Text

Rev 1,Change 0 to Odcm
	ML20064F201
Person / Time
Site:	Calvert Cliffs
Issue date:	08/26/1993
From:	Hill J, Wendell R; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20064F188	List: ML20064F187; ML20064F201; ML20064F222; ML20064F674;
References
	PROC-930826, NUDOCS 9403150214
	Download: ML20064F201 (247)
	v • d • e

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ATTACHMENT (1)

ODCM TEXT WITH CHANGES e

t 9403150214 931231 PDR ADOCK 05000317 R. PDR

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OFFSITE DOSE CALCULATION MANUAL Revision 1, Change 0 For The Baltimore Gas And Electric Company Calvert Cliffs Nuclear Power Plant PREPARED BY: & < DATE: 7- // - 93 RE ogram er l

REVIEWED BY:

//b _A L Genefal Supervisor - Chemistryd

_- - DATE: f /D f3

_. / /

i REVIEWED BY: d h d. cwu,W ,PM Atre:torj5nvironmental Programs, Corporate Affairs Group DATE: 2 73 REVIEWED BY: DATE: 723J General Supe. 'nor - Tect6dal Services, Fossil Energy Division '

REVIEWED BY:

n

-m-al SJpervisor - Nucl* Plant eranons DATE: f

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REVIEWED BY: 4.4 28@YALA/ DATE: 8 M Generaj Supervisar :31e[ical And 6da:rols /

REVIEWED BY: .

Ik neral Supervisor - Radwoon Safety DATE: [ /f!93

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REVIEWED BY: 93 - 10 L _

DATE: //2I/9) !

POSRC Meenng Number ~

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/ DATE: P-EI ~9 3 APPROVED Plant BY[: General Manager' L 1

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Offsite Dose Calculation Manual Page 2 of 247 Revision 1, Change 0 1

s Table Of Contents

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Purpose....................................................................................................................4 A ppli cabili ty/ scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . ..... . . .. . ...... . .... .. . .. 4 Definitions................................................................................................................5 References................................................................................................................9 Ra di o a et i v e Li q ui d Effl u ents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . 12 Reiease Pathways. .

..........................................................12 Types of Liquid Relcases..... ......... . .. . . . .................................13 Processing Equipment. .... .. . .. ....... .. ... ... .. .................... . .. . 14 Liquid EfDuent Radiation Monitor Alarm and Trip Setpoints. .. ....... ............15 Liquid Waste Discharge Radiation Monitor (0.RE-2201). . . . ... . ... . . . . 15 Steam Generator Blowdown Effluent Radiation Monitors (1/2-RE-4095) . . .... .. . 24 Steam Generator Blowdown Tank Radiation Monitors (1/2-RE-4014). . . . . . . . 34 Limits On Radionuclide Concentrations in Liquid Effluents. .. .. ...... .. ... ... . 44 Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents . . .. .. ..... .. . . . .. .. . .... .....................49 Limits For The Liquid Waste Processing System. . ...... .. ... .. .............57 Ra di oa et i v e G as eo us E ffl u en ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .

Release Pathways.. ... .. .. . .. .. ... ...... .... . .. .... . . ... ... .. 59

, Types of Gaseous Releases.. .. .. ... . .. . . . .. .................63 Processing Equipment.. .. . .. ....................................63 Gaseous Effluent Radiation Monitors And Serpoints... . .. .... ... . . . . . . . . . 64 Wide Range Gas Monitor (1-RE-5416). . .. . .. .. . . . . . . . . . . 64 Wide Range Gas Monitor (2-RE-5416). ... . . .. . .. .. .. .. . .. ... . 76 Westinghouse Plant Vent Stack Monitor (1-RE-5415). . . . . . .. .............77 Westinghouse Plant Vent Stack Monitor (2-RE-5415). . .. ... .. . ... ... . 88 Gaseous Radwaste Treatment System Radiation Monitor (0.RE-2191).. .... .. . .. . 89 Annual Total Body Dose Rate Due To Noble Gases in Gaseous Effluents. ... ... ..... 99 Annual Skin Dose Rate Due To Noble Gases In Gaseous Effluents. .. ... . . . . . . . . . 106 Annual Organ Dose Rates Due To Iodines And Particulates In Gaseous Effluents.. . .114 Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents....... ... ...121 Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents.. ...... .... .....127 Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents. . ...133 Limits For The Gaseous Waste Processing System....... ...... ....... ............ . . . . 140 Limits On Total Annual Dose - Gases, Liquids, and Outside Storage Tanks... .. . ....142 Special Exceptions and Assumptions For Calculation of Doses and Dose Rates. ........146 Radiological Emironm ental M onitoring Program .......................................................... 148 -

Radiological Environmental Monitoring Program .. ... .. . ...... . . . ... .. ... . . .....148 ;

I2nd U s e Cens u s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ...... . ..... 152 1nterlaboratory Comparison Program .. ....... ..... ..................................154 Annual Radiological Environmental Operating Report . .. ............................155 i Independent Spent Fuel Storage Installation Monitoring Program. . .. . . . ... .. . 157 l A d m i ni st ra ti on Of Th e O D CM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 162 5

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Offsite Dose Calculation Manual Page 3 of 247 Revision 1. Change 0 I

Table Of Contents (Continued)

Attachments...........................................................................................................165

1. Final Grading And Drainage Plan .. .... ..... ......................... .... . . . . . . . . . . . 16 5

2. Outfall 001 - Sources Of Liquid Radioactive Waste... ...... ... ... . .. .. ......... .166

3. Outfalls 002,003,004 - Potential Sources Of Liquid Radioactive Waste. . .. . . . . . . . 169

4. Block Diagram Of Liquid Radioactive Waste Systems ........... .. .. ..................171

5. Dominant And Less Dominant Radionuclides In Typical Radwaste Discharges. .....172

6. Liquid Effluent Dose Factors. . .. ... . .. .. . ........ .... .. .......... ..... 173

7. General Information Related To Gaseous Releases Via The Main Vents ............ .176

8. General Information Related To Gasecus Releases Via Pathways Other Than The Main Vents .... . .... .. .... . . . .... . . .................................177

9. Block Diagram of Radioactive Gaseous Waste Treatment System...... . . ...... 178

10. Noble Gas Dose Factors . ... . . . . .. ... . . . ..... . . . . . . . . . 179

11. Empirical Derivation Of Site-specific Dose Factors. ...... .....................I80

12. Gaseous Effluent Pathway Dose Factors. .. .... . . ... . . . .... . ...... .....I85

13. Environmental Monitoring Sites. . . .. .. .. . . .. ..... . . ... . .. 233

14. Radiological Environmental Monitoring Program Surveillances for Direct Radiation... ..... .. . . .. .. .. . ....................234

15. Radiological Environmental Monitoring Program Surveillances for Airborne Activity . ... .. .... ....... . . ... . .. ..... ... . 235

16. Radiological Environmental Monitoring Program Surveillances for Waterborne Activity . . . . . ... . ... . . . ... . .... . .. 236

17. Radiological Environmental Monitoring Program Surveillances for Ingestible Activity ... .. . . . . . . . . . ............ .. .... 237

18. Map Of Environmental Monitoring Sites For REMP (5 Km Radius) .. .. . . ... . 238

19. Map Of Environmental Monitoring Sites For REMP (10 Mile Radius) . . . .... . 239

20. Environmental Monitoring Sites For ISFSI . . . . . . . . .. ... ........ ... .... . .. 240

21. Map Of Environmental Monitoring Sites For ISFSI.. . ... . .. . . . . . . . . . . 241

22. Map Of Environmental Monitoring Sites For ISFS! (Enlarged).. . .... . ... . . . . . . . 24 2

23. Effluent Radiation Monitors. .. .. . .. ... ...... .. . .... . ... . . .. . . 24 3

24. List Of Effective Pages.

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Offsite Dose Calculation Manual Page 4 of 247 Revision 1, Change 0.

l( I . PURPOSE A. The ODCM lists the radiological emuent controls established at Calvert Cliffs Nuclear Power Plant (CCNPP) for the purpose of ensuring the amount of radioactive materials released to the emironment are as low as reasonably achievable.

B. The ODCM defines parameters and methodologies for i. iting doses and dose rates resulting from the release of radioactive materials in liquid and gaw A emuents.

C. The ODCM defines parameters and methodologies for calculating alarm and trip setpoints for Tecimical Specification related radiation emuent monitoring systems.

D. The ODCM defines and establishes controls for the Radiological Emironmental Monitoring Program.

II. APPLICABILITY / SCOPE A. The infonnation presented in this procedure is applicable to any division, department, section, or unit within the Baltimore Gas And Electric Company (BG&E) which is either whoUy or partly responsible for performing any of the activities listed in the PURPOSES section of this procedure.

Responsible organizations include, but are not limited to, the following:

( 1. BG&E, Nuclear Energy Division (NED), CCNPP Department (CCNPPD), Chemistry Section

2. BG&E, Corporate Affairs Group, Environmental Programs Section 3, BG&E, Fossil Energy Division, Technical Sc.rvices Section, Chemistry Unit

4. BG&E, NED, CCNPPD, Electrical and Controls (E&C) Section

5. BG&E, NED, CCNPPD, Operations Section

6. BG&E, NED, CCNPPD, Padiation Safety Section l B. This procedure is appEcable to the determination of alarm and trip setpoints for the folicwing radioactive gaseous emuent tuonitoring instrumentation:

1. 0-RE-2191

2. 1/2-PI-5415 1

3. 1/2-PI-5416 C.

This procedure is applicable to the determination of alarm and trip setpoints for the following radioactise liquid emuent monitoring instrumentation:

1. 0-RE-2201

2. 1/2 RE-4014 l

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Offsite Dose Calculation Manual Page 5 of 247 Revision 1. Change 0 i 3. 1/2-RE-4095 D. This procedure is applicable to the determination of the offsite doses and/or offsite dose 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 procedure is applicable to the determination of the radiological affects on the environment due to the presence of Calvert Cliffs Nuclear Power Plant.

F. The ODCM is based on Technical Specifications, BG&E's interpretation ofindustry standards, and recommendations made by Combustion Engineering.

III. DEFINITIONS A. Abnormal and/or Unanticipated Radioactise Release:

Any unplanned or uncontrollec lease of radioactive material from the site boundary.

B. Action:

That part of a control or specification which prescribes remedial measures required under designated conditio:6.

C. Channel Functional Test:

A analog CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify operability including alarm and/or trip functions. A bistable CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel sensor to verify operability including alarm and/or trip functions.

D. Batch Release:

A BATCH RELEASE is the discharge ofliquid (or gaseous) waste of a discrete volume.

(NUREG-0133, page 14)

E. Channel Calibration:

A CHANNEL CALIBRATION 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 CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHAhWEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of i

sequential. overlapping or total channel steps such that the entire channel is calibrated.

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iD F. Channel Check:

k A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the san,e parameter.

G. Composite Sample:

A COMPOSITE sample is a combination of individual samples obtained at intenals that are very short (e.g., hourly) in relation 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 through the system.

II. Continuous Release:

A CONTINUOUS release is the discharge ofliquid (or gaseous) wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the CONTINUOUS release. (NUREG-0133, page 14)

I, Dominant Radionuclide:

A DOMINANT RADIONUCLIDE is one whose activity is greater than 1 % of the total activity found in a TYPICAL RELEASES ofliquid or gaseous radwaste.

J. Dose Equivalent Iodine-131:

I DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, 1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844,

Calculation of Distance Factors for Power and Test Reactor Sites."

K. Frequency Notation:

The frequency notation specified for the performance of Surveillance Requirements shall correspond to the intervals defined in the following Table.

Notation Frequency S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 6 months R At least once per '18 months 'l l

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Offsite Dose Calculation Manual Page 7 of 247 Revision 1, Change 0 I S/U Prior to each reactor startup k

P Completed prior to each release N.A. Not applicable Refueling hiterval At least once per 24 months L. Gamma Isotopic Analysis:

A GAMMA ISOTOPlc ANALYSIS is a analytical method of measurement used for the identification and quantification of gamma-emitting radionuclides.

M. Gaseous Radwaste Treatment System:

A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous efDuents by collecting primary coolant system offgases from the primary systern and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

N. Less Dominant Radionuclide:

A LESS DOMINANT RADIONUCLIDE is one whese activity is less than 1% of the total activity found in TYPICAL RELEASES ofliquid or gaseous radraste.

O. Lower Limit of Detection:

The LLD, as defined by Technical Specifications, is the smallest concentration of radioactive matenal in a sample that will yield a net count, above system background, that will be detected with 95 9 probability with only 5% probability of falsely con:luding that a blank observation represents a "real" signal.

P. Members of the Public:

MEMBERS OF THE PUBLIC shall include 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 persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

Q. Offsite Dose Calculation Manual:

The OFFSITE DOSE CALCULATj0N MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls (as specified by the Technical Specification Limiting Conditions of Operation), (2) the Radiological Environmental Monitoring Programs required by Technical Specification 3.12.1, and (3) a description of the information that should be included in the innual Radiological Environmental Operating Report required by Technical Specification 6.9.p7.

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i f R. 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 dermition sha!! be the assumption that all necessary attendant instrumentation, controls, 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).

S. 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 confmement.

T. Rated Thermal Power:

Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWI.

U. Simultaneous Releases:

Simultaneous liquid releases are discharges ofliquid radwaste which occur at the same time.

Simultaneous gaseous releases are discharges of;;aseous radwaste which occur at the same time.

i V. Site Boundary:

The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. (The SITE BOUNDARY is depicted on Attachment 18,

Environmental Monitoring Sites)

W. Source Check:

A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

X. Thermal Power:

The THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

Y. Typical Radwaste Releases (or Typical Radwaste Effluents):

TYPICAL RADWASTE RELEASES are dermed as (1) all releases conducted during any calendar quaner while either Unit I 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 I or Unit 2.

This definition of TYPICAL RADWASTE RELEASES is intended to ensure the concentrations of DOMINANT radionuclides represent realistic, maximum-expected values. This defmition 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.

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Offsite Dose Calculation Manual Page 9 of 247 '

Revision 1, Change 0 This defmition may be modified by the GSC, however, the new defmition shall be documented

-(. in accordan:e with the provisions outlined in the applicable section of the ODCM. (e.g., See the section which contains information related to documenting the fixe & adjustable setpoint.)

Z. 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 materials, or any area within the SITE BOUNDARY used for l residntial quaners of for industrial, commercial, institutional, and/or recreational purposes. ;

AA. Ventilation Exhaust Treatment System:

A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or High Efficiency Particulate Air (HEPA) fliers for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

BB. Venting:

Venting is the controlled process of discharging air or gas from a confmement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner i j that replacement air or gas is not provided or required during venting. Vent, used in system

( names, does not imply a venting process.

CC. Waste Gas Holdup System:

See GASEOUS RADWASTE TREATMENT SYSTEM.

W IV. REFERENCES A. Development References

1. 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 Dose: To Man From Routine Release Of Rea: tor Effluents For The Purpose Of Compliance With 10 CFR Part 50, Appendix I,*

Revision 1, (October 1977).

3. Regulatory Guide 1.111,

Methods For Estimating Atmospheric Transpon And Dispersion Of Gaseous Effluents in Routine Releases From Ligh'-Water-Cooled Reactors,' Revision 1, (July 1977).

4. CCNPP System Description Number 14B, ' Reactor Coolant Waste Processing System Description? ;

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Offsite Dose Calculation Manual Page 10 of 247 Revision 1, Change 0 i

5. Updated Final Safety Analysis Repon, Chapter 11, ' Waste Processing And Radiation

( Protection."

6. CCNPP System Description Number 14D, ' Miscellaneous Liquid Waste Processing System Description."

7. 01 17D,

Miscellaneous Waste Processing System"

8. OI-17C,

Reactor Coolant Waste Processing System"

9. Title 10 of the Cod: of Federal Regulations, Pan 20

10. Title 10 of the Code of Federal Regulations, Pan 50

11. Calven Cliffs Nucl:ar Power Plant Semi-Annual Radiological Effluent Release Repon (1986, 1987, 1985).

12. Radioactive Decay Data Tables, David C. Kocher,1981.

13. Radiological Health Handbook, Bureau of Radiological Health, Jan.1970.

14. TE-001,

Main Vent Stack Flow Measurement"

15. ETP-87-16, " Main Vent Stack Flow Measurement"

16. Verification And Validation Of The Gaseous Release Permit Ponion Of The CCNPP EMS

( Coiaputer Code, J. S. Bland And Associates, July 10,1990.

17. Land Use Survey In The Vicinity Of The Calven 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"

19. CCI-302, Calven Cliffs Alarm Manual

20. TID-14F:',

Calculation of Distance Factors for Power and Test Reactor Sites"

21. " Plant Data Book", BC&E CCNPP Units 1 and 2, Becht:1 Power Corporation, Volume 1, Job 6750.

22. 50.59 Log No. 82-B-999-028-R00, Safety Analysis No. 2, FCR 82-1053, Supplement 1, (Component Cooling System) [BS27]

23. 50.59 Log No. 90-0-074-011-R2, Activity MASE 90-7 (Plant Nitrogen System) [B527] l

24. 50.59 Log No. 90-0-029-045-RI, Activity MASE 90-6 (Plant Heating System) [B527]l

25. 50.59 Log No. 90-0-037444-R1, Activity MASE 90-5 (Demineralized Water System) [B527] l

26. $0.59 Log No. 90-B-012-043-R1, Activity MASE 90-4 (Service Water System) [B527] l l 27. 50.59 Log No. 90-0-027-037-R2, Activity MASE 90-8 (Auxiliary Boiler System) [B527] l

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( 28. Bechtel Power Corporation, Calculation Number M-90-20, " Allowable Radioactive Contammation Levels in the Plant Heating System" [B527]

29. Bechtel Power Corporation, Calculation Number M-90-18, " Allowable Radioactive Contammation Levels in the Nitrogen System Header" [B527]

30. Bechtel Power Corporatior., Calculation Number M-9044, " Allowable Radioactive Contammation Levels in Auxiliary Boiler Water * [BS27]

31. Bechtel Power Corporation, Calculation Number M-90-21,

Allowable Radioactive Contamination Levels in the Demineralized Water System- [B527]

32. Bechtel Power Corporation, Calculation Number M-90-19,

Allowable Radioactive Contamination Levels in the Service Water System" [B527]

33. Bechtel Power Corporation, Job Number 11865, Calculation Number 7.4.3-15, " Allowable Radioactive Contamination Levels in the Condensate Storage Tank" [B527]

34 CCI-205, Serpoint Control Procedure

35. Ol-8 A, 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).

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-037-120-R2, Activity MASE 90-11 (Condensate Storage Tank) [BS27] l B. Perfonnance References

1. TE-001, " Main Vent Stack Flow Measurement" i

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- V. RADIOACTIVE LIQUID EFFLUENTS l (k A. Release Pathways l

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1. Introduction ;

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a) Radioactive liquid waste generated as a result of operating the Calvert Cliffs Nuclear Power Plant (CCNPP) rnay be released to the Chesapeake Bay', :

l b) By design, 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 DN. j c) A diagram which shows the location of each outfall is included as Attachment 1.

2. Outfall 001 a) Water from the Chesapeake Bay is pumpea through the condensers and is dischargec to the Chesapeake Bay through the circulating water discharge conduits, known as outfall

( 001. i 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 conduit extends 850 feet into the Chesapeake bay.

d) The circulating water discharge conduit may accept liquid radioactive waste from l various sources. Sources which may contribute radioactive material to the circulating water discharge conduit are tabulated in At:achment 2.

3. Outfalls 002,003, and ON 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.

b) Sources which could potentially contribute radioactive material to each of these outfalls are tabulated in Attachment 3.

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).

The f ederal controls e*d seinistrative limits associated with the retesse of radioactive materlats from eeNPP g are discussed else.Aere in this doctrent.

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Offsite Dose Calculation Manual Page 13 of 247 Revision 1, Change O f 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 (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 with 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 (1) In accordance with applicable safety evaluations (Ref. 33), 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.

B. Types of Liquid Releases

1. All liquid radwaste releases are classified as either BATCH releases or CONTINUOUS releases.

2. The definition of

BATCH release

is included in the definitions section of the ODCM.

( 3. The definition of

CONTINUOUS release

is included in the definitions section of the ODCM.

Offsite Dose Calculation Manual Page 14 of 247 Revision 1, Change 0 4' 4. Liquid radwaste discharges have been classified as CONTINUOUS or BATCH as shown on Attachments 2 and 3.

[

C. 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 through outfalls 002,003, and O(M; however, the waste shall be analyzed for radioactivity in accordance with the analysis frequencies contained in approved CCNPPD Chemistry Section procedures.

2 Modifications a) Major changes or modifications to the liquid waste processing system shall be reported to the Commission in the Semi-annual Radioactive Effluent Rele Report for the time interval in which the modification was completed (per Technical Specification 6.15.1). .

b) A

major" change or modification includes, but is not limited to the removal or permanent bypass of any of the following:

(1) degassifier (2) reactor coolant waste receiver tank

( (3) reactoi coolant waste monitor tank (4) letdown filter (5) reactor coolant waste ion exchanger (6) miscellaneous waste ion exchanger (7) miscellaneous waste filter (8) miscellaneous waste receiver tank (9) miscellaneous waste monitor tank (10) evaporator

3. Detailed Description a) A detailed description of the liquid waste processing system is beyond the scope of the ODCM.

b) For more information on the Miscellaneous Liquid Waste Processing System see System Description Number 14D, " Miscellaneous Liquid Waste Processing System Description.'

i l

Offsite Dose Cc!culation Manual Page 15 of 247 Revision 1, Change 0 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.*

D. 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 b) Functions of 0-RE-2201 (1) continuously measure the activity contained in liquid waste discharge line (Technical Specification 3.3.3.10)

(2) continuously indicate (via 0 RI 2201) the activity of liquids contained in liquid waste discharge line (Technical Specification 3.3.3.10)

(3) alarm (via 0-RI-2201) prior to exceeding 10 CFR 20, Appendix B. Table II, Column 2 limits (per Technical Specification 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-RI-2201) exceeds the fixed high radiation trip serpoint 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).2 (2) The functions of 0-RE-2201 are listed in paragraph (b);bove.

d) Monitors equivalent to 0 RE-2201 (1) There are no equivalent monitors for 0-RE-2201.

Technical specification 1.6 f

'l

g Offsite Dose Calculation Manual Page 16 of 247 ,

Revision 1, Change 0 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 Technical Speci6 cation 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 concentratirns specified in 10 CFR 20, Appendix B, Table II, Column 2, or (b) two independent samples are analyzed in accordance with Technical Specification 4.11.1.1.1; AND at least two technically qualified members of the Facility Staffindependently verify the release rate calculations: AND two qualified operators verify the discharge valve line up.

f) Surveillances for 0-RE-2201 (1) Technical Specification 4.3.3.10 requires demonstrating the OPERABILITY of 0-RE-2201 by satisiying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 3 (b) SOURCE CHECK prior to each release

( (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months ,

g) Serpoints 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 serpoint (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 refer to these r,etpoints as follows:

(a) The 0-R] 2201 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint.

Technical Specifications table 1.2 L.J

Offsite Dose Calculation Manual Page 17 of 247 Revision 1, Change 0 (b) The 0-RI-2201 adjustable plant computer high radiation alarm and

{ manual control trip setpoint will be referred to as the adjustable serpoint.

(c) The 0-RJ-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) General information (a) This serpoint is considered to be a fixed serpoint. 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 serpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the liquid waste processing system.

(d) The current value for the fixed serpoint is specified in the CCNPP Alarm Manual.

(e) The CCNPP Alarm Manual refers to this alarm and trip setpoint as the I

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 CCI-205.

(h) The fixed serpoint shall be calculated as described below'.

(2) Calculating the fixed serpoint for 0-RI 2201 (a) The fixed alarm and trip setpoint for 0-RI-2201 shall be calculated as follows:

FIXED ALARM AND TRIP SETPOINT FOR 0-RI-2201 Sg < K l ( Ed / F, ) [ l ( A,L, ) ( e ) ) + Mg }

st 3 4d Per Technical specification 3.3.3.10.

, ' This formula has been derived from WUttEG 0133, AcbendJt, page AA-1.

4 s

. Offsite Dose Calculation Manual Page 18 of 247 i Revision 1, Change 0 l

)

(. Sg =

the fixed alarm and trip setpoint for 0-RI-2201 (cpm)

)

1 Kg =

a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20 l 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 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.

=

F, the dilution water flow rate (gpm) prior to the point of release to UNRESTPJCTED AREAS I

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.

DILUTION WATER FLOW RATE F, =

F,,+ F,, + F, 4. A 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.

Additional circulating water pumps may be required as specified in approved Chemistry Procedures.

If a release ofliquid 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-PJ-2201, or otherwise comply with the action requirements

( of Technical Specification 3.3.3.10. ;

l i

t I

- Offsite Dose Calculation Manual Page 19 of 247 Revision 1. Change 0

, F, =

the minimum salt water 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 o' 0 gpm should be used when calculating the fixed setpoint.

If a release of liquid radwaste is to be conducted using less than the minimum 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 0-RI-2201, or otherwise comply with the action requirements of Technical Specification 3.3.3.10.

=

F, maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3.

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 serpoint, a flow serpoint is not required-for the flow measuring device (0-FE-2199) in the effluent line-to verify compliance with Technical Specification 3.3.3.10.

Ag =

specific activity limit for the release of radionuclide, i, to UNRESTRJCTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table II, Note 1 as described below; microcuries per milliliter).

(

In order to calculate a meaningful and accurate fixed serpoint, the specific radionuclides, i, chosen for calculating the fixed serpoint should correspond to those DOMINANT AND LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP.

Attachment 5 provides funher guidance for determining the identity of those radionuclides, i, to be used to calculate a fixed setpoint.

I Values for A shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the c0liective total of all LESS DOMINANT RADIONUCLIDES.

SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE i Ag =

{ f, ) ( Am) , Eq.3L

=

f, 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.

'I

' Offsite Dose Calculation Manual Page 20 of 247 Revision 1. Change 0 I Ag

= . the sum of the total specific activities of agl radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm )

l This value corresponds to 1 MPC.

Ag shall be calculated as shown below.

l TOTAL SPECIFIC ACTIVITY EQUIVALENT TO I MPC b[(f,)(Ag )/Ag]=1 Eq. 4L' Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2.

For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, B, Note 2).

use 3E-8 microcuries per milliliter as the value for Ag (per 10 CFR 20, Appendix

\ 1 =

the MPC limit (MPCs) for unrestricted areas i

This value is based on the MPC limit from 10 CFR 20, Table II, Note 1.

=

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 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.

l (3) Documenting the fixed setpoint for 0-RI-2201 (a) Whenever the fixed serpoint is calculated, the specific values chosen for each of the parameters shall be documented in accordance with CCI-205.

This formte has been derived frce 10 CFR 20, Table !!, ketes 1, 2, and 3.

, 'I

Offsite Dose Calculation Manual Page 21 of 247 Revision 1, Change 0 (4) Changing the fixed serpoint for 0-Rl-2201 (a) If the fixed setpoint calculated in accordance with equation IL exceeds the nuximum range of the monitor, the fixed serpoint 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-Rl-2201 may be established at values lower than the maximum allowable serpoint, if desired.

(c) A serpoint change should be initiated whenever any of the parameters identified in equation IL have changed.

(d) The fixed serpoint should not be changed unless one of the following occurs:

7 i) the relative activity of any radionuclide in TYPICAL LIQUID EFFLUENTS, f 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 muumum dilution water flow rate is not available for a liquid release, iii) the values listed in 10 CFR 20, Table II, column 2 have changed, i )

{ 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) CCI-205 contains the administrative controls associated with changing and approving the fixed serpoint.

i) The adjustable alarm and trip setpoint for 0-RI-2201 (1) General information (a) This setpoint is an adjustable serpoint. The adjustable setpoint is calculated and adjusted prior to each release from the liquid waste processing system.

5 (b) The adjustable setpoint is based on the specific activities of the ,

radionuclides present in the undiluted liquid waste (as determined by j radiochemical analysis per Technical Specification 4.11.1.1.1). 1 i

(c) Whenever the adjustable setpoint is exceeded, discharges from the liquid waste processing system will be manually suspended. :

I f As detemired in accordance with Attachment s.

i l

l 1

1

- I i

Offsite Dose Calculation Manual Page 22 of 247 Revision 1, Change 0 (d) See Ol-17C, " Reactor Coolant Waste Processirig System", or OI-17D,

-( " Miscellaneous Waste Processing System," for a full list of operator actions taken in response to this alarm.

(e) The adjustable serpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the liquid waste processing system.

(f) The value for the adjustable setpoint is recorded on the liquid release permit in accordance with Chemistry section proceduren (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 prict to each release as shown below.

(2) Calculating the adjustable setpoint for 0-RI-2201 (a) The adjustable serpoint is based on the specific activities of the radionuclides in the undiluted liquid waste (as detennined by radiochemical analysis per Technical Specification 4.ll.1.1.1),'and g shall be calculated as shown below.

ADJUSTABLE SETPOINT FOR 0-RI-2201 S, < l.501 [ ( A, ) ( e, ) + Bkg )

Eq. SL -

=

S,y 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.8 Ag. =

specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) 0 The "awlysis errors" and " calibration errors" refer to errors which are within established cpality assurance and quality control tirnits,

.4. , , ~ '

Offsite Dose Calculation Manual Revision 1, Change 0 Page 23 of 247 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 and trip setpoint for 0-RI-2201 (a) Whenever the adjustable serpoint 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).

(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 serpoint.

(b) If the adjustable alarm and trip serpoint 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.

(d) Whenever 0 RI-2201 is operable, the calculated value for the adjustable j serpoint shall be eniered into the plant computer prior to each release from the liquid waste processing system.

(e) Plant Operating Instructions (e.g., OI-17C and OI-17D) contain administrative centrols associated with entering the adjustable setpoint into the plant computer.

j) The low radiation alarm for 0-RI-2201 l i

(1) This alarm is integral to the liquid release discharge monitor, as purchased from the supplier.

(2) The current value for the low alarm serpoint is specified in the CCNPP Alarm ;

Manual.

J (3) The low alarm serpoint may be used to determine the OPERABILITY of this monitor (per Technical Specification 4.3.3.10, CHANNEL FUNCTIONAL TEST).

l i

(4) The alarm generated by the low alarm serpoint may be used to terminate a !

release in the event 0-RE-2201 fails (i.e., downscale failure or circuit failure) in accordance with Technical Specification 4.3.3.10.

(

. 'I

-Offsite Dose Calculation Manual Page 24 of 247 Revision 1. Change 0

( (5) The low alarm setpoint calculations are not described in the ODCM.

k (6) Changes to the low alarm setpoint are controlled by CCI-205.

2.

Steam Generator Blowdown Ernuent Radiation Monitors (1/2-RE-4095) a) General description of 1/2-RE-4095 (1) munber 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

, b) Functions of 1/2-RE-4095 (1) continuously measure the activity contained in steam generator blewdown ef0uent line (Technical Specification 3.3.3.10)

(2) continuously indicate (via 1/2-RI-4095) the activity of liquids contained in the steam generator blowdown efDuent line (Technical Specification 3.3.3.10)

(3) alarm (via 1/2-RI-4095) prior to exceeding 10 CFR 20, Appendix B. Table U, Column 2 limits (per Technical Specification 3.11.1.1) (Note: A technical evaluation shall be conducted to ensure compliance with UFSAR 10.2.2.4.) ;

(4) automatically terminate steam generator blowdown releases to i UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4095) exceeds the fixed alarm serpoint 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.

1 in8nic.i spuification 1.6

. . ._ f

Offsite Dose Calculation Manual - Page 25 of 247 !

Revision 1, Change.0 (3) It should be noted that if the steam generator blowdown processing system heat j

( 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 muumum channels operabiliy requirement of Specification 3.3.3.10 may not be satisfied.

l d) Monitors equivalent to 1/2-RE-409.5 j 1

(1) 1/2-RE-4014 is normally considered the PRIMARY MONITOR for measuring I 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.

(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 alamung 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 l concentration of radioactive materials released to UNRESTRICTED AREAS in accordance with Technical Specification 3.11.1.1 as long as the following a conditions are satisfied:

(

(a) the OPERABILITY of 1/2-RE-4014 must be demonstrated in accordance with Technical Specification 4.3.3.10, Table 3.3.13(1b),

and (b) the blowdown ion exchangers are isolated (or the 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 (per Technical Specification 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 j' alarm and trip serpoint 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

{

S

Offsite Dose Calculation Manual Page 26 of 247 Revision 1. Change 0 (b) a grab sample is collected AND analyzed in accordance with the

( provisiors described below:

i) analysis shall determine EITHER the gross gunma activity or gross beta activity of the sample ii) sampling and analysis shall be completed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 accedance with the LLDs of Technical Specification 4.11.1.1.1 f) Surveillances for 1/2-RE-4095 (1) Techr'ical Specification 4.3.3.10 requires demonstrating the OPERABILITY of 1/2-RE-4095 by satisfying the checks, calibrations, and tests listed below (a) CHANNEL CHECK within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months "

(

(b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Serpoints for 1/2-RJ-4095 (1) There are three radiation alarm setpoints a'ssociated with the Steam Generator Blowdown Effluent Radiation Monitor.

(a) 1/2-RI-4095 fixed high radiation alarm and automatic control trip setpoint (b) 1/2-RI-4095 adjustable plant computer high radiation alarm and manual control trip serpoint .

(c) 1/2-RI-4095 low radiation alarm serpoint (2) In order to simplify the setpoint tenninology, climinate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

Technical specifications Table 1.2

's

Offsite Dose Calculation Manual ' ~ ' Page 27 of 247 Revision 1, Change O '

~;

(a) The 1/2-RI4095 fixed high radiation alarm and automatic control trip -

. ,(-.

setpoint will be referred to as the fixed setpoint.

i (b) The 1/2-R14095 adjustable plant computer high radiation alarm and .

manual control trip setpoin: will be referred to as the adjustable setpoint.

(c) The 1/2-RI4095 low radiation alarm serpoint will be referred to as the low setpoint.

(3) Each of these alarm serpoints are described below.

h) The fixed setpoint for 1/2-RI4095 '

(1) General information (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.

(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 setpoint is specified in the CCNPP Alarm Manual.

(e) The CCNPP Alann Manual refers to this alarm and trip serpoint as the 1/2-RI4095 Steam Generator Blowdown Recovery High Alarm.

Di (f) This setpoint is integral to the steam generator blowdown discharge monitor, as purchased from the manufacturer.-

(g) The fixed serpoint is admmistratively controlled by CCl-205.

. (h) The fixed alarm and trip setpoint shall be calculated as described below 12, (2) Calculating the fixed se: point for 1/2-RI4095 .;

(a) The fixed alarm setpoint for 1/2-RI-4095 shall be calculated in accordance with equation IL.

]

. It should be reted that the UfsAR (section 10.2.2.0 states, "the blowdwn ticpid'monit'or has en alare setpoint selected to atlow an annual overage continuous blowdun past the sonitor of 10 g;n without exceeding one curie discharged per year, excluJing tritiLen."

Per Technical Specification 3.3.3.10

'8

- ~~ .- .. .-. . - . . . - , . , _

Offsite Dose Calculation Manual Revision 1, Change 0 Page 28 of 247 1

FIXED SETPOINT FOR 1/2-RI-4095 Sg i K ir { ( F,/F, ) [ I ( Ag ) ( e, ) ) + Bkg } Eq.IL 13 Sg =

the fixed alarm and trip setpoint for 1/2-RI-4095 (cpm)

K, =

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 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.

)

=

F, the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS i 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.

'l l

DILUTION WATER FLOW RATE l

Fa =

F,,+ F,,+ F, !

4E I

F, =

the minimum circulating water system flow rate necessary to conduct liquid releases 13 sqation it has been derived f rer umC c133, A:dends, page AA-1.

(

\

l

Offsite Dose Celculation Manual

,, Page 29 of 247 Revision 1, Change 0 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 gallons per minute.

Additional circulating water pumps may be required as specified in approved chemistry section procedures.

If a release ofliquid 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 serpoint has been calculated and entered into 1/2-RI iO95, or otherwise comply with the action requirements of Technical Specification 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, dif0 cult 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 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 Technical Specification 3.3.3.10.

=

] F, maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste Dow rates for various waste streams are tabulated in Attachments 2 and 3.

Since the steam generator blowdown now rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 ppm per circulating water pamp), 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 serpoint is not required-for the flow measuring device in the ef0uent line-to verify compliance with Technical Specification 3.3.3.10.

Ag =

specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table II, Note I as described below; microcuries per milliliter)

In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides,1, chosen for calculating the fixed setpoint should correspond to those DOMINANT AND LESS :

DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP.

Attachtnent 5 provides funher guidance for determining which radionuclides, i, should be used to calculate a fixed setpoint.

Values for A shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the co#liettive total of all LESS DOMINANT RADIONUCLIDES.

I

_ I

Offsite Dose Calculation Manual Pcge 30 of 247 Revision 1, Change 0

(' -

SPECIFIC ACTIVITY LIMIT FOR EACH RADIONUCLIDE i A,g

=

( f, ) ( Ag , ) Eq.3L

=

- f, a fraction which represents the relative activity contribution of nuclide i to the average total ef0uent 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.

=

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.

An, =

the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID 3

RADWASTE RELEASE (microcuries/cm )

This value corresponds to 1 MPC.

An, shall be calculated as shown below.

TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC

[ [ ( f, ) ( Ag,)/Ag]=1 Eq. 4L

Ag =

the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, 3

Column 2 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2, i

For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for Ag (per 10 CFR 20, Appendix B, Note 2).

1 = i the MPC limit (MPCs) for unrestricted areas j This value is based on the MPC limit from 10 CFR 20. Table II, Note 1.

This fornula has been derived from 10 cFR 20, Table 11, hotes 1, 2, and 3.

I l

- - . . , L

Offsite Dose Calculation Manual Page 31 of 247 Revision 1, Change 0 Bkg = an approximation of the detector 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.

(3) Docum... :ing the fixed setpoint for 1/2-R)-4095 (a) Wherever the fixed setpoint is calculated, the spew .; values chosen for each of the variables shall be documented in accordance with CCI 205.

(4) Changing the fixed setpoint for 1/2 RI-4095 (a) If the fixed setpoint calculated in accordance with equation IL exceeds the maximum range of the monitor, the fixed serpoint 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 serpoint, if desired.

(c) A serpoint change should be initiated whenever any of the parameters identified in equation IL 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 has changed by greater than 10%, and the new radionuclide mixture yields a fixed serpoint 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 listed in 10 CFR 20, Table II, 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-4095" carlier in this section). l ;

(e) CCI-205 contains the administrative controls associated with changing and approving the fixed alarm and trip serpoint.

1 i) The adjustable alarm and trip setpoint for 1/2 RI-4095 l 1

1

[ As determined in accordance with Attachnent 5. 1 i

H

,, i

Offsite Dose Calcuhtion Manual' Page 32 of 247 -

Revision 1, Change 0 I .. (1) General information

[

(a) This serpoint is an adjustable setpoint. The adjustable setpoint is calculated and adjusted prior to each release from the steam generator blowdown processing system.

(b) The adjustable serpoint is based on the specific activities of the !

radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Technical Specification 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 full list of operator actions taken in response to this l alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the steam generator blowdown processing system.

(O The value for the adjustable setpoint is recorded on the liquid release permit in accordance with Chemistry section procedures.

(g) This alarm is not integral to the steam Senerator blowdown effluent monitor, as purchued from the supplier.

(

(h) This alarm is generated by tne plant computer which monitors output ,

from 1/2-RI-4095, and provides an alarm to plant operators when the adjustable alarm and trip serpoint has been exceeded.

(i) A value for the adjustable alarm and trip setpoint shall be calculated prior to each release as shown below.

(2) Calcu!ating 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 analysis per Technical Specification 4.11.1.1.1), and shall be calculated as shown below.

ADIUSTABLE SETPOINT FOR 1/2-RI-4095 S $ 1.50 [ [ ( A, ) ( e, ) + Bkg ] Eq. SL

Where, inis f orrnuls may be derived f rorn WREc 0133, A21erdJn, page AA-1.

i I,

Offsite Dose Calculation Manual Revision 1, Change 0 Page 33 of 247

=

S, the adjustable alarm and trip setpoint for 1/2-R14095 (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 v ith monitor calibrations.17 A =

specific activity of radionuclide, i, in the undiluted waste stream (microcuries per 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.

Ekg =

an approximation of the detector background prior to initiating the liquid release (cpm)

(3) Documenting the adjustable setpoint,1/2-RI4095 (a) Whenever the adjustable serpoint 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 serpoint for 1/2-R14095 (a) If the adjustable serpoint exceeds the maximum range of the monitor, the serpoint 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 than or equal to the fixed setpoint.

(c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpcint.

(d) Whenever 1/2-R14095 is operable, the calculated value for the l

adjustable setpoint shall be entered into the plant computer prior to each release from the steam generator blowdown processing system.

l (e) Plant Operating Instructions (e.g., OI-8A) contain administrative l

controls associated with entering the adjustable serpoint in the plant computer.

j) The low setpoint for 1/2-R14095 aThe xs 'quality analysis errors" control s'vf " calibration errors" refer to errors w5ich are within estabtished quality assurance limits.

f m

mm . . - . . . . -

Offsite Dose Calculation Manual Page 34 of 247 Revision 1, Change 0 (1) This alarm is integral to the steam generator blowdowm 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 serpoint may be used to determine OPERABILITY of this monitor (per Technical Specification 4.3.3.10, CHANNEL FUNCTIONAL 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 CCI-205.

(6) The ODCM does not address the calculations associated with the low alarm setpoint.

3.

Steam Generator Blowdoum Tank Radiation Monitors (1/2 RE-4014) a) General description of 1/2-RE-4014 (1) nu+r of radiation elements: one per unit (2) Type of radiation element: off-line scintillation detector

( (3) output: analog (4) Designations for radiation indicators (a) 1-RI-4014 (b) 2-RI-4014 (5) units for radiation indicator: counts per minute (6) supplier: Westinghouse (7) A 3 gallon per minute sample is cooled, passed through the detector, and pumped back into the steam generator blowdowm tank.

b) Functions of 1/2-RE-4014 (1) continuously measure the activity contained in an off-line sample of the steam generator blowdown tank (Technical Specification 3.3.3.10)

(2) continuously indicate (via 1/2-RJ-4014) the specific activity in an off-line sample of the steam generator blowdown tank (Technical Specification 3.3.3.10)

(3) alarm (via 1/2-RI-4014) prior to exceeding the 10 CFR 20, Appendix B, Table l II, Column 2 limits (per Technical Specification 3.11.1.1) (Note: A technical I k

evaluation shall be conducted to ensure compliance with UFSAR 10.2.2.4.)

l I

l

Offsite Dose Calculation Manual Page 35 of 247 Revision 1, Change 0 (4) automatically termmate steam generator blowdown releases to

}

UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4014) exceeds 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)'8 (2) The functions of this monitor are listed in section (b) above.

d) Monitors equivalent to 1/2-RE-4014 (1) 1/2-RE-4014 is normally considered the PRIMARY MONTTOR 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 the steam generator blowdown processing system.

(2) In the event PRIMARY MONITOR (1/2-RE 4014) is inoperable or otherwise unavailable, the BACKUP MONITOR (!/2-RE-4095) is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR.

(3) 1/2-RE-4095, Steam Generator Blowdown Effluent Radiation Monitor, performs measurement, indication, alarm, and isolation functions equivalent to 1/2-RE-4014 (see

Function of 1/2-RE-4014" carlier in this section), unless l 1/2-RE 4095 is bypassed as described below.

(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 Specification 3.3.3.10 may not be satisfied (unless 1/2-RE 4014 is operable).

e) Radiological effluent pntrols 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 Technical Specification 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" carlier in this section) AND the l alarm and trip setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to i UNRESTRICTED AREAS are less than the concentrai ons specified in l 10 CFR 20, Appendix B. Table D, Column 2, or ;

Technical specification 1.6

,, I i

Offsite Dose Calculation Manual Page 36 of 247 Revision 1, Change 0

~

f (b) a grab sample is collected AND analyzed in accordance with the .

T- provisions described below:

i) analysis shall determine EITHER the gross gamma activity or gross beta activity of the sample ii) sampling and analysis shall be completed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the specific activity of the steam generator blowdown is greater than 0.01 microcuries per gram IODINE DOSE EQUIVALENT iii) sampling and analysis shall be completed at least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if the specific activity of the steam generator blowdown is less than or equal to 0.01 microcuries per gram 10 DINE DOSE EQUIVALENT iv) the LOWER LIMITS OF DETECTION for the gross gamma and/or gross beta analyses are in accordance with the LLDs of -

Technical Specification 4.11.1.1.1 f) Surveillances for 1/2-RE-4014 (1) Technical Specification 4.3.3.10 requires demonstrating the OPERABILITY of 1/2-RE-4014 by satisfying the checks, calibrations, and tests listed below (a) CHANNEL CHECK within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months " (b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Serpoints 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 serpoint (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:

Technical specificaricm rable 1.2 I

l 8

l 1

'l

Offsite Dose Calculation Manual Page 37 of 247 Revision 1, Change 0 8,

(a) The 1/2-RI-4014 ftxed high radiation alarm and automatic control trip serpoint will be referred to as the fixed setpoint.

