ML20082R199
| ML20082R199 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1994 |
| From: | Floyd E, Kay D, Robert Prince TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20082R197 | List: |
| References | |
| NUDOCS 9505020003 | |
| Download: ML20082R199 (238) | |
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1UELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION RADIOLOGICAL EFFLUENT 1994 ANNUAL REPORT REVIEW / APPROVAL Reviewed by: [ 9 W-#- 93' Edwin T. Floyd Date Senior Radiation Protection Technician Reviewed by: . 4/4/ 4-(0-95 Douglas CDKay j Date Radiation Protection Supervisor Approved by: 771ce /i //- 9 f Robert J. Prince Date Radiation Protection Manager O 45 COMANCHE PEAK STEAM ELECTRIC STATION R PDR P.O. Box 1002 Glen Rose. Tesas 7600-l(K)2
TABLE OF CONTENTS , i ACRONYMS AND ABBREVIATIONS ,
1.0 INTRODUCTION
2.0 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 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RELATED INFORMATION 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 G.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 j 6.8 Meteorological Monitoring Program 6.9 Assessment of Doses 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 L67el 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 8.0 ATTACHMENTS 8.1 Offsite Dose Calculation Manual For TU Electric Comanche Peak Steam Electric Station Units 1 and 2, Revision 11 i j ii l
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 iii l I 4
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1.0 INTRODUCTION
l This Annual Radioactive Effluent Release Report, for Comanche l Peak Steam Electric Station Unit 1 and Unit 2, is submitted as i required by Technical Specification 6.9.1.4 and Offsite Dose. Calculation Manual- (ODCM) Administrative Control 6.9.1.4 for f the period January 1, 1994, through December 31, 1994. ! The radioactive effluent monitoring program is conducted as described in the following report. The results of this report indicate the continued efforts to maintain the release of i radioactive effluents to as low as reasonably achievable. The l total ~ activity released and the resulting dose due to gaseous t effluents has decreased for the second consecutive year while ~ the total activity (excluding tritium) released and the : resulting dose due liquid effluents has also decreased for the j second consecutive year. These trends reflect improvements ! implemented in the program resulting in continued benefits and i positive results. Overall, the activity released and j associated dose to the public resulting from releases of liquid and gaseous effluents have been maintained as low as ! reasonably achievable. , l Information pertaining to the following areas is included in ; this report. , t e A summary of the quantities of radioactive liquid and j 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 and Unit 2 .l 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 'j 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. ,
# Changes to the ODCM in the form of a complete, legible i copy of the entire ODCM. j I
e A listing of new locations for dose calculations and/or ; environmental monitoring identified by the Land Use { Census. : e A description of the events leading to liquid holdup ! tanks or gas storage tanks exceeding Technical , Specification limits. l i i
1 l e A list and description of abnormal releases of radioactive material from the site to unrestricted areas. e A description of secondary resin releases to the LVW Pond, e A description of major changes to radioactive waste treatment systems (liquid, gaseous and solid).
- An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from CPSES Unit 1 and Unit 2 in 1994.
- 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 Standards for Nuclear Power Operation."
e An assessment of the radiation doses from radioactive liquid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary. 2.0 SUPPLEMENTAL INFORMATION 2.1 Reculatory 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 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 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.
2.1.2 Iodine-131. Todine-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 iodine-131, iodine-133, tritium and all 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 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 matel- ./ in liquid effluents released, from ach unit, to unrestricted areas 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 mrems to any organ, and l
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- b. During any calendar year to less than or equal to 3 mrems to the whole body and to i less than or equal to 10 mrems to any ;
organ. 2.1.4 LVF Pond Resin Inventory The quantity of radioactive material contained in resins transferred to the LVW pond shall be limited by the following expression: (264/V) - E A /C 3 3 3
< 1.0 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 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 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. , 2.2 Effluent Concentration Limits 2.2.1 Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary. I l 1 m_-
1 2.2.2 hiauid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 pCi/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 radioactivity 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 i l for gamma emitting radionuclides using gamma ) spectroscopy, prior to release. Composite I samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste ) Monitor Tanks (WMT), Laundry Holdup and 1 Monitor Tanks (LHMT) and Waste Water Holdup Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha 4 radioactivity in the onsite laboratory using i liquid scintillation and gas flow proportional counting techniques, respectively. Composite . samples were analyzed quarterly for Sr-89, Sr- l l 90 and Fe-55 by a contract laboratory l (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 present and the total volume of the effluent released during periods of discharge. 4 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 l For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab ' samples were obtained over the peric d 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 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 i Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release with the exception of Containment vents made as a precursor to a Containment purge. In these cases, samples 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 cotal amount of radioactivity released in the batch mode. For continuous efflu nt 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 adsorbers and particulate filters. The radiciodine adsorbers and particulate filters were analyzed weekly for I-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and i tritium grab samples, radiciodine adsorber and l particulate filter analyses from the current i l l
i i i week and the average effluent flow rate for ! the previous week were used to determine the , total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross 1 alpha activity, in the onsite laboratory using the gas flow proportional counting technique. , Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by an offsite laboratory (Teledyne Brown). ; 2.4 Batch Releases f A summary of information for gaseous and liquid batch releases is included in Table 7.1. r 2.5 Abnormal Releases Abnormal releases are defined as unplanned or uncontrolled releases of radioactive material from the site boundary. Two (2) abnormal gaseous effluent releases and one (1) abnormal liquid effluent release occurred during the period covered by this report. These events are 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 te be ground level releases. 4.O LIOUID EFFLUENTS I The quantities of radioactive material released in liquid effluents are summarized in Tables 7.5 and 7.6. 5.O HOLID WASTES , The quantities of radioactive material released as solid effluents are summarized in Table 7.13.
t 6.0 RELATED INFORMATION f 6.1 Ooerability of Liould and Gaseous Monitorina , _ Instrumentation ! ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 i require an explanation of why . designated - inoperable l liquid and gaseous monitoring instrumentation was not restored to operable status within thirty days. i During the period covered by this report, there were no instances where these instruments were inoperable for more than thirty days. j
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6.2 Chances to the Offsite Dose Calculation Manual During the period covered by this report, there were two revisions to'the ODCM. In accordance with the ODCM i Administrative Control 6.14.c, .these changes are submitted in the form of a complete copy of the entire l ODCM. The ODCM, current as of December 31, 1994, is j contained in Attachment 8.1. The changes included in , these revisions are summarized below: Revision 10. effective April 22. 1994 - i e The methodology used to calculate the radiation i monitor alarm setpoint for the liquid effluent' ! monitor was revised. Under certain circumstances i the setpoint was overly conservative since it i factored in the non-gamma emitting radionuclides. l The monitor is gamma sensitive only and therefore l the setpoint calculational methodology was revised to provide a more appropriate setpoint. l t e The reporting requirements for the Radiological Effluent Release Report was changed from Semiannual ; to Annual and the report due date was revised to ! prior to May 1 of each year. e The ACTION statement for the Auxiliary Building to LVW Pond Liquid Effluent Line radiation monitor was , revised to require a mandatory 12-hour grab l sampling frequency when the monitor. is declared j inoperable. 7 e Part II, Table 2.5 pathway dose parameters for resident, milk cow, garden, X/Q and D/O values were revised based on the results of the 1993 Land Use Census.
..c 1-e Revised the general ODCM text in Part II, Section-2.0, Gaseous Effluents, to delete the specific number of hours designated for the batch release portion of a Containment Building purge. Revision 11. effective November 7. 1994 - e Part I, Section 3.3.3.6, revised the- ACTION statement wording to be consistent with other similar TS/ODCM action statements, e The liquid release type, maximum flow rate and tank volume for the Condensate Polisher Backwash-Recovery Tanks were updated for Unit 2 operations. The nomenclature for the Clarifier sump - and it's discharge rate were updated also. e The ACTION statement for the Service Water System Effluent Lines was revised to allow the use of Unit 1 or Unit 2 monitors and Unit 1 or Unit 2 Component Cooling Water monitors as a backup depending on system lineups and operability. e New type Turbine Building sump monitors have no sample flow since they are an on-line type monitor. The " loss of sample flow" notation is inappropriate for these monitors and was corrected. e Two garden sample locations were deleted from the environmental sampling prog am and two new locations were added. 6.3 New Locations for Dose Calculations or Environmental Monitorino ODCM Administrative Control 6.9.1.4 requires any new locations for ' dose calculations and/or environmental monitoring, identified by the Land Use Census, to be included in the Annual Radioactive Effluent Release Report. Based on the 1994 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/Q values were submitted to revise Table 2.5 of the ODCM. I l I During 1994, beef cattle were allowed to graze on pasture land within a portion of the Site Boundary. The presence l of cattle in sectors South (S) and South-Southeast (SSE) required that the calculated doses due to gaseous effluents be adjusted. Based on the new X/Q value used for gaseous pathway tritium dose calculations, the doses were revised. The doses reported in Tables 7.9, 7.10, 7.11 and 7.12 reflect this correction. 6.4 Liouid Holduo and Gas Storage 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 as Xe-133 equivalent). These limits were not exceeded during the period covered by this report. 6.5 Noncompliance with Radiological 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. 6.5.1 Abnormal Gaseous and Liquid Releases e On January 14, 1994, at approximately 10:00 hours, Radwaste personnel were preparing to drain condensate from Gas Decay Tank-03 (GDT-03). The drain valve was opened for water removal. When personnel entered the room they discovered water on the floor and water coming from the gas decay trap upper inlet flange. Minutes later, the drain valve was closed. The GDT-03 pressure was noted to have decreased from 7.3 psig to 0.3 psig. An unplanned non-routine i permit accounted for the released noble l l i l I ___--_ - --_1
gas from GDT-03. The dose contribution for this release was calculated to be
- 1. 56E-06 mrad gamma air dose and 1. 71E-04 mrad beta air dose. As a corrective action the flange was repaired and returned to service.
l l e On February 14, 1994, at approximately ! 15:00 hours, Engineering personnel I reported a pressure loss from the Unit 2 Reactor Coolant Drain Tank (RCDT). It was determined that a potential unmonitored release pathway existed between the Unit 2 RCDT and the Turbine l Building Instrument Air Compressor room via the hydrogen lines. The leak was confirmed to be between the primary sample room and the hydrogen bottles i located outside the Turbine Building. A J system valve (2-7155) was leaking by and the RCDT pressure was released by this valve and out a piping hole. It was I conservatively estimated that a maximum 1 of 650 cubic feet of noble gas could have been released. An unplanned non-routine permit accounted for the gas potentially , released from the RCDT. The dose ! contribution for this release was l calculated to be 1.00E-04 mrad gamma air ; dose and 4.46E-05 mrad beta air dose. The leaking valve was isolated and caution tags were hung to prevent another release from this same source. The valve materials are being evaluated for continued use or replacement with a different type of valve material, e On July 5, 1994, at approximately 12:00 at the termination of a liquid release discharge for Waste Monitor Tank 2 (WMT2) t it was noted that a 3% decrease had also occurred for Waste Monitor Tank 1 (WMT1). WMT1 was in recirculation during the WMT2 discharge and sampling was also being performed for WMT1. A valve being used as a boundary valve between the tanks had known seat leakage. Due to ineffective communications, the valve being used as a block valve was returned to its normal open position allowing the unplanned release. During the discharge of WMT2 and recirculation of WMT1 approximately
o I e 160 gallons of WMT1 liquid was discharged ; without sampling or permitting. An ; unplanned non-routine permit accounted ' for the released liquid from WMT1. The I whole body dose contribution for this l release was calculated to be 3.39E-07 { mrem. As a corrective action the leaking valve was repaired and returned to service. The Operations Radwaste status board was enhanced and its proper use ; emphasized to ensure adequate ; communication of equipment status.
-l 6.5.2 Failure to Meet Soecified Samolinc }
Recuirements ! e On January 11, 1994, Chemistry was .! preparing the quarterly composite sample j filters for shipment to an offsite vendor ! for Sr-89 and Sr-90 analysis. The sample i filter for the period October 5, 1993 at ! 08:00 through October 6, 1993 at 02:10 ! was missing. Table 4.11-2 of the ODCM requires that the primary plant
-ventilation system be sampled by l composite analysis for Sr-89 and Sr-90 quarterly. The missing sample filter r constitutes a missed surveillance due to failure to sample. ;
A change to the procedure was made to t prompt technicians to take extra i precautions to retain the filters for i strontium analysis. The Count Room Coordinator also performs an inventory of the filters and places them in the ! composite drawer and initials the accompanying paperwork to confirm that each filter was saved. j
# On January 19, 1994, at 18:13 the Unit 1 I Turbine Building Sump #2 radiation ;
monitor (1-RE-5100) had an alert alarm. The water passing through this monitor to . the LVW ponds was diverted to the co- ! current waste system. Chemistry sampled , the effluent and samples were less than minimum detectable activity. The monitor , was declared inoperable and the diversion l valve was manually realigned to the LVW. ! A work request was written on the monitor j due to the erroneous alarm and the ODCM ! I I i I
required actions when the monitor is inoperable were initiated. This condition requires the special condition surveillance for grab samples of the l Turbine Building sump effluent at 24 hour intervals. On January 20, 1994, at 15:41 new setpoints were implemented for 1-RE-5100 and at 17:24 the ODCM required actions were terminated when control room personnel declared 1-RE-5100 operable. It was believed (by the control room personnel) that the monitor diversion function was in automatic. On January 24, 1994, at 20:00 the Unit 1 reactor operator asked radwaste operators i to verify the condition of 1-RE-5100 l after overhearing discussions that the I diversion valve was in manual. The ! manual alignment was verified. This caused the required special condition surveillance for grab samples to be missed four times. The Plant Incident Report on this event determined the root cause to be verbal miscommunication between the radwaste operators and control room operators as to the condition of the diversion valve prior to termination of the LCOAR. The review of ;
- logs by operator and supervisory personnel did not recognize the abnormal conditions noted on the logs.
Based on this event, nomenclature changes and additional guidance on the operation of these divert valves were added to procedures. The event has been incorporated into operator training. The form used to implement required ODCM actions when the monitor is inoperable was revised to clarify nomenclature for the status of the diversion function.
- On March 5, 1994, at 14:27 Unit 2 was manually tripped. A relief valve on the feedwater heater water box lifted draining to the Unit 2 Turbine Building Sump 2-04. At 14:30 a loss of sample flow alarm for the Unit 2 Turbine
Building Sump 2-04 radiation monitor (2-RE-5100) was received in the control room. The flow from the sump was automatically diverted to the co-current waste system Waste Water Holdup Tanks (WWHT's). Radwaste operators were not informed of the alarm or diversion. At 17:10, (2 hours and 40 minutes after the diversion) the Field Support Supervisor reported the WWHT overflowing. A radwaste operator responded and found the WWHT overflowing to the condenser hotwell area and to the same Turbine Building Sump 2-04. The radwaste operator received permission from the Shif t Supervisor to realign the 2-RE-5100 divert valve to the LVW ponds. Approximately 12,000 gallons were released to the LVW ponds. These actions caused the required samples of ODCM 3.3.3.4-1.6 and 3/4.11.1.1 to be missed. The effluents from the WWHT and the Turbine Building Sump 2-04 should have been sampled prior to realignment. Radiological sampling by chemistry after the realignment verified the water was l less than the minimum detectable activity l l and the radiation monitor showed no i indication of radioactivity present af ter I the realignment. There was no release of radioactivity to the environment. o On August 7, 1994, the weekend coverage Environmental technician did not collect the required daily radiological water sample of the LVW system discharging through Outfall 101 to Squaw Creek Reservoir as required by ODCM Table l 4.11-1. The technician was knowledgeable of the required sample but no mechanism was in place to remind him to collect the sample. A " weekend coverage check off sheet" has been developed and implemented and a revision to the " Daily Environmental Activity Checklist" has been made to include the sampling requirements.
l l e On February 26, 1994, at 07:37 the i Control Room received an alarm on the South Wide Range Gas Radiation Monitor (WRGM) due to a " channel loss of sample flow." The alarm was acknowledged at 07:38 at the Unit 1 console but no further actions were initiated. Station procedure ALM-3200 requires operators to attempt to restart the sample pump, but this was not done. The loss of sample flow condition rendered the monitor inoperable, but this condition went unnoticed by operations personnel. I' l At approximately 12 : 00 while preparing to l initiate a containment vent release j permit, the Unit Supervisor discovered the inoperable WRGM monitor. After determining that there was no known ! reason for the pump to be inoperable, the i I pump was restarted at 12:12. The required special conditions for l continued operations with an inoperable WRGM are contained in ODCM Table 3.3-8, Action Statements 35, 36 and 37. One l action was not performed as required. The requirement to continuously collect particulate and iodine samples with auxiliary sampling equipment, per Action 37, was missed, since auxiliary sampling was not placed in service while the monitor was inoperable. Other requirements of Actions 35 and 36 were not missed since required backup monitoring instrumentation was in service and the WRGM was returned to an operable condition within time frame specified in the action statements plus the allowable 25% extension. The South WRGM was immediately restored to an operable condition upon starting the sample pump. All backup and associated monitors (North WRGM, North and South Vent 9 tack Particulate, Iodine and Gas (PIG) monitors, Auxiliary Building Vent Monitor, Safeguards Building Vent Monitor and Unit 1 and Unit 2 Containment PIG monitors) were operable
l and there was no indication of any unusual or unmonitored radioactive release during the period the South WRGM monitor was inoperable. Several corrective actions have been accomplished and others are being pursued as a result of this event. The alarm acknowledge function has been modified to require that each individual alarm be modified, rather than being able to acknowledge multiple alarms with one button. Numerous equipment malfunction alarms tend to reduce operator awareness and these equipment problems are being evaluated to reduce the number of problem , radiation moniter alarms received in the Control Room. More operator training scenarios are being added to the training ; program to give operators additional experience with the ODCM monitors and their associated action statements. ; 6.6 Resin Releases to the LVW Pond A total of 2770 f t' 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. ! 6.7 Chances to the_Licuid, Gaseous and Solid Waste Treatment Systems In accordance with the CPSES Process Control Program, Section 2.2a, major changes to the Radwaste Treatment 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 the SORC. During this reporting period no design modifications were approved or implemented involving major changes to Radwaste Treatment Systems. Although not considered a major change to a radwaste ; treatment system, the radioactive floor drain system was modified to eliminate large volumes of non-radioactive inputs into the system. This was accomplished by expanding the Component Cooling Water Drain system to include drains previously connected to the radioactive waste floor drains which only receive non-radioactive leakage. .
i l 6.8 Meteorolocical Monitorino Procram t In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 1994, is retained onsite. This data is available for , review by the NRC upon request. 6.9 hssessment of Doses 6.9.1 p_oses Due to Liauid Effluents 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 l on a quarterly and annual basis in Table 7.7. 6.9.2 Doses Due to Gaseous 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. 6.9.3 Dose Due to Radiciodines, Tritium and Particulates The doses to an infant, child, teen and adult , from radioiodines and particulates, for the i pathways listed in Part II, Table 2.4 of the ODCM, were calculated using the highest dispersion and deposition factors, as 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 through 7.12. , 1 1 l 1
s 6.9.4 40CFR190 Dose Evaluation ODCM Radiological Effluent Control 3.11.4 requires dose evaluations to demonstrate compliance with 40 CFR Part 190 only if the calculated quarterly or yearly doses exceed 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 1994 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 Boundary Three activities are considered in this evaluation: fishing on Squaw Creek Lake, recreation activities at the CPSES employee recreational area and site tours through the CPSES Visitors Center. The highest dose occurred in the evaluation for fishing, resulting in a dose of 2.28E-2 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 submersion. Liquid pathways are not considered since all doses are calculated at the point of cirewater discharge into the lake. 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. 1 l l
? ?. SECTION 7.0 TABLES l l
Table 7.1 BATCH LIOUID AND GASEOUS RELEASE
SUMMARY
Ouarter 1 Ouarter 2 Ouarter 3 Ouarter 4 A. Licuid Releases All Sources i Number of Batch Releases 6.10E+01 6.70E+01 6.70E+01 5.90E+01 j Total Time Period for Batch Rcleases (min) 1.64E+04 1.44E+04 2.02E+04 2.16E+04 - Maximum Time Period for a Batch Release (min) 4.48E+02 4.51E+02 5.05E+02 4.83E+02 l Average Time Period for a Batch Release (min) 2.70E+02 2.15E+02 3.01E+02 3.66E+02 l Minimum Time Period for a Batch Release (min) 2.00E+00 4.50E+01 3.30E+01 2.00E+00 l Average Stream Flow During Periods of Release (ft'/s) N/A N/A N/A N/A i l B. Gaseous Releases All Sources Number of Batch Releases 4.60E+01 4.00E+01 4.30E+01 3.20E+01 Total Time Period for Batch Releases (min) 1.50E+04 1.40E+04 1.40E+04 1.28E+04 Maximum Time Period for a Batch Release (min) 4.07E+02 7.21E+02 4.72E+02 7.21E+02 Average Time Period for a Batch Release (min) 3.26E+02 3.51E+02 3.25E+02 4.00E+02 Minimum Time Period for a Batch Release (min) 2.02E+02 2.11E+02 1.73E+02 1.86E+02 1 I i l i T-1 J l l l i
