Text

Rev 0.K to ODCM, Chapter 10 & App F
	ML20035A157
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	01/31/1993
From:	; COMMONWEALTH EDISON CO.
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	PROC-930131-01, NUDOCS 9303240195
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ti E C C/0 Lac CTRL JSK, c. PAILL l

DIRECICR Uf hut. HEACIC6 HEGULATION February 24, 1993 l

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Attached are the recent revisions to the Offsite Dose Calculation Manual's (ODCM) Chapter 10 and Appendix F for Zion Station.

Please complete l

the following manual update:

REMOVE INSERT Zion Station Annex Zion Station Annex Entire Chapter 10.

Entire Chapter 10

p. 10-1 to 10-iv, Revision 0.K. Jan. 1993 10-1 to 10-17

p. 10-i to 10-v, 10-1 to 10-19 Zion Station Annex Zion Station Annex Entire Appendix F Entire Appendix F i

p. F-1 to F-iv, Includes Rev. O.K F-1 to F-23

p. F-1 to F-iv,

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F-1 to F-22 j

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i ZION REVISION 0.K JANUARY 1993 i

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PAGE REVIS103 CHAPTER 10 10-i 0.K 10-ii 0.K 10-iii 0.K 10-iv 0.K 10-v 0.K 10-1 0.K 10-2 0.K

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1 ZION REVISION 0.K JANUARY 1993

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CHAPTER 10 l

l RADI0 ACTIVE EFFLUENT TREATMENT AND MON 1TORING 1

1 TABLE OF CONTENTS PAGE 10.1 AIRBORNE RELEASES......................

I i

10.1.1

System Description

1 i

10.1.1.1 Waste Gas Holdup System...................

1 10.1.1.2 Ventilation Exhaust Treatment System I

10.1.2 Radiation Monitors I

10.1.2.1 Final Vent Stack Effluent Monitors I

10.1.2.2 Auxiliary Building vent Effluent Monitors..........

2 i

10.1.2.3 Containment Purge Effluent Monitors.............

2 10.1.2.4 Waste Gas Decay Tank Monitors................

3 10.1.2.5 Condenser Air Ejector Monitors 3

1 10.1.2.6 Service Building Ventilation Monitor 3

l 10.1.2.7 Miscellaneous Ventilation Monitors 3

t 10.1.3 Alarm and Trip Setpoints 3

10.1.3.1 Setpoint Calculation 3

10.1.3.2 Release Limits 4

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10.1.3.3 Rel e a se Mixtu re.......................

5 10.1.3.4 Conversion factors 5

10.1.3.5 HVAC Fl ow Ra t es.......................

6 10.1.4 Allocation of Effluents from Common Release Points 7

10.1.5 Dose Projections for Batch Releases.............

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10.2 LIQUID RELEASE 7

10.2.1 System Dest.ription 7

10.2.1.1 Lake Dischange Tanks 7

10.2.1.2 Turbine Buildti:9 Fire Sump 7

10.2.2 Radiation Monitors

~

8 10.2.2.1 Lake Discharge Tank Monitors 8

l 10.2.2.2 Turbine Building Fire Sump Monitor 8

i 10.2.3 Alarm and Trip Setpoints 8

L 10.2.3.1 Setpoint Calculation 8

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10-ii 1

ZION REVISION 0.K JANUARY 1993 i

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CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) 10.2.3.2 Discharge flow Rates 9

10.2.3.2.1 Lake Discharge Tank Discharge Flow Rate...........

9 10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate 9

10.2.3.3 Release Limits 10 t

10.2.3.4 Rel e a se Mi xtu re.......................

10 10.2.3.5 Conversion Factors

.....................10 10.2.3.6 Liquid Dilution Flow Rates 10 10.2.4 Allocation of Effluents from Common Release Points 10 10.2.5 Projected Concentrations for Releases............

10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM.......

