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| number = ML20070E836 | | number = ML20070E836 | ||
| issue date = 03/01/1991 | | issue date = 03/01/1991 | ||
| title = Offsite Dose Calculation Manual | | title = Offsite Dose Calculation Manual | ||
| author name = | | author name = | ||
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) | | author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) | ||
Latest revision as of 23:47, 23 May 2020
| ML20070E836 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/01/1991 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20070E831 | List: |
| References | |
| PROC-910301, NUDOCS 9103060308 | |
| Download: ML20070E836 (265) | |
Text
{{#Wiki_filter:.. ._.. . _ _ _ . . . . . - . _. Attachment 8.1 Offsite Dose Calculation Manual-for CPSES Unit 1 l.. l( l 9103060'JO8 910301 POR R ADOCK 05000445 FDR
TABLE OF CONTENTS f.iL91 List of Tables v , List of Figures vii Cross Reference to Technics: Specifications and REC viii References xi Introduction xii PART I RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 - DEFINITIONS I 1-0 SECTION 2.0 - NOT USED I 2-0 SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVEILLANCE I 3/4-0 REQUIREMENTS 3/.4.0 - Applicability I 3/4-1 3/4.3.3.4 - Radioactive Liquid Effluent I 3/4-3 Monitoring Instru.nentation 3/4.3.3.5 - Radioactive Gaseous Effluent I 3/4 8 Monitoring Instrumentation ! 3/4.3.3.6 - Meteorological Monitoring I 3/4-13 l Instrumentation 3/4.7.15 - Sealed Source Leakage I 3/4-15 3/4.11.1.1 - Liquid Effluent Concentration I 3/4-17 3/4.11.1.2 - Liquid Efflaent Oose I 3/4 21 ! 3/4.11.1.3 - Liquid Radwaste Treatment System I 3/4-22 l l 3/4.11.1.4 - Evaporation Pond I 3/4-22a 3/4.11.2.1 - Gasecus Effluent Dose Rate I 3/4 23 3/4.11 ~2.2 - Gaseous Effluent Dose - Noble Gas I 3/4 27 3/4,11.2.3 - Gaseous Effluent Dose - Iodine 131, I 3/4-28 Iodine-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
TABLE OF CONTENTS P_iL91 3/4.11.4 - Radioactive Effluents Total Dose I 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 - Map. Defining Unrestricted Areas and I51 Site Boundary for Radioa:tive Gaseous and Liquid Effluents SECTION 6.0 - ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 - Annual Padiological Environmental I61 Operating Report 6.9.1.4 - Semiannual Radioactive Effluent I 6-2 Release Report 6.14 Offsite Dose Calculation Manual I 6-3 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS II l-1 1.1 General Methodology for Determining Liquid II l-1 Effluent Monitor Setpoints 1.1.1 leotopic. Concentration of the Waste Tank II l-2 1.1.2 Eaximum Ef fluent Flow Rate (f) 11 1-2 1.1.3 Dilution of Liquid Effluents Due to II 1-3 L Circulating Water Flow (F) l 1.1.4 Actual Dilution Factor (ADF) II l-3 l ' l.1.5 Required Dilution Factor (ROF) II l-4 1.1.6 Upper Setpoint Limit for II l-5 Detector XRE-5253 11 Rev. 1 8/89 l l
TABLE OF CONTENTS PJLR2 , 1,2 Dose Calculation for Liquid Effluents 11 1 7 1.2.1 Calculation of Dose Due to a II 1 7 Batch Release 1.2.2 Calculation of Dose Due to !! l-9 Radionuclide Buildup in the Lake 1.3 Dose Projections for Liquid Effluents II l-11 1.4 Service Water Effluent Radiation II l-16 Monitors 1RE-4269/4270 1.5 -l'arbine Building Sump Effluent Radiation 11 1-17 Monitor 1RE 5100
-1.6 Definitions'of Ccmmon Liquid Effluent i. an1ters II 1-18 2.0- GASEOUS EFFLUENTS II 2-1 2.1 Gaseous Effluent Monitor Setpoints II 2-1 2.1,1 Dose Rates Due to Noble Gases II-2-3 2.1.2 . Plant Vent Stack Noble Gas II 2-5 Monitors XRE-5570A/B and XRE-5567A/B ;
2.1.?- Plant -Vent Flow Monitors II 2-7 2.1.4 Auxiliary; Building Ventilation Exhaust II 2-8 Monitor XRE 5701 2.1.5 Containment Atmosphere Gaseous II 2-10 , Monitor 1RE-5503 p 2.1.6 Dose Rates Due-to.Radioiodines, 11 2-12 Tritium, and. Particulates s l' 2.1.7 Plant Vent Stack Iodine Monitors II 2-13 XRE-5575A/B 2.1.8 Plant Vent Stack Particulate II 2-14
, iionitors XRE-5568A/B l
l iii Rev. 0 3/89
f
-TABLE OF CONTENTS 1 Elat i l
2.2 Gaseous Effluent Dose Calculations II 2-17 1 2.2.1 Dose Due to Noble Gases' II 2 17 2.2.2 Dose Due to Radiotodines, Tritium, 11-2 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 II 2-49
'2.4 Definition of Gaseous Effluent Parameters 11 2 50 3.0 ' RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1 31 Sampling Locations
. II 3-1 3.2 Interlaboratory Comparison Program II 3-1 _
' APPENDIX .
g A.. -Pathway Dose -Rate Paraineter (Pj) A-1 l B. : Inhalation. Pathway Dose factor: B-l= C. LGround Plane Pathway Dose Fr.ctor. C-1 D. LGrass-Cow-HilkLPathway Dose Factor- 01
-E. ' Cow Meat Fathway Dose Factor E-1 L F. Vegetation Pathway Dose Factor F .1 u
- . G.? Supplemental-Guidence Statements ~ G-1 x
k' l I; W L iv -Rev. 1 b
-8/89
_ a _
1,jjt of iables 11blLtb IJilt h22 PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.1 frequency Notation I l-5 1.2 Operational Modes I l-6 3.3-7 Radioactive liquid Effluent Monitoring I 3/4-4 Instrumentation 4.3-3 Radioactive Liquid Effluent Monitoring 1 3/4 6 Instrumentation Surveillance Requirements 3.3-8 Radioactive Gaseous Effluent Mor.itoring 1 3/4-9 Instrumentation 4.3-4 Radioactive Gaseous Effluent Monitoring 1 3/4-11 Instrumentation Surveillance Requirements 3.3-9 Meteorological Monitoring Instrumentation 1 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 Radiological Environmental Monitoring I 3/4-34 Program 3.12-2 Reporting Levels for Radioactivit.v i 3/4-40 Concentrations in Environmental Shmples 4.12-1 Detection Capabilities for Envircamental I 3/4-41 Sample Analyses (LLDs) PART II - CALCULATIONAL METHODOLOGIES 1.1 Site Related Ingestion Dose Commitment 11 1-12 Factor (Att) 2.1' Dose Factors for Exposure to a Semi- 11 2-16 Infinite Cloud of Noble Gases 2.2 Pathway Dose Rate Parameter (Pj) 11 2-23 2.3 Pathway Dose Factors 11 2-24 1' v Rev. 1 8/89
List of Table: Table *%, lille P_tqg I Controlling Receptor Pathways and II 2 45 5 1.ocations, and Atmospheric Dispersion Parameters (For Dose Calculations Required by Radiological Effluent ; Control 3/4.11.2.3) j 1 2.5 Deleted 11 2-46 5 3.1 Environmental Sampling t.ocations 11 3-3 1 1 l i l L 1 l l l vi 12/90
- _ - . - . _ . _ - ..~ .. _. _ _ _ _ _ _ . _ _ _ _ _ . . _ . _ . . _ . _ . _ . . _ _ _ _ . . _ _ . _ . _ . - ,
i List of Fiaures-Fiaure- 11.tig fjtg.g 1 PART I- RADIOLOGICAL EFFLUENT CONTROLS - 5.1-3 Site Boundary and Unrestricted Areas I52 PART II - CALCULATIONAL METHODOLOGIES
-1,1 Liquid Effluent Discharge Pathways 11 1 22 1.2- Energy Response to Gamma Radiations II 1-23 for RD 33 Type Detector 1.3 Circulating Water Pump Curves II 1 24 1.4 ' Liquid Waste Processing System II l 2.1- Gaseous Waste Processing System II 2 56 2.2L Plume Depletion Effect for Ground II 2-57 Level Releases
'2,3-~
' Vertical Standard Deviation of 11 2-58 Material in a Plume 2.4 Relative' Deposition for_ Ground- II 2-59 Level Releases 2;5_ .0 pen Terrain Correction Factor II 2-60
-3.1 RadiologicalJEnvironmental Monitori.g II 3-9 Locations-5 f
L l .l r-L , I k vii -Rev. 0: 3/89
Cross Reference to Technical Soecifications and REC Number or Document Section Reouirement ODCM Section PART I-RADIOLOGICAL EFFLVENT CONTROLS (REC) Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements Tech Specs 6.8.3.e.2 Limit liquid effluent concentration 3/4.11.1.1 Tech Specs 6.8.3.e.3 Effluent monitoring, sampling, and 3/4.11.1.1 and analysis requiremerits 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 Determinc cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2, 3/4.11.2.3, 3/4.11.1.1, and 3/4.11.2.4 Tech Specs 6.8.3.e.6 Effluent treatment systems 3/4.11.1.3 and operability requirements 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 6.8.3.9.9 Limit gaseous effluent iodine and 3/4.11.2.3 particulate dose Tech Specs 6.8.3,e.10 Limit total dose 3/4.11.4 Tech Specs 6.S.3.f.1
~
Monitoring, sampling, and analysis 3/4.12.1 of radiation in the environmer:t Tech Specs 6.8.3.f.2 Land Use Census 3/4.12.2 Tech Specs 6.8.3.f.3 Interlaboratory Comparison Pi) gram 3/4.12.3 PART II - CALCULATIONAL METHQQQllfdfji REC 3/4.11,1,1 Liquid effluent concentrat!,n 1.1-REC I3/4.11.1.2 Dose due to liquid efflue'.ts 1.2 REC 3/4.11.1.3 Dose projections for l'. quid 1.3 releases L i viii Rev. 0 3/89
Cross Reference to Technical Soecifications and REC Number or
~ Document Section Reouirement ODCM Section REC- 3/4.ll.2.1.a Dose rate due to noble gases 2.1.1 REC 3/4.ll.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 REC 3/4.11.2.3 Doses due to iodines, tritium, 2.2.2 and particulates with half-lives greater than eight days l
REC 3/4.11.2.4 Dose projections for gaseous 2.2.3-releases L 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
- changes to environmental sampling locations REC 3/4.1f4.3 Description of the Interlaboratory 3.2 Co.nparisen _ Program
, REC 3.3.3 4 Radioactive liquid effluent
- munitoring-channels alarm / trip L setpoints i
o- liquid waste monitor (XRE-5253)- -1.1.6 o turbint building sump monitor- 1.5 (IRE-5100)
.o service wa m monitor 1.4 (1RE-4269/4270) p i
l- ix Rev. 0 lj 3/89 L C_____-_____-__ , . ._
r Cross Reference to Teshnical Soecifications and REC Number or Document Section Reouirement ODCM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alarm / trip setpoints o noble gas release rate monitors 2.1.3 XRE 5570A and XRE-55708 (WGRM ; release rate channels) j 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 I (auxiliary building vent monitor) XRE-5701 o sampler flow rate monitor 2.1.3 l
- l. XFT 5570A2/82 1
-Tech Specs 3.3.3.1 Radiation monitoring channels L alarnV' trip setpoint t'
l_ o Containment atmosphere gaseous 2.1.5 monitor (containment vent monitor) 1RE-5503-Tech Specs 6.9.-l.4 Assessment.of radiation doses due 2.2.4 REC 6.9.1.4 to liquio and gaseous effluents released during the previous year 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 L Tech Specs 6.9.1.4 Assessment of doses to.the most 2.2.4 L REC 6.9.1.4 likely exposed member of the public L from reactor releases and direct radiation x Rev. 0 3/69
.. .___.__._m.._ _ _ _ - _ _ _ _ _ . - _ _ _ _ . _ _ _ . _ _ . _ _ _ _ .
REFERENCES
- 1. Boegli, J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, U. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
- 3. " Environmental Report," TV Flectric, Comanche Peak Steam Electric Station.
- 4. " Final Safety Analysis Report," TV Electric, Comanche Peak Steam Electric Station.
- 5. Methods for Estimating Atmospheric Trcasport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, U.S. NRC RegulatoryGuide1.111(March 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. 5, Department of Commerce (July 1968).
3
- 8. " Unit 1 Technical Specifications," TV Electric, Comanche Peak Steam Electric Station.
- 9. Implementation of Programmatic Controls for Radiological Effluent .
Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Oose Calculation Manual or to the Process Control Program (Generic Letter 89 01), USNRC, January 31, 1989,
- 10. CPSES Technical Evaluation No. RP-90 3077, " Calculation of Site Related 5 Ingestion Oose Commitment Factors For Sb 122."
5
- 11. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," USNRC Regulatory Guide 1.109 (March 1976).
~ . s. 12/90 4 -
INTRODUCTION l The OFFSITE DOSE CALCULATION MANUAL (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 11 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 The ODCM will be maintained at ,the plant for use as a reference guide and training document on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. TV Electric initiated changes to the ODCM will be implemented in accordahce with Section 6.14 of the Technical Specifications. xii Rev. 0 3/89
The ODCM follows the methodology and models suggested by NUREG 0133 (Ref.1) and Regulatory Guide 1.109, Revision 1 (Ref. 2). Simplifying assumptions he"e been applied in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements. This simplified approach wil_1 result in a more conservative dose evaluation, but requires the letst amount of time for establishing compliance with regulatory requirements. This manual is designed to provide necessary information in order to simplify the dose calculations. The dose calculations can be optionally expanded to several levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the 00CM may be initiated to-implement more complex calculations as systems become available and are validated that can reliably, economically and properly perform these more complex calculations. A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Semiannual Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses. Where additional clarification or information is required to adequately implement certain ODCH requirements, supplemental guidance is provided in Appendix G of Part II.- / I xiii Rev. 1 8/89
PART I RADIOLOGICAL EFFLUENT CONTROLS I
I i l l SECTION 1.0 DEFINITIONS I: i j-0
.COMAN HE PEAK-- UNii 1 110 hj
1 l 1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Controls. ACTION 3 1.1 ACTION shall be that part of a-Control which prescribes remedial measures required under designated conditions. ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify 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. CHANNEL CAllBRATION 1.5 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total cFannel steps. such that the entire channel is calibrated. CHANNEL CHECK-1.6 A CHANNEL- CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. DIGITAL CHANNEL-OPERATIONAL TEST 1.10 - A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the . digital computer hardware using-data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions. k REV. O COMANCHE PEAK - UNIT 1 1 1-1 3/89
DEFINITIONS DOSE E0VIVALENT l-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I 131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132,1-133,1-134, and I :" actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table 111 of 110-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977. FRE0VENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. MEMEE9fSl 0F THE PUBLIC 1.18 MEMBEI'(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 pl ant , OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in tk calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in tiie calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4. OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). REV. O COMANCHE PEAK - UNIT 1 1 1-2 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, p~ level, and average reactor coolant temperature specified ic Table 1.2. PRIMARY PLANT VENTILATION SYSTEM 1.24 A PRIKARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas ef fluents . PURGE - PURQ1HS 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. BAIED THERMAL POWER 1.29 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 1.33 The SITE BOUNDARY shall be that line as shown in Figure 5.1-3. SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. THERMAL POWER 1.38 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. REV. O COMANCHE PEAK - UNIT 1 I l-3 3/89
DEFINITIONS UNRESTRICTED AREA-
-1.41 An UNRESTRICTED AREA shall be any area-at or-beyord the SITE B0UNDARY access to which is not controlled by the licensee for purp; of protection of individuals -from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential _ quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTING 1.42 . VENTING shall be the controlled-process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING' process. WASTE GAS HOLDUP SYSTEM 1.43 A WASTE GAS HOLDUP-SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluerts by collecting Reactor Coolant System . . offgases1from the Reactor. Coolant System and providing for delay or holdup for
.the purpose of reducing the total radioactivity prior to release to the environment.
l-REV. O COMANCHE PEAK - UNIT 1 I l-4 3/89
TABLE 1.1 EBI.0VENCY. NOTATION NOTATION FRE0VENCY S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days 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. REV. O COMANCHE PEAK - UNIT 1 . I l-5 3/89
TABLE 1.2 OPERATIONAL MODES AVERAGE REACTIVITY % RATED COOLANT MODE CONDITION. Keff THERMAL POWER
- TEMPERATUR1
- 1. POWER OPERATION 2 0.99 > 5% 2 3500F
- 2. STARTUP 1 0.99 s 5% 1 3500F
- 3. HST STANDBY < 0.99 0 1 3500F
- 4. HOT SHUTDOWN < 0.99 0 3500F>Tavg
> 2000F
- 5. COLD SHUTDOWN < 0.99 0 5 2000F
- 6. REFVELING** $ 0.95 0 s 1400F W
- Excluding decay heat.
** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
REV. O COMANCHE PEAK - UNIT I 1-6 3/89
, _p._e . an a 4 - h= J-.-n$ nlL4 m -na,
' SECTION 2.0 NOT USED ,
4-e, i I 2-0 REV. I 8/89
S. ,-_ A A .m. u-- 4 _ A a SECTIONS 3.0 AND 4.0 CONTROLS AND SVRVEILLANCE REQUIREMENTS REV O C0HAtlCHE PEAK - UNIT 1 1 3/4 0 3/89 l
3/4 CONTROLS AND SURVElllANCE REQUIREMENTS 3/4.0 APpllCABILITY # CONTR0ls 3.0.1 Compliance with the Controls contained in the succeeding Controls is
- required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 When a Control is not met, except as provided in the associated ACTION requirements, within 1 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:
- a. At least HOT STANDBY within the next 6 hours,
- b. At least H0T SHUTDOWN within the following 6 hours, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual controls. This control is not applicable in MODE 5 or 6. 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements Exceptions to these requirements are stated in the individual controls.
# The associated basis from the CPSES Technical Specifications applies to this section.
l REV. O l
- COMANCHE PEAX - UNIT 1 1 3/4-1 3/89.
1
l APPLICABILITY SURVEllLANCE RE0VIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveillance interval, but
- b. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
Exceptions to these requirements are stated in the individual controls. 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance Requirement 4.0.2, shall constitute noncompliance with the OPLRABILITY 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 delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not rave to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Require 5ent(s) associated with the Control has been performed within the stated surveiilance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual controls. REV. O COMANCHE PEAK - UNIT 1 1 3/4-2 3/89
m . --a a am- i - + -;M--> -w d- -J-' S==i ', MA,4u -- b-4-A--- A A--- 4 INSTRUMENTATION RADIOACTIVE L10010 EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordanct 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 0FFSITE DOSE CALCULATION MANUAL (00CM) . APPLICABILITY: At all times. ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, b With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels 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 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 .
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 CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST 4: the frequencies shown in Table 4.3-3 . REV. O COMANCHE PEAK - UNIT 1 I 3/4-3 3/89 l l l
4 S E z e TABLE 3.3-7 A 3E RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION b
=
MINIMUM CHANNELS j INSTRUMENT OPERABLE ACTION
- 1. Radioactivity Monitors Providtog 31 ara and Automatic Termination of Release
- a. Liquid Radwaste Effluent Line (XRE-5253) 1 30
- b. Turbine Building (Floor Drains) Sumps Effluent Line 1 31
~~
(IRE-5100) s'
*- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
- a. Service Water System Effluent Line (IRE-4269, IRE-4270) 1/ train 32
- 3. Flow Rate. Measurement Devices
- a. Liquid'Radwaste Effluent Line (XFT-5288) 1 33 un na CD C M)*
O f I
l TABLE 3.3 7 (Continued) ACTION STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE 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 with Control 4.11.1.1.1, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 31- With the number of channels OPERABLE less than required oy 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 10-7 microcurie /ml:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131, or
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.
ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue provided that:
- a. With the component cooling water monitors (1RE-4509, 1RE-4510, &
1RE-4gll) OPERABLE and indicating an activity of less than IX10- 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
- b. At least once per 12 hours, grab samples are collected and analyzed for more than 10' microcurie gadioactivity
/ml.at a lower limit of detection of no ACTION 33- With the number of channels OPERABLE less than required by the
. Minimum Channels OTERABLE requirement, effluent releases via this pathway nsay continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow.
L ! REV. O COMANCHE PEAK - UNIT 1 1 3/4-5 3/89
8 I E - 3 x
. TABLE 4.3-3 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS
~
ANALOG DIGITAL CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBPATION TEST TEST
- 1. Radioactivity. Monitors Providing Alarm and Automatic Temination of Release ,
g a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. Q(1) b b. Turbine Building (Floor Drains) Sumps - Effluent Line(IRE-5100) D M R(4) N.A. Q(2)
- 2. Radioactivity Monitors Providing Alarm But ,
Not Providing Automatic Termination of Release
- a. Service Water System Effluent Line (IRE-4269, 1RE-4270) D M R(4) N.A. Q(3)
- 3. Flow Rate Measurement Devices w :o D2 a. Liquid Radwaste Effluent Line (XFT-5288) D(5) N.A. R Q N.A. ;
____ __ ._ _ . _ . _ _ _ . . .. . ~ . _ __._._,. _ _ . . ._ TABLE 4,3-3 (Continued) . TABLE NOTATIONS 4 (1); The OlGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that '
' automatic isolation of this pathway and Control Room alarm annunciation occur if any of the:following conditions exist: . ,
- a. ' Instrument indicates measured levels above the Alarm / Trip Setpoint, or
- b. Circuit failure (Channel Out of Service - Loss of Power, Loss of
-Counts, Loss of Sample Flow, or Check Source Failure).
(2) The DIGITAL CHANNEL.0PERATIONAL 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
- b. Circut 'ailure (Channel Out of Service Loss of Power, loss of Counts . oss of Sample Flow, or Check Source failure).
(3) The OlGITAL CHANNEL OPERATIONAL TEST shall elso demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist:
.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).
- (4) 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 thst-have been related to the initial calibration, reference j -standards certified by'NBS, or standards that have been obtained from suppliers that participate in measurement assurance activities with NBS shall: be used.- 3 (5) CHANNEL. CHECK:shall consist of verifying indication of flow during seriods of release. CHANNEL CHECK _shall be made'at least once per 24 1ours on days on which continuous, periodic, or batch-releases are made.-
L REV. O COMANCHE PEAK - UNIT 1 1 3/4 7 3/89 i e
, - , , ,,-p -- - -= v g - w-v+ w q -
4 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUM WTATION CONTROLS l l 3.3.3.5 in accordance with CPSES TS 6.8.3.e.1, the radioactive gaseous I effluent monitoring instrumentation channels shown in Table 3.3-8 shall be { OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of ' Control 3.11.2.1 are not exceeded . The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCH. APPLICABILITY: As shown in Table 3.3 8 l ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative,
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3 8 . Restore the inoperable instrumantation 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.
SVRVEILLANCE RE0VIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and OlGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3 4 . M REV 1 COMANCHE PEAK - UNIT 1 1 3/4-8 8/89
TABLE 3.3-8
'RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.
i ' MINIMUM CHANNELS' INSTRUMENT OPERABLE- APPLICABILITY ACTION
- 1. WASTE GAS HOLDUP SYSTEM a.-Noble Gas Release Rate Monitor - Providing Alarm and Automatic Termination.
of Release [XRE-5570A & XRE-55708 ,. (effluent release' rate channel)) I/ stack ** 34
- 2. PRIMARY PLANT VENTILATION m a. Noble Gas Release Rate Monitor 2 [XRE-5570A & XRE-55708 lo (effluent release rate channel)] 1/ stack
- 36
- b. lodine Sampler t (WRGM sample skid) 1/ stack
- 37
- c. Particulate Sampler' . 1/ stack
- 37 r
- d. Sampler Flow Rate Monitor,
.SMPL Flow 1 (X-RFT-5570A-1, 4-X-RFT-55708-1) 1/ stack * ,
35 4 t El
?1 *.
O . h E
TABtE 3,3 8 (Continued) TABLE NOTATIONS At all times.
** During Batch Radioactive Releases via this pathway. l ACTION 34 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of ,
the tank (s) may be released to the environment provided I that prior to initiating the release:
- a. The auxiliary building vent duct monitor (XRE 5701) is i confirmed OPERABLE, or
- b. At least two independent samples of the tank's contents av3 analyzed, and
- c. At !*ast two technically qualified members of the facility stat f independently verify the release rate calculations and discharge valve lineup.
Otherwise, susper.d release of radioactive effluents via this pathway. ACTION 35 With the number of channels OPERABLE less than required by 4 the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is estimated 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 5570B (low range activity) or XRE 5567A, XRE-55678) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours; or (b) The Plant Vent Flow Rate Monitor, PROC FLOW N 4 (X-FT 5570A-1, X-FT 55708 1), is OPERABLE, and an .: alternate Plant Vent Noble Gas Activity Monitor is i OPERABLE (XRE-5567A, XRE 5567B) 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. 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 4.11-2. l I 3/4-10 Revision 4 October 22, 1990
TABLE 4 i RADIDAC11VE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENis ANr. TOG DIGITA! CHANNII ( f TAN'4f i CilANNEL SOURCE CitANNEL OPERAIIONAL OPIRAlloNAl INSTRUMENT CHECK CHECK CALIBRATION TEST ILSI I. WAS1E GAS HOLDUP $YSTEM
- a. Noble Gas Release Rate Monitor -
Providing Alarm nd Automatic Termination of Reie.se [XRE-5570A, XRE-5570B (effluent release rate channel)] P P R(3) N.A. Q(I)
- 2. PRIMARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor
[XRE-5570A, XRE-55708 (effluent release rate channel)) D # R(3) N.A. Q(2)
- b. Iodine Sampler p (WRGH sample skid) W(4) N.A. N.A. N.A. N.A.
C
- c. Particulate Sampler (WRGM Sample Skid) W(4) N.A. N.A. N.A. N.A.
- d. Sampler Flow Rate Monitor, SMPL Flow 1 4 (X-RFT-5570A-1, X-RFT-55708-I) D N.A. R Q N.A. 4 RN' E1 Si "'s 8
;3 u j =
8
~ ~ . - - . - . ..-----. . - . . - . . . . - . _ . - . - ..-. -. -
i i TABLE 4.3 4 (Continuedl TABLE NOTATIONS 1 I
# Prior to any release from the WASTE GAS HOLOUP SYSTEM or containment PURGING or VENTING, not to exceed 31 days.
(1) The OlGITAL CHANNEL OPERATIONAL. TEST shall also demonstrate that automatic isolation-of this pathway and control room alarm annunciation
~
occurs if any of the following condition exists: a.-Instrument indicates measured levels above the Alarm / Trip Setpoint, or
- b. Circuit failure, (Channel Out of Service Loss of Power, Loss of 1 Counts, Loss of Sample Flow, or Check Source Failure), i l
(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 standar'ds that have been obtained from suppliers that cparticipate 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-suppliers that participate in measurement assurance activities with NBS '
shall- be used.