(b) The 1/2-R]-4014 adjustable plant computer high radiation 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.

(3) Each of these alarms is described below.

h) The fixed alarm and trip setpoint for 1/2-RI-4014 (1) General Information (a) This alarm and trip serpoint is considered to be a fixed serpoint. The fixed serpoint 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 serpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the steam generator blowdown processing system.20

( (d) The current value for the fixed alarm and trip setpoint is specified in the CCNPP Alarm Manual. '

(e) The CCNPP Alarm Manual refers to the fixed setpoint as the 1/2-RI-4014 Steam Generator Blowdown High Alarm.

(f) The fixed setpoint is integral to the liquid release discharge monitor, as purchased from the manufacturer.

(g) The fixed alarm and trip serpoint is admmistratively controlled by CCI-205.

(h) "Ihe fixed alarm and trip setpoint shall be calculated as described below2 '.

(2) Calculating the fixed alarm and trip serpoint 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) states, "the blowdown liquid monitor has an alar:r, setpoint selected to allow an annual average continuous blowdown past the eenitor of 10 ppm without exceeding one curie discharged per year, excluding tritiun.

Per Technical specification 3.3.3.10.

(,

'i

Offsite Dose Calculation Manual Page 38 of 247 Revision 1, Change 0

(-

FIXED ALARM AND TRIP SETPOINT FOR 1/2-RI-4014 Sg .1 Kg{ ( F, / F, ) [ [ ( Ag )( e i )] + Bkg } Eq.IL 22 Where, Sg = the fixed alarm and trip serpoint 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 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 0.50] 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.

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 serpoints . 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.

=

F, 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 rate shall be calculated in accordance with equation 2L.

DILUTION WATER FLOW RATE F, =

F,,+ F,,+ F, 4E

=

F, the minimum circulating water system flow rate necessary to conduct liquid releases 22 squet to, to has been oerived f rom munc-0133, a:eerer, p se wi.

{

l Offsite Dose Calculation Manual - Page 39 of 247 i Revision 1, Change 0

]

l l

.(~ A minimum of two circulating water pumps (one circulating water pump per conduit accepting l

( radwasa) shall be operable when discharging liquid radwaste - via this monitor - to outfall 001. l

'i 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 ofliquid radwaste from the s: cam generator blowdown system is to be conducted using i 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-RJ-4014, or otherwise comply with the action requirements of Technical Specification 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 nummum salt water Dow rate of 0 gpm should be used when calculating the fixed serpoint.

The maximum flow rate for one salt water pump is listed on Attachment 2.

If a release ofliquid radwaste is to be conducted using less than the minimum 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, or otherwise comply with the action requirements of Technical Specification 3.3.3.10.

F, = maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste 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 Technical Specification 3.3.3.10.

A, = specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table II, Note I 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 DOMINANT AND LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CChTP, Attachment 5 provides further guidance for determining which radionuclides, i, should be used to calculate a fixed serpoint.

Values for A shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the coNiective total of all LESS DOMINANT RADIONUCLIDES.

(

i

-f

Offsite Dose Calculation Manual Page 40 of 247 Revision 1, Change 0

(: .

k SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE,i A,

g

=

( f, ) ( Ag) 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.

Ag =

the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID 3

RADWASTE RELEASE (microcuries/cm )

This value corresponds to 1 MPC.

Calculate the value of A g as shown below.

TOTAL SPECIFIC ACTTVITY CORRESPONDING TO 1 MPC AT THE SITE BOUNDARY

'I

[ [ ( f, ) ( Ag )/Ag]=1 Eq. 4L23 Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2.

For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for Ag (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 Table II, Note 1.

e,

= absolute detector efficiency for nuclide, i (cpm /microcuries per milliliter)

The detector efficiency for each radionuclide may k calculated from data collected during calibration of the radiation monitor.

23 inis for,nute hei been oerived f rom to cra zo, tabte si, motes 1, 2, and.3.

(

1

Offsite Dose Calculation Manual Page 41 of 247 Revision 1 Change 0 l i Bkg = an approximation of the detector 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.

(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 CCI-205.

(4) Changing the fixed setpoint for 1/2 RI 4014 (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 setpoint may be established at values lower than the maximum allowable serpoint, if desired.

(c) A serpoint change should be initiated whenever any of the parameters identified in equation IL (identified in this section of th: ODCM) have changed.

(d) The fixed setpoint should not be changed unless one of the following

( occurs:

i) the relative activit>2' of any radionuclide in TYPICAL LIQUID EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed serpoint which is 10% (or more) lower than the current fixed setpoint, ii) the minimum dilution water flow rate is not available for a liquid release, iii) the values listed in ?9 CFR 20, Table II, column 2 have

< a r_;'

iv) Ae raL son monitor has been recently calibrated, repaired, or mhuiu altered, or v) the monitor is not conservative in its function (see

Functions of 1/2-RE-4014" carlier in this section). l (e) CCl-205 contains the administrative controls associated with changing and approving the fixed setpoint.

As determined in accordance with Attachment 5.

I.

me = _ . _ .- . - . . . . - - -

~

Offsite Dose Calculation Manual Page 42 of 247 Revision 1, Change 0 i) The adjustable alarm and trip setpoint for 1/2-RI-4014 (1) General information (a) This serpoint is an adjustable setpoint. The adjustable setpoint is calculated and adjusted prior to each release from the steam generator blowdown processing system.

(b) The adjustable serpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Technical Specification 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 full list of operator actions taken in response to this l alarm.

(e) The adjustable serpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharg s from the steam generator blowdown processing system.

(f) The value for the adjustable serpoint is recorded on the liquid release permit in accordance with Chemistry section procedures.

(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-RJ-4014, and provides an alarm 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 serpoint 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 Technical Specification 4.11.1.1.1), and the alarm and trip setpoint is calculated as shown below.

ADJUSTABLE ALARM AND TRIP SETPOINT FOR 1/2-RI-4014 S, <

_ 1.50 [ [ ( A, ) ( e, ) + Bkg ] . Eq. 51 25 Eqsation si has been derived from NUREG 0133, Addenden, page AA-1.

l.

1 Offsite Dose Calculation Manual Page 43 of 247 Revision 1, Change 0 -

.t

.(.

S,g

= the adjustable alarm and trip setpoint for 1/2-RI4014 (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, and (5) errors associated with monitor calibrations,26 A, = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter)

= absolute detector efficiency for nuclide, i (cpm /microcuries per milliliter) e, The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Ekg = an approximation of the detector background (cpm)

(3) Documenting the adjustable setpoint for 1/2-RI-4014 q (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 setpoint for 1/2-RI-4014 (a) If the adjustable setpoint exceeds the maximum range of the monitor, the serpoint 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 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-RI-4014 is operabl'e, the calculated value for the l adjustable letpoint shall be entered into the plant computer prior to each release from the steam generator blowdown arid processing system. l (e) Plant Operating Instructions (e.g., OI-8A) contain administrative l ,

controls associated with entering the adjustable serpoint in the plant computer.

6 The *anatysis errors" and " calibration errors" refer to errors which are within established quality assurance and Quality control tirnits. ,

...n .. .- .- .-

Offsite Dose Calculation Manual Page 44 of 247

' Revision 1, Change 0.

j) The low alarm setpoint for 1/2-RI-4014 I(

(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 CCI-205.

(4) The ODCM does not address the calculations associated with the low alarm setpoint.

E. Limits On Radionuclide Concentrations In Liquid Efiluents

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

'I a) The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases (per Technical Specification 3.11.1.1).

b) It should be noted that NUREG-0133 specifies 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) Routine surveillances for BATCH releases (1) Sample each

BATCH" of radioactive liquid waste prior to its release (per Technical Specification 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, I.

131, Mo 99, and Cc-144) in the

BATCH" sample, prior to the ~ BATCH" ,

release (per Technical Specification 4.11.1.1.1).

[ l

_~ _ _

Offsite Dose Calculation Manual Page 45 of 247 1

. Revision 1, Change 0 l

1

{.- (3) Determine the concentration of tritium contained in a monthly COMPOSITE i i sample at least once per month (per Technical Specification 4.11.1.1.1).

(4) Detennine the concentrations of Sr-89 and St-90 contained in a quarterly COMPOSITE sample at least once per quaner (per Technical Specification i 4.11.1.1.1). j (5) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED APIAS (per Technical Specification 4.11.1.1.2).

b) Routine surveillances for CONTINUOUS releases (1) Sample CONTINUOUS releases of radioactive liquid waste at least once per month (per Technical Specification 4.11.1.1.1).

(2) Determine the concentrations of principle gamma emitters (including, but r.ot limited to, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141, I.

131 Mo-99, and Ce-144)in the undiluted, CONTINUOUS waste stream sample (per Technical Specification 4.11.1.1.1).

(3) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Technical Specification 4.11.1.1.2).

4. Responsible Plant Organizations

(

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.

5. Initiating Conditions a) The surveillances for BATCH releases shall be performed prior to each BATCH 27 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 monthly2s 29 (until the CONTINUOUS release has been termmated) and, if activity is identified in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved chemistry section procedures.

6. Calculation Methodology Per Technical Specification 4.11.1.1.1.

Per Technical specification 4.11.1.1.1.

The LOWER LIM 115 oF Mil 07106, shsil conform to Technicet specification 4.11.1.1.1, Table 4.11 1.

t

~.m__< s..

Offsite Dose Calculation Manual Page 46 of 247 Revision 1, Change 0 tf a) At CCNPP, there are two methodologies for calculating the concentrations of T radionuclides in the receiving waters, at the point of release to ' UNRESTRICTED AREAS, resulting from the discharge ofliquid waste.

(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.

b) 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, ensure the concentrations of radionuclides in UNRESTRICTED AREAS are less than one MPC by verifying the following inequality is true:

LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (RIGOROUS METHOD)

(

( F, / F, ) [ ( A, / Ag ) 5. 1 Eq.6L30

=

F, the actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS l The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow l

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, 4E l l

l F,, = the actual circulating water system flow rate j The flow rate of each circulating water pump is 203,000 gallons per minute.

30 Equation 6L has been derived f rm 10 eFP 20, Apperdix B Table 11, hote 1.

a n .

Offsite Dose Calculation Manual Page 47 of 247 Revision 1, Change 0 l

F,, = the salt water system flow rate t,f 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. l l

The maximum flow rate for one salt water pump is listed on Attachment 2.

=

F, actual undiluted radwaste flow rate (gpm) l 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.

Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm )

A, =

the specific activity 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 II, Note 1.

! Simplified method c)

(1) Whenever a computer system and appropriate software are unavailable to perform the rigorous calculations described in the previous section, ensure the concentrations of radionuclides in UNRESTRICTED AREAS are less than one MPC by verifying the following inequality is true.

LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (SIMPLIFIED METHOD)

{ F, / [ ( F, ) ( A,333t, ) ( K,, ) ] } [ A, i 1 4M

=

F, actual undiluted radwaste flow rate (gpm) l 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.

l

. this equation has been oerived fece 10 CFR 20, Appendix B. Tablo II, kote 1.

Offsite Dose Calculation Manual Page 48 of 247 Revision 1. Change 0 t

Values of rnaximum undiluted radwaste flow rates for various waste streams are tabulated in

{ Attachments 2 and 3.

F, = the actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS l The actual dilution water flow rate is the sum of the circulating water llow rate, the salt water flow l rate, and the undiluted radwaste flow rate.

DILUTION WATER FLOW RATE

=

F, F ,+ F,, + F, Eq.2L F, = the actual circulating water system flow rate l

The flow rate of each circulating water pump is 200,000 gallons per minute.

F,, =

the actual salt water system flow rate l

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 muimum flow rate for one salt water pump is listed on Attachment 2.

Ag =

the specific activity limit for 1-131 corresponding to the limiting concentration specified in 10 CFR 20, Appendix B, Table II, Column 2 This value is 3E-7 microcuries per milliliter.

A, =

the specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per 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 II, Column 2, (unitiess) (per Technical Specification 3.11.1.1)

The safety factor 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 II, Column 2.

A safety factor of 1.00 will yield a activity which corresponds to the 10 CFR 20, Appendix B, Table II, 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 D, 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.

l

.. S

Offsita Dose Calculation Manual Page 49 of 247 Revision 1, Change 0 The particular value selected for the safety factor is somewhat arbitrary, however a safety factor !

,(' does provide plant personnel with a degree of admmistrative control over the use of simplified l equations for generating radioactive liquid release permits. This administrative control is designed to minimize the possibility of violating 10 CFR 20, Appendix B, Table II, Column 2 limits I whenever simplifying assumptions are used.

The use of a safety factor is consistent with 10 CFR 20.l(c) which states that the licensees should,

" .. in addition to complying with the limits set forth in this part [10 CFR 20], 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 1-131 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 I-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 limits for concentration of radionuclides

( in liquid effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.1.1 for acticns to be taken in the event the l

concentrations of radionuclides in UNRESTRICTED AREAS exceed one MPC.

F. Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents

1. Introduction

, a) Appendix I to 10 CFR 50 specifies total body dose limits and organ dose limits associated with the release of radioactive liquids to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluenttontrols are described below.

2. Radiological Effluent Controls -l l

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 l mrems per calendar year (Technical Specification 3.11.1.2). l l

9

Offsite Dose Calculation Manual Page 50 of 247 Revision 1, Change 0 i 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 (Technical Specification 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 UhTESTRICTED 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 Technical Specification 4.11.1.2 and 4.11.1.3).

b) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the current 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 Technical Specification 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, 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 Technical Specification 4.11.1.2).

b) For B ATCH 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 32 (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 body 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:

32

( rhe towra LIMITS of DETECilok shall conform to Technical specification 4.11.1.1.1, Table 4.11 1.

Offsite Dose Calculation Mriual Page 51 of 247 -

Revision 1, Change 0 k-CUMULATIVE TOTAL BODY OR ORGAN, o, DOSE FROM LIQUID RELEASES, r Dg =

[ D,, Eq.8L

=

D. rot the sum total of the total body or organ, o, dose for all liquid 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 resulting from any single release of radioactive l$q' u(i.e., the total body and id to an UNRESTPJCTED 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 l

(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 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, F, ROM A LIQUID RELEASE (R]GOROUS EQUATION)

D, =

{ V, / [ ( 60 )( F, )) } [ { ( A, ) ( Cg } } Eq.9L33 ;

Where, 33 Equation 9L has been oerived from FJREG 0133, 4.3.

l w

Offsite Dose Calculation Manual = Page $2 of 247 Revision 1 Change 0 F, = actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS l The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow l rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated in accordance with equation 2L.

i DILUTION WATER FLOW RATE F, =

F,, + F,, + F, 4E F, = actual circulating water system flow rate l The flow rate of each circulating water pump is 200,000 gallons per minute.

F,, = actual salt water system flow rate l 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.

i The maximum flow rate for one salt water pump is listed on Attachment 2.

q

= actual undiluted radwaste flow rate (gpm)

F, l 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.

V, = vo!ume of undiluted radwaste (gallons)

A, = specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

Cg = 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

._ i

Offsite Dose Calculation Manual Page 53 of 247 Revision 1, Change O.

. i, .(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 radioactive liquid to an UNRESTRICTED AREA-may be calculated in accordance with equation 10L.

(2) Whenever a computer system is unavailable to perform the rigorous organ dose calculations de.ccribed 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 sccordance with equation 11L. l TOTAL BODY DOSE FROM A LIQUID RELEASE (SIMPLIFIED EQUATION)

Dg =

{ [ ( 58.6 ) ( V, ) ] / [ ( K,, ) ( F, ) ] } [ A, 4 M@

I D, =

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 /ml (the dose factor for Cs-134 to the lower gastrointestinal tract)

2) 1.000 hr/60.00 min

3) 1.000 gallons /3.785 liters V, =

volume of undiluted radwaste (liters)

Ky =

a constant, actually a safety factor, which is the ratio of the CCNPP total body dose limit to the total body dose limit of Specification 3.11.1.2, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the total body dose is ahvays less than or equal to the total body dose limit of Specification 3.11.1.2.

A safety factor of 100 will yield a total body dose which corresponds to the total body dose limit of Specification 3.11.1.2.

Eqsations 10L has been derived f rom WUREG-0133, 4.3.

i 0

Offsite Dose Calculation Manuel Page 54 of 247 Revision 1 Change 0 l

{

A safety factor of 0.500 will yield an total body dose which corresponds to one-half the total body i

! dose limit of Specification 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 Eenerating radioactive liquid release permits. This admmistrative control is designed to minimize the possibility of violating Technical Specification 3.11.1.2 when simplifying assumptions are used.

'Ihe

use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should,

. . in addition to complying with the limits set forth in this part [10 CFR 20], 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.

=

F, aM Nm wam b ram @W p&r m h ph d reb m WEmmD MM l .

The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow l 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

d

=

F,, + F,, + F, 4A F, = actual circulating water system flow rate l

The flow rate of each circulating water pump is 200,000 gallons per minute.

F, = actual salt water system flow rate l

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) l s

j

' i

Offsite Dose Calculation Manual Pcge55 of 247 Revision 1. Change 0 l[ If the actual undilut:.d radwaste flow rate is less than l'A 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, =

specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

DOSE TO THE ORGAN, o, FROM A LIQUID RELEASE (SIMPLIFIED EQUATION) 35 D, =

{ [ ( 449 ) ( V, ) ) / [ ir( K ) ( F, )) } [ A, Eq.IIL

=

D, the dose commitment to the maximum exposed ORGAN due to each release of radioactive liquid waste to ars UNRESTRICTED AREA 449 = a conversion constant which includes:

1) 1.02E5 mremitt per microcurie /ml (the dose factor for 1-131 to the thyroid)

2) 1.000 hr!60.00 min I 3) 1.000 gallons /3.785 liters <

V, =

volume of undiluted radwaste (liters)

K sr = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Specification 3.11.1.2, (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 Specification 3.11.1.2.

A safety factor of 1.00 will yield a orFan dose which corresponds to the orgu dose limit of .

Specification 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 Specification 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 I does provide plant personnel with a degree of administrative control over the use of simplified I equations for generating radioactive liquid release permits. This administrative controlis designed I to minimize the possibility of violating Technical Specification 3.11.1.2 when simplifying assumptions are used.

] Equations 11L has been derived f rom NUREG-c133, 4.3.

f

. Offsite Dose Calculation Manual Page 56 of 247 Revision 1. Change 0

(,

The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should,

(' .

" . in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effon to maintain radiation exposures, and releases of radioactive materials in effh'ents to UNRESTRICTED ARE AS, as low as is reasonably achievable."

This safety factor has been included in equation llL to account for any potential nonconsenatism associated with applying the 1-131 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.

F, =

dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flew rate is the sum of the circulating water flow rate, the sah water flow l rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated in accordance with equation 2L.

DILUTION WATER FLOW PATE F, =

F ,+ F, + F, Eq.2L

=

, actual circulating water system flow rate l

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 J rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

4

=

F, actual undiluted radwaste flow rate (gpm) l 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.

I Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. l A, =

specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

7. Corrective Actions

( 1

\

72,; g y _ .~ ~2= = . . . _ _ , _ _ _ -

~- a m .

~

Offsite Dose Celculation Manual' Page 57 of 247 Rcrision 1. Chtnge 0

)' a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification limits for 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 Technical Specification 3.11.1.2 for actions to be taken in the event the calculated cumulative total body dose exceeds 3 mrem per calendar quarter or 6 mrem per calendar year.

c) Refer to Technical Specification 3.11.1.2 for actions to be taken in the event the calculated cumulative organ dose-for any organ-exceeds 10 mrem per calendar quaner or 20 mrem per calendar year.

G. Limits For The Liquid Waste Processing System

1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the liquid 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.

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 Technical Specification 3.11.1.3).

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 Technical Specification 3.11.1.3).

c) The routine surveillances which are performed to verify compliance with this ndiological effluent controls are described below.

3. Surveillance Requirement (s) a) The previous 92-day, cumulative, total body dose-to hEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-shall be calculated, as described in the ODCM, at least once per 60 days'(per Technical Specification 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 q once per 60 days (per Technical Specification 4.11.1.3).

4

. ~ . , _ .- . . . .- .

Offsite Dose Calculation Manual Page 58 of 247

' Revision 1, Change 0 c) The CCNPP organization (s) responsible for performing these surveillances are

-( idertified in the next section.

4. Responsible Plant Organization (s) I a) The Chemistry Scction is responsible for performing the surveillances, listed above, whenever the appropriate irutiating conditions, listed below, are present.

5. Initiating Conditions a) Perform the surveillances, listed above, at least once per 60 dcys (per Technical Specification 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 secdon procedures.

c) For CONTINUOUS releases, perform the surveillances, listed above, at least monthly 36 (until the CONTINUOUS release has been tenninated) 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 contained in the following section.

( 6. t .ulation Methodology a) The cumulative total body dose and the cumulative organ doses for the previous 92 days shall be calculated in acccrdance 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 a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification limitt a 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 Technical Specification 3.11.1.3 for actions to be taken in the event the calculated cumulative total body dose exceeds 0.36 mrem for the previous 92 days.

c) Refer to Technical Specification 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.

The LOWER LIMITS oF DETEeflow shall conform to Technical specification 4 11.1.1.1, Table 4.11 1.

9

Offsite Dose Calculation Manual Page 59 of 247-Revision 1, Change 0 VI. RADIOACTIVE GASEOUS EFTLUENTS A. Release Pathways

[B527]

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 leaks), there are 2 pathways by which waste gas from the site may be discharged :o the atmosphere. These pathways are listed below. General information related to each of these potential release pathways is contained on Attachment 7.

(1) Unit 1 main vent stack (2) Unit 2 main vent stack c) Depending on plant conditions, (e.g., primary-to-secondary leaks) a potential exists for the release of radioactive materials from other pathways. These f.athways are listed below. General information related to each of these potential reluse pathways is contained on Attachment 8.

(1) auxiliary boiler deaerator (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 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 I main vent stack.

i b) The radioactive gaseous waste is mixed with and diluted by the outside air and buildmg exhausts prior to exiting the Unit I main vent stack.

c) The Unit 1 main vent stack is secured to the Unit I reactor containment building.

(

Offsite Dose Calcelation Menual Page 60 of 247 Revision 1 Change 0 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 containment building dome. As a result, the Unit 1 main 37 vent stack does not qualify as a " free-standing" stack greater than 80 rneters tall .

c) The Unit 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 sivA 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 radioactiva caseous waste is mixed with and diluted by the outside air and building exhausts prior riting the Unit 2 main vent stack.

d) The Unit 2 main vent stack is secured to the Unit 2 reactor containment building.

e) The top of the Unit 2 main vent stack is at elevation 203.5 feet (MSL), and as such is 10.1 feet above the top of the reactor 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.

I 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 vem 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 leak, the MSR steam could become contaminated.

Therefor, a potential exists for the release of radioactive gases in steam discharged from the auxiliary boiler deaerator.

c) The discharge of steam is accomplished via a re:ief vent. 0-VBV-1891, which allows excess pressure to be vented to atmosphere.

d) In the event the auxiliary boiler deaerator 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:

(1) the MSR steam activity obtained from a sample.

(2) the duration of the discharge, As defined by Repletory Guide f 37 .M

Offsite Dose Calculation Manual Page 61 of 247 Revision 1, Change 0 (3) the estimated steam discharge flow rate, and (4) the measured or average annual metrological conditions, e) 38 In accordance with applicable safety evaluations , continued operation of this system is allowed as long as the concentration of radionuclides h the 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 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 metrological conditions, d) The total capacity of the atmospheric steam dump valve is 5 percent of steam flow with the reactor at full power (per UFSAR,10.1.2.1),

3

6. Plant Nitrogen System a) Radioactive gases are not normally vented from this pathway, b) Nitrogen is supplied to various components 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 resuhing doses / dose rates at the site boundary can be estimated if the following parameters are known:

(1) the specific activity,of the gas in the plant nitrogen system as determined by GAMMA ISOTOPIC ANALYSIS, (2) the pressure of the nitrogen system, (3) the volume of the nitrogen system, and (4) the measured or average annual metrological conditions.

see 50.59 tog ko. 90 0-027-037 RI.

k

Offsite Dose Calculation Manual Page 62 of 247 Revision 1, Change 0.

d) It should be noted that the amount of radioactivity released could be estimated based on

{ knowledge of other related parameters, 3

e) In accordance with applicable safety evaluations ', continued operation of this system is allowed as long as the concentration of radionuclides is less than 13,400 MPCs.

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, (2) the duration of the discharge, (3) the estimated flow rate during the discharge, and (4) the measured or average annual metrological conditions.

8. Emergency Air Lock a) Radioactive gases are not normally vented from this pathway.

( b) In the event radioactive gases were to be released through the emergency air lock, the amount of radioactidty released and the resulting doses / dose rates at the site boundary can be esttmated if the following parameters are knowm:

(1) the containment air activity obtained from a sample, (2) the volume of the a:r lock (9.558 cubic meters),

(3) the measured or average annual metrological conditions. '

9. Plant Compressed Air a) Radioactive gases are not normally vented from this pathway.

q b) In the event the plant compressed air 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 knowm:

(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

' see 50.59 Los he. 90 0 074-011 R1

i Offsite Dose Calculation Manual Page 63 of 247 Revision 1, Change 0

]

l (4) the measured or average annual metrological 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. Other unmonitored release paths should be evaluated and added to the ODCM as necessary.

B. Types of Gaseous Releases

1. All gaseous radwaste releases are classified as either BATCH releases or CONTINUOUS releases.

2. The definition of BATCH release is included in the definitions section of the ODCM.

3. The definition of CONTINUOUS release is included in the defmitions section of the ODCM.

4. Gaseous radwaste discharges have been classified as CONTINUOUS or BATCH as shown on l Attachments 7 and 8.

a C. Processing Equipment

1. Simplified Flow Diagram a) An overview of the gaseous waste processing system, including major equipment imd (norrnal) flow paths, is outlined on Attachment 9.

2. Modifications a) Major changes or modifications to the gaseous waste processing system shall be reponed to the Commission in the Semi-annual Radioactive Effluent Release Report for the time interval in which the modification was completed (per Technical Specification 6.18.1).

b) A

major

change or modification includes, but is not limited to, the removal or permanent bypass of any of the following:

(1) waste gas decay tank (2) waste gas surge tank i

Offsite Dose Calculation Manual Page 64 of 247 Revision 1, Change 0

! 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."

D. Gaseous Efiluent Radiation Monitors And Setpoints

1. Wide Range Gas Monitor (1-RE-5416) a) General description (1) The Wide Range Gas Monitor (WRGM) contains 3 radiation elements (a) low-range noble gas detector i) Designation of radiation element: 1-RE 5416 ii) type of radiation element: Off-line scintillation iii) output: digital i

iv) Radiation indic.ator: 1-RIC-5415 v) units for radiation indicator are user programmable and are _;

normally set to microcuries per cubic centimeter vi) supplier: Sorrento Electrorucs (formerly General Atomics)

(b) mid range, noble gas detector i) Designation of radiation element: 1-RE 5417 ii) type of radiation element: Solid state iii) This noble gas monitor is used to measure the release of ,

radioactivity from unit I main vent in the event of an accident. l (UFSAR,11.2.3.2.12) l t

iv) setpoints for the mid-range detector will not be addressed in the ODCM (c) high-range, noble gas detector i) Designation of radiation element: 1-RE-5418 li) type of radiation element: Solid state

Offsite Dose Calculation Manual Page 65 of 247 Revision 1, Change 0 h iii) 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.

b) Functions of 1-RE-5416 (1) continuously measure the release rate of noble gases emanating from the Unit 1 main vent stack (Technical Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2)

(2) continuously indicate (via 1-RIC-5415) the release rate of noble gases emanating from the Unit I main vent stack (Technical Specification 4.11.2.1.1 or Technical Specification 4.11.2.1.2, Table 4.11-2)

(3) alarm (via 1-RIC-5415) prior to exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mr/yr (per Technical Specification 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 Technical Specification 3.11.2.1.a) l c) OPERABILITY cf 1-RE-5416 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of perfonning its specified function (s)'U (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 low 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 meascring noble gas activity released via the Unit 1 Plant Vent Stack.

Technical Specification 1.6 k

Offsite Dose Calculation Manual Page 66 of 247 Revision 1, Change 0 (4) In the event PRIMARY MONITOR (1-RE-5415) is inoperable or otherwise 3 (. unavailable, the BACKUP MONITOR (1-RE-5416) is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR.

c) Radiological effluent controls for 1-RE 5416 (1) Technical Specification 3.3.3.9 states that releases via the plant vent stack may 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 mr/yr to the total body and are less than 3000 mrlyr to the skin (per Technical Specification 3.11.2.1.a), or (b) an " equivalent monitor" (see " Monitors Equivalent to 1-RE-5416" -

earlier in this section) is operable AND the alarm and trip setpoint(s) l 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 Technical Specification 3.II.2.1.a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in accordance with Specifications 3.11.2.1.a. 4.11.2.1.1, and 4.11.2.1.2 (per Technical Specification 4.3.3.9, Table 3.3-12,

ACTION 37).

f) Surveillances for 1-RE-5416 .

(1) Technical Specification 4.3.3.9 requires dernonstrating the OPERABILITY of 1-RE-5416 by satisfying the checks, calibrations, and tests listed below:

(a) CH ANNEL CHECK within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

(b) SOURCE CHECK within the past 31 days (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Serpoints for 1-RIC-5415 (1) Requiremenu and commitments (a) The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM.

(Technical Specification 3.3.3.9)

Technical specifications Table 1.2

'1

Offsite Dose Caisulation Manual Page 67 of 247 Revision 1, Change 0 (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 alann setpoints associated with, or otherwise related to, the WRGM.

(a) 1 RIC-5415 fued high-high radiation alarm serpoint (b) 1-RIC-5415 faed high radiation alarm setpoint-(c) 1-RIC-5415 adjustable plant computer high radiation alarm serpoint (3) In order to simplify the serpoint terminology, elimmate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these serpoints as follows (a) The 1-RIC-5415 high-high radiation alarm setpoint will be referred to as the ftxed high alarm serpoint l

(b) The 1-RIC-5415 high radiation alarm setpoint will be referrt.d to as the fued alert setpoint l

(c) The 1-RIC-5415 adjustable plant computer high radiation alarm serpoint will be referred to as the adjustable setpoint (4) Each of these alarm serpoints are described below.

( h) Fixed high alarm setpoint for 1-RIC-5415 l

(1) General information (a) The high alarm setpoint is considered to be a fixed serpoint. The fixed high alarm serpoint is not adjusted for each release.

l (b) Whenever the fixed high alarm setpoint is exceeded, an alarm will be generated. l.

(c) The current value for the fixed high alarm setpoint is specified in the l CCNPP Alarm Manual.

(d) The CCNPP Alarm Manual 42 refers to the fixed high alann setpoint as the Unit I Wide Range Noble Gas Radiation Monitor high alarm serpoint.

4 (e) The fixed high alarm serpoint is integral to the WRGM, as purchased from the supplier. l (f) The fixed high alarm setpoint is administratively controlled by CCI-205. l 42 The CeNPP Alarm Ma%el is controlled by CCl 302.

f

'i

Offsite Dose Calculation Manual Pcge 68 of 247 Revision 1, Change 0 (g) The fixed high alarm serpoint shall be calculated as described below. l (2) Calculating the fixed high alarm serpoint for 1-RIC-5415 (a) The fixed high alarm setpoint for 1 RIC-5415 (WRGM) shall be l calculated in accordance with equation 1G.'3 FIXED HIGH ALARM SETPOINT FOR l-RIC-5415 Sg $_ [c' / ( x/Q ) ] [ F,, / ( F,, + F,, ) ] [ A rto 3 N' Where.

=

Sg the fixed high alarm serpoint for 1 RIC-5415 (microcuries per second) c' =

a conversion constant (IE6 cubic centimeters per cubic meter) 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)

Unit 1 main vent releases are considered *long-term" releases'5, and as such, the highest historical annual average dispersion factor, (x!Q), is used in the setpoint calculations.

( The hichest 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 contentrations (e.g., routine noble gas releases)

(UFS AR, 2.3.6.3)

F,, = the estimated main vent sta:k (diluted gaseous radwaste) flow rate for unit, x, (cubic meters per second)

The estimated main vent stack flow rates for Unit I and Unit 2 are defined below.

Fg = 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.

Use the nominal Unit I main vent stack flow rate listed on Attachment 7.

The alarm and trip setpoints ... shatt be deterzined and adjusted in accordance with the methodology and parameters of the CCCM. (Technical specification 3.3.3.9).

Equation 1G has been derived f rom NUREG-0133, 5.2.1.

NJREG 0133, 3.3 m ~ - y

Offsite Dose Calculation Manual Page 69 of 247 Revision I, Change 0.

/

This nominal main vent stack flow rate is based on the results of an approved engineering test t( procedure" The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (d. 25%). 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 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.

Fg =

the estimated main vent stack (diluted gaseous radwaste) flow rate for unit 2 (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 alarm serpoint.

l 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'7 The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (f. 259). 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 responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for eith:r Unit 1 or Unit 2 has in: cased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

Ag =

the sum of the total specific activities of all radionuclides found in TYPICAL GASEOUS 3

RADWASTE RELEASES (microcuries/cm )

Calculate A g in accordance with equation 2G.

SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT

[ [ ( f, ) ( An.n)lIAiuI bMPc Eq. 2G" Where, see ETP 87-16, Revision 0, " Main Vent Stack Flow Measurement

Unit 1", conpleted in Novecber 1987.

see ETP 8716, Revision D. " Main Vent Stock Flow Measurement - Unit 2", conpleted in Novecber 1987 This equation has been derived from 10 cFR 20, Apoendix B, Table II, hote 1.

n

l Offsite Dose Calculation Manual Page 70 of 247

. Revision 1, Change 0 l

I' fj =

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.

Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, >

Column 1 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B. Table II, Column 1.

For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E-14 microcuries per milliliter as the value for Ag (per 10 CFR 20, Appendix B, Note 2).

Lgpc =

the site MPC limit (MPCs) for unrestricted areas The value chosen for L,, 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 lunits of Specification 3.11.2.1(a),

h should be noted that by using ~2" as the MPC limit (10 CFR 50.72), instead of using the limits of Specification 3.ll.2.l(a), a safety factor has been incorporated into equation 2G.

t An alarm serpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4-g hour NRC notification" (specified in 10 CFR 50.72) is required.

(3) Documenting the fixed high alarm serpoint (a) Whenever the fixed high alarm setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with CCl-205.

(4) Changing the fixed high alann setpoint for 1-RIC-5415 (a) If the fixed high alarm setpoint calculated in accordance with equation IG 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 established at values lower than the maximum allowable serpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in the setpoint calculation equations (identified in this sec; ion of the ODCM) have changed.

Addende To setpoint calculations For WRcM Monitors 1 Ric 541s and 2 RIC 5415, R.L. conatser, Decenber 10, 1991.

5

l Offsite Dose Cciculation Manual Page 71 of 247 Revision 1, Change.0 -

(d)

'{ The fixed high alarm setpoint should not be changed unless one of the following occurs:

I i) the relative activity50of 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 serpoint, ii) the historical maximum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (Lg ,c) has changed. l iv) the Unit 1 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 II, column I have changed, vi) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or L

vii) the monitor is not conservative in its function (see " Functions of I RE-5416" earlier in this section). l (e) CCl-205 contains the administrative controls associated with changing

{ and approving fixed high alarm setpoint.

l i) Fixed alert setpoint for 1-RIC-5415 l .

(1) General information (a) The fixed alert setpoint is considered to be a fixed setpoint. The fixed alert serpoint is not adjusted for each release.

(b) Whenever the fixed alert serpoint is exceeded, an alarm will be generated. l (c) The CCNPP Alarm Manual does not reference this setpoint.

l-(d) The fixed alert setpoint is integral to the WRGM, as purchased from the l 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 CCI-205.

_l_

l As determined in accordance with Attachment 5.

. " " As determined by analysis of the TE-001 and ETP 87-16 test results.

~

i

'Offsite Dose Calculation Manual Page 72 of 247 Revision 1, Change 0

(, (g) The fixed alert setpoint shall be calculated as described below52.

l (2) Calculating the fixed alert setpoint for 1-RIC-5415 l

(a) The fixed alert serpoint for 1-RIC-5415 shall be calculated as described l below:

FIXED ALERT SETPOINT FOR l-RIC-5415 l

Sg < K,,[ Sng ]

Eq. 3G Where, Sg =

the fixed alert setpoint for 1 RIC-5415 (microcuries per second) l Sg =

the fixed high alarm setpoint for 1-RIC-5415 (microcuries per second)

K =

a'c nstant, actually a safety factor, which is the fraction of the fixed high setpoint (unitiess).

st l

The safety factor chosen shall be less than or eqt.al 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 alami serpoint.

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, l

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 Technical Specification 3.3.3.9 limits.

The

use of the safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should,

. in addition to complying with the limits set forth in this part [10 CFR 20], 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 trip serpoints ... should correspond to a value(s) which represents a safe margin '

of assurance that the instantaneous gaseous release limit of Specification 3.11.2.1(a) will not be exceeded." (per NUREG-0133,5.1.1).

The alarm and trip setoolnts .. shall be deterptined and adjusted in accordance with the methodology and parameters of the 00cM. (Technical specification 3.3.3.9).

l o

Offsite Dose Calculation Manual Page 73 of 247 Revision 1, Change 0.

[ 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 serpoint. l (3) Documenting the fixed alert alarm setpoint l (a) Whenever the fixed alert alann setpoint is calculated, the specific values l chosen for each of the variables shall be documented in accordance with CCI-205.

(4) Changing the fixed alert alarm setpoint for 1-RIC-5415 l (a) A setpoint change should be initiated whenever any of the parameters identified in equation 3G have changed.

(b) The fixed alert setpoint should be changed whenever the fixed high j setpoint is changed.

(c) The fixed alert setpoint should be changed if the value of the safety l factor is changed.

(d) See CCI-205 for a description of activities associated with setpoint changes and serpoint approvals.

I j) Adjustable alarm setpoint for 1-RIC-5415 (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 _l each release of a WGDT, each containment vent, and each containment 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 concentrations are determined by radiochemical analysis in accordance with applicable chemistry section procedures as required by Technical Specification 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 Alann Manual for a full list of operator actions taken in l response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT, a i containment vent, or a containment purge via the main vent.

(

Offsite Dose Calculation Manual Page 74 of 247 Revision 1, Change.0 (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-RIC-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.

(2) Calculating the adjustable setpoint for 1/2-RIC-5415 (a) The adjustable alarm serpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Technical Specification 4.11.2.1.2), and the alarm setpoint is calculated as shown below.

ADJUSTABLE ALARM SETPOINT FOR 1/2-RIC-5415 S

4 .$i. (1.50) ( Fg ) ( c' ) { [ ( F, / F,, ) [ ( Ag )( e )) + Bkg }

3 Eq.29G 53 S

ed; "*@****WObUMMON"N F"4 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 tenninated 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.5'

=

F, 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.

=

F,, the estimated main vent stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second)

Equation 29G has been derived from WREG 0133, Ackiendan, page AA 1.

The " analysis errors" and acalibration errors" refer to errors which are within established cpality assurance and quality control limits.

a

Offsite Dose Calculation Manual Page 75 of 247 Revision 1, Change 0

{ 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 Attaciunent 7.

This nominal 55 main vcat stack flow rate is based on the results cf 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 (i 25 %). 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 l 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.

A, =

specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or the containment building (microcuries per cubic centimeter)

=

e, absolute detector efficiency for nuchde, i (microculies Xe-133 equivalent per microcuries nuclide i)

The detector efficiency for each radion telide may b[ calculated from data collected during calibration of the radiation monitor.

Bkg =

an approximation of the detector background (microcuries per cubic centimeter)

I' c' =

a comersion constant (lE6 cubic centimeters per cubic meter)

(3) Documenting the adjustable alarm serpoint 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 serpoint 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 serpoint.

(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.

s 55 see ETP 87-16, Revision 0, ** Main Vent stock Flow Measurement - Unit 1", or ETP 8716, Revision 0, " Main Vent stack Ftow Measurement Unit 2, comleted in Novenber 1987

'f l

Offsite Dose Calculation Manual Revision 1, Change 0 Page 76 of 247 (c) Chemistry section procedures (e.g., CP-604) contain administrative y

\ 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 5416" carlier in this section), the calculated value for the adjustable serpoint shall be entered into the plant computer prior to each release of a WGDT, a containment vent, or a contabunent purge via the main vent.

2. Wide Range Gas Monitor (2-RE-5416) a) all information related to 1-RE-5416 is applicable to the Unit 2 WRGM with the following exceptions (s) b) Monitors equivalent to 2-RE-5416 (1) '

2-RE-5415 [the " Westinghouse Plant Vent Stack Monitor") has the capability of providing the measurement and alarm functions of 2-RE-5416 during times when 2-RE-5416 is declared inoperable (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)

(

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Offsite Dose Celculation Manual Revision 1, Change 0 Page 77 of 247

3. Westinghouse Plant Vent Stack Monitor (1 RE 5415) t_^

( a) The Westinghouse Plant Vent Stack Monitor contains 2 radiation elements (1)- 1-RE-5414 (a) particulate detector (b) off-line nintillation detcaot (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 (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 b) Functions of 1-RE-5414 (1)

The functions of 1-RE-5414 are mentioned here only as a basis for excluding this radiation element from the serpoint controls of Specification 3.3.3.9.

(2) This radiation element measures particulate activity contained on a moving particulate filter which is 99% efficient for particle sizes 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, *It is not considered to be practicable to apply instantaneous alarm and trip setpoints to integrating radiation monitors sensitive to radiciodines, radioactive materials in particulate form and radionuclides other than noble gases."

i

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Offsite Dose Calculation Menual Page 78 of 247 Revision 1. Change ()

56

' c) Functions of 1-RE-5415 (1)- continuously measure the activity (CPM) of noble gases emanating from the Unit I main vent stack (Technical Specification 4.11.2.1.2, Table 4.11-2)

(2) continuously indicate (via 1-RI-5415) the activity (CPM) of noble gases emanating from the Unit I main vent stack (Technical Specification 4.11.2.1.2, Table 4.11-2)

(3) alano (via 1 RI-5415) plior to exceeding the site bound:ry, noble-gu, total- s body-dose-rate limit of 500 mr/yr (per Technical Specification 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 Technical Specification 3.11.2.1.a) l 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)57 (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 almn functions of 1-RE-5415 during times when 1-RE-5415 is declared inoperable.

(2) 1-RE-5415 provides redundant monitoring [for 1-RE-5416] at the low 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.

(5) The absence of a radiation element dedicated to measuring the particulate -

activity in the Wide Range Gas Monitor does not preclude the use of I-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 Specification 3.3.3.9 (see " Functions of 1-RE-5414" carlier in this section);

this (radiation element) monitors noble gases. other radiation elements sonitor particulates in this waste stream.

Technical specification 1.6 -

.w . - u.-.. - -. ..- ...;- . . - = , - - .- .-

Offsite Dose Calculation Manual Page 79 of 247 1 Revision 1, Change O f) Radiological effluent controls for 1-RE-5415

(

(1) Technical Specification 3.3.3.9 states that releases via the plant vent stack may 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 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Technical Specification 3.11.2.1.a), or (b) an " equivalent momtor* (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 Technical Specification 3.11.2.1.a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in accordance with Specifications 3,lI.2.1.a. 4.11.2.1.1, and 4.11.2.1.2 (per Technical Specification 4.3.3.9, Table 3.3-12, ACTION 37).

(2) Technical specification 3.II.2.1.b (i.e., dose rates due te iodines and paniculates at the SITE BOUNDARY) is not applicable to noble gas detector or to the serpoints 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 control in this section of the ODCM.

g) Surveillances for 1-RE-5415 (1) Technical Specification 4.3.3.9 requires demonstrating the OPERABILITY of 1-RE-5415 by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sa (b) SOURCE CHECK within the past 31 days (c) CHANNEL CALIBRATION 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 serpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM.

(Technical Specification 3.3.3.9) i Technical Specifications Table 1.2 i

Offsite Dose Calculation Manual Revision 1 Chan e 0 . Page 80 of 247 (b) :

I- The method for calculating fixed or adjustable setpoints shall be k provided in the ODCM. (NUREG-0133,5.1.1)

(2) There are three alarms associated with, or otherwise related to,1 RE-5415.

