ML20108C545
| ML20108C545 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1995 |
| From: | Floyd E PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20108C543 | List: |
| References | |
| NUDOCS 9605070019 | |
| Download: ML20108C545 (246) | |
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1UELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 1995 -
December 31, 1995 Prepared By: Date: N~O'[
- 5. T. Floyd Radiation Protection Technician Reviewed By: Date: d-ll- 90
() D. C. Kay Radiation Protectio ()n Supervisor Approved By: -t Q Date: Nfbb!
J. R. Curtis l}RadiationProtectionManager 9605070019 960430 PDR ADOCK 05000445 R PDR P.0,i m 1002 Glen Rose. Texas 76043-1002 l
TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS
1.0 INTRODUCTION
1.1 Executive Summary 2.O SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total Radioactivity 2.4 Batch Releases 2.5 Abnormal Releases 3.0 GASEOUS EFFLUENTS 4.O LIQUID l'FFiUENTS 5.0 SOLID WAllTES 6.O RELATED IliFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the Offsite Dose Calculation Manual 6.3 New Locations for Dose Calculations or Environmental Monitoring 6.4 Liquid Holdup and Gas Storage Tanks 6.5 Noncompliance with Radiological Effluent Control Requirements 6.6 Resin Releases to the LVW Pond 6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems 6.8 Meteorological Monitoring Program 6.9 Assessment of Doses i
I TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary 7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents--Summation of All Releases 7.4 Gaseous Effluents--Ground Level Releases 7.5 Liquid Effluents--Summation of All Releases 7.6 Liquid Effluents 7.7 Doses From Liquid Effluents 7.8 Doses From Gaseous Effluents; Noble Gas Air Dose 7.9 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Adult Age Group 7.10 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Teen Age Group 7.11 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Child Age Group 7.12 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Infant Age Group 7.13 Solid Waste and Irradiated Fuel Shipments 8.O ATTACIDENTS 8.1 Offsite Dose Calculation Manual For TU Electric Comanche l Peak Steam Electric Station Units 1 and 2, Revision 12 l 8.2 Joint Frequency Tables for 1995 1
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! ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station ECL Effluent Concentration Limit LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks REC Radiological Effluent Control SORC Station Operations Review Committee WMT Waste Monitor Tanks WWHT Waste Water Holdup Tanks ,,
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10 INTRODUCTION l
l This Annual Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station Unit 1 and Unit 2, is submitted as required by Technical Specification 6.9.1.4 and Offsite Dose Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 1995, through December 31, 1995.
1.1 Executive Summary The radioactive ef fluent monitoring program for the year 1995 was conducted as described in the following report.
l The results of the monitoring program indicate the i continued effort to maintain the release of radioactive effluents to the environment as low as reasonably achievable.
The total gaseous activity released for 1995 was 28.32 curies. This is an increase over the 1994 total of 2.20 curies due mainly to the planned release of the contents of three waste gas decay tanks and the cyclic release of noble gases detected on some of the primary plant ventilation stack samples. The total represents the second lowest total since startup of Unit 1.
Dose due to gaseous activity released increased to 3.25E-2 mrem for 1995 from the 1994 dose of 1.21E-2 mrem.
The increase was expected due to the planned waste gas decay tank releases and the noble gases from the stacks.
The dose represents 1.08E-1% of the allowable limit.
Total activity (excluding tritium) released in 1995 in liquid effluents was 1.24E-1 curies. This is the third year in a row that the total activity has decreased.
Minimizing the introduction of water into the radwaste processing system and reprecessing and treatment of water contributed to the reduction of activity released.
The total tritium activity released in 1995 in liquid effluents was 840 curies. This total is down from 1994's total of 880 curies.
The calculated.whole body dose due to liquid effluents i released in 1995 was 7.65E-2 mrem, up from 1994's dose of 5.9E-2 mrem whole body. The 1995 dose represents 1.28%
of the allowable limit. Dose is nuclide dependent and i even though the activity decreased in 1995, the dose I
increased based on the nuclides present in this years liquid effluents. Most dose is due to tritium (>95%).
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During 1995, CPSES conducted the first planned releases from the waste gas decay tanks. The contents of three tanks were released contributing 1.75 curies to the total gaseous activity of 28.32 curies. This was the first waste gas decay tank release in over five years of '
operation. ;
Liquid effluents released to Squaw Creek Reservoir contributed to the concentration of tritium found in Squaw Creek environmental water samples. During 1995, the tritium concentration in the reservoir peaked at 9900 pCi/l for the second quarter and has decreased to 7000 pCi/l based on fourth quarter samples. These levels are below reportable levels and may indicate an equilibrium level will soon be achieved below calculated levels.
The CPSES meteorological system achieved a 93.8%
recoverable data rate for the j int frequency parameters required by Regulatory Guide 1.23 of wind speed, wind direction and delta temperature. All other parameters achieved a >90% recoverable data rate also. During 1995 ;
a "Special Report" was submitted to the NRC due to a l lightning strike on the meteorological system that i rendered the system inoperable for >7 days. A new ;
lightning deterrent system was installed on the I meteorological tower to attempt to eliminate the i lightning strikes.
There was one reportable abnormal release during 1995.
During maintenance conducted to drain condensate collected in the waste gas decay tank #6, the gas trap l failed to operate properly resulting in the release of !
500 cubic feet of waste gas. Tne release was monitored by the stack effluent monitors and the activity and dose !
were accounted for by an abnormal (non-routine) release j permit. Results are included in the totals provided in this report. There were 0.073 curies released resulting in a calculated gamma air dose of 1.45E-7 mrad.
During 1995 there were no Technical Specification /ODCM effluent radiation monitors out of service for >30 days.
There was considerable effort made to eliminate electrical noise problems, add. updated firmwear, add smoothing algorithms to reduce spiking and change liquid monitors to adjacent-to-line monitors to solve problems with degraded flow and high temperatures.
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[ Revision 12 of the ODCM was issued and became effective l on December 8, 1995. There were several changes made including: numerous editorial changes; figures were updated to correct pump flow rates; replaced the specific references to the EPA Interlaboratory Comparison program j anc relocated Tables 2.5, 3.1, and Figure 3.1 to the annual Land Use Census. No changes affected the radiological effluent monitoring program directly.
For _995, the total volume of buried solid radwaste was l 14.77 cubic meters, down from 55.1 cubic meters in 1994. '
The total buried activity is approximately the same in l 1995 as in 1994, with 1,130 curies buried in 1995 and 1,080 curies burie J in 1994. The dry active waste volume is very low for 1995 with only 4.67 cubic meters buried. j The majority of buried solid waste volume comes from '
spent resins and filters at 10.1 cubic meters. Also, spent resins and filters were responsible for >99.9% of all the total activity buried.
Overall, the radioactive effluent monitoring program has been conducted in an appropriate manner to ensure the activity released and associated dose to the public has been maintained as low as reasonably achievable.
Information pertaining to the following areas is included in this report:
e A summary of the quantities of radioactive liquid and gaseous effluents released from Unit 1 and Unit 2 during the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974 e A summary of solid waste shipped from Unit 1 end Unit 2 in the format shown in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974, supplemented with three additional categories: class of waste (per 10CFR61) , type of container (Strong Tight, HIC) and shipped and buried volumes and curies.
e An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.
e Changes to the ODCM in the form of a complete, legible copy of the entire ODCM.
- A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census.
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l e A description of the events leading to liquid holdup l tanks or gas storage tanks exceeding Technical j Specification limits.
i e A list and description of abnormal releases of l l
radioactive material from the site to unrestricted areas.
I e A description of secondary resin releases to the LVW
- Pond.
l l e A description of major changes to radioactive waste '
treatment systems (liquid, gaseous and solid).
! e An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from CPSES Unit 1 and Unit 2 in 1995. l e An assessment of radiation doses to the likely, most exposed MEMBER OF THE PUBLIC from CPSES Unit 1 and Unit {
2 releases and other nearby uranium fuel cycle sources, '
including doses from primary effluent pathways and direct !
radiation, for the reporting period, to show conformance with 40 CFR 190, " Environmental Radiation Protection j scandards for h* lear Power Operation." l l e An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the site Boundary.
2.0 SUPPLEMENTAL INFORMATION 2.1 Reculatorv Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive materials released in gaseous effluents from the site to l
areas at and beyond the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited I to the following:
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- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.2 Iodine-131. Iodine-133. Tritium and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ.
The dose to a MEMBER OF THE PUBLIC from j iodine-131, iodine-133, tritium and all i radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
2.1.3 Licuid Effluents ',
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:
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- a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and I b. During any calendar year to less than or equal to 3 mrems to the whole body and to .
less than or equal to 10 mrems to any I organ.
2.1.4 LW Pond Resin Inventerv The quantity of radioactive material contained in resins transferred to the LW pond shall be
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E3 A /C < 1.0 3 3 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:
A3 = pond inventory limit for a single radionuclide j (Curies),
C3 = 10CFR20, Appendix B, Table 2 Column l 2, concentration for a single radionuclide j (pCi/ml),
V = volume of resins in the pond (gallons), and 264 = conversion factor (pCi/Ci per ml/ gal) 2.1.5 Total Dose '
l The annual (calendar year) dose or dose i commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
l 2.2 Effluent Concentration Limits 2.2.1 Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in I release rate calculations since the applicable i limits are expressed in terms of dose rate at )
the site boundary.
2.2.2 Licuid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive ef fluents released to unrestricted areas. A value of 2.0E-04 gCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.
2.3 Measurements and Acoroximations of Total Radioactivity Measurements of total radioact,ivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPSES ODCM.
2.3.1 Licuid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT), Laundry Holdup and Monitor Tanks (LHMT) and Waste Water Holdup Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory (Teledyne Brown). The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and
- estimated concentrations of each radionuclide l present and the total volume of the effluent released during periods of discharge.
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For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite ;
samples were analyzed quarterly, for Sr-89 and Sr-90, by an offsite laboratory (Teledyne Brown).
i For continuous releases to the Circulating ,
Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge. These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques. '
Composite samples were also analyzed for ;
tritium and gross alpha radioactivity using i liquid scintillation and gas flow proportional counting techniques, respectively. Composite -
samples were analyzed quarterly for Sr-89, Sr- '
90 and Fe-55 by a contract laboratory (Teledyne Brown).
2.3.2 Gaseous Radioactive' Effluents Each gaseous batch release was sampled and ;
analyzed for radioactivity prior to release.
For releases from Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the ,
Containment Building, samples were taken using j charcoal and particulate filters, in addition 1 to noble gas and tritium grab samples, and '
analyzed for gamma emitting radionuclides prior to each release with the exception of i Containment vents made as a, precursor to a j Containment purge. In these cases, samples I collected and analyzed as a prerequisite to the vent were used to estimate total radioactivity released during the subsequent purge. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.
For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radiciodine I
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[ adsorbers and particulate filters. The l radiciodine adsorbers and particulate filters i l were analyzed weekly for I-131 and gamma '
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! spectroscopy. Results of the noble gas and l tritium grab samples, radiciodine adsorber and i
particulate filter analyses from the current week and the average effluent flow rate for
. the previous week were used to determine the i total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross i alpha activity, in the onsite laboratory using !
the gas flow proportional counting technique. i i
Quarterly composites of particulate filters '
were analyzed for Sr-89 and Sr-90 by an offsite laboratory (Teledyne Brown).
2.4 Batch Releases A summary of information for gaseous and liquid batch
- releases is included in Table,7.1.
2.5 Abnormal Releases Abnormal releases are defined as unplanned or uncontrolled releases of radioactive material from the site boundary.
One (1) abnormal gaseous effluent release occurred during the period covered by this report. This event is described in section 6.5.1 of this report.
A summary of information for gaseous and liquid abnormal releases is included in Table 7.2.
3.O GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 7.3 and 7.4. All releases of radioactive material in gaseous form are considered to be ground level releases.
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4.O LIOUID EFFLUENTS j l l The quantities of radioactive material released in liquid j
effluents are summarized in Tables 7.5 and 7.6. '
l 5.O SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Table 7.13.
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l 6.O RELATED INFORMAT,1QH ]
6.1 Ooerability of Liauid and Gaseous Monitorino )
Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require an explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to operable status within thirty days.
During the period covered by this report, there were no-instances where these instruments were inoperable for more than thirty days.
6.2 Chances to the Offsite Dose Calculation Me.nual During the period covered by this report, there was one revision to the ODCM. In accordance with the ODCM Administrative Control 6.14.c, the changes are submitted in the form of a complete copy of the entire ODCM. The ODCM, current as of December 31, 1995, is contained in Attachment 8.1. The changes,includedsin '~
this revision are summarized below:
Revision 12. effective December 8. 1995 -
e Certain radiological effluent administrative controls, most notably 3/4.11.1.1, were revised to be consistent with CPSES Technical Specification Amendment 42/28. The revision changed the control 3.11.1.1 limits to "10 times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2" for discharge of liquid effluents from the site.
e Minor editorial / clarification changes were incorporated to better r'eflect 10CFR20 implementation or to reflect preferred wording.
- Unnecessary references to CPSES Technical Specifications were deleted from ODCM Controls 4 3.12.1, 3.12.2 and 3.12.3.
e Part II, Figure 1.1 " Liquid Effluent Discharge Pathways" was revised. Page 2 of 2 was deleted.
It represented the Liquid Waste Processing System diagram which was not necessary to illustrate the CPSES liquid effluent discharge pathways described in the ODCM.
e Revised requirements for participation in an Interlaboratory Comparison Program due to changes in the EPA Interlaboratory Program.
e Part II, Table 1.1 and Figure 1.1 were revised to reflect an increased maximum pump flow rate of 300 gallons / minute from the Waste Water Holdup Tanks.
o ODCM Table 2.5, 3.1 and Figure 3.1 were relocated to the annual Land Use Census so that the results will be included in the Land Use census each year ;
and can be maintained current at all times, l 6.3 New Locations for Dose Calculations or Environmental fionitorino ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental I monitoring, identified by the Land Use Census, to be !
included in the Annual Radioactive Effluent Release Report. Based on the 1995 Land Use Census, no new receptor locations were identified which resulted in changes requiring a revision in current environmental sample locations. Values for the new nearest resident, milk animal, garden, X/O and D/0 values were included in the 1995 Land Use Census.
6.4 Licuid Holduo and Gas Storace Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the Technical Specification limits. Technical Specification 3.11.1 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten curies, excluding tritium and dissolved or entrained noble gases. Technical Specification 3.11.2.2 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered an '1-133 equivalent). These limits were not exceeded during the period covered by this report.
6.5 Noncomoliance with Radiolocical Effluent Control Recuirements This section provides a listing of events that did not comply with the applicable requirements of the Radiological Effluent Controls given in Part I of the CPSES ODCM. Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite.
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l 6.5.1 Abnormal Gaseous and Licuid Releases 1
e On October 27, 1995, a routine weekly condensate drain from Gas Decay Tank (GDT-06) to the Waste Holdup Tank (WHT) was in progress. Drain flow had been i l established utilizing the pressure in the GDT as the driving head and the flow rate l was set at less than 30 g.p.m. as required by procedure. After several minutes of draining, the flow rate became erratic and increased to greater than 30 l g.p.m. (maximum instrument range), at l which time the Radwaste Operator adjusted ;
flow to less than 30 g.p.m. and draining ,
continued. Upon investigation, the l second Radwaste Operator noted that the '
level in the WHT had not increased to the level expected (2% change vs. Ils expected) and that the GDT pres sure had decreased by approximately 14.5 psi.
Based on these conditions the condensate drain was secured and Radwaste supervision was informed of the decrease in GDT pressure. i The reduction in GDT pressure without a corresponding increase in WHT level that l occurred during this event was indicative l that gas had been released to the WHT, I which resulted in an unplanned non-routine radioactive effluent release to tha environment via the plant ventilation system. A review of the data from the l Auxiliary Building Ventilation Radiation I Monitor confirmed that, a release had occurred. The release was documented on the required Station Procedure effluent release data sheet (STA-603-8).
The GDT gas trap did not function as designed, the flow indicator indicated erratic flow due to a condensate / gas flow mixture and then flow indication would increase due to gas flow. Pressure in the GDT decreased without a corresponding increase in WHT level which was l indicative that gas was being released i
from the system.
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The following corrective actions have been taken or are under development: i e The performance of condensate drains from the GDTs was temporarily suspended until interim guidance was provided to ensure an unplanned release would not occur. This action was taken based on the potential for a recurrence of this event.
e The gas traps were repaired.
e Schedule periodic preventive maintenance on the gas traps in the WGPS.
9 Develop lessons learned for training purposes based on information derived from this event and provide this training information to Radwaste Operators.
The effects of this event on the safety of the plant or to the public are not significant. The quantity and concentration of radioactivity in the gas released was measured and confirmed to be within acceptable limits for release to the environment. The release resulted in 0.073 curies of noble gases being released with a calculated gamma air dose of 1.45E-7 mrad and which is <0.001% of any release limit.
6.5.2 Failure to Meet Soecified Samolino Reauirements For the year 1995, there were no instances of failure to meet the specified sampling criteria as required in the ODCM.
6.6 Resin Releases to the LVW Pond A total of 1156 ft3 of resin was transferred to the LVW pond during the period covered by this report. The results of the sample analyses indicate no radioactive material was transferred to the pond.
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6.7 Chances to the Licuid, Gaseous and Solid Waste Treatment Systems i
In accordance with the CPSES Process Control Program, l Section 2.2a, major changes to the Radwaste Treatment I Systems (liquid, gaseous and solid) shall be reported to :
the Commission in the Annual Radioactive Effluent Release !
Report for the period in which changes were reviewed by j the CORC. l During this reporting period no design modifications were approved or implemented involving major changes to Radwaste Treatment Systems, i i
6.8 Meteoroloaical Monitorina Procram In accordance with ODCM Administrative Control 6.9.1.'4, a summary of hourly meteorological data, collected during 1995, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 8.2.
- 6.9 Assessment of Doses i .
l 6.9.1 Doses Due to Liould Effluents i
The doses to an adult from the fish and cow-meat consumption pathways from Squaw Creek Reservoir were calculated in accordance with the methodology and parameters in the ODCM.
The results of the calculations are summarized on a quarterly and annual basis in Table 7.7.
6.9.2 Doses Due to Gameous Effluents The air dose due to gamma emissions and the air dose due to beta emissions were calculated using the highest annual average atmospheric dispersion factor at the Site Boundary location, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 7.8. j l
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6.9.3 Dose Due to Radiciodines, Tritium and Particulates The doses to an infant, child, teen and adult from radiciodines and particulates, for the l
pathways listed in Part II, Table 2.4 of the ODCM, were calculated using the highest dispersion and deposition factors, as l
appropriate, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Tables 7.9 l
through 7.12.
I i 6.9.4 40CFR190 Dose Evaluation l
l l ODCM Radiological Effluent Control 3.11.4 l
requires dose evaluations to demonstrate compliance with 40 CFR Part 190 only if the calculated quarterly or yearly doses exceed l two times the applicable quarterly or annual
! dose limits (see Sections 2.1.1, 2.2.2 and 2.2.3). At no time during 1995 were any of these limits exceeded, therefore no evaluations are required.
6.9.5 Doses to a MEMBER OF THE PUBLIC From Activities Inside the Site Boundarv l Three activities are considered in this l evaluation: fishing on Squaw Creek Lake, recreation activities at the CPSES employee l recreational area and site tours through the l CPSES Visitors Center.
The highest dose occurred in the evaluation for fishing, resulting in a dose of 9.06E-4 mrem /yr. The dose to a MEMBER OF THE PUBLIC (fisherman) on Squaw Creek Lake was calculated based on fishing twice a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation and l submersion. Liquid pathways are not l considered since all doses are calculated at the point of cirewater discharge into the lake.
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The dose to a MEMBER OF THE PUBLIC engaged in recreational activities at the CPSES employee recreational park was calculated based on one visit a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation, submersion and ground plane.
The dose to a MEMBER OF THE PUBLIC during site tours through the CPSES Visitors Center was calculated based on two visits per year, thirty minutes each visit. Pathways included in the calculation were gaseous inhalation and submersion.
All calculations were performed in accordance with the methodology and parameters in the ODCM.
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SECTION 7.0 i
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Table 7.1 BATCH LIOUID AND GASEOUS RELEASE
SUMMARY
Ouarter 1 Quarter 2 Ouarter 3 Quarter 4 A. Liouid Releases All Sources Number of Batch Releases 3.10E+01 2.90E+01 2.50E+01 1.90E+01 Total Time Period for Batch Releases (min) 1.21E+04 1.09E+04 1.04E+04 7.22E+03 Maximum Time Period for a Batch Release (min) 4.83E+02 4.53E+02 4.67E+02 4.31E+02 Average Time Period for a Batch Release (min) 3.89E+02 3.75E+02 4.16E+02 3.80E+02 Minimum Time Period for a Batch Release (min) 6.40E+01 5.40E+01 3.48E+02 7.70E+01 Average Stream Flow During Periods of Release (f t*/s) N/A N/A N/A N/A B. Gaseous Releases All Jources Number of Batch Releantes 3.60E+01 3.40E+01 4.90E+01 4,00E+01 Total Time Period for Batch Releases (min) 1.34E+04 1.21E+04 1.44E+04 1.39E+04 Maximum Time Period for a Batch Release (min) 7.21E+02 5.15E+02 4.11E+02 4.24E+02 AverageTimePeriodforaBatchRelhase (min) 3.72E+02 3.55E+02 2.94E+02 3.48E+02 Minimum Time Period for a Batch Release (min) 1.90E+01 2.71E+02 1.39E+02 2.40E+02 T-1
TABLE 7.2 ABNORMAL BATCH LIOUID AND GASEOUS RELEASE
SUMMARY
Ouarter 1 Ouarter 2 Ouarter 3 Quarter 4 A. Liouids Number of Releases 0 0 0 0 Total Activity Released, Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 B. Gases Number of Releases 0 0 0 1 Total Activity Released. Ci 0.00E+00 0.00E+00 0.00E+00 7.34E-02
~~
T-2
. _ - - _ - -- - - . . . - - . _. c- - - __ - . - - . . - _ - - - - - _ _ _ _ - - _ - - - . - - - - - _ _ - - _ _ _ _ _ . _ _ - - - - _ - - _ - - - _ _ _ _ - - , - ~
. . _ _ . . _ _ _ _ m_ _ . . . - . _ _ - . _ . _ . . . _ _ _ _ _ _ . . _ . _ . . . _ _ _ . . . _ . ___ _ _ . _ . . _ . _ _
TABLE 7.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELFASES
/
Units -Quarter Quarter Quarter Quarter Est, Total 1 2 3 4 Error, %
A. Fission and Activation Gases i
j 1. Total release Ci 6.40E+00 3.68E-01 1.07E+01 1.03E+01 2.35E+01
( 3. Average release rate for pCi/sec 8.31E-01 1.10E-01 1.34E+00 1.30E+00 l period l
l 3. Percent of ODCM REC % 3.02E-04 1.08E-04 4.14E-04 4.27E-04 limit (Total Body Dose Rate)
B. Iodines
- 1. Total Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N/A
- 2. Average release rate for pC1/sec 0.00E+00 0.00E+00 0.00E+00
^
0.00E+00 L period
- 3. Percent of ODCM REC % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l limit (Organ Dose Rate) l C. Particulates l
'1. Particulates with half Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F/A l
lives > 8 days
(
- 2. Average release rate for pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 period
- 4. Gross alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
I radioactivit.y l
D. Tritium
- 1. Total release Ci 2.48E+00 4.61E+00 9.21E+00 6.85E+00 2.38E+01 !
- 2. Average release rate for pCi/sec 3.19E-01 5.87E-01 1.16E+00 8.62E-01 period i
{ 3. Percent of ODCM REC % 5.64E-03 1.04E-02 2.05E-02 1.52E-02 limit (Organ Dose Rate)
+
- T-3 i
I
. -. . . . . . .~ . . . . . . . - - . - . - . - . . ..- . - . - .- . .. . - - . . -
TABLE 7.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2
- 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 1.40E-01 1.09E-01 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
Kr-85 Ci 0.00E+00 0.00E+00 2.29E-05 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 2.57E-06 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 3.33E-07 0.00E+00 Xe-133 Ci 5.32E+00 5.52E-01 9.84E-01 2.07E-01 Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci O.00E+00 0.00E+00 1.61E-02 0.00E+00 Xe-138 f.i 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 5.32E+00 5.52E-01 1.14E+00 3.16E-01
- 2. Iodines I-131 Ci 0.00E+00 0.00E+00 0'. 4 0 E + 0 0 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Cf 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates l H-3 Ci 2.30E+00 4.56E+00 1.78E-01 5.89E-02 Total for period Ci 2.3CE+00 4.56E+00 1.78E-01 5.89E-02 T-4
TABLE 7.4 (con' t . )
GASEOUS EFFLUENTS--GROUND LEVEL RELEASES i
1 I
Continuous Mode Batch Mode l Nuclides Released Units Quarter Quarter Quarter Quarter l 3 4 3 4
- 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 1.64E-01 1.71E-01 Kr-85M Ci O.00E+00 0.00E+00 4.78E-03 0.00E+00 l Kr-85 Ci 0.00E+00 0.00E+00 1.71E+00 7.30E-02 Kr-87 Ci 0.00E+00 0.00E+00 4.75E-03 0.00E+00 l Kr-88 Ci 0.00E+00 0.00E+00 8.86E-03 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 2.99E-05 Xe-133M Ci 0.00E+00 0'.00E+00 1.71E-03 0.00E+00 Xe-133 Ci 8.18E+00 9.65E+00 5.12E-01 4.30E-01 l Xe-135M Ci 0.00E+00 0.00E+00 1.47E-02 0.00E+00 l
Xe-135 Ci 0.00E+00 0.00E+00 6.15E-02 0.00E+00 l
Xe-138 Ci 0.00E+00 0.00E+00 3.25E-03 0.00E+00 i Total for period Ci 8.18E+00 9.65E+00 2.49E+00 6.73E-01 i
- 2. Iodines I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0'.'0 0 E + 0 0 0.00E+00 l Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates i
H-3 Ci 9.14E+00 6.74E+00 6.85E-02 1.11E-01 Rb-88* Ci 0.00E+00 0.00E+00 1.13E-02 0.00E+00 Cs-138* Ci 0.00E+00 0.00E+00 5.98E-04 0.00E+00
- Total for period Ci 9.14E+00 6.74E+00 8.04E-02 1.11E-01 l
l
- Note: Half lives c 8 days j l !
l T-5 l
- - n . -
l TABLE 7.5 LIOUID EFFLUENTS--SUMMATION OF ALL RELEASES Units Quarter Quarter Quarter Quarter Est. Total l 1 2 -3 4 Error, %
1 I A. Fission and Activation Products
- 1. Total release (not Ci 3.92E-02 3.91E-02 1.95E-02 2.73E-02 3.03E+01 including tritium, gases, alpha)
- 2. Average diluted pCi/ml 1.16E-09 1.01E-09 5.01E-10 1.07E-09 concentration during period
- 1. Total release Ci 1.68E+02 1.78E+02 1.70E+02 3.24E+02 1.34E+01
- 2. Average diluted pCi/ml 4.96E-06 4.60E-06 4.35E-06 1.27E-05 concentration during period
- 1. Total release C1 1.41E-03 3.90E-04 6.89E-06 1.29E-03 1.16E+01
- 2. Average diluted pCi/ml 4.16E-11 1.01E-11 1.77E-13 5.05E-11 concentration during period
D. Gross Alpha Radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N/A E. Volume of waste released Liters 2.48E+06 2.23E+06 2.15E+06 1.52E+06 2.20E+00 (prior to dilution)
F. Volume dilution of water Liters 3.39E+10 3.86E+10 3.90E+10 2.55E+10 1.00E+01 used during period (Note 1)
Note 1: The dilution volume reported is the total dilution volume l during periods when effluent releases were occurring.
The additional dilution volume available when there are l no effluent releases occurring is not included.
I T-6
TJuBLE 7.6 LIOUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 H-3 Ci 0.00E+00 0.00E+00 1.6BE+02 3.7BE+02 Na-24 Ci 0.00E+00 0.00E+00 9.67E-06 0.00E+00 Cr-51 Ci O.00E+00 0.00E+00 5.46E-04 4.94E-04 Mn-54 Ci O.00E+00 0.00E+00 3.29E-04 1.15E-03 Fe-55 Ci 0.00E+00 0.00E+00 1.30E-02 1.69E-02 Co-57 Ci O.00E+00 0.00E+00 6.12E-06 2.05E-05 Co-58 Ci 0.00E+00 0.00E+00 5.14E-03 5.9BE-03 Fe-59 Ci 0.00E+00 0.00E+00 4.64E-04 1.42E-04 Co-60 Ci 0.00E+00 0.00E+00 1.6aE-03 4.21E-03 Zn-65 Ci 0.00E+00 0.00E+00 0.00E+00 2.86E-05 Se-75 Ci 0.00E&OO 0.002+00 0.00E+00 3.39E-05 Sr-92 Ci 0.00E+00 0.00E+00 0.00E+00 1.66E-05 Zr-95 Ci 0.00E+00 0.00E+00 5.39E-05 7.39E-05 Nb-95 Ci 0.00E+00 0.00E+00 1.67E-04 1.70E-04 Mb-97 Ci 0.00E+00 0.00E+00 1.91E-05 9.41E-06 Mo-99 Ci 0.00E+00 0.00E+00 4.09E-06 4.94E-06 Tc-99M Ci 0.00E+00 0.00E+00 3.99E-06 4.81E-06 Aa-110M Ci 0.00E+00 0.00E+00 2.53E-04 3 . 0 B'f.- 0 5 Sn-113 Ci 0.00E+00 0.00E+00 1.52E-05 1.96E-05 In-113M Ci 0.00E+00 0.00E+00 1.91E-05 2.25E-05 Sb-122 Ci 0.00E+00 0.00E+00 3 '. '6 6 E - 0 4 0.00E+00 Sb-124 Ci 0.00E+00 0.00E+00 1.56E-03 5.44E-04 Sb-125 Ci 0.00E+00 0.00E+00 1.45E-02 9.66E-03 Sb-126 Ci 0.00E+00 0.00E+00 2.00E-04 4.89E-06 Sb-127 Ci 0.00E+00 0.00E+00 2.34E-05 0.00E+00 I -131 Ci 0.00E+00 0.00C+00 1.66E-04 2.93E-0(_
Te-131M Ci 0.00E+00 0.00E+00 5.21E-06 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 2.57E-04 3.25E-05 cm-137 C1 0.00E+00 0.00E+00 5.40E-04 B.0BE-05 La-140 Ci 0.00E+00 0.00E+00 2.14E-05 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 1.93E-05 1.16E-04 Termi for nar4nd ci o_00E+00 o.coE+oo ; saE+02 i_7aE+02 l l
T-7
- l l
l
TABLE 7.6 (continued)
LIOUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Kr-85 Ci 0.00E+00 0.00E+00 4.11E-04 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 9.99E-04 3.90E-04 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tneal for carind Ci 0.00E+00 0.00E+00 1.41F-03 3.90E-04
'o T-8
l l
. I TABLE 7.6 (continued)
LIOUID EFFLUENTS l
Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 H-3 Ci 0.00E+00 0.00E+00 1.70E+02 3.24E+02 Cr-51 Ci 0.00E+00 0.00E+00 4.92E-05 2.04E-03 Mn-54 Ci 0.00E+00 0 00E+00 3.65E-04 9.96E-04 Fe-55 Ci 0.00E+00 0.00E+00 9.72E-03 5.03E-03 Co-57 Ci 0.00E+00 0.00E+00 4.46E-06 3.50E-05 Co-58 Ci 0.00E+00 0.00E+00 2.50E-03 7.20E-03 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 3.47E-05 Co-60 Ci 0.00E+00 0.00E+00 2.92E-03 4.10E-03 Zn-65 Ci 0.00E+00 0.00E+00 0.00E+00 3.09E-05 Sr-92 Ci 0.00E+00 0.00E+00 2.17E-04 4.29E-06 Zr-95 Ci 0.00E+00 0.00E+00 1.62E-05 6.18E-04 Nb-95 Ci 0.00E+00 0.00E+00 2.92E-05 9.79E-04 Zr-97 Ci 0.00E+00 0.00E+00 1.75E-05 1.41E-06 Nb-97 Ci 0.00E+00 0.00E+00 4.21E-06 1.57E-05 Aa-110M Ci 0.00E+00 0.00E+00 1.09E-03 5.14E-04 Sn-113 Ci 0.00E+00 0.00A+00 1.04E-05 1.03E-04 In-113M Ci 0.00E+00 0.00E+00 6.12E-06 1.33E-04 Sn-117M Ci 0.00E+00 0.00R+00 0 .'0 0 E+ 0 0 1.29E-05 Sb-125 Ci 0.00E+00 0.00E+00 2.27E-03 5.49E-03 ;
4 j
I-131 Ci 0.00E+00 0.00E+00 7.91E-06 0.00E+00, i I-133 Ci 0.00E+00 0.00E+00 6.03E-06 0.00E+00 cm-134 Ci 0.00E+00 0.00E+00 9.77E-05 0.00E+00 cm-136 Ci 0.00E+00 0.00E+00 4.37E-05 0.00E+00 cm-137 Ci 0.00E+00 0.00E+00 1.57E-04 0.00E+00 No-239 Ci 0.00E+00 0.00E+00 9.BRE-06 0.00E+00 Term 1 far nar4nd ci 0.00E+00 0.00E+00 1.70E+02 3.2dE+02 1
T-9 l
T
! l l
l l l l TABLE 7.6 (continued) j i
LIOUID EFFLUE M !
i l
Continuous Mode Batch Mode !