-(4) -The CHANNELL CHECK shall consist of visually verifying that the collection element (i.e., filter or cartridge, etc.) is in place for sampling.
b
-REV. O COMANCHE PEAK - UNIT 1 1 3/4-12 3/89
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3,3.3.6 The meteorological monitoring instrumentation channels shown in Table 3.3.3-9 shall be-OPERABLE. APPLICABILITY: At all times. ACTION:
- a. With 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 cau:e of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each of the above meteorological _ monitoring instrumentation channels shall be demonstrated OPERABLE: a At least once per 24 hours by performance of a CHANNEL CHECK, and
- b. At least once per 184 days by performance of a C % NNEL CALIBRATION.
l l , l ntV. O J COMANCHE PEAK - UNIT 1 1 3/4-13 3/89
)
l
TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT LOCATIQN OPERABLE
- 1. WIND SPEED 1 of 3
- a. X-SY 4117 Nominal Elev. 60 m.
- b. X-SY 4118 Nominal Elev.10 m,
- c. X-SY-4128* Nominal Elev. 10 m.
- 2. WIND DIRECTION 1 of 3
- a. X-ZY-4115 Nominal Elev 60 m.
- b. X-ZY-4116 Nominal Elev.10 m.
- c. X-ZY-4126* Nominal Elev.10 m.
- 3. AIR TEMPERATURE - a T 1 of 2
- a. X-TY-4119 Nominal Elev. 60 m. and Nominal Elev 10 m.
b X-TY-4120 Nominal Elev. 60 m. and Nominal Elev.10 m.
- Mounted on backup tower.
REV. O COMANCHE PEAK - UNIT 1 1 3/4-14 3/89 ) l
INSTRUMENTATION SEALED SOURCE CONTAMINATION CONTROLS 3.7.15 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination. APPllCollllTY: At all times. ACTION With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations.
SURVElllANCE RE0VIREMENTS 4.7.15.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
- a. The licensee, or
- b. Other persons specifically authorized by the Commission or an Agreement State, ,
The test method shall have a detection sensit!vity 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 previcusly subjected to core flux) shall be tested at the frequency described below,
- a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
- 1) With a half-life greater than 30 days (excluding Hydrogen 3), and
- 2) In any form other than gas.
REV. O COMANCHE PEAK - UNIT 1 I 3/4-15 3/89 l l l
SVRVEILLANCE RE0VIREMENTS (Continued) ,
- b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last te,st date shall be tested prior to being placed into use; and
- c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.
4.7.15.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than cr equal to 0.005 microcurie of removable contamination, t REV. O l COMANCHE PEAK - UNIT 1 I 3/4-16 3/89
3/4.11 RADIDACTIVE EFFLVENTS 3/4.11.1 L10VID EFFLVENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 6.8.3.e.2 and 3, the concentration of re 'ioactive material released in liquid effluents to VNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part
- 20. Appendix B, Table 11, Column 2 for radionuclides other than dissolved or ined noble geses. For dissolled or gntrained noble gases, the c ic . tration shall be limited to 2 x 10 9 microcurie /ml totai activity.
APPLICABILITY: At all times. 1 ,A,(_TlQ!j: (a) With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately l restore the concentration to within the above limits. 1 (b) The provisions of Controls 3.0.3 and 3.0.4 are not applicable. SURVEllLANCE RE0VIREMENTS 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 00CM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1. REV. O COMANCHE PEAK - UNTI 1 1 3/4-17 3/89
TAB.E 6.11 1 Radioactive Liquid Vasu Sampling and Analysis Program l LOWLR LDtit~ MIN DiVM OF DETECTICH t,1QVID RILEASE $AMPLIh3 ANALYSIS TYPE OF ACTIVITY (L.LD ) (1) TTPE F31RVENCY T*.EQVT.NCY ANALYSIS (*C1/al)
- 1. Batch Waste P P Release Each Batch Each latch Principal Camma $x10' Tank.s (2) _tmittere(3) 1-131 1:10-6
- a. Vaste Monitor P M Dissolved and Tanka One latch /M Entratned Cases 1x10*3
- b. Lauttry (Canna T.aitters) toldup and P M (4)(9)
Monitor Each latch Composite it -1 1:10*5 (0 Tanka Cross Alpha 1:10'#
- a. Wastewater Hold-up Tanka (8) P (4) (9) St-89. Ar-90 Each SLtch Composite Q $x10'0 l3 Pe-SS 1:10-6
- d. Condensate P P Principal Gamma Polisher Each Satch toch Batch .tsittees (3) Sul0*I Sackvash Escovery 1-131 lx10 6 Taaks (6)(7) 3 ~
- 4. Composest M Coolins Coepoeite(6) R-3 1x10"5 Water Drata Taak (7)
W W
- l. Continuous Grab Sample Releases (5) Principal Camma 5:10*7 t
- a. Turbine E* 1 " * " ' 3 )
Bldg Sumps g.g3g g,gn-6 NO. 1&2 Effluents 3
. (6) (7) Composite (4)
M s.3 gat 0-5
- b. Turbine Bldg Sump NO. 4 E f fluents (7) (10)
COMANCHE PEAK - IJNIT 1 1 3/4-13 REV 3 . 4/90 W
I
- TABLE 4.11 1 (Continued)
TABLE NOTATIONS (1) De LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, abo"e system background, that will be detected with 95% l probability with only 5% probability of falsely concluding that a blank ; observation represents a 'real" signal. For a particular measurement system, which may include radiochemical separation: LLD = E V 2.22 x 10 6 . y , exp (.ut) Where: LLD = the "a priori' lower limit of detection (microcurie per unit massorvolume), s3 = the standard deviation of the background counting rate or of tie countir.g rate of a blank sample as appropriate (counts per minute). E = the counting efficiency (counts per disintegration), Y = the sample size (units of mass or volume), 2.22 x 106 . the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A the radioactive decay constant for the particular radionuclide (sec 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 priori (before the fact) limit representing the capability of a measurement system and not as an 1 contariori (after the fact) limit for a particular measurement. (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCH to assure representative sampling. REV. O COMANCHE PEAK - UNIT 1 ! 3/4 19 3/89
,.c-,,-- ---,r -
e , a,-- -.~.,o < , - , . ,c --m-~ .w,.-..,.r -- ~ - .--c-~- ,v, , -- a - , ,n- ---,w.,..-~,----w n-
TABLE 4.11 1 (Coatimqdj TAPLE NOTATIONS i (3) The principal gamma emmiters for which the LLD specification applies include the following radionuclides: Mn 54, Fe 59, Co 58, Co 60, Zn 65, ' Ho 99, Cs 134, Cs 137, Ce 141. Ce 144 shall also be measured, but with an LLD of 5 x 10 6 This list does not mean that aly these nuclides are to be considered. Other gamma peaks that are nJentifiable, 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 Guide 1.21, Appendix B, Revision 1 June 1974. (4) A composite sample is one in which the quantity of liquid sampled is proportional to the Quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. (5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. (6) Tnese waste streams shall be required to be sampled and analyzed in 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 Blowdown monitors or secondary sampling and analysis; or (b) Activity is present in the respective tanks or sumps during the previout 4 weeks. If neither of the above situations exists, then sampling and analysis of tnese tanks and sumps need not be performed. (7) All flow from this waste stream shall be diverted to the Wastewater Holdup Tanks when results of sample analyses show radioactivity present in the waste stream at concentrations greater than or equsl to the LLO values given in this table. Sampling and analysis of the respective tanks or sumps are not required when flow is diverted to the Wastewater Holdup Tanks. (8) Waste Water Holdup Tanks shall be discharged directly tc the Circulating 3 Water Discharge Tunnel when results of sample analyses show radioactivity present values in the tanks at concentrations greater than or equal to the LLO values,given in this table. If the concentrations are less than these RetentionWaste Pond,Water Holdup Tanks may be discharged to the Low Volume (9) With the exception of the required monthly composite sample for H 3 3 composite analyses for Waste Water Holdup Tanks are not required when these tanks are discharged to the Low Volume Retention Pond per Note (8), above. (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.
COMANCHE PEAK - UNIT 1 1 3/4 20 REV. 3 (/90
1 4 1 RADIOACTIVE EFFLUENTS i DEEE CONTROLS 4
]
l 3.11.1.2 in accordance with CPSES TS 6.8.3.e.4 and 6.8.3.e.5 the dose or dose 3 commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see figure 5.1 3) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the !'
whole body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ, ;
APPLICABILITY: At all times. ACTION: 1
- a. With the calculated dose from the release of radioactive materials in 4
liquid 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 identi'tes the cause(s) for exceeding the limit (s) ' and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, ard (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.
-b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
f SURVEILLANCE RE0VIREMENTS 4.11.1.2 Culmulative dose contributions from liquid effluents for the current. calendar quarter-and the current calendar year shall-be determined in- , accordance with the methodology and parameters in the ODCM at least once per 4 31 days. . REV. O C0HANCHE PEAX - UNIT 1 1 3/4-21 3/89
. = _ _ _ . _ _ _ _ _ . _ ._._ _ , ._ _ . . _ . _
- _ - - - ._ _ - _-.-_-.. - - -.- _ - = _ _ _ - - - - - . - _ _ . - . __
4 1 i I RADI0 ACTIVE EFFLUENTS L10VID RADWASTE TREATMENT SYSTEM .; CONTPOLS , i j 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 i to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure S.1 3) would exceed 0.06 trem to the whole body or 0.2 mrem to any organ in a 31-day q period.
I APPLICABillH: At all times. ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged 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 pr(vi: ions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNREsIRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized. 4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be con',idered OPERABLE,by meeting Controls 3.11.1.1 and 3.11.1.2. REV. 1 COMANCHE PEAK UNIT 1 1 3/4 22 8/89 \ - .- .. . . - .- .
E PADI08CTIVE RFFLUENTS EVAPORATION POND CONTROLS 3.11.1,4 The quantity of radioactive material contained in the evaporation pond shall be limited by the following expression: 38i'I y < 1.o
;c) excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day half life, .
j= pond inventory limit for single radionuclide "j" (Curies), CJ= 10 CFR 20, Appendix B. Table !!, Column 2, concentration for single radionuclide *j" (microcuries/ml), V= design volume of liquid and slurry in the pond (gallons), and 264 - conversion unit (microCuries/ Curie per milliliter / gallon). APPLICABillTY: At all times. ACTION:
- a. With the quantity 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.
SURVEllLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained it. ' tach batch of slurry (used powdex resin) to be transferred to the evaporation pond shall 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 j
- C'0 * 'R UCi/cm l
f pCVm where: Q4= 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, ts-134, Cs-137, Co 58 and Co 60. Estimates of the Sr 89 and Sr 90 batch concentration shall be included based on the most recent quarterly composite analysis, REY. 2 COMANCHE PEAK UNIT 1 1 3/4-22a 11/89 i I
RADIOACTIVE EFFLUENTS EVAPORATION POND SURVEILLANCE RE0VlREMENTS (Continued) Cj = 10 CFR 20, Appendix B. Table !!, Column 2, concentration for single radionuclide "j" (microcuries/ milliliter), and 2 R= Slurry volume to resin weight ratio (ml/gm) REV. 2 C0fiANCHE PEAX - UNIT 1 1 3/4 22b 11/89 1
_ _ _ . . __m.-.____._._ - -- -- i 1 RADIOACTIVE ErRVENTS
)
3/4.11.2 CASE 005 EFFLUENTS DOSE RATE i 3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Fig.re 5.1 3) shall be limited to the following: i
- 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 lodine-131, for lodine 133, for tritium, and for all radionuclides
_ 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:- (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.
SURVEILLANCE RE0VIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be-within the above limits in accordance with the methodology and parameters in the ODCM. 4.11.2.1.2 The dose rate due to lodine 131, lodine 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 representative samples and performing-analyses in accordance with the sampling and analysis program specified _in Table 4.11-2. I REV. 0
-COMANCHE PEAK - UNIT 1 I 3/4 23 3/89
)
4 1 o TABt.E 4.II-2 o Radioactive Caseous Waste Sampling and Analysis Premre (*) I
- rn e I
m MI'lIMUM SAMPLING ANALYSIS IJATR LIMIT OF 7,, GASEOUS RELEASE TY"E TYPE OF n FREQUENCY FREQUENCY 11ETFCTION (Lt.D) ( I ) ACTIVITY ANALYSIS spCf/st) t- Waste Gas Storage P j g Tank Each Tank P Each Tank Crab Sample Principal Gaimsa Emitters (2) 1w10
- 2. Containment Purge P
~ P or Vent Each Release (3) Each Release (3) Principal comma Lettters(2) Ix10-Crab Sample M
H-3 foxtde) Ix10
~
- 3. Plant Vent M(3), (4). (5) e Principal Casma Emitters (2) 1xlO Crab sample M(3)
~ H-3 (oxide) Ix10
~
g Continuous (6) W(7) g -12 RadAoiodine i ro b Adsorber Continuous (6) W(7) Principal Camma Emitters (2) -11 1x10 Particulate Sample Continuous (6) M Gross Alpha 1 Composite Par- IrlO~ I ticulate Sample l Continuous (6) Q Sr-89. Sr-90 - I Composiee Par- lx10 m :o
%m ticulate Sample an <
e. Lble Gas ** Continuous (6) Bet a or Cmwa ble Gas l talo I L
- Table notations next page
**Diis sample i s con t i nuou s l y ana l yzed by a r ad i at. ion ensni t or ,
l l
TABLE 4.11 2 (Continued) TABLE NOTATIONS (1) The LLO is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank - observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 sb 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), s) = the standard deviation of the background counting rate or of tie counting rate of a blank sample as appropriate (counts per minute), E = th counting efficiency (counts per disintegration), V = the sample size (units of mass or volumc), 2.22 x 106 . the number of disintegrations per minute per microcurie, Y - the fractional radiochemical yield, when applicable, A - the radioactive decay constant for the particular radionuclide (sec-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 recog.:ized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system , and not as an a costeriori (after the fact) limit for a particular measurement. REV. 0 l COMANCHE PEAX - UNIT 1 1 3/4 25 3/89 l _ _ . -
TABLE 4.11 2 (Continued! TABLE NOTATIONS (Continuedl (2) The principal gamma emitters for which the LtD specification applies include the following radionuclides: Kr 87, Kr SB, 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 todine 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 Guide 1.21, Appendix B. Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER 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 l-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.
' i) 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 af ter 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 LL0s may be increased t,y a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQU! VALENT l 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 1 3/4-26 3/89 puiium is
RADIOACTIVE EFFLUENIS 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 equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABillTY: At all times. LClLQ3
- 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 RE0VIREMENTS 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 00CM at least once per 31 days. REV-. O COMANCHE PEAX UNIT 1 1 3/4 27 3/89 i l
RADIOACTIVE EFFLUENTS DOSE - 1001NE 131.-10 DINE-133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 in accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.9, the dose to a HEMBER OF THE PUBLIC from lodine 131, lodine 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:
- 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.
ApplICABillTY: At all times. ACTION:
- a. With the calculated dose from the release of lodine 131, lodine 133, tritium, and radionuclides in particulate form with half lives greater.
than 8 days in gaseous effluents exceeding any of the above limits, prepare and 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 and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVElllANCE RE0VIREMENTS 4.11.2.'3 Cumulative dose contributions for the current calendar quarter and
- current calendar year for lodine 131, lodine 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 once per 31' days.
L _ REV. O L COMANCHE PEAK - UNIT 1 1 3/4 28 3/89 L L
i RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 6.8.3.e.6, the PRIMARY PLANT VENTILATION SYSTEM and the WASTE GAS HOLOUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see figure 5.1 3) would
)xceed:
- 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 the above limits, prepare and submit to the Commission within 30 days, pursuant to specification 6.9.2, a Special Report that includes the following information:
- 1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taksn to prevent a recurrence,
- b. The provisions of Control 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY 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 1
a [ RADI0 ACTIVE EFFl>Qil$ l 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 ' e limited to less than or equal to 25 mrems to the whole body or any organ, , 1 except the thyroid, which shall be limited to less than or equal to 75 mrems, i l APPLICABIllTY: 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.ll.2.2a, 3,11.2.2b, 3.ll.2.3a., or 3.ll.2.3b., calculations shall be made including direct radiation
-contributions from the units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been !
exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. ; 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 cause of the exposure levels or concentrations, if the estimated dose (s) exceeds the above limits,-and if the release condition resulting in-violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report 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.l' 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
RADI0 ACTIVE EFFLUENTS (Cpptinued) 3/4.11.4 TOTAL i)0SE SURVEILLANCE REOUIREMENTS 4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4. REY. O COMANCHE PEAK UNIT 1 1 3/4-31 3/89
_ _ _ _ _ _ . . _ _ _ ~ _ _ _ _ _ __ _. __ __ __ _ _ _ . _ _ _ . _ . -- . 1G.12 RADIOLOGICAL ENVIRONMENTAL MONITORING i 3/4,12.1 MONITORING PROGPM ($NTROLS 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 3.121. l APPLICABILITY: At all times. I ACTION:
- a. With the Radiological Environmental Monitoring Program not being 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 the program as required and the plan for preventing a recurrence,
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 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 cortective 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 radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + .. 1 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12 2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of
- control 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual Radiological Environmental Operating Report required by Control 6.9.1.3.
! IThe methodology and parameters used to estimate the potential annual dose to l a MEMBER OF THE PUBLIC shall be indicated in this report. I REV. 0 l COMANCHE PEAK - UNIT 1 ! 3/4 32 3/89
RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS ACTION (Continuedl c, With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.121, 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 a,onitoring 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 ODCM reflecting the new location (s).
- d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12 1 from the specific locations given in the table and figure (s) in the ODCH, and shall be analyzed pursuant to the requirements of Table 3.12 1 and the detection capabilities required by Table 4.12 1. k REV O COMANCHE PEAK - UNif 1 1 3/4 33 3/89
i t i n ' TABLE 3.12-1
- f Radiological Environmental Monitoring Progree [
2 ' ] Q rn e NU89BER GF r o REPRESENTATIVE 9
^
EXPOSURE PATHWAY SAlePLES MIO SAM? LING AND TYPE. AMD FREQUEECT AND/0R SAMPLE SAfEPLE LOCATIOil5III COLLECTIO*t FREQUERCY OF AMALYSIS 4 . j g 1. Direct Radiation (2) Forty routine monitoring stations Quarterly. Gaema dose quarterly q either with two or more dosteeters
- or with one instrument for measur-
~
) ing and recording dosa rate !
- continuously placed as follows
- [
An inner ring of stations, one in [ each seteorelegical sector in the i general area of the SITE 800880 arf ;; I i t An outer Ping of stations, one in > w each meteorological sector in j
) the 6- to 8-ke rac+ge from the t a*
site: and
. }
The balance of the stations to be i placed in spectal interest areas i such as population centers. nearby ! j residences, schools, and in one or two areas to serve as control l stations. l
- 2. Airborne ,
Samples free five locations: Continuous sampler ! i Radiofodine and Radioicdine Cannister: ! Particulates operatten with sample I-131 analysis wed ly ; Rg collection weekly. I co < Three samples free close to er more frequently the three SITE 800#0ARY if required by dust Particulate Sancier-i 3 locations. in different loading. Gross beta radio-i sectors, of the highest activity analysis calculated annual average followi filter i ground-level D/O: change: "I and , genea isotopic analysis O ) of ;
- composite (by !
i location quarterly. f
"' - ^"' :o- - --_ _ - - - - - - - -_. - - - , - - - - - - - - - - - , - - - - - - - - - - - _ _ - - - - - - , . - - - ,
N cs TA8LE 3.12-1 (Continued) Radiological Environmental Monitoring Progree S m
- NUMOER OF o REPRESENTATIVE SAMPLING As0 TYPE AND FREQUENCY
" EXPOSURE PATWAY SANPLES Amo COLLECTION FPEGUENCY OF ANALYSIS AND/OR SAMPLE SMFLE LOCATION 5(II c One sample from the 3 vicinity of a causenity
- having the highest calcu-
" lated annual average ground-level D/0: and l One sample free a control location, as for eraerle 15 to 30 km distant and in the least prevalent wind direction. (3) w 3. Waterborne s Gaeas isotopic anal-Squaw Creek Reservoir (6) Monthly composite of
- a. Surface weekly grab saeples. ysis(5) monthly.
u". Composite for trittua analysis quarterly. Monthly composite of Gamma isotepic anal-Lake Granbury weekly grab samples ysis(5) monthly. when Lake Granbury Composite for tritive is receiving letdown analysis quarterly. free SCR. Otherwise, monthly grab sample.III Monthly Gamma isotopic anal-o :o Control-Brazos River psis(5) conthly. os2 upstress of Lake Granbury Composite for tritium O analysis quarterly. Quarterly Gamma isotopic (5)
- b. Ground Samples from two sources and tritive analysis if likely to be affected(8). quarterly.
\
n 1 h 2 TABLE 3.12-1 (Continued) Radiological Environmental Monitoring Protfaa 1 NUMBER OF i A REPRESENTATIVE R EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE A4D FREQUENCY j , ARD/OR SAMPLE SMIPLE LOCATIDIl5(I) COLLECTIO4 FREQUENCY OF ANALYSIS E
~
- 3. Waterborne (Continued) i j ._, c. Drinking One sample from Squaw Creek Composite of weekly I-131 analysts of Reservoir. grab samples over each composite sample j 2-week perfod when when the dose calcu-I-131 analysis fs lated for the con-i perfermed: seethly sumption of the water i
compostte of weekly is greater than 1 eree grab samples other- per year (9) . Gross wise. beta and gamma 150-j ~ topic analyses (5) R monthir. Composfte for trftfue analysts j h quarterly.
- d. Sediment One sample from downstream area Seelannually. Gamma isotopic analy- l free with existing or potential sis (5) samlannually. '
Shoreline recreational value. l
- 4. Ingestion i a. Milk Samples free stiking anteals in Seafoonthly when Gamma isotopic (5) three locations within 5 he anteals are on and 1-131 analysis i j distance having the highest dose pasture: eenthly seafsonthly when !
, ,, potential. If there are none, at other times. anteals are on pas- l l y e. sample from of1 king enteals in ture; monthly at l each of three areas between 5 other times.
- to 8 km distent where doses are calculated to be greater than I aree per yr.(9) One saeple
- from allking animals at a control location. 15 to 30 km distant and in the least prevalent wind directien.(3l-
_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -__._.._.._____a
[ g TABLE 3.12-1 (Continued) Radiological Environmental Monitoring Prograe i n
- i3; - nunsER or REPRESENTATIVE t j ,
! EIPOSURE PATiefAY SAMPLES Aa0 SAMPLING ANO TYPE AND FREQUENCY t i a N AND/0R SAprLE SAMPLE LDCATIQh5(1) COLLECTIOM FREQUENCY OF ANALYSIS l' c 4. Ingestion (Continued) E
- Sample seelannually. Games isotopic I
i
- b. Fish and Gne sample of at least two
~ Invertebrates recreationally important species analysis (5) on j i '
i in vic"ntty of plant discherge area. edible portions. .1
- One sample of same species On areas .
not influenced by plant discharge. ]
- c. Food Products
- One sample of each principal citss At time of harvest (10) Gamma isotopic l analysis (5) on 4
of food products from any area [ that is irrigated by water in which edible portion. [ N Ifquid plant wastes have been [
?
w discharged.
" Gamma isotopic (5)
A sample of broad leaf vegetation Monthly. when l grown nearest eacn of two dif- available. and I-131 analyses. I ferent offsite locations of highest predicted annual average j i ground level D/0 ff milk sampling 15 not performed at all required t 'l l ocations. (5) i a One sample of each of the sieller Monthly. when Gamma isotopic ; j > broad leaf vegetation grown 15 to available. and I-131 analyses. i ra m 30 km distant in the least pre-DQ valent wind direction (3) if etik sampling is not performed at all
-' required locations.
i i ! i i
- Reports from 3 additional airborne radiof odine saeple locations may be supplemented for broad leaf I I, vegetation samples. ;
e I
IMLE 3.121 (Continuedl TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall ba provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the ODCM. Refer to NUREG 0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment, if specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time, in these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCH. 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 ODCH including a revised figure (s) and table for the ODCH reflecting the new location (s). (2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters, film badges shall not be used as dosimeters for measuring direct radiation. (3) The purpose of this sample is to obtain background information. If it is not practical to ettablish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. (4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and 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 1 3/4 38 8/89 1
TABLE 3.12-1 (Continued) 4 i TABLE NOTATIONS (Continued) (5) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the eff'uents I 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 1 significant influence of the discharge. (7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge. (8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or ; recharge properties are suitable for contamination. (9) The dose shall be calculated for the 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 continuourly, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. REY. O COMANCHE PEAK - UNIT 1 1 3/4-39 3/89
o x. e TABLE 3.I2-2 m Reporting Levels for Radioactivity Concentrations in Environmental Samples . 9 x AIRBORNE FARTICULATE FISM MItX Ftm FRUDUCTS
- IdATER OR CASES (pCi/m') (pC1/kg met) (pC1/1) (pC1/kg. wet) g ANALYSIS (pci/1)
Z
~
N-3 20.000 Mn-54 1.000 30.000 Fe-59 400 10.000 Co-58 1,000 30.000
~
Co-60 300 10.000 N 20.000 i In-65 300 8 400 Ir-Wb-95 0.9 3 300 T-131 2 30 10 1.000 60 1.000 Cs-134 50 20 2.000 70 2.000 Co-I37 200 300 De-1.a-140 D"Q (*) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pt.hway exists, a value of
- - 30.000 pC1/1 may be used.
o (**) If no. drinking water pathway exists, a value of 20 pCi/I ecy be used. I i
1 d j. i. ?, n a ... )
%I i' TABLE f. 12-1
-y Detection Capabilities for Environmental Sample Analysis (" (
N Lower Limit of Detection (LLD) (3) - e Q
'~
WATER (pC1/1) AIR 30MBE FARTICULATE Ok GASES (pC1/m') FISH (pC1/kg, wet) .. MILK (pC1/1) FOOD FRODUCTS
~(pC1/kg. wet)
SEDIIE!NT ANALYSIS (pC1/kg, dry) o
,~
Croen Beta 4 0.01 i H-3 2000* Mn-54 15 130 r.
- f. Fe-59 30 260
- w I ) Co-58.60 15 130
- In-65 30 260
! L-hb-95 15 i I-131 1** 0.07 1 60 ] Co-134 15 0.05 130 15 60 150 l Co-137 18 0.06 150 18 80 180 Ba-La-140 15 15 i (a :xs 1 Nm ) ce < 4 *~
- If no drinking water pathway esists, a veIne of .3000 pC1/1 may be used.
