ML20202G936
| ML20202G936 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/30/1999 |
| From: | COMMONWEALTH EDISON CO. |
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| References | |
| PROC-990130, NUDOCS 9902050348 | |
| Download: ML20202G936 (122) | |
Text
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X244 ALL l
Document Control Desk j
Director of Nuclear Reactor Regulation i
U.S. Nuclear Regulatory Commission j
Mail Station PI-137 Washington DC 20555 l
i January 30,1999 l
Attached are revisions to the Offsite Dose Calculation Manual, Byron Annex, Chapters l
10,11 and 12. Please update your manual as follows:
i Remove:
Insert:
i Chapter 10, Rev.1.3, February 1997 Chapter 10, Rev.1.4, October 1998 Chapter 11, Rev.1.5, October 1997 Chapter 11, Rev.1.6, October 1998 Chapter 12, Rev.1.5, October 1997 Chapter 12, Rev.1.6, January 1999 l
[
Please sign below indicating your manual has been updated and that your controlled copy number is correct.
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Name Date Return to:
Comed Procedures Clerk 1400 Opus Place,4th Floor i
Downers Grove,IL 60515 t
-or-O i
hD Procedures Clerk 4th Floor ETW 111
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r 9902050348 990130 L t
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f ODCM Chapter 10, Revision 1.4 Summary of Changes Page ri:
Revision Descriotion:
10-i New Revision Number.
)
10-il Updated Page Number References.
8 10-iii Updated Page Number References.
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10-3 Removed Component Cooling Water Monitor Description from Section 10.1.2 Airborne Process Radiation Monitors.
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10-7 Added Component Cooling Water Monitor Description to Section 10.2, Liquid Process Radiation Monitors.
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10-9 Added dual reference to applicable Technical Requirements Manual and Administrative Technical Requirements Table.
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BYRON Revision 1.4 October 1998 BYRON ANNEX INDEX i
CHAPTER 10 REVISION 1.4 P
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(p VadprotodemW10R1-4 doc) 10-1 i
BYRON R vision 1.4 October 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE NUMBEB 10.1 AIRBORNE RELEASES 10-1 10-1 1.
System Descnption 1.
Waste Gas Holdup System 10-1 2.
Ventilation Exhaust Treatment System 10-1 2.
Radiation Monitors 10-1 1.
Auxiliary Building Vent Effluent Monitors 10-1 2.
Containment Purge Effluent Monitors 10-2 3.
Waste Gas Decay Tank Monitors 10-2 4.
Gland Steam and Condenser Air Ejector Monitors 10-2 5.
Radwaste Building Ventilation Monitor 10-3 6.
Miscellaneous Ventilation Monitors 10-3 l
3.
Alarm and Trip Setpoints 10-3 1.
Setpoint Calculations 10-3 1.
Auxiliary Building Vent Effluent Monitors 10-3 2.
Containment Purge Effluent Monitors 10-3 l
3.
Waste Gas Dccay Tank Effluent Monitors 10-3 2.
Release Limits 10-4 3.
Release Mixture 10-5 4.
Conversion Factors 10-5 5.
HVAC Dilution Flow Rates 10 5 4.
Allocation of Effluents from Common Release Points 10-5 5.
Dose Projections for Batch Releases 10-5 9
(ptadprotodcmty10R14 doc) 10-il
.. - ~ - -.
BYRON RLvision 1.4 October 1998 i
CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)
NUMBER PAGE 10.2 LIQUID RELEASES 10-5
===1.
System Description===
10-5 1.
Release Tanks 10-6 2.
Turbine Building Fire and Oil Sump 10-6 3.
Condensate Polisher Sump 10-6 l
2.
Radiation Monitors 10-6 1.
Liquid Radwaste Effluent Monitors 10-6 2.
Station Blowdown Monitor 10-6 3.
Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX) Outlet Line Monitors 10-6 4.
Turbine Building Fire and Oil Sump Monitor 10-7 5.
Condensate Polisher Sump Monitor 10-7 6.
Component Cooling Water Monitor 10-7 1
3.
Alarm and Trip Setpoints 10-7 1.
