ML20028G831
| ML20028G831 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/30/1990 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20028G829 | List: |
| References | |
| PROC-900630, NUDOCS 9009050095 | |
| Download: ML20028G831 (231) | |
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' TABLE OF CONTD4TS f
em List of Tables v i List of Figures yjg I Cross Reference to Technical Specifications and REC viii ; References xi introduction- xii i PART I RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 DEFINITIONS Il0 SECTION 2.0 NOT USED I20 SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVE!LLANCE I 3/4 0 REQUIREMENTS , 3/4.0 - Applicability I 3/4-1
-3/4.3.3.4 - Radioactive Liquid Effluent ! 3/4 3 Monitoring Instrumentation 3/4.3.3.5 - Radioactive Gaseous Effluent ! 3/4 8 i Monitoring Instru:aentation 3/4.3.3.6 - Meteorological Monicoring I 3/4 13 i instrumentation ,
3/4.7.15 - Sealed Source Leakage 1 3/4 15 , 3/4.11.1.1 - Liquid Effluent Concentration I 3/4 17 3/4.11.1.2 - Liquid Efficent Oose 1 3/4 21 3/4.11.1.3 - Liquid Radwaste Treatment System ! 3/4 22 3/4.11.1.4 - Evaporation Pond I 3/4 22a 3/4.11.2.1 - Gaseous Effluent Dose Rate i 3/4 23 3/4.11.2.2 - Gaseous Effluent Dose Noble Gas ! 3/4 27 3/4.11.2.3 - Gaseous Effluent Dose - lodine-131, ! 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 i Rev. 2 11/89 9009050095 900829 PDR ADOCK 05000445 R PDC
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d TABLE OF CONTENTS Elat 3/4.11.4 + Radioactive Effluents Total Dose 1 3/4-30 3/4.12.1 - Radiological Environmental Monitoring I 3/4-32 Program 3/4.12.2 - Land Use Census I 3/4-44 3/4.12.3 - Interlaboratory Comparison Program I 3/4 45 BASES I B 3/4-0 SECTION 5.0 DESIGN FEATURES I50 5.1.3 - Maps Defining Unrestricted Areas and I 5-1 Site Boundary for Radioactive Gaseous and liquid Effluents SECTION 6.0 ADMINISTRATIVE CONTROLS I60 6.9.1.3 - Annual Radiological Environmental I 6-1 Operating Report 6.9.1.4 - Semiannual Radioactive Effluent !62 Release Report 6.14 Offsite Dose Calculation Manual I 6-3 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS 11 1-1 1.1 General Methodology for Determining Liquid II 1-1 Effluent Monitor Setpoints l 1.1.1 Isotopic Concentration of the Waste Tank II l 2 l 1.1.2 Maximum Effluent Flow Rate (f) II 1-2 i 1.1.3 Dilution of Liquid Effluents Due to !! 1-3 Circulating Water Flow (F) i 1.1.4 Actual Dilution Factor (ADF) II 1-3 1.1.5 Required Dilution Factor (RDF) 11 1-4 ' l.1.6 Upper Setpt. int Limit for 11 1-5 Detector XRE-5253 11 Rev. I 8/89 L
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TABLE OF CONTE!75 hal , 1.2 Dose Calculation for Liquid Effluents II 1-7 1.2.1 Calculation of Dose Due to a !! l-7 Batch Release 1.2.2 Calculation of Dose Due to 11 1-9 Radionuclide Buildup in the Lake 1.3 Dose Projections for Liquid Effluents 11 1 11 ' t 1.4 Service Water Effluent Radiation 11 1-16 Monitors IRE-4269/4270 ; 1.5 Turbine Building Sump Effluent Radiation !! 1-17 Monitor 1RE-5100 1.6 Definitions of Common Liquid Effluent Parameters !! 1-18 2.0 GASEOUS EFFLUENTS 11 2 1 2.1 - Gaseous Effluent Monitor Setpoints - 1121 2.1.1 Dose Rates Due to Noble Gases II 2-3 2.1.2 Plant Vent Stack Noble Gas II 2 Monitors XRE-5570A/B and XRE 5567A/B , 2.1.3 Plant Vent Flow Monitors 11 2-7 2.1.A Auxiliary Building Ventilation Exhaust 11 2-8 Monitor XRE-5701 2.1.5 Containment Atmosphere Gaseous II 2-10 i Monitor 1RE-5503 2.1.6 Dose Rates Due to Radioiodines, !! 2-12 Tritium, and Particulates 2.1.7 Plant Vent Stack Iodine Monitors !! 2-13 XRE-5575A/B 2.1.8 Plant Vent Stack Particulate II 2 14 Monitors XRE-5568A/B l iii Rev. 0 3/89 ( . - - -
TABLE OF CCNTENTS E19.t 2.2 Gaseous Effluent Dose Calculations II 2 17 2.2.1 Dose Due to Noble Gases II 2-17 2.2.2 Dose Due to Radioiodines, Tritium, II 2-18 and Particulates 2.2.3 Dose Projections for Gaseous Effluents II 2-20 2.2.4- Dose Calculations to Support Other II 2-20 ' Requirements ; 2.3 Meteorological Model II 2 47 2.3.1 Dispersion Calculations II 2-47 2.3.2 Deposition Calculations 11 2-49 i 2.4 Definition of Gaseous Effluent Parameters II 2-50 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1 3.1' Sampling Locations 11 3-1 - 3.2 Interlaberatory Comparison Program II 3-1 APPENDIX A. Pathway Dose Rate Pcrameter (Pj) A-1 l B. Inhalation Pat hway Dose Factor B-1 C. Ground Plant Pathway Dose Factor C-1 . D. Grass-Cow Hilk Pathway Dose Factor D-1 E. Cow Meat Pathway Dose Factor E-1 F. Vegetation Pathway Dose Factor F-1 G. Supplemental Guidance Statements G-1 6 i iv Rev. 1 8/89 1
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List of Tables j Table No. li,tli E121 ; PART I - RADIOLOGICAL EFFLUENT CONTROLS I y l 1.1 Frequency Notation I15 ! 1.2 Operational Modes I16 3.3 7 Radioactive Liquid Effluent Monitoring 1 3/4 4 . Instrumentation ! 4.3-3 Radioactive Liquid Effluent Monitoring I 3/4-6 Instrumentatior, Surveillance Requirements ' 3.3 8 Radioactive Gaseous Effluent Monit'oring 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 4.11-2 Radioactive Gaseous Waste Sampling and 1 3/4 24 Analysis Program 3.12-1 R:diological Environmental Monitoring I 3/4 34 Progsm . 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 .
' ample Analyses (LLDs) ;
PART II - CAMillATIONAL METHODOLOGIES L 1.1 Site Related Ingestion Dose Commitment II 1-12 Factor (Att) - 2.1 Dose Factors for Exposure to a Semi- II 2 16 : Infinite Cloud of Noble Gases 2.2 Pathway Dose Rate Parameter (Pj) !! 2-23 2.3 Pathway Dose Factors II 2 24 v Rev. I 8/89
list of Tables Igble No. g g 2.4 Atmospheric Dispersion and Depletion 11 2 Parameters for Radiological Effluent Control 3/4.11.2.3 Calculations 2.5 Controlling Receptors, locations, and II 2 46 Pathways (For Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3) 3.1 Environmental Sampling locations 1133 vi Rev. 0 3/89 4
I list of Fiaures i Fi9ure 111.11 Pigg pART I- RADIOLOG((A'. EFFLUENT CONTROLS l 5.1-3 Site Boundary eno 'Jnrestricted Areas I52 PART II - CALCULATIONAL METHODOLOGIES I 1.1 Liquid Effluent Discharge Pathways II 1-22 , 1.2 Energy Response to. Gamma P.adiations for RD 33 Type Detector II l 23 j 1.3 Circulating Water Pump Curves II 1 24
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1.4 Liquid Waste Processing System i II.1-251 ; 1 2.1 Gaseous Waste Processing System II 2-56 2.2 Plume Depletion Effect for Ground II 2-57 Level Releases 2.3 Vertical Standard Deviation of II 2-58 Material in a Plume - 2.4 Relative Deposition for Ground- II 2 59 level Releases 2.5 Open Terrain Correction Factor !! 2-60 3.1 Radiological Environmental Monitoring Locations II 3-9 7 vii Rev. 0 3/89
sL Cross Refergnee to Technical _hifications and REC Number or Document Section Reauirement ODCM Section 4 PART l RADIOLOGICAL EFFLUENT CONTROLS (REC) Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation operability, surveillance, and 3/4.3.3.4 and , setpoint requirements 3/4.3.3.5 Tech Specs 6.8.3.e.2 Limit liquid effluent'concentrati 3/4.11.1.1 Tech Specs 6.8.3.e.3 Effluent monitoring, sampling, and analysis requirement!. 3/4.11.1.1 and - 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, d.i;es 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.e.6 Effluent treatment systems operability requirements 3/4.11.1.3 and 3/4.11.2.4 Tech Specs 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 particulate dose 3/4.11.2.3 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 Tech Specs 6.8.3.f.3 Interlaboratory Comparison Program 3/4.12.3 PART II - CALCULATIONAL METHODCLOGIES REC 3/4.11.1.1 Liquid effluent concentration 1.1 REC 3/4.11.1.2 Dose due to liauid effluents 1.2 REC 3/4.11.1.3 Dose projections for liquid 1.3 releases viti Rev. 0 3/89
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. Cross Reference to Technical Scecifications and REC !
, i Number or Document Section Reouirement ODCM Secti2D REC 3/4.ll.2.1.a Dose rate due to noble gases 2.1.1-
REC 3/4.11.2.1.b Dose rate due to iodine, tritium, 2.1.6 - and particulates with half lives greater than eight days REC 3/4.11.2.2 Air dose due to noble gases 2.2.1 t REC 3/4.11.2.3 Doses due to iodines, tritium, 2.2.2 + and particulates with half-lives greater than eight days , REC 3/4.11.2.4 Dose projections for gaseous 2.2.3 releases ' REC 3/4.11.4 Total dose due to releases of 2.2.4 radioactivity and direct radiation REC 3/4.12.1 Description of radiological 3.1 environmental sampling locations REC 3/4.12.2 Dose calculations for identifying 2.2.4 l changes to environmental sampling locations , Rtc 3/4.!? 3 Description of the Interlaboratory 3.2 l Comparison Program , REC 3.3.3.4 Radioactive liquid effluent monitoring channels alarm / trip setpoints o liquid waste monitor (XRE-5253) 1.1.6 o turbine building sump monitor 1.5 (IRE-5100) o service water monitor 1.4 (IRE-4269/4270) ix Rev. 0 3/89
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.i Cross Reference to Technical Snecifications and REC ,
i Number or l Document Section Reautrement ODCM Section i REC 3.3.3.5 Radioactive gaseous effluent ' monitoring channels alarm / trip 4 setpoints o noble gas release rate monitors 2.1.3 XRE 5570A and XRE 5570B (WGRM release rate channels) o noble gas activity monitors 2.1.2 , XRE 5570A and XRE 55708 : (WRGM low range activity channel) ' XRE 5567A and XRE 55678 (PIG noble gas channel) o waste gas holdup system monitor 2.1.4 (auxiliary building vent monitor) XRE 5701 o sampler flow rate monitor 2.1.3 XFT 5570A2/B2 Tech Specs 3.3.3.1 Radiation monitoring channels alarm / trip setpoint o Containment atmosphere gaseous 2.1.5 monitor (containment vent monitor)1RE-5503 Tech Specs 6.9.1.4 Assessment of radiation doses due 2.2.4 REC 6.9.1.4 to liquid and gaseous effluents released during the previous yehe ; Tech Specs 6.9.1.4 Assessment of doses to members of 2.2.4 REC 6.9.1.4 the public inside the site boundary Tech Specs 6.9.1.4 Assessment of doses to the most 2.2.4 REC 6.9.1.4 likely exposed member of the public from reactor releases hnd direct radiation x Rev. 0 3/89
b I REFERENCES f
- 1. Boegli, J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield .
" Preparation of Radiological Effluent Technical Specifications for j Nuclear Power Plants," NUREG 0133 (October 1978), i
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor l Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, ,
trar< dix I, U. S. NRC Regulatory Guide 1.109, Rev.1 (October 1977). j
- 3. "tnvoronmental Report," TU Electric, Comanche Peak Steam Electric Station. i
- 4. " Final Safety Analysis Report," TU. Electric, Comanche Peak Steam Electric '
Station. t i Methods for Estimating Atmospheric Transport and Dispersion of Gaseous S. Efnuents in Routine Releases from Light Water-Cooled Reactors, U.S. NRC-Regulatory Guide 1.111 (harch 1976).
- 6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors, U.S.
NRC Regulatory Guide 1.111, Rev. 1 (July 1977).
- 7. Meteorology and Atomic Energy: Edited by Slade, D. H.; U. S. Department -
of Commerce (July 1969). 4 b " Unit 1 Technical Specifications," TV Electric, Comanche ,"cak Steam Electric Station. l
- 9. Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of tne.
Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program + (Generic letter 89 01), USNRC, January 31, 1989. , l t i 1 l- xi Rev. I 8/89 y ----w.,.-
INTRODUCT10N The OFFSITE DOSE CALCULATION MANL'AL (ODCM) is a supporting document of the CPSES Technical Specification. Part I of the ODCM contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3, (2) descriptions of the ; information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by. Technical Specifications 6.9.1.3 and 6.9.1.4, and (3) Controls for Meteorological Monitoring Instrumentation and Sealed Source Leakage. Part II -' of the ODCM describes the methodology and parameters to be used in the ! calculation of offsite doses due to radioactive liquid and gaseous effluents ! and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. Part II of the ODCM also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Liquid and Gaseous Radwaste Treatment System configurations are shown in Figures 1.4 and 2.1 ' l The ODCM will be maintained at the plant for use as a reference guide and training docu9ent on accepted methodologies and calculations. Changes in the calculat4n methods or parameters will be incorporated into the ODCM in order to assure that the ODCM rtpresents the present methodology in all applicable areas. TV Electric initiated changes to the ODCM will be implemented in accordance with Section 6.14 of the Technical Specifications. xii Rev. 0 3/89
i i s I t The ODCM 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 i 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 ODCM may be initiated to implement more complex calculations as systems become available ' and are validated that can reliably, ecMomically and properly perform these I more complex calculations. A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Semiannual Radioactive Effluent Release Report) i'equirements is to use a computerized system to determine the effluent releases and update cumulative doses. ' 1 Where additional clarification or information is required to adequately
- implement certain ODCM requirements, supplemental guidance is provided in Appendix G of Part II.
l l xiii Rev. 1 8/89 l
S RADIOLOGICAL EFFLUENT CONTROLS 1 l
l .. L; h s i 9 9 r SECTION 1.0 DEFINITIONS . 1 1 1 I l l l l COMANCHE PEAK - UNIT I REV 0 I 1-0 3/85 l I l l
l l '. 0 DEFINITIONS l ' i The defined terms of this section appear in capitalized type and are I applicable throughout these Controls. J ACTION l 1.1 ACTION shall be that part of a Control which prescribes remedial measures required under designated conditions. ; ANALOG CHANNEL OPERATIONAL TEST i 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 OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL ! OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy. 4 CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the .
- hannel values of such that it responds within the required range and accuracy to known input. -
The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, intarlock and/or trip functions and may be ' performed by any series of sequential, overlapping, or total channel steps : such that the entire channel is calibrated. [HANNEL CHECK f
'. 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, i
DIGITALCHANNELOPERATIONALTQT, 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. R 0 COMANCHE PEAK UNIT 1 111 3/ g
r ; l DEFINITIONS I DOSE EQUIVALENT I-131 !
' 1.11 00SE EQUIVALENT I 131 shall be that concentration of I 121 (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 1-135 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, i
ERE00ENCY NOTATION ? t 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance - Requirements shall correspond to the intervals defined in Table 1.1. MEMBERfS) 0F THE PUBLIC : 1.18 MEh2R(S)-0F THE PUBLIC-shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or 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 monitorino Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the - information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by i 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 OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubriention 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). REV. O COMANCHE PEAK - UNIT 1 I l-2 3/89
DEFINITIONS OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2. PRIMARY PLANT VENTILATION SYSTEM i 1.24 A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through chcrcoal 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. ;
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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, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement. l-RATED THERMAL POWER I l.29 RATED THERMAL POWER shall be a total reactor core heat transfer rate to ' the reactor coolant of 3411 MWt. REPORTABLE EVENT ' 1.31 A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73. SITE BOUNDARY s 1.33 The SITE BOUNDARY shall be that line as shown in Figure 5.1-3. SOURCE CHECK l 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. REV. O COMANCHE PEAK - UNIT 1 Il3 3/89
i DEFINITIONS UNRESTRICTED AREA i 1.41 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY ! access to which is not controlled by the licensee for purposes of protection ' of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial. I commercial, institutional, and/or recreational purposes. ! VENTING 1.42 VENTING shall be the controlled process of discharging air or gas from a i confinement to maintain temperature, pressure, humidity, concentration, or
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other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not 1 l taply a VENTING process. I t WASTE GAS HOLDUP SYSTEM r ' 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. ' 6 y l 1 REV. O CDMANCHE PEAK - UNIT 1 I l-4 3/89 l
r. TABLE 1.1 FREOUENCY NOTATION NOTATION FREQUENCY-S At least once per 12 hours. O 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. i 1 1 REV. O COMANCHE PEAK - UNIT 1 . I l-5 3/89
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4 TABLE 1.2 l OPERATIONAL MODES AVERAGE l REACTIVITY % RATED COOLANT ; MODE CONDITION. Keff THERMAL POWER
- TEMPERATURE I
- 1. POWER OPERATION 2 0.99 > 5% 2 3500F i
- 2. STARTUP 2 0.99 s 5% 1 3500F l.
- 3. HOT STANDBY < 0.99 0 2 3500F
- 4. HOT SHUTDOWN < 0.99 0 3500F>Tavg
> 2000F
- 5. COLD SHUTDOWN < 0.99 0 1 2000F
- 6. REFUELING ** s 0.95 0 s 1400F i
- Excluding decay heat.
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** Fuel fully in the reactor tensioned or withvessel with the head the vessel head closure bolts less than removed.
i I i REV. O COMANCHE PEAK - UNIT Il6 3/89
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i 1 1 SECTION 2.0 NOT USED I 2-0 REY. I 8/89
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SECTIONS 3.0 AND 4.0-CONTROLS AND SURVEILLANCE REQUIREMENTS
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COMANCHE PEAK'- UNIT 1 I 3/4-0 h9 J T n ,--
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1/4 CONTROLS AND SURVEILLANCE RE0VIREMENTS' 3/4.0 APPLICABILITY # CONTROLS f 3.0.1 Compline with the Controls contained in the succeeding Controls _ is required during_the OPERATIONAL MODEF 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 is restored prior to expiration of the ' specified time intervals, completion of the ACTION requirements is not
. required. i
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3.0.3. When a Control is not met, except as provided in the associated ACTION ; requirements, within 1 hour action shall be initiated to- place the unit in a - MODE in which the specification does not apply by placing it, as _ applicable, in c
- a. At least HOT STANDBY within the next 6 hours,
- b. At least HOT SHUTU iN within the following.6 hours, and
- c. At least COLD'SHUTDuWN within-the subsequent 24 hours..
Where corrective measures are completed that permit operation under the ACTION-requirements, the action may be taken in accordance with the specified time j limits as measured from the f.ime of failure to meet the Control. Exceptions ' to these requirements are stated in the individual controls. This control is not applicable in MODE 5 or 6. 3.0.4 Entry into an OPERATIONAL MODE or other 9ecified condition shall. not ' be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERMiONAL MODE or specified condition may be'made in accordance with ACTION requirements when conformance to them permits I continued oper,ation of the facility for an unlimited period of time. This , provision shall not prevent passige through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual controls. I L # The associated basis f rom the CPSES Technical Specifications applies to this section. REY. O COMANCHE PEAK - UNIT 1- I 3/4-1 3/89. l L l
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" 1 APPLICABILITY' I i
SURVflLLANCE REOUIREMENTS ) 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions ~ specified for individual Contrels unless otherwise-stated in~ Lan individual Surveillance Requirement. I s 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with: H
- a. Ainterval,.
maximum butallowable extension not to exceed 25% of the surveillance
- b. The combined tiine icterval for any three consecutive surveillance intervals snall. not exceed 3.25 times the specified surveillance i.nterval. '
l Exceptions to these requirements are stated in the individual controls. i 4.0.3 Failure to perform a Surveillance Requirement within the-allowed surveillance interval, defined by Surveillance Requirement 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control. The
' time limits of the ACTION requirements are applicable at the time it-is identified that a Surveillance Requirement has not been performed. The. ACTION requirements may be delnyed for up to 24 hours to permit the completion of the l
surveillance when the allowable outage:tirae limits of the ACTION requirements are less than 24 hours. Surveillance Requ'rements do not have to be performed n on inoperable equipment. 1 4.0.4 Entry into an OPERATIONAL MODE or other spacified condition shall-not be made unless the Surveillance Requirecent(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 requirementt, are stated in the individual controls. l h COMANCHE PEAK - UNIT 1 I 3/4-2 9 i
~ INSTRUMENTATION RADIDACTIVE 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 determined and adjusted in accordance with the methodology'and
; parameters in the OFFSITE 00SE CALCULATION MANUAL (ODCM) .
g . APPLICABILITY: At'all times. ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel Alarn;/ Trip Setpoint less conservative than required by the above g
Control, i!'unediately suspend the release of radioactive liquid 1 effluents monitored by the affected chann , or declare'the channel inoperable, or change the setpoint so it is acceptably conservative, b With less than the minimum number of radioactive liquid effluent monitering instrumentation channels OPERABLE, take the ACTION shown in
-Table 3.3-7 . Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful. explain in t5e next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable .
SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAL'BRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHAhNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3 M REV. O COMANCHE PEAK - UNIT 1 I 3/4-3 3/89 1 I
..7 n .M s3 E
A 10aLL3_J-I_ R RADIDACTIVE LIOUID EFFLUENT M ITORING INSTRIMENTATION i c MINIORM _z
] JFSTRUMENT CHAlmELS OPERABLE l
ACTION s
- 1. Radioactivity Monitors Providing Alarm and Automatic Terminattan of Release. '
- a. Liquid Radwaste Effluent Line (XRE-5253) 1 -30 -!
- b. Turbine Building (Floor D 4 ins) Sunps Effluent Line
- 1 31 (IRE-5100)
M l
- i 2. Radioactivity Monitors Providi.sg Alare But Not Providing Automatic Terslaation of Release .,
i
- a. Service Water System Effluent Line (IRE-4269, IRE-4270) . 1/ train .32
- 3. Flow Rate Measurement Devices i
- a. Liquid Radwaste Effluent Line (XFT-5288) 1. 33 RA -
8 .* = 0
. -- . , , .- - -. , . _ . _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ = _ _ _
-TABLE =3.3-7 (Continuedi l ACTION STATEMENTS ACTION 30- 'With the number of channels OPERABLE less than required by the
' Minimum Channels 0PERABLE requirement, effluent releases via this pathway may continue provided~that prior to initiating a release:
- a. At least two, independent samples are analyzed in accordance lwith-Control 4.11.1.1.1, and
- b. At least two technically qualified members of the facility staff f 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 OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may-continue provided grab samples are. analyzed for. !
radioactivity at a lower limit of detection of no more-than 10 - p microcurie /ml: 1
- 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 activit's of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I 131. r ' ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue i provided that:
- a. -With th'e component cooling water monitors (IRE-4509, IRE-4510, &
1RE-4 !- IX10'gil) OPERABLE and indicating an activity of less'than microcurie /ml, a grab sample is collected and analyzed-for radioactivity at a lower limit of detection of no more than 10-7 microcurie /ml at least every 31 days; or [ l
- b. At least once per 12 hours, grab samples are collected and h analyzed for adioactivity at a lower li;;?t-of detection of no more than 10-(' microcurie /ml.
l ACTION 33- With the number of channels OPERABLE loss than required by the l- 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. REV. O COMANCHE PEAK - UNIT 1 I 3/4-5 3/89 l e .
47 - e n 1 n E - 9" x s TABLE 4.3-3 RADI0 ACTIVE LIOUID EFFLUENT NONITORING INSTIRBENTATION SURVEILLANCE REQUIREEN ANALOG- DIGITAL CHAlWIEL CHAf01El CHAf81EL SGIRCE CH4151EL INSTRUMENT OPERATIONAL OPERATIONAL CHECK CHECK. CALIBRATION TEST TEST
- 1. Radioactivity Monitors Providing' Alarm and Automatic Termination of Release !
- a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. Q(1)~
- b. Turbine Building-(Floor Drains) Sumps Effluent Line(IRE-5100) D N R(4) 'N.A. Q(2)
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Terimination of Release ,
i a. Service Water System Effluent Line (IRE-4269,1RE-4270) D- N N.A. R(4) Q(3) i
- 3. Flow Rate Measurement Devices w :o 3% a. Liquid Radwaste Effluent Line
, (XFT-5288). D(5) . N.A. R.
Q- 'N.A.
'y.7,.
_y -
, ~ - - - , -e- .
y n ,<-~ . .,a--, . . ggy-- , ,<.q,. -- e n' &
# _ . ~ . . ~ . . - .
g
' TABLE 4.3-3 JContinued)
"ABLE NO"ATIONS (1)~ The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that l automatic isolation of this pathway and Control Rcom alarm annunciation occur if any of the following conditions exist:
{
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint, Lor J l
- 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~ Alarm / Trip Setpoint, or i
- b. Circuit failure (Channel Out of Service - Loss of Power, Loss of i Counts, Loss of Sample Flow, or Check Source Failure).
(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control
-Room alarm annunciation occurs if any of the following ' conditions exist:
- a. Instrument indicates measured levels above the Alarm Setpoint, or q g ,
l b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure). (4) The initial CHANNEL CALIBRATION shall be performed using one or more of L L the reference standards certified by the National Bureau of Standards (NBS) or using standards that have_been obtained from suppliers that participate in measurement assurance activities with NBS. 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, reference standards-certified by NBS, or standards that have been obtained from supplier:: that participate in measurement assurance activities with NBS 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 d:ys on which continuous, periodic, or batch releases are made. REV. O COMANCHE PEAX - UNIT 1 I 3/4-7 3/89
p
.( ,
R{SJf9MENTAT!0N. RADI6 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.5 In accordance with CPSES TS 6.8.3.e.1, the radioactive.g'aseous effluent monitoring-instrumentation channels shown in Table 3.328.shall be-OPERABLE'with their Alarm / Trip Setpoints set to ensure that the limits.of Control 3.11.2.1 are not exceeded . The Alarm / Trip Setpoints of these channels shall be determined and adjusted'in accordance with the metoodology. and parameters in the ODCM. APPLICABILITY: As shown in Table 3.3-8 ACTION:
- a. With a radioactive gastous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspcod tne release of radioactive gaseous effluents monitored by the nffected 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 channtls OPERABLE, take:the ACTION shown in Table 3.3-8 . Restore the inograble instrumentation to OPERABLE status within 30 days and, if unsuccessful explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a. timely manner,
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. -
SLRy.fjLLANCE REOUIREMENTS 4.3.3.5 Each radioactive gaseous effluent. monitoring irstrumentation channel . shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE. CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4 . REV.'l COMANCHE PEAK --UNIT 1 I 3/4 8 8/89 {
n h2 2 m ^ A
^
f TABLE 3.3-8 g RADI0 ACTIVE GASEOUS EFFLUENT MONITORIIIG INSTRMENTATION-
~
-e l
- MINIMim CHAf88ELS INSTRUNENT OPERABLE APPLICABILITY
~
ACTION
- 1. IfASTE GAS HOLOUP SYSTEM
- a. Noble Gas Rel?ase Rate Honitor - Providing Alam-
~ and Automatic Temination "
of Release R [XRE-55704 & XRE-55708 [ (effluent release rate channel)] 1/ stack **- 34
- 2. PRIMARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor
[XRE-5570A & XRE-55708 (effluent release rate channel)] I/ stack
- 36
- b. Iodine Sampler (INtGM sample skid)~ 1/ stack
- 37 RR c. Particulate. Sampler .1/ stack *-
37
$< (WRGM sample skid). i o
- d. Sampler Flow. Rate Monitor '
(XFT-5570A2,XFT-557082) . 1/ stack-
- 35- ;
t b g~ -g ,, e ym .N-+ y < ,,; -gg-- - ; m . ,g - s ,e ,
,,s+4 ,, wm- - , , - _,y_ _ ..___s
J < _j
. N
'b TABLE 3.3 8 (ContinuedF ESLL!iORll0LS -
J
~* 9 At alll times.
** During Batch Radioactive Rcleases via thi;s pathway.
ACTION 34- With the number of channels OPERABLE:less than required by the. ;
' Minipum Channels OPERABLE requirement, the contents of the tank (s)-
may be rele6 Led to the environment provided that prior to inititting the release: )'
.~
- a. The auxiliary building vent duct monitor (XRE-5701) is confirmed OPERABLE, or j ~
L
- b. At least two independent samples of- the tank's' contents are anelyzed, and-s
- c. At least two-technically' qualified members of the facility-staff independently verify the release rate calculations and i discharge valve lineup.
