ML20076L746

Rev 1.2 to Odcm,Chapters 10,11,12 & App F

ML20076L746
Person / Time
Site:	Byron
Issue date:	08/31/1994
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-940831, NUDOCS 9411040175
Download: ML20076L746 (100)

Text

-X244 NRC C/0 30C C(RL DSK, C. PATEL

' DIRECTOR OF fdUC. REACTOR REGULATION

.U. S. NUC. REGULATORY COMMISSION MAIL STATION P1-137 WASHIhGTOf4 DC October 25,1994

?.0SSS Attached are the recent revisions to the Offsite Dose Calculation Manual's (OfCM) Chapters 10,11, 12 and Appendix F for Byron Station. Please complete the following manual update:

Reasore lasert Byron Station Byron Station Entire Chapter 10 Entire Chapter 10 Rev.1.0 Rev.1.2 Byron Station Byron Station ,

Entire Chapter 11 Entire Chapter 11 Rev.1.0 Rev.1.2 ,

Byron Station Byron Station Entire Chapter 12 Entire Chapter 12  ;

Rev.1.0 Rev.1.2

(

Byron Station Byron Station Entire Appendix F Entire Appendix F Rev.1.0 Rev.1.2 Please sign and date this control sheet and return to:

Comed c/o Document Centrol Emergency Preparedness I 1400 Opus Place - 5th Floor '

Downers Grove, R. 60515 (708) 663-2992 or (708) 6634496  !

Your signature ideates you have verified that your control number is correct, and you have  !

updated your manual. l Signature l

D' A Date n, , , .

OT v- .

0

- l EPCEPIPMocctrD 29 b l 9411040175 940831 i PDR ADOCK 05000454 '

k

BYRON R

vision 1.2 August 1994

[~T BYRON ANNEX INDEX

'b PAGE REVISION CHAPTER 10 10-1 1.2 10-il 1.2 10-lii 1.2 10-IV 1.2 10-v 1.2 10-1 1.2 10-2 1.2 10-3 1.2 10-4 1.2 10-5 1.2 10-6 1.2 10-7 1.2 10-8 1.2 10-9 1.2 10-10 1.2 10-11 1.2 10-12 1.2 10-13 1.2 .

10-14 1.2 V 10-15 1.2 10-16 1.2 10-17 1.2

/%

10-i

BYRON Ravi:lon 1.2 Augu:t 1994

.=

CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS NUMBER PAGE 10.1 AIRBORNE RELEASES . . ... . . . . . . . . 1

1. System Description . . ..... ..... . .. ...... ..... 1

1. Waste Gas Holdup System . . . .... .. . . 1

2. Ventilation Exhaust Treatment System . .. . . .. 1

2. Radiation Menitors . .. .. .. . . . . . . 1

1. Auxiliary Building Vent Effluent Monitors . . . ... . .. 1

2. Containmeni Purge Effluent Monitors . . . . . . . 2

3. Waste Gas Decay Tank Monitors . . .. .. . . . ... 2

4. Gland Steam and Condenser Air Ejector Monitors .. . ... 2

5. Radwaste Building Ventilation Monitor . . . .. 2

6. Component Cooling Water Monitor . . . . . 2 Miscellaneous Ventilation Monitors 3

( 3.

7.

Alarm and Trip Setpoints . .

3 l . . .

1. Setpoint Calculations . . . . ... . ... 3

1. Auxiliary Building Vent Effluent Monitors . 3

2. Containment Purge Effluent Monitors . .. . 3

3. Waste Gas Decay Tank Effluent Monitors . . . . 3

2. Release Limits . . .... . .. . 3

3. Release Mixture . . .... . . . . . . 4

4. Conversion Factors . . . . .. . .. 4 S. HVAC Dilution Flow Rates ... .. 4 l . .

4. Allocation of Effluents from Common Release Points . . . . . 5

5. Dose Projections for Batch Releases . . ... . . ... . 5 O

10-ii

f.

, BYRON Rrvizion 1.2 August 1994 CHAPTER 10 O)

\

RADIOACTIVE EFFLUENT TREATMENT AND fW NITORING TABLE OF CONTENTS (Cont'd)

NUMBER PAGE 10.2 LIQUID RELEASES . ....... ... ..... .... .... . .. .... .. 5

1. System Description . .. ... .. ..... ...... ... ........ . 5

1. Release Tanks . . . ... .. . . ... . . .... .. ...... 5

2. Turbine Building Fire and Oil Sump .. . .. .. .. . . 5

3. Condensate Polisher Sump ... .... ........ .. .. .... 5

2. Radiation Monitors . . .. ... . ..... . ... . . .. 6

1. Liquid Radwaste Effluent Monitors . .... . .. . . . .. 6

2. Station Blowdown Monitor . . . .. . . . . ..... 6

3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Une Monitors ..... .. .. . . 6

4. Turbine Building Fire and Oil Sump Monitor .. .. ....... . 6

5. Condensate Polisher Sump Monitor ... .... . . . . . . .. 6

3. Alarm and Trip Setpoints . . . . ......... ... . .. ... ....... ... 6

1. Setpoint Calculations . . . .. .......... . . .. . ... . ... 7

1. Liquid Radwaste Effluent Monitor .... ..... ... .... 7

2. Station Blowdown Monitor . . ... ......... . 7

2. Discharge Flow Rates .. . .. .. . .. .. . ... ... ... 8

1. Release Tank Discharge Flow Rate . . . . . . . 8

3. Release Limits . . . . . . . . . .. .. . .. . . ... 8

4. Release Mixture . . . . . .. .. . . . . . 8

5. Conversion Factors . . . . . . ............ . ..... ... ... 8

6. Liquid Dilution Flow Rates . ..... . . ... . . . . . 9

4. Allocation of Effluents from Common Release Points .. . . . 9

5. Projected Concentrations for Releases . . .... . .. . 9 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . ....... .... . 10 t

i k

10-lii

BYRON R: vision 1.2 -

August 1994 CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the Byron Station Noble Gas Effluent 10-11 10-2 Assumed Composition of the Byron Station Uquid Effluent 10-12 O

F O

10-iv

- BYRON Rsvision 1.2 August 1994 TN CHAPTER 10 t )

%J LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-13 10-2 Simplified Uquid Radwaste Processing Diagram 10-14 10-3 Uquid Release Flowpath 10-15 10-4 Simplified Solid Radwaste Processing Diagram 10-16 l

I i

i i

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10-v

BYRON R: vision 1.2 August 1994 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified HVAC 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 Vent Stack 1 and Vent Stack 2 in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent 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 deiay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Section 11.3.2 of the Byron /Braidwood UFSAR.

10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive materialin 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 utspheric cleanup systems are not considered to be ventilation exhaust treatment system components.

10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors 1RE-PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks.

Both vent stack monitors feature automatic isokinetic sampling, grab sampling, iodine and particulate sampling and tritium sampling. In normal operation all three noble gas channels (low, mid-range, high) are on line and active. On a high alarm the low and mid-range noble gas channels are closed and only the high range noble gas channel remains active. The iodine and particulate channels, however, continue to operate under all conditions.

No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.

O 10-1

. BYRON Rzvizion 1.2 August 1994 10.1.2.2 Containment Purge Effluent Monitors

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Monitors 1RE-PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 containments, respectively. When airborne radioactivity in the containment purge effluent stream exceeds a specified level station personnel will follow established procedures to terminate the release by manually activating the containment purge valves. Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent.

No automatic isolation or control functions are performed by these monitors.

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

Monitors 1(2)RE-AR011 and 1(2)RE-ARO12 monitor the containment atmosphere. On high alarm during a containment purge, these monitors will automatically terminate the purge.

10.1.2.3 Waste Gas Decay Tank Monitors Monitors ORE-PR002A/B continuously monitor the noble gas activity released from the gas decay tanks.

On high alarm, the monitors automatically initiate closure of the valve OGW104 thus terminating the release.

Pertinent information on these monitors and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-1.

10.1.2.4 Gland Steam and Condenser Air Ejector Monitors Monitors 1RE-PR027 and 2RE-PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. No control device is initiated by these channels.

The following actions are initiated by this monitor:

a) Start 00G01C, Off-Gas Ejector HVAC System Exhaust Fan b) Close 100G035 and 200G035 c) Open OOG038,100G037, and 200G037 Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1, 10.1.2.5 Radwaste Building Ventilation Monitor Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. No control device is initiated by this channel.

Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Tables 11.5-1.

10.1.2.6 Component Cooling Water Monitor 10-2

BYRON R: vision 1.2 August 1994 Monitors ORE-PR009 (common),1RE-PR009 (Unit 1), and 2RE-PR009 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PR009 initiates closure of both component cooling water surge tank (CCWST) vents,1RE-PR009 initiates closure of the Unit 1 CCWST vent, and 2RE-PR009 initiates closure of the Unit 2 CCWST vent.

Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-1.

10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel.

Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1.

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 2.5% of the maximum permissible release rate for the high alarm and 1/4% of the maximum release rate for the alert alarm.

The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissible releace rate for the high alarm and 5% of the maximum release rate for the alert alarm.

10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.25 times the containment noble gas activity during purge.

However, per procedure, the total station release rate is limited to 1% of the maximum permissible release rate during this evolution. (See Section 10.1.3.2) 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.25 times the analyzed waste gas tank activity during release.

However per procedure, the total station release rate is limited to 1% of the maximum permissibic release rate during this evolution. (See Section 10.1.3.2) 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS Section 12.4 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Q,.

10-3

. BYRON Revision 1.2 August 1994 L (1.11)Q,, E {KY,} s 500 mrem /yr (10-1)

Q , [ { {fi) [E-(X/Q), exp(-A,R/3600u,)

t (10-2)

+ 1.11 V,]} < 3000 mrem /yr The summations 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, Vent Release [pCi/sec]

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

The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A.

Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

Since the solution to Equation 10-2 is more conservative than the solution to Equation 10-1, the value of Equation 10-2 (1.02 x 107 pCi/sec) is used as the limiting noble gas release rate. During .tolutions involving releases from the containment or waste gas decay tanks, the total station release rate is procedurally limited to 1 x 105 pCi/sec (1%

of the maximum permissible release rate).

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.  !

l 10.1.3.4 Conversion Factors

)

I The response curves used to determine the monitor count rates are based on the sensitivity to Xe-133 for conservatism. l 1

10-4 i

BYRON R: vision 1.2 August 1994 10.1.3.5 HVAC Dilution Flow Rates The plant vent stack flow rates are obtained from the RM-11 console in the control room. If the values cannot be obtained from RM-11, the following default values are used.

Unit 1 - 1.02 x 108 cc/sec Unit 2 - 1.00 x 10' cc/sec 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, allocation is mado evenly between units.

10.1.5 Dose Projections for Batch Releases The 10CFR20 dose limits have been converted into a station administrative release rate limit using the methodology in the ODCM Compliance is verified prior to each release.

Doses are calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50.

10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid release flowpath diagram is provided in Figure 10-3. A simplified liquid radwaste processing diagram is provided in Figure 10-2.

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 11.2.2 of the Byron /Braidwood Updated Final Safety Analysis Report.

10.2.1.1 Release Tanks There are two radwaste release tanks (OWXOIT and OWX26T 30,000-gallon capacity each) which receivo liquid waste before discharge to the Rock river.

10.2.1.2 Turbine Building Fire and Oil Sump The turbine building fire and oil sump receives water from selected turbine building sumps, the tendon tunnel sumps, and the diesel fuel oil storage sumps, all of which are normally non-radioactive but potentially contaminated. The effluent from this sump is monitored, and if radioactive contamination exceeds a predetermined level pump operation is automatically terminated. The water may then be sent to the liquid radwaste treatment system.

10.2.1.3 Condensate Polisher Sump O

10-5

BYRON R: vision 1.2 August 1994 The condensate polisher sump receives waste water from the condensate polisher N

system which is normally non-radioactive but potentially contaminated. The effluent from this sump is monitored and if radioactive contamination exceeds a predeter-mined level sump discharge is terminated and major condensate polisher inputs to the sump are automatically isolated. The water may then be sont to the liquid radwaste treatment system.

10.2.2 Radiation Monitors 10.2.2.1 Uquid Radwaste Effluent Monitors Monitor ORE-PR001 is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves OWX-353 and OWX-869 to terminate the release.

Pertinent information on the monitor and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-2.

10.2.2.2 Station Blowdown Monitor Monitor ORE-PRO 10 continuously monitors the recirculating water blowdown. No control device is initiated by this channel.

Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.

O 10.2.2.3

!] Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Une Monitors Monitors 1RE-PR002,2RE-PR002,1RE-PR003, and 2RE-PR003 continuously monitor the RCFC and ESSW outlet lines.

No control device is initiated by these channels.

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

10.2.2.4 Turbine Building Fire and Oil Sump Monitor Monitor ORE-PR005 continuously monitors the fire and oil sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps, close valve 00D030, and terminate the release. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.

10.2.2.5 Condensate Polisher Sump Monitor Monitor ORE-PR041 continuously monitors the condensate polisher sump discharge.

On high alarm the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5.2.

[] 10.2.3 Alarm and Trip Setpoints

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10-6

BYRON Revision 1.2 August 1994 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area.

10.2.3.1.1 Liquid Radwaste Effluent Monitor Durir.g release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading.

However, per procedure, the maximum release rate is limited to a value that will result in less than 50% of 10*DWC at the discharge point. (See Section 10.2.3.2).

10.2.3.1.2 Station Blowdown Monitor The monitor setpoint is found by solving equation 10-3.

P s C* + (1. 50 x CT ) x FL / " + FL (10-3)

P Release Setpoint [pCi/mt) 1.50 Factor to account for minor fluctuations in count rate C" Concentration of activity in the cirt ulat- [pCi/ml]

ing water blowdown at the time of discharge

(" Background reading")

C7 Analyzed activity in the release tank [pCi/ml]

excluding trit!um F* Circulating Water Blowdown Rate [gpm]

FL Maximum Release Tank Discharge Flow Rate [gpm]

The flow rate from the radwaste discharge tank.

O 10-7

BYRON Rrvision 1.2 August 1994 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained.

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

FL, = 0.5(Fict/{ (C, /10.DWQ) (10-4)

The summation is over radionuclides 1.

FL, Maximum Permitted Discharge Flow Rate The maximum permitted flow rate from the radwaste discharge tank based on radiological limits (not chemistry limits which may be more restrictive) [gpm]

Fjc Circulating Water Blowdown Rate [gpm]

C, Concentration of Radionuclide iin [pCl/mL) s the Release Tank f

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

DWC, Derived Water Concentration [pC1/ml]

The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402.

10 Multiplier 10.2.3.3 Release Limits Release limits are determined from 10CFR20. Discharge rates and setpoints are adjusted to ensure that 50% of 10*DWC are not exceeded.

10.2.3.4 Release Mixture For monitors ORE-PR001 and ORE-PR010 the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis.

For all other liquid effluent monitors the release mixture is the radionuclides which are listed in Table 10-2. Each nuclide in the mix is at a concentration which is 10% of the 10 times the DWC value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 -

20.2402. l 10.2.3.5 Conversion Factors 10-8 .

I

BYRON R:: vision 1.2 August 1994 The readouts for the liquid effluent monitors are in pCi/mt. The epm to pCi/mi conversion is based on the detector sensitivity to Cs-137.

10.2.3.6 Uquid Dilution Flow Rates Dilution flow rates are obtained from the rnain control board in the control room. Uguid effluents are not released if this information is unavailable.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is made evenly between units.

10.2.5 Projected Concentrations for Releases After determining FL,from Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6.

Cf = C((FL,/(FL, + Fla)] (10-5)

(( Cf/10 OWC, }si (10-6)

The summation is over radionuclides 1.

Cf Concentration of Radionuclide iin the Unrestricted Area [pCi/mL]

The calculated concentration of radionuclide iin the unrestricted area as determined by Equation 10-5.

C[ Concentration of Radionuclide I in the [pCi/mL]

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

DWC, Derived Water Concentration [pCi/md The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402.

10 Multiplier FL, Maximum Release Tank Discharge [gpm]

Flow Rate Fl, Circulating Water Blowdown Rate [gpm]

O 10-9

. BYRON Revillon 1.2 August 1994

[J,

~) 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

Figure 104 is a simplified diagram of the solid radwaste processing system.

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BYRON Rivilion 1.2 August 1994 Table 10-1 i Assumed Composition of the Byron Station Noble Gas Effluent Percent of Isotope Effluent Ar-41 00.89 Kr-85m 00.18 Kr-85 24.9 Kr-87 00.4 I

Kr-88 00.28 l

Xe-131m 01.4 i Xe-133m 00.57 Xe-133 71,1 1

Xe-135 00.53 Xe-138 00.04 l

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10-11 1

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BYRON R vilion 1.2 August 1994 C\ Table 10-2

%) l Assumed Composition of the Byron Station Liquid Effluent )

l Isotope Concentration isotope Concentration l l

(pCl/mi) (pCl/ml)

Ru-103 8.00E - 06 Mn-54 1.00E - 05 Ag-110m 3.00E - 06 Fe-59 5.00E - 06 Te-127 2.00E - 05 Co-58 9.00E - 06 Te-129m 2.00E - 06 Co40 3.00E - 06 Te-131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr-95 6.00E - 06 ,

1-130 3.00E - 07 Nb-95 1.00E - 05 l-131 3.00E - 08 Mo-99 4.00E - 06 l-132 8.00E - 07 l-133 1.00E - 07 1

l-135 4.00E - 07 7-V Cs-134 9.00E - 07 l Cs-136 9.00E - 06 Cs-137 2.00E - 06 ,

l Ce-144 1.00E - 06  !

Np-239 1.00E - 05 l l

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BYRON Revision 1.2 August 1994 Una1 condenser 2.500 (During Unt i eiertup)

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F Rerumng 4. An now retse are ensign now rams in cubic feet per nanute.

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-- PROCESSING DIAGRAM 10-15

-e BYRON R vbi n 1.2 August 1994 s.

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BYRON Revision 1.2 August 1994 O

SOUDFIED PORTADLE DEMWFOR

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BYRON Revision 1.2 i August 1994 BYRON ANNEX INDEX PAGE REVISION CHAPTER 11 11-1 1.2 il 1.2 11-lii 1.2 11-iv ' 1.2 11 1.2 ~

11-2 1.2 11-3 1.2 11-4 1.2 11-5 1.2 11-6 1.2 11-7 1.2 11-8 1.2 11-9 1.2 11-10 1.2 11-11 1.2 11-12 1.2 13 1.2 11-14 1.2 11-15 1.2 11-16 1.2 0 11-17 11-18 11-19 1.2 1.2 1.2 f

O 11-1

BYRON Revision 1.2 August 1994 -

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS PAGE 11.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 Ol l

I O

11-li w ___-- - _ _ . - _ _ __

BYRON Revision 1.2

• - August 1994

('%

(ji CHAPTER 11 UST OF TABLES NUMBER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 11-12 11-3 Detection Capabilities for Environmental Sample Analysis 11-13 cd 11-iii

BYRON RI: vision 1.2 August 1994 CHAPTER 11 UST OF FIGURES NUMBER TITLE PAGE 11-1 Onsite Air Sampling Locations 11-16 11-2 Offsite Air Sampling Locations 11-17 11-3 inner Ring and Outer Ring TLD Locations 11-18 11-4 Ingestion and Waterborne Exposure Pathway Sample Locations 11-19 0

d O

11-iv

__ . _ _ _ _ _ _ _ _ - _ - - . _ _ _ _ . _ _ _ _ _ ___ _ ______.._________.________--___.__m___a

,e  ?

f BYRON Revision 1.2 August 1994 .

t J

CHAPTER 11 MC ; LOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program for the environs around Byron Station is given in Table i 11-1, Reporting levels and lower limits of detection for this program are given in Tables 11-2 and 11-3,

. respectively.

