ML17059A424

Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm.

ML17059A424
Person / Time
Site:	Nine Mile Point
Issue date:	07/06/1994
From:	Abbott R, Terry C NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17059A422	List: ML17059A421 ML17059A423 ML17059A424 ML18040A294
References
PROC-940706, NUDOCS 9409020228
Download: ML17059A424 (192)

Text

NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 1 OFF-SITE DOSE CALCULATION MANUAL ODCM DATE AND INITIALS APPROVALS REVISION 14 R. B. Abbott Plant Manager Unit 1 C. D. Terry V.P. Nuclear Engineering 1I NIAGARA MOHAWK POWER CORPORATION 9409020228 940825 PDR ADOCK 05000220 Unit 1 ODCM R PDR Revision 14 004152LL June 1994

SUMMARY

OP REVISIONS Revision 14 Effective 06 30 94 PAGE DATE lg 2g Si 6i 8i 9i 11 13/15 18i February 1987 21@ 24i 25i 36 52-8li 86-116 44'7 49/

3i 4i 7i 10'4'9i 20i 22'3i 26 35 December 1987 45'6i 50'1 i 82 85 January 1988

• 29 May 1988 (Reissue)

• 64, 77, 78 May 27, 1988 (Reissue) ig 22Bp 124g 112 February 1990 ii iig iii,22Ag 19@ 21@ 25@ 26@

12 16i 18'8 40i 45 47 i 52 i 55i 59 89i 92i 93'7 129i June 1990 91-93, 95 June 1992 3i 4 21@ 92i 95a-c February 1993 10, 16-20 March 1993 5J 13'8i 20'5 30i 65i 79 June 1993 66, 69 December 1993 16, 69 June 1994 Unit 1 ODCM Revision 14 004152LL June 1994

ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS Pacae

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis 2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 Liquid Radwaste Effluent Alarm Setpoint 2.1.4 Discussion 2.1;4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 'Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2 1.4.5

~ Service Water System Contamination 2 ' Liquid Effluent Concentration Calculation 2.3 Dose Determinations 2.3.1 Maximum Dose Equivalent Pathway 3.0 GASEOUS EFFL'UENTS 10 3.1 Setpoint Determinations 10 F 1 1 Basis 10 3.1.2 Stack Monitor Setpoints 10 3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints 12 3.1.4 Emergency Condenser Vent Monitor Setpoint 13 3.1.5 Discussion 13 3.1.5 ' Stack Effluent Monitoring System Description 13 3.1.5.2 Stack Sample Flow Path >> RAGEMS 13 3.1.5.3 Stack Sample Flow Path - OGESMS 14 Unit 1 ODCM Revision 14 004152LL June 1994

ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)

Pacae 3~1 5.4 Sample Frequency/Sample Analysis 14 3.1.5.5 I-133 Estimates 14 3.1.5.6 Gaseous Radwaste Treatment System Operation 15 3' Dose and Dose Rate Determination 15 3.2. 1- Dose Rate 16 3.2.1.1 Noble Gases 16 3.2.1.2 Tritium, Iodines and Particulates 18 3.2.2 Dose 19 3.2.2.1 Noble Gas Air Dose 19 3.2-2.2 Tritium Iodines and Particulates 20 3.2.2.3 Accumulating Doses 21 3' Critical Receptors 21 3.4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 22 4.0 40 CFR 190 REQUIREMENTS 23 4.1 Evaluation of Doses From Liquid Effluents 24 4' Evaluation of Doses From Gaseous Effluents 25 4.3 Evaluation of Doses From Direct Radiation 26 4.4 Doses to Members of the Public Within the Site Boundary 26 5.0 ENVIRONMENTAL MONITORING PROGRAM 29 5.1 Sampling Stations 29 5.2 Interlaboratory Comparison Program 29 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements 30 Unit 1 ODCM Revision 14 004152LL June 1994

ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd).

Pacae Table 1-1 Average Energy Per Disintegration 32 Tables 2-1 A Values for the NMP-1 Facility 33 to 2-8 Table 3-1 Critical Receptor Dispersion Parameters for Ground Level and Elevated Releases 41 Table 3-2 Gamma Air and Whole Body Plume Shine Dose Factors for Noble Gases (B, and Vi) 42 Table 3-3 Immersion Dose Factors for Noble Gases 43 Tables 3-4 to 3-22 Organ Dose and Dose Rate Factors (Q) 44 Table 3>>23 Parameters for the Evaluation of Doses to Real Members of the Public from Gaseous and Liquid Effluents 63 Table 5.1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations 64 Figure 5.1-1 Nine Mile Point On-Site Map 68 Figure 5.1-2 Nine Mile Point Offsite Map 69 Figure 5.1.3-1 Site Boundaries 70 Appendix A Liquid Dose Factor Derivation (~) 71 Appendix B Plume Shine Dose Factor Derivation (B( and V)) 74 Appendix C Organ Dose and Dose Rate Factors for Iodine - 131 6 133, Particulates and Tritium (g) 78 Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 88 Unit 1 ODCM Revision 14 004152LL -iii- June 1994

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS), 10 CFR 20, 10 CFR 50, and 40 CFR 190. The contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," September 1982; Draft NUREG-0473, Revision 2, "Radiological Effluent Technical Specifications for BWR's", "July 1979'UREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978; the several Regulatory Guides referenced in these documents; and, communication with the NRC staff.

Section 5 contains a detailed description of the Radiological Environmental Monitoring (REM) sampling locations.

Should it be necessary to revise th'e ODCM, these revisions will be made in accordance with Technical Specifications.

Unit 1 ODCM Revision 14 004152LL June 1994

2 ~0 LIQUID EFFLUENTS Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2. Setpoints for the Service Water System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste release or other identified probable source.

Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides identified in each batch of liquid waste prior to its release.

After release, the Liquid Radwaste monitor setpoint may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report, or install blank flange in the discharge line and declare inoperable in accordance with the technical spec ification.

Since the Service Water System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the alarm setpoints are calculated by using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher) in the E<(pCi/ml)+ expression (Section 2.1.2, 2.1.3).

The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding MPC values for the same isotopes, whichever are higher) including tritium and other non-gamma emitters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits.

2' ~ 2 Service Hater System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Water System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:

Setpoint (Hi alarm) <0.9 Z Ci ml CF TDF F + background I

[(pCi/ml)n MPC,]

Setpoint (Alert alarm) <0.7 Z Ci ml . CF TDF F + background l

[(pC ml)z MPC,]

(pCi/ml) > concentration of gamma emitting isotope i the sample, or the corresponding MPC of gamma in emitting isotope (units ~ pCi/ml).

i (MPC)whichever is higher (pCi/ml) n concentration of any radioactive isotope the sample including tritium and other i in non-gamma emitters or corresponding MPC of isotope i, MPC whichever is higher (units ~

pCi/ml ) .

TDF Total Dilution Flow (units = gallons/minutes).

Service Water Flow (units = gallons/minutes).

Unit 1 ODCM Revision 14 004152LL June 1994

2.1 ~ 2 Service Water System Effluent Line Alarm Setpoint (Cont'd)

CF monitor calibration factor (units = net cpm/pCi/ml ) .

liquid effluent radioactivity concentrations MPH limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

Sample Those nuclides present in the previous batch release from the liquid radwaste effluent system or those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units = pCi/ml) or those nuclides present in the service water system.**

(MPC)N same as MPC, but for gamma emitting nuclides only.

0.9 and 0.7 factors of conservatism to account for inaccuracies.

Z~ [ (pCi/ml ) z/MPC,) = Required Dilution Factor. I f MPC values are used in the (pCi/ml)+, they must also be used in calculating RDF (numerator).

TDF/F~ Actual Dilution Factor 2,1.3 Liquid Radwaste Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:

E I f (pCi/ml) n'/MPCi)

E

/ [ (pCi/ml ) n/MPC()

(pCi/ml) + concentration of gamma emitting isotope sample or the corresponding MPC of gamma emitting i in the isotope i, (MPC), whichever is higher.

(pCi/ml concentration of any radioactive isotope sample including tritium and other non-gamma i in the emitters or the corresponding MPC of isotope whichever is higher. (units i MPC, pCi/ml).

TDF Total Dilution Flow (units = gallons/minutes).

Radwaste Effluent Flow (units = gallons/minutes).

CF monitor calibration factor (units = net cps/pCi/ml).

• • For periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.

Unit 1 ODCM Revision 14 June 1994

2 ' ~ 3 Liquid Radwaste Effluent Line Alarm Setpoint (Cont'd) liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR MPC<

20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis of the contents of the radwaste tanks to be released.

(units = pCi/ml)

(MPC) I same as MPC, but for gamma emitting nuclide only.

0.9 and 0.7 factors of conservatism to account for inaccuracies.

E[(pCi/ml)z/MPC,] = Required Dilution Factor. If MPC values are used in the (pCi/ml), they must also be used in calculating RDF (numerator).

Notes: (a) If TDF/F Z,[(pCi/ml)n/MPC;)

the discharge could not be made, since the monitor would be continuously in alarm. To avoid this situation, F will be reduced (normally by a factor of 2). to allow setting the alarm point at a concentration higher than tank concentration. This will also result in a discharge canal concentration at approximately 50%

maximum permissible concentration.

(b) The value used for TDF will be reduced by the fractional quantity (1-FT), where FT is tempering fraction (i.e., diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).

2.1.4 Discussion 2 '.F 1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only on a batch mode. To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (blank flange installed or di.scharge valve chain-locked closed) following the completion of a batch release or series of batch releases.

This mechanical isolation remains in place and will only be removed prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-1A are performed and monitor setpoints have been properly adjusted.

2.1.4.2 Simultaneous Discharges of Radioactive Liquids.

If during the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor is inoperable) the discharge shall be terminated immediately. The liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high grab sample analysis result) has been determined and the appropriate corrective measures taken to ensure 10CFR20, Appendix B, Table II, Column 2 (Technical Specification Section 3.6.15.a(1)) limits are not exceeded.

Unit 1 ODCM Revision 14 004152LL June 1994

2.1.4.2 Simultaneous Discharges of Radioactive Liquids (Cont'd)

In accordance with Site Chemistry procedures, controls are in place to preclude a simultaneous release of liquid radwaste batch tanks.

In addition, an independent verification of the discharge valve line-up is performed prior to discharge to ensure that simultaneous discharges are prevented.

2 '.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing of each batch of liquid radwaste prior to sampling.

Liquid Radwaste Tanks scheduled for discharge at Nine Mile Point Unit 1 are isolated (i.e. inlet va'ives marked up) and at least two tank volumes of entrained fluids are recirculated prior to sampling. Minimum recirculation time is calculated as follows:

Minimum Recirculation Time ~ 2.0(T/R)

Where:

2.0 = Plant established mixing factor, unitless T Tank volume', gal R ~ Recirculation flow rate, gpm Additionally, the Hi, Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70% of its calculated response to the grab sample or corresponding MPC values. Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.

2~'.4.4

~ ~ Liquid Radwaste Systems Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15.

Utilization of the radwaste system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks: \

1) Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin. (See Fig. B-1)

2) High Conductivity (Floor Drains): Waste Evaporator (See Fig. B-1)

Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the .release of each batch of liquid waste. This same dose projection of Section 2.3 will also be performed in the event that untreated liquid waste is discharged, to ensure that the dose limits of Technical Specification 3.6.15.a(2) are not exceeded. (Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Objective given in Section II-D of Appendix I to 10 CFRSO).

Unit 1 ODCM Revision 14 004152LL June 1994

2 '.4 ' Liquid Radwaste Systems Operation (Cont'd)

For the purpose of dose projection, the following assumptions shall be made with regard to concentrations of non-gamma emitting

~ radionuclides subsequently analyzed off-site:

a) [H-3] 6 H-3 Concentration found recent condensate storage tank analysis b) [Sr-89] S 4 x Cs-137 Concentration c) [Sr-90] s 0.5 x Cs-137 Concentration d) [Fe-55] s 1 x Co-60 Concentration Assumed Scaling Factors used in b, c, and d above represent conservative estimates derived from analysis of historical data from process was'te streams. Following receipt of off-site H-3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations and actual tank volumes discharged.

2 ~ 1 ~ 4.5 Service Water System Contamination Service water is normally non-radioactive. If contamination is suspected, as indicated by a significant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLD requirements of Technical Specification Table 4.6.15-1 completed. If it is determined that an inadvertent radioactive discharge is occurring from the service water system, then:

a) A 50.59 safety evaluation shall be performed (ref. IGE Bulletin 80-10)i b) daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c) an incident composite shall be prepared for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and, d) dose projections shall be performed in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by supervision at the time of the incident).

Additionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.

2 ~2 Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.1.5.a (1).

The concentration of radioactive material released in liquid effluents to unrestricted areas (see Figure B-7) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/milliliter (pCi/ml) total activity.

Unit 1 ODCM Revision 14 004152LL June 1994

2' Liquid Effluent Concentration Calculation (Cont'd)

The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Water System and emergency condenser start<<up vent discharges are included in the calculation.

The calculation is performed for a specific period of time. No credit taken for averaging over the calendar year as permitted by 10CFR20.106. The limiting concentration is calculated as follows:

MPC Fraction = E~[(E, CF,)/(MPC) E, F,) )

Where:

MPC Fraction The limiting concentration of 10 CFR 20, Appendix B, Table or II, entrained for radionuclides other than dissolved noble gases.. For noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.

C.=(pCi/ml) ~ The concentration of nuclide effluent stream s, pCi/ml.

i in particular F, The flow rate of a particular effluent stream s, gpmo MPCi The limiting concentration of a specific nuclide i from 10CFR20, Appendix B, Table II, Column 2 (noble gas limit is 2E-4 pCi/ml).

Z,(pCi/ml)>F,) = The total activity rate of nuclide i, in all effluent streams s.

The total flow rate of all effluent streams s, gpm P

Z,(F,)

(including those streams which do not contain radioactivity).

A value of less than one for MPC fraction is considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).

2.3 Dose Determination 2 ~3 ~1 Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Point Unit 1 facility by Charles T. Main, Inc., of Bostoni MA This. report presented the calculated dose equivalent rates to individuals as well as the population within a 50-mile radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1 July 1980 through 31 December 1980 and from January 1981 through 31 December 1981. The radwaste liquid releases are based on a canal discharge rate of 590 ft~/sec which affects near field and far field dilutiony therefore, this report is specific to this situation. Utilizing the effluent data contained in the Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the environmental pathway models specified in Regulatory Guides 1.109 and 1.111 as incorporated in the NRC computer codes LADTAP for.

liquid pathways, and XOQDOQ and GASPAR for gaseous effluent pathways. Dose equivalent rates were calculated for the total body as well as seven organs and/or tissues for the adult, teen, child, and infant age groups. From the standpoint of liquid effluents, the pathways evaluated included fish and drinking water ingestion, and external exposure to water and sediment.

Unit 1 ODCM Revision 14 004152LL June 1994

2.3.1 Maximum Dose Equivalent Pathway (Cont'd)

The majority of the dose for a radwaste liquid batch release was received via the fish pathway. However, to comply with Technical Specifications for dose projections, the drinking water and sediment pathways are included. Therefore, all doses due to .liquid effluents are calculated monthly for the fish and drinking water ingestion pathways and the sediment external pathway from all detected nuclides in liquid effluents released to the unrestricted areas to each organ. The dose projection for liquid batch releases will also include discharges from the emergencydosecondenser vent as factor, ~, is applicable, for all pathways. Each age group given in Tables 1-1 to 1-8. To expedite time the dose is calculated for a maximum individual instead of each age group.

This maximum individual will be a composite of the highest dose factor of each age group for each'organ, hence A. The following expression from NUREG 0133, Section 4.3 is used to calculate dose:

Di = Zi (245t.(hTgCgFg) )

Where:

D, The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period (dT), mrem.

hT, = The length of the L th time period over which Cz and Fz are averaged for all liquid releases, hours.

C~ ~ The average concentration of radionuclide, i, in undiluted liquid effluents during time period hT from any liquid release, pCi/ml.

The site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma or beta emitter for a maximum individual, mrem/hr per pCi/ml.

F The near field average dilution factor for C~ during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, unitless.

A values for radwaste liquid batch releases at a "discharge rate of 295 ft~/sec (one circulating water pump in operation) are presented in tables l-l to 1-4. A values for an emergency condenser vent release are presented in tables 1-5 to 1-8. The emergency condenser vent releases are assumed to travel to the perimeter drain system and released from the discharge structure at a rate of

. 33 ft~/sec. See Appendix A for the dose factor A, derivation. To

.expedite time the dose is calculated to a maximum individual. This maximum individual is a composite of the highest dose factor A of each age group a for each organ t and each nuclide i. If a nuclide is detected for which a factor is not listed, then calculated and included in a revision to the ODCM.

it will be All doses calculated in this manner for each batch of liquid effluent will be summed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in the quarter and year of interest. In all cases, the following relationships will holds Unit 1 ODCM Revision 14 004152LL June 1994

2 ~ 3.1 Maximum Dose Equivalent Pathway (Cont'd)

For a calendar quarter:

D, < 1.5 mrem total body D, < 5 mrem for any organ For the calendar year:

D, < 3.0 mrem total body D, < 10 mrem for any organ Where:

D, total dose received to the total body or any organ due to liquid effluent releases.

If these limits are exceeded, a special report will be submitted to the NRC identifying the cause and proposed corrective actions. In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits contained in 40 CFR 190 have been exceeded. Dose limits, as contained in 40 CFR 190 are total body and organ doses of 25 mrem per year and a thyroid dose of 75 mrem per year.

These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation. The liquid pathway analysis will only include the fish and sediment pathways since the drinking water pathway is insignificant. This pathway is only included in the station's effluent dose projections to comply with Technical Specifications. Liquid, gaseous and direct radiation pathway doses will consider the James A.

FitzPatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear Station.

In the event the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have been exceeded, then a report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15.d of the Technical Specifications.

Section 4.0 of the ODCM contains more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.

