147 5.27e+03 6.10e+03 3.65e+02 0.00e+00 3.56e+03 2.21e+05 1.73e+05 u.187 8.48e+00 7.08e+00 2.48e+00 0.00e*00 0.00e+00 2.90e+04 1.55e+05 No 239 2.30e+02 2.26e+01 1.24e+01 0.00e+00 7.00e+01 3.76e04 1.19e+05 Conversion factors are in units of mren/yr per uC1/c eic meter.
UNT-005-014 Revision 4 Attachment 6.19 (3 of 27) 240
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: P4 i
Pi factors for Teen age group Dy nuclide.
Waterford Steam Electric Station Pathway : Inhalation Pathway for Pi Nuclide Organ Dose Conversion factors Bone Liver T. Sody Thyroid Kl@ey Lung GI LLI H3 I C 14 0.00e+00 1.27e+03 1.27e*03 1.27e+03 1.27e*03 1.27e+03 1.27e+03 Sa 24 2.00e+04 1.38e+06 1.384.87e+03
+06 1. 4.87e+03 4.87e+03 4.87e+03 4.87e+03 4.87e+0i 1.38e+06 1.38e+06 1.38e+06 1.38e+04
................................38e+M...........................................
P 32 ..
l Cr 51 1.89e+% 1.10e*05 7.16e+04 0.00e+00 0.00e+00 0.00e+00 9.28e+06 !
Mn-54 0.00e+00 0.00e+00 0.00e+00 5.11e+06 8 1.35e+02 7.50e+01 3.07e+01 2.10e+06 3.00e+0 Mn.56 0.00e+00 1.27e+06 1.98e+M 6.68e+ 06 40e+03...........................................
Fe-55 0.00e+00 1.70e+00 2.52e.01 0.00e*00 1.79e+00 1.52e+04 5.74e+04 Fe.59 3.34e+M 2.38e+M 5.54e+03 0.00e+00 0.00e+00 1.24e+05 6.39e+0 1.59e+01 3.70e+06 0.00e+00 0.00e+00 1.53e+06 1.78e+05
...............................1.43e+M.........................................
Co 58 ......
\
Co 60 0.00e+00 2.07e+03 2.78e+03 0.00e+00 0.00e*00 1.34e+06 9.52e+06 j Ni 63 0.00e+00 5.80e+05 1.51e+06 1.98e*06 0.00e+00 0.00e+00 8.72e+06 2.59e+05 4.34e+0 '
1.98e+06 0.00e*00 0.00e+00 3.07e*05 1 62e+06
............................6...........................................
Ni 65 ......
Cu-66 2.18e+00 2.93e.01 1.27e 01 0.00e+00 0.00e+00 9.36e+03 3.67e+06 2n.65 0.00e*00 3.86e+06 2.03e+00 8.48e.01 0.00e+00 6.41e+00 1.11e+06 6.14e+06 1.34e+0 6.24e+06 0.00e+00 8.66e+06 1.24e+06 4 66e+06 1
............................5...........................................
Zn.69 ......
i Br 83 4.83e-02 9.20e.02 6.46e-03 0.00e+00 6.02e.02 1.58e+03 2.85e+02 '
Br*84 0.00e+00 0.00e+00 3.44e*02 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e*00 0.00e+0 0.00e+00 0.00e*00 0.00e*00 0.00e+00
............................0 Sr.85 4.33e*02............................................
ab 86 0.00e*00 0.00e+00 1.83e+01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ab 88 0.00e*005.46 0.00e+00 1.90e+05 8.60e+06 0.00e+00 0.00e+00 0.00e*00 1.77e+06 2.72e+02 0.00e+00 0.00e+00 0.00e+ 00 2.92e-05
.........................e+02.........................................
ab-89 ............
$r*89 0.00e+00 3.52e+02 2.33e+02 0.00e+00 0.00e+00 0.00e*00 3.38e.07 sr.90 4.34e*05 1.08e+08 0.000.00e+00 1.25e*M 0.00e+00 0.00e+00 2.42e+06 3.71e+05 6.68e+06 0.00e+00 0.00e+00 1.65 7.65e+05
.........................e+00....:...................................e+07
$r 91 ..............
$r 92 8.80e+01 0.00e+00 3.51e+00 0.00e+00 0.00e+00 6.07e+06 2.59e+0 Y 90 9.52e+00 2.98e*03 0.00e+00 0.00e+ 4.06e.01 0.00e+00 0.00e+00 2.74e+06 1.19e+05 0.00e*00 0.00e+00 2.93e+05 5.59e+05 Y*91 00 '8.00e+01........................................
Y.91a 6.6te+05 0.00e+00 1.77e*M 0.00e+00 0.00e+00 2.96e+06 4.09e+05 Y 92 3.70e.01 0.00e+00 1.42e.02 0.00e+00 0.00e+00 3.20e+03 3.02e+01 1.47e+01 0.00e+00 6.29e.01 0.00e+00 0.00e+00 2.68e+06 1.65e+05 Cameralen factere are in mits of aremryr per uct/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.19 (4 of 27) 241
1 i
l DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: P4 Pi factors for Teen age group cy nuclide.
Waterford Steam Electric Station Pathway : Inhetetton Pathway for Pt Nuclice organ Dose Conversion factors Bone Liver T. Body Thyroid Kidiey Lung f.! LLI Y-93 Zr 95 1.35e+02 0.00e+00 3.72e+00 0.00e+00 0.00e+00 8.32e+04 5.79e+05 1.46e+05 4.58e+04 3.15e+04 0.00e+00 6. 74e+04 2.69e+06 1.49e+05 Zr-97 1.38e+02 2.72e+01 1.26e+01 0.00e+00 4
.................................................... 12e+01 ..........................
1.30e+05 6.30e+05 Wb-95 Mo-99 1.86e+04 1.03e+04 5.66e+03 0.00e+00 1.00e+04 7.51e+05 9.68e+04 Tc 101 0.00e+00 1.69e+02 3.22e+01 0.00e+00 4.11e+02 1.54e+05 2.69e05 5.92e 05 8.40e 05 8.24e 04 0.00e+00 03 6.67e+02 8.72e 07
...................................................1.52e Tc 99m Ru 103 1.38e 03 3.86e-03 4.99e-02 0.00e+00 5.76e 02 1.15e+03 6.13e+03 Ru-105 2.10e03 0.00e+00 8.96e+02 0.00e+00 7.43e+03 7.83e+05 1.09e+05 1.12e+00 0.00e+00 4.34e 01
........................................ 0.00e+00......................................
1.41e+00 1.82e+04 9.04e+04 Ru 106 A9*110m 9.84e+04 0.00e+00 1.24e+04 0.00e+00 1.90e+05 1.61e+07 9.60e+05 1.38e+04 1.31e04 7.99e+03 0.00e+00 2.50e+04 6.75e+06 2.73e+05 Te 125m 4.88e03 2.24e+03 6.67e+0
..................................... 2 1.40e+03 0.00e+00 5.36e+05 7.50e+04 Te 127 Te 127m 2.01e+00 9.12e 01 4.42e 01 1.42e*00 7.28e+00 1.12e+04 8.08e+04 Te-129 1.80e+04 8.16e+03 2.18e+03 4.38e+03 6.54e+04 1.66e+06 1.59c05 7.10e 02 3.38e 02 1.76e 0
..................................... 2 5.18e.02 2.66e*01 3.30e+03 1.62e+03 Te 129m Te 131 1.39e+04 6.58e+03 2.25e+03 4.58e+03 5.19e+04 1.98e+06 4.05e+05 Te 131m 1.58e 02 8.32e 03 5.04e 03 1.24e 02 6.18e-02 2.34e+03 1.51p01 9.84e+01 6.01e+01 4.02 e0
......................................1 Te 132 7.25e+01 4.39e+02 2.38e+05 6.21e+05 t 130 3.60e+02 2.90e+02 2.19e+02 2.46e+02 1.95 e03 4.49e+05 4.63e+05 1 131 6.24e+03 1.79e+04 7.17e+03 1.49e+06 2.75e+04 0.00e+00 9.12e03 3.54e+04 4.91e+04 2.64++04 8.40e+04 0.00e+00 6.49e+03
.........................................1.46e+07 1 132 .....................................
1 133 1.59e+03 4.38e03 1.58e03 1.51e+05 6.92e+03 0.00e+00 1.27e+03 1 134 1.22e+04 2.05e+04 6.22e+03 2.92e+06 3.59e+04 0.00e+00 1.03e+04 8.88e+02 2.32e+03 8.40e
.................................... 02 3.95e+04 3.66e+03 0.00e+00 2.04e+01 1 135 ca 134 3.70e+03 9.44e+03 3.49c03 6.21e+05 1.49e+04 0.00e+00 6.95e+03 cs 136 5.02e05 1.13e+06 5.49e+05 0.00e+00 3.75e+05 1.46e+05 9.76e+03 5.15e+04 1.94e+05 1.3Te+0
..................................... 5 0.00e+00 1.10e+05 1.78e+04 1.09e+04 Cs 137 Cs 138 6.70e05 8.48e+0S 3.11e+05 0.00e+00 3.04e+05 1.21e+05 8.48e+03 Be 139 4.66e+02 8.56e+02 4.46c02 0.00e+00 6.62e+02 7.87e+01 2.70e 01 1.34e+00 9.44e-04 3.90e 02 0.00e+00 8.88e 04 6.46e+03 6.45e+03 Conversion factors are in units of arenvyr per uCf/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.19 (5 of 27) 242 i
DOSE FACTORS DUE T3 RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi factors for Teen age group Oy nuclide.
l Waterford Steam Electric Station
) Pathway : Inhalation Pathway for Pi l
l Nuclide Or9an Oose Conversion Factors Bone Liver T. Booy Thyroic Kidney Lung GI LLI Ba 140 5.47e+04 6.70e+01 3.52e+03 0.00e+00 2.28e+01 2.03e+06 2.29e+05 Ba 141 1.42e-01 1.06e 04 4.74e 03 0.00e+90 9.84e 05 3.29e+03 7.46e-04 sa 142 3.70e-02 3.70e-05 2.27e 03 0.00e+00 3.14e-05 1.91e+03 4. 79e-10 La-140 4.79e+02 2.36e+02 6.26e+01 0.00e+00 0.00e+00 2.14e+05 4.87e+05 La 142 9.60e 01 4.25e-01 1.06e-01 0.00e+00 0.00e+00 1.02e+04 1.20e+04 co-141 2.84e+04 1.90e+04 2.17e+03 0.00e+00 8.88e+03 6.14e+05 1.26e+05 Co-143 2.66e*02 1.94e+02 2.16e+01 0.00e+00 8.64e*01 1.30e+05 2.55e+05 Co-144 4.89e+06 2.02e*06 2.62e+05 0.00e+00 1.21e*06 1.34e+07 8.64e+05 Pr-143 1.34e+04 5.31e+03 6.62e*02 0.00e+00 3.09e+03 4.83e+05 2.14e+05 Pr-144 4.30e 02 1.76e 02 2.18e-03 0.00e+00 1.01e 02 1.75e+03 2.35e 04 Nd 147 7.86e+03 8.56e+03 5.13e+02 0.00e*00 5.02e+03 3.72e+05 1.82e+05 W 187 1.20e+01 9.76e+00 3.43e+00 0.00e+00 0.00e+00 4.74e+04 1.77e+05 hp 239 3.38e+02 3.19e*01 1.77e+01 0.00e+00 1.00e+02 6.49e+04 1.32e+05 Conversion factors are in smits of acerfyr per uct/ciele meter.
l l
l l
UNT-005-014 Revision 4 Attachment 6.19 (6 of 27) 243
l
)
DOSE FACTORS DUE TO RAGiofiUCU DES OTHER THAN N0BLE GASES: Pj Pi f actors for Child age group by ructide.
Waterford Steas Electric Station Pathway : Inhalation Pathway for Pi Nuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kichey Lung GI LLI H3 0.00e+00 1.12e+03 1.12e+03 1.12e+03 1.12e+03 1.12e+03 1.12e+03 C 14 3.59e+04 6. 73e+03 6.73e+03 6.73e+03 6.73e+03 6.73e+03 6.73e+03 Na 24 1.61e+04 1.61e+04 1.61e+04 1.61e+04 1.61e+04 1.61e+04 1.61e+04 P.32 2.60e+06 1.14e+05 9.88e+04 0.00e+00 0.00e+00 0.00e+00 4.22e+04 cr 51 0.00e+00 0.00e+00 1.54e+02 8.55e+01 2.43e01 1.70e+04 1.08e+03 Mn 54 0.00e+00 4.29e+04 9.51e+03 0.00e+00 1.00e+04 1.58e+06 2.29e+04 Mn-56 0.00e+00 1.66e+00 3.12e-01 0.00e+00 1.67e00 1.31e+04 . 1.23e+05 Fe 55 4.74 e04 2.52e+04 7.77e+03 0.00e+00 0.00e+00 1.11e+05 2.87e+03 Fe 59 2.07e+04 3.34e*04 1.67e+04 0.00e+00 0.00e+00 1.27e+06 7.07e+04 Co 58 0.00e+00 1.77e+03 3.16e+03 0.00e+00 0.00e+00 1.11e+06 3.44e+04 co-60 NI.63 0.00e+00 1.31e+04 2.26e+04 0.00e 00 0.00e+00 7.07e+06 9.62e+04 8.21e+05 4.62e+04 2.80e+04 0.00e+00 0.00e 00 2.75e+05 6.33e+03 Ni 65 cu 64 2.99e00 2.96e.01 1.64e-01 0.00e+00 0.00e*00 8.18e03 8.40e04 0.00e+00 1.99e+00 1.07e+00 0.00e+00 6.03e+00 9.58e03 3.67e+06 Zn 65 4.26c+04 1.13e+05 7.03e+04 0.00e+00 7.14e+04 9.95e+05 1.63
...........................................................................e+06 Zn.69 Br 83 6.70e 02 9.66e.02 8.92e 03 0.00e+00 5.85e 02 1.42e+03 1.02e+06 Br.84 0.00e+00 0.00e+00 4.76e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.48e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br 85 Rb 86 0.00e+00 0.00e+00 2.53e+01 0.00e00 0.00e00 0.00e+00 0.00e+00 ab 88 0.00e+00 1.98e05 1.14e+05 0.00e+00 0.00e+00 0.00e+00 7.99e+03 0.00c00 5.62e+02 3.66e+02 0.00e+00 0.00e+00 0.00e+00 1 Rb 89 72 e01 sr.89 0.00e+00 3.(5e+02 2.90e+02 0.00e00 0.00e 00 0.00e+00 1.89c00
$r.90 5.99e+05 0.00e+00 1.72e+04 0.00e+00 0.00e+00 2.16e+06 1.67e+05 1.01e+08 0.00c00 6.44e+06 0.00e 00 0.00e+00 1.48e+07 3 Sr 91 43e+05......
$r.92 1.21e+02 0.00e+00 4.59e+00 0.00e00 0.00e+00 5.33e+04 1.74e+05 Y-90 1.31e+01 0.00c00 5.25e-01 0.00e+00 0.00e+00 2.40e+04 2.42e05 4.11e+03 0.00e+00 1.11e02 0.00e+00 0.00e+00 2.62c05 2 Y 91 68e05......
Y 91m 9.14e+05 0.00e+00 2.44e+04 0.00e+00 0.00e00 2.63e+06 1.84e+0S Y 92 5.07e.01 0.00e+00 1.84e.02 0.00e+00 0.00c00 2.81e+03 1.72e+03 2.03c01 0.00c 00 5.81e.01 0.00e+00 0.00e 00 2.39e+04 2.39c05 Conversion f actors are in mits of arem/yr per uct/ceic meter.
UNT-005-014 Revision 4 Attachment 6.19 (7 of 27) 244
l DOSE rACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj l
l t
l l
Pi factors for Child age group cy nuclide.
waterford steam Electric Station l
Pathway : Inhalation Pathway for Pi l
l l
Nuclide Organ Dose Conversion factors Bone Liver T. Sody Thyroid Kidney Lung CI.LLI Y-93~ 1.86e+02 0.00e00 5.11e00 0.00e+00 0.00e+00 7.44e+06 3.88e+05 Zr.95 1.90e+05 4.18e+04 3.70e+04 0.00c00 5.96e+06 2.23e+06 6.11e+04 Zr 97 1.88e+02 2.72e+01 1.60e+01 0.00e+00 3.89e+01 1.13e+05 3.51e+05 Nb.95 2.35e+04 9.18e+03 6.55e+03 0.00e+00 8.62e+03 6.14e+05 3.70e+04 Mo.99 0.00e+00 1.72p02 4.26e+01 0.00e+00 3.92e+02 1.35e+05 1.27e+05 Tc 101 8.10e 05 8.51e.05 1.08e 03 0.00e+00 1.45e.03 5.85e+02 1.63e+01 i 1
Tc 99m 1.78e-03 3.48e 03 5.77e 02 0.00c00 5.07e.02 9.51e+02 4.81e+03 '
Ru.103 2.79e+03 0.00e 00 1.07e+03 0.00e+00 7.03e+03 6.62e+05 4.48e+06 Ru.105 1.53e+00 0.00e+00 5.55e.01 0.00e+00 1.34e+00 1.59e+06 9.95e+06 Ru-106 1.36e+05 0.00e+00 1.69e+06 0.00e+00 1.86e+05 1.43c07 4.29e+05 As.110m 1.69e06 1.14e+06 9.14e+03 0.00e+00 2.12e*% 5.48e+06 1.00e*05 Te.125m 6.73e+03 2.33e+03 9.14e+02 1.92e*03 0.00e+00 4.77e+05 3.38e+04 Te.127 2.77e+00 9.51e 01 6.11e.01 1.96e+00 7.07e+00 1.00e+06 5.62e+04 Te 127m 2.49e+04 8.55e+03 3.02e*03 6.07e+03 6.36e+06 1.48e06 7.14e06 Te.129 9.77e.02 3.50e 02 2.38e.02 7.14e-02 2.57e-01 2.93c03 2.55e06 Te-129m 1.92e+06 6.84
- 05 3.04e+03 6.33e+03 5.03e+06 1.76e+06 1.82e+05 Te.131 2.17e.02 8.44e03 6.39e.03 1.70e-02 5.88e.02 2.05e+03 1.33e+03 Te 131m 1.34*02 5.92e+01 5.07e+01 9.77e*01 4.00e+07 2.06e+05 3.08c05 -
Te 132 4.81e+02 2.72e+02 2.63e+02 3.17e+02 1.77e+03 3.77e+05 1.38e+05 1 130 8.18e+03 1.64e+06 8.44e+03 1.85e+06 2.45e+06 0.00c00 5.11e+03 1 131 4.81e+06 4.81e+06 2.73e+04 1.62e+07 7.88e+06 0.00e+00 2.84e*03 1 132 2.12e+03 4.07e+03 1.88e+03 1.94e+05 6.25e+03 0.00e+00 3.20e+03 1 133 1.66e+06 2.03e+06 7.70e+03 3.85e+06 3.38e+06 0.00e+00 5.68e+03 1 134 1.17e*03 2.16e+03 9.95e+02 5.07e+06 3.30e03 0.00e00 9.55e+02 1-135 4.92e+03 8.73e+03 4.14e+03 7.92e+05 1.34e+06 0.00e+00 4.44e*03 Cs 134 6.51e+05 1.01e+06 2.25e+05 0.00e+00 3.30e+05 1.21e+05 3.85 c 03 Ca.136 6.51e+06 1.71e+05 *1.16e+05 0.00e+00 9.55e+06 1.65e+06 4.18e+03 Cs 137 9.06e+05 8.25e+05 1.28e+05 0.00e+00 2.82e+05 1.04e+05 3.62e+03 Cs 138 6.33e+02 8.40e+02 5.55e+02 0.00e00 6.22e+02 6.81e+01 2.70e+02 8e.139 1.86e+00 9.84e.06 5.37e 02 0.00e+00 8.62e.04 5.77e+03 5.77e+06 Convereien f acters are in mits of area /yr per uti/ceic meter.
UNT-005-014 Revision 4 Attachment 6.19 (8 of 27) 245
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: ?j Pi factors for Child age group by nuclide.
Watertord Steam Electric Station Patngty : Inhalation Pathway for Pi Nuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kidney Lung GI LLI 1
l Ba 140 7.40e 04 6.48e01 4.33e+03 0.00e+00 2.11e+01 1. 74e+06 1.02e+05 !
Be 141 1.96e-01 1.09e.04 6.36e 03 0.00e+00 9.47e 05 2.92e+03 2.75 e+02 Ba-142 5.00e-02 3.60e.05 2.79e 03 0.00e+00 2.91e 05 1.64e+03 2.74e+00 !
............................................................................... 1 Lc 140 6.44e+02 2.25 e+02 7.55e+01 0.00e00 0.00e+00 1.83e05 2.26e+05 La-142 1.29e+00 4.11e 01 1.29e-01 0.00e+00 0.00e+00 8.70e+03 7.58e+04 I co 141 3.92e04 1.95e+04 2.90e+03 0.00e+00 8.55e+03 5.44c05 5.66e04 l Co.143 3.66e+02 1.99e+02 2.87e+01 0.00e00 8.36e+01 1.15e+05 1.27e+05 Co-144 6.77e+06 2.12e+06 3.61e+05 0.00e+00 1.17e+06 1.20e+07 3.88e+05 Pr 143 1.85e+04 5.55e+03 9.14e+02 0.00e+00 3.00e+03 4.33e+05 9.73e+04 Pr-144 5.96e-02 1.85e 02 3.00e 03 0.00e+00 9.77e.03 1.57e03 1.97e+02 Nd 147 1.08e+0+ 8.73e+03 6.81e+02 0.00e00 4.81e+03 3.28c05 8.21e+04 W-187 1.63e+01 9.66e+00 4.33e+00 0.00e+00 0.00e00 4.11e+04 9.10e+04 Np-239 4.66e+02 3.34e+01 2.35e+01 0.00e+00 9.73e+01 5.81e+04 6.40e+04 conversion f actors are in mits of aren/yr per uct/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.19 (9 of 27) 246
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pj Pi factors for fr M t age group by nuclide.
Waterford Steam C dctric Station Pathway : Inhaletion Pathway for PI Nuclide Organ Dose Conversion factors
+
Bone Liver T. Sody Thyroid Kidney Lung GI.LLI H.3 C-16 0.00e+00 6.47e+02 6.47e+02 6.47e+02 6.47e+02 6.47e+02 6.47e+02 2.65e+06 5.31e+03 5.31e+03 5.31e+03 5.31e+03 5.31e+03 5.31e+03 Na*24 1.06e+06 1.06e+06 1.06e+06 1.06e+06 1.06e+06 1.06e+04 1.06e+06 P.32 2.03e+06 1.12e+05 7.74e+04 0.00e+00 0.00e+00 0.00e+00 1.61e+06 Cr.51 0.00e+00 0.00e+00 8.95a+01 5.75e+01 1.32e+01 1.28e+06 3.57e+02 Mn*54 0.00e+00 2.53e+04 4.98e*03 0.00e+00 6.98e+03 1.00e*06 7.06e*03 Mn.56 Fe*55 0.00e*00 1.54e*00 2.21e 01 0.00e+00 1.10e+00 1.25e+06 7.17e*06 Fe.59 1.97e+06 1.17e+04 3.33e+03 0.00e+00 0.00e*00 8.69e+06 1.09e+03 1.36e+06 2.35e*06 9.68e+03 0.00e+00 0.00e+00 1.01e+06 2.48e+06 Co.58 Co.60 0.00e+00 1.22e*05 1.82e+03 0.00e+00 0.00e+00 7.77e+05 1.11e+06 Wl.63 0.00e+00 8.02e+03 1.18e*06 0.00e+00 0.00e+00 4.51e+06 3.19e*06 3.39e*05 2.04e+06 1.16e+06 0.00e*00 0.00e+00 2.09e+05 2.42e+0 Wl.65 3.