Setpoint Calculations 10-7 1.
Station Blowdown Monitor 10-6 1.
Release Mixture 10-8 2.
Liquid Radwaste Effluent Monitor 10-8
\\O 1.
Release Tank Discharge Flow Rate 10-8 2.
Release Mixture 10-9 3.
Liquid Dilution Flow Rates 10-9 4.
Projected Concentrations for Releases 10-9 3.
Other Liquid Effluent Monitors 10-10 4.
Conversion Factors 10-10 4.
Allocation of Effluents from Common Release Points 10-10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 10-10 O
(p.Vedprotmacmey10R1-4 doc) 10-lii
BYRON Revision 1.4 October 1998 CHAPTER 10 Oi LIST OF TABLES i
NUMBER PAGE
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i 10-1 Assumed Composition of the Byron Station Noble Gas Effluent 10-11 10-2 Assumed Composition of the Byron Station Liquid Effluent 10 12 i
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(p VadproteacmbyloR1-4 doc) 10-iv
i BYRON R; vision 1.4 October 1998 CHAPTER 10 iV LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-13 10-2 Simplified Liquid Radwaste Processing Diagram 10-15 10-3 Liquid Release Flowpath 10-16 i
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(ptadprotodemey10R1-4 doc) i 10-v l
1 BYRON Revision 1.4 October 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Desenption A simplified HVAC and gaseous effluent flow diagram is provided in Figure 10-1. The pnncipal release points for potentially radioactive airbome 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 delay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is desenbed in Chapter 11 of the Byron /Braidwood UFSAR.
10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive materialin particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior tu release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1.
Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
10.1.2 Radiation Monitors 10.1.2.1 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, noble gas monitoring, grab sampling, iodine and particulate sampling and tritium sampling.
No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Chapter 11.
O (r. Vadprotodemty10R1-4 doc) 10-1
BYRON Rsvision 1.4 October 1998 G
10.1.2.2 Containment Purge Effluent Monitors Monitors 1RE PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 containments, respectively. When airbome 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 Chapter 11.
Monitors 1(2)RE AR011 and 1(2)RE-AR012 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 Chapter 11.
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.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Chapter 11.
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(p:Vodprotedcmby1oR1-4 acc) 10-2 i
BYRON R; vision 1.4 October 1998 10.1.2.5 Radwaste Building Ventilation Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. On high alarm, ORE-PR026 initiates isolation of the radwaste building ventilation system.
Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Chapter 11.
10.1.2.6 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 Chapter 11.
10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculation 10.1.3.1.1
. :.tiliary 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 0.25% 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 release 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.
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.
O (pvacproteccmey1oR1-4 doc) 10-3
BYRON R; vision 1.4 October 1998
[3 10.1.3.2 Release Limits V
Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS Section 12.4 are not exceeaed. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Qu.
(1.11)otyE{ViFi) S 500 mrem /yr (10-1) cerE{(t > tti {x/c)vexpc-A a/3s00 pv)
(10-2>
i 1
V )}
3000 mrem /yr
+ 1.11 i
The summations are over noble gas radionuclides 1.
f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
Qu Total Allowed Release Rate, Vent Release
[ Ci/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 7
10-1, the value of Equation 10-2 (1.02 x 10 Ci'sec) is used as the limiting noble gas I
release rate. During evolutions involving releGses from the containment or waste gas decay tanks, the total station release rate is procedurally limited such that the maximum permissible release rate is not exceeded.
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'f'V (ptadproteccmey10R1-4 doc) 10-4
BYRON R; vision 1.4 October 1998 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.
10.1.3.4 Conversion Factors.
The response curves used to determine the monitor count rates are based on the sensitivity to Xe-133 for conservatism.
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, flow rates can be estimated from the operating fan combinations.
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 compnsed of contnbutions from both units. Consequently, allocation is made 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 venfied 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 venfy compliance with 10CFR50.
10.2 LIQUID RELEASE 10.2.1 System Desenption 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 desenbed in Chapter 11 of the Byron /Braidwood Updated Final Safety Analysis Report.
10.2.1.1 Release Tanks There are two radwaste release tanks (OWX0lT and OWX26T 30,000-gallon capacity each) which receive liquid waste before discharge to the Rock River.