Otherwise, suspend release of radioactive effluents.via this pathway. ACTION 35- 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 astimated at least once per 4 hours . ACTION 36- With the number of channels OPERABLE 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 i (low range activity) or XRE-5567A, XRE 5567B) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 ' ! hours; or (b) The Plant Vent Flow Rate Monitor (XFT-5570A1, XFT-5570B1) is OPERABLE, and an alternate Plant Vent Noble Gas Activity 4 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 12 hours and these samples are analyzed for radioactivity within 24 hours. i ACTION 37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4i11-2. REV. O COMANCHE PEAK - tJNIT 1 I 3/4-10 3/89
6_'
- l. .. . . . . g. ,
_ , . 7,
-x -
~
n h 2 m
;E TABLE 4.3-4
- , RADIGACTIVE GASEGUS EFFLUENT MONITORInc INSTRIBENTATION SURVEILLANCE REGUIRENENTS' C
5 ANALOG DIGITAL'~
- CHAIRIEL CHA181EL
" CHAlstEL SOURCE CHAISIEL ' OPERATIONAL OPERATIONAL-INSTRUMENT CHECK CHECK CALIBRATION TEST- TEST
- 1. WASTE GAS HDLDUP SYSTEM
- a. -Noble Gas Release Rate Monitor -
Providing Alarm and Automatic
~
Termination of Release R [XRE-5570A, XRE-55708(effluent release
? rate channel)] P P R(3) 'N.A. Q(I)~
~
~
- 2. PRIMARY PLANT VENTILATION
- a. Iloble Gas Release Rate Monitor.
[XRE-5570A, XRE-55708(effluent release rate channel)] D F R(3) H .?.. Q(2)-
- b. Iodine Sample:-
(WRGM sample ~ skid) -W(4) 'N.A. N.A. N.A. N.A. w= c. Particalate Sampler (NRCM Sample Skid) N(4) N.A. N.A. P.A. N.A. D'.2 w
-d. Sampler Flow Rate Monitor (XFT-5570A2,XFT-557082) D N.A. R Q N.A.
k
'k TABLE 4 3-4 (Continued)
TABLE NOTATIONS
# Prior to any release from the WASTE GAS HOLOUP-SYSTEM,or containment PURGING or VENTING, not-to exceed'31 days..
3
-(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 fellowing condition exists:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or
- b. Circuit 1 failure, (Channel Out of Service - Lo s of Power, Loss of Counts, Loss of Sample. Flow, or Check Source F--ilure). <
(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. Circuit 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 , the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained _from suppliers that participate in measurement assurance activities with NBS. 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 calibratior, reference standards certified by NBS, or standards that have been obtained from suppliers that participate in measurement assurance activities with NBS 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. r 4 Y REV. O COMANCHE PEAK - UNIT 1 I 3/4-12 3/89
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological - ing instrumentation channels shown in Table 3.3.3-9 shall be OFi.s -- APPLICABILITY: At all times. ACTION:
- a. hlth one or more required meteorological monitoring channels inoperable 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 RE0'JIREMENTS 4.3.3.6 Each of the above meteorological mon'.toring 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.
REV. O COMANCHE PEAK - UNIT 1 I 3/4-13 3/89 1
l
?
-TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT LOCATION
- OPERABLE
- l. WIND SPEED 1 of 3-
.a. X-SY-4117 Nominal-Elev. 60 m.
1
- b. X-SY-4118 ~ Nominal Elev. 10 m. -
- c. X-SY 4128* 'Nomint.1 Elev. 10 m.
- 2. WIND DIRECTION 1 of 3
=t
- a. X-ZY-4115 Nominal Elev. 60 m.
{ b. X-ZY-4116- Nominal Elev. 10 m. p , l 1
- c. X-ZY-4126* Nominal Elev.10 m.
- 3. AIR TEMPERATURE - a T 1 of 2 '
- a. X-TY-4119 Nominal Elev. 60 m. and- 1 Nominal Elev.10 m.
b..X-TY-4120 Nominal Elev. 60 m. and Nominal Elev. 10 m. ,
- Mounted on backup tower.
1 REV. O COMANCHE PEAK - UNIT 1 1 3/4-14 3/89
v.. . - INSTRUMENTATION l SEALED ~ SOURCE CONTAMINATION CONTR0ls ___
. 1 3.7.15 Each sealed source containing radioactive material either in excess' of 100 microcuries of beta and/cr gamma emitting material or 5 micrcCuries of alpha emitting material shall be free of_ greater- thant or equal to 0.005 microcurie of removable contamination.
APPllCABillTY: At all times. .-, ACTION , With a sealed source having removable contamination in 'excesa cf-the above q limits, irmediately withdraw the. sealed source from use and Ithere q
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations, j SURVEILLANCE REOUIREMENTS I
4.7.15.1 Test Requirements - Each sealed source shall be tested for~ leakage I i-and/or contamination-by:
- a. The licensee, or
- b. Other persons specifically authorized by the Commission or an t
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:
l- 1) With a half-life greater than 30 days (excluding Hydrogen 3), and
- 2) In any form other than gas.
REV. O COMANCHE PEAK - UNIT 1 I 3/4-15 3/89 l l
SURVEILLANCE ME0VIREMENTS (Continued)- by~
- b. Stored sources not in use - Each sealed source'and fission detector R ' shall be tested prior to use or transfer 'o another-licensee unless R "" ' tested within the previous 6 months. Sealed sourcesand fission detectors trar'..' erred without a. certificate indicating the last test
-' date shall be tested prior to being'placed into use; and-m c. Startup sources and fission detectors - Each sealed startup source and fission datector shall be tested prior to installation nr within 31 days prior te being subjecteel to core flux and following-repair. or-maintenance to tra source.
[. ' 4.7.15.3 Reports - A report = shall be pt epared and submitted to the - .
,ax -
Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence-of- greater than or caual- to I 1 0.005 microcurie of removable contamination. s
) '-.
- f'_'
.eA bih.
fi ;,
?$t h y ,
ye , p COMANCHE PEAK - UNIT 1 I 3/4-16 m('l 9 kj&
- q r- .,
a; 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 L10VID EFFLL'ENTS CONCENTRATION CONTROLS 3.11.1.l' In accordance-with CPSES TS 6.8.3.e.2 and 3, the concentration of radioactive material released in liquid effluents- to UNRESTRICTED AREAS (see. Figure 5.1-3)'shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or-- entrained noble gases. For_ dissolved or entrained noble gases, _the concentration shall be limited to 2 x 10 9 microcurie /ml total activity. APPLICABILITY: At all times. ACTION: (a) With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. (b) The provisions of Controls 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to 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 accordance with the methodology and parameters in the _0DCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1. REV. O COMANCHE PEAX - UNTI 1 I 3/4-17 3/89
+ -.s .--.~a.-~e. ..n.. .n u a .x - - ..--.na--a._-.a -.,-ar.,. m , .- -
..g_
i TABLE 6.11-1 Radioactive Liquid Waste Sampling and Analyste Program. MINIMUM LohT.R LIMIT I,1 QUID RELT,Ast SAMPLING 0F DETECTION '; ANALYSIS TTPE OF ACTIVITT TTPE FREQUENCT FREQUENCY .(LLD)(1) ANALYSIS (*C1/al)
- 1. Eatch Waste P P Release Each Batch Each Batch Tanks (2)
Principal Gamma 5x10'I Emittere(3) *
- a. Vaste I-131 1x10
- Moottor F M Tanks Cae Batch /M Dissolved and ,
Estrataed Cases 1:10-5 .,
- b. Laundry (Gemas Emitters) toidup and P M Monitor- Each Satch Ceapeette (4)(9)
Tenha E-3 lx10'5 l 2' )
- c. Wastewater Grose Alpha la10'I' I
Eeld-up ' Tanka (8) P .Q (4) (9, sr 49, sr-90 5:10 Each Batch Campeette l*c
- d. Condensate Fe-SS 1:10
F F Polisher ' Principal Gamma Eaab Satch Each Satah Inittere'(3) Backwash $x10'I Resevery 1-131 1 10 Tasks (4)(7)
- e. Campesest N L
Coeltas gg) Campeelte E-3 Water Desta 1x10'3 s Tank (7) y v , 2 . Continuous erah sample Releases (5) l' Priasipal Canna 5:10'I
- a. Turbine 881"*'* ( 3 )
Bldg Sumps No. 1&2 1-131 1x10 Effluents . 3 (6) (7) M (4) 33 galo-5 Ceaposite
- b. Turbine Bldg Sump No. 4 E f fluents '
(7) (10) COMANCHE PEAK - UNIT 1 1 3/4-13 REV. 3 4/90
TABLE 4.11'-l (Continued) TABLE NOTATIONS (1) Th'e LLD is defined, for purposss 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: -
-4.66 sb E V 2.22 x 10 6 . y . exp (-Aot)
Where: LLD = the "a pr mass or volume)_ tori" lower limit of detection (microcurie per unit sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate-(counts per minute), E = the counting efficiency (counts per disintegration), V = the-sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the r&dioactive 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. 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. (2) A batch release is the discharge of 14uid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. REV. O COMANCHE PEAK - UNIT 1 I 3/4-19 3/89
A TABLE a.11 1 (Continutdf
;l; TABLE NOTATIONS '
(3) The principal gamma emmiters for which the LLO specification applies ' include Mo 99, Cs-134. the following radionuclides: Cs-137, Ce 141. Mn 54, Fe 59, Co 58 Co 60, 2n 65, an:LLD of 5 x 10 6 Ce 144 shall also be measured- but with- ' are to be considered.This-list does not mean that only these nuclides with those of the above nuclides, shall also be analyzed and the. Semiannual Radioactive Effluent Release Report pursuant to Control Revision 1 Jund 1974.6.9.1.4 in the format outlined in Regulatory Guide.l.21,! (4) A composite ~sampie is one in which the quantity of liquid sampled ~is proportional to the quantity of liquid waste discharged and in which the i method of sampling of the liquids employed results in a spacimen that is representative released. (5) i A continuous release is the discharge of liquid wastes of a nondiscrete-volume, e.g., continuous from a volume of a system that has an input flow during the release. J l (6)' These waste streams shall be required to be sampled and ar.alyzed in 1 accordance with this table if either of the following conditions exist: (a) Activity is present in the secondary system as indicated by either Steam Generator analysis; or Blowdown monitors or secondary sampling and H i (b) Activity is previous present in the respective tanks or sumps during the 4 weeks. "
\
these tanks and sumps-need not be performed.If neither of thel (7) All flow from this waste stream shall be diverted to the Wastewate Holduo Dnks when results of sample analyses show radioactivity preser.t in the waste values givenstream at concentrations greater than or equal to the u.D in this table. Sampling and analysis of the respective t tanks or Holdup Tanks.sumps are not required when flow is diverted to the Wastewater (8) Waste Water Holdup Tanks shall be discharged directly to the Cir;:ulating 3 Water Discharge Tunnel when results of sample analyses show radioactivi present in the tanks at concentrations greater than or equal to the LLO values values,given in this table. If the c>ncentrations are less than these Retention Pond. Waste Water Holdup Tanks may be discharged to the Low Volume l i (9) -{ With the exception of the reqeired monthly composite sample for H 3, '3 !- composite these tanks anal ar/ses for Waste Water Holdup Tanks are not required when above. e discharged to the Low Volume Retention Pond per Note (8), p (10) Sampling and analysis of Turbine Building Sump No. 4 shall be required ! 3
.when secondary waste streams are transferred to the Co current Waste System (i.e., Waste Water Holdup Tanks) per Note (7), above.
j j COMANCHE PEAK - UNIT 1 I 3/4-20 REV. 3 4/90
. i l
l
s l r
-RADIOACTIVE EFFLUENTS !
Q.QS1 CONTROLS = 3.11.1.2 In accordance with CPSES TS 6.8.3.e.4 and 6 8.3.e.5 the dose or dose comm!tment to a MEMBER OF THE PUBLIC from radioactive mhterials in liquid
. effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.13) t
.shall be limited: j
-r
- a. During any calendar quarter to less than or equal to 1.5 mrems to tne- j 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. .
tody and to less than or equal to 10 mrems to any organ, i 3 APPLICABILITY.: At all times. , l LClLQB:
.a. With the calculated dose from the release of radioactive materials in l~ liquid effluents exceeding any of the above limits, prepare and submit
.to the Commission within 30 days, pursuant to Specification 6.9.2, a
~
1 Special Report that identifies the cause(s) for exceeding the' limit (s) and defines the corrective actions that have been taken to reduce-the releases and the proposed corrective actions to.be taken'to assure j that subsequent releases will be in compliance with the above limits. 1 This Special Report shall also include:-(1) the results of ' radiological analyses of the drinking water tource, and (2) the ' radiological impact on finished drinking water supplies'with regard to-the requirements' of 40 CFR Part al. Safe Drinking Water. Act. 1 h
- b. The provisions of Controls 3.0.3 and 3.0.4 are not: applicable.
SURVEILLANCE RE0VIREMENTS _ l' 4.11.1.2 Culmulative dose contributions from liquid effluents for the current calendar quarter end the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per
- 31. days.
l l REV. O COMANCHE PEAK - UNIT 1 I 3/4-21 3/89 1
RADIOACTIVE EFFLUENTS LIOUID RADWASTE TREATMENT SYSTEM-CONTROLS l 3.11.1.3 In accordance with CPSES TS 6.8.3.e.6, the Liquid Radwaste Treatment System.shall be OPERABLE and appropriate portions.of the system shall' be used - to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to 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.
't ACTION:
l-L a. With radioactive liquid waste being discharged without treatment ano in excess of the above limits and any portion of the Liquid Radwaste t Treatment System not in operation, prepare and submit to the ' Commission within 30 days, pursuant to Specification 6.9.2, a Special- ' Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without' treatment, identification of any-inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE' status, and
- 3. Summary description of action (s)'taken to prevent a recurrence,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
i 198HJLLANCE REOUIREMENTS 4-.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Liquid Radwaste Treatment Systems Le are not being fully utilized. 4.11.1.3.2 The installed-Liquid Radwaste Treatment System shall be considered E OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. L I. i REV. 1 COMANCHE PEAK - UNIT 1 I 3/4-22 8/89 l l l l
- RADIOACTIVE E7rLUENTS
} ' EVAPORATION POND CONTROLS' '
3.11.1.4 The quantity of radioactive material contained in the evaporation pond shall-be. limited.by the following expression: EE1*I y J. ej < 1,o , excluding tritium, dissolved or entrained noble' gases, and radionuclides with ~ less than an 8 day half life, where: , Aj = pond inventory limit for single radionuclide "j" (Curies), l Cj = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j" (microcuries/ml), V= design volume of liquid and slurry in' the pond (gallons),:and 254 = cc,nversion unit (microcuries/ Curie per milliliter /gallen). 1 APPLICABILITY: At all times. ACTION: a. With the cuantity of radioactive material in the evaporation pond 2 exceeding the above limit, immediately suspend all. additions of-radioactive material to the pond,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEllt, :E REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each batch of slurry (used powdex resin) to be transferred to the evkporation pond s' hall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to the evaporation pond shall be limited by the expression: o UCi/gm i < cuooe ' R cygn where:- Qj = concentration of radioactive materials (microCuries/gm) 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. Estimates of the Sr 89 and Sr-;0 batch concentration shall be included based on the most recent quarterly composite analysis, t REV. 2 COMANCHE PEAK - UNIT 1 I 3/4-22a 11/89 t l
" ~
.u , . , ,, t
,, ~ -
_i4^ 3 v RADIOACT2VE EFFLUENTS
;,EVAPORATIQ G g '
SURVEILLANCE REOUIREMENTS (Continued) o-l ': P Cj = 10 CFR 20,-Appendix B, Table II, Column 2. concentration for single radionuclide "j" (microCuries/ milliliter), and 2 4 R= Slurry volume to resin weight ratio (ml/gm) ' t i i REV. 2 COMANCHE PEAX - UNIT 1 I 3/4-22b 11/89 l t
,n. -
1 RADIOACTIVE EFFLUENTS I
,.1 3/4.11.2 GASEOUS EFFLUENTS I DOSE RATE 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 i areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to-the following: 1
- a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and
- b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides 1 in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY: At all times. ACTION- .i 1 l
-(a) With the dose rate (s) exceeding the above limits, immediately restore the '
release rate to within the above limits (s). (b). The provisions of Controls 3.0.3 and 3.0.4 are not applicable, SVRVEILLANCE RE0VIREMENTS -
~
4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be I determined to be within the above limits in accordance with the methodology and parameters in the ODCH. . l 4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all-radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall' be determined to be within the above limits in accordance the methodology and parameters in the ODCM by obtaining i representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2
., 1 REV. 0 l COMANCHE PEAK - UNIT 1 I 3/4-23 3/89 l
l- :
e-o TABLE 4.11-2 g E Radioactive Gaseous Waste Sampling and Analysis Program (*) x m o MINIMUM SAMPLING
;K GASEOUS RELEASE TYPE FREQUENCY ANALYSIS TYPE OF LOWER LIMIT OF--
PREQUENCT
' ACTIVITY ANALYSIS DETECTION spC1/el) (LLD)(I)'
C
- l. Waste Gas Storage P
, Tank P
- Each Tank Each Tank ~
2. Crab Sample Principal Camma Emitters (2) lx10
*~* Containment Purge P or Vent P Each Release (3) Each Release (3)-
Crab Sample Principal Comma Emitters (2) lx10
~
M H-3 (oxide) lx10 3. ' Plant vent M(3), (4). (5) Principal Ca m Emitters (2) lx10 Grab Sample
- M(3) H-3 (oxide) ~ '
w lx10 Continuoue(6)-
} .
U(7) Radtolodine 1-131 ~ lx10
$ Adoorber Continuoue(6) W(7)
Particulate Principal Ca m Emitters (2) lxlO -I' Sample Continuous'6) M Gross Alpha Composite Par- Ix10'II ticulate Sample Continuous (6) Q co y Composite Par- Sr-89. Sr-90 lx10~ M to - ticulate Sampie
- Noble Cas **
Continuous (6) Beta or Casmaa Noble Cas ' lx10 l-
- Table notations next page
**This sample is continuously analyzed by a radiat ion monitor i
.._ . _- . ._ ,2._.-. _ .
, TABLE 4.11-2 (Continued)
TABLE NOTATIONS f (1) The LLD is defined, for purposes of these specifications as the'smhilest concentration of. radioactive material in a sample that will yield e 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 radicchemical separation: LLD = E V 2.22 x 10 6 . y , exp (-Aat) Where: LLD = the "a priori" lower limit of detection (microcurie per unit
-mass or volume),
s3 = the standard deviation of the background counting rate or of. tie counting rate of a blank sample as appropriate (counts per: minute), E = the counting efficiency ~ (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicabis, A=t _(secgeradioactivedecayconstantfortheparticularradionuclide
),and at a the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should-be used in the calculation. It should be recognized that the LIS i: defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an A posteriori (after the fact) lim'it for a particular measurement. COMANCHE PEAK - UNIT 1 I 3/4-25 9
TABLE 4.11-2 (Continued) TABLE NOTATIONS (Continued 1 (2) The principal gamma emitters for which the LLO spec.fication 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 of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4, in the format outlined in Regulatory -.uide 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 within a 1-hour period. This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical Specification 4.4.7 shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. (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 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 sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER 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 factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. REV. O COMANCHE PEAK - UNIT 1 I 3/4-26 3 89
1 RADIOACTIVE EFFLUENTS 0 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: !i
- 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 eo al to 10 mrads for gamma radiation and less than or equal to 20 mr for beta radiation.
APPLICABILITY:- At all times. ACTION i
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit-to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that-subsequent releases will be in compliance with the above limits,
- 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 and-current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31- days. 1' REV. O COMANCHE PEAK'- UNIT 1 I 3/4-27 3/89
e i
' U RADIOACTIVE EFFLUENTS- 1 h
DOSR - 10 DINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN i PAR"ICULATE FORM i CONTROLS l 3.11.2.3 In accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.9, the dose to 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 (see Figure 5.1-3) shall be limited to the.following: l
- 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. 1 ACTION:
- a. With the calculated dose from the release of Iodine-131, Iodine-133, 'l tritium, and radionuclides in particulate form with half-lives greater "
than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for i exceeding the limit and defines the corrective actions that have to be i 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 l l 4.11.2.3 Cumulative dose contributions for the current esiendar quarter and current calendar year for Iodine-131, Iodine-133,: tritium, and radionuclides ) in particulate form with half-lives greater than 8 days ~shall be determined in accordance with the metholodogy and parameters in the ODCM at least snce per 31 days.
'1 1
REV. 0 l COMANCHE PEAK - UNIT 1 I 3/4-28 3/89 L i l i i
. RADIOACTIVE EFFLUENTS 11 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 HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity' when the projected doses in 31 days due to gaseous effluent releases, 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 treatment and in excess of P.' above limits, prepare and submit to the Commission within 30 dav . aursuant to specification 6.9.2, a Special Report that includae -
.owing information:
- 1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment tc. 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 4.11.2.4.l' Doses'due to gaseous releases from each unit to areas at and beyond-the SITE B9UNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized. 4.11.2.4.2 The installed PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE- by meeting Controls 3.11.2.1 and
-3.11.2.2 or 3.11.2.3.
REV. O COMANCHE PEAK - UNIT 1 1 3/4-29 3/89
F RADI0 ACTIVE EFFLUENTS- ' 3/4.11.4 TOTAL DOSE 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 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 -
-1 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 Control 3.11.1.2a., 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a., or ..
3.ll.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to l determine whether the above limits of Control 3.11.4 have been exceeded _ If such is the case, prepare and submit to the Commission: within 30 days, pursuant to Specification 6.9.2, a Special Report that K i defines th9 corrective action to be taken to reduce subsequent L releases to prevent recurrence of exceeding the above limits and _ ! includes the schedule for achieving conformance with the above limits. ' l-This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered _by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the a cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of-40 CFR Part 190 has not already been corrected, the Special Repert-shall include a request for a variance H in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. REV. O COMANCHE PEAK - UNIT 1 I 3/4-30 3/89
, a 1
'j RADI0 ACTIVE EFFLUENTS (Contihued)- '
3/4.11.4-TOTAL DOSE SURVEILLANCE REQUIREMENTS i 4.11.4.2' Cumulative dose contributions from direct radiation from the units i and from radwaste storage tanks shall be_ determined in accordance with *.he 0 methodology and parameters in the ODCM. This requirement is applicable only 1 under. conditions- set forth in ACTION a. of Control 3.11.4. , 1 l l L t i. l.' i i.. I; 1 REV. O COMANCHE PEAK - UNIT 1 I 3/4-31 3/89 l
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINA 3/4.12.1 MONITORING PROGRAM CONTROLS 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. 1 1 APPLICABILITY:^ At all times.
)
ACTION:
- a. With the Radiological Environmental Monitoring Program not being i conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3 a description of the reason s) for not conducting recurrence, the program as re, quired and the plan for preve(nting a l
- b. With the level of radioactivity as the result of- plant effluents in an-environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission 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 effluents 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 l -
radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) reporting level (1) + concentration reporting level (2)(2) +... 1 1.0 z L When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if l the potential annual dose
- to A MEMBER OF THE PUBLIC from all 1 l
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 estimat the potential annual dose to L
L a MEMBER OF THE PUBLIC shall be indicated in this report. 1 u i l REV. O COMANCHE PEAK - UNIT 1 I 3/4-32 3/89 i
RADIOL GICAL' ENVIRONMENTAL MONITORING-1 CONTROLS ACTION (Continued) ' c.. With milk or fresh leafy vegetable samples unavailable from one 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 the ODCM. 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 ODCM, including a revised figure (s) and table for the 00CM reflecting the:
- newlocation(s).
- d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS I l L 4.12.1 The radiological environmental monitoring samples shall be collected I pursuant to Table '3.12-1 from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of ; Table 3.12-1 and tho detection capabilities required by Table 4.12-1. ' l L L t t REV. 0 CDMANCHE PEAK - UNIT 1 I 3/4 33 3/89
!.. r3 TA8LE 3.12-1 Radiological Environmental Monitoring Program S
m , NUN 8ER OF o REPRESENTATIVE ' EXPOSURE PATHWAY SANPLES AND SAMPLING AND TYPE AND FREQUENCY.. AND/OR SAMPLE SAMPLE LOCATIONS (l)
. COLLECTION FREnnEarY OF ANALYSIS I i
g 1. Direct Radiation (2) Forty routine monitoring stations Quarterly. Gamma dose quarterly either with two or more dosfeeters
~ or with one instrument for seasur-ing and recording dose rate ,
continuously. placed as follows: y An inner ring of stations. one in i each seteorological sector in the ' general area of the SITE SOUNDARY:
- An outer ring of stations. one in w each meteorological-sector in 1 the 6- to 8-ke range from the l
L site: and i The balance of the stations to be 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.
Radiolodine and Samples free five locations: Continuous sampler Particulates Radiofodine Cannister: operation with sample I-131 analysis weekly Q collection weekly.. g< Three samples free close to or more frequently the three SITE SOUNDARY 'if. required by dust Particulate Sammier: i locations, in different' loading. Gross beta radio-sectors, of the highest activity analysis calculated annual average followl filter ground-level D/0: change: 4) and ' gamma isotopic analysis (Si of composite (by ! location quarterly. \. - . - a .. . . . . . . , , - -
g" TA8tE 3.12-1 (Continued)
, Radiological Environmental Monitoring Program I
m NUMBER OF o REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING ANO TYPE AND FRE00ENCY AND/OR SAMPLE S M LE LOCATIONS (I)
. COLLECTION FREQUENCY OF ANALYSIS g
One sample free the
- vicinity of a community i
" having the highest calcu-
! lated annual average ground-level O/0: and -i One sample from a control location, as for example 15 to 30 km distant and in the least prevalent eind direction. (3) w 3. Waterborne N ,
-a. Surface Squaw Creek Reservoir (0) Nonthly composite of u Gamma isotopic anal-weekly grab samples. .ysis(5) sonthly. '
Composite for trittua analysis quarterly. Lake Granbury Nonthly composite of Gamma isotopic anal-weekly grab sample", ysis(5) eenthly. when Lake Granbury- Composite for tritfue is receiving letdown ~ analysis quarterly. free SCR. Otherwise, sonthly grab sample.(7) w :o ! Control-Brazos River' Nonthly Gamma isotopic anal- '
. upstream of Lake Granbury ysis(5) sonthly.
Composite for tritium analysis quarteriv.
- b. Ground Samples from tuo sources Guarterly Gamma isotopic (5) if itkely to be'affected(8). and tritium analysis >
quarterly;
- _. . ._ - - ..-:..,... . _ _ . , _ . . . _ . _. . . _ , - m. _._... .
n L h TABLE 3.12-1 (Continued) g Radiological Environmental Monitoring Progree
- r "U
NUNSER OF m REPRESENTATIVE t
) EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY
, AND/0R SAMPLE' SAMPLE LOCATIONS (l) C0rarCTION FREQUENCY OF ANALYSIS E 3. Waterborne (Continued)
--4 i
- c. Orinking One sample from Squaw Creek Composite of weekly I-131 analysis of Reservoir. grab samples over-. each composite sample _-
! .2-week period when when the dose calcu-I-131 analysis is lated for the con-performed: eenthly sumption of the water composite of weekly is greater than 1 aren grab samples other- per year (9) . Gross ;
~ wise. beta and games iso- '
y topic analyses (5) ; y monthly. Composite w for tritime analysis quarterly.
. i
- d. Sedteent One saarle. from downstream area Seelannually.
from with existing or potential Gamma isotopic analy-Shoreline sis (51 seafannually. recreational value. ,
- 4. Ingestion
- a. Milk' Samples free oliking animals in- Seafsonthly when Gamma isotopic (5) three locations within 5 km animals are on and I-131 analysis distance having the highest dose pasture: eenthly seafsonthly when o potential. If there are none, at other times.
g e. sample free oliktng antaals in animals are on pas-ture: eenthly at each of three areas between 5 other times. to 8 km distant where doses are
-calculated to be greater than ,
I arem per yr.(9) One sample free ellking animals at a control location. 15 to 30 km distant and .. in the.least l direction.(3) prevalent wind- i g.--.g .4.a .- .+e 7~.- ,w. A_ . ,y,, , e , _ y _ _ _ _ _ _ _ _ _ _ _ _ _ _______,_}__ . _ _ _ , _ , _ _
s n g TABLE 3.12-1 (Continued)
> Radiological Environmental Monitoring Progree m NUMBER OF F
, REPRESENTATIVE m EXPOSURE.PATHNAY SAMPLES AND SAMPLING AND TYPE AII0 FRE0eENCY N AND/0R SAMPLE SAfrLE LOCATIONS (I) COLLECTION FRE00ElICY OF ANALYSIS' c- 4. Ingestion (Continued)
&* b.. Fish and One sample of at least two Sample seelannually. Gamma isotopic !
~
l Invertebrates recreationally toportant species analysis (5) en in vicinity of plant discharge area. edible portions. One sample of same species in areas not influenced by plant discharge. ;
- c. Food Products
- One sample of each principal class At tfee of harvest (10) Gamma isotopic
_ 'of food products from any area analysis (5) on that is irrigated by water in which edible portion. ;
- N 11guld plant wastes have been i '
i w discherged. A sample of broad leaf vegetation Monthly. when Gamma isotopic (5) I grown nearest each of two dif- available. and I-131 analyses. ferent offsite locations of i highest predicted annual average ground level SIG if alik samp11ng is not performed at all required locations. i One sample of each of the sieller Monthly, when (5) Gamma-isotopic broad leaf vegetation grown 15 to available. and I-131 analyses. co :o 30 km distant in the least pre-D ".c valent wind direction (3) if milk. sampling is not performed at all
~
required locations. Reports from 3 additional airborne radiofodiae sample locations may be supplemented for broad leaf ~ vegetation samples.