Cu 66 2.39e+00 2.86e.01 1.23e-01 0.00e*00 0.00e*00 8.12e*03 5.01e+06 2n-65 0.00e+00 1.88e+00 7.74e-01 0.00e+00 3.98e*00 9.30e+03 1.50e+06 1.93e+06 6.26e+06 3.11e+06 0.00e+00 3.25e+06 6.47e+05
.......................................................................5.14e+06 2n.69 Br.83 5.39e.02 9.67e-02 7.18e.03 0.00e+00 4.02e.02 1.47e+03 1.32e+06 tr.84 0.00e+00 0.00e+00 3.81e+0? 0.00e+00 0.00e*00 -0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.00e+02 0.00e+00 0.00e+00 0.00e+00 0 Br.85 00e+00 Rb-86 0.00e+00 0.00e+00 2.04e+01 0.00e+00 0.00e+00 0.00e+00 0.00ee00 Rb-88 0.00e+00 1.90e*05 8.82e+06 0.00e*00 0.00e+00 0.00e+00 3.04e+03 0.00e+00 5.57e+02 2.87e+02 0.00e+0 0.00e+00 0.00e+00 3.39e+02 Rb 89 0...............................
Sr-89 0.00e+00 3.21e+02 2.06e*02 0.00e+00 0.00e+00 0.00e+00 6.82e+01 Sr.90 3.98e+05 0.00e*00 1.14e+06 0.00e+00 0.00e+00 2.03e+06 6.40e+06 6.09e*07 0.00e+00 2.59e+06 0.00e*00 0
.................................................... 00e+00 ..........................
1.12e+07 1.31e+05 Sr-91 Sr 92 9.56e+01 0.00.3*00 3.46e*00 0.00e+00 0.00e+00 5.26e+06 7.34e*0e Y.90 1.05e*01 0.00c+00 3.91e.01 0.00e+00 0.00e+00 2.38e+06 1.40e+05 3.29e*03 0.00e*00 852e+01 0.00e+0
............................................... 0 0.00e+00 2.69e+05 1.04e+05 Y-91 Y 91m 5.88e*05 0.00e+00 1.57e+06 0.00e+00 0.00e+00 2.65e+06 7.03e*06 Y 92 4.07e*01 0.00e+00 1.39e*02 0.00e+00 0.00e+00 2.79e+03 2.35e+03 1.66e*01 0.00e+00 4.61o.01 0.00e+00 0.00e+00 2.45e*06 1.27e+06 Conversion facters are in units of areevyr per uct/steic meter.
UNT-005-014 Revision 4 Attachment 6.19 (10 of 27) 247
00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: P:
Di factors for Infant ege grouo by nuclide.
Waterfora Steam Electric Statico l Pethway Inhalation Pathway for Pi Nuclide Organ Dose Conversion Factors Bone Liver T. Body Thyroid I:fdney Lung i
GI LLI i
Y-93 Zr-95 1.50e+02 0.00e+00 4.07e+09 0.00e+00 0.00e+00 7.64e+06 1.67e+05 Zr-97 1.15e+05 1.50e+02 2.79e+06 2.56e+01 1 2.03e+04 0.00e+00 3.11e+04 1.75e+06 2.17e+04 I Nb 95 0.00e+00 2.59e+01 1.10e+05 1.60e.05 17e+01............................................ .
s Mo 99 1.57e+04 6.63e03 3.78e+03 0.00e+00 4. 72e+03 4. 79e+05 1.27e+04 Tc 101 0.00e+00 1.65e+G2 3.23e+01 0.00e+00 2.65e+02 1.35e+05 4.87e+06 6.51e-05 8.23e-05 8
................................ 0.00e+00 9.79e-04 5.8&e+02 8.44e+02 12e.04...........................................
1 Tc 99m ..
j Ru.103 1.40e-03 2.88e-03 3.72e.02 0.00e+00 3.11e 02 8.11e+02 2.03e+03 i Ru-105 2.02e+03 0.00e00 1.22e+00 0.00e+00 4 6.79e+02 0.00e+00 4.24e*03 5.52e+05 1.61e+06 ;
Ru.106 0.00e*00 8.99e.01 1.57e*04 4.84e+06 10e.01........................................... ..
Ag.110m 8.68a+06 0.00e+00 1.09e+06 0.00e00 1.07e+05 1.16e+07 1.64e+05 fe.125e 9.98e+03 4.76e*05 7.22e+03 5.00e*03 0.00e+00 1.09e+06 3.67e+06 3.30e+04 1.99e0
........................... 3...........................................1.29e+06 6.58e+02 1.62e*03 0.00e+00 4.47e+05 Te.127 .......
Te 127m 2.23e+00 9.53e 01 4.89e-01 1.85e+00 4.86e+00 1.03e+06 2.44e+04 i fe 129 1.67e+06 7.88e.02 6.90e*03 2.07e*03 4.87e+03 3.75e06 1.31e+06 2.73e+06 3.47e-0 i 1.88e.02 6.75e-02 1.75e.01 3.00ce3 2.63e+04
............................2...................................... ...........
Te 129m 1.41c06 6.09e+03 2.23c03 5.47e*03 3.18e+04 1.68e+06 6.90e Te-131 Te-131m 1.74e.025.50 1.07e+02 8.22e-03 5.00e.03 1.58e 02 3.99e-02 2.06 e03 8.22e+03 i 3.63e*01 8.93e+0i 2.65e+02 1.99
...-,-...................e+01.........................................e+05 1.19e+05 '
fe 132 .............
I 130 3.72e+02 2.37e02 1.76e+02 2.79e+02 1.03e+03 3.40e+05 4.41e+M I 131 6.36e+03 1.39e04 5.57e+03 1.60e+M 1.53e+06 0.00e+00 1.99e+03 3.79e*06 4.64e
.......................... 1.96e+06 1.68e+07 5.18e+M 0.00e+0 06........................................ 0 1.06e43 1 132 ...........
I 133 1.69e+03 3.54e+03 1.26e+03 1.69c05 3.95e+03 0.00c00 1.90e03 1 134 1.32e+06 9.21e+02 1.8 1.92e+06 5.60e+03 3.56e+06 2.24e+06 0.00e+00 2.16e+03
....................... 6.65e+02 4.45e+06 2.09e+03 0 00c00 1.2?e+03 l 135 8e03........~............................. ...............c OP134 3.5ee+03 7.60e+03 2.77e03 6.96e+05 8.47e*03 0.00e+00 1.83e+03 Cs*136 5.96e+05 4.83c06 7.03e+05 1.35e* 7.Me+06 0.00e*00 1.90e+05 7.97e+06 1.33e+03 Cs-137 5.29e+M 0.00e*00 5.64e+04 1.18e+ 1.43e+03 05....................................... 06............
1 Cs 138 5.49e+05 6.12e+05 4.55e+06 0.00e00 1.72e+05 7.13eM 1.33e+03 84 139 5.05c02 7.81e02 3.98e+02 0.00e 00 4.10e+02 6.54e+01 8.76e+02 I 1.48e+00 9.86e.04 4.30. 02 0.00e+00 5.92e.04 5.95e+03 5.10e+M i
l Conversion factors are in mits of aren/yr per uCf/c2fc meter, r
l l l l
l UNT-005-014 Revision 4 Attachment 6.19 (11 of 27) l 248
l l
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi factors for infant age group cy nuctide.
Waterfore steam Electric Station Pathway : Inhalation Pathway for Pi l I l Nuclide 0 gen pogg Cg,nversion factors Bone Liver t. Body Thyroid Kidney Lung GI LLI j Ba-140 Ba 141 5.60e+04 5.60e+01 2.90e+03 0.00e+00 1.34*01 1.60e+06 3.84e+04 i Ba 142 1.57e 01 1.08e-04 4.97e 03 0.00e+00 6.50e 05 2.97e+03 4.75e03 3.9Be 02 3.30e-05 t.96e 03 0
.......................................... 00e+00 ....................................
1.90e 05 1.55e+03 6.93e+02 La 140 1 l La 142 5.05e+02 2.00e+02 5.15e+01 0.00e+00 0.00e+00 1.68e05 8.48
- 04 I co 141 1.03e+00 3.77e 01 9.04e 02 0.00e+00 0.00e+00 8.22e+03 5.95e+04 2.77e+% 1.67e+04 1.99
...................................e03 0.00e+00 5.25e+03 5.17e+05 2.16e+04 Co 143 Co 144 2.93e+02 1.93e+02 2.21e+01 0.00e+00 5.64e+01 1.16e+05 4.97e+04 Pr 143 3.19e06 1.21e+06 1.76e+05 0.00e+00 5.38e+05 9.84e+06 1.48e+05 1.40e M 5.24e+03 6.99e+ 1.97e+03 4.33e+05 3.72e+>s Pr 144 02 0.00e00. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
[ Nd 147 4.79e 02 1.85e-02 2.41e-03 0.00e00 6.72e-03 1.61e+03 4.28e+03 l W 187 7.94e+03 3.13e+03 5.00e+02 0.00e+00 3.15e+03 3.22e+05 3.12e+04 l 1.30e+01 9.02e+00 3.12e+
- .................................... 00 0.00e00 0.00e+00 3.96*04 3.56e04 NP 239 3.71e+02 3.32e+01 1.84e+01 0.00e+00 6.62e+01 5.95e+04 2.49e+04 l
Conversion factors are in tmits of area /yr per UCf/ ethic meter.
l r
UNT-005-014 Revision 4 Attachment 6.19 (12 of 27) i
- 249
. - . - _ - - - ~_- - . . . - - . .- . --
30SE FACTORS DUE TO RAD 10NUCLIDES OTHER THAN N0BLE GASES: Pi Pi f actors for Aault age group cy nuclide.
Watertora steam Electric station Pathway : Cow's Milk (food) Pathway for Pi Nuclide Organ Dose Conversion Fectors Bone Liver T. Body Thyroid Kidney Lunt CI LLI H3 C-14 0.00e+00 7.63e+02 7.63e+02 7.63 M 2 7.63e02 7.63c02 7.63e+02 Na-24 2.63e+08 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+07 2.44e+06 2.44e+06 2.44e+06' 2.64e+06 2.44e*06
............................................................ 2.44e+06 2.44e+06 P 32 Cr 51 1.71e+10 1.06e+09 6.61e+08 0.00e+00 0.00e+00 0.00e+00 1.92e+09 Mn-54 0.00e+00 0.00e+00 2.86e+04 1.71e+04 6.30e+03 3.79e+06 7.19e+06 0.00e+00 8.41e+06 1.61e+06 0.00e+00 2.50e+06 0 Mn*56 00e+00 2.58e07 Fe-55 0.00e+00 4.15e 03 7.37e-06 0.00c 00 5.27e-03 0.00e00 1.33e 01 2.51e+07 1.73e+07 4.05e+06 0.00e+00 0.00e00 9.68 p 06 .9.95e+06 fe 59 2.97e+07 6.98e+07 2.68e+07 0.00e*00 0.00 1.95e+07 2.33e+08
.......................................................e+00 Co 58 Co 60 0.00e+00 4.71e+06 1.06e+07 0.00e+00 0.00e+00 0.00e00 9.55e*07 Ni 63 0.00e+00 1.64e+07 3.62e+07 0.00e+C0 0.00e+00 0.00e+00 3.08e+08 6.73e+09 4.66e+08 2.26e+08 0.00e+00 0
.................................................... 00e*00 ..........................
0.00e+00 9.73e+07 Ni 65 Cu 64 3.76e 01 4.88e.02 2.23e.02 0.00e+00 0.00e+00 0.00e+00 1.24e+00 In 65 0.00e+00 2.39e+06 1.12e+06 0.00e00 6.03e06 0.00e*00 2.04e+06 1.37e+09 4.37e+09 1.97e09 0.00e+00
.................................................. 2.92e*09 0.00e+00 2.75e+09 Zn 69 Br 83 2.18e.12 4.17e 12 2.90s.13 0.00e+00 2. 71o. 12 0.00e+00 6.26e.13 Br-86 0.00e+00 0.00e+00 1.18e 02 0.00e*00 0,00e+00 0.00e+00 1.71e 02 0.00e+00 0.00e+00 2.08e.24 0.00e+00 0
.................................................... 00e+00..........................
0.00e+00 1.63e 29 Br 85 Rb 86 0.00e+00 0.00e+00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb 88 - 0.00e+00 2.59e+09 1.21e+09 0.00e00 0.00e+00 0.00e00 5.12e+08 0.00e+00 0.00e+00 0.00e+00 0
.......................................... 00e+00 0.00e+00 0.00e+00 0.00e+00 Rb-89 Sr 89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e00 0.00e+00 0.00e+00 sr 90 1.45e*09 0.00e+00 4.16e+07 0.00e*00 0.00e*00 0.00e+00 2.33e+08 4.68e+10 0.00e+00 1.15e10 0
.......................................... 00e 00 0.00e*00 0.00e*00 1.35e+09 Sr 91 Sr 92 2.90e06 0.00e+00 1~17e+03 0.00e+00 0.00e00 0.00e+00 1.38e+05 Y*90 4.95e.01 0.00e+00 2.14e-02 0.00e00 0.00e+00- 0.00e00 9.81e+00 7.09e*01 0.00e+00 1.
.................................jpc00 0.00e*00 0.00e+00 0.00e+00 7.52e+05 Y 91 Y'91m 8.59e+03 0.00e+00 2.30e+02 0.00e+00 0.00e+00 0.00e+00 4.73e+06 Y 92 6.27e 20 0.00e+00 2.43e 21 0.00e+00 0.00e+00 0.00e00 1.84e.19 5.6&e-05 0.00e+00 1.65e 06 0.00e+00 0.00e+00 0.00e+00 9.88e.01 Conversion f acters are in unite of seance meter-aram/yr per WCi/soe for all nustidae except N 3, which is in units of area /yr per uCl/c @ic meter.
UNT-005-014 Revision 4 Attachment 6.19 (13 of 27) 250
I i i l l l
l' i
1 DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: P i
I i
l l
(
l i
I Pi factors for Adult age group by nuctice. .
Waterfero Steam Electric Station l
Pathway : Cow's Mitk (food) Pathway for Pi l
Nuclide Organ Dose Conversion Factors h i
(
l Bone Liver T. 8ody Thyroid Ki@ey Lung G! LLI ;
Y 93 l 2r 95 2.24e 01 0.00e+00 6.19e-03 0.00e+00 0.00e+00 0.00e+00 7.11e+03 Zr 97 9.43e+02 3.03e+02 2.05e+02 0.00e+00 4.75e+02 0.00e+00 9.59e+05
- i. 34e 01 8.76e 02 4.01e 02 0.00e+00 1.32e 01 0.00e00 2.71e+
Nb-95 04 ..
Mo 99 8.26e04 4.59e+04 2.47e+04 0.00e+00 4.54e+04 0.00e+00 2.79e+08 0.00e+00 2.48c07 4. 72e+06 0.00e+00 5.61e+07 0.00 e00 5.74e+07 Tc.101 1
- 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 l ......................................................................
Tc 99m 0.00e+00 t
Ru-103 3.34e+00 9.44e+00 1.20e+02 0.00e*00 1.43e*02 4.63e+00 5.59e+03 Ru 105 1.02e+03 0.00e+00 4.39e+02 0.00e00 3.89e+03 0.00e+00 1.19e+05 i 8.64e 06 0.00e+00 3.41e 06 0.00e+00 1.12e-02 0.00e00
.......................................................................5.29e-01 Ru-106 As 110m 2.04e+04 0.00e+00 2.58e+03 0.00e*00 3.94e+04 0.00e+00 1.32e+06 i
Te 125m 5.82e+07 5.39e+07 3.20e+07 0.00e00 1.06e+08 0.00e+00 2.20e+10 1.63e+07 5.90e06 2.18e+06 4.90e06 6.63e+07 0 6.50e+07 l
l ..............................................................
Te-127 00e+00 ................
i l
' Te-127m 6.56e+02 2.35e+02 1.42e+02 4.86e+02 2.67e+03 0.00e+00 5.17e+04 Te-129 4.58e+07 1.64e+07 5.58e+06 1.17e+07 1.86e+08 0.00e+00 1.53e+08 2.92e-10 1.10e 10 7.11e 11 2.24e-10 1.23e 09 0 l
Te-129m 00e+00 2.20e 10 Te-131 6.02e+07 2.25e+07 9.53e+06 2.07e+07 2.51e+08 0.00e+00 3.03e+08 {
Te-131m 3.95e 33 1.65e 33 1.25e 33 3.25e.33 1.73e 32 0.00e+00 5.60e 34 i 3.62e+05 1.77e+05 1.47e+05 2.80e+05 1.79 0.00e+00 1.76e+07
( .......................................................e+06 Te 132 l
I 130 2.40e+06 1.55e+06 1.46e+06 1.72 e06 1.50e+07 0.00e+00 7.35e+07 l l 131 4.21e+05 1.24e+06 4.90e+05 1.05e+08 1.94e+06 0.00e+00 1.07e+06 2.96e+08 4.24e+08 2.43e08 1.39e+11 7 0.00e+00 1.12e+08 1 132 26e+08 i
1 133 1.67e-01 4.47e 01 1.56e 01 1.56e+01 7.12e 01 0.00e+00 8.39e 02 1 134 3.88e06 6.76e+06 2.06e+06 9.91e+08 1.18e+07 0.00e+00 6.06e+06 2.11e 12 5.72e-12 2.05e-12 9.92e-11 9
............................... ................... 10e-12 ..........................
0.00e+00 4.99e-15 1 135 Ca*134 1.29e+04 3.38e+04 1.25e+04 2.23c46 5.42e+04 0.00e+00 3.82e+04 '
Cs 136 5.65e+09 1.34e+10 1.10e+10 0.00e00 4.35e+09 1.44e+09 2.35e+08 2.63e+08 1.04e+09 7 48e+08 0.00e+00
.................................................. 5.78e+08 7.93e*07 1.18e+08 Cs 137 Ca*138 7.38e+09 1.01e+10 6.61e+09 0.00e+00 3.43*09 1.14e+09 1.95e+08 8e-139 9.72e.24 1.92e 23 9.50e-24 0.00e+00 1.41e 23 1.39e 24 8.18e-29 4.54e 08 3.24e.11 1.33e 09 0.00e+00 3.03e.11 1.84e.11 8.06e-08 l Corwersion factors are in mits of square meter-arem/yr per WCl/sec for all !
nucLtdes except M 3, which is in mits of arem/yr per uCl/c2ic meter, i
4 4
UNT-005-014 Revision 4 Attachment 6.19 (14 of 27) i 251 i
JOSE FACTORS DUE TO RADIONUCLIDES
, OTHER THAN N0BLE GASES: %
i i
Pi factors for Adult age group by nuclide.
Waterford Steam Electric Station Pathway : Ccw's Milk (food) Pathway for Pi Nuclide Organ Dose Corwersion f actors Bone Liver T. Body Thyroid Cichey Lung GI LLI Ba 140 2.69e+07 3.38e+04 1.76e+06 0.00e+00 1.15e+04 1.93e04 5.54e+07 Ba 141 3.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Ba.142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 4.52e+00 2.28e+00 6.01e-01 0.00e+00 0.00e+00 0.00e00 1.67e+05 La 142 1.90e 11 8.66e-12 2.t$e.12 0.00e+00 0.00e+00 0.00e+00 6.32e 08 Ce 141 4.64e+03 3.28e+03 3.72e+02 0.00e+00 1.52e*03 0.00e+00 1.25e+07 Ce 143 4.16e+01 3.08e+04 3.40e+00 0.00e+00 1.35e+01 0.00e+00 1.15e+06 Ce 144 3.58e05 1.50e+05 1.92e+04 0.00e+00 8.87e+04 0.00e+00 1.21e+08 Pr 143 1.58e+02 6.33e+01 7.83e+00 0.00e+00 3.66e*01 0.00e+00 6.92e+05 Pr 144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 Nd 147 9.42e+01 1.09e+C2 6.51e+00 0.00e+00 6.36e01 0.00e+00 5.22e+05 W 187 6.52e+03 5.45e+03 1.91e+03 0.00e+00 0.00e+00 0.00e+00 1.79e+06 No 239 3.68e+00 3.61e 01 1.99e+01 0.00e 00 1.13e+00 0.00e 00 7.41e+04 Corwersion f actors are in min of spare meter.oren/yr per uCl/sec for all nuclides except M 3, which is in units of aren/yr per uct/ cubic meter.
UNT-005-014 Revision 4 Attachment 6.19 (15 of 27) 252 1
4 3
I i
i DOSE FACTORS DUE TO RAD'.0NULLIDES OTHER THAN NOBLE GASES: Pj l
1 i
j
't i
j ,
i; -
j PI factors for Te*, age group cy nuctice.
i Waterforo steam Electric station i
Pathway : COW's Milk (food) Pathway for Pi ,
Nuclide organ 00se Conversion Factors i
Bone Liver i- T. Sody Thyroid Kidney Lms GI-LLI 1
i H.3 c.14 0.00e+00 9.94c02 9.94e02 9.94e02 9.94e+02 9.94e02 9.94e+02
- 1. No.24 4.86e+08 9.72e+0T 9.72e+07 9.72e+07 9.72e07 9.72e+07 9.72e+07
!. 27e+06 4.27e+06 4.27e+06 4.27e+06 4.27e+06 4. 4.27c06 l
...............................................................27e+06 ...............
P 32 i Cr.51 3.15e+10 1.95e+09 1.22e+09 0.00e+00 0.00e+00 0.00e+00 2.65e09 j h 54 0.00e+00 0.00e00 4.99e*04 2.77e+04 1.09e*04 7.13e+04 8.39e*06 j 0.00e+00 1.40e+07 2.78e+06 0.00e*00 4.18e+06 0.00e*00 Mn.56 2.87e*07 i Fe.55 0.00e+00 7.36e.03 1.31o.03 0.00e+00 9.32e.03 0.00e+00 4.85e-01 i Fe.59 4.45e*07 3.16e+07 7.36e*06 0.00e00 0.00e*00 2.00e*07. 1.37e+07
- j. 5.18e+07 1.21e+08 4.6Te+07 0.00e*00 0.00e*00 1, ............................................................ 3.81e+0T 2.86e*08 Co.58 i Co.60 0.00e+00 7.94e*06 1.83e+0F 0.00e+00 0.00e*00 0.00e*00 1.09e*08 l
Nl.63 0.00e+00 2.78e07 6.26e+07 0.00e00 0.00e*00 0.00e+00 3.62e+08 1.18e*10 8.35e08 4.01e+08 0.00e+00 0.00e*00 0.00 1.33e08 i .................................................................e+00 NI.65 Cu-64 6.87e.01 8.780 02 4.00e.02 0.00e+00 0.00e+00 0.00e+00 4.76e+00 l 2n-65 0.00e+00 4.26e+04 2.00e04 0.00e+00 1.08e+05 0.00e+00 3.30e+06 ,
n 2.11e+09 7.32e+09 3.41e*09 0.00e+00 4.68e*09 3.10e+09 l
2n-69 0.00e*00 tr.43 4.01e.12 7.65e.12 5.35e.13 0.00e+00 5.00e.12 0.00e+00 1.41e.11 Br.44 0.00e+00 0.00e+00 2.18e.02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.71e.24 0.00e+00 0.00e+00
............................................................ 0.00e+00 0.00e+00 Br.85 Rb.86 0.00e*00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ab-88 0.00e+00 4.73e+49 2.22e+09 0.00e+00 0.00e+00 0.00e+00 7.00e*08 0.00e+00 0.00e*00 0.00e+00 0.00e*00 0.00 0.00e*00 0.00e+00
.......................................................e+00 Rb.89 3r.89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e*00 2.6Te+09 0.00e+00 7.66e+07 0.00e+00 0.00p00 0.00e+00 3.19e*08 tr.90 6,61e+10 0.00e*00 1.63e+10 0.00e+00 0 0.00e+00 1.86e+09 sr.91 00e+00..........................
tr.92 5.33e*04 0.00e+00 2.12e+03 0.00e+00 0.00e+00 0.00e+00 2.42e+05 Y-90 9.07e.01 0.00e*00 3.86e.02 0.00e*00 0.00e+00 0.00e+00 2.31e+01 1.30e+02 0.00e+00 3.51e+00 0.00e+00 0
.................................................... 00e+00 ..........................
-0.00e+00 1.07e*06 Y.91 Y 91a 1.58e+04 0.00e+00 4.24e*02 0.00e*00 0.00e+00 0.00e+00 6.48e+06 Y-92 1.15e.19 0.00e+00 4.39e.21 0.00e+00 0.00e+00 0.00e+00 5 A2e.18 1.04e-04 0.00e+00 3.01e.06 0.00e+00 0.00e+00 0.00e+00 2.8dc00 Conversion facters are in mits of sepaare meter.oren/yr per uct/ses for all raastidos except N.3, which is in units of arearyr per uct/ceis meter.