/
Nuclides Released Units Quarter Quart'sr Quarter Quarttt 3 4 3 4 mammmer Vr-85 Ci 0.00E t CJ 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 6.89E-06 1.24E-03 1 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 4.51E-05 Tet al for neriod ci 0.00F+00 0.00E+00 6.99E-06 1.29E-03 I
i l
l I
TABLE 7.7 DOSES FROM LIOUID EFFLUENTS (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Body ___
Quarter 1 1.73E-03 1.81E-02 1.73E-02 1.54E-02 1.62E-02 1.60E-02 1.71E-02
% Limit 1.73E-02 1.81E-01 5.78E-01 1.54E-01 1.62E-01 1.60E-01 1.71E-01 per unit Quarter 2 2.39E-04 2.08E-02 2.07E-02 2.06E-02 2.06E-02 2.07E-02 2.20E-02
% Limit 2.39E-03 2.08E-01 6.91E-01 2.06E-01 2.06E-01 2.07E-01 2.20E-01 per unit _
Quarter 3 4.18E-04 2.15E-02 2.13E-02 2.08E-02 2.11E-02 2.10E-02 2.12E-02
% Limit 4.18E-03 2.15E-01 7.11E-01 2.08E-01 2.11E-01 2.10E-01 2.12E-01 per unit Quarter 4 2.49E-05 1.72E-02 1.72E-02 1.71E-02 1.71E-02 1.72E-02 2.61E-02
% Limit 2.49E-04 1.72E-01 5.72E-01 1.71E-01 1.71E-01 1.72E-01 2.61E-01 per unit Tota! 2.41E-03 7.77E-02 7.65E-02 7.39E-02 7.50E-02 7.50E-02 8.64E-02 1995 ,
% Limit '1.21E-02 3.88E-01 1.28E+00 3.70E-01 3.75E-01 3.75E-01 4.32E-01 per unit I i
l i T-10 l
s
TABLE 7.8 i DOSES FROM GASEOUS EFFLUENTS Noble Gas Air Dose (mrad)
Air Dose (mrad) Gamma Air Beta Air Quarter 1 3.72E-04 7.45E-04 *
% Limit per unit 3.72E-03 3.72E-03 '
Quarter 2 1.34E-04 1.21E-04
% Limit per unit 1.34E-03 6.04E-04 Quartar 3 5.22E-04 1.39E-03
% Limit pe. unit 5.22E-03 6.94E-03 Quarter 4 5.38E-04 1.18E-03
% Limit per unit 5.38E-03 5.90E-03 Total 1995 1.57E-03 3.43E-03
% Limit per unit 7.83E-03 8.58E-03
'o l
I T-11
TABLE 7.9 DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Adult Age Group, (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 0.00E+00 2.11E-03 2.11E-03 2.11E-03 2.11E-03 2.11E-03 2.11E-03 0.00E+00 t Limit 0.00E+00 1.41E-02 1.41E-02 1.41E-02 1.41E-02 1.41E-02 1.41E-02 0.00E+00 per Unit Qtr-2 0.00E+00 3.93E-03 3.93E-03 3.93E-03 3.93E-03 3.93E-03 3.93E-03 0.00E+00 t Limit 0.00E+00 2.62E-D2- 2.62E-02 2.62E-02 2.62E-02 2.62E-02 2.62E-02 0.00E+00 per Unit Qtr-3 0.00E+00 7.85E-03 7.85E-03 7.85E-03 7.85E-03 7.85E-03 7.85E-03 0.00E+00 t Limit 0.00E+00 5.23E-02 5.23E-02 5.23E-02 5.23E-02 5.23E-02 5.23E-02 0.00E+00 per Unit Qtr-4 0.00E+00 5.84E-03 5.84E-03 5.84E-03 5.84E-03 5.84E-03 5.84E-03 0.00E+00 t Limit 0.00E+00 3.89E-02 3.89E-02 3.89E-02 3.89E-02 3.89E-02 3.89E-02 0.00E+00 per Unit Total 0.00E+00 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 0.00E+00 1995
% Limit 0.00E+00 6.58E-02 6.58E-02 6.5BE-02 6.58E-02 6.58E-02 6.58E-02 0.00E+00 per Unit T-12
TABLE 7.10 DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Teen Age Group, . (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 0.00E+00 2.43E-03 2.43E-03 2.43E-03 2.43E-03 2.43E-03 2.43E-03 0.00E+00
% Limit 0.00E+00 1.62E-02 1.62E-02 1.62E-02 1.62E-02 1.62E-02 1.62E-02 0.00E+00 g r Unit Q'e r- 2 0.00E+00 4.52E-03 4.52E-03 4.52E-03 4.52E-03 4.52E-03 4.52E-03 0.00E+00
% Limit 0.00E+00 3.01E-02 3.01E-02 3.01E-02 3.01E-02 3.01E-02 3.01E-02 0.00E+00 per Unit Qtr-3 0.00E+00 9.02E-03 9.02E-03 9.02E-03 9.02E-03 9.02E-03 9.02E-03 0.00E+00
% Limit 0.00E+00 6.01E-02 6.01E-02 6.01E-02 6.01E-02 6.01E-02 6.01E-02 0.00E+00 per Unit
- Qtr-4 0.00E+00 6.71E-03 6.71E-03 6.71E-03 6.71E-03 6.71E-03 6.71E-03 0.00E+00
% Limit 0.00E+00 4.47E-02 4.47E-02 4.47E-02 4.47E-02 4.47E-02 4.47E-02 0.00E+00 per Unit Total 0.00E+00 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 0.00E+00 1995
% Limit 0.00E+00 7.56E-02 7.56E-02 7.56E-02 .7.56E-02 7.56E-02 7.56E-02 0.00E+00 per Unit i
T-13 t
- TABLE 7.11 i
DOSES FROM GASEOUS EFFLUENTS t
Iodines, Particulates and Tritium .
Child Age Group, (mrem) j Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 0.00E+00 3.48E-03 3.48E-03 3.4BE-03 3.48E-03 3.48E-03 3.48E-03 0.00E+00 i % Limit 0.00E+00 2.32E-02 2.32E-02 2.32E-02 2.32E-02 2.32E-02 2.32E-02 0.00E+00 l per Unit '
1 Otr-2 0.00E+00 6.47E-03 6.47E-03 6.47E-03 6.47E-03 6.47E-03 6.47E-03 0.00E+00
% Limit 0.00E+00 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 0.00E+00 per Unit Qtr-3 0.00E+00 1.29E-02 1.29E-02 1.29E-02 1.29E-02 1.29E-02 1.29E-02 0.00E+00
% Limit 0.00E+00 8.62E-02 8.62E-02 8.62E-02 8.62E-02 8.62E-02 8.62E-02 0.00E+00 per Unit Qtr-4 0.00E+00 9.61E-03 9.61E-03 9.61E-03 9.61E-03 9.61E-03 9.61E-03 0.00E+00
% Limit 0.00E+00 6.41E-02 6.41E-02 6.41E-02 6.41E-02 6.41E-02 6.41E-02 0.00E+00 per Unit Total 0.00E+00 3.25E-02 3.25E-02 3.25E-02 3.25E-02 3.25E-02 3.25E-02 0.00E+00 1995 ,
% Limit 0.00E+00 1.08E-01 1.08E-01 1.08E-01 1.08E-01 1.08E-01 1.08E-01 0.00E+00 per Unit I
l T-14 6
i
[
1
TABLE 7.12 DOSES FROM GAS 3OUS EFFLUENTS Iodines, Particulates and Tritium
, Infant Age Group, (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin t Body -
Qtr-1 0.00E+00 2.71E-03 2.71E-03 2.71E-03 2.71E-03 2.71E-03 2.71E-03 0.00E+00 j % Limit 0.00E+00 1.80E-02 1.80E-02 1.80E-02 1.80E-02 1.80E-02 1.80E-02 0.00E+00 ;
per Unit Qtr-2 0.00E+00 5.03E-03 5.03E-03 5.03E-03 5.03E-03 5.03E-03 5.03E-03 0.00E+00 l % Limit 0.00E+00 3.35E-02 3.35E-02 3.35E-02 3.35E-02 3.35E-02 3.35E-02 0.00E+00 ;
per Unit i Qtr-3 0.00E+00 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 0.00E+00 f I
% Limit 0.00E+00 6.70E-02 6.70E-02 6.70E-02 6.7dE-02 6.70E-02 6.70E-02 0.00E+00 per Unit Qtr-4 0.00E+00 7.47E-03 7.47E-03 7.47E-03 7.47E-03 7.47E-03 7.47E-03 0.00E+00
% Limit 0.00E+00 4.98E-02 4.98E-02 4.98E-02 4.98E-02 4.98E-02 4.98E-02 0.00E+00 per Unit Total 0.00E+00 2.52E-02 2.52E-02 2.52E-02 2.52E-02 2.52E-02 2.52E-02 0.00E+00 1995 6
% Limit 0.00E+00 8.42E-02 8.42E-02 8.42E-02 8.42E-02 8.42E-02 8.42E-02 0.00E+00 iper Unit l
T-15
TABLE 7.13 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS :
F A. Solid Waste Shipped Offsite for Burial or Disposal j (Not Irradiated Fuel)
- 1. Type of waste Shipped Shipped Buried Buried m Ci m3 Ci
- a. Spent resins / filters 1.01E+01 1.13E+03 1.01E+01 1.13E+03
- b. Dry active waste 2.73E+02 6.09E-01 4.67E+00 3.51E-01
- c. Irradiated components ,
- d. Other (oil sent to 4.60E+00 3.65E-05 1 processor for '
incineration)
TOTAL 2.88E+02 1.13E+03 1.48E+01 1.13E+03 Includes 129.9 m3 of suspected clean trash sent to offsite processor for monitoring before final disposition.
Eqt;.g: Shipped volumes and curies are not always equal to the buried volumes and curies due to some burials occurring outside the twelve month time period in which the shipments occurred.
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity ;
Composition (by type of waste) ', (Ci) !
Cs-137 2.10 2.38E+01 Cs-134 1.47 1.66E+01 Ni-63 35.82 4.06E+02 Mn-54 1.58 1.79E+01 H-3 0.00 1.96E-02 C-14 0.03 3.07E-01 Tc-99 LLD I-129 LLD Other* M 1.74E+01 Total 100.00 1.13E+03
- Nuclides representing <1% of total shipped activity: Co-58, Ni-59, Ru-106, Sb-125, Pu-238, Pu-239/40, Pu-241, Am-241, Cm-242, Cm243/244.
T-16
TABLE 7.13 (Continued)
SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity composition (by type of waste) (Ci)
- b. Dry active waste Co-58 28.79 1.75E-01 Co-60 9.59 5.84E-02 Fe-55 54.31 3.31E-01 H-3 1.16 7.04E-03 Ni-63 3.64 2.22E-02 Tc-99 LLD ,
I-129 LLD l C-14 0.60 3.66E-03 Other* M 1.17E-02 Total 100.00 6.09E-01
- Nuclides representing <1% of total shipped activity: Mn-54, Fe-59, Zr-95, Nb-95, Cs-134, Cs-137, Pu-241, Cm-242.
I
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity Composition (by type of waste) (Ci)
- c. Other - Oil sent to processor for Co-58 11.60 4.23E-06 1 incineration Co-60 12.89 4.70E-06 l Fe-55 69.95 2.55E-05 Ni-63 4.77 1.74E-06 H-3 0.00 1.73E-09 C-14 0.46 1.66E-07 Tc-99 IJ,.D I-129 LLD Other* M 1.15E-07 Total 100.00 3.65E-05
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, - - - _ -- = - - - - - = - - '
1 TABLE 7.13 (Continued)
SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS s
l
- 3. solid waste Disposition (Mode of Transportation: Truck) i Waste Type Waste Container Number of Destination Class Type Shipments
- a. Resin / filters B Poly
- HIC 1 Chem-Nuclear i Barnwe11,SC C ' soly
- HIC 2 Chem-Nuclear Barnwell,SC
- b. Dry active A Strong- 5 SEG waste tight Oak Ridge,TN A Strong- 4 AERC tight Oak Ridge,TN
- High Integrity Container B. Irradiated Fuel Shipaments (Disposition)
Number of Shioments Mode of Transoortation Destination 0 N/A N/A o,
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ATTACHMENT 8.1 i
Offsite Dose Calculation Manual I
for CPSES Unit 1 and Unit 2 1
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! l OFFSITE DOSE CALCULATION NANUAL l
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- 1 l . TU ELECTRIC l
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, COMANCHE PEAK STEAM ELECTRIC STATION l
UNITS 1 AND 2 l
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Rev 8 01/93
TARLE OF CONTENTS
. f.111 List of Tables v List of Figures vii Cross Reference to Technical Specifications and REC viii References xi 4
Introduction xit
, PART I - RADIOLOGICAL EFFLUENT CONTROLS i
. SECTION 1.0 - DEFINITIONS I10 l SECTION 2.0 - NOT USED I 2-0 SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVEILLANCE I 3/4-0 REQUIREMENTS 3/4.0 - Applicabifity I 3/4-1 1
3/4.3.3.4 - Radioactive Liquid Effluent I 3/4-3 Monitoring Instrumentation
- 3/4.3.3.5 - Radioactive Gaseous Effluent I 3/4-8 Monitoring Instrumentation 3/4.3.3.6 - Meteorological Monitoring I 3/4-13 i Instrumentation i
i 3/4.7.15 - Sealed Source Contamination ! 3/4-15 3/4.11.1 -
Liquid Effluents I 3/4-17
- 3/4.11.1.1 - Concentration Controls I 3/4-17 3/4.11.1.2 - Dose I 3/4-21 3/4.11.1.3 - Liquid Radweste Treatment System I 3/4-22
! 3/4.11.1.4 - LVW Pond Resin Inventory I 3/4-22a 1
l 3/4.11.2 Gaseous Effluents I 3/4-23 3/4.11.2.1 - Dose Rate I 3/4-23 l
3/4.11.2.2 - Dose - Noble Gases ! 3/4-27 j 3/4.11.2.3 - Dose - Iodine-131. I 3/4-28 lodine-133. Tritius, and Radioactive Material in Particulate Fore 3/4.11.2.4 - Gaseous Radweste Treatment System I 3/4-29 COMANCHE PEAK - UNITS 1 AND 2 i Rev. 8 1/93
TABLE OF CONTENTS (continued)
Number / Title g 3/4.11.4 -
Total Dose I 3/4-30 3/4.12.1 -
Radiological Environmental I 3/4-32 Monitoring Program 3/4.12.2 -
Land Use Census I 3/4-44 3/4.12.3 -
Interlaboratory Comparison I 3/4-45 Program BASES I B 3/4-0 SECTION 5.0 - DESIGN FEATURES I 5-0 5.1.3 -
Map Defining Controlled Areas. I 5-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents l
SECTION 6.0 - ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 -
Annual Radiological Environmental I 6-1 Operating Report 6.9.1.4 -
Annual Radioactive Effluent I 6-2 l Release Report 1
6.14 -
Offsite Dose Calculation Manual I 6-3 (00CM)
PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS II 1-1 1.1 10CFR20 and Radiological Effluent Control II 1-2 3/4.11.1.1 Compliance 1.1.1 Isotopic Concentration of the II 1-3 Waste Tank 1.1.2 EffluentFlowRate(f) II 1-3 1.1.3 Dilution of Liquid Effluents II 1-4 1.1.4 ActualDilutionFactor(ADF) II 1-5 l 1.1.5 RequiredOilutionFactor(RDF) II 1-6 1.1.6 10CFR20 Compliance II 1-6 I
CfMANCHE PEAK - UNITS 1 AND 2 11 REV. 10 4/94
TABLE OF CONTENTS (continued) '
Number / Title .P.121 1.2 Radiation Monitor Alarm Setpoints II 1-7 1.2.1 Primary Liquid Effluent Monitor II 1-7 ,
(XRE-5253) '
1.2.2 Turbine Building Sump Effluent II 1-8 Radiation Monitors (1RE-5100 and 2RE-5100) 1.2.3 Service Water Effluent Radiation II 1-9 Monitors (1RE-4269/4270 and 2RE-4269/4270) I i
1.2.4 Auxiliary Building to LVW Pond II 1-9a Radiation Monitor (XRE-5251A) 1.3 Dose Calculations for Liquid Effluents II 1-10 1.3.1 Calculation of Dose Due to II 1-11 Liquid Releases 1.3.2 Calculation of Dose Due to II 1-12 Radionuclide Buildup in the Lake 1.4 Dose Projections for Liquid Effluents II 1-15 1.5 Definitions of Common Liquid Effluent II 1-16 Parameters 2.0 GASEOUS EFFLUENTS II 2-1 2.1 Radiological Effluent Control II 2-3 3/4.11.2.1 Compliance 2.1.1 Dose Rates Due to Noble Gases II 2-3 2.1.2 Dose Rates Due to Radiciodines, II 2-5 ;
Tritium, and Particulates 2.2 Gaseous Effluent Monitor Setpoints II 2-6 2.2.1 Plant Vent Effluent Release Rate II 2-7 Monitors (XRE-5570A/XRE-55708) 2.2.2 Plant Vent Stack Noble Gas Activity II 2-8 Monitors (XRE-5570A/XRE-55708 and XRE-5567A/XRE-55678) 2.2.3 Sampler Flow Rate Monitors II 2-9 (X-RFT-5570A-1/X-RFT-55708-1) 2.2.4 Auxiliary Building Ventilation II 2-9 Exhaust Monitor (XRE-5701)
COMANCHE PEAK - UNITS 1 AND 2 iii Rev. 9 9/93
TABLE OF CONTENTS (continued)
Number / Title h
2.2.5 Containment Atmosphere Gaseous II 2-10 l Monitors (1RE-5503/2RE-5503) 2.3 Dose Calculati ons for Gaseous Effluents II 2-12 !
l 2.3.1 Dose Due to Noble Gases II 2-12 !
l 2.3.2 Dose Due to Radiciodines, Tritium. II 2-13 l and Particulates '
2.4 Dose Projections for GaseavaEffluents II 2-15 2.5 Dose Calculations to Support Other II 2-16 Requirements ,
i 2.6 Meteorological Model II 2-18 l 1
2.6.1 Dispersion Calculations II 2-18 I i
2.6.2 Deposition Calculations II 2-20 l 2.7 Definitions of Gaseous Effluents Parameters II 2-21 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1
! 3.1 Sampling Locations II 3-1 1
3.2 Interlaboratory Comparison Program II 3-1 APPENDICES !
A. Pathway Dose Rate Parameter A-1
- 8. Inhalation Pathway Dose Factor B-1 l C. Ground Plane Pathway Dose Factor C-1 D. Grass-Cow-Milk Pathway Dose Factor D-1 l E. Cow-Meat Pathway Dose Factor E-1 l F. Vegetation Pathway Dose Factor F-1 G. Supplemental Guidance Statements - Deleted G-1 i
COMANCHE PEAK - UNITS 1 AND 2 iv 9/93 l
List of Tables Table No. 1111.1 PASLt PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.1 Frequency Notation I 1-5 1.2 Operational Modes I 1-6 3.3-7 Radioactive Liquid Effluent Monitoring I 3/4-4 Instrumentation l
l 4.3-3 Radioactive Liquid Effluent Monitoring I 3/4-6 Instrumentation Surveillance Requirements 3.3-8 Radioactive Gaseous Effluent Monitoring I 3/4-9 Instrumentation 4.3-4 Radioactive Gaseous Effluent Monitoring I 3/4-11 j Instrumentation Surveillance Requirements 3.3-9 Meteorological Monitoring Instrumentation I 3/4-14 4.11-1 Radioactive Liquid Waste Sampling and I 3/4-18 Analysis Progras 4.11-2 Radioactive Gaseous Waste Sampling and I 3/4-24 Analysis Program 3.12-1 Radiological Environmental Monitoring I 3/4-34 Program l
3.12-2 Reporting Levels for Radioactivity I 3/4-40 Concentrations in Environmental Samples l 4.12-1 Detection Capabilities for Environmental I 3/4-41 l Sample Analysis (LL0s)
l PART II - CALCULATIONAL METHODOLOGIES I
l 1.1 Summary of Liquid Release Pathways !! 1-19 l 1.2 Site Related Ingestion Dose Commitment II 1-20 Factor (Ag )
2.1 Summary of Gaseous Release Pathways !! 2-26 2.2 Dose Factors for Exposure to a Semi- II 2-27
- Infinite Cloud of Noble Gases l 2.3 Pathway Dose Rate Parameter (Pj) II 2-28 i
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COMANCHE PEAK - UNITS 1 AND 2 y Rev. 8 1/93
List of Tables '
Table No. T.itle E111 I i
2.4 Pathway Dose Factors !! 2-29 ;
l 2.5 Controlling Receptor Pathways and II 2-50 Locations, and Atmospheric Dispersion Parameters (For Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3) 3.1 Environmental Sampling Locations II 3-3 COMANCHE PEAK - UNITS 1 AND 2 vi Rev. 8 1/93
TABLE OF CONTENTS List of Fiaures E1GEft Iltlft P.Agit PART I - RADIOLOGICAL EFFLUENT CONTROLS 5.1-3 Controlled Area. Unrestricted Area I 5-2 and Site Boundary for Radioactive Gaseous and Liquid Effluents PART II - CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways II 1-24 1.2 Circulating Water Pump Curves II 1-26 1.3 Energy Response to Gamma Radiations II 1-27 for RD-33 Type Detector 2.1 Gaseous Waste Processing System II 2-52 2.2 Plume Depletion Effect for Ground- II 2-53 i Level Releases 2.3 Vertical Standard Deviation of II 2-54 Material in a Plume 2.4 Relative Deposition for Ground- II 2-55 Level Releases 25 Open Terrain Correction Factor II 2-56 3.1 Radiological Environmental Monitoring II 3 4 Locations i
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COMANCHE PEAK - UNITS 1 AND 2 vii REV. 12 12/95
Cross Reference to Technical Soecifications and REC Number or Document section Reautrement ODCN Section PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC)
Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and j
operability surveillance. and 3/4.3.3.5 setpoint requirements Tech Specs 6.8.3.e.2 Limit liquid effluent concentration 3/4.11.1.1 Tech Specs 6.8.3.e.3 Effluent monitoring. sampling. and 3/4.11.1.1 and
- analysis requirements 3/4.11.2.1 Tech Specs 6.8.3.e.4 Limit doses due to liquid effluents 3/4.11.1.2 Tech Specs 6.8.3.e.S Determine cumulative and projected 3/4.11.1.2
- doses due to radioactive effluents 3/4.11.2.2 3/4.11.2.3.
) 3/4.11.1.3 and !
j 3/4.11.2.4 l Tech Specs 6.8.3.e.6 Effluent treatment systems 3/4.11.1.3 and 4
operability requirements 3/4.11.2.4
~
l Tech Specs 6.8.3.e.7 Limit gaseous effluent dose rate 3/4.11.2.1 l
- Tech Specs 6.8.3.e.8 Limit noble gas air dose 3/4.11.2.2
- Tech Specs 6.8.3.e.9 Limit gaseous effluent iodine and 3/4.11.2.3 particulate dose
- Tech Specs 6.8.3.e.10 Limit total dose 3/4.11.4 l Tech Specs 6.8.3.f.1 Monitoring, sampling. and analysis 3/4.12.1 of radiation in the environment
- Tech Specs 6.8.3.f.2 Land Use Census 3/4.12.2 Tech Specs 6.8.3.f.3 Interlaboratory Comparison Program 3/4.12.3 PART II - CALCULATIONAL METHODOLOGIES i REC 3/4.71.1.1 Liquid effluent concentration 1.1 i
} REC 3/4.11.1.2 Dose due to liquid effluents 1.3
[ REC 3/4.11.1.3 Dose projections for liquid 1.4 releases i
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COMANCHE PEAK - UNITS 1 AND 2 viii Rev. 8 1/93
CROSS-REFERENCE TO TECHNICAL SPECIFfCATIONS AND REC (continued)
Number or Document Section Recuirement ODCM Section REC 3/4.11.2.1.a Dose rate due to noble gases 2.1.1 REC 3/4.11.2.1.b Dose rate due to iodine, 2.1.2 tritium, and particulates with haif-lives greater ,
i than eight days ~
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REC 3/4.11.2.2 Air dose due to noble gases 2.3.1 REC 3/4.11.2.3 Doses due to iodine, 2.3.2 tritium, and particulates l with half-lives greater than eight days :
REC 3/4.11.2.4 Dose projections for 2.4 gaseous releases REC 3/4.11.4 Total dose due to releases 2.5 of radioactivity and direct radiation e REC 3/4.12.1 Description of radiological 3.1 environmental sampling ,
locations 1 REC 3/4.12.2 Dose calculations for 2.5 identifying changes to environmental sampling locations REC 3/4.12.3 Description of the 3.2 Interlaboratory Comparison Program <,
REC 3.3.3.4 Radioactive liquid effluent monitoring channels alarm / trip setpoints
- liquid waste monitor 1.2.1 (XRE-5253)
- service water monitors 1.2.3 (1RE-4269/4270 and 2RE-4269/4270)
- auxiliary building to LVW Pond 1.2.4 radiation monitor (XRE-5251A)
COMANCHE PEAK - UNITS 1 AND 2 ix Rev. 9 9/93
Cross Reference to Technical Snecifications and REC Number or M Section Reautrement ODCM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alare/ trip setpoints o noble gas release rate monitors 2.2.1 XRE-5570A and XRE 55708 (WGRM release rate channels) o noble gas activity monitors 2.2.2 XRE-5570A and XRE-55708 (WRGM low range activity channel)
XRE-5567A and XRE-55678 (PIG noble gas channel) o waste gas holdup systcm monitor 2.2.4 (auxiliary building vent monitor)
XRE-5701 o sampler flow rate monitor 2.2.3 XFT-5570AZ/BZ Tech Specs 3.3.3.1 Radiation monitoring channels alare/ trip satpoint
... o Containment atmosphere gaseous 2.2.5 monitors (containment vent monitors) 1RE-5503 and 2RE-5503 Tech Specs 6.9.1.4 Assessment of radiation doses due 2.5 REC 6.9.1.4 to liquid and gaseous effluents released during the previous year Tech Specs 6.9.1.4 Assessment of doses to members of 2.5 REC 6.9.1.4 the public inside the site boundary Tech Specs 6.9.1.4 Assessment of doses to the most 2.5 REC 6.9.1.4 likely exposed member of the public from reactor releases and direct radiation COMANCHE PEAK - UNITS 1 AND 2 x Rev. 8 1/93 l
i REFERENCES ;
1 ,
- 1. Boegli. J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Effluent Technical Specifications i I
for Nuclear Power Plants." NUREG-0133 (October 1978).
l
- 2. Calculation of Annual Doses to Man from Routine Releases of 1 j Reactor Effluents for the Purpose of Evaluating Compliance with l 10CFR Part 50, Appendix I, U. S. NRC Regulatory Guide 1.109. Rev.
1 (October 1977).
5
- 3. " Environmental Report." TU Electric, Comanche Peak Steam Electric j Station.
[ 4. " Final Safety Analysis Report," TU Electric, Comanche Peak Steam l Electric Station.
! 5. Methods for Estimating Atmospheric Transport and Dispersion of l Gaseous Effluents in Routine Releases from Light-Water Cooled j Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).
} 6. Methods for Estimating, Atmospheric Transport and Dispersion of l Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors. U.S. NRC Regulatory Guide 1.111. Rev. 1 (July 1977).
- 7. Meteorology and Atomic Energy
- Edited by Slade. D. M.; U. S. l l Department of Commerce (July 1968). 1
- 8. " Technical Specifications," TU Electric. Comanche Peak Steam 4
Electric Station.
- 9. Implementation of Programmatic Controls for Radiological Effluent j Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the l Process Control Program (Generic Letter 89-01), USNRC. January 31, 1989.
- 10. CPSES Technical Evaluation No. RP-90-3077, " Calculation of Site
. Related Ingestion Oose Commitment Factors For Sb-122."
- 11. " Calculation of Annual Doses to Man from Routine Releases of 2
Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I." USNRC Regulatory Guide 1.109 (March 1974).
- 12. Code of Federal Regulation, Title 10 Parts 20 and 50.
f 4
i COMANCHE P2AK - UNITS 1 AT G i xi Rev. 8 1/93
1NTR000CTf0N i The'0FFSITE DOSE CALCULATION MANUAL (00CM) is a supporting document of the CPSES Technical Specifications. Part I of the 00CM contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by
- Technical Specification 6.8.3. (2) descriptions of the information that should be L
i included in the Annual Radiological Environmental Operating and Annual 10 ,
Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.3 and 6.9.1.4. and (3) Controls for Meteorological Monitoring Instrumentation and i
Sealed Source Leakage. Part II of the 00CM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive '
- liquid and gaseous effluents and in the calculation of liquid and gaseous
! effluent monitoring instrumentation alarm / trip setpoints. Liquid and Gaseous 12
^
- Radwaste Treatment System configurations are shown in Part II. Figures 1.1 and ,
2.1.
i
. The 00CM is maintained for use as a reference guide and training document on 12 l -accepted methodo l ogies and calculations. Changes in the calculation methods or
! parameters will be incorporated into the 00CM in order to assure that the 00CM represents the present methodology in all applicable areas. ' TV Electric initiated ctanges to the 00CM will be implemented in accordance with Section 6.14
- of the Technical Specifications. "
The OOCH follows the methodology and models su]gested by NUREG-0133 (Ref. 1) and i Regulatory Guide 1.109. Revision 1 (Ref. 2). Simplifying assumptions have been ,
2 applied in this manual where applicable to providt a more workable document for
! 1mplementing the Radiological Effluent Control requirements. This simplified approach will result in a more conservative dose evaluation, but requires the i
least amount of time for establishing compliance with regulatory requirements.
l This manual is designed to provide necessary information in order to simplify the
- dose calculations. The dose calculations can be optionally expanded to several
- levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculation in accordance with ;
Regulatory Guide 1.109. Future changes to the 00CM may be initiated to implement
. more complex calculations as systems become available and are validated that can
, reliably, economically and properly perform these more. complex calculations. A j beneficial approach to implementing the Radiological Effluent Control Program and 10 l Regulatory Guide 1.21 (Annual Radioactive Effluent Release Report) requirements j is to use a computerized system to determine the effluent releases and update cumulative doses.
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I l j 1.0 DEFINITIONS _
] The defined terms of this section appear in capitalized type and are i applicable throughout these Controls.
)
AGllE I 1.1 ACTION shall be that part of a Control which prescribes remedial i measures required under designated conditions. ,
t \
i ANALOG CHANNEL OPERATIONAL TEST I i 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a l simulated signal into the channel as close to the sensor as practicable to j verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG '
CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the j j alarm, interlock and/or Trip Setpoints such that the Setpoints are within i j the required range and accuracy. j CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the i channel such that it responds within the required range and accuracy to j known values of input. The CHANNEL CALIBRATION shall encompass the entire
- channel including the sensors and alarm, interlock and/or trip functions and may be p3rformed by any series of sequential, overlapping, or total l channel stepr'such that the entire channel is calibrated.
l 4
CHANNEL CHECK i
i 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status ;
j with other in/* cations and/or status derived from independent instrument
- channels measuring the same parameter.
DIGITAL CHANNEL OPERATIONAL TEST ,,
! 1.10 A O!GITAL CHANNEL OPERATIONAL TEST shall consist of exercising the
- digital computer hardware using data base manipulation and injecting j simulated process data to verify OPERASILITY of alarm and/or trip functions.
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l COMANCHE PEAK UNITS 1 AND 2 PART I 1-1 1/93
EI_NfT10NS 009F E001VAtENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131. 1-132. I-133. 1-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those 4 listed in Table III of TID-14844. " Calculation of Distance Factors for Power and I Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109. Revision 1. '
Cctober 1977.
FREQUENCY NOTATION l 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. l t
1 MEMBER (S) 0F THE PUBLIC l 1.18 MEMBER (S) 0F THE PUBLIC means an individual in a CONTROLLED or UNRESTRICTED 12 AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in ,
which the individual receives an occupational dose, l l
0FFSITE $5E CALCULATION MANUAL !
1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from I radioactive gaseous and liquid effluents in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual 10 Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.
OPERABtF - OPERABILITY 1.20 A system subsystem, train, component or device shall be<0PERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power. cooling or seal water lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are l also capable of performing their related support function (s).
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OEFINITIONS l
l OPERATIONAL MODE - MODE 1
1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
l PRIMARY PLANT VENTILATION SYSTEM 1.24 A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed ',nd i
installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing i
iodines or particulates from the gaseous exhaust stream prior to the .
}
release to the environment. Such a system is not considered to have any effect on noble gas effluents.
PURGE - PURGING 1.26 PURGE or PURGING shall be the controlled process of discharging air l
or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.
EATED THERMAL ~ POWER 1.29 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
l REPORTABLE EVENT 1.31 A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73.
SITE BOUNDARY 1.33 The SITE BOUNDARY shall be that line as shown in Figure 5.1-3.
SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. l THERMAL POWER I
1.38 TPF.RMAL POWER shall be the total reactor core heat transfer rate to the reacc.or coolant.
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DEFINITIONS UNRESTRICTED AREA 1.41 An UNRESTRICTED AREA means any area beyond the SITE BOUNDARY. 8 VENTING 1.42 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
WASTE GAS HOLDUP SYSTEM 1.43 A WASTE GAS HOLOUP SYSTEM shall be any system designed and installed l to reduce radioactive gaseous effluents by collecting Reactor Coolant !
System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
i
[g l80LLED AREA 8 1.44 A CONTROLLED AREA means an area outside of a restricted area, as 8 defined in 10 CFR 20.1003, but inside the SITE BOUNDARY, access to which can be limited by the licensee for any reason.
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'e REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 1-4 1/93
TABLE 1.1 FREOUENCY NOTATION gggIlg FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days 1
Q At least once per 92 days.
SA At least once per 184 days.
SR At least once per 9 months.
R At least once per 18 months.
S/U Prior to each reactor startup.
N.A. Not applicable.
P ., Completed prior to each release.
I, COMANCHE PEAK UNITS 1 AND 2 PART I 1-5 01/93
l TABLE 1.2 l
l OPERATIONAL MODES l
AVERAGE REACTIVITY % RATED COOLANT g CONDITION. Keff THERMAL POWER
- TEMPERATURE
- 1. POWER OPERATION 1 0.99 > 5% 1 3500F
- 2. STARTUP 1 0.99 l 1 5% 1 3500F
- 3. HOT STANDBY < 0.99 0 1 3500F
- 4. HOT SHUTDOWh < 0.99 0 3500F>Tavg
> 2000F
! 5. COLD SHUTDOWN < 0.99 0 5 2NOF
- 6. REFUELING ** 5 0.95 0 s la00F l l
l l
l
- Excluding decay heat.
1
! ** Fuel in the reactor vessel with the vessel head closure bolts less than l fully tensioned or with the head removed.
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COMANCHE PEAK - UNITS 1 AND 2 PART I 1-6 01/93 J
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I SECTION 2.0 NOT USED i
COMANCHE PEAK UNITS 1 AND 2 PART I 2-0 01/93
SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-0 01/93
3/4 CONTROLS AND SURVEfLLANCE REOUIREMENTS 3/4.0 APPLICABILITY # l CONTROLS l
3.0.1 Compliance with the Controls contained in the succeeding Controls is l required during the OPERATIONAL MODES or other conditions specified I therein; except that upon failure to meet the Control, the associated l ACTION requirements shall be met.
3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION rquirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a Control is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in;
- a. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- b. At least HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where correcti.ve measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual controls.
This control is not applicable in MODE 5 or 6.
3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTICM requires a shutdown if they are not met within a l specified time interval. Entry into an OPERATIONAL MODE or,ppecified condition may be made in acccrdance with ACTION requirements when conformance to them permits continued operttion of the facility for an unlimited period of time. This provisira shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
Exceptions to these requirements are stated in the individual controls, i
- The associated basis from the CPSES Technical Specifications applies to this section.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-1 1/93
l I
APPLICABILITY '
SURVEILLANCE REOUIREENTS i 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement.
l 4.0.2 Each Surveillance Requirement shall be performed within the 7 l specified time interval with a maximum allowable extension not to exceed l l 25% of the surveillance interval. Exceptions to these requirements are !
stated in the individual controls.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance Requirement 4.0.2, shall l constitute noncompliance with the OPERASILITY requirements for a Control.
l The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The i ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do l not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the
- Control has been performed within the stated surveillance interval or as
! otherwise spdCified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
Exceptions to these requirements are stated in the individual controls.
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- I COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-2 1/93
INSTRUMENTATf0N RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordance with CPSES TS 6.8.3.e.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be 8 determined and adjusted in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY: At all times.
ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels'0PERABLE, take the ACTION shown in Table 3.3-7. Restore the inoperable instrumentation to OPERABLE status 10 within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1
4.3.3.4 Each radioactive liquid effluent monitoring instrumentation channel l shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG l CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3.