O **1f no dricking water pathway exists, a valve of 15 pC1/1 mey be weed. I 1 I i 4
)
4 -
TABLE 4.12-1 (Continued 1 TABLE NOTATIONS (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.).3. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guf % 4.13. (3) The LLD is defined, for purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will yield a net , round, that will be detected with 95% count, above probability system with only abacka!% probability of falsely concluding that a blank observation represents a "real" signal. 4.Q$_lb LLD " E V exp (.Act) 2.22 Where: LLO - the "a priori" lower limit of detection (picocurie per unit mass or volume), sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E the counting efficiency (counts per disintegrationj, V - the sample size (units of mass or volume), 2.22 - the number of disintegrations per minute per picocurie, Y - the fractional radiochemical yield, when applicable, A-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 Lit should be used in the calculation. COMANCHE PEAK - UNIT 1 I 3/4-42 REV. 0 3/89
l TABLE 4.12 1 (Continued) TABLE NOTATIONS (Continued) (3) Continued it should be recognized that the LLD is defined as an 1 oriori (before the fact) limit representing the capability of a measurement system and not as an A costeriori (after tho f act) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LL0s will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interferin these LLD'g nuclides, or other s unachievable. uncontrollable In such cases, the circumstances contributing factors may render shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. s l { REV. O COMANCHE PEAK - UNIT 1 1 3/4-43 3/89
-- , , -, r w. ,-+4--
*W- -r4 -- r - -._,.4, . -
( PAD 10 LOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 In accordance with CPSES TS 6.8.3.f 2, a Land Use Census shall be conducted and shall identify within a 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 ml (500 ft2) producing broad leaf vegetation.
APPLICABILITY: At all times. ACTION.:
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report.
- b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20%
greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) within 30 days, to the Radiological Environmental Monitoring Program given in Part 11 of the ODCH. 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 ODCM reflecting the new location (s),
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE00lrEriNTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE B0VHDARY 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 PEAK - UNIT 1 1 3/4-44 8/89
. - _ ~~ _ - - -- _ _ RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 12.3 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 baen approved by the Commission, that correspond to samples required by Table 3.12-1. APf_LICABILITY* At all times, hillM:
- 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. EURVEILLANCE RE0VIREMENTS 4.12.3 The Ir..erlaboratory Comparison Program shall be described in the ODCH. 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. REV. O COMANCHE PEAK - UNIT 1 I 3/4-45 '89 l l
a - - - ~ - sr4 1 2-s,'- an--- - - 4. m,- i BASES i-l l I B 3/4-0 REV. 1 8/89
- . - . . - - . - - . - _ . .. ..- . . ~ - - - - - _ - _ _ .
1 l ltGIRUMENTATION BASES ~ 3/4.3.3.4 RADI0 ACTIVE LIOVID 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 3 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 EFFlVENT MONITORING INSTRUMENTATION The radioactive gaseous effluent' instrumentation is provided to monitor l 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 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of -10 CFR Part 20. The OPERABILITY and'use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to'10 CFR . Part 50. 3/4.3.3.6 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient- meteorological data are available for estimating potential radiation doses to-the public as a _ result of routine or accidental release of radioactive materials-to.the atmosphere. This capability is-required to _ 1 evaluate the need for= initiating protective measures to protect th9 health' and_ safety of the public-and is consistent with the recommendations of the second proposed _ Revision-1 to Regulatory Guide 1.23, "Onsite Meteorological
~_ Programs," April 1986.
l _ I REV. O COMANCHE PEAK - UNIT 1 I B 3/4-1 3/89
I INSTRUMENTATION BASES 3/4,7.15 SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10CFR70.39(c) limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values. Sealed sources are classif.ied into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled-are required to be tested more often than ths:o which are not Sealed sources a whhn Tre continuously enclosed within a aielded mechan;ta (i.e., sealed , sourtes within radiation monitoring or borc. measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
't
?
o s I REV. O COMANCHE PEAK - UNIT 1 1 B 3/4-2 3/89 L 1
, , _ - __ _, . , _ . _ _ . , . . , _ , . . , , .~.__ . . _ . _ _ , ,m _ , _ , .. . _ ..
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 L1001D 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, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. .The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. This control applies to the release of radioactive materials in liquid effluents from all units at the site. The required detection capabilities for radioactive materials in liquid
-waste = samples are tabulated in terms of- the lower limits of detection (LLDs).
Detailed discussion of the LLD and other detection limits can be found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300, 3/4.11.1.2 DOSE This' contrcl is 'provided to implement the requirements of Sections II. A, III. A and IV. A of 10CFR50, Appendix 1. The Control implements the guides set - forth in Section II.A of Appendix 1. The ACTION statements provide the : required operating flexibility ano at the same time implement the guides set forth in Section-IV.A of Appendix I to assure that the releases of-radioactive material in liquid effluents to UNRE3TRICTED AREAS will be-kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility-will not result in radionuclide concentrations in the finished drinking water that are-in excess
-of the requirements of 40CFR141. The dose calculation methodology and
' parameters in the ODCM implement the requirments in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedur%s based on models and data, such that the actual exposure-of a MEMBER OF THE PUBLIC through appropriate _ pathways is unlikely to be substantially underestimated. The equations specified in 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 Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision l- 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,'" April 1977.
REV. O COMANCHE PEAK - UNIT 1 I B 3/4-3 3/89 l .
RADIOACTIVE EFFLVfNTS BASES QQ1E (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 L10VID 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 11.0 of Appendix 1 to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set -forth in Section II.A of Appendix I,10 CFR Part 50 for liquid effluents. This control applies to the release of radioactive materials in liquid effluents 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 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 1n ControlJ3.11.1.4 assumes the pond inventory 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.
2 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 radienuclides to their respective concentration limitation is less than the ratio of the 10-CFR Part 50, Appendix 1. Section II,A, total body leyel.to the 10 CFR 20.105(a), whole body dose limitation, or that: de l C 3 "'*
- 500 woms/yr o.ooo REV. 2 COMANCHE ,LAK - UNIT 1 I B 3/4-4 11/89
_ .._ . . ...m ._ - . . . . - _ _ . . .-.,___ . _ __ . _ . _ _ _ _
- RADIOACTIVE EFFLUENTS
- BASES _
*~~~
EVAPORATION POND (Continued) s where: cj - : radioactive. slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA EP, in microcuries/ milliliter, and Cj - 10 CFR 20, Appendix-B, Table !!, Column 2, concentration for 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 I gm/ml and_the absorption characteristics for gamma radiation are essentially that-of water. Therefore, I I *.!.- I < aoos i .C, I c, e mugem _ 7 j < a006 UCi/gm R y pCvml c
. where the terms a N defined in Control.'4.ll.l.4.
. Th'e batch limits. provide assurance that activity input to the EP will be minimized, and a means _of identifying that the radioactive. material released '
is within- the inventoryil tmitation of Control 3.11.l.4. 1 t 5 L _ _ _ REV. 2 COMANCHE PEAXi UNIT. I B 3/4-5 11/89,
- , ., , ,-,-,-,_ - . - - . - - -- -, . . . , . , . , , - - , ,.w.
n o@f0 ACTIVE EFFLUEWS BASES 'I 3/4111.2 CASE 0VS' EFFLUENTS 3 /a .11. 2.1 DOSE PATE This control is provided to ensure that the dose at any time at and beyond _the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 to UNRESTRICTED TheAREAS. 1 annual dose limits are the-doses associated with-the concentrations of 10CFR20, Appendix B, Table II, Column 1. _These limits provide reasonable assurance that radioactive-material discharged in gaseous effluents will not , result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA,- i 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. ! doses for such MEMBERS OF THE PUBLIC shall be given-in the 00CM.The meth 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 j 4 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 corr 6sponding thyroid dose rate - above
-to 1500 background mrems/ year, to a child via the inhalation pathway to less than or equal This control applies to the release.of radioactive materials in gaseous
.. ' effluents -from.al.1 units at the site. -
-The required dete'.tionicapabilities for radioactive materials in liquid-o 1 Detailed discussion 3f the LLDs and-other detection limits can ,
i i Currie, L.A., " Lower Limit of Detection' Definition and Elaboration of a-L u lNUREG/CRe4007 (September 1984), and innual, theHASL-300, HASL Procedur }r ' B $1
- COMANCHE-PEAX UNIT 1 October 22, 1990 I B 3/4 6 ;
1 i v- - - , - -,,w, -- ,w- w w - e
1 I RADIDACTIVE EFFLUENTS
-l SASES 3/4.11,2,2 00SE - NOBLE GASES This control is provided to implement the requirements of Sections !!.B. !!I. A and IV. A of 10CFR50, Appendix 1.
forth in Section 1.8 of Appendix !. 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 ! to assure that the. releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonat,1y achievable." -The Surveillance Requirements implement the requirements in Section III. A of Appendix ! that conformance with the guides of Appendix 1 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 00CM 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 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.
The 00CM equations provided for determining the air doses at and beyond the SITE BOUNDARY 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 radwtste treatment systems, the gaseous effluents from the shared system are 1 proportioned among the units sharing that system. l l COMANCHE PEAX --UNIT 1 I B 3/4-7 October 22, 1990 l
l DBD10 ACTIVE EFFlVEN7S DASES
}L4jl.2.3 00SE IN PnRTICULATE FORM 100lNE 131. 100lNE 133. TRITIUM. AND RAD 10AM !VE MATERIAL This control is provided to implement the requirements of Sections ll.C.
Ill.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 ! to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section ll!.A of Appendix ! that con 4rmance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure be of a MEMBER substantially OF THE PUBLIC through appropriate pathways is unlikely to underestimated. The 00CM calculational methodology and parameters for calculating the coses 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
' Appendix Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, 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 radionuclice 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 ccnsumption 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. COMANCHE PEAK - UNIT'l ! B 3/4 8 October 22, 1990
- dad 10ACTfVE EFFLUENTS BASES 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABillTY of the WASTE GAS HOLOUP SYSTEM and the PRIMARY PLANT SYSTEM ensures that the systems will be available for use whenever gaseous effluents recuire 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, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section I1.0 of Appendix ! to 10 CFR Part 50. The specified-limits governing the 'use of appropriate portions of the systems were specified as a- suitable fraction of the dose design objectives set forth in Sections ll.B and II.C of Appendix 1,10 CFR Part- 50. for gaseous effluents.
This control applies to the release of radictetive 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 Jproportioned among the units sharing that system. L -COMANCHE PEAK - UNIT 1 I B 3/4 9 October 22, 1990- }
W ^ ACTIVE EFFLUENTS isSES 2 s.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 recuires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites containing up to four reactors, it is highly unlikely that the resJ tant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 4 Part 190 if_the individual reactors remain within twice the dose design oojectives of Appendix 1,- and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small. The Special Report I
)
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 limi For the purposes of the Special Report, it may be ascumed 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 for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. L COMANCHE PEAK - UNIT 1 I B 3/4 10 October 22, 1990 I l -
1 I 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITOPHQ BASES 3/4.12,1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the fromhighest the plant potential radiation exposc = of. MEMBERS OF THE PUBLIC resulting oper.ation. This monitoring program implements Section IV.B.2 of Appendix 1 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 provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1. November 1979. The initially specified monitoring commercial operation. program will be effective for at least the first 3 years of Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LL0s). The LL0s required by Table 4.12 1 are considered optimum for routine environmental measurements in-industrial laboratories, it should be. recognized that the LLO is defined as an A oriori (before the fact) limit representing the capability of a measurement particular measurement. system and not as an A costeriori (after the fact) limit for a Detailed discussion of the LLO, 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 Hanual, HASL 300. 3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the 00CM are made if required by the results of this census. The best information from the door-to door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendig I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m' 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 vegetablgs assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the folicwing assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetatign (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m'. COMANCHE PEAK - UNIT 1 I B 3/4 11 October 22, 1990 1
, . . . - . . ~ . - . . - . - . - _ - - - . - . - .. .... - . _ - ..~ - -. .- _ _ . . - . _ .- - .
J RADIOLOGICAL EWIRONMENTAL MONITORING I BASfs
-3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 4
The requirement for participation in an approved Interlaborator Comparison Program is provided to ensure that independent checks on ythe precision and accuracy of the measurements of radioactive materials in environmenta'l 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 !Y.B.2 of Appendix ! to 10 CFT< Part 50, t 15
.i 3
- COMANCHE-PEAX UNIT 1 'I B 3/4 12 October 22, 1990 a_. . . , _ _ _ _ - _ . - _ _ _ _ , _ . . . , . . . -
I 1 9 SECTION 5.0 DESIGN FEATURES I 5-0
5.0= DESIGN FEATURES i MAP DEFINING UNRESTRICTED AREAS AND EXCLUSION AREA BOUNDARY FOR RADI0 ACTIVE GASE0US AND LIOUl0 EFFLUENTS 5.1.3- Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE B0UNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3. The definition 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. b-REV. 0
-COMANCHE PEAK -UNIT 1 I'5-1 3/89 l'
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,a a. 5 A1 a k A ,-ana- - .n - --- ,-M-m.6 4,- a m--A5- .,+A sm+, 4,4,o A f' SECTION 6,0 ADMINISTRATIVE CONTROLS I 6-0
ADMINISTRATIVE CONTROLS ANNUAL RfDIOLOGICAL 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 Oose 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 shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as scon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1,; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable. A single submittal may be made for a multiple unit station. One map shall cover stations near the SITE B0UNDARY; a second shall include the more distant stations. REV. O COMANCHE PEAK - UNIT 1 1 6-1 3/89
@h!NISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT R1 LEASE 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 radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974, with data 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 released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology ud parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM). 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 upo:, request. REV. O COMANCHE PEAK - UNIT 1 1 6-2 3/89 l
h ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January l'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 sources, 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 i 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 liquid or
. gaseous effluent monitoring instrumentation was not corrected within the time specified in Controls 3.3.3.4 or 3.3.3.5, respectively; and a description of the events leading to liquid holdup tanks or-gas storage tanks exceeding the Technical Specification limits.
l 6.14 0FFSITE-DOSE CALCULATION MANUAL (ODCM) Changes to the ODCH:-
.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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose,1or 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 I 6-3 8/89
l l ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCVLATION MANUAL (ODCM) (continued) 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-made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date-(e.g., month / year) the change was implemented, T h REV, O COMANCHE PEAK - UNIT 1 I 6-4 3/89
a - w5 J - _w PART 11 CALCULAT10flAL METHODOLOGIES e
SECTION 1.0 LIQUID EFFLUENTS The L#.nche 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., uC1/ml). The conversion factor for detector output from counts per minute to uCi/mi is determined during the calibration of each monitor and is input into the data base for the monitor microprocessor. 1.1 GENERAL METHODOLOGY FOR DETERMINING LIOUID EFFLUENT MONITOR SETPOINTS Normal liquid releases from the radwaste system will be batch type releases and will originate from the laundry holdup tanks and waste monitor tanks and terminate in Squaw Creek Reservoir. To ensure such discharges do not exceed the limits of 10CFR20, Appendix B, Table II, Column 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 te 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, f 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. 11 1-1 Rev. 0
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I 3/89
,.. . - .. - . - . . - - - - . . . -. ~ --_ - . - . - - - . . . . .
Further, if the calculated 7alue 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 Isotooic Concentration of the Waste Tank Determine the isotopic concentration of the waste tank to be released: I Cg =t C, + (C, + C, + Ct + C,,) %, M) 1 3 Where: IC g - Sum of the concentrations of each radionuclide, 1, . in the waste tank (uci/ml) IC . Sum of the concentrations of each measured gamma-g E emitter, g, (uti/ml) as required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. Ca _ concentration cf alpha emitters as measured in the. most recont monthly composite sample (uCi/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 (uC1/ml)
. required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.
Ct = concentration of 3H as measured 'in the most recent monthly composite sample (uC1/ml) required by-Radiological _ Effluent f,ontrol 3/4.11.1.1, Table 4.11-1. 6
-CFe = concentration of 55F e 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, i 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:
11 1-2 Rev. 1 8/89
. - _ __ .-- - - - . - . . - . . . . . - - - - . - . -. - -~
Radwaste System Pumos laundry Holdup and Monitor Tank Pump #1 - 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 Holduo 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.- ' l.1.3 Dilution of Liauid Effluents Due to Circulttina Water Flow (F) Since: liquid effluent from the radwaste trea . ment system is mixed with circulating water prior to being discharged to Squaw Creek Reservoir, the setpoint for detector XRE-5253 is i function of the circulating . water. flow rate. The maximum circulati,'g water f_ low 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:
~
1 . F(diluting flow) = (275,000 gpm/ pump) x (# of pumps) x SF lEq.12) Where: SF - Safety Factor of (.9). This compensates for flow fluctuations from the rate predicted by the circulating i water pump' curves (Fig. 1.3). L - L 11 1-3 Rev. 1 8/89
?
As an additiona1' 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 rekases, 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. 14) Where: f - effinent 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, Ff, 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 required dilution flow for any other concurrent release.- x 1.1.5- Reauired Dilution Factor (RDF) The required dilution factor ensures that the maximum permissible concentrations expressed in 10CFR20, Appendix B, Table II, Column?*,
.and a total concentration of dissolved or entrained noble gases of 2 x 10-4 uti/ml are not exceeded during a discharge. The required dilution factor' includes a safety. factor of 2 to provide a margin of ,
a,ssurance that the instantaneous concentration limits are not exceeded.
- MPCs listed in 10CFR20 give values for each isotope in both a soluble and insoluble form. The lowest value for each isotope should be used. A value of-2 x 10-4 uCi/ml for dissolved or entrained noble gases shall be used.
11 1-4 Rev. 1
. 8/89
l RDF = (I (Cg /KPCg )) x hr . 1 i
= (I (C,/MPC ) + (C,/MPC, + C,/MPC, + C /MPC t t
+ C,,/MPC,,)) x SF [Eq. 1-4 Where: MPCj* Maximum Permissible Concentration of Radionuclide i SF = Safety Factor of 2.
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 maximc.n value for the high alarm setpoint for detector XRE 5253 would then be calculated in accordance with the equation for C1 w in the following section. i [ See footnote on page !! 1 4. i II 1-4a Rev. 1 8/89 l
i ! 1.1.6 Vooer Setooint Limit for Detector XRE 5253 a C p=(ADF/RDF)xj C [Eq. 1-5) l g Where: C1w The liquid waste effluent monitor alarm setpoint, , This corresponds to the gamma concentration in the undiluted ',aste stream which after dilution would result in MPC level releases (uCi/ml). All other variables are as previously defined. ' i As a further consideration, the reservoir into which the diluted c [ 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: s F' = r_(1 (C{/MPCg )) (Eq. 1-6) Where: F' = Adjusted Circulating Water flow Rate C'i Concentration of radionuclide i in the Reservoir-(uCi/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 intike structure as indicated by location SW6 on Table- 3.1 and- Figure 31- of. this manual, , MPCi * = Maximum Permissible Concentr',?. ion of hidionuclide i F = (275,000 gpm/ pump) x (r of u mps) x SF , NOTE: If C'i is-less than LLD then F' r F and no t.djusted flow- ,
- rate need be considered in the calculation of ADF. The
, LLO. 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 !! 1 5 Rev. 0 1
3/89
When considering the mixture of nuclides in the liquid ef fluent stream in terms of detector sensitivity, the most probable nuclides present would be those referer,ced in Radiological Ef fluent Control 3/4.11.1.1, Table 4.11 1. Table Notation 2. Figure 1.2 is a representative energy spectrum response for the RD 33 type cetector used in XRE 5253. This curve illustrates that for any given mixture of the most probable ghmma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant, in fact between 137Cs 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 ef fluent concentrations. However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required. L
!! l-6 Rev. 0 3/89 1
J
i 1.2 DOSE CALCVLATION FOR L10VID 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 calculated using the following equation: D T
=ID k +
ID(lake), (Eq. 1-7) k m Where: Di = the dose commitment to the total body or any organ 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 k(mrem). The equation for calculating Ok is given in Section 1.2.1 (Eq. 1 8). 0(lake)m = the dose comnitment received by the total body or any organ diring the desired time period, m, (normally m = 31 days) due to the buildup in the 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 af Dose Due to a Batch Release The dose commitment to the total body or any organ due to a batch release will be calculated using the following equation: Dk
- iI ^1t 'k cik "k (Eq. 1-8)
!! l 7 Rev. 0 3/89
Where: t( 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 895 r, 90S r, 2 h, ' 55Fe 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 average undiluted liquid effluent flow rate to the average circulating water flow rate during the release. The average liquid effluent flow rate is based on the actual flow past the monitor into the circulating water. Fk averaoe undiluted liauid effluent flow rate circulating water flow rate Att the site related ingestion dose commitment factor for the total body or any organ, , for each identified gamma or beta emitter (mrem /hr per uC1/ml). Att is calculated as follows:
- l'l4*l0 (U /D + U BF [Eq. 1-10]
A h wW f ) DF g Where: 1.14x105 - unit conversion factor, Uw - adult water consumption, 730 liters /yr Ur adult fish consumption, 21 kg/yr BFj bioaccumulation factor for radionuclide i, in fish from Table A 1, Ref. 2 (pCi/kg per pCi/1) l 11 1 8 Rev. 0 3/89
1 DFi = adult dose conversion factor for radionuclide i, from Table E ll, Ref. 2 (mrem /pCi ingested) Dw Dilution factor from the near field area within one quarter mile of the release point to the potable water intake for the adult water consumption; 1.0 for CPSES. (unitiess) Calculated values for Att are given in Teble 1.1. 1.2.2 [JLkulation of Dose Due to Radionuclide Builduo in the Lake The dose 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 buildup is determined as follows: D(lake )m = 1.14x 10 4(I DFt (C'twU, + C'itU t))t (Eq. 1-ill i Where. 1.14 x 10 4 = units conversion factor j C'iw = 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 j manual (pti/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) l t = 744 hrs (31 days) or other time period of interest (hr) All other variables are previously defined. 11 1-9 Rev. 0 3/89
NOTE: This calculation is only required if activity is detected in water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1, Table 4.12-1. If the measured activity in water or fish is less than the required LLD values, the concentration for that particular pathway is assumed to be zero. l l-11 1-10 Rev. 0 3/89
l.3 DOSE PROJECTIONS FOR L10VID EFFLVENTS Radiological Effluent Control 3/4.11.1.3 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 UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to ary organ in a 31 day period. The following calculational method is provided for performing this dose projection. At least once every 31 days, the total dose from all liquid releases for the quarter to date will be divided by the number of days into the quarter and multiplied by 31. 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 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. 11 1 11 Rev, 0 l 3/89 L- - - - . -
TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml) ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LtfNG Cl-LLI H-3 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 4.62E+07 2.87t+06 1.79E+06 0.00E+00 0.00E+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 0.00t+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 Mn-56 0.00E+00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03 Fe-55 B.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 l 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 En-65 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 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-8B 0.00E+00 .2.99E+02 1.59E+02 0.00E+00 0.00E+00 0.00E+00 4.00E-09 i Rb-89 0.00E+00 1.98E+02 1.39E+02 0.00E+00 0.00E+00 0.00E+00 1.15E-Il
$r-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 l
11 1-12 Rev. O i 3/89 L
TABLE !.1 SITE RELATED INCESTION DOSE COMMITMENT FACTOR A i' (mrem /hr per uCi/ml) ISOTOPE ROSE LIVER T-BODY TRYROID KIDNEY LttNG 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 St-91 8.79E+02 0.00E+00 3.55E+01 0.00E+00 0.00E+60 0.00E+00 4.19E+03 St-92 3.33E+02 0.00E+00 1.44E+01 0.00E*00 0.00E+00 0.00E+00 6.60E+03 Y-90 1.38E+00 0.00E+00 3.69E-02 0.00E+00 0.00E+00 0.00E+00 1.46E+04 Y-91m 1.30E-02 0.00E+00 5.04E 04 0.00E+00 0.00E+00 0.00E+00 3.82E-02 Y-91 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 1.llE+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-91 0.00E+00 1.39E+00 0.00E+00 2.82E+03 Zr-97 1.53E-01 3.09E-02 1.41E-02 0.00E+00 4.67E-02 0.00E+00 9.57E+03 Nb-95 4.47E+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 1.05E+03 0.00E+00 1.07E+03 Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.07E-02 4.92E+01 Tc-101 3.03E-02 4.36E-02 4.28E-01 0.00E+00 7.85E-01 2.23E-02 1.31E-13 Ru-103 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00 2.31E+03 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+0! 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 Tc-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 4.11E+03 5.00E+04 0.00E+00 6.03E+04 Te-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01 11 1-13 Rev. 0 3/89
=. - - - . _ _ _ - -- --- -- --.- .- . .
TABLE 1.1 SITE RELATED INCESTION DOSE COMMITMENT TACTOR A U (mrem /hr rer uCi/ml) ISOTOPE PONE 1.IVER T-BODY THYR 0tD r!DNEY Lt'NG GI-LLI Te-131m 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.00E+00 B.74E+04 Te-131 2.0$E+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 1.87t+03 1.63E+04 0.00E+00 8.02E+04 1-130 9.01E+01 2.66E+02 1.0$E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 1-131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E403 0.00E+00 1.87E+02 I-132 2.42E+01 6.47E+0) 2.26E+01 2.26E+03 1.03E+02 0.00E+00 1.?2E+01 1-133 1.69E+02 2.94E+02 8.97E601 4.32E+04 5.13E+02 0.00E+00 2.64E+02 1-134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01 0.00E+00 2.99E-02 I-135 5.28E+01 1.38E+02 5.10E+01 9.llE+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 0.005+00 6.97E+04 9.55E+03 1.42E+04 Cs-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 Cs-138 2.69E+02 5.31E+02 2.63E+02 0.00E+00 3.90E+02 3.85E+01 2.27E-03 Ba-139 9.00E+00 6.41E-03 2.64E-01 0.00E+00 5.99E-03 3.64E-03 1.60E+01 Ba-140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+0' Bn-141 4.37E+00 3.30E-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 1.701-03 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-14t 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+0! 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
TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Aj, , (mrem /hr per uti/ml) , ISOTOPE S.Qg g T BODY THYROID KIDNEY M 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 8.34E404 Np 239 1.28E 01 1.2SE 02 .6.91E 03 0.00E+00 3.91E 02 0.00E+00 2.57E+03
*Sb 122 1.98E+01 3.90E 01 5.79E+00 2.69E 01 0.00E+00 1.03E+01 5.68E+03 5 l
**Sb 124 2.41E+02 4.54E+00 9.50E+01 5.81E 01 0.00E400 1.87E+02 6.81E+03
- The adult dose conversion factors, Oft , for Sb 122 are not published in 5 Reference 2. The calculation of dose conversion factors and site related ingestion dose commitnant factors for Sb 122 is documented in Reference 10.
