ML20212H731
| ML20212H731 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1986 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3P87-0568, W3P87-568, NUDOCS 8703060207 | |
| Download: ML20212H731 (145) | |
Text
Enclosure to W3P87-0568 Semiannual Radioactive Effluent Release Report July 1, 1986 - December 31, 1986 Waterford 3 SES Louisiana Power and Light 0703060207 861231 PDR ADOCK 05000382 R
PDR W310526HP 1NW w
i 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 Abnormal Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA-
7.0 ASSESSMENT
OF DOSES 7.1 Dose at Site Boundary 7.2 Dose to the Critical Receptors 7.3 Doses due to Liquid Effluents 7.4 40 CFR 19 Dose Evaluation 7.5 Doses to Public Inside the Site Boundary 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 9.0 TABLES 10.0 ATTACHMENTS W310526HP 1
-~ _
1.0 SCOPE
)
This Semiannual Radioactive Release Report is submitted as required by Louisiana Power and Light's Waterford 3 Technical Specification 6.9.1.8.
It covers the period from July 1, 1986 through December 31, 1986.
Included in this report is a summary of the quantities of radioactive L
Liquid and gaseous effluents and solid wastes released from the plant t.
1 during the reporting period.
In addition, a summary of the meteorological data and results from the assessment of radiation doses due to the release of liquid and gaseous radioactive effluents, is reported for the entire 1986 year.
Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.
Other required information in this report includes:
(1) explanatien of why certain instrumentation was not restored to operable status within the time specified in the ACTION Statement, as per Waterford 3 SES Tech-nical Specification 3/4.3.3.11; (2) changes to the Off-Site Dose Calculation Manual, and (3) a report of an unplanned abnormal release.
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous 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.
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1 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, 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 Iodines; 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 mres/yr to any organ.
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.
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7
.)
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 10CFR 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 to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 area to the total body and less than or equal to 5 arem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 arem to any organ.
2.1.4 Uranium Fuel Cycle Sources 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.
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1 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases; Iodines; and Particulates, Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.
2.2.2 Liquid Effluents-The maximum permissible concentration (NPC) values specified in 10CFR20, Appendix B, Table II, Column 2 are used as the permissible concentrations of 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 effluents..
2.3 Average Energy This is not applicable to Waterford 3 SES's radiological effluent technical specifications.
2.4 Measurements and Approximations 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 4.11-1 and 4.11-2 of the Waterford 3 SES Plant Technical Specifications.
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l 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 = Average Weekly Noble Gas Monitor Reading Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch.
In all cases the measured total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.
2.4.2 Iodines and Particulates Iodines and particulates discharged were sampled using a continuous sampler. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volume discharged were used to calculate the previous week's activity released.
Composites of the particulate samples were analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes). Particulate gross alpha was measured weekly using gas flow proportional counting techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was performed.
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Grab tritium samples for continuous and batch releases were analyzed monthly. The determined concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.
2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases. For batch releases, gamma l
analysis was performed on the sample prior to release.
For both continuous and batch releases, Sr-89, Sr-90, and l
Fe-55 composite samples were analyzed quarterly by a contract laboratory (Teledyne Isotopes). Tritium and gross alpha composite samples were analyzed monthly using liquid scintil-lation and gas flow proportional techniques respectively.
For radionuclides analyzed in composite samples, the measured concentrations of the previous composite were used in deter-mining concentrations in liquid effluents.
The measured total radioactivity in liquid effluent releases was determined from the measured concentrations of each radio-nuclide present and the total volume of the effluent discharged.
2.5 Batch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1.
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2.6 Unplanned Abnormal Releases 2.6.1 Unplanned Abnormal Release October 21, 1986 Description of Event On October 21, 1986, an unplanned release was made from Boric Acid Condensate (BAC) Tank D to the Circulating Water (CW)
System; however, the limits of Technical Specifications 3.11.1.1, 3.11.1.2, and 3.11.1.3 were not exceeded. Based upon grab sample results, the maximum organ dose was 1.25E-5 mrem (liver) and the maximum total body dose was 8.53E-6 mrem.
Cause of Event On October 21, 1986, BAC Tank A was in the process of being discharged in accordance with approved procedure OP-7-001, Boron Management System. The Boron Management effluent radiation monitor was inoperable, but in accordance with Technical Specification 3.3.3.10 effluent releases may con-tinue for up to 14 days provided that prior to initiating
'a release at least two independent samples are analyzed and at least two technically qualified members of plant staff independently verify the release rate calculation and dis-charge valve lineup. Earlier BAC Tank D was placed in recir-culation to be sampled in preparation for discharging later in the day. At 1319, Operations personnel commenced discharging BAC Tank A to the CW system, but did not secure recirculation of BAC Tank D as required by OP-7-001. At 1538, a sample from BAC Tank D was analyzed. Si;:ce the BAC Pump aligned for discharge produces a higher discharge pressure than one aligned for recirculation, EAC Tank D level increased from 77%
to 94%. At 1610 recirculation of BAC Tank D was secured when the level increase was noted. At 1617, a second sample of BAC Tank D was analyzed. At 1710, the discharge of BAC Tank A was 4
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terminated when BAC Pump A was secured and its discharge valve shut. Valves BM547 and BM549, which are normally shut by the loss of flow radiation monitor trip, and BM556 (BAC discharge to CW stop valve) were not closed. The recircula-tion of BAC Tank D was then restarted. With valves BM547, BM549 and BM556 open and BAC Pump B Discharge Isolation Valve (BM5408) leaking, a flow path from BAC Tank D to the CW System was established and the release from BAC Tank D began. At 1745, BAC Tank D level was noted to be decreasing and recir-culation of the tank was secured. The release from BAC Tank D stopped at this time. The estimated amount of the release is 1225 gallons.
The root cause of the event was procedural noncompliance.
Secondary causes were valve BM540B leaking by its seat, valve BM556 not being readily accessible and not being shut expeditiously, and the Boron Management radiation monitor being out of service.
Actions Taken to Prevent Recurrence OP-7-001 was revised on 10-23-86 to explain more explicitly that a BAC Tank cannot be discharged to the CW system while any other BAC Tank is on recirculation. The Operations Department received a letter from the Operations Superintendent emphasizing that procedure noncompliance will not be tolerated. The utility nonlicensed operator who did not adhere to OP-7-001 was disciplined. Station Modification Request 1696 has been initiated for installation of an isolation valve located in a more accessible area and a work request was written to repair valve BM540B.
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Radiological Consequences of the Release Because activity levels from the BAC Tank samples recorded by Health Physics personnel were well within the limits specified in 10CFR20, this event in no way posed a threat to the health and safety of plant personnel or the general public. Details are as follows:
i) Tech Spec 3.11.1.1 - Maximum Concentration of Radionuclides l
All nuclides were less than the Maximum Permissable Concentration.
ii) Tech Spec 3.11.1.2 - Dose to Member of the Public (QTR)
Total Body 8.53E-6 area 5.69E-4% of Tech Spec Limit Organ (Liver) 1.25E-5 mren 2.5E-4% of Tech Spec Limit iii) Tech Spec 3.11.1.3 - Radwaste System Treatment Operability Total Body 8.53E-6 mrem 1.42E-2% of Tech Spec Limit Organ (Liver) 1.25E-5 mrem 6.25E-3% of Tech Spec Limit 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tabics 1A, 1B, and IC.
Note that there are no elevated releases at Waterford 3 SES.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 28.
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5.0 SOLID WASTES I
I The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3.
6.0 METEOROLOGICAL DATA The summary of the hourly meteorological data from January 1,1986 through December 31, 1986 is present in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability in Table 4.
The Waterford-3 data recovery results by parameter are as follows:
Delta T 81.9%
WS/WD 94.2%
Delta T, WS/WD 78.3%
The data losses were largely due to equipment failures related to the aging meteorological system components, as well as problems with the strip chart recorders.
LP&L has endeavored to correct the equipment problems and minimize data loss as evident by the following actions:
Replacement of all cables and selected sensors on both the primary and backup towers, Repair / replacement of components on the elevator systems of both the primary and backup towers, Improvement in the spare parts inventory onsite especially with respect to the strip chart recorders, and Implementation of improved surveillance and maintenance procedures for the meteorological system.
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3; In addition, LP&L subcontracted with Ebasco Services, Inc. to perform an independent audit of the Meteorological System in 1986; many of the recommendations resulting from this audit have already been implemented in the meteorological monitoring system. Ebasco meteorologists have also been reviewing the data base, and identifying ongoing problems such that corrective action can be taken.
7.0 ASSESSMENT
OF DOSES 7.1 Dose at the Site Boundary An assessment of air doses from gaseous effluents was performed at the site boundary. Based on actual meteorological conditions existing during the reporting period and excluding any sectors over water, this location was determined to be the ESE sector at 1000 meters. Doses were assessed at this location considering only beta gamma exposures due to noble gas. The results of these assessments for the year 1986 are summarized as follows:
Beta air dose:
5.00 mrad Gamma air dose:
2.00 mrad The beta and gamma air doses are 25% and 20% of the Technical Specification Dose Limits respectively.
7.2 Dose to the Critical Receptor 7.2.1 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 1986.
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4 An assessment of the dose was performed for the residential location nearest to the plant with the highest dispersion parameters. Using'1986 land use census data and actual meteorological data, the critical receptor location for the nearest residence was determined to be in the N sector at a 7
distance of 1300 meters. The dose calculation was performed considering the inhalation, ground plane exposure, and cow's milk ingestion pathways.
7.2.2 The maximum dose to the critical organ was determined to be-5.46 mrem to the infant thyroid.' This represents 36% of the annual Technical Specification Dose Limit.
i I
7.3 Doses Due to Liquid Effluents The annual dose to the maximum exposed individual from liquid effluents during 1986 from Waterford 3 SES was 1.34E-1 arem total body and 2.16E-1 mrem to the maximum exposed organ (CI-LLI). These values are 4.5% and 2.2% respectively of the annual Technical Specification Dose Limit.
l 7.4 40CRF190 Dose Evaluation In accordance with Waterford 3 Offsite Dose Calculation Manual.
Section 8.15, dose evaluations to demonstrate compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Waterford Technical Specifications, dealing with dose frcm 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 1986 were any of these limits exceeded; therefore, no evaluations are required.
I W310526HP 13
7.5 Doses to Public Inside the Site Boundary The member of the Public Inside the Site Boundary expected to have the maximum exposure due to gaseous effluents is an employee at Waterford I and II fossil fuel plants, located in the NW sector, approximately 670 meters from the plant. Based on an assumption of 25% occupancy (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 all employees are adults, the maximum organ dose was 2.74 mrem to the thyroid.
1 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Control Program for the period this report covers.
l l
8.2 Changes to the Offsite Dose Calculation Manual 8.2.1 On July 10, 1986, Revision 5 of the Waterford 3 Offsite Dose Calculation Manual was changed and approved for issue by the PORC. Approval by the Plant Manager was received on July 11, 1986.
The changes were made to incorporate new environmental sample locations to the Radiological Environmental Monitoring Program (REMP).
8.2.1.1 A shoreline sediment sample location (SFWJ-1) was added.
(Attachment 10.2. Attachment 10.3, and 0.5) 8.2.1.2 A TLD (P-1. Attachment 10.3) was moved to prevent theft.
8.2.1.3 The control broadleaf sample location (BLK-15) was moved due to new deposition factors.
(Attachment 10.2, Attachment 10.3, and Attachment 10.7)
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8.2.1.4 The control milk sample location (MKQ-45) was moved so that milk from cows fed wholly on pasture grass vould be sampled.
(Attachment 10.2, Attachment 10.3, and Attachment 10.7) 8.2.1.5 0.4 was changed to include zone 35 at a distance of 30-35 miles from the plant.
8.2.3 None of these described changes actually changed dose, dose rate or setpoint calculations.
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 Technical Specification Table 3.12-1.
Milk is collected, when available, from the control location and three identi-fied sampling locations as indicated in ODCM, Table 2 and Table 3.
8.4 Report of Technical Specification Required Instrument Inoperability Technical Specification, Limiting Condition for Operation (LCO),
3.3.3.11 requires the reporting in the Semiannual Effluent Release Report of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement.
8.4.1 Monitor
Waste Gas Holdup System Hydrogen Monitor and Oxygen Monitors Period of Inoperability:
3/21/85 - 12/30/86 (At end of reporting period monitors were still inoperable)
Time Required by Technical Specifications to Restore Operability:
14 days s
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Cause of Inoperability:
Due to design problems excess amounts of moisture were allowed to leak into both the Beckman 0 and Delphi H and 0 2
2 2
analyzer systems.
Reason Inoperability Not Restored Within Allotted Time:
Extensive hours were spent attempting to restore these analyzers to operable status.
Several analyzer cells were replaced, the solenoid and regulator were repaired, and the sample pump was both repaired and replaced. After these efforts failed to return the monitor to service, a station modification was initiated to replace the analyzer cells with less moisture sensitive models and to completely redesign the sample line condensate drain system.
This modification entailed work in several areas of the plant and on four different systems. All existing piping and electronics associated with the Waste Gas Holdup System Hydrogen and Oxygen Honitors was essentially scrapped and redesigned.
Work included re-routing all sample lines in the Laundry Room, modifying the existing drain header, and fabrication of a new drain header to tie into the Vent Gas Collection Header.
Re-routing of the Gas Surge Header Sample line and fabrication of its drain was performed in Safeguards Room B.
On Gas Decay Tank A a new separator and drain line on the Waste Gas Collec-tion Discharge Header was added to the second low point.
Actual work on the Gas Analyzer Panel consisted of (1) adding 12 new solenoid valves in the sample inlets; (2) modifying the panel to accommodate the new exo-sensor units; (3) installing a new pump and its associated tubing; and (4) wiring of all new and relocated components.
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While testing the system, the Gas Decay Tank "C" sample line was found to be crossed with the Gas Surge Tank sample line.
Due to greater pressure in the Gas Decay Tank than that of the Cas Surge Tank the sampling pump diaphragm was blown.
This event also identified other problems with the system which required correction.
Design changes have been made to uncross the lines and install a pressure switch to prevent any subsequent over-pressurization. The pump was replaced and new wiring was installed. Additional moisture traps, pressure regulators, valves and pressure indicators have been installed.
A detailed test procedure was prepared and approved. Testing of the system was completed in early December however attempts to make the system operable have been unsuccessful.
LP&L is in the process of reevaluating the system.
An update will be forwarded via the next semiannual report.
9.0 TABLES 1
Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents IB Semiannual Airborne Continuous Elevated and Ground Level Releases 1C 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 10.0 ATinCHMENTS 1.
Off-Site Dose Calculation Manual, HP-1-230, Revision 5 - Change 2.
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TAB E 1 (1 of 1)
REPORT CATEGORY
- BATCH RELEASE
SUMMARY
- RELEASE POINT
- ALL.
TYFE OF RELEASE
- BATCH LIQUID AND OASEGUS FERIOD START TIME
- 4344:00 HRS-= 12: 00AM.J.iLY 1, 19S6 PERIOD END TIME
- 8759:59 HRS = 11:59PM DECEMBER 31, 19S6
- - - - _ - - - - - - - - - - - - - _ - - - - - _ _ - - - - - - - - - - _ - - - - - - - - - - _ - - = _
LIQUID RELEASES-NUMBER OF RELEASES 282 TOTAL TI.ME.FOR ALL RELEASES :
75213.0 MINUTES MAXIMUM TIME FOR A RELEASE 926.0 MINUTES AVERAGE TIME FOR A RELEASE 466.7 MINUTES MINIMUM TIME FOR A RELEASE 99.0 MINUTES AVERAGE STREAM FLOW 927132.5 GPM GASEQUS RELEASES MUMBER OF RELEASES 79 TOTAL TIME FOR ALL RELEASES :
20667.0 MINUTES MAXIMUM TIME FOR A RELEASE 3788.0 MINUTES AVESAGE TIME FOR A RELEASE 261.6 MINUTES MINIMUM TIME FOR A RELEASE 1.0 MINUTES 18 v
v r.-
.m.-
e
--,,.4 y
TABLE 1A (1 of 1)
REPORT' CATEGORY
- SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY
- A L AIRBORNE E F_UENTS
- REPORTING PERIOD
- QUARTER 4 3 AND QUARTER # 4
..M..
- u.b. ART-J i_
i ed.
.u...s-,icR 4 :co._ _._...i.ivem.
ds._
- HOURS
- -40URS
- ERROR %
TYFE OF EFFLUENT
- 4345-6552 :6553-8760 :
A. FISSION AND ACTIVATION
__________________________' PRODUCTS 1.
TOTAL. RELEASE
- CURIES
- 3.14E.03 : 4.03E 03 : 1.50E 01:
__L_so._c RATt r-g H FtRIU.D
.,J U I /.o - -
1. o-7 c O.,.,
_x. g. o.,
m
. cu AVcK,.,Au_c_
nc e u.
u u.
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A D. RADIGIODINES 1.
TOTAL IODINE-131
- CURIES
- 7.56E-04 : 1.09E-03 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR FERIOD
- UCI/SEC
- 4.76E-05 : 6.85E-05 :
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A 1
i C.
PARTICULATES 1.
PARTICULATES(HALF-LIVES?G DAYS)
- CURIES
- 3.62E-06 : 1.53E-04 : 1.50E 01:
- 3. AVERAGE RELEASE RATE FOR PERIOD
- UCI/SEC
- 2.2GE-07 : 9.61E-06 :
- 3. PERCENT GF APPLICABLE LIMIT N/A N/A
?.
GROSS ALPHA RADIOACTIVITY
- CURIES
- 7.84E-06 : 6.96E-06 :
D.
TRITIUM 1.
TOTAL RELEASE
- CURIES
- G.50E 01 : 2.92E 01 : 1.50E 014
- 2. AVERAGE RELEASE RATE FOR PERIOD
- UCI/SEC
- 3.35E 00 : 1.34E 00 :
- 3. PERCENT OF AFPLICABLE LIMIT N/A N/A 19
TAB 2 1B (1 of 2)
REPORT CATEGORY
- SEMIANNUAL AIRBORNE CONTINUQUS ELEVATED AND OROUND
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
- TYPE OF ACTIVITY-
- FISSION GASES. 10 DINES, AND PARTICULATES
. REPORTING PERIOD
- OUARTER # 3 AND OUARTER # 4 ELEVATED RELEASES ORCUND RELEASES UNIT
- QUARTER 3 : QUARTER 4 : QUARTER 3 QUARTER 4 :
- HOURS
- HOURS HOURS
- HOURS NUCLIDE.
- 4345-6552 :6553-8760 :4345-6552 :6553-8760 :
_______-_-___---_______---_______________________--_-____-_-- = -= _____--______
FISGION GASEG KR-S5M CURIES
- 0.00E-01 : 0.00E-01 : 1.13E 01 : 5.06E 00 :
KR-87 CURIES
- 0.00E-01 : 0.00E-01 : 2.31E-01 : 0.00E-01 :
KR-88 CURIES
- 0.00E-01 : 0.00E-01 : 2.06E 01 : 0.00E-01 :
XE-131M CURIES
- 0.00E-01 2 0.00E-01 : 2.89E 00 : 0.00E-01 :
XE-133M CURIES
- 0.00E-01 : 0.00E-01 : 3.01E 00 : 6.62E 00 :
XE-123 CURIES
- 0.00E-01 : 0.00E-01 : 1.91E 03 : 2.61E 03 :
XE-135 CURIES
- 0.00E-01 : 0.00E-01 : 8.59E 01 : 6.75E 01 :
TOTAL FOR PERIOD CURIES
- 0.00E-01 : 0.00E-01 : 2.03E 03 : 2.69E 03 :
I0 DINES s-131 CURIES
- 0.00E-01 : 0.00E-01 : 7.56E-04 : 1.09E-03 :
I-132 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.51E-06 :
I-133 CURIES
- 0.00E-01 : 0.00E-01 : 1.71E-05 : 0.00E-01 :
TOTAL FOR PERIOD CURIES
- 0.00E-01 : 0.00E-01 : 7.74E-04 : 1.09E-03 :
FARTICULATES H-3 CURIES
- 0.00E-01 : 0.00E-01 : 8.12E 01 : 2.35E 01 :
CR-51 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.40E-05 :
MN-54 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.39E-06 :
FE-59 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.71E-06 :
CO-53 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.94E-05 :
4 CO-60 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.30E-06 :
ZR-95 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.03E-06 :
NB-95 CURIES
- 0.00E-01 : 0.00E-01 0.00E-01 : 4.86E-06 :
TC-99M CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 3.16E-07 :
RU-103 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 2.55E-07 :
20
TABE IB' '(2 of 2)
REPORT CATEGORY
- SEMIANNUAL AIRBORNE CONTINUOUS ELEVATED A'D GROUND N
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
-TYPE OF ACTIVITY-FISSION OASES, IODINES, AND PARTICULATES
' REPORTING PERIOD
- ' QUARTER # 3 AND OUARTER tr 4 ELEVATED RELEASES
- - GROUND RELEASES UNIT OUARTER 3 : QUARTER 4 : QUARTER 3 : QUARTER 4 :
HOURS
- HOURS
- HOURS
- HOURS NUCLIDE ' ____..____________: ___________: _4 345-6552 : 6553-8760 : 4345-6552. I 6553-S760 PARTICULATES CONTINUED CS-137
- . CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 3.62E-07 :
G ALPHA CURIES
- 0.00E-01 : 0.00E-01 : 7.84E-06 : 6.95E-06 :
- TOTAL FOR PERIOD CURIES
- 0.OOE-01 : 0.00E-01 :-8.12E 01 : 2.8SE 01
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ = - _ _
1 i -
s a
f
+
f 4
i t
I i
b l
r 21 f
i 4
P f
e-ww,--
pn,,--yw y y eg e-,p--r-r-,,,~r-n,,..~.-.e-,v,w-.,-n.,,s,.w-n-m.,-,w-...,pn m.
--.--,,..,,reww-,_,m--,,_,_--,_.-,,., -
,, _ -.,,,,, - - - - ~.,, -,,
1 l
TAME 1C (1 of 1)
REPORT CATEGGRY
- SEMIANNUAL AIRBORNE BATCH ELEVATED AND OROUND
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY
- FISSION GASES. IODINES, AND PARTICULATES REPORTING PERIOD
- QUARTER # 3 AND QUARTER i 4
_____________________________________________ i ELEVATED RELEASES OROUND RELEASES
- I UNIT CUARTER 3 : QUARTER 4 : QUARTER 3 :0UARTER 4 :
i
- HOURS
- HOURS
- HOURS
- HOURS NUCLIDE
- 4345-6552 :6553-8760 :4345-6552 86553-8760 :
FESSION GASES KR-85M CURIES
- 0.00E-01 0.00E-01 : 7.14E-01 : 1.35E 00 :
KR-G5 CURIES
- 0.00E-01 : 0.00E-01 : 7.29E 00 : 3.14E 00 :
KR-87 CURIES
- 0.00E-01 : 0.00E-01 : 1.06E-01': 1.83E-01 :
KR-GS CURIES
- 0.00E-01 : 0.00E-01 : 6.45E-01 : 1.31E 00 :
XE-131M CURIES
- 0.00E-01 : 0.00E-01 : 1.34E 01 : 1.06E 01 :
XE-133M CURIES
- 0.00E-01 : 0.00E-01 : G.26E 00 : 1.46E 01 :
XE-133 CURIES
- 0.00E-01 : 0.00E-01 : 1.06E 03 : 1.29E 03 :
XE-135 CURIES
- 0.00E-01 : 0.00E-01 : G.27E 00 1.99E 01 :
XE-138 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.73E-02 :
AR-41 CURIES
- 0.00E-01 : 0.00E-01 : 5.10E-01 : 5.01E-01 :
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ =
TOTAL FOR PERIOD CURIES
- 0.00E-01 : 0.00E-01 1.10E 03 : 1.34E 03 :
10 DINES NONE PARTICULATES H-3 CURIES
- 0.00E-01 : 0.00E-01 3.G?E 00 : 3.79E-01 :
NA-24 CURIES
- 0.00E-01 : 0.00E-01 : 9.3GE-07 0.00E-01 :
MN-54 CURIES
- 0.00E-01 : 0.00E-01 : 2.57E-06 0.00E-01 :
CO-SS CURIES
- 0.00E-01 : 0.00E-01 : 1.05E-06 0.00E-01 :
RB-SS CURIES
- 0.0CE-01 : 0.00E-01 4.63E-05 : 0.00E-01 :
TOTAL FOR FERIOD CURIES
- 0.00E-01 : 0.00E-01 3.39E 00 : 3.79E-01 a 22
TABLE 2A (1 of 1)
REPORT CATEGORY _
SEMIANNUAL SUMMATION OF'ALL RELEASES _BY QUARTER TYPE OF ACTIVITY
- ALL LIQUID EFFLUENTS REPORTING PERIOD
- QUARTER 4 3 AND QUARTER # 4 UNIT
- QUARTER 3 : QUARTER 4 :EST. TOTAL:
- HOURS-HOURS ERROR %
.TYFE OF EFFLUENT
- 4345-6552 :6553-8760 :
A.. FISSION AND ACTIVATION FRODUCT3
_=___=____--_--_--_-___--------_
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM. GASES, ALPHA)
- CURIES
- 1.95E 00 : 6.30E-01 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD
- UCI/ML
- -1.55E-08 : 4.57E-09 :
- 3. PERCENT OF APPLICADLE LIMIT i
N/A N/A D. TRITIUM 1.
TOTAL RELEASE
- CURIES
- 1.66E 02 7.70E 01 : 1.50E 012 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD IUCI/ML
- 1.33E-06 5.53E-07 :
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C.-DISSOLVED AND ENTRAINED GASES 1.
TOTAL RELEASE CURIES 2.67E 01 3 4.39E 01 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION LURING PERIOD UCI/ML 2.11E-07 3.1GE-07 :
3.
PERCENT OF APFLICABLE LIMIT N/A N/A D. GROGG ALPHA RADI0 ACTIVITY 1.
TOTAL RELEASE CURIES
- 0.00E-01 : 0.00E-01 : 1.50E 01:
E. WASTE VOL RELEASED (PRE-DILUTION)
GAL 1.63E 06 1.G5E 06 : 1.50E 018 F. VOLUME OF DILUTION WATER USED 80AL 3.33E 10 2.44E 10 1.50E 01 23
TAB 2 2B (1 of 2)
. REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUGUS AND BATCH RELEASES
- . TOTALS FOR EACH NUCLIDE RELEASED.