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ZION REVISION 0.K JANUARY 1993

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CHAPTER 10 LIST OF TABLES i

NUMBER TITLE PAGE 10-1 Assumed Composition of the Zion Station Noble Gas Effluent 10-12 10-2 HVAC Exhaust Fan Capacities 10-13 i

10-3 Liquid Dilution Flow Pump Capacities 10-14 O

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10-iv

ZION REVISION 0.K t

JANUARY 1993 CHAPTER 10 f

LIST OF FIGURES NUMBER TITLE PAGE 10-1 Simplified Gaseous Radwaste and 10-15 Gaseous Effluent Flow Diagram 10-2 Simplied Liquid Radwaste Processing Diagram 10-17 l

10-3 Simplified Liquid Effluent Flow Diagram 10-18 10-4 Simplified Solid Radwaste Processing Diagram 10-19 10-5 Example NMC Monitor Response 10-20 1

0 f

I 10-v

ZION REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1.

The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack and Unit 2 Vent Stack in Figure 10-1).

In the classification scheme of Section 4.1.4, each is classified as a ground level release point (see Table A-1 of Appendix A).

10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Section 11.1.2.3 of the Zion FSAR.

10.1.1.2 Ventilation Exhaust Treatment System ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

The ventilation exhaust treatment systems are shown in Figure 10-1.

Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

10.1.2 Radiation Monitors

~

10.1.2.1 Final Vent Stack Effluent Monitors Monitors IRIA-PR49 (Unit 1) and 2RIA-PR49 (Unit 2) continuously monitor the final effluent from the auxiliary building vent l

stacks.

Both vent stack monitors feature automatic isokinetic sampling and grab sampling.

i 10-1

ZION REVISION 0.K JANUARY 1993 In normal operation all three noble gas channels (low, mid-range, high) are on line and active. On a high alarm from the mid-and/or high range channels the particulate, iodine, low range noble gas and mid-range noble gas channels are isolated, and only the high range noble gas channel remain; active.

No automatic isolation or control functions are performed by these monitors. On high alarm, the control room operator will notify the health physics group and reduce the release rate as

{

appropriate.

Because of the conservatism built into the setpoint calculations (Section 10.1.3), there is an adequate margin between the setpoint and release limit to accommodate this procedure.

Pertinent information on these monitors is provided in UFSAR Table 11.5-1.

10.1.2.2 Auxiliary Building Vent Effluent Monitors Monitors IRT-PR25 (Unit 1), 2RT-PR25 (Unit 2) and ORE-0014 (common) continuously monitor the effluent from the auxiliary building vent stacke No automatic isolation or control functions are performed by these monitors. On high alarm, the control room operator will O-notify the health physics group and reduce the release rate as appropriate.

Because of the conservatism built into the l

setpoint calculations (Section 10.1.3) there is an adequate margin between the setpoint and release limit to accommodate this procedure.

i Pertinent information on monitor ORE-0014 is provided in UFSAR l

Table 11.5-2.

10.1.2.3 Containment Purge Effluent Monitors Monitors IRT-PR09 (Unit 1) and 2RT-PR09 (Unit 2) continuously monitor the effluent from the Unit I and Unit 2 containments, respectively. On high alarm, the monitors automatically initiate closure of the four air-operated butterfly valves (RV0001/2/3/4 purge valves for each unit).

Pertinent information on these monitors is provided in UFSAR Tables 11.5-1 and 11.5-2.

Monitors 1(2)RIA-PR40 continuously monitor.he Unit 1(2) atmosphere. On high alarm, the monitors automatically initiate closure of valves RV0001-RV0006 inclusive.

10-2

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l ZION REVISION 0.K JANUARY 1993 10.1.2.4 Waste Gas Decay Tank Monitors Monitors ORT-PR10A/B continuously monitor the noble gas activity released from the gas decay tanks.

On high alarm, the monitors automatically initiate closure of the valve ORCV-WG014 thus terminating the release.

I l

Pertinent information on these monitors is provided in UFSAR Table 11.5-2.

10.1.2.5 Condenser Air Ejector Monitors Monitors IRE-0015 and 2RE-0015 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. No control device is initiated by these channels.

Pertinent information on these monitors is provided in UFSAR Table 11.5-2.