Figures 11-1 through 11-4 show sampling and monitoring locations.

i r

a V  :

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r P

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11-1 l s

BYRON Revision 1.2 August 1994 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplina or Monitorina Locations

• Collection Frecuency of Analysis

1. Direct Radiation a. Inner Rina Quarterly Gamma dose quarterly indicators BY-102-1,1.0 mi NNE (1.6 km B)

BY-102-2,1.0 mi NNE (1.6 km B)

BY-103-1,1.7 mi NE (2.7 km C)

BY-103-2,1.7 mi NE (2.7 km C)

BY-104-1,1.4 mi ENE (2.2 km D)

BY-104-2,1.4 mi ENE (2.2 km D)

BY-105-1,1.3 mi E (2.1 km E)

BY-105-2,1.3 mi E (2.1 km E)

BY-106-1,1.4 mi ESE (2.2 km F)

BY-106-2,1.4 mi ESE (2.2 km F)

BY-107-1,1.4 mi SE (2.2 km G)

BY-107-2,1.4 mi SE (2.2 km G) 4.*-108-1, 0.6 mi SSE (1.0 km H)

BY-108-2,0.6 mi SSE (1.0 km H)

BY-109-1,0.6 mi S (1.0 km J)

BY-109-2,0.6 mi S (1.0 km J)

BY-110-1,0.6 mi SSW (1.0 km K)

BY-110-2,0.6 mi SSW (1.0 km K)

BY-111-3,0.8 mi SW (1.2 km L)

BY-111-4,0.8 mi SW (1.2 km L)

BY-112-3,0.8 mi WSW (1.3 km M)

BY-112-4,0.8 mi WSW (1.3 km M) e 6 e .

O O BYRON 9

Revision 1.

August 1994 Table 11-1 (Cont.)

Radiological Envuonmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplina or Monitorina Locations

• Collection Freauency of Analysis .

1. Direct Radiation BY-113-1,0.7 mi W (1.1 km N)

(Cont'd) BY-113-2, 0.7 mi W (1.1 km N)  !

BY-114-1,0.8 mi WNW (1.3 km P)

BY-114-2,0.8 mi WNW (1.3 km P)

BY-115-1,1.0 mi NW (1.6 km Q)

BY-115-2,1.0 mi NW (1.6 km Q)

BY-116-1,1.4 mi NNW (2.2 km R)

BY-116-2,1.4 mi NNW (2.2 km R) j

b. Outer Rina Quarterly Gamma dose quarterly Indicators BY-201-3,4.5 mi N (7.2 km A)

BY-201-4,4.5 mi N (7.2 km A)

BY-202-1,4.5 mi NNE (7.2 km B)

BY-202-2,4.5 mi NNE (7.2 km B)

BY-203-1,5.1 mi NE (8.2 km C)

BY-203-2,5.1 mi NE (8.2 km C)

BY-204-1,4.2 mi ENE (6.8 km D)

BY-204-2,4.2 mi ENE (6.8 km D)

BY-205-1,3.9 mi E (6.3 km E) '

BY-205-2,3.9 mi E (6.3 km E)

BY-206-1,4.2 mi ESE (6.8 km F) ~

BY-206-2,4.2 mi ESE (6.8 km F)

BY-207-1,4.2 mi SE (6.8 km G)

BY-207-2,4.2 mi SE (6.8 km G) 11-3

_ _ _ _ - _ _ _ - _ _ - - - _ = _ _ _ _ _ - - _ - = _ _ _ _ _ _ _ _ _ _ -

BYRON Revision 1.2 August 1994 Table 11-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampfino or Monitorina Locations

• Collection Frecuency of Analysis

1. Direct Radiation BY-208-1,4.1 mi SSE (6.6 km H)

(Cont'd) BY-208-2,4.1 mi SSE (6.6 km H)

BY-209-1, 3.8 mi S (6.1 km J)

BY-209-4, 3.6 mi S (5.8 km J)

BY-210-3,4.75 mi SSW (7.6 km K)

BY-210-4,4.75 mi SSW (7.6 km K)

BY-211-1, 5.2 rni WSW (8.4 km L)

BY-211-4,4.9 mi WSW (7.9 km L)

BY-212-1,4.9 rni SW (7.9 km M)

BY-212-4,4.9 mi WSW (7.8 km M)

BY-213-1, 5.0 mi W (8.0 km N)

BY-213-4, 5.0 mi W (8.0 km N)

BY-214-1,4.8 mi WNW (7.7 km P)

BY-214-4,4.8 mi WNW (7.7 km P)

BY-215-1,5.2 mi NW (8.4 km Q)

BY-215-4,5.2 mi NW (8.4 km Q)

BY-216-1,4.8 mi NNW (7.7 km R)

BY-216-2,4.8 mi NNW (7.7 km R)

c. Special Interest Quarterly Gamma dose quarterly on one set. Gamma dose on Indicators second set if requested by CECO.

Two TLDs at each of the airborne pathway indicator locations specified in Part 2 of this table.

e -- - - -

6 e.

O QON B . Revision 1. 9~~

- August 1994

Table 11-1 (Cont.)

Radiological Envronmental Monitoring Program Exposure Pathway Sampling or . Type of Frequency +

and/or Samole Samplina or Monitorina Locations

• Collection Freauency of Analysis

1. Direct Radiation Controls (Cont'd)

Two TLDs at each of the I

airborne pathway controllocations specified in Part 2 of this table.

I

2. Airborne f

. Radioiodine and Indicators Continuous sampler operation Radioiodine Canister:

Particulates with sample collection weekly, I-131 analysis weekly.

a. Near Site Boundary or more frequently if required by dust loaoing.

BY-21, Byron Nearsite N, Particulate Sampler 0.26 mi N (0.42 km A)

BY-22, Byron Nearsite ESE, s. Gross beta analysis 0.30 mi ESE (0.48 km F) following filter BY-23, Byron Nearsite S, change."

0.60 mi S (0.97 km J)- b. Gamma isotopic BY-24, Byron Nearsite SW, analysis on ,

0.65 mi SW (1.05 km L) quarterty compo- >

site" (by location). ,

b. Near Community with Hiohest Calculated .

Annual Averaae Ground Level D/O Samolina Train:

BY-1, Byron,3.5 mi N (5.6 km A) Test and maintenance ,

weekly.

k

{

11-5

BYRON Revision 1.2 August 1994 Table 11-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplina or Monitorina locations

• Collection Freauency of Analysis

2. Airborne (Cont'd) c. Other BY-3, Nearsite - East, 3.8 mi E (6.1 km E)

BY-4, Paynes Pt.,4.5 mi SE (7.2 km G)

By-5, Nearsite - South 3.6 mi S (5.8 km J)

BY-6, Oregon,4.6 mi SSW (7.4 km K)

Controls BY-2, Stillman Va!Iey, 6.2 mi ENE (10.0 km D)

BY-7, Mt. Morris,7.8 mi W (12.6 km N)

BY-8, Leaf River,7.0 mi NW (11.3 km Q)

3. Waterborne

a. Surface BY-9, Woodland Creek,2.1 mi NW Weekly from BY-12, BY-13, Gamma isotopic (3.4 km Q) and BY-29 weekly from BY-9 analysis

• cn monthly BY-12, Oregon Pool of Rock River, if Woodland Creek is flowing. composite from each Downstream of Discharge, location. Tritium l

4.5 mi SSW (7.2 km K) analysis on quarterly BY-13, Rock River, Upstream of Intake, composite from each 2.6 mi WNW (4.2 km P) location.

BY-29, Byron, Upstream of Intake 3.5 mi N (5.6 km A) e 6 - - - -

e

O O BYRON ON Revision 1.2 August 1994 Table 11-1 (Cont.)

Radiological Envvonmental Monitoring Program Exposure Pathway Samping or Type of Frequency and/or Sample Samplina or Monitorina Locations

• Collection Frecuency of Analysis

3. Waterbome (Cont'd)

, b. Ground /WeII Indicators Quarterly Gamma isotopic" and l Water - Tritium analysis on i Offsite BY-14, CECO Offsite WeII quarterly.

0.3 mi ESE (0.5 km F)

BY-18, McCoy Farmstead 1.0 mi SW (1.6 km L)

c. Shoreline BY-12, Oregon Pool of Rock River, Semiannua!!y Gamma isotopic" analysis Sediments Downstream of Discharge, semiannually.

4.5 mi SSW (7.2 km K)

BY-13, Rock River, Upstream of Intake,2.6 mi WNW (4.2 km P) ,

BY-29, Byron, Upstream of Intake, 3.5 mi N (5.6 km A)

4. Incestion

a. Milk Indicators Semimonthly: May to Ocicber Gamma isotopic

• and Monthly: November to April 1-131 analysis on each -l sample. I BY-20, K. Reeverts Dairy Farm, 2.1 mi NE (3.4 km C)

BY-27, Kenneth Druien Dairy Farm, 5.8 mi WSW (9.3 km M)

BY-30, Don Roos Dairy, 5.13 mi SE (8.2 km G) 11-7

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

BYRON Revision 1.2 August 1994 Table 11-1 (Cont.)

Radiological Emnronmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Samplina or Monitorina Locations' Collection Freauency of Analysis

4. Incestion (Cont'd)

Controls BY-26, Glen Hazzard's Dairy, 13.5 mi N (21.6 km A)

b. Fish and BY-12, Oregon Pool of Rock River, Three times per year (spring, Gamma isotopic

• Invertebrates Downstream of Discharge, summer, and fa!!). analysis on edible Representative 4.5 mi SSW (7.2 km K) portions.

samples of BY-13, Rock River, Upstream of commercially intake,2.6 mi WNW (4.2 km P) and recrea- BY-29, Byron, Upstream of Intake l tionally 3.5 mi N (5.6 km A) important species.

c. Vecetables BY-19-1, River Road Across from At time of harvest Gamma isotopic

• Air Sampler BY-01 analysis on edible 2.7 mi N (4.3 km A) portions.

~J \J N., .)

BYRON Revision 1.2 August 1994 Table 11-1 (Cont.)

Radiological Envwonmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samolina or Monitorina Locations

• Collection Frecuency of Ana!vsis

4. Incestion (Cont'd)

d. f_ood Products Indicators Grown nearest each of two different Monthly when available and Gamma isotopic

• and offsite locations of highest required; reauired only if I-131 analysis Samples of predicted annual average ground milk samolina is not performed three differ- level D/Q (see Table F-5) ent kinds of broadleaf vegetation Controls From a location 15 to 30 km from Monthly when available and Gamma isotopic

• and the station in direction of least required; recuired only if l-131 analysis One sample prevalent wind direction milk samplina not performed each of broadleaf vegetation similar to that col-lected for the above requirement l

11-9 l

BYRON Revision 1.2 August 1994 TABLE 11-1 (Cont'd)

Radiological Envronmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplina or Monitorina Locations

• Collection Freauency of Analysis

5. Land Use Census

a. Milch Animals 1. Site boundary to 2 miles Annually during growing season Enumeration by a door-to-door or equivalent counting technique.

2. 2 to 5 miles Annually during growing season Enumeration by using referenced information from county agricul-tural agencies or other reliable sources.

3. At dairies listed in item Annua!!y during growing season Inquire as to feeding 4.a. practices:

a. Pasture only.

b. Feed and chop only.

c. Pasture and feed; if both, ask farmer to estimate fraction of food from pasture:

<25%, 25-50%,

50-75%, or >75%

e 5 e .

,y

[

(v) OBYRON

\ ,)

Revision 12 u

August 1994 TABLE 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplina or Monitorina Locations

• Collection Freauency of Analysis

b. Nearest in all 16 sectors up to 5 miles. Annually Residence NOTE: Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and allocations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Submit controlled revisions of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples.

See Table D-16 for definitions of sector codes used with ki'ometer distances.

6 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to a!!ow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

i i

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11-11 l

Revision 1.2 August 1994 BYRON TABLE 11-2 Reporting Levels for Radioactmty Concentrations in Envwonmental Samples Water Airborne Particulate Fish Milk Food Products Analysis foci /L) or Gases (DCi/m')_ (DCi/ka. wet) (DCi/L) (DCi/ko. wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

• For drinking water samples. This is the 40 CFR Part 141 value. if no drinking water g

pathway exists, a value of 30,000 pCi/L may be used.

l 11-12 O O O .

O O D~

- Revision 12

~.

August 1994 '

BYRON TABLE 11-3 Detection Capabigties for Envuonmental Sample Analysis Lower Umit of Detection (LLD)*

Airbome Particulate Water or Gases Fish Milk Food Products Sediment Analysis (pCi/L) foci /m') (DCi/ka. wet) (pCi/L) (DCi/ka. wet) (DCt/ka. dry)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 i Co-58, 60 15 130 Zn-65 30 260 Zn-Nb-95 15 l-131 1' O.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 -150 18 80 180 Ba-La-140 15 15 11 . . _ _ - - - . - . , , . - - -. . - . . . . _. .. . - . . - . - . . .. . . . . . . -

BYRON Rrvision 1.2 August 1994 -

Table 11-3 (Cont'd)

Detection Capabilities for Environmental Sample Analysis General Notes:

1. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

2. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

Footnotes:

'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 percent probability with only 5 percent 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, LLD =

E V 2.22 Y exp (4 At)

LLD = The a priod ri_ lower limit of detection (picocuries per unit mass or volume).

S. = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (count per minute).

E = The counting efficiency (counts per disintegration).

V = The sample size (units of mass or volume).

2.22= The number of disintegrations per minute per picoeurie.

Y = The fractional radiochemical yield, when applicable.

). = The radioactive decay constant for the particular radionuclide (seed ).

At= The elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).

Typical values of E, V, Y, and at should be used in the calculation, it should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analysis shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctutions, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

11-14

- + l:

BYRON- .'Ravition 1.2 ,

August 1994 i

e Table 11-3 (Cont'd)

Detection Capabilities for Envronmental Sample Analysis

• = If no drinking water pathway exists, a value of 3000 pCl/L may be used. ,

• = LLD for drinking water samples. If no drinking water pathway exists, an LLD of 60 pCi/L may be used.

L i

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11-15

l BYRON Rivhion 1.2 August 1994 .

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.)

BYRON Rrvilion 1.2

. August 1994 4

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. CHAPTER 12.0 ,

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P SPECIAL NOTE The transfer of the Byron Radiological Effluent Technical Specifications to the ODCM was - I approved by the Nuclear Regulatory Commission in Technical Specification Amendment 46, dated April 13,1992. ,

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

BYRON R: vision 1.2 August 1994 BYRON ANNEX INDEX CHAPTER 12 1

PAGE REVISION PAGE REVISION l 12 - l 1.2 12 - 45 1.2 12 - li 1.2 12 - 46 1.2 l 12 - lii 1.2 12 - 47 1.2 l 12 - iv 1.2 12 - 48 1.2 l 12 - 1 1.2 12 - 49 1.2 I 12 - 2 1.2 12 - 50 1.2 12 - 3 1.2 12 - 51 1.2 12 - 4 1.2 12 - 52 1.2 12 - 5 1.2 12 - 53 1.2 12 - 6 1.2 12 - 54 1.2 l 12 - 7 1.2 12 - 55 1.2 12 - 8 1.2 12 - 56 1.2 12 - 9 1.2 12 - 57 1.2 12 - 10 1.2 12 - 58 1.2 12 - 11 1.2 12 - 12 1.2 12 - 13 1.2 12 - 14 1.2 12 - 15 1.2 12 - 16 1.2 12 - 17 1.2 12 - 18 1.2 12 - 19 1.2 l

12 - 20 1.2 12 - 21 1.2 12 - 22 1.2 12 - 23 1.2 12 - 24 1.2 i 12 - 25 1.2 12 - 26 1.2 12 - 27 1.2 12 - 28 1.2 12 - 29 1.2 12 - 30 1.2 12- 31 1.2 12 - 32 1.2 12 - 33 1.2 12 - 34 1.2 12 - 35 1.2 12 - 36 1.2 12 - 37 1.2 12 - 38 1.2 12 - 39 1.2 12 - 40 1.2 12 - 41 1.2 12 - 42 1.2 12 - 43 1.2 12 - 44 1.2 12-ii

BYRON R vi ion 1.2

. August 1994

/^\ CHAPTER 12 O

RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-2 12.2 INSTRUMENTATION 12-5

1. Radioactive Uquid Effluent Monitoring instrumentation 12-5

2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-10 12.3 UQUID EFFLUENTS 12-17

1. Concentration 12-17

2. Dose 12-22

3. Liquid Radwaste Treatment System 12-24 12.4 GASEOUS EFFLUENTS 12-27

1. Dose Rate 12-27

( 2. Dose - Neble Gases 12-31

3. Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form 12-33

4. Gaseous Radwaste Treatment System 12-35

5. Total Dose 12-37 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-39

1. Monitoring Program 12-39

2. Land Use Census 12-52

3. Interlaboratory Comparison Program 12-53 12.6 REPORTING REQUIREMENTS 12-54

1. Annual Radiological Environmental Operating Report 12-54

2. Annual Radioactive Effluent Release Report 12-56

3. Offsite Dose Calculation Manual (ODCM) 12-57

4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-58 12-lii

BYRON R: vision 1.2 August 1994 -

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

IIST OF TABLES TABLE TITLE PAGE 12.0-1 Compliance Matrix 12-1 12.1-1 Frequency Notations 12-4 12.2-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-6 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12-8 12.2-3 Radioactive Gaseous Effluent Monitoring )

instrumentation 12-11 )

l 12.2-4 Radioactive Gaseous Effluent Monitonng i instrumentation Surveillance Requirements 12-14 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-18 12.4-1 Radioactive Gaseous Waste Sampling and Analysis l Program 12-28 '

12.5-1 Radiological Environmental Monitoring Program 12-42 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-48 12.5-3 ?stection Capabilities for Environmental Sample Analysis 12-49 O

12-iv I

4 BYRON Rsvision 1.2

. August 1994 BYRON STATION Table 12.0-1 COMPUANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification 10 CFR 50 1. Gamma air dose and beta air dose due to A-1 12.4.2 6.8.4.e.8 Appendix I airborne radioactivity in effluent plume. A-2

a. Whole body and skin dose due to airborne A-6 N/A N/A radioactivity in effluent plume are reported A-7 only if certain gamma and beta air dose criteria are exceeded. A-13 12.4.3 6.8.4.e.9

2. CDE for all organs and all four age groups due to iodines and particulates in effluent plume. All A-29 12.3.2 6.8.4.e.4 pathways are considered.

3. CDE for all organs and all four age groups due to radioactivity in liquid effluents.

10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 6.8.4.e.3

- components (direct, ground and plume shine)

1. and committed effective dose equivalents (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 data base.

40 CFR 190 1. Whole body dose (DDE) due to direct dose, A-35 12.4.5 6.8.4.e.10 (now by ground and plume shine from all sources at a reference, station.

also part of A-13 10 CFR 20) 2. Organ doses (CDE) to an adult due to all pathways.

Technical 1. " Instantaneous" whole body (DDE), skin (SDE), A-8 12.4.1 6.8.4.e.7 Specifications and organ (CDE) dose rates to an adult due to A-9 radioactivity in airborne effluents. For the organ A-28 dose, only inhalation is considered.

A-32 12.3.1 6.8.4.e.2

2. " Instantaneous" concentration limits for liquid effluents.

I O  ;

12-1

BYRON R: vision 1.2 August 1994 .

