ML20106D405

Offsite Dose Calculation Manual

ML20106D405
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1984
From:	OMAHA PUBLIC POWER DISTRICT
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ML20106D387	List: ML20106D386 ML20106D400 ML20106D405
References
PROC-840831, NUDOCS 8410250126
Download: ML20106D405 (36)

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TABLE OF-CONTENTS Reference Section of Section No. Title Technical Specifications Page No.

1 INTRODUCTION --- 1 2 EFFLUENT MONITOR SETP0INTS ---. 2 12.1 Liquid Effluent Radiation 2.9.1(1)d. & e. 2 Monitors 2.2 Gaseous Effluent Radiation 2.9.1/2)e. & f. 4 Monitors 3 CONCENTRATION'IN LIQUID 2.9.1(1)a. 8 EFFLUENTS 4- ~ DOSE CONTRIBUTIONS FROM 2.9.1(1)b. 10 LIQUID EFFLUENTS 4.1 Ingestion Dose Commitment --- 10 Factors

5 LIQUID RADWASTE TREATMENT. 2.9.1(1)c. 13 SYSTEM 6__ CONCENTRATIONS IN GASE0US 2.9.1(2)a. 14 EFFLUENTS 6.1 Noble Gases --- 14 6;2' Radiciodines.and Particulates --- 14 DOSE CONTRIBUTIONS FROM GASEOUS 2.9.1.(2)b. 17 7.

EFFLUENTS Air Dose Due to Noble Gases 17 7.1 ---

"? ~ Dose Due to Radioiodines and 17 7.2 ---

Particulates 8 GASE0US RADWASTE TREATMENT 2.9.1(2)c. 25 SYSTEM 3.11 26

9. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

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LISTING 0F TABLES-

.Titl e - Page No.

P Table No.

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foriLiquidPathways(Adult) 12

- 1- JA g 19 2: .-Dose Factors for Noble Gases

-Dose Factors for I-131,.H-3:and' Radioactive 20

.3 Particulates Via Inhalation Pathway (Child)

Dose Factors for I-131, H-3 and Radioactive 21 T4.

Particulates Via Inhalation Pathway (Infant)

Dose Factors for I-131, H-3 and Radioactive- 22 5:

Particulates Via. Ground and Food Pathways (Child) 6 Dose Factors for-I-131, H-3 and Radioactive 12 3 Particulates Via Ground and Food Pathways '(Infant)

Annual ~ Average Dispersion and Relative Deposition 24 17

' Factors 27

.8; Reporting-Levels for Radioactivity Concentra-tions in Environmental Samples Detection ~ Capabilities for Environment Sample: 28_

9 Analysis Lower Limit of; Detection (LLD)

Radiological Environmental Monitoring Program 30 110- -

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Figure No. - Title Page No.

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1. INTRODUCTION Section 50.36a of 10.CFR Part 50 requires certain specific provisions to l assure that releases of radioactive material-from the plant to unrestricted areas during normal plant operations, including expected operational occur-rences, are kept as low as is reasonably achievable. These provisions have been incorporated in the pertinent sections of the Technical Specifications of the Fort Calhoun Station Unit No. 1 as deemed appropriate and necessary in order to provide conformance with Section 50.36a and Section 50.36, " Technical Specifi-cations," of 10 CFR Part 50.

.The Offsite Dose Calculation Manual (0DCM) has been developed to provide

- guidance-for calculating the concentrations of radioactive effluents, the doses to any individual via various exposure pathways, and alarm and trip action setpoints for radiation effluent monitors in order to comply with the provisions of Section 20.106 and 10 CFR Part 20 and Section 50.36a and Appendix I of 10 CFR

.Part 50. The ODCM is a manual that also describes the methodology and para-meters to be used in the calculation of doses to any individual in the unre-stricted areas due to radioactive liquid and gaseous effluents.

Section 2 of'this manual contains the equations and methodology to be used

~at the Fort Calhoun Station for each alarm and trip setpoint on each effluent release point according to Specifications 2.9.1(1)d. and 2.9.1(1)e. for liquid effluents and Specifications 2.9.1(2)e. and 2.9.1(2)f. for gaseous effluents.

High. alarm monitor setpoints will be set based on values as determined by 0DCM, but not to exceed the upper scale of the monitor.

Sections 3, 4, and 5 of this manual are applicable to specification on liquid effluents. . Sections 3 and 4 contain the equations and methodology to be used according.to Specifications 2.9.1(1)a. and 2.9.1(1)b. Section 5 describes the equipment or subsystem (s) of liquid radwaste treatment system to be used for providing compliance with Specification 2.9.1(1)c.

Sections 6, 7, and 8 of this manual are applicable to specification on

gaseous effluents. Sections 6 and 7 contain the equations and methodology to be used accord _ing to Specifications 2.9.1(2)a. and 2.9.1(2)b. Section 8 describes

the equipment or subsystem (s) of the gaseous radwaste treatment system to be used for providing conformance with Specification 2.9.1(2)c.

-Section 9 provides the details describing the Radiological Environmental Monitoring Program as required by Specification 3.11. This section also pro-vides a map and table of the sample locations and the analysis schedule.