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COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-3 REV. 10
TABLE 3.3-7 8
RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION h
n MINIMUM e CHANNELS x
g INSTRtMENT OPERABLE ACTION
?; 1. Radioactivity Monitors Providing Alarm and u Automatic Termination of Release
- a. Liquid Radweste Effluent Line (XRE-5253) 1 30 e
- b. Turbine Building (Floor Drains) Sumps Effluent Lines 1/ sump 31 g 8 (IRE-5100 & 2RE-5100)
L 9 10 c. Auxiliary Building to LW Pond Liquid Effluent Line 1 31A (XRE-5251A)
- 2. Radioactivity Monitors Providing Alara But Not Providing Automatic Termination of Release I
- a. Service Water System Effluent Lines 1/ train 32 8 (IRE-4269, IRE-4270, 2RE-4269 & 2RE-4270) um 3u.'2 3. Flow Rate Measurement Devices o
- a. Liquid Radwaste Effluent Line (XFT-5288) 1 33
i i
TABLE 3.3-7 (Continued) j ACTION STATEMENTS I 2
\
i ACTION 30- With the number of channels OPERABLE less than required by the l l Minimum Channels OPERABLE requirement, effluent releases via this j
[
pathway may continue provided that prior to initiating a release:
i a. At least two independent samples are analyzed in accordance with l Control 4.11.1.1.1; and I
' b. At least two technically qualified members of the facility staff independently verify the release rate cadculations and discharge
, line valving, i Otherwise, suspend release of radioactive effluents via this
- pathway.
ACTION 31- With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this a pathway may continue provided grab samples are analyzed for
! 8 principal ga p emitters at a lower limit of detection of no more
- than 5 x 10 microcurie /m1:
1
! a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE j EQUIVALENT I-131; or
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram 8 DOSE EQUIVALENT I-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)
l
} 10 ACTION 31A-With number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal emitters at a lower-limit of detection of no more than 5 x 10~7 gamma microcurie /m1 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue provided that:
l 11 a. With the component cooling water monitors (uRE-4509, uRE-4510, &
uRE-4g11)* OPERA 8LEandindicatinganactivityoflessthan 1X10~ microcurie /m1, a grab sample is collected and analyzed f radioactivityatalowerlimitofdetectionofnomorethan10~9r !
microcurie /a1 at least every 31 days; or
- b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and 8 analyzedforprincipalgammaemit}ersatalowerlimitof detection of no more than 5 x 10~ microcurie /m1. (Referto Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)
7 NOTE: Collection of grab samples is not required when there is no process flow at the monitor.
11 "u" designates monitor for the applicable unit, e.g., 1 or 2.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-5 REV. 11 11/94
TABLE 3.3-7 (Continued)
ACTION STATEMENTS (Continued) l ACTION 33- With the nuster of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place may be used to estimate flow.
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COMANCHE PEAK UNITS 1 AND 2 PART I 3/4 Sa 4/94 i 1
. . . . . . - - - - - - . - . _ - . _ - _ - . _ _ . . ._ . . _ - . - - =. . . - - .
c, TABLE 4.3-3 x
RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE00lREqlG1 k
A ANALOG DIGITAL M CHANNEL CHANNEL c- INSTRIBENT CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL 5 CHECK CHECK CAL IBRATION TEST TEST d 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release b a. Liquid Radweste Effluent Line (XRE-5253) O P
~ R(4) N.A. Q(1)
- b. Turbine Building (Floor Drains) Sumps 8
Effluent Lines (IRE-5100 & 2RE-5100) 0 M R(4) N.A. Q(2)
, 9 c. Auxiliary Building to LVW Pond Liquid g 0 M R(4) N.A.
Effluent Line (XRE-5251A) Q(2)
~
- 2. Radioactivity Monitors Providing Alarm But g Not Providing Automatic Termination of Release di a. Service Water System Effluent Lines 8 (IRE-4269, IRE-4270, 2RE-4269 & 2RE-4270) 0 M R(4) N.A. Q(3)
- 3. Flow Rate Measurement Devices,
- a. Liquid Radwaste Effluent Line (XFT-5288) 0(5) N.A. R Q N.A.
sf S ."
e
TABLE & 3-3 (Continued)
TABLE NOTATTONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if any of the following conditions exist:
l
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint: or
- b. Circuit failure (Channel Out of Service - Loss of Power. Loss of l
Counts. Loss of Sample Flow, or Check Source Failure).
l (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic flow diversion of this pathway (from the Low Volume Waste Treatment System l to the Co-Current Waste Treatment System) and Control Room alarm annunciation occur if any of the following conditions exist:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint; or
- b. Circuit failure (Channel Out of Service - Loss of Power. Loss of 11 Counts. Loss of Sample Flow
- or Check Source Failure).
For Radiation Monitors 1-RE-5100.and 2-RE-5100. " Loss of Sample Flow" is not applicable.
(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control 1 Room alarm annunciation occurs if any of the following conditions exist: l l a. Instrument indicates measured levels above the Alarm Setpoint; or l b. Circuit failure (Channel Out of Service - Loss of Power. Loss of Counts. Loss of Sample Flow, or Check Source Failure). '
l l
(4) The initial CHANNEL CALIBRATION shall be performed using one or more of the 8 reference standards certified by the National Institute of, Standards and l
Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These l standards shall permit calibrating the system over its intended range of l energy and measurement range. For subsequent CHANNEL CALIBRATION, sources 8 that have been related to the initial calibration, reference standards certified by NIST. or standards that have been obtained from suppliers that '
participate in measurement assurance activities with NIST shall be used.
l (5) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
l l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-7 REV. 11 t
l 11/94 l
1 INSTRUMENTATION '
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ;
CONTROLS l
3.3.3.5 In accordance with CPSES TS 6.8.3.e.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their Alare/ Trip Setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in aCCordance with the methodology and 8 parameters in Part II of the 00CM.
APPLICABILITY: As shown in Table 3.3-8.
ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-8. Restore the inoperable instrumentation to OPERA 8LE status 10 within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.
I c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREE NTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the,, CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.
M i
1 COMANCHE PEAK UNITS 1 AND 2- PART I 3/4-8 REV. 10 W
TABLE 3.3-8 RADI0 ACTIVE GASEOUS EFFt.UENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. WASTE GAS HOLDUP SYSTEM ,
m N a. Noble Gas Release Rate e Monitor - Providing Alare g . and Automatic Termination of Release vi [XRE-5570A & XRE-55708 a
(effluent release rate channel)] 1/ stack ** 34 E
o 2. PRIMARY PLANT VENTILATION m
- a. Noble Gas Release Rate Monitor
[XRE-5570A & XRE-55708 y (effluent release rate channel)] 1/ stack
- 36 E
-i b. Iodine Sampler
~
- 37 U
P c. Particulate Sampler 1/ stack .* 37
- d. Sampler Flow Rate Monitor SMPL Flos 1 (X-RFT-5570A-1, 1/ stack
- 35 4 X-RFT-55708-1) 4 i
.e
~
8
l TABLE 3.3-8 (Continued) i TABLE NOTATIONS
- At all times.
- During 8atch Radioactive Releases via this pathway.
ACTION 34- With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, the contents of the tank (s) may be released to the environment provided that prior i
to initiating the release:
$ a. The auxiliary building vent duct monitor (XRE-5701) is confirmed OPERABLE, or i b. At least two independent samples of the tank's contents
) are analyzed, and
! c. At least two technically qualified members of the l
facility staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this 3
pathway.
k ACTION 35- With the number of channels OPERA 8LE'less than required by the 4 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is j estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. !
ACTION 36- With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, offluent releases via j this pathway may continue provided that:
?
l (a) A Plant Vent Noble Gas Activity Monitor (XRE-5570A, l XRE-55708 (low range activity) or XRE-5567A, XRE-55678)
! is OPERA 8LE, and the plant vent flow rate is estimated
- at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or
(b) The Plant Vent Flow Monitor, PROC FLOW N'(X-FT-5570A-1, 4
. X-FT-55708-1), is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERA 8LE (XRE-5567A, i
XRE-55678) or grab samples are taken at least once per i 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for j radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or I (c) The plant vent flow rate is estimated at least once per 1
' 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for j radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j ACTION 37- With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the i affected pathway may continue provided samples are continuously
! collected with auxiliary sampling equipment as required in Table i 4.11-2.
d COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-10 1/93 y - - - - - ,- -,-
TABLE 4.3-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIRENENTS hf ,
ANALOG DIGITAL
]; CHANNEL CHANNEL gg CHANNEL SOURCE CNANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST A
3" 1. WASTE GAS HOLDUP SYSTEM h a. Noble Gas Release Rate Monitor -
25 Providing Alare and Automatic gj Termination of Release
_o [XRE-5570A, XRE-55708(effluent release yo rate channel)] P P R(3) N.A. 0(1) 5 n3 2. PRINARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor
[XRE-5570A, XRE-55708(effluent release 3 rate channel)) D # R(3) N.A. 0(2)
-, b. Iodine Sampler u, (WRGM sample skid) W(4) N.A. N.A. M.A. N.A.
A 10
- d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1. D N.A. R 0 N . .\ . 4 X-RFT-55708-1) 4 3
u
l TABLE 4.3-4 (Continued)
TABLE NOTATIONS l
3 # Prior to any release from the WASTE GAS HOLOUP SYSTEM or j containment PURGING or VENTING, not to exceed 31 days.
(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that
- automatic isolation of this pathway and control room alarm annunciation j occurs if any of the following condition exists
J j a. Instrument indicates measured levels above the Alarm / Trip j Setpoint, or i b. Circuit failure, (Channel Out of Service - Loss of Power, Loss i of Counts, Loss of Sample Flow, or Check Source Failure).
}
{ (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that j control room alarm annunciation occurs if any of the following conditions exists:
! a. Instrument indicates measured levels above the Alarm Setpoint.
l or
- l b. Circuit failure, (Channel Out of Service - Loss of Power, Loss i of Counts, Loss of Sample Flow, or Check Source Failure).
4 (3) The init1Al CHANNEL CALIBRATION shall be performed using one or more of 8 the refe~rence standards certified by the National Institute of
{ Standards and Technology (NIST) or using standards that have been
! obtained from suppliers that participate in measurement assurance j activities with NIST. These standards shall permit calibrating the i system over its intended range of energy and measurement range. For 8 ;
i subsequent CHANNEL CALIBRATION, sources that have been related to the i
- initial calibration, reference standards certified by NIST, or ,
i standards that have been obtained from suppliers that participate in I j measurement assurance activities with NIST shall be used.
i (4) The CHANNEL CHECK shall consist of visually verifying that the !
4 collection element (i.e., filter or cartridge, etc.) is in place for '
j sampling.
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0 REY. 8 i COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-12 1/93
- . . _ . . . - - - - - .. - .= - - - - - . . . - - _ - . . . ___ _._- .- -
INSTRUMENTATION H OROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table 8 3.3-9 shall be OPERA 8LE.
APPLICABILITY: At all times.
ACTION:
11 a. With less than the minimum number of meteorological monitoring instrumentation channels OPERA 8LE for more than 7 days, prepare and submit a Special Report to the Commission pursuant to CPSES Technical Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
SURVEILLANCE REOUIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE:
- a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by performance of a CHANNEL CHECK; and
- b. At least once per 184 days by performance of a CHANNEL CALIBRATION.
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COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-13 REV. 11 l
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TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUENTATION MINIMUM INSTRulDT LOCATION OPERABLE
- 1. WIND SPEED 1 of 3
- a. X-SY-4117 Nominal Elev. 60 m.
- b. X-SY-4118 Nominal Elev. 10 m.
- c. X-SY-4128* Nominal Elev. 10 m.
- 2. WINO DIRECTION 1 of 3
- a. X-ZY-4115 Nominal Elev. 60 m.
- b. X-ZY-4116 Nominal Elev. 10 m.
- c. X-ZY-4126* Nominal Elev. 10 m.
- 3. AIR TEMPERATURE - AT 1 of 2
- a. X-TY-4119 Nominal Elev. 60 m. and
.. Nominal Elev. 10 m.
- b. X-TY-4120 Nominal Elev. 60 m. and Nominal Elev. 10 m.
- Mounted on backup tower. ',
COMANCHE PEAK UNITS 1 ANO 2 PART I 3/4-14 01/93
INSTRUENTATION SEALED SOURCE CONTAMINATION CONTR1 5 3.7.15 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY: At all times.
ACTION 1
With a sealed source having removable contamination in excess of the above '
limits, immediately withdraw the sealed source from use and either:
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations.
SURVEILLANCE REOUIREMENTS 4.7.15.1 Test Requirements - Each sealed source shall be tested for
, leakage and/or contamination by: j
- a. The licensee, or
- b. Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
4.7.15.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously, subjected to core flux) shall be tested at the frequency described below.
- a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
1)Withahalf-lifegreaterthan30 days (excludingHydrogen3),
and
- 2) In any form other than gas.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-15 1/93
.. .. . . . - . . - _ = - . - _ _ . . . . -- .. ._
SURVEILLANCE REOUIREMENTS (Continued) l
- b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and
- c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.
4.7.15.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.
7.
9 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-16 1/93
I 3/4.11 RADICACTfVE EFFLUENTS l
3/4 11.1 LIOUID EFFLUFNTS v
l CONCENTRATION CONTR019 i
3.11.1.1 In accordance with CPSES TS 6.8.3.e.2 and 3. the concentration of 12 radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20. Appendix B. Table 2. Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 104 i microcurie /ml total activity.
APPLICABILITY: At all times.
ACTION-I l
- a. With the concentration of radioactive material released in liquid effluents 8 L
to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits.
l immediately restore the concentration to within the above limits,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to j the sampling and analysis program of Table 4.11-1.
l l 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance 8 l with the methodology and parameters in Part II of the 00CM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
! I I
1 i
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i l
- COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-17 REV. 12
! 12/95 n
TABLE 4.11-1 Radioactive Uquid Waste Sampling and Analysis Program UQUID RELEASE SAMPUNG MINIMlUM TYPE OF ACTIVITY LOWER UMIT OF TYPE FREQUENCY ANALYSIS ANALYSIS DETECTION (1)
FREQUENCY (gCl/mi)
- 1 A. Batch Waste Release (2) P P PrincipalGamma 5.0E 07 Tanks to the Circulating Each Batch 7
Each 8atch Emitters (3) ;
Water Discharge 1131 1.0E-06 e
- a. Weste Monrter l Tanks Dissolved & Entrained (3) 'O 1.0E-05 D. Laundry Holdup ****I **** I !
j & Monitor Tanks M H3 1.0E 05 !
l c. Waste Water Composite (4)
Holdup Tanks (8) Gross % 1.0E47 l7 1
i d. Plant Effluent '
Q St 89, Sr 90 5.0E 08 I l Tanks Composite (4) ' 7A i Fe-55 1.0E-06 -
- 18. Batch Waste Release (2) P P Principal Gamma Tanks to the LVW Pond 5.0E 07 l Each Batch Each Batch Emitters (3)
- a. Condensate Polisher Backwash Recovery Tanks (6.7)
- b. Waste Water Holdup Tanks (6,8)
I9 l
- 7 H-3 1.0E-05 i 2A. Continuous Release (S) Daily Grab Composite Principal Gamma 5.0E-07 to the Circulating Sample (9) over pond Emitters (3)
Water Discharge decharge
- a. Low Volume Wests I*I ' ' 1.0E 06 l l Dissolved & Entramed (3) 1.0E 05 l8 Gases (Gamme Emitters) i l ,
H3 1.0E 05 !
I Gross Alpha 1.0E 07 Q St-80. Sr-90 5.0E 08 Composite (4)
Fe55 1.0E 06 7
- 28. Continuous Releases (5) W W Principal Gamma 5.0E 07 to the LVW Pond Grab Sample l Emitters (3)
- a. Turbine Bldg. Sump .
I No. 2 Effluents (6,7) 1131 1.0E 06
- b. Turbine Bldg. Sump No. 4 Effluents (6,7)
- c. Aux g g 6g 1.0E 05
!g COMANCHE PEAK - UNIT 1 AND 2 PART I 3/4-18 Rev 9 09/93
1 l TABLE 4.11-1 (Continued)
TABLE NOTATIONS
- (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will
! yield a not count, above system background, that will be detected with
! 955 probability with only 55 probability of falsely concluding that a j blank observation represents a "real" signal.
! For a particular measurement system, which may include radiochemical j separation:
f 4.66 sh i LLD =
E V 2.22 x 100 Y exp (-AAt)
]
! Where:
l LLD = the "a priori" lower limit of detection (microcurie per l unit mass or volume),
- sb = the standard deviation of the background counting rate or
]
of the counting rate of a blank sample as appropriate (counts per minute),
- E
- the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
i 2.22 x 100 = the number of disintegrations per minute per j microcurie, j Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide(s-1),and ,
At = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and t should be used in the calculation.
It should be recognized that the LLD is defined as an a nriori (before i the fact) limit representing the capability of a measurement system and not as an a nesteriori (after the fact) limit for a particular i measurement.
(2) A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then 8 thoroughly mixed by a method described in Part II of the 00CM to assure representative sampling. 4 COMANCHE PEAK UNITS 1 ANO 2
~
PART I 3/4-19 b8 01/93
TABLE 4.11-1 (Continued)
TABLE NOTATIONS (3) The principal gamma emiters for which the LLD specification applies include the following radionuclides: Mn-54. Fe-59. Co-58. Co-60. Zn-65. 8 Mo-99. Cs-134. Cs-137. and Ce-141 for fission and corrosion products, and Kr 87. Kr-88. Xe-133. Xe-133m. 4e-135, and Xe-138 for dissolved or entrained gases. Ce-144 shall also be measured, but with an LLD of 5 x 10 6 This list does not mean that only these nuclides are to be considered. Other gama peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual 10 Radioactive Effluent Release Report pursuant to Control 6.9.1.4 in the format outlined in Regulatory Guide 1.21. Appendix B. Revision 1. June 1974.
(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quant 1ty of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.. from a volume of a system that has an input flow during the continuous release.
(6) These waste streams shall be sampled and analyzed, in accordance with this 7 table if radiocctive material is detected 'in the LVW Pond composite samples in concentrations that exceed 10% of the limits of 10 CFR 20.
Appendix B. Table 2. Column 2. This sampling shall continue until 2 8 consecutive samples from the waste stream show that the concentration of 7 radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20. Appendix B. Table 2. Column 2.
(7) All flow from these waste streams shall be diverted to the Waste Water 12 Holdup Tanks if activity is present in the waste stream in concentrations ,
that exceed 10 times the limits of 10 CFR 20. Appendix B. Table 2. Column
- 2. Sampling and analysis of the respective Tanks or sumps are not required 7 when flow is diverted to the Waste Water Heldup Tanks.
(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the 12 Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed 10 times the limits of 10 CFR 20.
Appendix B. Table 2. Column 2. Otherwise. WWHTs may be discharged to the 8 Low Volume Waste Pond. WWHT discharges to the Circulating Water Discharge 7 Tunnel shall be sampled and analyzed per Item 1A.c of this tabM. WWHT 10 discharges to the LVW Pond shall be sampled and analyzed per item 1B.0 of this table.
(9) Samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the release is 7 occurring. To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained contant for all samples taken for the composite sample.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-20 REV. 12 12/95
- - .- - _ . . - - - - .. ._.- - - . ___ _ - - = _ _ - .
RADIDACTIVE EFFLUENTS t DE I CONTROLS !
3.11.1.2 In accordance with CPSES TS 6.8.3.e.4 and 6.8.3.e.5 the dose or 8 l dose comitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrens to any organ, and
- b. During any calendar year to less than or equal to 3 mress to the
) whole body and to less than or equal to 10 mreas to any organ.
APPLICABILITY: At all times. l ACTION:
- a. With the calculated dose from the release of radioactive l materials in liquid effluents exceeding any of the above limits, prepare and submit to the Comission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cadse(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and tha proposed corrective actions to be taken to assure that !
subsequent releases will be in compliance with the above limits.
This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141 Safe Drinking Water Act.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REOUIREE NTS 1
4.11.1.2 Culaulative dose contributions from liquid effluents for the 8 current calender quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part !! of the ODCM at least once per 31 days.
4 REY. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-21 1/93
RADIQACTIVE EFFLUENTS LI0ljl0 RADWASTE IREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with CPSES TS 6.8.3.e.6, the Liquid Radwaste 8 Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mres to the whole body or 0.2 mrem to any organ in a 31-day period. i l
APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes'the following information:
- 1. Explanation of why liquid radwaste was being discharged
~~w ithout treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Sunnary description of action (s) taken to prevent a recurrence.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS 8 and UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the 00CM when Liquid Radwaste Treatment Systems are not being fully utilized.
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be 1 ;
considered OPERA 8LE by meeting Controls 3.11.1.1 and 3.11.1.2. I l
REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22 1/93
RADI0 ACTIVE EFFLUENTS LVW POND RESIN INVENTORY 7 CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins 7 transferred to the LVW Pond shall be limited by the following expression :
7 264 . I . <1.0 j J excluding tritium, dissolved or entrained noble gases, and radionuclides 7 l with less than an 8 day half life, l where: 7 Aj = pond inventory limit for single radionuclide "j" (Curies), 7 l Cj = 10 CFR 20, Appendix B Table 2. Column 2, concentration for 8 single radionuclide "j" (microCuries/ml),
V= volume of resins in the pond (gallons), and 7 264 = unit conversion factor (microCuries/ Curie per 7 milliliter / gallon).
APPLICABILITY:, At all times. 2 i l
l ACTION:
- a. With the. quintity of radioactive material contained in resins 8 in the LVW Pond exceeding the above limit, immediately suspend all additions of resins to the pond.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not 2 applicable.
SURVEILLANCE REOUIREMENTS 4.11.1.4 Prior to transferring any batch of used powdex resin to the pond, 8 the total inventory of radioactive materials in resins contained in the !
pond, including the batch to be transferred, shall be determined to be within the above limit. The inventory shall be determined based on analysis of a representative sample of the resin batch. Decay of radionuclides 12 previously discharged resins may be taken into account in determining inventory levels.
I l
l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22a 1/93
t RADI0 ACTIVE EFFLUENTS 1
LVW POND RESIN INVENTORY 7 SURVEILLANCE REQUIREMENTS (Continued)
Additionally, each batch of resins transferred to the pond shall be limited 8 by the expression:
8 1 0.1 l
l Where: Qj = Concentration of radioactive materials (microCuries/ml) 8 in wet, drained slurry (used powdex resin) for radionuclide "j", excluding tritium, dissolved or
- entrained noble gases, and radionuclides with less than l an 8-day half-life. The analysis shall include at least Ce-144, Cs-134. Cs-137, Co-58 and Co-60. 7 Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent quarterly l composite analysis, Cj = 10 CFR 20, Appendix 8. Table 2, Colu.mn 2, concentration 8 for single radionuclide "j" (microcuries/ milliliter).
l l
l l l
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l l l
l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22b Rev. 8 ERRATA (6/93) l
1 3/4.11 RADI0 ACTIVE EFFLUENTS 1
3/4.11.2 GASEQUS EFFLUENTS DOSE RATE t
3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7. the dose rate due 12 to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the 12 l total body and less than or equal to 3000 mrems/yr to the skin: and l
- b. For Iodine-131, for Iodine-133 for tritium, and for all radionuclides in l particulate form with half-lives greater than 8 days: Less than or equal l
1 to a dose rate of 1500 mrem /yr to any organ.
APPLICABILITY: 'At all times. !
ACTION
- a. With the dose rate (s) exceeding the above limits. immediately restore the release rate to within the above limits (s).
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 1
I 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed according to 8 the sampling and analysis program of Table 4.11-2.
! 4.11.2.1.2 The results of the radioactivity analyses shall be used in accordance 12 l with the methodology and parameters in Part II of the ODCM to assure that the l dose rates at or beyond the SITE BOUNDARY are maintained within the limits of Control 3.11.2.1.
l l
C0MANCHE PEAK UNITS 1 AND 2 PART I 3/4-23 REV. 12 12/95
i 8
$ TABLE 4.Il-2 Radioactive Caseous Weste Sampling and Analysis Program (*)
n
. NINIDEDI LOWER LIMIT OF c- SABWLING ANALYSIS TYPE OF DETECT 1001 (LLD)(1)
-4 GASEOUS RELEASE TYPE PREQUEBCT FREQUENCY ACTIVITY ANALYSIS onCi/al)
<n
- 1. Weste Cao Storage F F ~
Tank Each Tank Each Tank Principal Camma Emitters (2) lx10
- 2. Containment Purge F F
,4
'* or Vent Each Release (3) Each Release (3) Principal Camma Emitters (2) lx10
-6 M N-3 (oxide) lx10 u
- 3. Plant Vent M(3). (4). (5) Principal Camma Emitters (2) lx10~
- ~6
$ Crab Sample M(3) N-3 (oxide) lx10 Continuoue(6) U(7) 1-131 lx10
-12 s Radiciodine i
to Adeorber
~II continuoue(6) W(7) Principal Camme Emitters (2) lx10 Particulate Sample
~II Coatinuous(6) M Gross Alpha 1x10 Composite Far- '
ticulate Sample Continuoue(6) Q Sr-89. Sr-90 lul0' I Composite Par-ticulate Sample O
g Continuous (6)
Noble Ga s **
Beta or Gamma Noble Gas lx10~
lI Ed
- Table notations next page
- 1his sample is continuously analyzed by a radiation monitor l1
TABLE 4.11-2 (Continued)
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
- S b
LLD =
E . y . 2.22 x 10 6 . y . exp (.AAt)
Where:
LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume),
s b = the standard devi f the b ck ofthecountingrateoftio rate or ablanksample!roundcounting(counts s appropriate per minute),
EW the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide(sec-!),and ,
At= the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an g oriori l (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-25 01/93
4 TABLE 4.11-2 (Continued) 4 TABLE NOTATIONS (Continued 1 1
(2) The principal gamma emitters for which the LLO specification applies j
' include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, t
Zn-65, I-131, Cs-134 Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be
! considered. Other gamma peaks that are identifiable, together with those i
10 of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report, pursuant to Control 6.9.1.4, in the 4
format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June j 1974
! (3) Sampling and analysis shall also be performed following shutdown, i startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER
! within a 1-hour period. This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical
.' Specification 4.4.7 shows that the DOSE EQUIVALENT I-131 concentration in
- 8 the primary coolant has not increased more than a factor of 3, and (2) i noble gas monitoring shows that effluent activity has not increased more j than a factor of 3.
i (4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. .
! (5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is 4 in the spent fuel pool.
3 (6) The ratio of the sample flow rate to the sampled stream flow rate shall
! be known for the time period covered by each dose or dose rate I
calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and i
3.11.2.3.
j (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from the i sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 155 of RATED THERMAL POWER within a 1-hour period and analyses j shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a
! factor of 10. This requirement does not apply if: (1)analysisshows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has 1 8 not increased more than a factor of 3; and (2) noble gas monitoring shows
{ that effluent activity has not increased more than a factor of 3.
i i
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-26 REV. 10 4/94
RADIQACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.8, the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION
- a. With the calculated air dose from radioactive noble gases in 8 gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for eiceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter 8 and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Part II of the 00CM at least once per 31 days.
REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-27 1/93
BRIDACTIVE EFFLUENTS DOSE - IODINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM CONTROLS l
3.11.2.3 In accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.9, the dose to i a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all I radionuclides in particulate form with half-lives greater than 8 days in '
gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
I
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of Iodine-131. Iodine- 8
, 133, tritium, and radionuclides in particulate form with half-
! lives gra ter than 8 days in gaseous effluents exceeding any of
( the above limits, prepare and submit to the NRC within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter 8 and current calendar year for Iodine-131 Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the metholodogy and parameters in Part II of the 00CM at least once per 31 days.
l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-28 1/93
RADIQACTIVE EFFLUENTS
! GASEOUS RADWASTE TREATMENT SYSTEM 1
CONTROLS i
j i 3.11.2.4 In accordance with CPSES TS 6.8.3.e.6 the PRIMARY PLANT j
i VENTILATION SYSTEM and the WASTE GAS HOLOUP SYSTEM shall be OPERABLE and
' appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed:
j a. 0.2 mrad to air from gamma radiation, or f
- b. 0.4 mrad to air from beta radiation, or !
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
3 ACTION:
- a. With radioactive gaseous waste being discharged without 8 I treatment and in excess of the above limits, prepare and submit i
to the NRC within 30 days, pursuant to specification 6.9.2, a Special Report that includes the following information:
l 1. Identification of any inoperable equipment or subsystems, and
] the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to i OPERABLE status, and J
I 3. Summary description of action (s) taken to prevent a j recurrence.
l
- b. The provisions of Control 3.0.3 and 3.0.4 are not applicable.
i 5
SURVEILLANCE REOUIREMENTS l i
i i 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and 8 i beyond the SITE BOUNDARY shall be projected at least once per 31 days in j accordance with the methodology and parameters in Part II of the 00CM when j Gaseous Radwaste Treatment Systems are not being fully utilized.
4.11.2.4.2 The installed PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS l HOLDUP SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1 and
- 3.11.2.2 or 3.11.2.3.
REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-29 1/93
i 3/4.11 RADI0f4CTIVE EFFLUENTS I 3/4 11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with CPSES TS 6.8.3.e.10. the annual (calendar year) dose 12 or dose comitment to any MEMBER OF THE PUBLIC due to releases of radioactivity )
and to radiation from uranium fuel cycle sources shall be limited to less than or i equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION-l
- a. With the caleulated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a. 3.11.1.2b. 3.11.2.2a. 3.11.2.2b. 3.11.2.3a.. or 3.11.2.3b..
l calculations shall be made including direct radiation contributions from j the units and from outside storage tanks to determine whether the above ,
limits of Control 3.11.4 have been exceeded. If such is the case, prepare 8 !
and submit to the NRC within 30 days, pursuant to Specification 6.9.2, a l Special Report that defines the corrective action to be taken to reduce i subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits, i l
This Special Report. as defined in 10 CFR 20.2203(a)(4)and 20.2203(b). 8 l
! shall include an analysis that estimates the radiation exposure (dose) to a
- MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all i effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits. and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall l
include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
l l b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l
l 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall 8 l be determined in accordance with Controls 4.11.1.2. 4.11.2.2. and 4.11.2.3, and in accordance with the methodology and parameters in Part II of the ODCM.
l t
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-30 REV. 12 l 12/95
RADIQACTIVE EFFLUENTS (Continued) l 3/4.11.4 TOTAL DOSE i
SURVEILLANCE REQUIREMENTS , 4.11.4.2 Cumulative dose contributions from direct radiation from the 8 l units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Part II of the 00CM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.
l l
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h COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-31 ff93
l 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/4.12 1 MONITORfNG PROGRAM CONTROLS 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as 12 specified in Table 3.12-1.
l APPLICABILITY: At all times.
ACTION-l 1
- a. With the Radiological Environmental Monitoring Program not being conducted 12 l as specified in Table 3.12-1. prepare and submit to the NRC. in the Annual l Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reason (s) for not conducting the program as required and l
the plan for preventing a recurrence.
! b. With the level of radioactivity as the result of plant effluents in an 8 l
environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter.
prepare and submit to the NRC within 30 days, pursuant to Specification l .6.9.2. a Special Report that identifies the cause(s) for exceeding the i
l limit (s) and defines the corrective action to be taken to reduce radioactive effluents 50 that the potential' annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2. 3.11.2.2.
or 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are ,
detected in the sampling nedium, this report shall be submitted if: l l concentration (1) concentration (2) . >_1. 0 reporting level (1)
- reporting level (2)
- l When radionuclides other than those in Table 3.12-2 are detected and are
! the result of plant effluents, this report shall be submitted if the l potential annual dose
- to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 3.11.1.2.
i 3.11.2.2. or 3.11.2.3. This report is not required if the measured level i
of radioactivity was not the result of plant effluents; .however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
l A
COMANCHE PEAX UNITS 1 AND 2 PART I 3/4-32 REV. 12 12/95
l 3/4.12 RADIOLOGTCAL ENVIRONMENTAL MONITORING 3/4 12.1 MONITORfNG PROGRAM l
l CONTROLS (Continued)
- c. With milk or fresh leafy vegetable samples unavailable from one or more of 12 the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program. The specific locations from which samples were unavailable may then be deleted from the monitoring program. New sampling locations shall be listed in the results of the annual Land Use Census.
l l d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
l l SURVEILLANCE REQUIREMENTS I
4.12.1 The radiological environmental monitoring samples shall be collected 12
- pursuant to Table 3.12-1 and shall be analyzed pursuant to.the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. The specific sample locations for the Radiological Environmental Mecitoring Program shall be listed and maintained current in the results of the annual Land Use Census.
l l
l l
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COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-33 REV. 12 12/95
TABLE 3.12-1 Radiological Environmental Monitoring Program E
j5 NUMBER OF ps REPRESENTATIVE Ei EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY y AN0/0R SAMPLE SAMPLE LOCATIONS (l) COLLECTION FREQUENCY OF ANALYSIS 52 ',
- 1. Direct Radiation (2) Forty routine monitoring stations Quarterly. Gamma dose quarterly either with two or more dosimeters Ei or with one instrument for measur-20 ing and recording dose rate continuously, placed as follows:
[]
3E An inner ring of stations, one in C'
each meteorological sector in the general area of the SITE BOUNDARY:
An outer ring of stations, one in m each meteorological sector in 3$ the 6- to 8-km range from the
[] site: and 10 The balance of the stations to be f' placed in special interest areas if such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.
- 2. Airborne Radiciodine and Samples from five locations: Continuous sampler Radiciodine Cannister:
Particulates operation with sample I-131 analysis weekly f! collection weekly, jg Three samples from close to or more frequently the three SITE BOUNDARY if required by dust Particulate Samoler:
locations in different loading. Gross beta radio-sectors, of the highest activity analysis calculated annual average following filter ground-level D/Q: change: (4) and gamma isotopic analysis (5) of composite (by location quarterly.
- - . - - . . . . . . . . . . . - . _ _ _ - . . . . _ - . - _ - _ . _ - . . - . - . = . . . _ - - - . . . _ - . -_.
TA8LE 3.12-1 (Continued) n Radiological Environmental Monitoring Program S
g NUMBER OF Q
m REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY A AND/0R SAMPLE SAMPLE LOCATIONS (l) ; COLLECTION FREQUENCY OF ANALYSIS ,
R '
, One sample from the c- vicinity of a community 5 having the highest calcu-d lated annual average ground-a level D/0: and
$ One sample from a control m location, as for example 15 to 30 km distant and in the least prevalent wind direction. (3)
$ 3. Waterborne i e .
- a. Surface Squaw Creek Reservoir (6) Monthly composite of Gamma isotopic anal- t w weekly grab samples, ysis(5) monthly.
1 Composite for tritium h analysis quarterly.
Lake Granbury Monthly composite of Gamma isotopic anal- i weekly grab samples ysis(5) monthly.
when Lake Granbury Composite for tritium is receiving letdown analysis quarterly.
from SCR. Otherwise, monthly grab sample.(7) o O Control-Brazos River Monthly Gamma isotopic anal-I upstream of Lake Granbury ysis(5) monthly.