12.1 DEFINITIONS 12.1.1 ACTION shall be that which prescribes remedial measures required under designated conditions.

12.1.2 ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signalinto the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shallinclude adjustments, as necessary, of the alarm interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

12.1.3 CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values ofinput. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

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

12.1.5 DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.

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

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

12.1.7 MEMBER (S) OF THE PUBLIC means an individualin a controlled or unrestricted area. However, an individualis not a memeber of the public during any period in which the individual receives occupational dose.

12.1.8 OPERABLE / OPERABILITY a system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

12.1.9 OPERATIONAL MODE (i.e. Mode) shall correspond to any one inclusive combination  ;

of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 of the Technical Specifications. I l

12.1.10 PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, I sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of ,

actual or simulated wet solid wastes will be accomplished in such a way as to assure j compliance with 10 CFR Parts 20,61,71 and State regulations, burial ground 1 requirements, and other requirements governing the disposal of radioactive wastes.

12-2

BYRON Rsvicion 1.2

, August 1994

/] 12.1.11 PURGE / PURGING shall be any controlled process of discharging air or gas from a

() confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to punfy the confinement.

12.1.12 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MW,.

12.1.13 SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.

12.1.14 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

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

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

12.1.17 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

12.1.18 VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive materialin palticulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the

, gaseous exhaust stream prior to the release to the environment. Such a system is G not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

12.1.19 VENTING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

12.1.20 WASTE GAS HOLDUP SYSTEM shall be any system 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 for the purpose of reducing the total radioactivity prior to release to the environment.

12.1.21 Definitions Peculiar to Estimating Dose to Members of the Public using the ODCM Computer Program.

a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.

b. PROJECTED - PROJECTED refers to using known release data from the p previous time period or estimated release data to forecast a future dose to members of the public. This data is not incorporated into the database.

12-3

BYRON R:villon 1.2 August 1994 .

TABLE 12.1-1 O

FREQUENCY NOTATIONS Notation Freauency S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days R At least once per 18 months S/U Prior to each reactor startup N.A. Not applicable P Completed prior to each release O O

12-4

BYRON Revision 1.2

, August 1994 b

G 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability Reauirements 12.2.1.A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parametels in the ODCM.

Anoticability: At all times Action

1. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1.

Restore the inoperable instrumentation to OPERABLE status within the time

(

specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

Surveillance Reauirements 12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.

The OPERABILITY and use of this instrumentation is consistent with the requirements l of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

O V

12-5

BYRON Revision 1.2 August 1994 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Uquid Radwaste Effluent Une (ORE-PR001) 1

b. Fire and Oil Sump (ORE-PR005) 1 34

c. Condensate Polisher Sump Discharge (ORE-PR041) 34

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 a) RCFC 1 A and 1C Outlet (1RE-PRM2) 1 32 b) RCFC 1B and 1D Outlet (1RE-PRC i) 1 32

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 2B and 2D Outlet (2RE-PR003) 1 32

b. Station Blowdown Une (ORE-PR010) 1 32

3. Flow Rate Measurement Devices

a. Uquid Radwaste Effluent Une (Loop-WXOO1) 1 33

b. Uquid Radwaste Effluent Low Flow Une (Loop-WX630) 1 33 l c. Station Blowdown Une (Loop-CWO32) 1 33 l

e _- ---_

6 e..

1 l

BYRON R villon 1.2 l August 1994 p TABLE 12.2-1 (Continued)

Q RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l

ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Section 12.3 and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels l OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and l analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.

l i

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in p! ace may be used to estimate flow.

l ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microCurb/ gram DOSE EQUIVALENT l-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

l l

l

/*

12-7 1

BYRON Revision 1.2 August 1994 TABLE 12.2-2 RADIOACTIVE LfQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CAllBRATION TEST TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Releaee

a. Liquid Radwaste Effluent Une (ORE-PR0! D P R(3) Q(1) N.A.

b. Fire and Oil Sump Discharge (ORE-PR005) D M R(3) Q(1) N.A.

c. Condensate Polisher Sump Discharge (ORE-PR041) D M R(3) Q(1) N.A.

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 a) RCFC 1A and 1C Outlet (1RE-PR002) D M R(3) Q(2) N.A.

b) RCFC 1B and 1D Outlet (1RE-PR003) D M R(3) Q(2) N.A.

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) D M R(3) Q(2) N.A.

b) RCFC 2B and 2D Outlet (2RE-PR003) D M R(3) Q(2) N.A.

b. Station Blowdown Une (ORE-PRO 10) D M R(3) Q(2) N.A.

3. Flow Rate Measurement Devices

a. Uquid Radwaste Effluent Line (Loop-WX001) D(4) N.A. R N.A. Q

b. Uquid Radwaste Effluent Low Flow Line D(4) N.A. R N.A. Q (Loop-WX630)

c. Station Blowdown Une (Loop-CWO32) D(4) N.A. R N.A. Q e 6 e. __

4

' BYRON Rzvision 1.2 -l August 1994 TABLE 12.2-2 (Continued)

\/' RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic i isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists; I

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or  ;

i

b. Circuit failure (monitor loss of communications - alarm only, detector loss of -

counts, or monitor loss of power), or

c. Detector check source test failure, or t

d. Detector channel out-of-service, or  ;

e. Monitor loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control -

room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or ,

O b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or l

c. Detector check source test failuie, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. 7 (3) The initial CHANNEL CAllBRATION shall be performed using one or more of the  !

reference standards certified by the NationalInstitute of Standards and Technology i (NIST) or using standards that have been obtained from suppliers that participate in  ;

measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shai:

be used.

i (4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.  !

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made. .

O 12-9 l

BYRON RIvilion 1.2 August 1994 O

12.2.2 Radioactive Gaseous Effluent Monitorina instrumentation Operability Reauirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 12.4 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Apolicability: As shown in Table 12.2-3  :

Action

1. With a radioactive gaseous effluent monitoring instrumentation channe! ]

Alarm / Trip Setpoint less conservative than required by the above specification, i immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channelinoperable.

2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-3.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release l Report pursuant to Section 12.6 why this inoperability was not corrected within j the time specified. '

Surveillance Reauirements 12.2.1.B Each radioactive gaseous effluent monitoring instrumentation channel shall be )

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and CHANNEL OPERATIONAL TEST  !

at the frequencies shown in Table 12.2-4. I Bases 12.2.1.C The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.

The instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to RETS. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 12.4 shall be such that concentrations as low as 1x104uCi/cc are measurable.

O 12-10

1

% ./ n40N k

i Revision 'r l-August 1994 TABLE 12.2-3 RADIOACT!VE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNE8.S INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Plant Vent Monitoring System - Unit 1

a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (1RE-PR028D) 1 39

2) Low Range (1RE-PR0288) 1 '39 i

b. lodine Sampler (1RE-PR028C) 1 40

c. Particulate Sampler (1RE-PR028A) 1 40

d. Emuent System Flow Rate Measuring Device (LOOP-VA019) 1 36- .

i

e. Sampler Flow Rate Measuring 36 Device (1FT-PR165) 1

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor--

Providing Alarm

1) High Range (2RE-PR028D) 1 39

2) Low Range (2RE-PR028B) . 1 39

! b. lodine Sampler (2RE-PR028C)

• 1 40

c. Particulate Sampler (2RE-PR028A) 1 40 Emuent System Flow Rate d.

Measuring Device (LOOP-VA020) 1 36

e. Sampler Flow Rate Measuring Device (2FT-PR165) 1 36 12-11

BYRON Revision 1.2 August 1994 TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (CONTD)

MINfMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

3. Not Used.

4. Gas Decay Tank System

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (ORE-PR002A and 28) 2 35

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) 1 37

b. lodine Sampler (RE-PR001C) 1 40

c. Particulate Sampler (RE-PR001A) 1 40

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Une (ORE-PR009 and RE-PR009) 2 41

BYRON Rzvision 1.2 August 1994 jq TABLE 12.2-3 (Continued)

Q RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (CONT'D)

TABLE NOTATIONS

• At all times.

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge vane lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 38 - Not used.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue ,

for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and '

these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 12.4-1.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requiremant, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, gaseous grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.4-1.

O 12-13

BYRON Revision 1.2 August 1994 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CAllBRATION TEST IS REQUIRED

1. Plant Vent Monitoring System - Unit 1

a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (1RE-PR028D) D M R(3) Q(2)

2) Low Range (1RE-PR028B) D M R(3) Q(2)

b. lodine Sampler (1RE-PR028C) D M R(3) Q(2)

c. Particulate Sampler (1RE-PR028A) D M R(3) Q(2)

d. Effluent System Flow Rate Measuring D N.A. R Q Device (LOOP-VA019)

e. Sampler Flow Rate Measuring Device D N.A. R Q *

(1FT-PR165)

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (2RE-PR028D) D M R(3) Q(2)

2) Low Range (2RE-PR028B) D M R(3) Q(2)

b. lodine Sampler (2RE-PR028C) D M R(3) O(2) e E e.

(^% -

G B N Revision 1.

August 1994 TABLE 12.2-4 (Con +inued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

DIGITAL l

CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CAllBRATION TEST IS REQUIRED

2. Plant Vent Monitoring System - Unit Two (Continued)

c. Particulate Sampler (2RE-PR028C) D M R(3) Q(2)

d. Effluent System Flow Rate Measuring D N.A. R Q

• Device (LOOP-VA020)

e. Sampler Flow Rate Measuring Device D N.A. R Q *

(2FT-PR165)

3. Not Used

4. Gas Decay Tank System

a. Noble Gas Activity Monitor P P R(3) Q(1)

Providing Alarm and Automatic Termination of Release (ORE-PR002A and 28)

5. Containment Purge System a Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) D P R(3) Q(2)

b. lodine Sampler (RE-PR001C) P P R(3) N.A.

c. Particulate Sampler (RE-PR001A) P P R(3) N.A.

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Une (0RE-PR009 and RE-PR009) D M R(3) Q(1) 12-15

BYRON R:vi lon 1.2 August 1994 TABLE 12.2-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS

• At all times.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the AlarmTTrip Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or l

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or l monitor loss of power), or j

c. Detector check source test failure, or j

\

d. Detector channel out-of-service, or i l

e. Monitor loss of sample flow.

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference i l

standards certified by the NationalInstitute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended j range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.

O1 12-16

BYRON R: virion 1.2

. August 1994 12.3 LIQUID EFFLUENTS -

12.3.1 Concentration Operability Reauirements 12.3.1.A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. For dissolved or entrained noble gases, the concentration shall be lin/ted to 2x10-' microcurie /ml total activity.

Apolicability: At all times Action:

1. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits,immediately restore the concentration to within the above limits.

Surveilla_r).ce Reauirements 12.3.1.1.B Radioactive liquid wastes shall be samr4ed and analyzed according to the sampling and analysis program of Table 12.3-1.

O 12.3.1.2.8 The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of re! ease are maintained with the limits of 12.3.1.A.

Bases 12.3.1.C This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10CFRPart 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within:

(1) the Section ll.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population.

This specification applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qnaltative Detection and Quantitative Determination - Application to RadiocbWst:y," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Umits for Radioanahtical Counting Techniques," Atlantic Richfield Hanford Company Report A3H-SA-215 (June 1975).

1 O  !

l l

12-17

BYRON Revision 1.2 August 1994 TABLE 12.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM TYPE OF ACTIVITY OF LIQUID RELEASE SAMPLING ANALYSIS ANALYSIS DETECTION TYPE FREQUENCY FREQUENCY (LLD)") l (pCi/m!)

1. Batch P P Principal Gamma 5x10-7 Release Each Batch Each Batch Emitters

• Tanks (2) 1-131 1x10 4 P M Dissolved and 1x10' One Batch /M Entrained Gases (Gamma Emitters)

P M H-3 1x10*

Each Batch Composite (')

Gross Alpha 1x 10

P Q Sr-89, Sr-90 5x10*

Each Batch Composite (*)

Fe-55 1x10 4

2. Continuous Continuous" W Principal Gamma 5x10-7 0

Releases

• Composite

• Emitters

• l 1

l l-131 1x10*

a. Circulating M M Dissolved and 1x10 4 l Water Grab Sample Entrained Gases Blowdown (Gamma Emitters)

Continuous

• M H-3 1x10 4

b. Waste Water Composite

• Treatment Discharge to j Circulating Gross Alpha 1x10-7 j Water Discharge I

c. Condensate Continuous

• Q Sr-89, Sr-90 5x10 4 Polisher Sump Composite

• il Discharge Fe-55 1x10*

O 12-18

BYRON Revision 1.2 August 1994 o.

TABLE 12.3-1 (Continued)

RADIOACTIVE !! QUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)") l TYPE FREQUENCY FREQUENCY ANALYSIS (pCl/ml)

3. Continuous WM WA Principal Gamma 5x10-7 Release

• Emmitters*

Essential 1-131 1x10*

Service Water, Reactor Containment Dissolved and Entrained Fan Cooler Gases (Gamma Emitters) 1x10 4 (RCFC)

Outlet Line H-3 1x10 4 O

l i

l O l 12-19 i

i j

l I

BYRON Rivilion 1.2 August 1994 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is definod, for purposes of these specifications, as the smallest concentration of radioactive materialin 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:

LLD = 4.66 s.

E V 2.22 x 108 Y exp (-Aat)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E= the counting efficiency (counts per disintegration),

V= the sample size (units of mass or volume),

2.22 x 10' = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable, A= the radioactivo decay constant for the particular radionuclide (see "),

and at = the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

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

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

(3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also La analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 12.6.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974, 12-20

BYRON Rsvizion 1.2 August 1994

[ TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(7) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater than 1x104 pCi/ml above background at any time during the week.

O O

12-21

BYRON RGvicion 1.2 August 1994 12.3.2 Dose 9,

Operability Reauirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

2. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

Apolicability: At all times.

Action:

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reauirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.3.2.C This section is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements imp;ement the guidos set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix i be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

12-22

BYRON R:vilion 1.2 August 1994 O

V 12.3.2 Dose (Continued) ,

l Bases '

This section applies to the release of radioactive materials in liquid effluents from each reactor at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Rodwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems I are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

l G l l

l 1

Io 12-23

BYRON R: vision 1.2 August 1994 12.3.3 Liauid Radwaste Treatment System Operability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

Apolicability: At all times.

Action:

1. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE ,

status, and

c. Summary description of action (s) taken to prevent a recurrence. j Surveillance Reauirements j 12.3.3.1.8 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and I parameters in the ODCM when the Liquid Radwaste Treatment System is not being J fully utilized. 1 1

12.3.3.2.B The installed Uquid Radwaste Treatment System shall be considered OPERABLE by  ;

meeting Sections 12.3.1.A and 12.3.2.A.

Bases 12.3.3.B The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system )

will be available for use whenever liquid effluents require treatment prior to release to j the environment. The requirement that the appropriate portions of this system be used  :

when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This section implements the i requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR  !

Part 50 and the design objective given in Section ll.D of Appendix I to 10 CFR Part 50.

O; 12-24 i

l BYRON . R: vision 1.2 August 1994 f3 b 12.3.3 Liould Radwaste Treatment System (Continued)

Bases The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.

This section applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or,if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O 1

l l

r '

12-25

BYRON Rsvision 1.2 August 1994 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operability Recuirements ,,

12.4.1.A The dose rate due to radioac9e materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. For noble gases: less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and

2. For lodine-131, lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to a dose rate of 1500 mrem /yr to any organ.

Acolicability: At all times.

Action:

1. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

Surveillance Reauirements 12.4.1.1.8 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

9 12.4.1.2.B The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate l form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of RETS. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY rpecified in 10 CFR 20.1301.

l 12-26

BYRON R:vi: ion 1.2 August 1994 12.4 GASEOUS EFFLUENTS

[G]

Bases For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to a dose rate of 500 mrem / year to the whole body or to less than or equal to a dose rate of 3000 mrem / year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrems/ year. j This section applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Umits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Interpretations 12.4.1.D This Technical Standard requires sampling and analysis following a power change exceeding 15% of Rated Thermal Power within a 1 - hour period. The laterpretation of this requirement for power changes is as follows:

a) Samples are required to be pulled within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the power transient.

b) If there are several power transients that exceed 15% RATED THERMAL POWER per hour, sampling need only be performed after the lagt transient but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the first transient that exceed 15% of RATED THERMAL POWER.

In all cases, sample analysis shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the start of the initial transient.

l 12-27

BYRON Revision 1.2 August 1994 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MIN! MUM TYPE OF LOWER LIMIT OF SAMPLING ANALYSIS ACTIVITY ANALYSIS DETECTION (LLD)W GASEOUS RELEASE TYPE FREQUENCY FREQUENCY (pCi/cc)

P P

1. Waste Gas Decay Each Tank Each Tank Principal Gamma Emitters

• 1x10 d Tcnk Grab Sample

2. Containment Purge P P Each Purge A d

Each Purge" Principal Gamma Emitters" 1x10 Grab Sample H-3 1x10-'

3. Auxiliary Eidg. M"* M Principal Gamma Emitters A 1x10' Vent Stack Grab Sample 3 H-3 1x10 (Unit 1 and 2)

Continuous" # l-131 1x10 42 Charcoal Sample .,,

Continuous" WM Principal Gamma Emmitters*

Particulate Sample 1x10~"

Continuous" M Gross Alpha Composite 1x10~"

Particulate Sample Continuous" Q Sr-89, Sr-99 Composite 1x10-"

Particulate Sample Continuous N.A. Notwo Gases: Gross Beta or Noble Gas Monitor Gamma 1x10*

e O e

BYRON Rr,visi n 1.2 August 1994 m

(*) TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive materialin 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:

LLD = 4.66 s.

E V 2.22 x 10' Y . exp (-Aat)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E= the counting efficiency (counts per disintegration),

V= the sample size (units of mass or volume),

J 2.22 x 10' = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (sec '),

and at = the elasped time between the midpoint of sample collection and the time of counting (sec).

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

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

(2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section O 12.6.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

12-29

BYRON R villon1.2 {

August 1994 TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canalis flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuelis in the spent fuel pool.

(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 12.4.1.A,12.4.2.A and 12.4.3.A.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

I

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BYRON Revhion 1.2 August 1994 t

i 12.4.2 Dose - Noble Gases Operability Reauirements _

i 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

2. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

A, pp:icability: At all times.

0 8.C10.Q:

1. With the calculated air dose from radioactive noble gases in gaseous effluents i exceeding any of the above limits, prepare and submit to the Commissica within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reauirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and the current calendar year for noble gases shall be determined in accordance with the rnethodology and parameters in the ODCM at least once per 31 days.

Bases 12.4.2.C This section is provided to implement the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.8 of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin gaseous effluents at or beyond the Site Boundary will be kept "as low as is reasonable achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. ,

1 A

U 12-31

BYRON Roviolon 1.2 August 1994 12.4.2 Qose - Noble Gases (Continued)

Bases The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive materials in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,

Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for deterrnining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. l This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equall'/ to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O 12-32

BYRON R vision 1.2

. August 1994 V 12.4.3 Dose -lodine 1-131. lodine-133. Tritium. and Radioactive Materialin Particulate Form l

ODerability Reauirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Byron l Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

2. During any calendar year: Less than or equal to 15 mrems to any organ.

Apolicability: At all times.

Action:

1. With the calculated dose from the release of lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days,in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will I be in compliance with the above limits.

Surveillance Reauirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year for lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days Bases 12.4.3.C This section is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin gaseous effluents at or beyond the Site Boundary will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

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BYRON Reviolon 1.2 August 1994 -

1 12.4.3 Qgag (Continued)  !