l I lll 4 00 00 r 0 0 e + + t E E r 0 0 a 0 0 u . . O 0 0 3 14 00 r 0 0 e - + t E E r 2 0 a 8 0 u Q 1 0 Y R A 2 M 00 00 M r 0 0 e + + U t E E S r 0 0 a 0 0 E u . S O 0 0 A E L E 1 R 00 21 r 0 0 S e + - t E E U r 0 8 O a 0 6 E u . 2 S O 0 9 A 7 G 2 E D - L N T B A A T D I U O I L H C T A B L A M R O i i N C C B A d d e e s s a a e e sl sl ee ee sR sR a a ey ey lt lt ei ei Rv Rv i i ft ft oc oc s A A d r r i el s el u ba e ba c mt s mt i uo a uo L NT G NT A B
TABLE 7.3 l 1 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Units Quarter Quarter Quarter Quarter Est. Total i 1 2 3 4 E_ror, % A. Fis=sion and Activation Gases
- 1. Total release Ci 1.22E+00 3.24E-01 2.97E-01 3.57E-01 2.35E+01
- 2. Average release rate for pCi/sec 1.57E-01 4.12E-02 3.74E-02 4.49E-02
_ period
- 3. Percent of ODCM REC % 2.37E-04 9.61E-05 1.79E-04 1.05E-04 limit (Total Body Dose Rate)
- 4. Percent of ODCM REC % 3.91E-05 8.34E-06 1.14E-05 9.16E-06 limit (Skin Dose Rate) l B. Iodines 1
- 1. Total Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N/A
- 2. Average release rate for pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 period
- 3. Percent of ODCM REC % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 limit (Organ Dose Rate)
C. Particulates
- 1. Particulates with half Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N/A lives > 8 days
- 2. Average release rate fcr pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 period
- 3. Percent of ODCM REC % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 limit (Organ Dose Rate)
- 4. Gross alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i radioactivity D. Tritium f
- 1. Total release Ci 1.18E+00 2.56E+00 2.98E+00 1.88E+00 2.38E+01
- 2. Average release rate for pCi/sec 1.52E-01 3.25E-01 3.74E-01 2.36E-01 period
- 3. Percent of ODCM REC % 1.11E-03 2.38E-03 2.73E-03 1.72E-03 limit (Organ Dose Rate)
T-3
TABLE 7.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter i l 1 2 1 2
- 1. Fission and Activation Gases i l
l Ar-41 Ci 0.00E+00 0.00E+00 2.57E-01 1.15E-01 l Kr-85M Ci 0.00E+00 0.00E+00 2.21E-03 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 8.38E-01 0.00E+00 l Kr-87 Ci 0.00E+00 0.00E+00 5.11E-03 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 4.88E-03 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 8.23E-04 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 2.23E-03 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 6.82E-02 2.08E-01 2 Xe-135M Ci 0.00E+00 0.00E+00 1.1SE-02 0.00E+00 l Xe-135 Ci 0.00E+00 0.00E+00 1.17E-02 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 2.21E-02 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 1.22E+00 3.24E-01
- 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 0.00E+00 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates H-3 Ci 1.13E+00 2.53E+00 5.61E-02 3.20E-02 Total for period Ci 1.13E+00 2.53E+00 5.61E-02 3.20E-02 T-4
TABLE 7.4 (con't.) GASEOUS EFFLUENTS--GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4
- 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 2.30E-01 1.27E-01 Xe-133 Ci 0._00E+00 0.00E+00 6.70E-02 2.27E-01 Xe-135 Ci .00E+00 0.00E+00 6.13E-05 2.95E-03 Total for period Ci 0.00E+00 0.00E+00 2.97E-01 3.57E-01
- 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 0.00E+00 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates H-3 C1 2.94E+00 1.75E+00 3.29E-02 1.25E-01 ,
I Total for period Ci 2.94F+00 1.75E+00 3.29E-02 1.25E-01 T-5 l l l
. . ~
TABLE 7.5 LIOUID EFFLUENTS--SUMMATION OF ALL RELEASES Units Quarter Quarter Quarter Quarter Est. Total 1 2 3 4 Error, %
.s A. Fission and Activation Products
- 1. Total release (not Ci 7.97E-02 6.87E-02 2.80E-02 7.24E-02 3.03E+01 including tritium, gases, alpha)
- 2. Average diluted pCi/ml 1.74E-09 1.36E-09 3.69E-10 9.47E-10 concentration during period
- 3. Percent of ODCM REC % 9.68E-03 6.76E-03 2.94E-03 5.80E-03 li' nit B. Tritium
- 1. Total release Ci 1.51E+02 2.23E+02 2.70E+02 2.44E+02 2.34E+01
- 2. Average diluted pCi/ml 3.29E-06 4.43E-06 3.56E-06 3.19E-06 concentration during period
- 3. Percent of ODCM REC % 3.29E-01 4.43E-01 3.56E-01 3.19E-01 limit C. Dissolved and Entrained Gases
- 1. Total release Ci 2.68E-04 1.01E-03 9.99E-04 3.14E-03 1.16E+01
- 2. Average diluted pCi/ml 5.85E-12 2.00E-11 1.32E-11 4.11E-11 concentration during period
- 3. Percent of ODCM REC % 2.92E-06 9.99E-06 6.60E-06 2.06E-05 limit D. Gross Alpha Radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N/A 2
E. Volume of easte released Liters 3.60E+06 3.10E+06 4.36E+06 4.54E+06 2.20E+00 (prior to dilution) F. Volume dilution of water Liters 4.59E+10 5.04E+10 7.57E+10 7.65E+10 1.00E+01 used during period (Note 1) Note 1: The dilution volume reported is the total dilution volume during periods when effluent releases were occurring. The additional dilution volume available when there are no effluent releases occurring is not included. T-6
l TABLE 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 1.51E+02 2.23E+02 Na-24 Ci 0.00E+00 0.00E+00 4.23E-05 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 2.33E-04 5.34E-04 Mn-54 Ci 0.00E+00 0.00E+00 3.04E-04 3.65E-04 Fe-55 Ci O.00E+00 0.00E+00 5.41E-02 5.20F-02 Co-57 Ci 0.00E+00 0.00E+00 3.40E-05 c .17E-06 Co-58 Ci 0.00E+00 0.00E+00 1.35E-02 6.10E-03 Fe-59 Ci 0.00E+00 0.00E+00 1.89E-64 2.19E-03 Co-60 Ci 0.00E+00 0.00E+00 4.63E-03 4.24E-03 Zn-65 Ci 0. 0 0,Ef LO, .4J 00E+00 9.26E-06 0.00E+00 As-76 Ci 0.00E+00 G00E+00 2.73E-06 0.00E+00 Br-82 Ci 0.0 9 00 O j E+00 2.90E-05 6.18E-06 Y-93 Ci 0.00E+00 0.QvS+00 3.39E-05 0.00E+00 Zr-95 Ci 0.00E+00 Og dq+p0 1.26E-04 2.28E-05 Nb-95 Ci 0.00E+00 0.00E+00 2.80E-04 9.65E-05 Nb-97 Ci 0.00E+00 0.00E+00 1.55E-05 4.23E-06 Mo-99 Ci 0.00E+00 0.00E+00 5.58E-05 1.16E-05 Tc-99M Ci 0.00E+00 0.00E+00 5.44E-05 1.13E-05 Ru-103 Ci 0.00E+00 0.00E+00 3.37E-0( 0.00E+00 Aa-110M Ci 0.00E400 0.00E400 8.42E-05 1.51E-05 Sn-113 Ci 0.00E+00 0.00E+00 5.69E-05 3.53E-06 In-113M Ci 0.00E+00 0.00E+00 7.74E-05 4.62F-06
., 'W4 Ci O.00E+00 0.00E+00 3.59E-04 7.68E-05 Sb-125 Ci 0.00E+00 0.00E+00 4.31E-03 2.23E-03 I - 13 '; Ci 0.00E+00 0.00E+00 1.29E-04 1.06E-05 Te-132 Ci 0.00E+00 0.00E+00 2.98E-06 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 5.74E-05 0.00E+00 JL-J 3 4 Ci 0.00E+00 0.00E+00 3.46E-04 2.90E-04 u d r-137 Ci 0.00E+00 0.00E+00 5.13E-04 4.66E-04 Ce-144 Ci 0.00E+00 0.00E+00 8.43E-05 6.34E-05 l 1
Total for period Ci 0.00E+00 0.00E+00 1.51E+02 2.23E+02 T-7
l l TABLE 7.6 (continued) LIOUID EFFLUENTS ! l 1 Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Kr-85 . Ci 0.00E+00 0.00E+00 0.00E+00 8.98E-05 Xe-133 Ci 0.00E+00 0.00E+00 2.59E-04 9.15E-04 Xe-135 Ci 0.00E+00 0.00E+00 9.30.5-06 2.71E-06 Total for nerio.' Ci 0.00E+00 0.00E+00 [, Qgl 1.01E-03 : T-8
TABLE 7.6 (continued) LIOUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quhrter Quarter Quarter Quarter 3 4 3 4 H-3 Ci 0.00E+00 0.00E400 2.70E+02 2.44E+02 Na-24 Ci O.00E+00 0.00E+00 3.89E-05 3.58E-05 Cr-51 Ci 0.00E+00 0.00E+00 8.01E-04 3.77E-03 Mn-54 Ci 0.00E+00 0.00E+00 3.02E-04 1.17E-03 Fe-55 Ci 0.00E+00 0.00E+00 1.34E-02 3.36E-02 Co-57 Ci O.00E+00 0.00E+00 2.30E-06 1.74E-05 Co-58 Ci 0.00E+00 0.00E+00 6.15E-03 1.55E-02 Fe-59 Ci 0.00E+00 0.00E+00 2.61E-03 2.47E-03 Co-60 Ci O.00E+00 0.00E+00 1.76E-03 4.30E-03 Zn-65 Ci 0.00E+00 0.00E+00 2.81E-07 1.91E-07 Br-82 Ci 0.00E+00 0.00E+00 1.59E-06 7.48E-06 Zr-95 Ci 0.00E+00 0.00E+00 5.39E-05 2.68E-04 Nb-95 Ci 0.00E+00 0.00E+00 1.21E-04 7.36E-04 Nb-97 Ci 0.00E+00 0.00E+00 0.00E+00 2.20E-05 Mo-99 Ci 0.00E+00 0.00E+00 1.19E-06 1.46E-05 Tc-99M Ci 0.00E+00 0.00E+00 1.16E-06 1.42E-05 Ru-105 Ci 0.00E+00 0.00E+00 0.00E+00 1.09E-05 An-110M Ci 0.00E+00 0.00E+00 3.48E-06 5.10E-05 Sn-113 Ci 0.00E+00 0.00E+00 4.35E-07 8.31E-05 In-113M Ci 0.00E+00 0.00E+00 5.39E-07 1.09E-04 Sb-122 Ci 0.00E+00 0.00E+00 0.00E+00 2.96E-04 Sb-124 Ci 0.00E+00 0.00E+00 5.12E-05 2.96E-03 Sb-125 Ci 0.00E+00 0.00E+00 1.84E-03 6.11E-03 I-131 Ci 0.00E+00 0.00E+00 3.00E-06 6.36E-05 _,_T-133 Ci 0.00E+00 0.00E+00 0.00E+00 1.24E-05 Ci 0.00E+00 0.00E+00 2.9BE-04 2.12E-04 f,Js-134 __ Cs-137 Ci 0.00E+00 0.00E+00 5.08E-04 3.76E-04 La-140 Ci 0.00E+00 0.00E+00 0.00E+00 3.65E-08 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 1.50E-04 Total for neriod Ci 0.00E+00 0.00E+00 2.70E+02 2.44E+02 T-9
~1 1
TABLE 7.6 (continued) LIOUID EFFLUENTS 1 Continuous Mode Batch Mode ' Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 1.26E-09 Xe-133 Ci 0.00E+00 0.00E+00 9.93E-04 3.07E-03 Xe-135 Ci 0.00E+00 0.00E400 5.82E-06 7.44E-05 Total for neriod Ci 0.00E+00 0.00E+00 9.99E-04 3.14E-03 TABLE 7.7 DOSES FROM LIOUID EFFLUENTS (mrem) Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Body Quarter 1 2.12E-03 1.45E-02 1.36E-02 1.12E-02 1.22E-02 1.17E-02 1.41E-02 % Limit 2.12E-02 1.45E-01 4.52E-01 1.12E-01 1.22E-01 1.17E-01 1.41E-01 per unit _ Quarter 2 1.67E-03 1.33E-02 1.25E-02 1.06E-02 1.14E-02 1.10E-02 1.16E-02 % Limit 1.67E-02 1.33E-01 4.17E-01 1.06E-01 1.14E-01 1.10E-01 1.16E-01 per unit Quarter 3 1.31E-03 1.60E-02 1.54E-02 1.38E-02 1.45E-02 1.41E-02 1.49E-02 % Limit 1.31E-02 1.60E-01 5.10E-01 1.38E-01 1.45E-01 1.41E-01 1.49E-01 per unit Quarter 4 1.17E-03 1.81E-02 1.76E-02 1.63E-02 1.68E-02 1.66E-02 2.22E-02 % Limit 1.17E-02 1.81E-01 5.85E-01 1.63E-01 1.68E-01 1.66E-01 2.22E-01 per unit Total 6.26E-03 6.20E-02 5.90E-02 5.18E-02 5.50E-02 5.34E-02 6.28E-02 1994 % Limit 3.13E-02 3.10E-O' 9.85E-01 2.59E-01 2.75E-01 2.67E-01 3.14E-01 per unit T-10
TABLE 7.8 DOSES FROM GASEOUS EFFLUENTS Noble Gas Air Dose (mrad) Air Dose (mrad) Gamma Air Beta Air Quarter 1 2.93E-04 2.89E-04
% Limit per unit 5.86E-03 2.89E-03 Quarter 2 1.20E-04 6.24E-05 % Limit per unit 2.40E-03 6.24E-04 Quarter 3 2.26E-04 8.64E-05 % Limit per unit 2.26E-03 4.32E-04 Quarter 4 1.33E-04 6.93E-05 % Limit per unit 1.33E-03 3.46E-04 Total 1994 7.72E-04 5.07E-04 % Limit per unit 3.86E-03 1.27E-03 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 1.01E-03 1.01E-03 1.01E-03 1.01E-03 1.01E-03 1.01E-03 0.00E+00
% Limit 0.00E+00 6.70E-03 6.70E-03 6.70E-03 6.70E-03 6.70E-03 6.70E-03 0.00E+00 per Unit Qtr-2 0.00E+00 2.18E-03 2.18E-03 2.18E-03 2.18E-03 2.18E-03 2.18E-03 0.00E+00
% Limit 0.00E+00 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 0.00E+00 per Unit Qtr-3 0.00E+00 2.54E-03 2.54E-03 2.54E-03 2.54E-03 2.54E-03 2.54E-03 0.00E+00
% Limit 0.00E+00 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 0.00E+00 per Unit Qtr-4 0.00E+00 1.60E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 0.00E+00
% Limit 0.00E+00 1.07E-02 1.07E-02 1.07E-02 1.07E-02 1.07E-02 1.07E-02 0.00E+00 per Unit Total 0.00E+00 7.31E-03 7.31E-03 7.31E-03 7.31E-03 7.31E-03 7.31E-03 0.00E+00 1994
% Limit 0.00E+00 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-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 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 0.00E+00
% Limit 0.00E+00 7.71E-03 7.71E-03 7.71E-03 7.71E-03 7.71E-03 7.71E-03 0.00E+00 per Unit Otr-2 0.00E+00 2.49E-03 2.49E-03 2.49E-03 2.49E-03 2.49E-03 2.49E-03 0.00E+00
% Limit 0.00E+00 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 0.00E+00 per Unit Qtr-3 0.00E+00 2.90E-03 2.90E-03 2.90E-03 2.90E-03 2.90E-03 2.90E-03 0.00E+00
% Limit 0.00E+00 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 0.00E+00 per Unit Qtr-4 0.00E+00 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 0.00E+00
% Limit 0.00E+00 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E 1.22E-02 0.00E+00 per Unit Total 0.00E+00 8.39E-03 8.39E-03 8.39E-03 8.39E-03 8.39E-03 8.30E-03 0.00E+00 1994 i
l t Limit 0.00E+00 2.81E-02 2.81E-02 2.81E-02 2.81E-02 2.81E-02 2.81E-02 0.00E+00 per Unit r T-13 1
TABLE 7.11 DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Child Age Group, (mrem) Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 0.00E+00 1.66E-03 1.66E-03 1.66E-03 1.66E-03 1.66E-03 1.66E-03 0.00E+00
% Limit 0.00E+00 1.10E-02 1.10E-02 1.10E-02 1.10E-02 1.10E-02 1.10E-02 0.00E+00 per Unit Qtr-2 0.00E+00 3.58E-03 3.58E-03 3.58E-03 3.58E-03 3.58E-03 3.58E-03 0.00E+00
% Limit 0.00E+00 2.40E-02 2.40E-02 2.40E-02 2.40E-02 2.40E-02 2.40E-02 0.00E+00 per Unit Qtr-3 0.0CE+00 4.16E-03 4.16E-03 4.16E-03 4.16E-03 4.16E-03 4.16E-03 0.00E+00
% Limit 0.00E+00 2.78E-02 2.78E-02 2.78E-02 2.78E-02 2.78E-02 2.78E-02 0.00E+00 per Unit I
Qtr-4 0.00E+00 2.64E-03 2.64E-03 2.64E-03 7.64E-03 2.64E-03 2.64E-03 0.00E+00
% Limit 0.00E+00 1.75E-02 1.75E-02 1.75E-02 1.75E-02 1.75E-02 1 75E-02 0.00E+00 per Unit l
Total 0.00E+00 1.21E-02 1.21E-02 1.21E-02 1.21E-02 1.21E-02 1.21E-02 0.00E+00 1994
% Limit 0.00E+00 4.02E-02 4.02E-02 4.02E-02 4.02E-02 4.02E-02 4.02E-02 0.00E+00 per Unit T-14 u _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . ____
TABLE 7.12 DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Infant Age Group, (mrem) Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 0.00E+00 1.29E-03 1.29E-03 1.29E-03 1.29E-03 1.29E-03 1.29E-03 0.00E+00
% Limit 0.00E+00 8.50E-03 8.58E-03 8.58E-03 8.58E-03 8.58E-03 8.58E-03 0.00E+00 per Unit Otr-2 0.00E+00 2.78E-03 2.78E-03 2.78E-03 2.78E-03 2.78E-03 2.78E-03 0.00E+00
% Limit 0.00E+00 1.86E-02 1.86E-02 1.86E-02 1.86E-02 1.86E-02 1.86E-02 0.00E+00 per Unit Qtr-3 0.00E+00 3.24E-03 3.24E-03 3.24E-03 3.24E-03 3.24E-03 3.24E-03 0.00E+00
% Limit 0.00E+00 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 0.00E+00 per Unit Qtr-4 0.00E+00 2.04E-03 2.04E-03 2.04E-03 2.04E-03 2.04E-03 2.04E-03 0.00E+00
% Limit 0.00E+00 1.37E-02 1.37E-02 1.37E-02 1.37E-02 1.37E-02 1.37E-02 0.00E+00 per Unit Total 0.00E+00 9.37E-03 9.37E-03 9.37E-03 9.37E-03 9.37E-03 9.37E-03 0.00E+00 1994
% Limit 0.00E+00 3.12E-02 3.12E-02 3.12E-02 3.12E-02 3.12E-02 3.12E-02 0.00E+00 per Unit T-15
TABLE 7.13 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)
- 1. Type of waste Shipped Shipped Buried Buried m Ci m2 Ci
- a. Spent resins / filters 4.16E+01 1.08E+03 4.16E+01 1.08E+03
- b. Dry active waste 4.50E+02 3.75E-01 1.35E+01 4.44E-01
- c. Irradiated components d. Other (oil sent to 8.70E+00 1.81E-03 procesisor for incineration)
TOTAL 5.00E+02 1.08E+03 5.51E+01 1.08E+03 Includes 228.3 m' of suspected clean trash sent to offsite processor for monitoring before final disposition. Note: 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)
- a. Spent resins / filters Co-60 21.00 2.26E+02 Fe-55 20.50 2.20E+02 Cs-137 20.24 2.18E+02 Cs-134 15.59 1.68E+02 Ni-63 14.71 1.58E+02 l Co-58 4.22 4.54E+01 Mn-54 3.34 3.59E+01 f H-3 0.01 1.13E-01 C-14 0.15 1.67E+00 Tc-99 <1 1.95E-03 I-129 LLD Other* 0.24 2.62E+00 Total 100.00 1.08E+03
- Nuclides representing <1% of total shipped activity: Cr-51, Ni-59, Fe-59, Ag-110m, Sr-90, Ce-144, Pu-238, Pu-241, Cm-242, Cm243/244. j l
T-16
i i l 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 63.63 2.39E-01 Co-60 6.21 2.33E-02 Cr-51 1.22 4.59E-03 Cs-137 1.08 4.04E-03 Fe-55 21.35 8.00E-02 i
Fe-59 1.30 4.87E-03 H-3 0.30 1.14E-03 Mn-54 1.36 5.11E-03 Ni-63 2.83 1.06E-02 Tc-99 LLD I-129 LLD C-14 0.63 2.37E-03 Other* O.09 3.86E-04 Total 100.00 3.75E-01
- Nuclides representing <1% of total shipped activity: Sb-125, Zr-95, Nb-95, Cs-134, Ce-144.
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity Composition (by type of waste) (Ci)
- c. Other - Oil sent to processor for Co-58 72.05 1.31E-03 incineration Co-60 11.51 2.08E-04 Cr-51 6.45 1.17E-04 Cs-137 0.58 1.04E-05 Fe-55 3.86 6.99E-05 Ni-63 5.53 1.00E-04 H-3 <0.01 9.06E-08 C-14 0.02 3.11E-07 I Tc-99 LLD !
I-129 LLD Total 100.00 1.82E-03 l l l l T-17 l e-__-____-___________________. __. __ _ _ . _ _ _ __ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _
TABLE 7.13 (Continued) SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS
- r-
- 3. Solid Waste Disposition (Mode of Transportatic, ;. Truck)
Waste Type Waste Container Numbei of Destination Class Type Shipments
- a. Resin / filters A Poly
- HIC 3 Chem-Nuclear Barnwell,SC B Poly
- HIC 4 Chem-Nuclear Barnwell,SC C Poly
- HIC 2 Chem-Nuclear Barnwell,SC
- b. Dry active A Strong- 6 SEG waste tight Oak Ridge,TN A Strong- 6 **Quadrex tight Oak Ridge,TN
- High Integrity Container ** Name change to American Ecology B. Irradiated Fuel Shipments (Disposition)
Nurnber of Shioments Mode of Transoortation Destination 0 N/A N/A T-18
ATTACHMENT 8.1 OFFSITE DOSE CALCULATION MANUAL l FOR ; i TU ELECTRIC COMANCH$ PEAK . STEAM ELECTRIC' STATION I UNITS 1 AND 2 i l l l l
I l' i l 0FFSITE DOSE CALCULATION MANUAL FOR
. TU ELECTRIC CONANCHE PEAK STEAM ELECTRIC STATION ,
UNITS 1 AND 2 O I I l Rev8 01/93
TABLE OF CONTENTS'
- t y
List of Tables v List of Figures vii Cross Reference to Technical Specifications and REC viii References xi Introduction xii PART I - RADIOLOGICAL EFFLUENT CONTROLS ! l SECTION 1.0 - DEFINITIONS I 1-0 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 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 i Nonitoring Instrumentation 3/4.3.3.6 - Meteorological Monitoring I 3/4-13 ,
Instrumentation
- 3/4.7.15 - Sealed Source Contamination I 3/4-15 3/4.11.1 -
Liquid Effluents ! 3/4-17 3/4.11.1.1 - Concentration Controls I 3/4-17 3/4.11.1.2 - Dose I 3/A-21 j 3/4.11.1.3 - Liquid Radweste Treatment System I 3/4-22 l t 3/4.11.1.4 - LVW Pond Resin Inventory I 3/4-22a 3/4.11.2 Gaseous Effluents ! 3/4-23 3/4.11.2.1 - Dose Rate I 3/4-23 3/4.11.2.2 - Dose - Noble Gases I 3/4-27 4 3/4.11.2.3 - Dose - Iodine-131. I 3/4-28 lodine-133. Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4 - Gaseous Radwaste Treatment System I 3/4-29 COMANCHE PEAK - UNITS 1 AND 2 i Rev. 8 1/93
TABLE OF CONTENTS-(continuGd) Number / Title ,P_192 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 ComparisLn 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 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 Release Report i 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 l 1.1.4 ActualDilutionFactor(ADF) II 1-5 1.1.5 Required Dilution Factor (RDF) II 1-6 1.1.6 10CFR20 Compliance II 1-6 COMANCHE PEAK - UNITS 1 AND 2 11 REV. 10 4/94
p TABLE OF CONTENTS (continuid) Number / Title Pigg 1.2 Radiation Monitor Alarm Setpoints 11.1-7 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-5100and2RE-5100) 1.2.3 Service Water Effluent Radiation II 1-9 Monitors (1RE-4269/4270 and , 2RE-4269/4270) 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 l 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 t 2.1.2 Dose Rates Due to Radioiodines, 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) L 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) ) l COMANCHE PEAK - UNITS 1 AND 2 iii Rev. 9 9/93 l
TABLE OF CONTENTS (continued) .
. Number /T1tle E422 2.2.5 Containment Atmosphere Gaseous II 2-10 Monitors (1RE-5503/2RE-5503) .
2.3 Dose Calculati ons for Gaseous Effluents II 2-12 ' 2.3.1 Dose Due to Noble Gases II 2-12 2.3.2 Dose Due to Radiciodines, Tritium. II 2-13 and Particulates , 2.4 Dose Projections for Gaseous Effluents II 2-15 2.5 Dose Calculations to Support Other II 2-16 Requirements 2.6 Meteorological Model II 2-18 e I 2.6.1 Dispersion Calculations II 2-18 2.6.2 Deposition Calculations II 2-20 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 ' 3.2 Interlaboratory Comparison Program II 3-1 APPENDICES A. Pathway Dose Rate Parameter A-1 B. Inhalation Pathway Dose Factor B-1 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 . F. Vegetation Pathway Dose Factor F-1 l G. Supplemental Guidance Statements - Deleted G-1 ; l I i COMANCHE PEAK - UNITS 1 AND 2 iv 9/93
List of Tables Table No. Title Pigg PART I - RADIOLOGICAL EFFLUENT CONTROLS l 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 i Instrumentation 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 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 Program 4.1l-2 Radioactive Gaseous Waste Sampling and I 3/4-24 . Analysis Program 3.12-1 Radiological Environmental Monitoring I 3/4-34 Program 3.12-2 Reporting Levels for Radioactivity I 3/4-40 Concentrations in Environmental Samples 4.12-1 Detection Capabilities for Environmental I 3/4-41 Sample Analysis (LLDs) PART II - CALCULATIONAL METHODOLOGIES 1.1 Summary of Liquid Release Pathways II 1-19 1.2 Site Related Ingestion Dose Commitment II 1-20 Factor (At) 2.1 Summary of Gaseous Release Pathways II 2-26 2.2 Dose Factors for Exposure to a Semi- II 2-27 Infinite Cloud of Noble Gases 2.3 Pathway Dose Rate Parameter (Pj) II 2 28 COMANCHE PEAK - UNITS 1 AND 2 y Rev. 8 1/93
kI
- $
- List of Tables Table No. Titig Eggg 2.4 Pathway Dose Factors II 2-29 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 t [
?
COMANCHE PEAK - UNITS 1 AND 2 vi Rev. 8 1/93
List of Fioures Fioure Title Eggg 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 !! 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 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 2.5 Open Terrain Correction Factor II 2-56 3.1 Radiological Environmental Monitoring II 3-9 Locations COMANCHE PEAK - UNITS 1 AND 2 vii Rev. 8 1/93
1 Cross Reference to Technical Snecifications and REC Number or Document Section Reauirement ODCM Section ! i PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC) Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and ! 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 I 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.5 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 3/4.11.2.4 Tech Specs 6.8.3..!.6 Effluent treatment systems 3/4.11.1.3 and e operability requirements 3/4.11.2.4
~
Tech S'p'ecs 6.8.3.e.7 Limit gaseous effluent dose rate 3/4.11.2.1
~ ~
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 l particulate dose Tech Specs 6.8.3.e.10 Limit total dose 3/4.11.4 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 j Tech Specs 6.8.3.f.3 Interlaboratory Comparison Program 3/4.12.3 j PART II - CALCULATIONAL METHODOLOGIES REC 3/4.11.1.1 Liquid effluent concentration 1.1 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 l COMANCHE PEAK - UNITS 1 AND 2 viii Rev. 8 1/93 i l
L CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC L (continued) l Number or Document Section Reauirement ODCM Section REC 3/4.11.2.1.a Dose rate due to noble gases 2.1.1 . l REC 3/4.11.2.1.b Dose rate due to iodine, 2.1.2 tritium, and particulates with half-lives greater than eight days 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 with half-lives greater I 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 radioaccivity and direct radiation 1 REC 3/4.12.1 Description of radiological 3.1 l environmental sampling l locations 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)
- turbine building sump 1.2.2 monitors (1RE-5100 and 2RE-5100)
- 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
l Cross Reference to Technical Specifications and REC Number or Document Section Reauirement 00CN Section j
.3.3.3.5 Radioactive gaseous' effluent
~
REC monitoring channels alarm / trip I setpoints l
)
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) l XRE-5567A and XRE-55678 (PIG noble gas channel) o waste gas holdup system monitor 2.2.4 (auxiliary building vent monitor) XRE-5701 o sampler flow rate monitor 2.2.3 XFT-5570A2/82 I l Tech Specs 3.3.3.1 Radiation monitoring channels alare/ trip setpoint
... 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 l 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
- - . . . _ , ~ , . REFERENCES p
- 1. Boegli, J.S., R. R. Bellamy. W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
i
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with .
10CFR Part 50 Appendix I. V. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
- 3. " Environmental Report," TV Electric Comanche Peak Steam Electric Station.
l 4. " Final Safety Analysis Report," TU Electric, Comanche Peak Steam Electric Station.
- 5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors. U.S. NRC Regulatory Guide 1.111 (March 1976).
- 6. Methods for Estimating. Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from iIght - 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.
Department of Commerce (July 1968).
- 8. " Technical Specifications," TU Electric Comanche Peak Steam
. Electric Station.
- 9. Implementation of Programmatic Controls for Radiological Effluent 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 Process Control Program.(Gen:ric Letter 89 01), USNRC, January 31, 1989.
- 10. CPSES Technical Evaluation No. RP-90-3077 " Calculation of Site ,
Related Ingestion Dose Commitment Factors For Sb-122."
]l
- 11. " Calculation of Annual Doses to Man from Routine Releases of l Reactor Effluents for the Purpose of Evaluating Compliance with l 10 CFR Part 50 Appendix I," USNRC Regulatory Guide 1.109 (March l 1976). j
- 12. Code of Federal Regulation Title 10. Parts 20 and 50.
I l l COMANCME PEAK - UNITS 1 AND 2 xi Rev. 8 1/93
fNTRODUCTION ! The OFFSITE DOSE CALCULATION MANUAL (00CM) is a supporting document of the i CPSES Techni 41 Specifications. Part I of the 00CM contains (1) the ) Radioactive Effluent Controls and Radiological Environmental Monitoring i Programs required by Technical Specification 6.8.3, (2) descriptions of the J information that should be included in the Annual Radiological Environmental 10 Operating and Annual Radioactive Effluent Release Reports requjred by Technical Specifications 6.9.1.3 and 6.9.1.4, and (3) Controls for Meteorological Monitoring Instrumentation and Sealed Source Leakage. Part II i of the ODCM describes the methodology and parameters to be used in the I 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. Part II of.the 00CM also contains a list and graphical description of the specific sample locations for the ; radiological environmental monitoring program. Liquid and Gaseous Radwaste 1 Treatment System configurations are shown in Part II, Figures 1.1 and 2.1. 1 The 00CM will be maintained at the plant for use as a reference guide and training document on accepted methodologies 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 i areas. TU Electric initiated changes to the 00CM will be implemented in ; accordance with Section 6.14 of the Technical Specifications. The 00CM follows the methodology and models suggested by NUREG-0133 (Ref. 1) and Regulatory Guide 1.109 Revision 1 (Ref. 2). Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements. This simplified approach will result in a more conservative dose evaluation, but requires the least amount of time for establishing compliance with regulatory requirements. 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 becom! available and are validated that can reliably, economically and properly perform these ' more complex calculations. A beneficial approach to implementintj the 10 Radiological Effluent Control Program and Regulatory Guide 1.21 (Annual Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses. COMANCHE PEAK - UNITS 1 AND 2 xii REV. 10 ! 4/94 !
