ML20067D061
| ML20067D061 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1993 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-94-0019, W3F1-94-19, NUDOCS 9403070312 | |
| Download: ML20067D061 (317) | |
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- A4.05 PR February 28, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control DesP- '
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, 1993. This report is submitted in accordance with Waterford 3 Technical Specification 6.9.1.8. .
If'you have any questions, please contact C.J. Thomas at (504) 739-6531.
Very truly yours, R.F. Burski Director Nuclear Safety RFB/CJT/ssf {
Attachment
-cc: (w/ Attachment) t L.J. Callan (NRC Region IV), NRC Resident Inspectors Office (w/o Attachment)
D.L..Wigginton (NRC-NRR), R.B. McGehee, N.S. Reynolds 040004 fp4S 9403070312 931231 * /
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Annual Radioactive Effluent Release i t
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January 1, 1993 - December 31, 1993 5
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TABLE OF CONTENTS 1.0 SCOPE 2.0. SUPPLEMENTAL INFORMATION !
2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy ,
2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Unplanned Abnorn al Releases :
3.0 GASE0US EFFLUENTS I 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES 7.1 Doses due to Gaseous Effluents 7.2 Doses due to Liquid Effluents 7.3 40 CFR Part 190 Dose Evaluation 7.4 Doses to Public Inside the Site Boundary 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program 8.2 Change.s to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 8.5 Activity Released via Secondary Pathways 8.6 Missed Effluent Samples 8.7 Major Changes to Radioactive Waste Systems 8.8 Additional Information W21419HP 1
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10,0 ATTACHMENTS l
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1.0 SCOPE i This Annual Radioactive Effluent Release' Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8. It covers the period from January 1, 1993 through December 31, 1993. l 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 gaseous effluents and solid wastes released from the plant during the reporting period; (2) A summary of the meteorological data collected during 1993; (3) Assessment of radiation doses due to liquid and gaseous radioactive effluents released during 1993; (4) A submittal of changes to the Offsite Dose Calculation Manual and Process Control Program during this reporting period.
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2.0- SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits !
The Limits applicable to the release of radioactive material in ,
liquid and gaseous effluents are described in'the following !
sections. These limits are addressed in UNT-005-014, Offsite Dose Calculation Manual.
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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 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents from the site to areas -at or beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than.or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, j
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal' to 20 mrad for beta radiation.
2.1.2 lodines; Particulates, Half Lives > 8 Days; and Tritium The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site-boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ.
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The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous:
effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas 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 2.0E-4 pCi/ml total activity.
The dose or dose commitment ier of the public from radioactive materials in w . effluents released to unrestricted areas shall be limited to the following:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
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.2.1.4 4
Uranium Fuel Cycle Sources The dose or dose commitment to any member of the public-due to releases of radioactivity and radiation from-i uranium fuel cycle sources shall.be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem)-over 12 consecutive months.
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-c mulations .since the applicable. limits are expressed in terms.of dose rate at the site boundary.
a 2.2.2 Liquid Effluents i The maximum permissible concentration (MPC) values
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specified in 10 CFR Part 20, Appendix B, Table II, Column 2 are used as the permissible concentrations of g liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC-for dissolved and entrained noble gases in liquid ef fluent s.
2.3 Averaae Enerav This is not applicable to Waterford 3's Effluent 'j Specifications. E-Bars are not requir:d to be calculated from j effluent release data.
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2,4 Measurements and Acoroximations of Total' Radioactivity The quantification of radioactivity in liquid and gaseous-effluents was accomplished by performing the sampling and )
radiological analysis of effluents in accordance with 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 Gases) .
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:
GR = Averane Weekly Noble Gas Monitor Readina Monitor Reading During Noble Gas Sampling ,
i 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' I and containment purge batch releases, a gas grab sample '
was analyzed prior to release to determine noble gas concentrations in the batch. In all cases the total- :
radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.
2.4.2 lodines and Particulates '
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' gamma spectroscopy. The l
determined radionuclide concentrations and effluent l
-volume discharged were used to calculate the previous week's activity released.
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The particulate samples were-composited and analyzed >
quarterly for Sr-89 and Sr-90 by a contract 1aboratory (Teledyne Isotopas). Particulate gross alpha activity
-was measured weekly using alpha scintillation counting ;
techniques. The determined activities were used to estimate effluent- 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.
r i 2.4.3 Liquid Effluents i
For continuous releases, samples were collected weekly and ;
I analyzed using gamma spectroscopy. The measured concentrations-were used to determine radionuclide' concentrations in the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release. .I 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 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.
The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent discharged.
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u 2.5 Batch Releases.
A summary'of information for gaseous and liquid batch releases is included in Table 1.,
2.6 Unplanned / Abnormal Releases During this reporting period, there was one abnormal release.
A liquid radioactive release was performed with the radiation l
monitor setpoint incorrectly specified. Licensee Event Report i (LER) Number 93-003 documents this event. A discussion is l provided below. l
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During the period from August 31, 1993 to-September 3, 1993 liquid radioactive releases were performed from Dry Cooling i Tower Sump #1 to the 40 Arpent Canal. The associated radiation monitor setpoint was incorrectly set to an administrative controlled value of 5.0 E-6 uci/ml instead of a value !
calculated as per the ODCM. During the releases, the !
radioactivity concentrations monitored remained below the ODCM I calculated setpoint. At no time were any of the ODCM dose or '!
concentration limits exceeded. I l
4 Description of Event:
Radioactivity was being detected in Dry Cooling Tower Sump #1 and Dry Cooling Tower Sump #2 intermittently during the pe-iod from August 31, 1993 to September 3, 1993. Releases were twie to the 40 Arpent Canal or the discharge of the affected Dry Cooling Tower Sump was directed to the Liquid Waste Management System, depending upon concentrations of isotopes within the affected Sump.
An inadequate shift turnover resulted in the Health Physics.
Technician assuming that the discharge from DCTS #1 was aligned to the Liquid Waste Management System, when, in fact, it was aligned to pump to the 40 Arpent Canal. The setpoint for DCTS ,
- 1. Radiation Monitor (PRM-IRE-6775) was set to 5.0 E-6 uci/ml, I W21419HP- 9 i
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Descriotion of Event (cont'd):
which is the administrative value when no . isotopes are present-in the Sump. If isotopes are present in the Sump, the setpoint is calculated as per.0DCM methodology and the high alarm value l
adjusted to the newly calculated value in order to ensure that concentration limits of ODCM specification 5.3.1 are not -
exceeded. The pumps for each Dry Cooling Tower Sumps are secured upon receipt of a high alarm on their respective radiation monitors.
The Health Physics technician did not calculate and enter a new setpoint for the Dry Cooling Tower Sump #1 radiation monitor because he believed that the waste was not-being pumped to the 1 40 Arpent Canal, Consequently, releases were made from Dry )
, Cooling Tower Sump #1 to the 40 Arpent Canal with an incorrect setpoint, during the period from August 31, 1993 to September 3, 1993. l Cause of Event: )
l The root cause of this event was an inadequate shift turnover l I
complicated by inappropriate assumptions by Health Physics count room personnel. i a
i Corrective Action: ,l l
l A sample was drawn from DCTS #1 on September 3,1993. The i sample did not contain any detectable isotopes. Therefore, the l monitor setpoint was maintained at 5.0 E-6 uti/ml. Data from the Control Room and radiation monitor trends were collected and a calculation was performed to determine if any limits had been exceeded. Additional instructions concerning releases from the Dry Cooling Tower Sumps were written and placed in-the counting room shift log book. The Count Room Technician who presumed incorrectly that the DCTS #1 was aligned to the Waste j Tanks was counseled.
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l A.ctions Taken to Prevent Recurrence j l
On September 4,1993, an additional interim measure was established requiring the Radiation Protection Superintendent be notified prior to discharging any DCTS-waste containing radioactivity. On September 10, 1993, additional instructions were issued to RP Shift Technicians that clarified the l requisite steps and information needed to assure a proper release of DCTS waste. RP Directive 93.4 was revised on October 26, 1993 to provide additional instructions on the information that should be recorded on shift turn-over documents. l 3.0 GASE0US EFFLUENTS i
The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A,1B, and IC. 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 j several statistical uncertainties due to sample counting, efficiency, volume, etc.
4.0 LIOUID 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.
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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. and
'Alaron Corp. These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal
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vol umes . Final disposal volumes are reported as they become available.
The estimated total error in % is based upon several statistical-uncertainties due to sample counting, efficiency, volume, etc.
6.0 METEOROLOGICAL DATA r
In Table 4 the hourly meteoroloaical data from January 1,1993 through December 31, 1993, 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:
Parameter Annual Data Recovery 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 D_ose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary 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 offsite locations that could be continuously occupied during plant-operation in each of the meteorological sectors surrounding 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 meteorological data collected during 1993, this -
location was determined to be in the NE sector at a distance of 966 meters from the plant. 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 1993 are summarized as follows:
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Beta air dose: 0.74 mrad Gamma air dose: 0.32 mrad i l
The beta and gamma air doses are 3.7% and 3.2% of the l
Annual Dose Limits, respectively. The results of the ,
dose calculations by quarter are summarized in Table 5.
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7.1.2 Maximum Organ Dose to the Critical Receptor l The maximum organ dose to a MEMBER OF THE PUBLIC from I-131, I-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 1993. '
An assessment of the maximum organ dose was performed- ;
for the critical receptor. The critical receptor was assumed 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 1993, 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. 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 l determined to be 0.09 mrem to the infant thyroid. This represents 0.6% of the Annual Dose Limit. Dose calculation :
results are summarized by quarters in Table 5.
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7.2 Doses Due to Liouid Effluents The annual doses to the maximum exposed individual resulting from exposure to liquid effluents released during 1993 from Waterford 3:were 0.17 mrem total body and 0.23 mrem to the maximum exposed organ (liver). These values are-5.7% and 2.3%
respectively, of the Annual Dose Limits. 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 Qose 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),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 1993 were any of these limits exceeded; therefore, no evaluations were rcquired.
7.4 Doses to Public Inside the Site Boundarv 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, approximately 670 meters from the plant. Based j 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 maximum organ dose would be !
less than 0.010 mrem to the thyroid. Total body and' skin' doses- "
were calculated to be 0.03 and 0.07 mrem, respectively. These H 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.
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I 8.0 RELATED INFORMATION 8.1 Chanaes to the Process Control Procram There were minor changes to the Process Control Program during the reporting period. Specific vendor information was removed from procedure RW-001-210, Process Control Program. Copies of the changes to the Process Control Program are included in
], Attachment 10.1.
8.2 Chanaes to the Offsite Dose Calculation Manual There were minor changes to the Offsite Dose Calculation Manual during the reporting period.
Several Radiological Environmental Monitoring Program sample location descriptions were updated. Added definition of " Major Change" to a radioactive waste system. Added a.section specifying preparation of the Annual Radioactive Effluent Release Report to the NRC. Added sections specifying content of special reports to the NRC. Added section addressing Secondary Release Paths. Clarified note in table 5.6-3 .
pertaining to MCES releases. Deleted MKE-4 sample location.
Deleted milk goats from dispersion / deposition table in Attachment 6.2. Copies of the changes to the Offsite Dose Calculation Manual are included in Attachment 10.2.
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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'8 . 4 Report of Reouired Effluent Instrument Inoperability ODCM Specifications, 5.6.1.b and 5.6.2.b requires reporting in the Semiannual Radioactive Effluent Release Report of why I designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the ACTION Statement. During the reporting period, there were no cases when instrumentation was not restored to operability within the time specified.
8.5 Activity Released Via Secondary Pathways The following secondary release paths were continuously monitored for radioactivity: 1) the Hot Machine Shop Exhaust (AH-35), 2) Decontamination Shop Exhaust (AH-34), 3) the RAB H&V Equipment Room Ventilation system Exhaust.(E-41A and E-418); and 4) 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. In addition to these release pathways, a steam release from the Steam Generators via-the !
Atmospheric Dump Valves was performed and an atmospheric l release from Auxiliary Component Cooling Water (ACCW) via the j Wet Cooling Towers was performed. The activity released via these secondary pathways resulted from routine operations and [
remained below significant levels.
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8.6 Missed Effluent Samples: j 8.6.1 No liquid or gaseous effluent samples were missed during this reporting period.
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8.7 ~ Ma.ior Chanaes to Radioactive' Waste Systems During the reporting period, no Major Changes were made to any.
Radioactive Waste Systems.
8.8 Additional Information The most recent Reactor Coolant System E-Bar calculation was 0.763 MeV/ Disintegration from a sample obtained on June 1, 1993. Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.
9.0 TABLES 1 Batch Release Summary-1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents 18 Semiannual Airborne Continuous Elevated and Ground Level Releases IC Semiannual Airborne Batch Elevated and Ground Level Releases 2A Semiannual Summation of All Releases by Quarter - All Liquid Effluents 2B Semiannual Liquid Continuous and Batch Releases 3 Solid Waste Shipped Offsite for Disposal 4 Joint Frequency Distribution of Meteorological Data 5 Dose Calculation Results for 1993 10.0 ATTACHMENTS 10.1 Changes to Process Control Program; January 1,1993 to December 31, 1993 (8 pages) 10.2 Changes to Offsite Dose Calculation Manual; January 1,1993 to December 31, 1993 (127 pages) 0 W21419HP 18
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TABLE 1 (1 of 2)
REPORT CATEGORY : BATCH RELEASE
SUMMARY
RELEASE PolNT : ALL TTPE OF. RELEASE : BATCH LIQUID AND CASEQUS PERIOD START TIME 0:00 HRS . 12:00AM JANUART 1, 1993 PERIDD END TIME : 4343:59 HRS s 11:59PM JUNE 30, 1993 LIQJID RELEASES NUMBER OF RELEASES : 63 TOTAL TIME FOR ALL RELEASES : 16349.0 MINUTES MAXIMUM TIME FOR A RELEASE : 344.0 MINUTES AVERAGE TIME FOR A RELEASE : 259.5 MINUTES MINIMUM TIME FOR A RELEASE : 116.0 MINUTES AVERAGE STREAM FLOW t &36746.9 CPM CASE 005 RELEASES NUMBER OF RELEASES : 3 TOTAL TIME FOR ALL RELEASES : 994.0 MINUTES MAXIMUM TIME FOR A RELEASE : 565.0 MINUTES AVERAGE TIME FOR A RELEASE : 331.3 MINUTES MINIMUM TIME FOR A RELEASE : 159.0 MINUTES W21419HP 19 !
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REPORT CATEGORT : BATCH RELEASE SUMMART RELEASE POINT : ALL TYPE OF RELEASE : BATCH LIQUID AND CASEQUS PERIOD START. TIME : 4344:00 HRS = 12:00AM JULY 1, 1993-PERICD END TIME : 8759:59 HRS = 11:59PM DECEMSER 31, 1993 '
LIQUID RELEASES WUMBER OF RELEASES : 73 TOTAL TIME FOR ALL RELEASES : 18423.0 MINUTES MAXIMUM TIME FOR A RELEASE : 298.0 MINUTES AVERACE TIME FOR A RELEASE : 252.4 MINUTES MINIMUM TIME FOR A RELEASE : 60.0 MINUTES AVERAGE STREAM FLOW 904974.6 GPM GASEOUS RELEASES I
NLMBER OF RELEASES : 0 TOTAL TIME FOR ALL RELEASES : 0.0 MINUTES MAXIMLM TIME FOR A RELEASE : 0.0 MINUTEC
- AVERAGE TIME FOR A RELEASE : 0.0 MINUTES MINIMUM TIME FOR A RELEASE : 0.0 MINUTES 4 I
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.i TABLE 1A '
(1 of 2)
REPORT CATEGORY : SEMIANNUAL SUMMATION OF ALL RELEASES 87 QUARTER TYPE OF ACTIVITY : ALL AIRBORNE EFFLUENTS-REPORTING PERIOD QUARTER # 1 AND QUARTER # 2 l
- UNIT : QUARTER 1 : QUARTER 2 :EST. TOTAL:
- HOURS : HOURS : ERROR X :
TYPE OF EFFLUENT : : 1-2160 :2161-4344 : :
A. FIS$10N AND ACTIVATION PRCDUCTS
- 1. TOTAL RELEASE : CURIES : 2.68E 02 : 2.71E 02 : 1.50E 01:
- 2. AVERACE RELEASE RATE FOR PERIG) :UCl/SEC : 3.44E 01 : 3.45E 01 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
B. RADIO 10 DINES
- 1. TOTAL IG)INE-131 : CURIES : 1.79E-09 1.08E-06 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 2.30E-10 : 1.38E-07 :
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- 3. PERCENT OF APPLICABLE LIMIT % : N/A : N/A :
C. PARTICULATES i
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kbkkhkhb[hhhkHkLbLkhh8bkhhh bbkkh5 $b$bbhIb5 b$bbhbi:i$5bbb5:
- 2. AVERAGE RELEASE RATE FOR PERICO :UCI/SEC : 0.00E-01 : 0.00E-01
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A
- 4. CROSS ALPHA RADICACTIVITY : CURIES : 3.31E-06 : 5.20E.06 :
D. TRITILM
- 1. TOTAL RELEASE : CURIES : 3.11E 01 : 5.05E 01 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERICD :UCl/SEC : 4.00E 00 : 6.42E 00 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A
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REPORT CATEGORT : SEMIAhWUAL SUMMATION OF ALL RELEASES BT QUARTER TYPE OF ACTIVITY : ALL AIRSORNE EFFLUENTS REPORTING PERIOD : QUARTER # 3 AND QUARTER # 4
- UNIT : QUARTER 3 0UARTER 4 *EST. TOTAL:
- :NOURS : HOURS ERROR % :
TYPE OF EFFLUENT -
- 4345-6552 :6553-8760 : :
A. FIS$10N AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE : CURIES : 2.45E 02 : 1.30E 02 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 3.08E 01 : 1.64E 01 :
- 3. PERCENT OF APPLICABLE LIMIT t % . W/A +
N/A :
B. RADIO 10DlWES
- 1. TOTAL 10 DINE-131 : CURIES : 0.00E-01 : 0.00E 01 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 0.00E-01 : 0.00E 01 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
C. PARTICULATES
- 1. PARTICULATES(HALF-i!VES>8 DATS) : CURIES : 0.00E-01 : 0.00E-01 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERICO :UCI/SEC : 0.00E-01 : 0.00E-01 :
- 3. PERCENT OF APPLICABLE LIMIT : % i N/A . N/A :
- 4. GROSS ALPHA RAD 10 ACTIVITY : CURIES : 7.30E.06 : 5.66E-06 D. TRITIUM
- 1. TOTAL RELEASE : CURIES : 1.63E 01 2 3.82E 00 1.50E 01:
- 2. AVERACE RELEASE RATE FOR PERIOD :UCl/SEC : 2.05E 00 4.81F-01 i
...................................................................... j
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
W21419HP 22
TABLE IB (1 of 2) 1 l
4 REPORT CATECORT : SEMIANNUAL AIRBORNE CONTINUOUS ELEVATED AND GROUND l LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED. l TYPE OF ACTIVITT : FISSION GASES, 10 DINES, AND PARTICULATES REPORTING PERIOD QUARTER # 1 AND QUARTER # 2
. ELEVATED RELEASES : CROUND RELEASES :
- UNIT :0UARTER 1 : QUARTER 2 QUARTER 1 : QUARTER 2 :
- : HOURS : HOURS ; HOURS HOURS : !
NUCL1DE : : 1 2160 22161-4344 1 2160 :2161-4344 : i
................................................................................ I i
FISSION CASES XE 133 : CURIES : 0.00E 01 : 0.00E-01 : 2.46E 02 : 1.90E 02 :
XE-135 : CURIES : 0.00E-01 : 0.00E-01 : 1.18E 01 : 1.88E 01 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 : 2.58E 02 : 2.09E 02 : 1 10 DINES 1-131 : CURIES : 0.00E-01 : 0.00E-01 1.79E 09 1.08E 06 :
PARTICULATES H3 : CURIES : 0.00E-01 0.00E-01 : 3.11F 01 : 5.01E 01 :
G ALPHA : CURIES : 0.00E-01 : 0.00E.01 3.31E-06 : 5.20E-06 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.0')E.01 : 3.11E 01 : 5.01E 01 :
I i
I l
i l
W21419HP 23
)
L
TABLE 1B (2 of 2) i REPORT CATEGORY
- SEMI ANNUAL AIRBORNE CONTINUCUS ELEVATED AND CROUND
- LEVEL RELEASES. TOTALS FOR EACH NUCLICE RELEASED.
TYPE OF ACTIVITY : FISSION CASES, 100!NES, AND PARTICULATES REPORTING PERIOD : QUARTER # 3 AND QUARTER # 4
- ELEVATED RELEASES : CRCUND RELEASES :
- UNIT : QUARTER 3 : QUARTER 4 : QUARTER 3 QUARTER 4 :
- : HOURS : HOURS 3 HOURS : HOURS :
NUCLICE : :4345-6552 :6553 8760 84345-6552 :6553-8760 :
FISSION CASES KR*85M XE-133 CURIES : 0.00E-01 : 0.00E 01 : 1.74E 00 : 0.00E-01 :
- CURIES : 0.00E+01 : 0.00E-01 : 2.12E 02 1.30E 02 :
XE-135 : CURIES : 0.00E-01 : 0.00E 01 2.57E 01 : 0.00E-01 : 1 AR-41
- CURIES : 0.00E-01 : 0.00E 01 : 5.34E 00 0.00E-01 :
TOTAL FvR PERIOD
- CURIES . 0.00E-01 : 0.00E-01 : 2.45E 02 : 1.30E 02 100!NES NONE PARTICULATES H-3 G ALPHA
- CURIES : 0.00E-01 : 0.00E 01 : 1.63E 01 3.82E 00 - ,
CURIES : 0.00E 01 : 0.00E 01 : 7.30E 06 : 5.66E.06 TOTAL FOR PERIOD 1
R
- CURIES : 0.00E 01 : 0.00E*01 : 1.63E 01 2 3.82E 00 i
................................................................................ l l
I l
i W21419HP 24 i
TABLE 1C (1 of 2)
REPORT CATEGORY : SEMIANNUAL AIRBORNE BATCH ELEVATED AND CROUND
- LEVEL RELEASES. TOTALS FOR EACH NLCLIOE RELEASED.
TYPE OF ACTIVITY : FISSION CASES. IODINES, AND PARTICULATES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2 ELEVATEL RELEASES : CROUND RELEASES :
- UNIT : QUARTER 1 QUARTER 2 : QUARTER 1 : QUARTER 2 :
- : HOURS HOURS 3 HOURS : HOURS :
NUCLIOE : : 1 2160 :2161 4344 1-2160 22161-4344 :
FISSION GASES KR-85M XE-131M
- CURIES : 0.00E-01 : 0.00E 31 2 3.16E-03 : 1.72E*02 :
XE-133M CURIES : 0.00E 01 : 0.00E-01 : 0.00E 01 : 1.14E 00 :
- CURIES : 0.00E 01 : 0.00E 01 : 8.60E 02 5.19E-01 :
XE 133 XE-135
- CURIES : 0.00E 01 : 0.00E-01 : 9.38E 00 : 6.02E 01 :
AR-41
- CURIES : 0.00E 01 : 0.00E 01 : 6.18E-02 : 3.91E 01 :
- CURIES : 0.00E-01 : 0.00E 01 4.11E-02 : 2.66E 01 :
TOTAL FOR PERIOD : CURIES : 0.00E 01 : 0.00E 01 9.57E 00 6.25E 01 :
10 DINES NONE PARTICULATES H-3 : CURIES : 0.00E*01.2 0.00E 01 3.33E-03 3.28E 01 :
4 l
l j
W21419HP 25
-_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - _ - - _ _ J
TABLE IC (2 of 2)
REPORT CATEGORY : SENIANNUAL AIRBORNE BATCH ELEVATED AND CROUND
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TTPE OF ACT!VITY : FIS$10N GASES, IC0!NES, AND PARTICULATES RFPORTING PERIOD QUARTER 8 3 AND QUARTER # 4 ELEVATED RELEASES : CROUND RELEASES
- UNIT QUARTER 3 : QUARTER 4 :QUARTEk 3 QUARTER 4 :
- HOURS HOURS :NOUR$ HOURS :
NucLIDE : :4345 6552 36553 8760 4345 6552 36553 8760 :
FISSION GASES N0hE 10 DINES NONE PARTICULATES NONE I
1 l
\
W21419HP 26 I -
r
TABLE 2A (1 of 2)
REPORT CATEGORY : SEMIANNUAL SUMMATION OF ALL RELEASES Bf QUARTER TYPE OF ACT!VITT ALL LIQUID EFFLUENTS REPORTlWG PERICD : QUARTER # 1 AND QUARTER # 2 UNIT :QUARTSt 1 :oVARTER 2 :EST. TOTAL:
HOUh5 HO JRS : ERROR % :
TYPE OF EFFLUENT : : 1 2160 22161 4344 : :
A. FIS$10N AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUOnJG : 9 TRIT!UM, CASES, ALPHA) : CURIES : 1.49E 01 : 1.92E*01 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : : : :
DURING PER100 :UCI/ML : 7.35E 09 : 6.09E 09 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
B. TRITIUM
- 1. TOTAL RELEASE : CURIES : 4.97E 01 : 1.23E 02 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATI0w . : :
DURING PERICD :UCl/ML : 2.45E-06 : 3.92E-06
- 3. PERCENT OF APPLICABLE LIMIT : % i N/A N/A :
C. DISSOLVED AND ENTRAINED CASES
- 1. TOTAL RELEASE : CURIES : 4.42E-01 3.00E 01 : 1.50E 01:
- 2. AVERACE DILUTED CONCENTRATION : : :
DURING PERICD :UCI/ML : 2.18E 08 : 9.54E 09 :
- 3. PERCENT OF APPLICABLE LIMIT % : N/A : N/A :
D. CROSS ALPHA RADICACTIVITY
- 1. TOTAL RELEASE 2 CURIES : 0.00E 01 : 0.00E 01 1.50s 01:
E. WASTE VOL RELEASED (PRE
- DILUTION) : CAL : 3.15E 05 : 2.28E D6 1.50E 01:
F. VOLUME OF DILUTION WATER USED : GAL : 5.37E 09 : 8.31E 09 : 1.50E 01:
W21419HP 27
1 l
l TABLE 2A (2 of 2)
REPORT CATECORY SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY : ALL LIQUID EFFLUENTS REPORTlWG PERIOD : QUARTER # 3 AND QUARTER # 4
- UNIT QUARTER 3 : QUARTER 4 EST. TOTAL:
- : HOURS HOURS : ERROR % :
TYPE OF EFFLUENT : 4345 6552 26553 8760 : :
A. FISSION AND ACTIVATION PR: DUCTS
- 1. TOTAL RELEASE (NOT INCLUDING : : : : :
TRITIUM, CASES, ALPHA) : CURIES 2.22E 01 : 4.09E-02 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : : : :
DURING PERIOD :UCI/ML : 5.77E-09 : 1.66E.09 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
B. TRITILM
- 1. TOTAL RELEASE : CURIES : 2.14E 02 : 1.03E 02 : 1.50E 01:
- 2. AVERACE DILUTED CONCENTRATION : : :
DURING PERIOD :UCI/ML : 5.56E-06 : 4.17E-06 :
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A :
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CUR!ES : 6.96E 01 : 2.40E.01 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : : : 3 DURING PERIOD M * .. . * .60E 08 : 9.7M -09 :
- 3. PERCEN" *LICABLE LIMIT : 1 : N/A : N/A D . CJ ' ' O w RAD 10 ACTIVITY
- 1. TOTA JSE : CURIES : 0.00E-01 : 0.00E-01 : 1.50E 01:
E. WASTE VOL RELEASED (PRE-DILUTION) : CAL 2.69E 06 2.14E 06 : 1.50E 01:
F. VOLUME OF DILUTION WATER USED : CAL : 1.02E 10 : 6.50E 09 1.5DE 01:
W21419HP 28
TABLE 2B (1 of 4)
REPORT CATEGORY : SEMIANNUAL LIQUID CONTINUUUS AND BATCH RELEASES
- TOTALS FOR EACH NUCL10E RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2
- CONTINUOUS RELEASES : BATCH RELEASES :
- UNIT :DUARTER 1 : QUARTER 2 : QUARTER 1 QUARTER 2 :
- : HOURS HOURS : HOURS : HOURS :
NUCLIDE : : 1-2160 2161-4344 1 2160 32161 4344 :
ALL NUCLIOES H3 : CURIES : 0.00E-01 : - 7.55E-02 3 4.97E 01 : 1.23E 02 :
NA-24 : CURIES : 0.00E 01 0.00E 01 9.06E 06 : 7.95E-06 :
CR-51 : CURIES : 0.00E-01 : 0.00E-01 5.93E-04 2.92E 04 :
MN-54 : CURIES : 0.00E-01 0.00E-01 : 6.79E 04 2.66E 03 :
FE-55 : CURIES : 0.00E-01 : 0.00E 01 : 3.34E+02 : 2.70E-02 :
FE-59 : CURIES : 0.00E-01 : 0.00E 01 : 1.89E 04 0.00E-01 :
Co-58 : CL' RIES : 0.00E-01 : 0.00E 01 : 1.69E 02 : 1.61E 02 :
Co-60 : CURIES : 0.00E 01 : 0.00E 01 : 4.14E 03 : 1.66E-02 :
RB-88 : CURIES : 0.00E-01 : 0.00E-01 : 2.97E 02 : 0.00E-01 :
SR-92 : CURIES : 0.00E-01 : 0.00E-01 : 4.44E 05 : 1.50E-04 :
ZR-95
- CURIES : 0.00E-01 : 0.00E 01 : 9.90E 04 : 1.43E 03 :
ZR 97 : . CURIES : 0.00E-01 : 0.00E 01 : 0.00E 01 1.42E-05 :
NB 95
- CURIES : 0.00E-01 : 0.00E 01 : 2.15E 03 : 3.07E-03 :
MO 99
- CURIES : 0.00E-01 : 0.00E-01 : 1.58E 04 : 7.2BE 04 :
TC 99M
- CURIES : 0.00E-01 : 0.00E 01 2 3.95E-04 : 4.52E-04 :
RU 106 : CURIES : 0.00E-01 : 0.00E 01 : 0.00E 01 : 2.10E 05 :
AG 110M
- CURIES : 0.00E 01 : 0.00E-01 : 3.75E 04 : 1.50E*05 :
1 131 : CURIES : 0.00E-01 : 0 00E 01 4.26E-02 : 8.57E 02 :
1-132 : CURIES : 0.00E 01 : 0.00E-01 : 0.00E 01 : 5.32E 05 :
1 133 : Lod!ES : 0.00E-01 : 0.00E-01 : 2.29E-03 1.15E-02 :
1 135 : CURIES : 0.00E 01 : 0.00E 01 : 4.54E 05 : 1.70E 03 :
CS 134 : CURIES : 0.00E*0* 0.00E-01 2.01E-03 : 5.11E-03 :
CS-137 : CUR!ES : 0.00E-01 : 0.00E 01 : 2.90E-03 7.89E-03 :
BA 140 : CURIES : 0.00E 01 : 0.00E 01 8.89E 05 : 1.22E 04 :
LA 140 : CURIES : 0.00E*01 : 0.00E 01 : 0.00E-01 : 1.03E 05 :
LA-142 : CURIES : 0.00E 01 : 0.00E 01 : 8.08E-05 1.09E 04 :
CE 144
- CURIES : 0.00E-01 : 0.00E 01 : 0.00E-01 : 1.16E-04 :
W-187
- CURIES : 0.00E 01 : 0.00E 01 : 0.00E 01 : 2.9BE 04 :
b W21419HP 29
T/UBLE 2B r
(2 of 4)
REPORT CATEGORY :
SEMIANNUAL LIQUID CCNTINUQUS AND EATCH RELEASES
- TOTALS FOR EACH NUCLIOE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD QUARTER # 1 AND QUARTER # 2
- CONTINUOUS RELEASES : BA RELEASES :
...............................................................TCH .................
- UNIT : QUARTER 1 QUARTER 2 :DUARTER 1 : QUARTER 2 :
- : HOURS : HOURS : HOURS : HOURS t NUCLIDE : : 1-2160 22161-4344 : 1-
.............................................................. 2160 22161-4344.................:
ALL NUCLIDES CONTINUED KR-85M KR 85 : CURIES : 0.00E-01 : 0.00E 01 : 4.61E-04 0.00E-01 :
- CURIES : 0.00E-01 0.00E-01 : 8.33E-03 : 8.54E-03 :
KR 87 KR-88 : CURIES : 0.00E 01 : 0.00E-01 : 1.21E-04 0.00E-01 :
- CURIES : 0.00E 01 : 0.00E-01 5.57E-04 : 0.00E-01 t XE-131M XE-133M : CURIES : 0.00E-01 : 0.00E 01 : 7.39E-03 : 7.42E-03 :
XE 133 CURIES : 0.00E 01 : 0.00E 01 : 2.02E 03 6.77E-04 :
XE 135M : CURIES : 0.00E 01 : 0.00E-01 : 4.12E-01 : 2.80E-01 CURIES : 0.00E 01 0.00E 01 : 0.00E 01 : 1.47E 03 :
XE 135 AR-41
- CUR!ES : 0.00E 01 : 0.00E-01 1.06E 02 : 2.62E-03 1 Co 57 : CUR!ES : 0.00E 01 : 0.00E 01 : 5.85E-05 5.51E-05 :
58 124 : CURIES : 0.00E-01 : 0.00E 01 2 3.12E 05 : 1.32E 04 :
SN-113 : CURIES : 0.00E 01 : 0.00E-01 : 2.42E-04 : 6.07E 05 :
NB 97
- CURIES : 0.00E-01 : 0.00E-01 3.97E-04 : 9.49E 04 :
SB-122 : CURIES : 0.00E 01 : 0.00E-01 : 3.31E 04 1.69E 03 : !
S8-125 : CURIES : 0.00E 01 : 0.00E*01 : 1.10E 05 1.05E-05 : i BR 82 : CURIES : 0.00E 01 : 0.00E 01 : 8.59E 03 7.81E-03 :
- CURIES : 0.00E 01 0.00E 01
..........................................................:.5.14E-05 2 3.71E-05 :
TOTAL FOR PERIOD
- CURIES : 0.00E 01 : 7.55E-0 5.03E 01 : 1.24E 02 :
...................................................... 2.........................
1 I
l 1
W21419HP 30
_ __ ' ~ ' '
TABLE 2B (3 of 4)
REPORT CATEGORY :
SEMIANNUAL LIQUID CONTINU0US AND BATCH RELEASES
- TOTALS FOR EACH NUCLICE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLI0ES REPORTING PERIOD : QUARTER # 3 AND QUARTER # 4
- CONTINUOUS RELEAS :
......................................................ES BATCH RELEASES :
- UNIT
- QUARTER 3 : QUARTER 4 : QUARTER 3 : QUARTER 4 :
- HOURS : HOURS :NOURS NUCLIDE : HOURS :
- :4345-6552 36553-87
..................................................... 60 :4345 6552 :6553 8760 :
ALL NUCLI0ES H-3 -
CR-51 CURIES : 1.01E-01 : 6.19E-02 2.14E 02 : 1.03E 02 :
MN 54
- CURIES : 0.00E-01 : 0.00E 01 4.32E 04 : 0.00E-01 :
FE-55 : CURIES : 0.00E-01 : 0.00E-01 : 1.34E 03 2.625-03 :
- CURIES : 0.00E-01 0.00E-01 : 3.18E-03 : 3.37E-03 :
CO-58 : CURIES : 1.20E-06 0.00E 01 : 7.29E-03 : 7.56E-03 :
- CURIES : 0.00E-01 : 0.00E-01 7.95E 03
- 1.48E 02 :
SR-92 : CURIES : 0.00E-01 : 0.00E-01 : 8.03E-02 0.00E-01 :
ZR 95 : Ctut!ES : 0.00E-01 : 0.00E 01 : 0.00E-01 3.88E-05 :
ZR-97 : CURIES : 0.00E 01 : 0.00E-01 1.17E 03 : 1.93E-03 :
N8 95 : CURIES : 0.00E 01 2 0.00E 01 : 0.00E-01 : 2.17E 06 :
NO 99 : CURIES : 0.00E 01 : 0.00E-01 : 2.29E-03 4.37E 03 :
TC-99M : CURIES : 0.00E 01 : 0.00E-01 : 1.11E-03 0.00E-01 :
RU 106 : CURIES : 0.00E*01 : 0.00E 01 : 1.68E 03 9.33E-06 :
1-131 : CURIES : 0.00E-01 : 0.00E*01 : 0.00E-01 3 4.27E 04 1-132 : CURIES : 0.00E-01 : 0.00E 01 : 5.55E-02 2.69E 04 :
- CURIES : 0.00E 01 0.00E 01 : 2.37E 04 : 0.00E 01 1-133 1-135 : CURIES : 0.00E 01 : 0.00E-01 : 3.65E 02 3 4.97E-05
- CURIES : 0.00E*01 0.00E-01 : 6.16E-03 0.00E-01 :
CS-134 CS-137 : CURIES : 1.88E 06 : 4.62E-07 : 4.42E 03 : 1.44E 03 :
LA-140
- CURIES : 3.93E 06 : 1.56E 06 3.74E 03 t 1.38E 03 :
- CURIES : 0.00E-01 0.00E-01 : 7.14E 05 0.00E-01 :
LA-142 W-187 : CURIES : 0.00E 01 : 0.00E-01 : 2.21E-05 0.00E 01 :
KR-85M : CURIES : 0.00E-01 : 0.00E-01 : 4.39E-03 2 0.00E 01 :
- CURIES CURIES: 0.00E-01
- 0.00E 01 : 0.00E 01 : 1.05E-03 : 1.96E-06 :
KR-87 0.00E 01 : 8.73E-03 6.78E 03 :
KR-88 : CURIES : 0.00E 01 : 0.00E 01 : 2.12E 04 : 0.00E-01 :
XE-131M : CURIES : 0.00E 01 : 0.00E-01 : 1.13E-03 : 0.00E 01 :
- CURIES : 0.00E 01 0.00E-0 : 9.98E-03 7.83E-03 :
.......................................................1 .........................
l l
l l
I i
W21419HP 31
TABLE 2B (4 of 4)
REPORT CATEGORY : SEMIANNUAL LIQUID CONTINUQUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD : QUARTER # 3 AND QUARTER # 4
- CONTINU0US RELEASES : BATCH RELEASES :
UNIT : QUARTER 3 :00ARTER 4 : QUARTER 3 200ARTER 4 :
- : HOURS : HOURS : HOURS 2 HOURS :
NUCLICE : :4345-6552 :6553 8760 34345 6552 :6553 8760 :
ALL NUCLIDES CONTINUED XE 133M : CURIES : 0.00E-01 : 0.00E 01 : 4.30E 03 : 4.68E 04 :
XE-133 : CURIES : 0.00E 01 : 0.00E 01 5.49E-01 : 2.24E-01 :
XE-135M CURIES : 0.00E-01 : 0.00E-01 : 1.49E 02 3 0.00E 01 :
XE-135 : CURIES : 0.00E 01 : 0.00E 01 : 2.4TE 02 : 1.03E-03 :
AR 41 : CURIES : 0.00E-01 0.00E 01 : 1.1]E-03 0.00E-01 :
Co-57 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E 01 1.00E 04 :
SW 113 : CURIES : 0.00E 01 : 0.00E 01 1.57E-04 : 3.13E-D4 :
NB 97 : CURIES : 0.00E 01 : 0.00E 01 : 0.00E 01 : 2.36E 04 :
SB-122 : CURIES : 0.00E-01 : 0.00E 01 2 4.09F 05 1.63E 05 :
SB 125 : CURIES : 0.00E 01 : 0.00E 01 : 3.97E 03 1.93E-03 :
BR-82 : CURIES : 0.00E-01 : 0.00E-01 : 6.05E-05 0.00E-01 :
TOTAL PERIOD s' CURIES : 1.01E 01 : 6.19E 02 2.15E 02 :
- 03F 02 :
......'FOR W21419HP 32
-- m
TABLE 3 (1 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THRU 12/31/93 WASTE CONTAINER WASTE TOTAL TYPE VOLUME (ft3) VOLUME (m3) ACTIVITY (Ci) ERROR (B) Non Compacted Dry 2080 58.91 1.69E-01 *1 25%
Activity Waste Shipped to Scientific Ecology 0.00 0.00E+00 25%
Group for Volume Burial Volume Buried Activity Reductior. *
(B) Non Compacted Dry 2080 58.91 2.50E-02 *1 125%
Activity Waste Shipped to Alaron Corp for Volume 6.30 2.50E-02 i25%
Reduction
- Burial Volume Buried Activity Waste volumes shipped for volume reduction do not reflect final burial waste volumes unless otherwise stated. ;
- 1 Activity determined by estimations. I
- 2 Activity determined by measurements.
?
W21419HP 33
TABLE 3 (2 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THRU 12/31/93 WASTE CONTAINER WASTE TOTAL TYPE VOLUME (ft3) VOLUME (m3) ACTIVITY (Ci) ERROR (B) Non Compacted Dry 2080 58.91 1.88E-02 *1 125%
Activity Waste Shipped to ATG Group for 7.54 1.88E-02 25%
Volume Burial Volume Buried Activity Reduction *
(B) Non Compacted Dry 2080 58.91 9.39E-02 *1 i25%
Activity Waste Shipped to Quadrex for Volume 0.00 0.00E+00 25%
Reduction
- Burial Volume Buried Activity I
Waste volumes shipped for volume reduction do not reflect final burial waste ,
volumes unless otherwise stated.
- 1 Activity determined by estimations.
- 2 Activity determined by measurements.
W21419HP 34
l
- j i
TABLE 3 (3 of 8) .;
SOLID WASTE SHIPPED 0FFSITE-FOR DISPOSAL
]
DURING PERIOD 1/1/93 THRU 12/31/93 i
WASTE CONTAINER i WASTE TOTAL TYPE VOLUME (ft3) VOLUME (m3) ACTIVITY (Ci) ERROR :l (A) Resin Waste Management 170.8 4.84 9.04E+01 *2 125%
Resin Dewatered in a >
High Integrity i Container (Bead Resin)
(A) Liquid Waste Management 370.2 10.49 1.22E+01 *2 f25% .
Resin Dewatered in a ,
High Integrity Container (Bead .
Resin) l t
Waste volumes shipped for volume reduction do not reflect final bu~ rial waste volumes unless otherwise stated. .
- 1 Activity determined by estimations.
- 2 Activity determined by measurements. !
I W21419HP 35 l
)
TABLE 3 (4 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THRU 12/31/93 1
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION' 3 Sole Use Cask Barnwell, SC' 3 Sole Use Flatbed Oakridge, TN 1 Sole Use Flatbed Wampum, PA. ;
1 Sole Use Flatbed Hanford, WA WASTE # OF TYPE OF CLASS SHIPMENTS TYPE CONTAINER MODE DESTINATION B 1 >A LSA Poly - HIC Truck . Barnwell, SC AU 1 LSA Strong-Tight Truck Wampum, PA f AU 1 LSA Strong-Tight Truck Hanford, WA
{
AU 1 LSA Strong-Tight Truck . Barnwell, SC AU 3 LSA Strong-Tight Truck OakRidge, TN AS 1 LSA Strong-Tight Truck -Barnwell, SC <
l W21419HP 36 1
TABLE 3 (5 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THRU 12/31/93
SUMMARY
BY MAJOR WASTE TYPES (A) Spend Resins, Filter Sludges, Evaporator Bottoms, etc.