10.1.2.6 Service Building Ventilation Monitor Monitor ORT-PR22 continuously monitors noble gas activity in the service building ventilation system. No control device is initiated by this channel.

Pertinent information on this monitor is provided in UFSAR eO Tabla 11.5-2.

10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORT-PR18B continuously monitors noble gas activity in the ventilation exhaust from the auxiliary equipment room, computer room, laboratories, decontamination room and other miscellaneous areas. No control device is initiated by this channel.

Pertinent information on this monitor is provided in UFSAR

[

Table 11.5-2.

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculation

~

The effluent noble gas monitor setpoints are conservatively based on the assumr. ion that a release is occurring simultaneously fo

.11 seven gaseous release points at the maximum expected ow rate for each pathway.

Furthermore, the set)oints are chosen such that an occurrence of simultaneous hig1 alarms on all seven pathways would correspond to a station i

release rate of one half of the Technical Specification limit.

10-3

i ZION REVISION 0.K JANUARY 1993 Pug s 0.5 x Q,, x 1/F" x K" x C"

@ -1) i Pug Setpoint for monitor, M, on release path, P.

[ cpm]

0.5 - Factor to reduce release rate by 50%.

Q,, -

Total Allowed Release Rate, Vent Release

[pCi/sec) i F" -

Mw mu Wu@ Muu PdN P.

[ Wad K" -

Factor to apportion a fraction of the total release rate, Q,,, to release path, P.

C" -

Conversion Factor for monitor, H

[ cpm per Ci/cc]

10.1.3.2 Release Limits Alarm and trip setpoints of gaseous efflucnt monitors are j

established to ensure that the release rate limits of the Technical Specifications and 10 CFR 20 are not exceeded.

The release limits are found by solving Equatioris 10-2 and 10-3 for the total allowed release rate of vent releases, Q,.

s (1.11)Q,, { ({.f,) < 500 mrem /yr (10-2)

O Q,, E ((f;)[((X/Q), exp(-A,R/3600u,)

(10-3)

+ 1.11 V,]) < 3000 mrem /yr 4

The sumations are over noble gas radionuclides i.

f; Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.

Q,,

Total Allowed Release Rate,

[pCi/sec)

Vent Release The total allowed release rate of all noble gas radionuclides released as vent releases.

The remaining parameters in Equation 10-2 have the same definitions as in Equation A-8 of Appendix A.

The remaining

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10-4

ZION REVISION 0.K JANUARY 1993 i

parameters in Equation 10-3 have the same definition as in Equation A-9 of Appendix A.

Equation 10-2 is based on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr) due to i

noble gases released in gaseous effluents (see Section A.I.3.1 of Appendix A).

Equation 10-3 is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.2 of Appendix A).

Equations 10-2 and 10-3 can each be solved for a value of Q,..

The monitor alarm and trip setpoints will be established based on the equation which yields the smaller release limit, Q,.

The exact settings are selected to ensure that 10 CFR 20 limits j

are not exceeded.

Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS.

10.1.3.3 Release Mixture In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1.

This mixture was O

conservatively chosen based on station isotopic release data averaged over a period of 7 years (1977 through June 1984).

l 10.1.3.4 Conversion Factors i

The response curves used to determine the monitor count rates are chosen in order to best match the reference noble gas mix.

Because Xe-133 and Xe-135 comprise 83.6% and 8.79% of this mix respectively, the Xe-133/Xe-135 90%/10% curves are used to ensure that the setpoints would be conservative with respect to quantity.

Example curves are shown ir. Figure 10-5.

10-5 s

ZION REVISION 0.K JANUARY 1993 10.1.3.5 HVAC Flow Rates HVAC flow rates are computed for 1(2)RT-PR25, ORE-0014 and 1(2)RIA-PR49 based on the number of operating fans in the monitored flow path.

{ { F, x N; (10-4)

Fu P i Fu Total Flow in Monitored Flow Path

[ cc/sec]

F Flow from fan i in path p.

[ cc/sec]

N, Number of fans, in operation

=

The maximum flow for each fan is used for setpoint calculations because this maximizes the flow, and therefore minimizes the calculated monitor sensitivity which is conservative.

