ML20210P387
| ML20210P387 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/17/1996 |
| From: | Earle C, Katz P BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20210P373 | List: |
| References | |
| PROC-961017, NUDOCS 9708270088 | |
| Download: ML20210P387 (314) | |
Text
{{#Wiki_filter:. _ , _ _ ._ l APPENDIX (B) i i i i CALVERT CLIFFS NUCLEAR POWER PLANT 1 OFFSITE DOSE CALCULATION MANUAL l lI i j . l
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OFFSITE DOSE CALCULATION MANUAL Revision 2, Change 0 For The - Baltimore Gas And Electric Company Calvert Cliffs Nuclear Power Plant _= 0) i . PREPARED BY: t cA/ N YA c
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d' DATE: / 0, [ (($ elechni W nted
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REVIEWED BY: ![ 4 DATE: /d RET &'pf T&m Manager /
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REVIEWED BY: DATE: General SupervisoWCheminitry REVIEWED BY: k b '/ b k' DATE: / O//J'!f 4 POSRC Meeting Number APPROVED BY& DATE: # l'
/ Plant General Manaber'/(
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Offsite DoSo C;lculation M:nual Page 2 of 313 Revision 2, Change 0 (l v TABLE OF CONTENTS PART 1.0: PURPOSE AND APPLICABILITY / SCOPE ..... . . . . . . . . . . . . . . . . . . . . . . . . . .. . . ..4 PURPOSE.. . .4 APPLICABILITY / SCOPE . . ,
.4 PART 2.0 : DEFINITIONS AND REFERENCES .. .. ... . . ............ .. ... . . . . . . . . . . . . . . . . . . . . , .. 6 DEFINITIONS . , . . .6 REFERENCES.. .
.11 DEVELOPMENT REFERENCES .. , . 11 1 PERFORMANCE REFERENCES.. . 13 I PART 3.0 / 4.0 : CONTROLS AND SURVEILLANCE REQUIREMENTS . ,, . .. ....... 14 APPLICABILITY . , .
.14 !
MONITORING INSTRUMENTATION.. . .16 RADIOACTIVE GASEOUS EFFLUENT.. . .16 RADIOACTIVE UQUID EFFLUENT., . 21 RADIOACTIVE EFFLUENTS. . 26 UQUl0 EF FLUENTS.. . 26 Concentration.. . . . . . . . 26 Dose .... . .. .
. . 30 Lkluid Radwaste Treatment System.. . 31 GASEOUS EFFLUENTS . . 32 Dose Rate . .. . . . . 32 Dose - Noble Gases . ..
36 Dose . lodine-131 & Radionuclides ln Particulate Form _. 37 . Gaseous Radwaste Treatment System .. . 3e TOTAL DOSE., . . . .. . .
. 39 RADIOLOGICAL ENVIRONMENTAL MONITORING: .40 PROGRAM.
(D
/' *) LAND USE CENSUS .
INTERLABORATORY COMPARISON PROGRAM..
. 40
. 52
.. S3 PART 5.0 : CALCULATIONAL METHODOLOGIES..... . ...... ..... ...... .. . . . . . . . .54 RADIOACTIVE LIQUID EFFLUENTS., . . 54 RELEASE PATHWAYS [BS27] .. . 54 TYPES OF LIQUID RELEASES.. . 56 PROCESSING EQUIPMLNT.. . , . . , , . . . . . ., , . 56 UQUID EFFLUENT RADIATION MONITOR ALARM AND TRIP SETPOINTS.. . 57 UMITS ON RADIONUCLIDE CONCENTRATIONS IN LIQUID EFFLUENTS.. . . . . . . . .
. . . . . . . . . 87 :
UMITS ON CUMULATIVE TOTAL BODY DOSES AND CUMULATIVE ORGAN DOSES FOR UOUID EFFLUENTS.. . 93 LIMITS FOR THE LIQUID WASTE PROCESSING SYSTEM.. .100 RADIOACTIVE GASEOUS EFFLUENTS. .103 RELEASE PATHWAYS (B527) .. .103 TYPES OF GASEOUS RELEASES.. .107 PROCESSING FOUIPMENT.. . . . . . , . . ..... ,. .108 GASEOUS EFFLUENT RADIATION MONITORS AND SETPOINTS.. . . . .108 ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS . .144 ANNUAL SKIN DOSE RATE DUE TO NOBLE GASFS IN GASEOUS EFFLUENTS., - . . . . . . .150 ANNUAL ORGAN DOSE RATES DUE TO IODINES AND PARTICULATES IN GASEOUS EFFLUENTS.. .158 CUMUL ATIVE GAMMA AIR DOSES DUE TO NOBLE GASES IN GASEnUS EFFLUENTS .165 CUMULATIVE BETA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS . .172 CUMULATIVE ORGAN DOSES DUE TO IOD;NES AND PARTICULATES IN GASEOUS EFFLUENTS. .178 UMITS FOR THE GASEOUS WASTE PROCESSING SYSTEM.. . . . . . . .185 UMITS ON TOTAL ANNUAL DOSE - GASES, UQUIDS, AND URANIUM FUEL CYCLE SOURCES .. .187 SPECIAL EXCEPTIONS AND ASSUMPTIONS FOR CALCULATION OF DOSES AND DOSE RATES., .190 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM., .193 RADIOU.,GICAL ENVIRONMENTAL MONITORING PROGRAM, . .193 LAND USE CENSUS... . . . . ..
.197 INTERLABORATORY COMPARISON PROGRAM.. . . . . , . . . . . . . .
.199 ANNUAL RADIOLOGIC #* ENVIRONMENTAL OPERATING REPORT.. .
.200
/ ) INDEPENDENT SPEN 1 ML STORAGE INSTALLATION MONITORING PROGRAM _., .203 Ql
= J
__ '.:______ .- 2_ _ . _. _ _ Offsita Dose"C lculation Manual Pcge 3 of 313s Revision 2, Change 0 TABLE OF CONTENTS RADIOACTIVE EFFLUENT RELEASE REPORT ,a. . . . ... . .. . . . . . . . . .. . . .. . .. . . .. . . . . .. . .. 208 INTRODUCTION.. .. -.. , . . - - - . . . . . ... . . . . _. .208 i l RESPONSIBILITIES..... .. . . . - . ._.. . 208
- REPORT CONTENTS . .. ._ , . . . . . , . . . . . . . . . . . . . , , . - . , .. . . . . . . . . . ..,m., . . . . ,,206 REPORT SUBMIT"i AL ...~.....,. .... . . .. . . . . . . . , . . . . . , ....... ... .. . .- ., .. . .. .. . . . . . .209
- ADMINISTRATION or: THE ODCM . . .. . . .. .. . . ., .. . , , . . , . . . .. .210 INTRODUCTlON _ _ _ . _ .._ . - _ - - . .210 CONTROLS ON THE ODCM... . . - . - - . 210 SURVEILLANCE REQUIREMENTS.... . _ _ ., 210 RESPONSIBLE COMPANY ORGANIZATIONS ., _ 211 INITIATING CONDITIONS.; _ . .__-..._ ___ .m. . . , _211 CALCULATlON METHODOLOGIES . . . . ... . . . . _ . _ c211 -
CORRECTIVE ACTIONS.. .. z ...m . . . .. . . 212 BASES....... . . .. .. . . . . . . . . . . . , . . ...212-EXECUTIVE
SUMMARY
OF CHANGES.. , . . . . , , . . .. , . .. . . .213 i P ART 6. 0 ATTAC H M E NTS .. . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . . . . . 214 l - Attachment 1 Final Grading And Drainage Plan.. . . . . .. . . . . . .. ... . . . .. o . ,, ,. .,215 Attachment 2 Outfall 001. Sources of Liquid Radioactive Waste... . . . .216 i Attachment 3 Outfalls 002,003,004 Potential Sources of Liquid Radioactive Waste . . , . . ..218 i Attachment 4 Block Diagram of Liquid Radioactive Waste Systems.... . . . . . . . . .. , .- . 210 Attachment 5 Dominant and Less Dominant Radionuclides in Typical Redwaste Discharges . . .220 Attachment 6 Liquid Effluent Dose Factors . . . . . . . . .. . .. . .. . .. . ,, . , , . . .221 Attachment 7 C*neral Information Related to Gaseous Releases via the Main Vents . . . .224 Attachment 8 General Infurmation Related to Gaseous Releases via Pathways other than the . Main Vents.. .225 i Attachment 0 Block Diagram of Gaseous Radioactive Waste Systems . . .. . ..226 Attachment 10 Noble Gas Dose Factors. . . . , , . , , .227 Attachment 11 Empirical Derivation Of Site-Specific Dose Factors , , . , . . . .228 !' Attachment 12 Gaseous Effluent Pathway Dose Factors.. . .. .. . ..233
. Attachment 13 Environmental Monitoring Sites for REMP.., ..... . . . . . , , . 299 -
AttaF.mnt 44 Radiological Environmental Monitonng Program Surveillances for Direct Radiation. .300 Attact tre it 15 Radiological Environmental Monitoring Program Surveillances for Airborne Activity.. .301 Attachtr. mt 16 Radiological Environmental Monitoring Program Surveillances for Waterborne Activity.. . .302 l Attachment 17 Radiological Environmental Monitonng Program Surveillances for Ingestible Activity.. c.303 Attachment 18 Map of Environmental Monitoring Sites for REMP (S Km Radius).. , , , .304 Attachment 19 Map of Environmental Monitoring Sites for REMP (10 Mile Radius). . . . 305 Attachment 20 Environmental Monitoring Sites for ISFSI . . . , . , . . . 306 Attachment 21 Map of Environmental Monitoring Sites for ISFSI.. , , . .307 Attachment 22 Map of Environmental Monitoring Sites for ISFSI(ENLARGED) . .308 Attachment 23 Effluent Radiation Monitors .. , . . . , . . , , , , , . , 309 Attachment 24 List OF Effective Pages.. . . . . . .310 4 4
-- ,~ - _ _ _ _ _ _ _ _ _ _____._____ _ _ _ _ . _ _ _ _ _
OffsNe Dose Calculation M:nual ~ Paga 4 of 313 Revision 2, Change 0
- PART 1.0: = - PURPOSE AND APPLICABILITY / SCOPE
-PURPOSE-1 A.' ; The ODCM lists the radiological effluent controls established at Calvert Cliffs Nuclear Power Plant (CCNPP) for the purpose of ensuring the amount of radioactive materials -
. released to the environment are as low as reasonably achievable.
- B. The ODCM defines parameters and methodologies for calculating projected doses and
~ dose rates resulting from the release of radioactive materials in liquid and gaseous ' , . j effluents. -
C. The ODCM defines parameters and methodologies for calculating alarm and trip setpoints for Technical Specification related radiation effluent monitoring systems. D. The ODCM defines and establishes controls for the Radiological Environmental
- Monitoring Program.
~
APPLICABILITYgCOPE A. The information presented in this manualis applicable to any division, department, section, or unit within the Baltimore Gas And Electric Company (BGE) which is either m-wholly or partly responsible for performing any of the activities listed in ti.e PURPOSES section of tiiis procedure. Responsible organizations include, but are not limited to, the following; e
- 1. t:,GE, Nuclear Energy Division (NED), CCNPP Department (CCNPPD),
CHEMISTRY SECTION i 2. BGE, Fossil Energy Division, Technical Services Section, Chemistry Unit
- 3. . BGE, NED, CCNPPD, Electrical and Controls (E&C) Section
- 4. .BGE,. NED, CCNPPD, Operations Section
- 5. BGE, NED, CCNPPD, Radiation Safety Section B. This manualis applicable to the determination of alarm and trip setpoints for the l following radioactive gaseous effluent monitoring instrumentation:
1
-1. 0-RE 2191
- 2. 1/2 RE 5415-3/ 1/2-RE 5416 C. This manualis applicable to the determination of alarm and trip setpoints for the - l' following radioactive liquid effluent monitoring instrumentation:
'1. 0-RE-2201 -
- 2. 1/2-RE-4014 t 9
k.
. - -- ~e e ~ - .,-- , .._- - _ _ - - . . _ , - .
Offsite Dose Calculation M:nual Pege 5 of 313 Revision 2, Change 0
- 3. 1/2 RE-4095 D. This manualis applicable to the determination of the offsite doses and/or offsite dose l rates due to the following:
- 1. Radioactive material in gaseous waste discharged from CCNPP
- 2. Radioactive material in liquid waste discharged from CCNPP
- 3. Radioactive material contained in outside storage tanks at CCNPP E. This manualis applicable to the determination of the radiological affects on the l environment due to the presence of Calvert Cliffs Nuclear Power Plant.
F. The ODCM is based on Technical Specifications, BGE's interpretation of industry standards and practices, and recommendations made by Combustion Engineering. w 'W O . O
Offsite Dose Calculation Manual Page 6 of 313 Revision 2, Change O PART 2.0 : DEFINITIONS AND REFERENCES DEFINITIONS The defined terms of thl:; section appear in capitalized type and are applicable throughout these Controls. Definitions !!nked to Technical Specification are designated by TS and the Technlcal Cpecification definition number it is linked to, o g. TS.1.0. ABRORMAL AND/OR UNANTICIPATED RADIOACTIVE RELEASE: Any unplanned or uncontrolled release of radioactive material from the SITE BOUNDARY. , ACTION: That part of a control whk,h prescribes remedial measures required under designated conditions. TS 1,0 l BATCH RELEASE: A DATCH RELEAbE is the discharDe of liquid (or gaseous) waste of a discrete volume. (NUREG-0133, page 14) CHANNEL CAllBRATION: - A CHANNEL CAllDRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRAT80N t. hall encompass the entire channelincluding the sensor and air m and/or trip functions, and shalli a de the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIDRATION niay be performed . 1 / series of sequential, overlapping or total channel steps such that the endre channelis calibrated. 41.0 l CHANNEL CHECK: - A CHANNEL CHECK shall be the quahtative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, compathon of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter TS.1.0 CHANNEL FUNCTIONAL TEST:
- a. An analog CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signalinto the channel as close to the primary sensor as practicable to veilfy OPERABILITY including alarm and/or trip functions. TS.I.0
- b. A bistable CHANNEL FUNCTIONAL TEST shall be injection of a simulated si0nalinto the channel sensor to verify OPERABILITY including alarm and/or trip functions. TS.1.0 COMPOSITE SAMPLE:
A COMPOSITE SAMPLE is a combination of individual samples obtained at intervals that are very short (e.g., hourty) in telation to the compositing time interval (e.g., monthly) to assure obtaining a representative sample. The sample volume should be proportionate to the volume of fluid, either liquid or gas, flowing threogh the system. CONTINUOUS RELEASE A CONTINUOUS RELEAT a the discharge of liquid (or gaseous) wastes of a nondiscrete volume; e.g., from a volume or system that bu on input flow during the CONTINUOUS RELEASE. (NUREG-0133. P.14.) DOMINANT RADIONUCLIDE: A DOMINANT RADIONUCLIDE is one whose activity is greater than 1% of the total activity found in a ; TYPICAL RELEASES of liquid or gaseous radwaste.
i Offsits Dose C:lcul tion Manu:1 P:ge 7 of 313 Revision 2, Change 0 DOSE EQUlVALENT IODINE 131: 0 DOSE EQUlVALENT l 131 shall be that concentration of l-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131,1132,1133,1-134, and 1135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table lit of TID 14844,
- Calculation of Distance Factors for Power and Test Reactor Sites." TS 1.0 l FREQUENCY NOTATION:
The frequency notation specified for the performance of Surveillance Requirements shall correspond to the intervals defined in the following Table TS 1.0. Freauency Nolation Table TS table 1.0 NOTATION FREQUENCY 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 St. At least once per 6 months R At least once per 18 months S/U Prior to each reactor startup P Completed prior to each release - N.A. Not applicable Refueling Interval At least once per 24 months GAMMA ISOTOPIC ANALYSIS: A GAMMA ISOTOPIC ANALYSIS is a analytical method of measurement used for the identification and quantification of gamma emitting radionuclides. GASEOUS RADWASTE TREATMENT SYSTEM: A G ASEOUS RADWASTE TREA1 MENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off0ases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. TS 1.0 GSC: GSC stands for General Supervisor Chemistry. LESS DOMINANT RADIONUCLIDE: A LESS DOMINANT RADIONUCLIDE is one whose activity is less than 1% of the total activity found in TYPICAL RELEASES of liq 23 or Da+eous radwaste. O-
Offsit) Dose C:Icut: tion Manu:1 Pcy) 8 of 313 Revision 2. Change 0 (7 LIQUID RADWASTE TREATMENT SYSTEM: A LIQUID RADWASTE TREATMENT SYSTEM is the system installed and designed to reduce radioactive liquid effluents. The minimum components necessary for reducing liquid radioactive effluents is either 13 or 14 Reactor Coolant Waste ton Exchange; however, other equipment in the system may be used in the maintenance of ALARA for liquid radioactive effluents. LOWER LIMIT OF DETECTION: The LLD, as defined by Technical Specifications,is the smallest concentration of radioactive materialin a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probability of f alsely concluding that a blank observation represents a *real" signal. MEMBERS OF THE PUBLIC: MEMBERS OF THE PUBLIC shallinclude all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are pelsons who enter the site to service equipment or to make deliveries TS 1.0. l This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL: 7 The OFFSITE DOSE CALCULATION MANUAL (ODCM) st.all contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of Oaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Environmental Radiolo0lcal Monitoring Program. The ODCM shall also contain the radioactive effluent controls, radiological , , , environmental mor,itoring activities, and descriptions of the information that should be included in the Annu il Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specification . Administrative Controls TS.1.0 () OPERABILITY: A system, subsystem, train, component or device shall be operable or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls l normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subcomponent or device to perform its function (s) are also capable of performing their related support function (s). TS 1.0 OPERATIONAL MODE: An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in below. TS.1.0 OpmationaMosn TS table 1.0
% RATED REACTIVITY THERMAL AVERAGE COOLANT MODJ, CONDITION. K.n POWER' TEMPERATURE POWER OPERATION 20.99 >5% 2300 'F STARTUP 20.99 55% 2300 'F HOT STANDBY < 0.99 0 2300 "F HOT SHUTDOWN <0.99 0 300
- F > T ,, > 200 'F COLD SHUTDOWN <0.99 0 5200 'F REFUELtNG" 50.95 0 5140 'F
/ 'h Euctuding decay heat k "
Reactar vessel head untded or removed and fuet tn the vessel
l Offsite Dose C:lculation M:nu:1 J Pege 9 of 313 Revision 2, Change 0 l PROCESS CONTROL PROGRAM: PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes , based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal and State and Local , regulations governing the disposa! of the radioactive waste. ,
- PURGE OR PURGING
PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. RATED THERMAL POWER: RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt. TS 1.0 l SIMULTANEOUS RELEASES: Simultaneous liquid releases are discharges of liquid radwaste which occur at the same time. Simultaneous gaseous releases are discharges of gaseous radwaste which occur at the same time. ELTJ BOUNDARY: The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. TS 1.0 l (The SITE BOUNDARY is depicted on Attachment 18, ' Environmental Monitoring Sites") - SOURCE CHECK: O A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity, TS 1,0 l THERMAL POWER: The THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. TS 1,0 l TYPICAL RADWASTE RELEASES (OR TYPICAL RADWASTE EFFLUENTS): TYPICAL RADWASTE RELEASES are defined as (1) all releases conducted during any calendar quarter while either Unit 1 or Unit 2 is in mode 1, and also includes (2) all releases conducted during any , calendar quarter following mode 1 operation of either Unit 1 or Unit 2. This definition of TYPICAL RADWASTE RELEASES is intended to ensure the concentrations of DOMINANT RADIONUCLlDES represent realistic, maximum expected values. This definition is also intended to ensure that the concentrations of DOMINANT RADIONUCLIDES is not biased " low", as would be the case, if periods of extended outages when the production of fission products is minimized-were included. This definition may be modified by the GSC, however, the new definition shall be documented in accordance with the provisions outlined in the applicable section of the ODCM. (e.g., See the section which contains information related to documenting the fixed / adjustable setpoint.). UNRESTRICTED AREA: An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive matenals, or any area within the SITE BOUNDARY used for residential quarters of/for Industrial, commercial, institutional, and/or recreational purposes. TS 1.0
. _ _ . _ _ . . . _ . _ . . _ _ _ _ . . _ _ - _ _ _ - -_.._.._.._m._m_.. - _ _ _ . _
Offsits Dosa C:Icul: tion M:nual Pege 10 of 313 Revision 2 Change 0 VENTILATION EXHAUST TREATMENT SYSTEM: O A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive rnaterialin particulate form in effluents by paulng ventilation or ve's i exhaust Cases through charcoal adsorbers and/or High Efficiency Particulate Air (HEPA) filters for the l purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environrnent. Such a system is not considered to have any effect on noble gas effluents. Engineered Saftty Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION UXHAUST TREATMENT SYSTEM components. TS 1.0 l VENTING: VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in sun 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. TS 1.0 l WASTE GAS HOLDUP SYSTEMt See GASEOUS RADWASTE TREATMENT SYSTEM.
'esa89 1
O - j i O
OffA Lese wiculation M:nual Pag)11 of 313 Rh an 2, C:-;noe 0 l w Mesces . mmm , cJgtumynnnn , 3 M AiO M $[j@tRENCES ; NUREG 0133, " Preparation Of Radiological Effluent Technical Specification For Nuclear Power Plants", Boegli, J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield, (October 1978).
- 2. Regulatory Guide 1.109," Calculation Of Annual Doses To Man From Routine Release Of Reactor Effluents For The Purpose Of Compliance With 10 CFR Part 50, Appendix 1," Revision 1, (October 1977). ,
- 3. 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).
- 4. CCNPP System Description Number 14B," Reactor Coolant Waste Processing System Description."
- 5. Updated Final Safety Analysis Report, Chapter 11. " Waste Processing A'nd -
Radiation Protection."
- 6. CCNPP System Description Number 14D, " Miscellaneous Liquid Waste Processing System Description."
, 7. 0117D, " Miscellaneous Waste Processing System" ;
- 8. 0117C,
- Reactor Coolant Waste Processing System" O. Title 10 of the Code of Federal Regulations, Part 20
- 10. - Title 10 of the Code of Federal Regulations, Part 50
- 11. Calvert Cliffs Nuclear Power Plant Semi Annuai rsadiological Effluent Release Report (1986,1987,1988).
i
- 12. Radioactive Decay Data Tables, David C. Kocher,1981,
- 13. Radiological Health Handbook, Bureau of Radiological Health, Jan.1970.
L
- 14. TE 001,
- Main Vent Stack Flow Measurement"
- 15. ETP 8716, " Main Vent Stack Flow Measurement"
- 16. Verification And Validation Of The Gaseous Release Permit Portion Of The CCNPP EMS Computer Code, J. S. Bland And Associates, July 10,1990. ,
- 17. Land Use Survey in The Vicinity Of The Calvert Cliffs Nuclear Power Plant September 1991, (for the year 1990), Baltimore Gas And Electric Company, Environmental Programs Section, C. Key, B. E. Helbing
- 18. CP 607, Revision 1. "Offsite Dose Calculation Manual"
..O .
d ,5;- -g yemu-mww-e-3--=?-m-t----9-w e -- -- - ewc-a i gP -
Off66t3 Do)3 C:lculation M:nu:1 P:ge 12 of 313 Revision 2, Change 0
- 19. CCI 302, Calvert Cliffs Alarm Manual
- 20. TID 14844," Calculation of Distance Factors for Power and Test Reactor Sites"
- 21.
- Plant Data Book". BGE CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1. Job 6750. .
$ 22. 50.59 Log No. 82 B 999 028 R00, Safety Analysis No. 2, FCR 821053, Supplement 1 (Component Cooling System) [B527) 23 50.59 Log No. 90-0-074 011 R2, Activity MASE 90-7 (Plant Nitrogen System) ! [B527) , - -
- 24. 50.59 Log No. 90 0 029 045 R1, Activity MASE 90-6 (Plant Heating System) !
[B527)
- 25. ~ 50.59 Log No. 90 0 037 044 R1, Activity MASE 90 5 (Demineralized Water Systela) [B527)
; 26. 50.59 Log No. 90 B 012 043 R1, Activity MASE 90-4 (Service Water System) .
[B527) - 27, 50.59 Log No. 90 0 027-037 R2, Activity MASE 90 8 (Auxiliary Boller System) i [B527) -- 28, Bechtel Power Corporation, Calculation Number M 90 20, " Allowable i Radioactive Contamination Levels in the Plant Heating System" [B527) ,
- 29. Bechtel Power Corporation. Calculation Number M-9018, " Allowable Radioactive Contamination Levels in the Nitrogen System Header" [8527)
- 30. Bechtel Power Corporation, Calculation Number M 90-04, " Allowable t Radioactive Contamination Levels in Auxiliary Boiler Water" [B527)
- i. - 31. Bechtel Power Corporation, Calculation Number M 90-21, " Allowable
- Radioactive Contamination Levels in the Domineralized Water System" [B527) ,
[ 32. Bechtel Power Corporation, Calculation Number M 9019. " Allowable Radioactive Contamination Levels in the Service Water S/ stem" (B527)
- 33. Bechtel Power Corporation, Job Number 11865, Calculatien Number 7.4.315,
" Allowable Radioactive Contamination Levels in the Condensate Storage Tank"
[B527)
- 34. CCl 205, Setpoint Control Procedure ,
- 35. OI 8A, Blowdown System
- 36. NUREG 1301,"OFFSITE DOSE CALCULATION MANUAL: Standard Radiological Effluent Controls for Pressurized Water Reactors", W. W. Meinke .
and T. H. Essig, (Published April 1991). O
,,-.-we. .+-.---,,-,.----e- we, + -igu. 4 -u.4*~$--+-we es mT- ww e% --w --,-en.e-- -._.wr . ,--n.,m4 -,,,-nm. ..,---.e+ ..,w.e_,
Offsit] Dose C:lculation M:nual Page 13 of 313 Revision 2 Change 0
~- 37. Radiological Environmental Monitoring Program Annual Report for the Calvert
()
\/
Cliffs Nuclear Power Plant Units 1 and 2 January 1 December 31,1991", Baltimore Gas And Electric Company, March 1992
- 38. 50.59 Log No. 90-B 037120 R2, Activity MASE 90-11 (Condensate Storage Tank) (B527)
PERFORMANCB REFERENCES
.. TE 001,
- Mal' vent Stock Flow Measurement" O
m% G l O V
Offsite Dose C:lculation Minu:1 Page 14 of 313 Revision 2, Change 0 PART 3.0 / 4.0 : CONTROLS AND SURVElLLANCE REQUIREMENTS I APPLICABILITY CONTROLS 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 f ailure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a Control shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Controlis restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 When a Controlis not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the control does not apply by placing it, as applicable, in: ,
- 1. At least HOT STANDBY within the next 6 hours,
- 2. At least HOT SHUTDOWN within the following 6 hours, and
- 3. At least COLD SHUTDO'NN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accerdance 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. 3.0.4 Entry into an OPERATIONAL MODE or other specified condit!cn shall not be made unless the conditions of the Control are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual controls. 3.0.5 When a system, subsystem, train, component or device is determined to be Inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Control, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and device (s)
-- * ' ' + '
l i ; Offse Dose C:lculation Manu:1 Pcge 15 of 313 i Revision 2, Change 0 , SURVEILLANCE r l O 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or i' i other conditions specified for individual Control unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requiremr it shall be performed within the specified time interval with , a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. 4.0.3 Failure to perform a Surveillance Requirement within the allowed survelilance interval, defined by Control 4.0.2, shall constitute noncompliance with the OPERABILITY requirements , for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. However, this time of applicability 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 have to be performed on inoperable equipment, t 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made ' unless the Surveillance Requirement (s) associated with the Control have been performpd
- within the stated surveillance interval or as otherwise specified. This provision shall not prevent
- passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
I , o s ) J k
I I Offsit] Dose Cilcut .'l:n M: null Pa0e 16 of 313 R: vision 2, Chango O MONITORING INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT i CONTROLS : 3.3.3.0 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.312 shall be OPERABLE with their alarm / trip setpoints set to ensare that the limits of Control 3.11.2.1 are not exceeded, The alarm / trip setpoints of these channels shall be 4 determined and adjusted in accordance with the methodology and parameters in the ODCM. APPLICABILITY: As shown in Table 3.312. ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Control, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpcint 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 3.312. ,,
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explaih in the next Annual Radioactive Effluent Release Report why the Inoperability was not corrected in a timely manner. O c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3 9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.311. O
'd
-w w , - ~ - - . - . , . - . , . , , , , , - - -
e Dose calcu!ation Manual Page 17 en 2. Change a ('v) TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMQM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor- Providing 1 35 Alarm and Automatic Termination of Release
- b. Effluent System Flow Rate Measuring 1 36 Device
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor 1 37
- b. lodine Sampler 1 38
- c. Particulate Sampler 1 38 At all times.
._--.- - _- - ~_ - - _ _ - _ .-. - - _ --- - - _ _ . _ _ _ _ _ . - .-
l Offsite D:se Calcul: tion Manual P:ge 18 of 313 i Revision 2, Change 0 TABLE 3.312 (Continued) ACTION EIA_TEMENTS i ACTION 35 - 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:
- a. Using the main vt at moriitor as a backup and recording RMS -
readings every 15 minutes during the release, or
- b. Provided that prior to initiating the release, at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway. 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 the flow rate is estimated at least once , por 4 hours. ACTION 37 - With the number of channels OPERABLE less than required by the , Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours, or (2) an equivalent monitor is provided. ACTION 38 - 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 as required in Table 4.11-2 with auxiliary sampling equipment, nv
Dose Calcutation Manual Page 19( J)' R on 2. Change 0 TABLE 4.3-11 RAD!OACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATK)N SURVBLLANCE REQUIREMENTS MODES IN CHANNEL WHICH 1 CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION ES_T REQUIRED
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor- P P R* SAM -
Providing Alarm and Automatic Termination of Release
- b. Effluent System Flow Rate D'* NA R NA
- Measuring Device l l 2.' MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor D M R* SAS * ,
- b. lodine Sampler W NA NA NA
- 1
- c. Particulate Sampler W NA NA NA
- At all times other than when the line is valved out and locked.
i
. i .
l ' t Offsits Dose Cciculation M:nual Page 20 of 313 : ReAsion 2. Change 0 TABLE 4.311 (Continued) IARLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic , isolation of this pathway and/or Control Room alarm annunciation occurs if the appropriate following condition (s) exists:
- 1. Instrument indicates neeasure levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Cn uit failure.
- 3. Instrument indicates a downscale failure. ,
(} The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards traceable to NIST or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system within its intended , range of energy and measurement range. For subsequent CHANNEL ' CAllBRATION, sources that have been related to the initial calibration can be used. (4) The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours on days on which effluent releases are made. O
,.y-
Offsit] Doso C:lculation M:nu:1 P ge 21 of 313 Revision 2, Chango 0 g RADIOACTIVE LIQUID EFFLUENT CONTROLS 3.3.3.10 The radioactive liquid offluent monitoring instrumentation channels shown in Table 3.313 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE ! DOSE CALCULATION MANUAL (ODCM). 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, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, o, declare the channelinoperable, or change the setpoint so it is acceptably conservative. .
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumontation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Exert best efforts to return the instruments to OPERABLE status within 30 days " and,if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. .
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12. O V
Offsit) Dose C:lculation M:nual Pcg)22 of 313 Revision 2, Chango 0
- TABLE 3.313 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSIRUMENT OPERABLE ACTION
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line 1 28
- b. Steam Generator Blowdown Effluent Line 1 29
- 2. FLOW RATE MEASUREMENT DEVICES
~ -a, Liquid Radwaste Effluent Line 1 30
- b. Steam Generator Blowdown Effluent Line 1 30
~~
e
Offsit) Dose C:lculation Manu:1 P:g)23 of 313 Revision 2. Change o
^
TABLE 3,313 (Continued) ACTION STATEMENTS 4 ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases 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 membera of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.
ACTION 29 - With the number of channels OPERABLE less than required by the Mirdmum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the LOWER LIMIT OF DETECTION - defined in Table 4.11-1:
- a. At least once per 12 hours when the specific activity of the ,
secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l 131.
- b. At least once per 48 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUlVALENT l 131.
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 the flow rate is estimated at least once per 4 hours during actual releases. Pump periormance curves may be used to estimate flow.
C.iculation C22nual Page 24 1 TABLE 4.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CHANNEL CHANNEL SOURCE CHANNEL FUNCTIOlGL INSTRUMENT CHECK CWCK CALIBRATION TEST
- 1. GROSS RADIOACTIVITY MONITORS FROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line D P RS SAM
- b. Steam Generator Blowdown Effluent Line D P RS SA*
) 2. FLOW RATE MEASUREMENT DEVICES a.. Liquid Radwaste Effluent Line D* NA R NA
- b. Steam Generator Blowdown Effluent Line D* NA R NA g i
4 W i 4 i a i
?
- e 4 . 8
, [
i
Off611) Doso C:l;ufstion Manual Pcg3 25 of 313 Revision 2, Chan0e 0 i TABLE 4.312 (Continued)
-O TABLE NOTATION
(}
- The CHANNEL TUNCTIONAL TEST shall also demonstrate that automatic
!colation of this pathway end/or Control Room alarm annunciation occur if the
- appocriate following condition (s) exists
~
1 Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
O Instrurnent indicates a downsuale failure. 1 II- The irutlat CHANNEL CALIBRATION shall De performed using one or more of the referenco ttandar# trac->able to NIST or using standards that have been obtained frorn wppdecihd. participate in measurement assurance activities with 4 NIST. These standar&4 5, hail permit calibrating tha system w"hin its intended . , , , range of energy and measurement range. For subsequent CHANNEL
- CALIBRATION, bources that have been related to the initial calibration can be
( used. , , l (3)
- CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hc rs on days on which effluent releases are made, i
l l l o O l i i
Offsite Dose Calculation Manual Page 26 cf 313 R; vision 2. Change 0 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS: Concentration 1 CONTROLS 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Psrt 20, Appendix B, Table ll, Column 2 for radionuclides other than dissolved or entr::ined noble - gases. APPLICABILITY: At all times. ACTION:
- a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable, s
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive hquid wastes shall be sampled and analyzed according to the , 5 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 ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
Offsit] Dose C:lculation M:nu:1 Pag)27 of 313 Revision 2. Change 0 TABLE 4.11 1
'}
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
~
LOWER LIMIT OF MINIMUM DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)* TYPE ~ FREQUENCY FREQUENCY ANALYSIS (mCl/rnl) A. Batch Waste P P Principal Gamma 5x10 Releases 6 Each Batch Each Batch Emitters
- l131 1x10*
4 Mo 99, Co-144 2x10 4 P M H-3 1x10 Each Batch Composite d Gross Alpha tx10 P O 4 Each Batch Composite d Sr-89, Sr-90 5x10 ,_ B. Turbine M M Principal Gamma 5x10 Building Emitters
- Sump ,
l-131 1x10* O Mo-99, Ce-144 2x10* O
Offsite Dose Calculation Manu 1 Page 28 of 313 Revision 2. Change 0 TABLE 4.11-1 (Continued) TABLE NOTATION The LLD is defined, for purposes of these controls, 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: 8' LLD = Ee Ve 2.22 x 10'
- Y
- exp(4At)
Where: LLD is the "a priori" LOWER LIMIT OF DETECTION as defined above, as . . , microcuries per unit mass or volume, 1 Sb is the standard deviation of the background counting rate or of the , counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10' is the number of disintegrations por minute per microcurie, Y is the fractional radiochemical yield, when applicable, A,is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between sample collection, or end of the sample collection period, and time of counting. 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 prio_rl (before the fact) limit representing the capability of a measurement system and not as an g Dosteriori (after the fact) limit for a particular measurement. y 4._,.g_,w.__,.. -,.-_...,,,.-p> . , , , , _ - , - . = .-y ' _ y v y.,ir 4%-e e +r"m 3- - ---, , -.- +u-
Offse Dose C:lculation Manu:1 Pags 29 of 313 Revision 2, Change 0 TABLE 4.11 1 (Continued) TABLE NOTATION ! i b
- Prior to sampling Reactor Coolant Waste and Miscellaneous Waste for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
- The principal gamma emitters for which the LLD control applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137 and Ce-141. 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 Annual Radioactive Effluent Release Report pursuant to Technical Specification - Administrative Controls. -
d
; A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is .
proportional to the quantity of liquid waste discharged in which the method of -- sampling employed results in a specimen that is representative of the liquids released. " 5
- )
P
.-m,...e,, +*.e, % -
.-.c.,,,..,m._ :.,-_,,.....,-
Offsit] Dose C:lculation M:nual Page 30 of 313 Revision 2, Change o LIQUID EFFLUENTS: 1 Q2H CONTROLS . . . . r 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited:
- a. During any calendar quarter to less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ, and ,
- b. During any calendar year to less than or equal to 6 mrems to the total body and ,
to less than or equal to 20 mrems to any organ. APPLICABILITY: At all times. ; ACTIOrli
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days 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 REQUIREMENTS 4,11.1.2 Monthly cumulative 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 60 days. 1 O .
~ vw - - -w,, v._,~,-, ,.a~ .-~ --. ,-a--..nn
.____.____________.m .__.m._ __ - . _ . _ _ . _ . _ _ . _ _ _ -
Offsu Dose C:lculation M: null Peps 31 of 313 Revision 2, Change 0 LIQUID EFFLUENTS: O Llauld Radwaste Treatment System CONTROLS 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM shall be used to reduce the ' radioactive materials in liquid wastes prior to their discharge when the calculated doses due to the liquid effluent to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 l
- mrem to any organ in a 92 day period.
^
APPLICABILITY: At alltimes. f i ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 a Special Report that includes the following information:
. 1. Explanation of why liquid radwaste was being discharged without' treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. ACTION (s) taken to restore the Inoperable equipment to OPERABLE status, and
- 3. Summary description of ACTION (s) taken to prevent a recurrence. .
- b. The provisions of Controls 3.0,3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS I I Ill Ill I
- 4.11.1.3 Monthly doses due to liquid releases to UNRESTRICTED AREAS shall be calculated at least once per 60 days in accordance with the methodology and paramet' 4 !. the ODCM.
i 4-O
l i Offut3 Dose C:lculation M:nu:1 Pcg2 32 of 313 i Revision 2, Change 0 (~]/ '\ GASEOUS EFFLUENTS Dose Rate CONTROLS 3.11.2.1 The dose rate due to radioactive materials released in gaseous offluents from the site to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 2) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For lodine 131 and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At alltimes. ACTION: ,
- a. With the dose rate (s) exceeding the above limits, without delay restore the reloese rate to within the above limit (s).
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
q SURVEILLANCE REQUIREMENTS O 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 and all radionuclides in particulate form with half lives greater than 8 days in gaseous offluents shall be determined to be within the above limits in accordance with 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 4.112. p V
Off< Calculation Manual P 313 Reviwa 2. Change 0 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT OF l SAMPLING MIN! MUM ANALYSIS DETECTION (LLD)* GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pCumi) A. Waste Gas P P Principal Gamma Emitters
- 1 x 10' Storage' Tank Each Tank Each Tank (Gaseous Emissions Only)
Grab Sample B. Containment Purge P P Principal Gamma Emitters
- 1 x 10' and Vent Each Tank
- Each Tank * (Gaseous Emissions Only)
Grab Sample C. Main Vent M MO Principal Gamma Emitters
- 1 x 10' l GrabSample (Gaseous Emissions Only)
Continuousf M H-3 1 x 10' Continuous
- W I-131 1 x 10'#
Charcoal Sample' Continuous
- W Principal Gamma Emitters" 1 x to" Particulate (1-131. Others)
Sample' Continuous
- M Gross Alpha 1 x 10-"
Composite l Particulate l Sample l Continuous
- O Sr-89, Sr90 1 x 10~"
Composite Particulate Samp!e l Continuous' Noble Gas Not;8e Gases 1x10* Monitor Gross Geta or Gamma D. Incinerated Oil i P P Principal Gamma Emitters 5 x 10 Each Batch" Each Batch' i l
. i
Offsite Dose Calculation Manual Page 34 of 313 ' Revision 2 Change 0 TABLE 4.11-2 (Continued) YABLE NOTATION a The LLD is defined, for purposes of these controls, 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: 8# LLD = - heVe 2.22 x 10'
- Y e exp (-AAt)
Where: LLD is the "a priori" LOWER LIMIT OF DETECTION as defined above, as microcuries per unit mass or volume, ~~ Sb is the standard deviation of the background counting rate or of the O counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass cr volume, 2.22 x 10' is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, 1is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between sample collection or end of the sample collection period, and time of counting. 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 a posteriori (after the fact) limit for a particular measurement. O
Offsit2 Doso Calcul: tion Manual Page 35 of 313 Revision 2, Change 0
,q TABLE 4.11-2 (Continued)
N.) TABLE NOTATION b The principal gamma emitters for which the LLD control applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. 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 Annual Radioactive Effluent Release Report pursuant to Technical Specification-Administrative Controls. c Sampling and analysis shall also be performed following shutdown, STARTUP, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one haur unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 5. The ratio of the sample flow rate to the sampled stream flow rate shall be known
,f - for the time period covered by each dose or dose rate calculation made in i accordance with Controls 3.11.2.1,3.11.2.2 and 3.11.2.3. -
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler When sampla collection time is less than seven days, the corresponding LLDs may be increased by a proportienal factor. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l 131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the nobk gas monitor shows that effluent activity has not increased more than a factor of 5. f Collect sample and analyze daily for totai Curie content per Technical Specification 3.11.1.2 when the Reactor Coolant System specific activity of Xe-133 is greater than 150 mci /ml. 9 incinerated oil may be discharged via points other than the main vent (e.g., Auxiliary Boiler). Releases shall be accounted for based on pre-release grab sample data. h Samples for incinerated oil releases shall be collected from and representative y of filtered oil in liquid form.
,O
Offsite Dose Calculation M:nual Page 36 of 313 Revision 2, Change 0 _ GASEOUS EFFLUENTS: Dose - Noble Gases CONTROLS 3.11.2.2 The Lir dose due to noble gases released in gaseous effluents to areas at and beyond the SITE SOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation and,
- b. During any calendar year: Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.
APPLICABILITY: At all times. ACTION: .
- 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 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.
'd b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4 4.11.2.2 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days. (V
Offsita Dose Cilculation M:nual P:gs 37 of 313 Revision 2, Change O fm GASEOUS EFFLUENTSI k) Dose -lodine 131 & Radionuclides in Particulate Form CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from lodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 15 mrems to any organ and,
- b. During any calendar year: Less than or equal to 30 mrems to any organ.
- c. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of burning contaminated oil.
APPLICABILIT_Y: At all times, . ACTION:
- a. With the calculated dose from the release of iodine-131 and radionuclides in ^
particulate form with half lives greater than 3 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within r~ 30 days a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective ACTIONS that have been taken to reduce the releases
'(~ and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Monthly cumulative dose contributions for the current calendar quarter and the current calendar year for iodine-131 and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days, p b
Offsite Doso Calcul: tion Manual Page 38 of 313 l Revision 2, Change O GASEOUS EFFLUENTS: Gaseous Radwaste Treatment System CONTROLS 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) exceeds 1.8 mrem to any organ in a 92 day period. APPLICABILITY: At all times, f' ACTION: .
- a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report that includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, a I O the reason for the inoperability, .
- 2. ACTION (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of ACTION (s) taken to prevent a recurrence,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 Monthly doses due to gaseous releases shnll be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM. O
i Offsite Dos] Cricut: tion M:nuti Pcge 39 of 313 Revision 2 Change 0 m TOTAL DOSE
'] CONTROLS 3.11.4 The annual (calendar year) dose or doce commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times. ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2.a,3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and 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 wi, thin 30 days 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 20A05c, 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 (o)
\#
also describe levels of radiation and concentrations 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.
gURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2,4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and outside 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 Control 3.11.4.a. J l
- Offsite Dose Calculati:n M:nual Pag)40 of 313
- Revision 2, Change 0 !
RADIOLOGICAL ENVIRONMENTAL MONITORING: __
~
PROGRAM CONTROLS-i i . . .... 3.12.1 The radiological environmental monitoring program shall be conducted as specified in
- Table 3.12 0 APPLICABILITY: At all times.
ACTION:-
- a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification Administrative' Controls, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission within 30 days after receiving the sample analysis a Special Report that identifies the cause(s) for exceeding the limit (s) m .,
and defines the corrective ACTIONS 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 Controls 3.11.1.2,3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12 2 are detected in the sample - i this report shall be submitted if: concentration (1) concentration (2) + .> 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 is equal to or greater than the calendar year limits of Controls 3.11.1.2,3.11.2.2 and 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. /J The methodology and parameters used to estimate the potential annual dose to a MEMBER OF
- THE PUBLIC shall be Indicated in this report.
f
_ _ y l I 4 Offsita Dose Calculati:n Manu11 - p:ge 41 of 313' l Revision 2, Change 0
]
- c. With fresh leafy vegetable samples unavailable from one or more of the sample
> O locations rc auired by Table 3.121, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable - may than_be deleted from the monitoring program. Pursuant to Control 6.6.2, identify the cause of the unavailability of samples and identify the new location (s) for obtaining the replacement samples in the next Annual Radiological Environmental Operating Report.
- d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS - 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to , Table 3.121 from the specific locations given in the table and figure (s) in the ODCM, and shall -
- be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities
- . required by Table 4.121.
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Off JRevi
. Calculation Manual.'
, Change 0- (- P 313 TABLE 3.12-1 i
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY-AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
- 1. DIRECT RADIATION
- 23 routine monitoring stations (DR1 - DR23) At least Quarteriy - Gamma dose atleast either with two or more dosimeters or with one quarterly.
instn: ment for measuring and recording dose rate continuously, placed as follows:
- j. an inner ring of stations, one in each .
. meteorological sector in the general area -
of the SITE BOUNDARY (DR1 - DR09)[ > an outer ring of stations, one in each 1 meteorological sector in the 6- to 8-km ; i range from the site (DR10 - DR18); the remaining stations (DR19 - DR23) to be placed in specialinterest areas such as population centers, nearby residences, schools, and in 1 area to serve as a control station.
.i b
3
. I -
i i
Off Calculation Manual P 313 Revi 2. Change 0 TABLE 3.12-1 (Continued) L RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM a EXPOSURE PATHWAY- NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY: AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS L
- 2. AIRBORNE Radiciodine and Samples from 5 locations (A1-AS): Continuous sampler operation with - Radiciodine Canister Particulates sample collection weekly, or more I-131 analysis weekly :
3 samples'(A1-A3) from close to the 3 frequently if required by dust loading. i SITE BOUNDARY locations, in different Particulate Samplet sectors of the highest calculated annual Gross beta - average ground-level D/O.' radioactivity analysis i folicwing filter 1 sample (A4) from the vicinity of a change;* Gamma isotopc d community having the highest analysis of composite j calculated annual average grot.nd-level (by location) i D/O. quarterly 1 sample (A5) from a control location, as
- for example 15-30 km distant and in the '
least prevalent wind direction. 'j i t 1 4 e 4
Off R2v e Calculation Manual 2.ChangeO V) ( Pag f313 TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY. AND!OR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
- 3. WATERBORNE
- a. Surface 1 sample at intake area (Wa1) COMPOSITE SAMPLE over 1-month GAMMA ISOTOPIC 1 sample at discharge area (Wa2) period
- ANALYSIS
- monthly.
Composite for tritium analysis quarterfy.
- b. Sed; ment from 1 sample from downstream area with existing Semiannually GAMMA ISOTOPIC shoreline d or potential recreational value (Wb1) ANALYSIS semiannually.
L 9
O Calculation Manual '( P
-'# 313 Rev195h 2. Change 0 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND Ti1ME AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COI I FCTION FREQUENCY - OF ANALYSIS
- 4. INGESTION
- a. Fish and 3 samples of commercially and/or Sample in season, or semiannually if GAMMA ISOTOPIC Invertebrates recreationally important species (2 fish they are not seasonal. ANALYSIS' m edible '
species and 1 invertebrate species) in vicinity portions.- of plant discharge area (la1-la3). 3 samples of same species in areas not influenced by plant dis:,harge (la4-la6).
- b. Food Products ' Samples of 3 different kinds of broad leaf Monthly during growing season. Gamma isotopic' and I-vegetation grown near the SITE BOUNDARY 131 analysis.
at 2 different locations of highest predicted annual average ground level D/Q (1b1-1b6). ' 1 sample of each of the similar broad leaf Monthly during growing season. Gamma isotopicd and l-vegetation grown 15 30 km distant in the least 131 analysis. prevalent wind direction (Ib7-Ib9). ' i r l l l l I l
+
I-
Offsit) Dose C:lcut tion M:nual Pag) 46 of 313 1 Revision 2, Change 0 1
- TABLE 3.12-1 (Continued) v TABLE NOTATION a
The code in parenthesis, e.g., DR1, A1, defines generic sample locations in this , control that can be used to identify the specific locations in the map (s) and table in the ODCM. Specific parameters of distance and direction sector from the central point between the two containment buildings and additional description where pertinent, is provided for each sample location in Table 3.12-1, and 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 requ red sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailabi!ity, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment
- malfunction, effort shall be made to complete corrcctive ACTION prior to the end l of the next sampling period. All deviations from the sampling schedule shall be
! documented in the Annual Radiological Environmental Operating Report -- ! pursuant to Technical Specification-Administrative Controls. 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 - l suitable alternative media and locations may be chosen for the particular j pathway in question and appropriate substitutions made within 30 days in the l radiological environmental monitoring program. Pursuant to Technical Specification-Administrative Controls, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining samples l in the next Annual Radiological Environmental Operating Report and also L include in the report a revised figure (s) and table for the ODCM reflecting the new location (s). i l l v! i-
Offsit) Dose Cciculation Manual Ptge 47 of 313 I Revision 2, Change O n TABLE 3.12-1 (Continued) () TABLE NOTATION b 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. The frequency of analysis or readout for TLD Systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. Due to the geographical limitations,9 sectors are monitored around the Calvert Cliffs Nuclear Power Plant. 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 ten times the yearly mean of control samples, GAMMA ISOTOPIC ANALYSIS shall be performed on the individual samples. GAMMA ISOTOPIC ANALYSIS means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility. A COMPOSITE SAMPLE is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program, COMPOSITE SAMPLE aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
- f. Exception to these locations is in the South Sector where DR7, A1,1b4, ib5, and 1b6 are located approximately 0.7 km from the release point. This location is conservative with respect to the site boundary, which is located approximately 2.1 km from the release point.
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( Dose Calculation Manual - Fio.,;on 2, Change 0 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE FISH & INVERTEBRATES MILK FOOD PRODUCTS WATER OR GASES (pCi/M') (pCilkg, wet) (pCi/I) (pCi/kg, wet) ANALYSIS (pCili) H-3 20,000" 1,000 30,000 Mn-54 Fe-59 400 10.000 1,000 30,000 Co-58 300 10,000 Co-60 300 20,000 Zn-65 Zr-Nb-95 400 0.9 3 100 1-131 2 10 1,000 60 1,000 Cs-134 30 20 2,000 70 2,000 Cs-137 50 200 300 Ba-La-140
" For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 l
l pCill may be used. 1 \ I
Page 49 of 3 Offs se Calculation Manual Revih 2, Change 0 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS" LOWER LIMIT OF DETECTION (LLDT FISH & INVERTEBRATES MILK FOOD PRODUCTS SEDIMENT WATER AIRBORNE PAR 1lCULATE OR GASES (pC6/M') (pCilkg, wet) (pCill) (pCilkg, wet) (pCi/kg do ) ANALYSIS (pCill) Gross Beta 4 0.01 H-3 2,000" Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 d 0.07 1 60 l-131 1 150 15 0.05 130 15 60 Cs-134 180 0.06 150 18 80 Cs-137 18 15 Ba-La-140 15
" If no drinking water pathway exists, a value of 3000 pCill may be used.
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Offsit3 Dose Cdculati:n M: null Page 50 of 313
- Revision 2, Change 0 :
A TABLE 4.12-1 (Cor.t!riued) U
' TABLE NOTATION This 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 5 the Annual Radiological Environmental Operating Report pursuant to Control 6.6.2. , b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. The LLD is defined, for purposes of these controls, as the smallest concerjtration 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:
y - 4.66 s LLD = Ee Ve 2.22 . Y e exp(-M t) Where: LLD is the "A priori" LOWER LIMIT OF DETECTION as defined above, an picocuries per unit mass or volume, sois the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute,
- E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and !
v'(.T h ne -,
Orfsite Dose Calcul: tion Minu:1 Page 51 of 313 Revision 2, Change 0 TABLE 4.121_ (Continued) TABLE NOTATION
-- At for anvironmental samples is the elapsed time between cample collection, or end of the sample collection period, and time of counting.
1 Typical values of E, V, Y and At should be used in the calculation.
~
lt should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capabliity of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances - may render these LLDs unachievable. In such cases, the contributing factors-shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification-Administrative Controls. LLD for drinking water samples. If no drinking water pathway exists, the LLD of GAMMA ISOTOPIC ANALYSIS may be used. O . 4 h a i e
Ofisite Dose C:lculation M:nu:1 Pag) 52 of 313 Revision 2 Change 0 ,q RADIOLOGICAL ENVIRONMENTAL MONITORING: LAND USE CENSUS CONTROLS - 3.12.2 A land use census shall be conducted and shallidentify within a distance of 8 km (5 miles), the location in each of the 9 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden' of greater than 50 m* (500 ft') proriucing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in , each of the 9 meteorological sectors of all milk animals and all gardens of greater than 50 m2 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, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Technical Specification or Technical Specification Admhiistrative Controls.
- b. With a land use census identifying a location (s) that yields a calculated dose or n dose commitment (via the same exposure pathway) 20 percent greater than at a I
) location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) te 'he radiological environmental monitoring program within 30 days. The mampling location (s), excluding the control station location, 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 Technical Specification-Administrative Controls, identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the ODCM reflecting the now location (s).
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVElLLANCE REQUIREMENTS 4,12.2 . The land census shall be conducted during the growing season at least once per 12 months using that information thot 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 Technical Specification Administrative Controls. Broad Isaf vegetation sampling of at least three different kinds of vegetation may be performed
^ at the SITE BOUNDARY m each of two different direction sectors with the highest predicted 3
j D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.
-._ _.4._,..__ . . _ , _ . _ _ . _ . . ._ .__ _ . . _ . . . _ . _ _ . . _ _
+
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L Offsite Dose C:lculation Manu:1 ' Pcgn 53 of 313 - -l Revision 2, Change 0 -- l I RADIOLOGICAL ENVIRONMENTAL MONITORING: O- INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3? Analyses shall be performed on all radioactive materials, t,trpr2ied as part of m ; interlsboratory Comparison Program that has been approved by the Comn lssion, that _ _1 correspond to samples required by Table 3.12-1. [ APPLICABILITY: . At all t!mes. , l
' 6CTION:
- a. With ana!yses 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 Technical Specification - Administrative Controls,
. b. ' The provisions of Controls 3.0.3 and 3.0.4 are not applicable, SURVEILLANCE REQUIREMENTS lll . . . . . . . . .
4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. 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 Technical , O Specification Administrative Coritrotsc - 5 !O __.x _
l Offsit) Doso C:lculation M:nu:1 Page 54 of 313 Rev!sion 2 Change O ( PART 5.0 : CALCULATIONAL METHODOLOGIES RADIOACTIVE LIQUID EFFLUENTS BELEASE PATHWAYS IBS2))
- 1. Introduction a) Radioactive liquid waste generated as a result of operating the Calvert Cliffs Nuclear Power Plant (CCNPP) may be released to the '
Chesapeake Bay'. b) There are four pathways by which all waste water, non-radioactive and radioactive, may be discharged from the site to the bay: (1) Outfall 001, (2) Outfall 002, . (3) Outfall 003, (4) Outfall 004, c) A diagram which shows the location of eacn outfall is included ac Attachment 1.
- 2. Outfall 001 a) Water from the Chesapeake Bay is pumped through the condensers and is discharged to the Chesapeake Bay through the circulating water discharge conduits, known as outfall 001, b) The liquid radioactive waste is mixed with and diluted by the circulating water prior to exiting the discharge conduit, c, The circulating water discharge coriduit extends 850 feet into the chesapeake bay, d) The circulating water discharge conduit may accept liquid radioactive waste from various sources. Sources which may contribute radioactive material to the circulating water discharge conduit are tabulated in Attachment 2.
1 Outfalls 002,003, and 004 a) There are three other potential pathways for the release of radioactive liquids to the bay. These pathways are designated outfall 002, outfall 003, and outfall 004. The federal controls and administrative limits associated with the release of radioactive materials from CCNPP are discussed elsewhere in this document.
i l Offsit] Dose Calculation M:nual Page 55 of 313 Revision 2, Change 0 b) Sources which could potentially contribute radioactive rnaterial to each of / ') these outfalls are tabulated in Attachment 3. G c) No radioactive materials are expected to be discharged from outfall 002 unless there is a primary to secondary leak, or unless there is an unforeseen and catastrophic failure of a condensate storage tank (CST). d) No radioactive materials are expected to be released from outfalls 003 or 004 unless there is an unforeseen and catastrophic failure of a refueling water tank (RWT).
- 4. Unmonitored release paths not shown on Attachment 3 should be evaluated -
and added to the ODCM as necessary.
- 5. Safety evaluations have been conducted for operating the following systems after they have become contaminated:
a) component cooling water system (1) In accordance with applicable safety evaluations (Ref. 22); . continued operation of this system is allowed as long as the concentration of radionuclides in the component cooling water system is less than 3,000 MPCs. b) plant heating system A (1) In accordance with applicable safety evaluations (Ref. 24 and ()~ Ref. 28), continued operation of this system is allowed as long as the concentration of radionuclides in the plant heating system is less than 0.3 MPCs. c) auxiliary boiler system (1) In accordance with applicable safety evaluations (Ref. 27 and Ref. 30) continued operation of this system is allowed as long as the concentration of radionuclides in the auxiliary boiler steam drum is less than 96 MPCs. d) demineralized water system (1) In accordance v4th applicable safety evaluations (Ref. 25 and Ref. 31) continued operation of this system is allowed as long as the concentration of radionuclides in the demineralized water system is less than 0.3 MPCs. e) service water system (1) In accordance with applicable safety evaluations (Ref. 26 and Ref. 32), continued operation of this system is allowed as long as the concentration of radionuclides in the service water system is less than 0.1 MPCs. f) condensate storage tank 'Y
Offsit3 Dose Calculation Manu;l ' Pag 3 56 of 313 Revision 2, Change 0
' In accordance with applicable safety evaluations (Ref. 33),
(1)-
,(qj continued operation of this system is allowed as long as the concentration of radionuclides in the condensate storage tank is less than 1.0 MPCs.
TYPES OF LIQUID RELEASES
- 1. Liquid radwaste discharges have been classified as CONTINUOUS or BATCH as shown on Attachments 2 and 3.
PROCESSING EQUIPMENT
- 1. Simplified Flow Diagram a) An overview of the liquid waste processing system, including major equipment and (normal) flow paths, is outlined on Attachment 4.
b) There is no processing equipment for wastes discharged thrcugh outfalls 002,003, and 004; however, the waste shall be analyzed for radioactivity in accordance with the analysis frequencies contained in approved . CHEMISTRY SECTION procedures.
- 2. Modifications a) Major changes or modifications to the liquid waste processing system shall be reported to the Commission in the Annual Radioactive Effluent '
G Release Report for the time interval in which the modification was l [d l completed (per Technical Specification - Administrative Controls). b) A " major" change or modification includes, but is not limited, to the removal or permanent bypass of any of the following: l (1) degassifier-(2) reactor coolant waste receiver tank (3) reactor coolant waste monitor tank l (4) letdown filter
-(5) reactor coolant waste ion exchanger i (6) miscellaneous waste ion exchanger L
(7) miscellaneous waste filter (8) miscellaneous waste receiver tank (9) miscellaneous waste monitor tank-(10) evaporator
; 3. Detailed Description .
Offsite Dose Calcul: tion Manual . Page 57 of 313 Revision 2, Change 0 - a) A detailed description of the liquid waste processing system is beyond' the ? cope of the ODCM. b) For rnore information on the Miscellaneous Liquid Waste Processing System see FSAR and System Description Number 14D, " Miscellaneous-Liquid Waste Processing System Description." c) For more information on the Reactor Coolant Waste Processing System see System Description Number 14B, " Reactor Coolant Waste Processing System Description." d) For more information see the Updated Final Safety Analysis Report. - Chapter 11 " Waste Processing And Radiation Protection." LIQUID EFFLUENT RADIATION MONITOR ALARM AND TRIP SETPOINTS
- 1. Liquid Waste Discharge Radiation Monitor (0 RE-2201) a) General description (1) number of radiation elements: one (2) type of radiation element:in-line scintillation detector (3) output: analog (4) radiation indicator; 0-RI-2201 (5) units for radiation indicator: counts per minute (6) supplier: Westinghouse J
b) Functions of 0-RE-2201 (1) continuously measure the activity contained in liquid waste discharge line (Control 3.3.3.10) (2) continuously indicate (via 0-RI-2201) the activity of liquids contained in liquid waste discharge line (Control 3.3.3.10) (3) alarm (via 0-RI-2201) prior to exceeding 10 CFR 20, Appendix B, Table ll, Column 2 limits (per Control 3.11.1.1) (4) automatically terminate discharges from the liquid waste processing system by closing the discharge isolation valves
' (MWS-2201-CV, and MWS-2202-CV) whenever the radiation indicator (0-Rl 2201) exceeds the fixed high radiation trip setpoint c)- OPERABILITY of 0-RE-2201 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s)
O (2) . The functions of 0-RE-2201 are listed in paragraph (b) above. 64, . , - - - - - - -
. - . . _ . _ ~ . _ _ .. - - . . .
Offsite Dose C:lculation Manu:1 Page 58 of 313 Revision 2, Chan0e 0
- Monitors equivalent to 0-RE 2201 4 d)
U
~
-(1) There are no equivalent monitors for 0-RE 2201.
e) Radiological effluent controls for 0-RE-2201 (1) Liquid waste discharges via this pathway may continue if any one of the following two conditions are satisfied (per Control 3.3.3.10). > (a) The liquid waste discharge monitor,0-RE 2201, is operable and the alarm and trip setpoint for this monitor is set to ensure the concentrations of radioactive materials - released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table _11, Column 2, or (b) two independent samples are analyzed in accordance with Control 4.11.1.1.1; AND at least two technically l qualified members of the Facility Staff independently verify the release rate calculations; AND two qualified , operators verify the discharge valve line up. f) Surveil!ances for 0-RE 2201 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of 0- l RE-2201 by satisfying the checks, calibrations, and tests listed bc;ow: (a) CHANNEL CHECK within the past 24 hours (b)- SOURCE CHECK prior to each release
-(c) CHANNEL CAllBRATION within the past 18 months 1
(d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 0-RI-2201 (1) There are three radiation alarm setpoints associated with, or otherwise related to; the liquid waste discharge monitor. (a) 0 RI-2201 fixed high radiation alarm and automatic control trip setpoint ~ (b) 0-RI-2201 adjustable plant computer high radiation alarm and manual control trip setpoint (c) 0-RI-2201 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will O refer to these setpoints as follows:
' - %..) _
~. - - , _ - - _ _ , _ _ _ ., , - . - < - . _ , _ , .-
Offsit3 Dose C:lculati:n M;nual - Page 59 of 313 Revision 2, Change 0. (a) The 0-Rl 2201 fixed high radiation alarm and automatic - > control trip setpoint will be referred to as the fixed setpcint. . (b)- - The 0-RI 2201 adjustable plant computer high radiation alarm and manual control trip setpoint will be referred to as the adjustable setpoint. (c) - The 0 Rl 2201 low radiation alarm setpoint will be referred to as the low setpoint. (3) Each of these alarm setpoints is described below. - h) Fixed setpoint for 0 RI 2201 (1) Generalinformation (a) This setpoint is considered to be a fixed setpoint. This setpoint is not adjusted for each release.
~
(b) Whenever the fixed setpoint is exceeded, discharges from the liquid waste processing system will be automatically suspended. (c) The fixed setpoint corresponds to the maximum F concentration of radionuclides allowed in liquid waste discharged from the liquid waste processing system. (d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. (e) The CCNPP Alarm Manual refers to this alarm and trip setpoint as the 0 RI 2201 Liquid Waste Discharge High Alarm. (f) The fixed setpoint is integral to the liquid release discharge monitor, as purchased from the supplier. (g) The fixed setpoint is administratively controlled by EN 100. , (h) The fixed setpoint shall be calculated as described below'. (2) Calculating the fixed setpoint for 0-RI-2201 (a) The fixed alarm and trip setpoint for 0-RI-2201 shall be calculated as follows:
\ -'
4
. Per Control 3.3.3.10. 'l
*q g- - - -
.my y-
, - ~
=
Offsite Dose Calculation M:nual Page 60 cf 313 Revision 2, Change 0
'(^ FIXED ALARM AND _ TRIP SETPOINT FOR 0-RI 220.
Sn, - S K.e(( Fe / F ) % [( Au )( ei)] + Bkg } Eq,1 L' Sg = the fixed alarm and trip setpoint for 0-RI 2201 (cpm) Kg = - a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20 MPC limit (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed - setpoint is always less than or equal to the limits of 10 CFR 20. A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC. A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs. It is recommended that a safety f:ctor of 0.5 be used for calculating the fixed . setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The use of a " safety margin"is in accordance with the provisions of NUREG-0133, -- section 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid p . release limit of 10 CFR Part 20 is not exceeded." _ This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint. Fe = - the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate. The dilution water flow ate shall be calculated in accordance with equation 2L. V' This formula has been derived from NUREG-0133, Addendum, page AA 1.
+
- + ~ . -- .- - -. - -.
Offsite Dose Chiculation Manual Pag;61 cf 313 Revision 2, Change 0 fl DlLUTION WATER FLOW RATE
'Q h = Fe, + F., + F. Eq.2L Fm = the minimum circulating water system flow rate necessary to conduct liquid releases A m!nimum of two circulating water pumps (one circulating water pump per conduit -
accepting radwaste) shall be operable when discharging liquid radwaste - via this monitor - to outfall 001. Additional circulating water pumps may be required as specified in approved Chemistry Procedures. If a release of liquid radwaste is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, then the release shall not be allowed until a new setpoint has been calculated and entered into 0-RI-2201, or otherwise comply with the ACTION requirements of Control 3.3.3,10. l F. = the minimum salt watcr system flow rate necessary to release liquid radwaste i If the minimum salt water flow rate available for liquid releases _is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate -- of 0 gpm should be used when calculating the fixed setpoint. O If a release of liquid radwaste is to be conducted using less than the minimum salt V water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 0-RI 2201, or otherwise comply with the ACTION requirements of Control 3.3.3.10. Fu = maximum undiluted radwaste flow rate (gpm) Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and S. Since the flow rate of undiluted liquid waste (120 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the flow rate of undiluted liquid waste need not be considered when calculating the ' dilution water flow rate. Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required-for the flow measuring device (0-FE-2199) in the effluent line-to verify compliance with Control 3.3.3.10. An it
= specific activity limit for the release of radionuclide, I, to UNRESTRICTED AREAS (calculated in eccordance.with 10 CFR 20, Appendix B, Table ll, Note 1 as described below; microcuries per milliliter).
' in order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, I, chosen for calculating the fixed setpoint should correspond to those q DOMINANT and LESS DOMINANT RADIONUCLIDES found in TYPICAL Q RADWASTE RELEASES from CCNPP.
l
Offsite Dot.c Calculation Manual Page 62 of 313 Revision 2 Change 0 Attachmant 5 provides further guidance for determining the identity of those O radionuclidos, i, to be used to calculate a fixed setpoint. Values for A,tn shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the collective total of all LESS DOMINANT RADIONUCLIDES. SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE I Aetn = ( f, ) ( Atta ) Eq.3L , f, = a fraction which represents the relative activity contribution of nuclide i to the average total effluent activity (unitiess) The average 'otal effluent activity does not include tritium or dissolved and entrained noble gases. This value may be obtained using the guidance provided on Attachment 5. - . A g tn = the sum of she total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3)
~
This value corresponds to 1 MPC. Artn shall be calculated as shown below. TOTAL SPECIFIC ACTIVITY EQUlVALENT TO 1 MPC E [ ( f, ) ( Attn ) / Aiu ) = 1 Eq.4L' A iu a the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B. Table ll, Column 2 (microcuries/cm3) For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table 11, Column 2. Fct each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for A,u (per 10 CFR 20, Appendix B, Note 2).
=
1 the MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, TaL'e 11, Note 1. e, = absolute detector efficiency for nuclide, I(cpm /microcuries per milliliter) O' This formula has been derived from 10 CFR 20, Table 11, Notes 1,2, and 3.
offsita Dose C:lcul: tion M:nu:1 Pcg2 63 et 313 R: vision 2, Change 0 f~ The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background prior to initiating the liquid release (cpm) Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. (3) Documenting the fixed setpoint for 0 RI 2201 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the parameters shall be documented in accordance with EN 1 100. (4) Changing the fixed setpoint for 0 RI 2201 (a) If the fixed setpoint calculated in accordance with equation il exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed alarm and trip setpoint for 0-RI 2201 may be established at values lower than the maximum allowable setpoint, if desired. - (c) A setpoint change should be initiated whenever any of the O parameters identified in equation 1L have changed.
\_)
(d) The fixed setpoint should not be changed unless one of the following occurs i) the relative activity' of any radionuclide in TYPICAL LIQUID EFFLUENTS, ef has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the minimum dilution water flow rate is not available for a liquid release, iii) the values list-1in 10 CFR 20 Table 11, column 2 have changed, iv) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or v) the monitor is not conservative in its function (see
" Functions of 0-RE 2201" earlier in this section).
(e) EN 1 100 contains the administrative controls associated with l changing and approving the fixed setpoint. O 1 As detemilned in accordance with Attachment 5.
. Offsit) Dose Calcul: tion M:nu:1 Pcge 64 of 313 flevision 2. Chan0e O p i) The adjustable alarm and trip setpoint for 0 RI 2201 (1) Generalinformation (a) This setpoint is an adjustable setpoint. The adjustable setpoint is calculated and adjusted prior to each release from the liquid waste processing system. (b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Control l 4.11.1.1.1). (c) Whenever the adjustable setpoint is exceeded, discharges from the liquid waste processing system will be manually suspended. (d) See Ol.17C, " Reactor Coolant Waste Processing System", or OI 17D,
- Miscellaneous Waste Processing System," for a futilist of operator ACTIONS taken in response to this alarm.