-t
_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___________________._______________.____.________m___._
TABLE 3.12-1 (Continued) TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where >ertinent, shall be provided for each and every sample location in Ta)1e 3.12-1 in a table i and figure (s in the ODCM. Refer to NUREG-0133. " Preparation of ' E Radiological) Effluent Technical Specifications for Nuclear Power F s October 1978, and to Radiological Assessment Branch Technical Position, $ Revision 1, November 1979. Deviations are permitted from the required , sampling schedule if specimens are unobtainable due to circumstances such as hazardous coWH. ions, seasonal unavailability, and malfunction of automatic samp1 By Squipment. If specimens are unobtainable due to sampling equipmed "alfunction, effort shall be made to complete corrective action Fior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report oursuant to Control 6.9.1.3. I It is recognized that, at times, it may not )e possible or practicable to continue to obtain samples of the media of choice at the most desired
-location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in questica and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Control L- 6.14, submit as a part of or concurrent with the next Semiannual Radioactive Effluent Release Report a complete legible copy of the ODCM l
including a revised figure (s) and table for the ODCM 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 (Tt.D) is considered to be one_ phosphor; two i or more phosphors in a packet are considered as two or more dosimeters. L Film badges shall not be used as' dosimeters for measuring direct L 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 m distance and wind direction criteria, other sites that provide valid > background data may be substituted. 1 (4) Airborne particulate sample filters shall be analyzed for gross beta L radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than_10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. REV. 1 COMANCHE PEAK - UNIT 1 I 3/4-38 8/89
\
v: TABLE 3/12-1 (Continued)' t TABLE NOTATIONS (Continued) (5) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents j 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 j significant influence of the discharge. . l (7) Lake Granbury shall be sampled near the letdown discharge and at a ! distance beyond significant influence of the discharge. l (8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or i recharge properties are suitable for contamination. (9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCH. (10) If harvest occurs more than once a year, sampling shall be performed
, during each discrete harvest. If harvest occurs continuously, stmpling shall be monthly. Attention shall be paid to including samples of-tuberous and root food products.
i 1 REV 0 COMANCHE PEAK - UNIT 1 I 3/4-39 3/89 L
I ! O a M TABLE 3.12-2 o Reporting Levels for Radioactivity Concentrations in Environmental Samples
- MATER AIRBORNE PARTICULATE FISH MIII FOOD PRODUCTS g ANALYSIS (pC1/1) OR CASES (pC1/e') (pC1/kg wet) (pC1/1) -(pC1/kg wet)
Z H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 l Co-58 1,000 30,000
~
Co-60 300 10,000 M i In-65 300 20,000 l o Zr-Nb-95 400 I-131 2 0.9 3 106 Cs-134 30 10 1,000 60 1,000' Cs-137 50 20 2.000 ~ 70 2,000 Ba-La-140 200 -300 D"Q (*) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water patinray exists, a value of . So - 30,000 pC1/1 may be used. o (**) If no drinking water pathway exists, a value of 20 pCi/l may be used.
.g - '
+ -
O n x rn TABLE 4.12-1 ' gj Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) E WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS - SEDIlE3tT "3 ANALYSIS (pC1/1) OR GASES (pC1/e') (pC1/kg, wet) (pC1/1) (pC1/kg wet) (pC1/kg. dry) Cross Beta 4 0.01 H-3 2000* Mn-54 15 130 Fe-59 30 260 w
]; Co-58,60 15 130
$ Zn-65 30 260 Zr-Nb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150' Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 dY rE op .c
,* If no drinking water pathway exists, a value of 3000 pCL/1 any be used.
C3 **If no drinking water pathway exists, a valve of 15 pC1/1 may be used.-
l
.- t : +
TABLE 4.12-1-(Continued) i i TABLE NOTATIONS-t
.(1) The: list does not mean that only these nuclides are to be considered. '
' Other peaks that are identifiable, together with those of the above nuclides, shall also be-analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.
(2) Required detection capabilities for thermoluminescent dosimeters used for
'1 environmental measurements shall be in accordance with the '
recommendations of Regulatory Guide 4.13.
,s (3) The LLD is defined, for purposes of these specifications, as the smallest 4 concentrations of radioactive material in a sample that will yield a net-count, above system background, that will be detected with 95%
s probability with only a 5% probability of falsely concluding that a- blank j observation represents a "real' signal. 1, 4.66 sh LLO = E V exp (' Aot) 2.22 Where: LLD-= the "a priori" lower limit of detection (picocurie per unit mass or i volume). sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), l 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A=t
-(secgeradioactivedecayconstantfortheparticularradionuclide
),and at = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and L\t should be used in the calculation. COMANCHE PEAK - UNIT 1 I 3/4-42 REV. 0 3/89 L 1 l
.I
., 1 TABLt 4.12-1 (Continued)
TABLE NOTATIONS (Continued) 1 (3) Continued It should be recogniz' ed that' the LLD is defined as an 't oriori (bet:re' i the fact)' limit representing the capability of a measurement system and l not as an 1 oosteriori (after the fact) limit for a particular measurecant. Analyses shall be performed in such a manner that the -) stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of i interfering nuclides, or other uncontrollable circumstances may renders these LLD's unachievable. In such cases, the contributing. factors shall be identified and described in the Annual Radiological Environmental j Operating Report pursuant to Control 6.9.1.3. "
.1 f
L i t i G I f! COMANCHE PL'AK - UNIT I I 3/4-43 3 9
RADIOLOGICAL' ENVIRONMENTAL MONITORING 3/4.12.2 -LAND USE CENSUS CONTROLS' , 3.12.2 In accordance with CPSES TS b.c...f.2, a Land Use Census shall be i conducted'and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the ; nearest residence, and the nearest garden
- of greater than 50 m2 (500 ft2 )- '
producing broad-leaf vegetation. APPLICABILITY: At all times. ACTION: '
- a. With a Land Use Census identifying a location (s) that yieldi a l calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4, ,
identify the new location (s) in the next Semiannual Radioactive Effluent Release Report. >
- b. With a Land Use Census ideni.lfying a location (s) that yields a [
calculated dose or dose commitment (via the same exposure pathway) 20% ' greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) : within.30 days, to the Radiological Environmental Monitoring Program t given in Part II of 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 or concurrent with the next Semiannual Radioactive Effluent Release Report a complete, legible copy of the entire ODCM including a revised figure (s) and table (s) for the 0DCM reflecting the new location (s), l
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable, SURVEILLANCE-REOUIREMENTS '
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 results, such as by a door-to-door survey, aerial survey, provide the best or by consulting local agriculture authorities. The results of the Land use Census shall be t 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 B0UNDARY 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, REV. 1 COMANCHE PEAX - UNIT 1 I 3/4-44 8/89 l -.
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{ RADIOLOGICAL ENVIRONMENTAL' MONITORING 3/412.3 INTERLABORATORY COMPARISON 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. I APPLICABILITY: At'all times. ACTION: l
- a. With analyses not being performed as required above, report the -
corrective actions taken to prevent.a recurrence to the Commission in the Annual Radiological-Environmental Operating Report pursuant to Control 6.9.1.3.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS l i1 4.12.3 The Interlaboratory Comparison Program shall- be des'cribed in the 00CM. I A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual . Radiological Environmental-Operating Report pursuant to Control 6.9.1.3. , l-r 1 L l w l 4 i i 4
-REV. O COMANCHE PEAK - UNIT 1 I 3/4-45 3/89
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INSTRUMENTATION BASES _.
.3/4.3.3.4 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable; the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted. in accordance with the methodology and parameters in.the ODCM 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 t The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. .The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64.of Appendix A to 10 CFR > Part 50. 3/4.3.3.6 METEOROLOGICAL INSTRUMENTATION l The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential 4 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 r proposed Revision 1 to Regulatory Guide 1.23, "0nsite Meteorological '
- Programs," April 1986.
i REV. O COMANCHE PEAK - UNIT 1 I B 3/4-1 3/89 L__________-_________________________ - .
1 l INSTRUMENTATION ] BASES j 3/4.7.15.50VRCE CONTAMINATION The limitations on' removable contamination for sources requiring leak i testing, includina alpha eritters, 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. Sealed sources are classified into three groups according'to their use, with Surveillance Requirements commensurate with the probability of damage to -l a source in that group. Those sources which'are frequently handled are- : required to be tested more often than those which are-not. Sealed source, , 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 ttsted unless they are removed from the shielded mechanism. v
-i i
s REV. O COMANCHE PEAK - U.11T 1 I B 3/4-2 3/89
k i 3/4.11 RADIOACTIVE EFFLUEN,.JJ BASES l 3/4.11.1- LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION-This control is provided to ensure that the concentration of radioactive-materials released in liquid waste effluents to UNRESTRICTED AREAS will be , less than the concentration levels specified in 10CFR20, Appendix B, Table II, l Column 2. This limitation provides additional assurance that the levels of , I radioactive materials in bodies of water in UNRESTRICTED AREAS will result in. j exposuras within: (1) the Section II.A design objectives of 10CFR50, Appendix ! I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to l the population. The concentration limit for dissolved or entrained noble !' gases is based upon the assumption that Xe 135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration i in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. This control applies to the release of radioactive materials in liquid effluents from all units at the site. o The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). ,' Detailed discussion of the LLD and other detection limits can be found in i ' Currie, L.A., " Lower Limit of Detection Definitien and Elaboration of a i Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR 4007 (September 1984), and in the HASL Procedures Manual, HASL-300. 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III.A and IV.A of 10CFR50, Appendix I. The Control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide th? -! 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-
- j. material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is L reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected~by plant operations, there is-reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculation methodology and parameters in the 00CM implement the requirments in Section III.A of Appendix
! that conf 0,mance with the guides of Apper.Jix I De shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER '
0F THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Efflunnts for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision a 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Olspersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,'" April 1977.
REV. O COMANCHE PEAK - UNIT 1 I B 3/4-3 3/89 P- - _ -___-_ --aw v e- * ' ' '
lgle iiii 8 RADI0 ACTIVE EFFLUENTS I RASES QQ11 (Continued) This control applies to the release of radioactive materials in liquid effluents from each unit at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportional among the units sharing that system. 3/4.11.1.3 L1001D 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 !!.D of Appendix ! 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 !!.A of Appendix 1, 10 CFR Part 50 for liquid effluents. This control applies to the release of radioactive materials in liquid efflua its from each unit at the site. For units with shared Radwaste Systems, , the liquid effluents from the shared system are to be proportioned among the j units sharing that system. = 3/4.11.1.4 EVAPORATION POND The inventory limits of the evaporation pond (EP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in Control 3.11.1.4 assumes the pond inventoQ is uniformly mixed, that the pond is located in an unrestricted area as defined in 10 CFR Part 20 and that the concentration limit in Note 1 to Appendix B of 10 CFR Part 20 applies. The batch limits of slurry to the EP assure that radioactive material in the slurry transferred to the EP are "as. low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of slurry will be transferred to the EP unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than the ratio of the 10 CFR Part 50 Appendix 1, Section !!.A. total body level to the 10 CFR 20.105(a), whole body dose limitation, or that: I l 2." " soo womey
- aoos I c, REV. 2
' COMANCHE PEAK UNIT 1 I B 3/4 4 11/89
RADICACTIVE EULUENTS BASES EVAPORATION POND (Continued) where: l cj = radioactive slurry concentration for radienuclide "j" ent;iing the UNRESTRICTED AREA EP, in microcuries/ milliliter, *r.J l 1 Cj = 10 CFR 20. Appendix B, Table II, Column 2, concentration for l single radionuclide "j", in microcuries/ milliliter. - - The average concentration of radioactive materials in a particular batch ~ of resin slurry released to the EP is dependent upon the slurry volume to resin weight ratio. Additionally, the wet drained slurry density is approximately 1 gm/ml and the absorption characteristics for gamma radiation are essentially that of water. Therefore, I .*.! - I < noon I c, i c, e wom> , L f * **** ' R j i where the terms are defined in Control 4.11.1.4. i ' The batch limits provide assurance that activity input to the EP will be i minimized, and a means of identifying that the radioactive material released ! is within the inventory limitation of Control 3.11.1.4. 1
- REV. 2 COMANCHE PEAK UNIT 1 I B 3/4 5 11/89 l
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i RADIOACTIVE EFrLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.' 00SE RATE This control is provided to ensure that the dose at any time at and l beyond the SITE BOUNDARY from gaseous effluents from all units on the site ! will be within the annual dose limits of 10CFR20 to UNRESTRICTED AREAS. The i annual 10CFR20, dose limits are Appendix the doses B, Table associated
!!, Column with the concentrations of
- 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Table II of 10CFR20, Appendix B (10CFR 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be '
sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The methodology for calculating doses for such MEMBERS OF TdE PUBLIC shall be given in the 00CM. The specified release rate limits restrict, at.all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ 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. This control applies to the release of radioac.tive materials in gaseous effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Dctailed discussion of the LLDs and other detection limits can be found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements." > NUREG/CR 4007 (September 1984), and in the HASL Procedures Manual, HASL 300, l l l l REV. O COMANCHE PEAK - UNIT I I B 3/4 6 3/89
RADIDACTIVE EULUENTS BASES 3/4.11.2.2 00SE - NOBLE GASES This control is provided to implement the requirements of Sactions II.B, ! Ill.A and IV.A of 10CFR50, Appendix 1. forth in Section I.B of Appendix I. TheThe control implements the guides set ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of the radioactive noble gases in gaseous 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 ar.d Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors," Revision 1. July 1977, 1 The ODCM ecuations provided for determining the air doses at and beyond the l SITE 30VNDARY are based upon the historical average atmospheric conditions. This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are 1 proportioned among the units sharing that system, i l e REV. 1 COMANCHE PEAK - UNIT 1 I B 3/4-7 8/89
i RADIOACTIVE EFFLUENTS' BASES 3/4.11.2.3 DOSE IN PART. CULATE - 10 DINE 131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL PORM ! This control is provided to implement the requirements of Sections !!.C,
!!!.A, and IV.A of 10CFR50, Appendix 1. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The 00CM calculational methods specified in the '
Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix ! 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 00CM calculational methodology and parameters for calculating the doses due to the actual release rates of the : subject materials are consistent with the methodology provided in Regulatory ' Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, + Appendix 1," Revision 1. October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in , Routine Releases from Light Water Cooled Reactors," Revision 1. July 1977. These equations also provide for determining the actual doses based upon'the historical average atmospheric conditions. The release rate specification for lodine-131, lodine 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 calculations were: individual inhalation of airborne radionucludes, (2) deposition of(1 ) 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. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. REV. O COMANCHE PEAK UNIT 1 1 B 3/4 8 3/89
1 DAD 10 ACTIVE EFrLUENTS BASES ' i 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY 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 protions 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, i General Design Criterion 60 of Appendix 4 to 10 CFR Part 50 and the design objectives given in Section 11.0 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 oojectives set forth in Sections !!.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents. This control applies to the release of radioactive materials in gaseous efflueets from each unit at the site. For units with shared Radwaste 1reatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. I REV. O COM.ANCHE PEAK UNIT 1 I B 3/4 9 3/89 1
PaDf0aCT7VE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE 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 releasew of radioactivity and to radiation from uranium fuel cycle sources exc9ed ?5 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 fo9r 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 rear. tors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radious of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405(c), 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 far dose limitation of 10-CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is 4 not considered a MEMBER OF THE PUBLIC during any period in which he/she is l engaged in carrying out any operation that is part of the nuclear fuel cycle. : l . 1 i COMANCHE PEAK UNIT 1 I B 3/4 10 3
f 3/4.12 DADf0 LOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PRCGRAM The Radiological Environmental Monitoring Program required by this l control provides representative measurements of radiation and of radioactive ; materials in those exposure pathways and for those radionuclides that lead to the fromhighest potential the plant radiation exposure of MEMBERS OF THE PUBLIC resulting operation. This monitoring program implements Section IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the Radiological Ef fluent 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 i provided by the Radiological Assessment Branch Technical Position on ' Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program commercial operation. will be effective for at least the first 3 years of , Following this period, program changes may be initiated ; based on operational experience. The requireu detection capabilities for environmental sample analyses are tatulated in tern af the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements i:, industrial laboratories, it should be recognized that the LLO is defined as an A ori.ori (before the fact) limit representing the capability of a measurement system and not as an A costeriori (after the fact) limit for a particular measurement. ' Detailed discussion of the LLD, and other detection limits, can Se found : in Currie, L. A.,
" Lower Limit of Detection: Cefinition and Elaborat.on 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 i 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 ODCM 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 ! 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 and cabbage), and (2) a vegetation yield of 2 kg/ms. REV. O COMANCHE PEAK - UNIT 1 I B 3/4 11 3/S9
RADIOLOGICat ENVID0 0 ental 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 ! to 10 CFR Part 50. COMANCHE riAK - UNIT 1 1 B 3/4 12 9 v
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1 5.0 DESIGN FEATURES MA) DEFLNING UNRESTRICTED ARI?AS AND EXCLUSION AREA BOUN9ARV FOR RA)l0AC"IVE GASEOUS AND LIOU D EFFLUENTS S.I.3 Information regarding radioactiv9 gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.13. The oefinition of UNRESTRICTED AREA used in implementing these Controls has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the Exclusion-(fenced) Area Boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a. REV. O COMANCHE PEAK - UNIT 1 1 5-1 3/89 l
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5 l i l L SECTION 6.0 ADMINISTRATIVE CONTROLS ! i i l 160 \ l l
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.3 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality and shall include copies of reports of the preoperational Radiological Environmental Monitoring Program of the unit for at least two years prior to initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretions, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies and with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. 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 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 the table and figures in 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 1979. In the event that some individual results are not available for inclusion with the report, the report i shall be submitted noting and explaining the reasons for the missing results. The report.missing data shall be submitted as soon as possible in a supplementary 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 al? 4 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 J 4.12-1 was not achievable. A single submittal may be made for a multiple unit station. ' One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. REV. O COMANCHE PEAK UNIT 1 I 6-1 3/89
. . _ _ . . _ . . - . _ _ . _ . _ ._m~ _ m _ _ . _ . , _ _.
i i ADMINISTRATIVE CONTROLS ! SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the ;
operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period " of the first report shall begin with the date of initial criticality. The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radicactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, ,
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1. June 1974, with data 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). ' The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), , or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents i released from the unit or station during the previous calendar year. This ' same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activitiesinsidetheSITEBOUNDARY(Figure 5.13)durin All assumptions used in making these assessments, i.e.,specific g the report period. activity, exposure time, and location, shali be included in these reports. Historical average meteorological conditior.s or the meteorological conditions concurrent with the time of release of raiioactive materials in gaseous effluents. as ' determined by sampling freque,ncy and measurement, shall be used for determining the gaseous p toway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the - 0FFSITE DOSE CALCULATION MANUAL (ODCM). A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. In lieu of submission with the Semiannual 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. REV. O COMANCHE PEAK - UNIT 1 162 3/89
ADMINISTRAilVE CONTROLS 1EMIANNEAL RAD 10 ACTIVE EFFLUENT RELEASE REPORT The Semiannual Radioactive Effluent Release Report to be submitted within 60 days After January 1 of each year 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 sourcan, including doses from primary effluent pathways and direct radiation, for the previous 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. 1, October 1977. The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Semiannual Radioactive Effluent Release Reports shall include. a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2. The Semiannual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of itquid 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.
.l 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
- 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 radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the SORC and the approval of the Vice President, Nuclear Operations.
l REV. 1 COMANCHE PEAK - UNIT 1 I63 8/89 ,
ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) feontinued)
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was mads. Each chan identified by markings in the margin of the affected pages,ge shall be clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
COMANCHE PEAK - UNIT 1 164 3i
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t w i PART !! CALCULATIONAL METHODOLOGIES i 4 l
1 1 l SECTION 1.0 LIQUID EFFLUENTS The Comanche Peak Steam Electric Station, Units 1 and 2, is located on the Squaw Creek Reservoir which serves as the point of supply and discharge for the plant circulating water. Liquid releases are made via the Circulating Water Discharge Canal. Discharge pathways for the liquid radwaste sources are shown in Figure 1.1. Although no significant releases of radioactivity are expected from the Station Service Water System, this effluent pathway is monitored as a precautionary measure. The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by GA Technologies. Since all DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uti/ml). The conversion factor for detector output from counts per minute to uCi/ml is determined during the calibration of each monitor and is input into the data base for the monitor microprocessor. , 1.1 GENERAL PETHODOLOGY FOR DETERMINING LIOUID EFFLUENT MONITOR SETPOI Normal liquid releases from the radwaste system will be batch type releases and will originate from the laundry holdup tanks and waste i monitor tanks and terminate in Squaw Creek Reservoir. To ensure such ' discharges do not exceed the limits of 10CFR20, Appendix B Table !!, Cciumn 2 at the release point to the unrestricted area, as specified in
- Radiological Effluent Control 3/4.11.1.1, an in line radiation detector (XRE 5253) monitors discharges to the circulating water discharge canal. XRV-5253 is the isolation valve controlled by detector XRE-5253. The isolation valve shuts automatically if the detector alarms or is placed out of service. The methodology for determining the setpoint for detector XRE-5253 is given in the following sections. It should be noted that the liquid effluent monitor setpoint values as determined using the methodology from the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required if the existing setpoint level cor.esponds to a lower value than the calculated value. Setpoints may be established at values lower than the calculated values, if desired.
11 1-1 Rev. 0 l 3/89
- - - - - - . _ - - - - - - - . . - - - . - - - - - _ _ _ _ - - - - - - _ _ _ - - . - - - - - - - - - - - - --, -r - - - , -- -
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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.
1.1.1 Isotonic Concentration of the Waste Tank Determine the isotopic concentration of the waste tank to be released: ICg i
=I C, + (C, + C, + C, + C,,) [tq. 1-1) ,
3 Where: IC t = Sum of the concentrations of each radionuclide, i, in the waste tank (uCi/ml) I C, = Sum of the concentrations of each measured gamma s emitter, g, (uCi/ml) as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. . Ca = concentration of alpha emitters as measured in the most recent monthly composite sample (uC1/ml) required by Radiological Effluent Control 3/4.11.1.1 Table 4.11 1. (Sample analyzed for gross alpha only) Cs = concentration of 89S r and 90S r as measured in the most recent quarterly composite sample (uCi/ml) required by Radiological. Effluent Control 3/4.11.1.1, - Table 4.11 1. Ct = concentration of 3H as measured in the most recent monthly composite sample (uci/ml) required by Radiological Effluent Control 3/4.11.1.1 Table 4.11 1. ' Ce F = concentration of 55F e as measured in the most recent quarterly composite sample (uC1/ml) required by . Radiological Effluent Control 3/4.11.1.1 Table 4.11-1. 1.1.2 Maximum Effluent Flow Rate (f) The effluent discharge rate is determined from the number of radwaste system pumps running and their capacity. The pumps that can be ( utilized to discharge liquid effluents to the circulating water discharge canal consist of the following: II l-2 Rev, 1 l 8/89 L
Radwaste System Pumos laundry Holdup and Monitor Tank Pump fl - 100 gpm Laundry Holdup and Monitor Tank Pump #2 - 100 gpm Waste Monitor Tank Pump #1 - 100 gpm Waste Monitor Tank Pump #2 - 100 gpm Co Current Waste System Pumos Waste Water Holdup Tank Pump #1 200 gpm Waste Water Holdup Tank Pump #2 200 gpm For radiation monitor setpoint calculations, the maximum effluent flow rate associated with the tank to be discharged is used. Therefore, no setpoint is required for the flow measuring device for the effluent release line. 1.1.3 Dilution of Liouid Effluents Due to Circulatina Water Flow (F) Since liquid effluent from the radwaste treatment system is mixed with circulating water prior to being discharged to Squaw Creek Reservoir, the setpoint for detector XRE 5253 is a function of the circulating water flow rate. The maximum circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll Rand pump curves (Fig.1.3) which indicate a flow rate per pump of 275,000 gpm. The actual circulating water dilution flow is given by: F(diluting flow) = (275,000 gpm/ pump) x (# of pumps) x SF (Eq.12) Where: SF = Safety Factor of (.9). This compensates for flow fluctuations from the rate predicted by the circulating waterpumpcurves(Fig.1.3). 1113 Rev. 1 8/89
As an additional consideration, the available dilution flow for any ! release may be corrected to allow for simultaneous releases from the Radwaste Processing System and the Co Current Waste System (i.e., a Waste Water Holdup Tank and a radwaste system tank may be released
- simultaneously). For simultaneous releases, the available dilution flow for any release is reduced by the required dilution flow for any other concurrent release.
1.1.4 Actual Dilution Factor (ADF) ADF is the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate. ' ADF = (f + F)/f (Eq.1-3) Where: f = effluent flow rate (gpm) > F = (275,000 gpm/ pump) x (# of pumps) x SF (Eq.1-2] NOTE: If radioactivity is detected in the Reservoir, an adjusted circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See section 1.1.6 for the calculation of F' (Eq.1-6). Also, if simultaneous releases are occurring, the available dilution flow shall be reduced by the i required dilution flow for any other concurrent release. 1.1.5 Reauired Dilution Factor (RDF) l The required dilution factor ensures that the maximum permissible concentrations expressed in 10CFR20, Appendix B. Table II, Column 2*, and a total concentration of dissolved or entrained noble gases of l 2 x 10*4 uCi/mi are not exceeded during a discharge. The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded, i
- HPCs listed in 10CFR20-give values for each isotops in both a soluble and insoluble form. The lowest value for each isotope should be used. A value of 2 x 10 4 uti/mi for dissolved or entrained noble gases shall be used.
11 1-4 Rev. 1
. 8/89
i W = ( r (C1 /eCg )) x sr 1 l i
= (t (C,/MPC ) + (C,/MPC, + C,/MPC, g + C /MPC, i
+ C,,/ecy )) x sr [tq. 1-4) l Where: MPCj* = Maximum Permissible Concentration of Radionuclide i SF = Safety Factor of 2. I All other variables and subscripts are previously defined.
NOTE: If RDF is less than 1, the tank effluent meets discharge ) limits without dilution. For conservatism, set RDF equal to 1.0. The maximum value for the high alarm + l setpoint for detector XRE 5253 would then be calculated in accordance with the equation for C1 w in the following } l section, l l 3 1 l L
- See footnote on page II 1 4.
II 1-4a Rev. 1 8/89
1.1.6 Ueoer Seteo9nt limit for Detector XRE-5253 C [Eq. 1-5) g = (ADT/RDT) x g C g Wheca: C1 w - The liquid waste effluent monitor alarm setpoint. This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC level releases (uC1/ml). All other variables are as previously defined. As a further consideration, the reservoir into which the diluted radwaste 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: F' = F (1 - { (C{/MPCg )) (gq , 1 6] Where: F' = Adjusted Circulating Water Flow Rate C'i - Concentration of radionuclide i in the Reservoir (uti/ml) as 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 circulating water intake structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual. MPCi * = Maximum Permissible Concentration of Radionuclide i F = (275,000 gpm/ pump) x (# of pumps) x SF NOTE: If C'i is less than LLD then F' = F and no adjusted flow rate need be considered in the calculation of ADF. The LLD values used for this determination shall be the LLD valves for water given in Radiological Effluent Control 3/4.12.1 Table 4.12-1.
*see footnote on page II 1 4 II l-5 Rev. 0 3/89
When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be +6 sse referenced in Radiological Effluent Control 3/4.11.1.1, T.n'r '
- 1. Table Notation 2. Figure 1.2 is a representative energy
- m. response for the RD 33 type detector used in XRE 5253. This
.. .e illuttrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. In fact between 137 C s and 60C0, the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations. However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required.