(B) Dry Compressible Waste, Contaminated Equipment, etc.
(C) Irriaded Components, Control Rods, etc.
(D) Other (N/A)
WASTE WASTE TOTAL TYPE 3 VOLUME (M ) ACTIVITY (C1) ERROR l
(A) 15.33 1.03E+02 i25%
.1 (B) 235.70* 3.07E-01 i25%
(C) NONE N/A' N/A (D) NONE N/A N/A :
- Includes all Type (B) waste volume.
W21419HP 37
A TABLE 3 (6 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL- l DURING PERIOD 1/1/93 THRU 12/31/93 1
. .l
SUMMARY
BY MAJOR WASTE TYPE (Cont'd) l 1
WASTE TYPE NUCLIDE NAME % ABUNDANCE CURIES l
1 (A) Co-58 3.70E+01 3.80E+01 l Co-60 8.32E+00 8.53E+00 i Cs-134 4.18E+00 4.29E+00 )
Cs-137 6.14E+00 6.30E+00 Fe-55 1.01E+01 1.04E+01 Mn-54 4.96E+00 5.09E+00 Ni-63 2.74E+01 2.81E+01 Ni-59 1.51E-02 1.55E-02 !
Sb-125 1.28E+00 1.32E+00 l Sr-90 3.81E-03 3.91E-03 Ce-144 9.19E-02 9.42E-02 H-3 3.04E-01 3.12E-01 C-14 2.19E-01 2.24E-01 Pu-238 1.15E-04 1.18E-04 Pu-239/240 4.84E-05 4.96E-05 Pu-241 1. 70E-02 1.74E-02 Am-241 2.16E-05 2.21E-05 Cm-242 5.50E-04 5.64E-04 Cm-243/244 5.93E-04 6.08E-04
' W21419HP 38
-- q y-- M "
w 19g--m Tr#.g T
TABLE 3 (7 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THr.U 12/31/93
SUMMARY
BY MAJOR WASTE TYPE (Cont'd)
WASTE TYPE NUCL1DE NAME % ABUNDANCE CURIES (B) Co-57 6.92E-01 2.13E-03 Co-58 3.44E+01 1.06E-01 Co-60 2.04E+01 6.25E-02 Cs-134 4.03E+00 1.24E-02 Cs-137 8.18E+00 2.51E-02 Fe-55 1.:'c+01 3.56E-02 Mn-54 4.03E+00 1.24E-02 Ni-63 3.43E+00 1.05E-02 Fe-59 1.03E+00 3.15E-03 Ni-59 2.62E-07 8.05E-05 Sb-125 1.18E-01 3.63E-04 Nb-95 9.97E-01 3.06E-03 Zr-95 5.12E-01 1.57E-03 Sr-89 3.19E-03 9.80E-06 Sr-90 1.34E-03 4.10E-06 Ce-141 1.33E-01 4.08E-04 Sn-113 2.31E-01 7.10E Ce-144 8.99E-02 2.76E-04 Cr-51 9.99E+00 3.04E H-3 3.28E-02 1.01E-04 C-14 2.17E-01 6.66E-04 Pu-238 1.18E-04 3.63E-07 Pu-241 4.43E-04 1.36E-06 !
Am-241 1.48E-04 4.54E-07 Cm-242 2.66E-03 8.17E-06 Cm-243/244 6.94E-04 2.13E-06 W21419HP. 39
TABLE 3-(8 of 8)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/93 THRU 12/31/93 NOTES NOTE 1: Scientific Ecology Group sent a combined total of 1.70E-01 M3 of Type B waste with a total of 5.82E-05 Curies of activity for bur.ial.
Estimates of the major nuclide composition are included the previous Effluent Release Reports. This waste was generated in 1992.
W21419HP 40
TABLE 4 (1 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA Joint frequency distribution of wind speed and direction in hours 01 01 93 00:00to 12 31 93 23:59 Pasquilt Class A Wind speed (M/s) at 10 m Level Wind Direct ion .35 .50 .51.75 .76 1.0 1.1 1.5 1.6-2.0 2.1 3.0 3.1 5.0 5.1 7.0 7.1 10 10.1-13 13.1 18.0 >18.0 Total O O 0 1 8 29 34 10 1 0 0 0 83 0 0 0 1 11 23 44 7 0 0 0 0 86 NE D 0 0 0 8 64 139 10 0 0 0 0 221 ENE O O 0 1 1 19 23 1 0 0 0 0 45 E 0 0 0 0 2 5 6 0 0 0 0 0 13 EsE O O O O O 4 10 3 0 0 0 0 17 sE O O O 1 0 3 15 9 0 0 0 0 28 SSE O O O O O 8 13 15 0 0 0 0 36 s 0 0 0 0 1 12 44 24 8 0 0 0 89 ssW 0 0 0 2 3 5 26 6 0 0 0 0 42 sw .0 0 0 2 3 17 46 4 0 0 0 0 72 Wsw 0 0 0 1 7 18 18 4 0 0 0 0 48 W 0 0 0 0 6 18 14 8 1 0 0 0 47 VWW 0 0 0 0 5 12 25 8 0 0 0 0 50 NW D 0 0 1 3 19 34 5 1 0 0 0 63 NNW D 0 0 2 3 25 48 23 5 0 0 0 106 Total 0 0 0 12 61 281 539 137 16 0 0 0 1046 Nurber of cates for A Stability: 0 Joint frequency distribution of wind speed and direction in hours 01-01 93 00:00to 12 31-93 23:59 Pasquill Class B Wind Speed (M/s) at 10 m Level Wind Direction .35 .50 .51.75 .76-1.0 1.1 1.5 1.6 2.0 2.1-3,0 3.1 5.0 5.1 7.0 7.1-10 10.1 13 13.1 18.0 >18.0 Totat N O 0 0 3 8 12 4 8 0 0 0 0 35 NNE O 0 0 1 4 13 9 4 0 0 0 0 31 NE O O O 3 4 29 23 0 0 0 0 0 59 ENE O O 0 0 1 8 8 1 0 0 0 0 18 E 0 0 0 0 2 5 3 1 0 0 0 0 11 ESE 0 0 0 0 0 2 4 1 1 0 0 0 8 SE D 0 0 0 0 3 10 9 0 0 0 0 22 ssE O O 0 0 1 2 19 3 1 0 0 0 26 s 0 0 0 0 0 4 15 10 3 0' 0 0 32 ssW 0 0 0 1 2 5 7 3 0 0 0 0 18 SW 0 0 0 3 1 5 7 1 0 0 0 0 17 Wsw 0 0 0 3 4 5 8 0 0 0 0 0 20 W 0 0 0 1 4 8 6 1 0 0 0 0 20 WNW 0 0 0 1 2 11 4 0 0 0 0 0 18-NW D 0 0 2 2 4 3 1 1 0 0 0 13 NWW 0 0 0 1 6 11 11 6 2 0 0 0 37 Total 0 0 0 19 41 127 141 49 8 0 0 0 385 Nurber of calms for B Stability: 0 W21419HP 41
..v . y. y-- , - . . ,
._ - . . ~ .
TABLE 4 (2 of 4)
JOINT FREQUENCY DISTRIBUTION.0F METEOROLOGICAL DATA Joint frequency distribution of wind speed and direction in hours 01 01 93 00:00to 12 31-93 23:59 Pasquilt Class C Wind speed (M/S) at 10 m Level Wind Direct ion .35 .50 .51. 75 .76-1.0 1.1 1.5 1.6 2.0 2.1 3.0 3.1 5.0 5.1-7.0 7.1-10 10.1 13 13.1-18.0 >18.0 Total N 0 0 0 1 8 10 8 6 1 0 0 0 34 NNE O 0 0 1 6 15 15 2 1 0 0 0 40 NE D 0 0 2 9 16 26 1 0 0 0 0 54 ENE O O O 3 5 6 9 1 1 0 0 0 25 E O O O 2 1 1 5 3 0 0 0 0 12 ESE O O O O 1 3 3 3 2 0 0 0 12 SE O O 0 0 2 6 11 14 2 0 0 0 35 SSE O O O O 3 11 15 4 0 0 0 0 33 S 0 0 0 0 2 5 23 5 1 0 0 0 36 SSW 0 0 1 1 1 7 9 4 0 0 0 0 23 SV 0 0 1 0 2 3 9 2 0 0 0 0 17 WSW 0 0 0 2 6 5 10 1 0 0 0 0 24 W 0 0 0 1 6 4 8 3 0 0 0 0 22 WNW 0 0 0 2 2 6 5 0 0 0 0 0 15 ,
NW 0 0 0 1 2 4 5 1 0 0 0 0 ;
13 NNW 0 0 0 0 5 4 15 17 5 0 0 0 46 ;
l Total 0 0 2 16 61 106 176 67 13 0 0 0 441
]
Nwber of calms for C Stability: O l
1 Joint frequency distribution of wind speed and direction in hours 01 01-93 00:00to 12 31 93 23:59 Pasquill Class D 1
Wind speed (M/S) at 10 m Level l Wind Ofrection .35 .50 .51 .75 .76 1.0 1.1 1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1 10 10.1 13 13.1 18.0 >18.0 Total N 0 0 3 6 22 51 145 62 10 1 1 0 301 NNE 0 0 1 11 19 41 80 29 5 3 0 0 189 NE 1 0 3 13 22 52 92 12 3 0 0 0 198 i ENE O 1 1 2 10 28 58 20 4 0 0 0 124 l E O O 3 2 4 9 37 17 2 0 0 0 74 l ESE O 0 1 1 4 12 75 43 2 0 0 0 138 l SE D 0 2 3 2 29 71 31 8 0 0 0 146 j SSE O O 1 11 12 41 93 31 0 1 0 0 190 l S 0 0 1 10 19 49 66 28 15 0 0 0 188 SSV 1 1 6 6 16 34 30 14 0 0 0 0 108 SW 1 2 2 9 19 33 33 5 0 0 0 0 104 WSW 0 0 7 7 10 17 19 1 0 0 0 0 61 V 0 0 6 19 18 18 13 7 0 0 0 0 81 WNW 0 0 1 5 12 15 9 1 0 0 0 0 43 NW 0 1 3 6 6 24 27 12 1 0 0 0 80 WWW 0 0 0 8 13 45 111 45 5 0 0 0 227 Total 3 5 41 119 208 498 959 358 56 4 1 0 2252 Nwber of calms for 0 Stability 0 W21419HP 42
~ . - - . - . - ~~ ._ .__ ~ . . - - .- .. . -.
TABLE 4 (3 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA Joint frequency distribution of wind speed and direction in hours 01-01 93 00:00to 12-31-93 23:59 Pasquill Class E Wind Speed (M/S) at 10 m tevel Wind Di rect ion .35 .50 .51 75 .76 1.0 1.1 1.5 1.6 2.0 2.1 3.0 3.1 5.0 5.1 7.0 7.1 10 10.1 13 13.1-18.0 >18.0 Total N 0 0 6 17 35 87 107 15 1 2 0 0 270 NNE 1 1 4 21 26 52 77 8 1 0 0 0 191 NE O 2 3 24 33 91 99 8 7 0 0 0 267 ENE 1 1 2 10 22 55 66 13 1 1 0 0 172 E O 3 3 9 8 40 54 9 0 1 0 0 127 ESE 1 1 5 8 9 39 70 10 1 0 0 0 144 SE 1 0 2 7 27 63 44 13 0 0 0 0 157 SSE 4 5 4 28 59 93 54 6 o 0 0 0 253 S 1 6 14 35 46 44 32 3 5 0 0 0 186 SSW 1 6 14 38 23 33 24 4 0 0 0 0 143 SW 2 7 16 37 31 23 20 2 0 0 0 0 138 WSW 0 8 17 41 25 36 16 0 0 0 0 0 143 W 2 4 14 47 21 17 8 2 0 0 0 0 115 WNW 2 5 6 35 21 15 3 0 0 0 0 0 87 NW 0 4 5 18 17 21 14 1 0 0 0 0 80 kWW 0 2 8 8 17 39 44 3 5 1 0 0 12 Total 16 55 7........
123 383 420 748 732 97 21 5 0 0 2600 Nmber of calms for E Stability: 11 Joint frequency distribution of wind speed and direction in hours 01 01-93 00:00to 12-31-93 23:59 Pasquilt Class F Wind Speed (M/S) at 10-m Level Wind O f rection .35 .50 .51 75 .76-1.0 1.1 1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1 7.0 7.1-10 10.1 13 13.1 18.0 >18.0 Total N 9 10 14 1 8 10 0 1 0 0 0 0 53 NNE 1 6 4 16 9 12 3 0 0 0 0 0 51 NE 1 2 6 10 18 23 6 0 0 0 0 0 66 ENE 1 1 3 9 10 10 5 0 0 0 0 0 39 E 2 1 1 4 1 4 4 0 0 0 0 0 17 ESE 1 2 3 3 2 0 1 0 0 0 0 0 12 SE 2 4 6 14 6 14 3 0 1 0 0 0 50 SSE 3 7 17 45 51 26 3 0 0 0 0 0 152 S 4 20 41 94 30 5 0 2 0 0 0 0 196 SSW 1 29 54 72 15 7 0 1 0 0 0 0 179 SW 6 24 50 40 9 2 0 0 0 0 0 0 131 WSW 11 21 34 49 17 4 0 0 0 0 0 0 136 W 2 9 31 34 11 2 0 0 0 0 0 0 89 WNW 4 6 16 16 7 1- 0 0 0 0 0 0 50
-NW 5 1 8 12 17 7 0 0 0 0 0 0 50 NWW 2 6 10 15 10 9 1 1 0 0 0 0 54 Total 47 148 294 447 221 136 27 5- 0 0 0 0 1325 Nwber of calms for F Stability: 28 W21419HP 43
. ~ . . - . . . . - - . . . . . . .- .. _ . ~ . .n . .w ~ , , _ . .
TABLE 4 (4 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA Joint frequency distribution of wind speed and direction in hours 01 01 93 00:00to 12-31 93 23:59 Pasquill Class G Wird Speed (M/S) at 10-m Level Wind Direction .35 .50 .51. 75 .76 1.0 1.1 1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7,0 7.1 10 10.1-13 13.1 18.0 >18.0 Total N 6 9 6 5 3 1 1 0 0 0 0 0 31 NNE 0 3 5 10 2 0 0 0 0 0 0 0 20 kE O 2 3 8 6 3 0 0 0 0 0 0 22 ENE 2 1 0 2 0 2 0 0 0 0 0 0 -7 E O 1 1 2 0 7 5 0 0 0 0 0 ' 16 '
ESE O 2 2 1 2 1 5 0 0 0 0 0 .13 SE 1 3 0 3 5 2 2 0 0 0 0 0 16 SSE 2 2 4 12 9 2 0 0 0 0 0 0 31 S 3 8 19 35 7 0 0 0 0 0 0 0 72 SSW 2 12 32 29 7 0 0 0 0 0 0 0 82 SW 6 22 43 17 1 0 0 0 0 0 0 0 89 WSW 1 23 28 8 1 0 0 0 0 0 0 0 61 W 9 25 16 7 0 0 0 0 0 0 0 0 57 WWW 3 12 12 6 0 0 0 0 0 0 0 0 33 NW 8 11 5 3 0 0 0 0 0 0 0 0 27 kNW 3 12 7 11 3 0 0 0 0 0 0 0 36 Total 46 148 1&3 159 46 18 13 0 0 0 0 0 613 Number of calms for G Stability: 59 Total valld hours for all stabilities = 8760 Total invalld hours for all stabilities = 0 W21419HP 44
TABLE 5 (1 of 2)
DOSE CALCULATION RESULTS FOR 1993 (DOSES DUE TO GASE0US RADI0 ACTIVE EFFLUENTS)
- UNIT 1 ** QUARTER 1 0F 1993 " " UN I T 1 " QUARTER 3 0F 1993 "
DOSE FROM RAD 10100lNES, PARTICULAIES, AND TRITIUM DOSE FROM RADIO 100lNES, PARTICULATES, AND TRITIUM AT CONTROLLING LOCATION:
T E NE : 2.6648E-09 TOTAL DOSE (MREM) FOR BONE : 0.0000E 01 TOTAL DOSE (MREM) FCR LIVER 2.8246E-02 TOTAL DOSE (MREM) FOR LIVER : 1.4824E 02 TOTAL DOSE (MREM) FOR TOTAL BCDY : 2.8246E 02 TOTAL DOSE (MREM) FOR TOTAL BODY : 1.4824E-02 TOTAL DOSE (MREM) FOR THYR 0!D : 2.8247E 02 TOTAL DOSE (MREM) FOR THYRolo : 1.4824E 02 TOTAL DOSE (MREM) FOR KIDNEY : 2.8246E-02 TOTAL DOSE (MREM) FOR KIDNEY : 1.4824E 02 TOTAL DOSE (MREM) FOR LUNG : 2.8246E-02 TOTAL DOSE (MREM) FOR LUNG : 1.4824E-02 TOTAL DOSE (MREM) FOR GI-LLI : 2.8246E-02 TOTAL DOSE (MREM) FOR GI LLI : 1.4824E 02 NO LE GAS DOSE AT SITE BOUNDARY: NOBLE GAS DOSE AT SITE BOUNDARY:
TOTAL BODY DOSE TOTAL (MREM) 4 6.7678E-02 TOTAL BTY DOSE TOTAL (MREM) : 1.1023E 01 SKIN DOSE TOTAL (MREM) : 1.5793E-01 SKIN DOSE TOTAL (MREM) : 2.2655E 01 NOBLE GAS AIRDOSE AT SITE BOUNDARY: NOBLE GAS AIRDOSE AT SITE BOUNDARY:
TOTAL GAMMA AIRDOSE (MRAD) : 7.9124E-02 TOTAL GAMMA AIRDOSE (MRAD) : 1.2272E 01 total BETA AIRDOSE (MRAD) : 2.0774E-01 TOTAL BETA AIRDOSE (MRAD) : 2.1390E-01
- UNIT 1 " QUARTER 2 0F 1993 " " UNIT 1 ** QUARTER 4 0F 1993 "
DOSE FROM RADICICX)!NES, PARTICULATES, AND TRITIUM DOSE FRC84 RADioltX)!NES, PARTICULATES, AND TRITIUM AT CONTROLLING LOCATION: AT CONTROLLING LOCATION:
TOTAL DOSE (MREM) FOR BONE : 1.6116E-06 TOTAL DOSE (MREM) FOR BONE : 0.0000E-01 TOTAL DOSE (MREM) FOR LIVER : 4.5887E-02 TOTAL DOSE (MREM) FOR LIVER : 3.4717E 03 TOTAL DOSE (MREM) FOR TOTAL 800y : 4.5886E-02 TOTAL DOSE (MREM) FOR TOTAL B00f : 3.4717E 03 TOTAL DOSE (MREM) FOR THYROID : 4.6504E-02 TOTAL DOSE (MREM) FOR THYR 010 3 3.4717E 03 TOTAL DOSE (MREM) FOR KIDNEY : 4.5888E 02 TOTAL DOSE (MREM) FOR KIDNEY : 3.4717E-03 TOTAL DOSE (MREM) FOR LUNG : 4.5885E 02 TOTAL DOSE (MREM) FOR LUNG 3.4717E-03 TOTAL DOSE (MREM) FOR GI-LLI : 4.5885E 02 TOTAL DOSE (MREM) FOR GI LLI : 3.4717E-03 NO2LE CAS DOSE AT SITE BOUNDARY: NOBLE CAS DOSE AT SITE BOUNDARY:
TOTAL BODY DOSE TOTAL (MREM) : 7.7224E 02 TOTAL BODY DOSE TOTAL (MREM) : 2.6676E-02 SKIN DOSE TOTAL (MREM) : 1.7846E 01 SKIN DOSE TOTAL (MREM) : 6.3317E 02 NOSLE CAS AIRDOSE AT SITE BOUNDARY: NOBLE CAS AIRDOSE AT S!TE BOUNDARY: I TOTAL GAMMA AIRDOSE (MRAD) : 8.9147E-02 TOTAL GAMMA AIRDOSE (MRAD) : 3.2029E-02 TOTAL BETA AIRDOSE (MRAD) : 2.1812E-01 TOTAL BETA AIRDOSE (MRAD) : 9.5271E 02 l
l
- UNIT 1 " TOTALS FOR 1993 "
DOSE FROM RADIO!CK)lNES, PARTICULATES, AND TRITIUM i AT CONTROLLING LOCATION:
TOTAL DOSE (MREM) FOR BONE : 1.6143E-06 TOTAL DOSE (MREM) FOR LIVER : 9.2429E 02 TOTAL DOSE (MREM) FOR TOTAL BODY : 9.2428E 02 I TOTAL DOSE (MREM) FOR THYROID : 9.3046E 02 TOTAL DOSE (MREM) FOR KIDNEY : 9.2429E-02 ;
TOTAL DOSE (MREM) FOR LUNG : 9.2427E-02 l TOTAL DOSE (MREM) FOR GI LLI : 9.2427E-02 NOBLE GAS DOSE AT SITE BOUNDARY:
TOTAL BODY DOSE TOTAL (MREM) : 2.8181E 01 SKIN DOSE TOTAL (MREM) : 6.2626E 01 NOBLE GAS AIRDOSE AT 5!TE BOUNDARY:
TOTAL CAMMt AIRDOSE (MRAD) : 3.2302E 01 TOTAL BETA AIRDOSE (MRAD) : 7.3503E 01 W21419HP 45
TABLE 5 (2 of 2)
DOSE CALCULATION RESULTS FOR 1993 (DOSES DUE TO LIQUID RADIDACTIVE EFFLUENTS)
- UNIT 1 ** QUARTER 1 0F 1993 **
TOTAL DOSE (MREM) FOR BONE : 1.0031E-02 TOTAL DOSE (MREM) FOR LIVER : 1.7300E 02 TOTAL DOSE (MREM) FOR TOTAL 80DY 1.2665E 02 TOTAL DOSE (MREM) FOR THYR 010 : 1.7643E-02 TOTAL DOSE (MREM) FOR KIDNEY : 5.8142E-03 10TAL DOSE (MREM) FOR LUNG : 1.9995E-03 TOTAL DOSE (MREM) FOR GI LLI : 1.0014E-03
- UNIT 1 ** QUARTER 2 0F 1993 **
TOTAL DOSE (MREM) FOR SONE : 2.5477E-02 TOTAL DOSE (MREM) FOR LIVER : 4.8603E 02 TOTAL DOSE (MREM) FOR TOTAL B@Y : 3.6873E 02 TOTAL DOSE (MREM) FOR THYRotD : 3.3643E 02 TOTAL DOSE (MREM) FOR KIDNEY : 1.9674E-02 TOTAL DOSE (MREM) FOR LUNG : 9.9608E-03 TOTAL DOSE (MREM) FOR GI-LLI : 7.2308E-03
- UNIT 1 ** QUARTER 3 0F 1993 **
TOTAL DOSE (MREM) FOR BONE : 8.072BE 02 TOTAL DOSE (MREM) FOR LIVER : 1.320$E 01 TOTAL DOSE (MREM) FOR TOTAL SCX)Y : 9.4257E 02 TOTAL DOSE (MREM) FOR THYROID : 4.7652E 02 TOTAL DOSE (MREM) FOR K!DNEY : 4.9969E 02 l TOTAL DOSE (MREM) FOR LUNG : 2.2094E 02 I TOTAL DOSE (MREM) FOR GI LLI : 1.2763E 02 l
- UNIT 1 ** QUARTER 4 0F 1993 **
TOTAL DOSE (MREM) FOR BONE : 1.4759E 02 TOTAL DOSE (MREM) FOR LIVER : 3.1'43E 02 TOTAL DOSE (MREM) FOR TOTAL BODY : 2.4300E 02 TOTAL DOSE (MREM) FOR THYROID : 6.7423E 03 TOTAL DOSE (MREM) FOR KIDNEY : 1.4796E 02 TOTAL DOSE (MREM) FOR LUNG : 9.3605E 03 TOTAL DOSE (MREM) FOR GI LLI 8.1838E 03
- UNIT 1 ** TOTALS FOR 1993 **
TOTAL DOSE (MREM) FOR BONE : 1.3099E 01 TOTAL DOSE (MREM) FOR LIVER : 2.2910E 01 TOTAL DOSE (MREM) FOR TOTAL BODY : 1.6809E 01 TOTAL DOSE (MREM) FOR THYROID : 1.056BE 01 10TAL DOSE (MREM) FOR KIDNEY : 9.0253E 02 TOTAL DOSE (MREM) FOR LUNG : 4.3415E 02 TOTAL DOSE (MREM) FOR GI LLI : 2.9179E 02 W21419HP 46
ATTACHMENT 10.1 (8 PAGES) b
-l CHANGES TO RW-001-210, PROCESS CONTROL PROGRAM (PCP) c t
January 1, 1993 To December 31, 1993 i
W21419HP 47 l
L PORC/IORC 00- O RW-001-210 REVISION 6 UTECTIVE DATE 1
W-3 RECORDS UNCONTROLLED COPY DO NOT USE IN ANY SAFETY - RFaTED TESTING.
MAINTENANCE. 09 OPERATK#eAL ACTMTY.
l l
SAFETY-RELATED :
i ADMINISTRATIVE PROCEDURE -
l l
)
UNT-001-002 Revision 12 Attachment 6.3 (1 of 2) 41
- PORC AND PORC - S/C REVIEW AND APPROVAL SHEET REVIEW OF: RW-001-210 - Process Control Program PORC D (Rev. 6) PORC - S/C D 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 does not exist, and that nuclear safety is/was not adversely affected.
PORC RECOMEED FOR AMOM MEMBER SIGNATURE NO MEMBER YES Maintenance j /. /
Superintendent
/
// j Operations / //'
Superintendent '
fAM /A MyQ Radiation Protection C Superintendent Quality Assurance f/' / "
Member
[h g.
Mgmt Knowledgeable )
V
( /
in Engineering j hp Manager Operations & V Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member Meeting No.93-054 Item No. VI- 0 Date: 8/5/93 This item is recommended for approval? Cl YES O NO This item requires SRC/NRC review prior to implementation? D YES D NO-If yes, ensure documentation supporting review is attached.
SIGNATURE RECOMMENDED FOR APPROVAL' YES NO DATE PORC-S/C Chairman j PORC Chairman {} gg) gg l Comments:
O,bh / /
Approved by N Date h/h/h General Manager Plant Operations UNT-001-004 Revision 14 Attachment 6.1 (1 of 1) 23
WATERFORD 3 SES Check Block-
, PLANT OPERATING MANUAL -
@ PORC CHANGE / REVISION / DELETION REQUEST PORC-S/C Procedure No.: [L/ -D 0 / - 2 I O
Title:
d m i n ,'s -u k'o e [<ocedo,<
lr e c e e t l',,,b-o [
A o3 < c. -
Effective Date : (if different from approvaldate)
COMPLETE A. B and C:
A. Change No.:
D. Revision:
N/4
/,
@ Permanent O Deviation Expiration Date:
C. Deletion: 0 Yes @ No DESCRIPTION OF CHANGE, REVISION, OR DELETION: Ad1#1 / e h e - e 1, - c t 2 . I . w , .2 . I . , . r r v . neL L k h L- Co n i-clie d Do de s h 1] A. 1 4 c A l1 0.e.l .- ,,m LL-~m.~k Wo% > c d l'c, e e d. l e 5 REASON FOR CHANGE, REVISION, OR DELETION: _ v'c nd 1, - $ o /! b [ ; r.m'. e a procc-sy p i s exh u , e s , ,, l l be a ypi e u , ,\ ~S ple ) ,1,o n a L , ,a ,
1 Originator: [/c Ou {< eo e Date: 6 3 OO 3 Tcchnical Revieb wh b Date: 3-b-9D ,
Group Head Revie[3 t! Date: 7h
- TEMPORARY APPROVAL: Data:
'R:fer to paragraphs 3.2.18 and 5.3.2.10c for temporary approval requirements UNT-001-003 Revision 16 Attachment 6.4 (1 of 1)
, 42
Administrative Procedure RW-001-210 Process Control Program Revision 6 l TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
~
3.0 DEFINITIONS 4.0 RESPONSIBILITIES l 5.0 PROCEDURE 5.1 Program Description 5.2 salidification Process Parameters 5.3 Administrative Controls 5.4 Waste Characterization and Classification 5.5 Quality Assurance 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 6 1-11 Revision 6 i
l 1 1
i I
- - - - - - - _ - - - - - - - - - - - - -- ---- -- -- -- - ]
Administrative Procedure RW-001-210 Process Control Program Revision 6 1.0 PURPOSE 1.1 The purpose of Waterford Steam Electric Station - Unit Number 3 (Waterford 3) Process Control Program (PCP) is to describe the program which provides reasonable assurance of the complete.
stabilization and/or solidification, as applicable of radioactive " wet waste" which may include resin slurries are in.
accordance with applicable Department of Transportation (DOT),
Nuclear Regulatory Commission (NRC), State and licensed burial facilities acceptance criteria for packaging and shipment to an approved burial site. Compliance with these criteria will be achieved through implementation of the PCP ar.d related Waterford 3 and vendor supplied procedures. Containers engineered and built to comply with the stability requirement may be used. Waterford.3 SES typically relies on Vendor supplied systems and/or services for stabilization and solidification services, i 2.0 MFERENCES 1
l 2.1 Waterford 3 Documents 2.1.1 FSAR Chapter 11.4, Solid Waste Management System l
2.1.2 FSAR Chapter 13.4, Review and Audit I 2.1.3 FSAR Chapter 13.2, Training 2.1.4 FSAR Chapter 13.5, Plant Procedures 2.1.5 Quality Assurance Program Manual (Special Scope)
)
{
Chapter 5 I 2.1.6 RW-002-401 Use of Radman Operating Program 2
Administrative' Procedure RB-001-210 Process Control Program. Revision 6 2.1.7 RW-002-411 Use of Radman Data Base. Manager and Recover 2.1.8 RW-002-110 Waste Sample Collection and Isotope Evaluation 2.2 Other Doc ~uments 2.2.1 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste 2.2.2 10CFR20.311, Transfer for disposal and manifests 2.2.3 10CFR71.91, Records 3.0 DEFINITIONS 3.1 Stability means structural stability as per 10CFR61.2 3.2 Solidification means the immobilization of wet radioactive wastes such as spent resins, sludges, and reverse osmosis concentrates as a result of a process of mixing the waste type with a solidification agent (s) to meet the requirements of the licensed disposal site and 10CFR61.
4.0 RESPONSIBILITIES ,
4.1 Radiation Protection Superintendent 4.1.1 The Radiation Protection Superintendent is . responsible for the overall effective management of the plant Process Control Program. The Radiation Protection Superintendent ensures.that changes are initiated to the Process Control Program procedures when necessary and that appropriate Health Physics support is provided.
3 e -- e .-n-
~ - , a + , a
Administrative Procedure RW-001-210 Process Control Program Revision 6 4.2 .Radwaste Foreman 4.2.1 The Radwaste Foreman who reports to the Radiation Protection Superintendent holds key responsibilities for implementation of the Process Control Program such as:
4.2.1.1 The preparation, review and approval of the Process Control Program procedures pertaining to the processing and packaging, of radioactive materials; 4.2.1.2 Data collection, trend analysis, long-term planning, and problem solving for the plant Process Control Program; 4.2.1.3 Managing radwaste stabi.1zation, dewatering i and packaging; '
l 4.2.1.4 Preparing procedures for stabilization, dewatering and packaging; 4.2.1.5 Interfacing with other groups as necessary to analyze and resolve problems relating to the Process Control program such as the ,
design of Radwaste Systems and Equipment; l
l 4.2.1.6 Preparing periodic reports summarizing the Process Control Program; 4.2.1.7 Procurement of materials and supplies i- required for implementation and maintenance l of the Process Control Program; 4
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Administrative Procedure RW-001-210 Process Control Program Revision 6 l i
4.2.1.8 That personnel receive appropriate training and are qualified for their respective duties; 4.2.1.9 Adequate staffing and sufficient-resources for efficient and economic operation of the Process Control Program.
4.3 Operations Superintendent 4.3.1 The Operations Superintendent is respor.sible for the effective operations of permanent plant radwaste systems and will coordinate radwaste activities with the radwaste department.
4.4 Chemistry Superintendent 4.4.1 The Chemistry Superintendent is responsible for interfacing with the Radwaste Foreman on items or problems relating to radwaste' processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.
4.5 Quality Assurance 4.5.1 Quality Assurance is responsible for:
4.5.1.1 Assessing the implementation and effectiveness of the quality assurance aspects of the Process Control Program through regular audits and selective monitoring of activities.
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Administrative Procedure RW-001-210 .
Process Control Program Revision 6 5.0 PROCEDURE 5.1 . Program Descriptien 5.1.1 Solidification System
Description:
Waterford 3 utilizes i vendor supplied portable solidification equipment for radioactive waste solidification. All vendor ;
solidification process procedures will be approved as plant procedures by Plant Operating Review Sub-Committee.
Reference 2.1.1 through 2.1.5 are Waterford 3 documents which either implement or describe activities which provide reasonable assurance that wastes are solidified or dewatered in accordance with all applicable regulations and criteria.
5.1.2 Sources of Waterford 3 Stabilization / Solidification Feeds:
The Cement solidification will be used to stabilize resins, if needed. During resin stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of resin. Solidification i using Aquaset/Petroset media will be used to process resins, oil, and water / acid. This process will not be connected to any plant waste systems and will be processed on a batch basis.
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Administrative Procedure RW-001-210 Process Control Program Revision 6 5.2 Solidification Process Parameters:
5.2.1 Solidification formulas and solidification process parameters are incorporated into the applicable vendor -
process control program. No exceptions or deviations from vendor supplied procedures or topical reports are anticipated for stabilized waste. The formulas are used to calculate the ratio of waste, cement, water and other reagents required to achieve an acceptable solidified product. Compatibility requirements of the waste stream with respect to the solidification media are described in the vendor process controls program.
Waste stream parameters are adjusted as necessary to meet these requirements.
5.2.2 Test solidifications are performed on waste stream samples to verify vendor calculated solidification formul as.
NOTE Vendor PCP along with applicable procedures will be approved as plant procedures prior to use.
5.2.3 Radioactive wastes shall be solidified or dewatered in accordance with the process control program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
Administrative Procedure RW-001-210 .
Process Control Program Revision 6 i 4 1 5.2.4 With solidification or dewatering not meeting disposal j site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the process control program, the procedures, and/or the solid waste system as necessary to prevent recurrence.
5.2.5 With solidification or dewatering not performed.in I accordance with the process control program, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and perform appropriate corrective action if required.
5.2.6 Solidification of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins), shall be verified in accordance with the vendor's process control program. i 5.2.7 If the initial test specimen from a batch of waste fails to verify solidification, the process control program shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program may be modified if practical to assure solidification of '
subsequent batches of waste.
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, Administrative Procedure RW-001-210 Process Control Program Revision 6 5.2.8 If any test specimen fails to verify solidification, the solidification of the batch nnder test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the vendors process control program, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the process control program.
5.3 Administrative Controls 5.3.1 Administrative controls utilized to insure compliance with applicable state and federal regulations and burial site criteria are detailed in the radioactive waste solidification surveillance procedure (s). These implementing document (s) for radioactive waste solidification and dewatering describes the requirements which must be met prior to processing radioactive waste, as well as the condition of the .
solidified or dewatered waste. Test solidifications, full scale calculations and operation of the solidification equipment are performed by vendor personnel. Dewatering operations will be performed by vendor personnel or by qualified Plant staff. Plant staff provides Health Physics and Quality Assurance coverage, operates plant radioactive waste systems, collects waste stream samples and performs isotopic analyses. Copies of all referenced documents are available on site for use by personnel engaged in solidification activities. '
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' Administrative Procedure RW-001-210 5 Process Control Program Revision 6 5.3.2 Changes to this Process Control Program shall be described in the semi-annual Radioactive Effluent' Release Report for the period in which the change is made.
5.4 Waste Characterization and Classification 5.4.1 Waste Classification 5.4.1.1 Solidified wastes are classified in accordance with the requirements of 10CFR61.55, as implemented by reference 2.1.6 and plant waste classification and characterization procedure (s).
5.4.1.2 Annual analysis will be performed on the waste streams to determine the isotopic abundance of gamma emitting isotopes in the streams as described in Reference 2.1.8.
Scaling factors for the non-gamma emitting and transuranic constituents will be developed from this annual analysis using References 2.1.6 and 2.1.7. The activity of each radionuclide in the solidified waste will be determined by a core sample or a calculational method employing the percent >
abundance and scaling factors with a dose to curie conversion factor as described in Reference 2.1.6.
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, Administrative Procedure RW-001-210 i Process Control Program Revision 6 l 1
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l 5.4.2 Waste Characteristics ~l 5.4.2.1 Solidified wastes will meet the l characteristics of 10CFR61.56(a).
Stabilized wastes will meet the characteristics of 10CFR61.56(b). Waste containers will be labeled to identify the ;
waste class. j 5.4.2.2 The manifesting requirements of 10CFR20.311 are implemented and records are maintained in accordance with 10CFR71.91.
5.5 Quality Assurance '
5.5.1 Quality Assurance Program Manual (Special Scope) ,
Chapter 5.
6.0 ATTACHMENTS ,
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ATT A'llMENT 10.2
(. PAGES)-
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l CHANGES TO UNT-005-014, 4
0FFSITE DOSE CALCULATION MANUAL (0DCM)
January 1, 1993 To December 31, 1993 t
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UNT-005-014 REVISION 3 EFFECTIVE DATE W 3 RECORDS UNCONTROLLED COPY RELATED TESTING, DO NOT USE IN ANY SAFETY MAINTENANCE.OR OPERATIONAL ACTMTY. ' ,
SAF3:2Y-RELA:23J ADMINISTRATIVE PROCEDURE OFFSITE DOSE CALCULATION MANUAL UNT-001-002 Revision 13 Attachment 6.3 (1 of 2) 48
REVIEW AND APPROVAL SHEET REVIEW 0F: UNT- 005-014 - Offsite Dose . PORC 0 -
Calculation Manual (Rev. 3) .
PORC - S/C O The PORC or PORC S/C has reviewed tis item and determined that a Safety / ' was performed (if applicable)',1tilat 3 an tibbivie'w)~e@Ta'fiti ques notexist,andthatnuclearfsafdy"is7Aas'ndt'adverselycaffected. PORC RECOMMENDED FOR APPROVAL MEMBER MEMBER SIGNATURE YES N0 r t dent f [IDT Operations Superintendent
, I, AN
[ Radiation Protection Superintendent YA r Y, uality Assurance y
/
n n rn Manager Operations & Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member Meeting No. 93-100 Item No. VI-D Date: 12/21/93 This item is recommended for approval? E YES O NO This item requires SRC/NRC review prior to implementation? O YES O NO If yes, ensure documentation supporting review is attached. SIGNATURE RECOMMENDED FOR APPROVAL YES NO DATE PORC-5/C Chairman ,/ PORC Chairman (3 #fc:s4y[ N /A/Ju/L7 - Comments: M [] , Y%/// j i Approved by n//UNLok Date /2/ 23/D - Gdneral Man (ger Plant Operations UNT-001-004 Revision 14 23 Attachment 6.1 (1 of 1) , 1 1 a
Check Block: WATERFORD 3 SES T PORC PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST C PORC-S/C Procedure No.: ONI 04
Title:
OFRITE bar (AtcwanoAl meaAt_ Effective Date : I I W (if different fmm approvaldate) COMPLETE A. B and C: A. Change No.: 4 Permanent B. Revision: Deviation Expiration Date: VM 3 C. Deletion: [ Yes g No DESCRIPTION OF CHANGE, REVISION, OR DELETION: [tv//t/ M /or d M rd5e,rAdh n [evam.ar kWMh <4n d fxdiMS. ek k ov ) D w vs RStsv: $$t $c, AFAfA 4 fif/4b forthtl
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" TEMPORARY APPRoh RO): Date:
- TEMPORARY APFROVAL: Date:
*Referto paragraphs 3.2.18 and 5.3.2.10c for temporary approval requirements i
UNT-001-003 Revision 16 1 Attachment 6.4 (1 of 1) i l 42 i
1 Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 !
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TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1 Site Characteristics . 5.2 Specifications and Surveillance Requirements 5.3 Liquid Effluents 5.4 Gaseous Effluents 5.5 Total Dose ' 5.6 Instrumentation - 5.7 Liquid.and Gaseous Radwaste Processes 5.8 Radiological Environmental Monitoring Program Requirements 5.9 Technical Specification Cross-References 5.10 Routine Effluent Release Reports 5.11 Special Effluent Reports ' 5.12 Secondary Release Paths 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 j 6.4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble j Gases 6.5 Inhalation Pathway Doses Due to Radionuclides Other Than Noble , Gases, Rj i I i 1 l i j
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Administrative Procedure. UNT-005-014 Offsite Dose Calculation Manual- Revision 3
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6.6 Ground - Plane Deposition Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Rj 6.7 Cow's Milk Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Rj 6.8 Meat Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Ri 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 Than Noble Gases, Ri 6.11 Liquid Waste Management System Effluent Sources and Release Pathways and Points 6.12 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources and Exhaust Release Points 6.13 Radiological Environmental Monitoring Program ' 6.14 Sample Location Table 6.15 Sector and Zone Designators for Radiological Sampling and Monitoring Points 6.16 REMP Sampling Locations Within 2 Miles of Waterford 3 6.17 REMP Sampling Locations Within 10 Miles of Waterford 3 6.18 REMP Sampling Locations Within 50 Miles of Waterford 3 6.19 Specifications Cross-Reference Table 6.20 Technical Specification Cross-Reference Table 6.21 Specific Factors Used to Determine Aj and Rj Values for the Offsite Dose Calculation Manual LIST OF EFFECTIVE PAGES Title Revision 3 1-250 Revision 3 2
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-Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 1.0 PURPOSE 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; (2) the general characteristics of the Waterford 3 site; (3) the detailed Radiological Environmental Monitoring Program (REMP);-(4) the description of the Radiological Environmental 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 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 sampling of liquids; and (10) the methodology to be used to comply with 40CFR190 criteria.
1.2 The Offsite Dose Calculation Manual (ODCM) 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 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. 1.3 ' Actual step-by-step dose calculations will be performed by in- l plant procedures which are consistent with the methodology , presented in this document. l
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- Administrative Procedure ~ UNT-005-014' Offsite Dose Calculation Manual Revision 3 M
2.0 REFERENCES
2.1 Waterford 3 SES Technical Specifications, Chapter 16 of ' Waterford 3 FSAR. 2.1.1 Technical Specification 6.14.1 2.1.2 Technical Specification 6.14.2 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. 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1, April 1977. 2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to. Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, Revision 1, October, 1977. 2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978. 2.6 Code of Federal Regulations: Title 10, Parts 20, 40, 50 and 100; Title 40, Part 190. m 4 W w r 4'"
Administrative Procedure .UNT-005-014 ) Offsite Dose Calculation Manual Revision 3 2.7 USNRC Generic Letter 89-01, implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of tre Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. 2.8 UNT-006-010, Event Notification and Reporting 2.9 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. 2.10 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June,1974. 2.11 UNT-006-Oll, Condition Report 3.0 DEFINITIONS 3.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions. a 5
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 3.2 CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within 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 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other. indications and/or status , derived from independent instrument channels measuring the same parameter. 3.4 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal 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 and/or trip functions.