. TYPE OF ACTIVITY
- ALL RADIONUCLIDES REPORTING PERIOD
- QUARTER w 3 AND QUARTER # 4
- CONTINUQUS RELEASES BATCH RELEASES
_____________ __ __________==_===_._______-_______________________ ______.___
UNIT
- QUARTER 3 QUARTER 4 : QUARTER 3 QUARTER 4 :
- HOURS HOURS
- HOURS
- HOURS NUCLILE
- 4345-6552 26553-8760 : 4345-6552 86553-8760 :
ALL NUCLIDES H-3 CURIES
- 0.00E-01 : 0.00E-01 1.65E 02 7.70E 01 :
NA-24 CURIES
- 0.00E-01 : 0.00E-01 : 1.12E-05 : 6.63E-05 :
CR-51 CURIES
- 0.00E-01 0.00E-01 : 1.53E-01 : 3.73E-02 :
MN-54 CURIES
- 0.00E-01 0.00E-01 : 6.80E-03' 2.91E-03 :
MN-56 CURIES
- 0.00E-01 : 0.00E-01 5.00E-05 0.00E-01 :
FE-55 CURIES
- 0.00E-01 : 0.00E-01 : 5.86E-02 : 2.70E-01 :
FE-59 CURIES
- 0.00E-01 : 0.00E-01 : 6.77E-02 : 6.27E-03 :
CO-59 CURIES
- 0.00E-01 : 0.00E-01 : 1.2SE 00 1.09E-01 :
C0-60 CURIES 0.00E-01 0.00E-01 4.32E-02 8.10E-03 :
ZN-65 CURIES
- 0.00E-01 0.00E-01 : 3.21E-05 1.32E-04 :
AB-88 CURIES
- 0.00E-01 : 0.00E-01 : 5.35E-03 : 1.02E-02 :
SR-89 CURIES
- 0.00E-01 : 0.00E-01 3.06E-05 8 3.70E-04 :
SR-92 CURIES 0.00E-01 0.00E-01 2.90E-05 7.G1E-06 :
IR-95 CURIES
- 0.00E-01 : 0.00E-01 : 1.3GE-02 5.36E-03 ZR-97 CURIES
- 0.00E-01 0.00E-01 : 2.96E-05 0.00E-01 :
NS-95 CURIES
- 0.00E-01 : 0.00E-01 : 1.91E-02 : 8.85E-03 :
M0-99 CURIES
- 0.00E-01 0.00E-01 1.53E-02 e 3.53E-03 :
TC-99M CURIES
- 0.00E-01 : 0.00E-01 : 5.90E-03 : 9.10E-04 :
RU-103 CURIES
- 0.00E-01 : 0.00E-01 : 3.23E-03 : 7.20E-04 :
40-110M CURIES
- 0.00E-01 : 0.03E-01 3.42E-04 8 0.00E-01 :
TE-132 CURIES
- 0.00E-01 0.OGE-01 6.99E-04 : 1.02E-05 :
I-131 CURIES
- 0.00E-01 0.00E-01 : 1.G7E-01 : 1.20E-01 :
I-133 CURIES
- 0.00E-01 0.00E-01 : 1.36E-02 : 4.31E-03 :
I-135 CURIES 0.00E-01 0.00E-01 9.30E-04 1.14E-04 :
CS-134 CURIES
- 0.00E-01 0.00E-01 : 1.17E-02 : 3.03E-04 :
CS-136 CURIES
- 0.00E-01 0.00E-01 5.96E-04 8.51E-06 :
CS-137 CURIES
- 0.00E-01 : 0.00E-01 : 2.55E-02 : 1.23E-03 :
BA-124 CURIES 0.00E-01 : 0.00E-01 : 0.00E-01 : G.44E-05 :
24
TAB 2 2B (2 ef 2)
REPORT CATEGORY
- ' SEMIANNUAL LIQUID CONTINUOUS AND' BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY
- ALL RADIONUCLIDES REPORTING PERIOD
- QUARTER # 3 AND QUARTER # 4 CONTINU0US RELEASES BATCH RELEASES LNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 :
HOURS IH0VRS HOURS HOURS NUCLIDE 84345-6552 86553-8760 84345-6552 86553-8760 ALL NUCLIDES CONTINUED BA-140 CURIES
- 0.00E-01 0.00E-01 : 9.27E-04 1.35C-03 :
LA-140 CURIES 0.00E-01 0.00E-01 4.87E-02 2.84E-02 :
CE-141 CURIES 0.00E-01 0.00E-01 6.74E-04 8 2.57E-04 :
CE-144 CURIES
- 0.00E-01 0.00E-01 : 0.00E-01 : 1.44E-05 :
W-&S7 CURIES
- 0.00E-01 0.00E-01 1.G9E-04 : 0.00E-01 :
NP-239 CURIES
- 0.00E-01 0.00E-01 4.55E-04 0.00E-01 :
KR-85M CURIES
- 0.00E-01 0.00E-01 : 1.41E-03 6.35E-04 :
CURIES
- 0.00E-01 : 0.00E-01 : 5.49E-03 4.31E-02 :
KR-85 KR-87 CURIES
- 0.00E-01 0.00E-01 : 0.00E-01 2.01E-05 :
KR-33 CURIES
- 0.00E-01 0.00E-01 : 4.97E-04 2.99E-04 :
XE-131M CURIES
- 0.00E-01 : 0.00E-01 8 3.11E-01 : 2.32E-01 :
XE-133M CURIE 5 0.00E-01 0.00E-01 1.60E-01 3.57E-01 :
XE-133 CURIES
- 0.00E-01 0.00E-01 : 2.61E 01 1 4.32E 01 :
XE-135M CURIES
- 0.00E-01 0.00E-01 : 1.65E-03 : 1.36E-04 :
XE-135 CURIES
- 0.00E-01 : 0.00E-01 1.1SE-01 8 5.65E-02 :
CC-57 CURIES
- 0.00E-01 0.00E-01 1.20E-03 6.06E-05 58-124 CURIES 0.00E-01 : 0.00E-01 9.14E-03 4.32E-03 :
SM-113 CURIES
- 0.00E-01 : 0.00E-01 4.14E-03 2.25E-03 :
NB-97 CURIES
- 0.002-01 : 0.00E-01 : 2.60E-03 2.42E-04 :
SB-122 CURIES 0.00E-01 0.00E-01 6.05E-04 : 2.44E-03 :
SC-46 CURIES
- 0.00E-01 : 0.00E-01 : 0.00E-01 2.30E-05 :
TOTAL FOR PERIOD CURIES
- 0.00E-01 : 0.00E-01 1.97E 02 1.21E 02 :
25
TABLE 3 (1 of 4)
- REGULAROTY GUIDE 1.21 REPORT ***
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL
- DURING PERIOD FROM 7/1/86 TO 12/31/86**
CONTAINER ESTIMATED WASTE TYPE VOLUME FT3 QUBIC METERS CURIES
% ERROR (CI)
COMPACTED DRY 95 61.8 1.0E+00
+/- 25%
ACTIVE WASTE NON COMPACTED 95 10.8 6.3E-03
+/- 25%
DRY ACTIVE WASTE COMPACTED DRY 95 24.2 2.2E-01
+/- 25%
ACTIVE WASTE AND FILTER CARTRIDGES LIQUID WASTE 182 10.3 5.9E+00
+/- 25%
MANAGEMENT. SYSTEM SPENT RESIN SOLIDIFIED WITH CEMENT LIQUID WASTE 182 5.2 1.2E+00
+/- 25%
MANAGEMENT SYSTEM SPENT RESIN DEWATERED LIQUID WASTE 182 5.2 2.5E+01
+/- 25%
MANAGEMENT SYSTEM AND RESIN WASTE MANAGEMENT SYSTEM SPENT RESIN SOLIDIFIED WITH CEMENT
- ESTIMATES OF MAJOR NUCLIDES BY WASTE TYPE **
WASTE TYPE NUCLIDE ABUNDANCE CURIES COMPACTED DRY Mn-54 1.8%
1.9E-02 ACTIVE WASTE Fe-55 8.7%
8.9E-02 Co-58 18.0%
1.8E-01 Co-60 4.3%
4.4E-02 Ni-59
.0%
.0E+00 Ni-63 2.0%
2.1E-02 Nb-94
.0%
.0E+00 H-3 1.3%
1.3E-02 C-14
.6%
5.7E-03 26
~
TABLE 3 (2 of 4)
.0%
.0E+00 Zr-95 1.5%
1.5E-02 Nb-95 1.4%
1.5E-02 Tc-99
.04
.0E+00 I-129
.0%
.0E+00 Cs-134 15.3%
1.5E-01 Cs-137 44.5%
4.5E-01 Pu-241
.0%
3.5E-06 Cm-242
.0%
7.4E-08 NON COMPACTED Mn-54 3.4%
2.2E-04 DRY ACTIVE WASTE Fe-55 36.2%
2.3E-03 Co-57 2.3%
1.4E-04 Co-58 25.1%
1.6E-03 Co-60 8.1%
5.1E-04 Ni-59
.0%
.0E+00 Ni-63 3.7%
2.3E-04 Nb-94
.0%
.0E+00 H-3
.0%
.0E+00 C-14 2.7%
1.7E-04 Sr-90
.0%
.0E+00 Zr-95 6.8%
4.3E-04 Nb-95 4.4%
2.8E-04 Tc-99
.0%
.0E+00 I-129
.0%
.0E+00 Cs-137 6.2%
3.9E-04 Pu-241
.0%
1.3E-07 Cm-242
.0%
2.4E-09 COMPACTED DRY ACTIVE Mn-54 3.2%
6.9E-03 WASTE AND CARTRIDGE Fe-55 42.0%
9.2E-02 FILTERS Co-57 1.7%
3.6E-03 Co-58 11.3%
2.5E-02 Co-60 10.8%
2.4E-02 Ni-59
.0%
.0E+00 Ni-63 5.3%
1.2E-02 Nb-94
.0%
.0E+00 H-3
.3%
6.8E-04 C-14 3.7%
8.1E-03 Sr-90
.0%
.0E+00 Tc-99
.0%
.0E+00 I-129
.0%
.0E+00 Cs-134 3.9%
8.5E-03 Cs-137 17.3%
3.8E-02 Pu-241
.0%
1.2E-06 Cm-242
.0%
1.8E-08 LIQUID WASTE Cr-51 2.6%
1.6E-01 MANAGEMENT SYSTEM Mn-54 1.4%
8.4E-02 SPENT RESIN Fe-55 3.2%
1.9E-01 SOLIDIFIED WITH Co-58 48.2%
2.9E+00 CEMENT Co-60 2.4%
1.4E-01 Ni-59
.0%
.0E+00 Ni-63 2.4%
1.4E-01 Nb-94
.04
.0E+00 H-3
.3%
1.7E-02 27
TABLE 3 (3 of 4)
.0%
9.1E-04 Sr-90
.0%
.0E+00 Tc-99
.0%
.0E+00 I-129
.0%
.0Et00 Cs-134 11.8%
7.0E-01 Cs-137 22.8%
1.4E+00 Co-141 1.8%
1.1E-01 Pu-241
.2%
9.5E-03 Cm-242
.0%
5.dt-07 LIQUID WASTE Mn-54 4.5%
5.5E-02 MANANGEMENT SYSTEM Co-58 79.3%
9.6E-01 SPENT RESIN Co-60
.9%
1.1E-02 DKWATERED Ni-59
.0%
.0E+00 Ni-63
.4%
5.0E-03 Nb-94
.0%
.0E+00 Sb-124 3.44 4.1E-02 H-3
.2%
2.1E-03 C-14
.0%
.0E+00 Sr-90
.04
.0E+00 Tc-99
.04
.0E+00 Cs-134 2.1%
2.6E-02 Cs-137 5.7%
6.9E-02 1-131 2.1%
2.6E-02 Pu-241
.0%
9.5E-07 Cm-242
.0%
.0E+00 LIQUID WASTE Hn-54 4.6%
1.1E+00 MANAGEMENT SYSTEM Co-58 59.0%
1.5E+00 AND RESIN WASTE Co-60 4.0%
9.7E-01 MANAGEMENT SYSTEM Ni-59
.0%
8.5E-03 SPENT RESIN Ni-63 2.2%
5.4E-01 SOLIDIFIED WITH Nb-94
.0%
.0E+00 CEMENT H-3
.1%
1.5E-02 C-14
.0%
2.2E-03 Sr-90
.0%
7.6E-03 Tc-99
.0%
.0E+00 I-129
.0%
.0E+00 Cs-134 9.5%
2.3E+00 Cs-137 16.6%
4.1E+00 Sr-89 1.8%
4.4E-01 Pu-241
.0%
3.8E-03 Cm-242
.0%
4.9E-05
- SOLID WASTE DISPOSITION
SUMMARY
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 2
TRUCK BARNWELL 5
TRUCK RICHLAND 0
TRUCK BEATTY 0
TRUCK OTHER NUMBER OF TYPE OF TYPE MODE OF 23
TABLE 3 (4 of 4)
CLASS SHIPMENTS SHIPMENTS CONTAINER TRANSPORT DESTINATION A
3 LSA STRONG TIGHT TRUCK RICHLAND A
1 L3A TYPE A TRUCK RICHLAND A
1 LSA STRONG TIGHT TRUCK BARNWELL A
1 LSA TYPE A TRUCK BARNWELL B
1 LSA TYPE A TRUCK RICHLAND 29
TABLE 4 (1 of 4)
JOINT FREGUENCY DISTRIBUTION OF WINS SPEE0 AND DIRECTION IN HOURS FOR JAN - K C 1994 PASSUILL CLASS A WING SPEED in/S) AT 10-m LEVEL WIND 31KEI1ON Ts sa st %
-2&:1.0__1.1:1.5__1.6:2.0__2.1:3.0__3.1:5.0__5.1:2.0__2.1:10.__10.1:13__13.1=11.0__118.0___IDIAL_____
N 0
0 0
2 0
3 12 5
1 0
0 0
23 NME O
O O
2 2
5 5
0 0
0 0
0 14 NE O
O O
2 1
6 8
3 0
0 0
0 20 ENE O
O o
0 1
30 36 to 0
0 0
0 77 E
O O
O O
2 5
5 0
0 0
0 0
12 ESE O
O O
1 0
4 4
0 0
0 0
0 11 SE O
O O
1 0
2 19 3
0 0
0 0
25 SSE O
O o
1 2
5 15 13 0
0 0
0 36 5
0 0
0 1
2 1
19 2
0 1
0 0
26 i
{
SSN 0
0 0
0 0
3 12 1
0 0
0 0
16 i
SW 0
0 0
0 0
2 8
1 0
0 0
0 11 WSW 0
0 0
0 1
3 5
3 0
0 0
0 12 W
0 0
0 0
0 1
4 1
0 0
0 0
6 WNW 0
0 0
0 0
0 1
2 0
0 0
0 3
ms 0
0 0
0 0
1 0
1 3
0 0
0 5
a e
a a
0 1
?
0_
?
0
__0 0
5.
l f
TOTAL 0
0 0
10 11 72 157 45 6
1 0
0 302 l
Mun0ER OF CALMS FOR A
STASILITY 0
l l
JOINT FREOUENCY DISTRIBUTION OF WIND SPEED AIS DIRECTION IN H0tNtS FOR JAN - KC 1996 PASOUILL CLASS S WIND SFEED IN/S) AT 10-m LEVEL WING atartrian
_is_ sa
_st_.7s
.7A_1.a 1,1:1,s 1 A-7 0__2.1-1 8 1-1:5.0__5.1:2.0__2.1:10.__10.1:13__13.1:18.0__118.0 _ IDIAL_____
4 N
O O
O 3
0 0
3 5
2 0
0 0
13 l
IEE O
O e
0 3
0 2
1 0
0 0
0 6
E O
O O
e 0
4 7
0 0
0 0
0 11 l
I EK e
0 0
1 1
12 0
0 0
0 0
20 E
O O
O O
1 2
4 0
0 0
0 0
7 ESE O
e 0
0 0
0 1
0 0
0 0
0 1
SE O
O O
1 1
4 5
3 0
0 0
0 14 SSE 9
0 0
0 0
3 9
4 0
0 0
0 16 S
0 0
0 1
1 1
7 1
2 0
0 0
13 SSW O
9 0
1 0
2 4
3 1
0 0
0 11 Su 0
0 0
0 1
3 7
3 1
0 0
0 15 USM O
O O
O O
7 4
2 0
0 0
0 15 W
0 0
0 0
1 1
2 1
0 0
0 0
5 tsaf 9
0 0
0 0
0 3
3 0
0 0
0 a
mi 0
0 0
0 0
1 2
3 0
0 0
0 temi 0
0 0
0
_0 0
?
1 1
0-8 0
___4 10TAL 0
0 0
7 9
34 76 30 7
0 _
0 0
163 I
NURDER OF CAlltS FOR R
STABILITY 0
i 30 e
TABLE 4 (2 of 4)
JOINT FRE0tENCY DISTRIDUTION IF WIND SPEED AND DIRECT!DN IN HOURS FOR JAN - DEC 1986 PASOUILL CLASS C WIND SPEED (M/S) AT 10-m LEVEL WI4 BIEC110N "2
51:.25-_.26:1.0__1.1:1 5 1.6:2.0__2.1:3.0__3.1:5.0__5.1:2.0__2.1=10.__10.1:13_13.1:18.0__118.0___IDIAL_
N 0
1 0
0 1
2 10
. 5 0
0 0
0 19 ME O
O O
1 0
0 6
1 0
0 0
0 8
NE O
O O
O 1
5 6
1 1
0 0
0 14 EME O
O O
1 3
5 9
2 0
0 0
0 20 E
O O
O O
O 1
9 0
0 0
0 0
10 EE O
e 0
1 0
2 1
0 0
0 0
0 4
SE O
O O
O 3
1 8
3 0
0 0
0 15 SSE e
0 0
0 3
6 12 2
1 0
0 0
24 5
0 1
0 0
3 2
7 2
0 0
0 0
15 SSN 0
0 0
0 0
2 5
6 0
0 0
0 13 SW 0
0 0
0 1
6 8
11 0
0 0
0 26 USE O
O O
2 1
8 5
5 0
0 0
0 21 W
0 0
0 0
1 8
5 3
0 0
0 0
17 teef 9
0 0
0 0
1 3
1 0
0 0
0 5
NW 0
0 0
0 1
3 2
0 1
0 0
0 7
a t
a 0
0 0
2
?
O O
0 1A TOTAL 0
3 0
5 18 52 102 49 5
0 0
0 231 NUNDER OF CAIJtS FOR C
STABILITY 0
JOINT FREDUENCY DISTR 18UTION OF WI W SPEED AND DIRECTION IN HOURS FOR JAN - K C 1986 PASCUILL CLASS 9 WINB SPEED (N/S) AT 10-e LEVEL WINS 31w r11am
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.s1_ _n 24.t.a 1.1-t.M 1 A-7.0__2.1:3.0__3.1:5.0__5.1:2.0__2.1:10.__10.1:13__13.1:18.0__118.0 _ IGIAL_____
N 0
1 2
9 12 36 77 36 5
0 0
0 178 tee O
O 6
13 14 32 62 26 9
0 0
0 162 E
O O
1 10 20 49 103 29 7
0 0
0 219 EME e
0 1
5 12 48 86 21 1
0 0
0 174 E
o 0
1 3
6 16 14 2
1 0
0 0
43 ESE O
?
1 1
1 12 17 2
0 0
0 0
36 SE O
O 1
4 3
70 40 8
0 0
0 0
76 SSE O
1 0
6 6
12 60 29 0
0 0
0 114 S
0 2
0 3
7 18 42 14 5
0 0
0 91 SSN 0
0 1
13 12 14 26 15 13 0
0 0
94 58 0
1 2
5 11 20 60 16 8
0 0
0 123 WSU 0
1 0
8 12 36 40 2
1 0
0 0
100 W
D 0
2 5
16 41 24 8
1 0
0 0
97 Isef 9
0 1
2 7
45 26 3
0 0
0 0
84 1
0 0
7 7
17 22 lb 1
0 0
0 65 lef--
0 0
1 15 38--
46 22 18 0
0 0
150 T IAL 1
8 20 99 161 454 745 248 70 0
0 0
1806 MLPMR OF CALMS FOR D
STABILITY 2
31
TABLE 4 (3 of 4)
JOINT FREDUENCY DISTRIBU1!ON OF WIND SPEED AND DIRECTION IN HOURS FOR JAN - K C 1996 PAS 0UILL CLASS E WIND SPEED (M/S) AT 10-m LEVEL FIND
. s t :.25__.26:1.0__1.1:1.5__1.6:2.0__~.1:3.0__3.1:5.0__5.1:2. 0__2.1:10._10.1:13__13.1:18.0__:t 18. 0___IDI AL___ __
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.w_ _ u N
1 1
3 14 27 62 84 28 6
0 0
0 226 lee 3
1 7
18 40 78 108 37 3
0 0
0 295 NE 0
0 11 15 24 al 79 24 3
0 0
0 237 EME O
0 3
6 34 66 87 18 6
0 0
0 220 E
1 0
4 5
13 61 45 5
5 0
0 0
139 ESE o
0 4
6 8
47 41 1
0 0
0 0
107 SE 1
1 5
6 9
50 64 7
0 0
0 0
143 SSE 1
0 3
12 21 61 65 8
0 0
0 0
171 S
1 1
4 37 37 59 54 16 1
0 0
0 210 SSW 1
1 6
31 32 9
38 7
0 0
0 0
168 SW 0
3 II 23 31 53 49 4
1 0
0 0
175 WSU 3
1 8
20 33 54 17 7
1 0
0 0
144 W
1 5
15 29 17 32 to 4
0 0
0 0
113 temi 1
4 15 20 22 16 6
0 0
0 0
0 84 MW 3
1 12 22 18 12 20 7
0 0
0 0
95
?
4 5
1?.
90 an sm
_la_
1 0
____0.
0 164 LTAL 19 23 116 276 386 832 825 te7 27 0
0 0
2691 NUMBER OF CALMS FOR E
STABILITY 14 JOINT FRE0tENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN N0tstS FOR JAN - DEC 1996 PASSUILL CLASS F WIND SPEES (M/S) AT 10-m LEVEL W188 a1 err 11 ass
_ w sa M1 75 76:1.0__1.1:1.5__1.&:2.0 ? 1-3.0__3.1:5.0__5.1:2.0 7 1:10*__10.1:13__13.1:18.0__:t18.0___IDIai N
3 1
4 16 12 13 6
1 0
0 0
0 56 lee o
3 9
to 12 12 0
0 0
0 3
0 46 NE 3
2 2
11 15 11 0
0 0
0 0
0 44 EE 5
1 6
12 16 22 4
0 0
0 0
0 E
2 2
6 5
4 5
0 0
0 0
0 0
24 ESE 1
1 4
1 3
5 1
0 0
0 0
0 16 SE O
4 5
10 6
6 0
0 0
0 0
0 31 SSE 1
5 12 16 25 22 2
0 0
0 0
0 83 i
S 5
4 26 44 70 40 5
0 0
0 0
0 194 SSE 3
4 25 44 28 15 0
0 0
0 0
0 119 SW 2
12 29 30 26 5
0 0
0 0
0 0
104 WSU 9
28 35 27 13 0
0 0
0 0
0 118 W
3 14 22 23 17 13 1
0 0
0 0
0 93 UNW 2
10 14 23 I?
2 2
0 0
0 0
0 65 MW 1
9 12 11 3
1 0
0 0
0 0
0 37 ammi 1
2 12 8
_2 8
3 0
0 0
0 0
41.
TOTAL 38 83 216 299 283 193 24 1
0 0
0 0
1137 NURKR OF CALMS FOR F
STABILITY 24 32 9
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9 REVIEW COVER SHEET fEVIEW OT:
HP-1 -2 3 0 (Chance 2) Offsite Dose Calculation Manual (Rev. 5)
PORC REVIEW The PORC has reviewed this ites and determined that a safety evaluation was performed (as applicable), that an unreviewed safety question does not exist (as applicable), that a change to the Technical Specifications is not required, and that nuclear safety is/was not adversely affected.
ORDER RECOMMENDED OF PORC MEMBER PORC MEMBER TOR APPROVAL DATE REVIEW SIGNATURE YES NO Maintenance Superintendent Operations j
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YES No X If the answer to any of the above is yes, complete and attach a 10CTR50.59 Safety Evaluation.
SATETY REVIEW J///b],-
DATE r,/2'//ft TECHNICAL REVIEW
(/lrIS // N z:1w DATE
(, /0 <-/9 L GROUP NEAD REVIEW MM DATE M/8[.
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DATE TEMPORARY APPK0 VAT.*
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i UNT 1 003 Revision 9 43.7 (1 of 1)
RE7 3T C07E1 SIZET HP-1-230 - (change 1) offsit-Dose calculation Manual (Rev. 5) 07:
- 9EC RETEIW The 703C has reviewed shia isas and desaraised shas a safasy evaluastas was performed (as appliaahla), shas as unreviewed satasy quassias daea ses estas (as applisahia),
shas a chasse se the Tashmisal spesifiaastans is nas required, and shas suolaar saf a:7 ta/was ass adversely affestad.
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WATERTORD 3 SES PI. ANT OPERATING MANUAL Checx Block Below
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l[lPORC-5/C CHANGE / REVISION / DEI.ITION REQUEST Procedure No.
HP-t-03o Title.nses oca awunw wec Effective Date (if different from approval date)
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YES NO X -
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YES N0 1
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C1T 1 003 Revision 6 43.7 (1 sf 1)
WATERFORD 3 SES P!. ANT OPERATING MANUAL Check Bleck Below CHANGE / REVISION / DELETION REQUEST ETPCM l[lPORC-S/C Procedure No, M P.I 3 3 o TitleCM4e I h.
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Change the facility as descetbed in the TSAR 7 YES NO V
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' US NO V 3.
Conduct tests / experiments not described in the TSAR?
YES NO l
4.
Require a change to the Technical Specifications?
YES NO /
If the answer to any of the above is yes, c:mplete and attaca a 10CTR30.39 Sa ety Evaluation.
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UNT 1 003 Revision S
'3.,7 (1 of O l
1
Surveillanca Procedura HP-1-230 Offsite Dose Calculation Manual Revision 5 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 PREREQUISITES 4.0 PRECAUTIONS AND LIMITATIONS 5.0 INITIAL CONDITIONS 6.0 MATERIAL AND TEST EQUIPMENT 7.0 ACCEPTANCE CRITERIA 8.0 PROCEDURE 8.1 Site Characteristics 8.2 Radiological Environmental Monitoring Program 8.3 Radiological Environmental Monitoring Interlaboratory Comparison Program 8.4 Liquid and Gaseous Radwaste Block Flow Diagras 8.5 Liquid and Gaseous Waste Sampling and Analysis 8.6 Dose Calculations Due to Liquid Effluents 8.7 Determination of Alarm / Trip Setpoints for Liquid Monitors 8.8 Representative Sampling of Liquids 8.9 Projecting Dose for Radioactive Liquid Effluents 8.10 Dose Rate Due to Caseous Effluents 8.11 Air Dose Calculations Due to Noble Cases 8.12 Dose Calculations Due to Radioiodines and Radioactive Materials in Particulate Torn 8.13 Determination of Alarm / Trip Satpoints for Caseous Monitors 8.14 Projecting Dose for Radioactive Caseous Effluents 8.15 40CrR190 Dose Evaluation 1
Surveillance Procedure IP-1-230 Offsite Dose Calculation Nasual Revision 5 9.0 SETFOINTS 10.0 ATTAC3 DENTS 10.1 Annual Average Dispersion and Deposition Paramet,ers for Areas at or Beyond the Unrestricted Area Boundary (Table 1) (1 page) 10.2 Radiological Environeestal ifonitorias Program (Table 2)
(2 pages) 10.3 Sample Location Table (Table 3) (9 pages) 10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) (1 page) 10.5 RENF Sample Locatiosa Within 2 Niles of Waterford 3 (Figure 1) (1 page) 1 10.6 RENF Sample Locations Withia 10 Miles of Waterford 3 (Figure 2) (1 page) 10.7 REHf Sample Locations Withia 50 Miles of Waterford 3 (Figure 3) (1 page) 10.8 Liquid Waste Maassenest System Effluent Sources and Release Fathways and Points (Figure 4) (2 pages) 10.9 Gaseous Iffluent Sources, Caseous Weste Managenest Systees Effluent Sources, and Enhaust Release Points (Figure 5)
(1page) 10.10 Open Terrain Correction Factor (Figure 6) (1 page) 10.11 Site Related Liquid Dose Factor (Table 5) (1 page) 10.12 Bioaccumulation Factor for Freshwater Fish and Invertebrate and Ingestion Dese Factors for Adults (Table 4) (5 pages) 10.13 Dese Factors for Espesure to a Seet !afinite Cloud of Noble t
Cases (Table 7) (1 page) s l
10.14 !ahalation Dese Factors for chi d (Table 8) (3 pages) p 10.15 Values of L Theta-V (Table 9) ages) fg 10.16 Pathway Dese Factors Due to Radionuclides Other Than Noble Cases, R (Table 10) (19 pages)
I i
10.17 Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes) (Figure 7) (1 page) i l
2
[
i
=
Surveillance Procedure IP-1-230 offsite Dose Calculation Manual Revision 5 10.18 Ananal Average Dispersion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) (1 page) 10.19 Amaual Average Deposition Parameters for Areas at er Beyond the Unrestricted Area Boundary (Table 12) (1 page) 10.20 00CN Technical Specificatiosa Cross-Reference (Table 13)
(1 page) 11.0 C0091ITNENTS AND REFERENCES I.!ST OF IFTECTIVE PAGES Title Revision 5 M
Revision S PP/t" Q
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Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5.
1.0 PURPOSE 1.1 This document provides:
(1) the general characteristics of the Waterford 3 site; (2) the detailed Radiological E' vironmental Moni-a toring Program (REMP); (3) the description of the Radiological t
Environmental Monitoring Interlaboratory Comparison Program; (4) the liquid and gaseous radwaste block flow diagram; (5) the Radioactive Liquid and Gaseous Waste Sampling and Analysis Programs; (6) 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; (7) the general methodology to be used to calculate effluent monitor setpoints and allowable release rates to ensure compliance with the Waterford 3 STS, 10CFR20, and 10CFR50 criteria; (8) the methodology to be used to ensure representative sampling of liquids; and (9) 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 (Nov., 1978) and Regulatory Guide 1.109 (Mar., 1976). 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-plant procedures which are consistent with the methodology presented in this document.