(a) 1-RI-5415 fixed high radiation alarm setpoint (b) 1-RI-5415 adjustable plant computer high radiation alarm setpoint (c) 1-RI-5415 low radiation alarm serpoint (3)

In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpuints as felicas (a) The 1-RI-5415 fixed high radiation alarm serpoint will be referred to as the fixed setpoint.

(b)

The 1-RI-5415 adjustable plant computer high radiation alarm setpoin: '

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 serpoints are described below, i) The fixed serpoint for 1-RI-5415 (1) General information '

(a)

This serpoint is considered to be a fixed setpoint. The fixed setpoint is not adjusted for each release.

(b) Whenever the fixed serpoint is exceeded, an alarm will be generated.

(c) The current value for the fixed serpoint is specified in the CCNPP Alarm Manual. '

i (d) The CCNPP Alarm Manual refers to this setpoint as the 1-RI-5415 High Radiation Alarm Serpoint. 3 (e) The fixed setpoint is integral to the Main Vent (Westinghouse) RMS as purchased from the supplier.

l (f) The fixed setpoint is administratively controlled by CCI-205.

(g) The fixed setpoint shall be calculated as described below5 ', I (2) Calculating the fixed setpoint for 1-RI-5415 The alarmofand parameters trip setpoints the oDOM. ... shall be determined and adjusted in accordance with the methodology and (Technical specification 3.3.3.9).

i

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Offsite Dose Calculation Manual Revision 1, Change 0 Page 81 of 247 1

(a) The fixed high radiation alarm setpoint for 1-RI-5415 (plant vent stack

{ monitor) shall be calculated in accordance with equation 4G.

THE FIXED HIGH ALARM SETPOINT FOR 1-RI-5415 Sg <

{ K,, / I ( x/Q ) ( Fg + F, ) ] } [ [ ( e, ) ( Ag)] Eq.4G" Sg =

the fixed radiation alarm serpoint for 1-RI-5415 (counts per minute)

Kg =

a constant, actually a safety f actor, which is the ratio of the CCNPP activny itmit to the MPC hnut, L gpc, 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.

. equation A safety 2G.factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, Lyp A safety factor of 0.500 will yield a fixed high serpoint 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 se point, 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 adequate time to respon.! 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 Technical Specification 3.3.3.9 limits.

The

use of a safety factor is consistent with 10 CFR 20.l(c) which states that the licensees should,

. in addition to complying with the limits set forth in this part (10 CFR 20], 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, section 5.1.1, ,

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 Specification 3.11.2.l(a) will not be exceeded."

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors !

in detector efficiencies, and other statistical aberrations from adversely impacting the calculated '

fixed setpoint.

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)

)

i Eqaation 4G has been derived from WUREG-0133, 5.2.1, tthe 500 mr/yr egaation).

k 1

Offsite Dose Calculation Manual Page 82 of 247 Revision 1 Change 0

(,

Unit I and Unit 2 main vent releases are considered *long-term" releases, 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, 2.3.6.3).

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)

(UFS AR, 2.3.6.3).

F oi

=

h esad main a sd &w ram h M 1 Mc mews per san 4 Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal ma'm vent stack flow rate is used to calculate the fixed high :e:pcint.

Use the nominal Unit I 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 62 The main vent stack flow rate shall be determined, in aaordance 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 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 cn Attachment 7.

==

F,, the estimated main vent stack flow rate for unit 2 (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 serpoint.

Use the nominal Unit I 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 65 The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (i 25%). 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 responsible for modifying the (main vent flow rates used in the) ODCM in the event the 0'

NUREG 0133, 3.3 see ETP-87-16, Revision 0, " Main Vent stack Flow Measuremer.t - Unit 1", cor;!eted in November 1987 63

{ see ETP 87-16, Revision 0,

Main Vent stack flow Measurement - Unit 2", conpleted in hovecber 1987.

I I

Offsite Dose Calculation Manual Revision 1, Change 0 Page 83 of 247 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,

= 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, a = the specific activities of radionuclide, i, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated in accordance with 10 CFR 20, Appendix B, Table II, Note I as described below; microcuries per milliliter)

Calculate A g in accordance with equation 50.

SPECIFIC ACTIVITY LIMIT FOR NUCLIDE IIN A RADIONUCLIDE MIXTURE

=

A,tn ( f, ) ( A7t, ) Eq. 5G f =

3 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.

ATLn =

the sum of the total r,pecific activities of all noble gas radionuclides found in TYPICAL GASEOUS 3

RADWASTE RELEASES (microcuries/cm )

Calculate A7t, in accordance with equation 2G.

SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIf

[ [ ( f, ) ( Ag)]/ AgiLurc Eq.2G" Lgpg = the MPC limit The value chosen for Lgpg in this equation is 2. The basis for this limit is 10 CFR 50.72.

It has been shown65 that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Specification 3.3.3.9.

Ecuation 2G has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

[ Adde-dJn To Setpoint Calculations for WRcM Monitors 1-Ric-5415 and 2-Ric 5415, R.L. conatser, Deceeer 10, 1991.

I l \

Offsite Dose Calculation Manual Page 84 of 247

- Revision 1, Change.0 It should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Specification 3.11.2.1(a), a safety factor has been incorporated into 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 serpoints 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-hour 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 20.106(a).

Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B. Table II, Column 1 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTr 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 Ag (per 10 CFR 20, Appendix B, Note 2).

(3) The low alarm setpoint for 1-RI-5415 (a) The ODCM does not address the calculations associated with the low alarm setpoint.

(b) The low alarm setpoint is specified in the CCNPP Alarm Manual.

(c) The low alarm setpoint may be used to determine OPERABILITY of this monitor (in accordance with the provisions of Technical Specification 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 accordance 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 maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters i identified in equation 4G have changed.

(d) The fixed setpoint should not be changed unless one of the following occurs: )

(

l l

t

l Offsite Dose Calculation Manual Revision 1, Change O Page 85 of 247 ;

l i) 66

the relative activity of any radionuclide in TYPICAL

( GASEOUS EFFLUENTS has changed by greater than 10%,

j and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) the historical maximum annual average atmospheric dispersion )

i 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 67 stack flow rate has changed by greater than or equal to 10 % ,

v) the values listed in 10 CFR 20, Table II, column I 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" carlier in this section). l (e) CCI-205 contains the administrative controls associated with changing and approving fixed alarm setpoint.

( j) Adjustable alarm serpoint for 1/2-RI-5415 (1) General information 1

(a) This setpoint is an adjustable setpoint. Whenever this radiation monitor 68 is operable, the adjustable setpoint is calcu'ated and adjusted prior to each release of a WGDT, each ccatamment vent, and each containment 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, l whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable chemistry section procedures as required by Technical Specification 4.11.2.1.2).

As determined in accordance with Attachment 5.

As detern:ined by analysis of the TE 001 an:f ETP 87-16 test results.

68 The adjustable setpoint may or may not be changed for each of the releases tisted here. A determination of whether to change the setpoint would only be required when conducting sirrut'aneous releases (i.e., if a purge or a vent is conducted while a WGDT is atso being released). In this case, two adjustable setpoints would be ;

calculated (i.e., one adjustable setpoint for the vent or purge and one adjustable setpoint for the WGDT). In -l the (

into case of sinuttaneous the plant cocputer. releases, the tower (more conservative) of the two adjustabte setpoints should be input .l l

.I i

Offsite Dose Calculation Manual Revision 1, Change 0 Page 86 of 247 (c) Whenever the adjustable serpoint is exceeded, the WGDT, purge, or vent discharge via the main vent will be manually suspended.

(d) Refer to the Alarm Manual for a full list of operator actions taken in response to this alarm. l (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 serpoint 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-RI-5415 adjustable serpoint 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.

(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 Technical Specification 4.11.2.1.2), and the alarm serpoint is calculated as shown below.

ADJUSTABLE ALARM SETPOINT FOR 1/2-RI 5415 S; i I R ( F, / Fg , ) [ [ ( 4, ) ( e, ) + Mg )

aa

4. m" S

ed; = 6e a@aW alam serph br EEMM (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 Equation 27G has been derived from WUREG40133, Addende, page AA 1.

I

Offsite Dose Calculation Manual Rev!sion 1, Change 0 Page 87 of 247 I

rates, (3) statistical fluctuations in detector efficiencies and (5) errors associated with monitor calibrations.70 , (4) errors associated with sample analysis k

F, =

maximum undiluted radwaste flow rate (cubic meters per second)

Values 7.of Attachment maximum undiluted radwaste flow rates for various waste stre F,, =

h eskad second) main vem stad @W gaseous rakaste) How rate for unk x Mc mes per Since the main vent stack flow rate will vary depending on the reactor unit, the config dampers, and the input gas streams, a conservative, nominal main vent stack flow rate is calculate the adjustable serpoint.

Use the nominal main vent stack flow rate, for the appropriate unit, listed on Attachment 7 This nominal procedure 71 main vent stack flow rate is based on the results of an approved engin The main vent stack flow rate shall be determined, in accordance with approved proce once per 6 months (i 25 Tt). The Test and Equipment Unit shall be responsible for perfo test. The results of the main vent flow rate test shall be evaluated to en used in the ODCM are an accurate reflection of the true main vent flow rates. The R vent flow rates used in the) ODCM in the event the main has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

[

A =

specific a.tivity of radionuclide, i, in the undiluted waste stream, either the WGDT or conta building as applicable (microcuries per milliliter) e, =

absolute detector efficiency for nuclide, i (cpm /microcuries per millither)

The detector efficiency for each radionuclide may be calculated from data collecte calibration of the radiation monitor.

Bkg

= an approximation of the detector 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 accor approved chemistry section procedures (e.g., CP404).

The " analysis errors a and quality control limits.and " calibration errors" refer to errors which are within established quality assurance See tTP 87-16, Revision 0, amain Vent Stock flow Measurement Unit ia, or E7P 8716, Revision 0, " Main Vent stack Flow Measurement Unit 2, corpleted in hovember 1987, i

)

i

= . - ~

Offsite Dose Calculation Manual Revision 1, Chr.nge 0. Page 88 of 247 I

(4) Changing the adjustable alarm serpoint for 1/2-RI-5415 b

(a) In all cases, the adjustable alarm serpoint 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) Chemistry 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-RI-5415 (1)

This alarm is integral to the main vent monitor, as purchased from the supplier.

' (2) The current value for th: low alarm setpoint is specified in the CCNPP Alarm Manual.

(3) The low alarm serpoint may be used to determine the OPERABILITY of this monitor (per Technical Specification 4.3.3.9, CHANNEL FUNCTIONAL TEST).

(4) The alarm generated by the low alarm setpoint may be used to terminate a release in the event 1/2-RI 5415 fails (i.e., downscale failure or circuit failure) in accordance with Technical Specification 4.3.3.9.

(5) The low alarm setpoint calculations are not described in the ODCM.

(6) Changes to the low alarm serpoint are controlled by CCI-205.

4. Westinghouse Plant Vent Stack Monitor (2 RE-5415) a)

All information 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-5416 [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 5416] at the low end of the concentration ranges (UFSAR 11.2.3 2.12).

I

Offsite Dose Calculation Manual -

Page 89 of 247 Revision 1, Change 0 I- 5. Gaseous Rarlwaste Treatment System Radiation Monitor (0-RE-2191) k a) Gen.ral description (1) The GASEOUS RADWASTE TREATMENT WSTEM Radiation Monitor (Waste Gas Decay Tank Radiation Monitor) contains 1 radiation element.

(2) It is a noble gas detNtoi.

(3) The detector is an in-line GM tube (UFSAR, Table 11-10).

(4) The radiation element i= designated 0-RE-2191.

(5) The radiation indicators designated 0-RI-2191.

(6) The units fer the radiation indicator are counts per minute.

(7) The monitor was manufactured by Westinghouse.

b) Functions of 0-RE-2191 (1) continuously measure the release rate of noble gases emanating from the waste Fas decay tank discharge header (Technical Specification 4.11.2.1.2, Table 4.11-2)

(2) continuously indicate (via 0-RI-2191) the activity (CPM) of noble gases 1 emanating ' rom the waste gas decay tank discharge header (Technical Specification 3.3.3.9 OPERABILITY requirement)

(3) alarm (via 1-R'-2191) prior to exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mr/yr (per Technical Specification 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 Technical Specification 3.11.2.1.a) l c) OPERABILITY of 0-RE-2191 (1) This monitor shall be operable (or have OPERABILITY) when it is capable or performing its specified functica(s)7a ,

(2) For more information on the function (s) of this monitor, see " Functions of 0-RE-2191" elsewhere in th:s section of the ODCM.

d) Mordtors equivalent to 0-RE-2191 (1) There are no equivalent monitors associated with 0-RE-2191 since there are no other radiation monitors permanently installed in the waste gas discharge header, however, Technical Specification 3.3.3.9 defines the plant vent stack monitor as a " BACKUP MONITOR.'

Technical specification 1.6

Offsite Dose Calculation Manual' Revision 1, Change 0 Page 90 of 24'7 (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-5416) is designated the BACKUP MONITOR if the WGDT is discharged via the Unit I 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 MONITOP. has the capability of ensuring the noble gas activity .

released from the GASEOUS RADWASTE TREATMENT SYSTEM-to the plant vent stack--does not exceed Technical Specification 3.11.2.1(a) at the SITE BOUNDARY (Technical Specification 3.3.3.9).

(7) In the event PRIMARY MONITOR (0-P.E-2191) is inoperable or otherwise unavailable, the designated BACKUP MONITOR (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 every 15 minutes (Technical Specification 3.3.3.9, Table 3.3-12, ACTION 35a).

e) Radiological effluent controls for 0-RE-2191 (1) Technical Specification 3.3.3.9 states that releases via the GASEOUS I RADWASTE TREATMENT SYSTEM may continue if ANY ONE of the following three conditions are satisfied:

(a) 0-RE-2191 is operable AND the alarm and trip serpoint(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 mr/yr to the total body and are less than 3000 mrlyr to the skin (per Technical Specification 3.11.2.1.a), or (b) One " BACKUP MONITOR" (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 ct the SITE BOUNDARY are less than 509 mr/yr to the total body and are less than 3000 mrlyr to the skin (per Technical Specification 3.11.2.1.a), or (c) All three activities described below are completed prior to the release:

i) at least two independent samples of the waste gas decay tank's contents are analyzed, and ii) at least two technically qualified members of the Facility Staff independently verify the release rate calculations, and iii) two qualified operators verify the discharge valve lineup.

(

Offsite Dose Calculation Manual Page 91 of 247 Revision le Change 0 f) Surveillances for 0-RE-2191 (1) Technical Specification 4.3.3.9 requires demonstrating the OPERABILITY of 0-RE-2191 by satisfying the checks, calibrations, and tests listed below (a) CHANNEL CHECK prior to each release 73 (b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months ,.

g) Setpoints for 0-RI-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.

(Technical Specification 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.

I (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 serpoint (c) 0-RE-2191 low radiation alarm setpoint (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will ref r to these serpoints as follows (a) The 0-RE-2191 fixed high radiation alarm and automatic control trip serpoint will be referred to as the fixed serpoint.

(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 serpoint.

(4) Each of these alarm setpoints are described below.

Technicet specifications Table 1.2 r

Offsite Dose Csiculation Manual Revision 1, Change 0 Page 92 af 247 h) Fixed setpoint for 0-R]-2191 (1)

General information (a) This serpoint 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.

(c) Whenever the fixed serpoint is exceeded, an alarm will be generated, and the WGDT release will be automatically suspended.

(d) The fixed setpoint corresponds to the maximum concentration of radionuclides al! owed (by equation 6G) in gaseous waste discharged from the gaseous radwaste processing system.

(e) The current value for the fixed serpoint is specified in the CCNPP Alarm Manual.

(f) The CCNPP Alarm Manual refers to this setpoint as the 0-RI-2191 liigh Radiation Alarm Serpoint. '

(g)

The fixed setpoint is integral to the waste gas discharge monitor, as purchased from the supplier.

(h) The fixed serpoint is administratively controlled by CCI-205.

( (i) The fixed serpoint shall be calculated as described below7 '.

(2) Calculating the fixed serpoint 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:

FIXED ALARM AND TR]P SETPOINT FOR 0-RI-2191 Sg .<;. K sr { { l / [ ( x/Q ) ( F, ) ] } [ [ ( e, ) ( A3 )] + Bkg } Eq.6G 75 l Where, K =

'7 a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, 1"Mrc, used in equation 2G (unitiess)

- The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Technical specification 3.3.3.9).

Equation 4G has been derived from W'JREG-0133, 5.2.1, (the 500 mr/yr equation).

Offsite Dose Qlculation Manual Page 93 of 247 Revision 1, Change 0 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, Iwc, used in equation 2G.

A safety factor of 1.00 is used for calculating the fixed setpoint. 1 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 Lec)*

A safety2G.

equation factor of 1.00 will yieM a fixed serpoint which corresponds to the MPC limit, Lec' I" A safety factor of 0.500 will y. -

high serpoint which corresponds to one-half the MPC limit, Lyc, in equation 2G.

Other values of safety factors-not to exceed 1.00-may be used for calculating the fixed serpoint as directed by the General Supervisor Chemistry.

The particular value selected for the safety factor is somewhat arbitrary, however a value less than or equal to 1.0 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 Technical Specification 3.3.3.9 limits.

The use of a safety factor is consistent with 10 CFR 20 l(c) which states that the licensees should,

" .. in addition to complying with the limits set forth in this part [10 CFR 20], 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 trip serpoints . . should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Specification 3.11.2.l(a) will not be exceeded." (per NUREG-0133,5.1.1).

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 serpoint.

Sg =

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 meter)

A waste 76 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 serpoint 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).

6

. WREG 0133, 3.3 o

.t

Offsite Dose Calculation Manual Revision 1, Change 0 Page 94 of 247 i

The maximum annual average on-shore concentrations occur in the southeast sector at a

-( 1300 meters (UFSAR, for purposes of routine, long-term concentrations (e.g., routine noble ga 2.3.6.3).

=

F, the estimated meters per second) maximum flow rate of undiluted gases through the waste gas discharg Since WGDT pressure is the motive force for discharge of a WGDT, the waste gas flow ra '

continually decrease as the release progresses (i.e., as tank pressure is decreased).

Use the estimated maximum WGDT discharge flow rate, listed on Attachment 7, to calcula fixed setpoint.

e,

= absolute detector efficiency for nuclide, i (cpm /microcuries per milliliter)

The detector efficiency for each radionoclide may be calculated from data collected du calibration of the radiation monitor.

A,1

=

the specific activities of radionuclide, i, found in TYPICAL GASEOUS RADWASTE RELE (calculated microcuries per inmilliliter) accordance with 10 CFR 20, Appendix B, Table 11, Note 1 as described b Calculate Ag,in accordance with equation SG.

SPECIFIC ACTIVITY LIMIT FOR NUCLIDE IIN A RADIONUCLIDE MIXTURE

-(

A, g

=

(f)(ATLn )

3 Eq.5G f =

a fraction which represents the relative activity contribution of noble gas radionuclide i to th noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess)

This value may be obtained using the guidance provided on Attachment 5.

Ag

= the sum of the total specific activities 3 of all noble gas radionuclides found in TYPICAL GAS RADWASTE RELEASES (microcuries/cm )

Calculate Ag in accordance with equation 2G.

t SPECIFIC ACTIVITY OF NOBLE GASES AT THE SITE BOUNDARY

[ ( f, ) ( A7t, ) ) il.t/ A IbMPC 1

Equation 20 has been derived from 10 cFR 20, Appendix B, Tabte !!, Note 1.

k l

4 1 l

. Offsite Dose Calculation Manual Page 95 of 247 Revision 1, Change 0

)

i Where, Ly = the MPC limit The value chosen for L, in this equation is 2. The basis for this limit is 10 CFR 50.72.

7a 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 Specification 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 -

Specification 3.ll.2.l(a), a safety factor has been incorporated into 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 serpoints 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 setpoua corresponding to 2 MPCs serves to initiate a determination of whether the "4-hour NRC notification" (specified in 10 CFR 50.72) is required.

Ag =

the specific activity limit fgr radionuclide, i, as obtained from 10 CFR 20, Appendix B. Table II, Column 1 (microcuries/cm )

For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 1.

.( For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE l EFFLUENTS, use 2E-14 microcuries per milliliter as the value for Ag (per 10 CFR 20, Appendix B Note 2).

Bkg =

an approximation of the detector background prior to initiating the gaseous release (cpm) l 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. r,be specific vi!ves chosen foi cach of the variables shall be documented in accordance with CCI-205.

(4) Changing the fixed setpoint for 0-RI-2191 (a) If the fixed setpoint calculated in accordance with equation 6G 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.

0 Addendet To setpoint calculations For WRcM Monitors 1*Ric 5415 and 2-RIC 5415, R.L. Conatser, December 10, 1991.

(

Offsite Dose Calculation Manual ' Page 96 of 247 '

Revision 1, Change 0 >

(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 equations 2G, SG, or 6G have changed.

(d) The fixed setpoint should not be changed unless one of the following Occurs:

i) the relative activity" of any radionaclide 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 maximum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, iv) values listed in 10 CFR 20, Table II, column I 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" earlier in this section). l (e) CCI-205 contains the administrative controls associated with changing and approving fixed alarm setpoint, i) Adjustable alarm setpoint for 0-RI-2191 (1) General information (a) This serpoint is an adjustable setpoint. Whenever this radiation monitor 8U is operable, the adjustable setpoint is calculated and adjusted prior to each release of a WGDT.

As determined in accordance with Attachment $.

The adjustable setpoint may or may not be changed for each WGDT release, A determination of whether to change the setpoint would only be required when conducting sicultaneous releases (i.e., 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 the vent or purge and one adjustable setpoint for the W:DT). In the case of simultaneous releases, the lower (more conservative) of the two adjustable setpoints should be input into the

. .. plant conputer.

5

.. - - - . - --.- c. - - . . - - - - -,

. . t

~

Offsite Dose Calculation Manual .

Revision 1, Change 0 : Page 97 of 247 - ,

i (b)~ The adjustable setpoint is based on the' specific activities of the

' 'r -

( radionuclides present in the WGDT. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable chemistry section procedures as required by Technical Specification , 4.11.2.1.2).

(c) Whenever the adjustable setpoint is exceeded, the WGDT discharge ~ .

will be manually suspended.

(d) Refer to the radwaste Alann Manual for a full list of operator actions -l !

taken in response to this alarm.

(e) i The adjustable setpoint corresponds to the maximum concentration of 4 radionuclides anticipated or expected when discharging a WGDT.

{

(f) The value for the adjustable setpoint is recorded on the gaseous release i permit in accordance with applicable chemistry section procedures.

(g) >

This alarm is not integral to the gaseous radwaste treatment system radiation monitor, as purchased from the supplier.

lf (h) - This alarm is generated by the plant computer which monitors outpu't '

from 0-Rl-2191, 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 - I setpoint shall be calculated prior to each release of a WGDT as shown

{ below.

(2) Calculating the adjustable serpoint for 0-RI-2191 (a) !

The adjustable alarm and trip serpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by '

radiochemical analysis per Technical Specification 4.11.2.1.2), and the alarm and trip serpoint is calculated as shown below.

i ADJUSTABLE ALARM AND TRIP SETPOINT FOR 0-RI-2191 S,g ._ < l.50 [ [ ( A g) ( e,) + Bkg ]

Eq.28Gs1 x

S,g . . = l the adjustable alam) and trip serpoint for 0-RI 2191 (cpm) t 1.50

= a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess)

Equation 280 has been derived f rom NUREG-0133, Addends, page AA-1.

1 ,

i i

'Offsite Dose Calculation Manual Revision 1, Change 0 Page 98 of 247 i

if 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 and (5) errors associated with monitor calibrations.82 , (4) errors associated with sample analysi

=

F, maximum allowed undiluted radwaste flow rate (cubic meters per second)

The maximum allowed undiluted radwaste flow rate for a WGDT is tabulated in A, =

specific activity of radionuclide, i, in the undiluted waste stream (microcuries per 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 serpoint for 0-RI-2191 (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 serpoint for 0-RI-2191 (a) In all cases, the adjustable serpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the adjustable serpoint exceeds the maximum range of the monitor, the serpoint 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 serpoint.

(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 'J-2191 (1)

This alarm is integral to the main vent monitor, as purchased from the supplier.

The " analysis errors" aM " calibration errors" refer to errors which are within established quality assurance and quotity control limits, f

't

Offsite Dose Calculation Manual Revision 1, Change 0 Page 99 of 247 (2)

The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual.

(3)

The low alarm serpoint may be used to determine the OPERABILITY of this monitor (per Technical Specification 4.3.3.9, CHANNEL 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 Technical Specification 4.3.3.9.

(5) The low alarm setpoint calculations are not described in the ODCM.

(6) Changes to the low alarm setpoint are controlled by CCI-205.

E.

Annual Total Body Dose Rate Due To Noble Gases In Gaseous Effluents

1. Introduction a) 10 CFR 20.105 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b)

Radiological effluent controls have been established to implement the requirements 10 CFR 20.105.

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 Technical Specification 3.11.2.1).

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 dis from the site, shall be determined in accordance with equation 7G (per Technical Specification 4.11.2.1.1),

b)

The results of the radioactive gaseous waste sampling and analysis program (re by Technical Specification 4.11.2.1.2, and implemented by various CCNPP ch section procedures) are used to calculate the annual total body dose rate due to noble gases in gaseous effluents.

c)

The plant group (s) responsible for performing the required surveillances are identified below.

(

Offsite Dose Calculation Manual Page 100 of 247 Revision 1, Change 0

4. Responsible Plant Organization (s) k a) The Chemistry Section is responsible for calculating the annual total 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.

5. Initiating Conditions a) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each release of a WGDT.

b) The annual total body dose rate 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 s3 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.

5 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 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 equation 7G."

ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN ALL GAS RELEASES The frequency is controtted by the implementing procedure, CP-612, and is based on plant conditions. Under no corditions shalt the f requency be less than once per month tiechnical specification 4.11.2.1.1 or 4.11.2.1.2, Tabte 4.11 2).

The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the 00cM. (Technical specification 3.3.3.9).

- -- -- . _ . _ _ , , . - _ _ - ~ - . ~ . . - - . - .- ~ . - . . .. -

Offsite Dose Calculation Manual Page 101 of 247 Revision 1, Change 0 j{ Dg =

[ D, Eq.7G Dg =

the site-boundary annual total body dose rate due to noble gases in all gaseous effluents discharged (simultaneously) from the site (mrem / year) l D, =

the site-boundary annual total body dose rate due to noble gases in release, r (mrem / year) l Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would 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.

Calculate the values of D, for each SIMULTANEOUS RELEASE as shown below.

b) At CCNPP, two methods exist for calculating D, (i.e., annual total body dose rate at the STTE BOUNDARY due to noble gases contamed 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 routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 8G.

ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD) l

Offsite Dose Calculation Manual Page 102 of 247 Revision 1, Change 0

l i

D, =

( x/Q ) [ [ ( K; ) ( Q, ) ] Eq.8G 85 Where, !

I J

=

x/Q the highest calculated annual average relative concentration for any area at or beyond the I UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

B6 All releases are censidered "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)

(UFS AR, 2.3.6.3)

K3 =

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 tabulated in Ai achnent 10.

Qy =

the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r I

(microcuries/second).

Calculate 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 l Where, Ag =

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)

Fouations SG has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B 8 and section c.2.e).

NUREG-0133, 3.3

?

Offsite Dose Calculation Manual Page 103 of 247 Revision 1, Change 0 '

l f

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, volumc, 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 (IE6 cubic centimeters per cubic meter) l' d) Simplified method (1) If a computer system and the appropriate software are NOT available, tne annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 10G.

( ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD) t D, =

[ ( x/Q ) ( K, )/(K ir Qa Eq.10G 87 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) b as 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) (UFS AR, 2.3.6.3)

K,,8 the empirically derived, site specific, average, total body, dose factor due to gamma emissions from TYPICAL GASEOUS EFFLUENTS (mremlyr per microcurie / cubic meter) Equations 100 has been derived from NUREG 0133, 5.2.1, and historical, site specific data. NUREG 0133, 3.3 ( i

Offsite Dose Calculation Manual Page 1(M of 247 Revision 1, Change 0 y 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 factor is presented on 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. K, = 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 Specification 3.11.2.1, (unitless) 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 equal to the annual total body dose rate limit of Specification 3.11.2.1. A safety factor of 1.00 will yield an arumal total body dose rate which corresponds to the annual total body dose rate limit of Specification 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 Specification 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the annual total body 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 Technical Specification 3.11.2.1 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should,

                 " .. in addition to complying with the limits set forth in this part [10 CFR 20], 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 !M to account for any potential nonconservatism to all associated withinapplying radionuclides identified the gaseous the empirically

elease. (trivedcould Such nonconservatism tota, body gamma conce dose fact whenever radionuclides having a torG body gamma dose factor greater than K are present in a gaseous release.

Q, = 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 i IN GASEOUS RELEASE r

Q, ( A, ) ( F, ) ( c' ) Eq.9G l u l 1 i

Offsite Dose Calculation Manual Revision 1, Change 0 Page 105 of 247 Where, A, = the specifk activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) F, the discharge Dow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has no: been conducted), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual total bo dose rate. Whenever possible, the actual discharge flow rate determined from actual release conditions initial pressure, volume, and temperature of a WGDT along with final pressure and temperatur 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 (IE6 cubic centimeters per cubic meter) l c)      Radiation monitoring system algorithms (1)     The plant vent stack radiation monitoring systems display values 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 Technical Specification 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 release rates. (a) It is possible to approximate the noble gas release rates for the Unit I

                                          ~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 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 for the Unit I and Unit 2 main vents based on output from 1/2-RIC-5415. ( t

Offsite Dose Calculation Manual Page 106 of 247 Revision 1, Change 0 (b) These calculations are described elsewhere in the ODCM. (See equation IG in the section " Calculating the Fixed 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 CCI-205. 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 Technical Specification limits for annual total body dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.1 for actions to be taken in the event the calculated annual total body dose rate due to noble gases in gaseous effluents exceeds 500 mrlyr. F. Annual Skin Dose Rate Due To Noble Gases In Gaseous Efiluents

1. Introduction a) 10 CFR 20.105 specifies dose rate 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 20.105. 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 Technical Specification 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirement ,

t a) The annual skin dose rate at the SITE BOUNDARY, due to noble gases in all gaseous i effluents discharged from the site, shall be determined in accordance with equation 11G ; (per Technical Specification 4.11.2.1.1).

                                                                                                                     -l l

( l 1

,l

Offsite Dose Calculation Manual Page 107 of 247 Revision 1, Change 0 b) The results of the radioactive gaseous waste sampling and analysis program (required 'g(~ by Technical Specification 4.11.2.1.2, and implemented by various 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) responsibie 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 appropriate 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. c) The annual skin dose rate due to noble gases in all gaseous effluents 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 gaseous effluents discharged from 8 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 burning of contaminated oil. f) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the cite is calculated for each ABNORMAL AND/OR UNANTICIPATED r RADIOACTIVE GAS RELEASE (as defined in CP-612). E) Whenever the correct initiating conditions are present, the annual skin dose rates shall be calculated as described below.

6. Calculation Methodology The frequency is controlled by the inclementing procedure, CP 612, and is based on plant conditions. Under no conditions shall the freqsency be less than once per month (Technical speef fication 4.11.2.1.1 or 4.11.2.1.2,

 ,-  Table 4.11-2),

t i l i

Offsite Dose Calculation Manual Revision 1, Change 0 Page 108 of 247 a) The annual skin dose rate, at the SITE BOUNDARY, due to noble gases in all gaseous { effluents discharged simultaneously from the site to UNRESTRICTED AREAS shall be K. calculated in accordance with equation llG.'D i ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN ALL SIMULTANEOUS GAS RELEASES, r D,g = [ D,, Eq.11G

D,g the annual skin dose rate at the SITE BOUNDARY due to noble gases in all 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 would 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 I 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., annual total skin dose rate at the SITE BOUNDARY due to noble gases containe8in 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 routine use unless a computer system and appropriate software are available. The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodotogy and parameters of the 00 N. (Technical specification 3.3.3.9). ' (.

Offsite Dose Calculation Manual l Revision 1, Change 0 Page 109 of 347 (2) If a computer system and the appropriate software are available, the annual skin

)r                                            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) I], = ( x/Q ) [ { [ L, + ( l.1 ) ( M, ) ] ( Q,) } Eq.12G'l 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 92 , 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) (UFS AR, 2.3.6.3) ( L' = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mremlyr 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. 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. Q,, = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second). Equation 12G has been derived f rom NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Apperdix B, Equation B-9 ard section c.2.1). NUREG-c133, 3.3 I

Offsite Dose Calculation Manual Page 110 of 247 Revision 1, Change 0 This value shall be calculated in accordance with equation 9G. INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r - Q,, = ( A, ) ( F, ) ( c' ) Eq.9G l 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 flov/ 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 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) l-d) Simplified method (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,f ) ] [ L, + ( 1.1 ) ( M,y ) ] [ Q,, Eq.13G'3 Where,

 <      Equation 12G has been derived f rom NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (WWix B, Equation B-9 and

,f section c.c.f). I

     ' Offsite Dose Calculation Manual Revision 1, Change 0                                                                                 Page 111 of 247 x/Q      =                                                                                                             I t                    the highest calculated annual average relative concentration for any area at or beyond the              I 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. , l 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) 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 Specification 3.11.2.1, (unitless) The safety factor chosen 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 Specification 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 Specification 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 Specification 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the annual skin dose rate, i however, Chemistry. other values-not to exceed 1.00--may be used as directed by the General S'ipervisor The panicular 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 control is designed to assumptions areminimize used. the possibility of violating Technical Specification 3.11.2.1 when simplify The use of a safety factor is consistent with 10 CFR 20.l(c) which states that the licensees shou

                  ". . in addition to complying with the limits set forth in this part [10 CFR 20], 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 13G to account for any potentia! nonconservatism associated with applying the empirically derived skin beta dose factor, L to all radionuclides identified in the gaseous release. Such nonconservatism could conceivab7,be present whenever radionuclides having a skin beta dose factor greater than L are present in a gaseous release. L =

    "           the empirically derived, site specific, average, skin dose factor due to beta emissions from TYPICAL GASEOUS EFFLUENTS (mremlyr per microcurie / cubic meter)

A site-specific, average, beta skin dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

     ' MJREG 0133, 3.3 k

Offsite Dose Calculation Manual Page 112 of 247 Revision 1, Change 0 I The calculation of this site-specific, average, beta skin 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 beta skin dose factor. M = 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.

Q,, the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second) This value shall be calculated in accordance with equation 90. ( INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r ( Q, = ( A, ) ( F, ) ( c' ) Eq.9G l

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 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 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 (IE6 cubic centimeters per cubic meter) l l 1

                                                                                                                        ,        I'j

Offsite Dose' Calculation Manual Page 113 of 247 Revision 1, Change 0 E 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 Technical Specification 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 Sorrento WRNGM,1/2-RE-5416, is a digital radir. tion 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 IG in the section " Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.") (5) The instrument algorithms and the (data base) values accessed by the instrument algorithms are controlled by CCl-205. 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 Technical Specification limits for annual skin dose rate for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b)- Refer to Technical Specification 3.11.2.1 for actions to be taken in the event the calculated annual skin dose rate exceeds 3000 mr/yr.- j '(

. O

Offsite Dose Calculation Manual Page 114 of 247-Revision 1, Change 0 G. Annual Organ Dose Rates Due To lodines And Particulates In Gaseous Effluents t-

1. Introduction a) 10 CFR 20.105 specifies dose rate 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 20.105. 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 mr/yr (per Technical Specification 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 Technical Specification 4.11.2.1.2).

! b) The resuhs 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. 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 organ dose rates due to iodines and particulates in gaseous effluents.

b) The CCNPP Chemistry Section calculates the annual organ dose rates whenever the l appropriate initiating conditions are present. ' c) These initiating conditions are contained in the following section. i I

5. Initiating Conditions d

l l 1 l 1 ( l l l

Offsite Dose Calculation Manual Page 115 of 247 Revision 1, Change 0 a) The annual organ dose rate-for each organ and at the SITE BOUNDARY--due to h iodines and paniculates in gaseous effluents is calculated at least weekly" for \. CONTINUOUS discharges from plant vent stacks. ' 1 b) The annual organ dose rate-for each organ and at the SITE BOUNDARY-due to iodines and paniculates in gaseous effluents is calculated for each discharge of combustion products resulting from the burning of contanunated oil. I c) The annui organ dose rate-for each organ and at the SITE BOUNDARY--due to iodines and paniculates in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED 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 a) The annual organ dose rate, at the SITE BOUNDARY, due to iodine and paniculate radionuclides in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 14G.'7 ANNUAL ORGAN, o . DOSE RATE DUE TO IODINES AND PARTICULATES IN ALL SIMULTANEOUS GASEOUS RELEASES, r FROM THE SITE,0

( Dg = [ D,, Eq.14G Dg = the site-boundary annual organ dose rate due to iodine and particulate radionuclides in all gaseous effluents discharged simultaneously from the site (" Unit 0")

D,, the site-boundary annual organ dose rate due to iodine and paniculate radionuclides in release, r Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE would include the release ofiodines and particulate radionuclides from the Unit 1 plant vent stack while also discharging iodines and paniculate radionuclides 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 (Technical specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11 2). See the definition of ABNORMAL / UNANTICIPATED GAS RELEASE in the DEFINITIONS section of the 00CM. The alarm ard trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the 00cM. (Technical specification 3.3.3.9). .

-{

( i l

                                                                                                                           ^
                                                                                                                        'l    l

Offsite Dose Calculation Manual Revision 1, Change 0 Page 116 of 247 I 6 An example of a SIMULTANEOUS RELEASE would include the release of iodine and ( radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay Calculate the values of D,, for each SIMULTANEOUS RELEASE as shown below, b) At CCNPP, two methods exist for calculating D to iodine and particulate radionuclides in gaseouEe(ffluents released toi.e. UNRESTRICTED AREAS). (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 follcwing 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 annual ( organ dose rates due to iodines and particulates in gaseous effluents released to , an UNRESTRICTED AREA shall be calculated in accordanx with equation 15G. ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS R r (RIGOROUS METHOD) D,, = ( x/Q ) [ ( P, ) ( Q,, ) Eq.15G'8 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. Equetion 15c has been derived from NUREG 0133, 5.2.1. ' WOREG-0133, 3.3 l

Offsite Dose Calculation Manual - Revision 1 Change 0 Page 117 oi 247 (- h 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), g( The maximum annual average on-shore concentratics occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (UFSAR,2.3.6.3). P. =

           '             the maximum organ inhalation pathway dose parameter for iodine and particulate radionuclides, i, for the most restrictive (i.e., child) age group (mrem / year per microcurie / cubic meter)

The inhalation pathway dose parameter * ' *en obtained in accordance with NUREG4133, 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, therefor no pathway dose factors are calculated for the ground plane or food pathways. . The latest NRC guidance has changed the critical recep" 'ge group from " infant" to " child.* [ The child, inhalation pathway dose parameters for variot .adionuclides, sorted by critical organ, are tabulated in Attachment 12. It should be noted that the dose parameters, Pi , (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 anot conl,in two separate tables for values of P, and K;.

Q,, = the release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second). Calculate the values of Q,, for each SIMULTANEOUS RELEASE in accordance with equation 9G. INSTANTANEOUS RELEASER RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS Q, =- ( A,, ) ( F, ) { c' ) Eq.9G l A,, = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) ( 1

'I

Offsite Dose Calculation Manual' Page 118 of 247 Revision 1, Change 0 i F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) ( li 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 organ dose rate. Additional gaidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (IE6 cubic centimeters per cubic meter) l d) simplified method (1) If a computer system and the appropria'e software are NOT available, the annual organ dose rate due to iodines and particulates in gaseous eftluents 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) j D,, = ( 1/ Kg ) ( x/Q ) ( P, ) [ Q,, Eq.16G'00 Where, Ky = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose rate limit to the organ dose rate limit of Specification 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 Specification 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 Specification 3.11.2.1. A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose rate limit of Specification 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 control is , i Equation 16G has been derived f rom NUREG-0133, 5.2.1. l

                                                                                                                   =
                        ,n                                                     ,     - - - - ,

Offsite Dose Calculation Manual Page 119 of 247 i Revision 1, Change 0 i designed to minimize the possibility of violating Technical Specification 3.11.2.1 when simplifying l d assumptions are used. 1 The we of a safety factor is consistent with 10 CFR 20.l(c) which states that the licensees should, !

                      ... in adA.W to complying with the limits set forth in this part [10 CFR 20], make every rewnable 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 160 to account for any potential nonconservatism associated with applying the dose parameter, P to all radionuclides identified in the gaseous release. Such nonconservatism could conceivaEe,be present whenever radionuclides having a dose parameter greater than P., are present in a gaseous release.

               =   the highest calculated annual average relative concentration for any area at or beyond the x/Q UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered *long-term" releases'Ul, 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 ann Ja1 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) (UFS AR, 2.3.6.3). 2 t

               =  the most restrictive dose parameter which would be reasonably anticipated for the inhalation pathway, child age group, thyroid organ, and I-131 radionuclide (mrem / year per microcurie / cubic meter)

The inhalation pathway dose parameters have been obtained in accordance with NUREG4)l33, 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, therefor 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. ;

      'Ul wuRio-0133, 3.3 a.

Offsite Dose Calculation Manual Page 120 of 247 Revision 1, Change 0 t It should be noted that the dose parameters, P , (listed in Attachment 12) calculated in accordance ( with NUREG4)l33, section 5.2.1.1 and the la, test 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 conl,in a two separate tables for values of P, and K,.

Q"

              = the release rate of iodine or particulate 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 IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASER Q, = ( A, ) ( F, ) ( c' ) Eq.9G l A, = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) F, = the discaarge 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 g Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate. 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 (IE6 cubic centimeters per cubic meter) 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.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for annual organ dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.1 for actions to be taken in the event the calculated annual organ dose rate to any organ exceeds 1500 mr/yr. ( I,

   - Offsite Dose Calculation Manual                                                                Pcge 121 of 247 Revision 1, Change 0 H.       Cumulative Ganuna Air Doses Due To Noble Gases In Gaseous Effluents 7

1. Introduction '

a) Appendix 1 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 effluents released to UNRESTRICTED AREAS, shall be less than 10 mrads in any calendar quarter, and shall be less than 20 mrads in any calendar year (per Technical Specification 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 (Technical Specification 4.11.2.2).

l 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 quarter and the current calendar year.

b) The CCNPP Chemistry Section calculates the cumulative gamma air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative gamma air (oses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Technical Specification 4.11.2.2).

b) The curr.ulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each release of a WGDT (CP-604).

                                                                                                                         'I c)        The cumulative gamma air doses due to noble gases in gaser effluents shall be calculated for each vent of a containment building (CP-604).

( i l R

Offsite Dose Calculation Manual- Page 122 of 247 Revision 1, Change 0 I d) The cumulative gamma air doses due to noble gases in gaseous effluents shall be ( calculated for each PURGE of a containment building (CP-6N). e) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated at least weekly'U2 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 oit g) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE'03 (CP-612). 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, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated using the following equation' '-

CUMULATIVE GAMMA, g, AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dg = [D Eq.17G Where, D = 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 8' contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of D,, for each gaseous release as described below. C2 The f requency is controlled by the ifnplementing procedure, cP 612, and is based on plan't conditions. under no conditions shall the frequency be less than once per month (Technical Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2). 03 The criteria used to define ABWORMAL AC UhANT!elPATED gas RELEASES may be found in cP-612 or cP-604 The alarm and trip setpoints ... shall be detertnined and adjusted in accordance with the methodology and parameters of the 00CM. (Technical Specification 3.3.3.9). I c

                                                                                                                     ;     o

Offsite Dose Calculation Manual ' Page 123 of 247

Revision 1, Change 0 k' -

b) At CCNPP, two methods exist for calculating D i.e., the gamma air dose at the SITE BOUNDARY due to noble gas radionuclides coma (ined in a gaseous radw discharged from the site during a specified time intenal). (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 gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 18G. ( GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)

D,, ( 3.17E-8 ) { x!Q ) [ [ ( M, ) ( 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) 106 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 The highest annual average dirpersion 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). Equation 1BG has been derived from NUREG-0133, 5.3.1.. NUREG 0133, 3.3 t,

Offsite Dose Calculation Manual Page 124 of 247 Revision 1. Change 0, M. = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad /yr 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. Q(, = the total (time averaged) activity of nob!c 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\, ( A,, ) ( F, ) ( 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)

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.