- UNT-005-014 Revision 4 Attachment 6.19 (16 of 27) 253
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pj P{ factors for Teen age group Oy nuclide.
Waterford Steam Electric Station Pathway : Cow's Milk (food) Pathway for Pi Nuclide Or9en Dose Conversion Factors Bone Liver T. Body Thyroid Kidiey Lung GI LLI Y 93 4.13e 01 0.00e+00 1.13e.02 0.00e+00 0.00e+00 0.00e00 1.26e+04 Zr 95 1.65e+03 5.20e+02 3.58e+02 0.00e+00 7.65e+02 0.00e+00 1.20e+06 Zr 97 7.90e 01 1.56e-01 7.20e 02 0.00e+00 2.37e-01 0.00e+00 4.23e+04 ND-95 1.41e+05 7.81e+06 4.30e+04 0.00e+00 7.57e+06 0.00e+00 3.34e+08 Mo 99 0.00e*00 4.47e+07 8.53e+06 0.00e+00 1.02e+0s 0.00e+00 8.01e07 Tc.101 3.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Tc 99m 5.80e+00 1.52e+01 2.10e+02 0.00e+00 2.41e+02 8.97e+00 1.06e+06 Ru.103 1.81e+03 0.00e*00 7.74e+02 0.00e+00 6.38e+03 0.00e+00 1.51e+05 Ru 105 1.58e.03 0.00e*00 6.13e.04 0.00e+00 1.99e.02 0.00e00 1.27e+00 Ru 106 2.89e+06 0.00e+00 4.73e+03 0.00e*00 7.24e+04 0.00e+00 1.80e+06 AS 110m 9.63e+07 9.11p07 5.54e+07 0.00e+00 1.74e*08 0.00e00 2.56e+10 Te.125m 3.00e+07 1.08e+07 4.02e+06 8.39e+06 0.00e*00 0.00e+00 8.86e+07 Te.127 1.22e+03 4.31e+02 2.61e+02 8.38e+02 4.92e+03 0.00e+00 9.38e+06 I Te.127m 8.44e+07 2.99e+07 1.00e+07 2.01e*07 3.42e+08 0.00e+00 2.10e06 Te.129 5.37e.10 2.00e 10 1.20e-10 3.86e.10 2.25e 09 0.00e+00 2.94e.09 Te.129m 1.10e+0S 4.09e+07 1.74e+07 3.55e+07 4.61eecs 0.00e*00 4.13e+0S Te 131 7.22e-33 2.98e 33 2.26e 33 5.57e.33 3.16e 32 0.00c00 5.93e 34 Te 131m 6.58e+05 3.15e+05 2.63e+05 4.75e+05 3.29e06 0.00e+00 2.53e+07 Te 132 4.29e+06 2.72e+06 2.56e+06 2.87e+06 2.61e+07 0.00e+00 8.61e+07 1 130 7.41e+05 2.14e+06 8.56e+05 1.75e+0s 3.30e+06 0.00e+00 1.65e+06 1 131 5.37e+08 7.52e+08 4.04pos 2.20e+11 1.30e+09 0.00e+00 1.49e08 1 132 2.96e 01 7.75e 01 2.78e.01 2.61e+01 1.22e+00 0.00e+00 3.38e 01 1 133 7.08e+0e 1.20e+07 3.66e+06 1.68e+09 2.11e+07 0.00e+00 9.09e+06 I-134 3.76e 12 9.92e.12 3.56e 12 1.65e 10 1.56e.11 0.00e+00 1.31e.13
~
!*135 2.29e04 5.90e+06 2.19e+04 3.80e*06 9.33e04 0.00e+00 6.54e+06 Cs 134 9.81e09 2.31e+10 1.07p10 0.00e+00 7.34e+09 2.80e+09 2.87e+08 Cs.136 4.44e+08 1.76e*09 1.38e+09 0.00e+00 9.60e+08 1.51e*08 1.42e+0B ca.137 1.34e+10 1.78e+10 6.20e+09 0.00e+00 6.06e+09 2.35e*09 2.53e+0S l
Cs.138 1.76e 23 3.38e.23 1.69e.23 0.00e+00 2.50e 23 2.91e 24 1.54e.26 Be 139 8.40e-08 5.91e 11 2.45e 09 0.00e*00 5.57e.11 4.07e.11 7.50e 07 Conversion f actors are in mits of sesore meter.oren/yr per uCl/ses for all nuntidee encept N 3, uhich is in m its of arem/yr per UCf/ cubic meter.
I i
UNT-005-014 Revision 4 Attachment 6.19 (17 of 27) 254
i COSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pi Pi factors for Teen age group oy nuctice.
Waterford Steam Electric $+ation Pathway : Ccw's Milk (food) Pathway for Pi Nuclide Organ Oose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung GI.LLI Ba.140 4.85e+07 5.95e+04 3.13e+06 0.00e+00 2.02e+04 4.00e 04 7.48e+07 Ba 141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Ba.142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 S.11e+00 3.99e+00 1.06e+00 0.00e+00 0.00e+00 0.00e+00 2.29e+05 La 142 3.43e.11 1.53e.11 3.80e.12 0.00e+00 0.00e+00 0.00e+00 4.64e 07 Co.141 8.88e+03 5.93e+03 6.81e+02 0.00e00 2.79e+03 0.00e+00 1.70e+07 Ce 143 7.65e+01 5.56e+04 6.21e+00 0.00e+00 2.50p01 0.00e+00 1.67c06 Co.144 6.58e+05 2.72e+05 3.54e+04 0.00e+00 1.63e+05 0.00e+00 1.66e 08 Pr.143 2.90e02 1.16e+02 1.44e01 0.00e+00 6.73e+01 0.00e+00 9.55e+05 Pr.144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Nd.147 1.81e+02 1.97e+02 1.18e+01 0.00e+00 1.16e+02 0.00e+00 7.11e+05 W.187 1.19e+04 9.73e+03 3.41e+03 0.00e+00 0.00e+00 0.00e+00 2.63e+06 Np 239 7.01e+00 6.62e.01 3.67e.01 0.00e+00 2.08e+00 0.00e+00 1.06e+05 I
Corwersion factors are in mits of square meter-erem/yr per uCf/sec for all ;
nuclides except H 3, which is in mits of aree/yr per uCl/ cubic meter.
l UNT-005-014 Revision 4 Attachment 6.19 (18 of 27) 255
DOSE FACTORS DUE TO RAD 10NUCLIDES OTHER THAN N0BLE GASES: Pi l
Pi factors for Child age group by nuctice.
Waterford steam Electric Station Pathway : Cow's Milk (food) Pathway for Pi i
Nuctide I
Organ Oose Conversion Factors '
I Bone Over T. Body Thyroid Kfchey Lung GI LLI '
H-3 C.14 Na 24 0.00e+00 1.57e+03 1.57e03 1.57e+03 1.57e+03 1.57e+03 1.57 1.19e+09 2.39e08 2.',9e08 2.39e08 2.39e+08 2.39e+08 2.39e+08 8.88e 06 8.88e+07 P.32 8.88e+06 8.88e+06 8.88e+06 8.88e+06 8.88e+06...................................
............ 1 Cr.51 7.78e+10 3.64e+09 3.00e09 0.00e+00 0.00e+00 0.00e+00 2.15e+
Mn.54 0.00e+00 0.00e+00 0.00e+00 1.02e+05 5.65e+04 1.54e+04 1.03e+05 5.40e 2.10e+
.......................... 07.......................................
5.59e+06 0.00e00 5.88e+06 0.00e+00 1.76*07 Mn.56 ............
Fe.55 0.00e+00 1.28e.02 2.90e.03 0.00e+00 1.55e 02 0.00e+00 1.86e Fe.59 1.12e+08 1.20e+08 5.93e+07 1.84e+07 0.00e+00 0.00e+00 3.35e+07 1.10 1.95e+
.......................... 08.......................................07 9.69e07 0.00c00 0.00e+00 5.64
- 2.03e08 Co-38 ............
Co.60 0.00e+00 1.21e+07 3.71e+07 0.00e00 0.00e+00 0.00e+00 7.07 NI.63 0.00e 00 2.96p10 4.32e+07 1.59e 1.27e+08 0.00e+00 0.00e+00 0.00e+00 2.39
.......................... 09.......................................00 1.07e+08 1.04e+09 0.00e+00 0.00c 00 0.00e+
Ni.65 ............
Cu 64 1.68e+00 1.58e.01 9.24e.02 0.00e+00 0.00e+00 0.00e+00 1.94 e Zn 65 0.00e+00 4.13*09 7.49c04 4.52e+04 0.00e00 1.81e+05 0.00e+00 3.51e+0 1.10e 6.85e+09 0.00e+00 6.94e+09 0.0 0e+00 1.93e+09
...........................10...................................
Zn.69 ...............
Br.83 9.87e.12 1.43e.11 1.32e.12 0.00e+00 8.65e 12 0.00e+00 8.99e.1 Br.84 0.00e+00 0.00e+00 5.36e.02 0.00e+00 0.00e+00 0.00e+00 0.00e+
0.00e+00 0.00e+
B r*85 8.40e.24 0.00e+00 0.00e+00 0 00................................... 00e+00 0.00e+00 ab.86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00 Rb.88 0.00e+00 0.00e+00 0.008.77e+09 5.39c09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.64e+
.........................e+00................................
Rb.89 .....................
$r-89 0.00e 00 0.00e00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+
sr.90 6.62e+09 1.12e+11 0 0.00e+00 1.89e+08 0.00e+00 0.00e+00 0.00e+00 2.56e
...................... 00e+00................................e+00 2.83e+10 0.00e+00 0.00 0.00e+00 1.50e+09 Sr.91 ........................
sr.92 1.31e+05 0.00e+00 4.94e+03 0.00e+00 0.00e+00 0.00e+00 2.89 Y 90 2.21e+00 3.22e*02 0. 9.00e+00 8.88e.02 0.00e+00 0.00e+00 0.00e00 4.19e0 8.63e+00 0.00e+00 0.00e+
.......................00e00........
Y 91 ..................... 00 0.00e00 9.18e+05 Y.91e 3.90e+04 0.00 ,00 1.04e+03 0.00e+00 0.00*00 0.00e+00 5.20e06 Y.92 2.80e.19 0.00c00 1.02e.20 0.00e+00 0.00e+00 0.00e+00 5.49e.
2.56e.04 0.00e00 7.32e.06 0.00e+00 0.00e00 0.00e+00 7.39e+0 nuclides except N.3, which is in units of aren/yr per uCf/ cu UNT-005-014 Revision 4 Attachment 6.19 (19 of 27) 256
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pj ,
i PI f actore for Child age grow by nuclide.
Waterford Steen Electric Stetten Pethway : Cow s Milk (food) Pathuey for Pi e
Nuclide 0. gen Dose Conversion factors Bone Liver T. Sody Thyroid Kidney- Luis Cl LLI Y.93-Zr 95 1.02e+00 0.00e*00 2.79e.02 0.00e+00 0.00e+00 0.00e+00 1.51e+04 Zr.97 3.83e+03 8.42e+02 7.50e+02 0.00e+0C 1.21e+03 0.00e00 8.79e+05 1.92e+00 2.78e 01 1.64e.01 0.00e00 3.99e.01 0 Nb.95 00e+00 4.21e+04 Mo.99 3.18e+05 1.24e+05 8.84e+04 0.00e+00 1.16e+05 0.00e+00 2.29e+08 Tc.101 0.00e+00 8.14e*07 2.01e*07 0.00e*00 1.74e+08 0.00e+00 6.73e+07 0.00e+00 0.00e*00 0.00e+00 0.00e+00
.................................................... 00e+00 0.
0.00p00 0.00e+00 ,
.......................... j Tc 99m Ru.103 1.33e+01 2.61e*01 4.32e+02 0.00e+00 3.79e+02 1.32e+01 1.48e+06 ;
Ru.105 4.28e+03 0.00e+00 1.65e+03 0.00e+00 1.08e*06 0.00e+00 1.11e+05 '
3.25e 03 0.00e+00 1. W .03 0.0 3.39e.02 0.00e+00 2.51e+00
...........................................0e00 ...................................
Ru.106 3 Ag.110e 9.24e06 0.00e+00 1.15e+06 0.00e+00 1.25e*05 0.00e+00 1.44e+06 '
To.125e 2.09e+08 1.41e*04 1.13e+08 0.00e+00 2.63e+08 0.00e+00 1.68e+10 1 7.38e+07 2.00e+07 9.86e+06 2.07 0.00e+00 0.00e00 7.12e+07
.............................................e+07 Te.127 Te.12Te 2.99e+03 8.06e+02 6.41e+02 2.0Te+03 8.50e+03 0.00e+00 1.17e+05 fe.129 2.08e+08 5.60e+07 2.47e+07 4.97e+07 5.93c+08 0.00e+00 1.68e08 1.33e.09 3.70e.10 3.15e.10 9
.......................................... 46e.10 ....................................
3.88e.09 0.00e+00 8.25e 08 To.129m Te.131 2.71e*08 7.58e+07 4.21e+07 8.75e+07 7.9Fe+08 0.00e*00 3.31e08 fe.131a 1.77e 32 5.40s.33 5.27e 33 1.36e.32 5.36e.32 0.00e+00 9.31e 32 1.60e+06 5.54e*05 5.89c05 1
.......................................... 14e+06 5.36e+06 0.00e+00 2.25e+07 Te.132 1.03e+07 4.54e+06 5.68e+06 6.61e+06 4.21p07 0.00e00 4.57e+07 t 130 1 131 1.73e+06 3.50e+06 1.80e+06 3.86e+08 5.23e+06 0.00e+00 1.64e+06 1.30e+09 1.31e+09 7.45e+08 4.33 2.15e+09 0.00e+00 -1.1Te08
.............................................e+11 1 132 1 133 7.01e 01 1.29e+00 5.92e.01 5.97c01 1.97e+00 0.00e+00 1.52e+00 t 134 1.72e+07 2.13e+07 8.05e+06 3.95e*09 3.55e+07 0.00e00 8.5Te+06 I 8.87e.12 1.65e 11 7.57e.1
..................................... 2 3.79e.10
. 2.52e.11 0.00e+00 1.09e 11 I
1 135 j Ca.134 5.43e+06 9.77e+06 4.62e+06 8.66e+06 1.50e+05 0.00e+00 7.45e+04 Cs 136 2.26e+10 1.01e+09 3.71e+10 2.86e+09 7.86e+09 1,80e*09 00.00e+00 1.15e+10 4.13e+09 2.00e+08
.......................................... 00e+00 1.48e+09 2.21e+08 9.7Te+07 Ca.137 Ca.138 3.22e+10 3.09e+10 4.55e+09 0.00e+00 1.01e+10 3.62e09 1.93e+08 84 139 4.27e.23 5.96e.23 3.77e.23 0.00e+00 4.18e.23 4.50e.24 2.74e.23 2.06e.07 1.10e.10 5.98e.09 0.00e*00 9.62e.11 6.48e.11 1.19e.05 Conversion f actors are in mits of square meter.arem/yr per uCf/ses for all nuclides except N 3, which is in m ite of area /yr per WCl/c Wic meter.
UNT-005-014 Revision 4 Attachment 6.19 (20 of 27; 257
l 1
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pj Pi factors for Child age group by nuclide.
Waterford Steam Electric Station Pathway : Cow's Milk (food) Pathway for Pi Nuctide organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidwy Lung GI LLI Ba 140 1.17e+08 1.03e05 6.84 e 06 0.00*00 3.34e+04 6.12e+04 5.93e+07 Sa 141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 Ba 142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 La 140 1.94e+01 6.79e+00 2.12e+00 0.00e+00 0.00e+00 0.00e+00 1.89e+05 La 142 8.30e-11 2.64e-11 8.28e 12 0.00e+00 0.00e+00 0.00e+00 5.24e 06 Ce-141 2.19e+04 1.09e+04 1.62e+03 0.00e+00 4.78e+04 0.00e+00 1.36e+07 Co.143 1.80e02 1.02e+05 1.4Teot 0.00e+00 4.27e+01 0.00e+00 1.49e+06 Co 144 1.62e06 5.09e*05 8.66e+04 0.00e00 2.82e+05 0.00e+00 1.33e+08 Pr.143 7.18e+02 2.16e+02 3.56e+01 0.00e+00 1.17e+02 0.00e00 7.75e+05 Pr.144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Nd.147 4.45e+02 3.60e+02 2.79e+01 0.00e+00 1.98e+02 0.00e 00 5.71e+05 W 187 2.89e+04 1.71e+04 7.69e+03 0.00e+00 0.00e+00 0.00e+00 2.41e+06 Np-239 1.73e+01 1.24e+00 8.71e 01 0.00e+00 3.58e+00 0.00e00 9.17e+04 j Conversion factors are in units of square meter.oren/yr per uct/sec for ELL l nuclides except N 3, which is in units of arem/yr per uCl/ cubic meter.
l l
l 4
UNT-005-014 Revision 4 Attachment 6.19 (21 of 27) 258 l
i
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi factors ter Infant age group by nuctice.
Waterford Steam Electric Station Pathway : Cow's Milk (food) Pathway for Pi Nuclide Orgen Dose Conversion Factors Bone Liver T. Body Thyroid Kichey Lung GI.LLI W3-c-14 0.00e00 2.38e+03 2.38e+03 2.38c03 2.38e+03 2.38e+03 2.38e+03 Na*24 2.34e+09 5.00e+08 5.00e08 5.00e08 5.00e+08 5.00e+08 5.00e+08 1.55 e+07 1.55e+07 1.55e+07 1.55e+07 1.5
..................................................... 5e+07 1.55e+07 1.55e+07 P-32 Cr.51 1.60e+11 9.43e+09 6.21e+09 0.00c00 0.00e+00 0.00e+00 2.17e+09 Hn-54 0.00e+00 0.00e+00 1.61e+05 1.05e05 2.30e+04 2.05e+05 4.70e+06 0.00e*00 3.90e07 8.84e+06 0.00e 00 8
.................................................... 64e+06 ..........................
0.00e+00 1.43e+07 Mn.56 Fe.55 0.00e*00 3.14e.02 5.42e 03 0.00e+00 2.70e.02 0.00e+00 2.86e+00 Fe.59 1.35e*08 8.73e+07 2.33e07 0.00e00 0.00e00 4.2Te07 1.11e07 2.24e+06 3.92e+08 1.54e+08 0.00e+00 1.16e+08 1.87e+08
...................................................0.00e+00 Co 58 Co 60 0.00e+00 2.42e+07 6.05e+07 0.00e*00 0.00e+00 0.00e+00 6.04e+07 ut.63 0.00e+00 8.81e+07 2.08e08 0.00e00 0.00e+00 0.00e00 2.10e+08 3.49e+10 2.16e+09 1.21e+09 0.00e+00
.................................................. 0.00e+00 0.00e+00 1.07e+08 N(.65 Cu 64 3.56e+00 4.03e01 1.83e01 0.00e+00 0.00e00 0.00e+00 3.07e+01 Zn.65 0.00e+00 1.86e+05 8.62e+06 0.00e+00 3.15e+05 0.00c00 3.82e+06 5.55e+09 1.90e10 8.78e+09 0
.......................................... 00e+00 9.23e+09 0.00e+00 1.61e+10 Zn.69 Gr.83 2.10e.11 3.79e.11 2.82e.12 0.00e+00 1.57e.11 0.00e+00 3.09e.09 Br-84 0.00e+00 0.00e+00 1.14e.01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e.23 0.00 0.00e+00 0.00e+00 0.00e00
.............................................e+00 Br-85 Rb.86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e 00 0.00e+00 0.00e00 Rb.88 0.00e+00 2.23e+10 1.10e+10 0.00e+00 0.00e+00 0.00e00 5.69e+08 0.00e+00 0.00e+00 0.00e+00
........................................ 0.00e*00 0.00e00 0.00e+00 0.00e+00 Rb 89 Sr 89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3r*90 1.26e+10 0.00e+00 3.61e+08 0.00e+00 0.00e+00 0.00e+00 2.59e+08 1.22e+11 0.00e*00 3.10e+10 0
........................... ............. 00e+00 0.00e+00 0.00e+00 1.52e+09 Sr.91 tr.92 2.73e+05 0.00e+00 9.87e+03 0.00e*00 0.00e+00 0.00e+00 3.23e*05 f.90 4.71c00 0.00e+00 1.75e.01 0.00e+00 0.00e+00 0.00e+00 5.00e+01 6.82e+02 0.00e+00 1.83e+01
.........................................0.00e*00 0.00e*00 0.00c00 9.41e*05 Y 91 .....................................
Y 91m 7.33e+04 0.00e+00 1.95e+03 0.00e+00 0.00e+00 0.00e+00 5.25e+06 Y-92 5.94e.19 0.00e+00 2.03e.20 0.00e+00 0.00e*00 0.00e+00 1.98e.15 5.44e-04 0.00c00 1.53e.05 0.00e*00 0.00e+00 0.00e+00 1.04e01 Conversten factors are in units of square seter.oren/yr per uct/sec for all ruclidos except M.3, which is in units of aren/yr per uct/csbic meter.
UNT-005-014 Revision 4 Attachment 6.19 (22 of 27) 259
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pj Pi factors for Infant age group by nuctide.
Waterford Steam Electric Station Pathway : Cow's Milk (foca) Pathway for Pt Nuclide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kleey Lung GI.LLI Y 93 Zr 95 2.16e+00 0.00e00 5.90e-02 0.00e+00 0.00e 00 0.00e+00 1.71e+06 Zr-97 6.80e+03 1.66e+03 1.18e+03 0.00e00 1.79e+03 0.00e+00 8.26e+05 4.07e+00 6.99e-01 3.19e.01 0.00e+00 7.04e 01 0.0
............................................................... 0e+00 4.46c04 Nb.95 Mo-99 h93e+05 2.44e+05 1.41e+05 0.00e+00 1.75c05 0.00e00 2.06e+0s i Tc.101 0.00e+00 2.08e*08 4.06e*07 0.00e00 3.11e+08 0.00e+00 6.86e+0F 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.0 i
............................................................... 0e+00...............
0.00e*00 l Tc.99m Ru-103 2.77e+01 5.70e+01 7.35e+02 0.00e+00 6.14e+02 2.90e+01 1.66e+06 Ru 105 8.67e+03 0.00e+00 2.90e03 0.00e+00 1.80e06 0.00e+00 1.05e+05 8.12e.03 0.00e+00 2.74e-03 0.00e+00 5.97e 0
......................................................... 2 0.00e+00 3.23e+00 Ru.106 1.90e*05 0.00e00 2.38e+06 0.00e+00 2.25e+05 0.00e+00 1.44e+06 Ag.110m 3.86e+0B 2.82e+0S 1.86e+08 0.00e*00 4.03e+0S 0.00e*00 1.46e+10 Te.125m 1.51e*08 5.06e+07 2.06e+0F 5.0Te+07 0
.................................................... 00e+00 ..........................
0.00e+00 7.18e+07 Te.127 6.34e+03 2.13e+03 1.36e+03 5.16e+03 1.55e*06 0.00e*00 1.33e+05 l Te*127a Te*129 4.21e+0S 1.40e+0S '5.10e+07 1.22e es 1.06e+09 0.00e+00 1.70e+08 2.81e.09 9.69e.10 6.56e.10 2,36e.09 7 s
.................................................... 00e.09 ..........................
0.00e+00 2.25e.07 i Te.129m 5.57e+0S 1.91e+08 8.58e+07 2.14e*08 1.39e*09 0.00e00 3.33e+0S To.131 To.131a 3.76e.32 1.39e.32 1.05e.32 3.35e.32 9.61e.32 0.00e+00 1.52e.30 3.38e+06 1.36e+06 1.12e+06 2,76e+06 9 ,
l
.................................................... 36e+06 ..........................
0.00e+00 2.29e+07 Te.132 1 130 2.11e+07 1.05e+07 9.75e+06 1.54e*07 6.54e+0F 0.00e+00 3.87e*07 l 131 3.54e+06 7.83e+06 3.14e+06 8.78e+04 8.60e+06 0.00e+00 1.68e+06 2.72e*09 3.21e+09 1.41e+09 1 3.74e+09 0.00e+00 1.14e+0s
...'....................................... 05e*12 ....................................