(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in -- discharges from the liquid waste processing system. O (f) The value for the adjustable setpoint is recorded on the V I, quid release permit in accordance with CHEMISTRY SECTION procedures. (g) This alarm is not integral to the liquid release discharge monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer, which monitors output from 0 RI-2201, and provides an alarm to plant operators when the adjustable alarm and trip setpoint has been exceeded. (i) A value for the adjustable alarm and trip setpoint shall be calculated prior to each release as shown below. (2) Calculating the adjustable setpoint for 0-RI 2201 (a) The adjustable setpoint is based on the specific activities of the radionuclides in the undiluted liquid waste (as dotarmined by radiochemical analysis per Control l 4.11.1.1.1), and shall be calculated as shown below. O(3 I
offsite Dose Calculation Manual P ge 65 of 313 R: vision 2, Change O ADJUSTABLE SETPOINT FOR 0-RI 2201 S.g 5, 1.60 ( % ( Aw ) { ei ) + Bkg ] Eq.6L Sg a the adjustable alarm and trip setpoint for 0 RI 2201 (cpm) 1,50 = a constant, actually a safety factor, which allows for fluctuations in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to - (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, or (5) errors associated with monitor calibrations.' A iu = specific activity of radionuclide, I, in the undiluted waste stream (microcuries per milliliter) e, s absoluto detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. -- Bkg = an approximation of the detector background (cpm) (3) Documenting the adjustable alarm and trip setpoint for 0 RI 2201 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with approved CHEMISTRY SECTION procedures (e g., CP 601), I (4) Changing the adjustable alarm and trip setpoint for 0-RI 2201 (a) In all cases, the adjustable alarm setpoint shall be set to a value which is less than or equal to the fixed setpoint. (b) If the adjustable alarm and trip setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (c) CHEMISTRY SECTION procedures (e.g., CP-601) contain administrative controls associated with calculating and approving an adjustable setpoint. O ' The " analysis enors" and " calibration errors" refer to errors which are within established quality b assurance and quallty control limits.
i Offstte Dose C:lculation M: null Pag)66 of 313 R: vision 2. Ch:nge 0 (d) Whenever 0 RI 2201 is operable, the calculated value for , - O the adjustable setpoint shall be entered into the plant computar prior to each release from the liquid waste processing system. (e) Plant Operating Instructions (e g.,0117C and 0117D) contain administrative controls associated with entering the adjustable sotpoint into the plant computer, j j) The low radiation alami for 0-RI 2201 (1) This alarm is integral to the liquid release discharge monitor, as - purchased from the supplier. 1 (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. (3) The low alarm setpoint may be used to determine the OPERABILITY of this monitor (per Control 4.3.3.10, CHANNEL l FUNCTIONAL TEST). - (4) The alarm generated by the low alarm setpoint may be used to terminate a release in the event 0-RE 2201 fails (i.e., downscale
- failure or circuit failure) in accordance with Control 4.3.3.10. ..
(5) The low alarm setpoint calculations are not described in the p ODCM. (6) Changes to the low alarm setpoint are controlled by EN-1 100.
- 2. Sicam Generator Blowdown Effluent Radiation Monitors (1/2 RE 4095) a) General description of 1/2 RE-4095 (1) number of radiation elements: one per unit (2) Type of radiation elements: in line scintillation detectors (3) output: analog (4) Designations for radiation indicators (a) 1 RI-4095 (b) 2-RI-4095 (5) units for radiation indicator; counts per minute (6)- supplier: Westinghouse j b) Functions of 1/2-RE-4095 (1) continuously measure the activity contained in steam generator blowdown effluent line (Control 3.3.3.10)
-.e m-.,.- 9..a.y_... r e -+---w -- - -e' ;%a-wT"
Offsite Dose Calculation M:nu:1 Page 67 of 313 : Revision 2, Change 0 (2) continuously indicate (/la 1/2 RI 4095) the activity of liquids (6 s ~
) contained in the steam generator blowdown effluent line (Control 3.3.3.10) l '
(3) alarm (via 1/2 Rl-4095) prior to uceeding 10 CFR 20, Appendix B, Table 11, Column 2 limits (per Control 3.11,1,1) (Nate: A l technical evaluation shall be conducted to ensure compliance with UFSAR 10.2.2.4.) (4) automatically terminate steam generator blowdown releases to UNRESTRICTED AREAS when the radiation Indicator (1/2 RI-4095) exceeds the fixed alarm setpoint - c) OPERABILITY of 1/2 RE 4095 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s), (2). The functions of this monitor are listed in section (b) above. (3) It should be noted that if the steam generator blowdown processing system heat exchangers are bypassed, it is possible for blowdown flow to bypass 1/2 RE 4095. If blowdown flow is allowed to bypass 1/2 RE 4095, the minimum channels -- OPERABILITY requirement of Control 3.3.3.10 may not be l satisfied. d) Monitors equivalent to 1/2 RE 4095 - (1) 1/2 RE 4014 is normally considered the PRIMARY MONITOR for measuring activity released via the steam generator blowdown processing system, and 1/2 RE 4095 is normally considered the BACKUP MONITOR for measuring activity released via tho steam generator blowdown processing system. (2) in the event PRIMARY MONITOR (1/2 RE-4014)is inoperable or otherwise unavailable, the BACKUP MONITOR (1/2 RE-4095)is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR. (3) 1/2 RE-4014, Steam Generator Blowdown Tank Radiation Monitor is considered to be " equivalent" monitor to 1/2 RE 4095 as specified below. (4) 1/2 RE 4014, Steam Generator Blowdown Tank Radiation
, . Monitor, is able to perform measurement, Indication, alarm, and isolation functions (see " Functions of 1/2 RE-4014" earlier in this
. section) which limit the concentration of radioactive materials released to UNRESTRICTED AREAS in accordance with Control l 3,11.1,1 as long as the following conditions are satisfied: ,
(a) the OPERABILITY of 1/2 RE-4014 must be demonstrated in accordance with Control 4.3.3.10, Table 3.3.13(1b), and
,, ~ , . , . _ . . _ . , , , . . . . , , . , . _ , , _ . . . . . - . m.,- , , , .m .. . -- , , . . . . . . . , . . _ - - . . , , . , . . , , . , , , . - ,
Offsit] Dor,o C:lcut: tion M:nu:1 Pag 2 66 of 313 R; vision 2, Chin 0-) O s (b) the blowdown ion exchangers are isolated (or the [b
\
decontamination factors for all radionuclides are verified to be greater than or equal to one for the duration of the release), and (c) the specific activities of radionuclides in the blowdown tank radiation monitor are representative of the activities of the radionuclides in the blowdown effluent line, e) Radiological effluent controls for 1/2 RE-4095 (1) Steam generator blowdown releases via this pathway may continue if any one of the following two conditions are satisfied (por Control 3.3.3.10): (a) A steam generator blowdown monitor (either 1/2 RE 4095 or 1/2 RE 4014)is OPERABLE (see
- OPERABILITY of 1/2 RE 4095"; and
- OPERABILITY of 1/2 RE-4014" earlier in this section) AND the alarm and trip setpoint for this monitor is set to ensure the concentrations of -
radioactive materials released in liquid offluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2, or -- (b) a grab sample is collected AND analyzed in accordance with the provisions described below: V i) analysis shall determine EITHER the gross gamma activity or gross beta activity of the sample li) sampling and analysis shall be completed at least once per 12 hours if the specific activity of the steam generator blowdown is greater than 0.01 microcuries per gram LODINE DOSE EQUIVALENT iii) sampling and analysis shall be completed at least once por 48 hours if the specific activity of the steam generator blowdown is less than or equal to 0.01 microcuries per gram IODINE DOSE EQUIVALENT iv) the LOWER LIMITS OF DETECTION (LLDs) for the gross gamma and/or gross beta analyses are in accordance with the LLDs of Control 4.11.1.1.1 f) Surveillances for 1/2 RE-4095 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of l 1/2 RE-4095 by satisfying the checks, calibrations, and tests listed below ( (3,/ (a) CHANNEL CHECK within the past 24 hours
Off t.Ite Doso C:lculation M:nu:1 Page 69 of 313 Revision 2 Change 0 p (b) SOURCE CHECK prior to each release (c) CHANNEL CAllBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1/2 RI-4095 (1) There are three radiation alarm setpoints associated with the Steam Generator Blowdown Effluent Radiation Monitor. (a) 1/2 RI-4095 fixed high radiation alarm and automatic controf trip setpoint (b) 1/2 RI-4095 adjustable plant computer high radiation alami and manual control trip setpoint (c) 1/2 Rl-4095 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows: (a) The 1/2 RI 4095 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed O setpoint. C * (b) The 1/2 RI 4095 adjustable plant computer high radiation alarm and manual control trip setpoint will be referred to as the adjustable setpoint. (c) The 1/2 RI 4095 low radiation alarm setpoint will be referred to as the low setpoint. (3) Each of these alarm setpoints are described below. h) The fixed setpoint for 1/2 RI-4095 (1) Generalinformation (a) This setpoint is considered to be a fixed alarm and trip setpoint. The fixed setpoint is not adjusted for each release. (b) Whenever the fixed setpoint is exceeded, discharges from the steam generator blowdown processing system to UNRESTRICTED AREAS will be automatically suspended. I
Off:lte Dose C:lcut: tion M:nu:1 Pcge 70 of 313 Revision 2, Change 0 3 (c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the steam generator blowdown processing system.' (d) The current value for the fixed setpo!nt is specified in the CCNPP Alarm Manual. (e) The CCNPP Alarm Manual refers to this alarm and trip setpoint as the 1/2 RI 4095 Steam Generator Blowdown Recovery High Alarm. (f) This setpoint is integral to the steam generator blowdown discharge monitor, as purchased from the manufacturer. (g) The fixed setpoint is administratively controlled by EN 1-100. (h) The fixed alarm and trip se' point shall be calculated as described below". . (2) Calculating the fixed setpoint for 1/2 RI 4095 (a) The fixed alarm setpoint for 1/2 RI-4095 shall be -- calculated in accordance with equation 1L. FIXED SETPOINT FOR 1/2 RI 4095 . Sn, 5 Kg { ( Fa/Fu ) E [( Au )( ei)) + Bkg ) Eq.1L 8 Sr, = the fixed alarm and trip setpoint for 1/2 RI 4095 (cpm) Kg = a constant, actually a safety factor, which is the ratio of the CCNJP activity limit to the 10 CFR 20 MPC limit (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20. A safety f actor of 1.00 will yield a fixed setpoint whic.h corresponds to 1.0 MPC. A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs. It is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry, it should be noted that the UFSAR (section 10.2.2.4) states,"the blowdown liquid monitor has an alarm setpoint selected to allow an annual average continuous blowdown past the monitor of 10 s gpm without exceeding one curie discharged per year, excluding tritium." Per Control 3.3.3,10. [V T Equation 1L has been derived from NUREG-0133, Addendum, page AA 1. l
Offsite Dose Calculation M:nual Pcge 71 of 313 l Revision 2, Change 0 ' The use of a " safety margin"is in accordance with the provisions of NUREG 0133, ! 4 section 4.1.1, which states, "The alarm and trip setpoints ... should correr. pond to a , value(s) which represents a safe margin of assurance that the instantaneous liquid ! release limit of 10 CFR Part 20 is not exceeded." This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint. ; t Fd = the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED , AREAS the dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow ratc. ThL dilution water flow rate shall be calculated in accordance with equation 2L. , . DILUTION WATER FLOW RATE -. i F. = F , + F., + F. Eq.2L
- F, = the minimum circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit !
accepting radwaste) shall be operable when discharging liquid radwaste - via this ; monitor to outfall 001. The flow rate of each circulating water pump is 200,000 gaPons per minute. l Additional circulating water pumps may be required as specified in approved CHEMISTRY SECTION procedures, li o release of liquid radwaste from the steam generator blowdown system is to be conoscted using less than minimum circulating water flow rate necessary to conduct > liquid releases, the release shall not be allowed until a new setpoint has been l calculated and entered into 1/2 RI 4095, or otherwise comply with the ACTION requirements of Control 3.3.3.10. F., = the minimum salt water system flow rate necessary to release liquid radwaste if the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate
- of 0 gpm should be used when calculating the fixed setpoint. >
The maximum flow rate for one salt water pump is listed on Attachment 2.
- If a release of liquid radwaste is to be conducted using less than the minimum salt i water flow rate necessary to conduct liquid releases, the release shall not be ,
allowed until a new setpoint has been calculated and entered into 1/2 RI 4095, or otherwise comply with the ACTION requirements of Control 3.3.3,10. ,
l Offsit) Dose C:Icut: tion M:nual Pa0e 72 of 313 ! Revision 2, Change O Fu = maximum undiluted radwaste flow rate (gpm) p)
\'
Values of maximum undiluted radwasta flow rates for various waste streams are tabulated in Attachments 2 and 3. Since the steam generator blowdown flow rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the steam generator blowdown flow rate need not be considered when calculating the dilution water flow rate. Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required-for the flow measuring device in the effluent line-to verify compliance with Control 3.3.3.10. A itn = specific activity limit for the release of radionuclide, I, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table ll, Note 1 as described below; microcuries per milliliter) in order to calculate a meaningful and accurate fired setpoint, the specific radionuclides, I, chosen for calculating the fixed setpoint should correspond to those DOMINANT and LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP. Attachment 5 provides further guidance for determining which radionuclides, I, -- should be used to calculate a fixed setpoint. Values for Aan shall be calculated, as desenbed below, for each DOMINANT (7) ( RADIONUCLlDE and for the collective total of all LESS DOMINANT RADIONUCLlDEs SPECIFIC ACTIVITY LIMIT FOR EACH RADIONUCLIDE i Aan = ( f,)( Ann) Eq.3L f4 = a fraction which represents the relative activity contribution of nuclide i to the average total effluent activity (unitless) The average total effluent activity does not include tritium or dissolved and entrained noble gases. This value may be obtained using the guidance provided on Attachment 5. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.
= the sum of the total specific activities of all radionuclides found in a TYPICAL Ann LIQUID RADWASTE RELEASE (microcuries/cm3) q This value corresponds to 1 MPC.
l
. OffWte Dose Calculation M:nu;l Page 73 of 313 Revision 2 Chan0e 0 Ann shall be calculated as shown below.
O ~ TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC l
% (( fi) ( Ana ) / Au ] = 1 Eq.4L'
= the specific activity limit for radionuclide, I, as obtained from 10 CFR 20, Appendix Au B, Table 11, Column 2 (microcuries/cm3) l I
For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE - EFFLUENTS, use the value from 10 CFR 20,- Appendix B, Table ll, Column 2. l For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E 8 microcuries per milliliter as the value for Au (per 10 CFR 20, Appendix B, Note 2). - =
-1 the MPC limit (MPCs) for UNRESTRICTED AREAS .
1
- This value is based on the MPC limit from 10 CFR 20. Table ll, Note 1. ,
Bkg = an approximation of the detector background (cpm) r Instead of using an approximation of the detector background, a value of 0 cpm : may be used as the detector background if so desired. (3) Documenting the fixed setpoint for 1/2 Rl-4095
- 4 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN 1 100.
(4) Changing the fixed setpoint for 1/2 RI-4095 (a) If the fixed setpoint calculated in accordance with [ equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenever any of the - parameters identified in equation 1L have changed.
- ) '
V - This fomiuta has been uerived from 10 CFR 20. Table 11, Notes 1,2, and 3. p -r e . eh - r--#~ --,--w -
Offsit3 Dose Odcul: tion M: null Pags 74 of 313 l' Revision 2, Change 0 (d) The fixed setpoint should not be changed unless one of I the following occurs: i) the relative activity' of r.ny radionuclide in TYPICAL LIQUID EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, il) the minimum dilution water flow rate is not available for a liquid release, ill) the v6tues listed in 10 CFR 20, Table ll, column 2 i have changed, i iv) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or 4 v) the monitor is not conservailve in its function (see ' Yunctions of 1/2 RE 4095" earlier in this section). . (e) EN 1 100 contains the administrative controls associated l with changing and approving the fixr.sd alarm and trip , setpoint. --
- 1) The adjustable alarm and trip setpoint for 1/2 RI4095
, (1) Generalinformation (a) This setpoint is an adjustable setpoint. The adjustable setpoint is calculated and adjusted prior to each release ! froin the steam generator blowdown processing system. (b) The adjustable setpoint is based on the specific activities ;! of the radionuclides present in the undiluted liquid waste (as dr' ermined by radiochemical analysis per Contrcl l 4.11.1,1.1). (c) Whenever the adjustable setpoint is exceeded, discharges from the steam generator blowdown processing system will be manually suspended. * (d) See Ol 8A for a fulllist of operator actions taken in response to this alarm. (e) The adjustable setpoint corresponds to the maximum
- concentration of radionuclides anticipated or expected in discharges from the steam generator blowdown processing systern ,
i
*O ^
As determined in accordance with Attachment 5.
,. - . . . - - - - - , ,,.,.,mm -
...,,,,_-#,,--,_m---- - --,e. . ., _ , . - - , - - , - - - . - . . - - . -
Offsite Dos 6 Cricul: tion M:nu: P:ge 75 of 313 Revision 2, Change 0 The value for the adjustable setpoint is recorded on the (q! (f) liquid release permit in accordance with CH6MISTRY 1 V SECTiON procedures. I l (0) This alarm is not integral to the steam generator blowdown effluent monitor, es purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 1/2 RI-4095, and provides an alarm to plant operators when the adjustable alarm and trip setpoint has been exceeded, - (i) A value for the adjustable alarm and trip setpoint shall be calculated prior to each release as shown below. (2) Calculating the adjustable setpoint for 1/2 RI 4095 , (a) The adjustable setpoint is based on the specific activities of radionuclides in the undiluted liquid waste (as - determined by radiochemical enalysis per Control l 4,11,1,1,1), and shall be calculated as shown below. ADJUSTADLR SETPOINT FOR 1/2 RI 4095 S.g 5, 1,60 [E ( Aio )( ei) + Bkg ) Eq 6L' . Where, S,4 = the adjustable alarm and trip setpoint for 1/2 RI-4095 (cpm) 1.50 = a constant, actually a safety factor which allows for fluctuation in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates. (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, or (5) errors associated with monitor calibrations.' A,u = specific activity of radionuclide,1, in the undiluted waste stream (microcuries per millikter) e, = absolute detector efficiency for nuclida, I (cpm /microcuries per milliliter) The detector efficiency for each radionuc!ide may be calculated from data collected during calibration of the radiation monitor. p) t V This formula may be derived from NUREG-0133, Addendum, pa00 AA 1. The " analysis errors" and
- calibration errors" refer to errors which are within established quahty assurarice and quality control limits.
I Offsit) Dose C:lcul: tion M: null P:g) 70 of 313 Revision 2, Change 0 ,- Bkg = an approximation of the detector background prior to initiating the liquid release ( (cpm) (3) Documenting the adjustable setpoint,1/2 RI-4095 I (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with approved CHEMISTRY SECTION procedures. (4) Changing the adjustable alarm and trip setpoint for 1/2 Rl 4095 (a) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) In all cases, the adjustable setpoint shall be set to a value which is less thai ' ' equal to the fixed setpoint. + , (c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint. .. (d) Whenever 1/2 RI 4095 is operable, the calculated value p/ ( for the adjustable setpoint shall be entered into the plant computer prior to each release from the steam generator blowdown processing system. (e) Plant Operating Instructions (o g., Ol 8A) contain administrative controls associated with entering the adjustable setpoint in the plant computer. j) The low setpoint for 1/2 RI-4095 (1) This alarm is integral to the steam generator blowdown effluent monitor, as purchased from the manufacturer. (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. - (3) The low alarm setpoint may be used to determine OPERABILITY of this monitor (per Control 4.3.3.10, CHANNEL FUNCTIONAL l TEST). (4) The low alarm setpoint may be used to terminate a release in the event 1/2 RE 4095 fails (i.e., downscale failure or circuit failure). (5) Changes to the low alarm setpoint are controlled by EN 1 100. (6) The ODCM does not address the calculations associated with the low alarm setpoint.
I OffsNe Dose C:lculation M:nual Pcg3 77 of 313 Revision 2. Change 0 l
- 3. Steam Generator Blowdown Tank Radiation Monitors (1/2 RE 4014)
O a) General description of 1/2 RE 4014 (1) number of radiation elements: one per unit ! I (2) . Type of radiation element: off line scintillation detector (3) output: analog f ^ (4) Designations for radiation indicators - (a) 1 RI 4014 f (b) 2 RI 4014 [ (5) units for radiation indicator: counts per minute - (6) supplier: Westinghouso - (7) . A 3 gallon per minute sample is cooled, passed through the detector, and pumped back into the steam generator blowdown tank.
.. i
- b) Functions of 1/2 RE 4014 (1) continuously measure the activity contained in an off line sample of the steam generator blowdown tank (Control 3.3.3.10) *
(2) continuously indicate (via 1/2 Rl 4014) the specific activity in an off line sample of the steam generator blowdown tank (Control l 3.3.3.10) (3) alarm (via 1/2 Rl 4014) prior to exceeding the 10 CFR 20 Appendix B, Table ll, Column 2 limits (per Control 3.11.1.1) l (Note: A technical evaluation shall be conducted to ensure compliance with UFSAR 10.2.2.4.) (4) automatically terminate steam generator blowdown releases to UNRESTRICTED AREAS when the radiation indicator (1/2 RI-4014) exce&ds the fixed alarm setpoint. : c) OPERABILITY of 1/2 RE 4014 (1)- This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s) (2) The functions of this monitor are listed in section (b) above.' m
- . ~ ~ - . - . _ - , . . - . - , . - . . _ . , . _ _ _ . _ _ . _ _ _ _ _ . . - . _ _ . - . . . . - . . - . . . . . . ~ . _ . _ . . . . . . - - - -
Offaib Dose Calculation Manual Pcg3 78 of 313 R: vision 2 Change 0 1 d) Monitors equivalent to 1/2 RE 4014 (1) 1/2 RE-4014 is normally considered the PRIMARY MONITOR for 4 measuring activity released via the steam generator blowdown processing system, and 1/2 RE 4095 is normally considered the BACKUP MONITOR for measuring activity released via the steam generator blowdown processing system, J (2) In the event PRIMARY MONITOR (1/2 RE 4014) is inoperable or otherwise unavailable, the BACKUP MONITOR (1/2 RE 4095)is ! able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR. - I (3) 1/2 RE 4095, Steam Generator Blowdown Effluent Radiation
- Monitur, performs measurement, indication, alarm, and isolation functions equivalent to 1/2 RD4014 (see
- Function of 1/2 RE-4014" earlier in his section), unless 1/2 RE 4095 is bypassed as ,
J described below. - t < 1 ' (4) It should be noted that if the steam generator blowdown + , processing system heat exchangers are bypassed, it is possible for blowdown flow to bypass 1/2 RE 4095 (the steam generator blowdown effluent radiation monitor). If blowdown flow is allowed to bypass 1/2 RE 4095, the minimum channels OPERABILITY -- requirement of Control 3.3.3.10 may not be satisfied (unless 1/2 l RE-4014 is operable). , e) Radiological effluent cuntrols for 1/2 RE 4014 - (1) Steam generator blowdown releases via this pathway may continue if any one of the following two conditions are satisfied ! (per Control 3.3.3.10): , (a) A steam generatar blowdown monitor (either 1/2 RE 4095 or 1/2 RE 4014)is OPERABLE (see " OPERABILITY of 1/2 RE 1095'l and " OPERABILITY of 1/2-RE-4014" earlier in th'.s section) AND the alarm and trip setpoint for this monitor is set to ensure the concentrations of - radioactive materials released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table ll, Column 2, or (b) a grab sample is collected AND analyzed in accordance with the provisions described below: r i I) analysis shall determine EITHER the gross gamme activity or gross beta activity of the sample .
- 11) sampling and analysis shall be completed at least once per 12 hours if the specific activity of the steam generator blowdown is greater than 0.01 O microcuries per gram IODINE DOSE EQUIVALENT
^
i b i
..._,..._......,,,,,_.._...,.-,,_,,.g.~,.. .,,,.m.,r. ..J__,4,,_,,.i..,_ . ,,.r,_,, .,, , , , , , . . - , . , - , , . , , _ - , . . _ , _ , . , - . - , _
OffsHe Dose Calculation Manu 1 Pag)79 of 313 : Revision 2, Change 0 ' lil) sampling and analysis shall be completed at least ; O, once per 48 hours if the specific activity of the steam generator blowdown is less than or equal to i 0.01 microcuries per gram IODINE DOSE EQUIVALENT iv) the LOWER LIMITS OF DETECTION for the gross t gamma and/or gross beta analyses are in accordance with the LLDs of Control 4.11.1.1.1 [ f) Surveillances for 1/2 RE 4014 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of l ' r 1/2 RE 4014 by satisfying the checks, calibrations, and tests . listed below (a) CHANNEL CHECK within the past 24 hours (b) SOURCE CHECK prior to each release (c) CHANNEL CAllDRATION within the past 18 months i (d) _ CHANNEL FUNCTIONAL TEST within the past 6 six months -- g) Setpoints for 1/2 RI-4014 (1) There are three radiation alarm setpoints associated with the * ! Steam Generator Blowdown Tank Radiation Monitor (a) 1/2 RI 4014 fixed high radiation alarm and automatic control trip setpoint (b) 1/2 RI-4014 adjustable plant computer high radiation alarm and manual control trip setpoint (c) 1/2 RI-4014 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows: (a) The 1/2 RI 4014 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint. (b) The 1/2 RI 4014 adjustable plant computer high radiation i alarm and manual control trip setpoint will be referred to as the adjustable setpoint, , (c) The 1/2 RI-4014 low radiation alarm setpoint will be ' referred to as the low setpoint. t (3) Each of these alarms is described below.
1 Offsite Dose C:lculation M:nu:1 - Page 80 of 313 ! R; vision 2 Change 0 h) The fixed alarm and trip setpoint for 1/2 RI 4014 (1) Generallnformation (a) This alarm and trip setpoint is considered to be a fixed setpoint. The fixed setpoint is not adjusted for each ! release. (b) Whenever the fixed setpoint is exceeded, discharges from the steam generator blowdown processing system to : UNRESTRICTED AREAS will be automatically suspended. - (c) The fixed setpoint corresponds to the maximum
- concentration of radionuclides allowed in liquid waste
. discharged from the steam generator blowdown processing system.' (d) The current value for the fixed alarm and trip setpoint is i specified in the CCNPP Alarm Manual. - i (e) The CCNPP Alarm Manual refers to the fixed setpoint as the 1/2 RI 4014 Steam Generator Blowdown High Alarm. (f) The fixed satpoint is integral to the liquid release discharge monitor, as purchased from the manufacturer. (g) The fixed alarm and trip setpoint is administratively - controlled by EN 1 100. (h) The fixed alarm and trip setpoint shall be calculated as described below', (2) Calculating the fixed alarm and trip setpoint for 1/2 RI-4014 (a) The fixed alarm and trip setpoint for 1/2-RI 4014 shall be calculated as follows: It should be noted that the UFSAR (section 10.2.2.4) Mates, "the blowdown liquid monitor has an _; alarm setpoint selected to allow an annual average continuous blowdown past the monitor of 10 ' Opm without exceeding one curie discharged per year, excluding tritium." Os .# Per Control 3.3.3.10.- l a-.~.~. .s.- ,-_- .__.z.___..___._..-_.___.__,_ _. . _ . _ . - _ -
Offsit] Dose Calculation Manu;l Page 81 cf 313 Revision 2, Change 0 (~T FIXED ALARM AND TRIP SETPOINT FOR 1/2 Rl-4014 V; Sn, 5 K.,(( F / F. ) E [( Au ) { ei)] + Bkg ) E q.1 L' Where, Sn, = the fixed alarm and trip setpoint for 1/2 RI-4014 (cpm) Kg = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20 MPC limit (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is etways less than or equal to the limits of 10 CFR 20. A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC. A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 M*Cs. It is recommended that a safety factor of 0.5 be used for calculating the fixed . setpoint, however, other values not to exceed 1.00- may be used as directed by the General Supervisor Chemistry. The use of a " safety margin"is in accordance with the provisions of NUREG 0133 -- SECTION 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded." This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint.
= the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED Fo AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. (~3 Equation 1L has been derived from NUREG-0133, Addendum, page AA 1.
Offsit] Dose CalculatM M:nual Page 82 cf 313 Revision 2, Change 0 /^' DILUTION WATER FLOW RATE i \ l Fe = F., + F., + F , Eq.2L F. = the mini,num circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit accepting radwaste) & hall be operable when discharging liquid radwaste - via this 1 mordter ~ to outfall 001. I l The flow rate of each circulating water pump is 200,000 gallons per minute. Additional circulating water pumps may be required as specified in approved CHEMISTRY SECTION procedures. If a release of liquid radwaste from the steam generator blowdown system is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been . calculated and entered into 1/2 Rl 4014, or otherwir,e comply with the ACTION requirements of Control 313.10. F. = the minimum salt water system flow rate necessary to release liquid radwaste --
!f the minimum salt water flov t rote available for liquid releases is unknown, difficult 3 to predict, or may decrease d atir g a liquid release, a minimum salt water flow rate (d of 0 gpm should be used wheti calculating the fixed setpoint.
- The maximum flow rate for one salt water pump is listed on Attachment 2.
If a release of liquid radwaste is to be conducted using less than the mir,imum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2 RI 4014, r otherwise comply with the ACTION requirements of Control 3,3.3.10. Fu = maximum undiluted radwaste flow rate (gpm) Values of maximum undiluted radwaste flow rates for various waste streams are tabulateo in Attachments 2 and 3. Since the steam generator blowdown ow rate (225 gpm maximum)is insignificant relative to the circulating water flow rate (200,000 gptr per circulating water pump), the steam generator blowdown flow rate need not be considered when calculating the dilution water flow rate. Since the maximum undiluted radwaste flow rete is used for calculat:ng the fixod setpoint, a flow setpoint is not required -for the flow measuring device in the effluent line to verify compliance with Control 3.3.3.10. A,tn = specific activity limit for the release of radionuclide, I, to UNRESTRICTED AREAS _g (calculated in accordance with 10 CFR 20, Appendix E, Table 11, Note 1 as (x / i desenbod below; microcuries por milliliter)
Offsit) Dose C:lculati:n M:nu 1 Pags 83 of 313
. Revision 2 Change 0
. in order to calculate a meaningful and accurate fixed setpoint, the specific 0 radionuclides, I, chosen for calculating the fixed setpoint should correspond to those DOMINANT and LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP.
Attachment 5 provides further guidance for determining which radionuclides, I, should be used to calculate a fixed setpoint. Values for A itn shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the collective total of all LESS DOMINANT RADIONUCLIDES. SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE,i A,t. = ( fi) ( Art. ) Eq.3L f, = a fraction which represents the relative activity contribution of nuclide i to the
~
average total effluent activity (unitiess) . The average total effluent activity does not include tritium or dissolved and entrained noble gases.
'This value may be obtained using the guidance provided on Attachment 5.
Artn = the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3) This value corresponds to 1 MPC. l Calculate the value of A 7tn as shown below. 4 i O
, , , . . - , . . - - , . . - . . , , . . - , . . . . - . , ~ . , . . . , . . , . , - ., . . - - . . . _ - - . . - . ,
__m _ _ _ _ _ _ - . - . ._ _ . _ _ . . _ _ _ . _ . _ _ . _ _ _ _ _ _ _ . _ . i 1
- Offsite Dose Calculation M:nual Peps 84 of 313 i Revision 2, Change 0 l
TO1 AL SPECIFIC ACTIVITY CORRESPONDING TO 1 MP 3 AT THE SITE BOUNDARY E [( fa )( An.a ) / Au] = 1 Eq.4L' - -f I a the specific activity limit for radionuclide, I, as obtained from 10 CFR 20, Appendix !
. Aui B, Table ll, Column 2 (microcuries/cm3) i L Ier all the DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE 6f Fi.UENTS, use the value from 10 CFR 20, Appendix B, Table ll, Column 2. !
For each of the LESS DOMINANT RADIONUCLlDEs found in TYPICAL ; RADWASTE EFFLUENTS, use 3E 8 microcuries per milliliter as the value for Ai u ! (per 10 CFR 20, Appendix B, Note 2), t 1- = the MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Table ll, Note 1. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter)
- The detector efficiency for each radionuclido may be calculated from data collected !
l during calibration of the radiation monitor. -- .
- Bkg = an approximation of the actector background (cpm) instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired.
1 (3) Documenting the fixed setpoint for 1/2 RI 4014 (a) Whenever the fixed setpoint is calculated, the specific - values chosen for each of the variables shall be : documented in accordance with EN 1 100. (4) Changing the fixed setpoint for 1/2 Rl-4014 (a) If the fixed setpoint calculated in accordance with equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. ' (b) The fixed alarm setpoint may be establishod at values lower than the maximum cllowable setpoint, if desired. (c)- A setpoint change should be initiated whenever any of the ; parameters identified in equation 1L (identified in this
- section of the ODCM) have changed.
L This formula has been derived from 10 CFR 20, Table 11, Notes 1,2, and 3. [
Offsite Dose C:lcul:ti:n Mmu;l Pag) 85 of 313 Revision 2, Change 0 O (d) The fixed setpoint should not be changed unless one of I the following occurs: i) the relative activity' of any radionuclide in TYPICAL LIQUID EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint,
- 11) the minimum dilution water flow rate is not Lyailable for a liquid release, iii) the values listed in 10 CFR 20, Table ll, column 2 have changed, IV) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or v) the monitor is not conservative in its function (see
" Functions of 1/2 RE 4014" earlier in this section). .
(e) EN 1 100 contains the administrative controls associated l with changing and approving the fixed setpoint.
- 1) The adjustable alarm and trip setpoint for 1/2-RI-4014 (1) Generalinformation (a) This setpoint is an adjustable setpoint. The adjustable setpoint is calculated and adjusted prior to each release from the steam generator blowdown processing rystem.
(b) The adjustable setpoint is based on the specific activities of the r ,dionuclides present in the undiluted liquid waste (as determined by radiochemical analysis ner Control l 4.11.1.1.1). (c) Whenever the adjustable setpoint is exceeded, discharges from the steam generator blowdown processing system will be manually suspended. (d) See OI 8A for a fulllist of operator ACTIONS taken in response to this alarm. (e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the steam generator blowdown processing system. (f) Tha value for the adjustable setpoint is recorded on the liquid release permit in accordance with CHEMISTRY SECTION procedures. I As determined in accordance with Attachment 5.
Offsit) Dose Calculation Manu;l P g) 86 of 313 Revision 2, Change 0 p) i V (g) This alarm is not integral to the steam generator blowdown tank radiation monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 1/2 Rl-4014, and provides an alarrn to plant operators when the 1/2 RI-4014 adjustable setpoint has been exceeded. (i) A value for the adjustable alarm and trip setpoint shall be calculated prior to each release as shown below. (2) Calculating the adjustable setpoint for 1/2 RI 4014 (a) The adjustable alarm and trip setpoint is based on the specific activity of the radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11,1,1,1), and the alarm and trip setpoint is l calculated as shown below. ADJUSTABLE ALARM AND TRIP SETPOINT FOR 1/2 RI-4014 8,aj $ 1,50 (E( Aw )( ei) + Bkg ] Eq 61) Sg = the adjustable alarm and trip setpoint for 1/2 Rl 4014 (cpm) (~~'s Q 1.50 = a constant, actually a safety f actor, .vhich allows for fluc uation in radiation monitor responso (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic ancmalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.2 Au = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter)
= absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter)
The detector efficiency for each radionuclide may be calculsted from data collected during calibration of the radiation monitor, Okg = an approximation of the detector background (cpm) (3) Documenting the adjustable setpoint for 1/2 RI-4014 m 2 Equation SL has been derived from NUREG-0133, Addeadum, page AA 1. The " analysis errors" and " calibration errors" refer to errors which are within established quahty [U) assurance and quality control limits.
Offs 6t3 Done Calculation M:nual Pcg3 87 of 313 Revision 2 Change 0 m (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be ) documented in accordance with approved CHEMISTRY l SECTION procedures.- (4) Changing the adjustable setpoint for 1/2 RI 4014 t (a) If the adjustable setpoint exceeds the maximum range of ! the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. l (b) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint. (c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable > setpoint. (d) Whenever 1/2 Rl 4014 is operable, the calculatedvalue , for the adjustable setpoint shall be entered into the plant computer prior to each release from the steam generator blowdown and processing system, (e) Plant Operating Instructions (e.g., Ol 8A) contain administrative controls associated with entering the adjustable setpoint in the plant computer, j) The low alarm retpoint for 1/2 Rl 4014 (1) This alarm is integral to the steam generator blowdown tank monitor, as purchased from the manufacturer. (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. (3) Changes to the low alarm setpoint are controlled by EN 1 100. (4) The ODCM does not address the calculations associated with the low alarm setpoint. LIMITS ON RADIONUCLIDE CONCENTRATIONS IN 6 ' QUID EFFLUENTS 1, introduction a) 10 CFR 20, Appendix B, specifies concentration limits associated with the release of radioactive materials to UNRESTRICTED AREAS. b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls
Offt.it] Dof,e Calculation Manual Pag) 88 of 313 Revision 2, Chango O n a) The concentration of radioactive material released in liquid effluents to / UNRESTRICTED AREAS shall be limited to the concentrations specified U) in 10 CFR 20, Appendix B, Table ll, Column 2 for radionuclides other than dissolved or entrained noble gases (per Control 3.11.1.1). b) It should be noted that NUREG 0133 spot.ifies that the concentration of radioactive materials in liquid effluents to UNRESTRICTED AREAS shall be limited to 2 E-4 microcuries per milliliter for dissolved or entrained noble gases, this control has not been incorporated into the CCNPP Technical Specifications, and as a result, the ODCM does not include calculations for same. c) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirements a) Routino surve:llances for BATCH RELEASES (1) Sample each " BATCH" of radiorctive Fquid waste prior to its release (per Control 4.11.1.1.1).
(2) Determine the concentrations of principle gamma emitters (including, but not limited to, Mn 54, Fe 59, Co-58, Co-60, Zn 65, -- Cs 134, Cs 137, Ce 141,1131, Mo 99, and Co 144)in the
- BATCH" sample, prior to the " BATCH" release (per Control l 4.11.1.1.1). ,
(3) Determine the concentration of tritium contained in a monthly COMPOSITE SAMPLE at least once per month (per Control l 4.11.1.1.1). (4) Determine the concentrations of Sr 89 and Sr 90 contained in a quarterly COMPOSITE SAMPLE at least once per quarter (per Control 4.11.1.1.1). (5) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Contro14.11.1.1.2). b) Routine surveillancas for CONTINUOUS RELEASES (1) Sample CONTINUOUS RELEASES of radioactive liquid waste at least once per month (per Control 4.11.1.1,1). (2) Determine the concentrations of principle gamma emitters (including, but not limited to. Mn-54, Fe 59, Co-58, Co-60, Zn 65, Cs 134. Cs-137, Ce 141,1-131, Mo 99, and Ce 144) in the undiluted, CONTINUOUS waste stream sample (per Control 4.11.1.1.1), (3) Calculate the concentrations of radionuclides in the receiving
,,h waters at the point the liquid radioactive waste is released to (V UNRESTRICTED AREAS (per Control 4.11.1.1.2).
Off:lla Dose Cciculation M:nu:1 Pega 89 of 313
- R:vi ion 2. Change 0
- 4. Responsible Plant Organizations
[m V l a) The CHEMISTRY SECTION is responsible for performing the sampling, analysis, and calculations required by the above surveillances. b) The conditions which initiate the required surveillances are contained in the following section, S. Initiating Conditions a) The surveillances for BATCH RELEASES shall be performed prior to each DATCH RELEASE' and may be performed more often as specified in approved CHEMISTRY SECTION procedures. b) The surveillances for CONTINUOUS RELEASES shall be performed at least monthly' (until the CONTINUOUS RELEASE has been terminated) and, if activity is identified'in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved CHEMISTRY SECTION procedures. G. Calculation Methodology a) At CCNPP, there are two methodologies for calculating the concentrations of radionuclides in the receiving waters, at the point of - release to UNRESTRICTED AREAS, resulting from the discharge of liquid waste. (1) The rigorous methou shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as weil as additional supporting information, are presented in the following sections. b) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a comr:-ter system and appropriate software are available. (2) If a computer system and the appropriate software are available, ensure the concentrations of radionuclides in UNRESTRICTED AREAS are less J,an one MPC by verifying the following inequality is true: g Per Control 4.11.1.1.1, t 3 l Per Control 4,11.1.1.1. V
- The LOWER LIMITS OF DETECTION shall conform to Control 4.11.1.1.1, Table 4.11 1.
Offsite Dose Calculation Manual Page 90 of 313 Revision 2, Change 0 LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (RIGOROUS METHOD) J 3
~ r. / F, i S ( Am / Au ) 5.1 Eq.6L'
= the actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE F. = F., + F., + F. . Eq.2L F ew = the actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute. -- F., = the salt water system flow rate if the actual salt water flow rete is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undsr.ed radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum u' m adwasta flow rates for various waste streams are tabulated in Attachme v 4 d9 A eu = the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries!cm3) An = the specific acNity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)
=
1 the MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Table 11, Note 1. Equation 6L has been derived from 10 CFR 20, Appendix B, Table ll, Note 1.
l Offsita Dose Calcul: tion Minuti Pag 3 91 of 313
% tsion 2, Change 0 -
c) Simplified method (1) Whenever a computer system and appropriate software are unavailable to perform the rigorou? calculations described in the previous section, ensure the concentrations of rWonuclides in UNRESTRICTED AREAS are less than one MPC b) verifying the following inequality is true. LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AhEAS (SIMPLIFIED METHOD) { Fu / [ ( F, ) ( Annu ; ( K.,)] } E A., $ 1 Eq.7L' Fu = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. F, a the actual dilution water flow rate (gpm) prior to the point of release to -- UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the O) ( salt water flow rate, and the undiluted radwaste flow rate. DILUTION WATER FLOW RATE Fe = F., + F., + F. Eq,2L Fm = the actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute. F, = the actual salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Anmu = the specific activity limit for 1-131 corresponding to the limiting concentration specified in 10 CFR 20, Appendix B, Table 11, Column 2 This value is 3E-7 microcuries per milliliter. I '
'% This equation has been derived from 10 CFR 20, Appendix B Table 11, Note 1.
l
Offsite Dosa Calculation M:nual P ge 92 of 313 Revision 2, Change 0 Au = the specific activity of nuclide, I, in the undiluted liquid radwaste (microcuries per
,- m
( v) = milliliter) Kg a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the activity limit of 10 CFR 20, Appendix B, Table ll, Column 2, (unitiess) (per Control 3.11.1.1) The safety f actor chosen shall be less than or equal to 1.00. This ensures the activity is always less than or equal to the activity limit of 10 CFR 20, Appendix B, Table 11 Column 2. A safety factor of 1.00 will yield a activity which corresponds to the 10 CFR 20, - Appendix B, Table 11, Column 2 activity limit. A safety factor of 0.500 will yield an activity which corresponds to one-half the activity limit of 10 CFR 20, Appendix B, Table 11, Column 2. It is recommended that a safety factor of 1.0 be used for calculating the activity, however, other values--not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. - The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provido plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release -- permits. This administrative controlis designed to minimize the possibility of violating 10 CFR 20, Appendix B, Table 11, Column 2 limits whenever simplifying Q assumptions are used. Q The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. This safety factor has been included in equation 7L to account for any potential nonconservatism associated with applying the I 131 MPC limit to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides which have an MPC value higher than the 1-131 MPC limit are present in a liquid release. d) Once the rigorous or simplified calculations have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS a) CHEMISTRY SECTION surveillance procedures (e.g., CP-212) shall contain/and/or reference administrative and/or Technical Specification l limits for concentration of radionuclides in liquid effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.
o
- .. -.. - ~ . . _ . - ..- . - ~ - -. - - - - - - . -
Offsite Dose C:lculition M:nual Pag 3 93 of 313 Revision 2, Change 0 b) Refer to Control 3.11.1.1 for ACTIONS to be taken in the event the l O - concentrations of radionuclides in UNRESTRICTED AREAS exceed one MPC, LIMITS 09 CUMULATlVE TOTAL BODY DOSES AND CUMULATIVE ORGAN DOSES FOR , LlOUl0 EFFLUENTS
- 1. Introduction a) Appendix l to 10 CFR 50 specifies total body dose limits and organ dose limits associated with the release of radioactive liquids to 4
- UNRESTRICTED AREAS. -
b) Radiological effluent controls havo been established *o implement the
- requirements of 10 CFR 50, Appendix 1.
c) These radiological effluent controls are described below. ). 2. Radiological Effluent Controls a) The total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 3 mrems per calendar quarter and 6 mrems per calendar year (Control 3.11,1.2). b) The organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 10 mrems per calendar quarter and 20 mrems per calendar year (Control 3.11.1.2).
- c) - The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirement (s) a) Cumulative total body doses to MEMBERS OF THE PUBLIC in
- UNRESTRICTED AREAS--for the current calendar month, the calendar quarter, the current calendar year, and the previous 92 days-shall be calculated, in accordance with equation 8L, at least once per 60 days (per Control 4.11.1.2 and 4.11,1.3).-
Cumulative organ doses to MEMBERS OF THE PUBLIC in b) UNRESTRICTED AREAS-for the current calendar month, the current t calendar quarter, the current calendar year, and the previous 92 days - snall be calculated, in accordance with equation 8L, at least once per.60 days (por Control 4.11.1.2 and 4,11.1.3).
- 4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for performing the
, surveillances, listed above, whenevet the appropriate initiating conditions, listed below, are present.
. , - . -m , , - , -
-. --- - - . . - - - . . - . . _~ - - . .. - . _ - .
Offsit3 Dose Calculation Menu 1 Paga 94 of 313 RIvision 2, Chan0e 0 a) Perform the surveillances, listed above, at least once per 60 days (per Control 4.11.1.2). , b) For BATCH RELEASES, perform the surveillances, listed above, prior to each BATCH RELEASE of radioactive liquid waste in accordance with approved CHEMISTRY SECTION procedures. c) For CONTINUOUS RELEASES, perform the surveillances, listed above, at least monthly (until the CONTINUOUS RELEASE has been terminated) and, if activity is identified' in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved CHEMISTRY SECTION procedures. .- d) Whenever the correct initiating conditions are present, the calculations required by the above mentioned surveillance (s) shall be completed in accordance with the methodology listed in the next section. 6 Calculation Methodology a) The cumulative total bod'y dose and the cumulative organ doses (for the , current calendar month, current calendar quarter, previous 92 days, and current calendar year) shall be calculated as follows: CUMULATIVE TOTAL BODV OR ORGAN, o, DOSE FROM LIQUID RELEASES, r Drot = E D, Eq,8L , , Da = the sum total of the total body or organ, o, dose for allliquid releases discharged during the applicable time interval D, = the organ or total body dose resulting from release, r Calculate the values of D, for each liquid release as described below. + b) At CCNPP, two methods exist for calculating D,(i.e., the total body and organ doses resulting from any single release of radioactive liquid to an UNRESTRICTED AREA), (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3). These methods, as well as additional supporting information, are presented in the following sections. c) ' Rigorous method
\ '
The LOWER LIMITS OF DETECTION shall conform to Control 4.11.1.1.1, Table 4.11-1. l
. . .. .- .- - . -.~. - ._. . ~ . - - .- - - ..
Offsit3 Dose Calcul tion M:nual - Pign 95 of 313
- R; vision 2. Ching2 0 ~
(1) So!ution of the following equation may prove too rigorous for O
' routine use unless a computer system and appropriate software are available.
(2) If a computer system and the appropriate software are available, the dose commitments due to each release of radioactive liquid to an UNRESTRICTED AREA shall be calculated in accordance with the following equation: DOSE TO THE TOTAL BODY OR ORGAN, o, FROM A LIQUID RELEASE (RIGOROUS EQUATION) D. = ( Vu / [( 60 )( Fe )] } Z { ( A )( C )) Eq.9L' '
- Where, Fd_. =
actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS
~
The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate. The dilution water flow rate shall be calculated in accordance with equation 2L. -- DILUTION WATER FLOW RATE O Fe = F., + F., + Fu Eq.2L F, e
= actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.
F, = actual satt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L. The maximum f!ow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm) If the ectual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. Vu = volume of undiluted radwaste (gallons) Equation 9L has been derived from NUREG-0133,4.3. t
- - - - - * - - , , - - - + . , ,
i Offsite Dos] Ccicul; tion Manu:1 Pcge 96 of 313 I Revision 2 Change 0 Ay = specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per q milliliter)
=
C. liquid release dose factor for nuclide, i, and organ, o (mrem /hr per microcurie /ml) The liquid release dose factors for principal gamma and beta emitters are listed in Attachment 6. The liquid release dose factors for principal gamma and beta emitters were obtained in accordance with the methodology of NUREG-0133, section 4.3.1 (for salt water sites). 60 = a constant, the number of minutes per hour (3) in the event a computer system is unavailable, a simplified equation may be used to calculate the total body and organ dose commitments due to individual liquid releases. (4) The simplified method is presented below. - d) Simplified methods (1) Whenever a computer system is unavailable to perform the - rigorous total body dose calculations described in the previous section, the total body dose commitments--due to each release of 3 radioactive liquid to an UNRESTRICTED AREA--may be (V calculated in accordance with equation 10L. (2) Whenever a computer system is unavailable to perform the rigorous organ dose calculations described in the previous section, the dose commitments--to the maximum exposed organ, due to each release of radioactive liquid to an UNRESTRICTED AREA--may be calculated in accordance with equation 11L. TOTAL t30DY DOSE FROM A LIQUID RELEASE (SIMPLIFIED EQUATION) Du, = { [( 58.6 )( Vu )]/ [( Ka)( F ))) E A,u Eq.10L' De = dose commitment, to the total body, due to each release of radioactive liquid to an UNRESTRICTED AREA 58.6 = a conversion constant which includes:
- 1) 1.33E4 mrem /hr per microcurie /mi (the dose factor for Cs-134 to the lower gastrointestinal tract)
- 2) 1.000 hr/60.00 min (d '
Equations 10L has been derived from NUREG-0133,4.3.
. - - - - . . - . - - - _ - - - - - _ - - - - _ _ - _ - . - . ~ . - - . _ .
Offsits Doss Calcul: tion Manual Page 97 of 313 Revision 2, Change 0
- 3) 1.000 gallons /3.785 liters -
O Vu = volume of undiluted radwaste (liters) . K# = a constant, actually a safety factor, which is the ratio of the CCNPP total body dose limit to the total body dose limit of Control 3.11.1.2, (unitiess)
- The safety factor chosen shall be less than or equal to 1.00. This ensures the total body dose is always less than or equal to the total body dose limit of Control l 3.11.1.2. .
A safety factor of 1.00 will yield a total body dose which corresponds to the total -
- body dose limit of Control 3.11.1.2.
- A safety factor of 0.500 will yleid an total body dose which corresponds to one-half the total body dose limit of Control 3.11.1.2. It is recommended that a safety factor of 1.0 be used for calculating the total body - dose, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry. - The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release ..- permits. This administrative controlis designed to minimize the possibility of violating Control 3.11.1.2 when simplifying assumptions are used. The use of a safety factor is consistent with the ALARA philosophy that licensees - should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. This safety factor has been included in equation 10L to account for any potential nonconservatism associated with applying the Cs-134 gastrointestinal dose conversion factor to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor greater than that of Cs-134 are present in a liquid release. Fa = actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate. The dilution water flow rate shall be calculated in accordance with equation 2L. 2 O
Offsit) Dose C:lculation M:nu:l: P:g3 96 of 313
- . Revision 2 Change 0 DILUTION WATER FLOW RATE
[fT X F. = F., + F., + F. Eq 2L F,e
= actual circulating water system flow rate The flow rate of each circulation water pump is 200,000 gallons per minute.
- F,, - = actual salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L.
The maximum flow rate for one salt water pump is listed on Attachment 2.
' F, -= actual undiluted radwaste flow rate (gpm)
If the actual undiluted radwaste flow rate is less than 1% of the total dilutionwater . . flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. - Au = specific activity of nuclide, i,-in the undiluted liquid radwaste (microcuries per ' milliliter) , DOSE TO THE ORGAN, o, FROM A LIQUID RELEASE (SIMPLIFIED EQUATION) D. = { [ ( 449 ) ( V. )] / [( K.,) ( Fe )) ) E Aiu Eq.11L' D, -=- the dose commitment to the maximum exposed ORGAN due to each release of radioactive liquid waste to an UNRESTRICTED AREA 449- = a conversion constant which includes:
- 1) 1,02E5 mrem /hr per microcurie /ml(the dose factor for 1-131 to the thyroid)
- 2) 1.000 hr/60.00 min
- 3) 1.000 gallons /3,785 liters
-V, =
volume of u.ndiluted radwaste (liters) 1 K,p = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Control 3.11.1.2, (unitiess)'
-( v- li~
. Equations 11L has been derived from NUREG-0133,4.3.
. - - . - - . . - - - .- _.- . - . . _ ~ . - . - _ . . . . ,
1 I Offsite D:se C:lcul tion Manual Paga 99 of 313- ! Revision 2, Change 0 -- , p The safety factor chosen shall be less than or equal to 1.00. This ensures the ' organ dose is always less than or equal to the organ dose limit of Control 3.11.1.2. _Q
' A safety factor of 1.00 will yield a organ dose which corresponds to the organ dose limit of Control 3.11.1.2.
A safety factor of 0.500 will yield an organ dose which corresponds to one half the organ dose limit of Control 3.11.1.2. It is recommended that a safety factor of 1.0 be used for calculating the organ dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. - The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release
- permits. This administrative controlis designed to minimize the possibility of violating Control 3.11.1.2 when simplifying assumptions are used. -
The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. This safety factor has been included in equation 11L to account for any potential nonconservatism associated with applying the 1131 thyroid dose conversion factor to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor ' greater than that of I 131 are present in a liquid release. 4
- _ Fe = dilution water flow rate (gp,m) prior to the point of release to UNRESTRICTED AREAS The actual diluti
- water flow rate is the sum of the circulating water flow rate, the salt water flow rate, arid the undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. ' DILUTION WATER FLOW RATE F4 = F. , + F. , + F., Eq.2L Few = actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute. F., .= salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L.
Offsite Dose Calculation Manual Page 100 of 313 Revision 2, Change 0 The maximum flow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. A,u = specific activity of nuclide, I, in the undiluted liquid radwaste (microcuries per milliliter)
- 7. Corrective ACTIONS a) CHEMISTRY SECTION surveillance procedures (e.g., CP-212) shall contain/and/or reference administrative and/or Controllimits for l cumulative total body doses or cumulative organ doses resulting from liquid effluents and shall specify corrective actions to be initiated when these limits are exceeded.
b) Refer to Control 3.11.1.2 for actions to be taken in the event the l calculated cumulative total body dose exceeds 3 mrem per calendar -. quarter or 6 mrom per calendar year. h, c) Refer to Control 3.11.1.2 for actions to be taken in the event the l QE;y calculated cumulative organ dose--for any organ--exceeds 10 mrem per y;,'q , calendar quarter or 20 mrem per calendar year. hM's' ~t LIMITS FOR THE LIQUID WASTE PROCESSING SYSTEM t l .? 4
- 1. Introduction
%m a) 10 CFR 50.36a requires licensees to maintain and use the equipment Tj installed in the liquid waste processing system for the purpose of 9 controlling effluents to the environment.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The liquid radwaste processing system shall be used to reduce the quantity of radioactive materials in liquid waste released to the environment whenever the total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 0.36 mrem for the previous 92 days (per Control 3.11.1.3).
O
Offsit3 Dose Calculation Manual Pags 101 of 313 Revision 2, Change 0
-m b) The liquid radwaste processing system shall be used to reduce the
()- quantity of radioactive materials in liquid waste released to the environment whenever.the organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 1.20 mrem for the previous 92 days (per Control 3.11.1.3), c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below
- 3. Surveillance Requirement (s) a) - The previous 92 day, cumulative, total body dose-to MEMBERS OF -
THE PUBLIC in UNRESTRICTED AREAS-shall be calculated, as described in the ODCM, a,least once per 60 days (per Control 4.11.1.3), b) The previous 92-day, cumulative, organ doses-to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS- shall be calculated, as described in the ODCM, at least once per 60 days (per Control 4.11.1.3).
- c) The CCNPP organization (s) responsible for performing these -
surveillances are identified in the next section.
- 4. Responsible P! ant Organization (s)
~
a) The CHEMISTRY SECTION is responsible for performing the surveillances, listed above, whenever the appropriate initiating
, conditions, listed below, are present.
- 5. Initiating Conditions a) Perform the surveillances, listed above, at least once per 60 days (per Control 4.11.1.2).
b) For BATCH RELEASES, perform the surveillances, listed above, prior to each BATCH RELEASE of radioactive liquid waste in accordance with approved CHEMISTRY SECTION procedures. l c) For CONTINUOUS RELEASES, perform the surveillances, listed above,
- at least monthly (until the CONTINUOUS RELEASE has been terminated) and, if activity is identified' in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved CHEMISTRY SECTION procedures.
I d) Whenever the correct initiating conditions are present, the calculations required by the above mentioned surveillance (s) shall be completed in accordance with the methodology contained in the following section. l. l i
- O j The LOWER LIMITS OF DETECTION shall conform to Cor, trol 4.11.1.1.1. Table 4.11-1. l t
i
i Offsita Dose Calculation Minutl Page 102 of 313 l Revision 2 Change 0 l
- 6. Calculation Methodology a) The cumulative total body dose and the cumulative organ doses for the previous 92 days sha:I be calculated in accordance with equation 8L~
found in the section, " Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents", found elsewhere in the ODCM.
- 7. Corrective ACTIONS E
a) ~ CHEMISTRY SECTION surveillance procedures (e.g., CP 212) shall , contaln/and or reference administrative and/or Controllimits for l cumulative total body doses or cumulative organ doses resulting from liquid effluents and shall specify corrective ACTIONS to be initiated when these limits a.e exceeded. , b) Refer to Control 3.11.1.3 for ACTIONS to be taken in the event the l calculated cumulative total body dose exceeds 0.36 mrem for the previous 92 days, c) Refer to Control 3.11.1.3 for ACTIONS to be taken in the event the ( calculated cumulative organ dose-for any organ--exceeds 1.2 mrem for the previous 92 days. I . t
OffsNe Dose Calcul lon Manu:1 Prg)103 of 313 R: vision 2, Chango 0
,_s RADIOACTIVE GASEOUS EFFLUENTS
( ) RELEASE PATHWAYS fB5271
- 1. Introduction a) Radioactive gaseous waste generated from operation of CCNPP may be released to the atmosphere.
b) By design (i.e., in the absence of primary to-secondary loaks), there are 2 pathways by which waste gas from the site may be discharged to the ' atmosphere. These pathways are !.sted below. Generalinformation related to each of these potential release pathways is contained on Attachment 7. (1) Unit i rnain vent stack (2) Unit 2 main vent stack c'; Depending on plant conditions, (e.g., primary to secondary leaks) a - potential e.vists for the release of radioactive mateaals from other pathways. Those pathways are listed below. Generalinformation related to each of these potential release pathways is contained on Attachment 8. " (1) auxiliary boiler deaerator C/ (2) steam generator atmospheric steam dump system (3) plant nitrogen system (4) turbine building ventilation exhaust (5) emergency air lock (6) plant compressed air (7) main steam line penetrations (8) containment equipment hatch (9) auxiliary feed pumps d) All of these pathways are described below.
- 2. Unit 1 Main Vent Stack a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 1 main vent stack.
b) The radioactive gaseous waste is mixed with and diluted by the outside ,3 air and building exhausts prior to exiting the Unit 1 main vent stack.
]
Offsita Dose Ccicut tion M:nuil Pags 104 of 313 , Ftevision 2, Change 0 m c) The Unit 1 main vent stack is secured to the Unit i reactor containment building. d) The top of the Unit 1 main vent stack is at elevation 203.5 feet (mean sea level, MSL), and as such is 10.1 feet above the top of the reactor I containment building dome. As a result, the Unit 1 main vent stack does not qualify as a " free-standing" stack greater than 80 meters tall'. e) The Un;t 1 main vent stack is designed to accept gaseous radioactive waste from various sources. Sources which may contribute radioactive material to the Unit 1 main vent stack are tabulated in Attachment 7.
- 3. Unit 2 Main Vent Stack a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 2 main vent stack.
b) The Unit 2 main vent stack is designed to accept radioactive gaseous waste from various sources. c) The radioactive gaseous waste is mixed with and diluted by the outside air and building exhausts prior to exiting the Unit 2 main vent stack, d) The Unit 2 main vent stack is secured to the Unit 2 reactor containment - building. / The top of the Unit 2 main vent stack is at elevation 203.5 feet (MSL), b] e) and as such is 10.1 feet above the top of the rcactor containment building dome. As a result, the Unit 2 main vent stack does not qualify as a " free standing" stack greater than 80 meters tall. f) The Unit 2 main vent stack is designed to accept gaseous radioactive waste from various sources. Sources which may contribute radioactive material to the Unit 2 main vent stack are tabulated in Attachment 7.
- 4. Auxiliary Boiler Deaerator a) Radioactive gases may be vented from the auxiliary boiler deaerator during periods of primary to secondary leakage.
b) Steam from the Moisture Separator Reheater (MSR) may be used in the deaerator, in the event of a primary to secondary laak, the MSR steam could become contaminated. Therefore, a potential exists for the release of radicactive gases in steam discharged from the auxiliary boiler deaerator, c) The discharge of steam is accomplished via a relief vent,0-VBV-1891, which allows excess pressure to be vented to atmosphere. As defined by Regulatory Guide 1.111
Offsit] D050 C:lculation M:nu:1 P:gs 105 of 313 Revision 2, Change 0 ,.s ' d) In the event the auxiliary boiler deaerator were to become contaminated, the amount of radioactivity released and the resulting doses / dose rates (V) : at the SITE BOUNDARY can be estimated if the following parameters are known: (1) the MSR steam activity obtained from a sample, (2) the duration of the discharge, (3) the estimated steam discharge flow rate, and (4) the measured or hverage annual meteorological conditions. - e) In accordance with applicable safety evaluations', continued operation of this system is allowed as long as the concentration of radionuclides in he auxiliary boiler steam drum is less than 96 MPCs.
- 5. Steam Generator Atmospheric Steam Dump System a) Radioactive gases are not normally vented from this pathway. -
b) Radioactive gases may be vented from the steam generator atmospheric steam dump system during periods of primary to secondary leakage. c) If a primary to secondary leak is present and the steam dump valves are opened, the amount of radioactivity released and the resulting n (,) doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known (per UFSAR,10.1.2.1): ' (1) the specific activity of a main steam sample as determined by GAMMA ISOTOPIC ANALYSIS, (2) the duration of discharge, (3) the estimated steam discharge flow rate, and (4) the measured or average annual meteorological conditions. d) The total capacity of the atriospheric steam dump valve is 5 percsnt of steam flow with the teactor at full power (per UFSAR,10.1.2.1). 6, Plant Nitrogen System a) Radioactive gases are not normally vented from this pathway. b) Nitrogen is supplied to various cornponents which contain radioactive materials (e.g., VCT). c) In the event the plant nitrogen system were to become contaminated, the amount of radioactivity released and the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known: O C ' See 50.59 Log No. 90-0-027-037 R1.
_m - Offsits Dose C:lculation Minu:1 Pcg3106 of 313 Revision 2, Change 0 W '(1) the specific activity of the gas in the plant nitrogen system as
- ( determined by GAMMA ISOTOPIC ANALYSIS, (2)- the pressure of the nitrogen systam, (3) the volume of the nitrogen system, and (4) the measured or average annual meteorological conditions, d) It should be noted that the amount of radioactivity released could be estimated based on knowledge of other related parameters.
e) In accornnce with applicable safety evaluations', continued operation of this system is allowed as long as the concentration of radionuclides is less than 13,d100 MPCs, 4
- 7. Turbine Building Exhaust a) Radioactive gases are not normally vented from this pathway.
b) In the event radioactive gases were to be released through the turbine building exhaust, the amount of radioactivity released and the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known: -- (1) the specific activity of the turbine building air, bV (2) the duration of the discharge, *
- (3) the estimated flow rate during the diccharge, and (4) the measured or average annual meteorological conditions,
- 8. Emergency Air Lock a) Radioactive gases are not normally vented from this pathway.
4 b) In the event radioactive gases were to be released through the emergency air lock, the amount of radioactivity released and the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known: the containment air activity obtained from a sample, (1) (2) the volume of the air lock (9.558 cubic meters); (3) the measured or average annual meteorological conditions.
- 9. Plant Compressed Air a) Radioactive gases are not normally vented from this pathway, A '
See 50.59 Log No. 90-0-074-011.R1.
-Offsit3 Dose C:lcut tion Manual Pcg3107 of 313 Revision 2, Change 0 b) in the event the plant compressed air system were to become .O.
V-contaminated, the amount of radioactivity released and the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known: 4 (1)- the specific activity of the compressed air system, (2) the pressure of the compressed air system, (3) the volume of the compressed air system, and (4) the measured or average annual meteorological conditions. -
- 10. Main Steam Line Penetrations a) Radioactive gases are not normally vented from this pathway.
b) This penetration is cooled by outside air. c) Gases may be released to the atmosphere through safety vents to the . roof at elevation 91.5 feet, d) See UFSAR 9.8.2.3.
- 11. Steam Driven Auxiliary Feed Pumps a) Radioactive gases are not normally vented from this pathway.
b) In the event radioactive gases were to be released through the auxiliary feed pumps, the amount of radioactivity released and the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known: (1) the activity in the steam, (2) the volume of steam released.
- 12. Containment Equipment Hatca a) Radioactive gases are not normally vented . rom this pathway.
b) In the event radioactive gases were to be released through the containment equipment hatch, the amount of radioactivity released and
- the resulting doses / dose rates at the SITE BOUNDARY can be estimated if the following parameters are known; (1) the containment air activity obtained from a sample,-
(2) the volume of the air released, (3) the measured or average annual meteorological conditions.
, - 13. Other unmonitored release paths should be evaluated and added to the ODCM L as necessary.
i Offsite Dose Calculation Minuti P:ge 108 of 313 _ Revision 2, Change 0 TYPES OF GASEOUS RELEASES b _1. Al! gaseous raciwaste releases are classified as either BATCH RELEASES or CONTINUOUS NtiLEASEs.
- 2. The definition of BATCH RELEASE is included iri the definitions section of the ODCM.
- 3. The definition of CONTINUOUS RELEASE is included in the definitions section i
of me ODCM.
- 4. Gaseous radwaste discharges have been classified as CONTINUOUS or -
BATCH as shown on Attachments 7 and 8. PROCESSING EQUIPMENT
- 1. Simplified Flow Diagram a) An overview of the gaseous waste processing system, including major equipment and (normal) flow paths, is outlined on Attachment 9. - .
- 2. Modifications a) Major changes or modifications to the gaseous waste processing system --
shall be reported to the Commission in the Annual Radioactive Eff'uent j Release Report for the time interval in which the modification was A completed (per Technical Specification - Administrative Controls). b) A " major" change or modification includes, but is not limitad to, the removal or perman int bypass of any of the following: (1) wasto gas decay tank (2) waste gas surge tank
- 3. Detailed Description a) A detailed description of the gaseous waste processing system is beyond the scope of the ODCM.
b) For more information on the Waste Gas System, see the CCNPP System Description Number 14A, " Waste Gas System." c) For more information on the Waste Gas System, see the CCNPP Updated Final Safety Analysis Report, Chapter 11," Waste Processing And Radiation Protection." GASEOUS CFFLUENT RADIATION MONITORS AND SETPOINTS 1: Wide Range Gas Monitor (1 RE-5416) a) General description
Offsit] Dose C:lculation M:nu;l Pag 3109 of 313 Revision 2, Change 0 (1) The Wide Range Gas Monitor (WRGM) contains 3 radiation O) a, elements (a) low-range noble gas detector i) Designation of radiation element: 1-RE-5416 li) type of radiation element: Off line scintillation iii) output: digital IV) Radiation indicator: 1 RIC-5415 - v) units for radiation indicator are user programmable and are normally set to microcuries per cubic centimeter vi) supplier. Sorrento Electronics (f armerly General Atomics) - (b) mid-range, noble gas detector l} Designation of radiation element: 1 RE 5417 l li) type of radiation element: Solid state O lii) This noble gas monitor is used to measure the ( release of radioactivity from unit 1 main vent in the - everit of an accident. (UFSAR, 11.2.3.2.12) l iv) setpoints for the mid-range detector will not be addressed in the ODCM j (c) high-range, noble gas detector i) Designation of radiation element: 1 RE-5418 li) type of radiation element: Solid state I lii) This detector is used to measure the release of radioactivity from unit 1 main vent in the event of an accident. (UFSAR, 11.2.3.2 12) iv) setpoints for the high range detector will not be addressed in the ODCM (2) The low range detector will be the only detector addressed further in the ODCM. i b) Functions of 1-RE 5416 (1) continuously measure the release rate of noble gases emanating (o) from the Unit 1 main vent stack (Control 4.11.21.1 or 4.11.2.1.2, Table 4.112) l
-f e
Offsite Dose C:lculation M:nual Pag)110 of 313 , Revision 2, Change 0 i (2) continuously indicate (via 1 RIC-5415) the release rate of noble
- gases emanating from the Unit 1 main vent stack (Control l . V 4.11.2.1.1 or Control 4.11.2.1.2, Table 4.112)
(3)- alarm (via 1 RIC-5415) prior to exceeding the site boundary, - . noble-gas, total-body dose-rate limit of 500 mr/yr (per Control l 3.11 2.1.a) (4) alarm (via 1-RIC-5415) prior to exceeding the site-boundary,
- noble-gas, skin-dose-rate limit of 3000 mr/yr (per Control l 3.11.2.1.a) c) OPERABILITY of 1-RE 5416 This monitor shall be operable (or have OPERABILITY) whe: it is (1) capable of performing its specified function (s).