This manual will be used along with plant administrative and surveillance and dose evaluation procedures for liquid and gaseous effluents and for environmental monitoring program. Any changes to this manual shall be reviewed and approved by the Plant Review Committee and audited by the Safety Audit and Review Committee, as designated by Specifications 5.5.1.69 and 5.5.2.8. Changes to this manual shall be submitted to the Commission pursuant to Specification 5.9.4.a.

a -.- _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ - - _ _ _ _ - _ - _ - _ _ _ _ _ _ _ .____ _ ____ -

- 2. EFFLUENT MONITOR SETPOINTS 2.1 Liquid Effluent Radiation Monitors 2.1.1' Steam Generator Blowdown Monitors (RM-054A and B) 4 These process radiation. detectors monitor the flow through the

. steam generator blowdown lines and automatically close-the blowdown

-isolation valves if the monitor high alarm setpoint is reached. The high alarm setpoint calculations are based on controlling the outfall at 10 CFR-Part 20 limits of 1.0E-07 pCi/cc for unrestricted areas, for unidentified isotopes.

The maximum allowable concentration in the blowdown line is calculated as follows:

(1.0E-07 pCi/cc) (Xg)

A=

g y a

where:

X = Dilution flow in the discharge tunnel (gpm).

g (Normal flow is based on 1 circulating water pump at 120,000 gpm)

Y = Blowdown flow rate (gpm). (Normal blowdown flow rate is based on 2 transfer pumps-with a design flow of 135 gpm each, 270 gpm total).

A = Maximum allowable blowdown line concentration (pCi/cc).

g Thehighalarmsetpoint(CPM)=

8.5E-01 (Sp) (A-)

g +B where:

8.5E-01 = Correction factor for instrument meter error.

S = Detector sensitivity factor (CPM /pCi/cc).

p (Sensitivity based on CS137)

A = Maximum allowable blowdown line activity (pCi/cc).

g B = Background (CPM).

Setpoints may be recalculated based on adjusted dilution flow and adjusted blowdown flow.

2. EFFLUENT MONITOR SETPOINTS (Continued) 2.1.2 Overboard Discharae Header Monitor (RM-055 or RM-055A)

This process radiation monitor provides surveillance of the waste monitor tank effluent.by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at the tunnel outfall is controlled below the 10 CFR' Part 20 limit of 1.0E-07 pCi/cc for unrestricted areas for unidentified isotopes by the high alarm setpoint which also closes the overboard flow control valve.

The maximum allowable concentration in the overboard discharge header is:

(1.0E-07 pCi/cc) (Xg)

Ag = y o

where:

X = Dilution flow in the discharge tunnel (gpm).

g Y = Maximum monitor tank discharge flow rate (gpm).

g A = Maximum allowable activity in discharge header (pCi/cc)..

The high alarm setpoint (CPM) =

8.5E-01' (Sp) (Ag.) + B where:

8.5E-01 = Correction factor for instrument meter error.

Sp = Detector sensitivity factor (CPM /pCi/cc).

(Sensitivity based on CS137)

A = Maximum allowable concentration in discharge header g

(pCi/cc).

B = Background (CPM).

-2. EFFLUENT ~MONITORSETPOINTS'(Continued)

-2.2. Gaseous Effluent Radiation Monitors

.2.2.1 Stack Particulate Monitors (RM-061/RM-050)

Either of these monitors may be used to measure airborne particulate activi.ty in the ventilation stack. The detector is located adjacent to a section of moveable filter paper on a capstan drive which is set to move'in a continuous mode. The monitor measures airborne particulate activity releases so that the unrestricted areas limits (of 1.0E-10 pCi/cc) for radionuclides with half-lives greater --

than 8 days are not exceeded at the site boundary. The Ventilation Isolation Actuation Signal (VIAS) is initiated when the high alarm setpoint is reached.

The maximum allowable release rate:

/ x(l'.0E+06cc/m3)=6.67E00uCi/sec

, f where:

1.0E-10 pCi/cc = Limiting activity at site boundary for unidentified isotopes with half lives greater than 8 days.

1.5E-05 sec/m3 = Annual average dispersion factor at the site boundary.

The high. alarm setpoint (CPM):

(6.67E00) (Sp ) (F3 ) (T)-

8.5E-01 +B (p

where:

1.1

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8.5E-01 = Correction for instrument meter error.

S = Detector s'ensitivity factor (CPM /pCi).

p (Sensitivity based on CS137)

F = Monitor sample flow rate (SCFM).

s T = Effective monitor response time (sec).

Fy = Vent stack flow rate (SCFM).

B = Background (CPM).

i s

2. EFFLUENT MONITOR SETPOINTS (Continued)

-2.2.2 Stack Gaseous Activity Monitors (RM-062/RM-051)

- Either of these monitors may be used to measure gaseous acti-vity'in the ventilation stack. The gas is monitored after passing through a particulate filter. The monitor controls gaseous activity releases so that the unrestricted area limits of 3.0E-07 uCi/cc for

-. noble gases are not exceaded at the site boundary. The Ventilation

. Isolation Actuation Signal is initiated when the high alarm setpoint is reached.