1 132 1 133 1.45e+00 2.95e+00 1.05e+00 1.38e+02 3.29e+00 0.00e+00 2.39e*00 1 134 3.63e+07 5.29e+07 1.55e+07 9.62e+09 6.22e*0T 0.00e00 8.95e+06 1.86e.11 3.77e.11 1.34e.11 8
........................... ............. 78e.10 4.21e.11 0.00e+00 3.89e.11 1 135 Ca.134 1.13e+05 2.25e+05 8.19e*06 2.01e+07 2.50e+05 0.00e+00 8.13e+06 Cs.136 3.65e+10 6.80e+10 6.87e+09 0.00e*00 1.75e+10 T.18e09 1.85e*05 1.90e+09 5.81e+09 2.17e+09 0.00e+0
............................................... 0 2.32e+09 4.76e+0S 8.83e*0T Cs 137 Ca.138 5.15e+10 6.02e+10 4.27e*09 0.00e+00 1.62e+10 6.55e+09 1.88e+0S 5e.139 9.01e.23 1.47e.22 7.10e.23 0.00e+00 7.31e.23 1.14e.23 2.34e.22 4.39e.07 2.91e.10 1.27e.08 0.00e*00 1.75e.10 1.TTe.10 2.78e.05 camersion factors are in units of saare meter.aren/yr per uct/sec for ELL nustidos except u.3, which is in units of aren/yr per uct/cete meter.
UNT-005-014 Revision 4 Attachment 6.19 (23 of 27) 260
l i DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES: Pi i
l z
FI factors for Infant age group by nuclide.
Waterfora steam Electric Station a
Pathway : Cow's Milk (food) Pathway for Pi 4 Nuclide Organ Oose Conversion Factors Bone Liver i T. Body Thyroid Kidiey Lung GI.LLI s
i 1
Ba.140 i Ba 141 2.41e+08 2.41e+05 1.24e+07 0.00e+00 5.72e+04 1.48e+05 5.92e+
Ba 142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+0 l
La 140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 00e+00........................................ .....
La 142 4.06e+01 1.60e+01 4.11e+00 0.00e+00 0.00e+00 0.00e+00 1.88e+0
, Ce 141 1. 74e.10 4.34e+04 6.40e-11 1.53e.11 0.00e*00 0.00e+00 0.00e*00 1.09e.05 2.64e+04 l
Co 143 0.00e*00 8.15e+03 0.00e*00 3.11e+03........................................1.37e+07 .......
co 144 3.97e+02 2.64e+05 3.01e+01 0.00e+00 7.68e+01 0.00e+00 1.54e+
> Pr*143 2.33e+06 9.52e+05 1.30e*05 0.00e+00 3.85e+05 0.00e+0e 1.33e+
1.49e+03 5.55e+0
........................... 2.....................................e+00 7.36e+01 0.00e+00 2.06e+02 0.00 7.84e+05 Pr*144 ..............
- Nd 147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e*00 0.00e+0 W 187 8.81e+02 6.09e+04 9.05e+02 4.23a+04 5.55e+01 0.00e+00 3.49e+02 0.00e+00 5.74e+
0.00e+00 0.00e*00 0.00e+00 2.49e*06
! ...............................1.46e+04......................................
Np.239 ........
3.65e+01 3.26e+00 1.84e*00 0.00e+00 6.51e*00 0.00e+00 9.Ekc Conversion factors are in units of square aster.oremfyr per uCf/sec for all nuttides except N 3, uhich is in talts of aremfyr por uCf/ cubic aster.
UNT-005-014 Revision 4 Attachment 6.19 (24 of 27) 261
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj Pi factors for all age groups by nuclide.
Waterford Steam Electric Station Pathway : Croung Plane Pathway for Pi Nuctide Organ Dose Conversion Factors T. Body Skin H3 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 No 24 1.71e+07 1.98e+07 P 32 0.00e+00 0.00e+00 Cr-51 6.65e+06 7.86e+06 Mn 54 1.10e+09 1.29e+09 Mn 56 1.29e+06 1.52e*06 Fe 55 0.00e+00 0.00e+00 Fe-59 3.89e+08 4.57e+08 Co-58 5.26e+08 6.16e+08 Co 60 4.40e+09 5.18e+09 Ni 63 0.00e+00 0.00e+00 Ni 65 4.24e+05 4.93e+05 Cu 64 8.67e+05 9.82e+05 Zn-65 6.88e+08 7.92e*08 2n-69 0.00e+00 0.00e+00 Br 83 6.96e+03 1.01e+04 87-84 2.89e+05 3.38e+05 Br*85 0.00e+00 0.00e+00 R&86 1.28e+07 1.47e+07 R>88 4.72e+04 5.40e+04 R&89 1.76e*05 2.11e+05 sr 89 3.07e+06 3.54e+04 Sr 90 _0.00e+00 0.00e+00 Sr-91 3.07e+06 3.59e+06 Sr 92 L11e+06 1.23e+06 Y 90 6.62e*05 7.58e+03 Y 91 1.51e+06 1.70e+06 Y 91m 1.43e+05 1.66e+05 Y 92 2.58e+05 3.06e+05 Comersten facters are in tnits of square meter.orewyr per utf/sec.
UNT-005-014 Revision 4 Attachment 6.19 (25 of 27) 262
. . _ ~ . - . . . . .. - -. - _ _ _ - ~ - _ - . .
1 i
l DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: Pj I 1
1 l
l 1
i i
Pi factors for all age groups by nuclide.
Waterford Steam Electric Station Pathway : Cround Plane Pathway for Pi l
i Nucilde Organ Dose Conversion Factors T. Body Skin Y 93 2.62e+05 3.5Se+05 Zr 95 3.43e+08 3.98e+08 2r-97 4.23e+06 4.92e+06 Nb-95 1.95e+08 2.30e+08 !
Mo 99 5.71e+06 6.61e+06 Tc 101 2.91e+04 3.23e+04 Tc 99m 2.63e+05 3.01e+05 Ru-103 1.54e+08 1.80e+08 Ru 105 9.09e+05 1.03e+06 ]
Ru-106 3.00e+08 3.60e+08 1
As 110m 3.13e+09 3.65e+09 Te 125m i 2.19e+06 3.00e+06 Te-127 4.25e+03 4.68e+03 Te 127m 1.18e+05 1.40e+05 Te 129 3.75e+04 4.43e+04 Te-129m 2.82e+07 3.30e+07 i Te 131 4.17e+04 4.93e+07 i
Te-131m 1.15e+07 1.35e+07 Te 132 6.05e+06 7.*2e+06 I 130 7.87e+06 9.26e+06 I 131 2.46e+07 2.98e+07 1 132 1.78e+06 2.09e+06 I 133 3.50e+06 4.26e+06 1 134 6.38e+05 7.58e+05 1 135 3.61e+06 4.21e+06 Cs 134 2.82e+09 3.28e+09 Cs 136 M16e+08 2.44e+08 Cs 137 1.15e+09 1.34e+09 Cs 138 5.13e+05 5.86e+05 l Be-139 1.51e+05 1.70e+05
)
Conversion factors are in smits of agasre meter arem/yr per uCl/sec.
UNT-005-014 Revision 4 Attachment 6.19 (26 of 27) 263
DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES: P i
l l
76 factors for all age groups by nucLace.
Watertora Steam Electric Station Pathway : Croma Plane Pathway for Pi Nuclide Organ Oose Conversion factors T. Body ! kin Ba 140 2.93e+07 3.35e+07 Ba 141 5.96e+04 6. 79e+04 Ba 142 6.41e+04 7.30e+04 La 140 2.74e+07 3.11e+07 La 142 1.09e+06 1.30e+06 Co.141 1.95e+07 2.20e+07 Co 143 3.30e+06 3.75e+06 Co 144 5.85e+07 6.77e+07 Pr-143 0.00e+00 0.00e+00 Pr 144 2.62e+03 3.01e+03 Nd 147 1.20e+07 1.44e+07 I W 187 3.36e+06 3.90e+06 l
Mp.239 2.44e+06 2.83e+06 l Conversion f actors are in units of sausre meter-erem/yr per uCl/sec. 1 UNT-005-014 Revision 4 Attachment 6.19 (27 of 27) 264
DOSE CONVERSION FACTORS ALL AGE GROUPS i
BY NUCLIDE (INHALATION AND INGESTION)
Inhalation Dose Conversion factors for Adult age grow by nuclide.
Waterford Steam Electric Station Nuctide organ Dese Conversion factore Bone Liver T. Body Thyroid Kistey Lung Gl LLI H3 0.00e+00 C 14 1. W 07 1.58e 07 1.58e 07 1.58e 07 1.58e-07 1.58e 07 Na 24 2.27e 06 4.26e 07 4.26e 07 4.26e-07 4.26e 07 4.26e 07 4.26e 07 1.28e-06 1.28e 06 1.28e 06 1.28e-0
............................................... 6 1.28e 06 1.28e 06 1.28e 06 P-32 Cr 51 1.65e-04 9.64e-06 6.26e 06 0.00e+00 0.00e+00 0.00e+00 1.08e 05 Mn 54 0.00e+00 0.00e+00 1.25e-08 7.44e 09 2.85e-09 1.80e 06 4.15e 07 0.00e*00 4.95e-06 7.87e-07 0
.......................................... 00e+00....................................
1.23e-06 1.75e.04 9.67e-06 Mn 56 Fe-55 0.00e*00 1.55e-10 2.29e-11 0.00e*00 1.63e 10 1.18e-06 2.53e 06 Fe-59 3.07e 06 2.12e 06 4.93e-07 0.00e+00 0.00e*00 9.01e-06 7. W -07 1.47e 06 3.47e-06 1.32e-06 0
.......................................... 00e+00 ....................................
0.00e+00 1.27e 04 2.35e-05 Co-58 Co 60 0.00e+00 1.W-07 2.59e-07 0.00e+00 0.00e*00 1.16e 04 1.33e 05 Ni 63 0.00e*00 1.44e 06 1.85e 06 0.00e*00 0.00e+00 7.46e-04 3. 05 5.40e-05 3.93e 06 1.81e-06 0
.......................................... 00e*00 ....................................
0.00e+00 2.23e-05 1.67e 06 Ni 65 Cu 64 1.92e 10 2.62e 11 1.14e 11 0.00e*00 0.00e+00 7.00e-07 1.54e-06 Zn-65 0.00e+00 1.83e-10 7.69e-11 0.00e+00 5.78e 10 8.48e-07 6.12e06 4.05e 06 1.29e 05 5.82e 0
..................................... 6 0.00e*00 8.62e 06 .1.00e 04 6.68e 06 In 69 4.32e 12 Br 83 8. W .12 5.65e 13 0.00e+00 5.27e 12 1.15e 07 2.04e 09 Br 84 0.00e+00 0.00e+00 3.01e 08 0.00e+00 0.00e+00 0.00e+00 2.90e 08 0.00e+00 0.00e+00 3.91e 0
..................................... 8 0.00e+00 0.00e+00 0.00e+00 2.05e 13 Br 85 ab M 0.00e+00 0.00e+00 1.60e-09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rtr48 0.00e+00 1.69e 05 7.37e-06 0.00e+00 0.00e+00 0.00e+00 2.08e 06 0.00e+00 4.84e 08 2.41e 0
..................................... 8 0.00e*00 0.00e+00 0.00e+00 4.18e 19 Rb 89 tr 89 0.00e+00 3.20e-08 2.12e 08 0.00e+00 0.00e*00 0.00e+00 1. W 21 Sr 90 3.00e 05 0.00e+00 1.09e 0.00e+00 0.00e+00 1.75e-04 4.37e 05 1.24e 02 0.00e+00 7.62e-
.................................... 06 0.00e+00 0.00e+00 1.20e-03 9.02e 05 Sr 91 tr 92 7.74e.09 0.00e+00 3.13e.10 -0.00e+00 0.00e+00 4.56e-06 2.39e 05 Y 90 8.43e 10 0.00e+00 3.64e 11 0.00e+00 0.00e+00 2.06e-06 5.38e-06 2.61e 07 0.00e+00 7.01e-
.................................... 09 0.00e+00 0.00e+00 2.12e 05 6.32e 05 Y'91 Y 91e 5.78e-05 0.00e+00 1.55e 06 0.00e*00 0.00e+00 2.13e-04 4.81e 05 Y*92 3. h 11 0.00e+00 1.27e.12 0.00e+00 0.00e+00 2.40e-07 1.66e 10 1.29e 09 0.00e+00 3.77e 11 0.00e+00 0.00e+00 1.96e 06 9.19e 06 Conversion factors are in mite of arem per pel inheted.
UNT-005-014 Revision 4 Attachment 6.20 (1 of 24) 265
DOSE CONVERSION FACTORS ALL AGE GROUPS BY tlVCLIDE (INHALATION AND INGESTION)
Inhalation Oose conversion factors for Adult age gro w by nuclide.
Waterford Steam Electric Station Nuclide Organ Does Conversion Factors Sone Liver T. Sody Thyroid Kidney Lung GI LLI Y 93 Zr-95 1.18e-08 0.00e+00 3.26e 10 0.00e+00 0.00c00 6.06e 06 5.27e-05 Zr 97 1.34e-05 4.30e 06 2.91e 06 0.00e+00 6.77e-06 2.21e 04 1.88e-05 1.21e 08 2.45e 09 1.13e 09 0.00e00 9.84e 06 6.54e 05 kb 95 3.71e 09 Mo 99 1.hu 9.77e 07 5.26e 07 0.00e+00 9.67e 07 6.31e 05 1.30e 05 Tc-101 0.00e+00 1.51e 08 2.87e 09 0.00e+00 3.64e-08 1.14e 05 3.10e 05 5.22e-15 7.52e-15 7.38e-14
........................................ 0.00e+00 1.35e 13 4.99e-08 1.36e-21 Tc 99m Ru-103 1.29e 13 3.64e 13 4.63e 12 0.00e+00 5.52e 12 9.55e-08 5.20e-07 Ru-105 1.91e-07 0.00e+00 8.23e-08 0.00e+00 7.29e 07 6.31e 05 1.38e-05 9.88e-11 0.00e+00 3.89e-1 0.00e+00 1.27e.10 1.37e 06 6.02e 06
......................................1 Ru-106 ........................................
8.64e-06 0.00e+00 1.09e-06 0.00e+00 1.67e 05 1.17e 03 1.14e-04 As 110m 1.35e 06 1.25e 06 7.43e-07 0.00e*00 2.46e06 5.79e 04 3.78e 05 Te-125m 4.27e 07 1.98e-07 5.84e-0
..................................... 8 1.31e.........................................
07 1.55e 06 3.92e 05 8.83e-06 Te 127 fe 127m 1.75et0 1.58e 068.03e 7.21e 11 07 3.87e.11 1.32e-10 6.37e-10 8.14e 07 7.17e 06 Te-129 1. h 07 4.11e 07 5.72e-06 1.20e 04 1.87e 05 6.22e 12 2.99e 12 1.55 12 4.87e 12 2.34e-11 2.42e-07 1.96e 08
..................................e............................................
Te129m Te 131 1.22e-M 5.84e-07 1.98e.07 4.30s.07 4.5Fe-06 1.45e.04 4.79e.05 1.39e-12 7.44e-13 4.49e 13 1.17e 12 5.46e 12 1.74e-07 2.30e 09 Te 131m 8.74e 09 5.45e 09 3.63e 09
........................................ 6.88e 09 3.86e-08 1.82e 05 6.95e 05 Te-132 t 130 3.25e 08 2.69e-04 2.02e-08 2.37e 08 1.82e 07 3.60e-05 6.37e 05 I 131 5.72e 07 1.68e 06 6.60e-07 1.42a 04 2.61e 06 0.00e+00 9.61e-07 3.15e.06 4.47e06 2.56e-
........~........................... 06 1.49e-03 7.66e.06 0.00e+00 7.85e.07 1 132 l 133 1.45e 07 4.07e 07 1.45e 07 1.43e-05 6.48e-07 0.00e+00 5.08e 08 I 134 1.08e 06 1.85c 06 5.65e-07 2.69e-04 3.23e-06 0.00e+00 1.11e 06 8.05e-08 2.16e-07 7
................................ 69e.08 ..............................................
3.73e-06 3.44e-07 0.00ee00 1.26e-10 1 135 Cs 134 3.35e 07 8.73e 07 3.21e 07 5.60e 05 1.39e 06 0.00e+00 6.56e 07 Co 136 4.66e.05 1.06e-04 9.10e-05 0.00e+00 3.50e 05 1.22e 05 1.30e-06 4.88e.06 1.83e05 1
................................ 38e-05 ..............................................
0.00e+00 1.07e 05 1.50e-06 1.46e 06 Ca 137 Cs 138 5.98e-05 7.76e-05 5.35e-05 0.00e+00 2.78e 05 9.40e-06 1.05e 06 8e 139 4.14e 08 7.76e-08 4.05e-08 0.00e00 6.00e 08 6.07e 09 2.33e 13 1.17e.10 8.32e-14 3.42e 12 0.00e+00 7.7Be 14 4.70e 07 1.12e 07 Conversion factere are in units of ares per pCl (theted.
UNT-005-014 Revision 4 Attachment 6.20 (2 of 24) 266
1
. 1 DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l l
l I
l Inhetstion Dose Conversion f actors for Adult age group by nuclide.
Waterford Steam Electric Station Nuclide Organ Dose Conversion Factors l
Bone Liver T. Body thyroid Kidney Lms Cl LLI
]
sa 140 4.88e 06 6.13e 09 3.21e 07 0.00e+00 2.09e 09 1.59e 04 2.73e 05 Ba-141 1.25e-11 9.41e-15 4.20e 13 0.00e+00 8.75e 15 2.42e 07 1.45e-17 Ba 142 3.29e 12 3.38e 15 2.07e 13 0.00e+00 2.86e-15 1.49e 07 1.96e-26 La 140 ]
4.30e 08 2.17e 08 5.73e 09 0.00e+00 0.00e+00 1.79e-05 5.73e 05 La 142 8.54e 11 3.88e-11 9.65e-12 0.00e+00 0.00e+00 7.91e 07 2.64e 07 Co 141 2.49e 06 1.69e-06 1.91e-07 0.00e+00 7.83e 07 4.52e-05 1.50e 05
............................................................................... 1 Co 143 2.334 08 1.72e 08 1.91e 09 0.00e+00 7.60e 09 9.97e 06 2.83e-05 l Co 144 4.29e 04 1.79e 04 2.30e 05 0.00e+00 0.00e+00 9.72e 04 1.02e 04 :
Pr-143 1.17e-06 4.69e 07 5.80e 08 0.00e+00 2.70e-07 3.51e 05 2.50e-05 l Pr.144 3.76e 12 1.56e 12 1.91e 13 0.00e+00 8.81e 13 1.27e 07 2.69e 18 Nd-147 6.59e 07 7.62e 07 4.56e 08 0.00e+00 4.45e 07 2.76e 05 2.16e 05 W 187 1.06e 09 8.85e-10 3.10e 10 0.00e+00 0.00e+00 3.63e-06 1.94e-05 Np 239 2.87e 08 2.82e 09 1.55e 09 0.00e+00 8.75e 09 4.70e 06 1.49e 05 Conwereton festere are in unite of arem per pCi inhaled.
i i
l i
i UNT-005-014 Revision'4 Attachment 6.20 (3 of 24) 267
DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) 4 Inhalation Dose Conversion f actors for Teen age group Dy nuclide.
Waterford Steen Electric station Nuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kimey Lung Gl*LLI N3 0.00e+00 1.59e 07 1.59e-07 1.59e 07 1.59e 07 1.59e-07 1.59e-07 C 14 3.25e 06 6.09e 07 6.09e-07 6.09e 07 6.09e 07 6.09e 07 6.09e-07 No 24 1.72e 06 1.72e 06 1.72e 06 1.72e 06 1.72e 06 1.72e 06 1.72e 06 P 32 2.h04 1.37e 05 8.95e 06 0.00e+00 0.00e+00 0.00e+00 1.16e 05 Cr 51 0.00e+00 0.00e+00 1.69e 08 9.37e 09 3.84e.09 2.62e-06 3.75 e-07 Mn 54 0.00e+00 6.39e.06 1.05e 06 0.00e+00 1.59e-06 2.48e-04 8.35e 06 Mn.56 0.00e+00 2.12e-10 3.15e-11 0.00e+00 2.24e.13 1.90e-06 7.18e 06 Fe 55 4.18e-06 2.h06 6.93e-07 0.00e*00 0.00e+00 1.55e-05 7.99e-07 Fe.59 1. h 09 4.62e-06 1.79e.06 0.00e+00 0.00e+00 1.91e.04 2.23e 05 Co 58 0.00e+00 2.h07 3.47e 07 0.00e+00 0.0fe+00 1.68e-04 1.19e 05 Co-60 0.03e+00 1.89e 06 2.48e-06 0.00e+00 0.00e+00 1.09e-03 3.24e 05 N1 63 7.23e 05 5.43e 06 2.47e 06 0.00e+00 0.00e+00 3.84e 05 1.77e 06 Ni.65 2.73e.10 3.66e-11 1.59e-11 0.00e+00 0.00e+00 1.17e.06 4.59e-06 Cu-64 0.00e+00 2.54e.10 1.06e 10 0.00e+00 8.01e 10 1.39e-06 7.68e 06 Zn 65 4.82e 06 1.67s 03 7.80e.06 0.00e+00 1.08e 05 1.55e 04 5.83e 06 2n-69 6.06e.12 1.15e 11 it.07e 13 0.00e+00 7.53e 12 1.90e-07 3.56e-08 Br-83 0.00e+00 0.00e+00 4.30e 08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br 84 0.00e+00 0.00e+00 5.41e 08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br 85 0.00e+00 0.00e+00 2.29e 09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rba6 0.00e+00 2.38e.05 1.05e.05 0.00e*00 0.00e+00 0.00e+00 2.21e 06 R688 0.00e+00 6.82e-08 3.40e.08 (.00e+00 0.00e+00 0.00e+00 3.65e-15 A>89 1.00e+00 4.40e 08 2.91e 08 0.00e+00 0.00e+00 0.00e+00 4.22e 17 sr-89 5.43e 05 0.00e+00 1.56e-06 0.00e*00 0.00e*00 3.02e 06 4.64e-05 Sr.90 1.35e 02 0.00e+00 8.35e-04 0.00e*00 0.00e+00 2.06e-03 9.56e 05
......................................... .................................... l Sr 91 1.10e-08 0.00e+00 4.h 10 0.00e+00 0.00e+00 7.59e-06 3.24e 05 '
tr.92 1.19e.09 0.00e+00 5.00e.11 0.00e+00 0.00e+00 3.43e 06 1.49e 05 T.90 3. h 07 0.00e+00 1.00e-00 0.10e+00 0.00e+00 3.66e.05 6.99e-05 Y*91 8.26e 05 0.00e+00 2.21e-06 0.00e+00 0.00e*00 3.67e 04 5.11e 05 Y tie 4.63e-11 0.00e+00 1.77e 12 0.00e+00 0.00e+00 4.00e 07 3.77e 09 Y 92 1.84e-09 0.00e+00 5.36e-11 0.00e+00 0.00e+00 3.35e 06 2.06e 05 Convereien facters are in units of ares per pCl inheted.
i f
UNT-005-014 Revision 4 Attachment 6.20 (4 of 24) 268
. i i ;
DOSE CONVERSION FACTORS ALL AGE GROUPS 1
1
) BY NUCLIDE (INHALATION AND INGESTION)
J l
l l
4 l
Inhetetton Oose Conversion factors for Teen age gro w by nuclide.
Waterford Steen Electric Station l Nuclide Organ Dose Conversion Factors Bone I.iver T. Sody Thyroid Kidney Lung GI LLI
)
Y 93 Zr 95 1.69e-08 0.00e+00 4.65e.10 0.00e+00 0.00e+00 1.04e-05 7.24e 05
- 1.82e 05 5. & 06 3.94e 06 0.00e+00 8.42e 06 3. h -04 1.86e 05 Zr 97
'1.72e-08 3.40e 09 1.57e 09 0.00e+00 5.1
..................................................... 5e 09 .........................