Bases i The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology  !

provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix l* Revision 1, October 1977 and Regulatory Guide 1.111, " Methods ,

for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determiaing the actual doses based upon the historical average j atmospheric conditions. The release rate specifications for lodine-131, lodine-133, l l tritium, and radionuclides in particulate form with half-lives greater than 8 days are l dependent upon the existing radionuclide pathways to man, in the areas at and beyond l the SITE BOUNDARY. The pathways that were examined in the development of these l l calculations were: (1)individualirhalation of airbome radionuclides, (2) deposition of <

radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animars graze I with consumpilon of the milk and meat by man, and (4) deposition on the ground with I subsequent exposure to man.  !

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more  !

than one unit on a site, the wastes from all units are mixed for shared treatment; by  !

such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An l estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or,if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

1 0

12-34

BYRON Rtvision 1.2 August 1994 12.4.4 Gaseous Radwaste Treatment System

{ Nf Operability Reauirements 12.4.4. A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to rug:ce releases of rs.Jioactivity when the projected doses in 31 days due to gaseous eft.uent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Byron Station ODCM Anner, Appendix F, Figure F-1) would exceed: l

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta raoiation, or l

3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

i Applicability: At all times.

Action:

1. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30  !

days, pursuant to Technical Specification 6.9.2, a Special Report that includes i the following information:

c a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability, l

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

Surveillance Reauirements l

12.4.4.1.8 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the l methodology and parameters in the ODCM when Gaseous Radwaste Treatrnent Systems are not being fully utilized.

12.4.4.2.B The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and 12.4.2 or 12.4.3.

Bases 12.4.4.1.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

O 12-35

BYRON R:visl:n 1.2 August 1994 12.4.4 Gaseous Radwaste Treatment System (Continued)

Bases The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Caiterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section li.D of Appendix I to 10 CFR Part 50. i The specified limits governing the usc of appropriate portions of the Gaseous Radwaste I Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more  ;

than one unit on a site, the wastes from all units are mixed for shared treatment; by i such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste pioducing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

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BYRON Rsvhion 1.2 ,

August 1994 )

p)

( 12.4.5 Total Dose Operability Reauirements 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Applicability: At all times.

Action:

1. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2,12.4.2, or 12.4.3, calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shallinclude an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, N for the calendar year that inciudes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shaji include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

Surveillance Recuirements 12.4.5.1.B Cumulativo dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2,12.4.2, and 12.4.3, and in accordance with the '

methodology and parameters in the ODCM.

12.4.5.2.B Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5.

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12-37 )

i I

1

BYRON Revision 1.2 August 1994 12.4.5 Total Dose (Continued)

Bases 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Section requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage I tanks are kept small. The Special Report will describe a course of acwon that should l result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the I 40 CFR Part 190 limits. For the purposes of the Special Report,it may be assumed j that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel j cycle sources is negligible, with the exception thd dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If j the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of l 40 CFR Part 190, the Special Report with a request for a variance (provided the release i conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff l action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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BYRON R: vision 1.2 August 1994

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( 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorina Proaram Operability Reauirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Acolicability: At all times.

Action:

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampiing medium, this report shall be submitted if:

concentration (1) . concentration (2) + .11.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5-2 are detected and are the resuit of plant effluents, this report shall be submitted if the potential annual dose

• to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

• The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

O 12-39

BYRON R; vision 1.2 August 1994 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

3. With the milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 12.5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Submit controlled version of the ODCM.within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.

Surveillance Reauirements 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by tru section provides representative measurements of radiation and of radioactive materials m ti ose exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the stadon operation.

This monitoring program implements Section IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories.

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

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.

40 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

O 12-40

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.l BYRON Rsvision 1.2 l August 1994  :

i l

12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interotetations

- 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply I downstream of the plant within 10 kilometers." Drinking water supply is defined as ,

water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

No community downstream of the plant within 10 kilometers uses a drinking water supply. Therefore, sampling is not required. However, the affected communities water' sources will be annually verified to assure that the source has not changed. i t

4 i

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b 12-41

BYRON Revision 1.2 August 1994 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONSM COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation 2 Forty routine monitoring stations Quarterly. Gamma dose quarterfy.

either with two or more dosimeters or with one instrument for measuring and recording dose rate cor.tinuously, placed as follows:

An inner ring of stations, one in each meteontogical sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6- to 8- km range from the site; and The balance of the stations to be placed in specialinterest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

G 6 - - - - -

9 - --

O O O BYRON Revision 1.2 August 1994 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONSm COLLECTION FREQUENCY OF ANALYSIS

2. Airbome Radioiodine and Samples from five locations: Continuous sampler Radiciodine Canister.

Particulates operation with sample 1-131 analysis weekly.

Three samples from close to the collection weekly, or three SITE BOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sampler highest calculated annual average loading. Gross beta radioactivity ground level D/Q; analysis following filter change;" and One sample from the vicinity of gamma isotopic analysis W a community having the highest of composite (by location) calculated annual average ground- quartetty.

level D/Q; and One sample from a control location, as for example 10 to 30 km distant and in the least prevalent wind direction.

3. Waterbome

a. Surface" One sample upstream. Composite sample over Gamma isotopic analysis" One sample downstream. 1-month period by monthly. Composite for weekly grab samples. tritium analysis quarterly,

b. Ground Samples from one or two sources Quarterly. Gamma isotopic" and only if likely to be affected W . tritium analysis quarterly.

12-43

BYRON Revision 1.2 August 1994 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS 9 COLLECTION FREQUENCY OF ANALYSIS

3. Waterborne (Continued)

c. Drinking One sample of each community Composite sample over 1-131 analysis on each drinking water supply within 2-week period" when composite when the dose 10 km downstream of the 1-131 analysis is calculated for the discharge. performed, monthly consumption of the water composite otherwise. is greater than 1 mrem per One sample from a control year.(8) Composite for gross location. beta and gamma isotopic analyses (4) monthly.

Composite for tritium analysis quarterly.

d. Sediment One sample from downstream area Semiannually. Gamma isotopic analysis" from shoreline with existing or potential semiannual!y.

recreational value.

4. Ingestion

a. Milk Samples from milking animals Semimonthly when Gamma isotopicW and 1-131 in three locations within animals are on analysis semimonthly when 5 km distance having the highest pasture, monthly at animals are on pasture; dose potential. If there are other times. monthly at other times.

none, then, one sample from milking animale in each of three areas between $ 'o 8 km distant where doses are ca.'culated to be greater than 1 mrerr per yr".

One sample from milking animals at a controllocation,15 to 30 km distant and in the least prevalent wind direction.

e 6 e-

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%J BYRON Revision 1:2 August 1994 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONSW COLLECTION FREQUENCY OF ANALYSIS

4. Ingestion (continued)

b. Fish and Representative samples of Three times per year Gamma isotopic anaysisW Invertebrates commercia!!y and recreationally (spring, summer and on edible portions.

important species in vicinity fall).

of plant discharge area.

Representative samples of commercially and recreationally important species in areas not influenced by plant discharge.

c. Food Products Representative samples of the At the time of Gamma isotopic analysisW principal classes of food products harvestW on edible portion.

from any area within 10 miles of the p' ant that is irrigated by water in which liquid plant wastes have been discharged.

Samples of three different kinds Monthly when Gamma isotopic W and 1-131 of broad leaf vegetation grown available. analysis.

nearest each of two different offsite locations of highest predicted annual average ground-level D/O if milk sampling is not performed.

One sample of each of the similar Monthly when Gamma isotopicWand 1-131 broad leaf vegetation grawn 15 to available. analysis.

30 km distant in the least prevalent wind direction if milk sampling is not performed.

12-45

BYRON R:visi:n 1.2 August 1994 TABLE 1251 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in Table 12.5-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133,

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiologico! Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampi;cg schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailabihty, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and allocations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Submit controlled revisions of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and I recording dose rate continuously may be used in place of, or in addition to, integrating i dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is I

considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dos! meters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographicallimitations; e.g.,

at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(3) Airborne particulate sample filters sha!! be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(5) The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone.

I I l .

12-46

BYRON' Rtvision 1.2 August 1994 e

TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS 1 (6) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling i employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g.,

hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

l (7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation t purposes in areas where the hydraulic gradient or recharge properties are suitable for ,

contamination.

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(9) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. >

?

1

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12-47 l

l

BYRON Revision 1.2 August 1994 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS l WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/t) OR GASES (pCi/m') (pCi/kg, wet) (pCi/t) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 '30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 l

• For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/t may be used.

la e 6" e

,n. , -- y ,

I a t \

U N Revision 1.2 August 1994 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS")

LOWER LIMIT OF DETECTION (LLD)*

WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SED! MENT ANALYSIS (pCi/() OR GASES (pCi/m') (pCi/kg, wet) (pCi/() (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000*

han-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 l-131 1 W 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

• lf no drinking water pathway exists, a value of 3000 pCi/t may be used.

12-49

BYRON R:villon 1.2 ,

August 1994 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISU)

TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1.

(2) Required detection capabilities for thermoluminescent dosimeters used for environment measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive materialin 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:

LLD = 4.66 S.

E V 2.22 Y exp (-lat)

Where:

LLD = the "a priori" lower limit of detection (picoCuries per unit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E= the counting efficiency (counts per disintegration),

V= the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y= the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (see d), and at = the elasped time between sample collection, or end of the sample collection period, and the time of counting (sec).

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

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

12-50

BYRON RIvillon 1.2 August 1994 A

( TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 0)

TABLE NOTATIONS (3) con 1d Analyses shall be perfonned in such a manner that the stated LLDs will be {

achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may rendor these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1.

(4) LLD for drinking water samples. If no drinking water pathway exists, the LLD of ,

gamma isotopic analysis may be used. I

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12-51

BYRON Revicion 1.2 August 1994 12.5.2 Land Use Census Operability Reauirements 12.5.2.A. A Land Use Census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, and the nearest residence. For dose calculation, a garden will be assumed at the nearest residence.

Acolicability: At all times.

Action:

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Section 12.4.3, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Section 12.6.1.

2. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Section 12.6.1, submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

Surveillance Reauirements 12.5.2.B The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1.

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM j are made if required by the results of this census. The best information from the I door-toajoor survey, from aerial survey, or from consulting with local agricultural authorities shall be used, This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part i I

50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations. l 12-52

BYRON ~R: vision 1.2 August 1994 O,

i ,

12.5.3 Interlaboratory Comoarison Procram Operabi!ity Reauirements 12.5.3.A Analyses shall be performed on radioactive materials, supplied as part of an interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 12.5-1.

Apolicability: At all times.

Action:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1.

Surveillance Reauirements 12.5.3.B The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1.

Bases p 12.5.3.C The requirement for participation in an approved Interlaboratory Comparison Program is h provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental samples 0 matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix l to 10 CFR Part 50.

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12-53 i

BYRON R:vliion 1.2 ,

August 1994 .

12.6 REPORTING REQUIREMENTS  ;

1 12.6.1 Annual Radioloaical Environmental Operatina Report

• Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Report shallinclude summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Section 12.5.2.

The Annual Radiological Environmental Operating Report shallinclude the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted i noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.  !

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps" covering all sampling locations keyed to a table giving distances and directions from the midpoint between the i reactors; the results of licensee participation in the Interlaboratory Comparison Program  !

and the corrective actions being taken if the specified program is not being performed )

as required by Section 12.5.3; reasons for not conducting the Radiological '

Environmental Monitoring Program as required by Section 12.5.1, and discussion of all deviations from the sampling schedule of Table 12.5-1; discussion of environmental ,

sample measurements that exceed the reporting levels of Table 12.5-2 but are not the  ;

result of plant effluents, pursuant to Section 12.5-1; and discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable. l l

l l

• A single submittal may be made for a multiple unit station.

l "One map may cover locations near the SITE BOUNDARY; a second may include the )

more distant locations. l O

12-5t

BYRON R; vision 1.2

. August 1994 O

kl 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.1 Annual Radioloalcal Environmental Operatina Report (Cont'd)

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in ths form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shallinclude an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This same report shall also 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 (see Byron Station ODCM Annex, Appendix F, Figure F-1) during the report period. All assumptions used in {

making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM.

The Annual Radiological Environmental Operating Report to be submitted prior to May 1 of each year shall also include an assessment of radiation doses to the most likely p exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190,

" Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1. October 1977.

In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

O G

12-55

BYRON ' Revision 1.2 )

August 1994 l 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.2 Annual' Radioactive Effluent Release Report" Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted prior to April 12 of the l following year. The period of the first report shall begin with the date of initial criticality, l

The Annual Radioactive Effluent Release Reports shallinclude a summary of the i quantities of radioactive liquid and gaseous effluents and solid waste released from the l unit as outlined in Regulatory Guide 1.21, " Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

l l

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three j additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of l container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g, cement, urea formaldehyde).

l The Annual Radioactive Effluent Release Reports shallinclude a list and description of I unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in l gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Reports shallinclude any changes made during the reporting period to the PCP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3.

The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Sect;on 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

' Semlannual Radiological Effluent Release Reports are required until the frequency change to annualis approved by the NRC in the Byron Technical Specifications.

Semiannual Radiological Effluent Release Reporting is required within 60 days after January 1 and June 1 of each year.

O 12-56

BYRON R:vizion 1.2

, August 1994 1

iO

'd 12.6.3 .Offsite Dose Calculation Manual (ODCM) l l 12.6.3.1 The ODCM shall be approved by the Commission prior to implementation.

12.6.3.2 Licensee-initiated changes to the ODCM:

I a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s); and f 2. A determination that the change will maintain the level of radioactive l l- effluent control required by 10 CFR 20,106,40 CFR Part 190,10 CFR i 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the f accuracy or reliability of effluent, dose, or setpoint calculations.

l l b. Shall become effective after review and acceptance by the Onsite Review and I investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.

c. Shall be submitted to the Commission in the form of the complete, legible copy of the entire ODCM as a part of or concurrent with the Annual' Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall v indicate the date (e.g., month / year) the change was implemented.

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12-57

BYRON Rcvision 1.2 August 1994 ,

12.6.4 Maior Chanaes to Liauid and Gaseous Radwaste Treatment Systems *"

Ucensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual' Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Onsite Review and investigative Function. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change cou'd be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplementalinformation;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the Ucense application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBUC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the Ucense application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found ,

acceptable by the Onsite Review and Investigative Function.

l

b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function. I 1

• " Ucensees may choose to submit the information called for in this standard as part of l the annual FSAR update.

O 12-58

, 'GYRON Rsvision 1.2 August 1994 f)

A_/

BYRON ANNEX INDEX:

PAGE REVISION ' PAGE REVISION -

APPENDlX F-F-l 1.2 F-43 1.2 O F-il 1.2 F-44 .1.2 I-F-iii 1.2 F-45 1.2 -

I- F-iv 1.2 F-46 1.2 F-1 1.2 F-47 1.2 F-2' 1.2 F-3 1.2 F-4 1.2 F-5 1.2 F-6 1.2 F-7 1.2 F-8 1.2 F-9 1.2 F-10 1.2 F-11 ' 1.2 F-12 1.2 F-13 1.2 F-14 1.2 F-15 1.2 F-16 1.2 F-17 1.2 O_ F-18 1.2 F-19 1.2 F-20 1.2 F-21 1.2 F-22 1.2 i F-23 1.2 l F-24 1.2 F-25 1.2 F-26 1.2 F 1.2 F-28 1.2 F-29 1.2 F-30 1.2 F-31 1.2 F-32 1.2 F-33 1.2 F-34 1.2 F-35 1.2

~F-36 1.2 F-37 1.2 F-38 1.2 t- F-39 1.2

!= F-40 1.2 F-41 1.2 j--

F-42 1.2 F-i

e BYRON Revision 1.2 August 1994 ,

APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 O

O F-li

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

BYRON Ravition 1.2 August 1994 APPENDIX F UST OF TABLES ,

NUMBER TITLE PAGE F Aquatic Environmental Dose Parameters F-2  :

F-2 Station Characteristics .

F-4 F-3 Critical Ranges F-5 F-4 Average Wind Speeds F-6 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-7 F-Sa X/Q and D/Q Maxima At or Beyond the .;'

Restricted Area Boundary F-8 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-9 F-7 Maximum Offsite Finite Plume Gamma Dose Factors i Based on 1 cm Depth at the Unrestricted Area  ;

Boundary for Selected Nuclides F-10

(

F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F-25 Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries - 250 and 30 Foot Elevation Data F-40

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distribution Table Summaries F-44

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed '

-Summary Table of Percent by Speed and Class F-iii

BYRON Rsvillon 1.2 August 1994 ,

APPENDIX F UST OF FIGURES NUMBER ET_LE PAGE F-1 Unrestricted Area Boundary F-46 F-2 Restricted Area Boundary F-47 O

l O

F-iv

)

BYRON Rsvision 1.2 4 August 1994 APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the Byron site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment.

F.2 REFERENCES

1. Sargent & Lundy, Analysis and Technology Division Byron Calculation No. ATD-0150,

' g Revisions 0 and 1.

2. " Irrigation from the Rock River" letter from G.P. Lahti (Sargent & Lundy) to J.C. Golden (NSEP), June 4,1990.

3. " Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation,1988.

4. " Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group,1992.

l l

l 0 ,

F-1 1

L_____________.____.______.____________________________________.__.___ . ,,

CYRON R: vision 1.2 August 1994 ,

Table F-1 Aquatic Environmental Dose Parameters General Information' There are no public potable water intakes on the Rock River downstream of the station.

There is no irrigation occurring on the Rock River downstream of the. station.

Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing.

According to Section 2.4.1.2 and Figure 2.4-5 of the Byron Environmental Report, there are four downstream dams on the Rock River within approximately 50 miles of the station one at Oregon, Dixon, and two at Sterling.

Water and Fish inaestion Parameters Parameter

• Value i

1/M*,1/M' 1.0 F*,cfs 6.55E4 F', cfs 6.25E3 t', hr* 24.0 t*, hrd 115 Limits on Radioactivity in Unprotected Outdoor Tanks' Outside Temporary Tank 5 10 Ci' (per Technical Specification 3.11)

• This is based on information in the Byron Environmental Report, Figure 3.3-1 and Section 2.1.3.2.1.

• The parameters are defined in Section A.2.1 of Appendix A.

• t' (hr) = 24 hr (all stations) for the fish ingestion pathway F-2 t

I EYRON Rsvizion 1.2. ,

August 1994 i

I

( Table F-1 (CorWd)

Aquatic Envronmental Dose Parameters Notes (Cont'd):

t"(br) = 115 hr (Rock River flows into Mississippi River about 115 miles downstream of the -

station at the rate of 1' mph based on the data in Table 2.2-5 of the Byron Station j Environmental Report).

l See Section A.2.4 of Appendix A. l

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

t i

+

6 t

J f

i

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F-3 )

BYRON R: vision 1.2 August 1994 Table F-2 Station Characteristics STATION: Byron LOCATION: 3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not applicable (NA)

1) Release Height = _m 2) Diameter = m

3) Exit Speed = __ms 4) Heat Content = KCal S'

CHARACTERISTICS OF VENT STACK RELEASE POINTS *

1) Release Height = 60.66 m' 2) Effective Diameter = 2.80 m

3) Exit Speed = 13.00 ms

• The station has two adjacent rectangular vent stack release points of the same height and cross section. Their centers are 15.01 m apart.

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m

2) Building Factor (D) = 60.6 m' METEOROLOGICAL DATA A 250 ft Tower is located 1036 m SW of vent stack release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA)

Vent 250M 250 - 30 M Ground 30 M 250 - 30 M

'Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.

O F-4

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BYRON Rsvision 1.2 August 1994  !

1

.'(' Table F-3 Criticai Ranges Unrestricted Area . Restricted Nearest Nearest Dairy Farm Boundary * -. Area Boundary Resident" Within 5 Miles' i Direction . (m) (m) (m)  !

N 1875 777 4300 None ,

NNE 1829 538 1600 None.