The maximum allowable release rate:

x 1.0E+06 cc/m3 =-2.0E+04 pCi/sec E /

where:

3.0E-07 pCi/cc = Limiting gaseous activity at site boundary for XE-133.

1.5E-05 sec/m3 = Annual average dispersion factor at the site boundary.

The high alarm'setpoint (CPM):

(2.00E+04)(S) p (60) 8.5E-01 +B (Fy) (28316)

(4.24E+01) (Sp )

= 8.5E-01 +B (Fg where:

8.5E-01 = Correction for instrument meter error.

Sp = Detector sensitivity factor (CPM /uCi/cc).

(Sensitivity based on CS137) 60 = Conversion (seconds to minutes).

28316 =-Conversion factor (ft3 tocc).

Fy = Vent stack flow rate (ft3/ min).

B = Background (CPM).

x - -

L s

= 2. ' EFFLUENT MONITOR SETPOINTS (Continued)

~2.2.3 -Stack Iodine Monitor (RM-060)

}

RM-060 monitors the gaseous waste discharged from the stack for iodine-(I-131) activity by continuously counting a charcoal filter cartridge through which a sample of ventilation stack air is passing at a known rate. The monitor alarm setpoint initiates the Ventilation

-Isolation Actuation Signal, when reached, and prevents the concentra-tion of iodine activity, at the site boundary, from exceeding 10 CFR Part 20 limits for unrestricted areas.

The maximum allowable release rate:

1 E /j x (1.0E+06 cc/m3) = 6.67E00 uCi/sec

.where:

1.0E-10 pCi/cc = Limiting activity at site boundary for I-131.

The high alarm setpoint (CPM):

(6.67E00) (Sp ) (F)(T)(E) s 8.5E-01 +B (Fg where:

8.5E-01 = Correction factor for instrument meter error.

Sp = Detector sensitivity factor (CPM /uCi), (Sensitivity based on 1 131)

F = Monitor sample flow rate (SCFM).

s T = Effective monitor response time (sec).

Fy = Vent stack flow rate (SCFM).

E' = Charcoal filter collection efficiency.

B =_ Background (CPM).

. _ _ _ _ _ _.-__. __ -- I-_---.__

2. ' EFFLUENT MONITOR SETPOINTS (Continued) 2.2.4 Condenser Air Ejector Monitor (RM-057)_ t j

This monitor is located in the turbine building and monitors the condenser off-gases. The purpose of this monitor is to monitor gaseous releases so that.the 10 CFR Part 20 limits for unrestricted areas are not exceeded.

The maximum allowable release rate:

E- x 1.0E+06 cc/m3 = 2.0E+04 uCi/sec E,

where:

3.0E-07 uCi/cc = Limiting gaseous activity at site boundary for XE-133. .

1.5E-05 sec/m3 = Annual average dispersion factor at the site boundary.

The high alarm setpoint (CPM):

(2.0E+04)(S) p (60) 8.5E-01

+B (Fy) (28316)

(4.24E+01) (Sp )

= 8.5E-01 +B (7 )

where:

8.5E-01 = Correction for_ instrument meter error.

S p = Detector sensitivity factor (CPM /pCi/cc).

(Sensitivity based on CS137) 60 = Conversion (seconds to minutes).

28316 = Conversion factor (cubic feet to cc).

Fy

= Condenser vent system flow rate (f t3/ min).

I

3. CONCENTRATIONS IN LIQUID EFFLUENTS The concentration of radioactive liquid effluents to the unrestricted area

-will be limited to the concentration levels of 10 CFR Part 20, Appendix B, Table II.

For batch releases (Monitor and Hotel Waste Tanks) and for continuous releases (Steam Generator Blowdown), the analyses will be performed in accor-dance with Table 3-11 of the Technical Specifications and the concentration of each radionuclide will be-less than or equal to the maximum permissible concen-trations of 10 CFR Part 20, Appendix B, Table II.

- The following method will be utilized to calculate the concentrations of liquid effluents for each radionuclide at the point of discharge based on certain known parameters:

a;f C4 =_ p- < MPC, where:

C is the concentration at the point of discharge for nuclide, 1, 9

in pCi/ml.

a is the concentration of nuclide, i, in the tank or steam generator, 9

in pCi/ml.

f is the total undiluted effluents flow rate, in gpm.

F is the total circulating water flow rate in the discharge canal, in gpm.

MPC is the maximum permissible concentration for nuclide, i, per 9 10 CFR Part 20, Appendix B, Table II.

NOTE: In addition to the above defined method, NOTES 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.

The lower limit of ' detection (LLD), referenced in Table 3-11 of the Tech-nical Specifications, is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b bb0 " E . V . 2.22 x 106 . Y . exp (-Aat)

3. CONCENTRATIONS IN LIQUID EFFLUENTS (Continued)

Where:

L LLD is the lower limit of detection as defined above, as microcuries per unit mass or. volume, l sg is the standard deviation of t!.e background counting rate or of the .

c5unting rate of.a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106.is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, x is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as before the fact limit representing the capability of a measurement system and not as after the fact

for a particular measurement.

r 3

~4. DOSE CONTRIBUTIONS FROM LIQUID EFFLUENTS The cumulative dose contributions to the total body and any organ of an individual will be calculated on a quarterly basis based on the total nuclides released from the plant to nrestricted areas during the previous calendar quarter. These dose contributions will be calculated using the following expression:

D =t j A 4

I(atag.f)

= tj A h E(atC) j where:

D is the cumulative dose commitment to the total body or any organ,

• T, from the liquid effluents for the total time period, in mren.