2.0 REFERENCES
2.1 Waterford SES Unit 3 STS (Standard Technical Specifications), Chapter 16 of Waterford 3 FSAR 4
a
furvaillcnca Prsesdura HP-1-230 Offsite Dose Calculation Manual Revision 5 2.1.1 Technical Specification Section 3/4 11.1 2.1.2 Technical Specification Section 3/4.11.2 2.1.3 Technical Specification Section 3/4 11.4 2.1.4 Technical Specification Section 3/4.12.1 2.1.5 Technical Specification Section '3/4.12.3 2.1.6 Technical Specification Section 6.14.1 2.1.7 Technical Specification Section 6.14.2 2.1.8 HP-1-215, NRC Radiological Reporting Requirements 2.2 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases of Gaseous Effluents from Light-Water-Cooled Reactors, July 1977 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of Ef-fluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977 2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluenta for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I. Revision 1, October, 1977 2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978 2.6 Title 10, Code of Federal Regulations, Parts 20, 50 and 100, Latest Edition 5
i
Survsillcnca Prcctdura HP-1-230 Offsite Dose Calculation Manual Revision 5 2.7 Title 40, Code of Federal Regulations, Part 190, Latest Edition 3.0 PREREQUISITES NONE 4.0 PRECAUTIONS AND LIMITATIONS References 2.1.6 and 2.1.7 should be satisfied at all times 5.0 INITIAL CONDITIONS Reference 2.1.6 should be satisfied prior to implementation.
6.0 MATERIAL AND TEST EQUIPMENT NONE 7.0 ACCEPTANCE CRITERIA NONE 8.0 PROCEDURE 8.1 SITE CHARACTERISTICS Waterford 3 SES is located on the west (right descending) bank of the Mississippi River at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of Killona and Taft.
6
~
Survai11caca Precsdura HP-1-230 Offsite Dose Calculation Manual-Revision 5 p
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 natural features' include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchar-train, 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.
I Most of the aan-made features are located on the narrow strip of dry landbetweentheMississipfiRiverandthewetlands. 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), Beker Industries, 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 (LPE) owns and operates the above-mentioned steam electric stations.
A map of the UNRESTRICTED AREA and SITE BOUNDARY for radioactive ef-fluents (Figure 5.1-3) is provided in the STS. LPE will have full control of 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 LPE with the exception of-the bottom lands below mean low water of the Mississippi River.
LPE owns, in title, all surface rights within the exclusion area boundary of the plant. Therd is presently no intention to allow ex-pioration for subsurface minerals from points on the surface of the exclusion area.
7 i
Survaillenca Precsdure HP-1-230 Offsita D:sa Calculatica M:nusi Rsvision 5 The Mississippi River,_ Louisiana Highway 18, the. Missouri Pacific Railroad right-of-way, and the west (right descending) bank levee of the M'ississippi 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 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 estir. ate of the maximum number of fossil plant personnel that would be within the exclusion area at any given time. Evacuation procedures for Waterford SES Units 1 and 2 are described in the Waterford 3 Emergency Plan Implementing Document.
A portion of the land within the SITE BOUNDARY is utilized for agricultural activities. Farmers presently work the land but l
can be expected to actually be in the field less than 10 parcent of the time.
l Fishing in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be ex-l pected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area.
. 8
--w--
---r-
-v-y,
--,w,-
,m----
-m-
-p.-
g w - +c
-er-----e-wwt
+m-
-w--
m Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 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 wor *ers are described in the Waterford 3 x
Emergency Plan Implementing Document.
The Waterford property is shown in Figure 5.1-3 of the 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 j
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 other industrial structures. There is a visitor center approximately 1.0 mile SSW of the plant.
The SITE BOUNDARIES for establishing effluent release limits along with radioactive effluent release points are given in Figure 5.1-3 of the STS. The nearest distances to the boundary line are shown in l
Table 1 of this procedure. The release point elevations for gaseous 1
effluents are provided in Figure 5.1-3 of the STS.
l l
The restricted area, defined for the parpose of controlling ingress into and egress from the site, coincides with the plant area which is enclosed by the plant perimeter fence.
l l
I i
l 9
l l
l
Survaillenca Prsesdura HP-1-230 Offsite Dose Calculation Manual Revision 5 For the purpose of establishing effluent release limits in accordance with 10CFR20 and Appendix I to 10CFR50, the concept of the restricted area, as defined above for the purpose of ingress and egress control, 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 outside the site boundary set forth in Table II, Column,1 of Appendix B to 10CFR20; (2) the concen-tration of radionuclides in liquid effluent at the unrestricted area boundary does not exceed the limits set forth in Table II, Column 2 of Appendix B to 10CFR20; and (3) the cumulative liquid and gaseous a
radionuclide releases do not result in exposures to individuals outside the UNRESTRICTED AREA or SITE BOUNDARY in excess of the limits set forth in Appendix I to 10CFR50.
A 1980 population by annular sectors within 5 miles of 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 l
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.
l 8.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
e I
This section satisfies Surveillance Requirement 4.12.1 of the Waterford 3 STS.
10
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 Table I shows the average annual dispersion parameters for areas at or beyond the exclusion area boundary. This table will be subject to change based on the annual land-use census results. Tables 2, 3 and 4 are the detailed Radiological Environmental Monitoring Program, the Sample Location Table, and the sector and zone designations for the sample locations, respectively. Figures 1, 2 and 3 show the sample locations for samples within 2,10 and 50 miles of Waterford 3, respectively.
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 docu-mented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical 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.
8.3 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM This section satisfies Surveillance Requirement 4 12.3 of the Waterford 3 STS.
4 11 4
Survaillenca Pr:cadura HP-1-230 Offsite Dose Calculation Manual Revision 5 Quality assurance in 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 detail the type of analysis, the preparation (collection) date, the date the results are returned, the mean of the analyses (usually tripli-
. cate), the standard deviation, the date the values are released for information, the known value, the three standard deviation limit, and a two standard deviation /three standard deviation warning / action flag. If the sample analysis indicates.results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report j
is submitted.
i 8.4 LIQUID AND GASEOUS RADWASTE BLOCK FLOW DIAGRAM This section of the document presents the block flow diagrams for i
the.radwaste systems. Any modifications to the radwaste systems I
should be documented in the ODCM. In order to obtain a more detailed description of the various components, see the appropriate sections of the FSAR. Figures 4 and 5 show the existing radwaste systems.
8.5 LIQUID AND GASEOUS WASTE SAMPLING AND ANALYSIS 8.5.1 Liquids 8.5.1.1 At Waterford 3 there are four liquid holdup systems that should always contain detectable activity.
These liquid radiological effluent batch release systems include:
12 l
Survaillcaca Precsdura HP-1-230 Offsite Dose Calculation Manual Revision 5 A. Boric Acid Condensate (BAC) - four tanks B. Waste Condensate (WC) - two tank's C. Laundry Waste (I,W) - two tanks D. Waste Tanks (WT) - three tanks 8.5.1.2 In addition to the tanks above, there are other holdup tanks and sumps that may contain detectable activity. These tanks and sumps include the following:
A. Regenerative W'aste Tank (RWT) - one tank B. Filter Flush Tank (FFT) - one tank C. Turbine Building Industrial Waste Sump (TBIWS) -
two sumps D. Dry Cooling Tower Sumps (DCTS) - two sumps NOTE If flow to the sump is isolated and volume of release is known, sump discharge may be treated as a batch release rather than a continuous release.
13
9 Survaillcaca Pr:csdura HP-1-230 Offsite Dose Calculation Manual Revision 5
- 8. 5.1. 3 If the contents of the RWT or FFT contain detectable
-radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks should be directed to the liquid ra(waste treatment system. The TBIWS shall be required to be sampled and analyzed if any of the following condi-tions exists:
(1) primary to secondary leakage is occurring or (2) activity is present in the secondary system, as indicated by either the steam generator blowdown monitor or secondary sampling and analysis; or (3) activity was present in the TBIWS during the previous four weeks. If none of these situations exists, then the sampling and analysis of this stream need not be performed. Sampling and analysis of the DCTS will be required only when detectable activity exists in the Component Cooling 4
Water System.
8.5.1.4 There are three additional liquid radiological effluent continuo'us releases at Waterford 3.
These include:
A.
Circulating Water Discharge 1.
Steam Generator Blowdown i
2.
Steam Generator Blowdown Heat Exchanger i
i B.
Auxilliary Component Cooling Tower (Water) pumps (ACTP) l 8.5.1.5 The Steam Generator Blowdown will be analyzed weekly via an in-line continuous composite sampler when blowdown is discharged to the waste ponds or l
circulating water discharge.
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14 l
_--n,
=.
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.5.1.5.1 Steam generator blowdown may be routed to the waste ponds only if no detectable radioactivity is present.
8.5.1.6 Sampling and analysis of the steam generator blowdown heat exchanger will be required only when detectable activity exists in the secondary system.
8.5.1 7 Sampling and analysis of the ACTP discharge will be required only when detectable activity exists in the
. Component Cooling Water System.
8.5.2 Gases 8.5.2.1 Waterford 3 gaseous radiological effluent batch releases include:
A.
Waste Gas Holdup Tanks (WGHT) - three tanks within the Gaseous Waste Management System (GWMS)
B.
Containment Purge (CP) 8.5.2.2 Gaseous radiological effluent continuous releases should include:
A.
The Fuel Handling Building (FHB) ventilation exhaust B.
The Containment Purge (CP)
C.
The Plant Stack (PS)
D.
The Main Condenser Evacuation and Turbine Gland Sealing System (MCE & TGSS) 15 L
wrw-
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.5.2.3 For the MCE & TGSS, if no primary to secondary leakage exists, then only the RETS Table 4.11-2 gross beta or samma analysis need be performed. If a primary to secondary leak exists and the release from the MCE & TGSS has not been released via the PS, then the sampling and analysis found in Table 4.11-2 must be performed. A continuous permit should be issued if detectable activity is released through the MCE and TGSS.
8.6 DOSE CALCULATIONS DUE TO LIQUID EFFLUENTS This section presents the calculated methods used for calculating l
liquid effluent doses in accordance with Surveillance Requirements 4.11.1.1.1, 4.11.1.2 and 4.11.1.3.1 of the Waterford 3 Standard Technical Specifications (STS).
NOTE The Waterford 3 Radiological Effluent Technical Specifications (RETS) are a subset of the Waterford 3 STS. For purposes of this document, RETS and STS are interchangeable.
8.6.1 The dose contributions for the total time period at gg g should be determined by calculation at least once every 31 days and a cumulative summation of these total body and any organ doses should be maintained for. each calendar quarter.
These dose contributions should be calculated for all radio-nuclides identified in liquid effluents released to the UNRESTRICTED AREA using the following expression:
16
Sury;illccca Pr:cidura HP-1-230 Offsite Dose Calculation Manual Revision 5 n
Dt1
- O'A Fgg[3 A C
(1) gg gg m
g[g D (2)
D =
gg g
where:
the cumulative dose commitment to the total body or D
=
gg any organ (t) from the liquid effluents for each liquid release in erem during time period (1) the cumulative dose commitment to the total body or D
=
e any organ (t) from the liquid effluents for all (A) time periods a
g{3 At in aren g
the length of the A*
time period over which the At
=
g release is made, in hours the concentration of radionuclide (i) in undiluted C
=
gg liquid effluent during time period At from any g
liquid release, in pCi/el the site-related ingestion dose commitment factor to A
=
gg the total body or any organ (t) for each identified nuclide (i) listed in Table 4.11-1 of the Waterford 3 STS in aree-m1 per br-pci (Table 5) during the near field average dilution factor for Cgg F
=
g 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.
17 P
3 4
g p
.,,,,,v.--
,v.-
,,-_.n--
. Survailla ca Pr:c: dura HP-1-230 Offsite Dose Calculation Manual Revisica 5 liquid radioactive waste flow F
=
1 discharge structure exit flow The liquid radioactive waste flow is the maximum flow from the effluent release. The discharge structure exit flow is the flow during disposal from the discharge structure release point into the receiving water body. For radionuclides not determined in each batch or weekly composite, the dose contri-i bution 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. When the current quarterly composite is analyzed, these contribu-tions will be updated as rppropriate.
2 8.6.2 Equation (2) above for calculating the dose contributions 4
l requires the use of a dose factor, A for each nuclide (i) gg, which embodies the dose factors and dilution factors for the i
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:
I (3) j Agg = K,(U,/D,+ U BF ) DCFgg f g t
where:
U,= 730 kg/yr. adult water consumption 1
i Dw = Dilution factor from near field area to potable water f
l intake = 220 i
{
220 = ava Mississippi flow
}
maximum discharge flow l
i 18 l
1 w
+as--'++--+9er9 g.+,*-pq-,ym-e-my-+=----,gweeppw-,y+s y rtur-&e-T r----->>'Elu-F-P*M&-"74u w
w
@=-yNas- --
- 'C*"--
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Surveillance Procedure KP-1-230 Offsite Dose Calculation. Manual Revision 5 gg = Composite dose parameter for the total body or critical A
organ (t) of an adult for nuclide (i) for all appro-1 priate pathways (ares /hr per pCi/ml) s 3
K, = Units conversion factor,1.14E5 = lo pCi/pci x 10 al/l + 8760hr/yr Uf = 21 kg/yr, adult fish cocsumption BF = Bioaccumulation factor for nuclide (i) in fish (pCi/kg g
per pCi/1) from Table A-1 of Regulatory Guide 1.109 (Table 6)
DCFgg = Dose conversion factor'for nuclide (i) and organ (t) for adults (ares /pci). Values are from Table E-11 of Regulatory Guide 1.109 (Table 6)
Inserting the usage factors of Regulatory Guide 1.109 as appropriate into equation (3) gives:
A
= [(3.78E + 5) + (2.39E + 6)BF ] DCF (4) it g
gg NOTE For other liquid pathways, the appropriate dose factors will be utilized.
I l
i
[
19 a
Survaillcica Prec2 dura HP-1-230 Offsite Dose Calculation Manual Revision 5 8.7 DETERMINATION OF ALARM / TRIP SETPOINTS FOR LIQUID MONITORS Waterford 3 STS 3.3.3.10 and 3.11.1.1 require that the liquid ef-fluent monitoring instrumentation alare/ 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 pCi/ml total activity.) This section presents the method to be used for determining setpoints in accordance with Surveillance Requirements of 4.11.1.1.2 of the Waterford 3 STS.
8.7.1 Determination of Liquid Monitor Setpoints 8.7.1.1 The calculated setpoin'ts for the liquid effluent monitors satisfy the following equation:
a (SF)(RF)(F+f)g[g C i (5)
TMPC (f) where; n
the undiluted effluent gamma concentration in pCi/ml IC
=
g i'I i
for all radionuclides (1). The value will be derived from radioanalysis of liquid effluent to be released.
This value will be supplied for each liquid release.
i 20
S:ry;illocca Pr:c: dura HP-1-230 Offsite Dose Calculation Manual Revision 5 e=
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 spa.
F=
the dilution water flow as determined via pump curves or other apropriate measures that determine currect plant operating configuration in spa.
NOTE F is large compared to f; /. F + f 2 F.
Safety factor to ensure that the effluent limit is SF =
not exceeded. Actual value is set by procedure (in the range 0.5 - 0.9).
Release fraction allocated to this release (to be RF =
used only in situations of simultaneous or concur-rent release).
n C
a C
g[1MPC # j E
~P WC =
lM g
the undiluted nongamma MPC) fraction for all
_ [,
=
MPCj nongamma radionuclides (j) 21
Surveillance Procedure HP-1-230 offsite Dose Calculation Manual Revision 5 C
undiluted samma MPC fraction for all gamma i
=
g radionuclides (i)
MPC)
Maximum Permissible Concentration for the applica-
=
ble nongamma-emitting isotope (j) from 10CFR20, Appendix B, table II, column 2.
Maximum Permissible Concentration for the applica-MPC
=
g ble samma-emitting isotope (i) from 10CFR20, Appendix B, table II, Column 2.
8.7.1.2 The values of C and C) will be measured for each g
release and the parameters for i and F will be supplied based on current plant operating configura-tions. The setpoint will be calculated in terms of pCi/a1 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 II, Column 2 to an UNRESTRICTED AREA.
(
Example:
Assume Cg = 3E-4 pCi/el C) = 3E-4 pCi/n1 f = 50 spa F = 750,000 spa NPCg = 2E-5 pCi/ml MPC) = 3E-7 pCi/ml 22 i
S rv;illecca Pr:ctdura HP-1-230 Offsite Dose Calculation Manual Revision 5 c = (f)T C;TMPC=3l5+
[ = IE+3 2
,, (50 spe) (1E+3) 3E-4 pCi/el)(750,000 rps)
(
c = 4.51E-3 pCi/al Then the SF and RF values can be applied; e.g., SF =
0.8 and RF = 1 because normally concurrent releases will not occur.
c = 3.61E-3 pCi/al 8.8 REPRESENTATIVE SAMPLING OF LIQUIDS 8.8.1 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 lor tanks from which releases are made, the following tests were performed prior to initial use for release purposes.
8.8.1.1 The tank was filled to a known volume.
8.8.1.2 A specific quantity of a selected chemical and/or sediments was added to the tank.
8.8.1.3 Recirculation was initiated through the normal path.
8.8.1 4 Periodic samples was taken until equilibrium is reached.
23
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.8.1.5 The time observed to completely six the tank is used as a minimum recirculation time prior to effluent sampling. Records of the test will be maintained.
4 i
8.9 PROJECTING DOSE FOR RADI0 ACTIVE LIQUID EFFLUENTS t
Technical Specification 3.11.1.3 requires that appropriate subsystems l
of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrea 4
total body or 0.2 ares to any organ in a 31-day period. The following calculational method is provided for performing this dose projection.
At le'ast 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 i
the quarter and multiplied by 31.
If this projected dose exceeds 0.06 mres total body or 0.2 ares any organ, and the Liquid Waste Management System has not been operating, it shall be operated, if I
operation would reduce the monthly projected doses below 0.06 mres f
total body or 0.2 ares any organ.
(This is performed in accordance with Surveillance Requirements 4.11.1.3.1 and 4.11.1.3.2.)
4 i
8.10 DOSE RATE DUE TO GASEOUS EFFLUENTS This section. presents the calculational methods used for calculating gaseous effluent doses in accordance with Surveillance Requirements 4.11.2.1.1 and 4.11.2.1.3 of the Waterford 3 STS.
i
?
l I
e I
24
=:
Surveillance Pr:c: dura HP-1-230 offsite Dose Calculation Manual Revision 5 8.10.1 Real Time Meteorological loput The instantaneous 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 values:
8.10.1.1 Release rate limit for noble gases:
Deb '
(NO)0v i 1 Kg (Q)gy (O
A I*Id ) (9)iv (I)
Des =
(X/Q)0viEl(bi+
i 8.10.1.2 Release rate limit for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days:
D0I = (X/Q)0v i 1 'it (S)iv (0) where:
D
= t e instantaneous dose rate to the total body (b) due eb to noble gases in sector 6 for the release in eres/yr; not to exceed 500 mres/yr Des = the instantaneous dose rate to the skin (s) due to noble gases in sector e for the release in eres/yr; not to exceed 3000 ares /yr 25
S:rvaillccca Pr:c: dura HP-1-230 offsite Dose Calculation Manual Revision 5 D6I = the instantaneous dose rate to the child thyroid (I) for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in sector 6 for the release in units of ares /yr; not to exceed 1500 mres/yr.
X' = a constant of unit conversion, IE6pci/pci.
Xg= the total body dose factor due to games emissions for each identified radionuclide (i) in units of ares /yr 8
per pC1/a (Table 7).
I,g the skin dose factor due to beta emissions for each a
identified radionuclide (i) in units of arad/yr per 3
pCi/m (Table 7).
the air dose factor due to gamma emissions for each M a g
identified radionuclide (i) in units of mead /yr per 8
pCi/a (Table 7).
Pgg = 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 mees /yr per pCi/m3 (Table 10, Page 2). The dose factor is based on the most restrictive group (child) and most restrictive organ at the SITE BOUNDARY.
8 Pgg = (child breathing rate of 3700 m /yr)(DFA ) (K') where g
DFA is the inhalation dose factor for each radio-g nuclide from Table 8.
26
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 n
g{g= summation for all identified radionuclides
~
(Q)g,= the average release rate of noble gas or of Iodine-131, Iodine-133, tritium, and radionuclides in the parti-culate form with half-lives greater than 8 days (i) during the time of release from all vent releases (v). Value is averaged over one hour and is in units of pCi/sec.
(X/Q)g = the average atmosphere dispersion factor at the SITE B0UNDARY for the time of the release in sector 8 in sec/a8 for all vent releases (v). When release time is greater than I hour, the average shall be based on observations of windspeed and atmospheric stability taken at least every hour during the release.
(X/Q)0v ' E0v/
where:
the average wind speed determined at least hourly,
=
during time of the release, in sector 0, at 10 meters above grade, in m/sec L,= 2.032/r0 sj'
- and, g
2.032 = (2/n)5 divided by the width in radians of a 22.5*
- sector, 0=
the distance from the release to the receptor for r
each sector (0) in a, and provided in Table 9.
27 L_.
Surv;ille:ca Pr:ccdura HP-1-230 Offsite Dose Calculation Manual
' Revision 5 I,) = the vertical (z) standard deviation of the materials in the plume, for stability class j, with a correc-tion for additional dispersion within the building wake cavity, restricted by the condition that 3 + 0.5D /n) </3o,)
2 I,3 = (o8 furthermore, zj ' N # j I
when (a,2+0.5D/n)>[ia,)
2 and D, = the maximum adjacent building height (z) either up or downwind from the release point.
o,) = the vertical (z) standard deviation of the material in the plume at the downwind distance for stability class J.
I 28
S2ry;illt:ca Pr:c: dura HP-1-230 Offsite Dose Calculation Manual Revision 5 i
The (X/Q) values to be calculated using the above model will be adjusted to reflect the results of analysis of the straight line trajectory model (Reference 2.2, R.G. 1.111, Sections C.I.c and C.2.c).
This adjustment is accomplished by multiply-ing the (X/Q) values by the correction factors, found
~
in Figure 6, which applies to areas with terrain features similar to those at the Waterford 3 site.
NOTE The Radioactive Effluent Release Report, to be sub-mitted within 60 days after January 1, of each year, shall include an annual summary of hourly meteorological data collected over the previous year. The meteorolog-ical conditions concurrent with the time of release of radioactive materials in gaseous effluents, as deter-mined by sampling frequency and measurements, shall be used for determining the gaseous pathway doses.
8.10.2 No Real Time Meteorological Input (Used in Place of Real Time)
The dose rate due to radioactive materials released in gascons effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following values and expressions:
8.10.2.1 Release rate limit for noble gases:
n K'(X/Q),g{g K Qgy1500eres/yr. total body (9) g n
g + 1.1M ) Q i 3000eres/yr. skin (10)
K'(X/Q),g{g(L g
gy 29
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.10.2.2 Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days a
K' TX7QI, g{g P N g 1500 ares /yr any organ (11) it i Where:
Q
= the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec Ti747,= 1.1E-5 sec/a in the ESE sector at 0.6 mile for 8
all vent releases (v) (the highest calculated annual
~
average dispersion factor at the SITE BOUNDARY)
NOTE All radioiodines are assumed to be released in elemental form.
8.11 AIR DOSE CALCULATIONS DUE TO NOBLE GASES This section presents the calculational methods used for calculating noble gas effluent dose to air in accordance with Surveillance Requirement 4.11.2.2 of the Waterford 3 STS.
l 8.11.1 Real Time Meteorological Input i
The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY will be determined by the following expressions:
I j
30 e
g.
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.11.1.1 During any calendar quarter, for gamma radiation:
a a
6y = (1.14E2)g[g (M ) j{g (At)) (X/Q)3 g (Q)g),
(12)
D g
During any calendar quarter, for beta radiation:
a m
85 = (1.14E2) g[g (N ) j{g (At)) (X/Q) jh(9)ijv (13)
D g
8.11.1.2, During any calendar year, for gamma radiation:
l a
a 6y = (1.14E2) g[g (M ) j[g (At)) (X/Q) jh(9)ijv II')
D g
During soy' calendar year, for beta radiation:
I a
a 6p=(1.14E2)g[g(N)j{g(At)(X/Q)jg(Q)gjy (15)
D g
y where all terms are as previously defined; and 1
6y =
t g t tal sassa (y) air dose in sector 6 from D
gaseous effluents for the total time period (e.g.,
I quarter or year) a jEl 0"j and not to exceed 5 mrad quarterly or 10 mead yearly the total beta (S) air dose in sector 6 from gaseous D
a op effluents for the total time period (e.g., quarter
' [
or year) i a
jEl j
At j-and not to exceed 10 mrad quarterly or 20 mrad yearly i
(1 6pci) (8760hr.)
yr.
1.14E2 m pCi
)
^
31 f
s 4
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5
.o
. Q)f)y the average release rate of radionuclides (i)
(
-=
during the time of release At for vent releases (v) j at) = the length of the j* time period over which (X/Q)gy and Q ), are accumulated for all gaseous releases g
(hours).
?
M and Ng= the gamma and beta air dose factors (respectively) g for a uniform semi-infinite cloud of radionuclide 3
(i) (arad/yr per pCi/m ) (Table 7)
(X/Q)jov = the average atmospheric # di$persionfactoratthe site boundary for thA time of the release (j), in
}
sector (6), in sec/m, for all vent releases (v).
a When release tinea is g: eater than one hour, the average shallibe based on observations of windspeed and atmospheric stability taken at least every hour during the releace.
8.11.2 No Real Time Meteorological Input (Used in Place'of Real Time)
The air dose due to noble geses released.in gaseous effluents to areas at or beyond the SITE BOUNDARY will be determined by the following expressionsLwhen the real time meteorological inputs are not applicable:
0 8.11.2.1 During any calendar quarter, for gar a radiation:
4 a
m (1.14E2) (X/Qi g{g (M ) j{g (At)) (Q)fjy (16)
D =
g y
During.any calendar quarter, for beta radiation:
i n
a p=(1.14E2)(X/Q),g{g(N)3{g(at)(Q)fjy (17)
D g
3 32 E-
,,,.-w
.. - - + -
e-.
v.--y.,4
Surveillance Procedurn HP-1-230 Offsite Dose Calculation Manual Revision 5 8.11.2.2 During any calendar year, for gamma radiation:
n a
- 2) (M), g{g (M ) ){g (At ) (Q)g),
(18)
D8 = (1.1 g
j During any calendar year, for beta radiation; n
a D = (1.14E2) (X/Q),g{g (N ) ){g (4t)) (Q)gjy (19) g where all values are as defined.previously; and the total gamma (y) air dose from gaseous effluents for the D =
total time period and not to exceed 5 mrad quarterly and 10 mrad yearly.
p = the total beta (S) air dose from gaseous effluents for the D
total time period and not to exceed 10 mrad quarterly and 20 mrad yearly.
Q ), = the average release rate of radionuclides (i) in gaseous g
effluent from all vent releases (v) in pCi/sec during the time period At).
(M), = 1.1E-5 sec/m3 in the ESE sector at 0.6 mile for all vent releases (v).
8.12 DOSE CALCULATIONS DUE TO RADI0 IODINES AND RADI0 ACTIVE MATERIALS IN I
PARTICULATE FORM This section g esents the calculational methods uced for calculating J
doses due to Iodine-131, Iodine-133, tritiusi, and radionuclides in particulate form in accordance with Surveillance Requirement 4.11.2.3 of the Waterford 3 STS.
33
Surveillenca Prac; dura HP-1-230 Offsite Dose Calculation Manual Revision 5 8.12.1 Real Time Meteorological Input 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 and beyond the SITE BOUNDARY will be determined by the following expressions:
8.12.1.1 During any calendar quarter for age group a:
n a
D0ca=(1.14E-4)g{3(Rita) jb1 (O'j) I(N)Sjv (0)ijv]
(20) 8.12,1.2 During any calendar year for age group a:
a a
D
=(1.1E-4)g{g(Rgg,) ){g (At)) [(W)0jv (0)ijv]
(21) 0ta where all terms are as previously defined; and D
= the cumulative dose due to Iodine-131, Iodine-133, 0ta tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents, to an organ (t), of an individual (a), in sector 8, for the total time period:
m I at i
3 j=1 not to exceed 7.5 mrem in any calendar quarter or 15 mrem in any calendar year.
1.14E-4 =
87 Chr.
.I l
34 l
l
~
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 the dose factor from each identified radionuclide R
=
ita (i), for each applicable organ (t), and age group 3
. (a), in eres/yr per pCi/m for the inhalation pathway 2
and in eres/yr per pCi/m -sec for the food and ground plane pathway from Table 10. For sectors with real pathways within 5 miles of the plant, the values of R are used based on these real pathways; for sectors g
with no real pathways within 5 miles from the plant, R is used assuming that the cow grass-milk pathway g
exists at the 5-mile distance. (R 's were calculated g
using the methodology found in Reference 2.5, pages 31-36.)
6jv = dispersion parameter for time period (j) and release W
pt (v) for calculation of food pathway dose 6jv * (NO)0vj f r the inhalation pathway W
0jv = (D/Q)0vj f r the food and ground plane pathway W
where (X/Q)0vj is as defined previously; and, (D/Q)0vj = relative deposition for the time period (At)), in sector (0), for release pt (v), in square meters.