(2) The functions of this monitor are listed in section (b) above, d) Monitors equivalent to 1 RE-5416 - (1) 1 RE-5415 [the " Westinghouse Plant Vent Stack Monitor") has the capability of providing the measurement and alarm functions of 1 RE 5416 during times when 1 RE 5416 is declared -- inoperable. (2) 1-RE-5415 provides redundant monitoring [for 1 RE-5416) at the Oi Iow end of the concentration ranges (UFSAR _11.2.3.2.12). (3) 1 RE 5415 is normally considered the PRIMARY MONITOR for measuring noble gas activity released via the Unit 1 Plant Vent Stack, and 1 RE-5416 is normally considered the BACKUP MONITOR for measuring noble gas activity released via the Unit . 1 Plant Vent Stack. (4) In the event PRIMARY MONITOR (1 RE 5415) is inoperable or otherwise unavailable, the BACKUP MONITOR (1 RE 5416)is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR. e) Radiological effluent controls for 1-RE-5416 (1) Control 3.3.3.9 states that releases via the plant vent stack may l continue if any one of the following three conditions are satisfied:
-(a)- 1 RE 5415 is operable AND the alarm and trip setpoint(s) for 1-RI 5415 are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Control 3.11.2.1.a), or 4
w --- -,-,,,n ,, , '
Offsite Dose C lculati:n M:nu:1 Page 111 of 313 Revision 2, Change 0 (b) an " equivalent monitor"is operable AND the alarm and/or O) ( trip setpoint(s) for the " equivalent monitor" are/is set to ensure annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control l 3.11.2.1.a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours in accordance with Controls 3.11.2.1.a,4.11.2.1.1, and 4.11.2.1.2 (per Control 4.3.3.9, l Table 3.312, ACTION 37). f) Surveillances for 1-RE 5416 (1) Control 4.3.3.9 requires demonstrating the OPERABILITY of 1 l RE-5416 by satisfying the checks, calibrations, and tests listed beiaw: (a) CHANNEL CHECK within the past 24 hours (b) SOURCE CHECK within the past 31 days (c) CHANNEL CAllBRATION within the past 18 months m (d) CHANNEL FUNCTIONAL TEST within the past 6 six months ( 'v) g) Setpoints for 1 RIC 5415 ' (1) Requirements and commitments (a) The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9) (b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM (per NUREG-0133, 5.1.1), (2) There are three radiation alarm setpoints associated with, or otherwise related to, the WRGM. (a) 1 RIC-5415 fixed high-high radiation alarm setpoint (b) 1-RIC-5415 fixed high radiation alarm setpoint (c) 1-RIC-5415 adjustable plant computer high radiation alarm setpoint (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows (n'-) (a) The 1-RIC-5415 high-high radiation alarm setpoint will be referred to as the fixed high alarm setpoint
Offsite Dose Calcutation Manual Pcg3112 of 313 ' Revision 2. Change o p (b) The 1 RIC-5415 high radiation alarm setpoint will be-Q referred to as the fixed alert setpoint (c) The 1 RIC 5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable i setpoint (4) Each of these alarm setpoints are described below, h) Fixed high r. farm setpoint for 1-RIC 5415 (1) Generalinformation - (a) The high alarm setpoint is considered to be a fixed setpoint. The fixed high alarm setpoint is not adjusted for each release. (b) Whenever the fixed high alarm setpoint is exceeded, an alarm will be generated. (c) The current value fcr the fixed high alarm setpoint is specified in the CCNPP Alarm Manual. (d) The CCNPP Alarm Manual' refers to the fixed high alarm -- setpoint as the Unit 1 Wide Range Noble Gas Radiation Monitor high alarm setpoint. (e) The fixed high alarm setpoint is integral to the WRGM, as purchased from the supplier, (f) The fixed high alarm setpoint is administratively controlled by EN-1-100. (g) The fixed high alarm setpoint shall be calculated as described below. (2) Calculatmg the fixed high alarm setpoint for 1 RIC-5415 (a) The fixed high alarm setpoint for 1-RIC-5415 (WRGM) shall be calculated in accordance with equation 1G.* FIXED HIGH A'. ARM SETPOINT FOR 1-RIC-5415 4 Sninn .$ [c' / ( x/Q )] [ Fox / ( Foi + Fez )] [ Ann ] - Eq.1G 3 Where, , Sr,,nn = the fixed high alarm setpoint for 1-RIC-5415 (microcuries per second) The CCNPP Alarm Manualis controlled by NO 1201. l pg The alarm and inp setpoints ... shall be determined and adjusted in accordance with the Q 8' methodology and parameters of the ODCM. (Control 3.3.3.9). Equation 1G has been derived from NUREG-0133,5.2.1. l
Offsite Dose Calculatiin M:nual Pa0)113 of 313 Revision 2, Chan00 0 - ,m c' = a conversion constant (1E6 cubic centimeters per cubic meter) (
) =
x/O the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) Unit 1 main vent releases are considered "long-term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used !n the setpoint calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) F,o
= the estimated main vent stack (diluted gaseous radwaste) flow rate for unit, x, (cubic meters per second)
~
The estimated main vent stack flow rates for Unit 1 and Unit 2 are defined below. F oi = the estimated main vent stack flow rate for Unit 1 (cubic meters per second)
~
Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow Q LJ rate is used to calculate the fixed high setpoint. Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. This nominal main vent stack flow rate is based on the results of an approved engineering test procedure The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The Radiological Effluent Technical Specifications (RETS) Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.
= the estimated main vent stack (diluted gaseous radwaste) flow rate for unit 2 (cubic Fe2 meters per second)
Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high alarm setpoint.
' NUREG-0133, 3.3 (o) v 2
See ETP 87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 1", completed in November 1987.
Offsit) Dose C:lculation Manu:1 Pag 3114 of $13 , Revision 2, Change 0 Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7.
\
This nominal main vent stack flow rate is based on the results of an approved engineering test procedure'. The main vent stack flow rate shall be determined, in accordance with approved _ procedures, at least once per 6 months (125%). The Test and Equiprr.ent Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is .- greater than the maximum discharge flow rates listed on Attachment 7. Aru = the sum of tha total specific activities of all radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (mlcrocuries/cm3) Calculate A7u in accordance with equation 2G. SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT E [( f,)( Am )) / Au 5, Lwe Eq.2G 8 _ Where. f, = a fraction which represents the relative activity contribution of noble gas O' radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value may be obtained using the guidance provided on Attachment 5. A 6u = the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix i B, Table ll, Column 1 (microcuries/cm3) For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table ll, Co;umn 1. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E 14 microcuries per milliliter as the value for A iu (per 10 CFR 20, Appendix B, Note 2). L MPc = the site MPC limit (MPCs) for UNRESTRICTED AREAS The value chosen for LMPc in this equation is 2. The basis for this limit is 10 CFR 50.72. It has been shown* that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Control 3.11.2.1(a). O' _ See ETP-8716, Revision 0," Main Vent Stack Flow Measurement - Unit 2", completed in November 1987.
s. Offsit) Dose Calcul: tion M:nuil ' Paga 115 of 313-Revision 2, CFange 0
- It should be noted that by'using "2" as the MPC limit (10 CFR 50.72), instead of 0 using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into
' equation 2G.
- l. ,
~
An alarm setpoint corresponding to 2 MPCs serves to initiate a determinatian of whether the "4 hour NRC notification"(specified in 10 CFR 50.72) is required. (3) Documenting the fixed high alarm setpoint (a) Whenever the fixed high alarm setpoint is calculated, the specific values chosen for each of the variables shall be - documented in accordance with EN 1 100. (4) Changing the fixed high alarm setpoint for 1 RIC-5415 (a) If the fixed high alarm setpoint calculated in accordance with equation 1G exceeds the maximum range of the . monitor, the fixed high setpoint shall be adjusted to a value which falls within the normal operating range of the . monitor. (b) The fixed high alarm setpoint may be esta; . led at values lower than the maximum allowable setpoint, if .-
- desired.
(c) A setpoint change should be initiated whenever any of the , \ parameters identified in the setpoint calculation equations - (identified in this section of the ODCM) have changed, (d) The fixed high alarm setpoint should not be changed unless one of the following occurs: i) the ralative activity' of any radionuclide in
- TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) the historical madmum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (Lupc) has changed,
' iv) the Unit 1 or Unit 2 main vent stack flow rate has . changed by greater than or equal to 10%', 2-3 ~ This equation has been derived from 10 CFR 20, Appendix B, Table ll, Note 1. Addendum To Setpoint Calculations For WRGM Monitors 1 RIC-5415 and 2 RIC-5415, R.L. Conatser, December 10,1991
. As determined in accordance with Attachment 5. ' O. - 3 As determined by analysis of the TE 001 and ETP 8716 test results.
f
, ,,,- , -.--. ,, , e , --- , . , , -.
Offsita Dose Calcul: tion M:nual Paga 116 of 313 Revision 2 Change 0 _p v) the values listed in 10 CFR 20 Table ll, column 1 ( have changed,
. vi) the radiation monitor has been recently calibrated, .'
repairedi or otherwise altered, or - vii) the monitor is not conservative in its function (see
" Functions of 1-RE 5416" earlier in this section),
(e) EN 1-100 contains the administrative controls associated . l 2- with changing and approving fixed high alarm setpoint. , i) Fixed alert setpoint for 1 RIC-5415 (1) Generalinformation
-(a) The fixed alert setpoint is considered to be a fixed setpoint. The fixed alert setpoint is not adjusted for each release.
(b) Whenever the fixed alert setpoint is exceeded, an alarm will be generated. (c) The CCNPP Alarm Manual does not reference this -- setpoint. O (d) The fixed alert setpoint is integral to the WRGM, as purchased from the supplier. ' (e) The current value for the fixed alert setpoint is specified in the CCNPP Setpoint File. (f) The fixed alert setpoint is administratively controlled by EN-1-100, (g) The fixed alert setpoint shall be calculated as described below 1. (2) Calculating the fixed alert setpoint for 1-RIC-5415 (a) The fixed alert setpoint for 1-RIC-5415 shall be calculated as described below: FIXED ALERT _SETPOINT FOR 1-RIC-5415 ' Snin ,5 K., [ Snnhh ] Eq.3G Where,- S% = ' the fixed alert setpoint for 1-RIC 5415 (microcuries per second) i The alarm and trip setpoints .., shall be determined and adjusted in accordance with the
- methodology and parameters of the ODCM, (Control 3.3.3.9).- l
.- - . - - - _ . - _ ~ _ . - - - . - - - . . - - . -. . .--
Offsita Dose C:lculation M: null Pags 117 of 313 Revision 2, F ge0 , S L = : the fixed high alarm setpoint for 1 RIC-5415 (microcuries per second) Kg = a constant, actually a safety factor, which is the fraction of the fixed high setpoint ynitiess). The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed alert setpoint is always less than or equal to the fixed high alarm setpoint. A safety factor of 1.00 will yield a fixed alert setpoint which corresponds to the fixed high alarm setpoint. A safety factor of 0.100 will yield a fixed alert setpoint which corresponds to one- - tenth the fixed high alarm setpoint. It is recommended that a safety factor of 0.1 be used for calculating the fixed alert setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a value less than 1.00 does provide plant personnel with adequate time to respond to . changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits. The use of the safety factor is consistent with ALARA philosophy that licensees - . - should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. The usa of a " safety margin"is in accordance with the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, l 5.1.1). This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated fixed alert setpoint. (3) Documenting the fixed alert alarm setpnint (a)-- Whenever the fixed alert alarm setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN-1-100. (4) Changing the fixed alert alarm setpoint for 1 RIC-5415 (a). A setpoint change should be initiated whenever any of the parameters identified in equation 3G have cha- @d.
-(b) The fixed alert setpoint should be changed whenever the fixed high setpoint is changed.
U
Offs.ito Dose Calculation M: null Pcg2118 of 313 R: vision 2, Ch:nge O c) lG (c) The fixed alert setpoint should be chcnged if the value of the safety f actor is changed. (d) See EN 1 100 for a description of activities associated l with setpoint changes and setpoint approvals, j) Adjustable alarm setpoint for 1 RIC 5415 (i) Generat information (a) This totpoint is an adjustable setpoint. Whenever this radiation monitor is operable, the adjustable satpoint is calculated and adjusted prior to each release of a WG0T. each containment vent, and each containtnent purge discharged via the main vent. (b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrMions are determined by - radiochemical analysis in accordance with applicable CHEMISTRY SECTION proceduras as required by Control 4.11.2.1.2). (c) Whenever the adjustable setpoint is exceeded, the WGDT, PURGE. or vent discharge via the main vont will be manually suspended (d) Refer to the Alarm Manual for a fulllist of operator ACTIONS taken in response to this alarm. (e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT, a containment vent, or a containment purge via the main vent. (f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable CHEMISTRY SECTION procedures. (g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 1/2 Rl0 5415, and provides an alarm to plant operators when the 1/2 RIC 5415 adjustable setpoint has been exceeded. (i) When this monitor is operable, a value for the adjustable alarm setpoint shall be calculated prior to each release of a WGDT, each containment vent, and each containment purge as shown below. x (2) Calculating the adjustable setpoint for 1/2 RIC 5415
Offut] Dos] C:lcut: tion M:nu:1 Pa03119 of 313 Revision 2, Chango 0 q (a) The adjustable alarm setpoint is based on the specific Q activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the alarm setpoint is calculated l as shown below. ADJUSTABLE ALARM SETPOINT FOR 1/2 RIC 5415 8.m 5, (1.50)( Fe, ) { c' ) { (( F. / Fe ) E,( A, )( ei) ) + Bk0 ) Eq,290' S., = the adjustable alarm setpoint for 1/2 RIC 5415 (microcuries per second) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor responso (unitiess) This safety factor helps ensure the relea e is not L.anecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies. (4) errors assoc'eted with sample analysis, and (5) errors associated with monitor calibrations.' Fu u maximum undiluted radwaste flow rate (cubic meters per second) - Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7. Fm = the estimated main vent stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second) Since the main vent stack flow rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the adjustable setpoint. Use the nominal main vent stack flow th 3, for the appropriate unit, listed on Attachment 7, This nominal main vent stack flow rate is based on the results of an approved engineering test procedure *,
!* Equation 29G has been derived from NUREG-0133, Addendum, page AA 1.
The " analysis errors" and " calibration errors" refer to errors which are within established quahty assurance and quality controllimits (q')
- See ETP 8716. Revision 0, Main Vent Stack Flow Measurement Unit 1", or ETP-8716, l Revision 0,
- Main Vent Stack Flow Measurement Unit 2, completed in November 1987. )
)
( Offsit] Doso Calculation Manu:1 Page 120 of 313 Revision 2. Change 0 The main vent stack flow rate shall be determined, in accordance with approved O procedures, at least once per 6 months (125%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is l responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7, Au = specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or the containment building (microcuries per cuble centimeter) e, = absolute detector efficiency for nuclide, I (microcuries Xe-133 equivalent per microcuries nuclide 1) i The detector efficiency for each radionuclide may be calculated from data collec+ad during calibration of the radiation monitor. Bkg = an approximation of the detector background (microcuries per cubic centimeter) c' = a conversion constant (1E6 cubic centimeters per cubic meter) (3) Documenting the adjustable alarm setpoint for 1/2 RIC 5415 -- (a) Whenever the adjustable setpoint is calculated, the ( specific values chosen for each of the variables shall be ( documented in accordance with approved CHEMISTRY SECTION procedures (e.g., CP 604). (4) Changing the adjustable alarm setpoint for 1/2 RIC 5415 (a) In all cases, the adjustable alarm setpoint shall be set to a value which is less than or equal to the fixed setpoint. (b) If the adjustable alarm setpoint exceeds the maximum range of the monitor, the cetpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (c) CHEMISTRY SECTION procedures (e.g., CP 604) contain administrative controls associated with calculating and approving an adjustable setpcint. (d) Whenever this monitor is operable and this monitor is performing the functions of the PRIMARY MONITOR (see
- Monitors Equivalent to 1 RE 5416" earlier in this section),
the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release of a WGDT, a containment vent, or a containment purge via the main vent.
Offsite Dose Calculation M:nu:1 Pcg3121 of 313 Revision 2 Change 0 , l
- 2. Wide Range Gas Monitor (2 RE 5416)
O { i a) allinformation related to 1 RE 5416 is applicable to the Unit 2 WRGM l with the following 3xceptions(s) i b) Monitors equivalent to 2 RE 5416 4 (1) 2 RE 5415 [the " Westinghouse Plant Vent Stack Monitor") has ' l the capability of providing the measurement and alarm functions , of 2 RE 5416 during times when 2 RE 6416 is declared l 4 inoperable :
. 1 (2) 2 RE 5415 provides redundant monitoring (for 2 RE 5416) at'the !
low end of the concentration ranges (UFSAR 11.2.3.2.12)
- 3. Westinghouse Plant Vent Stact; Monitor (1 RE 5415) .
a) The Westinghouse Plant Vent Stack Monitor contains 2 radiation elements , (1) 1 RE 5414 l (a) particulate detector (b) off line scintillation detector (c) analog output (d) supplies signals to radiation indicator 1/2 RI 5414 (e) values displayed by 1/2 RI 5414 are in units of counts per minute (f) the detector manufacturer is Westinghouse - (2) 1 RE 5415 (a) noble gas detector (b) off line GM Tube (c) analog output f (d) supplies signals to radiation indicator 1/2 RI 5415 (e) values displayed by 1/2 RI 5415 are in units of counts per minute (f) the detector manufacturer is Westinghouse [ j b) Functions of 1 RE 5414 0
, . _ , . . . . . , _ , . . - . - _ _ _ , _ . , . _ , . _ . . , _ _ . . . . , _ . _ .._....,,,..--,.m- . . . _ , . _ . _ . . , _ . . , -
Offsito Dose Calculation M:nu:1 Peg)122 of 313 R; vision 2. Change 0 e (1) The functions of 1 RE 5414 are mentioned here only as a basis I for excluding this rMiation element from the setpoint controls of
\ Control 3.3 3.9.
(2) This radiation element measures particulate activity contained on a moving particulate filter which is 99% efficient for particle clzes greater than 1.0 micron (UFSAR 11.2.3.2.1) (3) The activity contained on the particulate filter is representative of the particulate activity emanating from the Unit 1 Plant Vent Stack. (4) The ODCM will not address alarm setpoints for 1 RE 5414 (particulate monitor) since NUREG-0133, section 5.1.1 states, lt is not considered to be practicable to apply instantaneous alarm and trip setpoints to integrating radiation monitors sensitive to radiolodines, radioactive materials in particulate form and radionuclides other than noble gases." c) Functions of 1 RE 5415' - (1) continuously measure the activity (CPM) of noble gases emanating from the Unit 1 main vent stack (Control 4.11.2.1.2, l Table 4.112) -- (2) continuously indicate (via 1-RI 5415) the activity (CPM) of noble
/ gases emanating from the Unit 1 main vent stack (Control l Q] 4.11.2.1.2, Tcble 4.112) -
(3) alarm (via 1 RI 5415) prior to exceeding the site boundary, noble-gas, total body dose-rate limit of 500 mr/yr (per Control l 3.11.2.1.a) (4) alarm (via 1 RIC 5415) prior to exceeding the site boundary, i noble-gas, skin-dose rate limit of 3000 mrlyr (per Control l 3.11.2.1.a) d) OPERABILITY of 1 RE 5415 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s). (2) The functions of 1 RE 5415 are listed in section (c) above, e) Monitors equivalent to 1 RE 5415 (1) The Wide Range Gas Monitor (i.e.,1 RE 5416) has the capability of providing the measurement and alarm functions of 1 RE 5415 during times when 1 RE 5415 is declared inoperable. ( This (radiation element) monitors noble gases. Other radiation elements monitor particulates in i V this waste stream.
Offssia Dose Calculation M:nu:1 Pcg3123 of 313 Revision 2 Change o (2) 1 RE 5415 provides redundant monitoring (for 1 RE 5410) at the low end of the concentrction ranges (UFSAR 11.2.3.2.12). (o] (3) 1 RE 5415 is normally considered the PRIMARY MONITOR for moasuring noble gas activity released via the Unit 1 Plant Vent Stack, and 1 RE 5416 is normally considered the BACKUP MONITOR for measuring noble gas activity released via the Unit 1 Plant Vent Stack. (4) In the event PRIMARY MONITOR (1 RE 5415)is inoperable or i otherwise unavailable, the BACKUP MONITOR (1 RE 5416)is l able to fulfill the measuring, indicating, and alarming functions - normally provided by the PRIMARY MONITOR. (5) The absence of a radiation eternent dedicated to measuring the particulate activity in the Wide Range Gas Monitor does not preclude the use of 1 RE 5416 as a backup for 1 RE 5415. This is mentioned only as a basis for excluding 1/2 RE 5414 from the setpoint controls of Control 3.3.3.9 (see " Functions of 1 RE 5414" l oorlier in this sectiort - f) Radiological effluent contre N e i#i 5415 (1) Control 3.3.3.9 states that releases via the plant vent stack may l -- continue if any one of the following three conditions are satisfied () V (a) 1 RE 5415 is operable AND the alarm and trip setpoint(s) for 1 RI 5415 are set to ensure the annual dose rates due ' to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total bcdy and are less than 3000 mrlyr to the skin (per Control 3.11.2.1.a), or (b) an " equivalent monitor" (see section (e) above) is operable AND the alarm and trip setpoint(s) for the
" equivalent monitor" are set to ensure annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1,a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours in accordance with Controls 3.11.2.1.a, 4.11.2.1.1, and 4.11.2.1.2 (per Control 4.3.3.9, l Table 3.3-12, ACTION 37).
(2) Control 3.11.2.1.b (i.e., dose rates due to iodines and particulates l at the SITE BOUNDARY) is not applicable to noble gas detector or to the setpoints related to the noble gas detector 1 RE 5415. As a result, the 1500 my/yr organ dose limit is not included as a radiological effluent controlin this section of the ODCM, g) Surveillances for 1 RE 5415 O
Offsite Dose Ccicut: tion Manu:1 Page 124 of 313 Revision 2 Change 0 ,o Control 4.3.3.9 requires demonstrating the OPERABILITY of 1-y) (1) RE 5415 by satisfying the chocks, cahbrations, and tests listed below; l (a) CHANNEL CHECK within the past 24 hours (b) SOURCE CHECK within the past 31 days (c) CHANNEL CAllBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months + h) Setpoints for 1 RI 5415 (1) Requirements and commitments (a) The alarm and trip setpoints ... shall be determined and adjusted in accordance with tqe methodology and parameters of the ODCM. (Control 3.3.3.9) - (b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM, (NUREG 0133,5.1.1) (2) There are three alarms associated with, or otherwise related to, 1 RE 5415. m 1 RI 5415 fixed high radiation alarm setpoint -
~. 1 RI 5415 adjustable plant computer high radiation alarm setpoint (c) 1 Rl 5415 low radiation alarm setpoint (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows (a) The 1 RI 5415 fixed high radiation alarm setpoint will be referred to as the fixed setpoint.
(b) The 1 RI 5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable setpoint. (c) The 1 RI 5415 low radiation alarm setpoint will be referred to as the low setpoint. (4) Each of these alarm setpoints are described below, l) The fixed setpoint for 1-RI-5415 g (1) Generalinformation ,
l Offsit) Dose C:lcul: tion M:nu:I Pag)125 of 313 R; vision 2, Ch:ng) 0 l - V() (a) This setptsint is considered to be a fixed setpoint. The fixed setpoint is not adjusted for each release. (b) Whenever the fixed setpoint is exceeded, an alarm will be generated, (c) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. (d) The CCNPP Alarm Manual refers to this setpoint as the 1 Rl 5415 High Radiation Alarm Setpoint. (e) The fixed setpoint is integral to the Main Vent (Westinghouse) RMS as purchased from the supplier. (f) The fixed setpoint is administratively controlled by EN 1-100. (g) The fixed setpoint shall be calculated es described below'. (2) Calculating the fixed setpoint for 1 Rl 5415 (a) The fixed high radiation alarm setpoint for 1 RI 5415 -- (plant vent stack monitor) shall be calculated in accordance with equation 4G. f3 V THE FIXED HIGH ALARM SETPOINT FOR 1 RI 5415 S n, 5 ( Ko / [( x/Q )( Fai + F43 ) } } % [( ei)( Au )) Eq. 4G' Sn, = the fixed radiation alarm setpoint for 1 RI 5415 (counts per minute) Ku = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, Lu,3c, used in equation 2G (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, LMPc, used in equation 2G. A safety f actor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, LMPc, in equation 2G. A safety factor of 0.500 will yield a fixed high setpoint which corresponds to one-half the MPC limit, LMPc, in equation 2G. It is recommended that a safety factor of 1.0 be used for calculating the fixed setpoint, however, other values not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9). (y , Equation 4G has been derived from NUREG 0133,5.2.1, (the 500 mrlyr equation). l 1
P OffsNe Dose C:lculation M:nu:1 Pcge 126 of 313 i Revision 2. Change 0 The particular value selected for the safety factor is somewhat arbitrary, however a ! O safety factor does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits, The use of a safety factor is consistent with the ALARA philosophy that licensees . should make every reasonable effort to maintain radiation exposures, and releases 1 of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is ! reasonably achievable. The use of a " safety margin"is in accordance with the provisions of NUREG 0133, section 5.1.1, which states that "... the alarm and trip setpoints .. should correspond - to a value(s) which represents a safe margin of casurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." { This safety margin will prevent minor fluctuations in the nominal plant vent stack ' flow rates, errors 'n detector efficiencies, and other statistical aberrations from adversely impacting the calculated fixed setpoint, 40 = the highest calculated annual average relative concentration for any area ator . 4 beyond the UNRESTRICTED AREA boundary (2.2E 6 seconds per cubic meter) ' Unit i and Unit 2 main vent releases are considered "long term" releases i, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the . setpoint calculations. O The highest annual average dispersion factor (x/Q) is 2.2E 6 (UFSAR,2.3.6.3) for L/ purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long term i concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). F oi = the estimated main vent stack flow rate for Unit 1 (cubic meters per second) Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high setpoint. i Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. This nominal main vent stack flow rate is based on the results of an approved eng{neering test procedure'. . e T
' NUREG 0133,3.3 2
See ETP 8716. Revision 0," Main Vent Stack Flow Measurement - Unit 1", completed in November 1987.
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Offsit] Dose Calculation Manual Page 127 of 313 Revision 2, Change O n The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%). The Test and Equipment Unit (b) shall be responsible for performing this test. The results of the main vent flow rate ! test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event I the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.
= the estimated main vent stack flow rate for unit 2 (cuble meters per second)
Fe Since the main vent stack flow rate will vary depending on the configuration of air - dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high setpoint. Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. This nominal main vent stack flow rata is based on the results of an approved engineering test procedure \ The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated tc ensure the main vent flow rates used in the ODCM are an .- accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event ( the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is - (]) greater than the maximum discharge flow rates listed on Attachment 7. - e, = atsolute detector officiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. A,tn a the specific activities of radionuclide, I, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated in accordance with 10 CFR 20, Appendix B, Table 11, Note 1 as described below; microcuries per milliliter) Calculate A,tn in accordance with equation SG. SPECIFIC ACTIVITY LIMIT FOR NUCLIDE IIN A RADIONUCLIDE MIXTURE Aitn = Eq. 50 { fe )( Ann ) f, = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value may be obtained using the guidance provided on Attachment 5. (V See ETP 8716, Revision 0. " Main Vent Stack Flow Measurement Unit 2", comp 5ted in November 1987.
Offse Dose Calculation M:nual Page 128 of 313 Revisio i 2, Change 0 Aya = the sum of the total specific activities of all noble gas radionuclides found in ' TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3) l Calculate Arm in accordance with equation 2G .
- SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT '
i ! E [( fa)( An. )) / Au 5 Lwo Eq 20' LMrc .= the MPC limit - The value chosen for Lupe in this equation is 2. The basis for this limit is 10 CFR 50.72. , P
- it has been shown' that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of !
Controf 3.3.3.9. . It should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into l equation 2G. The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-t 0133, section 5.1.1, which states that, "... In all cases, conservative assumptions j O may be necessary in establishing these setpoints to account for system variables,
... the variability in release flow, ... and the time lag between alarm and final isolation of radioactive effluents."
An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4 hout NRC notification"(specified in 10 CFR 50.72) is required. The use of a limiting specific activity equivalent to 2 MPCs is consistent with the , provisions of 10 CFR 20.1302. - A,u = the specific activity limit for radionuclide, I, as obtained from 10 CFR 20, Appendix -
- B, Table ll, Column 1 (microcuries/cm3)
For all the DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B Table 11, Column 1. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E 14 microcuries per milliliter as the value for As
-(per 10 CFR 20. Appendix B, Note 2).
~
4 (3)- The low alarm setpoint for 1 RI 5415 : ' i Equation 2G has been derived from 10 CFR 20. Appendix B. Table 11 Note 1.
- Addendum To Setpoint Calculations For WRGM Monitors 1 RIC 5415 and 2-RIC 5415 R.L N Conatser, December 10,1991. i t.
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.rs.- ..,--- .--- er--.. - - - . . - - - - . . -
Offsate Doso C:lculation M:nu 1 Pag) 129 of 313 Revision 2, Change 0 (^^j (") '"" """'"'"*""***"'"'"''' with the low alarm retpoint, 1 (b) The low alarm setpoint is specified in the CCNPP Alarm Manual. (c) The !ow alarm setpoint may be used to determine OPERABILITY of this monitor (in accordance with the provisions of Control 4.3.3 9, Table 4.311, Note 2). (4) Adjusting the fixed setpoint for 1 RI 5415 (a) If the fixed setpoint calculated in accordanco with equation 4G exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed setpoint may be established at values lower than the rnaximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenover any of the parameters identified in equation 4G have changed. (d) The fixed setpoint should not be changed unless one of .- the following occurs: O i) the relative activity' of any radionuclide in (V TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the historical maximum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, Iv) the estimated Unit 1 main vent stack flow rate or Unit 2 main vent stack flow rate has changed by greater than or equal to 10%', v) the values listed in 10 CFR 20, Table 11, column 1 have changed, vi) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or vii) the monitor is not conservative in its function (see section " Functions of 1/2 RE 5415" earlier in this section). O , i As determined in accordance wit 5 Attachmant 5.
'N #
As determined by analysis of the TE 001 and ETP-8716 test results.
Offsito Dose C:lculation Manual Page 130 of 313 Revision 2, Change 0 (e) EN 1 100 contains the administrative controls associated l with changing and approving fixed alarm setpoint. j) Adjustable alarm setpoint for 1/2 RI 5416 (1) General information (a) This setpoint is an adjustable setpoint. Whenever this radiation monitor is operable, the adjustable setpoint is calculated and adjusted' prior to each release of a WGDT, each containment vent, and each containment purge discharged Wa the main vent. (b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable CHEMISTRY SECTION procedures as required by Control 4,11.2.1.2). - (c) Whenever the adjustable setpoint is exceeded, the WGDT, PURGE, or vent discharge via the main vent will be manually suspended. . (d) Refer to the Alarm Manual for a fulllist of operator N ACTIONS taken in response to this alarm.
} (e) The adjustable setpoint corresponds to the maximum contentration of radionuclides anticipated or expected when discharging a WGDT, a contsinment ven;, or a containment purge via the main vent.
(f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable CHEMISTRY SECTION procedures. (g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 1/2 RI 5415, and provides an alarm to plant operators when the 1/2 R! 5415 adjustable setpoint has been exceeded. The adjustable setpoint may or may not be changed for each of the releases listed here. A determination of whether to change the setpoint would only be required when conducting simultaneous releases (l.o., if a purge or a vent is conducted while a WGDT is also being released), in this case, two adjustable setpoints would be calculated (i.e., one adjustable setpoint for tne vent or purDe and one adjustable setpolni for the WGDT). In tha case of /7N simultaneous releases, the lower (more conservative) of the two adjustable setpoints should La V Input into the plant computer.
Off6663 Dose C:lculation M:nual Pa03131 of 313 R: vision 2, Change 0 (i) When this monitor is operable, a value for the adjustable O alarm setpoint shall be calculated prior to each release of a WGDT, each containment vent, and each containment purge as shown below. l (2) Calculating the adjustable setpoint for 1/2-RI 5415 (a) The adjustable alarm setpoint is based on the specific , activity of the radionuclides in the undiluted gaseous ! waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the alarm setpoint is calculated l as shown below, , i ADJUSTABLE Al. ARM SETPOINT FOR 1/2 RI 5415 . s..; <: 1,50 ( F./ Fe,)[E ( A,o )( ei) + Bkg ) Eq,270' S,aj =. the adjustable alarm setpoint for 1/2 RI.5415 (cpm) -
. t 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess) >
This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector officiencies, O (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.' Fu = maximum undiluted radwaste flow rate (cubic meters per second) Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7. t Fe, = the estimated main vent stack (diluted gaseous radwaste) flow rate for unit x (cubic metere per second) Since the main vent stack flow rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the adjustable setpoint. Use the nominal main vent stack flow rate, for the appropriate unit, listed on Attachment 7. This nominal main vent sta k flow rate is based on the results of an approved engineering test procedure Equation 27G has been derived from NUREG 0133, Addendum, page AA 1, 3 The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and ouality controllimits. O8 See ETP 8716 Revisivn 0,' Main Vent Stack Flow Measurement Unit 1*, or ETP 8710, Fevision 0, " Main Vent Stack Flow Measurement - Unit 2, completed in November 1987.
Offsita Dose Calculation M:nual Page 132 of 313 Revision 2, Change 0 The main vent stack flow rate shall be determined, in accordance with approved ( procedures, at least once per 6 months (t 25%). The Test and Equipment Unit L shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is l responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7. Au = specific activity of radionuclido, I, in the undiluted waste stream, either the WGDT or containment building as applicable (microcuries por milliliter) l e, = absoluto detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector officiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Okg = an approximation of the d,tector background (cpm) (3) Documenting the adjustable alarm setpoint for 1/2 RI 5415 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be -- documented in accordance with approved CHEMISTRY SECTION procedures (e.g., CP-604). (4) Changing the adjustable alarm setpoint for 1/2 RI 5415 - (a) In all cases, the adjustable alarm setpoint shall be set to a value which is less than or equal to the fixed setpoint. (b) If the adjustable alarm setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (c) CHEMISTR'l SECTION procedures (e.g., CP 604) contain administrative controls associated with calculating and approving an adjustable setpoint. (d) Whenever this monitor is operable and this monitor is performing the functions of the PRIMARY MONITOR (see
" Monitors equivalent to 1 RE 5415" earlier in this section),
the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release of a WGDT, a containment vent, or a containment purge via the main vent. k) The low alarm setpoint for 1/2 Rl 5415 c (1) This alarm is integral to the main vent monitor, as purchased from the supplier.
OffWie Dose C:lculati:n M:nual Page 133 of 313 f Revision 2, Change 0 (2) The current value for the low alarm setpoint is specified in the > O CCNPP Alarm Manual. The low alarm setpoint may be used to determine the (3) . OPERABILITY of this monitor (per Control 4.3.3.9, CHANNEL l FUNCTIONAL TEST). (4) The alarm generated by the low alarm setpoint may be used to ' terminate a release in the event 1/2 Rl 5415 falls (i.e., downscale failure or circuit failure) in accordance with Control 4.3.3.9. , (5) The low alarm setpoint calculations are not described in the . i ODCM. (0) Changes to the low alarm setpoint are controlled by EN 1 100. , 4. Westinghouse Plant Vent Stack Monitor (2 RE 5415) a) Allinformation related to 1 RE 5415 is applicable to the Unit 2 plant vent stack monitor with the following exception (s): - b) Monitors equivalent to 2 RE 5415 (1) 2 RE 5410 [the "WRNGM"] has the capability of providing the - measurement and alarm functions of 2 RE 5415 during times when 2 RE 5415 is declared inoperable. (2) 2 RE 5415 provides redundant monitoring [for 2 RE 5416J at the low end of the concentration ranges (UFSAR 11.2.3.2.12).
- 5. Gaseous Radwaste Treatment System Radiation Monitor (0-RE 2191) a) General description (1) The GASEOUS RADWASTE TREATMENT SYSTEM Radiation Monitor (Waste Gas Decay Tank Radiation Monitor) contains 1 radiation element.
(2) It is a noble gas detector. (3) The detector is an in line GM tube (UFSAR, Table 11 10). (4) The radiation element is designated 0 RE 2191. l (5) The radiation indicators designated 0-RI 2191. (6) The units for the radiation indicator are counts per minute. l (7) The monitor was manufactured by Westinghouse, b) Functions of 0 RE 2191 , O
OffsiD Dose Cricuillion M:nu:1 Pcg3134 of 313 Revision 2, Change 0 j n (1) continuously measure the release rate of noble gases emanating yi from the waste gas decay tank discharge header (Control l 4.11.2.1.2 Table 4.112) (2) continuously indicate (vla 0 Rl 2191) the activity (CPM) of noble gases emanating from the waste gas decay tank discharge header (Control 3.3.3.9 OPERABILITY requirement) (3) alarm (via 1 Rl 2191) prior to exceeding the site boundary, noble-gas, total-body dose-rate limit of 500 mr/yr (per Control l 3.11.2.1.a) (4) alarm (via 1 RI 2191) prior to exceeding the site boundary, noble. ) gas, skin dose rate limit of 3000 mrlyr (per Control 3.11.2.1.a) ; c) OPERABILITY of 0 RE 2191 (1) This monitor shall be operable (or have OPERABILITY) when it is : capable of performing its specified function (s). (2) For mor6 information on the function (s) of this monitor, see
- Functions of 0-RE 2191" elsewhere in this section of the ODCM.
i d) Monitors equivalent to 0-RE 2191 -- (1) There are no equivalent monitors associated with 0 RE 2191 O since there are no other radiation monitors permanently installed in the waste gas discharge header, however, Control 3.3.3.9 defines the plant vent stack monitor as a " BACKUP MONITOR." l (2) 0 RE 2191 is designated the PRIMARY MONITOR for measuring noble gas activity released via the GASEOUS RADWASTE
. TREATMENT SYSTEM. !
(3) 1 RE 5415 (or 1 RE 5410)is designated the BACKUP MONITOR
- if the WGDT is discharged via the Unit 1 main vent.
(4) 2 RE 5415 (or 2 RE 5416)is designated the BACKUP MONITOR if the WGDT is discharged via the Unit 2 main vent. ! (5) WGDTs are normally discharged through the Unit 1 main vent stack, (6) The BACKUP MONITOR has the capability of ensuring the noble gas activity released from the GASEOUS RADWASTE TREATMENT SYSTEM to the plant vent stack--does not exceed Control 3.11.2.1(a) at the SITE BOUNDARY (Control 3.3.3.9). O .
. , . -4.-.....-w %, ~ . - ..-,--sw.~ v --.w-
Offsit] Dose C:lculation M:nu:1 Peg)135 of 313 R; vision 2. Change 0 g (7) In the event PRIMARY MONITOR (0-RE 2191) is inoperable or ( otherwise unavailable, the designated BACKUP MONITOR L (either 1 RE 5415,1 RE 5416,2 RE 5415, or 2 RE 5416)is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR as long as plant operators record the BACKUP MONITOR readings overy 15 minutes (Control 3.3.3 0, Table 3.312, ACTION 35a). e) Radiological effluent controls for 0-RE 2191 (1) Control 3.3.3.9 states that releases via the GASEOUS l RADWASTE TREATMENT SYSTEM may continus if ANY ONE of the following three conditions are satisfied: (a) 0 RE 2191 is oparablo AND the alarm and trip setpoint(s) for 0 RI 2191 are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Control 3.11.2.1.a), or (b) One
- BACKUP MON! TOR" (see section (e) above) is operable; AND the " BACKUP MONITOR" readings are recorded every 15 minutes during the release; AND the alarm and trip setpoint(s) for the " BACKUP MONITOR" -
are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to A the total body and are less than 3000 mr/yr to the skin V (per Control 3.11.2.1.a), or (c) All three activities desenbed below are completed prior to the release: i) at least two independent samples of the waste gas decay tank's contents are analyzed, and lii at least two technically qualified members of the Facility Staff independently verify the release rate calculations, and lii) two qualified operators verify the discharge valve lineup. f) Surveillances for 0-RE 2191 (1) Control 4.3.3.9 requires demonstrating the OPERABILITY of 0- l RE 2191 by satisfying the checks, calibrations, and tests listed beiow (a) CHANNEL CHECK prior to each release (b) SOURCE CHECK prior to each release h b (c) CHANNEL CAllBRATION within the past 18 months
( Offsit] Dose C:lculation Minu I Pag 3136 of 313 Revision 2, Change 0 g , (d) CHANNEL FUNCTIONAL TEST within the past 6 six i months g) Setpoints for 0 Rl.2191 (1) Requirements and commitments (a) The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9) (b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM. (NUREG-0133,5.1.1) (2) There are three radiation alarm setpoints associated with, or otherwise related to,0 RE 2191. (a) 0 RE 2191 fixed high radiation alarm and automatic control trip setpoint (b) 0-RE 2191 adjustable plant computer high radiation alarm and manual control trip setpoint (c) 0-RE 2191 low radiation alarm setpoint - (3) in order to simplify the setpoint terminology, eliminate ambiguity, Q V and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows * (a) The 0-RE 2191 fixed high radiation alarm and auto'rnf.c control trip setpoint will be referred to as the fixed setpoint. (b) The 0-RE 2191 adjustable plant computer high radiation alarm and manual control trip setpoint will be referred to as the adjustable setpoint. (c) The 0-RE 2191 low radiation alarm setpoint will be referred to as the low setpoint. (4) Each of these alarm setpoints are described below. h) Fixed setpoint for 0-RI 2191 (1) General information (a) This setpoint is considered to be a fixed setpoint. The fixed setpoint is not adjusted for each release. (b) The fixed setpoint is an alarm and trip setpoint. (g v j (c) Whenever the fixed setpoint is exceeded, an alarm will be generated, and the WGDT release will be automatically suspended.
OffWie Dose Calculation M:nual Pag)137 of 313 Revision 2. Change 0 (d) The fixed setpoint corresponds to the maximum O concentration of radionuclides allowed (by equation 6G) in gaseous waste discharged from the gaseous radwaste - j processing system. ; (e) The current value for the fixed setpoint is specified in the , CCNPP Alarm Manual. (f) The CCNPP Alarm Manual refers to this setpoint as the 0 . RI 2191 High Radiation Alarm Setpoint.
)
(g) The fixed setpoint is integral to the waste gas discharge - monitor, as purchased from the supplier, (h) The fixed setpoint is administratively controlled by EN 1 100. (i) The fixed setpoint shall be calculated as described below', (2) Calculating the fixed setpoint for 0 RI 2191 (a) The fixed alarm and trip setpoint for 0 RI 2191 (waste gas discharge monitor) shall be calculated as described . below: FlXED ALARM AND TRIP SETPOINT FOR 0-RI 2191 . Sn. 5 K., { { 1/ [( x/Q )( F. )] } E [( ei)( Au )] + Bkg ) Eq.60' , Where, Kg = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, Lupe, used in equation 2G (unitiess)
- The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, Lupc, used in equation 2G.
A safety factor of 1.00 is used for calculating the fixed setpoint. l By setting the safety factor to 1, the safety factor is disabled. Although it may appear that if this safety factor is set to 1.0, no safety margin exists, in actuality, another margin of safety has been incorporated into equation 2G (see definition of Lupe). A safety factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, Lupc. in equation 2G. The alarm and trip setpoints ... shall be determined and adjusted in accordance with the O. methodology and parametem of the ODCM. (Control 3.3.3.9). Equation 6G has been derived from NUREG-0133,5.2.1, (the 500 mr/yr equation). r
- - - - - . - - . - ~ . - _ _ - - - - --- - _ - - - -
i Offse Dose Ccicublon M:nu:1 Page 138 of 313 Revision 2, Change 0 l p A safety factor of 0.500 will yield a fixed high setpoint which corresponds to one- I half the MPC limit, Luec,in equation 2G. l Other values of safety factors-not to exceed 1,00-may be used for calculating the fixed setpoint as directed by the General Supervisor Chemistry. l The particular value selected for the safety factor is somewhat arbitrary, however a f value less than or equal to 1.0 does provide plant personnel with adequate time to : l respond to changing plant conditions and to initiate corrective ACTIONS so as to i minimize the possibility of v%lating either the 10 CFR 50.72 limit or the Control l 3.3.3.9 limits. t
- The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases '
of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is ; reasonably achievable. The use of a " safety margin"is in accordance with the provisions of NUREG 0133 which states that "... the alarm and trP setpoints ... should correspond to a value(s)- which represents a safe margin of assurance that the instantaneous gaseous . release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG 0133, l 5.1.1). This safety margin will prevent minor fluctuations in the nominal WGDT discharge - flow rates, errors in detector efficiencies, and other statistical aberrations from adversely impacting the calculated fixed setpoint. Sr, a the fixed radiation alarm setpoint for 0 Rl 2191 (CPM) ' , x/Q = the highest calculated historical annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E 6 seconds per cubic l meter) A waste gas decay' tank release via the Unit 1 or Unit 2 main vent is considered a "long term" release , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations. The highest annual average dispersion factor (x/Q) is 2.2E 6 (UFSAR,2.3.6.3) for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.0.3). The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine,long term
- concentrations (e.g./ routine noble gas releases)(UFSAR,2.3.6.3).
Fu = the estimated _ maximum flow rate of undiluted gases through the waste gas discharge heador (cubic meters per second) Since WGDT pressure is the motive force for discharge of a WGDT, the waste gas e flow rate will continually decrease as the release progresses (i.e., as tank pressure
~ '
Is decreased). t w t - NUREG 0133,3.3 i
( Offsit3 Doso C:lcul: tion Minuil P:ge 139 of 313 Revision 2, Change 0 q Use the estimated maximun: WGDT discharge flow rate, listed on Attachment 7, to Q calculate the fixed setpoint. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. A etn a the specific activities of radionuclide, i, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated in accordance with 10 CFR 20, Appendix B, Table ll, Note 1 as described below; microcuries per milliliter) Calculate A,tn in accordance with equation SG SPECIFIC ACTIVITY LIMIT FOR NUCLIDE IIN A RADIONUCLIDE MIXTURE Aia = ( fi )( Atu ) Eq. 60 f, = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess)
~
This value may be obtained using the guidance provided on Attachment 5. A 7tn = the sum of the total specific activities of all noble gas radionuclides found in Os TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3). Calculate A ttn in accordance with equatiun 2G. SPECIFIC ACTIVITY OF NOBLE GASES AT THE SITE BOUNDARY
% [( fi )( Ara )) / Au 5 Lwe Eq. 2G' Where, Lupe = the MPC limit The valae chosen for LMrc in this equation is 2. The basis for this limit is 10 CFR 50.72.
It has been shown' that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Control 3.3.3.9.
,c [ Equation 2G has been derived from 10 CFR 20. Appendix B Table 11, Note 1.
t Addendum To Setpoint Calculations For WRGM Monitors 1 RIC 5415 and 2 RIC 5415, o ( .
\- Conatser, December 10.1991.
i
Offsit] Dose C:lculation M:nu:1 Pag) 140 of 313 R: vision 2, Ch:nge 0 it should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into k]_/ equation 2G. The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-0133, section 5.1.1, which states that, " .. In all cases, conservative assumptions may be necessary in establishing these setpoints to account for system variables,
. the variability in release flow, . , and the time lag between alarm and final isolation of radioactive effluents."(NUREG-0133,5.1.1)
An alarm sotpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4 hour NRC notification"(specified in 10 CFR 50.72)is required. A,u = the specific activity limit for radionuclido, I, as obtained from 10 CFR 20 Appendix B. Table 11, Column 1 (microcuries/cm3) For all the DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table ll, Column 1. For each of the LESS DOMINANT RADIONUCLlDEs found in TYPICAL
- RADWASTE EFFLUENTS, use 2E 14 microcuries per milliliter as the value for A iu (per 10 CFR 20, Appendix B, Note 2).
Okg = an approximation of the detector background prior to initiating the gaseous release -- (cpm) (q x Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. ' (3) Documenting the fixed setpoint for 0 RI 2191 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the vanables shall be documented in accordance with EN 1 100. (4) Changing the fixed setpoint for 0 RI 2191 (a) If the fixed setpoint calculated in accordance with equation GG exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating ange of the monitor. (b) The fixed setpoint may be estatlished at values lower than the maximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenever any of the parameters identified in equations 2G, SG, or 6G have changed. (d) The fixed setpoint should not be changed unless one of the following occurs: O V
Offsite Dose Calculation Manu:1 Pag)141 cf 313 i Revision 2, Change 0 l ,o i) the relative activity' of any radionuclide in l TYPlCAL GASEOUS EFFLUENTS has changed tb) by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the historical maximum annual average atmospheric dispersion factor 'nas changed, lii) the MPC limit at the SITE BOUNDARY, (presently i 2 MPCs) has changed, Iv) values ksted in 10 CFR 20, Table 11, column 1 have changed, v) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or vi) the monitor is not conservative in its function (see section
- Functions of 0 RE 2191" eartier in this ,
section). (e) EN 1 100 contains the administrative controls associated l with changing and approving fixed alarm setpoint. --
- 1) Adjustable alarm setpoint for 0 Rl 2191 G
b) (1) Generalinformation (a) This setpoint is an adjustable setpoint. Whenever this radiation monitor is operable, the adjustable setpoint is calculated and adjusted
- prior to each release of a WGDT.
(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the WGDT. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable CHEMISTRY SECTION procedures as required by Control 4.11.2.1.2). (c) Whenever the adjustable setpoint is exceeded, the WGDT discharge will be manually suspended. (d) Refer to the radwaste Alarm Manual for a full list of operator ACTIONS taken in response to this alarm. As determined in accordance with Attachment 5. The adjustable setpoint may or may not be changed for each WGDT release. A determination of whetner to chan00 the setpoint would only be required when conducting simultaneous releases (Le., if a purge or a vcnt is conducted while a WGDT is also being released). In this case, two m adpstable setpoints would be calculated (i.e., one adjustable setpoint for the vent or purge and [V T one % ,,. Mble setpoint for the WGDT). In the case of simultrincous releases, the lower (more conservat,ve) of the two pdjustable setpoints should be input into the plant computer.
l Offsite Dose C:lculation M:nual Pag)142 of 313 Revision 2 Change O n (e) The adjustable setpoint corresponds to the maximum I
- ] concentration of radionuclides anticipated or expected k when discharging a WGDT.
(f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable j CHEMISTRY SECTION procedures. (g) This alarm is not integral to the GASEOUS RADWASTE TREATMENT SYSTEM radiation monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 0-RI 2101, and provides an alarm to plant operators when the 0-RI 2191 adjustable setpoint has been exceeded. (i) When this monitor is operable, a value for the adjustable alarm and trip setpoint shall be calculated prior to each release of a WGDT as shown below. -
,2) Calculating the adjustable setpohit for 0 Rl 2191 (a) The adjustable alarm and trip setpoint is based on the -
specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis Q per Control 4.11.2.1.2), and the alarm and trip setpoint is l h calculated as shown below. - ADJUSTABLE ALARM AND TRIP SETPOINT FOR 0-RI 2191 S.m $ 1.60 [E ( A4. )( ei) + Bkg ) Eq.28G' S,aj = the adjustable alarm and trip setpoint for 0 RI 2191 (cpm) 1.50 = a constant, actually a safety f actor, which allows for fluctuation in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.' Fu = maximum allowed undiluted radwaste flow rate (cubic meters per second) The maximum allowed undiluted radwaste flow rate for a WGDT is tabulated in Attachment 7. g Equation 28G has been derived from NUREG-0133, Addendum, page AA 1. l
- V; The ' analysis errors
- and ' calibration errors" refer to errors which are within established quality assurance and quality controllimits.
Offsits Dose C:lculation M:nual Pags 143 of 313 Revision 2, Change O
= specific activity of radionuclide, I, in the undil'/ted waste stream (microcuries per Ao milliliter) e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter)
The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (cpm) ; (3) Documenting the adjustable alarm setpoint for 0 RI 2191 -
! t (a) Whenever the adjustable setpoint is calculated, the ;
specific values chosen for each of the variables shall be ' documented in accordance with approved CHEMISTRY SECTION procedures (e.g., CP 604), (4) Changing the adjustable alarm setoolnt for 0 Rl 2191 (a) in all cases, the adjustable i.etpoint shall be set to a value
- which is less than or equal to the fixed setpoint.
(b) If the adjustable setpoint exceeds the maximum range of -- l the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the i monitor. (c) CHEMISTRY SECTION procedures (e.g., CP 604) contain administrative controls associated with calculating and approving an adjustaole setpoint. (d) Whenever this monitor is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release of a WGDT via the main : vent, j) The low alarm setpoint for 0-Rl 2191 (1) This alarm is integral to the main vent monitor, as purchased from the supplier. (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. (3) The low alarm setpoint may be used to determine the OPERABILITY of this monitor (per Control 4.3.3,9, CHANNEL l FUNCTIONAL TEST). (4)- The alarm generated by the low alarm setpoint may be used to terminate a release in the event 0-RI-2191 fails (i.e., downscale failure or circuit failure) in accordance with Control 4.3.3.9. n- - - < - , + n,~,,, -v-,- - - ----,,w, r- ,.-nna.m-,-r,--+-we,
Offsit) Dose C:lculation M nu:1 Peg)144 of 313 Revision 2, Change 0 (5) The low alarm setpoint calculations are not described in the O ODCM. (6) Changes to the low alarm setpoint are controlled by EN 1 100. ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS
- 1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of l radioactive materials to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.1301. The 10 CFR 50 Appendix 1, Design Objectives for ALARA Radioactive Effluents, upon which these calculations are based, are more restrictive than the public dose limits of 10 CFR 20.1301. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The annual total body dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 500 mr/yr --
(per Control 3.11.2.1). ,
, C] b) The routine surveillances which are performed to verify compliance with this radiological effluent control is described below. -
- 3. Surveillance Requirement a) The annual total body dose rate, due to noble gases in all gaseous effluents discharged from the site, shall be determined in accordance with equation 7G (per Control 4.11,2.1.1).
b) The results of the radioactive gasece' waste sampling and analysis program (required by Control 4.11.2.1.2, and implemented by various l CCNPP CHEMISTRY SECTION procedures) are used to calculate the annual total body dose rato due to noble gases in gaseous effluents. c) The plant group (s) responsible for performing the required surveillances are identified below.
- 4. Responsible Plant Organization (s) a) The CHEMISTRY SECTION is responsible for calculating the annual iotal body dose rate due to noble gases in gaseous effluents, b) The CCNPP CHEMISTRY SECTION calculates the annual total body dose rate whenever the appropriate initiating conditions are present.
c) These initiating conditions are contained in the following section. O' 5. Initiating Conditions
Of fsit] Doso Ccicul: tion M:nu;l Pags 145 of 313 ! Revision 2, Change 0 (g a) The annual total body dose rato due to noble gases in gaseous offluents is calculated for each release of a WGDT. b) The annual total body dose rato due to noble gases in gaseous effluents is calculated for each vent of a containment building. c) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each PURGE of a containment building. d) The annual total body dose rate due to noble gases in gaseous effluents is calculated at least weekly' for CONTINUOUS discharges from plant vent stacks. e) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each discharge of combustion products resulting from the burning of contaminated oil, f) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE (as defined in CP-612). g) Whenever the correct initiating conditions are present, the annual total body dose rates shall be calculated as described below.
- 6. Calculation Methodology (w
s a) The annual total body dose rate, at the SITE BOUNDARY, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall - be calculated in accordance with equaCon 7G.* ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN ALL GAS RELEASES De = % D, Eq.7G
= the site-boundary annual total body dose rate due to noble gases in all gaseous Doi effluents discharged (simultaneously) from the site (mrem / year)
Dy = the site boundary annual total body dose rate due to noble gases in release, r (mrem / year) Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclidos from the Unit 1 plant vent stack while also discharging noble gases from the Unit 2 plant vent stack. The frequency is controlled by the implementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control l 4.11.2.1.1 or 4.11.2.1.2, Table 4.112). The alami and trip setpoints . shall be determined and adjusted in accordance with the [mV) methodology and parameters of the ODCM. (Control 3.3.3 9). I
Offdt2 D:se Cciculation M:nuit Pcge 146 of 313 i R vision 2. Ching3 0 An example of a SIMULTANEOUS RELEASE would include the release of noble [] (/ gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. Calculate the values of D,t for each SIMULTANEOUS RELEASE as shown below. b) At CONPP, two methods exist for calculating D,,(i.e., annual total body dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site). (1) The rigorous method sha!! be used IF a computer system and the - appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software . are available.
!p (2) If a computer system and the appropriate software are available, I
V the annual total body dose rato due to noble gases in gaseous - effluents discharged from the site to UNRES TRICTED AREAS shall be calculated in accordance with equation 8G. ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD) Dri = ( x/Q ) [E ( Ki ) ( Oi , )] Eq.8G' Where, x/O = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) 2 All releases are considered "long-term" releases , and as such, the highest historical annual average dispersion factor, (x/Q), is used iri the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routirie, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) Equations 8G has been derived from NUREG-0133,6.2.1, and Regulatory Guide 1.109 (] (,,) (Appendix B, Equation B-8 and Section C.2.e). NUREG-0133, 3.3 I I l
! Offsit3 Dose Cilculati:n M:nu:1 Pcg3147 of 313 ) Revision 2, Change 0
- f. m The maximum annual average on-shore concentrations occur in the southeast
' I sector at a distance of 1300 meters for purposes of routine, long-term O concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3)
K, = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, I (mremlyr per microcurie / cubic meter) The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.109, Appendix B, Table B 1, The total-body dose factors for various noble gas radionuclides are tabulvw . Attachment 10. O,, = the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second). Calquiate the values of Q, for each SIMULTANEOUS RELEASE as shown below. INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLiDE IIN GASEOUS RELEASE r Q,, = ( A , ) { F, ) ( c' ) Eq.9G Where, A, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r G (microcuries/ cubic centimeter) Y.) = F, the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual total body dose rate. Whenever possible, the actual discharge flow rate cetermined from actual ,dase conditiont (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures .'e g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method (1) If a computer system and the-sppropriate software are NOT available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in acenrdance with equation 10G. O ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r U! (SIMPLIFIED METHOD)
Offsit] Dose C:lculation M:nu:1 Paga 148 of 313 Revision 2, Change 0 D, = [( x/Q ) ( K , ) / ( K,) ] E Q, Eq.10G'I [Q)1 J Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for - purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) Ky = the empirically derived, site specific, average, total body, dose factor due to hamma - emissions from TYPICAL GASEOUS EFFLUENTS (mrem /yr per microcurie / cubic meter) A site specific, average, gamma total body dose factor for TYPICAL GASEOUS -- EFFLUENTS has been calculated from historical data. The calculation of this site-specific, average, gamma air dose factoris presented on (] G Attachment 11 (use section 3.4.5 of the old ODCM.) Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma total body dose factor. Kg = a constant, actually a safety factor, which is the ratio of the CCNPP annual total body dose rate limit to the annual total body dose rate limit of Control 3.11.2.1, l (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the annual total body dose rate is always less than or equa' to the annual total body dose rate limit of Control 3.11.2.1. A safety factor of 1.00 will yield an annual total body dose rate which corresponds to the annual total body dose rate limit of Control 3.11.2.1. A safety factor of 0.500 will yield an annual total body dose rate which corresponds to one-half the annual total body dose rate limit of Control 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the anaual total booy dose rate, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry.
,m . _ .
(") l Equations 10G has been derived from NUREG-0133,5.2.1, and historical, site-specific data. NUREG-0133, 3.3
Offsite Dose C:lculation Manual P ge 149 of 313 Revision 2 Chango O n The particular value selected for the safety factor is somewhat arbitrary, however a
) safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative controlls designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptinns are used.
- The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.
This safety factor has been included in equation 10G to account for any potential - nonconservatism associated with applying the empirically derived total body gamma dose factor, K,yg, te all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a total body gamma dose factor greater than K,yg are present in a gaseous release. O, = the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second)
- Calculate the values of Q, for each SIMULTANEOUS RELEASE in accordance with .
equation 9G. INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE ilN GASEOUS RELEASE r ( Q) Q,, = ( A, ) ( F, ) ( c' ) Eq. 9G Where, A, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual total body dose rate. Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) e) Radiation monitoring system algorithms A i t V
- Offsits Dose C:lculation Manual Pcg3150 of.313 Revision 2, Change O (1) The plant vent stack radiation monitoring systems display values f( . which are proportional to the annual total body dose rates due to noble gases emanating from the plant vent stacks.
(2) The values displayed by the plant vent stack radiation monitoring systems are not used for the purpose of effluent accountability per se, but the values displayed can provide a gross approximation of annual total body dose rate (see Control l 3.3.3.9), (3) The Westinghouse Main Vent Noble Gas Monitor,1/2-RE-5415, is an analog system and does not employ instrument algorithm to - determine noble gas release rates.- 4 (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RI 5415. (b) These calculations are described elsewhere in the ODCM. (See equation 4G in the section " Calculating the Rxed . Setpoint for 1/2-RI 5415.") 4 (4) The Sorrento WRNGM,1/2 RE 5416, is a digital radiation ! monitoring system which employs an instrument algorithm to -- determine noble release rates (microcuries per second). (a) It is possible to approximate the noble gas release rates d for the Unit 1 and Unit 2 main vents based on output frorn ' 1/2-RIC-5415. (b) These calcu'ations are described elsewhere in the ODCM, (See equation 1G in the section " Calculating the Fixed j High-High Alarm Setpoint for 1/2-RIC-5415.") (c) The instrument algorithms and the (data base) values . accessed by the instrument algorithms are controlled by l EN-1 100. f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below,
- 7. Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.g., CP 213) shall contain/and or reference administrative and/or Control limits for annual l total body dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.
b)_ Refer to Control 3.11.2.1 for actions to be taken in the event the l calculated annual total body dose rate due to noble gases in gaseous effluents exceeds 500 mr/yr. ( ' S d
+. --. , .
- . - . . _ _ _ , .~. _... _ ._....._ .___ __.
'[
Offsita Dose C:lculation M:nual- Pcg3151 of 313 Revision 2 Change 0 - q ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS
- 1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of l radioactive materials to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the + requirements of 10 CFR 20.1301. c) These radiological effluent controls are described below. 2.- Radiological Effluent Controls a)' The annual skin dose rate, due to noble gases in gaseous waste-discharged to UNRESTRICTED AREAS, shall be less than 3000 mr/yr (per Control 3.11.2.1). 4 b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below. -
- 3. Surveillance Requirement a) The annual skin dose rate at the SITE BOUNDARY, due to noble Oases --
in all gaseous effluents discharged from the sits, shall be determined in accordance with equation 11G (per Control 4.11.2,1,1), b) The results of the radioactive gaseous waste sampling and analysis - program (required by Control 4.11.2,1.2, and implemented by various l CCNPP CHEMISTRY SECTION procedures) are used to calculate the annual skin dose rate due to noble gases in gaseous effluents. c) The plant group (s) responsible for performing the required surveillances
- are identified below.
- 4. Responsible Plant Organization (s) a)_ The CHEMISTRY SECTION is responsible for calculating the annual skin dose rate due to noble gases in gaseous effluents, b) The CCNPP CHEMISTRY SECTION calculates the annual skin dose rate whenever the appropriatL initiating conditions are present.
c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions a) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each release of a WGDT, b) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each vent of.a containment building.
_- -. -. ._~ .- - _ - .------- . . _ _ _ - . - Offsite Dose Calcul tion Manual Pags 152 of 313 Revision 2. Change 0 c) The annual skin dose rate due to noble gases in all gaseous effluents O discharged from the site is calculated for each PURGE of a containment building. d) The annual skin dose rate due to noble gases in all g'aseous effluents discharged from the site is calculated at least weekly for CONTINUOUS discharges from plant vent stacks. e) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each discharge of combustion products resulting from the buming of contaminated oil. 2 f) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE (as defined in CP-612). g) Whenever the correct initiating conditions are present, the annual skin dose rates shall be calculated as described below.
- 6. Calculation Methodology a) The annual skin dose rate, at the SITE BOUNDARY due to noble gases in all gascous effluents discharged simultaneously from the site to --
UNRESTRICTED AREAS shall be calculated in accordance with equation 11G.2 ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN ALL SIMULTANEOUS GAS RELEASES, r D.o = EDr i Eq.11G
= the annual skin dose rate at the SITE BOUNDARY due to noble gases in all D.o simultaneous discharges of gaseous radwaste from the site (" Unit 0")
D., = the annual skin dose rate at the SITE BOUNDARY due to noble gases in release, r Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE wou'd include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging noble gases from the Unit 2 plant vent stack. An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. The frequency is controlled by the implementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control l w 4.11.2.1.1 or 4.11.2,1.2, Table 4.11-2). 2 The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9). l
_.. _ . _ _ _ - - _ . . _. _ . _ _ _ . - . _ _ m_ _ _ - _ __._ -_. _ -__ i Offsita Dose C:lculttion Manual Page 153 of 313 Revision 2, Change O f Calculate the values of Dyfor each SIMULTANEOUS RELEASE as shown below.
-(
6 b) At CCNPP, two methods exist for calculating D,(i.e., annual total skin dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available, - (3) These methods, as well as additional supporting information, are presented in the following sections.
. c) Rigorous Method (1) Solution of the following equation may prove too rigorous for wtine use unless a computer system and appropriate software .
E,re available. (2) If a computer system and the appropriate software are available,
- the annual skin dose rate due to noble gases in gaseous release, -
r, discharged from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 12G. ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD). Du = ( x/Q ) E ( [ Li + ( 1.1 ) ( M. )) ( 4 ) } Eq.12G' Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases *, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E 6 (UFSAR,2.3.6.3) for purposes of routine,long-term concentrations (e.g., routine noole gas releases) (U FSAR, 2.3.6.3)
' The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3)
Equation 12G has been derived from NUREG-0133,5.2.1, and Regulatory Guide 1.109 O ,' - (Appendix B, Equation B-9 and Section C.2.f). NUREG 0133,3.3 4
. _ .m-, _
_ _ . - _ m_m, ._.
.- . - . ..-.- .- ~ . . .. - . . . . .-
Offsita Dose C:lcut: tion M: null Pag)154 of 313 Revision 2, Change 0
=q ( = the skin dose factor due to beta emissions for each identified noble gas Q radionuclide, I (mrem /yr per microcurie / cubic meter)
The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B 1. The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10. M, = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mradlyr per microcurie / cubic meter) The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. 4 The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10. 1,1 = The conversion constant,1.1 mrem / mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose. . O, = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second). This value shall be calculated in accordance with equation 9G. l INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r . Q,, = ( A., ) ( Fr ) ( c' ) Eq.9G A,, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), e the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual skin dose rate. Whenever possible, the actual dischargo flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g , CP-601 and CP-604), c' = a conversion constant (1E6 cubic centimeters per_ cubic meter) d) Simplified method
Offsite Dose Calctilation M:nual Pags 155 of 313 Revision 2, Change 0 -
.g (1) If a computer system and the appropriate software are NOT available, the annual skin dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 13G.
ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD) - D., = [ ( x/Q ) / ( K., ) ) [ L.,, + ( 1.1 ) ( M.,, ) ) E Q, Eq,13G ? Where, x/O = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long term" releases', and as such, the highest - historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) 4 (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur h the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) Kg = a constant, actually a safety factor, which is the ratio of the CCNPP annual skin dose rate limit to the annual skin dose rate limit of Control 3.11.2.1, (unitiess) The safety factor enosen shall be less than or equal to 1.00. This ensures the annual skin dose rate is always less than or equal to the annual skin dose rate limit of Control 3.11.2.1. [ A safety factor of 1.00 will yield an annual skin dose rate which corresponds to the annual skin dose rate limit of Control 3.11.2.1. A safety factor of 0.500 will yield an annual skin dose rate which corresponds to one half the annual skin dose rate limit of Control 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the annual skin dose rate, however, other values--not to exceed 1.00--may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of admin!strative control over the use of s.implified equations for generating radioactive gaseous release permits.= This administrative controlis designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used. Equation 13G has been derived from NUREG-0133,5.2.1, and Regulatory Guide 1.109 l .v - (Appendix B, Equation B-9 and Section C.2.f). ud
- .- - - _ -.,,en-. e-
Offsit2 Dose Calculition Manual Pege 156 cf 313 Revision 2, Change O p The use of a safety factor is consistent with the ALARA philosophy that licensees g - should make every reasonable effort to maintain radiation exposures, and releases
- of radioactive materlats in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.
This safety factor has been included in equation 13G to account for any potential nonconservatism associated with applying the empirically derived skin beta dose factor, L,y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a skin beta dose factor greater than L,y are present in a gaseous release. L,y a the empirically derived, site specific, average, skin dose factor due to beta emissions from TYPICAL GASEOUS EFFLUENTS (mrem /yr per microcurie / cubic meter)
- A site specific, average, beta skin dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.
The calculation of this site-specific, average, beta skin dose factor is presented on , Attachment 11. defer to the table on Attachment 11 for the current value for the empirically derived, site specific, average beta skin dose factor. . 4 M,y = the empirically derived, site specific, average, air dose factor due to gamma ( emissions from TYPICAL GASEOUS EFFLUENTS (mradlyr per microcurie / cubic ( meter) - A site-specific, average, gamma air dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data. The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11. Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma air dose factor. 1.1 = The conversion constant,1,1 mrem / mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose. O, = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second)
- This value shall be calculated in accordance with equation 9G.
INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE ilN GASEOUS RELEASE r Q,, = ( A,, ) ( F, ) ( c' ) Eq.9G
-V -2 NUREG-0133,3.3 -
. . - . . _ ~
Offsite Dose Calculation Manu:1 Page 157 of 313 Revision 2 Change O A A, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r V (microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual skin dose rate. Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT alo.1g with final pressure and temperature) shall be used in equation 9G. - Additional guidance for calculating discharge flow rates may be contairied in approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP-604), c' = a conversion constant (1E6 cubic centimeters per cubic meter) e) Radiation monitoring system algorithms - (1) The plant vent stack radiation monitoring systems display values which are proportional to the annual skin dose rate due to noble gases emanating from the plant vent stacks. -- (2) The values displayed by the plant vent stack radiation monitoring
/ systems are not used for the purpose of effluent accountability
\'
. per se, but the values displayed can provide a gross '
approximation of annual skin dose rate (see Control 3.3.3.9). (3) The Westinghouse Main Vent Stack Noble Gas Monitor,1/2-RE-5415, is an analog system and does not employ instrument algorithm to determine noble release rates. (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RI 5415. (b) These calculations are described elsewhere in the ODCM (See equation 4G in the section " Calculating the Fixed Setpoint for 1/2 RI 5415.") (4) The Sorrtento WRNGM,1/2-RE 5416, is a digital radiation monitoring system which employs an instrument algorithm to determine noble release rates (microcuries per second). (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415. (b) These calculations are described elsewhere in the ODCM.
, (See equation 1G in the section " Calculating the Fixed (mj High High Alarm Setpoint for 1/2-RIC-5415.")
= Offsits Dose C:lcu!: tion Manual - Pcge 158 of 313 Revision 2, Change 0 (5) The instrument algorithms and the (data base) values accessed 3
I by the instrument algorithms are controlled by EN-1-100, f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are 4 initiated as described below.
- 7. Corrective actions
, a) CHEMISTRY SECTION surveillance procedures (e.g., CP 213) shall contain/and or reference administrative and/or Control limits for annual l skin dose rate for gaseous effluents and shall specify corrective actions - to be initiated when these limits are exceeded. b) . Refer to Control 3.11.2.1 for actions to be taken in the event the l calculated annual skin dose rate exceeds 3000 mrlyr.
~ ANNUAL ORGAN DOSE RATES DUE TO lODINES AND PARTICULATES IN GASEOUS EFFLUENTS Introduction 1.
a) 10 CFR 20.1301 specifies dose rate limits associated with the release of l radioactive materials to UNRESTRICTED AREAS. -- b) Radiological effluent controls were originally established to implement O the requirements of 10 CFR 20.1301. The 10 CFR 50 Appendix 1, Design Objectives for ALARA Radioactive Effluents, upon which these calculations are based, are more restrictive than the public dose limits of 10 CFR 20.1301. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The annual organ dose rates, due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 1500 mrlyr (per Control 3.11.2.1).
- b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.
- 3. Surveillance Requirements a) The CHEMISTRY SECTION's sampling and analysis procedure (s) (e.g.,
CP-504, CP 604) shall describe the CCNPP radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2). b) The results of the' radioactive gaseous waste sampling and analysis program are used to calculate the annual organ dose rates due to iodines and particulates in gaseous effluents. O
- U c) The plant group (s) responsible for performing the required surveillances are identified below.