Unit 1 ODCM Revision 14 004152LL June 1994

GASEOUS EFFLUENTS Setpoint Determinations Basis Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release rate. The setpoints will be activated if the instantaneous dose rate at or beyond the (land) site boundary would exceed 500 mrem/yr to the whole body or 3000 mrem/yr.to the skin from the continuous release of radioactive noble gas in the gaseous effluent.

Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits .for annual release rate over the projected longest period of release.

Monitor setpoints from continuous release points will be determined once per quarter under normal release rate conditions and will be based on the isotopic composition of the actual release in progress, or an offgas isotopic distribution or a more conservative default composition specified in the pertinent procedure. If the calculated setpoint is higher than the existing setpoint, mandatory that the setpoint be changed.

it is not Monitor setpoints for emergency condenser vent monitors are conservatively fixed at 5 mr/hr for reasons described in Sections 3.1.4 and therefore do not require periodic recalculations.

Under abnormal site release rate conditions, mo'nitor alarm setpoints from continuous release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by CORM Supervision. In particular, contributions from both JAF and NMP-2 and the Emergency Condenser Vents shall be assessed.

J During outages and until power operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be Usede Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to exceeding the corresponding total body dose rates.

The skin dose rate limit is not used in setpoint calculations because it is never limiting.

3 '.2 Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures. These methods shall apply the following general criteria:

(1) Rationale for Stack monitor settings is based on the general equation:

release rate actual = release ate max. allowable corresp. dose rate, actual corresp. dose rate, max. allowable Z..

lQi(VI+(SF) I(~/9) ~ ) 500 mrem/yr Unit 1 ODCM Revision 14 004152LL June 1994

3.1.2~ Stack Monitor Setpoints (Cont'd)

Where:~ k Q<

~

release rate for each isotope i, pCi/sec.

V( gamma whole body dose factor in units of mrem/yr per pCi/sec. (See Table 3-2).

instantaneous release rate limit pCi/sec.

(2) To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the Hi Hi alarms on the stack monitors shall be set lower than or equal to (0.9) (Q) . Hi alarms shall be set lower than or equal to (0.5) (Q)

(3) Based on the above conservatism, the dose contribution from JAF and NMP-2 can usually be ignored. During Emergency Classifications at JAF or NMP-2 due to airborne effluent, or after emergency condenser vent releases of significant proportions, the 500 mrem/yr value may be reduced accordingly.

(4) To convert monitor gross count rates to pCi/sec release rates, the following general'formula shall be applied:

(C -B) K, = Q = pCi/sec, release rate Where:

C monitor gross count rate in cps or cpm B monitor background count rate K, stack monitor efficiency factor with units of pCi/sec-cps or pCi/sec-cpm (5) Monitor K, factors shall be determined using the general formulas K, = E,Q;/(C -B)

Where:

Q, = individual radionuclide stack effluent release rate as determined by isotopic analysis.

K, factors more conservative than those calculated by the above methodology may be assumed.

Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used to calculate k,:

1/K, ~ E = E F Z Y 3. E4da f f Sec.-pCi Where:

f = stack flow in cc/sec.

E = efficiency in units of cpm-cc/pCi or cps-cc/pCi (cpm = counts per minute; cps = counts per second).

E = cpm-cc/bps or cps-cc/@ps.

From energy calibration curve produced during NIST traceable primary gas calibration or transfer source calibration (bps ~ beta per second;

@ps = gammas per second).

Unit 1 ODCM Revision 14 004152LL June 1994

3.1+2 Stack Monitor Setpoints (Cont'd)

Yg = b/d (betas/disintegration) or Y/d (gammas/disintegration).

F, i Activity fraction of nuclide in the mixture.

i ~ nuclide counter.

k = discrete energy beta or gamma emitter per nuclide counter.

s = seconds.

This monitor calibration method assumes a noble gas distribution typical of a recoil release mechanism. To ensure 'that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in the calculation.

3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints (1) The Hi-Hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec. This alarm point may be set equal to or less than 1 Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation.

(2) The Hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec. According to the Unit 1 Technical Specifications, Note (C) to Table 4.6.14-2, the channel functional test of the condenser air ejector radioactivity monitor shall demonstrate that automatic isolation of this pathway occurs if either of the following conditions exist:

i) Instruments indicate two channels above the Hi>>Hi alarm setpoint, ii) Instruments indicate one channel above Hi-Hi alarm setpoint and one channel downscale.

This automatic isolation function is tested once per operating cycle in accordance with station procedures.

(3) To convert monitor mR/hr readings to pCi/sec, the formula below shall be applied:

(R) (K) = QpCi/sec recombiner discharge release rate Where:

R = mR/hr monitor indicator.

Kg efficiency factor in units of pCi/sec/mR/hr determined prior to setting monitor alarm points.

(4) Monitor KR factors shall be determined using the general formula:

KR = E)Q;/R Where:

Q, = individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.

K factors more conservative than those calculated by the above methodology may be assumed.

Unit 1 ODCM Revision 14 004152LL June 1994

3.1o3 Recombiner Discharge (Off Gas) Monitor Setpoints (Cont'd)

(5) The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part 50). Additionally, these setpoints serve to limit buildup of fission product activity within the station systems which would result extended periods.

if high fuel leakage were to be permitted over 3 ~1~4 Emergency Condenser Vent Monitor Setpoint The monitor setpoint was established by calculation ("Emergency Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC File Code f16199). Assuming a hypothetical case with (1) reactor water iodine concentrations higher than the Technical Specification Limit, (2)

reactor water noble gas concentrations higher than would be expected at Technical Specification iodine levels, and (3) leakage of reactor steam into the emergency condenser shell at 300% of rated flow (or 1.3 E6 lbs/hr), the calculation predicts an emergency condenser vent monitor response of 20 mR/hr. Such a release would result in less than 10 CFR 20 dose rate values at the site boundary and beyond for typical emergency condenser cooldown periods.

Since a 20 mR/hr monitor response can, in theory, be achievable only when reactor water iodines are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been adopted.

3.1

~ ~ 5 Discussion 3.1 5.1

~ Stack Effluent Monitoring System Description The NMP-1 Stack Effluent Monitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEMS) and the old General Electric Stack Monitoring System (OGESMS). During normal operation, the OGESMS shall be used to monitor station noble gas effluents and collect particulates and iodine samples in compliance with Technical Specification requirements.

The RAGEMS is designed to be promptly activated from the Main Control Room for use in high range monitoring during accident situations in compliance with NUREG 0737 criteria. Overall system schematic for the OGESMS and RAGEMS are shown on Figure B-9. A simplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure B-8.

The RAGEMS can provide continuous accident monitoring and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specification Table 4.6.15-2 limits.

Activities as low as 5.0E-8 and as high as 2.0E5 pCi/cc for noble gases are detectable by the system.

3 '.5 2 Stack Sample Flow Path - RAGEMS The effluent sample is obtained inside the stack at elevation 530'sing an isokinetic probe with four orifices. The sample line then bends radially out and back into the stack; descends down the stack and out of the stack at approximately elevation 257'; runs horizontally (enclosed in heat tracing) some 270'long the off gas tunnel; and enters the RAGEMS located on the Turbine Building 250'Dilution cabinet Unit 0) and Off Gas Building 247'Particulate, Iodine, Noble Gas stations Units 1-3).

Unit 1 ODCM Revision 14 004152LL June 1994

Stack Sample Flow Path - RAGEMS (Cont'd)

In the Dilution cabinet of the'RAGEMS, the stack gas may be diluted during accident si.tuations approximately 100-200X (first stage) or 10000-40000 X (first and second stage) with gaseous ni.trogen supplied from an on-si.te liquid nitrogen storage tank (see Figure B-9).

From Unit 0, the sample gas enters Unit 1-3 of RAGEMS and flows thru in-line particulate and iodine cartridges and then thru either a 6 liter (low range) or 30 cc (high .range) noble gas chamber. The sample gas next flows back thru Unit 0 and the off gas tunnel; and back into the stack.

3 ' ' ' Stack Sample Flow Path - OGESMS The OGESMS sample is obtained from the same stack sample probe as the the exit of the stack at elevation 257', the sample line RAGEMS. From runs east approximately 20'nd then vertically approximately 8'o the OGESMS skid. In the OGESMS, sample flows thru a particulate/iodi.ne cartridge housing and four noble gas scintillation detectors (i.e., 07 and 08 low range beta detectors and RN-03A and RN-03B high range gamma detectors). From OGESMS, the stack sample flows back into the stack at approximately elevation 257'.

All OGESMS detector outputs are monitored and recorded remotely in the Main Control Room. Alarming capabilities are provided to alert Operators of high release rate conditi.ons prior to exceeding Technical Speci.fication 3.6.15.b (1) a dose rate limits.

Stack particulate and iodine samples are retrieved manually from the OGESMS and analyzed in the laboratory using gamma spectroscopy at frequencies and LLDs specified in Table 4.6.15-2 of the Technical Specifications.

3.1

~ ~ 5 '

~ Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utili.zed, radioactive gaseous wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2. Particulate samples are saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr-90 at monthly intervals minimally. The latter three analyses are performed off-site from a composite sample. Sample analysis frequencies are increased during elevated release rate conditions, followi.ng startup, shutdown and in conjunction with each drywell purge.

Consistent with Technical Specification Table 4.6.15-2, stack effluent tritium is 'sampled monthly, during each drywell purge, and weekly when fuel is off loaded until stable release rates are demonstrated. Samples are analyzed off-site.

Line loss correction factors are applied to all particulate and iodine results. Correction factors of 2.0 and 1.5 are used for data obtained from RAGEMS and OGESMS respectively. These correction factors are based on empirical data from sampling conducted at NMP-1 i.n 1985 (memo from J.

Blasiak to RAGEMS File, 1/6/86, "Stack Sample Representativeness Study:

RAGEMS versus In-Stack Auxiliary Probe Samples" ).

3 'o5 ~ 5 I-133 Estimates Monthly, the stack effluent shall be sampled for iodines over' 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the I-135/I-131 and the I-133/I-131 ratios calculated. These ratios shall be used to calculate I-133, I-135 release for longer acquisition samples collected during the month.

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3.1.5 ' I-133 Estimates (Cont'd)

Additionally, the I-135/I-131 and I-133/I-131 ratios should also be determined after a significant change in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).

3 ~ 1.5 ~ 6 Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3.6.15.b.

To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as applicable, cumulative dose contributions for the current calendar quarter and current calendar year shall be determined monthly in accordance with section 3.2 of this manual. Initial dose calculations shall incorporate the following assumptions with regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:

a) H-3 release rate 5 4 pCi/sec b) Sr>>89 release rate .'5 4 x Cs-137 release rate c) Sr-90 release rate S 0.5 x Cs-137 release rate d) Fe-55 release rate S 1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NMP 34023, C. Ware to J. Blasiak, April 29, 1988, "Dose Estimates for Beta-Emitting Isotopes" ). Following receipt of off-site H<<3, Sr-89, Sr-90, Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(1), 4.6.15.b.(2), and 4.6.15.b.(3) dose and dose rate determinations will be made monthly to determine:

(1) Total body dose rates and gamma air doses at the maximum X/Q land sector site boundary interface and beyond.

(2) Skin dose rates and beta air doses at the maximum X/Q land sector site boundary interface and beyond.

(3) The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at a critical receptor location beyond the site boundary.

Average meteorological data (ie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases) shall be utilized for dose and dose rate calculations. Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the site boundary will be lower than equivalent site boundary dose and dose rates. Therefore, under these conditions, calculations of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected.

The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.

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Dose and Dose Rate Determinations (Cont'd)

Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened for reactor cooldown, if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened, or if significant activity is detected in the Emergency Condenser Shell.

Without tube leakage dose contributions from emergency condenser vent releases are to be determined based on condensate storage tank and emergency condenser shell isotopic distributions.

When releases from the emergency condenser have occurred, dose rate and dose determinations shall be performed using methodology in 3.2.1 and 3.2.2. Furthermore, environmental sampling may also be initiated to refine any actual contribution to doses. See Section 3.4.

Critical organ doses and dose rates may,be conservatively calculated by assuming the existence of a maximum individual. This individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide. It is assumed that all pathways are applicable and the highest X/Q and/or D/Q value for actual pathways as noted in Table 3-1 are in effect. The maximum individual's dose is equal to the same dose that person would receive if they were simultaneously subjected to the highest pathway dose at each critical receptor identified for each pathway. The pathways include grass-(cow and goat)-milk, grass-cow-meat, vegetation, ground plane and inhalation.

To comply with Technical Specifications we will calculate the maximum individual dose rate at the site boundary and beyond at the critical residence.

If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluatedi and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.

3 ~2~1 Dose Rate Dose rates will be calculated monthly, at a minimum, or when the Hi-Hi stack monitor alarm setpoint is reached, to demonstrate that dose rates resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10CFR.20. These'limits are:

Noble Gases Whole Body Dose Rate: 500 mrem/yr Skin Dose Rate: 3000 mrem/yr Tritium Iodines and Particulates Organ Dose Rate: 1500 mrem/yr 3.2 1. 1 Noble Gases The following noble gas dose rate equation includes the contribution from the stack (s) elevated release and the emergency condenser vent (v) ground level release when applicable (See section 3.2).

To ensure that the site noble gas dose rate limits are not exceeded, the following procedural actions are taken from Unit 1 exceed 10% of the limits:

if the offsite dose rates

1) Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.

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3.2.1.1 Noble Gases (Cont'd)

2) Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.

3) Notify the SSS of the James A. Fitzpatrick Nuclear Plant and request the Fitzpatrick contribution to offsite dose.

4) Increase the frequency of performing noble gas dose calculations, if necessary, to ensure Site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.

Additionally, alarm setpoints are set at 50% of the dose rate limit to ensure that site limits are not exceeded. This alarm setpoint is adjusted the limit.

if the noble gas dose rate from Unit 1 is greater than 10% of For total body dose rates (mrem/sec):

DR(mrem/sec) = 3.17E-SZ)[(V~ + (SF)Q(X/Q) ~ )Q+ (SF)Q (X/Q)Q ]

For skin dose rates (mrem/sec):

DR,~p(mrem/sec)= 3.17E-SE,[(L,(X/Q), + 1.11(SF) (B( + g(X/Q) ~ ))Q +

... (L; + 1.11(SF)M;) (X/Q)Q.)

Where:

DR total body gamma dose rate (mrem/sec).

DR +p skin dose rate from gamma and beta radiation (mrem/sec).

V) the constant accounting for the gamma whole body dose rate from stack radiation for an elevated finite plume releases for each identified noble gas nuclide, i.

Listed on Table 3-2 in mrem/yr per pCi/sec.

the constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per pCi/m ( from Reg. Guide 1. 109)

Q iQ. the release rate of isotope i from the stack(s) or vent(v); (pCi/sec)

SF structural shielding factor.

X/Q the relative plume concentration (in units of sec/m') at the land sector site boundary or beyond. Average meteorological data (Table 3-1) is used. "Elevated" X/Q values are used for stack releases (s = stack); "Ground" X/Q values are used for Emergency Condenser Vent releases (v = vent).

Li the constant accounting for the beta skin dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per pCi/m~ ( from Reg. Guide 1. 109)

B; the constant accounting for the air gamma radiation from the elevated Finite plume resulting from stack releases for each identified noble gas nuclide, i. Listed in Table 3-2 in mrad/yr per pCi/sec.

Unit 1 ODCM Revision 14 004152LL June 1994

3.2.1.1 Noble Oases (Cont'd) the constant accounting for the gamma air dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per pCi/m~ (from Reg. Guide 1.109)

See Appendix B for derivation of B, and V,.

3 ~ 2 ~ 1.2 Tritium, Zodines and Particulates To ensure that the 1500 mrem/year site dose rate limit is not exceeded, offsite dose rates for tritium, iodine and particulates with half lives greater than 8 days shall be calculated monthly and when release rates (Q) exceed 0.34 pCi/sec using the following equation.

D~ (mrem/sec) = 3.17E-BEj[E, R~ [W, Q + W Q.])

Where:

Total dose rate to each organ k of an individual in age group a (mrem/sec).

Wj dispersion parameter either X/Q (sec/m~) or D/Q (1/m~)

depending on pathway and receptor location assumed.

Average meteorological data is used (Table 3-1).

"Elevated" Wj values are used for stack releases (s = stack); "Ground" Wj values are used for Emergency Condenser Vent releases (v = vent).

the release rate of isotope i, from the stack (s) or vent(v); (pCi/sec).

the dose factor for each isotope i, pathway ), age group a, and organ k (Table 3-4, through 3-22; m'-mrem/yr per pCi/sec for all pathways except inhalation, mrem/yr per pCi/m~. The R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision li as presented in Appendix C.

3.17E-8 = the inverse of the number of seconds in a year.

When the release rate exceeds 0.34 pCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

The use of the 0.34 pCi/sec release rate threshold to perform dose rate calculations is )ustified as follows:

(a) The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.34 pCi/sec calculated using the equation:

1500 ~ (Q, pCi/sec) x (+Wj)

Where:

1500 site boundary dose rate limit (mrem/year).

(RgWj) the maximum curie-to-dose conversion factor equal to 4.45E3 mrem-sec/pCi-yr for Sr-90, child bone at the critical residence receptor location beyond the site boundary.

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3.2.1.2 Tritium, Iodines and Particulates'(Cont'd)

(b) The use of 0.34 pCi/sec release rate threshold and the 4.45E3 mrem-sec/pCi-yr curie-to-dose conversion factor is conservative since curie-to-dose conversion factors for other isotopes likely to be present are significantly lower.

In addition, if the organ dose rate exceeds 5% of the annual limit, the following procedural actions will be taken:

1) Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.

2) Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.

3) Notify the SSS of the James A. Fitzpatrick contribution to offsite dose.

4) Increase the frequency of performing dose calculations if necessary to ensure site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.