!! l-6 Rev. 0 1
3/89
1.2 DOSE CALCULATION FOR L1001D EFFLUENTS For implementation of Radiological Effluent Control 3/4.11.1.2,the dose commitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose commitments will be maintained for each calendar quarter and each calendar year. 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 j calculated using the following equation: ' DT*IDk
- ID(1***I n (Eq. 1-7) k a '
I Where: DT = the dose ecmmitment to the total body or any organ i due to all releases during the desired time interval (mrem). Ok the dose commitment received by the total body or any organ during the duration of batch release r k(mrem). The equation for calculating Dk is given in Section 1.2.1 (Eq. 1 8). 0(lake)m - the dose commitment received by the total body or any organ during the desired time period, m. (normallym=31 days)duetothebuildupinthe lake of previously discharged radionuclides. The equation for calculating D(lake)m is given in Section 1.2.2 (Eq. 1-11). 1.2.1 Calculation of Dose Due to a Batch Release The dose comitment to the total body or any organ due to a batch release will be calculated using the following equation: ll Dk*EAhk g i t C F (Eq. 1-2] II 1-7 Rev, 0 3/89
Where: tk = the time duration of the batch release k (hrs) ' Cik = the isotopic concentration (uti/ml) of , radionuclide i found in the pre release sample for batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For 89S r, 90S r, 3 H, 55 eF and alpha emitters, the ; last measured value will be used in the dose calculation. Fk = the near field average dilution factor during a ' liquid effluent release. This is defined as the ratio of the averag' undiluted liquid effluent flow rate to the average circulating water flow rate during the release. The cerage liquid effluent flow rate is based on the actual flow past the monitor into the circulating water. Fk = avernoe undilutec' liauid effluent flow rate circulating water flow rate Aj, = the site related ingestion dose commitment factor for the total body or any organ, , for each identified gamma or beta emitter (mrem /hr oeruti/ml). Att is calculated as follows: Ah = 1.14x10$ (U,/Dy + UgBFg ) DF g (Eq. 140] > Where: 1.14x105 . unit conversion factor, Uw - adult water consumption, 730 liters /yr Ur = adult fish consumption, 21 kg/yr BFt - bioaccumulation factor for radionuclide i, in fish from Table A-1, Ref. 2 (pCi/kg per pCi/1) 11 1-8 Jev. 0 3/89
~ . - . . _ - - _ . _ ,_ _ _ _ - _ . _ _ _
r ! i DFj = adult dose conversion factor for radionuclide i, from ! Table E-11, Ref. 2 (mrom/pCi ingested) Dw - Dilution factor from the near field area within one quarter mile of l the release point to the potable water intake for the I adult water consumptioni 1.0 ) forCPSES,(unitiess) [ Calculated values for Ai r are given in Table 1.1. l : 1 1.2.2 Calculation of Dose Due to Radionuclide Builduo in the Lake The dase contribution due to buildup of previously discharged , radionuclides in the lake must be considered in the committed dose calculation only if they are detected in the water of Squaw Creek Reservoir or in fish from Squaw Creek Reservoir. The contribution to the total dose due to this builduo is i determined as follows: D(lake)m = 1.14x10-4( I DF i (C'{wU, + C'it U t))t (Eq. 1-111 l l 1 l Where: 1.14 x 10 4 = units conversion factor C'tw = concentration of radionuclide i in the reservoir as measured at the circulating water intake structure shown as location SW6 on Table 3.1 and Figure 3.1 of this manual (pCi/1) C'jf = concentration of radionuclide i in fish sampled from Squaw Creek Reservoir from location F1 on Table 3.1 and Figure 3.1 of this manual (pci/kg) t = 744 hrs (31 days) or other time period of intenast (hr) All other variables are previously defined. II l-9 Rev. 0 3/89 , 1
- 1. '. - , , - - - . - - - - , .-
~ -
t i NOTE:: This calculation is only required if activity is '! detected in water and/or fish in excess of the 1 appropriate LLD values given'in Radiological' Effluent Control 3/4.12.1, Table 4.12-1. If the measured activity in water or fish is less than the required LLD values, the concentration for ' that particular pathway is assumed to be zero. , l 1 i E i.. t i i t o 4 i i II 1-10
~
Rev. O 3/89 4 - .y - -
i
. 1.3 DOSE PROJECTIONS FOR L10VID EFFLUENTS i Radiological Effluent Control 3/4.ll.l.3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit' to VNRESTRICTED AREAS would exceed 0.06 i mrem total body or 0.2 mrem to any organt in a 31-day period. The following calculational methoc is provided for performing this dose projecticw At itast onea every 31 dayL the total dose from all liquid releases ,
for the quarter to-date will be diviried by-the number of days into the. ' quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. If this projected dose i exceeds 0.06 mrem total body or 0.2 mrem any organ,- appropriate portions of the Liquid Radwaste Treatment System shall be used to reduce radioactivity levels prior to release. 1 II l-11 Rev. 0 3/89
o _; TABLE 1.1 , SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml) 1* ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG CI-LLI H 0.00E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 C-14 3.15E+04 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 Na-24 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 ! P-32
- . 4.6?E+07 2.87E+06 1.79E+06 0.00E+00 'O.00E+00 0.00E+00 5.20E+06 Cr-51 0.00E+00 0.00E+00 1.49E+00 8.94E-01 3.29E-01 1.98E+00 3.76E+02 Mn-54 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+041
, Mn-56 0.00E+00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03 Fe-55 8.87E+02 6.13E+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 ,
Fe-59 1.40E+03 3.29E+03 1.26E+03 0.00E+00 0.00E+00 9.19E+02 1.10E+04 Co-58 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Co-60 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16E+03 Ni-63 4.19E+04 2.91E+03 1.41E+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02 Ni-65 1.70E+02 2.21E+01 1.01E+01- 0.00E+00 0.00E+00 0.00E+00 5.61E+02 Cu-64 0.00E+00 1.69E+01 7.93E+00 0.00E+00 4.26E+01 0.00E+00 1.44E+03 L Zn-65 1' 2.36E+04 7.50E+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4.73E+04- ) Zn-69 5.02E+01 9.60E+01 6.67E+00 0.00E+00 6.24E+01 0.00E+00 1.44E+01 u Br-83 0.00E+00 0.00E+00 4.38E+01 0.00E+00 0.00E+00 0.00E+00 6.30E+01 Br-84 0.00E+00 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 4.45E-04 Br-85 0.00E+00 0.00E+00 2.33E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-15 Rb-86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 Rb-88 0.00E+00 2.99E+02 1.59E+02 0.00E+00 0.00E+00 0.00E+00 4.00E-09 Rb-89 0.00E+00 1.98E+02 1.39E+02 0.00E+00 0.00E+00 0.00E+00 1.15E-11 Sr-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 II 1-12 P e .- 0 3; s9
TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/a'.) IT ISOTOPE ROSE LIVER T-BODY THYROID KIDNEY LlTNG GI-LLI Sr-90 1.18E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 Sr-91 8.79E+02 0.00E+00 3.55E+01 0.00E+00' O.00E+00 0.00E+00 4.19E+03 Sr-92 3.33E+02 0.00E+00 1.44E+01 0.00E+00 0.00E+00 0.00E+00 6.60E+03' Y-90 1.38E+00 0.00E+00 3.69E-02. 0.00E+00 0.00E+00 0.00E+00 1.46E+04 Y-91m 1.30E-02 0.00E+00 5.04E-04 0.00E+00 0.00E+00 0.00E+00 3.82E-02 Y 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 1.11E+04 Y-92 1.21E-01 0.00E+00 3.53E-03 0.00E+00 0.00E+00 0.00E+00 2.12E+03 Y-93 3.83E-01 0.00E+00 1.06E-02 0.00E+00 0.00E+00 0.00E+00 1.22E+04 Zr-95 2.77E+00 8.88E-01 6.01E-01 0.00E+00 1.39E+00 0.00E+00 2.82E+03 Zr-97 1.53E-01 3.09E-02 1.415-02 0.00E+00 -4.67E-02 0.00E+00 9.57E+03 Nb-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Mo-99 0.00E+00 4.62E+02 8.79E+01 0.00E+00 1.0$E+03 0.00E+00 1.07E+03-Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.07E-02 4.92E+01 Tc-101 3.03E-02 4.36E-02 4.28E-01 0.00E+00 7.85E-01 2.23E-02 1.31E-13 Ru-103 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00'2.31E+03 -Ru-105 1.65E+00 0.00E+00 6.51E-01 0.00E+00 2.13E+01 0.00E+00 1.01E+03 Ru-106 2.95E+02 0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E+00 1.91E+04 Ag-110m 1.42E+01 1.31E+01 7.80E+00 0.00E+00 2.58E+01 0.00E+00 5.36E+03 Te-125m 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04 Te-127m 7.05E+03 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E+04 Te-127 1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.00E+00 9.03E+03 Te-129m 1.20E+04 4.47E+03 1.89E+03 4 llE+03 5.00E+04 0.00E+00 6.03E+04 Te-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01 j II l-13 pe. o 1/89
TABLE =1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uC1/ml) it ISOTOPE' BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Te-131m 1.80E+03 8.BIE+02 7.34E+02 1.39E+03 8.92E+03 0.00E+00 8.74E+04 Te '31 2.05E+01 8.57E+00 6.47E+00 1.69E+01' 8.98E+01 0.00E+00 2.90E+00 Te-132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 1.63E+04 0.00E+00 8.02E+04-I-130 9.01E+01 2.66E+02 1.05E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 1-131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 1-132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.00E+00 1.22E+01 1-133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.00E+00 2.64E+02 I-134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01' O.00E+00 2.99E-02 1-135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.00E+00 1.56E+02' Cs-134 3.03E+05 7.21E+05 5.89E+05 0.00E+00 2.33E+05 7.75E+04 1.26E+04 Cs-136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42E+04 Cs-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.60E+05 5.99E+04 1.03E+04 Cs-138 2.69E+02 5.31E+02 2.o3E+02 0.00E+00 3.90E+02 3.85E+01 2.27E-03 Ba-139 9.00E+00 6.41E-03 2.64E-01 0.00E+00 5.99E-03 3.64E-03 1.60E+01 Ba-140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+03 Ba-141 4.37E+00 3.3CC-03 1.48E-01 0.00E+00 3.07E-03 1.87E-03 2.00E-09 Ba-142 1.98E+00 2.03E-03 1.24E-01 0.00E+00 1.72E-03 1.15E-03 2.78E-18 La-140 3.58E-01 1.80E-01 4.76E-02 0.00E+00 0.00E+00 0.00E+00 1.32E+04 La-142 1.83E-02 7.55E-03 2.07E-03 0.00E+00 0.00E+00 0.00E+00 6.08E+01 Ce-141 8.01E-01 5.41E-01 6.15E-02 0.00E+00 2.52E-01 0.00E+00 2.07E+03 Ce-143 1.41E-01 1.04E+02 1.16E-02 0.00E+00 4.60E-02 0.00E+00 3.90E+03 Ce-144 4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 Pr-143 1.32E+00 5.28E-01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 11 1-14 Rev 0 3/89 l _ _ _ _ _ _ . .. .. . . - - - ~- - ' ' ' ' '
.c l' TABLE-1.1. SITE RELATED (mrem INGESTION
/hr perDOSE COMMITMENT FACTOR uCi/ml)-
- A*
ISOTOPE MONE LIVER T-BODY THYROTD- KIDNEY LUNG GI-LLI. Pr-144 4.31E-03 1.79E-03 2.19E-04 0.00E+00 1.01E-03 0.00E+00 6.19E-10 Nd-147 9.00E-01 1.04E+00 6.22E-02 0.00E+00 6.08E-01 0.00E+00 4.99E+03 W-187 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04 Np-239 1.28E 1.2SE-02 6.91E-03 0.00E+00 '3.91E-02 0.00E+00 2.57E+03 II 1-15 Rev. 0 l l 3/89
- t 1.4 SERVICE WATER EFFLUENT RADIATION MONITORS 1RE-4269/4270i The concentration of radioactive material,in the service water effluent line normally is expected to be insignificant. Therefore, the monitor- F 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 4 a radiation monitor alarm setpoint determined as follows: , C,, = ( I Cg)+M a [Eq. 1-12] Where: Csw - the Service Water effluent monitor alarm setpoint. Cg = the concentration of each measured gamma ' emitter g, observed in the effluent (uci/ml)- DF = [(Cj/MPCj) - the dilution factor required to ensure maximum permissible concentrations'are not exceeded. 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 p release stream, doses due to releases from this stream shall be calculated in accordance with the methodology given in Section 1.2, with the near field average dilution factor, Fk, equal to 1.0. l' 1. L l' l l' u l o 1 11 1-16 Rev. I 8/89
1.5 TURBINE BUILDING SUMP EFFLUENT RADIATION MONITOR 1RE-5100 The-purpose-of the turbine building sump monitor (1RE-5100) is;to-monitor turbine building sump discharges and divert this discharge from the Low Volume Retention Pond to the Waste Water Holdup Tanks if radioactivity is detected. Because the only sources of water;to the
-turbine building sump are from the secondary steam-system, activity is expected only if a significant primary-to-secondary leak-is present.*
Since only turbine building sump water with no detectable radioactivity (as defined in Radiological Effluent Control 3/4.11.1.1, Table 4.11 1). is allowed to go to the Low Volume Retention Pond, 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 col.lected. Then, if this setpoint is exceeded, 1RE-5100 will direct valves.1RV-5100A and B to divert discharges from the turbine building sumps-to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir in accordance with Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. If a radioactive release is made from a waste water holdup tank, doses due to this release shall be. calculated in accordance with the methodology i given in Section 1.2. Tritium may be detected in the Turbine Building Sump due to leakage from the Turbine Generator Primary Water Cooling System (TGPWCS), which uses tritium as a tracer to detect system leakage into the generator. Requirements for handling tritium from TGPWCS leakage, when there is no primary-to-secondary leakage, are provided in Supplemental Guidance Statemer.t #3 given in Appendix G. II 1-17 Rev. ! ) 8/89
1.6 DEFINITIONS OF COMMON L10VID EFFLUENT PARAMETERS SECTION OF IERM DEFINITION INITIAL USE ADF- Actual Dilution Factor (unitless). This is defined 1.1.4 as the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate. A h The site related ingestion dose commitment factor- 1.2.1 to the total body or any organ, t , for each identified gamma or beta emitter, i. (mrem /hrperuti/ml) BF1- Biaccumulation factor for radionuclide,- 1, in fish 1.2.1 from Reg. Guide 1.109. (pCi/kg per pCi/1) Ca The concentration of alpha emitters in liquid waste 1.1.1 as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uci/ml) Ce F The concentration of 55F e in liquid waste as 1.1.1 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. (uci/ml) cg The concentration of each measured gamma emitter, g 1.1.1 in the 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 (uci/ml) Ci The concentrations of radionuclide, i, in the 1.1.1 waste tank. (uC1/ml) C'i The concentration of radionuclide i in the 1.1.6-Reservoir as 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'jf The concentration of radionuclide i in fish 1.2.2 sampled from the reservoir from location F1 on Table 3.1 and Figure 3-1 of this manual (pCi/kg). II l-18 Rev. 0 3/89
T i h Cik- The isotopic concentration of ridionuclide 1. 2.1 - ! found in the pre-release sample for batch-release k. Concentrations are determined , primarilyfromgammaiisotopicanagysisgf the For VSr vuse, 4H, {iquid' effluent sample.bFe>and alpha emitters, the last measured value will be used. (uCi/ml)- C'jw The concentration of radionuclide i in the 1.2.2 reservoir as measured at the circulating water intake structure shown as location SW6 on Table 3.1 and Figure 31 of this manual t (pCi/1). Cw1 The liquid waste effluent monitor alarm setpoint. 1.1.6 ' This . corresponds to the gama concentration in the undiluted waste stream which after dilution would result in MPC-level releases. L (uti/ml) l' Cs The concentration of 89S r and 90S r in liquid 1.1.1, waste as 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 (uci/ml) Csw The Service Water effluent monitor alarm setpoint. 1.4 (uC1/ml) Ct The concentration of 3 H in liquid waste as 1.1.1 measured in the analysis of the most recent monthly composite. sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uCi/ml) ; DFj Adult dose conversion factor for radionuclide, 1.2.1 1, from Reg. Guide 1.109 (mrem /pCi ingested): Ok The dose comitment received by the total body 1.2 or any organ during the duration of batch release k of liquid effluents. (mrem) O(lake)mThe dose comitment received by'the total body or any organ during a desired time period, m,- 1.2
]
due to the buildup in the lake of previously discharged radionuclides. (mrem) OT- The total dose comitment to the total body or any 1.2 organ due to all releases of liquid effluents during a desired time interval. (mrem) II l-19 Rev. 0 3/89
_ ,.---,..t, , , , - > - Dw Dilution factor, from the near field area within 1.2.1 1/4 mile of the release point to the potable water intake for adult water consumption, 1.0 for CPSES_(unitless) f Effluent flow rate. (gpm) 1.1.2 F Circulating water flow rate (or dilution flow rate). (gpm) F' Adjusted circulating water flow rate to account for 1.1.4 buildup of radionuclides in the circulating water due to previous releases. (gpm) Fk The near field average dilution factor'during a 1.2.1 liquid effluent release-(unitiess). This is defined as the ratio of the average: undiluted liquid waste flow to the average circulating water flow during the release. MPCa Maximum Permissible Concentration
- of a mixture 1.1.5 of unidentified alpha emitters. (uCi/ml)
MPCF e Maximum Permissible Concentration
- of 55Fe. 1.1.5 (uCi/ml)
MPC g Maximum Permissible Concentration
- of each 1.1.5 identified gamma emitter, g. (uCi/ml)
MPCi Maximum Permissible Concentration
- of 1*1*5 radionuclide, f. (uCi/ml)
MPCs um Perm MaxgSrandgSr.sible of Concentration
- of a mixture 1.1.5 (uti/ml)
MPCt MaximumPgH) rmissible Concentration
- of 1*1*5 tritium ( (uCi/ml)
SF Safety Factor of 0.9. This compensates for flow 1.1.3 fluctuations from the rate predicted by the circulating water pump curves.
*MPCs are given in 10CFR20, Appendix B. Table II, Column 2. Values are given for each isotope in both a soluble and insoluble form. The most conservative (lowest) value for each isotope should be used. A-value of 2x10-4 uCi/ml for dissolved or entrained noble gas shall be used.
II l-20 Rev. 0 3/89
RDF Required Dilution Factor (unitiess).- This is 1.1.5' defined as the dilution factor that ensures the maximum permissible isotopic concentrations . expressed in 10CFR20, Appendix B. Table II, Column 2, are not exceeded during a discharge. tk- The time duration of batch release k. (hours) 1~.2.1 Ur Adult fish consumption. '(kg/yr) 1.2.1 Uw Adult water consumption. (liters /yr) 1~.2.1 II l-21 Rev. 0 3/89
UNIT 1 SSW " -* TRAIN A tessuse w..s. UNIT 1 SSW TRAIN B N'-*'"" V
.......
- g a ss* w =
LlOutD EFFLUENT- " M"'* 8 mae-s2ss UNIT 2 SSW DISCHARGE PATHWAYS ._ TRAIN 8 FIGtNIE 1.1 1 P weet. wetes O.etest tot se.edup Tomas & g-~ ~ v & care. w e., L g v v Outfall 201
' Deeeb.r sta 0
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m ,~~~ t.. . ,,,, seis gat. aso GPut N 21120 GAL. (300 GPM) l a** eta-Pa. , g 4 L 4 k E ach we.se 1 48 net 2 I s, Twbs.e T.rbt
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- wv. s. im ccw ..
- ---- -- - --- F,L O.W.Ac ,TM,SF
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Gb gen. g 3 . ossec 1 I3 5 Cat. e A. 135 G AL. e A. ' 2300 Gat. i 2300 GAL. 135 Gat . mavesumare eaow 60 GPea. eA. 80 GPa4 eA. 40 Gree paves rem TA.et 40 GPM MW
*'~'**I
i
-. , .. . . r . .
t i l l i 5
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7_ 10 1 . 9 a co- i 3 7 6 5 0 0.2 0.4 0.8 0.8 1.0 1.2 1.4 l- GAMMA PHOTON ENERGY,MeV ENERGY RESPONSE TO gal?iA RADIATIONS :
, FOR RD-33 TYPE DETECTOR Figure 1.2
{N ero* oorson or m curs was gewone from wry mosooc canvasons ueng a enemw or ame geomery. assoa on one games per escaspreson. II 1-23 Rev. 0 3/89
. i i
. > > > 6 i i i > i-
- osamm:3. c m . uns a semi i -
w
..lgg.3 a - - - - -- -- -
__. ...:..__ _= .
--- - a .
.:e -
_ _ . ._ m _ __ . _ _ _ ___
. . . . .- - .. -:=-- .= __ _ _ _ _
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5 SECTION 2.0 GASEOUS EFFLUENTS- _ 2. I' GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values-as determined using the methodology _ in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments'are not required if the existing setpoint level corresponds to a lower value than the calculated value. 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 monitor reading associated. with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated. At CPSES, all gaseous effluents are released to the atmosphere through the two common Plant Vent Stacks (Stacks A & B) (Figure 2.1). Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative ground-level release. Each Plant Vent Stack is equipped with a Wide Range Gas Monitor (WRGM) and a Particulate, lodine, and Noble Gas Monitor (PIG). These monitors are part of the plant Digital Radiation Monitoring System (DRMS) supplied by GA-Technologies. 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 uCi/ml is determined during the calibration of each individual monitor, and is input into the data base for the monitor microprocessor. II 2-1 Rev. 0 4 3/89
The WRGMs are designated as monitors XRE 5570A and XRE-55708 for. Stacks' A and'B, respectively. Each WRGM consists of a inw' range (10 7 to ' 10 1 uC1/cc), r.id range (10-4 to 102 uti/cc), and high range (10*1 to 105 uCi/cc) noble gas activity detector.- The WRGMs:also have an effluent release rate channel which uses inputs from the appropriate.WRGM noble gas activity detectors and the plant vent stack flow. rate detectors (XFT-5570A1/B1) to provide an indication of noble gas release rate in uti/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. Exceeding the~ WRGM effluent release rate channel high alarm setpoint'also initiates automatic termination of Waste Gas Decay Tank releases. L L The stack PIGS are designated as particulate channels XRE-5568A and XRE-55688, iodine channels XRE-5575A and XRE 5575B, and noble gas ' channels XRE-5567A and XRE-5567B 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 required. Therefore, a methodology is provided for calculating the PIG noble gas monitor setpoints. Additionally, methodologies are provided for calculating setpoints for the PIG particulate and iodine channels, although these channels are not required by the Radiological, Effluent Controls Program. L Other monitors that may be used for effluent monitoring and control are
-the Auxiliary Building Ventilation Duct Monitor, XRE-5701, and the Containment PIG Noble Gas Monitor,1RE-5503. XRE-5701 me be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary L
Building Ventilation Duct. XRE-5701 also provides the automatic control function for termination of Waste Gas Decay Tank releases. ; L 1RE-5503 monitors the Containment atmosphere and provides the only automatic control function for termination of Containment vents or purges. 1 II 2-2 Rev. 0 3/89 1
2.1 1 Dose Rates Due to Noble Gases For implementation of Radiological Effluent Control 3/4,ll.2.1.a, the dose rate to the total body and skin of an individual at'the. SITE BOUNDARY due to noble gases shall be calculated as follows: A. Calculate the total' body dose rate due to noble gases (noble gases) i i [Eq. 2-1) Where:- Dt = the total body dose rate at the SITE BOUNDARY due to noble gases (mrem /yr) (T/Q) = the highest annual average relative concentration at the SITE BOUNDARY (3.3 x 10-6 sec/m3 in the NNW sector at a distance of 1.29 miles from the-pl ant * . ) NOTE: The annual average I/Q is also used in determining setpoints for containment purge or vent as required by Techn'ical Specification 3.3.3.1. Ki = total body dose factor due to gamma emissions from noble gas radionuclide i from Table.2.1 (mrem /yr per uCi/m3). Qi = the- total release rate of radionuclide 1 - from '.ne plant vent stacks (uti/sec) (.%e C below for calculation of Qi) B. Calculate the skin dose rate due to noble gases D, = %) I (Eq. 2 2) (noble gases) (Li + 1.1 M ) Q i Where: Ds = the skin dose rate at the SITE BOUNDARY due to noble gases (mrem /yr)
- Reference ~CPSES FSAR, Section 2.3.5.2.
II 2-3 Rev. 0 3/89
Lj = the skin dose factor.due to beta. emissions from , noble gas radionuclide it from Table 2.1 (mrem /yr peruCi/m3) 1.1 = conversion factor of mrem skin dose per mrad air dose. Mi = air dose factor due to gamma emissions from noble gas radionuclide i from Table 2.1 (mrad /yr peruCi/m3) All other terms are as previously defined. I C. Calculation of the Qj term Qi is defined as the total release rate (uC1/sec) of radionuclide i from the plant. vent stacks. Qi is given by: Qi*{,XivF V [Eq. 2-3) Where: Xjy - the concentration of radionuclide i present-at each plant vent stack (uti/cm3) Fy = the flow rate at each plant vent stack (cm3/ sec) y = index over all plant vent stacks The concentration of radionuclide i present at each plant vent' stack monitor due to all_ release sources (e.g , continuous . and batch sources), Xi v, is calculated using Eq. 2-4. This calculation is performed for each plant. vent stack using the estimated concentration and flow rate for each individual stack. s 1 Xiy = Xic Fc + (1/2)XiB FB Fe + (1/2) FB [Eq. 2-4] Where: Xi c = The concentration of radionuclide i in the continuous release stream at each stack as. sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11 2 (uci/cm3). The samples are taken from each plant vent stack at the WRGM skid. 5 11 2-4 Rev. O t 3/89
Fc = The continuous flow rate contribution of' each plant stack (cm3 / sec). These finw rates are measured directly in each plant-vent stack-(XFT-5570Al/81). XiB = The' concentration of radionuclide i in the batch release as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. These samples are taken prior to release from the confinement to be released.
-FB = The estimated flow rate contribution associated with the release of the batch source (cm3 /sec) 1/2 = factor to account for distribution of the b'atch release to' each plant vent stack, assuming uniform distribution of the batch release between both stacks. (unitiess)
NOTE: If there is no batch release source, FB and XiB are zero, and Xi y --Xi c. The flow rate at each plant vent, Fy, is given by: Fy = Fc + (1/2) FB (Eq.2-5) NOTE: If there is no batch release source, FB is zero, and Fy = Fc-2 .1. .' Plant Vent Stack Noble Gas Activity Monitors XRE-5570yB flow rance noble cas activity) and XRE-5567A/B These channels may be used for establishing noble gas activity setpoints when no automatic control functions are required by Radiological Effluent Control 3/4.3.3.5. The alarm setpoint for these channels will be calculated using Eqs. 2-6 and 2-7. These calculations will be performed for each plant vent stack. X gy 500 x SF x AF = 125 XGV (Eq. 2-6] t D t Cg = the lesser of < X gy 3000 x SF x AF = 750 XGV (Eq. 2-7 ) s D,
!! t-5
Rev. 0 3/89
i Where: 0g = The alarm setpoint for each plant vent noble gas. ' activity monitor (uci/cm3)- Xcy~= (noble gases) Xjy
= the concentration of' noble gases present at each.- 1 plant vent stack due to the combined sources:as- ;
calculated from the radionuclide concentrations-
. determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control r 3/4.11.2.1, Table 4.11-2(uti/cm3).
(See Section 2.1.1.C for the determination of Xi v). 500 = the dose rate limit to the total body of an individual in'an unrestricted area due to noble : gases. (mrem /yr) 3000 = the dose rate limit to the skin of the body of an individual in an unrestrict'ed area due to noble gases.- (mrem /yr)- SF = Safety Factor of 0.5-applied to compensate for statistical: fluctuations, errors of measurement, and non-uniform distribution of release activity between.the stacks. (unitiess) l
' AF = Allocation Factor of 0.5 applied to account for releases from both plant stacks ~ simultaneously (unitiess). This factor will limit the dose rate contribution from each stack to 1/2 the limit for the site..
II 2-6 Rev. 0 3/89
l 2.1.3
= Plant' Vent Effluent Release Rate and Samole Flow Rate Monitors , A. Plant Vent Stack Release Rate Monitors XRE-5570 A/B'(Effluent Release Rate Channel) . '
The WRGM effluent release rate channels monitor the release rate. of-radioactive materials from each olant vent stack by combining-inputs from,the WRGM noble gas activity channel (uCi/cm3) indication and a stack flow rate (cm3/sec) indication (XFT-5570Al/BI) to yield an effluent release rate (uCi/sec). , ,4 By establishing an-alarm setpoint for this monitor, an' increase- ; in either noble gas activity or stack flow, rate will cause-an 1 alarm trip. The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay. Tank Releases. The setpoint for each plant vent effluent
~
release rate monitor will be calculated using Eq. 2-8. This , calculation will be performed for each plant vent stack. Cf = Co Fy (Eq. 2-8) : where: Cf - The setpoint for each plant vent stacE effluent release rate monitor. (uCi/sec)- All other terms are previously defined. i B. Samoler Flow Rate Monitors XFT-5570A2/B2 The WRGMs are designed to sample.isokinetically from the plant' vent stacks. Isokinetic sample flow is. maintained 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 s loss of sample flow alarm setpoints are established permanently. in accordance with vendor specifications. II 2-7 Rev. 0 3/89
I.1.4 Auxiliary Buildino Ventilation Exhaust Monitor XRE 5701 "
' Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, . ACTION 34, allows.for.the Auxiliary Building Ventilation Duct Monitor (XRE- 'l 5701)'to be used as.a backup to the'WRGM for monitoring Waste Gas.~ ,
Decay Tank (WGDT) releases. XRE-5701 monitors WGDT releases by. < measuring activity in the Auxiliary Building Vent Duct land providing l an automatic control function for termination of WGDT release ~s.. ! If required, the' alarm setpoint fer XRE-5701 will be calculated
' using the following methodology. The alarm setpoint calculation is based on the following assumptions:
(1) a waste. gas decay tank release is the only batch release , occurring.(i.e., a containment purge or vent is not occurring at q thesametime). (2)'the source contribution:due to other sources in the Auxiliary { Building is negligible relative to the source contribution due ' to the release of the waste gas decay tank. i The concentration at the /.uxiliary Building Vent Monitor during a-waste gas Jecay. tank release is calculated as follows:
'X F F iaux = 1GDT CDT
- 1ABV ABV (Eq. 2-9] :
FGDT + FABV From assumption (2) above, (XiGDT FGDT>> XiABV FABV)i therefore, this equation can be reduced to: laux iGDT- CDT (Eq. 2-10) aux Where: XiGDT.= the concentration of noble gas radionuclide 1 (uC1/cm3) in the'WGDT as sampled in accordance j with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. This sample is taken prior to release from the WGDT.' FGDT = the flow rate contribution associated with the release of a WGDT (cm3/sec) L II 2-8 Rev 0 3/89 l l
XiABy = the concentration of noble gas radionuclide;i (uC1/cm3)intheAuxiliaryBuilding' ventilation stream due to sources other.than the waste gas-decay tanks'(see assumption (2), above) FABV = the flow rate contribution associated with sources in_the Auxiliary Building other than the waste gas decay tanks. This is the measured or estimated flow rate in the auxiliary building _ . vent duct. Faux = the total flow rate at the Auxiliary Building-Ventilation Monitor during the release of a waste
. gas decay tank - FGDT +.FABV Xi aux = the concentration of noble gas radionuclide. i at the Auxiliary Building Ventilation Monitor _ during a waste gas decay tank release.