- c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY including alarm and/or trip function.
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-Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3 '
35 The FREQUENCY NOTATION specified for the performance of i Surveillance Requirements shall correspond to the following- I intervals. k NOTATION FRE0VENCY S At least once per 12 hours. ; D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. 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. N.A. Not applicable. 3.6 MEMBER (S) 0F THE PUBLIC shall include all persons who are'not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. 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. 3.7 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant , instrumentation, controls, electrical power, required for the system, subsystem, train, component, or device to. perform its function (s) are also capable of performing their related support function (s). . 7
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 3.0 DEFINITIONS (cont'd) 3.8 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature as specified.
REACTIVITY % OF RATED AVERAGE COOLANT OPERATIONAL MODE CONDITION. Keff THERMAL POWER
- TEMPERATURE
- 1. POWER OPERATION 2 0.99 > 5% 1350 F
- 2. STARTUP 2 0.99 5 5% 2 350 F
- 3. HOT STANDBY < 0.99 0 1350 F
- 4. HOT SHUTDOWN < 0.99 0 350 F> Tavg>200 F
- 5. COLD SHUTDOWN < 0.99 0 $ 200*F
- 6. REFUELING ** s 0.95 0 s 140 F
- Excluding decay heat.
** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
3.9 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. 3.10 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. 3.11 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. 8
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 1
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3.0 DEFINITIONS (cont'd) 3.12 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreation purposes. This definition is applicable to areas established for effluent release limits. See Attachment 6.1. 3.13 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous racioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the_ gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) (atmospheric cleanup systems i are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. 3.14 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 9
Administrative Procedure UNT-005-014 3 Offsite Dose Calculation Manual Revision'3 P 3.0 DEFINITIONS (cont'd) 3.15 A WASTE GAS HOLDUP SYSTEM 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. 3.16 A MAJOR CHANGE to a radioactive waste system shall be any alteration or modification to the system that causes waste characteristics (e.g. chem form, pH, etc.), waste form or waste activity in liquid gaseous or solid effluents to significantly deviate. l 1 l l I e 10 i
Adm'inistrative Procedure UNT-005-014 0ffsite Dose Calculation Manual Revision 3 l l
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4.0 RESPONSIBILITIES
- 4.1 General Manager, Plant Operations has lead responsibility for ,
.I ensuring implementation of the Radiological Effluent l
Specifications and Radiological Environmetal Monitoring Program - as required by Technical Specification 6.8.3 and as set forth in this procedure. 4.2 The Radiation Protection Superintendent is responsible for ensuring Radiological Effluent Specifications and the Radiological Effluent Monitoring Program are performed as required according to procedures and methodologies established by this document. He is also responsible for ensuring the Annual Effluent Release Report is performed and issued as required. 4.3 Manager, Security and General Support is responsible for ensuring the Radiological Environmental Monitoring Program is performed as required according to procedures and methodologies established by this document. He is also responsible for issuance and submittal of the Annual Environmental Report as required by this document. He is also responsible for the negotiation and maintenance of vendor contracts to supply Sample Analyses and Reports as required by the Radiological Environmental Monitoring Program. He is also responsible for ensuring the Land Use Census is performed as required. s 4 11
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 1 5.0 PROCEDURE ! I 5.1 SITE CHARACTERISTICS Waterford 3 SES is located on the west (right descending) bank of 4 the Mississippi River at River Mile 129.6 between Baton Rouge, - Louisiana, and New Orleans, Louisiana. The site is in the northwestern section of St. Charles Parish, Louisiana, near the ! towns of Killona and Taft. ; The geographic coordinates for the Waterford 3 reactor are Latitude 29 59' 42" North, and Longitude 90 28' 16" West. Based on the UTM (Universal Transverse Mercator) Zone 15, the UTM coordinates are Northing 3,320,743 meters and Easting 743,962 meters. The Mississippi River is the closest prominent natural feature. to : Waterford 3, while other important nature features include Lac des 1 Allemands, about 5.5 miles southwest of the site, and Lake Pontchartrain, about 7 miles northeast of the site. The land
. slopes gently from its high points near the Mississippi-(10-15~ft.
above mean sea level) to extensive wetlands located 1.5 to 2.5 . miles inland from the river. Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford 3 site are several large industrial facilities, including.
- Waterford 1 and 2 (0.4 miles northwest. of the site), Little Gypsy Steam Electric Station (0.8 miles northeast of the site, across the.
river from Waterford 3), Agrico, a fertilizer manufacturer (0.6 miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and Union Carbide, a chemical manufacturer (1.2 miles east-southeast). Louisiana' Power & Light Company (LP&L) owns and Entergy Operations, Inc. operates the above-mentioned steam electric stations. l 12
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.1 SITE CHARACTERISTICS (cont'd) 1 Attachment 6.1 provides a map of the UNRESTRICTED AREA and SITE BOUNDARY for radioactive effluents. LP&L will have full control of. > 4 all activities conducted within the exclusion area boundary of the : Waterford 3 site. All of the property within the designated exclusion area is owned by LP&L with the exception of the bottom lands below mean low water of the Mississippi River. LP&L owns, in title, all surface rights within the exclusion area ' boundary of the plant. There is presently no intention to allow exploration for subsurface minerals from points on the surface of the exclusion area. The Mississippi River, Louisiana Highway 18, the Missouri Pacific Railroad right-of-way, and the west (right descending) bank levee of - the Mississippi River constitute traversals of the site exclusion area as allowed by 10CFR100.3 (a). Refer to the Waterford 3 Emergency Plan Implementing Document for the arrangements which have been made to give LP&L authority and control over these traversals. (Note that Louisiana Highway 3127 does traverse the SITE BOUNDARY I but not the exclusion area. However, LP&L does have the authority to control this traversal in accordance with the Waterford 3. Emergency Plan Implementing Document.) In addition to Waterford 3, there are two fossil-fueled units, Waterford SES Units 1 and 2, which are owned by LP&L and which are within the site exclusion area. The plant staff for these two units consists of about 60 people. Since this includes workers assigned to shifts, it is a conservative estimate of the maximum number of fossil plant personnel that would be within the exclusion area at i any given time. Evacuation procedures for Waterford SES. Units 1 and 2 are described in the Waterford 3 Emergency Plant Implementing . Document. 13
Administrative Procedure UNT-005-014 I Offsite Dose Calculation Nanual Revision 3 5.1 SITE CHARACTERISTICS (cont'd) A portion of the land within the SITE BOUNDARY is utilized for agricultural activities. Farmers presently work the land but can be expected to actually be in the field less than 10 percent of the time. Fishing in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be expected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area. Texaco maintains a gas valve station east-southeast of the Waterford 3 SES island structure just within the radius of the exclusion area. This valve station is automated and requires only periodic monthly maintenance involving, typically, two persons. Evacuation procedures for these maintenance workers are. described in the Waterford 3 Emergency Plan Implementing Document. The Waterford property is shown in Figure 5.1-3 of the Waterford 3 Site-Technical Specifications (STS) and includes 3,561.3 acres. The plant area is about 48 acres and is defined as including the > fenced area immediately adjacent to Waterford 3. The site area is shown in Figure 5.1-3 of the STS along with principal station structures and nearby features. The site' includes only station structures and does not include any residential, recreational, or I other industrial structures. There is a visitor center and adjacent recreational area approximately 1.0 mile SSW of the plant. ll The SITE BOUNDARIES for establishing effluent release limits along
-l with radioactive effluent release points are given in Attachment 6.1. The nearest distances to the boundary line are shown in {
Attachment 6.2 of this procedure. The release point elevations for gaseous effluents are provided in Attachment 6.1. 14
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.1 SITE CHARACTERISTICS (cont'd) The restricted area, defined for the purpose of controlling access for tne purpose of protecting individuals against undue risks from radiation and radioactive materials, coincides with the current or future Security Protected Area fence. _; For the purpose of establishing effluent release limits in l i accordance with 10CFR20 and Appendix I to 10CFR50, the concept of the restricted area, as defined above, is not applicable. The effluent release limits are established in order to ensure that: (1) the concentrations of the radionuclides in gaseous effluents discharged from the plant stack and exhaust systems do not result ; in exceeding the limits at the site boundary, with limits set j forth in Table II, Column 1 of Appendix B to 10CFR20; (2) the concentration of radionuclides in liquid effluent at the unrestricted area boundary does not exceed the limits set forth .j in Table II, Column 2 of Appendix B to 10CFR20; and (3) the. cumulative liquid and gaseous radionuclide releases do not result in exposures to individuals within the UNRESTRICTED AREA or at the SITE BOUNDARY in excess of the limits set forth in Appendix I ; to 10CFR50. , 1980 population by annular sectors within 5 miles or Waterford 3 can be found in the Environmental Report. Population was estimated for 1977 and projected for 1980. The methodology for estimating and projecting population is described in detail in section 6.1.4.2 of the Environmental Report. The closest town to Waterford 3 is Killona, 0.9 miles west-northwest. Other towns near the plant include Norco 2.5 miles east; Hahnville, 3.7 miles east-southeast; and Laplace, 4.7 miles north. There are also smaller settlements and homes along both banks of the river, the nearest such place to Waterford 3 being Montz,1.0 mile - northeast. 15
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.1 Compliance with the SPECIFICATIONS contained in the succeeding sections is required during the OPERATIONAL MODES or other 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 to expiration of the specified time intervals, completion of the ACTION requirements is not required. 5.2.3 Surveillance Requirements shall be applicable during all OPERATIONAL MODES or other conditions specified for individual systems unless otherwise stated in'an individual Surveillance Requirement. 5.2.4 Each Surveillance Requirement shall be performed within the specified time interval with: 5.1.4.1 A maximum allowable extension not to exceed 25% of the surveillance interval.
?
16
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS Cont'd 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 System for Operation. Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment. 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-Oll and UNT-006-010 procedures. l l l 17 l l 1
Administrative Procedure UNT-005-014 ;
~ - 0ffsite Dose Calculation Manual Revision 3 [
~ 5.3 LIQUID EFFLUENTS 5.3.1 Concentration Soecification 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 /ml total activity. APPLICABILITY: At all times ACTION: With the concentration of radioactive material re? Ised in liquid effluents to UNRESTRICTED AREAS exceeding 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 RE0VIREMENTS
- a. Radioactive liquid wastes shall.be sampled and analyzed according to the sampling and analysis program of Table 5.3-1. l f
l 1 18
ea4 . *-a- -ca__ +-6 J am. .Aea ae .L 4 Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3
-5.3 LIQUID EFFLUENTS (cont'd)
- 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. i i 1
)
9 k 19 + _a,- _ ,. -
Administrative Procedure 'UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.3-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM 0F DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a i TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL) A. Batch Waste P P Release Each Batch Each Batch Principal Gamma 5x10~7 Tanks b,f,g,h,i Emittersc I-131 lx10-6
- 1. Boric Acid >
Condensate P M Dissolved and lx10-5 Entrained Gases
- 2. Waste One Batch /M (Gamma Emitters)
Condensate P M H-3 lx10-6 Each Batch Composited
- 3. Laundry Gross Alpha lx10-7 Waste P Q Sr-89, Sr-90 5x10-8
- 4. Turbine Each Batch 'Composited Building Inoustrial Waste Fe-55 lx10-6 Sumps *
- 5. Dry Cooling Tower Sumps
#1 and #2* t
- 6. Regenerative Waste '!
- 7. Filter Flush .
- 8. Waste
-*When release from this source is batch in r,ature.
20 w s ,-,e
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.3-1 (Continued) LOWER LIMIT MINIMUM 0F DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (gCi/mL) B. Continuous W W ' Release .f e Grab Sample Principal Gamma 5x10-7 Emittersc
- 1. Turbine I-131 lx10-6 Building Industrial Waste Sumps **h M M Dissolved and 1x10-5
- 2. Dry Cooling Grab Sample Entrained Gases Tower (Gamma Emitters) ,
Sump #1**i i W M -H-3 1x10-5
- 3. Dry Cooling Grab Sample Composited Tower Sump #2**i Gross-Alpha 1x10-7 W Q _
Sr-89, Sr-90 5x10-8
- 4. Circulating Grab Sample Composited i Water l Discharge- Fe-55 lx10-6 l Steam Gene- I rator Blow-down HXi
- 5. Auxiliary Component Cooling Water Pumpsi i
**When release from this source is continuous in nature.
- I l
21
-Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.3-1 (Continued)
LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY. (LLD)a - TYPE FREQUENCY FREQUENCY ANALYSIS (gCi/mL) B. Continuous W W Principal Gama Releasee .f Continuousk Composited Emittersc 5x10-7
- 6. Steam Generator I-131 lx10-6 ,
Blowdown Dischargejil M M Dissolved and lx10-5 Grab Sample Entrained Gases (Gamma Emitters) W M H-3 lx10-5 Continuousk Composited Gross Alpha lx10-7 W Q Sr-89, Sr-90 5x10-8 Continuousk Composited_ Fe-55 lx10-6 s e 4 O 4 22 1 i
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 i TABLE 5.3-1 (Continued) ' TABLE NOTATION , aThe LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a :, ample that will yield a net l count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical , separation: LLD = E-V 2. 22 x 10 Y e " * Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per l minute, E is the counting efficiency, as counts per disintegration, t V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fraction radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and i i At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. Typical values of E, V, Y, and At should be used in the calculation. 23
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.3-1 (Continuedl TABLE NOTATIONS It should be recognized that tne LLD is defined as an a criori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. b 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 by a method described in Section 5.3.6 to assure representative sampling. cThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and report 9d in the Annual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8. i d A composite sample is one in which the quantity of liquid sampled is. proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. eA continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. f Prior to analyses, all samples taken'for the composite shall be thoroughly mixed in order f7r the composite sample to be representative of the effluent release 24
Administrative' Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.3-1 (Continued) TABLE NOTATIONS 91f the contents of the filter flush tank or the regenerative waste 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 radwaste treatment system. l hTurbine Building Industrial Waste Sump (TBIWS) The TBIWS shall be required to be sampled and analyzed in accordance with this table if any of the following conditions exist: l l (1) Primary to secondary leakage is occurring; or, 1 (2) Activity is present in the secondary system as indicated by either I the SGB monitors or secondary sampling and analysis; or, i l (3) Activity was present in the TBIWS during the previous 4 weeks. I If none of the above situations exists, then the sampling and analysis of this stream need not be performed. i Sampling and analysis of the dry cooling tower sumps and the auxiliary component cooling water pump discharge will be required only when detectable activity exists in the CCW. j Sampling and analysis of the circulating water discharge-steam generator I blowdown heat exchanger discharge (CWD-SGB) will be required only when detectable activity exists in the secondary system, jSampling and analysis of the steam generator blowdown will be required only when the blowdown is directed to the circulating water system or Waterford . 3 waste pond. 25
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE.5.3-1 (Continued) TABLE NOTATLONS Steam generator blowdown to the Waterford 3 waste pond 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 pond will be terminated upon detection of sample activity greater than the LLD levels of Table 5.3-1. i k To be representative of the quantities and concentration of radioactive materials in liquid effluents, samples shall be. collected continuously in , proportion to the rate of flow of the effluent stream. I Steam generator blowdown discharge to the waste pond is not available unless radiation monitoring and automatic' isolation capabilities are added-to the waste pond discharge path. l 26 l
't
Administrative Procedure .UNT-005-014 Offsite Dose Calculation Manual Revision 3
~
5.3 LIQUID EFFLUENTS (cont'd) 5.3.2 Dose Specification 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: 3
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or' equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to.the Commission within 30 days, pursuant to Technical Specification 6.9.2, a l Special Report that identified the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include ,
(1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished-drinking water supplies with regard to the requirements
~
of 40 CFR Part 141. 27
i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) SURVEILLANCE REQUIREMENTS:
- 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 Section 5.3.7 at least once per 31 days.
D 28 j
Administrative Procedure UNT-005-014 ! Offsite Dose Calculation Manual Revision 3 I l 5.3 LIQUID EFFLUENTS (cont'd) ! l 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 0.06 mrem.to the total body or 0.2 mrem to any organ in a 31' day period. APPLICABILITY: At all times. I ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above j limits and any portion of the liquid radwaste treatment system not in operation, prepare and 1 submit to the Commission within 30 days pursuant-to Technical Specification 6'.9.2 a Special Re :vt 1 that includes the following information. I
- 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 i
- 3. Summary description of action (s) taken to ;
prevent a recurrence. - l l l 29
Administrative Procedure UNT-005-014 I Offsite Dose Calculation Manual Revision 3
)
5.3 LIQUID EFFLUENTS (cont'd) 'i I SURVEILLANCE REOUIREMENTS
- 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 I Specifications 5.3.1 and 5.3.2.
30 1 _____ _ _ _ _ _ _ _ _ - - _ - _ . - - - - _ - - . - . - - _ - - _ _ . - - - - - ---_-->_------------n---
Administrative Procedure' UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) 5.3.4 Liouid Effluent Dose Calculation 5.3.4.1 The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Section 5.3.2 using the following expression: fl ' Dtt = Dt, F, I A tt Cri (1) bl D= t D,t (2) t=1 Du - the cumulative dose commitment to the 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; ,
i At t- the length of the (th. 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
, yCi/ml;
\
'j 1
+ 31 i
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) 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- pCi (Attachment 6.3), and; F t
- the near field average dilution factor for Ci c 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, y' liquid radioactive waste flow disch arg e 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. 32
- , _ ~ , . .
q Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual. Revision 3 5.3 LIQUID EFFLUENTS (cont'd) 1 5.3.4.2 Equation (1) above for calculating the dose contributions required the use of a dose factor, Ait, f r each nuclide (i) 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: 4t = K o(D +a UrBF,) DCFn (3) where: F Uw - 7301/yr adult water consumption; 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); 4 33
. . . . . . ,. . -. ._- .. - _~
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual- Revision 3 5.3 'I LIQUID EFFLUENTS (cont'd) i Ait = Composite dose parameter for the total body or critical organ-(t) of an adult for I nuclide (1) for all appropriate. pathways (mrem-ml/hr-yci); i Ko
= Unit conversion factor; )
= 6 3 1.14e + 5 = 10 % 10 % + 8760 % .
Uf = 21 kg/yr, adult fish consumption; , BFj = Bioaccumulatio.n factor for nuclide (i) in fish (pci/kg per pCi/1) from Attachment 6.21 and; DCFit - Dose conversion factor for nuclide (1) and organ (t) for adults (mrem /pCi). Values are from Table E-11 of Regulatory Guide 1.109. NOTE For other liquid pathways the appropriate dose factors will be utilized. 1 I 34 l l
)
_]
- . .- ~ . . - . - _. . - .. _. Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) 5.3.5 Liauid Effluent Monitor Setnoint Calculation Methodoloav Specifications 5.3.1 and 5.6.1 require that the liquid effluent monitoring instrumentation alarm / trip setpoints be set so that the concentration of radioactive material released from the site is limited to 10CFR20, 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 2E-4 yCi/ml total activity). This section presents the method to be used for determining setpoints in accordance with Surveillance Requirements 5.3.1 and 5.6.1. 5.3.5.1 The calculated setpoints for the liquid effluent monitors satisfy the following equation: , (SF)(RF)(F + f)T C f c= '"i (4) TMPC(f) where; C,
- the undiluted effluent gamma concentration yC1/ml'for all radionuclides i). The value will be derived from radioanalysis of liquid effluent to be released. This value 1 will be supplied for each liquid release; .
35
Administrative Procedure UNT-005-014 Offsite' Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) c = the setpoint, in pCi/ml, of the liquid effluent monitor measuring the - radioactivity concentration in the effluent line prior to dilution and subsequent release. This setpoint represents a value which, if exceeded would result in concentrations exceeding the limits of 10CFR20, Appendix B, Table II. Column 2, to an UNRESTRICTED AREA; f = the liquid effluents flow as measured at the liquid effluent monitor location in gpm; F = the dilution water flow as determined via pump curves or other appropriate mes:ures that determine correct plant operating configuration in gpm; NOTE If F is large compared to f then F + f :: F. SF - Safety factor to ensure that the effluent limit is not exceeded. Actual value is set by procedure (in-the range 0.5 - 0.9); ) l 36
Admini trative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) RF = Release fraction allocated to this release (to be used only in situations of simultaneous or concurrent release); C' CJ TMPC = T +T Q MPC; ,% MPC, C the undiluted nongamma MPC 3 fraction for all P J nongama emitting radionuclides (j); C undiluted gamma MPC fraction for all gamma 3 MP i emitting radionuclides (ih MPCj - Maximum Permissible Concentration for the applicable nongamma-emitting isotope (j) from 10CFR20, Appendix B, Table II, Column 2; and-MPCj = Maximum Permissible Concentration for the applicable gamma-emitting isotope (i) from 10CFR20, Appendix B, Table II, Column 2. l 1 37
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 d 5.3 LIQUID EFFLUENTS (cont'd) 5.3.5.2 The values of C4 and Gj will be measured for each release as appropriate and the parameters for f and F will be supplied based on current plant operating configurations. The setpoint will be ' calculated in terms of pC1/ml and the liquid effluent monitor will be adjusted as necessary to ensure that liquid releases are secured prior to exceeding limits specified in 10CFR20, Appendix B, Table -11, Column 2 to an UNRESTRICTED AREA. i 6 5 4 38
,,,-n -, e-n- 4
Administrative Procedure ~ UNT-005-014 Offsite Dose Calculation Manual Revision 3 j l
~
5.3 LIQUID EFFLUENTS (cont'd) , i j i 5.3.6 Representative liauid Samplina l Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling. Large volumes of liquid waste should 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. Recirculation was initiated through the normal path.
- d. Periodic samples were taken until equilibrium was reached.
- e. The time observed to completely mix the tank is ,
used as a minimum recirculation time prior to effluent sampling. Records of the. test will be ; maintained. 39 l
.l 1
Administrative Procedure .UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd) 5.3.7 Dose Pro.iection for Liouid Effluents Specification 5.3.3 requires that appropriate j subsystems of the liquid radwaste treatment system be-used to reduce releases of' radioactivity when the projected doses due to the liquid effluent from each l reactor unit to UNRESTRICTED AREAS-would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. 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 Waste Management 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.) l 40 1
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
~
5.3 LIQUID EFFLUENTS (cont'd) 5.3.8 Liauid Effluent Bases
- a. CONCENTRATION (Section 5.3.1)
F
-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 Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)
Publication 2. 1 e j 41
-i j
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3- , t 5.3 LIQUID EFFLUENTS (cont'd) ; 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 radioactivity is detected in these tanks, the contents from these tanks must be discharged to the liquid radwaste system where the contents may then be monitored upon discharge. 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 (revised annually), Currie, L. A., " Limits for- Qualitative Detection and Quantitative Determination - Application to , Radiochemistry," Anal . Chem. 40, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Handford Company Report ARH-SA-215 (June. l 1975). a i L m 42
'I
Administrative Procedure UNT-005-014 Offsite -Dose Calculation Manual Revision 3
~
5.3 -LIQUID EFFLUENTS (cont'd)
- b. DOSE (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 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in 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. i i l 43 I l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.3 LIQUID EFFLUENTS (cont'd)
- b. DOSE (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 based on models and data, such that the actual I l exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be i substantially underestir.ated. The equations j specified for calculating the doses due to the i actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, l
" Calculation of Annual Doses to Man from Routine l Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of i Implementing Appendix 1," April 1977.
44
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 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 i 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 l assurance that the releases of radioactive materials in liquid effluents will be kept "as low l
- as is reasonably achievable." This specification implements the requirements of 10CFR Part 50.36a, i General Design Criterion 60 of Appendix A 10 CFR Part 50 and the design objective give'n in Section 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.
4 6 45
e Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS EFFLUENTS 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 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times ACTION:
- With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report.
4 46
Administrative' Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS EFFLUENTS (cont'd) 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.
r
- 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.
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47 j i 1
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.4-1 ' RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM , MINIMUM TYPE OF LOWER LIMIT OF SAMPLING ANALYSIS ACTIVITY ANALYSIS DETECTION (LLD)a GASEOUS RELEASE TYPE FREQUENCY FREQUEMNCY ( Ci/ml) , P P A. Waste Gas Holdup Each Tank Each Tank Principal Gamma Emittersb 1x10-4 Tanks Grab Sample < P P B. Containment PURGE Each PURGEc Each PURGEC Principal Gamma Emittersb lx10-4 4 (Plant Stack) Grab Sample M H-3 3 lx10-6 C.1 Plant Stack MC* del Principal Noble Gas Gamma lx10-4 Grab' Sample M- Emittersb l H-3 lx10-6 C.2 Fuel Handling Me,J Principal Noble Gas Gamma- , Building Grab Sample M Emittersb lx10-4 i Ventilation H-3 lx10-6 ! (Normal) Exhaust 1. 48 l I l L- - -_ _ - _ - _ - _ - _ _ _ - _-_ _ _ _ __._-_.______
Administrative Procedure UNT-005-014 . Offsite Dose Calculation Manual Revision 3 TABLE 5.4-1
- RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF SAMPLING ANALYSIS ACTIVITY ANALYSIS DETECTION (LLD)a GASEOUS RELEASE TYPE FREQUENCY FREQUEMNCY (pCi/ml)
D.1 All Release Types as W9 I-131 lx10-12 listed in B., C.1, and Continuousf ,h,j Charcoal C.2 above Sample I-133 lx10-10 D.2 Main Condenser W9 Principal Noble Gas Evacuation and Turbine Continuous f ,h,j Particulate Gamma Emittersb lx10-Il Gland Sealing System Sample M Gross Alpha Continuousf ,h,j Composite Ix10-Il Particulate ' Sample Q Sr-89, Sr-90 Continuous ,h,j f Composite lx10-Il i Particulate Sample Noble Gas Noble Gases Continuousf ,h,j Monitor Gross Beta or Gamma lx10-6 49
, , . - .- . - - . , -- .'e . - i+ - -- % . e. . , m 4 , .m .- -, .,wr-
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4-1 (Continued) TABLE NOTATION aThe LLO is defined, for purpose 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 . For a particular measurement system, which may include radiochemical separation: LLD = " ' EV 2. 22 x 10 6 Y e-* Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, , V is the sample size in units of mass or volume, - 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, q A is the radioactive decay constant for the particular radionuclide, j and i I 50
-)
-Administrative' Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 M
5.4-1 (Continuedl TABLE NOTATION At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a priori (befare the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. 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-s9, I-131, 1-133, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.8. cSampling shall also be performed within 24 hours following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. Analysis for principle gamma emitters as defined in (b) above shall be completed within 48 hours of sampling. d Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. eTritium grab samples shall be taken at least once per 7 days from .the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. . 51
1 Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4-1 (Continued) TABLE NOTATIONS f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Section 5.4.1, 5.4.2, and 5.4.3. , 9 Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 ' concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. h If no primary to secondary leakage exists, then only the gross beta or gamma noble gases analysis need be performed for the main condenser evacuation and turbine gland sealing system. If a primary to secondary leak exists and the release from the main condenser encuation and turbine gland sealing system has not been released via the plant stack, th= the sampling and analysis must be performed. i Note (c) above is not applicable for the plant stack unless the noble gas
. monitor shows that effluent activity has increased by a factor of 3.
dFuel Handling Building sampling is required whenever irradiated fuel is in i the storage pool. 52
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
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5.4 GASE0US 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 BOUNDARY (see Attachment 6.1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
- b. During any calendar year: Less than or equal to
( 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. I 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 1 Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the reiaases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. l l 53 l 1
.. .)
.]
Administrative Procedure UNT-005-014 : Offsite Dose Calculation Manual' Revision 3 k 5.4 GASE0US EFFLUENTS (cont'd) SURVEILLANCE RE0VIREMENTS: 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. 6 9 4 l l l
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54
1w, d - me- A-mJ w Administrative Procedure UNT-005-014 4 Offsite Dose Calculation Manual Revision 3 a 5.4.3 Dose - Iodine-131. Iodine-133. Tritium, and Radionuclides in Particulate Form-Specification l The' dose to MEMBER OF THE PUBLIC from~ iodine-131, iodine-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 B0UNDARY (see Attachment 6.1) shall be limited to the following:
- a. During any calendar quarter: Less~than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than ~or equal to 15 mrems to any organ.
r APPLICABILITY: At all times t b e m 55 i
Administrative Procedure. UNT-005-014 Offsite Dose Calculation Manual Revision 3
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5.4 GASEOUS EFFLUENTS (cont'd) AC110N: 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 effluents exceeding any of the above limits, prepare and 1 submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that ' identifies the cause(s) for exceeding the limit and ' defines the corrective actions that have been taken to s reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in. compliance with the above limits. SURVEILLANCE RE0VIREMENTS: : 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-livee greater than 8 days shall be i determined in accordance with the methodology and parameters in Section 5.4.7 at least once per 31 days.
-1 l
l i I i I
)
56 ! 1
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Administrative Procedure- UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4- GASEOUS EFFLUENTS (cont'd) 5.4.4 Gaseous Radwaste Treatment Soecification The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE I 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 BOUNDARY (see Attachment 6.1) would exceed either:
- a. 0.2 mrad to air from gamma radiatlon, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. ,
APPLICABILITY: At all times. r 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 that- - includes the following information:
- a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 57
Administrative Procedure- UNT-005-014 1 Offsite Dose Calculation Manual Revision.3
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5.4 GASEOUS EFFLUENTS.(cont'd) l
- c. Summary description of action (s) taken to prevent a recurrence. I SURVEILLANCE RE0VIREMENTS:
I
- a. Doses due to gaseous releases to areas at and beyond' the SITE B0UNDARY 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.
l l 58
a L Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
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5.4 GASE0US EFFLUENTS (cont'd) 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 BOUNDARY shall be limited to the following values and expressions: Release rate limit' for noble gases: K' (%), f Kg Q,, s 500 '",'" total body- (5)
;- 1 t
F K'(%), (Lf + 1,1Nf )Q,y 5 3000 7 skin (6) Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days: (%), f Pnq v s 1500 "; any organ (7) 11 59
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
]
l 5.4 GASEOUS EFFLUENTS (cont'd)
]
l Where: K' = a constant of unit conversion, IE6 pCi/ pCi; Kj = 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 pCi/m3 (Attachment 6.4). The constant 1.1 converts air dose to skin dose; I d 60
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 ) l 5.4 GASE0US EFFLUENTS (cont'd) 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 pCi/m3 (Same as Rj values for the child receptor listed in Attachment 6.5). The dose factor is based on the most restrictive age group (child) and most restrictive organ (thyroid) at the SITE B0UNDARY; Pit - (child breathing rate of 3700 m3/yr)(DFAj) (K') where DFAj is the inhalation dose factor for each radionuclide from Table E-9, Reference 2.4;
= summation for all identified radionuclides; f
i= 1 O
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3-
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5.4 GASE0US EFFLUENTS (cont'd) Qjy - the average release rate of radionuclides I (i) (either noble gas or Iodine-131, Iodine-133, tritium, and radionuclides in ' cne carticulate 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 yCi/sec; and (X/Q)y = 1.lE-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). The actual X/Q for the time of release may be determined and used under certain circumstances. NOTE All radiciodines are assumed to be released in elemental form. 62
'Administrafive Procedure UNT-005-014- ._
- Offsite Dose Calculation Manual Revision 3 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 BOUNDARY will be determined by the following expressions:
- a. During any calendar quarter, for gamma radiation:
D7 = (1.14e + 2)(%),f #;f At j Qfj, (8) i=1 j=l and for beta radiation: Dp = (1.14e + 2)(%),f N,f Atj Q,y, (9)
!=1 j=1
- b. During any calendar year, for gamma radiation:
D7 = (1.14e + 2)(%),f N,f Atj Qfj, (10) I=1 J=1 and for beta radiation: D, = (1.14 e + 2)(%), f N, f Atj ' Qfjy (11) i=1 J=1 l 63 l I
Administrative Procedure. UNT-005-014-Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS EFFLUENTS (cont'd) Where: Dy - the total gamma (y) air dose from gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad yearly; ; Dg - the total beta (B) air dose from gaseous effluents for the total time period and not to exceed 10 mrad quarterly and 20 mrad yearly; Qjjy - the average release rate of radionuclides (1) in gaseous effluent from all vent releases (v) in pCi/sec during the time period Atj; (}6), - 1.1E-5 sec/m3 in the ESE sector at 0.6 mile for all vent releases (v). The actual X/Q for the time of release' may be determined and used under certain circumstances; 64
. . .= --
-I
' Administrative Procedure UNT-005-014' l Offsite Dose Calculation Manual Revision 3
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5.4 GASE0US EFFLUENTS (cont'd) - Atj = the length of the jth time period over which Qjjy are accumulated for all gaseous releases in hours; and Mi and Nj = the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (i) in mrad /yr per.pCi/m3 (Attachment 6.4). 1.14E2 - a constant of units conversion
= (1 yr/8760 hr) (106 pCi/pci) i e
W 65-1
l Administrative Procedure- UNT-005-014 - Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.7 Calculational Methodology for Doses Due to Radiciodines, Tritium, and Radioactive Materials in Particulate Form This section presents the calculational methods'used for calculating doses due to iodine-131, -iodine-133, tritium, and radionuclides in particulate form in accordance with Surveillance Requirement. 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 B0UNDARY will be determined by the following expressions: During any calendar quarter: D,t, = 1.14 e - 4 At Ryt, #, Qj v (12) i=1 During any calendar year: D,t, = 1.14 e - 4 Atf R,t, #v Q,y (13) lal 4 66
- i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
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5.4 GASEOUS EFFLUENTS (cont'd) Where: 1.14E a constant of units conversion
= lyr/8760 hr; Dita =
the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in [ gaseous effluents; not to exceed 7.5 mrem quarterly or 15 mrem yearly; , Wy = the dispersion parameter for estimating i the dose to an individual at the controlling location for long term vent releases (v); h; = (y6), for the inhalation pathway from vent 3 releases (v) in sec/m3, from historical data, at the location of the critical receptor (Attachment 6.2); i h; = (y6), for the food and ground plane pathways . from vent releases (v) in m2, from historical data at the location of the 1 critical receptor (Attachment 6.2), l with the exception of tritium, which , shall use h( = (yf),; 67
Administrative Procedure UNT-005-014
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Offsite Dose Calculation Manual Revision 3 i 5.4 GASEOUS EFFLUENTS (cont'd) Rita - the dose factor from each identified radionuclide (1), for each applicable 3 7 organ (t), and age group (a), in mrem /yr per uCi/m3 for the inhalation pathway { (Attachment 6.5) and in mrem /yr per uCi/m2-sec for the food and ground plane pathways (Attachments 6.6, 6.7, 6.8, 6.9, 4 and 6.10). For sectors with real pathways within 5 miles of the plant, the values of Ri are used based on these real l 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 Reference 2.5, pages 31-36.); Qiy - the average release rate of radionuclides (1) in gaseous effluent from all vent releases (v) in pCi/sec; and At - the time required for the release in hours for all releases per quarter-or per year. 68
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 i
5.4 GASE0US EFFLUENTS (cont'd) : t 5.4.8 Gaseous Effluent Monitor Setpoint Calculational Methodoloav 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 are not exceeded. 5.4.8.2 The calculated high alarm / flow termination setpoint is the maximum value for that particular release. For conservatism, an administrative safety factor (SF) of usually 10% will be utilized in the setpoint , calculation. To allow for simultaneous releases from common or different release points a Release Fraction (RF) may be used to allocate percentages of the' total allowable release. 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: , o 69
i Administrative Procedure UNT-005-014 ,
' Offsite Dose Calculation Manual Revision 3 1
1 5.4 GASE0US EFFLUENTS (cont'd)
- a. Total body (Qtb) ;
Where: J (500 E23XRFXSF) Qu>= n (14) ' __ EK0 (}6),(1.0e + 6$)'"l, i w 30, 1
-summation of all nuclides considered; 1.)
Qtb = maximum release rate allowed to give a ' limiting total body dose rate of 500 mrem /yr in pCi/sec; Kj = 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); 4 70
Administrative Procedure UNT-005-014' Offsite Dose Calculation Manual Revision 3-5.4 GASE0US EFFLUENTS (cont'd) Qjy = average release rate of isotope (i) from the release point (v) in pCi/sec; [ RF = release fraction allotted to release point in consideration; (}6),= 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; and SF = administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.). Usually, the SF takes on a value of 0.9. . I e m 71 \
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS EFFLUENTS (cont'd)
- b. For Skin (Q skin):
(3000 E !)(RF)(SF) Osun = ", (15) E(L i+1.1M i)0iy (T[),(1.0e + 6%) W n IQ,i w where all terms are as defined as above except: Oskin = maximum release rate allowed to give a limiting skin dose of 3000 mrem /yr in pCi/sec; Lj = skin dose factor.due to beta emissions for each identified radionuclide (i) 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 (i) in units of mrad /yr per pCi/m3 (Attachment 6.4). =
72
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. 0ffsite-Dose Calculation Manual Revision 3
. 1 5.4 GASE0US EFFLUENTS (cont'd) 'i 5.4.8.4 The monitor setpoint is' calculated is the following manner: l
.f
-l SN = (16)
Fw l 1 Where- t SN = maximum monitor setpoint in pCi/cm; i Fm ax = maximum effluent flow rate (cm3/sec); and. Q = Minimum value of Qtb or Qskin. 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 body dose becomes more limiting than skin 1 and the release limit is: (500 '"'"")(RF)(SF) (17) 0" (%),(1. 0e + 6 %)(K u -88) ; l o 73 1
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.4 GASE0US EFFLUENTS (cont'd) where: QKr-88 = the maximum release rate, based on Kr-88, allowed to give a limiting total body dose rate of 500 mrem /yr in pci/sec; and ; i KKr the total body dose factor due- to Kr-88 in units of mrem /yr per pCi/m3 : (Attachment 6.4). ; All other terms are as previously defined. The monitor setpoint can be calculated as: '
"- 8" SN = (18)
Fw and all terms are previously defined P e 74
Administrative. Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 c 5.4 ' GASEOUS EFFLUENTS (cont'd) l 5.4.9 Dose Pro.iection 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 , 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. for performing this dose projection. At least once every 31 days the gamma air dose,- 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 these projected doses exceed any of the values listed above and the Gaseous Waste Management. , System has not been operating, it shall be - operated to reduce radioactivity-levels prior to release. (This is performed in accordance with the Surveillance Requirements of Specification-5.4.4.) i
-g a
F e 75 f a
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
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5.4 GASE0US EFFLUENTS (cont'd) 5.4.10 Gaseous Effluent Bases l 1
- a. DOSE RATE (Section 5.4.1) I This specification is provided to-ensure that the dose at any time at and beyond the SITE BOUNDARY from !
gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column -1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in a UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, 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 BOUNDARY. Examples of calculations-for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall-be given in the ODCM. 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. 76
i Administrative Procedure UNT-005-014- l 1 Offsite Dose Calculation Manual Revision 3 i 5.4 GASEOUS EFFLUENTS (cont'd) ! l 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 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K.,
" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
- 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 . guides set forth in Section II.B of Appendix I. i e 9 77
Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3 5.4 GASEOUS 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 lthe 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, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating , Compliance with 10 CFR Part 50, Appendix I," Revision 1, October.1977 and Regulatory Guide-1.111, " Methods for. Estimating Atmospheric - Transport and Dispersion of Gaseous Effluents in - ' Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. 78 )
' Administrative Procedure- UNT-005-014 Offsite Dose Calculation Manual Revision 3
'5.4 GASE0US EFFLUENTS (cont'd)
Sections 5.4.2 and 5.4.3 equations provided for ' determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. Grab sampling of effluents from the main condenser ; evacuation and turbine gland sealing system is not required when this source has been continuously discharging to the plant stack over the past 30 days. If no primary to secondary leakage in the steam 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 present in the release. If a primary to secondary leak exists, then the release from the main condenser evacuation and turbine gland sealing 3 systems will. be sampled and analyzed in accordance with Table 5.4-1. t 79-av - ' - - - -- ~ A ,e
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 . .t 5.4 GASEOUS EFFLUENTS (cont'd)
- c. 10 DINE-131. 10 DINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICUl. ATE FORM (Section 5.4.3)
This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of ( 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.
'i 4
e 80
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 - 5.4 GASEOUS EFFLUENTS (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,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"
Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE B0UNDARY. 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 and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 9 I 81 1 4
Administrative Procedure UNT-005-014 Offsite. Dose Calculation Manual Revision 3 i
~
5.4 GASEOUS EFFLUENTS (cont'd)
- d. GASEOUS RADWASTE TREATMENT (Section 5.4.4)
The OPERABILITY of-the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. 'The discharge from the main condenser evacuation and turbine gland sealing system shall be required to be directed to the plant stack when the release rate of I-131 from this source is 1 2 x 10-4 pCi/s. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This 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 10 CFR Part 50. The , specified limits governing the use of appropriate t 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. 4 l 82 .l
Administrative Procedure -UNT-005-014 Offsite Dose Calculation Manual Revision 3 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 and to radiation from uranium fuel cycle sources shall l be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. APPLICABILITY: At all times. -) i 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 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding _the above i limits and includes the schedule for achieving conformance with the above limits. m 83
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 :
~
5.5 TOTAL DOSE (cont'd) This Special Report, 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 i the release (s) covered by this report. it shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report l is considered a tinely request, and a variance is { granted until staf'. action on the request is complete. l I SURVEILLANCE RE0VIREMENTS: l
- a. Cumulative dose contributions from liquid and 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 the ODCM. 9 84
. Administrative Procedure UNT-005-014
- Offsite Dose Calculation Manual Revision 3 9
w 5.5 TOTAL DOSE (cont'd)
- b. Cumulative dose contributions from direct radiation from the. reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and . parameters in the ODCM.
This requirements is applicable.only under condition set forth in Specification 5.5.1. 4 i t 6 l i 1 t l l 85
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 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 mrem to the total body or any organ (except the thyroid, which shall- be' limited to less than or equal to 75 mrem) 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 mrom to the total body (liquid releases). (2) 10 mrem to any organ (liquid releases). (3) 15 mrem to the thyroid or any organ from radiciodines and particulates~(gaseous releases). 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. e 86
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 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 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 i 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 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. 87
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 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 FR 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 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives if Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a , MEMBER OF THE PUBLIC to within 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 1HE 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. 88
--. r .. . _ _ _ _ . . . . - . . . _ - ..- . - . - Administrative Procedure- UNT-005-014 q 0ffsite Dose Calculation Manual Revision 3 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.- 4 4 89 m e e o r+ - g
. . ~. . -. . -- . _ . - . .- . .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.6 INSTRUM'.FTATION 5.6.1 Badioactive Liauid Effluent Monitorina Instrumentation Specification The radioactive liquid effluent monitoring instrumentation channels shown in Table 5.6-1 shall be OPERABLE with.their alarm / trip setpoints set to ensure 4 that the limits of Specification 5.3.1 are not exceeded. 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 instrumentation channel alarm / trip setpoint less 1 conservative than required by the above Specification, immediately suspend the release of.
radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable. W 90 i
Administrative Procedure UMT-005-014-Offsite Dose Calculation Manual Revision 3 5.6 INSTRUMENTATION-(Cont'd)
- 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. status within 30 days 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 i i SURVEILLANCE REQUIREMENT ! Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown. in Table 5.6-2. 4 I 4 4 91
Administrative Procedure
, UNT-005-014 .