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S I i I I i ( COMANCHE PEAK UNITS 1 AND 2 1/93 ,
> _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - , . . , ~ . . . , . _ _ . _ . - . - . , _ . - , _ . . . - . - . , , - - - . - , . ,
.,,I
r SECTION 1.0 DEFINITIONS e e COMANCHE PEAK UNITS 1 AND 2 PART I 1-0 1/93
1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Controls. ACTION 1.1 ACTION shall be that part of a Control which prescribes remedial measures required under designated conditions. ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERA 81LITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the 1 alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy. CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to 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 performed by any series of sequential, overlapping, or total channel ste W such that the entire channel is calibrated. CHANNEL CHECK 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 with other indications and/or status derived from independent instrument channels measuring the same parameter. DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions. i I COMANCHE PEAK UNITS 1 AND 2 PART I 1-1 1/93
l l DEFfNITIONS l
)
DOSE EOUIVALENT I-131 l l 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 l (microcurie / gram) which alone would produce the same thyroid dose as the * ' quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 l actually present. The thyroid dose conversion factors used for this l calculation shall be those listed in Table III of TID-14844, " Calculation of .' Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977. FREOUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. HEMBER(S) 0F THE PUBLIC 8 1.18 MEMBER (S) 0F THE PUBLIC means an individual in a CONTROLLED AREA or UNRESTRICTED AREA. Individuals are not MEMBERS OF THE PUBLIC if they are employees of the licensee, its contractors or vendors. Also excluded from . this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the. plant. OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from 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 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmertal Monitoring Programs required by Section 6.8.3 and (2) descriptions ut the information that should be included in the Annual Radiological Environmental 10 Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4. OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERA 8ILITY when 1;. 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 also capable of performing their related support function (s). l l 1 COMANCHE PEAK - UNITS 1 AND 2 PART I 1-2 REV. 10 4/94
DEFINITI0WS ! i OPERATIONAL PG E - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one e inclusive combination of core reactivity condition, power level, and i average reactor coolant temperature specified in Table 1.2. i f PRIMARY PLANT VENTILATION SYSTEM 1.24 A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and ; installed to reduce gaseous radiciodina or radioactive material in j particulate form in effluents by passing ventilation or vent exhaust gases i through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the . release to the environment. Such a system is not considered to have any , effect on noble gas effluents. ! PURGE - PURGING 1.26 PURGE or PURGING shall be the controlled process of discharging air ; or gas from a confinement to maintain temperature, pressure, humidity, t concentration or other operating conditions, in such a manner that i replacement air or gas is required to purify the confinement' RATED THERMAPPOWER f 1.29 RATED THERMAL POWER shall be a total reactor core heat transfer rate ; to the re ctor coolant of 3411 MWt. REPDFI/2 C EVENT 1.31 A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73. i 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. THERMAL POWER 1.38 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. COMANCHE PEAK UNITS 1 AND 2 PART I 1-3 1/93
DEFINITIONS r UNRESTRICTED AREA 1.41 An UNRESTRICTED AREA means any area be_ yond the SITE 80VNDARY. 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, e used in system names, does not imply a VENTING process. WASTE GAS HOLDUP SYSTEM , 1.43 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed 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. CONTROLLED 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 limit 6d by the licensee for any reason. REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 1-4 1/93
TABLE 1.1 FRE00ENCY NOTATION NOTATION FREQUENCY 5 At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days 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. 9 COMANCHE PEAK UNITS 1 AND 2 PART I 1-5 01/93
TABLE 1.2 OPERATIONAL MODES i AVERAGE REACTIVITY % RATED COOLANT ggg CONDITION. K e rr THERMAL POWER
- TEMPERATURE ,
- 1. POWER OPERATION 1 0.99 > 5% 1 3500F
- 2. STARTUP 1 0.99 s 5% 1 3500F
- 3. HOT STANDBY < 0.99 0 1 3500F -
- 4. HOT SHUTDOWN < 0.99 0 3500F>Tavg
> 2000F i
- 5. COLD SHUTDOWN < 0.99 0 5 2000F
- 6. REFUELING ** 5 0.95 0 5 1400F
- Excluding decay heat. !
** Fuel in th.e reactor vessel witn u.. . sel head closure bolts less than fully tdnsidned or with the head removed.
7 1 7 COMANCHE PEAK - UNITS 1 AND 2 PART I 1-6 01/93 i
l l SECTION 2.0 NOT USED i COMANCHE PEAK UNITS 1 AND 2 PART I 2-0 01/93 l 1
l' t b' SECTIONS 3.0 AND 4.0 CONTROL 5 l AND SURVEILLANCE REQUIREMENTS
?
1 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-0 ,,j,3
- - ~ . . . . - . .. -. - - . - . - - - -
i 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY f ; CONTROLS i 3.0.1 Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified , therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION requirements are not met within the . specified time intervals. If the Control fs restored prior to expiration of the specified time intervals, completion of the ACTION requirements is ; not required. ; 3.0.3 When i Control is not met, except as provided in the associated i ACTION requ rements, within 1 hour action shall be initiated to place the i unit in a It00E in which the specification does not apply by placing it, as : applicable, in
- a. At least HOT STANDBY within the next 6 hours,
- b. At least HOT SHUTDOWN within the following 6 hours, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ; ACTION requfrerents, the action may be taken in accordance with the specified time Jimits 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 OPERATICMil M00E or other specified condition shall not be made when the conditions "or the Control are not met and the associated ACTION requires a shstdown if they are not met within a specified time interval. E' tt
- into an OPERATIONAL MODE or specified condition may be made 'n dr:r(eance with ACTION requirements when '
conformance to them irt.ite ce7t'nued operation of the facility for an ; unlimited period of time., this t'ovision shall not prevent passage through or to OPERATIONAL M CEJ n r#re h to comply with ACTION requirements. ! Exceptions to these requirement < are stated in the individual controls. ' i i The associated basis from the CPSES Technical Specifications applies to i this section. t COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-1 1/93 i
APPLICABILITY iggyLILLANCE REOUIREMENTS _ 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. 4.0.2 Each Surveillance Requirement shall be performed within the 7 specified time interval with a maximum allowable extension not to exceed 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 j constitute noncompliance with the OPERABILITY 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 ACT!6d requirements may be delayed for up to 24 hours to perr.it the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do 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 specified. 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. l i COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-2 1/93
INSTRUMENTATION PADI0 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. I
- b. With less than the minimum number of radioactive liquid en' fluent '
monitoring instrumentation channels ~0PERABLE, take the ACTION shown in l 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 currected in a timely manner. *
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.3.4 Each radioactive liquid 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 4.3-3. C0HANCHE PEAK UNITS 1 AND 2 PART I 3/4-3 REV. 10 l 4/99
IMLE 3.3-7 8 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION M MINIMUM c CHANNELS
- =
g INSTRLKNT OPERABLE ACTION g 1. Radioactivity Monitors Providing Alarm and n 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 t' 8 (1RE-5100 & 2RE-5100)
[ 9 10 c. Auxiliary Building to LVW Pond Liquid Effluent Line 1 31A (XRE-5251A)
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
- a. Service Water System Effluent Lines 1/ train 32 8 (1RE-4269, 1RE-4270, 2RE-4269 & 2RE-4270) un
'g'.2 3. Flow Rate Measurement Devices G
- a. Liquid Radweste Effluent Line (XFT-5288) 1 33
h TABLE 3.3-7-(Continued)- ACTION STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimus' Channels OPERABLE requirement, effluent releases via this P pathway may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1; and
- b. At least two technically qualified members of the facility staff independently verify the release rate. calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 31- With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this 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:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131; or
- b. At least once per 24 hours when the specific activity of the-secondary coolant is less than or equal to 0.01 microcurie / gram 8 DOSE EQUIVALENT I-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)
10 ACTION 31A-With number of channels OPERABLE less than required by the Minimum Channels OPERABLE 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 /ml at least once per 12 hours. ACTION 32- With the number of channels OPERABLE less than required by the Minimum Chennels OPERABLE requirement, operations may continue provided that: 11 a. With the component cooling water monitors (uRE-4509, uRE-4510, & uRE-4g11)*OPERABLEandindicatinganactivityoflessthan 1X10~ microcurie /m1, a grab sample is collected and analyzed f radioactivityatalowerlimitofdetectionofnomorethan10-9r microcurie /m1 at least every 31 days; or
- b. At least once per 12 hours, 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)
~ '
ACTION 33- With the number 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 hours during actual releases. Pump performance curves generated in place may be used to estimate flow. l l I COMANCHE PEAK UNITS 1 AND 2 PART I 3/4 Sa 4/94
7-1 - i l n TABLE 4.3-3 ' , z RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l 9 ANALOG DIGITAL A CHANNEL CHANNEL R CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL c INSTRUMENT CHECK CHECK CALIBRATION TEST TEST 2'i d 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release l 5 a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. Q(1)
- b. Turbine Building (Floor Drains) Sumps 8 Effluent Lines (1RE-5100 & 2RE-5100) D M R(4) N.A. Q(2)
, 9 c. Auxiliary Building to LVW Pond Liquid D M R(4) N.A. Q(2) g Effluent Line (XRE-5251A) w
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release E a. Service Water System Eff iuent Lines 8 (1RE-4269, 1RE-4270, 2RE-4269 & 2RE-4270) D M R(4) N.A. 'Q(3)
- 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent Line l (XFT-5288) 0(5) N.A. R Q N.A.
i 3.*
, TABLE 4.3-3 (Continued)
TABLE NOTATIONS (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:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint; or
- b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic flow diversion of this pathway _(from the Low Volume Waste Treatment System 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 Alare/ Trip Setpoint; or 11 b. Circuit failure (Channel Out of Service - Loss of Power, Loss of 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 ] Room alarm annunciation occurs if any of the following conditions exi,st:
- a. Instrument indicates measured levels above the Alarm Setpoint; or
- b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts,LossofSampleFlow,orCheckSourceFailure).
(4) The initial CHANNEL CALIBRATION shall be performed using one or more of 8 the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, 8 reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with MIST shall be used. (5) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. 4 , COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-7 REV. 11 11/94 5
fNSTRUMENTATf0N RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
- CONTROLS 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 Alarm / Trip Setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The Alarni/ 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 OPERABLE, take the ACTION shown in Table 3.3-8. 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 Contrcl 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 REQUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE 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. l COMANCHE PEAK UNITS 1 AND 2- PART I 3/4-8 REV. 10 __ _ _ _ _ _ _ _ _ _ - _ Of94
TABLE 3.3-8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION n SS MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION ((
- 1. WASTE GAS HOLDUP SYSTEM ,
3E a. Noble Gas Release Rate
- Monitor - Providing Alare g and Automatic Termination q of Release v' [XRE-5570A & XRE-55708 (effluent release rate channel)] 1/ stack ** 34 c3 2. PRIMARY PLANT VENTILATION ro
- a. Noble Gas Release Rate Monitor
[XRE-5570A & XRE-55708
,, (effluent release rate channel)] 1/ stack
- 36 3G
-d b. Iodine Sampler (WRGM sample skid) 1/ stack
- 37
{} iS c. Particulate Sampler 1/ stack
- 37
") (WRGM sample skid)
- d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1, 1/ stack
- 35 4 X-RFT-55708-1) 4 3
3 Est
-TABLE 3.3-8 (Continued)
TABLE NOTATIONS
- At all times.
** During Batch Radioactive Releases via this pathway.
ACTION 34- With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior ; to initiating the release l
- a. The auxiliary building vent duct monitor (XRE-5701) is confirmed OPERABLE, or ]
4
- b. At least two independent samples of the tank's contents are analyzed, and ,
- c. At least two technically qualified members of the i facility staff independently verify the release rate i calculations and discharge valve lineup. ;
Otherwise, suspend release of radioactive effluents via this I pathway. ACTION 35- With the number of channels OPERABLE 'less than required by the 4 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is istimated at least once per 4 hours. 9 ACTION 36- With the number of channels OPERA 8LE less than required by the ' Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that: (a) A Plant Vent Noble Gas Activity Monitor (XRE-5570A, XRE-55708 (low range activity) or XRE-5567A, XRE-55678) i is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours; 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 OPERABLE (XRE-5567A. XRE-55678) or grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours; or (c) The plant vent flow rate is estimated at least once per 4 hours, and grab samples are taken at least once per j 12 hours and these samples are analyzed for i radioactivity within 24 hours. ' ACTION 37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the i affected pathway may continue provided samples are continuously 1 collected with auxiliary sampling equipment as required in Table 4.11-2. l l CONANCHE PEAK UNITS 1 AND 2 PART I 3/4-10 1/93 )
TABLE 4.3-4 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS hf . ANALOG DIGITAL j; , CHANNEL CHANNEL 52 CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL
"' INSTRUMENT CHECK CHECK CALIBRATION TEST TEST A
3; 1. WASTE GAS HOLDUP SYSTEM h a. Noble Gas Release Rate Monitor - 35 Providing Alare and Automatic gj Termination of Release _o [XRF.-5570A. XRE-55708(effluent release y rate channel)] P P R(3) N.A. 0(1) 5 n3 2. PRIMARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor
[XRE-5570A. XRE-55708(effluent release
]E rate channel)] D # R(3) N.A. 0(2)
N
,, b. Iodine Sampler u, (WAGM sample skid) W(4) N.A. N.A. N.A. M.A.
1 L
- c. Particulate Sampler (WRGM Sample Skid) W(4) N.A. N.A. N.A. N.A.
- d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1 D N.A. R 0 M.A. 4 X-RFT-55708-1) 4 3
3 (a _m .___a,--m ,u . , , . -- w: __ r--- ..r-- .,s- s -se m- - =+ -g e a-- -iri eg s- m ---- ------w,+ - -,m
1
)
TABLE 4.3-4 (Ccntinued) TABLE NOTATIONS i Prior to any release from the WASTE GAS HOLDUP SYSTEM or 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 , occurs if any of the following condition exists. ; l
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or
- b. Circuit failure, (Channel Out of Service - Loss of Power, *.oss ;
of Counts Loss of Sample Flow, or Check Source Failure). (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following ; conditions exists;
- a. Instrument indicates measured levels above the Alarm Setpoint, !
or ;
- b. Circrit failure, (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).
(3) The initial 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 sta.ndards that have been l obtained from suppliers that participate in measurement assurance t activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For 8 subsequent CHANNEL CALIBRATION, sources that have been related to the ; initial calibration, reference standards certified by MIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with MIST shall be used. (4) The CHANNEL CHECK shall consist of visually verifying that the collection element (i.e., filter or cartridge, etc.) is in place for sampling. i 1 l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-12 1/93
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION I I CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table ' j 8 3.3-9 shall be OPERABLE. - APPLICABILITY: At all times. ACTION: i 11 a. With less than the minimum number of meteorological monitoring instrumentation channels OPERABLE 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 hours by performance of a CHANNEL CHECK; and ,
- b. At least once per 184 days by performance of a CHANNEL CALIBRATION.
1 i COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-13 REV. 11 11/94
( TABLE 3.3-9 l METEOROLOGICAL MONITORING INSTRUENTATION f' MINIMUN INSTRUENT LOCATION OPERABLE
- 1. WIND SPEED 1 of 3
- a. X-SY-4117 Nominal Elev. 60 m. I l b. X-SY-4118 Nominal Elev. 10 m.
- c. X-SY-4128* Nominal Elev. 10 m.
- 2. WIND 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.
l l
- Mounted on backup tower.
COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-14 01/93
INSTRl3ENTATION 1
'A i A SEATED M IRCE CONTAMIN_Al1Qg CONTROLS l 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 With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either: , 1
- 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:
- a. The licensee, or
- b. Other persons specifically authorized by the Commiission 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) With a half-life greater than 30 days (excluding Hydrogen 3),
. and
- 2) In any form other than gas. ]
l! l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-15 1/93
9 O l SURVEILLANCE REQUIREMENTS (Continued)
- 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 beirg l placed into use; and j
- 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 i 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. oF* e l l I COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-16 1/93 j
3/4.11 RADIQACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 6.8.3.e.2 and 3, the concentration of 8 radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to 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 10 4 microcurie /ml total activity. APPLICABILITY: At all times. g_TJQH: (a) With the concentration of radioactive material released in liquid 8 effluents to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits, 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 REOUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1. 4.11.1.1.2 The results of the radioactivity analyses shall be used in 8 accordance with ;he 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 REV. 8 I COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-17 1/93
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 (pCl/ml) . 1 A. Batch Weste Release (2) P P Principal Gamma 5.0E-07 7 Tanks to the Circulating Each Batch Each Batch Emitters (3) i Water Cischarge - l-131 1.0E-06 l [
- a. Waste Monitor Tanks Dissolved & Entrained (3) 1.0E-05 0
- b. Laundry Holdup ases ( amma Ernators) ;
& 'Aonitor Tanks M H-3 1.0E 05 f
- c. Waste Water Composite (4) j7 f Holdup Tanks (8) Gross Alpha 1.0E-07 -
l
- d. Plant Effluent -
O Sr-89, E. 90 5.0E-08 Tanks Composite (4) 7A : Fe-55 1.0E-06 I
- 18. Batch Weste Release (2) P P Principal Gamma 5.0E-07 l Tanks to the LVW Pond Each Batch N.h Batch Emtters (3)
- a. Condensate 7 Polisher Backwash .
Recovery Tanks (6,7) 1-131 1.0E 06
- b. Weste Water I9 i
. Holdup Tanks (6.8) i
- 7 H-3 1.0E 05 l
2A, Continuous Release (5) Daily Grab Composto principalGamma 5.0E 07 to the Circulating Sample (9) over pond Emtters (3) , Water Discharge discharge
- a. Low Volume Waste Pond Effluents Dissolved & Entrained (3) 1.0E-05 I8 Gases (Gamma Emitters) t H-3 1.0E 05 l !
Gross Alpha 1.0E-07 ! ! O Sr-89, St-90 5.0E 08 - l Composite (4) 7 l
- 28. Continuous Reisases (5) W W Principal Gamma 5.0E-07 :
to the LVW Pond Grab Sample Emtters (3) !
- a. Turbine Bldg. Sump .
[ No. 2 Effluents (6,7) ! 1131 1.0E-06 [
- b. Turbine Bldg. Sump ;
No. 4 Effluents (6,7) i
- c. Auxilia Bld H-3 1.0E-05 Seco (6.7) ryguents jg l j
COMANCHE PEAK - UNIT 1 AND 2 PART I 3/4-18 Rev 9 i 09/93
~
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 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-i 4.66 sb LLD = E V 2.22 x 10u . y exp (-AA:) l Where: LLD = the "a priori" lower limit of detection (microcurie per ' unit mass or volume), sb = the standard deviation of the background counting rate or i of the counting rate of a blank sample as appropriate (counts per minute), l EN thecounting. efficiency (countsperdisintegration), 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 (s- 1 ), and At = the elapsed time between the midpoint of sample collection l and the time of counting (s), i 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 the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. l (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 ODCM to assure representative sampling. COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-19 b8 01/93
i TABLE 4.11-1 (Cond nued) l }.. TABLE NOTATf0NS k 1 (3) The principal gamma emmiters for which the LLO specification applies j include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, j 8 Zn-65 Mo-99, Cs-134 Cs-137, and Ce-141 for fission and corrosion ' products, and Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for ;
'dissolvedoregtrainedgases. Ce-144 shall also be measured, but with an l LLD of 5 x 10 . This list does not mean that only these nuclides are to ,
be considered. Other gamma peaks that are identifiable, together with j those of the above nuclides, shall also be analyzed and reported in the ; 10 Annual 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. ! A composite sample is one in which the quantity of liquid sampled is. (4) proportional to the quantity of liquid waste discharged and in which the j method of sampling employed results in a specimen that is representative ' of the liquids released. I (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 j continuous release. ; 7 (6) These waste streams shall be sampled and analyzed, in accordance with [ this table, if radioactive material is detected in the LVW Pond composite ! samples in concentrations that exceed 105 of the limits of 10 CFR 20, l 8 Appendix B Table 2 Column 2. This sampling shall continue until 2 i 7 consecutive samples from the waste stream show that the concentration of !
. radioactive materials in the waste stream is less than or equal to 10% of j the limits of 10 CFR 20, Appendix 8, Table 2 Column 2. !
7 (7) All flow from these waste streams shall be diverted to the Waste Water ! Holdup Tanks if activity is present in the waste stream in concentrations j 8 that exceed the limits of 10 CFR 20, Appendix B Table 2. Column 2. : 7 Sampling and analysis of the respective Tanks or sumps are not required ! when flow is diverted to the Waste Water Holdup Tanks. i 7 (E) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the ! Circulating Water Discharge Tunnel when results of sample analyses J indicate activity in concentrations that exceed the limits of 10 CFR 20, l 8 Appendix 8. Table 2. Column 2. Otherwise, WWHTs may be discharged to the l 7 Low Volume Waste Pond. WWHT discharges to the Circulating Water. l Discharge Tunnel shall be sampled and analyzed per Item 1A.c of this l table. WWHT discharges to the LVW Pond shall be sampled and analyzed per t 10 Item 18.b of this table. 7 (9) Samples shall be taken at least once per 24 hours while the release is 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 constant for all samples taken for the composite sample. COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-20 REV. 10 4/94
RADIGACTIVE EFFLUENTS D.QZ 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 dose commitment to a MEM8ER 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 mrems to any organ, and
- 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 organ.
, APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Comission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the calise/,5) for exceeding the limit (s) and defines the corrective :
~ actio1s that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. ; This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.11.1.2 Culaulative dose contributions from liquid effluents for the 8 current calendar quarter and the current calendar year shall be determined in accordance with the methodology 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 3/4-21 1/93
I RADIOACTIVE EFFLUENTS LIOUID RADWASTE TREATMENT 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 CONTROLLEO AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. APPLICABILITY: At all times. ACTION:
- a. With radioactive liquio vaste being discharged without treatment and in excess of the abo a limits and any portion of the Liquid Radwaste Treatment System rat 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 ,
'~without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to I OPERABLE status, and
- 3. Summary 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 OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22 1/93
RAD 10 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 :
y .I . <1.0 J J excluding tritium, dissolved or entrained noble gases, and radionuclides 7 with less than an 8 day half life, where: 7 Aj = pond inventory limit for single radionuclide "j" (Curies). 7 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 ACTION:
- a. With the quantity 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 l 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 j pond, including the batch to be transferred, shall be determined to be i within the above limit. The inventory shall be determined based on analysis of a representative sample of the resin batch. Decay of radionuclides la previously discharged resins may be taken into account in determining inventory levels. REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22a 1/93
1 RADIQACTIVE EFFLUENTS LVW POND RESIN INVENTORY 7 SURVEILLANCE REOUIREMENTS (Continued) 4 Additionally, each batch of resins transferred.to the pond shall be limited 8 ' by the expression: 8 ' O.) 1 0.1 j 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 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 composite analysis, Cj = 10 CFR 20 Appendix B Table 2, Column 2, concentration 8 for single radionuclide "j" (microcuries/ milliliter). i l i i COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22b Rev. 8 ERRATA (6/93) l\
l _, RADIQACTIVE EFFLUENTS 1 3/4.11.2 GASEQUS EFFLUENTS l DOSE RATE j 3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7, the dose : rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be l limited to the following: '
- a. For noble gases: Less than or equal to 500 mroms/yr to the whc 's body and less than or equal to 3000 mrems/yr to the skin, ,
and ; a
- b. For Iodine-131, for Iodine-133, for tritium, and for all !
radionuclides in particulate form with half-lives greater than 8 t days: Less than or equal to 1500 mres/yr to any organ. APPLICABILITY: At all times. I e ACTION: , i (a) With the dose rate (s) exceeding the above limits, immediately restore i the release rate to within the above limits (s). ! (b)Theprov'IsionsofControls3.0.3and3.0.4arenotapplicable. SURVEILLANCE REQUIREMENTS , t 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed 8 according to 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 8 accordance with the methodology and parameters in Part II of the 00CM to assure that the dose rates at the SITE BOUNDARY are maintained within the limits of Control 3.11.2.1. 1 i i
- l l
REV. 8 l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-23 1/93
I i ! O E
$ TABLE 4.11-2 N .
y Radioactive Caseous Waste Sayling and Analysis Program (*) S 7e MINIIEIN LOWER LIMIT OF c- SME' LING ANALYSIS TYPE OF DETECTION (LLD)(1)
$ GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS spC1/ml)
Y
~ 1. Weste Gas Storage P P
~
Tank Each Tank Each Tank Francipal Gamma Emitters (2) lx10 C Crab Sample
- 2. Containment Furge P F N or Vent Each Release (3) Each Relesee(3) Frincipal Camme Emitters (2) lx10~
~0 M N-3 (oxide) 1x10
- 3. Plant Vent M(3), (4), (5) Frincipal Ca m Emitters (2) lx10~
A Q Crab Sample M(3) B-3 (oxide) lx10 -6 c-. g Continuoue(6) U(7) I-131 lx10
-12
% Radiotodine i
m. Adeorber Continuoma(6) U(7) Principal Comma Emitters (2) lx10~ Ferticulate Sample Coatinuoue(6) M Cross Alpha tul0
~I Composite Far-ticulate Sample Continuous (6) Q Sr-89. Sr-90 lxa0 ~II Composite Far-ticulate Sample O
Continuous (6) Noble Gas ** Be t a o r Camuna Noble Cas lx10 lI W
- Table notations next page
**This sample is continuously analyzed by a radiation monitor l1
TABLE 4.11-2 (Continued) TABLE NOTATIONS (1)TheLLDisdefined,forpurposesofthesespecifications,asthe smallest concentration of radioactive material in a sample that will l 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: b LLD = E . y . 2.22 x 10 6 . y . exp (.Aat) i Where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), s b = the standard devi f the b rate or ofthecountingrateoftion ablanksampick!roundcounting(counts e s appropriate per minute), O 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 I microcurie, 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 time of counting (s). Typical values of E, V, Y, and at should be used in the calculation. P l It should be recognized that the LLD is defined as an a oriori l (before the fact) limit representing the capability of a measurement system and not as an g nosteriori (after the fact) limit for a particular measurement. l I COMANCHE FEAK UNITS 1 AND 2 PART I 3/4-25 01/93
TABLE 4.11-2 (Continued) TABLE NOTATIONS (Continued) (2) The principal gamma emitters for which the LLO specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59 Co-58, Co-60, Zn-65, 1-131, 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 format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, : startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER l within a 1-hour period. This requirement does not apply if: (1) l 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) noble gas monitoring shows that effluent activity has not increased more than a factor of 3. I (4) Tritium grab samples shall be taken.at least once per 24 hours 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 ! in the spent fuel pool. (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 ' l_ calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3. ~ (7) Samples shall be changed at least once per 7 days and analyses shall be , completed within 48 hours after changing, or after removal from the
- 1 sampler. Sampling shall also be performed at least once per 24 hours for 4 at least 7 days following each shutdown, startup or THERMAL POWER change ;
exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses < shall be completed within 48 hours of changing. When samples collected ! for 24 hours are analyzed, the corresponding LLDs may be increased by a j factor of 10. This requirement does not apply if: (1)analysisshows ' that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has 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. 4 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-26 REV. 10 e
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 REOUIREMENTS 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 m6thodology and parameters in Part II of the 00CM at least once per 31 days. I l l l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-27 1/93 , l
RADI0 ACTIVE EFFLUENTS DOSE - 100INE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM i CONTROLS j I 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 1 radionuclides in particulate form with half-lives greater than 8 days in I 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:
- 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 l- 133, tritium, and radionuclides in particulate form with half-l 1.tves greater 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 l 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. REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-28 1/93
RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 6.8.3.e.6 the PRIMARY PLANT 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:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times. ACTION:
- a. With radioactive gaseous waste being. discharged without 8 treatment and in excess of the above limits, prepare and submit to the NRC within 30 days, pursuant to specification 6.9.2, a Special Report that ircludes the following information:
- 1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Control 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS __ l 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and 8 beyond the SITE SOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized. 4.11.2.4.2 The installed PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS l HOLOUP SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.2 or 3.11.2.3. i REV. 8 CCHANCHE PEAK UNITS 1 AND 2 PART I 3/4-29 1/93
. - . . . . .- - . - - ~ . . .. .-
RADIDACTIVE EFFLUENTS i TOTAL DOSE l
~' i CONTROLS i
3.11.4 In accordance with CPSES TS 6.8.3.e.10, the annual (calendar year) ' dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of j 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. . ! APPLICABILITY: At all times. ACTION:
- a. With the calculated 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., calculations shall be made including ! direct radiation contributions from the units and from outside i storage tanks to determine whether the above limits of. Control , 3.11.4 have been exceeded. If such is.the case, prepare and 8 , submit to the NRC within 30 days, pursuant to Specification ' 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of 1 exceeding the above limits and includes the schedule for
, achieving conformance with the above limits. This Special 8 ,
Report, as defined in 10 CFR 20.2203(a)(4) and 20.2203(b), shall
- include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, ;
, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and
- 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, ' fh'e'Special Report shall include a request for a variance in t 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. !
- b. The provisions of Controls 3.0.3 and 3.0.4 are not' applicable.
SURVEILLANCE REQUIREMENTS ; 1 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents 8 shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in &ccordance with the methodology and parameters in Part II i of the 00CM. COMANCHE DEAK UNITS 1 AND 2 PART I 3/4-30 Rev. 8 , ERRATA (6/93)
i RADI0 ACTIVE EFFLUENTS (Continued) 3/4.11.4 TOTAL DOSE SURVEILLANCE REQUIREMENTS 4.11.4.2 Cumulative dose contributions from direct radiation from the 8 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. I j l COMANCHE PEAK UNITS 1 AND 2 ffg3 l PART I 3/4-31
, . - . _ - _ = _ . ._ .- _ - -_
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 1 3.12.1 In accordance with CPSES TS 6.8.3.f.1, the Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1. APPLICABILITY: At all times. ACTION:
- a. With the Radiological Environmental Monitoring Program not being ,
conducted as specified in Table 3.12-1, prepare and submit to ; the Conmiission, in the Annual 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 the plan for preventing a recurrence. '
- b. With the level of radioactivity as the result of plant effluents 8 in an 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 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective action to be taken to reduce
. radioactive affluents so 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 :
medium, this report shall be submitted if: ; concentration (11 . concentration (21 ' reporting level (1) reporting level (2) ...> 1.0 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 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, 3.11.2.2, or 3.11.2.3.