Composite for tritium analysis quarterly.
- b. Ground Samples from two sources Quarterly Gamma isotopic (5) if likely to be affected(8) . and tritium analysis ,
quarterly.
. . - . -_~ -.- - __ - . - . . . - - . . - . . . . . . .-. - . . - .- - .
i TA8LE 3.12-1 (Continued) c3 Radiological Environmental Monitoring Program S
3" NUMBER OF E2 REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY A AND/OR SAMPLE SAMPLE LOCATIONS (l) .'. COLLECTION FREQUENCY OF ANALYSIS 3E
. 3. Waterborne (Ccntinued)
!! c. Drinking One sample from Squaw Creek Composite of weekly I-131 analysis of Cl Reservoir. grab samples over each composite sample
_. 2-week period when when the dose calcu-2n I-131 analysis is lated for the con-
@5 performed; monthly sumption of the water n> composite of weekly is greater than 1 aren grab samples other- per year (9) . Gross i wise, beta and gamma iso-topic analyses (5) 33 monthly. Composite 33 for tritium analysis
-- quarterly. t us <
3 d. Sediment One sample from downstream area Semiannually. Gamma isotopic analy- !
h> from with existing or potential -
sis (5) semiannually.
Shoreline recreational value.
- 4. Ingestion '
- a. Milk Samples from milking animals in Semimonthly when Gamma isotopic (5) three locations within 5 km animals are on and I-131 analysis distance having the highest dose pasture; monthly semimonthly when potential. If there are none, at other times. animals are on pas-sample from milking animals in ture; monthly at each of three areas between 5 other times. i to 8 km distant where doses are calculated to be greater than 1 arem per yr.(9) One sample o from milking animals at a control
- ^ location, 15 to 30 km distant and ll in the least direction.(3) prevalent wind
TABLE 3.12-1 (Continued) c3 Radiological Environmental Monitoring Program S
]; NUMBER OF Sj REPRESENTATIVE
"' EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY
?? AND/OR SAMPLE SAMPLE LOCATIONS (l) /, COLLECTION FREQUENCY OF ANALYSIS 3E
, 4. Ingestion (Continued)
C 55 b. Fish and One sample of at least two Sample semiannually. Gamma isoto Dj Invertebrates recreationally important species analysis (5)pic on
_. In vicinity of plant discharge area. edible portions.
!! One sample of same species in areas n3 not influenced by plant discharge.
- c. Food Products
- One sample of each principal class At time of harvest (10) Gamma isotopic of food products from any area analysis (5) on A that is irrigated by water in which edible portion.
?$ liquid plant wastes have been
, - discharged.
$ A sample of broad leaf vegetation Monthly, when Gamma isotopic ( '
la grown nearest each of two dif- available. and I-131 analyses.
ferent offsite locations of highest predicted annual average ground level D/0 if milk sampling is not performed at all required locations.
(5)
One sample of each of the similar Monthly, when Gamma isotopic broad leaf vegetation grown 15 to available. and I-131 analyses.
30 km distant in the least pre-l !! valent wind direction (3) if milk
- sampling is not performed at all required locations.
l l
l OReports from 3 additional airborne radioiodine sample locations may be supplemented for broad leaf l vegetation samples.
TABLE 3.12-1 (Continued)
TARI F NOTATIONS (1) For each sample location required by Table 3.12-1 specific parameters of 12 distance and direction sector from the centerline of cne reactor and additional description where pertinent, are provided in information maintained current in the results of the annual Land Use Census.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions.
seasonal unavailability, and malfunction of automatic sampling equipment.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable 8 specific alternative media and locations may be chosen for the particular pathway in question and approoriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. New sampling locations 12 shall be lised in the results of the annual Land Use Census.
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of. or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor: two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.
(3) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid ;
background data may be substituted.
(4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall b6 performed on the individual samples. ,
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-38 REV. 12 12/95
i i
TABLE 3.12-1 (Continued)
TABLE NOTATIONS (Continued) 4 i
(5) Gamma isotopic analysis means the identification and quantification of gamma-emittig radionuclides that may be attributable to the effluents i
from the facility.
i j (6) The Reservoir shall be sampled in an area at or beyond but near the
- mixing zone. Also, the Reservoir shall be sampled at a distance beyond significant influence of the discharge.
t i (7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge.
j (8) Groundwater samples shall be taken when this source is tapped for 5 drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
(9) The dose shall be calculated for the maximum organ and age group, using 8
the methodology and parameters in Part II of the ODCM.
l ..-
1 (10) If harvest occurs more than once a year, sampling shall be performed l
during each discrete harvest. If harvest occurs continuously.
sampling shall be monthly. Attention shall be paid to including
, samples of tuberous and root food products.
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t TABLE 4.12-1 (Continued) TABLE NOTATIONS l (1) The list does not mean that only these nuclides are to be considered. ' Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. , (2) Required detection capabilities for thermoluminescent dosimeters used l for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. (3) The LLD is defined, for purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 55 probability of falsely concluding that a l blank observation represents a "real" signal. 4.66sb LLD = E V Y exp (-AAt) 2.22 Where: LLD = thi'"a priori" lower limit of detection (picocurie per unit mass or volume), sh= the standard devdation of the backcround counting rate or of the counting rate of a b1ank sample as appPopriate (counts per minute), E = the counting efficiency (counts per disintegration), V=thesamplesize(unitsofmassorvolume), 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable. A= the radioactive decay constant for the particular radionuclide (sec-1),and At = the elapsed time between the midpoint of sample collection and the timeofcounting(s). Typical values of E, V, Y, and At should be used in the calculation. l 4 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-42 , 1/93
l TABLE 4.12-1 (Continued) , TABLE NOTATIONS (Continued) l l I (3) Continued It should be recognized that the LLD is defined as an a criori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular i measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally , 4 background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. 1 l 4 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-43 1/93
3/4.12 RADIOLOGICAL ENVfRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A Land Use Census shall be conducted and shall identify within a distance 12 of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal. the nearest residence, and the nearest garden
- of greater than 50m2 (500 ft2 ) producing broad leaf vegetation.
APPLICABILITY: At all times. ACTION :
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3. pursuant to Control 6.9.1.4. identify the new location (s) in the next Annual Radioactive Effluent Release Report. 10
- b. With a Land Use Census identifying a location (s) that yields a calculated 12 :
dose or dose commitment (via the same exposure pathway) 20% greater than at l a location from which samples are currently being obtained in accordance 1 with Control 3.12.1, add the new location (s) within 30 days, to the Radiological Environmental Monitoring Program. The sampling locations having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. New sampling 12 locations shall be listed in the results of the annual Land Use Census.
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey. or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/0s in lieu of the garden ,
census. Specifications for broad leaf vegetation sampling in Table 3.12-1. i Item 4.c. shall be followed, including analysis of control samples. COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-44 REV. 12 12/95
3/4.12 RADIOLOGICAL ENVIPONMENTAL MONITORfNG 3/4 12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS e 3.12.3 Analyses shall be performed on all radioactive materials, supplied as 12 part of an Interlaboratory Comparison Program. that correspond to samples
- required by Table 3.12-1.
APPLICABILITY: At all times. ACTION-
- a. With analyses not being performed as required above, report the corrective 12 actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental
- Operating Report pursuant to Control 6.9.1.3.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS i l 4.12.3 The Interlaboratory Comparison Program shall be described in Part II of 8 the 00CM. A summary of the results obtained as part of the above required
- Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.
i l a i ~ h COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-45 REV. 12 12/95
BASES l l i i CDMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-0 01/93
INSfRUENTATION BASES i a 3/4.3.3.4 RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION l The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid , , effluents during actual or potential releases of liquid effluents. The 8 ' Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II of the 00CM
,t to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is ;
consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR 50. i 3/4.3.3.5 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ! The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in 1 gaseous effluents during actual or potential releases of gaseous effluents. ' The Alarm / Trip Setpoints for these instruments shall be calculated and 8 adjusted in accordance with the methodology and parameters in Part II of the 00CM to ensure that the alarm / trip will occur prior to exceeding the dose rate limits of Control 3.11.2.1. The OPERASILITY and use of this instrumentation is consistent with the requirements of General Design . Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.6 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient : eteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of the second proposed Revision 1 to Regulatory Guide 1.23, "Onsite Meteorological Programs," April 1986. REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-1 01/93
- _ = . . . .- .
~ INSTRUMENTATION 4 BASES i 3/4.7.15 SEALED tmnCE CONTAMINATION 4 The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10CFR70.39(c) limits for plutonium. This limitation will ensure that leakage from Byproduct. Source, and Special Nuclear Material sources will not exceed allowable I intake values. Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage 4 to a source in that group. Those sources which are frequently handled are t required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from 1 the shielded mechanism. l 4 .r I i 4 4 i e 1 l i ! CDMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-2 01/93 1
Eli RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4 11.1.1 CONCENTRATION CONTROLS This control is provided to ensure that the concentration of radioactive 12 materials released in liquid waste effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in CONTROLLED AREAS and UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix 1. 10 CFR Part 50. to a MEMBER OF THE PUBLIC and (2) restrictions authorized by 10 CFR 20.1301(e). The concentration limit for the dissolved or entrained noble gases is based upon the assumption that XE-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This control does not affoct the requirement to comply with the annual limitation of 10 CFR 20.1301 (a). This control applies to the release of radioactive materials in liquid effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in Currie. L.A., " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A. III.A and IV.A of 10CFR50, Appendix I. The Control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required 8 operating flexibility and 3t the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculation methodology and parameters in Part II of the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of the ODCM for calculating 8 the doses due to the actual release rates of COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-3 REV. 12 12/95
l 3/4 11 RADf0 ACTIVE EFFLUENTS BASFS (Continued) l 3/4 11 1.2 00SE (Continued) l radioactive materials in liquid effluents are consistent with the methodology , provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from
- Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50. Appendix I." Revision 1. October 1977 and Regulatory Guide 1.113.
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor i Releases for the Purpose of Implementing Appendix I." April 1977.
This control applies to the release of radioactive materials in liquid 8 effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2. 3/4.11.1 3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate I portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a. General Design Criterion 60 of Appendix A'to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste l Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I.10 CFR Part 50 for liquid effluents. This control applies to the release of radioactive materials in liquid 8 effluents from each unit at the site. The liquid effluents from the shared ' radwaste treatment system are proportioned equally between Unit 1 and Unit 2. 3/4.11.1 4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the 8 consequences of an uncontrolled release of the pond resin inventory. The expression in Control 3.11.1.4 assumes the pond inventory is uniformly mixed, and that the pond is located in a CONTROLLED AREA as defined in 10 CFR Part 20. and that the concentration limit in Note 4 to Appendix B of 10 CFR Part 20 applies. This expression limits the total quantity of radioactive materials in resins discharged to the LVW Pond to a value such that the average concentration in the resins. calculated over the total volume of resins in the pond, will not exceed I the Effluent Concentration Limits specified in 10 CFR 20. Appendix B. Table 2. ; ! Column 2. Because Control 3.11.1.1 limits the concentration of liquid effluents 12 ;
- from other pathways to the LVW Pond to 10 times the 10 CFR 20 Effluent '
Concentration values. also limiting the average concentration in resins to the Effluent Concentration values will assure that the average concentration in the pond from all sources. calculated over the total volume of the pond (liquid and l resins), will not exceed the limits of Contrcl 3.11.1.1. COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-4 REV. 12 12/95
i RADI0 ACTIVE EFFLUENTS BASES (Continued) i 3/4.11.1.4 LVW POND RESIN INVENTORY (Continued) 7 The batch limits for resins transferred to the LVW Pond assure that 8 radioactive material in the slurry transferred to the Pond are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of slurry will be 8 transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than 10% of the limits established in 10 CFR 20 Appendix B. l The batch limit is arbitrarily established at 10% of the 10 CFR 20, 8 l Appendix B limits to minimize input of radioactive materials to the LVW I Pond consistent with detection limits for the resin analysis. The batch limit also provides assurance that the radioactive material released is within the inventory limitation of Control 3.11.1.4. l I l l l l COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-5 Rev. 8 ERRATA (6/93)
3/4 11 RADI0 ACTIVE EFFLUENTS BASES (Continued) 3/4 11.2 GASEOUS EFFLUENTS 3/4 11.2.1 Dov RATE This control. in conjunction with Controls 3.11.2.2 and 3.11.2.3. is 12 provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of l 10CFR20 for MEMBERS OF THE PUBLIC. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the l skin. These release rate limits also restrict, at all times, the corresponding I thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year. Because these dose rate limits are applied on 12 an instantaneous basis and because of the overriding 10 CFR 50. Appendix I. l cumulative dose limitations established in Controls 3.11.2.2 and 3.11.2.3. these l limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC. either within or outside the SITE BOUNDARY. to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR 20.1301(a). For MEMBERS OF T.HE PUBLIC who may at times be 8 l in CONTROLLED AREAS within the SITE BOUNDARY. the occupancy factors for those ! MEMBERS OF THE PUBLIC will usually be sufficiently low to compensate for any l increase in the atmospheric diffusion factor above that for the SITE B0UNDARY. The methodology for calculating doses for such MEMBERS OF THE PUBLIC is provided in PART II of the ODCM. This control applies to the release of radioactive materials in gaseous effluents from all units at the site. The required detection capabilities for radioactive materials in gaseous 12 waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLDs and other detection limits can be found in Currie. L.A.. " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR-4007 (September 1984). and in the HASL Procedures Manual. HASL-300. ! COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-6 REV. 12 12/95
3/4.11 RADI0 ACTIVE EFFLUENTS BASES (Continued) l l 3/4 11.2.2 00SE - NOBLE GASES { l This control is provided to implement the requirements of Sections II.B. III. A and IV. A of 10CFR50. Appendix I. The control implements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required 8 operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low l as is reasonably achievable." The Surveillance Requirements implement the { requirements in Section III.A of Appendix I that conformance with the guides of I Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the ODCM for calculating the 1 doses due to the actual release rates of the radioactive noble gases in gaseous j effluents are consistent with the methodology provided in Regulatory Guide 1.109.
" Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50. Appendix I." Revision 1.
October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors." Revision 1. July 1977. The ODCM equations provided 12 for determining the air doses at or b(y,nd the SITE BOUNDARY are based upon the historical average atmospheric conditiom l This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the shared 8 radwaste treatment system are proportioned equally between Unit 1 and Unit 2. l l l COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-7 REV. 12 j 12/95
3/4.11 PADICACTfVE EFCLUENTS l BASES (Continued) l 3/4.11.2 3 DOSF - 10 DINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C. III.A. and IV.A of 10CFR50. Appendix 1. The Controls are the guides set forth in Section II.C of Appendix I, The ACTION statements provide the required operating 8 flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous , (ffluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is l reasonably achievable." The 00CM calculational methods specified in the l Surveillance Requirements implement the requirements in Section III.A of Appendix ! I that conformance with the guides of Appendix I be shown by calculational procedures based on"models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially ! underestimated. The calculational methodology and parameters specified in Part II of the 00CM for calculating the doses due to the actual release rates of the i subject materials are consistent with the methodology provided in Regulatory l Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50. Appendix I." i Revision 1. October 1977 and Regulatory Guide 1.111. " Methods for Estimating l Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors." Revision 1. July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specification for Iodine-131. 12 l Iodine-133, tritium, and radionuclides in particulate form with half-lives l greater than 8 days is dependent upon the existing radionuclide pathways to man ! in the areas at or beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne rad 1onuclides. (2) deposition of radionuclides onto green leafy vegetation with , I subsequent consumption by man. (3) deposition onto grassy areas where milk i l animals and meat-producing animals graze with consumption of the milk and meat by : man, and (4) deposition on the ground with subsequent exposure of man. ' This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the shared 8 l radwaste treatment system are f,roportioned equally between Unit 1 and Unit 2. l l I l l COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-8 REV. 12 l 12/95
RADIQACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEQUS RADW/,STE TREATMENT SYSTEM ! l The OPERABILITY of tne WASTE GAS HOLDUP SYSTEM and the PRIMARY PLANT l SYSTEM ensures that the systems will be available for use whenever gaseous ' effluents require treatment prior to release to the environment. The l requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive l materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, i General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design ! objectives given ir Section II.D of Appendix I to 10 CFR Part 50. The specified limits gu 'rning the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. This control applies to the release of radioactive materials in gaseous ! effluents from each unit at the site. The gaseous 7'fluents from the 8 l shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2. i REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-9 01/93
3/4.11 RADI0 ACTIVE EFFLUENTS BASES (Condnued) l 3/4 11.4 TOTAL DOSE i This control is provided to meet the dose limitations of 40 CFR Part 190 12 l that have been incorporated into 10 CFR Part 20.1301(d). The control requires l the preparation and submittal of a Special Report whenever the calculated doses i due to releases of radioactivity and to radiation from uranium fuel cycle sources l exceed 25 mrems to the total body or any organ, except the thyroid which shall l be limited to less than or equal to 75 mrems. For sites containing up to four reactors it ir, highly unlikely that the resultant dose to a MEMBER OF THE PUBLiC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I. and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small. The ! Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report. it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements 8 l of 40 CFR Part 190. the Special Report with a request for a variance (provided i the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions' of 40 CFR 190.11 and 10 CFR 20.2203(a)(4) and 20.2203(b). is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190. and does not apply in any. way to the other requirements for dose limitation of 10 CFR Part 20. as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF l THE PUBLIC during any period in which he/she is engaged in carrying out any l operation that is part of the nuclear fuel cycle. Demonstration of compliance 12 l with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to ! 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301. l ! l l l l COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-10 REV. 12 12/95
3/4.12 RADf0 LOGICAL ENVfRONMENTAL MONITORING BASES 3/4 12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of comercial operation. Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in Currie. L. A., " Lower Limit of Detection: Definition and Elaboration of a l Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at or 12 beyond the SITE BOUNDARY are identified and that modifications to the 1 Radiological Environmental Monitoring Program are made if required by the results I of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. l This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be ; identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the i following assumptions were made: (1) 20% of the garden was used for growing ' broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m . i COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-11 REV. 12 12/95
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. l
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l 1 1 i l l i i i COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-12 01/93
l l l I i l l l l 1 l l l l l l l ! SECTION 5.0 DESIGN FEATURES ! l l l l i l COMANCHE PEAK - UNITS 1 AND 2 PART I 5-0 01/93 l I
50 DESfGN FEATURES MAP DEFINING CONTROLLFD AREAS. UNRESTRICTED AREAS AND SITE BOUNDARY 8 l FOR RADICACTIVE GASEQUS AND LIOUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which allows identification of structures and release points as well as definition of CONTROLLED AREAS. UNRESTRICTED AREAS and the SITE B0UNDARY are shown in Figure j 5.1-3. The UNRESTRICTED AREA. as shown in Figure 5.1-3, is that area beyond the SITE BOUNDARY. Access to this area is not limited or controlled by the licensee. This is consistent with the definition of UNRESTRICTED AREA given in 10 CFR 20.1003. The SITE B0UNDARY coincides with the Exclusion (fenced) Area Boundary, as defined in 10 CFR 100.3(a). For calculations performed pursuant to 10 CFR 12 50.36a. the concept of UNRESTRICTED AREAS. established at or beyond the SITE BOUNDARY. is utilized in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable. The CONTROLLED AREA as shown in Figure 5.1-3. is that area that is inside 8 the SITE BOUNDARY but is outside of any plant areas defined by the licensee as restricted areas, per the definition of restricted area in 10 CFR 20.1003. Access to the CONTROLLED AREA is limited or controlled by the licensee. This is consistent with the definition of CONTROLLED AREA given in 10 CFR 20.1003. i 4 i O COMANCHE PEAK UNITS 1 AND 2 PART I 5-1 REV. 12 12/95
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l SECTION 6.0 ADMINISTRATIVE CONTROLS COMANCHE PEAK - UNITS 1 AND 2 PART I 6-0 01/93
ADMIN 1STRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.3 A Routine Annual Radiological Environmental Operating Report covering 8 l the operation of the units during the previous calendar year shall be submitted i prior to May 1 of each year.
The Annual Radiological Environmental Operating Report shall include summaries. interpretations. and an analysis of trends of the results of the radiological environmental surveillance activities for the report period. including a comparison with preoperational studies and with operational controls, as appropriate and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. l The report shall also include the results of the annual Land Use Census required 12 by Control 3.12.2. l ! The Annual Radiological Environmental Operating Report shall include the 12 l l results of analysis of all radiological environmental samples and of all i , environmental radiation measurements taken during the period pursuant to the ! I locations listed and maintained current in the results of the annual Land Use ( Census, as well as sumarized and tabulated results of these analyses and j measurements in the format of the table in the Radiological Assessment Branch l Technical Position. Revision 1. November 1979. In the event that some individual ! l results are not available for inclusion with the report. the report shall be ! submitted noting and explaining the reasons for the missing results. The missing i data shall be submitted as soon as possible in a supplementary report. The Annual Radiological Environmental Operating Report shall also include 12 ; the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor: the results of participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3: reasons for not conducting the Radiological Environmental Monitoring Program us required by Control 3.12.1. and discussion of , all deviations from the sampling schedule of Table 3.12-1: discussion of l environmental sample measurements that exceed the reporting levels of Table 3.12-l 1: and discussion of all analyses in which the LLD required by, Table 4.12-1 was not achievable.
- A single submittal may be made for both units. 8
** One map shall cover stations near the SITE BOUNDARY: a second shall include l
( the more distant stations. Maps are included in the results of the annual 12 Land Use Census. COMANCHE PEAK UNITS 1 AND 2 PART I 6-1 REV. 12 12/95
ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 10 6.9.1.4 A routine Annual Radioactive Effluent Release Report covering the 12 operation of the units during the previous year of operation shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date of initial criticality.
The Annual Radioactive Effluent Release Report shall include a sumary of 10 the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. " Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants." Revision 1. June 1974. with data sumarized on a quarterly basis following the format of Appendix B thereof. For solid wastes. the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g.. LSA. Type A. Type B. Large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement. urea formaldehyde). The Annual Radioactive Effluent Release Report shall include an annual 10 sumary of hourly meteorological data collected over the previous year. This annual sumary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured). or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseot.s effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE B0UNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments. i.e.. specific activity, exposure time, and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in 8 accordance with the methodology and parameters in Part TI of the OFFSITE DOSE CALCULATION MANUAL (00CM).
- A singic submittal may be made for both units. The submittal should 12 contine those sections that are common to both units at the station.
- In lieu of submission with the Annual Radioactive Effluent Release Report, 10 the licensee has the option of retaining this sumary of required meteorological data on site in a file that shall be provided to the NRC upon request.
COMANCHE PEAK UNITS 1 AND 2 PART I 6-2 REV. 12 12/95
ADMINISTRATfVE CCHiROLS 10 ANNUAL RADI0 ACTIVE EFr*LUENT RELEASE REPORT,(Continued) 10 The Annual Radioactive Effluent Release Report shall also include an i assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC l from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance witn 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 8, October 1977. 10 The Annual Radioactive Effluent Release Report shall include a list and 8 description of unplanned releases, from the site to CONTROLLED AREAS and UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period. 10 I The Annual Radioactive Effluent Release Report shall include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2. 10 The Annual Radioactive Effluent Release Report shall also include the 1 fc11owing: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Controls 3.3.3.4 or 3.3.3.5, respectively; and a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Technical Specification limits. 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) Changes to the 00CM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.o. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations ju'stifying the change (s) and
- 2) A determination that the change will maintain the level of 8 radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190. 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
1 b. Shall become effective after review and acceptance by the 50RC and the 9 approval of the Vice President of Nuclear Operations. COMANCHE PEAK UNITS 1 AND 2 PART I 6-3 REV. 10 4/94
ADMf NISTRATIVE CONTROLS ; 1 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) (Continued)
- c. Shall be submitted to the Commission in the form of a complete, !
legible copy of the entire 00CM as a part of or concurrent with the ! 10 Annual Radioactive Effluent Release Report for the period of the I report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. l l l l f COMANCHE PEAK UNITS 1 AND 2 PART I 6-4 REV. 10 4/94
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SECTION 1.0 LIQUZD EFFLUENTS The Comanche Peak Steam Electric Station (CPSES) is a 2-unit nuclear generating 8 { facility. Each unit is a 1150 Ne. 4-loop. Westinghouse PWR. The units share a j common primary liquid radwaste processing system. CPSES is located on Squaw { Creek Reservoir (SCR). which serves as the point of supply and discharge for the 7A plant circulating water. Radioactive liquid effluent releases from the primary radwaste processing system are batch type releases, from the Plant Effluent Tanks (PET). Laundry Holdup & Monitor Tanks (LHMT) and Waste Monitor Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially 7 1 radioactive liquid effluent releases from secondary systems include a continuous release from the Turbine Building Sumps (TB Sump). the Unit 1 and Unit 2 9 Component Cooling Water Drain Tanks (CCWDT). Auxiliary Building Sumps 3 and 11. and the Unit 1 and Unit 2 Diesel Generator Sumps 1, 2, 3 and 4. and batch 8 releases from the Condensate Polisher Backwash Recovery Tanks (CPBWRT). These j secondary pathways from each unit are normally discharged to the comon Low ! Volume Waste (LVW) Pond for chemical treatment. The LVW Pond normally discharges to SCR via the circulating Water Discharge Tunnel. Alternatively, secondary waste streams may be routed to the common Waste Water Holdup Tanks (WWHT). The l WWHTs may be released on a batch basis to the LVW Pond or to SCR via the 7 Circulating Water Discharge Tunnel, depending on th'e levels of radioactivity present. Table 4.11-1 of Part I of this document requires that secondary waste 12 I streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20. Appendix B. Table j
- 2. Column 2. Also, releases from the Station Service Water (SSW) System are 8 monitored for radioactivity, although no significant releases of radioactivity .
are expected from this pathway. Sampling and analysis requirements for all ; release sources are given in Part I. Table 4.11-1. All batch release sources are ! i isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior to sampling, to assure representative sampling. The recirculation or mixing times necessary to assure representative sampling shall be specified in station procedures. i 1 i
. I COMANCHE PEAK - UNITS 1 AND 2 PART II 1-1 Rev. 12 12/95 ~
f A sumary of all liquid effluent release sources, volumes, flow rates, and 7 associated radiation monitors is shown in Table 1.1. A flow diagram of all liquid effluent discharge pathways is shown in Figure 1.1. The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics). Since the DRMS monitors provide a digital output. l they may be calibrated to read out in the appropriate engineering units (i.e.. uCi/ml). The conversion factor for detector output from counts per minute to uC1/ml is determined in the calibration process and input into the database for the monitor microprocessor. 1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 3/4.11.1.1 COMPLIANCE 8 To demonstrate compliance with 10 CFR 20.1301. ODCM Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to CONTROLLEDL AREAS and UNRESTRICTED AREAS be limited to 10 times the concentrations specified in 10 CFR 20. Appendix 8. 12 Tabl'e 2. Column 2. for radionuclides other than dissolved or entrained 7 noble gases, and to 2E-4 uCi/ml for dissolved or entrained noble gases. 10 CFR 20 compliance is checked for all discharges to SCR via the Circulating Water Discharge Tunnel listed in Table 1.1. Because the LVW 8 Pond is located in a CONTROLLED AREA. discharges to the LVW Pond are also checked for 10 CFR 20 compliance. If radioactive materials are present in the LVW Pond discharge in concentrations that exceed 10% of the limits I of 10 CFR 20. Appendix B. Table 2. Column 2. then all inputs to the LVW 8 Pond are sampled and checked for compliance with 10 CFR 20. The following 7 l methodology is used to determine compliance with these limits. i 1 4 ( l l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-2 Rev. 12 l 12/95
1.1.1 Isotonic Concentration of the Waste Tank j Determine the isotopic concentration in waste stream to be released: IC1= ICg + (Ca + Cs + Ct + CFe) i g [Eq 1-1] l Where: ICj = Sum of the concentrations of each radionuclide, in the i release (uC1/ml) 7 ICg= Sum of the concentrations of each measured g gasuna emitter, g, (uC1/ml) as required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. Ca = Concentration of alpha emitters as measured in the most recent composite sample (uci/ml) required by Radiological Effluent Control 3/4.11.1.1 Table 4.11- , 1. (Sample analyzed for gross alpha only) 7 Cs = Concentration of 89S r and 90S r as measured in the 7 most recent composite sample (uC1/ml) required by
. Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.
Ct= Concentration of 3H as measured in the most recent 7 composite sample (uci/ml) required by Radiological Effluent Control 3/4.11.1.1 Table 4.11-1. l CFe= Concentration of 55F e as measured in the most recent 7 ! compositesample(uC1/ml)requiredbyRadiological Effluent Control 3/4.11.1.1 Table 4.11-1. 1.1.2 Effluent Flow Rate (f) i , The maximum effluent discharge flow rates for each release 7 source are shown in Table 1.1. For pre-release calculations, 8 l the maximum effluent flow rate is normally used. For post-release calculations, the average effluent flow rate during the release may be used. When the maximum effluent flow rate 8 is used for pre-release calculations, no setpoint is required l for the flow measuring device for the effluent release line. { If a lower effluent flow rate is used in pre-release l calculations, a flow measuring device setpoint shall be established to ensure that the ratio of the Required Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-3 01/93
i 1 Dilution Factor (RDF) to the Actual Dilution Factor (ADF) is maintained 8 less tnan or equal to 1.0. as discussed in Section 1.1.6. ADF and RDF are defined in Section 1.1.4 and 1.1.5. respectively. 1.1.3 Dilution of Liauid Effluents
- a. Discharges to SCR via Circulating Water Discharge Tunnel 7 I
Since liquid effluents from the radwaste treatment system. Waste Water 7 I i Holdup Tanks and the LVW Pond are mixed with Circulating water prior to i 1 \ l being discharged to Squaw Creek Reservoir, compliance with 10 CFR 20 is ' a function of the Circulating water flcu rate. The maximum Circulating water flow rate per plant is 1.1 million gpm. This is determined from l the Ingersoll-Rand pump curves (Fig.1.2) which indicate a flow rate per pump of 275.000 gpm. The actual Circulating water dilution flow is given by: l l F(diluting flow) - (275.000 gpm/ pump) x'(# of pumps) x 0.9 l [Eq. 1-2] Where: 0.9 - Safety Factor to compensate for flow fluctuations from I the rate predicted by the Circulating water pump curves (Fig. 1.2). As an additional consideration, the available dilution flow for any ! release may be corrected to allow for simultaneous releases from the Radwaste Processing System, a Waste Water Holdup Tank, and/or the LVW Pond (i.e., a radwaste system tank, a Waste Water Holdup Tank, and the LVW Pond may be discharged simultaneously). For simultaneous releases, the available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases. Also, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isetopes. It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows: F' - F (1 - E, (C',/10ECL,)) [Eq. 1-3] 12 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-4 Rev. 12 12/95
Ehere: F' - Adjusted Circulating Eater Flow Rate 7 C', - Maximum concentration of radionuclide i in Squar 12 l Creek Reservoir (uC1/ml) as measured in the analysis of the monthly samples of the reservoir ; required by Radiological Effluent Control 3/4.12.1. Table 3.12.1. Sample locations are listed and maintained current in the results of the annual Land l Use Census. ! ECLi - Effluent Concentration Limit of radionuclide 1. from 8 10CFR20. Appendix B. Table 2. Column 2 F - (275.000 gpm/ pump) x (# or pumps) x 0.9 7 NOTE: If C', is less than LLD then F' - F and no adjusted flow rate need be considered in the calculation of ADF. The LLD values I ~ used for this determination shall be the LLD values for water given in Radiological Effluent Control 3/4.12.1. Table 4.12-1. i
)
! b. Discharges to the LVW Pond , 1 i Secondary release sources are discharged directly to the LVW Pond - with no dilution (i e.. F-0). l i 1.1.4 Actual Dilution Factor (ADF) 1 i l ADF is the ratio of the effluent flow rate plus the Circulating : water flow rate divided by the effluent flow rate. l ADF - (f + F)/f [Eq. 1-4] Where: f- Effluent flow rate (gpm) , F- Dilution flow rate (gpm) NOTE: If radioactivity is detected in the Reservoir. an adjusted Circulating water flow rate. F' shall be used ! in place of F in the calculation of ADF. See Section 1.1.3 for the calculation of F' (Eq. 1-3). Also, if I simultaneous releases are occurring, the available dilution flow shall be reduced by the required dilution flow for any other concurrent release. COMANCHE PEAK - UNITS 1 AND 2 PART II 1-5 Rev. 12 12/95
1.1.5 Reauired Dilution Factor (RDF) The required dilution factor ensures that the limits of Control 12 3/4.11.1.1 (i.e. 10 times the effluent concentrations expressed in 10CFR20. Appendix B. Table 2. Column 2. and a total concentration of dissolved or entrained noble gases of 2 x 10 4 uC1/ml) are not exceeded during a discharge. The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded. RDF - (E , (C,/10ECL,)) x SF 12 (p , (C,/10ECL,) + (C /10ECL, + C,/10ECL, + C /10ECL t t + Cr,/10ECLr.)) x SF [Eq. 1-5] l Where: ECL, - Effluent Concentration Limit of radionuclide 1. from 8 10CFR20. Appendix B. Table 2. Column 2 l SF - Safety Factor of 2. 7 l All other variables and subscripts are previously defined. NOTE: If RDF is less than 1. the release meets discharge limits 7 l without dilution. For conservatism, set RDF equal to 1.0. The maximum value for the high alarm setpoint for detector l XRE-5253 would then be calculated in accordance with the l equation for C i ,, in Section 1.2.1. 1.1.6 10 CFR 20 Comoliance , Compliance with 10 CFR 20 is demonstrated if the Actual Dilution Factor 7 (ADF) is greater than or equal to the Required Dilution Factor (RDF). or: IE. 1 1.0 [Eq. 1-6] 7 ADF l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-6 Rev. 12 12/95 m
1.2 RADIATION MONITOR ALARM SETPOINTS 7 1.2.1 Primary Liouid Effluent Monitor XRE-5253 7 To ensure that releases from the primary radwaste processing system do 12 not exceed 10 times the 10 CFR 20. Appendix B. Table 2. Column 2 limits at the point of release to the CONTROLLED AREA or UNRESTRICTED AREA. a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the discharge isolation valve 7 controlled by XRE-5253. The isolation valve shuts automatically if the detector alarms on high radiation or a detector operation failure occurs. It should be noted that the liquid effluent monitor setpoint 10 values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments. That is. 7 setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor. Since the radiation monitor XRE-5253 is a gamma sensitive device, the 10 monitor setpoint value shall be set based on the gama radionuclides present in the waste stream. Therefore, a Required Dilution Factor gamma (RDF,) must be determined before the setpoint can be calculated. RDF, - E (C,/10ECL,) X SF [Eq. 1-6a] 12 Where: RDF, - The required dilution factor (gamma) corresponding to the gama concentration in the undiluted waste stream ensuring that 10 times the effluent concentration limits in 10CFR20. Appendix B. Table 2. Column 2 are not exceeded at the point of release during a discharge. If RDF, is less than 1. set RDF, equal to 1.0. SF - A required safety factor of 2 is used to account for 10 the presence of Tritium, composited Alpha emitters. Fe-55. Sr-89 and Sr-90 values which are undetectable by this monitor and are at or near equilibrium and/or not cpected to change rapidly under most plant conditions and statistical errors of measurement. COMANCHE PEAK - UNITS 1 AND 2 PART II 1-7 Rev. 12 12/95
The monitor XRE-5253 setpoint is determined using the following 10 calculation: Ci , - (ADF/RDF,) x E, C, [Eq. 1-7] Where: C,- i The liquid waste effluent monitor alarm setpoint. This 12 corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1. All other variables are as previously defined. 7 When considering tne mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be tnose referenced in Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. Table Notation 2. Figure 1.3 is a representative energy spectrum response for the RD-33 type detector used in XRE-5253. This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. In fact between "'Cs and "Co. the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations. However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required. 1.2.2 Turbine Buildina Sumn Effluent Radiation Monitor 1RE-5100 and 2RE-5100 8 The purpose of the turbine building sump monitor (1RE-5100 and 2RE-5100) is to monitor turbine building sump discharges and divert this discharge from the Low Volume Waste Pond to the Waste Water Holdup Tanks if radioactivity is detected. Because the only sources of water 7 to the turbine building sump are from the secondary steam system. activity is expected only if a significant primary-to-secondary leak is present. Since detectable radioactivity is not normally present in the 8 Turbine Building Sumps, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet I alarm, should an inadvertent I I l CCNANCHE PEAK - UNITS 1 AND 2 PART II 1-8 Rev. 12 1 12/95
radioactive release occur. To this end. the setpoint e111 be 8 l initially established at three (3) times background until further data I can be collected. Then if this setpoint is exceeded the monitor will 8 l direct control valves to divert the turbine building sumps discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek 7 ) Reservoir, if required by Radiological Effluent Control 3/4.11.1.1. I Table 4.11-1. When radioactive materials are detected in the Turbine 12 ! Building Sumps, a setpoint then may be established for 1RE-5100 or 2RE-5100 using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond. 1.2.3 Service Water Effluent Radiation Monitors 1RE-4269/4270 and 8 f 2RE-4269/4270 The concentration of radioactive material in the service water effluent 7 line normally is expected to be insignificant. Therefore, the monitor alert alarm setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. To this end, the alarm setpoint will be initially established at three (3) times background until further data can be collected. If this effluent stream should become contaminated. radionuclide concentrations should be determined from grab samples and a radiation mo'iitor a' arm setpoint determined as follows: C- ( E, C,) + DF < [Eq. 1-8] 7 l Where: C, - Service Water effluent monitor alarm setpoint l C, - Concentration of each measured gama emitter g. l observed in the effluent (uC1/ml) i DF = E,(C,/10ECL,) - Dilution factor required to ensure 12 limits of Control 3/4.11.1.1 are not exceeded. For this release pathway no additional dilution is available. I Therefore, if the calculated DF is greater than 1.0. any releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1. If radioactivity is detected in this COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9 Rev. 12 12/95
release stream, doses due to releases from this stream shall be 7 calculated in accordance tsith the methodology given in Section 1.3. with the near field average dilution factor. F . equal to 1.0. 1.2.4 Auxiliary Buildina to LVW Pond Radiation Monitor XRE-SPE 9 i The purpose of the Auxiliary Building to LVW Pond monitor (XRE-5251A) is to 9
- monitor the Auxiliary Building Sumps 3 and 11. Unit I and Unit 2 Diesel Generator
] Sumps 1 through 4 and the Unit 1 and Unit 2 Component Cooling Water Drain Tanks
- continuous dischrges and divert these discharges from the Pond to the Waste Water Holdup Tanks if radioactivity is detected. Since detectable radioactivity is not normally present in these discharges, the monitor setpoint should be
! established as close to background as practical to prevent spuc'ous alarms and yet alarm should an inadvertent radioactive re' lease occur. To this end, the j setpoint will be initially established at three (3) times background until
- further data can be collected. Then, if this setpoint is exceeded. XRE-5251A
! will direct valves X-HV-WM182 and 183 to divert the discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological - Effluent Control 3/4.11.1.1. Table 4.11-1. When radioactive materials are 12 ! j detected in the discharges, a setpoint then may be established for XRE-5251A using the methodology in Section 1.2.1 to ensure that the limits of Control l i 3.11.1.1 are not exceeded in discharges to the LVW Pond. ' i. i i I 1 l i COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9a Rev. 2.! l 12/95
l 1.3 DOSE CALCULATION FOR LIOUID EFFLUENTS For implementation of Radiological Effluent Control 7 3/4.11.1.2, the dose coinnitment from the release of liquid l effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose connitments will be maintained for each calendar quarter and each calendar year. Dose calculations will be performed for releases from the Plant Effluent Tanks, Waste Monitor Tanks, 7A Laundry Holdup & Monitor Tanks, Waste Water Holdup Tanks, and 7 the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir. Although the LVW Pond is 8 located in a CONTROLLED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no real pathways for exposure to members of the public. Doses for these pathways will be calculated when the LVW Pond is 7 discharged to Squaw Creek Reservoir. The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a calendar year) will be calculated using the following equation: DT= IDk + ID(lake)u [Eq 1-9] k m Where DT= the dose commitment to the total body or any organ due 8 to all releases during the desired time interval from ! allreleasesources(area). Ok= the dose commitment received by the total body or any 7 organduringthedurationofreleasek(area). The equation for calculating Dk is given in Section 1.3.1(Eq.1-10) O(lake)s= the dose commitment received by the total body or any 7 organ during the desired time period, s, (normsily a = l 31 days) due to the buildup in the lake of previously discharged radionuclides. The equation for calculatingD(lake)sisgiveninSection1.3.2(Eq.