Offsite Dose Calculation Manual Revision 3 - t TABLE 5.6-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Boric Acid Condensate Discharge 1 28
- b. Waste, Waste Condensate and Laundry Discharge 1 28
- c. Dry Cooling Tower Sumps 1/ sump 29
- d. Turbine Building Industrial Waste Sump 1 29
- e. Circulating Water Discharge (Blowdown Heat Exchanger and Auxiliary Component Cooling Water Pumps) # 1 29
- 2. CONTINUOUS COMPOSITE SAMPLERS
- a. Steam Generator Blowdown Effluent Line 1 29
- 3. FLOW RATE MEASUREMENT DEVICES I a. -Boric Acid Condensate Discharge. 1 30
- b. Waste, Waste Condensate and Laundry Discharge 1 30
- c. Turbine Building Industrial Waste Sump
- N.A. N.A.
- d. Dry Cooling . Tower Sumps
- N.A. N.A.
- e. Circulating Water Discharge * (Blowdown and Blowdown Heat Exchanger.and Auxiliary Component Cooling Water Pumps) N.A. N.A.
# Automatic termination of blowdown discharge only 92
- e
Administrative. Procedure ~ UNT-005-014 0ffsite Dose Calculation Manaul Revision 3' TABLE 5.6-1 (Continued) TABLE NOTATIONS
- Pump performance curves generated in place shall be used to estimate flow.
ACTION STATEMENTS ACTION 28 - 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 analysed 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 29 - 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 grab samples are collected and are analyzed within 24 hours of collection time for radioactivity at a lower limit of detection lof at least 10-7 microcurie /ml. The sample collection frequency .is:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or a
93
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manaul Revision 3 TABLE 5.6-1 (Continued) TABLE NOTATIONS
- b. At least once per 24 hours when the specific activity of.
the secondary coolant is less than or equal to 0.01-microcurie / gram DOSE EQUIVALENT I-131. ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via e this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at ' least once per 4 hours during actual releases. ' Pump performance curves generated in place may be used to estimate flow. i n e i l e 94 I
Administrative-Procedure UNT-005-014 Offsite Dose Calculation Manaul Revision 3 TABLE 5.6-2 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. RADI0 ACTIVITY MONITORS PROVIDING ALARMS AND AUTOMATIC TERMINATION OF RELEASE
- a. Boric Acid Condensate Discharge P P R(3) Q(1)
- b. Waste, Waste Condensate and Laundry Discharge P P R(3) Q(1).
- c. Dry Cooling Tower Sumps D M R(3) Q(5)
- d. Turbine Building Industrial Waste Sump D M R(3) Q(5)
- e. Circulating Water Discharge (Blowdown Heat Exchanger Auxiliary Component Cooling Water Pumps) # D M R(3) Q(5)
- 2. CONTINUOUS COMPOSITE SAMPLERS
- a. Steam Generator Blowdown Effluent Line D(6) N.A. R Q
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Boric Acid Condensate Discharge D(4) N.A. R Q
- b. Waste, Waste Condensate and laundry Discharge D(4) N.A. R Q
- c. Turbine Building Industrial Waste Sump N.A. N.A. N.A. N.A.
- d. Dry Cooling Tower Sumps N.A. N.A. N.A. N.A. ,
- e. Circulating Water Discharge (Blowdown and Blowdown Heat >
Exchangers and Auxiliary Component Cooling Water Pumps) N.A. N.A. N.A. N.A.
# Automatic termination of Blowdown discharge only ,
95
. ~ . . -..
Administrative Procedure UNT-005-014 ' Offsite Dose Calculation Manual Revision 3 I TABLE 5.6-2 (Continued) TABLE NOTATION I. The CHANNEL FUNCTIONAL TEST 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 shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. 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 shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 <
hours on days on which continuous, periodic, or batch releases are made. 5. The CHANNEL FUNCTIONAL TEST 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: I. Instrument indicates measured levels above the alarm set.
- 2. Circuit failure.
- 3. Instrument controls not set in operate mode.
6. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous releases are made to the Circulating Water System or Waterford 3 waste pond.
?
96 vw - w , ,w e
Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3 5.6 INSTRUMENTATION (cont'd) 5.6.2 Radioactive Gaseous Effluent Monitorina Instrumentation Specifications t The radioactive gaseous effluent monitoring instrumentation channels shown in Table 5.6.3 shall be OPERABLE with their alarm / trip setpoints set to ensure I q that the limits of Specification 5.4.1 are not exceeded. I The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 5.4.8. l l APPLICABILITY: As shown in Table 5.6-3 ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
I
. (
l
\
97 i
.I
Administrative Procedure UNT-005-014
-Offsite Dose Calculation Manual Revision 3 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 or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to j Technical Specification.6.9.I.8, why this '
inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are 1 continued. SURVEILLANCE RE0UIREMENTS: - Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL 3 FUNCTIONAL TEST operations at the frequencies shown in Table 5.6-4. B r 1 i P 98 i
. Administrative Procedure- UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.6-3 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Release 1 **
35
- b. Effluent System Flow Rate Measuring Device 1 ** 36 MAIN CONDENSER EVACUATION AND TURBINE
, GLAND SEALING SYSTEM
- a. Noble Gas Activity Monitor I **** 37
- b. Iodine Sampler # 1 **** 39
- c. Particulate Sampler # 1 **** 39
- d. Sampler Flow Rate Monitor 1 **** 36
'#If a primary to secondary leak. exists or if the noble gas monitors in the main condenser evacuation and turbine gland sealing' system or if the steam generator blowdown monitor indicates the presence of radioactivity in the secondary system, the flow from this release point shall be diverted immediately to the plant stack. These instruments are in ,
the plant stack and sampling for radiciodines and_particulates shall occur at the plant vent when this occurs. Effluent flow may be redirected to the normal exhaust path with activity in the secondary system provided that the requirements of specifications 5.4.1, 5.4.2, 5.4.3, 5.4.4, 5.6.1, 5.6.2 are satisfied. When any of.the_ limits in in specification 5.4.4 will be exceeded and effluent flow is via the normal exhaust path,: effluent flow should be diverted to the plant' stack for treatment. . 99
- _ _ _ _ _ w e. - .- . -#. .-
- r e m ~ w _ ___m ~
Admi,nistrative Procedure' UNT-005-014 ~ Of fsite Dose Calculation Manual ~ Revision 3 TABLE 5.6-3 (Continued) RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT. OPERABLE APPLICABILITY ACTION
. REACTOR AUXILIARY BUILDING -VENTILATION SYSTEM (PLANT STACK)
- a. Noble Gas Activity Monitor -
Providin9 Alarm and Automatic Termination of Release # 1
- 37
- b. Iodine Sampler 1
- 39
- c. Particulate Sampler 1
- 39
- d. Flow Rate Monitor 1
- 36
'e. Sampler Flow Rate Monitor 1
- 36 FUEL HANDLING BUILDING VENTILATION SYSTEM (NCRMAL)
- a. Noble' Gas Activity Monitor 1 *** 37
- b. Iodine Sampler 1 ***
39
- c. Particulate Sampler.- 1 ***
39 , d. Flow Rate Monitor 1- *** 36 e.. Sampler Flow Rate Monitor 1 *** 36
# Automatic termination of containment purge only.
l 100
Administrative UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.6-3 (Continued) TABLE NOTATIONS ,
*At all times.
**During gas waste decay tank discharge.
***With irradiated fuel in the storage pool.
****When the main condenser is under a vacuum.
ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best efforts are made to repair the instrument and that, prior to initiating the release:
- a. At least two independent saaples 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; u
9 101
Admiaistrative UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.6-3 (Continued) TABLE NOTATIONS ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERADLE 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 4 hours. For the waste gas holdup tank this action item is applicable only during periods of release. For the main condenser evacuation and turbine gland sealing systems, this action item applies only during release via the discharge silencer and only during turbine gland sealing operations and/or vacuum pump operation. ACTION 37 - With the number of r ranels OPERABLE less than required by ' the Minimum Channels OPERABLE requirement, effluent releases via this pathway pay continue provided best efforts are made to repair the instrument and that grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. However, containment purging of radioactive effluents must be immediately suspended during this condition for the plant stack only. ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected 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. 4 102 1
Administrative UNTi OO5-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.6-4 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS CHANNEL MODES IN WHICH l CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE IS INSTRUMENT CHECK . CHECK CALIBRATION TEST REQUIRED
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor -
i Providing Alarm and Automatic Te + Mation of Release P P R(3) Q(1) * '
- b. Effluent System Flow Rate
- Measuring Device P N.A. R Q *
- 2. MAIN CONDENSER EVACUATION AND TURBINE GLANDS SEALING SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2) *
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Sampler Flow Rate Monitor D N.A. R 'Q *-
103 _.____---__-_____m. -.m4 -m. m g.- . - y . s** .n g, -. g ~ m,. ,a
.g . , ,, . , y y
Administrative UNT-005-014 Offs'ite Do'se Calculation Manual Revision 3~ ' 1 TABLE 5.6-4 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
- 4. REACTOR AUXILIARY BUILDING '
' VENTILATION. SYSTEM (PLANT STACK) '
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release D M R(3)
- Q(6)
- b. Iodine Sampler. W N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. 'N.A. N.A. *
- d. Flow Rate Monitor D N.A. R
- Q <
- e. Sampler Flow Rate Monitor D N.A. R
- Q
, 5. FUEL HANDLING BUILDING VENTILATION SYSTEM (NORMAL)
- a. Noble Gas Activity Monitor D. M R(3) ***
Q(2)
- b. Iodine Sampler W N.A. N.A. N.A. '***
- c. Particulate Sampler W N.A. N.A. N.A. ***
i
- d. Flow Rate Monitor D N.A. R ***
Q
- e. Sampler Flow Rate Monitor D N.A. R ***
Q
# Automatic termination of containment purge only. i
-104
._. . - - . .- . - . . ~ _ . - . - . - - - . - . - _- . . . - . . - _ . . _ _ _ _ _ _ _ _ _
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 i TABLE 5.6-4 (Continued) ' 1SBLE NOTATIONS
*At all times.
***When irradiated fuel is in the spent fuel pool.
1. The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists: i 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
2. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
3. 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 CALIBRATION, sources that have been related to the initial calibration - shall be used. 6. The CHANNEL FUNCTION TEST 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 set.
- 2. Circuit failure.
- 3. Instrument controls not set in operate mode.
e 105 u --
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5.6 INSTRUMENTATION (Cont'd) i 5.6.3 Instrumentation Bases
- a. RADI0 ACTIVE LIOUID 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 - liquid effluents. The alarm / trip setpoints for ' these instruments shall be calculated 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 of General Design Criteria 60, 63, and 64 of .
Appendix A to 10 CFR Part 50. R I I O e 106
Administrative Procedure UNT-005-014 Offsite Dose. Calculation Manual Revision 3 5.6 INSTRUMENTATION (Cont'd)
- b. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (5.6.3)
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be 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
- 20. This instrumentation also include provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the' WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with tSe requirements of General Design Criteria 60, 63, anc 64 of Appendix A to 10 CFR Part 50.
t 4 e 107
' Administrative ~ Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.7 LIQUID AND GASEOUS RADWASTE PROCESSES The block flow diagrams of the radwaste systems are shown in Attachments 6.11 and 6.12. In order to obtain a more detailed description, see the appropriate sections of the FSAR. i Y
6 108
Admin'istrative Procedure UNT-005-014 Offsite Dase Calculation Manual Revision 3 l 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS 5.8.1 Radioloaical Environmental Proaram Specification The radiological environmental monitoring program shall 4 be conducted as specified in Table 5.8-1. APPLICABILITY: At all times. ACTI0B:
- a. With the radiological environmental monitoring program not being conducted as specified in Table 5.8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating 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.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 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 that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose * +.o a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications
}j 5.3.2, 5.4.2, and 5.4.3. . 109
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5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) i 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) + concentration (2) + .. 1 1.0 < reporting level (1) reporting level- (2)
*The methodology and parameters used to estimate the potential annual dose to A MEMBER OF THE PUBLIC'shall be indicated in this report. .
9 8 110
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'Offsite Dose Calculation Manual Revision.3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd)
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. l 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 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 Semiannual Radioactive Effluent Release Report and also include in the report revisions of Attachments 6.13, 6.14, 6.16, 6.17 and 6.18 reflecting the new location (s). e 111
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 i 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS { (Cont'd) l 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 l be analyzed pursuant to the requirements of Table 5.8-1 and the detection capabilities required by Table 5.8-3. J h 1 6 112 ,
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Offsite Dose Calculation Manual Revision 3 TABLE 5.8-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF c -
REPRESENTATIVE EXPOSURE PATHWeY SAMPLES AND SAMPLING AND
- TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONSa COLLECTION FRE0VENCY OF ANALYSIS
- 1. DIRECT RADIATIONb 31 routine monitoring stations Quarterly Gamma dose quarterly.
either with 2 or more dosimeters or with one instrument for .i 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 of stations, 1 in 10 of the meteorological sectors in the 6 - to 8-km range from the site; I the balar.ce of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control .i stations ' OThe 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 in the sampling program. 113 w %. c p e.+ - v- w * , . . - ..a . - -_ w - _ . _ _ _ _ _ _ _ -._m.___ . _ _ . ___ _ _ _ _ _ . _ -_.
' Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS a COLLECTION'FRE00ENCY OF ANALYSIS
- 2. AIRBORNE Radiciodine and Samples from 5 locations: Continuous sampler Radiciodine' Canister Particulates operation with sample I-131 analysis weekly.
3 samples from close to the collection weekly, or 3 SITE BOUNDARY locations, in more frequently if different sectors, of the required by dust Particulate Sampler: highest calculated annual average loading. Gross beta radioactivity-ground-level D/Q. analysis following filter change;- I sample from the vicinity of a Gamma isotopic analysise community having the highest of composite (by 1 calculated annual average location) _ quarterly. 3 ground-level D/Q. I sample from a control location, as for example 15-30 km distant and in the least prevalent < i wind direction.c 114 _ .. _ __ - , , - _ , , _ . _~ -
r: Administrative Procedure -UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-1 (Continued) RADIOLOGICAL ENVIRON'iENTAL MONITORING PROGRAM
- NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS a COLLECTION FRE0VENCY OF ANALYSIS'
- 3. WATERBORNE
- a. Surfacef I sample upstream Composite sample over Gamma isotopic analysisek 1 sample downstream 1-month periodgk. monthly. Composite for tritium analysis quarterly.
- b. Ground Samples from 1 or 2 sources Quarterly Gamma isotopice and tritium only if likely to be affected h. analysis quarterly.
- c. Drinking I sample of each of 1- to 3 of Composite sample I-131 analysis on each the nearest water supplies that over 2-week period 9 composite when.the dose could be affected by its when I-131 analysis calculated for the discharge. is performed, monthlyk consumption of the water composite otherwise is greater,than 1 mrem per year.1 Composite for gross beta and gamma isotopic analysese monthlyk . Composite for tritium analysis quarterly.
- d. Sediment 1 sample from downstream area Semiannually Gamma isotopic analysise from with existing or potential semiannually.
shoreline recreational value. 115
Administrative Procedure UNT-005-014 Offsite- Dose Calculation Manual Revision 3 TABLE 5.8-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS a COLLECTION FREQUENCY OF ANALYSIS
- 4. INGESTION
- a. Milk Samples from milking animals Semimonthly when Gamma isotopice and I-131' in 3 locations within 5 km animals are on analysis semimonthly when distance having the highest pasture; monthly at dose potential. If there are animals are on pasture; other times. monthly at other times.
none, then, I sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated,to be greater than 1 mrem per yr.1 1 sample from milking animals at a control location 15-30 km distant and in the least prevalent wind direction.c
- b. Fish and I sample of each commercially Sample in season, or Gamma isotopic analysise-Inverte- and recreational important semiannually if they brates on edible portions.
species in vicinity of plant are not seasonal discharge area. 4 1 samole of same species in areas not influenced.by plant discharge.
'116 4 . __-, _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _M
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TABLE 5.8-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM * , NUMBER OF , REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY , AND/0R SAMPLE SAMPLE LOCATIONS a COLLECTION FRE0VENCY OF ANALYSIS ~'
- c. Food i
1 sample of each principal class At time of harvestj Gamma isotopic analysise Products of food products from any area on edible portion. that is irrigated by water in which liquid plant wastes have discharged. Samples of 1 to 3 different kinds Monthly when Gamma isotopice and I-131 . of broad leaf vegetation grown available analysis. nearest each of two different offsite locations of highest predicted annual average ground-level D/Q if milk sampling is not ' performed. I sample of_each of the similar Monthly when Gamma isotopice and I-131 ' broad leaf vegetation grown available analysis. ' 1S-30 km distant in the least prevalent wind direction if milk sampling is not performed. 117 ' I
- ___ - - ________-_ - . . _ _ = . - . -- - - .- -_ .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-1 (Continued) TABLE NOTATLONS aspecific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Attachments 6.14, 6.16, 6.17 and 6.18. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other 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 Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table reflecting the new location (s), 118
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-1 (Continued 1 TABLE NOTATIONS bone or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the 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. cThe purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. d Airborne' particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gantma isotopic analysis shall be performed on the individual samples, eGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. 119 1
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 H TABLE 5.8-1 (Continued) TABLE NOTATIONS f 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. 9A 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 of sampling employed results in a specimen that is representative of the 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. hGroundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. , i The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in this document. JIf 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. k 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. 120 4 w -w- n -
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Administrative Procedure UNT-005-014 a Offsite Dose Calculation Manual Revision 3 l TABLE 5.8-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting. Levels WATER AIRBORNE PARTICULATE FISH MILK F000 PRODUCTS-3 ANALYSIS (pC1,-() OR GASES.(pCi/m3) (pci/kg, wet) (pCi/()~ (pCi/kg, wet) . ;H-3 20,000 ' I , Mn-54 1,000 30,000 l Fe-59 400 10,000 l Co-58 1,000 30,000 Co-60 300 10,000 , i Zn-65 300 20,000 - i
- Zr-Nb-95 400 1-131 2 0.9 3 100 t
Cs-134 30 10 1,000 60 1,000 Cs-137 50' 20 2,000 70 2,000 1 Ba-La-140 200 300 r 121- , , _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ . . . . - _ , .- ._ _. ._, . , - , _ _ _ .-. . ... .-.
Administrative Procedure
. UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limits of Detection (LLD)bc E AIRBORNE PARTICULATE FISH HILK FOOD PRODUCTS SEDIMENT ANALYSIS (pu/f) OR GASES'(pCi/m3) (pCi/kg, wet) (pci/() (pCi/kg, wet) (pci/kg, dry -
gross beta 4 0.01 H-3 '2000' Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 I Zr-Nb-95 15 I-131 I- d 0.07 1 60 I Cs-134 15 0.05 130 15 60 150 i Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 122 I 6m _ _ _ _ _ _ _ _ _ _ ________.__._____...w _ . , . , _ -~ . . - . A. .- . ~ , - - .,w .
-,,,...,% .- . .,,..er .-,w. . _ . _ _ - ,#,.... , .y. . . . . , , , .
Admin'istrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 TABLE 5.8-3 TABLE NOTATIONS aThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to 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. cThe 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. For a particular measurement system, which may include radiochemical separation: LLD = " E-V 2. 22 x 10* Y e" Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, 4 l 123 r-w>
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i TABLE 5.8-3 TABLE NOTATIONS E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 6 2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y and At should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the > fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular meas.~ement. Analyses shall be performed in such a manner that the stated LLDs will be ' achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In ' such cases, the contributing factors shall be identified and described in-the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7. F d LLD for drinking water samples. If no drinking water pathway exists, the . LLD of gamma isotopic analysis may be used. 124 1
.Rdministrative Procedure UNT-005-014 0ffsite Dose Calculatian Manual Revision 3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.2 Interlaboratory Comparison Proaram Specification Analyses shall be performed on all radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission. l APPLICABILITY: At all times. ACTION: I
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the ,
Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7. SURVEILLANCE RE0VIREMENTS The Interlaboratory comparison Program shall be described in Section 5.8.5. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological- Environmental Operating Report pursuant to Technical Specification 6.9.1.7. 125
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5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) , 5.8.3 Land Use Census Soecification A land use census shall be conducted and shall identify within a distance of ' km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden
- of greater than 50 mr (500 ft2) producing broad leaf vegetation.
APPLICABILITY: At all times. ACTION:
- a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 5.4.3, identify the new location (s) in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.
e i 126
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENT
- 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 i being obtained in accordance with Specification i 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 pathway, may be deleted from this monitoring program aftor October 31 of the year in which this land use census was conducted. Pursuant to Technical Specification 6.9.1.8 identify the new ( location (s) in the next Semiannual 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).
- 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 Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
. l 1
127 1
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~ 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS
- 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.
.l 128
.. . . . . -= . Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.4 Discription of the Radioloaical Environmental Monitorina Proaram The Radiological Environmental Monitoring Program (REMP) 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. 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, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical 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 l Environmental Monitoring Programs. I i l I I I 129
I Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.5 Description of .the Interlaboratory Comparison Proaram , As described in Section 5.8.2 the quality assurance _in 1 radiological environmental sampling will be maintained . 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, ,ha.kncu n value, the three standard deviation limit, and a two standard deviation /three I 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. ; 1 l l 1 1 l 130 l l
Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREME 5.8.6 Disnersion 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. l 4 4 F 4 131
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 - 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) 5.8.7 Radioloaical Environmental Monitorina Bases
- a. INTERLABORATORY COMPARISON 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. l l 9 t 132 q l l
.- . .~ . . - - . - . - . _ . . . . - - ..
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5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'
- b. LAND USE CENSUS (Section 5.8.3)
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 used. 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 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/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/mr , l I l l 133 1
Administrative Procedure UNT-005-014 ! Offsite Dose Calculation Manual Revision 3 - l l l 5.9 TECHNICAL SPECIFICATION CROSS-REFERENCES Changes to the Technical Specifications (TS) recommended by Generic Letter 89-01 (Reference 2.8) resulted in programmatic controls for radiological effluents, radiological environmental monitoring, and effluent radiation monitoring instrumentation being relocated to the Offsite Dose Calculation Manual. All references of the former version of the TS that are contained in current plant operating procedures shall be cross-referenced to specifications contained in the ODCM using Attachment ~6.20. Relocated requirements set forth in the ODCM should be incorporated into current plant operating procedures as they undergo routine review and revision. ( 4 m 134
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i-5.10 ROUTINE EFFLUENT RELEASE REPORTS 5.10.1 Annual Radioactive Effluent Release Report t 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. 5.10.1.1 The radioactive effluent release report. shall include a summary of the quantities of i radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory Guide 1.21,
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled ,
Nuclear Power Plants", Revision.1, June 1974, with dhta summarized on a quarterly basis following the format of Appendix B thereof. ' 5.10.1.2 The Annual Radioactive Effluent Release I 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 4 measured) on magnetic tape, or in the form i of joint frequency distributions of wind speed, wind direction, and atmospheric . stability. e I 135
~
Administrative Procedure .UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) In lieu of submission with the Radioactive Effluent Release Report, the summary of required meteorological data may be filed on site 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 1 during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gasecus Effluents to members of the public due to their activities inside the site boundary during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The 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. 4 136
Administrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) 5.10.1.3 The Annual Radioactive Effluent Release Report shall also include once a year an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium . fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 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. 5.10.1.4 The Annual Radioactive Effluent Release Report shall include the following 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),
137
I Administrative Procedure UNT-00S-014 Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) 1 D. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), E. Type of container (e.g., Type A, Type B), and F. Solidification agent or absorbent (e.g., cement, urea' formaldehyde). 5.10.1.5 The Annual Radioactive Effluent Release Report shall include a list and description cf unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. I 5.10.1.6 The Annual Radioactive Effluent Release Report shall include any changes to the Process Control Program (PCP) or the Offsite Dose Calculation Manual (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the_ land use census pursuant to ODCM 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. ~ 138
.___2. :
_ ._ _ _ __ .__ _ _ . . - ~ _ _ Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.10 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). .
i 139 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual ' Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) B. 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 Waste 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 10CFR50.59 140
-Administrative Procedure :UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd)
- 2. Sufficient detailed information to totally support the reason for.
the change without benefit of-additional or supplemental information.
- 3. A detailed description of the equipment, components and procescas 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. 141
Administrative' Procedure UNT-005-014 I Offsite Dose Calculation Manual Revision 3 5.10 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.
5.10.1.7 The Annual Radioactive Effluent Release Report shall include, if applicable, a description of events which led to exceeding the following limiting condition for operation: , l l 142
-. _ . _ _ _ . . - . _ . _ __ _ .~ _
Administrative Procedure UNT-005-014-Offsite Dose Calculation Manual Revision 3 5.10 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 the following:
- 1. For noble gases: 500 mrem /yr or less to the total body and 3,000 mrem /yr or less to the skin, and
- 2. For iodine-131, iodine-133, tritium, and all radioactive materials in particulate form with half-lives greater,than 8 days: 1,500 mrem /yr or less to l
any organ. 5.10.1.8 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
Administrative Procedure UNT-005-014 Offsite' Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) A. The quantity of radioactive material contained in each of the following unprotected tanks shall be limited to less than or equal to 1.57 x 10-2 curies, excluding tritium and dissolved or entrained noble gases. For outside temporary storage tanks, the curie content shall be limited such that a rupture will not result in exceeding 10CFR Part 20 limits at the ! unrestricted area boundary. ! l
- 1. PWST i
- 2. Outside temporary tank 5.10.1.9 The Annual Radioactive Effluent Release Report shall, if applicable, identify the cause of the unavailability of milk or fresh leafy vegetable samples at locations required by ODCM 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 4 report. 1 144 J
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) 5.10.1.10 The Annual Radioactive Effluent Release Report shall identify the new location (s), if a land use census. pursuant to ODCM 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 0DCM Specification 5~.4.3. 5.10.1.11 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. 5.10.1.12 With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable as required by ODCM Specification Table 5.6-1 for 30 days or longer, explain in the next Annual Radioactive Effluent Release-Report, pursuant to Specification 6.9.1.8, why this inoperability was not corrected within the time specified. W
-i 145 i
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.10 ROUTINE EFFLUENT RELEASE REPORTS (cont'd) 5.10.1.13 With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable as required by 00CM Specification Table 5.6-3 for 30 days or longer, explain in the next Annual Radioactive Efflueat Release Report, pursuant to Specification 6.9.1.8, why this in operability 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. ' 5.10.1.14 The Annual- Radioactive' Effluent Release Report shall identify any missing or late analysis results' for radioactive effluent samples collected during the reporting + period. 146
. . _ _ . _ . _ . . _. .. _ _ - . .. . . . =
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS 5.11.1 Abnormal Operation of Radioactive Gaseous Waste Treatment System 5.11.1.1 The Shift Supervisor shall be inmediately notified and a Condition Report promptly initiated whenever the following limiting condition for operation is exceedad: 5.11.1.2 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 wauld-exceed either:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
4 i 147
_ .__. ___ ~ . . . . . _ . . c Administrative Procedure UNT-005-014 l Offsite' Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd) l A. A Special Report shall be prepared for I submittal to the NRC within 30 days if gaseous waste is being discharged without treatment and in excess of the above limits. B. The Special Report shall include the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for 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.
s O 148
. - - - - . ~ . . _ . . - -.
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd) 5.11.2 Abnormal Operation of Radioactive Liouid Wasqr Treatment System ; 5.11.2.1 The Shift Supervisor shall be immediately notified and a Condition Report promptly initiated whenever the following limiting condition for operation is exceeded: ; 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 would exceed 0.06 meem to the total body or 0.2 mrem to any organ in a 31 day period. A. A Special Report shall be prepared for ! submittal to the NRC within 30_ days if radioactive liquid waste is being ; discharged without treatment and in excess of the above limits. B. The Special Report shall include the d following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for 4
the inoperability 4 149
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd)
- 2. Action (s) taken to restore the
' inoperable equipment to operable status
- 3. Summary description of action (s)- ,
taken to prevent a recurrence.
'l l
W 150 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 9 5.11 SPECIAL EFFLUENT REPORTS (cont'd) 5.11.3 Radioactive Liauid Effluent Dose Reports 5.2.4.1 The Shift Supervisor shall be immediately notified and a Condition Report promptly initiated whenever the following limiting condition for operation is exceeded: The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
- a. During any calendar quarter, to 1.5 mrem or less to the total body and to 5 mrem or less to any organ, and -
- b. During any calendar year, to 3 mrem or less to the total body and to 10 mrem or less to any organ. _ .
1 l 151
)
Administrative Procedure UNT-005-014 ; Offsite Dose Calculation Manual- Revision 3 ' 5.11 SPECIAL EFFLUENT REPORTS (cont'd) A. A Special Report shall be prepared for submittal , to the NRC within-30 days. 1 B. The 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. i NOTE The following step is applicable only if drinking water supply is taken from the receiving water. C. The Special Report shall also include the results of radiological analyses of the drinking water and the radiological impact on finished drinking water supplies with regard to the requirements of Code of Federal Regulations,_ title 40 part 141. 1 l I l 152 i
Administrative Procedure- UNT-005-014 Offsite Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd) 5.11.4 Radioactive Gaseous Effluent Dose Report - Noble Gases 5.11.4.1 The Shift Supervisor shall be immediately notified and a Condition Report initiated whenever the following limiting condition for operation is exceeded: The air do:a due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter, to 5 mrad or less gamma radiation and to 10 mrad or less for beta radiation and
- b. During any calendar year, to 10 mrad or less for gamma radiation and to-20 mrad or less for beta radiation.
A. A Special Report shall be prepared for submittal to the NRC within 30 days. B. The Special Report shall' identify the cause(s) for exceeding the limit (s) and define the corrective i actions that have been taken to reduce the ' releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with the above limits. 153
-Administrative Procedure UNT-005-014 Offsite-Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd) 5.11.5 Radioactive Gaseous Dose Report Non-Ncble Gases 5.11.5.1 The Shift Supervisor shall be immediately notified and a Condition Report promptly i initiated whenever the following limited condition for operation is exceeded: ,
The dose to a' member of the public from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at an beyond the site boundary shall be limited to the following:
- a. During any calendar quarter, to 7.5 '
mrem or less to any organ and
- b. During any calendar' year, to 15 mrem l or less to any organ.
A. A Special Report shall be prepared for. submittal to the NRC within 30 days. B. The 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 subsequent releases will be in compliance with the abovo limits. l 154 i
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3 i I I 5.11 SPECIAL EFFLUENT REPORTS (cont'd) l 1 5.11.6 Radioactive Effluent Dose Report - Uranium Fuel Cycle 5.11.6.1 The Shift Supervisor shall be immediately notified and a Condition Report promptly ; initiated whenever the following limiting condition for operation is exceeded: The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to 25 mrem or less to the total body or any organ except the thyroid, which shall be limited to 75 mrem. A. A Special Report shall be prepared for submittal to the NRC within 30 days. o m 155
Administrative Procedure UNT-005-014. Offsite Dose Calculation Manual Revision 3 r 5.11 SPECIAL EFFLUENT REPORTS (cont'd) B. The Special Report shall define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. The Special Report, as defined in 10 CFR Part 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. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. C. If the estimated doses ~ exceed the above limits, and:if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of Code of Federal Regulations, Title 40 Part 190. w 156
Administrative Procedure :UNT-005-014
.0ffsite Dose Calculation Manual Revision 3 5.11 SPECIAL EFFLUENT REPORTS (cont'd) 5.11.7 Environmental Protection Aaency Reportable Ouantities 5.11.7.1 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 initiated whenever any radionuclide released over a 24 hour 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 Emergency Planning Committee. Methods for determination of reportability and the Reportable Quantities values for radionuclides are contained within 40CFR302. T 1 4 e 157
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 3
~
5.12 SECONDARY RELEASE PATHS 5.12.1 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 of a likely potential arises for contributing more than 10% of the doses evaluated in this manual. 5.12.2 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 Decon Shop / Hot Machine Shop Exhaust
. Turbine Building Ventilation Exhaust
. Unmonitored Tank Atmospheric Vents Radioactive Waste Compactor Building Radioactive Waste Solidification Building
- Cooling Tower Atmospheric Entrainment 6.0 ATTACHMENTS Refer to Table of Contents w
158
i 1 l SITE B0UNDARY FOR , RADI0 ACTIVE GASEQUS AND LIQUID EFFLUENTS I
# l 11 Lastle Gwen, L2&3 r
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I u # , k A 4 P UNT-005-014 Revision 3 Attachment 6.1 (1 of 1) 159 I
HISTORICAL AVERAGE DISPERSION AND DEPOSITION PARAMETERS FOR AREAS AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY ANNUAL AVERACE ATNosPNERIC DISPEas!ON AND DEPOSITION PARAMETER $ SASED ON WISTORICAL METEOROLOGICAL DATA AND CURRENT LAND USE CENSU$ teceptor type or Ofrection Sector Dietence_ X/0 D/0 Location from site Location from site No Decay undepleted (miles) (meters) (sec/m3) (1/m2f site soundary N' A 0.8 1287 1.De-05 1.4e-08 NNE* 8 0.6 m 1.6e-05 3.4e 06 nee 8 C 0.6 m 1.5e 05 2.8e-08 ENE 0 0.6 m 1.6e-05 2.5e 06 E E 0.8 1287 6.9e 06 1.3e-08 ESE F 0.6 m 1.1e-05 2.3e-08 SE G 0.6 m 1.1e-05 3.1e-06 ssE 0.8 N 1287 6.3e 06 2.4e 08 s J 1.6 25 75 8.9e-07 2.Te 09 SSW 3.1 t 4989 3.0e 07 7.9e 10 SW 3.4 L 5472 3.3e-07 9.1e 10 WSW N 1.5 2414 1.7e 06 4.9e 09 W 1.0 N 1609 2.3e-06 7.3e 09 WNW 0.8 P 1287 7.5e-06 2.7e-08 W G 0.8 1287 1.0e 05 3.2e-08 kW a 0.9 1448 9.4e-06 2.4e-08 Residente W A g,9 1443 7,ge.06 1.8e 08 NNE B 1.3 2092 3.De 06 5.8e 09 NE C 0.9 1448 6.3e-06 1.2e-08 ENE D 0.9 E 1448 6.Se-C6 1.ie-08 E 2,2 3541 7.4e-07 1.0e 09 ESE F 3.1 4989 3.7e-07 4.8e-10 SE G 4.0 6437 2.3e-07 3.6e 10 W N 1.0 1609 2.3e 06 7.3e-09 WW P 0.9 1448 5.6e-06 2.De-08 W G 0.9 1648 7.7e-06 2.3e-08 MW R 3.0 4828 7.7e-07 1.3e 09 Nith Cow er# 0 0.9 1443 7.7e-06 2.3e-08 W G 4.9 7886 2.6e-07 4.te 10 vegetable coroen N A 1.0 1609 6.le 06 1.4e-08 NNE 8 1.3 2092 3.De-06 5.8e 09 , NE C 0.9 1448 6.3e-06 1.2e-08 ENE D 0.9 1448 6.Se-06 1.ie-08 E E 2.2 3541 7.4e-07 1.0e-09 ESE F 2.2 , 3541 7.De-07 1.1e-09 st ; G 2.3 3701 6.2e-07 1.3e-09 WSW N 1.5 2414 4 1.7e-06 4.9e-09 W W 1.1 i 1770 1.9e-06 5.7e 09 j WW P 0.9 1448 5.6e-06 2.De-08 W G 0.9 1448 7.7e-06 1 2.3e 08 NW R 3.0 4828 7.7.-06 ) 1.3. 09 ' Seef Cow E E 3.2 5150 3.7e-07 4.2e 10 E5E 3.5 F 5633 3.0e 07 3.6e 10 St G 4.5 7242 1.9e 07 2.Se 10 ! WSW N 1.2 1931 2.7e 06 8.6e-09 I WW P 0.9 1448 5.6e-06 2.De-08 W 0 0.9 1448 7.7e-06 2.3e-08 NW R 2.3 3701 1.3e 06 2.4e-09 ; Notes:
- The alte tomdery in this sector is located over water. The location comot be occLg>ied cantinuousty for the Life of the ptont.