Offsite Dose C:lculation M:nual Pags 159 of 313
- Revision 2 Change 0
, 4. Responsible Plant Organization (s) 1 a) The CHEMISTRY SECTION is responsible for calculating the annual organ dose rates due to iodines and particulates in gaseous effluents.
' b) The CHEMISTRY SECTION calculates the annual organ dose rates whenever the appropriate initiating conditions are present.
c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions a) The annual organ dose rate-for each organ and at the SITE BOUNDARY-due to iodines and particulates in gaseous effluents is calculated at least weekly' for CONTINUOUS discharges from plant vent stacks.
b) The annual organ dose rate-for each organ and at the SITE BOUNDARY--due to lodines and particulates in gaseous effluents is 4 calcule'ed for each discharge of combustion products resulting from the . E burning of contaminated oil. c) The annual organ dose rate-for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is - calculated for each ABNORMAL AND/OR UNANTICIPATED 2 RADIOACTIVE GAS RELEASE . d) Whenever the correct initiating conditions are present, the annual organ ' dose rates shall be calculated as described below.
- 6. Calculation Methodology 4
a) The annual organ dose rate, at the SITE BOUNDARY, due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 14G. ANNUAL ORGAN, o , DOSE RATE DUE TO lODINES AND PARTICULATES IN ALL n SIMULTANEOUS GASEOUS RELEASES, r FROM THE SITE, O Doo = E D, Eq.14G 9 The frequency is controlled by the implementing procedure, CP-612, and is based on plant
. conditions. Under no conditions shall the frequency be less than once per month (Control l 4.11.2.1.1 or 4.11.2.1.2, Table 4.112).
2 See the definition of ABNORMAIJUNANTICIPATED GAS RELEASE in the DEFINITIONS section of the ODCM. O* The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9). l
)
Offsite Dose C:lculation M:nual Pags 160 of 313 )' Revision 2 Change 0 Doo = the site-boundary annual organ dose rate due to iodine and particulate O radionuclides in all gaseous effluents discharged simultaneously from the site (" Unit 0") t D, = - the site-boundary annual organ dose rate due to iodine and particulate radionuclides in release, r Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE would include the release of iodines and particulate radionuclides from the Unit 1 plant vent stack while also discharging lodines and particulate radionuclides from the Unit 2 plant vent stack. - An example of a SIMULTANEOUS RELEASE would include the release of lodine ' and particulate radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. > Calculate the values of D, for each SIMULTANEOUS RELEASE as shown below.
~
b) At CCNPP, two methods exist for calculating D, (i.e., the annual organ ' dose rates due to iodine and particulate radionuclides in gasecus , effluents released to UNRESTRICTED AREAS). 2 m (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and - the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are , presented in the following sections. c) Rigorous Method
- (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropnate software are available.
(2) If a computer system and the appropriate software are available, the annual organ dose rates due to iodines and particulates in gaseous effluents released to an UNRESTRICTED AREA shall be calculated in accordance with equation 15G. ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (RIGOROUS METHOD) Du = ( x/Q ) E ( P i ) ( Q,, ) Eq.15G' O, . Equation 15G has been derived from NUREG-0133,5.2.1.
Offsits Dose Cciculation Minu:1 Page 161 of 313 Revision 2. Change 0 Where, . . .
~
x/Q -= the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate
- calculations.
The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long term concentrations (UFSAR,2.3.6.3). The maximum annual average on shore concentrations occur in the southeast - sector at a distance of 1300 meters for purposes of routine, long-term concentrations (UFSAR,2.3.6.3). Pi '= the maximum organ inhalation pathway dose parameter for lodine and particulate radionuclides, i, for the most restrictive (i.e., child) age group (mrem / year per microcurie / cubic meter) The inhalation pathway dose parameters have been obtained in accordance-with . N U R EG-0133, 5.2.1.1. The pathway dose factor specified in NUREG 0133,5.2.1.b, specifies calculating the exposure to the " INFANT" age group, where the exposure is due to a .- combination of three separate pathways.
- 1) inhalation,
- 2) ground plane, and
- 3) food.
The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways. The latest NRC guidance has changed the critical receptor age group from " infant" to " child." The child, inhalation pathway dose parameters for various radionuclides, sorted by-critical organ, are tabulated in Attachment 12. It should be noted that the dose parameters, P,, (listed in Attachment 12) calculated in accordance with NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the " inhalation Pathway Factors," Ki , calculated in accordarice with NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of P, and K e 0,, = .the release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous
- release, r (microcuries/second).
' NUREG-0133,3.3 ,a e w .y,- e . - - - . , ...,L - -
-- - . . . . - . . . - . .- - .. . - . . . - . . - . - - - . - . . - ~
l Offsit) Dose C:lculation Minual Page 162 of 313 Revision 2, Change 0 Calculate the values of Q, for each SIMULTANEOUS RELEASE in accordance with V(y - equation 9G.' INSTANTANEOUS RELEASE RATE OF LODINE OR PARTICULATE NUCLIDE I IN GASEOUS RELEASER J Qu = ( An ) ( F,) ( c' ) Eq.9G A, = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, I(microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rat A is unknown (e.g., the release has not been conducted), the Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual urgan dose rate. Additional guidance for calculating discharge flow rates may be contained irr . approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter)
, d) simplified method (1) If a computer system and the appropriate software are NOT available, the annual organ dose rate due to iodines and particulates in gaseous effluents discharged from the site to
! UNRESTRICTED AREAS may be calculated in accordance with equation 16G. ^ ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (SIMPLIFIED METHOD) D., = ( 1/ K t) ( x/Q ) ( P.o ) E Q,, i Eq.16G' Wherd, K., = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose rate limit to the organ dose rate limit of Control 3.11.2.1, (unitiess)
-The safety factor chosen shall be less than or equal to 1.00. This ensures the
- organ dose rate is always less than or equal to the organ dose rate limit of Control l
-3.11.2.1 A safety factor of 1.00 will yield an organ dose rate which corresponds to the organ dose rate limit of Control 3.11.2.1.
^ _ ,n
'~
Equation 16G has been derived from NUREG 0133,5.2.1. 1
OfIsita Dos] Calcul: tion M:nu:1 Peg)163 of 313 Revision 2 Change 0 A safety factor of 0.500 will yield an organ dose which corresponds to one-half the o)- organ dose rate limit of Control 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the organ dose rate, however, other values -not to exceed 1.00--may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative controlis designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used. The use of a safety factor is consistent with the Al. ARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. This safety factor has been included in equation 16G to account for any potential nonconservatism associated with applying the dose parameter, Pmy,to all - radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a dose parameter greater than Pm, are present in a gaseous release.
~
x/O = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) O V All releases are considered "long-term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (U FSAR, 2.3.6.3). The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). P,m
= the most restrictive dose parameter which would be reasonably anticipated for the inhalation pathway, child age group, thyroid organ, and 1-131 radionuclide (mrem / year per microcurie / cubic meter)
The inhalation pathway dose parameters have been obtained in accordance with NU REG-0133, 5.2.1.1. The pathway dose factor specified in NUREG 3133,5.2.1.b, specifies calculating the exposure to the " INFANT" age group, where the exposure is due to a combination of three separate pathways.
- 1) inhalation, l
D' ' NUREG-0133, 3.3
. . - - - . . ~ . - - ~.. . . - - , ..- - - - - - .-
- Offsite Dose Cciculation Manual- P:ge 164 of 313 Revision 2. Change 0
- 2) ground plane, and O ; 3) food, The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways.
The latest NRC guidance has changed the critical receptor age group from " infant"
' to " child."
The child, inhalation pathway dose parameters for various radionuclides, sorted by -
. critical organ, are tabulated in Attachment 12.
' It should be noted that the dose parameters, P,, (listed in Attachment 12) calculated in accordance with NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the " Inhalation Pathway Factors," K,, calculated in accordance with NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two -
separate tables for values of P, and K,. O, = the release rate of iodine or particulate radionuclide, I, in (simultaneous) gaseous release, r (microcuries/second). Calculate the values of Og for each SIMULTANEOUS RELEASE in accordance with equation 9G.
. INSTANTANEOUS RELEASE RATE OF LODINE OR PARTICULATE NUCLIDE i IN GASEOUS ,
! RELEASE r I Q,, = ( A., ) ( F, ) ( c' ) Eq.9G A, = the specific activity of iodine or particulate radionuclide, I, in (simultaneous) release, r (microcuries/ cubic centimeter) I F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) i If the discharge flow rate is unknown (u.g., the release has not been conducted), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to
' calculate the annual organ dose rate.
i Additional guidance for calculating discharge flow rates may be contained in . approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP 604). c' -= a conversion constant (1E6 cubic centimeters per cubic meter) e)~ -Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below. O
= _ . . __ _ . _ _ _ _ _ _ _ . _ _ _ . ._
Offsita Dose C:lculation M:nu:1 Pag 3165 of 313 Revision 2, Change o n 7. Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.g., CP 213) shall contain/and/or reference administrative and/or Control limits for annual l organ dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded. b) Refer to Control 3.11.2.1 for actions to be taken in the event the l calculated annual organ dose rate to any organ exceeds 1500 mr/yr. CUMULATIVE GAMMA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS
- 1. Introduction -
a) Appendix l to 10 CFR 50 specifies cumulative gamma air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS. b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. - c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls --
a) The cumulative gamma air dose, due to noble gases in gaseous A effluents released to UNRESTRICTED AREAS, shall be less than 10 V mrads in any calendar quarter, and shall be less than 20 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirement (s) a) The cumulative gamma air doses, for the current calendar month, the calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).
b) The plant group (s) responsible for performing the required surveillance (s) are identified below. 4, Responsible Plant Organizations a) The CHEMISTRY SECTION is respcasible for calculating the cumulative gamma air doses for the current calendar quarter and the current calendar year.
. b) .The CHF.MISTRY SECTION calculates the cumulative gamma air doses 4
whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.
Offsit3 Dose C-lculation M:nu;l Page 166 of 313 Revision 2, Change 0 5 Initiating Conditions d a) The cumulative gamma air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Control l-4.11.2.2), b) The cumulative gamma air doses due to noble gases in gaseous effluents sholl be calculated for each release of a WGDT (CP-604). c) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each vent of a containment building (CP-604). - d) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each PURGE of a containment building (CP-604). e) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated at least weekly' for CONTINUOUS discharges from plant vent stacks (CP-612). - f) The cumulative gamma air doses due to noble gases in gaseous
- effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil. ,
g) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each ABNORMAL AND/OR O UNANTICIPATED RADIOACTIVE GAS RELEASE (CP-612). 3 - h) Whenever the correct initiating conditions are present, the cumulative gamma air doses shall be calculated as described below.
- 6. Calculation Methodology a) The cumulative gamma air dose at the SITE BOUNDARY (e.g., for the current calendar month, current calendar quarter, a.urrent calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated using the following equation':
C The frequency is controlled by the implementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control l 2 4.11.2.1.1 or 4.11.21.2. Table 4.11-2).- The criteria used to dafino ABNORMAL AND UNANTICIPATED GAS RELEASES may be found
'3 in CP-612 or CP-604.
The alarm and trip setpoints ... sha;l be determined and adjusted in accordance with the _f
\
methodology and parameters of the ODCM. (Control 3.3.3.9). l
Offsite Dose C:lculation Manual Page 167 of 313 Revision 2, Change 0
~
(3 ( ,/ CUMULATIVE GAMMA, g, AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t De = E D., Eq.17G Where, Dj = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t D,, = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of D g, for each gaseous release as described below. b) At CCNPP, two methods exist for calculating Dg ,(i.e., the gamma air . dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site during a specified time interval). (1) The rigorous method shall be used IF a computer system and the appropriate software are available.
\
V (2) The simplified method may be used IF a computer system and ' the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the gamma air dose due to noble gases in gasecus effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 18G. /G, G
Offsite Dose C:lculation Minuil Pega 168 of 313 Revision 2, Change O GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION) D, = { 3.17E-8 )( x/Q ) E [( Me)( Q',)] Eq.18G' Where, - 3.17E-8 = The conversion constant,3.17E 8, represents the inverse of the number of seconds in a year. x/Q =~ the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) - A All releases are considered "long term" releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-tern concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). M, a the air dose factor due to gamma emissions fer each identified noble gas radionuclide, I (mradlyr per microcurie / cubic meter) The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B Table B 1. The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.
= the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r Ok (microcuries).
. At CCNPP, all releases are considered long term releases. Calculate the values of Q,, for each release in accordance with equation 19G. Equation 18G has been derived from NUREG 0133,5.3.1.. 8 s NUREG 0133,3.3
Offsite Doso Calculation M:nu:1 Pcg3169 of 313 Revision 2, Change 0 3 TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r (& _ Q'u = ( A., ) ( F, ) ( tu ) ( c' ) Eq.19G A, a the specific activity of noble gas radionuclide, I, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter) F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide 1. Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 19G. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP 604), t, = the duration of the gaseous radwaste release (seconds) -- c' = a conversion constant,1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter. (3) In the event a computer system is unavailable, a simplified e aation may be used to ca'culate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS. (4) The simplified method is presented below, d) simplified method (1) If a computer system and approp iate software are NOT available to perform the rigorous gamma air dose calculation described in the previous section, the gamma air dose, due to noble gas radionuclides, in any single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 20G. m
.- ~ . - .. - - - _ - . -. --
Offsit3 Dose C:lculation M:nual Page 170 of 313 Revision 2, Change 0 ( GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) D, = [ ( 3.17E-8 ) ( x/Q ) ( M., ) / K.,) EQ'u Eq.20G' 3.17E-8 = The conversion constant,3.17E 8, represents the inverse of the number of seconds in a year,- x/Q = the higN:st calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases *, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on-shore concentrations occur in the southedst , sector at a distance of 1300 meters for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). My = the empirically derived, site specific, average gamma air dose factor for each - identified noble gas radionuclide, I (mrad /yr per microcurie / cubic meter) O A site specific, average, gamma air dose factor has been calculated from historical data. The calculation of this site specific, average, gamma air dose factor is presented on Attachment 11 (use section 3.4.5 of the old ODCM.) Kg = a constant, actually a safety factor, which is the ratio of the CCNPP gamma air dose limit to the gamma air dosn limit of Control 3.11.2.2, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the gamma air dose is always less than or equal to the gamma air dose limit of Control l 3.11.2.2. A safety factor of 1.00 will yield an gamma air dose which corresponds to the gamma air dose limit of Control 3.11.2.2. A safety factor of 0.500 will yield an gamma air dose which corresponds to one-half the gamma air dose limit of Control 3.11.2.2. It is recommended that a safety factor of 1.0 be used for calculating the gamma air dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. 'L ' Equation 20G has been derived from NUREG-0133,5.3.1. k' # NUREG 0133,3.3
..-,a_ = - - -
. - -- -=- ~ , .. - . - - . - _ . - - - - - -
Offsit3 Dose Calculation M: null Pcg3171 of 313 Revision 2, Change O n The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control _ () ~ over the use of simplified equations for generating radioactive gaseous release permits. This administrative controlls designed to minimize the possibility of violating Control 3.11.2.2 when simplifying assumptions are used The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.- This safety factor has been included in equation 20G to account for any potential - nonconservatism associated with applying the empirically derived gamma air dose factor, M,y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a gamma air dose factor greater than M,y are present in a gaseous release.
= the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r Ok (microcuries) -
At CCNPP, all releases are considered long term releases. Calculate the values of O, for each release in accordance with equation 19G. . TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r , \_O) ' Q'w = ( A, ) ( Fr ) ( t, ) ( c' ) Eq.19G A, = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter). t F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second). If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be usod to calculate the average activity for nuclide i. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP-604), t, = the duration of the gaseous radwaste release (seconds). C' = d Conversion constant,1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter. e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are - initiated as described below.
Offsit] Dose C:lculation M:nual Page 172 of 313 Revision 2, Change O p 7, Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Control limits for quarterly l and yearly gamma air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded. b) Refer to Control 3.11.2.2 for actions to be taken in the event the l calculated cumulative gamma air doses exceed 10 mrads per calendar quarter or 20 mrads per calendar year. CUMULATIVE BETA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS
- 1. Introduction a) Appendix ! to 10 CFR 50 specifies cumulative beta air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS, b) Radiological effluent controls have been established to implement the .
requirements of 10 CFR 50, Appendix l. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls
(] 'v a) The cumulative beta air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 20 mrads in any calendar quarter, and shall be less than 40 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below,
- 3. Surveillance Requirement (s) a) The cumulative beta air doses, for the current calendar quarter and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Control 4.11.2.2).
b) The plant group (s) responsible for performing the required surveillance (s) are identified below.
- 4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for calculating the cumulative beta air doses for the current calendar quarter and the current calendar year.
b) The CHEMISTRY SECTIO' 4 calcu'ates the cumulative beta air doses whenever the appropriatr initiatir g conditions are present n c) These initiating conditir,3 e,w suitained in the following section.
. - -- . . - _ . . .. . - ~ - _ . - . _ - _ - - - - -
Offsite Dose C lculation M:nual Pagn 173 of 313-Revision 2, Change 0
,q _ 5. _ Initiating Conditions b a)- The cumulative beta air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Control 4.11.2.2),
b) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each release of a WGDT (CP-604). c) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each vent of a containment building (CP-604). d) The cumulative beta air doses due to noble gases in gaseous effluents - are calculated for each PURGE of a containment building (CP-604). e) The cumulative beta air doses due to noble gases in gaseous effluents , are calculated at least weekly' for CONTINUOUS discharges from plant vent stacks (CP 612). f) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each discharge of combustion products resulting from , the buming of contaminated oil, g) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each ABNORMAL AND/OR UNANTICIPATED -. 8 RADIOACTIVE GAS RELEASE (CP-612). h) Whenever the correct initiating conditions are present, the cumulative
\ beta air doses shall be calculated as described below, *
- 6. Calculation Methodology a) The cumulative beta air doses (e.g., for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due
<- to noble gases in gaseous effluents shall be calculated in accordance with equation 21G. CUMULATIVE BETA AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Du = E Du Eq. 21G Where. D m. = the cumulative beta air dose (mrad) at the SITE BOUNDARY due to noble gas t radionuclides contained in all gaseous radwaste discharged from the site during the - time interval, t The frequency is controlled by the implementing procedure, CP 612, and is based on plant . conditions Under no conditions shall the frequency be less than once per month (Controls l 2 4.11.2.1.1 or 4.11.2.1.2 Table 4.112). (m N The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found
- in CP-612 or CP-604.
t Offsit] Dose Cal;ul: tion M:nual Pag)174 of 313 Revision 2, Change 0 ri m Da, = the beta air dose (mrad) due to noble gas radionuclides contained in gaseous radwaste reicaps, r, discharged from the site during the time interval of interest Calculato the ve'ues of Dn, for each gaseous release as described below, b) At CCNPP, twu methods exist for calculating Dn,(tne beta air dose at the SITE DOUNDARY due to noble gas radionuclides contained in ti gaseous radwaste release, r, discherged from the site). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous method - (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. -- (2) If a computer system and the appropriate software are available, the cumulative beta air dose due to noble gases in gaseous
;d effluents r!! eased to UNRESTRICTED AREAS shall be calculated in accordance with equation 22G.
BETA AIR DOSE Di 'O NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION) Ds, = ( 3.17E 8 ) ( xlQ ) % [ ( N ) ( Q'i, )) Eq 220' r Where, y Da, = the beta air dose due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest 3.17E 8 = The conversion constant,3.17E-8, represents the inverse of the number of seconds in a year. x/O = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E 6 seconds per cubic meter) All releases are considered "long term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. (3 ' Equation 22G has been derived from NUREG 0133,5.3.1. 5
) ' NUR EG-0133, 3.3
i OfIsit] Dose C:lcul: tion M:nual Pco) 175 e' 313 Revision 2. Change 0 l
-, The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for
\
(O purposes of routine, long term concentrations (e g., toutino noble gas releases) (U FSAR, 2.3.6.3). The maximum annual average on shore concenbations occur in (; e southeast sector at a distance of 1300 meters for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). N, = the air dose factor due to beta emissions for each identified noble gas radionuclide, I (mradlyr por micrecurio/ cubic meter) The beta air dose factors have been obtained from Regulatory Guide 1.109, - Appendix B, Table B-1. The beta air dose factors for various noble gas radionucliaes are tabulated in Attachment 10 (Attachment 1 of old ODCM).
= the total (time averageri) activity of noble gas radionuclide, I, in gaseous release, r Ok (microcuries).
At CCNPP, all releases arc considered long term releases. Calculate the values of Q,, for each release in accordance with equation 19G. TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r
/
t .
\ Q'i, = ( An ) ( F, ) { ti, ) ( c' ) Eq.19G A ,, = the specific activity of noble gas radionuclide,i,in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter).
F, = the discharge flow rate for releaso, r, discharged during the time interval of interest (cubic meters per second). If the discharge flow rate is unknown (e g., the gaseous radwaste has r.ot been released), the Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculats the average activity for nuclide 1. Additional guidan:o for calculating discharge flow rates may be contained in approved CHEMISYRY SECTION procedures (e.g., CP 601 and CP-004). t,i = the duration of the gaseous radwaste release (seconds). c' a a conversion constant,1E6 cubic centimeters per cubic meter. (3) In the event a computer system is unavai'able, a simplificd equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS (nv)
Offsib Dose C:lculation M:nual Pegs 176 of 313 Revision 2. Change 0 (4) The simplified method is presented below. O 1 j d) Simplified method j l (1) If a computer system and the appropriate software are NOT . available to perform the rigorous beta air dose calculation ' described in the previous section, the beta air dose resulting from ! a sirigle release of waste gases discharged to UNRESTRICTED - AREAS may be calculated in accordance with equation 23G. BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) . Da, = [ ( 3,17E 4 ) ( x/Q ) ( N.,, ) / K.,] E Q'u Eq,23G' 3.17E 8 = The conversion constant,3.17E4, represents the inverse of the number of seconds in a year, x/O a the highest calculated annual average relative concentration for any area at er . beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long term" releases', and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. -- 1 i The highest annual cverage dispersion factor (x/0)is 2.2E 6 (UFSAR,2.3.6.3) for O purposes of routine, long term concentrations (e.g., routine noble gas releases) (U FSAR, 2.3.0.3). The maximum annual average on shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). N, = the empirically derived, site specific, average beta air dose factor for each identified noble gas radionuclide, I (mradlyr per microcurie / cubic meter) A site specific, average, beta air dose factor has been calculated from historical data.
- The calculation of this site specific, average, beta air dose factor is presented on Attachment 11, Kg = a constant, actually a safety factor, which is the ratio of the CCNPP beta air dose limit to the beta air dose limit of Control 3.11.2.2, (unitiess) i The safety f actor chosen shall be less than or equal to 1.00. Th!s ensures the beta cir dose is always less than or equal to the beta air dose limit of Control 3.11.2.2. 7
- A safety factor of 1.00 will yield an organ dose which corresponds to the beta air dose limit of Control 3.11.2.2. ' : Equation 23G has been derived from NUREG-0133,5 3.1.
2 NUREG 0133,3.3 f 1
, c e ,.e e- +-e*- + w y r,w _,.-,---ve,,ww a, e, w w--
Offsit) Dose Cciculati:n Manual Page 177 of 313 Revision 2, Change 0 ! A safety factor of 0.500 will yleid an beta air dose which corresponds to one-half the O beta air dose limit of Control 3.11.2.2. . t it is recommended that a safety factor of 1.0 be used for calculating the beta air { dose, however, other values-not to eneed 1.00- may be used as directed by the j General Supervisor Chemistry. ! The particular vaM selected for the safety factor is somewhat arbitrary, however a safety factor doee provide plant personnel with a degree of administrative control ; over the use of sit.pified equations for generating radioactive gaseous release
- permits. This administrative controlls designed to minimize the possibility of -
violating Control 3.11.2.2 when simplifying assumptions are used. - The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases t of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is - reasonably achievable.
- This safety factor has been included in equation 23G to account for any potential nonconservatism associated with applying the empirically derived beta air dvse .
factor, N,,,, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a , beta air dose factor greater than N,,, are present in a gaseous release. O', = the total (time averaged) activity of noble gas radionuclide, I, in gaseous release, r (microcuries) At CCNPP, all releases are considered long term releases. Calculate the values of Q, for each release in accordance with equation 19G. TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r Q'u = ( An ) ( F, ) ( t., ) { c' ) Eq.19G A, a the specific activity of noble gas radionuclide, I, in release, r, discharged during the - time interval of interest (microcuries/ cubic centimeter) F,_ = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been
- released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide 1.
Additional guidance for calculating discharge flow rates may be contained in , approved CHEMISTRY SECTION procedures (e.g., CP-601 and CP-604). t, .= the duration of the gaseous radwaste re!aase (seconds). ! c' = a conversion constant,1E6 cubic centimeters per cubic meter.
,-r 4 , a-e., e-vw-me+-, mmw>-----v m,-g-, no-----~.---no,v,ememw w w w , w -+ = = =s====-== * *, * #-~ - " "-- **~
i Offsite Dose Calcul:ti:n M:nual Page 178 of 313 Revision 2, Change 0 I e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below. l
- 7. Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.g., CP-213) shall contain/and or referenc. administrative and/or Control limits for quarterly l and yearly beta air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.
b) Refer to Control 3.11.2.2 for actions to be taken in the event the l calculated cumulative beta air doses exceed 20 mrads per calendar quarter or 40 mrads per calendar year. CUMULATIVE ORGAN DOSES DUE TO IODINES AND PARTICULATES IN GASEOUS EFFLUiNTS ;
- 1. Introduction .
a) Appendix l to 10 CFR 50 specifies cumulative organ dose limits
- associated with the release of radioactive materials to UNRESTRICTED AREAS. --
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls i
a) The cumulative organ dose due to lodines and particulates in gaseous 4 effluents released to UNRESTRICTED AREAS shall be less than 15 mrems per calendar quarter, and shall be less than 30 mrems per calendar year (per Control 3.11.2.3). b) The cumulative organ dose due to lodines and particulates in gaseous, , contaminated oil combustion products released to UNRESTRICTED AREAS shall be less than 0.015 mrems per quarter, and shall be less than 0.030 mrems per year (per Control 3.11.2.3). - c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below. O 7 y -- g - -
Offsits Dose Ccicul: tion Minu:1 Pag)179 of 313 Revision 2 Change 0
- 3. Surveillance Requirements 0 a) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 60 days in accordance with the ODCM (per Controi 4.11.2.3).
The plant group (s) responsible for performing the required surveillances b) are identified below. 'i
- 4. Responsible Plant Organizations '
a) The CHEMISTRY SECTION is responsible for implementing the , surveillances required by Control o.11.2.3. b) The CCNPP CHEMISTRY SECTION calculates the cumulative organ doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section. - . S. Initiating Conditions a) The cumulative organ dose-for each organ-shall be determined at least -- once per 60 days (Control 4.11.2.2). The cumulative organ dose- for each organ-due to lodines and O b) particulates in gaseous effluents shall be calculated at least weekly' for CONTINUOUS discharges from plant vent stacks (CP 612). c) The cumulative organ dose-for each organ--due to lodines and , particulates in gaseous effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil. d) The cumulative organ dose-for each organ-due to iodines and particulates in gaseous effluents shall be calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE (CP-612). e) Whenever the correct initiating conditions are present, the annual cumulative organ doses shall be calculated as described below.
- 6. Calculation Methodology The cumulative organ doses (for the calendar month, calendar quarter, a)
. previous 92 days, and calendar year) due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS shall be calculated in accordance with equation 24G.
'~
L The frequency is controlled by the implementing procedure, CP 612, and is based on plant O' conditions. Under no conditions shall the frequency be less than once per month (Controls 4.11.2.1.1 or 4.11.2.1.2, Table 4.112), l
-e-gg -r- .ywy -
g- g ,,,,gy-w-w-w 9,. yr---q-e.wy gy-.-g w g p.7,,g _ , . , , _ ,,,.- 7y -.4m,_ ,- , u,_. 4._w,pg - +.y_,,,. --ww.m...,,-,v. e m %m m y. .,, . w-wem.
Offsit) Dose Calculation M:nucl Page 180 of 313 Revision 2, Change O CUMULATIVE DOSE TO ORGAN, o, FROM ALL GASEOUS RELEASES, r, DISCHARGED O DURING TIME INTERVAL, t V De = E D., Eq.240 Where,
= the cumulative dose (mrad) to organ, o, at the SITE BOUNDARY, due to lodine and Du particulate radionuclides contained in gaseous waste discharged from the site during the time interval, t D, a the dose (mrad) to organ, o, at the SITE BOUNDARY due to lodine and particulate radionuclides in gaseous release, r, discharged from the site during the time interval of interest ,
Calculate the values of D, for each gaseous release as described below, b) At CCNPP, two methods exist for calculating D,(the organ doses due to iodines and particulates resulting from any single release of radioactive - gases to an UNRESTRICTED AREA). (1) The rigorous method shall be used IF a computer system and the " appropriate software are available. (2) The simphfied method may be used IF a computer system and
- O. the appropriate software are NOT available. .
(3) These methods, as well as additional supporting information, are presented in the following sections, c) Rigorous method (1) Application of the following equation may prove too rigorous for routine use unless a computer system and the appropriate software are availablo, (2) If a computer system and the appropriate software are available, the organ doses due to lodines and particulates contained in any single release of radioactive gases to UNRESTRICTED AREAS shall be calculated in accordance with equation 25G. 4
.g w ---- -,sr a'o.i- e.+e =__ - - _ _ -- - . -
OffsitJ Dose Calculation M nual Pag)181 of 313 Revision 2 Change 0 /' 3 V (DOSE RIGOROUS TO EQUATION) ORGAN, o, DUE TO IODINES AND PARTICULATES IN GAS RELEASE, r Du = ( 3,17E 8 ) ( W, ) E ( Rip. ) ( Q'u ) Eq.250' Where, D, = the dose (mrem) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the sito during the time interval . of interest ! 3.1/E 8 = The conversion constant,3.17E 8, represents the inverse of the number of seconds in a year. W, = the dispersion parameter for estimating the dose to an individual at the controlling location for long term releases, and may at sume one of two values as described below W,is x/O for the inhalation pathway (2.2E-6 sec/ cubic meter) - W,is D/O for the food and ground plane pathways (meters 2) D/O = the dispersion parameter at the controlling location for long term releases (meters 2) _ The volun for D/O has been determined to be 8.63E 10 m 2,2 The grass-cow-milk pathway is the controlling pathway.' ' The controlling sector is the south-southwest sector. The controlling location is at a distance of 4800 meters.' R ,p. = the dose factor for each identified iodine or particulate radionuclide, I, exposure pathway, p, receptor age group, a, and organ, o (m4 mrem / year per microcuries/second or mrem / year per microcuries/ cubic meter) dose factors have been derived for the following pathways
- 1) inhalation - see Attachment 12
- 2) ground plane see Attachment 12
- 3) grass cow-milk - see Attachment 12
- 4) grass-cow-meat- see Attachment 12
- 5) vegetation - see Attachment 12 Equation 25G has been derived from NUREG-0133,5.3.1.
2 See CP-607 Revision 2 section 3.4.3. fx See the " Land Use Survey",1990. See the " Land Use Survey",1990.
-____.___.__.m__
Offsitz Dose C:Iculation M:nu;l Pag 2182 of 313 Revision 2. Change 0 The inhalation pathway dose factors were obtained using the formula from NUREG-0 0133,5.3.1.1. The ground plane dose factors were obtained using the formula from NUREG 0133, 5.3.1.2. The grass cow milk pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.3. l The grass cow meat pathway dose factors were obtained using the formula from NUREG 0133,5.3.1.4. The vegetation pathway dose factors were obtained using the formula from NUREG 0133,5.3.1.5.
- O', a the total (time averaged) activity of iodine or particulate radionuclide, I, in gaseous -i release, r, discharged during the specified time interval (microcuries)
At CCNPP, all releases are considered long term releases. Calculate the values of Q, for each releese in accordance with equation 19G. TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE iIN " GASEOUS RELEASE r Q'i, = ( Ai r ) ( F,) ( ti, ) ( c' ) Eq.19G . A, = the specific activity of iodine and particulate radionuclide, i, in release, r, discharged l during the time interval of interest (microcuries/ cubic centimeter) F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released),' the
- Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide 1.
Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g., CP 601 and CP 604). t, = the duration of the gaseous radwaste release (seconds) c' = a conversion constant,1E6 cubic centimeters per cubic meter (3) -In the event a computer system and the appropriate software are unavailable, a simplified equation may be used to calculate the organ doses due to individual gaseous releases.- p (4) The simplified method is presented below. V
= -
n,.. .n . , , - ,..a , .. - -,- - . , , ..,,-.._._,,v ,_ , . , , , - . . .~
Offsit] Dose C Icul: tion Manual Pcge 183 of 313 Revision 2, Change 0 , d) simplified method \ (1) If a computer system and appropriate software are NOT available to perform the rigorous organ dose calculations described in the previous section, the organ doses due to iodines and particulates in a single release of radioactive gases discharged to an UNRESTRICTED AREA may be calculated in accordance with equation 26G. DOSE TO ORGAN, o, FROM IODINES AND PARTICULATES IN GAS RELEASE, r (SIMPLIFIED EQUATION) Dm.a, = [( 3.17E-8 )( W,) ( Run ) / Ko) E ( Q$,) Eq.260' D mm, = the maximum dose to any organ, o, due to iodines and particulates contained in any single release, r, of radioactive gases to an UNRESTRICTED AREA 3,17E-8 = The conversion constant,3.17E-8, represents the inverse of the numberuf seconds in a year. D/O = the dispersion parameter at the controlling location for long term releases (meters.2) The value for D/Q has been determined to be 8.63E 10 m 2.8 The grass-cow-milk pathway is the controlling pathway.' The controlling sector is the south southwest sector. The controlling location is at a distance of 4800 meters.' R i.3 33
= the infant, thyroid, dose factor for I 131 via the grass-cow-milk pathway (m2 mrem / year per microcuries/second)
This value is 1.05E12 and it is listed en Attachment 12. Kg = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Control 3.11.2.3, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose is always less than or equal to the organ dose limit of Control 3.11.2.3. A safety factor of 1.00 will yield an organ dose which corresponds to the organ dose limit of Control 3.11.2.3. A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose limit of Control 3.11.2.3.
' Equation 26G has been derived from NUREG-0133,5.3.1. ,s See CP 607, Revision 2 section 3.4.3. / T See the " Land Use Survey",1990.
V
- See the
- Land Use Survey" 1990. I
Offsite Dose C:lculation M:nual Pcg3104 of 313 Revision 2, Change O c it is recommended that a safety factor of 1.0 be used for calculating the organ dose, ( - however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative controlis designed to minimize the possibility of violating Control 3.11.2.3 when simplifying assumptions are used. The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable. This safety factor has been includud in equation 26G to account for any potential nonconservatism associated with applying the infant, thyroid, grass cow milk dose factor, Rn33, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a pathway dose factor greater than Rg3, are present in a gaseous release. - , Ok = the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r (microcuries)
~~
At CCNPP, all releases are considered long term releasec. This value shall be calculated in accordance with equation 10G. TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE iIN GASEOUS RELEASE r Q'i, = ( A., ) ( F, ) { ti, ) ( c' ) Eq.190 A,, = the specific activity of lodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter) F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i. Additional guidance for calculating discharge flow rates may be contained in approved CHEMISTRY SECTION procedures (e.g., CP 601 and CP 604). t, = the duration of the gaseous radwaste release (seconds) c' = a conversion constant,1E6 cubic centimeters per cubic meter /~' N.)s
l Offsit) Dose Calculation Manu 1 Pcg31.l5 of 313 l Revision 2, Change 0 J l e) Once the calculations above have been completed, the calculation ! results are compared to the applicable limits and corrective actions are ! initiated as described below. ,
- 7. Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.0, CP 213) shall contain/and or reference administrative and/or Control limits for l cumulative organ dose for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded, b) Refer to Control 3.11.2.3 for actions to be taken in the event the l calculated cumulative gamma air doses exceed any of the radiological effluent controls listed above.
LIMITS FOR THE GASEOUS WASTE PROCESSING SYSTEM
- 1. Introduction a) 10 CFR 50.30a requires licensees to maintain and use the equipment installed in the gaseous waste processing system for the purpose of controlling effluents to the environment.
.~
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a. 4 c) These radiological effluent controls are described below. *
- 2. Radiological effluent controls a) The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 1.20 mrads gamma radiation in a 92 day period (per Control 3.11.2.4).
b) The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 2.4 mrads beta radiation in a 92 day period (per Control 3.11.2.4). c) The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce the quantity of radioactive materials in gaseous, waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY exceeds 1,80 mrem to any organ in a 92 day period (per Control 3.11.2.4). d) The routine surveillances which are performed to verify compliance with this radiological effluer.t controls are described below.
Offsit3 Dose C:lculation M:nual PCO2186 of 313 Revision 2 Chance 0
- 3. Surveillance Requirement (s) a) The cumulative gamma air doso, for the previous 92 days, due to noble gases in gaseous effluents, shall be determined at least once every 60 ,
days (Control 4.11.2.2). b) The plant group (s) responsible for performing the required surveillance (s) are identified below. -
- 4. Responsible Plant Organizations a) The CHEMISTRY SECTION is responsible for calculating the cumulative -
gamma air doses for the current calendar month, the previous 92 days, the current calendar quarter, and the current calendar year, b) The cumulative gamma air dose for the previous 92 days is calculated whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section. S. Initiating conditions a) For a listing of initiating conditions associated with calculating gamma air dosos, see " Initiating Conditions"in the section of the ODOM titled, -
" Cumulative Gamma Air Doses Due To Noble Gases in Gaseous Effluents."
b) For a listing of initiating conditions associated with calculating beta air - doses, see " Initiating Conditions"in the section of the ODCM titled,
" Cumulative Beta Air Doses Due To Noble Gases in Gaseous Effluents."
c) For a listing of initiating conditions associated with calculating cumulative organ doses, see " initiating Conditions"in the section of the ODCM titled,
" Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents."
- 6. Calculation methodology a) Calculate the previous 92-day cumulative gamma air dose as described in the section " Cumulative Gamma Air Doses Due To Noble Gases in Gaseous Effluents."
b) Calculate the previous 92 day cumulative beta air dose as described in the section " Cumulative Beta Air Dosos Due To Noble Gases in Gaseous Effluents." c) Calculate the previous 92 day cumulative organ dose as described in the section " Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents."
~h (V
Offsite Dose Cdculation M:nual P:ge 187 of 313 Revision 2 Change 0
- 7. Corrective actions a) CHEMISTRY SECTION survel?uce procedures (e g., CP 212) shall contain/and or reference administrative end/or Control limits for 92-day l cumulative gamma, beta, or organ doses for gaseous effluents and shall specify corrective actions to be initiated when those limits are exceeded.
b) Refer to Control 3.11.2.4 for actions to be taken in the event the l calculated 92 day cumulative gamma air, beta air, or organ doses exceed any of the radiological effluent controls listed above. LIMITS _ON TOTAL ANNUAL DOSE GASES. LIQUIDS. AND URANIUM FUEL CYCLE SOURCES
- 1. Introduction a) 40 CFR 100 specifies annual dose limits for radionuclides released to the environment.
b) Radiological effluent controls have been established to implement the requirements of 40 CFR 190. c) These radiological effluent controls are described below.
- 2. Radiological offimnt controls
(] V a) The total body dose from exposure to the combination of liquid releases, gas ruloases, and uranium fuel cycle sources shall be less than 25 mrem - for the current calendar year (per Control 3.11.4). b) The organ dose (for the maximum exposed organ, not including the thyroid) from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrom for the current calendar year (per Control 3.11.4). c) The thyroid dose from exposure to the combination of liquid relear.es, gas releases, and uranium fuel cycle sources shall be less than 75 mrem for the current calendar year (per Control 3.11.4), d) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirements a) The cumulative gamma air doses, for current calendar month, the current calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once overy 60 days (Control 4.11.2.2).
b) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar o month, the current calendar quarter, and the current calendar year, shall be determined at least once every 60 days in accordance with the t] \ ODCM (per Control 4.11.2 3).
i [ Offsits Dose Cdculati:n M:nual Pag 3188 of 313 Revision 2, Change O c) Cumulative total body dose to MEMBERS OF THE PUBLIC in ; UNRESTRICTED AREAS-for the current calendar month, the calendar i quarter, and the current calendar year -shall be calculated at least once per 60 days (per Control 4.11.1.2). d) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the current calendar quarter, and the current calendar year-shall be calculated at least once per 60 days (per Control 4.11.1.2). i e) The direct radiation dose to MEMBERS OF THE PUBLIC exposed to uranium fuel cycle sources (i.e., reactor units and outside storage tanks) . shall be determined IF THE APPo.OPRIATE INITIATING CONDITIONS ARE PRESENT. t
- 4. Responsible Plant Organization (s) a) The CHEMISTRY SECTION is responsible for implementing the effluent surveillances required by Control 4.11.4.1.
b) The CHEMISTRY SECTION is responsible for ensuring implementation of the direct radiation surveillances required by Control 4.11.4.2. c) IT SHOULD BE NOTED THAT NO SURVEILLANCES NEED BE .. PERFORMED UNLESS THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT. d) Those initiating conditions are contained in the following section. - i S. Initiating conditions a) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated doses from liquid ! effluents exceed any of the following (per Control 4.11.4.2): (1) Six (0) mrom per quarter to the total body (2) Twelve (12) mrem per calendar year to the total body (3) Twenty (20) mrem per quarter to any organ (4) Forty (40) mrem per calenda'r year to any organ b) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated air doses from noble gasses in gaseous effluents exceed any of the following (per i Control 4.11.4.2): (1) Twenty (20) mrad gamma per quarter - (2) Forty (40) mrad gamma per calendar year (3) Forty (40) mrad beta per quarter l
. + - - - - s,sn-e ,,a------sas ~, n -m~ ,me - - - - ---n-.-w<,-------. , r a----namm- n.,-, +- ee-,-.c,, e .- +-n
Offsit3 Dose C:lculation M nu:1 Peps 189 of 313 R: vision 2 Charge 0 (4) Eighty (80) mrad beta per calendar year O c) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated organ doses from lodines and particu!stes in gaseous effluents exceed any of the ; following (per Control 4.11.4.2): , (1) Thirty (30) mrom per quarter to any organ : (2) Sixty (60) mrem per calendar year to any organ : d) Whenever the correct initiating conditions are present, the total doses - from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated as shown below.
- 6. Calculation methodology I a) The total body dose and the organ doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be !
calculated in accordance with equation iT and 2T respectively. l ) TOTAL, TOTAL BODY DOSE FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES i Dn n = Dr.t + De + D.,,6 Eq.1T TOTAL ORGAN DOSES FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL ' CYCLE SOURCES . D..a = Dr.L + D., + Dani Eq.2T
= the dose (mrem) to total body resulting from the combination of all gas releases, all Dun liquid releases, and all uranium fuel cycle sources.
Dn o = the dose (mrem) to organ, o, resulting from the combination of all gas releases, all-liquid releases, and all uranium fuel cycle sources. Separate values shall be calculated for each of the organs listed below: 1, bone
- 2. liver '
- 3. thyroid
- 4. kidney
- 5. lung-O 1 i
Offsite Dose C:lculation M:nu:1 Pcg3190 of 313 R:vbion 2 Ch ng)0
- 6. GI tract Da =
the cumulative dose (mrem) to organ, o, for allliquid releases discharged in a given time interval Calculate this value as specified by equation 8L. Dj = the site-boundary cumulative gamma air dose (mrad) due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Calculate this value as specified by equation 17G, except substitute K, for M,(see - Attachment 10). Dg = the site-boundary cumulative organ dose (mrem) resulting from the release of lodine and particulate radionuclides in gaseous releases from the site Calculate this value as specified by equation 24G. D% = the calendar. year cumulative dose (mrom) to the maximum exposed MEMBER OF . THE PUBLIC due to direct radiation from the reactor units and outside storage tanks This value shall be based on the results of direct radiation measurements from - TLDs or continuous dose rate instruments placed near the SITE BOUNDARY (e.g., from radiological environmental monitoring sites DR1 DR9 described on Attachment 13 and shown on Attachment 18). O The CHEMISTRY SECTION, and the Radiation Safety Section are responsible for l determining this value, b) Compare the calculated values to the radiological effluent controls (listed in this section), and if any of the radiological effluent controls have been exceeded, perform the appropriate corrective actions listed below.
- 7. Corrective actions a) CHEMISTRY SECTION surveillance procedures (e.g., CP 212) shall contain/and or reference administrative and/or Control limits for total l dose for liquid releases, gaseous releases, and uranium fuel cycle sources and shall specify corrective actions to be initiated when these limits are exceeded.
b) Refer to Control 3.11.4 for actions to be taken h the event the total dose l exceeds any of the radiological effluent controls listed above. c) If any of the radiological effluent controls have been exceeded, refer to 40 CFR 302, Appendix B, and verify the quantities of radioactive materials released are less than the values specified. [3758) D (v
Offsite Dose Calculation M:nual Pag)191 of 313 Revision 2, Change 0 s SPECIAL EXCEPTIONS AND ASSUMPTIONS FOR CALCULATION OF DOSES AND DOSE ( ) RATES v
- 1. Camp Conoy a) Location (1) Camp Conoy is located within the SITE BOUNDARY.
(2) Camp Conoy is located in the SE sector. (3) Camp Conoy is approximately 3000 feet from the plant. b) Occupancy (1) Camp Conoy is frequently visited by MEMBERS OF THE PUBLIC. (2) Maximum occupancy for ti, EMBERS OF THE PUBLIC at Camp Conoy is restricted to approximately 3380 hours per year. . , c) Meteorology (1) The highest historical annual average x/Q for Camp Conoy is . 2.40E 6 seconds per cubic meter.' (] d) Dose calculation assumptions (1) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at Camp Conoy will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the SITE BOUNDARY. (2) No special considerations are required for addressing potential exposure at Camp Conoy.
- 2. Visitors Center a) Location (1) The Visitors Center is located within the SITE BOUNDARY.
(2) The Visitors Center is located in the WNW sector. (3) The Visitors Center is approximately 1000 feet from the plant. b) Occupancy (1) The Visitors Centeris frequently visited by MEMBERS OF THE PUBLIC. [ See CP 607, Revision 2 page 24. 'w) See CP-607, Revision 2 page 24.
OffMt3 Dose Calcul: tion M:nu:1 Pcoe 192 of 313 Revision 2. Change 0 (2)- Maximum occupancy for MEMBERS OF THE PUBL 8C at The Visitors Center is restricted to daylight hours. c) Meteorology (1) The highest historical annual averag
' is 8.68E-6 seconds per cubic meter ,e x/Q for the Visitors Center ;
i i (2) The wind frequency for the WNW sector,' based on 1983 meteorological data, is four percent (4%). i d) Dose calculation assumptions - (1) "Using a conservative basis of 10% wind frequency, and E Individual visiting the center for 330 hours / year during the periods of worst case meteorological conditions would be most highly-exposed."' (2)- -The dose calcu'ated for the controlling SITE BOUNDARY is more . conservative b' a factor of 7.* t (3) Based on ser . sons (b) and (c) above, any actual exposure to a MEMBER O THE PUBLIC at The Visitors Center will be less than the calculated exposure for a MEMBER OF THE PUBLIC at - the SITE BOUNDARY. 1 (4) No special considerations are required for addressing potential exposure at The Visitors Center.
- i i
9 See CP 607, Revision 2 page 24. ' See CP 607. Revision 2 page 24. ' [] V-8 See CP 607, Revision 2 page 24. See CP-607, Revision 2 page 24, r
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_ - . . , . . - _ . _ . . . . . , . . . - - - . ..,,....-,.,.___.,_....-.4, ,,, - . .
Offsite Dose Calculation Manu;l Page ig3 of 313 i Revision 2, Change 0 ! RAD 60 LOGICAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM:'
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals. l b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1, Section IV.B.2, c) These radiological environmental controls are described below.
- 2. Controls on the Radiological Environmental Monitoring Program (REMP) a) The REMP shall consist of environmental sample locations, analysis parameters, analysis frequencies, detection limits, and ACTION ievels all -
of which conform to the requirements of Control 3.12,1. (See l Attachment 13,14,15,16, and 17), b) The REMP shall maintain a map showing sample locations near the S!TE BOUNDARY in accordance with Control 3.12.1, (See Attachment l 18). c) The REMP shall maintain a map showing sample locations within a 8 km. , radius of the plant in accordance with Technical Specification - Administrative Controls. (See Attachment 19).
- 3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations DR1-DR23 listed on Attachment 13, 4
(2) In the event any of the monitoring stations, DR1 DR23, described on Attachment 13 become unavailable, establish new monitoring stations (with new dosimetry) as described below: (a) In lieu of any location DR1 DR9 described on Attachment 13, establish a new monitoring station in the same meteorological sector in the general area of the SITE BOUNDARY.
~ This portion of the environmental monitoring program is designed to monitor the environment surrounding the CCNPP. A separate environmental monitoring program designed to monitor the l environment surrounding the Independent Spent Fuel Storage Installation is describod elsewhere d in the ODCM.
_- . _._ .__ . _ _ _ _ _ ___ _ . . _ _ _ _ _ m __. . __ ._ _ . . _ _ _ offsNe Dose Calculation Manual Pcge 194 of 313 Revision 2, Change 0 n (b) In lieu of any location DR10-DR18 described on f Attachment 13, establish a new monitoring station in the same meteorological sector in the 6-8 km range from the i site. l (c) In lieu of any location DR19 DR23 described on Attachment 13, establish a new monitoring station in either a specialinterest area (e.g., population center, ! nearby residence, school) or a control station whichever is applicable. t (3) In the event any dosimetry at an existing monitoring location DR1 DR23 becomes unavailable, place new dosimetry at the
- monitoring station.
(4) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14. (5) The sampling locations (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), vla the , same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was , conducted in accordance with Control 3.12.2.b. b) Surveillances for airborne activity
, (1) Radiolodine and particulate samples shall be collected from -
locations A1 A5 listed on Attachment 13. (2) In the event any of the monitoring stations, A1 AS, described on Attachment 13 become unavailable, establish new monitoring station (s) (fitted with new radiolodine and particulate samplers) as described below: (a) In lieu of any location A1 A3 described on Attachment 13, establish a new monitoring station in the general area of the SITE BOUNDARY, such that the three monitoring stations are located in the meteorological sectors with the
- three highest calculated annual average ground level D/Q.
(b) In lieu location A4 described on Attachment 13, establish a new monitoring station near a community having the highest calculated annual average ground level D/Q. . (c) In lieu of location A5 described on Attachment 13 establish a new " control" location 15 to 30 kilometers from the plant in the least prevalent wind direction. (3) In the event any radiolodine cartridge or particulate filter becomes unavailable from an existing monitoring location A1 A5 described on Attachment 13, place new radiciodine cartridge or particulate iO filter in the air sampler at the monitoring station.
= - ------ - - .:
Offsit3 Dose C:lculation M:nu 1 Pcge 195 of 313 Revision 2. Chan0e 0 s (4) Analyze the samples at the frequencies and for the parameters identified on Attachment 15. (5) The sampling locatlans(s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of tho yearin which the land use census was , conducted in accordance with Control 3.12.2.b. l
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c) Surveillances of waterbome activity (1) Water and sediment samples shall be collected from the locations Wa1, Wa2, and Wbi listed on Attachment 13. (2) In the event any of the samples at Wa1, Wa2, or Wb1 are unavailable, collect substitute samples as described below: (a) in lieu of a liquid sample at Wa1, collect a substitute sample of surface water from the intake area. . (b) in lieu'of a liquid sample at Wa2, collect a substitute sample of surface water from the discharge area.
^
(c) In lieu of sample at Wbi, collect a substitute sample of sediment from a downstream shoreline with existing or potential recreational value. (3) Analyze the samples at the frequencies and for the parameters identified on Attachment 16. (4) The sampling locations (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted in accordance with Control 3.12.2.b. d) Surveillances for ingestible activity (1) Fish / invertebrate, milk, and food product samples shall be collected from the locations lai thru la6 and Ib1 thru lb9 listed on Attachment 13. (2) In the event any of the samples at lai thru la6 or Ib1 thru lb9 are unavailable, collect substitute samples as described below:- (a) In lieu of samoles at lai thru la3, collect substitute three commercially and/or recreationally important species (two fish species and one invertebrate species) from the vicinity of the plant discharge area. O
Offsite Dose Calculation M:nual Pag)106 of 313 Revision 2. Change 0 q (b) In lieu of samples at la4 thru la6 collect three I Q commercially and/or recreationally important species (two fish species and one invertebrate species) from an area not influenced by plant discharges. (c) In lieu of samples at Ib1 thru lb6, collect three kinds of I broad leaf vegetation grown near the SITE BOUNDARY at two different locations of highest average ground level D/Q'. (d) In lieu of samples at Ib7 thru Ib9, collect one sample each of the similar broad leaf vegetation grown 15 30 km - distant in the least prevalent wind direction. l (3) Analyze the samples at the frequencies and for the parameters identified on Attachment 17. (4) The sampling locations (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), v!a the same exposure pathway, may be deleted from the Radiological . Environmental Monitoring Program after October 31 of the year in which the land use consus was conducted in accordance with l Control 3.12.2.b.
- 4. Responsible Company Organizations a) The CHEMISTRY SECTION, BG&E CCNPPD is responsible for ensuring l d performance of the surveillances listed above. -
- 5. Initiating conditions a) Collect samples in accordance with the frequencies specified on Attachments 14,15,16, and 17.
b) Analyze samples in accordance with the frequencies specified on Attachments 15,16, and 17. c) Calculate the potential annual doses in accordance with the methodology outlined below if any of the following conditions are true: (1) any of the above surveillance results reveallevels of environmental activity greater than the ACTION Levels specified on Attachments 15,16,17 (per Control Table 3.12 2) (2) any radionuclides other than those in Attachments 15,16, and 17 are detected, and the radionuclidos are the result of plant offluents. d) The REMP Manager is responsible for notifying the General Supervisor-- l Chemistry, CCNPP, if any of the following conditions are true: (v) With fresh leafy >egetable samples unavailable from one or more of the sample locations listed on Attachment 13, perform corrective actions specified by Control 3.12.1.c. l
Offse Dose C:lcutation M:nu:1 Pag)197 of 313 Revision 2, Chango 0 /' (1) any of the above surveillance results reveallevels of ( environmental activity greater than the ACTION Levels specified on Attachments 15,1617 (per Control Table 3.12 2) (2) any radionuclides other than those in Attachments 15,16, and 17 are detected, and the radionuclides are the result of piant effluents, and the potential annual doses due to the radionuclides are gteater than the calendar year limits of Controls 3.11.1.2, l 3.11.2.2, and 3.11.2.3.
- 6. Calculation methodology a) If the correct initiating conditions, as described above, are present, calculate potential annual doses for the pathway of interest in accordance with the methodclogies contained in ODCM, or b) if methodologies other than those listed in the ODCM are used to calculate potential annual doses, such methodologies shall be documented in the AREOR in accordance with Control 3.12.1.b. ,
- 7. Corrective ACTIONS a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the -
next sampling period, and document in the AREOR (per Control 4.12.1, l Table 3.121, notation "a"). g b) If the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is not being conducted in accordance with Attachments 13,14,15,16, or 17 document deviations in the AREOR (per Control 3.12.1.a). c) With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, establish a new monitoring location and document applicable information in the AREOR (per Control l 3.12.1.c). d) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15,16, or 17, submit a Special Report to the NRC (per Control 3.12.1.b). e) When radionuclides other thar, u ose (;sted on Attachments 15,16, and 17 are detected; and if those reconuclides are the result of plant effluents; and if the potential annual doses due to the i'adionuclides are greater than the calendar year limits of Controls 3.11.1.2,3.11.2.2, and 3.11.2.3; submit a Special Report in accordance with Control 3.12.1.b. LAND USE CENSUS
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.3 requires licensees to identify changes in the u. e of UNRESTRI ' 'ED AREAS in order to permit
{], f modifications in monitoring prograri .
i Off 6H3 Dose Cdculation M:nuil Paga 198 of 313 Revision 2 Chan0e 0 b) Radiological environmental controls have been estLblished to implement O ' the requirements of 10 CFR 50, Appendix 1, Section IV.B.3. c) These radiological environmental controls are described below. i
- 2. Controls on the Land Use Census !
i a) - Identify the location of the nearest milk animal, within a distance of 8 km , of the plant site,in each of the 9 meteorological sectors (per Control l 3.12.2), b)' identify the location of the nearest residence, within a distance of 8 km - ! of the plant site,in each of the 9 meteorological sectors (per Control l 3.12.2). < c) Identify the location of the nearest garden, within a distance of 8 km of , the plant site, in each of the 9 meteorological sectors; or if the garden v census was not conducted, obtain samples of three different kinds of broad leaf vegetation from the SITE BOUNDARY in two different meteorological sectors which have the highest predicted SITE * ! BOUNDARY D/O (per Control 3.12.2). .
- 3. Surveillance Requirement (s)
~~
a) Perforrn a land use census that will provide the best results. Example methods may include, but are not limited to, the following: (1) door to-door surveys * (2) aerial views (3) consult local agricultural authorities b) Document the results of the land use census in the Annual Radiological , Environmental Operating Report in accordance with Technical Specification Administrative Controls. c) Perform an Independent Technical Review of the land use census data.
- 4. Responsible Company Organizations a) The Chemistry Section, BG&E CCNPPD, is responsible for ensuring the l performance of the surveillances listed above.
_5. Initiating conditions a)- Conduct the land use census during the growing season, and conduct
-- the land use census at least once per 12 months. ;
. 8. Calculation methodology a) Calculato doses for the pathways of interest in accordance with the !
4 O methodologies contained in Regulatory Guide 1.109, or 4 . ,a .. ,,%-..%r., , ,,, -y m_,,,..m-,r,..--m.2,,. ,,,.. - , ,.,,,.-,.m. _ . -. ~.. , , , - ~ - . ., . - , ,, J .
l j Offsit3 Dose Cciculation M:nual Page 199 of 313 Revision 2, Change 0 l b) if methodologies other than those listed in Regulatory Guide 1.109 are ( used to calculate doses, such methodologies should be documented in the Annual Radiological Environmental Operating Report. l
- 7. !
Corrective actions a) The results of the land use census shall be used to determine the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM's sample locations identified on Attachment 13. l b) If the land use census has identified a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, perform the following activities. (1) Document the new location (s)in the next Annual Rediological Environmental Operating Report in accordance with Technical Specification Administrative Controls, and (2) revise the figures and tables in the ODCM to reflect the new l location (s). . c) If the land use census has identified a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) which is 20% greater than the equivalent location identified on Attachment 13, - perform the following activities. (1) Add the new location (s) to the RADIOLOGICAL , ENVIRONMENTAL MONITORING PROGRAM within 30 days, * (2) document the new location (s)in the next Annual Radiological Environmental Operating Report in accordance with Technical Specification Administrative Controls, and (3) revise the figures and tables in the ODCM to reflect the new location (s). INTERLABORATORY COMPARISON PROGRAM
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantitles of radioactive material released in affluents and resultant radiation doses to individuals, b) Radiological environmental controls have been established to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are parformed as part of the quality assurance program for environmental monitoring, f c). These radiological environmental controls are described below.
N
- 2. Controls on the Interlaboratory Comparison Program
Offsite Dose C:Icut: tion M: null Pago 200 of 313 Revision 2, Chango O n a) Analyze INTERLABORATORY COMPARISON PROGRAM samples l supplied by either the Commission or a Commission approved laboratory t by for all parameters listed on Attachments 15,16, and/or 17, as applicable' (per Control 3.12.3).
- 3. Surveillance Requirement (s) a) A sumrnary of the results obtained as part of the interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification -
Administrative Controls. b) This section of the ODCM shall describe the Interlaboratory Comparison Program.
- 4. Responsible Company Organizations a) The CHEMISTRY SECTION, BGSE CCNPPD, is responsible for l ensuring performance of the surveillances listed above.
- 5. Initiating conditions a) Analyze INTERLABORATORY COMPARISON PROGRAM samples whenever they are supplied by either the Commission or a Commission -
approved laboratory. p y
- 6. Calculation methodology a) Analysis methods and calculational methodologies used to satisfy the above surveillances shall be documented in approved procedures.
- 7. Corrective actions a) If analyses are not performed as required, document actions taken to prevent reoccurrence in the Annual Radiological Environmental Operating Report (AREOR) pursuant to Technical Specification - l Administrative Controls.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 1. Introduction -
a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to provide data on measurable levels of radiation and radioactive materials in the environment. b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1, Section IV.B.2. c) These radiological environmental controls are described below. ! Since no Commission approved laboratory supplies TLDs as part of a comparison program, no l w TLDs are analyzed as part of the INTERLABORATORY COMPARISON PROGRAM.
Offsit? Dose Calculation Manu;l Pcge 201 of 313 Revision 2, Change O p 2. Controls on the Annual Radiological Environmental Operating Report (AREOR) (v) a) The AREOR shallinclude a summary description of the radiological environmental monitoring program (REMP). b) The AREOR shallinclude a summary description of the Independent 1 Spent Fuel Storage Installation Monitoring Program (ISFSIMP), c) The AREOR shallinclude a table similar to Attachment 13 which states the distance and direction from the central point between the two containment buildings to each of the REMP sample points, d) The AREOR shallinclude a table similar to Attachment 20 which states the distance and direction from the central point of the ISFSI to each of the ISFSIMP sample points. e) The AREOR shallinclude summaries, interpretations, and an a1alysis of trends of the results of the radiological environmental surveillance activities for the report period. f) The AREOR shallinclude a comparison between the annual REMP results and the Radiological Environmental Operating Report preoperational studies.
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g) The AREOR shallinclude a comparison between the annualISFSIMP results and Radiological Environmental Operating Report pre fuel load studies. h) The AREOR shallinclude a comparison with operational contro s as appropriate.
- 1) Tha AREOR shallinclude a comparison with the previous environmental surveillance reports.
j) The AREOR shallinclude an assessment of the observed impacts of plant operation on the environment. k) The AREOR shallinclude an assessment of the observed impacts of ISFSI operation on the environment. l} The AREOR shallinclude the results of the land use censuses required by Control 3.12.2. m) The AREOR shallinclude the results of analysis of all radiolegical environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20. n) The AREOR shallinclude the results of all environmental radiation measurenients taken during the period pursuant to the locations specified on Attachments 13 and 20. o) The AREOR shallinclude summarized and tabulated results-in the j format of the table in the Radiological Assessment Branch Technical v Position, Revision 1, November 1979-of analysis of all radiological
Offsit) Dose C:lcul: tion Manual P g)202 of 313 i Revision 2, Change 0 ( environmental samples taken during the period pursuant to the locations ( specified on Attachments 13 and 20. p) The AREOR shallinclude summarized and tabulated results--in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979--of all enWonmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20. q) The AREOR shallinclude an explanation for missing results,if some individual results (as described in the above paragraph) are not available for inclusion with the report. ' r) The AREOR shallinclude any data which was missing from previous reports. s) The ARECR shallinclude at least two legible maps' covering all REMP sampling laations keyed to a table giving distances and directions from the central point between the two containment buildings. , t) The AREOR shallinclude at least one legible map covering ail ISFSIMP sampling locations keyed to a table giving distances and directions from the central point of the 13FSI. u) The AREOR shallinclude results of the licensee participation in the INTERLABORATORY COMPARISON PROGRAM required by Control l
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G' 3.12.3. , v) The AREOR shallinclude a discussion of all deviations from the sampling schedules listed on Attachments 14,15,16, and 17, and specify the reason (s) for the deviations, and the plan for preventing recurrence. w) The AREOR shallinclude a discussion of all analyses in which the LLD listed on Attachments 15,16, and 17 (and required by Control Table l 4.12-1) was not achievable. x) The AREOR shallinclude the identification of the cause of unavailability of samples (if any), and describe the locations used for replacement samples. y) The AREOR shallinclude any permanent changes in the sample locations in the monitoring program. z) The AREOR shallinclude revised figure (s)(e.g.,like Attachments 18 and
- 19) and tables (e.g., like Attachment 13) for the ODCM which reflect any new REMP sample location (s).
aa) The AREOR shallinclude revised figure (s)(e.g.,like Attachments 2. and
- 22) and table (s) (e.g., like Attachment 20) for the ODCM which reflect any new ISFSIMP sample location (s).
fj Ont thall cover stations near the SITE BOUNDARY; a second shall include the more V distans ._,a _1s.
3 Offsit) Dose Calculation Manual Pag)203 of 313 l Revision 2, Change 0 l l ( bb) The AREOR shall receive an independent review for technical content (3 ,/ prior to submittal to the NRC. cc) The AREOR shallidentify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result, dd) Material provided in the AREOR shall be consistent with the objectives outlined in the ODCM and 10 CFR 50, Appendix 1, Section IV.3.2, IV.3.3 j and IV,C.
- 3. Surveillance Requirement (s) -
a) Write the Annual Radiological Environmental Operating Report covering the previous calendar year's operation of the reactor units.
- 4. Responsible Company Organizations a) The Chemistry Section, BG&E CCNPPD, is responsible for ensuring the l performance of the surveillances listed above'. -
- 5. Initia:ing conditions a) Submit the Rutine AREOR (covering operation of the reactor units for "
the previous calendar year) of each year in accordance with Technical Cpecifications - Administrative Controls.
's) 6. Calculation methodology '
a) Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures, or should be included in the AREOR.
- 7. Corrective actions a) If analyses are not performed as required, document actions taken to prevent reoccurrence in the AREOR pursuant to Technical Specification
- Administrative Controls.
INDEPENDENT SPENT FUEL STORAGE INSTALLATION MONITORING PROGRAM
- 1. Introduction a) The Technical Specifications for the Independent Spent Fuel Storage Installation' (ISFSI), licensed under 10 CFR 72, require that monitoring for the ISFSI be added to the existing environmental monitoring program for CCNPP.
2 A separate company may be contracted to complete the Routine AREOR. (sJv The Technical Specifications For Calvert Cliffs Independent Spent Fuel Storage installation is Appendix 'A' to Materials License SNM-2505. l
- - - - ~
l Offsit] Dose Calculation Manu:1 Pag) 204 of 313 Revision 2, Change 0 O b) BG&E has committed to additional monitoring for the ISFSt.' Q) c) Radiological environmental controls have been established to implement the requirements and commitments described above. d) These radiological environmental controls are described below.
- 2. Controls on the ISFSI Monitoring Program a) Environmental monitoring sites, as described in Attachment 20, shall be established to monitor the air, egetation, and soil as well as direct radiation in the ISFSI environs b) Analysis parameters, analysis frequencies, detection limits, and ACTION levels shall conform to the applicable requirements of Controls 3.12.1. l (See attachment 14,15,16, and 17) c) Map (s) shall be maintained and shall show the locations of the 9nvironmental monitoring sites with respect to plant facilities. (See '
attachme.nt 21 and 22). -
- 3. Surveillance Requirements a) Surveillances for direct radiation n (1) Direct radiation dosimetry shall be collected from locations
( SFDR1 SFDR16, DR7, and DR30 listed in Attachment 20. , (2) In the event any dosimetry at an existing monitoring location SFDR1-SFDR16, DR7, or DR30 becomes unavailable, place new dosimetry at the monitedng station. (3) Analyze the dosimeters at 'he frequencies and for the parameters identified on Attachment 14 b) Surveillances for airbome particulate activity (1) Air particulate samples shall be collected from locations A1 and SFA1-SFA4 listed on Attachment 20. (2) In the event any particulate filter becomes unavailable from an existing monitoring location A1 or SFA1-SFA4 described on Attachment 20, place a new particulate filter in the air sampler at the monitoring station.
' See the letter titled " Response to NRC's Comments to Environmental issues Regarding BG&E',s License Application for Calvert Cliffs Independent Spent Fue: Storage Installation (ISFSI)" from Mr. R. E. Denton (BG&E) to Director, Office of Nuclear Material Safety and Safeguards (NRC),
dated November 1,1990. 2 Environmental monitoring sites and monitoring parameters specifically excluded from the O ISFSIMP hclude airbome radiciodines, radiciodines in food products, surface water, and fish (" and invenebrates. Additionally, soil samples shall be collected in lieu of shoreline sediment. The sampling frequency for vegetation and soil shall be quarterly.
- _-- ---_--_--m.___ . - - _ _ _ _ . _ _ _ - _ _ _
I Offsit) Dise C lculati:n M:nu 1 Page 205 of 3'13 Revision 2, Change 0 (3) (A) Analyze the samples at the frequencies and for the parameters identified under " Particulate Filters" on Attachment 15, c) Surveillances for deposition on vegetation (1) The vegetation samples SFb1 SFb5 shall be collected from the locations listed on Attachment 20. (2) In the event any of the sampling sites SFb1 SFb5 described on 1 Attachment 20 become unavailable, establish new sampling sites ' as described below: (a) In lieu of sample SFb1, collect vegetation grown in the NW sector of the ISFSt. 1 (b) In lieu of sample SFb2, collect vegetation grown in the l general vicinity of the CCNPP Visitor's Center. ' i (c) In lieu of sample SFb3, collect vegetation grown in,the North North West sector of the ISFSt. (d) In lieu of sample SFb4, collect vegetation grown in the South sector of the ISFSI. (e) In lieu of sample SFb5, collect vegetation grown in the m ( Southeast sector of the ISFSt.
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V (3) Analyze the samples quarterly for the non-lodine parameters identified under " Food Products" on Attachment 17. d) Surveillances for soil activity (1) The soil samples SFS1-SFSS shall be collected from the locations listed on Attachment 20. (2) In the event any of the sampling sites SFS1-SFS5 described on Attachment 20 become unavailable, establish new sampling sites as dcscribed below: (a) in lieu of sample SFS1, collect soilin the NW sector of the ISFSI. (b) In lieu of sample SFS2, collect soil in the general vicinity of the CCNPP Visitor's Center. (c) In lieu of sample SFS3, collect soilin the North North West sector of the ISFSI. (d) In lieu of sample SFS4, collect soil in the South sector of the ISFSI. (e) In lieu of sample SFSS, collect soil in the Southeast sector (rw) of the ISFSt.
l Offsita Dose Calcul: tion Manual Pcg3 206 of 313 Revision 2, Chan00 0 l (( (3) Analyze the samples quarterly for the parameters identified under
" Shoreline Sediment Sample" on Attachment 16.
- 4. Responsible Company Organizations a) The CHEMISTRY SECTION, BG&E CCNPPD, is responsible for l ensuring the performance of the surveillances listed above.