3 ~2 ~2 Dose Calculations will be performed monthly at a minimum, to demonstrate that doses resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I. These limits are:

Noble Gases 5 mR gamma/calendar quarter 10 mrad beta/calendar quarter 10 mR gamma/calendar year 20 mrad beta/calendar year Tritium Iodines and Particulates 7.5 mrem to any -organ/calendar quarter 15 mrem to,any organ/calendar year 3.2.2.1 Noble Gas Air Dose The following Noble Gas air dose equation includes contributions from the stack (s) elevated release and the emergency condenser vent (v) ground level release when applicable (see section 3.2):

For gamma radiation'mrad):

D (mrad) 3. 17E-BE,(M,(X/Q) Q+ (B; + g(X/Q),) Q.) ~ t For beta radiation (mrad):

D>(mrad) ~ 3.17E-SE~N,[(X/Q)Q+ (X/Q), Q) ~ t Where:

gamma air dose (mrad).

beta air dose (mrad).

Note that the units for the gamma air dose are in mrad compared to the units for the limits are in mR. The NRC recognizes that 1 mR=1 mrad, for gamma radiation.

Unit 1 ODCM Revision 14 004152LL June 1994

3.2 ~ 2~1 Noble Gas Air Dose (Cont'd)

'I B( the constant accounting for the air gamma radiation from the elevated finite plume resulting from stack releases for each identified noble gas nuclide, i. Listed in Table 3-2 in mrad/yr per pCi/sec.

N, The constant accounting for the air beta dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed on Table 3-3 in mrad/yr per pCi/m (from Reg. Guide 1.109).

Q., Q. = the release rate of isotope i, from the stack (s) or vent (v); (pCi/sec) .

3. 17E-8 = the inverse of the number of seconds in a year.

.the constant accounting for the air gamma dose from immersion in the semi-infinite cloud for each identified noble pas nuclide, i. Listed on Table 3-3 in mrad/yr per pCi/m (from Reg. Guide 1.109).

total time during release period, sec.

All other parameters are as defined in section 3.2.1.1.

3.2.2.2 Tritium, Zodines and Particulates To ensure that the 15 mrem/yr facility dose limit is not exceeded, offsite doses for tritium, iodines, and particulates with half lives greater than 8 days shall be calculated monthly using the following equation:

D~ (mrem) 3 17E SZj[E, ~ [W, Q+ WQ) ) ~ t Where:

total dose to each organ k of an individual in age group a(mrem).

Wj dispersion parameter either X/Q (sec/m~) or D/Q (1/m~)

depending on pathway and receptor location assumed.

Average meteorological data is used (Table 3-1) .

"Elevated" Wj values are used for stack releases (s ~ stack); "Ground" Wj values are used for Emergency Condenser Vent releases (v ~ vent).

Q iQ the release rate of isotope i from stack(s) or vent (v); (pCi/sec) .

the dose factor for each isotope i, pathway j, age group a, and organ k (Tables 3-4, through 3-22; m~-mrem/yr per pCi/sec). R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1; as presented in Appendix C.

3.17E-S the inverse of the number of seconds in a year.

total time during the release period, sec.

Unit 1 ODCM Revision 14 004152LL June 1994

3 ' '.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air, beta air, and the critical organ for each age group. Dose estimates will, also, be calculated monthly prior to receipt of any offsite analysis data i.e., strontium, tritium, and iron-55. Results will be summed for each calendar quarter and year.

The critical doses are based on the following:

noble gas plume air dose direct radiation from, ground plane deposition inhalation dose cow milk ingestion dose goat milk ingestion dose cow meat ingestion dose vegetation (food crops) ingestion dose The quarterly and annual results shall be compared to the limits listed in paragraph 3.2.2. If the limits are exceeded, special reports, as required by Section 6.9.3 of the Technical Specification, shall be submitted.

3 ' Critical Receptors, In accordance with the provisions of 10 CFR 20 and 10 CFR 50/

Appendix I, the critical receptors have been identified and are contained in Table 3-1.

For elevated noble gas releases the critical receptor is the site boundary.

When 1985 average annual X/Q values are used for ground level noble gas releases, the critical receptor is the maximum X/Q land sector site

\

boundary interface.

For tritium, iodines, and particulates with half lives greater than eight days, the critical pathways are grass-(cow and goat)-milk, grass-cow meat, vegetation, inhalation and direct radiation (ground plane) as a result of ground deposition.

The grass-(cow and goat)<<milk, and grass-cow-meat pathways will be based on the greatest D/Q location. This location has been determined in conjunction with the land use census (technical specification 3.6.22) and is sub)ect to change. The vegetation (food crop) pathway is based on the greatest D/Q garden location from which samples are taken. This location may also be modified as a result of vegetation sampling surveys.

The inhalation and ground plane dose pathways will be calculated at the critical residence.

Because the Technical Specifications state to calculate "at the site boundary and beyond", the doses and/or dose rates must be calculated for a maximum individual who is exposed to all pathways at. the site boundary and at the critical residence. The maximum individual is a composite of the highest dose factor of each age group, for each or'gan and total body, and each nuclide. Since the crit, ical residence location has the greatest occupancy time, the resultant dose at the residence including all pathways is limiting.

However, due to the Technical Specification wording, the inhalation and ground plane dose at the site boundary along with all other pathways, will be calculated assuming a continuous occupancy time.

Unit 1 ODCM Revision 14 004152LL June 1994

3 ~3 Critical Receptors (Cont'd)

Zn lieu of correcting land site boundary ground plane and inhalation dose factors for occupancy time, a Technical Specification change will be submitted to change the requirement from calculating "at the site boundary and beyond" to "at the site boundary or beyond". Unit 1 will then calculate at the, critical residence since this should be the limiting dose. Until this change is effective, the dose and/or dose rate calculations for tritium, iodines, and particulates with half lives greater than 8 days will conservatively assume that the ground plane and inhalation pathway critical receptors are at the site boundary, i.e., X/Q and D/Q, respectively, are calculated at the site boundary.

3.4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases The doses resulting from the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual environmental samples. Ground deposition samples will be obtained from an area or areas of maximum projected deposition.

These areas are anticipated to be at or near the site boundary and near projected plume centerline. Using the methodology found in Regulatory Guide 1;109, the dose will be calculated to the maximum exposed individual. This dose will then be compared to the dose calculated in accordance with 3.2.2. The comparison will result in an adjustment factor of less than or greater than one which will be used to adjust the other doses from other pathways. Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2. Other environmental sample media may include milk, vegetation (such as garden broadleaf vegetables),

etc. The adjustment factors from these pathways may be applied to the doses calculated per 3.2.2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjust calculated doses.

Doses calculated from actual environmental sample media will. be based on the methodology presented in Regulatory Guide 1.109. The regulatory guide equations may be slightly modified to account for short intervals of time (less than one year) or modified for simplicity purposes by deleting decay factors. Deletion of decay factors would yield more conservative results.

Unit 1 ODCM Revision 14 004152LL June 1994

a.o 40 CFR 190 REQUIREMENTS 'I The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:

"Uranium fuel cycle means the operations of milling of uranium orei chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non<<uranium special nuclear and by-product materials from the cycle."

Section 3.6.15.d of the Technical Specifications requires that when the calculated doses associated with the effluent releases exceed twice the applicable quarter or annual limits, the licensee shall evaluate the calendar year doses and, if required, submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources.

is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem). This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190. If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and be taken to reduce subsequent releases.

if possible, action will The report to the NRC shall contain:

1) Identification of all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at the site that contribute to the annual dose of the maximum exposed member of the public.

2) Identification of the maximum exposed member of the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.

The total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 1 will be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the limit was exceeded. The direct dose components will be determined by either calculation or actual measurement. Actual measurements will utilize environmental TLD dosimetry. Calculated measurements will utilize engineering calculations to determine a pro)ected direct dose component. In the event calculations are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specifications.

Unit 1 ODCM Revision 14 004152LL June 1994

40 CFR 190 REQUIREMENTS (Cont'd)

The doses from Nine Mile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site. Other uranium fuel cycle facilities within 5 miles of the Site include Nine Mile Point Nuclear Station Unit 2 and the James A. Fitzpatrick Nuclear Power Plant. Doses from other facilities will be calculated in accordance with each facilities'DOM.

For the purpose of calculating doses, the results of the Radiological Environmental Monitoring Program may be included for providing more refined estimates of doses to a real maximum exposed individual. Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual environmental sample results. Reports will include all significant details of the dose determination if radiological sampling and analyses are used to determine if the dose limits of 40CFR190 are exceeded.

F 1 Evaluation of Doses From Liquid Effluents For the evaluation, of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered. Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways that will be considered. The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data. Because of the nature of the receptor location and the extensive fishing in the area, the critical individual may be a teenager or an adult.

The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area. This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.

Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology.

Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted. This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view. Table 3-23 presents the parameters used for calculating doses from liquid effluents.

The dose from fish sample media is calculated as:

Z( [Cg (U) (D~) f) (1E+3)

Where:

i, j,via fish

~ The total annual dose to organ of an individual of age group a, from nuclide pathway pf in mrem per year.

The concentration 'of radionuclide i in fish samples in pCi/gram.

= The consumption rate of fish in kg/yr.

lE+3 = Grams per kilogram.

Unit 1 ODCM Revision 14 004152LL June 1994

4.1 Evaluation of Doses From Liquid Effluents (Cont'd)

(D~) = The ingestion dose factor for age group a, nuclide i, fish pathway p, and organ Table E-11) (mrem/pCi).

j, (Reg. Guide 1.109,

~ The fractional portion of the year over which the dose is applicable.

The dose from shoreline. sediment sample media is calculated as:

Zi [Cg (U) (4E+4) (0.3) (D~) f) where:

= The of total annual dose to organ j, of an individual nuclide i, via the sediment age group a, from pathway p, in mrem per year.

~ The concentration of radionuclide sediment in pCi/gram.

i in shoreline U ~ The usage factor, (hr/yr) (Reg. Guide 1.109).

4E+4 ~ The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm) times the number of grams per kilogram.

0.3 = The shore width factor for a lake.

D~ ~ ~ The dose factor for age group a, nuclide i, sediment pathway s, and organ j. (Rep. Guide 1.109, Table E-6) (mrem/hr per pci/m ).

~ The fractional portion of the year over which the dose is applicable.

4.2 Evaluation of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered. These include the deposition, inhalation cows milk, goats milk, meat, and food products (vegetation).

However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc. Data from the most recent census 'and sample location surveys should be utilized. Doses may also be calculated from actual environmental sample media, as available. Environmental sample media data such as TLD, air sample, milk sample and vegetable (food crop) sample data may be utilized in lieu of effluent calculational data.

Doses to member of the public from the pathways contained in ODCM section 3.2.2.3 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable. Doses calculated from environmental sample media will be based on the methodologies found in Regulatory Guide 1.109.

Unit 1 ODCM Revision 14 004152LL June 1994

Evaluation of Doses From Direct Radiation The dose contribution as a result of direct radiation shall be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded .

Direct radiation doses as a result of the reactor; turbi ne and radwaste buildings and outside radioactive storage tanks ( as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations, site boundary or other special interest locations . For the evaluation of direct radiation doses utilizing environmental critical receptor in question, such as the critical residence, TLDs,'he etc . , will be compared to the control locations . The comparison involves the difference in environmental TLD results between the receptor location and the average control location result .

4 .4 Doses to Members of the Public Within the Site Boundary The Semi-Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary as defined by Figure 5.1-1 of the specifications. A member of the public, as defined by the Technical Specifications, would be represented by an individual who visits the sites'nergy Center for the purpose of observing the educational displays or for picnicking and associated activities.

Fishing is a major recreational activity in the area and on the Site as a result of the salmonoid and trout populations in Lake Ontario.

Fishermen have been observed fishing at the shoreline near the Energy Center from April through December in all weather conditions. Thus, fishing is the major activity performed by members of the public within the site boundary. Based on the nature of the fishermen and undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Energy Center and the Unit 1 facility. This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.

The pathways considered for the evaluation include the inhalation pathway, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated whole body dose. The direct radiation dose pathway, in actuality, includes several pathways. These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose (as applicable), possible direct radiation dose from the facility and a ground plane dose (deposition). Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

Other pathways, such as the ingestion pathway, are not applicable since these doses are included under calculations for doses to members of the public outside of the site boundary. In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming, boating and wading which are prohibited at the facility.

Unit 1 ODCM Revision 14 004152LL June 1994

. ~

Doses to Members of the Public Within the Site Boundary (Cont'd)

The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period. The radionuclide concentrations are then multiplied by the appropriate X/Q value, inhalation dose factor, air intake rate, and the fractional portion of the year in question.

Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109. Table 3-23 presents the reference for the parameters used in the following equation.

NOTE 4 The following equation is adapted from equations C-3 and C<<4 of Regulatory Guide 1.109. Since many of the factors are in units of pCi/m~, m~/sec., etc., and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Guide equations.

Dj, Zl [ (CI) F (X/Q) (DFA) i~(BR) at]

Where:

The maximum dose from all nuclides to the organ )

and age group (a) in mrem/yr.

The average concentration in the stack release of C,

nuclide i for the period in pCi/m~.

Unit 1 average stack flowrate in m~/sec.

X/Q The plume dispersion parameter for a location approximately 0.50 miles west of NMP-1g the plume dispersion parameter is 8.9E-06 (stack) and was obtained from the C.T. Main five year average annual X/Q tables. The stack (elevated) X/Q is conservative when based on 0.50 miles because of the close proximity of the stack and the receptor location.

(DFA) 0, The dose factor for nuclide i, organ ), and age group a in'mrem per pCi (Reg. Guide 1.109, Table E-7).

(BR) ~ Annual air intake for individuals in age group a in m~ per year (obtained from Table E-5 of Regulatory Guide 1.109).

Fractional portion of the year for which is to be i

radionuclide was detected and for which a dose calculated ('n years).

Unit 1 ODCM Revision 14 004152LL June 1994

~.4 Doses to Members of the Public Within the Site Boundary (Cont'd)

~

The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs. The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1. The resultant dose may be ad)usted for a background dose by subtracting the applicable off-site control soil or shoreline sediment sample radionuclide activities. In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the water (i.e., the use of waders), then the ground dose pathway (deposition) may not be evaluated.

The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, potential submersion in the plume, possible direct radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated by average environmental TLD readings. At least two environmental TLDs will be utilized at one location in the approximate area where fishing occurs. The TLDs will be placed in the field on approximately the beginning of a calendar quarter and removed on approximately the end of the calendar quarter.

For the purposes of. this evaluation, TLD data from quarters 2, 3, and 4 will be utilized.

The average TLD readings will be adjusted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLD value. The applicable quarterly control TLD values will be utilized after ad)usting for the appropriate time period (as applicable). In the event of loss or theft of the TLDs, results from a TLD or TLDs in a nearby area may be utilized.

Unit 1 ODCM Revision 14 004152LL June 1994

5 ~0 ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2. The meteorological tower is shown in Figure 5.1-1.

The location is shown as TLD location 17. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick Nuclear Power Plant, respectively. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982. These dispersion calculations are attached as Appendix E.

The calculated dispersion or deposition parameters will be compared to the results of the annual land use census. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days'f a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.

Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Crosscheck Program. Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which crosscheck samples are available. An attempt will be made to obtain a QC sample to program sample ratio of 5% or better. The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.

Specific sample media for which EPA Cross Check Program samples are available include the following:

gross beta in air particulate filters gamma emitters in air particulate filters

- gamma emitters in milk gamma emitters in water tritium in water

- I-131 in water Unit 1 ODCM Revision 14 004152LL June 1994

Capabilities for Thermoluninescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b of the Technical Specifications are based on ANSI Standard N545,use.

section 4.3. TLDs are defined as phosphors packaged for field In regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the above capabilities per type of TLD. Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs. Required detection capabilities are as follows:

5 ~ 3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 mR/hr during the field cycle. The responses obtained shall have a relative standard deviation of less than 7.5%. A total of at least 5 TLDs shall be evaluated.

5.3.2 Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The average of the relative standard deviations of the responses shall be less than 3.0%. A total of at least 4 TLDs shall be evaluated.

5,3 3 Dependence of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where. the exposure rate is known to be constant. This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures. For these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85. At least 6 TLDs shall be evaluated.

5 '.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV.

The response shall not differ from that obtained with the calibration source by more than 25% for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV. A total of at least 8 TLDs shall be evaluated.

5 ~ 3.5 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations. To accomplish this, the TLD shall be rotated through at least two perpendicular planes. The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10%. A total of at least 4 TLDs shall be evaluated.

5.3 ~ 6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6. The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10%. A total of at least 4 TLDs shall be evaluated for each of the four conditions.

Unit 1 ODCM Revision 14 004152LL June 1994

5 ~3 ~7 Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged for field use) for a period equal to the field cycle in an area where the exposure rate is known to be constant.

The TLDs shall be exposed under two conditions: (1) packaged in a thin, sealed plastic bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle. The TLD or phosphor, as appropriate, shall be dried before readout. The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10%. A total of at least 4 TLDs shall be evaluated for each condition.

5.3.8 Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known. If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3). The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. A total of at least 3 TLDs shall be evaluated.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 1-1 Average Energy Per Disintegration ISOTOPE ~Ref ~Eev die(e ~Ref Ar-41 1.294 (3) 0.464 (3)

Kr-83m 0.00248 0.0371 Kr-85 0.0022 0.250 Kr-85m 0.159 0.253 Kr-87 0.793 1.32 Kr-88 1.95 0.377 Kr-89 2 '2 (2) 1.37 (2)

Kr-90 2.10 (2) 1.01 (2)

Xe-131M 0.0201 0.143 Xe-133 0.0454 0.135 Xe-133m 0.042 0.19 Xe-135 0.247 0.317 Xe-135m 0.432 0.095 Xe-137 0.194 1.64 Xe-138 1.18 0.611 ORNL-4923, Radioactive Atoms Su lement I, M.S. Martin, November 1973.

(2) NEDO-12037, "Summary of Gamma and Beta Emitters and Intensity Data";

M.E. Meek, R.S. Gilbert, January 1970. (The average energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value assumption used in this reference).