b The animeLa et thfe Location do not produce milk for homen consumption. UNT-005-014 Revision 3 Attachment 6.2 (1 of 1) 160 i
SITE RELATED LIQUID INGESTION DOSE COMMITMENT ^ FACTORS (Aj) FOR INDIVIDUAL NUCLIDES ACE GRQJP: ADULT DISCHARGE POINT! CIRCULA11NO WATER (into Mississippi River) WUCLIDE ORGAN 00$E CONVERSION FACTORS
\
BONE LIVER T.80DY THYR 010 KIDNEY LUNG 01 LLI W3 C 14 0.00E+00 2.66E 01 2.66E-01 2.66E-01 2.66E-01 2.66E 01 2.66E 01 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 4.08E+02 4.08E+02 4.08E+02 4.08E+02 ' P 32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.19E+06 CR 51 MN-54 0.00E+00 0.00E+00 1.27E+00 7.62E 01 2.81E-01 1.69E+00 3.21E+02 0.00E+00 4.38E+03 8.35E+02 0.00E+00 1.30F+03 0.00E+00 1.34E+04 MW-56 FE-55 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.52E+03 FE 59 6.59E+02 4.56E+02 1.06E+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 1.04E+03 2.45E+03 9.38E +02 0.00E+00 0.00E+00 6.83E+02 8.15E+03
+
CO 58 CD-60 0.00E+00 8.95E+01 2.01E+02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 NI 63 0.00E*00 2.57E+02 5.67E+02 0.00E+00 0.00E+00 0.00E+00 4.83E41 3.12E+04 2.16E+03 1.05E+03 0.00E+00 0.00E+00 0.00E+00 4
........-................................................................ 51E+02 NI-65 CU 64 1.27E+02 1.64E+01 7.51E+00 0.00E+00 0.00E+00 0.LME+00 4.17E+02 ZN 65 0.00E*00 1.00E+01 4.70E+00 0.00E+00 2.52E+01 0.00E+00 8.53E+02 2.32E+04 7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.64
............................................................................E+04 2N-69 BR 83 4.93E+01 9.43E+01 6.56E+00 0.00E+00 6.13E+01 0.00E+00 1.42E+01 BR-84 0.00E+00 0.00E+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11
............................................................................E-04 BR-85 j
RB-86 0.00E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f 0.00E+00 1.01E+05 RB-88
- 4. 71E+04 0.00E+00 0.00E+00 0.00E+00 1.99E+04 0.00E+00 2.90E+02 1.54E+02 0.00E+00 0.00E+00 0.00E+00 4.00
............................................................................E*09 RB 89 SR.89 0.00E+00 1.92E+02 1.35E+02 0.00E+00 0.00E+00 0.00E+00 1.12E 11 '
SR-90 2.22E+04 0.00E+00 6.38E+02 0.00E+00 0.00E+00 0.00E+00 3.57E+03 i 5.47E+05 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 1 l
......................................................................... 58E+04 sR-91
)
SR-92 4.09E+02 0.00E+00 1.65E+01 0.00E+00 0.00E+00 0.00E+00 1.95E+03 Y-90 1.55E+02 0.00E+00 6.71E+00 0.00E+00 0.00E+00 0.00E+00 3.08E+03 5.79E-01 0.00E+00 1.55E 02 0.00E+00 0.00E+00 0.00E+00 6.14
............................................................................E+03 Y 91M Y 91 5.47E-03 0.00E+00 2.12E-04 0.00E+00 0.00E+00 0.00E+00 1.61E 02 8.49E+00 0.00E+00 2.27E 01 0.00E+00 0.00E+00 0.00E+00 4.67E+03 )
i Y 92 5.09E-02 0.00E+00 1.49E 03 0.00E+00 0.00E+00 0.00E+00 8.91
............................................................................E+02 .... -
Conversion f actors are in u11ts of areWhr per uCl/ml UNT-005-014 Revision 3 Attachment 6.3 (1 of 6) 161 i
SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL NUCLIDES ACE CROUPt A00Li DISCHARCE PolWf t CIRCULATING WATER (into Mississippt U ~r) NUCLIDE ORGAW DOSE CONVERSION FACTORS BONE L IVER T . BCD f THYR 010 K!0NEY LUNG 01 LLt Y 93 1.61E 01 0.00E+00 4.46E 03 0.00E+00 0.00E+JO 0.00E+00 5.12E *03 ZR-95 2.52E 01 8.07E 02 5.46E 02 0.00E+00 1.27T, 01 0.00E+00 2.56E+02 ZR-97 1.39E-02 2.81E 03 1.28E 03 0.00E+00 4.246 03 0.00E+00 8.69E+02 WS 95 4.47E+00 2.49E+00 1.34E+00 0.00E+00 2.46E+00 0.00E+00 1.51E+04 MD-99 0.00E+00 1.05E+02 1.99E+01 0.00E+00 2.37E +02 0.00E+00 2.43E+02 TC-99M 8.96E 03 2.53E 02 3.23E 01 0.00E+00 3.85E-01 1.24E-02 1.50E+01 TC 101 9.22E 03 1.33E-02 1.30E 01 0.00E+00 2.39E-01 6.79E 03 3.99E-14 RU-103 4.50E+00 0.00E+00 1.94E+00 0.00E+00 1.72E+01 0.00E+00 5.25E+02 ku 105 3.75E 01 0.00E+00 1.48E 01 0.00E+00 4.84E+00 0.00E+00 2.29E+02 RU-106 6.69E+01 0.00E+00 8.46E+00 0.00E*00 1.29E+02 0.00E+00 4.33E+03 AG 110M 8.27E 01 7.65E-01 4.54E-01 0.00E+00 1.50E+00 0.00E+00 3.12E+02 TE 125M 2.57E+03 9.30E*02 3.44E+02 7.72E+02 1.04E+04 0,00E+00.1.03E+04 TE-127M 6.49E+03 2.32E+03 7.70E+02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 TE-127 1.05E+02 3.78t+01 2.28E+01 7.81E+01 4.29E+02 0.00E+00 8.32E+03 TE 129M 1.10E+04 4.11E+03 1. 74E *03 3.78E+03 4.60E+04 0.00E+00 5.55E+04 TE 129 3.01E+01 1.13E+01 7.33E+00 2.31E+01 1.26E+02 0.00E+00 2.27E+01 TE-131M 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 0.00E+00 8.05E+04 TE 131 1.89E+01 7.88E+00 5.96E+00 1.55E+01 8.27E+01 0.00E+00 2.67E+00 TE 132 2.41E*03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.39E+04 I 130 2.74E+01 8.09E+01 3.19E+01 6.86E+03 1.26E+02 0.00E+00 6.97E+01 1 131 1.51E+02 2.16E+02 1.24E+02 7.08E+04 3.70E+02 ' O.00E+00 5.70E+01 1 132 7.37E+00 1.97E+01 6.89E+00 6.89E+02 3.14E+01 0.00E+00 3. 70E+00 1 133 5.15E+01 8.96t+01 2.73E+01 1.32E+04 1.56E+02 0.00E+00 8.06E+01 1 134 3.85E+00 1.05E+01 3.74E+00 1.81E+02 1.66E+01 0.00E+00 9.11E 03 1 135 1.61E+01 4.21E*01 1.55E+01 2.78E+03 6.75E+01 0.00E+00 4.75E+01 CS-134 2.98E+05 7.09E+05 5.79E+05 0.00E+00 2.29E+05 7.61E+04 1.24E+04 CS 136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.39E+03 1.40E+04 CS-137 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.77t+05 5.89E+04 1.01E+04 CS-138 2.64E+02 5.22E+02 2.59E+02 0.00E+00 3.84E+02 3.79E+01 2.23E 03 BA-139 9.66E 01 6.88E 04 2.83E 02 0.00E+00 6.43E 04 3.90E-04 1.71E+00 Conversion f actora are in mits of meesn/hr per uCl/ml UNT-005-014 Revision 3 Attachment 6.3 (2 of 6) 162
1
.j i
l 1 1 SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL NUCLIDES ACE CROUP: ADULT DISCHARCE PolkT CIRCULATING WATER (into Mississippi River) NUCLIDE ORGAN DOSE CONVER$10N FACTORS BONE LIVER T . BCD Y TNTR010 KIDNEY LUNG Gl-LLI SA 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 BA-142 2.12E-01 2.18E-04 1.33E 02 0.00E+00 1.84E-04 1.23E 04 2.99E 19 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 CE-141 2.59E 02 1.75E 02 1.99E 03 0.00E+00 8.15E 03 0.00E+00 6. 71E+01 CE*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*?43 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 4.2SE 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 B.10E+04 NP-239 2.89E 02 2.85E 03 1.57E 03 0.00E+00 8.88E-03 0.00E+00 5.P/.E+02 Conversion factors are in units of mrem /hr per uti/mi UNT-005-014 Revision 3 Attachment 6.3 (3 of 6) 163
k SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL NUCLIDES ACE CRajP: AOULT O!SCHARGE POINT: ALL OTHERS tinto 40 Arpent Canal) NUCLIDE ORGAN DOSE CONVER$10N FACTORS BONE LIVER T.80DY THYkoto KIONEY LONG GI LLI H3 C-14 0.00E+00 8.96E+00 8.96t+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 3.15E+04 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 NA-24 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 P-32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E*00 5.20E+06 CR-51 MN 54 0.00E+00 0.00E+00 1.49E+00 8.94E-01 3.29E 01 1.98E+00 3.76E+02 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 MN.56 0.00E+00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03 FE-55 8.87E+02 6.13E+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 FE-59 1.40E+03 3.29E+03 1.26E+03 0.00E+00 0.00E+00 9.19E+02 1.10E+04 CO 58 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Co-60 N1-63 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16t+03 4.19E+04 2.91E+03 1.41E+01 0.00E+00 0.00E+00 0.00E+00 6.07E+02 NI-65 CU-64 1.70E+02 2.21E+01 1.01E+01 0.00E+00 0.00E+00 0.00c+00 5.61E+02 2N 65 0.00E+00 1.69E+01 7.93E+00 0.00E*00 4.26E+01 0.00E+00 1.44E+03 2.36E+04 7.50E+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4. 73E+04 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 0.00E+00 0.00E+00 4.38E+01 0.00E+00 0.00E+00 0.00E+00 6.30E+01 BR 84 0.00E*00 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 4.45E 04 BR 85 0.00E+00 0.00E+00 2.33E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 RB 88 0.00E+00 2.95E+02 1.56E+02 0.00E+00 0.00E+00 0.00E+00 4.07E 09 R8 89 St.89 0.00E+00 1.95E+02 1.37E+02 0.00E+00 0.00E+00 0.00E+00 1.13E-11 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E +00 0.00E+00 7.66E+03 SR.90 1.18E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 S4-91 8.79E+02 0.00E+00 3.55E+01 0.00E+00 0.00E+00 0.00E+00 4.19E+03 SR-92 3.33E+02 0.00E+00 1.44E+01 0.00E+00 0.00E+00 0.00E+00 6.60E+03 Y 90 1.38E+00 0.00E+00 3.69E 02 0.00E+00 0.00E+00 0.00E+00 1.46E+04 Y 91M 1.30E-02 0.00E+00 5.04E-04 0.00E+00 0.00E+00 0.00E+00 3.82E-02 Y-91 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 1.11E+04 Y 92 1.21E.01 0.00E+00 3.53E-03 0.00E+00 0.00E+00 0.00E+00 2.12E+03 Conversion f actors are in mits of arem/hr per uC1/mi UNT-005-014 Revision 3 Attachment 6.3 (4 of 6) 164
1 SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS ~(Aj) FOR INDIVIDUAL NUCLIDES ACE CRGJP: ADULT DISCHARGE POINT: ALL OTHERS (into 40 Arpent Canal) NUCL10E ORGAN DOSE CONVERSION FACTORS BONE LIVER T.800Y THYR 0!D KIDNEY LUNG CI LLI Y-93 3.83E-01 0.00E+00 1.06E 02 0.00E+00 0.00E+00 0.00E+00 1.22E+04 ZR-95 2.77E+00 8.88E-01 6.01E 01 0.00E+00 1.39E+00 0.00E+00 2.82E+03 2R-97 1.53E 01 3.09E-02 1.41E-02 0.00E+00 4.67E-02 0.00E+00 9.57E+03 NB 95 4.98E+00 2.77E+00 1.49E+00 0.00E+00 2.74E+00 0.00E+00 1.68E+04 NF 99 0.00E+00 4.62E+02 8.79E+01 0.00E+00 1.05E+03 0.00E+00 1.07E+03 TC-99M 2.94E-02 8.32E 02 1.06E+00 0.00E+00 1.26E+00 4.07E 02 4.92E+01 TC-101 3.03E 02 4.36E 02 4.28E 01 0.00E+00 7.85E-01 2.23E-02 1.31E 13 RU-103 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00 2.31E+03 20 105 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+04 AG-110M~ 1.41E+01 1.30E+01 7.74E+00 0.00E+00 2.56E+01 0.00E+00 5.32E+03 ! TE-125N 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04 TE 127M 7.0$E+03 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E+04 TE-127 1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.00E+00 9.03E+03 TE-129M 1.20E+04 4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.00E*00 6.03E+04 TE-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01 fE-131M 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.00E+00 8.74E+04 TE-131 2.05E+01 8.57E+00 6.47E+00 1.69E+01 8.98E+01 0.00E+00 2.90E+00 TE 132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 .1.63E+04 0.00E+00 8.02E+04 I 130 9.01E+01 2.66E+02 1.0$E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 1 131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 'O.00E+00 1.87E+02 1-132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.00E+00 1.22E+01 1-133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.00E+00. 2.64E+02 1-134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01 0.00E+00 2.99E 02 1-135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.00E+00 1.56E+02 CS-134 3.03E+05 7.21E+05 5.89E+05 0.00E+00 2.33E+05 7.75E+04 1.26E+04 CS 136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42f+04 CS-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 CS 138 2.69E+02 5.31E+02 2.63E+02 0.00E+00 3.90E+02 3.85E+01 2.27E-03 BA 139 9.00E+00 6.41E-03 2.64E 01 0.00E+00 5.99E 03 3.64E-03 1.60E+01 conversion f actors are in mits of arem/hr per uti/ml UNT-005-014 Revision 3 Attachment 6.3 (5 of 6) - 165
- - ,y -
SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Aj) FOR INDIVIDUAL NUCLIDES AGE CROUP AOULT DISCHARGE PolNT: ALL 01HERS (into 40 Arpent Canet) NUCLICE ORGAN 00SE CONVERSION FACTORS BONE LIVER T.80DY THYR 010 KIDNEY LUNG GI LLI BA-140 BA-141 1.88E+03 2.37t+00 1.23E+02 0.00E+00 8.05E-01 1.35E+00 3.88E+03 4.37E +00 3.30E 03 1.48E 01 0.00E+00 3.07E 03 1.87E-03 2.06E-09 8A 142 1.98E+00 2.03E-03 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 CE 141 1.83E 02 8.33E-03 2.07E 03 0.00E+00 0.00E+00 0.00E+00 6.08E+01 8.01E 01 5.42E 01 6.15E 02 0.00E+00 2.52E 01 0.00E+00 2
......................................................................... 07E+03 CE*143 CE*144 1.41E 01 1.04E+02 1.16E 02 0.00E+00 4.60E 02 0.00E+00 3.90E+03-4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 PR 143 1.32E+00 5.28E 01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+0 PR 144 3.-
V 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 6.08E-01 0.00E+00 4.99E+03 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8
......................................................................... 34E+04 NP 239 1.28E 01 1.25E 02 6.91E-03 0.00E+00 3.91E 02 0.00E+00 2.57E+03 Conversion f actors are in uilts of areavhr per uCI/mi UNT-005-014 Revision 3 Attachment 6.3 (6 of 6) 166
DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES' - L Nuclide. p-air *(Nj) p-Skin **(Lj) y-air *(Mj) y-Body **(Kj) - Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 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.llE-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 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 .8.84E-03 ,
, mrad - m pCi - yr ;
, , mrem - m pCi - yr :
Extracted from Table B-1 of Regulatory Guide 1.109, Revision 1,1977 8 1 l
.i UNT-005-014 Revision 3 Attachment 6.4 (1 of 1) l 167 j l
i
. . - - - = - . . _ . . - - . -- . .. i 4 INHALATION PATHWAY DOSES DUE TO l1 RADIONUCLIDES OTHER THAN N0BLE GASES, Rj I PATHWAY: INHALATION { i ACE GROUP: ADULT ( 1 0F 3 ) i NUCLICE ORGAN DOSE CONVERSION FACTORS BONE LIVER T.800Y THYROID K!0NEY LUNG GI LLI M3 C-14 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 NA 24 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 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 MM 54 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 NN 56 FE 55 0.00E+00 1.24E+00 1.83E-01 0.00E+00 1.30E+00 9.44E+03 2.02E+04 FE-59 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 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, co-60 kl.63 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1. 78E+ 0 1.34E+04
....................................................................5 NI 65 CU-64 1.54E+00 2.10E 01 9.12E 02 0.00E+00 0.00E+00 5.60E+03 1.23E+04 ZN 65 0.00E+00 1.46E+00 6.15E-01 0.00E+00 4.62E+00 6.78E+03 4.90E+04 3.24E+04 1.03E+05 -4.66E+04 0.00E+00 6.90E+04 8.64E+05
....................................................................... 5.34E+04 ZN-69 i
BR 83 3.46E 02 6.51E 02 4.52E-03 0.00E+00 4.22E-02 9.20E+02 1.63E+01 BR*84 0.00E+00 0.00E+00 2.41E+02 0.00E+00 0.00E+00 0.00E+00 2.32E+02 0.00E+00 0.00E+00 3.13E+02 0.00E+00 0.00E+00 0.00E+00 1
......................................................................... 64E 03 BR 85 Ra 86 0.00E+00 0.00E+00 1.28E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 88-88 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 0.00E+00 3.87E+02 1.93E+02 0.00E+00 0.00E+00 0.00E+00 3
......................................................................... 34E......
RB-89 09 58 89 0.00E+00 2.56E+02 t.70E+02 0.00E+00 0.00E+00 0.00E+00 9.28E 12 5R-90 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.5DE+05 9.92E+07 0.00E+00 6.10E+06 0,00E+00 0.00E+00 9.60E+06 7
......................................................................... 22E+05 5R-91 SR 92 6.19E+01 0.00E+00 2.50E+00 0.00E+00 0.00E+00 3.65E+04 1.91E+05 YJ90 6.74E+00 0.00E+00 2.91E-01 0.00E+00 0.00E+00 1.65E+04 4.30E+04 2.D9E+03 0.00E+00 5.61E+01 0.00E+00 0.00E+00 1.70E+05 5.06E+
..............................................................................05 Y-91M Y 91 2.61E 01 0.00E+00 1.02E 02 0.00E+00 0.00E+00 1.92E+03 1.33E+00 Y 92 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 1.03E+01 0.00E+00 3.02E 01 0.00E+00 0.00E+00 1.57E+04 7
......................................................................... 35E+04 Conversion factors are in units of mese/yr per uCl/ cubic meter.
UNT-005-014 Revision 3 Attachment 6.5 (1 of 12) 168
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: INHALATION ACE CROUP: ADULT ( 2 0F 3 ) l I i NUCL10E ORGAN DOSE CONVERSION FACTORS 1 CONE LIVER T .8007 THYROIO K!0NEY LUNO 01-LL1 I Y 93 i 9.44E+01 0.00E+00 2.61E+00 0.00E+00 0.00E+00 4.85E+04 4.22E+05 22-95 j 1.07E +05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 ZR-97 9.6BE+01 1.96E+01 9.04E+00 0.00E+00 2.97E+01- 7.87E+04 5.23E+05 ka-95 1.41E+04 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+04 2.48E+05 TC-99M 1.03E-03 2.91E 03 3. 70E-02 0.00E+00 4.42E-02 7.64E+02 4.16E+03 TC-101 4.18E-05 6.02E 05 5.90E-04 0.00E+00 1.08E-03 3.99E+02 1.09E.11 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 T.90E-01 0.00E+00 3.11E 01 0.00E+00 1.02E+00 1.10E+04 4.82E+04 RU 106 6.91E+04 0.00E+00 8.72E+03 0.W +00 1.34E+05 9.36E+06 9.12E+05 AD.110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.53E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE.127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE.127 1.40E+00 6.42E-01 3.10E-01 1.06E+00 5.10E+00 6.51E+03 5.74E+04 TE 129M 9.76E+03 4.67E+03 1.58E+03 3.442+03 3.66E+04 1.16E+06 3.83E+05 TE 129 4.98E 02 2.39E 02 1.24E.02 3.90E.02 1.87E 01 1.94E+03 1.57E+02 TE-131M 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05
?E-131 1.11E 02 5.95E 03 3.59E 03 9.36E-03 4.37E 02 1.39E+03 1.84E+01 TE 132 2.60E+02 2.15t+02 1.62E+02 1.90E+02 1.46E+03 2.88E*05 5.10E+05 1 130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 0.00E+00 7.69E+03 1 131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 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 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 1 154 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 0.00E+00 1.01E+00 1 135 2.68E+03 4.98E+03 2.57E+03 4.48E+05 1.11E+04 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+04 1.04E+04 C1 136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS 137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 CS 138 3.31E+02 6.21E+02 3.24E+02 0.00E+00 4.80E+02 4.86E+01 1.86E.03 BA 139 9.36F 01 6.66E*04 2.74E-02 0.00E+00 6.22E-04 3.76E+03 8.96E+02 Conversion factors are in units of areW yr per uCl/ctble meter.
UNT-005-014 Revision 3 . Attachment 6.5 (2 of 12) 169
. INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj ,
t PATHWAY: INNALATION AGE CROUP: ADULT ( 3 of 3 ) NUCLIOE ORGAN DOSE CONVER$10N FACTOR $ , BONE LIVER f.BCCY THYR 010 (IDNEY LUNO Gl*LLI 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 1.00E-01 7.53E 05 3.36E-03 0.00E+00 7.00E 05 1.94E+03 1.16E-07 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 CE 141 1.99E+04 1.35E+04 1.53E+03 1.00E+00 6.26E+03 3.62E+05 1.20E+05 CE 143 1.86E+02 1.38E+02 1.53E+01 0.00E+00 6.08E+01 7.98E+04 2.26E+05 CE 144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+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 05 ND 147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+00 7.08E+00 2.48E+00 0.00E+00 0.00E+00 2.90E+04 1.55E+05 NP*239 2.30E+02 2.26E+01 1.24E+01 0.00E+00 7.00E+01 3.76E+04 1.19E+05 Conversion f actors are in mits of mrem /yr per uCl/ cubic meter. UNT-005-014 Revision 3 Attachment 6.5 (3 of 12) 170
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: INHALATION ACE CROUP: TEEN ( 1 0F 3 ) NUCLICE ORGAN 00sE CONVERSION FACTORS BokE LIVER T.BCOY THYROIO KIONEY LUNG O! LLI H3 C 14 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4. 87E+03 4.87E+03 NA-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38
............................................................................E+04 P-32 CR 51 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 MW 54 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+0 6.68E+04
....................................................................6...........
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+04 1.59E+01 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03
- 3. 70E +04 1.43E+04 0.00E+00 0.00E+00 1 1.78E+05
............................................................... 53E+06 CD 58 Co-60 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 NI-63 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 1.42E+04
..............................................................3.07E+05 N1 65 CU-64 2.18E+00 2.93E-01 1.27E 01 0.00F+no 0.00E+00 9.36E+03 3.67E+04 ZN-65 0.00E+00 2.03E+00 8.48E 01 0.00E+00 E.41E+00 1.11E+04 6.14E+04 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1 4.66E+04 ZW-69 24E+06 BR 83 4.13E 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+00 4.33E+02 0.00E+00 0.00E+00 0 0.00E+00
............................................................... 00E+00 8R-85 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 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 0.00E+00 5.46t+02 2.72E+02 0.00E+00 0.00E+00 2.92E 05
............................................................. 0.00E+00 RS 89 S4-89 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 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 7.65E+05
..............................................................1.65E+07 SR 91 SR-92 8.80E+01 0.00E+00 3.51E+00 0.00E+00 0.00E+00 6.07E+04 2.59E+05 Y 90 9.52E+00 0.00E*00 4.06E-01 0.00E+00 0.00E+00 2.74E+04 1.19E+05 2.98E+03 0.00E+00 8.00E+01 0.00E+00 0.00E+00 5.59E+05
............................................................. 2.93E+05 Y 91M Y 91 3.70E-01 0.00E+00 1.42E-02 0.00E+00 0.00E+00 3.20E+03 3.02E+01 Y-92 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 1.47E+01 0.00E+00 4.29E-01 0.00E+00 0.00E+00 2.68 1.65E+05
..................................................................E+04 ..............
Corwersion factors are in units of area /yr per uti/ ethic meter. UNT-005-014 Revision 3 . Attachment 6.5 (4 of 12) 171
l INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATNWAY: INHALATION ACE CROUP: TEEN ( 2 0F 3 ) NUCLIDE ORGAN DOSE CONVER$10N FACTOR $ BONE LIVER T .BCDY THYROID E!0NEY LUNG Cl*LLI Y 93 1.35E+02 0.00E+00 3.72E+00 0.00E+00 0.00E+00 8.32E+04 5.79E*05 2R 95 1.46t+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 Na 95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 MD-99 0.00E+00 1.69E+02 3.22E+01 0.00E+00 4.11E+02 1.54E+05 .2.69E+05 TC 99M 1.38E.03 3.86E-03 4.99E 02 0.00E+00 5.76E 02 1.15E+03 6.13E+03 TC 101 5.92E-05 8.40E-05 8.24E-04 0.00E+00 1.52E 03 6.67E+02 8.72E 07 RU 103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 RU 105 1.12E+00 0.00E+00 4.34E 01 0.00E+00 1.41E+00 1.82E+04 9.04E+04 RU-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 AC 110M 1.38t+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE 125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE-127M 1.80E+04 8.16E+03 1.78E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE 127 2.01E+00 9.12E-01 4.42E 01 1.42E+00 7.28E+00 1.12E+04 8.08E+04 TE 129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.0$E+05 TE 129 7.10E 02 3.38E-02 1.76E-02 5.18E-02 2.66E 01 3.30E+03 1.62E+03 TE-131M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 TE-131 1.58E 02 8.32E 03 5.04E 03 1.24E 02 6.18E.02 2.34E+03 1.51E+01 TE 132 3.60E+02 2.90E+02 2.19E+02 2.46E+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+04 0.00E+00. 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 1 132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 0.00E+00 1.27E+03
!*133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 1 134 8.88E+02 2.32E+03 8.40E+02 3.95E404 3.66E+03 0.00E+00 2.04E+01 1 135 3.7DE+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 0.00E+00 6.95E+03 c5 134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76t+03 c5 136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 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 BA 139 1.34E+00 9.44E 04 3.90E-02 0.00E+00 8.88E 04 6.46E+03 6.45E+03 Corwersion factors are in units of aren/yr per uCl/cuale meter.
I l UNT-005-014 Revision 3 Attachment 6.5 (5 of 12) 172 l 1
INHALATION PATHWAY DOSES DUE TO - RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: INHALATION AGR GROUP: TEEN ( 3 of 3 ) NUCL10E ORGAN 00SE CONVERSION FACTORS BONE LIVER T.800Y THYR 010 K!0NEY LUNG Gl*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+00 9.84E 05 3.29E+03 7.46E 04 BA 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 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.8EE+03 6.14E+05 1.26E+05 CE 143 2.66E+02 1.94E+02 2.16E+01 0.00E+00 8.64E+01 1.30E+05 2.55E+05 CE 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 NP 239 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 1.32E+05 Conversion f actors are in tnits of messi/yr per uti/ctbic sieter. UNT-005-014 Revision 3 Attachment 6.5 (6 of 12) 173
, INHALATION PATHWAY DOSES DUE TO ,
RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: INHALA110N ACE CROUPt CHILD ( 1 0F 3 ) NUCLIOE ORGAN DOSE CONVER$10N FACTORS 80NE LIVER T.80DY THYR 010 K!0NEY 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 2.43E+01 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 MW-56 0.00E+00 1.66E+00 3.12E-01 0.00E+00 1.67E+00 1.31E+04 1.23E+05 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE 59 2.07E+04 3.34Et04 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 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2 75E+05 6 33E+03 NI 65 2.99E+00 2.96E 01 1.64E 01 0.00E+00 0.00E+00 8.18E+03 8.40E+04 CU-64 0.00E+00 1.99E+00 1.07E+00 0.00E+00 6.03E+00 9.58E+03 3.67E+04 2N 65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 2N 69 6.70E 02 9.66E 02 8.92E 03 0.00E+00 5.85E 02 1.42E+03 1.02E+04 Ba 83 0.00E*00 0.00E+00 4.74E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR 84 0.00E+00 0.00E+00 5.48E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 84 85 0.00E+00 0.00E+00 2.53E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RS 86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 k8 88 0.00E+00 5.62E+02 3.66E+02 0.00E+00 0.00E+00 0.00E+00 1.72E+01 RS 89 0.00E+00 3.45E+02 2.90E+02 0.00E+00 0.00E+00 .0.00E+00 1.89E+00 Sa 89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR 90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 54 91 1.21E+02 0.00E+00 4.59E+00 0.00E+00 0.00E+00 5.33E+04 1.74E+05 SR 92 1.31E+01 0.00E+00 5.25E 01 0.00E+00 0.00E+00 2.40E+04 2.42E+05 Y 90 4.11E+03 0.00E+00 1.11E+02 0.00E+00 0.00E+00 2.62E+05 2.68t+05 Y 91M 5.07E-01 0.00E+00 1.84E 02 0.00E+00 0.00E+00 2.81E+03 1.72E+03 Y 91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 Y-92 2.04E+01 0.00E+00 5.81E 01 0.00E+00 0.00E+00 2.39E+04 2.39E+05 Conversion factors are in units et arem/yr per uCl/ctbic meter. . UNT-005-014 Revision 3 Attachment 6.5 (7 of 12) 174
-l l
INHALATION PATHWAY DOSES DUE TO < i RADIONUCLIDES OTHER THAN NOBLE GASES, Rj l 1 e i. PATHWAY: INHALATION ACE CROUP: CHILD ( 2 0F 3 ) l I NUCLICE ORCAN DOSE CONVERSION FACTOR $ SONE LIVER T.8C0Y THYROID K!DNEY LUNG GI LLI Y-93 1.86E+02 0.00E+00 5.11E+00 0.00E+00 0.00E+00 7.44E+04 3.89E+05 2R 95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 2R 97 1.88E+02 2.72E+01 1.6CE+01 0.00E+00 3.88E+01 1.13E+05 3.51E+05 NS 95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 No 99 0.00E+00 1.72E+02 4.2SE+01 0.00E+00 3.92E+02 1.35E+05 1.27E+05 TC 99M 1.78E-03 3.48E*03 5.77E-02 0.00E+00 5.07E 02 9.51E+02 4.81E+03 TC-101 8.10E 05 8.51E-05 1.08E-03 0.00E+00 1.45E.03 5.85E+02 1.63E+01 RU 103 2.79E+03 0.00E+00 1.07E+03 0.00E+0^, 7.03E+03 6.62E+05 4.48E+04 RU-105 1.53E+00 0.00E+00 5.55E 01 0.00E+00 1.34E+00 1.59E+04 9.95E+04 RU-106 1.34E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 AC-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 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-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-127 2.77E+00 9.51E 01 6.10E 01 1.96E+00 7.07E+00 1.00E+04 5.62E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 TE-129 9.77E-02 3.50E 02 2.38E*02 7.14E 02 2.57E-01 2.93E+03 2.55E+04 TE 131M 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 TE-131 2.17E 02 8.44E 03 6.59E 03 1.70E 02 5.88E-02 2.05E+03 1.33E+03 TE 132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1. 77E+03 3.77t+05 1.38E+05 1 130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 0.00E+00 5.11E+03 1 131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 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+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 1 134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.00E+00 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 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 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03
................................................................................ )
Cs*137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 C5 138 6.33E402 8.40E+02 5.55E+02 0.00E+00 6.22E+02 6.81E+01 2.70E+02 84-139 1.84E+00 9.84E-04 5.36E-02 0.00E+00 8.62E-04 5.77E+03 5.77[+04 Conversion f actors are in mits of mrem /yr per uCl/ctbic seter. UNT-005-014 Revision 3 Attachment 6.5 (8 of 12) 175
. INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj P
PATHWAY: INHALATION ACE CR31P: CHILD ( 3 of 3 ) e NUCLICE ORGAN DOSE CONVER$10N FACTORS BONE LIVER T.80DY THYR 010 Kl0NEY LUNG GI-LLI BA 140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1. 74E+06 1.02E+05 84 141 , 1.96E-01 1.09E 04 6.36E 03 0.00E+00 9.47E-05 2.92E+03 2. 75E+02 BA 142 4.99E-02 3.60E-05 2.79E-03 0.00E+00 2.91E-05 1.64E+03 2. 74E+C 0 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 7.59E+04 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE 143 3.66E+02 1.99E+02 2.87E+01 0.00E+00 8.36E+01 1.15E+05 1.27E+05 CE 144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.8?E+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 1.57E+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 W 187 1.63E+01 9.66E+00 4.33E+00 0.00E+00 0.00E+00 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 factors are in tnits of arem/yr per uCl/ cubic meter.
. UNT-005-014 Revision 3 Attachment 6.5 (9 of 12) 176
-INHALATION PATHWAY DOSES DUE TO -
RADIONUCLIDES OTHER THAN NOBLE GASES, Rj e PATHWAY: INHALATION AGE CROUP: INFANT ( 1 0F 3 ) , NUCLIDE ORGAN 00SE CONVER$10N FACTORS BONE LIVER T.BCX)Y THYR 010 KIONEY LUND GI LLI
'I, H3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C 14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 NA 24 1.06E+04 1.06E+04 1.06E+04 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 CA 51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 !
MN 54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 MW 56 0.00E+00 1.54E+00 2.21E 01 0.00E+00 1.10E+00 1.25E+04 7.17E+04 FE 55 1.97E +04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 - FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 Co-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 I 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 2.39E+00 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 ZN 65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 ZN-69 5.39E 02 9.67E 02 7.18E.03 0.00E+00 4.02E.02 1.47E+03 1.32E+04 BR-83 0.00E+00 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 0.00E+00 8R 85 0.00E+00 0.00E+00 2.04E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8 86 0.00E+00 1.90E+05 8.82E+04 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 Re 89 0.00E+00 3.21E+02 2.06E+02 0.00E+00 0.00E+00 0.00E+00 6.82E+01 SR 89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05
$R-91 9.56E+01 0.00E+00 3.46E+00 0.00E+00 0.00E+00 5.26E+04 7.34E+04 SR 92 1.05E+01 0.00E+00 3.91E 01 0.00E+00 0.00E+00 2.35E+04 1.40E+05 Y 90 3.29E+03 0.00E+00 8.82E+01 0.00E+00 0.00E+00 2.69E+05 1.04E+05 Y 91M 4.07E 01 0.00E+00 1.39E-02 0.00E+00 0.00E+00 2.79E+03 2.35E+03 Y 91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 Y 92 1.64E+01 0.00E+00 4.61E 01 0.00E+00 0.00E+00 2.45E+04 1.27E+05 Corwersion f actors are in inits of arem/yr per uCi/ cubic meter.
l UNT-005-014 Revision 3 Attachment 6.5 (10 of 12) l 1 1 177 l i
. __ _ - . . =-- _ - ~ . INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES Rj PATHWAY: lNMALATION AGE CRCUP: INFANT ( 2 0F 3 )
NUCLICE ORGAN 00SE CONVER$10N FACTORS BONE LIVER f. BODY THYROID 'KIONET LUNG GI-LLI Y-93 1.5CE+02 0.00E+00 4.07E+00 0.00E+00 0.00E+00 7.64E+04 1.67E+05 2R-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 ZR 97 1.50E+02 2.56E+01 1.17E+01 0.00E+00 2.59E+01 1.10E+05 1.40E+0$ NB 95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 MD-99 0.00E*00 1.65E*02 3.23E+01 0.00E+00 2.65E+02 1.35E+05 4.87E+04 TC-99M 1.40E-03 2,88E 03 3.72E 02 0.00E+00 3.11E 02 8.11E+02 2.03E+03 TC-101 6.51E 05 8.23E 05 8.12E 04 0.00E+00 9.79E 04 5.84E+02 8.44E+02 RU-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU-105 1.22E+00 0.00E+00 4.10E 01 0.00E+00 8.99E 01 1.57t+04 4.84E+04 RU 106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1. 64E +05 AG-110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE 125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE 127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE-127 2.23E+00 9.53E 01 4.89E-01 1.85E+00 4.86E+00 1.03E+04 2.44E+04 TE 129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 TE 129 7.88E-02 3.47E 02 1.88E 02 6.75E 02 1.75E 01 3.00E+03 2.63E+04 TE 131M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 TE 131 1.74E-02 8.22E 03 5.00E 03 1.58E 02 3.99E 02 2.06E+03 8.22E+03 TE 132 3.72E+02 2.37E+02 1.76t+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1 130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04- 0.00E+00 1.99E+03 I 131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 1 132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 0.00E+00 1.90E+03 1 133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 I-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 0.00E+00 1.29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.00E+00 1.83E+03 C5 134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 C5 136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7 13E+04 1.33E+03 CS-138 5.05E+02 7.81E+02 3.98E+02 0.00E+00 4.10E+02 6.54E+01 8.76E+02 EA*139 1.48E+00 9.84E-04 4.30E-02 0.00E+00 5.92E 04 5.95E+03 5.10E+04 Conversion f actors are in units of messe/yr per uCl/ cubic meter. 4
)
UNT-005-014 Revision 3 Attachment 6.5 (11 of 12) ! 178 I l l
INHALATION PATHWAY DOSES DUE TO * ' RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATNWAY: INHALATION AGE CROUP: INFANT ( 3 0F 3 ) NUCLIDE CROAN DOSE CONVERSION FACTORS BONE LIVER T.BCDY THYROID KIDNEY LUNG lil-LLI BA 140 BA 141 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 BA-142 1.57E 01 1.08E-04 4.97E-03 0.00E+00 6.50E 05 2.97E+03 4.75E+03 3.98E-02 3.30E-05 1.96E 03 0.00E+00 1.90 1.55E+03 6.93E+02
.........................................................E.05 LA 140 .......................
LA 142 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 8.48E+04 CE 141 1.03E+00 3.77E 01 9.04E-02 0.00E+00 0.00E+00 8.22E+03 5.95E+04 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.17E+05 2.16E+04
................................................... 5.25E+03 CE 143 CE-144 2.93E+02 1.93E+02 2.21E+01 0.00E+00 5.64E+01 1.16E+05 4. 97E+ 04 PR 143 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.3SE+05 9.84E+06 1.48E+05 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1 4.33E+05 . 3.72E+04
..................................................... 97E+03 PR-144 ..........................
NO 147 4.79E-02 1.85E 02 2.41E-03 0.00E+00 6.72E-03 1.61E+03 4.28E+03 W 187 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 1.30E+01 9.02E+00 3.12E+00 0.00E+00 0 3.96E+04 3.56E+04 WP 239
.......................... 00E+00 3.71E+02 3.32E+01 1.88E+01 0.00E+00 6.62E+01 5.95E+04 2.49E+04 Conversion factors are in units of sarem/yr per UCi/ cubic meter. ,
UNT-005-014 Revision 3 ~ Attachment 6.5 (12 of 12) 179
.1 I
I 1 i GROUND - PLANE DEPOSITION PATHWAY ! DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj ; { i PATHWAY: CROUND DEPOSil0N ACE CROUP: ALL ( 1 or 3 ) NUCL10E ORCAN DOSE CONVERSION FACTORS T. BODY SKIN H3 0.00E+00 0.00E+00 C 14 0.00E+00 0.00E+00 NA 24 1.19E+07 1.39E+07 P-32 0.00E+00 0.00E+00 CR 51 4.66E+06 5.51E+06 MW 54 1.39E+09 1.63E+09 NN-56 9.03E+05 1.07E+06 FE 55 0.00E+00 0.00E+00 FE $9 2.73E+08 3.21E+08 CO-58 3.795+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+0i 2N-65 7.47E+08 8.59E+08 ZW 69 0.00E+00 0.00E+00 sa 83 4.87t+03 7.08t+03 88 84 2.03E+05 2.36E+05 BR 85 0.00E+00 0.00E+00 R8 86 8.99E+06 1.03E+07 R8 88 3.31E+04 3.78E+04 RS 89 1.23E+05 1.48E+05 52 89 2.16E+04 2.51E+04 SR 90 0.00E+00 0.00E+00 SR 91 2.15E+05 2.51E+06 ' SR 92 7.77t+05 8.63E+05 Y-90 4.49E+03 5.31E+03 Y 91M 1.00E+05 1.1M *05 Y-91 1.07E+06 1.21E+06 Y 92 1.80E+05 2.14E+05 Conversion f actors are in units of square sorter-mreavyr per uti/sec. UNT-005-014 Revision 3 Attachment 6.6 (1 of 3) : 180 9
GROUND - PLANE DEPOSITION PATHWAY - DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: CROUND DEPOSTION ACE GROUP: ALL ( 2 OF 3 ) NUCLIDE ORGAN DOSE CONVEks!ON FACTORS T. STY SKIN Y-93 1.63E+05 2.51E+05 ZR 95 2.45E+08 2.84E+08 ZR 97 2.96E+06 3.44E+06 NS 95 1.37E+08 1.61E+08 MO-99 3.99E+06 4.63E+06 TC 99M 1.84E+05 2.11E+05 TC 101 2.04E+04 2.26E +04 RU-103 1.08E+08 1.26E+08 RU-105 6.36E+05 7.2tt+05 RU-106 4.22E+08 3.07E+08 AG 110M 3.44E+09 4.01E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.16E+04 1.08E+05 TE 127 2.98E+03 3.28E+03 TE-129M 1.98E+07 2.31E+07 TE-129 2.62E+04 3.10E+04 TE 131M 8.03E+06 9.46E+06 P TE 131 2.92E+04 3.45E+07 TE-132 4.23E+06 4.98E+06 1-130 5.51E+06 6.69E+06 I-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 1-135 2.53E+06 2.95E+06 CS-134 6.86E+09 8.00E+09 CS 136 1.51E+08 1.71E+08 CS 137 1.03E+10 1.20E+10 CS 138 3.59E+05 4.10E+05 8A 139 1.06E+05 1.19E+05 Conversion f actors are in units of square meter-erem/yr per uti/sec. 1 UNT-005-014 Revision 3 Attachment 6.6 (2 of 3) 181
1 _i GROUND - PLANE DEPOSITION PATHWAY , DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj , 4 1 1 PATHWAYr CROUND DEPOST10N ACE CROUPt ALL ( 3 0F 3 ) s i NUCLICE ORGAN DOSE CONVER$10N FACTORS '
?
- 7. SCDY SKlW r
$A 140 2.05E+07 2.35E+07 BA 141 4.17E+04 4.75E+04 i
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 ' CE 144 6.95E+07 8.04E+07 Pa*143 0.00E+00 0.00E+00 i PR 144 1.83E+03 2.11E+03 i ND 147 8.39E+06 1.01E+07 W-187 2.35E+06 2.73E*06 WP 239 1.71E+06 1.98E+06 Conversion factors are in units of square meter-mram/yr per uti/sec. 1 4 : i UNT-005-014 Revision 3 Attachment 6.6 (3 of 3)' t 182 l 2
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COW'S MILC (CONTANINATED FORACE) ACE CROUP: ADULT ( 1 0F 3 ) NUCL10E ORGAN DOSE CONVERSION FACTORS BONE LIVER f.BCCY THYR 0!D CIDNEY LUNG Cl*LLI H-3 0.00E+00 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 C 14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 NA-24 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 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 0.00E+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 MW 56 0.00E+00 4.15E-03 7.36E 04 6.00E+00 5.27E-03 0.00E400 1.32E 01 FE 55 2.51E+07 1.74E+07 4.05E+06 0.00E+00 0.00E+00 9.68E+06 9.95E+06 FE-59 2.97E+07 6.98E+07 2.68E+07 0.00E+00 0.00E+00 1.95E+07 2.33E+08 Co 58 0.00E+00 4.71E+06 1.0M+07 0.00E+00 0.00f+00 0.00E+00 9.55E+07 Co-60 0.00E+00 1.64E+07 3.62E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 NI-63 6.73E+09 4.66E+08 2.26E+08 0.00E+00 0.00E+00 0.00E+00 9.73E+07 NI-65 3.70E-01 4.81E 02 2.19E 02 0.00E+00 0.00E+00 0.00E+00 1.22E+00 CU-64 0.00E+00 2.38E+04 1.12E+04 0.00E+00 6.01E+04 0.00E+00 2.03E+06 2N 65 1.37E+09 4.37E+09 1.97E+09 0.00E+00 2.92E+09 0.00E+00 2.75E+09 ZW-69 2.09E 12 4.00E 12 2.78E 13 0.00E+00 2.60E 12 0.00E+00 6.01E-13 84 83 0.00E+00 0.00E+00 1.17E-02 0.00E+00 0.00E+00 0.00E+00 1.68E.02 BR-84 0.00E + 00 0.00E+00 1.93E 24 0.00E+00 0.00E+00 0.00E+00 1.52E-29 BR 85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8-86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.12E+08 Re-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-89 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR 89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.33E+08 SR 90 4.68E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E+09 SR 91 2.89E+04 0.00E+00 1.17E+03 0.00E+00 0.00E+00 0.00E+00 1.3tE+05 SR 92 4.8SE 01 0.00E+00 2.11E 02 0.00E+00 0.00E+00 0.00E+00 9.68E+00 Y-90 7.08E+01 0.00E+00 1.90E+00 0.00E+00 0.00E+00 0.00E+00 7.51E+05 Y-91M 5.98E-20 0.00E+00 2.32E 21 0.00E+00 0.00E+00 0.00E+00 1.76E 19 Y-91 8.59E+03 0.00E+00 2.30E+02 0.00E*00 0.00E+00 0.00E+00 4.73E+06 Y-92 5.58E-05 0.00E+00 1.63E 06 0.00E+00 0.00E+00 0.00E+00 9.77E-01 Conversion f actors are in units of seasre meter mrem /yr per uCl/sec for et t nuclides except M 3 which is in units of mram/yr per uCl/ cubic meter. UNT-005-014 Revision 3 Attachment 6.7 (1 of 12) 183
COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GA5ES, Rj PATNV.Y: COWS MILK (CONTAMINATED FORACE) AT' 6..JUP: ADULT ( 2 0F 3 ) nJCLIDE ORGAN 00SE CONVER$10N FACTORS BONE LIVER 1.BCDY THYR 010 K10NEY LUNG GI LLI Y 93 2.23E 01 0.00E+00 6.17E 03 0.00E+00 C.00E+00 0.00E+00 7.08E+03 ZR-95 9.43E+02 3.03E+02 2.05E+02 0.00E+00 4.75E+02 0.00E+00 9.59E+05 2R-97 4.33E 01 8.74E 02 4.00E-02 0.00E+00 1.32E-01 0.00E+00 2. 71E+04 NB-95 8.26E+04 4.59E+04 2.47E+04 0.00E+00 4.54E+04 0.00E+00 2.79E+08 MO-99 0.00E+00 2.48E+07 4.71E+06 0.00E+00 5.61E+07 0.00E+00 5.74E+07 TC-99M 3.32E+00 9.38E+00 1.20E+02 0.00E+00 1.43E+02 4.60E+00 5.55E+03 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-103 1.02E+03 0.00E+00 4.39E+02 0.00E+00 3.89E+03 0.00E+00 1.19E+0i RU 105 8.57E.04 0.00E+00 3.38E 04 0.00E+00 1.11E-02 0.00E+00 5.24E 01 RU 106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.94E+04 0.00E+00 1.32E+06 AG 110M 5.82E+07 5.39E+07 3.20E+07 0.00E+00 1.06E+08 0.00E+00 2.20E+10 TE 125M 1.63E+07 5.90E+06 2.18E+06 4.90E+06 6.63E+07 0.00E+00 6.50E+07 TE 127M 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 0.00E+00 1.54E+08 TE 127 6.53E+02 2.34E+02 1.41E+02 4.84E+02 2.66E+03 0.00E+00 5.15E+04 TE 129M 6.02E+07 2.2SE+07 9.53E+06 2.07E+07 2.51E+08 0.00E+00 3.03E+08 TE-129 2.82E 10 1.06E 10 6.88E 11 2.17E 10 1.19E-09 0.00E+00 2.13E 10 TE-131M 3.61E+05 1.77E+05 1.47E+05 2.80E+05 1.79E+06 0.00E+00 1.75E+07 TE 131 3.60E-33 1.51E 33 1.14E-33 2.96E 33 1.58E 32 0.00E+00 5.10E 34 TE 132 2.40E+06 1.55E+06 1.46E+06 1. 72E +06 1.50E+07 0.00E+00 7.35E+07 1 130 4.20E+05 1.24E+06 4.89E+05 1.0$E+08 1.93E+06 0.00E+00 1.07E+06 1 131 2.96E+08 4.23E+08 2.43E+08 1.39E+11 7.26E+08 0.00E+00 1.12E+08 1-132 1.64E-01 4.39E-01 1.54E 01 1.54E+01 7.00E 01 0.00E+00 8.25E-02 1-133 3.87E+06 6.73E+06 2.05E+06 9.89E+08 1.17E+07 0.00E+00 6.05E+06 I-134 2.02E 12 5.48E 12 1.96E 12 9.49E 11 8.71E 12 0.00E+00 4.77E 15 1 135 1.28E+04 3.36E+04 1.24E+04 2.22E+06 5.39E+04 0.00E+00 3.80E+04 CS-134 5.65E+09 1.35E+10 1.10E+10 0.00E+00 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.93E+07 1.18E+08 CS 137 7.38E+09 1.01E+10 6.61E+09 0.00E+00 3.43E+09 1.14E+09 1.95E+08 CS 138 9.04E 24 1.79E 23 8.85E 24 0.00E+00 1.31E 23 1.30E-24 7.62E 29 BA-139 4.42E 08 3.15E-11 1.29E-09 0.00E+00 2.94E*11 1.79E-11 7.84E 08 Conversion f actors are in mits of square reter-erem/yr per uti/sec for all nuclides except N 3 which is in mits of mrom/yr per uCI/ cubic reter. UNT-005-014 Revision 3 Attachment 6.7 (2 of 12) 184 . I
COW's MILK-PATHWAY DOSE FACTORS DUE TO ' RADIONUCLIDES OTHER THAN NOBLE GASES, Rj L PATHWAY: COW'S MILK (CONTAMINATED FORAGE) ACE CROUPt ADULT ( 3 0F 3 ) NUCL10E ORCAN DOSE CONVERSION Fact 0R$ SONE LIVER t.g:my THYR 0!D KIONEY LUNC Cl LLI BA*140 BA-141 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.93E+04 5.53E+07 8A 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 0.00
............................................................................E+00 LA-140 LA 142 4.51E+00 2.27E+00 6.01E 01 0.00E+00 0.00E+00 0.00E+00 1.67E+05 CE*141 1.86E 11. 8.45E-12 2.10E 12 0.00E+00 0.00E+00 0.00E+00 6.17E 08 4.84E+03 3.28t+03 3.72E+02 0.00E+00 1.52E+03 0.00E+00.1
......................................................................... 25E+07 CE.143 CE-144 4.16E+01 3.07E+04 3.40E+00 0.00E+00 1.35E+01 0.00E+00 1.15E+06 PR 143 3.58E+05 1.50E+05 1.92E+04 0.00E+00 8.87E+04 0.00E+00 ' 1.21E+08 1.58E+02 6.33E+01 7.83E+00 0.00E+00 3.66E+01 0.00E+00 6
......................................................................... 92E+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+00 W 187 9.42E+01 1.09E+02 6.51E+00 0.00E+00 6.36E+01 0.00E+00 5.22E+05 6.51E+03 5.45E+03 1.90E+03 0.00E+00 0.00E+00 0.00E+00 1.7B
............................................................................E+06 NP 239 4.60E+01 4.52E+00 2.49E+00 0.00E+00 1.41E+01 0.00E+00 9.27t+05 Conversion factors are in units of square meter erem/yr per uCl/sec for all nuctides except H+3 which is in tritte of mrom/yr per uCl/ctbic meter.