1.62e 05 7.88e 05 Nb 95 Mo-99 2.32e 06 1.29e 06 7.08e 07 0.00e+00 1.25e-06 9.39e 05 1.21e 05 Tc 101 0.00e+00 2.11e 08 4.03e 09 0.00e+00 5.14e 08 1.92e-05 3. m -05 7.40e-15 1.05e 14 1.03e 13 0.00e+00 1 8. m 08 1.09e 16 Tc 99m 90e..........................
13 Ru-103 1.73e 13 4.83e 13 6.24e 12 0.00e+00 7.20e 12 1.44e-07 7.66e-07 Ru.105 2.63e 07 0.00e+00 1.12e-07 0.00e+00 9.29e 07 9.79e 05 1. W 05 1.40e.10 0.00e+00 5.42e.11 0.00e+00 2.27e 06 1.13e 05
..................................................1.76e.10 Ru 106 A9 110m 1.23e 05 0.00e+00 1.55e 06 0.00e+00 2.38e.05 2.01e 03 1.20e M To.125m 1. & -66 1.64e-06 9.99e.07 0.00e*00 3.13e 06 8.44e 04 3.41e-05 6.10e 07 2.80c07 8.34e 08 1.
........................................ 75e-07 ....................................
0.00e+00 6.70e 05 9.38e 06 T**127 2.51e 10 1.14e.10 5.52e 11 1.77e 10 9.10e.10 1.40e-06 1.01e-05 Te 127m To.129 2.25e 06 1.02e 06 2.73e 07 5.48e 07 8.17e 06 2.07e 04 1.99e.05 8.87e-12 4.22e-12 2.20e-12 6.4
.......................................... 8e=12 3.32e.11 4.12e 07 2.02e 07 Te 129m To.131 1.76e.06 8.23e-07 2.81e.07 5.72e 07 6.49e 06 2.47e+M 5.06e-05 Te-131m 1.97e-12 1.04e-12 6.30s.13 1.55e*12 7.72e+12 2.92e 07 1.89e 09 1.23e.08 7.51e 09 5.03e 09 9
.......................................... 06e+09....................................
5.49e-08 2.97e 05 7.76e 05
, Te 132 -
l-130 4.50e 08 .3.63e 08 2.74e 08 3.07e 08 2.44e 07 5.61e 05 5.79e-05 <
I 131 7.80e 07 2.24e 06 8.96e-07 1.86e 04 3.44e 06 0.00e+00 1.14e-06 I 4.43e 06 6.14e 06 3.30e 06 03 1.05e 05 0.00e+00 8.11e 07
.........................................1.83e 1 132 1 133 1.99e.07 5.47e 07 1.97e 07 1.89e 05 8.65e-07 0.00e+00 1.59e 07
!*134 1.52e 06 - 2.56e 06 7.78e 07 3.65e 04 4.49e.06 0.00e+00 1.29e 06 1.11e 07 2.90e 07 1.05e+07 4 4.58e.07 0.00e*00 2.55e 09
!*135 96e-06 Cs 134 4.62e-07 1.18e.06 4.36e.07- 7.h.05 1.86e.06 0.00e+00 8.69e 07 Cs 136 6.28e-05 1.41e.06 4.86e 05 0.00e*00 4.69e-05 1.83e-05 1.22e 06 6.44e 06 2.42e 05 1.71e+05
....................................... ,. 00e+000 1.38e.05 2.22e-06 1.36e 06 Cs 137 Cs 138 8.38e*05 1.06e-04 3.89e.05 0.00e+00 3.80e-05 1.51e 05 1.06e 06 8e.139 5.82e 08 1.07e 07 5.58e 08 0.00e+00 8.28e.08 9.84e 09 3.38e 11 1.67e 10 1.18e.13 4.87e 12 0.00e+00 1.11e 13 8.08e-07 8.06e-07 Conversion f acters are in units of arem per pCi irheted.
I l
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l UNT-005-014 Revision 4 Attachment 6.20 (5 of 24) i 269 1
1
. - , . - . -- - . .- -l
00SE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l l
l Inhalation Dose Converston factors for Teen age group by nuclide.
I Waterford Steam Electric Station Nuclide Organ Dose Conversion Factors l
Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba 140 6.84e 06 8.38e-09 4.40e 07 0.00e+00 2.85e 09 2.54e 04 2.86e-05 Ba 141 1.78e-11 1.32e-14 5.93e-13 0.00e+00 1.23e 14 4.11e 07 9.33e 14 Ba 142 t. 62e 12 4.63e 15 2.84e-13 0.00e+00 3.92e 15 2.39e-07 5.99e 20 l
............................................................................... 1 La 140 5.99e 08 2.95e-08 7.82e 09 0.00e+00 0.00e+00 2.68e-05 6.09e 05 )
La 142 1.20e 10 5.31e 11 1.32e 11 0.00e+00 0.00e+00 1.27e 06 1.50e-06 Ce 141 3.55e 06 2.37e 06 2.71e 07 0.00e+00 1.11e 06 7.67e 05 1.58e 05 Co 143 3.32e 08 2.42e 08 2.70e-09 0.00e+00 1.08e-08 1.63e-05 3.19e-05 '
Ce 144 6.11e 04 2.53e 04 3.28e-05 0.00e+00 1.51e-04 1.67e 03 1.08e-04 Pr*143 1.67e-06 6.64e-07 8.28e 08 0.00e+00 3.86e 07 6.04e 05 2.67e 05 !
Pr-144 5.37e 12 2.20e-12 2.72e 13 0.00e+00 1.26e 12 2.19e 07 2.94e 14 Nd-147 9.834 07 1.07e 06 6.41e 08 0.00e+00 6.28e 07 4.65e-05 2.28e-05 W 187 1.50e 09 1.22e-09 4.29e-10 0.00e+00 0.00e+00 5.92e 06 2.21e 05 Np 239 4.23e-08 3.99e-09 2.21e-09 0.00e+00 1.25e.08 8.11e 06 1.65e 05 Conversion f actors are in units of arem per pCf Irheted.
l I
UNT-005-014 Revision 4 Attachment 6.20 (6 of 24) l 270 l
DOSE CONVERSZON FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l Inhalation Oose Conversion factors for Child age group by nuctide.
Waterford Steam Electric Station Nuctide Organ Dose Conversion Factors Bone Liver T. Body Thyreld K f chey Lung G! LLI l
H3 C 14 0.00e+00 3.04e 07 3.04e 07 3.04e 07 3.04e 07 3.04e 07 3.04e 07 l- No 24 9.70e 06 1.82e 06 1.82e-06 1.82e-06 1.82e-06 1.82e 06 1.82e 06 l- 4.35e 06 4.35e 06 4.35e-06 4.35e 0
............................................... 6 4.35e-06 4.35e 06 '4.35e 06 P 32 Cr-51 7.04e 04 3.09e 05 2.67e 05 0.00e+00 0.00e+00 0.00e+00 1.14e 05 Mn-54 0.00e+00 0.00e+00 1. 0.00e+00 4.17e 06 2.31e 08 6.57e-09 4.59e-06 2.93e 07 W-05 2.57e 06
........................................ 0.00e+00 2.71e 06 4.26e-04 6.19e 06 Mn 56 Fe-55 0.00e+00 4.68e-10 8.43e-11 0.00e+00 4.52e 10 3.55e-06 3.33e-05 Fe-59 1.28e-05 6.80e 06 2.10e06 0.00e*00 0.00e+00 3.00e-05 7.75e-07 5.59e-M 9.06e 06 4.51e 06
........................................ 0.00e*00 0.00e+00 3.43e 04 1.91e 05 Co 58 Co-60 0.00e+00 4.79e 07 8.55e 07 0.00e+00 0.00e*00 2.99e.06 9.29e 06 NI 63 0.00e+00 3.55e 06 6.12e 06 0.00e+00 0.00e+00 1.91e 03 2.60e 05 2.22e 04 1.25e-05 7.56e-l
.................................... 06 0.00e*00 0.00e+00 7.43e 05 1.71e 06 N1 65 Cu 64 8.08e 10 7.99e 11 4.44e.11 0.00e+00 0.00e+00 2.21e 06 2.27e 05 Zn 65 0.00e+00 5.39e 10 2.90e-10 0.00e+00 1.63e-09 2.59e06 9.92e 06 1.15e-05 3.06e 05 1.90e-0
..................................... 5 0.00e+00 1.93e-05 2.69e.06 4.41e 06 2n 49 Br 83 1.81e 11 2.61e 11 2.41e.12 0.00e+00 1.58e.11 3.86e 07 2.75e-06 Br 84 0.00e+00 0.00e+00 1.28e+07 0.00e+00 0.0Ge+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1
................................ 48e 07 ..............................................
0.00e+00 0.00e*00 0.00e*00 0.00e*00 Br.85 Rb 86 0.00e+00 0.00e+00 6.86e 09 0.00e*00 0.00e*00 0.00e+00 0.00e+00 Rb 88 0.00e+00 5.36e 05 3.09e-05 0.00e+00 0.00e+00 0.00e+00 2.16e-06 0.00e+00 1.52e.07 9.90e-
................................... 00 0.00e+00 0.00e+00 0.00e+00 4.66e.09 Ab 89 Sr-89 0.00e*00 9.33e 08 7.85e 08 0.00e+00 0.00e+00 0.00e+00 5.11e 10 tr-90 1.62e-06 0.00e*00 4.66e-06 0.00e*00 0.00e+00 5.83e-04 4.52e 05 2.73e02 0.00e+00 1.76e.0
..................................... 3 0.00e+00 0.00e+00 3.99e.03 9.28e 05 Sr 91 se 92 3.28e 08 0.00e+00 1.24e-09 0.00e+00 0.00e+00 1.44e05 4.70e 05 Y 90 3.54e-09 0.00e+00 1.42e-10 0.00e+00 0.00e+00 6.69e.06 6.55e-05 1.11o.06 0.00e+00 2.99e.0
..................................... 0 0.00e*00 0.00e+00 7.07e-05 7.24e 05 Y-91 Y tie 2.47e-06 0.00e+00 6.59e 06 0.00e+00 0.00e*00 7.10e.06 4.97e05 Y 92 1.37e10 0.00e+00 4.90s.12 0.00e+00 0.00e*00 7.60e.07 4.66e-07 5.50e-09 0.00e+00 1.57e 10 0.00e*00 0.00e+00 6.46e.06 6.46e 05 Conversion factors are in unite of arem per pcl inheted.
1 1
UNT-005-014 Revision 4 Attachment 6.20 (7 of 24) 271 l-l l
i
. . . - . . ~ ..
\
.t \
P DOSE CONVERSION FACTORS ALL AGE GROUPS i
BY NUCLIDE (INHALATION AND INGESTION)
I d
1 1
1 Inhalation Oose Conversion factors for Child age group Oy nuclide.
Waterford Steam Electric Station Nuclide Organ 00se Conversion Factors
)
1 Bone Liver T. Body Thyroid Kidney Lung GI LLI J
i Y 93 5.04e 08 0.00e+00 1.38e 09 0.00e+00 0.00e+00 2.01e 05 1.05e 04
- Zr 95 5.13e 05 1.13e 05 1.00e 05 0.00e+00 1.61e 05 6.03e 04 1,65e-05 2
Zr-97 5.07e 08 7.34e 09 4.32e 09 0.00e+00 1.05e 08 3.06e 05 9.49e 05 4
Nb 95 6.35e 06 2.48e 06 1.77e 06 0.00e+00 2.33e-06 1.66e M 1.00e 05 1- Mo-99 0.00e+00 4. W -08 1.15e-08 0.00e00 1.06e-07 3. W -05 3.42e 05 l Tc 101 2.19e 14 2.30e 14 2.91e 13 0.00e+00 3.92e 13 1.58e-07 4.41e 09 Tc 99m 4.81e 13 9.41e 13 1.h11 0.00e*00 1.37e 11 2.57e-07 1.30e 06 tu-103 7.55e 07 0.00e+00 2.90c07 0.00e+00 1.90e-06 1.79e 04 1.21e 05 Ru-105 4.13e 10' O.00e+00 1. h 10 0.00c00 3.63e-10 4.30e 06 2.69e 05 Ru 106 3.68e 05 0.00e+00 4.57e 06 0.00e+00 4.97e-05 3.87e 03 1.16e M j
As 110m 4.h06 3.08e-06 2.47e 06 0.00e+00 5.74e 06 1.48e-03 2.71e 05 l Te 125m 1.82e 06 6.29e 07 2.47e 07 5.20e 07 0.00e+00 1.29e 04 9.13e 06 3
............................................................................... l Te 127 7.49e-10 2.57e 10 1.65e 10 5.30e 10 1.91e-09 2.71e 06 1.52e 05 1
'Te 127h 6.72e-06 2.31e-06 8. W-07 1.64e 06 1.72e-05 4.00e 04 1.93e 05
- Te 129 2.64e-11 9.45e 12 6.44e 12 1.93e-11 6.96e.11 7.93e-07 6.89e 06 Te-129m 5. h 06 1.85e-06 8.22e 07 1.71e-06 1.36e-05 4.76e.M 4.91e-05 t To.131 5.87e 12 2.28e 12 1.78e.12 4.59e-12 1.59e-11 5.55e 07 3.60e 07 Te*131a 3.63e 08 1.60e 08 1.37e-08 2.64e-08 1.08e-07 5.56e-05 8.32e 05
)
d Te 132 1.30e-07 7. W 08 7.12e 08 8. m 08 4.79e 07 1.02e-04 3.72e 05 l 130 2.21e 06 4.43c06 2.28e-06 4.99e 04 6.61e 06 0.00e+00 '1.38e*06 1 131 1.30e 05 1.30s 05 7.37e 06 4.39e-03 2.13e 05 0.00e+00 7.68e 07 j 1 132 5.72e 07 1.10e 06 5.07e 07 5.23e-05 1.69e 06 0.00e+00 8.65e 07 1 133 4.48e-06 5.49e-06 2.08e-06 1.04e.03 9.13e 06 0.00e+00 1.48e 06 1 1 134 3.17e 07 5.84e 07 2.69e 07 1.37e 05 8.92e 07 0.00e+00 2.58e 07 1 135 1.33e 06 2.36e 06 1.12e-06 2.14e 04 3.62e-06 0.00e+00 1.20e 06 Cs 134 1. W 04 2.74e M 6.07e-05 0.00e+00 8.93e 05 3.27e 05 1.04e 06 Cs 136 1. N -05 4.62e 05 3.14e 05 0.00e+00 2.58e 05 3.93e-06 1.13e 06 Cs 137 2.45e-M 2.23e-M 3.47e-05 0 Joe +00 7.63e-05 2.81e-05 9.78e 07 Cs 135 1.71e 07 2.27e 07 1. h 07 0.00e+00 1.68e 07 1.84e-08 7.29e 08 Be 139 4.90e 10 2. 6 13 1.45e.11 0.00e+00 2.33e 13 1. W 06 1. W -05 Corwereien facters are in units of aren per pcl inhaled.
I UNT-005-014 Revision 4 Attachment 6.20 (8 of 24) 272 1
i
r DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Inhalation 'ose
. Converston factors for Child age group Dy nuctide.
Waterford Steam Electric Station Nuctide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kidney Lung GI LLI Ba 140 2.00e 05 1.75e 08 1.17e 06 0.00e+00 5.71e 09 4.71e 04 2.75e 05 Be 141 5.29e 11 2.95e 14 1.72e 12 0.00e+00 2.56e-14 7.89e 07 7.44e 08 Ba-142 1.35e 11 9.73e-15 7.54e-13 0.00e+00 7.87e 15 4.44e 07 7.41e 10 l La 140 1.74e 07 6.08e OS 2.04e 08 0.00e+00 0.00e+00 4.94e 05 6.10e 05 l La 142 3.50e-10 1.11e 10 3.49e 11 0.00e+00 0.00e+00 2.35e 06 2.05e 05 Co 141 1.06e 05 5.28e 06 7.83e 07 0.00e+00 2.31e 06 1.47e 04 1.53e 05 Co 143 9.89e 08 5.37e 08 7.77e 09 0.00e+00 2.26e-08 3.12e 05 3.44e 05 Ce 144 .1.83e 03 5.72e 04 9.77e 05 0.00e+00 3.17e 04 3.23e-03 1.05e 04 Pr.143 4.99e.06 1.50e 06 2.47e 07 0.00e+00 8.11e-07 1.17e-04 2.63e 05 Pr 144 1.6te.11 4.99e.12 8.10e 13 0.00e+00 2.64e-12 4.23e-07 5.32e 08 Nd 147 2.92e 06 2.36e 06 1.84e 07 0.00e+00 1.30e-06 8.87e 05 2.22e 05 W 187 4.41e 09 2.61e 09 1.17e 09 0.00e+00 0.00e+00 1.11e 05 2.46e-05 Np-239 1.26e 07 9.04e 09 6.35e 09 0.00e+00 2.63e 08 1.57e 05 1.73e 05 Corwersion f actors are in mits of aram per pcl inhaled.
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4 UNT-005-014 Revision 4 Attachment 6.20 (9 of 24) 273
DOSE CONVERS10N FACTORS ALL AGE GROUPS i
BY NUCLIDE (INHALATION AND INGESTION)
InheLation Oose Conversion factors for Infant age grota ey nuclide.
Waterford Steae Electric Station Nuctide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kidriey Lung GI LLI H3 C 14 0.00e+00 4.62e 07 4.62e 07 4.62e 07 4.62e 07 4.62e 07 4.62e 07 Na*24 1.89e 05 3.79e-06 3.79e 06 3.79e.06 3.79e 06 3.79e 06 3.79e 06 7.54e-06 7.54e 06 7.54e 06 7.54e-06 7 P 32 54e-06..........................
7.54e 06 7.54e 06 Cr 51 1.45e 03 8.03e 05 5.53e-05 0.00e+00 0.00e+00 0.00e+00 1.15e 05 Mn-54 0.00e+00 0.00e+00 6.39e 08 4.11e 08 9.45e 09 9.17e 06 2.55e 07 0.00e*00 1.81e 05 3. W 06 0
.......................................... 00e+00 3. W 06 7.14e 04 5.04e 06 Mn-56 0.00e+00 1.10e 09 Fe-55
- 1. m 10 0.00e*00 7. h 10 8.95e 06 5.12e 05 Fe-59 1.41e 05 8.39e-06 2.38e 06 0.00e+00 0.00e+00 6.21e.05 7.82e 07 9.69e 06 1.68e-05 6.77e 06 0
.......................................... 00e*00 ....................................
0.00e*00 7.25e-04 1.77e 05 Co-58 co-60 0.00e+00 8.71e 07 1.30e-06 0.00e+00 0.00e+00 5.55e 04 7.95e 06 Ni 63 0.00e+00 5.73e 06 8.41e 06 0.00e+00 0.00e+00 3.22e 03 2.28e 05 2.42e 04 1.46e 05 8.29e-06
........................................ 0.00e+00 0.00e+00 1.49e-04 1.73e-06 Ni 65 Cu 64 1.71e 09 2.03e 10 8.79e 11 0.00e+00 0.00e*00 5.80e 06 3.58e 05 2n-65 0.00e*00 1.34e 09 5.53e 10 0.00e+00 2.84e 09 6.64e 06 1.07e 05 1.38e.05 4.47e 05 2
................................ 22e-05..............................................
0.00e+00 2.32e 05 4.62e 04 3.47e 05 2n-69 Sr-43 3.85e-11 6.91e-11 5.13e-12 0.00e+00 2.87e-11 1.05e.06 9.44e.06 Br*84 0.00e+00 0.00e+00 2.72e 07 0.00e+00 0.00e+00 0.00e*00 0.00e*00 0.00e+00 0.00e+00 2.86e 07
........................................ 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Br-85 Ab-86 0.00e+00 0.00e+00 0.00e+00 1.46e-08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb 88 1. m 06 6.30e 05 0.00e+00 0.00e+00 0.00e+00 2.17e 06 0.00e+00 3.98e-07 2
............................... 05e 07 ..............................................
0.00e+00 0.00e+00 0.00e+00 2.42e-07 Rb-89 SP 49 0.00e+00 2.29e 07 1.47e 07 0.00e+00 0.00e+00 0.00e+00 4.87e 08 SP*90 2.84e-04 2.92e-02 0.00e+00 1 0.00e+00 8.15e-06 0.00e+00 0.00e+00 1.45e-03 4.57e 05 0.00e+00 0.00e+00 8.03e 03 9. W 05
................................ 85e-03..............................................
Sr-91 Sr-92 4.43e-08 0.00e+00 2.47e 09 0.00e+00 0.00e+00 3. N 05 5.24e-05 YM 7.50e-09 0.00e+00 2.79e 10 2.35e-06 0.00e+00 6 Y-91 30e 08~ 0.00e+00 0.00e+00 1.70e-05 1.00e-04 0.00e+00 0.00e+00 1.92e-04 7.43e 05 Y*91e 4.20e.04 0.00e*00 1.12e.05 0.00e+00 0.00e+00 1.75e-03 5.02e-05 Y'92 2.91e.10 0.00e+00 9.90e 12 0.00e+00 0.00e*00 1.99e-06 1.68e-06 1.17e 08 0.00e*00 3.29e-10 0.00e+00 0.00e+00 1.75e-05 9.04e-05 Corwersion facters are in initts of aree per pci inheted.
UNT-005-014 Revision 4 Attachment 6.20 (10 of 24) 274
00SE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l l
I I
1 l
Inhelation Oose Conversion factors for Infanc ege group Dy nuclide.
Waterford Steam Electric Statson i
Nuclide Organ Dose Conver. tion factors Bone Liver T. Body Thyroid Kidiey Lung GI LLI r
Y-93 1.07e 07 0.00e+00 2.91e 09 0.00e+00 0.00e+00 5.46e-05 1.19e 04 Zr-95 8.24e 05 1.99e-05 1.45e 05 0.00e+00 2.22e 05 1.25e-03 1.55e 05 I 1r-97 1.07e 07 1.83e 08 8.W 09 0.00e+00 1.85e 08 7.88e 05 1.00e 04 Nb 95 1.12e 05 4.59e 06 2.70e 06 0.00e00 3.37e 06 3.42e 04 9.05e 06 Mo 99 0.00e+00 1.18e 07 2.3?e 08 0.00e+00 1.89e 07 9.63e 05 3.48e-05 Tc 101 4.65e 14 5.88e 14 5.80e 13 0.00e+00 6.99e-13 4.1Te-07 6.03e 07 Tc 99m 9.98e-13 2.06e-12 2~. W 11 0.00e+00 2.22e-11 5.79e-07 1.45e 06 Ru-103 1.44e 06 0.00e+00 4.85e-07 0.00e+00 3.03e 06 3.94e 04 1.15e 05 Ru-105 8.74e-10 0.00e+00 2.93e so 0.00e 00 6.42e 10 1.12e 05 3.46e 05 Ru-106 6.20e 05 0.00e+00 7.77e 06 0.00e+00 7.61e 05 8.26e-03 1.17e 04 AS*110m 7.13e-06 5. W 06 3.57e-06 0.00e+00 7.80e-06 2.62e 03 2.36e-05 Te-125e 3.40e 06 1.42e 06 4.70e-07 1.16e-06 0.00e+00 3.19e-04 9.22e 06 Te.127 1.59e-09 6.81e 10 3.49e 10 1.32e-09 3.47e-09 7.39e-06 1.74e 05 Te 127m 1.19e 05 4.%e 06 1.48e-06 3.48e 06 2.68e-05 9.37a: 04 1.95e 05 Te 129 5.63e-11 2.44e-11 1.34e-11 4.82e-11 1.25e.10 2.14e-06 1.88e-05 Te-129m 1.01e-05 4.35e-06 1.59e-06 3.91e 06 2.27e-05 1.20e 03 4.93e 05 Te.131 1.24e-11 5.87e 12 3.57e 12 1.13e 11 2.85e.11 1.47e-06 5.87e 06 Te-131m 7.62e-06 3.93e 08 2.59e.08 6.36e 08 1.89e-07 1.42e 04 8.51e 05 Te 132 2.66e-07 1.69e 07 1.24e-07 1.99e-07 7.39e-07 2.43e-04 3.15e 05 I-130 4.54e-06 9.91e-06 3.98e-06 1.14e-03 1.09e-05 0.00e+00 1.42e 06 I*131 2.71e 05 3.17e 05 1.40e 05 1.06e 02 3.70e 05 0.00e+00 7.56e-07 3 132 1.21e 06 2.53e 06 8.De 07 1.21e-04 2.82e 06 0.00e+00 1. h -06 I 133 9.46e-06 1.37u.05 4.00e 06 2.54e-03 1.60e-05 0.00e+00 1.54e 06 I-134 6.58e-07 1.34e 06 4.75e 07 3.18e-05 1.49e-06 0.00e+00 9.21e 07 1-135 2. % -06 5.43e 06 1.98c 06 4.97e 04 6.F" 06 0.00*00 1.31e 06 I Cs*134 2.83e-04 5.02e-04 5.32e 05 0.00e00 1. m 04 5.69e-05 9.53e 07 Cs 136 3.45e.05 9.61e-05 3.78e 05 0.00e+00 4.03e-05 8.40e 06 1.02e 06 Cs 137 3.92e-04 4.37e 04 3.25e 05~ 0.00e*00 1.23e 04 5.09e 05 9.53e 07 Cs 138 3.61e-07 5.58e-07 2.84e-07 0.00e 00 2.93e 07 4.67e 08 6.26e 07 8e 139 1.06e-09 7.03e.13 3.07e 11 0.00e00 4.23e-13 4.25e 06 3.64e 05 Cerworsion f actors are in units of aram per pCI inheled.