5, Initiating conditions a) Collect samples in accordance with the frequencies specified on Attachments 14,15,16, and 17. Soil and vegetation samples shall be collected quarterly. b) Analyze samples in accordance with the frequencies specified on Attachments 14,15,16, and 17. Soil and vegetation samples shall be analyzed quarterly. c) Calculate the potential annual doses in accordance with the methodology outlined elsewhere in this section if any of the following - conditions are true: (1) any of the above surveillance results reveallevels of
-~
environmental activity greater than the ACTION Levels specified on Attachments 14,15,16, and 17, as appropriate. (per Control l Table 3.12 2), or (2) any radionuclides other than those listed on Attachments 14,15, 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than the limits listed in Control 3.12.1.b. d) The Chemistry Section, BG&E CCNPPD, is responsible for notifying the General Supervisor--Chemistry, CCNPP, if any of the following conditions are true: (1) any of the above surveillance results reveallevels of environmental activity greater than the ACTION Levels specified on Attachments 14,15,16, and 17, as appropriate (per Control l Table 3.12-2), or (2) any radionuclides other than those in Attachments 14,15,16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than the limits listed in Coatrol 3.12.1.b. n 1 1
Offsite Dose Calcul: tion Manu:1 Page 207 of 313 Revision 2, Change 0 O %J
- 6. Calculation methodology a) If any (of the above) surveillance results reveallevels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15,16, or 17 (per Control Table 3.12 2), calculate potential annual doses l for the pathway of interest, in accordance with the methodologies contained in Regulatory Guide 1.109.
b) If methodologies other than those listed in Regulatory Guide 1.109 are used to calculate potential annual doses, such methodologies shall be documented in accordance with Control 3.12.1.b. ,
- 7. Corrective actions a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR.
b) If the ISFSIMP is not being conducted in accordance with the
" Surveillance Requirements" listed elsewhere in this section, document -
deviations in the AREOR. c) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15,16, or 17, as appropriate, submit a Special Report to the NRC (per Control 3.12.1.b). O d) When radionuclides other than those listed on Attachments 15,16, and 17 are detected, and when those radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, submit a Special Report if required by and in accordance with Control 3.12.1.b. O l
l Offsit] Dose Calculation Minual Page 208 of 313 Revision 2. Change 0 O RADIOACTIVE EFFLUENT RELEASE REPORT
\j INTRODUCTION
- 1. Technical Specification Administrative Controls requires submittal of a written report to the NRC every 12 months.
- 2. The report is described below.
RESPONSIBILITIES
- 1. The General Supervisor Chemistry is responsible for the timely and accurate completion of the report.
REPORT CONTENTS
- 1. The Radioactive Effluent Release Report (RERR) covering the operation of the unit shall be submitted every 12 months in accordance with 10 CFR 50.36a.
- 2. The RERR shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives ou!!ined in the ODCM and in conformance to 10CFR50.36a and 10CFR50, Appendix 1, section IV.B.1. .
Principle Gamma Emitters from Batch Waste Releases and Turbine Building Sump shall be analyzed and included in this report pursuant to Table Notation c n of Control Table 4.11-1, " Radioactive Liquid Waste Sampling and Analysis Q Program." In addition, Principal Gamma Emitters from the Waste Gas Storage Tank, Containment Purge and Vent, and the Main Vent shall be analyzed and included in this report pursuant to Table Notation b of Controls Table 4.11-2,
" Radioactive Gaseous Waste Sampling and Analysis Program." Additional information which may be required in the report is contained in Controls 3.3.3.9.b,3.3.3.10.b and Technical Specification - Administrative Controls.'
- 3. The RERR shallinclude 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-hourlisting 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.2 This same report shallinclude 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. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
in lieu of submission with the RERR, Sr" and Sr* analysis results may be submitted in a
, supplementary report, provided the results are submitted no later than May 15 of each year.
p) in lieu of submission with the Radioactive Effhent Release Report, this summary of required t meteorological data may be retained on site in a file that shall be provided to the NRC upon U request. I I
1 Offsits Dose Calcul: tion Manuil P go 209 of 313 l Revision 2, Change 0 (] (,/
- 4. The RERR 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 calcu;ating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."
- 5. The RERR shall include the following information for each class of solid waste '
(as defined by 10 CFR Part 61) shipped offsite during the report period:
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement or estimate),
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Source of waste and processing employed (e.g., de? atered spent resin, compacted dry waste, evaporator bottoms),
.~
- e. Solidification agent or absorbent (e.g., cement).
- 6. The RERR shallinclude a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents mado during the reporting period.
- 7. The RERR shallinclude any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and a listing of new locations for dose calculations identified by the annualland use census pursuant to Control 3.12.2.
- 8. The RERR shallinclude any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP)' The report shall contain:
- a. A description of the equipment, components and processes involved,
- b. Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the POSRC.
REPORT SUBMITTAL
- 1. Prior to submittal a Independent Technical Review will be performed.
- 2. The RERR will be submitted every 12 months in accordance with 10 CFR 50.36a and 50.4.
h , (G Licensco initiated changes to the PCP shall become effective upon review by the POSRC and approval of the Plant General Manager.
Offsita Dose C:lculation M:nual Page 210 of 313 Revision 2 Change 0 r] ADMINISTRATION On THE ODCM V INTRODUCTION
- 1. Procedures covering the ODCM and the implementation of the ODCM shall be implemented.
- 2. Administrative controls have been established to implement controls on the ODCM.
- 3. These administrative controls are described below. .
CQNTROLS ON THE ODCM
- 1. The format, organization, content, and administration of the ODCM are controlled by CH-1-103.
- 2. Methodologies identified in the ODCM are implemented by various BG&E organizations in accordance with approved procedures. (See the .
" RESPONSIBILITIES" section of CH-1103 for a list of those Sections of BG&E l responsible for approving and maintaining procedures which implement the requirements of the ODCM.)
- 3. The main vent stack flow rates shall be verified in accordance with the surveillances described in the following section.
- 4. Licensee initiated changes to the ODCM:
(A) - a) Shall be documented and records of reviews performed shall be retained. This documentation shall contain (1) Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s); (2) A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and 10 CFR Part 50, Appendix l, and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations; b) Shall become effective upon review by the onsite review function and approval of the plant manager; and c) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in 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 shallindicate the date (i.e., month and year) the change was implemented. - n v 1
Offsita Dose Calculation Manual Page 211 of 313 i Revision 2, Chango O SURVEILLANCE REQUIREMENTS
- 1. Complete audits and PERIODIC REVIEWS of the ODCM in accordance with CH 1-103.
- 2. Determine main vent stack flow rates for both units as described below, a) The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%).
b) The Test and Equipment Unit shall be responsible for performing this ' test. c) The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. d) IF the main vent stack flow rate for either unit, as determined in accordance with approved Test and Equipment procedure (s), changes i 10% from the values referenced in Attachment 7 of the ODCM, a - technical evaluation shall be initiated to determine if the ODCM should be revised. RESPONSIBLE COMPANY ORGANIZATIONS
- 1. CH 1-103 identifies the responsibilities of various personnel and company l O organizations which administer and implement the ODCM. This section of the '
ODCM identifies company organizations which are assigned responsibility for implementing the surveillances described above.
- 2. The Test Equipment Unit is responsible for ensuring the main vent stack flow rate test procedure (e.g., TE-001 or equivalent) is completed in accordance with the surveillances listed above.
- 3. The Test Equipment Unit is responsible for forwarding main vent stack flow rate test results to the General Supervisor - Chemistry.
- 4. The RETS Program Manager, CCNPPD CHEMISTRY SECTION, is responsible for evaluating main vent flow rate test results (e.g., TE-001 or equivalent results) and for performing the technical evaluation described in the above surveillances.
INITIATING CONDITIONS
- 1. Main vent stack flow rates shall be determined at least once per 6 months (1 25%), or more often if required by Controls.
- 2. Complete PERIODIC REVIEWS of the ODCM as specified in CH-1 103.
/N .I i
j Offsits Doss Cciculation Manual Page 212 of 313 l Revision 2, Change 0 l CALCULATION METHODOLOGIES
- 1. Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures.
- 2. Documents which serve as a basis for calculation methodologies used in the ODCM should be maintained in an accessible location.
(1) Supporting documents may be incorporated into the ODCM (e.g., as Attachments).
~
(2) Supporting documents may be maintained in a " procedure history file" (3) Supporting documents may be identified in the " references" section of the ODCM. CORRECTIVE ACTIONS
- 1. IF main vent stack flow rates, as determined in accordanec with appropriate Test Equipment procedure (s), change i 10% from the values referenced in -
Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised. BASES -'
- 1. [8527), NRC Inspection Report INSR 91-30/30 O
0
i Offsit? Dose C:lculation M:nual Page 213 of 313 j Revision 2, Change 0 l l n EXECUTIVE
SUMMARY
OF CHANGES ()o - Rev. Chg, Description No. No. 0 0 Initialissue of ODCM under control of CCl-413 0 1 Added the words " Revision 0, Change 1" to title page. Added commitment / bases tracking number [B527] to margins of pages 10,11,12, and 60. Added a
- Bases" section to page 160. Added " Executive Summary of Changes" section to page 160. Modified " List Of Effective Pages." Changed " Fossil Energy Division" to " Corporate Affairs Group."
l 1 0 This revision adds the Radiological Environmental Monitoring Program for the ISFSI to I the ODCM. Other minor changes were made. All changes are listed below. Page numbers refer to Revision 1, Change 0. (1) Changed Revision numbers on all pages (pp.1247) (2) Changed title from RETS Coordinator to RETS Program Manager (pp. 1, 70,75,82,87,16?). (3) included ' Radiation Safety Section in the Applicability / Scope (p. 4) and assigned them responsibility to assist in measurement of direct radiation (p.145). (4) Corrected typographical errors (pp. 9, 27, 33, 45, 49, 53, 63, 74,124,130,138,143,151,152,168,181, 225, 236). (5) Updatad references to reflect new revision numbers for safety evaluations, and added another safety evaluation (pp.10,11,55) (6) Clarified requirements for minimum number of circulating water pumps for liquid releases (pp. 18,29, 39) (7) IncMded . reference to Technical Specification 3.3.3.10 (pp.18,29,39). (8) Removed subjective reference to " insignificant" related to monitor background count rates (pp. 20,31,41). (9) Deleted references to specific section numbers within the ODCM (pp. 21,25,31,35,41, 65,71,78,85, 96). (10) Provided additional Guidance regarding when fixed setpoints - should be changed pp. 21,31,41,71,85, and 96). (11) Changed reference from release permit,0117C, or 0117D to Alarm Manual (pp. 73,86,97), and deleted inappropriate p reference to Alarm Manual (pp. 32,33,42,43). (12) Stipulated thet the adjustment of (~j monitor setpoints is not required if the monitor is either inoperable or not the primary - monitor (pp. 23,33,43,76,88). (13) Modified definitions of parameters to " actual" instead of " minimum" flow rates (pp. 46,47,48, 52,54,55,56), (14) Deleted unnecessary paragraphs (pp. 46,47,48,52,53,54,56). (15) Specified that the flow rate of undiluted radwaste and the flow rate of service water may be 0 gpm when calculating dilution water flow rate (pp. 47,48,53,54,56). (16) Moved paragraphs (pp. from p. 63 to pp. 61 and 62). (17) Deleted incorrect sensitivity requirement for plant radiation monitors (pp. 66,78,89). (18) Changed nr,me of setpoints (pp. 67-73). (19) Deleted reference to 2 MPC limit (p. 67). (20) Updated ODCM to correspond to recent change to CCNPP Alarm Manual (p. 71). (21) Editorial changes (pp. 72,150,236,233). (22) Removed provision for not chan0ing the adjustable setpoint for routine gaseous releases (p. 73),(23) Modified formula for fixed setpoint to include value of background (pp. 92,95). (24) Deleted inappropriate reference to adjusting setpoint for 0-RI-2191 when discharging containment vents and PURGES (p. 98). (25) Specified units for dose rate (pp.101). (26) Specified calculation constant for calculating instantaneous release rate (pp.102, 103,104,105,110,112,117,118,120). (27) Specified units for dose (pp.136), (28) Specified value of x/Q and D/Q (pp.136). (29) included environmental r cnitoring program for ISFSI (pp. 148,155-161,233,238-241,243). (30) Revised Attachment 5 (guidance for calculating "radionuclide mixture") to include use of computer data base (p. 172). (31) Added system interconnections between liquid and solid waste processing systems to diagram of liquid waste processing system, Attachment 4 (p.171). (32) Added containment vent release path to diagram of gaseous waste system Attachment 9 (p.178). (33) Changed list of effective pages (pp. 244-247). p, _ _ _ _ _ _ _ _ _ . _ i
Offsite Dose Cciculation M:nual P:ga 214 of 313 Revision 2, Change 0 (O Rev. Chg. Description h No. 2 No. 0 Extensive revision to incorporate Technical Specification removed by license amendment. Part i and Part 2 incorporate parts of previous version of ODCM and Technical Specification to be removed in the license amendment. Part 3/4 are the Technical Specifications moved and modified to fit in the ODCM in accordance with Generic Letter 89-01. Part 5 is the remaining contents of the previous version of the ODCM with modifications to references to the removed portions of the Technical Specifications and the new structured Technical Specifications. In addition, the Unh 1 Main Vent flowrate was updated to reflect data from surveillance tests, liquid dose factors were added for Sb-122, Eu154 and Eu155, references to CCI procedures were updated, updated 10 CFR 20 references, added gaseous pathways for containment equipment hatch and auxiliary feed pumps, added requirements for independent technical review of reports, added section for Radioactive Effluent Release Report, added details to ODCM controls, updated REMP sampling descriptions and maps, and responsibilities for the Radiological Environmental g Monitoring Program were changed from Corporate Affairs to Nuclear Division. PART 6,0 : ATTACHMENTS Attachment 1 Final Grading And Drainage Plan ~ Attachment 2 Outfall 001 - Sources of Liquid Radioactive Waste Attachment 3 Outfalls 002,003,004 - Potential Sources of Liquid Radioactive Waste Attachment 4 Block Diagram of Liquid Radioactive Waste Systems Attachment 5 Dominant and Less Dominant Radionuclides in Typical Radwaste " Discharges Attachment 6 Liquid Effluent Dose Factors
/Q Attachment 7 Generalinformation Related to Gaseous Releases via the Main Vents V Attachmen' 8 General Information Related to Gaseous Releases via Pathways other than the Main Vents Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems Attachment 10 Noble Gas Dose Factors Attachment 11 Empirical Derivation Of Site-Specific Dose Factors Attachment 12 Gaseous Effluent Pathway Dose Factors Attachment 13 Environmental Monitoring Sites for PEMP Attachment 14 Radiological Environmental Monitoring Program Surveillances for Direct Radiation Attachment 15 Radiological Environmental Monitoring Program Surveillances for Airbome Activity Attachment 16 Radiological Environmental Monitoring Program Surveillances for Waterbome Activity Attschment 17 Radiological Environmental Monitoring Program Surveillances for Ingestible Activity Attachment 18 Map of Environmental Monitoring Sites for REMP (5 Km Radius)
Attachment 19 Map of Environmental Monitoring Sites for REMP (10 Mile Radius) Attachment 20 Environmental Monitoring Sites for ISFSI Attachment 21 Map of Environmental Monitoring Sites for ISFSI Attachment 22 Map of Environmental Monitoring Sites for ISFSI (ENLARGED) Attachment 23 Effluent Radiation Monitors Attachment 24 List of Effective Pages
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v
. . . . -- .. ~ . ..- .- . - . . ~ . - . - . - . . - _ . - - . . - - ~ .
;- OffsNe Dose Calculation M nual Page 215 of 313 .;
t Revision 2, Change 0:: Attachment 1- . Final Grading And Drainage Plan -
- A reference diagram which depicts the grading for and the drainage from the Calvert Cliffs Nuclear Power Plant can be found in the following reference: ,
Final Grading And Drainage Plan - , .
- Calvert Cliffs Nuclear Power Plant Units I and 2, ;
BGE Document ID Number: 61517SH0001 BGE Document ID Number: 61514SH0002 The above reierenced grading and drainage plan is intended for reference only.
. This drawing may not reflect the changes and modifications since March 1975. ,
~
j s -
- 1. . f% ,
Q . i d 4 a t
Dose Calculation Manual
.y ;
R 2. Change 01 Page 216Q1 Attachment 2 Outfa!! 001 - Sources of Liquid Radioactive Waste Waste Stream Radiahon Type of Max. Discharge Maximum Volume Notes Monitor Release Flow Rate gal / min liters / min gal liters Rx Coolant Wst. Mon.Tk.- 0-RE-2201 Batch 120 454 9000018 3.407E51 s Rx. Coolant Wst Rec. Tk. 0-RE-2201 Batch 120 454 9000018 -3.407E51s ' Misc. Wst. Mon. Tk. 0-RE-2201 Batch 120 454 400018 15140ts Misc. Wst. Rec. Tit - 0-RE-2201 Batch 120 454 4000t s 15140 1s - Aux. Boiler Steam Drum All releases are via Auxiliary Blowdown Tank Aux. Blowdown Tk. Unmonitored Continuous 20015 757 N/A N/A Waste Neut. Tk.11 Unmonitored Batch 10001 37901 45988 1.74E5 Waste Neut. Tk.12 Unmonitored Batch 10001 3790 47749 1.80E5 -i Stm. Gen. Blowdown Tk. 1/2-RE-401417 Batch 14 2252 8522 23503 88953 Component Cooling Wated Unmonitored Continuous variable 5 variab!e5 440908 1.669ES Condenser Hotwells Unmonitored Batch 13 45007 170007 1.05ES 3.97ES Salt Water System Unmonitored Continuous 15500 58670 N/A N/A Condensate Storage Tanks Unmonitored Batch variable 9 variable 9 3.5E510 1.3E610 Demin. Water Storage Unmonitored Batch variable 9 variable 9 3.5E510 1.3E610 Tank" - Precoat Sump 12 Unmonitored Continuous 50 94.6 10305 39004 , 6
---_-.g, ,,
g\ ( Page 217 g .I Dose Calcu!ation Manual R n 2, Change O Attachment 2 Outfa!1001 - Scurces of Liquid Radioactive Waste
- 1. This flow rate is only an approximation. The motive force is gravity
- 2. This is the maximum flow rate. The actua! flow rate will be considerably less,
- 3. This is the maximum volume of the tank, however, since this is a CONTINUOUS RELEASE, the volume discharged would be calculated from the discharge flow rate Pnd duration of the release.
- 4. There is no direct path by which radioactive liquid from the CCW System cculd enter outfall 001. Liquid from the CCW System may leak into either the Salt Water System (which drains to outfail 001) or the Liquid Waste Processing System (via Aux. B!dg. Drains).
- 5. Radioactive liquid is not normally released from the CCW system. Flow rate to outfail 001 may occur via Salt Water System. For this pathway, the flow rate will vary (e g., depending on size of leak). See Safety Analysis No. 2, FCR 82-1053, Supplement 1.
- 6. System volume is 5894 cubic feet. Conversion constant is 0.13368 cubic feet per gallon.
- 7. The flow rate shown here is the flow rate for one condensate pump. Verify the number on condensate pumps in service, and modify this flow rate accordingly.
- 8. Radioactive liquid is not normally released from the CST. The CST would drain to outfal1001 only if catastrophic tank failure occurred.
Small leaks would be collected ty storm drains which would be released to outfal1002.
- 9. Flow rate should be calculated on a case-by-case basis.
- 10. Volume obtained from ~ Plant Data Book", BG&E CCNPP Units 1 and 2 Bechtel Power Corporation Volume 1. Job 6750.
- 11. Radioactive liquid is not normally released from the demineralized water storage tank (DWST) The DWST would drain to outfall 001 only if catastrophic tank failure occurred. Small leaks would be collected by the storm crains which wou!d be rel eased to outfa!! 002.
- 12. If the precoat sump contents were contaminated, releases would probably be directed to outfa!! 001, hovtever depending on the valve line-ups, the sump may be discharged to outfall 002.
- 13. May be a CONTINUOUS RELEASE if contaminated sealing steam is operated during the release.
- 14. Although steam generator releases are normally BATCH RELEASES, discharges may at times ce coenuous. Verify type of release to I be conducted prior to discharge.
- 15. This is the maximum rated discharge for two pumps in operation. If less than two pumps will be operable for the release, a flow setpoint l
l should be specified for the release.
- 16. The volume specified is the design basis volume from Table 11-1 of the UFSAR.
The steam generator blowdown effluent radiation monitor,1/2-RE-4095, may be equivalent to the 1/2-RE-4014 (see part 5. Liquid l 17. Effluent Radiation Monitor Alarm and Trip Setpoints. para. 2) I l l
Dose Calculation Manual ( ) Page 218 [ R ston 2 Change 0 Attachment 3 Outfal!s 002,003; 004 - Potential Sourc<.5 of Uguid Radioactive Waste Waste Volume Stream Radiation Type of Max. Discharge Ficw Rate Maximum Volume Outfall Monitor Release gal / min hters I min gal liters Turbine Bldg. Sump No.11 Unmomtored Continuous 470 889 1950 7381 002 Turtine Bldg. Sump No.12 Unmomtcred Continuous 470 889 2415 9141 002 Turbine Bldg. Sump No. 21 Unmonitcred Continuous 470 889 2490 9425 002 Turbine Bldg. Sump No. 22 Unmonitored Continuous 470 889 2182 8259 002 Precoat Sump Unmonitored Continuous 50 94.6 10305 39004 002 Diesel Oil Interceptor Sump Unmonitored Continuous 100 378.5 5790 21920 004 Yard OilInterceptor Unmonitored Ccotinuous variable 3 variable 3 N/A N/A 002 Refueling Water Tank Unmonitored Batch / Cont.7 variable 3 variable 3 4.2E5 1.6E6 any9 Condensate Storage Tank Unmonitored Batch / Cont.7 variable 3 vanable3 3.5E56 1.3E66 002M Service Water System 1/2-RE-1595 Continuous variable 3 variable 3 31418 1.189ES 002 Demin. Water Storage Tara Unmonitored Batch / Cont.7 varQble3 variable 3 3.5ESS 1.3E66 0022 Plant Heating System Unmonitored Continuous variable 3 variable 3 N/A N/A 0028
- 1. The maximum discharge flow rate is dependent on the influent flow rate (e g., turbine building sump discharges).
- 2. The contents of these tanks are not norma!!y discharged to the environment, however in the event of a smallleak or catastrophic tank failure, the tank contents could be released to the designated outfail(s).
- 3. Maximum discharge flow rate sha!! be determined on a case-by-case basis.
- 4. It is also possible for the CST to be discharged via the condenser hotwells.
- 5. Flow rate should be calculated on a case-by-case basis.
- 6. Volume obtained from " Plant Data Book", BG&E CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1, Job 6750.
- 7. Releases via this pathway would be considered a BATCH RELEASE if a catastrophic tank failure occurred. In the event of a small leak, the release may be considered a CONTINUOUS RELEASE. The release mode should be determinatt 1 on a case-by-case basis.
- 8. The plant heating system is a closed system and is not normally released to the environment. In the e.ent of a leak, the effluent may be released to the environment via the turbine building sumps (outfall 002). In some cases, depend'ng on the location of the leak, the effluent would be collected in the auxiliary building sump and subsequently released through the nquid radioactive waste processing system. The effluent pathway should be determined on a case-by-case basis.
- 9. The contents of these tanks are not normally discharged to the environment, however in the event of a small leak or catastrophic tank failure, the tank untents could be released to outfall 002,003, or 004..
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. 1
[ \ (, l R Dose Calculation Manual on 2. Change 0 - Q Page 219 ( w/ l Attachment 4 Block Diagram of Liquid Radioactrve Waste Systems Reactor Coolant Vaste M:seetterwovs Veste i thes I thee a tret 2 t.pu t 2 l thet t tems 2 ansa S W Laurury CWCS 81C Weest frC D see CVCS SVC $/G Leedmann re,e W enne 4 Lore %rw fare Leem e:_ s w do D-emu tres ea2; 1' nC W so Fsitors (25 12e W g.gIE**994 1' 2-8tE-4914 fees Weseo semesse Tee AUTCruTIC:
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Offsita Doss Calculation Manu 1 Page 220 of 313 Revision 2 Change 0 O Attachment 5 DOMINANT and LESS DOMINANT RADIONUCLlDEs in Typical Radwaste Discharges The term f,- a fraction which represents the relative activity contribution of nuclide i to the average total effluent cctivity - is used in several equations in the ODCM (e.g., equations 2G. SG,3L, and 4L). This attachment provides guidance for calculating the values of f,.
- 1. Select the calendar quarters which contain at least one " typical" liquid (or gas) release (see definition of TYPICAL RADWASTE RELEASE).
- 2. For each of the calendar quarters selected above, obtain a listing of the nuclides, nuclide activities, and release (end) dates.
- a. This data may be obtained from the Radioactive Effluent Release Report (s) for the time periods of' ' l Interest, or
- b. This data may be obtained from a computer-based effluent management system (if available).
- c. The values of nuclide activities and release end times may be close approximations of the true values.
- 3. Sum the quarterly activities (curies) for each individual radionuclide.
Ari = EAa i Eq.1R
- 4. Sum the quarterly activities for all radionuclides, i. -
- . Ar = E Ari Eq.2R
- 5. Calculate the fraction of the total activity attributable to each radionuclide (i.e., the relative activity of nuclide 1).
fi = Ay/At i Eq.3R l B. Characterize each radionuclide as either " dominant" or "less dominant" as shown below: The radionuclide is defined as a DOMINANT RADIONUCLIDE if the following inequality is true. fi 2. 0.010 Eq.4R The radionuclide is defined as a LESS DOMINANT RADIONUCLIDE If the following inequality is true, fa < 0.010 Eq.-SR O
I I Offsit:r D0so Cdculation Manu;l Paga 221 of 313 Revision 2 Change O Attachment 6 Liquid Effluent D0se Factors O) ( v (mrem /hr per uCi/ml) Nuchde Bone Liver Tbody Thyroid Kidney Lung Ottract H3 0 000E+00 2 820E-01 2 820E 01 2.820E 01 2 820E-01 2.820E-01 2 820E-01 BE 7 2.700E+01 1.100E +01 6.500E +0i 1.300E+00 1.600E+01 3.100E +00 2.700E +02 C 14 1.450E +04 2 900E+03 2.900E +03 2 900E+03 2 900E+03 2.900E+03 2.900E+03 NA 24 4 570E41 4 570E 01 4 570E-01 4 570E 01 4 570E-01 4.570E 01 4 570E-01 P 32 4 690E+06 2 910E+05 1.810E +05 0 000E+00 0 000E+00 0.000E+00 5270E+05 CR 51 0 000E+00 0 000E+00 5580E+00 3 340E+00 1230E+00 7.400E+00 1.400E+03 ' MN 54 0 000E+00 7 060E+03 1.350E +03 0 000E+00 2.100E +03 0 000E+00 2.160E+04 MN-56 0 000E+00 1.780E+02 3150E+01 0 000E+00 2.200E +02 0 000E+00 5 670E+03 F E 55 5110E+04 3 530E+04 8 230E+03 0 000E+00 0 000E+00 1.070E+04 2.030E +04 FE 59 8060E*04 1.900E+05 7.270E+04 0 000E+00 0.000E +00 5.300E+04 6.320E +05 CO 57 0 000E+00 1.420E+02 2.360E+02 0 000E+00 0 000E+00 0 000E+00 3 590E+03 C0-58 0 000E+00 6 030E+02 1.350E+03 0 000E+00 0 000E+00 0 :X)0E+00 1.220E404 CO-60 0 000E+00 1.730E+ 03 3 820E+03 0 000E+00 0 000E+00 0 000E+00 3 250E+04 NI63 4 960E+04 3 440E+03 1670E+03 0 000E+00 0 000E +00 0 000E+00 7.180E +02 NI65 2 020E+02 2 620E+01 1.200E +01 0 000E+00 0 000E+00 0 000E+00 6 650E+02 " CU-64 0 000E +00 2140E+02 1.010E +02 0 000E+00 5 400E+02 0 000E+00 1.830E +04
) ZN-65 1610E +05 5130E +05 2 320E+05 0 000E+00 3 430E+05 0.000E +00 3.230E +05
- ZN49 3 430E+02 6.500E +02 4 560E+01 0 000E+00 4 260E+02 0 000E+00 9 850E*01 BR-82 0 000E +00 0 000E +00 4 070E+00 0 000E +00 0 000E+00 0 000E+00 4 670E+00 BR 43 0 000E +00 0 000E+00 7.250E-02 0 000E+00 0 000E+00 0 000E+00 1040E-01 BR-84 0 000E +00 0 000E +00 9 390E-02 0 000E+00 0 000E +00 0 000E+00 7.370E-07 BR 85 0 000E+00 0 000E +00 3 860E 03 0 000E+00 0 OC . 5.+00 0 000E+00 0 000E+00 R B-86 0 000E+00 6 240E+02 2 910E+02 0 000E+00 0 000E +00 0 000E+00 1.230E +02 R B-88 0 000E+00 1.790E +00 9 490E-01 0 000E +00 0 000E +00 0 000E +00 0 000E+00 RB 89 0 000E *00 1.190E+00 8 340E-01 0 000E+00 0 000E +00 0 000E+00 0 000E +00 SR.89 4 990E+03 0 000E +00 1430E+02 0 000E+00 0 000E+00 0 000E+00 8 000E+02 SR-90 1.230E +05 0 000E+00 3 010E+04 0 000E+00 0 000E+00 0 000E+00 3 550E+03 SR-91 9180E +01 0 000E+00 3.710E+00 0.000E +00 0 000E+00 0.000E +00 4 370E+02 SR 92 3 480E+01 0 000E +00 1510E+00 0 000E*00 0 000E+00 0.000E +00 6 900E+02 Y 90 6 060E +00 0 000E +00 1.630E-01 0 000E+00 0.000E +00 0 000E+00 6 420E+04 Y 91M 5 730E-02 0 000E+00 2 220E 03 0 000E+00 0 000E+00 0 000E+00 1.680E-01 Y-91 8880E+01 0 000E *00 2 370E+00 0 000E+00 0 000E+00 0.000E+00 4 890E+04 Y 92 5 320E41 0 000E+00 1.560E-02 0 000E+00 0 000E+00 0 000E+00 9 320E+03 Y 93 1600E +00 0.000E +00 4 660E 02 0 000E+00 0 000E+00 0 000E+00 5.350E+04 ZR-95 1590E +01 5110E+00 3 460E+00 0 000E+00 8 020E+00 0.000E+00 1620E +04
(] ZR 97 8 810E41 1.780E 01 8130E-02 0 000E+00 2 680E-01 0 000E+00 5 510E+04 \.,_,) N B-05 4 470E +02 2 490E+02 1340E+02 0 000E+00 2 460E+02 0.000E+00 1510E+06 N B-97 3 750E+00 9 490E 01 3 460E-01 0 000E+00 1.110E+00 0 000E+00 3 500E+03
. ._ ~ _. - . . - . ., - . - -- - - . . - - . . ~ . - . .
.Offr ~ Do.
- 91 Pag 3 222 0f 313 Rev Jn 2 -
- Attachment 6 -
Liquid Effluent Dose Factors
- _ (mrem /hr per uCi/ml)
Nuchde Bone- Uver Tbody - Thyroid Kidney t.ung G1 tract
~ MO-99 0 000E+00 1.280E+02 2.430E +01 N00EM 2.890E+02 0 000E+00 2.960E< 02 TC-99M 1.300E 02 3 660E-02 4 660E 01 0.000E+00 5.5ME 01 1.790E 02 2.170E+01 TC 101 1.330E 02 1.920E-02 1.880E 01 0 0U0E+00 3 460E-01 9.810E-03 0.000E+00 RU 103 1.070E+02 0.000E +00 4 600E+01 0 000E+00 4 070E+02 0 000E+00 1.250E+04 RU 105 8 890E+00 . 0 000E+00 3 510E+00 0 000E+00 1.150E+02 . 0 000E+00 5.440E+03 RU-106 1.590E+03 ~ 0.000E+00 2 010E+02 0 000E+00 3.060E+03 0 000E+00 1.030E+05 RH-103M 0000E+00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 CD-109 2.100E+05 4 000E+00 1.600E+06 1.500E+05 2.200E+07 1.800E+05 2.500E+06 AG-110M . 1.560E +03 1.450E+03 8.600E+02 0.000E+00 2 850E+03 0.000E+00 5.910E +05 SN 113 - 6.700E+03 1.200E+03 2.100E+04 6.200E+02 1.600k+03 7.300E+02 2.200E +05 SB-122 5300E+01 5.520E+01 6 690E+02 8.780E+00 2 610E+01 1.140E+01 6.580EiO3 l -
SB 124 2.770E+02 5230E+00 1.100E +02 6.710E 01 0.000E+00 2.150E+02 7.860E+03 58-125 1.770E+02 1.980E+00 4 210E+01 1.800E 01 0 000E +00 - 1.360E+02 1.950E +03 TE 125M 2.170E+02 7.860E+01 2.910E+01 6 520E+01 8820E+02 0 000E+00 8 660E+02 7E-127M 5.480E+02 1.963E+02 6.680E+01 1.400E +02 2.230E+03 0.000E+00 1.840E +03 f TE 127 8 900E+00 3.200E+00 1.930E+00 6 600E+00 3 630E+01 0 000E+00 7.030E+02 ,
- - - TE 129M 9.310E+02 3 470E+02 1.470E+02 3 200E+02 3 890E+03 0 000E+00 4 690E+03 TE 129 2.540E+00 9 550E 01 6.190E-01 1.950E+00 1.070E+01 0.000E+00 1.920E +00
+ TE 131M 1400E +02 6 850E+01 5.710E+01 1.080E+02 6 940E+02 0 000E+00 6.800E+03 TE 131 1.590E+00 6 660E-01 5 030E-01 1.310E+00 6990E+00 0.000E+00 2.260E 01 TE-132 2.040E +02 1.320E+02 1.240E +02 1.460E+02 1270E+03 0 000E+00 6.240E+03 1130 3 900E+01 1.170E +02 4 610E+01 - 9 910E+03 1.820E+02 0 000E+00 1.010E +02 1131 2.180E+n2 3120E+02 1.790E +02 1.020E+05 5 350E+02 0 000E+00 8730E+01 l132 1.060E+01 2.850E+01 9 960E+00 9960E+02 4 540E+01 0 000E+00 5 350E+00 l-133 7.450E+01 1.300E+02 3 950E+01 1.900E+04 2.260E+02 0.000E +00 1.160E+02 1134' 5 560E+00 1.510E+01 5.400E+00 2 620E+02 2.400E +01 0.000E +00 1.320E 02 1135 2.320E+01 6080E+01 2.240E+01 4 010E *03 9.750E+01 0 000E+00 6 870E+01 CS 134 ' 6 840E+03 1.630E+04 1.330E+04 0 000E+00 5.270E +03 1.750E+03 2.850E+02 CS 136 7.160E+02 2.830E+03 - 2.040E+03 -- 0 000E+00 '1.570E+03 2.160E+02 3.210E+02 CS-137 8.770E+03 1.200E+04 7.850E +03 0.000E+00 4 070E+03 1.350E+03 2.320E+02 CS-138 - 6 070E+00 - 1.200E+01 5.940E+00 0 000E +00 8 810E+00 8 700E 01 5.120E-05 BA 139 -' - 7.850E+00 5 590E 03 - 2.300E-01 0 000E+00 5 230E 03 3.170E-03 1.390E+01 BA 140 1.640E+03 2.060E+00 1000E+02 0 000E+00 7.020E-01 1.180E+00 3.380E +03 BA 141 3 810E+00 ' 2 880E 03 1.290E 01 0 000E+00 - 2 680E 03 - 1630E 03 1.800E-09 BA-142 1.720E+00 1.770E-03 1.000E 01 0.000E+00 1.500E-03 1.000E 03 0.000E+00
- LA-140 - 1.570E +00 7.940E 01 2.100E 01 0.000E+00 0 000E+00 0 000E+00 5 830E+04 CE 139 1000E+02 - 4 800E+01 3 700E+02 6 200E-01 3 400E+01 4 800E+00 3.200E+03 -
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1 I l Offsite Dose Calcul: tion Manual . Pags 223 of 313 Revision 2 Change 0 - Attachment 6
. Liquid Effluent Dose Factors (mrem /hr per uCl/ml).
Nuclide'~ _
! Bone. Liver -- Tbody- Thyroid Kidney Lung Oltract LA 142 8 000E42 . 3 670E42 9130E-03 0 000E+00 0 000E+00 0.000E +00 2 680E+02 CE 141 3 430E+00 2 320E+00 2.630E 01. 0000E+00 1.000E+00 0 000E+00 8.860E +03 1
CE 143 6 040E-01 4 460E+02 4 940E 02 0.000E+00 1.970E-01 0 000E+00 1.670E+04 CE 144 1.790E+02 7.470E+01 9.590E +00 0.000E+00 4.430E+01 0 000E+00 6.040E+04 PR 143 5790E+00 ~ 2.320E +00 2.870E 01 0.000E +00 1.340E+00 0.000E+00 2.540E+04 PR 144 1.900E 02 ' 7.870E-03 9 640E44 0.000E+00 4 440E 03 0.000E+00 2.730E 09 - NO-147 3 960E+00 4.580E+00 2.740E41 0.000E+00 2.680E+00 0.000E+00 2.200E+04 EU-154 3 870E+02 4 760E+01 3 390E+01 0.000E+00 2.200E+02 0.000E+00
. 3 450E+04 EU 155 5 420E+01 7.68E +00 4.960E+00 0 000E+00 3.550E+01 0 000E+00 6 050E+03 W 187 9.160E+00 7.660E +00 2 680E+00 0 000E+00 0 000E+00 0 000E+00 2.510E+03 NP-239 3 530E 02 3 470E-03 1.910E 03 0 000E+00 1.000E-02 0 000E+00, 7.110E+02 HG-203 1,400E+05 0 000E+00 1.600E+05 0.000E+00 1.600E+06 1.000E +05 3 200E'+05 1
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Calculation Manual Page 224 of 313 Rev: 2 Change O Attachment 7 General Information Related to Gaseous Releases via the Main Vents Waste Stream Radiation Type of Nominal Dtscharge . Maximum Discharge . Note -
. Monitor . release Flow Rate Flow Rate m'l sec .SCFM m'/sec SCFM.
Waste Gas System (WGDT)- 0-RE-2191' Batch N/A N/A 2.36E-2 50 2 , Cntmt. Vent (via H2 Purge) 1/2-RE-5415 Batch' N/A N/A 2.36E-2 50-l- Cntmt. Purge (5% Modified)' . 1/2-RE-5415 Continuous N/A N/A 1.928 4085 ' Cotmt. Purge (10% Modified) 1/2-RE-5415 Continuous N/A N/A 7.996 16940' 2
. Cntmt. Purge (100% Modified) 1/2-RE-5415 Continuous N/A N/A 17.70 .37500 2
! Unit 1 Main Vent Release 1-RE-5415' Continuous 59.4 125858 65.34 138444 8 8 (56.4') (119339') (61.9 ) (131273 ) Unit 2 Main Vent Release 2-RE-5415' Continuous 5
- l 47,1 99749' 51.78 109724 i l
Since the WGDT is released to the plant vent stack,1/2-RE-5415 and 1/2-RE-5416 may also be used to monitor releases from a WGDT. 2 The WRGM,1/2-RE-5416, may also monitor main vent releases.. A containment vent is considered a " batch" release (even th? ugh inleakage of radioactive gases into the containment atmosphere may occur during the time the vent is in progress). The WRGM,1-RE-5416, may also monitor main vent releases. This is the mean main vent stack flow rate as determined by approved Engineering Test Procedure (i.e., ETP-87-16). " This is the maximum vent stack flow rate as determined by approved Engineering Test Procedure (i.e., ETP-87-16). This is the mean main vent stack flow rate as determined by approved test procedure (i.e. TE-001) for period 8/90 through 3/96.~ This is the maximum vent stack flow rate as determined by approved test procedure (i.e. TE-001) for the period 8/90 through 3/96. The WRGM,2-RE-5416, may also monitor main vent releases. , 4
. i
Dose Ca!culation Manua! ( ) Page 225 of 313 (} R n 2 Chsnge 0 Attachment S General Information Related to Gaseous Releases via Pathways other than the Main Vents Waste Streams Radiation Monitor Type of Release Nominal Discharge N :n Flow Rate Aux. Boiler Deaerator Unmonitored See Footnote i See Footnote # Sim. Gen. Atm. Stm. Dumps Unmonitored See Footnote 1 See Footnote 2 Plant Nitrogen System Unmonitored See Footnote 1 See Footnote 2 Turbine Bldg. Vent. Exh. Unmonitored See Footnote 1 See Footnote 2 Emergency Air Lock Unmonitored See Footnote 1 See Footnote 2 Plant Compressed Air Unmonitored See Footnote See Footnote 2 Main Steam Line Penetrations Unmonitored See Footnote 1 See Footnote 2 Steam Driven Auxiliary Feed Pumps Unmonitored See Footnote 1 See Footnote 2 l Containment Equipment Hatch Unmonitored See Footncte1 See Footnote 2 Since radioactive gaseous waste is not normally vented via this pathway, the determination of release type (i.e., continuous or batch) will be evaluated on a case-by-case basis. Since radioactive gaseous waste is not normally vented via this pathway, the determination of discharge flow rate will be evaluated on a case-by-case basis. e
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Dose Calculation Manual ( )' ~ ~ ' Page 226 of 313 ' , , ,1' sion 2 Change 0 Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems
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Offsit3 Dose Calculation M:nual - Pa9e 227 of 313 R vision 2 Change 0 - 1 Attachment 10 I Noble Gas Dose Factors Nuclide . : GAMMA BODY DOSE ' BETA SKIN DOSE _ GAMMA AIR DOSE BETA AIR DOSE-K, -k M. _ N, (mrem /yr)/(pul/m3) (mrem /yr)/(pCi/m3). _(mradlyr)/(pCl/m3) (mradlyr)/(pCi/m3) Ar-41 8.84E+03 2.69E+03 9.30E+ 03 3.28E+03 Kr 85 1.61 E+01 1.34E+03 - 1.72E+01 .1.95E+03 Kr-85m 1.17E+03 1.46E+03 133E+03 ' 1.97E+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 X3131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 , Xo-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 . 3.27E+02 1.48E+03 Xe 133m 2.51 E+ 02 9.94E+02 Xs-135 - 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xs-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xo 138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 t e f O . I J t 4 0
Offsits. Dose Calculation Manuti - Page 228 of 313 -
- Revision 2 Change O Attachment 11 Empirical Derivation Of Site-Specific Dose Factors The total body dose, the skin dose, and the air doses -resulting from gamma and beta emitting radionuclides in discharges of gaseous radwaste- are normally calculated using mclide specific dose factors. However, these same doses may be estimated using empirically denvea, site specific, dose factors as shown below.
TOTAL-BODY, GAMMA-DOSE FACTOR A site specific, total body, gamma-dose factor has been derived from historical data in accordance with l the following equation. - K., = E ( Ki)( fi ) Eq.1F Km = the empirically derived, site specific, total-body, gamma dose factor due to all noble gases released during a specified time period
- . Values of Kg have been calculated using gaseous radwaste discharge data .
collected over several years. , The results of the calculations appear in the Table on page 5 of this attachment. K, = the total body dose factor due to gamma emissions for each identified noble gas ' , radionuclide, I (mrem /yr per microcurie / cubic meter)
. The total-body dose factors for gamma rays from noble gas radionuclides were i obtained from Regulatory Guide 1.109, Appendix B. Table B-1.
The total-body dose factors for various noble gas radionuclides are tabulated in Attachment 10, f, = a fraction which represents the relative activity contribution of noble gas radionuclide I to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5. i t
- a
a
- Offsite Dose Calculation Manual Page 229 of 313 Revision 2 Change 0 (N Attachment 11 -Q[ Empirical Derivation of Site Specific Dose Factors SKIN, BETA-DOSE FACTOR .
A site specific, skin, beta-dose factor has been derived from historical data in accordance with the following equation. L.,, = E( Le )( fi ) Eq.2F Lm = the empirically derived, site-specific, skin, beta-dose factor due to all noble gases - released during a specified time period Values of Ly have been calculated using gaseous radwaste d:scharge data collected over several years. The results of the calculations appear in the Table on page 5 of this attachment. the skin dose factor due to beta emissions for each identified noble gas Li = radionuclide, I (mrem /yr per microcurie / cubic meter) The beta skin dose factors have been obtained from Regulatory Guide 1.109, _
. Appendix B, Table B 1.
'. The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10.- .
- f, = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)
This vatuo has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachrnent 5.
/~5,
(/
Offsit3 Dose Cricut: tion M:nual Pcge 230 of 313 Revision 2 Chango O Attachment 11 Ernpirical Derivation of Sito Specific Dose Factors GAMMA AIR-v0SE FACTOR A site specific, gamma air dose f acto
- has been derived from historical data in accordance with the following eqtation.
M.,, = ( Mi ) ( f, ) Eq.3F M., = the empirically derived, site specific, gamma air dose factor due to all noble gases - released during a specified time period Values of M,y have been calculated using gaseous radwaste discharge data collected over several years. The results of the calculations appear in the Table on page 5 of this attachment.
~
M, = the air dose factor due to gamma emissions for each identified noble gas radionuclide, I (mradlyr per microcune/ cubic meter) Tna gamma air dose factors have been obtained from Regulatory Guide 1.109, " Appondix B, Teble B 1. The gamma air dode factors for various noble gas radionuclides To tabulated in O r f, = Attachment 10. a fraction which represents the relative activity contributiun of noble gas radbnuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gas 30us radwaste discharges for the years 1980,1987, and 1988 in accordance with equation 3R on Attachment 5.
'l
j Offsite Dose Calculation M:nual Page 231 of 313 Revision 2 Change O Attachment 11 Empirical Derivation of Site Specific Dose Factors BETA AIR DOSE FACTOR A site-specific, beta air-dose factor has been derived from historical data in accordance with the following equation, N.,, a E ( Ni)( f,) Eq.4F the empirically derived, site specific, beta air dose factor due to all noble gases
=
Nm released during a specified time period Values of N,yg have been calculated using gaseous radwaste discharge data collected over several years. The results of the calculations appear in the Table on page 5 of this attachment. N, = the air dose factor due to beta emissions for each identified noble gas radionuclide,
- i (mradlyr per microcurio/ cubic meter)
The beta air dose factors have been obtained from Regulatory Guide 1,109, ~' Appendix B, Table B 1. The beta air dose factors for various noble gas radionuclides are tabulated in O. Attachment 10 (Attachment 1 of old ODCM). . f, = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5. t O
..-.---.-.-.-_-----..-.--.-----.-.-e_- -
ft Offsits Dose C:lculation M:nu:1 Pcg3 232 of 313 l Revision 2 Change 0
?
Attachment 11
'O Empirical Derivation of Site Specific Dose Factors i
j SITE 4PECIFIC, AVERAGE DOSE FACTORS Year K.,, L.,, M . ,, N. . ; 1986 330 790 390 1100 1987 340 810 400 1100 '
~
1988 390- 960 450 1200 Average 350 850 410 1100 Maximum % difference 11 % 13% 10% 9%
~
As can be seen from the above table, the percent difference between the yearly dose factors and the 3 year average dose factors range from 9% to 13%, This variability is minor considering other areas of ) uncertainty inherent in the environmental dose calculation models. 11 should be noted that the emperically derived, $lte specific, average dose factors listed in the above table shall only rarely be used, in those rare instances where emperically derived, site specific, average dose factors are used, the results shall be carefully evaluated by qualified members of the facility staff to O ensure the estimated doses are only a small fraction of the Controllimits. Additionally, the dosos shall be recalculated using the RIGOROUS METHODS prior to submitting the Radioactive Effluent Release Report. l j' i 4
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Offsit) 00se Calculatl0n M:nual Pags 233 Of 313 Revision 2 Change 0 Attachment 12 O Gaseous Effluent Pathway Dos 0 Factors GRASS COW MEAT DOSE FACTORS ADULT (m2'mrom/yr per uCl/sec) Nuclide Bone Uver Tbody Thyroid Kidney Lung Ottract H-3 0 000E +00 3 250E+02 3 250E+02 3 200E+02 3 200E+02 3 250E+02 3 250E+02 C 14 3 330E+05 6 000E+04 6 000E+04 6 600E+04 6 000E+04 6 600E+04 6 600E+04 NA 24 1640E43 1.640E 03 1840E 03 1440E 03 1640E 03 1.640E 03 1.640E 03 P 32 4 650E+09 2 690E+08 1800E+08 0 0000 +00 0 000E400 0 000E*00 5230E+08 CR41 0 000E*00 0 000E +00 7.070E +03 4 220E+03 1.500E +03 9380E+03 1.780E +06 MN44 0 000E +00 9150E+00 1.750E +06 0 000E +00 2 720E+06 0 000E+00 2 800E+07 MN46 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 F E45 2 930E*08 2 020E+08 4 720E*07 0 000E+00 0 000E+00 1.130E +08 1.100E+08 FE49 2 670E*08 6 270E+08 2 400E+08 0 000E+00 0 000E+00 1.750E+08 2 090E+09 CO $7 0 000E+00 6640E+06 9 370E+06 0 000E +00 0 000E+00 0 000E+Cio 1.430E +08 C048 0 000E+00 1.830E +07 4100E+07 0 000E +00 0 000E+00 0 000E+00 3 700E+08 CO 60 0 000E+00 7 $20E +07 1000E+08 0 000E*00 0 000E +00 0 000E+00 1410E+09 N143 1890E+10 1310E+09 6 330E+08 0 000E +00 0 000E +00 0 000E+00 2 730E +08" N145 0 000E*00 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 CU44 ZN45 ZN49 0 000E*00 3 500E+08 0 000E+00 2 950E-07 1.130E +09 0 000E+00 1390E 07 5120E*08 0 000E+00 0 000E*00 0 000E*00 0 000E+00 7 450E-07 7 570E+08 0 000E*00 0 000E+00 0 000E+00 0 000E+00 2 520E 05 7.130E +08 0 000E +00 BR42 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E *00 BR-83 0 000E+00 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0R44 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BR45 0 000E *00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E +00 RB46 0 000E *00 4 870E+08 2270E*06 0 000E +00 0 000E+00 0 000E+00 9 600E +07 RB48 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RB49 0 000E*00 0 000E+00 0 000E +00 0 000E *00 0 000E+00 0 000E+00 0 000E +00 5R49 3 010E+08 0 000E +00 6 650E+06 0 000E+00 0 000E+00 0 000E+00 4 840E+07 SR4C 1240E*10 0 000E+00 3 050E+09 0 000E+00 0 000E+00 0 000E+00 3 590E+08 SR 91 0 000E+00 0 000E +00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 1.380E 09 SR 92 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y 90 1.070E *02 0 000E*00 2 800E+00 0 000E+00 0 000E+00 0 000E+00 1.130E +06 Y 91M E000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+0C Y 91 1.130E *06 0 000E+00 3 030E+04 0 000E+00 0 000E+00 0 000E+00 6 240E+08 Y-92 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 Y 93 0OLOE+00 0 000E+00 0 WOE +00 0 000E+00 0 000E+00 0 000E+00 2 080E47 2RM 1.880E+06 6 040E+05 4 090E +05 0 000E*00 9 480E+05 0.000E +00 1.910E *09 % ZR497 1830E-05 3 090E 00 1690E-06 0 000E +00 5 580E-06 0 000E+00 1.140E* JO
Offsit] Dose Calcul:tl0n Manual Page 234 of 313 R0 vision 2 Change 0 Attachment 12 Gaseous Effluent Pathway D0se Factors GRASS COW MEAT DOSE FACTORS ADULT (m2*mrom/yr por uCl/sec) Nuchde Bone Uver Tbody Thyroid K6dney Lung Gitract NB-95 2 290E+06 1.280E +06 6 060E*05 0 000E+00 1260E+06 0 000E+00 7.750E+09 NB-97 0 000E+00 0 000E+00 0 000E*00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 MOM 0 000E+00 1.090E *05 2.070E +04 0 000E+00 2 400E+05 0 000E+00 2 520E+05 TC#M 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 ' 10,101 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0.000E+00 0.000E +00 RU 103 1.000E +08 0 000E +00 4 550E*07 0 000E+00 4 030E+08 0 000E +00 1.230E
- 10 AU105 0 000E +00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E +00 RU 106 2 800E +09 0 000E+00 3 540E+08 0 000E*00 5400E+09 0 000E+00 1810E+11 RH 103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 HH 106 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+CIO O000E+00 AG 110M 6690E+06 6190E+06 3 670E+06 0 000E+00 1220E+07 0 000E+00 2.520E + 09
$8122 5 580E +03 5 820E+03 7 OSOE+04 9 250E+02 2 750E *03 1200E+03 6 930E+05 l
SB 124 19BOE+09 3 740E*07 7 850E+08 4 000E +06 0 000E* 00 1.540E +09 5620E+10" SD 125 1910E+09 2130E+07 4 540E+08 1.940E +06 0 000E+00 1470E +09 2.100E + 10 TE 125M 3 590E *08 1.300E +08 4 810E +07 1.080E *08 1460E *09 0 000E +00 1430E +09 TE 127M 1.120E+09 3 990E+08 1360E+08 2 850E+08 4 530E +09 0 000E+00 3.740E+09 TE 127 0 000E +00 0 000E+00 0 000E+00 0 000E+00 1090E 09 0 000E+00 2100E 08 TE 129M 1.140E*09 4 270E +08 1810E+08 3 930E+08 4 770E+09 0 000E +00 5760E*09 TE-129 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E
- 00 TE 131M 4 510E*02 2 210E +02 1.840E+02 3 500E+02 2 240E+03 0 000E+00 2.190E +04 TE-131 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00
- 1E 132 1.400E +06 9 070E+05 8 510E+05 1.000E+06 8 730E+06 0 000E+00 4 290E+07 1130 2 350E46 6 940E 06 2 740E 06 5 880E 04 1,080E 05 0 000E+00 5 960E 06 6-131 1.080E +07 1540E+07 8 830E+06 5 050E+09 2 640E+07 0 000E+00 4 070E +06 1132 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 l-133 4 300E 01 7.470E 01 2 280E 01 1.100E +02 1.300E +00 0 000E+00 6 720E 01 l134 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 1135 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 CS 134 6570E+08 1.560E+09 1.280E+09 0 000E+00 5000E+08 1.6SOE+08 2 740E+07 CS 136 1,180E +07 4 670E+07 3 300E+07 0 000E+00 2 600E+07 3 560E+06 5 300E+06 CS 137 8720E+08 1.190E +09 7.810E+08 0 000E+00 4 050E +08 1.350E +08 2 310E+07 CS-138 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BA-130 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 O DA 140 2 880E+07 3 610E+04 1.890E+06 0 000E+00 1.230E*04 2 070E+04 5 920E+07 BA-141 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 l
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Offstt] 00se C:lculation M:nu:1 Page 235 Of 313 Revision 2 Change O Attachment 12 Q Gaseous Effluent Pathway D0se Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2* mrem /yr per uCi/sec) Nucikle Bone Liver Tbody Thyroid Kidney Lung Ottract DA 142 0 000E+00 0 000E *00 0 000E*00 0 000E+00 0 000E*00 0.000E+00 0 000E+00 LA 140 3 000E 02 1.810E 02 4 790E 03 0 000E+00 0 000E+00 0 000E +00 1.330E+03 LA 142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00
^
CE 141 1.400E *04 9 480E +03 1.000E *03 0 000E+00 4 400E+03 0 000E+00 3 020E+07 CE 143 2 090E42 1.550E +01 1.710E 03 0 000E+00 6 800E43 0 000E +00 5780E*02 CE 144 1460E+06 6 000E+05 7.830E +04 0 000E+00 3610E+05 0 000E+00 4 030E+08 PR 143 2130E+04 8 540E+03 1060E +03 0 000E+00 4 930E+03 0 000E+00 9 330E*07 PR 144 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 NO-147 7,000E *03 8180E +03 4 900E+02 0 000E+00 4 780E+03 0 000E+00 3 930E+07 EU 154 8030E+06 9 870E *06 7.020E+05 0 000E+00 4 720E+00 0 000E +00 7.150E+06 EU 155 1.110E
- 06 1580E*05 1.020E*05 0 000E+00 7.300E +05 0 000E+00 1.240E*08 W 187 2160E 02 1810E-02 6 320E-03 0 000E+00 0 000E *00 0 000E +00 5920E+00 NP 239 2 500E 01 2 510E 02 1.390E 02 0 000E+00 7.840E 02 0 000E +00 5150E+03 "
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Offsit] Dose Calculati:n Manu:1 Pag)236 Of 313 Revision 2 Chango 0 ( Attachment 12 k Gas 00cs Effluent Pathway D0se Factors GRAM-COW MEAT DOSE FACTORS TEEN (m2* mrem /yr per uCi/sec) Nuctede Bone Uver Tbody Titytold Kidney Lung Gittact H3 0 000E +00 1.940E +02 1.940E+02 1.940E +02 1.940E+02 1.940E+02 1.940E +02
. C 14 2810E+05 $ 620E44 5620E+04 5 620E+04 6.820E+04 5 620E+04 5 620E+04 NA-24 1470E 03 1470E-03 1.470E 03 1470E43 1470E-03 1.470E43 1.470E43 P 32 3 930E +09 2 440E+08 1.520E+08 0 000E+00 0 000E+00 0 000E+00 3 300E+08 CR41 0 000E *00 0 000E+00 5650E+03 3140E+03 1.240E+03 8 0702+03 9 500E +05 MN54 0 000E+00 6 980E +06 1.380E +06 0 000E+00 2 080E408 0 000E +00 1.430E+07 MN50 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Fr-55 2 380E*08 1690E +08 3 930E+07 0 000E+00 0 000E *00 1.070E +08 7.300E +07 FE59 2130E*08 4 980E+08 1920E*08 0 000E+00 0 000E+00 1.570E +08 1.180E +09 C047 0 000E +00 4 630E*06 7.690E +00 0 000E+00 0 000E+00 0 000E+0O 8450F+07 C048 0 000E +00 1.410E
- 07 3 250E*07 0 000E400 0 000E*00 0 000E*00 1.940E* 08 CO40 0 000E+00 5 830E *07 1.310E +08 0 000E +00 0 000E+00 0 000E+00 7 600E+08 Ni63 1520E +10 1070E+09 5150E+08 0 000E+00 0 000E+00 0 000E+00 1.710E + 08" NI-65 0 000E +00 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 O CU44 0 000E +00 2 410E-07 1.130E 07 0 000E +00 0100E-07 0 000E+00 1.870E 05 ZN45 2 500E +08 8 690E +08 4 050E+08 0 000E+00 $560E*08 0 000E+00 3 680E+08 ZN 69 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 BR42 0 000E *00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 BR43 0 000E* 00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E*00 BR-84 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BR 05 0 000E +00 0 000E+00 0 000E +00 0 000E *00 0 000E+00 0 000E+00 0 000E+00 RB46 0 000E +00 4 060E+08 1910E+08 0 000E+00 0 000E+00 0 000E+00 6 010E+07 R D-88 0 000E +00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E +00 0 000E+00 RB49 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 SR49 2 540E *08 0 000E+00 7,290E +06 0 000E*00 0 000E+00 0 000E*00 3 030E+07 SR-90 8050E+06 0 000E+00 1990E+09 0 000E+00 0 000E+00 0 000E+00 2.2t>0E + 08 SR 91 0 000E+00 0 000E*00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 1100E-09 SR 92 0 000E+00 0 000E*00 0 000E*00 0 000E+00 0.000E+00 0 000E +00 0 000E+00 Y 90 8980E+01 0 000E+00 2 420E+00 0 000E+00 0 000E +00 0 000E+00 7 400E+05 Y-91 M 0000E*00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y 91 9 560E+05 0 000E+00 2 560E+04 0 000E+00 0 000E+00 0 000E+00 3 920E+08 Y-92 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y-93 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 1690E-07 ZR 95 1510E+06 4 7ECE+05 3.270E + 05 0 000E+00 6 990E+05 0 000E +00 1,100E +09
( ZR 97 1530E-05 3 020E 06 1.390E-06 0 000E+00 4 680E 06 0 000E+00 8180E 01
l Offsit3 Dose Calculation M';nual ap 237 of 313 Revision 2 Change 0 4 Attachment 12 Gaseous Effluent Pathway D0se Factors GRASS COW-MEAT DOSE FACTORS TEEN (m2* mrem /yr per UCl/sec) Nuchde Bone Uvor Tbody Thyro 6d Kidrwy Lung Oltract NS 96 1.790E +06 9 940E+05 $470E+05 0 000E+00 9 640E+05 0 000E+00 4 250E+09 NS 97 0 000E+00 0 000E*00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E +00 ) i Mo-99 0 000E+00 8 980E+04 1.710E+04 0.000E+00 2 060E+05 0 000E+00 1610E +05
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TC 99M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 TC 101 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0.000E+00 ~ 0 WOE *00 RU 103 8800E*07 0 000E+00 3 680E+07 0 000E+00 3 030E +08 0 000E+00 7.180E+09 RU 105 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RU 106 2 300E+09 0 000E+00 2 970E+08 0 000E+00 4 5%E+09 0 000E+00 - 1.130E +11 RH 103M - 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RH 100 0 000E+00 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+0O 0000E+00 AG.110M 5060E+06 4 790E+00 2 910E+06 0 000E+00 9.140E +06 0.000E+00 1.350E+09
$B 122 3 300E +03 3 440E+03 4170E+04 5 460E+02 1.620E +03 7.000E+02 4100E+05 l l
SB-124 1620E+09 2 980E+07 6 310E+08 3 670E+06 0 000E*00 1.410E+09 3 260E+1I I SB 125 1560E+09 1.710E+07 3 660E+08 1.490E+06 0 000E+00 1,370E+09 1.220E + 10 TE 125M - 3 030E+08 1.090E +08 4 050E+07 8470E+07 0 000E+00 0 000E+00 8940E+08 TE 127M 9 410E +08 3 340E+08 1.120E+08 2 240E+08 3 820E+09 0 000E+00 2.350E +09 TE 127 0 000E+00 0 000E+00 0 000E*00 0 000E*00 0 000E+00 0 000E+00 1.750E 08 l- TE 129M 9 580E+08 3 500E+08 1.520E +08 3 090E+08 4 010E*09 0 000E+00 3 600E+09 1E 129 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0.000E +00 0 000E+00 0.000E+00 t TE 131M 3 760E *02 1800E+02 1.500E +02 2 710E+02 1 880E+03 0 000E+00 1450E *04 TE 131 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 l TE 132 1.150E+06 7.260E +05 6 840E+05 7.660E +05 6 970E+06 0 000E+00 2 300E+07 { l130 1890E-06 5 480E 06 2190E 06 4 470E 04 8 440E 06 0 000E+00 4 210E-06 4 1131 8 950E+06 1.250E+07 6 730E+06 3 660E+09 2.160E +07 0.000E+00 2 480E+06 l-132 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 '
- l133 3 590E 01 6.100E-01 1,860E 01 8 510E +01 1.07bE+00 0 000E+00 4 $10E 01 1-134 0 000E+00 0 000E+00 0 000E+00 0 000E400 0 000E+00 0 000E+00 0 000E +00 1135 0 000E+00 0.000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 CS 134 5 230E+08 1.230E+09 5710E+08 0 000E *00 3 910E+08 1.490E+08 1.530E +07 CS 136 9 220E+06 3 630E +07 2 440E+07 0.000E+00 1.970E+07 3110E+06 2 920E+06
- CS 137 - 7.240E+06 9 630E+08 3 360E+08 0 000E+00 3.280E+08 1.270E+08 1370E+07 CS 138 0.000E+00 0 000E*00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BA 139 0 000E+00 ' 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 BA 140 2480E+07 2 910E+04 1530E+06 0 000E+00 9 880E+03 1.960E+04 3 670E+07
, BA 141 0 000E+00 0 000E+00 0 000E +00 . 0000E*00- 0 000E+00 0 000E+00 0 000E+00 a.- -
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Offsite D0se C:lcul: tion Manual P g3 238 of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW. MEAT DOSE FACTORS TEEN (m2*mrtm/yr por uCl/sec) Nuchde Bone Uver Tbody Thytold Midney Lung Gltract DA 142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 LA 140 2 000E 02 1,450E-02 3 070E43 0 000E+00 0 000E+00 0 000E +00 8 350E+02 LA 142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 CE 141 1.180E +04 7.800E+03 9030E+02 0 000E+06 3 700E+03 0 000E+00 2.250E+07 ' CE 143 1.700E42 1.200E+01 1.430E 03 0 000E+00 5 740E 03 0 000E+00 3 850E+02 CE 144 1.230E +06 5 000E+05 6 000E*04 0 000E +00 3 040E +05 0 000E+00 3 090E+08 PR 143 1.700E+04 7.150E *03 8 920E*02 0 000E+00 4160E+03 0 000E+00 5900E+07 PR 144 0 000E+00 0 000E +00 0.000E +00 0 000E *00 0 000E*00 0 000E+00 0 000E+00 ND 147 6240E+03 6.790E +03 4 000E+02 0 000E +00 3 980E+03 0 000E+00 2 450E +07 EU 154 6 090E+06 7.870E +05 5540E+05 0 000E+00 3 520E+06 0 000E+00 4160E *08 EU 155 1330E +06 1290E+05 7.970E +04 0 000E +00 5 030E+05 0 000E+00 7.380E +0S W 187 1.810E 02 1.480E 02 5170E 03 0 000E +00 0 000E+00 0 000E+00 3 990E +00 NP 239 2 230E 01 2110E 02 1.170E 02 0 000E *00 6 610E 02 0 000E+00 3 390E+03" I V - I
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Offsite D0s0 C:lculation Manu:1 Pags 239 of 313 Revision 2 Change O f Attachment 12 Gaseous Effluent Pathway D0se Factors GRASS COW MEAT DOSE FACTORS CHILD (m2* mrem /yr per uCl/sec) Nuchde Bone Uver Tbody Thyroid Kidney Lung Gitract H3 0 000E+00 2.340E+02 2 340E+02 2 340E+02 2.340E +02 2 340E+02 2.340E+02 C 14 5290E+05 1000E+05 1.000E +05 1.060E +05 1.000E+05 1.000E+05 1060E +05 NA 24 2 340E-03 2 340E-03 2 340E 03 2 340E.03 2 340E 03 2 340E 03 2 340E 03 P 32 7.410E +09 3 470E +08 2 000E+08 0 000E+00 0.000E +00 0 000E+00 2 000E *00 CR51 0 000E +00 0 000E+00 8 810E+03 4 890E+03 1.340E+03 8930E+03 4 670E+05 MN54 0 000E+00 7 990E+06 2130E+00 0 000E+00 2 240E+06 0 000E+00 6 700E*06 MN56 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 FE45 4 570E+08 2 420E+08 7,510E+07 0 000E+00 0 000E+00 1.370E +08 4 490E+07 FE49 3 780E*08 0120E+08 3 050E+08 0 000E +00 0.000E+00 1.770E +08 6 370E+08 C047 0 000E+00 5920E+06 1.200E +07 0 000E*00 0 000E+00 0 000E+0'0 4 850E+07 C0 58 0 000E*00 1.650E +07 5040E*07 0 000E+00 0 000E+00 0 000E+00 9 600E+07 C040 0 000E *00 0930E+07 2 040E+08 0 000E+00 0 000E*00 0 000E+00 3 840E+08 Nb63 2 910E+10 1500E +09 9 910E+0S 0000E+00 0.000E+00 0 000E+00 1050E +08" NI45 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 CU 64 0 000E *00 3 240E-07 1900E-07 0 000E*00 7 820E-07 0 000E+00 1.520E-05 ZN45 3 750E+08 1000E*00 6 220E+08 0 000E+00 6300E+08 0 000E+00 1.760E +08 ZN49 0 000E +00 0 000E*00 0 000E*00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0R-82 0 000E +00 0 000E+00 0 000E +00 0000E+00 0 000E*00 0 000E+00 0 000E +00 . DR43 0 000E +00 0.000E +00 0 000E+00 0 000E *00 0 000E+00 0 000E*00 0 000E+00 BR44 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0R 85 0 000E +00 0 000E*00 0 000E*00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 RB46 0 000E +00 5700E+08 3 540E +08 0 000E*00 0 000E+00 0 000E*00 3 710E+07 RB-88 0 000E*00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 R B-80 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0.000E *00 0 000E+00 0 000E +00 SR49 4 820E *08 0 000E+00 1,380E+07 0 000E+00 0 000E+00 0 000E*00 1.660E *07 SR DO 1040E+10 0 000E+00 2 640E+09 0 000E+00 0 000E+00 0 000E+00 1.400E +08 SR 91 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 1.010E-09 SR 92 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 Y-90 1.700E +02 0 000E+00 4 550E+00 0 000E+00 0 000E+00 0 000E+00 4 840E+05 Y 91M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y 91 1.810E +06 0 000E+00 4 830E+04 0 000E+00 0 000E+00 0 000E+00 2.410E + 08 Y 92 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y-93 0 000E+00 0 000E+00 0 000E+00 0 00DE+00 0 000E +00 0 000E+00 1.550E-07 fi ZR D5 2 680E+06 5890E+05 5 240E+05 0 000E+00 8 430E +05 0 000E+00 6140E +08 ZR 97 2 840E-05 4100E-06 2 420E-06 0 000E+00 5 890E-06 0 000E+00 6 210E-01
Offsito 00$o Calculation Manual Page 240 Of 313 Revision 2 Chango O Attachment 12 Gas 00us Effluent Pathway Dose Factors GRASS-COW MEAT DOSE FACTORS CHILD (m2* mrem /yr por UCl/sec) Nuchde Done Liver Tbody Thyroid Kidney Lung Gitteet NBM 3 0 DOE *06 1200E+06 6610E+05 0 000E+00 1.130E +06 0 000E*00 2 230E+09 NB 97 0 000E+00 0 000E *00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E*00 MO4 0 000E+00 1250E *05 3 090E+04 0 000E+00 2 870E +05 0 000E +00 1030E+05 1C&M 0000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 ' TC 101 0 000E *00 0 000E *00 0 000E +00 0 000E+00 0 000E*00 0 000E +00 0 000E +00 RU 103 1500E+08 0 000E +00 $900E+07 0 000E+00 3 920E+08 0 000E+00 4020E+09 RU 105 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E *00 RU-106 4 440E+09 0 000E+00 5 540E *06 0 000E+00 5 990E +09 0 000E+00 6 900E+10 HH 103M 0000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0OCOE+00 RH 100 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+0O 0 000E +00 AG 110M 8400E*00 5670E*06 4 530E +06 0 000E+00 10GOE+07 0 000E +00 6 750E*08 5B 122 2 080E *03 2170E*03 2 630E+04 3 450E+02 1.020E +03 4 460E*02 2 580E*05 l 50 124 2 930E +09 3 800E* 07 1030E+09 6 460E*06 0 000E+00 1620E+09 1830E + 10' SB-125 2 650E +09 2190E +07 5 960E +0B 2 640E+06 0 000E +00 1590E+09 6 800E *09 TE 125M $690E*06 1540E *08 7.590E+07 1600E +08 0 000E +00 0 000E+00 5 4ME *08 TE 127M 1770E +09 4 700E*08 2110E +08 4 240E+08 5 000E*09 0 000E +00 1440E
- 09 TE 127 0 000E *00 0 000E + 00 0 000E+00 0 000E+00 1210E-09 0 000E *00 1660E-08 TE 129M i 810E +09 5 040E +08 2 800E+08 5820E+08 5 300E*09 0 000E +00 2 200E+09 T E 129 0 000E +0] 0 000E *00 0 000E*00 0 000E +00 0 000E*00 0 000E *00 0 000E +00 TE 131M 7 000E*02 2 420E +02 2 580E+02 4 980E+02 2 340E+03 0 000E +00 9 8:0E +03 TE 131 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E*00 OC00E*00 10 132 2 090E+00 9 270E*05 1120E+06 1350E +06 8 000E +06 0 000E +00 9 330E +00 l130 3 390E 06 0 850E 06 3 530E-06 7.540E-04 1.020E-05 0 000E+00 3 200E-06 6131 1660E +07 1670E+07 9 490E+0* 5 520E+09 2.740E
- 07 0 000E+00 1490E+06 b132 0 000E *00 0'00E+00 0 000E *00 0 000E*00 0 000E +00 0 000E *00 0 0CCE *00 1133 6 680E-01 8 200E 01 3120E 01 1530E+02 1380E +00 0 000E
- 00 3 330E 01 1-134 0 000E +00 0 000E+00 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 b135 0 000E +00 0 000E +00 0 000E*00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 CS 134 9200E+08 1.510E +09 3190E+08 0 000E*00 4 690E*08 1680E*08 61!cE+06 CS 136 1590E+07 4 370E +07 2 830E +07 0 000E+00 2 330E+07 3 470E+C6 1.540E
- 06 CS 137 1330E
- 00 1200E+09 iBSOE*08 0 000E*00 4160E*08 1.500E +08 7 990E +06 CS 138 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E *00 BA 139 0 000E+00 0 000E+00 0 000E+00 DC00E+00 0 000E+00 0 000E+00 6 000E+00 B A-140 4 390E+07 3 850t+04 2 560E*08 0 000E+00 1250E +04 2 290E+v4 2 22ti+07
OffsitJ Dose C"Iculatl0n Manual Pag 3 241 Of 313 l Revision 2 Chango 0 l l r Attachment 12 Q] Gaseous Effluent Pathway 0050 Factors GRASS-COW MEAT DOSE FACTORS CHILD (m2'mrom/yr per uCl/sec) Nuchde Bone Uver Tbody Thyroid Kidney 1.ung Gitract BA 141 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 DA 142 0 000E+00 0 000E *00 0 000E *00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 LA 140 6 410E 02 1090E-02 6 380E 03 0 000E +00 0 000E+00 0 000E+00 $270E+02 LA 142 0 300E*00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 CE 141 2 220E+04 1.110E + 04 1.640E *03 0 000E+00 4 840E+03 0 000E+00 1.380E +07 CE 143 3 300E42 1.7 DOE *01 2.590E43 0 000E +00 7.510E43 0 000E+00 2 620E +02 CE 144 2 320E+00 7 200E+05 1.240E +0$ 0000E+00 4 020E+05 0 000E+00 1.890E +08 PR 143 3 390E *04 1.020C +04 1.680E +03 0 000E*00 $$10E+03 0 000E+00 3 000E+07 PR 144 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 NO 147 1.170E *04 9 480E+03 7 340E+02 0 000E +00 $200E+03 0 000E +00 1.500E*07 EU 154 1,120E +07 1010E+00 9190E*05 0 000E+00 4 420E+06 0 000E+00 2 340E+08 EU 155 2 330E *00 1680E +05 1310E +05 0 000E400 6 280E+05 0 000E +00 4 200E+08 W 187 3 300E-02 i D90E 02 8 920E 03 0 000E+00 0 000E +00 0 000E +00 2 790E*00" NP-239 4 200E 01 3 020E42 2.120E 02 0 000E+00 8 730E 02 0 000E +00 2 230E+03 i . o V
Offsite Dose Calculation Manual Page 242 of 313 Revision 2 Change O Attachment 12 O Gaseous Effluent Pathway Dose Factors GRASS COW MEAT DOSE FACTORS INFANT (m2* mrem /yr per uCl/sec) Nuchde Done Liver Tbody Thyroid Kidney Lung Ottract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK en % O . O 4
Offsite Dose Calculation M:nu:1 Page 243 Of 313 ' Revision 2 Change 0 l o Attachment 12 (d i Gaseous Effluent Pathway D050 Factors VEGETATION DOSE FACTORS ADULT (m2'mremlyr per uCl/sec) Nuchde Bone Uver Tbody Thyroid Kidney Lung Oltract H-3 0 000E+00 2.200E +03 2 200E+03 2.260E+03 2 200E+03 2 200E +03 2.200E +03 ! C 14 8 970E+05 1.790E +05 1.790E+05 1.790E+05 1.790E + 05 1.790E +05 1.790E+05 NA 24 2.700E *05 2.700E *05 2 700E+05 2.700E *05 2.700E *05 2.760E+05 2.7COE *05 P 32 1.400E +09 8.730E+07 5420E+07 0 000E+00 0 000E+00 0 000E+00 1.$80E*08
- CR41 O!VJOE+00 0 000E+00 4 600E+04 2 790E+04 1.030E +04 6190E*04 1.170E+07 MN44 0 000E +00 3110E+08 5940E+07 0 000E*00 9 270E+07 0 000E +00 9 640E +08 MN-56 0 000E +00 1.610E *01 2.850E + 00 0 000E+00 2 040E+01 0 000E+00 5130E+02 FE 55 2 090E+08 1.450E +08 3 370E+07 0 000E+00 0 000E +00 8 060E+07 8290E+07 F E 59 1.270E +08 2 9 DOE +08 1.140E +08 0.000E + 00 0 000E+00 6350E*07 9960E+08 CO.51 0 000E+00 1.170E +07 1950E+07 0 000E+00 0 000E+00 0 000E+06 2.970E +08 CO 58 0 000E+00 3 000E*07 6 920E+07 0 000E+00 0 000E +00 0 000E+00 6 260E +08 C040 0 000E*00 1.670E +08 3 090E+08 0 000E+00 0 000E+00 0 000E+00 3140E+09 N143 1.040E
- 10 7.210E
- 08 3 490E+08 0 000E*00 0 000E+00 0 000E +00 1.500E +08" N145 0150E+01 7.990E +00 3 650E+00 0 000E*00 0 000E+00 0 000E+00 2 030E +02 O CU 64 0 000E +00 9270E+03 4 350E+03 0 000E+00 2 340E +04 0 000E +00 7100E+05 ZN45 3170E*08 1010E+09 4 500E+08 0 000E+00 0 750E+08 0 000E+00 6 360E +08 ZN49 8 750E 06 1670E-05 1,160E-00 0 000E+00 1090E 05 0 000E+00 2 510E 06 0R-82 0 000E+00 0 000E*00 1.510E *06 0 000E+00 0 000E+00 0 000E+00 1.730E +06 BR 83 0.000E +00 0 000E+00 3 210E+00 0 000E+00 0 000E +00 0 000E+00 4 630E *00 BR44 0 000E+00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E +00 0 000E+00 l.