When At) is greater than one hour, relative deposi-tion shall be based on observation of atmospheric stability taken at least every hour during At).
fd 0 ev (D/Q)0vj *(0.3927)(r )
0 35
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 where:
(0.3927)r0= are length of the 22.5* sector at distance r I"
0 meters.
f6= wind direction factor; equals 1 if wind in hour t is into sector 0; equals zero if wind is not into sector 8.
dgy = relative deposition rate for ground-level vent release (v) at distance (r ) in sector (0) for all e
stability classes of interest, (meters -1) taken from Figure 7.
8.12.2 ho Real Time Meteorological Input (Used in Place of Real Time).
The dose to an individual from Iodine-131, Iodine-133, tritium, and radienuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the following expressionr:
8.12.2.1 During any calendar quarter:
n Dgg, = 1.14E-4 at I Rig, W Q (22) y gy.
i=1 8.12.2.2 During any calendar year:
n D
= 1.14E-4 at I R S
(23) ita ita v iv i=1 where all terms are as previously defined; and at = the time required for the release in hours for all releases per quarter or per year 36
~
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 Dig, = the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in gaseous effluents; not to exceed 7.5 arem quarterly or 15 ares yearly W,=
the dispersion parameter for estimating the dose to an indi-vidual at the controlling location for long term vent releases (v)
,= (i7Q)y for the inhalation pathway from vent releases W
3 (v) in sec/m, from Table 11 or Table 1, for the critical receptor.
W,=
(D/Q)y for the food and ground plane pathways from 2
vent releases (v) in m, from Table 12 or Table 1, for the critical receptor.
8.13 DETERMINATION OF ALARM / TRIP SETPOINTS FOR GASEOUS MONITORS Waterford 3 STS 3.3.3.11 states that the radioactive gaseous ef-fluent monitoring instrumentation alarm / trip setpoint be set to ensure that the limits of Waterford 3 STS 3.11.2.1 are not ex-ceeded.
l l
37
.w-.
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.13.1 Setpoint Calculations for Gaseous Monitors The calculated high level alare and flow termination trip retpoints will be regarded as the limiting conditions for the actual setpoint adjustments. The gaseous effluent radiation monitor setpoints are usually expressed in pCi/cc. For conservatism, an administrative safety factor SF (% of dose rate limit) will be introduced into setpoint calculation. To allow for multiple sources of release from different or common release points, the allowable operating setpoints will be controlled administrative 1y by allocating a percentage of the total allowable release to each release source (RF).
I 8.13.2 General Gaseous Setpoint Bases Gaseous setpoints will be based on noble gas dose rate (less than or equal to 500 mres/yr total body, and less than or equal to 3000 ares /yr skin). Specifically, gaseous setpoints will be based on the most limiting of the following equations:
8.13.2.1 Total Body
, (500 mres/yr.)(RF)(SF)
(XTQ)y(IE6pCi/pci) n I K Q g gy i=1 a
I Q*
I i=1 Then, based on maximum flow rate, the monitor setpoint SN in uCi/cc can be calculated:
Q tb SN = F,,,
38
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 where:
F,,,
maximum effluent flow rate (cc/sec).
=
n summation of all nuclides considered.
I
=
i=1 Qtb = maximum release rate all wed to give limiting total body (tb) dose of 500 area /yr (pCi/sec).
Kg= the total body dose factor due to gamma emissions for each 3
identified radionuclide (i) in units of area /yr per pCi/m (Table 7).
average release rate of isotope (i) from the release point Q
=
gy (v) in pCi/sec.
RF = release fraction allotted to release point in consideration.
(57Q)y= 1.1E-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.
SF = administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.).
Usually, the SF takes on a value between 0.5-0.8.
39
-r--,,,
-,n.4
-g----
,,-.v-------.-------we.
-wm_.3
,-..y.,,-,, - -,
,--,-----m4-
,._y7,.-
-.-y-,-.---
,--,-i.-,--+-.,w.
Surveillance Procedure-HP-1-230 Offsite Dose Calculation Manual Revision 5 8.13.2.2 For skin (3000 meen/yr.)(RF)(SF)
(25) 9 skin -
(M),(IE6pci/pci)n m
I (Lg + 1.1 M )Qgy g
i=1 a
I Q, i
i=1 SN = S skin Faax where all terms are as defined above except:
Q,g,=
maximum release rate allowed to give limiting skin dose of 3000 meen/yr (pci/sec).
Lg= skin dose factor due to beta emissions for each identified radionuclide (1) in units of arem/yr per pCi/m3 (Table 7).
1.1 = conversion facter to convert from air to skin dose.
Mg= air dose factor due to gamma emissions for identified noble 3 from Table 7.
gas isotope (i) in units of mead /yr per pCi/m 8.13.3 Gaseous Setpoint Calculations Based on Kr-88.
Since the noble gas dose rate is more limiting than the i
~
radiciodine dose rate, the initial monitor setpoints can be based on a conservative count rate using Kr-88 until operating experience is accumulated. Total body dose will be more limiting than skin dose; therefore, the release limit would be 40 L
Surveillance Procedure HP-1-230 offsite Dose Calculation Manual Revision 5 (500 ares /yr.)(RF)(SF)
(24a) g Kr-88,
(X/Q),(le6pci/pci)(KKR-88)
Then, based on maximum flow rate, the monitor setpoint SN in pCi/cc can be calculated:
Kr-88 (26)
SN =
F,,,
where:
4 4
F,,, a maximum effluent flow rate (cc/sec)
NOTE To determine whether total body or skin dose is more I
limiting for Kr-88, equations (24) and (25) are solved for Q Since a lower Q is required to reach Kr-88 Kr-88 the total body limit of 500 mres/yr, the total body dose is more limiting.
8.14 PROJECTING DOSE FOR RADI0 ACTIVE GASEQUS EFFLULUS Technical Specification 3.11.2.4 requires that appropriate subsystems of the Caseous 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 BOUNDARY would exceed, in a 31-day period, either:
0.2 mrad to air from samma radiation; or 0.4 erad to air from beta radiation; or 0.3 mrem to any organ of a KEMBER OF THE PUBLIC.
41
~
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 The following calculational method is provided for performing this dose projection.
At least once every 31 days the samma air dose, beta air dose and the maximum organ dose for the month-to quarter will be divided by the number of 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 Surveillance Requirements 4.11.2.4.1 and 4.11.2.4.2.)
8.15 40CFR190 DOSE EVALUATION This section demonstrates compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Waterford 3 STS. 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 mres to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mres) over 12 consecutive months.
Dose evaluations to demonstrate compliance with the above dose limits need be performed only if the quarterly doses calculated in sections 8.6, 8.10, 8.11 and 8.12 exceed twice the dose limits of STS 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a or 3.11.2.3.b, respectively; i.e., quarterly doses exceeding 3 mrem to the total body (liquid releases), 10 mres to any organ (liquid releases), 10 stad gamma air dose, 20 mrad beta air dose, or 15 mrem to the thyroid or any organ from radioiodines and particulates (gaseous releases). Otherwise, no evaluations are required.
I l
42 l
Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5
/
\\
V For the evaluation of doses to real individuals from liquid releases *,
the same calculational methods as employed in section 8.6 will be used. However, more encompassing and realistic assumptions will be made conderning the dilution and ingestion of radionuclides by individuals who live and fish in the Waterford 3 area. The results of the Radiolosidal Environmental Monitoring Program will be used in determining the realn tic dose based on actual measured radio-i nuclide concentrations. Yor the evaluation of doses to real indivi-duals from gaseous releases, the same calculational methods as employed in sections 8.10, 8.11 and 8.12 will be used.
In sections j-8.10 and 8.11, the total body dose factor should be substituted for the samma air dose factor (H ) to determine the total body dose.
g Otherwise, the same calculational sequence applies. More raalistic l
assumptions will be made concerning the actual location of real,
l individuals, the meteorological conditions, and the consumption of
!O 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 radio-nuclide concentrations.
Cumulative dose contributions from direct radiation, from the reactor unit, and from Radweste Storage Tanks shall be determined utilizing the results of routine plact perimeter surveys, TLD data, or a combination of both when necessary, i
(
9.0 SETPOINTS l,
NONE 10.0 ATTACHMENTS l
10.1 Annual Average Dispersion and Deposition Parameters For Areas At or Beyond the Unrestricted Area Boundary (Table 1) 43 l
l
Surveille.cca Pr:cedurs HP-1-230 offsite Dose Calculation Manual Revision 5 Ov 10.2 Radiological Environmental Monitoring Program (Table 2) 10.3 Sample Location Table (Table 3) 10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) 10.5 REMP Saagle Locations Within 2 Miles of Waterford 3 (Figure 1) 10.6 REMP Sample Locations Within 10 Miles of Waterford 3 (Figure 2) 10.7 REMP Sample Locations Within 50 Miles of Waterford 3 (Figure 3) 10.8 Liquid Waste Management System Effluent Sources and Release pathways and Points (Figure 4) 10.9 Gaseous Effluent Sources, Gaseous Weste Management Systems Effluent Sources, and Exhaust Release Points (Figure 5) 10.10 Open Terrain Correction Factor (Figure 6) 10.11 Site-Related Liquid Dose Factor (Table 5) 10.12 Bioaccumulation Factor for Freshwater Fish and Invertekrate and Ingestion Dose Factors for Adults (Table 6) 10.13 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Cases (Table 7) 10.14 Inhalation Dose Factors for Child (Table 8) 10.15 Values of L-Theta-V (Table 9)
O 44
3:rveillecca Pr:c:duro NP-1-230 Offsite Dose Calculation Manual Revision 5 l
10.16 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R (Table 10) 10.17 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) (Figure 7) 10.18 Annual Average Dispersion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) i 10.19 Annual Average Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary (Table 12) 10.20 ODCN Technical Specifications Cross-Reference (Table 13) 11.0 C0f0flTMENTS AND REFERENCES O
I 4
O 45
ABLE 1 i
mam AWAAGE DISPER$les (I/s) Aus NPOSITION (S/S) WALUES i
SteunB LEW L RELEASE. e 5 CSRRECTED USIME STauM at SPEN TERRAIN FACTORS i
SPECIFIC P4Iu18 SF luTEM ST
_l RELEASE
- TYPE OF DIRECTItu SISieuCE I/O -
I/G I/O B/G It LOCATIGu FBen SITE (NILES)
( KTERS) (SEC/ CMS.uETER) (SEC/CNB. KTER) (SEC/CUS.NETER) (PER SS. ETER) i 2.264 MT MCAY
[
0.000 MY CAY uutEPLETED WWEPLETES MPLETE
- 1.*.7
- 1. *.7
.i l.itt.M ll 1:'!
't:
-47 nf E
3.3.
5 ii.
E UEKT&tLE GARKM u
1.14 1778.
4.M-44 4.M -44 4.1E-44 1.1E-40 S
WEETAKE SaRM5 WNE I.34 2097 2.9E-44 2.9E-46 2.5E-46 5.K-49 S
WEGElaKE u
NE 1.e4 14ev.
- 4. K-46 4.M-46 4.1E-te 9.2E-49 S
W Eia8LE E
EK 4.94 1448.
4.5E-44 4.4E-46 5.M-M 1.1E-40 i
G METABLE GaRSEN E
3.26 5149.
3.6E-47 3.4E-47 2.K-47 4.M-14 1
Elli3tlInil:
'll 1:11 Hil:
i:R$
1:#3 1:113 1:113 UE E TA9LE SARSEN 9.96 1448.
3.1E-46 3.1E-M 2.0E-46 1.1E-40 8
UE KTAKE EARK s SSN G.94 1448.
3.0E-46 3.0E-46 3.E-46 1.M-48 i
E KEETaKE SARKs SW 9.99 1440.
5.1E-46
- 5. 9E-46' 4.
-Se 2.3E-48 w KMRE.aRKu e.94 1.9E-48, WGETa9LE s usu 1448.
5.1E-44 5.eE-44 4.
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in..
1.u-M -
.u-M i.M-M
. M-4 h,
MMW W
G vfGET4KE GARMM Muu
.4 1444.
5.5E-46
.4E-44 4.K -46
. M-40 MMIntf tuMi
.i:
1:18 88:
kMS kH3 1:H2 1:11-11
)!
E MSIKKES E
4.06 1297.
1.tE 1.tE-45 8.9E-44 2.4E-te i
6 K SIK uCES muE 4.00 1297.
9.1 -46 9.
-Se 0.1 -46 2.
-44 9
G RESIK uCES ME 4.96 1448.
6.
-Se 6.
-46 5.
-46 1.
-48 ss G
RESIK K ES EK G.90 1444.
6.
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-46
- 5. M-46 1 1E-04 l'
E K SIK uCES E
2.44 4184.
5.M-47 5.
-47 4.M -4?
6.0E-14 4
- E RESIKKES ESE 3.40 5472.
3.M-47 2.9E-47 2.4E-47 3.9E-10 G
MSIKuCES SE 3.99 6276.
2.M-47 2.2E-47 1.M-47 3.0E-14 i
E RESIK uCES U
1.34 2092.
1.
-46 1.M-44 1.1E-46 3.M-49 i
E K SiK uCES unu 4.90 1440.
5.
-46 5.4E-46 4.K-46 2.0E-40 t
S MSIKMCES Nu 4.94 1448.
7.
-44 7.4E-M e.5E-46 2.M-ee E
RESIK uCES Muu 2.44 3219.
1.M-46 1.5E-46 1.M-46 3.M-49 6
SITE DOUnteRY N
4.00 1297.
1.K -45 1.0E-45 0.9E-46 2.4E-04 l
E SITE B8umMRY EuE 4.64 9M.
1.6E-05 1.K-45 1 4E-05 3.4E-68 G
SITE DeumMRY ME G.64 9M.
- 1. W-05 1.4E-45 1.M-45 2.0E-OS 1
11!! t=:ta?
'"I
- tt ilth 1:52 1:5!!
1:tt!
1:M:t!
E SITE temuMRT ESE 4.69 9M.
1.lE-45 1.1E-05 9.K-M 2.M-00 G
SITE DeputeRY SE 0.44 9M.
1.
-45 4.M-M
.4E 2.4E 40 1.K-05 9.3E 3.tE-es t
E SITE DeunteRT SSE 4.00 6.1 -
~
9.5E-07
.M-4 2.M -49 G
SITE taunteRY 1.44 75.
3.
1111 ::==?
53 1:n afk I:H3 1:fl*
1: lit kif:!:
S
$1TE teumMRT USN 1.50 2414.
1.M-44 1.M-46 1.4E-46 4.9E-49 G
SITE temuMAY u
1.44 lett.
2.X-44 2.2E-84 2.tE-M 7.3E-49 6
SITE tenuteRT unu 8.94 1297. ~
7.M-M 7.M-46
- 6. W-46 2.M-40 E
SITE DeumMRY su 8.00 1297.
9.9E-46 9.K-44 8.M-46 3.2E-40 E
SITE touuMRY Muu 9.94 1440.
9.lE-46 9.0E-46 8.tE-44 2.4E-40_
j HP-1-230, REV. 5
.46 A?IACHMEal? 10.1 (1 of 1)
t.
l.i lm l
t l
Sample Type Esceties Amelysis Fregeoecy Walens 713 A-2. 5-l. C-l. B-2. E-1 yla" l>serterly N/A I
F-2. S-2. E-2. J-2. E-l.
2 L-1. M-1, k-l. F-l 4-3 R-l. A-5. 3-4. 5-5. E-5 F-4. E-4. E-6 F-6. q-5 l
R-6 F-9 C-9. E-15. J-15 s'
E-3e Radialedine med APP-l. APQ-1. APG-1 Groes bete. 1-131 Usekly 285m j,g
~{
a b
i s
Particulates APC-l. APE-30 feetapic Qasrterly compeelta 3700 e /qtr Gremed Water #
ett3-1 y feetapic. E-3 q)sseterly 4 11 tere Brieking Water
- BedG-2. 385-5. Ste-7 E-3 Qearterly compeelte Bemegemeene Groes hete, y iseteric Heathly campeetta 4 litare 8
1-131 Seet-eaetbly composite sarface Unter" StfG-2. SIM-5. Ste-7 E-3 Omerterly campeelte p
y f eetapic Itsethly compeetta 4 litese m t J
i, shorettee sedsment sans-3, $Ho33-l y feetapic Semi-seemelly 2 kilograme s
(
li g
M*Q MT h
Y 4
HEIL pett-4. perg-5.-a.g 44 3 jng4Q-1 y teetapic. 1-131 Semi-me.6thly/moothly 4 liters J Q g i3 3wt 6ish FE-l. FE-2 y f ootegic le sensee er See grees I
g semi-seemelly Feed Nredacts FFF-1 y teetapic At harvest time See grene t
k h
Broad Leef 314-1. BLB-l. 355-46 y feetaple, 1-131 30enthly See grene M**
thee milk semples 3
met cellected
{
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l' I!
i NP-I-230. Revisten 5 g
Attachneet 10.2 (1 of 2)
~
~-
~
n
^
Tabib2sAtimmed)
One er more instruments, such as a presserized ion chamber, for==amartes and reccrding dose rate centimeensly a.
may be used in pisce of, or in addities te, integrating desiseters. A TIS is censidered ese phospher, two or more 7--f v is a pocket are considered t=e er unre desierters. Ge3 graphical limitatican affect siting of desimeters.
b.
Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 he'ars or more after sampling to allow for rades and theren daughter decay. 'If grees beta activity se air particulate samples is greater than tee times the yearly mean of centrol samples,' gamma isetapes analysis shall be performed en the individeal samples. Gamma asetapic analysis means the identificaties and geestificaties of gamme-emitting radieneclides that may be attribestable to the efilmeets from the facility.
Drinking Unter and Surface Water samples are identical samples.
c.
d.
The domestream sample is beyond the mixing asse.
A composite sample will contain aliquets of sample 'mha= propertiemal to the genetity of flowing ligeid that c.
results in a specimes representative of the liquid flew.
f.
Cremad water samples shall be takes uhea this searce is tapped for drinking er irrienties perpenes'ia areas where the hydraulic gradicat er recharge properties are suitable for contaoimati.e.
3 This analysis will be perfereed shes the dose calculated for the comeaupties of water is greater thee 1 eres per year as calculated for maximos orgas aos age groep as per the em (m secties 8.6).
h.
Milk will be cellected seeinenthly when anlants are en pestere, monthly otherwise. If milk sampling is not performed, breed leafy vegetaties will be sampled.
- i. Striped mellet, gizzard shad, f reshester drum, and catfish will be cellected. If they are not available, substitute species will be collected and identified le reporting.
J.
One sangle of each principal class of feed products will be sasyled in se ares irrigated by water is which pleet wastes have been inadverte.atly discharge.1 (see secties 8.5 of this precedere). If harvest occurs more than esce a year, sampling shall be performed daring each discrete harvest. If harvesting occurs cactiemees-
]
ly, sampling shall be monthly. Tehereas and rest predacts will be sampled whos. available.
j i
48 ~
l EP-I-230, Revision 5 Attechneet 10.2 (2 of 2) i i i I
I
_j
TABLE 3
<s SAMPLE LOCATION TABLE (s_-)
LOCATION LOCATION MILES FROM SECTOR H
DESCRIPTION PLANT DIRECT 10H
...... 'J M S E R........................................................................
DIRECT RADIATIOH (TLD)
A-2
( Eastbank ) On fence enclosure 1.1 N
surrounding water tower west of Little Gypsy opposite Etienne St.
Access from River Road (LA 628).
The TLD's are located on the (S) fence opposite the entrance gate to the water teuer.
d-)
( East bank ) On fence enclosing the 0.8 HHE s,*.
transmission tower 0.3 miles west i
(up-river) from Little Cypsy.
Access from River Road (LA 428).
TLD's are located at SW corner of fence enclosure.
)
C-1
( Eastbank ) On fence enclosing the 0.8 NE Little Gypsy Cooling Water Intake.
Access is from River Road (LA 628) across from Little Cypsy Power Station entrance.
TLD's are on the l
south side (inside) of the Cooling Water Intake fence enclosure, directly opposite the entrance gate.
D-2 (Eastbank) Located at USGS, Witness 1.1 ENE Post Survey Marker approximately l
0.3 miles east of Little Cypsy Power Station.
Access from River Road i
(LA 628) near the west and of the Bonne Carre Spillway.
TLD's are on the back of the Survey Marker Sign (located on levee).
E-l
( Westbank ) Located on utility pole 0,2 E
along River Road (LA 18) approxi-mately 0.3 miles east of Waterford 3 plant entrance.
Access from LA 10.
TLD's are on the third utility pole east of the construction
,fs
(
entranca road. 0,3 (I of 9 )
)
HP-t-230, Revision 5 49
Table 3 (continued)
,\\............................................................................
/y LOCATION LOCATION MILES FROM SECTOR HUNDER DESCRIPTIOH PLANT DIRECTICH F.2
( Westbank ) Located on fence f.t ESE enclosure surrounding the LP&L substation on LA 3142.
Access
~
from LA 3t42 approximately 0.2 miles south of LA 10.
TLD's are on the southeast corner of the fence enclosure.
G-2
( Westbank ) Located on utility pole 1.2 SE on East side of LA 3142 near Witco entrance gate (Hext to Union Carbide Star Plant Cate 3).
Access from LA 3142 approximately 0.2 miles north of railroad overpass.
H2 (Westbank) Located on fence enclosure 1.2 S$E to shall road off of LA 3142.
Access from LA 3142 south of railroad overpass
[
)
on east side of LA 3142.
TLD's are on
's >
the south side of the gate for shall road.
(Just south of Texaco pipeline station)
J2 (Westbank ) Located on northeast 1.3 corner of fence enclosing Texaco valve station south of LA 3127.
Access from LA 3127, approximately 0.6 miles west of LA 3127/3142 intersection.
X.1
( Westbank ) Located behind " Private 1.0 SSW l
Road" sign at Cate 0 entrance off of LA 3127.
Access from LA 3127, approximately 1.3 miles west of LA 3127/3142 intersection.
(Cate e is the access to the Waterford 3 suitchyard station) r L.I
( We s tb ank ) located behind " Private 1.0 SW l
Road" sign at LP&L Cate 9 entrance off of LA 3127, approximately 1.6
/~N miles west of LA 3127/3142 inter.
' t section.
(Cate 9 is an access road f '~')
for Waterford 3) l i
l HP-1 230, Revision 5 50 0.3 (2 of 1) 1
+
Table 3 (continued)
/~',.............................................................................
()
LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPT!0H PLANT DIRECT!0H M-1
( Westbank ) Located on south gate 0.7 WSW into the Waterford 1 and 2 fuel oil storage tank enclosure.
Access is either thru LP&L Gate 8, Gate 9 off of LA 3127, the shell access road from LA le between Waterford 3, or thru the Waterford I and 2 access road.
H-1
( Westbank ) Located behind the "No 0.9 W
Trespassing" sign off on Short Street, in Killona, just south of the entrance to killona Elementary School.
P-1 (Westbank ) Located t; hind "":
0.8 WNW e
' r-ter' ;"
4;- on Short Street, 70*
in killona. appae4 e'_-!y a.._,_...'6 LD n Ik T
.i__..6m
.a_
W Husi ~61 Ait. sm/is iFArsid hi9-f.
O h P 0-1
( Westbank ) Located on fence 0.8 HW 3
enclosing air sample station approximately 0.5 miles west of Waterford I and 2 on River Road (LA 19).
R-l (Westbank ) Located on fence 0.5 HHW enclosure for Waterford I and 2 Cooling Water Intake Structure.
i Access is from River Road (LA 19) opposite Waterford I and 2.
TLD's are on the southwest corner of fence.
A-5 (Eastbank) Located on utility 4.5 H
l pole just east of the Shady Hook Trailer Park on Hwy el in La Place.
TLD's are on second ut!!ity pole east of trailer park on north side of Hwy 61 (eastern and of La Place).
'O HP-l-230, Revision 51 0.3 (3 of 1)
I.
.. ~.
Table 3 (continued)
(
LOCATION LOCAT!0H MILES FROM SECTOR
.'~'
NUMBER DESCRIPT!0H PLANT DIRECTION 3-4 (Eastbank) Located on utility pole 3.8 NNE just east 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 gast of access road.
D-5 (Eastbank ) Located on fence gate 4.2 EHE on shell 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 elles north on shell access road from Hwy 61.
/ 'N E-5 (Eastbank) Located on the Harco 4.2 E
(~s/
Substation fence enclosure.
Access from River Road (LA 40) onto Wesco St. (adjacent to Horco Shell Chemical Plant), take Wesco St. to the dead end.
TLD's are located on sixth fence post south of the north substation gate.
4 F-4
( Westbank ) Located on utility pole 3.5 ESE behind blonde brick house on Aquarius St. in Hahnv111a.
Access from River Road (LA 18) and turn onto Oak St.
Follow Cak St. to Hickory St., turn right on Hickory St. and follow to Aquarius St. and turn left.
Blonde brick house is second house on right (west) side of Aquarius St. heading south.
G-4 (Westbank) Located on railroad sign 3.2 1E northwest side of LA 3160/raltroad track intersection.
Adcass from either LA 3127 or River Poad (LA IS) onto LA 3160.
O HP-t-230, Revision $, 0,3 (4 of 9 )
Table 3 (continued)
(-~[2............................................................................
('#
LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLANT O!RECTION H-6 (Westbank ) Located on a construction 5.7 SSE sign on the southwest side of the
,second canal bridge east of LA 3160 along LA 3127.
1 P-6 (Westbank ) Located on utility pole 5.5 WNW 1
at southwest corner of LA 640/
railroad track intersection.
Utility pole is just west of LA 440 and east of radio transmission tower.
G-5 (Westbank) Located on fence post 5.0 HW 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 5 '. 3 NHW enclosing LPtL Laydown Yard on LA 3223 in La Place.
Access from Hwy 61 onto Elm St. (LA 3223),
take Elm St. to the northeast corner of LA 3223/ railroad inter.
section.
TLD's are located on the southeast corner of fence enclosure.
F-?
(Eastbank ) Located on entrance 9.2 E9E gate to Destrehan Substation.
Access from River Road (LH 40),
approximate 0.3 miles east of Luling-Destrehan Ferry, onto Destrehan Road (west of Dunge Corp. Crain Elevator), and proceed to substation gate.
C-9 (Westbank ) Located on back fence 0.1
$E of LP&L District Office in Luling.
Access via Ellington St. from either River Road (LA 10): or Second or Third St. from Paul O
Hallard Rd. (LA 52) to Ellington St.
HP-t-230, Revision 5 53 0.3 (5 of 9i
--u n e ss u a l
Table 3 (continued)
/m t
'x
LOCATION LOCATION MILES FROM SECTOP HUMSER DESCRIPT!0H PLANT
' DIRECTION E-15
( Eastbank ) Located on Kenner 11.8 E
Substation fence enclosure.
Access from either River Road (LA 48) or Hwy 61. turn onto Alliance Ave.
TLO's are located on the north side of the fence enclosure, near a light pole.
J-15
( Westbank ) Located on fence 12.0 enclosure surrounding LP6L 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 on fence at 27.0 E
LP6L General 0(Itce on Delaronde St. in Algiers.
TLD's are on O
the fence facing the M6ssissippi River, in the passageway to the i
transformer shop.
Cirborne 4
APP-1
( Westbank ) Located in soybean 0.9 WNW i
field at northwest corner of Short St. in W111ona.
APQ-I (Westbank ) Located at northwest 0.8 HW corner of soybean fleid on east side of Killona.
Access from River Road (LA 10) approximately 0.6 miles east of LA 18/3141 intersection.
APC-l
( We stbank ) Located at the north 0.5 4E side of the Secondary Hatrology Tower.
- O i
i H?=l-230, Revision 5 At t **h**"t i o ' 3 ( 4 f9>
54
Table 3 (continued)
(
)
LOCATION LOCATION MILES FROM SECTOR DESCRIPT!0H PLANT DIRECT!0H
'.'....HUMBER APC-1 (Eastbank ) Located inside the 0.0 NE Little Gypsy Cooling Water Intake Structure fence enclosure.
APE-30*
(Westbank) Located on the roof of 27.0 E
the LP6L Ceneral Office building en Delaronde St. In Algiers.
FC d Products PPP-1 (Westbank ) Located in' soybean 0.8 WHW field en eastern edge of Millene.
between air saeple stations APP-t and APQ-l.
c d Leaf 1
SLG-1 (Westbank ) Located between LA 10 0.4 HW and soybean fleid on eastern edge Killona, near air sample station APG-1.
SLt-l (Eastbank ) Leested at wooded ares 0.8 HNE at the southwestern corner of the LP6L Little Gypsy plant along River Road, bf SLX 15 *
(Westbanh) Located 3.5 eines 89W 15.0 SSW A
er Des Allemands en Hwy. 90.
gPh E(
3 u i
O HPal-230, Revision 5 SS 0.3 (7 of 9)
I
Table 3 (continued)
, -)
4 LOCATION LOCATION H!LES FRON
$ECTOR HUMBER DESCRIPTION PLANT DIRECTIOH Ingestion Milk NN E.4'
< Westbank ) Located.4 miles west 4.0 E
of the Time $ aver in Hahnv111e off of River Road.