This report is not required if the measured level of : radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual Radiological Environmental Operating Report 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.
) REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-32 1/93
RADIOLOGICAL ENVIRONMENTAL MNITORING CONTROLS ACTION (Continued 1
- c. With milk or fresh leafy vegetable samples unavailable from one 8 or more of 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 given in Part II of the 00CM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Control 6.14, submit as a part of or concurrent with the Semiannual Radioactive Effluent Release Report, a complete, legible copy of the entire 00CM, including a revised figure (s) and table for the 00CM reflecting the new location (s).
- d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
1 SURVEILLANCE REQUIREMENTS 1 4.12.1 The radiological environmental monitoring samples shall be 8 collected pursuant to Table 3.12-1 from the specific locations given in Table 3.1 and Figure 3.1 in Part II of the 00CM,'and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Ta,ble 4.12-1. , l l l l l l . REV. 8 COMANCHE PEAK UNITS 1 AND 2 Pf4T I 3/4-33 1/93 l
TABLE 3.12-1 Radiological Environmental Monitoring Program "o
@ NUMBER OF M REPRESENTATIVE E EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY u AND/0R SAMPLE SAMPLE LOCATIONS (l) COLLECTION FREQUENCY OF ANALYSIS 9
- 1. Direct Radiation (2) Forty routine monitoring stations ' Quarterly. Gamma dose quarterly either with two or more dosimeters E or with one instrument for measur- j Q ing and recording dose rate continuously, placed as follows:
[ E An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY: An outer ring of stations, one in 1 o each meteorological sector in M the 6- to 8-km range from the [ site: and i R The balance of the stations to be P placed in special interest areas
% such as population centers, nearby residences, schools, and in one
{ or two areas to serve as control stations.
- 2. Airborne Radioiodine and Samples from five locations: Continuous sampler Radioiodine Cannister:
, Particulates operation with sample I-131 analysis weekly collection weekly, e Three samples from close to or more frequently " the three SITE BOUNDARY if required by dust Particulate Scroler:
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.
TABLE 3.12-1 (Continued) c3 Radiological Environmental Monitoring Program S 3; NUMBER OF , 5@ REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY
?' AND/OR SAMPLE SAMPLE LOCATIONS (l) '. COLLECTION FREQUENCY OF ANALYSIS 3E , One sample from the .
c: vicinity of a community 25 having the highest calcu-Dl lated annual average ground- _o level D/0: and
!! One sample from a control na location, as for example 15 to 30 km distant and in the least prevalent wind direction. (3)
- 3. Waterborne
]
- a. Surface Squaw Creek Reservoir (6) Monthly composite of Gamma isotopic anal-
. u, weekly grab samples, ysis(5) monthly. ' 3s Composite for tritium
- {g analysis quarterly.
Lake Granbury Monthly composite of Gamma isotopic anal-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 0 Control-Brazos River Monthly Gamma isotopic anal- . l! 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.
l TABLE 3.12-1 (Continued) n Radiological Environmental Monitoring Program S E NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY A AND/OR SAMPLE SAMPLE LOCATIONS (l) ~ COLLECTION FREQUENCY OF ANALYSIS N *
. 3. Waterborne (Continued) b i
- c. Drinking One sample from Squaw Creek Composite of weekly I-131 analysis of I d Reservoir. grab samples over each composite sample I
._. 2-week period when when the dose calcu- > I-131 analysis is lated for the con- i 5 performed: monthly sumption of the water l
n3 composite of weekly is greater than 1 aren ' grab samples other- per year (9) . Gross wise. beta and gamma iso-topic analyses (5) A monthly. Composite d for tritium analysis
- quarterly.
w 1 d. Sediment One sample from downstream area Semiannually. Gamma isotopic analy-E2 from with existing or potential sis (5) semiannually. Shoreline recreational value.
- 4. Ingestion
- a. Milk Samples from uliking 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.
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 O location. 15 to 30 km distant and
$ in the least direction.(3) prevalent wind
TABLE 3.12-1 (Continued) n Radiological Environmental Monitoring Program S g NUMBER OF g REPRESENTATIVE m EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY A AND/OR SAMPLE SAMPLE LOCATIONS (l) l, COLLECTION FREQUENCY OF ANALYSIS R
, 4. Ingestion (Continued) b b. Fish and One sample of at least two Sample semiannually. Gamma isotopic d Invertebrates recreationally important species analysis (5) on in vicinity of plant discharge area. edible portions.
o One sample of same species in areas m 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 3 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 4, 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
.O broad leaf vegetation grown 15 to available. and I-131 analyses. 'g 30 km distant in the least pre-u valent wind direction (3) if alik sampling is not performed at all required locations.
- Reports from 3 additional airborne radioiodine sample locations may be supplemented for broad leaf vegetation samples.
TABLE 3.12-1 (Continued)
; TABLE NOTATlQU 8 (1) Fcr each and every sample location required by Table 3.12-1, specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided in Table 3.1 and Figu e 3.1 in Part II of the 00CM. Deviations are permitted from the required sampling schedule if. specimens are unobtainable due to circumstances such as hazardous conditions, seasonal l
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 8 choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular l pathway in-question and appropriate substitutions made within 30 days in I the Radiological Environmental Monitoring Program given in Part II of the 00CM. Pursuant to Control 6.14, submit as a part of or concurrent with 10 the next Annual Radioactive Effluent Release Report a complete legible copy of the 00CM including a revised figure (s) and table for the 00CM reflecting the new location (s). (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 hours or more after sampling to allow for radon and i thoron daughter decay. If gross beta activity in air particulate samples l 1s greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. l l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-38 REV. 10 4/94
TABLE 3.12-1 (Continued) TABLE NOTATIONS (Continued) (5) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (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. (7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge. (8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (9) The dose shall be calculated for the maximus organ and age group, using 8 the methodology and parameters in Part II of the 00CM. (10) If harvest occurs more than once a year, sampling shall be performed
- during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including i samples of tuberous and root food products.
1 l 1 I REY. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-39 1/93 l
l . i TMitt3.12-2 l Itparting imels for ihdioactivity Concentratias in Bwirummtal Saples n y idER AllEGIE PNE10AATE FI91 MILX RXD FIU10!S g M @t/1) Gt 96ES (pCfM) (pCIAeg wt) (pCi/l) (pCi/hg. ut) M E H-3 E.G)D(*) N MHis 1.000 30.000
; re e 400 m. Coo 3 Coe 1.000 30.000 a ca e 300 m.000 m aHs an E.au > 2ritHIS 410 $ I-131 2(**) 0.9 3 100 N
Cs-134 30 10 1.000 tid 1.GD Cs-3P SD E 2.0G) 70 2.00) Be-la-le 2B 3B E (*) rer <king unter suples. Ws is 4) CRt Put 141 vehe. If no <kirqi teter pathay edsts, a value # 30.000 gfill any be tsed. M P (**) If no &irkirqlistur pather edsts, a value W E pC1/1 siy be used. 8 2 4 u
l l TAILE 4.12-1 Detectim Cgnb(11 ties for Ekwiruunntal Suple Analysis (1)(2) g Lawar Limit of Dbtectim (LID) (3) f 5 m uma momeE RWHGLM RSi MLK RXD MHOS SEDDet y All C SIS @f/1) Gt G6ES (pCiM) ptAqh net) (pCi/1) (pCi/kg.tet) (pCf Ag. dry) R c Gruss Beta 4 0.01 { H-3 2HP m NHi4 15 13) Fe s 30 2D
# ces, e is 130 nas 30 ao 2ritHIS E I-131 1** 0.5 1 60 Cs-134 15 0.5 130 15 8) 15 0 g Cs-ly B 0.06 ED 18 m 180
- ItHa-140 15 15 M
- If rm tirkirg natur petfuy adsts, a wake of 3XD pC1A sur be used.
** If rm #fektre W pathey edsts, a vehe of E pCIA my be used.
3 3 63
l l TABLE 4.12-1 (Continued 1 TABLE NOTATIONS \ (1) The list does not mean that only these nuclides are to be corisidered. 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 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 5% probability of falsely concluding that a blank observation represents a "real" signal. 4.66sb LLO = E V Y exp (-AAt) 2.22 Where: LLD = thi'"a priori" lower limit of detection (picocurie per unit mass i or volume), 1 ss= the standard dev<ation of the backaround counting rate or of the c5unting rate of a b'ank sample as appfopriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 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 l
L 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. I COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-42 1/93
TABLE 4.12-1 (Continued) I (- k' TABLE NOTATIONS (Continued)
'(3) continued
( It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an g nosteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LL0s will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these 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. l ) l l \ COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-43 1/93
RADIOLOGfCAL ENVf RONMENTAL MONITORf NG 3/4.12.2 LAND USE CENSUS i CONTROLS 3.12.2 In accordance with CPSES TS 6.8.3.f.2, a Land Use Census shall be conducted and shall identify within a distece of 8 km (5 mile.) the location ineachofthe16meteorologicalsectorsofthenearestmilkagimal,thg) nearest residence, and the nearest garden
- of greater than 50m (500 ft I producing broad leaf vegetation.
APPLICABILITY: At all times. l 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 ' 10 new location (s) in the next Annual Radioactive Effluent Release Report. 1 b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than j at a location from which samples are currently being obtained in i accordance with Control 3.12.1, add'the new location (s) within 30 days, : to the Radiological Environmental Monitoring Program given in Part II of j the 00CM. 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. Pursuant to Control 6.14, submit as a part of 10 or concurrent with the next Annual Radioactive Effluent Release Report a complete, legible copy of the entire 00CM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s).
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 1 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/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1 Item 4.c. shall be followed, including analysis of control samples. l COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-44 REV. 10 e@s
I~ RADIOLOGICAL ENVIRONENTAL MNITORING 3/4.12.3 INTERLABORATORY CGtPARISON PROGRAM CONTROLS 3.12.3 In accordance with CPSES TS 6.8.3.f.3, analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory , Comparison Program that has been approved by the Commission, 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 actions taken to prevent a recurrence to the ' Commission in the Annual Radiolosical 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 REOUIREMENTS 4.12.3 The Interlaboratory Comparison Program s'ha11 be described in Part 8 II of the 00CM. A sunnary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Invironmental Operating Report pursuant to Control 6.9.1.3.
. t I
i i h I I REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-45 1/93
2 e O* BASES COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-0 01/93
INSTRUMENTATION BASES 3/4.3.3.4 RADIQACTIVE LIOUID EFFLUENT MONITORING INSTRlMENTATION 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 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. 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 relenses of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and 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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.6 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological 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 BASES 3/4.7.15 SEALED SOURCE CONTAMINATION 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 intake values.
I Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are 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 the shielded mechanism. COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-2 01/93
3/4.11 RADIQACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS j This control is provided to ensure that the concentration of 8 radioactive materials released in liquid waste effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table 2, Column 2. This limitation provides additional 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 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 1 CFR Part 20.1301(a) and (b) to individual MEMBERS OF THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Colonission on Radiological Protection (ICRP) Publication 2. This control applies to the release of radioactive materials in liquid effluents from all units at the site. l The regaffed detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discuss'on of the LLD and other detection limits can be < found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration I of a Proposed Position for Radiological Effluent and Environmental ! Measurements." NUREG/CR-4007(September 1984),andintheHASLProcedures 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 i guides set forth in Section II.A of Appendix I. The ACTION statements 8 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to 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 operatten 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 requirments 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 8 the the 00CM for calculating the doses due to the actual release rates of i REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-3 01/93
RADIDACTIVE EFFLUENTS BASES QQE (Continued) 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 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 LIOUID 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 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 II.D of' Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents. 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. 8 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 Castrol 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 the Effluent Concentration Limits specified in 10 CFR 20, Appendix 8. Table 2, Column 2. Because Control 3.11.1.1 limits the concentration of liquid effluents from other pathways to the LVW Pond to 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 resins), will not exceed the 10 CFR 20 Effluent Concentration values. REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-4 01/93
~ RADIQACTIVE EFFLUENTS r BASES (Continued) 3/4.11.1.4 LVW POND RESIN INVENTORY (Continued) 7 f 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 i 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. The batch limit is arbitrarily established at 10% of the 10 CFR 20, 8 Appendix 8 limits to minimize input of radioactive materials to the LVW 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. COMANCHE pef.K UNITS 1 AND 2 PART I B 3/4-5 Rev. 8 l ERRATA (6/93) l I
l RADIOACTIVE EFFLUENTS l BASES l 3/4.11.2 GA unlit EFFLUENTS 3/4.11.2.1 OnW RATE This control, in conjunction with Controls 3.11.2.2 and 3.11.2.3, is 8 , provided to ensure that the dose at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose i limits of 10CFR20 to CONTROLLED AREAS and UNRESTRICTED AREAS. The , specified release rate limits restrict, at all times, the corresponding , gamma and beta dose rates above background to a M ER OF THE PUBLIC at or : beyond the SITE BOUNDARY to less than or equal to 500 arems/ year to the i whole body or to less than or equal to 3000 mress/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid . dose rate above background to a child via the inhalation pathway to less ] than or equal to 1500 mrems/ year. Because these dose rate limits are 8 applied on an instantaneous basis and because of the overriding 10 CFR 50, j Appendix I, cummulative dose limitations, established in Control 3.11.2.2 and 3.11.2.3, these limits provide reasonable assurance that radioactive i , material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in a CONTROLLED AREA or an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations that - would result in excceding the annual total effective dose equivalent limit 1 specified in.10 CFR 20.1301. For MEMBERS OF THE PUBLIC who may at times j be in CONTROLl,ED AREAS within the SITE BOUNDARY, the occupancy factors for
, those MEMBERS OF THE PUBLIC will usually be sufficiently low to compensate
! for any increase in the atmospheric diffusion factor above that for the l SITE BOUNDARY. The methodology for calculating doses for such MEMBERS OF THE PUBLIC is provided in PART II of the 00CM. l This control applies to the release of radioactive materials in gaseous 4 effluents from all units at the site. i 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 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 i Measurements." NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual HASL-300.
REV. 8 ; COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-6 01/93 m _ _ _ _ _ _ _ . --. _ -
~- !
; RADI0 ACTIVE EFFLUENTS i
BASES i 3/4.11.2.2 DOSE - NOBLE GASES 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 8 4, provide the required operating flexibility and at the same time implement l3, 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
- I and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
} The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by
{, calculational procedures based on models and data such that the actual .; exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely -) to be substantially underestimated. The dose calculation methodology and 5 parameters established in Part II of the ODCM for calculating the doses i due to the actual release rates of the radioactive noble gases in gaseous f 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 equtfions provided for determining the air doses at and beyond the SITE B0UNDARY are based upon the historical average atmospheric conditions. l This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the 8 ! shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2. REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-7 01/93
I RADIGACTIVE EFFLUENTS BASES l 3/4.11.2.3 DOSE - 10 DINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE l MATERIAL IN PARTICULATE FORM i This control is provided to implement the requirements of Sections : II.C. III.A, and IV.A of 10CFR50, Appendix I. The Controls are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the 8 , required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The calculational methodology and parameters specified in Part II of the ODCM for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and i Dispersion oPGaseous 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 Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days is dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the esiculations were: (1) individual inhalation of airborne radionucludes, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the 8 shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2. l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B'3/4-8 01/93
RADICACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEQUS RADWASTE TREATMENT SYSTEM The OPERASILITY of the WASTE GAS HOLDUP SYSTEM and the PRIMARY PLANT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate 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 effluents from the 8 shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2. l 9 i i i REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-9 01/93
RADI0 ACTIVE EFFLUENTS l l BASES (Continued) 3/4.11.4 TOTAL DQ1E This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives 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 tra annual dose to a MEMBER OF THE PUBLIC to within the 40 l CFR Part 190 11h.ics. 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 radious of 8 km must be considered. If the dose to any MEMBER OF 8 THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR
. 20.2203(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 THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-10 Rev. 8 ERRATA (6/93)
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITfEING PROGRAN 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 measureable 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 coinnercial 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'tn industrial laboratories. It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (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 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 and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the 00CM are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the , requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. ' Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation i.e., similar to lettuce andcabbage),and(2)avegetationyieldof2kg/s(c. COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-11 01/93
.', 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 l 10 CFR Part 50. 6 1 l l l COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-12 01/93 I
SECTION 5.0 DESIGN FEATURES COMANCHE PEAK - UNITS 1 AND 2 PART I 5-0 01/93
5.0 DESIGN FEATURES MAP DEFINING CONTROLLED AREAS. UNRESTRICTED AREAS AND SITE BOUNDARY 8 l FOR RADIQACTIVE GASEOUS AND LIOU!O EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, 8 which allows identification of structures and release points as well as definition of CONTROLLED AREAS, UNRESTRICTED AREAS and the SITE BOUNDARY are shown in Figure 5.1-3. ' The UNRESTRICTED AREA, as show in Figure 5.1-3, is that area 8 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 BOUNDARY coincides with the Exclusion (fenced) Area Boundary, as defined in 10 CFR100.3(a). The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Controls to keep levels i
of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a. The CONTROLLED AREA, as shown in Figure 5.1-3, is that area that 8 : is inside 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 i of CONTROLLED AREA given in 10 CFR 20.1003. I 1 i i ! I e 1 i l COMANCHE PEAK UNITS 1 AND 2 PART I 5-1 Rev. 8 ERRATA (6/93)
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I ADMINISTRATIVE CONTROLS i l l l l I. i r COMANCHE PEAK - UNITS 1 AND 2 PART I 6-0 01/93
I ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.3 Routine Annual Radiological Environmental Operating Reports 8 covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year.
The Annual Radiological Environmental Operating Reports shall include l summaries, interpretations, and an analysis of trends of the results of the i radiological environmental surveillance activities for the report period, including a comparison with preoperational studies and with operational i controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Control 3.12.2 ' The Annual Radiological Environmental Operating Reports shall include 8 the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 3.1 and Figure 3.1 in Part II of the Offsite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1 November i 1979. In the event that some individual 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 data shall be
. submitted as soon as possible in a supplementary report.
The reports shall also include 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 licensee 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 as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1,; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12.1; 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 the more distant stations.
1 COMANCHE PEAK UNITS 1 AND 2 PART I 6-1 0 l l i
ADMINISTRATIVE CONTROLS 10 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 10 6.9.1.4 Routine Annual Radioactive Effluent Release Reports covering the operation of the units during the previNs year of operation shall be submitted prior to May 1 of each year. The period of the first report snall begin with the date of initial criticality.
10 The Annual Radioactive Effluent Release Report shall include a summary of t the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, cnd 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 summarized 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). 10 The Annual Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may he 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, Gnd atmospheric stability.** This same report shall include an assessment of tSe radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same rerort shall also include an assessment of the radiation doses from l radioactive liquid and gasecus O Muents to MEMBERS OF THE PUBLIC due to their l activities inside the SITE BOUNL ' (Figure 5.1-3) during the report period. All assur.ptions 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 l determined by sampling frequency and measurement, shall be used for determining l 8 the gaseous pathway doses. The assessment of radiation doses shall be l performed in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM). l 8
- A single submittal may be made for both units. The submittal should 10 combine those sections that are common to both units at the station. This report shall be submitted semi-annually per Technical Specification 6.9.1.4 until a License Amendment is issued to revise this Technical Specification.
10 ** In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary 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. 10 4/94
l ADMfNISTRATIVE CONTROLS 10 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) 10 The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including I doses from primary effluent pathways and direct radiation, for the previous l calendar year to show conformance with 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 i 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 The Annual Radioactive Effluent Release Report shall include a listing of f 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 i i following: 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. i 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) Changes to the 00CM: < f
- 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 justifying the change (s) and
- 2) A determination that the change will maintain the level of '
B radioactive effluent control required by 10 CFR 20.1302, 40 CFR , Part 190, 10 CFR 50.36a, and Appendix I 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 SORC and the . 9 approval of the Vice President of Nuclear Operations. i COMANCHE PEAK UNITS 1 AND 2 PART I 6-3 REV. 10 , 4/94 i
'ADMINISTRATfVE CONTROLS 6.14 OFFSITE 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 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. t COMANCHE PEAK UNITS 1 AND 2 PART I 6-4 REV. 10 4/94 -----_-----a
t e e PART II CALCULATIONAL METHODOLOGIES COMANCHE PEAK - UNITS 1 AND 2 01/93
SECTION 1.0
, LIQUID EFFLUENTS 1
. 8 The Comanche Peak Steam Electric Station (CPSES) is a 2-unit nuclear generating facility. Each unit is a 1150 MWe, 4-loop, Westinghouse PWR. The units share a common primary liquid radwaste processing system. CPSES is located on Squaw 7A Creek Reservoir (SCR), which serves as the point of supply and discharge for the 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
! 7 Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially radioactive liquid effluent releases from secondary systems include 9 a continuous release from the Turbine Building Sumps (TB Sump), the Unit 1 and Unit 2 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 8 batch releases from the Condensate Polisher Backwash Recovery Tanks (CPBWRT). These secondary pathways from each unit are normally discharged to the common 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 WWHTs may be released on a batch basis to the LVW Pond or to SCR 7 via the Circulating Water Discharge Tunnel, depending on the levels of radioactivity present. Table 4.11-1 of Part I of this document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed the limits of 10 CFR 20, 8 Appendix B, Table 2, Column 2. Also, releases from the Station Service Water (SSW) System are 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 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 1 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-1 11/94 1
A susuary of all liquid effluent release sources, volumes, flow rates, 7 and 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 7 the plant Digital Radiation Monitoring System (DRMS) supplied by q Sorrento Electronics (formerly General Atomics). Since De 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 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 8 CCMPLIANCE To demonstrate compliance with 10 CFR 20.1301, ODCM 8 Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS be limited to the concentrations specified in 10 CFR 20 Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases, and to 2E-4 uC1/m1 for dissolved or entrained noble gases. 10 CFR 20 compliance is checked for all discharges to SCR via the Circulating Water Discharge 7 Tunnel listed in Table 1.1. Because the LW Pond is located 8 in a CONTROLLED AREA, discharges to the LW Pond are also checked for 10 CFR 20 compliance. If radioactive materials are present in the LW Pond discharge in concentrations that : . exceed 10% of the limits of 10 CFR 20, Appendix 8 Table 2, l Column 2, then all inputs to the LW Pond are sampled and checked for compliance with 10 CFR 20. The following methodology is used to determine compliance with these 7 limits. l Rev. 8 l COMANCHE PEAK - Ulf!TS 1 AND 2 PART II 1-2 01/93 l
1.1.1 Isotonic Concentration of the Watte Tank Determine the isotopic concentration in waste stream to be released: IC1= ICg+(Ca+Cs+Ct + Cre) i i g [Eq 1-1] Where: LCj = Sum of the concentrations of each radionuclide, in the i release (uC1/s1) 7 IC g= Sum of the concentrations of each measured g gamma 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 1 most recent composite sample (uC1/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 895 r and 90S r as measured in the 7 I most recent composite sample (uC1/ml) required by Radiological Effluent Control 3/4.11.1.1 Table 4.11-l -
Ct= Concentration of 3H as measured in the most recent 7 compositesample(uci/ml)requiredbyRadiological Effluent Control 3/4.11.1.1. Table 4.11-1. CFe= Concentration of 55F e as measured in the most recent 7 l compositesample(uCi/ml)requiredbyRadiological Effluent Control 3/4.11.1.1. Table 4.11-1. I 1.1.2 Effluent Flow Rate (f) The maximum effluent discharge flow rates for each release 7 source are shown in Table 1.1. For pre-release calculations, 8 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 for the flow measuring device for the affluent release line. If a lower effluent flow rate is used in pre-release 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 L______.____________________.__.______-_-_-._______. _ - . _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ ._._ . - _ _ _ _ . _ _ _ _ _ _ ___ _ _ _ _ _ . _
DilutionFactor(RDF)totheActualOilutionFactor(ADF)is 8 maintained less than 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, j respectively. 1.1.3 Dilution of Liouid Effluents
- a. Discharges to SCR via Circulating Water Discharge Tunnel 7 Since liquid effluents from the radwaste treatment system, 7 Waste Water Holdup Tanks and the LW Pond are mixed with Circulating water prior to being discharged to Squaw Creek Reservoir, compliance with 10 CFR 20 is a function of the Circulating water flow rate. The maximum Circulating water i
flow rate per plant is 1.1 million gps. This is determined from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate 7 a flow rate per pump of 275,000 gpe. The actual Circulating water dilution flow is given by:
. F(diluting flow) = (275,000 gps / pump) x (# of pumps) x 0.9 7
[Eq. 1-2] Where: 0.9 = Safety Factor to compensate for flow 7 fluctuations from the rate predicted by the Circulating water pump curves (Fig. 1.2). As an additional consideration, the available dilution flow 7 for any release may be corrected to allow for simultaneous releases from the Radweste Processing System, a Waste Water Holdup Tank, and/or the LW Pond (i.e., a radwaste system tank, a Waste Water Holdup Tank, and the LW Pond may be
]
dischargedsimultaneously.) 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 radweste flows may build up a concentration of radioactive isotopes. It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows: l F' = F (1 - 1 (C'1/ECL1 )) [Eq 1-3] 8 Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-4 01/93 j l .
-- -_ ---_- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- -- -- - - J
i Where: F'= Adjusted Circulating Water Flow Rate l 7 C'i = Concentration of radionuclide 1 in the Reservoir 7 (uC1/ml)asmeasuredintheanalysisofthamonthly sample of the Reservoir required by Radiological { Effluent Control 3/4.12.1. Table 3.12.1. This sample is taken at the Circulating water intake structure as indicateo by location SW6 on Table 3.1 and Figure 3-1 of this manual. ECl.1 = Effluent Concentration Limit of radionuclide 8 i, from 10CFR20, Appendix B, Table 2 Column 2 F= (275,000 gps / pump) x (i of pumps) x 0.9 7 NOTE: If C'1 is less than LLD then F' = F and no adjusted flow 7 rate need be considered in the calculation of ADF. The LLD values used for this deters.ination shall be the LLD valves for water given in Radiological Effluent Control 3/4.12.1. Table 4.12-1.
- b. Discharges to the LVW Pond 7
1 Secondary release sources are discharged directly to the LVW 7 - Pond with no dilution (i.e., F=0).
- 1.1.4 Actual Oilution Factor (ADF)
ADF is the ratio of the effluent flow rate plus the 7 ; Cire.ulating water flow rate divided by the effluent flow rate. l ADF=(f+F)/f [Eq. 1-4] 7 ; i
, Where: f=effluentflowrate(gpe) t F = dilution flow rate (gps) 7 l
NOTE: If radioactivity is detected in the Reservoir, an adjusted 7 ! Circulating water flow rate F', shall be used in place of F l in the calculation of ADF. See section 1.1.3 for the calculationofF'(Eq.1-3).'Also,ifsimultaneousreleases 1 are occurring, the available dilution flow shall be reduced by the required dilution flow for any other concurrent release. Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 fMT II 1-5 01/93
1 1.1.5 Reauired Dilution Factor (RDF) The required dilution factor ensures that the effluent 8 concentrations expressed in 10CFR20, Appendix 8. Table 2, ; Column 2,'and a total concentration of dissolved or entrained ! noble gases of 2 x 10-4 uC1/m1 are not exceeded during a discharge. The required dilution factor includes a safety . factor of 2 to provide a margin of assurance that the 1 instantaneous concentration limits are not exceeded. $ RDF = (I t (C /ECLj)) x SF 1 8 ,
=
(Ig (C g/ECLg) + (Ca/ECla + Cs/LU s + 8 Ct/ECL t+Ce/ECLe))xSF F F [Eq 1-5] 8 Where: ECLj = Effluent Concentration Limit of 8 ; radionuclide 1, from 10 CFR20, Appedix
- 8. Table 2. Column 2 !