**The adult dose conversion factors, OFj,.for Sb 124 are not published in 5 Reference 2. The site related dose commitment factors for Sb 124 were caleviated t.**ng the " Adult ingestion Dose Factors" given in Table A 3 of Refer 6 Ace 11, and Equation 1 10 of Part !!, Section 1.2.1 of this Manual.
r 11 1 15 P.ev. 5 , 12/90
l.4 SERVICE WATER EFFLUBT_ DAD QTION MONITORS 1RE 4253/_4 HQ The concentration of radioactive material in the service water effluent line noimally is expected to be insignificant. Therefore, the monitor alert alarm setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. To this end, the alarm setpoint will be initially established at three (3) times background until further data can be collected, if this effluent stream should become contaminated, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows: sw
*( IC ) + DF [Eq. 1-12)
R Where: Cgw = the Service Water ef fluent monitor alarm setpoint. Cg the concentration of each measured gamma emitter g, observed in the effluent (uti/ml) DF - [ (C3/MPC i ) o the dilution factor required to ensure maxdmum 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 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, F(, equal to 1.0. I 11 1-16 Rev. 1 8/89
1.5 TURBINE BVil0ING SUMP EFFlVENT RADIATION MONITOR 1RE 5100 The purpose of the turbine building sump monitor (IRE 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 surp water with no detectable radioactivity (as defined in Radiological Effluent Control 3/4.11.1.1, Table 4.11 1) is tilowed 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 collected. 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 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 Statement #3 given in Appendix G.
l l 11 1-17 Rev. 1 8/89
1 I l 1 1.6 QEr!NITIONS OF COMMON LIOUID EFFLUENT PARAMETERS SECTION OF M DEFINITION INITIAL USE ADF Actual Oilution f actor (unitiess). 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 g 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 /hr per uti/ml) BFj Biaccumulation factor for radionuclide, i, 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) CeF The concentration of 55F e in liquid waste as 1,1.1 measured in the analysis of the most recent quarterly composito sample required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. (uti/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 (uC1/ml) Cj The concentrations of radionuclide, i, in the 1.1.1 waste tank. (uCi/ml) C'j 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. (uti/ml)
C'jr 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). l
!! l 18 Rev 0 3/89 i
- - - . - . . - - - ~ - - _ - - . . - - - . . - _ . . . .
A f [1 i i Cik The isotopic concentration of radionuclide i 1.2.1 i found in the pre release sample for batch i release k. Concentrations are determined 1 primarilyfromgammaisotopicanagysispf the liquid effluent sample. For W$r. WUSr, JH, bbFe and alpha emitters, the last ; L measured value will be used. (cCi/ml) : e C'jw The concentration of radionuclide i in the 1.2.2 ! , reservoir as measured at the circulating water d intake structure shown as location SW6 on 1 Table 3.1 and Figure 3 1 of this manual (pC1/1). i C1w The liquid waste effluent monitor alarm setpoint. 1.1.6 This corresponds to the gamma concentration
- in the undiluted waste stream which after dilution would result in MPC level releases. '
(uti/ml) Cg. The concentration of 895 r and 90S r in liquid 1.1.1 waste as measured in the analysis of the most t recent quarterly composite sample required by ) Radiological Effluent Control- 3/4.11.1.1, Table 4.11 1 (uct/mi) Cw 3 The Service Water effluent monitor alarm setpoint. 1.4 (uC_1/ml) ' Ct The concentration of 3H 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 (uti/ml) DFj Adult dose conversion factor for-radionuclide, 1.2.1 1,fromReg. Guide 1.109(mrem /pCiingested) Ok The dose commitment received by the total body- 1.2 i or any organ during the duration of batch- , release k of liquid effluents. (mrem) . 0(lake)mThedose_commitmentreceivedbythetotalbody 1.2 I or:any organ during a desired time period..m. ' due- to the buildup in the lake of previously - glischarged radionuclides. (mrem) Di The total dose commitment to:the total body or any 1.2 organ due to all- releases of-liquid effluents during a desired. time interval. (mrem) 1 li I l
!! l 19 Rev. 0 3/89 L - . . - _ _._.__u___..__..__.._._.__..._. _ _ _ . . , . . _ , _ - - . _ _ . _ _
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. (uC1/ml)
MPCF e Maximum Permissible Concentration
- of 55F e. 1.1.5 (uCi/ml)
MPCg Maximum Permissible Concentration
- of each 1.1.5 identifitd gamma emitter, g. (uCi/ml)
MPCi Maximum Permissible Concentration
- of 1.1.5 radionuclide, i. (uti/ml)
MPCs MaxiumPerm11sibleConcentration*ofamixture 1.1.5 of o Sr and VUSr. (uCi/ml) MPCt Maximum Permissible Concentration
- of 1.1.5 tritium (3H) (uCi/mi)
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 2x10-9 uCi/mi for dissolved or entrained noble gas shall be used.
II 1-20 Rev. 0 3/89
RDF Required Oilution factor (unitiess). This is 1.1.5 { defined as the dilution factor that ensures i the maximum permissible isotopic concentrations i expressed in 10CFRt0, Appendix B. Table 11, Column 2, are not exceeded during a discharge. tk The time duration of batch release k (hours) 1.2,1 Uf Adult fish consumption. (kg/yr) 1.2.1 Uw Adult water consumption. (liters /yr) 1,2,1 I
!! l 21 Rev. 0 3/89 l
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l 11 1-23 Rev. 0 3/89 l' . - . _ ,_.. . . _ . . _ . _ _ _ _ _ _ . _ _ , _ . _ _ _ _ _ _ _ _ , . . _ _ _ . _ _ __ _ . _ ,
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i SECTION 2.0 GASEOUS EFFLUENTS i 2.1 - .0ASEOUS EFFLUENT MONITOR SETP0lNTS The gaseous monitor setpoint values as determined using the methodology l in the following sections will be regarded as upper bounds for the i 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 i c 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 I 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, t
Ii EachP1'antVentStack.isequippedwithaWideRangeGasMonitor.(WRGM)
= and a Particulate, Iodine, 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- <
ou,tput, 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/mi is determined during the calibration of-each individual monitor, and is input into the data base
.for the monitor microprocessor.
1 L II 2-1 Rev. 0 3/89 b./,, , , m..-. , - _ , _ . , m..-.- . -- . . - , _ . - - - . . _ - . . , , ~ . _ . - _ . _ . - . _ , , _ - _ . - -
- . . , _ - . . - - _ - , , - - . - l
The WRGMs are designated as monitors XRE 5570A and XRE 5570B for Stacks A and B, respectively. Each WRGH consists of a low range (10-7 to 10 1 uCi/cc), mid range (10 4 to 102 uti/cc), and high range (10 1 to 105 uti/cc) noble gas activity di ~* tor. The 4 WRGMs also have an effluent release rate channel whic .ses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X FT 5570A 1/B 1) tc provide an indication of noble gas release rate in uti/sec. Alarm setpoints are established for the WRGH 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. The stack PIGS are designated as particulate channels XRE 556BA and XRE 556BB, iodine channels XRE 5575A and XRE 55758, 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 tc 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. Other monitors that may be used for effluent monitoring and control are the Auxiliary Building Ventilation Duct Monitor, XRE-5701, and the Containment PlG Noble Gas Monitor, 1RE 5503. XRE 5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct. XRE 5701 also provides the automatic control function for termination of Waste Gas Decay Tank releases. 1RE-5503 monitors the Containment atmosphere and provides the only automatic
, control function for termination of Containment vents or purges.
11 2-2 kevision 4 1 October 22, 1990 '
2.1.1 Dose Rates Due to Noble Cases For implementation of Radiological Ef fluent control 3/4.11.2.1.a, the dose rate to the total body and skin of an individual at the SITE BOUNDARY due to noble gases shall be calculated as follows: A. Calculate the total body dose rate due to noble gases De * (*#9) ! EQ (Eq. 2-11 (noble gases) i i Where: Dt = the total body dose rate at the SITE BOUNDARY due to noble gases (mrem /yr) (77Q) = 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 plant *.) NOTE: The annual nyerage K7Q is also used in determining setpoints for containment purge or vent as required by Technical Specification 3.3.3.1. Kt = total bcdy dose f actor due to gamma emissions from noble gas radionuclide i from Table 2.1 (mrem /yr per uti/m3) Qt = the total release rate of radionuclide i from the plant vent stacks (uti/sec) (See C below for c61culation of Qi)
- 8. Calculate the skin dose rate due to noble gases D, = (X/Q) I (Eq. 2-21 (nchie gases) (Lt + 1.1 M1 ) Qt Where: Os " the skin dose rate at the SITE 80VN,0ARY due to noble gases (mrem /yr) s
- Reference CPSES FSAR, Section 2.3.5.2.
11 2-3 Rev. 0 3/89
l
, i li = the skin dose factor due to beta (missions from i noble gas radionuclide i from Table 2.1 (mrem /yr {
per uCi/m3) 1.1 = conversion factor of mrem skin dose per mrad air ., dose. I Mi air dose factor due to gamma emissloris from , noble gas radionuclide i from Table 2.1 (mrad /yr per uCi/m3) , , All other terms are as previously defined. C. Calculation of the Qi term , Qt is defined as the total release rate (uti/sec) of radionuclide i from the plant vent stacks. Qt is given by: 9i * [, X ir vv (Eq. 2-3l Where: Xi y = the concentration of radionuclide i present ateachplantventstack(uCi/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., continuout i 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. .
Xiy = XicFe + ()/2)XiB Ill . y i( g) p [Eq. 2-41 D Where: Xi c_= The concentration of radionuclide i in _the. continuous release stream at each stack as- ! sampled in accordance with Radiological Efflue'nt l
+
Control: 3/4.11.2.1. Table 4.11 2 (uti/cm3). ! The samples are taken from each plant vent stack at the WRGM skid, ' l !! 2 4 Rev. 0 + L 3/89 L L . _ . _ - . _ . _ . ,_
Fe The continuous flow rate contribution of each plant stack (cm3/sec). These flow rates are measured directly in each plant vent stack (X FT 5570A 1/8 1). Xt g l4 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. F B
- The estimated flow rate contribution associated with the release of the batch source (cm3/sec) 1/2 = factor to account for distribution of the batch 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 Fg and X iB are zero, and Xt y = Xt e. The flow rate at each plant vent, Fy, is given by: 1 Fy Fe + (1/2) Fe (Eq.24i NOTE: If there is no batch release source, f B is zero, and Fy Fe. 2.1.2 Plant Vent Stack Noble Gas Activity Monitort XRE 5570A/B flow rance noble can 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 1 these channels will be calculated using Eqs. 2 6 and 2-7. These calculations will be performed for each plant vent stack. Xgy 500 x SF x AF = 125 XCV ltq. 2-6) D t CC = the lesser of
- X gy j,000, 00 x sr x Ar = 750 Xey ggq , y,y)
D, D, 11 2 5 Revision 4 October 22, 1990
Where: Co The alarm setpoint for each plant vent noble gas activity monitor (uCi/cm3) XGV * (noble gases) Xt y the concentration of noble gases present at each plant vent stack due to the combined sources as calculated from the radionuclide concentrations 1 determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control , 3/4.11.2.1. Table 4.11 2.(uct/cm3). j _(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 unrestricted area due to noble gases. (mrem /yr) _ SF = Safety Factor of 0.5 applied to compensate for i statistical fluctuations errors of measurement, and non-uniform distribution of release activity 1 ,- between the stacks. (unitiess)- 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. 4 i f i l 11 2 6 Rev 0 3/89 ; o
-.,rm.,~, . . - , , , , - ~ , ~ . , , . . .._.. _ ., ,_...,_. . _,.._.._.._-...___._,..._,_-. ...__ _ _ .._.._..... _,__ ._. ...,,. . . _ , , .
2,'l . 3 - Plant Vent Effluent Release Rate and Samole Flow Rate Monitors A, Plant Vent Stack Release Rate Monitors XRE 5570A/B f Effluent Release Rate Channtl). The WRGH effluent release rate channels monitor the 4 release rate of radioactive materials from each plant vent stack by combining inputs from the WRGH noble gas activity channel (UCi/cm3) indication and a stack flow rate (cm3 / sec) indication (X FT-5570A 1/B-1) to yield an effluent release rate (uti/sec). By establithing an nlarm setpoint for thi, monitor, an increue it; either the noble gas activity or stack flow rate will cause an alara
-trip. The WRGH effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases. The setpoint for each plint vent offluent release rate monitor will be calculated using Eq.
2 8. This calculation will be performed for eacn int vent stack.- f, r CG Fy [Eq. 2-8] where: Cf = The setpoint for each plant vent stack effluent release rate monitor. (uCi/sec) All other terms are previously defined. B. Samoler ' v _ ate Monitors (X-RFT-5570A-1/8-1) 4. 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' loss of sample flow alarm setpoints are established permanently in accordance with vendor specifications.
l i
!! 2-7 Revision 4 October 22, 1990
--___t - - - - - - - _ - - _ - - - - ~ - - -
U , 2 .' 1. 4 Auxiliary Buildina Ventilation Exhaust Monitor XRE-5701 Radiological Effluent Control 3/4.3.3.5, Table 3.3 8, ACTION 34, t' lows for the Auxiliary Building Ventilation Duct Monitor-(XRE-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 acti ity in the Auxiliary Building Vent Duct and providing l an automt. tic control function for termination of WGDT releases, if required, the alarm setpoint for XRE-5701 will be calculated using the following methodology. The alarm setpoint calculation is based on the following 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 the same time).
- (2) in6 source contribution due to other sources in the Auxiliary ,
Buil.3ing 's negligible relative to the source contribution due , to the reiease of the waste gas decay tank. , The concentration at the-Auxiliary Building Vent Monitor during a waste _ gas decay tank release is calculated as follows: I X iaux
= iGDT GDT * *iABV F ABV [Eq. 2-9}
FGDT + FABV From assumption (2) above, (XiGDT FGDTn XiABV FABV)i therefore, this equation can be reduced to: inux iGDT GDi [Eq. 2-10] aux Where: XiGDT the concentration of noble gas radionuclide i
.(uci/cm3) in the.WGDT as sampled in accordance with -Radiologi. cal 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) 11 2-8 Rev. 0: 3/89 J' m ,
, _ < - . . _ . . - , c ._--9
XiABV = the concentration of noble gas radionuclide i (uti/cm3) in the Auxiliary Building 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 = FGOT + FABV Xi aux = the < oncentration 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 re', ease rate for radionuclide i at each plant vent stack may be given by: Xi y Fy = Xi c fc + (1/2) XiB fB [Eq. 2-11] For this case of a batch release of a waste gas decay tank, make the following substitution into this equation (see assumption (1), above): XiB o = X aux i Faux [Eq. 2-12] Therefore.. Xjy 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 y Fy is approximately equal to 1/2 X iaux faux-11 2-9 Fev. 0 3/89
Xi v Fy = (1/2) X aux i Faux (Eq. 2 14) At the alarm setpoint concentration at each plant vent monitor, Xjy - Co. 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 Co. Therefore, CG max fy - (1/2) Caux Faux (Eq. 2-15] Solving for Caux yields: Caux - 2 CGmax fv (Eq. 2-16] Faux Where: Caux the Auxiliary Building ventilation exhaust monitor dlarm setpoint (UCi/Cm3) CG max = maximum of the monitor setpoints for the two stacks. All other variables are previously defined. 2.1.5 Containment Atmosobere Gaseous Monitor 1RE-5503 For implementation of Technical Specification 3/4.3.3.1, the alarm setpoint for the Containment Atmosphere Gaseous Monitor for Containment Ventilation Isolation will be calculated using the l. following methodology. The alarm setpoint calculation is based on the following assumptions: (1) a containment purge or vent operation is tht only batch release occurring (i.e., a waste gas decay tank purge operation is not L 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 contribution from Containment Building purge or vent operation. II 2-10 Rev. 0 3/89
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 assumption ~(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 f_ low rate contribution associated with the release of tSe containment atmosphere (cm3/sec) Therefore, Xi v.Fy = Xi c-_Fe + (1/2) Xi cont 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 Fc, then Xi v::Fy is approximately equal to 1/2 X cont- i Fcont-Xi y Fy =.(1/2) X i cont fcont [Eq. :2-19)
^.
11'2-11 Rev. 0 3/89-
At the alarm setpoint concentration at each plant vent monitor, X i y - Co. Also, the containment atmosphere gaseous monitor alarm setpoint, Ccont, corresponds to the noble gas concentration, Xi cont, 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 Cc. Therefore, CG max Fv - (1/2) Ccont Fcont [Eq. 2-20) Solving for Ccont yields: Ccont . 2C Gmax Fv [Eq. 2-21] Fcont Where: Ccont the containment atmosphere gaseous monitor alarm setpe at (uci/cm3) CG max = maximum of the monitor setpoints for the two stacks. All other variables are previously defined. 2.1.6 Dose Rates Due to Radiciodines. Tritium, and particulates _0rgan dose rates due to iodine-131 and iodine-133, tritium, and all radioactive materials in particulate form with half-lives greater than eight days will be calculated to implement the requirements of Radiological Effluent Control 3/4.ll.2.1.b as follows: Do = W Q) t PQ it (Eq. 2-22] IP&T 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) 1 II 2-12 Rev 0 3/89
. - . . _ . _ - . . - - - . - - - _ ~ . - . - . ...- - - . -
Pj = pathway dose rate parameter factor for radionuclide, i_, _ (for radioiodines, particulates, and tritium) for the _
' inhalation pathway in mrem /yr per uCi/m3* (Table 2.2)-
l IP&T = Iodine-131, iodine-133, particulates Xth 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. 2 .~1. 7. Plant Vent Stack Iodine Monitors XRE 5575A/B The setpoint for the Plant Vent Stack Iodine Monitors should be established to ensure compliance with Radiological Effluent Control 3/4.ll.2.lb. These setpoints-are not required by Radiological Effluent 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 mrem /yr to any organ for compliance. An allocation factor (AF) and safety factor (SF) are also utilized for this
' determination._ Additionally, the ratio of the dose rate due to only I-131 to the dose rate due to I-131 and I-133 is includea-as a
- factor-in the determination since-the stack iodine mor.itor utilizes-l
- a single channel analyzer set on the I-131 photopeak (i.e., only I'-
131 is detected, not all' iodines). The equation for calculating the Iodine Monitor Setpoint for each stack, CI , is: 3 l: c=1 1 7y 1500x-AFxSF[D I-131 = IV) hI-131 [Eq. 2-23) D o (D 7 j D, (D 7 )
*The latest NRC guidance has deleted the requirement to determine P i f or 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.
II 2-13 Rev. 0 3/89
. . - ._ - ~ . - _ -.= . - - - _- . . . . _ - . - - . - . _. .
I 1 I Where: C I = The setpoint for each plant vent stack lodine Monitor (uCi/cm3) t-XIV " (todines)_Xi v
= the concentration of radioiodines 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. (uCi/cm3)
_(See Section 2.1.1.c for the determination of-Xjy). 1500 = the dose rate limit to any organ due to 1-131, tritium and particulates with half-lives greater Lthan eight-days (mrem /yr)_ D1 .131 - the organ dose rate due to I-131 calculated using Eq 2-22 considering only 1-131. D1 = the organ = dose _ rate due to I-131 and 1-133 calculated using Eq. 2-22 considering only 1-131 and I-133. All other vari _ ables arc previously defined. L l.' 2.1.8 Plant Vent Stack Particulate Monitors 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:-
Cp = Kpy 1500 x AF-x SF = bV _[Eq. 2-24] D, D, l II 2-14 Rev. 1 L 8/89 L I
I Where: Cp - The setpoint for each plant vent stack ; l Particulate Monitor (uti/cm3) XPV - (particulates) X iy
- the concentration of particulates present at each plant vent stack due to the combined scurces 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 other variables are previously defined. i l l l II 2-15 Rev. 0 3/89
.. . . - _ . . --. ~. . . ~ . . - . . . - - - . - . ~ - . . . - ..
TABLE 2.1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES * , Isotope y-Body *** (K) 8-Skin ***(L) y - Ai r * * (M) B-Air **(N) Kr -8 3m 7.56E-02 --- 1.93E+01 2.66E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1,34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 .2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+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 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03-Xe-137 1.42E+03 1.22E+04- 1.51E+03 1.27E+04 Xe-138- -8.83E+03 4.13E+03 9.21E+03 4.75E+03-Ar-41 -8.84E+03 2.69E+03 9.30E+03 3.28E+03
- Values taken from Reference 2, Table B-1 l
I
** mead-m8 uCi-yr l *** meen-m 5-uC1-yr I
l l 11 2-16 Rev. 1 8/89
2.2 GASEOUS EFFLVENT DOSE CALCULATIONS 2.2.1 Dose Due to Noble Gases 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 BOVNDARY 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, The air dose over the desired time period will be calculated as follows: Dy - air dose due to gamma emissions from noble gas radionuclides (mrad) Dy = 3.17 x 10 8 (X/Q) (Eq. 2-25) I g,3g,) Mi Q'1 Where: 3.17 x 10-8 = the fraction of a year represented by one second Q'j = the cumulative release of radionuclide i during the period of interest. (uti) (Q'i = Qj (uCi/sec) x release duration (sec)) Q'j is based on the noble gas activities in each plant vent stack and WGDT or Containment Samples required by Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. All other variables are previously defined. Og - air dose due to beta emissions from noble gas radionuclides (mrad) O g = 3.17 x 10-8 (X/Q) (noble 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 uCi/m3), All other variables are previously defined. II 2-17 Rev. 0 3/89
Note: If the methodology in this section is used .in determining dose to an individual rather than air dose due to noble gases, substitute Ki for Hj, (Lj + 1.1 Mj) for Nj, and the Annual Average X/Q values from Table 2.4 for the highest annual average relative {5 concentration (X/Q) at the SITE BOUNDARY. 2.2.2 Dose Due to Radiciodines. Tritium. and Particulates 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 sumation 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). Op = PATHS 3.17 x 10-8 W' yp{R$,a,oiQ'i (sq. -271 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 indichten the maximum potential exposures. Locations of interest 5 are listed in Table 2.4, W' = X/Q for the inhalation pathway in sec/m3 X/Q f 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 L 11 2-18 Fev. 5 10.' 10
W' 0/Q for the food and ground plane pathways in m 2, 0/Q is tne annual average deposition at the location of interest. Values for 0/Q are listed in Table 2.4. If desired, the highest individual receptor 0/Q value may t.e used. NOTE: For tritium, the dispersion parameter, W' is taken as the annual average X/0 values from Table 2.4 for inhalation, food and ground plane pathways. PPi ,a o dose factor for radionuclide i, pathway p, age group a and organ o, in mrem /yr per uCi/m3 for the inhalation pathway and m2(mrem /yr) per uCi/sec for food and-ground plane pathways, except for tritium which is in mrem /yr per 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'j - cumulative release of radionuclide, i, during the period of interest (uCi). Q'j is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1, Table 4.11 2. I&PT Iodines, particulates with half 1tves greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed. PATHS = the real. pathways of exposure to individuals at the
- locations of interest as indicated in Table 2.4. 5
*The methodologies used for determining values of RPi ,a,o for each pathway are given in Appendices 8 through F.
11 2 19 Rev. 5 12/90
2.2.3 Dose Pro.iections 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 tho 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 0.3 mrem to any organ of--a HEMBER 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 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 as 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 Suocort Other Reauirements l For the purpose of implementing the requirements of Radiological Effluent Control. 6.9.1.4, the Semiannual Radioactive Effluent Release L 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-tI1e dosrs 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 .i Section 2.2.2 for doses due to iodines, tritium, and particulates.
.This same report shall also include an assessment of the radiation Rev. O Il 2-20 3/89
doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE BOUNDARY. This assessment shall be performed in accordance with the metiiodologies 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 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, 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 milk animal, and the nearest vegetable garden. Additionally, when a location is identified that yields a calculated dose 20% greater than at a location where environment 0 samples are currently being obtained, add the new location witeln 30 days to the Radiological Environmental Monitoring locations described in Section 3.1 of this manual. For the purpose-of implementing Radiological Effluent Control 3/4.11.4, L 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 I from the effluent releases exceed twice the limits of Controls 3/4.11.1.2, 3/4.11~2.2, or 3/4.11.2.3. -This assessment will be included in the Semi-annual Radioactive Effluent Release Report to be submitted 60 days after January 1 of the year after the assessment was required._ Otherwise, no assessments are required. Rev. 0 II_2-21 3/89
i 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 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 should be substituted for the gamma air dose factor (Mj) to determine the total body dose, Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of food. Data obtained from the latest land use census should be used to determine locations for evaluating doses. The results of the Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations. 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 sut.mitted if th j determination is required. Rev. O 11 2-22 3/89
I i TABLE 2.2 PATHWAY DOSE RATE PARAMETER (Pi)*
- BASED ON THE INHA1ATION PATHWAY FOR THE CHI 1D AGE GROUP l ORGAN DOSE FACTORS N'0CLIDE l- . . . .. - . ... .... .. . . -..
l BONE LIVER T. SODY THYROID KIDNEY LUNG GI.LLI t H.3 0.00E+00 1,12E+03 1.12E+03 1.12E+03 1,12E+03 1.12E+03 l'.12E+03 . P 32 2.60E+06 1.14E+05- 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.1.E+05 2.87E+03 FE 59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 Co.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 Co.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI.63 -8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03
-ZN.65' :4.26E+04 1.13E+05 7,03E+04 'O 00E+00 7.14E+04- 9,95E+05 1.63E+04 RB.86 0.00E+00.-1.98E+05 1.14E+05 -0.00E+00 0.00E+00 0.00E+00 7.99E+03 E .SR.89 5,99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08' O.00E+00 6,44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y.91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00- 2.63E+06 1.84E+05 ZR.95 1.90E+05: 4.18E+04 3.70E+04 0'.00E+00 5.96E+04 2.23E+06- 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55Ev03 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 RU.106 1.36E+05 0.00E+00. 1.69E+04 0.00E+00- -1.84E+05 1.43E+07- 4-29E+05 .
AG.110M 1.69E+04 1.14E+04 9.14E+03 'O.00E+00 2.12E+04 5.48E+06-~1.00E+05 TE.125M 6.73E&O3 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 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 .- 30 E+05 1.21E+05 ' 3. 8 5 E+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&O3 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 5.56E+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+0C 1.00E+03 4.33E+05 9.73E+04 ND 147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 . 81E+03 3.28E+05 8.21E+04
.................................................. .........Rev - * -
II 2-23 3/89
q
'l i
TABLE 2.3 PATHWAY DOSE FACTORS AGE CROUP: ALL PATHWAY: CROUND PLANE l ORGAN DOSE FACTORS NUCLIDE l.............. ..... l T. BODY SKIN H.3 0.00E+00 0.00E+00 P.32 0.00E+00 0.00E+00 CR.51 4.65E+06 5.50E+06 MN 54 1.39E+09 1,62E+09 FE.55 0.00E+00 -0.00E+00 E
~FE.59 2.73E+08 3.21E+08
- CO 58 3.79E+08 4.44E+08 I
CO.60 2.15E+10 2.53E+10
.NI 63 0.00E+00 0.00E+00 ZN 65 7.47E+08 8.59E+08 i RB.86 8.97E+06 1,03E+07 SR.89 2.16E+04 2.51E+04 SR.90 0.00E+C0 0.00E+00 l
.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 -4 RU.106L- 4.22E+08 .5.06E+08 j;~ AG 110M 3,44E+09 14.01E+09 TE.125M 1.55E+06 2.13E+06
.TE.127M 9.17E+04 1,08E+05 L
TE.129M 1.98E+07- 2.31E+07 I .I.131 :1.72E+07 2.09E+07 I.133 2.45E+06 2.98E+06 o CS.134 6.86E+09 8.00E+09
. CS 136- 1.51E+08 1.71E+08 b CS.137 1.03E+10 ~1.20E+10 BA.140 2.06E+07- 2.36E+07 CE.141 1,37E+07 1.54E+07 .