BR45 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 l RD46 0 000E400 2190E+08 1.020E +08 0 000E+00 0 000E+00 0 000E +00 4 320E+07 l l RB48 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 RB 89 0 000E +00 0 000E400 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E*00 SR49 9 900E *09 0 000E+00 2 86JE+08 0 000E+00 0 000E+00 0 000E +00 1600E+09 SR-90 8050E+11 0 000E +00 1.480E +11 0 000E+00 0 000E+00 0 000E+00 1.750E + 10 SR 91 3 200E+05 0 000E+00 1.290E+04 0 000E+00 0 000E+00 0 000E+00 1.520E +06 SR P2 4 270E +02 0 000E+00 1.850E +01 0000Ee2 0 000E+00 0 000E+00 8 460E+03 Y 90 1.330E+04 0 000E*00 3 560E+02 0 000E+00 0 000E+00 0 000E+00 1.410E+08 Y-91M 5 830E 09 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 1.710E 08 Y-91 5130E+06 0 000E+00 1.370E +05 0 000E+00 0 000E+00 0 000E+00 2 820E+09 Y 92 9 010E41 0 000E*00 2 630E 02 0 000E+00 0 000E+00 0 000E+00 1580E+04 Y 93 1.740E+02 0 000E*00 4 800E+00 0 000E+00 0.000E+00 0 000E+00 5 520E+06 ZR.95 1.190E +06 3.810E+05 2 580E*05 0 000E+00 5 970E+05 0 000E +00 1210E+09 (y ZR-97 3 330E*02 6 730E+01 3 080E*01 0 000E+00 1020E+02 0 000E+00 2 080E +07
Offsit] Dose C:lcul: tion M: null Page 244 of 313 Revision 2 Change O A Attachment 12 Q Gaseous Effluent Pathway D0so Factoro VEGETATION DOSE FACTORS ADULT (m2*mtem/yr per uCl/sec) Nuchde Bone Uver Tbody Thyroid Kidney Lung Citract NB 95 1420E *05 7 910E+04 4 250E*04 0 000E+00 7.81,E+04 0 000E+00 4 800E+08 NB 97 2 900E-06 7 340E 07 2 680E 07 0 000E +00 8 500E 07 0 000E+00 2.710E 03 MO 99 0 000E *00 6 250E400 1.190E+00 0 000E *00 1410E +07 0.000E+00 1450E *07 TCMM 3 000E +00 8 000E+00 1.100E +02 0 000E+00 1.320E + 02 4 240E+00 5120E+03' TC 101 0 000E *00 0 000E *00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 HU103 4 600E +06 0 000E *00 2.070E *06 0 000E*00 1.830E+07 0 000E +00 5610E+08 RU-105 5 390E+01 0 000E+00 2130E+01 0 000E +00 6 900E402 0 000E+00 3 300E+04 RU106 1930E*08 0 000E +00 2 440E+07 0 000E+ 00 3 720E+08 0 000E+00 1.250E +10 RH 103M 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 RH 100 0 000E +00 0 000E +00 0 000E400 0 000E +00 0 000E+00 0 000E+Cio 0 000E *00 AG 110M 1000E *07 9 700E +06 5800E*00 0 000E +00 1ct20E+07 0 000E *06 3 980E +09
$D122 7 500E+05 7 820E+05 9 470E +06 1.240E+05 3 690E+05 1.610E+05 9 320E *0/
l SB-124 1040E +08 1.900E +06 4110E+07 2 520E*05 0 000E+00 8 080E +07 2 950E+09 ** SB-125 1300E+08 1520E+06 3 250E+07 1.390E+05 0 000E +00 1.050E +08 1.500E+09 f TE 125M 9 660E +07 3 500E +07 1290E *07 2 900E+07 3 930E+0S 0 000E+00 3 B60E+08 TE 127M 3 490E +08 1.250E
- 08 4.260E +07 8920E+07 1420E *09 0 000E+00 1.170E +09 TE 127 5 760E +03 2 070E+03 1250E *03 4 270E +03 2 350E+04 0 000E *00 4 640E +05 TE 12DM 2 550E +08 9 600E *07 4 030E +07 8750E+07 1000E *09 0 000E+ % 12SOE+09 TE 129 6 650E 04 2 500E 04 1.620E-04 5100E 04 2 790E-03 0 000E*00 5 020E 04 TE 131M 9120E +05 4 460E+05 3 720E+05 7 060E+05 4 520E+06 0 000E+00 4 430E +07 TE 131 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E *00 0 000E+C4 0 000E +00 TE 132 4 290E +00 2 770E +06 2 000E *06 3 060E+00 2 670E+07 0 000E+00 1.310E +08 l130 3 960E+05 1.170E +06 4 610E+05 9 900E*07 1820E+06 0 000E*00 1010E+06 6131 8090E+07 1.160E
- 08 6 630C+07 3 7 DOE +10 1.980E +08 0 000E+00 3 050E +07 F132 5 740E401 1540E *02 5380E+01 5380E+03 2 450E*02 0 000E +00 2 890E +01 1133 2120E *00 3 690E+06 1.120E +06 5420E+08 6 440E+06 0 000E+00 3.310E +06 l-134 1.000E 04 2 880E-04 1030E 04 5 000E 03 4 590E 04 0 000E+00 2 510E 07 1135 4 080E +04 1070E*05 3 940E+04 7 040E*06 1.710E +05 0 000E+00 1.210E+05 CS 134 4 660E +09 1.110E
- 10 9070E+09 0 000E *00 3 590E+09 1.190E+09 1940E+08 CS 138 4 200E+07 1.660E+08 1.190E+08 0 000Et00 9 240E+07 1270E+07 1890E+07 CS-137 6 300E*09 8700E*09 5700E+09 0 000E +00 2 950E+09 9 810E+08 1.680E +08 CS 138 0 000E *00 0 000E*00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E +00 BA 139 2 950E 02 2.100E 05 8 640E 04 0 000E+00 1.960E-05 1190E 05 5 230E 02 C BA-140 1.290E +08 1620E+05 8 430E+06 0 000E+00 $490E+04 9 250E+04 2 G50E*08 k
BA 141 0 000E +00 0.000E +00 0 000E+00 0 000E +00 0 000E400 0 000E+00 0 000E+00
OfIsite D0so C:lculation Minuti Pag) 245 Of 313 Revision 2 Change O Attachment 12 Gaseous Effluent Pathway D0se Factors [sV) VEGETATION DOSE FACTORS ADULT (m2* mrem /yr per uCl/sec) Nucikle Bone uver Tbody Thyroid Kidney Lung Gitract BA 142 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 LA-140 1970E+03 9 920E *02 2 620E+02 0 000E +00 0 000E+00 0 000E+00 7.280E +07 LA 142 1400E 04 0 350E 05 1.580E415 0 000E+00 0 000E *00 0 000E+00 4 640E 01 CE 141 1.900E +05 1.330E +05 1510E+04 O b00E *00 6170E+04 0 000E+00 5080E+00 CE.143 1.000E +03 7 420E*05 8 210E+01 0000E*00 3 200E+02 0 000E+00 2 770E+07 CE 144 3 290E*07 1.380E +07 1.770Ee06 0 000E+00 8100E+06 0 000E+00 1.110E + 10 PR 143 6 340E+04 2 540E +04 3140E*03 0 000E+00 1.470E *04 0 000E*00 2,760E +08 PR 144 0 000E *00 0 000E *00 0 000E +00 0 000E+00 0 000E*00 0 000E +00 0.000E *00 ND 147 3 340E+04 3 800E +04 2 310E*03 0 000E *00 2.250E+04 0 000E+00 18!4E+08 EU 154 4 050E*07 5970E+06 4 250E+00 0 000E+00 2 800E +07 0 000E+00 4 320E+09 EU 155 6 710E*06 9 510E*05 6140E+05 0 000E+00 4 390E+00 0 000E+00 7 490E+C4 W 187 3 820E +04 3190E *04 1,120E +04 0 000E +00 0 000E+00 0 000E +00 1050E*07 NP 239 1420E+03 1400E +02 7.720E +01 0 000E*00 4 370E*02 0 000E+00 2 870E +07 O -
Offsit] D0se Calcul; tion M:nual P:ge 246 of 313 Revision 2 Change 0 Atlachment 12 (-) v Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2* mrem /yr per uCi/sec) Nuchde Bone Uver Tbody Thyroid Kidney Lung Ortract 43 0 000E+30 2 590E+03 2500E+03 2 590E+03 2.590E +03 2 590E+f 3 2.590E +03 C 14 1.450E +06 2 910E +05 2 910E+63 2 010E+05 2 910E+0S 2 910E+( ) 2 910E*05 NA 24 2 450E *05 2 4$0E+05 2.450E +05 2 450E+05 2 450E+05 2 450E*05 2 450E+05 P 32 1610E +09 9 900E+07 6230E+07 0 000E+00 0 000E+00 0 000E+00 1,350E +08 CR51 0.000E + 00 0 000E+00 0200E+04 3 44M+04 1.300E *04 6850E+04 1.040E +07 MN54 0 000E +00 4 520E +08 8 970E+07 0 000E+00 1.350E +08 0 000E+00 9.270E +08 MN tG 0 00CE400 1450E *01 2 580E +00 0 000E *00 1.830E*01 0 000E +00 9 540E +02 F E 55 3 250E*05 2 310E+08 5380E+07 0 000E+00 0 000E+00 1400E+08 9 980E +07 FE59 1810E408 4 220E+08 1630E+08 0 000E +00 0 000E +00 1330E+08 9 9BOE +08 CO-57 0 000E+00 1.790E *07 3 000E+07 0 000E+00 0 000E+00 0 000E+0D 3 340E 608 C048 0 000E +00 4 380E+07 1.010E +08 V 000E400 0 000E+00 0 000E+00 6040E+08 CO40 0 000E* 00 2 490E+08 5600E+08 0 000E+00 0 000E+00 0 000E+00 3 240E +09 Ni 63 1610E +10 1.130E *09 5450E+08 0 000E+00 0 000E+00 0 000E+00 1810E+08a N645 57300+01 7.320E *00 3 330E400 0 000E+00 0 000E+00 0 000E+00 3 970E+02 f^ CU 64 0 00DE *00 8400E+03 3 950E403 0 000E+00 2100E+04 0 000E+00 6 510E +05 ZN45 4 240E +08 1.470E +00 6 060E+08 0 000E +00 9 410E406 0 000E+00 0230E+08 ZN-09 81 DOE 00 1500E 05 1090E 00 0 000E*00 1020E-05 0 000E +00 2.880E-05 DR-82 0 000E *00 0 000E+00 1330E406 0 000E +00 0 000E+00 0 000E +00 0 000E +00 BR 83 0 000E +00 0 000E+00 3 010E *'s 0 000E+00 0 000E+00 0 000E400 0 000E+00 DR 84 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0OCOE+00 BR 85 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RD40 0 000E+00 2 730E *00 1280E +08 0 000E+00 0 000E +00 0 000E+00 4 050C* 07 RB88 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RB 89 0 000E *00 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 SR 89 1510E +10 0 000E+00 4 330E+08 0 000E+00 0 000E *00 0 000E+00 1800E+09 SR 90 7 510E+11 0 000E+00 1850E+11 0 000E+00 0 000E+00 0 000E+00 2.110E + 10 SR91 2 990E+05 0 000E+00 1.190E +04 0 000E+00 0 000E+00 0 000E+00 1.360E
- 06 SR 92 3 970E+02 0 000E+00 1.690E *01 0 000E+00 0 000E+00 0 000E+00 1.010E + 04 Y-90 1240E +04 0 000E+00 3 340E+02 0 000E+00 0 000E +00 0 000E+00 1.020E +08 091M 5 430E 09 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 2 560E47 Y 91 7.870E +06 0 000E+00 2.110E+05 0 000E+00 0 000E+00 0 000E +00 3 230E+09 Y 92 8 470E-01 0 000E+00 2 450E 02 0 000E+00 0.000E +00 0 000E+00 2.320E+04 Y 93 1030E+02 0 000E+00 4 470E*00 0 000E+00 0 000E+00 0 000E+00 4 960E+06 p - Z R-95 1.740E +06 6490E+05 3 780E+05 0 000E+00 8 070E+05 0 000E+00 1270E +09 h ZR97 3 090E +02 6110E *01 2 810E +01 0 000C+00 9 260E+01 0 000E+00 1.650E +07
._ ~ - -- -- - .=. -.
Offsito D0se C:lculation Minu:1 Pcge 247 Of 313 R; vision 2 Ch:nge 0 Attachment 12 Gaseous Effluent Pathway Dose Factors {v] VEGETATION DOSE FACTORS TEEN (m2*rnrem/yr per uCl/sec) Nuchde Bone Liver Tbody Thyroid Kidney Lung Ottract NDM 1920E+05 1060E+05 5 660E +04 0 000E+00 1.030E *05 0 000E+00 4 550E+08 NB 97 2 690E46 6 670E-07 2 440E-07 0 000E+00 7.000E 07 0 000E+00 1.590E 02 MOM 0 000E *00 5740E+06 1090E +06 0 000E+00 1.310E + 07 0.000E *00 1.030E +07 TCMM 2 700E +00 7.540E + 00 9 770E+01 0 000E +00 1.120E+02 4190E+00 4 950E +03 TC 101 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RU 103 6870E+06 0 000E +00 2 940E +06 0 000E+00 2 420E*07 0 000E*00 5740E+08 RU 105 5000E+01 0 000E +00 1.940E +01 0 000E *00 6 310E+02 0 000E +00 4 040E +04 RU 106 3 090E *08 0 000E+00 3 900E +07 0 000E+00 5970E+08 0 000E+00 1480E +10 R H.10'lM 0000E+00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 RH 100 0 000E +00 0 000E +00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 0 000E +00 AG-110M 1$20E*07 1440E*07 8740E*06 0 000E+00 2 740E+07 0 000E+00 4 040E +09 SB 122 4 920E+05 5130E+05 6 220E*06 8150E +04 2 420E+05 1000E+05 6.120E+07 50124 l 1550E+08 2 850E+06 6 030E+07 3 510E+05 0 000E+00 1.350E+08 3110E+00 - 50125 2140E +08 2 340E+06 5000E+07 2 040E+05 0 000E +00 1.680E +08 1600E+09 TE 125M 1480E+08 5 340E*07 1.980E +07 4140E+07 0 000E +00 0 000E +00 4 370E+08 TE 127M 5510E+08 1900E+08 6 500E +07 1.310E +08 2 240E+09 0 000E+00 1.370E +09 TE 127 5 430E *03 1920E*03 1.170E +03 3 740E+03 2 200E +04 0 000E+00 4190E +0S TE 129M 3 670E +08 1.300E +08 5810E+07 1.180E *08 1 ?>40E *09 0 000E*00 1.380E +09 T E 129 6 220E 04 2 320E44 1.510E 04 4 450E44 2 610E 03 0 000E+00 3 400E-03 TE 131M 8 440E*05 4 050E+05 3 380E +05 6 000E+05 4 220E+06 0 000E+00 3 250E +07 TE 131 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 TE132 3 900E +06 2 470E+06 2 320E+06 2 600E+06 2.370E +07 0 000E+00 7820E+07 l130 3 540E+05 1.020E +06 4 090E+05 8 350E +07 1.580E +06 0 000E +00 7 870E +05 1,131 7.700E +07 1.000E +08 5 790E +07 3140E+10 1850E+08 0 000E +00 2.130E +07 1132 5180L+01 1.300E +02 4 870E *01 4 570E+03 2140E +02 0 000E*00 5 910E +01 1-133 1970E+06 3 340E+06 1020E*06 4 600E+08 5 B60E +06 0 000E+00 2.530E +C6 l-134 9 590E 05 2 540E-04 9130E 05 4 240E-03 4 010E-04 0 000E +00 3 350E46 6135 3 680E *04 9 480E +04 3 520E +04 6100E*06 1.500E *05 0 000E *00 1050E*05 CS 134 7.090E+09 1<670E*10 7.740E +09 0 000E+00 5 300E +09 2 020E+09 2 080E+06 CS-136 4290E+07 1690E +08 1.130E +08 0 000E +00 9190E+07 1450E+07 1.360E+07 CS 137 1010E+10 1350E+10 4 690E+09 0 000E +00 4 590E +09 1.780E+09 1.920E +08 CS 138 0 000E+00 0 000E+00 0 000E+C0 0 000E+00 0 000E+00 0 000E*00 0 000E+00 BA 139 2 770E42 1950E 05 8 080E-04 0 000E +00 1.840E-05 1.340E 05 2 470E 01 BA-140 1380E+08 1.690E +05 8.910E +06 0 000E +00 5750E+04 1.140E +05 2130E+08 B A 141 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00
Offsito Dose Calculation M:nual Pcg3 248 of 313 R0 vision 2 Change O p Attachment 12 ii Gas 00us Effluent Pathway Dos 0 Factors V VEGETATION DOSE FACTORS TEEN (m2* mrem /yr per uCi/sec) Nuchde Bone Uver Tbody Thytold Kidney Lung Oltract DA 142 0 000E+00 0 000E+00 0 000E+00 0 000E*00 0 000E +00 0 000E+00 0 000E+00 LA 140 1.800E +03 6840E+02 2.350E +02 0 000E+00 0.000E +00 0 000E+00 6 080E+07 LA 142 1280E 04 5 000E45 1.420E 05 0 000E +00 0 000E+00 0 000E+00 1.730E +00 CE 141 2 820E+05 1.880E+05 2.100E +04 0 000E+00 8 800E+04 0 000E+00 6.380E +08 CE 143 9 370E +02 6820E*05 7.620E +01 0 000E+00 3 000E+02 0 000E+00 2 000E+07 CE 144 5770E+07 2.180E +07 2 830E+C6 0 000E +00 1300E+07 0 000E+00 1.330E + 10 PR 143 7.120E +04 2 840E+04 3 550E+03 0 000E+00 1650E*04 0 000E+00 2.340E+08 PR 144 0 000E+00 0 000E +00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 ND 147 3 630E*04 3 940E+04 2 300E+03 0 000E+00 2 320E+04 0 000E*00 1420E+08 EU 154 7 000E +07 9120E*00 6430E+00 0 000E+00 4 000E+07 0 000E+00 4 820E+09 EU.165 1 540E+07 1.480E +06 9190E+05 0 000E+00 $800E+00 0 000E+00 8510E+09 W 167 3 500E+04 2 900E+04 1.020E +04 0 000E*00 0 000E+00 0 000E+00 7.840E *06 NP 239 1.380E +03 1.300E +02 7 240E+01 0 000E+00 4 090E+02 0 000E+00 2100E +07-* O
Offsit3 00se C:lcul&Jon M:nud P:g) 249 Of 313 Revision 2 Change 0 g Attachment 12 i Gaseous Effluent Pathway 00se Factors 4 VEGETATION DOSE FACTORS CHILD (m2' mrem /yr per uCl/sec) Nuclide Bue Uver Tbody Thyroid Kkiney Lung Ottract H-3 0 000E+00 4 010E+03 4 010E +03 4 010E+03 4 010E+03 4 010E+03 4 010E+03 C 14 3 500E*00 7.010E +05 7.010E+05 7.010E +05 7.010E+05 1.010E+C3 7.010E+05 NA 24 3 830E+05 38 W +05 3 830E+05 3 830E+05 3 830E+05 3 830E+05 3 830E +05 P 32 3 370E+09 1.580E *08 1.300E+08 0 000E+00 0 000E+00 0 000E400 9300E+07 CR 51 0 000E+00 0 000E+00 1.100E +05 6 540E+04 1.790E+04 1.190E+05 6.250E+06 MN44 0 000E +00 6 610E+08 1.700E+08 0 000E+00 1.050E+08 0 000E+00 5 550E*08 MN46 0 000E *00 1.900E401 4 280E +00 0 000E+00 2 290E+01 0 000E+00 2 750E+03 FE45 8000E+08 4 240E+08 1.310E +08 0 000E+00 0 000E +00 2 400E+08 7.860E +07 FE49 4 010E +08 6 490E+08 3 230E*D8 0 000E+00 0 000E+00 1.880E +08 6 700E+08 C047 0 000E+00 2 990E*07 6 040E+07 0 000E+00 0 000E +00 0 000E+00 2.450E+08 C048 0 000E +00 6 470E+07 1980E+08 0 000E+00 0 000E+00 0 000E+00 3 770E+08 C040 0 000E+00 3 780E+0S 1.120E+09 0 000E+00 0 000E+00 0 000E+00 2.100E +09 NLC3 3 950E +10 2110E+09 1.340E+09 0 000E+00 0 000E+00 0 000E +00 1.420E +08" ( l NI45 1.050E +02 9 890E +00 $770E+00 0 000E+00 0 000E+00 0 000E +00 1.210E+03 CU44 0 000E*00 1 110E +04 6 690E+03 0 000E+00 2 680E+04 0 000E+00 5 200E* 05
\ ZN 05 8120E+08 2100E*00 1.350E +09 0 000E+00 1.300E+ 09 0 000E+00 3 800E+08 ZN49 1510E.05 2180E 05 2 020E 06 0 000E+00 1.320E-05 0 000E+00 1.380E 03
( DR 82 0 000E *00 0 000E+00 2 040E
- 06 0 000E+00 0 000E+00 0 000E +00 0 000E+00 f
BR43 0 000E*00 0 000E +00 5 550E+00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 l 0R 84 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BR 85 0 000E +00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 R D-86 0 000E+00 4 520E+08 2 780E+08 0 000E+00 0 000E+00 0 000E+00 2 910E+07 RB 88 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RB49 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 SR-89 3 590E+10 0 000E*00 1.030E+09 0 000E+00 0 000E+00 0 000E+00 1.390E +09 SR 90 1240E+12 0 000E *00 3150E+11 0 000E+00 0 000E +00 0 000E+00 1.670E +10 S R-91 5 500E+05 0 000E +00 2 080E+04 0 000E+00 0 000E+00 0 000E+00 1.210E +06 SR92 7.280E*02 0 000E+00 2 920E+01 0 000E+00 0 000E +00 0 000E+00 1.380E +04
- Y 90 2 300E +04 0 000E+00 6170E+02 0 000E+00 0 000E+00 0 000E+00 6 560E+07 Y-91M 9 940E 09 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 1.950E 05 Y 91 1.870E+07 0 000E *00 5010E+05 0 000E+00 0 000E+00 0 000E+00 2.400E+09 Y 92 1560E+00 0 000E*00 4 460E-02 0 000E+00 0 000E+00 0 000E+00 4 510E+04 Y-93 3 010E+02 0 000E+00 8 250E+00 0 000E+00 0 000E +00 0 000E+00 4 4SOE+06 ZR 95 3 900E+06 8 580E+05 7 640E+05 0 000E+00 1.230E +06 0 000E +00 8 950E +08 l (,/ 2R 97 5 640E +02 819M 01 4 810E *01 0 000E+00 1 170E+02 0 000E +00 1.230E +07
Offsb Dose C:lculation Manu:1 Pega 250 of 313 Revision 2 Change 0 , Attachment 12 i Gaseous Effluent Pathway Dose Fectors VEGETATION DOSE FACTORS CHILD i
- ' (m2*mtemlyr per uCi/sec) ;
1 Nucikle tone Liver Tbody Thyroid Kidney Lung Oltract N646 4.100E +05 1.$90E +05 1.140E +05 0 000E+00 1.500E+05 0 000E+00 2.950E +08 N8-97 4 900E-06 8 850E 07 4130E 07 0 000E+00 9 820E 07 0 000E+00 2.730E 01 ; 4 MO-99 0 000E+00 7.830E +06 1.940E +06 0 000E+00 1.670E +07 0 000E+00 6.490E+06 i TC 99M 4 850E+00 9120E*00 1.510E +02 0 000E+00 1.330E+02 4 630E+00 5190E+03 *
- TC-101 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0.000E +00 0.000E+00 0.0COE +00 RU-103 1.550E *07 0 000E*00 5940E+06 0 000E+00 3 890E+07 0 000E+00 3 990E+08 t RU 105 9170E+01 0 000E+00 3 330E +01 0 000E+00 8 000E+02 - 0 000E+00 $980E+04 RU 106 7.450E+ 08 0.000E+00 9.300E+07 0 000E+00 ' 1.010E+09 0 000E+00 1100E+10 l 'RH133M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 DME+00 RH 106 0 000E+00 0.000E400 0.000E +00 0 000E+00 - 0 000E+00 0.000E+00 0 000E+00 i I
AG 110M 3 220E+07 2.170E+07 1.740E +07 0 000E*00 4 050E+07 0 000E +00 2 580E+09
$B 122 3 050E+05 3180E+05 3 850E +06 5.050E+04 1.500E +05 6540E+04 3 790E+07 l
88-124 3.520E+08 4 570E*06 1.230E +08 7.780E+05 0 000E+00 1.960E *08 2 200E+09
- i
- $B125 4 990E*',a 3 850E+06 1.050E +08 4 620E+05 0.000E +00 2.780E +08 1,190E +09 TE 125M 3 510E+08 9 500E+07 4 670E+07 9 840E+07 0 000E+00 0 000Ee00 3 360E*08 TE 127M 1.320E+09 3 500E+08 1.570E +08 3.160E+08 3 770E+09 0 000E+00 1.070E +09
$ TE 127 1.000E +04 2.700E+03 2.150E+03 6 930E+03 2 850E+04 0 000F+00 3 910E+05 , TE 129M 8 540E +08 2 390E+08 1.330E +08 2.750E +08 2.510E +09 0 000E+00 1.040E +09 TE 129 1,150E-03 3 220E-04 2.740E 04 8 220E 04 3 370E 03 0 000E+00 7.170E 02 TE 131M _1 540E+06 5 330E+05. 5680E+05_ 1.100E+06 5160E+06 0 000E+00 2160E+07 TE 131. 0 000E*00 0 000E*00 0 000E +00 0 000E+00 0 000E+00 0 000E*00 0 000E*00 - TE 132 6 980E*06 3 090E +06 3.730E +06 4 500E+06 2 870E+07 0 000E+00 3110E+07 l130 0210E+05 1.200E *06 6470E+05 1.380E+08 1.880E+06 0 000E+00 $870E+05 , 4-131 1430E +08 1.440E*08 8180E+07 4 760E*10 2.360E+08 0 000E+00 1.280E +07 l 132 9 200E *01 1.690E+02 7.770E +01 7.840E+03 2.590E+02 0 000E+00 1990E+02 1-133 3 590E+06 4.440E+06 1,680E +06 8250E+08 7.400E+06 0 000E+00 1.790E+06 I l134 1.700E 04 3.180E-04 1.460E44 7.280E 03 4 840E 04 0 000E+00 2.100E-04 i135 6540E+04 1.180E*05 5.570E+04 1.040E+07 1.810E+05 - 0 000E+00 8 980E*04 CS 134 1.000E+10 2 630E+10 5.540E+09 0.000E+00 8140E+09 2.920E+09 1.420E+08 4
- CS 136 8060E*07 2 220E+08 . 1.430E +08 0 000E+00 .1.180E+08 1.760E +07 7.790E+06 -
CS-137 2.300E + 10 2 290E +10 3 380E +09 0 000E+00 7.460E+09 2.680E* 09 1430E+08 CS 138 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 - BA 139 5,110E-02 2 730E-05 ' 1480E 03 0.000E+00 2 380E 05 1.610E 05 : 2 950E +00 DA 140 ' 2770E*08 2 430E+05 1.620E+07_ _ 0 000E+00 7.000E+04 1.450E+05 1.400E+08 BA 141 0 000E+00 - 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 a..a , _ . _ . , _ . _ . _ _ , _ . ~ . . _ . _ - _ _ . _ _ . - . . . . _ . . . . - . _ .u . . . _ . - _ . _ ~ . . _
Offsit) D050 Calculation M:nu:1 Pag) 251 of 313 R; vision 2 Chin 00 0 Attachment 12 []' (/ Gaseous Effluent Pathway 00s0 Factors VEGETATION DOSE FACTORS
)
CHILD (m2* mrem /yr per uCl/sec) Nuchde Bone Uver Tbody Thytold K6dney Lung Gitract DA 142 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E *00 LA 140 3 230E+03 1.130E +03 3 810E*02 0 000E+00 0 000E+00 0 000E+00 3150E+07 LA 142 2.320E 04 7 400EWs 2 320E 05 0.000E+00 0 000E+00 0 000E+00 1470E
- 01 CE 141 6350E+05 3 200E+05 4 840E+04 0 000E+00 1.430E+05 0 000E+00 4 070E+08
- CE 143 1.730E +03 9 300E +05 1.300E +02 0 000E+00 3 930E*02 0.000E+00 1.370E +07 CE 144 1.270E + 08 3 980E+07 6 780E+08 0 000E+00 2 210E*07 0 000E+00 1440E+10 PH 143 1480E+05 4 460E+04 7.370E *03 0.000E +00 2.410E +04 0 000E*00 1600E+08 PR 144 0 000E *00 0 000E *00 0 000E+00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 ND 147 7.100E +04 5800E+04 4 490E+03 0 000E+00 3180E+04 0 000E+00 9180E+07 EU 154 1600E +08 1?s00E+07 1.370E+07 0 000E *00 6 570E+07 0.000E +00 3 480E+09 EU 155 3 440E+07 2 480E+00 1940E+06 0 000E+00 9 200E+06 0.000E +00 6 200E+09 W 187 6 470E +04 3 830E +04 1.73E+04 0 000E+00 0 000E+00 0 000E+00 5 380E+06 NP-239 2 550E +03 1830E+02 1290E+02 0 000E+00 5 300E+02 0 000E+00 1 360E + 07-~
t
. _ _ _ - . - - - ~ . . - . - . - . - . - _ - . ~ - - . -. .
l Offsito D:se C:lculation Minuil PC0e 252 of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS INFANT (m2' mrem /yr per uCl/sec) ! l Nuchde -Bone Uvot Tbody Thyroid Kidney Lung Gltract i THIS PATHWAY 18 NOT APPLICABLE
- TABLE INTENTIONALLY LEFT BLANK 2
1 I as % 4 +- A i
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a __
, 1 . - - . . . . - . . - - . . - . . - - - . - . - _ . - . _ . . . . . . _ . . . - - , . - . - - , . - . . - . . ...-...a,..-...-.
- m. _ . . . . . _ _ _ . _ _ _ . . _ . _ _ . _ . . _ _ _ _ . _ _ _ _ - . _ _ _ _ ..- _ _ - _ __.
i i OffsNe Dose C:lculati:n M:nu:1 Peps 253 of 313 l l Revision 2 Change 0 Attachment 12 l I Gaseous Effluent Pathway Dose Factors ! GROUND PLANE DOSE FACTORS ADULT l (m2*mtemlyr per uCl/sec) Nuchde bone Uvor Tbody 1hyroid Kidney Lueq OHrect
- 1 THis PATHWAYis NOT APPLICABLE ,
TABLE INTENTIONALLY LEFT BLANK Y . t i i i a M t k u e t 4
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Offsit) Dose C:loulation M:nuil Page 254 of 313 j Revision 2 Change 0 3 Attachment 12 : Gas 00us Effluent Pathway D0se Factors GROUND PLANE DOSE FACTORS - TEEN (m2' mrem /yr per uCl/sec) ; i Nuchde Bone Livet Body Thyto6d K6dney Lung Oltract I H3 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 f f' C 14 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 NA 24 1.210E*07 1,210E+07 1.210E +07 1.210E+07 1.210E+07 1.210E+07 - 1.210E +07 i i P-32 0 000E+00 0 000E+00 0.000E + 00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 ' ; CR41 4 680E+06 4 680E+06 4 680E+06 - 4 680E+06 4 680E+06 4 680E+06 4 680E+06 J MN44 1.340E+09 1.340E+09 1.340E *00 1.340E+09 1.340E+09 1,340E+09 1.340E+09 j MN46 9 050E+05 9050E+05 90$0E+05 9 050E+05 0050E+05 9 050E+05 9 050E +05 l TE45 0 000E*00 0.000E+00 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 FE49 2 750E+08 2 750E+08 2.750E +08 2.750E+08 i 1 2.700E*06 2.750E +08 2.750E +08 I C048 ' 3 820E*06 - 3 820E+08 3 820E+08 3.820F*06 3 820E+08 3 820E+0It 3 820E+08 l C040 2.190C + 10 2100E+10 2.180E *10 2.160E +10 2.160E+10 2.100E
- 10 2.160E +10 [
N143 0 000E*00 0 000E+00 0 000E+00 0,000E+00 0 000E+00 0.000E+00 0 000E+00 l N145 2 970E *05 2 970E+05 2 970E+05 2 970E+05 2 970E+05 2 970E+05 2 970E+05" CU44 6090E+05 6 090E*05 6090E+05 6 090E+05 6 090E+05 6 090E+05 6 090E+05 ZN45 7,450E + 08 7.450E +08 7 450E+08 7.450E+08 7 450E+08 7.450E+08 7.450E+08 - ZN49 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 ! BR 83 4 890E+03 4 890E+03 4 890E+03 4 890E+03 4 890E+03 4 890E+03 4 890E+03 BR44 2.030E *05 2 030E +05 2.030E+05 2.030E
- 05 2.030E*05 2 030E +05 2 030E +05 l
- DR45 0 000E+00 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 RB40 8 980E*06 8 980E +06 8 980E+06 8 980E+06 8 980E+08 8 980E+06 8980E+06 RB48 3 290E+04 - 3 290E+04 3 290E+04 3 290E+04 3.290E+04 3 290E+04 3 290E +04 RB 89 1.210C+05 1.210E+05 1210E+05 1210E*05 1.210E+05 1.210E+05 1210E+05 SR49 2160E+04 2.100E+04 2160E+04 2.100E +04 2.160E+04 2.160E+04 2,100E+04 SR 90 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 SR-91 2,190E*06 - 2.190E+06 2.190E *06 2.190E +06 2.190E+06 2.190E+06 2.190E+06 SR 92 7.770E+05 7.770E+05 7.770E+05 7.770E +05 7.770E+05 7.770E+05 7.770E +05 !
Y 90 '4 400E+03 4 480E+03 4 480E+03 4 480E+03 4 400E+03 4 480E+03 4 480E+03 Y 91M 1.010E+05 1.010E+05' 1.010E+05 1.010E+05 1.010E+05 - 1.010E +05 1.010E+05 Y 91 1.000E+06 1.080E+06 1.080E+06 1.080E+06 1.000E+06 1.080E+06 1.080E+06
;Y 92 1.800E+05 1.800E +05 1.800E+05 - 1.800E+05 1.800E +05 1.800E+05 1.800E+05 ;
Y43 1,850E+05 - 1850E+05 1.850E +05 1,850E +05 1.850E+05 1,850E+05 1.850E+05 ZR45 2 480E+08. 2.480E+08 2.480E+08 2 480E+08 2.480E+08 2.480E+08 2 480E+08 2R 97 2.940E+06 2 940E+06 2 940E+06 2.940E+06 2 940E+06 2 940E+06 2.940E+06 NS-95 1.360E+08 1.360E+08 1.360E +08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 t
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i Offsit) Dose Calculation M:nual P gs 255 of 313 R: vision 2 Change o Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS TEEN (m2'mremlyr per UCl/sec) Nucede tone Liver Tbody Thytold K4dney Lung OMeact MO-99 4 050E+00 4 OBOE +08 4 050E+06 4 050E+06 4 050E+06 4 050E+06 - 4 050E +06 TC 99M 1.830E+05 1.830E *05 1.830E+05 1.830E+05 1.830E+05 1.830E +05 1.830E+05 TC-101 2.040E +04 2 040E+04 2 040E+04 2 040E+04 2 040E+04 2 040E+04 2.040E+04 RU 103 1,000E +08 1.090E+08 - 1,090E+06 1.090E+08 1.090E +06 1.090E+08 1.090E+08 - RU 105 6 300E+05 6 360E+05 0.360E+05 6 360E*05 6.360E +05 6.360E+05 6.360E+05 RU 106 4.210E +08 4 210E+08 4 210E+08 4 210E+08 4.210E+08 4.210E*06 4.210E+08 1
- RH 103M 0,000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 - 0.000E +00 l RH 106 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0.000E+00 0 000E+00 0 000E+00 - .
AO 110M 3 470E+09 3 470E+09 3 470E*09 3.470E+09 3 470E+09 - 3 470E+09 3 470E+09 58 122 1070E+07 1070E+07 1.070E+07 1.070E+07 1.070E +07 1.070E +07 1.070E *07 l ' TE 125M 1.550E*00 1.650E +06 1550E+06 1650E+06 1.550E+06 1.550E +06 1.550E +06 10127M 9170E+04 9170E*04 9.170E +04 9170E*04 9.170E+04 9170E+04 9.170E +04 1E 127 3 000E +03 3 000E+03 3 000E+03 3 000E+03 3 000E+03 3 000E+03 3 000E+03^ , i 2,000E+07 TE 129M 2.000E
- 07 2,000E+07 2 000E+07 2.000E+07 2 000E+07 2 000E+07 ,
TE 129 2 000E+04 2 000E+04 2 000E +04 2.600E +04 2.000E+04 2.600E +04 2 600E+04 TE 131M 8030E+06 6030E+06 8030E+06 8 030E+06 0030E+06 8030E+06 8030E+06 2 TE 131 2 930E+04 2 930E+04 2 930E+04 2 930E+04 2%30E+04 2 930E+04 2 930E+04 TE 132 4 220E+06 4 220E*06 4 220E+06 4 220E+06 4 220E+06 4 220E+06 4 220E +06 1130 $$30E+06 5530E+06 5530E+06 5530E+06 5530E+06 5530E+06 5.530E+06 l131 1,720E+07 1.720E +07 1.720E+07 1.720E+07 1.720E+07 1.720E+ 07 1.720E +07 l132- 1.240E +06 1.240E +06 1,240E+06 - 1.240E+06 1.240E+06 1.240E +00 1.240E+06 -
-l133 2 470E*06 - 2.470E +06 2 470E+06 2.470E +06 2.470E+06 2 470E+06 2 470E+06 I
1134 4 490E+05 4 490E+05 4 490E+05 4 400E+05 4 490E+05 4.490E +05 4 490E+05 4 6135 2 560E+06 2.560E +06 2.560E +06 2.560E+06 2.560E+06 2.560E +06 2 560E+06 CS 134 6.750E +09 6750E+09 6 750E+09 6.750E+09 6 750E+09 6750E+09 6.750E+09 CS 136 1.490E+08 1.490E+06 1.490E+08 1.490E +08 1.490E +08 1,490E+08 - 1.490E+08 CS 137 1.040E +
- 0 1.040E+10 1.040E +10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS 138 3 590E*05 3 590E*05 3 590E+05 3 590E+05 3 590E+05 3 590E +05 3 590E+05 BA 139 - 1.000E +05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA 140 - 2.050E +07 2 050E+07 2 050E*07 2 050E+07 2 0$0E+07 - 2 050E+07 2.050E +07 BA 141 4180E+04 4180E*04 - - 4.100E*04 4180E+04 4180E+04 4180E*04 4180E+04 BA 142 _ 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 LA 140 1,910E+07 -- -
~1910E+07 1,910E+07 1.910E+07 1910E+07 1.910E+07 1.910E+07 !
- LA 142 7.360E+05 . - 7 360E+05 7.360E+05 7.360E +05 7.360E+05 7,360E +05 7.360E +05 CE 141 1.360E+07 1.360E+07 - _i360E+07 _1.300E+07 _1.360E+07 1.300E+07 1.360E+07 -
. - . - _ ._ _._. _ . _ ~ _ . . _ , . ~ . _ , _ _ _ . . ~ , _ _ . _ . _ _ _ . - , _ _ _ _ . _ . _ _ _.
Offsite Dose Calculation Manual Page 250 of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS TEEN (m2*mtem/yr per uCl/sec) Nucl6de Done Liver Tbody Thyroid K6dney Lung Oltract CE 143 2 320E*06 2 320E+06 2 320C +06 2.320E +06 2.320E + 06 2! *06 2 320E*06 CE 144 0 %0E+07 6 %0E *07 6950E+07 6 M0E+07 6 950E+07 f ,JE+07 6 950E +07 PR 143 0 000E*00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 PR 144 1830E*03 1 830E+03 1.030E + 03 1.830E+E A 1830E+03 1830E+03 1830E+03 ND-147 8400E+06 8400E+06 8 400E*06 8400E+06 8400E+06 8 400E*06 8 400E*06 EU 154 2 700E+10 2.700E + 10 2 700E*10 2.700E
- 10 2.700E + 10 2 700E+10 2 700E*10 EU 1!,5 9570E+08 9 670E *06 9 570E408 9 $70E +08 9 570E +08 9 570E*08 9 $70E
- 08 W 187 2 300E+06 2 300E*06 2 300E+06 2 300E+06 2 360E +06 2 360E +06 2 300E* 06 NF 239 1710E *06 1710E +06 1.710E
- 06 171OE*06 1.710E + 06 1710E
- 06 1710E +06 e
Offsite D05o Calculetl0n Manu81 Page 257 Of 313 Revision 2 Chango 0 i Attachment 12 Gaseous Etfluent Pathway D0se Factors GROUND PLANE DOSE FACTORS CHILD (m2'intem/yr per uCl/sec) Nuthde Borie Over Tbody Thytold Kidney Lur.g Oltract 11 3 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +(O 0 000E *00 0 000E +00 C-14 0 000E +00 0 000E+00 0 000E +00 0 000E +00 0 000E *00 0 000E*00 0 000E +00 NA 24 1210E *07 1210E*07 1210E +07 1210E*07 1 210E+07 1210E+07 1210E+07 P 32 0 000E +00 0 000E *00 0 000E *00 0 000E *00 0 000E 400 0 000E+00 0 C00E+00 CR 51 4 000E +00 4 680E *00 4 680E*00 4G80E+00 4680E+00 4 680E+00 4000E+00 MN-54 1340E *09 1.340E +09 1.340E + 09 1.340E +09 1.340E *09 1.340E +09 1340E+09 MN 56 9 050E +05 9050E+05 90'OE+05 9 050E +05 90'cE+05 9 050E+05 9 050E+05 F E-55 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 C00E +00 0 000E+00 FE 59 2 750E+08 2 750E +08 2 750E*08 2 750E+08 2750E*08 2 750E*08 2 7502.+08 CO-58 3 820E+08 3 820E *08 3 820E+08 3 820E+08 3 820E *08 .1820E*08 3 820E*08 CO 60 2100E +10 2100E
- 10 2100E*10 2100E + 10 2100E+10 P 100E
- 10 2160E *10 NI63 0 0000 +00 0 000E +00 0 0000 + 00 0 000E*00 0 000E*00 ((00E+00 0 000E+00 N145 2 970E *05 2 070E*05 2 970E +05 2 970E *05 2 970E+05 2 970E+05 2 970E+05
- CU44 6 090E + 05 6090E+05 0 090E+05 6ODOE+05 0 000E+05 6 090E +05 6 OX>E + 05 ZN65 7 450E*08 7 450E+08 7 450E+08 7.450E +08 7 450E+08 7. 450E + 08 7 450E+08 ZN 09 0 000E*00 0 000E *00 0 000E *00 0 000E+00 0 000E*00 0.XCE
- 00 0 000E *00 DR 83 4 000E*03 4 890E + 03 4800E*03 4 890E *0* 4 890E +03 4 590E+03 4 890E+03 DR44 2 030E *05 2 030E +05 2 030E *05 2 030E+05 2 030E +05 2 030E+05 2 030E +05 DR 85 0 000E *00 0 000E *00 0 000E+00 0 000E+00 0 000E +00 OIDOE*00 0 000E +00 RD40 8 980E *06 8980E+06 8980E+06 8 980E*06 8 960E*06 8te80E+06 8 980E.00 R U-88 3 090E +04 3 290E +04 3 290E +04 3 290E *04 3 290E *04 3 P90E *04 3 290E+04 R D-89 1210E*05 1210C +05 1210E*05 1210E *05 1210E+05 1.310E +05 1210E *05 SR 89 2160E+04 2 iGOE *04 2100E *04 2160E*04 2160E *04 2M60E*04 2100E*04 5R 00 0 000E +00 0 000E+0n 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 SR 91 2190E+06 2190E *06 2190E+06 2190E*06 2190E*06 2190E *08 2.190E+ C2 GR-92 7.770E *05 7.770E+05 7.770E *05 7.770E *05 7.770E +05 7,770E
- 05 7.770E*05 Y 90 4 480E +03 4 480E+03 4 480E+03 4 480E+03 4 480E+03 4 480E+03 4 400E+03 Y 91M 1010E+05 1.010E+05 1010E+05 1.010E+05 1.010E +05 1010E *05 1.010E
- 05 Y 91 1080E +06 1080E+06 1080E*06 1080E+06 1080E +06 9 OBOE +06 1080E + 06 Y 92 1800E+05 1800E+05 1800E*05 1800E*05 1.800E +05 1 800E+05 1800E+05 Y 93 1850E +05 1.850E + 05 1850E +05 1850E+05 1650E+05 1.850E +05 1850E+05 ZR 95 2 480E+08 2 400E+08 2 480E+08 2 480E+08 2 480E +08 2480E+08 2 480E+08 ZR 97 2 940E *06 2 940E +06 2 94vE *06 2.940E+06 2 940E+06 2.940E
- 00 2 940E+06 NB 95 %)E
- 08 1360E+08 1300E +08 1300E+08 1360E *08 1360E
- 08 1360E +08 MO 09 TE+06 4 050E +06 4 050C +06 4 050E+06 4 050E +06 4 050E +06 4 000E+06 I
Offsita Dose C:Iculatl0n Manu:1 Ptge 258 Of 313 Revi5 ion 2 Change 0 m Attachment 12 Gaseous Effluent Pathway DO5e Factors lV) GROUND PLANE DOSE FACTORS CHILD (m2 mrem /yr per uCl/sec) Nuclide Bone Liver Tbody Thyroid Kidney Lung Ottract TC-99M 1.830E +05 1.830E+05 1.830E+05 1.830E+05 1830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2 040E+04 2 040E+04 2 040E+04 2.040E+04 2.040E +04 2.040E+04 RU-103 1.000E +08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.000E+08 1.090E +08 RU-105 6 360E+05 6 360E+05 6 360E+05 6 360E+05 6:360E+05 6.360E +05 6 360E+05 ' RU-106 4.210E +08 4 210E+08 4 210E +08 4 210E+08 4.210E +08 4.210E+08 4 210E*06 R H-103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 a000E+00 0 000E+00 0 000E+00 RH-G 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E +00 0 000E+00 AG-110M 3 470E+09 3 470E+09 3 470E+09 3.470E+09 3 470E+09 3.470E +09 3 470E+09 SB-122 1.070E+07 1.070E+07 1.070E +07 1.070E+07 1.070E +07 1.070E +07 1.070E+07 l T E-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE 127M 9170E+04 9.170E+04 9170E+0L 9170E+04 9.170E+04 9.170E +04 9170E +04 TE 127 3 000E+03 3 000E+03 3 000E+03 3 000E +03 3 000E+03 3 000E+03 3 000E+03 TE-129M 2 000E+07 2.000E+07 2.000E+07 2.000fi+07 2 000E+07 2 000E+07 2 000E+07" TE 129 2 600E +04 2 600E+04 2 000E +04 2,6000+04 2 600E+04 2 600E+04 2.600E +04 p TE 131M 8030E+06 8.030E+06 8 030E +06 8 030E+06 8 030E+06 8 030E +06 8 030E+06 T E-131 2 930E+04 2 930E+04 2 930E+04 2.930E+04 2 930E+D4 2 030E+04 2 930E+04 TE 132 4 220E+06 4 220E+06 4 220E +06 4 220E*06 4 220F+06 4 220E+06 4 220E+06 l-130 5 530E+06 5 5~,0E+06 5 530E+06 5 530E+06 5 530E+06 5 530E+06 5 530E+06 6-131 1.720E +07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 l-132 1.240E+06 1.240E +06 1.240E +06 1240E+06 1.240E+06 1.240E+06 1240E+06 l-133 2.470E +06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2 470E+06 2 470E+06 l-134 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 430E+05 1135 2 560E+06 2 560E+06 2.560E+06 2.560E+06 2.560E +06 2fA0E +06 2 560E+06 CS 134 6.750E+09 6.750E+09 6.750E +09 6.750E +09 6 750E+09 6.750E +09 6 750E+09 CS-136 1.490E+08 1490E+08 1.490E +08 1.490E+08 1.490E+08 1.490E+08 1 490E+0S CS 137 1.040E+10 1.040E+ 10 1040E+10 1.040E+10 1.040E+10 1.040E+10 1040E +10 CS-138 3 590E+05 3.590E +05 3 590E+05 3 590E+05 3.590E+05 3.590E+05 3.590E+05 BA 139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1060E+05 1.060E +05 1060E +05 BA 140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2 050E+07 2.050E+07 BA 141 4180E+04 4.180E+04 4180E+04 4.180E+04 4.180E+04 4180E+04 4180E+04 BA 142 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 LA-140 1910E+07 1910E+07 1.91LE +07 1910E+07 1910E+07 1 910E+07 1910E+07 LA-142 7.360E+05 7.360E+05 7.360E +05 7.360E +05 7.360E+05 7.360E +05 7.360E+05 fm CE 141 1.360E+07 1.360E+07 1360E +07 1.360E+07 1.360E +07 1.360E+07 1360E+07 CE 143 2.320E +06 2.320E+06 2.320E +06 2 320E+06 2 320E+06 2 320E +06 2 320E+06
Offsita Dose Calculation Manual Page 259 of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND Pt.ANE DOSE FACTORS CHILD (m2*mrom/yr per uCi/sec) Nucl6de Bone Uver Tbody Thyroid Kidney Lurq Ottract CE 144 6 950E+07 6 950E+07 6 950E+07 6950E+07 6.950E+07 6950E+07 6950E+07 PR 143 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 PR-144 ^ 1.830E +03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1830E+03 ND-147 8400E+06 8400E+06 8 400E+06 8400E+0G 8 400E+06 8.400E+06 8 400E+0e EU 154 2.700E+10 2.700E +10 2.700E+ 10 2.700E+10 2 700E+10 2.700E+10 2.700E+10 EU-155 9 570E+08 9 570E+08 9 570E+08 9 570E+08 9.570E+08 9 570E+08 9.570E +08 W+187 2.360E +00 2.360E+06 2 3WE+06 2 360E+06 2.360E+06 2 360E+06 2.360E406 NP 239 1.710E +06 1.710E +00 1,710E+00 1.710E+06 1.710E+06 1.710E+06 1.710E +06
%#u %/
i Offsita Dose C-Iculitl0n Manu 1 Page 260 of 313 ) R; vision 2 Change 0 l Attachment 12 [d Gaseous Effluent Pathway D0se Factors GROUND PLANE DOSE FACTORS INFANT (m2* mrem /yr per uCl/sec) Nuchde Bone uver Tbody Thyroid Kktney Lung Gltract H-3 0 000E*00 0 000E+00 0000E+00 0.000E +00 0 000E+00 0.000E+00 0 000E+00 C 14 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 NA 24 1.210E +07 1.210E+07 1.210E+07 1.210E+07 1.210E
- 07 1.210E +07 1.210E +07 P-32 0 000E+ 00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 '
CR 51 4 680E+06 4 680E+06 4 680E+06 4 680E+06 4 680E+06 4 680E+06 4 680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN56 9050E+05 9 050E+05 9 050E+05 9 050E+05 9 050E+05 9050E+05 9 050E+05 FE45 n 000E+00 0.000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 F E-59 2.750E +08 2.750E +08 2 750E +08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3 820E+08 3 820E+08 3 820E+08 3 820E+08 3 820E+08 3 820E+08 3 820E+08 C040 2160E+10 2160E+10 2.160E+10 2.160E+10 2.160E +10 2.160E+10 2.160E +10 N143 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 0002+00 0 000E+00 0 000E+00 N145 2 970E+05 2 970E+05 2 970E+05 2970E+05 2 970E+05 2 970E+05 2 970E+05 " CU44 6 090E+05 6 090E+05 6 000E+05 6 090E+05 6 090E+05 6 090E+05 6 090E+05 m ZN45 7 450E+08 7.450E +08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E +08 2N49 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 BR43 4 890E+03 4 890E+03 4 890E+03 4 890E +03 4 890E+03 4 890E+03 4 890E+03 BR44 2.030E +05 2 030E+05 2.030E+05 2 030E+05 2 030E+05 2 030E+05 2.030E +05 BR45 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 RB46 8 980E+06 8980E+06 8 980E+06 8.980E+06 8 980E+06 8.080E+06 8 980E+06 RB48 3 290E+04 3.290E +04 3 290E +04 3 290E+04 3 290E+04 3 290E+04 3 290E+04 RB40 1.210E +05 1.210E +05 1210E+05 1.210E+05 11 0E+05 1210E+05 1.210E+05 SR49 2160E+04 2160E+04 2160E+04 2.160E+04 2.160E +04 2.160E+04 2.160E +04 5R.90 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 GR 91 2.190E +06 2.190E+06 2.190E+06 2.190E +06 2.190E+06 2.190E+06 2.190E +06 SR 92 7.770E +05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y.90 4 480E +03 4 480E+03 4 480E+03 4.480E+03 4 480E+03 4 480E+03 4 480E+03 Y 91M 1.010E+05 1.010E +05 1.010E+05 1.010E+05 1.010E +05 1.010E+05 1.010E+05 Y.91 1.080E +06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 Y 92 1.800E+05 1.800E+05 1.800E+05 1.800E+0S 1.800E +05 1.800E+05 1.800E+05 Y 93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E +05 ZR 95 2.480E +08 2 480E+08 2 480E+08 2.480E +08 2 480E+08 2 480E+08 2.480E .08 ZR-97 2 940E+06 2 940E+06 2 940E+06 2 940E+06 2 940E+06 2 940E+06 2.940E +06 N B-95 1,360E +08 1.360E+08 1.360E +08 1.360E +08 1.360E +08 1.360E+08 1.360E+08 ( ) MO-99 4 050E+06 4 050E+06 4 050E+06 4 050E+06 4 050E+06 4 050E+06 4 050E+06 v l 1
Offsita D0se C:lCul: tion M: null P ge 261 of 313 Revision 2 Chango 0
,m Attachment 12 Gaseous Etnuent Pathway D0se Factors (V) GROUND PLANE DOSE FACTORS INFANT (m2* mrem /yr per uCi/seC)
Nuchde Bone Uver Tbody Thyroid Kidney Lung Ottract TC-99M i 830E+05 1830E +05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E +05 TC-101 2 040E+04 2 040E+04 2.040E *04 2 040E+04 2 040E+04 2.040E+04 2 040E+04 RU 103 1.090E +08 1.090E+08 1.000E+08 1.090E+08 1.090E +08 1.090E+08 1.090E+08 RU 105 6 360E*05 6.360E+05 6.360E+05 6.360E+05 6 360E+05 6 360E+05 6 360E+05 ' ' RU 100 4 210E+08 4 210E+08 4 210E+08 4 210E+08 4 210E+08 4 210E+08 4.210E+08 RH-103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RH 106 0 000E+00 0.000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E*00 0 000E+00 AG-110M 3 470E+09 3 470E+09 3 470E +09 3 470E+09 3 470E+09 3 470E+09 3 470E+09 SB-122 1070E +07 1.070E+07 1070E+07 1.070E +07 1.070E +07 1070E +07 1.070E+07 l T E-125M 1.550E+06 1.550E+06 1.550E+06 1.550E +06 1.550E+06 1.550E +06 ' 1.550E*06 TE-12'7M 9170E+04 9.170E+04 9.170E +04 9.170E +04 9.170E +04 9170E +04 9.170E +04 TE 127 3 000E*03 3 000E+03 3 000E+03 3 000E+03 3 000E+03 3 000E+03 3 000E +03 TE 129M 2 000E+07 2 000E+07 2.000E +07 2.000E+07 2 000E+07 2 000E+07 2.000E+07 " TE 129 2 600E+04 2 600E+04 2 600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 p t TE 131M 8 030E+06 8 030E+06 8 030E+06 8 030E+06 8 030E +06 8 030E+06 8 030E+06
'n TE 131 2 930E+04 2 930E+04 2 930E+04 2 930E+04 2 930E+04 2 930E+04 2 930E+04 TE-132 4 200E+06 4 220E+06 4 220E+06 4 220E+06 4.220E +06 4 220E+06 4 220E+06 6-130 5 530E+06 5 530E+06 5 530E+06 5 530E+06 5 530E+06 5 530E+06 5 530E+06 1-131 1.720E+07 1.720E +07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 l132 1.240E +06 1.240E+06 1.240E+06 1.240E +06 1240E+06 1240E+06 1.240E +06 I-133 2 470E+06 2.470E+06 2.470E+06 2 470E+06 2.470E +06 2 470E+06 2.470E+06 l-134 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 490E+05 4 490E+05 l-135 2.560E +06 2 560E+06 2 500E+06 2 560E+06 2.560E+06 2.560E +06 2.560E +06 CS 174 6 750E+09 u750E+09 6.750E+09 6 750E+09 6.750E+09 6.750E+09 6.750E+09 CS*36 1490E+08 1.490E+08 1.400E+08 1.490E+08 1,490E+08 1.490E +08 1 490E+08 CS-137 1.040E +10 1.040E +10 1.040E +10 1.040E+10 1.040E + 10 1.040E+10 1040E+10 CS-138 3 590E+05 3.590E+05 3 590E+05 3 590E+05 3 590E+05 3 590E+05 3.590E+05 BA 139 1.060E +05 1.060E+05 1.060E+05 1.000E+05 1.060E+05 1.060E+05 1.060E+05 BA 140 2 050E+07 2 050E *07 2.050E+07 2.050E+07 2.050E+07 2 050E+07 2.050E+07 BA 141 4180E +0 t 4.180E+04 4180E+04 4180E+04 4.180E +04 4.180E+04 4.180E +04 BA-142 4 490E+04 4 490E*04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 4 490E+04 LA-140 1.910E +07 1.910E+07 1910E+07 1910E+07 1.910E +07 1910E+07 1.910E +07 LA-142 7.360E+05 7.360E +05 7.360E +05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E +07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 CE-143 2 320E+06 2.320E+06 2.320E*06 2 320E+06 2.320E+06 2 320E+06 2 320E +06
Offsits Doss Calculation Manual Page 262 of 313 Revision 2 Change O Attachment 12 Gaseous Effluent Pathway Dose Factors Os GROUND PLANE DOSE FACTORS INFANT (m2* mrem /yr per utilsec) rvuclide Bone Liver Tbody Thyroid Kidney Lung Ottract CE-144 6 950E+07 6 950E +07 6 950E+07 6 950E+07 6 950F+07 6 950E+07 6 950E+07 PR 143 0.000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 PR 144 1.830E +03 1.830E+03 1.830E+03 1.830E *03 1.830E+03 1.830E+03 1.830E +03 ND-147 0400E+00 8.400E*06 8 400E+06 8 400E+06 8 400E+06 8 400E+06 8 400E+06 EU-154 2.700E+10 2.700E +10 2.700E+10 2.700E +10 2.700E+10 2.700E+10 2.700E+10 EU 155 9 570E+08 9 570E+08 9.570E+08 9 570E+00 9.570E+08 9 570E+08 9 570E+08 W 187 2 360E +06 2.360E +06 2 360E+06 2.360E +06 2.360E+06 2.360E+06 2.360E+06 NP 239 1.710E+06 1.710E +06 1.7t 0E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 m *W O
Offsh) Dose Calcul: tion Minu:1 Page 263 of 313 j Revision 2 Change 0 g Attachment 12 i Gaseous Effluent Pathway Dose Factors b' INHALATION DOSE FACTORS ADULT (mrem /yr per uCl/mi Nuchde Bone Liver Tbody Thyroid Kidney Lung Gttract H-3 0 000E+00 1.200E+03 1.260E+03 1.200E+03 1.260E+03 1.260E+03 1.260E+03 C 14 1.820E +04 3 410E+03 3 410E+03 3 410E+03 3 410E+03 3.410E+03 3.410E+03 NA 24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 P 32 1.320E+06 7.710E+04 5 010E+04 0 000E+00 0.000E+00 0 000E+00 8 640E+04 ' CR 51 0 000E+00 0.000E+00 1.000E+02 5 950E+01 2.280E+01 1.440E+04 3.320E+03 MN44 0 000E +00 39GOE+04 6 300E+03 0 000E+00 9 840E+03 1.400E+06 7.740E +04 MN46 0 000E+00 1.240E +00 1.830E 01 0 000E+00 1.300E +00 9 440E+03 2 020E+04 FE45 2 460E+04 1.700E +04 3 940E+03 0 000E+00 0 000E +00 7.210E+04 6 030E+03 FE49 1.18CZ+04 2.780E+04 1.060E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 2 CO-57 0 000E+00 6 920E+02 6 710E+02 0.000E +00 0 000E+00 3.700E+0 i 3.140E+04 CO48 0 000E+00 1.580E+03 2.070E+03 0 000E+00 0.000E+00 9 280E+05 1.060E+05 CO-60 0 000E+00 1.150E +04 1.480E+04 0 000E+00 0 000E +00 5 970E+06 2.850E +05 NI-63 4 320E +05 3140E+04 1.450E+04 0 000E+00 0.000E+00 1.780E+05 1.340E+0e N145 1.540E+00 2100E-01 9120E 02 0 000E+00 0 000E+00 5.600E+03 1230E+04 Q CU44 0 000E+00 1.4GOE+00 6150E 01 0 000E+00 4 620E+00 6 780E+03 4 900E+04 ZN45 3 240E+04 1.030E+05 4 660E+04 0 000E+00 6.900E+04 8 640E+05 5 340E+04 ZN49 3 380E-02 6 510E-02 4 520E 03 0 000E+00 4 220E-02 9 200E+02 1.630E +01 B R-82 0 000E+00 0 000E+00 1.350E+04 0 000E+00 0 000E+00 0 000E+00 1.040E+04 BR 83 0 000E+00 0 000E+00 2 410E+02 0 000E+00 0.000E+00 0 000E+00 2.320E +02 BR-84 0 000E+00 0 000E+00 3130E+02 0 000E+00 0.000E +00 0 000E+00 1.640E-03 BR 85 0 000E+00 0 000E+00 1.280E +01 0 000E+00 0 000E+00 0.000E+00 0 000E+00 RB46 0 000E+00 1.350E+05 5 900E+04 0 000E+00 0.000E+00 0.000E+00 1.660E+04 RB48 0 000E +00 3 870E+02 1.930E+02 0 000E+00 0 000E+00 0 000E+00 3.340E-09 RB-89 0 000E+00 2 560E+02 1.700E+02 0 000E+00 0 000E+00 0 000E+00 0 000E +00 SR-89 3 040E+05 0 000E+00 8 720E+03 0 000E+00 0 000E+00 1400E+06 3 500E+05 SR 90 9920E+07 0 000E+00 6.100E +06 0 000E+00 0.000E+00 9600E+06 7.220E+05 SR 91 6.190E+0i 0 000E+00 2.500E+00 0 000E+00 0 000E+00 3 650E+04 1.910E+05 SR 92 6 740E+00 0 000E+00 2 910E-01 0 000E+00 0 000E+00 1.650E+04 4 300E+04 Y-90 2.090E +03 0 000E +00 5 610E+01 0 000E+00 0 000E +00 1.700E+05 5 060E+05 Y-91M 2.610E-01 0 000E+00 1.020E-02 0 000E+00 0.000E+00 1.920E+03 1.330E+00 Y-91 4 620E +05 0 000E+00 1.240E+04 0 000E+00 0 000E+00 1.700E+06 3 850E+05 Y-92 1.030E*01 0 000E+00 3 020E-01 0 000E+00 0 000E+00 1.570E +0* 7.350E +04 Y 93 9 440E+01 0 000E +00 2.610E+00 0 000E+00 0 000E+00 4 850E+04 4 220E+05 ZR 95 1070E+05 3 440E+04 2.330E+04 0.000E+00 5 420E+04 1.770E+06 1.500E +05 ZR-97 9 680E+01 1960E+01 9 040E+00 0 000E+0c 2970E+01 7.870E+04 5 230E+05 l i l
Offsits Dose Calcul: tion Manual P.-%e 264 of 313 Revision 2 Change 0 l g Attachment 12 ( Gaseous Effluent Pathway D0s0 Factors INHALATION DOSE FACTORS ADULT (mrem /yr per uCl/mi Nuchde Bone Liver Tbody Thyroid Kidney Lung Gitract NB-95 1.410E+04 7.820E +03 4 210E+03 3 000E+00 7.740E+03 5 050E+05 1.040E+05 NB-97 2 220E-01 5 620E 02 2.050E-02 0 000E +00 6.540E 02 2.400E+03 2 420E+02 MO-99 0 000E+00 1.210E +02 2 300E+01 0.000E+00 2.910E+02 9120E+04 2.480E+05 TC-IDM 1.030E 03 2 910E 03 3.700E-02 0 000E+00 4 420E 02 7.640E +02 4160E+03 - TC 101 4180E 05 6 020E 05 5 900E-04 0.000E+00 1.000E-03 3 990E+02 0.000E+00 RU-103 1.530E*C3 0 000E+00 6 580E+02 0 000E+00 5 830E+03 5 050E+05 1.100E +05 RU-105 7.000E-01 0 000E+00 3110E-01 0 000E+00 1.020E+00 1.100E+04 4 820E + 04 RU-106 6 910E+04 0 000E+00 8.720E+03 0.000E+00 1.340E +05 9 360E+06 3120E+05 RH 103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RH 106 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 0 000E+0D 0000E+00 AG-110M 1080E+04 1000E +04 5940E+03 0 000E+00 1.970E +04 4 630E+06 3 020E+05 SD 122 3.100E +03 4110E+03 4110E+04 1.070E+03 1.550E+03 1670E+05 2 020E+05 l SB-124 3120E+04 5 890E+02 1.240E+04 7.550E+01 0 000E+00 2.480E +06 4 060E+05" SB 125 5 340E+04 5 950E+02 1260E+04 5400E+01 0 000E+00 1.740E+06 1.010E +05 TE 125M 3 420E+03 1.580E+03 4 670E+02 1.050E +03 1.240E +04 3140E+05 7.060E +04 TE 127M 1.260E+04 5.770E+03 1.570E+ 03 3 290E+03 4 580E+04 9 600E+05 1.500E +05 TE 127 1400E *00 6 420E 01 3100E 01 1.060E +00 5.100E+00 6 510E+03 5 740E+04 TE-129M 9 760E+03 4 070E+03 1.580E +03 3 440E+03 3 660E+04 1 160E+06 3 830E+05 TE 129 4 f 80E-02 2 300E-02 1240E 02 3 900E 02 1.870E 01 1940E+03 1.570E +02 TE 131M 6 9%E+01 4.360E +01 2.900E+01 5 500E+01 3 090E+02 1.460E+05 5 560E+05 TE-131 1 110E-02 5 950E 03 3 590E-03 9 360E 03 4 370E 02 1.390E +03 1840E +01 TE-132 2 600E+02 2.150E+02 1.620E +02 1.900E+02 1.460E+03 2 880E+05 5100E+05 l130 4 580E +03 1.340E +04 5280E+03 1 140E+06 2 090E+04 7.690E +03 0 000E+00 1131 2.520E +04 3 680E+04 2.050E+04 1.190E+07 6130E+04 0 000E+00 6 280E+03 l-132 1.160E +03 3 260E+03 1.160E+03 1.140E+05 5.180E+03 0 000E+00 4 060E+02 1133 8 640E+03 1.480E +04 4 520E+03 2.150E+06 2.580E+04 0 000E+00 8 880E+03 1,134 6 440E+02 1.730E+03 6150E+02 2 980E+04 2.750E +03 0 000E+00 1010E+00 1135 2 680E+03 6 D80E+03 2.570E+03 4 480E+05 1.110E+04 0.000E +00 5 250E +03 CS 134 3.730E +05 8 480E+05 7.280E+05 0 000E+00 2.870E +05 9.760E+04 1.040E+04 CS-136 3 900E+04 1.460E+05 1.100E+05 0.000E +00 8560E+04 1.200E+04 1.170E+04 CS-137 4 780E +05 6.210E+05 4 280E+05 0 000E+00 2.220E+05 7.520E+04 8 400E+03 CS-138 3.310E+02 6 210E+02 3.240E+02 0 000E+00 4 800E+02 4 860E+01 1.860E-03 BA 139 9 360E 01 6 660E-04 2 740E-02 0.000E+00 6.220E 04 3 760E+03 8960E+02 {