SF = Safety Factor of 2. 7 - I All other variables and subscripts are previously defined. ! NOTE: If RDF is less than 1, the release meets discharge limits 7 - without dilution. For conservatism, set RDF equal to 1.0. ; The maximum value for the high alarm satpoint for detector 7 ; XRE-5253 would then be calculated in accordance with the ! equation for C1 w in Section 1.2.1. 1.1.6 10 CFR 20 Como11ance t Compliance with 10 CFR 20 is demonstrated if the Actual 7 i Dilution Factor (ADF) is greater than or equal to the Required j DilutionFactor(RDF),or. , , i RDE 1 1.0 [Eq 1-6] 7 ADF Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-6 01/93 l
. l
+
7 1,2 RADIATION MONITOR ALARM SETPOINTS ; 7 1.2.1 Primary Licuid Effluent Monitor XRE-5253 l 8 To ensure that releases from the primary radwaste processing system do not exceed 10 CFR 20 Appendix 8. Table 2 Column 2 limits at the ' point of release to the CONTROLLED AREA or UNRESTRICTED AREA, a ; 7 radiation detector (XRE-5253) monitors discharges to the Circulating , Water Discharge Tunnel. XRV-5253 is the discharge isolation valve ' controlled by XRE-5253. The isolation valve shuts automatically if I the detector alarms on high radiation or a detector operation failure i 10 occurs. It should be noted that the liquid effluent monitor setpoint 7 values determined using the methodology from this section will be 4 regarded as upper bounds for the actual setpoint adjustments. That is, 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. .
. 10 Since the radiation monitor XRE-5253 is a gamma sensitive device the monitor setpoint value shall be set based on the gamma radionuclides present in the waste stream. Therefore, a Required Dilution Factor gama (RDF g ) must be determined before the setpoint can be calculated. f l
RDF g = I (C,/ECL,) X SF [Eq. 1-6t: i Where: RDF 9
= The required dilution factor (ganna) corresponding to the '
gama concentration in the undiluted waste stream
^
ensuring the effluent concentration limits in 10CFR20, , Appendix B, Table 2, Column 2 are not exceeded during a ! release. If RDF 9 is less than 1, set RDFg equal to.l.0. i SF = A required safety factor of 2 is used to account for 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 expected to change rapidly under most plant conditions and statistical errors of measurement. COMANCHE PEAK - UNITS 1 AND 2 PART II 1-7 Rev. 10 4/94
- 10. The monitor XRE-5253 setpoint is datermin:d using tha following calculation:
10 C), = (ADF/RDF g ) x IgCg [Eq. 1-7] 8 Where: C ), = The liquid waste effluent monitor alarm setpoint. This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in Effluent Concentration Limit level releases (uCi/ml). All other variables are as previously defined. I 7 When considering the mixture of nuclides in the liquid effluent stream I in terms of detector sensitivity, the most probable nuclides present would be those 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. 137 In fact between Cs and SO Co the total change in sensitivity is approximately 7%. Because this is well within the accuracy of l 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. 8 1.2.2 Turbine Buildino Sumo 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 7 this discharge from the Low Volume Waste Pond to the Waste Water j Holdup Tanks if radioactivity is detected. Because the only sources of water to the turbine building sump are from the secondary steam system, tetivity is expected only if a significant 8 primary-to-secondary leak is present. Since detectable radioactivity is not normally present in the Turbine Building Sumps, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm, should an inadvertent COMANCHE PEAK - UNITS 1 AND 2 PART II 1-8 Rev. 10 4/94
g radioactive release occur. To this cnd, the setpoint will Da 7 initially cstablish::d at thr&O (3) times background until further data 8 can be collected. Then, if this setpoint is exceeded, the monitor will direct control '9'ves 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 7 Creek Reservoir, if required by Radiological Effluent Control ! 3/4.11.1.1, Table 4.11-1. When radioactive materials are detected in the Turbine Building Sumps, a setpoint then may be established for ' 8 1RE-5100 or 2RE-5100 using the methodology in Section 1.2.1 to ensure that 10 CFR 20 Effluent Concentration limits are not exceeded in cischarges to the LVW Pond. 8 1.2.3 Service Water Effluent Radiation Monitors 1RE-4269/4270 and 2RE-4269/4270 7 The concentration of radioactive material in the service water effluent 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 monitor alarm setpoint determined as follows:
7 C,= 3 (I gC g) + OF [Eq. 1-8] 7 Where:C sw = Service Water effluent monitor alarm setpoint C g
= Concentration of each measured gamma emitter g, observed l
intheeffluent(uC1/ml) 8 0F = I (C j /ECL j g ) = Dilution factor required to ensure effluent concentration limits are not exceeded. 7 For this release pathway no additional dilution is available. 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 4/94
7 release strcam, doses due to releases from this stream shall be calculated in accordance with th3 methodology given in S;ction 1.3, with the near field average dilution factor, Fk, equal to 1.0. 9 1.2.4 Auxiliary Buildina to LVW Pond Radiation Monitor XRE-5251A 9 The purpose of the Auxiliary Building to LVW Pond monitor (XRE-5251A) is to monitor the Auxiliary Building Sumps 3 and 11, Unit 1 and Unit 2 Diesel ; Generator Sumps 1 through 4 and the Unit 1 and Unit 2 Component Cooling Water Drain Tanks continuous discharges 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 spurious alarms and yet alarm should an inadvertent radioactive release occur. To this end, the 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 w 'here 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 detected in the discharges, a setpoint then may be established for XRE-5251A using the methodology in Section 1.2.1 to ensure that 10CFR20 effluent concentration limits are not exceeded in discharges to the LVW Pond.
i f COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9a 4/94
; 1.3 DOSE CALCULATION FOR LIOUID EFFLUENTS 1
For implementation of Radiological Effluent Control 7 1 3/4.11.1.2, the dose commitment from the release of liquid i effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose cormitments 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 L 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 Rese'rvoir. 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)s (Eq 1-9] k n Where DT= the dose commitment to the total body or any organ due 8 to all releases during the desired time interval from allreleasesources(ares). Ok= the dose commitment received by the total body or any 7 i organduringthedurationofreleasek(mres). The equation for calculating Dk is given in Section i 1.3.1 (Eq. 1-10) D(lake)s= the dose commitment received by the total body or any 7 i organ during the desired time period, s (normally a = 31 days) due to the buildup in the lake of previously discharged radionuclides. The equation for calculating 0(lake)misgiveninSection1.3.2(Eq. 1-12). 7 Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-10 01/93
To demonstrate compliance with the dose liaits of Control 8 3/4.11.1.2, thecalculatedcumulativedose(i.e.,thetotal dose for both units) will be compared to two times the dose 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 Licuid Releases 7 The dose commitment to the total body or any organ due to a 7 release will be calculated using the following equation. Ok* Ii 1A tk Cik Fk [Eq. 1-10] 7 Where: tk = the time duration of the release k (hrs) 7 Cik = Theisotopicconcentration(uC1/ml)of 7 radionuclide i found in the release sample for release k. Concentrations are determined primarily from gamma isotopic analysis of the , liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured ) value will be used in the dose calculation. l 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 effluent flow rate is based on the actual average flow into the Circulating water during the release.
1 i Fk = averaae undiluted 11auid affluent flow rate 7 circulating water flow rate Rev. 8 COMANCHE PEAK - UNITS 1 tiND 2 PART II 1-11 01/93
Ari = the site related ing:stion dose commitment 7 factor for the toal body or any organ, r , for each identified gamma or beta emitter (ares /hr per uC1/ml) . Ajr is calculated as follows: Aj, = 1.14x105 (Uw/Dw + Uf BFj) DFj [Eq. 1-11] 7 Where: 1.14x105 = unit conversion factor, 7 ! Uw
= adult water consumption from Squaw Creek 8 i Reservior, 0 liters /yr for CPSES.
Ur
= adult fish consumption, 21 kg/yr 7 BFj = bioaccumulation factor for radionuclide i, in 7 fish from Table A-1, Ref. 2 (pC1/kg per l pCi/1) 7 DFj =
adult dose conversion factor for radionuclide 7 1, from Table E-11, Ref. 2 (ares /pC1 ingested) Dw
=
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 Ajr are given in Table 1.2. -- 1.3.2 Calculation of Dose Due to Radionuclide Builduo in the Lake 7 i l The dose contribution from significant pathways, due to 8 l buildup of previously discharged radionuclides in the lake, l must be considered in the committed dose calculation only if Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-12 01/93
radioactivity is detected in the watcr of Squaw Creek 8 Reservoir or in fish from Squaw Creek Reservoir. Based on the design calculations presented in the CPSES FSAR, Appendix 11A and documented in CPSES Engineering Calculation No. ME-CA-0000-3161, the significant pathwys 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 censu , this pathway should be included in the dose calculation. Also, water from Squaw Creek Reservoir or Squaw Creek is not used as a source of drinking water, so the drinking water pathway is not included in dose calculations. To further simplify the calculation, the dose due to 8
, consumption of meat and milk from cows drinking water from 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 significantly contributes to the dose from these pathways (i.e.,>95%ofthetotaldose). The calculation does show a 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 isotopes.
The contribution to the total dose due to the buildup of 8 I radionuclides in the reservo'ir is determined as follows: b 0(lake), = 1.14x10-4 [(E j DF j C'jf U)+ f 8 l DFt C'tw Oaw (Umilk Fmt + Umeat Fft}l i [Eq. 1-12] i COMANCHE PEAK UNITS 1 AND 2 PART II 1-13 Rev. 8 ERRATA (6/93)
l Wh;re: 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 I this manual-(pC1/kg)- l DFt
= adult ingestion dose conversion factor for 8 tritium for the organ of interest form Table E-11, Ref. 2 (ares /pC1).
C'tw = concentration of tritium in the reservoir. 8 , This value shall correspond to the highest concentration measur9d at any Squaw Creek Reservoir sample location (pC1/1). ; Qaw
=
the consumption rate of contaminated water by 8 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, f 1.0E-2 pC1/1 per pC1/ day from Table E-1, Rev.
- 2. ;
Useat = adult meat consumption rate, 110Kg/yr from 8 Table E-5, Ref. 2. Fft = the stable element transfer coefficient for 8 tritium that relates the daily intake rate of tritium by a cow to the concentration in meat, j 1.2E-2 pC1/kg per pCi/ day. Rev. 8 i PART II 1-14 COMANCHE PEAK - UNITS 1 AND 2 01/93
All oth;r variables are previously d; fined.- 7 , NOTE: This calculation is only required if activity is detected in 7 i water and/or fish in excess of the appropriate LLD values , given in Radiological Effluent Control 3/4.12.1. Table 4.12-1. l If the measured activity in water or fish is less than the { required LLD values, the concentration for that particular ; pathway is assumed to be zero. : 1.4 DOSE 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 . doses due to the liquid effluent from each reactor unit to j CONTROLLED AREAS and UNRESTRICTED AREAS would exceed 0.06 mres ; total body or 0.2 arem to any organ in a 31-day period. The ; following calculational method is provided for performing this 7 j dose projection. j At least once every 31 days, the total dose from liquid 8 releases 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 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 mrom total body , or 0.2 arem for any organ, appropriate portions of the Liquid Radweste Treatment System shall be used to reduce radioactivity levels prior to release. , , l Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-15 01/93
1.5 DEFINITIONS OF COM40N LIOUID EFFLUENT PARAMETERS 7 IEE DEFINITION 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. A17 The site related ingestion dose commitment factor to the 7 total body or any organ, r , for each identified gamma or
- beta emitter, 1. (mrem /hr per uC1/ml)
BF1 Biaccumulation factor for radionuclide, 1, in fish from 7 Reg. Guide 1.109. (pC1/kg per pC1/1) Ca the concentration of alpha emitters in liquid waste as 7 measured in the an& lysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1 Table 4.11-1. (uC1/ml) F The concentration of 55F e in liquid waste as measured Ce 7 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) cg The concentration of each measured galuna emitter, g in the 7 waste tank as measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1 (uC1/ml)
C1 The concentrations of radionuclide, i, in the waste tank. 7 (uC1/ml) C'j The concentration of radionuclide 1 in the Reservoir as 7 measured in the analysis of the monthly sample of the 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. (uci/ml) , C'if The concentration of radionuclide 1 in fish sampled from 7 the reservoir from location F1 on Table 3.1 and Figure 3-1 of this manual (pC1/kg). Cik The isotopic concentration of radionuclide i found in 7 the pre-release sample for batch release k. i Concentrations are determined primarily from genna l isotop,ig ana For l 895r, WSr, dysis H, 55Fofe the andliquid alpha effluent emitters,sample. the -l last measured value will be used. (uC1/ml) COMANCHE PEAK - UNITS 1 AND 2 PART II 1-16 01/93
. .. . .= - . _ . .
l l C'1w The concentration of radionuclide 1 in the reservoir as 7
. measured at the Circulating water intake structure shown as location SW6 on Table 3.1 and Figure 3-1 of this manual (pC1/1).
Cw1 The liquid waste effluent monitor alarm setpoint. This 8 corresponds to the galant concentration in the undiluted waste stream which after dilution would result in ECL-levelreleases.(uC1/ml) Cs The concentration of 895 r and 90S r in liquid waste as 7~ measured 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) Csw The Service Water effluent monitor alarm setpoint. 7 (uC1/ml) Ct The concentration of 3H in liquid waste as measured in the 7 analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1 Table 4.11-1 (uC1/ml) r DF1 Adult dose conversion factor for radionuclide, 1, from 7 : Reg. Guide 1.109(ares /pC1 ingested) Ok The dose commitment received by the total body or any organ 7 durin the duration of batch release k of liquid effluents. : (mrem ' D(lake)s The dose commitment received by the total body or 7 , any organ during a desired time period, m, due to . the buildup in the lake of previously discharged - radionuclides. (mrem) DT The total dose commitment to the total body or any organ due 7 to all releases of liquid effluents during a desired time interval. (mrem) Dv Dilution factor, from the near field area within 1/4 mile of 7 I the release point to the potable water intake for adult water consumption,1.0forCPSES(unitiess) f Effluent flow rate. (gpm) 7 l F Circulatingwaterflowrate(ordilutionflowrate). (gpm) 7 l F' Adjusted Circulating water flow rate to account for buildup 7 of radionuclides in the Circulating water due to previous releases. (gps) REV. 8 , COMANCHE PEAK - UNITS 1 AND 2 PART II 1-17 01/93
,-s J m n Fk The near field average dilution factor during a liquid 7 effluentrelease(unitiess). This is defined as the ratio '
of the average undiluted liquid waste flow to the average Circulating water flow during the release. j ECla Effluent Concentration Limit
- of a mixture of 8 '
unidentified alpha emitters. (uC1/ml) j ECLF e Effluent Concentration Limit
- of 55Fe. (uC1/ml) 8 ECL g Effluent Concentration Limit
- of each identified gauna 8 emitter, g.- (uC1/ml)
ECLj Effluent Concentration Limit
- of radionuclide, 1. 8 (uC1/ml) ffluent Concentration Limit
- of a mixture of 895 r and 8 ECLslOr. S (uC1/ml)
ECL EffluentConcentrationLimit*oftritium(3) H 8 , t (uC1/ml) SF Safety Factor of 2. Used in the calculation of the Required 7 l Dilution Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are
, not exceeded.
RDF RequiredDilutionFactor(unitiess). This is defined as the 8 dilution factor that ensures that the effluent concentrations ' expressed in 10CFR20, Appendix B, Table 2, Column 2, are not exceeded during a discharge. ; tk Thetimedurationofbatchreleasek.(hours) 7 Uf Adult fish consumption. (kg/yr) 7 Uw Adult water consumption. (liters /yr) 7
*EffluentConcentrationlimits(ECL)forliquidsaregivenin 8 10CFR20, Appendix B, Table 2. Column 2. A value of 2x10-4 ,
uC1/m1 for dissolved or entrained noble gas shall be used. ' i l l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-18 01/93
7 TABLE 1.1 7
SUMMARY
OF LIOUID RELEASE PATHWAYS 7 1. RELEASES TO SCR VIA THE CIRC WATER DISCHARGE Release Source Release Type Max Flow Max Vol Monitor Rate (com) (aal) 7A PET-1 Batch 100 30000 XRE-5253 i PET-2 Batch 100 30000 XRE-5253 i 7 WMT-1 Batch 100 5340 XRE-5253 i WMT-2 Batch 100 5340 XRE-5253 LHMT-1 Batch 100 5875 XRE-5253 LHMT-2 Batch 100 5875 XRE-5253 9 WWHT-1 Batch 200 30500 None i WWHT-2 Batch 200 30500 None 7 LVW Pond Continuous 1600 - None
- 2. RELEASES TO THE LVW POND Release Source Release Type Max Flow Max Vol Monitor i Rate (ana) (cal) 11 CPBWRT-A Batch 1550 8500 None CPBWRT-B Batch 1550 17000 None 9 WWHT-1 Batch 200 33100 None WWHT-2 Batch 200 33100 None 7 TBSump2(Uniti) Continuous 300 -
1RE-5100 8 TBSump4 (Unit 2) Continuous 300 - 2RE-5100 9 AB Secondary
- Continuous 380 -
XRE-5251A 7 3. DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) Release Source Release Type Max Flow Max Vol Monitor Rate (com) (aal) 8 Unit 1 SSW Train A Continuous 17,000 - 1RE-4269 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 i 9 HQIE-
- AB Secondary Effluents contain the following sources: l 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 l CCWOT (Unit 1) 40 l CCWDT (Unit 2) 40 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-19 REV. 11 11/94
1 TABLE 1.2 7 PAGE (1 of 4) SITE RELATE 0 INGESTION DOSE COMMITMENT FACTOR A17 j (mrem /hrperuC1/ml) l ISOTOPE B.Qtli LlyIR T-BODY THYROID KIDEY l&tiG GI-LLI i 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 MOS4 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 I
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 0.00E+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 l 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 ) BR-85 0.00E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 8 RB-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 RB-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 2.21E4tl 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 0.00E+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 Y-91M 5.44E-03 0.00E+00 2.11E-04 0.00E+00 0.00E+00 0.00E+00 1.60E-02 8 Y-91 8.45E+00 0.00E+00 2.25E-01 0.00E+00 0.00E+00 0.00E+00 4.64E+03 8 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 1 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-20 01/93
- . . ___________ _ __ _____-_______A
i TABLE 1.2 7 l' PAGE (2 of 4) SITE RELATED INGESTION DOSE CGetITMENT FACTOR Ajr , (d em/hr per uC1/ml) ISOTOPE SQt!E Llyfd T-BODY THYROID flDjlEl UHifa 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 1.96E+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 . TE-125M 2.57E+03 9.29E+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00 1.02E+04 8 TE-127M 6.49E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 8 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 > TE-131M 1.066+03 8.11E+02 6.75E+02 1.28E+03 8.21E+03 0.00E+00 8.04E+04 8 i 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 1.50E 2.14E+02 1.22E+02 6.99E+04 3.68E+02 0.00E+00 5.64E+01 8 r I-132 7. 1.95E 41- 6.81E+00 6.81E+02 3.10E+01 0.00E+00 3.68E+00 8 ! I-133 5.09E M 8.86E+01 2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.96E+01 8 l 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 i CS-134 2.98E+05 7.09E+05 5.79E+05 0.00E+00 2.29E+05 7.62E+04 1.24E+04 8 ! CS-136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.39E+03 1.40E+04 8 CS-137 3.81E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E404 1.01E+04 8 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 - UNITS 1 AND 2 PART II 1-21 01/93
TABLE 1.2 7 PAGE (3 of 4) SITE RELATED INGESTION DOSE COMITMENT FACTOR Aj, (idem /hr per uC1/ml) ISOTOPE SQ!!E LIgg T-BODY THYROID KlHf,1 LMG GI-LLI 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 8 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 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 PR-144 1.AQE-03 7.49E-04 9.16E-05 0.00E+00 4.23E-04 0.00E400 2.59E-10 8 NO-147 3.76E-01 4.35E-01 2.60E-02 0.00E+00 2.54E-01 0.00E+00 2.09E+03 8
'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
*SB-122 4.42E+00 8.71E-02 1.29E+00 6.01E-02 0.00E+00 2.30E+00 1.27E+03 8
**SB-124 5.38E+01 1.01E+00 2.12E+01 1.30E-01 0.00E+00 4.18E+01 1.52E+03 8 -
**BR-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 0.00E+00 4.45E+03 3.78E+02 8
**SB-126 2.20E+01 4.47E-01 7.93E+00 1.35E-01 0.00E+00 1.35E+01 1.80E+03 8
**S8-127 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 '
N i e 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- , l related ingestion dose commitment factors for Sb-122 is docu mnted in Reference 10. .
** 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 related dose commitment factors for Sb-124, Sb-125. Br-82, Sb-126 Sb-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, Section 1.3.1 of this Manual.
t I s e S , i REV. 8 , COMANCHE PEAK - UNITS 1 AND 2 PART II 1-23 01/93
l l l unit 1 SSW-Train A O uquid Waste ' "d* E Processing l unit 1 SSW-Train BM [Outtau 501\
$ System 1E-4270 e sese Shutdown (see page 2) l unit 2 SSW-Train A H i , 33. loo ,ee. 3 x=52s3 I un= 2 SSW-Tr* a F ;;g,,,
$ MPE ,
A " '**' 5 - = foo,,,,, ,gh / N C Weste Water a U OutisN 201 Z , . , _ .
" Cirt Wetw r 9 W Tanks A: 8500 gal /1550 gpm Discharge Squaw Creek
{ (2 tanks) B: 17000 gel /1550 gpm C. P.
\Tunnet/ \
h Backweeh iL o 3,73 ,
._4.. ...,.
80 0 300 gen Tanks I K-5100 3 AW8 unal - T Turbine o U _ aussng a a n _. Sunp No. 2 gtj } \ j n Low wune Waste Ponds b 1ers get 300 gem ay Turbine sumeng 7242gai Una 2 2 E s100 X Chemical 150 gpm Turbine u
- ) XE-5251A Sump No.4 a a n n n RGURE 1.1 (page 1 of 2) unit I una2 ^*d"*'Y UQUID EFFLUENT una1 una2 DieselGen. DieselGen. Ihdding Sumps Sumps CCW M CCW Drain DISCHARGE PATHWAYS Tank Tank 8"*P'
-- .x.. Nos.1 & 2 Nos.3 & 4 Nos. 3 & 11 NEY:
21 ~ 135 gol es. 135 gol ea. 2300 gal 2300 gel - 135 gal ea. N 50 gpm es. 50 gpm es. 40 apm 40 gpm 50 opm es. - Flow path ll >MPC Flow Path N <MPC
.zm. . -
l 8 LIOUID WASTE PROCESSING SYSTEM m naams CHAesIEL A l DRAge enaansassa B l DRA888 Cesaasawa C I i m w,g, g Egydysm t Dr.i.e Ft r Dr.4.s L.h Lau.assy & to.4 r Tk + ~~ , ,e .-. e. ~~ , ~ ,r , ~ g Shake Acces-estet.,g, suggage.g 388.P. X l 9,.bne l J __ l 1 s , , , ..e.. i J L Q s.n W Ew.p.' I Ew.p.t.t., 8 A.w.re. O.m.ete I p.st.go l P.ch.g.
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l e _ 4-l a g Car..s.mmewe., a e - -a- De e g St.r.g. T te g FIGURE 1.1 (page 2 of 2) LIQUID EFFLLENT DISCHARGE PATHWAYS 1 NOTES: O, f 0) Sp. red h pl.co g4 m Duch sge volve cape.e on j w on monsor n e.d. no.e of now, or a ch.nn.1 out-of-s.rwice al.rme. l
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- 3 3 1 3 3 5 2 2 1 aa, amu . wuu, i lll .- 1_. . L 1_.. .- _L_-_- __L_ _L_ .1 .. l l l
COMANCHE PEAK - UNITS 1 AND 2 PART II 1-26 01/93
l l l 1 50 I 40 30 N \ 2 x 1 [ % % , .. k :- / 2C l - f f Cs13 II_ 10 l f .._ 9 co~ 8 7
)
6 5 0 0.2 0.4 0.8 0.8 1.0 1.2 1.4 GAMMA PHOTON ENEAGY, MeV ENERGY RESPONSE TO CAMMA RADIATIONS
, FOR RD-33 TYPE DETECTOR 1 Figure 1.3 irneare n ,s n e. . ,,, ,no. ,,y c ,,,,,, ,, , ,,, ,,,,,,,,
- Based on one m ser W
;w.se l
COMANCHE PEAK - UNITS 1 AND 2 PART II 1-27 0143
4 i SECTION 2.0 ; GASEOUS EFFLUENTS > 8 . At CPSES, normal radioactive gaseous effluents are collected in a ! common exhaust air intake plenum, processed through charcoal and HEPA : V tc de a S k d c B Du o e t 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), i 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
. WGOT discharges are treated as batch releases. Because Containment !
Building purges are only allowed during MODES 5 and 6 ej 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 remainder of a purge is treated as a contribution to the continuous ' release already occurring through the plant vent stacks. i i 8 Operating experience has shown that occasional releases may be required ! from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS l during outages, from Volume Control Tank (VCT) vents during maintenance j on the Waste Gas Processing System, from the Containment Buildings during Integrated Leak Rate Tests (ILRT), and from secondary steam f releases (potentially radioactive during periods of primary-to-secondary leaks). These releases occur infrequently and are treated as batch releases. 1 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-1 Rev. 10 4/94
A sussiary 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 ; f effluent discharge pathways is shown in Figure 2.1. l Each Plant Vent Stack is equipped with a Wide Range Gas Monitor 8
- l. (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.,uCi/ml). The conversion factor for detector output from counts per minute to uC1/m1 is determined during the calibration of each individual monitor, and is input into the data base for the monitor microprocessor.
. The WRGMs are designated as monitors XRE-5570A and ).tE-55708 for
,, Stacks A and B, respectively. Each WRGM consists of a low range
(10-7 to 10-l'uC1/cc), mid range (10-4 to 102 uCi/cc),
~
and high range (10-1 to 105 uC1/cc) noble gas activity-detector. The WRGMs also have an effluent release rate channel 4 which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X-FT-5570A-1/8-1) 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 Radiological Effluent Control 3/4.3.3.5. Execeeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic terutnation of Waste Gas Decay Tank releases. I 1 The stack PIGS are designeted as particulate channels XRE-5568A and XRE-55688, iodine channcis 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 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 control are the Auxiliary Building Ventilation Duct Monitor, XRE-5701, and the Containment PIG Noble Gas Monitors,.1RE-5503 and 2RE-5503. XRE-5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct. 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 provide the only automatic control function for termination of Containment vents or purges. 2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 CCMPLIANCE 8 2.1.1 Dose Rates Due to Noble Gates For implementation 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 rate due to noble cases 8 D=IDtv g = I v(X/Q) % K; O y [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(uRee/yr) j i Dv= t the total body dose rate at the SITE 8 { BOUNDARY due to noble gases from release l sourcev(wres/yr), i Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-3 01/93 i
. a
(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 *.)