UNT-005-014 Revision 3 Attachment 6.7 (3 of 12) 185
1 1 l
. C0W's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COWis MILK (CONTAMINATED FORACE)
ACE CRG,lPt TEEN ( 1 0F 3 ) NUCL10E ORGAN DOSE CONVERSION FACTORS BONE LIVER T 800Y THIR010 K!0NEY LUNG Cl LLI H-3 0.00E+00 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 C-14 4.86E+08 9.72E+07 9. 72E +07 9.72E+07 9. 72E+07 9.72E+07 9.72E+07 NA 24 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 P 52 3.15E+10 1.95E+09 1.2?E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN 54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.18E+06 0.00E+00 2.87E+07 NN 56 0.00E+00 7.36E-03 1.31E-03 0.00E+00 9.31E 03 0.00E+00 4.84E 01 FE 55 4.45E+07 3.16E+07 7.36E+06 0.00E+00 0.00E+00 2.00E+07 1.37E+07 FE 59 5.18E+07 1.21E+08 4.67E+07 0.00E+00 0.00E+00 3.81E+07 2.86E+08 Co-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.09E+08 Co 60 0.00E+00 2.78E+07 6.26E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 NI 63 1.18E+10 8.35E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 NI 65 6.77E 01 8.65E 02 3.94E 02 0.00E+00 0.00E+00 0.00E+00 4.69E+00 CU 64 0.00E+00 4.25E+04 2.00E*04 0.00E+00 1.07E+05 0.00E+00 3.29E+06 ZN 65 2.11E+09 7.32E+09 3.41E+09 0.00E+00 4.68E+09 0.00E+00 3.10E+09 2N 69 3.85E 12 7.34E.12 5.13E 13 0.00E+00 4.79E 12 0.00E+00 1.35E-11 8R.83 0.00E+00 0.00E+00 2.15E 02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 84 84 0.00E+00 0.00E+00 3.45E 24 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+00 0.00E+00 0.00E+00 0.00E+00 R8 86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 RB-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8 89 0.00E+00 0.00E+00 0.00E+00 0.00L WO 0.00E+00 0.00E+00 0.00E+00 SR 89 2.67E+09 0.00E+00 7.66E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 SR 90 6.61E*10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 SR.91 5.31E+04 0.00E+00 2.11E+03 0.00E+00 0.00E+00 0.00E+00 2.41E+05 SR-92 8.94E-01 0.00E+00 3.81E 02 0.00E+00 0.00E +00 0.00E+00 2.28E+01 Y 90 1.30E+02 0.00E+00 3.51E+00 0.00E*00 0.00E+00 0.00E+00 1.07E+06 Y-91M 1.10E 19 0.00E+00 4.19E-21 0.00E+00 0.00E+00 0.00E+00 5.17E 18 Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 Y-92 1.03E-04 0.00E+00 2.98E-06 0.00E+00 0.00E+00 0.00E+00 2.83E+00 Conversion f actors are in mits of square meter mrem /yr per UCi/sec for ett nuclides except N 3 which is in mits of arem/yr per uCl/ctbic meter. UNT-005-014 Ilevision 3 Attachment 6.7 (4 of 12) 186
COW's MILK PATHWAY DOSE FACTORS DUE TO ' RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: CCW'S MILK (CONTAMINATED TORAGE) ACE GROUP: TEEN ( 2 of 3 ) WUCL10E ORGAN DOSE CONVER$!ON FACTORS BONE LIVER 7.StcY THYROID K!DNEY LUNG Ol*LLI Y 93 4.12E-01 0.00E+00 1.13E 02 0.00E+00 0.00E+00 0.00E+00 1.26E+04 ZR-95 ' 22-97 1.65E+03 5.20E+02 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 7.88E-01 1.56E-01 7.19E 02 0.00E+00 2.37E 01 0.00E+00 4.22E+04 NS-95 , MO 99 1.41E+05 7.81E+0/. 4.3GE+04 0.00E+00 7.57E+04 0.00E+00 3.34E+08 TC-99M 0.00E+00 4.47E+07 8.53E+06 0.00E+00 1.02E*08 0.00E+00 8.01E+07 - 5.76E+00 1.61E+01 2.08E+02 0.00E+00 2.39E+02 8.92E+00 1.05E+04 TC-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 20 105 1.81E+03 0.00E+00 7.74E+02 0.00E+00 6.38E+03 0.00E+00 1.51E+05 1.56E 03 0.00E+00 6.07E 04 0.00E+00 1.97E-02 0.00E+00 1.26E+00 RU 106 AG 110M 2.89E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 TE 125M 9.63E+07 9.11E+07 5.54E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 3.00E+07 1.08E+07 4.02E+06 8.39E+06 0.00E+00 0.00E+00 8.86E+07 TE-12/N , 1b127 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.10E+08 TE 129M 1.21E+03 4.29E+02 2.60E+02- 8.35E+02 4.90E+03 0.00E+00 9.34E+04 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 0.00E+00 4.1
.......................................................................... 3E+08 .....
TE 129 TE-131M 5.20E-10 1.94E 10 1.16E-10 3.71E-10 2.18E-09 0.00E+00 2.84E 09 TE-131 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.29E+06 0.00E+00 2.53E+07 6.58E 33 2.71E 33 2.06b33 5.07E 33 2.88E 32 0.00E+00 5.40 34
............................................................................E TE 132 1-130 4.29E+06 2.72E+06 2.56t+06 2.87E+06 2.61E+07 0.00E+00 8.61E+07 1-131 7.38E+05 2.14E+06 8.53E+05 1.74E+08 3.29E+06 0.00E+00 1.64E+06 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 0.00E+00 1.49E+08 1-132 1 133 2.91E 01 7.62E 01 2.74E 01 2.57E+01 1.20E+00 0.00E+00 3.32E-01 1-134 7.07E+M 1.20E+07 3.66E+06 1.67E+09 2.10E+07 0.00E+00 9.07E+06 3.58E 12 9.50E 12 3.41E 12 1.58E 10 1.50E 11 0.00E+00 1.25E 13 I 135 2.28E+04 5.87E+04 2.18E+04 3.78E+06 9.27E+04 0.00E+00 6.518t+04 CS 134 9.82E+09 2.31E+10 1.07E+10 0.00E+00 7.34E+09 2.80E+09 2.87E+08 C5 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 6.06t+09 2.35E+09 2.53E+08 CS 138 BA 139 1.64E 23 3.15E 23 1.57E 23 0.00E+00 2.33E 23 2.71E 24 1.43E 26 8.17E-08 5.75E-11 2.38E 09 0.00E+00 5.42E 11 3.96E 11 7.29E-07 Conversion factors are in units of square meter mrem /yr per uCI/sec for all nuclides except H-3 which is in units of arem/yr per uCl/ctbic meter.
UNT-005-014 Revision 3 Attachmerit 6.7 (5 of 12) 187
a l COW's MILK PATHWAY DOSE FACTORS DUE TO ' RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COW'S MILK (CONTAMINATED FORACE) ACE CRC 1JP TEEN ( 3 07 3 ) i NUCL10E ORGAN DOSE CONVERSION FACTORS BONE LIVER T.BCDY THYR 0!D K!0NEY LUNG GI-LLI BA.140 BA.141 4.85E+07 5.95E+04 3.13E+06 0.00E+00 2.02E+04 4.00E+04 7.48E+07 SA 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 0.00E+00 0.00E+00
..................................................... 00E+00 LA 140 ;
LA 142 8.10E+00 3.98E+00 1.06E+00 0.00E+00 0.00E+00 0.00E+00 2.29E+05
- CE-141 3.35E 11 1.49E 11 3.71E 12 0.00E+00 0.00E*00 0.00E+00 4.53E 07 8.8BE+03 5.93E+03 6.81E+02 0.00E+00 2 0.00E+00 1.70E+07
..................................................... 79t+03 CE-143 CE 144 7.64E+01 5.56E+04 6.21E+00 0.00E+00 2.49E+01 0.00E+00 1.67E+06 PR 143 6.58t+05 2.72E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6 0.00E+00 9.54E+05
..................................................... 73E+01 PR 144 ..........................
NO 147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W 187 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.11E+05 1.19E+04 9.71E+03 3.40E+03 0. Pf+00 0 0.00E+00 2.63E+06
..................................................... 00E+00 NPa239 8.78E+01 8.28E+00 4.60E+00 0.00E+00 2.60E+01 0.00E+00 1.33E+06 Conversion factors are in units of square meter erem/yr per uCf/see for ett nuclides except H 3 which is in mits of mrom/yr per uti/ cubic swter.
T 4 4 UNT-005-014 Revision 3 Attachment 6.7 (6 of 12) 188
COW's MILK PATHWAY DOSE FACTORS DUE TO . RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COW'S MILK (CONTAMINATED FORA 0E) ACE LROUP1 CHILD ( 1 0F 3 ) NUCL!OES ORGAN DOSE CONVERSION FACTORS BONE LIVER T 800Y THYRDIO E!0NEY LUNG 01 LL! N3 0.00E+00 1.57E+03 1. 57E+03 1.57E+ 03 1.57E+03 1. 57E+03 1.57E+03 C 14 1.19E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 NA-24 8.85E+06 8.85E+07 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 P 32 7.78E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 CR 51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.88E+06 0.00E+00 1.76E+07 MM-56 0.00E+00 1.28E-02 2.90E-03 0.00E+00 1.55E-02 0.00E+00 1.86E+00 FE-55 1.07E+08 5.93E+07 1.84E+07 0.00E+00 0.00E+00 3.35E+07 1.10E+07 FE-59 1.20E+08 1.95E+08 9.69E+07 0.00E+00 0.00E+00 5.64E+07 2.03E+08 Co-58 0.00E+00 1.21E+07 3.71E+07 0.00E+00 0.00E+00 0.00E+00 7.07E+07 00 60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 NI 63 2.96E+10 1.59E+09 1.04E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 65 1.66E+00 1.56E-01 9.10E-02 0.00E+00 0.00E+00 0.00E+00 1.91E+01 Cw 64 0.00E+00 7.4 6E+04 4.51E+04 0.00E+00 1.80E+05 0.00E+00 3.50E+06 ' 2N 65 4.13E+09 1.iDE+10 6.85E+09 0.00E+00 6.94E+09 0.00E+00 1.93E+09 ZN 69 9.47E-12 1.37E 11 1.26E 12 0.00E+00 8.30E 12 0.00E+00 8.62E 10 BR 83 0.0CE+00 0.00E+00 5.2SE-02 0.00E+00 0.00E+00 0.00E+06 0.00E+00 BR-84 0.00E+00 0.00E+00 7.81E-24 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+00 0.00E400 0.00E+00 0.00E+00 RB 86 0. 00E+00 8.77E+09 5.39E+09 0.00E+00 0.00E+00 0.00E+00 5.64E+08 R8-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RS-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 52 89 6.62E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.56E+08 SR 90 1.12E+11 0.00E+00 2.83E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 SR-91 1.30E+05 0.00E+00 4.92E+03 0.00E+00 0.00E+00 0.00E+00 2.88E+05 52-92 2.18E+00 0.00E+00 8.75E-02 0.00E+00 0.00E+00 0.00E+00 4.13E+01 I Y 90 3.22E+02 0.00E+00 8.62E+00 0.00E+00 0.00E+00 0.00E dn 9.17E+05 l i
.................................................................... ....... i I
Y-91M 2.68E 19 0.00E+00 9.74E 21 0.00E+00 0.00E+00 0.00E+00 .24E 16 i Y 91 3.90E+04 0.00E+00 1.04E+03 0.00E+00 0.00E+00 0.00E+00
- 80E+06 j Y 92 2.53E 04 0.00E+00 7.24E 06 0.00E+00 0.00E+00 0.00E+00 7.31E+00 Conversion factors are in units of square meter-mrem /yr per uCl/sec for all '
nuclides except M 3 which is in units of arem/yr per uC1/ctbic meter. i UN1-005-014 Revision 3 Attachment 6.7 (7 of-12) J 189 -l 1
.i 1
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COW'S MILK (CONTAMihATED FORACE) ACE CROUP: CN!LD ( 2 0F 3 ) NUCL10E$ ORMN DOSE CONVERSION FACTORS BONE LIVER T.800Y THYR 010 EIONEY LUNG Ol*LLI 1 Y 93 1.01E+00 0.00E+00 2.78E 02 0.00E+00 0.00E+00 0.00E+00 1.51E+04 2R 95 3.83E+03 8.42E+02 7.50E+02 0.00E+00 1.21E+03 0.00E+00 8.79E+05 2R-97 1.92E+00 2.77E-01 1.64E 01 0.00E+00 3.98E-01 0.00E+00 4.20E+04 NB 95 3.18E+05 1.24E+05 8.84E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+08 MO 99 0.00E+00 8.14E+07 2.01E+07 0.00E+00 1. 74E +08 0.00E+00 6.73E+07 TC-99M 1.32E+01 2.59E+01 4.29E+02 0.00E+00 3.76E+02 1.32E+01 1.47E+04 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 4.28E+03 0.00E+00 1.6: E+03 0.00E+00 1.08E+04 0.00E+00 1.11E+05 RU-105 3.82E 03 0.00E+00 1.39E 03 0.00E+00 3.36E 02 0.00E+00 2.49E+00 RU 106 9.24E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 A0 110N 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE.125M 7.385+07 2.00E+07 9.84E+06 2.0TE+07 0.00E+00 0.00E+00 7.12E+07 TE-127M TE 127 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 0.00E+00 1.68E+08 1E*129M 2.98E+03 8.02E+02 6.38E+02 2.06E+03 8.47E+03 0.00E+00 1.16t+05 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 0.00E+00
....................................................................... 3.31E+08 TE 129 1E-131M 1.28E-09 3.58E-10 3.04E 10 9.15E 10 3.75Ea09 0.00E+00 7.98E 08 TE-131 1.60E+06 5.53E+05 5.89E+05 1.14E+06 5.35E+06 0.00E+00 2.24E+07 1.62E 32 4.93E 33 4.81E-33 1.24E 32 4.89E*32 0.00E+00 8.49E-
............................................................................. 32 TE 132 1 130 1.02E+07 4.53E+06 5.48E+06 6.60E+06 4.21E+07 0.00E +00 4.57E+07 1 131 1.73E+06 3.49E+06 1.80E+06 3.84E+08 5.22E+06 0.00E+00 1.63E+06 1.30E+09 1.31E+09 7.45E+08 4.33E+11 2.15E+09 0.00E+00 1 I 132 17t+08 1 133 6.89E 01 1.27E+00 5.82E+01 5.87E+01 1.94E+00 0.00E+00 1.49E+00 l 134 1.72E+07 2.12E+07 8.03E+06 3.94E+09 3.54E+07 0.00E+00 8.56E+06 8.48E 12 1.58E 11 7.25E 12 3.62E-10 2.41E 11 0.00E+00 1.04E 1
...............................................................................1 1 135 C5 134 5.40E+04 9.72E+04 4.60E+04 8.61E+06 1.49E+05 0.00E+00 7.40E+04 C3 136 2.26E+10 3.72E+10 7.84E+09 0.00E+00~ 1.15E+10 4.13E+09 2.00E+08 1.01E+09 2.86E+09 1.80E+09 0.00E+00 1.48E+09 2.21E+08 9.77
............................................................................E+07 CS 137 CS-138 3.22E+10 3.09E+10 4.55E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08 8A 139 3.98E 23 5.53E-23 3.51E 23 0.00E+00 3.89E 23 4.19E 24 2.55E 23 2.01E.07 1.07E 10 5.82E 09 0.00E+00 9.36E 11 6.30E.11 1.16E-0
.............................................................................. 5 .
)
conversion factors are in units of square meter erem/yr per uCI/sec for ett ruclides except H 3 which is in units of mram/yr per ucl/ cubic meter. ) ~ UNT-00S-014 Revision 3 Attachment 6.7 (8 of 12) 190
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN_ NOBLE GASES, Rj PATHWAY: CCW'S MILK (CONTAMINATED FORACE) ACE CROUP: CHILD ( 3 0F 3 ) NUCLICES ORGAN 00SE CONVERSION 7 ACTORS BONE LIVER T.800Y THYR 010 K!0NEY LUNG GI 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 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 1.94E+01 6.78E+00 2.11E+00 0.00E+00 0.00E+00 0.00E+00 1.89E+05 CE 141 8.10E 11 2.58E.11 8.08E.12 0.00E+00 0.00E+00 0.00E+00 5.11E-06 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.78E+04 0.00E+00 1.36E+0
...............................................................................7 CE.143 CE.144 1.87F+02 1.02E+05 1.47E + 01 0.00E+00 4.26E+01 0.00E+00 1.49E+06 PR.143 1.62E+06 5.09E+05 8.66E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.1TE+02 0.00E+00 7.75E+05 PR 144 WD 147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00f+00 4.45E+02 3.60E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5. 70E+05 W 187 2.89E+04 1.71E+04 7.68E+03 0.00E+00 0.00E+00 0.00E+00 2.40E+0
.............................................................................. 6 NP-239 2.16t+02 1.55E+01 1.09E+01 0.00E+00 4.48E+01 0.00E+00 1.15E+06 Conversion factors are in units of square enter-mrom/yr per uCi/see for all nuclides except H 3 which is in units of mrem /yr per uCl/ cubic seter.
J i l l J l UNT-005-014 Revision 3 Attachment 6.7 (9 of 12) 1 191 ' i
.. = -
l 1 COW's MILK PATHWAY DOSE FACTORS DUE TO l RADIONUCLIDES OTHER THAN NOBLE GASES, Rj 1 PATHWAY COW'S MILK (CONTAMINATED FORACE) ACE GROUP: INFANT ( 1 0F 3 ) I NUCLICE orc,AN 003E CONVER$10N FACTOR $ BONE LIVER f. BODY THYROID K!DNEY LUNG GI.LLI H3 C 14 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 NA 24 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 1.54E+07 P-32 1.60E+11 9.43E+09 6.21E+09 0.00E+00 0.00E+00 0.00E+00 2.17E+09 CR 51 0.00E+C0 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN 54 0.00E+00 3.90E*07 8.84E+06 0.00E+00 8.64E+06 0.00E+00 1.43E+07 MM-56 FE*55 0.00E+00 3.14E.02 5.42E-03 0.00E+00 2.70E.02 0.00E+00 2.85E+00 1.35E+08 8. 73E+07 2.33E+07 0. 00E +00 0.00E+00 4.27E+07 1.11E+07 7E-59 2.24E+08 3.92E+08 1.54E+08 0.00E+00 0.00E+00 1.16E+08 1.87E+08 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 N1 63 0.00E+00 8.82E+07 2.08E+08 0.0DE+00 0.00E+00 0.00E+00 2.10E+08 3.49E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 NI.65 CU-64 3.50E+00 3.97E 01 1.80E 01 0.00E+00 0.00E+00 0.00E+00 3.02E+01 2N 65 0.00E+00 1.86E+05 8.59E+04 0.00E+00 3.14E+05 0.00E+00 3.81E+06 5.55E+09 1.90E+10 8.78E+09 0.00E+00 9.23E+09 0.00E+00 1.61E+
..............................................................................10 ZN-69 BR 83 2.02E 11 3.63E.11 2.70E.12 0.00E+00 1.51E.11 0.00E+00 2.96Ea09 84 84 0.00E+00 0.00E+00 1.12E.01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.51E-23 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 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.69E+08 RS-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
$2 89 1.26E+10 0.00E+00 3.61E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 st.90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 SR-91 2.72E+05 0.00E+00 9.83E*03 0.00E+00 0.00E+00 0.00E+00 3.21E+05 $
SR 92 4.64E+00 0.00E+00 1.72E-01 0.00E+00 0.00E+00 0.00E+00 5.00E+01 'I Y 90 6.81E+02 0.00E+00 1.83E+01 0.00E+00 0.00E+00 0.00E+00 9.41E+05 Y-91M 5.67E.19 0.00E+00 1.93E.20 0.00E+00 0.00E+00 0.00E+00 1.89E.15 1 Y 91 ' 7.33E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 ' 5.25E+06 Y.92 5.38E-04 0.00E+00 1.51E-05 0.00E+00 0.00E+00 0.00E+00 1.03E+01 Conversion factors are in units of square awter.arem/yr per UCl/see for all nuclides except N-3 which is In Lnits of mrem /yr per UCI/CLhlc meter. UNT-005-014 Revision 3 Attachment 6.7 (10 of 12) 192 i i
C0W's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: COW'S MILK (CONTAMINATED FORAGE) ACE Croup: INFANT ( 2 0F 3 ) NUCLICE ORCAN DOSE CONVERSION FACTORS BONE LIVER T.80DY THYR 0!D KIDNEY LUNG 0] LLI Y-93 l 2.16E+00 0.00E+00 5.87E-02 0.00E+00 0.00E+00 0.00E+00 1.70E+04 1 2R-95 6.80E+03 1.66E+03 1.18E+03 0.00E+00 1.79E*03 0.00E+00 8.26E+05 2R 97 4.06E+00 6.97E 01 3.18E 01 0.00E+00 7.03E 01 0.00E+00 4.45E+04 h8-95 5.93E+05 2.44E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.06E+08 MO-99 0.00E+00 2.08E+08 4.06E+07 0.00E+00 3.11E+08 0.00E+00 6.85E+07 TC 99M 2.75E+01 5.67E+01 7.30E+02 0.00E+00 6.10E+02 2.96E+01 1.65E+04 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 8.67E+03 0.00E+00 2.90E+03 0.00E+00 1.80E+04 0.00E+00 1.0$E+05 RU-105 8.05E-03 0.00E+00 2.71E-03 0.00E+00 5.92E 02 0.00E+00 3.20E+00 RU-106 1.90E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.44E+06 AG-110M 3.86E+08 2.82E+08 1.86E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE-125M 1.51E+08 5.04E+07 2.04E+07 5.07E+07 0.00E+00 0.00E+00 7.18E+C7 TE 12nt 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE 127 6.32E+03 2.12E+03 1.36E+03 5.14E+03 1.54E+04 0.00E+00 1.33E+05 TE 129M 5.57E+08 1.91E+08 8.58E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 TE 129 2.72E 09 9.37E 10 6.35E 10 2.28E-09 6.77E 09 0.00E+00 2.17E-07 TE-131M 3.38E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 0.00E+00 2.29E+07 TE 131 3.43E 32 1.27E-32 9.62E-33 3.06E 32 8.76E 32 0.00E+00 1.38E 30 TE 132 2.11E+07 1.04E+07 9.75E+06 1.54E+07 6.53E+07 0.00E+00 3.87E+07 1 130 3.55E+06 7.81E+06 3.13E+06 8.75E+08 8.58E+06 0.00E+00 1.67E+06 I-131 2.72E+09 3.20E+09 1.41E+09 1.05E+12 3.74E+09 0.00E+00 1.14E+08 t 1 132 1.43E+00 2.90E+00 1.03E+00 1.36E+02 3.24E+00 0.00E+00 2.35E+00 1 133 3.63E+07 5.28E+07 1.55E+07 9.60E+09 6.21E+07 0.00E+00 8.93E+06 1 134 1.76E-11 3.60E-11 1.28E 11 8.40E 10 4.03E 11 0.00E+00 3.73E 11 1-135 1.12E+05 2.23E*05 8.14E+04 2.00E+07 2.49E+05 0.00E+00 8.08E+04 CS-134 3.65E+10 6.80E+10 6.87E+09 0.00E+00 ' 1.75E+10 7.18E+09 1.85E+08 CS-136 1.98E+09 5.81E+09 2.17E+09 0.00E+00 2.32E+09 4.74E+08 8.82E+07 CS-137 5.15E+10 6.02E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.88E+08 CS 138 8.39E 23 1.36E 22 6.61E-23 0.00E+00 6.80E-23 1.06E 23 2.18E-22 BA 139 4.27E 07 2.83E 10 -1.24E 08 3.00E+00 1.7CE 10 1.72E 10 2.71E 05 Corwersion f actors are in mits of square meter-erem/yr per uCl/sec for all nuclides except M 3 which is in mits of aren/yr per uCi/cthic meter. UNT-005-014 Revision 3 Attachment 6.7 (11 of 12) 193 1
- - - - _= - -
i COW's MILK PATHWAY DOSE-FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj i i i PATHWAY COW'S MILK (CONTAMINATED FORAGE) ACE CROUP INFANT ( 3 0F 3 ) l NUCLICE ! ORGAN DOSE CONVERSION FACTORS BONE LIVER f.BCDY THYR 010 K!DNEY LUNG GI.LLI BA 140 2.41E+08 2.41E+05 1.24E+07 0.00E+00 5.72E+04 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 4.0$E+01 1.60E+0i 4.11E+00 0.00E+00 0.00E+00 0.00E+00 1.88E+05 LA-142 1.70E-10 6.24E 11 1.49E 11 0.00E+00 0.00E+00. 0.00E+00 1.06E 05 CE 141 4.34E+04 2.64E+04 3.11E+03 0.00E+00 8.15E+03 0.00E+00 1.37E+07 CE 143 3.97E+02 2.63E+05 3.00E+01 0.00E+00 7.67E+01 0.00E+00 1.54E+06 CE*144 2.33E+06 9.52E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.33E+08 PR 143 1.49E+03 5.55EE02 7.36E+01 0.00E+00 2.06E+02 0.00E+00 7.84E+05 PR-144 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 kD 147 8.81E+02 9.0SE+02 5.53E+01 0.00E+00 3.49E+02 0.00E+00 5.74E+05 W 187 6.08E+04 4.23E+04 1.46E+04 0.00E+00 0.00E+00 0.00E+00 2.48E+06 NP*239
~
4.57E+02 4.08E+01 2.31E+01 '0.00E+00 8.15E+01 0.00E+00 1.18E+06 Conversion factors are in tsilts of separe meter-erem/yr per uC1/sec for ett nuclides except N-3 which is in units of arem/yr per uCl/ ethic meter. 1 1 UNT-005-014 Revision 3 Attachment 6.7 (12 of 12) 194
l l L MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Ri l PATHWAY: MEAT (CONTAMINATED FORACE) ACE CROUP: ADULT ( 1 07 3 ) NUCLICE CACAN DOSE CONVERSION FACTORS j i SONE LIVER T . 83)Y THYROID KIONEY LUNO 01 LLI H3 0.00E+00 3.25E+02 3.25E+02 3.25E+02 3.25E+02 3.25E+02 3.25E+02 C-14 2.41E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 1 j NA 24 1.36E 03 1.36E 03 1.36E-03 1.36E-03 1.36E 03 1.36E-03 1.36E 03 l
................................................................................ l P 32 4.66E+09 2.90E+08 1.80E+08 0.00E+00 0.00E+00 0.00E+00 5.24E+08 CR-51 0.00E+00 0.00E+00 7.05E+0 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN 54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 NN 56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE 55 2.93E+08 2.03E+08 4.72E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 FE*59 2.66E+08 6.24E+08 2.39E+08 0.00E+00 0.00E*00 1.74E+08 2.08E+09 Co 58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.69E+08 Co-60 0.00E+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+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 0.00E+00 2.71E 07 1.27E 07 0.00E+00 6.84E 07 0.00E+00 2.31E-05 ZN-65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 2N 69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR 83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR 84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR 85 l 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8+86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.60E+07 R8 88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 sa 89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 j SR 90 1
1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.59E+08 } ER 91 1.521 10 0.00E+00 6.14E 12 0.00E+00 0.00E+00 0.00E+00 7.23E.10 5R 92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 90 1.08E+02 0.00E+00 2.89E+00 0.00E+00 0.00E+00 0.00E+00 1.14E+06 Y 91M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 91 1.13E+06 0.00E+00 3.03E+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 Corwersion factors are in units of square meter-mrem /yr per uCl/see for att nuclides except N 3 which is in units of meesvyr per uC1/ctbic meter. UNT-005-014 Revision 3 Attachment 6.8 (1 of 9) 195
l MEAT PATHWAY DOSE FACTORS DUE TO RAD 10NUtt. IDES OTHER THAN N0BLE GASES, Rj PATHWAY: MEAT (CONTAMINATED FORACE) i ACE CROUP: AOULT ( 2 0F 3 ) ( NUCLICE ORGAN 00$E CONVERSION FACTOR 5 1 80NE LIVER T. BODY THYRO!O K!DNEY LUNO Gl*LLI 1 Y-93 4.69E*12 0.00E+00 1.30E.13 0.00E+00 0.00E+00 0.00E+00 1.49E 07 t 2R 95 1,87E+06 6.01E+05 4.07E+05 0.00E+00 9.42E+05 0.00E+00 1.90E+09 I 24 97 2.07E-05 4.17E-06 1.91E-06 0.00E+00 6.30E.06 0.00E+00 1.29E+00 { NO 95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 MO-99 0.00E+00 1.00E+05 1.90E+04 0.00E+00 2.26t+05 0.00E+00 2.32E+05 TC 99M 4.45E 21 1.26E 20 1.60E 19 0.00E+00 1.91E.19 6.16E 21 7.44E 18 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.01E+08 0.00E+00 1.23E+10 RU 105 5.78E 28 0.00E*00 2.28E-28 0.00E+00 7.46E.27 0.00E+00 3.53E 25 RU 106 2.80E+09 0.00E+00 3.54E+08 0.00E+00 5.40E+09 0.00E+00 1.81E+11 AG 110M 6.68E+06 6.18E+06 3.6TE+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE 125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE 127M 1.12E*09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE 127 2.12E 10 7.62E 11 4.59E 11 1.57E 10 8.64E 10 0.00E+00 ' 1.67E*08 TE 129N 1.13E+09 4.23E+08 1.79E+08 3.90E+C8 4.73E+09 0.00E+00 5.71E+09 TE 129 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE 131M 4.51E+02 2.21E+02 1.84E+02 3.49E+02 2.23E+03 0.00E+00 2.19E+04 TE+131 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE 132 1.42E+06 9.18E+05 8.62E+05 1.01E+06 8.84E+06 0.00E+00 4.34E+07 l=130 2.11E-06 6.22E 06 2.45E 06 5.27E 04 9.71E 06 0.00E+00 5.35E 06 I 131 1.07E+07 1.54E+07 8.80E+06 5.03E+09 2.63E+07 0.00E+00 4.0$E+06 1 132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 1 133 3.65E 01 6.35E 01 1.94E 01 9.34E+01 1.11E+00 0.00E+00 5.71E 01 1 134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 135 4.43E.17 1.16E 16 4.28E 17 7.64E 15 1.86E 16 0.00E+00 1.31E*16 CS 134 6.58E+08 1.56E+09 1.28E+09 0.00E+00 5.06E+08 1.68E+08 2.74E+07 CS 136 1.21E+07 4.76E+07 3.43E+07 0.00E+00 2.65E+07 3.63E+06 5.41E+06
................................................................................ i l
CS 137 8.72E+08 1.19E+09 7.81E+08 0.00E+00 4.0$f+08 1.35E+08 2.31E*07 CS 138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SA 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 mits of square meter-mrom/yr per uCl/sec for all nuclides except M 3 which is in mits of eree/yr per uCi/ctbic meter. UNT-005-014 Revision 3 Attachment 6.8 (2 of 9) i 196 i i I
\
\
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES - OTHER THAN NOBLE GASES, Rj l PATHWAYt MEAT (CONTAMINATED FORAGE) ACE CROUP: ADULT ( 3 0F 3 ) NUCLICE ORGAN DOSE CONVERSION FACTORS BONE LIVER T.B0DY THYR 010 K10NEY LUNG 01-LLI i 8A 140 2.87E+07 3.61E+04 1.88E+06 0.00E+00 1.23E+04 2.07E+04 5.92E+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 3.71E 02 1.87E 02 4.94E 03 0.00E+00 0.00E+00 0.00E+00 1.37E+03 LA*142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE 141 1.40E+04 9.50E+03 1.08E+03 0.00E+00 4.41E+03 0.00E+00 3.63E+07 CE 1.3 2.01E 02 1.48E+01 1.64E 03 0.00E+00 6.53E 03 0.00E+00 5.55E+02 CE 144 1.46E+06 6.09E*05 7.13E+04 0.00E+00 3.61E+05 0.00E+00 4.93E+08 PR 143 2.10E+04 8.41E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.18E+07 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 7.07E+03 8.17E+03 4.89E*02 0.00E+00 4.78E+03 0.00E+00 3.92E+07 W-187 2.07E-02 1.73E 02 6.04E 03 0.00E+00 0.00E+00 0.00E+00 5.66E+00 NP.239 6.53E+02 6.42E+01 3.54E+01 0.00E+00 2.00E+02 0.00E+00 1.32E+07 Cornersion f actors are in mits of square meter mram/yr per uCI/sec for all nuclides except H-3 which is in units of mrem /yr per UCi/ cubic meter. I l l 1 UNT-005-014 Revision 3 Attachment 6.8 (3 of 9) 197 l l I
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: MEAT (CONTAMINAffD FORACE) ACE CROUP: T((N ( 1 0F 3 ) WUCLIDE ORGAN DOSE CONVER$10N f ACTOR $ BONE LIVER f.8CDY THVROID K!DNEY LUNG Cl LLI H3 0.00E+00 1.94E+02 1.94E+02 1.94E+02 1.94E+02 1.94E+02 1.94E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4. 08E+07 4.08E+07 NA 24 1.0BE 03 1.08E 03 1.08E-03 1.08E-Q3 1.08E 03 1.08E-03 1.08E 03 P 32 3.93E+09 2.44E+08 1.53E+08 0.00E+00 0.00E+00 0.00E+00 3.31E+08 CR-51 0.00E+00 0.00E+00 5.64E+03 3.13E+03 1.24E+03 8.05E+03 9.47E+05 MN-54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 MM 56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 fE-55 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.0TE+08 7.31E+07 FE 59 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56E+08 1.17E+09 CD 58 0.00E+0V 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 0.00E+00 0.00E+00 7.60E+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+0 J.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CU-64 0.00E+00 2.21E 07 1.04E 07 0.00E+00 5.60E-07 0.00E+00 1.72E 05 ZN-65 2.50E+08 8.69E+08 4.0$E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 ZN 69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR 83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 82 84 0.00E+00 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 84 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 4.07E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.02E+07 as 88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 sR-89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07
$R 90 8.05E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08
$4 91 1.28E 10 0.00E+00 5.08E 12 0.00E+00 0.00E+00 0.00E+00 5.79E 10 SR 92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 90 9.06E+01 0.00E+00 2.44E+00 0.00E+00 0.00E+00 0.00E+00 7.47E+05 Y 91M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 91 9.54E+05 0.00E+00 2.56E>04 0.00E+00 0.00E+00 0.00E+00 3.91E+08 .
Y 92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00G+00 0.00E+00 Conversion factors are in units of square meter area /yr per uti/sec for all nuclides except N 3 which is in trif ts of mrte/yr per uCl/ctbic sieter. UNT-005-014 Revision 3 Attachment 6.8 (4 of 9) 198
)
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj 4 PATHWAY 2 MEAT (CONTAMINATED FORACE) ACE GR3)P: TEEN ( 2 0F 3 ) NUCL!0E ORGAN DOSE CONVERSION FACTORS BONE LIVER f.83)Y THYRol0 KIONEY LUNG GI LLI Y-93 3.96E 12 0.00E+00 1.09E 13 0.00E+00 0.00E+00 0.00E+00 1.21E 07 22 95 1.50E+06 4.73E+05 3.25E*05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 2R 97 1.72E 05 3.41E 06 1. 57E -06 0.00E+00 5.17E 06 0.00E+00 9.23E-01 N8 95 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.65E+05 0.00E+00 4.26E+09 Mo-99 0.00E+00 8.27E+04 1.58E+04 0.00E+00 1.89E+05 0.00E+00 1.48E+05 TC 99M 3.53E-21 9.E6E 21 1.28E 19 0.00E+00 1.47E 19 5.47E-21 6.47E 18 TC-101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-103 8.57E+07 0.00E+00 3.66E+07 0.00E+00 3.02E+08 0.00E+00 7.16E+09 RU 105 4.83E-28 0.00E+00 1.87E*28 0.00E+00 6.09E 27 0.00E+00 3.90E 25 RU-106 1.82E*39 0.00E+00 2.97E+08 0.00E+00 4.55E+09 0.00E+00 1.13E+11 AG 110M 5.06E+06 4.79E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 TE 125M 3.03E+08 1.09E+08 4.0$E+07 8.47E*07 0.00E+00 0.00E+00 8.94E+08 TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 0.00E+00 2.35E+09 TE 127 1.80E 10 6.38E 11 3.88E 11 1.24E*10 7.29E 10 0.00E+00 1.39E 08 TE-129H 9.$0E+08 3.53E+08 1.50E+08 1.07E+08 3.97E+09 0.00E+00 3.57E+09 TE-129 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-131M 3.76E+02 1.80E+02 1.50E+02 2.71E+02 1.88E+03 0.00E+00 1.45E+04 TE 131 0.00E+00 0.00E+00 0.00E+00 0.002600 0.00E+00 0.00E+00 0.00E+00 TE-132 1.16E+06 7.36E+05 6.92E+05. 7.76E+05 7.06E+06 0.00E+00 2.33E+07 I 130 1.70E 06 4.91E 06 1.96E 06 4.00E 04 7.56E 06 0.00E+00 3.77E 06 I 131 8.92E+06 1.2SE+07 6.71E+06 3.65E+09 2.15E+07-0.00E+00 2.47E+06 1 132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I 133 3.05E 01 5.18E*01 1.58E 01 7.23E+01 9.09E 01 0.00E+00 3.92E 01 1 134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 135 3.60E-17 9.27E 17 3.44E.17 5.96E-15 1.46E 16 0.00E+00 1.03E 16 Cs 134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS 136 9.40E+06
- 3. 70E +07 2.48E+07 0.00E+00 2.01E+07 3.1TE+06 2.98E+06 CS 137 7.24E+08 9.63E+08 3.36E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07 CS 138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SA 139 0.00E+00 0.00E+00 0.00E#0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Conversion f actors are in mits of square meter-mrem /yr per uti/sec for all .
nuclides except N-3 which is in units of mram/yr per UCl/ cubic meter. UNT-005-014 Revision 3 Attachment 6.8 (5 of 9) 199 1
. MEAT PATHWAY DOSE FACT 0P,S DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rt PAINWAY: MEAT (CONTAMINATED FORACE)
ACE CROUP: TEEN ( 3 0F 3 ) NUCLIOE ORGAN DOSE CONVER$10N FACTORS BONE LIVER T.BCDY THYR 0!D K10NEY LUNG GI LLI SA 140 2.38E+07 2.91E+04 1.53E+06 0.00E+00 9.87E+03 1.96E+04 3.64E+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+uo 0.00E+00 0.00E+00 LA*140 3.05E 02 1.50E-02 3.99E-03 0.00E+00 05d+00 0.00E+00 8.61E+02 LA-142 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE 141 1.18E+04 7.87E+03 9.04E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 CE 143 1.69E.02 1.23E+01 1.37E 03 0.00E+00 5.51E 03 0.00E+00 3.69E+02 CE 144 1.23E+06 5.08E+05 6.60E+04 0.00E+00 3.04E+05 0.00E+00 3.09E+08 PR 143 1.76E+04 7.04E+03 8.78E+02 0.00E+00 4.09E+03 0.00E+00 5.80E+07 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 6.23E+03 6.77E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 W 187 1.73E 02 1.41E 02 4.95E.33 0.00E+00 0.00E+00 0.00E+00 3.82E+00 NP 239 5.70E+02 5.38E+01 2.99E+01 0.00E+00 1.69E+02 0.00E+00 8.65E+06 Corwersion f actors are in uilta of square meter-mrem /yr per uCI/sec for all 1 nuclides except H 3 which is in units of arevn/yr per uti/ ethic meter. UNT-005-014 Revision 3 Attachment 6.8 (6 of 9) 200
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MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHUAY: MEAT (CONTANINATED FORACE) ACE CROUP: CH]LD ( 1 0F 3 ) NUCL10ES ORGAN DOSE CONVERs!ON FACTORS BONE LIVER T .BC0Y THYROID K10NEY LUNG Cl LLI H3 C 14 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 3.83E+08 7.67E+07 7.67E+07 7.67E+07 7. 67E +07 7.67E+07 7.67E+07 NA 24 1.72E 03 1.72E-02 1.721-03 1.72E-03 1.72E 03 1.72E.03 1.