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. l Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP401 and CP-604). tg = the duration of the gaseous radwaste release (seconds) c' = a conversion constant, IE6 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 equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS. J (4) The simplified method is presented below. i i 1

Offsite Dose Calculation Manual Page 125 of 247 Revision 1, Change 0 ( d) simplified method (1) If a computer system and appropriate 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. GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) Dy = [ ( 3.17E-8 ) ( x/Q ) ( M, ) / K,, ) [ Q'y Eq.20G'U7 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) All releases are considered long-term" releases'08, 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-term concentrations (e.g., routine noble gas releases) (UFS AR, 2.3.6.3). M = the empirically derived, site specific, average gamma air dose factor for each identified noble gas radionuclide, i (mradlyr per microcurie / cubic meter) 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.) K = a constant, actually a safety factor, which is the ratio of the CCNPP gamma air dose limit to the

   'f gamma air dose limit of Specification 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 Specification 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 Specification 3.11.2.2. 07 Equation 20G has been derived f rom NUREG 0133, 5.3.1. 108 WUREG 0133, 3.3 I

   . Offsite Dose Calculation Manual                                                                     Page 126 of 247 Revision 1, Change 0

-y A safety factor of 0.500 will yield an gamma air dose which corresponds to one-half the gamma air ( dose limit of Specification 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. 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 admmistrative control is designed to minimize the possibility of violating Technical Specification 3.11.2.2 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should,

                      . in addition to complying with the limits set forth in this part [10 CFR 20), make every reaso lable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is asonably achievable."

Tms 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 to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable *t%,present whenever radionuclides having a gamma air dose factor greater than M ara present in a gaseous release.

              = the total (time averageM activity of noble gas radionuclide, i, in gaseous release, r (microcuries)

Q] 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\, = ( A, ) ( F, ) ( 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). 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 uidance F for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). I t, = the duration of the gaseous radwaste release (seconds). ( I i I, i

Offsite Dose Calculation Manual Page 127 of 247 Revision 1, Change 0 c' = a conversion constant, IE6 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 cot.ective 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 Technical Specification limits for quarterly and yearly gamma air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.2 for actions to be taken in the event the calculated cumulative gamma air doses exceed 10 mrads per calendar quarter or 20 mrads per calendar year. I. Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents

1. Introduction a) Appendix I 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 1. c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The cumulative beta air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, sh Al be less than 20 mrads.in any calendar quarter, and shall be less than 40 mrads in .my calendar year (per Technical Specification 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 (Technical Specification 4.11.2.2).

I'

Offsite Dose Calculation Manual Page 128 of 247 Revision 1, Change 0 1 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 CCNPP Chemistry Section calculates the cumulative beta air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative beta air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days (Technical Specification 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-6(M). d) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each PURGE of a containment building (CP-604). s(- e) The cumulative beta air doses due to noble gases in gaseous effluents are calculated at least weekly'U' 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 burning of contaminated oil. g) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for . each ABNORMAL AND/OR UNANTICIPATED 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, cunent calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated in accordance with equation 21G.

The frequency is controlled by the inptementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Technical specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2). The criterie used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in cP 612 or CP 604

Offsite Dose Calculation Manual Pege 129 of 247 Revision 1, Change 0 1 CUMULATIVE BETA AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DUR.ING TIME INTERVAL, t D,g = [D g, Eq.21G Where, D, 3

the cumulative beta 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, g = the beta air dose (mrad) 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 D g, (the beta air dose at the SITE BOUNDARY due to noble gas radionuclides 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 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 effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 22G.

BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION) D, g

( 3.17E-8 ) ( x/Q ) [ [ ( N, ) ( Q';, ) ] Eq. 22G 111 Equation 22G has been derived from NURIG 0133, 5.3.1. i.

Offsite Dose Calculation Manual Page 130 of 247 Revision 1, Change 0 ('- i Where, D, g

                    =   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/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) uz 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 southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFS AR, 2.3.6.3).

                   =   the air dose factor due to beta emissions for each identified noble gas radionuclide, I (mradlyr per N,

microcurie / 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 Attachment 10 ( (Attachment 1 of old ODCM). Q}, = the total (time aveiaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries). At CCNPF, 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'i, ( A, ) ( F, ) ( 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). F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second). n2

g ,,,,,,,,33, 3,3 l

Offsite Dose Calculation Manual Page 131 of 247 Revision 1, Change 0 =f( If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the t ' 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). tg = the duration of the gaseous radwaste release (seconds). c' = a conversion constant, IE6 cubic centimeters per cubic meter. (3) In the event a computer system is unavailable, a simplified equation may be used to calculate 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 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 single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 230. ( BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) D, g

( ( 3.17E-8 ) ( x/Q ) ( N ) / K,,) [ Q( Eq.23G 113 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) All releases are considered "long-term" releases'", and as such, the highest historical annual l average dispersion factor, (x/Q), is used in the dose calculations. ! 1 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). l Equation 230 has been derived f rom NUREG 0133, 5.3.1. NUREG 0133, 3.3 1

Offsite Dose Calculation Manual Page 132 of 247 Revision 1, Change 0 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) (UFS AR, 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 Specification 3.11.2.2, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the beta air dose is always less than or equal to the beta air dose limit of Specification 3.11.2.2. A safety factor of 1.00 will yield an organ dose which corresponds to the beta air dose limit of Specification 3.11.2.2. A safety factor of 0.500 will yield an beta air dose which corresponds to one-half the beta air dose limit of Specification 3.11.2.2. It is recommended that a safety factor of 1.0 be used for calculating the beta air 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 Technical Specification 3.11.2.2 when simplifying assumptions are used. The

use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should.

in addition to complying with the limits set forth in this part [10 CFR 20], 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 23G to account for any potential nonconservatism associated with applying the empirically derived beta air dose factor, N to all radionuclides

                . identified in the gaseous release. Such nonconservatism could conceivaSfe, be present whenever radionuclides having a beta air dose factor greater than N, are present in a gaseous release.
            =

Q( 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 i IN GASEOUS RELEASE r (

Offsite Dose Calculation Manual Page 133 of 247 Revision 1 Change 0 Q',, = ( A i , ) ( F, ) ( ti , ) ( c' ) Eq.19G ( A, 3

the specine activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter)

           =  the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters F,

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, IE6 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.

7. Corrective Actions a) Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for quarterly and yearly beta air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.2 for actions to be taken in the event the calculated cumulative beta air doses exceed 20 mrads per calendar quaner or 40 mrads per calendar year. J. Cumulative Organ Doses Due To Iodines And Particulates In Gaseous Effluents

1. Introduction a) Appendix I to 10 CFR 50 speciGes 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 I. c) These radiological effluent controls are described below. ( l#

Offsite Dose Cciculation Manual Page 134 of 247 Revision 1, Change 0

2. Radiological Effluent Controls a) The cumula'.ive organ dose due to iodines and particulates in gaseous 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 Technical Specification 3.11.2.3).

b) The cumulative organ dose due to iodines 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 Technical Specification 3.11.2.3). c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirements a) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESiRICTED AREAS), for the current calendar month, the current calendar quarter, arid the current calendar year, shall be determined at least once every 60 days in accordan:e with the ODCM (per Technical Specification 4.11.2.3).

b) The plant group (s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organizaticns

(- a) The Chemistry Sectiori is responsible for implementing the surveillances required by Technical Specification 4.11.2.3. 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.

5. Initiating Conditions a) The cumulative organ dose-for each organ-shall be determined at least once per 60 days (Technical Specification 4.11.2.2).

b) The cumulative organ dose-for each organ-due to iodines and particulates in gaseous effluents shall be calculated at least weekly"5 for CONTINUOUS discharges from plant vent stacks (CP-612). c) The cumulative organ dose-for each organ-due to iodines and particulates in gaseous-effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil, the frequency is controlled by the irplementing procedare, CP 612, and is based on plant conditions. Under no corrJitions shalt the frequency be less then once per month (Te:hnical Specification 4.11.2.1.1 or 4.11.2.1.2, l Table 4.11 2). [ l l 1

Offsite Dose Calculation Manual Page 135 of 247 Revision 1, Change 0 '. 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 a) The cumulative organ doses (for the calendar month, calendar quarter, 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.

CUMULATIVE DOSE TO ORGAN, o, FROM ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t D, = [ D, Eq. 24G Where, D, = the cumulative dose (mrad) to organ, o, at the SITE BOUNDARY, due to iodine and particulate radionuclides contained in gaseous waste discharged from the site during the time interval, t O" = the dose (mrad) to organ, o, at the SITE BOUNDARY due to iodine 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 IP 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 the appropriate software are available. ( l

n. ,

Offsite Dose Calculation Manual Page 136 of 247 Revision 1, Change 0

 -ff;                            (2)      If a computer system and the appropriate software are available, the organ
  ,4 doses due to iodines and particulates contained in any single release of radioactive gases to UNRESTRICTED AREAS shall be calculated in accordance with equation 25G.

DOSE TO ORGAN, o, DUE TO IODINES AND PARTICULATES IN GAS RELEASE, r (RIGOROUS EQUATION) D,, = ( 3.17E-8 ) (, W ) [ ( R ,, ) ( Q ) Eq.25G n6 Where, D,, = the dose (mrem) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides l in gaseous 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. W ,

                =    the dispersion parameter for estimating the dose to an individual at the controlling location for long term releases, and may assume one of two values as described below                                        :

W ,is x/Q for the inhalation pathway (2.2E-6 sec/ cubic meter) l

                                                                                    -2 W ,is D/Q for the food and ground plane pathways (meters )

( -2 D/Q = the dispersion parameter at the controlling location for long term releases (meters ) l The value for D/Q has been determined to be 8.63E-10 m-2 u7 , l The grass-cow-milk pathway is the controlling pathway."8 l The controlling sector is the south-southwest sector."' l The controlling location is at a distance of 4800 meters.120 l R = the dose factor for each identified ioding or particulate radionuclide, i, exposure pathway, p, receptor age group, a, and organ, o (m mrem / year per microcuries/second or miem/ year per microcuries/ cubic meter) H6 Equation 2sG has been derived from WUREG 0133, 5.3.1. see cP-607, Revision 1, section 3.4.3. see the " Land Use Survey",1990. ] It should be noted that the controlling sector mentioned in the UFsAR, section 2.3.6.4, is inaccurate because the UFSAR has not been L4x$ated to include the results of the 1990 " Land use survey." See the " Land Use survey", 1990. [ 1 l

Offsite Dose Calculation Manual- Page 137 of 247 Revision 1, Change 0 ( 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 The inhalation pathway dose factors were obtained using the formula from NUREG-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. 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.

' Q'" the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r, discharged during the specified time interval (microcuries) \ l 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 10 DINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r

Q\, ( A, ) ( F, ) ( tg ) ( c' ) Eq.19G A" = the specific activity of iodine 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 Dow 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. > 1 Additional guidance for calculating discharge Dow rates may be contained in approved chemistry ; ( section procedures (e.g., CP-601 and CP-6(M). i

l 1

l

        ;Offsite Dose Calculation Manual                                                                     Page 138 of 247 Revision 1, Change 0
 ' _I    ty         =   the duration of the gaseous radwaste release (seconds) c'         =   a conversion constant, IE6 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. (4) The simplified method is presented below. 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)

   -(      D,,               =

[ ( 3.17E-8 ) ( W , ) ( R ,3y ) / K 3 sr ] (Q ) Eq.26G 121 D "*' = 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 number of seconds in a year.

                                                                                                              -2 DiQ        =   the dispersion parameter at the controlling location for long term releases (meters )

The value for D/Q has been determined to be 8.63E-10 m-2122 l The grass-cow-milk pathway is the controlling pathway.123 The controlling sector is the south-southwest sector.124

           ' Equation 26G has been derived f rom WUREG 0133, 5.3.1.

22 see CP 607, Revision 1, section 3.4.3. See the " Land Use Survey",1990. It should be noted that the controlling sector mentioned in the UFsAR, section 2.3.6.4, is inaccurate because - the UFSAR has not been updated to include the results of the 1990 " Land use Survey."

      ' Offsite Dose Calculation Manual                                                                        Page 139 of 247 Revision 1, Change 0                                                                                                         i i

i. The controlling location is at a distance of 4800 meters.125 kR i-u t

the infant, thyroid, dose factor for I-131 via the grass-cow-milk pathway (m 2 mrem / year per microcuries/second) This value is 1.05E12 and it is listed on 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 Specification 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 Specification 3.11.2.3. A safety factor of 1.00 will yield an organ dose which corresponds to the organ dose limit of Specification 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 Specification 3.11.2.3. 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 control is designed to minimize the possibility of violating Technical Specification 3.11.2.3 when simplifying

,                    assumptions are used.

( The

use of a safety factor is consistent with 10 CFR 20.l(c) which states that the licensees should,

                        . . in addition to complying with the limits set forth in this part [10 CFR 20], 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 26G to account for any potential nonconservatism associated with applying the infant, thyroid, grass-cow-milk dose factor, y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable e present whenever radionuclides having a pathway dose factor greater than R Lui are present in a gaseous release. l t Q3 = the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r (microcuries) l At CCNPP, all releases are considered long term releases. This value shall be calculated in accordince with equation 19G. TOTAL RELEASER (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS l l see the "Le M Use Survey", 1990. 1 1 I,.

   -.                _           -~           ._ _ _ _ . . . _ . _ _          _._ _ _ _           .._ _ _. _. ..             _   ,

Offsite Dose Calculation Manual Page 140 of 247 Revision 1, Change 0

Q\, ( A,, ) ( F, ) ( t,, ) ( c' ) Eq.19G A, = the specific activity of iodine 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).

           =   the duration of the gaseous radwaste release (seconds) t,,

c' = a conversion constant, IE6 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.

7. Corrective Actions a) Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for cumulative organ dose for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.3 for actions to be taken in the event the calculated cumulative gamma air doses exceed any of the radiological effluent controls listed above. K. Limits For The Gaseous Waste Processing System

1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the gaseo is 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. c) These radiological effluent controls are described below. ' I i r

                                                                     ,           _          . _ _                              ~_l.

Offsite Dose Calculation Manual Pcge 141 of 247 Revision 1, Change 0; _( 2. Radiological effluent controls I 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 efnuent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 1.20 mrads gamma radiation in a 92 day period (per Technical Specification 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 efauent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 2.4 mrads beta radiation in a 92 day period (per Technical Specification 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 Technical Specification 3.11,2.4). d) The routine surveillances which are performed to verify compliance with this radiological efauent controls are described below.

3. Surveillance Requirement (s) a) The cumulative gamma air dose, for the previous 92 days, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Technical

] Specification 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.

5. Initiating conditions a) For a listing of initiating conditions associated with calculating gamma air doses, see

                          " Initiating Conditions" in the section of the ODCM titled, " Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents."

(

l l

Offsite Dose Calculation Manual Page 142 of 247 Revision 1, Change 0 l- 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 Doses 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 Paniculates In Gaseous Effluents."

7. Corrective Actions a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification limits for 92-day cumulative ganuna, beta, or organ doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Technical Specification 3.11.2.4 for actions to be taken in the event the ( calculated 92-day cumulative gamma air, beta air, or organ doses exceed any of the radiological effluent controls listed above. L. Limits On Total Annual Dose - Gases, Liquids, and Uranium Fuel Cycle Sources

1. Introduction a) 40 CFR 190 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 effluent controls a) The total body dose from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Technical Specification 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 mrem for the current calendar year (per Technical Specification 3.11.4). I I

Offsite Dose Cciculation Manual Page 143 of 247 Revision 1, Change 0 c) The thyroid dose from exposure to the combination of liquid releases, gas releases, and ( uranium fuel cycle sources shall be less than 75 mrem for the current calendar year (per Technical Specification 3J11.4). ' 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 quaner, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days (Technical Specification 4.11.2.2). l b) 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 Technical Specification 4.11.2.3).

c) C.tmulative total body dose to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the calendar quarter, and the current calendar year-shall be calculated at least once per 60 days (per Technical Specification

4. I 1.1.2).

d) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the current calendar quaner, and the current calendar year-shall be calculated at least once per 60 days (per Technical Specification 4 11.1.2). ( 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 APPROPRIATE INITIATING CONDITIONS ARE PRESENT.

4. Responsible Plant Organization (s) l a) The Chemistry Section is responsible for implementing the effluent surveillances required by Technical Specification 4.11.4.1.

b) The Chemistry Unit, Technical Services Section, BG&E Fossil Energy Division, is responsible for implementing the surveillances for direct radiation required by i Technical Specification 4,11.4.2. c) IT SHOULD BE NOTED THAT NO SURVEILLANCES NEED BE PERFORMED j UNLESS THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT. d) These initiating conditions are contained in the following section. l

5. Initiating conditions a) The total dose from liquid releases, gas releases, and uranium fuel cyc!e sources shall be determined whenever the calculated doses from liquid effluents exceed any of the ;

following (per Technical Specification 4.11.4.2): ; ( (1) Six (6) mrem per quarter to the total body l i 1

Offsite Dose Calculation Manual ' Revision 1. Change 0 Page 144 of 247

 ;                            (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 calendar 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 emuents exceed any of the following (pc 'echnical Specification 4.11.4.2):

(1) Twenty (20) mrad gamma per quaner (2) Fony (40) mrad gamma per calendar year (3) Fony (40) mrad beta per quaner (4) Eighty (80) mrad beta per calendar year c) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated organ doses from iodines and paniculates in gaseous effluents exceed any of the following (per Technical Specification 4.11.4.2): (1) Thirty (30) miem 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 methodobgy 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.

TOTAL, TOTAL BODY DOSE FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Dg = Dg + D, + Dg Eq IT ; 1 TOTAL ORGAN DOSES FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE i SOURCES D, = Du + D, + D, Eq.2T i [ I

                                      . _                                                                             e

Offsits Dose Calculation Manual Revision 1, Change 0 Page 145 of 247

  . Dg        =

the dose (mrem) to total body resulting from the combination of all gas releases, all liquid releas and all uranium fuel cycle sources. { , D, = 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

6. GI tract Dg =

the cumulative dose (mrem) to organ, o, for all liquid releases discharged in a given time interval Calculate this value as specified by equation 8L. D = 0 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 I Calculate this value as specified by equation 17G, except substitute K, for M, (see Attachmen D, = the site-boundary cumulative organ dose (mrem) resulting from the release of iodine and particulate radionuclides in gaseous releases from the site Calculate this value as specified by equation 24G. Dg = the calendar-year cumulative dose (mrem) 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 o dose rate instruments placed near the SITE BOUNDARY (e.g., from radiological environmental monitoring sites DRI-DR9 described on Attachment 13 and shown on Attachment 18). The Environmental Programs Section, BG&E Corporate Affairs Group, and the Radiation Safety Section are responsible for 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

(

Offsite Dose Calculation Manual Page 146 of 247

     . Revision 1, Change 0 8-a)        Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference

.( administrative and/or Technical Specification limits for total dose for liquid releases, gaseous releases, and uranium fuel cycle sources and shall specify corrective actions to be initiated when these limits are exceeded. b1 Refer to Technical Specification 3.11.4 for actions to be taken in the event the total dose 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. [375B] M. Special Exceptions and Assumptions For Calculation of Doses and Dose Rates

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 MEMPERS OF THE PUBLIC. (2) Maximum occupancy for MEMBERS OF THE PUl.LIC at Camp Conoy is restricted to approximately 3380 hours rer ye.ar. c) Meteorology (1) The highest historical annual average x/Q for Camp Conoy is 2.40E-6 seconds per cubic meter.126 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.12r (2) No special consideratior, are required for addressing potential exposure at Camp Conoy.

2. Visitor's Center a) Location see eP 607, Revision 1, page 24

see CP 6e7, Revision 1, page 24 l.

Offsite Dose Calculation Manual Page 147 of 247 Revision 1, Change 0 (1) The Visitor's Center is located within the site boundary.

'('

_(2) The Visitor's Center is located in the WNW sector. (3) The Visitor's Center is approximately 1000 feet from the plant. b) Occupancy (1) The Visitor's Center is frequently visited by MEMBERS OF THE PUBLIC. (2) Maximum occupancy for MEMBERS OF THE PUBLIC at The Visitor's Center is restricted to daylight hours. c) Meteorology (1) The highest historical annual average x/Q for the Visitor's Center is 8.68E-6 seconds per cubic meter.128 (2) The wind frequency for the WNW sector, based on 1983 meteorological da:a, is four percent (4 7c).129 d) Dose calculation assumptions (1) *Using a conservative basis of 10% wind frequency, and individual visiting the , center for 330 hours / year during the periods of worst case meteorological conditions would be most highly exposed..no I (2) The dose calculated for the controlling site boundary is more conservative by a f actor of 7."' (3) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at The Visitor's Center will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the site boundary. (4) No special considerations are required for addressing potential exposure at The Visitor's Center. See CP 607, Revision 1, page 24. See CP 607, SevibiDS 1, page 24.

      " See CP 607, Revision 1, pese 24.

see eP-607 Revision 1, page 24 I

   . Offsite Dose Calculation Manual Revision 1, Change 0                                                                               Page 148 of 247 VII, RADIOLOGICAL ENTIRONMENTAL MONITORING PROGRAM A.        Radiological Emironmental Monitoring Program"2 l

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 resultani radiation doses to individuals.

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 Environmentai Monitoring Program (REMP) a) The REMP shall consist of environmental sample locations, analysis parameters, analysis frequencies, detection limits, and action levels all of which conform to the requirements of Technical Specification 3.12.1. (See Attachment 13,14,15,16, and 17). b) The REMP shall maintain a map showing sample locations near the site boundary in accordance with Technical Specification 3.12.1. (See Attachment 18). c) The REMP shall maintain a map showing sample locations within a 8 km. radius of the plant in accordance with Technical Specification 6.9.1.7. (See Atta:.hment 19).

3. Surveillance Requirements a) Surveillances for direct radiation '

(1) Direct radiation dosimetry shall be collected from locations DR1-DR23 listed on Attachment 13. (2) In the event any of the monitoring stations, DRI-DR23, described on Attachment 13 become unavailable, establish new monitoring stations (with new dosimetry) as described below: (a) In lieu of any location DRI-DR9 described on Attachment 13, establish a new monitoring station in the same metrological sector in the general area of the SITE BOUNDARY. (b) Inlieu of anylocation DR10-DR18 described on Attachment 13,

establish a new monitoring station in the same metrological sector in the 6-8 km range from the site. This portion of the enviroenental monitoring program is designed to monitor the environment surrowding the Ce@P. A separate envirorrnental monitoring program designed to monitor the envirorrnent surrowding the Independent spent Fuel storage Installation is described elsewhere in the CDcM.

i Offsite Dose Calculation Manual Page 149 of 247 - Revision 1, Change 0 i (c) l In lieu of any location DR19-DR23 described on Attachment 13, ' { establish a new monitoring station in either a special interest area (e.g., population center, nearby residence, school) or a control station whichever is applicable. (3) in the event any dosimetry at an existing monitoring location DRI-DR23 becomes unavailable, place new dosimetry at the monitoring station. l (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), 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 Technical Specification 3.12.2.b. b) Surveillances for airbome activity (1) Radiciodine and particulate samples shall be collected from locations Al-A5 listed on Attachment 13. (2) In the event any of the monitoring stations Al-AS, described on Attachment 13 become unavailable, establish new monitoring station (s) (fitted with new radiciodine and particulate samplers) as described below: (a) In lieu of any location Al-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 metrological 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 oflocation A5 described on Attachment 13 establish a new

                                               control location 15 to 30 kilometers from :he plant in the least prevalent wind direction.

(3) In the event any radiciodine cartridge or particulate filter becomes unavailable from an existing monitoring location Al-A5 described on Attachment 13, place new radiciodine cartridge or particulate filter in the air sampler at the monitoring station. (4) Analyze the samples at the frequencies and for the parameters identified on Attachment 15. (5) 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 i census was conducted in accordance with Technical Specification 3.12.2.b. _ ,_ (

Offsite Dose Calculation Manual'_ Page 150 of 247 Revision 1, Change 0 c) Surveillances of waterborne activity ( (1) Water and sediment samples shall be collected from the locations Wal, Wa2, l and Wbl listed on Attachment 13. (2) In the event any of the samples at Wal, Wa2, or Wbl are unavailable, collect substitute samples as described below: (a) In lieu of a liquid sample at Wal, 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 Wbl, 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 Technical Specification 3.12.2.b. d) Surveillances for ingestible activity (1) Fish /invenerbrate, milk, and food product samples shall be collected from the locations ial thru la6 and Ib1 thru Ib9 listed on Attachment 13. (2) In the event any of the samples at lal thru la6 or Ibl thru Ib9 are unavailable, collect substitute samples as described below: (a) In lieu of samples at Ial thru la3,' collect substitute three commercially and/or recreationally imponant species (two fish species and one invenebrate species) from the vicinity of the plant discharge area. (b) In lieu of samples at la4 thru la6, collect three commercially and/or recreationally imponant species (two fish species and one invenebrate species) from an area not influenced by plant discharges. (c) In lieu of samples at Ibl thru Ib6, collect three kinds of broad leaf vegetatiod grown near the SITE BOUNDARY at two different locations of highest average ground level D/Q'33. (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. With fresh leafy vegetable so ptes (nevallable from one or more of the sanple locations listed on Attschment 13, perform corrective a:tions specified by Technical specification 3.12.1.c. f I

Offsire Dose Calculation Manual Pcge 151 of 247 Revision 1, Change 0 g\ (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), 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 Technical Specification 3.12.2.b.

4. Responsible Company Organizations a) The Technical Services Section, BG&E Fossil Energy Division is responsible for-performing 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 reveal levels of environmental activity ( greater than the Action Levels specified on Attachments 15,16,17 (per l Technical Specification 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 plant effluents. d) The Environmental Programs Section, BG&E Corporate Affairs Group, is responsible for notifying the General Supervisor-Chemistry, CCNPP, if any of the following conditions are true: (1) any of the above surveiMance results reveal levels of environmental activity greater than the Action Levels specified on Attachments 15,1617 (per Technical Specification 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 plant ef0uents, and the potential annual doses due to the radionuclides are greater than the calendar year limits of Specifications 3.11.1.2, 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 methodologies contained in ODCM, or i

i i

*i

Offsite Dose Calculation Manual Page 152 of 247 Revision 1 Change 0 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 Technical Specification 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 Technical Specification 4.12.1, Table 3.12-1, notation "a").

b) If the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is not being conducted in accordance with Attachments 13,14,15,16, or 17 document l deviations in the AREOR (per Technical Specification 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 Technical Specification 312.1.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 rhical Specification 3.12.1.b). e) When radionuclides other than those listed on Attachments 15,16, and 17 are detected; and if those radionuclides are the result of plant effluents; and if the potential annual doses due to the radionuclides are greater than the calendar year limits of Specifications 3.11.1.2,3.11.2.2, and 3.11.2.3; submit a Special Report in accordance with Technical Specification 3.12.1.b. B. Land Use Census

1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.3 requires licensees to identify changes in the use of UNRESTRICTED AREAS in order to permit modifications in monitoring programs.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1, Section IV.B.3. c) These radiclogical environmental controls are described below.

2. Controls on the Land Use Census a) Identify the location of the nearest milk ammal, within a distance of 8 km of the plant site, in each of the 9 metrological sectors (per Technical Specification 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 metrological sectors (per Technical Specification 3.12.2). 9 1

Offsite Dose Calculation Manual Page 153 of 247 Revision 1. Change 0 c) Identify the location of the nearest garden, within a distance of 8 km of the plant site, in - 1(. each of the 9 metrological sectors; or if the garden census was not conducted, obtain samples of three different kinds of broad leaf vegetation from the SITE BOUNDARY in two different metrological sectors which have the highest predicted SITE BOUNDARY D/Q (per Technical Specification 3.12.2).

3. Surveillance Requirement (s) a) Perform 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 Specification 6.9.1.7.

4. Responsible Company Organizations a) The Environmental Programs Section, BG&E Corporate Affairs Group, is responsible for performing the surveillances listed above.

Initiating conditions ( a) Conduct the land use census during the growing season, and conduct the land use census at least once per 12 months.

6. Calculation methodology a) Calculate doses for the pathways of interest in accordance with the methodologies contained m Regulatory Guide 1.109, or 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.

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.

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 Specification 4.11.2.3, perform the following activities. (1) Document the new location (s) in the next Annual Radiological Environmental Operating Report in accordance with Specification 6.9.1.7, and ( (2) revise the figures and tables in the ODCM to reflect the new location (s). l

'o

Offsite Dose Calculation Manual Page 154 of 247 Revision 1, Change 0. Q c) If the land use census has identified a location (s) that yields a calculated dose or dose V 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 Specification 6.9.1.7, and (3) revise the figures and tables in the ODCM to reDect the new location (s). > C. 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 quantities of radioactive material released in effluents 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 material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. I c) These radiological environmental controls are described below.

2. Controls on the Interlaboratory Comparison Program a) Analyze INTERLABORATORY COMPAPJSON PROGRAM samples supplied by either the Commission or a Conunission approved laboratory for all parameters listed on Attachments 15,16, and/or 17, as applicable * (per Technical Speci0 cation 3.12.3).

3. Surveillance Requirement (s) a) A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

b) This section of the ODCM shall describe the Interlaboratory Comparison Program.

4. Responsible Company Organizations a) The Chemistry Unit, Technical Services Section, BG&E Fossil Energy Division, is responsible for performing the surveillances listed above.

The EPA say sumly the INTERLABORATo8Y CoMPARisch PRocRAM sanples, since no Corrrnission a; proved laboratory supplies TLDs as part of a conparison program, no TLDs are analyzed as part of the INTERLABORAToRY e0MPAR!$oN [ PRDcRAM. g

   . Offsite Dose Calculation Manual Revision 1, Change 0                                                                              Page 155 of 247.-      '

5. Initiating conditions

(.- a) Analyze INTERLABORATORY COMPARISON PROGRAM samples whenever they are supplied by either the Commission or a Commission approved laboratory.

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 Repon (AREOR) pursuant to Specification 6.9.1.7.

I. Annual Radiological Emironmental 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.

2. Controls on the Annual Radiological Environmental Operating Repon (AREOR) a) The AREOR shall include a summary description of the radiological environmental monitoring program (REMP).

l b) The A.REOR shallinclude a summary description of the Independent Spent Fuel Storage Installation Monitoring Program (ISFSIMF). c) The AREOR shall include a table similar to Attachment 13 which states the d direction from the central point between the two containment buildings to each of the REMP sample points. l d) The AREOR shall include 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 shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the repon period, f) The AREOR shall include a comparison between the annual REMP results and the Radiological Environmental Operating Repon preoperational studies. g) The AREOR shall include a comparison between the annual ISFSIMP results and Radiological Environmental Operating Report pre-fuel-load studies. ( h) The AREOR shall include a comparison with operational controls as appropriate. f.

        - Offsite Dosa Calculation Manual                                                               Page 156 of 247 Revision I, Change 0

f. i) The AREOR shall include a comparison with the previous environmental surveillance

(. reports. j) The AREOR shall include an assessment of the observed impacts of plant operation on the environment. k) The AREOR shall include an assessment of the observed impacts ofISFSI operation on the environment.

1) The AREOR shall include the results of the land use censuses required by Specification 3.12.2.

m) The AREOR shall include the results of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20. n) The AREOR shall include the results of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20. l o) The AREOR shall include summarized and tabulated results-in the format of the table-in the Radiological Assessment Branch Technical Position, Revision 1, November 1979-of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20. l p) The AREOR shall include summarized and tabulated results-in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November

 .I'                              1979-of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20.                                        l q)       The AREOR shall include 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 shall include any data which was missing from previous reports. us s) The AREOR shall include at least two legible maps covering all REMP sampling l locations keyed to a table giving distances and directions from the central point between the two containment buildings. t) The AREOR shall include at least one legible map covering all ISFSIMP sampling locations keyed to a table giving distances and directions from the central point of the ISFSI. u) The AREOR shall include,results of the licensee participation in the INTERLABORATORY COMPARISON PROGRAM required by Specification 3.12.3. ; v) The AREOR shall include 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. I one map shall cover stations near the SITE BOUCARY; e se:ond shall include the enore distent stations.

Offsite Dose Calculation Manual Page 157 of 247 Revision 1, Change 0 w) The AREOR shall include a discussion of all analyses in which the LLD listed on f i(- ' Attachments 15,16, and 17 (and required by Technical Specification Table 4.12-1) was not achievable. x) The AREOR shall include the identification of the cause of unavailability of samples (if any), and describe the k> cations used for replacement samples. y) The AREOR shall include any permanent changes in the sample locations in the monitoring program. z) The AREOR shall include revised figure (s) (e.g., like Attachments 18 and 19) and tables (e.g., like Attachment 13) for the ODCM which reflect any new PIMP sample l location (s). aa) The AREOR shall include revised figure (s) (e.g., like Attachments 21 and 22) and table (s) (e.g., like Attachment 20) for the ODCM which reflect any new ISFSIMP sample location (s).

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 Environmental Programs Section, BG&E Corporate Affairs Group, is responsible

( for performing the surveillances listed above*.

5. Initiating conditions a) Submit the Routine AREOR (covering operation of the reactor units for the previous calendar year) by May 1 of each year.

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 l reoccurrence in the AREOR pursuant to Specification 6.9.1.7. !

                                                              '                                                                 l E.       Independent Spent Fuel Storage Installation Monitoring Program                                               l. l

1. Introduction l

l

A separate conpany may be contra:ted to corptete the Routine ARIOR.

Offsite Dose Calculation Manual Page 158 of 247 Revision 1, Change 0 a) The Technical Specifications for the Independent Spent Fuel Storage Installation'37

 .(                               (ISFSI), licensed under 10 CFR 72, require that monitoring for the ISFS! be added to the existing environmental monitoring program for CCNPP.

b) BG&E has committed to additional monitoring for the ISFSI.138 l c) Radiological environmental controls have been established to implement the requirements and commitments described above. d) These radiological environmental controls are described below. l

2. Controls on the ISFSI Monitoring Program l a) Environmental monitoring sites, as described in Attachment 20, shall be established to monitor the air, vegetation, and soil as well as direct radiation in the ISFSI environs,'3' b) Analysis parameters, analysis frequencies, detection limits, and action levels shall conform to the applicable requirements of CCNPP Technical Specifications 3.12.1.

(See attachment 14,15,16, and 17) c) Map (s) shall be maintained and shall show the locations of the environmental monitoring sites with respect to plant faci'ities. (See attachment 21 and 22).

3. Surveillance Requirements l a) Surveillances for direct radiation l

(- (1) Direct radiation dosimetry shall be collected from locations SFDRI-SFDR16, DR7, and DR30 listed in Attachment 20. (2) In the event any dosimetry at an existing monitoring location SFDRl-SFDR16, DR7, or DR30 becomes unavailable, place new dosimetry at the monitoring station. (3) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14. . b) Surveillances for airborne particulate activity l (1) Air particulate samples shall be collected from locations Al and SFAl-SFA4 listed on Attachment 20. The Technical specifications For Calvert Clif fs Independent $ pent fuel storage Instellation is Appendix "A" to Materials License shM 2505. See the letter titled

Response to WRC's Coments to Environnentet Issues Regarding Be&E's License Application for Calvert Cliffs Irderendent Spent Fuel Storage Installation tlSFSI)" from Mr. R. E. Denton (Sc1E) to Director, of fice of Wuclear Material safety ard safeguards (kRc), dated Novenber 1,1990.

Environmental sonitoring sites and monitoring parameters specificet ty excluded from the ISFSIMP incti.de airborne radiciodines, radiciodines in food products, surf ace water, and fish and invertebrates. Additionally, soll saep!es shall be collected in lieu of shoreline sediment. The sampling frequency for vegetation and soit shall be cuarterly. I, L

Offsite Dose Calculation Manual Page 159 of 247 Revision 1, Change 0 (2) In the event any particulate filter becomes unavailable from an existing { monitoring location Al or SFAl-SFA4 described on Attachment 20, place a i new paniculate filter in the air sampler at the monitoring station.

(3) Analyze the samples at the frequencies and for the parameters identified under

                                           " Particulate Filters" on Attachment 15.

c) Surveillances for deposition on vegetation l' (1) The vegetation samples SFbl SFb5 shall be collected from the locations listed on Attachment 20. (2) In the event any of the sampling sites SFbl-SFb5 described on Attachment 20 become unavailable, establish new sampling sites as described below: (a) In lieu of sample SFbl, collect vegetation grown in the NW sector of the ISFSt. (b) In lieu of sample SFb2, collect vegetation grown in the general vicinity of the CCNPP Visitor's Center. (c) In lieu of sample SFb3, collect vegetation grown in the North North West sector of the ISFSI. (d) In lieu of sample SFb4, collect vegetation grown in the South sector of the ISFSI. (c) In lieu of sample SFb$, collect vegetation grown in the Southeast sector of the ISFSI. (3) Analyze the samples quarterly for the non-iodine parameters identified under

                                          ' Food Products' on Attachment 17.

d) Surveillances for soil activity l (1) The soil samples SFSI-SFS5 shall be collected from the locations listed on Attachment 20. (2) In the event any of the sampling sites SFSI.SFS5 described on Attachment 20 become unavailable, establish new sampling sites as described below: (a) In lieu of sample SFS1, collect soil in the NW sector of the ISFSI. l (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 soil in the North North West sector of the ISFSI. (d) In lieu of sample SFS4, collect soil in the South sector of the ISFSt. l (e) In lieu of sample SFSS, collect soil in the Southeast sector of the ISFSI. l C

Offsite Dose Calculation Manual Page 160 of 247 Revision 1, Change 0 (3) Analyz: the samples quanerly for the parameters identified under

Shoreline Sediment Sample" on Attachment 16.

4. Responsible Company Organizations l

a) The Technical Services Section, BG&E Fossil Energy Division, is responsible for performing the surveillances listed above.

5. Initiating conditions l

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 Technical Specification 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 Specification 3.12.1.b. d) The Environmental Programs Section, BG&E Corporate Affairs Group, is responsible for notifying the General Supervisor-Chemistry, CCNPP, if any of the following conditions are true: (1) any of the above surveillance results reveal levels of environmental activity greater than the Action Levels specified on Attachments 14,15,16, and 17, as appropriate (per Technical Specification 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 Specification 3.12.1.b.

6. Calculation methodology l

a) If any (of the above) surveillance results reveal levels of environmental activity greater than the Action Levels specified on Attachments 14,15,16, or 17 (per Technical Specification Table 3.12-2), calculate potential annual doses 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 ! Technical Specification 3.12.1.b. i (' I l I 1

1 Offsite Dose Calculation Manual Page 161 of 247 Revision 1, Ctange 0

1. Corrective Actions l

'( 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 Attachme- 15,16, or 17, as appropriate, submit a Special Report to the NRC (per Technica' ecification 3.12.1.b). 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 Technical Specification 3.12.1.b. ( l l (

Offsite Dose Calculation Manual Page 162 of 247 Revision 1, Change 0 VIII. ADMINISTRATION OF THE ODCM I A. Introduction 1. Technical Specification 6.8.1 requires written procedures covering the ODCM and the implementation of the ODCM.

2. Administrative controls have been established to implement the requirements of Technical Specification 6.8.1.

3. These administrative controls are described below.

B. Controls On The ODCM 1. The format, organization, content, and admmistration of the ODCM are controlled by CCI-413. 2. Methodologies identified in the ODCM are implemented by various BG&E organizations in accordance with approved procedures. (See the " RESPONSIBILITIES" section of CCI-413 for a list of those Sections of BG&E 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. C. Surveillance Requirements { l. Complete audits and PERIODIC REVIEWS of the ODCM in accordance with CCI-413.

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 (i 25 %).

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, s D. Responsible Company Organizations

1. CCI-413 identifies the responsibilities of various personnel and company 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 I above.

l

" - ca = xa :.. . a. -- - - : . Offsite Dose Calculation Manual Page 163 of 247 i Revision 1, Change 0

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 l vent flow rate test results (e.g., TE-001 or equivalent results) and for performing the technical evaluation described in the above surveillances.

E. Initiating Conditions

1. Main vent stack flow rates shall be determined at least once per 6 months (125%), or more often if required by Technical Specifications.

2. Complete PERIODIC REVIEWS of the ODCM as specified in CCI-413.

F. 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) Supponing documents may be maintained in a " procedure history file". ( (3) Supponing documents may be identified in the " references

section of the ODCM.

G. Correctise Actions

1. IF main vent stack flow rates, as determined in accordance with appropriate Test Equipment procedure (s), change i 10W from the values referenced in Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised.

H. Bases

1. [B527], NRC Inspection Repon INSR 91-30/30 I. Emutive Summary Of Changes

1. Revision 0, Change 0: Initial Issue of ODCM under control of CCI-413. l

2. Revision 0, Change 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 l

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.*

Offsite Dose Calculation Manual Revision 1 Change 0 Page 164 of 247 3. Revision 1. Change 0: This revision adds the Radiological Environmental Monitoring Program '(J for the ISFSI to 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.1-247). (2) Changed title from RETS Coordinator to RETS Program Manager (pp. 1, 70, 75, 82, 87, 163). (3) lacluded 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, 136, 138, 143, 151, 152, 168, 181, 225, 236). (5) Updated references to reDect new revision numbers for safety evaluations, and added another safety evaluation (pp. 10, 11, 55). (6) Clarined requirements for minimum number of circulating water pumps for liquid releases (pp. 18, 29, 39). (7) Included reference to Technical Specification 3.3.3.10 (pp.18,29,39). (B) 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 serpoints should be changed pp. 21,31,41,71, 85, and 96). (1I) Changed reference from release permit, OI 17C, or OI-17D to Alarm Manual (pp 73, 86, 97), and deleted inappropriate reference to Alarm Manual (pp. 32,33,42,43). (12) Stipulated that the adjustment of 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, $2,54,55,56). (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 name of serpoints (pp. 67-73). (19) Deleted reference to 2 MPC limit (p. 67). (20) Updated ODCM to correspond to recent change to CCNPP Alarm Manual I (p. 71). (21) Editorial changes (pp. 72,150,236,233). (22) Removed provision for not changing 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-PJ-2191 when discharging containment vents and purges (p. 98). (25) Specified units for dose rate (pp.101) (26) Specified calculation constant for calculating mstantaneous 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 monitoring 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). l a i l

Offsite Dose. Calculation Kinual Pcge 165 of 247 Revision-1, 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: Plant Data Book, Calvert Cliffs Nuclear Power Plant Units 1 and 2, Bechtel Power Corporation, Job 6750, March 1975, Volume 1, Section 27, Drawing C-17 ( The above referenced grading and drainage plan is intended for reference only. This drawing may not reflect the changes and modifications since March 1975.

                                                                                                                 .t 165

                                                                                                                                                         .m O .3 te Dose Calculation Manual Revision I, Change O                                                                                                                                  Page io6 of 247 ATTACilMENT 2 (Page i of 3)

OUTFAtl.001 - SOURCES OF LIQUID RADIOACTIVE WASTE Waste Radiation Type of Max. Discharge Stream Monitor Maximum Volume Notes release Flow Rate gal / min liters / min gal liters Rx. Coolant Wst. Mon. Tk. 0-RE-2201 Batch 120 454 90000'6 3.407E5 i6 Rx. Coolant Wst. Rec. Tk. 0-RE-2201 Batch 120 454 i 90000 s 3.407ES'8 Misc. Wst. Mon. Tk. 0-RE-2201 Batch 120 454 4000 16 15140 16 Misc. Wst. Rec. Tk. 0-RE-2201 Batch 120 454 4000'6 15140'6 Aux. Boiler Steam Drum All releases are via Auxiliary B;owdown Tank Aux. Blowdown Tk. Unmonitored Continuous 200 15 757 N/A N/A Waste Neut. Tk. I1 Unmonitored Batch 1000' 3790' 45988 1.74E5 Waste Neut. Tk,12 Unmonitored Batch 1000' 3790' 47749 1.80E5 Stm. Gen. Blowdown Tk. 1/2-RE-4014" Batch" 225 2 852 2 2350' 8895 3 Component Cooling Water # Unmonitored Continuous variable' variable s 440906 1.669ES Condenser liotwells Unmonitored Batch'3 4500 7 17000 7 1.05E5 3.97ES Salt Water System Unmonitored Continuous 15500 58670 N/A N/A Condensate Storage Tank" Unmonitored Batch variable' variable' 3.5ES l.3E6'O Demin. Water Storage Tank" Unmonitored Batch variable' variable' 3.5E5' l.3E6'O 12 Precoat Sump Unmonitored Continuous 50 94.6 10305 39004

t>ltsite Dose Calculation Manual Revision I, Change 0 Page 167 of 247 ATTACilMENT 2 (Page 2 of 3) OUTFALL 001 - SOURCES 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 actual 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 and duration of the release. 4. There is no direct path by which radioactive liquid from the CCW System could enter outfall 001. Liquid from the CCW System may leak into either the Salt Water System (which drains to outfall 001) or the Liquid Waste Processing System (via Aux. Bldg. Drains). 5. Radioactive liquid is not normally released from the CCW system. Flow rate to outfall 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. 4 81 Radioactive liquid is not normally released from the CST. The CST would drain to outfall 001 only if catastrophic tank failure occurred. Small leaks would be collected by storm drains which would be released to outfall 002.