(3) NCRP Report No. 58, "A Handbook of Radioactivity Measurements Procedures"; 1978 (4) The average energy. includes conversion electrons.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-1

~ VALUES - LIQUID*

RADWASTE TANK INFANT mrem - ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 2.90E-1 2.90E-1 2.90E-1 2.90E-1 2.90E-1 2.90E-1 Cr 51 1.29E-2 8.39E-3 1.83E-3 1.63E-2 3.75E-1 Cu 64 1.13E-1 5.23E-2 1.91E-1 2.32 Mn 54 1.87E+1 4.23 4.14 6.86 FE 55 1.31E+1 8.44 2 '6 4. 13 l. 07 Fe 59 2.84E+1 4.96E+1 1.96E+1 1.47E+1 2.37E+1 Co 58 3.34 8.34 8.33 Co 60 1.02E+1 2:40E+1 2.42E+1 Zn 65 1.72E+1 5.91E+1 2.73E+1 2.87E+1 5.00E+1 Sr 89 2.32E+3 6.66E+1 4.77E+1 Sr 90 1.74E+4 4.43E+3 2.17E+2 Zr 95 1.91E<<1 4.66E-2 3.30E-2 5.02E-2 2 32E+1 Mn 56 ~- 2.40E-4 4-15E-5 2.07E-4 2.18E-2 Mo 99 2.34E+1 4.57 3.50E+1 7 '1 Na 24 2.37 2.37 2.37 2.37 2 '7 2.37 2 37 I 131 3.03E+1 3.54E+1 1.57E+1 1.17E+4 4.17E+1 1 28 I 133 4.22 6.15 1. 80 1.12E+3 7.23 1.04 Ni 65 1.33E-3 1.51E-4 6.85E-5 1.15E-2 I 132 1.58E-4 3.21E-4 1.14E-4 1.50E-2 3.58E-4 2.60E-4 Cs 134 3.54E+2 6.60E+2 6.67E+1 1.70E+2 6.97E+1 1.79 Cs 136 4.05E+1 1.19E+2 4.45E+1 4.75E+1 9.71E+1 1.81 Cs 137 4.91E+2 5.75E+2 4.07E+1 1 54E+2 6.24E+1 1.80 Ba 140 1.50E+2 1.50E-1 7.74 3.57E-2 9.23E-2 3.69E+1 Ce 141 7 '1E-2 4.40E-2 5.17E-3 1 ~ 36E-2 2.27E+1 Nb 95 3.85E-2 1.59E-2 9.18E-3 1.14E-2 1.34E+1 La 140 1.18E-2 4.67E-3 1.20E-3 5.48E+1 Ce 144 2.79 1.14 1.57E-1 4.62E-1 1.60E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section l.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-2 24, VALUES - LIQUID*

RADWASTE TANK CHILD mrem ml hr - pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 4.39E-l 4.39E-1 4.39E-1 4.39E-1 4.39E-1 4.39E-1 Cr 51 2.13E-2 2.13E-2 1.40 7.86E-1 2.30E-1 1.42 7 '1E+1 Cu 64 2.51E-6 2.70 1.63 2.51E-6 6.52 2.51E-6 1.27E+2 Mn 54 6.92 3.38E+3 9.06E+2 6.92 9.53E+2 6 92 2.84E+3 Fe 55 9.21E+2 4.88E+2 1.51E+2 2.76E+2 9.05E+1 Fe 59 1.30E+3 2.11E+3 1.05E+3 1.34 1.34 6.12E+2 2.19E+3 1.89 7.46E+1 2 '4E+2 1-89 1.89 89 4.26E+2 Co 58 ~

Co 60 1.12E+2 3.28E+2 7.48E+2 1.12E+2 1.12E+2 1.12E+2 1.31E+3 Zn 65 2.15E+4 5.73E+4 3.56E+4 3.85 3 ~ 61E+4 3 85 1.01E+4 Sr 89 3.26E+4 1.10E-4 9.32E+2 1.10E-4 1.10E-4 1 ~ 10E-4 1.26E+3 Sr 90 4.26E+5 1.08E+5 5.74E+3 Zr 95 1.70 1.33 1.32 1.23 1.38 1 ~ 23 1.08E+2 Mn 56 1.65E-1 3.73E-2 2.00E-1 2.39E+1 Mo 99 5.35E-3 9.57E+1 2.37E+1 5.35E-3 2.04E+2 5.35E-3 7.91E+1 Na 24 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 I 131 2.09E+2 2.10E+2 1.19E+2 6.94E+4 3.45E+2 5.60E-2 1 ~ 87E+1 I 133 3.39E+1 4.19E+1 1.59E+1 7.78E+3 6.98E+1 1.38E-4 1.69E+1 Ni 65 2.67E-1 2 '1E-2 1.47E-2 3.08 I 132 6.13E-3 1.13E-2 5.18E-3 5.22E-1 1.72E-2 1.32E-2 Cs 134 3.68E+5 6.04E+5 1 27E+5 3.54E+1 1.87E+5 6.72E+4 3.29E+3 Cs 136 3.52E+4 9.67E+4 6.26E+4 6.21E-1 5.15E+4 7.68E+3 3.40E+3 Cs 137 5.15E+5 4.93E+5 7.28E+4 5.37E+1 1.61E+5 5.78E+4 3.14E+3 Ba 140 3.61E+2 3.96E-l 2.11E+1 7.96E-2 1.82E-1 2.68E-1 1.83E+2 Ce 141 1.50E-1 1.07E-l 6.99E-2 6.34E-2 8.24E-2 6.34E-2 5.40E+1 Nb 95 5.21E+2 2.03E+2 1.45E+2 6.39E-1 1.91E+2 6.39E-1 3.75E+5 La 140 1.50E-1 5.93E-2 2.68E-2 1 03E-2 1.03E-2 1.03E-2 1.36E+3 Ce 144 5.00 1.81 6.06E-1 3.58E-1 1.16 3.58E-1 3.80E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section l.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-3 A, VALUES LIQUID*

RADWASTE TANK TEEN mrem ml hr pCi I

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 3.28E-1 3.28E-1 3.28E-1 3.28E-1 3.28E-1 3.28E-1 Cr 51 1.02E-1 1.02E-1 1.39 8.16E-1 3 84E-1 1.94 2 '6E+2 Cu 64 1.20E-5 2.89 1.36 1.20E-5 7.32 1.20E-S 2 '4E+2 Mn 54 3.31E+1 4.34E+3 8 87E+2 '.31E+1 1.32E+3 3.31E+1 8.86E+3 Fe 55 6.94E+2 4.92E+2 1.15E+2 3.12E+2 2 '3E+2 Fe 59 1.07E+3 '.49E+3 9.64E+2 6.41 6.41 7.89E+2 5.87E+3 Co 58 9.03 9.82E+1 2.15E+2, 9.03 9.03 9. 03 1.24E+3 Co 60 5.36E+2 7.96E+2 1.12E+3 5.36E+2 5 '6E+2 5.36E+2 3.93B+3 Zn 65 2.10E+4 7.28E+4 3 '0E+4 1.84E+1 4.66E+4 1.84E+1 3.08E+4 Sr 89 2.44E+4 5.24E-4 6.98E+2 5.24E-4 5.24E-4 5.24E-4 2.90E+3 Sr 90 4.66E+5 1.15E+5 1.31E+4 Zr 95 6.20 6.00 5.97 5.90 6.04 5.90 2.28E+2 Mn 56 1.81E-1 3.22E-2 2.29E-1 1.19E+1 Mo 99 2.56E-2 9.22E+1 1.76E+1 2.56E-2 2.11E+2 2.56E-2 1.65E+2 Na 24 1.39E+2 1.39Ei2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 I 131 1.55E+2 2.17E+2 1.16E+2 6.31E+4 3.73E+2 2.68E-1 4.30E+1 I 133 2.53E+1 4.29E+1 1.31E+1 5.99E+3 7.52E+1 6.60E-4 3.25E+1 Ni 65 2.08E-1 2.66E-2 1.21E-2 1.44 I 132 4.90E-2 1.28E-2 4.60E-3 4.32E-1 2.02E-2 5.59E-3 Cs 134 3.05E+5 7.18E+5 3.33E+5 1.69E+2 2.28E+5 8.73E+4 9.10E+3 Cs 136 2.98E+4 1.17E+5 7.88E+4 2.97 6.38E+4 1.01E+4 9.44E+3 Cs 137 4.09E+5 5.44E+5 1.90E+5 2.57E+2 1.85E+5 '.21E+4 7.99E+3 Ba 140 2.35E+2 4.10E-1 1.55E+1 3 ~ 81E-1 4.79E-1 5.75E-1 3.63E+2 Ce 141 3.46E-1 3.32E-1 3.07E-1 3.04E-1 3.17E-1 3.04E-1 8.16E+1 Nb 95 4.44E+2 2.48E+2 1.18E+2 3.06 2.40E+2 3.06 1.05E+6 La 140 1.57E-1 1.02E-1 6.35E-2 4.94E-2 4.94E-2 4.94E-2 3.05E+3 Ce 144 3.99 2. 65 1.83 1.71 2 27 1.71 5.74E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section l.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-4 A, VALUES - LIQUID*

RADWASTE TANK ADULT mrem ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 4.45E-1 4.45E-1 4.45E-1 4.45E-1 4.45E-1 4.45E-1 Cr 51 1.82E-2 1-82E-2 1 27 7.64E-1 2.93E-1 1. 67 3.14E+2 Cu 64 2.75 1.29 6.94 2.35E+2 Mn 54 5.94 4.38E+3 8.41E+2 5.94 1.31E+3 5.94 1.34E+4 Fe 55 6.64E+2 4.58E+2 1.07E+2 2.56E+2 2.63E+2 Fe 59 1.03E+3 2.43E+3 9.31E+2 1.15 1 ~ 15 6.79E+2 8.09E+3 Co 58- l. 62 9.15E+1 2.03E+2 1.62 l. 62 1. 62 1.82E+3 Co 60 9.60E+1 2.57E+2 6.71E+2 9.60E+1 9.60E+1 9 60E+1 4.99E+3 Zn 65 2.31E4 7.36E+4 3.32E+4 3.30 4.92E+4 3.30 4.63E+4 Sr 89 2.25E+4 9.39E-5 6 '5E+2 9.39E-5 9.39E-5 9.39E-S 3.60E+3 Sr 90 5.60E+5 1.37E+5 1.62E+4 Zr 95 1.36 1- 15E 1.12 1.06 l. 21 1. 06 3.06E+2 Mn 56 1.73E-1 3.07E-2 2 20E-1 5.52 Mo 99 4.58E-3 8.70E+1 1.66E+1 4.58E-3 1.97E+2 4-58E-3 2.02E+2 Na 24 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 I 131 1.45E+2 2.07E+2 1.19E+2 6.79E+4 3.55E+2 4 80E-2 5.47E+1 I 133 2 35E+1 4.09E+1 1.25E+1 6.02E+3 7.14E+1 1 18E-4 3.68E+1 Ni 65 1.93E-1 2.51E-2 1. 14E-2 6.36E-1 I 132 4.68E-3 1.25E-2 4.38E-3 4.38E-1 2.00E-2 2.35E-3 Cs 134 2.98E+5 7.08E+5 5.79E+5 3.03E+1 2.29E+5 7.61E+4 1.24E+4 Cs 136 2.96E+4 1.17E+5 8.42E+4 5.32E-1 6.51E+4 8.93E+3 1.33E+4 Cs 137 3 '2E+5 5.22E+5 3.42E+5 4.60E+1 1.77E+5 5 90E+4 1.02E+4 Ba 140 2.24E+2 3.49E-1, 1.47E+1 6.83E-2 1.64E-1 2.29E-l 4.61E+2 Ce 141 9.53E-2 8.20E-2 5.75E-2 5.44E-2 6.72E-2 5.44E-2 1.06E+2 Nb 95 4.39E+2 2.44E+2 1.32E+2 5.47E-1 2.41E+2 5.47E-1 1.48E+6 La 140 1.11E-1 6.03E-2 2.24E-2 8.84E-3 8.84E-3 8.84E-3 3.78E+3 Ce 144 2.48 1.22 4.24E-1 3.07E-1 8.47E-1 3.07E-1 7.37E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1y and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE A, VALUES 5 LIQUID*

EMERGENCY CONDENSER VENT INFANT mrem ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 7.43E-4 7 43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 Cr 51 3.30E-S 2.15E-5 4.70E-6 4.18E-S 9 '1E-4 Cu 64 2.89E-4 1.34E-4 4.89E-4 5.94E-3 Mn 54 4.79E-2 1.08E-2 1.06E-2 1.76E-2 Fe 55 3.35E-2 2.16E-2 5.78E-3 1 ~ 06E-2 2.75E-3 Fe 59 7.29E-2 1.27E-1 5. 02E-2 3.76E-2 6.08E-2 Co 58 8.58E-3 2 '4E-2 2.14E-,2 Co 60 2.60E-2 6.15E-2 6.19E-2 Zn 65 4.42E-2 1.52E-1 6.99E-2 7.35E-2 1 ~ 28E-1 Sr 89 5.95 1.71E-1 1.22E-1 Sr 90 4.46E+1 1.14E+1 5.57E-1 Zr 95 4.90E-4 1.19E-4 8.47E-S 1.29E-4 5.95E-2 Mn 56 6.17E-7 1.06E-7 5 30E-7 5.60E-5 Mo 99 6.00E-2 1.17E-2 8.97E-2 1.98E-2 Na 24 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 I 131 7.77E-2 9.16E-2 4.03E-2 3.01E+1 1.07E-1 3 '7E-3 I 133 1.08E-2 1.58E-2 4.62E-3 2.87 1.85E-2 2.67E-3 Ni 65 3.41E-6 3.86E-7 1.76E-7 2 94E-5 I 132 4.05E-7 8.22E-7 2.93E-7 3.85E-5 9 17E-7 6 66E-7 Cs 134 9.08E-l 1.69 1.71E-1 4.36E-1 1.79E-1 4.60E-3 Cs 136 1.04E-1 3.06E-1 1.14E-1 1.22E-1 2,49E-2 4 64E-3 Cs 137 1.26 1.47 1.04E-1 3.95E-1 1.60E-1 4.61E-3 Ba 140 3.85E-1 3.85E-4 1.99E-2 9.15E-5 2.37E-4 9.47E-2 Ce 141 1 ~ 85E-4 1.13E-4 1.33E-S 3.48E-5 5 '2E-2 Nb 95 9.88E-5 4.07E-S 2.35E-5 2.92E-S 3.43E-2 La 140 3.03E-5 1.20E-S 3.08E-6 1.41E-1 Ce 144 7 '6E-3 2.93E-3 4.02E-4 1. 19E-3 4.11E-1

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section l.

Unit 1 ODCM Revision 14 004152LL June 1994

0 TABLE 2-6 A, VALUES LIQUID*

EMERGENCY CONDENSER VENT CHILD mrem - ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 1.44E-l 1 44E-1 1.44E-1 1.44E-1 1 44E-1 1.44E-1 Cr 51 3.78E-S 3.78E-S 1.37 7.58E-1 2.07E-1 1.38 7.24E+1 Cu 64 2.63 1.59 6. 35 1 23E+2 Mn 54 1.23E-2 3.36E+3 8.95E+2 1.23E-2 9.42E+2 1.23E-2 2.82E+3 Fe 55 9.04E+2 4.79E+2 1.49E+2 2.71E+2 8.88E+1 Fe 59 1.28E+3 2.07E+3 1.03E+3 2.38E-3 2.38E-3 6.00E+2 2.15E+3 Co 58 3.36E-3 7.01E+1 2.15E+2 3 '6E-3 3.36E-3 3.36E-3 4.09E+2 Co 60 1.99E-1 2.08E+2 6.14E+2 1.99E-1 1.99E-1 1.99E-1 1.15E+3 Zn 65 2.15E+4 5.73E+4 3.56E+4 6.84E-3 3.61E+4 6.84E-3 1.01E+4 Sr 89 3.07E+4 8.78E+2 1.19E+3 Sr 90 4.01E+5 1.02E+5 5.40E+3 Zr 95 3.01E-1 6.78E-2 '6.06E-2 2.19E-3 9.61E-2 2.19E-3 6.84E+1 Mn 56 1.65E-1 3.73E-2 2.00E-1 2 '9E+1 Mo 99 8.16E+1 2.02E+1 1.74E+2 6.75E+1 Na 24 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 I 131 1.86E+2 1.87E+2 1.06E+2 6.19E+4 3.08E+2 1.67E+1 I 133 3.08E+1 3.81E+1 1.44E+1 7.07E+3 6.35E+1 1.53E+1 Ni 65 2.66E-1 2.50E-2 1.46E-2 3.07 I 132 6.01E-3 1.10E-2 5. OBE-3 5. 12E-1 1. 69E-2 1.30E-2 Cs 134 3.68E+5 6.04E+5 1.27E+5 6.29E-2 1.87E+5 6.71E+4 3.25E+3 Cs 136 3.51E+4 9.66E+4 6.25E+4 1.10E-3 5.14E+4 7.67E+3 3.40E+3 Cs 137 5.14E+5 4.92E+5 7 27E+4 9.55E-2 1 60E+5 '.77E+4 3.08E+3 Ba 140 2.48E+2 2.17E-1 1.45E+1 1.42E-4 7.09E-2 1.30E-1 1.26E+2 Ce 141 3.08E-2 1.54E-2 2.39E-3 1.13E-4 6.83E-3 1.13E-4 1.91E+1 Nb 95 5.21E+2 2.03E+2 1.45E+2 1.14E-3 1.90E+2 1.14E-3 3.75E+5 La 140 1.31E-1 4.59E-2 1.55E-2 1.83E-S 1.83E-5 1.83E-S 1.28E+3 Ce 144 1.64 5.15E-1 8.81E-2 6.36E-4 2.85E-1 6.36E-4 1.34E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-7