Pertinent data for the fans is provided in Table 10-2.

HVAC flows for the remaining monitors are conservatively fixed at upper bound values. They are listed below.

Monitor Flow in cc/sec ORT-PR10A/B 6.60E5 1(2)RE-0015 7.32E5 0RT-PR22 5.96E6 IRT-PR09A 1.65E6 (vent mode) 1.46E6 (mini-purge mode) 1.46E7 (purge mode) 2RT-PR09A 4.35E6 (vent mode)*

4.11E6 (mini-purge mode) 1.99E7 (purge-mode) 2.70E6 (routine, hot lab only) l

' Flow greater than Unit I due to " hot lab" hood exhaust fan flow.

10-6 P

ZION REVISION 0.K JANUARY 1993 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building miscellaneous ventilation system and the gas decay tanks are comprised of contributions from both units. Under l

normal operating conditions, it is difficult to apportion the radioactivity between the units.

Consequently, allocation normally is made evenly between units.

10.1.5 Dose Projections for Batch Releases Projected doses are calculated before purging the containment or venting the waste gas decay tanks.

Per procedure, a representative sample is obtained and analyzed, and the total release is calculated.

Prior to the release the projected dose rate (in mrem / year) is calculated based on the assumption that the release is continuous for the entire year.

10.2 LIQUID RELEASES 10.2.1

System Description

A simplified liquid waste processing diagram is provided in Figure 10-2.

A simplified liquid effluent flow diagram is provided in Figure 10-3.

The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment.

The system is described in Section 11.1.3 of the Zion FSAR.

10.2.1.1 Lake Discharge Tanks There are two lake discharge tank.s (OA and OB, 30,000-gallon capacity each) which receive liquid waste before discharge to Lake Michigan.

10.2.1.2 Turbine Building Fire Sump The turbine building floor and equipment drain tanks receive turbine building waste which is released to the fire sump for processing by the waste water treatment facility and ultimate discharge into Lake Michigan. The discharge constitutes a low level radioactive release.

10-7 1

ZION REVISION 0.K JANUARY 1993 cisd 10.2.2 Radiation Monitors 10.2.2.1 Lake Discharge Tank Monitors Monitors ORT-PR04 and ORT-PR05 are used to monitor all releases from the lake discharge tanks. On high alarm, the monitor j

automatically initiates closure of a valve to prevent further releases. The valve is located over 250 feet downstream of the monitor to allow closure prior to exceeding release limits.

The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Pertinent information on these monitors is provided in UFSAR Table 11.5-3.

10.2.2.2 Turbine Building Fire Sump Monitor t

Monitor ORT-PR25 continuously monitors the discharge line from the fire sump pumps to the waste water treatment facility. On high alarm, the monitor automatically trips all of the fire sump pumps, thereby containing the liquid in the turbine building. The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Pertinent information on the monitor is provided in UFSAR Table 11.5-3.

10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of the Technical Specifications and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoints are found by solving Equation 10-5 for a conservative mixture of radionuclides found in liquid effluents.

d P s K x (C

)(F /F')

(10-5)

P Release Setpoint

[pti/mt)

The alarm setpoint for radioactivity 16 be released in liquid effluents.

C.

Maximum Permissible Concentration

[pCi/mL]

d F

Dilution Flow Rate

[gpm]

The flow rate of the radwaste dilution stream (condenser cooling water).

10-8

ZION REVISION 0.K JANUARY 1993 F'

Discharge Flow Rate

[gpm]

The flow rate from the lake discharge tank or fire sump as appropriate.

K Factor of conservatism.

K - 0.5 for lake discharge tank K = 1.0 for for sump 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Lake Discharge Tank Discharge Flow Rate Prior to each batch release, the water is recirculated, sampled, and analyzed.

The results of the analysis of the waste sample determine the discharge rate of each batch as follows:

F'm,,= (Cy)(Fi/C)

(10-6) l F',,

Maximum Permitted Discharge Flow Rate

[gpm]

m The maximum permitted flow rate from the lake discharge tank.