NE .1585 528 1900 3000 ,

ENE 1234 474 2100 None

-E 1227 468 .2100 None ESE 991 480 2300 None l SE 1006 427 1200 None SSE 800 410 1000 None S 945 295 800 None SSW 975 299 1000 None ,

SW 1067 451 1200 None  !

WSW 1212 386 2700 None t VV 1189 379 2700 8000 WNW 1227 385 1200 5300

- O- NVV 1128' 445 1600 4800 NNW 1044 658 2100 None  ;

'See Updated Final Safety Analysis Report Table 2.1-1a and Environmental Report. 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. i

• 1993 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the l '

nearest conservative 100 maters.

I

• 1993 annual milch animal census, by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.

O F-5

BYRON Rrvision 1.2 August 1994 Table F-4 Average Wind Speeds Averaae Wind Speed (m/sec)*

Downwind Direction Elevated

• Mixed Mode Ground Level" N 7.9 6.3 4.2 NNE 7.6 6.3 4.5 NE 6.8 5.8 4.1 ENE 6.6 5.6 4.0 E 6.9 5.9 4.5 ESE 6.9 5.9 4.5 SE 6.5 5.7 4.0 SSE 6.2 5.4 3.7 S 6.3 5.4 4.0 SSW 6.0 5.3 3.9 SW 6.1 5.4 4.2 WSW 6.4 5.6 4.1 W 6.8 5.5 3.4 WNW 7.1 5.7 3.7 l

NW 7.1 5.7 3.8 NNW 7.7 6.0 4.1

• Based on Byron site meteorological data, January 1978 through December 1987. Calculated in Reference 2 of Section F.2 using formulas in Section B.1.3 of Appendix B.

"The elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values.

O F-6

. g BYRON

~

Revision 1.2 August 1994 Table F-5 XIQ and DlQ Maxima at or Beyond the Unrestncted Area Boundary b

Downwind Mixed Mode (Vent) Release Ground Level Release Ofrection Radius x/Q Radius D/Q Radium x/0 0/Q (meters) (sec/m**3) (meters) (1/m**2) (meters) (sec/m**3) (1/m**2)

N 1875. 1.988E-07 1875. 1.983E-09 1875. 8.676E-07 4.671E-09 NNE 1829. 1.677E-07 1829. 1.927E-09 1829. 7.531E-07 4.271E-09 NE 1585. 1.530E-07 1585. 1.821E-09 1585. 7.876E-07 4.388E-09 ENE 1234. 1.353E-07 1234. 1.764E-09 1234. 8.808E-07 5.036E 09 .

E 1227. 1.688E-07 1227. 2.335E-09 1227. 1.143E-06 6.226E-09 i ESE 991. 2.519E-07 991. 3.540E-09 991. 1.692E-06 9.8%E-09 SE 1006. 3.020E-07 1006. 3.578E-09 1006. 2.480E-06 1.118E-08 SSE 800. 4.497E-07 800. 3.761E-09 800. 4.152E-06 1.420E-08 S 945. 2.249E-07 945. 2.792E-09 945. 1.946E-06 9.364E-09 SSW 9 75. 1.476E-07 975. 1.970E-09 975. 1.305E-06 6.672E-09 SW 1067. 1.148E-07 1067. 1.786E-09 1067. 9.279E-07 5.316E-09 WSW 1212. 1.199E-07 1212. 1.903E-09 1212. 7.646E-07 5.002E-09 W 1189. .1.758E-07 1189. 1.870E-09 1189. 9.348E-07 5.330E-09 WNW 1227, 1.205E-07 1227. 1.292E-09 1227. 6.543E-07 3.745E-09 NW 1128. 1.686E-07 1128. 1.719E-09 1128. 8.807E-07 4.984E-09 NNW 1044. 3.047E-07 1044. 3.223E-09 1044. 1.432E-06 8.871E-09  ;

Byron Site Meteorological Data 1/78 - 12/87 l

Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

X/Q is used for beta skin, and inhalation dose pathways. See Sections A.1.2, A.1.3, and A.1.4.2 of Apprendix A.

I D/Q is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/Q at or beyond the unrestricted area boundary (UAB).

F-7'

BYRON Revision 1.2 August 1994 Table F-Sa X/Q and DIQ Maxima at or Beyond the Restncted Area Boundary Downwind Mixed Mode (Vent) Release Gromd Level Release Direction Radius X/Q Radius D/Q Radius X/Q D/Q (meters) (sec/m*=3) (meters) (1/m**2) (meters) (sec/m**3) (1/m**2)

N 777. 6.357E-07 777. 7.004E-09 777. 3.290E-06 2.036E-08 NNE 538. 8.778E-07 538, 1.046E-08 538. 5.086E-06 3.193E-08 NE 528. 6.803E-07 528. 7.792E-09 528. 4.371E-06 2.646E-08 ENE 474. 5.341E-07 4 74. 5.947E-09 4 74. 4.014E-06 2.346E-08 E 468. 6.698E-07 468. 7.930E-09 468. 5.359E-06 2.930E-08 ESE 480. 7.377E-07 480. 8.963E-09 480. 5.434E-06 3.144E-08 SE 427. 1.126E-06 427. 1.063E-08 427. 1.024E-05 4.352E-08 SSE 410. 1.349E-06 410. 8.744E-09 410. 1.305E-05 4.044E-08 5 295. 1.441E-06 295. 1.171E-08 295. 1.391E-05 5.707E-08 SSW 299. 9.382E-07 299. 8.293E-09 299. 9.376E-06 4.197E-08 SW 451. 3.949E-07 451. 5.065E-09 451. 3.666E-06 2.095E-08 Wsw 386. 6.098E 07 386. 7.425E-09 386. 4.699E-06 3.088E-08 W 379. 1.041E-06 379. 8.116E-09 379. 6.009E-06 3.275E-08 WNW 385. 7.454E-07 385. 6.081E-09 385. 4.382E-06 2.370E-08 NW 445. 7.394E-07 445. 6.117E-09 445. 4.068E-06 2.198E-08 NNW 658. 6.123E-07 658. 6.177E-09 658. 2.980E-06 1.874E-08 Byron Site Meteorological Date 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

l l

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode

data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/Q at or beyond the restricted area boundary (RAB).

BYRON Revision 1.2 August 1994 .

Table F-6 DIQ at the Nearest MiBc Cow and Meat Animal Locations within 5 miles .

-l Downwind Nearest Milk Cow D/Q(1/m**2) Nearest Meat Animal D/Q(1/m**2)

Direction Radius Mixed Ground Radius Mixed Ground (meters) Release Release (meters) Release Release 4

N 8000. 1.895E-10 3.643E-10 4800. 4.499E-10 9.079E-10 NNE 8000. 1.835E-10 3.192E-10 2400. 1.282E-09 2.677E-09 NE 3000. 7.187E-10 1.462E-09 5500. 2.799E-10 5.027E-10 ENE 8000. 1.096E-10 1.928E-10 3700. 3.792E-10 7.603E-10 E 8000. 1.417E-10 2.361E-10 3600. 5.164E-10 9.770E-10 ESE 8000. 1.614E-10 2.635E-10 2400. 1.082E-09 2.209E-09 SE 8000. 1.698E-10 3.050E-10 2700. 9.439E-10 2.085E-09 ssE 8000. 1.387E-10 2.664E-10 5600. ~2.515E-10 5.049E 10 s 8000. 1.290E-10 2.305E-10 1000. 2.603E-09 8.531E-09 ssW 8000. 9.795E-11 1.729E-10 4800. 2.253E-10 4.309E-10 SW 8000. 9.554E-11 1.596E-10 6000. 1.545E-10 2.674E-10 .

Wsw 8000. 1.202E-10 1.858E-10 2700. 6.571E-10 1.270E-09 W 8000. 1.055E-10 1.916E-10 2700. 5.945E-10 1.310E-09 ,

WNW 5300. 1.464E-10 2.968E-10 5300. 1.464E-10 2.968E-10 NW 4800. 1.978E-10 4.088E-10 6400. 1.233E-10 2.448E*10 ,

NNW 8000. .1.349E-10 2.571E-10 -6400. 1.979E 10 3.837E-10 Byron site Meteorological Data 1/78 - 12/87 I

t Note: Based on Reference 2 in Section F.2 and the formulas in Section B.4 of Appendix B.

Approximate distance from the station as determined by annual census. ,

The ground level release data are provided for reference purposes only.

Routine dose calculations are performed using mixed rnode release data.

F _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . - _ _ . _ _ _ _ _ - - . . _ _ _ _ _ _ . _ _ . . _ _ _ _ _

BYRON Revision 1.2 August 1994 Table F-7 Max' mum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-33m l

Downwind unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR i

(meters) (meters) (mrad /yr)/(uci/sec) (meters) (arad/yr)/(uci/sec) {

{

N 1875. 1875. 2.330E-05 1.757E-05 1875. 9.565E-05 7.212E-05 NME 1829. 1829. 1.937E-05 1.460E-05 1829. 8.084E-05 6.095E-05 NE 1585. 1585. 1.773E 05 1.336E-05 1585. 8.469E-05 6.386E-05 ENE 1234 1234 1.672E-05 1.260E-05 1234 1.002E-04 7.555E-05 E 1227. 1227. 2.049E-05 1.545E-05 1227. 1.252E-04 9.441E-05 ESE 991. 991. 3.142E-05 2.369E-05 991. 1.925E-04 1.451E-04 SE 1006. 1006. 3.694E-05 2.785E-05 1006. 2.683E-04 2.023E-04 SSE 800. 800. 5.135E-05 3.872E-05 800. 4.267E-04 3.217E-04 S 945. 945. 2.723E-05 2.053E-05 945. 2.121E-04 1.600E-04 SSW 975. 975. 1.795E-05 1.353E-05 975. 1.407E-04 1.061E-04 SW 1067. 1067. 1.379E-05 1.040E-05 1067. 9.817E-05 7.402E-05 WSW 1212. 1212. 1.483E-05 1.118E-05 1212. 8.590E-05 6.477E-05 W 1189 1189. 2.193E-05 1.654E-05 1189. 1.100E-04 8.293E-05 WNW 1227. 1227. 1.514E-05 1.141E-05 1227. 7.802E-05 5.883E-05 NW 1128. 1128. 2.112E-05 1.593E-05 1128, 1.033E-04 7.789E-05 NNV 1044 1044. 3.852E-05 2.904E-05 1044, 1.691E-04 1.275E-04 Byron Site Meteorologicat Data 1/78 - 12/87 i

l Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

Approximate distance from midpoint between gasous effluent release points.

I e 5 e .

BYRON Reymon 1.2,

' August 1994

+

l Table F-7 (Contmued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-85m -

i i

Dowwind unrestricted Mixed Mode (Vent) Release Grotrid Level Release Direction Area Bound Radius V VSAR Radius G GBAR (meters) (meters) (mrad /yr)/(UCi/sec) (meters) (arad/yr)/(uti/sec)

N 1875. 1875. 2.177E-04 2.094E-04 1875. 6.403E-04 6.143E-04 NNE 1829 1829. 2.076E-04 1.999E-04 1829. 5.544E-04 5.319E NE 1585. 1585. 2.022E-04 1.947E-04 1585. 5.773E-04 5.539E-04 ENE 1234. 1234. 1.984E-04 1.911E-04 1234. 6.395E-04 6.133E-04 E 1227. 1227. 2.331E-04 2.245E-04 1227. 7.968E-04 7.640E !

ESE 991. 991. 3.260E-04 3.138E-04 991. 1.136E-03 1.088E-03 SE 1006. 1006. 3.710E-04 3.571E-04 10%. 1.584E-03 1.517E SSE 800, 800. 4.393E-04 4.223E-04 800. 2.273E-03 2.175E-03 s

S 945. 945. 2.813E-04 2.708E-04 945. 1.240E-03 1.188E-03 SSW '

9 75. 9 75. 2.079E-04 2.002E-04 975. 8.631E-04 8.272E-04.

SW 1067. 1067. 1.688E-04 1.627E-04 1067. 6.286E-04 6.027E-04 WSW 1212. 1212. 1.751E-04 1.687E-04 1212. 5.594E-04 5.366E-04 W 1189. 1189. 2.092E-04 2.013E-04 -1189. 6.723E-04 6.446E-04 WNW 1227. -1227. 1.464E-04 1.409E-04 1227. 4.690E-04 4.496E-04 NW 1128. 1128. 1.926E-04 1.852E-04 1128. 6.017E-04 5.766E-04 kNW 1044. 1044. 3.126E-04 3.005E-04 1044. 9.676E-04 9.272E 04-Byron Site Meteorological Data 1/78 - 12/87 .

4 I .

F-11

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Dourwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCi/sec) (meters) (mrad /yr)/(uCi/sec)

N 1875. 1875. 2.535E-06 2.452E-06 1875. 7.318E-06 7.077E-06 NNE 1829. 1829. 2.469E-06 2.388E-06 1829. 6.382E-06 6.171E-06 NE 1585. 1585. 2.415E-06 2.335E-06 1585. 6.622E-06 6.403E-06 ENE 1234. 1234. 2.367E-06 2.289E-06 1234. 7.225E-06 6.986E-06 E 1227. 1227. 2.787E-06 2.695E-06 1227. 9.101E-06 8.801E-06 ESE 991. 991. 3.828E-06 3.702E-06 991. 1.270E-05 1.228E-05 SE 1006. 1006. 4.364E-06 4.220E-06 1006. 1.803E-05 1.743E-05 SSE 800. 800. 5.153E-06 4.983E-06 800. 2.577E-05 2.492E-05 s 945. 945. 3.321E-06 3.211E-06 945. 1.404E-05 1.358E-05 ssW 975. 975. 2.493E-06 2.411E-06 9 75 . 9.869E-06 9.543E-06 SW 1067. 1067. 2.018E-06 1.951E-06 1067. 7.232E-06 6.993E-06 Wsu 1212. 1212. 2.070E-06 2.002E-06 1212. 6.309E-06 6.100E-06 W 1189. 1189. 2.436E-06 2.356E-06 1189. 7.472E-06 7.225E-06 WNW 1227. 1227. 1.708E-06 1.652E-06 1227. 5.191E-06 5.019E-06 NW 1128. 1128. 2.238E-06 2.164E-06 1128. 6.678E-06 6.458E-06 NNW 1044. 1044. 3.579E-06 3.461E-06 1044. 1.071E-05 1.036E-05 Byron Site Meteorological Data 1/78 - 12/87

^ -

g BYRON Revision 1.2

' August 1994 Table F-7 (Contmued) i Maxenum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Untertncted Area Boundary for Kr-87 Dowwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G G8AR (meters) (meters) (mrad /yr)/(uCf/sec) (meters) (arad/yr)/(uci/sec)

N 1875. 1875. 7.122E-04 6.916E-04 1875. 1.811E-03 1.758E-03 NNE 1829. 1829. 6.891E-04 6.692E-04 1829. 1.555E-03 1.510E-03 NE 1585. 1585. 6.817E-04 6.620E-04 1585. 1.622E-03 1.574E ENE 1234. 1234. 6.838E-04 6.641E-04 1234. 1.822E-03 1.769E-03 E 1227, 1227. 7.930E-04 7.701E-04 1227. 2.214E-03 2.149E-03 ESE 991. 991. 1.126E-03 1.094E-03 991. 3.256E-03 3.162E-03' SE 1006. 1006. 1.264E-03 1.227E-03 1006. 4.356E-03 4.229E-03 SSE 800. 800. 1.455E-03 1.413E-03~ 800. 6.185E-03 6.005E-03 5 945. 945. 9.680E-04 9.401E-04 945, 3.451E-03 3.350E 03 1

SSW 975. 9 75. 7.216E-04 7.008E-04 975 2.374E-03 2.305E-03 SW 1067. 1067. 5.927E-04 5.756E-04 1067. 1.725E-03 1.675E-03 WSW 1212. 1212. 6.132E-04 5.955E-04 1212. 1.613E-03 1.566E-03 W 1189. 1189. 7.081E-04 6.877E-04 1189 1.971E-03 1.914E-03 WNW 1227. 1227. 4.978E-04 4.834E-04 1227. 1.381E-03 1.341E 03 NW 1128. 1128. 6.517E-04 6.329E-04 1128. 1.753E-03 1.702E-03 NNW 1044. 1044. 1.040E-03 1.010E-03 1044, 2.826E-03 2.744E-03 Byron Site Meteorological Data 1/78 - 12/87 F-13

__ . _ _ _ _ - . _ __ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - -

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Dowrwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bomd Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uti/sec) (meters) (mrad /yr)/(uct/sec)

N 1875. 1875. 1.781E-03 1.732E-03 1875. 4.631E-03 4.499E-03 NNE 1829. 1829 1.744E-03 1.696E-03 1829. 4.012E-03 3.898E-03 NE 1585. 1585. 1.725E-03 1.677E-03 1585. 4.174E-03 4.056E-03 ENE 1234. 1234. 1.721E-03 1.674E-03 1234. 4.617E-03 4.485E-03 E 1227. 1227. 2.008E-03 1.952E-03 1227. 5.701E-03 5.538E-03 ESE 991. 991. 2.794E-03 2.717E-03 991. 8.165E-03 7.931E-03 SE 1006. 1006. 3.153E-03 3.066E-03 1006. 1.124E-02 1.092E-02 SSE 800. 800. 3.656E-03 3.554E-03 800. 1.601E-02 1.555E-02 S 945. 945. 2.414E-03 2.348E-03 945. 8.831E-03 8.577E-03 Ssv 975. 975. 1.821E-03 1.771E-03 975. 6.146E-03 5.970E-03 SW 1067. 1067. 1.486E-03 1.445E-03 1067. 4.488E-03 4.360E-03 WSW 1212. 1212. 1.525E-03 1.483E-03 1212. 4.060E-03 3.944E-03 W 1189. 1189. 1.756E-03 1.707E-03 1189. 4.882E-03 4.743E-03 WNW 1227. 1227. 1.235E-03 1.201E-03 1227. 3.406E-03 3.309E-03 NW 1128. 1128. 1.611E-03 1.567E-03 1128, 4.344E-03 4.219E-03 NNW 1044. 1044, 2.548E-03 2.477E-03 1044. 6.974E-03 6.773E-03 Byron Site Meteorological Data 1/78 - 12/87 l

i l

O 9 9

[~s y *

,/~\ . .

t s N.)) V BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-89 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCi/sec) (meters) (mrad /yr)/(uCi/sec)

N 1875. 1875. 3.874E-04 3.764E-04 1875. 5.119E-04 4.972E-04 NNE 1829. 1829. 3.917E-04 3.80SE-04 1829. 4.514E-04 4.384E-C.