CE.144 6.96E+07 8.05E+07 PR 143 0.00E+00 0.00E+00 ND.147 8.39E+06 1.01E+07 Rev. O II 2 24- 3/89
TABLE 2.3 PATHVAY DOSE FACTORS , AGE GROUP: ADULT PATHWAY: GRASS. COW. MILK
..................................................... ........................ j j ORGAN DOSE FACTORS l yycL1pE l........................................................ ............ l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 7,62E+02 7.62E+02 7.62E+02 7.62E+02 7,62E+02 7.62E+02 - 1 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 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3,78E+04 7.17E+06 MN 54 0,00E+00 8.40E+06 1,60E+06 0,00E+00 2,50E+06 0.00E+00 2,57E+07 FE.55 2.51E+07 1.73E+07' 4.04E+06 0,00E+00 0.00E+00 9,66E+06 9.93E+06 FE.59 2.97E+07 6.97E+07 2,67E+07 0.00E+00 0,00E+00 1.95E+07 2,32E+08 CO.58 0,00E+00 4.71E+06 1.05E+07 0.00E+00 0.00E+00 0.00E+00- 9,54E+07 1Q0 60 0.00E+00 1,64E+07 3.61E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 NI 63 6,72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 ZN.65 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 1,45E+09 0.00E+00 4.16E+07 0.00E+00 0,00E+00 0.00E+00 2.32E+08 SR 90 4,67E+10 0.00E+00 1.15E+10 0,00E+00 0.00E+00 0.00E+00 1.35E.09 Y.91 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 ZR.95 9 41E+02 3.02S+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 NB 95 8.24E+04 4.58E+04 2.46E+04 0,00E+00 4.53E+04 0,00E+00 2.78E+08 RU.103 '1.02E+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 AG.110M 5.81E+07 5.38E+07 -3.19E+07- 0,00E+00 1.06E+08 0.00E+00 -2,19E+10 TE.125M 1.63E+07 5.89E+06 2.18E+06 -4.89E+06 6.61E+07 0,00E+00 6.49E+07 TE.127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0,00E+00 -l.53E+08 TE.129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0,00E+00 3.02E+08 I.131 .2.96E+08- 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 '1.12E+08 I.133. ~3.87E+06- 6.73E+06 2,05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06
-CS.134 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CSa136 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, 9.5 E+08 BA.140 2,69E+07 3.38E+04 1.76E+06 0.00E+00 1,15E+04. 1.94E+04 5.54L'07 CE.141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+C7 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+0; ND.147 -9.40E+01 1.09E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5.22E+J5 l
Rev. O II 2-25 3/89 ,
._ _- . - _ _ . _ - . . . _ _ _ - _ . _ __m _ _ _ . . _ _ _ - - _ _ .
a l TABLE 2.3 PATHWAY DOSE FACTORS l ACE CROUP: TEEN PATHWAY: CRASS. COW. MILK l ORGAN DOSE FACTORS XUCLIDE l*...... ..... - ... .. .. .. .. . ...... ..........................
-l BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI H.3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 P 32 3.15E+10 1.95E&O9 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR.51 0.00E+00. 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 KN.54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 FE.55 4.46E+07 3.16E+07- 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E+07 FE.59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 CO.58 0.00E+00 7,94E+06 1.83E+07 0.00E+00 0,00E+00 0.00E+00 1.10E+0B CO.60 -0.00E+00- 2.78E+07 6,27E+07 0.00E+00 -0.00E+00 0.00E+00 3.62E+08 NI.63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN.65 2.11E+09- 7,32E+09 3.42E+09 0.00E+00- 4.69E+09 0.00E+00 3.10E+09 RB 86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 10.00E+00 0.00E+00 7.00E+08 SR 89- '2.68E+09 0.00E+00 7.67E+07 0.00E&OO- 0.00E+00 0.00E+00 3.19E+08 SR.90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0,00E+00 0.00E+00 1.86E+09 Y.91- 1.58E+04 0.00E+00 4.24E+02 0.00E+00- 0.00E+00 0.00E+00 6.48E+06 ZR.95: -1.65E+03 5.21E+02 3.58E+02 0.00E+00 '7.65E+02 0.00E+00 1.20E+06 NB.95- 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 RU.103 L1.81E+03 0.00E+00 _7.75E+02 0.00E+00_ 6.39E+03 0.00E+00 1.51E+05
-RU.106- -
3.76E+04 0.00E+00 4.73E+03--0.00E+00- 7.24E+04 0,00E+00 1.80E+06-AC.110M 9.64E+07. 9.12E+07 ~5.55E+07 0.00E+00 11.74E+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 L1.00E+07 2.01E+07 :3.42E+08 0.00E+00 2;11E+08
-tee 129M :1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 I.131 5.38E+08 7.53E+08 :4.05E+08 2.20E+11 - 1.30E+09 0.00E+00 1.49E+08' 14133 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
-CSa136 + 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 bbkkb h(h9h bh 2$7hk bh h hkk bb b[bbk bb k hbh bh b bbk bb k hhh b8 PR-143 2.90E+02 1.16E+02- 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05
'ND.147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 Rev. O II 2-26' 3/89
TABLE 2,3 PATHWAY DOSE FACTORS A0E CROUP: . CHILD PATHWAY: CRASS. COW.MILX l ORGAN DOSE FACTORS NUCLIDE l........*........................ ....... ........................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 1,57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P.32 7.77E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 CR.51 -0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5,40E+06 MN.54= 0.00E+00 2,10E+07 5,59E+06 0.00E+00 5.89E+06 0,00E+00 1,76E+07 FE.55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 FE.59 1.20E+08 1.95E+0J 9,70E+07 0,00E+00 0.00E+00 5.65E+07 2.03E+08 C0 58 0,00E+00 1,21E407 3,72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 CO.60 0,00E+00 4.32E+07 1.27E+08 0,00E+00 0,00E+00 0.00E+00 2.39E+08 NI.63 2.97E+10 1.59E+09- 1.01E+09 0.00E+00 0,00E+00 0.00E+00 1.07E+08 " ZN.65 - 4,14E+09 1.10E+10 6.86E+09 0,00E+00 6,95E+09 0.00E+00 1,94E+09 RB 86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65E+08-SR.69 6,63E+09 0.00E+00 1,89E+08 0,00E+00 0,00E+00 0.00E+00 2.57E+08 SR.90- 1.12E+11 0.00E+00 2.84E+10 0,00E+00 0.00E+00 0.00E+00 1,51E+09 Y.91 3,91E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0,00E+00 5.21E+06 ZR.95- 3,84E&O3- 8.43E+02 7.51E+02 0,00E+00 1.21E+03 0.00E+00' 8.80E+05
-NB.95; 3.18E+05- 1.24E+05- 8.86E+04 0,00E+00 -1,16E+05 0.00E+00 2.29E+0B
-RU 103~ -4,29E+03 0.00E+00 1,65E+03 '0,00E+00 1.08E+04 0,00E+00 l'.11E+05 RU.106 -9.25E+04 0.00E+00 1.15E+04 0.00E+00 1,25E+05 0.00E+00 1,44E+06 AG 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 7.13Et07 TE.127M 2.08E+08 -5,61E+07 2.47E+07 4.98E+07.- 5,94E+08 0.00E+00 1.69E+08 -
TE.129M 2.72E+08 7.59E+07 4,22E+07 8,76E+07 7,98E+08 0.00E+00 3.31E+08 I.131: -1,31E+09 1 31E+09 7,46E+08 4.34E+11 2.16E+09 0,00E+00 1,17E+08 I.133 1.72E+07 2,13E+07 8 05E+06 '3.95E+09 3.55E+07 0.00E+00 8.58E+06:
- CS.134- 2.-27E+10 3,72E+10 7,85E+09. 0.00E+00 1.15E+10 4.14E+09- 2,01E+08 CS.136 v 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 1 BA.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 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0,00E+00 1.36E+07 bbkkk k hbh bk h b9b bh h 67b hk b$bbb bb h hhb bb b bbh bb k bbk b8 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 II 2-27 3/89
i TABLE 2.3 PATHVAY DOSE FACTORS ACE CROUP: INFANT PATWAY: CRASS. COW MILK
'l ORGAN DOSE FACTORS VUCLIDE l < ~ - < * * - - - . - . - . . '-
l BONE LIVER T. BODY THYROID KIDNEY LUNG OI.LLI b$h b bbkhbb h$b8h bh h h8k bb h bhb bh h$bhb bb h$bhk bb h$h8b bb P 32 1.60E+11 9.42E+09 6.21E+09 0.00E+00 0.00E+00 0.00E+00 2.17E+09 CR.51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN 54- 0.00E+00 _3.91E+07 8.85E+06 0.00E+00 8.65E+06 0.00E+00 1.43E+07 FE.55 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE.59- 2.25E+08 3.93E+08 1.55E+08 0.00E+00 0.00E+00 1.16E+08 1.88E+08 1C0 58 0.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00- 6.05E+07 CO.60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 hk$hh b[hbh 5b h5[6k b9 k)hkkb9 b$bbb bb b bbb bb b)bbb bb k bhk+bh ZN.65- 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 RB.86: 0.00E+00 2.23E+10 1,10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR.89. 1.26E+10 0,00E+00 3.62E+08 -0.00E+00 0.00E+00 0.00E+00 2.59E+08-SR.90 1,22E+11 0.00E+00 3.10E+10 0.00E+00. 0.00E+00 0.00E+00- 1,52E+09 1
'Y.91 7 .' 34 E+04 0.00E+00- 1.95Et03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 y
-ZR.95- 6.81E+03 '1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 NB 95-_ 5,94E+05 2.45E+05: 1.41E+05 '0.00E+00 '1.75E+05 0.00E+00 2.07E+08
.RU.103i 18,68E+03 0.00E+00 2.90E+03- O.00E+00 1.81E+04 0.00 1.06E+05
?...........'....................................................E+00 ............... I RU 106' cl.91E+05 0.00E+00 2.38E+04 -0.00E+00 2.25E+05 0.00E+00 -1.45E+06 AG.110M .3.86E+08 2.82E+08 1.87E+08 0.00E+00 4.03E+08- 0.00E+00- 1.46E+10
'TE.125M 1.51E+08 -5.05E+07 2.04E+07 5.08E+07 0.00E+00 -0.00E+00 7.19E+07 gTE 127M -4:22E+08 1.40E+08 '5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE 129M 5.58E+08 1.91E+08 L8.59E+07 2.14E+08 11.39E+09 0.00E+00 3.33E+0B i 1 131 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 6.22Et07 0.00E+00' 8.96E+06 CS.134' 3.65E+10 6.81E+10 .6,88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS.136- 1.98E+09 : 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08- 8.85E+07 l' 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. 4 9 E+05. 5.94E+07 CE.141- - 4. 34E+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 0.00E+00-.1.37Lc07 CEa144 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. O II 2-28 3/89
a J I.:a - 4_.J L_e_rs _r&a- ~ 4 n .a. ----.A J.-+._ aa TABLE 2. 3 PATHVAY DOSE FACTORS ACE GROUP: ADULT PATHVAY: CRASS.COV. HEAT l ORGAN DOSE FACTORS NUCLIDE l ... .. . . . . - . * *- . .. . . . - ........ l BONE LIVER T. BODY THYROID KIDNEY LUNG 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 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN.54 0,00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 FE.55 2.93E+08 2.03E+08 4.73E+07 0.00E+00 0,00E+00 1.13E+08 1.16E+08 FE.59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 Co.58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0,00E+00 3.70E+08 CO.60 0.00E+00 7.52E+07 1,66E+08 0.00E+00 0.00E+00 'O.00E+00 1.41E+09 NI.63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 IN.65 3.56E+08 1.13E+09 5.12E+08 0,00E+00 7.57E+08 0.00E+00 7,13E+0B RB.86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0,00E+00 0.00E+00 9.59E+07-hR89 h$b2k$bh'b$bbkhbb'hIkkk+b6 b$bbkIbbb$bbkbbb$bbkbbE$h5kbh' SR.90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 Y.91 1.13E+06- 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 ZR.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05- 0.00E+00 1.90E+09. NB.95 - 2.30E+06 -1.28E+06 '6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 RU 103- 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00- 1.23E+10-
~
RU 106 2.80E+09-- 0.00E+00 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG.110M 6.68E+06 "6.18E+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 TE.129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 I.131 1.08E+07 1.54E+07 8.82E+06- 5.04E+09 2.64E+07 .0.00E+00 4-06E+06 .
I 133 3.68E.01 6.41E.01 -1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 CS.134 6.58E+08 1.57E+09 1.28E+09 'O.0^F+00 5.07E+08 1.68E+08 .2.74E+07 CS.134 1.21E+07 4.78E+07 3.44E+07 0. C' 'O 2.66E+07 3,65E+06 5.43E+06 CS.137 8.72E+08 1.19E+09 7.82E+08- 0.00E+00 4.05E+08' 1.35E+08 2.31E+07 -BA.140- - 2.90E+07 3.64E+04 1.90E+06. 0.00E+00 1.24E+04 2.08E+04 5.96E+07 -CE.141 1.41E+04 9.51E+03 1.08E+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. 0-11 2-29 3/89
l l TABLE 2.3 PATHVAY DOSE FACTORS ACE GROUP: TEEN PATHVAY: GRASS.COV. MEAT I ORGAN DOSE FACTORS XUCLIDE l............. ... ................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI:LLI H.3 0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1,93E+02 P.32 3.91E+09 2.42E+08 1.52E+08 0.00E+00 0.00E+00 0.00E+00 3.29E+08 CR.51 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 KN.54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 FE.55 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08 7.31E+07 FE.59 2.12E+08 4.95E+0B 1.91E+0B 0.00E+00 0.00E+00 1.56E+08 1.17E+09 Co.58 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+0B CO.60 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+0B 0.00E+00 0.00E+00 0.00E+00 1.71E+0S ZN.65 2.50E+08 8.68E+08 4.0$E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 RB.86 0.00E+00 4.065+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.00E+07 SR 89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 SR.90 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 Y 91 9.54E+05 0.00E+00 2.56E+04 0.00L+00 0.00E+00 0.00E+00 3.91E+08 IR.95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 NB 95 1.79E+06 9.95E+05 5,48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 RU.103 8.56E+07 0.00E+00 3.66E+07 0.0;E+00 3.02E+08 0.00E+00 7.15E+09 RU.105 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.54E+09 0.00E+00 1.13E+11 AG.110M 5.06E+06 4.78E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 TE.125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.00E+00 0.00E+00 8.94E+08 TE.127M 9.41E+08 3.34E+08 1.12E+08 2.24L+08' 3.81E+09 0.00E+C0 2.35E+09 TE.129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 1 131 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 I.133 3.08E 01 5.22E-01 1,59E.01 7.29E+01 9.16E 01 0.00E+00 3.95E.01 CS.134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS.136 9.43E+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 1.18E+04 7.87E+03 9.05E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 CE.144 1.23E+06 5.08E+05 6.60E&O4 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 5.79E+07 RD.147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 Rev. 0 l l 11 2-30 3/89
TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS.COV. MEAT l ORGAN DOSE FACTORS GUCL1DE l......... ..... . ..... ... ............... ...................... I BONE LIVER T. BODY THYROID KIDNEY LUNO GI-LLI H.3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 P.32 7.38E+09 3.45E+08 2.85E+08 0.00E+00 0.00E+00 0.00E+00 2.04E+08 CR.51 0.00E+00 0.00E+00 B.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 FE.55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 FE.59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 CO 58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.5BE+07 CO.60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI 63 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08 ZN.65 3.76E+08 1.00E+09 6.22E+08 0.00E+00 6.31E+08 0,00E+00 1.76E+08 RB.86 0.00E+00 5.76E+08 3.54E+0B 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 2R.90 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+0B 0.00E+00 4.01E+09 RU.iO6 4.44E+09 0.00E+00 5.54E+08 0.00E+00 6,00E+09 0.00E+00 6.91E+10 AG-110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+0B TE 125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 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.lBE+09 I.131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06 I.133 5.72E.01 7.08E.01 2.68E.01 1.31E+02 1.18E+00 0.00E+00 2.85E P1 CS.134 9.23E+08 1.51E+09 3.19E+08 0.00E+00* 4.69E+08 1.68E+08 8.16E+06 CS.136 1.63E+07 4.48E+07 2.90E+C7 0.00E+00 2.39E+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 BA.140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 CE.141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE.144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+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. O 11 2-31 3/89
.. ~ . .- .- - - -- . . .. _- . -
i I TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHVAY: GkASS . COW. MEAT I ORGAN DOSE FACTORS KUCLIDE l.................. .................................................. l BONE LIVER T. BODY . THYROID KIDNEY LUNG CI.LLI H-3 0.00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0.00E+00 0.00E+00 P 32 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR 51 0.00E+00 0,00E+00 0.00E+00' 0,00E+00 0.00E+00 0,00E+00 'O 00E+00 KN 54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00- 0.00E+00 0.00E+00 FE.55 0.00E+00 0,00E+00 0.00E+00 0,00E+00 0.00E+00 0,00E+00. 0.00E+00 FE.59 0.00E+00. 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CC 58 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+C0 0.00E+00 0,00E+00
- C( . 50 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+03 0,00E+00 0.00E+00-U".63- 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E?C3 0.00E+00 0.00E+00 71 65 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 0.00F+00 9.00E+00 0.00E+00 kB.86'...O
...... 00E+00 SR.89 0,00E+00 0.00E+00 0,00E+00 0.00E+00 0,00E+00 0;00E+00 0.00E+00 SR.90 0.00E+00 0.00E+00 0,00E+00 0,00E+00- 0,00E+00 0.00E+00 0.00E+00 Y.91' 0,00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 ZR.95 =0.00E+00 0.00E+00 0,00E+00. 0,00E+00 0,00E+00 0,00E+00 0.00E+00
'NB 95 .0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 RU.103 --0.00E+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 0.00L'+00.'O.00E+00 0.00E+00
.AG 110M 0.00E+00 10.00E+00 0.00E+00 0,00E+00 0.00E+00- 0.00E+00 0,00E+00
~
LTE.125M -0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00: 0.00E+00 0.00E+00 TE.127M LO.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 0.00Et00
-I 131- 0,00E+00 0,00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00
133 0.00E+00 -0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00.0.00E+00 '
ca.134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 -0.00E+00 CS.136i 0.00E+00 0.00E+00 .0.00E+00f 0.00E+00- 0'00E+00. . 0.00E+00 0,00E+00 CS.137 10,00E+00- 0.00E+00 'O.00E+00 0.00E+00 0.00E+00: 0.00E+00' 0.00E+00 , BA 140l 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'O.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 l' ..............................................................................
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+06 0.00E+00 ND 147: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L . Rev. O i- - 11 2 32 3/89
t TABLE 2.3 PATHVAY DOSE FACTORS ACE GROUP: ADULT PATHVAY: GRASS. COAT-MILK l ORGAN DOSE FACTORS NUCLIDE l....- . .- . .. ..... .- .... ..... [ EONE LIVER T, BODY THYROID KIDNEY LUNC GI.LLI - H.3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 .1.56E+03 1.56E+03 P.32 2,05E+10 1.27E+09 7.92E+08 0.00E+00 0.00E+00 0.00E+00 2.30E+09
.............................................................................. l CR 51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 '
KN 54 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 FE.55 -3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 FE 59 3.87E+05 9,09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 CO 58- 0,00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 '.15E+07 CO.60 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E+00 0.00E+00- , '0E+07 NI.63 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 .1.17E+07 ZN.65 1.65E+08 5.24E+08 2.37E+08 0,00E+00 3.51E+08 0.00E+00 3.30E+08 RB.86 0.00E+00 3.12E+08 1.45E+08 0.00E+00 0.00E+00 0,00E+00 6.14E+07 SR 89 3.05E+09 0.00E+00 8.76E+07 0.00E+00 0.00E+00 0,00E+00 :4.89E+08 SR.90 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 -0.00E+00 2,84E+09 Y.91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+03 - 5.68E+05
'ZR 95 1.13E+02 3.63E+01' 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 NB 95 9,92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.'35E+07 RU-103 1.22E+02 - 0.00E+00' 5.27E+01 0.00E+00 4.67E+02 'O.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 3484E+06 0.00E+00 1.27E+07 0.00E+00- 2.64E+09
'TE-125M 1.96E+06 7.090+05 2.62E+05 5.89E+03. 7.96E+06 0.00E+00 7.81E+06
'TE.127M 5.50E+06 1.97E+06 6,70E+05 -1.41E+06- 2.23f+07 0.00E+00 1.84E+07 <
TE 129M' 7.23E+06 2.70E+06 1.14E+06 -2.481+06 - 3.0?E+07 0.00E+00 3.64E+07-l3 I 131 3.56E+L8 5.09E+08_ 1,92F+08 1.67E+11- 8,73'+08 0.00E+00 1.34E+08 l ..._..............-............................................................
- I.133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 '1.41E+07' O.00E+00 7.2SE+06 CS 134 1.70E+10 4.04E+10 3.!t0E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08
'CS.136 7.92E+08 3.11E+09 2.23F+09 0.00E+00 1.74E+00 2.38E+08 3.55E+08
.......................-............ ..............................~...........
CS.137 2.22E+10- 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 . BA 140 3.24E+06 14.07E+03- 2.12E+05 0. 00~E+00 1.38E+03 2.33E+03 6.67E+06 L. - CE-141 5.82E+02 3.94E+02 4.47E+01. 0.00E+00 1.83E+02 0,00E+00 1.51E+06 l ..........................s................................................... CE.144 4.30E+04 1.80Et04 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 8.30E+04 ND.147 1.13E+01 1.31E+01 7.82E-01 0.0JE+00 7.65E+00 0.00E+00 6.28E+04 Rev. O j II 2-3. 3/89 u _
l TABLE 2.3 PATHVAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: CRASS GOAT. MILK l ORGAN DOSE FACTORS NUCL1DE l. ...... .. ........................................................ I BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI H.3 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+00 3.18E+09 CR.51 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN.54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 FE.55 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00E+00 2.61E+05 1.78E+05 FE.59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 CO.58 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 CO.60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07 N1 63 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ZN 65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+0B 0.00F.+00 3.72E+08 RB.86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0,00E+00 8.40E,0/ SR.89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 SR.90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 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 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 NB.95 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 RU.103 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82E+04 RU.106 4.50E+03 0.00E+00 5.6BE+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 AG.110M 1.16E+07 1.09E+07 6,65E+06 0.00E+00 2 'ME+07 0.00E+00 3.0?E+09 TE.125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 ' .00E+00 0.00E+00 1.06E+07 , TE.127M 1.01E+07 3.59E+06 1.20E+06 2,41E+06 4.11E+07 0.00E+00 2.520+07 TE.129H 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 I-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+08 1 133 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS.134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS-136, l.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08 CS.137 4.12E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 BA.140 5.8;E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 CE-141 1.0)S+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06 CE.144 7.90E+04 3.27E+04 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 11 2 34 3/89
i c. 2. 2 . 3 FATHt a# $E FACTORS ACE CROUP: CH. PATHWAY: URASS. COAT. MILK 1 ORGAN DOSE FACTORS UUCL1 del......................**............................................ I BONE LIVER T. BODY THYROID KIDNEY LUNG C1.LLI H.3 0.60E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 P.32 9.32E+10 4.36E+09 3.59E+09 0.00E+00 0.00E+00 0.00E+00 2.5BE+09 CR.51 0.00E+00 0.00E+0 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.4BE40$ MN.54 0.00E+00 2.52E+0 6.71E+05 0.00E+00 7.06t+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 1. 5 6 F.+06 2.53E+06 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.64E406 Co.58 0.00E+00 1.46E+06 4.46E+06 0.00E&OO 0,00E+00 0.00E+00 8.49E+06 Co.60 0.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 N1 63 3.5;E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 ZN 65 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08 RB.86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 SR.89 1.39E+10 0.00E+00 3 97E+08 0.00E+09 0.00E+00 0.00E+00 5.39E+08 SR.90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Y.91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.24E+05 ZR 95 4.60E+02 1.01E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1.0$E+05 NB.95 3.82E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU.103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 RU.106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG.110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE.125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.00E+00 0.00E+00 8.55E+06 TE.127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE.129H 3.26E+07 9.10E+06 5.06E+06 1.05E+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 1 133 2.06E+07 2.55E+07 9.66E+06 4.74E409 4.25E+07 0.00E+00 1.03E407 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
......t.1 .....................................................................
CS.137 9.66E+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+A0 1. 59 E+07 PR.143 ? 61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9.29E-04 ND.147 s.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Rev. 0 ' 11 2 35 3/89
i s. l l 1 - TABLE 2.3 PATHVAY DOSE TACTORS ! ]. i AGE GROUP: INTANT PATHVAY: CRASS. COAT. MILK L l ............................................................................... l ORGAN DOSE TACTORS HUCL1DE l...........~...... . .... . . *...... .................... l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI ' H.3 b.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 I CR.51 0.00E400 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN.54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06
- TE.55 1,76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 FE.59 2.92E+06 5.10E+06 2.01E+06 0.00E+00__0.00E400 1.51E+06 2.44E+06 CO 58 -0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 ?