- 1-12). 7 Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-10 01/93
l To demonstrate compliance with the dose lisits of Control 8 3/4.11.1.2, thecalculatedcumulativedose(i.e.,thetotal doseforbothunits)willbecomparedtotwotimesthedose limits for a unit. In other words, the dose assigned to each unit will be one-half of the total doses from all releases from the site. 1.3.1 Calculation of Dose Due to Liouid Releases 7 The dose commitment to the total body or any organ due to a 7 l release will be calculated using the following equation. Ok= 2jAj tk Cik Fk [Eq. 1-10] 7 Where: tk = the time duration of the release k (hrs) 7 l Cik = The isotopic concentration (uC1/ml) of 7 radionuclide i found in the release sample for ( release k. Concentrations are determined primarily from galana isotopic analysis of the 1 liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured i value will be used in the dose calculation. Fk = The near field average dilution factor during 7 a liquid effluent release.' This is defined as the ratio of the average undiluted liquid { effluent flow rate to the average Circulating ! water flow rate during the release. The average liquid effluet flow rate is based on the actual average flow into the Circulating water during the release. L , Fk = averaae undiluted 11auid effluent flow rate 7 ! circulating water flow rate ( l l l Rev. 8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-11 01/93 1
4 Air = the site related ingestion dose commitment 7 factor for the toal body or any organ, r , for each identified ga ma or beta emitter (ares /hr per uC1/ml). Ajr is calculated as follows: l j Aj, = 1.14x105 (Uw/Dw + U fBF1 ) DFj i [Eq. 1-11] 7 Where: 1.14x105 = unit conversion factor, 7 Uw = adult water consumption from Squaw Creek 8 Reservior, 0 liters /yr for CPSES. 1 l. Uf = adult fish consumption, 21 kg/yr 7 BF1
=
bioaccumulation factor for radionuclide i, in 7 fish n' rom Table A-1, Ref. 2 (pC1/kg per i
! pC1/1) 7
- DFj =
adult dose conversion factor for radionuclide 7 1,fromTableE-11,Ref.2(mres/pCi ingested) Ow
=
Dilution factor from the near field area 7 within one-quarter mile of the release point to the potable water intake for the adult water consumption; 1.0 for CPSES. , (unitiess) Calculated values for A17 are given in Table 1.2. 1.3.2 Calculation of Dose Due to Radionuclide Builduo in the Lake 7 1
- The dose contribution from significant pathways, due to 8 buildup of previously discharged radionuclides in the lake, f must be considered in the comitted dose calculation only if Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-12 01/93
radioactivity is det cttd in the water of Squaw Creek 8 Reservoir or in fish from Squaw Creek Reservoir. Based on the design calculations presented in the CPSES FSAR, Appendix I 11A and documented in CPSES Engineering Calculation No. ME-
- CA-0000-3161, the significant pathways included in this calculation are fish consumption from Squaw Creek Reservoir and consumption of meat from cows drinking water from Squaw Creek. Additionally, consumption of milk from cows drinking water from Squaw Creek is included, but a CPSES site-specific
! consumption factor of 0 is normally used since there are no identified animals milked for human consumption along Squaw { Creek. If animals milked for consumption are identified
- along Squaw Creek during the annual land use census, this l pathway should be included in the dose calculation. Also, i water from Squaw Creek Reservoir or Squaw Creek is not used as i
a source of drinking water, so the drinking water pathway is ! not included in dose calculations. I To further simplify the calculation, the dose due to 8 I consumption of meat and milk from cows drinking water from i Squaw Creek is only calculated for tritium. CPSES
- Engineering Calculation No. ME-CA-0000-3161 shows that tritium is the only isotope routinely released from CPSES that 4
fiignificantly contributes to the dose from these pathways (f.e., >95% of the total dose). The calculation does show a j significant dose contribution from Ru-106 for the cow-meat ] pathway, but this isotope has not historically been observed in actual CPSES liquid effluent samples. The dose from the fish consumption pathway will be calculated for all measured j isotopes. i The contribution to the total dose due to the buildup of 8 l radionuclides in the reservo'ir is determined as follows: } D(lake), = 1.1hl d @ g DF9 C'$7 U)+ f 8 DF i t C'tw Oaw (Umilk Fmt + Umeat Fft)l [Eq. 1-12] 4 COMANCHE PEAK UNITS 1 AND 2 PART II 1-13 Rev. 8 ERRATA (6/93)
Where: 1.14 x 10-4 = units conversion factor (yr/hr) C'jr = concentration of radionuclide i in fish 7 sampled from Squaw Creek Reservoir from location F1 or Table 3.1 and Figure 3.1 of this manual (pC1/kg) DFt' = adult ingestion dose conversion factor for 8 l tritium for the organ of interest form Table E-11, Ref. 2 (mres/pci). l C'tw = concentration of tritium in the reservoir. 8 This value shall correspond to the highest j concentration measured at any Squaw Creek I Reservoir sample location (pC1/1). Qaw
=
the consumption rate of contaminated water by A l a cow, 60 1/ day from Table E-3, Ref. 2. Umilk = adult milk consumption rate. A CPSES site 8 specific useage factor of 0 is normally used unless milk cows are identifed along Squaw Creek during the annual Land Use Census. If
- milk cows are identifed, a value of 310 1/yr from Table E-5, Ref. 2, should be used.
Fat = the stable element transfer coefficient for 8 tritium that relates the daily intake rate of '
- tritium by a cow to the concentration in milk, !
i 1.0E-2 pC1/1 per pC1/ day from Table E-1, Rev. 2. Umeat
=
adult meat consumption rate, 110Kg/yr from 8 i Table E-5, Ref. 2. l Fft = the stable element transfer coefficient for 8 tritium that relates the daily intake rate of i tritium by a cow to the concentration in meat. 1.2E-2 pCi/kg per pC1/ day. Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-14 01/93
I i : All oth;r variables are previously defined. 7 ! NOTE: This calculation is only required if activity is detected in 7 water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1 Table 4.12-1. ) If the measured activity in water or fish.is less than the required LLD values, the concentration for that particular pathway is asswea to be zero. 1.4 00SE PROJECTIONS FOR LIOUID EFFLUENTS 7 Radiological Effluent Control 3/4.11.1.3 requires that 8 appropriate portions of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected l doses due to the liquid effluent from each reactor unit to I CONTROLLED AREAS and UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this 7 dose projection. At least once every 31 days, the total dose from liquid 8 releases for each unit for the previous three months will be l divided by the number of days in the three month period and multiplied by 31. Also, this dose projection may include the estimated dose for a unit due to any anticipated unusual releases during the period for which the projection is made. If the projected dose for a unit exceeds 0.06 aren total body , or 0.2 ares for any organ, appropriate portions of the Liquid Radweste Treatment System shall be used to reduce radioactivity levels prior to release. I i i i Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1 *5 01/93
. . -- - . - - - - . - - ~ . - - - _ - - _ - . . _ _ - - - - . _ . . -
i j i l 1.5 DEFINITIONS & CCH40N LIOUID EFFLUENT PARAMETERS 7 i { If,BR DEFINITION i j ADF ActualDilutionFactor(unitiess). This is defined as the 7 ratio of the effluent flow rate plus the circulating water { flow rate divided by the affluent flow rate. l j 4 Ari The site related ingestion dose commitment factor to the 7 total body or any organ, r , for each identified gamma or j beta emitter, 1. (mrem /hrperuC1/ml) i 1 BFj Biaccumulation factor for radionuclide, 1, in fish from 7 1 Reg. Guide 1.109. (pC1/kg per pC1/1) 1 Ca the concentration of alpha emitters in liquid waste as 7 } measured in the analysis of the most recent monthly composite l sample required by Radiological Effluent Control 3/4.11.1.1, l Table 4.11-1. (uC1/ml)
- Cpe The concentration of 55F e in liquid waste as measured 7 i
1' in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control
.. 3/4.11.1.1, Table 4.11-1. (uC1/ml) 3
! cg The concentration of each measured ganom emitter, g in the 7 i waste tank as measured in the analysis of the sample of each i batch as required by Radiological Effluent Control 3/4.11.1.1 Table 4.11-1 (uC1/ml) Ci The concentrations of radionuclide, 1, in the waste tank. 7 1 (uC1/ml) i* C'j The concentration of radionuclide i in the Reservoir as 7 measured in the analysis of the monthly sample of the l Reservoir required by Radiological Effluent Control { 3/4.12.1 Table 3.12-1. This sample is taken at the Circulatory Water Intake Structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual. l (uC1/ml) C'y The concentration of radionuclide i in fish sampled from 7 the reservoir from location F1 on Table 3.1 and Figure j, 3-1 of this manual (pC1/kg). j Cik The isotopic concentration of radionuclide i found in 7
- the pre-release sample for batch release k.
i Concentrations are determined primarily from gamma
! isoto For j 895 r,p,ig ana;ysis
'#USr, Fofethe dH, 55 andliquid alphaeffluent emitters,sample. the
] last measured value will be used. (uC1/al) i i
i ~ COMANCHE PEAK - UNITS 1 AND 2 PART II 1-16 01/93 4 ___ . _ _ _ - . --. ,.v.~ - - ~ - ' ' -
,Ilgd DEFINfT10N C ' ,, The maximum concentration of radionuclide i in SCR as measured in 12 analysis of monthly samples of SCR.
C,, The liquid waste effluent monitor alarm setpoint. This corresponds to the gama concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1. (uC1/ml) C, The concentration of "Sr and "Sr in liquid waste as measured in the 7 analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. (uCi/ml) C,, The Service Water effluent monitor alarm setpoint. (uCi/ml). l
- C The concentration of 3H in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. (uC1/ml)
DF, Adult dose conversion factor for radionuclide, i, from Reg. Guide 1.109. (mrem /pCi ingested) D, The dose commitment received by the total body or any organ during 4 the duration of batch release k of liquid effluents. (mrem) i D(lake), The dose commitment received by the total body or any organ during a i desired time period, m due to the buildup in the lake of previously j discharged radionuclides. (mrem) D, The total dose commitment to the total body or any organ due to all releases of liquid effluents during a desired time interval. (mrem) , i D, Dilution factor, from the near field area within 1/4 mile of the j
- release point to the potable water intake for adult water consumption. 1.0 for CPLES. (unitiess) ,
f Effluent flow rate. (gpm) ; i F Circulating water flow rate (or dilution flow rate.). (gpm) l F' Adjusted Circulating water flow rate to account for buildup of I radionuclides in the Circulating water due to previous releases. (gpm) l l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-17 Rev. 12 12/95
Ifati DEEIETlQti F. The near field average dilution factor during a liquid effluent release 7 (unitiess). This is defined as the ratio of the average undiluted liquid waste flow to the average Circulating water flow during the release. ECL, Effluent Concentration Limit
- of a mixture of unidentified alpha 8 emitters. (uCi/ml)
ECLr, Effluent Concentration Limit
- of 55Fe. (uCi/ml)
ECL, Effluent Concentrat.on Limit
- of each identified gamma emitter, g.
(uC1/ml) ECL, Effluent Concentration Limit
- of radionuclide.1. (uC1/ml).
ECL, Effluent Concentration Limit
- of a mixture of "Sr and "Sr. (uCi/ml)
ECL t Effluent Concentration Limit
- of tritium (3H). (uC1/ml).
SF Safety Factor of 2. Used in the calculation of the Required Dilution 7 Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded. RDF Required Dilution Factor (unitless). This is defined as the dilution 12 factor that ensures that 10 times the effluent concentrations expressed i in 10CFR20. Appendix B. Table 2. Column 2 are not exceeded at the ! point of release to CONTROLLED AREAS and UNRESTRICTED AREAS during a discharge. ) I t, The time duration of batch release k. (hours) 7 i U, Adult fish consumption. (kg/yr) U, Adult water consumption. (11cers/yr)
- Effluent Concentration limits (ECL) for liquids are given in 10CFR20. Appendix B. Table 2. Column 2. A value of 2x104 oC1/ml for dissolved or entrained noble gas shall be used.
COMANCHE PEAK - UNITS 1 AND 2 PART II 1-18 Rev. 12 12/95
l TABLE 1.1 7 StMiARY OF LIOUID RELEASE PATHWAYS 7
- 1. RELEASES TO SCR VIA THE CIRC WATER DISCHARGE 7 Release Source Release Type Max Flow Max Vol Monitor l Rate (com) (aal) l PET-1 Batch 100 30000 XRE-5253 7A PET-2 Batch 100 30000 XRE-5253 WMT-1 Batch 100 5340 XRE-5253 7 i WMT-2 Batch 100 5340 XRE-5253 i LHMT-1 Batch 100 5875 XRE-5253 LHMT-2 Batch 100 5875 XRE-5253 WWHT-1 Batch 300 30500 None 12 WWHT-2 Batch 300 30500 None LVW Pond Continuous 1600 -
None 7
- 2. RELEASES TO THE LVW POND Release Source Release Type Max Flow Max Vol Monitor l Rate (com) -(cal) i CPBWRT-A Batch 1550 8500 None -11 CPBWRT-B Batch 1550 17000 None WWHT-1 Batch 200 33100 None 9 WWHT-2 Batch 200 33100 None TBSump2 (Unit 1) Continuous 300 -
1RE-5100 7 TBSump4 (Unit 2) Continuous 300 - 2RE-5100 8 AB Secondary
- Continuous 380 -
XRE-5251A 9
- 3. DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) 7 Release Source Release Type Max Flow Max Vol Monitor l Rate (anm) (aal) 2 Unit 1 SSW Train A Continuous 17,000 - 1RE-4269 8 Unit 1 SSW Train B Continuous 17,000 -
1RE 4270 Unit 2 SSW Train A Continuous 17,000 - 2RE-4269 Unit 2 SSW Train B Continuous 17,000 - 2RE-4270 80.TE: 9
- AB Secondary Effluents contain the following sources:
1 Max. Flow (com) ! Auxiliary Building Sump 3 50 Auxiliary Building Sump 11 50 Diesel Generator Sump 1 (Unit 1) 50 Diesel Generator Sump 2 (Unit 1) 50 Diesel Generator Sump 3 (Unit 2) 50 Diesel Generator Sump 4 (Unit 2) 50 CCWDT (Unit 1) 40 CCWDT (Unit 2) 40 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-19 REV. 12 12/95
TABLE 1.2 7 PAGE (1 of 4) SITE RELATED INGESTION DOSE COMMITMENT FACTOR A1 ,. (mrem /hrperuCi/ml) ISOTOPE RQE Llylg T-BODY THYROID KIDNEY LufG GI-LLI H-3 0.00E+00 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 8 C-14 3.13E+04 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 8 NA-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 8 P-32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06 8 CR-51 0.00E+00 0.00E+00 1.27E+00 7.62E-01 2.80E-01 1.69E+00 3.20E+02 8 MM-54 0.00E+00 4.38E+03 8.35E+02 0.00E+00 1.31E+03 0.00E+00 1.34E+04 8 MN-56 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.51E+03 8 FE-55 6.58E+02 4.55E+02 1.06E+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 8 FE-59 1.04E+03 2.44E+03 9.35E+02 0.00E+00' O.00E+00 6.82E+02 8.16E+03 8 CO-58 0.00E+00 8.91E+01 2.00E+02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 8 CO-60 0.00E+00 2.56E+02 5.65E+02 0.00E+00 0.00E+00 0.00E+00 4.81E+03 8 NI-63 3.11E+04 2.16E+03 1.05E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 8 NI-65 1.26E+02 1.64E+01 7.49E+00 0.00E+00 0.00E+00 0.00E+00 4.16E+02 8 CU-64 0.00E+00 9.97E+00 4.68E+00 0.00E+00 2.51E+01 0.00E+00 8.49E+02 8 ZN-65 2.32E+04 7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.65E+04 8 ZN-69 4.93E+01 9.44E+01 6.56E+00 0.00E+00 6.13E+01 0.00E+00 1.42E+01 8 BR-83 0.00E+00 0.00E+00 4.05E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 8 BR-84 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11E-04 8 8R-85 0.00E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 8 R8-86 0.00E+00 1.01E+05 4.71E+04 0.00E+00 0.00E+00 0.00E+00 2.00E+04 8 R8-88 0.00E+00 2.94E+02 1.56E+02 0.00E+00 0.00E+00 0.00E+00 3.93E-09 8 R8-89 0.00E+00 1.95E+02 1.37E+02 0.00E+00 0.00E+00 0.00E+00 1.13E-11 8 SR-89 2.21E408 0.00E+00 6.35E+02 0.00E+00 0.00E+00 0.00E+00 3.55E+03 8 SR-90 5.47E405 0.00E+00 1.33E+05 0.00E+00 0.00E+00 0.00E+00 1.58E+04 8 SR-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 0.00E+00 1.94E+03 8 SR-92 1.54E+02 0.00E+00 6.67E+00 0.00E+00 0.00*+00 0.00E+00 3.06E+03 8
- Y-90 5.77E-01 0.00E+00 1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.11E+03 8 i Y-91M 5.44E-03 0.00E+00 2.11E-04 0.00E+00 0.00E+00 0.00E+00 1.60E-02 8 j Y-91 8.45E+00 0.00E+00 2.25E-01 0.00E+00 0.00E+00 0.00E+00 4.64E+03 8 i Y-92 5.06E-02 0.00E+00 1.48E-03 0.00E+00 0.00E+00 0.00E+00 8.87E+02 8
REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-20 01/93
TABLE 1.2 7 PAGE (2 of 4) SITE RELATED INGESTION DOSE COMITMENT FACTOR A1 , (mrem /hrperuC1/ml) ! ISOTOPE E LIER T-BODY THYROID KM1 L11lifa GI-LLI Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E+00 0.00E+00 0.00E+00 5.10E+03 8 ZR-95 2.40E-01 7.70E-02 5.21E-02 0.00E+00 1.21E-01 0.00E+00 2.44E+02 8 ZR-97 1.33E-02 2.68E-03 1.22E-03 0.00E+00 4.05E-03 0.00E+00 8.30E+02 8 NB-95 4.46E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 8 MO-99 0.00E+00 1.03E+02 1.%E+01 0.00E+00 2.35E+02 0.00E+00 2.39E+02 8 TC-99M 8.86E-03 2.51E-02 3.20E-01 0.00E+00 3.80E-01 1.23E-02 1.48E+01 8 TC-101 9.13E-03 1.31E-02 1.29E-01 0.00E+00 2.37E-01 6.72E-03 3.95E-14 8 RU-103 4.42E+00 0.00E+00 1.91E+00 0.00E+00, 1.69E+01 0.00E+00 5.16E+02 8 RU-105 3.69E-01 0.00E+00 1.45E-01 0.00E+00 4.76E+00 0.00E+00 2.26E+02 8 RU-106 6.59E+01 0.00E+00 8.33E+00 0.00E+00 1.27E+02 0.00E+00 4.27E+03 8 AG-110M 8.81E-01 8.13E-01 4.84E-01 0.00E+00 1.60E+00 0.00E+00 3.33E+02 8 l TE-125M 2.57E+03 9.29E+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00'~1.02E+04 8 I TE-127M 6.49E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 8 I TE-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.00E+00 8.31E+03 8 TE-129M 1.10E+04 4.11E+03 1.74E+03 3.78E+03 4.60E+04 0.00E+00 5.55E+01 8 TE-129 3.01E+01 1.13E+01 7.32E+00 2.31E+01 1.26E+02 0.00E+00 2.27E+01 8 l TE-131M 1.066+03 8.11E+02 6.75E+02 1.28E+03 8.21E+03 ,0.00E+00 8.04E+04 8 TE-131 1.89E+01 7.88E+00 5.95E+00 1.55E+01 8.26E+01 0.00E+00 2.67E+00 8 TE-132 2.41E+03 1.56E+03 1.46E+03 1.72E+03 1.50E+04 0.00E+00 7.38E+04 8 I-130 2.72E+01 8.02E+01 3.17E+01 6.78E+03 1.25E+02 0.00E+00 6.90E+01 8 I-131 1. 2.14E+02 1.22E+02 6.99E+04 3.68E+02 0.00E+00 5.64E+01 8 I-132 7. 1.95E+01 6.81E+00 6.81E+02 3.10E+01 0.00E+00 3.68E+00 8 I-133 5. 8.86E+01 2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.96E+01 8 I-134 3.80E+00 1.03E+01 3.71E+00 1.79E+02 1.65E+01 0.00E+00 9.01E-03 8 I-135 1.59E+01 4.16E+01 1.54E+01 2.75E+03 6.69E+01 0.00E+00 4.70E+01 8
- CS-134 2.98E+05 7.09E+05 5.79E+05 0.00E+00 2.29E+05 7.62E+04 1.24E+04 8 l CS-136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.39E+03 1.40E+04 8 l CS-137 3.81E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E+04 1.01E+04 8 l CS-138 2.64E+02 5.22E+02 2.59E+02 0.00E+00 3.83E+02 3.78E+01 2.23E-03 8 BA-139 9.29E-01 6.61E-04 2.72E-02 0.00E+00 6.18E-04 3.76E-04 1.65E+00 8 REV. 8 COMANCHE PEAK - UNITG 1 AND 2 PART II 1-21 01/93
TA8LE 1.2 7 PAGE(3of4) SITE RELATED INGESTION DOSE COMITMENT FACTOR Aj, ) (mrem /hrperuC1/ml) i ! ISOTOPE HQtiE LlYER T-BODY THYROID KlDE.Y. Lulifa GI-LLI I i ! BA-140 1.94E+02 2.45E-01 1.27E+01 0.00E+00 8.31E+00 1.39E-01 4.00E+02 8 } BA-141 4.51E-01 3.41E-04 1.53E-02 0.00E+00 3.17E-04 1.93E-04 2.06E-10 8 f BA-142 2.04E-01 2.09E-04 1.28E-02 0.00E+00 1.77E-04 1.19E-04 2.87E-19 8 ! LA-140 1.50E-01 7.53E-02 1.99E-02 0.00E+00 0.00E+00 0.00E+00 5.52E+03 8 ' LA-142 7.66E-03 3.16E-03 8.66E-04 0.00E+00 0.00E+00 0.00E+00 2.54E+01 8 CE-141 2.24E-02 1.51E-02 1.72E-03 0.00E+00 7.05E-03 0.00E+00 5.79E+01 8 l CE-143 3.94E-03 2.91E+00 3.24E-04 0.00E+00 1.29E-03 0.00E+00 1.09E+02 8 CE-144 1.17E+00 4.89E-01 6.26E-02 0.00E+00. 2.91E-01 0.00E+00 3.94E+02 8 ). PR-143 5.52E-01 2.21E-01 2.73E-02 0.00E+00 1.28E-01 0.00E+00 2.41E+03 8 l PR-144 1.Il0E-03 7.49E-04 9.16E-05 0.00E+00 4.23E-04 0.00E+00 2.59E-10
. 8
- ND-147 3.76E-01 4.35E-01 2.60E-02 0.00E+00 2.54E-01 0.00E+00 2.09E+03 8 j W-187 2.95E+02 2.48E+02 8.65E+01 0.00E+00 0.00E+00 0.00E+00 8.11E+04 8
{ NP-239 2.86E-02 2.79E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.74E+02 8 j *SB-122 4.42E+00 8.71E-02 1.29E+00 6.01E-02 0.00E+00 2.30E+00 1.27E+03 8 l **SB-124 5.38E+01 1.01E+00 2.12E+01 1.30E-01 0.00E+00 4.18E+01 1.52E+03 8 ) **8R-82 0.00E+00 0.00E+00 1.78E+02 0.00E+00 0.00E+00 0.00E+00 2.05E+02 8
**SB-125 4.27E+01 4.58E-01 8.58E+00 3.80E-02 0.00E400 ,4.45E+03 3.78E+02 8 i **SB-126 2.20E+01 4.47E-01 7.93E+00 1.35E-01 0.00E+00 1.35E+01 1.80E+03 8 j **SB-127 4.94E+00 1.80E-01 1.90E+00 5.94E-02 0.00E+00 2.93E+00 1.13E+03 8
**LA-141 1.14E-02 3.55E-03 5.81E-04 0.00E+00 0.00E+00 0.00E+00 4.23E+02 8 l
l I 1 i e
?
l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-22 01/93
!
- The adult dose conversion factors, DF1 , for Sb-122 are not published 5 in Reference 2. The calculation of dose conversion factors and site-related ingestion dose commitment factors for Sb-122 is documented in Reference 10.
j The adult dose conversion factors, DFj, for Sb-124, Sb-125, Br-82, 7 Sb-126, Sb-127 and La-141 are not published in Reference 2. The site- 8 l related dose commitment factors for Sb-124, Sb-125, Br-82, Sb-126, Sb-l 127 and La-141 were calculated using the " Adult Ingestion Dose Factors" given in Table A-3 of Reference 11, and Equation 1-11 of Part II, l Section 1.3.1 of this Manual. l l r REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-23 01/93
O From l Urut 1 SSW- Tran A 1RE-4269 O Lapd Waste Processang l Urut1 SSW-Tran Ek3 ; Ougas 501 f System 1RE-4270 + g, 3% Z f Urut2 SSW-Tran A ) trmoundment Q , 2RE4269 m XRE-5253 33J00 W l Urut 2 SSW-Tran B p 2RE-4270 88" **' 3 )( XRV4253 Z
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I 1 I i l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-25 Rev. 12 12/95
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COMANCHE PEAK - UNITS 1 AND-2 3 PART II 1-27 1
SECTION 2.0 GASEOUS EFFLUENTS 8 l At CPSES, normal radioactive gaseous effluents are collected in a common exhaust air intake plenum, processed through charcoal and HEPA filters, and discharged to the atmosphere through the two common Plant Vent Stacks designated as Stack A and Stack B. Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative _ ground-level release. 8 Routine gaseous effluent releases may occur from the Unit 1 and Unit 2 Containment Buildings (purges and vents). Waste Gas Decay Tanks (WGOT), and the plant vent stacks (continuous ventilation). The normal . I ventilation exhaust via the plant vent stacks is considered a ! continuous release. Containment Building vents for pressure relief and l WGOT discharges are treated as batch releases. Because Containment Building purges are only allowed during MODES 5 and 6 and because radioactivity is discharged rapidly from the containment atmosphere 10 during purges, the first portion (i.e., the release period during which most containment atmospheric radioactivity is discharged) of a 8 Containment Building purge is considered a batch release. The j remainder of a purge is treated as a contribution to the continuous l release already occurring through the plant vent stacks. 8 Operating experience has shown that occasional releases may be required i from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS l during outages, from Volume Control Tank (VCT) vents during maintenance on the Waste Gas Processing System, from the Containment Buildings ! during Integrated Leak Rate Tests (ILRT), and from secondary steam releases (potentially radioactive during periods of primary-to-secondary leaks). These releases occur infrequently and are treated as batch releases. COMANCHE PEAK - UNITS 1 AND 2 PART II 2-1 Rev. 10 4/94
A summary of all gaseous effluent release points, release 8 sources,flowrates(ifapplicable)andassociatedradiation monitors is shown in Table 2.1. A flow diagram of all gaseous effluent discharge pathways is shown in Figure 2.1. Each Plant Vent Stack is equipped with a Wide Range Gas Monitor 8 (WRGM) and a Particulate, Iodine, and Noble Gas (PIG) Monitor. These monitors are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics). Since all DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e.,uC1/ml). The conversion factor for detector output from counts per minute to uC1/ml is determined during the calibration of each individual monitor, and is input into the data base for the monitor microprocessor. l The WRGMs are designated as monito'rs XRE-5570A and XRE-55708 for
~
Stacks A and B, respectively. Each WRGM consists of a low range j (10-7 to10-1uCi/cc), midrange (10-4 to 102uCi/cc), and high range (10-1 to 105 uC1/cc) noble gas activity l detector. The WRGMs also have an effluent release rate channel 4 i which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X-FT-5570A-1/B-1) to provide an indication of noble gas release rate in uC1/sec. Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of l Radiological Effluent Control 3/4.3.3.5. Execeeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases. The stack PIGS are designated as particulate channels XRE-5568A and XRE-55688, iodine channels XRE-5575A and XRE-55758, and noble gas channels XRE-5567A and XRE-55678 for Stacks A and B, respectively. The stack PIG noble gas channels may be used as a j back-up to the WRGM when no automatic control functions are \ Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-2
required. Therefore, a methodology is provided for calculating , the PIG noble gas monitor setpoints. Methodologies are not 8 provided for calculating setpoints for the PIG particulate and-iodine channels, since these channels are not required by the Radiological Effluent Controls Program, and because it is not practical to establish instaneous setpoints for integrating type monitors (reference 1). Other monitors that may be used for effluent monitoring and 8 l control are the Auxiliary Building Ventilation Duct Monitor, XRE-5701, and the Containment PIG Noble Gas Monitors, 1RE-5503 and l 2RE-5503. XRE-5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct. l XRE-5701 also provides the automatic control function for termination of Waste Gas Decay Tank releases. 1RE-5503 and 2RE- 8 5503 monitor the Unit 1 and Unit 2 Containment atmospheres, ' respectively, and provitte the only automatic control function for termination of Containment vents or purges. l l 2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE 8 2.1.1 Dose Rates Due to Noble Gates i For implementa. tion of Radiological Effluent Control 8 3/4.11.2.1.a, the dose rate to the total body and skin of an individual at the SITE BOUNDARY due to noble gases released from the site shall be calculated as follows: A. Total body dose rata due to noble antet 8 D=IDtv t v
= I (X/Q) I Ki Qv [Eq. 2-1]
v (noble gases) Where: Dt= the total body dose rate at the SITE 8 BOUNDARY due to noble gases from all releasesources(mrem /yr) Ov= t the total body dose rate at the' SITE 8 BOUNDARY due to noble gases from release sourcev(mres/yr). Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-3 01/93
(X/Q) = the highest annual average relative concentration at the SITE BOUNDARY (3.3x10-6sec/m3 in the NNW sector at a distance of 1.29 miles from the plant *.) i NOTE: The annual average X3 is also used in determining setpoints for containment purge or vent as required by Technical Specification 3.3.3.1. Ki= total body dose factor due to ganna 8 emissions from noble gas radionuclide i from Table 2.2 (mrem /yr per pC1/m3) Qiy = the total release rate of noble gas 8
)
radionuclide i from the release source v I (pC1/sec) (See C below for calculation of Qiv) y = index over all release sources 8 i B. Skin dose rate due to noble cases l D=IDsv s v
= I v(X/Q) I (L; + 1.1 M;) Q y (noble gases) 8
[Eq. 2-2) i Where: Ds = the skin dose rate at the SITE BOUNDARY due 8 to noble gases from all release sources.