~
NOTE: The annual average X/Q 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 gama 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 ' rom the release source v (pC1/sec) (Seu C below for calculation of Qiv) v = index over all release sources 8 B. Skin dose rate due to noble cases D=ED3y = I(X/Q) (L i+ 1.1 M i) Q y 3 E v v (noble gases) 8 Where: Ds = the skin dose rate at the SITE BOUNDARY due 8 to noble gases from all release sources. (mrem /yr) Dsy= 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
r i
)
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 l l mrad air dose. i
)
Mi= air dose factor due to gamma emissions from 8 l noble gas radionuclide i from Table 2.2 (mRao/yrperpC1/m3) All other terms are as previously defined. > P C. Release Rate 8 Qj is defined as the total release rate (pC1/sec) of 8 radionuclide i from all release sources. Qj is given by: , Q=IQ$y = 4 IX jyFy [Eq. &3] lB v v ; Where: Xjy = the measured concentration of radionuclide 8 i 1 present in each release source v i (pC1/cm3) ry = the flow rate from each release source v 8 : (cm3/ sec) Qjy = the release rate of radionuclide i from 8 release source v (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 i 1 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-Do = I D, = I (X/Q) I P; Qi I v v IP&T [Eq. 2-4} Rev 8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-5 01/93 l
Where: Do
= the total organ dose rate due to iodine-131, iodine-133, particulates with 8 half-lives greater than eight days, and tritium from all release sources. -
1 (mres/yr.) Day = the organ dose rate due to iodine-131, 8 ) iodine-133, particulates with half-lives ; greater than eight days, and tritium from ! releasesourcev(ares /yr) Pj = pathway dose rate parameter factor for 8 radionuclide, 1, (for radiciodines, ' particulates, and tritium) for the inhalation pathway in den /yr per uCi/m3 (Table 2.3). The methodology used for , determining values of Pj is given in ; Appendix A.. IP&T = iodine-131, iodine-133, particulates with , half-lives greater than eight days, and tritium. These are the isotopes over which 8 the summation function is to be performed. All other variable are previously defined. 2.2 GASEOUS 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. Rev8 PART II 2-6 01/93 co"^"c!EPEAK-UNITS 1AND2
n I' 2.2.1 Plant Vent Effluent Release Rate Monitors 8 XRE-5570A and XRE-55708 Effluent Release Rate Channels The WRGM effluent release rate channels monitor the 8 release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble gas activity channel (uC1/cm3) indication and a stack j flow rate (cm3/sec) indication (X-FT-5570A-1/B-1) to j 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 I rate will cause an alarm trip. The WRGM effluent channel I 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: 500 X SF = 125 QNG ,
,_. l IONG } D t
site = the lesser of Q 3000 X SF = 750 QNG Q NG [Eq.2.6] s s Where: Qsite = the total site noble gas release rate limit 8 corresponding to a dose rate at the SITE BOUNDARY of 500 mres/yr to the total body or 3000 mres/yr to the skin (uci/sec) ! E QNG = (noble gases) Qj 8
=
the actual release rate of noble gases from 8 , all release sources as calculated from the ! radionuclide concentrations determined from l the analysis of the appropriate samples taken in accordance with Radiological l Effluent Control 3/4.11.2.1. Table 4.11-2 l 500 = the dose rate limit to the total body of an 8 individual at the SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) l l Rev 8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 2 7 01/93
i 3000 = the dose rate limit to the skin of the body 8 of an individual at the SITE BOUNDARY due to noble gases from all release sources. (mrem /yr) SF = Safety Factor of 0.5 applied to 8 compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks. (unitiess) Then the release rate setpoint for each stack monitor, 8 Cr, in uCi/sec is determined as follows: Cr = Qsite AF [Eq 2-7] Where: AF = Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitiess). This factor 8 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 8 XRE-5570A/XRE-55708 (WRGN low rance noble ans activity 8 l channel) and XRE-5567A/XRE-5567B (PIG noble aat channel). The WRGM low range noble gas activity channels provide 8 noble gas 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. Therefore, setpoint adjustments are not performed for these channels. Radiological 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- l 55678) as a backup for an inoperable WRGM effluent Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-8 01/93
n release rate channel wh;n no automatic control function is 8 required. Th3 alarm setpoint for th2se channels, C G in uC1/cm3, is determined using the following methodology: r [Eq. 2-8) 8 Cr
- c, , 7g )
Where: Fpys = the maximum stack flow rate 8 (cc/sec)correspondingto 115,000 ' cfm during normal operations and 130,000 cfm during containment purges. 2.2.3 h aler Flow Rate Monitors (X-RFT-5570A-1/B-1) 8 The WRGMs are designed to sample isokinetically from the plant vent stacks. Isokinetic sample flow is maintained 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 setpoints are established permanently in accordance with vendor specifications. ; 2.2.4 Auxiliary Buildino Ventilation Exhaust Monitor (XRE-57011 8 . Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, 8 ACTION 34, allows for the Auxiliary Building Ventilation { (A8V) Duct Monitor (XRE-5701) to be used as a backup for an inoperble WRGM for monitoring Waste Gas Decay Tank i (WGOT) releases. XRE-5701 monitors WGOT releases by measuring activity in the Auxiliary Building Vent Duct and providing an automatic control function for termination of 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: l (1) a waste gas decay tank release is the An.ly batch 8 release occurring (i.e., a containment purge or vent is not occurring at the same time). Rw 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-9 01/93
j 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 WGDT release. These are the WGDT batch release, the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/3 will be used for the ABV monitor setpoint determination. The total release rate from the site at the alarm sutpoint reisase rate from each stack would correspond to a value of 2Cr uC1/sec. ! To determine the ABV monitor setpoint, the release rate l contribution from the ABV will be limited to 1/3 of the limiting site release rate: I l O aux = 1/3 2Cf= 2/3 C f [Eq.2-9] Where: Qaux = The limiting release rate 8 ; contribution from the Auxiliary
, Building Vent during WGOT releases !
.,, (uC1/sec)
Other terms have been previously defined. 8 To determine the setpoint, Caux, for the ABV monitor in uC1/cc, the limiting A8V release rate is divided by the 8 maximum ABV flow rate: C,yx = = [Eq.2-10] aux aux Where: Faux = the maximum A8V flow rate (cc/sec) 8 corresponding to 106,400 cfa. 3.2.5 containment Atmotohere Gaseous Monitors (1RE-5503 and 2RE-5503) 8 For 1mplementation 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 i setpoint calculation is based on the following assumption: Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-10 01/93
r (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 determination. The total release rate , from the site at the alarm setpoint release rate from each 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: - Q cong -{ 2Cf=}C f [Eq.2-11] Where: Qcont = the limiting release rate 8 contribution from a containment release (uC1/sec) Other terms have been previously defined. 8 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: O C f Ccont " contFcont
- 2cont F [Eq.2-12]
Where: Fcont = the maximum containment release 8 flow rate (cc/sec) corresponding to 750 cfm for containment vents and ; . 30,000 cfm for containment purges. l l Rev 8 1 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-11 01/93
8 2.3 DOSE CALCULATIONS FOR GASEOUS EFFLUENTS 8 The methodologies for calculating doses from gaseous effluents 8 are given in Sections 2.3.1 and 2.3.2 below. For purposes of demonstrating compliance with the dose limits of Radiological ' Effluent Controls 3.11.2.2 and 3.11.2.3, the calculated cumulativedoses(i.e.,thetotaldoseforbothunits)willbe compared to two times the dose limits for a unit. In other words, the doses assigned to each unit will be one-half the total doses from all releases from the site. l 2.3.1 Dose Due to Noble Gases 8 For implementation of Radiological Effluent Control 8 3/4.11.2.2, the cumulative air dose due to noble gases i to areas at and beyond the SITE BOUNDARY will be l calculated at least once per 31 days and a cumulative summation of the air doses will be maintained for each
~~~
calendar quarter and each calendar year. The air dose over the desired time period will be calculated as follows: I A. Air Dose Due to r.a-- Emissions 8 l Dy = air dose due to gamma emissions from noble gas 8 radionuclides from all release sources (arad) D y = 3.17 x 10-8 (yg) (noble gases) Mi U i [Eq.2-13] 8 l l
- Where: 3.17 x 10-8 = the fraction of a year represented 8 by one second Q'j = the cumulative release of radionuclide i during 8 the period of interest from all relemet sources (uC1)
(Q'j = Qj (uC1/sec) x release duration (sec)) 8 Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-12 01/93
Q'j is based on the noble gas activities in 8 each plant vent stack and WGDT or Containment Samples required by Radiological Effluent i Control 3/4.11.2.1, Table 4.11-2. ) All other variables are previously defined.
- 8. Air Dose Due to Beta Emissions 8 f
Dg= air dose due to beta emissions from noble gas 8 radionuclides (arad) Dg = 3.17 x 10-8 (X/7) (noble gases) N g Q'4 [Eq.2-14] 8 Where: N1= the air dose factor due to beta emissions from 8 noble gas radionuclide i from Table 2.2 (mrad /yrperuC1/m3). All other variables are previously defined. 8 Note: If the methodology in this section is used in 8 determining dose to an individual rather than air dose due to noble gases, substitute Kj for Mj, (Lj + 1.1 Mj) for Nj, and the Annual Average X/Q values from Table 2.5 for the l highest annual average relative concentration ; (X/Q) at the SITE BOUNDARY. ! 2.3.2 Dose Due to Radiciodines. Tritium. and Particulates 8 For implementation of Radiological Effluent Control 8 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 and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year. The dose over the desired period will be calculated as follows: Op = pgfHs3 17
- 10 W' IP T, i,a o i Q'j [Eq.2-15]
nov s COMANCHE PEAK - UNITS 1 AND 2 PART II 2-13
[( l Where: Dp = dose due to all real pathways to organ, o. 8 of an 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 I releasesources(mrem). W' = the dispersion parameter for estimating the 8 dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. Locations of interest are listed in Table 2.5, W' = X/Q for the inhalation pathway in sec/m3, X/Q is the annual average relative 8 concentration at the location of interest. Values for X/Q are listed in Table 2.5. If desired, the highest individual receptor X/Q or X/Q valve may be used, or W' = D/Q for the food and ground plane pathways 8 in m-2 0/Q is the annual average deposition at the location of interest. Values for D/Q are listed in Table 2.5. If desired, the highest individual receptor D/Q or D/Q value may be used. NOTE: For tritium, the dispersion parameter, W' 8 is taken as the annual average X/Q values from Table 2.5 for inhalation, food and ground plane pathways. RPi .a.o
= dose factor for radionuclide 1, 8 pathway p, age group a and organ o, in mrem /yr per uCi/m3 for the inhalation pathway and m2(nRem/yr) per uCi/sec for food i and ground plane pathways, except for tritium which is in mrem /yr per uC1/m3 for all pathways. The values for Rpi a.o for each pathway, radionuclide, age group and organ are listed in Table 2.4.
Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-14 01/93 l 4
l The methodologies used for determining 8 values of RP 1,a,o for each pathway are given in Appendices B through F. l Q'j = cumulative release of radionuclide, i. 8 duringtheperiodofinterest(uC1).Q'j is based on the activities measured in each plant vent stack from the analyses of the I particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1 Table 4.11-2. l I&PT = Iodines, particulates with half-lives 8 greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed. PATHS = The real pathways of exposure to 8 individuals at the locations of interest as indicated in Table 2.5. 2.'4 DOSE PROJECTIONS OR GASEOUS EFFLUENTS 8 Radiological Effluent Control 3/4.11.2.4 requires that 8 appropriate portions of 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 and beyond the SITE BOUNDARY would exceed, in a 31-day period, either: j 0.2 mrad to air from gamma radiation; or 8
)
0.4 mrad to air from beta radiation; or 8 l 0.3 mrom to any organ of a MEMBER OF THE PUBLIC. 8 i i The following calculational method is provided for performing 8 this dose projection: At least once every 31 days the galuna air dose, beta air dose and 8 , 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 Rev 8 , COMANCHE PEAK - UNITS 1 AND 2 PART II 2-15 01/93
include the estimated dose du3 to 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 tne PRIMARY PLANT 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 REQUIREMENTS For the purpose of implementing the requirements of Radiological f 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 assessment shall be a summary of the doses determined in accordance with Section 1.3 for doses due to liquid effluents, Section 2.3.1 for air doses due to noble ~ gases, and Section 2.3.2 for doses due to iodines, tritium, and particulates. This sa.me 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 BOUNDARY. 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 I 8 census shall be performed using the methodology in Section 2.3.2, l 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 l use census changes, the critical location (i.e., the location where an l individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest milk animal, and the nearest COMANCHE PEAK - UNITS 1 AND 2 PART II 2-16 Rev. 10 4/94
[ vegetable gard;n, Additionally, when a location is'idantified that yields.a calculated dose 20% greater than at a location where environmental samples are currently being obtained, add the new location within 30 days to the Radiological Environmental Monitoring locations j described in Section 3.1 of this manual. ! 1 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 j 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 event calculated doses from the , effluent releases exceed twice the limits of Controls 3/4.11.1.2, f 3/4.11.2.2, or 3/4.11.2.3. This assessment will be included in the l 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. i However, more encompassing and realistic assumptiors will be made l 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 i 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 (Mg ) to determine the total body dose. Otherwise .the same calculational sequence applies. More realistic assumptions will be made concerning > the actual location of real individuals, the meteorological conditions, and the consumption of foods Data obtained from the latest land use census should be used to COMANCHE PEAK - UNITS 1 AND 2 PART II 2-17 Rev. 10 ! 4/94
l J determine locations for evaluating doses. The results of the 18 Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured-radionuclide concentrations. The dose component due to direct radiation may be determined by 8 + calculation or actual measurement (e.g., thermoluminescent dosimeters, micro-R meter, etc.). The calculation or actual measurement of direct radiation shall be documented in the i Special Report that must be submitted if this determination is required. 1 2.6 METEOROLOGICAL MODEL 8 , 2.6.1 Disnersion Calculations 8 Atmospheric dispersion for gaseous releases is calculated 8 using a str&ight line flow Gaussian model similar to the Constant Mean Wind Direction model given in Regulatory Guide 1.111, Section C.1.c. The method given here is . 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: , f=2.0326K i Nr [ q. -6] I 3(r) 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 in dose calculations. Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-18 01/93
7 K = terraincorrectionfactor(Figure 2.5) 8 njk = the number of hours meteorological conditions are observed to be in a given l wind direction, wind speed class, k, and atmospheric stability class, J. ; N = total hours of valid meteorological data throughout the period of release. 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 in the model. r = downwind distance from the release point to 8 the location.of interest (meters)- ujk = the average windspeed (midpoint of 8 windspeed class, k) measured at the 10 meter level during stability class j. (meters /sec) Ij(r) = the vertical plume spread with a volumetric 8 correction for a release within the building wake cavity, at a distance, r, for stability class, j, expressed in meters. NOTE: All parameters are considered dimensionless unless 8 otherwise indicated. The equation for calculatin9 Ij(r) is: 8 (aj 2 + 0.5 b2j ,)1 [Eq. 2-17] I (r) j = the lesser of
/Ta j [Eq. 2-18]
Where: aj = the vertical standard deviation of 8 . materials in the plume at distance, r, for atmospheric stability class, j, expressed in meters (Figure 2.3) l Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-19 01/93
f~1 0.5 = the building shape factor. 8 b = the vertical height of the reactor 8 containment structure (79.4 meters) 2.6.2 Deposition Calculations 8 The relative deposition per unit area is calculated as follows: 8 KDz h*0.392 r [Eq.2-19] Where: D/Q = deposition per unit area normalized by 8 sourcestrength(m-2) 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 used, z is set equal to 8 one. 0.3927 = the width in radians of a 22.50 sector. 8 Other variables are as previously defined. 8 i i NOTE: All parameters are considered dimensionless unless 8 otherwise indicated.
\
i nw a l CDMANCHE PEAK - UNITS 1 AND 2 PART II 2-20 01/93 I i
I l 2.7 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS 8 IER Definition l 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 i limit for the site B vertical height of the reactor containment structure C G the alarm setpoint for each plant vent stack noble gas 8 activity monitor (uC1/cm3) Cf the alarm setpoint for each plant vent stack effluent release rate monitor (uC1/sec) ) l caux the Auxiliary Building Ventilation Exhaust monitor
... alarmsetpoint(uC1/cm3) ccont the Containment Atmotphere 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 (des /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 (des /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 s COMANCHE PEAK - UNITS 1 AND 2 PART II 2-21 01/93
~
[ l i Igra Definition l I Skin dose rate at the-SITE B0UNDARY due to noble gases
~
- Ds- 8 from all release sources. (mrem /yr)
J Dsy Skin dose rate at the SITE BOUNDARY due to noble 8 gases from release source v. (mrem /yr) j i i Dt . Total body dose rate at the SITE BOUNDARY due to noble 8 l gases from all release sources. (mrem /yr) l Dvt 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) l t Dy Air dose due to gamma emissions from noble gases from all 8 ! release. sources. (mrad) I D/Q Annual average relative deposition at the location of interest. (m-2) l 6 Plume depletion factor at distance r for the appropriate ; stability class (radiciodines and particulates). ; 8 Fy Flow rate from each release source v. (cm3sec)
/ 8 Faux Maximum Auxiliary Building Ventilation flow rate 8 !
(cm3/sec)correspondingto 106,400 cfm. Fcont Maximum containment release flow rate (cm3/sec) 8 corresponding to 750 cfm for containment vents and 30,000 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. COMANt,HE PEAK UNITS 1 AND 2 PART II 2-22 Rev. 8 , ERRATA (6/93)
$ Jgg, Definition K terrainrecirculationfactor(Unitiess) 8 Kj total body dose factor due to gasuna emissions from noble 8 gas radionuclide 1 (des /yr per uCi/m3) L1 skin dose factor due to beta emissions from noble gas 8 radionuclide1(des /yrperuC1/m3) Mi air dose factor due to gamma emissions from noble gas 8 radionuclide1(des /yrperuC1/m3) i Ni air dose factor due to beta emissions from noble gas 8 radionuclide 1 (d es/yr per uC1/m3) 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 N total hours of valid meteorological data 8 P1 pathway dose rate parceeter-for radionuclide 1, (other 8 thannoblegases)fortheinhalationpathway(des /yrper uC1/cm3) Qaux the limiting release rate contribution from the 8 Auxiliary Building Vent during WGOT releases (uC1/sec) Qcont the limiting release rate contribution from a containment 8 release (uC1/sec) Qj total release rate of radi:muclide i from all release 8 sources (uC1/sec) Rev 6 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-23 O
g Definn1 inn Qjy the total release rate of radienuclide i froa release 8 source v (uC1/sec) Q'j cumulative release of radionuclide i during the period 8 of interest from all release sources (uC1) I QNG the actual release rate of noble gases from all 8 l release sources as calculated from the radionuclide j concentrations determined from analyses of samples , taken in accordance with Control 3/4.11.2.1, Table 4.11-2 QSITE the total site noble gas release rate limit corresponding 8 i to a dose rate at the SITE BOUNDARY'of 500 mrem /yr to the $ total body or 3000 mRom/yr to the skin (uci/sec) RPi ,a.o dose factor for radionuclide 1, pathway p, and age group 8 a, and organ o (mrem /yr per uC1/m3) or (m2. mrem /yr per l
.. uC1/sec)
~ r distance from the point of release to the location of 8 interestfordispersioncalculations(meters) . i SF Safety Factor of 0.5 applied to compensate for 8 statistical fluctuations, errors of measurement, and non i uniform distribution of release activity between the stacks Ej(r) vertical plume spread with a volumetric correction for a 8 i release within the building wake cavity, at a distance, r, for stability class, j, expressed in meters > aj vertical standard deviation of the plume concentration (in 8 meters),atdistance,r,forstabilitycategoryj l
~
jk wind speed (midpoint of windspeed class k) at ground 8 level (m/sec) during atmosphere stability class j j Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-24 01/93
IEg Definition W' the dispersion parameter for estimating the dose to an 8 individual at the location where the combination of existing pathways and receptor age groups indicates the maximum exposures X/Q the annual average relative concentration at the location 8 of interest (sec/m3) X/Q the hightest annual average relative concentration at the 8 SITEBOUNDARY(sec/m3)(3.3x10-6sec/m3 in the NNW sector) Xyi the measured concentration of radionuclide i present in each release source v (uCi/cm3) z
~
the fraction of time the wind blows to the sector of 8 interest 1.1 conversion factor of mrem skin dose per mrad air dose 8 500 the dose rate limit to the total body of an individual at 8 I the SITE BOUNDARY due to noble gases from all release ; sources (den /yr) ! 3000 the dose rate limit to the skin of the body of the 8 individual at the SITE BOUNDARY due to noble gases from allreleasesources(den /yr) Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-25 01/93
n h TABLE 2.1 a l8
SUMMARY
OF GASEOUS RELEASE PATHWAYS A l8 N 1. RELEASES VIA THE PLANT VENT STACKS 8 E RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfa)
] MONITORfS) l8
, R Stack A Continuous 115.000 XRE-5570A/XRE-5567A 8 Stack 8 Continuous 115.000 XRE-55708/XRE-55678 N 8 WGOT's Batch 20 XRE-5570A&B/XRE-5701 8 U-1 Cont. Vent. Batch 750 1RE-5503 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 s E
- 2. RELEASES VIA THE ILRT VENT ,
l8 7
$ RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfa) MONITOR (S) 8 ILRT Batch - -
8 EE g .< sa 3 3 3
-- ___.____. _ __ _ . _ _ _ _ _ _ - _ _ _ . _ _ - e _ - - + - - *- -wi- .--e -+r--- - ___ _ _ _ _ _ _ _ _ _ . ___ _ _ _ _ _ _____m ,e
TABLE 2.2 8 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- Isotone Y-Bodv***(K) B-Skin ***(L), Y Air **(M) B-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 1.34E403 1.72E+01 1.95E403 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 1.73E+04 1.06E+C4 Kr-90 1.56C+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 4 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.1,38 8.83E+03 4.13E+03 9.21E403 4.75E+03 Ar-41 8.84E+03. 2.69E+03 9.30E+03 3.28E+03 ,
- Values taken from Reference 2. Table 8-1
** mrad-m3 uCi-yr *** y
. uC1-yr i Rev 8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-27 01/93 l
A f TABLE 2.3 PATHWAY DOSE RATE PARAMETER (Pi)*
- BASED ON THE INHAIATION PATHWAY FOR THE CHILD AGE GROUP l ORGAN DOSE FACTORS NUCLIDE l.............................-..-....................................
l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI l ................................................................................ H.3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P.32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN 54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE.55 4.74E+04 2.52E+04 7.77E+03 0.00EM0 0.00E+00 1.11E+05 2.87E+03 FE.59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 Co.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 a Co.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00EMO 7.07E+06 9.62E+04 l NI.636- 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 1.13E+05 7.03E+04 0.00E+00 7.14E+04- 9.95E+05 1.63E+04 I
. RB.86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 I SR-89 5.99E+05 0.00E+00 1.72E+04 0.00540 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y.91 9.14E45 0.00E40 2.44E+04 0.00EM0 0.00E+00 2.63E+06 1.84E+05 ZR.95 1.90E+05 4.18E+04 3.70544 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 7.03Ed 3 6.62E+05 4.48E+04 RU.106 1.36E+05 0.00E+00 1.69E44 0.00E+00 1.84E+05 1.43E+07 4.29E+05 AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00840 2.12E+04 5.48E+06 1.00E+05 TE.125N 6.73E+03 2.33E+03 9.14E+02 1.92EM3 0.00E40 4.77E+05 3.38E+04 TE.127M 2.49E+04 8.55E+03 3.02E4 3 6.07E43 6.36E+04 1.48E+06 7.14E+04 l TE.129K 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1 131 4.81E+44 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03
................................................................................ l I.133 1.66E+04 2.03E+04 7.70E+03 3.85E46 3.38E+04 0.00E+00 5.48E+03 l CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E40 3.30E+05 1.21E+05 3.85E+03 CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS.137 9.07 EMS 8.25E+05 1.28E+05 0.00E+00 2.82EM5 1.04E+05 3.62E+03 AA.140 7.40E+04 6.48E+01 4.33E+03 0.00E400 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E43 0.00E+00 8.55E43. 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17EM6 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 - LNTS 1 APO 2 PART I 2-28 b8 01/93
l l l TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ALL PATHWAY: GROUND PIME l ORGAN DOSE FACTORS NUCLIDE j.........--.......... l T. BODY SKIN 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 1.62EM9 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 110N 3.44E+09 4.01E+09 TE.125N 1.55 EMS 2.13E+06 TE.127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31E+07 I.131 1.72E+07 2.09E+07 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 l BA.140 2.06E+07 2.36E+07 !