9 (pYadprotodemey10R1-4 doc) 10-5
BYRON R; vision 1.4 October 1998 10.2.1.2 Turbine Building Fire and Oil Sump g
The turbine building fire and oil sump receives water from selected turbine building j
sumps, the tendon tunnel sumps, and the diesel fuel oil storage sumps, all of which are r
normally non-radioactive but potentially contaminated. The effluent from this sump is monitored, and if radioactive contamination exceeds a predetermined level pump 1
operation is automatically terminated. The water may then be sent to the liquid radwaste treatment system.
I 10.2.1.3 Condensate Polisher Sump
{
The condensate polisher sump receives waste water from the condensate polisher system which is normally non-radioactive but potentially contaminated. The effluent i
from this sump is monitored and if radioactive contamination exceeds a predetermined
[
level sump discharge is terminated and major condensate polisher inputs to the sump are automatically isolated. The water may then be sent to the liquid radwaste treatment system.
l 10.2.2 Radiation Monitons 10.2.2.1 Liquid Radwaste Effluent Monitors.
i 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.
j Pertinent information on the monitor and associated control devices is provided in Byron /Braidwood UFSAR Chapter 11.
i 10.2.2.2 Station Blowdown Monitor Monitor ORE-PRO 10 continuously monitors the recirculating water blowdown. No control i
device is initiated by this channel.
Pertinent information on this monitor is provided in Byron /Braidwood UFSAR i
Chapter 11.
i 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX) Outlet Line i
Monitors Monitors 1RE-PR002,2RE-PR002,1RE PR003, and 2RE-PR003 continuously monitor the RCFC and SX outlet lines.
No control device is initiated by these channels.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Chapter 11.
(ptadprotacmty10R14 doc) 10-6
BYRON R: vision 1.4 October 1998 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 Chapter 11.
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 Chapter 11.
10.2.2.6 Componeat Cooling Water Monitor 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 Chapter 11.
10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area.
Setpoint calculations normally consist of identified release mixtures, dilution factors, conversion factors (detector sensitivity), and conservatism factors.
O (p:Vacprotodemey10R1-4 doc) 10-7
BYRON R:; vision 1.4 October 1998 O
10.2.3.1.1 Station Blowdown Monitor
\\
During release, the monitor setpoint is found by solving equation 10-3.
C" + (1.50 x C,, (ptmaxj (pm, yrmaxyy g39_3y T
P S I'
Release Setpoint
[ Cl/ml]
l.50 Factor to account for minor fluctuations in count rate Concentration of activity in the circulating water blowdown
[ Ci/ml]
at the time of discharge
(" Background reading")
C' Analyzed activity in the release tank
[ Cl/ml]
excluding tritium F
Circulating Water Blowdown Rate
[gpm]
Fmo Maximum Release Tank Discharge Flow Rate
[gpm]
The flow rate from the radwaste discharge tank.
10.2.3.1.1.1 Release Mixture The release mixture used for the setpoint determination is the radionuclide mix identified in the release tank grab sample isotopic analysis.
10.2.3.1.2 Liquid Radwaste Effluent Monitor
'(
)
.(/
During release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading.
However, per procedure, the maximum discharge flow rate is limited to a value that will result in less than 50% of 10*DWC at the c'ischarge point. (See Section 10.2.3.1.2.1) 10.2.3.1.2.1 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:
F'a = 0.5( F a'/ E(C, /10
- DWC,))
m g10 4)
The summation is over radionuclides i.
E==
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]
Nw Circulating Water Blowdown Rate
[gpm]
C, Concentration of Radionuclide iin the Release Tank
[ Ci/ml]
The concentration of radioactivity in the radwaste discharge.ank based on measurements of a sample drawn from the tank.
\\,s (p:vadprotedemey1oR1-4 doc) 10-8
BYRON Revision 1.4 October 1998
- DWC, Derived Water Concentration
[ Ci/ml]
O The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402.
10 Multipher 10.2.3.1.2.2 Release Mixture The release mixture used for the setpoint determination is the radionuclide mix identified in the release tank grab sample isotopic analysis.