NKO-5 (Westbank ) Located at the Webre's 5.0 H1d
' house, just across LA le from river marker, et the eastern end of
(
a la gg
- Edgard, WKQ f*
Les w a eee e ! % =la, ou psos, M e 2, T40.#
( Easthank ) L..;;ed.t th. LOL' 44-HW h h/Ah6.YN(A 2..) Nie ta ut saw n.td4 AM k
2 44 Mar.
8 b e s t b N sI 1 I T o e w i.a rr. ra m i m a y miles west of i.0 NW 3
MNO-l Waterford 3 at the corner of
'e River Road and Post $4reet in y
- Millona, gb Fich l
l FH-l*
Upstream of the plant intake structure, 4
i FH-2 Downstrees of the plant intake structure.
W;terborne CWJ-l (Westbank ) Located at 40 Arpent 0.3 9
Canal south of the plant.
Access free LA 3f27 through LP4L Cate 8.
The canal is northwest of the shall accese road / railroad track inter =
section.
I HP-l-230, Revision 5 56 Attacheent 10.3 (9 of 9) i
e Table 3 (continued)
LOCAT!0H LOCATION MILES FROM SECTOR HUMSER DESCRIPTION PLANT DIRECT!0H l
DWG-2 (Westbank) Located at the Union 2.0 ESE SWC-2 Carbide drinking water canal.
Access from LA 3142 through Gate 23.
SHWE-3
( We stbank ) Located at the Foot 3.0 E
1 Ferry Landing off of LA 18 in WM *f
O n.,,......s) weM14,At 40 MfMT CMA' gg, g'gg r v g e t. l
. n-s -a
,.n.c a a,n D'
DWE-5 (Eastbank) Located at the 4.5 E
3 SWE-5 St. Charles Parish Waterworks off of River Road (LA 48) near How Sarpy.
DWP-7*
( Westbank ) Located at the St.
6.5 HW SWP-7 John Parish Waterworks off of LA 18 in Edgard.
O DEH0TES CCHTROL LOCATIONS l
i O
HP-t-230, Revision J 0.3 (9 of 9) g
~
.wj i
SECTOR A m 20 E EE51 541035 FOR BASIGIDGICAL SAIFLING Am Moul10BIIIC FOINTS SECTOS MOIEleCIATIBE 2 DIE McIWICIATM CDffERLIE OF SECTOR IN RFCEFFt Tale IIORTE 22 (*
191125 79001 l
FRON FACILITY SECTOR FACILITY 20E O & 360
- A N
4-1 1
225 B
ISE 1-2 2
l 45 C
- IE 2-3 3
1 675 D
EE 3-4 4
90 E
E 4-5 5
I12h F
ESE 5-6 6
135 C
SE 6-7 7
1575 E er SSE 7-8 8
Iso J
S S-9 9
202%
E SSW 9-14 le 225 L
SW le-15 15 2475 M
IdSW 15-24 2e
{
270 m
v 2e-25 25 292%
P lAAd 25-7 38 Mp 3
315 Q
Inf 35 44 4e
)wp' 3375 R
MRI 44-45 45 as-se so k
AREA SEQWrf - As area is identified by a Sector and Zeme designeter. Thus, ares M-1 is that aree d ich lies between 344 3/4 and Ilk degrees true earth free the facility est. to a radies of I elle. Area G-4 weeld be that area between 123 3/4 to 146 h degrees and the 3-and 4-eile arcs free the facility. For Airberee, lagesties (eilk), and Feed Predocts pathweys, the sector designator will he preceded by acremyes AP, M and FP, respectively.
- The letters I and O have been emitted free these sector designators se as to elisimete possible coefusies I.etween letters and e e rs.
i IIP-1-233. Revisies 5 Sg AttacLeent 10.5 (I of I)
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FIGURE Ll0UlD WASTE MANAGEMENT-SYSTEM EFFLUENT SOURCES AND RELEASE PATHWAYS AND POINTS j
RELE g
[N S SOURCES l
runeest anmius l
RAE Ftoon onalNs AND
,Tiill g
neousiniat wasic sears 3
i
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l 63 l
LIP-1-230, Rev.15' -
Attachinent 10.8 (2 of 2)
I
sm d
(
(,
w i
FIGURE 5 GASEOUS EFFLUENT SOUL l CESS GASEOUS WASTE MANAGEMENT SYSTEMS EFFLUENT SOURCES Am EXHAUST RELEASE POINTS I
anEASE POINH SYSmm SOURCES l
PRESSURE DECURATOR AlfTO-ISOIATICII VAB.VE s m 45 DECAT CAS SURCE NEADER g
TANES: ft. ASH TANE.
BADIATION ASTE CAS CAS DECAY g
V01.ilME CTRL TANK.
CAS r,,s,"I FILTER CDwSES$0ss TA81ES. A.S coR:C ACID CONThS.
4
$URCE TANE
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-0648 tjuLNC80 TANK REActuR A AND 3 AND C CD:fT. VENT NEADER dl l
M EQUIP. DRAIN
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SUw VFNT CAS COLLECTION NEADER RA&/ CTS VENT. SYSt.
I llets VtirT GAS Q)LIACT.
1 H
t S
l 4
NEADER. R OIO-CNEM-RADI ATION M*lTORS i
I BAnoRAl0RT. COllNTING 8
ROOM.V1LVE CALLIRY.
REACTOR AUt CONTARIDENT pl M-IRE-Ol00.15 j
l ptCON &REA AND ROOM.
SLDC. VENTILATION PURCE PRM-IBE-Ol00.23 m
y a
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t
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I P uNT STACE rAN i
r-2 Srf i
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g e
i AIFTO R$0LATION VALVE
{
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MAIN CONDENSER EVAC.
g AND lbERINE LI AND
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(40' ELEV)
L 1
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STRAINER W
SEFARATOR g
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i 118ER. MANDIING RHil.DINC g
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y RADIAfl0N NWITORS RrruttlNo cAhAL. CASE 2 SET TO DRAIN
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r ggNST ERHAUSTS. A AND B FAN gggegLgv)
I IIP-1-230 Revision.5 0.9 (1 of 1)
.-, = --
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d 2010%f Nol1038VOD HP-1-230, Revision 5 65 0.10 (1 of 1) ww-
-.-,-v-.--w__.,,--y,,,,,,.,..,,-.m
-,.,-,-y p.,,. -
m-,y
+y_y,.---9
,gey-9 yyg-e-w
TABLE 5 SITE RELATED LIQUD DOSE FACTORS.
-(
Ag = ( 3. 78E+ 05 + 2.39E+ 06BF) )DCFjg
<mres/hr per uCi/ml) 2.1 DCF <mram/pCi>
Ar-UJ f
ELEMENT BFf CI LLI LIVER GI LLI LIVER 3.20E+02
~
Cr-51 2.0E+02 6.69E-07 Mn-54 4.0E+02 1.40E_05 4.57E-06 1.34E+04 4.37E+03 Mn-56 4.0E+02 3.67E_06 1.15E-07 3.51E+03 1.20E+02 Fe-55 1.0E+02 1.09E-06 1.90E-06 2.61E+02 4.55E+02 Fe-59 1.0E+02 3.40E-05 1.02E-05 8.14E+03 2.44E+03 i
Co-58 5.0E+01 1.5tE-05 7.45E-07 1.81E+03 8.93E+01 Co-60 5.0E+01 4.02E-05 2.14E-06 4.82E+03 2.57E+02 Hi-63 1.0E+02 1.88E-06 9.01E-06 4.50E+02 2.16E+03 Hi-65 1.0E+02 1.74E-06 6.86E-08 4.17E+02 1.64E+01 Cu-64 5.LF+01 7.10E-06 8.33E-08 8.51E+02 9.99E 00 i
Zn-65 2.0E+03 9.70E-06 1.54E-05 4.64E+04 7.36E+04 3.56E+03 Sr-89 3.0E+01 4.94E-05
()
1.58E+04 Sr-90 3.0E+0!
2.19E-04 6.13E+03 i
Y-90 2.5E+01 1.02E-04 2r-95 3.3E 00 3.09E-05 9.75E-09 2.55E+02 8.06E-02 2r-97 3.3E 00 1.05E-04 3.39E-10 8.32E+03 2.80E-03 Hb-95 3.0E+04 2.10E-05 3.46E-09 1.51E+06 2.48E+03 I-131 1.5E+01 1.57E-06 5.95E-06 5.69E+0!
2.16E+02 Cs-134 2.0E+03 2.59E-06 1.48E-04 1.24E+04 7.07E+05 Cs-137 2.0E+03 2.11E-06 1.09E-04 1.01E+04 5.21E+05 1.
Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1,1977.
2.
Extracted from Table E-11 of Regulatory Guide 1.109, Revision 1,1977.
HP-1-230, Revision $ 0.11 (1 of 1) 66
- (d.
i TABLE 6 BIOACCUMtTLATION FACTOR FOR FRESHWATER FISH AND INVERTEBRATEI (pci/Kg per pCi/ liter)
FRESHWATER ELEMENT FISH INVERTEBRATE H
9.0E-01 9.0E-01 C
4.6E 03.
9.1E 03 Na 1.0E 02 2.0E 02 P
1.0E 05 2.0E 04
. Cr 2.0E 02 2.0E 03 Mn 4.0E'02 9.0E 04 Fe 1.0E 02 3.2E 03 Co 5.0E 01 2.0E 02 Ni 1.0E 02 1.0E 02 Cu 5.0E 01 4.0E 02 Zn 2.0E 03 1.0E 04 Br 4'.2E 02 3.3E 02 Rb 2.0E 03 1.0E 03 Sr 3.0E 01 1.0E 02 Y
2.5E 01 1.0E 03 r
i Zr 3.3E 00 6.7E 00 l
l 1.
Extracted from Table A-1 of Regulatory Gaide 1.109, Revision.1, 1977.
HP-1-230, Revision 3 0.12 (1 of 5) 67
=
--1e e9-g
--i--
yy.,
mr-'"8*N T e
-W' tw*wT-yP-um---
T8""'-*---r N
-F WT-w t'-etN"""""WT--'---cm='*
w-w*'M**W=w--*"'--'NN'"'--N'--------==-m^*-N
n
=,-o a
2-a
...u..
- ~..
,a a
.x s.
~
-2..,
u ~
..._..__2-.
TABLE 6
).
BI0 ACCUMULATION FACTOR FOR FRESHWATER I
FISH AND INVERTEBRATE (pCi/Kg per pCi/ liter)
FRESHWATER ELEMENT FISH INVERTEBRATE Nb 3.0E-04 1.0E-02 I'
Mo 1.0E 01 1.0E 01 Tc 1.5E 01 5.0E 00 t
Ru 1.0E 01 3.0E 02 Rh 1.0E 01 3.0E 02 Te 4.0E 02 6.1E 03
'l I
1.5E 01 5.0E 00 Cs 2.0E 03 1.0E 03 Ba 4.0E 00 2.0E 02 La 2.5E 01 1.0E 03 i
Ca 1.0E 00 1.0E 03 Pr 2.5E 01 1.0E 03 Nd 2.5E 01 1.0E 03 W
1.2E 03 1.0E 01 Np 1.0E 01 4.0E 02 1.
Extracted from Table A-1.of Regulatory Guide 1.109, Revision 1, 1977.
. HP-1-230, Revision $, 0.12 (2 of 5 )
g
--w
.reew wt--.me,e
,e-m-,
wwm'-w,-,ww-e.w,-mm-ycen.,,,,9 g,-m yy.-ep-m e t-au-vge mm-gF-wwNw--'-g4m-em ww ew gggcyay =
99
_c9"$wi-
?"'-~%
-e 7-^t"^"
v TABLE 6
^
INCESTtra 00$E FACTOR $ FCA Acutr$
l'4Em PE4 8CI INCESTEDI NUCLILE SONE LIvf4 T.AOLY TNYAct0 KIONEY LUNG GI-LLI H
)
NO DATA 1.QSE-01 l.CS E-0 7 1.0Si=07 1.0SE-07 1.0SE-07 1.0SE-07 C 14 2.84E-06 S.68E-07 S. 6 8 E -0 7 5.68E-07 5.68E-07 S.68F-07 S.68E-07 NA 24 1.70E-04 1.7CE-06
- 1. 70E -06 1.TCE-06 1 70E-06 1.70F-06 1.70E-06 4-.
P 32 1.93E-04 1.20r-OS 7.44E-Os NO DATA NC CATA NO DATA 2.17E-05 CR St NO DATA NO CATA
- 2. 6c E -0 9 1.S1E-09 S.86E-10 3.S3E-09 6.69E-07 MN S4 NO UATA 4.575-06
- 8. 72 E -0 7 NO DATA 1.J4E-06 NO DATA 1.40E-OS MN 56 NO DATA 1.1SC-07 2.04!-0 4 NO DATA 1.46E-07 NO DATA 3.67F-06 rE 35 2.7SE-06 1.90F-06 4.4 J C-0 7 40 DATA NO DATA 1.06E-06 1.09E-06 FE $9 4.34E-06 1.02E-OS
- 3. 9 t E-06 NO DATA NO DATA 2.8SE-04 3.40E-05 CO 58 NO DATA 7.4Si-07
- 1. 6 7 E -0 6 NO DATA NO DATA NO DATA
!.51E-05 CO 60 NO DATA 2.14F-06
- 4. 72C-0 6 40 DATA NO DATA NO DATA 4.02E-05 MI 63 1.30E-C4 9.0tf-06
- 4. 36 E-0 6 NO DATA NO DATA NO DATA 1.88E.06 I
(
NI 45 S.28E-07 6.84E-08 3.13 E -0 8 40 OATA NO DATA NO DATA 1.745-06
(
CU 64 NO DATA 8.33E-08
- 3. 9 t E-0 8 No DATA 2.10E-07 NO DATA 7.10E-06 O
ZN 65 4.84E-06 1.34E-05
- e. 9eE -0 6 NO DATA 1 03E-OS NO DATA 9.70F-06
\\- '
2N 69 1.0 3E-08 t.97E-e8
- 1. 3 7 E-0 9 40 DATA 1.20E-08 NO DATA 2.96E-09 i
l sa 83 10 DATA NO DATA 4.02E-08 No DATA NO DATA No DATA S.79E-08 BA 84 NO DATA NO D AT A, S.21E-0 8 NO DATA NO DATA NO DATA 4.09E-13
(
Sm SS NO DATA NO DATA 2.14 E -0 9 NO DATA NO DATA NO DATA LT.E-24 at 86 40 QATA 2.11E-05
- 9. 8 3 E -0 4 NO DATA NO DATA NO DATA 4.16E-06 as 88 NO DATA 6.0SE-08 3.2 t E-0 8 NO D A TA NO DATA NO DATA 8.36E-19 l
I at 89 NO DATA 4.01E-08
- 2. 82 C-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR '89 3.08E-04 NO DATA
- 8. 84 E-0 6 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 No DATA
- 1. 86 E-0 3 No DATA NO DATA No DATA 2.19E-o*
SR 91 S.67E-06 NO DATA 2.29E-17 NO DATA NO DATA M0 DATA 2.70E-05 54 92 2 1SE-06 No DATA 9 30E-0 8 NO DATA NO DATA NO DATA 4.2 6E-05 Y 90 9.62E-09 NO DATA
- 2. 58 E-10 No CATA NO DATA No DATA 1.02E-04 Y 9tM 9.09E-11 NO DATA 3.52E-12 NO CATA NO DATA NO DATA 2.67E-10 Y 91 1.4tE-07 NO DATA
- 3. 7 7 E-0 9 NO DATA NO DATA NO DATA 7.76E-05 Y -92 8.4SE-10 NO CATA 2.47E-11 N0 DATA NO DA TA NO DATA 1.48E-0S
(
HP-1-230, Rev. 5 0.12 (3 of 5) 69 e
em.
ye
---w w
--v
-t-ww----7
-2W v*-"wM P
~ ' '
N i
J TABLE '6 (continued)
INCESil04 005E FACf0*S FCs acutf5 (mmEN Ph4 PCI INGE5ff01 MUCLICE SONt L!vER f.600Y TNY90tc EIONEY LUNC GI-tLI Y 93 2.48E-C9 NO DATA 7.40E-11 NO DATA NO DAT A NO DATA 8.50E-05 24 95 3.04E-08 9.75E-09
- 6. 60E-0 9 NO DATA 1.S3E-08 NO DATA 3.09E-45 28 97 1.68E-09 3 39E-10 1.S S E-10 NO DATA S.12E-10 NO DATA 1.0SE-04 N4 95 6.22E-09 3 46E-09
- 1. 86E-0 9 NO DATA 3 42E-09 NO DA7A 2.10E-05 MO 99 NO DATA 4.31E-06 8.2 0 E-0 7 No DATA 9.76t-06 No DATA 9.99E-04 l
TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1 06E-08 3 42E-10 4 13E-07 i
i' TC101 2.541-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 4U103 1.4SE-07 No UATA 7.97E-04 40 OATA 7.06E-07 NO OATA 2.16E-05 j
2U105 1.54E-08 Nu CATA
- 6. 00 E -01 NO DATA 1 99E-07 NO DATA 9.42E-06 2U106 2.7tE-06 NO DATA
- 3. 48 E-0 7 NO DATA S.11E-06 40 NATA L.78E-04 AG1 tom 1.604-07 1.48E-07
- 8. 79 E-0 8 NO DATA 2 9tE-07 NO DATA 6.04E-05 TE125m 2 6SE-06 9.71E-07 3 59C-07 8.068-07 1.094-05 40 DATA 1.07E-05 FE127* 6.77E-06 2.42C-06 8.2 S E-0 7 1.73E-06 2.75E-05 NO DATA' 2.27E-05
\\
TEt27 1.10E-0F 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129m 1.1SE-05 4 299-06
- 1. A2 E-0 6 3.95E-06 4.80E-OS N0 DATA S.79E-05 FE129 3.14E-08 1.18E-08 7.6s E-0 9 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131m 1.73E-06 8.44C-07 7.0SE-OF 1.34E-06 8.STE-06 NO DATA 4.40E-OS i
TE131 1.97E-08 4 23E-09
- 6. 22 E -09 1.62E-08 8.63E*00 40 DATA 2.79E-09 TE132 2.52E-06 1 63E-06
- 1. 5 4 E -0 6 1.80E-06 1.57E-OS N0 DATA 7.7tE-05 I 130 7.56E-07 2.21E-06
- 8. 40E-0 7 1 49E-04 3.48E-06 No DATA 1 92E-06 1 131 4.14E-06 S.95E-06 3.4tE-06 1 95E-03 1.02E-oS NO DATA 1.57E-06 8 112 2.03E-07 S.43P-07
- 7. 5 3 E-0 7 3 63E-04 4.31E-06 No DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1 03E-OF 4.99E-04 4.SSE-07 NO DATA 2.51E-10 I 135 4.43E-07 1 162-06
- 4. 2 8E -0 7 7.6SE-05 1.46E-06 NO DATA 1.31E-04 C3134 6.22E-05 1.48E-04
- 1. 21 E -0 4 No DATA 4.79E-05 1.59E-05 2.59E-46 C3136 6.5tE-06 2.575-05 1.8SE-OS NO DATA 1.43E-OS 1.96E-06 2.92E-06 C5137 7.97E-0S 1.09E-04 7.14 E -0 5 NO DATA 3.70E-05 1 23E-05 2.11E-06 CS130 S.52E-08 1.09E-07 S. 40 E -0 8 No DATA 8.01E-QA 7.91E-09 4.6SE-13 sA139 9.70E-08 6.9tE-11
- 2. 84 E-0 9 NO DATA 6.46E-11 3 92E-11 1.72E-07
\\
HP-1-230, Rev.'5-70 0.12 (4 of 5 )
m t\\m TABLE 6 (continued)
INGE5fl0N 00$E F AC70R$ Pan 40utf 5 tutEM PLR PCI INCE5fE05 NUCLICE SONE liver f.A00Y THYt010 EIONEY LUNC Cl-LLI SA140 2.03C-05 2.55E-08 1 3 J E -0 6 340 CATA R.67t-09 1.44E-05 4.18E-05 RA141 4.71E-08 1.44C.11
- 1. 5 9E-0 9 90 DATA 3.3tE-tt 2.02E-11 2.22E-17 94142 2.13E-Os 2.19E-11
- 1. 34 k -0 9 no DATA 1.SSE-11 1.24E-11 1.00E-26
...... -.......... -. -.. -. -... - -......... ~
Lat40 2.500-09 1.262-09 J.3JC-10 90 Data NO DAFA N0 CATA 9.2SE-05 LA142 1.2EE-10 S.82!-11 1 45E-11 NO DATA NC OATA 90 CATA 4.2SE-07
- E141 9.36E-09 6.lsE-09 F.19C-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.4SE-09 1.22F-04 1.3SE-10 90 OATA S.37E-10 NO DATA 4.56E-OS CE144 4.AsE-07 2.04E-07
- 2. 62 E-0 8 NO DATA 1.21E-07 40 DATA 1 6SE-04 P a t.4 3 9.20E-09 3 69C-09 4.56E-10 NO DATA 2.13E-09 90 CAfa 4.03E-05 Pal 44 3.01E-11 1.25!-11
- 1. S st.12 No DATA 7.05E-12 No DATA 4.33E-18 Not47 6.29E-09 7.J7E-09
- 4. 3S E-10 90 DATA 4.2SE-09 90 OATA 3.49E-05 m 197 1.03E-07 8.6tE-04 3 01E-Se 90 CATA NO DATA NO DATA 2.82E-05 nr239 1.19E-09 1.17C-10
- 6. 4 S E-11 90 DATA 3.4SE-10 NO DATA
'2.40E-05 I
l l
l l
i 0.12 (5 of 5)
HP-1-230, Rev. 5 71 c-,.,
gw,__,
__p., _,,,, - _, -,,,,,, _ - _ _ _., _., -, - _ - -, _.,.,,,
~%
TABLE 1' 00$t FACT 0t$ FOR EXP05URE TO A StMt.!Nr141TE CLOUD or N0st! GAtt!
NucIlde s.atr*( Nt )
s.$ kin *
- f.j,1 )
,. Ate *( Mi)
,.ledy t Kg ;
Kr.83e 2.88E.04 1.93E.05 7.56E.04 Kr 85e 1.97t.03 1.46t.03 1.23[.03 1.17E 03 Kr.85 1.95t-03 1.34t.03 1.72E-05 1.61E 05 Kr.47 1.03C-02 9.73t.03 6.17E.03 5.92E.03 Kr.88 2.93E-03 2.37t.03 1.52t-02 1.47E-02 Kr.89 1.04E 02 1.01E.02 1.73E.02 1.66E.02 Kr 90 7.83E-03 7.29E.03 1.63E-02 1.56E.02 Ie.131e 1.11E.03 4.76C-04 1.56E-04 9.15E 05 Ie 133's 1.48t.03 9.94t-04 3.27t.04 2.51E.04 Ie 133 1.05E.03 3.06E-04 3.53t-04 2.94E 04 Ie-135e-7.39E.04 7.11E-06 3.36E.03 3.12t-03 i
Ie 135 2.46t.03 1.86E 03 1.92t.03 1.81E.03 l
Ie.137 1.27t.02 1 22t.02 1.51t.03 1.42E 03 Ie 538 4.75E-03 4.13t-03 9.21t-03 8.83E-03 Ar.41 3.28E 03 2.69t-03 9.30E-03 8.84t.03 I
3 ered-e l
pCl-yr 3
eree.e pC1.pr l
2.88t 04 = 2.88 s 10*4 l
I t
O 0.13 (Icf1)
HP-1-230, Rev. 6 72
TABLE 8 ~
INMatafl0N OC1E 8&C7045 F04 CHILO (DFA )
i temEM PE4 PCI INH 4LE04 Cl-LLI NUCLIOE SOME Livte
- f. AODY TNYuGIO E10NEY LuMG H
J N0 oaf 4 3.c4E-07 3.04 E-O f 1.04d=07
- 1. 04 C -0 7 3.04E-07 1.04E-07 C 14 9.70E-04 1 82E-06 1.92E-06 4.E2E-66 8 42E-06 1.87E-06 1.a2E-06 44 24 4.35C-06 4.JS* 06
- 4. 3 3E -0 6 4.34E-on 4.35E-e6 4.35E-06 4 3SE.06 P 32 7.04E-04 1.09E-05 2.6FC-0$
NO DATA NC OATA No DATA 1.14E-05 CR St NO DATA NO DAf4 4 17E-Os 2.J1r-na 6.57E-09 4.59E-06 2.93E-07 MN S4 40 OATA 1.16!-05 2.57F-0e NO DATA 2.71E-06 4 26E-04 6.19F-06 aN 16 40 04fA 4.48E-to S.43E-tt NO DATA 4.52E-10 3.SSE-06 3.33E-05 FE SS 1.2dE-0$ 6.80E-ce
- 2. t G E-0 6 40 CATA NO DATA 3.00E-05 7.75E-07 FE 59 S.59C-06 9.G4E-06
- 4. S t C-0 6 NU oaf 4 NO DATA 3.43C-04 1.9tE-0$
CO $4 40 DATA 4.19E-07 8.SSE-0 7 NO 04f%
NC OATA 2.99C-04 9.29E-06 CO 60 NO DATA 3.SSE-04 6.12 E -0 6 No DATA No DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.2SF-01 7.56E-06 NO DATA NO 04T4 7.43E-05 1.7tf-06 i
- 48 6S 8.'0 0 E-10 7.99E-It 4.44E-11 40 DATA NC OATA 2.21E-04 2.2 7E-05 l
Cu 64 NO 04f4 5.J9E-10 2.90C-10 40 DATA 1.63E-09 2.59E-04 9.92E-06 2.44%
8.tSE-05 3.04E-05 1.90E-05 40 04f4 1.93E-05 2.69E-04 4.41E-06 AM 61 1.81E-11 2.6tt-11 2.4tC-12 NO DATA 1.S8E-Il 3.44E-07 2.75E-06 na 83 40 DATA NO 04f4 1.2 SE-0 7 NO JAT4 NO DATA NO DATA LT E-24 da 24 40 OATA Mu cara 1 4 nt-0 7 40 94f4 NO DATA NC OATA LT E-24 E9 SS NO DATA NO DATA
- 6. 84 E-09 NO DATA NC DATA NO DATA LT E-24 me 46 NO DATA S.36C-05
- 1. 09E.c s 40 CATA NO DATA DC DATA 2.16E-04 At 44 40 DATA 1.S2E-0F 9.90C-04 NO 04fA NO 04T4 NO DATA 4.66E-09 R8 89 NO DATA 9.31C-04
- 7. 0 4 E -0 4 NO DATA MC CATA NO DATA S.11E-10 59 39 1.62E-04 NO DATA 4.6*E-06 NO DATA N0 DATA S.31C-04 4.52E-05 sa 90 2.73E-02 40 NATA
- 1. 74E -0 3 No 0474 NC 04f4 1.99C-03 9.2st-OS 54 94 3.20E-04 40 DATA
- 1. 24 E -0 9 NO DATA NO DATA 1.44E-05 4.708-05 SR 92
- 3. 54 E-09 NO DATA 1.42E-10 NO DAT4 NG OATA 6.49C-06 6.SSE-05 Y 90 1.11E-06 NO DATA
- 2. 9 4f -0 8 NC 04f4 NO DATA 7.07E-05 7.2*E-05 Y. 9tp 1.37E-10 NO DATA 4.9at-17 NO DATA 40 0474 7.60F-07 4.44E-OF Y 91 2.47E-04 NO DATA
- 4. S 9 E -0 6 No DATA Nn DATA 7.10E-04 4.97E-OS Y 92 S.SOE.09 No DATA t.5 7E-t o NO DAT4 40 047A 6.46E-c6 6.46E-c5
, 0.14 (1 of 3)
HP-1-230, Rev. 5 73 i
C TABLE a (Continued) i, i
I.5MaLafluN OLsf FacTues FOR CHILO (DFA )
i l
tueEm Ptt PCI INMALEDI SUCLICE Sugt LIhER f. dO CY THv4080 stomEY LU v4 GI-LLI Y 91 S.04E-08 40 DATA-1.lut-09 40 0474 40 DAf4 2 0tt-05 1.0SE-04 22 91 S.lAT-OS t.15E-0$
1.00E-05 40 DATA 1.61t-05 6.03E-04 1 6SE-05 28 97 S.07E-04 7.J4E-09 4 32E-09 40 04T4 1.054-08 1.06E-09 9.49E-OS 4
44 95 6.3SE-04 2.48E-06 1.77E-06 40 Cafa 2.33E-06 8.66E-04 1.00E-OS MO 99 NO DATA 4.465-04 1.15E-04 NO Daft 1.06E-07 3.66E-OS 1.42E-OS TC 99P 4.81E-13 9.41C-13 1.56E-11 NO DATA 1.37E-11 7.S7E-07 1.30E-04 TC101 2.19E-14 2.30E-t*
2.91E-13 90 04TA 3.17E-13 1.SAE-07 4.4tF-09 au1OS 7.SSE-07 Mc DAT4 2.90E-07 40 DATA 1.10E-04 1.798-04 1.21E-CS AUSGS 4.13E-10 4U DATA 1.SOE-10 mn DATA 3.634-10 4 30E-06 2.69E-05 i
AU104 3 64E-05 40 04fA 4.57E-04 90 DATA 4.97E-0$
3.87E-03 1.16E-04 l
AG110m 4.56E-06 3 00E=06 2.47E-06 40 UATA S.74L-06 1.4eE-03 2.71E-09 TE1254 1.82E-04 6.29E-07 2.47E-0 7 S.203-07 4C OATA 1.29E-04 9.13E-06 TE12Tm 6.72E-04 2.3tt-ce
- 2. 71F-06 1.52E-OS i
TEt21e 5.19E-C6 1 4SE-04 8.22E-07 1.7tt-04 1.166-09 4.76E-04 4.9tE-05 1E129 2.64E-11 9.4SE-12 6.44C-12 1.93E-11 6.*4L-11 7.9tt-07 6.89E-06 TE13tp 3.63E-04 1.60E-04
- 1. 3 7E-0 0 2.64E-08 1.084-07 S.S6E-OS 8 32E-05 fE131 S.87C-12 2.28E-12 1.78C-12 4.S94-12 1.99C-11 S.SSE-07 3.60E-07 fE132 1.30E-07 7.34E-08 7.12E-08 8 34E-08 4.79E-07 1.02E-04 3 72E-05 1 130 2.21E-04 4.4JE-06 2.2sE-06 4.99E-04 6.6th-06 46 OATA 1.3st-04 I 131 1 30E=0S 1.30E-05
- 7. 3 7 E-06 4.39E-03 2.13E-05 NO 04T4 - 7.6st-07 1 132 S.72E-07 1.10E-06 S.0FE-07 S.2 SE-OS 1 69E-06 40 DATA 8.6SE-07 1 133 4.44C-04 S.49C-06
- 2. 00 E-04 1.04E-03 9.13E-06 #0 D4TA 1.4eE-04 I 134 3.17E-07 S.84E-07 2 69E-07 1.37E-01 e.92E-07 no DATA
- 2. Set-07 t 135 1.13E-04 2.16E-06 1.12E-06 2.14C-04 3 62E-06 40 DATA 1.20E-06 C5134
- 1. 76 E-04
- 2. 74C-04
- 6. 0 7 E -0 5 40 DATA e.93E-OS 3.27E-05 1.04E-04 C511e 1.76E-09 4.62E-0$
3.14E-05 40 DATA 2.544-0$
3.93E-04 1.13E-06 C1137 2.4SE-04 2.23E-04 1.4FE-OS 40 CATA 7.63E-05 2.8tE-OS 9.74E-07 C513e 1.71E-07 2.2FE-07
- 2. 3 3E -13 1.56E-04 1.56E-05 HP-1-230, Rev. 5 74 0.14 (2 of 3) p-m.-m-ee.9--
r-w--mg wm..,e.-
9 y
w.* app
,---yw-gg,,
.----,.,,wy,m
-ww-yww
j I
l
,~\\
(J TABLE,8 (continued) 1 i
I INHaL ATION DUSE FACT 04S FOR CHILO (DFA )
1 IPREN, P!4 PCl INMatf01 NUCLIUE BUNE Livt4 f.80CY THva01C E10NEY LUNG St-LLI 0A140 2.00E-OS 1.7SE-04 1.1 F C-0 6 NO DATA S.71L-09 4.7tE-04 2.75E-05 BA141 S.29E-11 2.1SE-14 1.72F-12 NO 04fA 7.54E-14 7.89E-07 F.44E-08 54142 1.35E-11 1.73CalS 7.34C-13 NO CATA 7.374-15 4.44C-07 7.41F-10 LA140 1.74E-07 6.04E-04
- 2. 04 E-0 4 NO DATA NO DATA 4.94E-0$
6.10E-05 LA142 3.50E-10 1.11E-10 3.49E-tt 90 OATA NO DATA 7.3Sf=04 2.0SE-05 CE141 1.06E-OS S.28E-04
- 7. 8 3 C -0 7 NO Cara 2.31E-06 1.47E-04 1.$1E-05 CE143 9.89E-04 S.17E-08 7.77E-09 40 DATA 2.26k-08 3.12E-05 1.44E-05 CE144 1 834-03 S.72C-04 9.77E-OS NO DATA 3.17E-04 1.23C-03 1.0SE-04 pt143 4.99E-06 1 30E-04 2 47E-0F NO DAf4 8.11t-07 1.174-04 2.63E-05 Pat 44 1 6tE-11 4.99E-12 4.10E-13 NO DATA 2 646-12 4.23E-07 S.32E-os N0147 2.92E-06 2.36E-06
- 1. 8 4 f-0 7 10 Daft 1.10E-c6 4.471-05 2.22F-0S w 137 4.41E-09 2.61C-09 1.1 F F -0 9 NO CafA NC OATA 1.11f-0S 2.44E-05 MP239 1.264-07 9.048-09 6.35E-09 MO DATA 2.63E-08 1.S7E-05 1.73E-OS
+
t HP-1-230, Rev. 5' 75 0 14 (3 of 3) w,-p-y-yw-
-n,-,w-.