l CE.141 1.37E+07 1.54E+07 CE.144 6.96E+07 8.05E+07 PR.143 0.00E+00 0.00E+00 I 1 ND.147 8.39E+06 1.01E+07 j J Rev 8 COMANCE PEAK - UMTS 1 APO 2 PART I 2-29 I i 1
TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS. COW.NIIK l ORGAN DOSE FACTORS NUCLIDEl.............................-...................................... l BONE LIVER T. BODY 11tYROID KIDNEY LUNC 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. 91.E+09 CR.51 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 l MN.54 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 l FE.55 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 FE 59 2.97E+07 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 0.00E400 0.00E+00 9.54E+07 CO-60 0.00E+00 1.64E+07 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 0.00540 0.00E+00 9.71E+07 ZN.65 .s.l.37EM 9 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 2.74E+09 RS.86 0.00E+00 2.59E+09 1.21E+09 0.00E+00- 0.00E40 0.00E+00 5.10E+08 SR.89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E+08 SR-90 4.67E+10 0.00E+00 1.15E+10 0.00E40 0.00E+00 0.00E+00 1. 35 E -09 Y-91 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 ZR.95 9.41E+02 3.02E+02 2.04E+02 0.00E+00 4. 74EM2 0.00E+00 9.57E+05 NB.95 8.24E+04 4.58E+04 2.46E+04 0.00EMO 4.53E+04 0.00E+00 2.78E+08 RU.103 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3. 88E+03 0.00E+00 1.19E+05 RU-106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.93E+04 0.00E+00 1.32E+06 l AG.110N 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 l TE-125M 1.63E+07 5.89E+06 2.185+06 4.895+06 6.61E+07 0.00E+00 6.49E+07 TE.127N 4.575+07 1.63E+07 5.57E+06 1.17E+07 1.86E+04 0.00E+00 1.53E+08 TE.129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 I.131 2.968+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 1.12E+08 I.133 3.878+06 6.73E+06 2.05E+06 9.88t+08 1.17E+07 0.00E+00 6.04E+06 CS.134 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44Ed9 2.35E+08 C5 136 2.63E+08 1.04EM9 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS-137 7.37EM9 1.01E+10 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 84 140 2.69E+07 3.38t+04 1.76t+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07 CE.141 4.84E+03 3.27E+03 3.71E+02 0.00E40 1.52E+03 0.00E+00 1.25E+07 CE.144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+08 PR-143 1.57t+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 COMANCIE PEAK . L. HTS 1 APO 2 Rev s PART I 2-30 01/93
TABLE 2.4 PATHWAY DOSE FACTORS I I AGE GROUP: TEEN PATHWAY: GEASS. COW.MIII l ORGAN DOSE FACTORS l NUCLIDE l..................................................................... ) l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 P.32 3.15E+10 1.95E+09 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E64 1.09E+04 7.13E+04 8.39E+06 MN.54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 FE.55 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E+07 FE.59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 Co.58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 Co.60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E40 0.00E+00 3.62E+08 NI.63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00540 0.00E+00 1.33E+08 ZN.65.. 2.11Ev09 7.32E+09 3.42549 0.00E+00 4.69E+09 0.00E+00 3.10E+09 RB.86 0.00E+00 4.73E+09 2.22EM9 0.00E+00 0.00E+00 0.00E+00 7.00E+08 , SR.89 2.68E+09 0.00E+00 7.678+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 1 SR.90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 1 Y.91 1.58E+04 0.00E+00 4.24EM2 0.00E+00 0.00E+00 0.00E+00 6.48E+06 ZR.95 1.65E+03 5.21E+02 3.58E+02 0.00E+00 7.65E+02 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 RU 103 1.81E+03 0.00E+00 7.75E4 2 0.00E+00 6.39E+03 0.00E+00 1.51E+05 ; RU 106 3.76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 AG.110M 9.64E+07 9.12E+07 5.55EM7 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE.125M 3.01E+07 1.08EM7 4.02EM4 8.40E+06 0.00EMO 0.00E+00 8.87E+07 TE.127N 8.45E+07 3.00E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 TE.129N 1.10E+08 4.09EM7 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 , 1 131 5.38Ed8 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 I.133 7.04546 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS.134 9.83E+09 2.31E+10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 CS.136 4.49E+08 1.77E+09 1.19EM9 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS.137 1.34E+10 1.78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 BA.140 4.87E47 5.97E+04 3.14EM6 0.00E+00 2.02E+04 4.01E+04 7.51E+07 CE 141 8.89E+03 5.94E+03 6.82E+02 0.00E+00 2.80E+03 0.00E+00 1.70E+07 CE.144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63845 0.00E+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 ND.147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7 12E+05 Rev 8 M - LNTS 1 APO 2 PART I 2-31 01/93
I l TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS. COW.MIIK l ORGAN DOSE FACTORS ! Nuct.IDEl..................................................................... l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI I
.............................................................................. l H3 0.00E+00 . 57E+03 1.57E+03 1.57h03 1.57h03 1.57 903 1.57E+03 P.32 7.77E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 :
CR-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1. 54h04 1.03E+05 5.40E+06 HN.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 1.84h07 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 0.00h00 5.65E+07 2.03E+08 CO.58 0.00E+00 1.21E+07 3. 72h07 0.00 000 0.00h00 0.00E 40 7.08E+07 ! CO.60 0.00E+00 4.32E+07 1.27h08 0.00h00 0.00E+00 0.00E+00 2.39E+08 ' NI.63 2.97E+10 1.59E+09 1.01E+09 0.00E40 0.00h00 0.00E+00 1.07E+08 ZN.65 . : . 4.14E+09 1.10 h10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94 h09 RB.86 0.00E+00 8.78E+09 5.40E+09 0.00h00 0.00E+00 0.00E+00 5.65E+08 SR.89 6.63h09 0.00E+00 1.89h08 0.00E+00 0.005+00 0.00E+00 2.57E+08 SR-90 1.12h11 0.00E+00 2.84 h10 0.00E+00 0.00E+00 0.00h00 1.51E 09 Y.91 3.91E+04 0.00E+00 1.05h03 0.00E40 0.00E+00 0.00E+00 5.21h06 ZR-95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21E+03 0.00E+00 8.80E45 NB.95 3.18h05 1.24h05 8.86h04 0.00E+00 1.16h05 0.00 h00 2.29E+08 RU.103 4.29E+03 0.00h00 1.65h03 0.00E+00 1.08h04 0.00h00 1.11 h05 , RU.106 9.25h04 0.00E+00 1.15E+04 0.00E+00 1.25h05 0.00E+00 1.44E+06 AC-110M 2.09h08 1.41E+08 1.13h04 0.00E+00 2.63E+08 0.00h00 1.68E+10 TE.125M 7.39t+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE.127M 2.08h08 5.6th07 2.47h07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE.129M 2.72E+08 7.59h07 4.22007 8.76E+07 7.98E+08 0.00E+00 3.31E+08 I.131 1.31849 1.31E+09 7.46E+08 4.34E+11 2.16h09 0.00h00 1.17E+08 I.133 1.72E+07 2.13E+07 8.05E+06 3.95E+49 3.55E+07 0.00E+00 8.58E+06 i CS.134 2.275+10 3. 72h10 7. 85h09 0.00h00 1.15E+10 4.14E+09 2.01E+08 CS.136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49h09 2.21h08 9.80E+07 : C5 137 3.23E+10 3.09h10 4.56E+09 0.00D00 1.01E+10 3.62h09 1.93E+08 BA-140 1.18h04 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 CE.141 2.19h04 1.09h 04 1.62EM3 0.00E+00 4.79E+03 0.00h00 1.36E+07 1 CE.144 1.63E+06 5.09t+05 8.67E+04 0.00h00 2.82h05 0.00h00 1.33E+08
- PR.143 7.18E+02 2.16h02 3.56E+01 0.00E+00 1.17t+02 0.00E+00 7.75E+05 ND-147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98E+02 0.00EMO 5 71E+05 F
COMANCFE PEAK , UMTS 1 APO 2 Rev 8 Pf,MT I 2-32 01/93
l 1 l l l TABLE 2.4 PATHWAY DOSE FACTORS AGE CROUP: INFANT PATHWAY: GRASS. COW.MIIX l 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 0.00E+00 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 0.00E40 8.65E+06 0.0CEMO 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 0.00E40 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 1.08t+08 ZN.65 c. 5.56E+09 1.91E+10 8.79EM 9 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 ..COE+00 3.62E+08 0.00E+00 0.00E+00 0.00E40 2.59E+08 SR.90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 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 1.18E+03 0.00E+00 1.79E+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 RU.106 1.91E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E40 1.45E+06 AG.110M 3.86EM8 2.82E+08 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE.125M 1.51E+08 5.05E+07 2.04E+07 5.081+07 0.00E+00 0.00E+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE.129M 5.58E+08 1.91E+08 8.59EM 7 2.14E+08 1.39E+09 0.00E+00 3.33E+08 1 131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.00E+00 1.15E+08 1 I.133 3.63EM7 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 0.07,+00 1.75E+10 7.19E+09 1.85E+08 CS 436 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 8.85E+07 , CS.137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55EM9 1.89E+08
,% 40 2.42E+08 'i.42E+05 1.25E+07 0.00E+00 5.75E+04 1.49E+05 5.94E+07
% 2.41 4. 34E+04 2.65E+04 3.12E+03 0.00E+00 8.17EM3 0.00E+00 1.37E+07 CE.144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08
, PR.143 1.49E+03 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 l ND.147 8.83E+02 9.0442 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 COMANCE PEAK - UMTS 1 ABO 2 Rev 8 FART I 2 33 01 93
TABLE 2.4 PATHWAY DOSE FACTORS ) 1 ACE CROUP: ADULT PATHWAY: GRASS-COW. MEAT l ORGAN DOSE FACTORS NUCLIDE 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 3.24r+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 l
.............................................................................. 1 CR.51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 l MN.54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 I FE.55 2.93E+08 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 0.00EMO 0.00E+00 2.73E+08 ZN. 6 5a - 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 2.27548 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 ZR.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 NB.95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 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 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 A> 110M 6.08E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE.125M 3.5YE+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE.127M 1.12L+09 3.99E+08 1.36E+0C 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE.129M 1.13:t+09 4.*3E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 1 131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E40 4.06E+06 l I.133 3.68E.01 6.41E 01 1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 CS.134 6. 58EM8 1.57E+09 1.28E+09 0.00E+00 5.07E+08 1.68E+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 CE.141 1.41E+04 9.51E+03 1.08EM3 0.00E+00 4.42E+03 0.00E+00 3.64E+07 CE.144 1.46E+06 6.10E+05 7.83E+04 0.00EMO 3.62E+05 0.00E+00 4.93E+08 PR.143 2.09E+04 8.40E+03 1.04E+03 0.00E40 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 COMANCE PEAK UMTS 1 APO 2 Rev 8 PA M I 2-34 01/93
f I TABLE 2.4 i PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GEASS. COW. NEAT l ORGAN D FACTORS NuCI.1DE 1....................................OSE ................................. l BONE LIVER T. 80DY THYROID KIDNEY I.U GI;I.LI '
.................................................................NC H.3 ............. !
0.00E+00 1.93E+02 1.93E+02 1.93EM2 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 0.00E+0 3.29E+08 CR 51 0............ l 1 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 2.09EM6 0.00E+00 1.44E+07 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+0 7,31E+07 '
................................................................. 8 FE-59 ............ ,
Co.58 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56E+08 1.17E+09 CO.60 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00EM0 0.00E+00 1.94E+08 4 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 7
...................................................................... 60E+08 NI.63 .......
l ZN.65 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71E+08 l 2.50E+08 8.68 EMS 4.05E+08 0.00E40 5.56E+08 0.00E+00 3.68t+08 ' RB.84 " 0.00E+00 4.06E+08 1.91 EMS 0.00E+00 0.00E+00 0.00E+00 6 00E+07 ;
* ................................................s.....................
SR.09 SR-90 2.55E+08 0.00E+00 7.29t+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 2.26E+08 ! 9.54 EMS 0.00E+00 2.56E+04 0.00EMO 0.00E+00 0.00E+00 3 !
...................................................................... 91E+08 ZR.95 NB.95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 i RU.103 1. 79EM6 9.95EM5 5.48E+05 0.00E+00 9.64E+05 0.00E+30 4.25E+09 ,
8.56E47 0.00EMO 3.66E+07 0.00E+00 3.02E+08 0.00E+00 7.
.................................... ................................. 15E+09 RU.106 2.365+09 0.00E440 2.97E+08 0.00EM0 4.54E+09 0.00E+00 1.13E+11 i AG.110N 5.06E+06 4.78EM6 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 TE.125K 3.03E+08 1.09E+08 4.05EM7 8.465+07 0.00E+00 0.00E+00 8.94E+08 TE.127N 9.41E+08 3.34E+08 1.12E+08 2.24 EMS 3.41E+09 0.00E+00 2.35E+09 ,
TE.129N 1 131 9.495M8 3.52E+08 1.50E+08 3.06 EMS 3.97E+09 0.00E+00 3.56E+09 l 8.93B+46 1.25E+07 6.72EM6 3.65EM9 2.15E+07 0.00E+00 2.47E+06 l I-133 3.088 01 5.22I.01 1.59E.01 7.29E+01 9.16E.01 0.00E+00 3.95E.01 CS.134 5.23E+08 1.23E449 5.71E+08 0.00E+00 3.91E448 1.49E+08 1.53E+07 CS.136 9.43E+46 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 C5 137 7.24E+08 9.63E+08 3.35E+08 0.00E+00 3.288+08 1.27E+08 1.37E+07 BA.140 2.39E+07 2.93E+44 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 CE.141 1.185+04 7.87E+03 9.05E+02 0.00E400 3.71E+03 0.00E+00 2.25E+07 CE.144 1.23I446 5.08E+05 6.60E+04 0.00E+00 3.03E+05 0.00E+00 3.09E+08 PR.143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.088+03 0.00E+00 5.79E+07 ND.147 6.23E+03 6.78t+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 Rev 8 COMANCFE PEAK - LNTS 1 AM) 2 PART I 2-35 01/93 l l
TABl.E 2.4 . PATHWAY DOSE FACTORS ACE GROUP: CHILD PATHWAY: GRASS. COW. MEAT l ORGAN DOSE FACTORS NUCLISE l--------------------------------------------------------------------- l BONE LIVER 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 0.00E+00 2.25E+06 0.00E+00 6.73E+06 FZ-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 3.04E48 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 0.00E40 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 RB 86 0.00E+00 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 0.00EMO 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 0.00E+00 3.90E+08 0.00E+00 4.01E+09 RU.106 4.44t+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00E+00 6.91E+10 AG.110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59EM7 1.60E+0S 0.00E+00 0.00E+00 5.49E+08 TE-127M 1.78E+09 4.78EM8 2.11E+08 4.25E+08 5.06E+09 0.00E+00 1.44E+09 TE 129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26Ed9 0.00E+00 2.18E+09 I.131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06 I-133 5.72E.01 7.08E.01 2.68E.01 1.31E+02 1.18E+00 0.00E+00 2.85E-01 CS-134 9. 23E+08 1.51E+09 3.19E+08 0.00E+0(P 4.69F+08 1.68E+08 8.16E+06 CS.136 1.63E+47 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.57E+06 CS-137 1.33Ed9 1.28E+09 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 1.26E+04 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 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E40 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 0.00E40 5.20E+03 0.00E+00 1 50E+07 Rev 8 COMANCE PEAK - lNTS 1 A>O 2 PART I 2-36 01/g3
TABLE 2.4 FATHWAY DOSE FACTORS ACE GROUF: INFANT PATHUAY: GRASS. COW. NEAT l ORGAN DOSE FACTORS NUCLIDE l-...........-.---..-..-.....-...--.......-......-.......--...-....... l BONE LIVER T. BODY THYROID KIDNEY LUNG CI-LLI H.3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l P.32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i CR.51 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.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 l Co.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00840 0.00E+00 0.00E+00 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E40 0.00E+00 0.00E+00 , ZN. 61. . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l RB-86 0.00E+00 0.00E40 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+C0 0.00E+00 0.00E+00 0.00E+00 0.00E+M SR.90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0 m 00 , Y.91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 2R.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E40 0.00E+00 i NB 95 0.00E+00 0.00E40 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l RU.103 0.00E+00 0.00E+00 0.00E+00 0.00540 0.00E+00- 0.00E+00 0.00E+00 l RU.106 0.00E+00 0.00E40 0.005400 0.00E40 0.00E+00 0.00E+00 0.00E+00 AG.110K 0.00E+00 0.00540 0.00E+00 0.00540 0.00E+00 0.00E+00 0.00E+00 TE.125N 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.127N 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129N 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00540 0.00E+00 0.00E+00 1 131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00540' O.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 0.005600 0.00E+00 0.00E+00 0.00E+00 0.00540 0.00E40 0.00E+00-C3 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 0.00E40 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 0.005400 0.00E40 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0.00B+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 Rev 8 COMANCE PEAK . M 1 M 2 PART I 2-37 01/93 !
. . _ _ , - _ - - - - - . l
~
- I- :
TABLE 2.4 i PATHUAY DOSE FACTORS , AGE GROUP: ADULT PATHUAY: GRASS. GOAT-MI1X . l ORGAN DOSE FACTORS i NUCLIDE l...........................--........................................ I l 80NE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI ' 1 f' H-3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 , P.32 2.05E+10 1.27E+09 7.92E+08 0.00E+00 0.00E+00 0.00E+00 2.30E+09 CR 51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 ! MN.54 0.00E+00' 1.01E+06 1.93E+05 0.00EM0 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 FE.59 3.87E+05 9.09E+05 3.48E+05 0.00EM0 0.00E+00 2.54E+05 -3.03E+06 Co.58 0.00E+00 5.66E+05 1.27EM6 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 0.00E+00 0.00E+00 3.70E+07 NI.63 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E40 0.00EM0 1.17E+07 I ZN.65.. . 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51 EMS 0.00E+00 3.30E+08 ! Rs.86 0.00E+00 3.12EM8 1.45EM8 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+00 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 0.00EM0 2.76E+01 0.00EMO 0.00E+00 0.00E+00' 5.68E+05 ZR.95 1.13E+02 3.63E+01 2.46EM 1 0.00E+00 5.70E+01 0.00E+00 1.15E+05 !' NS 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 0.00E+00 4.67E42 0.00E+00 1.43E+04 i RU.106 2.45E+03 0.00540 3.10EM2 0.00E+00 4.73E+03 0.00E+00 1.59E+05 + AG.110N 6.99E+06 6.475+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 - TE.125M 1.96E+06 7.09E+05 2.62E+05 5.89E45 7.965+06 0.00E+00 7.81E+06 TE.127M 5.50EM6 1.97E+06 6.70E+05 1.41546 2.23E+07 0.00E+00 1.84E+07 l
- TE.129N 7.23EM6 2.70E+06 1.14E+06 2.48EM6 3.02E+07 0.00E+00 3.64E+07 i j I.131 3.56EM8 5.09E+08 2.92E+08 1.675+11 8.73EM S 0.00E+00 1.34E+08 I.133 4.65E+06 8.10E+06 2.47E+06 1.19EM9 1.41E+07 0.00E+00 7.28E+06 C5 134 1.70E+10 4.04E+10- 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08 CS.136 7.92E+08 3.13E+09 2.25E+09 0.00E+00 1.74E+09 2.383M8 3.55E+08 1
! CS-137 2.22E+10 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.37E+08 RA.140 3.24E+06 4.07EM3 2.12E+05 0.00E+00 1.385+03 2.33E+03 6.67E+06 CE.141 5.82E+02 3.94E+02 4.47EM1 0.00E+00 1.83EM 2 0.00E+00 1.51E+06 CE.144 4.30E+04 1.80E+04 2.31E+03 0.00EM0 1.07E44 0.00E+00 1.45E+07 PR.143 1.90E+01 7.60E+00 9.40E.01 0.00E+00 4.39E+00 0.00E+00 8.3C M 4 ND.147 1.13E+01 1.31E+01 7.82E.01 0.00E+00 7.65EMO 0.00E+00 6.28E+04 Rev 8 COMANCE PEAK - LNTS 1 Af0 2 PART I 2-38 01/93
TABLE 2.4 PATHUAY DOSE FACTORS ACE GROUP: TEEN PATHVAY: GRASS.
. . . . . . . . . GOAT . MI IJ l
NUCLID E j . . . . . . . . . . . . . . . . . - . . . - - . . . . . . ORGAN DOS E FACTORS l BONE LIVER T. BODY THYROID
................................................... KIDNEY LUNG GI.LLI i H.3 ........................... 1 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04!
F-32 3.78E+10 2.34E+09 1.46E+09 0.00E+00 i
................................................ 0.00E+00 CR 51 0.00E+00 3.18E+09 i
MN-54 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E FE 55 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00
.....................................................E+00 FE.59 2.61E+05 1.78E+05 i
Co.58 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+ Co.60 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+! 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0
.................................................. 00E+00 NI.63 0.00E+00 4.35E+07 I
ZN.65 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E400 0.00E+00 1.60Ei RB . 86. . 2.53E+08 0.00E+00 5.67E+08 8.78E+08 4.10E+08 2.67E+08 0.00E+00 0.00E+00 0 5.62E+08 0.00E40 3.72E+l
.................................................. 00E+00 SR.89 0.00E+00 .8.40E+07 SR.90 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+ ,
Y.91 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E40 0.00E+00 3.90E+l 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0
.................................................. 00E+00 ZR-95 0.00E+00 7.78E+05 NB.95 1.98E+02 6.25E41 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+ i RU.103 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09t+03 0.00E+00 4.01E+
2.17E+02 0.00E+00 9.29E+01 0.00E+00 7 0.00E+00 1.82E+04
.................................................. 66E+02 RU.106 ........................... ;
4.50EM3 0.00E+00 5.685+02 0.00E+00 8.69E+03 0.00E+00 2.16E+0 AG-110N 1.16EM7 1.09E+07 6.65E+06 0.00E+00 2.09547 0.00E+00 3.07E TE-125K 3.61546 1.30E+06 4.82E+05 1.01E+06 0 0.00E+00 1.06E+07
.................................................. 00E+00 ...........................
{ 1 TE.127K 1.01E+07 3.598+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2.52Ei TE.129N I-131 1.32E+07 4.90E+06 2.098+06 4.268+06 5.53E+07 0.00E+00 4.96E+ , 6.45E48 9.03E+08 4.85EM8 2.64E+11 1.565+ 0.00E+00 1.79E+08
~
...................................................... 09 1 131 .......................
l CS.134 8.495+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+C0 1.09E+07 i CS.136 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+C9 8.62E+08 i 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.895+09 4.55E+04 4.27E+08
...............s......................................
CS.137 ....................... SA.140 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07t+09 7.60E+08 CE.141 5.84E+06 7.16E+03 3.76E+05 0.00E400 2.43EM3 4.81E+03 9.01E+06 i . 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0 2.04E+06 CE.144 7.90E+04 3.27E+04 00E+00 ................. { PR.143 4. 25E43 0.00E+00 1.95E+04 0.00E+00- 1.99E+07 < ND-147 3.485+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.395+01 0.00 8.54E+04
...............................................................E+00 ...............
Rev 8 i COMANCE PEAK - UMTS 1 APO 2 PART I 2-39 O I
I TABLE 2.4 , FAT 1tWAY MSE FACTORS AGE GROUF: CHILD PATHWAY: GRASS. COAT-MIIK l ORGAN DOSE FACTORS NUCL1DE 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+0i 1.22E+04 6.78EM3 1.85E+03 1.24E+04 6.48E+05 l 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 0.00EMO 0.00E+00 4.36E+05 1.43E+05 FE.59 1.56E+06 2.53E+06 1.261+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 1.53EM7 0.00E+00 0.00E+00 0.00E+00 2.87E+07 NI.63 3.56E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 ZN- 61. . 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8. 33 EMS 0.00E+00 2.32E+08 RB.86 0.00E+00 1.05E+09 6.47E+04 0.00E+00 0.00E+00 0.00E+00 6.77E+07 I SR.89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 SR.90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 j Y.91 4.69E+03 0.00E+00 1.25EM2 0.00E+00 0.00EM0 0.00E+00 6.24E+05 i ZR.95 4.60E+02 1.01E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1.05E+05 i NB.95 3.82E+04 1.49E+04 1.06EM4 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 1.29EM3 0.00E+00 1.33E+04 RU.106 1.11E+44 0.00E+00 1.385+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG.110M 2.51EM7 1.69E+07 1.35E+07 0.005400 3.15E+07 0.00E+00 2.01E+09 TE.125M 8.86E+06 2.40E+06 1.18846 2.49EM6 0.00E+00 0.00E+00 8.55E+06 TE.127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE.129N 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56EM 7 0.00E+00 3.97E+07 I-131 1.575+09 1.57E+09 8.95E+08 5.21E+11 2.54E+09 0.00E+00 1.40E+08 I.133 2.068+07 2.55E+07 9.66EM6 4.74EM9 4.25E+07 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+0S C5 136 3.04EM9 8.36E+09 5.41EM9 0.00E+00 4.45E+09 6.64E+08 2.94E+08 CS.137 9.685+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA.140 1.41EM7 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 6.11EM4 1.04E+04 0.00E+00 3.385+04 0.00EMO 1.59E+07 FR.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 M-M1M2 PART I 2-40 01/93
TABLE 2.4 . PATHWAY DOSE FACTORS ACE CROUP: INFANT PATHWAY: CEASS. GOAT-MIIK l ORGAN DOSE FACTORS NUC1.10E I..................................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG CI .I.LI H-3 0.00E+00 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 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 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 1.51EM6 2.44E+06 Co.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 NI.63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN.65 - 6.67E+04 2.29E+09 1.05E+09 0.00EMO 1.11E+09 0.00E+00 1.93E+09 RS.86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 , 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 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31E+05
- ZR.95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 i N5 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 3.48EW2 0.00E+00 2.17E+03 0.00E+00 1.27E+04 '
RU.106 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 - AC.110K A. 63E47 3. 38EM7 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE.125M 1.81E+07 6.05E+06 2.45EM6 6.09E+06 0.00E+00 0.00E+00 8.62E+06 , TE.127M 5.06EM7 1.68E+07 6.12EM6 1.46E+07 1.24E+08 0.00E+00 2.04E+07 l TE.129M 6.698+07 2.29E+07 1.03E+07 2.57E+47 1.67E+08 0.00E+00 3.99E+07 I.131 3.27549 3.85E+09 1.69E49 1.27E+12 4.50E+09 0.00E+00 1.37E+08 l I.133 4.365+07 6.35E+07. 1.865+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 t CS.134 1.095+11 2.04E+11 2.06E+10 0.00E+00 5.26E+10 2.15E+10 5.55E+08 ! Cs.136 5.94E+09 1.75E+10 6.52E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+08 CS.137 1.54E+11 1.41E+11 1.285+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 6.89EM3 1.78E+04 7.13E+06 CE.141 5.21I403 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE.144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 l PR.143 1.78E+02 6.66E+01 8.83E+00 0.00E+00 2.48E+01 0.00E+00 9.40E+04 ND.147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6 89E+04 : Rev 8 COMANCE PEAK - LNTS 1 APO 2 PART I 2-41 ;
P TABLE 2.4 PATHWAY DOSE FACTORS ACE GROUP: ADULT PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE 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 CR.51 0.00E+00 0.00E+00 4.64E44 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 0.00E+00 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 0.00EMO 0.00E+00 1.7 E+10 Y.91 5.12E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 ZR.95 1.172+06 3.77E+05 2.55E+05 0.00E+00 5.91 EMS 0.00E40 1.19E+09 N8 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 2.44EM7 0.00E+00 3.72548 0.00E+00 1.25E+10 AC 110K 1.05EM7 9.75EM6 5.79E+06 0.00E+00 1.92E47 0.00E+00 3.98E+09 TE.125N 9.66t+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TE.127N 3.49E+08 1.25EM8 4.26EM7 8.93E47 1.42E+09 0.00E+00 1.17E+09 TE-129N 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05EM9 0.00E+00 1.26E+09 I.131 8.085+07 1.16E+08 6.62E47 3.79E+10 1.98t+08 0.00E+00 3.05E+07 I.133 2.095+06 3.63EM6 1.11E+06 5.34E+08 6.33EM6 0.00E+00 3.26E+06 CS.134 4.67EM9 1.11E+10 9.08E+09 0.00840 3.598+09 1.19E+09 1.94E+08 CS.136 4.28E47 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 1.92E+07 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 1.29E+08 1.62E+05 8.47EM6 0.00E40 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+44 0.00E+00 2.74E+08 ND.147 3.34E+04 3.85E+04 2.31E+03 0.00EMO 2.25E+04 0.00E+00 1.85E+08 j Rev 8 l COMANCE PEAK - LNTS 1 APO 2 PART I 2-42 01/93
l. TARE 2.4 PATHUAY DOSE PACTORS AGE GROUP: TEEN PATHWAY: VEGETATION l ORGAN DOSE FACTORS
.Nucl.1DE l..............................-.........
............-........e.......
l BONE LIVER T. BODY- THYROID KIDNEY LUNG G
........................................................................I.LL1 H.3 ......
I 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 0.00E+00 1.34 ;
.........................................................................E+08 CR.51 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 1.47E+08 1.00
.........................................................................E+08 FE-59 Co.58 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+08 l Co.60 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 -l 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24
.........................................................................E+09 NI.63 .....
i ZN.65 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E40 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 RB.86 " 0.00E+00 2.73E+08 1.28E+08 ^ 00E+00 0.00E @ 0.00E+00 4.04E+0
........................................ .................................. 7 SR 89
{ SR.90 1.52E+10 0.00E+00 4.34E+08 0.00E40 0.00E+00 0.00E+00 1.80E+09 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E40 0.00E+00 2.11E+10 Y.91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+0
........................................................................... 9 2R.95 e
NB.95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.985+05 0.00E+00 1.25E+09 RU.103 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03EM S 0.00E+00 4.56E+08 ; 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+0
........................................................................... 8 RU.106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.978+08 0.00E+00 1.48E+10 !
AG 110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2. 74EM7 0.00E+00 4.03E+09 : TE-125N 1.48E48 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 l
.............................................................................. l TE-127N 5.52E+08 1.96E+08 6.56E407 1.315+08 2.245409 0.00E+00 1.37E+09 i TE.129N I.131 3.61E+08 1.34E+08 5.72E+07 1.175+08 1.51E+09 0.00E+00 1.36E+09 7.69I47 1.08EM8 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07- :
.............................................................................. l I-133 1.94E+06 3.29E+06 1.00E+06 4.598+08 5.77E+06 0.00E+00 2.49E+06 CS.134 (
CS 136 7.10E+09 1.67t+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 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.595+09 1.78E+09 1.92E+08 BA.140 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.78E+04 1.15E+0", 2.15E+08 CE-141 2.83E45 1.89E+05 2.17E+04 0.00E400 8.90E+04 0.00E+00 5.41E+08 CE.144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 PR.143 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 ND.147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 Rev8 1 2 PART I 2-43 01/93
d TABLE 2.4 PATHWAY DOSE FACTORS ACE CROUP: CHILD PATHWAY: VEGETATION yuct10E i..................................................................... 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 CR.51 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN.54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 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+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI.63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 ZN.65 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 NB.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 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 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+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 1 131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 I.133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS.134 1.60E+10 2.63 D10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 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 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 4.49Ev 3 0.00E+00 3.18E+04 0.00E+00 9.18E+07 Rev 8 COMANCE PEAK . UMTS 1 APO 2 PART I 2-44 01/83 .