9. Flow rate should be calculated on a case-by-case basis.

10. Volume obtained from

Plant Data Book", BG&E CCNPP Units I 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 drains which would be released to outfall 002.

12. If the precoat sump contents were contaminated, releases would probably be directed to outfall 001, however 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.

 . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ _ _ . _ - . _ _ _ _ _ _ _ _ _ _ . _ _ - - _ - ___                                              a    --*n a

q

    ... ate Doae Calculation Manual Revision 1. Change 0 -                                                                                                                                                Page 168 of 247 1
                                                                                                                                                                                               ~t ATTACl! MENT 2 (Page 3 of 3)

OUTFAll,001 - SOURCES OF LIQUID RADIOACTIVE WASTE 14. Althoughprior conducted steam generator to discharge. releases are normally batch releases, discharges may at times be continuous. Verify type o l 15.

            ' setpoint This isshould the maximum be specifiedrated for thedischarge release. for two pumps in operation. If lees than two pumps will be operable for the release'

16. 'i The volume specified is the design basis volume from Table 11-1 of the UFSAR.

j 17. The steam generator blowdown efiluent radiation monitor,1/2-RE-4095, may be equivalent to the 1/2-RE-40lc (see si; f m _ _m__ __________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _

m- t

                                 , ate Dose Calculation Manual                                                                                                         ,

Mevision 1 Change 0 Page 69 of 247 l. ATTACilMENT 3 (Page 1 of 2) OUTFALLS 002,003, OM - POTENTIAL SOURCES OF LIQUID RADIOACTIVE WASTE Waste Radiation Type of Siream Max. Discharge Maximum Volume Outfall Monitor Release Flow Rate

gal / min liters / min gal liters Turbine Bldg. Sump No.11 Unmonitored Continuous 470 889 1950 7381 002 !

Turbine Bldg. Sump No.12 Unmonitored Continuous 470 889 2415 9141 002 Turbine Bldg. Sump No. 2P Unmonitored Continuous 470 889 2490 9425 002 ! Turbine Bldg. Sump No. 22 Unmonitored Continuous 470 889 2182 8259 002 Precoat Sump Unmonitored Continuous r 50 94.6 10305 390M 002 j Diesel Oil Interceptor Sump Unmonitored Continuous 100 378.5 5790 21920 004 Yahl Oil Interceptor Unmonitored Continuous variable3 variable 3 N/A N/A 002 . Refueling Water Tank Unmonitored Batch / Cont.' variable 3 variable 3 4.2E5 1.6E6 any' Condensate Storaru Tank Unmonitored Batch / Cont.' variable 3 variable 3 3.5E56 6 1.3E6 0022 4 Service Water System 1/2-RE-1595 Continuous variable3 variable3 31418 1.189ES 002 P Demin. Water Storage Tank Unmonitored Batch / Cont.' variable 3 3 6 variable 3.5E5 1.3E6' 002 2 Plant Heating System Unmonitored Continuous variable3 variable 3 N/A N/A 002 8 _ . _ _ _ _ _ _ _ _ _ ___._____m_ _ . _ _ _

n -

n. .

s..v;te Dose Calculation Manual Revision 1, Change O Page i70 of 247 - ATTACllMENT 3 (Page 2 of 2) OUTFALLS 002,003,004 - POTENTIAL SOURCES OF LIQUID RADIOACTIVE WASTE 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 normally discharged to the environment, however in the event of a small le failure, the tank contents could be released to the designated outfall(s). 3. Maximum discharge flow rate shall 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 I 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 even release may be considered a continuous release. The release mode should be determination on a case-by-case basis. 8. The plant heating system is a closed system and is not normally released t'o the environment. In the event released to the environment via the turbine building sumps (outfall 002). In some cases, depending on the location of the le effluent would be collected in the auxiliary building sump and subsequently released through the liquid radioactiv system. The efiluent pathway should be determined on a case-by-case basis. 9. The failure,contents of these the tank contents tanks could are nottonormally be released discharged outfali 002,003, or 004.. to the environment, however in the event of a small leak o

                                                                                     . ite Dese Calculation Manual Revision I, Change 0                                                                               A TACHMENT 4                                                                                                I4 17IOI247 Bi OCK DIAGRAM OF l10(30 RADIOACTIVE WASTE SYSTEMS Reacter Coolant Was te                                                                         Miscellaneous klaste (htt {                  (b(t j                tkit 2             t.bi t 2                    lbt e 1                  (>>11 2              Auw. OldQ       Lm nh CYCS                    *C &mn                8C D en           CvC9                         S/G                      S/G Letrirywn               Two                   Tw4 D sins          1 L *<a*wu t ats=n                      Flow &*n                 Bieswrywun           Ibs t t&2       (Y nins il                   ii                    1'                  Il l'

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Evamratw ._,,_<r , , , , _*r Pre-ret ter to a ^ l' Evaporefors G _ ib tc Acid N CJM Stwmp Tmes til To Sottd W wte Processig r p ' System L L

                                                                                             #C V M                                   PC WeCo Ion Ewchwgars G                                     tm n mtD    e TirNnn Bldg.

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Offsite Dose Calculation Manual Pege 172 of 247 Revision 1, Change 0 ATTACHNIEST 5 (.- DOhilNAST AND LESS DOME MT RADIONUCLIDES IN TYPICAL RADWASTE DISCHARGES The term f,- a fraction which represents the relat:ve activity contribution of nuclide i to the average total effluent activity - 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 defmition of TYPICAL RADWASTE RELEASE).

2. For each of the calendar quarters selected above, obtain a listing of the nuclides nucFde activities, and release (end) dates.

a. This data may be obtained from the Semi-Annual Radioactive Ef0uent Release Report (s) for the time periods of interest, or

b. this data may be obtained from a computer-based ef0uent management system (if available). l

c. The values of nuclide activities and release end times may be close approximations of the true values.

3. Sum the quanerly activities (curies) for each individual radionuclide.

Ag = [ A,9 Eq 1R < 4. Sum the quanerly activities for all radionuclides, i. AT

An Eq.2R

5. Calculate the fraction of the total activity attributable to each radionuclide (i.e., the relative activity of nuclide i).

f, = Ag/A7 Eq.3R 6.. Characterize each radionuclide as either dominant" or "less dominant" as shown below: The radionuclide is defined as a DOMINANT RArlONUCLIDE if the following inequality is true. f, 2. 0.01 0 Eq.4R The radionuclide is defined as a LESS DOMINANT RADIONUCLIDE if the following inequality is true. f, < 0.010 Eq. SR ( l I

     -                 .     -         - ~ .          - . .       - . -         . . --. .                             -

l Offsite D0se Calculation Manual Page 173 of 247 1 Revision 1, Clange 0 l ATTACHMENT 6 ; LIQUID EFFLUENT DOSE FACTORS (mrem /hr per uCi/ml) Nuclide Bene Liver 7 body Thyroid Kidney Lung Gitract H-3 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+01 1.300E+00 1.600E+C1 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 . 5 7 0E- 01 4 . 5 7 0E- 01 4 . 5 7 0E- 01 4 . 57 0E- 01 4. 57 0E- 01 4. 5 70E- 01 4. 5 7 0E- 01 P-32 4.690E+06 2.910E+05 1.810E+05 0.000E+00 0.000E+00 0.000E+00 5.270E+05 CR-51

0. 000E+ 00 0. 000E+ 00 5.580E+ 00 3.34 0E+ 00 1.23 0E+00 7.4 00E+ 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 3.150E+01 0.000E+00 2.260E+02 0.000E+00 5,670E+03

       .FE-55       5.110E+04 3.530E+04 8.230E+03 0.000E+00 0.000E+00 1.970E+04 2.030E+04 FE-59 8.060E+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 CO-58 0.000E+00 6.030E+02 1.350E+03 0.000E+00 0.000E+00 0.000E+00 1.220E+04 CO-60

0. 000E+ 00 1. 73 0E4 03 3. 82 0E+03 0. 000E+00 0. 000E+ 00 0.000E+00 3.250E+04 NI-63 4.960E+04 3.440E+03 1.670E+03 0.000E+00 0.000E+00 0.000E+00 7.180E+02 NI-65 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 2.140E+02 1.010E+02 0.000E+00 5.400E+02 0.000E+00 1.830E+04 ZN-65 1.610E+05 5.130E+05 2.320E+05 0.000E+00 3.430E+05 0.000E+00 3.230E+05 EN-69 3.430E+02 6.560E+02 4.560E+01 0.000E+00 4.260E402 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-83 0.000E+00 0.000E+00 7.250E-02 0.000E+00 0.000E+00 0.000E+00 1.040E-01 BR-84 0.000E+00 0.000E400 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 0.000E+00 0.000E+00 0.000E+00 RB-86 0. 000E+ 00 6.24 0E+ 02 2. 910E+ 02 0.000E+00 0.000E+ 00 0. 000E+00 1.23 0E+ 02 RB-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 B.340E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.990E+03 0.000E+00 1.430E+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+01 f SR-91 9.180E+01 0. 000E+ 00 3. 710E4 00 0. 000E+00 0. 050E+r 0 0. 000E+ 00 4.370E+02 SR-92 3.480E+01 0.000E+00 1.510E+00 0.000E+00 0.000E+00 0.000E+00 6.900E+02 a

Offsite D0se Calculation Manual Page 174 of 247 Revisica 1, Change O ATTACHMENT 6 i LIQUID EFFLUENT DOSE FACTORS (mrem /hr per uCi/ml) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract Y-90 6.060E400 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 8. 8 8 0E+ 01 0. 000E+ 00 2. 3 70E+ 0 0 0. 000E+ 00 0. 000E+ 00 0. 000E+ 00 4. 8 90E+04 Y-92 5.320E-01 0.000E+00 1.560E-02 0.000E+00 0.000E+00 0.000E+00 9.320E+03 Y-93 1.690E+00 0.000E+00 4.660E-02 0.000E+00 0.000E+00 0.000E+00 5.350E+04 "R-95 1.590E+01 5.110E+00 3.460E+00 0.000E+00 8.020E+00 0.000E+00 1.620E+04 ZR-97 8.810E-01 1.780E-01 8.130E-02 0.000E+00 2.680E-01 0.000E+00 5.510E+04 NB-95 4.470E+02 2.490E+02 1.340E+02 0.000E+00 2.460E+02 0.000E+00 1.510E+06 NB-97 3.750E+00 9.490E-01 3.460E-01 0.000E+00 1.110E+00 0.000E+00 3.500E+03 MO-99 0.000E+00 1.280E+02 2.430E+01 0.000E+00 2.890E+02 0.000E+00 2.960E+02 ( TC-99M 1.300E-02 3.660E-02 4.660E-01 0.000E+00 5.560E-01 1.790E-02 2.170E+01 TC-101 1.330E-02 1.920E-02 1.880E-01 0.000E+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 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+00 0.000E+00 CD-109 2.100E+05 4.000E+06 1.600E+06 1.500E+05 2.200E+07 1.000E+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.?30E+04 6.200E+02 1.600E+03 7.300E+01 2.200E+05 SB-124 2.770E+02 5.230E+00 1.100E+02 6.710E-01 0.D00E+00 2.150E+02 7.060E+03 SB-125 1.770E+02 1.960E+00 4.210E+bl 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 0.820E+02 0.000E+00 8.660E+02 TE-12 7M 5.4 8 0E+ 02 1. 96 0E+ 02 6. 6 8 0E+ 01 1.4 00E+ 02 2. 2 3 0E+03 0. 000E+ 0 0 1. 64 0E+ 03 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. 4 70E+ 02 1. 4 70E+ 02 3.2 00E+02 3. 89 0E+03 0. 000E+ 00 4. 6 90E+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 1.400E+02 6.850E+01 5.710E+01 1.000E+02 6.940E+02 0.000E+00 6.800E+03 TE-131 1.590E+00 6.660E-01 5.030E-01 1.310E+00 6.990E+00 0.000E+00 2.260E-01 _ ._. I

_ _ ~ Offsite D0se Calculation Manual Page 175 of 247

  ' Revision 1, Change O ATTACHMENT 6                                                  '

b { LIQUID EFFLUENT DOSE FACTORS (mrem /hr per uCi/ml) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract TE-132 2.040E+02 1.320E+02 1.240E+02 1.460E402 1.270E+03 0.000E+00 6.240E+03 7-130 3.960E+01 1.170E+02 4.610E+01 9.910E+03 1.820E+02 0.000E+00 1.010E+02 1 I-131 2.180E+02 3.120E+02 1.790E+02 1.C20E+05 5.350E+02 0.000E+00 8.230E+01 I-132 1.060E+01 2.850E+01 9.960E+00 9.960E+02 4.540E+01 0.000E+00 5.350E+00 2-133 7.450E+01 1.300E+02 3.950E+01 1.900E+04 2.260E+02 0.000E+00 1.160E+02 I-13. 5.560E+00 1.510E+01 5.400E+00 2.620E+02 2.400E+01 0.000E+00 1.320E-02 I-135 2.320E+01 6.000E+01 2.240E+01 4.010E+03 9.750E+01 0.000E+00 6.070E+01 CS-134 6.840E+03 1.630E+04 1.330E+04 0.000E+00 5.270E+03 1.750E+03 2.850E+02 ES-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 A.700E-01 5.120E-05 BA-139 7. 8 50E+ 00 5. 5 9 0E- 03 2. 3 00E- 01 0. 000E+ 00 5.23 0E-03 3.170E-03 1.3 90E+ 01 BA-140 1.640E+03 2.060E+00 1.080E+02 0.000E+00 7.020E-01 1.180E+00 3.380E+03 i BA-141 3. 810E+00 2. E 10E-03 1.290E- 01 0 000E+00 2. 6 8 0E-03 1. 630E-03 1. 8 00E-09 BA-142 1.720E+00 1.770E-03 1.080E-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 1.000E+02 4.800E+01 3.700E+02 6.200E-01 3.400E+01 4.800E+00 3.200E+03 LA-342 8.060E-02 1,670E-02 9.130E-03 0.000E+00 0.000E+00 0.000E+00 2.680E+02 CE-141 3.430E+00 2.320E+00 2.630E-01 0.000E+00 1.080E+00 0.000E+00 8.860E+03 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 5.790E+00 2.320E+00 2.870E-01 0.000E+00 1.340E+00 0.000E+00 2.540E404 PR-144 1.900E-02 7.870E-03 9.640E-04 0.000E+00 4.440E-03 0.000E+00 2.730E-09 ND+147 3.960E+00 4. 50 0E+00 2.74 0E-01 0. 000E+ 00 2.68 0E+00 0. 000E+00 2.2 00E+04 W-187 9.160E+00 7.660E+00 2.680E+00 0.000E+00 0.000E+00 0.000E+00 2.510E+03 1 NP-239 3.530E-02 3.470E-03 1.910E-03 0.000E+00 1.080E-02 0.000E+00 7.110E+02 ! HG-203 I 1.4 00E+ 05 0. 000E + 00 1.6 00E+ 05 0. 000E+00 1. 6 00E+06 1. 000E+ 05 3.200E+ 05 j 1

                     ..,ite Dose Calculation Manual
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f . Revision 1, Change O P.g i16 of 247 ATTACilMENT 7 GENERAL INFORMATION RELATED TO GASEOUS RELEASE $ VIA TIIE MAIN VENTS Waste Stream 1 Radiation Type of Nominal Discharge Maximum Discharge Notes , Monitor release Flow Rate Flow Rate m 3/sec SCFM 3 m /sec SCFM Waste Gas Systern (WGDT) . 0-RE-2191 2 Batch N/A N/A 2.36E-2 50 Cntmt. Vent (via 112 Purge) 3 l 1/2-RE-5415 Baten' N/A N/A 2.36E-2 50 Cntmt. Purge (5% Modified) 1/2-RE-5415 3 Continuous N/A N/A 1.928 4085 Cntmt. Purge (10% Modified) 1/2-RE-5415' Continuous N/A N/A 7.996 16940 3 Cntmt. Purge (100% Modified) 1/2-RE-5415 Continoous N/A N/A 17.70 37500 i Unit 1 Main Vent Release I-RE-5415 5 Continuous 59.4 6 125858 6 65.34 7 138444 7 8 Unit 2 Main Vent Release 2-RE-5415 Continuous 47.I' 997496 51.78 7 109724 7 Information for waste streams not insted la this t ble should be evetuated on a case-by-case basis. Since the WGOT le reteesed to the plant vent stack, 1/2-RE-5415 and 1/2-R5-5416 may etso be used to monitor reteeses from a ucer. l The WRCM,1/2-RE-5416, may also monitor main vent reteeses. A contelnment vent Is considered a "betcha release (even though Inteekega of radioactive gases into the contaltwent etmos@ere may occur daring the time the vent is In progressi. The WRCM,1-RE-5416, may also smitor main vent reteeses. This la the mean meln vent stock flow rate es determined by approved Engineering Test Procedere (i.e., ETP-87-16). This Is the moulcun vent stock flow rate as determined by approved Engineering fest Procedt're (I.e., ETP-87-16). O ~ The WRCM, 2-RE-5416,' may etso monitor mein vent reteeses.

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Osmie Dose Calculation lwanual Page Iil of 247 $ Revision I, Change 0 I t

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ATTACllMENT 8 t I GENERAL INFORMATION REl.ATED TO GASEOUS RELEASES VIA PATilWAYS OTIIER TIIAN Tile MAIN VENTS - I e Waste Stream' Radiation Type of Nominal Discharge Notes Monitor Release Flow Rate ' i Aux. Iloiler Deaerator Unmonitored See Footnote 2 See Footnote l Sim. Gen. Atm. Stm. Dumps Unmonitored See Footnote2 See Footnote l Pinnt Nitrogen System Uomonitored See Footnote 2 See Footnote 3 z . Turbine Illdg. Vent. Exh. Unmonitored See Footnote See Footnote 3 2 Emergency Air Lock Unmonitored See Footnote See Footnote l 2 Plant Compressed Air Unmonitored See Footnote See Footnote l Main Steam Line Penetrations Unmonitored See Footnote 2 See Footnote 3 Information for waste streams not (Isted in this table shouta be evaluated on a case-by-case basis. Since radioactive gaseous waste is not normat ty vented via this pathesy, '.he determination of release type (i.e., continuous or batch) will be evaluated on a case-by-case basis. since radioactive gaseous waste is not norectly vented via this pathway, the determination of discharge flow rate will be evaluated on a case-by-case basis. ,

m -

Of fstte Dose Calculation Manual At tachment 9 Paae 178 of 240 RevIston 1 Radioactive Gaseous Waste Treatment System (CCNPP) 5 e >

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A waste cas A A I_ Decay Tants v t__. A 610 ft 3 - C - _ 150 psig g]f u o o y o o u y u u o o u 0-PE-2191 Automatic Isoleum R l-RE-5415 , 2-RE-5415 HEPA Fitter ,) 1-RE-5416 A l 2-RE-5416 C - twcoet nitors h g g Unit t Wu 2

     @ - Radletion Elet                 Piet vent                                                                                             py,n, y n,

                                       .       . . . . ~ . .  .      . ~ . . . . . - . . .   ...           .~.   -.

Offsite Dose Calculation Manual Page 179 of 247 I Revision 1, Change 0 ATTACIBfENT 10 NOBLE GAS DOSE FACTORS CA H A BODY DOSE BETA SKih DOSE CA*MA AIR DOSE BETA AIR DOSE 41UCLIDE K L M N (mreer/yr)/(aci/m ) (mrem /yr)/(gD1/m#) (mrad /yr)/(gCl/m#) (ared/yr)/(gCf/m#) Ar 41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Kr 85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr 85m 1.17E+03 1.46E+03 1.23E+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 xe 131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 xe-133 2.94E+02 3.06E+02 3.53E< -)2 1.05E+03 ( xe 133m 2.51E+02 9.94E+02 3.27E + 02 1.48E+03 xe 135 1.81E*03 1.86E+03 1.92E+03 2.46E+03

     *e 135m            3.12E+03              7.11E+02              3.36E+03                     7.39E+02
      *e 138            8.83E+03              4.13E+03              9.21E+03                     4.75E+03 i

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                                                                                     . - . - .-                    . ~... .

Offsite Dose Calculation Manual Page 180 of 247 Revision 1, Change 0 ; ATTACIBIENT 11 BfPIRICAL DERIVATION OF SITE SPECIFIC DOSE FACTORS ' Page1of5 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 nuclide specific dose factors. However, these same doses may be estimated using empirically derived, site speciDc, dose factors as shown below. TOTAL-BODY, GAADIA-DOSE FACTOR A site-specific, total body, gamma-dose factor has been derived from historical data in accordance with the following equation. K = [ ( K, ) ( f, ) Eq. IF

K, ,, the empirically derived, site-specific, total-body, gammadose factor due to all noble gases l released during a specified time period Values of K several year,s,., have been calculated using gaseous radwaste discharge data co 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 r radionuclide, i (mrem yr 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 tabulated in Attachment 10.

t 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 value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5.

l i i _ _ +. _ _ _

Offsite Dose Calculation Manual Page 181 of 247 Revision 1, Change 0 ( ATTACIBIENT 11 DiPIRICAL DERIVATION OF SITE-SPECIFIC DOSE FACTORS Page 2 of 5 l SKIN, BETA-DOSE FACTOR A site-specific, skin, beta-dose factor has been derived from historical data in accordance with the following equation. L,,, = [ ( L, ) ( f )' 3 Eq.2F L,,8

                 =    the empirically derived, site-speciDc, skin, beta-dose factor due to all noble gases released during a speciDed time period Values of L several year,s,., have been calculated using gaseous radwaste discharge data co The results of the calculations appear in the Table on page 5 of this attachment.

L, = the skin dose factor due to beta emissions for each identified noble gas 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 (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. (

Offsite Dose Calculation Manual Revision 1, Change 0 Page 182 of 247 ATTACHMENT 11 EMPIRICAL DERIVATION OF SITE-SPECIFIC DOSE FACTORS Page 3 of 5 GAADIA-AIR-DOSE FACTOR A site-specific, gamma-air-dose factor has been derived from historical data in accordance with the following equation. M,y = [ ( M, ) ( f, ) Eq.3F ,

M,, ' the empirically derived, site-specific, gamma-air-dose factor due to all noble gases released daring a specified time period Values of M have been calculated using gaseous radwaste discharge data collected over several years,.y ( 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 microcurie / cubic meter) The gamma air dose factors have been obtained from ReFulatory Guide 1.109, Appendix B. Table B-1. The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

f. =

a fraction which represents the relative activity contri>ution of noble gas radionuclide i to the total noble gas activity for TYPJCAL GASEOUS EFFLUENTS (unitless) 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. (

l Offsite Dose Calculation Manual Page 183 of 247 Revision 1, Change 0 l l ' l ATTACIBIENT 11 l EMPIRICAL DERIVATION OF SITE-SPECIFIC DOSE FACTORS Page 4 of 5 BETA-AIR-DOSE FACTOR A site-specific, beta-air-dose factor has been derived from historical data in accordance with the following equation. N,, , = [ ( N, ) ( f; ) Eq 4F N *= the empirically derived, site-specific, beta-air-dose factor due to all noble gases released during a specified time period Values of N, have been calculated using gaseous radwaste discharge data collected over several years, t 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 microcurie / 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 Attachment 10 (Attachment 1 of old ODCM). f3 = 0 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. l

i

                                                                              ..                                         l

Offsite Dose Calculation Manual Page 184 of 247 Revision 1, Change 0 ATTACHMENT 11 ( EMPIRICAL DERIVATION OF SITE SPECIFIC DOSE FACTORS Page 5 of 5 SITE-SPECIFIC, 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 l 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 un;ertainty inherent in the environmental dose calculation models. It should be noted that the emperically-derived, site-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 ensure the estimated doses are only a small fraction of the Technical Specification limits. Additionally, the doses shall be recalculated using the RIGOROUS METHODS prior to submitting the Semi-Annual Radioactive Effluent Release Report. t a

l

        ' Offsite Dose Calculation Manual                                                               Page 185 of 247 Revision 1, Change 0 i

ATTACHMENT 12

-(

GRASS-COW-MEAT DOSE FACTORS ADULT (m2

mrem /yr per uCi/sec)

Nuclide Ecne Liver Tbody Thyroid Kidney Lung Gitract E-3 0.000E+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 C-14 3.330E+05 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 NA-24 1.840E-03 1,840E-03 1.840E-03 1.840E-03 1.840E-03 1.040E-03 1.840E-03 P-32 4. 6 5 0E+ 09 2. 8 90E+0B 1. 8 00E+0B 0. 000E+00 0. 000E+00 0. 000E+00 5.23 0E+08 CR-51 0. 000E+00 0. 000E+ 00 7. 07 0E+03 4.22 0E+03 1. 56 0E+03 9. 3 80E+03 1.78 0E+ 06 KN-54 0. 000E+0C 9.150E+ 06 1.75 0E+06 0. 000E+00 2.72 0E+06 0. 000E+00 2. 8 00E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E-00 0.000E+00 0.000E+00 FE-55 2.930E+08 2.020E+08 4.720E+07 0.000E+00 0.000E+00 1.130E+08 1.160E+08 FE-59 2.670E+06 6.270E+08 2.400E+0B 0.000E+00 0.000E+00 1.750E+08 2.090E+09 CO-57 0.0002 00 5.640E+06 9.370E+06 0.000E+00 0.000E+00 0.000E+00 1.430E+08 CO-58 0.0C:E+00 1.830E+07 4.100E+07 0.000E+00 0.000E+00 0.000E+00 3.700E+08 l CO-60 0.00;E+00 7.520E+07 1.660E+08 0.000E+00 0.000E+00 0.000E+00 1.410E+09 b~7{ NI-63 1. 8 90E+10 1. 310E+09 6.33 0E+08 0. 000E+00 0. 000E+00 0. 000E+00 2.73 0E+ 08 NI-65 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 2.950E-07 1. 3 90E- 07 0. 000E+ 00 7.4 50E-07 0. 000E+00 2,52 0E- 05 ZN-65 3.560E+0B 1.130E+09 5.120E+0B 0.000E+00 7.570E+08 0.000E+00 7.130E+08 "N-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 BR-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 4. 870E+08 2.270E+0B 0.000E+00 0,000E+00 0.000E+00 9.600E+07 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 3. 010E+08 0. 000E+00 8.650E+06 0. 000E+00 0.000E+00 0.000E+00 4.84 0E+07 SR-90 1.240E+10 0. 000E+ 00 3. 05 0E+09 0. 000E+00 0. 000E+00 ~ 0. 000E+00 3.59 0E+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 0.00'.'E-01 0.000E+00 0.000E+00 . Y-90 1.070E+02 0.000E+00 2.860E+00 0.000E+00 0.000E+00'O.000E+00 1.130E+06 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 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 0. 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2 080E-07 ZR-95 1. 0 0 0E+06 6. 04 0E+05 4. 090E+05 0. 000E+00. 9.4 80E+ 05 0. 000E+00 1. 910E+09 ZR-97 1.830E-05 3.690E-06 1.690E-06 0.000E+00 5.580E-06 0.000E+00 1.140E+00 NE-95 2.290E+06 1.280E+06 6.860E+05 0.000E+00 1.260E+06 0.000E+00 7.750E+09-NE-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 1.090E+05 2.070E+04 0.000E+00 2.460E+05 0.000E+00 2.520E+05 TC-99M 0.000E+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 1.060E+08 0.000E+00 4.550E+07 0.000E+00 4.030E+08 0.000E+00 1.230E+10 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. 8 0 0E+0 9 0. 000E+00 3. 54 0E+08 0. 000E+00 5. 4 00E+09 0. 000E+ 00 1,010E+11 s % -

Offsite D0se Calculation Manual Page 186 of 247 Revision 1, Change 0 ATTACHMENT 12 k GRASS-COW-MEAT DOSE FACTORS ADULT (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RB-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+00 0.000E+00 AG-110M 6.690E+06 6.190E+06 3.670E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 SB-124 1.980E+09 3.740E+07 7.850E+08 4.800E+06 0.000E+00 1.540E+09 5.620E+10 SB-125 1.910E+09 2.130E+07 4.540E+08 1.940E+06 0.000E+00 1.470E+09 2.100E+10 TE-125M 3.590E+08 1.300E+0B 4.810E+07 1.080E+08 1.460E+09 0.000E+00 1.430E+09 TE-127M 1.120E+09 3.990E+08 1.360E+0B 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 1.090E-09 0.000E+00 2.100E-08 TE-129M 1.140E+09 4.270E+08 1.810E+08 3.930E+08 4.770E+09 0.000E+00 5.760E+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 1.840E602 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 TE-132 1.400E+06 9.070E+05 8.510E+05 1.000E+06 8.730E+06 0.000E+00 4.290E+07 I-130 2.350E-06 6.940E-06 2.740E-06 5.BBOE-04 1.000E-05 0.000E+00 5.980E-06 I-131 1.080E+07 1.540E+07 8.83 0E+06 5.050E+09 2.64 0E+07 0.000E+00 4.070E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 4.300E-01 7.470E-01 2.280E-01 1.100E+02 1.300E+00 0.000E+00 6.720E-01 I-134 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00'O.000E+00 CS-134 6.570E+0B 1.560E+09 1.280E+09 0.000E+00 5.060E+08 1.680E+08 2.740E+07 CS-136 1.180E+ 07 4. 6 70E+07 3. 36 0E+07 0. 000E+ 00 2.600E+ 07 3. 560E+ 06 5. 3 00E+06 CS-137 0.720E+08 1.190E+09 7.810E+0B 0.000E+00 4.050E+08 1.350E+08 2.310E+07 CS-138 0.000E+0L 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-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 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 3.600E-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 0.00CE+00 0.000E+00 0.000E+00 CE-141 1.400E+04 9.480E+03 1.080E+03 0.000E+00 4.400E+03 0.000E+00 3.620E+07 CE-143 2.090E-02 1.550E+01 1.710E-03 0.000E+00 6.800E-03 0.000E+00 5.780E+02 CE-144 1.460E+06 6.090E+05 7.830E+04 0.000E+00 3. 610E+05 0.000E+00 4. 93 0E+08 PR-143 2.130E+04 8.540E+03 1.060E+b3 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 ND-147 7.080E+03 8.180E+03 4.900E+02 0.000E+00 4.780E+03 0.000E+00 3.930E+07 W-187 2.160E-02 1.810E-02 6.320E-03 0.000E+00 0.000E+00 0.000E+00 5.920E+00 NP-239 2.560E-01 2.510E-02 1.390E-02 0.000E+00 7.840E-02 0.000E+00 5.150E+03-I

l Offsite Doze Calculation Manual Paga 187 of 247 Revision 1,' Change 0 j ATTACHMEffT 12 GRASS-COW-MEAT DOSE FACTORS TEEN (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 C-14 2.810E+05 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04

 .NA-24     1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 P-32     3.930E+09 2.440E+08 1.520E+08 0.000E+00 0.000E+00 0.000E+00 3.300E+08 CR-51     0.000E+00 0.000E+00 5.650E+03 3.140E+03 1.240E+03 8.070E+03 9.500E+05 MN-54     0.000E+00 6.980E+06 1.380E+06 0.000E+00 2.080E+06 0.000E+00 1.430E+07 MN-56     0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55    2.380E+08 1.690E+08 3.930E+07 0.000E+00 0.000E+00 1.070E+08 7.300E+07 FE-59    2.130E+08 4.980E+08 1.920E+0B 0.000E+00 0.000E+00 1.570E+08 1.180E+09 CO-57     0.000E+00 4.530E+06 7.590E+06 0.000E+00 0.000E+00 0.000E+00 8.450E+07 CO-58     0.000E+00 1.410E+07 3.250E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+08 CO-60     0.000E+00 5.830E+07 1.310E+08 0.000E+00 0.000E+00 0.000E+00 7.600E+08 N!-63     1.520E+10 1.070E+09 5.150E+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 CU-64 0.000E+00 2.410E-07 1.130E-07 0,000E+00 6.100E-07 0.000E+00 1.870E-05 "N-65 2.500E+08 8.690E+08 4.050E+08 0.000E+00 5.560E+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 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 BR-B5 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 4.060E+08 1.910E+08 0.000E+00 0.000E+00 0.000E+00 6.010E+07 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 2.540E+08 0.000E+00 7.290E+06 0.000E+00 0.000E+00 0.000E+00 3.030E+07 SR-90 8.050E+09 0.000E+00 1.990E+09 0.000E+00 0.000E+00 0.000E+00 2.260E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E-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 8.980E+01 0.000E+00 2.420E+00 0.000E+00 0.000E+00 0.000E+00 7.400E+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 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 1.690E-07 2R-95 1.510E+06 4.760E+05 3.270E+05 0.000E+00 6.990E+05 0.000E+00 1.100E+09 2R-97 1. 53 0E-05 3. 02 0E- 06 1. 3 90E-06 0. 000E+00 '4. 5 80E-06 0. 000E+ 00 8.18 0E-01 NB-95 1.790E+16 9.940E+05 5.470E+05 0.000E+00 9.640E+05 0.000E+00 4.250E+09 NB-97 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 8.980E+04 1.710E+04 0.000E+00 2.060E+05 0.000E+00 1.610E+05 7C-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+0D 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 8.600E+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 f RU-106 2.360E+09 0.000E+00 2.970E+08 0.000E+00 4.550E+09 0.000E+00 1.130E+11

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Offsite Dose Calculation Manual Pcga 188 of 247 Revision'1, Change 0 i ATTACHMENT 12 GRASS. COW-MEAT DOSE FACTORS TEEN (m

mrem /yr per uCi/see)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00 AG-110M 5. 06 0E+ 06 4. 790E+ 06 2. 910E+ 06 0. 000E+ 00 9.14 0E+ 06 0. 000E+00 1. 350E+09 SB-124 1.620E+09 2.980E+07 6.310E+0B 3.670E+06 0.000E+00 1.410E+09 3.260E+10 SB-125 1.560E+09 1.710E+07 3.660E+0B 1.490E+06 0.000E+00 1.370E+0.0 1.22sE+10 TE-125M 3.030E+08 1.090E+08 4.050E+07 8.470E+07 0.000E+00 0.n00E,00 B.940E+08 TE-127M 9.410E+08 3.340E+0B 1.120E+08 2.240E+0B 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 TE-129M 9.580E+08 3.560E+08 1.520E+0B 3.090E+08 4.010E+09 0.000E+00 3.600E+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 3.760E+02 1.800E+02 1.500E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 ( 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 1.150E+06 7.260E+05 6.840E+05 7.660E+05 6.970E+06 0.000E+00 2.300E+07 ,( I-130 1.890E-06 5.480E-06 2.190E-06 4.470E-04 8.440E-06 0.000E+00 4.210E-06 I-131 8.950E+06 1.250E+0? 6.730E+06 3.660E+09 2.160E+07 0.000E+00 2.480E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 3.590E-01 6.100E-01 1.860E-01 8.510E+01 1.070E+00 0.000E+00 4.610E-01 1-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2-135 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 5.710E+08 0.000E+00 3.910E+0B 1.490E+0B 1.530E+07 CS-136 9.220E+06 3.630E+07 2.440E+07 0.000E+00 1.970E+07 3.110E+06 2.920E+06 CS-137 7.240E+08 9.630E+0B 3.360E+08 0.000E+00 3.280E+08 1.270E+0B 1.370E+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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.380E+07 2,910E+04 1.530E+06 0.000E+00 9.880E+03 1.960E+04 3.670E+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 2.960E-02 1.450E-02 3.870E-03 0.000E+00 0.000E+00 0.000E+00 6.350E+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 7.860E+03 9.030E+02 0.000E+00 3.700E+03 0.000E+00 2.250E+07 CE-143 1.760E-02 1.280E+01 1.430E-03 0.000E+00 5.740E-03.0.000E+00 3.850E+02 CE-144 1.230E+06 5.080E+05 6.600E+04 0.000E+00 3.040E+05 0.000E+00 3.090E+08 PR-143 1.790E+04 7.150E+03 8.920E+02 0.000E+00 4.160E+03 0.000E+00 5.900E+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 6.240E+03 6.790E+03 4.060E+02 0.000E+00 3.980E+03 0.000E+00 2.450E+07 W-187 1.810E-02 1.480E-02 5.170E-03 0.000E+00 0.000E+00 0.000E+00 3.990E+00 NP-239 2.230E-01 2.110E-02 1.170E-02 0.000E+00 6.610E-02 0.000E+00 3.390E+03

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Offsite Dose Calculation Manual Page 189 of 247 Revision 1,' Change O ATTACHMENT 12 L GRASS-COW-MEAT DOSE FACTORS CHILD , 2 (m

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Eldney Lung Gitract H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 C-14 5.290E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+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+0B 2.860E+08 0.000E+00 0.000E+00 0.000E+00 2.050E+08 CR-51 0.000E+00 0.000E+00 B.810E+03 4.890E+03 1.340E+03 8.930E+03 4.670E+05 MN-54 0.000E+00 7.990E+06 2.130E+06 0.000E+00 2.240E+06 0.000E+00 6.700E+06 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 4. 570E+08 2. 42 0E+08 7. 510E+07 0. 000E+ 00 0. 000E+00 1.3 70E+08 4.4 90E+07 FE-59 3.780E+08 6.12 0E+0B 3. 05 0E+08 0. 000E+ 00 0. 000E+00 1.770E+08 6.3 70E+08 CO-57 0.000E+00 5.920E+06 1.200E+07 0.000E+00 0.000E+00 0.000E+00 4.850E+07 CO-58 0.000E+00 1.650E+07 5.040E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+07 [ CO-60 0.000E+00 6.930E+07 2.040E+08 0.000E+00 0.000E+00 0.000E+00 3.840E+08 6L , NI-63 2. 910E+10 1. 5 60E+09 9. 910E+08 0. 000E+00 0.000E+00 0.000E+00 1. 050E+0 8 NI-65 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 1.960E-07 0.000E+00 7.820E-07 0.000E+00 1.520E-05 ZN-65 3.750E+0B 1. 000E+09 6.220E+08 0. 000E+00 6.300E+08 0.000E+00 1.760E+08 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 BR-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 5.760E+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 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 4.820E+08 0. 000E+ 00 1.3 80E+07 0. 000E+00 0. 000E+00 0. 000E+0' 1.860E+07 SR-90 1.040E+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 0.000E400 4.550E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+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 1.810E+06 0.000E+00 4.830E+04 0.000E+00 0.000E+00 0.000E+00 2.410E+0B Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.550E-07 ZR-95 2. 6 8 0E+ 06 5. 890E+05 5.24 0E+ 05 0. 000E+00 8.430E+05 0.000E+00 6.140E+0 8 ZR-97 2.840E-05 4.100E-06 2.420E-06 0.000E+00 5.890E-06 0.000E+00 6.210E-01 NB-95 3.090E+06 1.200E+06 8.610E+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 MO-99 0.000E+00 1.200E+05 3.090E+04 0.000E+00 2.670E+05 0.000E+00 1.030E+05 TC-99M 0.000E+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 1.560E+08 0.000E+00 5.980E+07 0.000E+00 3.920E+08 0.000E+00 4.020E+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+08 0.000E+00 5.990E+09 0.000E+00 6.900E+10

Offsite Dose Calculction Manual Pagn 190 of 247 Revision 1, Change O ATTACHMENT 12 i ( GRASS-COW-MEAT DOSE FACTORS CHILD (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00 AG-110M 8.400E+06 5.670E+06 4.530E+06 0.000E+00 1.060E+07 0.000E+00 6.750E+0B SB-124 2.930E+09 3.800E+07 1.030E+09 6.460E+06 0.000E+00 1.620E+09 1.830E+10 SB-125 2.850E+09 2.190E+07 5.960E+08 2.640E+06 0.000E+00 1.590E+09 6.800E+09 TE-125M 5.690E+0B 1.540E+08 7.590E+07 1.600E+08 0.000E+00 0.000E+00 5.490E+06 TE-127M 1.770E+09 4.7BOE+0B 2.110E+08 4.240E+0B 5.060E+09 0.000E+00 1.440E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 1.660E.08 TE-129M 1.810E+09 5.040E+08 2.800E+0B 5.820E+0B 5.300E+09 0.000E+00 2.200E+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 7.000E+02 2.420E+02 2.580E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 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 2.090E+06 9.270E+05 1.120E+06 1,350E+06 8.600E+06 0.000E+00 9.330E+06 I-130 3.390E-06 6.850E-06 3.530E-06 7.540E-04 1.020E-05 0.000E+00 3.200E-06 ( I-131 1.660E+07 1.670E+07 9.490E+06 5.520E+09 2.740E+07 0.000E+00 1.490E+06 2-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2-133 I-134 6.680E-01 8.260E-01 3.120E-01 1.530E+02 1.380E+00 0.000E+00 3.330E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 9.220E+08 1.510E+09 3.190E+08 0.000E+00 4.690E+0B 1.680E+0B B.150E+06 CS-136 1.590E+07 4.370E+07 2.830E+07 0.000E+00 2.'330E+07 3.470E+06 1.540E+06 CS-137 1.330E+09 1.280E+09 1.880E+08 0.000E+00 4.160E+0B 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.390E+07 3.850E+04 2.560E+06 0.000E+00 1.250E+04 2.290E+04 2.220E+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 5.410E-02 1.890E-02 6.380E-03 0.000E+00 0.000E+00 0.000E+00 5.270E+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 2.220E+04 1.110E+04 1.64 0E+ 03 0. 00 0E+ 00 4. 84 0E+ 03 0. 000E+ 00 1. 3 8 0E+ 07 CE-143 CE-144 3.300E-02 1.790E+01 2.590E-03 0.000E+00 7.510E-03 0.000E+00 2.620E+02 2.320E+06 7.260E+05 1.240E+p5 0.000E+00 4.020E+05 0.000E+00 1.890E+08 PR-143 3.390E+04 1.020E+04 1.680E+03 0.000E+00 5.510E+03 0.000E+00 3.660E+07 PR-144 ND-147 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 W-187 1.170E+04 9.4 8 0E+ 03 7.34 0E+02 0. 000E+00 5.2 00E+03 0. 000E+00 1.500E+ 07 NP-239 3.360E-02 1.990E-02 8.920E-03 0.000E+00 0.000E+00 0.000E+00 2.790E+00 4.200E-01 3.020E-02 2.120E-02 0.000E+00 8.730E-02 0.000E+00 2.230E+03 e

s.+.~ < . .: 2 : "- ' . .. u. ~ ' '

Offsite Dose Calculation Manual Page 191 of 247 Revision 1,' Change O ATTACHMENT 12

'4-GRASS-COW-MEAT DOSE FACTORS INFANT (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 1 i l 1 f j m

1 i

        .Offsite Dose Calculation Manual                                      Page 192 of 247    i Revision 1, Change 0 l

f ATTACHMENT 12 ! I. 1 GRASS-COW-MEAT DOSE FACTORS l l INFAh7 ' (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract E 4 Y 1

_ ~ 1 I Offsite Dose Calculation Manual Page 193 of 247 Revision 1, Change 0

ATTACHMENT 12 VEGETATION DOSE FACTORS ADULT . (m2

mrem /yr per uCi/sec) !