, l (mrem /yr)
Osv= the skin dose rate at the SITE BOUNDARY due 8 to noble gases from release source v. (mrem /yr)
- Reference 4, Section 2.3.5.2. 8 i Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-4 01/93
l Lj = the skin dose factor due to beta emissions 8 from noble gas radionuclide i from Table 2.2 (mrem /yr per pC1/m3) 1.1 = conversion factor of mrem skin dose per mrad air dose. M1= air dose factor due to gamma emissions from 8 noble gas radionuclide i from Table 2.2 (mrad /yr per pC1/m3) All other terms are as previously defined. C. Release Rate 8 Qj is defined as the total release rate (pCi/sec) of 8 1 radionuclide i from all release sources. Qj is given by: l Q= IQjy 4 y
= I X9,F, [Eq. 2-3] 8 v
L C. Where: X,= 1 the measured concentration of radionuclide 8 1 present in each release source y j (pC1/cm3) l Fy = the flow rate from each release source v 8
/
(cm3sec) Qjy = the release rate of radionuclide i from 8 releasesourcev(pC1/sec) y = index over all release sources 8 2.1.2 Dose Rates Due to Radiciodines. Tritium. and Particulates 8 Organ dose rates due to iodine-131 and iodine-133, 8 tritium, and all radioactive materials in particulate form with half-lives greater than eight days released from the { site will be calculated to implement the requirements of Radiological Effluent Control 3/4.11.2.1.b as follows: D=1 o Day = I (X/Q) I P; Q 1 Y v IP&T IE'2~4l 9 Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-5 0UM
- Where
- Do
= the total organ dose rate due to iodine-131, iodire-133, particulates with 8
- half-lives greater than eight days, and f tritium from all reisase sources. i
{ (mrem /yr.) { Day = the organ dose rate due to iodine-131, 8 { iodine-133, particulates with half-lives l greater than eight days, t,nd tritium from l ) release source v (mrem /yr) l Pi = pathway dose rate parameter factor for 8 p radionuclide,i,(forradioiodines, l particulates, and tritium) for the , inhalation pathway in mrem /yr pet uCi/m3 i (Table 2.3). The methodology used for { determining values of Pi is given it:
- Appendix A.
) IP&T = iodine-131,' iodine-133, particulates with l half-lives greater than eight days, and tritium. These are the isotopes over whici: 8 }[ i the summation function is to be performed. } i All other variable are previously defined. I 2.2 GASEQUS EFFLUENT MONITOR SETPOINTS 8 The gaseous monitor _setpoint values, as determined using the 8 methodology in the following sections, will be regarded as upper bounds for the actual setpoint adjustments. Setpoints may be established at values lower than the calculated values if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a , value that falls within the normal operating range of the monitor. If a calculated setpoint is less than the measured concentration 8 associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated. Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-6 01/93
2.2.1 Plant Vent Effluent Release Rate Monitors 8 XRE-5570A and XRE-55708 Effluent Release Rate Chanhals The WRGM effluent release rate channels monitor the release rate 8 of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble gas activity channel 3 (uC1/cm ) indication and a stack flow rate (cm3 /sec) indication (X-FT-5570A-1/B-1) to yield an effluent release rate (uC1/sec). By establishing an alarm setpoint for this monitor, an increase in either the noble gas activity or stack flow rate will cause an alarm trip. The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases. The setpoint for each plant vent effluent release rate monitor will be calculated using the following methodology: Osm - the lessor of: 0 , 500 x sr = 125 b [Eq. 2.5] 0, 0, OR 0, y sr = 750 [Eq. 2.6] Where: Om, - Total site noble gas release rate limit 12 corresponding to a dose rate at or beyond the SITE BOUNDARY of 500 mrem /yr to the total body or 3000 mrem /yr to the skin. (uC1/sec) I
- 0. - (noble gases) 0, 8 Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1. Table 4.11-2.
500 - Dose rate limit to the total body of an 12 individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) COMANCHE PEAK - UNITS 1 AND 2 PART II 2-7 Rev. 12 12/95
r 3000 - Dose rate _ limit to the skin of the body of an 12 individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) i SF - Safety Factor of 0.5 applied to compensate for 8 statistical fluctuations, errors of measurement. and non-uniform distribution of release activity between the stacks (unitless) i Then the release rate setpoint for each stack monitor. C,. in i uC1/sec is determined o:; f Flows: 8 C, - 0,,,, AF [Eq. 2-7]
]
I Where: AF - Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitiess). This factor will limit the release rate contribution from each stack to 1/2 the limit for the site. 2.2.2 Plant Vent, Stack Noble Gas Activity Monitors XRE-56/0A/XRE-5570B (WRGM low rance noble oas activity channel) l and XRE-5567A/XRE-5567B (PIG noble cas channel) The WRGM low range noble gas activity channels provide noble gas I concentration data to the effluent release rate channels, as discussed in Section 2.2.1 above. The monitor design does not include an alarm setpoint for this channel that provides an audible alarm if the setpoint is exceeded. Inerefore, setpoint adjustments are not performed for these channels. Radiological I Effluent Control 3/4.3.3.5. Table 3.3-8. ACTION 36 allows for use of the stack PIG noble gas monitors (XRE-5567A and XRE-5567B) as a backup for an inoperable WRGM effluent l l l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-8 Rev. 12 12/95
release rate channel wh n no automatic control function is 8 required. The alarm setpoint for thIse channels, Cs in uC1/cm3, is determined using the following methodology: Cf (Eq. 2-8] 8 i j " CG FPVS Where: Fpys = the maximum stack flow rate 8 (cc/sec) corresponding to 115,000 i i cfm during normal operations and 130,000 cfm during containment purges. 1 2.2.3 Sa=nler Flow Rate Monitors (X-RFT-5570A-1/B-11 8 } j The WRGMs are designed to sample isokinetically from the } plant vent stacks. Isokinetic sample flow is maintained 1 8 automatically by the monitor microprocessor. The sampler flow rate monitors are designed such that if there is a )! .,. loss of sample flow, the stack monitor automatic control functions are initiated. The loss of sample flow alarm i setpoints are established permanently in accordance with vendor specifications. 2.2.4 Auxiliary Buildino Ventilation Exhaust Monitor (XRE-57011 8 i s Radiological Effluent Control 3/4.3.3.5 Table 3.3-8, 8 i ACTION 34, allows for the Auxiliary Building Ventilation
- (A8V) Duct Monitor (XRE-5701) to be used as a backup for j an inoperble WRGM for monitoring Waste Gas Decay Tank i (WGDT) releases. XRE-5701 monitors WGOT releases by i
measuring activity in the Auxiliary Building Vent Duct and < providing an automatic control function for termination of j WGDT releases. If required, the alarm setpoint for XRE-5701 will be calculated using the following methodology. The alarm setpoint calculation is based on the following assumption: (1) a waste gas decay tank release is the gnh batch 8 release occurring (i.e., a containment purge or vent is not occurring at the same time). Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-9 O
Based on assumption (1) above, there are a maximum of 8 three release sources that may contribute to the total release rate from the site during a WGOT release. There are the WGOT batch release, the continuous release from Stack A, and the continuous release from Stack 8. Therefore, a release factor of 1/3 will be used for the ABV monitor setro!nt determination. The total release rate from the stte at the alarm setpoint release rate from each stack would correspond to a value of 2Cr uC1/sec. To determine the A8V monitor setpoint, the release rate contribution from the A8V will be limited to 1/3 of the limiting site release rate: O aux = 1/3 2Cf= 2/3 C f [Eq.2-9] Where: Qaux = The limiting release rate 8 contribution from the Auxiliary L Building Vent during WGDT releases l ,, (uC1/sec) Other terms have been previously defined. 8 To determine the setpoint, Caux, for the A8V monitor in uC1/cc, the limiting A8V release rate is divided by the 8 maximum A8V flow rate: 2C C,yx= [Q =h , [Eq.2-10] aux aux Where: Faux = the maximus A8V flow rate (cc/sec) 8 corresponding to 106,400 cfs.
.5 Containment Atmonohere Ganeous Monitors (1RE-5503 and 5 2RE-5503) 8 i
For implementation of Technical Specification 3/4.3.3.1, 8 the alarm setpoint for the Containment Atmosphere Gaseous Monitor for Containment Ventilation Isolation will be
- calculated using the following methodology. The alarm ,
setpoint calculation is based on the following assumption: Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-10 01/93
(1) a purge or vent from each containment may occur 8 simultaneously and no other batch release is occuring (i.e., a waste gas decay tank release is not occurring at the same time as a containment release). Based on assumption (1) above, there are a maximum of 8 four release sources that may contribute to the total release rate from the site during a containment release. These are a Unit 1 Containment release, a Unit 2 Containment release the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/4 will be used for the the containment monitor setpoint determinatioc. The total release rate from the site at the alarm setpoint release rate from each j stack would correspond to a value of 2Cr uC1/sec. To determine the containment monitor setpoint, the release rate contribution from a containment release will be limited to 1/4 of the limiting site release rate: oco ,t={ 2Cf=jC f [Eq.2-11] j Where: Qcont = the limiting release rate 8 contribution from a containment release (uC1/sec) Other terms have been previously defined. 8 i To determine the setpoint, Ccont, for the containment 8 monitor in uC1/cc, the limiting containment release rate is divided by the maximum containment release flow rate: Q C cont , f [Eq.2-12) Cg=p cont cont , Where: Fcont = the maximum containment release 8 l flow rate (cc/sec) corresponding to j 750 cfm for containment vents and l 30,000 cfm for containment purges. Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-11 01/93
l8 l 2.3 DOSE CALCULATIONS FOR GASEQUS EFFLUENTS 8 l l l The methodologies for calculating doses from gaseous effluents 8 i are given in Sections 2.3.1 and 2.3.2 below. For purposes of ' demonstrating compliance with the dose limits of Radiological l Effluent Controls 3.11.2.2 and 3.11.2.3, the calculated ; cumulative doses (i.e., the total dose for both units) will be l compared to two times the dose limits for a unit. In other l words, the doses assigned to each unit will be one-half the total doses from all releases from the site. : ! 2.3.1 Cose Due to Noble Gases 8 For implementation of Radiological Effluent Control 0 3/4.11.2.2, the cumulative air dose due to noble gases j to areas at and beyond the SITE BOUNDARY will be - i calculated at least once per 31 days and a cumulative sumation of the air doses will be maintained for each i calendar quarter and each calendar year. The air dose ; over the desired time period will be calculated as follows: l A. Air Dose Due to ca- Emissions 8 Dy = air dose due to gamma emissions from noble gas 8 i radionuclides from all release ' sources (arad) i l Dy = 3.17 x 10-8 [yg) (noble gases) M 8 i O'i [Eq.2-13] l Where: 3.17 x 10-8 = the fraction of a year represented 8 l by one econd Q'1 = the cumulative release of radionuclide i during 8 the period of interest from all release sources (uC1) (Q'i = Qj (uC1/sec) x release duration (sec)) 8 l Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-12 01/93
0', is based on the noble gas activities in each plant eent stack 8 and WGDT or Containment Samples required by Radiological Effluent Control 3/4.11.2.1. Table 4.11-2. All other variables are previously defined. B. Air Dose Due to Beta Emissions 8 D, - Air dose due to beta emissions from noble gas radionuclides. (mrad) 0, = 3.17 it 10 (7IO) N, O', [Eq . 2 -14 ) Where: N, - Air dose factor due to beta emissions from noble gas radionuclide i from Table 2.2. (mrad /yr per uC1/m'). All other variables are previously defined. NOTE: If the methodology in this section is used in 12 determining dose to an individual rather than air dose due to noble gases, substitute K, for M,, (L, + 1.1 M,) for N,, and the Annual Average X/0 values from information listed and maintained current in the results of the annual Land Use Census f'or the highest annual average relative concentration (X/09 at the SITE B0UNDARY. l 2.3.2 Dose Due to Radiciodines Tritium. and Particulates 8 For implementation of Radiological Effluent Control 3/4.11.2.3. the cumulative dose to each organ of an individual due to iodine-131. iodine-133. tritium, and particulates with half-lives greater than 8 days will be calculated at least once per 31 days I and a cumulative sunination of these doses will be maintained for j each calendar quarter and each calendar year. The dose over the ! desired period will be calculated as follows: Dp - E 3.17 x 10.s W' E R' i a.o 1 0' , [Eq.2-15] paths I&PT COMANCHE PEAK - UNITS 1 AND 2 PART II 2-13 Rev. 12 12/95
there: 0, - Dose due to all real pathtays to organ, o. of an 8 individual in age group, a. from iodine-131, iodine-133. tritium, and radionuclides in particulate
- form with half-lives greater than eight days from all release sources (mrem).
W' - Dispersion parameter for estimating the dose to an individual at the location where the combination of ! existing pathways and receptor age groups indicates l the maximum potential exposures. Locations of 12 l interest are listed in the results of the annual Land Use Census. W' - X/0 for the inhalation pathway in sec/m 3 X/0 is the 8 annual average relative concentration at the location of interest. Values for X/Q are listed in the 12 results of the annual Land Use Census. If desired. 8 the highest individual receptor X/0 or X/0 value may I be used, or W' - D/Q for the food and ground plane pathways in m *2 l D/0 is the annual average deposition at the location of interest. Values for D/0 are listed in the 12 l results of the annual Land Use Census. If desired, the highest individual receptor D/0 or D/0 value may 8 be used. l NOTE: For tritium, the dispersion parameter. W' is taken as 12 l the annual average X/Q values from information listed and maintained current in the results of the annual Land Use Census for inhalation, food and ground plane pathways. R', , , , , - Dose factor for radionuclide 1. pathway p, age group 8 a and organ o, in mrem /yr per uC1/m 3 for the inhalation pathway and m2 (mrem /yr) per uCi/sec for food and ground plane pathways, except for tritium which is in mrem /yr per uC1/m 3 for all pathways. The values for RP,..., for each pathway radionuclide, age group and organ are listed in Table 2.4. i l l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-14 Rev. 12 , ( 12/95 !
f 1 The methodioogies used for determining values of 8 R', u for each pathway are given in Appendices B j through F O',- Cumulative release of radionuclide.1. during the period of interest (uC1). Q', is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1. Table 4.11-2. I&PT - Iodines, particulates with half-lives greater than eight days, and tritium. These are the isotopes l over which the summation function is to be performed. l PATHS - The real pathways of exposure to individuals at 12 the locations of interest. l 2.4 DOSE PROJECTIONS FOR GASEOUS EFFLUENTS 8 Radiological Effluent Control 3/4.11.2.4 requires that appropriate portions of 12 the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent from a unit to areas at or beyond the SITE BOUNDARY would exceed, in a 31-day period, either: 0.2 mrad to air from gamma radiation; or 8 0.4 mead to air from beta radiation: or : 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. , The following calculational method is provided for performing this dose projection: At least once every 31 days the gamma air dose, teta air dose and the maximum organ dose for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also, this dose ' projection may i COMANCHE PEAK - UNITS 1 AND 2 PART II 2-15 Rev. 12 12/95
include the estimated dose dug 90 any anticipated unusual releases during the period for which the projection is made, such as Waste Gas 8 Decay Tank release. If the projected doses for a unit exceed any of the values listed above, appropriate portions of the PRIMARY PLANT l VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be used to reduce radioactivity levels prior to release, 8 2.5 DOSE CALCULATIONS TO SUPPORT OTHER REOUIREMENTS ' For the purpose of implementing the requirements of Radiological 10 Effluent Control 6.9.1.4, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to radioactive 10 liquid and gaseous effluents from the station during the previous year 8 of operation. This a:sessment shall be a summary of the doses determined in accordance with Section 1.3 for doses due to liquid i effluents, Section 2.3.1 for air doses due to noble gases, and Section l 2.3.2 for doses due to iodines, tritium, and particulates. This same I report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE SOUNDARY. This assessment shall be 8 performed in accordance with the methodologies in Sections 1.3, 2.3.1, and 2.3.2, using either historical average or concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors. All assumptions and factors used in the determination shall be included in the report. For the purpose of implementing Radiological Effluent Control 3/4.12.2 dose calculations for the new locations identified in the land use 8 census shall be performed using the methodology in Section 2.3.2, substituting the appropriate pathway receptor dose factors and dispersion parameters for the location (s) of interest. Annual average dispersion parameters may be used for these calculations. If the land usecensuschanges,thecriticallocation(i.e.,thelocationwherean individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest milk animal, and the nearest 4 i COMANCHE PEAK - UNITS 1 AND 2 PART II 2-16 Rev. 10 l 4/94 ) -
vegetable garden. Additionally, when a location is identified that l t yields a calculated dose 20% greater than at a location where ' p environmental samples are currently being obtained, add the new location within 30 days to the Radiological Environmental Monitoring locations described in Section 3.1 of this manual. For the purpose of implementing Radiological Effluent Control 3/4.11.4, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by summing the annual doses determined for a member of the 8 public in accordance with the methodology of Sections 1.3, 2.3.1, and 2.3.2 and the direct radiation dose contributions from the units and from outside storage tanks to the particular member of the public. This assessment must be performed in the evet calculated doses from the effluent releases exceed twice the limits of Controls 3/4.11.1.2, 3/4.11.2.2, or 3/4.11.2.3. This assessment will be included in the I 10 Annual Radioactive Effluent Release Report to be submitted the year, after the assessment was required. Otherwise, no assessments are required. For the evaluation of doses to real individuals from liquid releases, 8 the same calculation methods as employed in Section 1.3 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides. The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentrations. For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed in Sections 8 2.3.1 and 2.3.2 will be used. In Section 2.3.1, the total body dose factor should be substituted for the gamma air dose factor (Mj ) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning i the actual location of real individuals, the meteorological conditions, and the consumption of food. Data obtained from the latest land use l , census should be used to l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-17 Rev. 10 4/94
determine locations for evaluating doses. The results of the 8 Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations. The dose component due to direct rr.diation may be determined by 8 calculation or actual measurement (e.g., thermoluminescent dosimeters, micro-R meter, etc.). The calculation or actual l measurement of direct radiation shall be documented in the Special Report that must be submitted if this determination is required. l 2.6 METEOROLOGICAL MODEL 8 l l 2.6.1 Disnersion Calculations 8 l Atmospheric dispersion for gaseous releases is calculated 8 using a straight line flow Gaussian model similar to the Constant Mean Wind Direction model given in Regulatory Guide 1.111, Section C.I.c. The method given here is l modified by including factors to account for plume depletion and effects of the open terrain. The average relative concentration is given by the following equation: i X f n 3g ), g=2.0326K [Eq.2-16] N rgI i l Where: X/Q = average concentration normalized by source 8 ( strength (sec/m3). 2.032 = (2/ w )1/2 . (2 w /16)-1 8 6 = plume depletion factor at distance r for 8 the applicable stability class (Figure 2.2). Normally, a value of 1.0 is assumed , when undepleted X/Q values are to be used i - in dose calculations. Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-18 01/93
K = terraincorrectionfactor(Figure 2.5) 8 njk = the number of hours meteorological conditions are observed to be in a given wind direction, wind speed class, k, and atmospheric stability class, j. N = total hours of valid meteorological data l throughout the period of release. j NOTE: If hourly meteorological data are used, all variable 8 subscripts are dropped, njk and N are set equal to 1, } and the hourly averaged meteorological variables are used i in the model. r = downwind distance from the release point to 8 thelocationofinterest(meters)
- ujk = theaveragewindspeed(midpointof 8 l windspeed class, k) measured at the 10
! meter level during stability class j. i
.- (meters /sec) j Ej(r) = the vertical plume spread with a volumetric 8 1
correction for a release within'the f building wake cavity, at a distance, r, for stability class, j, expressed in meters. ? f NOTE: All parameters are considered dimensionless unless 8
- otherwise indicated. '
i The equation for calculating Ej(r) is: 8 1 j '(aj + 0.5 b 27 ,)1 [Eq.2-17] j I (r) 3
= the lesser of /
\
l l
/Ta j [Eq.2-18]
Where: } aj = the vertical standard deviation of 8 j materials in the plume at distance, r, for j atmospheric stability class, j, p~ pressed in meters (Figure 2.3) { i Rev 8 4 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-19 01/93
l 0.5 = the building shape factor. 8 ) 2 b = the vertical height of the reactor 8 containment structure (79.4 meters) I i 1 2.6.2 Denosition Calculations 8 1 l l The relative deposition per unit area is calculated as follows: 8 i D KD* 9 q"0.3927r [Eq. 2-19] Where: D/Q = deposition per unit area normalized by 8 sourcestrength(m-2) j Dg = relative deposition rate for a ground level 8 release (m-1)(Figure 2.4) z = the fraction of time the wind blows to the 8 sector of interest. NOTE: If hourly meteorological data are u_. 4 z is set equal to 8 one. 0.3927 = the width in radians of a 22.50 sector. 8 l Other variables are as previously defined. 8 ; i NOTE: All parameters are considered dimensionless unless 8 otherwise indicated. Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-20 01M
1 2.7 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS 8 M Definition AF Allocation Factor of 0.5 applied to account for releases 8 from both stacks simultaneously. This factor will limit the release rate contribution from each stack to 1/2 the limit for the site 8 vertical height of the reactor containment structure C G the alarm setpoint for each plant vent stack noble gas 8 activitymonitor(uC1/cm3) Cr the alarm setpoint for each plant vent stack effluent releaseratemonitor(uC1/sec) caux the Auxiliary Building Ventilation Exhaust monitor
,,. alarmsetpoint(uC1/cm3) ccont the Containment Atmosphere Gaseous monitor alarm setpoint 8 (uC1/cm3)
Dg relative deposition rate for a ground-level release (m-1) Do the total organ dose rate due to tritium, iodines, and 8 particulates with half-lives greater than eight days from all gaseous release sources (mrem /yr) Day the organ-dose rate due to tritium, iodines, and 8 particulates with half-lives greater than eight days from gaseous release source v (aftem/yr) Dp dose to any organ of an individual from radioiodines, 8 tritium and radionuclides in particulate form with half-lives greater than eight days from all release sources (mrem) Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-21 01/93
. _. . _ ~ _
Igrg Definition Ds Skin dose rate at the SITE B0VHDARY due to noble gases 8 from all release sources. (mrem /yr) Dsv Skin dose rate at the SITE BOUNDARY due to noble 8 gases from release source v. (mrem /yr) Dt Total body dose rate at the SITE BOUNDARY due to noble 8 gases from all release sources. (mrem /yr) l Ovt Total body dose rate at the SITE BOUNDARY due to 8 noble gases from release source v. (mrem /yr) Dg Air dose due to beta emissions from noble gases from all 8 release sources. (mrad) Dy Air dose due to gamma emissions from noble gases from all 8 release sources. (mrad) D/Q Annual average relative deposition at the location of l interest. (m-2) 8 Plume depletion factor at distance r for the appropriate stability class (radioiodines and particulates). 8 Fy Flow rate from each release source v. (cm3sec)
/ 8 Faux Maximum Auxiliary Building Ventilation flow rate 8 (cm3sec)correspondingto
/ 106,400 cfm.
Fcont Maximumcontainmentreleaseflowrate(cm3sec) / 8 corresponding to 750 cfm for containment vents and 30,000 l cfm for containment purges. Fpys Maximum stack flow rate (cc/sec) corresponding to 8
- 115,000 cfm during normal operations and 130,000 cfm during containment purges.
COMANCHE PEAK UNITS 1 AND 2 PART II 2-22 Rev. 8 ERRATA (6/93)
.. . . . . . . - . - - - .-_--~ -. -. - - .- .- - _ -. - - . _ - _ _ _ . _ . . .
Jagg, Definition K terrainrecirculationfactor(Unitiess) 8 Kj total body dose factor due to gasuna emissions from noble 8 gasradionuclide1(den /yrperuC1/m3) L1 skin dose factor due to beta emissions from noble gas 8 i radionuclide1(des /yrperuC1/m3) l Mi air dose factor due to gamma emissions from noble gas 8 radionuclide1(den /yrperuC1/m3) l Nj air dose factor due to beta emissions from noble gas 8 radionuclide 1 (den /yr per uC1/m3) l njk number of hours meteorological conditions are observed 8 to be in a given wind direction, wind speed class k, and atmospheric stability class j j N total hours of valid meteorological data 8 P1 pathway dose rate parameter for radionuclide 1, (other 8 thannoblegases)fortheinhalationpathway(des /yrper uC1/cm3) Qaux the limiting release rate contribution from the 8 l Auxiliary Building Vent during WGUT releases (uC1/sec) Qcont the limiting release rate contribution from a containment 8 release (uC1/sec) Qj total release rate of radionuclide i from all release 8 l sourcss(uC1/sec) I f I . Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-23 01/93
l Ig3 Definition 8 0,, Total release rate of radionuclide i from release source v. (uci/sec) 1 ( O', Cumulative release of radionuclide i during the period of interest from all release sources. (uC1) 1 0,. Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from analyses of samples taken in accordance with Control 3/4.11.2.1. Table 4.11-2. . Osm Total site noble gas release rate limit corresponding to a dose rate at 12 or beyond the SITE BOUNDARY of 500 mrem /yr to the total body or 3000 mrem /yr to the skin. (uC1/sec) R',.o Dose factor for radionuclide 1. pathway p. and age group a. and organ o 8 (mrem /yr per uC1/m ) 3 or(mr -mrem /yr per uCi/sec). I r . Distance from the point of release to the location of interest for 1 dispersion calculations. (meters) SF Safety Factor of 0.5 applied to compensate for statistical ! fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks. I,(r) Vertical plume spread with a volumetric correction for a release within the building wake cavity, at a distance, r. for stability class. J. l expressed in meters. 03 Vertical standard deviation of the plume concentration (in meters), at distance, r. for stability category j. G3 Wind speed (midpoint of windspeed class k) at ground level (m/sec) during atmosphere stability class j. I a COMANCHE PEAK - UNITS 1 AND 2 PART II 2-24 Rev. 12 12/95
Igm Definition 8 W' Dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum exposures. X/0 Annual average relative concentration at the location of interest. (sec/m3 ) II0 Highest annual average relative concentration at the SITE BOUNDARY. (sec/m3 ) (3.3 x 10-8 sec/m3 in the NNW sector) X,, Measured concentration of radionuclide i present in each release source
- v. (uC1/cma ), '
l z Fraction of time the wind blows to the sector of interest. 8 ! 1.1 Conversion factor of mrem skin dose per mrad air dose. l 500 Dose rate limit to the total body of an individual at or beyond the 12 SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) l 3000 Dose rate limit to the skin of the body of the individual at or beyond l the SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) l i l l l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-25 Rev. 12 12/95
n h TABLE 2.1 5 l8
SUMMARY
OF GASEOUS RELEASE PATHWAYS A l8
^ 1. RELEASES VIA THE PLANT VENT STACKS E l8 Z
RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfa) MCNITOR(S) 8 E C' Stack A Continuous 115.000 XitE-5570A/XRE-5567A 8 Stack 8 Continuous 115.000 XRE-55708/XRE-55678 8
^8 WGOT's Batch 20 XRE-0570A48/XRE-5701 8 U-1 Cont. Vent. Batch 750 1RE-StiO3 8 U-1 Cont. Purge Batch 30.000 1RE-5503 8 U-2 Cont. Vent. Batch 750 2RE-5503 8 U-2 Cont. Purge Batch 30.000 2RE-5503 8 5
0
- 2. RELEASES VIA THE ILRT VENT
, 8 7 $ RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfe) MONITOR (S) 8 ILRT Batch - -
8 g .< sw a b 3 4
--- -__._--_---____---__-.____--_-___-____--_-___--------___._____-___-a
TABLE 2.2 8 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- l Isotone T-Bodv***(K) B-Skin ***(L) Y-Air **(M) S-Air **(N)
Kr-83m 7.56E-02 --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E404 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03- 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E403 1
- Values taken from Reference 2, Table B-1 i
** mrad-n3 uCi-yr l ***
M uC1-yr 4 i Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-27 01/93
TABLE 2.3 PATHWAY DOSE RATE PARAMETER (Pi)*
- BASED ON THE INHA1ATION PATHWAY I FOR THE CHIl.D AGE GROUP j l ORGAN DOSE FACTORS f NUCLIDE l.....................................................................
l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H.3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 i 4 P-32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 l CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 i MN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04
; FE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03
- FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 I CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 i
Co.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI.6 3- :- 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 4.26E+04 1.13C+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 R3 86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00EM0 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU.103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04
....................................................s...........................
RU.106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 , AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE.127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE.129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I.131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I.133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03
................................................................................ 1 CS.137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 I BA.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND.147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 COMANCE PEAK - UMTS 1 APO 2 PART I 2-28 Rev 8 ,
01/93 l l
f l c l l TABLE 2.4 PATWAY DOSE FACTORS ACE GROUP: ALL PATWAY: GROUND PLANE l ORGAN DOSE FACTORS NUCLIDE l-------------------.- l T. BODY SKIN l H-3 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 CR-51 4.65E+06 5.50E+06 MN.54 1.39E+09 1.62E+09 FE.55 0.00E+00 0.00E+00 FE 59 2.73E+08 3.21E+08 Co-58 3.79E+08 4.44E+08 CO.60 2.15E+10 2.53E+10 NI-63 0.00E+00 0.00E+00
.- ZN.65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 SR.90 0.00E+00 0.00E+00 Y.91 1.07E+06 1.21E+06 ZR.95 2.45E+08 2.84E+08 NB.95 1.37E+08 1.61E+08 RU.103 1.08E+08 1.26E+08 RU.106 4.22E+08 5.06E+08 AG-110M 3.44E+09 4.01E+09
, TE-125N 1.55E+06 2.13E+06 TE-127N 9.17E+04 1.08E+05 TE-129N 1.98E+07 2.31E+07 I-131 1.72E+07 2.09E+07 l I-133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.00E+09 CS-136 1.51E+08 1.71E+08 CS.137 1.03E+10 1.20E+10 BA.140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR 143 0.00E+00 0.00E+00 ND.147 8.39E+06 1.01E+07 l t l Rev8 COMANCE PEAK - LNTS 1 AlO 2 01/93 PART I 2-29
TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS-COW-MI1K
] ORGAN DOSE FACTORS NUCLIDE l -------------------------------- ------------------- ---------------
l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 P.32 1.70E+10 1.06E+09 6.58E+08 0.00E+00 0.00E+00 0.00E+00 1.91E+09 1 CR-51 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN.54 ) 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 1 l FE.55 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 . 1
.............................................................................. 1
( FE-59 2.97E+0? 6.97E+07 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.32E+08 CO-58 0.00E+00 4.71E+06 1.05E+07 0.00E+00 0.00E+00 0.00E+00 9.54E+07 CO 60 0.00E+00 1.64EM 7 3.61E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 [ NI.63 6.72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 l ZN-65 .s.l.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 2.74E+09 RB-86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.10E+08 SR.89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00EMO 0.00E+00 2.32E-08
- SR.90 4.67E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E.09 l Y.91 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 bR-9h 9 kik bh h bhk bh h bkh bh b bbk bb b hkh bh b bbk bb 9 hhh bh NB.95 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 RU.103 1.02EM3 0.00E+00 4.38E+02 0.00E+00 3.88EM 3 0.00E+00 1.19E+05 1 ..............................................................................
l RU.106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.935+04 0.00E+00 1.32E+06 l AG.110M 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 TE.125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E47 0.00E+00 6.49E+07 , TE.127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.00E+00 1.53E+08 l TE-129M 6.01E+07 2.24E+07 9.51E+06 2.06EM7 2.51E+08 0.00E+00 3.02E+08 l I.131 2.965+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 1.12E+08 I-133 3.875+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 CS-134 5.64EM9 1.34E+10 1.10E+10 0.00E+00 4.34EM9 1.44E+09 2.35E+08 CS.136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 l CS-137 7.37E+09 1.01E+10 6.60E+09 0.00E+00 3.42EM9 1.14E+09 1.95E+08 ! BA.140 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07
- CE-141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 j ..............................................................................
CE-144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85EM4 0.00E+00 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 0.00E+00 3.65E+01 0.00E+00 6.90E+05 ND.147 9.40E+01 1.09E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5.22E+05 COMANCE PEAK . LNTS 1 APO 2 PART I 2-30 b8 01/93
i 1 ? l TABLE 2.4 i PATHWAY DOSE FACTORS 1 ] AGE GROUP: TEEN PATHWAY: GRASS. COW-MIIK
- l ORGAN DOSE FACTORS l NUCLIDE l------- ------ -------------- ---- - ----------------- -- - ---- -
! l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI ( .............................................................................. l H.3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 I P.32 3.15E+10 1.95E+09 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09' l CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 i MN.54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 l FE-55 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E+07 1 FE.59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 l Co.58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 Co.60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 l NI.63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00EM0 0.00E+00 1.33E+08 f ZN.65.:. 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 j R4 86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08
- - SR.89 2.68EM9 0 00E+00 7.67E+07 0.00E+00 0.00EMO 0.00E+00 3.19E+08 SR.90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09
! Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 1 l ZR.95 1.65E+03 5.21E+02 3.58E+02 0.00E40 7.65E4 2 0.00E+00 1.20E+06 - NB-95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 j RU.103 1.81EM 3 0.00EM0 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 4 1 .............................................................................. 1 i RU.106 3.76E+04 0.00E+00 4.73E+03 0.00EMO 7.24E+04 0.00E+00 1.80E+06 l l AG.110M 9.64E+07 9.12E+07 5.55EM7 0.00E+00 1. 74 EMS 0.00E+00 2.56E+10 I j TE.125N 3.01E+07 1.088+07 4.02EM6 8.40E+06 0.00E+00 0.00E+00 8.87E+07 i .............................................................................. l TE-127M 8.45E+07 3.00E+07 1.00E47 2.01E4 7 3.42E+08 0.00E+00 2.11E+08 l TE-129N 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 6.14E+08 , I.131 S.385+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 { .............................................................................. l I-133 7.04544 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06
- CS.134 9.83EM9 2.31E+10 1.07t+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 j CS-136 4.49E+08 1.77E+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 u ..............................................................................