10.2.3.1.2.3 Liquid Dilution Flow Rates Dilution flow rates are obtained from the main control board in the control room. If this information is unavailable, releases may continue for up to 30 days provided the dilution flow rates are estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the re! ease, in accordance with Technical Requirements Manual Table T3.11.a-1 (ATR Table 3.3-12).
10 2.3.1.2.4 Projected Concentrations for Releases After determining Fb= 0from Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6.
C = CI[F' !(F'..
- F'a)]
z30 5y El C" /10
- DWC, ) 51 (so_e)
The summation is over radionuclides i.
CI Concentration of Radionuclide iin the Unrestricted Area
[ Cl/mL]
The calculated concentration of radionuclide i in the unrestricted area as determined by Equation 10-5.
CT Concentration of Radionuclide iin the
[ Cl/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
[ Cl/ml]
The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402.
10 Multiplier F' a Maximum Release Tsnk Discharge
[gpm]
m Flow Rate Naa Circulating Water Blowdown Rate
[gpm]
(p Vadprotedemty1oR1-4 doc) 10-9
BYRON Rsvision 1.4 October 1998 i
10.2.3.1.3 OtherLiquid Effluent Monitors I
For all other liquid effluent monitors, including ORE-PR001 and ORE-PRO 10 when not batch releasing, setpoints are determined such that the concentration limits do not exceed 10 times the DWC value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402 in the unrestricted area. Release mixtures are based on a representative isotopic mixture of the waste stream or inputs to the waste stream, or l
defaulted to the mix listed in Table 10-2.
10.2.3.1.4 Conversion Factors l
The readouts for the liquid effluent monitors are in uCi/ml. Conversion factors are determined for each monitor (CPM /uCl/ml).
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10.2.4 Allocation of Effluents from Common Release Points.
Radioactive liquid effluents released from either release tank (0WX01T or OWX26T) are compnsed of contributions from both units. Under normal operating conditione, # !:,
l difficult to apportion the radioactivity between the units. Consequently, allocation is 1
made evenly between units.
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.
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BYRON Revision 1.4 October 1998 Table 10-1 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 0.04 Kr-88 00.28 Xe-131m 01.4 Xe-133m 00.57 Xe-133 71.1 Xe-135 00.53 Xe-138 00.04 9
(p Vadprotodemby10R1-4 doc) 10-11
1 BYRON Rrvisian 1.4 October 1998 Table 10-2 i
Assumed Composition of the Byron Station Liquid Effluent Isotope Concentration Isotope Concentration
( Ci/ml)
( Ci/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 Co-60 3.00E - 06 Te 131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr 95 6.00E - 06 l130 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 l135 4.00E - 07 Cs-134 9.00E - 07 Cs-136 9.00E - 06 j
e a
i Cs-137 2.00E - 06 Ce-144 1.00E - 06 Np-239 1.00E - 05
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ODCM Chapter 11, Revision 1.6
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Summary of Changes Page #:
Revision Descrintion:
11-i New Revision Number 11 Il-8 Miscellaneous Format Changes to maintain consistency throughout the Chapter.
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11-7 Removed Dairy BY-27 from REMP Sampling Program. The dairy is no longer active, and no samples can be obtained.
l1-13 Deleted BY-27 from Figure Il-4," Ingestion and Waterborne Exposure Pathway Sample Locations" i
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BYRON Revision 1.6 October 1998 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS PAGE 11.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 O
O (pvao;rotvxicmty11R1-6. doc) 11-ii
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CHAPTER 11 l
LIST OF TABLES NUMBER TLLE PAGE i
11-1 Radiological Environmental Monitoring Program 11-2 l
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BYRON Ravision 1.6 October 1998 CHAPTER 11 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Onsite Air Sampling Locations 11-10 11-11 11-2 Offsite Air Sampling Locations 11 3 Inner Ring and Outer Ring TLD Locations 11-12 11-4 Ingestion and Waterborne Exposure Pathway 11-13 Sample Locations O
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BYRON Revision 1.6 October 1998 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -
The radiological environmental monitoring program for the environs around Byron Station is given in 1
Table 11-1.