Nuclide Bene Liver Tbody Thyroid Kidney Lung Gitract i E-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 C-14 8. 9 70E+ 05 1. 790E+ 05 1. 7 9 0E+ 05 2 . 79 0E+ 05 1. 790E+ 05 1. 790E+ 0 3 1. 790E+ 05 NA-24 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 P-32 1.400E+09 8.730E+07 5.420E+07 0.000E+00 0.000E+00 0.000E+00 1.580E+08 CR-51 0.000E+00 0.000E+00 4.660E+04 2.790E+04 1.030E+04 6.190E+04 1.170E+07 KN-54 0.000E+00 3.110E+08 5.940E+07 0.000E+00 9.270E+07 0,000E+00 9.540E+08 MN-56 0.000E+00 1.610E+01 2.850E+00 0.000E+00 2.040E+01 0.000E+00 5.130E+02 ! FE-55 2.090E+0B 1.450E-08 3.370E+07 0.000E+00 0.000E+00 8.060E+07 8.290E+07 FE-59 1.270E+0B 2.990E+08 1.140E+08 0.000E+00 0.000E+00 8.350E+07 9.960E+08 . CO-57 0.000E+00 1.170E+07 1.950E+07 0.000E+00 0.000E+00 0.000E+00 2.970E+08 CO-58 0.000E+00 3.090E+07 6.920E+07 0.000E+00 0.000E+00 0.000E+00 6.260E+08 g CO-60 0.000E+00 1.670E+08 3.690E+08 0.000E+00 0.000E+00 0.000E+00 3.140E+09 g , NI-63 1.040E+10 7.210E+08 3.490E+08 0.000E+00 0.000E+00 0.000E+00 1.500E+0B NI-65 6.150E+01 7.990E+00 3.650E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 CU-64 0.000E+00 9.270E+03 4.350E+03 0.000E+00 2.340E+04 0.000E+00 7.900E+05 ZN-65 3.170E+08 1.010E+09 4.560E+08 0.000E+00 6.750E+08 0.000E+00 6.360E+08 ZN-69 8.750E-06 1.670E-05 1.160E-06 0.000E+00 1.090E-05 0.000E+00 2.510E-06 I BR-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 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 RB-86 0.000E+00 2.190E+0B 1.020E+08 0.000E+00 0.000E+00 0.000E+00 4.320E+07 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 9.960E+09 0.000E+00 2.860E+08 0.000E+00 0.000E+00 0.000E+00 1.600E+09 SR-90 6.050E+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-92 4.270E+02 0.000E+00 1.850E+01 0.000E+00 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 5.130E+06 0.000E+00 1.370E+05 0.000E+00 0.000E+00 0.000E+00 2.820E+09 Y-92 9.010E-01 0.000E+00 2.630E-02 0.000E+00 0.000E+00 0.000E+00 1.580E+04. - Y 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 1.210E+09 ZR-97 3.330E+02 6.730E+01 3.080E+01 0.000E+00 1.020E+02 0.000E+00 2.080E+07. NB-95 1.420E+05 7.910E+04 4.250E+04 0.000E+00 7.810E+04 0.000E+00'4.800E+08 NB-97 2.900E-06 7.340E-07 2.680E-07 0.000E+00 8.560E-07 0.000E+00 2.710E-03 MD-99 0.000E+00 6.250E+06 1.190E+06 0.000E+00 1.410E+07 0.000E+00 1.450E+07 TC-99M 3.060E+00 8.660E+00 1.100E+02 0.000E+00'1.320E+02 4.240E+00 5.120E+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-203 4.800E+06 0.000E+00 2.070E+06 0.000E+00 1.830E+07 0.000E+00 5.610E+08 I RU-105 5.390E+01 0.000E+00 2.130E+01 0.000E+00 6.960E+02 0.000E+00 3.300E+04 RU-106 1.930E+08 0.000E+00 2.440E+07 0.000E+00 3.720E+0B 0.000E+00 1.250E+10

1

Offsite Dose Calculation Manual Page 194 of 247 Revision 1, Change O ATTACHMENT 12 VEGETATION DOSE FACTORS ADULT (m2

mrem /yr per uCi/see)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract I RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0D 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 1.060E+07 9.760E+06 5.800E+06 0.000E+00 1.920E+07 0.000E+00 3.980E+09 SB-124 1.040E+08 1.960E+06 4.110E+07 2.520E+05 0.000E+00 8.080E+07 2.950E+09 SB-125 1.360E+08 1.520E+06 3.250E+07 1.390E+05 0.000E+00 1.050E+08 1.500E+09 TE-125M 9.660E+07 3.500E+07 1.290E+07 2.900E+07 3.930E+0B 0.000E+00 3.860E+08 TE-127M 3.490E+08 1.250E+0B 4.260E+07 8.920E+07 1.420E+09 0.000E+00 1.170E*09 TE-127 5.760E+03 2.070E+03 1.250E+03 4.270E+03 2.350E+04 0.000E+00 4.540E+05 TE-129M 2.550E+08 9.500E+07 4.030E+07 8.750E+07 1.060E+09 0.000E+00 1.280E+09 TE-129 6.650E-04 2.500E-04 1.620E-04 5.100E-04 2.790E-03 0.000E+00 5.020E-04 TE-131M 9.120E+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+00 0.000E+00-TE-132 4.290E+06 2.770E+06 2.600E+06 3.060E+06 2.670E+07 0.000E+00 1.310E+08

l. I-130 3.960E+05 1.170E+06 4.610E+05 9.900E+07 1.820E+06 0.000E+00 1.010E+06 I-131 8.090E+07 1.160E+08 6.630E+07 3.790E+10 1.980E+08 0.000E+00 3.050E+07 I-132 5.740E+01 1.540E+02 5.380E+01 5.380E+03 2.450E+02 0.000E+00 2.890E+01 '

I-133 2.120E+06 3.690E+06 1.120E+06 5.420E+08 6.440E+06 0.000E+00 3.310E+06 I-134 1.060E-04 2.880E-04 1.030E-04 5.000E-03 4.590E-04 0.000E+00 2.510E-07 I-135 4.080E+04 1 070E+05 3.940E+04 7.040E+06 1.710E+05 0.000E+00 1.210E+05 CS-134 4.660E+09 1.110E+10 9.070E+09 0.000E+00 3.590E+09 1.190E+09 1.940E+08 CS-136 4.200E+07 1.660E+08 1.190E+08 0.000E+00 9.240E+07 1.270E+07 1.890E+07 CS-137 6. 3 6 0E+ 09 B.700E+ 09 5. 700E+ 09 0.000E+ 00 2.950E+ 09 9. 810E+0B 1. 6 80E+08 CS-130 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 1.190E-05 5.230E-02 BA-14L 1.290E+08 1.620E+05 8.430E+06 0.000E+00 5.490E+04 9.250E+04 2.650E+08 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 1.970E+03 9.920E+02 2.620E+02 0.000E+00 0.000E+00 0.000E+00 7.280E+07 LA-142 1.400E-04 6.350E-05 1.580E-05 0.000E+00 0.000E+00 0.000E+00 4.640E-01 CE-141 1.960E+05 1.330E+05 1.510E+04 0.000E+00 6.170E+04 0.000E+00 5.080E+0B > CE-143 1.000E+03 7.420E+05 8.210E+01 0.000E+00 3.260E+02 0.000E+00 2.770E+07 CE-144 3.290E+07 1.380E+07 1.770E+06 0.000E+00 8.160E+06 0.000E+00 1.110E+10-PR-143 6 340E+04 2.540E+04 3.140E+03 0.000E+00 1.470E+04 0.000E+00 2.780E+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 3.860E+04 2.310E+03 0.000E+0D 2.250E+04 0 000E+00 1.950E+0B W-187 3.820E+04 3.190E+04 1.120E+04 0.000E+00 0.000E+00 0.000E+00 1.050E+07 NP-239 1.4 2 0E+03 1.4 00E+ 02 7.72 0E+01 0. 000E+00 4.370E+ 02 0.000E+00 2. 870E+ 07 f

Offsite Dose Calculation-Manual Paga 195 of 247 Reviolon 1,: Change 0 l , ATTACHMENT 12 i { ( VEGETATION DOSE FACTORS TEEN 2 (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract E-3 C-14 0.000E+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 NA-24 1.450E+06 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 P-32 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 CR-51 1.610E+09 9.960E+07 6.230E+07 0.000E+00 0.000E+00 0.000E+00 1.350E+08 MN-54 0.000E+00 0.000E+00 6.200E+04 3.440E+04 1.360E+04 8.850E+04 1.040E+07 MN-56 0.000E+00 4.520E+08 8.970E+07 0.000E+00 1.350E+08 0.000E+00 9.270E+08 FE-55 0.000E+00 1.450E+01 2.580E+00 0.000E+00 1.830E+01 0.000E+00 9.540E+02 FE-59 3.250E+08 2.310E+0B 5.380E+07 0.000E+00 0.000E+00 1.460E+08 9.980E+07 CO-57 1.810E+0B 4.220E+08 1.630E+08 0.000E+00 0.000E+00 1.330E+08 9.980E+08 CO-58 0.000E+00 1.790E+07 3.000E+07 0.000E+00 0.000E+00 0.000E+00 3.340E+0B CO-60 0.000E+00 4.380E+07 1.010E+08 0.000E+00 0.000E+00 0.000E+00 6.040E+08 NI-6' 0.000E+00 2.490E+08 5.600E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 NI-65 1.610E+10 1.130E+09 5.450E+08 0.000E+00 0.000E+00'O.000E+00 1.810E+08 ( CU-64 5.730E+01 7.320E+00 3.330E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 ZN-65 0.000E+00 8.400E+03 3.950E+03 0.000E+00 2.120E+04 0.000E+00 6.510E+05 4.240E+0B 1.470E+09 6.860E+0B 0.000E+00 9.410E+0B 0.000E+00 6.230E+08 ZN+69 BR-82 8.190E-06 1.560E-05 1.090E-06 0.000E+00 1.020E-05 0.000E+00 2.880E-05 BR-63 0.000E+00 0.000E+00 1.330E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 3.010E+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-86 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

0. 000E+ 00 2.73 0E+08 1.2 8 0E+ 08 0. 000E+00 0. 000E+00 0. 000E+00 4. 050E+07 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 1.510E+10 0. 000E+ 00 4. 33 0E+ 08 0. 000E+ 00 0. 000E+00 0. 000E+00 1. 800E+09 SR-90 7.510E+11 0.000E+00 1.850E+11 0.000E+00 0.000E+00 0.000E+00 2.110E+10 SR-91 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 1.240E+04 0. 000E+00 3.34 0E+02 0. 000E+00 0. 000E+00 0. 000E+ 00 1. 020E+08 Y-91M 5.430E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E-07 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 Y-93 8.470E-01 0.000E+00 2.450E-02 0.000E+00 0.000E+00 0.000E+00 2.320E+04 ZR-95 1.630E+02 0.000E+00 4.470E+00 0.000E+00 0.000E+00 0.000E+00 4.980E+06 ZR-97 1.740E+06 5.490E+05 3.780E+05 0.000E+00 8.070E+05 0.000E+00 1.270E+09 3.090E+02 6.110E+01 2.810E+01 0.000E+00 9.260E+01 0.000E+00 1.650E+07 NB-95 1.920E+05 1.060E+05 5.860E+04 0.000E+00 1.030E+05 0.000E+00 4.550E+08 NB-97 2.690E-06 6,670E-07 2.440E-07 0.000E+00 7.800E-07 0.000E+00 1.590E-02 MO-99 0.000E+00 5.740E+06 1.090E+06 0.000E+00 1.310E+07 0.000E+00 1.030E+07 TC-99M 2.700E+00 7.540E+00 9.770E+01 0.000E+00 1.120E+02 4.190E+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 6.870E+06 0.000E+00 2. 94 0E+06 0. 000E+ 00 2.420E+07 0.000E+00 5.740E+08 RU-105 5.000E+01 0. 000E+ 00 1. 94 0E+ 01 0. 000E+ 00 6.310E+02 0. 000E+00 4. 04 0E+ 04 RU-106 3. 090E+ 08 0. 000E+ 00 3. 900E+ 07 0. 000E+ 00 5. 970E+08 0.000E+ 00 1.4 8 0E+10

{

u. S

Offsite Dose Calculation Manual Pegs 196 of 247 Ravision 1, Ohtnge O ATTACHMENT 12 ( VEGETATION DOSE FACTORS TEEN (m

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00 AG-110M 1. 52 0E+ 07 1.4 4 0E+07 8.74 0E+06 0. 000E+ 00 2.74 0E+07 0. 000E+00 4. 04 0E+09 SB-124 1.550E+08 2.850E+06 6.030E+07 3.510E+05 0.000E+00 1.350E+08 3.110E+09 SB-125 2.140E+08 2.340E+06 5.000E+07 2.040E+05 0.000E+00 1.880E+08 1.660E+09 TE-125M 1.480E+08 5. 34 0E+ 07 1. 98 0E4 07 4.14 0E+ 07_ 0. 000E+ 00 0. 000E+ 00 4. 3 70E+ 08 TE-127M 5.510E+08 1.960E+08 6.560E+07 1.310E+08 2.240E+09 0.000E+00 1.370E+09 TE-127 5.430E+03 1.920E+03 1.170E+03 3.740E+03 2.200E+04 0.000E+00 4.190E+05 TE-129M 3.670E+08 1.360E+0B 5,810E+07 1.180E+08 1.540E+09 0.000E+00 1.380E+09 TE-129 6.220E-04 2.320E-04 1.510E-04 4.450E-04 2.610E-03 0.000E+00 3.400E-03 TE-131M 8.440E+05 4.050E+05 3.380E+05 6.090E+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-TE-132 3.900E+06 2.470E+06 2.320E+06 2.600E+06 2.370E+07 0.000E+00 7.820E+07 ( I-130 3.540E+05 1.020E+06 4.090E+05 8.350E+07 1.580E+06 0.000E+00 7.870E+05 I-131 7.700E+07 1.000E+08 5.790E+07 3.140E+10 1.850E+08 0.000E+00 2.130E+07 1-132 5.180E+01 1.360E+02 4.870E+01 4.570E+03 2.140E+02 0.000E+00 5.910E+01 I-133 1.970E+06 3.340E+06 1.020E+06 4.660E+0B 5.860E+06 0.000E+00 2.530E+06 I-134 9.590E-05 2.540E-04 9.130E-05 4.240E-03 4.010E-04 0.000E+00 3.350E-06 I-135 3.680E+04 9.480E+04 3.520E+04 6.100E+06 1.500E+05 0.000E+00 1.050E+05 CS-134 7.090E+09 1.670E+10 7.740E+09 0.000E+00 5.300E+09 2.020E+09 2.000E+08 CS-136 4.290E+07 1.690E+08 1.130E+0B 0.000E+00 9.190E+07 1.450E+07 1.360E+07 CS-137 1.010E+10 1.350E+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+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 2.770E-02 1.950E-05 8.080E-04 0.000E+00 1.840E-05 1.340E-05 2.470E-01 BA-140 1.380E+08 1.690E+05 8.910E+06 0.000E+00 5.750E+04 1.140E+05 2.130E+08 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 1.800E+03 8.840E+02 2.350E+02 0.000E+00 0.000E+00 0.000E+00 5.080E+07 LA-142 1.280E-04 5.690E-05 1.420E-05 0.000E+00 0.000E+00 0.000E+00 1.730E+00 CE-141 2.820E+05 1.880E+05 2.160E+04 0.000E+00 B.860E+04'O.000E+00 5.300E+08 CE-143 9.370E+02 6.820E+05 7.620E+01 0.000E+00 3.060E+02 0.000E+00 2-050E+07 . CE-144 5.270E+07 2.180E+07 2.830E+b6 0.000E+00 1.300E+07 0.000E+00 1.330E+10 PR-143 7.120E+04 2.840E+04 3.550E+03 0.000E+00 1.650E+04 0.000E+00 2.340E+08 PR-144 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.630E+04 3.940E+04 2.360E+03 0.000E+00 2.320E+04 0.000E+00 1.420E+08 W-187 3.550E+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 2.100E+07 2

   'Offsite Dose Calculation Manual                                                     Page 197 of 247 Ravision 1,: Change O ATTACHMENT 12

( VEGETATION DOSE FACTORS CHILD (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+06 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 NA-24 3.830E+05 3.830E+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+0B 0.000E+00 0,000E+00 0.000E+00 9.300E+07 CR-51 0.000E+00 0.000E+00 1.180E+05 6.540E+04 1.790E+04 1.190E+05 6.250E+06 MN-54 0.000E+00 6.610E+08 1.760E+0B 0.000E+00 1.850E+08 0.000E+00 5.550E+08 MN-56 0.000E+00 1.900E+01 4.280E400 0.000E+00 2.290E+01 0.000E+00 2.750E+03 FE-55 8.000E+0B 4.240E+08 1.310E+08 0.000E+00 0.000E+00 2.400E+0B 7.860E+07 FE-59 4.010E+08 6.490E+08 3.230E+08 0.000E+00'O.000E+00 1.880E+08 6.760E>08 CO-57 0.000E+00 2.990E+07 6.040E+07 0.000E+00 0.000E+00 0.000E+00 2.450E+08 CO-58 0.000E+00 6.470E+07 1.980E+08 0.000E+00 0.000E+00 0.000E+00 3.770E+08 CO-60 0.000E+00 3.780E+08 1.120E+09 0.000E+00 0.000E+00 0.000E+00 2.100E+09 NI-63 3.950E+10 2,110E+09 1.340E+09 0.000E+00 0.000E+00 0.000E+00 1.420E+08 NI-65 1.050E+02 9.890E+00 5.770E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 I CU-64 0.000E+00 1.110E+04 6.690E+03 0.000E+00 2.680E+04 0.000E+00 5.200E+05 ZN-65 8.120E+08 2.160E+09 1.350E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 ZN-69 1.510E-05 2.180E-05 2.020E-06 0.000E+00 1.320E-05 0.000E+00 1.380E-03 BR-82 0.000E+00 0.000E+00 2.040E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.550E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ER-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ER-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 4. 52 0E+ 08 2. 78 0E+ 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 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 3.590E+10 0.000E+00 1.030E+09 0.000E+00 0.000E+00 0.000E+00 1.390E+09 SR-90 1.240E+12 0.000E+00 3.150E+11 0.000E+00 0.000E+00 0.000E+00 1.670E+10 SR-91 5,500E+05 0.000E+00 2.080E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+06 SR-92 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 6.170E+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 5.010E+05 0.000E+00 0.000E+00 0.000E+00 2.490E+09 Y-92 1.560E+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 4.4 80E+06 ZR-95 3.900E+06 8.580E+05 7.640E+05 0.000E+00 1.230E+06 0.000E+00 8.950E+08 2R-97 5.640E+02 8.150E+01 4.810E+01 0.000E+00 1.170E+02 0.000E+00 1.230E+07 NB-95 4.100E+05 1.590E+05 1.140E+05 0.000E+00 1.500E+05 0.000E+00 2.950E+0B NB-97 4.900E-06 8.850E-07 4.130E-07 0.000E+00 9.820E-07 0.000E+00 2.730E-01 MO-99 0.000E+00 7.830E+06 1.940E+06 0.000E+00 1.670E+07 0.000E+00 6.480E+06 I TC-99M 4.650E+00 9.120E+00 1.510E+02 0.000E+00 1.330E+02 4.630E+00 5.190E+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 1.550E+07 0.000E+00 5.940E+06 0.000E+00 3.890E+07 0.000E+00 3.990E+08 { RU-105 9.170E+01 0.000E+00 3.330E+01 0.000E+00 8.060E+02 0'000E+00 5.980E+04 RU-106 7.4 5 0E+08 0. 000E+ 00 9. 3 00E+ 07 0. 000E+ 00 1. 010E+09 0. 000E+ 00 1.16 0E+10 { l l e -

Offsite Dose Calculation Manual Pcga 198 of 247 Revision 1, Change O ATTACHMENT 12 VEGETATION DOSE FACTORS CHILD 2 (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 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 3.220E+07 2.170E+07 1.740E+07 0.000E+00 4.050E+07 0.000E+00 2.580E+09 SB-124 3.520E+0B 4.570E+06 1.230E+08 7.780E+05 0.000E+00 1.960E+0B 2.200E+09 SB-125 4.990E+08 3.850E+06 1.050E+08 4.620E+05 0.000E+00 2.780E+0B 1.190E+09 TE-125M 3.510E+08 9.500E+07 4.670E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+0B TE-127M 1.320E+09 3.560E+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 0.000E+00 3.910E+05 TE-129M B.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. 54 0E4 06 5. 3 30E+ 05 5. 6 80E+ 05 1.100E+ 06 5.160E+06 0. 000E+00 2.16 0E+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 3.110E+07 I-130 6.210E+05 1.260E+06 6.470E+05 1.380E+08 1.880E+06 0.000E+00 5.870E+05 4 I-131 1. 4 3 0E+ 08 1.4 4 0E+ 08 0.18 0E+ 07 4. 76 0E+10 2. 36 0E+ 08 0. 000E+00 1. 28 0E+07 I-132 9.200E+01 1.690E+02 7.770E+01 7.840E+03 2.590E+02 0.000E+00 1.990E+02 I-133 3.590E+06 4.440E+06 1.680E+06 8.250E+0B 7.400E+06 0.000E+00 1.790E+06 I-134 1.700E-04 3.160E-04 1.460E-04 7.280E-03 4.840E-04 0.000E+00 2.100E-04 I-135 6.540E+04 1.180E+05 5.570E+04 1.040E+07 1.810E+05 0.000E+00 8.980E+04 CS-134 1.600E+10 2.630E+10 5.540E+09 0.000E+00 8.140E+09 2.920E+09 1.420E+08 CS-136 8. 06 0E+ 07 2. 220E+0B 1.4 3 0E+08 0. 000E+ 00 1.18 0E+ 08 1. 76 0E+07 7. 790E+06 CS-137 2.390E+10 2.290E+10 3.380E+09 0.000E+00 7.460E+09 2.680E+09 1.430E+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 1.480E-03 0.000E+00 2.380E-05 1.610E-05 2.950E+00 BA-140 2.770E+08 2.430E+05 1.620E+07 0.000E+00 7.900E+04 1. 4 50E+ 05 1. 4 00E+ 08 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 3.230E+03 1.130E+03 3.810E+02 0.000E+00 0.000E+00 0.000E+00 3.150E+07-LA-142 2.320E-04 7.400E-05 2.320E-05 0.000E+00 0.000E+00 0.000E+00 1.470E+01 CE-141 6.350E+05 3.260E+05 4.840E+04 0.000E+00 1.430E+05 0.000E+00 4.070E+08 CE-143 1. 73 0E+ 03 9. 36 0E+ 05 1.3 60E+ 02 0.000E+00 3. 93 0E+ 02 0.000E+00 1.370E+ 07 CE-144 1.270E+08 3.980E+07 6.780E+p6 0.000E+00 2.210E+07 0.000E+00 1.040E+10 PR-143 1.480E+05 4.460E+04 7.370E+03 0.000E+00 2.410E+04 0.000E+00 1.600E+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 7.160E+04 5.800E+04 4.490E+03 0.000E+00 3.180E+04 0.000E+00 9.180E+07 W-187 6,470E+04 3.830E+04 1.720E+04 0.000E+00 0.000E+00 0.000E+00 5.380E+06 NP-239 2.550E+03 1.830E+02 1.290E+02 0.000E+00 5.300E+02 0.000E+00 1.360E+07 k n

        -    -          ..       .-    -   .-           .=     .- .      .   .       -          --
                                                                                                      )

i Offsite Dose Calculation Manual .Pege 199 of 247 I Revision 1,3 Change 0 ATTACHMENT 12 k VEGETATION DOSE FACTOR $ i 1 INFANT (m2

mrem /yr per uci/see)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract l l l l 1 1 4 I i l-< 4

Offsite Dose Calculation Manual Page 200 of 247 Revision 1, Change 0 ATTACHMENT 12 l (~ VEGETATION DOSE FACTORS INFANT (m2

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract l l l ot' 1

A 1 l1

Offsite Dose Calculation Manual Page 202 of 247 Revision 1, Change 0 I ATTACHMENT 12 i ( 1 GROUND PLANE DOSE FACTORS l

                                                                                          .l ADULT 2

(m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract

Offsite Dose Calculation Manual Pege 200 of 247 Ravision 1, Change 0

,                                          ATTACHMENT 12

{. VEGETATION DOSE FACTORS INFANT 2 (m

mrem /yr per uCf . c)

Nuclide Bone Liver Tbody . Thyroid Kidney Lung Gitract /. t P e

s Offsite Dose Calculation Manual Page 201 of 247 Revision 1, -Change O . ATTACHMENT 12 [' GROUND PLANE DOSE FACTORS ADULT (m2

mrem /yr per uCi/sec)

Nuclide Bene Liver Tbody Thyroid Kidney Lung Gitract eeo eeee= =maeeeeoeeee oeoeeeoeeoeoeeoeeeeeeee oe. eoeeeeoeeeeeeaeoeeoeeoeeeseee. e I s

Offsite Dose Calculation Manual Page 202'of 247 Revicit'n 1, Chage O ATTACHMENT 12

-(

GROUND PLANE IDSE FACTORS ADULT (m

mrem /yr per uCi/sec)

Nuclide Bone Liver 7 body Thyroid Kidney Lung Gitract t o

Offsite Dose Calculation Manual Page 203 of 247 Revision 1,2 Change O ATTAChiENT 12 > (- GROUND PLANE DOSE FACTORS TEEN 2 (m

mrem /yr per uC1/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 0.000E+00 0.000E+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+ 0 7 1. 210E + 0 7 1. 210E+ 07 1. 210E+ 0 7 1. 210E+ 0 7 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 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9 050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.750E+0B 2.750E+08 2.750E+0B 2.750E+08 2.750E+08 2.750E+0B 2.750E+08 CO-58 3.820E+08 3.820E+08 3.B20E+08 3.820E+0B 3.820E+0B 3.820E+0B 3.820E+0B CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E400 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 g CU-64 6. 090E+05 6. 090E+05 6.090E+05 6. 090E+05 6.090E+05 6.090E+05 6.0903+05

ZN-65 7.4 50E+0B 7.4 50E+08 7.450E+0B 7.450E+0B 7.450E+08 7.4 50E+08 7.450E+08 ZU-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00'O.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 BR-84 2. 030E+ 05 2. 03 0E+05 2.03 0E+05 2. 030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1. 210F+ 0 5 1. 210E+ 0 5 1. 210E+ 05 1. 210E+ 05 1. 210E+ 05 1. 210E+ 05 1. 210E+ 05 '

SR-89 2.160E+04 2.370E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+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 7.770F+05 7.770E+05 7.770E+05 7.??OE+05 Y-90 4.4 0 0E+03 4.4 80E+03 4.480E+03 4.48 0E+03 4.480E+03 4.4 80E+03 4.4 80E+03 Y-91M 1.010E+C's 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.0800+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.0BOE+06 1.080E+06 Y-92 1.800E+05 1.800E+DS 1.800E+05 1.800E+05 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+0B 2.480E+0B 2.480B+0B 2.480E+08 2.4803+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 NB-95 1.360E+0B 1.360E+0B 1.360E+08 1.360E+08 1.360E+08 1.360E+0B 1.360E+0B MO-99 4. 050E+06 4.050E+ 06 4. 050E+ 06 4.050E+06 4.05 0E+06 4. 050E+06 4. 050E+06 - TC-99M 1. 8 3 0E+ 05 1. 03 0E+ 05 1. 8 3 0E+ 05 1. 83 0E+ 05 1. 83 0E+ 05 - 1. 83 0E+ 05 1. 8 3 0E+ 0 5 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 1.090L+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+0B 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+0B 4.210E+08 4.210E+08

RH-103M 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7 . RH-106 0.000E+00 0.00.E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

( AG-110M 3.4 70E+09 3.4 70E+ 09 3.4 70E+ 09 3. 4 70E+09 3.470E+09 3.4 70E+09 3.4 70E+ 09 l

O(fsite Dose Calculation Manual Page 204 of 247 Revision 1, Change O ATTACHMENT 12 k GROUND PLANE DOSE FACTORS TEEN (m2

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE 127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+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 TE-131M B.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 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 4.220E+06 4,220E+06 4.220E+06 4.220E+06 4,220E+06 4.220E+06 4.220E+06 2-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 I-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+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 I-134 4.4 90E+05 4.4 90E+ 05 4.4 90E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 { I-135 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 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1. 4 9 0E+ 0S 1. 4 90E+ 08 1.4 90E+ 08 1. 4 90E+ 08 1. 4 90E+ 08 1. 4 90E+ 08 1.4 90E+ 0 B CS-137 1.040E+10 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 1.060E+05 1.060E+0!. 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.C50E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 EA-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 1.910E+07 1.910E+07 1.910E+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 1.360E+07 1.360E+07 1.360E+07 1.360E407 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 CE-144 6.950E+07 6.950E+07 6.950E,07 6.950E+07 6.950E+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 8.400E+0C 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 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 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 l u

                              ._i.

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Offsite Dose Calculation Manual Page 205 of 247 Revision 1,: Change O ATTACHMENT 12 1 GROUND PLANE DOSE FACTORS CHILD (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract E-3 0.000E+00 0.000E+00 0.000E+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+C0 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 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.750E+08 2.750E+0B 2.750E+08 2.750E+0B 2.750E+0B 2.750E+0B 2.750E+08 CO-5B 3.820E+0B 3.820E+0B 3.820E+08 3.820E+08 3.820E+0B 5.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+0B 7.450E+08 7.450E+0B ZN-69 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 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.980E+06 B.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04-2.160E+04.2.160E+04 2.160E+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 4.4 80E+03 4.4 80E+03 4.4 80E+03 4.480E+03 4.4 80E+03 4.4 80E+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 1.0BOE+06 1.080E+06 1.0BOE+06 1.080E+06 1.0BOE+06 1.080E+06 1.080E+06 Y-92 1. 8 0 0E+ 05 1. 8 0 0E+ 0 5 1. 8 0 0E+ 0 5 1. 8 0 0E + 05 1. 8 0 0E+ 05 1. 8 0 0E+ 05 1. 8 0 0E+ 0 5 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 2.4BOE+0B 2.480E+09 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+0B' ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 -1.360E+08 1.360E+08 1.360E+0B 1.360E+0B 1.360E+0B 1.360E+08 1.360E+0B i MO-99 4.050E+06 4.050E+06 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 1.830Ev05 1.830E+05 1.830E+05 1.830E+05 i TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 1 EU-103 1.090E+0B 1.090E+0B 1.090E+0B 1.090E+08 1.090E+08 1.0$0E+0B 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+0B 4.210E+0B 4.210E+0B 4.210E+0B 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , f RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 l l AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 j l l

+          .-

i Offsite Dose Calculation Manual Pxga 206 of 247 j Revision 1, Change 0 j ATTACHMENT 12 i i( ! GROUND PLANE DOSE FACTORS I CHILD (m

mrem /yr per uCi/sec) t Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E404 9.170E+04 9.170E+04 9.170E+04 i TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 TE-12 9M 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 TE-131M B.030E+06 0.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 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 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E406 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+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 I-134 4.490E+05 4. 4 90E+05 4.4 90E+05 4.4 90E+05 4.4 90E4 05 4.490E+05 4.4 90E+05

( I-135 2.560E+06 2.560E+06 2.560E+06 2.560EA06 2.560E+06 2.560E+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. 4 90E4 08 1.4 90E+ 08 1.4 90E+ 08 1.4 90E+0B 1.4 90E+ 08 1.4 90E+08 1.4 90E+ 0B CS-137 1.040E+10 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 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+0F 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 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.IB0F+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 1.910E+07 1.910E+07 1.910E+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 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 LE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+37 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 1.930E+03 ND-147 8.400E406 B.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+C6 2.360E+06 NP-239 1.-710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1

Offsite Dose Calculation Manuel Paga 207 of 247 Revision 1/ Change O ATTACHMENT 12 1 GROUND PLANE DOSE FACTORS INFANT (m2

mrem /yr per uci/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 P-32 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 CR-51 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MN-54 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06'4.680E+06 4.680E+06 MM-56 1. 3 4 0E+ 0 9 1. 3 4 0E+ 09 1. 3 4 0E+ 09 1. 3 4 0E+ 09 1. 3 4 0E+ 09 1. 3 4 0E+ 0 9 1. 3 4 0E4 09 FE-55 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-59 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CO-58 2.750E+08 2.750E+08 2.750E+08 2.750E+0B 2.750E+08 2.750E+0B 2.750E+08 CO-60 3.820E+08.3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 NI-63 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 2. 970E+05 2.970E+05 2. 970E+05 2.970E+05 2. 970E+05 2. 970E+05 2 970E+05 ( 6.090E+05 6.090E+05 6,090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 2N-69 7.450E+08 7.450E408 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ER-84 4.890E+03 4.090E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-85 2. 03 0E+ 05 2. 03 0E+05 2. 030E+05 2. 030E+05 2. 030E+05 2. 030E+05 2.030E+05 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 RB-88 8.980E+06 8.980E+06 8.980E+06 8.980E406 8.980E+06 8.980E+06 8.980E+06 RB-89 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 SR-89 1. 210E+ 0 5 1. 210E+ 0 5 1. 210E+ 05 1. 210E+ 05 1. 210E+ 0 5 1. 210E+ 0 5 1. 210E+ 05 ' SR-90 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04.2.160E+04 2.160E+04 SR 91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-92 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 i Y-90 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 l Y-91M 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 ' Y-91 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E405 Y-92 1.000E+06 1.000E+06 1.080E+06 1.080E+06 1.080E+06 1.000E+06 1.080E+06 l Y-93 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 ZR-95 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 I ZR-97 2.4 80E+ 08 2 4 80E+ 08 2.4 80E+08 2.4 80E+0B 2.4 80E+08 2.480E+08 2.480E+08 NB-95 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E406 MD-99 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+0B 1.360E+08 4.050E+06 4.050E+06 4.050E+06 4.050E+06.4.050E+06 4.050E+06 4.050E+06 l TC-99M 1.830E+05 1.830E+05 1.630E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 RU-103 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 1.090E+0B 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 RU-106 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 4.210E+ 08 4.210E+08 4.210E+ 08 4.210E+ 08 4.210E+08 4.210E+ 08 4.210E+0B RH-103M RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ' 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 u I

Offsite' Dose Calculation Manual Paga 208 of 247' Revision 1, Change O ATTACHMENT 12

 't GROUND PLANE DOSE FACTORS INFANT (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+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 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 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 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 I-132 1.240E+06 1.240E+06 3.240E+06 1.240E+06 1.240E+06 1.240E+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 I-134 4.490*.+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 { I-135 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 6.750E+09 6.750E+09 6.750E+09 6.750E+09.6.750E+09 6.750E+09 CS-136 1. 4 90E+08 1. 4 90E+08 1.4 90E+0B 1. 4 90E+ 0B 1.4 90E+ 08 1.4 90E+08 1. 4 90E+08 CS-137 1. 04 0E+10 1. 04 0E+10 1. 04 0E+10 1. 04 0E+10 1. 04 0E+10 1. 04 0E+10 1. 04 0E+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 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 4.180E+04 4.180E+04 4.180E+04 4.180E+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 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E405 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 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+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 8.4 00E+06 8.4 00E+06 8.4 00E+06 8.4 00E+ 06 8.400E+06 8.400E+06 8.4 00E+06 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 1.710E+0p 1.710E+06 1.710E+06 1.710E+06 1.710E+06 i l I l i

   - - . -__-e-                     .                        .

Offsite Dose Calculation Manual Page 209 of 247 Revision 1," Change O ATTACHMENT 12 a 1 INHALATION DOSE FACTORS ADULT (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+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 MN-54 0.000E+00 3.960E+04 6.300E+03 0.000E+00 9.840E+03 1.400E+06 7.74DE+04 MN-56 0.000E+00 1.240E+00 1.830E-01 0.000E+00 1.300E+00 9.440E+03 2.020E+04 FE-55 2.460E+04 1.700E+04 3.940E+03 0.000E+00 0.000E+00 7.210E+04 6.030E+03 FE-59 1.180E+04 2.780E+04 1.060E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 CO-57 0.000E+0) 6.920E+02 f.710E+02.0.000E+00 0.000E+00 3.700E+05 3.140E+04 CO-58 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 3.140E+04 1.450E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 ( NI-65 1.540E+00 2.100E-01 9.120E-02 0.000E+00 0.000E+00 5.600E+03 1.230E+04 CU-64 0.000E+00 1.460E+00 6.150E-01 0.000E+00 4.620E+00 6.780E+03 4.900E+04 ZN-65 3.240E+04 1.030E+05 4.660E+04 0.000E+00 6.900E+04 8.640E+05 5.340E+04 ZN-69 3.380E-02 6.510E-02 4.520E-03 0.000E+00 4.220E-02 9.200E+02 1.630E+01 BR-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 2.130E+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 RB-86 0.000E+00 1.350E+05 5.900E+04 0.000E+00 0.000E+00 0.000E+00 1.660E+04 RB-88 0. 000E+00 3. 870E+ 02 1. 93 0E+02 0. 000E+00 0. 000E+00 0. 000E4 00 3.34 0E-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 1.400E+06 3.500E+05 SR-90 9.920E+07 0.000E+00 6.100E+06 0.000E+00 0.000E+00 9.600E+06 7.220E+05 SR-91 6.190E+01 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 1.240g+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+04 7.350E+04 Y-93 .9.440E+01 0.000E+0L 2.610E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05 ZR-95 1.070E+05 3.440E+04 2.330E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 2R 97 9.680E+01 1.960E+01 9.040E+00 0.000E+00 2.970E+01 7.870E+04 5.230E+05 NB-95 1.410E+04 7.820E+03 4.210E+03 0.000E+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. 3 00E+01 0. 000E+ 00 2. 910E+02 9.12 0E+04 2.4 80E+05 TC-99M 1.030E-03 2.910E-03 3.700E-02 0.000E+00 4.420E-02 7.640E+02 4.160E+03 TC-101 4.180E-05 6.020E-05 5.900E-04 0.000E+00 1.080E-03 3.990E+02 0.000E+00 RU-103 1.530E+03 0.000E400 6.500E+02 0.000E+00 5.830E+03 5.050E+05 1.100E+05 RU-105 7.900E-01 0.000E+00 3.110E-01 0.000E+00 1.020E+00 1.200E+04 4.820E+04

( RU-106 6.910E+04 0.000E+00 8.720E+03 0.000E+00 1.340E+05 9.360E+06 9.120E+05 a

Offsite Dose Calculation Manual Page 210 of 247-Revision 1, Change O ATTACHMENT 12 t INHALATION DOSE FACTORS ADULT (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.000E+0 1.000E+04 5.940E+03 0.000E+00 1.970E+04 4.630E+06 3.020E+05 SB-124 3.120E+0* 5.890E+02 1.240E+04 7.550E+01 0.000E+00 2.480E+06 4.060E405 SE-125 5.340E+04 5.950E+02 1.260E+04 5.400E+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 3.140E+05 7.060E+04 TE-127M TE-127 1.260E+04 5.770E+03 1.570E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 1.400E+00 6.420E-01 3.100E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 TE-129M 9.760E+03 4.670E+03 1.580E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 TE-129 4.980E-02 2.390E-02 1.240E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 TE-131M 6.990E+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 1.640E+01 TE-132 2.600E+02 2.150E+02 1.620E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 .( I-130 2-131 4.580E+03 1.340E+04 5.200E+03 1.140E+06 2.090E+04 7.690E+03 0.000E+00 2-132 2.520E+04 3.580E+04 2.050E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 1.160E+03 3.260E+03 1.160E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 2-133 B.640E+03 1.480E+04 4.520E+0'. 2.15CE+06 2.580E+04 0.000E+00 8.880E+03 1-134 6.440E+02 1.730E+03 6.150E+02 2.980E+04 2.750E+03 0.000E+00 1.010E+00 I-135 2.680E+03 6.980E+03 2.570E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 CS-134 3. 73 0E+ 05 8.4 8 0E+ 05 7.2 8 0E+ 05 0. 000E+ 00 2. 870E+ 05 9.76 0E+04 1. 04 0E+04 CS-136 CS-137 3.900E404 1.460E+05 1.100E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04

4. 780E+ 05 6.210E+ 05 4.2 8 0E4 05 0. 000E+ 00 2.220E+05 7. 52 0E+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 BA-140 9.360E-01 6.660E-04 2.740E-02 0.000E+00 6.220E-04 3.760E+03 8.960E+02 EA-141 3.900E+04 4.900E+01 2.570E+03 0.000E+00 1.670E+01 1.270E+06 2.180E+05 BA-142 1.000E-01 7.530E-05 3.360E-03 0.000E+00 7.000E-05 1.940E+03 1.160E-07 LA-140 2.630E-02 2.700E-05 1.660E-03 0.000E+00 2.290E-05 1.190E+03 0.000E+00 LA-142 3.440E+02 1.740E+02 4.580E+01 0.000E+00 0.000E+00 1.360E+05 4.580E+05 CE-141 6.830E-01 3.100E-01 7.720E-02 0.000E+00 0.000E+00 6.330E+03 2.110E+03 CE-143 1.990E+04 1.350E+04 1.530E+03 0.000E+00 6.260E+03 3.620E+05 1.200E+05 1.B60E+02 1.380E+02 1.530E+01 0.000E+00 6.080E+01 7.980E+04 2.,60E+05 CE-144 3.430E+06 1.430E+06 1.840E+05 0.000E+00 8.480E+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 ND-147 3.010E-02 1.250E-02 1.530E-03 0.000E+00 7.050E-03 1.020E+03 2.150E-08 W-187 5.270E+03 6.100E+03 3.650E+02 0.000E+00 3.560E+03 2.210E+05 1.730E+05 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 1.240E+01 0.000E+00 7.000E+01 3.760E+04 1.190E+05 i

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Of f site Dose Ca' ulation Manual Page 211 of 247 Revision 1,. Change O ATTACHMENT 12 ( INHA1.ATION DOSE FACTORS TEEN (mrem /yr per uC1/m3 ) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0. 0 0 0E+ 0 0 1. 2 7 0E+ 03 1. 2 7 0 E + 0 3 1. 2 7 0E+ 03 1. ? ? 0E + 03 1. 2 7 0E+ 03 1. 2 7 0E+ 0 3 C-14 2. 6 00E+ 04 4. 870E+03 4. 870E+ 03 4. 8 70E+ 03 4.870E+03 4. 870E+ 03 4. 8 70E+ 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 7.160E+04 0.000E+00 0.000E+00 0.000E+00 9.280E+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 5.110E+04 8.400E+03 0.000E+00 1.270E+04 1.980E+06 6.680E+04 MN-56 0.000E+00 1.700E+00 2.520E-01 0.000E+00 1.790E+00 1.520E+04 5.740E+04 FE-55 3.340E+04 2.380E+04 5.540E+03 0.000E+00 0.000E+00 1.240E+05 6.390E+03L FE-59 1.590E+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. 92 0E+ 02 9. 200E+02 0. 000E+00 0. 000E+00 5. 86 0E+ 05 3.14 0E+ 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 NI-63 5.800E+05 4.340E+04 1.980E+04 0.000E+00 0.000E+00 3.070E+05 1.420E+04 ( NI-65 2.18 0E+ 00 2. 93 0E-01 1. 270E-01 0. 000E+00 0. 000E+ 00 9. 36 0E+03 . 3. 670E+04 CU-64 0.000E+00 2.030E+00 8.480E-01 0.000E+00 6.410E+00 1.110E+04 6.140E+04 2N-65 3.860E+04 1.340E+05 6.240E+04 0.000E+00 8.640E+04 1.240E+06 4.660E+04 ZN-69 4.830E-02 9.200E-02 6.460E-03 0.000E+00 6.020E-02 1.580E+03 2.850E+02 BR-82 0.000E+00 0.000E+00 1.820E+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 BR-84 0.000E+00 0.000E+00 4.330E+02 0.000E+00 0.000E+00 0.000E+00 0.000E400 BR-85 0.000E+00 0.000E+00 1.830E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0. 000E+ 00 1. 900E+ 05 8.4 00E+ 04 0.000E+00 0.000E+00 0.000E+00 1.770E+04 RB-88 0.000E+00 5.460E+02 2.720E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-05 RB-89 0.000E+00 3.520E+02 2.330E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 SR-89 4.340E+05 0.000E+00 1.250E+04 0.000E+00 0.000E+00 2.420E+06 3.710E+05 SR-90 1.080E+0B 0.000E+00 6.680E+06 0.000E+00 0.000E+00 1.650E+07 7.650E+05 SR-91 8.800E+01 0.000E+00 3.510E+00.0.000E+00 0.000E+00 6.070E+04 2.590E+05. SR-92 9. 52 0E+ 00 0. 000E4 00 4. 060E- 01 0. 000E+00 0.000E+ 00 2.74 0E+04 1.190E+05 Y-90 2.980E+03 0.000E+00 8.000E+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 3.020E+01 Y-91 6.610E405 0.000E+00 1.770E+04 0.000E+00 0.000E+00 2.940E+06 4.090E+05 Y-92 1. 4 70E+ 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 8.320E+04 5.790E+05 ZR-95 1.460E+05 4.580E+04 3.150E+04 0.000E+00 6.740E404 2.690E+06 1.490E+05 ZR-97 NE-95 1.380E+02 2.720E+01 1.260E+01 0.000E+00 4.120E+01 1.300E+05 6.300E+05 1.860E+04 1.030E+04 5.660E+03 0.000E+00 1.000E404 7.510E+05 9.680E+04 NB-97 3.140E-01 7.780E-02 2.840E-02 0.000E+00 9.120E-02 3.930E+03 2.170E+03 MO-99 0.000E+00 1.690E+02 3.220E+01 0.000E+00 4.110E+02 1.540E+05 2.690E+05 TC-99M 1.380E-03 3.860E-03 4.990E-02 0.000E+00 5.760E-02 1;150E+03 6.130E+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 B.960E+02 0.000E+00 7.430E+03 7.830E+05 1.090E+05 7 RU-105 1.120E+00 0.000E+00 4.340E-01 0.000E+00 1.410E+00 1.820E+04 9.040E+04 ( RU-106 9.840E+04 0.000E+00 1.240E+04 0.000E+00 1.900E+05 1.610E+07 9.600E+05