From Section 2.1.1, Item C, the release rate for radionuclide i at each plant vent stack may be given by: Xi y Fy = Xi e Fe + (1/2) XiB FB [Eq. 2 11] For.this ca:e of a batch release of a waste gas decay tank, make the following substitution into this equation (see assumption (1),. above): XiB F B = X iaux Faux [Eq. 2-12] Therefore, Xi y Fy = Xi c Fc + (1/2) X aux i Faux [Eq. 2-13] Now, assuming that the source contribution from the Auxiliary Building vent (due to the release of the waste gas decay tank), X aux i Faux, is much greater than the source contribution due to all continuous sources to each plant vent stack, Xi cFe, then Xi v Fy is approximately equal to 1/2 X auxi Faux. II 2-9 Rev. 0 3/89
\
Xi v_Fy - (1/2) X aux i Faux (Eq. 2-14] t 4 At.the alarm setpoint concentration at each plant vent monitor, .Xty =' Ca. Also, the Auxiliary Building Ventilation Monitor alarm setpoint, , Caux, corresponds to the noble gas concentration, Xi aux, that would-result in the alarm setpoint concentration at each plant vent stack : monitor. Since plant vent monitor alarm setpoints are calculated .. separately for each stack, the maximum of the two plant vent stack ' monitor alarm setpoints should be used in this calculation for ca. : Therefore, CG max Fy - (1/2) Caux faux [Eq.2-15] l-Solving for Caux yields: Caux = 2 C Gmax Fy (Eq. 2-16]' L . Faux 'i i T !' Where: Caux = the Auxiliary Building ventilation exhaust monitor alarm setpoint (uci/cm3) CG max = maximum of the monitor setpoints for the two stacks. l- All other variables are previc'aly defined. 2.1.5 Containment A(mosobere Gaseous Monitor 1RE-5503 For implementation of Technical Specification 3/4.3.3.1, the alarm setpoint for the Containment Atmosphere Gaseous Monitor for
- j. Containment Ventilation Isolation will be calculated using the !
I following methodology. The alarm setpoint calculation is based on the following assumptions: (1) a containment purge or vent operation is the only batch release occurring (i.e., a waste gas decay tank purge operation is not occurring at the same time). , (2) the source contributions due to all other continuous sources to the plant vent are negligible relative to the source 'l contribution from Containment Building purge or vent operation. II 2-10 Rev. 0 3/89
h From Section'2.1.1.-Item'C, the release rate for radionuclide i at each-plant vent stack ~may be given by: Xi y Fy Xi c Fe + (1/2) XiB FB (Eq. 2-11). For this case of a batch release due to a containment purge or vent operation, make the following substitution into this equation (see ass'.:mption (1), above) XiB FB = Xi cont Fcont (Eq. 2-17) Where: Xi cont = the concentration of noble gas radionuclide i. (uCi/cm3) in the containment release' stream as sampled in accordance with Radiological Effluent - Control. 3/4.11.2.1 Table = 4.11-2. This sample is taken prior to release from the Containment Building. Fcont = the flow rate contribution associated with the release of the containment atmosphere (cm3/sec) Therefore, Xi v Fy = Xi c F, + (1/2) X icont Fcont (Eq.2-18] Now, assuming that the source contribution from the containment purge-or vent, X icont Fcont, is much greater than the source contribution due to all continuous sources to each plant vent stack, Xi c Fci then Xi v Fy is approximately equal to 1/2 X icont Fcont-Xi y Fy = (1/2) X icont Fcont (Eq. 2-19] Il 2-11 Rev. 0 3/89
At the alarm setpoint concentration at each plant vent monits , e m* Co. Also,- the containment atmosphere gaseous monitor'alcui crate.t , Ccont, corresponds to the noble gas concentration,- Xi cont, the would result in the alarm setpoint concentration at eath: plant m t stack monitor. Since plant vent monitor alarm setpoints are calculated separately for each stack, the maximum of the two plant vent stack monitor alarm setpoints should be used in this calculation for Co. Therefore, f CG max Fv = (1/2) Ccont Fcont [Eq. 2-20) Solving for Ccont yields: ,, Ccont . 2C Gmax Fv (Eq. 2-21]~ Fcont ' t Where: Ccont = the containment atmosphere gaseous monitor alarm ! setpoint (uti/cm3) ' CG max = maximum of the monitor setpoints for the ho stacks. All other variables are previously defined, p 2.1.6 Dose Rates Due to Radiciodines. Tritium. and particulates b " Organ dose rates due to iodine-131 and iodine-133, tritium, and a. .i radioactive materials in particulate form with half lives greater than eight days will be calculated to implement the requirements of 1 Radiological Effluent Control 3/4.11.2.1.b as follows: D = (K/Q) E PQ 9 IPAT gi [Eq. 2-22] Where: Do = the total organ dose rate due to iodine-131, iodine-133, I particulates with half-lives greater than eight days, and tritium. (mrem /yr) > l H l 1 1 II 2-12 Rev. 0 3/89 .________________1__________________.__
Pj = pathway dose rate parameter factor for radionuclide, i, (for radiciodines, particulates, and tritium) for the inhalation pathway in mRevyr per uCi/m3* (Table 2.2) ; IP&T = lodine 131, iodine 133, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed. ' All other variables are previously defined. : i 2.1.7 Plant. Vent Stack fodine Monitors XRE-5575A/B l The setpoint for the Plant Vent Stack Iodine Monitors should be estab'ished to ensure compliance with Radiological Effluent Control i 3/4.ll.2.lb. These setpoints are not required by Radiological l Ef fluent Control 3/4.3.3.5. Table 3.3 8. The methodology used ' performs dose rate calculations in accordance with Section 2.1.6 and compares them with the Radiological Effluent Control dose rate limit of 1500 mReWyr to any organ for compliance. An allocation factor (AF) and safety factor (SF) ere also utilized for this determination. Additionally, the ratio of the dose rate due to only 1 131 to the dose rate due to I-131 and 1-133 is included as a factor in the determination since the stack fodine monitor utilizes ; a single channel analyzer set on the I 131 photopeak (i.e., only I-131 is detected, not all lodines). The equation for calculating the lodine Monitor Setpoint for each stack, Cg, is: c; xgy 1500 x AF x SF [Dg g3gh , 375 (XIV) [*t-131\lEq. 2-23)
*o *o
( *t ) \*I }
*The latest NRC guidance has deleted the requirement to determine P t for L the. ground plane and food pathways. In addition, the critical age group has been changed from infant to child. The methodology used for determining values of Pi is given in Appendix A.
1 11 2-13 Rev. 0 l 3/89
, _ _ . _ __ _ _ __ ..__ . _ ~ . . . _ _ _ . . . . _ _
i I ll u ( Where: CI The setpoint for each plant vent stack lodine Monitor l (uCi/cm3) X IV*(iodfnes)Xy i
= the concentration of radiciodines present at each plant vent stack due to the combined sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate sample; taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. (uti/cm3)
(See Section 2.1.1.c for the determination of Xi v). 1500 the dose rate limit to any organ due to 1 131, tritium and particulates with half lives greater than eight days (mrem /yr) 01131
- the organ dose rate due to 1 131 calculated using Eq. 2 22 considering only 1-131.
01 = the organ dose rate due to I 131 and 1-133 calculated using Eq. 2 22 considering only 1 131 and 1-133. All other variables are previously defined. 2.1.8 Plant Vent Stack Particulate Monitort XRE-5568A/B The setpoint for the Plant Vent Stack Particulate Monitors should be established to ensure compliance with Radiological Effluent control 3/4.11.2.1.b. The methodology used performs dose rate calculations in accordance with Section 2.1.6 and compares them with the Radiological Effluent Control dose rate limit of.1500 mrem /yr to any ' organ for compliance. An allocation factor (AF) and safety factor (SF) are also utilized for this determination. The equation for calculating the Particulate Monitor Setpoint for each stack, Cp . is: C p= K g 1500 AF a $F = " bv) (Eq. 2 24] 0, D, 11 2-14 Rev. 1 8/89 l 1
Where: Cp The setpoint for each plant vent stack Particulate Monitor (uti/cm3) Xpy = (particulates) X iy
= the concentration of > articulates present at each plant vent stack due to the combined sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11 2. (uti/cm3).
All c' r variables are previously defined. 11 2-15 Rev. 0 3/89
TABLE 2.1 DOSE TACTORS TOR EXPOSURE TO A SEMI-INTINITE CLOUD OT NOBLE GASES
- Isotope y-Body *** (K) 6-Skin ***(L) y-Air **(M) 6-Air **(N)
Kr-83m 7.56E-02 --- 1.93E+01 2.66E+02 Kr-Van 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37t+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.4BE+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- Values taken from Reference 2, Table B-1
** mead-s8 uCi-yr
*** aree-o' uCi-yr l
11 2-16 Rev. 1 l 8/89 m
m 2.2 GASEOUS EFFLUENT DOSE CALCULATIONS 2.2.1 Dose Due to Noble Cases For implementation of Radiological Effluent Control 3/4.11.2.2, the cumulative air dose due to noble gases to areas at and beyond the SITE BOUNDARY will be 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. l The air dose over the desired time period will be calculated as l follows: Dy air dose due to gamma emissions from noble gas radionuclides (mrad) Dy I [Eq. 2-25) 3.17 x 10 8 (X/Q) p g,3,3) Mt Q't Where: 3.17 x 10 8 . the fraction of a year represented by one second O'i = the cumulative release of radionuclide i during the period of interest. (uC1) (Q'i = Qi (uti/sec) x release duration (sec)) ; l Q't is based on the noble gas activities in each plant vent stack and WGOT or Containment Samples required by Radiological Effluent Control 3/4.11.2.1, l Table 4.11 2. ' All other variables are previously defined. D, = air dose due to beta emissions.from noble gas radionuclides (mrad) l I 06 - 3.17 x 10 8 (X/Q) gases)Nj Q'i [Eq. 2-26). Where: Ni = the air dose factor due to beta emissions
, from noble gas radionuclide i from Table 2.1 (mrad /yr per uC1/m3).
All other variables are previously defined. 11 2 17 Rev. 0 3/89
Note: If the methodology in this section is used in i determining dose to an individual rather than air dose ; due to noble gases, substitute Ki for Mj, (Lj + : 1.1 Mj) for Nj, and the Annual Average X/Q values from Table 2.7 for the highest annual average relative - concentration (X[Q)atthe$1TEBOUNDARY. . 2 2.2 Dose Due to Radiciodines. Tritium, and Particulates i for implementation of Radiological Effluent Control 3/4.11.2.3, ! the cumulative dose to each organ of an individual due to ! iodine-131, iodine-133, tritium, and particulates with half- > lives greater than 8 days will be calculated at least once per , 31 days 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: , Dp = dose due to all real pathways to organ, o, 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 (mrem). D = I 3.17 x 10'8 W' p p I R I'"' Q'I [Eq. 2 27] PATHS IPAT Where: W' = the dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum 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 concentration at the location of interest. Values for X/Q are listed in Table 2.4. If desired, the highest individual receptor X/Q valve may be used, or II 2-18 Rev. 0 3/89
i W' = D/Q for the food and ground plane pathways in m 2, D/Q is the annual average deposition at the location of interest. Values for D/0 are listed in Table 2.4. If desired, the highest individual receptor D/Q value may be used. NOTE: For tritium, the dispersion parameter, W' is taken as the annual average X/Q values from Table 2.4 for inhalation, food and ground plane pathways. j RPi a.o dose factor for radionuclide i, pathway p, age group a and organ o, in mrem /yr per uti/m3 for the inhalation i pathway and m2(mrem /yr) per uti/sec for food and ground plane pathways, except for tritium which is in mrem /yr per uti/m3 for all pathways. The values for RPi .a.o for each pathway, radionuclide, age group and organ are listed in Table 2.3*, Q'i cumulative release of radionuclide, i, during the period of interest (uti). Q'j is based on the activities measured in each plant vent stack from the l analyses of the particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1, ! Table 4.11-2.
!&PT - lodines, particulates with half-lives greater than
, eight days, and tritium. These are the isotopes l over which the summation function is to be performed. PATHS - the real pathways of exposure to individuals at the i locations of interest as indicated in Table 2.5. , 1
*The methodologies used for determining values of RPi ,a.o for each pathway are given in Appendices B through F.
11 2 19 Rev. 0 3/89
2.2.3 Dose Proiettions for Gaseous Effluents Radiological Effluent Control 3/4.11.2.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment Systems be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a - 31-day period, either: 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or ' O.3 mrem to any organ of a MEMBER OF THE PUBLIC. ; The following calculational method is provided for performing this dose projection. At least once every 31 days the gamma air dose, beta air dose and the maximum organ dose for the quarter to date will be divided by the l number of days into the quarter and multiplied by 31. Also, this dose ! projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made, such ac Waste Gas Decay Tank releases. If these projected doses exceed ; any of the values listed above, appropriate portions of the Gaseous Waste Processing System shall be used to reduce radioactivity levels prior to release. 2.2.4 Dose Calculations to Sunoort Other Reauirements For the purpose of implementing the requirements of Radiological Effluent Control 6.9.1.4, the Semiannual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents from the station during the previous 6 months of operation. This assessment shall be a summary of the doses determined in accordance with Section 1.2 for doses due to liquid effluents, Section 2.2.1 for air doses due to noble gases, and Section 2.2.2 for doses due to iodines, tritium, and particulates. This same report shall also include an assessment of the radiation Rev. 0 . I1 2 20 3/89
?
doses from radioactis e liquid and gaseous effluents to members of the public due to their activities inside the SITE BOUNDARY. This assessment shall b performed in accordance with the methodologies in Sections 1.2, 2.2.1, and 2.2.2, using either historical average or concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors. All assumptions l 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 census shall be performed using the methodology in Section 2.2.2, i 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 use census changes, the critical _ location (i.e., the location where an individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest slik animal, and the nearest vegetable garden. Additionally, when a location is identified that
'ields a calculated dose 20% greater than at a location where '
.avironmental samples are currently being obtained, add the new ocation within 30 days to the Radiological Environmental Monitoring loiations described in Section 3.1 of this manual.
For the purpose of implementing Radiological Effluent Control 3/4.11.4, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by summing the annual doses determined for a member of the public in accordance with the methodology of Sections 1.2, 2.2.1, and 2.2.2 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 3/4.11.1.2,3/4.11.2.2,or3/4.11.2.3. This assessment will be included in the Semi annual Radioactive Effluent Release Report to be submitted 60 days after January 1 of the year after the assessment was require'd. Otherwise, no assessments are required. Rev. O
!! 2-21 3/89
For the evaluation of doses to real individuals from liquid releases, the same calculation methods as employed in section 1.2 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides. The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide l concentrations. For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed in sections 2.2.1 and 2.2.2 will be used. In section 2.2.1,_the total body dose factor snould be substituted for the g6mma air dose factor (Mj) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the , meteorological conditions, and the consumption of food. Data ob'.ained - from the latest land use census should be used to determine lo.ations for evaluating doses. The results of the Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations. The dose component due to direct radiation may be determined by 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 Special Report that must be submitted if this determination is required. I i l L Rev. O 11 2-22 3/89
1 TABLE 2.2 PATHWAY DOSE RATE PARAMETER (Pi)*
- BASED ON THE IKKALATION PATHWAY i FOR THE CHILD AGE GROUP l l
l ORGAN DOSE FACTORS UUCLIDE l.. . . .... ... .... - - * ..- .. .... - . . ...~......... l BONE LIVER T. BODY THYROID KIDNEY UUNG CI LLI H3 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
................................................................................ I 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 FE.55 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03
................................................................................ l FE.59 Co.58 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 CO.60 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7,07E+06 9.62E+04 NI.63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 RB.86 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 SR.90 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 Y.91 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB 95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU.103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 i
RU.106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 l AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 l ................................................................................ r TE.127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE.129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1,76E+06 -1.82E+05 I 131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I.133 1.66E+04 2.03E+04 7.70E+03 3,85E+06 3.38E+04 0.00E+00 5.48E+03 CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 C3 136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS.137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA 140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR.143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND.147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04
............................................................. Rey. 0.............
II 2-23 3/89
s.. i i 1 l 1 I i TABLE 2.3 l PATHWAY DOSE FACTORS AGE GROU?: A1.1. PATHWAY: GROUND PLANE - l ORGAN DOSE FACTORS I h'UCLIDE l.....................
)
l T. BODY SKIN j H3 0.00E+00 0.00E+00 1 1 1 P . 'J 2 0.00E+00 0.00E+00 l
............................... 1 CR.51 4.65E+06 5.50E+06 MN.54 1.39E+09 1.62E+09 FE.55 0.00E+00 0.00E+00 !
FE.59 2.73E+08 3.21E+08 Co.58 3.79E+08 4.44E+08 CO.60 2.15E+10 2.53E+10 l N1 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 5.06t+08 AG.110M 3.44E+09 4.01E+09 TE.125M 1.55E+06- 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 C$.136 1.51E+09 1.71E+0A CS 137 1.03E+10 1.20E+10 RA.140 2.06E+07 2.36E+07 CE.141 1.37E+07 1.54E+07
............................... r CE.144 6.96E+07 8.05E+07 PR.143 0.00E+00 0.00E+00 l
ND.147 8.39E+06 1.01E+07 Rev. 0 11 2 24 3/89
l TABLI 2.3 PATHWAY DOSE TACTOR $ ACE CROUP: ADULT PATHWAY: CRASS. COW.MI1X
] ORCAN DOSE TACTORS VUCL1DE l.. - - -* - - *- * . ....
l BONE LIVER T. BODY TRYROID KIDNEY LUNO CI.LLI H3 0.00E+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 P.32 1.70E+10 1.06E+09 6.58E+08 0.00E+00 0.00E+00 0.00E+00 1.91E+09 CR.51 MN.54 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28t+03 3.78E+04 7.17E+06 FE.55 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57t+07 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 TE.59 C0 58 2.97E+07 6.97E+07 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.32E+08 CO.60 0.00E+00 4.71E+06 1.05E+07 0.00E+00 0.00E+00 0.00E+00 9.54E+07 0.00E+00 1.64E+07 3.61E&O7 0.00E+00 0.00E+00. 0.00E+00 3.08E+08 NI 63 ZN.65 6.72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 1.37E+09 4.36E+09 1.97E+09 0,00E+00 2.91E+09 0.00E+00 2.74E+09 RB.86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.10E+08 SR.89 SR.90 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E-08 Y.91 4.67E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E-09 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 ZR.95 NB.95 9.41E+02 3.02E+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 RU.103 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 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 A0 110M 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 TE.125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E+07 0.00E+00 6.49E+07 TE.127M 4.57E+07 1.63E+07 5.57t+06 1.17E+07 1.86E+08 0.00E+00 1.53E+08 TE.129M I.131 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 1.12E+08 1 133 CS.134 3.87t+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS.136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS.137 7.37E+09 1.01E+10 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 BA.140 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07 CE.141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 ! 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 1.57E+02 6.32E+01 7.81E+00 0.00E+00 3.65E+01 0.00E+00 6.90E+05 ND.147 9.40E+01 1.09E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5 22E+05 Rev. O II 2-25 3/89
. , . _ . . . . . . . _ . . . - . . -m-- . - .- . . - . -- - "- .
l l i TABLE 2.3 l PATHVAY DOSE FACTORS ACE CROUP: TEEN PATHWAY: CRASS. COW. MILK l ORCAN DOSE FACTORS NUCL1DE l .. - =- -- - .. .- - . * . . . . l BONE LIVER T. BODY TNYROID KIDNEY LUNC LLI
........................................................................Cl 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. CR.51 0.00E+00 65E+09 ....... KN.54 0. 0C6 500 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 FE.55 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37
.........................................................................E+07 FE.59 Co.58 5.19E+07 1.21E+08 4.68t+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 Co.60 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62
.........................................................................E+08 N1 63 ZN.65 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 RB 86 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+0
........................................................................... 8 SR.89 SR 90 2.68E+09 0.00E+00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 Y.91 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 l
l ZR.95 NB.95 1.65E+03 5.21E+02 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 ) 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58t+04 0.00E+00 3.34E+08 RU.103 l 1.81E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 l RU 106 3,76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1,80E+06 AC.110M 9.64E+07 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE.125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.00E+00 0.00E+00 8.87E+07 TE.127M 8.45E+07 3.00E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2,11E+08 TE.129M 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 1 131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 I.133 7.08E+06 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 1.19E+09 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 4.87E+07 5.97E+04 3.14E+06 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 1.63E+05 0.00E+00 1.66E+0B 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 1.81F'02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.1 E+05 Rev. 0 II 2-26 3/89
I l 1 TABLE 2.3 PATHWAY DOSE FACTORS l A0E CROUP: CHILD PATNVAY: CRASS. COW. MILK i l ORGAN D FACTORS nUCL1DE l....................................OSE ................................. l BONE LIVER T. BODY THYROID KIDNE CI.LLI
........................................................Y H.3 LUNC 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P 32 7.77E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.0 2.15E+09 CR.51 0E+00................ !
MN 54 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 FE.55 0,00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 t 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+ l l ................................................................ 07 1.10E+07 FE.59 ............. Co.58 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08 Co.60 0.00E+00 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+ 2.39E+08
................................................................ 00 NI.63 .............
ZN.65 2.97E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+0B R3 86 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0 5.65E+08
............................................................ 00E+00 SR.89 .................
SR.90 6.63E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.57E+08 Y.91 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 3.91E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+0 5.21E+06
................................................................. 0............
IR.95 NB.95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21E+03 0.00E+00 8.SOE+05 RU.103 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+0B 4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08t+04 0.00E+00 1
...................................................................... 11E605 RU 106 l
9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 l AC 110M 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE.125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 l TE.127M 2.08E+08 5.61E407 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 ! TE.129M I.131 2.72E+08 7.59E.07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 I.133 CS 134 1.72E+07 2.13E+07 8.0$E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 l CS 136 2.27E+10 3.72E+10 7.85E+09 0.00E+00 1.15E+10 4.14E+09 2.01E+08 1,01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 CS.137 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08
&A.140 1.18E+08 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 CE.141 2.19E+04 1.09 E+04 1.62E+03 0,00E+00 4.79E+03 0.00E+00 1.36E+07 CE.144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR 143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND.147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.71E+05 Rev. O 11 2-27 3/89
TABLE 2.3 PATHVAY DOSE FACTORS ACE CROUP: INFANT PATHVAY: CRASS.COV. MILK l ORCAN DOSE FACTORS SUCLTDE l * .. - - - * - * * . *- l BONE LIVER T. BODY THYROID K1DNEY LUNC CI.L
...........................................................................LI H.3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 P.32 1.60E+11 9.42E+09 6.21E+09 0.00E+00 0.00E+00 0.00E+00 2.17
.........................................................................E+09 CR 51 0.00E+00 0.00E+00 1.61E+05 1,05E+05 2.30E+04 2.05E+05 4.70E+06 MN.54 FE.55 0.00E+00 3.91E+07 8.85E+06 0.00E+00 8.65E+06 0.00E+00 1.43E+07 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1,11E+07 FE.59 2.25E+08 3.93E+08 1.55E+08 0.00E+00 0,00E+00 1.16t+08 1.88E+08 Co.58 CO.60 0.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.0$E+07 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+0
........................................................................... 8 NI 63 ZN.65 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+0B 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1,61E+10 RB 86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+0
........................................................................... 8 SR.89 SR.90 1.26E+10 0.00E+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.54E+08 Y.91 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0,00E+00 0.00E+00 5.26
..........................................................................E+06 ZR 95 NB.95 6.81E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 RU.103 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 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 0.00E+00 1.45E+06 AC.110M 3.86E+08 2. 82E408 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE:125F
) 5)Efp8,,, p ppEfpf 2.p4Efpf 5.p8Efpf p.ppEfpp p.ppEfpp J )9E+pJ 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 1 131 5.58t+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.00E+00 1.15E+08 I 133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.96E+06 CS.134 CS 136 3.65E+10 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 8
.i.................................................................... 85E+07 CS.137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 BA.140 2.42E+08 2.42E+05 1.25E+07 0,00E+00 5.75E+04 1.49t+05 5.94E+07 CE.141 4. 34 E+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 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 ND.147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0,00E+00 5.75E+05
)
Rev. 0 l Il 2 28 3/89
TABLE 2.3 PATHWAY DOSE TACTORS j ACE CROUP: ADULT PATHWAY: CRASS. COW. MEAT ! l ORGAN DOSE TACTORS NUCL1DE l. - *- *** * * ' * - - - .- .... l BONE LIVER T. BODY TNYROID KIDNEY LUNO
.......................................................................CI.LLI H.3 .......
0.00E+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 P 32 4.63E+09 2.88E+08 1.79E+08 0.00E+00 0.00E+00 0.00E+00
.................................................................... 5.21E+08 CR.51 MN 54 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 '
TE.55 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 - 2.93E+08 2.03E+08 4.73E+07 0.00E+00 0.00E+00 1.13E+08 I
.................................................................... 1.16E+08 FE.59 .........
Co.58 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 Co.60 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 0.00E+00 7.52E+07 1.66K+08 0.00E+00 0.00E+00 0.00E+00
.....................................................................1,41E+09 ........
i NI 63 ZN.65 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 RB.86 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+0B ' 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E'00 0.00E+00 9
...................................................................... 59E+07 i
SR.89 l SR.90 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 ! l- Y.91 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+0B 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6
...................................................................... 24E+08 ZR.95 NB.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 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 .
AC 110M 6.68E+06 6.18t+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE.125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE.127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 i TE.129M I 131 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 4 I.133 3.68E.01 6.41E 01 1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 i CS.134 6.58t+08 1.57E+09 1.28E+09 0.00E+00 5,07 E+08 1.68E+08 2.74E+07 CS.136 1.21E+07 4.78E+07 3.44E+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+0A 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 1.08t+03 0.00E+00 4.42E+03 0.00E+00 3.64E+07 CE.144 1.46E+06 6.10E+05 7.83E+04 0.00E+00 3.62E+05 0.00E+00 4.93E+08 PR.143 2.09E+04 8.40E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 ND.147 7.08E+03 8.18E+03 4.90E+02 0.00E+00 4.78E+03 0.00E+00 3.93E+07 Rev. O 11 2 29 3/89
l TABLE 2.3 PATHWAY DOSE TACTORS AGE CROUP: TEEN PATHWAY: CRASS. COW. MEAT l ORGAN DOSE TACTOR $ i NUCL1DE l * = . * . . - *. ..... BONE LIVER i l T. BODY THYROID KIDNEY
.......................................................................GI;LLI H.3 LUNC 0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 I P.32 l 3.91E+09 2.42E+08 1.52E+08 0.00E+00 0.00E+00 0.00E+0 3.29E+08
................................................................. 0............
CR 51 MN.54 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 TE.55 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 , 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+0
................................................................. 8 7.31E+07 TE.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 0.00E+00 0.00E+00 1.94E+08 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00
.................................................................... 7.60E+08 NI.63 .........
ZN.65 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71E+08 i RB.86 2.50E+08 8.68E+08 4.0$E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 0.00E+00 4.06E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00
.................................................................... 6.00E+07 SR.89 SR.90 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 Y.91 8.04E+09 0.00E+00 1.99t+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 ,
9.54E+05 0.00E+00 2.56t+04 0.00E+00 0.00E+00 0.00E+00 3.9
....................................................................... 1E+08 ZR.95 s
NB.95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 l RU.103 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 8.56E+07 0.00E+00 3.66t+07 0.00E+00 3.02E+08 0.00E+00 7 i
...................................................................... 15E+09 RU 106 2.36E+09 0.00E+00 2.97t+08 0.00E+00 4.54E+09 0.00E+00 1.13E+11 -!
AG 110M 5.06E+06 4.78t+06 2,91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 ' TE.125M 3.03E+08 1.09t+08 4.0$E+07 8.46t+07 0.00E+00 0.00E+00 8.94E+0
........................................................................... 8 ..