\
BA 140 BA 141 3 900E+04 1.000E-01 4 900E+01 7.530E-05 2.570E +03 3 360E-03 0 000E+00 0 000E +00 1.670E+01 7.000E 05 1270E 106 1.940E+03 2.180E +05 1.160E 07 ,
Offsite Dose Calculation Manual Page 265 of 313 Revis10n 2 Change 0 I Attachment 12 Gaseous Efouent Pathway D0se Factors INHALATION DOSE FACTORS ADULT (mrem /yr per uCi/m') Nuchde Bone Liver Tbody Thyroid Kidney Lung Gltract BA-142 2 630E-02 2.700E-05 1.660E 03 0 000E+00 2 290E 05 1.190E+03 0.000E +00 LA 140 3 440E*02 1.740E*02 4 580E+01 0 000E+00 0 000E+00 1.360E+05 4 580E+05 LA-142 6 830E 01 3.100E-01 7.720E-02 0.000E+00 0 000E+00 6.330E+03 2.110E+03 CE 141 I M0E+04 1.350E +04 1.530E+03 0 000E +00 6 260E+03 3 620E+05 N E+05' CE 143 1.860E +02 1.380E +02 1.530E+01 0 000E+00 6 080E+01 7.980E+04 2.260E +05 CE 144 3 430E+06 1.430E+06 1.840E +05 0 000E+00 8480E+05 7.780E +06 8.160E +05 PR 143 9 360E+03 3 750E+03 4 640E+02 0 000E+00 2.160E+03 2.810E+05 2 000E+05 PR 144 3 010E-02 1.250E-02 1.530E-03 0 000E+00 7.050E 03 1.020E+03 2.150E48 ND-147 5 270E+03 6.100E +03 3 o60E+02 0 000E+00 3 560E+03 2.210E+05 1.730E +05 EU 154 5 920E+06 7.280E +05 5180E+05 0.000E+00 3 490E+06 4 670E+0D 2 720E+05 EU 155 8 080E+05 1.140E+05 7.370E +04 0.000E +00 5 270E+05 7.570E +05 4 760E +04 W 187 8 480E+00 7.080E+00 2 480E+00 0.000E+00 0 000E+00 2.900E+04 1.550E +05 NP-239 2 300E+02 2 260E+01 1240E+01 0 000E+00 7.000E+01 3 760E+04 1.190E + 05^ l
Offsita Dose C Iculat10n M:nual P:g3 266 of 313 Revision 2 Change 0
- Attachment 12 74 Gaseous Effluent Pathway D0se Factors (v) INHALATION DOSE FACTORS TEEN (mrem /yr per uCi/mD Nuchde Bone Uver Tbody Thyroid Kidney Lung Gitract H-3 0 000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.770E+03 1.270E+03 C-14 2.600E+04 4 870E+03 4 870E+03 4 870E+03 4.870E+03 4 870E+03 4 870E+03 NA 24 1.380E+04 1.380E +04 1.380E+04 1.380E+04 1.380E+04 1,380E+04 1.380E +04 P-32 1.890E +06 1.100E +05 7.160s.+04 0 000E+00 0 000E+00 0 000E+00 9 680E+04 -
CR 51 0 000E+00 0.000E+00 1.350E+02 7.500E+01 3 070E+01 2.100E+04 3 000E+03 MN 54 0.000E+00 5110E+04 8 400E+03 0 000E+00 1.270E+04 1.980E+06 6 680E+04 MN-50 0 000E*00 1.700E *00 2 520E 01 0 000E+00 1.790E +00 1.520E+04 5.740E+04 FE S5 3 340E*04 2.380E+04 5 540E+03 0 000E+00 0 000E +00 1.240E+05 6 390E +03 FE 59 1590E+04 3 700E+04 1.430E+04 0.000E+00 0 000E+00 1.530E +06 1,780E+05 CO-57 0 000E+00 6 920E+02 9.200E+02 0.000E+00 0.000E+00 5.860E+05* 3.140E+04 CO-58 0 000E+00 2.070E+03 2.780E +03 0 000E+00 0.000E +00 1.340E+06 9 520E+04 CO-60 0 000E +00 1.510E +04 1.980E +04 0 000E+00 0.000E +00 8.720E+06 2 590E+05 N143 5 800E+05 4 340E+04 1.980E +04 0.000E+00 0 000E +00 3 070E+05 1.420E+04 ~~ NI-65 2.180E +00 2 930E-01 1.270E 01 0 000E+00 0.000E+00 9.360E+03 3 670E+04 CU 64 0 000E+00 2 030E+00 8 480E.01 0 000E+00 6 410E+00 1.110E +04 6140E+04 ('N ZN 65 3 860E+04 1.340E +05 6 240E+04 0 000E+00 8.640E+04 1.240E+06 4 660E+04 ZN49 4 830E-02 9 200E-02 6 460E 03 0 000E +00 6 020E.02 1580E+03 2 850E+02 BR42 0 000E+00 0 000E +00 1820E+04 0.000E +00 0 000E+00 0.000E+00 0 000E+00 BR 83 0 000E+00 0 000E+00 3 440E+02 0 000E+00 0.000E+00 0 000E+00 0 000E +00 BR44 0 000E+00 0 000E+00 4 330E+02 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0R45 0 000E*00 0 000E+00 1,830E +01 0 000E+00 0.000E+00 0 000E+00 0 000E+00 R B-88 0.000E+00 1.900E+05 8 400E+04 0.000E +00 0 000E+00 0.000E +00 1.770E+04 RB48 0.000E+00 5.460E+02 2.720E+ 92 0 000E+00 0.000E +00 0.000E+00 2 920E-05 R B-89 0 000E+00 3 520E+02 2 330Eo 0 000E+00 0.000E+00 0 000E+00 3 360E 07 SR 89 4 340E+05 0 000E+00 1250E+04 0 000E +00 0 000E+00 2 420E+06 3.710E+05 SR 90 1.080E +08 0 000E+co 6.680E+06 0 000E+00 0 000E +00 1.650E+07 7.650E +05 SR-91 8800E+01 0 000E+00 3 510E+00 0 000E+00 0.000E+00 6 070E+04 2 590E+05 SR-92 9 520E+00 0 000E+00 4 060E 01 0 000E+00 0 000E+00 2.740E+04 1.190E+05 Y-90 2.980E +03 0 000E+00 8 ')00E+01 0 000E+00 0 000E+00 2.930E+05 5 590E+05 Y 91M 3 700E 01 0 000E+00 1 420E-02 0 000E+00 0 000E+00 3 200E+03 ~1020E+01 Y-91 6.610E +05 0 000E+00 1.770E+04 0.000E+00 0 000E+00 2.940E+ 06 4 090E+05 Y 92 1.470E+01 0 000E+00 4 290E-01 0 000E+00 0 000E+00 2.680E+04 1.650E+05 Y-93 1.350E+02 0.000E+00 3.720E+00 0 000E+00 0.000E+00 B320E+04 5 790E+05 A ZR-05 1.400E *05 4 580E+04 3150E+04 0 000E+00 6.740E+04 2 690E+0G 1490E+05 I b (/ ZR 97 1.380E+02 2.720E +01 1.260E+01 0 000E +00 4120E +01 1.300E +05 6 300E +05
Offsita D0s3 Ccicut: tion Minuit P:ge 267 Of 313 Revision 2 Change O fm Attachment 12 ( ) Gaseous Effluent Pathway D0se Factors V INHALATION DOSE FACTORS TEEN (mrem /yr per uCl/m ) Nuchde Bone uver Tbody Thyroid Kidney Lung Gttract ND-95 1.860E+04 1.030E+04 5 660E+03 0 000E+00 1.000E *04 7.510E+05 9 680E*04 N B-97 3140E41 7.780E-02 2 840E-02 0 000E+00 9120E 02 3.930E+03 2.170E +03 MO49 0 000E+00 1.690E+02 3 220E+01 0 000E+00 4110E+02 1.540E+05 2 690E+05 TC-99M 1.380E43 3 860E 03 4 990E-02 0 000E+00 5.760E-02 1.150E +03 6130E+03 - TC-101 5 920E-05 8 400E-05 8 240E-04 0 000E+00 1.520E-03 6 670E+02 8 720E-07 RU-103 2.100E +03 0 000E +00 8 960E+02 0 000E+00 7.430E +03 7.830E +05 1.090E +05 RU 105 1.120E +00 0 000E+00 4 340E-01 0 000E+00 1.410E+00 1.820F +04 9 040E+04 RU.106 9 840E+04 0 000E+00 1.240E +04 0 000E +00 1900E+05 1610E+07 9 600E+05 RH 103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 RH-106 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0.000E+00' O000E.+00 AG 110e i 1.380E+04 1.310E+04 7.900E +03 0 000E+00 2.500E+04 6 750E+06 2.730E +05 SB 122 3100E+03 4110E+03 4.110E+04 1070E +03 1550E+03 1.670E+05 2.020E +05 l SB 124 4 300E+04 7.940E+02 1680E+04 9 760E+01 0 000E +00 3 850E+00 3 980E+05 "
$8125 7.380E+04 8 080E+02 1.720E +04 7.040E +01 0 000E+00 2.740E+06 9 920E+04 Q TE 125M 4 880E+03 2 240E+03 6 670E+02 1400E +03 0 000E+00 5 360E+05 7.500E +04 d TE 127M 1.800E+04 8.160E+03 2.180E +03 4 380E+03 6 540E+04 1.660E+06 1.590E +05 TE 127 2.010E+00 9120E 01 4 420E-01 1.420E +00 7.280E+00 1 120E +04 8 080E+04 TE-129M 1.390E +04 6 580E+03 2 250E+03 4 580E+03 5190E+04 1.980E +06 4 050E+05 TE-129 7.100E-02 3.380E-02 1.760E-02 5.180E 02 2.660E-01 3 300E+03 1.620E+03 TE 131M 9 840E+01 6 010E+01 4 020E+01 7.250E +01 4 390E+02 2.380E+05 6 210E+05 TE 131 1.580E 02 8 320E 03 5 040E 03 1.240E 02 6.180E-02 2.340E+03 1.510E+01 TE 132 3 600E+02 2.900E+02 2.190E +02 2.460E+02 1.050E +03 4 490E+05 4 630E+05 l130 6 240E+03 1.790E+04 7.170E +03 1.490E +06 2.750E+04 0 000E+00 9120E+03 1131 3 540E+04 4 910E+04 2.640E+04 1.460E +07 8.400E +04 0 000E+00 6 490E+03 4132 1.590E +03 4 380E+03 1.580E+03 1510E+05 6 920E+03 0 000E+00 1.270E+03 1133 1.220E+04 2.050E+04 6 220E+03 2 920E+06 3 590E+04 0 000E +00 1.030E+04 1134 8880E+02 2.320E +03 8 400E+02 3 950E+04 3.660E +03 0 000E+00 2.040E+01 l-135 3.700E +03 9 440E +03 3 490E+03 6.210E +05 1.490E+04 0 000E+00 6 950E+03 CS-134 5.020E+05 1.130E*06 5 490E+05 0.000E +00 3.750E+05 1.460E+05 9 760E+03 CS-136 5150E+04 1,940E+05 1.370E+05 0 000E+00 1.100E+05 1.780E+04 1.090E+04 CS-137 6.700E +05 8 480E+05 3110E+05 0 000E+00 3 040E+05 1.210E +05 8 480E+03 CS 138 4 660E+02 8 560E*02 4 460E+02 0.000E+00 6 620E +02 7.870E+01 2.700E 01 BA 139 1.340E+00 9 440E-04 3 900E-02 0 000E+00 8 880E 04 6 460E+03 6 450E+03 f'N BA 140 5 470E+04 6.700E+01 3 520E+03 0 000E+00 2 280E+01 2.030E+06 2.290E+05 B A 141 1420E 01 1.060E-04 4 740E 03 0 000E+00 9 840E-05 3 290E+03 7 460E 04
Offsite D0se Calculation Manual Page 268 Of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS TEEN (mrem /yr per uCi/mD Nuchde Bone Uver Tbody Thyroid K6dney Lung Gttract BA 142 3 700E 02 3.700E-05 2 270E-03 0.000E+00 3.140E-05 1910E+03 0 000E+00 LA 140 4 790E+02 2 360E*02 6 260E+01 0 000E+00 0 000E+00 2140E+05 4 870E+05 LA 142 9 600E41 4 250E-01 1060E-01 0 000E+00 0.000E+00 1.020E+04 1.200E +04 CE 141 2 840E +04 1.900E +04 2.170E+03 0 000E+00 8B80E+03 6.140E+05 1.260E+05 - CE 143 2 600E+02 1.940E +02 2.160E+01 0 000E+00 8.640E+01 1.300E+05 2.550E+05 CE 144 4 690E+06 2 020E+06 2 620E+05 0 000E +00 1.210E+06 1.340E+07 8 640E+05 PR-143 1.340E +04 5 310E+03 6 620E+02 0 000E+00 3 090E+03 4 830E+05 2.140E+05 PR 144 4 300E 02 1,760E-02 2180E-03 0 000E+00 1.010E-02 1.750E+03 2 350E-04 ND-147 7.860E *03 8 560E+03 5130E+02 0 000E+00 5 020E+03 3.720E +05 1.820E+05 EU 154 7 540E+06 9 840E+05 6 880E+05 0 000E+00 4 350E+06 7.300E +06
- 2.670E+05 EU-155 1000E +06 1.570E+05 9 680E+04 0 000E+00 6120E+05 1.210E+07 4.780E +05 W 187 1.200E+01 9 760E+00 3 430E+00 0 000E+00 0.000E+00 4.740E+04 1.770E+05 N P-239 3 380E +02 3190E+01 1.770E+01 0.000E+00 1.000E+02 6 490E+04 1.320E+05 "
Offsit3 Dose C:lcul: tion Manu:1 Pag 3 269 Of 313 f Revision 2 Change 0
- Attachment 12
( Gaseous Effluent Pathway D0se Factors b INHALATION DOSE rMCTORS CHILP (mrem /yr per uCl/m*) Nuclide Bone Liver Tbody Thyroid Kidney Lung citract H3 0 000E+00 1.120E +03 1.120E +03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 C-14 3 590E+04 6.730E+03 6 730E+03 6 730E+03 6.730E+03 6 730E+03 6 730E +03 NA 24 1.610E+04 1610E+04 1.610E +04 1.610E+04 1.610E+04 1.610E+04 1.610E +04 P 32 2 600E *06 1.140E* 05 9 880E+04 0 000E+00 0 000E+00 0.000E +00 4 220E+04 - CR-51 0 000E+00 0 000E+00 1.540E +02 8.550E+01 2 430E+01 1.700E+04 1.080E+03 MH-54 0 000E+00 4 290E+04 9 510E+03 0 000E+00 1.000E+04 1.580E +06 2.290E+04 MN56 0 000E+00 1.660E+00 3120E-01 0 000E+00 1670E+00 1.310E+04 1.230E +05 F E-55 4 740E+04 2 520E+04 7.770E +03 0.000E+00 0 000E+00 1.110E+05 2 870E+03 FE 59 2.070E +04 3 340E+04 1670E+04 0 000E+00 0.000E+00 1.270E+06 7.070E +04 CO 57 0 000E+00 9 030E+02 1.070E+03 0000E+00 0 000E+00 5.070E+05 1.320E+04 CO 58 0 000E+00 1.770E+03 3160E +03 0 000E+00 0 000E+00 1.110E +06 3 440E+04 CO-60 0 000E+00 1.310E+04 2 260E+04 0 000E+00 0 000E+00 7.070E+06 9 620E+04 NI-63 8 210E *05 4 630E +04 2.800E+04 0.000E +00 0 000E+00 2.750E +05 6.330E+03 ~ Ni-65 2 900E+00 2 960E-01 1.640E-01 0 000E+00 0 000E+00 8180E+03 8.400E+04 p CU-64 0 000E+00 1990E +00 1.070E+00 0 000E+00 6 030E+00 9 580E+03 3 670E+04 5 ZN-65 7.030E+04 0 000E+00 7.140E+04 9 950E+05 1630E +04 4 260E+04 1.130E +05 ZN 69 6 700E-02 9 6SOE-02 8 920E 03 0 000E+00 5 850E-02 1.420E+03 9 510E+03 0R 82 0 000E+00 0 000E+00 2 090E+04 0.000E +00 0 000E+00 0 000E+00 0 000E +00 DR-83 0 000E+00 0 000E+00 4 740E+02 0 000E+00 0 000E +00 0 000E+00 0OCOE+00 BR-84 0 000E+00 0 000E+00 5 480E+02 0 000E+00 0 000E+00 0 000E+00 0.000E +00 BR 85 0 000E+00 0 000E +00 2 530E+01 0.000E+00 0.000E+00 0.000E+00 0 000E+00 RB 86 0 000E+00 1980E+05 1 140E+05 0 000E+00 0.000E+00 0 000E+00 7.990E +03 R B-08 0 000E+00 5 620E+02 3 660E+02 0 000E +00 0.000E +00 0 000E+00 1.720E +01 RB-89 0 000E+00 3 450E+02 2 900E+02 0 000E+00 0 000E+00 0 000E+00 1.890E +00 SR49 5 990E+05 0 000E+00 1.720E +04 0 000E+00 0.000E +00 2.160E +06 1670E+05 SR 90 1.010E+0S 0 000E+00 6 440E +06 0 000E+00 0 000E+00 1.480E+07 3 430E+05 GR 91 1.210E +02 0 000E +00 4 590E+00 0.000E +00 0 000E+00 5.330E+04 1740E +05 SR 92 1.310E +01 n 000E+00 5 250E-01 0 000E+00 0 000E+00 2 400E+04 2 420E+05 Y 90 4110E+03 0 000E+00 1.110E+02 0 000E+00 0 000E+00 2.620E+05 2680E+05 Y-91M 5 070E-01 0.000E +00 1.840E 02 0 000E+00 0 000E+00 2.810E+03 1.720E+03 Y 91 9.140E +05 0 000E+00 2.440E +04 0 000E+00 0 000E +00 2 630E+06 1.840E +05 Y-92 2 040E+01 0 000E+00 5 810E 01 0 000E+00 0.000E+00 2 390E+04 2.390E +05 Y-93 1.860E +02 0 000E+00 5110E+00 0 000E+00 0 000E+00 7.440E+04 3 890E+05 ZR 95 1.900E +05 4180E+04 3.700E+04 0 000E+00 5 960E+04 2.230E+06 6110E+04 V
Offsite Dose Calculation Manual Page 270 of 313 l Revision 2 Change O Attachment 12 Gaseous Effluent Pathway Dose Factors C INHALATION DOSE FACTORS CHILD (mrem /yr per uCi/m') Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR-97 1.880E+02 2.720E +01 1.600E +01 0 000E+00 3 890E+01 1.130E +05 3.510E+05 NB 95 2.350E +04 9.180E+03 6 550E+03 0 000E+00 8 620E+03 6140E*05 3 700E+04 NB-97 4 290E-01 7.700E 02 3 600E-02 0 000E+00 8 550E-02 3 420E+03 2.780E+04 MO-99 0 000E+00 1.720E + 02 4 260E+01 0 000E+00 3 920E+02 1.350E +05 1270E+05 - TC 99M 1.780E 03 3 480E 03 5.770E 02 0 000E+00 5.070E-02 9510E+02 4 810E+03 TC-101 8100E-05 8 510E-05 1.080E-03 0.000E+00 1.450E-03 5.850E+02 1.630E+01 RU 103 2 790E+03 0 000E +00 1.070E+03 0 000E+00 7.030E +03 6 620E+05 4 480E+04 RU 105 1.530E +00 0 000E+00 5 550E-01 0 000E+00 1.340E +00 1.590E +04 9 950E+04 RU 106 1.360E+05 0 000E+00 1.690E+04 0 000E+00 1.840E+05 1.430E+07 4 290E+05 RH-103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 RH 106 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 AG 110M 1690E+04 1.140E+04 9140E+03 0 000E+00 2120E+04 5 480E+06 1.000E+05 SB-122 1.440E+03 1.980E+03 1.900E +04 4 960E+02 7.180E+02 7.730E +04 9 360E+04 - l SB 124 5 740E+04 7.400E +02 2 000E+04 1.260E +02 0 000E+00 3.240E +06 1.640E + 05 SB 125 9 840E+04 7 590E+02 2 070E+04 9100E+01 0 000E+00 2 320E+06 4 030E +04
\ TE 125M 6 730E+03 2 330E+03 9140E + 02 1920E+03 0 000E+00 4 770E+05 3 380E+04 TE 127M 2 490E+04 8 550E+03 3 020E+03 6070E+03 6.360E+04 1430E+06 7.140E+04 TE 127 2.770E+00 9 510E 01 6110E-01 1.960E +00 7.070E +00 1000E +04 5 620E+04 TE 129M 1.920E+04 6 850E+03 3 040E+03 6.330E +03 5 030E+04 1.760E+06 1.820E +05 TE 129 9,770E-02 3 500E 02 2.380E-02 7.140E-02 2.570E-01 2 930E+03 2 550E+04 TE.t 31M 1 340E+02 5 920E+01 5 070E+01 9 770E+01 4 000E+02 2 060E+05 3 080E+05 TE 131 2170E 02 8 440E-C3 6 590E-03 1.700E42 5 880E-02 2 050E +03 1.330E+03 TE 132 4 810E+02 2.720E +02 2 630E+02 3170E +02 1840E+03 3 770E+05 1380E+05 l130 8180E+03 1.640E+04 8 440E+03 1.850E+06 2.450E+04 0 000E+00 5.110E+03 1131 4 810E+04 4 810E+04 2 730E +04 1.620E+07 7.880E +04 0 000E+00 2 840E+03 l-152 2.120E +03 4 070E+03 1.880E +03 1.940E +05 6.250E+03 0 000E+00 3 200E+03 b133 1.660E+04 2 030E+04 7.700E+03 3 850E+06 3 380E+04 0 000E+00 5 480E+03 1-134 1.170E+03 2.160E+03 9 950E +02 5 070E+04 3 300E+03 0 000E+00 9.550E+02 b135 4 920E+03 8 730E+03 4140E+03 7 920E+05 1.340E +04 0 000E+00 4 440E+03 CS-134 6 510E+05 1.010E+06 2 250E+05 0 000E+00 3.300E+05 1210E+05 3 850E+03 CS 136 6 510E+04 1 710E +05 1.160E+05 0 000E+00 9 550E+04 1.450E +04 4180E+03 CS-137 9070E+05 8250E+05 1.280E +05 0 000E+00 2.820E+05 1OGE+05 3 620E+03 CS-138 6 330E+02 8 400E+02 5 550E+02 0 000E+00 6 220E+02 6 810E+01 2.700E+02 p BA 139 1.840E +00 9 840E-04 5.370E-02 0 000E+00 8 620E-04 5770E+03 5.770E+04 5 B A 140 7 400E+04 6 480E+01 4 330E+03 0 000E+00 2110E+01 1.740E +06 1.020E+05 l
. - .. ~ - . . - . - - . - . _ . . - . - . . . -
.; Offsita Dose Cakulation Manual Paga 271 of 313 Revision 2 Change O'
+
Attachment 12
- Gaseous Effluent Pathway Dose Factors s _./ INHALATION DOSE FACTORS ,
CHILD (mrem /yr per uCi/m')- Nuclide ' Sone 1.lver Thody Thyroid Midney Lung Gltract B A-141 1.900E41 ~ 1.000E o4 6.360E-03 0.000E+00 9 470E 05 2.920E+03 2.750E+02
- BA 142 5.000E42 3 600E45 2.790E-03 0.000E+00 2.910E-05 1.640E+03 2.740E+00 LA 140 - 6.440E+02 - 2.2COE+02 7.550E +01 0.000E+00 0.000E+00 ' 1.830E+05 2.260E+05 LA-142 1.300E+00 4110E-01 1.290E 01 0 000E+00 - 0.000E+00 8.700E+03 7.590E+04 -
CE 141 3.920E+04 1.950E+04 2.900E+03 0.000E+00 8.S$0E+03 5.440E+05 5060E+04 CE 143 3 660E+02 1.990E+02 2.870E+01 0 000E+00 8.360E+01 1.150E+05 1.270E+05 CE 144 6.770E+06 2.120E+06 3 610E+05 0.000E+00 1.170E+06 1.200E+07 3.890E+05 4 PR 143 1.850E+04 5.550E+03 9.140E+02 0.000E+00 3.000E+03 4J30E+05 9.730E+04 PR 144 5 960E 02 -- 1.850E42 3.000E-03 0.000E+00 9.770E43 1.570E+03 1.970E+02 ND-147 1.000E+04 8.730E+03 6 810E+02 0.000E+00 4 810E+03_ 3.280E+05 8.210E+04 EU-154 1.010E+07 9.210E+05 6400E+05 0 000E+00 4 030E+06 6.140E+06. 1.100E+05 .; . EU-155 2.070E+06 1.500E+05 1.180E+05 = 0.000E+00 5.590E+05 1.030E+06 _1.990E+05 W 187- 1.630E+01 9 660E+00 4 330E+00 0 000E+00 0.000E+00 4110E+04 9.100E+04 - NP 239 4 700E+02 3.340E+01 2.350E+01 0.000E+00 9.730E+01 5.810E+04 6 400E+04
\
4 e 4 ~ O ;
. - . . . - - -- - ~.~
)- Offsit) Dose CilCulatirn Minual - Pega 272 Of 313 R2 vision 2 Change 0 Attachment 12- i
.b Gaseous Effluent Pathway Dose Factors
. V) INHAl.ATION DOSE FACTORS INFANT-(mrem /yr per uCl/m')-
Nuclide Bone 1 tver Tbody Thyroid Kidney Lung Getract H-3 : 0.000E+00 6.470E+02 6.470E+02 - 6 470E+02 6.470E+02 6.470E+02 6.470E +02 C-14 2.650E +04 ' 5.310E+03 5.310E+03 5 310E+03 5.310E+03 5.310E+03 5.310E+03 NA 24 1.000E+04 1.060E+04 1.060E +04 1.060E+04 1.060E+04 1.000E+04 1.060E+04 P-32 2.030E *06 1.120E +05 7.740E+04 0 000E+00 - 0.000E+00 0 000E+00 - 1.610E+04 - CR51 0 000E+00 0 000E+00 8.950E+01 5.750E+01 1.320E +01 1.280E +04 3.570E+02
. MN-54 0000E+00 2.530E+04 4 900E+03 0 000E+00 4 980E+03 1.000E+06 7.060E+03 MN-56 0.000E +00 1.540E+00 2.210E 01 0.000E+00 1.100E+00 1.250E +04 7,170E+04 FE-55 1.970E +04 1.170E +04 3 330E+03 - 0 000E+00 0 000E+00 8.690E+04 1.090E +03 FE 59 1.360E +04 2.350E+04 9 480E+03 0 000E+00 0 000E+00 1.020E+06 2.480E+04 CO-57 0.000E+00 6510E+02 6 410E+02 0.000E+00 0.000E +00 3.700E+05 4 860E+03 CO-58 0 000E+00 1.220E +03 1.820E +03 0 000E+00 0 000E+00 7.770E +05 1.110E+04 C040 0.000E+00 8 020E+03 1.180E+04 0 000E+00 0.000E +00 4 510E+06 3.190E+04 N143 3 390E+05 2.040E +04 1.160E+04 0 000E+00 0.000END 2 090E+05 2.420E+03 ~
N645 2.390E *00 2.840E 01 1.230E 01 0 000E+00 0 000E+00 8.120E+03 5.010E+04 CU44 0.000E+00 1.880E+00 7.740E 01 0 000E+00 3 980E+00 9.300E+03 1.500E+04
\ ZN-65 1.930E+04 6 260E+04 - 3.110E+04 0.000E+00 3 250E+04 6 470E+05 5.140E+04 ZN 69 5 390E-02 9 670E 02 7.180E 03 0.000E+00 4 020E 02 1.470E+03 - 1.320E+04 BR42 0 000E+00 0.000E+00 1.330E+04 0 000E+00 0 000E+00 0.000E+00 0.000E+00 BR43 0 000E +00 0.000E+00 3 810E+02 0 000E+00 0.000E+00 0 000E+00 0.000E+00 BR44 0 000E+00 0 000E+00 - 4 000E+02 0.000E+00 : 0.000E+00 0.000E+00 0.000E+00 BR45 0 000E+00 0 000E+00 2.040E +01 - 0 000E+00 0.000E+00 0 000E+00 - 0 000E+00 RB46 0 000E+00 1.900E+05 8.820E+04 0 000E+00 0.000E +00 0.000E+00 3 040E+03 RB-88 0 000E+00 5.570E+02 2 870E+02 0.000E+00 0.000E+00 0.000E+00 3.3%E+02 RS49 0 000E+00 -3 210E+02 2.000E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 SR49 3980E+05 - 0 000E+00 1.140E+04 0.000E+00 0 C00E+00 2.030E +06 6.400E+04 SR 90 4 090E+07 0.000E+00 2.590E+06 0.000E+00 : 0000E+00 1.120E+07 1.310E+05 i .
SR 91 9560E+01 0 000E+00 3 460E+00 0.000E+00 0 000E+00 - 5.260E+04- 7.340E+04 - SR-92 : 1.050E+01 - 0 000E+00 3 910E 0.000E+00 0 000E+00 2.38vE+04 1.400E+05 Y 90 3 290E+03 - -- 0000E+00 . 8.820E+01 0 000E+00 - 0.000E+00. 2.690E +05 ' 1.040E+05 Y 91 M - 4 070E 0 000E+00 : - 1.390E-02 . ~ 0.000E+00 0.000E+00 2.790E +03 . 2.350E+03 Y-91 ' 5.880E+05= 0.000E+00 1.570E+04 - - 0 000E+00 0 000E+00 2.450E+06 7.030E+04 Y 92 1.640E+01 0.000E+00 - 4.610E 0 000E+00 - 0.000E+00 2.450E+04 1.270E+05 Y-93 1.500E+02 0.000E+00 4 070E+00 0 000E+00 0.000E+00 7.640E+04 1.670E+05
' ZR - 1.150E+05 . 2.790E+04 - 2.030E +04 . 0.000E+00 3.110E+04 1.750E+06 2.170E+04
( " ZR 97 - 1.500E+02 - - 2 560E+01 1.170E+01 0.000E+00 2 590E+01 1.100E+05 1.400E+05 we+ w 'n-
. Offsits Dose C lculation Manu:1 Page 273 of 313 R:vl2 ion 2 Ch:nge 0 q
Attachment 12 Gaseous Effluent Pathway D0se Factors . - INHALATION DOSE FACTORS INFANT - 8 , (mremlyr per uCi/m ) , Nuclide Bone Liver Tbody Thyroid Midney Lung Oltract NB-95 1.570E+04 6 430E+03 - 3.780E+03 0 000E+00 4.720E+03 4.790E+05 1.270E+04 NB-97 3 420E 01 7.290E 02 2.630E 02 0.000E +00 5.700E-02 3.320E +03 2.690E+04 MO-99 0 000E+00 1.650C+02 3.230E +01 0 000E+00 2.650E+02 1.3SOE+05 4 870E+04 TC 99M 1.400E 03 2.880E 03 3.720E 02 0.000E+00 3.110E-02 8.110E+02 - 2.030E+03 - , TC 101 6 510E-05 8.230E 05 8.120E 04 0.000E+00 9.790E 04 5.840E+02 - 8.440E +02 , RU 103 2 020E+03 0 000E+00 6.790E+02 0.000E+00 4.240E+03 5 520E+05 1.610E+04 4 RU 105 1.220E+00 0.000E+00 4100E 01 0 000E+00 8 990E-01 1.570E+04 4.840E +04 RU 106 8 680E+04 0.000E+00 1.090E+04 0 000E+00 1.070E+05 1.160E+07 1.640E+05
- RH 103M - 0.000E+00 0.000E+00 0 000E+00 0 000E+00 . 0.000E+00 0.000E+00 0 000E+00 RH 106 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+du OOCOE+00 5- AG 110M 9 900E+03 7.220E+03 5.000E+03 0.000E+00 1.090E +04 3.670E +06 3 300E+04 5B-122 5 430E+02 7.200E +02 7.200E+03 1.880E+02 2.720E+02 2.930E+04 3.540E +04 l
88 124 3 790E+04 5.560E+02 1200E+04 1.010E+02 0 000E+00 2.650E+06 5 910E+04 - SB 125 5.170E+04 4.770E+02 1.090E+04 6.230E+01 0.000E+00 1.640E+06 1.470E+04 3 TE 125M 4.760E +03 1.990E +03 6.580E+02 1.620E+03 0 000E+00 4 470E+05 1290E+04 } TE 127M 1.670E+04 6 900E+03 2.070E+03 4 870E+03 3.750E+04 1.310E+06 2.730E+04 TE 127 ' .2 230E+00 9 530E 01 4.890E-01 1.850E+00 4 860E+00. 1.030E+04 2 440E+04 TE-129M 1.410E+04 6 090E+03 2.230E+03 5.470E+03 3.180E+04 1680E+06 6.900E+04 t TE 129 7.880E 02 3 470E-02 1.880E-02 6.750E 02 1.750E-01 3 000E+03 2.630E +04 TE 131M - 1.070E+02 5.500E+01 3 630E+01 8 930E+01 2.650E+02 - 1.990E+05 1.190E+05 . TE-131 1.740E-02 0 220E 03 5 000E-03 1.580E 02 3.990E 02 2.060E+03 8.220E+03 TE 132 -3.720E+02 ' 2.370E+02 1.760E+02 2.790E +02 1.030E+03 3.400E+05 4 410E+04 b130 6 360E+03 1.390E +04 5.570E+03 1.600E+06 1.530E+04 0 000E+00 1.990E +03 [ 1131- _3 790E+04 4 440E+04 1.960E+04 1.480E +07 5.180E+04 0 000E+00 1060E+03 b132- 1.690E+03 3 540E+03 1.260E+03 1.690E+05 3 950E+03 0 000E+00 1.900E+03 1133. 1.320E+04 1.920E+04 5600E+03 3f60E+06 2.240E+04 0 000E+00 2.160E+03 L134 9 210E +02 - 1.880E+03 6 650E+02 4 450E+04 - 2.090E +03 0 000E+0C - 1.290E+03 1-135 . 3 860E+03 7.600E +03 2.770E +03 6.960E+05 8.470E+03 0 000E+00 1.830E+03 CS 134 3 960E+05 - 7.030E+05 7.450E+04 0.000E+00 1.900E+05 7.970E +04 -1.330E +03 CS 136 4 830E+04 ' 1.350E+05- 5.290E *04 0.000E+00 5 640E+04 1180E+04 1.430E +03 CS-137 - 5400E+05- 6.120E+05 4 550E+04 0.000E+00 1.720E+05 7.130E+04 1.330E+03
- CS 138.- 5 050E+02 7.810E+02 3 980E+02 0.000E+00 - 4.100E+02 6.540E+01 8.760E+02 I
= BA 139 1.480E+00 9 840E-04 4 300E-02 0 000E+00 - ~5.920E-04 -5950E+03- 5.100E+04
- BA 140 5 600E+04 - 5 600E+01 2.900E+03 0 000E+00 1.340E+01 1.600E+06 - 3 840E+04 Bf 141 1.570E 01 1.080E 04 4 970E 03 0 000E+00 6.500E 05 2.970E+03 4.750E+03
,,--er.+e - -c...,- . -,
Offsite DO5e CalculatiOrt Manual Page 274 of 313 Revision 2 Change 0 = Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mrem /yr per uCi/mi Nuclide Bone Liver Tbody Thyroid Kidney Lung Ottract 0A 142 3 980E-02 3 300E-05 1960E 03 0 000E+00 1.900E 05 1.550E+03 6.930E+02 LA-140 5050E+02 2 000E +02 5150E+01 0 000E+00 0 000E+00 1.680E +05 8 480E+04 LA 142 1030E+00 3 770E41 9 040E-02 0 000E+00 0 000E+00 8.220E+03 5 950E+04 CE 141 2.770E +04 1.670E *04 1.990E +03 0 000E+00 5,250E +03 5170E+05 2.160E+04 - CE 143 2 930E*02 1930E +02 2.210E+01 0 000E+00 5 640E+01 1.160E* 05 4 970E+04 CE 144 3.190E+06 1.210E+06 1.760E +05 0 000E+00 5.380E+05 9 840E+06 1.480E +05 PR-143 1.400E *04 5240E+03 6 990E+02 0 000E+00 1.970E+03 4 330E+05 3.720E +04 PR 144 4 790E42 1.850E 02 2 410E-03 0 000E+00 6 720E43 1.610E+03 4.280E+03 tm-147 7.940E +03 8130E+03 5 000E+02 0 000E+00 3150E+03 3 220E+05 3.120E+04 L U-154 4140E+06 4 640E+05 3 430E +05 0 000E +00 1 540E+06 4 270E+0B 3 980E+04 EU 155 8 300E+05 8 010E+04 4 840E+04 0 000E +00 2 210E+05 7.280E +05 7.270E+ 04 W 187 1.300E +01 0020E+00 3120E*00 0 000E+00 0 000E +00 3 0GOE+04 3 560E +04 NP 239 3 710E+02 3 320E+01 1.880E *01 0 000E+00 6 620E+01 5 950E+04 2 490E+04 -
Offsit) D0se C:lcul;tl0n Manual P:ge 275 Of 313 Revision 2 Change 0 Attachment 12 Gaseous Effluent Pathway Dose Factons V) e GRASS-COW MILK DOSE FACTORS ADULT (m 2* mrem /yr per uCl/sec) Nuclide Bone uver Tbody Thyroid Kidney Lung Gitract H3 0 000E+00 7.630E +02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 C-14 3 630E+05 7.200E+04 7.200E+04 7.200E +04 7.260E +04 7.260E+04 7.260E+04 NA 24 2 540E+06 2.540E+06 1540E+06 2.540E+06 1540E+06 2.540E +06 2.540E +06 P 32 1,710E+10 1.000E+09 C600E+08 0.000E +00 OC00E+00 0 000E+00 1920E+09 ' CR-51 0 000E+00 0 000E+00 2.860E+04 1.710E +04 6.300E+03 3 800E+04 7.200E+06 MN 54 0 000E+00 8 400E+06 1600E+06 0 000E+00 2.500E+06 0.000E+00 2.570E+07 MN-56 0 000E+00 4 230E 03 7.510E 04 0 000E+00 5 380E-03 0.000E+00 1.350E-01 FE 55 2.510E +07 1.730E+07 4 040E+06 0.000E+00 0.000E +00 9 670E+06 9.950E +06 FE 59 2 980E+07 7.000E+07 2.680E+07 0.000E+00 0 000E+00 1950E+07 2.330E+08 CO-57 0 000E+00 1.280E+06 2.130E+06 0.000E+00 0 000E+00 0 000E+Cio 3.250E+07 CO-58 0 000E+00 4 720E+06 1.060E +07 0 000E+00 0 000E+00 0 000E+00 9 570E+07 CO40 0 000E+00 1.640E +07 3 620E+07 0 000E+00 0.000E+00 0 000E+00 3.080E+08 N163 6 730E+09 4 660E+08 2.260E+08 0 000E +00 0 000E+00 0 000E+00 9 730E+07 *' N145 3 700E-01 4 810E 02 2.190E42 0.000E+00 0.000E +00 0 000E+00 1220E+00 CU 64 0 000E+00 2.410E +04 1.130E +04 0 000E+00 6 080E+04 0.000E+00 2.050E +06 ZN.65 1.370E +09 4 360E+09 1.970E +09 0 000E+00 2 920E+09 0 000E+00 2.750E +09 ZN-69 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0R42 0 000E +00 0 000E+00 0.000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 BR-83 0 000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0 000E+00 0.000E +00 BR 84 0.000E+00 0 000E+00 0 000E+00 0.000E +00 0.000E+00 0 000E+00 0 000E+00 BR 85 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 R B-86 0 000E+00 2.590E+09 1.210E+00 0 000E+00 0 000E+00 0 000E+00 5.110E+08 RB-88 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 RB-89 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 SR-89 1.450E +09 0.000E+00 4.160E+07 0 000E+00 0 000E+00 0.000E+ 00 2.330E+0S SR90 4 680E+10 0 000E+00 1.150E +10 0 000E+00 0 000E+00 0 000E+00 1.350E+09 SR-91 3 s30E+04 0 000E+00 1.270E+03 0.000E+00 0.000E +00 0 000E +00 1.490E+05 SR-92 4 890E-01 0 000E+00 2110E-02 0 000E+00 0.000E +00 0.000E + 00 9 680E+00 O (.)
Offsite D0se C:lculation Manu:1 Pros 276 of 313 Revision 2 Change 0 Attachment 12 [h V Gaseous Effluent Pathway Dose Factors GRASS-COW MILK DOSE FACTORS ADULT (m' ' mrem /yr per uCl/sec) Nuclide Bone Uver Tbody Thyroid Kidney Lung Gitract Y 90 7.070E+01 0.000E+00 1.900E +00 0.000E+00 0.000E+00 0 000E+00 7.500E+05 Y 91M 0 000E+00 0.000E +00 0 0'OE+00 0.000E+00 0 000E+00 0.000E +00 0 000E+00 Y 91 8600E+03 0 000E+00 2.300E +02 0.000E+00 0 000E+00 0.000E +00 4 730E+06 Y-92 5 420E-05 0 000E+00 1.580E-06 0.000E+00 0 000E+00 0 000E+00 9 490E-01 ' Y 93 . 2 330E 01 0 000E+00 6 430E-03 0.000E+00 0.000E+00 0 000E+00 7.390E +03 ZR45 9 400E+02 3 030E+02 2 050E+02 0 000E+00 4 700E+02 0.000E +00 9 620E+05 ZR 97 4 200E 01 8 590E-02 3 930E-02 0.000E+00 1.300E 01 0.000E+00 2 660E+04 NB45 8250E+04 4 590E+04 2.470E+04 0 000E+00 4 540E+04 0 000E+00 2.700E +08 N B-97 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 5 470E 09 MO-99 0 000E+00 2 520E+07 4 800E+06 0 000E+00 5.720E +07 0 000E+00 5.850E+07 TC-99M 3.250E+00 9190E+00 1.170E +02 0.000E +00 1.400E+02 4 500E+00 5 440E +03 TC 101 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 RU-103 1.020E+03 0 000E+00 4 390E+02 0 000E+00 3890E+03 0 000E+00 1.190E+05
- RU 105 8 570E-04 0 000E+00 3 380E 04 0.000E +00 1.110E-02 0 000E+00 5.240E 01 p RU 106 2 040E+04 0 000E+00 2 580E +03 0 000E+00 3 940E+04 0 000E+00 1.320E +C6 RH 103M 0000E+00 0.000E+00 0 000E+00 0.000E+00 0 000E+00 0,000E+00 0 000E +00 RH 106 0 000E +00 0 000E+00 0.000E +00 0 000E+00 0 000E*00 0 000E+00 0 000EG AG 110M S530E+07 5 300E+07 3.200E+07 0 000E+00 1060E+08 0 000E+00 2.200E +10 SB-122 6 010E+05 6 279E +05 7.500E+06 9 960E+04 2.960E+05 1290E+05 7 470E+07 l SB 124 8 580E+08 1.620E A7 3 400E+08 2.080E +06 0 000E+00 6 680E+08 2.440E +10 S B-125 6 810E+08 7.610E+06 1.620E +08 6 930E+05 0 000E+00 5 250E+08 7.500F +09 TE 125M 1.630E+0' 5 900E+06 2.180E+06 4 900E+06 6630E+07 0 000E+00 6.500E +07 TE 127M 4 580E+07 1640E+07 5 580E+06 1.170E +07 1.860E+08 0 000E+00 1.540E+08 TE-127 6 720E+02 - 2 410E+02 1450E+02 4 980E+02 2.740E+03 0 000E+00 5.300E +04 TE 129M 6 040E +07 2 250E+07 9 570E+06 2.080E+07 2.500E+08 0 000E+00 3.040E +08 TE 129 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0.000E+0C 0 000E+00 TE 131M 3 610E+05 1.770E+05 1470E+05 2 800E+05 1.700E+06 0 000E+00 1.750E +07 TE 131 0 000E+00 0.000E+00 0 000E +00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 T E-132 2.390E +06 1.550E+06 1450E+06 1.710E+06 1.490E+07 0.000E+00 7.320E +07 L130 4 260E+05 1260E+06 4 960E+05 1.070E +08 1.960E+06 0 000E+00 1.080E+06 l-131 2.960E+08 4 240E+08 2.430E +08 1.390E+11 7.270E+08 0 000E+00 1.120E+08 l-132 1.640E 01 4 370E 01 1.530E 01 1.530E+01 6 970E 01 0 000E+00 8.220E 02 1-133 3 970E+06 6.900E+0G 2100E+06 1.010E+09 1.200E *07 0 000E+00 6 200E +06 y
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' Offsita Dose Criculdi ni Manual- ' Ptgs 277 Of 313 -
Revision 2 Change 0 : Attachment 12 - Gaseous Effluent Pathway Dose Factors ( GRASS-COW MILK DOSE FACTORS
-ADULT-2 (m
- mrem /yr per uCi/sec)
~ Nuchde : -Bone Uver Tbody Thyroid . Kkiney Lung Getract I-134 0 000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1135- 1.390E +04 3 630E+04 1.340E+04 2.400E+08 5 630E+04 0 000E +00 _ 4.100E +04 e CS 134 5 650E+09 1.340E+10 1.100E+10 0 000E+00 4 350E+09 1.440E+09 2.350E +08 .
CS-136 2 610E+08 1.030E+09 7.420E+08 0.000E+00 5.740E+08 7.870E+07 1.170E+08
- CS-137 - 7,380E+09 1.010E+10 6.610E+09 0 000E+00 3 430E+09 1.140E+09 1.950E+08 l
CS 13G 0000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l 0.000E+00 0 000E+00 B A-139 4.700E-08 0.000E +00 1.380E 09 0 000E+00 - 0.000E+00 0.000E+00 8.340E 08 e BA 140 2 690E+07 3 380E+04 1.760E+06 0.000E+00 1.150E+04 1.930E+04 5.540E+07 BA 141 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 BA 142 - 0.000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 LA 140. 4 400E+00 2.260E+00 5 970E-01 0 000E+00 0.000E +00 0 000E+00 1.660E+05 ! LA-142 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 3 030E-08 . CE 141 - 4 8/0E +03 3.270E+03 - 3.710E+02 0 000E+00 1.520E+03 0.000E+00 1.250E+07 i. CE 143 4100E+01 3 090E+04 3 420E+00 0.000E+00 1.360E+01 0.000E+00 1.160E+06 CE 144 3.580E+05 1.500E +05 1.920E +04 0 000E+00 8 870E+04 0.000E+00 1.210E+08 , - PR 143 1.590E+02 6.370E +01 7.880E+00 0 000E+00 3 680E+01 0 000E+00 6 960S +05 PR 144 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0 000L+00 NO-147 fi -120E+01 1,090E+02 6 520E+00 0 000E+00 6 370E+01 0.000E+00 5.230E+05 EU 154 2.370E+04 2.910E+03 2.070E+03 0.000E+00 1.390E+04 0.000E+00 2.110E+06 EU 155 3 300E+03 4 680E+02 3 020E+02 0 000E+00 2.160E+03 0 000E+00 3.680E +05 W 187- 6.560E+03 5.480E+03 - 1.920E+03 0 000E+00 0.000E+00 0 000E+00 1800E +06 NP-239 3 660E +00 3 600E 01 1.980E 41 0 000E+00 1.120E+00 0 000E+00 7.390E +04 h i a 4 4
~
i f
- . . .~, ~. - .- -~_ .. . - - -. .~ . ~ . _ _ . . . - . - - . - . - - .
1 i Offsita Dose C:lculation Minu:1 Page 278 of 313 l
. Revision 2 Change O' Attachment 12-g Gas 00us Effluent Pathway D0se Factors GRASS-COW MILK DOSE FACTORS TEEN -f (m 2* mrem /yr per uCi/sec)
Nuchde Bone 1 Uver Tbody Thyroid Kidney Lung Gitract
'H-3 0 000E+00 9 940E+02 9 940E+02 9 940E+02 9 940E+02 9.940E +02 9.940d+02
- C 14 6.700E+05 1.340E +05 1.340E +05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA 24 - 4 440E+06 4 410E+06 4 440E+06 4 440E+06 4 440E+06 4 440E+06 4.440E+06 P 32 3.150E+10. 1.950E+09 .1.220E+09 0 000E+00 0.000E+00 0.000E+00 2.650E+09
- CR 51 0 000E+00 0.000E+00 5.000E+04 2.780E+04 1.100E+04 7.130E+04 8.400E+06 MN54 - 0 000E+00 1.400E+07 2.780E+06 0 000E+00 4170E+06 0 000E+00 2 870E+07 MN56. 0 000E+00 7.510E43 1.330E 03 0.000E+00 9.500E 03 0 000E+00 4 940E 01 >
FE55 4 450E+07 3.160E+07 7.360E +06 0.000E+00 0.000E+00 2.000E+07 1.370E+07 FE 59 - 4 680E+07 0 000E+00 0 000E+00 3 820E+07 2 870E+08 ; j 5.200E+07 1.210E+08 CO-57 0 000E+00 2.250E*06 3.760E+06 0.000E+00 - 0.000E+0C 0.000E +CIO 4190E+07 CO-58 0 000E+00 7 950E+06 1.830E +07 0 000E+00 0.000F 10 0 000E+00 1.100E +08 C040 0 000E+00 2.780E+07 6 260E+07 0 000E+00 0 000E+00 0 000E+00 3 620E+08 Ni-63 1.180E+10 0.350E+08 4 010E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+0&^ Ni45 6 780E 01 8 660E 02 3 940E 02 0.000E+00 0 000E+00 0 000E +00 - 4.700E+00 CU44 0 000E+00 4 290E*04 2 020E+04 0 000E +00 1.090E+05 0 000E+00 3 330E+06 ZN45 2110E+09 7.310E+00 3.410E+09 0000E+00 4 660E+09 0 000E+00 3.100E +09 ZN 69 0 000E+00 0.000E +00 0 000E+00 0 000E+00 0.000E +00 0.000E +00 0 000E+00 , BR-82 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 BR 83 0 000E+00 0.000E +00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E+00 BR-84 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 t BR 85 0 000E+00 0.000E+00 0.000E +00 0.000E +00 0 000E+00 0.000E+00 ' O.000E+00 RB 86 0 000E+00 4 730E+09 2.220E+09 0.000E+00 0.000E+00 0.000E+00 7 000E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E+00 - , RB-81e 0 000E+00 0.000E+00 - 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E +00 SR 89 2.670E+09 0.000E +00 7.660E +07 0.000E+00 0 000E+00 -0.000E+00 3.180E+08 SR 6 610E+10 0.000E+00 1.630E+10 0 000E+00 0.000E+00 - 0.000E+00 1.860E+09 SR 91 5.750E+04 0 000E+00 2.290E+03 0.000E +00 0,000E+00 0.000E+00 2.610E+05
- SR 92 - ' 6 950E 01 - -0.000E+00- 3.810E 02 0.000E+00 0.000E+00 0 000E+00 2.280E+01
. Y 90 . 1.300E+02 - 0.000E+00 3 500E+00 0.000E+00 0.000E+00 0 000E+00 1.070E+06 Y 91M 0.000E+00 0.000E+00 0.000E+00 ' 0 000E+00 0.000E+00 0.000E+00 0 000E+00 4 Y 91 1.580E+04 0 000E+00 4 240E+02 - 0.000E +00 0.000E+00 - 0 000E+00 6.480E+06 Y 92 1.000E-04 0.000E +00 2.900E-06 0.000E+00 - 0 000E+00 0 000E+00 2.750E+00 Y-93 4.300E-01 0 000E+00 1.180E 02 0.000E+00 0 000E+00 0.000E+00 1.310E+04 2R 1.650E +03 5 220E+02 - 3 590E+02~ 0.000E+00 7.670E+02 0.000E+00 1.200E+06
.g 1 ZR 97. _ 7,750E-01 1.530E-01 7.060E 02 0.000E+00 ' 2.320E 01 0.000E+00 ' 4.150E+04 1
- -_ . _ _ _ ._ . . _ - . _ , _ . _ _ . . , _ , __ - . - _ ~
-. . .- ~, . --.. -- .- .~ - . . - - . . .-.-
Offsite Dose Calculation Minu 1 - PEge 27w of 313 . Revision 2 Change 0 Attachment 12 O - Gaseous Effluent Pathway D0se Factors
. GRASS-COW-MILK DOSE FACTORS
. TEEN-(m' ' mrem /yr per uCl/sec) ,
- Nachde Bone Liver Tbody Thyroid Kidney - Lung Getract ND-95 1.410E+05 7.800E +04 4.300E +04 0 000E+00 - 7.570E+04 0.000E+00 3 340E+08 NS 97 0 000E+00 - 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 6.340E-06 MO 90 0 000E+00 4 560E+07 - 8 690E+06 0.000E+00 1.040E+08 0.000E +00 8.160E+07
- TC-99M 5.640E+00 1.570E +01 2.040E+02 0.000E+00 2.340E+02 S730E+00 1.030E+04 '
TC 101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 RU-103 1.810E+03 0.000E+00 7.750E+02 0.000E+00 6.400E+03 0.000E+00 1.520E+05 RU-105 1.570E-03 0.000E+M 6 080E 0.000E+00 1.970E-02 0.000E+00 1.260E+00 RU 106 3.750E+04 0.000E+00 4.730E+03 0 000E400 7.230E+04 0.000E+00 1.800E+ 06 RH 103M 0000E+00- 0.000E+00 - 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 RH-106 0000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0 (rJOE+00 0 000E+00 AG 110M 9 630E+07 9110E+07 5540E+07 0.000E +00 1.740E+08 0.000E+00 2.560E +10 SB-122 7.760E+05 8.090E+05 9 800E+06 1.290E+05 3 820E+05 1660E+05 9 640E+07 l SB-124 1.530E+09 2.820E+07 5.970E+08 3.470E+06 0.000E+00 1.340E+09 3 080E+10" I SB-125 1.220E +09 1.330E +07 2 850E+08 1.160E+06 0 000E+00 1.070E+09 9 480E+09 TE 125M 3 000E+07 1.080E+07 4 020E+06 8.390E+06 0 000E+00 0 000E+00 8.B60E +07 , TE 127M 8.440E+07 2.990E +07 1,000E+07 2.010E+07 3 420E+08 0000E+00 2.100E +08 ' TE-127 1240E+03 4 410E+02 2 680E+02 8.590E+02 5 040E+03 0.000E+00 9 610E+04 TE 129M -1.110E+08 4.100E+07 1.750E+07 3 570E+07 4 620E+08 0 000E+00 4.150E+08 TE 129 0 000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E-09 0 000E+00 2180E-09 TE 131M 6.570E+05 3.150E+05 2.630E+05 4.740E+05 3.290E+06 0.000E+00 2.530E +07 TE 131 0 000E+00 - 0.000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E +00 0.000E+00 TE 132 4 280E+06 2.710E+06 2 550E+06 2.860E+06 2.600E+07 0000E+00 8 580E+07 1,130 7.490E+05 2.170E +06 8 660E+05 1.770E+08 3.340E+06 0 000E+00 1.670E+06 l131 5.380E+08 7.530E +08 4 040E+08 2.200E+11 1.300E+09 0.000E+00 1.490E +08 l132 2.900E 01 7,590E 01 2.720E 01 - 2.560E+01 1.200E+00 0 000E+00 3.310E-01 l-133 7.240E+06 1.230E+07 3.750E+06 - 1.720E+09 - 2.150E +07 0000E+00 9300E+06 l134 0.000E+00 ' O.000E+00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 - l-135 2 470E+04 6 350E+04 2.350E+04 - 4 080E+06 1.000E+05 0.000E+00 7.030E+04 }' CS 134 9 810E+09 2.310E+10 1.070E+10 0 000E+00 7.340E+09 2.800E+09 - 2.870E+08 CS 136 - 4 450E+08 1.750E+09 1.180E+09 0.000E+00 9.530E+08 1.500E+08 1.410E+08 c CS-137 1,340E+10 1.780E+ 10 6 200E+09 0.000E+00 6.060E+09 2 350E+09 2.530E+08 - CS-138 - 0 000E+00 0 000E+00 - 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E +00 BA-139 . 8 690E-00 0,000E+00 2.530E 09 0.000E+00 0 000E+00 0.000E+00 7.750E 07 BA 140 4 850E+07 5.950E+04 - 3.130E+06 0.000E+00 2.020E+04 4 000E+04 7.490E+07
- BA-141 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 i
, . - - - . - ~ . . - . . - . - . , --- - , - . ,r - - , -
Offsit) D:se cdcul: tion M:nual Page 280 of 313 Revision 2 Change O n Attachment 12 Gaseous Effluent Pathway D0se Factors (V ) GRASS-COW MILK DOSE FACTORS TEEN (m'
- mrem /yr per uCl/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gltract BA-142 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 LA 140 8 060E+00 3 900E+00 1050E+00 0 000E+00 0 000E+00 0 000E+00 2.270E +05 LA 142 0.000E +00 0.000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 2.230E 07 CE-141 8 870E+03 5 920E+03 6 810E+02 0 000E+00 2.790E +03 0 000E+00 1.690E+07 ' CE-143 7.690E +01 5 600E +04 6 250E+00 0 000E+00 2 510E+01 0 000E+00 1,680E +06 CE-144 6.580E +05 2.720E+05 3 540E+04 0 000E+00 1.630E+05 0 000E+00 1.660E +08 PR-143 2.920E +02 1.170E+02 1.450E+01 0 000E+00 6 770E+01 0.000E +00 9 610E+05 PR 144 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E +00 ND-147 1.810E +02 1.970E+02 1.180E+01 0 000E+00 1.160E+02 0 000E+00 7.110E +05 EU-154 3 920E+04 5 060E+03 3 570E+03 0 000E+00 2.260E+04 0 000E *0'0 2.670E+06 EU 155 8 600E+03 8 310E+02 5140E+02 0 000E*00 3 250E+03 0 000E+00 4.760E+06 W 187 1.200E +04 9 780E+03 3 430E +03 0 000E+00 0 000E+00 0 000E+00 2.650E+06 NP-239 6 990E+00 6 590E-01 3 660E 01 0 000E+00 2.070E +00 0 000E+00 1.060E +05" m I i
~
Q)
_, . _ ._ -_ _._ m - - _ _ ,_ - . _ _ _ _ _ . _ _ Offsit) Dose C:lculation Manu:1 - Paga 281 of 313 Revision 2 Change 0
- g. - Attachment 12 q~ -
Gaseous Effluent Pathway D0se Factors
. GRASS-COW MILK DOSE FACTORS CHILD '
(m 2* mrem /yr per uCi/sec) . -Nuchde Bone: Uver Tbody Thyroid Kidney Lung 04 tract H-3 0.000E+00 1,570E+03 1.570E+03 1.570E+03 - 1.570E+03 1.270E +03 1.570E+03 C 14 - 1.650E+06 3 290E+05 3.290E+05 3 290E+05 3 290E+05 3 290EQ'i 3.290E+05 NA 24 9.230E+06 9.230E+06 9.230E+06 - 9.230E +06 9.230E+06 ' 9.230E+06 9.230E+06 P 32 7.770E+10 3 640E+09 3.000E+09 0 000E+00 ' O000E+00 0.00nE+00 2.150E+09 ' CR 51 0 000E+00 0 000E+00 1.020E+05 5.660E+04 1.550E+04 1.030E+05 5 410E+06
- MN-54 0.000E+00 - - 2 000E+07 - 5.580E+06 0.000E+00 5 870E+06 0.000E+00 1.760E +07 MN-50 .0.000E+00 1.310E-02 2.950E 03 - 0.000E+00 1.580E 02 0.000E+00 1.900E+00 FE 55 1.120E+08 5930E+07 1.640E +07 0.000E+00 0 000E+00 3.350E+07 1.10CE+07 F E-59 1.200E+08 1,950E+08 9.710E+07 . 0.000E+00 0.000E+00 5 650E+07 2.030E +08
-CO 57 0 000E+00 . 3.840E+06 7.770E+06 0.000E+00 - 0.000E+00 0.000E+0D 3.140E+07 CO-58 0 000E+00 1.210E+07 3.720E+07 0.000E+00 0.000E+00 0 000E+00 7.080E+07 _
C040 0.000E+00 4 320E+07 1.270E +08 0.000E+00 0.000E+00 0 000E+00 2 390E+08 NI43 2.960E+10 1.590E+09 1,010E+09 0(V0E+00 0.000E +06 0 000E+00 1.070E+06 ~ N145 1.660E+00 1.560E 01 9.110E 02 0 000E+00 0 000E+00 0.000E+00 1.910E+01 p CU44 0 000E+00 7.550E+04 4 560E+04 0.000E+00 1.820E+05 0.000E+00 3.540E+06 ZN45 4130E+09 1.100E+10 6 850E+09 0.000E+00 6940E+0? O000E+00 1930E+09 ZN$9 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 2.140E-09 BR42 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 B R-83 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 BR44 0.000E+03 '- 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR45 0 000E+(C 0.000E+00 - 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E +00 RB46 0 000E+00 8770E+09 5.390E+09 0 000E+00 0 000E+00 0.000E+00 5.640E+08 RB48- 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB49 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I SR89 6 620E+09 - 0.000E+00 1.890E+08 0.000E +00 0 000E+00 0.000E+00 2.560E+08 7
- SR 90
- 1.120E+11 0.000E+00 2.830E+10 - 0.000E+00 0.000E+00 0.000E+00 1.510E+09 -
SR-91 1,410E+05 0 000E+00 5.330E+03 0.000E+00 0 000E+00 0.000E+00 3.120E+05 SR-92 2.190E+00 0.000E+00 6.760E 02 0 000E+00 ' O.000E+00 0.000E+00 4.140E+01 Y-90 : 3.220E+02 0.000E+00 8.610E+00 0.000E+00 - 0.000E+00 0.000E+00 9.150E+05 Y 91M 0.000E+00- 0.000E+00 0.000E+00 ' O.000E+00 . 0.000E+00 0000E+00 0.000E+00 Y 91 3 910E+04 0.000E+00 1.040E+03 0.000E+00 0.000E+00 ' O.000E+00 5.210E+06
~ Y 2.460E 0 000E+00 7.030E-06 040E+00 0.000E+00 - 0.000E+00 7.100E+00 -
Y-93 1,060E+00 0.000E+00 2.900Ee 0.000E+00 0.000E+00 0 000E+00 - 1.570E+04
,y ZR 95 - 3 840E+03 8 450E+02 7.520E+02 0.000E+00 1.210E +03 0.000E+00 8 810E+05 Q ZR-97 1.800E+00 - 2.720E-01 1.610E 01 0.000E+00 3.910E-01 0 000E+00 4.130E+04
. -- - .- -.- .. .- - ~ . - . - - . _ . - _ - ~ . - - - . - .. ,
offsits Dose Calcul: tion Manu11 Pago 282 of 313 i- ~ Revision 2 Change 0 -
+'
Attachment 12 Gaseous Effluent Pathway D0se Factors
\ - GRASS-COW-MILK DOSE FACTORS -
CHILD (m'
- mrem /yr per uCl/sec)
Nucl6de - Bone- Liver . Tbody Thyroid Kidney Lung Oltract NB-95 ' 3180E+05 1.240E+05 8.840E+04 0.000E+00 < 1.160E+05 0.000E+00 2.290E+08 NB-97 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 1.450E 06 . s MO 0.000E+00 8.290E+07 2 050E+07 0.000E+00 1.770E+08 0.000E+00 6 860E+07 TC-99M 1.290E+01 2.540E+01 4.200E+02 0.000E+00 3.680E+02 '1.290E+01 1.440E+04 ' TC-101 0 000E+00 0 000E*00 0.000E+00 0.000E+00 0.000E +00 0.000E+00 0.000E+00 RU 103 4 290E+03 0.000E+00 1.650E+03 0.000E+00 1.080E +04 0.000E+00 1.110E+05 RU 105 3 820E43 - 0 000E+00 1.390E-03 0.000E+00 3 360E 02 0.000E+00 2 490E+00 RU-106 9 240E+04 0.000E+00 1.150E+04 0.000E+00 1.250E+05 0.000E+00 1,440E+06 RH-103M 0 000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0D 0.000E+00 AG-110M 2.090E+08 1.410E*08 1.130E+08 0 000E+00 2 630E+08 0000E+00 1680E+ 10 50-122 4140E+06 4.320E+06 5.230E+07 6 870E+05 2.040E+06 8.890E+05 5.150E+08 l SB 124 3 620E+09 4 700E+07 1.270E+09 7 990E+06 0 000E+00 2.010E+09 2.260E+10 - SB 125 2.000E409 2.240E+07 0.080E+08 2.690E+06 0.000E+00 1.620E+09 6.930E +09 TE 125M 7.380E+07 2.000E+07 9.840E* 06 2.070E+07 0.000E+00 0 000E+00 7.120E+07 f . 5 TE 127M - 2 080E+08 5 600E+07 2.470E+07 4 970E+07 5 930E+08 0.000E+00 1.680E+08 TE 127 3 060E+03 8 250E+02 6.560E +02 2.120E+03 8.710E+03 0 000E+00 - 1.200E+05 TE 129M 2.720E+08 7.610E +07 4 230E+07 - 8.780E+07 8000E+08 0.000E+00 3 320E+08 1E 129 0 000E+00 0 000E+00 0.000E+00 0 000E+00 2.870E 09 0 000E+00 6120E 08 TE-131M 1.600E+06 '5530E+05 5890E+05 1.140E+06 5350E+06 0 000E+00 2.240E +07 TE-131 0 000E+00 0.000E +00 - 0 000E+00 0.000E +00 0 000E+00 0.000< g JO 0.000E+00 i TE 132 1.020E+07 4.520E+06 5.460E+06 6.580E+06 4 200E+07 0.000E+00 4 550E+07 l130 1.750E+06 3 540E+06 1.820E+06 3 000E+08 5.290E+06 0,000E+00 - 1.660E+06 l-131 1.300E+09 1.310E409 7,460E+08 4 340E+11 2.150E+09 0.000E+00 1.170E+08 l-132 6 860E41 1.260E+00 5.800E-01 5.850E+01 1.930E+00 0 000E+00 1.480E +00 1-133 1.760E+07 2,180E+07 - 8.230E+06 4 040E+09 3 630E+07 0.000E+00 8.770E+06 4 l134 0 000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 ' l-135 5.840E+04 1.050E +05 4 970E+04 - 9.300E+06 1.610E+05 0 000E +00 8.000E+04 CS-134 2.260E+10 3 710E+10 7.830E + 09 .. 0.000E+00 1 150E+10 4130E+09 2.v00E+08 CS-136 1.000E+09 2.760E+09 1.790E+09 0.000E +00 1.470E+09 2.100E+08 9.700E+07 CS-137 - 3.220E+10 _ 3.090E+10 4.550E+09 0 000E+00 1.010E+10 3.620E+09 1.930E+08 CS-138 - 0 000E+00 0.000E+00 0 000E+00 'O.000E+00 0.000E+00 0.000E+00 0.000E+00 i BA-139 . 2.140E 07 : 0.000E+00 6.190E 09 0.000E+00 0 000E+00 0.000E+00 1.230E 05 BA-140 .1.170E+08 1,030E+05 6 840E+06 0.000E+00 3 340E+04 - 6.120E+04 5.940E+07
\ BA 141 0.000E+00 0.000E+00 0 000E+00 - 0.000E+00 0 000E+00 0.000E+00 0 000E+00
.Offsits Dose Calculation Manual Page 283 of 313 R: vision 2 Ching) O h
Attachment 12 ' C Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS > CHILD (m'
- mrem /yr per uCl/sec)-
Nucl6de Bone Uver Tbody Thyroid Midney Lung Getract BA-142 - 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 LA-140 1,930E+01 6.740E+00 2.270E+00 0.000E+00 - 0.000E+00 0 000E+00 1.880E+05 'i LA 142 = 0 000E+00 - -0.000E+00 0.000E+00 0.000E+00 0.000F+00 0.000E+00 - 2.510E46 - CE 141 2.190E+04 1.090E+04 1.620E+03 0.000E+00 4.780E+03 0.000E+00 1.360E+07 '
. CE 143 - 1.890E+02 1.020E+05 1.480E +01 0.000E+00 4.290E+01 0.000E+00 1.500E +t4 CE 144 1.620E+00 5.090E+05 8 660E+04 0 000E+00 1820E+05 0.000E+00 1.330E+C3 '
PR 143 7.230E +02 2.170E+02 3 590E+01 0.000E+00 1.170E+02 0.000E+00 7.800E +05 PR 144 0 000E+00 0.000E+00 0000000 0.000E+00 0.000E +00 0.000E +00 0.000E +00 1 ND-147 4 450E+02 3 600E+02 2.790E+01 0 000E+00 1.980E+02 0.000E+00 5.710E+05 l EU-154 - -9420E+04 8.470E+03 7.740E+03 0.000E+00 3.720E+04 0.000E+0D 1.970E+06 EU-155 - 1.970E+04 ' 1.420E+03 1.110E+03 0.000E+00 5.300E+03 0 000E+00 3.540E+06 W 187 2 910E+04 1,720E+04 7.730E+03 0.000E+00 0.000E+00 0.000E+00 2.420E+06 - NP 239 1.720E +01 1.230E+00 8.680E41 0.000E+00 3 570E+00 0 000E+00 9140E +04" i ( i h } 4 1 2 S o-b t
l Offsits Dose C:lculition M:nuai Pcge 264 Of 313 1
- Revision 2 Change 0 - _
pz Attachment 12
-. Gaseous Effluent Pathway Dose Factors
--- GRASS-COW MILK DOSE FACTORS INFANT .