, CO.60 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 2.52E+07 NI 63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN#65 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09 l RB.86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 SR.89. 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 4 SR 90 2.55E+11 0.00E+00 6 50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y.91 8.80E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31E+05 ZR.95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 4 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 3,48E+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 AG.110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 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 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE.129M 6.69E+07~ 2.29E+07 1.03E+07- 2.57E+07 1.67E+08 0.00E+00 3.99E+07 1 131- 3.27E+09 3.85E+09 .1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 1 133 4.36E+07 6.35E+07, 1.86E+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 134 5.94E+09 1.75E+10 ( S2E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+08 CSe137 1.54E+11 .1.81E+11 1.28E+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 6.89E+03 1.78E+04 7.13E+06 CE.141 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1,64E+06 CE.144 2.79E+05 1.14E+05 1,56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07
.PR 143 1.78E+0? 6.66E+01 8.83E+00 0.00E+00 2.48E+01~ 0.00E+00 9.40E+04 ND.141 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6.89E+04 Rev. 0 11 2 36 3/89
_ ._ _._m._______.-_____ __ ,_
1 TABLE 2.3 PATKVAY DOSE TACTORS ACE GROUP: ADULT PATHVAY: VECETATION I ORGAN DOSE FACTORS t VUCL1DE l. ......*. . *. *.**...... **...... . ............ ............... I BONE LIVER T. BODY THYROID KIDNEY LUNC Gl.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 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN.54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0 00E+00 9,58E+08 TE.55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 TE.59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 Co.58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 : Co.60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 " N!.63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 ZN.65 3.17E+08 1.01E+09 4.56E+08 0.00E*00 6.75E+08 0.00E+00 6.36E+08 RB.86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 SR 89 9.98E+09 0.00E+00- 2.86E+08 0.00E+00 0,00E+00 0.00E+00 1.00E+09 SR.90 6.0$E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Y.91 5.12E+06 0.00E+00- 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 ZR 95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+0$ 0.00E+00 1.19E+09 NB.95 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 ' RU.103 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 5.57E+08 RU.106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08- 0.00E+00 1.25E+10 AG 110M 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE.125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86t+08 TE.127H 3,49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 TE.129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 1 131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 I.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.134 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 1.92E+07 CS.137- 6.36E+09 8,70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BA.140 1.29E+08 1.62E+0S 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08 CE.141 1.97E+05 1. 33 E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08 CE.144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 -1.11E+10 PR 143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1,45E+04 0.00E+00 2.74E+08 ND.147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Rev. O 11 2 37 3/89
TABLE 2.3 PATL'AY DOSE FACTORS ACE GROUP: TEEN PATFa'AY : VEGETATION j ORGAN DOSE TACTORS VUCL1DE f........* . ......*......... ... .. *.*.............................. I BONE L1VER T. BODY THYROID KIDNEY LUNG GI.LLI H3 0.00E+00 2,59E+03 2.59E+03 2.59E+03 2.590+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+0B CR.51 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 KN.54 0.00E+00 t. 54E+0s 9.01E+07 0.00E+00 1.16E+0B 0.00E+00 9.32E+08 FE.55 3.26E+08 i 31r+08 5.39E+07 0.00E+00 0.00E600 1.47E+0B 1.00E+08 TE.59 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+0B C0 58 0.00E+00 4.36E+07 1.01E+0B 0.00E+00 0.00b+00 0 00E+00 6.01E+08 CO.60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00t+00 3.24E+09 N1 63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0,00E+00 0.00E+00 1.BiL+0C EN.65 *.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+0B RB.86 0.00E+00 2.73E+08 1.28E+0B 0.00E+00 0.00E+00 0.00E+00 4.04E+07 SR.89 1.52E+10 0.00E+00 4.34E+0B 0.00E+00 0.00E+00 0.00E+00 1.80E+09 SR.90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Y.91 7.84F+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 IR.95 1.7/E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB.95 1. '/2 E+0 5 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 RU.106 i,09E+08 0.00E+00 1.90E+07 0.00E+00 5.97E+08 0.00E+00 1.4BE+10 AG.110H 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E400 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.127F 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+0B 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 4.59E+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+0B BA.140 1.39E+08 1.71t+05 8,97E+06 0.00E+00 5.7BE+04 1.15E+05 2.15E+0B CE.141 2.83E+05 1. 8 91'.+0 5 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+0B Rev. O 11 2 38 3/89
TABLI 2. 3 PATHWAY DOSE FACTORS AGE CROUP: CHILD PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE l..................................................................... l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 P 32 3.35E+09 1.57E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 9.25L ? CR.51 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 KN.54 0.00L+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 TE.55 8.01E+08 4.25E+0B 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE 59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+0B Co.58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 CO.60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI.63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 IN.65 8.12E+03 2.16E+09 1.35E+09 0.00E+00 1.36E409 0.00E+00 3.80E+08 RB.86 0.00E+00 4.51E+06 2.77E+08 0.00E+00 0.00Ltan 0.00E+00 2.90E+07 SR.89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR.90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y.91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ZR 95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+0C NB.95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 RU 103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU.106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1,16E+10 AG 110M 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 TE 125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 TE.127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE.129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2,47E+09 0.00E+00 1.02E+09 I.131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 I.133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS.134 1.60E+10 2.63 +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+0.5 1.63E+07 0,00E+00 7.96E+04 1.46E+05 1.41E+08 CE.141 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08
- CE.144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 PR.143 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND.147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 Rev. 0 11 2 39 3/89
TABLE 2.3 PATHVAY DOSE TACTORS ACE CROUP: INFANT PATHWAY: VECETATION l ORCAN DOSE TACTORS UUCL1DE l... ..>.. * * *. . . . . . .. . . ... ....... .... l BONE LIVER T. BODY TRYROID KIDNEY LUNG C1.LLI H.3 0.00E+00 0.00E+00 0.00E+00 v.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 0.00E400 0.00E+00 0.00E+00 CR 51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KN 54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 YE.55 0.00E+00 0.00E+00 f/.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 0.00E400 0.00E+00 0.00E+00 Co.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E400 0.00E400 N1 63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN 65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB.86 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00!+00 SR.89 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR.90 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y.91 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E 00 0.00E+00 0.00E+00 ZR.95 0.00E+00 0.00E+00 0.00t+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+00 0.00E+00 A0 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 0.00E400 0.00E+00 0.00E+00 TE.127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129M 0.00E+00 0.00E+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 0.00E400 0.00E+00 0.00E+00 0.00E+00 1 133 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 0.065+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.136 0,00E+00 0,00E+00 0,00E,30 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+0C 0.00E+00 0.00E+00 0,00E+00 0.00F+00 CE.141 0.00E+00 0.00E+00 0.00E+0C * .00E+00 0.00E+00 0,00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 PR.143 0.00E+00 0.00E+00 0.00E+00 0.00E&D0 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 l 11 2 40 3/89
TABLE 2.3 PATWAY DOSE FACTORS ACE CROUP: ADULT PATWAY: INHA1ATION
. 4.......
l ORGAN DOSE FACTORS gy LipE l..................................................................... l BONE LIVER T. BODY TRYROID KIDNEY LUNG GI.LLI M.3 0.00E+00 1.26E+0) 1.26E+03 1.26E+03 1.26E+03- 1.26E+03 1.26E+03 P.32 1.32E+06 7.71E+04 5.01E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+04 CR.51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3;32E+03 KN.54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE.55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE.59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 Co.58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 CO.60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85F.+05 NI 63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 EN 65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 R3 86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 SR.89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 SR.90 . 9.92E+07 0.00E+00 -6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05
'Y.91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+0$
ZR.95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 NB.95 - 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU.103 1.53E+03 '0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU.106- 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG.110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE.125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE.127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE.129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05. I.131 2.52E+04 3.58E+04 2.0$E+04 1.19E+07 6.13E+04 0.00E+00 .6.28E+03 1 133 8.64E+03 1.48E+06 4 52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03
^
CS.134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS 136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS.137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA.140 3.90E+04 4.90E+01 2.57E+03 0,00E+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+03 CE.144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 PR 14.1 9.36E+03 3.75E+03 4,64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND.14? 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 Rev. 0 11 2 41 3/89
TABLE 2.3 PATHWAY DOSE FACTORS AGE CROUP: TEEN PATHWAY: IRRALATION l ORGAN DOSE FACTORS l VUCLIDE l. *. **- . * ... - * **.* * .. * .. . . ..... l BONE LIVER T. BODY TRYROID KIDNEY LUNG CI.LLI H3 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 9.28E+04 CR 51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 i KN.54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 i 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 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 C0 58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 CO.60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI.63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN.65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB.86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 SR.89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2,42E+06 3.71E+05 SR.90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y.91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR.95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NB.95 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+05 RU 106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 AG.110M' 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE.125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE.127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE.129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I 131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 -6.49E+03 I.133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS 134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 '9.76E+03 CS.136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS.137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA 140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE.141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE.144 4.89E+06 2.02E+26 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 j ND 147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 Rev. O
!! 2 42 3/89 l
I' j 4 TABLI 2.2 PATHWAY DOSE FACTORS i ACE CROUP: CHILD PATHWAY: INHALATION 1 ............................................................................... l ORGAN DOSE TACTORS XUCLIDE l 1 l BONE LIVER T. BODY THYROID KIDNEY LUNC CI 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 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 KN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E406 2.29E+04 TE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 TE.59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0,00E+00 1.27E+05 7.07E+04 CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 N1 63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 -4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB.86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+05 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y.91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00- 2.63E+06 1.84E+05 ZR.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03- 6.14E+05 3.70E+04 RU 103 2.79E+03 -0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU.106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1,84E+05 1.43E+07 4.29E+05 AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00- 4.77E+05 3.38E+04 TE.127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE.129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1,82E+05 I.131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I.133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS.134 6.51E+05 1.01E+06 2,25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 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. O
!! 2 43 3/89
TABLE 2.3 PADNAY DOSE FACT 0kS ACE OROUP: INTANT PATHVAY: INHALATION l ORGAN DOSE TACTORS UUCL1DE l- .- * *- .*- - .....* ....... . ........ I BONE LIVER T. BODY THYROID KIDNEY LUNG 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.G23+00 0.00E+00 1.61E+04 CR.51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 KN 54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE.55 1.97E+04 1.17E+04 3.3*t+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 TE.59 1.36E*04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 Co.58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO.60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 NI.63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 ZN.65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3. 2 5 E+04 6.47E+05 5.14E+04 R3 86 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 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR.90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y 91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 ZR 95 1.15 F.+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NB.95 1.57E*04 6.43E+03 3.78E+03 0.00E+00 4. 7 2 F.+03 4.79E+05 1.27E+04 RU.103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4. 24E+03 5.52E+05 1.61E+04 RU.106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG.110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE.125M 4. 7 6 E+03 1.99E+03 6.58t+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE.127M 1.67E+04 6.90E+03 2.07E+03 4.87t+03 3.75E+04 1.31E+06 2.73E+04 TE 129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68t+06 6.90E+04 1 131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I.133 1.32E+04 1.92E+04 5.60E+03 3. 56E+06 2.24E+04 0.00E+00 2.16E+03 CS 134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS.136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18 E+04 1.43E+03
.....s.........s...............................................................
CS.137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 EA.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 5.17 E+05 2.16E+04 CE.144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5. 38 E+05 9.84E+06 1.48E+05 PR.143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND 147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 Rev. O II 2-44 3/89 u ___ ________________
1 VA8LE 2.4 s (Sheet 1of2) ) CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND ATMOSPHERIC O!SPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) ! Pathway Distance X/0 0/0 l Sector- (Note 2) (Miles) (Notes 3. 4) (Notes S. 6) , Resident 2.20 9.28E 07 5.32E 09 N Garden None - - Milk Cow None - - Resident 2.30 5.12E 07 2.60E 09 NNE Garden 2.40 - 2.30E 09 Milk Cow None - - Resident 2.30 3.58E 07 1.28E 09 _ NE Garden 2.70 - 8.92E 10 Milk Cow 4.50 -- 2.70E-10 Resident 2.40 2.58E 07 7.08E 10 ENE Garden 2.60 - 5.77E 10 5 Milk Cow None - - Resident 2.40 3.02E 07 6.62E 10 . E Garden None - - Milk Cow None - - Resident-- 2.30 3.68E 07- 9.00E 10 ' ESE Garden -2.30 - 9.00E 10 Milk Cow- None - -- ~ Resident 2.00 7.10E 07 2.80E 09 SE Garden 2.50 - 1.60E 09 Milk Cow None - - Resident 1.60 9.96E 07 5.92E 091 SSE- Garden. 4.80 -- 4.48E 10 Milk Cow 2.20 - 1.80E 09 v - - -- , Resident 1.60 7.74E 07 4.66E 09-S ' Garden. 4.30 - 4.34Ee10
- Milk Cow 4.20 - 4.56E 10-Resident 1.90' 4.42E 07 2.06E 09 SSW: Garden- None - -
Milk Cow - None - - Rev. 5 L - II 2-45 12/90
TABLE 2.4 . ! (Sheet 2) i CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND l ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS I REQUIRED 8Y RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) ! Pathway Distance X/Q D/Q Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6) i Resident 1.00 1.60E 06 7.50E 09 J' SW Garden 2.10 - 1.10E 09 Milk Cow 4.70 - 1.79E 10 Resident 1.00 1.80E 06 6.50E 09 WSW Garden 1.10 - 5.64E 09 i Milk Cow None -- - Resident 1.50 8.40E 07 2.80E 09 W Garden 1.50 -- 2.80E 09 Milk Cow None - -- Resident 2.00 7.30E 07 2.50E-09 WNW Garden 3.00 -- 1.04E 09 5 Milk Cow None -- -- Resident 2.70 6.98E 07 2.24E 09 NW Garden None - -- i
. Milk Cow None -- --
-Resident 2.70 7.62E 07 3.22E 09 NNW Garden 4.90 --
8.48E 10 i Milk Cow 4.50 -- 9.60E 10 i NOTES: . . (1) Receptor locations are'taken from the nearest receptor locations identified in the CPSES 1990 land use census. (2)-In addition to the pathways shown, the inhalation and ground plane pathways are present at the nearest resident. (3) The units for X/Q are Sec/ Cubic Meter. (4) X/Q. Values at, distances 1.0, 1.5, 2.0, 2.5,.3.5, 4.0, 4.5, and 6.0 miles were taken frc.a Table 2.316. " Average Annual Relative Concentration at 4 CPSES," of the CPSES Environment Report Operating Licensing Stage (Reference 3). The X/Q values at other distances were determined by linear interpolation. (5).The units for D/Q are inverse square meters (6) D/Q values at distances 1.0, 1.5, 2.0,-2.5, 3.5,-4.0, 4.5, and 6.0 miles were taken from Table 2.3-17, " Average Annual Relative Deposition Rate." of the CPSES Environmental Report, Operating License Stage (Reference 3). The D/Q values at other distances were determined by linear interpolation. II 2-46 Rev. 5 i 12/90
. , . , . , , . , . - - + - . . - , . - - . + , . - - . . - . . , ~
- _ _ _ = - - .. _ - . - . - - -.
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 8 (Eq. 2-30] (a)8 + 0.5 b /n)I I)(r) = the les,er of 4
/~3 (Eq. 2-31) o)
w Where: a)
=
the vertical standard deviation of materials in the plume at distance, r, for atmospheric stability class, j, expressed in meters. (Figure 2.3) 0.5 = the building shape factor. l b = the vertical height of the reactor containment structure (79.4 meters) l Rev. O II 2-48 3/89
2.3.2 Decosition Calculations The relative deposition per unit area is calculated as follows: D' D, g (Eq. 2-32) Q 0.3927 r Whero: D/Q = depositiv4 per unit area normalized by source strength (m 2) Og = 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. I l l Rev. O
!! 2 49 3/89
2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS Section of ler2 Definition Initial Use AF - Allocation factor of 0.5 applied to account 2.1.2 for releases from both 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. Co 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 Cr the alarm setpoint for each plant vent stack 2.1.3 eff'uent release rate monitor (uCi/sec)
' aux - the Auxiliary Building Ventilation Exhaust 2.1.4 monitor alarm setpoint. (uti/cm3) ccont - the Containment Atmosphere Gaseous monitor 2.1.5 alarmsetpoint.(uci/cm3)
C1 - the setpoint for each plant vent stack lodine 2.1.7 Monitor. (uci/cm3) Cp - the setpoint for each plant vent stack 2.1.8 particulate Monitor. (uCi/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). Dp = dose to any organ of an individual from 2.2.2 radioiodines, tritium and radionuclides in particulate from with half lives greater l than eight days. (mrem) Rev. I 11 2-50 8/89 l u_ -
--t'
l l Section of Igrm Definition Initial Use Ds skin dose rate at the SITE BOUNDARY due to 2.1.1 noble gases. (mrem /yr) Dt total body dose rate at the SITE BDUNDARY 2.1.1 due to noble gases. (mrem /yr) Og air dose due to beta emissions from noble 2.2.1 gases. (mrad) Dy air dose due to gamma emissions from noble 2.2.1 gases (mrad) D/0 the annual average relative deposttion at 2.2.2 thelocationofinterest.(m*2) 6 plume depletion factor at distance r for 2.3.1 the appropriate stability class (radioiodines and particulates). FB the estimated flow rate contribution 2.1.1 associated with the release rate of the batch source. (cm3/sec) FC - the continuous flow rate contribution of 2.1.1 each plant vent stack. (cm3/sec) Fv the flow rate at each plant vent stack. 2.1.1 (cm3sec)
/
FABV the flow rate contribution associated with 2.1.4 the sources In the Auxiliary Building other thanthewastegasdecaytanks.(cm3sec) / Faux - the total flow rate at the Auxiliary 2.1.4 Building Ventilation Monitor during the release of a Waste Gas Decay Tank. (cm3/ sec) Fcont the flow rate contribution assc:iated with 2.1.5 - the release of the Containment Atmosphere. (cm3/ sec) , FGDT = the flow rate contribution associated with 2.1.4 the release of a Waste Gas Decay Tank. (cm3/ sec) Rev. O
!! 2 51 3/89 ,
i Section of Ig3 Definition Initial Use K = terrain recirculation factor. (Unitiess) 2.3.1 Ki = total body dose factor due to gamma 2.1.1 emissions from noble gas radionuclide 1. (mrem /yr per uti/m3) Li - skin dose factor due to beta emissions 2.1.1 I from noble gas radionuclide 1. (mrem /yrperuCi/m3) Mt = air dose factor due to gamma emissions 2.1.1 from noble gas radionuclide 1. (mrem /yrperuti/m3)
.Ni = air dose factor due to beta emissions 2.2.1 from noble gas radionuclide i.
(mrem /yr per uti/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 Pj = dose parameter for radionuclide i, (other 2.1.6
'han noble gases) for the inhalation pathway (mrem /yr per uti/cm3)
Qi = total release rate of radionuclide i from 2.1.1 the Plant Vent Stacks. (uCi/sec) Q'i = cumulative release of radionuclide i 2.2.1 during the period of interest. (uci) RPi ,a o = dose factor for radionuclide i, 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. 0 l 11 2 52 3/89 l
i section of Ism Definition Initial Vit 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. Djk - 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 relative 2.1.1 concentration at the SITE BOUNDARY. (sec/m3)
. (3.3 x 10 6 sec/m3 in the N 1 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, 1 Rev. O 11 2-53 3/89
i i Section of ltra Definition initial Use Xe i - the concentration of radionuclide i in the 2.1.1 l 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) Xyi the concentration of radionuclide i present 2.1.1 at each plant vent stack. (uci/cm3) 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 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) Xjy 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 Radiological Effluent Control 3/4.11.2.1, Table 4.112. (uCi/cm3) 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) 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) Rev. O 11 2-54 3/89 l ._ . . -- -
Section of Term Definition Jnitial U:e, l Xi cont - the concentration of noble gas radionuclide 2.1.5 1 i in the containment release stream as I 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 combined sources as calculated from the radionuclido 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. (utt/cm3) z - the fraction of time the wind blows to the 2.3.2 sector of interest 1.1 - conversion factor of mrem skin dose per 2.1.1 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) l Rev. 1 11 2-55 8/89
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I , SECTION 3.0 1 RADIOLOGICAL ENVIRONMENTAL MONITORING g 3.1 SAMPLING LOCATIONS 1 Sampling locations as required in Radiological Effluent Control ; 3/4.12.1. Table 3.12 1 are described in Table 3.1 and shown on the map in Figure 3.1. NOTE: For the purpose of implementing Radiological Effluent Control
^
3/4.12.1, sampting 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.
l The sampling locations shown on Table 3.1 are the minimum locations i required for compliance with Radiological Effluent Control 3/4.12,1. If desired,~ additional locations may be monitored as special t,tudies to evaluate potential pathways of exposure without adding such locations to thu monitoring program given in Table 3.1.
- 3.2 INfERLABORATORY COMPARISON PROGRAM for the purpose of implementing Radiological Effluent Control 3/4.12.3, TV Electric has contracted Teledyne.lsotopes 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 conc 6ntrations of radionuclides known to the issuing age'ncy 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 a19rt it _to any po.ssible problems. - ' Participant laboratories measure the concentrations of specified t;adionuclides 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 II 3 1 '3/89 i_ __ - . . . . _ . _ . _ _ _ _ _ _ _ . - _ _ _ _ _ _ . . _ . _ . . _ . . - _ . _ . _ . _ . _ _ _ .,
or lower than the known values or outside the control limits indicate a need to check the instruments or prortiures : $,1, Teledyne participate; in the environmental sample crosscheck program for milk and water sanles conducted by the U.S. Environmental Protectica Ayency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas. Ilevada. 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. 0 11 3-2 3/89
Table 3.1 l Environmentsi fsepling Locations Satopling Luetttsn Sample Point (Sector - Miles?, Type ( ) Al N-1,45 ($1ers Creek Park) A A2 N-9.4 (Crat, bur g , A _f3 E-3.5 (Children's Horne) A _fa SSE-4.5 (Clen Rose) A
,, A5 , _
S/SSW-l.2 A i A6 A SW-12.3 (Contre'} A7 SV/WSW-0.95 , , , A A8 NW-1.0 _r..... A R1 N-1.45 (Squaw Creek paw., R C N-4.4 , , , _ R E..t N-6.5 ,, _ R R4 N-9.4 (Gra,nkny) _ F(5 , NNE-1.1 _ R R6 NNE-5.65 R R7 NE-l.7 R _ _ # .. 3N _s,.__ _ _ __ _ NE- 4 . 8 R 13 _ ENE-2.5 R R10 ENE-5.0 R
+
Ril E-0.5 R Rev. O 11 3 3 3/89 l
Table 3.1 (Continued) Environmer.tal Sampling Locations Sampling Location Sample Point (Sector - Miles) Type R12 E-1.9 R __ R13 E-3.5 (Children's Hone) R R14 E-4.2 R R15 ESE-1.4 R R16 ESE-4.7 R a R17 SE-1.3 R R13 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 Rone) R
_ R23 S-1.5 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 (Contro1} R R30, WSW-1.0 R R31 WSW-5.35 R I l Rev. 0 II 3-4 3/89
Table 3.1 Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Type ( R32 WSW-7.0 R R33 W-1.0 R R34 W-2.0 R R35 W-5.5 R R36 VNW-1.0 R t R37- WNW-5.0 R 4 R38 VRW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R41 NW-9.9 (Tolar) R R42 RNW-1.35 R-R43 NNW-4.6 R i g ' SWl' N-l.5;(Squaw Creek . l Reservoir Marina) SW t - SW2 N-9.9 (Lake Cranbury) SW/DW( } c = ->
-SW3-- 'N-19.3 (Control-Brazca River) SW L SW4 NE-7.4 (Lake _Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW 3)
SW6- NNW-0.1 (Squav1C reek Reservoir) SW/DW( , 13, GWl' W-1.2 (NOSF potable' vater) GW (4 ) ,-( 5 ) E CW2 WSW-0.1 (Plant potable CW I water) l Rev. O II 3-5 3/89
Table 3.1 (Continued) Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Type ( ) G) GV3 SSE-4.6 (Glen Rose) GW (2>,(51 GV4 N-9.8 (Granbury) ,, GW
\5)
GW5 N-1.45 (Squaw Crect Park) GW SSI NNE-1.0 (Squaw Creek Reservoi-) SS 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(0) M M4 SW-13.5 (Cont. 1) M F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FPI 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. 0 11 3-6 3/89
(2) The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground well water (location GW4). 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 3.121, 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 olant 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 meritored for radioactivity to meet the requirements of the Radiological Environmental Monitoring Program specified in Radiological Effluent Control 3/4.12.1, Table 3.121. 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 374.12.1, Table 3.12-1. (7) Per the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1, Table 3.12-1, broad leaf vegetation is required to be sampled only when milk sampling is not Rev. O II 3-7 3/89
performed at all required locations. Broad leaf sampling will be performed at the specified locations if milk samples are unavailable from any location, i s. Rev. 0 11 3-8 3/89
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APPENDIX A - PATHWAY DOSE RATE PARAMETER P g (inhalation)' = K'-(BR) DFA g (Eq. A-1] where:
- Pj the pathway dose rate parameter for radionuclide, i, (other than I
noble gases) for the inhalation pathway, in mrom/yr per microcurie /m3. The dose factors are based on the critical
~
- individual organ for the child age group.
- K
= con'ersion v factor, 106 pCi/ microcurie
.= 3700 m3/yr, breathing rate for child (Ref. 2. Table E 5)
BR
' DFAj-
= the maximum organ inhalation dose factor for the child age group for the ith radionuclide (mrem /pCi). Values are taken from Table E-9, Reg,- Guide 1.109 (Ref. 2)
Resolution of _the units. yields: 9 Pg (inhalation) = 3.7 x 10 DFAg (mrem /yr per uCi/m ) 8 (Eq. A-2) f t o ~ The-latest NRC. Guidance has deleted the requirement to determine Pi (ground-pl ane)-- and;_ Pj "(food) , In addition, the critical age group has been changed f_ rom _ infant to child. Rev. O h II A-1 3/89 i
, . . . . ~ . . - , . . - , - - . - , , . . - , , , . - . . . . , . . - . . . . . , , - . . . . , , - - , , ., . , - , , , _ , . . , - - ,
l l l APPENDIX B I INHALATION PATHWAY DOSE FACTOR (R t.a.o) I R g,,, = k' (BR) (DFA g, ) (mrem /yr per microcurie /m3 ) (Eq. B-1) where: k' - conversion factor, 106 pC1/ microcurie BR - breathing rate, 1400, 3700, 8000, and 8000 m3/yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E-5) DFAj,3,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 DFAi ,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
APPENDIX C GROUND PLANE PATHWAY DOSE FACTOR (R G j) R = k' k" (SF) DFG ((1-e ~ it )/A ] [Eq. C-1] where: k' - conversion factor, 106 pCi/ microcurie k" = conversion factor, 8760 hr/yr A t
- decay constant for the ith radionuclide, sec -1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec.
(15 yrs) 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. Doses to all other organs are assumed equal to the total body dose. SF = 0.7, shielding factor, from Table E-15, Reg. Guide 1.109 (Ref. 2) Rev. 1 II C-1 8/89
APPENDIX 0 C GRASS COW MILK PATHWAY DOSE FACTOR (R i,a,o) R
= k' [(QF*UAP (i w Il
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* *( t,a.o th)/Y,)c'Yf
~
[((fpx f,)/ Y p) + ((1-fp xf) e g [Eq. D-1} where: k' = conversion factor, 106 picoeurie/ microcurie (pCi/uci) QF = cow consumption rate, 50 kg/ day, (R.G. 1.109) UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109) Yp agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG 0133) Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2, (NUREG 0133) Fm = stable element transfer coefficient (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 radiciodine (Table E-15, R.G. 1.109) 0Fli ,a,o = the ingestion dose factor for organ, o, and the ith-radionuclide for each respective age group, a (Tables E-Il to E-14, R.G. 1.109) l 1 = decay constant for the ith radionuclide, sec' A, = decay constant for weathering, 5.73 x 10-7 see -1 (NUREG-0133) , tr '
- 1.73 x 105 sec, the transport time from pasture to cow l to milk to receptor (Table E-15, R.G.1.109)
Rev. O II D 1 3/89
APPENDIX D (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 - - l.0, the fraction of the year that the cow is on pasture.