~ VALUES LIQUID*

EMERGENCY CONDENSER VENT TEEN mrem - ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 1.74E-1 1.74E-l 1.74E-1 1 ~ 74E-1 1.74E-1 1.74E-1 Cr 51 1.81E-4 1.81E-4 1.28 7.12E-1 2.81E-1 1 ~ 83 2.15E+2 Cu 64 2.86 1.35 7 '4 2.22E+2 Mn 54 5.89E-2 4.29E+3 8.52E+2 5.89E-2 1 28E+3 5.89E-2 8.81E+3 Fe 55 6.89E+2 4.88E+2 1.14E+2 3.10E+2 2.11E+2 Fe 59 1.05E+3 2.46E+3 9.50E+2 1.14E-2 1.14E-2 7.76E2 5.82E+3 Co 58 1.61E-2 8.78E+1 2.02E+2 1.61E-2 1.61E-2 1.61E-2 1.21E+3 Co 60 9.53E-l 2.57E+2 5.78E+2 9.53E-1 9.53E-1 9.53E-l 3.34E+3 Zn 65 2.10E+4 7.28E+4 3.39E+4 3.28E-2 4.66E+4 3.28E-2 3 '8E+4 Sr 89 2.38E+4 6.81E+2 2.83E+3 Sr 90 4.54E+5 1.12E+5 1.27E+4 Zr 95 2.56E-1 8.80E-2 6.38E-2 1.05E-2 1.24E-1 1.05E-2 1.79E+2 Mn 56 1.81E-1 3.22E-2 2.29E-1 1.19E+1 Mo 99 8.57E+1 1.63E+1 1.96E+2 1.54E+2 Na 24 1.38E+2 1.38E+2 1.38E+2 1.38E+2 1.38E+2 1.38E+2 1.38E+2 I 131 1.47E+2 2.06E+2 1.10E+2 6.00E+4 3.54E+2 4.77E-4 4.07E+1 I 133 2.42E+1 4.11E+1 1.25E+1 5.74E+3 7.21E+1 3.11E+1 2.08E-1 2.66E-2 1 ~ 21E-2 1.44 4.86E-3 1.27E-2 4.56E-3 4.29E-1 2.00E-2 5.54E-3 3.05E+5 7.18E+5 3.33E+5 3.01E-1 2.28E+5 8.71E+4 8.93E+3 Cs 136 2.98E+4 1.17E+5 7.87E+4 5.28E-3 6.38E+4 1.01E+4 9.43E+3 Cs 137 4.09E+5 5.44E+5 1.89E+5 4.57E-l 1.85E+5 7.19E+4 7.73E+3 Ba 140 1.96E+2 2 '7E-2 1.27E+1 6.77E-4 8.23E-2 1.62E-1 3.03E+2 Ce 141 2.43E-2 1.64E-2 2.36E-3 5.40E-4 8.02E-3 5.40E-4 4.54E+1 Nb 95 4.41E+2 2.45E+2 1.15E+2 5.43E-3 2.37E+2 5.43E-3 1.05E+6 La 140 1.05E-1 5.17E-2 1.38E-2 8 78E-5 8 78E-5 8.78E-5 2.96E+3 Ce 144 1.27 5.28E-1 7.12E-2 3.04E-3 3.17E-1 3.04E-3 3.19E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section l.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 2-8 A, VALUES LIQUID*

EMERGENCY CONDENSER VENT ADULT mrem ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 2.27E-l 2.27E-1 2.27E-1 2.27E-1 2.27E-1 2.27E-l Cr 51 3.24E-5 3.24E-5. 1.24 7.43E-1 2.74E-1 1. 65 3.12E+2 Cu 64 2. 72 1.28 6.86 2.32E+2 Mn 54 1.06E-2 4.37E+3 8.33E+2 1.06E-2 1.30E+3 1. 06E-2 1. 34Ei4 Fe 55 6.58E+2 4.55E+2 1.06E+2 2.54E+2 2.61E+2 Fe 59 1.02E+3 2.41E+3 9 '2E+2 2.04E-3 2.04E-3 6.72E+2 8.02E+3 Co 58 2.88E-3 8.83E+1 1.98E+2 2.88E-3 2.88E-3 2.88E-3 1.79E+3 Co 60 1.71E-1 2.56E+2 5.65E+2 1.71E-1 1.71E-1 1.71E-1 4.81E+3 Zn 65 2.31E+4 7.36E+4 3.32E+4 5.87E-3 4.92E+4 5.87E-3 4.63E+4 Sr 89 2.18E+4 6.27E+2 3.50E+3 Sr 90 5.44E+5 1.34E+5 1.57E+4 Zr 95 2.40E-1 7.81E-2 5.35E-2 1.88E-3 1.22E-1 1.88E-3 2.42E+2 Mn 56 1.73E-1 3.07E-2 2.20E-1 5.52 Mo 99 8.04E+1 1.53E+1 1.82E+2 1.86E+2 Na 24 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 I 131 1.37E+2 1.96E+2 1.12E+2 6.43E+4 3.36E+2 5.17E+1 I 133 2.25E+1 3.91E+1 1.19E+1 5.75E+3 6.82E+1 3.51E+1 Ni 65 1.93E-1 2.50E-2 1.14E-2 6.36E-1 I 132 4.64E-3 1.24E-2 4.34E-3 4.34E-1 1.98E-2 2.33E-3 Cs 134 2.98E+5 7.08E+5 5.79E+5 5.39E-2 2.29E+5 7.61E+4 1.24E+4 Cs 136 2.96E+4 1.17E+5 8.42E+4 9.46E-4 6.51E+4 8.92E+3 1.33E+4 Cs 137 3.82E+5 5.22E+5 3.42E+5 8.19E-2 1.77E+5 5.89E+4 1.01E+4 Ba 140 1.84E+2 2.32E-l 1.21E+1 1 '1E-4 7.88E-2 1.33E-1 3.79E+2 Ce 141 2.21E-2 1.50E-2 1.78E-3 9.67E-5 7.00E-3 9.67E-S 5.68E+1 Nb 95 4.38E+2 2.44E+2 1.31E+2 9.73E-4 2.41E+2 9.73E-4 1.48E+6 La 140 9.90E-2 4.99E-2 1.32E-2 1.57E-5 1.57E-S 1.57E-5 3.66E+3 Ce 144 1.17 4.89E-1 6.33E-2 5.45E-4 2.90E-1 5.45E-4 3.95E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODOM Revision 14 004152LL June 1994

TABLE 3-1 Critical Receptor Dispersion Parameters'or Ground Level and Elevated Releases ELEVATED ELEVATED GROUND GROUND'OCATION DIR MILES ~Xsec m'i ~D~m'g XIIXsec m'y ~D~msi Residences E (980) 1.4 1 ~ 8 E-07b 5.2 E-09 4.02 E-07 8 58 E-09 Dairy Cowsf SE (1300) 2.6 2.2 7.0 E-10'.0 6;00 E-08 1.64 E-09 E-08'.2 Milk SE (130D) 2.6 E-10'.7 6.00 E-08 1.64 E-09 E-08'.1 Goats'eat Animals ESE (1150) 1.8 E-08'.0 E-09'.5 1.16 E-07 3.54 E-09 Gardens E (974) 1.8 E-09'.4 2.53 E-07 5.55 E-09 E-07'.4 Site Boundary ENE (674) 0.4 E-06~ E-08'~ 6.63'E-06 6.35 E-08

a. These values will be used in dose calculations beginning in April 1986 but may be revised peri.odically to account for changes in locations of farms, gardens or critical residences.

b. Values based on 5 year annual meteorological data (C.T. Main, Rev. 2)

c. Values based on 5 year average grazing season meteorologi.cal data (C.T. Main Rev. 2)

d. Value are based on most restri.ctive X/Q land-based sector (ENE). (C.T. Mai.n, Rev. 2)

e. Values are based on average annual meteorological data for the year 1985.

f. Conservative location based on past dairy cow and goat milk history.

Unit 1 ODCM Revt.sion 13 004152LL 41 December 1993

a TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors*

For Noble Gases

~ Gamma Whole Gamma Air B, Body V, mead r m rem Irr Nuclide ~Ci sec ~Ci sec Kr-85 2.23E-6 Kr-85m 1.75E-3 1.68E-3 Kr-87 1.02E-2 9.65E-3 Kr-88 2.23E-2 2.17E-2 Kr-89 2.50E-2 1.71E-2 Kr-83m 2.26E-6 a

Xe-133 2.80E-4 2.41E-4 Xe-133m 2.27E-4 1.87E-4 Xe-135 2.62E-3 2.50E-3 Xe-135m 5.20E-3 4.89E-3 Xe-137 2.30E-3 2.20E-3 Xe-138 1.32E-2 1 '6E-2 Xe-131m 1.74E-S 1.47E>>6 Ar-41 1.64E-2 1.57E-2

• Calculated in accordance with Regulatory Guide 1.109. (See Appendix B.)

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-3 IMMERSION DOSE FACTORS*

Nuc1 ide Q~B~od ** ~L-skin ** *** gQl-Ai~r***

Kr 83m 7.56E>>02 1 ~ 93E1 2.88E2 Kr 85m 1.17E3 1. 46E3 1.23E3 1.97E3 Kr 85 1.61El 1.34E3 1.72E1 1.95E3 Kr 87 5.92E3 9.73E3 6.17E3 1.03E4 Kr 88 1.47E4 2.37E3 1.52E4 2.93E3 Kr 89 1.66E4 1.01E4 1.73E4 1.06E4 Kr 90 1.56E4 7.29E3 1.63E4 7 83E3 Xe 131m 9.15E1 4.76E2 1.56E2 1.11E3 Xe 133m 2.51E2 9.94E2 3.27E2 1.48E3 Xe 133 2.94E2 3.06E2 3.53E2 1.05E3 Xe 135m 3. 12E3 7.11E2 3.36E3 7.39E2 Xe 135 1.81E3 1.86E3 1.92E3 2.46E3 Xe 137 1.42E3 1.22E4 1.51E3 1.27E4 Xe 138 8.83E3 4.13E3 9.21E3 4.75E3 Ar 41 8.84E3 2.69E3 9.30E3 3.28E3

• From, Table B-l. Regulatory Guide 1. 109 Rev. 1

• • mrem/yr per pci/m3.

• • • mrad/yr per pCi./m~.

Unit 1 ODCR Revision 14 004152LL June 1994

TABLE 3-4 DOSE AND DOSE RATE R; VALUES - INHALATION r .

INFANT'rem pCi/m NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3* 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 C 14* 2.65E4 5 '1E3 5.31E3 5 '1E3 5.31E3 5.31E3 5.31E3 Cr 51 8.95E1 5.75E1 1.32El 1.28E4 3.57E2 Mn 54 2.53E4 4.98E3 4.98E3 1.00E6 7.06E3 Fe 55 1.97E4 1.17E4 3.33E3 8.69E4 1.09E3 Fe 59 1.36E4 2.35E4 9.48E3 1.02E6 2.48E4 Co 58 1.22E3 1.82E3 7.77E5 1.11E4 Co 60 8.02E3 1 18E4 4.51E6 3.19E4 Zn 65 1.93E4 6 '6E4 3.11E4 3.25E4 6.47E5 5 14E4 Sr 89 3.98E5 1.14E4 2.03E6 6.40E4 Sr 90 4.09E7 2.59E6 l. 12E7 1.31E5 Zr 95 1.15E5 2.79E4 2.03E4 3.11E4 1.75E6 2.17E4 Nb 95 1.57E4 6.43E3 3.78E3 4.72E3 4.79E5 1.27E4 Mo 99 1.65E2 3.23El 2.65E2 1.35E5 4 87E4 I-131 3.79E4 4.44E4 1.96E4 1.48E7 5.18E4 1.06E3 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 2.16E3 Cs 134 3.96E5 7."03E5 7.45E4 1.90ES 7.97E4 1.33E3 Cs 137 5.49ES 6 '2ES 4.55E4 1.72ES 7.13E4 1.33E3 Ba 140 5.60E4 5.60E1 2.90E3 1.34E1 1.60E6 3.84E4 La 140 5.05E2 2.00E2 5 '5E1 1.68ES 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5.17E5 2.16E4 Ce 144 3.19E6 1.21E6 1.76E5 5.38ES 9 84E6 1.48E5 Nd 147 7.94E3 8.13E3 5.00E2 3.15E3 3.22E5 3.12E4

• mrem/yr per pci/m~.

This and following Q Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.

Unit 1 ODCR Revision 14 004152LL 44 June 1994

TABLE 3-5 DOSE AND DOSE RATE Q VALUES INHALATION CHILD mrem r pCi/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 1.12E3 1.12E3 1.12E3 1.12E3 1-12E3 1.12E3 C 14* 3.59E4 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 Cr 51 1.54E2 8.55E1 2.43E1 1.70E4 1.08E3 Mn 54 4.29E4 9.51E3 1.00E4 1 58E6 2 29E4 Fe 55 4.74E4 2.52E4 7.77E3 1-11E5 2.87E3 Fe 59 2 '7E4 3.34E4 1.67E4 1 27E6 7.07E4 Co 58 1.77E3 3.16E3 1 11E6 3.44E4 Co 60 1.31E4 2.26E4, 7.07E6 9 62E4 Zn 65 4.26E4 1.13E5 7.03E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99ES 1.72E4 2.16E6 1.67ES Sr 90 1.01E8 6.44E6 1.48E7 3.43ES Zr 95 1.90E5 4.18E4 3.70E4 5.96E4 2.23E6 6.11E4 Nb 95 2.35E4 9.18E3 6.55E3 8.62E3 6.14E5 3.70E4 Mo 99 1.72E2 4.26E1 3.92E2 1.35E5 1. 27ES I 131 4.81E4 4.81E4 2'. 73E4 1.62E7 7.88E4 2.84E3 I 133 1.66E4 2.03E4 7.70E3 3.85E6 3.38E4 5 '8E3 Cs 134 6.51E5 1.01E6 2.25E5 3.30E5 1. 21E5 3. 85E3 Cs 137 9.07E5 8.25E5 1.28E5 2.82E5 1.04E5 3.62E3 Ba 140 7 40E4 6.48El 4.33E3 2.11E1 1.74E6 1.02E5 La 140 6.44E2 2.25E2 7.55E1 1.83E5 2.26E5 Ce 141 3.92E4 1.95E4 2.90E3 8.55E3 5.44ES 5.66E4 Ce 144 6.77E6 2.12E6 3.61E5 1~ 17E6 1.20E7 3.89E5 Nd 147 1 08E4 8.73E3 6.81E2 4.81E3 3.28E5 8.21E4

• mrem/yr per pci/m'.

Unit 1 ODQ4 Revision 14 004152LL June 1994

TABLE 3-6 DOSE AND DOSE RATE R; VALUES INHALATION pCi/m'EEN mme mr NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 C 14* 2 60E4 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 Cr 51 1.35E2 7.50E1 3.07E1 2.10E4 3.00E3 Mn 54 5.11E4 8.40E3 1.27E4 1.98E6 6.68E4 Fe 55 3.34E4 2.38E4 5 '4E3 1.24ES 6.39E3 Fe 59 1.59E4 3.70E4 1.43E4 1.53E6 1.78E5 Co 58 2.07E3 2.78E3 1.34E6 9.52E4 Co 60 1. 51E4 1.98E4 8.72E6 2.59ES Zn 65 3.86E4 1.34E5 6.24E4 8 '4E4 1.24E6 4.66E4 Sr 89 4.34E5 1.25E4 2.42E6 3.71E5 Sr 90 1.08E8 6 '8E6 1.65E7 7.65ES Zr 95 1.46ES 4.58E4 3.15E4 6.74E4 2.69E6 1.49E5 Nb 95 1 86E4 1.03E4 5.66E3 1.00E4 7.51ES 9.68E4 Mo 99 1.69E2 3.22E1 4.11E2 1.54ES 2.69ES I 131 3.54E4 4. 91E4 2.64E4 1 ~ 46E7 8.40E4 6.49E3 I 133 1.22E4 2.05E4 6.22E3 2 '2E6 3.59E4 1. 03E4 Cs 134 5.02ES 1.13E6 5.49ES 3.75ES 1.46E5 9 '6E3 Cs 137 6.70ES 8.48E5 3.11E5 3.04E5 1.21E5 8.48E3 Ba 140 5.47E4 6.70E1 3.52E3 2.28E1 2.03E6 2.29E5 La 140 4.79E2 2 '6E2 6.26El 2 14ES 4 87E5 Ce 141 2.84E4 1.90E4 2.17E3 8.88E3 6.14E5 1.26E5 Ce 144 4.89E6 2-02E6 2.62E5 1.21E6 1.34E7 8.64E5 Nd 147 7.86E3 8.56E3 5.13E2 5 02E3 3.72ES 1.82E5

• mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-7 DOSE AND DOSE RATE VALUES - INHALATION ADULT mrem r pCi/m

~UC~LI BONE ~LIVE T BODY ~TYROID KIDNEY LUNG GI-LLI H 3* 1.26E3 1.26E3 1. 26E3 1.26E3 1.26E3 1.26E3 C 14* 1.82E4 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 Cr 51 1.00E2 5.95E1 2.28E1 1.44E4 3.32E3 Mn 54 3.96E4 6. 30E3 9.84E3 1.40E6 7.74E4 Fe 55 2.46E4 1.70E4 3.94E3 7.21E4 6.03E3 Fe 59 1.18E4 2.78E4 1.06E4 1.02E6 1.88E5 Co 58 1.58E3 2.07E3 9.28ES 1.06E5 Co 60 1.15E4 1 '8E4 5 '7E6 2 85E5 Zn 65 3.24E4 1.03ES 4.66E4 6.90E4 8 64ES 5.34E4 Sr 89 3.04ES 8.72E3 1.40E6 3.50ES Sr 90 9.92E7 6.10E6 9 60E6 7.22ES Zr '95 1.07E5 3.44E4 2.33E4 5.42E4 1.77E6 1.50E5 Nb 95 1.41E4 7.82E3 4.21E3 7.74E3 5.05E5 1.04E5 Mo 99 1.21E2 2 30E1 2.91E2 9.12E4 2.48ES I 131 2.52E4 3.58E4 2.05E4 1.19E7 6.13E4 6.28E3 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 8.88E3 Cs 134 3.73E5 8.48E5 7.28ES 2.87ES 9.76E4 1.04E4 Cs 137 4.78ES 6.21ES 4.28ES 2.22E5 7.52E4 8.40E3 Ba'40 3.90E4 4.90E1 2.57E3 1.67E1 1.27E6 2.18E5 La 140 3.44E2 1.74E2 4.58E1 1.36E5 4.58ES Ce 141 1.99E4 1.35E4 1.53E3 6.26E3 3.62ES 1 20ES Ce 144 3.43E6 1.43E6 1.84ES 8.48ES 7 '8E6 8 '6E5 Nd 147 5.27E3 6.10E3 3 65E2 3.56E3 2.21ES 1.73ES

• mrem/yr per pCi/m .