UNT-005-014 Revision 4 Attachment 6.20 (11 of 24) 275 1
DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Inhalation Dose Conversion factors for Infant age group cy nuclide.
Waterford steam Electric Station Nuclide organ Oose Conversion factors Bone Liver T. Body Thyroid Kithey Lung GI-LLI Ba 140 Ba 141 4.00e-05 4.00e 08 2.07e 06 0.00e+00 9.59e-09 1.14e-03 2.74e 05 1.12e 10 7.70e 14 3.55e 12 0.00e+00 4.64e-14 2.12e 06 3.39e 06 Ba 142 2.84e-11 2.36e-14 1.40e 12 0.00e+00 1.3!e.14 1.11e 06 4.95e 07 La 140 3.61e 07 1.43e 07 3.68e-08 0.00e+00 0.00e+00 1.20e 04 1.06e 05 La 142 7. 10 2.69e-10 6.46e-11 0.00e+00 0.00e+00 5.87e 06 4.25,05
-Co 141 1.98e 05 1.19e-05 1.42e-06 0.00e*00 3.75e-06 3.69e 04 1.54o 05 Ce 143 I
Co 144 2.09e 07 1.38e 07 1.58e 08 0.00e+00 4.03e-08 8.30e 05 3.55e 05 2.28e-03 8.65e 04 1.26e-04 0.00e+00 3.84e 04 7.03e-03 1.06e-04 Pr 143 1.00e 05 3.74e-06 4.99e-07 0.00e+00 1.41e-06 3.09e-04 2 Pr*144 66e-05......
Nd 147 3.42e-11 1.32e-11 1.72e-12 0.00e+00 4.80e 12 1.15e 06 3.06e-06 W 187 5.67e 06 5.81e.06 3.57e 07 0.00e+00 2.25e-06 2.30e 04 2.23e-05 9.26e-09 6.44e-09 2.23e 09 0.00e+00 0.00e+00 2 Wp-239 83e-05 2.54e 05 2.65e 07 2.37e 08 1.34e 08 0.00e+00 4.73e-08 4.25e-05 1.78e 05 C rwersion factors ye in wits of arem per pCi inhaled.
i l
1 UNT-005-014 Revision 4 Attachment 6.20 (12 of 24) 276 l
i DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l Ingestion Dose Conversion factors for Acult age group by nuctide. !
Waterford Steam Electric Station Nuclide Organ Dose Conversion Factors Bone Liver T. Body Thyroid Kichey Li. rig cl.LLI H3 C 14 0.00e+00 1.05e 07 1.05e 07 1.05e 07 1.05e 07 1. 05e 07 1.05e 07 Nea24 2. h 06 1.70e 5.68e 07 5.68e 07 5.68e 07 5.68e 07 5.68e-07 5.68e 07 06 1.70 1.70e-06 1.70e 06 1.70e 06 06 1.70e 06
.........................e-06....................................1.70e P 32 .................
Cr 51 1.93e 04 1.20e 05 7.46e 06 0.00e+00 0.00e+00 0.00e+00 2.17e 05 Mn 54 0.00e+00 0.00e+00 4.570.00e+00 2.66e 09 1.59e 09 5.86e 10 3.53e-09 6.69e-07 8.72e 07 0.00e+00 1.36e 06 0 00e+00 1.40e 05
..........................e06....................................
Mn 56 ................
Fe 55 0.00e+00 1.15e-07 2. h -08 0.00e+00 1.44e-07 0.00e+00 3.67e-06 Fe 59 2.75e
- 4. h -06 06 1.h M3.91e-06 1.02e- 4.43e-07 0.00e+00 0.00e+00 1.06e-06 1.09e-06 Co-58 0.00e+00 0.00e+00 2 35e 06 3.40e 05 05...................................................
Co-60 Ni.63 0.00e+00 7.45e-07 1.67e 06 0.00e+00 0.00e+00 0.00e+00 1.51e 05 0.00e+00 1.30e-04 9.01 2.14e-06 4.72e-06 0.00e+00 0.00e+00 0.00e+00 4.02e 05 4.34e-06 0.00e+00 0.00e+00 1.aSe-06
..........................e06...................................0.00e+00 Ni 65 .................
Cu 64 5.28e 07 6. h 08 3.13e-08 0.00e+00 0.00e+00 0.00e+00 1.74e-06 Zn-65 0.00e+00
- 4. h 06 1.548.33e 06 3.91e-08 0.00e+00 2.10e-07 0.00e+00 7.10e 06 6.96e-06 0.00e*00 1.03 05 0.00e+00 9.70e 0e
.........................e In 69 05..............................e Br-83 1.03e-08 1.97e.06 1.37e-09 0.00e+00 1.28e-08 0.00e+00 2.96e-09 Br-84 0.00e*00 0.00e+00 0.000.00e+00 4.02e 08 0.00e+00 0.00e+00 0.00e+00 5.79e 08 5.21e-08 0.00e*00 0.00e*00 0.00e+00 4.09e 13
.........e...............e+00............................... ......................
Br8605 M.00e+00 0.00e+00 2.14e 09 0.00e+00 0.00e+00 0.00e+00 Rb Rb 86 0.00e+00
[ 0.00e+00 6.0 2.11e 05 9.83e-06 0.00e+00 0.00e+00 0.00e+00 4.16e 06 3.21e 08 0.00e+00 Rb-89 5e 08..........................
0.00e+00 0.00e+00 8.36e 19 1
i Sr 89 0.00e+00 4.01e-08 2.82e-08 0.00e+00 0.00e+00 0.00e+00 2.33e-21 tr 90 3.08e-04 0.00e+00
..... 7.58e.03 0.00e+00 8. h .06 0.00e+00 0.00e+00 0.00e+00 4.94e 05 0.00e+00 0.00e*00 0 00e+00 2.19e 04 )
sr-91..........................1.8de.03..............................
sr-92 5.67e-06 0.00e+00 2.29e.07 0.00e+00 0.00e+00 0.00e+00 2.70e-05 Y.90 2.15e 9.62e 09 06 0.000.00e+00 9.30e 08 0.00e+00 0.00e+00 0.00e+00 4.26e-05 2.58e.10 0.00e+00 0 00e+00 0.00e+00 1.02e 04
.........................e+00...........................
Y 91 ..........................
Y 9te 1.41e-07 0.00e+00 3.77e-09 0"D0e+00 0.00e+00 0.00e+00 7.76e-0 Y 92 9.09e-11 0.00e+00 3.52e.12 0.00e+00 0.00e+00 0.00e+00 2.67e 10 8.45e-10 0.00e+00 2.47e.11 0.00e+00 0.00e+00 0.00e+00 1.48e-05 Conversion factors are in teilts of arem por PCI Ingested.
i i J
(
UNT-005-014 Revision 4 Attachment 6.20 (13 of 24) 277 i
DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Ingestion Dose Conversion f actors f or Adult age group Dy nuclide.
Waterford Steam Electric Ctetton Nuclide Organ Dose Conversion factors Bone Liver T. Body Thyroid Kichey Lung GI-LLI Y 93 Zr-95 2.68e 09 0.00e+00 7.40e 11 0.00e+00 0.00e+00 0.00e+00 8.50c05 I Zr-97 3.04e-08 9.75e 09 6.60e 09 0.00e00 1.53e-08 0.00e+00 3.09e 05 1.68e-09 3.39e-10 1.55e 10 0.00e+00 5.1 Nb-95 2e-10 .........................
0.00c 00 1.05e 04 ;
6.22e 09 Mo-99 3. W 09 1.86e 09 0.00w00 3.42e-09 0.00e+00 2.10e-05 Tc-101 0.00e+00 4.31e 06 8.20e 07 0.00e+00 9.76e 06 0.00e+00 9.99e 06 2.54e-10 3.66e-10 3.59e 09 0.0
........................................... 0e+00 6.59e-09 1.87e 10 1.10e 21 Tc 99m ]
Ru-103 2.47e 10 6.98e-10 8.89e 09 0.00e+00 1.06e-08 3.42e-10 4.13e 07 1.85e 07 0.00e+00 7.97e 08 0.00c00 7. W 07 0.00e+00 2.16e-05 Ru 105 )
1.54e 08 0.00e+00 6.08c 09 0.00e+00 0.00e+00 9.42e 06
...................................................1.99e-07 Ru 106
........................... l 2.75e-06 0.00e+00 3.48e 07 0.00e+00 5.31e 06 0.00e+00 1.78e 04 '
As 110m 1.60e 07 1.48e 07 8.79e 08 0.00e+00 2.91e 07 0.00e+00 6.04e 05 Te 125m 2.68e-06 9.71e 07 3.59c07 8
.......................................... 06n.07 1.09e 05 0.00e+00 1.07e 05 Te 127 1.10e-07 3.95e 08 2.38e-08 8.15e 08 4.48e 07 0.00e+00 8.68e 06 Te 127m 6.77e 06 2.42e 06 8.25e-07 To.129 1.73e-06 2.75e 05 0.00e+00 2.27e 05 3.14e.08 1.18e 08 7.65e 09
........................................ 2.41e-08 1.32e 07 0,00e+00 2.37e 08 Te.129m Te.131 1.15e 05 4.29c06 1.82e 06 3.95e-06 4.80e 05 0.00e+00 5.79e-05 Te 131m 1.97e-08 8.23e 09 6.22e-09 1.62e-08 8.63e 08 0.00e+00 2.79e-09 1.73e 06 8.46e 07 7.05e 07 06 8.57e-06 0.00e+00 8.40e-05
.........................................1.34e Te 132 1 130 2.52e
- 7. 06 1.63e06 1.53e-06 1.80e 06 1.57e 05 0.00e00 7.71e 05 t 131 -07 2.23e 06 8.80e 07 1.89e-04 3.48e 06 0.00e+00 1.92e 06 4.16e-06 5.95e-06 3.41e-06
.........................................1.95e 03 1.02e 05 0.00e+00 1.57e-06 1 132 t 133 2.03e-07 5.43e.07 1.90e07 1.90e-05 8.65e-07 0.00e00 1.02e-07 1 134 1.42e-06 2.47e 06 7.53e-07 3.63e-04 4.31e 06 0.00e+00 2.22e 06
- 1. h -07 2.88e.07 1.03e-07 4
.......................................... 99e-06 ....................................
4.58e-07 0.00e+00 2.51e-10 I.135 4.43e 07 Cs 134 1. W-06 4.28e07 7. m -05 1. h 06 0.00e00 1.31e 06 Cs-136 6.22e-05 1.48e 04 1.21e.04 ~0.00e00 4.79e.05 1.59e-05 2.59e-06 6.51e-06 2.57e-05 1.85e 05
............................ ........... 0.00e+00 1.43e.05 1.96e 06 2.92e 06 Cs 137 Cs 138 7.97e 05 1.09e 04 7.14c 05 0.00e00 3.70e 05 1.23e-05 2.11e 06 8e-139 5.52e-08 1.09e-07 5.40e-08 0.00e00 8.01e 08 7.91e-09 4.65e-13 9.70e 08 6.91e.11 2.84e.09 0.00e00 6.46e.11 3.92e 11 1.728 07 Comersion facto.s are in tetits of aram per pcl ingested.
UNT-005-014 Revision 4 Attact. ment 6.20 (14 of 24) 278
DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
In0estion 00se Conversion f actors for Adult age group tn nuclide.
Waterford Steam Electric Station Nuclide Organ Dose Conversion Factors Bone Liver T. Sody Thyroid Kichwy Lung Cl LLI l
Ba 140 2.03e 05 2.55e-08 1.33e 06 0.00e+00 8.67e-09 1.46e 08 4.18e-05 '
sa-141 4.71e 08 3.56e-11 1.59e 09 0.00e+00 3.31e 11 2.02e 11 2.22e 17 )
Ba 142 2.13e 08 2.19e-11 1.34e 09 0.00e+00 1.85e-11 1.24e 11 3.00e 26 .
.................................. ................ ........................... )'
La 140 2.50e 09 1.26e 09 3.33e 10 0.00e+00 0.00e+00 0.00e+00 9.25e 05 La 142 1.28e-10 5.82e-11 1.45e-11 0.00e+00 0.00e+00 0.00e+00 4.25e-07 !
Co 141 9.36e 09 6.33e 09 7.18e 10 0.0CM 2.94e 09 0.00e+00 2.42e 05 l co 143 1.65e-09 1.22e-06 1.35e*10 0.00e+00 5.37e 10 0.00e+00 4.56e 05 I Co 144 4.88e-07 2.04e-07 2.62e-08 0.00e+00 1.21e 07 0.00e+00 1.65e 04 Pr-143 9.20e 09 3.69e-09 4.56e-10 0.00e+0C 2.13e 09 0.00e+00 4.03e 05 Pr 144 3.01e-11 1.25e 11 1.53e 12 0.00e+00 7.05e-12 0.00e+00 4.33e-18 Nd-147 6.29e-09 7.27e 09 4.35e-10 0.00e+00 4.25e 09 0.00e+00 3.49e 05 W 187 1.03e 07 8.61e 08 3.01e 08 0.00e*00 0.00e+00 G.00e+00 2.82e 05 hp 239 1.19e 09 1.17e 10 6.45e-11 0.00e*00 3.65e 10 0.00e+00 2.40e-05 Corworsion factors are in mite of arem por pC1 Ingested.
i I
f UNT-005-014 Revision 4 Attachment 6.20 (15 of 24) 279
. __ - _ . . _ ._._..m__ _
DOSE CONVERSION FACTORS ALL AGE GROUPS BY HUCLIDE (INHALATION AND INGESTION) i ingestion Dose Conversion factors for Teen age group by nuclide, Waterford steen Electric station f t
Nuclide Organ Dose Cor. version factors tone Liver T. Body Thyroid Kidney Lung Cl LLI H3 '
t C 14 0.00e+00 1.06e 07 1.06e 07 1.06e 07 1.06e 07 1.06e-07 1.06e 07 Na 24 4.06e 06 8.12e 07 8.12e 07 8.12e 07 8.12e 07 8.12e 07 8.12e 07 j 2.30e-06 2.30e 06 2.30e 06 2.30 06 2.30e-06 2.30e 06 2.30e-06
.............................................e P 32 Cr 51 2.76e 04 1.71e 05 1.07e 05 0.00e+00 0.00e+00 0.00e+00 2.32e 05 w S4 0.00e*00 0.00e+00 3.60e 09 2.00e 09 7.89e-10 5.14e-09 6.05e 07 0.00e+00 5.90e 06 1.17e-06 0.0 1. % -06 0.00e+00 1.21e-05 w 56 0e+00 ...................................
Fe 55 0.00e+00 1.58e 07 2.81e 08 0.00e+00 2.00e-07 0.00e*00 1.04e-05 Fe 59 3.7Be 06 2.68e-06 6.25e 07 0.00e+00 0.00e+00 1. h -06 1.16e-06 5.87e06 1.37e 05 5.29e-06 0.0
........................................... 0e+00 0.00e+00 4.32e 06 3.24e-05 Co 54 Co 60 0.00e+00 9.72e-07 2.24e 06 0.00e+00 0.00e*00 0.00e*00 1.34e-05 Ni 63 0.00e+00 2.81e 06 6.33e-06 0.00e+00 0.00e+00 0.00e+00 3. W -05 1.77e-04 1.25e 05 6.00e.06
........................................ 0.00e+00 0.00e+00 0.00e*00 1.19e-06 ut.65 Cu 64 7.49e 07 9.57e-08 4.36e 0s 0.00e+00 0.00e+00 0.00e+00 5.19e 06 2n 65 0.00e+00 1.15e-07 5.41e et 0.00e+00 2.91e-07 0.00e+00 8.92e-06 5.Tse-06 2.00s.05 9.33e.0
..................................... 6 0.00e+00 1.28e-05 0.00e*00 8.47e-06 2n-69 tr 83 1.47e 08 2.80s.08 1.96e-09 0.00e+00 1.83e 08 0.00e+00 5 W 08 Br 84 0.00e+00 0.00e+00 5.76e-es 0.00e+00 0.00e+00 0.00e*00 0.00e+00 0.00e+00 0.00e+00 7.22e-0
..................................... 8 0.00e*00 0.00e+00 0.00e+00 0.00e+00 Br 85 Rb-86 0.00e+00 0.00e+00 3.05e 09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Rb-88 0.00e+00 2.98e-05 1.40e 05 0.00e+00 0.00e+00 0.00e*00 4.41e-06 0.00e*00 8.52e-08 4.54 08 0.00e+00 0.00e+00 0.00e*00 7.30e-15 !
...................................e ab 89 ............................................
1 tr 09 0.00e+00 5.50e.es 3.89e.08 0.00e*00 0.00e*00 0.00e*00 8.43e 17 tr-90 4.40e-M 0.00e+00 1.26e.05 0.00e+00 0.00e+00 0.00e+00 5.24e.05 8.30e 05 0.00e+00 2.05e 0
..................................... 3 0.00e+00 0.00e+00 0.00e*00 2.33e 04 Sr-91
$r-92 8.07e-06 0.00e+00 3.21e-07 0!O0e+00 0.00e*00 0.00e+00 3. W 05 Y 90 3.05e 06 0.00e+00 1.30e-07 0.00e+00 0.00e+00 0.00e+00 7.77e 05 1.37e 08 0.00e+00 3.60e-10 0.
........................................... Doe +00... 0.00e+00 0.00e+00 1.13e-04 Y 91 Y 91s 2.01e-07 0.00e+00 5.39e.09 0.00e+00 0.00e+00 0.00e+00 8.24e-05 Y 92 1.29e 10 0.00e+00 4.93e.12 0.00e*00 0.00e+00 0.00e*00 6.09e-09 1.21e-09 0.00e+00 3.50e.11 0.00e*00 0.00e+00 0.00e*00 3.32e 05 l 1
Conversten facters are in units of aren por pCI Ingested.
UNT-005-014 Revision 4 Attachment 6.20 (16 of 24) 280
00SE CONVERSION FACTORS AU. AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) 4 J
d 1
In9estion Oose Conversion factors for Teen age group cy nuctide.
4 Waterford Steam Electric station 1
Wuctide Organ Oose Conversion factors i
Bone Liver T. Body Thyroid Kidney Lung G! LLI Y 93 Zr-95 3.83e 09 0.00e+00 1.05e 10 0.00e+00 0.00e+00 0.00e+00 1.17e 04 I Zr 97 4.12e-08 1.30e 08 8.94e-09 0.00e+00 1.91e 08 0.00e+00 3.00e 05 2.37e 09 4.69e 10 2.16e 10 0.00e+00 7.11e 10 0.00e+00 1.27e 04 Nb 95 Mo 99 8.22e-09 4.56e 05 2.51e-09 0.00e+00 4.42e 09 0.00e+00 1.95e 05 0.00e+00 6.03e 06 1.15e-06 0.00e+00 1.38e-05 0.00e+00 1. m 05 Tc 101 3.60e 10 5.12e 10 5.03e 09 0.00e+00 9.26e-09 3.12e 10 8.7 )
Tc-99m 5e 17.....
)
Ru-103 3.32e 10 9.26e 10 1.20e 08 0.00e+00 1.38e 08 5.14e-10 6.08e 07 Ru-105 2.55e 07 0.00e+00 1.09e-07 0.00e+00 8.99e-07 ' O.00e+00 2.13e 05 2.18e 08 0.00e+00 8. W -09 0.00e+00 2.75e 07 0.00e+00 Ru-106 1.76e 05
........ ).
3.02e 06 0.00e+00 4.94e-07 0.00e+00 7. 06 0.00e+00 1.L8e-04 l As 110m 2.05e 07 1.94e-07 1.18e-07 0.00e*00 3. N 07 0.00e+00 5.45e 05 Te 125m 3.83e 06 1.38e-06 5.12e 07 1.07e-06 0.00e+00 0.00e+00 05
.......................................................................1.13e Te-127 1.58e 07 5.60e08 3. W -08 1.09e-07 6.40c07 0.00e+00 1.22e 05 Te 127m Te.129 9.67e 06 3.43e-06 1.15e 06 2.30e 06 3.92e 05 0.00e 40 2.41e 05 4.48e-08 1.67e 08 1.0c e08-3.20e.08 1.88e-07 0.00e+00
...................................................................... 2.45e-07 ........
Te 129m 1.63c05 6.05e 06 2.58e-06 5.2&e-06 6.82e-05 0.00e+00 6.12e 05 Te 131 2.79e-08 1.15e 08 8.72e 09 2.15e 08 1.22e-07 0.00e+00 2.29e 09 Te 131m 2.44e 06 1.17e-06 9. & 07 1.76e-06 1.2 0.00e+00 9.39e 05 Te-132 2e-05.........................
I 130 3.49e 06 2.21e 06 2.08e 06 2.33e-06 2.12e-05 0.00e+00 7.00* 05 I 131 1.03e-06 2.98e-06 1.19e-06 2.43e-04 4.59e-06 0.00e+00 2.29e-06 5.85e 06 8.19e.06 4.40e-06 2.39e-0
............................................... 3 1.41e...............................
05 0.00e+00 1.62e 06 1-132 l-133 2. N 07 7.30e.07 2.62e 07 2.46e-05 1.15c06 0.00e+00 3.18e 07 2.01e-06 3.41e 06 1.04e-06 4. % -04 5.98e 06 0.00e+00 2.58e-06 1 134 1.46e 07 3.87e 07 1.39e-07 6.45e-06 6.10e 07 1 135 0.00e+00 5.10e 09 6.10e 07 1.37e 06 5.82e-07 -1.01e 04 2. W 06 0.00e+00 1.74e-06 Cs 134 Cs 136 8.37e 05 1.97e.04 9.14e-05 0.00e+00 6.26e 05 2.39e-05 2.45e 06 8.59e-06 3.38e 05 2.27e 05 0.00e+00 1.84c 2. h .06 2.72e 06 Cs 137 05......................
Ca*138 1.12e-04 1.49e 04 5.19e-05 0.00e+00 5.07e 05 1.97e-05 2.12e-06 Se 13J 7.76c 08 1.49e 07 7.45e-08 0.00e+00 1.10e 07 1.28e-08 6. % 11 1.39e-07 9.78e 11 4.05e 09 0.00e+00 9.22e-11 6. m -11 1.24e 06 Conversion factors are in mits of aren per pcl Ingested.
UNT-005-014 Revision 4 Attachtnent 6.20 (17 of 24) 281 2 1
DOSE CONVERS10N FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Ingestion Dose Conversion factors for Teen age group cy nuctide.