A gT is the ingestion dose commitment factor to the total body or any organ,t, for each identified principal gamma and beta emitter listed in Table 3-11 of the Technical Specifications, in mrem /hr per pCi/ml.

At is the length of timo period over which C 9, f, and F are averaged for all liquid releases, in hours.

ag , C , f, F are as defined under Section 3. of this manual.

9 The cumulative dose contributions to the total body and any organ will be reviewed quarterly to verify satisfaction to the design objectives and the actions of Technical Specification 2.9.1 (1) determined.

4.1 Ingestion Dose Commitment Factors The above equation for calculating the dose contributions requires the use of an ingestion dose commitment factor, A for each nuclide, i, which embodies the dose factors, and dilution factoN,for the points of pathway origin (only drinking water and fish consumption are considered the major pathways of exposure due to liquid effluents). The adult total body dose factor and the adult critical organ (liver) dose factor for each radio-nuclide are obtained from Regulatory Guide 1.109, Revision 1. The inges-tion dose commitment factor can be calculated from the following expres-sion:

-A t -AI#

t A e I P + 21 BF j e DF h = 1.14 E+05 [W 4

p

4. DOSE CONTRIBUTIONS FROM LIQUID EFFLUENTS (Continued) where:

li 'D" - Dilution point to factor from the the drinking waternear field19 facility area of the miles release downstream.

Aj - Radioactive decay constant of nuclide, 1, in (days ~1),

t - The average-transit time from the point of release to the P drinking water facility including the time through the purification plant and the water distribution system, in days.

tf - The time for radionuclide decay during transit through the aquatic food chain, in days.

BF, - Bioaccumulation factor for nuclide, 1, in fish for fresh water site, in pCi/kg per pCi/1.

DF Dose conversion factor for nuclide, i, for adults, in j

mrem /pC1.

1.14E+0S - Unit Conversion Factor (1.0E+06 cpCi/u i x 1.0E+03 h e 8760 hr/yr)

Tabulated below are the appropriate values and other references:

Parameter Value D, 30.8(dimensionless) t 0.75 day p

t f

I day BF j Table A-1 of Regulatory Guide. 1.109 DF, Table E-11 of Regulatory Guide 1.109 Resolution of the units yields:

I I + BF 9 e DF Ah = 2.40E+06 1.13 e 4 The values for ingestion dose comitment factor, A for the adult totalbody,andcriticalorgan(liver),arepresentedibT,able1. T I

[!T . .

TABLE 1

c. Aj , for Liquid Pathways (Adult)

(mrem /hr per pCi/ml)

Nuclide Total Body Liver H-3 5.1E-01 5.1E-01 iCR-51 1.3E+00 0.0 MN-54 8.4E+02 4.4E+03 FE-59 9.3E+02 2.4E+03

.CO-58 2.0E+02 9.0E+01 C0 5.8E+02 2.6E+02 ZN-65 3.3E+04 7.4E+04 SR-89 6.5E+02 0.0 SR-90 1.4E+05 0.0 ZR-95 .6.9E-02 1.0E-01 NB-95 1.3E+02 2.4E+02 MO-99 1.7E+01 9.0E+01 RU-103 2.1E+00 0.0 I-131 1.2E+02 2.1E+02 I-133 1.3E+01 4.4E+01 I-135 1.5E+00 4.0E+00 CS-134 5.8E+05 7.1E+05 CS-136 8.4E+04 1.2E+05 CS-137 3.4E+05 5.2E+05 BA-140 1.6E+01 3.0E-01 l

L .

l k 5.- LIQUID RADWASTE TREATMENT SYSTEM The major equipment or subsystem (s) of the liquid radwaste treatment system are comprised of waste filters, and evaporator. This equipment, including associated pumps, valves and piping, is used in different combinations on an as-needed basis in order to process the liquid effluent to provide compliance with the as low as is reasonably achievable philosophy and the applicable sections of 10 CFR Part 20.

Waste filters (WD-17A and WD-178) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the Appendix I dose design objective evaluation; therefore, the inoperability of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid

. pathways. The inoperability of waste filters will not be considered a reportable event in accordance with Specification 2.9.1(1)c.

Every effort will be made to process all liquid waste, except from the hotel waste tanks, through the evaporator before entering the monitor tanks. If the radioactive liquid waste was discharged without processirig through the

~

evaporator a special report shall be submitted to the Commission, pursuant to Specification 2.9.1(1)c.

The quantity of radioactive material contained in each unprotected outdoor -

liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.

=

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6. CONCENTRATIONS IN GASEOUS EFFLUENTS

.The concentration of radioactive gaseous effluents to the unrestricted areas will be limited to the concentration levels of 10 CFR Part 20, Appendix B, Table II.