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-8 DOSE AND DOSE RATE R; VALUES GROUND PLANE ALL AGE GROUPS me~mr em r pci/sec UCLIDE TOTAL BODY SKIN H 3 C 14 Cr 51 4.65E6 5.50E6 Mn 54 1.40E9 1.64E9 Fe 55 Fe 59 '.73EB 3.20E8 Co 58 3.80E8 4.45E8 Co 60 2.15E10 2.53E10 Zn 65 7.46E8 8.57E8 Sr 89 2.16E4 2.51E4 Sr 90 Zr 95 2.45E8 2.85E8 Nb 95 1 36E8 1.61E8 Mo 99 3.99E6 4.63E6 I 131 1.72E7 2.09E7 I 133 2.39E6 2 91E6 Cs 134 6.83E9 7.97E9 Cs 137 1.03E10 1.20E10 Ba 140 2.05E7 2.35E7 La 140 1.92E7 2.18E7 Ce 141 1.37E7 1.54E7 Ce 144 6.96E7 8.07E7 Nd 147 8.46E6 1.01E7 Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-9 DOSE AND DOSE RATE R; VALUES -'COW MILK INFANT gP~mrem pCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 2 '8E3 C 14'r 3.23E6 6.89ES 6.89E5 6.89ES 6.89ES 6.89ES 6.89ES 51 8.35E4 5 45E4 1.19E4 1.06E5 2.43E6 Mn 54 2.51E7 5.68E6 5,. 56E6 9.21E6 Fe 55 8.43E7 5.44E7 1.45E7 2.66E7 6.91E6 Fe 59 1.22E8 2.13E8 8.38E7 6.29E7 1.02E8 Co 58 1.39E7 3.46E7 3.46E7 Co 60 5.90E7 1. 39EB 1.40E8 Zn 65 3 '3E9 1.21E10 5 58E9 5.87E9 1.02E10 Sr 89 6.93E9 1.99E8 1.42EB Sr 90 8.19E10 2 09E10 1 '2E9 Zr 95 3.85E3 9.39E2 .6.66E2 1 01E3 4.68ES Nb 95 4 '1E5 1.64ES 1 17E5 1.54ES 3.03E8 Mo 99 1.04E8 2.03E7 1.55E8 3.43E7 I 131 6.81E8 8.02E8 3.53E8 2.64E11 9.37E8 2.86E7 I 133 8.52E6 1.24E7 3 '3E6 2.'26E9 1.46E7 2.10E6 Cs 134 2.41E10 4.49E10 4.54E9 1.16E10 4.74E9 1. 22E8 Cs 137 3.47E10 4.06E10 2.88E9 1.09E10 4.41E9 1.27E8 Ba 140 1.21E8 1.21ES 6.22E6 2.87E4 7.42E4 2.97E7 La 140 2.03E1 7.99 2.06 9.39E4 Ce 141 2.28E4 1.39E4 1.64E3 4.28E3 7.18E6 Ce 144 1.49E6 6.10E5 8.34E4 2.46ES' 8.54E7 Nd 147 4.43E2 '4.55E2 2 '9E1 1 76E2 2 89ES mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-10 DOSE AND DOSE RATE R; VALUES COW MIL'K - CHILD m~~mrem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID ~IDNEY LUNG GI-LLI H 3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 C 14 1.65E6 3.29ES 3.29E5 3.29E5 3.29E5 3.29ES 3.29E5 Cr 51 5.27E4 2.93E4 7.99E3 5.34E4 2.80E6 Mn 54 1.35E7 3.59E6 3.78E6 1.13E7 Fe 55 6.97E7 3.07E7 1.15E7 2.09E7 6 85E6 Fe 59 6.52E7 1.06ES 5.26E7 3.06E7 1 ~ 10ES Co 58 6.94E6 2.13E7 4.05E7 Co 60 2.89E7 8.52E7 1.60E8 Zn 65 2.63E9 7.00E9 4.35E9 4.41E9 1.23E9 Sr 89 3.64E9 1.04ES 1.41ES Sr 90 7.53E10 1.91E10 '1.01E9 Zr 95 2.17E3 4.77E2 4.25E2 6.83E2 4.98E5 Nb 95 1,86E5 1.03E4 5.69E4 1.00ES 4.42ES Mo 99 4.07E7 1.01E7 8.69E7 3.37E7 I 131 3.26ES 3.28ES 1 86ES 1.08E11 5.39ES 2.92E7 I 133 4.04E6 4.99E6 1 ~ 89E6 9.27ES 8.32E6 2.01E6 Cs 134 1.50E10 2.45E10 5.18E9 7.61E9 2.73E9 1.32ES Cs 137 2.17E10 2-OSE10 3.07E9 6.78E9 2.44E9 1.30ES Ba 140 5.87E7 5.14E4 3.43E6 1.67E4 3.07E4 2.97E7 La 140 9.70 3.39 1.14 9 '5E4 Ce 141 1.15E4 5.73E3 8.51E2 2.51E3 7.15E6 Ce 144 1.04E6 3.26E5 5.55E4 1.80E5 8.49E7 Nd 147 2.24E2 1.81E2 1.40E1 9.94E1 2.87ES mrem/yr per pci/m~.

Unit 1 ODCR Revision 14 004152LL June 1994

TABLE 3-11 DOSE AND DOSE RATE Q VALUES - COW MILK TEEN m~~mrem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 C 14'r

6. 70ES "

1.34E5 1.34ES 1.34E5 1. 34E5 -

1. 35E5 1.34E5 51 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Mn 54 9.01E6 1.79E6 2 '9E6 1.85E7 Fe 55 2.78E7 1.97E7 4 59E6 1 25E7 8.52E6 Fe 59 2.81E7 6.57E7 2.54E7 2.07E7 1.55E8 Co 58 4.55E6 1.05E7 6.27E7 Co 60 1.86E7 4.19E7 2.42ES Zn 65 1.34E9 4 '5E9 2.17E9 2.97E9 1.97E9 Sr 89 1.47E9 4.21E7 1.75E8 Sr 90 4.45E10 1.10E10 1 25E9 Zr 95 9.34E2 2.95E2 2.03E2 4.33E2 6 SOES Nb 95 1 86E5 1.03ES 5.69E4 1.00E5 4.42ES Mo 99 2,. 24E7 4.27E6 5.12E7 4.01E7 I 131 1.34E8 1.88ES 1.01E8 '.49E10 3.24ES 3.72E7 I 133 1.66E6 2.82E6 8.59E5 3.93ES 4.94E6 2.13E6 Cs 134 6.49E9 1.53E10 7.08E9 4.85E9 1.85E9 1.90E8 Cs 137 9.02E9 1.20E10 4.18E9 4.08E9 '1.59E9 1.71E8 Ba 140 2.43E7 2.98E4 1.57E6 1.01E4 2.00E4 3 '5E7 La 140 4.05 1.99 5.30E-1 1.14ES Ce 141 4.67E3 3.12E3 3.58E2 1.47E3 8.91E6 Ce 144 4.22E5 1.74E5 2.27E4 1.04E5 1.06E8 Nd 147 9. 12E1 9.91El 5.94EO 5 '2E1 3.58E5 mrem/yr per pCi/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-12 DOSE AND DOSE RATE R; VALUES - COW MILK ADULT mr~mr em r pCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 7.63E2 7.63E2 7.63E2 7 63E2 7.63E2 7.63E2 C 14 3.63E5 7-26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.48E4 8.85E3 3.26E3 1 ~ 96E4 3.72E6 Mn 54 5.41E6 1.03E6 1 ~ 61E6 1 ~ 66E7 Fe 55 1.57E7 1.08E7 2.52E6 6.04E6 6. 21E6, Fe 59 1.61E7 3.79E7 1.45E7 1.06E7 1. 26E8 Co 58 2.70E6 6 '5E6 5.47E7 Co 60 1.1QE7 2.42E7 2.06E8 Zn 65 8.71E8 2.77E9 1.25E9 1.85E9 1.75E9 Sr 89 7.99E8 2.29E7 1.28E8 Sr 90 3.15E10 7.74E9 9.11EB Zr 95 5.34E2 1.71E2 .1.16E2 2.69E2 5.43E5 Nb 95 1.09E5 6.07E4 3.27E4 6.00E4 3.69E8 Mo 99 1.24E7 2.36E6 2.81E7 2.87E7 I 131 7 '1E7 1.06E8 6.08E7 3.47E10 1.82EB 2.80E7 I 133 9.09E5 1.58E6 4.82E5 2.32E8 2.76E6 1.42E6 Cs 134 3.74E9 8.89E9 7.27E9 2.88E9 9.55E8 1.56EB Cs 137 4.97E9 6.80E9 4.46E9 2.31E9 7.68E8 1.32E8 Ba 140 1.35E7 1.69E4 8.83E5 '.75E3 9.69E3 2.77E7 La 140 2.26 1.14 3.01E-1 8,35E4 Ce 141 2.54E3 1.72E3 1.95E2 7.99E2 6.58E6 Ce 144 2.29ES 9.58E4 1.23E4 5.68E4 7.74E7 Nd 147 4.74E1 5.48E1 3.28EO 3.20E1 2.63ES mrem/yr per pci/m~.

Unit 1 (XXR Revt.sion 14 004152LL June 1994

TABLE 3-13 DOSE AND DOSE RATE VALUES GOAT MILK - INFANT m~~meem pCi/sec NUCLIDE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 BONE'.23E6 6.33E3 6;33E3 6.33E3 6.33E3 6.33E3 6.33E3 C 14 6.89ES 6.89E5 6.89ES 6.89E5 6.89ES 6.89E5 Cr 51 1.00E4 '.56E3 1.43E3 1.28E4 2.93E5 Mn 54 3.01E6 6.82E5 6.67E5 1.11E6 Fe 55 1.10E6 7.08E5 1.89E5 3.46ES 8 '8E4 Fe 59 1.59E6 2.78E6 1.09E6 8.21E5 1 33E6 Co 58 1 ~ 67E6 4 '6E6 4 16E6 Co 60 7.08E6 1.67E7 1 68E7 Zn 65 4.24E8 1.45E9 6.70EB 7.04E8 1.23E9 Sr 89 1 ~ 48E10 4.24EB 3.04E8 Sr 90 1.72Ell 4.38E10 2.15E9 Zr 95 4.66E2 1.13E2 8.04E1 1.22E2 5.65E4 Nb 95 9.42E4 3.88E4 2.24E4 2.78E4 3.27E7 Mo 99 1.27E7 2.47E6 1.89E7 4.17E6 I 131 8.17EB 9.63EB 4.23E8 3.16El 1.12E9 3.44E7 I 133 1.02E7 1.49E7 4.36E6 2.71E9 1.75E7 2.52E6 Cs 134 7.23E10 1.35E11 1.36E10 3.47E10 1.42E10 3 '6EB Cs 137 1. 04E11 1.22E11 8 63E9 3.27E10 1.32E10 3.81E8 Ba 140 1.45E7 1.45E4 7.48E5 3.44E3 8.91E3 3.56E6 La 140 2.430 9.59E-1 2.47E-1 1.13E4 Ce 141 2.74E3 1.67E3 1.96E2 5.14E2 8 62E5 Ce 144 1.79ES 7.32E4 1.00E4 2.96E4 1.03E7 Nd 147 5.32E1 5.47E1 3.35EO 2.11E1 3.46E4 mrem/yr per pci/m3.

I Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-14 DOSE AND DOSE RATE R; VALUES GOAT MILK CHILD He~mrem pCi/sec NUCLIDE BONE ~ICE T. BODY THYROID KIDNEY LUNG GI-LLI H 3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 C 14 ,

1.65E6 3.29ES 3.29E5 3.29E5 3.29ES '.29ES 3.29E5 Cr 51 6.34E3 3.52E3 9.62E2 6.43E3 3.36ES Mn 54 1.62E6 4.31ES 4.54ES 1.36E6 Fe 55 9.06ES 4.81ES "

1.49ES 2.72E5 8.91E4 Fe 59 8.52ES 1.38E6 6.86E5 3.99E5 1.43E6 Co 58 8.35E5 2.56E6 4 87E6 Co 60 3.47E6 1'. 02E7 1.92E7 Zn 65 3.15E8 8.40E8 5.23E8 5.29E8 1.48E8 Sr 89 7.77E9 2.22E8 3.01E8 Sr 90 1.58E11 4.01E10 2.13E9 Zr 95 2.62E2 5.76E1 5.13E1 8.25E1 6.01E4 Nb 95 5 05E4 1.96E4 1.40E4 1 85E4 3.63E7 Mo 99 4,95E6 1.22E6 1.06E7 4.09E6 I 131 3.91E8 3.94E8 2.24E8 '1.30E11 6.46E8 3.50E7 I 133 4.84E6 5.99E6 2.27E6 1 '1E9 9.98E6 2.41E6 Cs 134 4.49E10 7.37E10 1.55E10 2.28E10 8. 19E9 3.97E8 Cs 137 6.52E10 6.24E10 9.21E9 2 '3E10 7.32E9 3.91E8 Ba 140 7.05E6 6.18E3 4.12E5 2.01E3 3.68E3 3.57E6 La 140 1.16 4.07E-1 1.37E-1 1.13E4 Ce 141 1.38E3 6.88E2 1.02E2 3.02E2 8.59E5 Ce 144 1.25E5 3.91E4 6.66E3 2.16E4 1.02E7 Nd 147 2.68E1 2.17E1 1.68EO 1.19E1 3.44E4 mrem/yr per pci/m~.

Unit 1 ODCH Revision 14 004152LL June 1994

TABLE 3-15 DOSE AND DOSE RATE Ri VALUES GOAT MILK TEEN me~mrem r pci/sec NUCLIDE BONE LIVER T ~ BODY THYROID KIDNEY LUNG GI-LLI H 3 2.64E3 2.64E3 2 64E3 2.64E3 2.64E3 2.64E3 C 14'r 6.70E5 1.34E5 1.34E5 1.34E5 1.34ES 1.35E5 1.34E5 51 3ellE3 1.73E3 6.82E2 4.44E3 5.23ES Mn 54 1.08E6 2.15E5 3.23ES 2.22E6 Fe 55 3.61E5 2.56E5 5.97E4 1.62ES 1.11ES Fe 59 3.67ES 8.57E5 3.31E5 2.70ES 2.03E6 Co 58 5.46E5 1.26E6 7.53E6 Co 60 2.23E6 5.03E6 2.91E7 Zn 65 1.61EB 5.58E8 2.60E8 '3.57E8 2 '6E8 Sr 89 3.14E9 8.99E7 3.74E8 Sr 90 9.36E10 2.31E10 2.63E9 Zr 95 1.13E2 3.56El 2. 45E1 5.23E1 8.22E4 Nb 95 2.23E4 1.24E4 6.82E3 1.20E4 5.30E7 Mo 99 2.72E6 5.19E5 6.23E6 4.87E6 I 131 1.61E8 2.26E8 1.21E8 6.59E10 3.89E8 4.47E7 I 133 1.99E6 3.38E6 1.03E6 4.72E8 5.93E6 2.56E6 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70E8 Cs 137 2.71E10 3.60E10 1.25E10 1.23E10 4.76E9 5.12E8 Ba 140 2.92E6 3.58E3 1.88E5 1.21E3 2.41E3 4.50E6 La 140 4.86E-1 2.39E-1 6.36E-2 1 ~ 37E4 Ce 141 5.60E2 3.74E2 4.30E1 1.76E2 1.07E6 Ce 144 5.06E4 2.09E4 2 '2E3 1.25E4 1.27E7 Nd 147 1.09E1 1.19E1 7.13E-1 6.99EO 4.29E4 mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-16 DOSE AND DOSE RATE R; VALUES GOAT MILK - ADULT m~~mrem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 C 14 3.63E5 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.78E3 '.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50ES 1.24E5 1.93ES 1.99E6 Fe 55 2.04ES 1 ~ 41E5 3.28E4 7.SSE4 8 07E4 Fe 59 2.10E5 4.95E5 1.90ES 1.38E5 1.65E6 Co 58 3 '5E5 7.27E5 6.58E6 Co 60 1 ~ 32E6 2.91E6 2.48E7 Zn 65 1.05ES 3.33ES 1.51ES 2.23ES 2.10E8 Sr 89 1.70E9 4.89E7 2 '3ES Sr 90 6.62E10 1.63E10 1.91E9 Zr 95 6.45E1 2.07E1 1.40E1 3.25E1 6.56E4 Nb 95 1.31E4 7.29E3 3.92E3 7.21E3 4.42E7 Mo 99 1.51E6 2.87ES 3.41E6 3.49E6 I 131 8.89E7 1.27E8 7.29E7 4.17E10 2.18ES 3.36E7 I 133 1.09E6 1.90E6 5 79ES 2.79ES 3.31E6 1.71E6 Cs 134 1.12E10 2.67E10 2.18E10 8.63E9 2.86E9 4.67ES Cs 137 1.49E10 2.04E10 1.34E10 6.93E9 2.30E9 3.95E8 Ba 140 1.62E6 2.03E3 1.06E5 6.91E2 1.16E3 3.33E6 La 140 2.71E-1 1.36E-l 3.61E-2 1.00E4 Ce 141 3.06E2 2.07E2 2.34E1 9.60E1 7.90E5 Ce 144 2.75E4 1.15E4 1 48E3 6.82E3 9.30E6 Nd 147 5.69EO 6.57EO 3.93E-1 3.84EO 3.15E4 mrem/yr per pci/m~.