Offsite Dose Calculation Manual Pega 212 of 247 l Ravision 1, Chenge 0 l l l NITACHMENT 12 INHALATION DOSE FACTORS . TI!EN l l 3 (mrem /yr per uCi/m ) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 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 SB-124 1.380E+04 1.310E+04 7.990E+03 0.000E+00 2.500E+04 6.750E+06 2.730E+05 4.300E+04 7.940E+02 1.680E+04 9.760E+01 0.000E+00 3.850E+06 3.980E+05 SB-125 7.380E+04 8.080E+02 1.720E+04 7.040E+01 0.000E+00 2.740E+06 9.920E+04 TE-12 5M 4. 88 0E+ 03 2. 24 0E+ 03 6. 6 70E+02 1. 4 00E+03 0. 000E+00 5. 36 0E+05 7. 500E+ 04 TE-127M 1.800E+04 0.160E+03 2.180E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 TE-127 2.010E+00 9.120E-01 4.420E-01 1.420E+00 .7.200E+00 1.120E+04 8.080E+04 TE-129M 1.390E+04 6.580E+03 2.250E+03 4.580E+03 5.190E+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. 6 00E+ 02 2.900E+02 2.190E+ 02 2.4 6 0E+02 1. 950E+03 4.4 90E+05 4.63 0E+05 1-130 ( 6.240E+03 1.790E+04 7.170E+ 03 1. 4 90E+06 2.750E+ 04 0.000E+00 9.120E+03 I-131 3.540E+04 4.910E+04 2.640E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 I-132 1.590E+03 4.380E+03 1.580E+03 1.510E+05 6.920E+03 0.000E+00 1.270E+03 I-133 I-134 1.220E+04 2.050E+04 6.220E+03 2.920E+06 3.590E+04 0.000E+00 1.030E+04 8.880E+02 2.320E+03 8.400E+02 3.950E+04 3.660E+03 0.000E+00 2.040E+01 2-135 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 1.13 0E+06 5.4 90E+ 05 0. 000E+00 3. 750E+ 05 1.4 60E+05 9. 760E+03

   'CS-136    5.150E+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. 4 8 0E+ 05 3.110E+ 05 0. 000E+ 00 3. 040E+05 1. 210E+05 8.4 80E+ 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 B.880E-04 6.460E+03 6.450E+03 BA-140 5.470E+04 6.700E+01 3.520E+03 0.000E+00 2.280E+01 2.030E+06 2.290E+05 BA-141 1.420E-01 1.060E-04 4.740E-03 0.000E+00 9.840E-05 3.290E+03 7.460E-04 BA-142 3,700E-02 3.700E-05 2.270E-03 0.000E+00 3.140E-05 1.910E+03 0.000E+00 LA-140 4.790E+02 2.360E+02 6.260E+01 0.000E+00 0.000E+00 2.140E+05 4,870E+05 LA-142 9.600E-01 4.250E-01 1.060E-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 8.B80E+03 6.140E+05 1.260E405 CE-143 2.660E402 1.940E+02 2.160E+01 0.000E+00 8.640E+01 1.300E+05 2.550E+05 CE-144 4.890E+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 2.180E-03 0.000E+00 1.010E-02 1.750E+03 2.350E-04 ND-147 7.860E+03 8.560E+03 5.130E+02 0.000E+00 5.020E+03 3.720E+05 1.820E+05 W-167 1. 200E+ 01 9. 76 0E+ 00 3.4 3 0E+ 00 0. 000E+ 00 0. 000E+ 00 4. 74 0E+04 1.770E+05 NP-239 3.380E+02 3.190E+01 1.770E401 0.000E+00 1.000E+02 6.490E+04 1.320E+05 (. l

offsite Doso Calculation Mr.nus1 Pcge 213 of 247 Revision 1,ichange 0

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ATTACHMENT 12 INHALATION DOSE FACTORS I CHILD (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract l H-3 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 P-32 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 CR-51 2.600E+06 1.140E+05 9.880E+04 0.000E+00 0.000E+00 0.000E+00 4.220E+04 MN-54 0.000E+00 0.000E+00 1.540E+02 8.550E+01 2.430E+01 1.700E+04 1.080E+03 MN 0.000E+00 4.290E+04 9.510E+03 0.000E+00 1.000E+04 1.5BCE+06 2.290E+04 FE-55 0.000E+00 1.660E+00 3.120E-01 0.000E+00 1.670E+00 1.310E+04 1.230E+05 FE-59 4.740E+04 2.520E+04 7.770E+03 0.000E+00 0.000E+00 1.110E+05 2.870E+03 CO-57 2.070E+04 3.340E+04 1.670E+J4 0.000E+00 0.000E+00 1.270E+06 7.070E+04 0.000E+00 9.030E+02 1.070E+03 0.000E+00 0.000E+00 5.070E+05 1.320E+04 CO-58 CO-60 0.000E+00 1.770E+03 3.160E+03 0.000E+00 0.000E+00 1.110E+06.3.440E+04 l 0.000E+00 1.310F+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 g NI-65 2.990E+00 2.960E-01 1.640E-01 0.000E+00 0.000E+00 0.180E+03 8.400E+04 CU-64 0.000E+00 1.990E+00 1.070E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 ZN-65 4.260E+04 1.130E+05 7.030E+04 0.000E+00 7.140E+04 9.950E+05 1.630E+04 ZN-69 6.700E-02 9.660E-02 8.920E-03 0.000E+00 5.850E-02 1.420E+03 9.510E+03 BR-82 0.000E+00 0.000E+00 2.090E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 4.740E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+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 RB-86 0.000E+00 0.000E+00 2.530E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-SS 0.000E+00 1.980E+05 1.140E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 RB-89 0.000E+00 5.620E+02 3.660E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.450E+02 2.900E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 SR-89 SR-90 5.990E+05 0.000E+00 1.720E+04 0.000E+00 0.000E+00 2.160E+06 1.670E+05 SR-91 1.010E+08 0.000E+00 6.440E+06 0.000E+00 0.000E+00 1.480E+07 3.430E+05 SR-92 1.210E+02 0.000E+00 4.590E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 1,310E+01 0.000E+00 5.250E-01 0.000E+00 0.000E+00 2.400E+04 2.420E+05 Y-90 Y-91M 4.110E+03 0.000E+00 1.110E+02 0.000E+00 0.000E+00 2.620E+05 2.680E+05 Y-91 5.070E-01 0.000E+00 1.040E-02 0.000E+00 0.000E+00 2.810E+03 1.720E+03 Y-92 9.140E+05 0.000E+00 2.440E+04 0.000E+00 0.000E+00 2.630E+06 1.840E+05 Y-93 2.040E+01 0.000E+00 5.810E-01 0.000E+00 0.000E+00 2.390E+04 2.390E+05 ZR-95 1.060E+02 0.000E+00 5.110E+00 0.000E+00 0.000E+00 7.440E+04 3.890E+05 1.900E+05 4.180E+04 3.700E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 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 NB-97 2.350E+04 9.180E+03 6.550E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04. MO-99 4.290E-01 7.700E-02 3.600E-02 0.000E+00 B.550E-02 3.420E+03 2.780E+04 0.000E+00 1.720E+02 4.260E+01 0.000E+00 3.920E+02 1.350E+05 1.270E+05 TC-99M 1.7BOE-03 3.460E-03 5.770E-02 0.000E+00 5.070E-02 9.510E+02 4.810E+03 TC-101 8.100E-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 4.400E404 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 1

W;t.4 . . . . n d.- :N.d di __. ._ _; , l 1 Offsite Dose Calculation Manual Pega 214 of 247 Revision 1, Change O ATI ACHMENT 12 ( INHALATION DOSE FACTORS CHILD (mrem /yr per uCi/m3) nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000Ev00 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 1.690E+04 1.140E+04 9.140E+03 0.000E+00 2.120E+04 5.480E+06 1.000E+05 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 9.100E+01 0.000E+00 2.320E+06 4.030E+04 TE-125M 6.730E+03 2.330E+03 9.140E+02 1.920E+03 0.000E+00 4.770E+05 3.380E+04 TE-127M 2.490E+04 8.550E+03 3.020E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 < TE-127 2.770E+00 9.510E-01 6.110E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 I 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-131M 1.340E+02 5.920E+01 5.070E+01 9.770E+01 4.000E+02 2.050E+05 3.080E+05 TE-131 2.170E-02 8.440E-03 6.590E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 TE-132 4.810E+02 2.720E+02 2.630E+02 3.170E+02 1.840E+03 3.770E+05 1.380E+05 ( I-130 8.180E+03 1.640E+04 8.440E+03 1.850E+06 2.450E+04 0.000E+00 5.110E+03 I-131 4.810E+04 4.810E+04 2.730E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 I-132 2.12 0E+ 03 4. 070E+ 03 1. 8 8 0E+03 1. 94 0E+ 05 6. 250E+03 0. 000E+ 00 3.200E+03 I-133 1.660E+04 2.030E+04 7.700E+03 3.850E+06 3.380E+04 0.000E+00 5.4 80E+03

 ,       I-134     1.170E+03 2.160E+03 9.950E+02 5.070E+04 3.300E+03 0.000E+00 9.550E+02 I-135     4.920E+03 8.730E+03 4.140E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 CS-134    6. 510E+ 05 1. 010E+ 06 2.2 50E+05 0. 000E+00 3.3 00E+05 1.210E+05 3. 850E+03 CS-136    6.510E+04 1.710E+05 1.160E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 CS-137    9. 070E+ 05 8. 2 50E+ 05 1.28 0E+ 05 0. 000E+ 00 2.82 0E+ 05 1.04 0E+05 3.620E+03 CS-138    6.330E+02 8.400E+02 5.55cE+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 BA-139    1.840E+00 9.840E-04 5.370E-02 0.000E+00 8.620E-04 5.770E+03 5.770E+04 BA-140    7.400E+04 6.4POE+01 4.330E+03 0.000E+00 2.110E+01 1.740E+06 1.020E+05 BA-141    1.960E-01 1.090E-04 6.360E-03 0.000E+00 9.470E-05 2.920E+03 2.750E+02 BA-142    5.000E-02 3.600E-05 2.790E-03 0.000E+00 2.910E-05 1.640E+03 2.740E+00 LA-140    6.440E+02 2.250E+02 7.550E+01 0.000E+00 0.000E+00 1.630E+05 2.260E+05 LA-142    1.300E+00 4.110E-01 1.290E-01 0.000E+00_0.000E+00 B.700E+03 7.590E+04 CE-141    3.920E+04 1.950E+04 2.900E+03 0.000E+00 8.550E+03 5.440E+05 5.660E+04 CE-143    3. 6 6 0E+ 02 1. 9 9 0E+ 02 2. 8 7 0E+01 0. 0 00E+ 00 B . 3 6 0E+ 01 1.15 0E+05 1. 27 0E+ 05 CE-144    6.770E+06 2.120E+06 3.610E+05 0.000E+00 1.170E+06 1.200E+07 3.890E+05 PR-143    1.850E+04 5.550E+03 9.140E+02 0.000E+00 3.000E+03 4.330E+05 9.730E+04 PR-144    5.960E-02 1.850E-02 3.000E-03 0.000E+00 0.770E-03 1.570E+03 1.970E+02 ND-147    1.080E+04 8. 73 0E+ 03 6. 810E+ 02 0. 000E+ 00 4. 810E+ 03 3.280E+05 8.210E+04 W-187     1.630E+01 9.660E+00 4.330E+00 0.000E+00 0.000E+00 4.110E+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

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 'd INHALATION DOSE FACTORS INFANT (mrem /yr per uCi/m3)

Nuolide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 C-14 0.000E+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 2.650E+04 5.310E,03 5.310E403 5.310E+03 5.310E+03 5.310E+03 5.310E+03 NA-24 1.060E+04 1,060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 P-32 CR-51 2.030E+06 1.120E+05 7.740E+04 0.000E+00 0.000E+00 0.000E+00 1.610E+04 MN-54 0.000E+00 0.000E+00 8.950E+01 5.750E+01 1.320E+01 1.280E+04 3.570E+02 MN-56 0.000E+00 2.530E+04 4.980E+03 0.000E+00 4.980E+03 1.000E+06 7.060E+03 FE-55 0.000E+00 1.540E+00 2.210E-01 0.000E+00 1.100E+00 1.250E+04 7.170E+04 1.970E+04 1.170E+04 3.330E+03 0.000E+00 0.000E+00 8.690E+04 2.090E+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 6.510E+02 6.410E+02 0.000E+00 0.000E+00 3.790E+05 4.860E+03 CO-58 0.000E+00 1.220E+03 1.820E+03 0.000E+00 0.000E400 7.770E+05 1.110E+04 CO-60 0.000E+00 8.020E+03 1.180E+04 0.000E+00 0.000E+00 4.510E+06 3.190E+04 NI-63 3.390E+05 2.040E+04 1.160E+04 0.000E+00 0,000E+00 2.090E+05 2.420E+03 i NI-65 2.390E+00 2.840E-01 1.230E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 CU-64 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. 02 0E-02 1.4 70E+ 03 1. 32 0E+ 04 BR-82 0.000E+00 0.000E+00 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00-BR-83 0.000E+00 0.000E+00 3.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 4.000E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 2.040E+01 0.000E+00 0.000E+00 0.000E+00 0.000E400 RB-86 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 3.390E+02 RB-89 0.000E+00 3.210E+02 2.060E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 SR-89 3.980E+05 0.000E+00 1.140E+04 0.000E+00 0.000E+00 2.030E406 6.400E+04 SR-90 4.090E+07 0.000E+00 2.590E+06 0.000E+00 0.000E+00 1.120E+07 1.310E+05 SR-91 9.560E+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-01 0.000E+00 0.000E+00 2.380E+04 1.400E+05 Y-90 3.290E+03 0.000E+00 8.820E+01 0.000E+C3 0.000E+00 2.690E+05 1.040E+05 Y-91M 4.070E-01 0.000E+00 1.390E-02 0.000E+00 0.000E+00 2.790E+03 2.350E+03 Y-91 5.880E+05 0.0001.+00 1.570E+04 0.000E+00 0.000E+00 2.450E+06 7.030E+04 Y-92 1.640E+01 0.000E+00 4.610Ew01 0.000E+00 0.000E+00 2.450E+04 1.270E+05 1 1 Y-93 1. 500E+ 02 0. 000E4 00 4. 070E+00 0.000E+ 00 0. 000E+ 00 7.64 0E+ 04 1. 670E+05 ZR-95 1.150E+05 2.790E+04 2.030E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 ZR-97 1.500E402 2.560E+01 1.170E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 NB-95 1.570E+04 6.43 0E+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 l 0.000E+00 1.6s0E+02 3.230E+01 0.000E+00 2.650E+02 1.350E405 4.870E+04 1 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 RU-105 1.220E+00 0.000E+00 4.100E-01 0.000E+00 8.990E-01 1.570E+04 4.840E+04 g RU-106 8.680E+04 0.000E+00 1.090E+04 0.000E+00 1.070E+05 1.160E+07 1.640E+05 2

Offsite Dose-Calculation Manual 'Page 216 of 240 I Revision 1, Change o I

                                                                                                         .1 ATTACHMENT 12 k

INHALATION DOSE FACTORS INFANT (mrem /yr per uti/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 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 SB-124 9.980E+03 7.220E+03 5.000E+03 0.000E+00 1.090E+04 3.670E+06 3.300E+04 SB-125 3.790E+04 5.560E+02 1.200E+04 1.010E+02 0.000E+00 2.650E+06 5.910E+04 5.170E+04 4.770E+02 1.090E+04 6.230E+01 0.000E+00 1.640E+06 1.470E+04 TE-125M 4.760E+03 1.990E+03 6.580E+02 1.620E+03 0.000E+00 4.470E+05 1.290E+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+0D 9,530E-01 4.890E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 TE-129M 1.410E+04 6.090E403 2.230E+03 5.470E+03 3.180E+04 1,680E+06 6.900E+04 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 TE-131 1.070E+02 5.500E+01 3.630E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 1.740E-02 8.220E-03 5.000E-03 1.580E-02 3.990E-02 2.060E403 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 { I-130 1-131 6.360E+03 1.390E+04 5.570E+03 1.600E+06 1.530E+04 0.000E+00 1.990E+03 1-132 3.790E+04 4.440E+04 1.960E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 I-133 1.690E+03 3.540E+03 1.260E+03 1.690E+05 3.950E+03 0.000E+00 1.900E+03 I-134 1.320E+04 1.920E+04 5.600E+03 3.560E+06 2.240E+04 0.000E+00 2.160E+03 1-135 9.210E402 1.880E+03 6.650E+02 4.450E+04 2.090E+03 0.000E+00 1.290E+03 CS-134 3.860E+03 7.600E+03 2.770E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 CS-136 3.960E+05 7.030E405 7.450E+04 0.000E+00 1.900E+05 7.970E+04 1.330E+03 CS-137 4.830E+04 1.350E+05 5.290E+04 0.000E+00 5.640E+04 1.180E+04 1.430E+03 CS-138 5.490E+05 6.120E+05 4.550E+04 0.000E+00 1.720E405 7.130E+04 1.330E+03 BA-139 5.050E+02 7.810E+02 3.980E+02 0.000E+00 4.100E+02 6.540E+01 8.760E+02 BA-140 1.480E+00 9.840E-04 4.300E-02 0.000E+00 5.920E-04 5.950E+03 5 100E+04 BA-141 5.600E+04 5.600E+01 2.900E+03 0.000E+00 1.340E+01 1.600E+06 3.840E+04 BA-142 1.570E-01 1.080E-04 4.970E-03 0.000E+00 6.500E-05 2.970E+03 4.750E+03 3.980E-02 3.300E-05 1.960E-03 0.000E+00 1.900E-05 1.550E+03 6.930E+02 LA-140 LA-142 5.050E+02 2.000E+02 5.250E+01 0.000E+00 0.000E+00 1.680E+05 8.480E+04 CE-141 1.030E+00 3.770E-01 9.040E-02 0.000E+00 0.000E+00 8.220E+03 5.950E+04 CE-143 2.770E+04 1.670E+04 1.990E+03 0.000E+00 5.250E+03 5.170E+05 2.160E+04 CE-144 2.930E+02 1.930E+02 2.210E+01 0.000E+00 5.640E+01 1.160E+05 4.970E+04 PR-143 3.190E+06 1.210E+06 1.760E+05 0.000E+00 5.380E+05 9.840E+06 1.480E405 PR-144 1.400E+04 5.240E+03 6.990E+02 0.000E+00 1.970E+03 4.330E+05 3.720E+04 ND-147 4.790E-02 1.850E-02 2.410E-03 0.000E+00 6.720E-03 1.610E+03 4.280E+03 W-187 7. 94 0E4 03 8.13 0E+03 5. 000E+ 02 0. 000E+00 3.150E+ 03 3.22 0E+05 3.120E+04 1.300E+01 9.020E+00 3.120E+00 0.000E+00 0.000E+00 3.960E+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 \ j 4 a

                                                                                                     .0_  l

Offsite Dose Calculation Manual Pigs 217 of 247 Revision 1,' Change O 5 ATTACHMENT 12 GRASS-COW-MILK DOSE FACTORS ADULT (m

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid T.idney Lung Gitract E-3 C-14 0.000E+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02-NA-24 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 P-32 CR-51 1.710E+10 1.060E+09 6.600E+08 0.000E+00 0.000E+00 0.000E+00 1.920E+09 0.000E+00 0.000E+00 2.860E+04 ' .710E+04 6.300E+03 3.800E+04 7.200E+06 MN-54 MN-56 0.000E+00 8.400E+06 1.600E+06 0.000E+00 2.500E+06 0.000E+00 2.570E+07 FE-55 0.000E+00 4.230E-03 7.510E-04 0.000E+00 5.380E-03 0.000E+00 1.350E-01 FE-59 2.510E+07 1.730E+07 4.040E+06 0.000E+00 0.000E+00 9.670E+06 9.950E+06 CO-57 2.980E+07 7.000E+07 2.680E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 CO-58 0.000E+00 1.280E+06 2.130E+06 0.000E+00 0.000E+00 0.000E+00 3.250E+07 CO-60 0.000E+00 4.720E+06 1.060E+07 0.000E+00 0.000E+00 0.000E+00 9.570E+07

0. 000E+ 00 1.64 0E+ 07 3.620E+ 07 0.000E+00 0. 000E+ 0 0 0. 000E+00 3.08 0E+ 0B NI-63 6.730E+09 4.660E+08 2.260E+08 0.000E+00 0.000E+00 0.000E+00 9.730E+07

( NI-65 3.700E-01 4.810E-02 2.190E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 CU-64 ZN-65 0.000E+00 2.410E+04 1.130E+04 0.000E+00 6.080Ee04 0.000t+00 2.050E+06 ZN-69 1.370E+09 4.360E+09 1.970E409 0.000E+00 2.920E+09 0.000E+00 2.750E+09 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 O.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-86 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-88 0.000E+00 2.590E+09 1.210E+09 0.000E+00 0.000E+00 0.000E400 5.110E+08 RS-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-90 1. 4 50E+ 09 0. 000E+ 00 4.16 0E+ 07 0.000E+00 0.000E+00 0.000E+00 2.330E+08 SR-91 4.680E+10 3.130E+04 0.000E+00 1.150E+10 0.000E+00 0.000E+00 0.000E+00 1.350E+09 SR-92 0. 000E+ 00 1.270E+ 03 0. 000E+00 0. 000E+00 0. 000E+00 1.4 90E+05 Y-90 4.890E-01 0.000E+00 2.110E-02 0.000E+00 0.000E+00 0.000E+00 9.680E+00 Y-91M 7.070E+01 0.000E+00 1.900E+00 0.000E+00 0.000E+00 0.000E+00 7.!00E+05 Y-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 8.600E+03 0.000E+00 2.300E+02 0.000E+00 0.000E+00 0.000E+00 4.730E+06 Y-93 5.420E-05 0.000E+00 1.580E-06 0.000E+00 0.000E+00 0.000E+00 9.490E-01 ZR-95 2.330E-01 0.000E+00 6.430E-03 0.000E+00 0.000E+00 0.000E+00 7.390E+03 ZR-97 9.4 60E+ 02 3. 03 0E+02 2. 050E+ 02 0. 000E+00 4.760E+02 0. 000E+ 00 9.62 0E+ 05 NB-95 4.260E-01 8.590E-02 3.930E-02 0.000E+00 1.300E-01 0.000E+00 2.660E+04 NB-97 8.250E+04 4.590E+04 2.470E+04 0.000E+00 4.540E+04 0.000E+00 2.790E+08 MO-99 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-09 TC-99M 0.000E+00 2.520E+07 4.800E+06 0.000E+00 5.720E+07 0.000E+00 5.850E+07 i TC-101 3.2 50E+ 00 9.190E+00 1.170E+ 02 0. 000E+00 1.4 00E+ 02 4.500E+00 5.44 0E+03 RU-103 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

1. 02 0E+ 03 0. 000E+ 00 4.390E+ 02 0. 000E+00 3. 890E+ 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

( RU-106 2.040E+04 0. 000E+00 2. 5 8 0E+ 03 0. 000E+ 00 3. 49' 0E+04 0.000E+00 1.320E+06

l Offsite Dose Calculation Manual Paga 218 of 247 Revision 1, Change D. l ATTACHMENT 12 1 GRASS-COW-MILK DOSE FACTORS ADULT (m2

mrem /yr per uti/see)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00-AG-110M 5.830E+07 5.390E+07 3.200E+07 0.000E+00 1.060E+0B 0.000E+00 2.200E+10 SB-124 8. 560E+ 08 1. 620E+07 3.4 00E+ 08 2. 080E+06 0. 000E+00 6. 680E+08 2.44 0E+10 SB-125 6.810E+08 7.610E+06 1.620E+08 6.930E+05 0.000E+00 5.250E+08 7.500E+09 TE-125M 1.630E+07 5.900E+06 2.180E+06 4.900E+06 6.630E+07 0.000E+00 6.500E+07 TE-127M 4.500E+07 1.640E+07 5.5BCE+06 1.170E+07 1.860E+08 0.000E+00 1.540E+0B TE-127 6.720E+02 2.410E+02 1.450E+02 4.980E+02 2.740E+03 0.000E+00 5.300E+04 TE-129M 6.040E+07 2.250E+07 9.570E+06 2.0BOE+07 2.520E+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+00 0.000E+00 TE-131M 3.610E+05 1.770E+05 1.470E+05 2.800E+05 1.790E+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 TE-132 2.390E+06 1.550E+06 1.450E+06 1.710E+06 1.490E+07 0.000E+00 7.320E+07 I I-130 4.260E+05 1.260E+06 4.960E+05 1.070E+08 1.960E+06 0.000E+00 1.080E+06 I-131 2.960E+0S 4.240E+08 2.430E+0B 1.390E+11 7.270E+08 0.000E+00 1.120E+08 I-132 1.640E-01 4.370E-01 1.530E-01 1.530E+01 6.970E-01 0.000E+00 8.220E-02 I-133 3.970E+06 6.900E+06 2.100E+06 1.010E+09 1.200E+07 0.000E+00 6.200E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 1.390E+04 3.630E+04 1.340E+04 2.400E+06 5.830E+04 0.000E+00 4.100E+04 CS-134 5.650E+09 1.340E+10 1.100E+10 0.000E+00 4.350E+09 1.440E+09 2.350E+0B 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 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 4.700E-08 0.000E+00 1.380E-09 0.000E+00 0.000E+00 0.000E+00 8.340E-08 BA-140 2.690E+07 3.380E+04 1.760E+06 0.000E+00 1.250E+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 0.000E400 0.000E+00 0.000Eo00 0.000E400 0.000E+00 0.000E+00 LA-140 4.490E+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 4.840E+03 3.270E+03 3.710E+02 0.000E+00 1.520E+03 0.000E+00 1.250E+07 CE-143 4.190E+01 3.090E+04 3.420E+00 0.000E+00 1.360E+01 0.000E+00 1.160E+06 CE-144 3.580E+05 1.500E405 3.920E+04 0.000E+00 B.870E+04 0.000E+00 1.210E+08 PR-143 1.590E+02 6.370E+01 7.880E+00 0.000E+00 3.600E+01 0.000E+00 6.960E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0D 0.000E+00 ND-147 9.420E+01 1.090E+02 6.520E+00 0.000E+00 6.370E+01 0.000E+00 5.230E+05

 'A-187    6.560E+03 5.480E+03 1.920E+03 0.000E+00 0.000E+00 0.000E+00 1.800E+06 NP-239 3.660E+00 3.600E-01 1.980E-01 0.000E+00 1.120E+00 0.000E+00 7.390E+04

Offsite Dose Calculation Manual Page 219 of 247 ] Revision 1,' Change O ATTACHMENT 12 k i GRASS-COW-MILK DOSE FACTORS TEEN (m

mrem /yr per uCi/sec)

Nuclide Bone Liver 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 9'940E+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 4.440E+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 MN-54 0. 000E+00 1.4 00E+ 07 2.780E+ 06 0. 000E+00 4.170E+06 0. 000E+00 2. 870E+07 MN-56 0.000E+00 7.510E-03 1.330E-03 0.000E+00 9.500E-03 0.000E+00 4.940E-01 FE-55 4.450E+07 3.16CE+07 7.360E+06 0.000E+00 0.000E+00 2.000E+07 1.370E+07 FE-59 5.200E+07 1.210E+0B 4.680E+07 0.000E+00 0.000E+00 3.820E+07 2.870E+0B CO-57 0.000E+00 2.250E+06 3.760E+06 0.000E+00 0.000E+00 0.000E+00 4.190E+07 CO-58 0.000E+00 7.950E+06 1.C~;s+07 0.000E+00 0.000E+00 0.000E+00 1.100E+0B CO-60 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 B.350E+08 4.010E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+0B NI-65 6.780E-01 8.660E-02 3.940E-02 0.000E+00 0.000E+00 0.000E+00 4.700E+00 CU-64 0. 000E+ 00 4.290E+04 2.020E+04 0.000E+00 1.090E+05 0.000E+00 3.330E+06 ZN-65 2.110E+ 09 7.310E+09 3.410E+ 09 0. 000E+00 4. 6 8 0E+ 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 BR-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 4. 73 0E+09 2.220E+09 0.000E+00 0.000E+ 00 0.000E+00 7. 000E+0B 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 2.670E+09 0.000E+00 7.660E+07 0.000E+00 0.000E+00 0.000E+00 3.180E+0B SR-90 6.610E+10 0.000E+00 1.630E410 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 l SR-92 8. 950E-01 0. 000E+ 00 3. 810E-02 0. 000E+ 00 0. 000E+ 00 0. 000E+ 00 2.2 8 0E+ 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 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 ! ZR-95 1.650E+03 5.220E+02 3.590E+02 0.000E+00 7.670E+02 0.000E+00 1.200E+06 { ZR-97 7.750E-01 1.530E-01 7.060E-02 0.000E+00 2.320E-01 0.000E+00 4.150E+04 1 NB-95 1.410E+05 7.800E+04 4.300E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+08 l NS-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.340E-08 MO-99 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 8.730E+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+00 6.080E-04 0.000E+00 1.970E-02 0.000E+00 1.260E+00 RU-106 3.750E+04 0.000E+00 4.730E+03 0.000E+00 7.230E+04 0.000E+00 1.800E+06

                                                                                                 .       I

Offsite Dose Calculation Manual Pege 220 of 247 Revision 1, Change O v ATTACHMENT 12 ( t GRASS-COW-MILK DOSE FACTORS TEEN (m2

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Eidney Lung Gitract I RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RE-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 9.630E+07 9.110E+07 5.540E+07 0.000E+00 1.740E+08 0.000E+00 2.560E+10 SB-124 1.530E+09 2.820E+07 5.970E+08 3.470E+06 0.000E+00 1.340E+09 3.080E+10 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+0D 0.000E+00 8.860E+07 TE-127M 8.440E+07 2.990E+07 1.000E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 TE-127 1.240E+03 4.410E+02 2.680E+02 8.590E+02 5.040E+03 0.000E+00 9.610E+04 TE-12 9M 1.110E+ 0 8 4.100E+07 1.75 0E+ 07 3. 57 0E+07 4.620E+08 0. 000E+00 4.150E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E400 1.670E-09 0.000E+00 2.180E-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 4.280E406 2.710E+06 2.550E+06 2.860E+06 2.600E+07 0.000E+00 B.580E+07 ( I-130 7.490E+05 2.170E+06 8.660E+05 1.770E+08 3.340E+06 0.000E+00 1.670E+06 I-131 5.380E408 7.530E+0B 4.040E+08 2.200E+11 1.300E+09 0.000E+00 1.490E+08 I-132 2.900E-01 7.590E-01 2.720E-01 2.560E+01 1.200E+00 0.000E+00 3.310E-01 I-133 -7.240E+06 1.230E+07 3.750E+06 1.720E+09 2.150E+07 0.000E+00 9.300E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00-0.000E+00-0.000E+00 I-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.B10E409 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 CS-137 1.340E410 1.700E+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-08 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+0? 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 8.060E+00 3.960E+00 1.050E+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 j CE-144 6.580E+05 2.720E405 3.540E+04 0.000E+00 1.630E+05 0.000E+00.1.660E+08 i 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 W-187 1.200E404 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 f I l.

1 Offsite Dose Calculation Manual page 221 of 247 ! Revision 1,' Change 0 l I ATTACHMENT 12 i l i l GRASS-COW-MILK DOSE FACTORS CHI 1J) (m2

mrem /yr per uCi/sec) 1 Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract )

f. H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 i C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 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 0.000E+00 0.000E+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 2.090E+07 5.580E+06 0.000E+00 5.870E+06 0.000E+00 1.760E+07 MN-56 0.000E+00 1.310E-02 2.950E-03 0.000E+00 1.500E-02 0.000E+00 1.900E+00 FE-55 1.120E+08 5.930E+07 1.840E+07 0.000E 00 0.000E+00 3.350E+07 1.100E+07 FE-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+00 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 CO-60 0.000E+00 4.320E+07 1.270E+08 0.000E+00 0.000E+00 0.000E+00 2.390E+08 NI-63 2.960E+10 1.590E+09 1.010E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 1.660E+00 1.560E-01 9.110E-02 0.000E+00 0.000E+00 0.000E+00 1.910E+01 CU-64 0.000E+00 7 550E+04 4.560E+04 0.000E+00 1.820E+05 0.000E+00 3.540E+06. ZN-65 4.130E+09 1.100E+10 6.850E+09 0.000E+00 6.940E+09 0.000E+00 1,930E+09 EN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.140E-09 - 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 BR-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 8.770E+09 5.390E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+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-39 6.620E+09 0.000E+00 1.890E+08 0.000E+00 0.000E400 0.000E+00 2.560E+0B SR-90 1.120E+11 0.000E+00 2.830E+10 0.000E+00 0.000E+0D 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 8.760E-02 0.000E+00 0.000E+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 0,000E+00 0.000E400 0.000E+00 0.000E+00 Y-91 3.910E+04 0.000E+00 1.040E+03 0.000E+00 0.000E+00 0.000E+00 5.210E+06 Y-92 2.460E-04 0.000E+ 0 0 7. 03 0EL OG 0. 000E+00 0. 000E+00 0. 000E+ 00 7.100E+ 00 Y-93 1.060E+00 0.000E+00 2.900E-02 0.000E+00 0.000E+00 0.000E+00 1.570E+04 ER-95 3.840E+03 8.450E+02 7.520E+02 0.000E+00 1.210E+03 0.000E+00 B.810E+05 2R-97 1.890E+00 2.720E-01 1.610E-01 0.000E+00 3.910E-01 0.000E+00 4.130E+04 NB-95 3.180E+05 1.240E+05 8.840E+04 0.000E+00 1.160E+05 0.000E+00 2.290E+08 NE-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E-06 MD-99 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 i TC-101 0.000E+00 0.000E+00 0.000E400 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 EU-105 3.820E-03 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 1.4 4 0E+06 i

Offsite Dose Calculation Manual Page 222 of 247 Revision 1, Change O ATTACHMENT 12 I GRASS-COW-MILK DOSE FACTORS CHILD 2 (m

mrem /yr per uCi/sec)

Nuclide Bone Livar Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00 AG-110M SB-124 2. 09 0E+ 08 1. 410E+08 1.13 0E+08 0. 000E+00 2. 63 0E+08 0. 000E+00 1.6 8 0E+10 SB-125 3.620E+09 4.700E+07 1.270E+09 7.990E+06 0.000E+00 2.010E+09 2.260E+10 2.900E+09 2.240E+07 6.080E+08 2.690E+06 0.000E+00 1.620E+09 6.930E+09 TE-125M 7.380E+07 2.000E+07 9. 84 0E+06 2. 070E+07 0. 000E+00 0. 000E+00 7.120E+07 TE-127M TE-127 2. 08 0E+ 08 5. 6 00E+ 07 2.4 70E+07 4. 970E+ 07 5. 93 0E+08 0. 000E+00 1.68 0E+0B

3. 06 0E+ 03 8.250E+ 02 6. 56 0E+02 2.12 0E+03 8.710E+03 0.000E+00 1.200E+05 TE-129 2.720E+08 7.610E+07 4.230E+07 8.780E+07 8.000E+08 0.000E+00 3.320E+08 TE-129M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.870E-09 0.000E+00 6.120E-08 TE-131 1.600E+06 5.530E+05 5.890E+05 1.140E+06 5.35CE+06 0.000E+00 2.240E+07 TE-131M TE-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 g I-130 1.020E+07 4.520E+06 5.460E+06 6.580E+06 4.200E+07 0.000E+00 4.550E+07 I-131 1.750E+06 3.540E+06 1.820E+06 3.900E+08 5.290E+06 0.000E+00 1.660E+06 I-132 1.300E+09 1.310E+09 7.460E+08 4.340E+11 2.150E+09 0.000E+00 1.170E+08 I-133 6. 8 6 0E-01 1.26 0E+ 00 5. 800E-01 5. 8 50E+01 1. 93 0E+ 00 0. 000E+00 1.4 80E+00 I-134 1.760E+07 2.180E+07 8.230E+06 4.040E+09 3.630E+07 0.000E+00 8.770E+06 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 5.840E+04 1.050E+05 4.970E404 9.300E+06 1.610E+05 0.000E+00 8.000E+04 CS-136 2. 2 6 0E+10 3. 710E+10 7. 8 3 0E+09 0. 000E+00 1.150E+10 4.13 0E+09 2.000E+08 CS-137 1. 000E+09 2.76 0E+ 09 1. 790E+ 09 0. 000E+ 00 1.4 70E+ 09 2.190E+ 08 9.700E+07 CS-138 3.220E+10 3.090E+10 4.550E+09 0.000E+00 1.010E+10 3.620E+09 1.930E+08

0. 0 00E+ 00 0. 000E+00 0. 000E+ 00 0. 000E+00 0. 000E+ 00 0. 000E+00 0.000E+00 BA-139 BA-140 2 140E-07 0.000E+00 6.190E-09 0.000E+00 0.000E+00 0.000E+00 1.230E-05 EA-141 1.170E+08 1.030E+0h 6.840E+06 0.000E+00 3.340E+04 6.120E+04 5.940E+07 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-142 1.930E+01 6.740E+00 2.270E+00 0.000E+00 0.000E400 0.000E+00 1.880E+05 CE-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.510E-06 CE-143 2.190E+04 1.090E+04 1.620E+03 0.000E+00 4.780E+03 0.000E+00 1.360E+07 CE-144 1. 8 90E+02 1. 02 0E+ 05 1.4 8 0E+ 01 0. 000E+ 00 4.290E+01 0. 000E+00 1.500E+06 :

PR-143 1.620E+06 5.090E+05 8.660E+04 0.000E+00 2.820E+05 0.000E+00 1.330E+08 PR-144 7.230E+02 2.170E+02 3.590E+01 0.000E+00 1.170E+02 0.000E+00 7.800E+05 ND-147 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 W-187 4.450E+02 3.600E+02 2.790E+01 0.000E+00 1.980E+02 0.000E+00 5.710E+05 NP-239 2.910E+04 1.720E+04 7.730E+03 0.000E400 0.000E+00 0.000E+00 2.420E+06 1.12 0E+ 01 1.230E+ 00 9. 6 80E-01 0. 000E+ 00 3. 570E+00 0. 000E+ 00 9.14 0E+04 (

    'Offsite Dose Calculation Manual                                         Pega 223 of-247 Revision 1, Change O ATTACHMENT 12 4

GRASS-COW-MILK DOSE FACTORS INFANT (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver 7 body Thyroid Kidney Lung Gitract H-3 0.000E+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 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 P-32 1.600E411 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 FE-55 1.350E+08 8.720E+07 2.330E+07 0.000E+00 0.000E+00 4.270E+07 1.110E+07 FE-59 2.250E+08 3.930E+08 1.550E+08 0.000E+00 0.000E+00 1.160E+09 1.880E+08 CO-57 0.000E+00 8.950E+06 1.460E+07 0.000E+00 0.000E+00 0.000E+00 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 CO-60 0.000E+00 8.810E+07 2.0BOE+08 0.000E+00 0.000E+00 0.000E+00 2.100E+08 NI-63 3.490E+10 2.160E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+0B

f. N1-65 3.510E+00 3.970E-01 l'.810E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 CU-64 0.000E+00 1.880E+05 8.690E+04 0.000E+00 3.170E+05 0.000E+00 3.850E+06 ZN-65 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 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 BR-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 2.220E+10 1.100E+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 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 1.260E+10 0.000E+00 3.610E+0B 0.000E+00 0.000E+00 0.000E+00 2.590E+08 SR-90 1.220E+11 0.000E+00 3.100E+10 0.000E+00 0.000E+00 0.000E+00 1.520E+09 SR-91 2.940E+05 0.000E400 1.060E+04 0.000E+00 0.000E+00 0.000E+00 3.480E+05 SR-92 4.650E+00 0.000E+00 1.730E-01 0.000E+00 0.000E+00 0.000E+00 5.010E+01 Y-90 6.800E+02 0.000E+00 1.820E+01 0.000E+00 0.000E+00 0.000E+00 9.390E+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 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-04 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 ZR-95 6.830E+03 1.660E+03 1.180E+03 0.000E+00 1.790E+03 0.000E+00 8.280E+05 ZR-97 3.990E+00 6.850E-01 3.130E-01 0.000E+00 6.910E-01 0.000E+00 4.370E+04 NB-95 5.930E+05 2.440E+05 1.410E+05 0.000E+00 1.750E+05 0.000E+00 2.060E+08 NB-97 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.700E-06 MO-99 0.000E+00 2.120E+08 4.130E+07 0.000E+00 3.170E+08 0.000E+00 6.980E+07 TC- 99M 2.690E+01 5.550E+01 7.150E+02 0.000E+00 5.970E+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 0.000E+00 1.060E+05 RU-105 8.050E-03 0.000E+00 2.710E-03 0.000E+00 5.920E-02 0.000E+00 3.210E+00 f RU-10E 1.900E+05 0.000E+00 2.380E+04 0.000E+00 2.i'50E+05 0.000E+00 1.440E+06

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Offsite Dose Calculation Manual Pcga 224 of 247 Revision 1, Change O ATTACHMENT 12 ! ( GRASS-COW-MILK DOSE FACTORS INFANT (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract l 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+00 0.000E+00 AG-110M 3.860E+08 2.820E+08 1.860E+08 0.000E+00 4.030E+08 0.000E+00 1.460E+10 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. 98 0E+ 09 4. 82 0E+ 07 1. 020E+09 6.24 0E+ 06 0. 000E+ 00 3.13 0E+ 09 6.64 0E+ 09 TE-125M 1.510E+08 5.040E+07 2.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 l TE-127M 4.210E+08 1.400E+08 5.100E+07 1.220E+08 1.040E+09 0.000E+00 1.700E+08 TE-127 6. 500E+ 03 2.18 0E+ 03 1.4 00E+ 03 5.2 90E+03 1. 590E4 04 0.000E+00 1.360E+05 TE-129M 5.590E+08 1.920E+08 8.620E+07 2.150E+08 1.400E+09 0.000E+00 3.340E+08 TE-129 2.0BCE-09 0.000E+00 0.000E+00 1.750E-09 5.180E-09 0.000E+00 1.660E-07 TE-131M 3.380E+06 1.360F+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 O_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

k I-130 3.600E+06 7.920E+06 3.180E+06 8.880E+0B 8.700E+06 0.000E+00 1.700E+06 1-131 2.720E+09 3.210E+09 1.410E+09 1.05CE+12 3.750E+09 0.000E+00 1.150E+08 1-132 1.420E+00 2.890E+00 1.030E+00 1.350E+02 3.220E+00 0.000E+00 2.340E+00 I-133 3.720E+07 5.410E+07 1.580E+07 9.840E+09 6.360E+07 0.000E+00 9.160E+06 I-134 0.000E+00 0.000E+00 0.000E+00 1.010E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.210E+05 2.410E+05 8.800E+04 2.160E+07 2.690E+05 0.000E+00 B.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 CS-137 5.15 0E+10 6. 02 0E+10 4.27 0E+ 09 0. 000E+ 00 1.620E+10 6. 550E+09 1. 8 80E+ 0B 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 4.550E-07 0. 000E+00 1.32 0E-08 0. 000E+00 0. 000E+ 00 0.000E+ 00 2. 88 0E-05 BA-140 2.410E+08 2.410E+05 1.240E+0? 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 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. 030E+ 01 1. 590E+ 01 4. 090E+ 00 0. 000E+00 0. 000E+00 0. 000E+00 1.870E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.210E-06 CE-141 4.330E+04 2.640E+04 3.110E+03 0.000E+00 B.150E+03 0.000E+00 1.370E+07 CE-143 4. 000E+02 2. 650E+ 05 3. 02 0E+ 01 0. 000E+ 00 7.720E+ 01 0. 000E+ 00 1. 550E+06 CE-144 2.330E+06 9.520E+05 1.300E+05 0.000E+00 3.850E+05 0.000E+00 1.330E+08 PR-143 1.490E+03 5.590E402 7.410E+01 0.000E+00 2.080E+02 0.000E+00 7.890E+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 8. 82 0E+02 9. 06 0E+02 5. 550E+01 0. 000E+00 3.4 90E+02 0. 000E+00 5.74 0E+05 W-187 6.120E+04 4.260E+04 1.470E+04 0.000E+00 0.000E+00 0.000E+00 2.500E+06 NP-239 3.64 0E+01 3.2 50E+00 1.84 0E+ 00 0. 000E+ 00 6.490E+00 0. 000E+ 00 9.4 00E+04

( l .