For various types of releases (batch and continuous) the analyses will be performed in accordance with the appropriate sampling and analysis-frequencies and type of activities of the Technical Specification, Table 3-12. The concen-tration'of each radionuclide at the unrestricted areas will be less than or equal to the maximum permissible concentrations of 10 CFR Part 20, Appendix B, Ta' ale II.

6.1: Noble Gases The following method is used to estimate the concentrations of gaseous effluents (noble gases) in the unrestricted areas (see Figure 1):

=K'.Q 9.fgMPC 9 Cj where:

C is the concentration of radionuclide, i, in the unrestricted 9

area, in uCi/ml.

is the release rate of radionuclide, i, from the ventilation Q, stack, in uCi/sec.

is the highest calculated annual average dispersion for any h area at or beyond the unrestricted area boundary, in sec/m3 (use value from Table 7).

K is the unit conversion factor (1.0 E-06 Ci/yCi).

Resolution of units yields:

C, = 1.5 E-11 . Q s9 MPC9 NOTE:' In addition to the above defined method, NOTES 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.

6.2 Radiciodines and Particulates The concentrations of radiciodines and particulates, with half-lives greater than 8 days, in the unrestricted areas (see Figure 1) will be estimated based on deposition of these radioactive materials on the ground at or near the location of receptors in the worst sector.

U'

-6. CONCENTRATIONS IN GASE0US EFFLUENTS (Continued)

-Therefore, the value x/Q in the above equation will be replaced by 3.8E-06 rec /m3 or:

C =

9 3.8E-12 Q$ <_ MPC$

The parameters and values are described under section 6.1 above.

NOTE: In addition to the above defined method, NOTES 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.

The lower limit of detection (LLD), referenced in Table 3-12 of the Technical Specifications, is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% proba-bility of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66s b U"E V 2.22 x 100 + Y exp (-Aat) r Where:

LLD is the lower limit of detection as defined above, as microcuries per unit mass or volume, si is the standard deviation of the background counting rate or of the cDunting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, s and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as before the fact limit representing the capability of a measurement syster,i and not as after the fact limit for a particular measurement.

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7. DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS The cumulative dose contributions, to each of the 16 cardinal sectors, from radioactive materials in gaseous effluents will be determined on a quarterly

' basis. The dose contributions are divided into two categories; namely, air doses due to noble gases and dose to an individual -(child or infant) from I-131, tritium and radioactive material in particulate form.

~7.1 Air Dose Due to Noble Gases

.The air dose in unrestricted area (see Figure 1) due to noble gases released in gaseous effluents is determined by the following expressions:

a. During any calendar quarter, for gamma radiation:

D =E 4 DFY.Q3.g j

b. During any calendar quarter, for beta radiation:

D g

=E 9 DF9 8.Q$.g where:

DF Y is' the air dose factor due to gamma emissions for each j identified noble gas radionuclide, i, in mrad /sec per pCi/m3 (Table 2).

8 is the air dose factor due to beta emissions for each

! DF I identified noble gas radionuclide, i, in mrad /sec per pCi/m3 (Table 2).

Q is the release, cumulative over the calendar quarter,

$ of noble gas radionuclides in gaseous effluents, i, in uCf.

r is the highest calculated annual average dispersion factor Q for area at or beyond the unrestricted area boundary, in sec/m3 (Table 7).

D,D are the total gamma air dose and beta air dose from Y 6 gaseous effluent, in mrad.

7.2 Dose Due to Radiciodines and Particulates The total body dose and dose to the critical organ (thyroid) of an individual (child or infant), for any calendar quarter from I-131, tritium, and radioactive materials in particulate form with half-lives greater than

! 8 days in gaseous effluents released to unrestricted areas (see Figure 1) is determined by the following expression:

D g=3.17E-08.forg.Eg R$ . Q, l

rr 7 .- DOSE CONTRIBUTIONS FROM GASE0US EFFLUENTS (Continued) where:

R is the dose factor for each identified radionuclide, i, in '

9 mrem /yr per pCi/m3 or m2 (mrem /yr) per pCi/sec (Tables 3, 4, 5, and 6).

Qj is the release, cumulative over the calendar quarter, of I-131, tritium and radioactive materials in particulate form in gaseous effluents, i, with half-lives greater than 8 days, in uC1.

D is the annual average deposition factor for estimating the -

'Q dose to an individual at the controlling locat. ion, in meters 2 (Table 7).

x is the annual average dispersion factor for estimating the

-Q dose to an individual at the controlling location, in sec/m3 (Table 7).

D is the quarterly cumulative dose from I-131, tritium, and g radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents, in mrem.

3.17E-08 is the inverse of the number of seconds in a year.

The cumulative dose contributions from radioactive materials in gaseous

. effluents will be reviewed quarterly to verify satisfaction to the design objectives and the actions of Technical Specification 2.9.1.(2)b deter-mined.

r-k-

• TABLE 2 Dose Factors for Noble Gases

. 2, B

Gamma Air Dose Factor DFgtaAirDoseFactor(mrad /secperpCi/m DF Y (mrad /sec per pCi/m3) g Nuclide 9 l

2.95E-04 2.80E-04 AR 3.90E-05 3.71E-05 KR-85M 5.45E-07 5.11E-07

- KR-85 1.96E-04 1.88E-04

- KR-87 4.82E-04 4.66E-04

- KR-88 4.95E-06 2.90E-06 XE-131M 1.04E-05 7.96E-06 XE-133M' ,

1.12E-05 9.32E-06 XE-133 1.07E-04 9.89E-05 XE-135M 6.09E-05 5.74E-05 XE-135

'2.92E-04 2.80E-04 XE-138 i

6 b

l l

L

3, s

TABLE 3 Dose Factors-for.I-131, H-3 and Radioactive Particulates .