TE.127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 0.00E+00 2.35E+09 TE.129M I.131 9.49E+08 3.52E+08 1.50E+08 3.06t+08 3.97E+09 0.00E+00 3.56E+09 ' 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 I.133 CS.134 3.08E.01 5.22E.01 1.59E.01 7.29E+01 9.16E.01 0.00E+00 3.95E.01 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS.136 l 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 CS.137 7.24E*08 9.63E+08 3.35E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07 BA.140 2.39E+07 2.93E+04 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 CE.141 1.182+04 7.87E+03 9.05E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 l CE.144 1.23E+06 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 4.08E+03 0.00E+00 5.'9E+07 ND.147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2 .E+07 Rev. O
!! 2 30 3/89
TABLI 2.3 h PATHWAY DOSE TACTORS ACE CROUP: CHILD PATHWAY: CRASS. COW. MEAT l ORGAN DOSE TACTORS NUCLIDE l....* .- * . - -- - .- . ... .................. l BONE LIVER T. BODY THYR 01D 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+0B 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 TE.55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 a .............................................................................. TE.59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 Co.58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 Co.60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08
............................................................................n NI.63 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08 ZN.65 3.76E+08 1.00E+09 6.22E+08 0.00E+00 6.31E+08 0.00E+00 1.76E+08 RB.86 0.00E+00 5.76E+08 3.54E+04 0.00E+00 0.00E+00 0.00E+00 3.71E+07 SR 89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07
- SR 90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 Y 91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR.95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 NB 95 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 RU.103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01E+09 RU.106 4.44E+09 0.00E+00 5.54E+08 3.00E+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. 54 E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 l TE.127M 1.78E+09 4.78E+08 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 5.26E+09 0.00E+00 2.18E+09 I.131 1.66t+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.4BE+06 I.133 5.72E 01 7.08E 01 2.68E.01 1.31E+02 1.18t+00 0.00E+00 2.85E.01 CS 134 9.23E+08 1.51E+09 3.19E+08 0.00E+00* 4.69E+0A 1.68E+08 8.16E+06 CS.136 1.63E+07 4.48E+07 2.90E+07 0.00E+00 2.J9E+07 3.56E+06 1.57E+06 CS.137 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06
&A.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 7.26t+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1,89E+08 PR 143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 3.60E+07 ND.147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07
]
Rev. 0 11 2 31 3/89
l i l i l TABLE 2.3 PATHWAY DOSE FACTORS ACE CROUP: INFANT PATHWAY: CRASS. COW. MEAT
.............................................................................. l l ORGAN DOSE FACTORS l XUCL1DE 1.... .. . . - .* . ...*. . . . . .......*.. ;
l BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI { H.3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 MN.54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ! TE.55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' FE.59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN 65 RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 Y.91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 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&OO 0.00E+00 AC.110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00d+00 0.00E+00 0.00E+00 5 TE 125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I TE.127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129M 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.'.37 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA.140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.lul 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l PR.143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND.*.47 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rev. O II 2-32 3/89
i TAall 2.3 FATHWAY DOSE TACTORS e AGE GROUP: ADULT PATHWAY: CRASS. GOAT. MILK j ; ORGAN DOSE TACTORS ' NUCL1DE l... ...... . .. - .. - ... .. .. .. ...... ........... l BONE LIVER T. BODY TNYROID KIDNEY LUN GI .LLI
..................................................................G 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 0.00 2.30E+09 '
...............................................................E+00 CR.51 ...............
MN.54 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 FE.55 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 :' 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+0 1.30E+05
................................................................. 5............
FE.59 Co.58 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 Co.60 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E+00 0.00 3.70E+07
...............................................................E+00 NI.63 ...............
ZN.65 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 l RB.86 1.65E+083.12E+08 0.00E+00 5.24E+08 2.37E+08 0.00E+00 3.51E+08 0.00E+00 3.30E+08
- 1. 45 E+08 0.00E+00 0.00E+00 0.00E+ 6.14E+01
................................................................ 00.............
SR.89 SR.90 3.05E+09 0.(iOE+00 8.76E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 Y.91 9.84E+10 0 ( OE+00 2.41E+10 0.00E+00 0.00Z+00 0.00E+00 2.84E+09 i
................... 0.kOE+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.68E+05 1.03E+03
! IR.95 l NB.95 1.13E+02 3.63E+01 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 RU 103 9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07 1.22E+02 0.00E+00 5.27t+01 0.00E+00 4.67E+02 0.00E+00
.................................................................... 1.43E+04 RU.106 2.45E+03 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.59E+05 AG.110M 6.99E+06 6.47E+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 5.89E+05 7.96E+06 0.00E+00 7.81
.........................................................................E+06 .....
TE.127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 0.00E+00 1.84E+07 TE.129M 1 131 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.00E+00 3.64E+07 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.00E+00 1.34E+08 I.133 CS 134 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.28E+06 CS.136 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08 7.92E+08 3.13E+09 2.25E+09 0.00E+00 1.74E+09 2.38E+08 3.55E+08 l CS.137 BA.140 2.22E+10 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 3.24E+06 4.07E+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.67E+06 CE.141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.00E+00 1.51E+06 CE.144 4.30E+04 1.80E+04 2.31E+03 0.00E+00 1.07E+04 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 8.30F+04 ND.147 1.13E+01 1.31E+01 7.82E 01 0.00E+00 7.65E+00 0.00E+00 6.28E+04
............................................................................ ~
Rev. O
!! 2 33 3/89
i e l TABLI 2.3 PATHVAY DOSE FACTORS ACE CROUP: TEEN PATHVAY: GRASS. COAT.MILX l ORGAN uUCL1DE l..................... . ... ... ... DOSE FACTORS l BONE LIVER T. BODY TNYROID KIDNEY CI.LLI H3 LUNG ............... 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 P.32 3.78E+10 2.34E+09 1.46E+09 0.00E+00 0.00E+00 0.00E+0 3.18E+09 CR.51 0............ MN 54 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 FE.55 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00E+00 2.61E+0 1.78E+05
................................................................. 5............
TE.59 CO.58 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 CO.60 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+0 4.35E+07 i
................................................................. 0............
NI 63 l ZN.65 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ' RB.86 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+0 8.40E+07
................................................................. 0............
SR.89 SR.90 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 1.39E+11 0,00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 Y.91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 0.00E+00 7
...................................................................... 78E+05 ZR.95 NB.95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 l RU 103 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82
- .........................................................................E+04 RU.106 i
l 4.50E+03 0.00E+00 5.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 AG.110M 1.16t+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09 TE.125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.J6E+07 TE.127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2,52E+07 TE.129M 1 131 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+08 1 133 CS.134 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS.136 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 1 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08
...............~..............................................................
CS.137 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 BA.140 5.84E+06 7.16E+03 3.76E+05 0.00r+00 2.43E+03 4.81E+03 9.01E+06 CE.141 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06 CE.144 7.90E+04 3. 2 ? F.&O4 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR.143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 ND.147 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.54E+04
............................................................... .. .. ~ -
Rev. O
!! 2-34 3/89
I l 1 TABLE 2.3 PATHWAY DOSE TACTORS AGE GROUP: CHILD PATHWAY: CRASS. COAT.M11X
] ORGAN DOSE TACTORS NUCL1DE 1- * * * * *- - .
......c.....................
l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E400 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 l P.32 l 9.32E+10 4.36E+09 3.59E+09 0.00E+00 0.00E+00 0.00E+00 2.5BE+09 CR.51 0.00E+00 0.00E+0c i
\
MN.54 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 l 0.00E+00 2.52E+0 6.71E+05 0.00E+00 7.06E+05 0.00E+00 2.11E+06 FE.55 1.45E+06 7.71E+0 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 . FE.59 Co.58 1.56E+06 2.53E+06 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.f4E+06 Co.60 0.00E+00 1.46t+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.49E+06 i 0.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 NI 63 , t ZN 65 3.56E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08 Rp;86 9 pp[fpp 1;p5[fgy p g?[fg8 g
,,,, ,, ,, ,, gg[fpp g pp[fgg g;gg[fpg p;??E;p?
SR.89 SR.90 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0,00E+00 3.16E+09 Y.91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.?4E+05 ZR 95 4,60E+02 1.01E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1,05E+05 NE.95 RU.103 3.82E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 5.14E+02 0.00E+00 1.98E+02 0,00E+00 1.29E+03 0.00E+00 1.33E+04 RU.106 1.11E+04 0.00E+00 1.38E+03 0.00K+00 1.50E+04 0.00E+00 1.73E+05 , AG 110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE.125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.00E+00 0.00E+00 8.55E+06
.............................................................................. i TE.127M 2.50E+07 6.72E+06 2.96E+06 5.97t+06 7.12E+07 0.00E+00 2.02E+07 TE.129M 3.26E+07 9.10E+06 5.06E+06 1.0$E+07 9.56E+07 0.00E+00 3.97E+07 1 131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+08 I.133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 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+08 CS.136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6.64E+08 2.94E+08 CS.137 9.68E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA.140 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 CE.141 2.63E+03 1.31E+03 1.95E+02 0.00E+00 5.74E+02 0.00E+00 1.63E+06 CE 144 1.95E+05 6.11E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 PR.143 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9 29E+04 ND.147 5.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6 S5E+04 Rev. O II 2-35 3/89 1^
1-
i 1 1 i TABLZ 2.3 PATHWAY DOSE FACTORS
'l AGE CROUP: INTANT PATHVAY: CRASS GOAT.MILX i l ORGAN DOSE FACTORS l NUCLIDE l. - * . ** ** - - ~- - ;
l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI 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 e CR.51 KN.54 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 TE.55 0.00E+00 4.68E+06 1.06t+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06 , 1.76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 TE.59 Co.58 2.92E+06 5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.44E+06 Co.60 0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7 25E+06 . 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 2.57%+07
.............................................................................. r N1 63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN 65 R3 86 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 i SR.89 SR.90 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 l Y.91 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 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+CL 9.91E+04 NB.95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU.103 1.04E+03 0.00E+00 3. 48 t+02 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
I AG.110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1,75E+09 - i TE.125M 1.81E+07 6.0$E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 ! TE.127M 5.06E+07 1.68t+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 s4E+07 TE.129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 I.131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08
'I.133 4.36E+07 6. 3 5 E+07 , 1. 86 E+07 1.15E+10 7.46E+07 0.00E+00 1,07E+07 CS 134 1.09E+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 l ..............................................................................
L CS.137 1.54E+11 1.81E+11 1.28t+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 BA.140 2.90E+07 2.90E+04 1.50E+06 0.00E+00 6 f
- F E3 1.78E+04 7.13E+06 CE.141 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9. 97 62 0.00E+00 1.64E+06
....................................................e -......................
CE.144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 PR.143 1.78E+02 6.66E+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. O l 11 2 36 3/89
TABLE 2.3 PATHWAY DOSE FACTORS ACE CROUP: ADULT PATNWAY: VEGETATION l ORGAN DOSE FACTORS UUCLIDE l * - * - ** - . .*.- * . . . .. .... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 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 nN 54 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 TE.55 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08 2.10E+08 1.45E+08 3.38t+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE.59 Co.58 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 Co.60 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00Er00 0.00E+00 6.23E+08 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 NI.63 ZN.65 1 04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 RB.86 3.17t+08 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 ) 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 ' SR.89 , SR.90 9.98E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 l l Y.91 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 5.12E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 , ER 95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5,91E+05 0.00E+00 1.19E+09 l NB.95 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 RU.103 4.77E+06 0.00E+00 2.06Es06 0.00E+00 1.82E+07 0.00E+00 5.57E+08 l .............................................................................. , RU.106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 l AC.110M 1.0$E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE.125M 9.66t+07 3.50E+07 1.29t+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TE.127M 3.49E+08 1.25E+08 4.26t+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 l ' TE.129M 2.51E+08 9.37E+07 3.97t+07 8.63E+07 1. 05E+09 0.00E+00 1.26E+09 I 131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.0$E+07 1 133 2.09E+06 3.63E+06 1,11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 CS.134 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 CS.136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 1.92E+07 l 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 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.6AE;08 CE 141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08
............,.................................................................. 1 CE.144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 l L
PR 143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 l ND.147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Rev. O 11 2 37 3/89
I j 1 i i l l TAELE 2.3 PATHWAY DOSE FACTORS i ACE CROUP: TEEN PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCL1DE l.*. .. . - - - - .. - *. .... ... ...* - .... l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI H.3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 P.32 1.60E+09 9.91E+07 6.20E+07 0.00E+00 0.00E+00 0.00E+00 1.34E+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 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9,32E+08 FE.55 1 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 g TE.59 Co.58 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9<91E+08 CO.60 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 ' 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI.63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 ZN 65 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 1173E+08 1.28E+08 0.00E+00 0.00E+00 0.00E+00 4.04E+07 i SR.89 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 ; SR.90 L Y.91 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ZR.95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98t+05 0.00E+00 1.25E+09 NB 95 ! 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU 103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 l RU 106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG.110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE.125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 TE.127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE.129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 1 131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I.133 1.94E+06 3.29E+06 1.00E+06 4.59t+08 5.77E+06 0.00E+00 2.49E+06 CS.134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5,31E+09 2.03E+09 2.08E+08 CS.136 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 4.59E+09 1.78E+09 1.92E+08 6A.140 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2.15E+08 CE.141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 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 Rev. O II 2 38 3/89
1 I I TABLE 2.3 PATHVAY DOSE FACTORS l A0E OROUP: CHILD PATHVAY: VECETATION l ORGAN DOSE FACTORS NUCLIDE l. .... . .. - . .. - - . . . .. .... l BONE LIVER T 80DY TNYROID KIDNEY CI.LLI
...............................................................LUNC 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 0.00 9.25E+07
...............................................................E+00 CR 51 ...............
MN.54 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 FE.55 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40 7.87E+07
...............................................................E+08 FE.59 ...............
Co.58 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 Co.60 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 0,00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.0 2.10E+09
............................................................. 0E+00 N1 63 ................
ZN.65 3.95E>10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 Rt.86 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 0.00E+00 4.51E+08 2.77E+08 0.00E+00 0.00E+00 0.00 2.90E+07
...............................................................E+00 SR.89 ...............
SR 90 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1,39E+09 Y.91 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.57E+10 1,87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.0 2.49E+09
............................................................. 0E+00 ZR.95 ................
NB.95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 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+0 3.97E+08
................................................................. 0 RU.106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 A0 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 3.56t+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE.129M I.131 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47Ev09 0.00E+00 1.02E+09 l 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 1 133 CS.134 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 1.60E+10 2.63E+10 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+C4 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 j CE.144 PR 143 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND.147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 Rev. O 11 2-39 3/89
1 l i TABLE 2.3 PATHVAY DOSE TACTORS ACE GROUP: INTANT PATHVAY: VEGETATION l i ORGAN DOSE TACTORS nUCLIDE I........... ... .... . .. . - j BONE l LIVER T. 80DY THYROID KIDNEY GI.LLI
............................................................... LUNG H.3 ...............
l 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.^0E+00 0.00E+00 P.32 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0 0.00E+00 CR.51 0E+00 ................ l l MN.54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+C0 0.00E+00 0.00E+00 l TE.55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 0.00E+00
............................................................ 00E+00 TE.59 ................. ;
Co.58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 0.00E+00
................................................................ 00.............
NI 63 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 0.00E+00
................................................................ 00 SR.89 ,
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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 0.00E+00
................................................................ 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 RU 103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 0.00E+00 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ .......................................................................... 00 ...
TE.12?M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129M 1 131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 133 CS.134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS 136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA.140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 CE.141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+C0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR 143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND.147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rev. O 11 2-40 3/89
- - _. . . ~ . - -
H [
-f
. . - t if
.i TABLE 2.3 PATHWAY DOSE FACTORS ACE CROUP: ADULT PATHWAY: INHALATION l ORGAN D FACTORS nuCLIDE l....................................OSE .................................
- l. BONE LIVER T. BODY THYROID. KIDNEY GI.LLI
................................................................ LUNG 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 8.64E+04
............................................................. 00E+00 CR.51 .................
MN.54 0.00E+00 0.00E+00 1.00E+02 5.95E+01' 2.28E+01 1.44E+04 3.32E+03 ( FE.55 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 < L 2.46Et04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.2 6.03E+03 l .............................................................. 1E+04 FE.59 ................ Co.58 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO.60 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5 2.85E+05
............................................................. 97E+06 N1 63 ................. -
ZN.65 4.32E+05 3.14E+04 1.45E+04 0.00E+00 - 0.00E+00 1.78E+05 1.34E+04-RB.86 3.24E+04 1.03E+05 4.66E+04 0,00E+00 6.90E+04 8.64E+05 5.34E+04 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 1.66E+04
........................................................... 0.00E+00 SR.89 ...................
SR.90 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 Y.91 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 3.85E+05
........................................................... 1.70E+06-ZR 95 ...................
NB.95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 RU.103 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 1.53E+03 0.00E+00 6.58E+02 0.00E+00- 5.83E+03 5.0 1.10E+05 ! .............................................................. 5E+05 RU.106 ................ AG.110M 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 ? TE.125M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 l.
......................................................................7.06E+04 TE.127M TE.129M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 i 1 131 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 l 2.52E+04 3.58E+04 2.0$E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+0
............................................................................ 3 1 133 CS.134 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 I CS.136 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 f
CS.137 BA 140 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 3.90E+04 4.90E+01 2.57E+0' O 00E+00 1.67E+01 1.27E+06 2.18E+05 CE.141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE.144 PR.143 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND.147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 Rev. O II 2-41 3/89 ' l J. L
t TABLE 2.; .w PATHWAY DOSE FA NORS AGE GROUP: TEEN PATHWk INHA1ATION l OROAN DOSE FACTORS KUCL1DE l.... .. - .- - ... l BONE LIVER T. BODY THYROID K10NEY LUNG G
.........................................................................I.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 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00= 9.28 ..........................................................................E+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 6.27E+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 FE.59 Co.58 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.7BE+05-CO.60 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 0.00E+00 1.51E+04 1.98t+04 0.00E+00 0.00E+00 8.72E+06 2.59E+ ........................................................................... 05 NI.63 ...
IN.65 5.80E+05 3.86t+0* 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 -1.42E+04 RB.86 1.34E+05 6.24E+04 0.00E+00- 8.64E+04 1.24E+06 4.66E+04 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0,00E+00 .1.77
..........................................................................E+04 SR.89 SR 90 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E405 Y.91 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 .1.65E+07 7.65E+35 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+1 ............................................................................ 5 ZR.95 NB.95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 1.86E+04 1.03E+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 0.00E+00 7.43E+03 7.83E+05 1.09E+0 ................................................................,........... 5 ..
RU.106 AG 110M 9.84E+04 0.00E+00 1~24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 TE.125M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE.127M TE.129M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 -1.59E+05 1 131 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5 19E+04 1.98E+06 4.05E+05 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I.133 C5 134 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04-CS 136 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS.137 BA 140 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 CE.141 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE.144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 PR.143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 ND.147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.o2E+05 Rev. O II 2-42 3/89
- t i
TABLE 2.3-PATHWAY DOSE FACTORS ACE GROUP: CHILD PATHWAY: INHA1ATION l ORGAN DOSE TACTORS NUCLIDE l..................................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 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 'O.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 1.5BE+06 2.29E+04 FE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE.59 C0 58 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 Co.60 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7,07E+06 9.62E+04 NI 63 ZN.65 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 RB.86 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 0.00E+00 .1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 SR.90 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 Y 91 1.01E+08 0.00E+00 6.44E+06 0.00E+s0 0.00E+00 1.48E+07 3.43E+05 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR.95 NB.95 1.90E+05 4.18E+04 3.70E+06 0.00E+00 5.96E+04 2.23E+06 6.11E+04 2.35E+04 9.18E+03 6 f;E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 0.00E+00 1..?t+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU.106 1.36E+05 0.00E+00 1.69E+04 'O.00E+00 1,84E+05 1.43E+07 4.29E+05 AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE.127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE.129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 .1.82E+05 I 131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I.133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS.137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR.143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND 147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 Rev. 0 l II 2 43 3/89
I TABLE 2.3 PATHWAY DOSE FACTORS ACE CROUP: INFANT PATHWAY: INHALATION l ORGAN DOSE FACTORS KUCL1DE 1. ' ' .-'-' ' - ...' .....' l BONE LIVER T. BODY THYROID KIDNEY LUNO- CI.LLI H3 0.00E+00 6.47E+02
. 6.47E+02' 6.47E+02 6.47E+02 6.47E+02 6.47E+02-P.32 2.03E+06 1.12E+05 7.74E+04 0.00E+00 0.00E+00 'O 00E+00 1.61E+04 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 0.00E+00 2.53E+04 4,98t+03 0.00EM0 4.98E+03 1,00E+06- 7.06E+03 FE.55 1.97t+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 FE.59 Co.58 1.36t+04 2.35E+04 9.48t+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 0.00E+00 1~.22E+03 1.82E+03 0.00E+00 0.00EMO 7.77t+05 1.11E+04 Co.60 0.00E+00 8.02E+03 1.18EM4 0.00E+00 0.00E+00 4.51E+06 3.19E+04 NI.63 ZN.65 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 RS.86 1.93E+04 6.26E+04 3.11E+04 0.00B+00 3.25E+04 6.47t+05 5.14E+04 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 @ SR.89 3.98E+05 0.00E+00 1.14E+04 0.00EMO 0.00EMO 2.03E+06 6.40E+04 h SR.90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 V Y.91 5.88t+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 i ...............................................................................
r ZR.95
# 1.15E+05 2.798+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NB.95 1.57t+04 6.43E+03 '3.78t+03 0.00E+00 4.72E+03 .4.79E+05 1.27E+04 RU.103 2.02E+03 0.00EMO 6.79E+02 0.00EM0 4.24E+03 5.52E+05 1.61E+04-RU 106 8.688+04 0.00E+00 1.09EM4 0.00E+00 1.078+05 1.16E+07 1.64E+05 AG.110M 9.988+03 7.22E+03 5.00EM3 0.00E+00~ 1.098+04 3.67E+06 3.30E+04 TE.125M 4.76t+03 1.998+03 6.58E42 1.62EM 3 0.00EMO 4.47E+05 1.29E+04 TE.127M 1.67E+04 6.90E+03 2.07t+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE.129M 1.41E+04 6.098+03 2.23E+03 5.478+03 3.18t+04 1.68t+06 6.90E+04 1 131 3.79E+04 4.44E+04 1.96E+04 1.48EM7 5.18E+C\ 0.00E+00 1.06t+03
, I 133 1.32E+04 1.92E+04 5.60E+03 3.56t+06 2.24E+04 0.00E+00 2.16E+03 CS.134 3.968+05 7.03E+05 7.45E+04 0.00EMO 1.90E+05 7.97E+04 1.33E+03 C5 136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18t+04 1.43E+03
...............s...............................................................
C5 137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA.140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 _ CE.141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE.144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.33E+05 9.84E+06 1.48E+05 PR.143 1.40E+04 5.24E+03 6.99EM2 0.00E+00 1.97t+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15EM3 3.22E+05 3.12E+04
\
Rev. 0 l II 2-44 3/89
i f TABLE 2,4 '! ATMOSPHERIC DISPERSION AND DEPLETION PARAMETERS FOR RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3 CALCULATIONS
+
Sector Miles X/Q D/Q N 4.5 2.4E-07 1.0E-09 NNE 2.4 4.7E-07 2.3E-09 NE 2.4 3.2E-07 1.lE-09 ENE 2.6 2.2E-07 5.7E-10 : E 3.5 1.5E-07 2.7E-10 ESE 2.3 3.7E-07 9.5E-10
-SE 3.6 2.4E-07 7.0E-10 SSE 2.0 5.8E-07 3.2E-09 S 4.8 1.0E-07 3.6E-10 i
SSW 4.3 9.2E-08 2.9E-10 SW 3.5 1.2E-07 3.3E-10 WSW l.5 6.9E-07 2.2E-09 W l.7 6.5E-07 2.2E-09 i WNW 3.0 3.7E-07 1.0E-09 L -NW 5.0 2.2E 6.3E-10 NNW 3.4 4.9E-07 1.9E-09 l l l- 1
- sec/m8 a
** m Rev. O l
II 2-45 3/89 ,
l i' TABLE 2.5 CONTROLLINO RECEPTORS, LOCATIONS, AND PATHWAYS (For Dose Calculations required by Radiological Effluent Control 3/4.11.2.3) DISTANCE ,, SECTOR- '(MILES) PATHWAY ACE CROUP N 4.5 Vegetation Child-NNE 2.4 Vegetation Child NE 2.4 Vegetation Child ENE 2.6 Vegetation Child E 3.5_ Vegetation Child ESE 2.3 Vegetation Child SE 3.6 Vegetation Child SSE 2.0 Vegetation Child S 4.8 Cow / Milk Infant SSW 4.3 Vegetation Child SW- 3.5 Vegetation Child WSW 1.5 Vegetation Child W 1.7 Vegetation Child l- WNW 3.0 Vegetation Child NW* - - - NNW 3.4 Vegetation L Child
*No pathway currently exists in this sector out to 5.0 miles.