I CS 137 1.34E+10 1.78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 j BA.140 4.87E+07 5.97E+04 3.14E+06 0.00E+00 2.02E+04 4.01E+04 7.51E+07 i CE-141 8.89E+03 5.94E+03 6.82E+02 0.00E+00 2.80E+03 0.00E+00 1.70E+07 j .............................................................................. I CE-144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 l PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 j ND.147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 l
- new a
; N N-M1M2 PART I 2-31 01/93 1
-- - . . _.~. . - . - . - - . - _ - . . . . - . - . .. - _
1 1 l 4 l l
! TABLE 2.4 i
f PATHWAY DOSE FACTORS ) j AGE GROUP: CHILD PATHWAY: GRASS. COW.MIIK
} ..............................................................................
l ORGAN DOSE FACTORS } NUCL1DE l- ---------------------------- ----- ---------- -------------------
- l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 4
i P.32 7.77E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 t
- CR-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 l
MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 FE.55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 FE.59 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08 C0-58 0.00E+00 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 Co.60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 NI.63 2.97E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 ZN.65.. 4.14E+09 1.10E+10 6.86E+09' O.00E+00 6.95E+09 0.00E+00 1.94E+09 RB.86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65E+08 SR.89 6.63E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.57E+08 SR.90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 Y.91 3.91E+04 0.00EMO 1.05E+03 0.00E+00 0.00E+00 0.00E+00 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21EM 3 0.00E+00 8.80E+05 NS-95 3.18E+05 1.24E+05 8.86E+04 0.00EM0 .1.16E45 0.00E+00 2.29E+08 RU-103 4.29E+03 0.00E+00 1.65E+03 0.00EMO 1.08E+04 0.00E+00 1.11E&O5 RU.106 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25 h05 0.00E+00 1.44E+06 AG.110M 2.09E+08 1.41E4 8 1.13 EMS 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE-125M 7.39E+07 2.00E47 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13EM7 TE-127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE.129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 I-131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 I.133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 CS.134 2.275+10 3.72E+10 7.85E+09 0.00EMO 1.15E+10 4.14E+09 2.01E+08 CS-136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 CS-137 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08 BA-140 1.18E+08 1.03E+05 6.86E+06 0.00E4 0 3.35E+04 6.14E+04 5.96E+07 CE 141 2.19E+04 1.09t+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 CE.144 1.63E+06 5.09E+05 8.67t+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR.143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND.147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98t+02 0.00E+00 5.71E+05 COMANCIE PEAK . UMTS 1 AfC 2 Rev 8 PART I 2-32 01/93
TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS. COW.MIIK j ORGAN DOSE FACTORS , NUCLIDE l........... ............ .......... ......... ....................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03. 2.38E+03 P.32 1.60E+11 9.42E+09 6.21E+09 0.00E+00 0.00I40 0.00E+00 2.17E+09 CR.51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN.54 0.00E+00 3.91E+07 8.85E+06 0.00EMO 8.65EM6 0.00E+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE.59 2.25E+08 3.93E+08 1.55E+08 0.00E+00 0.00E+00 1.16E+08 1.88E+08 Co.58 0.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.05E+07 Co.60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 NI.63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+08 ZN.65 o. 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 RB.86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR.89 1.26E+10 0.00E+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+03 SR.90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 l Y.91 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR.95 6.81E+03 1.66E+03 1.188+03 0.00E+00 1.795+03 0.00E+00 8.27E+05 NB.95 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 RU.103 8.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81E+04 0.00E+00 1.06E+05 1 RU.106 1.91E+05 0.00E+00 2.34E+04 0.00E+00 2. 25 EMS 0.00E+00 1.45E+06 I AG.110M 3.86E+08 2.82E+08 1.87E+08 0.00E+00 4.03 EMS 0.00E+00 1.46E+10 TE-125M 1.51E+04 5.05E+07 2.04EM7 5.08EM7 0.00E+00 0.00E+00 7.19E+07 l
.............................................................................. l TE.127M 4.22 EMS 1.40EM8 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 l TE.129N 5.585+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 '
I.131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.00E+00 1.15E+08 j I.133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.96E+06 CS.134 3.65E+10 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS-136 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 8.85E+07
.m............................................................................
CS.137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 ; ! BA.140 2.42E+08 2.42E+05 1.25EM 7 0.00E+00 5.75E+04 1.49E+05 5.94E+07 l CE.141 4.34E+04 2.65E+04 3.12E+03 0.00E+00 8.17EM3 0.00E+00 1.37E+07 j ..............................................................................
- CE.144 2.33E+06 9.53E+05 1.30E+05 0.00E40 3.85E+05 0.00E+00 1.34E+08 j PR.143 1.49E+03 5.56E+02 7.37t+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 ND.147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50EM2 0.00E+00 5.75E+05 COMANCE PEAK - LNTS 1 APO 2 Rev 8 PART I 2-33 01 93
-- -. -- -- - - - - - - =-
TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUF: ADULT PATHWAY: GRASS. COW. NEAT l ORGAN DOSE FACTORS nuCt.IDE l......................................-..-...............-........... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 P-32 4.63E+09 2.88E+08 1.79E+08 0.00E+00 0.00E+00 0.00E+00 5.21E+08 CR.51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 , MN.54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 l FE.55 2.93E+06 2.03E+08 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 i FE.59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 Co.58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 Co.60 0.00E+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 NI.63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 ZN.65 - 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 RB.86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.59E+07 SR.89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 SR 90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 Y.91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 I ZR.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 l NB.95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 l RU.103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU.106 2.80E+09 0.00E+00 3.54548 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG.110M 6.68E+06 6.185M6 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 ! TE.125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46EM9 0.00E+00 1.43E+09 l TE.127M 1.12E+09 3.99E+08 1.36E+04 2.85E+08 4.53E+09 0.00E+00 3.74E+09 l TE.129M 1.13E49 4.23EM8 1.795+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 I.131 1.085+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 I.133 3.688 01 6.41E.01 1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 C5 134 6.58E+08 1.57t+09 1.28E+09 0.00E+00 5.07E+04 1.68t+08 2.74E+07 CS.136 1.21E+07 4.78E+07 3.46E+07 0.00E+00 2.66E+07 3.65E+06 5.43E+06 CS.137 8.72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07 BA.140 2.90E+07 3.64E+04 1.90E+06 0.00E+00 1.24E+04 2.08E+04 5.96E+07 l CE-141 1.41E+04 9.51E+03 1.088+03 0.00E+00 4.42E+03 0.00E+00 3.64E+07 l CE.144 1.46E+06 6.10E+05 7.83E+04 0.00E+00 3.62E+05 0.00E+00 4.93E+08 l PR.143 2.09E+04 8.40E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 ND.147 7.08E+03 8.18E+03 4.90E+02 0.00E+00 4.78E+03 0.00E+00 3.93E+07 COMANCHE PEAK - UMTS 1 AfC 2 PART I 2-34 01/93 l
. __ _ _ _ _ . _ ,_ _ ~ . _ . _ _ - . _ . . _ . _ . _ _ TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUF: TEEN PATHWAY: CRASS. COW. MEAT l ORGAN NUGLIDE l..........-........................DO W FACTORS .................................. l BONE LIVER T. BODY THYROID KIDNEY LU GI-LLI
.................................................................NG H.3 .............
0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 P.32 3.91E+09 2.42E+08 1.52E+08 0.00E+00 0.00E+00 0.00 3.29E+08
...............................................................E+00 CR.51 ...............
MN.54 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 FE.55 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08
.................................................................... 7.31E+07 FE.59 .........
Co.58 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56E+08 1.?7E+09 CO.60 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+08 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+0 7.60E+08
................................................................. 0 NI 63 ............
ZN.65 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E40 0.00E+00 1.71E+08 2.50E+06 8.68t+08 4.05E+08 0.00E+00 5. 56E48 0.00E+00 3.68E+08 RB.86*~ 0.00E+00 4.06E+08 1.91E+08 0.00EM0 0.00E+00 0.00E+00
.................................................................... 6.00E+07 SR.89 SR.90 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 Y.91 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.?.6E+08 9.54E+05 0.00E+00 2.568+04 0.00E+00 0.00E+00 0.00E+00
.................................................................... 3.91E+08 ZR.95 NB.95 1.50E+06 4.73E+05 3.2554 5 0.00E+00 6.95E+05 0.00E+00 1.09E+09 RU.103 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 ;
8.56EM7 0.00E+00 3.66E+07 0.00E+00 3.02 EMS 0.00E+00 '
.................................................................... 7.15E+09 RU.106 2.36549 0.00E+00 2.97E+08 0.00EM0 4.54E+09 0.00E+00 1.13E+11 AG.110N 5.06EM6 4.78E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 !
TE.125N 3.03E+08 1.098+08 4.05E+07 8.46E+07 0.008+00 0.00r.+00 8.94E+
.......................................................................... 08 ...
TE.127N 9.41E+08 3.34E+08 1.12E+04 2.24E48 3.81E+09 0.00E+00 2.35E+09 TE.129N 1 131 9.495M8 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 8.93E+04 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 I I.133 3.085 01 5.22E.01 1.59E.01 7.29E+01 9.16E-01 0.00E+00 3.95E.01 CS.134 5.23848 1.23EM9 5. 71E48 0.00E+00 3.91E+08 1.49E+08 1.53E+07 C5 136 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 CS.137 7.24E408 9.63EM8 3.35 EMS 0.00E+00 3.28E+08 1.27E+08 1.37E+07 BA.140 2.39EM 7 2.93E+04 1.54EM6 0.00E+00 9.94E43 1.97E+04 3.69E+07 CE.141 1.185+04 7.87E+03 9.05E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 l CE.144 1.23EM6 5.088+05 6.60E+04 0.00E+00 3.03 EMS 0.00E+00 3.09E+08 FR.143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 ND.147 { 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 i N PEAK . M 1 AW 2 Rw 8 PART I 2-35 01/93
.i 1 i i l! TABLE 2.4 i PATHWAY DOSE FACTORS a t { ACE GROUP: CHILD PATHWAY: GRASS.C0W-MEAT l ORGAN DOSE FACTORS ! NUCLIDE l...--- -------------- --------.-------------------- --------------- i LIVER l BONE T. BODY THYROID KIDNEY LUNG GI-LLI H.3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 P.32 7.38E+09 3.45E+08 2.85E+08 0.00E+00 0.00E+00 0.00E+00 2.04E+08 CR.51 0.00E+00 0.00E+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN.54 0.00E+00 8.01E+06 2.13E+06 0.00EMO 2.25E+06 0.00E+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 FE.59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 Co.58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 CO.60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI.63 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08 ZN.65 - 3.76E+08 1.00E+09 6.22E+08 0.00E+00 6.31E+08 0.00E+00 1.76E+08 R3 86 0.00E40 5.76E+08 3.54E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07 SR.89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR-90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 Y.91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR 95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 NB.95 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 RU.103 1.55E+08 0.00E+00 5.96E+07 0.00!!+00 3.90EM8 0.00E+00 4.01E+09 RU.106 4.44E+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00E+00 6.91E+10 AG.110N 8.39E+06 5.67EM6 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 TE.125M 5.69E+08 1.54E+08 7.59E+07 1.60E48 0.00E+00 0.00E+00 5.49E+08 TE-127M 1.78E+09 4.78E48 2.11E+08 4.25E48 5.06E+09 0.00E+00 1.44E+09 TE-129N 1.795+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 I-131 1.66EM7 1.67E+07 9.48t+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06 I.133 S.728 01 7.08E.01 2.68I.01 1.31E+02 1.18t+00 0.00E+00 2.85E.01 CS-134 9.23E48 1.51E+09 3.19E48 0.00E+0m 4.69E+08 1.68E+08 8.16E+06 CS.136 1.63E+07 4.48E47 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.57E+06 CS 137 1.33E+09 1.28EM9 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 BA 140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E44 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE.144 2.32E46 7.26E+05 1.24 EMS 0.00E+00 4.02E+05 0.00E+00 1.89E+08 PR.143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42EM3 0.00E+00 3.60E+07 ND 147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 8 COMANCif PEAK . LNTS 1 APO 2 PART I 2-36 01/g3
TABLE 2.4 PATHWAY DOSE FACTORS l AGE GROUP: INFANT PATHWAY: GRASS-COW. MEAT l l ORGAN DOSE FACTORS l NUCLIDE l-----..-.--------.---------- -----...--.---.-...--.-. ---------..-.-- l BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI H.3 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E<C0 0.00E+00 0.00E+00 P 32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR.51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 , MN-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' FE.55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE.59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN. 6 5 . - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR.89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y.91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 kk$95 b bbkMb b bbkbb b bbkUb b$bbkMb b bbkUb b$bbkUb b$bbkUb NB.95 0.00E+00 0.00E+00 0.00E+00 0.00E40 0.00E+00 0.00E+00 0.00E+00 RU.103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 RU 106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ) AG.110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129K 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.133 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00EMO 0.00E+00 0.00E+00 CS.134 0.00540 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA.140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND.147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
.....eee....d...ee............e..ee..........e.e....e....e......e....e.....e..
Rev 8 COMANCE PEAK . UMTS 1 AND 2 PART I 2-37 01/93
4 i ) i i i i i 4 TABLE 2A PATHWAY DOSE TACTORS 1
- AGE GROUP: ADULT PATHWAY: CRASS-GOAT-MILK l ...............................................................................
l ORGAN DOSE TACTOR $ i NUCLIDE l--------------------------- ----------- -- ---- ------------------ - ! l BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI j 4 H.3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 4 P.32 2.05E+10 1.27E+09 7.92E+08 0.00E+00 0.00E+00 0.00E+00 2.30E+09 j
- CR.51 {
0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+0S ' l MN.54 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06
- FE.55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 1
l .............................................................................. FE 59 3.87E+05 9.09E+C5 3.48E+05 0.00E40 0.00E+00 2.54E+05 3.03E+06
- Co-58 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07
) Co.60 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E40 0.00E+00 3.70E+07 i
- NI.63 8.08E+08 5,60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 ZN.65.. 1.65EM8 5.24E+08 2.37EM8 0.00E+00 3.51E+08 0.00E+00 3.30E+08 l R8 86 0.00E+00 3.12E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07 l SR.89 3.05E+09 0.00E+00 8.76E+07 0.00E+00 0.00E+00 0.00E+0C 4.89E+08
- SR 90 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09
! Y.91 1.03E+03 0.00E+00 2.76E+01 0.00EM0 0.00E+00 0.00E+00 5.68E+05 l ZR 95 1.13E+02 3.63E+01 2.46E+01 0.00EM0 5.70E+01 0.00E+00 1.15E+05 l NE.95 9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07
- RU.103 1.22E+02 0.00E+00 5.27E+01 0.00E40 4.67E402 0.00E+00 1.43E+04 l RU-106 2.45EM3 0.00E+00 3.10EM 2 0.00E+00 4.73E+03 0.00E+00 1.59E+05 i AG-110N 6.99E+06 6.47E+06 3.84E+06 0.00F+~# 1. DM7 0.00E+00 2.64E+09 TE-125N 1.96E+06 7.09E+05 2.62E+05 5. 894M5 7.96E+00 0.00E+00 7.81E+06 TE-127M 5.50E+06 1.97EM6 6.70E45 1.41E+06 2.23E+07 0.00E+00 1.84E+07 i TE-129N 7.23E+06 2.70E+06 1.14EM6 2.48E+06 3.02E+07 0.00E+00 3.64E+07 l a
I.131 3.565+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.00E+00 1.34E+08 c .............................................................................. l I-133 4.65EM6 8.10E+06 2.47E+06 1.19EM9 1.41E+07 0.00E+00 7.28E+06 i j CS.134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08 l CS-136 7.92EM8 3.13E+09 2. 25EM9 0.00E+00 1.74E+09 2.38E+08 3.55E+08 l s .............................................................................. CS.137 2.22E+10 3.03E+10 1.99E+10 0.00EM0 1.03E+10 3.42E+09 5.87E+08
- R4-140 3.24E+06 4.07E+03 2.12E45 0.00E+00 1.3814 3 2.33E+03 6.67E+06 j CE-141 5.82E42 3.94E+02 4.47E+01 0.00E+00 1. 8'JE+02 0.00E+00 1.51E+06
! CE-144 4.30E+04 1.80E+04 2.31E+03 0.00E40 1.07E+04 0.00E+00 1.45E+07 i PR.143 1.90E+01 7.60E+00 9.40E.01 0.00E+00 4.39E+00 0.00E+00 8.30E+04 I ND.147 1.13E+01 1.31E+01 7.82E.01 0.00E+00 7.65E+00 0.00E+00 6.28E+C's 4
Rev 8 . COMANCE PEAK - LNTS 1 APO 2 01/93 a PART I 2-38 _ - - . - _ ~ - - . - . . -
.. - ._. - . - . - - - - - . . - . - . - - - . - . - . . - - - - - = - - - - _
1 i 4 i TABLE 2.4 , PATHWAY DOSE FACTORS 4 j AGE GROUP: TEEN
...................................... PATHWAY: CRASS. GOAT NIIK 1
4 l NucL10E I............................. ORGAN DOSE FACTORS l BONE LIVER T. BOD ........................................ THYROID KIDNEY LUNC i
....................................Y...................................GI.LLI H.3 .......
j P.32 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E ' 3.78E+10 2.34E+09 1.46t+09 j ...................................... 0.00E+00................................ CR 51 0.00E+00 0.00E+00 3.1 8E+09 4 MN.54 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E FE.55 0.00E+00 5.79E+05 4.11E+05 1.68E+06 3.34E+05 9.58E+04 0.0 0.00E+00 5.02E+05 9.00E i i ......................................... 0E+00................................. FE.59 0.00E+00 a 61E+05 1.78E+0 5 i i CO.58 Co.60 6.74E+05 0.00E+00 9.53E+05 1.57E+06 6.04E45 0.00E+00 0.00E+00 4.96E+0
~
2.20E+05. 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 i NI.63 0.00E+00 0.00E+00 4.35 0.00E+00..................................E ..... I j ZN.65 R8 86,. 1.42E+09 1.00E+04 4.81E+07 0.00E+00 0.00E+00 0.00E+ 2.53E+08 0.00E+00 5.67E+08 8.78E+08 4.10E+08 2.67E+08 0 0.00E+00 5.62E+04 0.00E+
........................................ 00E+00 0.00E+00 0.00E+00 8.40E+07 1
' SR.89 ..................................... SR.90 5.62E+09 0.00E+00 1.61Ed8 0.00E+00 0.00E+00 0.00E+00 Y.91 1.39E+11 1.90E+03 0.00E+00 0.00F.+005.09E+01 3.43E+10 0.00E+00 0.00E+00 0.00E+ j ...................................... 0.00E+00.................................. ZR.95 0.00E+00 0.00E+00 7.78E+0 5 NB.95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 RU.103 1.69E+04 2.17E+02 0.00E+00 9.38E+03 5.16E+03 9.29E+01 0 0.00E+00 9.09E+03 0.00E+00
........................................ 00E+00 RU.106 7.66E+02 0.00E+00 1.82E+04 4.50E+03 0.00E+00 5.685+02 0.00E+00 8.69E+03 0.00E+00 2 AG-110N TE.125N 3.61E+06 1.16E+071.30E+06 1.09E+07 4.82E+05 16.65E+06 0.00E+00 2.095+07 0.00
........................................01546 0.00E+00 0.00E+00 1.06E+07 TE.127N 1.01E+07 3.59E46 1.20E+06 2.41E+06 4.11E+07 0.00E+0 TE.129N 1 131 1.32E+07 6.45E+08 9.03E+08 4.90E+06 4.85E+042.09E+06 2.64 4.265+06 5.53E+07 0.00E+
...........................................E+11 I.133 1.56E+09 0.00E+00 1.79E+08 CS.134 8.495+06 1.44E+07 4.40E+06 2.015+09 2.53E+07 0.00E+00 1.09 CS.136 2.95E+10 1.35E+09 5.30E+09 6.93E+10 3.22E+10 3.56E+09 0.00 0.00E+00 2.20E+10 8.41E+09 8.62
...............r...........................E+00 CS.137 2.89E+09 4.55E+08 4.27E+08 BA.140 4.02E+10 5.34E+10 1.86t+10 0.00E+00 1.82E+10 7.07E+09 7.60E+0 CE.141 5.84E+06 7.16E4 3 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+0 1.07E+03 7.12E+02 8.188+01 0.00E+00 0.00E+00 2.04E+06
................................................ 3.35842 CE.144 .............................
FR.143 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 ND 147 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.088+00 0.00E+00 1.15E+05 2.18E+01 2.37E+01 1.42E+00 0.00E+00 0.00E+00 8.54E+04
.................................................1.39E+01 ...............------ . ---
Rev8 COMANCFE PEAK - LNTS 1 APO 2 PART I 2-39 #
1 e f i i TABLE 2.4 PAUfWAY DOSE FACT 0k.i AGE GROW: CHILD PATHWAY: GRASS. GOAT-MIIK l ORGAN DOSE FACTORS NUCLIDE l-.-------------.---------------------------.------------------------- l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 P 32 9.32E+10 4.36E+09 3.59E+09 0.00E+00 0.00E+00 0.00E+00 2.58E+09 CR.51 0.00E+00 0.00E+0/ 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 0.00E+00 2.52E+0- 6.71E+05 0.00E+00 7.06E+05 0.00E+00 2.11E+06 FE.55 1.45E+06 7.71E+0: 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 FZ.59 1.56E+06 2.53E+06 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.64E+06 CO.58 0.00E+00 1.46E+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.49E+06 Co.60 0.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07
.........................~.... .. ............................................
NI-63 3.56E+09 1.91E+0S 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 ZN.65a. 4.96E+08 1.32EM9 8.22 EMS 0.00E+00 8.33E+08 0.00E+00 2.32E+08 RB.86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 5k".59"'[$5hkhib"b$bbkIbb"5$9)iIbk'~b$bbk$bb"b$bbkhbb"b$bbkhbb"5$59 SR.90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Y.91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.24E+05 ZR.95 4.60E+02 1.01E+02 9.00EM1 0.00E+00 1.45E+02 0.00E+00 1.05E+05 NB.95 3.82E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU.103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 KU.106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG.110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.188+06 2.495+06 0.00E+00 0.00E+00 8.55E+06 TE.127M 2.50E+07 6.72E46 2.96E+06 5.97E+04 7.12E+07 0.00E+00 2.02E+07 TE.129M 3.26E+01 9.10E+06 5.06E+06 1.05I+07 9.56E+07 0.00E+00 3.97E+07 I.131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.00EM0 1.40E+08 I.133 2.06EW7 2.55E+07 9.66E+06 4.74E+09 4. 25E47 0.00E+00 1.03E+07 CS.134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+10 1.24E+10 6.01E+08 C5 136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6.64E+08 2.94E+08 CS.137 9.68E+10 9.26E+10 1.37t+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 CE.141 2.63E+03 1.31E+03 1.95E+02 0.00E+00 5.74E+02 0.00E+00 1.63E+06 CE 144 1.95E+05 6.11E+04 1.04E+04 0.00E+00 3.38544 0.00E+00 1.59E+07 PR.143 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Rev 8 l COMANCE PEAK . L.NTS 1 MO 2 PART I 2-40 01/93
.~s . _ . . . . . - s . . . . a. x ,n-a m ..nw.-na-.w- . m.-...su~-,~u._ + ~ . . ..~_nax...- . , _ . - - - - - - . . . . . . . _ . _ _ _ . . . .-, ..
i i 4 5 I ? I i TABLE 2.4 PATHUAY DOSE FACTORS a j AGE GROUP: INFANT PATHUAY: GRASS. COAT-MI1K l l ORGAN DOSE FACTORS NUCLIDE l......--------- -------- - -------------------------------.- --- --- l. l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI M.3 0.00E+00 4.86K+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 i i P-32 1.92E+11 1.13E+10 7.44E+09 0.00E+00 0.00E+00 0.00E+00 2.60E+09 CR.51 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN.54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06 j FE.55 1.76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 ! FE.59 2.92E+06 5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.44E+06 ! C0 58 0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO.60 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 2.52E+07 i NI.63 4.19E+09 2.59E+08 1.46E+08 0.00EMO 0.00E+00 0.00E+00 1.29E+07 l . ZN 65 . 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+GO 1.93E+09 l RB.86 . 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 5 SR.89 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08
- SR.90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09
- Y.91 8.80E+03 0.00E+00 2.34E42 0.00E+00 0.00E+00 0.00E+00 6.31E+05
) .............................................................................. ! Z1 95 8.17E+02 1.99E+02 1 Is1E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 NB 95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU.103 1.04E+03 0.00E+00 3.485+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 I RU.106 2.28E44 0.00E+00 2.85EM3 0.00E+00 2.70E+04 0.00E+00 1.73E+05
- AG.110M 4.63E+07 3.38547 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE-125N 1.81E+07 6.05E+06 2.45E+06 6.09EM6 0.00E+00 0.00E+00 8.62E+06 i TE.127N 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07
. TE-129N 6.69547 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 ; 1 I.131 3.27549 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 I j .............................................................................. i 1-133 4.36547 6.35E+07. 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 i CS.134 1.095+11 2.04E+11 2.06E+10 0.00E+00 5.26E+10 2.15E+10 5.55E+08 1 CS.136 5.94E+09 1.75E+10 6.52EM9 0.00E+00 6.96E+09 1.42E+09 2.65E+08 ! CS.137 1.54E+11 1.41E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 BA.140 2.90E47 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04 7.13E+06 l CE.141 5.21E+03 3.18E+03 3.74E4 2 0.00E+00 9.79E+02 0.00E+00 1.64E+06 i .............................................................................. j CE.144 2.79E+05 1.14E45 1.56EM4 0.00E+00 4.62E+04 0.00E40 1.60E+07 PR 143 1.78EM 2 6.66EMI 8.83E+00 0.00E+00 2.48E41 0.00E+00 9.40E+04 j ND.147 1.06t+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6.89E+04 3 i Rev 8 l COMANCSE PEAK - L.NTS 1 APO 2 01/93 4 PART I 2-41
. . . . . , . - - - , - , , -~ - - -nm~ ,
l TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: VEGETATION . l ORGAN DOSE FACTORS WUCLIDE l.........----------- ----------------------------- ------ ---------.- l BONE LIVER T. BODY THYROID KIDNEY LUNC GI-LLI H.3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 P-32 1.40E+09 8.69E+07 5.40E+07 0.00E+00 0.00E+00 0.00E+00 1.57E+08 l CR-51 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN.54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08
- FE.55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE.59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 CO-58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 Co.60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 NI.63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 ZN-65.. 3.17E+08 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 RB.86 0.00EM0 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 SR-89 9.98E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09
! SR.90 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Y.91 5.12EM6 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 i i ZR.95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09
- NB-95 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 RU.103 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 5.57E+08
! RU.106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 J AG.110K 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 ] TE 125M 9.66E+07 3.50E+07 1.29E+07 2.90547 3.93E+08 0.00E+00 3.86E+08 TE.127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42EM9 0.00E+00 1.17E+09 TE-129K 2.51E+08 9.37t+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 ) I.131 8.08EM7 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 ) 3 .............................................................................. I-133 2.095+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 , CS-134 4.675+09 1.11E+10 9.04E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08
- CS.136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 1.92E+07 y ..............................................................................
CS.137 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BA 140 1.27E+08 1.62E+05 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08
> CE.141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08 . CE 144 3.29E+07 1.38E+07 1.77EM6 0.00E+00 8.16E+06 0.00E+00 1.11E+10 PR 143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 < ND.147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Rev8 ; M-M1M2 PART I 2-42 01/93
1 1 l l l l TABLE 2.4 PATHWAY DOSE FACTORS ' ACE CROUP: TEEN PATHWAY: VEGETATION l ORG DOSE FACTORS NUCLIDE l.... ..........~.... .--......-.AN ................-....... ........... l BONE LIVER T. BODY THYROID
................................................... KIDNEY LUNG CI .LI.I H.3 ...........................
0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 P 32 1.60E+09 9.91E+07 6.20E+07 0.00E+00 0.00E+00 CR.51 0.00E+00 1.34E+08 MN.54 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 FE-55 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.00E+08 FE-59 1.47E+08
................... j Co.58 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+08 '
CO.60 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 3.24E+09 NI.63 0.00E+00 ZN.65 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 l RB.86 ~ 0.00E+00 2.73E+08 1.28E+08 0.00E+00 0.00E+00 4.04E+07
.......................................................... 0.00E+00 SR.89 ...................
SR.90 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 Y.91 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 3.22E+09
.......................................................... 0.00E+00 ZR.95 ...................
NB.95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 RU.103 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 5.70E+08
.......................................................... 0.00E+00 RU.106 ...................
3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97Et08 0.00E+00 1.48E+10 AG.110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE.125K 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0 4.37E+08
............................................................ 00E+00 .................
TE.127M 5.52E+08 1.96t+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE.129M I.131 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00 2.13E+07
...............................................................E+00 I.133 ...............
CS-134 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS-136 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48E+07
.................................................................... 1.39E+07 CS.137 BA.140 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 CE.141 1.39E+08 1.71E+05 8.97E+46 0.00E+00 5.78E+04 1.15E+05 2.15E+08 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 CE-144 PR.143 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 ND.147 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.a2E+08 Rev 8 COMANC$E PEAK . UP4TS 1 APO 2 PART I 2-43 N
1 i 1 1 TABLE 2.4 PATHWAY DOSE FACTORS I ) AGE CROUP: CHILD PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE l ------- -------- ------------------------------ ----------- ------- ' - l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H.3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 P.32 3.35E+09 1.57E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 9.25E+07 5 CR-51 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 i MN-54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 a FE-55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 CO-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08
- CO.60 0.00E&OO 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI.63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 2
ZN.64. 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 RB.86 0.00E+00 4.51E+08 2.77E+08 0.00E+00 0.00E+00 0.00E+00 2.90E+07 SR.89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR.90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y-91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 NS-95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 RU-103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 q RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 AG.110M 3.21E+07 2.17E+07 1.73E+07 0 00E+00 4.04E+07 0.00E+00 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08
.............................................................................. 1 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE-129M 8.40E+04 2.35E+08 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 I-131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 l 4 I-133 3.53E+06 4.37t+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS.134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 4
CS.136 ,8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.81E+07 8.00E+06 CS.137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 l BA-140 2.79E+08 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08 CE 144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 Rev 8 COMANCE PEAK - UMTS 1 APO 2 PART I 2 44 01/93 l
l 1 t I 1 l TABLE 2.4 PATHWAY DOSE FACTORS ACE GROUF: INFANT PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE I..................................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l H.3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P.32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR.51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN.54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE.55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE.59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO.58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 C0 60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l NI.63 0.00E+00 0.00E+00 0.00EM0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN.65.,. 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 hk$h9 b$bbkhbb b$bbk bb b bbk bb b$bbk bb b$bbk bb b$bbk bb bIbbk bb' SR.90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y.91 0.00E+00 0.00EMO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 21 95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N8 95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU.103 0.00E+00 0.00E+00 0.00EM0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU.106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AG.110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129M 0.00E+00 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 CS.137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA.140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR.143 0.00E+00 0.00EM0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND.147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rev8 COMANCE PEAK . UMTS 1 APO 2 PART I 2-45 . 01/93
l i i TABLE 2.4 j PATHWAY DOSE FACTORS i I AGE GROUF: ADULT PATHWAY: INHALATION l ! l ORGAN DOSE FACTORS y NUCLIDE l..--..------- ----- -------- --------- ----------- ------------- --.. l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI . H.3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 T , P 32 1.32E+06 7.71E+04 5.01E+04 0.N E+00 0.00E+00 0.00E+00 8.64E+04 CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 I MN-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 i 4 FE-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 ! i FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00EMO 1.02E+06 1.88E+05 . Co.58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 l Co.60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 l n ............................................................................... NI.63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E40 1.78E+05 1.34E+04 ZN.65 - 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 ! RB 86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 i SR 89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 I 4 SR.90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 j Y-91 4.62 EMS 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 1 ZR 95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 ! NS-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05
- RU-103 1.53EM3 0.00E+00 6.58EM 2 0.00E+00 5.83E+03 5.05E+05 1.10E+05 I RU.106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1. 34'E+05 9.36E+06 9.12E+05
) AG.110N 1.085+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 i TE 125N 3.42E+03 1.58E43 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 4 TE 127N 1.268+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 i TE-129N 9.76543 4.67E+03 1.58EM3 3.44E+03 3.66E+04 1.16E+06 3.83E+05 I-131 2.52E+04 3.58EM4 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I I.133 8.64E43 1.48E+04 4.52E+03 2.15E+06. 2.58E+04 0.00E+00 8.88E+03 4 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 j CS.136 3.90E+04 1.46EM S 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 1 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03
; EA.140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 j CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.265+03 3.62E+05 1.20E+05
}
! CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.44EM5 7.78E+06 8.16E+05 I PR-143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 '
i ............................................................................... g,; 3
- - - =2 -r , 2 4.
m __
_ . . _ _ _ _ _ __ _ _ _ _ ~ _ _ . _ . _ . -._ _ _ ____ _ _ _ _ - _ . _ _ _ _ TABLE 2.4 PATHUAY DOSE FACTORS AGE GROUP: TEEN PATHUAY: INHAIATION j ORGAN DOS NUCLIDE l...........- --.....-........ . . ... E FACTORS --........ ....-............... l BONE LIVER T BODY THYROID KIDNEY GI-LLI I ................................................................ LUNG H.3 ............... 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03
- P.32 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00 9.28E+04
................................................................E+00 CR.51 ...............
MN.54 0.00E+00 0.00E+00 1.35E+02 7.50E401 3.07E+01 2.10E+04 3.00E+03 FE.55 0.00E+00 5.11E+04 8.40E4 3 0.00E+00 1.27E+04 1.98E+06 6.68E+04 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+ 6.39E+03
................................................................. 05.............
FE 59 Co.58 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 Co.60 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72 2.59E+05
................................................................E+06 NI.63 ...............
ZN.65 5.80 EMS 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 RB . 56. - 3.86E+04 1.34545 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 0.00E+00 1.90E+05 8.40E+04 0.00540 0.00E+00 0.00E+00
..................................................................... 1.77E+04 l
SR.89 SR.90 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00540 2.42E+06 3.71E+05 Y.91 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.6iE+07 7.65E+05 6.61E+05 0.00E+00 1.77E44 0.00E+00 0.00E+00 2.94E+0 4.09E+05
.................................................................. 6 ZR.95 ............
NB.95 1.46E+05 4.58E+04 3.15EM4 0.00E+00 6.74E+04 2.69E+06 1.49E+05 RU.103 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43EM3 7.83E+05
..................................................................... 1.09E+05 RU.106 AG 110N 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 TE.125N 1.38E+04 1.31E+04 7.998+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 4.88EM3 2. 24E43 6.675+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE-127N TE-129N 1.80844 8.16543 2.18E+03 4.385+03 6.54E+04 1.66E+06 1.59E+05 1 131 1.395+04 4.58543 2.25E43 4.58E+03 5.19E+04 1.98E+06 4.05E+05 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133 CS.134 1.22E+04 2.05E+04 6.22EM 3 2.92E46 3.59E+04 0.00E+00 1.03E+04 CS.136 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS.137 R4 140 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 5.47E+04 6.70E+01 3.52E+03 0.00540 2.28E+01 2.03E+06 2.29E+05 CE.141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE.144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E47 8.64E+05
, PR.143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 i ND.147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 ; l ............................................................................... t
- n. .
COMANCFE PEAK - LNTS 1 APO 2 PART I 2-47
a i } } [ 1, TABLE 2.4 4 i PATHWAY DOSE FACTORS ! ACE GROUP: CHILD
....................................... PATHWAY: INHAIATION i
l ........................................ NUCLIDE l................-....-....... ORGAN DOSE FACTORS { l BONE LIVER T. . THYROID KIDNEY LUN CI-LLI J .................................. BODY.................................C H.3 ............ 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1 P 32 j 2.60E+06 1.14E+05 9.88 0.00E+00 0.00E+00 0.00E+0
..................................E+04................................ 0............