n_-,w.&---ee-- - -
.-y--.--v_,,,,-----,--,
w---
--- - -- m y-v g,e,g ww,w-,-,-r-
w---,--
,ym,
i O
~
TABLE 9 I
Values of L-Theta-V l
(Inverse Meters-Sewared)
Calculated Usins Oren-Terrain Factors i
i 2
j Pathwavt MILK 00AT e
i s
i M k l
Sector Distance Paseuill Cateserv l,
(Miles) (Meters)
A B
C D
E F
8
(
w N
I E
3.3 5311 5.23E-07 7.70E-07 1.87E-04 5.67E-06 f.01E-06 1.4&E-05 2.35E-05 m
i J
k i
e
,?
l!
t i.
l i
i t
I i
!i
+
ji l
i ;
i iip-1-230 REVISION 5 76 ATTACIIMENT 10.15 (1 of 5) l A
i 4
1
- i t
TABLE.9 (CONT.)
i Values of L-Theta-V
+
(Inverse Meters-Sevared)
Calculated Usins Been-Terrain Factors I
l Pathuav! MILK COWS f'
t I
f Sector Distance Paseuill Cateserv y
j (Miles) (Meters)
A B
C D
E F
6 1
i i
NW 1.1 1770 3.20E-06 1.40E-05 3.1tE-05 7.01E-05 1.03E-04 1.50E-04 2.42E-04
{
l g
NW 4.4 7081 3.44E-07 3.70E-07 9.40E 3.1&E-04 5.10E-06 0.52E-04 1.40E-05 N
4 M
)
I T
l 6
0 i
l j
i
.i I
IIP-1-230, Rev. 5 77 Attachraent 10.15 (2 of 5)
I I
I I
i i' 4
O-O O
l TABLE 9 I
values of L-Theta-U l
(Inverse Meters-Seuared) j i
j Calculated Usins Oren-Terrain Factors t
Pathwavi VEGETABLE GARDEN 2
I I
k Paseuill Cateserv g.
j Sector Distance (Miles) (Noters)
A 8
C 8
E F
G M $}
N 1.1 1770 3.28E-04 1.60E-05 3 19E-05 7.01E-05 1 03E-04 1.58E-04 2.42'-04 I
NNE 1.3 2092 2.42E-04 9.85E-06 2.02E-05 4.44E-05 4.85E-05 1.04E-04 1.43E-04 k
)i l
NE 1.0 1609 3.91E-06 2.12E-05 4.15E-05 8.91E-05 1.30E-04 2.00E-04 3.06E-04 l
ENE 0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.98E-04
)l E
3.2 5150 5.48E-07 8.35E-07 2.01E-06 6.04E-06 9.57E-04 1.54E-05 2.49E-05 ESE 2.3 3701 9.17E-07 2.00E-04 4.55E-04 1.23E-05 1 89E-05 2.99E-05 4.74E-05 SE 2.3 3701 9.17E-07 2.00E-06 4.55E-06 1.23E-05. 1.89E-05 2.99E-05 4.74E-05 S
0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3.98E-04 l
l l
SSW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1 71E-04 2.61E-04 3.98E-04 I
SW 0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1 71E-04 2.41E-04 3.98E-04 WSW 0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1 71E-04 2.61E-04 3.98E-04 l
W 1.1 1770 3.28E-04 1.60E-05 3.19E-05 7.01E-05 1 03E-04 1.58E-04 2.42E-04 t
WNW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3.98E-04 i
NW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.98E-04
[
l NNW 2.9 4467 6.3&E-07 1.08E-06 2.54E-04 7.44E-04 1 17E-05 1.87E-05 3.00E-05 1
IIP-1-230, Revision S 78 ATTACIIMENT 10 15 (3 Of 5)
I
O' O
O TABLE 9 i
Values of L-Theta-V (Inverse Meters-Sevared)
I Calculated Usins Oren-Terrain Factors Pathuavt RESIDENCES Sector Distance Passuill Cateserv (Miles) (Meters)
A B
C D
E F
8 k
N 0.8 1287 7.77E-04 4.13E-05 7.7BE-05 1.59E-04 2.32E-04 3.54E-04 5.40E-04 NNE 0.8 1287 7.77E-04 4.13E-05 7.78E-05 1 59E-04 2.32E-04 3.54E-04 5.40E-04 s
NE 0.9 1448
.4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.99E-04 gj kh ENE 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.98E-04 E
2.4 4184 7.54E-07 1.44E-04 3.35E-04 9.41E-04 1.4&E-05 2.33E-05 3.71E-05 ESE 3.4 5472 5.00E-07 7.13E-07 1.74E-04 5.32E-04 8.49E-04 1.38E-05 2.23E-05 52,
SE 3.9 4276 4.09E-07 5.02E-07 1.2&E-06 4 02E-04 4.50E-04 1.0&E-05 1.74E-05
's t
fh[
W 1.3 2092 2.42E-04 9.85E-06 2.02E-05 4.44E-05 4.85E-05 1.0&E-04 1.43E-04 WNW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.90E-04 NW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1 71E-04 2.41E-04 3.98E-04 s
NNW 2.0 3219 1.15E-06 2.93E-04 4.50E-04 1.69E-05 2.5&E-05 4.02E-05 4.32E-05 l
i I
IIP-1 230, Revision 5 79 0.15 (4.of 5) l i
-l
Y r9 i
Values of L-Theta-V f
(Inverse Meters-Seuared)
Calculated Usins Deen-Terrain Factors I
l Pathuaw! SITE BOUNDARY 1
l Sector Distance Paseuill Cateserv i
(Miles) (Meters)
A B
C D
E F
S i
i N
0.8 1207 7.77E-04 4.13E-05 7.7BE-05 1.59E-04 2.32E-04 3.54E-04 5.40E-04 NNE 0.4 944 2.01E-05 7.94E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 9.61E-04 NE 0.6 964 2.01E-05 7.74E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 9.41E-04 l
ENE 0.4 944 2.01E-05 7.94E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 9.41E-04
~
kI I
E 0.8 1287 7.77E-04 4.13E-05 7.78E-05 1.59E-04 2.32E-04 3.54E-04 5.40E-04 3
ESE 0.4 9&&
2.01E-05 7.94E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 9.41E-04 kI SE 0.6 946 2.01E-05 7.94E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 f.61E-04
\\
f '.
I SSE 0.8 1287 7.77E-04 4.13E-05 7.79E-05 1.5?E-04 2.32E-04 3.54E-04 5.40E-04 I
S 1.4 2575 1.68E-04 5.4&E-06 1.14E-05 2.02E-05 4.21E-05 6.5&E-05 1.02E-04 D'
l SSW 3.1 4989 5.75E-07 9.07E-07 2.1BE-04 4.44E-04 1.02E-05 1.64E-05 2.65E-05
)
j.
SW 3.4 5472 5.00E-07 7.13E-07 1.74E-04 5.32E-04 8.4tE-04 1.38E-05 2.23E-05 jg i
WSW 1.5 2414 1.SSE-04 4.55E-06 1.38E-05 3.29E-05 4.09E-05 7.59E-05 1.19E-04 1
W 1.0 1609 3.91E-04' 2.12E-05 4.15E-05 S.91E-05 1.30E-04 2.00E-04 3.04E-04 l_
j WNW 0.8 1287 7.77E-04 4.13E-05 7.70E-05 1.5tE-04 2.32E-04 3.54E-04 5.40E-04 i
NW 0.8 1287 7.77E-04 4.13E-05 7.70E-05 1.59E-04 2.32E-04 3.54E-04 5.40E-04 j
NNW 0.9 144B 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.41E-04 3.98E-04 1
l l
e 1
IIP-1-230, Revision 5 Be 0.15 (5 of 5) l
)
1 i
i
O O
O.
TABLE 10 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, R i EHVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY: IHHALATIOH AGE GROUP: INFANT (1 OF 4)
HUCLIDE ORCAN D0SE FACTORS (MREM /YR PER UCI/CU.NETER)
TOTAL BODY BOHE LIVER THYROID KIDHEY LUNC GI-LLI H----3
.647E+03
.000E+00
.647E+03
.647E+03
.647E+03
.647E+03 547Et03 CR--51
.892E+02
.000E+00
.000E+00
.575E+02
.132E+02
.128E+05
.357E403 MH--54
.490E+04
.000E+00
.253E+05
.000E+00
.490E+04
.100E+07
.706E*04 i
FE--59
.948E+04
.136E+05
.235E+05
.000E+00
.000E+00
.102E+07
.244E+05 2
CO--58
.182E+04
.000E+00
.122E+04
.000E+00
.000E+00
.777E+06
.111E+05 CO--60
.it9E+05
.000E+00
.802E+04
.000E+00
.000E+00
.451E+07
.319E+05 2H--65
.311F+05
.193E+05
.626E+05
.000E+00
.325E+05
.647E+06
.514E+05 SR--89
.114E+05
.398E+06
.000E+00
.000E+00
.000E+00
.203E+07
.612 Emus SR--90
.259E+07
.409E+08
.000E+00
.000E+00
.000E+00
.it2E+08
.13tE+04
)
2R--95
.203E+05
.tl5E+06
.279E+05
.000E+00
.31tE+05
.175E+07
.217E+05 I--131
.196E+05
.379E+05 7444E+05
.148E+08-
.518E+05
.000E+00
.106E+04 I--133
.560E+04
.132E+05
.192E+05
.356E+07
.224E+05
.000E+00
.216E*04 CS-134
.745E+05
.396E+06
.703E+06
.000E+00
.190E+06
.834E+05
.333E+04 CS-136
.529E+05
.483E+05
.135E+06
.000E+00
.564E+05
.118E+05
.143E-04 CS-137
.455E+05
.549E+06
.612E+06
.000E+00
.172E+06
.713E+05
.133E+04 BA-140
.290E+04
.560E+05
.560E+02
.000E+00
.134E+02
.160E+07
.384E+05 CE-141
.199E+04
.277E+05
.167E+05
.000E+00
.525E+04
.517E+06
.216E+05 l
BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, 1
DEPLETED X/O AND RELATIVE DEPOSITION
. 0.16 (I of 19)
IIP-1-230, Revision $
g
O (3
~
VO TABLE 10 (CONV PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R1 ENVIRONMENTAL PATHUAY-DOSE COHVERSION FACTORS R(I) FOR CASEOUS DISCHARGES PATHWAY: IHRALATION ACE CROUP: CHILD
( 2 0F 4 )
HUCLIDE ORCAN D0SE FACT 0RS (MREH/YR PER UCI/CU. HETER)
TOTAL BODY BONE LIVER THYROID KIDHEY LUNG CI-LLI H----3
.112E+04
.000E+00
.112E+04
.112E+64
.112E+04
.112E+04
.112E+44 CR--51
.154E+03
.000E+00
.400E+44
.855E+42
.243E+02
.176E+45
.198E+04 HH--54
.951E+04
.000E+00
.429E+85
.000E+0e
.166E+05 -
.158E+97
.229E+45 FE--59
.167E+05
.267E+05
.334E+85
.000E+46
. 4 8 6E+ 0 0
.127E+87
.707E+45 C0--58
.316E+04
.000E+00
.177E+64
.006E+64
. 0 0 6E+ 0 6
.111E+07
.344E+45 CO--60
.226E+05
.000E+00
.131E+05
. 0 0 0E+ 4 8
.000E+08
.787E+07
.962E+05 2H--65
.703E+05
.426E+05
.113E+46
.006E+06
.714E+65
.995E+46
.163E+45 SR--89
.l?2E+05
.599E+06
.606E+00
. 00 6E+ 0 6
. 60 6E+ 0 0
.216E+47
.167E+86 SR--90
.644E+07
.101E+09
.006E+44
. 6 0 6E+ 9 9
. 6 6 6E+ 4 4
. 111E+48
.343E+66 ZR--95
.370E+05
.190E+06
.418E+05
.600E+0e
.596E+45
.223E+07
.618E+05 I--131
.273E+05
.481E+05
.481E+05
.162E+08
.788E+05
. e t 6E+ 0 6
.284E+44 I--133
.770E+04
.166E+05
.283E+05
.385E+07
.338E+05
.08DE+98
.548E+64 CS-134
.225E+06
.651E+06
.181E+47
.400E+64
.33SE+86
.121E+06
.385E+64 CS-136
.116E+06
.651E+05
.171E+06
.400E+00
.955E+65
.145E+45
.418E+64 CS-137
.128E+06
.907E+06
.825E+46
.646E+44
.282E+46
.144E+66
.362E+64 BA-140
.433E+04
.740E+05
.648E+02
.000E+49
.211E+02
.174E+07
.182E+86 CE-141
.290E+04
.392E+05
.195E+05
.000E'+64
.855E+04
.544E+96
.566E+05 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHO A VALUE OF 1 FOR X/0, DEPLETED X/G AND RELATIVE DEPOSITION HP-1-230, Revision ' S 82 0.16 (2 of 19) i t
ei T
O O
O TABLE 10 (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, R
~
1 ENVIRONMENTAL PATHWAY-DOSE CONVERSIGH FACTORS RC I) FOR CASEOSS DISCWARGES PATHWAY: INHALATION ACE GROUP: TEEN
( 3 0F 4 )
HUCLIDE ORGAH D0SE FACTORS (MREM /YR PER UCI/CU. METER)
TOTAL BODY BONE LIVER THYROID KIDHEY LUNC
,CI-LLI H----3
.127E+04
.000E+00
.127E+04
.127E+44
.127E+04
.127E+04
.127E+44 CR--51
.135E+03
.000E+00
.000E+04
.750E+02
.307E+02
.214E+85
.306E+44 MN--54
.840E+04
.000E+00
.5itE+05
.000E+09
.127E+05
.198E+47
.668E+05 FE--59
.143E+05
.159E+05
.370E+05
.000E+06
.000E+00
.153E+07
.178E+46 C0--58
.278E+04
.000E+00
.207E+04
.000E+06
.000E+00
.134E+07
.952E+05 C0--60
.198E+05
.000E+00
.t5tE+05
.000E+00
.000E+00
.872E+07
.259E+46 2H--65
.624E+05
.386E+05
.134E+06
.000E+08
.864E+05
.124E+07
.466E+05 SR--89
.125E+05
.434E+06
.000E+00
.000E+06
.006E+00
.242E+07
.371E+46 SR--90
.668E+07
.198E+09
.000E+00
.000E+00
.000E+00
.165E+08
.765E+06 2R--95
.315E+05
.146E+06
.458E+05
.000E+04
.674E+05
.269E+07
.149E+06 I--131
.264E+05
.354E+05
.491E+05
.146E+68
.840E+05
.000E+00
.649E+04 I--133
.622E+04
.122E+05
.205E+05
.292E+47
.359E+05
.000E+00
.193E+05 CS-134
.549E+06
.502E+06
.113E+07
.000E+48
.375E+06
.146E+06
.976E+04 i
CS-136
.137E+06
.515E+05
.194E+06
.000E+08
.118E+06
.178E+05
.109E+05 CS-137
.311E+06
.670E+06
.840E+06
.000E+et
.304E+06
.121E+06
.848E+04 BA-140
.352E+04
.547E+05
,670E+02
.000E+00
.228E+02
.283E+07
.229E+06 CE-141
.217E+04
.284E+05
.190E+05
.000E+06
.889E+04
.614E+06
.126E+06 BASED OH 1 UCI/SEC RELEASE RATE OF EACH I'SOTOPE I AND A VALUE OF t FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION IIP-1-230. Revision 5 83 0.16 (3 of 19) 4
?
TABLE IG (CON' PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R1 I
r ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS RCI) FOR CASE 0WS DISCHARGES PATHWAY: INHALATION AGE GROUP: ADULT (4 0F 4) i HUCLIDE ORCAN D0SE FACT 0RS (MREM /YR PER UCI/CU. METER)
TOTAL BODY BONE LIVER THYROID KIDNEY LUNG GI-LLI H----3
.126E+04
.400E+09
.126E+04
.126E+44
.126E+04
.126E+04
.126E+44 CR--51
.106E+03
.000E+06
.000E+44
.595E+02
.228E+42
.144E+45
.332E+44 MH--54
.630E+04
.000E+00
.396E+05
.000E+48
.984E+04
.140E+47
.774E+45 FE--59
.106E+05
.118E+05
.278E+05
.006E+00
.406E+00-
.302E+47
.188E+46 CO--58
.207E+04
.000E+00
.158E+04
.000E+00
.646E+48
.928E+46
.166E+06 CO--68
.148E+05
.000E+00
.415E+45
.009E+40
.400E+49
.597E+47
. 285E+ 66 ZH--65
.466E+05
.324E+05
.193E+46
. 0 0 0E+ 4 4
.696E+05
.864E+66
.534E+45 i
SR--89
.872E+04
.304E+06
. 00 6E+ 0 4
.000E+44
.006E+44
.146E+07
.356E+46 SR--90
.610E+07
.992E+08
.006E+44
.000E+49
. 04 6E+ 0 4
.966E+07
.722E+66 I
2R--95
.233E+05
.107E+06
.344E+05
.086E+40
.542E+05
.177E+07
.lSeE+46 I--131
.205E+05
.252E+05
.358E+45
.119E+48
.613E+05
.00DE+00
.628E+44
[
I--133
.452E+04
.864E+04
.148E+05
.215E+0?
.258E+45
.040E+48
.888E+04 i
CS-134
.728E+06
.373E+06
.848E+46
.000E+04
.287E+66
.976E+05
.te4E+45 CS-136
.110E+06
.390E+05
.146E+46
.600E+00
.856E+05
.120E+05
.it7E+45 CS-137
.428E+06
.478E+06
.621E+06
. 04 6E+ 0 4
.222E+66
.752E+45
.164E+45-BA-140
.257E+04
.390E+05
.490E+42
.000E+44
.f67E+02
.127E+07
.218E+46
[
I CE-141
.153E+04
.199E+05
.135E+45
. 46 6E+ 8 6
.626E+44
.362E+66
.124E+66 t
I i
BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR M/G, l
DEPLETED X/O AND RELATIVE DEPOSITION i
HP-1-230. Revision 5 84 0.16 (4 of 19) i
TABLE 10 (CON'
~
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R1 ENVIRONMENTAL PATHWAY-DOSE CONVERSIGH FACTORS RCI) FOR CASE 05S DISCHARGES PATHWAY: GROUND-PLANE DEPOSITION AGE GROUP: ALL
'(1 0F 1 )
HUCLIDE ORGAN D0SE FACT 0RS (SO. METER-MREM /YR PER UCI/SEC)
H----3
.000E+00 CR--51
.463E+07 HH--54
.138E+10 FE--59
.27tE+09 CO--58
.376E+09 CO--60
.215E+11 2N--65
.741E+09 SR--89
.215E+05 SR--90
.000E+00 2R--95
.243E+09 I--131
.172E+08 I--133
.245E+07 CS-134
.477E+10 l
CS-136
.150E+09 CS-137
.103E+11 BA-140
.204E+08 CE-141
.136E+08 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF l FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION HP-1-230 Revision'.5 85 Attichment 10.16 (5 of 19) l l
i!
i
O V~
,m TABLE 13 (CON' 4
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R1
~
i ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR CASEOWS DISCHARGES t
PATHWAY: COWS MILK (CONTAMINATED FORAGE)
AGE GROUP: INFANT (1 0F 4) 7 HUCLIDE ORCAN D0SE FACTORS (SO. METER-MREM /YR PER UCI/SEC) a TOTAL BODY B0HE LIVER THYROID KIDHEY LUNC CI-LLI H----3
.238E+04
.000E+00
.230E+04
.230E+04
.238E+04
.238E+04
.238E+04 a
CR--51
.804E+06
.000E+00
.000E+00
.525E+06
.115E+06
.162E+07
.234E+98 j
MH--54
.442E+08
.000E+00
.195E+09
.000E+06
.432E+08
.064E+08
.716E+68 FE--59
.770E+09
.112E+10
.196E+10
.000E+00
.000E+00
.578E+09
.934E+09 C0--58
.300E+09
.000E+00
.121E+09
.000E+06
.000E+00
. 0 0 6E+ 0 6
.302E+09 CO--60
.104E+10
.000E+00
.441E+09
.000E+00
.000E+00
. 0 0 6E+ 0 0
.105E+16 l
2H--65
.439E+11
.277E+11
.951E+11
.000E+00
.461E+11
.000E+00
.863E+11 j
SR--89
.180E+10
.628E+11
.000E+00
.000E+08
.000E+00
.006E+00
.129E+10 i
SR--90
.15~E+12
.608E+12
.000E+00
.000E+00
.006E+06
.006E+00
.759E+16 2R--95
.587E+04
.340E+05
.828E+04
.400E+08
.892E+84
.000E+00
.412E+07
)
I--131
.141E+10
.271E+10
.320E+10
.105E+13
.373E+10
.000E+44
.114E+09 I--133
.155E+08
.363E+08
.529E+08
.962E+10
.704E+08
.006E+04
.895E+07 CS-134
.340E+11
.181E+12
.33?E+12
.000E+44
.867E+11
.356E+11
.915E+49 i
CS-136
.108E+11
.982E+10
.289E+11
.000E+00
.115E+11
.235E+10
.439E+09 CS-137
.213E+11_
.257E+12
.301E+12
.000E+44
.808E+11
.327E+11
.941E+69 l
BA-140
.619E+08
.120E+10
.120E+07
.000E+00
.285E+06
.738E+86
.295E+89 l
CE-141
.155E+05
.216E+06
.132E+06
.606E+06
.407E+05
. 0 0 6E+ 0 0
.682E+68 i
. FOR X/G, BASED OH 1 UCI/SEC RELEASE Rt.TE OF ECCt1 ISGTOPE I AND A VALUE OF 1 i
DEPLETED X/O AND Rit0TIVE DEPOSITION 1
}
~
t HP-1-230. Revision 5 86 0.16 (6 of 19) i l
i
.i :
~
~
~
~
]
tu
~
1 TABLE 19 (CON'T),
0
'd PATHWAY D3SE FALT0RS DDE TO RADIOMSCLIDES OTHER THMI NOBLE EASES, R1 6
ENVIRONMENIAL PATHWAY-DOSE CONVERSION FACTORS RCI) FOR.GASEGWS DISCNARCEs PATHWAY: CCWS MIta (CONTAMINATED FORAGE)
ACE CROUP: CHILD (2 0F 4) s l
NUCLIDE OkCAN DGsE FA C T O R ~5 '
-' SQ. METER-NREM/YR PER UCI/SEC )
TOTAL BeJY BONE LIVER YHYA0!D KIDHEYf LUNG CI-LLI H- --3
.157C+04
.000E+00 157E+02
.137E+04
.1M7F+04
.157E+0f-
.157E+04 CR -51
.500E+06
.000E+00 00 0E+ 0 e
.282E+06
.770E+05
.515E+06
.269E+08 MH -54
.279E*08
.000E+08 195E+09 400E+00
.294E+08
.000E+C0
.879E+08 FE--59
.483E+09
.600E+09
.970E+09
.000E+00
.000E+00
.28iE+09
.401E+10 em CO--58
.185E+09
.aSsE+00
.605E+08
.000E+00
.000E+00
. 0 0 6E+ 0 0
.353E+09 CO--60
.636E+09
.000E*uo
.216E+09
.000E+00
.006E+00
.000E+00
.120E+19 ZN--65
.342E+11 20?E+11 1550E+11
.000E+00
.347E+11
.000E+0C'
.966E+10
-s l
SR -89
.542E+0S
.330E+11
.000E+00
.000E+00
. 0 0 0E+ 0 0
.06DE+0p
.128E+10 l
SR -90
.142E+12
.558E+12
. 0 0 3E+ 0 0
.000E+00
.000E+00
.000E+00
.752E+10
~i
.191E+05
.421E+04
.000E+00
.602E+04
.000E+00
.439E+07 2R -95
.374E+04 1--131
.743E+09
.130E+10
.131E+10
.432E+12
. 'e l 5E+ 13
.000E+00
.itdttG9
'~
I--133
.805E+07
.172E+08
.213E+08
.335E+10
.354E+05
.000E+00
.057E+07 l
CS-134
.388E+11
.112E+12
.184E+12
.es0F+00
.570Et11
.26%E+11
.992E+09' C5-136
.894E+14
.503E+10
.138E+11
. 0 0 0E.+ 0 0 '
.736E+10
.110E= t ?