Via Inhalation Pathway

. (mrem /yr per pC1/m3) R9 (Child)

L Nuclide Total Body Thyroid

~

- H-3 1.1E+03 1.IE+03 CR-51' 1.5E+02 8.5E+01 MN-54 9.5E+03 0.0

~ FE-59 -1.7E+04 0.0 l C0-58L 3.2E+03 0.0 0.0

': > 2 .3E+04

- C0 ~

ZN-65 7.0E+04 0.0

-SR-89 1.7E+04- 0.0

- SR-90 6.4E+06 0.0 l ZR-95 3.7E+04 0.0-c 1-131 2.7E+04 1.6E+07 ,

CS-134 2.2E+05 0.0 CS-136 1.2E+05 0.0 CS-137 1.3E+05 0.0 4.3E+03 0.0 1

BA-1,40 i

t-i L.

T' ,

TABLE 4 Dose Factors for I-131, H-3 and Radioactive Particulates 1

Via Inhalation Pathway (mrem /yr per pC1/m3) Rg (Infant)

Total Body Thyroid Nuclide H-3 6.5E+02 6.5E+02 CR-51. 8.9E+01 5.8E+01

. MN-54 5.0E+03 0.0 FE-59 9.5E+03 0.0 C0-58 1.8E+03 0.0 CO-60 1.2E+04 0.0

~ZN-65 3.1E+04 0.0 SR-89 1.1E+04 0.0 SR-90 2.6E+06 0.0 ZR-95 2.0E+04 0.0 2.0E+04 1.5E+07 I-131

- CS-134 7.4E+04 0.0 CS-136 5.3E+04 0.0 CS-137 4.6E+04 0.0 BA-140 2.9E+03 0.0

+

• r

4 q: ' -

?

TABLE 5 Dose Factors for I-131. H-3 and Radioactive Particulates Via Ground and Food Pathways _ ,

z .

(m -mrem /yr per uCi/sec) Rg (Child) 7 Nuclide Total Body Thyroid ', , .

H-3 5.8E+03* 5.8E+03*

CR-51 4.8E+06 3.8E+04 ,

MN-54 1.5E+09 0.0 '$'

FE-59 8.2E+08 0.0 7 C0-58 6.3E+08 0.0 s

r CO-60 2.3E+10 0.0 ,

ZN-65 6.8E+09 0.0 1

SR-89 1.2E+09 0.0 /-

SR-90 3.4E+11 0.0 ,f

/

ZR-95 2.5E+08 0.0 .

f-I-131 4.8E+08 2.7E+11

-'i CS-134 1.8E+10 0.0 CS-136 1.2E+09 0.0 CS-137 1.7E+10 0.0 '

BA-140 4.2E+07 0.0 t

• Units for H-3 are mrem /yr per pCi/m8 t

1

-22 '

, t

. /:

's li I s

a. ,,

I

\,, .s TABLE 6

' ,, p y n

1 l(' Dose Factors for I-131 H-3 and Radioactive P Via Ground and Food Pathways (m3. mrem /yr per pCi/sec) R9 (Infant)

~

r j '

p'; ,

Total Body Thyroid hch <

i H-3 2.4E+03* 2.4E+03*

/. ,

- ),

/O < ,,CP-S1 4.8E+06 5.5E+04 p . .

0.0 MN-541 ,1 1.3E+09 f/c,,(, y'{i -

\\l l 3.6E+08 0.0

, E-59 -

[

1l 4.2E+08 0.0

,/l ,s r: , CO-58 0.0

'l ,

CO-60

• 2.2E+10 Y iZN-65 - 6.3E+09 0.0 j -

j l. : ; .'

a , ,sR-DS ' 2.0E+08 0.0 i ..

1 2.1E+10 0.0

/'c/.\  : - ,

l' b,SR-90 ZR-95 ', 2.5E+08 0.0

/ '

7.3E+08 5.3E+11

, I -1.L' . ,

1- '

/ 1.1E+10 0.0 1 ,

CS-i U{I' '

s+ <

t,CS-136 1.2E+09 0.0

).si0 .

.i

>yj~:' ,

1.3E+10 0.0

/ f.5 J f, ,3

,o ,-137 t .-

hA-140 h, ,

2.7E+07 0.0

p. - ,

t

• Units ',br H-3 are mrom/yr'per pCi/m8 1

1

, ,, .7 1

t

./'

/

'f y,

i

) o ,

' a e

y 4-1 N

B%

l ,

,l -

ll- -23

.e)"

e h

r:

TABLE 7 Annual Average Dispersion and Relative Deposition Factors x D- . Dose to Air Dose Via Dose to Individual Units- Beta Tritium Total Body Any Organ

-Q or U Gamma sec/m3 1.5E-05 II) 1.5E-05 II) 3.5E-06(2) 3.8E-06(3) 3.8E-06(3) ,,

-2' I D m ---- --- --- 1.2E-08 I4) 1.2E-08.4)

-U

- (1) ;-The highest calculated annual average dispersion factor for any area at or beyond the unrestricted area boundary for long term releases.