..........................................................................72E-03 P-32 CR 51 7.42E+09 3.47E+08 2.86t+08 0.00E+00 0.00E+00 0.00E+00 2.05E+08 MN-54 0.00E+00 0.00E+00 8.79E+03 4.88E+03 1.33E+03 8.91E+03 4.66E+05 0.00E*00 8.01E+06 2.13E+06 0.00E+00 2.25E+06 0.00E+00 6
......................................................................... 72E+06 MM-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 4.37E+08 2.42E+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 1.77E+08 6
......................................................................... 34E+08 C0 58 CO 60 0.00E+00 1.64E+07 5.02E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 NI.63 0.00E+00 6.93E+07 2.04E+D8 0.00E+00 0.00E+00 0.00E+00 3.84E+08 2.91E+10 1.56E+09 1.02E+09 0.00E+00 0.00E+00 0.00 1.05E+08
..................................................................E+00 N1 65 CU+64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IN 65 0.00E+00 2.97E 07 1.80E 07 ' O.00E+00 7.19E 07 0.00E+00 1.40E.05 3.75E+08 1.00E+09 6.22E+08 0.00E+00 6.30E+08 0.00E+00 1
......................................................................... 76E+08 2N 69 BR-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0
......................................................................... 00E+00 BR 85 Ra 86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RS-88 0.00E+00 5.77E+08 3.55E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07 0.00C+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 0.00E+00 0.00E+00 0.00E+00 SR 90 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40
............................................................................E+08 SR 91 54 92 2.40E 10 0.00E+00 9.0$E 12 0.00E+00 0.00E+00 0.00E+00 5.29E.10 Y 90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.71E+02 0.00E+00 4.59E+00 0.00E+00 0.00E+00 0.00E+00 4
......................................................................... 88E+05 T-91M Y 91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 92 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 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 mits of somre meter mrem /yr per uCf/sec for all nuclides except N 3 which is in units of arem/yr per uti/ cubic meter. UNT-005-014 Revision 3 Attachment 6.8 (7 of 9) 201
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAT: MEAT (CONTANINATED FORACE) ACE CRCUP: CHILO ( 2 0F 3 ) kUCLICES ORGAN DOSE CONVER$!ON FACTORS BONE L1VER 1.BCCY THYR 010 K!DNEY LUNO OI LLI Y 93 ZR 95 7.44E-12 0.00E+00 2.04E 13 0.00E+00 0.00E+00 0.00E+00 1.11E 07 ZR 97 2.66E+06 5.85E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 3.21E 05 4.63E 06 2.73E 06 0.00E+00 6.65E 06 0 7.02E 01
............................................................... 00E+00 NB 95 M0-99 3.10E+06 1.21E+06 8.62E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 TC 99M 0.00E+00 1.15E+05 2.84E+04 0.00E+00 2.46E+05 0.00E+00 9.51E+04 6.20E 21 1.22E 20 2.01E 19 0.00E+00 1.77E 19 6 6.91E 18
............................................................... 17E................
TC 101 21 RU-103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-105 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01E+09 9.02E-28 0.00E+00 3.2TE 28 0.00E+00 7.93E- 0.00E+00 5.88E 25 RU-106 27...................... AG-110M 4.44E+09 0.00E+00 5.54E+08 0.00E+00 5.99E+09 0.00E+00 6.90E+10 TE-121M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6. 74E+08 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00 0.00E+00 5.49E+08
.........................................E+00........................
TE-127M TE-127 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 0.00E+00 1.44E+09 TE-129M 3.39E-10 9.13E 11 7.26E 11 2.34E 10 9.63E 10 0.00E+00 1.32E 08 1.79E+09 5.00E+08 2.7BE+08 5.77E+08 5.26 0.00E+00 2.18E+09
........................................................E+09 ........................
TE 129 TE*131M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE*131 7.00E+02 2.42E+02 2.58E*02 4.98E+02 2.34E+03 0.00E+00 9.82E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 0.00E+00 0.00E+00
........................................................E+00 TE 132
(*133 2.12E+06 9.38E+05 1.13E+06 1.37E+06 8.71E+06 0.00E+00 9.45E+06 t 131 3.04E 06 6.13E*06 3.16E 06 6.76E 04 9.17E 06 0.00E+00 2.87E 06 1.65E+07 1.66E+07 9.46E+06 5.50E+09 2.73 0.00E+00 1.48E+06
........................................................E+07 1 132 1 133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 134 5.67E 01 7.021-01 2.6M-01 1.30E+02 1.17E+00 0.00E+00 2.83E 01 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00 0.00E+00 0.00E+00
........................................................E+00 1 135 ........................
CS 134 6.52E 17 1.17E 16 5.55E*17 1.04E.14 1.80E 16 0.00E+00 8.94E 17 CS-136 9.22E+08 1.51E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.16E+06 1.62E+07 4.58E+07 2.88E+07 0.00E+00 2.37 3.54E+06 1.57E+06
........................................................E+07 CS 137 CS 138 1.33E+09 1.2SE+09 1.88E+08 0.00E+00 4.16E+08 1.50E+08. 7.99E+06 SA-139 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 ........................
. Conversion f actors are in mits of square meter-eree/yr per uCl/sec for all ruclides except H 3 which is in units of aravyr per UCI/ ethic meter. UNT-005-014 Revision 3 Attachment 6.8 (8 of 9) 202
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES
- OTHER THAN NOBLE GASES, Rj PATWVAY: MEAT (CONTAMINATED FORAGE)
ACE CROUP: CHILD ( 3 0F 3 ) NUCLIDES ORGAN Dost CONVERSION FACTORS BONE LIVER T. BODY THYROID K!DNEY LUNC 01 LLI BA 140 4.38E+07 3.84E+04 2.56E+06 0.00E+00 1.25E+04 2.29E+04 2.22E+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 5.59E 02 1.95E 02 6.08E 03 0.00E+00 0.00E+00 0.00E+00 5.44E+02-LA 142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' CE 141 2.22E+04 1.11E+04 1.64E+03 0.00E+00 4.86E+04 0.00E+00 1.38E+07 CE-143 3.17E 02
- 1. 72E+01 2.49E 03 0.00E+00 7.21E 03 0.00E+00 2.52E+02 CE 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 3.60E+07 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 ,
1.17E+04 9.47E+03 7.33E+02 0.00E+00 5.19E+03 0.00E+00 1.50E+07 I W-187 3.21E 02 1.90E 02 8.53E-03 0.00E+00 0.00E+00 0.00E+00 2.67E+00 WP-239 1.07E+03 7.71E+01 5.42E+01 0.00E+00 2.23E+02 0.00E+00 5.70E+06 Conversion factors are in units of square meter-mrom/yr per uCi/sec for all nuclides except M 3 nahich is in istits of arem/yr per uCl/ ethic meter. 1 i l UNT-005-014 Revision 3 Attachment 6.8 (9 of 9)_ 203 i
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj ; I PATNWAY: LEAFY VECETABLES ADE CROUP ADULT ( 1 0F 3 ) NUCLIDE ORCAN DOSE CONVERSION FACTORS BONE LIVER f.800Y THYR 010 KIONEY LUNO 01 LLI M3 C 14 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 NA 24 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69 2.69E+05 2.69E+05
........................................................E+05 P-32 ........................
CR-51 1.40E+09 8.73E+07 5.43E+07 0.00E+00 0.00E+00 0.00E+00 1.58E+08 NN-54 0.00E+00 0.00E*00 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E*07 ' 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9 0.00E+00 9.59E+08
..................................................... 31E+07 ..........................
NN-56 FE 55 0.00E+00 1.59E+01 2.82E+00 0.00E+00 2.02E+01 0.00E+00 5.07Z+02 FE-59 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 ' 1.26E+08 2.96E+08 1.14E+08 0.00E+00 8.28E+07 9.88E*08
........... ....................................... 0.00E+00 ............................
CO 58 C0+60 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 N! 63 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 1.04E+10 7.2tt+08 3.49E+08 0.00E+ 0.00E+00 0.00E+00 1.50E+08
................................................00...............................
NI.65 CU 64 6.15E+01 7.99E+00 3.64E+00 0.00E+00 0.00E+00 0.00E+00 2.03E+02 Zu 65 0.00E+00 9.20E+03.4.32E+03 0.00E+00 2.32E+04 0.00E+00 7.84E+05 3.17t+08 1.01E+09 4.56E+08 0.00E+0 6.75E+08 0.00E+00 6.36E+08
.................................................0..............................
ZN 69 84 83 5.49E 06 1.0$E.05 7.31E.07 0.00E+00 6.83E 06 0.00E+00 1.58E 06 8R 64 0.00E+00 0.00E+00 3.11E+00 0.00E+00 0.00E+00 0.00E+00 4.47E+00 0.00E+00 0.00E+00 2.48E 11 0.00E+00 0.00E+00 1.94E 16
................................................... 0.00E+00 SR 85 ............................
R8 86 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RS 88 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.33E+07 0.00E+00 3.43E 22 1.82E 22 0.00E+00 0.00E+00 4.74E 33
................................................... 0.00E+00 ............................
R8 89 88 89 0.00E+00 3.89E 26 2.73E 26 0.00E+00 0.00E+00 0.00E+00 0.00E+00 52 90 9.97E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0 0.00E+00 1. 75E+10
..................................................... 00E+00 sA 91 ..........................
St-92 3.05E+05 0.00E+00 1.23E+04 0.00E+00 0.00E+00 0.00E+00 1.45E+06 Y 90 4.17E+02 0.00E+00 1.85E+01 0.00E+00 0.00E+00 0.00E+00 8.45E+03 1.33E+04 0.COE+00 3.57E+02 0.00E+00 0 0.00E+00 1.41E+08 Y 91M 00E+00 .......................... Y 91 5.221 09 0.00E*00 2.02E.10 0.00E+00 0.00E+00 0.00E+00 1.53E.08 Y 92 5.11E*06 0.0 & 00 1.37E+05 0.00E+00 0.00E*00 0.00E+00 2.81E+09 9.15E 01 0.00E+00 2.68E-02 0.00E+00 0 0.00E+00- 1.60E+04
..................................................... 00E+00 ..........................
Conversion f actors are in wilts of square meter-meenvyr per u:i/sec for att nuclides except M 3 which is in uilts of sirem/yr per uCi/ ethic sieter. UNT-005-014 Revision 3 Attachment 6.9-(1 of 9) 204 1
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATNWAY LEAFY VECETABLES ACE CR3JP: ADULT ( 2 0F 3 ) NUCLIDE ORGAN 00SE CONVER$10N FACTORS BONE LIVER T.BCDY THYR 010 K10NEY LUNG GI LLI Y-93 ZR 95 1.70E+02 0.00E+00 4.68E+00 0.00E+00 0.00E+00 0.00E+00 5.38E+06 ZR 97 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09 3.37E+02 6.81E+01 3.11E+01 0.00E+00 1.03E+0 0.00E+00 2.11E+07 ka-95 2 ..................... MO 99 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 TC 99M 0.00E+00 6.15E+06 1.17E+06 0.00E+00 1.39E+07 0.00E+00 1.43E+07 3.10E+00 8.77E+00 1.12E+02 0.00E+00 1.33E+0 4.30E+00 5.19E+03
.......................................................... 2.....................
TC 101 RU-103 8.22E 31 1.18E 30 1.16E 29 0.00E+00 2.13E-29 6.05E-31 0.00E+00 RU 105 4.TTE+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 5.57E+08 5.39E+01 0.00E+00 2.13E+01 0.00E+00 6.96E+0 0.00E+00 3.29E+04 RU 106 2 ..................... AG 110M 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 TE 125M 1.0$E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.9 0.00E+00 3.86E+08
...................................................... 3E+08 .........................
TE 127M TE 127 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 0.00E+00 1.17E+09 TE 129M 5.66E+03 2.03E+03 1.22E+03 4.19E+03 2.31E+04 0.00E+00 4.47E+05 2.51E+08 9.38E+07 3.98E+07 8.63E+07 1. 0.00E+00 1.27E+09
..................................................... 0$E+09 ..........................
1E 129 TE-131M 7.62E 04 2.87E.04 1.86E-04 5.85E-04 3.20E-03 'O.00E+00 5.75E-04 TE 131 9.12E+05 4.46E+05 3.72E+05 7.0M+05 4.52E+06 0.00E+00 4.43E+07 1.50E-15 6.27E 16 4.74E 16 1.23E 15 6.57 15 0.00E+00 2.13E 16
........................................................E TE 132 I-130 4.30E+06 2.78E+06 2.61E+06 3.07E+06 2.68E+07 0.00E+00 1.32E+08 I 131 3.92E+05 1.16E+06 4.57E+05 9.81E+07 1.81E+06 0.00E+00 9.96E+05 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98 0.00E+00 3.05E+07
........................................................E+08 1 132 1 133 5.76E+01 1.54E+02 5.39E+01 5.39E+03 2.45E+02 0.00E+00 2.89E+01 t 134 2.09E*06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 0.00E+00 3.26E+06 9.65E-05 2.62E 04 9.38E 05 4.54E 03 4.17E-04 2.29E-07 1 135 0.00E+00 ..................
CS 134 3.90E+04 1.02E+05 3.77E+04 6.73r+06 1.64E+05 0.00E+00 1.15E+05 C5 136 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 4.2TE+07 1.68E+08 1.21E+08 0.00E+00 9.38E+07 1.91E+07
..............................................................1.29E+07 Cs 137 6.36t+09 CS 138 8. 70E +09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BAa139 3.91E.11 7.73E 11 3.83E 11 0.00E+00 5.68E 11 5.61E.12 3.30E-16 2.86E-02 2.03E-05 8.36E-04 0.00E+00 1.90E 0 1.15E.05 5.07E-02
.......................................................... 5..................... .
Conversion factors are in units of square meter-mrem /yr per uCl/sec for all nuclides except H 3 which is in tnits of arem/yr per UCi/ctbic meter. UNT-005-014 Revision 3 Attachment 6.9 (2 of 9) 205
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: LEAFY VECETABLES ACE CROUP ADULT ( 3 0F 3 ) WUCLICE ORGAN DOSE CONVERSION FACTORS BONE LIVER I.800Y THYR 010 K10NEY LUNG GI LLI SA 140 1.2SE+08 1.61E+05 8.42E+06 0.00E+00 5.49E+04 9.24E+04 2.65E+08 BA-141 1.15E 21 8.70E 25 3.89E 23 0.00E+00 8.09E 25 4.94E.25 5.43E 31 84-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 LA-140 1.98E+03 9.97E+02 2.63E+02 0.00E+00 0.00E+00 0.00E+00 7.32E*07 LA-142 2.02E-04 9.19E*05 2.29E-05 0.00E+00 0.00E+00 0.00E+00 6.71E-01 CE 141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.19E+04 0.00E+00 5.10E+08 CE.143 CE-144 9.98E+02 7.38E+05 8.16E+01 0.00E+00 3.25E+02 0.30E+00 2.76E+07 PR 143 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 6.26E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00
.......................................................................2.74E+08 PR 144 ND-147 3.09E 26 1.28E 26 1.57E*27 0.00E+00 7.23E.27 0.00E+00 4.44E 33 V 187 3.33E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 3.80E+04 3.18E+04 1.11E+04 0.00E+00 0.00E+00 0.00E+00 1.04E+07 WP 239 9.54E+04 9.3BE+03 5.17E+03 0.00E+00 2.93E+04 0.00E+00 1.92E+09 Corwersion f actors are in mits of square meter mrom/yr per uCl/sec for all nuclides except 11-3 which is in units of mrom/yr per uCI/cteic meter.
l l j l l UNT-005-014 Revision 3 ! Attachment 6.9 (3 of 9) i 206 l I
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: LEAFY VECETABLES AGE CROUP: TEEN ( 1 0F 3 ) T NUCL10E ORGAN 00$E CONVERSION FACTORS BONE LIVER Y.83)Y THYR 010 KIONEY LUNG GI-LLI N3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 NA 24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 P 32 1.61E+09 9.97E+07 6.24E+07 0.00E+00 0.00E+00 0.00E+00 1.35E+08 CR 51 0.00E+00 0.00E+00 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04E+07 MN 54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 MW-56 0.00E+00 1.43E+01 2.55E+00 0.00E+00 1.81E+01 0.00E+00 9.44E+02 FE-55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.79E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.90E+08 CO 58 0.00E+00 4.36E+07 1.00E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 CO-60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 N!.63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 NI 65 5.72E+01 7.31E+00 3.33E+00 0.00E+00 0.00E+00 0.00E+00 3.97E+02 CU-64 0.00E+00 8.34E+03 3.92E+03 0.00E+00 2.11E+04 0.00E+00 6.47E+05 ZN-65 4.24E+08 1.47E+09 6.871+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 2N 69 5.15E 06 9.80E 06 6.86E 07 0.00E+00 6.41E 06 0.00E+00 1.81E 05 B2-83 0.00E+00 0.00E+00 2.91E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 84 84 0.00E+00 0.00E+00 2.25E 11 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+00 0.00E+00 0.00E+00 0.00E+00 28 86 0.00E+00 2.74E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 4.05E+07 as.88 0.00E+00 3.17E-22 1.69E 22 0.00E+00 0.00E+00 0.00E+00 2.71E 29 RS 89 0.00E+00 3.50E-26 2.47E 26 0.00E+00 0.00E+00 0.00E+00 5.36E-35 st 89 1.51E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09
$t-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 54-91 2.85E+05 0.00E+00 1.13E+04 0.00E+00 0.00E+00 0.00E+00 1.29E+06 l st 92 1.97E+02 0.00E+00 1.69E+01 0.00E+00 0.00E+00 0.00E+00 1.01E+04 {
Y-90 1.24E+04 0.00E*00 3.35E+02 0.00E+00 0.00E+00 0.00E+00 1.02E+08 i Y 91M ! 4.86E 09 0.00E+00 1.86E.10 0.00E+00 0.00E+00 0.00E+00 2.29E 07 Y*91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.21E+09 Y-92 8.60E 01 0.00E+00 2.49E-02 0.00E+00 0.00E+00 0.00E+00 2.36E+04 j l Conversion factors are in units of square meter mrom/yr per uCl/sec for all nuclides except N-3 which is in units of mrem /yr per ucl/ cubic meter. UNT-005-014 Revision 3 Attachment 6.9 (4 of 9) 207
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PAINWAY: LEAFY VECETABLES AGE CROUP: TEEN ( 2 0F 3 ) NUCL10E ORGAN DOSE CONVEtS10N FACTORS BONE LIVER T.800Y THYR 010 K10NEY LUNG Cl LLI Y 93 1.59E+02 0.00E+00 4.36E*00 0.00E+00 0.00E+00 0.00E+00 4.86E+06 2R-95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 2R 97 3.12E+02 6.18E+01 2.85E+01 0.00E+00 9.37E+01 0.00E+00 1.67E+07 NS 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 5.65E+06 1.08E+06 0.00E+00 1.29E+07 0.00E+00 1.01E+07 TC-99H 2.74E+00 7.63E*00 9.89E+01 0.00E+00 1.14E+02 4.24E+00 5.01E+03 TC-101 7.64E-31 1.09E 30 1.07E 29 0.00E+00 1.97E 29 6.62E-31 0.00E+00 RU-103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.40E+07 0.00E+00 5.70E+08 RU 105 5.00E+01 0.00E+00 1.94E+01 0.00E+00 6.31E+02 0.00E+00 4.04E+04 RU 106 2.38E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG-110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E +07 0.00E+00 4.03E+09 TE 125N 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 TE 127N 5.51E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE 127 5.34E+03 1.89E+03 1.15E+03 3.68E+03 2.16E+04 0.00E+00 4.12E+05 TE 129M 3.62E+0S - 1.34E+08 5.73E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 TE 129 i 7.14E-04 2.66E 04 1.59E 04 5.10E-04 3.00E 03 0.00E+00 3.90E 03 TE 131N 8.44E+05 4.05E+05 3.38E+05 6.09E+05 4.22E+06 0.00E+00 3.25E+07 TE 131 1.39E 15 5.75E 16 4.36E 16 1.07E 15 6.10E 15 0.00E+00 1.14E 16 TE-132 3.91E+06 2.47E+06 2.33E+06 2.61E+06 2.37E+07 0.00E+00 7.84E+07 I-130 3.51E+05 1.01E+06 4.0$E+05 8.28E+07 1.56E+06 .0.00E+00 7.80E+05 1 131 7.69E+07 1.08t+C8 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 1-132 5.19E+01 1.36E+02 4.88E+01 4.58E+03 2.14E+02 0.00E+00 5.92E+01 1 131 1.94E+06 3.29E*06 1.00E+06 4.59E+08 5.76E+06 0.00E+00 2.49E+06 1 134 . 8.73E 05 2.31E 04 8.31E 05 3.85E 03 3.65E 04 0.00E+00 3.05E 06
................................................................................ 4 i
I 135
!.52E+04 9.07E+04 3.36E+04 5.83E+06 1.43E+05 0.%E*D0 1.00E+05 CS 134 7 10E+09 1.67E+10 7.75E+09 0.00E+00 9.31r+09 2.03E*09 2.08E+08 Cs-136 .{
4.37E+07 1.72E+08 1.16E+08 0.00E+00 9.37E+07 1.4aE+07 1.38E+07 j CS 137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 CS 138 3.61E 11 6.93E 11 3.47E 11 0.00E+00 5.12E 11 5.96E 12 3.15E 14 EA 139 2.69E 02 1.89E 05 7.83E-04 0.00E+00 1.78E 05 1.30E 05 2.40E-01 Conversion factors are in units of square meter mrem /yr per uti/sec for all nuclides except M*3 which is in units of mrem /yr per UCl/ cubic meter. UNT-005-014 Revision 3 Attachment 6.9 (5 of 9) 208
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: LEAFY VECETABLES ACE CROUP: TEEN ( 3 0F 3 ) 1 WUCLIOE ORGAN DOSE CONVERSION FACTORS SONE LIVER T.SODY THYR 010 KIDNEY LUNG OI LLI BA 140 1.38E+08 1.6?E+05 8.90E+06 0.00E*00 5.74E+04 1.14E+05 2.13E+08 BA 141 1.08E-21 8.04E 25 3.59E 23 0.00E+30 7.46E 25 5.50E 25 2.29E 27 BA-142 0.00E+00 0.00E+00 0.00E+00 0.00E+(0 0.00E+00 0.00E+00 0.00E+00 LA.140 1.81E+03 8.88E+02 2.36E+02 0.00E+0il 0.00E+00 0.00E+00 5.10E+07 LA 142 1.85E 04 8.23E 05 2.05E 05 0.00E+00 0.00E+00. 0.00E+00 2.51E+00 CF 141 2.83E+05 1.89E+05 2.17E+04 0.00E+0C 8.89E+04 0.00E+00 5.40E+08 CE 143 9.33E+02 6.79E+05 7.58E+01 0.00E+0C 3.04E+02 0.00E+00 2.04E+07. CE 144 5.27E+07 2.18E+07 2.83E+06 0.00E+0C 1.30E+07 0.00E+00 1.33E+10 PR 143 7.00E+04 2.80E+04 3.49E+03 0.00E+0C 1.63E+04 ~ 0.00E+00 2.30E+08 PR 144 2.89E 26 1.18E 26 1.47E*27 0.00E+00 6.80E 27 0.00E+00 3.19E 29 No 147 3.62E+04 3.94E+04 2.36E+03 0.00E+ 01 2.31E+04 0.00E+00 1.42E+08 W 187 3.54E+04 2.88E*04 1.01E+04 0.00E+C0 0.00E+00 0.00E+00 7.80E+06 WP-239 1.60E+05 1.51E+04 8.38E+03 0.00E*00 4.74E+04 0.00E+00 2.43E+09 Corwersion f actors are in units of square meter arem/yr per uCl/see for att ' nuclides except N 3 which is in wilts of arem/yr per uCl/ctbic meter. UNT-005-014 Revision 3 Attachment 6.9 (6 of 9)
~
209
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATNWAY: LEAFY VEGETABLES ACE CROUPt CHILD ( 1 0F 3 ) NUCLICES ORGAN 000E CONVER$10N FACTORS BONE LIVER T .BCD Y THYR 010 K!ONEY LUNG GI-LLI M3 0.00E+00 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78t+08 1.78E+08 1.78E+08 1.78E+08 NA-24 3.73E+05 3.DE+06 3.D E+05 3.73E+05 3.73E+05 3.DE+05 3.73E+05 P-32 3.37E+09 1.58E+08 1.30E+08 0.00E+00 0.00E+00 0.00E+00 9.31E+07 CR 51 0.00E+00 0.00E+00 1.17E+05 6.50E+04 1. 78E +04 1 19E+05 6.21E+06 ' MW-54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 .00E+00 5.58t+08 MM-56 0.00E+00 1.88E+01 4.24E+00 0.00E+00 2.27E+01 0.00E+00 2.72E+03 FE-55 7.66E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE-59 3.98E*08 6.43E+08 3.20E+08 0.00E W0 0.00E+00 1.86E+08 6.70E+08 CD-58 0.002+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E +00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI 63 3.95E+10 2.11E+09 1.38E+09 0.00E+00 0.00E+00 0.00E+00 ' 1.42E+08 NI 65 1.05E+02 9.89E+00 5.77E+00 0.00E+00 0.00E+00 0.00E+00 1.21E+03 CU-64 0.00E+00 1.10E+04 6.64E+03 0.00E+00 2.66E+04 0.00E+00 5.16E+05 ZN-65 8.13E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 ZN 69 9.49E-06 1.37E 05 1.27E 06 0.00E+00 8.32E 06 0.00E+00 8.65E 04 8R 83 0.00E+00 0.00E+00 5.37E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR 84 0.00E+00 0.00E+00 3.82E 11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8R 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 4.52E+08 2.78E+08 0.00E+00 0.00E+00 0.00E+00 2.91E+07 R8 88 0.00E+00 4.3TE-22 3.04E 22 0.00E+00 0.00E+00 0.00E+00 2.15E 23 RB 89 0.00E+00 4.61E-26 4.10E 26 0.00E+00 0.00E+00 0.00E+00 4.02E 28 SR-89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR 90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 SR 91 5.24E+05 0.00E+00 1.98E+04 0.00E+00 0.00E+00 0.00E+00 1.16E+06 ' S4-92 7.28E+02 0.00E+00 2.92E+01 0.00E+00 0.00E+00 0.00E+00 1.38E+04 Y-90 2.31E+04 0.00E+00 6.18E+02 0.00E+00 0.00E+00 0.00E+00 6.57E+07 Y 91M 8.91E-09 0.00E+00 3.24E 10 0.00E+00 0.00E+00 0.00E+00 1.74E 05 Y 91 1.86E+07 0.00E+00 4.99E+05 0.00E+00 0.00E*00 0.00E+00 2.48E+09 Y 92 1.58E+00 0.00E+00 4.53E-02 0.00E+00 0.00E+00 0.00E+00 4.58E+04 Comersion f actors are in mits of square meter-mrem /yr per uCl/sec for all nuclides except H 3 which is in mits of mesm/yr per uCi/ cubic meter. UNT-005-014 Revision 3 Attachment 6.9 (7 of 9) I 210
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATNWAY: LEAFY VE0ETABLES ACE CROUP 2 CHILD ( 2 0F 3 ) NUCL10ES ORGAN DOC CONVER$10N FACTORS BONE LIVER 1.BCDY THYR 0!D CIDNEY LUNO 01-LLI Y-93 ZR-95 2.93E+02 0.00E+00 8.04E+00 0.00E+00 0.00E+00 0.00E+00 4.37E+06 ZR 97 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 5.70E+02 8.24E+01 4.86E+01 0.00E+00 1.18E+02 0.0 1.25E+07
................................................................ 0E+00 N8-95 MO 99 4.10E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 TC-99M 0.00E+00 7.71E+06 1.91E+06 0.00E+00 1.65E+07 0.00E+00 6.38E+06 4.71E+00 9.24E+00 1.53E+02 0.00E+00 1.34E+0 4.69E+00 5.26E+03
.......................................................... 2.....................
TC 101 RU-103 1.41E-30 1.47E-30 1.87E 29 0.00E+00 2.51E 29 7.78E 31 4.68E 30 RU 105 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 9.16E+01 0.00E+00 3.32E+01 0.00E+00 8.05E+0 0.00E+00 5.98E+04
.......................................................... 2.....................
RU 106 7.45E+08 0.00E+00 9.30E+07 AG 110M 0'.'00E+ 00 1.01E+09 0.00E+00 1.16E+10 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2,58E+09 TE 125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0 3.38E+08
............................................................... 00E+00 TE 127M TE 127 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE 129M 9.85E+03 2.65E+03 2.11E+03 6.81E+03 2.80E+04 0.00E+00 3.85E+05 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 1.03E+09
............................................................. 0.00E+00 TE 129 TE 131M 1.32E 03' 3.69E-04 3.14E-04 9.43E 04 3.87E 03 0.00E+C0 8.23E-02 TE-131 1.54E+06 5.33E+05 5.68E+05 1.10E+06 5.16E*06 0.00E+00 2.1U +07 2.57E-15 7.83E-16 7.64E 16 1.97E-15 7.77E 15 1.35E 14
............................................................. 0.00E+00..................
TE*132 7.00E+06 3.10E+06 l-130 3. 74E +06 4.51E+06 2.88E+07 0.00E+00 3.12E+07 1-131 6.16E+05 1.24E+06 6.41E+05 1.37E+08 1.86E+06 0.00E+00 5.82E+05 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 1.28E+07
..............................................................0.00E+00 1 132 1-133 9.22E+01 1.69E+02 7.79E+01 7.86E+03 2.59E+02 0.00E+00 1.99E+02 l 134 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 0.00E+00 1.76E+06 1.55E-04 2.88E 04 1.32E-04 6.62E 03 4.40E-04 1.91E-04 1-135 0.00E+00 CS 134 6.26E+04 1.13E+05 5.33E+04 9.97E+06 1.73E+05 0.00E+00 8.58E+04 CS-136 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 8.24E+07 2.33E+08 1.47t+08 0.00E+00 1.21E+08 1.80 7.96E+06
..................................................................E+07 CS 137 CS-138 2.39E+10 2.29E+10 3.38t+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 i M 139 6.57E 11 9.13E 11 5.79E 11 0.00E+00 6.43E-11 6.91E.12 4.21E-11 4.95E 02 2.64E 05 1.44E 03 0.00E+00 2.31E 05 1.56E-0 2.86E+00
.................................................................... 5........... .
Conversion factors are in mits of separe seter-mrem /yr per uti/sec for all nuclides except N 3 which is in mits of mram/yr per uC;/ cubic seter. UNT-005-014 Revision 3 . Attachment 6.9 (8 of 9) 211 I
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: LEAFY VECETABLES ACE CROUPt CHILD ( 3 0F 3 ) NUCL10ES ORGAN DOSE CONVER$!ON FACTOR $ BONE LIVER T.900T THYR 010 K!DWEY LUNO Cl LLI BA-140 2.77E+08 2.42E*05 1.61E+07 0.00E+00 7.89E+04 1.45E+05 1.40E+08 BA-141 1.99E 21 1.11E 24 6.47E 23 0.00E+00 9.62E 25 6.53E 24 1.13E 21 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 3.25E+03 1.13E+03 3.53E+02 0.00E+00 0.00E+00 0.00E+00 3.16E+07 LA 142 3.36E 04 1.07E 04 3.35E-05 0.00E+00 0.00E+00 0.00E+00 2.12E+01 CE 141 6.56E+05 3.27E+05 4.86E+04 0.00E+00 1.43E+06 0.00E+00 4.08E+08 CE-143 1.72E+03 9.31E+05 1.35E+02 0.00E+00 3.91E+02 0.00E+00 1.36E+07 CE 144 1.27E+08 3.98E+07 6.78E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 PR*143 1.46E+05 4.37E+04 7.23E+03 0.00E+00 2.37E+04 0.00E+00 1.57E +08 PR 144 5.37E 26 1.66E 26 2.70E 27 0.00E+00 8.79E 27 0.00E+00 3.58E 23 , NO-147 7.15E+04 5.79E+04 4.48E+03 0.00E+00 3.18E+04 0.00E+00 9.17E+07 W 187 6.43E+04 3.81E+04. 1.71E+04 0.00E+00 0.00E+00 0.00E+00 5.35E+06 WP 239 3.86E*05 2.77E+04 1.95E+04 0.00E+00 8.01E*04 0.00E+00 2.05E+09 Conversion factors are in units of square mter-mree/yr per uCl/see for at t nuclides except N 3 which is in tnits of mrom/yr per UCl/ cubic meter. l UNT-005-014 Revision 3 Attachment 6.9 (9 of 9) 212
GOAT's MILK PATHWAY DOSE FACTORS DUE TO . RADIONUCLIDES OTHER THAN NOBLE GASES, Ri PATHWAY: 00AT'S MILK (CONTAMINATED FORAGE) A0E GROUP: ADULT ( 1 0F 3 ) NUCLICE ORGAN DOSE CONVER$10N FACTORS BONE LIVER f . BODY THYROID K10NEY LUNO Ol LLI M3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C 14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.2TE+07 NA 24 2.93E+05 2.93E+05 2.93E+05 2.93E+05 2.93E+05 2.93E+05 2.93E+05 P-32 2.05E+10 1.28E+09 7.93E+08 0.00E+00 0.00E+00 0.00E+00 2.31E+09 CR-51 0.00E+00 0.00E+00 3.43E+03 2.0$E+03 7.55E+02 4.55E+03 8.62E+05 MN 54 0.00E+00 1.01E+06 1.93E+05 0. 00E+ 00 3.00E+05 0.00E+00 3.09E+06 NN-56 0.00E+00 4.9BE 04 8.84E-05 0.00E+00 6.32E 04 0.00E+00 1.59E 02 FE 55 3.26E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.29E+05 FE 59 3.86E+05 9.07E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.02E+06 Co 58 0.00E+00 5.66E605 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 Co-60 0.00E+00 1.97E+ D6 4.34E+04 0.00E+00 0.00E+00 0.00E+00 3.70E+07 N! 63 8.07E+08 5.60E *07 2.71E+07 0.00E + 00 0.00E+00 0.00E+00 1.1 TE+07 NI 65 4.44E 02 5.77E 03 2.63E 03 0.00E+00 0.00E+00 0.00E+00 1.46E-01 CU 64 0.00E+00 2.66E+03 1.25E+03 0.00E+00 6.70E+03 0.00E+00 2.26E+05 ZW 65 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.50E+08- 0.00E+00 3.30E+08 ZN 69 2.51E 13 4.80E 13 3.34E 14 0.00E+00 3.12E*13 0.00E+00 7.21E 14 BR 83 0.00E+00 0.00E+00 1.40E 03 0.00E+00 0.00E+00 0.00E+00 2.02E 03 BR 84 0.00E+00 0.00E+00 2.32E-25 0.00E+00 0.00E+00 0.00E+00 1.82E 30 84 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 3.11E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07-R8 88 0.00E+00 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 52 89 3.05E+09 0.00E+00 8.75E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 SR 90 ?.83E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09 52 91 6.07E+04 0.00E+00 2.45E+03 0.00E+00 0.00E+00 0.00E+00 2.89E+05 SR 92 1.03E+00 0.00E+00 4.44E 02 0.00E+00 0.00E+00 0.00E+00 2.03E+01 Y 90 8.50E+00 0.00E+00 2.28E 01 0.00E+00 0.00E+00 0.00E+00 9.01E+04 Y 91M 7.18E 21 0.00E+00 2.78E 22 0.00E+00 0.00E+00 0.00E+00 2.11E*20 Y 91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0,00E+00 5.67E+05 Y 92 6.69E 06 0.00E+00 1.96E 07 0.00E+00 0.00E+00 0.00E +00 1.1TE 01 Conversion factors are in units of square meter arem/yr per uCl/sec for sLL nuctides except M*3 which is in units of mrom/yr per UCl/ctble meter. UNT-005-014 Revision 3 Attachment 6.10 (1 of 12) - 213
GOAT's MILK PATHWAY DOSE FACTORS DUE TO . RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: C0AT'S MILK (CCNTAMINATED FORACE) AGE GROUP: ADULT ( 2 0F 3 ) NUCLICE ORGAN DOSE CONVER$!ON FACTORS BONE LIVER T .8C0Y THYR 010 K!ONEY LUND 01-LLI Y 93 2.68E 02 0.00E+00 7.40E 04 0.00E+00 0.00E+00 0.00E+00 8.50E+02 2R 95 1.13E+02 3.63E+01 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 22 97 5.20E 02 1.05E 02 4.80E-03 0.00E+00 1.58E-02 0.00E+00 3.25E+03 N8 95 9.91E+03 5.51E+03 2.96E+03 0.00E+00 5.45E+03 0.00E+00 3.34E+07 MO-99 0.00E+00 2.97E+06 5.66E+05 0.00E+00 6.73E+06 0.00E+00 6.89E+06 fC 99M 3.98E 01 1.13E+00 1.43E+01 0.00E*00 1.71E+01 5.52E 01 6.66E+02 TC-101 0.00E+00 0.00E+00 0.00E+00 0.00E>00 0.00E+00 0.00E+00 0.00E+00 RU-103 1.22E+02 0.00E+00 5.26E+01 0.00E+00 4.66E+02 0.00E+00 1.43E+04 RU-105 1.03E 04 0.00E+00 4.06E 05 0.00E+00 1.33E-03 0.00E+00 6.29E 02 RU-106 2.45E+03 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.58E+05 AG 110M 6.99E+06 6.46C+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE-125M 1.95E+06 7.08E+05 2.62E+05 5.8aE+05 7.95E+06 0.00E+00 7.80E+06 TE 127M 5.49E+06 1.96E+06 6.69E+05 1.40E+06 2.23E+07 0.00E+00 1.84E+07 TE 127 7.83E+01 2.81E+01 1.70E+01 5.80E+01 3.19E+02 0.00E+00 6.18E+03 TE-129M 7.22E+06 2.69E+06 1.14E+06 2.48E+06 3.02E+07 0.00E*00 3.64E+07 TE 129 3.39E 11 1.27E 11 8.25E 12 2.60E 11 1.42E-10 0.00E+00 2.56E 11 i TE-131M 4.33E+04 2.12E+04 1.77E+04 3.36t+04 2.15E+05 0.00E+00 2.10E+06 TE 131 4.32E 34 1.81E 34 1.37E 34 3.56E 34 1.89E-33 0.00E+00 6.12E-35 TE-132 2.SBE+05 1.86E+05 1.73E+05 2.06E+05 1.80E+06 0.00E+00 8.82E+06 I-130 5.04E+05 1.49E+06 5.87E+05 1.26E+08 2.32E+06 0.00E+00 1.2EE+06 I 131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.71E+08 0.00E+00 1.34E+08 1 132 1.97E-01 5.27E-01 1.84E.01 1.84E+01 8.40E-01 0.00E+00 9.90E 02 1-133 4.64E+06 8.08E+06 2.46E+06 1.19E+09 1.41E+07 0.00E+00 7.26E+06 1 134 2.42E 12 6.57E 12 2.35E 12 1.14E.10 1.05E 11 0.00E+00 5.73E 15 1 135 1.54E+04 4.03E+04 1.49E+04 2.66E+06 6.47E+04 0.00E+00 4.56E+C2 CS 134 1.70E+10 4.04E+10 3.30E+10 0.00E+00.1.31E+10 4.34E+09 7.06E+08 CS-136 7.90E+08 3.12E+09 2.24E+09 0.00E+00 1.73E+09 2.38E+08 3.54E+08 C5 137 2.21E+10 3.03E+10 1.98E+10 0.00E+00 1.03E+10 3.42E+09 5.86E+08 CS 138 2.71E 23 5.36E 23 2.65E-23 0.00E+00 3.94E 23 3.89E+24 2.29E 28 BA 139 5.30E-09 3.78E 12 1.55E 10 0.00E+00 3.53E 12 2.14E.12 9.40E-09 t Corwersion f actors are in mits of square seter-mram/yr per uti/sec f or at t nuclides except N 3 which is in mits of mram/yr per uCl/ctbic meter.
. UNT-005-014 Revision 3 Attachmant 6.10-(2 of 12) 214 ,
. - . = -- . -- ,
G0AT's MILK PATHWAY DOSE FACTORS DUE T0 . RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: GOAT'S MILK (CONTAMINATED FORAGE) ACE CROUP: ADULT ( 3 0F 3 ) NUCLICE ORGAN DOSE CONVERSION FACTORS BONE LIVER T.80DY TNTR010 KIONET LUNG GI-LLI BA-140 3.23E+06 4.05E+03 2.11E+05 0.00E+00 1.38E+03 ~ 2.32E+03 6.64E+06 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 5.41E 01 2.73E 01 7.21E 02. 0.00E+00. 0.00E+00 0.00E+00 2.00E+04 - LA-142 2.23E-12 1.01E 12 2.53E 13 0.00E+00 0.00E+00 0.00E+00 ~7.40E.09 CE 141 5.81E+02 3.93E+02 4.46E+01 0.00E+00 1.83E+02 0.00E+00 1.50E+06 CE 143 4.99E+00 3.69E+03 4.08E.01 0.00E+00 1.62E+00 0.00E+00 '1.38E+05 CE.144 4.29E+04 1.79E*04 2.30E+03 0.00E+00 1.06E+04 0.00E+00 1.45E+07 PR 143 1.89E+01 7.60E+00 9.39E 01 0.00E+00 4.39E+00 0.00E*00 8.30E+04 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 1.13E*01 1.31E+01 7.81E-01 0.00E+00 7.63E+00 0.00E+00 6.27E+04 W 187 7.82E+02 6.53E+02 2.28E+02 0.00E+00 0.00E +00 0.00E+00 2.14E+05 WP 239 5.52E+00 5.43E 01 2.99E 01 0.00E+00 1.69E+00 0.00E+00 1.11E+05 Conversion factors are in units of square meter.orem/yr per uCi/sec for all nLelfdes except H-3 elch is in units of arom/yr per uCl/ cubic sieter. i UNT-005-014 Revision 3 Attachment 6.10 (3 of 12: .
)
215 a l 1
.I
1 I
, G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj ;
l PATHWAY: COAT'S MILK (CONTAMINATED FORACE) ) Ar.E GROUP: TEEN ( 1 Of 3 ) I l NUCLIDE ORGAN 005E CONVERSION FACTORS I EONE LIVER t.80DY THYA0!O E!DNEY LUNG GI-LLI H3 0.00E+00 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9,72E+07 NA 24 5.11E+05 5.11E+05 5.11E+05 5.11E+05 5.11E+05 5.11E+05 5.11E+05 P 32 3.78E+10 2.34E+09 1.47E+09 0.00E+00 0.00E+00 0.00E+00 3.18E+09 CR 51 0.00E+00 0.00E*00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN 54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 MN-56 0.00E+00 8.83E 04 1.57E-04 0.00E+00 1.12E-03 0.00E+00 '5.81E 02 FE-55 5.79E+05 4.11E+05 9.57E+04 0.00E+00 0.00E+00 2.60E+05 1. 78t+05 FE-59 6.74E+05 1.57E +06 6.07E+05 0.00E+00 0.00E+ N 4.96E+05 3.72E+06 Co-58 0.00E+00 9.52E+05 2.19E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 CD 60 0.00E+00 3.34E*06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07
- NI 63 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.59E+07 NI.65 8.12E 02 1.04E-02 4.73E.03 0.00E+00 0.00E+00 0.00E+00 5.63E 01 CU-64 0.00E+00 4.73E+03 2.23E+03 0.00E+00 1.20E+04 0.00E+00 3.67E+05 ZN 65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 .