**In addition to the pathway shown, the plume, inhalation, and ground plane '
pathways are present at each receptor location. 1-l Rev. O II 2-46 3/89
;![
2.3 METEOROLOGICAL. MODEL , 1 2.3.1 -Discersion Calculations Atmospheric dispersion for gaseous releases is calculated using j a straight line flow Gaussian model sim1'ar to the Constant Mean 'I, 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: ' X- k Rq. 2-20 4 = 2.0326 K I j , k k " ' 'A E j(') j Where: X/Q = average concentration normalized by source strength (sec/m3). 2.032 = (2/ w )l/2 . (2 w /16)-l r 6
=
plume depletion factor at distance r for 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. ! K = terrain correction factor (Figure 2.-5) njk = the number of hours meteorological conditions are j observed to be in a given wind direction, wind speed class, k, and atmospheric stability class, J. N = total hours of valid meteorological data throughout the period of release. l. NOTE: If hourly meteorological data are used, all variable subscripts are dropped, njk and N are set equal to 1, and the hourly averaged meteorological variables are used in the model. Rev. O II 2-47 3/89 r
1 r = downwind distance from the release point to the location of interest (meters) iijk - the average windspeed (midpoint of windspeed class, k) measured at the 10 meter level during stability class j, (meters /sec) Ij(r) = the vertical plume spread with a volumetric-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 otherwise-indicated. The equation for calculating Ij(r) is: e (0 8 + 0.5 baf,)! [Eq. 2-30] 3 E3 (r) = the lesser of < OO j [Eq. 2-31) w Where: a = 3 the vertical standard deviation of materials in the plume at distance, r, for atinospheric stability class, j, expressed in meters. (Figure 2.3) 0.5 - the building shape factor, b - the vertical height of the reactor containment structure (79.4 meters) Rev. v II 2-48 3/89
l 2.3.2' Denosition Calculations The relative. deposition per unit area is ' calculated as follows: KD:
.= 0.392 r Where:
D/0 = deposition per unit area normalized by source strength (m-2) Dg = relative deposition rate for a ground level release (m 1) (Figure 2.4) z = the fraction of time the wind blows to the sector of interest. NOTE: If hourly meteorological data are~ used, z is set equal to one. 0.3927 = the width in radians of a 22.50 sector. Other variables are as previously defined. NOTE: All parameters are considered dimensionless unless'otherwise-indicated. Rev. O II 2-49 3/89
-w su ui a ,
i l .2.4 DEFINITIONS OF GASLOS EFFLUENTS PARAMETERS Section of IAUD Definition Initial Use AF = Allocation Factor o' O.5 applied to account 2.1.2 for releases from ooth stacks simultaneously. This factor will limit the dose rate ' contribution from each stack'to 1/2.the limit for the site. B = vertical height of the reactor containment ~ 2.3.1 structure. CG = the alarm setpoint for each plant vent stack 2.1.2 noble gas activity monitor (uci/cm3) CGmax . maximum of the monitor setpoints for the two 2.1.4 stacks Cf -the alarm setpoint for each plant vent stack 2.1.3 effluent release rate monitor (uC1/sec) caux = the Auxiliary Building Ventilation Exhaust 2.1.4 monitor alarm setpoint. (uCi/cm3) ccont = the Containment Atmosphere Gaseous monitor- 2.1.5 alarm setpoint. (uCi/cm3) CI = the setpoint for each plant vent stack Iodine 2.1.7 Monitor. (uC1/cm3) Cp = the setpoint for-each plant vent stack- 2.1.8 particulate Monitor. (uti/cm3) Dg .= relative deposition rate for a ground-level 2.3.2 release (m 1) Do = the total organ dose rate due to tritium, 2.1.6 iodines, and particulates with half-lives greater than eight days in gaseous releases. (mrem /yr). Op = dose to any organ of an individual from 2.2.2 radiciodines, tritium and radionuclides in particulate from with half-lives greater than eight days. (nRem) Rev. 1 II 2-50 8/89
i Section of Ig_r2 Definition- Initial Use Os = skin dose rate at the SITE BOUNDARY due to 2.1.1 noble gases. (mrem /yr) D.t total-body dose rate at the SITE BOUNDARY 2.1.1 due to noble gases. (mrem /yr) Og
= air dose due to beta emissions from noble- 2.2.1 gases. (mrad) 1 0 7- = air dose due to gamma emissions from noble 2.2.1 gases (mrad)
D/Q = the annual average relative deposition at 2.2.2 , [ the location of interest. (m-2) !' 6 - plume depletion factor at distance r for 2.3.1 1 the appropriate stability class I (radioiodines and particulates). FB = the estimated flow rate contribution 2.1 1 associated with the release rate of the batch source. (cm3/sec) L FC - the continuous flow rate contribution of 2.1.1 ).- each plant vent stack. (cm3/sec) l Fy - the flow rate at each plant vent stack. 2.1.1 (cm3/sec) FABV- - the flow rate contribution associated with 2.1.4 the sources in the Auxiliary Building other than the waste gas decay tanks. (cm3/sec) Faux - the total flow rate at the Auxiliary 2.1.4 Building Ventilation Monitor during the l release of a Waste Gas Decay Tank. (cm3/ sec) i ) Fcont - the flow' rate contribution associated with 2.1.5 the release of the Containment Atmosphere. (cm3sec)
/
FGDT - the flow rate contribution associated with 2.1.4 the release of a Waste Gas Decay Tank. (cm3/ sec) Rev. 0 1 II 2-51 3/89
~
Section of 11tra Definition Initial Use K: = terrain recirculation factor. (Unitiess) 2.3.1 Kt = total body dose factor due to gamma 2.1.1 emissions from noble gas radionuclide i. (mrem /yrperuCi/m3) Li - skin dose factor due to beta emissions' 2.1.1 from noble gas radionuclide i. (mrem /yrperuCi/m3) Mi = lir dose ~ factor due to gamma emissions -2.1.1 from noble gas radionuclide i. (mrem /yrperuCi/m3) Ni = air dose factor due to beta emissions 2.2.1 from noble gas radionuclide i. (mrem /yrperuti/m3) njk = number of hours meteorological conditions 2.3.1 are observed to be.in a given wind direction, wind speed class k, and atmospheric stability class j. N~ = total hours of valid meteorological data. 2.3.1 Pt = dose parameter for radionuclide i,.(other 2 . l '. 6 than noble gases) for the inhalation pathway (mrem /yr per uCi/cm3) Qi = total release rate of radionuclide i from 2 .1.1 - - the Plant Vent Stacks. (uC1/sec) Q'i = cumulative release of radionuclide i 2.2.1 during the period of interest. (uci) RPi ,a.o = dose factor for radionuclide 1, pathway 2.2.2 p, and age group a, and organ o. (mrem /yr per uCi/m3) or (m2. mrem /yr per uCi/sec) '
'l Rev. O II 2-52 3/89
Section of Igm Definition Initial Use r - distance from the point of release-to 2.3.1. the location of interest for dispersion calculations. (meters). SF - Safety Factor of 0.5 applied to compensate 2.1.2 for statistical fluctuations, errors of measurement, and non uniform distribution of release activity between the stacks. Ij(r) - vertical plume spread with a volumetric 2. 3 .1 - correction for a release within the building wake cavity, at a distance, r, for stability class, j, expressed in meters. oj - vertical standard deviation of the plume 2.3.1 concentration (in meters), at distance, r, for stability category J. iijk - wind speed (midpoint of windspeed class k) 2.3.1 at ground level (m/sec) during atmosphere stability class J. W' - the dispersion parameter for estimating 2.2.2 the dose to an 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 2.2.2 the location of interest. (sec/m3) X/Q = the highest annual average relitive 2.1.1 concentration at the SITE BO'JNDARY. (sec/m3) (3.3 x 10-6 sec/m3 in the NNW sector) XiB = the concentration of radionuclide i in the 2.1.1 batch release stream, (uti/cm3) as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. Rev. O 11 2-53 3/89
i Section of
-It.tm Definition Initial Use i
Xc. i - the concentration'of.radionuclide i in the 2.1.1 continuous release stream at each stack as sampled in accordance with-Radiological- Effluent Control- 3/4.11.2.1, Table 4.11-2. (uti/cm3) Xy i = the concentration of radionuclide i present- 2.1.1 at each plant vent stack. (uci/cm3) i XyG - the concentration of noble gases present at 2.1.2 each plant vent stack due to the combined sources as calculated from the radionuclide 1 , l concentrations determined from the analysis ' of_the appropriate samples taken in -! accordance with Radiological Effluent-Control 3/4.11.2.1', Table 4.11-2. (uci/cm3) XyI = the concentration of radionuclide present ' 2.1.7 at each plant vent stack due to the combined sources as calculated from the radionuclide concentration determined from the analysis of the appropriate ! samples taken in accordance with i Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. (uti/cm3) L XiABV = the concentration of noble gas radionuclide 2.1.4 i in the Auxiliary Building ventilation stream due to sources other than the waste : gas decay tanks. (uC1/cm3) L Xi aux = the concentration of noble gas radionuclide 2.1.4 i at the Auxiliary Building ventilation monitor during a waste gas decay tank release.. (uci/cm3) l Rev. O II 2-54 3/89
s i Section of' Igng Definition: , Initial Use Xi cont - the' concentration of noble gas radionuclide - 2.1.5 i i in the containment release stream as sampled in accordance with Radiological Effluent -; Control 3/4.11.2.1, Table 4.11-2. (uCi/cm3) XiGDT - the concentration of noble gas radionuclide 2.1.4 : i in the waste gas decay tank as sampled , in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. (uCi/cm3) _ Xpy = the concentration of particulates present 2.1.8 at each plant vent stack due to the
- p combined sources as calculated from the radionuclide concentration determined '
from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2 (uti/cm3) ' z i
- the fraction of time the wind blows to the 2.3.2 p sector of interest 1.1 - conversion factor of mrem skin dose per .2.1.1 L
mrad air dose. 500 - the dose rate limit to the total body of 2.1.2 an individual in an unrestricted area due to noble gases. (mrem /yr) 3000- ,
- the dose rate limit to the skin of the- 2.1.2 body of an individual in an unrestricted area due to noble gases. (mrem /yr) 1500 - the dose rate limit to any organ due to 2.1.7 iodines, tritium, and particulates with half-lives greater than eight days.
(mrem /yr) Rev. 1 11 2-55 8/89
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. PLUME TRAVEL DISTANCE (KILOMETERS) l' L Vertioni Standard Davistion of Material in a Plume (Letters denote Pasquill Stability Class)
NOTE: THESE ARE STANDARO RELATIONSHIPS AND MAY HAVE TO BE MOOlFIED POR CERTAIN TYPES OF TERRAIN ANO/OR CLIMATIC CONDITIONS (E.G., VALLEY, DE8ERT, OVE R WATE R). Figure 2.3 Rev. O II 2-58 3/89
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_ _ _ . _ _ . . . ~ , a SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 LAMPLING LOCATIONS Sampling locations as required in Radiological- Effluent Control 3/4.12.1, Table 3.121 are described in Table 3.1 and shown on the map-in Figure 3.1. 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 be performed as specified in Section 2.2.4.
' The sampling locations shown on Table 3.1 are the minimum locations required for compliance with Radiological Effluent Control 3/4.12.1.
If desired, additional locations may be monitored as special studies to evaluate potential pathways of exposure without adding such locations. to the monitoring program given in Table 3.1. 3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3.- TV 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 participant laboratories and specifies control limits. Results consistently higher Rev. 0 l 11 3-1 3/89
- . - - ' - ' ' ' ' ' ' ' ' ' ~ ' ' ' ' ' '
=_.- _ - _ _ _ . . .
or lower than the known values or outside the control'11mits 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 Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results of the program are included in the Annual Radiological- ; Environmental Operating Report, as required by CPSES Technical Specification 6.9.1.3. Rev. O j II 3-2 3/83
-.1 Table 3,1 Environmental Sampling Locations Sampling Location Sample
__ Point (Sector - Miles) Type (I) Al N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A A3 E-3.5 (Children's Home) A A4 SSE-4.5 (Glen Rose) A AS S/SSW-1.2 A A6 sg.12.3 (Control) A A7 SW/WSW-0.95 A A8 NW-1.0 A R1 N-1.49 (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 RIO ENE-5.0 R R11' E-0.5 R Rev. O II 3-3 3/89
, Table 3.1 (Continued) Environmental Sampling Locations Sampling Location Sample. Point (Sector - Miles) Type (I) R12 E-1.9 R R13 E-3.5 (Children's Home) R-R14 E-4.2 -R RIS ESE-1.4 R , R16 ESE-4.7- R = R17 SE-1.3 ' R' i R18 SE-3.85 R '[ R19 SE-4.6 R R20 SSE-1,3 R R21 SSE-4.4 (Glen Rose) R R22 -SSE-4.5 (Glen Rose) R R23 S.I.$ R R24 S-4.2 R R25 SSw.1.1 R R26 SSw-4.4 (State Park)- R R27 Sw-0.9 R R28 Sw.4.8 (Girl Scout Camp) R R29 Sw-12.3 (Control) R R30 wSw.l.0 R R31 WSW-5.35 R l Rev. O II 3-4 3/89
- . .-. _. . . ,-. . - . . --- - ~ - .
l 3 ', 4 Inble 3.1 Environmental Sampling Locations-Sampling Location Sample' y Point (Sector - Miles) Type U) R32 WSW-7.0 R R33 W-1.0 ' R 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 i R R41 NW-9.9 (Tolar) R , 1 R42 NNW-1.35 R l R43 NNW-4.6 R SW1 N-1.5 (Squaw Creek Reservoir Marina) SW j SW2 N-9.9 (Lake Granbury) SW/DW( } SW3 N-19.3 (Control-Brazos River) -SW SW4 NE-7.4 (Lake Granbury) SW SWS ESE-1.4 (Squaw Creek Reservoir) SW(3) SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW( (5i 1 GW1 W-1,2 (NOSF potable water) GW l (4),(5) GW2 WSW-0.1 (Plant potable GW water) Rev. O II 3-5 3/89
t t
-Table 3.1 (Continued)
Environmental Sampling Locations Sampling Location Sample Point (Sector - Hiles) Type 5U t>) GW3 SSE-4.6 (Glen Rose) GW
.t2i,t3s GW4 N-9.8 (Granbury) GW-t3>
1 GW5 N-1.45 (Squaw Creek Park) GW SSI NNE-1.0 (Squaw Creek Reservoir) SS i SS2 N-9.9 (Lake Granbury) SS SS3 NE-7.4 (Lake Granbury) SS M1 SSE-2.2 M M2 not used(6) g M3 not used(6) g M4 SW-13.5 (Control) M F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FP1 ENE-9.0 (Leonard Bros.' Pecan Farm)FP FP2 E-4.2 (truck farm) FP FP3 SW-13.5 (Control) FP BL1 N-1.45 BL BL2 SW-1.0 ( BL BL3 SW-13.5 (Control) 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. Rev. O II 3-6 3/89
(2) The municipal water sys' tem.for the' City of Granbury is supplied by
- .ca water from Lake Granbury (location SW2) and ground well water (locationGW4). Each of these input supplies for the Granbury municipal water system is sampled. These samples are not required for compliance with Radiological Effluent Control. 3/4.12.1, Table 3.'12-1, because they are not.affected by. plant discharges.
-(3) This sample (location SW5) is representative of discharges from Squaw-Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury.
(4) The plant potable water is supplied by surface water from Squaw Creek Reservoir (location SW6) and ground well water (location 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 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 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. (6) Due to the current availability of milk sampling locations, milk samples are taken at only two locations (i.e., one sample and one control). If additional milk sampling locations are identified in future land use census, this table will be revised to include up to a maximum of 3 samples and one control, as indicated in the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1 Table 3.lbl. (7) Per the Radiological Environmental Monitoring Program given in Radiolo.gical Effluent Control 3/4.12.1, Table 3.12-1, broad kif vegetation is required to be sampled only when milk sampling is not Rev. O i 11 3-7 3/89
n; ;; f' , ic m peformed at all required locations. Broad leaf sampling will be performed at the specified locations-if milk samples are unavailable. *
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APPENDIX A PATHWAY DOSE RATE PARAMETER Pg (inhalation) = K' (BR) DTAg (gq , g.g) where: Pi = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m3 The dose factors are based on the critical individual organ for the child age group. K' = conversion factor, 106 pCi/ microcurie BR = 3700 m3/yr, breathing rate for child (Ref. 2, Table E 5) DFAj = the maximum organ inhalation dose factor for the child age group for the ith radionuclide (mrem /pC1). Values are taken from Table E9, Reg. Guide 1.109(Ref.2) Resolution of the units yields: P g (inhalation) = 3.7 x 10' DFAg (aRem/yr per uC1/m') (Eq. A-2) The latesc NRC Guidance hht deleted the requirement to determine Pi (ground plane) and Pi (food). In aodition, the critical age group has been changed from infant to child. Rev. O II A 1 3/89
- . - - - - - - - . - - , _ - - - - , _ _ - - - - - - -- - - - - - - - - - - - - - - - - - - - - , - , - _ . - - . -----_ _--_-__,_,_-_, M
1 APPENDIX B I INHALATION PATHWAY DOSE FACTOR (R i.a.o) R I a g,,,, k' (BR) (DTAg,,,,) (arem/yr per microcurie /as ) [Eq. B-1) where: k' conversion factor, 106 pC1/ microcurie BR breathing rate, 1400, 3700, 8000, and 8000 ::3/yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E 5) DFAi ,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA i a.o. Values are taken from Tables E 7 through E 10 Reg. Guide 1.109 (Ref.2) Rev. O II B 1 3/89 l l 4
APPEND 1X C GROUND PLANE PATHWAY DOSE FACTOR G(R j) 7 R = k' k" (SP) DFG g [(1-e "Ai ")/Ag ] [Eq. C-Il where: k' = conversion factor, 106 pCi/ microcurie k" = conversion factor, 8760 hr/yr A g = decay constant for the ith radionuclide, see -1 t - the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs) ; DFGj = the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2). Values are taken from Table E 6, Reg. Guide 1.109 (Ref. 2). These values apply to all age groups. Oose factors are provided for the total body and skin only. 00ses 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 Rey, 1 II C-1 8/89
, _ , _ e W
l l APPENDIX D C GRASS COW MILK PATHWAY DOSE FACTOR (R 1,,,o) ; R
, = k' [(Q 7 xUg)/( + A ,)] x (F,) x (r) x (DFLg,,,,) x
[((f px f,)/ Y )p + ((1-f xp f,) e ~
- i*h)/Y,1 e" Yf IEq. D-Il ;
where: k' = conversion factor,106 picoeurie/ microcurie (pCi/uct) Qp = 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 l groups, respectively (R.G. 1.109) Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG 0133) Ys = agricultural productivity by unit area of stored feed, l 2.0 kg/m2, (NUREG 0133) l Fm = stable element transfer coefficient (Table E 1, R.G. 1.109) l r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E 15 R.G. 1.109) l DFli ,a,o = the ingestion dose factor for organ, o, and the ith j radionuclide for each respective age group, a (Tabiss 1 E-11 to E-14, R.G. 1.109) i
= decay constant for the ith radionuclide, sec-1 A, = decay constant for weathering, 5.73 x 10*7 see -l (NUREG 0133) l tr = 1,73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, R.G.1.109)
Rev. O II D-1 3/89
- ----...-.u.. . , , , , - . . . .
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. 1 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, RC t is based on (X/0): C R t a.o
= k'k F, Q7UAP DE t,,,o (.75 (.3/g)) (Eq. D-2) where:
k = 103 grams /kg H = 8 grams /m3, absolute humidity of the atmosphere
.75 = fraction of total feed grass mass thr.t is water .5 = ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-0133)
DFLt .a.o = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-Il to E 14, R.G.1.109) All other parameters and values are as given above. C NOTE: Goat milk pathway factor, R i.a.o will be computed using the cow-milk pathway factor equation. Fm factor for goat milk will be from Table E-2, R.G.1.109. Rev, O II D-2 3/89
I APPENDIX E ! COW MEAT PATHWAY DOSE FACTOR (RM i,a o) R"g,,,, = P (Q p xUAP) (i* w}
- IIf ) x (r) x ( Mg,,,o) x
(((f px f,)/Y ) p+ ((1 - f f,)pe' A *h)/Y,) i x e~ ^1"f (Eq. E-ll ' where: ' k' = conversion factor,106 picoeurie/ microcurie (pCi/uti) - QF = cowconsumptionrate,50kg/ 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) l Fr - 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 (Table E 15. R.G. 1.109) DFli ,a o = the ingestion dose factor for organ, o, and the ith ; radionuclide for each respective age group, a (Tables E-Il to E-14, R.U. 1.109) ! A i - decay constant for radionuclide i, sec*l A, = decay constant for weathering, 5.73 x 10 7 sec -1 (NUREG 0133) tr = 1.73 x 106 sec, the transport time from pasture to receptor (NUREG 0133) i th = 7.78 x 106 sec, the transoort time from crop to receptor (NUREG 0133) Rev. O II E-1 3/89 __-_.__.____.__________________________.m_._ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _
1 APPENDIX E (CONTINUED) Yp agricultural productivity by unit area of pasture feed grass. 0.7 kg/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 based on its airborne concentration rather than the deposition. Therefore R N1 is based on (X/Q): 1 M i R t a.o " I f 9TUAP (DE x 0.75 x (0.5/H) t.a.o [4. F-2] { 1 l where: All terms are as defined above and in Appendix D. Rev. O II E 2 3/89 l l
I APPENDIX F. ' Y VEGETATION PATHWAY DOSE FACTOR (R j y ) R
,,, = k' x (r/ (Y, ( Ag + A,D ) x M g ,,,,) x
((h ft* r
+ tif f e i*h) (Eq. F-1) where:
k' = 106 picoeurie/ microcurie (pCi/uti) UL A = the consumption rate of fresh leafy vegetation, 0, 26, a2, 64 i kg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) T US = the consumption rate of stored vegetation, 0, 520, 630, A 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) fl the fraction of the annual intake of fresh leafy vegetation grown locally,1.0 (NUREG-0133) f g = the fraction of the stored vegetation grown locally .76 (NUREG-0133) t t = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds (Table E-15. R.G. 1.109(24 hrs)) t h = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds (Table E-15, R.G.1.109 (60 days)) a Rev. O II F-1 3/89 t i l L l '_ .
APPENDIX F (CONTINUED) yh the vegetation areal density, 2.0 kg/m2 (Table E-15, 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, R Y1 is based on (X/0) R
,,,, = k'k (U f +U 8 f) (DM,t.a a) (.75 (.5/H)) (Eq. F-2) where: l All terms are as defined above and in Appendix D.
i i i l I l-I I i i Rev. O 11 F-2 3/89
APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS i
?
G0 Rev. I 8/89
6 t ( i SUPPLEMENTAL GUIDANCE STATEMENT #1
SUBJECT:
LOWER LIMITS OF DETECTION FOR RADIOLOGICAL ANALYSES REQU LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROL ACTION STATEMENTS ' Radiological Effluent Control 3/4.3.3.4, Action Statements 31 and 32 allow for ' effluent releases to continue when specified liquid effluent monitoring ; instrumentation is inoperable if grab samples are collected and analyzed for radioactivity at a lower limit of detection (LLD) of no more than 10'7 u ti/ml . The basis for this LLD is Regulatory Guide 1.21, Appendix A, Section B.3, which states that the sensitivities of analyses of liquid i effluents should be sufficient to permit the measurement of the following concentrations: 10-7 uC1/ml by gross radioactivity measurements; 5x10-7pC1 / mi of each gamma emitting radionuclide; 10 5 u C1/ml of each of the dissolved and entrained noble gas radionuclides; 10 7 u ti/ml of gross alpha radioacti.ity; 10 5 pC1/ml of tritium; and 5x10 8 uC1/ml of strontium -89 ano strontium -90. 1 Based on this guidance, compliance with the action statement may be achieved by analysis for gross gamma activity with a LLD of 10-7 pC1/mi or by gamma l isotopic analysis for principal gamma emitters with an LLD of 5x10-7 pCi/ml. ; If gamma isotopic analysis is performed, the 5x10-7 pC1/ml LLD shall apply l to those radionuclides listed in Notation 3 of ODCM Table 4.11 1. l 1 4 1 l l
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l l l G1 Rev. 1 1 8/89
i SUPPLEMENTAL GUIDANCE STATEMENT #2 '
SUBJECT:
LOWER LIMITS OF DETECTION FOR DISSOLVED AND ENTRAINED REQUIRED BY THE LIQUID WASTE SAMPLING AND ANALYSIS PROGR Radiological Effluent Control 3/4.11.1.1, Table 4.11 1, requires that one batch per month of batch releases be sampled and analyzed for dissolved and entrained gases at an LLD of 1x10-5 uCt/ml. For purposes of implementing this requirement, it is assumed that the required LLD applies to those noble gas isotopes listed in Notation 2 of ODCM Table 4.112. I l Il l l I l l G-2 Rev. 1 8/89
I SUPPLEMENTAL GUIDANCE STATEMENT #3 l
SUBJECT:
TRITIUM LEAKAGE FROM THE TURBINE GENERATOR PRIMARY WATER COOLING SYSTEM (TGPWCS) The purpose of this statement is to provide guidance for handling tritium detected in the Turbine Building sumps due to leakage from the TGPWCS, when there is no primary to secondary leakage. (Note: Tritium is used in the TGPWCS as a tracer to detect leakage of cooling water into the generator coils.) Discharge of the Turbine Building Sumps to the Low Volume Retention Pond may continue when tritium is detected in the Turbine Building Sumps, due to known leakage from the TGPWCS, provided that: (1) the tritium concentration does not exceed the 10 CFR 20 limit for release to an carestricted area (3x10 3 uCi/ml); and (2) there are no detectable principal gamma emitters or 1 131. Radiological Effluent Control 3/4.11.1.1, Table 4.11 1, requires that Turbine Building Sump discharges be diverted to the Waste Water Holdup Tanks when radioactivity is present in the sumps at concentrations greater than or equal to the maximum LLD values given in Table 4.11-1. For tritium, the value established for required diversion is lx10 5 uCi/ml. These requirements are established based on acceptable activities in the sump resulting from primary-to secondary leakage. The guidance which allows discharges of tritium to continue to the Low Volume Retention Pond up to concentrations of 3x10'3 uC1/ml is acceptable since the total activity of tritium is a known, fixed quantity. (Note: The maximum inventory of tritium in the TGPWCS is approximately 700 mci.) Additionally, the dose associated with the release of tritium, due to TGPWCS leakage, is negligible, as demonstrated by the calculation shown below. The total activity of tritium discharged due to TGPWCS leakage shall be determined from sampling of the TGPWCS and reported in the Semiannual Radioactive Effluent Release report. G-3 I Rev. 1 ' 8/89
k CALCULATION OF DOSE DUE TO TRITIUM LEAKAGE FROM THE TGPWCS ASSUMPTIONS:
- 1. The maximum inventory of tritium (700 mci) in the TGPWCS is released to the Low Volume Retention (LYR) Pond.
- 2. The volume of water in the LVR Pond is IE+07 gal.
- 3. The average discharge flow rate from the LVR Pond to the Circulating Water Discharge is 600 gpm.
- 4. The duration required to release the LVR Pond is 14 days (336 hrs).
- 5. The minimum required dilution flow of 500,000 gpm is available, The dose due to the release of the LVW Pond is calculated using ODCM Equation 1 8:
D - At tk Ct Fk Where: At - the dose conversion factor for tritium; 8.96E+00 mrem /hr per pC1/ml (from ODCM Table 1.1) tk - release duration; 336 hrs (from assumption 5) i l-t Cj - the concentration of tritium for the release. The average tritium concentration for the release is determined by dividing the total tritium activity j by the total volume of water in the pond which results in an average tritium concentration of 1.85E-05uti/mi G4 Rev. 1 8/89
4 I Fk = the average dilution %: tor during the release. The average dilution factor is calculated by dividing the average effluent flow rate by the average circulating water flow rate, resulting in a value of 1.2E 03. Therefore,: 0 f8.96E+00 mrem /hrh(336 hrs)(1.85E05pCi/ml)(1.2E03)
\ uCi/mi f D - 6.68E 05 mrem The calculated dose of 6.680 05 mrem is 2.2E-03% and 6.7E 04% of the annual dose limits for the total body and any organ, respectively.
I i G-5 Rev. 1 ' 8/89
SUPPLEMENTAL GUIDANCE STATEMENT #4
SUBJECT:
SAMPLING OF CCW DRAIN TANK Radiological Effluent Control 3/4.11.1.1. Table 4.11 1, requires that the CCW Drain Tank be sampled and analyzed on a batch btsis prior to release. This batch sampling requirement may be fulfilled by routing the contents of the CCW Drain Tank to the Waste Water Holdup Tanks and performing the required batch sampling prior to discharge of the Waste Water Holdup Tank. I G6 Rev 1 l 8/89
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i I i i PROCESS CONTROL PROGRAM
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1 t L i b i TU ELECTRIC COMANCHE PEAK STEAN ELECTRIC STATION Revision 0 April 1989
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i TABLE OF CCNTENTS Pace ; List of Figures 111 Definitions iv
1.0 INTRODUCTION
11 , 1.1 PURPOSE 11 i 1.2 SCOPi' I 11 i 1.3 PRECAUTIONS / LIMITATIONS 11 ! 1.4 RESPONSIBILITIES 12 ' 2.0 RADICACTIVE WASTE PROCISSINC REQUIREMENTS 21 2.1 SOLID RADI0 ACTIVE WASTE 21 2.1.1 Operability criteria 2.1.2 Tests / Inspections 21 2.1.3 Basis 21 22 2,2 MAJOR CHANCES TO LIQUID CASEOUS & SOLID 22 RADVASTE TREATMENT SYSTEMS 3.0 PROGRAM DESCRIPTION 31 3.1 PROCESSING OF WET RADIDACTIVE WASTE 31 3.1.1 Processing Methods 31 3.1.2 Processing System Description 31 2 3.1.3 Prequalification Testing 31 3.1.4 System Qualification Tests 31 + l 3.1.5 Equipment /Systen Operability Requirements 32 3.1.6 Batch Preprocessing Sampling 32 3.1.7 Surveillance Testing 32 3.1.8 Acceptance Criteria 33 3.1.9 Correceive Actions 33 l 3.2 PROCESSINC OF DRY ACTIVE WASTE 34 3.3 MIXED WASTE 35 l' 4.0 VASTE CLASSIFICATION AND CHARACTERIZATION 41 4.1 WASTE CLASSIFICATION 41 i Rev. 0 4/89 4
n- 3 i 1 i i l TASI.E OF CONTENTS (cont) gagg I l 4.2 WASTE CHARACTERISTICS ' 41 5.0 SPECITIC VASTE STREAM PROCESSING DESCRIPTIONS 51 5.1 WET RADI0 ACTIVE WASTE STREAMS 51 5.1.1- Resins 1 5,1.2 Cartridge Filters 51 ) 5.1.3 Evaporator Concentrat*J 52 5.1.4 Studge 52 ! 5.1.5 53 ! Miscellaneous Liquids 53 j 5.2 DRY ACTIVE WASTE 53 ) 6.0 ADMINISTRATIVE CONTROLJ 61 6.1 PROCEDURES 61 I i 6.2 QUALITY ASSURANCE 61 I 6.3 CHANCES TO THE PCP 61 6.4 DOCUMENTATION 62 6.5 TRAINING 62
7.0 REFERENCES
71 1 I 11 Rev. 0 4/89 4
- ~ -. . _ _
LIST OF FICURES Figure No. g 11 CPSES Radioactive Waste Management 14 Organizational Responsibilities 51 Dewatering Process Flow Chart 54 52 DAV Process Flow Chart $,$ 111 Rev. 0 4/69 4 4
i i I DEFINITIONS Terms in this manual which have a specific definition or meaning are capitalized (e.g. "0PERA81LITY"). Definitions for such capitalized terms i are found in Section 1.0 of the CPSES Technical Specifications, with the exception of " PROCESSING" which it defined below: < PROCESSING PROCESSING meets thall burial shipping and be theground conversion of wet radioactive waste into a form that requirements. I i 4 l l l l l 1
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__ - - - ~ . . - - . -- - - - - - - SECTION 1.0 i INTRODUCTION L 1.1 PURPOSE i The purpose of the CPSES Process Control Program (PCP) is to establish i a program which will provide reasonable assurance that all radioactive wastes generated at CPSES that are to be disposed of at a land disposal facility are PROCESSED and packaged such that applicable Federal regulations, State rules and regulations, and disposal site criteria are satisfied. The PCP contains a general description of the methods , for controlling the PROCESSING and packaging of radioactive wastes. ; ! specific parameters for each method, and the administrative controls ' l and quality assurance required to ensure compliance with applicable i regulations and requirements. 1,2 SCOPE ! This progras defines criteria for the PROCESSING of the following waste streams for disposal at a land disposal facility: l (1) Wet Wastes (a) Resins (bead and powdered) . (b) Cartridge Filters ! (c) Eysporator Concentrates (d) Sludge (e) Miscellaneous liquids (2) Dry Active Wastes (DAW) (a) Compactible (b) Noncompactible 1.3 PRECAUTIONS / LIMITATIONS Except as specifically described in this document, the following general precautions and limitations apply to the PROCESSING and , i I packaging of all radioactive wastes generated at CPSES for disposal at ' a land disposal facility. These precautions and limitations shall be included in appropriate station or vendor implementing procedures. (1) No liquid asterials within'the scope of this program shall be packaged for disposal. l_ (2) No package shall be loaded for shipment if it has any indication of a hole or failure. These packages shall either be repacked, or placed in an overpack. (3). Radioactive vaste shall not be packaged for disposal in cardboard or fiberboard boxes. 11 Rev, 0 4/89 l 4
(4) Only H16 h Integrity Containers (HIC) approved for burial at a land disposal facility shall be utilized for packaging dowatered wastes when vaste form stability is required per 10CFR61. (5) No objects or materials shall be placed into HICs that may cause chemical or physical damage to the container per the vendors 10CTR61 Topical Report or other Federal, State or Burial Facility requirements. (6) As auch as practical, polyethylene HICs shall be kept out of direct sun 118 ht to prevent ultraviolet li6he degradation. Protection from direct sunli he S shall be provided when HICs are stored for extended periods. (7) Radioactive waste shall not be packaged for disposal if it is pyrophoric. Pyrophoric materials contained in radioactive vaste shall be treated, prepared, and packaged to be nonflammable prior to disposal. (8) Radioactive waste in gaseous form shall not be packaged for disposal. (9) Radioactive vaste containing hasardous material shall be treated to reduce to the maximum extent practicable the potential hazard from the nonradiological materials. Biological, pathogenic or infectious material is not expected to be produced and will be handled on a case by case basis. (10) Radioactive wastes shall not be packaged for disposal if it is readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water. (11) Radioactive waste shall not be packaged for disposal if it contains, or is capable of generating quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling or disposing of the waste. (12) Samples shall be handled and collected in accordance with applicable CPSES procedures and in keeping with A1 ARA principles. (13) PROCESSING evolutions should be periodically monitored for adverse chemical reactions and temperature changes. 1.4 R55PON815!LITIE5 1.4.1 Vice President. Nuclear Operations It is the responsibility of the Vice President, Nuclear Operations, to ensure that the requirements contained in this manual are achieved during the PROCESSING of radioactive vaste by developing appropriate administrative and laplementing procedures. An organizational chart showing specific station 12 Rev 0 4/89 a
i i t responsibilities the Vice President, for radioactive waste PROCESSING assigned by i Nuclear Operations. is shown on Figure-1 1. The Vice President. Nuclear Operations, is responsible for approving changes to this PROCESS CONTROL PROGRAM, as required by Technical Specification 6.13. .