[gpm]

Fi, Actual Dilution Flow Rate

[gpm]

The actual flow rate of the radwaste dilution stream (based on pump curves).

C Sample Radioactivity Concentration

[pti/mL]

The concentration of radioactivity in the lake discharge tank based on measurements of a sample drawn from the tank.

C has the same definition as in Equation 10-5.

10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate This release path is a continuous discharge. Consequently, the release rate F' in Equation 10-6 is set equal to maximum design 10-9

ZION REVISION 0.K JANUARY 1993 capacity for the pumps on the effluent of the waste water treatment facility.

10.2.3.3 Release Limits Release limits are determined from 10 CFR 20.

i 10.2.3.4 Release Mixture The release mixture used for setpoint determination is the worst case radionuclide mix chosen on the basis of station isotopic analysis data reviewed for 1978.

10.2.3.5 Conversion Factors The conversion factor for ORT-PR25 (fire sump monitor) is based on detector response curves for 1131. The conversion factors for monitor ORT-PR04 and ORT-PRO 5 are based on detector response curves for Csl37.

10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are computed based on the number of operating pumps in the flow path.

F'

{ F7 x N; (10-7) d F

Dilution Flow Rate

[gpm]

B F7 Dilution Flow Rate from pump i (gpm]

Number of pumps of type i operating N,

=

Pertinent flow data for the pumps is provided in Table 10-3.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the lake discharge tank and turbine building fire sump are comprised of contributions from both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the utits. Consequently, allocation is based on the unit discharge canal used for dilution.

4 10.2.5 Projected Concentrations for Releases Projected concentrations are calculated before initiating i

liquid discharges.

Per procedure, a representative sample is obtained and analyzed and the projected concentrations are 10-10

ZION REVISION 0.K JANUARY 1993 I]

calculated using conservative dilution flows prior to release.

Because the fire sump is a continuous release, it is sampled daily and isotopic analyses are performed weekly.

Doses due to liquid effluents are calculated as required by the RETS.

10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM i

The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

O i

10-11

ZION REVISION 0.K JANUARY 1993

()

Table 10-1 Assumed Composition of the Zion Station Noble Gas Effluent Isotooe Percent of Effluent Ar-41 1.92E-1 l

Kr-83m 1.0E-4 Kr-85m 2.24E-1 Kr-85 5.50E-2 Kr-87 1.22 Kr-88 3.19 Kr-89 1.0E-4 Xe-131m 1.85

()

Xe-133m 7.56E-1 Xe-133 8.36El Xe-135m 1.03E-1 Xe-135 8.79 i

Xe-137 1.0E-4 Xe-138 4.37E-3 L

4 Note:

Based on station isotopic release data averaged over 7 years (1977 through June 1984).

1

ZION REVISION 0.K JANUARY 1993

(

TABLE 10-2 HVAC EXHAUST FAN CAPACITIES i

FAN CC/SEC CFM CFH

1 Aux. Bldo 0A Exh. Fan 3.16 x 10' 6.70 x 10*

4,020,000 7

08 Exh. Fan 3.16 x 10 6.70 x 10' 4,020,000 OC Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000

2 Aux. Bldo.

OD Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 OE Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 0F Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000

1 Purae Exh.

IA Purge Fan 1.46 x 10' 3.10 x 10' 1,860,000 7

IB Purge Fan 1.46 x 10 3.10 x 10' 1,680,000 H' Purge Fan lA 1.70 x 10 3.60 x 10' 21,600 5

5 H Purge Fan IB 1.75 x 10 3.40 x 10' 22,200 2

2 Purce Exh.

2A Purge Fan 1.65 x 10' 3.50 x 10' 2,102,400 2B Purge Fan 1.72 x 10' 3.65 x 10' 2,188,800 6

H Purge Fan 2A 1.82 x 10 3.85 x 10' 23,100 2

5 2

H Purge Fan 2B 1.75 x 10 3.71 x 10 22,260 i

2 Hot Lab Exh. 0A 1.50 x 10" 3.18 x 10' 191,000 Hot Lab Exh. OB 1.18 x 10' 2.51 x 10' 150,600 i

Misc. Exh.