.486E+09 CS-137
.22mE+11
.161E+12
.154E+12
.000E+00
.503E+11
.181 E+ 1.1 -
. 95 =C- 0 ->
BA-140
.341E+08
.584F*09
.511E+06
.000E+00
.367E+06
.305E+G6 1296E+a9 CE-141
.600E+04
.10'sE+ 06
.54dE+05
.000E+00
.239E405
.000E+00
.E?9E+08 a
r i
s BASED ON 1 UCI/dEu RELEASE RHTE CF EACH 100 TOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED
/0 AND RELAT!vE DEPOSITION z
~
~
87 0.16 (7 or 19)-
IIP-1-230, Revision,5j i
'5 i
'i !
f 9
r.
~
' y) _
~
- v
(_
2
+
TABLE HD (CON'T)
PATHWAY DOSE-FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Ri s
ENVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR CASEOUS-DISCHARGES PATHWAY: COWS MILK (CONTAMINATED FORAGE)
ACE GROUP: TEEN (3 0F 4)
HUCLIDE ORGAH D0SE FACT 0RS (SQ. METER-MREN/YR' PER UCI/SEC )
TOTAL BODY BONE LIVER THYROID KIDHEY LUNG GI-LLI H- --3
.994E+03
.000E+00
.394E+03
.994E+03
.994E+03
.994E+03
.994E+03 CR--51
.249E+06
.000E+00
.000E+00
.138E+06
.546E+05-
.355E+06
.418E+08 MH--54
.139E+08
.000E+00
.700E+0S
.000E+00
.209E+08'
.000E+00
.144E+09 FE -59
,233E+09
.259E+09
.604E+09
.000E+00
.000E+00
.190E+09
.143E+10 CO--58
.913E+08
.000E+00
.396E+00
.000E+00
.000E+00 000E+00
.546E+09 I
CD--60
,313E+09
.000E+00
.139E+09
.000E+00
.000E+00
.000E+00
.181E+10 2N--65
.170E+11
.105E+11
.365E+11
.000E+00
.234E+11
.000E+00
.155E+11 SR--89
.382E+09
.133E+11
.000E+00
.000E+00
.000E+00
.000E+00
.159E+10 SR -90
,816E+11
.330E+12
.000E+00
.000E+00
.000E+00
.00GE+00
.928E+10 -
2R--95
.179E+04
.824E+04
.260E+04
.000E+00
.382E+04
.000E+00
.600E+07-I--131
.403E+09
.536E+09
.750E+09
.219E+12
.129E+10
.000E+00-
.148E+09 i
I--133
.366E+07
.708E+07
.120E+08
.168E+10
.211E+08
.000E+00
.908E+07 I
CS-134
.53tE+11
.486E+11
.it4E+12
.000E+00
.364E+11
.139E+11
.142E+10 CS-136
.589E+10
.223E+10
.877E+10
.000E+00
.477E+10
.752E+09
.705E+09 CS-137
.310E+11
.669E+11
.890E+11
.000E+00
.303E+11
.118E+11
.127E+10 BA-140
.156E+08
.242E+09
.296E+06
.000E+00
.100E+06
.199E+06
.373E+09 CE-141
.340E+04
.443E+05
.296E+05
.000E+00
.139E+05
.000E+00
.846E+08 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q,
. DEPLETED M/O AND RELATIVE DEPOSITION i
t llP-1-230, Revision %
88 0.16 (8 of 19)
}
i
-l s
'/
~*C.^.+
o O
0; TABLE lO'(CON'T) t PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER i
THAN NOBLE GASES, R i
[
l i
,1
\\'
ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARGES i
AGE GROUP: AOULT (4 0F 4) 1 PATHWAY: COWS MILK (CONTAMIHATED FORAGE) 1 i
l HUCLIDE ORGAH D0SE FACT 0RS (SQ.NETER-MREN/YR PER UCI/SEC )
TOTAL 80DY BONE LIVER THYROID KIDNEY
. LUNG GI-LLI i
i H----3
.763E+03
.000E+00
.763E+03
.763E+03
.763E*03.
.763E+03
.763E+03 CR--51
.143E+06
.000E+00
.000E+00
.852E+05
.314E*05
.189E+06
.359E+08 HH--54
.802E+0?
.000E+00
.420E+08
.000E+00
.125E+08
.000E+00
.129E+09 I'
FE--59
.133E+09
.148E+09
.348E+09
.000E+00
.000E400
.973E+08
.116E+10 f
CO--58
.528E+08
.000E+00
.235E+08
.000E+00
.000E+00
.000E+00
.477E+09 CO--60
.181E+09
.000E+00
.820E+08
.000E+00
.000E+00
.000E+00
.154E+10 2N--65
.986E+10
.685E+10
.218E+11
.000E+00
.146E+11
.000E+00
.13?E+11 i
SR--89
.208E+09
.724E+10
.000E+00
.000E+00
.000E+00
.000E+00
..ft6E+10 SR--90
.574E+11
.234E+12
.000E+00
.000E+00
.000E+00
.000E+00
.676E+10 l
2R--95
.102E+04
.47tE+04
.tStE+04
.000E+00
.237E+04
.000E+00
.479E+07
(
I--131
.242E+09
.295E+09
.423E+09
.138E+12
. 724E+09
.000E+00
.it1E+09 i
j
'I--133
.205E+07
.388E+07
.674E+07
.99tE+09
.118E+08
'.000E+00
.606E+07
(
CS-134
.545E+11 200E+11
.666E+11
.000E+00
.216E+11
.716E+10
.it?E+10 i
l CS-136
.372E+10
.131E+10
.517E+10
.000E+00
.287E+10
.394E+09
.587E+09~
l-CS-137
.331E+11
.369E+11
.505E+t1
.000E+00
.171E+11
.569E+10
.977E+09 BA-140
.878E+07
.134E+09
.t68E+06
.000E+00
.572E+05
.964E+05
.276E+09 CE-141
.185E+04
.242E+05
.163E+05
.000E+00
.759E+04
.000E+00
.625E+08 s
I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/Q, i
8ASED OH 1 DEPLETED X/Q AND RELATIVE DEPOSITION 89 0.16 (9 of 19) j' IIP-1-230; Revision 5;
O o
c'
~
TABLE 10 (CON'T)
+
i.
PATIMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Ri l
I l
i
~
EHVIROHMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES 1
AGE CROUP: CHILD (1 0F 3)
PATHWAY: MEAT (CONTANINATED FORAGE) l j
HUCLIDE ORGAH D0SE FACT 0RS (SQ.NETER-NREM/YR PER UCI/SEC )
________________________________________________________EY j
TOTAL BODY B0HE LIVER THYROID KIDH LUNG GI-LLI H----3
.234E+03
.000E+00
.234E+03
.234E+03
.234E+03
.234E+03
.234E+03 3
l CR--51
.8/5E+04
.000E+00
.000E+00
.486E+04
.133E+04
.887E+04
.464E+06 MH--54
.213E+07
.000E+00
.800E+07
.000E+00
.224E+07
.000E+00
.672E+07 FE--59
.302E+09
.375E+09
.606E+09
.000E+00
.000E+00
.176E+09
.63tE+09 i
CO--58
.501E+08
.000E+00
.164E+08
.000E+00
.000E+00
.000E+00
.955E+08 CO--60
.204E<09
.000E+00
.693E+08
.000E+00
.000E+00
.000E+00
.384E+09 l
ZH--65
.62fE+09
.375E+09
,999E+09
.000E+00
.629E+09
.000E+00
.175E+09 SR--89
.137E+08
.480E+09
.000E+00
.000E+00
.000E+00
.000E+00
.186E+08 t
SR--90
.264E+10
.104E+11
.000E+00
.000E+00
.000E+00
.000E+00
.f40E+09 j
2R--95
.520E+06
.266E+07
.584E+06
.000E+00
.836E+06
.000E+00
.609E+09 l
I--131
.94tE+07
.165E+08
.166E+08
.547E+10
.272E+08
.000E+00
.147E+07 t
I--133
.269E+00
.574E+00
.710E+00
.132E+03
.118E+01
.000E+00
.286E+00 CS-134
.314E+09
.907E+09
,149E+10
.000E+00
.461E+09
.165E+09
.802E+07 f
CS-136
.284E+08
.160E+08
.439E+08
.000E+00
.234E+08
.349E+07
.154E+07 CS-137
.188E+09
.133E+10
.t28E+10
.000E+00
.416E+09
.150E+09
.799E+07 i
BA-140
.254E+07
.435E+08
.38tE+05
.000E+00
.124E+05
.227E+05
.220E+08 CE-141
.164E+04
.221E+05
.110E+05
.000E+0D
.484E+04
.000E+00
.138E+08 i
l
~
1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, f
BASED OH 1 DEPLETED X/O AND RELATIVE DEPOSITION L
llP-1-230 Revision 5 90 0.16 (10 of 19)
I
)
r TABLE 10 (CON'T)
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R1 i
l FOR GASEOUS DISCHARGES i
ENVIROHMENTAL PATHWAY-DOSE COHYERSIGH FACTORS R(I)
AGE GROUP: TEEH (2 0F 3)
PATHWAY: MEAT (CONTAMINATED FORAGE)
I N'CLIDE ORCAH D0SE FACTORS (SQ.NETER-NREM/YR PER UCI/SEC)
U
)
____________________________________________________ KIDNEY j
TOTAL BODY BONE LIVER THYROID LUNG GI-LLI H----3
.194E+03
.000E+00
.194E+03
.194E+03
.194E+03
.194E+03
.194E+03 CR--51
.56fE+04
.000E+00
.000E+00-
.312E+04
.123E+04
.801E+04
.943E+06 MH--54
.139E+07
.000E+00
.700E+07
.000E+00
.209E+07
.000E+00
.143E+08 FE--59
.190E+09
.2ftE+09
.493E+09
.000E+00
.000E+00
.156E+09
.it7E+10 i
'CO--58
.323E+08
.000E+00
.140E+08
.000E+00
.000E+00
.000E+00
.193E+09 j
CO--60
.131E+09
.000E+00
.583E+08
.000E+00
.000E+00
.000E+00
.760E+09 j
ZN--65
.405E+09
.250E+09
.868E+09
.000E+00
.555E+09
.000E+00
.367E+09 SR -89
.726E+07
.253E+09
.000E+00
.000E+00
.000E+00
.000E+00
.302E+08 i
SR--90
.199E+10
.805E+10
.000E+00
.000E+00
.000E+00
.000E+00
.226E+09 2R--95
.325E+06
.150E+07
.472E+06
.000E+00
.693E+06
.000E+00
.109E+10 i
I--131
.667E+07
.887E+07
.124E+08
.363E+10
.214E+08
.000E+00
.246E+07
~
I--133
.160E+00
.309E+00
.524E+00
.732E+02'
.920E+00
.000E+00
.397E+00 CS-134
.562E+09
.514E+09
.121E+10
.000E+00
.385E+09
.147E+09
.15tE+08 i
f CS-136
.245E+08
.926E+07
.365E+08
.000E+00
.198E+08
.313E+07
.293E+07 CS-137
.335E+09
.724E+09
.963E+09
.000E+00
.328E+09
.127E+09
.137E+08 I
.152E+07
.236E+08
.289E+05
.000E+00
.980E+04
.194E+05
.364E+08 i
CE-141
.901E+03
.ll?E+05
.784E+04
.000E+00
.369E+04
.000E+00
.224E+08-l UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, 8ASED.0H 1 DEPLETED X/O AHD RELATIVE DEPOSITION i
! 0.16 (11of 19) l IIP-1-230, Revision 5 91 I
i
O O
O TABLE 10 (CON'T)-
PATHWAY DOSE FACTORS DUE T0 RADIONUCLIDES OTHER c
THAN N0BLE GASES, R 1
ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHNRGES 1
i AGE GROUP: ADULT, < 3 0F 3 )
l PATHWAY: MEAT (COHTAMIHATED FORAGE) i HUCLIDE ORCAH D0SE FACT 0RS (SO. HETER-MREN/YR PER UCI/SEC)
UNG i
TOTAL 80DY 80HE LIVER THYROID KIDHEY L
CI-LLI i
H----3
.325E+03
.000E+00
.325E+03
.325E+03
.325E+03
.325E+03
.325E+03 i
l CR--51
.702E+04
.000E+00
.000E+00
.419E+04
.155E+04
.931E+04
.176E+07 MH--54
.175E+07
.000E+00
.917E+07
.000E+00
.273E+07
.000E+00
.281E+08 i
3 l'
FE--59
.238E+09
.264E+09
.62tE+09
.000E+00
.000E+00
.t?4E+09
.20?E+to i
C0--58
.408E+08
.000E+00
.t82E+08
.000E+00
.000E+00
.000E+00
.368E+09 CO--60
.t66E+09
.000E+00
.752E+08
.000E+00
.000E+00
.000E+00
.141E+10 l
2H--65
.5tfE+09
.355E+09
.fl3E+10
.000E+00
.756E+09
.000E+00
.712E+09 f
SR--89
.862E+07
.300E+09
.000E+00
.000E+00
.000E+00
.000E+00
.482E+08 SR--90
.305E+10
.124E+11
.000E+00
.000E+00
.000E+00
.000E+00
.359E+09 2R--95
.406E+06
.187E+07
.599E*06
.000E+00
.940E+06
.000E+00
.190E+10 1
l I--131
.875E+07
.107E+08
.153E+08.
.50tE+10
.262E+08
.000E+00
.403E+07 I
q l
I--133
.196E+00
.370E+00
.643E+00
.945E+02
.fl2E+01
.000E+00
.578E+00 CS-134
.126E+t0
.647E+09
.t54E+10
.000E+00
.498E+09
.165E+09
.269E+08 l
CS-136
.338E+08
.it9E+08
.469E+08
.000E+00
.261E+08
.358E+07
.533E+07 CS-137
.78tE+09
.872E+09
.119E+10
.000E+00
.405E+09
.135E+09
.23tE+08 l
BA-140
.187E+07
.285E+08
.358E+05
.000E+00
.122E+05
.205E+05
.587E+08 CE-141
.107E+04
.140E+05
.946E+04
.000E+00
.440E+04
.000E+00
.362E+08 l
l BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION 1
l L
IIP-1-230, Revision d 92 0.'16 (12 of 19) l t
l O
O O
2 TABLE 10 (CON'T) 4 PATlWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3
+
ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR CASEOUS DfS8HbRGES AGE CROUP: CHILD (1 0F 3)
PATHWAY: LEAFY VEGETABLES t
HUCLIDE O R G A H-D0SE FACT 00S (SQ.NETER-MREM /YR PER UCI/SEC) 4
,----------------------KIDHEY TOTAL 80DY BONE LIVER THYROID LUNG CI-LLI H----3
.400E+04
.000E+00
.400E+04
.400E+04
.400E+04
.400E+04 400E+04 j
l CR--51
.116E+06 000E+00
.000E+00
.645E+05
.176E+05
.it9E+06
.617E+07 i
NH--54
.t??E+09
.000E+00
.664E+09
.000E+00
.386E+09
.000E+00
.557E+09 i
FE--59
.318E+09
.395E+09
.639E+09
.000E+00
,000E+00
.185E+09
.665E+09 CO--58
.196E+09
.000E+00
.64tE+08
.000E+00
.000E+00
.000E+00
.374E+09 CO--60
.it2E+10
.000E+00
.378E+09
.000E+00
.000E+00
.000E+00
.210E+10 ZH--65
.134E+10
.8ttE+09
.216E+10
.000E+00
.136E+10
.000E+00
.380E+09 SR--89
.102E+10
.357E+11
.000E+00
.000E+00
.000E+00
.000E+00
.138E+10 i
SR--90
.315E+12
.124E+13
.000E+00
.000E+00
,000E+00
.000E+00
.167E+11
-l-2R--95
.752E+06
.384E+07
.844E+06
.000E+00
.12tE+07
.000E+00
.881E+09 I--131
.815E+08
.143E+09
.143E+09
.474E+11
.235E+09
.000E+00
.128E+08
)
I--133
.165E+07
.354E+07
.437E+07
.812E+09
.729E+07
.000E+00
.176E+07 l
CS-134
.538E+10
.155E+11
.255E+11
.000E+00
.790E+10
.284E+10
.138E+09 l
CS-136
.144E+09
.8ttE+08
.223E+09
.000E+00
.119E+09
.17?E+08
.783E+07 1
.330E+10
.239E+11
.229E+tt
.000E+00
.746E+10
.268E+10
.143E+09 l
B4-140
.160E+08
.275E+09
.24tE+06
.000E+00
.783E+05
.143E+06
.139E+09 i
CE-141
.483E+05
.652E+06
.325E+06
.000E+00
.143E+06
.000E+00
.406E+09 1
l 1
UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/Q, BASED OH 1 DEPLETED X/G AND RELATIVE DEPOSITION t
. 0.16 (13 of 19)
IIP-1-230, Revision 5 93
TABLE 10 (CON'T) i PATIMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER l
THAN N0BLE GASES, R i
1
)
l ENVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR CASE 008 DISCHARGES AGE GROUP: TEEN (2 0F 3) l PATHWAY: LEAFY VEGETABLES 4
l HUCLIDE ORGAN D0SE FACT 0RS
( SQ. METER-MREM /YR PER UCI/SEC) 1 TOTAL BODY BONE LIVER THYROID KIDHEY LUNG CI-LLI 3
j H----3
.259E+04
.000E+00
.259E+04
.259E+04
.259E+04
.259E+04
.259E+04 q
CR--51
.613E+05
.000E+00
.000E+00
.340E+05
.134E+05
.875E+05
.f03E+08 j
MH--54
.900E+08
.000E+00
.454E+09
.000E+00
.135E+09
.000E+00
.93fE+09 l
FE--59
.16tE+09
.178E+09
.416E+09
.000E+00
.000E+00
.f3tE+09
.983E+09 4
CO--58
.100E+09
.000E+00
.434E+08
.000E+00
.000E+00
.000E+00
.599E+09 CO--60
.560E+09
.000E+00
.249E+09
.000E+00
.000E+00
.000E+00
.324E+10 2H--65
.685E+09
.423E+09
.147E+10
.000E+00
.940E+09
.000E+00
.622E+09 SR--89
.431E+09
.150E+11
.000E+00
.000E+00
.000E+00
.000E+00
.t?9E+10
{i SR--90
.185E+12
.75fE+12
.000E+00
.000E+00
.000E+00
.000E+00
.211E+11 i
ZR--95
.372E+06
.171E+07
.541E+06
.000E+00
.795E+06
.000E+00
.125E+10 l
I--131
.577E+08
.767E+08
.107E+09
.313E+11
.185E+09
.000E+00
.212E+08 I--133
.100E+07
.194E+07
.329E+07
.459E+09
.57?E+07
.000E+00
.249E+07 4
CS-134
.752E+10
.689E+10
.162E+11
.000E+00
.515E+10
.197E+10
.202E+09 I
CS-136
.114E+09
.431E+08
.170E+09
.000E+00
.924E+08
.146E+08
.137E+08 l
.469E+10
.101E+11
.135E+11
.000E+00
.459E+10
.178E+10
.f92E+09 I
BA-140
.884E+07
.137E+09
.168E+06
.000E+00
.570E+05
.113E+06
.212E+09 CE-141
.216E+05
.281E+06
.188E+06
.000E+00
.884E+05
.000E+00
.537E+09
,t BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VnLUE OF 1 FOR M/Q, DEPLETED X/Q AND RELATIVE DEPOSITION l
l 0.16 (14 of 19)
I IIP-1-230, Revision 5 94 i
O o
ad TABLE 10 (CON'T)
I PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER l
l THAN NOBLE GASES, R1 ENVIRONMENTAL PATHWAY-DOSE COHVERSIDH FACTORS R(I) FOR CASE'00S DISCHARGES AGE GROUP: ADULT (3 0F 3)
PATHWAY: LEAFY VEGETABLES HUCLIDE ORGAN D0SE FACT 0RS (SO. METER-MREM /YR PER UCI/SEC)
TOTAL BODY B0HE LIVER THYROID KIDHEY LUHC' CI-LLI H----3
.226E+04
.000E+00
.226E+04
.226E+04
.226E+04
.226E+04
.226E+04 CR--51
.462E+05
.000E+00
.000E+00
.276E+05
.102E+05
.613E+05
.it6E+08 MH--54
.597E+08
.000E+00
.313E+09
.000E+00
.930E+08
.000E+00
.958E+09 FE--59
.tl3E+09
.125E+09
.295E+09
.000E+00
.000E+00
.823E+08
.982E+09 CO--58
.686E+08
.000E+00
.306E+08
.000E+00
.000E+00
.000E+00
.62fE+09 CO--60
.369E+09
.000E+00
.167E409
.000E+00
.000E+00
.000E+00
.314E+10 2H--65
.456E+09
.317E+09
.101E+10
.000E+00
.674E+09
.000E+00
.635E+09 SR -89
.284E+09
.990E+10
.000E+00
.000E+00
.000E+00
.000E+00
.159E+10 SR--90
.148E+12
.605E+12
.000E+00
.000E+00
.000E+00
.000E+00
.175E+11 2R--95
.254E+06
.it7E+07
.375E+06
.000E+00
.589E+06
.000E+00
.119E+10 i
I--131
.66tE+08
.806E+08
.itSE+09
.378E+11
.198E+09
.000E+00
.304E+08 I--133
.tllE+07
.209E+07
.363E+07
.534E+09
.634E+07
.000E+00
.326E+07 CS-134
.882E+10
.453E+10
.100E+11
.000E+00
.349E+10
.tl6E+10
.189E+09 CS-136
.120E+09
.422E+08
.167E+09
.000E+00
.927E+08
.f27E+08
.189E+08 CS-137
.570E+10
.636E+10
.870E+10
.000E+00
.295E+10
.981E+09
.168E+09 BA-140
.837E+07
.120E+09
.16tE+06
.000E+00
.546E+05
.919E+05
.263E+09 f
CE-141
.150E+05
.196E+06
.133E+06
.000E+00
.616E+05
.000E+00
.507E+09 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/O AHD RELATIVE DEPOSITION At tachinent-10.16 (15 of 19)
IIP-1-230, Revision 5 95
i O
O o
TABLE 10 (CON'T)
I PAilWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER i
THAN N0BLE GASES, R i
g 4
l i
I ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR CASEOUS DISCHARCES PATHWAY: COATS MILK (CONTAMINATED FORAGE)
AGE GROUP: INFANT (1 0F 4 )
HUCLIDE ORCAN D0SE FACT 0RS (SO. METER-MREN/YR PER UCI/SEC)
TOTAL 80DY 80HE LIVER THYROID KIDHEY LUNG CI-LLI f
l H----3
.405E+05
.000E+00
.405E+05
.405E+05
.405E+05
.405E+05
.405E+05 CR--51
.966E+05
.000E+00
.000E+00
.630E+05
.138E+05
.123E+06
.28tE+07 i
NH--54
.530E+07
.000E+00
.234E+08
.000E+00
.518E+07
.000E+00
.859E+07 I!
FE--59
.100E+08
.146E+08
.254E+08
.000E+00
.000E+00
.75tE+07
.121E+08 CO--58
.360E+08
.000E+00
.145E+08
.000E+00
.000E+00
.000E+00
.362E+08 l
CO--60
.125E+09
.000E+00
.529E+08
.000E+00
.000E+00
.000E+00
.126E+09 l,
ZH--65
.527E+10
.333E+10
.114E<t1
.000E+00
.554E+10
.000E+00
.964E+10 1
SR--89
.376E+10
.132E+12
.000E+00
.000E+00
.000E+00
.000E+00
.271E+10 j
SR--90
.325E+12
.128E+13
.000E+00
.000E+00
.000E+00
.000E+00
.159E+ll j
2R -95
.705E+03
.408E+04
.994E+03
.000E+00
.107E+04
.000E+00
.495E+06 I--131
.169E+10
.326E+10
.384E+10
.126E+13
.448E+10
.000E+00
.137E+09 I--133
.186E+68
.436E+08
.635E+08
.115E+11
.840E+08
.000E+00
.107E+08 CS-134
.302E+12
.542E+12
.101E+13
.000E+00
.260E+12
.107E+12
.275E+10 j
CS-136
.324E+11
.295E+11
.867E+11
.000E+00
.345E+11
.706E+10
.132E+10 CS-137
.640E+11
.772E+12
.903E+12
.000E+00
.242E+12
.982E+11
.282E+10 i
BA-140
.743E+07
.144E+09
.144E+06
.000E+00
.342E+05
.885E+05
.354E+08 CE-141
.186E+04
.260E+05
.158E+05
.000E+00
.488E+04
.000E+00
.818E+07 l
I k
l BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION j
, 0.16 (16 of 19) l!
IIP-1-230. Revision k 96 a
l I
i.
O o
o TABLE ID (CON'T)
TN O
PATIMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R
.f i
v i
ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARCES AGE GROUP: CHILD
( 2 - OF 4 )
PATHWAY: COATS MILK (COHTAMIHATED FORAGE)
HUCLIDE ORCAN D0SE FACT 0RS (SO. METER-MREM /YR PER UCI/SEC)
LUNC GI-LLI TOTAL BODY BONE LIVER THYROID KIDNEY H----3
.267E+05
.000E+00
.267E+05 *
.267E+05
.267E+05
.267E+05
.267E+05 CR--51
.609E+05
.000E+00
.000E+00
.338E+05
.924E+04
.618E+05
.323E+07 1
MH--54
.335E+07
.000E+00
.126E+08
.000E+00
.353E+07
.000E+00
.106E+48 FE--59
.629E+07
.780E+07
.126E+08
.000E+00
.000E+00
.366E+07
.f3fE+08 CD--58
.222E+08
.000E+00
.727E+07
.000E+00
.000E+00
.000E+00
.424E+08 CD--60
.764E+08
.000E+00
.259E+08
.000E+00
.000E+00
.000E+00
.143E+09*
l 2H--65
.411E*10
.248E+10
.660E+10
.000E+00
.416E+10
.000E+00
.itdE+10 l
SR--89
.198E+10
.694E+11
.000E+00
.000E+00
.000E+00
.000E+00'
.268E+10 l
SR--90
.297E+12
.it?E+13
.000E+00
.000E+00
.000E+00
.000E+00
.158E+11 2R--95
.449E+03
.230E+04
.505E+03
.000E+00
.722E+03
.000E+00
.527E+06 l
I--131
.892E+09
.156E+10
.157E+10
.519E+12
.258E+10
.000E+00
.140E+49 l
I--133
.966E+07
.206E+08
.255E+08
.474E+10
.425E+08
.000E+00
.103E+08 i
CS-134
.it6E+12
.337E+12
.552E+12
.000E+00
-.171E+.12
.614E+11
.298E+10 l
CS-136
.268E+11
.351E+11
.415E+11
.000E+00
.22tE+11
.329E+10
.146E+10 i
.683E+11
.484E+12
.463E+l2
.000E+00
.151E+t2
.543E+11
.290E+10
}
BA-140
.409E+07
.701E+08
.614E+05
.000E+00
.200E+05
.366E+05
.355E+08 l
CE-141
.970E+03
.131E+05
.653E+04
.000E+00
.286E+04
.000E+00
.815E+07 i
BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR N/0, DEPLETED X/O AND RELATIVE DEPOSITION l
I HP-1-230. Revision 5- 0.16 (17 of 19) 97 t
i l
O o
o TABLE 10 (CON'T) i I
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3
j i
1 i
ENVIROHHEHTAL PATHUAY-DOSE COHVERSION FACTORS R(I) FOR CASEOUS DISCHARGES 1
l PATHWAY: COATS MILK (CONTAM1 HATED FORAGE)
ACE GROUP: TEEN
( 3 0F 4 )
i l,
HUCLIDE ORGAN D0SE FACT 0RS (SG. HETER-MREH/YR PER UCI/SEC) j l
TOTAL BODY BONE LIVER THYROID KIDNEY LUNC CI-LLI 1
H----3
.169E+05
.000E+00
.169E+05
.169E+05
.169E+05
.169E+05
.t69E+05 CR--51
.299E+05
.000E+00
.000E+00
.166E+05
.655E+04
.427E+05
.502E+07 MH--54
.167E+07
.000E+00
.84tE+07.