Waterford Steam Electric Station Nuclide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kichey Lune Gl*LLI Ba 140 2.84e 05 3.48e-08 1.83e 06 0.00e+00 1.18e 08 2.34e-08 4.38e 05 Ba 141 6.71e 08 5.01e 11 2.24e-09 0.00e+00 4.65e-11 3.43e 11 1.43e 13 Ba 142 2.99e 08 2.99e 11 1.84e 09 0.00e+00 2.53e-11 1.99e 11 9.18e-20 La 140- 3.48e 09 1.71e 09 4.55e-10 0.00e+00 0.00e+00 0.00e+00 9.82e 05 La 142 1.79e-10 7.95e 11 1.98e 11 0.00e+00 0.00e+00 0.00e+00 2.42e 06 Co 141 1.33e-08 8.88e 09 1.02e 09 0.00e+00 4.18e-09 0.00e+00 2.54e-05 Co-143 2.35e 09 1.71e 06 1.91e 10 0.00e+00 7.67e-10 0.00e+00 5.14e 05 Ce 144 6.96e-07 2.88e 07 3.74e 08 0.00e+00 1.72e-07 0.00e+00 1.75e 04 Pr-143 1.31e 08 5.23e 09 6.52e 10 0.00e+00 3.04e 09 0.00e+00 4.31e-05 Pr 144 4.3Go.11 1.76e 11 2.18e 12 0.00e+00 1.01e-11 0.00e+00 4.74e-14 Nd 147 9.38e-09 1.02e 08 6.11e 10 0.00e+00 5.99e-09 0.00e+00 3.68e 05 W 187 1.46e-07 1.19e 07 4.17e 08 0.00e+00 0.00e*00 0.00e+00 3.22e-05 NP 239 1.76e 09 1.66e 10 9.22e 11 0.00e+00 5.21e 10 0.00e+00 2.67e 05 l
Conversion facters are in units of aram per pcl ingested. J I
UNT-005-014 Revision 4 Attachment 6.20 (18 of 24) 282
t DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Ingestion Oose Conversion factors for Child age group cy nuctide.
Waterford steam Electric Station Nuctide Orgen Dose Conversion Factors Bone Liver T. Body Thyroid Kidrwy Lun0 GI*LLI M3 C 14 0.00e+00 2.03e 07 2.03e 07 2.03e 07 2.03e 07 2.03e 07 2.03e 07 No 24 1.21e 05 2.42e 06 2.42e-06 2.42e 06 2.41e 06 2.42e 06 2.42e 06 5.80e 06 5.80e 05 5.80e 06
.- ..................................... 5.80e 06 5.80e 06 5.80e-06 5.80e-06 P 32 Cr-51 8.25e 04 3.86e 05 3.18e 05 0.00e+00 0.00e+00 0.00e+00 2.28e 05 Mn-54 0.00e+00 0.00e+00 8.90e-09 4.94e 09 1.35e 09 9.02e 09 4.72e-07 0.00e+00 1.07e 05 2.85e-06
........................................ 0.00e+00 3.00e-06 0.00e+00 8.98e-06 Mn-56 Fe-55 0.00e+00 3.34e-07 7.54e-08 0.00e+00 4.04e-07 0.00e+00 4.84e-05 Fe-59 1.15e 05 6.10e 06 1.89e 06 0,00e+00 0.00e+00 3.45e-06 1.13e-06 1.65e-05 2.67e 05 1.33e 05
........................................ 0.00e+00 0.00e+00 7.74e 06 2.7Be-05 Co-58 Co-60 0.00e.00 5.29e-06 0.00e+00 1.80e 06 5.51e-06 0.00e+00 0.00e+00 0.00e+00 1.05e 05 Ni-63 1. h 05 0.00e+00 0.00e+00 0.00e+00 2.93e-05 5.h04 2.88e-05 1.8Be-
.................................... 05 0.00e+00 0.00e+00 0.00e+00 1.94e 06 ut.65 Cu 64 2.22e 06 2.09e 07 1.22e-07 0.00e+00 0.00e+00 0.00e+00 2.W05 2n-65 0.00e+00 2.45e 07 1.48e-07 0.00e+00 5.92e 07 0.00e+00 1.15e 05 1.37e 05 3.65e 05 2.27e 0
..................................... 5 0.00e+00 2.30e 05 0.00e+00 6.41e 06 2n*69 Br.83 - 4.380 08 6.33e.08 5.85e.09 0.00e+00 3.84e.08 0.00e+00 3.99e.06 Be 84 0.00e+00 0.00e+00 1.71e-07 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.98
...................................e-07 Br-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 R&86 0.00e+00 0.00e+00 9.12e-09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 R&88 0.00e+00 6.70e-05 4.12e 05 0.00e+00 0.00e+00 0.00e+00 4.31e 06 0.00e+00 1.90e 07 1
................................ 32e 07 0.00e+00 0.00e+00 0.00e+00 9.32e 09 Ab89 Sr-89 0.00e+00 1.17e-07 1.04e-07 0.00e+00 0.00e+00 0.00e+00 1.02e 09 Sr 90 1.32s-03 0.00e+00 3.77e-05 0.00e+00 0.00e+00 0.00e+00 5.11e 05 1.70e-02 0.00e+00 4.31
................................,...e-03 0.00e+00 0.00e+00 0.00e+00 2.29e M Sr-91 Sr-92 2.40e 05 0.00e+00 9.06e-07 0.00e+00 0.00e+00 0.00e+00 5.30e 05 Y 90 9.03e-06 0.00e+00 3.62e 07 0.00e*00 0.00e+00 0.00e+00 1.71e M 4.11e 08 0.00e+00 1 A0e-09
........................................ 0.00e+00 0.00e+00 0.00e+00 1.17e M T 91 T 91a 6.02e-07 0.00e+00 1.61e-08 0.00e+00 0.00e+00 0.00e+00 8.02e-05 Y 92 3.82e-10 0.0Ce+00 1.h11 0.00e+00 0.00e+00 0.03e+00 7.48e-07 3.60e-09 0.00e+00 1.03e-10 0.00e+00 0.00e+00 0.00e+00 1.04e-M Conversion factors are in unite of area per pCi Ingested.
UNT-005-014 Revision 4 Attachment 6.20 (19 of 24) 283 t
l
_ . - _ . __ _ . - _ . _ - - . _-__ - . . _ - - _ . _~ . . . _ _ _ _ _ _ . - .,
J DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) i J
i Ingestion Oose Conversion factors for Child age group by nuclide.
Watertora steam Electric Station i
Wuctide Organ Dose Conversion Factors Bone Liver T. Body Thyreld Kistey Lung GI LLI j Y 93 l'
2r 95 1.14e 08 0.00e+00 3.13e 10 0.00e+00 0.00e+00 0.00e+00 1.70e 04 Zr 97 1.16e 07 2.55e 08 2.27e 08 0.00e+00 3.65e-08 0.00e+00 2. h 05 6.99e-09 1.01e-09 5.96e 10 0.00e+00 1.45e 09 0.00e+00 04
.......................................................................1.53e Nba95 2.25e 08 Mo 99 8. % 09 6.26e-09 0.00e+00 8.23e 09 0.00e+00 1.62e 05 Tc 101 0.00e+00 1.33e 05 3.29e-06 0.00e*00 2.84e-05 0.00e+00 1.10e 05 1.07e-09 1.12e 09 1.42e 08 0.00e*00 1.91e 08 Tc 99m 5.92e 10 3. h 09 Ru 103 9.23e 10 1.81e 09 3.00e-08 0.00e+00 2.63e-08 9.19e 10 1.03e 06 Ru 105 7.31e-07 0.00e+00 2.81e-07 0.00e+00 1.84e-06 0.00e+00 1.89e 05 6.45e 08 0.00e+00 2.34e-08 0.00e+00 5.67e-07 0.00 4.21e-05
--...............................................................e+00 Ru 106 1.17e 05 0.00e+00 1.44e-06 0.00e+00 1.58e 05 0.00e+00 1.82e M As 110m 5.39e 07 3.64e 07 2.91e 07 0.00e*00 6.78e 07 0.00e+00 4.33e 05 Te 125m 1.14e 05 3.09e 06 1.52e-06 3.20e 06 0.00e*00 1.10e 05
-...........................................................0.00e*00 Te 127 Te 127m 4.71e 07 1.27e-07 1.01e-07 3.26e-07 1.34e-06 0.00e+00 1.84e 05 Te 129 2.89e-05 7.78e 06 3.43e 06 6.91e 06 8.24e-05 0.00e*00 2.34e 05 1.34e-07 3.74e-06 3.18e-08 9.56e-04 0.00e+00 8.34e-06
.................................................. 3.92e 07 Te-129m Te 131 4.67e 05 1.36e-05 7.56e 06 1.57e-05 1.43e-04 0.00e+00 5.94e-05 8.30e-08 2.53e 05 2.47e-as 6.35e-08 2.51e 07 0.00e+00 4.36e-07 Te-131m 7.20e 06 2.49e-06 2.65e-06 5.12e-06
.................................................. 2.41e 05 0.00e+00 1.01e-04 Te 132 l*130 1.01e-05 4.47e n6 5.40e-06 6.51e-06 4.15e-05 0.00e+00 4.50e-05 !
!*131 2.92e 06 5.90e 06 3.04e 06 6.50s-04 8.82e 06 0.00e+00 2.76e 06 1.72e 05 1.73e 05 9.83e-06 5.72e-0
............................................... 3 2.84e-05 0.00e+00 1.54e 06 1 132 l 133 8.00e-07 1.47e 06 6.76e-07 6.82e 05 2.25e 06 0.00e+00 1.73e-06 1 134 5.92e-06 7.32e 06 2.77e-06 1.36e-03 1.22e.05 0.00e*00 2.95e-06
- 4. h 07 7.78e.07 3.58e-07 1
.......................................... 79e.05 ....................................
1.19e-06 0.00e+00 5.16e-07 1 135 Cs 134 1.75e 06 3.15e 06 ~1.49e-06 2.79e.04 4.83e 06 0.00e+00 2.40e 06 2.h u 3.84,.M 8.10 05 0.00e+00 1.19e-M 4.27e-05 2.07e 06 Cs 136 2.35e-05 6.64e-05
...............................,4 18e.05 0.00e*00 3.44e 05 5.13e 06 2.27e-06 Cs 137 Cs 138 3.27e.04 3.13e-04 4.62e-05 0.00e+00 1.02e-06 3.67e-05 1.96e-06 Be-139 2.2Be-07 3.17e-07 2.01e.07 0.00e+00 2.23e-07 2.40e 08 1.44e-07 4.14e-07 2.21e.10 1.20e 08 0.00e+00 1.93e.10 1.30e 10 2.39e-05 Conversten f actors are in mits of aram por pCI Ingested.
UNT-005-014 Revision 4 Attachment 6.20 (20 of 24) 284
1 l
l l
DOSE CONVERSION FACTORS ALL AGE GROUPS l
BY NUCLIDE (INHALATION AND INGESTION) .
Ingestion Oose Conversion factors for Child age group cy nuclide.
Watertore Steen Electric Station Nuclide Organ Dose Conversion factors l
l l
Bone Liver T. Body Thyroid Kleey Lung G!-LLI Ba 140 3.31e 05 7.28e 08 4.8te 06 0.00e+00 2.37e 08 4.34e 08 4.21e 05.
Ba 141 2.00e 07 1.12e 10 6.51e 09 0.00e+00 9.69e.11 6.58e-10 1.14e 07 Ba 142 3.74e 08 6.29e 11 4.88e 09 0.00e+00 5.09e 11 3.70e 11 1.14e 09 La 140 1.01e 08 3.53e 09 1.10e 09 0.00e+00 0.00e+00 0.00e+00 9.84e 05 ta 142 5.24e 10 1.67e-10 5.23e 11 0.00e+00 0.00e+00 0.00e+00 3.31e 05 Co 141 3.97e 08 1.98e 08 2.94e-09 0.00e+00 8.68e 06 0.00e+00 2.47e-05 Co 143 6.99e 09 3.79e 06 5.49e 10 0.00e+00 1.59e 09 0.00e+00 5.55e 05 Ce 144 2.08e 04 6.52e 07 1.11e 07 0.00e+00 3.61e-07 0.00e+00 1.70e 04 Pr 143 3.93e.08 1.18e 08 1.95e-09 0.00e*00 6.39e 09 0.00e+00 4.24e-05 Pr.144 1.29e-10 3.99e 11 6.49e.12 0.00e+00 2.11e-11 0.00e+00 8.59e 08 Nd 147 2.79e-08 2.26e 08 1.75e-09 0.00e+00 1.24e 08 0.00e+00 3.58e 05 l W 187 4.29e 07 2.54e 07 1.14e 07 0.00e+00 0.00e+00 0.00e+00 3.57e 05
............................................................................... l up-239 5.25e 09 3.77e 10 2.65e-10 0.00e+00 1.09e.09 0.00e+00 2.79e-05 1
Corwersion f actors are in tstite of aren per pCl ingested.
l l
UNT-005-014 Revision 4 Attachment 6.20 (21 of 24) 285
l DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION) l l
l I
Ingeetton Dose Conversion factors for infant age group Dy nuctide. .
Waterford Steen Electric Stetton )
I l Nuclide Orgen Oose Conversion Fectors l
Sone Liver T. Body Thyroid Kidney Lung Ol*LLI l
H3 0.00e+00 3.08e 07 3.08e 07 3.08e 07 3.08e-07 3.08e 07 3.08e 07 C 14 2.37e-05 5.06e 06 5.06e 06 5.06e 06 5.06e 06 5.06e 06 5.06e 06 l No 24 1.01e 05 1.01e 05 1.01e 05 1.01e 05 1.01e 05 1.01e 05 1.01e 05 l P 32 1.70e-03 1.00e-04 6.59e 05 0.00e+00 0.00c00 0.00e+00 2.30e 05 Or 51 3.00e+00 0.00e+00 1.41e 08 9.20e 09 2.01e 09 1.79e 08 4.11e 07 Mn 54 0.00e+00 1.99e 05 4.51e 06 0.00e+00 4.41e 06 0.00e+00 7.31e 06 Mn-56 0.00e+00 8.18e 07 1.41e 07 0.00e+00 7.03e 07 0.00e+00 7.43e 05 Fe-55 1.39e-05 8. m 06 2.40e 06 0.00e+00 0.00e+00 4.39e 06 1.14e 06 Fe-59 3.08e-05 5.38e-05 2.12e 0' O.00e+00 0.00e+00 1.59e-05 2.57e 05
............................................................................... l Co 58 0.00e+00 3.60e-06 8. m 06 0.00e+00 0.00e+00 0.00e+00 8.97e 06 Co-60 0.00e+00 1.08e-05 2.55e 05 0.00e+00 0.00e+00 0.00e00 2.57e 05 Ni 63 6.34e 04 3.92e-05 2.20e 05 0.00e+00 0.00e+00 0.00e+00 1.95e 06 Ni 65 4.70e-06 5.32e 07 2.42e 07 0.00e00 0.00e+00 0.00e+00 4.05e 05 Cu-64 0.00e+00 6.09e 07 2.82e 07 0.00e00 1.03e-06 0.00e+00 1.25e-05 Zn-65 1.84e 05 6.31e-05 2.91e 05 0.00e00 3.06e-05 0.00c00 5.33e 05 2n-69 9.33e-08 1.68e 07 1.25e-08 0.00e+00 6.98e-08 0.00e+00 1.37e 05 Br-83 0.00e+00 0.00e+00 3.63e-07 0.00e+00 0.00e00 0.00e+00 0.00e+00 Br 84 0.00e+00 0.00e+00 3.82e 07 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ,
............................................................................... l Br 85 0.00e+00 0.00e+00 1.94e-08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 l tb 86 0.00e+00 1.70e 04 8.40e 05 0.00e+00 0.00e*00 0.00e+00 4.35e-06 ,
l Rb-88 0.00e+00 4.98e-07 2.73e 07 0.00e+00 0.00e+00 0.00e+00 4.85e 07 l Rb-89 0.00e+00 2.86e 07 1.97e-07 0.00e+00 0.00e+00 0.00e+00 9.74e 08 Sr*89 2.51e 03 0.00e+00 7.20e 05 0.00e+00 0.00*00 0.00e+00 5.16e 05 SP 90 1.85e 02 0.00e+00 4.71e 03 0.00e+00 0.00e+00 0.00e+00 2.31e 04 Sr-91 5.00e 05 0.00e+00 1.81e-06 0.00e+00 0.00e+00 0.00e+00 5.92e-05
, Sr-92 1.92e-05 0.00e+00 7.13e 07 0.00e00 0.00e00 0.00c00 2.07e 04 j T 90 8.69e-08 0.00e+00 2.33e-99 0.00e+00 0.00e+00 0.00c 00 1.20e 04
............................................................................... l T-91 1.13e 06 0.00e00 3.01e-08 0.00e+00 0.00e00 0.00e+00 8.10e-05 T 91m 8.10e-10 0.00e00 2.76e 11 0.00e+00 0.00e00 0.00e00 2.70e 06 T 92 7.65e-09 0.00e00 2.15e-10 0.00e00 0.00e00 0.00e+00 1.46e-04 Corwersion f actors are in mits of eram per pCl Ineseted.
t I
4 s
i UNT-005-014 Revision 4 Attachment 6.20 (22 of 24) 286
00SE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Ingestion Oose Conversion factors for Infant age group Dy nuctide.
Waterford steen Electric Stetton Nuclide Organ Oose Conversion factors Bone Liver T. Body Thyroid Kichey Lwig GI LLI Y-93 2.43e 08 0.00e+00 6.62e 10 0.00e+00 0.00e+00 0.00e+00 1.92e 04 Zr 95 2.06e 07 5.02e 08 3.56c 08 0.00e+00 5.41e 08 0.00e+00 2.50e 05 Zr 97- 1.48e 08 2.54e 09 1.16e 09 0.00e+00 2.56e-09 0.00e+00 1.62e 04 Nb 95 Mo 99 4.20e 08 1.73e 04 1.00e 08 0.00e+00 1.24e 08 0.00e+00 1.46e-05
'Tc 101 0.00e*00 3.40e 05 6.63e-06 0.00e+00 5.08e 05 0.00e+00 1.12e-05 2.27e 09 2.86e-09 2.83e.08 0.00e+00 3.40e-08 1.56e.09 4.86e 07 Tc 99m Ru-103 1.92e.09 3.96e 09 5.10e.08 0.00e+00 4.26e.08 2.07e 09 1.15e-06 Ru 105 1.48e-06 0.00e*00 4.95e-07 0.00e*00 3.08e 4 0.00e+00 1.80e-05 1.36e-07 0.00e+00 4.58e 08 0.00e+00 1.00e.06 0.00e+00 5.41e-05 Ru 106 2.41e-05 0.00e+00 3.01e 06 0.00e+00 2.85e 05 0.00e*00 1.83e 04 As 110m 9.96e.07 7.27e 07 4.81c07 0.00e*00 1.04e-06 0.00e+00 3.7Te-05 Te 125m 2.33e.05 7.79e 4 3.15e 4 7.84e.06 0.00e+00 0.00e*00 1.11e-0
..............................................................................5 T**127 1.00e.06 3.35e-07 2.15e 07 8.14e-07 2.44e 06 0.00e+00 2.10e 05 Te 127m 5.85e-05 1.94e.05 7.08e 4 1.60e.05 1.44e.04 0.00e+00 2.36e.05 Te.129 2.86e.0T 9.79e.08 6.63e 08 2.30s.07. 7.07e.07 0.00e*00 To.129m
................ 2.27e.05 Te.131 1.00e.04 3.43e 05 1.54e.05 3.86e 05 2.50e.04 0.00e*00 5.97e-05 1.76e.07 6.50e 08 4. E -08 1.57e-0T 4.50e 07 0.00e+00 7.11e.06 Te 131m 1.52e 05 6.12e 4 5.0$e.06 1.24e.05 4.21e 05 -0.00e+00 1 Te 132 03e......
04 1 130 2.08e-05 1.03e 05 9.61e 06 1.52e 05 6.44e 05 0.00e+00 3.81e 05 1 131 6.00e 06 1.32e 05 5.30e 06 1.48e.03 1.45e 05 0.00e+00 2.83e 06 3.59e.05 4.23e.05 1.86e.05 1.39e.02 4.94e.05 0.00e+00 06
.......................................................................1.51e I-132 l
I 133 1. W .06 3.37e 06 1.20e 4 1.58e-04 3.76e e 0.00e+00 2.73e 06 1-134 1.25e.05 1.82e-05 5.33e 4 3.31e-03 2.14e-05 0.00e+00 3.08e 4 8.69e.07 1.78e 4 6.33e 07 4.15e 05 1. W 4
...................................................1.99e...........................
~
4 0.00e*00 1 135 Co.134 3. W .06 7.24e 4 2.he 6.49e.06 8.07e 06 0.00e+00 2.62e 06 3.77,4 7.03e.04 7.10e.05 0.00e+00 1.81e 4 7.42e.05 1.91e 06 Co 136 4.59e.05 1.35e-04 5.06e-05 0.00e+00 5 1.10e.05 2.05e 4
.................................................... 38e.05.......................... ,
co 137 Ca.138 5.22e 4 6.11e 4 4.33e.05 0.00e+00 1.64e.04 6. m .05 1.91e 06 '
Se 139 4.41e-07 7.82e-07 3.79e.07 0.00e+00 3.90e-07 6.09e.08 1.25e 4 8.41e.07 5.84e 10 2.55e 08 0.00e+00 3.51e.10 3.54e 10 5.58e 02 1 -
Convereien facters are in mite of arem per pCi ingened.
l 1
UNT-005-014 Revision 4 Attachment 6.20 (23 of 24) 287
DOSE CONVERSION FACTORS ALL AGE GROUPS BY NUCLIDE (INHALATION AND INGESTION)
Ingestion Dose Conversion factors for Infant age group cy nuctide.
Waterford Steam Electric Station Nuclide Or9en Dose Conversion factors Sone Liver T. Sody Thyroid Kidrwy Lun8 GI LLI Ba 140 1.71e 04 1.71e 07 8.81e 06 0.00e+00 4.06e 08 1.05e 07 4.20e-05 Ba-141 4.25e 07 2.91e-10 1.34e 08 0.00e+00 1.75e 10 1.77e 10 5.19e 06 Ba 142 1.84e 07 1.53e 10 9.06e 09 0.00e+00 8.81e 11 9.26e 11 7.59e 07 La 140 2.11e 08 8.32e-09 2.14e 09 0.00e+00 0.00e+00 0.00e+00 9.77e 05 La 142 1.10e 09 4.04e 10 9.67e 11 0.00e+00 0.00e+00 0.00e+00 6.86e 05 Ce 141 7.87e 08 4.80e-08 5.65e 09 0.00e+00 1.48e 08 0.00e+00 2.48e 05 co 143 1.48e 08 9.82e-06 1.12e 09 0.00e+00 P.86e 09 0.00e+00 5.73e 0S Co 144 2.98e 06 1.22e 06 1.67e 07 0.00e+00 4.93e 07 0.00e+00 1.71e-04 Pr 143 8.13e 08 3.04e 08 4.03e 09 0.00e+00 1.13e-08 0.00e+00 4.29e 05 Pr-144 2.74e-10 1.06e-10 1.38e-11 0.00e*00 3.84e.11 0.00e+00 4.93e 06 led 147 5.533-08 5.68e-08 3.48e-09 0.00e+00 2.19e-08 0.00e+00 3.60e 05 W-187 9.03e 07 6.28e-07 2.17e 07 0.00e+00 0.00e+00 0.00e+00 3.69e.05 Np*239 1.11g 06 9.93e 10 5.61e-10 0.00e*00 1.98e.09 0.00e+00 2.87e 05 Conwereton factors are in mits of ares per pci inoested.
UNT-005-014 Revision 4 Attachment 6.20 (24 of 24) 288 l
1
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL Values for Aj, Pj, and Ri were calculated as per NUREG-0133. Recommended values for various factors in the calculations were as specified in NUREG-0133. The location of most of the recommended factors are contained in Regulatory Guide 1.109. All factors used in Waterford-3 SES's calculations are for the maximum individual and are not ' site specific. The various factors are discussed below.
e Stable element transfer coefficients for vegetation, cow's milk, goat's milk and meat were obtained from Regulatory Guide 1.109 Tables E-1 and E-2 (Attachment 6.21, page 2).
- Animal consumption rates were obtained from Regulatory Guide 1.109 Table E-3, (Attachment 6.21, page 3).