(m mrem /yr per uCl/sec) Nuchde ' Bone. Uver Tbody: Thyroid Kidney Lung Ottract H-3. 0000E+00 2.380E+03 2.380E+03 2.380E+03 2.380E
- 03 2.380E+03 2.380E+03
. C 14 - 3.230E+06 6 890E+05 6 890E+05 6890E+05 - 6 890E+05 6 890E+05 6 890E+05 NA 1.610E+07 - 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 P 32 1.600E+11 9 420E+09 - 6.210E+09 0.000E +00 0.000E+00 0 000E+00 2.170E+09 -
CR 51 - 0.000E+00 0 000E+00 - 1.610E+05 1.050E+05 2.300E+04 2.050E+05 4 710E+06 MN-54 0 000E+00 - - 3 890E+07 8 830E+06 0.000E+00 8 630E+06 0.000E+00 1,430E+07 MN 56 0 000E+00 3 210E 02 ~ 5 530E-03 0.000E+00 2.760E-02 0 000E+00 . 2.910E +00 F E-55 1.350E+08 8.720E+07 2.330E+07 0 000E+00 0 000E+00 4 270E+07 1.110E+07 FE 2.250E+08 3 930E+08 1.560E +08 0.000E+00 0.000E+00 1.160E+08 1.880E +08 l CO-57 0 000E+00 8 950E+06 1.460E+07 - 0 000E+00 0.000E+00 0 000E+0'd 3.050E+07 CO-58 0 000E+00 2 430E+07 6 060E+07 0 000E+00 0 000E+00 0.000E+00 6 050E+07 C040 0 000E+00 8 810E+07 2 080E+08 - 0.000E+00 0 000E+00 0.000E+00 2.100E+08 NI43 3 490E+10 2.160E+09 1.210E+09 0 000E+00 0.000E +00 0.000E+00 1.070E+00+ - N145 3 510E+00 3.970E-01 1.810E 01 0.000E+00 0.000E+00 0 000E+00 3.020E+01 CU44 - 0 000E+00 - 1.880E+05 8 690E+04 0 000E+00 3170E+05 0.000E+00 3 850E+06 2N4f 5 550E+09 1.900E+10 8 780E+09 0 000E+00 9 230E+09 0 000E+00 1.610E+10 ' ZN-69 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 7.360E 09 BR42 0.000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0.000E+00
- BR-83 ' O.000E+00 0.000E +00 0 000E+00 0.000E+00 0.000E+00 0 000E+00 0 000E+00 BR 84 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR45 0 000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB46 0.000E+00 2.220E+10 L100E+10 0.000E+00 0 000E+00 0 000E+00 5.690E+08 RB-88 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E +00 0.000E+00 0.000E+00 RB49 0.000E+00 0 000E+00 0.000E+00 0 000E+00 0.000E +00 0.000E+00 0.000E+00 SR49 1.260E+ 10 0.000E+00 3.610E+08 0.000E+00 0.000E+00 0 000E+00 2.590E+08 SR 90 ~ 1220E +11 0 000E+00 - 3.100E +10 0 000E+00 0.000E+00 0 000E+00 1.520E+09 4 - SR 91 2 940E+05 0.000E+00 1.060E+04 0,000E+00 0.000E+00 - 0.000E+00
- 3.480E+05 SR92. 4.650E+00 0.000E+00 - 1J30E C1 0 000E+00 0 000E+00 0.000E+00 5.010E+01 Y 90 6 800E+02 0 000E+0n - 1.820E+01 - 0.000E+00 . 0.000E+00 0.000E+00 9.390E+05 Y 91M -0000E+00
. .0 000E+00 0.000E+00 0 000E *00 0.000E+00 0.000E +00 0.000E+00 l Y-91 7.330E+04 0 000E+00 -: 1.950E+03 0.000E+00 0.000E+00 0.000E+00 - 5.260E+06 Y 92 ' 5.220E o4 0.000E+00 1.470E 05 0 000E+00 0.000E+00 0.000E+00 9.970E+00
~
Y 93 2.250E+00 0.000E+00 6.130E-02 0,000E+00 0.000E+00 0.000E+00 1.780E+04 2R-95 ' 6 830E+03 . --1.660E+03 - 1.180E+03 ~ 0 000E+00 1.790E+03 0 000E+00 8.280E+05 V ZR-97 3 090E +00 6 850E 01 3.130E-01 ~ 0.000E+00 ' 6.910E-01 0.000E+00 4 370E+04 _____ _ . - , # .~. g.,.- r y e . ,m-,, . m- . . ..____-.,._:.r.n -
Offsit] D0se C:lculation Manual Prgs 285 of 313 Revision 2 Change O n Attachment 12
- v) Gaseous Effluent Pathway D0se Factors GRASS-COW MILK DOSE FACTORS INFANT (m2. mrem /yr per uCl/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract NB-95 5930E+05 2.440E +05 1.410E+05 0 000E+00 1,750E+05 0 000E+00 2.060E+08 NB-97 0 000E+00 '1000E +00 0 000E+00 0 000E+00 0.00C2 +00 0.000E +00 3 700E-06 MO-99 0 000E+00 2.120C+08 4.130E +07 0 000E+00 3170E+08 0.000E +00 6 960E+07 T C-99M 2 690E+01 5 550E+01 7.150E+02 0.000E+00 5970E+02 2 900E+01 1.610E+04 ' TC 101 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 RU-103 8 690E+03 0 000E+00 2 910E+03 0.000E+00 1.810E +04 0000E+00 1.060E+05 RU 105 8 OGOE-03 0 000E+00 2.710E 03 0 000E+00 5 920E-02 0 000E+00 3 210E+00 RU-106 1.900E+05 0 000E+00 2.380E+ 04 0 000E+00 2.250E+ 05 0 000E+00 1.440E+06 RH 103M 0.000E+00 0 000E+00 0 000E+00 0.0002+00 0.000E +00 0 000E+00 0.000E +00 RH-100 0.000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 AG 110M 3 860E+08 2 820E+08 1,860E+08 0 000E+00 4 030E+08 0 000E+00 1460E+10 SB-122 6.400E+05 6 670E+05 8 080E +06 1.000E +05 3.150E+05 1.370E+05 7 950E+07 l SB-124 6 980E+09 1.030E+08 2.160E+09 1.850E +07 0 000E+00 4.370E+09 2.150E +10" SB-125 4 980E+09 4 820E+07 1.020E+09 6.240E+06 0 000E*00 3130E+09 6 640E+09 p TE-125M 1.510E+08 5 040E+07 2 040E+07 5 070E+07 0 000E +00 0.000E +00 7.180E+07 V TE-127M 4 210E+08 1.400E+08 5100E+07 1.220E+08 1.040E+09 0.000E+00 1.700E+08 TE-127 6 500E+03 2.180E+03 1.400E+03 5 290E+03 1.590E+04 0 000E+00 1.360E+05 TE 129M $590E+08 1.920E+08 8 620E+07 2.150E+08 1.400E +09 0 000E+00 3.340E+08 TE-129 2 080E-09 0 000E+00 0 000E +00 1.750E-09 5180E 09 0 000E+00 1.660E-07 TE-131M 3 380E+06 1.360E+06 1.120E+06 2.760E+06 9 350E+06 0.000E+00 2 290E+07 TE 131 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0 000E+00 TE 132 2.100E+07 1.040E +07 9 720E+06 1.540E+07 6 510E+07 0 000E+00 3.850E+07 b130 3 600E+06 7.920E+06 3.180E +06 8 880E+08 8 700E+06 0.000E *00 1.700E+06 l-131 2.720E +09 3 210E+09 1.410E+09 1.050E+12 3 750E+09 0 000E +00 1.150E+08 l-132 1.420E+00 2.890E +00 1.030E +00 1.350E+02 3 220E+00 0.000E+00 2.340E+00 l133 3 720E*07 5 410E+07 1580E+07 9 840E+09 6.360E+07 0.000E+00 9160E+06 1134 0000E+00 0.000E+00 0.000E+00 1.010E-09 0 000E+0? 0.000E+00 0.000E+00 L135 1.210E +05 2,410E+05 8 800E+04 2.160E+07 2.690E +05 0 000E+00 8.740E+04 CS-134 3 650E+10 6 800E+10 6 870E+09 0.000E+00 1.750E + 10 7.180E+09 1.850E *08 CS-136 1.960E+09 5.770E+09 2.150E +09 0 000E+00 2.300E+09 4 700E+08 8.760E+07 C S-137 5150E +10 6 020E+10 4 270E+09 0.000E+00 1.620E +10 6 550E+09 1.880E+08 CS 138 0.000E+00 0.000E+00 0 000E +00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA 139 4550607 0 000E+00 1.320E-08 0.000E+00 0.000E+00 0.000E+00 2.880E-05 A BA 140 2 410E+08 2.410E+05 1240E+07 0 000E+00 5.730E+04 1.480E +05 5 920E+07 BA-141 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00
Offsite Dose Calculation Manual Page 286 of 313 i Revision 2 Chan0e O Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS COW-MILK DOSE FACTORS INFANT (m2'mremlyr per uCl/ soc; Nuchde Done Liver Tbody Thyroid K6dney Lung Gltract BA 142 0 000E +00 0 000E +00 0 000d+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 LA 140 4 030E +01 1 MOE *01 4 090E +00 0 000E+00 0 000E+00 0 000E+00 1470E*05 LA 142 0 000E +00 0 000E +00 00%E+00 0 000E+00 0.000E+00 0 000E400 5 210E-00 CE 141 4 330E+04 2 540E +04 3110E+33 0 000E+ 00 8150E+03 0 000E+00 1.370E*07 - CE 143 4 000E+02 2 050E+05 3 020E+01 0 000E+00 7.720E +01 0 000E+00 1.550E +06 CE 144 1330E+06 9 $20E +05 1300E+05 0 000E+00 3 850E +05 0 000E +00 1.330E +08 PR 143 1 awD D3 5590E+0/ 7 410E*01 0 000E *00 2 080E+02 0 000E +00 7890E+05 PR 144 0 '.cc+00 0 000E400 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 f40-147 8820E*02 9000E+02 5 550E+01 0 000E+00 3 490E *02 0 000E*00 5740E+05 EU 154 1 OBOE *05 1500E+04 9 010E+03 0 000E *00 4 070E+04 0 000E+0b 1.680E*00 EU 155 2 210E +04 2 550E*03 1320E+03 0 000E+00 5710E+03 0 000E+00 3 410E*06 W 187 6120E*04 4 200E+04 1470E +04 0 000E+00 0 000E+00 0 000E *00 2 500E +06 NP-239 3 040E+01 3 250E+00 1.840E+00 0 000E +00 6490E+00 0 000E+00 0400E+44 ^
Offstto D0se Calculation Mrnual Page 287 Of 313 Revision 2 Chan0e O Attachment 12 Gaseous Effluent Pathy.ay D0se Factors GRASS GOAT MILK DOSE FACTORS ADULT (mm m/yr per uCl/sec) Nuchde Bone Liver Tbody Thytold K6dney Lung Ottract H-3 0 000E +00 1500E*03 1.500E
- 03 1500E +03 1.600E403 1.500E *03 1.500E
- 03 C 14 3 630E +05 7 200E+04 7 200E*04 7 260E*04 7200E+04 7 200E+04 7 200E*04 NA 24 3 060E *05 3 000E +05 3 050E*05 3 0%00+05 3 050E+05 3 050E+05 3 060E+05 P 32 2 050E+10 1270E *09 7 930E +08 0 000E*00 0 000E+00 0 000E+00 2 310E+09 '
CR41 0 000E*00 0 000E*00 3 430E+03 2 050E+03 7 500E*02 4 500E+03 8540E+05 MN54 0 000E*00 1.010E +06 1920E+05 0 000E+00 3 000E +05 0 000E+00 3 090E+06 MN 56 0 000E +00 $ 080E44 9 010E45 0 000E+00 6 450E-04 0 000E+00 1620E 02 FE45 3 200E+05 2 250E +05 3200E+04 0 000E+00 0 000E+00 1200E +05 1290E+05 FE49 3 870E+05 9 ODOE *05 3 490E *05 0 000E*00 0 000E*00 2 540E +05 3 030E *06 C0 57 0 000E+00 1,540E *05 2 550E +05 0 000E+00 0 000E+00 0 000E+60 3 900E+06 C048 0 000E* 00 5 600E +05 1270E*06 0 000E +00 0 000E+00 0 000E+00 1.150E + 07 C040 0 000E +00 1970E+00 4 340E*06 0 000E +00 0 000E+00 0 000E+00 3 700E+07 NI-63 8070E*08 5000E+07 2 710E +07 0 000E*00 0 000E*00 0 000E+00 1.170E +07 *- f4I45 4 440E-02 5 770E-03 2 630E-03 0 000E+00 0 000E*00 0 000E+00 1400E 01 CU-64 0 000E+00 2 690E +03 1200E+03 0 000E+00 6 770E+03 0 000E+00 2 290E+05 ZN+5 1c50E+08 5 240E *08 2 370E+08 0 000E+00 3 500E+08 0 000E+00 3 300E+08 ZN69 0A00E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BR -82 0 000E*00 0 000E+00 3 900E*06 0 000E+00 0 000E +00 0 000E+00 4 470E+06 DR43 0 000E+00 0 000E+00 1240E 02 0 000E+00 0 000E+00 0 000E+00 1.7tCE 02 BR-84 0 000E +00 C v00E*00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 BR-85 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 RB80 0 000E+00 3.110E +08 1.450E +08 0 000E+00 0 000E +00 0 000E+00 6140E + 07 RB48 0 000.1 + 00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 R D-89 0 000E +00 Ob00E*00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 SR 49 3 050E +09 0 000E*00 8740E+07 0 000E+00 0 000E*00 0 000E+00 481CE+08 SR 90 9 830t+10 0 000E *00 2410E*10 0000E+00 0 000E+00 0 000E+00 2 640E +09 SR 91 6580E+04 0 000E+ 00 2 660E+03 0 000E+00 0 000E+00 0 000E+00 3130E +05 SR 92 1030E *00 0 000E +00 4 440E 02 0 000E+00 0 000E+00 0 000E +00 2 030E *01 Y 90 8 480E+00 0 000E+00 2 280E41 0 000E +00 0 000E+00 0 000E +00 8 990E +04 Y 91M 0000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 Y 91 1030E+03 0 000E+00 2.760E +01 0 000E+00 0 000E+00 0 000E+00 5680E+05 Y 92 6 510E46 0 000E +00 1.900E-07 0 000E+00 0 000E+00 - 0 00DE*00 1.140E 01 Y 93 2 800E 02 0 000E+00 7.720E-04 0 000E+00 0 000E+00 0 000E+00 8 870E+02 l ZR-95 1 140E +02 3 640E *01 2 470E+01 0 000E+00 5 710E*01 0 000E+00 1.150E + 05 I I
l Offsit] 00se Calcut:ti:n Manual P ge 288 Of 313 Revision 2 Change O Attachment 12 [V Gaseous Effluent Pathway D0se Factors GRASS GOAT MILK DOSE FACTORS ADULT (m' 'mremlyr per uCl/sec) Nuclide Bone Liver Tbody fliyroid Kidney Lung Oltract ZR 97 5110E42 1.030E42 4 710E43 0 000E+00 1.560E 02 0 000E*00 3190E+03 NB45 0900E*03 5510E+03 2 900E+03 0 000E+00 $440E+03 0 000E+00 3 340E+07 NB 97 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 MO49 0 000E +00 3 030E+06 5700E+05 0 000E +00 6 860E+06 0 000E+00 7 020E*06 7C 9DM 3 D00E 01 1.100E +00 1.400E +01 0 000E*00 1.670E+01 5 400E 01 6 520E+02 TC 101 0 000E+00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E* 00 RU 103 1220E+02 0 000E +00 5270E+01 0.000E +00 4 670E+02 0 000E*00 1430E+04 RU-105 1030E44 0 000E+00 4 on0E 05 0 000E+00 1.330E-03 0 000E+00 6 290E 02 RU 106 2 450E+03 0 000E+00 3.100E+02 0 000E+00 4 730E+03 0 000E+00 1.580E* 05 RH 103M 0000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+06 0 000E +00 RH 106 0 000E +00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 AG 110M 6990E*06 6470E+06 3 840E +06 0 000E+00 1.270E +07 0 000E+00 2.640E +09 50122 7.210E *04 7.620E +04 9110E*05 1200E+04 3 550E+04 1550E+04 8 900E*06" l SB 124 3 090E *06 5840E+04 1.220E *06 7.490E +03 0 000E +00 2 410E+06 8 770E+07 SB 125 2 450E *06 2 740E +04 5840E+05 2 490E +03 0 000E +00 1890E*06 2 700E +07 k 1E 125M 195nr+06 7.0BOE+05 2 620E+05 5800E+05 7 950E+06 0 000E+00 7.810E+06 TE 127M 5490E+06 1900E+06 6 690E+05 t .400E +0S 2230E+07 0 000E+00 1840E+07 TE 127 8060E*01 2 890E+01 1.740E +01 5970E+01 3 280E+02 0 000E+00 6 360E+03 TE 129M 7.250E
- 06 2.710E+06 1.150E +06 2 490E+06 3 030E +07 0 000E+00 3 650E +07 TE 129 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0.000E +00 TE 131M 4 330E +04 2120E+04 1.770E +04 3 360E+04 2.150E+05 0 000E+03 2.100E + 06 TE 131 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 0 000E +00 TE 132 2.870E +05 1860E+05 1.740E +06 2 050E+05 1.790E* 06 0 000E+00 8790E+06 6130 $110E+05 1.510E+06 $950E+05 1.280E +08 2 350E+06 0 000E+00 1.300E+06 b131 3 560E+08 5 090E+08 2 920E+08 1670E+11 8720E+08 0 000E+00 1,340E +08 b132 1960E-01 5 200E-01 1.840E-01 1.840E +01 8 360E-01 0 000E+00 9 800Fi?
h133 4 760E+06 8280E+06 2.520E+06 1220E+09 1.440E +07 0 000E+00 7.440E +06 6134 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0.000E+ 00 0 000E+00 1-135 1670E+04 4 300E+04 1.610E+04 2.880E +06 6 990E+04 0 000E+00 4.920E+04 CS-134 1.700E + 10 4 030E*10 3 300E+10 0 000E+00 1.310E+10 4 330E+09 7.060E*0S CS-136 7.840E +06 3 090E+09 2.230E+09 0 000E+00 1.720E +09 2 360E+0S 3 520E+08 CS-137 2.210E +10 3.030E +10 1980E+10 0 000E+00 1030E+10 3 420E+09 5860E+0S CS 138 0 000E+00 0 030E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 A BA-139 5 640E-09 0 000E*00 0 000E+00 0 000Eo30 0.000E +00 0 000E 00 1.000E-08 B A 140 3 230E +06 4 050E+03 2110E +05 0 000E+00 1.380E *03 2 320E+03 6 650E*06
Offsit) 00se C:lculation M:nu:1 Paga 289 Of 313 Revision 2 ChanDe O Attachment 12 j (v Gaseous Effluent Pathway Dose Factors i GRASS-GOAT MILK DOSE FACTORS l ADULT 1 (m' ' mrem /yr per uCl/sec) Nuclide Bone uver Tbody Thyroid Kidney Lung Getract BA 141 0.000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 BA 142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0.000E +00 0 000E +00 LA 140 5 380E 01 2.710E-01 1.990E+04 0 000E*00 C.000E+00 0.000E+00 1.990E+04 L A 142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 3 640E 09
- CE 141 5 810E+02 3 930E+02 4 450E+01 0 000E+00 1.820E +02 0 000E+00 1.500E +06 CE 143 5020E*00 3 710E+03 4110E 01 0 000E+00 1.630E+00 0 000E+00 1.390E+05 CE 144 4 290E+04 1,790E+04 2 300E*03 0 000E+00 1000E +04 0 000E+00 1450E+07 PR 143 1910E+01 7.650E +00 9 450E 01 0 000E+00 4 410E+00 0 000E+00 8 350E*04 PH 144 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 00vE+00 0 000E+00 0 000E+00 ND 147 1.130E +01 1.310E +01 7.820E 01 0 000E+00 7.640E+00 0.000E +0D 0.270E*04 EU 154 2 840E+03 3 490E+02 2 480E+02 0 000E+00 1.670E+03 0 000E+00 2 530E+05 EU 155 3 950F+02 5610E+01 3 620E+01 0 000E +00 2 590E+02 0 000E+00 4 410E+04 W 187 7 870E+02 6.580E+02 2 300E+02 0 000E+00 0 000E+00 0 000E+00 2.160E+05 -
NP 239 4 390E 01 4 320E-02 2 380E 02 0 000E+00 1.350E-01 0 000E+00 8 860E*03 s V
Offsit) Dose C Icut: tion M:nW Pags 290 Of 313 R2 Vision 2 Ch:n03 0 Attachtnent 12 Garwus Effluent Pathway D0s0 Factors C GRASS GOAT. MILK DOSE FACTORS TEEN (rn' 'mrom/yr per uCl/ soc) Nuclide Bone Liver Tbody Thyroid Kidney Lung Oltract H-3 0 000E+00 2 030E *03 2 030E+03 2 030E+03 2 030E+03 2.030E +03 2 030E*03 C-14 6 700E +05 1.340E *05 1.340E +05 1.340E + 05 1.340E +05 1.340E +05 1.340E +05 NA 24 5330E*05 5 330E+05 5 330E*05 5 330E*05 5330E*05 6330E+05 5330E+05 P-32 3 780E*10 2 340E+09 1.470E *09 0 000E +00 0 000E +00 0 000E+00 3J.30E+09 - CR51 0 000E +00 0 000E*00 6 000E+03 3 330E+03 1.310E+03 8560E+03 1.010E +00 MN44 0 000E+00 1.680E+06 3 330E+05 0 000E+00 5010E*05 0 000E +00 3 440E+00 MN46 0 000E +00 9 010E44 1600E 04 0 000E+00 1.140E 03 0 000E+00 5 930E-02 FE-55 5 790E+05 4100E +05 9 570E +04 0 000E*00 0 000E+00 2 000E+05 1J80E*05 FE49 6 750E *05 1.580E
- 06 6090E+05 0 000E +00 0 000E+00 4 970E +05 3 730E+06 CO 57 0 000E+ 00 2 690E+05 4 $20E*05 0 000E*00 0 000E+00 0 000E +0D 5030E+06 C048 0 000E
- 00 9 540E+05 2 200E+00 0 000E+00 0 000E+00 0 000E +00 1.310E +07 C040 0 000E +00 3 340E+06 7 510E+00 0 000E +00 0 000E+00 0 000E+00 4 350E +07 N143 1420E +09 1.000E*08 4 810E+07 0 000E +00 0 000E +00 0 000E+00 1.590E*07 -
NI45 0130E-02 1.040E-02 4 730E 03 0 000E*00 0 000E+00 0 000E +00 5.640E 01 r- CU44 0 000E +00 4 790E*03 2.250E +03 0 000E+00 1210E *04 0 000E+00 3 710E+05 t ( ZN45 2 530E +08 8 780E+08 4 000E+08 0 000E+00 5620E+08 0 000E+00 3 720E+08 ZN49 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 BR42 0 000E +00 0 000E +00 6 670E+06 0 000E+00 0 000E +00 0 000E+00 0 00^5 +00 BR43 0 000E +00 0 000E +00 2 290E-02 0 000E +00 0 000E +00 0 000E+00 0 000E+00 DR 64 0 000E *00 0 000E +00 0 000E +00 0 000E *00 0 000E+00 0 000E+00 0 000E +00 BR-85 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RB 46 0 000E+00 5 670E+08 2 670E + 08 0 000E+00 0 000E+00 0 000E +00 8 400E+07 RB48 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 R049 0 000C+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 SR-89 5620E+09 0 000E*00 1.160E +08 0 000E+00 0 000E+00 0 000E +00 6 690E+08 SR 90 1390E+11 0 000E+00 3 430E*11 0 000E+00 0 000E +00 0 000E+00 3 900E+09 SR 91 1.210E+05 0 000E*00 4 810E+03 0 000E+00 0 000E+00 0 000E+00 5.480E+05 SR 92 1880E+00 0 000E+00 8 010E42 0 000E+00 0 000E+00 0 000E+00 4 790E+01 Y-90 1.560E +01 0 000E+00 4 200E 01 0.000E+00 0.000E +00 0 000E+00 1200E+05 Y 91M 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E+00 0 #0E+00 0 000E+00 Y-91 1.900E *03 0 000E+00 5 090E+01 0 000E +bo 0.000E +00 0 000E+00 7.780E +0S Y 92 1200E45 0 000E+00 3 480E-07 0 000E*00 0 000E+00 0 000E+00 3 300E-01 Y 93 5160E42 0 000E+00 1410E43 0 000E +00 0 000E+00 0 000E+00 1.580E *03 ZR-95 1.990E+02 6 200E+01 4 310E+01 0 ONE +00 9 200E+01 0 000E+00 1.450E+05 ZR 97 9 300E42 1.840E-02 8 480E 03 0CO 00 2 790E 02 0 000E+00 4 980E+03
l Offsit3 Dose Calcul: tion M:nu:1 P:g3 291 of 3 3 i R; vision 2 Ch:nge 0
-m Attachment 12
) Gaseous Effluent Pathway D0se Factors (V GRASS GOAT MILK DOSE FACTORS TEEN (m' 'rnrem/yr per uCl/sec)
Nuclkie Bone Uver itafy Thyro 6d Kidney Lung Gltract NB 95 1.090E + 04 9 370E+03 5100E+03 0 000E+00 9 080E+03 0 000E+00 4 010E+07 ND-97 0 000E*00 0 000E+00 0 000E* 00 0 000E+00 0 000E+00 0 000E+00 / 610E-09 , MO 99 0 000E+00 5470E+06 1.040E+06 0 000E+00 1250E+07 0 000E+00 9 800E+06 TC4MA 6 770E 01 1890E +00 2 450C+01 0 000E+00 2 810E*01 1.050E +00 1.240E+03 - TC 101 0.000E* 00 0 000E400 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 RU 103 2.180E +02 0 000E +00 9 310E+01 0 000E+00 7 670E+02 0 000E+00 1820E +04 R U-105 1.890E-04 0 000E400 7.290E-05 0 000E +00 2 370E-03 0 000E+00 1520E 01 RU 106 4 500E+03 0 000E+00 5670E+02 0 000E +00 8 680E+03 0 000E+00 2.160E +05 R H-103M 0000E+00 0 000E+00 0 000E*00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 RH 108 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+0D 0000E*00 AG.110M 1.100E+07 1.090E
- 07 6 650E+06 0 000E +00 2 000E+07 0 000E+00 3 070E +09 SB 122 9 310E*04 9 710E+04 1.180E *06 1.540E + 04 4 580E +04 2 000E*04 1.160F +07 l
SB 124 5510E+00 1020E+05 2150E +06 1250E +04 0 000E+00 4810E+06 1110E+08 ~ 50 125 4 380E*06 4 790E+04 1.030E+ 06 4190E+03 0 000E+00 3 850E406 3 410E+07 A TE 125M 3 600E +06 1300E+06 4 820E+05 1010E + 06 0 000E+00 0 000E+00 1060E +07 Q) I TE 127M 1010E407 3 5 DOE +00 1.200E +06 2 410E +06 4100E407 0 000E+00 2 520E+07 TE 127 iw90E+02 5 290E*01 3 210E +01 1030E +02 6 050E *02 0 000E+00 1.150E +04 1E 129M 1330C+07 4 920E*06 2100E+06 4 280E +06 5 550E+07 0 000E+00 4 9BOE +07 TE 123 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 TE 131M 7,890E + 04 3 780E+04 3150E+04 5 690E+04 3 940E+05 0 000E*00 3 030E +06 T E-131 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 TE 132 5130E+05 3 250E+05 3 000E +05 3 430E +05 3120E +06 0 000E+00 1030E+07 l130 8 990E +05 2 600E+06 1.040E +06 2120E +08 4 010E +06 0 000E+00 2 000E +C6 l131 6 450E +08 9 030E*08 4 850E+08 2 640E + 11 1500E +09 0 000E +00 1.790E +08 l132 3 480E 01 9110E41 3 270E 01 3 070E+01 1.430E +00 0 000E +00 3 970E-01 6133 8 690E+06 1470E *07 4 500E+06 2 060E*09 2 590E +07 0 000E+00 1.120E +07 l 114 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 1-135 2 960E *04 7 620E*04 2 820E+04 4 900E+06 1200E*05 0 000E +00 8440E+C4 CS 134 2 040E + 10 6 93t1E +10 3 210E+10 0 000E+00 2 200E*10 8 410E+09 8 620E+0S CS-136 1330E +09 5 250E *00 3 530E+09 0 000E+00 2 860E+09 4 510E+08 4 230E+0S CS 137 4 020E + 10 5340E*10 1800E +10 0 000E +00 1820E+10 7.060E +09 7 600E+08 CSA 38 0 000E + 00 0 000E+ 00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+' 7 BA 139 1040E 08 0 000C+00 0 000E+00 0 000E +00 0 000E*00 0 000E *00 9 310E48 f BA 140 5830E+06 7.140E +03 3 750E +05 0 000E +00 2 420E*03 4 800E +03 8 990E+C6
\ ) BA 141 0 000E +00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E*00 0 000E+00
OfIsit3 Dose C Icul: tion Manu 1 P:ga 292 of 313 R visl0n 2 Chingo 0
. Attachment 12 ,
Gaseous Effluent Pathway D0se Factors (, GRASS GOAT. MILK DOSE FACTORS TEEN (mmrom/yr per uCl/sec) Nut;l6de Bone Liver Tbody Thyroid Kidney Lung Oltract BA.142 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000F.+00 0 000E +00 0 000E +00 LA 140 9 700E41 4 750E41 1200E 01 0 000E+00 0 000E+00 0 000E+00 2.730E +04 LA 142 1.980E 12 6 780E 13 2190E 13 0 000E+00 0 000E+00 0 000E+00 2 670E 08 CE 141 1C60E+03 7.110E *02 8170E+01 0.000E+00 3 350E+02 0 000E+00 2 030E+06 - CE 143 9.2?OE +00 6720E+03 7?s00E 01 0 000E*00 3 010E+00 0 000E+00 2 020E+05 CC 144 7.900E404 3 270E+04 4 240E +03 0 000E+00 1.950E+04 0 000E+00 1.990E +07 PR 143 3 500E+01 1.400E+01 1=740E*00 0 000E+00 8130E+00 0 000E+00 1.150E+05 PR 144 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E *00 ND 14r 2.100E *01 2 370E+01 1420E+00 0 000E+00 1.390E +01 0 000E+00 8.530E +04 EU 154 4 700E*03 0070E+02 4 280E+02 0 000E+00 2.720E +03 0 000E *00 3 210E+05 EU 155 1.030E +03 9 970E+01 6170E+01 0 000E+00 3 900E+02 0 000E400 5.710E+05 W 187 1 440E+03 1.170E+03 4110E+02 0 000E+00 0.000E+00 0 000E+00 3.180E+05 NP 239 8 390E41 7 910E-02 4 390E42 0 000E*00 2 480E-01 0 000E+00 1.270E+04 ~ O - NJ
Offsite D0se Calculation Manual Page 203 of 313 Revision 2 Chango O Attachment 12 Gaseous Effluent Pathway D0se Factors GRASS-GOAT MILK DOSE FACTORS CHILD (m2'rnternlyr per uCl/ soc) Nuchde Bone Uver Tbody Thyroid Kidney Lung Ottract H-3 0 000E +00 3 200E*03 3.200E + 03 3 200E +03 3 2000 03 3 200E+03 3.200E +03 C 14 1650E+00 3 290E +05 3 290E +05 3 290E +05 3 290E+05 3 290E+05 3 290E +05 NA 24 1.110E+00 1.110E +00 1.110E+00 1 110E *06 1 110E *00 1.110E +06 1.110E +06 P 32 9 330E *10 4 370E+09 3 000E+09 0 000E +00 0 000E+00 0 000E+00 '580E+09 ~ CR41 0 000E+00 0 000E +00 1220E +04 6 793E *03 1800E+03 1.240E +04 6 490E+05 MN.54 0 000E+00 2 510E +06 6000E+05 0 000E +00 7 050E+05 0 000E+00 2.110E +0G MN46 0 000E +00 1570E 03 3 550E-04 0 000E +00 1900E-03 0 000E +00 2 280E 01 fE45 1450E*00 7,700E
- 05 2.390E +05 0 000E+00 0 000E*00 4 360E*05 1.430E +05 F E 59 1570E*00 2 630E*00 1.200E +06 0 000E +00 0 000E*00 7.350E* 05 2 640E +00 C047 0 000E+00 4 000E+05 9 320E+05 0 000E*00 0 000E+00 0 000E *0D 3 770E+00 C0 58 0 000E+00 1.400E +06 4 4a0E*00 0 000E+00 0 000E *00 0 000E +00 8500E+06 CO-00 0 000E +00 5180E *06 1.530E +07 0 000E + 00 0 000E +00 0 000E *00 2 870E+07 Ni-63 3 500E *09 1900E +08 1210E *08 0 000E +00 0 000E+00 0 000E +00 1.280E +07 **
Ni 05 10a0E 01 1.870E 02 1090E 02 0 000E+00 0 000E +00 OCJ0E+00 2 290E
- 00 CU44 0 000E + 00 8 410E+03 5 000E+03 0 000E*00 2 030E*04 0 002E +00 3 950E +05 ZN 65 4 000E+08 1.320E +09 8220E+00 0 000E *00 8 330E+08 0 000E +00 2 320E+08 ZN 09 0 000E+00 0 000E*00 0 000E +00 0 000E+00 9000E*00 0 000E +00 0 000E +00 BR62 0 000E
- 00 0 000E*00 1.330E + 07 0 000E +00 0 000E + 00 0 000E +00 0 000E +00 BR43 0 000E +00 0 000E+00 5 620E-02 0 000E+00 0 000E *00 0 000"*00 0 000E +00 BR 84 0 000E*00 0 000E+00 0 000E*00 0 000E +00 0 000E +00 0 000E +00 0 000E+00 BR 85 0 000E +00 0 000E +00 0 000E*00 0 000E +00 0 000E+00 0 000E +00 0 000E +00 R D-86 0 000E *00 1050E*09 6 4~ ~.+08 0 000E *00 0 000E+00 0 000E+00 6 770E +07 RD48 0 000E +00 0 000E +00 0 000E+00 0 000E+00 0 000E*00 0 000E +00 0 000E +00 RD49 0 000E *00 0 000E+00 0 000E +00 0 000E+00 0 000E +00 0 000E+00 0 000E*00 SR49 1.390E +10 0 000E+00 3 970E+08 0 000E+00 0 000E +00 0 000E +00 5.360E+08 SR 90 2 350E+11 0 000E+00 5 950E +10 0 000E +00 0 000E*00 0 000E +00 3190E *09 SR-91 2 970E +05 0 000E+00 1.120E +04 0 000E+00 0 000E+00 0 000E +00 6SCOE+05 SR 92 4 590E+10 0 000E +00 1840E-01 0 000E+00 0 000E+00 0 000E+00 8090E+01 Y 90 3 800E +01 0 000E+00 1030E +00 0 000E+00 0 000E+00 0 000E +00 1 100E+05 Y 91M 0 000E+00 0 000E*00 0 000E +00 0 000E +00 0 000E +00 0 000E+00 0 000E *00 Y 91 4 690E+03 0 000E +00 1.250E +02 0 000E *00 0 000E+00 0 000E+00 6 250E+05 Y 92 2 950E 05 0 000E +00 8 440E-07 0 000E +00 0 000E +00 0 000E+00 8 520E 01 Y 93 1270E 41 0 000E+00 *4 480E 03 0 000E+00 0 000E+00 0 000E+00 1.890E +03 ZR-95 4 610E + 02 1010E +02 9 030E*01 0 000E+00 1450E+02 0 000E+00 1.060E +05 l
l l
Offsit3 D0se C:lculatl0n Minu:1 Pcge 294 Of 313 Revision 2 Change 0 Attachment 12 p] g Gase0uo Effluent Pathway D0se Factors GRASS GOAT MILK DOSE FACTORS l i CHILD (In' 'rnremlyr per uCi/sec) I Nuclide Bone Liver Tbody Thyroid Kidney Lung Gittact ZR 97 2 200E 01 3 270E 02 1.930E 02 0 000E+00 4 690E 02 0 000E+00 4 20E+03 NS 95 3 810E*04 1,4BOE +04 1.000E +04 0 000E+00 1390E+04 0.000E+00 2.750E+07 NB 97 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 1.740E 07 MOM 0000E+00 9 950E+06 2 460E+06 0 0002+00 2.120E+07 0 000E+00 8 230E+06
- TC 99M 1.550E+00 3 040E +00 5040E+01 0 000E+00 4 420E+01 1.550E+00 1.730E +03 TC 101 0 000E400 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 RU 103 5150E+02 0 000E +00 1980E+02 0 000E+00 1.300E +03 0 000E+00 1330E+04 RU 105 4 590E 04 0 000E *00 1.600E 04 0 000E +00 4 030E-03 0 000E+00 2 990E 01 RU 106 1.110E +04 0 000E*00 1.380E+03 0 000E+00 1.500E+04 0 000E*00 1.720E +05 RH 103M 0000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E*06 0 000E +00 RH 100 0 000E*00 0 000E +00 0 000E+00 0 000E +00 0.000E +00 0 000E+00 0 000E+00 AG 110M 2 510E*07 1.690E+07 1.350E +07 0 000E+00 3150E+07 0 000E400 2 010E+09 SB 122 7 680E *04 8 010E +04 9.700E+05 1.270E +04 3 780E*04 1650E+04 9 540E+06 *- l SB 124 1.300E +07 1690E*05 4 570E+06 2 B80E+04 0 000E+00 7.243E+06 8150E+07
$B 125 1040E+07 8050E+04 2190E+06 9 670E+03 0 000E+00 5820E+06 2 490E +07 V TE 125M 8 8ME+06 2 400E +06 1,180E +06 2 480E *06 0 000E+00 0 000E+00 8 540E*06 TE 127M 2 500E+07 6 720E *00 2 DGOE*06 5970E+06 7.120E +07 0 000E+00 2020E+07 TE 127 3 670E*02 9 910E+01 7.880E +01 2 540E402 1.050E *03 0 000E+00 1440E + 04 TE 129M 3 270E+07 9130E+06 5 080E+06 1.050E+ 07 9 600E+07 0 000E +00 3 990E+07 T E 129 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 7.340E 09 TE 131M i920E+05 8 640E +04 7.070E +04 1.370E + 05 6 430E*05 0 000E+00 2 690E+06 1E 131 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0.000E+00 0 000E +00 TE 132 1.230E +06 5420E+05 6 550E*05 7.900E +05 5040E+00 0 000E+00 5 460E+06 l130 2100E+06 4 250E+06 2_190E +06 4 680E+08 6350E+06 0 000E+00 1990E +06 1131 1570E*09 1.570E +09 8 950E+08 5210E+11 2 580E+09 0 000E+00 1400E *08 l132 8 230E 01 1.510E+00 6 560E-01 7.020E+01 2.320E+00 0 000E+00 1.780E +00 1-133 2110E407 2 610E+07 9 880E+06 4 850E+09 4 350E+07 0 000E+00 1.050E+07 l134 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 1-135 - 7.000E+04 1200E+05 5960E+04 1 100E+07 1.930E+05 0 000E+00 9 600E+04 CS 134 6790E+10 1.110E+11 2 350E+10 0 000E+00 3 450E+10 1.240E +10 6 010E+08 CS-136 3 010E+09 8280E+09 5.360E+09 0 000E+00 4 410E+09 6 580E+08 2.910E+0S CS 137 9 670E +10 926CE*10 1.370E +10 0 000E+00 3 020E+10 1.090E +10 5000E+00 CS 138 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00
( BA 139 2 560E 05 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 14BOE C6 B A 140 1410E+07 1.230E+04 8 210E+05 0 000E+00 4 010E+03 7.340E+03 7.120E +06
- -. ,--- y
Offsite D0so Calculation Manual Pa0e 295 of 313 Revision 2 Change 0 . Attachment 12 l Gaseous Effluent Pathway Dose Factors GRASS GOAT MILK DOSE FACTORS CHILD (m'
- mrem /yr per UCl/sec) iduclide Bone Liver Tbody Thyroid Kidney Lung Gftract BA 141 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E *00 0 000E +00 BA 142 0 000E+00 0 OtCE +00 0 000E *00 0 000E+00 0' ODE +00 0 000E +00 0 000E+00 LA 140 2 310E*00 8 090E 01 2.730E-01 0 000Z+00 0 000E+00 0 000E+00 2 260E*04 LA 142 4 770E 12 1 $20E 12 4 770E 13 0 000E+00 0 000E+00 0 000E+00 3 020E 07 CE 141 2 620E+03 1.310E +03 1940E+02 0 000E+00 5730E+02 0 000E+00 1.630E+06 CE 143 2 270E+01 1.230E +04 1.780E *00 0 000E +00 5.150E+00 0 000E+00 1.000E *05 CE 144 1950E +05 6100E *04 1.040E *04 0 000E+00 3 380E+04 0 000E+00 1.590E +07 PR 143 8070E*01 2 000E*01 4 300E*00 0 000E+00 1410E+01 0 000E+00 9 350E+04 PR 144 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 tid 147 5 340E+01 4 320E *01 3 350E+00 0 000E+00 2 370E+01 0 000E+06 6850E+04 EU 154 1 130E *04 1020E+03 9 2 DOE +02 0 000E +00 4 470E+03 0 000E+00 2 300E*05 EU 155 2 300E+03 1.700E
- 02 1330E *02 0 000E+00 6 630E+02 0 000E+00 4 250E+05 W 187 3 490E*03 2 070E +03 9 770E+02 0 000E +00 0 000E+00 0 000E+00 2 900E+05 "
f4P 239 2 000E+00 1480E-01 1.040E-01 0 000E +00 4 280E-01 0 000E +00 1.100E +04
Offslta D0se Cciculation Manual Pcgo 296 of 313 R viSI:n 2 Change 0 l s Attachment 12 Gaseous Elfluent Pathway D0se Factors A GRASS GOAT MILK DOFE FACTORS INFANT (m'
- mrem /yr per uCl/sec)
Nuclide Bone Uver Tbody Thyroid Kidney Lung Ottract ! H-3 0 000E+00 4 800E +03 4 800E+03 4 800E+03 4 860E+03 4 860E+03 4 800E+03 C 14 3 230E+00 6890E*05 6 890E+05 6 890E+05 6 890E+05 6 890E+05 6 890E+05 NA 24 1.930E+ 06 1930E+00 1930E+00 1.930E+00 1930E+06 1930E+06 1930E+0S P 32 1920E+11 1130E*10 7 450E +09 0 000E+00 0 000E+00 0 000E+00 2 600E+09 C R-51 0 000E+00 0 000E+00 1940E+04 1260E+04 2.700E +03 2 460E+04 5 650E+05 MN-54 0 000E+00 4 670E+00 1 M0E+00 0 00CE+00 1.040E +06 0 000E+00 1.720E +06 MN46 0 000E+00 3 850E-03 6 630E 04 0 000E+00 3 310E 03 0 000E +00 3 490E 01 FE45 1700E +00 1 130E+00 3 030E+05 0 000E+00 0 000E+00 5540E+05 1.440E
- 05 FE59 2 920E *00 5110E+06 2 010E+00 0 000E+00 0 000E+00 1.SiOE+06 2 440E+06 CO 57 0 000E*00 1070E406 1350E+00 0 000E+00 0 000E +00 0 000E+0D 3.600E + 06 C048 0 000E+00 2 910E*00 7 270E +06 0 000E +00 0 000E+00 0 000E+0C 7.200E +06 C040 0 000E+00 1.000E +07 2500E+07 0 000E+00 0 000E*00 0 000E+00 2 520E*07 N143 4190E + 09 2 590E+0B 1.450E*08 0 000E+00 0 000E+00 0 000E*00 1.290E+07 -
Nf65 4 210E 01 4 770E 02 2.170E 02 '000E+00 0 000E+00 0 000E+00 3 630E+00 g' CU44 0 000E + 00 2 090E +04 9 680E *03 0 000E+00 3 540E +04 0 000E *00 4 290E+05 ZN-65 6660E+08 2 200E+09 1.050E +09 0 000E+00 1.110E +09 0 000E +00 1.930E+03 ZN49 0 000E
- 00 0 000E*00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 DR 82 0 000E *00 0 000E+00 2330E+07 0 000E+00 0 000E+00 0 000E +00 0 000E +00 BR-83 0 000E+00 0 000E +00 1190E 01 0 000E+00 0 000E +00 0 000E+00 0 000E +00 BR 84 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 DR 85 0 000E+00 0 000E+00 0 000E+00 0.000E+00 0 000E+00 0 000E +00 0 000E+00 RB 86 0 000E+00 2 670E +09 1320E+09 0 000E +00 0 000E+00 0 000E +00 6 830E+07 RD80 0 000E+00 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E +03 0 000E +00 R B-89 0 000E+00 0 000E+00 0 000E+00 0 000E +00 0 000E +00 0 000E+00 0 000E +00 SR 89 2 640E
- 10 0 000E+00 7 580E+08 0 000E+00 0.000E +00 0 000E+00 5 430E+08 SR 90 2 550E+11 0 000E+00 6500E+10 0 000E+00 0 000E +00 0 000E+00 3.190E+09 SR-91 8180E+05 0 000E +00 2 240E+04 0 000E+00 0 000E+00 0 000E*00 7 310E+05 SR 92 9 700E* 00 0 000E+00 3 620E 01 0 000E +00 0 000E+00 0 000E+00 1OCOE+02 Y! 8.160E
- 01 0 000E+00 2190E+00 0 000E+00 0 000E +00 0 000E+00 1.130E +05 -
Y 91M 0000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 Y 91 8 800E*03 0 000E+00 2.340E+02 0 000E+00 0 000E+00 0 000E+00 6.310E +05 Y 92 6 270E 05 0 000E+00 1.760E-06 0 000E+00 0.000E *00 0 000E+00 1200'i+ 10 Y 93 2 700E-01 0 000E +00 7.350E-03 0 000E+00 0 000E+00 0 000E+00 2.130E +03 ZR 95 8190E+02 2 000E+02 1420E +02 0 000E+00 2.150E +02 0 000E+00 9 940E+00 ) U
Offsit3 D0se C:lculation M:nu:1 Pcon 297 Of 313 Revision 2 Chan0e O Attachment 12 b Gaseous Effluent Pathway D0se Factcrs GRASS GOAT MILK DOSE FACTORS I INFANT (mi* mrem /yr per uCl/sec) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ZR 97 4 790E 01 8 220E 02 3 760E-02 0 000E+00 8.290E-02 0 000E+00 5240E+03 NB 95 7.120E +04 2 930E+04 1.690E +04 0 000E+00 2.100E +04 0 000E+00 2 470E+07 NB-97 6 590E 12 1.410E 12 5 070E 13 0 000E+00 1.100E 12 0 000E+00 4 440E 07 MO 99 0 000E +00 2 540E+07 4 960E+06 0 000E +00 3 800E+07 0 000E+00 8 830E+06 ' T C-99M 3 230E +00 6.660E +00 8 570E+01 0 000E+00 7.160E +01 3 4SOE+00 1.930E +03 TC 101 0 000E+00 0.000E +00 0 000E+00 0 000E+00 0 000E+00 0.000E +00 0 000E+00 RU 103 1.040E *03 0 000E+00 3 490E+02 0 000E+00 2170E*03 0.000E400 1270E+04 RU-105 9 670E-04 0 000E +00 3 260E 04 0 000E+00 7.110E 03 0.000E +00 3 B'AE 01 RU 106 2 280E+04 0 000E+00 2 850E+03 0 000E +00 2 700E+04 0 000E+D0 1.730E +05 RH 103V 0 000E+00 0 000E +00 0 000E+00 0 000E+00 0 000E+00 0 000E+Cio 0000E+00 RH 10'. 0 000E+00 0 000E*00 0 000E+00 0.000E +00 0 000E+00 0 000E+00 0 000E+00 AG 110M 4 630E+07 3.380E+07 2.240E+07 0 000E+00 4 840E+07 0 000E+00 1.750E +09 5B 122 7 680E +04 8 010E*04 9.700E +05 1.270E+04 3 780E+04 1650E+04 9.540E+00 " l I
&B 124 2 510E +07 3 700E+05 .390E+06 6 670E+04 0 000E+00 1.570E +07 7.750E +07 SB 125 1.790E +07 1.740E *05 3 690E+06 2 250E+04 0.000E+00 1,130E+ 07 2.390E+07 \
TE 125M 1.810E*07 6.050E+06 2 450E+06 6 090E+06 0 000E+00 0 000E+00 8620E+05 TE 127M 5050E+07 1680E+07 6120E+06 1.460E+07 1.240E+08 0 000E+00 2 040E*07 TE 127 7 800E*02 2 610E+02 1.680E + 02 6 350E+02 1.900E+ 03 0 000E+00 1640E +04 TE 129M 6 710E +07 2 300E+07 1.030E+07 2 580E+07 1680E +06 0 000E+00 4 010E+07 TE 129 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 2 000E-06 TE 131M 4 050E+05 1.630E+05 1350E+05 3 310E+00 1.120E+06 0 000E+00 2.750E + 06 TE 131 0 000E*00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 TE 132 2 520E*06 1.250E +06 1.170E+06 1.840E +06 7.820E +06 0 000E+00 4 620E+06 L130 4 320E+06 9 510E+06 3 820E+06 1.070E+09 1.040E+07 0.000E+00 2 040E +06 b131 3 270E+09 3 850E+09 1.690E +09 1.270E +12 4 500E+09 0 000E+00 1.370E +08 L132 1.710E +00 3 470E +00 1.230E +00 1630E+02 3 870E +00 0 000E+00 2 810E+00 b133 4 4SOE +07 6 490E+07 1900E +07 1.180E +10 7 630E+07 0 000E+00 1.1000 +07 1134 0 000E+00 0 000E+00 0 000E+00 1.210E-09 0 000E+00 0 000E+00 0 000E+ D L135 1.460E+05 2 900E+05 1.060E +05 2 600E+07 3 230E +05 0 000E+00 1.050E +05 CS 134 1.090E+11 2 040E+11 2 060E+10 0.000E+00 5 250E+10 2.150E+10 5 540E+0S CS 136 5 880E+09 1.730E+10 6 450E+09 0 000E+00 6900E+03 1410E+09 2 630E+08 CS 137 1540E +11 1810E+11 1.280E +10 0 000E+00 4 850E +10 1960E+10 5 650E+08 CS 138 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 BA 139 5 450E-08 0 000E +00 1580E-09 0 000E+00 0 000E+W 0 000E +00 3 450E-M O BA 140 2 890E+07 2.890E +04 1.430E +06 0 000E+00 6 870E+03 1.780E+04 7110E +M
Offsits 00se Cdculitl0n M:nual Page 298 of 313 Revision 2 ChanDe O f Attachment 12 I Gaseous Effluent Pathway Dose Factors GF ASS-GOAT-MILK DOSE FACTORS INFANT (m mrem /yr per uCl/sec) Nuchde Bone Liver Tbody Thyroid K6dney Lung Ottract BA 141 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 DA 142 0 000E+00 0 000E *00 0 000E+00 0 000E+00 0 000E+00 0 000E+00 0 000E +00 LA 140 4 840E+00 1,910E +00 4 900E41 0 000E+00 0 000E+00 0 000E +00 2 240E+04 LA 142 0 000E+00 0 000E +00 0 000E+00 0 000E *00 0 000E+00 0 000E*00 0 000E+00 ' cE 141 5200E+03 3.170E+03 3 730E+02 0 000E+00 9.780E402 0 000E+00 1.640E+06 CE 143 4 800E*01 3180E *04 3 030E+00 0 000E+00 9 270E.+00 0 000E+00 1.800E+05 CE.144 2 790E405 1,140E+05 1.$GOE+04 0 000E+00 4 620E+04 0 000E+00 1600E+07 PR 143 1.790E+02 6710E+01 8 890E+00 0 000E+00 2 490E+01 0 000E+00 9 470E+04 PR 144 0 000E+00 0 000E*00 0 000E+00 0 000E+00 0 000E*00 0 000E+00 0 000E+00 ND-147 1.000E+01 1.090E +02 6 660E+00 0 000E+00 4190E+01 0 000E+0v 6 890E+04 EU 154 1.300E +04 1.800E +03 1080E+03 0 000E+00 4 890E+03 0 000E +00 2 250E+05 EU 155 2050E+03 3 000E+02 1580E +02 0.000E +00 6 850E+02 0 000E+00 4100E+05 W 187 7.350E
- 03 6110E+03 1,770E +03 0 000E+00 0 000E+00 0 000E*00 3 000E+05" NP-239 4 360E+00 3 900E-01 2 210E 01 0 000E+00 7.780E41 0 000E+00 1.130E +04 Oa -
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l l Offsib Dose C:lculation M:nu:1 Pege 299 of 313 l R: vision 2 Change 0 i Attachment 13 - Environmental Monitoring Sites for REMP ; i O SAMPi.E SITE SECTOR DISTANCE km ml i DESCRIPTION
?
, DR1 NW 0.6 0.4 Onsite, Along Cliffs DR2 WNW 2.7 1.7 Rt. 765, Auto Dump DR3 W 2.3 1.4 Rt. 765, Giovanni's Tavem (Knotty Pine) DR4 WSW - 2.0 1.2 Rt,765, Across from White Sand Drive DRS SW 2.4 1.5 Rt. 765 at Johns Creek DR6, A4 SSW 2.0 1.8 Rt. 765 at Lusby, Frank's Garage l i DR7, A1, Ib4, Ib5, Ib6 0 0.7 0.5 Onsite, before entrance to Camp Conoy i DR8, A2 SSE 2.5 1.5 Camp Conoy Road at Emergency ! Siren DR9, A3 SE 2.6 1.6 Bay Breeze Road DR10 NW 6.4 4.0 Calvert Beach Rd & Decatur St DR11 WNW 6.6 4.1 Dirt Road off Mackall Rd & Parran i Rd DR12 W 6.7 4.2 Bowen Rd & Mackall Rd DR13 WSW 6.1 3.8 Mackall Rd near Wallville DR14 SW 6.4 4.0 Rodney Point
- DR15 SSW 6.2 3.9 Mill Bridge Rd & Tumer Rd
, DR16 8 6.5 4.1 Across from Appeal School - DR17 SSE 5.9 3.7 Cove Point Rd & Little Cove Point : Rd DR18 SE 7.1 4.5 Cove Point ~ O DR10 DR20' NW NNW 4.4 0.4 2.8 Long Beach 0.3 Onsite, near shore DR21, AS, Ib7, Ib8, Ib9 WNW . 19.3 12.1 Emergency Operations Facility l DR20 S 12.5 7.8 Solomons Island DR23 ENE 12.6 7.9 Taylors Island, Carpenter's Property Wai NNE 0.2 0.1 Intake Area Wa2, la1, la2 N 0.3 0.2 Discharge Area Wb1 ESE 0.6 0.4 Shoreline at Barge Road Ibi,Ib2,Ib3, SSE 2.6 1.6 Garden Plot off Bay Breeze Rd 4 la4,la5 (Area not influenced by Plant Patuxent River '
- Discharge) la3 E 0.9 0.6 Camp Conoy in6 NNW 10.7 6.7 Kenwood Beach i
O ' 4 Distance and direction from the central point of the two containment buildings, i
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Offee Dose Calculation Manual Pcos 300 of 313 Revision 2 Change 0 - ; Attachment 14 ! Radiological Environmental Monitoring Program , Surveillances for Direct Radiation I i PARAMETER UNITS FREQUENCY LLD - ACTION LEVEL ! GAMMA DOSE"8 mR at least quarterly
- N/A l
-i i
(f) Each sample point shall be monitored using two or more doslmeters OR one instrument for measuring and recording dose rate continuously. (2) ~ LLD for TLDs used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4,13, t i b I k 4 d I l d f a 3 1 e O
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l Offsit] Dose Calculation Manu:1 P:03 301 of 313 R: vision 2 Change 0 Attachment 15 h i _ Radiological Envis amental Monhoring Program Surveillar'aes for Airborne Activity (NY G RADIOlODINE CANNISTER PARAMETER UNITS FREQUENCY LLD ACTION LEVEL
- l131 pCi/m 8 at least weekly 0.07 0.9 PARTICULATE FILTER (1) .
PARAMETER UNITS FREQUENCY LLD ACTION LEVEL
- Gross Beta Activity pCl/m' at least weekly m 0.01 N/A * -
Cs 134 pCl/m' at least quarteriy W 0.05 10.0 i V Cs-137 pCl/m' at least quarterly W 0.06 20 0 (1) All samples consist of cot.tinuous sampler operation with sample collectisn weekly, or more frequently if required by dust loading. (2) Analyze for gross beta activity 24 hours or more after sampling to allow for radon and thoron daughter decay. (3) Although there is not an ACTION Level for gross beta activity, if this parameter is greater than ten times the yearly mean of the control sample, perform GAMMA ISOTOPIC ANALYSIS on the individual sample. (4) Perform a OAMMA ISOTOPIC ANALYSIS of a quarterly COMPOSITE SAMPLE. A separate COMPOSITE SAMPLE shall be prepared for each sample location, A1 thru AS. Each COMPOSITE SAMPLE shall be a prepared from individual particulate filter samples collected during the applicable calendar quarter and from a single location. (5) If an ACTION Levelis exceeded, check the initiatin0 conditions listed in sections REMP SECTION 5.c and REMP SECTION 5.d, and perform the corrective actions specified in section REMP SECTION 7.d and/or REMP SECTION 7.e. C/
Offsite Dose C:lculati:n Manu:1 P:02 302 of 313 R; vision 2 Change O Attachment 16 g Radiological Environmental Monitoring Program Surveillances for Watertiome Activity SURFACE WATER DAMPLE W PARAMETER UNITS FREQUENCY LLD ACTION LEVEL
- H3 pCl/l at leasi quarterly 2000W 20,000 W Mn-54 pCl/l at least monthly 15 1000 Fe 59 pCl/l at least monthly 30 400 Co 58 pCl/l at least monthly 15 1000 Co-60 pCl/l at least monthly 15 300 Zn-65 pCl/l at least monthly 30 300 Zr 95 / Nb-95 pCl/l at least monthly 15 400 1131 pCl/l at least monthly 1 2 Cs 134 pCill at least monthly 15 30
!O V Cs 137 pCl/l at least monthly 18 50 ' Ba 140 / La 140 pCl/l at least monthly 15 200 SHORELINE SEDIMENT SAMPLE PARAMETER UNITS FREQUENCY LLD ACTION LEVEL A Cs 134 pCl/kg, dry at least semiannually 150 N/A Cs 137 pCl/kg, dry at least semlannually 180 N/A (f) The water sample shall be a composite of individual samples collected over a 1 month period. (2) If an ACTION Level is exceeded, check the initiating conditions listed in sections REMP SECTION 5.c and REMP SECTION 5.d. and perform the corrective actions specified in section REMP SECTION 7.d and/or REMP SECTION 7.e. (3) If a drinking water pathway does not exist, a value of 3000 pCl/l may be used. (4) If a drinking water pathway does not exist, a value of 30,000 pCl/l may be used. .f) v i
Offsit] Dose C;lculation M:nu:1 P:02 303 of 313 R: vision 2 Change O Attachment 17 Radiolo0lcal Environmental Monitoring Program Suveillances for ingestible Activity [-~) v FISH ANDINVERTEBRATES W PARAMETER UNITS FREQUENCY LLD ACTION LEVEL "' Mn54 pCl/k0, wet A 130 30,000 Fe-59 pCl/kg, wet
- 260 10,000 Co 58 pCl/kg, wet A 130 30.000 Co-00 pCl/kg, wet
- 130 10,000 Zn-65 pCl/kg, wet A 260 20,000 Cs 134 pCl/kg, wet
- 130 1000 M 150 2000 Cs 137 pCl/kg, wet MILK PARAMETER UNITS FREQUENCY LLD ACTION LEVEL *)
l l131 pct /l, wet at least monthly (*) 1 3 l Cs 134 pCl/l, wet at least monthly W 15 60 Cs 137 pCl/1, wet at least monthly
- 18 70 l Ba 140 / La 140 pCl/l, wel et least monthly W 15 300 FOOD PRODUCTS PARAMETER UNITS FREQUENCY LLD ACTION LEVEL
- l131 pCl/kg, wet at least monthly
- 60 100 l Cs 134 pCl/kg, wet at least monthlyW 60 1000 Cs 137 pCl/kg, wet at lecst monthly
- 80 2000 l (f) Edible portions of the fish and invertebrates shall be used for analysis.
(2) The fish and invertebrates shall be sampled at least once per year in season, or semiannually if they are not seasonal. I (3) The food products shall be sampled during the growing season. I (4) The milk samples need be collected and analyzed only if the milk is commercially available in quantities greater than 010 liters per year (see NUREG-0133,5.3.1.1). (5) If an ACTION Levelis exceeded, check the initiating conditions listed in sections REMP SECTION 5.c and REMP SECTION 5.d, and perform the correctivo actions specified in section REMP SECTION 7.d and/or REMP SECTION 7.e. l l ll l V) l
Offr.ita Dose Cticul: tion M:nuil P:De 304 of 313 R: vision 2 Ch:nge O Attachment 18 Map of Environrnental Monitoring Sites for REMP (5 Km Radius) I
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Off site Dose Calc.ulation Manual Page 305 of 313 Revision 2 Change O Attat.hrnent 19 Map of Environtnental Monitonru) Sites for REMP (10 Mile Radius) "~~ T y i .#4 '. ." ~~ '" ~ b
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I OffLt3 Dose C:lculation ihnici Pag? 300 of S13 R:visl:n 2 Ch:nDe O Attachment 20 Environmental Monitoring Sites for ISFSI \ GTAT!ON DESCRIPTION DISTANCE' DIRECTIONS (Kilometers) (Sector) AIR SAMPLERS 3 A1 On Site Beforo Entrance to Camp Conoy 0.7 SE l SFA1 Meteorological Station 0.4 NW ' SFA2 CCNPP Visitors Center 0.7 NNE SFA3 North Northwest of ISFSI 0.1 NNW SFA4 South of ISFSI 0.1 S
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Ij,D LOCATIONS SFOR1 Colloce.ted with Plant TLD #159 0.1 SW SFDR2 Collocated with Plant TLD #160 0.1 N l GFOR3 Collocated with Plant TLD #161 0.1 NNE SFDR4 Collocated with Plant TLD #162 < 0.1 NE SFDRS Collocated with Plant TLD #163 < 0.1 E FFDRB Collocated with Plant TLD #164 0.1 ESE SFDR7 CCNPP Visitors Center 0.7 NNE SFDR8 North Northwest of ISFSI 0.1 *NNW l SFDR9 South of ISFSI 0.1 S SFDR10 North Northwest of ISFSI 0.1 NNW SFDR11 West Northwest of ISFSI 0.1 WNW SFOR12 West of ISFSI < 0.1 W - SFDR13 South Southwest of ISFSI < 0.1 SSW SFDR14 South Southeast of ISFSI 0.1 SSE ( SPDR15 SFDR16 East Northeast of ISFSI West Southwest of ISFSI
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< 0.1 ENE WSW DR72 On Site Before Entrance to Camp Coaoy 0.7 SE l DR30 Meteorolc;;!d Station 0.4 NW VEGETATION SFb1 Meteorolo0lcal Station 0.4 NW SFb2 CCNPP Visitors Center 0.7 NNE SFb3 North Northwest of ISFSI 0.1 NNW SFt>4 South of ISFSI 0.1 S SFb5 On Site Before Entrance to Camp Conoy 0? SE l SolL SFS1 Meteorological Station 0.4 NW SFS2 CCNPP Visitors Center 0.7 NNE SFS3 North Northwest of ISFSI 0.1 NNW SFS4 South of ISFSI 0.1 S SFSS On Site Before Entrance to Camp Conoy 0.7 SE l h'
V Distance and direction from the Central Point of the ISFSI. Common to both the REMP and the ISFSIMP.
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OffMt2 Dose C Icut: tion M:nu:1 Page 307 of 313 Revision 2 Change O Attachment 21 Map of Environmental Monitoring Sites for ISFSI r NNE NNW , _ _ , _ _,,
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Offsite Dose Celcut: tion Minu:1 Pace 308 of 313 , t R vision 2 Change 0 : ! Attachrnent 22
- Map of Environmental Monitoring Sites for ISFSI (ENLARGED)
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Offsite Dosa Ccicut: tion Minuit Page 309 of 313 l Revision 2 Change 0 Attachment 23 O Effluent Radiation Monitors Description Radiation Radiation Element Indicator Liquid Waste Discharge Radiation Monitor 0-RE 2201 0 RI 2201 Steam Generator Blowdown Effluent Radiation Monitor 1 RE 4095 1 RI-4095 Steam Generator Blowdown Effluent Radiation Monitor 2 RE-4095 2 RI-4095 Steam Generator Blowdown Tank Radiation Monitor 1 RE 4014 1 RI 4014 Steam Generator Blowdown Tank Radiation Monitor 2 RE-4014 2 Rl 4014 Wide Range Gas Monitor, Low Range 1 RE 5416 1 RIC 5415 Wide Range Gas Monitor, Low Range 2 RE 5416 2 RIC 5415 Westin0 house Plant Vent Stack Monitor 1 RE 5415 1 RI 5415 Westinghouse Plant Vent Stack Monitor 2 RE 5415 2 RI 5415 GASEOUS RADWASTE TREATMENT SYSTEM Radiation 0-RE 2191 0-RE 2191 Monitor Accident Monitors Not Addressed By The ODCM Wide Range Gas Monitor, Mid Range 1 RE 5417 Wide Range Gas Monitor, High Range 1 RE 5418 Wide Range Gas Monitor, Mid Range 2 RE 5417 Wide Range Gas Monitor, High Range 2 RE 5418 O O i 1
Offsite Dose Calculatl0n Manual Page 310 Of 313 Revision 2 Change 0 j Attachment 24 List OF Effective Pages Page No Change No Page No Change No. Page No Change No 1 0 31 0 61 0 2 0 32 0 62 0 3 0 33 0 63 0 4 0 34 0 64 0 b 0 35 0 65 0 6 0 36 0 06 0 7 0 37 0 67 0 8 0 38 0 68 0 9 0 39 0 69 0 10 0 40 0 70 0 11 0 41 0 71 ,0 12 0 42 0 72 0 13 0 43 0 73 0 14 0 44 0 74 0 16 0 45 0 75 0 16 0 46 0 76 0 17 0 47 0 77 0 18 0 SS 0 78 0 19 0 49 0 79 0 20 0 50 0 80 0 21 0 51 0 81 0 22 0 $2 0 82 0 23 0 53 0 83 0 24 0 54 0 84 0 25 0 55 0 85 0 26 0 56 0 86 0 27 0 57 0 87 0
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Offsite D0s0 Calculation Manual Pa0e 312 of 313 Revision 2 Change O Attachment 24 List OF Effectivo Pages Page f40 Change 74o Page f4o Change 74o. Pagef40 Change IJo 101 0 211 0 241 0 102 0 212 0 242 0 163 0 213 0 243 0 184 0 214 0 244 0 105 0 215 0 245 0 106 0 210 0 240 0 187 0 217 0 247 0 188 0 218 0 248 0 189 0 219 0 249 0 190 0 220 0 250 0 191 0 221 0 251 0 192 0 222 0 252 0 193 0 223 0 253 0 i 104 0 224 0 254 0 195 0 225 0 255 0 190 0 226 0 2'33 0 197 0 227 0 257 0 198 0 220 0 258 0 109 0 229 0 259 0 200 0 230 0 260 0 201 0 231 0 261 0 202 0 232 0 262 0 203 0 233 0 263 0 204 0 234 0 204 0 205 0 235 0 265 0 200 0 230 O 206 0 207 0 237 0 267 0 208 0 230 0 200 0 209 0 239 0 269 0 210 0 240 0 270 0
Offsite Dose Calculation Manual Page 313 of 313 R0 vision 2 Chan00 0 Attachment 24 Ust OF Effective Pages Page fJo Change No Page No Change No Page No Change No 271 0 301 0 272 0 302 0 273 0 303 0 274 0 304 0 275 0 305 0 270 0 300 0 277 0 307 0 278 0 308 0 279 0 309 0 260 0 310 0 281 0 311 0 242 0 312 0 283 0 313 0 264 0 285 0 M 0 287 0 26U 0 289 0 290 0 291 0 292 0 293 0 294 0 295 0 296 0 297 0 298 0 299 0 300 0 I l
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