.000E+00
.25tE+07
.000E+00
.172E+08 FE--59
.303E+07
.336E+07
.785E+07
.000E+00 900E+00
.247E+07
.t86E+08 l
CO--58
.110E+08
.000E+00
.476E+07
.000E+00
.000E+00
.000E+00
.656E+08 1'
C0--60
.376E+08
.000E+00
.167E+08
.000E+00
.000E+00
.000E+00
.217E+09 2H--65
,205E+10
.126E+10
.439E+10
.000E+00
.28tE+10
.000E+00
.186E+10 SR--89
.802E+09
.280E+11
.000E+00
.000E+00
.000E+00
.000E+00
.334E+10 J
SR--90
.17tE+12
.694E+12
.000E+00
.000E+00
.000E+00
.000E+00
.195E+11
+
j 2R--95
.214E+03
.98SE+03
.312E+03
.000E+00
.458E+03
.000E+00
.720E+06 1
l I--131
.484E+09
.643E+09
.901E+09
.263E+12
.155E+10
.000E+00
.178E+09 I--133
.440E+07
.850E+07 144E+08
.201E+10
.253E+08
.000E+00
.109E+08 l
CS-134
.tS9E+12
.346E+12 343E+12
.000E+00
.109E+12
.4t?E+tt
.427E+to CS-136
.177E+11
.669E+10 263E+11
.000E+00
.143E+11
.226E+10
.212E+10 CS-137
.930E+11
.20tE+12 267E+12
.000E+00
.909E+11
.353E+11
.380E+10 BA-140
.187E+07
.290E+08 356E+05
.000E+00
.12tE+05
.239E+05
.448E+08 CE-141
.408E+03
.532E+04 355E+04
.000E+00
.167E+04
.000E+00
.102E+08 i
I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHO A VALUE OF *1 FOR M/0, f
8ASED OH 1 DEPLETED M/0 AND RELATIVE DEPOSITION I
i IIP-1-230, Revision 'S
'98 0.16 (18 of 19) j i,
1 w
1 TABLE ID (CON' PATHWAY DOSE FACTORS DUE TO RADIONUCLlDES OTHER l
THAN NOBLE GASES, R 3
t i
FOR CASE 0BS OfSONARGES 1:
ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) j, AGE GROUP: ADULT (4 0F 4) l PATHWAY: COATS MILK (CONTAMINATED FORAGE) t I
i q;
( SG. METER-MREN/YR PER UCI/SEC)
)
HUCLIDE ORGAN D 0 S.E FACT 0RS
___________________________________________ROID KIDHEY LUNG CI-LLI TOTAL BODY BONE LIVER THY l
H----3
.130E+05
.400E+00
.136E+05
.130E+45
.130E+05
.130E+05
.130E+05 CR--51
.171E+05
.000E+00
.000E+00
.102E+05
.37?E+04
.227E+05
.436E+47 MH--54
.963E+06
.000E+00
.503E+07
.880E+0e
.350E+07
.400E+00
.155E+08 i
FE--59
.174E+07
.193E+67
.453E+07
.489E+88
.60eE+40
.127E+07
.151E+49 CO--58
.633E+07
.000E+00
.282E+87
.000E+08
.000E+00
.006E+60
.573E+49 C0--60
.217E+08
.000E+00
.964E+47
.000E+44
.000E+00
.046E+04
.195E+49 ZH--65
.118E+10
.823E+49
.262E+18
.40DE+08
.175E+10
.664E+44
.165E+10 h
SR--89
.436E+09
.152E+11
.000E+00
.000E+08
.006E+04
.606E+64
.244E+14 GR--90
.121E+12
.491E+12
.000E+44
.084E+99
.000E+04
.000E+04
.142E+11 l
2R--95
.123E+03
.565E+03
.181E+03
.484E+44
.294E+03
.SetE+08
.575E+06
~;
I--131
.291E+09
.355E+09
.507E+09
.166E+12
.969E+49
.646E+08
.134E+49 4
I--133
.247E+07
.465E+07
.809E+47
.119E+14
.141E+4e
.400E+00
.727E+07 CS-134
.163E+12
.840E+11
.200E+12
.448E+44
.647E+11
.215E+11
.358E+18 CS-136
.112E*11
.393E+10
.155E+11
.480E+00
.963E+10
.119E+14
.176E+10 CS-137
.992E+11
.111E+12
.151E+12
.000E+44
.514E+11
.171E+11
.293E+10 BA-140
.105E+07
.16fE+08
.202E+85
.000E+t9
.687E+44
.116E+65
.331E+69 CE-141
.223E+03
.290E+04
.196E+44
.000E+tt
.911E+03
. 0 4 4E+ 4'8
.750E+47 1
FOR M/0,
]
UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 8ASED ON 1
]
DEPLETED X/O AND RELATIVE DEPOSITION I'
99 Attachment l'O.16 (19 of 19)
A
. IIP-1-230, Revision l
i lt 4
FIGURE 7
('s.
Relative Deposition for Ground-Level Releases L
)
(All Atmospheric Stability Classes) 10-3 104
\\
s '
c N g W
E
%w x
E h
\\
r N
4 E
2 10-5
% q A
o C, $
ll
's x
cE N '
AN g
l p
N' 5
N g
10-6 t
i i
l I
!l I
l ll l
ll l
i 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
O(j Obtained from Regulatory Guide 1.111 (March, 1976)
HP-1-230, Rev. 5 100 0.17 (1 of 1)
TABLE 11
)
ANNUAL AVERACE DISPERSION PARAMETERS AT OND THE UNRESTRICTED iREi RooNDA.T i
=
~
31 STANCE tu N1LES' b ANNUAL AVERAGE CN1/8 (SEC/NETER CUSES)
O EECTOR G.254 4.500 9.750 1 000 1.500 2 000 2.500 3.044 3.544 4.000 4.50e 3.04M-05 9.309E-04 4.854E-te 2.454E-44 9.92M-47 5.453E-07 3.51M-47 2.490E-47 1.075E-47 1.476E-47 1.201E-47 w
3.794E-05 1 154E-45 5.947E-ee 3.449E-04 1.215E-44 4.472E-07 4.34M-07 3.449E-47 2.29M-47 1 007E-07 1.471E-47 l
,0 S
5.09M-OS 2.532E-05 7.903E-04 3.975E-64 1.e43E-64 S.910E-07 5.499E-07 4.44eE-47 3.44eE-07 2 441E-47 1.95eE SSW 5.144E-05 1.546E-05 7.917E-04 3.987E-04 1 41M-44 S.964E-07 5.792E-47 4.111E-47 3.19eE-47 2.453E-47 2.eeM-47 g
SW 2.860E-05 S.434E-04 4.441E-04 2.258E-44 9.174E-67.5.049E-47 3.289E-07 2.330E-67 1.764E-07 1.39 M-07 1.137E-47 WSW 5.349E-05 1 433E-45 9.485E-04 4.30ef-64 1.748E-04 9.444E-07 4.245E-07 4.431E-07 3.*34M-07 2 43eE-47 2.14eE-47 W
7.591E-45 2.274E-05 1.159E-05 5.815E-04 2.344E-04 1.296E-94 S.452E-47 4.032E-47 4.57M-47 3.421E-07 2.941E-47 WNW 9.40SE-05 2.847E-05 1.429E-05 7.113E-04 2.847E-04 1.577E-te 1.435E-44 7.421E-47 5.649E-47 4.48eE-67 3.481E-47 L
NW 7.943E-05 2.340E-05 1 182E-OS 5.898E-04 2.372E-04 1 32M-44 S.634E-67 4.192E-07 4.71M-07 3.744E-47 3.071E-47 i
NNW 7.231E-05 2.140E-05 1.07eE-05 5.331E-04 2.14eE-44 1.1SSE-04 7.797E-07 5.594E-47 4.244E-47 3.385E-07 2.77eE-47 N
4.57&E-05 1.937E-05 9.590E-04 4.749E-04 1 894E-04 1.651E-04 4.92SE-47 4.994E-67 3.00M-07 3.030E-47 2.490E-97 NME 7.052E-05 2.072E-05 1 023E-05 5.642E-04 2.620E-04 1.123E-04 7.440E-07 5.334E-67 4.07&E-07 3.248E-47 2.472E-47 NE 5.347E-05 1.578E-05 7.791E-04 3.852E-04 1.53 M-44 8.515E-67 5.418E-47 4.04eE-07 3.691E-47 2.44M-07 2.92eE-07 l
ENE 4.982E-05 1 474E-45 7.381E-04 3.459E-04 1.45&E-44 0.042E-47 5.29e(-07 3.843E-47 2.899E-07 2.34M-47 1.092E-47 E
4.442E-05 1.390E-05 7.121E-64 3.54M-64 1.43eE-04 7.885E-47 5.137E-07 3.e&M-67 2 774E-47 2 197E-07 1 794E-47 ESE 4.549E-05 1 375E-05 7.000E-04 3.540E-04 1.430E-04 7.844E-47 5.097E-47 3.420E-47 2.734E-07 2.157E-47 1 764E-47 SE SSE 01 STANCE IN N1LES ANNUAL AVERAGE CH1/8 (SEC/NETER CU N D)
SEARING 5.000 7.500 10.000 15 000 20.000 25.004 30.000 35.444 44.444 45.446 58.000 1.003E-47 5.320E-48 3.522E-64 2.479E-48 1 43M-88 1 47eE-te 0.544E-09 7.424E-49 5.931E-49 5.111E-49 4 474E-49 1.22SE-07 4.524E-08 4.32M-08 2 554E-48 1 745E-49 1.327E-48 1.452E-48 S.657E-09 7.31M-49 4 30eE-99 5 524E-4 S
1.435E-07 S.718E-08 5.791E-ee 3.435E-98 2 379E-et 1 79M-48 1 424E-08 1 17 M-te 9.923E-49 S.544E-09 7 51eE-4 SSW 1.477E-67 8.987E-48 5.996E-OS 3.54SE-48 2.47eE-OS 1.871E-48 1.48SE-08 1.227E-48 1.039E-48 S.975E-49 7 975 SW g
9.518E-08 5.690E-OS 3.387E-00 2 012E-te 1 395E-te 1 031E-te 0.348E-49 6 87M-49 5.01eE-09 5.019E-09 4 4etE-49 o
WSW 1.79 M -07 9.549E-08 6.352E-08 3.742E-ee 2 462E-et 1.957E-48 1.55M -ee 1 278E-68 1.eSeE-te 9.309E-09 8.154E-0 T
W 2.484E-07 1.340E-47 S.970E-te 5 375E-08 3 747E-98 2 837E-OS 2.242E-40 1.849E-48 1.585E-08 1.371E-te 1 205E-t WNW 3.09&E-07 1.4SM-47 1.137E-07 6.872E-48 4.821E-te 3.667E-08 2.934E-te 2.432E-te 2.448E-48 1.79M-08 1 579E-te NW 2.582E-07 1.405E-07 9.447E-40 5 719E-68 4.009E-ee 3.040E-08 2.43SE-08 2 024E-48 1.71M-ee 1.49eE-48 1 310E-40 WW 2.33&E-47 1.274E-07 S.54SE-08 5 195E-OS 3 445E-08 2.77JE-08 2.22eE-68 1.SeeE-te 1.564E-te 1.35aE-08 1 194E-te-N 2.098E-07 1.150E-07 7 785E-08 4.735E-68 3 334E-OS 2.54M-48 2.44eE-48 1.494E-GS 1.44M-te 1 25M-48 1 144E-OS NME 2.252E-07 1.237E-07 8 383E-08 5.104E-OS 3 599E-08 2.740E-te 2.265E-OS 1.832E-te 1.541E-te 1 35M-te 1.195E-48 NE 1.707E-07 9.379E-08 4.35SE-08 3.873E-68 2 731E-08 2.885E-08 1.474E-08 1 391E-08 1.1SM-48 1 029E-ee 9 47M-49 ENE 1.592E-07 8.497E-08 5.873E-OS 3.541E-08 2.50M-08 1 90M-ee 1.527E-te 1.247E-40 1.07eE-OS 9.35eE-69 0.243E-69 E
1.50&E-07 S.117E-08 5.433E-OS 3.255E-68 2 270E-08 1.718E-08 1.37eE-GS 1 13M-OS 9.444E-09 S.311E-49 7.3e M-ESE 1.472E-07 7.872E-08 5 241E-08 3.117E-08 2 144E-GS 1.433E-08 1 298E-te 1.071E-44 9.443E-99 7.829E-49 4.SeeE-49 SE SSE CH1/G (SEC/NETER CUSES) FOS EACH SESNENT SESNENT SOUNDAS1ES IN N1LES DIRECT 10N
.5-1 1-2 2-3 3-4 4-5 5-14 10-24 20-34 30-44 40-54 ev S
4.780E-04 1.119E-04 3.622E-07 1.890E-07 1.249E-07 5 547E-04 2.11M-ee 1 484E-te 7.442E-49 5.119E-49 FROM SITE y
E SSW 5.SS3E-04 1.370E-04 4.434E-47 2.325E-07 1 481E-07 4.82M-48 2 59eE-et 1 334E-00 S.479E-09 4.315E-49 ts SW 7.905E-06 1.009E-04 5.845E-07 3.084E-07 1.949E-07 9 134E-04 3 490E-98 1 902E-48 1.174E-48 S.57M-49
[
WSW 7.84&E-04 1.320E-04 5.94&E-07 3.14&E-67 2 01M-47 9.30SE-et 3.422E-48 1.SeeE-48 1 23eE-te 0.987E-09 w
W 4.409E-04 1.033E-04 3.383E-07 1.78SC-47 1 145E-47 5 317E-48 2 043E-48 1 454E-40 4.89M-09 5.424E-09 3
WNW S.367E-04 1.947E-O'e 4.42&E-07 3.385E-07 2 162E-47 1.444E-07 3.822E-48 1.967E-48 1.281E-te 9.322E-49 MW 1.150E-05 2.649E-06 8.484E-07 4.427E-07 2.984E-07 1.39M-47 5 451E-08 2 85eE-GS 1.87M-08 1.37M-48 NNW 1.425E-05 3.231E-06 1.043E-04 5.713E-67 3.764E-07
- 1.755E-47 4.959E-te.
3.482E-te 2.437E-te 1.795E-ee N
1.181E-05 2.48&E-04 S.844E-07 4.7&M-07 3.089E-07 1.4eM-47 5 792E-48 3.040E-48 2.024E-48 1 49eE-te 5
NME 1.049E-05 2.42&E-04 S.003E-07 4.3eSE-47 2.794E-47 1 325E-67 5 24eE-ee 2.784E-48 1.94M-08 1.350*-48 NE 9.412E-06 2 154E-04 7.147E-07 3.04M-07 2.565E-07 1 196E-47 4.790E-48 2.553E-te 1 697E-ee 1.254E-48 O
ENE 1.02&E-05 2.297E-04 7.597E-07 4.121E-07 2.487E-07 1 285E-47 5.144E-48 2.75SE-08 1.035E-48 1.35M-te E
7.814E-06 1 745E-04 5.742E-07 3.124E-07 2.037E-07 9.74M-48 3 918E-et 2.093E-ee 1 39M-48 1.430E o ESE 7.367E-06 1 657E-04 5.437E-07 2.931E-07 1.9430-07 9.047E-08 3 604E-08 1.914E-08 1.270E-08 9.347E-49 SE 7.063E-04 1.419E-04 5.281E-07 2.009E-07 1.807E-07 8.447E-08 3 301E-48 1.72M-08 1.135E-ee 8.322E-09
! O ccr 7.notr_a4 s.A17F-04 5.244E-07 2.747E-07 1.771E-07 S.225E-08 3 145E-48 1.441E-et 1 073E-08 7.839E-09
1 TABLE Ay
. ANNUAL DEPOSITION PARAMETERS EDR AREAS AT OR BEY ESTRICTED AREA BQUNDARY kh sessessessesesseesses
=EtaTIvE SEr0SITION PER uMIT neEn (Neo-21 af rixES PSINTS Sr StuNulNS SECTS =5 sesessessessessesese SISECTION SISTANCES IM.NILES 4
- d. FEON SITE 6.25 0.50 0.75 1.00 1.50 2.44 2.54 3.64 3 54 4.44 4.54 e
S 1.059E-07 3.582E-08 1.839E-08 8.744E-69 3.141E-49 1.55SE-69 9.172E-14 4.046E-14 4.22&E-14 3.132E-te 2.413E-14 E$
SSW 1.506E-07 5.C72E-48 2.404E-08 1.23SE-48 4.447E-09 2.245E-69 1.299E-99 S.543E-10 5.983E-14 4.434E-10 3.417E-14 i
C)
SW 2.13&E-47 7.222E-OS 3.70SE-08 1.743E-68 4.332E-69 3.140E-69 1.849E-49 1.211E-09 8.519E-14 4.313E-14 4.845E-10 WSW 1.450E-07 5.500E-05 2.Se5E-08 1.342E-68 4.893E-69 2.42&E-49 1.429E-09 9.335E-16 4.583E-16 4.870E-te 3.759E-10 l
P8 W
S.78EE-08 2.972E-08 1.52&E-08 7.254E-09 2.444E-09 1.292E-09 7.649E-14 4.982E-10 3.546E-te 2.598E-te 2.te2E-te i
WNW 1.835E-07 4.204E-05 3.185E-08 1.514E-08 5.440E-49 2.498E-69 1.5SSE-09 1.044E-69 7.319E-te 5.424E-te 4.194E-14 l
NW 2.144E-07 7.249E-CS 3.722E-08 1.749E-08 4.354E-09 3.152E-49 1.854E-49 1.215E-49 8.551E-te 4.337E-te 4.SS4E-14 i
i
-Lp NMW 2.242E-07 7.582E-08 3.893E-08 1.851E-08 4.44SE-69 3.297E-09 1 941E-09 1.271E-09 S.945E-14 4.429E-16 5.14SE-14 N
1.443E-07 5.557E-OS 2.853E-08 1.354E-08 4.872E-09 2.41&E-49 1.423E-09 9.316E-14 4.555E-10 4.85SE-te 3.743E-14 l
NME 1.34SE-07 4.427E-05 2.37eE-08 1.129E-05 4.057E-09 2.012E-09 3.185E-09 7.754E-10 5.45SE-14 4.645E-14 3 117E-14 i
NE 1.119E-07 3.70eE-OS 1.944E-08 9.240E-09 3.319E-09 1.446E-09 9.492E-10 4.34&E-10 4.44&E-10 3.309E-16 2.554E-10 ENE 9.912E-OS 3.352E-08 1.721E-08 8.182E-09 2.939E-09 1.45SE-49 8.582E-14 5.424E-14 3.954E-14 2.93eE-14 2.25SE-10 E
3.409E-08 2.911E-08 1.495E-08 7.10eE-49 2.552E-09 1.26&E-09 7.453E-te 4.SS4E-te 3.434E-te 2.545E-14 1.941E-10 ESE 9.069E-08 3.047E-08 1.575E-OS 7.484E-09 2.489E-09 1.334E-99 7.SS2E-10 5.142E-te 3.410E-14 2.6SSE-te 2.644E-14 SE 1.225E-07 4.144E-OS 2.12SE-08 1.011E-08 3.433E-09 1.802E-09 1.041E-49 4.947E-10 4.SSSE-te 3.423E-10 2.792E-te SSE 1.401E-07 5.413E-OS 2.779E-08 1.321E-08 4.74eE-09 2.354E-09 1.384E-99 9.075E-10 4.344E-14 4.733E-te 3.447E-14 SIRECTION SISTANCES IN MILES FROM SITE 5.00 7.50 10.60 15.G4 20.46 25.40 34.44 35.64 44.00 45.00 50.00 S
1.917E-10 8.517E-11 5.140E-11 2.64GE-11 1.570E-11 1.05SE-11 7.583E-12 5.494E-12 4.427E-12 3.53?E-12 2.SSFE-12 SSW 2.715E-10 1 20eE-10 7.305E-11 3.492E-11 2.235E-11 1.498E-11 1.474E-11 S.642E-12 4.2eSE-12 5.407E-12 4.087E-12 SW 3.845E-10 1.717E-14 1.040E-10 5.257E-11 3.182E-11 2.133E-11 1.529E-11 1 14SE-11 0.925E-12 7.129E-12 5.819E-12 j
WSW 2.987E-10 1.327E-te 3.437E-11 4.042E-11 2.459E-11 1 44GE-11 1.181E-11 0.870E-12 4.89&E-12 5.549E-12 4.496E-12 j Ej W
1.591E-10 7.04&E-11 4.2SOE-11 2.143E-11 1.349E-11 S.779E-12 4.291E-12 4.724E-12 3.473E-12 2.934E-12 2.395E-12 ba WNW 3.321E-10 1.475E-10 S.935E-11 4.514E-11 2.734E-11 1.833E-11'1 313E-11 9.841E-12 7.447E-12 4.125E-12 4.999E-12 t
l NW 3.SSOE-10 1.724E-10 1.044E-10 5.277E-11 3.194E-11 2.142E-11 1 534E-11 1.152E-11 S.959E-12 7.15eE-12 5.041E-12 i
NNW 4.05SE-10 1.803E-10 1.092E-10 5.524E-11 3.341E-11 2.240E-11 1.605E-11 1.205E-11 9.371E-12 7.486E-12 4.116E-12 j-NME 2.47&E-10 1.100E-10 4.444E-11 3.34tE-11 2.039E-11 1.347E-11 9.794E-12 7.354E-12 5.710E-12 4.54SE-12 3.72SE-12 N
2.974E-10 1.321E-10 8.003E-11 4.045E-11 2.44SE-11 1.442E-11 1 176E-11 S.832E-12 4.847E-12 5.484E-12 4.4?SE-12 NE 2.02eE-10 9.001E-11 5.452E-11 2.754E-11 1.44SE-11 1.118E-11 S.013E-12 4.017E-12 4.479E-12 3 737E-12 3.454E-12 ENE 1.794E-10 7.970E-11 4.82SE-11 2.440E-11 1 477E-11 9.902E-12 7.095E-12 5 32SE-12 4.143E-12 3 349E-12 2.761E-12 E
1.55SE-10 4.921E-11 4.193E-11 2.119E-11 1 283E-11 S.444E-12 4.142E-12 4.427E-12 3.59BE-12 2.874E-12 2.34&E-12 ESE 1.441E-10 7.292E-11 4.417E-11 2.233E-11 1.351E-11 9.040E-12 4.492E-12 4.875E-12 3 790E-12 3.020E-12 2.471E-12 j
SE 2.218E-10 9.852E-11 5.94SE-11 3.017E-11 1.82&E-11 1.224E-11 0.772E-12 4.587E-12 5.121E-12 4.091E-12 3.339E-12
~
i SSE 2.897E-10 1.207E-10 7.797E-11 3.941E-11 2 3SSE-11 1.599E-11 1 146E-11 S.604E-12 4.690E-12 5.344E-12 4.342E-12 seessssssssssssssssssses RELATIVE DEPOSITION PER UNIT ASEA (N88-21 SV SOUNNING SECTORS 888888884888888888888888 SESMENT SOUNSARIES IN MILES l
3 SIRECTIGN
.5-1 1-2 2-3 3-4 4-5 5-18 14-20 24-34 30-44 46-56 r'
FRon SITE E
S 1.79eE-08 3.483E-09 9.413E-10 4.310E-10 2.443E-10 9.393E-11 2.717E-11 1.877E-11 5.751E-12 3.544E-12
-i o
SSW 2.545E-08 5.214E-09 1.341E-09 4.113E-10 3.45SE-10 1.334E-10 3.847E-11 1.525E-11 S.143E-12 5.440E-12 lI SW 3.424E-08 7.424E-09 1.93SE-09 S.704E-10 4.924E-te 1.094E-14 5.478E-11 2.171E-11 1.159E-11 7.176E-12 y
CSU 2.800E-OS 5.734E-09 1.497E-09 4.724E-10 3.805E-10 1.443E-16 4.233E-11 1.678E-11 S.959E-12 5.545E-12 re W
1.491E-08 3.055E-09 7.975E-10 3.582E-10 2.024E-10 7.792E-11 2.254E-11 S.934E-12 4.771E-12 2.953E-12 ucW 3.114E-08 4.378E-09 1.445E-09 7.477E-te 4.230E-10 1.427E-10 4.70&E-11 1.045E-11 9.946E-12 4.145E-12 C3 NW 3.43SE-08 7.452E-09 1.945E-09 8.737E-10 4.943E-10 1.901E-10 5.499E-11 2.179E-11 1.144E-11 7.203E-12 Nru 3.805E-08 7.794E-09 2.035E-09 9.139E-10 5.170E-10 1.98SE-10 5.752E-11 2.286E-11 1.217E-11 7.535E-12 u)
N 2.789E-08 5.712E-09 1.491E-09 4.697E-10 3.789E-10 1 457E-10 4.215E-11 1.471E-11 S.921E-12 5.522E-12 NME 2.322E-08 4.754E-09 1.242E-09 5.57&E-10 3.155E-10 1.213E-10 3.518E-11 1 391E-11 7.42SE-12 4.590E-12
,s NE 1.900E-08 3.891E-09 1.01eE-09 4.543E-10 2.581E-10 9.926E-11 2.972E-11 1.13SE-11 6.478E-12 3.742E-12 EEE 1.482E-08 3.44eE-09 8.995E-10 4.040E-10 2.2SSE-10 0.789E-11 2.543E-11 1.00SE-11 5.381E-12 3.331E-12 o
[
en E
1.461E-08 2.992E-09 7.812E-10 3.509E-10 1.985E-10 7.433E-11 2.200E-11 S.752E-12 4.674E-12 2.893E-12 ESE 1.539E-08 3.153E-09 S.230E-10 3.&94E-10 2.091E-10 0.042E-11 2.32eE-11 9.220E-12 4.924E-12 3.44SE-12 SE 2.080E-08 4.260E-09 1.112E-09 4.994E-10 2.825E-10 1.087E-10 3.143E-11 1.244E-11 4.453E-12 4.118E-12
)
SSE 2.717E-08 5.565E-09 1.453E-09 4.524E-10 3.491E-10 1.419E-10 4.10&E-11 1.427E-11 S.691E-12 5 379E-12 l
i m
, =. _ _ _
v-O ODCM TECHNICAL SPECIFICATIONS CROSS-REFERENCE (TABLE 13)
Tech Spec ODCN Dose Calculation Section Section Methodolony 3.3.3.10 8.7 Determination of Alarm / Trip 3.11.1.1 Setpoints for Liquid 4.11.1.1.2 Monitors 3.3.3.11-8.13 Determination of Alarm / Trip 3.11.2.1 Setpoints for Gaseous 3.11.2.4 Monitors 4.11.2.4.1
[
3.11.1.1 8.6 Liquid Effluents 4.11.1.1.1 3.11.1.2 4.11.1.2 3.11.1.3 av 4.11.1.3.1 3.11.2.1 8.10 Gaseous Effluents 4.11.2.1.3 (Dose rate due to Noble Gases, 4.11.2.4.1 Radiciodines, Particulates, and Radionuclides with half-lives greater than 8 days.)
l 3.11.2.1 8.11 Noble Gases 3.11.2.2 4.11.2.2 l
3.11.2.3 8.12 Radioiodines, Particulates, and 4.11.2.3 Radionuclides with half-lives greater than 8 days 3.11.4 8.15 Total Dose 4.11.4.1 (40CFR190) 4.11.4.1 3.12.1 8.2 Radiological Environmental 4.12.1 Monitoring l
3.12.3 8.3 Interlaboratory Comparison Program 4.12.3 I
iO l
HP-1-230, Rev.5 0.20 (1 of 1)
4 Refer:
10CFR50.36a Louisiama / 3,7eAnoNNeS1neer. e.o.eoxe0340 POWER & L1GHT NEW ORLEANS, LOUISIANA 70160 (504)595 3100
+
Nu NIvsi[0 March 2, 1987 W3P87-0568 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semiannual Radioactive Effluent Release Report Enclosed is the subject report on effluent releases which covers the period of July 1 to December 31, 1986. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-1117) of Appendix A to Facility Operating License No. NPF-38 and 10 CFR 50.36a(a)(2), pursuant to 10CFR50.4.
Very truly yours,
[
K.W. Cook Nuclear Safety and Regulatory Affairs Manager KWC:GEW:ssf Enclosure cc (w/ enclosure):
R.D. Martin, NRC Region IV NRC Resident Inspectors Office cc (w/o enclosure): G.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR pfh E.L. Blake W.M. Stevenson
!f l
"AN EQUAL OPPORTUNITY EMPLOYER" i