ZN 69 4.62E 13 8.80E 13 6.16E 14 0.00E+00 5.75E 13 0.00t+00 1.62E 12 BR 83 0.00E+00 0.00E+00 2.58E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8R-64 0.00E+00 0.00E+00 4.14E-25 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+00 0.00E+00 0.00E+00 0.00E+00 R8 86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+00 8.40E+07 RB 88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E +00 0.00E+00 0.00E+00 ~ RS 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
$R 89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 SR-90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09
$t-91 1.12E+05 0.00E+00 4.44E+03 0.00E+00 0.00E+00 0.00E+00 5.06E+05 5A 92 1.88E+00 0.00E+00 8.00E 02 0.00E+00 0.00E+00 0.00E+00 4.78E+01 Y 90 1.56E+01 0.00E+00 4.21E 01 0,00E+00 0.00E+00 0.00E*00 1.29E+05 Y-91M 1.31E 20 0.00E+00 5.02E 22 0.00E+00 0.00E+00 0.00E+00 6.21E 19 Y-91 1.90E+03 0.00E+00 5.08E+01 0.00E+00 0.00E+00 0.00E+00 7.77E+05 Y 92 1.24E 05 0.00E+00 3.58E 07 0.00E+00 0.00E+00 0.00E+00 3.39E 01 Conversion f actors are in units of sauere seter-wom/yr per uti/sec f or aL L ruclides except M 3 which is in taits of mrom/yr per UCl/ctbic meter.
l
. UNT-005-014 Revision 3 Attachment 6.10 (4 of 12) 216
GOAT's MILK PATHWAY DOSE FACTORS DUE TO - RADIONUCLIDES OTHER THAN N0BLE GASES, Rj PATHWAY: "dAges MILr (CONTAMINATED FORACE1 i ACE CROUPt TEEN ( 2 0F 3 ) NUCLIOE ORCAN DOSE CONVERSION FACTORS l BONE LIVER T.8C0Y TNYR0!D K!DNEY LUNG GI LLI Y-93 4.94E 02 0.00E+00 1.36E 03 0.00E+00 0.00E+00 0.00E+00 1.51E+03 2R 95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 2R 97 9.46E-02 1.87E 02 8.62E-03 0.00E+00 2.84E 02 0.00E+00 5.07E+03 NS 95 1.69E+04 9.37t+03 5.16E+03 0.00E+00 9.08E+03 0.00E+00 . 4.01E+07 Mo 99 0.00E+00 5.37E+06 1.02E+06 0.00E+00 1.23E+07 0.00E+00 9.61E+06 TC-99M 6.91E-01.1.93E+00 2.50E+01 0.00E+00 2.87E+01 1.07E+00 1.27E+03 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 2.17E+02 0.00E+00 9.29E+01. 0.00E+00 7.66E+02 0.00E+00 1.81E+04 RU 105 1.88E 04 0.00E+00 7.29E 05 0.00E+00 2.37E 03 0.00E+00 1.52E 01 RU 106 3.47E+03 0.00E+00 5.67E+02 0.00E+00 8.68E+03 0.00E+00 2.16E+05 AG.110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.08E+07 0.00E+00 3.07E+09 TE 125M 3.60E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 ' TE 127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.10E+07 0.00E+00 2.52E+07 TE 127 1.45E+02 5.15E+01 3.12E+01 1.00E+02 5.88E+02 0.00E+00. 1.12E*04 TE 129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 TE-129 6.24E 11 2.33E 11 1.39E 11 4.46E 11 2.62E*10 0.00E+00 3.41E 10 TE 131M
-7.88E+04 3.78E+04 3.15E+04 5.69E+04 3.94E+05 0.00E+00 3.03E+06 TE 131 7.90E 34 3.26E 34 2.47E 34 6.09E 34 3.45E-33 0.00E+00 6.49E 35 TE-132 5.15E+05 3.26E+05 3.07E+05 3.44E+05 3.13E+06 0.00E+00 1.03E+07 I 130 8.86E+05 2.56E+06 1.02E+06 2.09E+08 3.95E+06 0.00E+00 1.97E+06 1 131 6.45E+08 9.03E+08 4.85E+08 2.63E+11 1.55E+09 0.00E+00 1.79E+08 1 132 3.50E-01 9.15E-01 3.28E-01 3.08E+01 1.44E+00 0.00E+00 3.98E 01 1 133 8.48E+06 1.44E+07 4.39E+06 2.01E+09 2.52E+07 0.00E+00 1.09E+07 +
I 134 4.30E-12 1.14E 11 4.09E 12 1.90E 10 1.80E 11 0.00E+00 1.50E 13 1 135 2.74E+04 7.04E+04 2.61E+04 4.53E+06 1.11E+05 0.00E+00 7.81E+04 CS 134 2.94E+10 6.93E+10 3.22E*10 0.00E+00- 2.20E+10 8.41E+09 8.62E+08 CS-136 1.34E+09 5.29E+09 3.55E+09 0.00E+00 2.88E+09 4.54E+08 4.26E+08 CS-137 4.02E+10 5.54E*10 1.86E+10 0.00E+00 1.82E+10 7.06E+09 7.60E+08 Cs-138 4.92E-23 9.4%E 23 J.72E-23 0.00E+00 6.98E-23 8.12E-24 4.29E 26 BA 139 9.81E 09 6.90E 12 2.86E 10 0.00E+00 6.50E 12 4.75E-12 8.75E-08 Conversion f actors are in units of square seter-mrem /yr per uCl/sec for all . nuclides except N-3 which is in units of mram/yr per uCi/ctbic meter. UNT-005-014 Revision 3 Attachment 6.10 (5 of 12) - 217
. G0AT's MILX PATHWAY DOSE FACTORS OVE TO RADIONUCLIDES OTHER THAN N0BLE GASES, Ri j =
i i I l PATHWAY! GOAT'S MILK (CONTAMINATED FORACE) ACE GROUP: TEEN ( 3 0F 3 ) NUCLICE ORGAN 00SE CONVERSION TACTORS BONE LIVER 7.B@Y THYROID KIDNEY LUNG O!*LLI BA-140-5.82E+06 7.13E+03 3.75E+05 0.00E+00 2.42E+03 4.80E+03 8.98E+06 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 9.72E-01 4.78E.01 1.27E 01 0.00E+00 0.00E+00 0.00E+00 2.74E+04 LA 142 4.02E.12 1.79E-12 4.45E.13 0.00E+00 0.00E+00 0.00E+00 5.44E-08 CE*141 1.07E+03 7.12E+02 8.17E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06. CE-143 9.17E+00 6.67E+03 7.45E-01 0.00E+00 2.99E+00 0.00E+00 ~ 2.00E+05 CE-144 7.90E+04 3.27E+04 4.24E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR 143 3.48E+01 1.3?E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+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 2.17E+01 2.36t+01. 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.53E+04 W-187 1.43E+03 1.17E+03 4.08E+02 0.00E+00 0.00E+00 0.00E+00 3.15E+05 NP 239 1.03E+01 9.93E 01 5.52E-01 0.00E+00 3.12E+00 0.00E+00 1.60E+05 Conversion f actors are in units of square nieter-mrom/yr per uCl/sec for all nuclides except N-3 which is in tritts of mree/yr per uCf/ cubic meter. 4 UNT-005-914 -hevision 3 Attachment 6.10 (6 of 12) 218 ,
G0AT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: GOAT'S MILK (CONTAMINATED FORAGE) AGE GROUP: CHlLO ( 1 0F 3 ) WUCL10ES ORGAN DOSE CONVER$10N FACTORS BONE LIVER 7.BC0Y THYR 010 KIONEY LUNG GI-LLI H3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.2DE+03 C 14 1.19E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 NA 24 1.06E+06 1.06E+07 1.06E+06 1.06E+06 1.06E+06 1.06E+06 1.06E+06 P 32 9.33E+10 4.37E+09 3.60E+09 0.00E+00 0,00E+00 0.00E+00 2.58E+09 CR-51 0.00E+00 0.00E+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 NN-54 0.00E+00 2.52E+06 6.70E+05 0.00E+00 7.06E+05 0.00E+00 2.11E+06 NN 56 0.00E+00 1.54E-03 3.48E-04 0.00E+00 1.86E-03 0.00E+00 2.23E-01 FE 55 1.39E+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 *D.00E+00 7.33E+05 2.63E+06 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 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 NI 63 3.56E+09 1.90E+08 1.24E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 NI-65 1.99E 01 1.87E-02 1.09E 02 0.00E+00 0.00E+00 0.00E+00 2.29E+00 CU-64 0.00E+00 8.32E+03 5.02E+03 0.00E+00 2.01E+04 0.00E+00 3.90E+05 2W-65 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08
........................................j.......................................
ZN 69 1.14E 12 1.64E 12 1.52E 13 0.00E+00 9.96E 13 0.00E+00 1.03E 10 BR 83 0.00E+00 0.00E+00 6.34E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 81-84 0.00E+00 0.00E+00 9.37E 25 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+00 0.00E+00 0.00E+00 0.00E+00 Rs 86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77t+07 R8 88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ W 0.00E+00 R8-89 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 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 SR 91 2.74E+05 0.00E+00 1.03E+04 0.00E+00 0.00E+00 1.00E+00 6.04E+05 5R 92 4.58E+00 0.00E+00 1.84E 01 0.00E+00 0.00E+00 E.00E+00 8.68E+01 Y 90 3.87E*01 0.00E+00 1.03E+00 0.00E+00 0.00E+00 f'.00E+00 1.10E+05 Y-91M 3.21E-20 0.00E+00 1.17E 21 0.00E+00 0.00E+0fs 0.00E+00 6.29E 17 Y-91 4.68E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+0f, 0.00E+00 6.24E+05 Y 92 3.04E-05 0.00E+00 8.69E 07 0.00E+00 0.00E+00 0.00E+00 8.77E-01 Conversion f actors are in units of square meter-mrem /yr per uCl/sec for alt ' nuclides except N-3 which la in mits of arem/yr per uCl/ cubic meter. UNT-005- 014 Revision-3 Attachment 6.10 (? of 12) 219 l i
. GOAT's MILX PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj PATHWAY: 00AT'S MILE (COWTAMINATED FORACE) ACE CROUP: CHILD ( 2 OF 3 ) NUCLICES ORGAN 00SE COWVERSION FACTORS BONE LIVER T . 83)Y TNYR010 K!0NEY LUWG GI-LLI Y 93 1.21E 01 0.00E+00 3.33E-03 0.00E+00 0.00E+00 0.00E+00 1.81E+03 ZR-95 4.60E+02 1.01E+02 9.00E*01 0.00E+00 1.45E+02 0.00E+00 1.0$E+05 ZR-97 2.30E 01 3.33E 02 1.96E 02 0.00E+00 4.78E.02 0.00E+00 5.04E+03 kB-95 3.81E+04 1.49E+04 1.06E+04 0.00E +00 1.40E+04 0.00E+00 2.75E+07 MD 99 0.00E+00 9.76E+06 2.42E+06 0.00E+00 2.09E+07 0.00E+00 8.08E+06 TC 99M 1.59E+00 3.11E+00 5.15E+01 0.00E+00 4.52E+01 1.58E+00 1.77E+03 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 RU 105 4.58E-04 0.00E+00 1.66E-04 0.00E+00 4.03E-03 0.00E+00 2.99E 01 RU-106 1.11E+04 0.00E+00 1.38t+03 0.00E+00 1.50E+04 0.00E+00 1. 72E +0$ AG 110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE 125M 8.85E+06 2.40E+06 1.18E+06 2.48E+06 0.00E+00 0.00E+00 8.54E+06 TE 127M 2.503+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE 127 3.57E+02 9.63E+01 7.66E+01 2.47E+02 1.02E+03 0.00E+00- 1.40E+04 TE 129M 3.26E+07 9.09E+06 5.06E+06 1.05E+07 9.56E+07 0.00E+00 3.97E+07 TE 129 1.54E.10 4.30E-11 3.65E*11 1.10E 10 4.50E 10 0.00E+00 9.58E-09 TE 131M 1.92E+05 6.64E+04 7.06E+04 1.36E+05 6.42E+05 0.00E+00 2.69E+06 15-131 1.94E 33 5.91E 34 5.77E'34 1.48E-33 5.86E 33 0.00E+00 1.02E 32 TE 132 1.23E+06 5.44E+05 6.57E+05 7.93E+05 5.05E+06 0.00E+00 5.48E+06 I 130 2.07E+06 4.19E+06 2.16E+06 4.61E+08 6.26E+06 0.00E+00 1.96E+06 I 131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.58E+09 0.00E+00 1.40E+08 1 132 8.27E-01 1.52E+00 6.99E 01 7.05E+01 2.33E+00 0.00E+00 1.79E+00 1-133 2.06t+07 2.55E+07 9.64E+06 4.73E+09 4.25E+07 0.00E+00 1.03r+07 1-134 1.02E 11 1.89E*11 8.70E-12 4.35E 10 2.89E 11 0.00E+00 1.25E 11 1 135 6.48E+04 1.17t+05 5.52E+04 1.03E+07 1.79E+05 0.00E+00 8.88E+04 CS-134 6.79E+10 1.11E+11 2.35E+10 0.00E+00 3.45E+10 1.24E+10 6.01E+08 Cs-136 3.03E+09 8.58E+09 5.40E+09 0.00E+00 4.44E+09 6.63E+08 2.93E+08 CS 137 9.67E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 Cs 138 1.19E 22 1.ME 22 1.05E-22 0.00E+00 1.17E 22 1.26E-23 7.64E 23 BA 139 2.41E 08 1.29E 11 6.98E-10 0.00E*00 1.12E 11 7.57E-12 1.39E-06 Corwersion f actors are in mits of square meter-arem/yr per uct/sec for at t nuclides except M 3 which is in units of mrem /yr per uci/cteic meter. UNT-005-014 Revision 3 Attachment 6.10 (8 of 12) 220
G0AT's MILK-PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rj i PATWWAft C0AT'S NILK (CONTAMINATED FORAGE) AGE CROUP CHILO ( 3 0F 3 ) NUCL10ES ORCAW OOSE CONVERSION FACTORS BONE LIVER T. BODY THYR 010 K!DNEY LUNG GI-LLI BA 140 1.41E+07 1.23E+04 8.20E+05 0.00E+00 4.01E+03 7.34E+03 7.12E+06 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 2.33E+00 8.14E-01 2.54E-01 0.00E+00 0.00E+00 0.00E+00 2.27E+04 LA 142 9.72E 12 3.10E 12 9.70E 13 0.00E+00 0.00E+00 0.00E+00 6.14E-07 CE-141
?.62E+03 1.31E+03 1.94E+02 0.00E*00 5. 74E+03 0.00E+00 1.63E+06 CE 143 2.*d E+01 1.22E+04 1.771+00 0.00E+00 5.12E+00 0.00E+00 1.79E+05 CE-144 1.956+05 6.11E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 PR-143 -
8.62E+Li 2.59E+01 4.28E+00 0.00E+00 1.40E+01 0.00E*00 9.30E+04 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 5.33E+01 4.32E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 W 187 3.47E+03 2.03E+03 9.21E+02 0.00E+00 0.00E+00 0.00E+00 2.88E+05 NP 239 2.59E+01 1.86E+00 1.31E+00 0.00E+00 5.38E+00 0.00E+00 1.38E+05 Conversion f actors are in mits of square meter prenvyr per uC1/sec for att nuclides except H-3 which is in units of mram/yr per uti/ctbic meter. 1
^l l
l l 4 1 UNT-005-014 Revision 3 Attachment 6.10 (9 of 12) 221
G0AT's MILX PATHWAY DOSE FACTORS DUE TO I i RADIONUCLIDES OTHER THAN NOBLE GASES, Rj ' PATHWAY: GCAT'S MILK (CONTAMINATED FORAGE) ACE GROUP: INFANT ( 1 07 3 ) i NUCL10E ORGAN 00$E CONVER510N FACTORS BONE LIVER T.8 COY THYR 010 KIONEY LUNO Gl*LLI N-3 C 14 0.00E+00 4 E6t+03 4.86t+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 NA*24 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 I 1.85E+06 1.85E+06 1.85E+06 1.85E+06 1.85E+06 1.85E+061. '
.......................................................... .............. 85E+06 P 32 CR 51 1.92E+11 1.13E+10 7.46E+09 0.00E+00 0.00E+00 0.00E+00 2.60E+09 MU 54 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1
......................................................................... 72E+06 MN-56 FE 55 0.00E+00 3.77E 03 6.50E 04 0.00E+00 3.24E 03 0.00E+00 3.43E 01 FE-59 1.76E+06 1.13E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 2.92E+06 5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06
....................................................................... 2.43E+06 CO-58 CO-60 0.00E+00 2.91E*06 T.26E+06 0.00E+00 0.00E*00 0.00E+00 7.25E+06 N1 63 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 2.52E+07 4.19E+09 2.59E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00
........................................................................1.29E+07 N! 65 CU-64 4.21E 01 4.76E 02 2.17E 02 0.00E+00 0.00E+00 0.00E+00 3.62E+00 2N-65 0.00E+00 2.07E+04 9.57E +03 0.00E+00 3.50E+04 0.00E+00 4.24E+05 6.66E+08 2.28E+09 1.0$E+09 0.00E+00 1.11E+09 0.00 1.93E+09
..................................................................E+00 ZN 69 BR 83 2.42E 12 4.36E 12 3.24E 13 0.00E+00 1.81E 12 0.00E+00 3.55E 10 BR 84 0.00E+00 0.00E+00 1.34E 02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.81E 24 0.00E+00 0.00E+00 0.00E+00
....................................................................... 0.00E+00 BR 85 R8*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 2.67t+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 0.00E+00 l
..................................................................E+00 RB 89 5R 89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.64E+10 0.00E+00 7.58E+08 0.00E+00 0.00E+00 0,00E+00 5.43E+08 SR 90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00
....................................................................... 3.19E+09 SR-91
$R 92 5.70E+05 0.00E+00 2.06E+04 0.00E+00 0.00E+00 0.00E+00 6.75E+05 Y 90 9.75E+00 0.00E+00 3.62E 01 0.00E+00 0.00E+00 0.00E+00 1.0$E+02 B.17E+01 0.00E+00 2.19E+00 0.00E+00 0.00E+00 0.00E+00 1
......................................................................... 13E+05 Y-914 Y 91 6.81E-20 0.00E+00 2.32E 21 0.00E+00 0.00E+00 0.00E+00 2.27E-16 Y 92 8.79E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00-6.30E+05 6.45E 05 0.00E+00 1.81E.06 0.00E+00 0.00E+00 0.00E+00 1
......................................................................... 23E+00 ......
- Conersion f actors are in mits of square meter-prem/yr per uCl/sec for at t nuc' aides except H-3 which is in units of mree/yr per uti/ ethic meter.
UNT-005-014 Revision 3 Attachment 6.10 (10 of 12) 222 l
G0AT's MILK PATHWAY DOSE FACTORS DUE TO ~ RADIONUCLIDESOTHERTHANNOBLEGASES,Rh _ PATHWAY: GOAT'S MILK (CONTAMINATED FORACE) ACE CROUP INFANT ( 2 0F 3 ) l NUCLIDE
- ORGAN 00$E CONVERSION FACTORS ,I BONE LIVER T.800Y TNYR010 K!DNEY LUNG Gl*LLI T-93 2.59E-01 0.00E+00 7.05E 03 0.00E+00 0.00E+00 0.00E+00 2.04E+C3 2R 95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.14E+02 0.00E+00 9.91E+04 Z2 97 4.87E 01 8.37E 02 3.82E-02 0.00E+00 8.43E 02 0.00E+00 5.34E+03 N8 95 7.12E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 Mo*99 0.00E+00 2.50E+07 4.87E+06 0.00E+00 3.73E+07 0.00E+00 8.22E+06 YC-99M 3.30E+00 6.80E+00 8.76E+01 0.00E+00 7.32E+01 3.56E+00 1.98E+03 TC 101 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 1.04E+03 0.00E+00 3.48E+02 0.00E+00 2.17t+03 0.00E+00 1.2TE+04 RU-105 9.66E 04 0.00E+00 3.25E 04 0.00E+00 7.11E.03 0.00E +00 3.84E-01 RU 106 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG.110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.83E+07 0.00E+00 1.75E+09 TE 125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 TE 127M 5.05E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE 127 i 7.58E+02 2.54E+02 1.63E+02 6.17E+02 1.85E+03 0.00E+00 1.59E+04 TE*129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 TE 129 3.26E 10 1.12E*10 7.62E.11 2.73E 10 8.12E 10 0.00E+00 2.61E 08 TE*131M 4.0$E+05 1.63E+05 1.35E+05 3.31E+05 1.12E+06 0.00E+00 2.75E+06 TE 131 4.11E*33 1.52E 33 1.15E 33 3.67E 33 1.05E.32 0.00E+00 1.66E 31 TE.132 2.53E+06 1.25E+06 1.17E+06 1.85E+06 7.84E+06 0.00E+00 4.64E+06 I 130 4.26E+06 9.37E+06 3.76E+06 1.0$E+09 1.03E+07 0.00E+00 2.01E+06 1 131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 0.00E+00 1.37E+08 I 132 1.72E+00 3.48E+00 1.24E+00 1.63E+02 3.89E+00 0.00E+00 2.82E+00 I.133 4.35E+07 6.34E+07 1.86E+07 1.15E+10 7.45E+07 0.00E+00 1.07E+07 l 134 2.11E 11 4.33E 11 1.54E 11 1.01E 09 4.84E.11 0.00E+00 4.47E 11 I 135 1.35E+05 2.68E*05 9.77E+04 2.40E+07 2.99E+05 0.00E+00 9.70E+04 CS*134 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.25E+10 2.15E+10 5.54E+08 CS 136 5.93E+09 1.74E+10 6.51E+09 0.00E+00 6.95E+09 1.42E+09 2.65E+08 CS 137 1.54E*11 1.81E+11 1.28E+10' O.00E+00 4.85E+10 1.96E+10 5.65E+08 CS 138 2.52E 22 4.09E 22 1.98E 22 0.00E+00 '2.04E.22 3.19E 23. 6.54E*22 RA-139 5.13E.08 3.40E 11 1.48E 09 0.00E+00 2.04E 11 2.06E.11 3.25E.06 Cormrsion f actors are in mits of scpere meter-eree/yr per uCl/sec for all rumtides except M-3 which is in units of aren/yr per uct/ ethic meter.
UNT-005-014 Revision 3 Attachment 6.10 (11 of 12) 223
GOAT's MILK PATHWAY 00SE FACTORS DUE TO RADIONUCLIOES OTHER THAN N0BLE GASES, Rj PATHWAY: 00AT'S MILK (CONTAMINATED FORAGE) ACE GROUPt INFANT ( 3 0F 3 ) NUCLICE ORGAN 00SE CONVERSION FACTORS BONE LIVER T.BCDY THYR 010 K10NEY LUNG GI LLI 8A 140 2.89E+07 2.89E+04 1.49E+06 0.00E+00 6.87E+03 1.78E+04 7.10E+06 BA 141 0.00E+0'J 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 4.86E+00 1.92E+00 4.93E 01 0.00E+00 0.00E+00 0.00E+00' 2.25E+04 LA 142 2.04E 11 7.49E*12 1.79E 12 0.00E+00 0.00E+00 0.00E+00 1.27E-06 CE 141 5.20E+03 3.17E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE 143 4.76E+01 3.16E+04 3.60E+00 0.00E+00 9.20E+00 0.00E+00 1.84E+05 CE-144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 PR 143 1.78E+02 6.67E+01 8.84E+00 0.00E+00 2.48E+01 0.00E+00 9.41E+04 PR 144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NO 147 1.06E+02 1.09E+02 6.65E+00 0.00E+00 4.19E+01 0.00E+00 6.88E+04 W-187 7.30E+03 5.07E+03 1.75E+03 0.00E+00 0.00E+00 0.00E+00 2.98E+05 NP 239 5.48E+01 4.90E+00 2.77E+00 0.00E+00 9.77t+00 0.00E+00 1.42E+05 Conversion factors are in units of square meter erem/yr per uCl/sec for all nuetides except N 3 which is in units of arem/yr per uci/ cubic meter. i l UNT-005-014 Revision 3 Attachment 6.10 (12 of 12) i 224
LIQUID WASTE MANAGEMENT SYSTEM EFFLUENT SOURCES AND RELEASE PATHWAYS AND POINTS I SOURCES SYSTEWS setttast PatmeATS l AND Posets eastt emme starme ,,,,, ,, easts tasse evo cage tem e I
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LIOUID WASTE MANAGEMENT SYSTEM EFFLUENT SOURCES * ' S AND RELEASE PATHWAYS AND POINTS S t1TF8tS attfAst Fatsedats ans poIIPts e 0 fire.ttf tull8BNL 18ASTt non. .i.s Am. ygggg 1 a gm$tpl AL kalif $l*f 5 g
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GASEOUS EFFLUENT SOURCES, GASEOUS WASTE MAflAGEMEtiT SYSTEM EFFLUEtiT SOURCES AfiD EXHAUST RELEASE POINTS
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MAIN COMDEN1tB IVACUAttON O StaAtutt W SIFAAATCg a eter$. A Aas a e tvtt MAMotlWC SUlt9tWC ITEL StotACE toot. h l RADIAttog segtTops servrtinC c D AL. case a st: g SteeAct Anta, tvrt 1AULt. CASE Dtt08 j to r=Ats PM IRE-5107A m .lRE-51078 e 1 A8 EA g rygt RANDLluC SLDC EDSt IIRANS19. A AFB B m FAs i LDCAL g" EDST g (I t 'EttT) l e Uf1T-005-014 Revision 3 Attachment 6.12 (1 of 1) 227 -
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE LOCATION ANALYSIS FRE00ENCY VOLUME TLD A-2, B-1, C-1, D-2, E-1, TLDa Quarterly N/A F-2, G-2, H-2, J-2, K-1, L-1, M-1, N-1, P-1, Q-1, R-1, A-5, B-4, D-5, E-5 F-4, G-4, H-6, P-6, Q-5 R-6, F-9, G-9, E-15, J-15 E-30 Radiciodine and APP-1, APQ-1, APG-1, Gross beta, I-131 Weekly 285m3/wk Particulates APC-1, APE-30 y isotopic b Quarterly composite 3700m3/gr Ground Waterf GWK-1 y ISOTOPIC, H-3 Quarterly 4 liters Drinking Water c DWG-2, DWE-5d, DWP-7 H-3 Quarterly composite Homogeneous Gross beta,-y isotopic Monthly composite k 4 liters I-1319 Semi-monthly composite Surface Waterc SWG-2, SWE-5d , SWP-7 H-3 - Quarterly corposite Homogeneous y isotopic Monthly composite k 4 liters Shoreline Sediment SHWE-3, SHWK-1 y isotopic Semi-annually 2 Kilograms Milk MKQ-5, MKQ-45, MKQ-1 y isotopic, I-131 Semi-m'onthly/monthlyh 4 liters Fish FH-1, FH-2 y isotopic. In season or , 500 grams semi-annually 1 Food Products *FPP-1, FPG-1 y isotopic At harvest timed 500_ grams g Broad Leaf BLQ-1, BLB-1, BLK-15 - y isotopic, I-131 Monthly 500 grams-When milk samples not collected 0 Irrigated Food Pathway does not exist. However, food products grown within the site-boundary are sampled and analyzed. UNT-005-014 Revision 3 Attachment 6.13- (1 of 3) 228
- - - _s _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ - - _ _ _ _ . _ _ _ _ _ _ 't - ___u- _m - P v
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-(Continued)
- a. 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.
- b. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after i sampling to allow for radon and thoron daughter decay. _If gross beta activity in air particulate samples is~ !
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.
- c. Drinking Water and Surface Water samples are identical samples.
- d. The downstream sample is beyond the mixing zone.
- e. A composite sample will contain aliquots of sample taken proportional to the quantity of flowing liquid that results in a~ specimen representative of the liquid flow.
f. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas i where the hydraulic gradient or recharge properties are suitable for contamination.
- g. This analysis will be performed when the dose calculated for the consumption of water is greater than 1 mrem per year as calculated for maximum organ and age group.
- h. Milk will be collected semimonthly when animals are on pasture, monthly otherwise. If milk sampling is not performed, broad leafy vegetation will be sampled.
- i. Striped' mullet, gizzard shad, freshwater-drum, and catfish will be collected. If they are not available, substitute species will be collected and identified in reporting. .
i
'i UNT-005-014 Revision 3' '
- Attachment 6.13 (2 of 3)
! -229 i L . . t
m g . RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM (Continued)
- q.
J. 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. l k. An anaylsis frequency of Every 4 Weeks satisfies.this requirement. - The maximum frequency is monthly. 't 4 l UNT-005-014 Revision 3 ' Attachment 6.13 .(3 of- 3) i 230
. _ . . . . . _ _ _ , . . . . - .-, . . . _ - ., - _. u. ... . _
SAMPLE LOCATION TABLE-LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD) A-2 (Eastbank) Located on a utility pole on 1.1 N River Road (La. 628) at the south corner of the Zephrin L. Perriloux Fire Station (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 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-2 (Eastbank) Located approximately 0.3 miles 1.1 ENE east of Little Gypsy Power Station. Access from River Road (LA 628) near the west end of the Bonne Carre Spillway. TLD's are on the fence at the West entrance to the spillway (located on levee). UNT-005-014 Revision 3 Attachment 6.14 (1 of 11) 231
l i l 1 SAMPLE LOCATION TABLE (Continued) ; i LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION ; I E-1 (Westbank) located on utility pole along 0.2 E River Road (LA 18) approximately 0.3 miles east of Waterford 3 plant entrance. Access from LA 18. TLD's are on the third utility pole east of the construction entrance road. F-2 (Westbank) Located on fence enclosure 1.1 ESE surrounding the LP&L substation on LA 3142. 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 (Next to Union Carbide Star Plant Gate 3). Access from LA 3142 approximately 0.2 miles north of railroad overpass. H-2 (Westbank) located on fence enclosure 1.2 SSE to shell road off of LA 3142. Access from LA 3142 south of railroad overpass on east side of LA 3142. TLD's are on , the south side of the gate for shell road. , (Just south of Texaco pipeline station). k UNT-005-014 Revision 3 , Attachment 6.14-(2 of 11) 232
SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION > f J-2 (Westbank) located on northeast corner 1.3 S of fence enclosing Texaco valve station
-i 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 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 r i the Waterfc d I and 2 fuel oil storage tank l enclosure. Itccess is either thru LP&L Gate 92, Gate 97 off of LA 3127, the shell ' l access road from LA 18 between Waterford 3, f or thru the Waterford I and 2 access road. - N-1 (Westbank) located behind the "No Trespassing" 0.9 W sign off on Short Street, in Killona just - south of the Killona Elementary School. UNT-005-014 Revision 3 Attachment 6.14 (3 of 11) 4 233 L
SAMPLE LOCATION TABLE (Continued) i LOCATION LOCATION MILES FROM SECTOR . NUMBER DESCRIPTION PLANT DIRECTION , 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 I and 2 on River Road (LA 18). . R-1 (Westbank) Located 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 (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. . UNT-005-014 Revision 3 Attachment 6.14 (4 of 11) 234 i
i SAMPLE LOCATION TABLE (Continued) I LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION. D-5 (Eastbank) Located on fence gate on shell 4.2 ENE-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. J 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. to the dead end. TLD's are located on fence beside of the north substation gate. F-4 (Westbank) located on utility pole behind 3.5 ESE blonde brick house 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. Blondo brick house is second house on right (west) side of Aquarius St. heading south. G-4 (Westbank) Located on railroad 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 3 Attachment 6.14 (5 of 11) - 235
SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION . MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION H-6 (Westbank) located on a road 5.7 SSE sign on the Northwest side of the second 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. Q-5 (Westbank) located on fence 5.0 NW surrounding (green) river marker on levee just east of Edgard. Fence post is located along River Road (LA 18) across from the Webre's house. R-6 (Eastbank) Located on fence enclosing 5.3 NNW 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 at the entrance of the fence enclosure. F-9 (Eastbank) Located on entrance gate 8.2 ESE to Destrehan Substation. Access from 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 3 Attachment 6.14 (6 of 11) l 236
l SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION . MILES FROM SECTOR , NUMBER DESCRIPTION PLANT DIRECTION G-9 (Westbank) located on back fence of 8.1 SE LP&L District Office in Luling. Access via Ellington St. from either River Road (LA 18); or Second or Third S. from Paul Mallard Rd. (LA 52) to Ellington St. 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. J-15 (Westbank) Located on fence enclosure 12.0 S surrounding LP&L switchyard at LA 631/ Hwy 90 intersection in Des Allemands. , TLD's are on the northwest corner of fence. Access from LA 631 via shell road. ; E-30* (Westbank) located at LP&L General 27.0 E Office or Delaronde St. in Algiers. TLD's are on a tree in the courtyard at the south entrance to the building. l UNT-005-014 Revision 3 Attachment 6.14 (7 of 11) . 237
- . , - - - - r -=w i-,n< v , -
SAMPLE LOCATION TABLE (Continued) i i LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION . PLANT DIRECTION i Airborne j . APP-1 (Westbank) Located in soybean / sugarcane 0.8 WNW field at northwest corner of Short St. in Killona. ' t i APQ-1 (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 l Cooling Water Intake Structure fence enclosure. i APE-30* (Westbank) located on the roof of the 27.0 E I LP&L General Office building on ! Delaronde St. in Algiers, Eood 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. ! . UNT-005-014 Revision 3 Attachment 6.14 (8 of 11) 238
.-. .. ~ ~. - , - . - . -
SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION MILES FROM SECTOR' ;
.t NUMBER DESCRIPTION PLANT DIRECTION FPG-1 (Westbank) Lccated in field east of Water- 0.4 SE ford 3 near the Back-up Meteorological ;
Tower and air sample station APG-1. The crops grown alternate between ; soybeans and sugar-cane. Broad Leaf i 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. i BLK-15* (Westbank) located 3.5 miles SSW of 15.0 SSW ' Des Allemands on Hwy. 90. 1 Inaestion L Milk ' MKQ-5 (Westbank) Located at the Webre's house, 5.0 NW { just across LA 18 from river marker, at 'I the eastern end of Edgard. 1 UNT-005-014 Revision 3 Attachment 6.14-(9 of 11) - 239
.~ . _ _ - . .- - _ _ _ .. . ..
SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION MILES FROM -SECTOR - NUMBER DESCRIPTION PLANT DIRECTION MKQ-45* (Eastbank) Located off of I-12 in Denham 42 NW Springs. Take LA 3002 south of LA 1034 then right to LA 1032. Turn left and go to farm 1 mile on the right. ' MKQ-1 (Westbank) 1.0 miles west of Waterford 3 1.0 NW at the corner of River Road and Post Street in Killona. Fish FH-l* Upstream of the plant intake structure. N/A N/A FH-2 Downstream of the plant discharge structure. N/A 'N/A Waterborne GWK-1 (Westbank) located at 40 Arpent Canal 0.5 SSW south of the plant. Access from LA 3127 through LP&L Gate 92 which is at the Waterford-3 Training Center. The canal is northwest of the shell access road / railroad track intersection. DWG-2 (Westbank) located at the Uninn Carbide 2.0 SE SWG-2 drinking water canal. Access from LA 3142 through Gate 28. UNT-005-014 Revision 3 Attachment 6.14 (10 of 11) 240
SAMPLE LOCATION TABLE (Continuedl LOCATION LOCATION MILES FROM SECTOR
;1 UMBER DESCRIPTION PLANT DIRECTION 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 4 (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 4 N/A - Not Applicable for this sampling location. - UNT-005-014 Revision 3 Attachment 6.14 (11 of 11) 241
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e a c; SECTOR AND ZONE DESIGNATORS FOR RADIOLOGICAL SAMPLING AND MONITORING POINTS .
- SECTOR NOMENCLATURE ZONE NOMENCLATURE CENTERLINE OF SECTOR IN DEGREES TRUE NORTH 22 1/2 MILES FROM FROM FACILITY SECTOR FACILITY ZONE i 0 & 360 *A N 0-1 1 22 1/2- B NNE 1-2 2 45 C NE 2-3 3 67 1/2 D ENE 3-4 4 i 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 H 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 's 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 1 mile. Area G-4 would be that area between 123 3/4 to'146k degrees and the 3- and 4-mile' arcs from the facility. For Airborne, Ingestion (milk), l and Food Products pathways, the' sector designator will be preceded by acronyms AP, MK, and FP, respectively. , o 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 3 Attachment 6.15 (1 of 1) 242
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REMP SAMPLING LOCATIONS WITHIN 50 MILES OF WATERFORD 3 ( t 1 I
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SPECIFICATION CROSS REFERENCE TABLE , Specification Methodology. Section Reouirement Section 5.3.1 Liquid Effluent Concentration 5.3.5 &-5.3.6 5.3.2 Dose due to Liquid Effluents 5.344 5.3.3 Dose Projections for Liquid Releases 5.3.7
- 5.4.1 Dose Rate Due to Noble Gases 5.4.5 & 5.4.8 5.4.1 Dose Rate Due to Iodine, Tritum 5.4.5 & 5.4.8 And Particulates with Half Lives Greater than Eight Days 5.4.2 Air Doses due to Noble Gases 5.4.6 5.4.3 Doses Due to lodines, Tritium 5.4.7 and Particulates with Half-Lives Greater than Eight Days.
5.4.4 Dose Projections for Gaseous Releases 5.4.9 i 5.5.1 Total Dose 5.5.2 5.6.1 Radioactive Liquid Effluent' Monitoring 5.3.5 , Channels Alarm / Trip Setpoints j 5.6.2 Radioactive Gaseous Effluent 5.4.8 ' Monitoring Channels Alarm / Trip Setpoints > 5.8.1 Radiological Environmental. 5.8.4-Monitoring Program 5.8.2 Interlaboratory Comparison Program 5.8.5 5.8.3 Land Use Census 5.8.3 o
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. UNT-005-014 Revision 3 Attachment 6.19 (1 of 1) 246 j 1
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TECHNICAL SPECIFICATION CROSS REFERENCE TABLE Specification Methodology Section Re_quirement Section 5.3.1 Liquid Effluent Concentration 3.11.1.1, 4.11.1.1.1, 4.11.1.1.2 5.3.2 Dose due to Liquid Effluents 3.11.1.2 & 4.11.1.2 5.3.3 Dose Projections for Liquid Releases 3.11.1.3, 4.11.1.3.1 & 4.11.1.3.2 5.4.1 Dose Rate Due to Noble Gases 3.11.2.1, 4.11.2.1.1, 4.11.2.1.2 & 4.11.2.1.3 5.4.1 Dose Rate Due to Iodine, Tritum 3.11.2.1, And Particulates with Half Lives 4.11.2.1.1, Greater than Eight Days 4.11.2.1.2 & 4.11.2.1.3 5.4.2 Air Doses due to Noble Gases 3.11.2.2 & 4.11.2.2 5.4.3 Doses Due to lodines, Tritium 3.11.2.3 & and Particulates with Half-Lives 4.11.2.3 Greater than Eight Days. 5.4.4 Dose Projections for Gaseous 3.11.2.4, Releases 4.11.2.4.1 & 4.11.2.4.2 UNT-005-014 Revision 3 Attachment 6.20 (1 of 2) 247
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l 1 TECHNICAL SPECIFICATION CROSS REFERENCE TABLE i Specification Methodology
- Section Reauirement Section I
- 5.5.1 Total Dose 3.11.4, 4.11.4.1 &
4.11.4.2 5.8.1 Radiological Environmental 3.12.1 & 4.12.1 Monitoring Program i 5.8.2 Interlaboratory Comparison Program 3.12.3 & 4.12.3 5.8.3 Land Use Census 3.12.2 & 4.12.2 5.6.1 Radioactive Liquid Effluent 3.3.3.10 & Monitoring Channels 4.3.3.10 Alarm / Trip Setpoints 5.6.2 Radioactive Gaseous Effluent 3.3.3.11 & Monitoring Channels Alarm / Trip 4.3.3.11 Setpoints 1 i t U s i UNT-005-014 Revision 3 . Attachment 6.20 (2 of-2) 248
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SPECIFIC FACTORS USED TO DETERMINE Aj and Rj VALUES FOR THE 0FFSITE DOSE CALCULATION MANUAL Values for Aj and Rj 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.
- Stable element transfer coefficients for vegetation, cow's milk, and meat were obtained from Regulatory Guide 1.109 Table E-1.
. Stable element transfer coefficients for goat's milk were obtained from Regulatory Guide 1.109 Table E-2. . Animal consumption rates were obtained from Regulatory Guide 1.109 Table E-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.
- External dose factors for standing on contaminated ground were obtained from Regulatory Guide 1.109 Table E-6.
. + 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.
. Other factors used were obtained from Regulatory Guide 1.109 Table E-15 for- l various parameters.
- Bioaccumulation factors for freshwater and saltwater vertebrates and invertebrates are listed on the following page.
s UNT-005-014 Revision 3 Attachment 6.21 (1 of 2) 249 1
. _ . _ , _- . ~
SPLCIFIC FACTORS USED TO DETERMINE Aj and Rj VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL 1 B10 ACCUMULATION FACTORS FOR VARIOUS ELEMENTS IN AN AQUATIC ENVIRONMENT Element Fresh-water Fresh water Salt water Salt water Fish Inverterbrates Fish inverterbrates N 9.00e-1 9.00e-1 9.00e 1 9.30e-1 C 4.60e 3 9.10e+3 1.80e+3 1.40e3 Na 1.00e 2 2.00e+2 6.70e-2 1.90e-1 P 1.00e+5 2.00e4 2.90e4 3.00e4 Cr 2.00e 2 2.00e+3 4.00e+2 2.00e+3 Mn 4.00e2 9.00e+4 5.50e+2 4.00e+2 Fe 1.00e+2 3.20e+3 3.00e+3 2.00e+4 Co 5.00e+1 2.00e+2 1.00e+2 1.00e+3 NI 1.00e 2 1.00e 2 1.00e 2 2.50e+2 Cu 5.00e1 4.00e+2 6.70e+2 1.70e3 Zn 2.00e+3 1.00e4 2.00e3 5.00e4 Br 4.20e+2 3.30e+2 1.50e 2 3.10e+0 Rb 2.00e3 1.00e 3 8.30e+0 1.70e+1 Sr 3.00e+1 1.00e+2 2.00e+0 2.00e+1 Y 2.50e1 1.00e 3 2.50e1 1.00c3 2r 3.30e+0 6.70e+0 2.00e+2 8.0Go 1 Mb 3.00e 2 1.00e 2 3.00c 2 1.00e+2 Mo 1.00e+1 1.00e+1 1.00e+1 1.00e1 Tc 1.50e1 5.00e+0 1.00e+1 5.00e+1 Ru 1.00e1 3.00e 2 3.00e+0 1.00e 3 Ag 2.00e0 8.00e2 3.00c 3 3.00e+3 Te 4.00c 2 6.10e+3 1.00e+1 1.00e+2 1 1.50e1 5.00e+0 1.00e+1 5.00e+1 Cs 2.00e3 1.00e+3 4.00e+1 2.50e1 Ba 4.00e 0 2.00e2 1.00e+1 1.00e+2 La 2.50e1 1.00e3 2.50e+1 1.00e3 Ce 1.00e+0 1.00e3 1.00e+1 6.00e2 Pr 2.50e+1 1.00e 3 2.50e1 1.00e3 Nd 2.50e+1 1.00e+3 2.50e+1 1.00e3 W 1.20e3 1.00e+1 3.00e1 3.00e+1 up 1.00e+1 4.00e+2 1.00e+1 1.00e+1 Cate obtained from Regulatory Guide 1.109 Table A 1 for all elements except Silver (AG) Which is from "Models and Pararmters for Envirorumental Radiological Assessments" (00E/ TIC 11468) and Niobium (Nb) Which is from the International Atomic Energy Agency (IAEA) Safety Scries No. 57, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine g Releases, Exposures of Critical Gro p . UNT-005-014 Revision 3 Attachment 6.21 (2 of 2) 250 _-}}