= 1.0,-the fraction of the cow feed that is pasture grass
- fs- .-
while the cow is on pasture.
- The concentration of tritium in milk is based on the airborne concentration rather than.the deposition. Therefore, RCj is based on (X/Q):
R g,,,,
= k'k F, Q7 Up DFL t.aa (.75 (.5/H)) (Eq. D-2]
where: k - --103 grams /kg H = 8 grams /m3, absolute humidity of the atmosphere
, .75 -= fraction of total feed grass mass that is water
.5: - - ratio of the-specific activity of-the feed grass water to
-the atmospheric water. (NUREG-0133)-
0FLt ,a,o_ = the ingest. ion dose factor for tritium and organ, o,
-; for each respective age-group, a (Tables E.ll to E-'14, R.G. 1.109)~
All other' parameters and values-are as given.above. L i C
- NOTE:: Goat-milk pathway factor, R 1,a,o will be computed using the cow-m' ilk . pathway factor equation. - Fm factor for. goat-milk will be from L' - Table' E-2, R.G.1.109.
. Rev. O II 0-2 3/89 L
l
+ --,.m-u
APPENDIX E-C0W MEAT PATHWAY DOSE FACTOR (RM i,a o) \ R _= k' (Qp xU AP (l* w) * (If I
- II) * ( Ni a.o} *
(((fpx f,)/Y p) + ((1 - f pf,) o ~A *h)/Y,) x e i i*f (Eq._ E-1] where: k' - conversion factor,;10 -picocurie 6 / microcurie (pCi/uCi) QF- - ce's consumption rate, 50 kg/ day, (R.G.1.109) .
~
UAP. - Receptor's meat consumption _ rate; 0, 41,- 65, 110 kg/yr for infant, child, teenager,- and adult age groups, respectively (R.G. l.109) . Ff - 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 radiciodine
- (Table E 15, R.G. - 1.109)"
0Fli ,a,o - the ingestion' dose _ factor.for organ .o,-and the-ith
~
radionuclide'foreachrespectiveagegroup,a(Tables E-Il to E-14 R.G.;1.109)_
'A i - decay constant-for radionuclide l', sec-l'
( =-. decay constant for weathering,.5.73 x 10-7 see -l
-(NUREG-0133) 1 t r. - l' 73 x 10. _. 6 sec, :the transport _ time. from pasture to [
receptor-(NUREG-0133)
-th. '7,78 x-106 sec, the-transport time from crop to receptor -
-(NUREG-0133)c Rev. 0 l II E 1 3/89 l -..
APPEN0!X 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 RM i is based on (X/Q): R ,,,,= k'k Fg QF UM (DFLt.u) x 0.75 x (0.5/H) (Eq. E-2) where: All terms are as defined above and in Appendix D. Rev. 0 II E-2 3/89
t APPENDIX F-- ! Y
-VEGETATION PATHWAY DOSE FACTOR (R j y )
R
= k' x (r/ (Y y ( Ap + Ay ))] x (DFLg, 1 x . ((U ) f g e'A UiL
~#
+Uff e- t*h] [Eq. F 11.
where:- k' - 106-picoeurie/ microcurie (pci/uci)- UL A
- the: consumption rate of fresh leafy vegetation, 0,-26', 42, 64 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G; 1.109)-
-US g the censumption rate of stored vegetation, 0, 520, 630, 520.kg/yr for infant, child, teenager, or adult ~ age groups respectively.-(R.G.-1.109)
.f t ,- the fraction of the annual Lintake of fresh leafy vegetation grown' locally, 1.0 (NUREG-0133)'
.f: g - . the} fraction of the stored vegetation grown -locally .76 (NVREG-0133)'
t l '- the average time between harvest of leafy vegetation and its. consumption, 8.6 x 10 4seconds - (Table E-15, . R.G. Ll.109(24 hrs)). th the average-time between harvest of stored leafy vegetation and its consumption,-5.18;x 10 --seconds 6
- l (Table E.15, R.G.-' l .109 (60 days))
L Rev. 0' 11 F-1 3/89
APPENDIX f (CONTINVED) yh - the vegetation areal density, 2.0 kg/m2 (Table E-15, R.G. 1.109) All other parameters are ac previously defined. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, RY j is based on (X/Q) R
= k'k (U fg+U fj (DFLt ,,o) (.M (.5/H)) [4. F-2]
l -where: All terms are as defined above and in Appendix D. Rev. O II F-2 3/89 l l
_ _ . _ - . . . = _ . _ . . _ . i APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS l l 1: ll 1 G-0 Rev. 1 8/89
SUPPLEMENTAL GU10ANCE STATEMENT #1
SUBJECT:
LOWER LIMITS OF DETECTION FOR RADIOLOGICAL ANALYSES REQUIRED BY LIQUID EFFLUENT MNITORING 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 Ci/ml . The basis for this LLO is Ragulatory Guide 1.21, Appendix A, Section B.3, which states that the sensitivities of analyses of liquid effluents should be sufficient to permit the measurement of the following concentrations: 10-7 uCi/mi by gross radioactivity measurements; 5x10-7pC1 / ml of each gamma emitting radionuclide; 10 5 aCi/ml of each of the dissolved and entrained noble gas radionuclides; 10-7 ,:Ci/ml of gross alpha radioactivity; 10 5 pCi/ml of tritium; and 5x10-8 uCi/ml of strontium 89 and strontium -90. Based on this guidance, compliance with the action statement may be achieved by analysis for gross gamma activity with a LLD of 10-7 uCi/ml or by gamma isotopic analysis for principal gamma emitters with an LLD of 5x10-7 uCi/ml. If gamma isotopic analysis is performed, the 5x10-7 uCi/ml LLD shall apply to those radionuclides listed in Notation 3 of ODCM Table 4.11-1. G-1 Rev. 1 8/89
SUPPLEMENTAL GUIDANCE STATEMENT #2
SUBJECT:
LOWER LIMITS OF DETECTION FOR DISSOLVED AND ENTRAINED GAS ANALYSES REQUIRED BY THE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 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 u C i/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 4.11-2. l G-2 Rev. 1 8/89
)
1 SUPPLEMENTAL GUIDANCE STATEMENT #3
SUBJECT:
TRITIUM LEAXAGE FROM THE TURBINE GENERATOR PRIMARY WATER COOLING SYSTEM (TGPWCS) The purpose of this statement is-to provide guidance for handling tritium 5 detected in the Turbine Building sumps or Waste Water Holdup Tanks (WWHis), 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 or WWHTs to the Low Volume Retention Pond may continue when tritium is detected due to known leakage from the TGPWCS, provided that: (1) the average o tritium concentration does not exceed the 10 CFR 20 limit for release to an unrestricted area (3x10-3 uCi/ml); and (2) there are no detectable principal gamma emitters or I 131. Per 10 CFR 20.106(a), concentrations may be averaged over a period of not greater than 1 year. 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 LLO values given in Table 4.11 1. It also requires that the 5
' Waste Water Holdup Tanks be discharged directly to the Circulating Water Discharge Tunnel when the maximum LLD valves are exceeded. For tritium, the
-value established for required diversion and discharged to the Circulating Water Discharge Tunnel is lx10 5 uti/ml. These requirements are established based on acceptable activities-in the sump resulting from primary-m to-secondary leakage. This supplemental guidance, which allows discharges of 5 tritium to continue to the Low Volume Retention Pond provided that the average tritium concentration does not exceed 3x10-3 uci/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 dos,e 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 frcm sampling of the TGPWCS and reported in the Semiannual Radioactive Effluent Release report. G3 Rev. 5 12/90
CALCULATION OF DOSE DUE TO TRIT!UM LEAKAGE FROM THE TGPWCS ASSUMPTIONS:
- 1. The maximum inventory of tritium (700 mci) in the TGPWCS is released to the Low Volume Retention (LVR) Pond.
- 2. The volume of water in the LVR Pond is lE+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 00CM Equation 1-8: D - Aj tk Ct Fk Where: Aj = the dose conversion factor for tritium; 8.96E+00 mrem /hr per pCi/ml (from ODCM Table 1.1) tk - release duration; 336 hrs (from assumption 5) Ci = the concentration of tritium for the release. The average tritium concentration for the release is determined by dividing the total tritium activity by the total volume of water in the pond which results in an average tritium concentration of 1.85E-05pCi/ml G-4 Rev. 1 8/89
Fk
- the average dilution factor 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,: D =(8.96E+00 mrem /hrh(336 hrs)(1,85E-05pCi/ml)(1.2E-03)
\ pCi/ml j' D = 6.68E-05 mrem 1
The calculated dose of 6.68E-05 mrem is 2.2E 03% and 6.7E-04% of th' annual dose limits for the total body and any organ, respectively. I
, G-5 Rev. I 8/89
i 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 basis 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. G-6 Rev. 1 8/89
CPSES - 00CM List of Effective Pages Preface The Effective Page Listing (EPL) provides a tabulation of the current pages in-the CPSES ODCM. Each page in the CPSES 00CM is identified with a page number, including pages that contain tables or figures. A revision number and date are included on each page. The revision number and date are changed when the change represents a substantive revision to the infonnation that is provided on the page. If the page ) is_ revised or reprinted but the revision is not considered substantive i (i.e., it is an editorial correction), the revision number will not be changed, but will have the reprint date. Since the EPL may.not be updated with each revision, an Instruction Sheet (s) will be provided for-subsequent revisions of the CPSES ODCM; it should be retained immediately in front of the EPL. To identify the effective revision level of a page in the CPSES ODCM, check these Instruction Sheets first and, if not found, the EPL second. If-any effective page_cannot be'found, notify TV Electric _ Nuclear Licensing and the required effective pages will be provided. Contact may.be made by: phone (214/812-8873) or by. mail.- A marked up copy of pages from the Instruction sheets or the EPL is_a convenient way to identify the required pages. L l I EPL-1 December 1990 1
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CPSES/0DCH Eff.'ctive Page Listing Pace No. Fivision No. PART 11
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CPSES/0DCM Effective Page Listing Pace No. Revision No. PART II G0 1 G1 1 G2 1 G3 Rev. 5 G4 1 G5 1 G6 1 EPL 8 December 1990
I I t Attachment 8.2 Joint Frequency Distribution Tables Meteorological Data, January 1 to December 31, 1990 i f I l 4 L
o D U 1 f (" COMANCHL Pl AK
, litil 'l 111
- IH;l it I.DH DI6' ll : 1/ 4/Y1 13 : l '.'
JOINI l'fE()U E N C Y 'I Mil [ I: X TRl MEL1 titlGI Mil l' (01/07 L f. S U lilMI -1.9 DIG.C/100 fli 3141r! L 1 (1 f l M.'i . A f luiti t/ 1/VO 0:00 ill 12/3t/90 23:00 l'H i t'N(1 I t]M H - 1O M l _ t VI-l U l tf a 3 6 '!.16 D (W IE H'i/ fit CON D ) U l tl D . ;'. ' . f.1 - .76- !.1- 1.(r .',1- 3.1- %.1 7.1- 10.1- 1:1.1 - >10 101.
- S ,. O OlR . '. 0 . /5 J.0 .. 2.0 3.0 /.0 10.0 13.0 10.0 L,
(4 HL 0 0 :: 1 0 ? 3 U O O U U o te.. O O ')
. O O .1 11 O O O O U 1. ~ '
LNL 0 0 0 0 u 4 9 o O O O o 1:t I; o ti o u o i 5 0 o O O h 9 l HL 0 O U O O 7 21 4 1 U O U 3'5 , GE O u O 1 O il ' I ,*I
.. / 3 O O O D .'
41.1 o o 0 1 O O j9 3 1 0 0 o '! 4 0 ' O O O U U 10 1 O O O O lt
!4al 0 0 v (> 0 () O O O O O O ti BW O O u O O O O O O O u o o W t '. L l O O O O O O O O O O O O O ll 0 0 U J O O O U U O O O O l 'l M i U O O O O O O O U O O O ()
.lt! t, = 1) () O Q U O j. 1 O O O .'
,l!!IJ
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,. g .,
H,elu!'8 01" l i, U Al I D 110l.1R 8 : 2 011 1:U ritIR d'~ V(d 1 D li' LURG: lll? T i l'i /41. i Bt![i G FOR lHE Pf:R IO D O/60
.e D3TC CfitiANCHr ptAK
- 1111 1 1 : Ut i '*- . llHILll s (;D M
- 1_
D AT E s . 1/-4/91 13:12 JOIf4 I FREQUEtiCY TADLL tlODE R A 1 EL Y UHGIADLE (-1.9 < D1/DZ (a - 1.7 D00.C/100 H)
- H1ADIL
- tIf CLASG D
- 1: l(ON 1/ 1/00 0:00 10 12/ 31/ VO 23 :00 j PR i td ARY 10WI H 10 M LLVI.L -
W i tJ D GPEED (ME1 E.lG / S L CON D ) ) t lI N O - .22- . 51 - .76- 1.1- 1.6- 2.1 - 3.1- D.1-- 7.l- 10.1- 13 .1 -- >10 101 0 04 c .LU .75 1.0 1.b 2.0 11 . 0 b0 7.0 10.0 13.0 10.0
. ._ __ . _, . . _ . ._._........._.m ... . . . . _ _ . - . . . . . _ ,
J -O n. 0 0 0 2 6 6 2 0 0 0 .t b
- lvtfl. O O O O 1 3 2 6 0 0 0 O 12
!. ilE O O O U O 4 6 3 0 0 0 0 13 , _ llE .0 0 0 0 1- 7 7 1 O O O O 16 i C 0 0 0= -0 1 7 4 2 0 0 0 0 14 (10E O O O O 2 14 2 11 4 1 O O O 4V L- GR .O 0 0 0 0 S 12 0 3 0 0 0 20 000 0 0 0 0 0 2 73 17 H O O o bu j- -U .0 0 ~ 0- 0 3 1 23 9 2 0 0 v 36 4
.0 011 O O O O 1 2 S 10 1 0 0 0 19
- 0 11 0 O' O O. 0 2 3 0 0 0 0 0 h USH 0-. 0 0 1 O O O O O O O O 1 11 O. O O O O O O O O O O O U WNW O' O O O -- 0 0 0 2 0 0 0 0 ?
NW 0 0 0 0 0 0 2 4 4 2 0 0 12 Ntuff 0 0 0 0 0 0 6 3 11 3 0 0 2D l: . . _ _ . . . . _ . . . , _ . _ _ . . . . . . . . _ . _ _ . . _ . . . . . _ . . _ . . . . _ _ _ . , . _ . - . . . . . _ . c 10lALG O O O 1 7 49 126 75 32 5 0 0 29b tultiDER-OF CALHHs 2U4 NUMDER Uf INVALID HOURG 200
- NilHDER '.iF U AL ID : llotlRH 29;"
I TIMAL llOURS FOR THE PERIODS 0760 i: _ _ l' l i
.- ,,4.- ..m.-...,_..._,, ..__-.-m.,.._.-.-,m . ~ . - , ~ . . . . . . . . . . . . . . . -._.m,.. . . , _ . - - . , , , . _ . . , . . - . , , . . ~ , . . - , . . - - . - , , - - - . . . ~ . _
a-_~~.---.- . t k Hills COMAtlCHE PEAK 1
-!!NI T a 111 HGl .li s CDit ,
'UATE:
1/ 4/91 13:12 l JOIN 1 FitCQUENC't TADIE 3, . _ , _ - . . . . _ _ - . - _ - , U L3 G HTL1 UNCTABLE F1./ < D1/Il <= + 1. 5 D L'C . C/100 H) ) D'1 r U11.1 I Y CLAUG G 1 1 F iHUM 1/ 1/90 0:00 10 12/31/90 23:00 , Plt l mal (Y l tlkt R -- 10 N LLUk'L W3ND Dl'Ef.D (ME TI'.R S / !'t; CON U ) f
. . - . , . . . _ . - . . _ . . . . . . . . . . . . _ . _ _ _ _ . . , . . _ . . __ _ .. _._ ._ ._ ._ _ _ _. ... i 03 ND. .?2- .51- r?6 - 1.1- 1.6- ? .1 - 3 '.1 - S . ;1 - 7.1- 10.1~ 13.1- >10 TOI. i 01R 50 .7S 1.0 1.0 2.0 3.0 S,0 7.0 10.0 13.0 10.0
__ . . . . ._ . _ , . . . . - - _. - ...._..._..._..m. , _ . . _ _ _ . H O O o n 0 ? 1? 24 6 2 0 0 46 Nt4U O 'O- 0 0 2~ -0 14 6- 5 0 0 0 3b-
- .NE O O O 1 5 7 7 2 1 0 0 0 23 >
(34L 0- 0 0 1 ? 10 S 2 0 -0 0 0 20 E O O O 2 3 0 ? O O u o O lb EDC 0 0 0 0 3 14 13 2 0 0 0 0 32. ! , _OC 0 0 0 0 t U 7 Y .3 0 0 0. 20 00f. O O O 0- 'l 12 35 10 17 0 0 0 03 i 2
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PROCESS CONTROL PROGRAM TV ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION Revision 1 December 1990
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i CPSES/PCP TABLE OF CONTENTS P_RE Definitions iv
1.0 INTRODUCTION
11 1.1 PURPOSE 1-1 1.2 SCOPE l1 1.3 PREC AUTIONS/ LIMITATIONS 12 1.4 RESPONSIBIllTIES 14 1.4.1 Vice President, Nuclear 14 Operations 1.4.2 Station Operations Review 14 Committee 1.4.3 Radiation Protection Manager 15 1.4.4 Other Responsibilities 15 2.0 RADI0 ACTIVE WASTE PROCESSING REQUIREMENTS 2-1 2.1 50L10 RADIOACTIVE WASTES 21 2.1.1 Operability Criteria 2-1 2.1.2 Tests / Inspections 2-2 2.1.3 Basis 23 2.2 MAJOR CHANGES TO LIQUID, GASEOUS, a 23 SOLIO RA0 WASTE TREATHEP' ev5TEMS 3.0 PROGRAM DESCRIPTION 3-1 3.1 PROCESSING OF WET RADI0 ACTIVE WASTE 31 3.1.1 Processing Methods 31
. 3.1.2 Processing System Description 3-2 3.1.3 Prequalification Testing 32 3.1.4 System Qualification Tests 32 3.1.S Equipment / System Operability 33 Requirements w
i 12/90
..--__-,___.---___,________y___
CPSES/PCP 3.1.6 Batch Preprocessing Sampling ;3 3.1.7 Testing / Inspections 34 3.1.8 Acceptance Criteria 36 3.1.9 Corrective Actions 37 3.2 PROCESSING OF DRY ACTIVE WASTE 38 3.3 MIXED WASTE 39 l 41 4.0 WASTE CLASSIFICATION AND CHARACTER!ZATION , 4.1 WASTE CLASSIFICATION 41 4.2 WASTE CHARACTERISTICS 42 5.0 SPECIFIC WASTE STREAM PROCESSING DESCRIPTIONS 51 5.1 WET RADI0 ACTIVE WASTE STREAMS 51 5.1.1 Resins 51 5.1.2 Cartridge Filters 53-5.1.3 Evaporator Concentrates 54 , 5.1.4 Sludge 55 5.1.5 Hiscellaneous Liquids 55 5.2 ORY ACTIVE WASTE 56 6.0 ADMINISTRATIVE CONTROLS 61 , . L6.1 PROCEDURES 61
, 6.2 QUALITY ASSURANCE 61 6.3 CHANGES TO THE PROCESS CONTROL PROGRAM 62.
6.4- DOCUMENTATION 62 6.5 TRAINING- 63
7.0 REFERENCES
71 i 12/90 11
CPSES/PCP LIST OF FIGURES Fiaure No. Iltle EJLqt 11 CPSES Radioactive 16 Management Organizational Responsibilities 51 Dewatering Process F',ow Chart 58 52 Solidification Process flow 59 Chart 53 DAW Process Flow Chart 5 10 iii 12/90
l l CPSES/PCP DEFINITIONS Terms in this manual which have a specific definition or meaning are capitalized (e.g., "0PERABILITY"). Definitions for such capitalized l terms are found in Section 1.0 of the CPSES Technical Specifications, ! with the exception of those terms defined below: PROCESSING PROCESSING shall be the conversion of radioactive waste into a form that meets shipping and burial ground requirements. l t iv 12/90
- - - _ - . _ . , . . - . . .~.. _... - ....-. - - . . - . -
CPSES/PCP SECTION
1.0 INTRODUCTION
, 1,1 PURPOSE The purpose of the CPSES Process Control Program (PCP) is to 1 establish a program which provides reasonable assurance that all radioactive waster PROCESSED at CPSES for disposal at a land disposal facility are PROCESSE0 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, speciffe parameters for each method, and the administrative controls and quality assurance required to ensure compliance with applicable regulations and requirements. This PCP is not 1
- applicable to radioactive wastes transported to an offsite vendor for PROCESSING, 1,2 KQPJ This program defines criteria for the PROCESSING of the following waste streams for disposal at a land disposal facility: , (1) Wet Wastes (a) Resins (beadandpowdered) (b) Cartridge Filters ' (c) Evaporator Concentrates
.(d). Sludge
-(e) Miscellaneous liquids
.1 1 Rev, 1
, 12/90 1:
- . = . . - _ . . - - . - - , _ . . . , - - -
CPSES/PCP (2) Dry Active Wastes (OAW) (a) Compactible (b) Noncompactible 1,3- PRECAUTIONS / LIMITATIONS l Except as specifically described in this document, the following general precautions and limitations apply to the PROCESSING and packaging of all radioactive wasies 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) Liquid wastes or wastes containing liquids shall contain 1 as little free standing and non corrosive liquid as is reasonably achievable. (2) No package shril 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 waste shall not be packaged for disposal in cardboard or fiberboard boxes. (4) Void spaces within the waste and between the waste and '1 its package shall be reduced to the extent practicable.
. (5) --Only High-Integrity Containers (HICs) approved for burial at a land disposal facility shall be utilized for Packaging dewatered' Wastes when waste form stability is required per 10 CFR 61.
1-2 Rev. I 12/90
? CPSES/PCP (6) No objects or materials shall be placed into HICs that may cause chemical or physical damage to the container per the vendor's 10 CFR 61 Topical Report or other Federal, State or Burial Facility requirements. (7) As much as practical, polyethylene HICs shall be i.ept out of direct sunlight to prevent ultraviolet light degradation. Protection from direct sunlight shall be provided when Hits are stored for extended periods. (8) Radioactive waste shall nut be packaged for disposal if it is pyrophoric Pyrophoric materials contained in radioactive wasta shall be treated, prepared, and packaged to be nonflammable prior to disposal. (9) Radioactive waste in gaseous form shall not be packaged for disposal. (10) Radioactive waste containing hazardous 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. (11) Radioactive waste 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.
- (12) 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.
K 13 12/90
CPSES/PCP ! l 4 (13) Samples shall be handled and collected in accordance with l applicable CPSES procedures and in keeping with ALARA principles. (14) PROCES$1NG evolutions should be periodically monitored , for adverse chemical reactions and temperature changes. l.4 RESPONSIBIllTIES 1 1.4.1 Vice President. Nuclear Oeeration; i I It is the responsibility of the Vice President, Nuclear Operations, to ensure that the requirements contained in this manual are achieved during the PROCES$1NG of radioactive waste by developing appropriate administrative and implementing procedures. An I organizational chart showing specific station responsibilities for radioactive waste PROCESSING assigned by the Vice President, 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 1 Specification 6.13.
1.4.2 Station Ooerations Review Committee TheStationOperationsReviewCommittee(50RC)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 L station. Ar.y subsequent revision to these documents shall also be reviewed by SORC prior to the initial use of the' revision. These reviews shall ensure compatibility with-station equipment and operation.
14 12/90
CPSES/PCP Additionally, 50RC is responsible for reviewing changes to this PCP prior to implementation. 50RC also reviews station administrative and implementing procedures for radioactive wasta PROCESSING activities. 1.4.3 Radiation protection Mangggt 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 .nese documents prior to their initial use. Review of vendor procedures for 1 waste PROCESSING shall include technical review by the Operations, Chemistry, Technical Support and Quality Assurance departments. 1 1-5 Rev. I 12/90
l CPSES/PCP l l l Vice President, Nucisar Operations 1
~~-
Plant Manager l l Manager, Radiation Protection ChemisW & Operations Manager Environmental Manager ; , l Responsible for: Responsible for: Responsible for: Fiber /Demineralizer Wet waste processing Sampling operation ( l.e., solidtilostion Radiological and - Evaporator operat6on & dowetenng) nonradiological analyses Rosin transfers DAW collocoon/pic-::::5,g 10CFR81 waste classification storage Transportation Disposal Radiation ProtA% support I Figure 11 CPSES Radioactive Waste Management Organizational Responsibilities l6 gey, i U/90
. :. .a- = . _ . . . . . - . . . - . . - . - . . . - -
. _ _ . _ . _ . . _ . _ _ . _ . _ _ . . _ _ _ ___ _ . _ _ _ ______.m_._.. _
CPSES/PCP
.SECTION 2.0 RADICACTIVE WASTE PROCESSING REQUIREMENTS L1._,50 LID RADI0 ACTIVE WASTES OPERABILITY CRITERIA 2.1.1 Radioacative 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.1
- a. With PROCESSING not meeting disposal site and shipping and transportation requirements, suspend shipment of the c inadequately PROCESSED wastes and correct this PROCESS CONTROL PROGRAM, the procedures.-and/or the Waste PROCES$1NG 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 meets burial 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.
l 2-1
- 12/90-l
CPSES/Prp l TESTS / INSPECTIONS l 2.1.2 Satisfactory PROCESSING of wet radioactive wastes (e.g., filter ; sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with this PROCESS CONTROL PROGRAM:
- a. If any test specimen fails to verify satisfactory PROCESSING,
- the PROCESSING 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 CONTROL PROGRAM, and subsequent I
l testing verifies satisfactory PROCESSING. PROCESSING of the
. batch may then be resumed using the alternative PROCESSING parameters determined by this PROCESS CONTROL PROGRAM; This PROCESS CONTROL PROGRAM shall be modified as required, as [
L provided in Technical Specification 6.13, to assure satisfactory PROCESSING of subsequent batches of waste and
- b. With the installed equipment incapable of meeting Operability Criterion 2.1.1, above, or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to PROCESS wastes as necessary to satisfy all applicable transportation and disposal requirements.