I l r ( TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: VEGETATION l ORGAN DOSE FACTORS Nuct.IDE l..................................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI 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 CO.60 0.00E+00 0.00E+00 0.00E+00 0.00EMO 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.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 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 ZR.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU.103 0.00E40 0.00E+00 0.00E+00 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 0.00EMO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.127M 0.00E+00 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j TE.129M 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 0.00E+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 0.00EMO 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 l 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 i CE.141 0.00E+00 0.00E40 0.00E40 0.00E@0 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00EMO 0.00E+00 0.00EMO 0.00E+00 0.00E+00 0.00E+00 PR.143 0.00E+00 0.00E+00 0.00E+00 0.00E40 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 l 1
...........................*.................................................. I Rev 8 COMANCE PEAK . UMTS 1 AND 2 PART I 2-45 01/93
1 TABLE 2.4 PATHUAY DOSE FACTORS l AGE GROUP: ADULT PATHUAY: INHA1ATION l l ORGAN DOSE FACTORS ! NUCLIDE l...............................-..................................... I < BONE LIVER T. BODY THYROID KIDNEY 1RNC GI-ILI l , H.3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 P-32 1.32E+06 7.71E+04 5.01E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+04 CR.51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 > MN.54 0.00E+00 3.96E+04 6.30EM3 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE.55 2.46EM4 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE.59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 Co.58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 ; co.60 0.00E+00 1.15E+04 1.44E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 i NI.63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E40 1.78EM5 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 R3 86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 SR.89 3.04E+05 0.00EMO 8.72E+03 0.00EM0 0.00E+00 1.40E+06 3.50E+05 ; SR.90 9.92EM7 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Y.91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 r
............................................................................... 3 ZR.95 1.07E+05 3.44EM4 .2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 ,
NB.95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 ! RU.103 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83EM3 5.05E+05 1.10E+05
............................................................................... i RU.106 6.91E+04 0.00EM0 4.72E+03 0.00E+00 1.34E45 9.36E+06 9.12E+05 AG.110N 1.088+04 1.00E+04 5.94E+03 0.00E+00 1.975+04 4.63E+06 3.02E+05 TE.125N 3.42E+03 1.585+03 4.675+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE.127N 1. 26EM4 5.77E+03 1.575+03 3.29E+03 4.585+04 9.60E+05 1.50E+05 TE.129N 9.76543 4.67E+03 1. 58EM3 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1 131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03
..........................................n ...................................
I.133 4.64EM3 1.48EM4 4.52E+03 2.15E+06 2.58E+04 0.00D00 8.88E+03 C5 134 3.73E45 8.48 EMS 7.288+05 0.00E+00 2.875+05 9.76E+04 1.04E+04 CS.136 3.90EM4 1.46E+05 1.10E+05 0.00E+00 8.565+04 1.20E+04 1.17E+04 CS-137 4.78 EMS 6.21E+05 4.28E+05 0.00E+00 2.22 EMS 7.52E+04 8.40E+03 BA.140 3.90E+04 4.90EM1 2.57E+03 0.00E+00 1.675+01 1.27E+06 2.18E+05
'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. 84EM5 0.00E+00 8.488+05 7.78E+06 8.16E+05 PR.143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56EM3 2.21E+05 1,73E+05 '
N PEAK - M 1 AW 2 PART I 2-46 l
i l l l l TABLE 2.4 l PATHWAY DOSE FACTORS , AGE GROUP: TEEN PATHWAY: INHAIATION l ORGAN DOSE FACTORS NUCL1DE l...............-.........-.............-.......................... . l SONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI 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 4 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 CR.51 MN.54 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 - 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE.55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03
............................................................................... 1 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 1.34EM6 9.52E+04 0.00E+00 1.51E+04 1.98EM4 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI.63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN.65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 R3 86.- 0.00E+00 1.90E+05 8.40E+04 0.00E40 0.00E+00 0.00E+00 1.77E+04 ;
SR.89 l SR.90 4.34E+05 0.00E+00 1.25EM4 0.00E+00 0.00E+00 2.42E+06 3.71E+05 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y.91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR.95 , 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74EM4 2.69E+06 1.49E+05 N8 95 1.86t+04 1.03R+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU.103 2.10E+03 0.00E+00 8.96E+02 0.00E40 7.43E+03 7.83E+05 1.09E+05 RU.106 9.84E+04 0.00E400 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 AG.110M 1.38E+04 1.31E+04 7.998+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE.125M 4.88E+03" 2.24E+03 6.67EM 2 1.40E+03 0.00E+00 5.36E+05 7.50E+04 i:i6ti6& i:iiii65"i:iiii65"i:iii;6i i:iiii6&"i:iiii6i i:iiii65' ti:iiii TE.129M 1.39EM4 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I.131 3.54E+04 4.91EM4 2.64E+04 1.46EM7 4.40E+04 0.00E+00 6.49E+03 I.133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E40 3.75E+05 1.46E+05 9.76E+03 CS.136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.75E+04 1.09E+04 CS.137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04EM5 1.21E+05 8.48E+03 AA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28t+01 2.03E+06 2.29E+05 i CE.141 2.84E+04 1.90E+04 2.17EM3 0.00E*00 8.88E+03 6.14E+05 1.26E+05
............................................................................... i CE.144 4.89EM6 2.02EM6 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 l PR.143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 ND.147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 Rev 8 COMANCE PEAK . LNTS 1 APO 2 PART I 2-47 l
w t l TABLE 2.4 1 PATHWAY DOSE FACTORS AGE GROUP: CHILD FATHWAY
. . . . . . . .: . .INHAIATI ON l
NUCLIDE l- ...................-*...... ORGAN DOSE FACTORS l BONE LIVER T. BODY KIDNEY H.3 THYROID ...................................... LUNC GI.LLI 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P.32 2.60E+06 1.14E+05 9.88E+04 0
......................................... 00E+00 CR.51 0.00E+00 0.00E+00 4.22E+04 MN.54 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1 FE.55 0.00E+00 4.74E+04 2.52E+04 4.29E+04 7.77E+03 9.51E+03 0.00 0.00E+00 .1.00E+04 1.58E+06 2.2
............................................E...................................
FE.59 do 0.00E+00 1.11E+05 2.87E+03 co.58 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.0 ' Co.60 0.00E+00 0.00E+00 1.31E+04 1.77E+03 2.26E+04 3.16E+03 0.00 0.00E+00 0.00E+00 1.11E+06 3.4 r
............................................E+00 N1 63 0.00E+00 7.07E+06 9.62E+04 ZN.65 8.21E+05 4.63E+04 2.80E+04 0.00540 0.00EM0 2.75E+05 6.33 RS.86 4.26t+04 1.13E+05 0.00E+00 1.98E+05 7.03E+04 1.14E+05 0.00E+ 0.00EMO 7.1e+04 9.95E+05 '1.63E+
.....;:...................................... 00 0.00E+@ 0.00E+00 7.99E+03 '
SR 89 ................................. SR.90 5.99E+05 0.00E+00 1.72E+04 0.00E40 0.00E+00 2.16E+06 1.67 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3 Y.91 9.14E+05 0.00E+00 2.44E+04 0
......................................... 00E+00 ZR.95 0.00E+00 2.63E+06 1.84E+05 i
NB.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6. RU.103 2.35E+04 2.79E+03 0.00E+00 9.18E+03 1.07E+03 6.55E+03 0.00 0.00E+00 8.62E+03 6.14E+05 3.7 7.03E+03 6.62E+05 4.48E+04
............................................E+00 RU.106 ...................................
AG.110N 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.2 TE.125M 1. 69E442.33E+03 6.73E+03 1.14E+04 9.14E+03 9.14E+02 1.92E+ 0.00E+00 2.12E+04 5.48E+06. 1.00 TE.127M 03 0.00E+00 4.77E+05 3.38E+04 TE.129M 2.49E+04 8.55E+03 3.02E43 6.07E+03 6.36EM4 1.48E+06 7.14E+04 I-131 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E46 1.82E+0 4.81E+04 4.81E+04 2.73E+04 1.625 4
...............................................7 ...............................
I.133 7.84E+04 0.00E+00 2.84E+03 1.66E+04 2.03E+04 7.70EM 3 3.85E+06 3.38E+04 0.00E+00 5.48E+0 C5 134 CS-136 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+0 6.51E44 1.71E+05 1.16E+05 0.00540 1.45E+04 4.18E+03
................................................. 9.55E+04 CS.137 .............................
BA.140 9.07 EMS 8.25E+05 1.285+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 CE.141 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 3.92E44 1.95E+04 2.90I403 0.00E+00 8 5.44E45 5.66E+04
................................................... 55E+03 CE-144 ...........................
PR-143 6.77t+06 2.12E+06 3.61E+05 0.00E+00 1.17EM6 1.20E+07 3.89E+05 ND 147 1.85E+04 5.55E+03 9.14E+02 0.00E400 3.00E+03 4.33E+05 9.73E+04 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+0 3.28E+05 8.21E+04 4
.........................................................3 -......-.- . . --.
. - - - - -- - - - - - -,-n - - . - . - . . . , , . . , . , - - n-, . . - - . - n----
i l l TABLE 2.4 FATHUAY DOSE FACTORS 1 ACE GROUF: INFANT FATHWAY: INHA1ATION I ORGAN D FACTORS l NUCLIDE l....................................OSE ................................. l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI i H.3 ........... ,,, 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 : F.32 2.03E+06 1.12E+05 7.74E+04 0.00E+00 0.00EMO 0.00 1.61E+04
................................................................E+00 CR.51 ...............
MN.54 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 FE.55 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.94E+03 1.00E+06 7.06E+03 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04
.............................. - .................................... 1.09E+03 FI.59 .........
Co.58 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 ; Co.60 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06
..................................................................... 3.19E+04 NI 63 ........s ZN.65 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00EM0 2.09E+05 2.42E+03 1.93E+04 6.26E+04 3.11E+04 0.00E400 3.2SE+04 6.47 EMS 5.14E+04 RS.86. 0.00E40 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03
. .. . . .Q QQ&Q QQqQ.Q&Qqqg g ggyyggygyy SR.89 SR.90 3.988+05 0.00E+00 1.14E+04 0.005+00 0.00E+00 2.03E+04 6.40E+04 Y.91 4.095+07 0.00E+00 2.595+06 0.00E+00 0.005400 1.12EM7 1.31E+05 5.885+05 0.00E+00 1.575+04 0.00S+00 0.00S+00 2.45E+06
..................................................................... 7.03E+04 ZR 95 .........
NB.95 1.15 EMS 2.798+04 2.03E+04 0.005+00 3.11E+04 1.75E+06 2.17t+04 RU 103 1.57E+04 6.43E+03 3.785+03 0.00S+00 4.72E+03 4.79E+05 1.27E+04 i 2.02E+03 0.00E+00 6.79EM2 0.00E+00 4.24E+03 5.52E+05 1.6
........................................................................ 1E+04 RU.106 AG.110N 8.685+04 0.ME+00 1.09E+04 0.008+00 1.078+05 1.16E+07 1.64E+05 TE.125M
- 9. 98EM3 7.22E+03 5.00E+03 0.00E+00 1.095+04 3.67E+06 3.30E+04 4.765+03 1.998+03 6.58842 1.62E+03 0.005M0 4.475+05 1.29E+04 TE.127M 1.67E+04 i
TE.129N
- 6. 90EM3 2.07E+03 4.875+03 3.75E+04 1.31E+06 2.73E+04 :
1 131 1.415+04 6.098+03 2.23E+03 5.478+03 3.188+04 1.688+06 6.90E+04 1 3.798+04 4.44E+04 1.96E+04 1.44E+07 5.188+04 0.00E+00 1.06E+03 I I.133 C8 134 1.325+04 1.92E+04 5.60E+03 3.568406 2.24E+04 0.00E+00 2.16E+03 CS 136 3.965+45 7.0384 5 7.45E+44 0.00E+00 1.90E+05 7.97E+04 1.33E+03 4.83E+04 1.35 EMS 5.29E+04 0.00540 5.64E+04 1.188+04 1.43E+03
...............s...............................................................
C3 137 j 5.49E+05 6.12E+05 4.55E+04 0.005+00 1.72E+05 7.13E+04 1.33E+03 BA.140 5.60E+44 5.60E41 2.90EM3 0.005400 1. 345M1 1.60E+06 3.84E+04 CE.141 2.77t+04 1.678+04 1.998+03 0.00E+00 5.258+03 5.178+05 2.16E+04 CE.144 3.198+06 1.21E+06 1.76E+05 0.008+00 5.388+05 9.84E+06 1.48E+05 PR.143 1.40E+04 5.24E+03 6.99E+02 0.008400 1.978+03 4.33E+05 3.72E+04 ND.147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22EM5 3.12E+04 Rev 8 COMANCE PEAK - LNTS 1 APO 2 PART I 2-49 01/93
8 TABLE 2.5 (Shtet 1 of 2) 5 CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND
^ ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) 5 Pathway Distance X/Q D/0 l Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6) i i
Resident 2.20 9.28E-07 5.32E-09 10 N Garden 3.40 -- 2.90E-09 ! 8 Milk Cow None -- -- l 10 Resident 2.40 4.7E-07 2.30E-09 5 NNE Garden 2.50 -- 2.30E-09 Milk Cow None -- -- 5 Resident 2.30 3.58E-07 1.28E-09 8 NE Garden 2.50 -- 1.00E-09 10 Milk Cow None -- -- 5 Resident 2.40 2.58E-07 7.08E-10 - 10 ENE Garden 2.40 -- 7.10E-10 5 Milk Cow None -- -- 5 Resident 2.40 3.02E-07 6.62E-10 10 E Garden 3.50 -- 2.70E-10 Milk Cow 3.50 -- 2.70E-10 7 Resident 2.0 4.7E-07 1.20E-09 10 ESE Garden 3.30 -- 4.30E-10 5 Milk Cow None -- -- 1 10 Resident 1.90 8.3E-07 3.40E-09 SE Garden None -- -- 5 Milk Cow None -- -- 10 Resident 1.50 1.1E-06 6.60E-09 SSE Garden 2.30 -- 2.40E-09 5 Milk Cow 2.20 -- 1.80E-09 10 Resident 1.50 8.5E-07 5.20E-09 7 S Garden 1.8 -- 5.38E-09 Milk Cow None -- -- 5 Resident 1.90 4.42E-07 2.06E-09 10 SSW Garden 4.40 -- 2.80E-10 5 Milk Cow None -- -- l COMANCHE PEAK UNITS 1 AND 2 PART II 2-50 Rev. 10 4/94
I 3 l TABLE 2.5 (Sh:et 2 of 2) 5 CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1). AN ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 1/4.11.2.3) 5 Pathway Distance X/Q Sector 0/Q (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6) 10 Resident 1.10 1.4E-06 5.50E-09 SW GarJen 1.70 -- 2.00E-09 5 Milk Cow None -- 5 Resident 1.00 1.80E-06 6.50E-09 10 WSW Garden 1.10 -- 5.60E-09 5 Milk Cow None -- -- 5 Resident 1.50 8.40E-07 2.80E-09 W Garden 1.50 -- 2.80E-09 Milk Cow None -- 8 Resident 2.95 3.76E-07 1.07E-09 10 WNW Garden 3.00 -- 5 1.0E-09 Milk Cow None -- 5 Resident 2.70 6.98E-07 2.24E-09 NW Garden None -- -- Milk Cow None -- I 5 Resident 2.70 7.62E-07 8 NNW Garden 3.22E-09
' 3.70 --
1.50E-09 Milk Cow 4.90 -- 8.50E-10 NOTES: 5 (1) Receptor locations are taken from the nearest receptor locations 10 5 identified in the CPSES 1993 Land Use Census. (2) In addition to the pathways shown, the inhalation and ground plane pathways are present at the nearest resident. (3) The units for X/Q are Sec/ Cubic Meter. (4) X/Q Values at distances 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, and 6.0 miles were taken from Table 2.3-16. " Average Annual Relative Concentration at CPSES," of the CPSES Environment Report, Operating Licensing Stage (Reference 3). The X/Q values at other distances were determined by linear interpolation. (5) The units for 0/Q are inverse square meters. (6) 0/Q values at distances 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, and 6.0 miles were taken from Table 2.3-17. " Average Annual Relative Deposition Rate," of the CPSES Environmental Report, Operating License Stage (Reference 3). The D/Q values at other distances were determined by linear interpolation. COMANCHE PEAK UNITS 1 AND 2 PART II 2-51 Rev. 10 4/94
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1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) Vereissi Stendent Devieden of Manwiel in a Mums (Letters denots Pesquill Stability Class) 10075: THESE ARE STANDARO RELATIONSHIPS AND ARAY HAVE TO BE h0000FIED POR CERTA 8N TYPES OF TERRAIN ANOMR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT. OVER WATER). FiEurs 2.3 COMANCHE PEAK - UNITS 1 AND 2 PAFtT ll 2-54 01/93
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SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 SAMPLING LOCATIONS l Sampling locations as required in Radiological Effluent Control 3/4.12.1. Table 3.12-1 are described in Table 3.1 and shown on the map in Figure 3.1. i 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 calculations used in making this determination will 8 be performed as specified in Section 2.5. The sampling locations shown on Table 3.1 are the minimum
- locations required for compliance with Radiological Effluent l l Control 3/4.12.1. If desired, additional locations may be I
monitored as special studies to evaluate potential pathways of i exposure without adding such locations to the monitoring program given in Table 3.1. 3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3, TU Electric has contracted Teledyne Isotopes Midwest Laboratory to perform the Interlaboratory Comparison Program. The program is operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to the participant laboratories. The purpose of the program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-1 01/93
l l participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Teledyne participates in the environmental sample crosscheck program for milk and water samples conducted by ! the U.S. Environmental Protection Ag'ency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Lrboratory, Las Vegas, Nevada. The results of the program are included in the Annual Radiological Environmental Operating Report, as required by CPSES Technical i Specification 6.9.1.3. f e e*
\
w a COMANCHE PEAK - UNITS 1 AND 2 PART II 3-2 01/93
r Table 3.1 Environmental Sampling Locations Sampling location Sample Point (Sector - Miles) ,T,ygg(1) . l Al N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A , A3 E-3.5(Children'sHome) A A4 SSE-4.5(GlenRose) A ! A5 S/SSW-1.2 A A6 SW-12.3(Control) A A7 SW/WSW-0.95 A A8 NW-1.0 A R1 N-1.45 (Squaw Creek Park) R
.:. R2 N-4.4 R
. R3 N-6.5 R R4 N-9.4(Granbury) R R5 NNE-1.1 R R6 NNE-5.65 R R7 NE-1.7 R R8 NE-4.8 R R9 ENE-2.5 R R10 ENE-5.0 R All E-0.5 R COMANCHE PEAK - UNITS 1 AND 2 PART II 3-3 01/93
Table 3.1(Continued) Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) h(1) ' R12 E-1.9 R R13 E-3.5(Children'sHome) R , R14 E-4.2 R R15 ESE-1.4 R R16 ESE-4.7 R R17 SE-1.3 R R18 SE-3.85 R R19 SE-4.6 R R20 SSE-1.3 R 121 SSE-4.4(GlenRose) R R22 SSE-4.5(GlenRose) R 1 R23 S-1.5 R R24 S-4.2 R R25 SSW-1.1 R R26 SSW-4.4(StatePark) R R27 SW-0.9 R R28 SW-4.8(GirlScoutCamp) R R29 SW-12.3(Control) R R30 WSW-1.0 R R31 WSW-5.35 R COMANCHE PEAK - UNITS 1 AND 2 PART II 3-4 01/93 l
l i I Table 3.1(Continued) Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Iyg(l) R32 WSW-7.0(Control) R l R33 W-1.0 R ; l R34 W-2.0 R R35 W-5.5 R R36 WNW-1.0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R41 NW-9.9(Tolar) R R42 NNW-1.35 R R43 NNW-4.6 R SW1 N-1.5 (Squaw Creek Reservoir Marina) SW SW2 N-9.9(LakeGranbury) SW/DW(2) SW3 N-19.3(Control-BrazosRiver) SW SW4 NE-7.4(LakeGranbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW(3) SWE NNW-0.1 (Squaw Creek Reservoir) SW/DW(4) GW1 W-1.2 (NOSF potable water) GW GW2 WSW-0.1 (Plant potable water) GW(4),(5) COMANCHE PEAK - UNITS 1 AND 2 PART II 3-5 01/93
TABLE 3.1 (Continued) ENVIRONMENTAL SAMPLING LOCATIONS l Sheet 4 of 6 Sampling Location Sample Point (Sector - Miles) Troe(l) GW3 SSE-4.6(GlenRose) GW(5) GW4 N-9.8(Granbury) GW(2),(5) l GW5 N-1.45 (Squaw Creek Park) GW(5) SSI NNE-1.0 (Squaw Creek Reservoir) SS l SS2 N-9.9(LakeGranbury) SS SS3 NE-7.4 (Lake Granbury) SS j l 8 M1 Deleted M i
- M2 notused(0) M M3 notused(0) M M4 SW-13.5 (Control) M l F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0(LakeGranbury) F FP1 ENE-9.0 (Leonard Bros. Pecan Farm) FP 11 FP2 Deleted FP j l 6 FP3 Deleted FP 11 FP4 Deleted FP FP5 SW-12.7 (Control) FP FP6 E-3.5(HappyHillsFarm) FP-BL1 N-1.45 BL BL2 SW-1.0(7) BL BL3 SW-13.5 (Control)(7) BL (1) Types
A - Air Sample; R - Direct Radiation; SW - Surface Water; GW - Ground Water; SS - Shoreline Sediment; M - Milk; F - Fish; FP - Food Products; BL - Broad Leaf Vegetation. COMANCHE PEAK - UNITS 1 AND 2 PART II 3-6 Rev. 11 11/94
(2) The municipal water system for the City of Granbury is supplied [ by surface water from Lake Granbury (location SW2) and ground wellwater(locationGW4). Each of these input supplies for the Granbury municipal water system is sampled. These samples are i not required for compliance with Radiological Effluent Control I 3/4.12.1 Table 3.12-1, because they are not affected by plant : discharges. l (3) This sample (location SWS) is representative of discharges from - Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury. i (4) The plant potable water is supplied by surface water from Squaw ' Creek Reservoir (location SW6) and ground well water (location l GW2). Each of these input supplies for plant potable water is ! sampled. (5)- Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 l and are therefore not required to be monitored for radioactivity } to meet the requirements of the Radiological Environmental ! Monitoring Program specified in Radiological Effluent Control l 3/4.12.1. Table 3.12-1. Although not required for compliance [ with the Radiological Environmental Monitoring Program groundwater sampling locations are included in the monitoring program to provide confirmation that ground water is not affected ; by plant discharges, f (6) Due to the current availability of milk sampling locations, milk 8 l samples are taken at only the control locations. If additional l silk sampling locations are identified in future land use centu:, this table will be revised to include up to a maximum of 3 l samples and one control, as indicated in the Radiological ! Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1, Table 3.12-1. 1 Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-7 01/g3
(7) Per the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1. Table 3.12-1, broad leaf ; vegetation is required to be sampled only when milk sampling is not performed at all required locations. Broad leaf stapling r will be performed at the specified locations if milk samples are unavailable from any location.
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i 5 APPENDIX A PATHWAY DOSE RATE PARAMETER Pi (inhalation) = K' (BR) DFAj [Eq. A-1) where: Pj = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in prem/yr per microcurie /m3 The dose factors are based on the critical individual organ for the child age group. K' = conversion factor, 106 pC1/ 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 0FAj (mrem /yr per uC1/m3) i The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi(food). In addition, the critical age group has been changed from infant to child. l COMANCHE PEAK - UNITS 1 AND 2 PART II A-1 01/93 1
i l APPENDIX B l 1 I INHALATIONPATHWAYDOSEFACTOR(R 1.a.o) I 3 R 4,,,, = k' (BR) (DFAj,,,g) (mrem /yr per microcurie /m ) [Eq. B-1] 4 where: k' = conversion factor, 106 pCi/ 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) DFA i ,a o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in wres/pci. The total body 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)
COMANCHE PEAK - UNITS 1 AND 2 PART II 8-1 01/93 i l l
( APPENDIX C GROUND PLANE PATHWAY DOSE FACTOR (R G j) G R = k' k" (SF) DFG g [(1-e-Ai t)/Aj ] [Eq.C-1] where: k' = conversion factor, 106 pC1/ microcurie k" = conversion factor, 8760 hr/yr Aj = decay constant for the ith radionuclide, sec -1 ) t = the exposure time (this calculation assumes that decay is I the only noerating removal mechanism) 4.73 x 108 sec, (15 yrs) DFGj =the ground plane dose conversion factor for the ith radionuclide (mres/hr per pC1/m2). Values are taken from I Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply 1 to all age groups. Dose factors are provided for the l 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) l l l COMANCHE PEAK - UNITS 1 AND 2 PART II C-1 01/93
o APPENDIX D C GRASSCOW-MILKPATHWAYDOSEFACTOR(R 1,a,o) Rf,,,o = k' [(Qp xUAP) / (A l *A w *Y)* m
- 1,a,o)*
[((f px f )/s Y )p + ((1-f xp f,) e~^i h)/Y t ,-A gf t [Eq.0-1] sg
)
where: k' = conversion factor, 106 picocurie / microcurie (pC1/uci) QF = cow consumption rate, 50 kg/ day, (R.G. 1.109) UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for infant, child, teenager, and adult age groups,respectively(R.G.1.109) Yp = agricultural productivity by unit area of pasture feed ' l
+ grass.0.7kg/m2(NUREG-0133)
~
Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2, (NUREG 0133) l Fm =stableelementtransfercoefficient(TableE-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) DFL i ,a o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109) Xq = 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 0-1 01/93
APPENDIX 0(CONTINUED) th = 7.78 x 106 sec, the transport time from pasture to , harvest to cow to milk to receptor (Table E-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 [ concentratior. rather than the deposition. Therefore, R C q, basedon(X/Q): C
= k ' k" F m 0F U [Eq.D-2]
t.a.o (.75(.5/H)) R DFL
,,,, AP 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, for each respective age group, a (Tables E-11 to E-14, R.G. 1.109) All other parameters and values are as given above. l C NOTE: Goat-milk pathway factor, R 1,a.o will be computed using the cow-milk pathway factor equation. Fu factor for goat-milk will be from Table E-2, R.G. 1.109. QF for goats is 6 kg/ day , from Table E-3, R. G. 1.109 8 ~ Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II D-2 01/93
3
)
i l l APPENDIX E l COW-MEATPATHWAY00SEFACTOR(RM i,a.o) ! l R"j,,,o = k' (Qp xUAP)/IAi+A)*I w f) x (r) x (DFli,a,0) * [((f px f )/Y 3 p) + ((1 - fp3f ) e' i h)/Y t 3
] x e tif
[Eq. E-1] where: 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) Fj'- = 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) 0FLi a.o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109) Aj = decay constant for radionuclide 1, sec-1 Aw = decay constant for weathering, 5.73 x 10-7 sec -l ! (NUREG-0133) l tr = 1.73 x 106 sec, the transport time from pasture to l receptor (NUREG-0133) j th = 7.78 x 106 sec, the transport time from crop to receptor l (NUREG-0133) l COMANCHE PEAK - UNITS 1 AND 2 PART II E-1 01/93 l l
i APPENDIXE(CONTINUED) Yp = agricultural productivity by unit area of pasture feed grass,0.7kg/m2(NUREG-0133) 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 btsed on its airborne N concentration rather than the deposition. Therefore R j is basedon(X/Q): R
,,,g = k ' k "' fF pQ UAP (0 t,a o) x 0.75 x (0.5/H) [Eq.E-2]
where: All terms are as defined above and in Appendix D. 1 CDMANCHE PEAK - UNITS 1 AND 2 PART II E-2 01/93
l l APPENDIX F l Y VEGETATION PATHWAY OOSE FACTOR (R w ) l l R
,,,, = k' x [r/ (Y y (A9+A,))]x(DFL9,,,g)x[(Uk)ft ,-A t9g 1 l
+Uff ge "A i t]h [Eq. F-1]
l where: k' = 106 picocurie / microcurie (pci/uci) ! UL A = the consumption rate of fresh leafy vegetation, 0, 26, 42, DJg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) US A = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) f t
= the fraction of the annual intake of fresh leafy i 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 ant" its consumption, 5.18 x 106 seconds (TableE-15,R.9.1,109(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 tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, RY 1 is based on (X/Q) Rf,,,o = k ' k "' [Ukft+Uff]g (DFLt.a,o) (.75 (.5/H)) [Eq. F-2] where: All terms are as defined above and in Appendix D. e l l Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II F-2 01/93 l l
T. - t i 4 l i l
)
i i APPENDIX G i i t SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED 8 : a n l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II G-1 01/93
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