NE 1585. 1585. 4.092E-04 3.975E-04 1585. 4.994E-04 4.851E-04 ENE 1234. 1234. 4.909E-04 4.769E-04 1234. 7.066E-04 6.863E-04 E 1227. 1227. 5.876E-04 5.709E-04 1227. 8.980E-04 8.723E-04 ESE 991. 991. 1.001E-03 9.729E-04 991. 1.662E-03 1.614E-03 SE 1006. 1006. 1.052E-03 1.022E-03 1006. 1.834E-03 1.782E-03 SSE 800. 800. 1.274E-03 1.237E-03 800. 2.736E-03 2.657E-03 S 945. 945. 8.388E-04 8.149E-04 945. 1.633E-03 1.586E-03 SSW 975. 975. 6.103E-04 5.929E-04 975. 1.138E-03 1.105E-03 SW 1067. 1067. 4.877E-04 4.738E-04 1067. 8.395E-04 8.154E-04 WSW 1212. 1212. 4.748E 04 4.612E-04 1212. 7.570E-04 7.353E-04 W 1189. 1189. 5.142E-04 4.995E-04 1189. 8.490E-04 8.246E-04 WNW 1227. 1227. 3.590E-04 3.488E-04 1227. 5.905E-04 5.735E-04 NW 1128. 1128. 5.205E-04 5.057E-04 1128. 8.806E-04 8.553E-04 NNW 1044. 1044. 9.408E-04 9.139E-04 1044. 1.738E-03 1.688E-03 Byron Site Meteorological Data 1/78 - 12/87 F-15

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Ganwna Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCi/sec) (meters) (mrad /yr)/(uCi/sec)

N 1875. 1875. 5.729E-06 5.558E-06 1875. 2.499E-06 2.423E-06 NNE 1829. 1829. 6.704E-06 6.504E-06 1829. 3.550E-06 3.443E 06 NE 1585. 1585. 8.897E-06 8.631E-06 1585. 5.093E-06 4.939E-06 ENE 1234. 1234. 2.065E-05 2.004E-05 1234. 1.415E-05 1.372E-05 E 1227. 1227. 3.111E-05 3.018E-05 1227. 2.640E-05 2.560E-05 ESE 991. 991. 8.428E-05 8.175E-05 991. 7.903E-05 7.663E-05 SE 1006. 1006. 7.483E-05 7.259E-05 1006. 6.589E-05 6.389E-05 SSE 800. 800. 1.281E-04 1.242E-04 800. 1.367E-04 1.325E-04 S 945. 945. 6.382E-05 6.191E-05 945. 6.374E-05 6.181E-05 SSW 975. 975. 4.060E-05 3.938E-05 975. 3.621E-05 3.511E-05 SW 1067. 1067. 2.851E-05 2.765E-05 1067. 2.698E-05 2.616E-05 WSW 1212. 1212. 2.087E-05 2.025E-05 1212. 1.563E-05 1.516E-05 W 1189. 1189. 2.105E-05 2.042E-05 1189. 8.775E-06 8.509E-06 WNW 1227. 1227. 1.541E-05 1.495E-05 1227. 8.279E-06 8.028E-06 NW 1128. 1128. 2.698E-05 2.618E-05 1128. 1.614E-05 1.5655-05 NNW 1044. 1044 6.070E-05 5.888E-05 1044. 4.455E-05 4.320E-05 Byron Site Meteorological Data 1/78 - 12/87 9 O O

BYRON Revision 1.2 August 1994 Table F-7 (Contmued) ,

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-131m i

Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec). (meters) (mrad /yr)/(uct/sec)

N 1875. 1875. 2.385E-05 1.897E-05 1875. 9.757E-05 7.650E-05 NNE 1829. 1829. 2.062E-05 1.650E-05 1829. 8.424E-05 6.608E-05 NE 1585. 1585, 1.931E-05 1.548E-05 1585. 8.807E-05 6.906E-05 ENE 1234. 1234. 1.814E-05 1.458E-05 1234. 1.003E-04 7.850E-05 E 1227. 1227. 2.206E-05 1.770E-05 1227. 1.290E-04 1.009E-04 ESE 991. 991. 3.255E-05 2.600E-05 991. 1.885E-04 1.472E-04 SE 1006. 1006. 3.838E-05 3.061E-05 1006. 2.741E-04 2.139E-04 SSE 800. 800. 5.287E-05 4.185E-05 800. 4.308E-04 3.351E-04 S 945. 945. 2.861E-05 2.284E-05 945. 2.140E-04 1.670E-04 SSW 975. 975. 1.939E-05 1.557E-05 975. 1.451E-04 1.134E-04 SW 1067. 1067. 1.511E-05 1.216E-05 1067. 1.030E-04 8.060E-05 WsW 1212. 1212. 1.568E-05 1.261E-05 1212. 8.542E-05 6.694E-05 W 1189. 1189. 2.220E-05 1.768E-05 1189. 1.056E-04 8.262E-05

- WNW 1227. 1227. 1.534E-05 1.222E-05 1227, 7.423E-05 5.806E-05 NW 1128. 1128. 2.119E-05 1.684E-05 1128. 9.904E-05 7.736E-05 NNW 1044 1044. 3.749E-05 2.966E-05 1044. 1.610E-04 1.257E-04 Byron Site Meteorological Data 1/78 - 12/87 F-17

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Max' mum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Botrid Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCI/sec) (meters) (mrad /yr)/(uci/sec)

N 1875. 1875. 5.052E-05 4.463E-05 1875. 1.779E-04 1.536E-04 NNE 1829. 1829. 4.621E-05 4.113E-05 1829. 1.541E-04 1.331E-04 NE 1585. 1585. 4.420E-05 3.946E-05 1585. 1.606E-04 1.387E-04 ENE 1234. 1234. 4.244E-05 3.799E-05 1234. 1.799E-04 1.549E-04 E 1227. 1227. 5.072E-05 4.530E-05 1227. 2.292E-04 1.971E-04 ESE 991. 991. 7.221E-05 6.419E-05 991. 3.291E-04 2.820E-04 SE 1006. 1006. 8.369E-05 7.422E-05 1006. 4.733E-04 4.049E-04 SSE 800. 800. 1.068E-04 9.370E-05 800. 7.166E-04 6.089E-04 S 945. 945. 6.295E-05 5.589E-05 945. 3.693E-04 3.159E-04 SSW 975. 975. 4.488E-05 4.011E-05 975. 2.539E-04 2.177E-04 SW 1067. 1067. 3.574E-05 3.203E 05 1067. 1.825E-04 1.569E-04 WSW 1212. 1212. 3.697E-05 3.312E-05 1212. 1.549E-04 1.336E-04 W 1189. 1189. 4.767E-05 4.218E-05 1189. 1.883E-04 1.619E-04 WNW 1227. 1227. 3.316E-05 2.937E-05 1227. 1.318E-04 1.132E-04 NW 1128. 1128. 4.462E-05 3.938E-05 1128. 1.731E-04 1.484E-04 NNW 1044. 1044 7.543E-05 6.613E-05 1044. 2.800E-04 2.397E-04 Byron Site Meteorological Data 1/78 - 12/87 8 9 9 .

O g[\ - -

BYRON Revision 12

- August 1994 Table F-7 (Contmued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Urwestncted Area Boundary for Xe-133 Downwind Unrestricted Mixed Mode (Vent) Release Ground Levet Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec) (meters) (arad/yr)/(uci/sec)

N 1875. 1875. 5.651E-05 5.145E-05 1875. 2.014E-04 1.806E-04 NNE 1829. 1829. 5.150E-05 4.714E-05 1829. 1.746E-04 1.566E-04 NE 1585. 1585. 4.921E-05 4.513E-05 1585. 1.820E-04 1.631E-04 ENE- 1234 1234 4.702E-05 4.320E-05 1234. 2.030E-04 1.816E-04 E 1227. 1227. 5.610E-05 5.145E-05 1227. 2.582E-04 2.306E-04 ESE 991. 991. 7.996E-05 7.309E-05 991. 3.684E-04 3.281E-04 SE 1006. 1006. 9.261E-05 8.450E-05 1006. 5.287E-04 4.702E-04 SSE 800. 800. 1.173E-04 1.061E-04 800. 7.899E-04 6.981E-04 S 945. 945. 6.950E-05 6.347E-05 945. 4.122E-04 3.665E-04 SSW 975. 975. 4.942E-05 4.534E-05 975. 2.848E-04 2.538E-04 SW 1067, 1067. 3.944E-05 3.627E-05 1067. 2.054E-04 1.834E-04 WSW 1212. 1212. 4.094E-05 3.764E-05 1212. 1.751E-04 1.569E-04 W 1189 1189. 5.295E-05 4.825E-05 1189. 2.119E-04 1.893E-04 WNW 1227. 1227, 3.679E-05 3.354E-05 1227, 1.481E-04 1.322E-04 NW 1128. 1128. 4.943E-05 4.494E-05 1128. 1.938E-04 1.726E-04 NNW 1044. 1044. 8.376E-05 7.580E-05 1044, 3.130E-04 2.786E-04 i

Byron Site Meteorological Data 1/78 - 12/87 F-19

___ _ _ __ _ . . , - _ ,_ - _ _ _ - . _ _ _ _ _ - _ . -. . _ . _ - -- - - - - ~

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-135m Dowruind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uci/sec)

N 1875. 1875. 3.355E-04 3.2386-04 1875. 7.574E-04 7.301E-04 NNE 1829. 1829. 3.191E-04 3.080E-04 1829. 6.3ME-04 6.124E-04 NE 1585. 1585. 3.171E-04 3.061E-04 1585. 6.645E-04 6.406E-04 ENE 1234. 1234. 3.275E-04 3.162E-04 1234. 7.919E-04 7.633E-04 E 1227. 1227. 3.794E-04 3.663E-04 1227 9.382E-04 9.043E-04 ESE 991. 991. 5.722E-04 5.524E-04 991. 1.502E-03 1.448E-03 SE 1006. 1006. 6.280E-04 6.062E-04 1006. 1.826E-03 1.759E-03 SSE 800. 800. 7.139E-04 6.889E-04 800. 2.546E-03 2.452E-03 S 945. 945. 4.850E-04 4.682E-04 945. 1.505E-03 1.450E-03 SSW 975. 975. 3.539E-04 3.416E-04 975. 1.019E-03 9.817E-04 SW 1067. 1067. 2.924E-04 2.823E-04 1067. 7.378E-04 7.111E-04 WSW 1212. 1212. 3.058E-04 2.952E-04 1212. 7.396E-04 7.129E-04 W 1189. 1189. 3.530E-04 3.407E-04 1189. 9.316E-04 8.978E-04 WNW 1227. 1227. 2.475E-04 2.389E-04 1227. 6.545E-04 6.307E-04 NW 1128. 1128. 3.32SE-04 3.208E-04 1128. 8.492E-04 8.183E-04 NNW 1044. 1044. 5.542E-04 5.346E-04 1044. 1.425E-03 1.373E-03 Byron Site Meteorological Data 1/78 - 12/87 O O O.

p . ..

d J V BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Max'r num Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135 Ocwnwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec) (meters) (mrad /yr)/(uCi/sec)

N 1875. 1875. 2.998E-04 2.898E-04 1875. 8.831E-04 8.532E-04 NNE 1829. 1829. 2.878E-04 2.783E-04 1829. 7.672E-04 7.412E-04 NE 1585. 1585. 2.805E-04 2.713E-04 1585. 7.977E-04 7.707E-04 ENE 1234. 1234. 2.749E-04 2.658E-04 1234. 8.772E-04 8.475E-04 E 1227. 1227. 3.233E-04 3.126E-04 1227. 1.099E-03 1.061E-03 ESE 991. 991. 4.486E-04 4.337E-04 991. 1.549E-03 1.496E-03 SE 1006. 1006. 5.112E-04 4.942E-04 1006. 2.178E-03 2.104E-03 SSE 800. 800. 6.045E-04 5.843E-04 800. 3.113E-03 3.006E-03 S 945. 945. 3.87BE-04 3.749E-04 945. 1.701E-03 1.643E-03 SSW 9 75. 975. 2.880E-04 2.785E-04 975. 1.190E-03 1.150E-03 SW 1067. 1067. 2.337E-04 2.260E-04 1067. 8.696E-04 8.400E-04 WSW 1212. 1212. 2.415E-04 2.335E-04 1212. 7.667E-04 7.407E-04 W 1189. 1189. 2.873E-04 2.778E-04 1189. 9.146E-04 8.835E-04 WWW 1227. 1227. 2.012E-04 1.945E-04 1227. 6.366E-04 6.150E-04 NW 1128. 1128. 2.641E-04 2.553E-04 1128. 8.175E-04 7.896E-04 NNW 1044. 1044. 4.267E-04 4.124E-04 1044. 1.313E-03 1.268E-03 Byron Site Meteorological Data 1/78 - 12/87 F-21

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Max' mum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unmstncted Area Boundary for Xe-137 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec) (meters) (mrad /yr)/(uti/sec)

N 1875. 1875. 6.403E-05 6.197E-05 1875. 9.597E-05 9.287E-05 NNE 1829. 1829. 6.358E-05 6.153E-05 1829. 8.275E-05 8.008E-05 NE 1585. 1585. 6.560E-05 6.348E-05 1585. 9.063E-05 8.770E-05 ENE 1234. 1234. 7.607E-05 7.362E-05 1234. 1.243E-04 1.203E-04 E 1227. 1227. 9.065E-05 8.773E-05 1227. 1.555E-04 1.504E-04 ESE 991. 991. 1.5092-04 1.461E-04 991. 2.80SE-04 2.714E-04 SE 1006. 1006. 1.596E-04 1.544E-04 1006. 3.144E-04 3.042E-04 SSE 800. 800. 1.905E-04 1.843E-04 800. 4.627E-04 4.477E-04 s 945. 945. 1.267E-04 1.226E-04 945. 2.775E-04 2.685E-04 SSV 975. 975. 9.229E-05 8.932E-05 975. 1.933E-04 1.870E-04 SV 1067. 1067. 7.424E-05 7.185E-05 1067. 1.418E-04 1.372E-04 WSW 1212. 1212. 7.355E-05 7.118E-05 1212. 1.309E-04 1.266E-04 W 1189. 1189. 8.087E-05 7.827E-05 1189. 1.518E-04 1.469E-04 WNW 1227. 1227. 5.651E-05 5.469E-05 1227, 1.056E-04 1.021E-04 NV 1128. 1128. 8.102E-05 7.841E-05 1128. 1.535E-04 1.486E-04 NNW 1044. 1044. 1.454E-04 1.407E-04 1044. 2.944E-04 2.849E-04 Byron Site Meteorologicat Data 1/78 - 12/87 l

l

, G 9 - _ _ _ .

9- _ _ _ _ _ _ _ _ _ - _ _ _ _ .

3 - . .

BYRON Revision 1.2 August 1994 Table F-7 (Contmued)

Maxknum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-138 Dowwind unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uti/sec) (meters) (arad/yr)/(uCf/sec)

N 1875. 1875. 7.317E-04 7.106E-04 1875. '1.559E-03 1.513E-03 NNE 1829. 1829. 7.040E-04 6.836E-04 1829. 1.310E-03 1.271E-03 NE 1585. 1585. 7.054E-04 6.850E-04 1585. 1.371E-03 1.330E-03 ENE 1234. 1234. 7.357E-04 7.145E-04 1234. 1.634E-03 1.586E-03 E 1227. 1227. 8.489E-04 8.244E-04 1227. 1.936E-03 1.879E-03 ESE 991. 991. 1.282E-03 1.245E-03 991. 3.103E-03 3.012E-03 SE 1006. 1006. 1.402E-03 1.362E-03 1006. 3.755E-03 3.644E-03 SSE 800. 800. 1.589E-03 1.543E-03 800. 5.212E-03 5.058E-03 S. 945. 945. 1.089E-03 1.058E-03 945. 3.103E-03 3.012E-03 SSW 975. 975. 7.991E-04 7.761E-04 975. 2.107E-03 2.046E-03 SW 1067. 1067. 6.61SE-04 6.427E-04 1067. 1.531E-03 1.487E-03 i

WSW 1212. 1212. 6.871E-04 6.674E-04 1212. 1.535E-03 1.490E-03 W 1189. 1189. 7.811E-04 7.586E-04 1189. 1.925E-03 1.869E-03 WNW 1227. 1227. 5.482E-04 5.324E-04 1227. 1.351E-03 1.311E-03 NW 1128. 1128. 7.355E-04 7.142E-04 1128. 1.756E-03 1.704E-03 NNW 1044. 1044. 1.215E-03 1.180E-03 1044, 2.955E-03 2.868E+03 Byron Site Meteorological Data 1/78 - 12/87 F-23.

BYRON Revision 1.2 August 1994 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar.41 Dowwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(ucl/sec) (meters) (mrad /yr)/(uci/sec)

N 1875. 1875. 1.120E-03 1.084E-03 1875. 2.935E-03 2.842E-03 NNE 1829. 1829. 1.085E-03 1.050E-03 1829. 2.531E-03 2.450E-03 NE 1585. 1585. 1.071E-03 1.037E-03 1585. 2.637E-03 2.553E-03 ENE 1234 1234. 1.069E-03 1.035E-03 1234. 2.943E-03 2.849E-03 E 1227. 1227. 1.244E-03 1.205E-03 1227. 3.609E-03 3.493E-03 ESE 991. 991. 1.753E-03 1.697E-03 991. 5.240E-03 5.072E-03 SE 1006. 1006. 1.975E-03 1.912E-03 1006. 7.123E-03 6.895E-03 SSE 800. 800. 2.290E-03 2.216E-03 800. 1.015E-02 9.828E-03 S 945. 945. 1.510E-03 1.462E-03 945. 5.616E-03 5.436E-03 SSW 975. 975. 1.128E-03 1.092E-03 975. 3.884E-03 3.759E-03 SW 1067. 1067. 9.228E-04 8.933E-04 1067. 2.826E-03 2.735E-03 WSW 1212. 1212. 9.527E-04 9.222E-04 1212, 2.594E-03 2.511E-03 W 1189. 1189. 1.105E-03 1.070E-03 1189. 3.148E-03 3.047E-03 WNW 1227. 1227. 7.765E-04 7.517E-04 1227. 2.201E-03 2.131E-03 NW 1128. 1128, 1.016E-03 9.837E-04 1128. 2.803E-03 2.713E-03 NNW 1044. 1044. 1.621E-03 1.570E-03 1044. 4.510E-03 4.366E-03 Syron Site Meteorological Data 1/78 - 12/87 9 9 9

) . ,

o V U BYRON Revision 1.2 August 1994 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Bounday for Kr-83m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec)

N 777. 777. 7.987E-05 6.022E-05 777. 3.877E-04 2.924E-04 NNE 533. 538. 1.059E-04 7.984E-05 538. 5.665E-04 4.272E-04 NE 528. 528. 8.271E-05 6.236E-05 528. 4.960E-04 3.740E-04 ENE 474. 4 74. 6.500E-05 4.901E-05 4 74. 4.60SE-04 3.473E-04 E 468. 468. 8.031E-05 6.056E-05 468. 5.867E-04 4.424E-04 ESE 480. 480. 8.935E-05 6.737E-05 480. 6.039E-04 4.553E-04 SE 427. 427. 1.280E-04 9.653E-05 427. 1.044E-03 7.870E-04 SSE 410. 410. 1.377E-04 1.038E-04 410. 1.210E-03 9.125E-04 5 295. 295. 1.466E-04 1.106E-04 295. 1.295E-03 9.767E-04 SSW 299 299. 9.895E-05 7.461E-05 299. 9.128E-04 6.883E-04 SV 451. 451. 4.721E-05 3.560E-05 451. 4.002E-04 3.017E-G4 WSW 386. 386. 7.311E-05 5.513E-05 386. 5.291E-04 3.989E-04 W 379 379. 1.136E-04 8.566E-05 379. 6.476E-04 4.883E-04 WNW 385. 385. 7.998E-05 6.031E-05 385. 4.644E-04 3.501E-04 l NW 445 445. 8.088E-05 6.098E-05 445. 4.352E-04 3.281E-04

, NNW 658. 658. 7.548E-05 5.691E-05 658. 3.486E-04 2.629E-04 l

Byron Site Meteorological Data 1/78 - 12/87 l

Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

i Approximate distance from midpoint between gaseous eff!uent release points.

l F-25

BYRON Revision 1.2 August 1994 Table F 'la (Continued)

Max' mum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-8Sm Dowwind Restricted Mixed Mode (Vent) Release Ground Levet Release Direction Area Bound Radius V VBAR Radius G G8AR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCi/sec)

N 777. 777. 5.990E-04 5.755E-04 777. 2.015E-03 1.929E-03 NNE 538. 538. 8.304E-04 7.980E-04 538. 2.732E-03 2.614E-03 NE 528. 528. 6.981E-04 6.712E-04 528. 2.441E-03 2.335E-03 ENE 474. 474. 5.790E-04 5.569E-04 474. 2.225E-03 2.129E-03 E 468. 468. 6.841E-04 6.578E-04 468. 2.791E-03 2.669E-03 ESE 480. 480. 7.377E-04 7.092E-04 480. 2.893E-03 2.767E-03 SE 427. 427. 9.807E-04 9.423E-04 427. 4.780E-03 4.569E-03 SSE 410. 410. 9.459E-04 9.080E-04 410. 5.323E-03 5.084E-03 S 295. 295. 1.046E-03 1.005E-03 295. 5.472E-03 5.226E-03 SSW 299. 299. 7.854E-04 7.549E-04 299. 3.979E-03 3.801E-03 SW 451. 451. 4.441E-04 4.273E-04 451. 1.962E-03 1.876E-03 WSW 386. 386. 6.265E-04 6.025E-04 386. 2.485E-03 2.376E-03 W 379. 379. 7.731E-04 7.421E-04 379. 2.912E-03 2.784E-03 WNW 385. 385. 5.485E-04 5.266E-04 385. 2.058E-03 1.967E-03 NW 445. 445. 5.566E-04 5.344E-04 445. 1.973E-03 1.886E-03 NNW 658. 658. 5.330E-04 5.118E-04 658. 1.750E-03 1.675E-03 Byron site Meteorologicat Data 1/78 - 12/87 O O O. .