(2)- For the nearest' residence at or close to real milk animal.

(3) iThe calculated annual average dispersion' factor for the controlling

. location in'the SSE-sector.

I4); The calculated annual' average. deposition factor for the nearest milk source or residence in the SSW sector, s

)

L

,)

J a

D t m -r-- - - n+ - , -mm e- n g-no -- s -,ga, -~ w,m-p ,,--g ,---v-,--+-,-w- g v g 1~--e

.~. 's T.

I

.. ' 8. GASEOUS RADWASTE TREATMENT SYSTEM

/

IThe waste gases at Fort Calhoun Station are collected in the vent header A.? where'the gas compressor (s) takes suction, compresses the gas and then delivers

~

it to one.of the four gas decay tanks. The waste gases are primarily treated in

^

these gas decay tanks by holding the gases for radioactive decay prior to final In order to provide conformance with the controlled release to the environs.

'.. dose design , objectives, gas decay tanks are normally stored for approximately 17

• ' days with earlier release allowed to support plant operation only and thus If achieve decay of short half-life radioactive materials, e.g., I-131, XE-133.

the radioactive gaseous wastes from the gas decay tank (s) were discharged without processing in accordance with the above conditions, a special report shall be submitted to the Commission pursuant to Specification 2.9.1(2)c.

N N The radioactive effluents from the controlled access area of the auxiliary

, building are filtered by the HEPA filters in the auxiliary building ventilation system. If the radioactive gaseous wastes were discharged without the HEPA filters, a s ecial report shall be submitted to the NRC pursuant to specifica-tion 2.9.1(2 c.

The discharge from the gas decay tanks is routed through charcoal and HEPA filter unit VA-82. No credit was taken for the operation of hydrogen purge

filters during the Appendix I dose design evaluation and doses through the of The unavailability gaseous pathways were well below the design objectives.

Hx hydrogen purge filters will not be considered a. reportable event as per Speci-A fication 2.9.1(2)c.

1 The containment air is precessed through at least one of the redundant containment HEPA and charcoal filters in the Containment Air Cooling and Filtering Units prior to purging. If the containment purges were made without processing through one of the Containment Air Cooling and Filtering Units, a special report shall be submitted to the Commission pursuant to Specification

-* 2.9 1(2)c.

A i'

rw

.I

'9. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program will be conducted, to measure changes in the levels of environmental radioactivity due to plant effluents, in accordance with Specification 3.11. The reporting levels for radioactivity concentrations in the environmental samples are provided in Table

8. Analytical techniques for the sampling program will provide assurance that the detection capabilities specified in Table 9 are achieved.

The specific details of the radiological environmental monitoring program are also presented here with additional detail provided in an Environmental Radiological Monitoring Procedure Manual. Table 10 provides the details regarding the sampling. station numbers, collection sites, and distance and location of each station from the centerline of the containment. The sample stations, specifically in the vicinity of the plant, are shown on Figure 2

-Deviations from the monitoring program, presented in Specification 3.11 and detailed.in Table 10, are permitted if specimens are unobtainable due to hazar-dous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program and other legitimate reasons.

If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Specification 3.11.1.

This program is the responsibility of Nuclear Environmental Monitoring Services.

TABLE 8 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

• Fe-59 Co-58 Co-60 Zn-65 Zy-Nb-95 I-131 CS-134 CS-137 Ba-140' Sample Units H-3 Mn-54 1E+03 3E+02 3E+02 4E+02 2E+00 -3E+01 SE+01 2E+02 Water -pCi/1- 2E+04 1E+03 4E+02 3E+04 1E+04 2E+04 -- -- 1E+03 2E+03 --

Fish pCi/kg -- 3E+04 1E+04 (wet) 3E+00 6E+01 7E+01 3E+02 pCi/l -- --

Milk -- -- -- -- --

Air i Particu-

late -- -- -- 9E-01 -- -- --

or Gases pCi/m3 -- -- -- --

1.0E+02 1.0E+03 2.0E+03 --

I' Broad Leaf pCi/k -- -- -- -- -- -- --

Vegetation (wet)g

• When more than one of the radionuclides are detected in the sampling medium, a non-routinc report shall be submitted, per Specification 5.9.4.b. if:

Concentration (1) ,- - - - - > 1.0 1

Reporting Level (1)Reporting

, Concentration Level (2) (2) 4 When radionuclides other than those listed above are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the general public.is equal to or greater than the dose objectives of limiting condition of operation 2.9.1.A and 2.9.1.B. This report is not required if the measured level ofl radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

4 4

i 1

j ,

A g A A

'?