Unit 1 GXtf Revision 14 004152LL June 1994

TABLE 3-17 DOSE AND DOSE RATE R; VALUES COW MEAT CHILD m~~mr emr pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 C 14 5 '9E5 1.06ES 1.06E5 1.06E5 1.06E5 1 '6ES 1.06ES Cr 51 4.55E3 2.52E3 6.90E2 4.61E3 2.41ES Mn 54 5.15E6 1.37E6 1.44E6 4.32E6 Fe 55 2.89ES 1.53ES 4.74E7 8.66E7 2 '4E7 Fe 59 2.04EB 3.30ES 1. 65EB 9.58E7 3.44EB Co 58 9.41E6 2.88E7 5.49E7 Co 60 4.64E7 1.37ES 2 '7ES Zn 65 2.38ES 6 '5EB 3.95ES 4 OOES 1.12EB Sr 89 2.65ES 7 '7E6 1.03E7 Sr 90 7.01E9 1.78E9 9.44E7 Zr 95 1.51E6 3.32E5 2 95ES 4.75E5 3.46EB Nb 95 4.10E6 1.59E6 1 '4E6 1.50E6 2.95E9 Mo 99 5.42E4 1.34E4 1.16ES 4.48E4 I 131 4.15E6 4.18E6 2.37E6 1.38E9 6.86E6 3.72E5 I 133 9.38E-2 1.16E-1 4.39E-2 2.15E1 1.93E-1 4.67E-2 Cs 134 6.09ES 1.00E9 2.11ES 3.10ES 1.11EB 5.39E6 Cs 137 8.99EB 8.60EB 1.27EB 2.80ES 1.01ES 5.39E6 Ba 140 2.20E7 1.93E4 1.28E6 6.27E3 1.15E4 1.11E7 La 140 2.80E-2 9.78E-3 3 '0E-3 2e73E2 Ce 141 1.17E4 5.82E3 8.64E2 2.55E3 7.26E6 Ce 144 1.48E6 4.65E5 7.91E4 2.57E5 1.21EB Nd 147 5.93E3 4.80E3 3.72E2 2.64E3 7.61E6 mrem/yr per pci/m~.

Unit 1 ODCR Revision 14 004152LL June 1994

TABLE 3-18 DOSE AND DOSE RATE RI VALUES COW MEAT TEEN m'-~remlrrr pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 C 14 2.81ES 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 Cr 51 2.93E3 1.62E3 6.39E2 4.16E3 4.90E5 Mn 54 4 50E6 8.93E5 1.34E6 9.24E6 Fe 55 1.50ES 1.07E8 2.49E7 6.77E7 4.62E7 Fe 59 1. 15ES 2.69ES 1.04ES 8.47E7 6.36E8 Co 58 8 05E6 1.86E7 1.11E8 Co 60 3.90E7 8 'OE7 5.09E8 Zn 65 1.59ES 5.52ES 2.57ES 3.53ES 2.34ES Sr 89 1.40ES 4.01E6 1.67E7 Sr 90 5.42E9 1.34E9 1.52ES Zr 95 8.50ES 2.68E5 1.84E5 3.94ES 6.19ES Nb 95 2.37E6 1.32E6 7.24ES 1.28E6 5.63E9 Mo 99 3.90E4 7.43E3 8.92E4 6.98E4 I 131 2.24E6 3.13E6 1.68E6 9.15E8 5.40E6 6 20E5 I 133 5.05E-2 8.57E-2 2.61E-2 1 20E1 1.50E-1 6 48E-2 Cs 134 3.46E8 8.13ES 3.77ES 2.58ES 9.87E7 1.01E7 Cs 137 4.88E8 6.49ES 2.26ES 2.21E8 8.58E7 9.24E6 Ba 140 1.19E7 1.46E4 7.68E5 4.95E3 9.81E3 1.84E7 La 140 1.53E-2 7.51E-3 2.00E-3 4.31E2 Ce 141 6.19E3 4.14E3 4.75E2 1.95E3 1.18E7 Ce 144 7.87ES 3.26ES 4.23E4 1.94ES 1.98E8 Nd 147 3.16E3 3.44E3 2.06E2 2.02E3 1.24E7 mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-19 DOSE AND DOSE RATE R; VALUES COW MEAT ADULT m~~meem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 3.25E2 3.25E2 3.25E2 3.25E2 3.25E2 3 25E2 C 14'r 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 51 3.65E3 2.18E3 8.03E2 4.84E3 9.17E5 Mn 54 5.90E6 1.13E6 1.76E6 1.81E7 Fe 55 1.85E8 1.28ES 2.98E7 7.14E7 7.34E7 Fe 59 1.44ES 3.39E8 1 30ES 9.46E7 1 13E9 Co 58 1.04E7 2.34E7 2. 12ES Co 60 5.03E7 1.11E8 9.45ES Zn 65 2.26E8 7.19E8 3.25ES 4.81ES 4 53ES Sr 89 1. 66ES 4.76E6 2.66E7 Sr 90 8 '8E9 2.06E9 2.42E8 Zr 95 1 ~ 06E6 3.40E5 2.30E5 5.34ES 1.08E9 Nb 95 3.04E6 1 ~ 69E6 9.08ES 1.67E6 1.03E10 Mo 99 4.71E4 8.97E3 1.07ES 1.09ES I 131 2.69E6 3.85E6 2.21E6 l. 26E9 6 '1E6 1.02E6 I 133 6.04E-2 1.05E-1 3.20E-2 1.54E1 1.83E-1 9.44E-2 Cs 134 4.35ES 1.03E9 8.45ES 3.35ES 1.11E8 1.81E7 Cs 137 5.88E8 8.04E8 5.26ES 2.73E8 9.07E7 1.56E7 Ba 140 1.44E7 1.81E4 9.44ES 6.15E3 1.04E4 2.97E7 La 140 1 ~ 86E-2 9.37E-3 2.48E-3 6.88E2 Ce 141 7.38E3 4.99E3 5.66E2 2.32E3 1.91E7 Ce 144 9 '3E5 3.90E5 5 '1E4 2 '1ES 3.16ES Nd 147 3.59E3 4.15E3 2.48E2 2.42E3 1.99E7 mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-20 DOSE AND DOSE RATE Rl VALUES VEGETATION CHILD m'~modem pCi/sec NUCLIDE BONE LIVE T. BODY THYROID KIDNEY LUNG GI-LLI H 3 4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 C 14 3.50E6 7.01E5 7 '1E5 7.01E5 7.01E5 7.01E5 7.01E5 Cr 51 1.17E5 6.49E4 1.77E4 1.18E5 6.20E6 Mn 54 6.65ES 1.77E8 1.86ES 5.58E8 Fe 55 7 '3ES 4.05ES 1.25E8 2.29E8 7.50E7 Fe 59 3.97ES 6.42ES 3.20ES 1.86ES 6.69ES Co 58 6.45E7 1.97ES 3.76E8 Co 60 3.78E8 1.12E9 2.10E9 Zn 65 8.12ES 2.16E9 1 ~ 35E9 1. 36E9 3.80ES Sr 89 3.59E10 1.03E9 1.39E9 Sr 90 1.24E12 3.15Ell 1.67E10 Zr 95 3.86E6 8.50ES 7.56E5 1.22E6 8.86ES Nb 95 1.02E6 3.99E5 2.85E5 3.75E5 7 37ES Mo 99 7.70E6 1.91E6 1.65E7 6.37E6 I 131 7.16E7 7.20E7 4.09E7 2.38E10 1.18ES 6.41E6 I 133 1.69E6 2.09E6 7.92E5 3 '9ES 3.49E6 8.44ES Cs 134 1.60E10 2.63E10 5.55E9 8.15E9 2.93E9 1.42E8 Cs 137 2.39E10 2.29E10 3.38E9 7.46E9 2.68E9 1.43E8 Ba 140 2.77ES 2.43ES 1.62E7 7.90E4 1.45ES 1.40E8 La 140 3.25E3 1.13E3 3.83E2 3.16E7 Ce 141 6.56E5 3.27ES 4.85E4 1.43ES 4.08E8 Ce 144 1.27E8 3.98E7 6.78E6 2.21E7 1.04E10 Nd 147 7.23E4 5 86E4 4.54E3 3.22E4 9.28E7 mrem/yr per pci/m~.

Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-21 DOSE AND DOSE RATE VALUES VEGETATION TEEN me~mr emr pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2 59E3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 C 14 1.45E6 2 91E5 2.91E5 2.91E5 2.91E5 2.91E5 2.91E5 Cr 51 6.16E4 3.42E4 1.35E4 8.79E4 1.03E7 Mn 54 4.54E8 9.01E7 1.36E8 9.32ES Fe 55 3.10ES 2 20E8 5.13E7 1.40E8 9.53E7 Fe 59 1.79ES 4.18E8 1.61E8 1.32E8 9.89ES Co 58 4.37E7 1 ~ 01ES 6.02ES Co 60 2.49ES 5.60ES 3.24E9 Zn 65 4.24ES 1.47E9 6.86E8 9 41ES 6.23ES Sr 89 1.51E10 4.33ES 1.80E9 Sr 90 7.51E11 1.85E11 2.11E10 Zr 95 1.72E6 5.44E5 3.74E5 7.99E5 1.26E9 Nb 95 4.80ES 2.66ES 1.46E5 2.58ES 1.14E9 Mo 99 5.64E6 1 ~ OSE6 1.29E7 1.01E7 I 131 3.85E7 5.39E7 2 '9E7 1.57E10 9.28E7 1.07E7 I 133 9.29E5 1.58E6 4 SOES 2.20ES 2.76E6 1.19E6 Cs 134 7.10E9 1.67E10 7 75E9 5.31E9 2.03E9 2 OSES Cs 137 1 ~ 01E10 1.35E10 4.69E9 4.59E9 1.78E9 1.92ES Ba 140 1.38ES 1.69ES 8.91E6 5.74E4 1.14E5 2.13ES La 140 1.81E3 S.SSE2 2.36E2 5.10E7 Ce 141 2 '3E5 1.89ES 2.17E4 8.89E4 5,40ES Ce 144 5.27E7 2.18E7 2.83E6 1.30E7 .1. 33E10 Nd 147 3.66E4 3.98E4 2.3863 2.34E4 1.44E8 mrem/yr per pci/m' Unit 1 ODCM Revision 14 004152LL June 1994

TABLE 3-22 DOSE AND DOSE RATE R, VALUES VEGETATION ADULT mam@emr pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY'.

LUNG GI-LLI H 3 2. 26E3 2.26E3 26E3 2.26E3 2.26E3 2.26E3 C 14 8.97E5 1.79ES 1.79ES 1.79E5 1.79E5 1.79ES 1.79ES Cr 51 4.64E4 2.77E4 1.02E4 6.15E4 1.17E7 Mn 54 3.13ES 5.97E7 9.31E7 9.58E8 Fe 55 2.00E8 1.38ES 3.22E7 7.69E7 7 '1E7

~ Fe 59 1.26E8 2.96ES 1.13E8 8.27E7 1.02E9 Co 58 3.08E7 6.90E7 6 24ES Co 60 1.67E8 '.69ES 3.14E9 Zn 65 3.17E8 1.01E9 4.56ES 6.75ES 6 '6ES Sr 89 9.96E9 2.86ES 1. 60E9 Sr 90 6.05E11 1.48E11 / 1.75E10 Zr 95 1.18E6 3.77E5 2.55E5 5.92ES 1.20E9 Nb 95 3.55E5 1.98E5 1.06ES 1.95ES 1.20E9 Mo 99 6.14E6 1.17E6 1.39E7 1.42E7 I 131 4 04E7 5.78E7 3.31E7 1.90E10 9.91E7 1.53E7 I 133 1.00E6 1.74E6 5.30E5 2.56ES 3.03E6 1.56E6 Cs 134 4.67E9 1.11E10 9.08E9 3.59E9 1.19E9 1.94E8 Cs 137 6.36E9 8.70E9 5.70E9 2.95E9 9.81E8 1.68ES Ba 140 1.29E8 1.61ES 8.42E6 5.49E4 9.25E4 2.65E8 La 140 1.98E3 9.97E2 2.63E2 7.32E7 Ce 141 1.97E5 1.33ES 1.51E4 6.19E4 5.09ES Ce 144 3.29E7 1.38E7 1.77E6 8.16E6 1.11E10 Nd 147 3.36E4 3.88E4 2.32E3 2.27E4 1.86E8 mrem/yr per pci/m~

Unit 1 QXR Revision 14 004152LL June 1994

TABLE 3-23 PARAMETERS FOR THE. EVALUATION OF DOSES TO REAL MEMBERS OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS P~athwa Parameters Value Reference Fish U (kg/yr) - adult 21 Reg. Guide 1.109 Table E-5 Fish D~ (mrem/pCi)

~ Each Radionuclide Reg. Guide 1. 109 Table E-11 Shoreline U (hr/yr) 67 Reg. Guide 1.09 adult 67 Assumed to be same as Adult

- teen Shoreline D~ Each Radionuclide Reg. Guide 1.109 (mrem/hr per pCi/m~) Table E-6 Inhalation DFA- Each Radionuclide Reg. Guide 1..109 Table E-7 Unit 1 ODCM Revt.sion 14 004152LL June 1994

NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 Type of *Map L i n II cin 'nv Pr r mN L i n Radioiodine and Particulates (air)

Nine Mile Point Road North (R-1) 1.8 mi I 88o E Radioiodine and Particulates (air)

Co, Rt. 29 5 Lake Road (R-2) 1.1 mi I 104 ESE Radioiodine and Particulates (air)

Co, Rt. 29 (R-3) 1.5 mi I 132o SE Radioiodine and Particulates (air)

Village of Lycoming, NY (R-4) 1.8 mi I 143o SE Radioiodine and Particulates (air)

Montario Point Road (R-5) 16.4 mi I 42o NE Direct Radiation (TLD) North Shoreline Area (75) 0.1 rnl I 5o N Direct Radiation (TLD) North Shoreline Area (76) 0.1 mi I 25o NNE Direct Radiation (TLD) North Shoreline Area (77) 0.2 mi I 45o NE Direct Radiation (TLD) North Shoreline Area (23) 0,8 mi I 70o ENE I

P Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi 90o E Direct Radiation (TLD) Rt. 29 (79) 1.1 mi @ 115o ESE Direct Radiation (TLD) 12 Rt. 29 (80) 1.4 mi I 133o SE Direct Radiation (TLD) 13 Miner Road (81) 1.6mi I 159'SE Direct Radiation (TLD) 14 Miner Road (82) 1.6mi I 181' Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi I 200 SSW Direct Radiation. (TLD) 16 Lakeview Road (84) 1.1 mi I 225o SW Direct Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 mi I 250 WSW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi I 265o W

• Map = See Figures 5.1-1 and 5.1-2 Unit 1 ODC8 Revision 14 004152LL June 1994

NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of *Map I L in Env.Pr r mN Direct Radiation (TLD) 19 North Shoreline (85) 0.2 mi I 294~ WNW Direct Radiation (TLD) 20 'orth Shoreline (86) 0.1 mi I 315o NW Direct Radiation (TLD) 21 North Shoreline (87) 0.1 mi 5 341'NW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi I 97' Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi I 111o ESE Direct Radiation (TLD) 24 Rt. 104 (90) 4.2 mi I 135~ SE Direct Radiation (TLD) 25 Rt. 51A (91) 4,8 mi @ 156 SSE Direct Radiation (TLD) 26 Maiden Lane Road (92) 4.4 mi I 183~ S Direct Radiation (TLD) 27 Co. Rt. 53 (93) 4.4 mi I 205 SSW Direct Radiation (TLD) 28 Co. Rt. 1 (94) 4.7 mi I 223o SW Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi 5 237o WSW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 mi I 163~ S Direct Radiation (TLD) 31 S. W. Oswego, Control (14) 12.6 mi I 226o SW Direct Radiation (TLD) 32 Scriba, NY (96) 3.6 mi 5 199 SSW Direct Radiation (TLD) 33 Alcan Aluminum, Rt. 1A (58) 3.1 mi@220~ SW Direct Radiation (TLD) 34 Lycoming, NY (97) 1.8 mi I 143o SE Direct Radiation (TLD) 35 New Haven, NY (56) 5.3 mi I 123o ESE Direct Radiation (TLD) 36 W. Boundary, Bible Camp (15) 0.9 mi I 237 WSW Direct Radiation (TLD) 37 Lake Road (98) 1.2 mi I 101~ E Surface Water 38 OSS Inlet Canal (NA) 7.6 mi I 235~ SW Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi I 70~ ENE (NA) = Not applicable

• IVlap = See Figures 5.1-1 and 5.1-2 Unit 1 ODC8 Revision 14 004152LL June 1994

NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALIVIONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of *Map Sam le Location Collection Site Env. Pro ram No. Loca ion Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi I 80o E Fish NMP Site Discharge Area (NA) 0.3 mi I 315~ NW Fish 42 NMP Site Discharge Area,(NA) I 55'E (and/or) 0.6mi Fish 43 Oswego Harbor Area (NA) 6,2mi I 235~ SW Milk 44 Milk Location ¹50 8 2 mi I 93o E Milk 45 Milk Location ¹7 5.5 mi I 107'SE Milk 47 Milk Location ¹65 17.0 mi @ 220 SW Milk 64 Milk Location ¹55 90mio 95' Milk 65 Milk Location ¹60 95mio90o E Milk 66 Milk Location ¹4 7.8 mi I 113~ ESE Milk (CR) 73. Milk Location (Woodworth) 13 9 mi I 234 SW Food Product 48 Produce Location ¹6++

(Bergenstock) (NA) 1.9 mi I 141 ~ SE Food Product 49 Produce Location ¹1++ 1.7 m) @ 96o E (Culeton) (NA)

Food Product 50 Produce Location ¹2++

(Vitullo) (NA) 1.9 mi I 101 o E Food Product 51 Produce Location ¹5++

(C.S. Parkhurst) (NA) 1.5 rni I 114o ESE Food Product 52 Produce Location ¹3++ 1,6mio84o E (C. Narewski) (NA)

The Jones milk location has been deleted due to the herd being sold. (Map location ¹46.)