Comp & Misc. Exh. 0A 2.81 x 10' 5.95 x 10 357,000 Comp & Misc. Exh OB 2.81 x 10' 5.95 x 10' 357,000 Ser. Bldo.

~

Decon. Rm. Exh.

1.91 x 10" 4.04 x 10' 242,580 Welding Rm. Exh.

1.09 x 10' 2.30 x 10' 138,000 5

8 Sandblast Rm. Exh.

9.44 x 10 2.00 x 10 120,000 5

Cave Exh.

6.14 x 10 1.30 x 10' 78,000 Machine Shop Exh.

1.42 x 10' 3.00 x 10' 180,000 m

U 10-13

ZION REVISION 0.K JANUARY 1993 TABLE 10-3 LIQUID DILUTION FLOW PUMP CAPACITIES PUMP NUMBER OF PUMPS RUNNING DILUTION FLOW CIRCULATING WATER 1

250,000 gpm CIRCULATING WATER 2

530,000 gpm CIRCULATING WATER 3

640,000 gpm SERVICE WATER I

I3,500 gpm SERVICE WATER 2

27,000 gpm SERVICE WATER 3

40,500 gpm O

10-14

REVISION 0.K JANUARY 1993 UNIT I CONTAINENT ITYPICAL1 O

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APPENDIX F t

F-i O.K F-il O.A t

F-iii O.A F-iv O.A I

F-1 O

t F-2 O.K F-3 0.K l

F-4 O.A F-5 O.K F-6 O.K F-7 O.K F-8 O.K F-9 O.K F-10 O.K F-11 0.K F-12 0.K F-13 O.K F-14 O.K F-15 O.K F-16 O.K s

F-17 O.K F-18 O.K F-19 O.K F-20 O.K 1

F-21 O.K l

F-21a O.K F-22 O

l F-i I

l 1

ZION REVISION 0.A APRIL 1991 APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1 AND 2 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 n

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APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environment Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 U/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary F-6 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-7 F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-8 i

O D

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F-iii 1

i i

ZION REVISION 0.A APRIL 1991 APPENDIX F i

LIST OF FIGURES NUMBER TITLE pAgg F-1 Unrestricted Area Boundary F-23 i

I i

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b I

4 I

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1 F-iv

l ZION REVISION O i

MARCH 1989 APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1 AND 2 i

F.1 INTRODUCTION i

I l

This appendix contains data relevant to the Zion site.

Included is a figure showing the unrestricted area boundary and f

values of parameters used in offsite dose assessment.

f F.2 REFERENCES 1.

Sargent & Lundy, Nuclear Safeguards & Licensing Division, Zion Calculation No. ZI-9-85, Rev.

O.

O l

l i

O I

l F-1 1

ZION REVISION O.K JANUARY 1993 Table F-1 Aquatic Environment Dose Parameters a

D Parameter Value Comment W

M 1/60 A

l f

M 1

A F",

cfs Fe(gpm)/448.86 A,B f

F, cfs 4.0E5 A

I tf, hre 24 t", hrd 5.5 e

Limits on Radioactivity in Unprotected Outdoor Tanks Outside Temporary Radioactive f

Liquid Storage Tank i 10 Ci (per Technical Specification 3.11.5) a The parameters are defined in Section A.2.1 of Appendix A.

h Comments:

A:

Based on the Lake Michigan Model discussed in Section C.I.3.1.2 of Appendix C.

B:

Fc is the average flow of condenser cooling water (gpm) during the period of discharge (either Unit 1 or 2).