. _ _ __- . _ _ ~ _ Offsite Dose Calculation Manual Page 225 of 247 Revision 1,' Change 0 '

    .                                             ATTACHMENT 12 GRASS. GOAT-MILK DOSE FACTORS ADULT (m2

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 C-14 0.000E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 NA-24 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 P-32 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 CR-51 2.050E*10 1.270E+09 7.930E+08 0.000E+00 0.000E+00 0.000E+00 2.310E+09 MN-54 0.000E+00 0.000E+00 3.430E+03 2.050E+03 7.560E+02 4.560E+03 8.640E+05 MN-56 0.000E+00 1.010E+06 1.920E+05 0.000E+00 3.000E+05 0.000E+00 3.090E+06 FE-55 0.000E+00 5.000E-04 9.010E-05 0.000E+00 6.450E-04 0.000E+00 1.620E-02 FE-59 3.260E+05 2.250E+05 5.260E+04 0.000E+00 0.000E+00 1.260E+05 1.290E+05 CO-57 3.070E+05 9.090E+05 3.490E+05 0.000E+00 0.000E+00 2.540E405 3.030E+06 CO-Co 0.000E+00 1.540E+05 2.550E+05 0.000E+00 0.000E+00 0.000E+00 3.900E+06 CO-60 0.000E+00 5.660E+05 1.270E+06 0.000E+00 0.000E+00 0.000E+00 1.150E+07 NI-63 0.000E+00 1.970E+06 4.340E+06 0.000E+00 0.000E+00.0.000E+00 3.700E+07 k NI-65 0.070E+08 5.600E+07 2.710E+07 0.000E+00 0.000E+00 0.000E+00 1.170E+07 CU-64 4.440E-02 5.770E-03 2.630E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 ZN-65 0.000E+00 2.690E+03 1.260E+03 0.000E+00 6.770E+03 0.000E+00 2.290E+05 ZN-69 1.650E+0B 5.240E+08 2.370E+0B 0.000E+00 3.500E+08 0.000E400 3.300E408 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 3.900E+06 0.000E+00 0.000E+00 0.000E+00 4.470E+06 BR-84 0.000E+00 0.000E+00 1.240E-02 0.000E+00 0.000E+00 0.000E+00 1.790E-02 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-86 0.000E+00 3.110E+0B 1.450E+0B 0.000E+00 0.000E+00 0.000E+00 6.140E+07 RB-88 RB-89 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-90 3.050E+09 0.000E+00 8.740E+07 0.000E+00 0.000E+00 0.000E+00 4.090E+08 i SR-91 9.830E+10 0.000E+00 2.410E+10 0.000E+00 0.000E+00 0.000E+00 2.840E+09 l ! SR-92 6.580E+04 0.000E+00 2.660E+03 0.000E+00 0.000E+00 0.000E+00 3.130E405 Y-90 1. 030E+ 00 0. 000E+ 00 4.4 4 0E- 02 0. 000E+ 00 0. 000E+ 00 0. 000E+00 2. 03 0E+01 Y-91M 8.480E+00 0.000E+00 2.280E-01 0.000E+00 0.000E+00 0.000E+00 8.990E+04 Y-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ~ Y-92 1. 03 0E+03 0. 000E+ 00 2. 760E+ 01 0. 000E+00 0. 000E+ 00 0. 000E+ 00 5.680E+05 j Y-93 6.510E-06 0.000E+00 1.900E-07 0.000E+00.0.000E+00 0.000E+00 1.140E-01 d ER-95 2.800E-02 0.000E+00 7.720E-04 0.000E+00 0.000E+00 0.000E+00 8.870E+02 ZR-97 1.140E+02 3.640E+01 2.470E+01 0.000E+00 5.710E+01 0.000E+00 1.150E+05 NB-95 5.110E-02 1.030E-02 4.710E-03 0.000E+00 1.560E-02 0.000E+00 3.190E+03 NB-97 9.900E+03 5.510E+03 2.960E+03 0.000E+00 5.440E+03 0.000E+00 3.340E+07 MO-99 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00'O.000E+00 0.000E+00 0.000E+00 3.030E+06 5.760E+05 0.000E+00 6.860E406 0.000E+00 7.020E+06 TC-99M 3.900E-01 1. 2 0 0E+ 00 1. 4 0 0E+ 01 0. 0 00E+ 00 1. 6 7 0E+ 01 5. 4 0 0E- 01 6. 52 0E+ 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 1.220E+02 0.000E+00 5.270E+01 0.000E+00 4.670E+02 0.000E+00.1.430E+04 k RU-105 1.030E-04 0. 000E+ 00 4. 06 0E-05 0.000E+ 00 1.3 3 0E-03 0.000E+ 00 6.290E- 02 RU-106 2. 4 50E+03 0. 000E+ 00 3.100E+02 0. 000E+00 4. 73 0E+ 03 0. 000E+ 00 1.58 0E+05

Offsite Dose Calculation Manual Page 226 of 247 Revision 1, Ch:nge O ATTACFMENT 12 ] GRASS-GOAT-Mll.K DOSE FACTORS ADULT (m

mrem /yr per uCi/sec)

Nuc1;de Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M RS-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M SB-124 6.990E+06 6.470E+06 3.840E+06 0.000E+00 1.270E+07 0.000E+00 2.640E+09 SB-125 3.090E+06 5.840E+04 1.220E+06 7.490E+03 0.000E+00 2.410E+06 8.770E+07 2.450E+06 2.740E+04 5.840E+05 2.490E+03 0.000E+00 1.890E+06 2.700E+07 TE-125M 1.950E+06 7.080E+05 2.620E+05 5.880E+05 7.950E+06 0.000E+00 7.810E+06' TE-127M 5. 4 90E+ 06 1. 96 0E+06 6. 6 90E+ 05 1.4 00E+06 2.23 0E+07 0. 000E+00 1. 84 0E+07 TE-127 TE-129M 8.060E+01 2.890E+01 1.740E+01 5.970E+01 3.280E+02 0.000E+00 6.360E+03

               ,?50E+06 2.710E+06 1.150E+06 2.490E406 3.030E+07 0.000E+00 3.650E+07 TE-129 0.;00E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 TE-131M TE-131 4.330E+04 2.120E+04 1.770E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 TE-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

2. 87 0E+ 05 1. 86 0E+ 05 3. 74 0E+05 2. 05 0E+ 05 1. 790E+06 0'. 000E+00 8. 790E4 06

{ 1-130 I-131 5.110E+05 1.510E+06 5.950E+05 1.280E+0B 2.350E+06 0.000E+00 1.300E+06 1-132 3.560E+08 5.090E+0B 2.920E+0B 1.670E+11 8.720E+08 0.000E+00 1.340E+08 1-133 1.960E-01 5.250E-01 1.840E-01 1.840E+01 8.360E-01 0.000E+00 9.860E-02 1-134 4.760E+0S 8.280E+06 2.520E+06 1.220E+09 1.440E+07 0.000E+00 7.440E+06 0.000E+00 0,000E+00 0.000E+00 0.000E+00 0.00CE+00 0.000E+00 0.000E+00 1-135 1.670E+04 4.360E+04 1.610E+04 2.880E+06 6.993E+04 0.000E+00 4.920E+04 CS-134

1. 700E+10 4. 030E+10 3. 3 00E+10 0. 000E+00 1.310E+10 4.33 0E+09 7. 060E+08 CS-136 7.840E+08 3,090E+09 2.230E+09 0.000E+00 1.720E+09 2.360E+0B 3.520E+08 CS-137

2. 210E+10 3. 03 0E+10 1. 98 0E+10 0. 000E+ 00 1. 03 0E+10 3.4 20E+ 09 5. 86 0E+08 CS-138 BA-139 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 5.640E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-08 BA-141 3.230E+06 4.050E+03 2.110E+05 0.000E+00 1.380E+03 2.320E+03 6.650E406 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 IA- 14 2 5.380E-01 2.710E-01 1.990E+04 0.000E*00 0.000E+00 0.000E+00 1.990E+04 CE-141 0.000E+00 0.000E+00 0.000E+00 0.000E 30 0.000E+00 0.000E400 3.640E-09 CE-143 5.810E+02 3.930E+02 4.450E+01 0.000E+00 1.820E+02 0.000E+00 1.5Q0E+06 CE-144 5.020E+00 3.710E+03 4.110E-01 0.000E+00 1.630E+00 0.000E+00 1.390E+05 PR-143 4.290E+04 1.790E+04 2.300E+(3 0.000E+00 1.060E+04 0.000E+00 1.450E+07 PR-144 1. 910E+ 01 7.6 50E+00 9.4 50E-01 0. 000E+ 00 4.410E+00 0. 000E+00 8.350E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 W-187 1.230E+01 1.310E+01 7.820E-01 0.000E+00 7.640E+00 0.000E+00 6.270E+04 NP-239 7.870E+02 6.580E+02 2.300E+02 0.000E+00 0.000E+00 0.000E+00 2.160E+05 4.390E-01 4.320E-02 2.380E-02 0.000E+00 1.350E-01 0.000E+00 8.860E+03 l

Offsite Dose Calculation Manual Pega 227 of 247 Revision 1,' Change O ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS TEEN (m2

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 C-14 0.000E+00 2.030E+03 2.030F+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 NA-24 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 5.330E+05 5.330E+05 5.330E+05 5.33sE+05 5.330E+05 5.330E+05 5.~330E+05 P-32 3.780E+10 2.340E+09 1.470E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 CR-51 0.000E+00 0.000E+00 6.000E+03 3.330E+03 1.310E+03 8.560E+03 1.010E+06 MN-54 0.000E+00 1.680E+06 3.330E+05 0.000E+00 5.010E+05 0.000E+00 3.440E+06 MN-56 0.000E+00 9.010E-04 1.600E-04 0.000E+00 1.140E-03 0.000E+00 5.930E-02 FE-55 5.790E+05 4.100E+05 9.570E+04 0.000E+00 0.000E+00 2.600E+05 1.780E+05 FE-59 6.750E+05 1.580E+06 6.090E+05 0.000E+00 0.000E+00 4.970E+05 3.730E+06 CO-57 0.000E+00 2.690E+05 4.520E+05 0.000E400 0.000E400 0.000E+00 5.030E+06 CO-58 0.000E+00 9.540E+05 2.200E+06 0.000E+00 0.000E+00 0.000E+00 1.310E+07 CO-60 0.000E+00 3.340E+06 7.510E+06 0.000E+00 0.000E+00 0.000E+00 4.350E+07 NI-63 1.420E+09 1.000E+08 4.810E+07 0.000E+00 0.000E+00'O.000E+00 1.590E+07 { NI-65 8.130E-02 1.040E-02 4.730E-03 0.000E+00 0.000E*00 0.000E+00 5.640E-01 CU-64 0.000E+00 4.790E+03 2.250E+03 0.000E+00 1.210E+04 0.000E+00 3.710E+05 ZN-65 2.530E+0B B.780E+0B 4.090E+0B 0.000E+00 5.620E+08 0.000E+00 3.720E+0B 2N-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 6.670E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 2.290E-02 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 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E408 2.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 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 0.060E+00 0.000E+00 0.000E+00 SR-89 5.620E+09 0.000E+00 1.160E+08 0.000E+00 0.000E+00 0.000E+00 6.690E+0B SR-90 1.390E+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 5.4 80E+ 05 L SR-92 1.680E+00 0.000E+00 8.010E-02 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 1.290E+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 1 900E+03 0.000E+00 5.090E+01 0.000E+00 0.000E+00 0.000E+00 7.780E+05 Y-92 1.200E- 05 0. 000E+00 3.4 8 0E-07 0. 000E+00 0. 000E+00 0. 000E+00 3. 3 00E- 01 Y-93 5.16 0E-02 0. 000E+ 00 1.410E- 03 0. 000E+ 00 0.000E+00 0. 000E+ 00 1. 58 )E+ 03 ER-95 1.990E+02 6.260E+01 4.310E+01 0.000E+00 9.200E+01 0.000E+00 1.450E+05 ER 9. 3 00E-02 1. 84 0E-02 8.4 8 0E-03. 0. 000E+00 2.790E-02 0. 000E+ 00 4.98 0E+03 NB-95 1.690E+04 9.370E+03 5.16 0E+03 0.000E+00 9.080E+03 0.000E+00 4. 010E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 7.610E-09 MO-99 0.000E+00 5.470E+06 1.040E+06 0.000E+00 1.250E+07 0.000E+00 9.000E+06 TC-99M 6.770E-01 1.890E+00 2.450E401 0.000E+00 2.810E+01 1.050E+00 1.240E+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 2.180E+02 0.000E+00 9.310E+01 0.000E+00 7.670E+02 0.000E+00 1.820E+04 RU-105 1,880E-04 0.000E+00 7.290E-05 0.000E+00 2.370E-C3 0.000E+00 1.520E-01 ( RU-106 4.500E+03 0,000E+00 5.670E+02 0.000E+00 8.680E+03 0.000E+00 2.160E+05

                                                                               . .. ~        .   -

i Offolte Dose Calculation Manual Page 228 of 247 1 Ravision 1, Change 0 { l t ATTACHMENT 12 i i i GRASS-GOAT-MILK DOSE FACTORS '

                                                   'rEEN (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract RH-103M 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00-RR-106 0.000E+00 0.000E+0D 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M SB-124 1.160E+07 1.090E+07 6.650E+06 0.000E+00 2.090E+07 0.000E+00 3.070E+09 5.510E+06 1.020E+05 2.150E+06 1.250E+04 0.000E+00 4.810E+06 1.110E+08 SB-125 4.380E406 4.790E+04 1.030E+06 4.190E+03 0.000E+00 3.850E+06 3.410E+07 TE-125M 3.600E+06 1.300E+06 4.820E+05 1.010E+06 0.000E+00 0.000S+00 1.060E+07 TE-127M 1.010E407 3.590E+06 1.200E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 TE-127

1. 4 9 0E+ 02 5. 290E+ 01 3. 210E+ 01 1. 03 0E+ 02 6. 050E+ 02 0. 0 00E+0 0 1.150E+ 04 TE-12 9M 1. 3 3 0E+07 4.92 0E+ 06 2.100E+ 06 4.2 8 0E+06 5. 550E+ 07 0. 000E+00 4. 980E+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-131 7.890E+04 3.780E+04 3.150E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 TE-131M TE-332 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00-( I-130 5.130E+05 3.250E+05 3.060E+05 3.430E+05 3.120E+06 0.000E+00 1.030E+07 1-131 B 990E+05 2.600E+06 1.040E+06 2.120E+08 4.010E+06 0.000E+00 2.000E+06 I-132 6.450E+08 9.C30E+08 4.850E+08 2.640E+11 1.560E+09 0.000E+00 1.790E+08 1-133 3.480E-01 9.110E-01 3.270E-01 3.070E+01 1.430E+00 0.000E+00 3.970E 01 I-134

8. 6 90E+06 1. 4 70E+07 4. 500E+ 06 2. 060E+ 09 2. 5 90E+ 07 0. 000E+00 1.120E+07 1-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 2.960E+04 7.620E+04 2.820E+04 4.900E+06 1.200E+05 0.000E+00 8.440E+04 CS-136 2.940E+10 6.930E410 3.210E+10 0.000E+00 2.200E+10 B.410E+09 8.620E+0B CS-137 1. 33 0E+ 09 5.250E+ 09 3. 53 0E+ 09 0. 000E+00 2. 86 0E+09 4.510E+08 4.23 0E+08 CS-138 4. 02 0E+10 5. 34 0E+10 1. 8 6 0E+10 0. 000E+00 1. 82 0E+10 7. 060E+ 09 7. 600E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 BA-140 1.040E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.310E-08 BA-141 5. 83 0E+06 7.14 0E+ 03 3. 750E+ 05 0. 000E+00 2.420E+03 4. 800E+ 03 8. 980E+06 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 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.760E-01 4.750E-01 1.260E-01 0.000E+00 0.000E+00 0.000E+00 2.730E+04 LA-142 CE-141 1.980E-12 8.780E-13 2.190E-13 0.000E+00 0.000E+00 0.000E+00 2.670E-08 CE-143

1. 060E+ 03 7.110E+ 02 8.170E+01 0. 000E+ 00 3. 3 50E+02 0. 000E+ 00 2. 030E+06 '

CE-144 9.230E+00 6.720E+03 7.500E-01 0.000E+00 3.010E+00 0.000E+00 2.020E+05 PR-143 7.900E+04 3.270E+04 4.240E+03 0.000E+00 1.950E+04 0.000E+00 1.990E+07 PR-144 3.500E+01 1.400E+01 1.740E+00 0.000E+00 8.130E+00 0.000E+00 1.150E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 2.180E+01 2.370E+01 1.420E+00 0.000E+00 1.390E+01 0.000E+00 8.530E+04 W-187 1.440E+03 1.170E+03 4.110E+02 0.000E+00 0.000E+00 0.000E+00 3.160E+05 NP 23 9 8.390E-01 7.910E-02 4.390E-02 0.000E+00 2.480E-01 0.000E+00 1.270E+04 I

Offsite Dose Calculation Manual Page 229 of 247 Revision 1, Change 0 ATTACHMENT 12 .( GRASS-GOAT-MILK DOSE FACTORS CHILD (m2

mrem /yr per uCi/see)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 P-32 9.330E+10 4.370E+09 3.600E+09 0,000E+00 0.000E+00 0.000E+00 2.580E+09 CR-51 0.000E+00 0.000E+00 1.220E+04 6.790E+03 1.860E+03 1.240E+04 6.490E+05 MN-54 0.000E+00 2.510E+06 6.690E+05 0.000E+00 7.050E+05 0.000E+00 2.110E+06 MN-56 0.000E+00 1.570E-03 3.550E-04 0.000E+00 1.900E-03 0.000E+00 2.280E-01 FE-55 1.450E+06 7.700E+05 2.390E+05 0.000E+00 0.000E+00 4.360E+05 1.430E+05 FE-59 1.570E+06 2.530E+06 1.260E+06 v.000E+00 0.000E+00 7.350E+05 2.6402+06 CO-57 0.000E+00 4.600E+05 9.320E+05 0.000E+00 0.000E+00 0.000E+00 3.770E+06 CO 58 0.000E+00 1.460E+06 4.460E+06 0.000E+00 0.000E+00.0.000E+00 8.500E+06

/      CO-60     0.000E+00 5.180E+06 1.530E+07 0.000E+00 0.000E+00 0.000E+00 2.870E+07 g,_j    NI-63     3.560E+09 1.900E+08 1.210E+08 0.000E+00 0.000E+00 0.000E+00 1.280E+07 NI-65      1.990E-01 1.870E-02 1.090E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 CU-64     0.000E+00'B.410E403 5.080E+03 0.000E+00 2.030E+04 0.000E+00 3.950E+05 2N-65     4.960E+08 1.320E+09 8.220E+08 0.000E+00 8.330E+08 0.000E+00 2.320E+08

2N-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 1.390E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.620E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E400 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-86 0.000E+00 1.050E+09 6.470E+08 0.000E+00 0.000E+00 0.000E+00 6.770E+07-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 1.390E+10 0.000E+00 3.970E+08 0.000E+00 0.000E+00 0.000E+00 5.380E+08 SR-90 2.350E+11 0.000E+00 5,.950E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 2.970E+05 0.000E+00 1.120E+04 0.000E+00 0.000E+00 0.000E+00 6.550E+05 -

SR-92 4.590E+10 0.000E+00 1.840E-01 0.000E+00 0.000E+00 0.000E+00 8.690E+01 Y-90 3.860E+01 0.000E+00 1.030E+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 B.4 4 0E-07 0. 000E+ 00 0. 000E+ 00 0. 000E+00 8.520E-01 Y-93 1.270E-01 0.000E+00 3.480E-03 0.000E+00 0.000E+0C 0.000E+00 1.890E+03 ZR-95 4. 610E+02 1. 010E+ 02 9. 03 0E+01 0. 00 0E+ 00 1. 4 5 0E+ 02 0. 00 0E+ 0 0 1. 06 0E+ 05 ZR-97 2.26 0E-01 3.270E-02 1.930E-02 0. 000E+ 00 4.690E-02 0. 000E+00 4. 950E+03 NB-95 3.810E+04 1.480E+04 1.060E+04 0.000E+00 1.390E+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 MO-99 0.000E+00 9.950E+06 2.460E+06 0.000*s+00-2.120E+07 0.000E+00 8.230E+06 TC-99M 1. 550E+00 3. 04 0E+ 00 5. 04 0E+01 0. 000E+00 4.420E+01 1. 55 0E+00 1.73 0E+03 TC-101 C.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 5.150E+02 0.000E+00-1.980E+02 0. 0 00E+ 0 0 1. 3 0 0E+ 03 0. 0 00E+ 00 1. 3 3 0E+ 04 { RU-105 4.590E-04 0.000E+00 1.660E-04 0. 000E+00 4. 03 0E- 03 0. 000E+00 2. 990E-01 RU-106 1.110E+04 0.000E+00 1.380E+03 0.000E+00 1.$00E+04 0.000E+00 1.720E+05

  .Offsite Dose Calculation Manual                                               Pcge 230 of 247 Revision 1, Change O ATTACHMENT 12

-b GRASS-GOAT-MILK DOSE FACTORS

                                               HILD (m

mrem /yr per uti/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+00 0.000E+00 AG-110M 2.510E+07 1.690E+07 1.350E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 SB-124 1.300E+07 1.690E+05 4.570E+06 2.BBOE+04 0.000E+00 7.240E+06 8.150E+07 SB-125 1.040E+07 8.050E+04 2.190E+06 9.670E+03 0.000E+00 5.820E+06 2.490E+07 TE-125M 8.850E+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+06 2.960E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 TE-127 3.670E+02 9.910E+01 7.880E+01 2.540E+02 1.050E+03 0.000E+00 1.440E+04 TE-129M 3.270E+07 9.130E+06 5.000E+06 1.050E+07 9.600E+07 0.000E+00 3.990E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.340E-09 TE-131M 1.920E+05 6.640E+04 7.070E+04 1.370E+05 6.430E+05 0.000E+00 2.690E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 _j TE-132 1.230E+06 5.420E+05 6.550E+05 7.900E+05 5.040E+C6 0.000E+00 5.460E+06

\ I-130    2,100E+06 4.250E+06 2.190E+06 4.680E+08 6.350E+06 0.000E+00 1.990E+06 I-131    1.570E+09 1.570E+09 8.950E+08 5.210E+11 2.580E+09 0.000E+00 1.400E+08-I-132    8.230E-01 1.510E+00 6.960E-01 7.020E+01 2.320E+00 0.000E+00 1.780E+00 I-133    2.110E+07 2.610E+07 9.880E+06 4.850E+09 4.350E+07 0.000E+00 1.050E+07 I-134    0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135    7.000E+04 1.260E+05 5.960E+04 1,120E+07 1.930E+05 0.000E+00 9.600E+04 CS-134   6.790E+10 1.110E+11 2.350E+10 0.000E+00 3.450E+10 1.240E+10 6.010E+08 Ca-136   3.010E+09 8.280E+09 5.360E+09 0.000E+00 4.410E+09 6.560E+08 2.910E+08 CS-137   9.670E+10 9.260E+10 1.370E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+08 CS-139   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-00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.480E-06 BA-140   1. 410E + 0 7 1. 2 3 0E+ 04 8.210E+05 0.000E+00 4.010E+03 7.340E+03 7.120E+06 BA-141   0.000E+00 0,oDCE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142   0.000E+00 6.00?E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 2.310E+0D A.050E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.260E+04 LA-142 4.770E-11 1.520E-12 4.770E-13 0.000E+00 0.000E+00 0.000E+00 3.020E-07 CE-141 2.620E+03 1.310E+03 1.940E+02 0.000E+00 5.730E+02 0.000E+00 1.630E+06 CE-143 2.270E+01 3.230E+04 1.780E+00 0.000E+00 5.150E+00 0.000E+00 1.800E+05 CE-144 1.950E+05 6.1' JOE +04 1.040E+04 0.000E+00 3.380E+04 0.000E+00 1.590E+07 PR-143   8. 670E+ 01 2. 000E+ 01 4.3 00E+ 00 0. 000E+00 1.410E+01 0.000E+00 9.3 50E+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 5.340E+01 4.320E+01 3.350E+00 0.000E+00 2.370E+01 0.000E+00 6.850E+04 W-187 3.490E+03 2.070E+03 9.270E+02 0.000E+00 0.000E+00 0.000E+00 2.900E+05 NP-239 2.060E+00 1.480E-01 1.040E-01 0.000E+00 4.280E-01 0.000E+00 1.100E+04 I

-l

Oifsite Dose Calculation Manual Page 231 of 247 l Revision 1,' Change 0 ! l r ATTACHMENT 12 ! (' i l GPr.;S-GOAT-MILK DOSE FACTORS INFANT (m2

mrem /yr per uci/see) l i

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ) H-3 C-14 0.000E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 NA-24 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 P-32 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 CR-51 1.920E+11 1.130E+10 7.450E+09 0.000E+00 0.000E+00 0.000E+00 2.600E+09 0.000E+00 0.000E+00 1.940E+04 1.260E+04 2.760E+03 2.460E+04 5.650E+05 MN-54 0.000E+00 4.670E406 1.060E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 MN-56 FE-55 0.000E+00 3.850E-03 6.630E-04 0.000E+00 3.310E-03 0.000E+00 3.490E-01 1.760E+06 1.130E+06 3.030E+05 0.000E+00 0.000E+00 5.540E+05 1.440E+05 FE-59 2.920E+06 5.110E+06 2.010E+06 0.000E+00 0.000E+00 1.510E+06 2.440E+06 CD-57 CO-58 0.000E+00 1.070E+06 1.75?E+06 0.000E+00 0.000E+00 0.000E+00 3.660E+06 0.000E+00 2.910E+06 7.270Es06 0.000E,00 0.000E+00 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 2.300E+07 0.000E+00 0.000E+00.0.000E+00 2.520E+07 NI-63 4.190E+09 2.590E+08 1.450E+0B 0.000E+00 0.000E+00 0,000E+00 1.290E+07 f NI-65 4.210E-01 4.770E-02 2.170E-02 0.000E+00 0.000E+00 0.000E+00 3.630E+00 CU-64 0.000E+00 2.090E+04 9.680E+03 0.000E+00 3.540E+04 0.000E+00 4.290E+05 ZN-65 6.660E+08 2.280E+09 1.050E+09 0.000E+00 1.110E+09 0 000E+00 1.930E+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 2.330E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 1.190E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-64 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00 0.000E+00 l BR-65 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 1.320E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 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 2.640E+10 0.000E+00 7.580E+0B 0.000E+00 0.000E+00 0.000E+00 5.430E+08 SR-90 2.550E411 0.000E+00 6.500E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 l SR-91 6.10 0E+ 05 0. 000E+00 2.24 0E+ 04 0.000E+00 0.000E+00 0.000E+00 7.310E+05. SR-92 l Y-90 9.760E+00 0.000E+00 3.620E-01 0.000E+00 0.000E+00 0.000E+00 1.050E+02 8.16 0E+01 0. 000E+ 00 2.190E+00 0. 000E+00 0. 000E+ 00 0. 000E+ 00 1.130E+05 I Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l Y-91 8.000E+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 1.200E+10 Y-93 LR-95 2.700E-01 0.000E+00 7.350E-03 0.000E+00 0.000E+00 0.000E+00 2.130E+03 I LR-97 8.190E+02 2.000E+02 1.420E+02 0.000E+00 2.150E+02 0.000E+00 9.940E+00 NB-95 4.790E-01 8.220E-02 3.760E-02 0.000E+00 8.290E-02 0.000E+20 5.240E+03 NB-97 7.120E+04 2.930E+04 1.690E+04 0.000E+00 2.100E+04 0.000E+00 2.470E+07 MD-99 6.590E-12 1.410E-12 5.070E-13 0.000E+00 1.100E-12 0.000E+00 4.440E-07 0.000E+00 2.540E+07 4.960E+06 0.000E+00 3.800E+07 0.000E+00 8.830E+06 TC-99M 3.23 0E+ 0 0 6. 66 0E+00 B .570E+ 01 0. 000E+ 0 0 7.16 0E+ 0'. 3.4 80E+ 00 1. 93 0E+ 03 i 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. 04 0E+ 03 0. 000E+00 3.4 90E+02 0. 000E+00 2.170E+03 0. 000E+00 1.270E4 04 i RU-105 9.670E-04 0.000E+00 3.260E-04 0.000E+00 7.110E-03 0.000E+00 3.850E-01 4 k RU-106 2.280E+04 0.000E+00 2.850E+03 0.000E+00 2.t00E+04 0.000E+00 1.730E+05 JL \

m.- . . . - . - ~. . Offsite Dose, Calculation Manual Page 232 of 247 Revision 1, Change O ATTACHMENT 12 GRASS-GOAT 4flLK DOSE FACTORS INFANT (m2

mrem /yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract 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+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 SB-124 2.510E+07 3.700E+05 7.790E+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 8.620E+06 TE-127M 5.050E+0? 1.680E+07 6.120E+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 1.640E+04 TE-129M 6.710E+07 2.300E+07 1.030E+07 2.580E+07 1.680E+08 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-08 TE-131M 4.050E+05 1.630E+05 1.350E+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 k I-130 4. 32 0E+06 9. 510E+ 06 3. 82 0E+06 1. 070E+ 09 1. 04 0E+07 0. 000E+00 2. 04 0E+ 06 I-131 3.270E+09 3.850E+09 1.690E+09 1.270E+12 4.500E+09 0.000E+00 1.370E+08 I-132 1.710E+00 3.470E+00 1.230E+00 1.630E+02 3.870E+00 0.000E+00 2.810E+00 I-133 4.460E+07 6.490E+07 1.900E+07 1.180E+10 7.630E+07 0.000E+00 1.100E+07 I-134 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.460E+05 2.900E+05 1.060E+05 2.600E+07 3.230E+05 0.000E+00 1.050E+05 CS-134 1. 09 0E+11 2. 04 0E+11 2. 06 0E+10 0. 000E+00 5.250E+10 2.15 0E+10 5. 54 0E+ 08 CS-136 5. 8 8 0E+ 09 1. 73 0E+10 6.4 6 0E+ 09 0. 000E+ 00 6. 900E+09 1.410E+09 2. 63 0E+08 CS-137 1.540E+11 1.810E+11 1.280E+10 0.000E+00 4.850E+10 1.960E+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 1.500E-09 0.000E+00 0.000E+00 0.000E+00 3.450E-06 BA-140 2.890E+07 2.890E+04 1.490E+06 0.000E+00 6.870E+03 1.780E+04 7.110E+06 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 4.840E+00 1.910E+00 4.900E-01 0.000E400 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 5.200E+03 3.170E+03 3.730E+02 0.000E+00 9.780E+02 0.000E+00-1,640E+06 CE-143 4.800E+0J 3.100E+04 3.630E300 0.000E+00 9.270E+00 0.000E+00 1.860E+05 CE-144 2.790E+05 1.140E+05 1.560E+04 0.000E+0D A.620E+04 0.000E+00 1.600E+07 PR-143 1.790E+02 6.710E+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 1.060E+02 1.090E+02 6.660E+00 0.000E+00 4.190E+01 0.000E+00 6.890E+04 W-187 7.350E+03 5.110E+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 7.780E-01 0.000E+00 1.130E+04 (

Offsite Dose Calculation Manual Page 233 of 247 Revision 1 Change 0 f, ATTACIIMENT 13 l ENVIRONMENTAL MONITORING SITES FOR REMP l SAMPLE SITE SECTOR DISTANCE' DESCRIPTION km mi en1 NW 0.4 0.6 l onsite, Alons clif fs l on2 WNW 2.7 1.7 ist. 765, Auto osp l oR3 . W 2.3 1.4 at. 765, ciovannies 1.vern <cnotty Pine) l on4 WSW 2.0 1.2 at. 765, Aeross from white send orive l ens SW 2.4 1.5 at. 765 et Johns creek l cas, A4 SSW 2.9 1.8 at. 765 et tusby l ca7, A1, roc, tes, ib6 S 0.7 0.5 on site before entrax e to com conoy l one, Az SSE 2.5 1.5 com conor no.d at Emersexy ciren l ca9, A3 SE 2.6 1.6 say sreeze moed l on10 NW 6.4 4.0 catvert seech ad a occatur st l on11 WNW 6.6 4.1 cirt need of f Mackelt ad & Parran Rd l c 12 W 6.7 4.2 sowen ad & Macket t ad l on13 WSW 6.1 3.8 maekatt ad near wativitte l

       *14                             SW           6.4         4.0                       nodney Point

( - l

     ,* is                            SSW           6.2         3.9             mit t seidse ad a Turner ad              l enie                               S           6.5         4.1              Access from Appeat school l

on17 SSE 5.9 3.7 cove Point ad & Little Cove Point ad l onts Sd 7.1 4.5 cove Point l en19 NW 4.4 2.8 tons se ch l ca2o NNW 0.4 0.3 onsite near shore l on21, As, 167, iba, ib9 WNW 19.3 12.1 Emergency offsite r eitity off at. 231 l 0a22 S 12.5 7.8 sotonons island l l on23 ENE 12.6 7.9 r.ytors ist.re l .j l wai NNE 0.2 0.1 Inteke vicinity l e.2, lei, 1 2 N 0.3 0.2 cischerse vicinity l ebt ESE 0.6 0.4 can, coney shoreline l 1b1, 1b2, ab3 SSE 2.6 1.6 Garden Plot off say sreere ad l 14 Ins Aren not influenced by Plant oisch. Petwent niver l 1:3 E 0.9 0.6 c , coney l l

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Offsite Dose Calculation Manual Page 234 of 247 ' Revision 1. Change 0 ATTACHMENT 14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCES FOR DIRECT RADIATION PARAMETER UNITS FREQUENCY LLD ACTION LEVEL GAMMA DOSEU) mR at ' east quarterty (2) N/A

   '1)      Each sample point sha!! be monitored using two or more dosimeters OR one instrument for measuring and recording dose rate continuously.

I ge) LLD for TLDs used for environmental measurements shall be in accordance with the recommendations of Regutatory Guide 4.13. ( l i

'L

Offsite Dose Calculation Manual Page 235 of 247

 ' Revision 1, Change 0 ATTACHMENT 15

.( RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCES FOR AIRBORNE ACTIVITY RADIOIODINE CANNISTER PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (:) 1131 pCi/m 3 at least weekly 0.07 0.9 PARTICULATE FILTER'l l PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) . Gross Beta ActMty pCi/m 3 at least weekly (2) 0.01 N/A (3) Cs-134 pCi/m 3 at least quarterfy(#l 0.05 10.0 Cs 137 pCl/m 3 at least quarterty(#l 0.06 20.0 (7) A!! samples consist of continuous sampler operation with sample collection weekly, or more frequently if required by dust loading (2) Analyze for gross beta actMty 24 hours or more after sampling to a!!ow for radon and thoron daughter decay. (3) Although there is not an Action Level fer gross beta actMty, if this parameter is greater than ten times the yearly mean of the control sample, perform gamma isotopic aralysis on the indMdual sample. (4) Perform a gamma isotopic analysis of a quarteriy composite sample. A separate composite sample shall be prepared for each sample location, A1 thru AS. Each composlie sample shall be a prepared from indMdual particu!r te filter samples collected during the applicable calendar quarter and from a single location. (5) If an Action Level is exceeded, check the initiating conditions listed in sections Vll.A.S.c and Vll.A.S.d. and perform the corrective actions specified in section VilA7.d and/or Vll.A.7.e. i

Offsite Dose Calsu?ation Manual Page 236 of 247 Revision 1. Change 0 - 1 ATTACEMENT 16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCES FOR WATERBORNE ACTIVITY SURPACE WATER SAMPLE N l l PARAMETER UNITS FREQUENCY LLD ACTION LEVELM H-3 pCi/l at least quarterly 2000% 20,000N Mn-54 pCi/l at least monthly 15 1000 Fe 59 pCi/l at least monthly 30 400 Co-58 pCi/l at least monthly 15 1000 Co40 pCi/l at least monthly 15 300 Zn-65 pCi/l at least monthly 30 300 Zr-95 / Nb-95 pCi/l at least monthly 15 400 1131 pCi/l at least monthly 1 2 I Cs-134 pCi/l at least monthly 15 30 Cs 137 pCi/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 M Cs-134 pCi/kg, dry at least semlannua!!p 150 N/A Cs 137 pCi/kg, dry at least semlannually 180 N/A (7) 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 VilAS.c and Vll.A.5.d, and perform the corrective actions specified in section Vll.A.7.d and/or Vll.A.7.e. - (3) If a drinking water pathway does not exist, a value of 3000 pCl/l may be used. l

    /4)      If a drinking water pathway does not exist, a value of 30,000 pCi/l may be used.

l f

                                                                                                                             .         I V

                                                                                                                      - ~ _ . , .

Offsite Dose Calculation Manual Page 237 of 247 Revision 1, Change 0 ATTACHMENT 17 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l( SURVEILLANCES FOR INGESTIBLE ACTIVITY i FISH AND INVERTEBRATES Ul PARAMETER UNITS FREQUENCY LLD ACTION LEVELPJ Mn-54 pCi/kg, wet p) 130 30,000 Fe-59 pCi/kg, wet p) 260 10,000 Co-58 pCi/kg. wet p) 130 30,000 Co60 pCi/kg, wet p) 130 10,000 Zn-65 pCi/kg, wet p) 260 20,000 Cs 134 pCi/kg, wet (2) 130 1000 Cs-137 pCi/kg. wet p) 150 2000 MILK PARAMETER UNITS FREQUENCY LLD ACTION LEVEL Pl 1131 pCi/1, wet at least monthly "> 1 3 ( Cs 134 pCi/1, wet at least monthly "i 15 60 Cs 137 pCi/l, wet at least monthly "> 18 70 Ba 140 / La 140 pCi/l, wet at least monthly "> 15 300 FOOD PRODUCTS PARAMETER UNITS FREQUENCY LLD ACTION LEVELP> l131 pCi/kg, wet at least monthlyW 60 100 Cs 134 pCi/kg. wet at least monthly

60 1000 Cs-137 pCi/kg, wet at least monthly W 80 2000 (7) Edib!e portions of the fish and Invertebrates shatl be used for analysis.

(2) The fish and invertebrates shall be sampled at least once per year in season, or semlannually if they are not seasonal. (3) The food products shall be sampled during the growing seanor.. (4) The milk sampfes need be collected and ana!yzed only if the milk is commercially available in quantities greater than 310 liters per year (see NUGREG 0133,5.3.1.1). If an Action Levelis exceeded, check the initiating conditions listed in sections Vil.A.S.c and Vll.A.5 d, and perform ( the corrective actions specified in section Vll.A.7.d and/or Vll.A.7.e.

     ' ONsite Dose Calculation Manual                                                                                                                                                                                                    Page 238 of 247
         & ision 1, Change 0 '-

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s Offsite Dose Calculation Manual P. ige 239 of 247 Revision 1, Change 0 .

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Offsite Dose Calculation Manual Page 240 of 247 Revision 1, Change O ATTACIOiENT 20 l ENVIRONMENTAL MONITORING SITES FOR ISFSI l { STATION DESCRIPTION DISTANCE' DIRFCTION I (Kiluneters) (Sector) AIR sofrLERs 2 A1 On Site Before Entrance to Camp Conoy 0.3 SE SFA1 hieteorological Station 0.4 NW SFA2 CCNPP Visitor's Center 0.7

 '                                                                                     NNE SFA3             Nonb Northwest ofISFS!                             0.1      NNW SFA4              South of ISFSI                                     0.1           S llD LOCATIONS SFDR1             Collocated with Plant TLD #159                     0.1        SW SFDR2             Collocated with Plant TLD #160                     0.1      NNW SFDR3             Collocated with Plant TLD #161                     0.1       NNE SFDR4             Collocated with Plant TLD #162                  <0.1          NE SFDR$             Collocated with Plant TLD #163                  <0.1             E SFDR6             Collocated with Plant TLD #164                     0.1       ESE SFDR7             CCNPP Visitor's Center                             0.7       NNE SFDRS             North of ISFSI                                     0.1         N SFDR9             Sous of!SFSI                                      0.1            S SFDR10            North Nonhwest of ISFS!

I 0.1 NNW SFDR11 West Northwest of ISFSI 0.1 WNW SFDR12 West ofISFSI <0.1 W SFDR13 South Southwest of ISFS! <0.1 SSW SFDR14 South Southeast of ISFSI 0.1 SSE SFDR15 East Northeast ofISFSI < 0.1 ENE SFDR16 West Southwest of ISFSI <0.1 2 WSW DR7 On Site Before Entrance to Camp Conoy 0.3 SE DR30 hieteorological Station 0.4 NW VEGETATION SFb1 hieteorological Station 0.4 NW SFb2 CCNPP Visitor's Center 0.7 NNE SFb3 North Nonhwest ofISFSI 0.1 NNW SFb4 South ofISFSI 0.1 S SFb5 On Site Before Entrance to Camp Conoy 0.3 SE E SFS1 hieteorological Station 0.4 NW SFS2 CCNPP Visitor's Center 0.7 NNE SFS3 Nonh Northwest ofISFSI 0.1 NNW SFS4 South of ISFSI 0.1 S SFS5 On Site Before Entrance to Camp Conoy 0.3 SE otstence av direction from the central reint of the tsrst. l 2 c,,,,, ,, ,,,, ,,, ,t,, ,,, ,,, ,,,,,,,, l

                                                                    .                                           I-

Offsite Dost Calculation Manual Page 241 of 247 Revision 1, Change 0 ATTACBMENT 21 l h

s MAP OF ENVIRONMENTAL MONITORING SITES FOR ISFSI l ( \ / 5 N i NNE i ' NNW '

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Map of Sampling Sites Independent Spent Fuel Storage installation (

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Offsite Dose Calculation Manual Page 242 of 247.

 ' Revision 1, Change 0 ATTACHMENT 22                                                                                                                     l

(

MAP'OF ENVIRONMENTAL MONITORING SITES FOR ISFSI (ENLARGED) l

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1 Offsite Dose Calculetion Manual Page 243 of 247 Revision 1, Change 0 ATTACHMENT 23 l 1 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-RI-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 Westinghouse Plant Vent Stack Monitor 1-RE-5415 1-Rl-5415 Westinghouse Plant Vent Stack Monitor 2 RE-5415 2-RI-5415 Gaseous Radwaste Treatment System Radiation Monitor 0-RE-2191 0 RI2191 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 5

                                                              -                            a

Offsite Dose Calculation Manual Page 244 of 247 Revision 1, Change 0 ATTACEMFSI 24 l '( LIST OF EFFECTIVE PAGES Page No. Change No. Page No. Change No. Page No. Change No. 1 0 26 0 5 0 l 2 0 27 0 52 0 3 0 28 0 53 0 4 0 29 0 54 0 l 5 0 30 0 55 0 6 0 31 0 56 0 7 0 32 0 57 0 8 0 33 0 58 0 9 0 34 0 59 0 10 0 35 0 60 0 l 11 0 36 0 61 0 l 12 0 37 0 62 0 l 13 0 38 0 63 0 14 0 39 0 64 0 15 0 40 0 65 0 16 0 41 0 66 0 17 0 42 0 67 0 18 0 43 0 68 0 19 0 44 0 69 0 20 0 45 0 70

                                          ,                           0 21                0          46           0        71         0 22                0          47           0        72         0 23                0          48           0        73         0 24                0          49           0        74         0

( 25 0 50 0 75 0 I

Offsite Dose Cciculation Menual Page 245 of 247 Revision 1, Change 0 ATTACHMENT 24 l ( UST OF EFFECTIVE PAGES Page No. Change No. Page No. Change No. Page No. Change No. 76 0 101 0 126 0 77 0 102 0 127 0 78 0 103 0 128 0 79 0 104 0 129 0 80 0 105 0 130 0 81 0 106 0 131 0 82 0 107 0 132 0 83 0 108 0 133 0 84 0 109 0 134 0 85 0 110 0 135 0 86 0 111 0 136 0 87 0 112 0 137 0 88 0 113 0 138 0 89 0 114 0 139 0 90 0 115 0 140 0 91 0 116 0 141 0 92 0 117 0 142 0 93 0 118 0 143 0 94 0 119 0 144 0 95 0 120 0 145 0 96 0 121 0 146 0 [ 97 0 122 0 147 0 98 0 123 0 148 0 l 99 0 124 0 149 0 100 0 (~ 125 0 150 0 l l 1 I 1

1 Offsite Dose Calculation Manual Page 246 of 247 Revision 1, Change 0 [ ATTACHME!TI 24 l UST OF EFFECTIVE PAGES Page No. Change No. Page No. Change No. Page No. Change No. 151 0 176 0 201 0 152 0 177 0 202 0 l 153 0 178 0 202 0 154 0 179 0 204 0 l 155 0 180 0 205 0 156 0 181 0 206 0 157 0 182 0 207 0 l 158 0 183 0 208 0 159 0 184 0 209 0 160 0 185 0 210 0 l 161 0 186 0 211 0 l 162 0 187 0 212 0 163 0 188 0 213 0 164 0 189 0 214 0 165 0 190 0 215 0 166 0 191 0 216 0 - 167 0 192 0 217 0 168 0 193 0 218 0 169 0 194 0 219 0 170 0 195 0 220 0 , i 171 0 196. 0 221 0 l 172 0 197 0 222 0 173 i 0 198 0 223 0 174 0 199 0 224 0 ( 175 0 200 0 225 0 I F'"

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