O BYRON 3~~

Revision 1.2 August 1994 Table F-7a (Contmued)

Maximum Offsee Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-85 t

Downwirri Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Botaxi Radius V VSAR Radius G GBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (arad/yr)/(uci/sec)

N 777. 777. 6.818E-06 6.593E-06 777 2.207E-05 2.134E-05 NNE 538. 538. 9.568E-06 9.252c-06 538. 2.971E-05 2.873E-05 NE 528. 528. 8.107E-06 7.840E-06 528. 2.658E-05 2.570E-05 ENE 474. 474. 6.771E-06 6.547E-06 474. 2.418E-05 2.338E-05 E 468. 468. 7.994E-06 7.730E-06 468. 3.044E-05 2.944E-05 ESE 480 480. 8.548E-06 8.266E-06 480. 3.147E-05 3.043E-05 SE 427. 427. 1.133E-05 1.095E-05 427. 5.222E-05 5.050E-05 SSE 410. 410. 1.090E-05 1.054E-05 410. 5.839E-05 5.647E-05 S 295. 295. 1.207E-05 1.168E-05 295. 5.918E-05 5.723E-05 SSW 299. 299. 9.177E-06 8.874E-06 299. 4.315E-05 4.173E-05 SW 451. 451. 5.220E-06 5.048E-06 451. 2.153E-05 2.082E-05 WSW 386. 386. 7.292E-06 7.051E-06 386. 2.687E-05 2.578E-05 W 379. 379. 8.828E-06 8.537E-06 379. 3.134E-05 3.031E-05 WNW 385. 385. 6.276E-06 6.069E-06 385. 2.212E-05 2.139E-05 NW 445. 445. 6.362E-06 6.152E-06 445. 2.130E-05 2.060E-05 NNW 658. 658. 6.046E-06 5.847E-06 658. 1.907E-05 1.844E-05 Byron Site Meteorological Data 1/78 - 12/87 F-27

. ~- , -

BYRON Revision 1.2 August 1994 Table F-7a (Continued)

Max'mum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Dowwind Restricted Mixed Mode (Vent) Release Ground Levet Release Direction Area Bound Radius V VBAR Radius G GSAR (meters) (meters) (mrad /yr)/(utt/sec) (meters) (mrad /yr)/(uct/sec)

N 777. 777. 2.002E-03 7 944E-03 777. 5.942E-03 5.769E-03 NNE 538. 538. 2.849E-03 2.s67E-03 538. 8.120E 03 7.884E-03 NE 528. 528. 2.424E-03 2.354E-03 528. 7.237E-03 7.027E-03 ENE 474. 474. 2.043E-03 1.984E-03 474. 6.613E-03 6.421E-03 E 468. 468. 2.396E-03 2.327E-03 468. 8.197E-03 7.959E-03 ESE 480. 480. 2.576E-03 2.501E-03 480. 8.563E-03 8.316E-03 SE 427. 427. 3.393E-01 3.295E-03 427. 1.393E-02 1.353E-02 SSE 410. 410. 3.189E 03 3.097E-03 410. 1.530E 02 1.486E-02 S 295. 295. 3.653E M3 3.547E-03 295. 1.622E-02 1.575E-02 SSW 299. 299. 2.789E-03 2.709E-03 299. 1.174E-02 1.140E-02 SW 451. 451. 1.587E-03 1.541E-03 451. 5.709E-03 5.543E-03 Wsw 356. 386. 2.232E-03 2.168E-03 386. 7.443E-03 7.227E-03 W 379. 379. 2.657E-03 2.580E-03 379. 8.790E-03 8.534E-03 WNW 385. 385. 1.894E-03 1.839E-03 385. 6.229E-03 6.048E-03 NW 445. 445. 1.907E-03 1.852E-03 445. 5.919E-03 5.747E-03 NNW 658. 658. 1.783E-03 1.731E-03 658. 5.192E-03 5.041E-03 Byron Site Meteorological Date 1/78 - 12/87 O O O. .

p m

/

,7 i

}

%s BYRON Revision 1.2 August 1994 Table F-7a (Conhnued)

Maximum OliA Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-88 Oourwind Restricted Mixed Mode (Vent) Release Ground Level Release i Direction Area Bound Redius V VBAR Radius G GBAR l (meters) (meters) (mrad /yr)/(uti/sec) (meters) (mrad /yr)/(uti/sec) l N 777. 777. 4.873E-03 4.737E-03 777. 1.449E-02 1.407E-02

. NNE 538. 538. 6.949E-03 6.756E-03 538. 1.964E-02 1.907E-02 l

NE 528. 528. 5.936E-03 5.771E-03 528. 1.755E-02 1.704E-02 ENE 4 74. 474. 5.009E-03 4.870E-03 474 1.599E-02 1.553E-02 E 468. 468. 5.889E-03 5.726E-03 468. 1.998E-02 1.940E-02 ESE 480. 480. 6.254E-03 6.109E-03 480. 2.076E-02 2.016E-02 SE 427. 427. 8.282E-03 8.050E-03 427. 3.413E-02 3.313E-02 SSE 410. 410. . 838E-03 7.618E-03 410. 3.785E-02 3.674E-02 ,

S 295. 295. 8.882E-03 8.634E-03 295. 3.917E-02 3.802E-02 SSW 299. 299. 6.829E-03 6.639E-03 299. 2.846E-02 2.763E-02 SW 451. 451. 3.896E-03 3.788E-03 451. 1.403E-02 1.363E-02 usu 386. 386. 5.427E-03 5. #76E-03 386. 1.787E-02 1.735E-02 W 379. 379. 6.431E-03 6.251E-03 379. 2.097E-02 2.036E-02 WNW 385. 385. 4.584E-03 4.455E-03 385. 1.483E-02 1.440E-02 NW 445. 445. 4.622E-03 4.492E-03 445. 1.419E-02 1.378E-02 NNW 658. 658. 4.324E-03 4.203E-03 658. 1.258E-02 1.222E-02 l

Byron Site Meteorological Data 1/78 - 12/87 l

F-29

BYRON Revision 1.2 August 1994 Table F-7a (Continued)

Max' anum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-89 Downwind Restricted Mixed Mode (Vent) Release Gromd Level Release Direction Area Bomd Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec) (meters) (mrad /yr)/(ucl/sec)

N 777. 777. 2.235E-03 2.171E-03 777. 4.669E-03 4.535E-03 NdE 538. 538. 3.749E-03 3.641E-03 538. 7.948E-03 7.720E-03 NE 528. 528. 3.089E-03 3.001E-03 528. 6.626E-03 6.436E-03 ENE 474. 474. 2.645E-03 2.569E-03 474. 6.153E-03 5.976E-03 E 468. 468. 3.102E 03 3.014E-03 468. 7.427E-03 7.213E-03 ESE 480. 480. 3.404E-03 3.306E-03 480. 7.840E-03 7.614E-03 sE 427. 427. 4.486E-03 4.35BE-03 427. 1.176E-02 1.142E-02 SSE 410. 410. 3.890E-03 3.779E-03 410. 1.141E-02 1.108E-02 s 295. 295. 5.518E-03 5.360E-03 295. 1.743E-02 1.693E-02 ssW 299. 299. 4.137E-03 4.019E-03 299. 1.248E-02 1.212E-02 su 451. 451. 2.136E-03 2.075E-03 451. 5.197E-03 5.047E-03 Wsw 386. 386. 3.333E-03 3.238E-03 386. 8.487E-03 8.243E-03 W 379. 379. 3.832E-03 3.722E-03 379. 1.037E-02 1.00/E-02 WNW 385. 385. 2.751E-03 2.672E-03 385. 7.432E-03 7.218E-03 NW 445. 445. 2.651E-03 2.576E-03 445. 6.506E-03 6.319E-03 NNW 658. 658. 2.158E-03 2.097E-03 658. 4.738E-03 4.602E-03 syron site Meteorologicat Data 1/78 - 12/87

~ -

g . _.

Y BYRON Reymon 1.2 August 1994 Table F-7s (Conhnued)

Maxenum Offste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-90 Downwind Restricted Mixed Mode (Vent) Release Groted Level Release Direction Area Bound Radius . V VBAR. Radius G- G8AR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uti/sec)

N 777. 777. 2.920E-04 2.833E-04 777. 2.771E-04 2.693E 04 NNE 538. 538. 9.216E-04 8.940E-04 538. 1.070E-03 1.038E-03 NE 528. 528. 6.927E-04 6.720E-04 528. 8.049E-04 7.803E-04 ENE 474. 474 6.455E-04 6.262E-04 474. 8.222E 04 7.971E-04 E 468. 468. 8.493E-04 8.239E-04 468. 1.189E-03 1.153E-03

• ESE 480. 480. 9.079E-04 8.807E-04 480. 1.223E-03 1.186E-03 SE 427. 427. 1.268E-03 1.230E-03 427. 1.855E-03 1.798E-03 SSE 410, 410. 1.055E-03 1.024E-03 410. 1.699E-03 1.648E-03 S 295. 295. 2.202E-03 2.136E-03 295. 4.311E-03 4.179E-03 SSW 299. 299. 1.624E-03 1.575E-03 299. 3.114E-03 3.019E-03 SW 451. 451. -5.560E-04 5.393E-04 451. 8.707E-04 8.441E-04 WSW 386. 386. 1.053E-03 1.021E-03 386. 1.701E-03 1.649E-03 ,

W 379. 379. 1.099E-03 1.066E-03 379. 1.610E-03 1.561E-03 WWW 385. 385. 8.138E-04 7.894E-04 385. 1.195E-03 1.158E-03 NW 445. 445. 6.789E-04 6.585E-04 445. 9.080E-04 8.802E-04 NNW 658. 658. 3.357E-04 3.256E-04 658. 3.703E-04 3.590E-04 Byron Site Meteorotogicat Data 1/78 - 12/87 l-i l

-F-31

BYRON Revision 1.2 August 1994 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-131m Downwind Restricted Mixed Mode (Vent) Release Gromd Level Release Direction Area Bomd Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (ared/yr)/(uci/sec)

N 777. 777. 7.605E-05 5.999E-05 777. 3.587E 04 2.793E-04 WNE 538. 538. 1.013E-04 8.007E-05 538. 5.146E'04 4.000E-04 NE 525. 528. 8.079E-05 6.401E-05 528. 4.534E-04 3.526E-04 ENE 474. 474. 6.397E-05 5.081E-05 474. 4.180E-04 3.249E-04 E 468. 463. 7.840E-05 6.215E-05 468. 5.378E-04 4.177E-04 ESE 480. 480. 8.641E 05 6.842E-05 480. 5.499E-04 4.272E-04 SE 427. 427. 1.224E-04 9.663E-05 427. 9.585E-04 7.436E-04 SSE 410. 410. 1.316E-04 1.034E-04 410. 1.120E-03 8.677E-04 s 295. 295. 1.379E-04 1.086E-04 295. 1.157E-03 8.957E-04 SSW 299. 299. 9.485E-05 T.499E-05 299. 8.215E-04 6.366E-04 SW 451. 451. 4.713E-05 3.751E-05 451. 3.728E-04 2.897E-04 WSW 386. 386. 7.042E-05 5.586E-05 386. 4.741E-04 3.682E-04 W 379. 379. 1.053E-04 8.276E-05 379. 5.723E-04 4.441E-04 WNW 385. 385. 7.411E-05 5.829E-05 385. 4.086E-04 3.169E-04 NW 445. 445. 7.532E-05 5.923E-05 445. 3.878E-04 3.009E-04 NNW 658. 658. 7.089E-05 5.580E-05 658. 3.187E-04 2.480E-04 Byron Site Meteorological Data 1/78 - 12/87

f'

. :. E- .

v .,

' BYRON Revision 1.2.-

August 1994 I Table F-7a (Contmued)

Maxirrann Offsile Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-133m Downwind Restricted Mixed Mode (Vent) Release Gromd Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (prod /yr)/(uCl/sec) (meters) (mrad /yr)/(uCi/sec)

N 777. 777. 1.485E-04 1.296E-04 777. 5.th t-04 S.152E-04 NNE 538. 538. 2.017E-04 1.766E-04 538. 8.473E-04 7.182E-04 hE 528. 528. 1.653E-04 1.452E-04 528. 7.508E-04 6.371E 04 ENE 474. 474. 1.340E-04 1.182E-04 474 6.889E-04 5.840E-04 E 468. 468. 1.612E-04 1.418E-04. 468. 8.788E-04 7.438E-04 ESE 480. 480. 1.755E-04 1.541E-04 480. 9.024E-04 7.644E-04 SE 427. 427. 2.410E-04 2.105E-04 427. 1.544E-03 1.303E-03 SSE 410. 410. 2.464E-04 2.136E-04 410. 1.774E-03 1.493E-03 5 295. 295. 2.641E-04 2.298E-04 295. 1.822E-03 1.531E-03 SSW 299. 299. 1.897E-04 1.662E-04 299. 1.306E-03 1.100E-03 SW 451. 451. 1.008E-Gi 8.916E-05 451. 6.134E-04 5.199E-04 WSW 386. 386. 1.459E-04 1.284E-04 386. 7.755E-04 6.565E-04 -)

W 379. 379. 1.985E-04 1.722E-04 379. 9.246E-04 7.807E-04 WNW 385. 385. 1.402E-04 1.217E-04 385. 6.573E-04 5.546E-04

' NW 445. 445. 1.425E-04 1.237E-04 445. 6.270E-04 5.296E-04 NNW 658. 658. 1.353E-04 1.176E-04 658. 5.321E-04 4.522E-04 ,

Byron Site Meteorological Date 1/78 - 12/87 I

I i F-33

_. _ _ _ _ _ _ . - _ . _ _ __ _ _-_- . - _ __ , _. . . . _ ~ __ _ . _ _ . - _ _ _ _ _ _ . ._ ___._____ __

BYRON Revision 1.2 August 1994 Table F-7a (Contimed)

Maximun Offsite Finite Plume Garnma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133 Dowwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCi/sec) (meters) (mrad /vr)/(uCf /sec)

N 777. 777. 1.640E-04 1.478E-04 777. 6.691E-04 5.926E-04 NNE 538. 538. 2.206E-04 1.991E-04 538. 9.273E-04 8.176E-04 NE 528. 528. 1.807E-04 1.636E-04 528. 8.238E-04 7.271E-04 ENE 474. 474. 1.459E-04 1.324E-04 4 74. 7.544E-04 6.653E-04 E 468. 468. 1.752E-04 1.586E-04 468. 9.594E-04 8.448E-04 ESE 480. 480. 1.915E-04 1.732E-04 480. 9.866E-04 8.693E-04 SE 427. 427. 2.615E-04 2.357E-04 427. 1.674E-03 1.470E-03 SSE 410. 410. 2.657E-04 2.379E-04 410. 1.909E-03 1.671E-03 S 295. 295. 2.831E-04 2.541E-04 295. 1.954E-03 1.708E-03 SSW 299. 299. 2.034E-04 1.834E-04 299. 1.407E-03 1.233E-03 SW 451. 451. 1.097E-04 9.976E-05 451. 6.715E-04 5.920E-04 VSW 386. 386. 1.584E-04 1.435E-04 386. 8.466E-04 7.455E-04 W 379. 379. 2.144E-04 1.922E-04 379. 1.003E-03 8.812E-04 WW 385. 385. 1.512E-04 1.356E-04 385. 7.116E-04 6.246E-04 NW 445. 445. 1.541E-04 1.382E-04 445. 6.805E-04 5.979E-04 NNW 658. 658. 1.486E-04 1.335E-04 658. 5.860E-04 5.180E-04 Byron Site Meteorologicat Data 1/78 - 12/87 8 9 9. -

O O'

~

O BYRON Revision 1.2 August 1994 Table F-7a (Conhnued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-135m Dowwird Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(ucl/sec) (meters) (mrad /yr)/(uCl/sec)

N 777. 777. 1.114E-03 1.074E-03 777. 3.170E-03 3.053E-03 ,

NNE 538. 538. 1.604E-03 1.548E-03 538. 4.526E-03 4.358E-03 NE 528. 528. 1.341E-03 1.29*.E-03 528. 3.963E-03 3.817E-03 .

ENE 474. 474 1.127E-03 1.087E-03 474. 3.655E-03 3.519E-03 E 468. 468. 1.313E-03 1.267E-03 468. 4.389E-03 4.226E-03 ESE $80. 480. 1.445E-03 1.394E-03 480. 4.682E-03 4.508E-03 SE 427. 427, 1.901E-03 1.833E-03 427.' 7.254E-03 6.984E-03 SSE 410. 410. 1.722E-03 1.661E-03 410. 7.557E-03 7.273E-03 S 295. 295. 2.104E-03 2.029E-03 295. 9.119E-03 8.775E-03 SSW 299. 299. 1.569E-03 1.514E-03 299. 6.478E-03 6.235E 03 SW 451. 451. 8.760E-04 8.455E-04 451 2.948E-03 2.839E-03 WsW 386. 386. 1.289E-03 1.244E-03 386. 4.307E-03 4.147E-03 W 379. 379. 1.552E-03 1.496E-03 379. 5.247E-03 5.050E-03 WNW 385. 385. 1.107E-03 1.067E-03 385. 3.752E-03 3.611E-03 NW 445. 445. 1.103E-03 1.064E-03 445. 3.446E-03 3.317E-03 NNW 658. 658. 1.013E-03 9.770E-04 658. 2.866E-03 2.760E-03 i

Byron Site Meteorological Data 1/78 - 12/87 F-35

BYRON Revision 1.2 August 1994 Table F-7a (Centinued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-135 Dowwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uci/sec) (meters) (arad/yr)/(uci/sec)

N 777. 777. 8.146E-04 7.873E-04 777. 2.716E-03 2.622E-03 NNE 538. 538. 1.131E-03 1.093E-03 538. 3.662E-03 3.535E-03 NE 528. 528. 9.534E-04 9.215E-04 528, 3.275E-03 3.162E-03 ENE 474. 474 7.918E-04 7.654E-04 474. 2.982E-03 2.879E-03 E 468. 4o8. 9.350E-04 9.038E-04 468. 3.745E-03 3.616E-03 ESE 480. 480. 1.006E-03 9.723E-04 480. 3.877E-03 3.743E-03 SE 427. 427. 1.335E-03 1.290E-03 427. 6.410E-03 6.18SE-03 SSE 410. 410. 1.286E-03 1.243E-03 410. 7.141E-03 6.892E-03 s 295. 295. 1.420E-03 1.373E-03 295. 7.284E-03 7.030E-03 SSW 299. 299. 1.070E-03 1.035E-03 299. 5.309E-03 5.125E-03 SW 451. 451. 6.081E-04 5.878E-04 451. 2.641E-03 2.550E-03 WSW 386. 386. 8.542E-04 8.257E-04 386. 3.319E-03 3.205E-03 W 379. 379. 1.047E-03 1.011E-03 379. 3.877E-03 3.742E-03 WNW 385. 385. 7.428E-04 7.178E-04 385. 2.737E-03 2.642E-03 WW 445. 445. 7.543E-04 7.288E-04 445. 2.631E-03 2.540E-03 NNW 658. 658. 7.230E-04 6.987E-04 658. 2.351E-03 2.270E-03 Byron Site Meteorological Data 1/78 - 12/87 i

(

~ . _-_- . . _ __ _.