- Usage or consumption rates for adult, teen, child, and infant age groups were obtained from Regulatory Guide 1.109 Table E-5. These values are for the maximum exposed individual, (Attachment 6.21, page 4),
e External dose factors for standing on contaminated ground were obtained from Regulatory Guide 1.109 Table E-6, (Attachment 6.21, pages 5-7).
e Other factors used were obtained from Regulatory Guide 1.109 Table E-15 for various parameters, (Attachment 6.21, page 8-9).
- Bioaccumulation factors for freshwater and saltwater vertebrates and .
invertebrates (Attachment 6.21, page 10).
- Inhalation and ingestion dose factors for adult, teen, child, and infant age groups were obtained from Regulatory Guide 1.109 Tables E-7 through E-14.
(Attachrent 6.20).
- Radionuclide half lifes and decay constants parameters (Attachment 6.21, p.11-13).
UNT-005-014 Revision 4 Attachment 5.21 (1 of 13) 289
i SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rg VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL 4
Stable Element Transfer coefficients by nuclide.
Waterford Steam Electric Station Element stable Element Transfer Data Siv Fm Ff Fm Veg/$of1 Cow Milk Meet Goat Nilk N
4.80e+00 1.00e-02 1.20e 02 1. m 01 C
No 5.50e+00 1.20e-02 3. m 02 1.00e 01 P
5.20e-02 4.W-02 3.00e 02 4.00e-02 1.10e+00 2.50e-02 4.60e 02 2. W 01 Cr Mn 2.50e 04 2.20e 03 2.40e 03 2.20e 03 Fe 2.90e 02 2.50e-04 8.00e 04 2.50e-04 Co 6.60e 04 1.20e 03 4.00e-02 1.30e 04 Nl 9.40e 03 1.00e-03 1.30e 02 1.00e 03 Cu
- 1. m -02 6. m 03 5. m 02 6. m 03 Zn 1.20e 01 1.40e-02 8.00e 03 1.30e 02 4.00e 01 3.90e 02 3.00e-02 3. m 02 tr 2. m 02 6. m 03 2. m 03 6.00e 03 Rb 1. m 01 3. m 02 3.10e 02 3. m -02 Sr
- 1. m 02 8.00e 04 6.00e 04 1.40e-02 Y 2.60e 03 1. m 05 4. W 03 1. m 05 2r 1. N -04 5. m 06 3.40e 02 5. W -06 Nb 9.40e-03 No
- 2. m -03 2.80e 01 2.50e-03 Tc 1.20e-01 7.50s 03 8.00e 03 7.50e-03 2.50e-01 2.50e 02 4.00e 01 2. m 02 Ru Rh 5.00e 02 1.00e-06 4.00e 01 1.00e 06 1.30e+01 1.00e-02 1. W 03 1.00e 02 As 1. m -01 5.00e-02 1. m 02 5.00e-02 Te 1.30e+00 1.00c03 7. m 02 1. m 03 1 2.00e 02 6. W -03 2. m 03 6.00e-02 Cs i
Ba 1.00e 02 1.20e 02 4.00e 03 3.00e 01 I
La
- 5. m 03 4.00e 04 3.20e 03 4.00e 04 2.50e 03 5.00e 06 2. m 04 5. m 06 Ce 2. m -03 1. m 04 1.20e-03 1.00e-04 Pr Nd 2.50e 03 5.00e 06 4.70e 03 5.00e 06 W 2.40e 03 5.00e 06 3. m 03 5.00e-06 kp 1.80e-02 5.00c 04 1.30e 03 5.00e-04 i
2.50e-03 5.00e 06 2.00e 04 5.00e 06 Units for transfer data are derived as follow Blv Fe
> pC1/kg in vegetation per pcl/kg in soll (no smits),
Ff > pCl/ liter In milk per PCf/ day ingested by animal (deys/ liter),
> pC1/kg in meat per pCl/ day ingested by anlent (deys/kg).
UNT-005-014 Revision 4 Attachment 6.21 (2 of 13) 290
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL l
1 l
j Animal Consumtion rates.
! Waterford steam Electric station Milk cow's feed intate rate : 50.00 kg/ day I Milk cow's water intate rate : 60.00 t/ day Beef cow's feed intate rate : 50.00 kg/ day Beef cow s water intate rate :
a 50.00 t/ day Goat's feed intake rate : 6.00 kg/ day Goat's water intate rate : 8.00 t/ day i
i l
I l
~
l l
{
l 1
l UNT-005-014 Revision 4 Attachment 6.21 (3 of 13)
. 291 i
- SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL Consunction rates for MAX! MAL individuals.
Waterfore Steam Electric Station produce veg usage rate for the Attt : 520.0 kg/yr produce veg usage rete for the Teen : 630.0 kg/yr proece veg usage rate for the Child : 520.0 kg/yr produce weg usage rete for the infant : 0.0 kg/yr Leafy veg usage rate for the Achant : 64.0 kg/yr leafy veg usage rate for the Teen : 42.0 kg/yr testy veg usage rate for the Child : 26.0 kg/yr leafy veg usage rate for the Infant : 0.0 kg/yr milk usage rate for the Adult : 310.0 t/yr milk usage rate for the Teen : 400.0 t/yr milk usage rate for the Child a 330.0 t/yr milk usage rate for the infant : 330.0 t/yr meet / poultry usage rete for the A mit i 110.0 kg/yr meet / poultry usage rete for the Teen : 65.0 kg/yr meet /peultry usage rate for the Child : 41.0 kg/yr most/ poultry usage rete for the Infant : 0.0 kg/yr fish usage rete for the A & lt : 21.0 kg/yr fish usage rate for the Teen : 16.0 kg/yr fish usage rate for the Child a 6.9 kg/yr fish usage rate for the Infant : 0.0 kg/yr seafood usage retc. for the Adult 5.0 kg/yr seefeed usage rate for the Teen : 3.8 kg/yr sestood usage rate for the Child : 1.7 kg/yr sesfeed usage rate for the Infant 0.0 kg/yr drink h2s usage rete for the A ett : 730.0 t/yr drink h2e usage rate for the Teen : 510.0 t/yr drink h2o usage rete for the Child : 510.0 t/yr drink h20 usage rete for the Infant : 330.0 t/yr shore roc usage rate for the Adult : 12.0 hr/yr shore ree usato rate for the feet : 67.0 hr/yr shore roc usage rete for the Child : 14.0 hr/yr shore roc usage rate for the Infant : 0.0 hr/yr Irdistation usage rate for the A< : 8000.0 m3/yr Inhaletten usage rete-for the Teen 8000.0 m3/yr '
irdialation usage rate for the Child : 3700.0 m3/yr inhetation usage rete for the Infant : 1400.0 m3/yr UNT-003-014 Revision 4 Attachment 6.21 (4 of 13) 292
I I
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE 0FFSITE DOSE CALCULATION MANUAL l
Ground Plane cose Conversion factors for all age groups by nuclide.
Waterford Steam Electric Station Nuclide Organ Oose Conversion Factors T. Sody Skin H3 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e*00 Na 24 2.50e 08 2. h 08 P 32 0.00e+00 0.00e+00 Cr 51 2.20e 10 2.60e-10 l Mn-54 5.80e 09 6. h 09 '
l Mn-56 1.10e 08 1. h -08 l Fe-55 0.00e+00 0.00e+00 Fe 59 8. h 09 9.40e 09 Co-54 7. h -09 8.20e 09 Co 60 1. h .08 2.00e.08 Ni 63 0.00e+00 0.00e+00 Ni-65 3. h 09 4.30e-09 Cu-64 1. h 09 1. N 09 Zn 65 4.00e-09 4.60e 09 Zn-69 0.00e+00 0.00e+00 Br 83 6.40e-11 9. h 11 Br 84 1.20e 08 1.40e-08 Br 85 0.00e*00 0.00e+00 Rb 86 6.30e.10 7.20e 10 Rb 88 3.50e 09 4.h 09 Rb-89 1.50e-08 1.h 08 sr 89 5.60e 13 6. h 13 Sr-90 0.00e+00 0.00e+00 Sr 91 7.10e 09 8.h 09 Sr 92 ~ 9. W 09 1. h 08 Y 90 2.20e 12 2.60e 12 Y 91 2.40e 11 2. h 11 Y 91m 3.80e 09 4.40e 09 Y 92 1.60e-09 1. h 09 Conversion factors are in tmits of mres/hr per pCf/sgasre meter.
UNT-005-014 Revision 4 Attachment 6.21 (5 of 13) 293
1 1
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE 0FFSITE DOSE CALCULATION MANUAL l
I l
l Ground Plane Dose Conversion factors for all age groups by nuclide.
j Waterford Steam Electric Station I
I Nuclide Organ Dose Conversion Factors T. Sody Skin )
l Y 93 5.h 10 7.80e-10 i Zr 95 5.00e 09 5.80e 09 l
Zr 97 5.50e 09 6.40e 09
............................. I Nb 95 5.10e 09 6.00e 09 Mo 99 1. m 09 2.20e 09 Tc 101 2. m -09 3.00e 09 Tc-99m 9. h 10 1.10e-09 Ru-103 3.60s 09 4.20e-09 l Ru-105 4. m -09 5.10e-09 Ru-106 1.50e 09 1.80e 09 As 110m 1.30e 08 2.10e 08 l
i Te 125m 3. W -11 4.80e 11
............................. i
! Te-127 1.00e-11 1.10e 11 I l
Te 127m 1.10e-12 1.30e-12 Te-129 7.10e 10 8.40e 10 l Te 129m 7. h 10 9.00e-10
! Te-131 2.20e 09 2.60e 06
! Te 131s 8. W 09 9. m 09 Te 132 1.N 09 2.00e 09 I 130 1.40e 08 1. N 08 l 1 131 2.80e-09 3.40e 09 1 132 1. N -08 2.00e 08 I 133 3. N 09 4.50e 09 I-134 1.60e 08 1. m -08 1 135 ~1.20e 08 1.40e-08 Cs-134 1.20e 08 1.40e 08 Cs Y36 _1. m 08 1. N 08 Cs 137 4.20e 09 4. m -09 Cs 138 2.10e-08 2.40e 08 Sa 139 2.40e 09 2.70e 09 Conversion factors are in snits of arem/hr per pC1/ square meter.
l 1
! UNT-005-014 Revision 4 Attachment 6.21 (6 of 13) 294 s
t
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL l
Cround Plane Dose Conversion factors for att age groups by nuclide.
Waterford Steam Electric Station Nuclide Organ Oose Conversion Factors T. Body Skin Ba 140 2.10e-09 2.40e 09 Ba-141 4.30e 09 4.90e 09 Ba 142 7.90e 09 9.00e 09 La 140 1.50e-08 1.70e-08 La-142 1.50e 08 1.80e 08 Co 141 5.50e 10 6.20e 10 Co 143 2.20e 09 2.50e-09 Co 144 3.20e 10 3.70e 10 Pr-143 0.M 0.00e+00 Pr-144 2.00e 10 2.30e 10 Nd-147 1.00e 09 1.20e 09 W 187 3.10e 09 3.60e 09 NP 239 9.50e 10 1.10e 09 "
Conversion f actors are in units of aroughr per pCi/souare meter.
UNT-005-014 Revision 4 Attachment 6.21 (7 of 13}
295
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL 3lte Soecific Parameters usea.
8arameter No. .t Description fraction of ingestea proouce grown in region FormJta syneet tg Value : 0.760 units . none Parameter No. 2 Description : fraction of teafy vegetables grown in region Foruuta Syneel i fL Value : 1.000 Units none Parameter No. 4 Deecription : fraction of activity retained on cross for airborne particulates Foruuta Syncot r Value : 0.200 Units : none Parameter No. :5 Description : fraction of activity retained on crops for airborne raciolacines Formula syneet : r Value : 1.000 Units : none Parameter No. : 6 Description : building shielding factor for maatsum individuals Formula syncot : SF Value : 0.700 Units : none Parameter No. : 11 Description : period of Long term buit:he of activity in
- sit or sediment Fofsula Syueet a t Value : 131400.000 Units : hr Parameter No. : 12 Description : transport time from animal feed milk man man individuals )
Foruuta Syuhel i tt Vetus !
- 2.000 '
units : daye Parameter No. : 15 Dancription : time delay for harvest of ves/ crops and ingestion by aniasts stored feed Foruuta Syuest : th value : 2160.000 units : hr Parameter No. : 16 -
Description : tima delay for harvest of ves/ crops and ingestion by men leafy veg mas indivd Foruuta Syuhet : tL vetus : 24.000
~~
Lmits a hr Peremeter No. : 17 Description a time deley for herwest of veg/ crops and ingestian by man pream:e veg man ind Fortsata 8)udset a th Vetus : 1440.000 units hr Parameter No. 37 Description : agricuttural productivity by unit aree stored feed feed-animal man Formula Syuhel Ys Vetus : 2.C00 units a kg/at UNT-005-014 Revision 4 Attachment 6.21 (8 of 13) 296
SPECIFIC FACTORS USED TO DETERMINE Ag, Pj_and Rj VALUES FOR THE i 4
0FFSITE DOSE CALCULATION MANUAL 1
Peresster so. . 38
] Description agricultural productivity by unit aree pasture grass feeo animal man 3 Formula Syneet Yp i
Value : 0.700 l Units : kg/m2 i )
4
- arameter no. *1
?
i Desertation time from staugnter et meet animet to consumption Forenata Symool : tf Value : 20.000 units : days
! Parameter No. : 43 Description : agricultural promJctivity by Latit eroe crops /veg man i Formula Syneset Yv j Value : 2.000 Units : kg/m2
, Parameter No. : 44 Description
- rate constant for removal of activity on plants try weathering
] Formula Syneet : Lasees w v
Value : 2.062938e 3 l Units : hr*1 I
,. Parameter No. : 69
, Description : fraction of year that milk cows are on pasture l Foreuta Syneel : fp l- VeLue : 1.000 a
LAtits : none a
Parameter No. 70 Description : fraction of year that milk goats are en posture ;
Formula Systiet fp !
Value : 1.000
- Units none Parameter No.
- 71 j Description
- fraction of year that beef cows are en pasture Forsede Syndsel fp fi VeLue : 1.000 j Units : nono Pereester No. : 73
- Description
- fraction of milk cow's intake from posture Fwende Systet a fs I Value : 1.000 l
~
Units a none 1
2 ~
Parameter No. : 74 Description a fraction of milk coat's intake from pasture Formula Syuest a fs ,,
Vetue : 1.000 Units none Parameter No. : 75 Description : fraction of beef cow's intake from posture Foreute Syehel a fs Value : 1.000 Units a none Parameter No. :M Desertation : ahootute rotative hueidity in the atmosonere Foruuta Syueel : M Value : 8.000 Units a s/m3 UNT-005-014 Revision 4 Attachment 6.21 (9 of 13) 297
4 1
SPECIFIC FACTORS USED TO DETERMINE Ag, Pj and Rg VALUES FOR THE 1 l
j OFFSITE DOSE CALCULATION MANUAL S!mma" ATION FACTORS FOR VARIGJS ELEMENTS
- W AN AQUATIC ENVIRONMENT i
Element Freen weter Freen.weter Sett* water Sett* water
, Flah Inverterorates Fish Irwerterorates i W 9.00e*1 9.00e.1 I 9.00e l 9.30e 1 C 4.60e*3 9.10e*3 1.80s.3 1.40e*3 l Ne 1.00e*2 2.00e*2 6.70e 2 1.90e-1 i j P 1.00e*5 2.00e*6 2.90e*6 3.00e*4 j Cr 2.00e*2 2.00e*3 4.00e*2 2.00e*3 No 4.00e*2 j
9.00e*4 5.50e*2 4.00e*2 fe 1.00e*2 3.20e*3 3.00e*3 2.00ee6 j Co 5.00e*1 2.00e+2 1.00e*2 1.00e*3 l MI 1.00e*2 1.00e*2 1.00e*2 2.50e*2
) Cu 5.00e*1 4.00e*2 6.70e*2 1.70e*3
{ 2n 2.00e*3 1.00e*6 2.00e*3 5.00ee4
- Br 4.20e*2 3.30e*2 1.50s-2 3.10e*e
} Ab 2.00e*3 1.00e*3 4.30e*e 1.70eet Sr 3.00e*1
- 1.00e*2 2.00eee 2.00eet Y 2.50e*1 1.00e*3 2.50 set 1.00e*3 Ir 3.30see 6.70ees 2.00e*2 0.00eet Nb 3.00e*2 1.00e*2 3.00e*2 1.00e*2 see 1.00eet 1.00e*t 1.00e*1 1.00e*1
! Te 1.50e*1
- 5.00see 1.00e*1 5.00 set tu 1.00 set 4
3.00e*2 3.00e*e 1.00e*3 AS 2.00e*e 8.00e*2 3.00e*3 3.00e*3
{ Te 4.00e*2 ..iee*3 1. ~ 1 1.00 2 j i 1.50e*1 5.00e*e 1.00eet 5.00eet j Ca 2.00e*3 1.00e*3
' 4.00 set 2.50e*t 84 4.00see 2.00 set 1.00 set 1.00e*2 j Le 2.50e*1 1.00e*3 2.50eet 1.00e*3 j Ce 1.00e*0 1.00e*3 1.00e*1 6.00e*2 l
} Pr 2.50e*1 1.00e*3 2.50 set 1.00e*3
- ** 2.50eet t.00e*3 2.50e*i 1.00e*3
{ W 1.30e*3 1.00 set 3.00e*1 3.00e*1 j Mp 1.00e*1 4 Wee +4 1.00 set 1.00e*1 1
1 I
( Oete etteined free segutetery Guide 1.10p TeMe A.t for att elemente easset j
SILwer(As) mich to from anseets and parameters for Ewirersomtal Reelotegiest j
Assessmentes (ole / TIC 11444) and Niebiustub) elsh le from the internettenet j Atemic EnerW Ageney(IA0A) Safety series me. ST, Genorte seedste one Peraseters
(
for Aseeestng the twirersomtet Trenefer of temierusatideo from asuttne toteases, Esposures of Critteet Groupe.
UNT-005-014 Revision 4 Attachment 6.21 (10 of 13) 298
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL 1
1 1
Radionuctido Parameters used. 1 Waterford steen Electric Station Nuc11de Peremoters Netf Life Decay constant i
l N3 1.2280e+01 years 1.7899e 09 1/ seconds C 14 5.7300e+03 years 3.8359e 12 1/ seconds No 24 1.5000e+01 hours 1.2836e-05 1/ seconds P 32 1.4290e+01 days 5.6141e-07 1/ seconds Cr-51 2.7704e+01 days 2.8958e-07 1/ seconds nn-54 3.1270e+02 days 2.5656e 08 1/ seconds ,
.................s.................................... I m-56 2.5754e+00 hours 7.4750e 05 1/ seconds I Fe 55 2.7000e+00 years 8.1406e-09 1/ seconds Fe-59 4.4630e+01 days 1.7976e 07 1/ seconds Co 54 7.0000e*01 days 1.1331e-07 1/ seconds I Co-60 5.2710e+00 years 4.1699e-09 1/ seconds ul 63 1.0010e+02 years 2.1958e 10 1/ seconds Ni 65 2.5200e+00 hours 7.6405e-05 1/ seconds Cu-64 1.2701e+01 hours 1.5160e-05 1/ seconds 2n 65 2.4440e+02 days 3.2825e 08 1/ seconds 2n-69 5.5600e+01 minutes 2.0778e-04 1/ seconds Or 83 2.3900e+00 hours 8.0561e 05 1/ seconds Or-84 3.1000e+01 minutes 3.6328e 04 1/ seconds Or 85 1.7200e+02 seconds 4.0299e-03 1/ seconds ab 86 1.8660e+01 days 4.2995e 07 1/ seconds ab 88 1.7000e+01 minutes 6.4901e 04 1/ seconds !
Rb-89 1.5440e+01 minutes 7.4822e 04 1/ seconds .
Sr 89 5.0550e+01 days 1.5470e-071/ seconds sr 90 2.8600e+01 years 7.6852e 10 1/ seconds sr-91 9.5000e+00 hours 2.0267e 05 1/ seconds Sr 92 2.7100e+00 hours 7.1048e 05 1/ seconds Y 90 6.4100e+01 hours 3.0038e-06 1/ seconds Y 91 5.8510e+01 days 1.3711e 071/ seconds Y.91e 4.9710e+01 minutes 2.3240e 04 1/ seconds Y 92 3.5400e+00 hours 5.4390e 05 1/ seconds UNT-005-014 Revision 4 Attachment 6.21 (11 of 13) 299
l j SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE l OFFSITE DOSE CALCULATION MANUAL 4
l l \
l l l
Redlonuclide Parameters used.
Wsterford Steen Electric station ,
I 1
NuctIde Parameters l
i Netf tife Decay constont Y 93 1.0100e+01 hours 1.9063e 05 1/ seconds Zr-95 6.4020e+01 days 1.2531e 07 1/ seconds Zr-97 1.6900e+01 hours 1.1393e 05 1/ seconds ub 95 3.5060e+01 days 2.2882e 07 1/ seconds l 2.9164e-06 1/ seconds
- Mo 99 6.6020e+01 hours i Tc 101 1.4200e+01 minutes 8.1355e 04 1/ seconde j ......................................................
l Tc 99m 6.0200e+00 hours 3.1984e 05 1/ seconds l Ru-103 3.9350e+01 days 2.0388e 07 1/ seconds Ru-105 4.4400e+00 hours 4.3365e-05 1/ seconds l ......................................................
Ru-106 3.6820e+02 days 2.1789e 08 1/ seconds As-110m 2.4985e+02 days 3.2109e 08 1/ seconds Te 125m 5.8000e+01 days 1.3832e-07 1/ seconds Te-127 9.3500e+00 hours 2.0593e-05 1/ seconds Te-12hs 1.0900e+02 days 7.3601e 08 1/ seconds To 129 6.9600e+01 minutes 1.6590e 04 1/ seconds Te 129m 3.3600e+01 days 2.3877e 07 1/ seconds Te 131 2.5000e+01 minutes 4.6210e 04 1/ seconds Te 131m 3.0000e+01 hours 6.4180e 06 1/ seconds Te 132 7.8200e+01 hours 2.4622e 06 1/setJnds I 130 1.2360e+01 hours 1.5578e 05 1/ seconds l 8.0400e+00 days 1-131 9.9783e 07 1/ seconds 1 132 2.3000e+00 hours 8.3713e-05 1/ seconds 1-133 2.0800e+01 hours 9.2568e 06 1/ seconds I 134 5.2600e+01 minutes 2.1963e-04 1/ seconds I 135 6.6100e+00 hours 2.9129e 05 1/ seconds ts-134 2.0620e+00 years 1.0659e 08 1/ seconds ts 136 1.3160e+01 days 6.0962e-07 1/ seconds Cs 137 3.0170e+01 years 7.2852e 10 1/ seconds co-134 3.2200e+01 mlrsetes 3.5877e 04 1/ seconds se 179 8.3100e+01 minutes 1.3902e 04 1/ seconds l
i 1.
e 4
UNT-005-014 Revision 4 Attachment 6.21 (12 of 13) 300 i
)
i E__________
SPECIFIC FACTORS USED TO DETERMINE Aj, Pj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL i
l Redlonuclide Parameters used.
Waterford Steam Electric Station l
NucLtde Parameters l
l Netf Life Decay constant Be 140 1.2789e+01 days 6.2730e 07 1/ seconds Be 141 1.8270e+01 minutes 6.3232e 04 1/ seconds 8e-142 1.0700e+01 minutes 1.0797e 03 1/ seconds La 140 4.0220e+01 hours 4.7872e 06 1/ seconds
! La 142 9.5400e+01 minutes 1.2109e 04 1/ seconds co 141 3.2500e+01 days 2.4685e-07 1/ seconds Co 143 3.3000e+01 hours 5.8346e 06 1/ seconds Co-144 2.8430e+02 days 2.8219e 08 1/ seconds l
Pr 143 1.3560e+01 days 5.9163e 07 1/ seconds Pr-144 1.7280e+01 minutes 6.6854e-04 1/ seconds Nd-147 1.0980e+01 days 7.3065e 07 1/ seconds W 187 2.3830e+01 hours 8.0798e 06 1/ seconds Np-239 2.3550e+00 days 3.4066e 06 1/ seconds I
i l
l 1
I 1
i 4
),
! UNT-005-014 Revision 4 Attachment 6.21 (13 of 13) i 301
}
i 2
_ . _ . __ _ __ _ _ . - - - - - _