' TABLE -

DETECTION' CAPABILITIES FOR ENVIRONMENTALJSAMPLE ANALYSIS-

, LOWER LIMIT OF DETECTION (LLD)*

t

- Gross Zy-Nb-95 I-131 CS-134. CS-137: ~Ba-140 Sample Units- Beta H-3 lMn-54 Fe-59 Co-58,60 'Zn-65 Il 1.5E+01 3.0E+01 1.5E+01 1.0E+00 1.5E+01 1.8E+01 1.5E+01.

Water' pCi/1- - 2.0E+04 1.5E+01 3.0E+01 1.3E+02 '2.6E+02 - - 1.3E+02 1.5E+02 -

Fish pCi/kg - - 1.3E+02 '2.6E+02 *

(wet)

- - - - 1.0E+00 1.5E+01 1.8E+01 1.5E+01 y Milk pCi/1. - - - --

a Air '

i Partic-4 ulate. -

- - 7.0E-02 - - -

! , or Gas pCi/m3 _1.0E-02 - -

! M' - - - - 1.5E+02 1.8E+02 -

j Sediment. . pCi/kg - - - -

1- (dry)

- - - 6.0E+01 6.0E+01 8.0E+01 -

Broad Leaf pCi/kg - - -

t Vegetation (wet)

• The LLD is-defined, for purposes of'these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background,.that will be detected with 95% probability with only.5 probability of falsely. concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include' radiochemical separation

1

'4.66 s b '

l LLD = E . V . 2.22 x 106 . Y . exp (-Aat)'

f j

3 _

4 q

3

^

> TABLE 9f(Continued)?

Where:

~

LLDnis the710wer limit of d'etection as defined above, as; microcuries. per unit mass or: volume,

- s fis the standard deviation of the background coun' ting rate o'ff of the counting rate of a blank' sample as b

appropriate, as counts per' minute, l E is the counting efficiency,'as counts per. disintegration, V;is the sample size in units.of mass or. volume,-

2.22 x 106 is the number of disintegrations per minutes per microcurie, Y is the frastional. radiochemical yield, when applicable, A is'the radioactive decay constant for the particular radionuclide, and i at for plant effluents is the elapse.dctime between the midpoint of sample collection and time of counting.

' Typical values' of E, V, Y, and at should.be used in'the calculation. .

It should be recognized that the LLD is defined as before the fact limit representing the capability of a measurement system and not as after the. fact. limit for a particular measurement.

TABLE 10-Radiological Environmental Monitorina Program Distance

. Sampling . from the Exposure Pathway Station Collection Containment Radial and/or Sample No. Site (Miles) (Degrees)

"A. Air Monitoring 1 Onsite Station #1 0.7 293 2 ~0nsite Station #2 0.6 225 3 Onsite Station #3 0.6 155

.4 3.1 286

'S- City (ofBlairEOF Background) 17.5 157 B.- TLD 6 Onsite Station #1 0.7 293

~7 Onsite Station #2 0.6 225 8 Onsite Station #3 0.6 155 9' City of Blair 3.1 286 10 E0F(Background) 17.5 157

_- 11 Fort Calhoun City Hall 4.8 149 12 Fence.around Intake

~ Gate at Desoto Refuge 2 101 13' Entrance to Plant from Hwy 73 (onsite) 0.6 180 14 Northwest of Plant (onsite) .

1.0 310 15 West-Southwest of Plant (onsite)- 0.7 250~

16 Southeast of Plant (onsite) 0.9 130 C. Water 17 - Missouri River @

MUD 17 156 18 West Bank of 0.5 106 Missouri River-19: Missouri River Upstream from Intake (Background) 0.1 345

li '~

t-TABLE-10(Continued)-

Radiological Environmental Monitoring Program Distance Sampling: - from the Collection Radial Exposure. Pathway ~ Station Containment and/or- Sample No. Site (Miles) (Degrees)

D. Milk - 20 Miller Farm (I) - 0.7 193

. 21 Japp Dairy

-(Background) 6.3 219

.E. Fish 22-25 4 Samples within Vicinity of Plant Discharge -- R.M.645 --

~ 26 West of Mondamin, <

Iowa (Background) --

R.M.666 --

F. Sediment- . 27 West Bank of River 0.5 106

'(1) When a milk sample ~is unavailable a milk sabple will be collected from the

Flynn Dairy. If both milk samples are unavailable, a broad leaf vegetation

' sample will be collected at the 'ocation.

m

\

t 7

.v.---_w-- .-m _ e g. g,-m -. m-- - - , ,,,-,y.,--y- w-, _w,_y.- .-__r.,,-,,_. , , , , , , , --

~

1

~

.;t*_'h 5' - v' , , - A

.c gggg ,

S No min gtilLL I

l NamnAsp .

I 7T Q  !

• o s I

~

q Fo CAbMcWN -

' suasTAM N

@ [Ivag

)

i o@_

N

, 7s f 1 l' OnahaiPublic Power District Radiological Environmental Fort Calhoun Station Monitoring Program f Unitho.1 (SampleSites) Figure 2 l.

. - .\. .

71 '

..... ~.

_ w _

, _ _ - . . - - _ - - . " . ' ' . _ " . . ' ' . . _ ~ . _ ' ~ _ ~ _ " . _ _ _ ' _- __

~ ~~ ~

- - - - - - . . . .._...,,_m_