BYRON Revision 1.2 August 1994 Table F-7a (Contmued)

Maximum Offsee Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-137 Dowwind Restricted Mixed Mode (Vent) Release Grotsid Level Rel'sse e 1 Direction Area Botsid Radius V VSAR Radius G GBAR (meters) (meters) (arad/yr)/(uci/sec) (meters) (arad/yr)/(uti/sec)

N 777. 777. 3.338E-04 3.230E-04 777. 7.619E-04 7.372E 04 NME 538. 538. 5.39'c-04 5.221E-04 538. 1.250E-03 1.209E-03 NE 528. 528. 4.433v 74 4.290E-04 528. 1.050E-03 1.016E-03 ENE 474. 474. 3.764E-04 3.643E-04 474. 9.728E-04 9.413E E 468. 468. 4.417E-04 4.275E-04 468. 1.168E-03 1.130E-03 ESE 480. 480. 4.860E-04 4.703E-04 480. 1.237E-03 1.197E-03 SE 427. 427. 6.397E-04 6.190E-04 427. 1.856E-03 1.796E-03 SSE 410. 410. 5.573E-04 5.393E-04 410. 1.81'IE-03 1.755E-03 S 295. 295. 7.699E-04 7.450E-04 295. 2.671E-03 2.584E-03 SSW 299. 299. 5.740E-04 5.555E-04 299. 1.901E-03 1.840E-03 SW 451. 451. 3.015E-04 2.918E-04 451. 8.062E-04 7.801E-04 WSW 386. 386. 4.678E-04 4.527E-04 386. 1.303E-03 1.261E-03 W 379. 379.~ 5.469E-04 5.292E-04 '379. 1.602E-03 1.550E-03 WNW 385. 385. 3.920E-04 3.793E-04 385. 1.148E-03 1.111E-03

' NW -445, 445, 3.807E-04 3.684E-04 445. 1.012E-03 9.792E-04 NNW 658. 658. 3.194E-04 3.090E-04. 658. 7.568E-04 7.322E-04 syron site Meteorological Data 1/78 - 12/87 F-37

_ _ __ - _ _ . ., . . . . -_ . . _ . . . ._ . . . , _ = _ - ._ _ _ - . - __ . - _. . ___ __-_.

BYRON Revision 1.2 August 1994 Table F-7a (Continued)

Maximum Offsite Finite Phrne Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-138

)

Dowwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uti/sec) (meters) (atrad/yr)/(uci/sec)

N 777. 777. 2.446E-03 2.375E-03 777. 6.577E-03 6.383E-03 NNE 538. 538. 3.565E-03 3.462E-03 538. 9.407E-03 9.129E-03 NE 528. 528. 3.004E-03 2.917E-03 528. 8.231E-03 7.988E-03 ENE 474. 4 74. 2.542E-03 2.469E-03 474. 7.585E-03 7.361E-03 E 468. 468. 2.950E-03 2.864E-03 468. 9.089E-03 8.820E-03 ESE 480. 480. 3.242E-03 3.148E-03 480. 9.708E-03 9.421E-03 SE 427. 427. 4.245E-03 4.122E-03 427 1.497E-02 1.453E-02 SSE 410. 410. 3.820E-03 3.709E-03 410. 1.552E-02 1.506E-02 S 295. 295. 4.720E-03 4.583E-03 295. 1.888E-02 1.832E-02 SSW 299. 299. 3.548E-03 3.445E-03 299. 1.341E-02 1.301E-02 SW 451. 451. 1.990E-03 1.933E-03 451. 6.108E-03 5.928E-03 WSW 386. 386. 2.911E-03 2.827E-03 386. 8.964E-03 8.699E-03 W 379. 379. 3.444E-03 3.344E-03 379. 1.092E-02 1.060E-02 WNW 385. 385. 2.461E-03 2.389E-03 385. 7.814E-03 7.582E-03 NW 445. 445. 2.446E-03 2.375E-03 445. 7.166E-03 6.954E-03 NNW 658. 658. 2.224E-03 2.159E-03 658. 5.956E-03 5.780E-03 Byron Site Meteorological Data 1/78 - 12/87 8 9 9 .

O O'

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L O

BYRON Revision 1.2 August 1994 Table F-7a (Conenued)

Maximum Offsite Finile Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Ar-41 Dowmelrd Restricted Nixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (arad/yr)/(ucl/sec) (meters) (mrad /yr)/(uCf/sec)

N 777. 777. 3.113E-03 3.013E-03 777. 9.438E-03 9.136E-03 NNE 538. 538. 4.416E-03 4.275E-03 538. 1.286E-02 1.244E-02 NE 528. 528. 3.755E-03 3.635E-03 528. 1.147E-02 1.110E-02 ENE 474. 474. 3.160E-03 3.059E-03 474. 1.047E-02 1.013E-02 E 468. 468. 3.711E-03 3.592E-03 468. 1.304E-02 1.262E-02 ESE 480. 480. 3.982E-03 3.855E-03 480. 1.358E-02 1.314E-02 SE 427. 427. 5.255E-03 5.086E-03 =27. 2.224E-02 2.152E-02 SSE 410. 410. 4.973E-03 4.814E-03 410. 2.457E-02 2.379E-02 S 295. 295. 5.645E-03 5.464E-03 295. 2.571E-02 2.489E-02 SSW 299. 299. 4.306E-03 4.168E-03 299. 1.865E-02 1.805E-02 SW 451. 451. 2.450E-03 2.371E-03 451. 9.118E-03 8.826E 03 WSW 386. 386. 3.437E-03 3.327E-03 386. 1.174E-02 1.137E-02 W 379. 379. 4.108E-03 3.976E-03 379. 1.382E-02 1.338E-02 WW 385. 385. 2.926E-03 2.833E-03 385. 9.788E-03 9.475E-03 NW 445. 445. 2.952E-03 2.857E-03 445. 9.334E-03 9.036E-03 NNW 658. 658. 2.769E-03 2.681E-03 658. 8.224E-03 7.961E-03 1

Byron Site Meteorological Data 1/78 - 12/87 F-39

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BYRON Revision 1.2 August 1994 SupplementalTable A Mixed Mode Joint Frequency DistribubOn Table Summaries 250 Foot Elevation Data Sumary Table of Percent by 01rection and Cisss Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .252 .214 .229 .246 .231 .171 .178 .162 .291 .322 _310 ,233 .211 .249 .286 .204 3.789 8 .158 .133 .133 .134 .088 .074 .069 .107 .156 .202 .174 .145 .139 .136 .170 .i6i 2.i79 C .217 .153 .183 .190 .155 .096 .126 .172 .238 .276 .252 .172 .223 .259 .313 .233 3.257 D 2.282 1.781 1.668 2.200 t.661 1.053 1.130 1.665 2.243 2.433 2.265 1.833 2.399 2.669 2.856 2.436 32.575 E 1.052 .909 .837 1.019 1.303 .911 1.120 1.405 2.257 2.475 2.028 1.599 1.601 1.728 1.908 1.283 23.437 F .360 .320 .301 .257 .442 .459 .561 .657 1.015 1.056 .683 .450 .436 .516 .635 .461 8.608 G .218 .141 .134 .113 .160 .199 .289 .323 .315 .342 .333 .241 .139 153 .181 .188 3.469 total 4.539 3.652 3.484 4.158 4.040 2.962 3.474 4.492 6.515 7.106 6.045 4.673 5.148 5.710 6.350 4.966 77.315 Sumary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total

.45 .000 .021 .006 .000 .006 .000 .000 .000 .010 .019 .014 .006 .030 .000 .016 .017 .144 1.05 .049 .040 .037 .020 .034 .026 .021 .015 .019 .040 .038 .056 .041 .060 .057 .037 .590 2.05 .233 .179 .209 .226 .174 .146 .157 .148 .177 .201 .214 .196 .245 .27'O .247 .198 3.220 3.05 .446 .368 .428 .487 .404 .306 .335 .377 .395 .464 .496 .436 .431 .466 .507 .467 6.813 4.05 .612 .561 .478 .493 425 .338 .379 .406 .486 .584 .689 .571 .570 .593 .643 .593 8.420 5.05 .772 .636 .537 .591 .475 .373 .400 .497 .690 .749 .892 .720 .715 .879 .978 .751 10.655 6.05 .753 .625 .574 .648 .543 .391 .473 .632 .799 .976 1.000 .826 .863 .997 1.264 .994 12.358 8.05 1. 17 4 .893 .775 1.027 1.206 .794 .961 1.257 1.986 2.289 1.783 1.299 1.471 1.608 1.760 1.403 21.708 10.05 .431 .282 .377 .591 .689 .485 .653 .932 1.573 1.492 .774 .479 .648 .694 .720 .448 11.268 13.05 .070 .046 .063 .075 .085 .104 .095 .228 .379 .291 .146 .085 .132 .143 .137 .058 2.138 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 4.539 3.652 3.484 4.158 4.040 2.962 3.474 4.492 6.515 7.106 6.045 4.673 5.148 5.710 6.350 4.966 77.315 NOTE: Wind directions in tables are presented in " wind frOm" and not " wind tO' direction.

In Order to determine the final mixed mode values,77.315% Of the elevated value (presented in the 250 FT Mixed Mode table) and 22.685% Of the ground level value (presented in the 30 FT Mixed Mode table) are used to calculate the final values.

O O _ - - - - -

O. .

BYRON Revision 1.2 -

August 1994 Supplemental Tatne A - Contmued Mixed Mode Joint Frequency Distrbubon Table Summaries 250 Foot Elevation Data Summary lable of Percent by Speed and Class Class A B C D E F G Speed

.45 .000 .000 .001 .039 .041 .032 .031 I 1.05 .007 .006 .020 .225 .160 .076 .097 2.05 .118 .079 .138 1.518 .812 .341 .214 3.05 .384 .268 .367 3.212 1.535 .618 .428 4.05 .599 .293 .453 3.697 2.053 .831 .493 5.05 .601 .363 .513 4.424 3.032 1.210 .511 6.05 .597 .374 .519 4.948 3.975 1.481 .464 8.05 .901 .496 769 8.786 7.260 2.652 .844 10.05 474 .243 .397 4.699 3.830 1.263 .362 13.05 .107 .057 .079 1.027 .740 .105 .024 18.00 .000 .000 .000 .000 .000 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F-41

BYRON Revision 12 August 1994 Supplernental Table A - Continued Mixed Mode Joint Frequency Distribubon Table Summaries 8YRON MIXED MOOE OFD t378-1987 30 FT ELEVATION 30 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .046 .051 .047 .035 .045 .030 .036 .047 .085 .135 .096 .072 .068 .087 .083 .058 1.023 8 .035 .033 .029 .031 .023 .011 .018 .026 .053 .077 .055 .043 .031 .046 .043 .041 .594 C .046 .034 .048 .051 .034 .028 .026 .035 .073 .096 .072 .050 .060 .068 .088 .057 .866 0 .714 .465 .502 .604 .443 .329 .328 .560 .848 .830 .688 .499 .810 .984 .921 .725 10.251 E .236 .198 .155 .234 .370 .285 .391 .825 1.190 .987 .631 .328 .378 .404 .414 .282 7.310 F .062 .041 .020 .043 .158 .133 188 .360 .385 .162 .077 .056 .063 .075 .086 .101 2.012 G .019 .009 .007 .014 .052 .055 .086 .093 .107 .054 .017 .006 .013 .016 .032 .049 .630 Total 1.t38 .831 .808 1.011 1.127 .872 1.073 1.947 2.741 2.341 1.636 1.055 1.424 1.681 1.666 1.314 22.685 Summary Table of Percent by Direction and Speed

! Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total l

l .45 .005 .005 .003 .000 .000 .000 .001 .001 .001 .003 .004 .003 .003 .002 .003 .013 .047 1.05 .015 .004 .007 .005 .009 .004 .004 .006 .008 .009 .013 .012 .014 02'2 .037 .038 .207 2.05 .067 .034 .018 .030 .067 .045 .044 .048 .097 .108 .099 .071 .084 .101 .134 .130 1.177 3.05 .136 .109 .066 .109 .232 .158 .165 .225 .295 .205 .156 .111 .116 .133 .164 .145 2.524 4.05 .174 .153 .128 .160 .265 .168 .221 .372 .429 .246 .207 .155 .151 .t56 .214 .195 3.393 5.05 .t51 .113 .122 .161 .184 .t10 .173 .364 .416 .271 .212 .149 .144 .164 .209 .192 3.136 6.05 .129 .094 .102 .138 .155 .104 .139 .296 .390 .298 .224 .119 .158 .172 .183 .160 2.861 8.05 .232 .142 .192 .253 .184 .167 .208 .437 .722 .651 .417 .222 .284 .411 .381 .253 5.156 10.05 .181 .115 .132 .128 .030 .085 .092 .166 .311 .409 .221 .125 .242 .321 .273 .145 2.976 13.05 .050 .060 .033 .027 .001 .030 .025 .028 .072 .133 .080 .063 .180 .162 .068 .041 1.054 18.00 .O17 .001 .004 .000 .000 .001 .00t .002 .000 .008 .004 .026 .045 .038 .00t .002 .150 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 000 .000 .000 .002 Total 1.158 .831 .808 1.011 1.127 .872 1.073 1.947 2.741 2.341 1.636 1.055 1.424 1.681 1.666 1.314 22.685 NOTE: Wind directions in tables are presented in " wind frOrn" and not " wind to" direction.

i i

l O

BYRON O

Revision 1.2 Au;ast 1994 '

l Supplemental Table A - Contnued ,

l Mixed Mode Joint Frequency Distribubon Table Summaries l

30 Foot Elevation Data 1

Surnreary Table of Percent by Speed and Class Class A B C D E F G Speed

.45 .000 .000 .000 .003 .007 .016 .022 1.05 .000 .000 .000 .006 .047 .088 .066 2.05 .002 .002 .009 .092 .479 .420 .174 3.05 .050 .028 .034 .521 1.110 .590 192 4.05 .130 .078 .102 1.213 1.251- .489 .129 5.05 .157 ~.087 .137 1.368 1.109 .246 .032 6.05 .140 .079 .120 5.362 1.058 .095 .008 8.05 .289 .173 .251 2.861 1.514 .062 .007 10.05 .177' .116 .142 1.972 .564 .006 .000 13.05 .075 .031 .053 .735 .159 .001 .000 18.00 .004 .000 .018 .117 .012 .000 .000 99.00 .000 .000 .001 .001 .000 .000 .000 F-43

BYRON Revision 1.2 August 1994 Supplemental Tsble B Ground Level Joint Frequency Distribubon Table Summaries Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW Total A .289 .317 .301 .244 .249 .190 .198 .197 .335 .454 .408 .318 .268 .342 .383 .302 4.792 8 .190 .187 .178 .158 .125 .065 .079 .130 .193 .268 .227 .193 .171 .192 .202 .210 2.767 C .269 .226 .252 .218 .190 .118 .152 .189 .302 .364 .306 .218 .272 .317 .397 .328 4.118 D 3.298 2.327 2.338 2.684 1.992 1.334 1.365 2.172 3.012 3.140 2.915 2.275 3.055 3.615 3.969 3.357 42.847 E 1.466 1.198 .988 1.331 1.661 1.226 1.472 2.553 3.628 3.107 2.414 1.710 1.995 1.980 2.316 1.719 30.766 F .504 .318 .185 .276 .699 .648 .803 1.293 1.732 .881 .499 .408 .476 .499 .646 .751 10.619 G .202 .091 .061 .099 .253 .250 .355 .400 .624 .396 .159 .078 .131 .160 .312 .520 4.091 Total 6.217 4.663 4.304 5.011 5.169 3.830 4.424 6.933 9.826 8.609 6.929 5.200 6.367 7.105 8.225 7.186 100.000 Summar y Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW Total

.45 .098 .099 .078 .030 .009 .000 .014 .032 .046 .045 .040 .030 .067 .042 .138 .211 .978 1.05 .308 .154 .125 .137 .121 .093 .090 .090 .127 .137 .205 .229 .265 .339 .503 .536 3.459 2.05 .939 .602 .458 .594 .843 .606 .598 .605 1.008 1.072 1.002 .839 .905 .995 1.305 1.265 13.635 3.05 1.164 1.030 .779 .981 1.468 1.075 1.093 1.478 1.982 1.467 1.292 .930 1.005 1.157 1.388 1.186 19.476 4.05 1.179 1.024 .878 .995 1.243 .831 1.027 1.727 2.110 1.421 1.240 .997 1.024 1.035 1.342 1.214 19.286 5.05 .839 .631 .658 .798 .724 .474 .652 1.254 1.636 1.250 1.038 .781 .813 .906 1.141 .971 14.566 6.05 .G12 .467 .496 .589 .417 .313 .418 .803 1.153 1.094 .859 .546 .786 .813 .867 .761 10.995 8.05 .755 .437 .612 .695 .310 .313 .405 .735 1.319 1.461 .898 .595 .915 1.177 1.090 .797 12.516 10.05 .253 .157 .183 .165 .032 .093 .103 .180 .374 .517 .270 .164 .350 .436 .378 .203 3.857 13.05 .053 .061 .034 .027 .001 .031 .025 .028 .072 .136 .081 .064 .190 .166 .071 .041 1.081 18.00 .016 .001 .004 .000 .000 .001 .001 .002 .000 .008 .004 .026 .045 .038 .001 .002 .150 19.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .000 .000 .000 .002 Total 6.217 4.663 4.304 5.011 5.169 3.830 4.424 6.933 9.826 8.609 6.929 5.200 6.367 7.105 8.225 7.186 100.000 NOTE: Wind directions in tables are presented in " wind from" and not " wind to* direction.

O O O .

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BYRON Revision 1.2 August 1994 Supplemental Table B -Contmued Ground Level Joint Frequency Distribubon Table Summaries l

l Surnmary Table of Percent by Speed and Class Class A B C D E F G Speed

.45 .004 .001 .000 .095 .257 .275' .346 1.05 .018 .012 .027 .508 1.035 1.080 .780 2.05 .286 .171 .246 3.256 5.028 3.228 1.419 3.05 .744 .428 .616 6.258 7.173 3.272 .985 4.05 .992 .581 .781 8.165 6.404 1.902 .460 5.05 .909 .506 .808 7.302 4.357 .607 .077 6.05 .712 .388 .613 6.167 2.938 .164 .013 8.05 .819 .500 .755 7.616 2.734 .081 .011 10.05 .230 .150 .196 2.606 .667 .009 .000 13.05 .075 .032 .055 .755 .161 .001 .000 18.00 .004 .000 .018 .117 .012 .000 .000 99.00 .000 .000 .001 .001 .000 .000 .000 1

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