I l 22 i 12/90
DSES/PCP I BASIS - - 2.1.3 This requirement implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 (FR Part 50. The i PROCESS parameters included in establishing this PROCESS CONTROL I PROGRAM may include, but are not limited to, waste type, waste pH, weste/ liquid / solidification agent / catalyst ratios, waste oil content, principal chemical constituents of the waste, mixing and curing times, !- and dewatering parameters. r I p 2.2 MAJOR CHANGES TO LIOU10. GASEOUS. AND SOLIO RAlW,J_iTl I' TREATMENT SYSTEMS i. Licensee initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, and solid): ! a. Shall be reported to the Commission in the Semiannual 1 Radioactive Effluent Release Report for the per' ' in which , the changes were reviewed by the SORC. The discussion of each change shall, contain:
- 1) A Summary of the evaluation that led to the
-determination that the change could be made in accordance with 10 CFR 50.59;- ,
i
- 2) Sufficient data 11ed information to support the reason 1 for the change without benefit of additior,al or i l
l -supplemental information;
. 3) A detailed ducription of the equipment. components, and PROCESSES involved and the interfaces with other i- plant systems;-
t I
-l1 23 Rev. I 12/90
_ - _ . . _ . _ . ._ _.- _ - ,.__ _._____m...._ .___ - ,.p ._ . y CPSES/PCP
- 4) An evaluation of the change, which sh w , the predicted '
releases of radioactivt materials in liquid and gaseous effluents and/c.* the quantity of solid waste that 4ffer fria those previously predicted in the License applicat1on anI amendments thereto;
- 5) An evaluttion of the change, which shows the expected maximum exporsures to a MEMBER OF THE PU81.!C in the UNRESTRICTED AREA and to.the general population that differ from those previously estimated in the License application and amendments theretoi
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waHe, to the actual releases for the period prior to when the change is to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
'8)- Documentation of the fact that the change was reviewed and found acceptable by the 50RC.
- b. Shall become effective upon review and acceptance by the 50RC. ;
l [ L W-l % l { o 24 Rev. I 12/90 _ _ . ~ . . . _ . _ - . . _ . _ . _ . . _ . _ . _ .
CPfE5/PCP SECTION 3.0 PROGRAM DEStali(10N 3.1 2R0 CESSING OF WET RADI0 ACTIVE WASTE 3.1.1 PROCESSING Methods Wet radioactive waste PROCESSED at CPSES shall be 1 PROCESSED into a form acceptable for disposal at a licensed facility. 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 compliance with 10 CFR 61 stability requirements shall have a topical report addressing 10 CFR 61 requirements under review or approved by the NRC. The Topical Reports and PCPs of other vendors may be refereneci in this PCP even if all vendors are not actively providing services or products at CPSES. However, if any other vendor is selected whose documents are not referenced, this document shall be revised to reference them. 3-1 Rev. I 12/90
CPSES/PCP 3.1.2 Proces sint;_$_yjigm Descriotion Detailed descriptions of the vendor's PROCESSING system shall be included in the vendor's Topical Report. 3.1.3 Preoualification Testina Prequalification tests shall be performed on each type of wet radioactive waste stream to demonstrate the ability of the PROCESS to produce an acceptable waste form per the requirements of 10 CFR 61. Thic prequalification testing is perfN med by the vendor and documented in the vendor's Topical Report. 3.1,4 System Oualification Tests Prior to the initial solidification of a given waste I stream type using a spacified PROCESS, a test shall be condu*:t M to demonstrate the ability of the PROCESS tystem to produce an acceptable waste form over the range of critical parameters identified during the prc.,_alification test ig. 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.
The dewatering PROCESS shall specify an endpoint for 1 each dewatering evolution so as to assure that the acceptance criteria specified in Section 3.1.8 are achieved. 3-2 Rev. 1 12/90
CPSES/PCP 3.1.5 Eauioment/ System Ooerability Recuirements 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) Instrumentat % and Controls (3) Mechanical 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 Botch Precrocessina Samolina Each batch of waste offered for PROCESSING shall be sampled and analyzed, as appropriate, in accordance with station procedures, the vendor's PCP and the Topical Report that addresses the 10 CFR 61 stability requirements. This sampling shall: (1) Provide necessary data to estimate curie content and to perform the waste classification analysis, t L (2) When solidification is involved, sampling 1
* -shall provide the data necessary'to:
l-1 3-3 Rev 1 12/90
CPSES/PCP (a) Ensure that waste stream parameters are within the bcunds for critical partmeters established in the vendor's PCP and 10 CFR 61 Topical Report.
@lE : Results of waste stream 1 chemcial analyses shall be reviewed by the PROCESSING vendor to ensure chemical constituents do not exist which could cause adverse chemical reactions during the solidification PROCESS or react adversely with the solidification container.
(b) Verify the applicability of pre- 1 ostablished mix ratios. 3.1.7 Testina/Insoections To satisfy the Test / Inspection requirements of Section 1 2.1.2 of this Program, a test or inspection shall be performed for each PROCESSING method to ensure that. the applicable acceptance criteria of Section 3.1.E are achieved. For dewatering this is accomplished by verifying that a specified end point is achieved for each _ dewatering evolution of the actual _ waste stream, o For solidification this is accomplished ~ by performing 1 a_ solidification of at-least one representative test
+ specimen from at least every tenth batch of each- type l- of wet radioactive waste offered for solidification.
The test specimen shall be verified in accordance with t the vendor's PCP. The purpose of this testing is to provide assurance that an acceptable waste form is produced using the pre-established formulations provided in the vendor's PCP. 3-4 Rev. 1
>!/90
_ . . . - _ _ __ _-~__ _ _. . . .. CPSES/PCP This test shall be performed on either a laboratory 1 scale or full scale test specimen which is similar both chemically and physically to the unadjusted waste stream to be PROCESSED. After the sample is collected, it should be conditioned in accordance with the vendor's PCP. The sample should then be mixed with the binder and additives in ratios determined using the vencer's pre-established formulations. The specimen should be observed to ensure that the applicable acceptance criteria specified in Section 3.1.8 are achieved. If the test results fail to meet the acceptance criteria, the following steps, as per 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 waste. PROCESSING of tho batch may then be resumed using the alternative PROCESSING parameters if the. alternative parameters will produce a product that falls within_the vendor's qualification envelope, s The vendor's PCP shall provide the method for
. determining the alternative PROCESSING parameters. _ Alternative PROCESSING-parameters I which fall within the vendor's qualification testing envelope shall be approved by the RP Supervisor, Radioactive Materials Control or his designee and shall be documented in accordance with the vendor's PCP. The vendor's PCP shall be modified as 3-5 Rev. I 12/90
CPSES/PCP 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 10 CFR 61 Topical Report. (2) If the test results failure is due to a malfunction of the PROCESSING equipment or the PROCESSING equipment is 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 Acceotance Criteria (1) Minimum Requirements 1 All classes of waste shall satisfy the 1 following acceptance criteria: (a) Liquid wastes -shall be solidified. 1 (b) Solid waste containing liquids'shall 1 not contain freestanding liquid in excess of 1% of the internal volume of the container. (2) Stability Requirements 1 For wastes which require structural stability, I the acceptance criteria are as follows: (a) The waste shall have structural 1 stability. 3-6 Rev. I 12/90
I CPSES/PCP Notwithstanding the provisions of-(b) 1 Section 3.1.8 (1)(a) and (b), liquid wastes or wastes containing liquid shall be converted into a form in which the freestanding liquid shall not exceed 1% of the internal volume of the container when contained within - a HIC, or 0.5% of the volume of the waste for wasto 'PROCESSEO to a stable form. 3.1.9 Corrective Actioni With PROCESSING not meeting the above acceptance -l , criteria or otherwise not ?,necting disposal site and shipping and transportation requirements,. suspend' shipment of the inadequately PROCESSED' waste and correct the PROCESS Control Program, the procedures, and/or the waste PROCESSING equipment as necessary to prevent a recurrence Additionally, an evaluation of similar wastes PROCESSED since the last successful surveillance. test shall be conducted to determine the extent'of the inadequately PROCESSED' waste. If such wastes have been shipped for disposal, the disposal - site operator shall be contacted and the problem j addressed, if PROCESSING it not performed in accordance with this 1-o
. . PCP,ithe improperly PROCESSED waste shall be tested-to ensure that it meets burial ground and shipping L requirements. Appropriate corrective actions shall p
be taken to prevent recurrence, l-Disposition of inadequately PROCESSED wastes will be handled on a case-by-case basis. 3-7 Rev. 1 12/90
CPSES/PCP 3.2 PROCESSING OF ORY ACTIVE WASTE-Dry Active Waste (OAW) generated it CPSES shall be PROCESSED by-segregation, sorting, and/or compaction. PROCESSING of DAW
-is pericrmed to accomplish the following functions:
(1) Packawt DAW in a fashion acceptable for disposal at a .' licensad disposal facility. , (2)- -Remove constituents not acceptable for disposal as ! OAW. L
-(3) Minimize volumes of DAW shipped for disposal by:
(a) removing reuseable and. uncontaminated items; and (b) reducing shipped volumes by compaction. 1 Onsite' PROCESSING of DAW at CPSES-shall be performed in 1 accordance with approved station procedures or vendor , l- procedures that have been reviewed'by the Radiation Frotection Manager. = Vendor equipment, personnel and procedures may be-
--used for DAW PROCESSING and-packaging.
The' segregation.of uncontami_nated waste from DAW is performed - to minimize the volume of DAW shipped for disposal. In order to provide- reasonable assurance that radioactive materials are - L~ - not released as clean waste, thef following requirements shall L be included in the segregation program, as discussed in L- Reference 7.5.3: l? , (1) Surveys, using equipment and techniques for detecting low levels of radioactivity, shall be made of items that may be contaminated and are to be disposed of as clean waste. 38 -Rev. 1 12/90
CPSES/PCP (2) Surveys may be conducted on individual items using ] portable survey instruments, such as pancake GM probes. However, in all cases, final measurements of each package (e.g., bag or box) of aggregated waste to be released as clean waste 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 not detectable { T with portable instrumentation. Final measurements shall be performed using sensitive detectors, such as scintillation detectors, in a low background area, ) 3.3 MIXED WAST 1 Mixed Waste is defined as waste that contains constituents-that satisy the definition of radioactive waste, subject to the Atomic Energy Act, and contains hazardous waste that either (1) is listed as hazardou; 1aste in.40 CFR 261, Subpart D, or (2) causes the waste to craibit any of the t,azardous waste characteristics identified in 40 CFR 261, Subpart C. Under current federal law, this waste is subject to dual regulatien by the NRC and 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 currently are no authorized disposal sites in the United States which are licensed to receive and dispose of mixed hazardous and radioactive waste.
. Since there currently is no avenue for disposal of mixed waste, efforts shall be made to reduce the generation of such waste at CPSES. To accomplish this, station procedures for chemical control and radioactive waste PROCESSING shall include the following requirements:
3-9 12/90 .__
CPSES/PCP (1) The 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 40 CFR 261. (2) Radioactive waste PROCESSING procedures shall include provisions for segregation and removal of non-radioactive hazardous constituents. Upon removal, such constituents would be handled as hazardous waste, as required by the EPA. (3) Mixed low-level radioactive waste generated at CPSES 1 hall not be shipped for disposal 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 until regulatory changes allow for disposal, or they are otherwise approved for disposal by appropriate regulatory agencies. l 3-10 Rev. I 12/90
CPSES/PCP SECTION 4.0 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
.61.55, using.one or more of the classification methods given in the USNRC's " Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (May 1983)".
Waste classification shall be performed in accordance with approved station procedures. The 'followl.ng specific requirements shall be incorporated in the program for sampling and analysis for weste classification: (1) Annual analyses shall be performed 'on representativo samples of each waste- stream or, alternatively, a PROCESS stream associated with the generation of the waste, for the nuclides listed in Table 1 and Table 2 of 10 CFR 61.55. (Note: Isotopic data from other 1 PWRs may be utilized until annual analyses are performed.) (2) The results of these annual analyses shall be used to develop isotopic abundances and scaling facators for difficult to measure nuclides (i.e., beta emitters and transuranics) based on correlations between those nuclides and more easily measured gamma emitters. L L (3) Gamma spectroscopy or gross radioactivity measurements shall be made for each container of waste PROCESSED L for disposal. Calculational methods for determining l 4-1 Rev. I 12/90
CPSES/PCP the total activity in each container shall be developed which use the results of the gamma spectroscopy or gross activity measurements, and the percent isotopic abundances and scaling factors from the annual analyses. (4) The classification program shall establish criteria and include provisions for an 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 WASTE CHARACURISTICS Waste PROCESSED for disposal at CPSES shall meet the applicable characteristics specified in 10 CFR 61.56. Waste classified as Class B, 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 I shall be accomplished by placement into a HIC, or by solidification using a PROCESS that produces a product which meets the stability requirements of 10 CFR 61.56, per Section 3.1 of this manual. The vendor's topical report shall include documentation of testing which verifies that the HIC or solidified product meets these stability requirements.
. Additionally, TV Electric shall comply with Federal or State requirements imposed specifically on an approved HIC or solidification product which limit the type and/or radioactive concentration of the waste to be placed in the approved HIC or solidified product.
i 4-2 Rev. I 12/90
CPSES/PCP SECTION 5.0 SPECIFIC WASTE STREAM PROCESSING DESCRIPTIONS 5.1 WIT RADIOACTIVE WASTE STREAMS 5.1.1 Resins Radioactive resins ria*, be accumulated from~one or more 1 of the following systems: (1) Chemical and Volume Control System-(CVCS) (2) . Spent Fuel Pool Cooling and Purification System (3) 1.iquid Waste Processing System (including the-filter /demineralizationsystem) (4) Boron Recycle System-(5) Boron Thermal Regeneration System (6) Steam Generator Blowdown System (SGBS) (7) Condensate Polishing Demineralizer System-(8) -Other miscellaneous ion exchange media as
, generated These resins may be transferred to the vendor's 1 PROCESSING skid, to the SRSTs or routed to the Waste L Conditioning Tank, if it is necessary to PROCESS l secondary condensate polishing powdex resins, they-are-transferred to the vendor's' PROCESSING skid.
l l l l l 5-1 Rev. 1 12/90 1 L
CPSCS/PCP Normally, spent resins are PROCESSED for disposal by 1 dewatering. The resin is transferred to the liner or HIC where it is PROCESSED utilizing vendor supplied services, per Section 3.1 of this manual. A representative sample of the resin is collected during transfer for calculations of curie content and waste classi- fication. Containers are sealed, surveyed, and labeled, as appropriate, and stored in a designated storage area until they are shipped for disposal. Alternatively, resins may be PROCESSED for disposal by 1 solidification. Resins are transferred to the Waste Conditioning Tank where they are isolated and sampled for isotopic content and PCP parameters as defined in the vendor's PCP. If necessary, the resins are chemically conditioned. The isotopic analysis results are used to estimate the waste classification,
-datormine the proper waste form stability requirewntt, and select the proper v.ntainer for transportar)p and disposal. The resins are then transfernd to the vendor's PROCESSING skid where they are solidified per Section 3.1 of this manual.
Containers are sealed, surveyed, and labeled, as appropriate, and are stored in a designated storage area until they are shipped for disposal. Flow charts of typical dewatering and solidification 1 PROCESSING paths are shown on Figures 5-1 and 5-2,
. respectively.
I, 5-2 Rev. 1 12/90
]
CPSES/PCP-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 Miscellaneous '
- (7)-
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 to be used for disposal are detere.ined. Normally, filters are _placed 1
-in a liner or HIC and dowat6ted; however,-filters may be dried and nandled as DAW if conditions allow,zor may-be encapsulated. Upon completion of PROCESSING, the containers are -sealed, surveyed, and labeled, _ as appropriate, and stored in a: designated' storage area' until they are shipped for_ disposal.
l '.
-5 3 Rev. I 12/90
I CPSES/PCP 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. When filters are 1 encapsulated by solidification in a container, isotopic concentrations may be determined by averaging over the volume of the solidified mass. 1 5.1.3 Evaoorator Concentrates y 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 system 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 inormally recycled. Therefore, volumes of evaporator 1 concentrates from liquid waste PROCESSING and boron __ recovery, that must be solidified, are expected to be relatively small. If solidification of evaporator concentrates is required, they would be transferred from the evaporators to the Waste Conditionng Tank-where batches are isolated and sampled for isotopic content and PCP parameters as defined in the vendor's
. PCP. If necessary, the concentrates are chemically conditioned. The isotopic analysis results are used 5-4 Rev. I 12/90
CPSES/PCP to estimate the waste classification, determine the 1 proper waste form stability requirements and select the proper container for transportation and disposal, The concentrates then are transferred to the vendor's PROCESSING skid where they are solidified 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. 5.1.4 sludae Radioactive sludge is accumulated and handled on a case-by case basis by periodically removing the sludge from various tanks and sumps located throughout the plant. Each batch of sludge is sampled for isotopic content and PCP parameters, 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 shipped for disposal. 5.1.5 Miscellaneous Liouids Miscellaneous liquids generated in the station will be collected and PROCESSED on a case-by-case basis. Such wastes may include decontamination wastes and chemical wastes collected from the Chemistry Labs. Batches of such waste are isolated, sampled for isotopic content i 5-5 Rev. I 12/90
CDSES/PCP and PCP parameters, chemically conditioned if necessary, and transferred to the vendor's PROCESSING skid where they are PROCESSED per Section 3.1 of this manual. Containers are sealed, surveyed, and labeled, as apcropriate, and stored in a designated storage area until they are shipped for disposal. 5.2 ORY ACTIVE WASTE Ory Active Waste (DAW) consists of radioactively contaminated 1 or activated waste which contains minimal amounts of liquids. DAW may be compactible, such as paper, plastic and protective clothing, or non-compactible, such as tools or plant equipment. This waste is segregated by station workers at the point of generation into receptacles designated for
" clean" or " contaminated" trash. " Clean" receptacles are used to collect trash that potentially is not contaminated.
" Contaminated" containers 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 assumed to be contaminated un+.il it is surveyed and proven clean. Bags are collected from the receptacles, surveyed for external dose rate, and taken to a desi_gnated sorting area for PROCESSING. Bags below a specified dose rate level, per station procedures, may be opened and the 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 contents of bags that are 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 items are then disposed of as DAW. Compactible items are collected 1 and may be compressed into approved strong, tight containers.
5-6 Rev. 1 12/90 - - - -
CPSES/PCP Noncompactible items are placed directly into approved strong, tight containers. Containers are sealed, surveyed, and 1 labeled, as appropriate, and stored in a designated storage area until they are shipped for disposal or offsite PROCESSING. A flow chart of the'OAW PROCESSING path is shown on Figure 5-3. 5-7 Rev. 1 12/90
.~ a CPSES/PCP Etch ffftkON TRSTE BR CH me TE NO ATE au _
YES PTE A 0 ING
,o in o "8,La% g gunSTE / FIED cu
=
=
5 ns YES PUICE IN \ FOR CNN & 015 FicURE 5-1 Dewatering Process Flow Chart 5-8 _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ ___ . w naa.
CPSES/PCP TilfWilFER 3R$7E TD ISOLAfE C MIX TE WRSTE emTCH -
#EPRE Tivt -
St.RVEILLPNCE -
" ST SOL ON l TEST?
Syg itE2J AfD7 Pi4tf9ETERS TES NO
$0 E SOL CA :
YES o CH WRE (MN SES NO
--e TO 6 -
CONTA'IER me RCCEPfftCE TMil&S M"S 3 c""'a'/ :([CORRECTIV YES o 6 STE ON
't STO O SHIP T ON FOR DISPOSAL / 40 01SPOEfL Figure 5 2 Solidification Process Flow Chart Rev, 1 59 12/90
.- 4 CPSES/PCP
" f4 !
w tw e rgfsastt g tw i
.a s w, vts s,w-CYN7' MFfiYM ESu."' TEth$ftIs eta
! et t m.
b b' ' > SPE F D
<ctP .s ar, as vm.u:
"l* a
]g tivtry easit e
vts W
- M" 9 Y 800 Ol3 PUER.
f me 01m30R.
= A l Of E* th 'Lf
/e
\rnib vts Erb 7 t sl an ip Figure 5 3 OAW Process flow Chart 5 10 12/90
CPSES/PCP SECTION 6.0 ADMINISTRATIVE CONTROLS 6 l' 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 of this manual. 6.2 00ALITY ASSURANCE Quality Assurance related activities for radioactive waste PROCES$1NG are implemented as described in the TV Electric CPSES Quality Assurance Manual. Such activities include: (1) : Review of documents and procedures affecting the PROCESSING, packaging, handling, and transportation of radioactive waste. (2) Review of procurement documents or, services.
-(3) Perform inspections as designated in applicable PROCESSING, packaging, and shipping procedures.
(4) Review applicable vendor QA programs for compliance with Regulatory and TV Electric requirements. (5) Perform audits of the radioactive waste management program at least-once per 24 months. (Note: Technical Specification Administrative Control 6.5.2.8.1 requires that audits of the Process Control Program and implementing procedures be performed under the cognizance of the Operations Review Comittee-at least once l per 24 months.) 6-1 12/90
- t
.CPSES/PCP (6). Documentation and retention of documentation of waste PROCESSING, packaging and shipping activities. 4 Those activities provide assurance that the final waste form, packaging, labeling, and transportation are in accordance with applicable regulations and requirements. ,
6.3 CHANGES TO THE PROCESS CONTROL PROGRAM Changes to this PCP shall be made in accordance with Technical Specification 6.13 which requires that changes to the PCP: (1) Shall be documented and records of reviews performed shall be retained for the duration of the unit Operating License. This documentation shall contain: (a) Sufficierit 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, and the-approval of the Vice President, Nuclear Operations. 6.4 DOCUMENTATION
. Procedures for radioactive waste PROCESSING, packaging, and transportation shall include requirements for maintaining and retaining LLW PROCESSING, packaging, and transportation records.
Detailed records for each container of waste shall be maintained. l 6-2 12/90
CPSES/PCP 6.5 TRAINING TV Electric and vendor personnel responsible for waste PROCESSING, packaging and transportation activities shall be trained and qualified to ensure that waste PROCESSING is performed in accordance with applicable requirements. Training programs shall establish a schedule for periodic requalification of at least once every two years. TV Electric shall verify the training of vendor personnel.
\
t 5-3 12/90
CPSES/PCP 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 Waste Licensing Branch, Technical Position on Radioactive Wasto Classification, May 1983 7.3 USNRC, tow level Waste Licensing Branch, Technical Position on Waste Form, May 1983 7.4 USNRC, Guidelines for Preparation and Implementation of a Solid Waste Process Control Program (Proposed), Draft Revision i 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, "Dewatered Spent Ion Exchange Resin Susceptibility to Exothermic Chemical Reaction" 7.5.3 IEN 85-92, Surveys of Wastes Before Disposai from Nuclear Reactor Facilities" 7.5.4 IEN 86-20, " Low level Radioactive Waste Scaling Factors, 10 CFR Part 61" 7.5.5 IEN 87-03, " Segregation of Hazardous and low-Level Radioactive Wastes" t 7-1 12/90
CPSES/PCP 7.5.6 IEN 87 07, " Quality Control of Onsite Dewatering / Solidification Operations By Outside Contractors" 7.5.7 IEN 88 08,
- Chemical Reactions With Radioactive Waste Sclidification Agents" 7.5.8 IEN 89 27, " Limitations on the Use of Waste Ftrts and liigh Integrity Containers for the Disposal of Low level Radioactive Waste" 7.6 CPSES Technical Specifications, Sections 6.5.2.8.1 and 6.13 7.7 CPSES Station Administrative Procedure STA 709, "Radioattive 1 Waste Management Program" 7.8 CPSES Radiation Protection Instruction, 7.8.1 RPI-203, " Shipment of Radioactive Materials" 7.8.2 RPI-204, " DAW Processing" 7.8.3 RPI 205, " Liquid Waste Orocessing" 7.8.4 RPI-209, " Radioactive Waste Classification
- 7.8.5 RPI-216, " Waste Steam Sampling and Data Base 1 Maintenance" ,
i 7.9 CPSES Chemistry Procedures: 7.9.1 CHM-517, " Chemistry Control of Liquid Waste Systems" 7.14 CPSES Radioactive Waste Systems Procedure RWS-301, "Radwaste Solidificatian Systems"
\
l 7-2 Rev. 1 12/90
- p -t l
CPSES/PCP l 7.11 Vendor Documents 1 7.11.1 CNSI DW-llll8 01 NP-A, "Dewater.ing -Topical Chem- 1 Nuclear Systems, Inc " ,1 7.11.2 SD 0P-003, " Process Control Program for CNSI Cement 1 Solidification Units" 7.11.3 : CNSI-2 (4313 01354-OlP A) Rev. 2, " Topical Report 1
-for Chem Nuct nr Systens, Inc., Hobile Cement '
Solidification Systems" . 1 7.12 TV Electric CPSES Quality Assu>ance Manual L l- . i. l l l L 1' 1: 7-3 Rev. 1 12/90 _ _
COMANCHE PEAK STEAM ELECTRIC STATION PROCESS CONTROL PROGRAM INSTRUCTION SHEET The following instructional information is being furnished to help insert Revision 1 Into the Comanche Peak Steam Electric Station PCP. In accordance with CPSES Technical Specification 6.13b. PCP Revision 1 became effective when it was approved by the Vice President. Nuclear Operations on December 15. 1990. Discard the old sheets and insert the new sheets as indicated below. Holders of the CPSES PCP should keep these instruction sheets in the front of the Effective Page Listing as a recora of the changes unti'l a new listing is issued. Remove Insert Cover Page Cover Page i through d v i through iv 1 1 through 1-4 1 1 through 1 6 2 1 through 2 , 2 1 through 2 4 3 1 through 3 5 3 1 through 3 10 4-1 and 4 2 4 1 and 4-2 5 1 through 5 5 5 1 through 5 10 6-1 and 6-2 6-1 through 6 3 7 1 and 7-2 7-1 through 7 3 EPL-1
/
l' - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ __
PROCESS CONTROL PROGRAM EFFECTIVE PAGE LISTING g4q[ EFFECTIVE REVISION /DATE i December 1990 , 11 December 1990 ! tii December 1990 iv December 1990 4 11 Revision 1 12 Revision 1 13 December 1990 14 December 1990 15 Revision 1 16(Figure 11) Revision 1 F 21 December 1990 22 December 1990 23 Revision 1 24 Revision 1 31 Revision 1 32 Revision 1 33 Revision 1 i 34 Revision 1
.35 Revision 1 36 Revision 1
- 3. Revision 1 8 Revision 1 December 1990 3 10 Revision 1 41 Revision 1 42 Revision 1 1 51 Revision.1 52 Revision 1 5-3 Revision 1 5-4 Revision 1 55 Revision 1 56 Revision 1
-5 7 Revision 1 5 8 (Figure 5 1) December 1990
- 5 9 (Figure 5 2)- Revision 1 5-10 (Figure 5 3) December 1990 61 December 1990 6? December 1990 6-3 December 1990 71 December 1990 72 Revision 1 J 7-3 Revision 1 EFL 1 December 1990
__ _ _ _ _ _ - . _ _ . _ _ _ _ _ . . _ , . _ _ _ _ - _ _ . . . _ _ . _ _ _. . _ _ . . __ _ _ _ _}}