• Map = See Figures 5.1-1 and 5.1-2

++ Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

(NA) Not applicable Control Result (location)

Unit 1 ODCM Revision 14 004152LL June 1994

e NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAIVIPLING LOCATIONS TABLE 5.1 (Continued)

Type of *Map I Lo i II i n i Env.Pr r L in Food Product 53 Produce Location ¹4++

(P. Parkhuist) (NA) 2.1 mi I 110 ESE Food Product (CR) 54 Produce Location ¹7++

(Mc Millen) (NA) 15.0 mi I 223'W Food Product (CR) 55 Produce Location (NA)

¹8

'Denman) 12.6 mi I 225 SW Food Product 56 Produce Location ¹9 1.6 mi @ 171~ S (O'onnor) (NA)

Food Product 57 Produce Location (C. Lawton) (NA)

¹10 2.2 mi I 123 ESE Food Product 58 Produce Location ¹11" (C. R. Parkhurst) (NA) 2.0 mi I 112 ESE Food Product 59 Produce Location (Barton) (NA)

¹12 1.9 mi I 115 ESE Food Product (CR) 60 Produce Location (Flack) (NA)

¹13 ' 15.6 mi I 225o SW Food Product 61 Produce Location (Koeneke) (NA)

¹14 1.9 mi I 95~ E Food Product 62 Produce Location (Whaley) (NA)

¹15 1.7 mi I 136~ SE Food Product 63 Produce Location (Murray) (NA)

¹16 1.2 mi I 207~ SSW

• Map See Figures 5.1-1 and 5.1-2

++ Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

(NA) Not applicable Control Result (location)

Unit 1 ODCH Revision 14 004152LL June 1994

0 FIGURE 5.1-1 Unit 1 (XX'evision 14 004152LL June 1994

FIGURE 5.1-2 Unit 1 ODQ4 Revision 14 004 152LL June 1994

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APPENDIX A LIQUID DOSE FACTOR DERIVATION Unit 1 ODCR Revision 14 004152LL June 1994

Appendix A Liquid Effluent Dose Factor Derivation, A A (mrem/hr per pCi/ml) which embodies the dose conversion factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water and the sediment. The total body and organ dose conversion factors for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109. To expedite time, the dose is calculated for a maximum individual instead of each age group. The maximum individual dose factor is a composite of the highest dose factor A of each nuclide i age group a, and organ t, hence A,. It should be noted that the fish ingestion pathway is the most sig'nificant pathway for dose from liquid effluents. The water consumption pathway is included for consistency with NUREG 0133.

The equation for calculating dose contributions given in section 1.3 requires the use of the composite dose factor A;, for each nuclide, i. The dose factor equation for a fresh water site is:

-X)t~ -X,t~

)(DFL)% +eee D>>

+ 69.3 DW e

-S,t e (3-e -3,eb' (DSS),)

(D.) (3i)

Where:

Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per pCi/ml).

Ko Is the unit conversion factor, 1914E5~1E6pCi/pCi x 1E3 ml/kg -: 8760 hr/yr.

U Water consumption (1/yr); from Table E-5 of Reg.

Guide 1.109.

U/ Fish consumption (Kg/yr); from Table E-5 of Reg.

Guide 1.109.

U, Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg. Guide 1.109.

(BF)~ Bioaccumulation factor for nuclides is in fishs (pCi/kg per pCi/1), from Table A-1 of Reg. Guide 1.109.

(DFL)~ Dose conversion factor for age, nuclides is group a, total body or organ t, (mrem/pCi)s from Table E-11 of Reg. Guide 1.109.

(DFS) i Dose conversion factor for nuclide body, from standing on contaminated ground i and total (mern/hr per pCi/m~); from Table E-6 of Reg.

Guide 1.109.

D Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitan Water Board, Onondaga County intake structure located west of the City of Oswego; (unitless).

Unit 1 ODCM Revision 14 004152LL June 1994

Appendix A (Cont'd)

D, Dilution factor from the near field area, within one, quarter mile of the rel'ease point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles; unitless).

69.3 conversion factor .693 x 100, 100 ~ K, (L/kg-hr)

• 40*24 hr/day/.693 in L/m~-d, and K, = transfer coefficient from water to sediment in L/kg per hour.

Average transit time required for each nuclide to reach the'point of exposure for internal dose, it is the total time elapsed from release of the nuclides to either ingestion for water (w) and fish (f) or shoreline deposit (s), (hr).

Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life), (hrs).

decay constant for nuclide i (hr').

Shore width factor (unitless) from Table A-2 of Reg.

Guide 1.109.

Example Calculation For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release:

(DFS) ) 2.80E-9 mrem/hr per pCi/m~

(DFL)4, 1.95E-3 mrem/pci 30 hrs. (w ~ water)

BF, 15 pCi/Kg per pCi/L t< 24 hrs. (f ~ fish)

U/ 21 Kg/yr t 1.314ES hrs. (5.48E3 days)

D 40 unitless U 730 L/yr D, 12 unitless Ko 1.14ES Ci Ci ml k U, 12 hr/yr (hr/Yr)

W 0.3 3.61E-3hr'rs 5.5 (s = Shoreline Sediment)

These values will yield an Factor of A. 6.79E4 mrem-ml per pCi-hr as listed in Table 2-4. It should be noted that only a limited number of nuclides are listed on Tables 2-1 to 2-8. These are the most common nuclides encountered in effluents. If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.

In addition, not all dose factors are used for the dose calculations. A maximum individual is used, which is a composite of the maximum dose factor of each age group for each organ as reflected in the applicable chemistry procedures.

Unit 1 ODCR Revision 14 004152LL June 1994

APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION Unit 1 ODOM Revision 14 004152LL June 1994

APPENDIX B For elevated releases the plume shine dose factors for gamma air (B;) and whole body (V~)g are calculated using the finite plume model with an elevation above ground equal to the stack height. To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is ad)usted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air. The equations are as follows:

Air

. Gamma B, E, R8 V, Where: K'onversion factor (see below for actual value).

mass absorption coefficient (cm~/gg air for B tissue for V,)

E = Energy of gamma ray per disintegration (Mev)

V, average wind speed for each stability class (s),

R = downwind distance (site boundary, m) 8 = sector width (radians) s = subscript for stability class I, = I function I, + kI~ for each stability class. (unitless, see Regulatory Guide 1.109)

Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)

W~hole Bod Patd V, 1. 11SB,e Where: t~ = tissue depth (g/cm~)

S . = shielding factor from structures (unitless) 1.11 = Ratio of mass absorption coefficients between tissue and air.

Where all other parameters are defined above.

'K = conversion factor [3.7 E10 midis 1.6 E<<6 ercr]

Ci-sec Mev .46

[1293 g ] [100 ~er ]

g-rad

~

m

~k ~

Pd Where: p ~ mass attenuation coefficient (cm /g; air for B~, tissue for V,)

p, = defined above Unit 1 ODCR Revision 14 004152LL June 1994

APPENDIX B (Cont'd)

There are seven stability classes, A thru F. The percentage of the year that each stability class occurs is taken from the U-2 FSAR. From this data, a plume shine dose factor is calculated foi each stability class and each nuclide, multiplied by its respective fraction and then summed.

The wind speeds corresponding, to each stability class are, also, taken from the U-2 FSAR. To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values. The average wind speed of the actual data is equal to 6.78 m/s, which compared favorably to the .FSAR average wind speed equal to 6.77 m/s.

The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide. These energies were taken from the handbook "Radioactive Decay Data Tables", David C. Kocher.

The mass absorption (p,) and attenuation (p) coefficients were calculated by multiplying the mass absorption (p,/p) and mass attenuation (p/p) coefficients given in the Radiation Health Handbook by the air density equal to 1.293 E-3 g/cc or the tissue density of 1 g/cc where applicable. The tissue depth is 5g/cm~ for the whole body.

The downwind distance is the site boundary.

Unit 1 ODCR Revision 14 004152LL June 1994

APPENDIX B (Cont'd)

SAMPLE CALCULATION Ex. Kr-89 F STABILITY CLASS ONLY Gamma Air

-DATA E

PE 2.22MeV 2.943 E-3m' 5064E-3m) k EE

=

~ PE 644m

.871 K

VF

.46 5.55 m/sec P R e .39 a, 19m.......vertical plume spread taken from "Introduction to Nuclear Engineering", John R. LaMarsh

-I Function Uc, .06 EE .33

1) .45 EE I> + kIz ~ 33 + ( ~ 871) ( ~ 45) ~ 72 dis.

Bi 0.46 Ci-sec Mev er s 2.943E-3m'.22Mev .72 (mQ) (g/m') (ercrs) (5.55 m/s) (.39) (644m)

(g-rad) 1.55(-6) rad s 3600 s hr 24 h d 365 d 1E3mrad rad Ci/s (~1E6 Ci.)

Ci 2.76(-2) mead r pCi/sec

<<(.0253 cm~/g) (Sg/cm~)

1.11 (.7) 2.76(-2) prado] [e )

pCi/secJ 1.89(-2) meadr pci/sec NOTE: The above calculation is for the F stability class only. For Table 3-2 and procedure values, a weighted fraction of each stability class was used to determine the B< and V> values.

Unit 1 ODCR Revision 14 004152LL June 1994

0 APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM Unit 1 ODQ4 Revision 14 004152LL June 1994

0 APPENDIX C DOSE PARAMETERS FOR IODINE 131 AND 133 g PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the organ dose factors for I-131i I 133@ particulates, and tritium. The dose factor, Q, was calculated using the methodology outlined in NUREG-0133. The radioiodine and particulate Technical Specification (Section 3.6.15) is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor. Washout was calculated and determined to be negligible. g values have been calculated for the adult, teen, child and infant age groups for all pathways. However, for dose compliance calculations, a maximum individual is assumed that is a composite of highest dose factor of each age group for each organ and pathway. The methodology used to calculate these values follows:

C.l Inhalation Pathwa K'BR) ~ (DFA) g, where:

Q(I) dose factor for each identified radionuclide of the organ of interest (units = mrem/yr per i

pci/m~) i K' constant'f unit conversion, 1E6 pCi/pCi (BR), Breathing rate of the receptor of age group a, (units ~ m~/yr);

(DFA)6, The inhalation dose factor for nuclide i, organ and age group a, and organ t (units ~

mrem/pci) .

The breathing rates (BR), for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.

A e Grou a Breathin Rate m~ r Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA)> for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.

Unit 1 ODCM Revision 14 004152LL June 1994

APPENDIX C (Cont'd)

C.2 Ground Plane Pathwa K'K SF DFG l>>e

-l,t R;(G)

Where:

K'ose Q(G) factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units ~ m~-mrem/yr per pci/sec)

A constant of unit conversion, 1E6 pCi/pCi A constant of unit conversion, 8760 hr/year The radiological decay constant for radionuclide i, (units sec')

t The exposure time, sec, 4.73E8 sec (15 years)

(DFG) ~

The ground plane dose conversion factor for radionuclide ig (units ~ mrem/hr per pCi/m~)

SF The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of DFG, values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.

Unit 1 ODCR Revision 14 004152LL June 1994

APPENDIX C (Cont'd)

C.3 Grass- Cow or Goat -Milk Pathwa

-l,iti Ri(C) ~ K' F r DFL ~f f + (~f g,)(e-1)ti, e

+ ") Y, Where:

K'ose Ei(C) factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, (units m2-mrem/yr per A

pci/sec) constant of unit conversion, lE6 pCi/pCi

~

The cow's or goat's feed consumption rate, (units = Kg/day-wet weight)

The receptor's milk consumption rate for age group a, (units =

liters/yr)

The agricultural productivity by unit area of pasture feed grass, (units = kg/m2)

Y, The agricultural productivity by unit area of stored feed, (units =

kg/m2)

The stable element transfer coefficients, (units pCi/liter per pci/day)

Fraction of deposited activity retained on cow's feed grass (DFL) Li The ingestion dose factor for nuclide i, age group a, and total body or organ t (units ~ mrem/pCi)

The radiological decay constant for radionuclide i, (units=sec -1)

The decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E-7 sec -1 (corresponding to a 14 day half-life)

The transport time from pasture to cow or goat, to milk, to receptor, (units = sec)

The transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units ~ sec)

Unit 1 CMXtt Revision 14 004152LL June 1994

APPENDIX C (Cont'd)

Fraction of the year that the cow or goat is on pasture (dimensionless)

,. Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f, is considered unity in lieu of site specific information. The value of f, is 0.5 based on 6 month grazing period. This value for f, was obtained from the environmental group.

Table C-1 contains the appropriate values and their source in Regulatory Guide 1.109 Revision l.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Rz(C) is based on X/Q:

+(C) ~ K'K' '~QP~(DFL)~ 0 75(0 5/H)

Where:

%(C) Dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units = mrem/yr per pci/m~)

A constant of unit conversion, 1E3 g/kg H Absolute humidity of the atmosphere, (units ~ g/m')

0.75 The fraction of total feed that is water o.s The ratio of the specific activity of the feed grass water to the atmospheric water Other values are given previously. A site specific value of H equal to 6.14 g/m~ is used. This value was obtained from the environmental group using actual site data.

Unit 1 ODCM Revision 14 004152LL June 1994

APPENDIX C (Cont'd)

C.4 Grass-Cow-Meat Pathwa

-l,)tb e g(C) ~ K' F r DFL [~f f + (~1-f f )(e

+ l) Y, Q(M) Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units ~ m~-mrem/yr per pci/sec)

The stable element transfer coefficients, (units = pCi/kg per P<</day)

The receptor's meat consumption rate for age group a, (units ~

kg/year)

The transport time from harvest, to cow, to receptor, (units ~

sec)

The transport time from pasture, to cow, to receptor, (units ~

sec)

All other terms remain the same as defined for the milk pathway. Table C-2 contains the values which were used in calculating g(M).

The concentration of tritium in meat is based on airborne concentration rather than deposition. Therefore, the R~(M) is based on X/Q.

RT (M) K'K' 'FPP~(DFL)~ [0 75(0 5/H) )

~

Where:

Q(M) ~ Dose factor for the meat ingestion pathway. for tritium for any organ of interest, (units mrem/yr per pCi/m')

All other terms are defined above.

K'l,tb C.S Ve etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed for milk. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

Q(V) ~ r (DFL)~ U",Fe + U',F,e Y(l, + A,).

Unit 1 ODCM Revision 14 004152LL June 1994

APPENDIX C (Cont'd)

Where:

W(V) Dose factor for vegetable pathway for radionuclide for the organ of interest, (units ~ m~-mrem/yr per pCi/sec) i K'L A constant of unit conversion, 1E6 pCi/pCi The consumption rate of fresh leafy vegetation by the receptor in age group a, (units = kg/yr)

U', The consumption rate of stored vegetation by the receptor in age group a (units ~ kg/yr)

F The fraction of the annual intake of fresh leafy vegetation grown locally F The fraction of the annual intake of stored vegetation grown locally The average time between harvest of leafy vegetation and its consumption, (units ~ sec)

The average time between harvest of stored vegetation and its consumption, (units = sec)

Yy The vegetation areal P density, (units = kg/m~)

All other factors have been defined previously.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.

In lieu of site-specific data, values for F and F~ of, 1.0 and were used in the calculation. These values were obtained0.76'espectively, from Table E-15 of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rz(V) is based on X/Q:

Rp(V) ~ K K (U ft. + U'a fc](DFL)~ 0.75(0.5/H)

Where:

+(V) . dose factor for the vegetable pathway fo'r tritium for any organ of interest, (units ~ mrem/yr per pCi/m~).

All other terms are defined in preceeding sections.

Unit 1 ODQ4 Revision 14 004152LL June 1994

0 TABLE C-l Parameters for Grass-(Cow or Goat)-Milk Pathways Reference Parameter Value Re . Guide 1.109 Rev. 1 Q, (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL)> (mrem/pCi) Each radionuclide Tables E-ll to E-14 F (pCi/liter per pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

Y, (kg/mi) 2.0 Table E-15 Y, (kg/m~) 0.7 Table E-15 t (seconds) 7.78 x 10~ (90 days) Table E-15 t, (seconds) 1.73 x 10~ (2 days) Table E-15 U~ (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 Unit 1 ODCM Revision 14 004152LL June 1994

TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Reference

~Pa amete Va ue e . Gu de .109 ev 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/day) Each stable element Table E-1 U (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL)> (mrem/pCi) Each radionuclide Tables E-11 to E-14 Y~ (kg/m~) 0.7 Table E-15 Y, (kg/m~) 2.0 Table E-15 tb (seconds) 7.78E6 (90 days) Table. E-15 tf ( seconds ) 1;73E6 (20 days) Table E-15 Q (kg/day) 50 Table E-3 Unit 1 ODCM Revision 14 004152LL June 1994

TABLE C-3 Parameters for the Vegetable Pathway Reference Parameter Value Re . Guide 1.109 Rev. 1 r (dimensionless) 1.,0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL)> (mrem/pCi) Each radionuclide Tables E-11 to E-14 U"), (kg/yr) infant 0 Table E-5

- child 26 Table E-5 teen 42 Table E-5

- adult 64 Table E-5 U'), (kg/yr) - infant 0 Table E-5 child 520 Table E-5 teen 630 Table E-5

- adult 520 Table E-5 t (seconds) 8.6E4 (1 day) Table E-15 t~ (seconds) 5.18E6 (60 days) Table E-15 Y(kg/m ) 2.0 Table E-15 Unit 1 QX8 Revision 14 004152LL June 1994

APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMS AND MONITORING SYSTEMS Uni.t 1 ODCM Revt.sion 14 004152LL June 1994

0 P