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1.4.2 Station Operations Review Consittee ' The Station Operations Review Committee (SORC) shall review the Topical Reports and Process Control Programs of vendors selected to provide waste processing services or products prior to their initial use at the station. Any subsequent revision to these documents shall also be reviewed by SORC prior to the ! initial use of the revision. These reviews shall ensure l compatibility with Station equipment and operation. Additionally. SORC is responsible for reviewing changes to this PCP prior to implementation. 50RC also reviews station administrative and implementing procedures for radioactive , vaste processing activities. ' 1.4.3 Radiation Protection Manaaer i The Radiation Protection Manager (RPM) is responsible for coordinating the review of, and for approving, vendor procedures for waste processing prior to the initial use of the documents at the station. He shall also approve any revisions to these documents prior to initial use of the revision. Review of vendor procedures for waste processing shall include technical review by the Operations Chemistry, and Results Engineering departments. 1.4.4 Other Responsibilities The Manager, Plant Operations, the Chemistry and Environmental Manager, and the Results Engineering Manager sh:11 support the RPM in reviewing vendor procedures for waste processing. ' i l 1 13 Rev. 0 4/89 4
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SECTION 2.0 RADICACTIVE WASTE PROCESSING REQUIREMENTS 01 SOLID RADIOACTIVE WASTES OPERABILITY CRITERIA 2.1.1 Radioactive wastes shall be PROCESSED in accordance with this PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site. APPLICABILITY: At all times. COMPENSATORY MEASURES:
- a. With PROCESSING not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct this PROCESS CORTROL PROGRAM, the procedures, and/or the Waste Processing System as necessary to prevent recurrence,
- b. With PROCESSING not performed in accordance with this PROCESS CONTROL PROGRAM, test the improperly PROCESSED waste in each container to ensure that it asets buria. ground and shipping requirements and take appropriate administrative action to prevent recurrence.
- c. The provisions of Technical Specifications 3.0,3 and 3.0.4 are not applicable.
TESTS / INSPECTIONS 2.1.2 Satisfactory PROCESSING of wet radioactive wastes (e.g. , filter sludgos spent resins, evaporator bottoms, boric acid solutions, and sodium sulf.*~ PROGRAM: solutions) shall be verified in accordance with this PROCESS CONTROL
- a. If any test specimen fails to verify estisfactory PROCESSINC. the PROCRSSINC of the batch under test shall be suspended until such time as additional testing can be performed, alternative PROCESSING parameters can be determined in accordance with this PROCESS CON'!1LOL PROGRAM, and subsequent testing verifies satisfactory PROCESSINC. PROCESSING of the batch may then be resumed using the siternative PROCESSING parameters determined by this PROCESS CORTROL PROGRAM; This PROCESS CONTROL PROGRAM shall be modified as required, as provided in Technical Specification 6.13, to assure satisfactory PROCESSING of subsequent batches of waste; and 21 Rev. 0 4/89 l l
4 _. . . . . . . . . . - .. . ~.. .
{b ) I b. With the installed equipment incapable of meeting Operab(11 v i' criteria 2.1.1. above, or declared inoperable, restore the ' equipment to CPERA4LE statn or provide for contract capability. to process wastes as necessa ry to satisfy all aplicable i transportation and disposal requirements. ) BASIS 2.1.3 This requirement toplements the requirements of 10CTR50.16s and ' Ceneral Design Criterion 60 of Appendix A to 10Cf1L Part 50. The process parameters included in establishing this PROCESS CONTROL PROCPM may include, but are not limited to, waste type, vaste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste pr'.act;al . chemical constituents, mixing and curing times, or dewatering parameters, 22 tAJCR CHANCES SYSTLMS* TO LIQUID. CASE 0VS AlfD SOLID RADVASTE TRE Licensee. initiated major changsg to the Radwaste Treatment Systems ' (liquid, gaseous, and solid): a. l Shall be reported to the Commission in the Sealannual Radioactive t Effluent Release Report for the period in which the evaluation was reviewed by the 50RC. The discussion of each change shall contain- , 1) !' A suasary of the evaluation that led to the determination that the change could be made in accordance with 10CTR50.59:
- 2) Sufficient detailed fr'ormation to totally support the reason for the change without benefit of additional or supplemental information:
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with ot;.or plant systems; a) An evaluation of the change, which shows the predicted releases of radioaative materials in liquid and gaseous effluencs ana/or t quantity of solid waste that differ from those previously '
predicted in the License application and amendments thereto: S) An evaluation of the change, which shows the expected maximwn l espesures to a MEMSER OF THE FUSLIC in the UNRESTICTID AAEA and - to the general population that differ from those previously estimated in the License application and amendments thereto: ,
- 6) A comparison of the predicted releases of radioactive asterials, in liquid and gaseous effluents and in solid vaste.
to the actual releases for the period prior r' when the-change. is to be made; 22 Rev. 0 4/89 4
- 7) An estimate of the~ exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the chang:~was reviewed and found acceptable by the SORL.
- b. Shall become effective upon review and acceptance by the SORC.
- Licensees may choose to submit the information called for in this Requirement as part of the annual FSAR update.
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t l l l l l c I 23 Rev. O L 4/89 e
SECTION 3.0 PROGRAM; DESCRIPTION s 3.1 PROCESSING OF VET RADIOACTIVE VASTE 3.1.1 PROCESSINC Methods Wet radioactive waste generated at CPSES shall be PROCESSED inte-a form acceptable for disposal'at a licensed facility by dowatering. - PROCESSING shall be performed utilizing vendor supplied- services and equipment operating in accordance with the-vendor's Process Control Program (PCP) and procedures. Any vendor selected to provide services or products ,used for toepliance with 10CFR61 stability requirements shall have a topical report addressing 10CFR61 requirements under review or-i approved by the NRC. When a vendor is initially selected..this document shall be revised to incorporate by- reference the vendor's Topical Report and PCP The Topical Reports and PCPs of multiple vendors may be referenced in this PCP even if all - vendors are not actively providing services or products at CPSES. However,'if any vendor is selected whose documents are not referenced, this document shall be revised to reference: them. 3.1.2 Processina Systes Description Detailed descriptions of the vendor's PROCESSING systes shall bei included in the. vendor's Topical Report. 3.1.3 Procualification Testina Prequalification tests shall-be performed on each type of-wet-radioactive waste stress to demonstrate the ability of the process to produce an acceptable waste form per the requirements of 10 CPR 61. This prequalification testing is performed by the vendor and documented-in the vendor's Topical Report. 3.1.4 Systea Qualification Tests Prior to the initial PROCESSING of a given waste stream type using a specified process, a test shall be conducted to demonst. ate the ability of the process system to produce an acceptable waste form over the range of critical parameters identified during the prequalification testing. Bounds for critical-parameters and specific operating limits shall be specified in the vendor's PCP. These tests shall be performed on laboratory scale or full scale specimens and shall ensure that the acceptance criteria specified in Section 3.1.8 are achieved. 31 Rev. 0 l 4/69 d
3.1.5' Eauipment/ System Operability Requirements Prior to each PROCESSING evolution, the vendor shall demonstrate' operability of the processing equipment which shall include but not be limited to the following: (1) Control Panel (2) Instrumentation and controls (3) f.echanical Equipment (4) Electrical Equipment The operability test shall be performed in.accordance with station procedures and the vendor's PCP and procedures. 3.1.6 Batch Preprocessing Samolina Each batch of waste offera- for PROCESSING shall be sampled and-analyzed, as appropriate, in accordance with station procedures and the vendor's PCP and the Topical Report that addresses the 10CFR61 stability requirements. This sampling shall: (1) Provide necessary data to estimate curie content and perform the waste classification analysis. (2) Ensure that waste streaa parameters are within the bounds for critical parameters established in the vendor's PCP and 10CFR61 Topical Report. NOTE: Results of waste stream chemical analyses shall be-reviewed by the PROCESSING vendor to ensure chemical constituents do not exist which could cause adverse chemical
. reactions during the devatoring process or react adversely with the dowatering container.
3.1.7 Testina/ Inspections To satisfy the Test / Inspection requirements of Section 2.1.2 of this Program, a test or inspection shall be performed for each dewatering evolution to ensure that the applicable acceptance criteria of Section 3.1.8 are-achieved. This is accomplished by verifying that a specified and point is achieved for each dowatering evolution of the actual' waste stress. If the test results (s'l to meet the acceptance criteria, the following steps, as f ar the Compensatory Measures of Section 2.1.1, shall be followed: (1) PROCESSING of the batch under test shall be suspended until such time as additional testing can be performed, alternative PROCESSING parameters can be determined, and subsequent testing verifies satisfactory PROCESSING of the 32 Rev. 0 4/89 1 4
t a waste. PROCESSING of the batch may then be resumed using-the alternative PROCESSING parameters:if the alternative =! parameters will produce a product that falls within the vendors qualification envelope. The vendor's PCP shall provide the method for determining the alternative PROCESSING parameters. Alternative i PROCESSING parameters which fall within the vendor's qualification testing envelope shall be approved by the Radwaste Coordinator or his. designee and shall be documented , in accordance with the vendor's PCP. The vendor'; PCP-shall be modified as required to assure-adequate PROCESSING;of subsequent batches of waste. ~Any changes should be consistent with the conditions, limitations, and , restrictions addressed in the vendor's 10CFR61. Topical Report. p (2)-If the test results failure is due to malfunction of the-processing equipment or the processing equipment is E inoperable, the equipment shall be returned to an OPERABLE condition or an alternate vendor shall be obtained to process waste as necessary to satisfy' applicable transportation and disposal requirements. 3.1.8 Dewatering Acceptance Criteria (1) Non Stable Waste Form - For wastes dewatered in non HICs, the acceptance criteria shall be less than or equal to one half of one percent (0.5%) of the internal volume of the container for free standing water. ! (2) Stable Waste Form - Waste shall be dewatered in an approved HIC, and the acceptance criteria shall be.less than or equal-to one percent (14) of the internal volume of the HIC for free standing water. Vendor documents for the dewatering process shall . include a specified end point for each dewatering L evolution which ensures that these acceptance criteria ,
- are achieved.
1 ! 3.1.9 Corrective Accions With dewatering not meeting the above acceptance criteria or otherwise not meeting disposal site and shipping and transportation requirements, suspend shipment of 33 Rev. 0 4/89 4
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the inadequately PROCESSED waste and correct the Process Control Program, the procedures, and/or the vaste processin5 equipment as necessary to prevent a recurrence. Additionally. an . evaluation of similar wastes PROCESSED since the last successf i surveillance testprocessed the inadequately shall be conducted waste. to determine the ' extent of If such vastes have'been shipped for disposal, the disposal site operator shall be' contacted and the probles addressed. ! If dowatering is not performed in accordance with this PCP the improperly PROCESSED waste shall be tested to ensure that it j meets burial ground and shipping requirements. Appropriate ' corrective action chall be es. ken to prevent recurrence. Disposition of inade s a case by. case basis. **oCESSED wastes will be handled on 3.2 PROCESSING OF DRY ACTIVE VASTE i t Dry Active Waste 4 (DAW) l generated at CPSES shall be processed by. ;f segregation, sorting, and/or compaction. Processin5 of DAW is' .; performed to accomplish the following functions: ' 1 E (1) Package DAW in a fashion acceptable for disposal at a. licensed disposal facility. (2) Remove constituents not acceptable for disposal as DAW' (3) Minimize volumes of DAW shipped for disposal by: o (a) removing reuseable and uncontaminated iteas; and (b) reducing shipped volumes by compaction. All processing of DAW at CPSES shall be performed in accordance with ' approved station procedures or vendor procedures that have been _ l' reviewed by the Radiation Protection Kanager. Vendor equipment, ' personnel and procedures may be used for DAW processing and packaging. ~ L The segregation of uncontaminated waste from DAW is performed to a ' minimise volumes of DAW shipped for. disposal. In order to provide reasonable assurance chac radioactive materials are not released as clean vaste, che , follovirs requirements- shall be included in the segregation program, as discussed in Reference 6.5.3: g (1) Surveys, using equipment and techniques for detecting low levels of radioactivity, shall be made of materials that may be contaminated l and that are to be disposed of as clean vastes. (2) Surveys may be conducted on individual items using portable survey I L instruments, such as pancake GM probes. However, in all cases. final measurements of each package (e.g. , bag or box) of aggregated i h 3-4 Rev. 0 4/89 l dl
waste to be released as clean vaste shall be performed to ensure that there has not been an accumulation of radioactive material due to the buildup of multiple quantities of contamination which were ' nondetectable with portable. instrumentation. Final measurements shall be performed using sensitive detectors in a low background area, such as scintillation detectors. 3.3 MIXED '.'AST t Mixed Vaste is defined as waste that contains-constituents that satisfy the definarirs of radioactive waste, subject to the Atomic Energy Act, ! and contains hazardous waste that either (1)-is listed as hazardous waste in 40CFR261. Subpart D, or (2) causes the waste to exhibit any of the hazardous waste characteristics identified in 40CFR261, Subpart C. Under cur ;ent federal law, this waste is subject to dual regulation by the NRC ...nd EPA where both agencies have control over the same waste.' Due to the complex regulatory issues that must be resolved pertaining to mixed waste, there are currently no authorized disposal sites in the United States which are licensed to receive and dispose of. aixed hazardous and radioactive waste. Since there is currently no avenue for disposal of mixed waste, efforts shall be made to reduce the generation of such vaste at CPSES. To accomplish this, station procedures for chemical control and radioactive waste processing shall include the following requirements: (1)1The Station chemical control program shall include a method to identify hazardous constituents of chemicals / chemical products and to evaluate and authorize any usage of these products in areas where mixed waste generation is likely to occur. This evaluation shall consider the substitution of products which are evaluated as non hazardous per 40CFR261. (2) Radioactive waste processing procedures shall-include provisions for segregation and removal of non radioactive hazardous constituents. Upon removal,cauch constituents would be handled as hazardous wasto as required by the EPA. (3) Mixed low level radioactive waste generated at CPSES shall not be shipped for (isposal to a low level radioactive waste disposal facility unless specific approval for such disposal is granted by the appropriate regulatory agencies. Such wastes shall be stored at CPSES until regulatory changes allow for disposal or they are otherwise approved for disposal by appropriate regulatory agencies. v 35 Rev. 0 4/89 l e
4 SECTION 4.0 4 WASTE CLASSIFICATION AND CHARACTERIZATION 4,1 WASTE CLASSIFICATION Radioactive waste generated at CPSES shall be classified as Class A, B. or C in accordance with the requirements of 10 CFR 61, Section 61.55, using one or more of the classification sothods given in the USNRC's-
"Lov. Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (May 1983)". Waste classification shall be performed in accordance with approved station procedures.
The following specific requirements shall be incorporated in the. program for sampling and analysis for waste classification:
.(1) Annual analyses shall be performed on representative ssaples of each waste stream or, alternatively, a process streas associated with the generation of the waste, for the nuclides listed.in Table 1 and Table 2 of 10 CFR.61 Section 61.55.
(2) The results of these annual analyses shall be used to develop isotopic abundances and scaling factors for difficult to seasure nuclides (i.e., beta esitters and transuranics) based on correlations between those nuclides and more easily acasured gamma emitters. (3) Camma spectroscopy or gross radioactivity seasurements shall'be made for each container of waste processed for disposal. Calculational methods for determining the total activity in each container shall be developed which use the results of the gamma spectroscopy or gross activity asasurements, and the percent. isotopic abundances and-scaling factors from the annual analyses. (4) The classification program shall establish criteria and include provisions for increased frequency for 'the sampling and analysis required by paragraph (1), above, if the failed fuel fraction changes by a factor of 10. (5) Each package of waste shall be clearly labeled as Class A, Class B, or Class C. 4.2 UASTE CHARACTERISTICS Waste PROCESSED for disposal at CPSES shall meet the applicable characteristics specified in 10 CFR 61, Section 61.56. Waste classified as Class 8, Class C, or Class A waste that will not be segregated from Class B and C wastes at the burial facility shall be processed into a stable waste form. This shall be accomplished by placement into a HIC which meets the stability requirements of 10 CFR { 41 Rev. O i 4/89 l 4
.}
61.56. per section 3.1.of this manual.. The vendor's topical report-shall include documentation of. testing which verifies that the HIC. meets.these stability requirements. Additionally,'TU Electric shall-comply with Federal or State requirements imposed specifically on'an approved HIC which limit the type and/or radioactive ' concentration of
, the vaste to be placed in the approved HIC'.
4 ; i 9 5 42 Rev. O { 4/89 d
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i SECTION 5.0 SPECIFIC VASTE STREAM PROCESSING DESCRIPTIONS ! 6 5.1 UET RADIOACTIVE WASTE STREAMS 5.1.1 Resins Resins will be accumulated from one or more of the following1 systems: (1) Chemical and Volume Control System (CVCS)
* (2) Spent ruel Pool Cooling and Purification System
(.4) Liquid Vaste-Processing System (including the fLIter/ demineralization system) (6) Boron Recycle System (5) Boron Thermal Regeneration System (6) Steam Generator Blowdown System (SGBS) ' (7) Condensate Polishing Domineraliser System (8) Other miscellaneous ion exchange medium as generated Spent NSSS and SGBS system resins are collected-in their' respective Spent Rosin Storage Tanks (SRSTs). 'These resins may-be transferred directly to the vendors processing skid from the SRSTs or, if desired, routed through the Waste Conditioning Tank. If it is necessary to process. secondary condensate polishing powdex resins, they are transferred from the Hot Phase Separator Tank, throu5h the Waste Conditioning Tank, to the vendor's processing skid. Spent resins will be processed for disposal by dewatering. The curie content and waste classification of each resin batch shall be estimated prior to sluicing af the spent resin to the vendor dewatering skid. ' Based on th19 estLaates . the proper liner or HIC and ~ cask for transportation and disposal are selected. The resin is transferred to the liner or HIC where it is dewatered ; utilising vendor supplied devatoring services per Section 3.1 of ' this manual. A representative sample of the resin is collected for final calculations of curie content and waste classification. Containers are sealed,' surveyed, and labeled', as. appropriate, and stored in a designated storage area until they are shipped for disposal,
'u A flow chart of a typical dowatering processing path is shown on Figure 5 1.
51 P.ev. 0 4/89 4
, 9; 5.1.2 Cartridae Filters Cartridge filters will be accumulated from one or more of the following: systems:
(1) Chemical and Volume Control System (2) Spent Fuel Pool Cooling and Purification System (3) Liquid Waste Processing System (including filter / demineralization system) (4) Boron Recycle System (5) Boron Recovery System (6) Steam Generator Blowdown System (7) Miscellaneous r Spent' filter cartridges are surveyed for_ dose rate upon removal; from the system. -The measured dose rate is used to: calculate isotopic content using a dose to curie conversion factor and scaling factors per section 4.1 of this manual. Based on the calculated isotopic content, the waste classification and the appropriate process and container for disposal are determined. Normally filters are placed in a liner-or HIC and dowatered. However, filters may be dried and handled as DAW, if conditions allow. Upon complettor. of the processing, containers are sealed, surveyed, and labeled, as appropriate, and stored in a designated storage area until they are shipped for disposal. For. purposes of waste classification, isotopic concentrations of filters dewatered in a liner or HIC should be determined as calculated over the volume of the cartridge filter itself, rather than averaged over the gross volume'of the container. A flow chart of a typical dewatering. processing path is shown on Figure 5 1. 5.1.3 Evaporator Concentrates Evaporator concentrates result'from operation of evaporators for processing of liquid wastes (e.g., floor drains) and boron recovery. Normally. liquid waste streams are processed through the filter /demineralizer systes for release to the environment. The liquid waste evaporator is available as an alternate processing method. The boron recovery evaporator is used to remove boron from reactor grade water and the boric' acid concentrates are normally recycled. 'Therefore, evaporator concentrates from liquid waste processing and boron recovery, that must be processed for disposal, are not normally anticipated. If solidification of evaporator concentrates is required, this PROCESS CONTROL PROGRAM shall be revised, per Technical Specification 6.13, to address solidification. 52 Rev. 0 4/89 l e
- - ~ -~- ~ - - ~
5 .1. 4 - ~ h ; i Radioactive sludge is accumulated and handled on a case by case basis by periodically removing the sludge from various tanks and sumps throughout the plant. Each batch of sludge is sampled for PCP parameters and isotopic content, chemically conditioned, if necessary, and PROCESSED per section 3.1 of this manual. Containers-are sealed, surveyed, and labeled, as appropriate, and stored in a designated storage area until they are riipped for diseosal. 5.1.5 Miscellaneous Liquids Miscellaneous liquids generat.ed in the t.tation will be collected and processed on a case by cate basis. Such vastes may include decontamination wastes and chemical west.a collected from the Chemistry Labs. Batches of such waste are isolated, _ sampled for PCP parameters and isotopic content, chemically conditioned, if necessary, and transferred to the vendor's processing skid where it is PROCESSED per section 3.1 of this manual. Containers are. sealed, surveyed, and labeled, as appropriate, and stored in a designated storage area until they are shipped for disposal. 5.2 DRY ACTIVE WASTE Dry Active Waste (DAW) consists of radioactively contaminated or activated waste which contains no liquids. DAW may be compactible, such as paper, plastic and protective clothing, or non compactible. such as tools or plant equipmeet. This. waste is segregated by station workers at the point of generation into receptacl;; da'ignated for
" clean" or " contaminated" trash. " Clean" receptacles are m d to collect trash that is potentially not contaminated. " Contaminated" cont,iners are used to collect waste that is known or suspected to be contaminated. However, for purposes of DAW processing, all waste collected in Radiation Controlled Areas-(i.e., that collected in both the " clean" and " contaminated" receptacles) is assua.. to be-contaminated until it is surveyed and proven clean. sags are collected from the receptacles, surveyed for external dose rate, and taken to a designated sorting area for processing. Bags below's specified dose rate level, per station procedures, any be opened and che contents surveyed individually for radioactivity. Items found to be not contaminated per station procedures, reusable items, and items not acceptable for disposal as DAW are removed. In general, the concents of bags above the specified dose rate level are not surveyed for contamination, but are examined for reusable items and items not acceptable for disposal as DAW. Contaminated iceas are then disposed of as DAW. Compactible items are collected and compressed into approved strong, eight containers. Noncompactible items are placed directly into approved strong, tight containers. Containers are sealed, surveyed, and labeled, as appropriate and stored in a designated storage area until they are shipped for disposal.
A flow chart of the DAW processing path is shown on Figure 5 2. 5-3 Rev. 0 4/89 4
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FIGURE 5-2 1 DAW Process Flow Chart 5-5 Rev. - 4/89 4
1 SECTION 6.0 ADMINISTRATIVE CONTROLS i 6.1- PROCEDURES Activities associated with the implementation of the requirements of this program shall be conducted in accordance with approved station procedures or vendor documents and procedures that have been reviewed-and approved per sections 1.4 and 3.2. 6.2 QUALITY ASSURANCE Quality Assurance related activities for radioactive waste processing are implemented as described in the TU Electric CPSES Quality Assurance Manual. Such activities include: (1) Review of documents and procedurat E$tveting the processing, packaging, handling, and transecreatten of radioactive vaste. (2) Review of procurement documents ut services. (3) Perform inspections as designated in applicable processing, packa81ng, and shipping procedures. (4) Review applicable vendor QA programs for compliance with Regulatory and TU Electric requirements. (5) Perform audits of the radioactive waste management program at least once per 24 months. (Note: Technical Specification Administrative Control 6.5.0.8.1 requires that audits of the Process Control Program and implementing procedures be performed under the cognizance of the Operations Review Committee at least once per 24 months.) (6) Documentation and retention of documentation of waste processing, packaging and shipping activities. These activities provide assurance that the final waste form, packaging, labeling, and transportation are in accordance with applicable regulations and requirements. 6.3 CRANCES TO THE PCP Changes to this PCP shall be made in accordance with Technical Specification 6.13. Technical Specification 6.13 requires. chat changes to the PCP: 61 Rev. 0 4/89 4
*1 a
i (1) Shall be documented and records of reviews performed shall' be ' retained for'the duration of the unit Operating License- . This' documentation shall contain: 7 (a) Sufficient information to support the change together with the ., appropriate analyses or evaluations justifying the change (s), and (b) A determination that the change will maintain the overall' conformance of the waste product to existing requirements of Federal, State, or other applicable regulations. (2) Shall become effective ~after review and acceptance by SORC, andlthe< approval of the Vice President. Nuclear Operations. 6.4 DOCUMCITATION i Procedures for radioactive waste PROCESSING, packaging, and . traniportation shall include requirements for maintaining and retaining LLW processing, packaging, and transportation records. Detailed , records for each container of waste shall be maintained. 6.5 TRAINING TU Electric and vendor personne1' responsible for waste processing, i L packaging and transportation activities shall be trained and qualified. ' I to ensure that vaste PROCES3ING is performed in accordance with , applicable requirements. Training programs shall establish a schedule- ., for periodic requalification of at least once every two yearse - TU - Electric shall verify the training of vendor personnel. t i l' l l l 62 Rev. O i 4/89 ! d
6 i s : SECTION 7 0 - REFERENCES
- 7.1 Code of Federal Regulations: ,
7.1.1 Title 10, Parts 20, 61, and 71 7.1.2 Title 49 Part 173 7.1.3 Title 40, Part 261 7.2 USNRC, Low-Level Vaste Licensing Branch, Technical Positten on i Radioactive Waste Classification, May 1983 7.3 USNRC, Low Level- Vaste Licensing Branch, Technical Position on Waste. Form, May 1983 7.4 USNRC, Guidelines for Preparation and Implementation of a Solid Waste e Process Control Program (Proposed), Draft Revision 3, September 1986 ' 7.5 USNRC, Office of Inspection and Enforcement. IE Information Notices: 7.5.1 -IEN 79 09, " Spill of Radioactively Contaminated Resins" 7.5.2 IEN 83 14, "Dowatered Spent Ion Exchange Rosin Susceptibility to Exothermic Chemical Reaction" 7.5.3 IEN 85 92, " Surveys of Wastes Before Disposal from Nuclear Reactor Facilities" 7.5.4 IEN 86 20, " Low Lavel Radioactive Waste Scaling Factors,10 CFR Part 61" 7.5.5 IEN 87 03, " Segregation of Hazardous and Low Level. Radioactive Wastes" [ -7.5.6 IEN 87 07, " Quality control of Onsite- Dewatering / Solidification l Operations 8J Outside Contractors" 7.5.7 IEN 88 08, " Chemical Reactions With Radioactive Waste solidification Agents" 7.5.8 IEN 89 27, "Limitatiors on the Use of Weste Forms and High . Integrity Containers for the Disposal of Low Level Radioactire Waste" 7.6 CPSES Technical Specificacians, Sections 6.5.2.8.~i and 6.13 . 7.7 CPSES Station Administratire Procedure STA 614 " Radioactive Waste L Control" 1-l 7-1 Rev 0 4/89 e
7.4 CPSES Radiation Protection Instructions: 7.8.1 RPI.203, " Shipment of Radioactive Materials" 7.8.2 RFI.204, " Liquid Waste Processing" 7.8.3 RPI.205, "DAV Processing" 7.8.4 RPI.209, " Radioactive Waste Classification" 7.9 CPSES Che'istry Procedures: 7.9.1 CHM.517, " Chemistry Control of Liquid Waste Systems" 7.9.2 CHM 518. "Radionuclide Verification and Correlation Program" 7.10 CPSES Radioactive Waste Systems Procedure RWS 301, "Radwaste Solidification Systeas" 7.11 Vendor Documents No vendor documents have currently been reviewed and approved by the CPSES Sc??. .This section shall be revised to reference specific vendor documents approved for use at CPSES upon review and approval by the SORC. 7.12 TU Electric Cr37S Quality Assurance Manual 72 Rev 0 4/89 j 1 1 4 _ _ _ _ _-- _ __ _ - _ - - _ - - _ - - _ - - - - - - - - - - - - -}}