CR.51 4.22E+04 HN.54 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.7 i FE.55 0.00E+00 4.74E+04 4.29E+04 2.52E+04 7.77E+ 9.51E+03 0.00E+00 1.00E+04 1.5 i I ................................... FE.59 0.00E+00- 0.00E+00 1.11E+05 03................................. 2.87E+03 l CO.58 Co.60 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.2 ! 0.00E+00 0.00E+00 1.77E+03 1.31E+04 2.26E+043.16E+03 0.00E+00 0.00E+00 1.11 { ....................................... 0.00E+00................................ NI.63 0.00E+00 7.07E+06 9.6 2E+04 ZN 65 8.21E+05 4.63E+04 2.80E+04 0.00540 0.00E+00 2.75E i i R8 86 4.26E+04 0.00E+00 1.13E+05 1.98E+05 1.14E+0 7.03E+04 0.00E40 7.14E+04 9.95E ) ......n............................ 5.................................. SR.89 0.00E+00 0.00E+00 0.00E+00 7 99E+03 j SR.90 Y.91 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16 1.01E+08 9.14E+05 0.00E+00 0.00E+00 2.44E+ 6.44E+06 0.00E+00 0.00E+00 1.48
- ................................... 04.................................
ZR.95 0.00E+00 0.00E+00 2.63E+06 1.84E+05 j NB.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E 2.35E+04 9.18t+03 1.07E+6.55E+03 0.00E+00 8.62E+03 6.14E+ 4 RU.103 2.79E+03 0.00E+00
................................... 03...................................
RU.106 0.00E+00 7.03E+03 6.62E+05 4 48E+04 AC-110N 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1,84E+05 1.43E+07 4.29E+05 i TE.125M 1.69E+04 6.73E+03 1.14E+04 2.33E+03 9.14EM9.14EM 3 0.00140 2.12E+04 5.48E+0
.................................... 2.....................................E+04 TE.127N 1.92E+03 0.00E+00 4.77E+05 3.38 i
TE.129N 2.49344 8.55E+03 3.02EM3 6.07EM3 6.36E+04 1.48E+06 7.1 l I-131 1.92E+04 4.81E+04 6.85E+03 4.81E+04 3.04E+03 6.33E+03 5.03E+04 1.76E+06 2.73E+04 ! ! ....................................... 1.62h+07 I.133 7.88E+04 0.00E+00 2.84E+03 CS.134 1.665+04 2.03E+04 7.70EM3 3.85EM6 3.38E+04 0.00E+00 5. ! CS.136 6.51E+05 6.51E+04 1.71E+05 1.01E+06 2.25E+05 1.16E+05 0 0.00E+00 3.30E+05 1.21EM5 3j
.........................................00EMO C5 137 9.55E+04 1.45E+04 4.18E+03 i RA.140 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82EM5 1.04E+05 3.6
- CE.141 7.40E+04 3.92EM4 1.95E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.0 2.90E+03 l-
....................................... 0.00E+00 CE.144 4.55E+03 5.44E+05 5.66E+04 ! PR-143 6.77EM6 2.12EM6 3.61E+05 0.00E+00 1.17EM6 1.20E+07 3.89E+05 j ND-147 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+0 1.0$E+04 8.73E+03 6.81E+02 0.00 ! ............................................E+00 4.81E+03 3.28t+05 8.21E+04 4
- COMANCE PEAK . UMTS 1 Am 2 -
Rev 8 PART I 2 48 1 4 01/93
.-e _-
TABE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: IN
. . . . . . . . . . HAIAT I ON,,,
1 NUCLIDE ORGAN DOSE FACTORS l l............................. 80NE LIVER T. BODY THYRO
..............................................ID H.3 KIDNEY I.UNO GI.LLI 0.00$+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.4 P 32 i
2.03E+06 1.12E+05 7.74E+04 0.00E+00
................................................. 0.00E+00 CR.51 0.00E+00 1.61E+04 l
MN.54 0.00E+00 0.00E+00 8.95EM1 5.75E+01 1.32E+01 1.28E+04 3.57EI i FE.55 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.94E+03 1.00E+06 7.06E 1.97E+04 1.17t+04 3.33E+03 0.00E+00 0.00E+ FI.59 00 8.69E+04 1.09E+03 Co.58 1.36t+04 2.35E+04 9.44E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+0! Co.60 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77t+05 1.11E+04 i 0.00E+00 8.02EM3 1.18E+04 0.00E+00 0.00
.....................................................5M0 NI 63 4.51E+06 3.19E+04 ZN.65 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00EM0 2.09E+05 2.42E+
R5 86,, 0.00E+00 6.26h04 1.93h04 1.90 005 3.11904 0.005+00 3.25E+04 6.47 EMS 5.14h04
- 8. 82h04 0.00E+00 0.00 0.00E+00 3.04E+03
......................................................E+00 St.89 .........................
SR.90 3.98E+05 0.00 h00 1.14E+04 0.00E+00 0.00840 2.03EM6 6.40E+04 Y.91 4.09E+07 0.00E+00 2.598+06 0.005M0 0.00E+00 1.12E+07 1.31E+05 5.84 EMS 0.00E+00 1.575+04 0.00540 0.00E+00 7.03E+04
...........................................................2.45EM6 ZR.95 ...................
NB.95 1.15E+05 2.79EM4 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17 h04 RU.103 1.57t+04 6.43 h03 3.78h03 0.00E+00 4.72E+03 4.79E+05 1.27t+04 2.02EM3 0.00h00 6.79E+02 0.00540 4.24E+03 1.61E+04
...........................................................5.52h05 RU.106 ...................
AG.110N 8.685+04 0.00E+00 1.098+04 0.C90 1.07845 1.16E+47 1.64E+05 TE.125N 9.985+03 7.22E+03 5.00E+03 0.00E+00 1.095+04 3.67E+06 3.30E+04 4.76EM3 1.9954 3 6.58842 1.62E+03 0.008+00 4.47 1.29E+04
................................................................E+05 TE.127N TE.129N 1.67t+04 6.90EM3 2.07E+03 4.87EM3 3.75544 1.3th06 2.73E+04 1 131 1.41544 6.098+03 2.23EM3 5.47EM3 3.185+04 1.68t+06 6.90E+04 3.795+04 4.44E+04 1.96844 1.44EM7 5.185+04 0.00E+00 1.06
..........................................................................E+03 I.133 CS-134 1.32544 1.92E+04 5.60EM3 3.56EM6 2.245M4 0.00E+00 2.16E+03 CS.136 3.965+05 7.03E4 5 7.45E+04 0.00E+00 1.90h05 7.97h04 1.33h03 4.835+04 1.35 EMS 5.29E+04 0.008+00 5.64E+44 1.188+04 1.43E+03
...............s...............................................................
C5 137 E4 140 5.49845 6.12E45 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 CE.141 5.60E+04 5.60D01 2.90EM3 0.00E+00 1.34E+01 1.60EM6 3.84 h04 2.77t+04 1.67EM4 1.99843 0.00E+00 5.25E+03 5.17E45 2.16E+04 CE.144 PR.143 3.198+06 1.21546 1.76h05 0.00E+00 5.38545 9.84E+06 1.48E+05 1.40Et04 5.24543 6.99EM2 0.00B+00 1.97543 4.33E+05 3.72E+04 i ND.147 7.94 h03 8.13h03 5.00E+02 0.00h00 3.15E+03 3.22EM S 3.12E+04 t Rev 8 COMANCE PEAK . Ur4TS 1 APO 2 PART I 2-49 01/93
TABLE 2.5 8 (Sheet 1) CONTROLLING RECEPT 0R PATHWAYS AND LOCATIONS (NOTE 1). AND 5 ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) TABLE RELOCATED: 12 CURRENT INFORMATION LISTED AND MAINTAINED CURRENT IN RESULTS OF ANNUAL LAND USE CENSUS l COMANCHE PEAK UNITS 1 AND 2 PART II 2-50 Rev. 12 12/95
1 l I THIS PAGE INTENTIONALLY LEFT BLANK 12 l i l 1 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-51 Rev. 12 12/95
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1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) Vertissi Stenderd Devieden of Macartei in a Mume (Letters denots Pasquill Stability Class) NOTE: THESE ARE STANDARO RELATIONSHIPS AND MAY HAVE TO BE MOOIPIED POR CERTAIN TYPES OF TERRAIN ANO/OR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT, OVER WATER). Fitura 2.3 COMANCHE PEAK - UNITS 1 AND 2 PART ll 2 54 01/93
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!.1 i COMANCHE PEAK - UNITS 1 AND 2 PART ll 2-55 01/93 6 _ _ ___J
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SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING I 3.1 SAMPLING LOCATIONS Sampling locations as required in Radiological Effluent Control 3/4.12,1. 12 Table 3.12-1 are listed and maintained current in the results of the annual Land Use Census. NOTE: For the purpose of implementing Radiological Effluent Control 3/4.12.1. sampling locations will be modified as required to reflect the findings of the Land Use Census. Dose 8 calculations used in making this determination will be performed as specified in Section 2.5. The sampling locations maintained in the results of the annual Land Use 12 Census are the minimum locations required for compliance with Radiological Effluent Control 3/4.12.1. If desired, additional locations may be monitored as special studies to evaluate potential pathways of exposure without adding such locations to the monitoring program. 3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3. TU 12 Electric has contracted with an outside laboratory to provide radiological j environmental analytical services with required participation in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program is conducted by a third-party laboratory which supplies environmental-type samples (e.g.. milk or water) containing concentrations of radionuclides known to the issuing laboratory but not to the participant laboratories. l The purpose of the program is to provide an independent check on the l participant laboratory's analytical procedures and to alert the participants to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the l issuing laboratory. Several months later the issuing laboratory reports the known values to the COMANCHE PEAK - UNITS 1 AND 2 PART II 3-1 Rev. 12 12/95
participant laboratories and specifies control limits. Results 12 consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. TU Electric's contracted outside laboratory participates in an environmental sample crosscheck program for representative sample media. ! The results of the program are included in the Annual Radiological Environmental Operating Report, as required by CPSES Technical Specification 6.9.1.3. i I l I 1 I i l . l i l i l COP %NCHE PEAK - UNITS 1 AND 2 PART II 3 2 Rav. 12 12/95
_ . _ _ . . _ . _ _ _ _ _ _ _ _ . . _ . . ~ . _ _ _ _ _ _ _ _ .. _ m_.._ _ _ _ . . - . _ _ TABLE 3.1 ENVERONMENTAL SAMPLENG LOCAT10NS i TABLE RELOCATED: 12 ; ENVIRONMENTAL SAMPLING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL LAND USE CENSUS i t l l l l 1 l I
- COMANCHE PEAK - UNITS 1 AND 2 PART II 3-3 Rev. 12 12/95
r l FlGURE3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS FIGURE RELOCATED: 12 l RADIOLOGICAL ENVIRONMENTAL MONITIORING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL l LAND USE CENSUS l l \ COMANCHE PEAK - UNITS 1 AND 2 PART II 3-4 REV. 12 12/95
_ _ -- .~_ . _ . _ - - - _ . . _ . . - _ - _- _ . _ _ ._ ._ _ l l APPENDIX A PATHWAY DOSE RATE PARAMETER P1 (inhalation) = K' (BR) DFAj [Eq. A-1] l where:
- Pj = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m3 The dose factors are based on the critical individual organ for the child age group.
K' = conversion factor, 106 pCi/ microcurie BR = 3700 m3/yr, breathing rate for child (Ref. 2, Table E-5) DFAj = the maximum organ inhalation dose factor for the child age group for the ith'radionuclide (mrem /pC1). Values are taken from Table E-9,
~"
Reg. Guide 1.109 (Ref. 2) Resolution of the units yields: Pi (inhalation) = 3.7 x 109 DFAj (mrem /yr per uC1/m3) [Eq. A-2] The latest NRC Guidance has deleted the requirement to determine Pj (ground plane) and P1(food). In addition, the critical age group has been changed from infant to child. l l l COMANCHE PEAK - UNITS 1 AND 2 PART II A-1 01/93 i a -- - _ i__ __ _
APPENDIX B I INHALATIONPATHWAYDOSEFACTOR(R i.a.o) 3 Rf,,,g = k' (BR) (DFAj,,,g) (mrem /yrpermicrocurie/m)[Eq.B-1] where: k' = conversion factor, 106 pC1/ microcurie BR = breathing rate, 1400, 3700, 8000, and 8000 m3/yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2. Table E-5) DFA1 .a.o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the i ith radionuclide, in mres/pci. The total bocy j' is considered as an organ in the selection of DFA1 .a.o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Ref.2) i ) , l 1 l l l I i i COMANCHE PEAK - UNITS 1 AND 2 PART II 8-1 01/93 I y
APPENDIX C GROUND PLANE PATHWAY DOSE FACTOR (R G j) i i O R = k'k"(SF)DFG 4 [(1-e-Ai t)/Aj ] [Eq. C-1] where: k' = conversion factor, 106 pCi/ microcurie { k" = conversion factor, 8760 hr/yr Aj e decay constant for the ith radionuclide, sec -1
=
t the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs) DFG1 =the ground plane dose conversion factor for the ith radionuclide (mres/hr per pC1/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply 1 to all age groups. Dose factors are provided for the total body and skin only. Doses to all other organs are assumed equal to the total body dose. SF = 0.7, shielding factor, from Table E-15, Reg. Guide 1.109 (Ref. 2) d l COMANCHE PEAK - UNITS 1 AND 2 PART II C-1 01/93
APPENDIX 0 C GRASS COW-MILK PATHWAY 00SE FACTOR (R ) Rf,,,o = k' [(Qp x UAP) / I A 1 + A w )] x (F,) x (r) x (DFLi a.o)
- t
[((f px f )/3 Y )p + ((1-f xp f ) 3e-^i h)/Y ] e'A tif 3 [Eq. D-1] l l where: k' = conversion factor, 106 picocurie / microcurie (pC1/uci) Qr =cowconsumptionrate,50kg/ day,(R.G.1.109) l UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for infant, child, teenager, and adult age j groups, respectively (R.G. 1.109) Yp = agricultural productivity by unit area of pasture feed l graf,s,0.7kg/m2(NUREG-0133) l Ys = agricultural productivity by unit area of stored feed, 2.0kg/m2,(NUREG0133) l Fm =stableelementtransfercoefficient(TableE-1,R.G. I 1.109) l r = fraction of deposited activity retained in cow's feed grass. 0.2 for particulates, 1.0 for radioiodine (TableE-15.R.G.1.109) , DFli,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables l E-11 to E-14 R.G. 1.109) l Aj = decay constant for the ith radionuclide, sec-1 Aw = decay constant for weathering, 5.73 x 10-7 sec -1 (NUREG-0133) tr = 1.73 x 105 sec, the transport time from pasture to cow
- to milk to receptor (Table E-15 R.G. 1.109)
COMANCHE PEAK - UNITS 1 AND 2 PART II D-1 01/93 1 l l
APPENDIX D (CONTINUED) th = 7.78 x 106 sec, the transport time from pasture to harvesttocowtomilktoreceptor(TableE-15,R.G. 1.109) fp = 1.0, the fraction of the year that the cow is on pasture. fs = 1.0, the fraction of the cow feed that is pasture grass . while the cow is on pasture. The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R C g, basedon(X/Q): C R = k ' k'" F, QpUAP DFL t.a.o (.75(.5/H)) [Eq.D-2] where: k'" = 103 grams /kg H = 8 grams /m3, absolute humidity of the atmosphere
.75 = fraction of total feed grass mass that is water
.5 = ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-0133)
DFL t .a.o = the ingestion dose factor for tritium and organ, o, foreachrespectiveagegroup,a(TablesE-11 toe-14 R.G.1.109) < All other parameters and values are as given above. C NOTE: Goat-milk pathway factor, R 1.a.o will be computed using the c u eilk pathay factor equation. Fu factor for goat-milk wil's be from Table.I-2, R.G. 1.109. QF for goats is 6 kg/ day from Table E-3, R. (i. 1.109 8 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II D-2 01/93 I
l l l APPENDIX E ' l J ] COW-MEAT PATHWAY DOSE FACTOR (RM i.a.o) i R 3,,,o = k' (0 pxUAP)/IA i + Aw ) x (Ff) x (r) x (DFL9,,,g)x [((f px f )/Y 3 f ) e~ i th)/Y3 ] x e it f p) + ((1 - f p3 l [Eq.E-1] where: i
- k' = conversion factor, 106 picocurie / microcurie (pC1/uC1)
QF = cow consumption rate, 50 kg/ day, (R.G. 1.109) UAP = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups,respectively(R.G.1.109) F"f = the stable element transfer coefficients, days /kg. (Table E-1, R.G. 1.109) r = fraction of deposited activity retained in cow's feed grass. 0.2 for particulates, 1.0 for radioiodine (TableE-15,R.G.1.109) DFli ,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 toe-14,R.G.1.109) < A1 = decay constant for radionuclide 1, sec-1 l Aw = decay constant for weathering 5.73 x 10-7 sec -1 (NUREG-0133) tr = 1.73 x 106 sec, the transport time from pasture to receptor (NUREG-0133) l th = 7.78 x 106 sec, the transport time from crop to receptor ' (NUREG-0133) COMANCHE PEAK - UNITS 1 AND 2 PART II E-1 01/93
APPENDIXE(CONTINUED) Yp = agricultural productivity by Jnit area of pasture feed grass,0.7kg/m2(NUREG-0133) l Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2, (NUREG 0133) fp = 1.0, the fraction of the year that the cow is on pasture. fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture. The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore RM 9, basedon(X/Q): (DFLt.a.o) x 0.75 x (0.5/H) [Eq. E-2] R
,,,, = k ' k '" Ff QUAP p
where: All terms are as defined above and in Appendix D. i, COMANCHE PEAK - UNITS 1 AND 2 PART II E-2 01/93
APPENDIX F Y VEGETATION PATHWAY DOSE FACTOR (R w ) Rf,,,, = k' x [r/ (Y y(A4 + A,))] x (DFLj,,,g)x[(Uk)fL e-A tiL
+U S f ge "A i t]
h [Eq.f-1] where: k' = 106 picocurie / microcurie (pC1/uC1) UL A = the consumption rate of fresh leafy vegetation, O, 26, 42, 64kg/yr for infant, child, teenager, or adult age j groups respectively. (R.G.1.109) l USA = the consumption rate of stored vegetation, 0, 520, 630, I 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) ' f L
= the fraction of the annual intake of fresh leafy vegetationgrownlocally,1.0(NUREG-0133) f g = the fraction of the stored vegetation grown locally .76 (NUREG-0133) t l
= the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds (TableE-15,R.G.
1.109 (24 hrs)) t h
= the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds (TableE-15,R.G.1.109(60 days))
COMANCHE PEAK - UNITS 1 AND 2 PART II F-1 01/93
APPENDIXF(CONTINUED) yy =thevegetationarealdensity,2.0kg/m2(TableE-15, 8 R.G.1.109) All other parameters are as previously defined. The concentration of tritiem in vegetation is based on the airborne concentration rather than the deposition. Therefore, R V $3 based on (X/Q) Rf,,,, = k ' k"' [UkfL+Uff]g (DFLta,o) (.75 (.5/H)) [Eq.F-2] where: All terms are as defined above and in Appendix D. l l 4 l l , l I l Rev 8 C0KANCHE PEAK - UNITS 1 AND 2 PART II F-2 01/93 4
APPENDIX G
.a.
SUPPLEMENTAL GUIDANCE STATEMENTS l 1 HAVE BEEN DELETED 8 1 REY. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II G-1 01/93
COMANCHE PEAK STEAM ELECTRIC STATION , 0FFSITE DOSE CALCULATION MANUAL (00CM) EFFECTIVE PAGE LISTlNG l l BELOW IS A LEGEND.FOR THE EFFECTIVE PAGE LISTINGS: i Revision 0 (TXX 89118) Submitted to the NRC March 2. 1989 ! Revision 1 (TXX-89595) Submitted to the NRC August 25. 1989 i Revision 2 (TXX-89711) Submitted to the NRC November 27. 1989 ! l Rev1sion 3 April 10. 1990 l Revision 4 October 9. 1990 , Revision 5 December 20, 1990 Revision 6 July 3. 1991 Revision 7 December 4.1991
. Revision 7A August 6. 1992 i Revision 8 (Unit 2 Operations) January 1. 1993 i Revision 9 September 28. 1994 Revision 10 April 22. 1994 Revision 11 November 7. 1994 Revision 12 December 8. 1995 i
$0 l
I COMANCHE PEAK - UNITS 1 AND 2 EPL - 1 REV. 12 12/95
l i 1 COMANCHE PEAK STEAM ELECTRIC STATION 0FFSITE 00SE CALCULATION MANUAL- i EFFECTIVE PAGE LISTING j i pace No. Revision No. [ Cover Sheet 8 ! i 8 ; 11 10 i iii 9 l iv 9 v 8 vi 8 vii 12 viii 8 ix 9 x- 8 xi 8 xii 12 P P.EL1 Divider Page - 01/93 I 1-0 01/93 I 1-1 01/93 I 1-2 12 1 1-3 01/93 l' l. I14 8 , I 1-5 01/93 I 1-6 01/93 1 2-0 01/93 I 3/4-0 -01/93 I 3/4-1 01/93 I 3/4-2 01/93 I 3/4-3 10 l l I 3/4-4 10
- I 3/4-5 11 I 3/4 Sa 4/94 l
1 3/4-6 9 I 3/4-7 11 I 3/4-8 10 1 3/4-9 01/93 i I 3/4-10 01/93 I 3/4-11 01/93 I 3/4-12 8 I 3/4-13 11 I 3/4-14 01/93 , I 3/4-15 01/93 i 4 I 3/4-16 01/93 i l l COMANCHE PEAK - UNITS 1 AND 2 EPL - 2 REV. 12 12/95 l .
1 COMANCHE PEAK STEAM ELECTRIC STATION l ! 0FFSITE DOSE CALCULATION MANUAL : EFFECTIVE PAGE LISTING , I ! Pace No. Revision No. I 3/4-17 12 I 3/4-18 9 : I 3/4-19 8 I 3/4 20 12 I 3/4-21 8 . l I 3/4 22 8 ! I 3/4-22a 8 I 3/4 22b 8 ERRATA I 3/4 23 12 I 3/4-24 01/93 I 3/4-25 01/93 I 3/4-26 10 I 3/4-27 8 i I 3/4-28 8 I I 3/4-29 8 i I 3/4-30 12 I 3/4 31 8 I 3/4-32 12 1 I 3/4-33 12 I 3/4-34 01/93 I 3/4-35 01/93 I 3/4-36 01/93 ' I I 3/4-37 01/93 I 3/4-38 12 I 3/4-39 8 , I 3/4-40 01/93 ! I 3/4-41 01/93 I 3/4 42 01/93 I 3/4-43 01/93 I 3/4-44 12 I 3/4-45 <- 12 I B 3/4-0 01/93 I B 3/4-1 8 l I B 3/4-2 01/93 i I B 3/4-3 12 l I B 3/4-4 12 i I B 3/4-5 8 ERRATA l I B 3/4-6 12 l l I B 3/4-7 12 I I B 3/4 8 12 I B 3/4-9 8 , I B 3/4-10 12 4 I COMANCHE PEAK - UNITS 1 AND 2 EPL - 3 REV. 12 12/95 i
COMANCHE PEAK STEAM ELECTRIC STAT 10N ! 0FFSITE DOSE CALCUL' ION MANUAL ! EFFECTIVE PAGE LISTING t Paae No. Revision No. I B 3/4-11 12 I 8 3/4-12 01/93 , i I50 01/93 ' I 5-1 12 i I 5-2 8 I 6-0 01/93 I 6-1 12 I 6-2 12 I 6-3 10 I 6-4 10 PART II : Divider Page. 01/93 II 1-1 12 II 1-2 12
'II 1-3 8 II'l-4 12 II 1-5 12 -
II 1 6 12 II 1-7 12 II 1-8 12 ; II 1-9 12 II 1-9a 12 II 1-10 8 11 1-11 8 II 1-12 8 II 1-13 8 ERRATA II 1 8 ; II 1-15 8 l II 1-16 01/93 II 1-17 12 II 1-18 12 II 1-19 12 i II 1-20 8 1 II 1-21 8 II 1-22 8 II 1-23 8 II 1-24 12 II 1-25 12 II 1-26 01/93 II 1-27 01/93 COMANCHE PEAK - UNITS 1 AND 2 EPL - 4 REV. 12 12/95
COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE.PAGE LISTING Paae No. Revision No. 11 2-1 10 II 2-2 8 II 2 3 8 II 2 4 8
.II 2-5 8 l II 2 6 8 II 2 7 12 II 2-8 12 II 2-9 8 11 2-10 8-II 2 11 8 II 2-12 8 II 2-13 12 II 2-14 12 II 2-15 12 II 2-16 10' II 2-17 10 II 2-18 8 II 2-19 8 II 2 20 8 II 2-21 8 II 2-22 8 ERRATA II 2-23 8 II 2-24 12 II'2-25 12 II 2-26 8 ERRATA II 2 27 8 II 2 28 8 11 2-29 8 II 2-30 8 II 2-31 " 8 II 2-32 8 II 2 33 8 II 2-34 8 II 2-35 8 11 2-36 8 II 2-37 8 II 2 38 8 II 2-39 8 II 2-40 8 II 2-41 8 II 2-42 8 II 2-43 8 l
COMANCHE PEAK - UNITS 1 AND 2 EPL - 5 REV. 12 12/95
i-COMANCHE PEAK STEAM ELECTRfC STATION i 0FFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING : Paae No. Revision No II 2-44 8 ! II 2 45 .8 1 II 2 46 8 ! II 2-47 8 l l !! 2-48 8 l II 2 49 8 . II 2-50 12 ! II 2-51 12 - II 2 52 01/93 : II 2-53 01/93 i II 2-54 01/93 i II 2-55 01/93 II 2-56 01/93 . I II 3-1 12 '! II 3-2 12 II 3-3 12 - l- II 3-4 12 II A 1 '01/93 i II B-1 01/93 II C-1 01/93 II 0-1 01/93 l II 0-2 8 II E-1 01/93 II E-2 01/93 II F-1 01/93 II F-2 8 II G-1 8
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i i r l COMANCHE PEAK - UNITS 1 AND 2 EPL - 6 REV. 12 12/95 1,, .- --
3 i : I l n I i 4 1 4 t I . l i I
'I l i ,
j ATTACHMENT 8.2 l i :
- l 1
i e Joint Frequency Tables for i i 4 3 i 1995 b I i l i I l 1 i 4 4 1 4 1 1 t 4
r R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY l l HOURS AT EACH WIND SPEED AND DIRECTION 4 PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 l STADILITY CLASS: A ELEt> A T I ON : 10 m. i Wind Speed (mph) at 10 m. level Wind Direttion 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 4 12 9 4 0 30 NNE 1 6 6 0 0 0 13 NE 2 6 11 1 0 0 20 ENE 1 3 5 1 0 0 10 E 1 6 5 0 0 0 12 ESE O 15 16 1 0 0 32 ) i SE 1 15 29 12 1 0 50 SSE 1 6 24 32 1 0 64 S 4 5 15 18 6 2 50 SSW O 4 9 11 0 0 24 SW 1 7 5 5 , 0 0 10 WSW 1 2 2 1 0 0 6 W 1 1 1 0 0 0 3 WNW 0 0 0 0 0 0 0 NW 1 4 6 9 6 0 26 NNW O 4 13 29 14 10 78 (J ARI ABLE 3 2 0 0 0 0 5 Totai 19 90 159 129 32 20 449 Periods of c a l m (h ou rs) : 1 Houro of misning data: 14 l l
R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 STADILITY CLASS: D ELEUATION: 10 m. Wind Speed (mph) at 10 m. level Wind Diraction 1-3 4-7 8-12 13-10 19-24 >24 TOTAL N 3 9 16 10 10 2 50 NNE O 7 19 15 4 0 45 NE 3 12 6 1 0 0 22 ENE. 2 3 4 4 0 0 15 E 2 7 2 0 0 0 11 ESE 1 14 4 1 0 0 20 SE 2 16 14 6 0 0 38 SSE 1 14 21 29 3 0 68 5 0 3 30 40 10 2 85 SSW 1 6 12 19 11 0 49 SW 0 4 12 7 1 0 24 WSW 3 5 7 4 1 0 20 W 1 0 2 2 0 0 5 WNW 0 3 2 0 0 0 5 NW 1 2 5 8 1 0 17 NNW 0 14 13 21 11 4 63 l UARIABLE 7 0 2 0 0 0 9 Totai 27 121 171 167 52 8 546 Periods of c a l m (hou rs) : 2 Hours of missing data: O r I i l
R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 STABILI TY CLASS: C ELEUATION: 10 m. Wind Speed (mph) at 10 m. level Wind Direttion 1-3 4-7 8-12 13-10 19-24 >24 TOTAL N 4 13 14 41 9 0 81 NNE 5 6 22 32 4 0 69 i NE 10 11 11 5 1 0 38 l ENE 5 6 5 3 0 0 19 l E 2 7 4 0 0 0 13 ESE 2 19 7 0 0 0 28 SE 3 27 20 6 0 0 56 SSE 3 18 29 42 2 0 94 S 4 12 50 65 23 5 159 SSW 1 11 2'7 38 18 1 96 SW 1 7 20 10 3 0 41 WSW 2 4 9 2 2 0 19 W 0 2 4 0 1 0 '7 l WNW 2 3 6 4 2 0 17 NW 2 2 7 6 6 2 25 NNW 2 15 14 30 27 4 92 VARIABLE 16 2 0 0 0 0 la Totai 64 165 249 284 98 12 872 Periods of c a l m (h ou rs) : 1 Hours of missing data: 0
R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 STABILITY CLASS: D ELEVATION: 10 m. Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 89 222 137 53 7 520 NNE 9 70 139 65 9 3 295 NE 23 55 95 39 1 1 214 ENE 20 45 66 7 1 1 140 E 19 101 19 5 1 0 145 ESE 31 101 29 3 1 0 165 SE 22 149 204 28 2 0 405 SSE 12 100 253 197 30 1 593 S 16 77 220 188 51 5 557 SSW 7 38 60 53 18 0 176 SW 9 34 24 24 3 0 94 l WSW 15 22 14 5 0 0 56 I W 6 18 9 3 1 0 37 WNW 4 19 9 '7 1 0 40 1 NW 8 25 35 36 21 0 125 1 NNW 10 29 116 '77 25 5 262 I VARIABLE 80 22 4 3 1 0 110 Totai 303 994 1518 8 7'7 219 23 3934 Periods of c a l m (hours) : 4 Hours of missing data: 1 l
l I R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 l t 3 TAD L LITY CLASS: E ELEVATION: 10 m., Wind Speed (mph) at 10 m. level Wind Direttion 1-3 4-7 0-12 13-10 19-24 >24 TOTAL l 1 1 N 7 16 37 5 0 0 65 i NNE 4 16 21 0 0 0 41 l NE 3 17 3 0 0 0 23 ENE 9 7 3 0 0 0 19 E 11 34 0 1 0 0 46 ESE 16 57 2 0 0 0 75 SE 14 170 133 9 0 0 326 SSE 15 138 235 39 6 0 433 S 20 74 117 34 0 0 245 SSW 25 31 44 17 0 0 117 j i i SW 31 19 26 20 1 0 97 l WSW 15 20 14 6 0 0 55 W 13 16 9 0 0 0 30 WNW 14 20 11 1 0 0 46 NW 20 51 42 2 0 0 115 NNW 16 11 12 2 0 0 41 VARIABLE 70 10 5 1 0 0 94
. . _ - _ . . _ _ _ _ _ . _ . _ . _ . _ _ _ . _ . _ _ . _ _ . _ _ . _ . _ _ - . _ _ _ . _ . _ _ - _ . ~ . _ . . _ .
- Tota 1 311 707 714 137 7 0 18'76 l
Periods of calm (hours): 4 Hours of missing data: 0
l R.G. 1.21 JOINT FREQUENCY TABLE I l T. U. ELECTRIC COMPANY l l HOURS AT EACH WIND SPEED AND DIRER. TION , PERIOD OF RECORD: 01-J AN -95 00:00 TO 31-DEC-95 23:59 l STADILITY CLASS: F El EUA TION: 10 m. , Wind Speed (mph) at 10 m. level Wind Direction 1-3 4 -'7 8-12 13 19-24 >24 TOTAL 1 N 1 3 1 1 1 0 7 l NNE O 2 6 0 0 0 8 l NE O O O O O O O ENE O O O O O O O E O O O O O O O 1 ESE 1 0 0 0 0 0 1 l SE 5 40 9 0 0 0 54 SSE 8 43 16 0 0 0 67 S 21 27 20 7 3 0 78 SSW 33 28 28 8 2 0 99 SH 37 23 18 1 0 0 '79 WSW 36 33 13 0 0 0 82 W 23 10 0 0 0 0 33 WNW 10 8 2 0 0 0 20 NW 12 34 1 1 0 0 48 NNW '7 ~7 1 0 0 0 15 l UARIABLE 24 2 0 0 0 0 26 Total 218 260 115 18 6 0 61/ Periods of c a l m (h ou rs) : 1 Hours of missing data: 0 t
l t i R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 STABILITY CLASS. G ELEVATION: 10 m. , Wind Speed (mph) at 10 m. level Wind Direttion 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 2 0 0 0 2 NNE O O O O O O O NE O 1 0 0 0 0 1 l 1 l ENE O O O O O O O I E O O O O O O O ESE 1 0 0 0 0 0 1 SE O 2 1 0 0 0 3 SSE 1 1 1 0 0 0 3 S 4 2 1 0 0 0 7 SSW 19 21 11 0 0 0 31 SW 18 26 4 0 O O 48 WSW 18 44 11 0 0 0 73 W 12 12 4 0 0 0 20 WNW 5 3 0 0 0 0 8 NW 13 15 2 4 4 0 30 NNW 2 6 1 7 0 0 16 UARIABLE 4 0 0 0 0 0 4 TotaI 9 '7 133 38 11 4 0 283 . Periods of calm (hours): 1 ! llours of missing data: 0
t i R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-95 00:00 TO 31-DEC-95 23:59 STADILITY CLASS: ALL ELEVATION: 10 m. Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 28 134 304 203 77 9 755 NNE 19 107 213 112 17 3 471 NE 41 102 126 46 2 1 318 i ENE 37 66 83 15 1 1 203 E 35 155 30 6 1 0 227 ESE 52 206 60 6 1 0 325 SE 47 419 418 63 3 0 950 SSE 41 320 579 350 45 2 1337 8 69 200 453 353 93 14 1102 1 i 1 DSW 86 139 191 146 49 1 612 l l SW 97 120 109 67 8 0 401 1 I WSW 90 130 '70 18 0 311 3 W 56 59 29 5 2 0 151 WNW 35 56 30 12 3 0 136 NW 57 133 98 66 38 2 394 NNW 37 86 170 166 '77 31 56'7 l UARIADLE 212 38 11 4 1 0 266 i f TotaI 1039 2470 2974 1638 421 64 8606 Periods of calm (hours): 14 Hours of missing data: 140}}