The constant 448.86 is the number 7

of gpm per cfs.

ctf (hr) = 24 hr (all stations) for the fish ingestion pathway.

d t" (hr) = 5.5 hr (distance to Lake County intake is 1.1 mile; flow rate of 0.2 mph).

e See Section A.2.4 of Appendix A.

f Tritium and dissolved or entrained gases are excluded from this limit.

t P

i 6

F-2

ZION REVISION O.K JANUARY 1993 Table F-2

)

i Station Characteristics I

1 STATION:

Zion Nuclear Power Station LOCATION:

Zion, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)

1) Release Height =

m

2) Diameter =

m

=

ms

4) Heat Content =

KCal s-1

-1

3) Exit Speed CHARACTERISTICS OF VENT STACK RELEASE POINT a

1) Release Height = 55.32 m

2) Diameter = 2212 m

3) Exit Speed

= 11.2 ms-1 i

CHARACTERISTICS OF GROUND LEVEL RELEASE i

4

1) Release Height = 0 m

a

2) Building Factor (D)

= 57.6 m

METEOROLOGICAL DATA A

250 ft Tower is Located 700 m NNW of elevated release point Tower Data Used in Calculations t

Wind Speed and Differential Release Point Direction Temperature Elevated (NA)

(NA)

Vent 125 250-35 Ground 35 250-35 l

aUsed in calculating the meteorological and dose factors in Tables F-5, F-6, F-7.

See Sections B.3 through B.6 of Appendix B.

l f

O F-3 i

i t

ZION REVISION 0.A APRIL 1991 l

Table F-3 Critical Ranges Site Nearest Nearest Dairy Farm a

Residentb Within 5 Milesc j

Boundary Direction (m)

(m)

(m) i N

469 3900 None NNE 475 d

None NE d

d None ENE d

d None E

d d

None ESE d

d None SE d

d None SSE d

d None S

433 2700 None SSW 439 2700 None SW 518 1900 None WSW 671 1600 None W

658 1500 None WNW 893 1500 None IM 847 1800 None NIN 725 2600 None a Used in calculating the meteorological and dose factors in Tables F-5 and F-7.

See Sections B.3 through B.6 of Appendix B.

b 1988 annual survey, Teledyne Isotopes Midwest Laboratories.

c 1988 milch animal census, Teledyne Isotopes Midwest Laboratories.

Used in calculating the D/Q values in Table F-6.

d Lake Michigan.

~

3 i

O F-4

REVISION 0.K JANUARY 1993 Table F-4 Average Wind Speeds l

Downwind Averace Wind Speed (m/secia i

Direction Elevated Mixed Mode Ground Level N

5.0 3.2 NNE 5.3 3.3 NE 5.8 4.1 l

ENE 5.6 3.9 E

5.7 3.9 ESE 5.1 3.3 1

SE 4.9 3.0 SSE 5.1 3.4 S

5.9 4.6 SSW 5.8 4.4 SW 5.1 4.0 WSW 5.2 4.6 W

5.1 4.4 WIM 4.8 3.7 NW 4.7 3.1

{

NNW 5.1 3.9 d

t Calculated in Reference 1 of Section F.2 using formulas in Section B.l.3 of Appendix B.

Based on Zion site meteorological data, January 1979 through December 1987.

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Site Doundary Finite Plume Gansna Dose Factors for Xc-133 Oownwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Directton Area Bound Radius V

VBAR Radius G

GRAR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uct/sec)

N 469.

469.

3.709E-04 2.363E-04 469.

1.412E-03 8.352E-04 NNE 475.

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NE 400.

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1.099E-03 6.5531-04 SSW 439.

439.

2.337E-04 1.559E 04 439.

9.702E 04 5.846E 04 SW St8.

518.

1.278E-04 8.824E-05 518.

5.633E-04 3.433E-04 WSW 671.

671.

7.715E-05 5.465E-05 671.

2.779E-04 1.722E-04 W

658.

7.644E-05 5.387E-05 658.

2.848E-04 1.759E-04 WNW 893.

893.

4.907E-05 3.511E-05 893.

1.820E-04 1.144E-04 NW 847.

847.

7.083E 05 5.045E-05 847.

2.647E-04 1.654E-04 NNW 725.

725.

1.188E-04 8.355E-05 725.

3.978E-04 2.459E 04 Zion Site Meteorological Osta 1/79 - 12/87

Not applicable--over Lake Michigan.

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ML20035A157

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