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Figures 11-1 through 114 show sampling and monitoring locations.
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GYRON Revision 1.6 October 1998 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequsncy and/or Sample Samplina or Monitorina Locations Collection Freauency of Analysis
- 1. Airbome Radiciodine and a.
Indicators-Near Field Continuous sampler operation Radioiodine Canister:
l Particulates with particulate sample 1-131 analysis biweekly l
BY-21, Byron Nearsite N, collection weekly, or more on near field and control O.3 mi N (0.5 km A) frequently if required by dust samples.'
l BY-22, Byron Nearsite ESE, loading, and radioiodine canister 0.4 mi ESE (0.6 km F) collection biweekly.
Particulate Sampler:
BY-23. Byron Nearsite S, 0.6 mi S (1.0 km J)
Gross beta analysis BY-24, Byron Nearsite SW, following weekly filter 0.6 mi SW (1.0 km L) change' and gamma isotopic analysis l
quarterly on composite filters by location on l
near field and j
control samples.
l b.
Indicators-Far Field BY-1, Byron,3.0 mi N (4.8 km A)
BY-4, Paynes Pt., 5.0 mi SE (8.0 km G)
BY-6, Oregon,4.7 mi SSW (7.5 km K) l l
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t Revision 1.6 October 1998 Table 11-1 (Cont.)
Radiological Environmertal Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Samplina or Monitorina Locations Collection Freauency of Analysis
- 1. Airbome (Cont'd) c.
Controls BY-8, Leaf River,6.8 mi WNW (10.9 km P)
- 2. Direct Radiation a.
Indicators-Inner Ring Quarterly Gamma dose quarterly BY-101 1 0.3 mi N (0.5 km A)
BY-10 i-?. 0 3 mi N (0.5 km A)
BY-1C 2-1,0 9 mi NNE (1.5 km B)
BY-102-2,10 mi NNE (1.5 km B)
BY-103-1,
- 7 mi NE (2.8 km C)
BY-103-2,1.7 mi NE (2.7 km C)
BY-104-1,1.5 mi ENE (2.4 km D)
BY-104-2,1.5 mi ENE (2.4 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 (2.3 km F)
BY-106-2,1.4 mi ESE (2.3 km F)
BY-107-1,1.4 mi SE (2.2 km G)
BY-107-2,1.4 mi SE (2.2 km G)
BY-108-1,0.7 mi SSE (1.1 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) l BY-110-1,0.6 mi SSW (1.0 km K)
BY-110-2,0.6 mi SSW (1.0 km K)
BY-111-3,0.7 mi SW (1.1 km L)
BY-111-4,0.8 mi SW (1.3 km L)
BY-112-3,0.8 mi'WSW (1.2 km M)
BY-112-4,0.8 mi WSW (1.2 km M) l l
(p%deutyr11R1-6 doc) 11-3 L-
E,YRON R: vision 1.6 October 1998 Table 11-1 (Cont.)
Radiological Environmental Monitcring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplino or Monitorino Locations Collection Frecuency of Analysis
- 2. 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 (1.2 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 (1.7 km Q)
BY-116-1,1.4 mi NNW (2.3 km R)
BY-116-2,1.4 mi NNW (2.3 km R) b.
Indicators-Outer Ring BY-201-3,4.5 mi N p.1 km A)
BY-201-4,4.4 mi N (7.1 km A)
BY-202-1,4.3 mi NNE (6.9 km B)
BY-202-2, 4.8 mi NNE p.6 km 3)
BY-203-1,4.8 mi NE (7.7 km C)
BY-203-2,4.7 mi NE p.5 km C)
BY-204-1,4.2 mi ENE (6.6 km D)
BY-204-2,4.1 mi ENE (6.5 km D)
BY-205-1,3.8 mi E (6.2 km E)
BY-205-2,3.8 mi E (6.2 km E)
BY-206-1,4.1 mi ESE (6.5 km F)
BY-206-2, 4.4 mi ESE p.0 km F)
BY-207-1,4.2 mi SE (6.7 km G)
BY-207-2,3.6 mi SE (5.8 km G)
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CYR Revision 1.6 October 1998 Table 11-1 (Cont.)
Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Samolina or Monitorina Locations Collection Frequency of Analysis
- 2. Direct Radiation BY-208-1,4.0 mi SSE (6.4 km H)
(Cont'd)
BY-208-2,3.7 mi SSE (5.9 km H)
BY-209-1,3.7 mi S (5.9 km J)
BY-209-4. 3.7 mi S (5.9 km J)
BY-210-3,3.9 mi SSW (6.2 km K)
BY-210-4,3.9 mi SSW (6.2 km K)
BY-211-1,4.9 mi SW (7.9 km L)
BY-211-4,4.9 mi SW (7.8 km L)
BY-212-1,4.7 mi WSW U.4 km M)
BY-212-4,4.7 mi WSW U.4 km M)
BY-213-1,4.7 mi W p.5 km N)
BY-213-4,4.6 mi W (7.4 km N)
[
BY-214-1,4.6 mi WNW (7.4 km P)
BY-214-4,4.9 mi WNW (7.8 km P)
BY-215-1,5.3 mi NW (8.4 km Q)
BY-215-4,5.2 mi NW (8.3 km Q)
BY-216-1,4.6 mi NNW (7.3 km R) r BY-216-2,4.8 mi NNW (7.6 km R) c.
Indicators-Other i
One at each airborne I
location given in part 1.a i
and 1.b.
d.
Control i
One at each airbome control location given in part 1.c.
i l
(p.Vedpronodcmeyr11R14 doc) 11-5
BYRON R: vision 1.6 October 1998 Table 11-1 (Cont.)
Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sampfe Samolina or Monitorina Locations Collection Frecuency of Analysis
- 3. Waterbome
- a. GroundN/ ell a.
Indicators Quarterly Gamma isotopic' and tritium analysis BY-14, Comed Offsite Well quarterly.
0.5 mi ESE (0.7 km F) i BY-18. McCoy Farmstead 0.7 mi SW (1.2 km L)
BY-32, Wolford Weli 1.8 mi W (2.9 km N) l b Drinkinc There is no drinking water pathway l
within 6.2 mi downstream of the station.
- c. Surface BY-12, Oregon Pool of Rock River, Weekly grab samples.
Gross beta and gamma Downstream of Discharge, isotopic analysis on 4.5 mi SSW (7.3 km K) monthly composite; tritium analysis on quarterly composite.
- d. Control BY-29, Byron, Upstream of Intake Weekly grab samples.
Gross beta and gamma 3.0 mi N (4.8 km A) isotopic analysis on monthly composite; tritium analysis on quarterly composite.
- e. Sediment BY-12. Oregen Pool of Rock River, Semiannually Gamma isotopic' Downstream of Discharge, analysis semiannually.
4.5 mi SSW (7.3 km K)
(p:b@kxicmtyr11R1-6. doc)
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October 1998 Table 11-1 (Cont.)
I Radiological Environmental Monitoring Program Exposure Pathway Samp;ing or Type of Frequency and/or Sample Samplino or Monitorino Locations Collection Frecuency of Analysis
- 4. Incestion
- a. Milk a.
Indicators Biweekly: May through Gamma isotopc' and October, monthly:
1-131 analysis on each Novemberthrough April.
sample.
BY-20, K. Reeverts Dairy Farm, 2.0 mi NE (3.2 km C)
BY-30, Don Roos Dairy, 5.3 mi SE (8.4 km G) b.
Controls BY-26 Glen Gazzard's Dairy, 12.0 mi N (19.2 km A)
- b. Fish a.
Indicator BY-31, Rock River in vicinity of Discharge, Two times annually Gamma isotopic' 2.2 mi WNW (3.5 km P) analysis on edible portions.
b.
Control BY-29, Byron, Upstream of !ntake 3.0 mi N (4.8 km A)
- c. Food Products a.
Indicators Annually Gamma isotopic' analysis on each Two samples from each of the four sample.
majorquadrants within 6.2 miles of the station.
(p:Vodprorodemeyr11R1-6. doc) 11-7
BYRON R: vision 1.6 October 1998 Table 11-1 (Cont.)
Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Samplino or Monitorina Locations Collection Frecuency of Analysis Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.
b.
Control Two samples within 9.3 to 18.6 miles of the station.
l l
(p:Wetyr11R1-6 doc) e e
B Revision 1.6 October 1998 TABLE 11-1 (Cont'd)
Radiological Environmental Monitoring Program l
'Far field samples are analyzed when the respective near field Lample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airbome effluents from the station, or at the discretion of the Radiation Protection Director.
I 2Airbome 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 allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yea 1y mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
l 3
Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station.
'l 131 analysis means the analytical separation and counting procedure are specific for this radionuclide.
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ODCM Chapter 12, Revision 1.6 j
Summary of Changes Page #
Revision Descriotion-12-ii Updated revision number 12iii-12-iv Updated page number references 12-1 Change Tech Spec references from Current Tech Spec (CTS) to Improved Tech Spec (ITS) 12 12-4 Updated Definitions to fully align with Improved Technical Specification and Technical Requirements Manual Definitions 12-5 Changed bases reference from CTS to ITS.
12 12-70 Format Changes. Format was updated to comply with ITS format, as documented in the Tchnical Requirements Manual Chapters 3.I1 and 3.12.
12-50 Old Steam Generator Storage Facility (OSGSF) Surveillance broken apart into two separate actions. Surveillance had required
('y initial survey of OSGSF, quanerly check of sump level, and requirement to remove water ifidentified. Initial Suciey completed and within requirements, so it has been removed. Surveillance 12.4.5.B.3 now only requires a quarterly sump level check. New Surveillance (12.4.5.B.4) requires any water identified to be sampled and analyzed.
12-71 Annual Radiological Environmental Operating Report due date extended from May l to May 15"', as specified in ITS 5.6.2 12-73 Technical Specification reference updated to reflect ITS.
12-74 Records Retention requirements removed from Tech Specs, and placed in UFSAR Chapter 17. Reference updated to reflect change Reference to On-site review and investigative function removed, replaced with Independent Technical Review and PORC.
12-75 Reference to On-site review and investigative function removed, replaced with Independent Technical Review and PORC.
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BYRON Revision 1.6 January 1999 g
CHAPTER 12.0 SPECIAL NOTE The transfer of the Byron Radiological Effluent Technical Specifications to the ODCM was approved by the Nuclear Regulatory Commission in Technical Specification Amendment 46, dated April 13,1992.
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BYRON Revision 1.6 January 1999 BYRON ANNEXINDEX CHAPTER 12 Revision 1.6 l
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BYRON Revision 1.6 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-2 12.2 INSTRUMENTATION 12-6 1.
Radioactive Liquid Effluent Monitoring instrumentation 12-6 2.
Radioactive Gaseous Effluent Monitoring Instrumentation 12-16 12.3 RADIOLOGICAL EFFLUENTS - LIQUID 12-25 1.
Concentration Limits for Effluents 12-25 2.
Dose From Liquid Effluents 12-31 3.
Liquid Radwaste Treatment System 12-33 12.4 RADIOLOGICAL EFFLUENTS - GASEOUS 12-36 1.
Dose Rate for Gaseous Effluents 12-36 2.
Dose - Noble Gases 12-41 3.
Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form 12-43 v
4.
Gaseous Radwaste Treatment System 12-46 5.
Total Dose 12-49 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-52 1.
Radiological Environmental Monitoring Program 12-52 2.
Land Use Census 12-66 3.
Intertaboratory Companson Program 12-69 12.6 REPORTING REQUIREMENTS 12-71 1.
Annual Radiological Environmental Operating Report 12-71 2.
Annual Radioactive Effluent Release Report 12-73 3.
Offsite Dose Calculation Manual (ODCM) 12-74 4.
Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-75 D
12-lii (p:radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999O CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
LIST OF TABLES TABLE TITLE PAGE 12.0-1 Compliance Mainx 12 1 12.1-1 Frequency Notations 12-5 12.2-1 Radioactive Liquid Effluent Monitoring 12-12 instrumentation 12.2-2 Radioactive Liquid Effluent Monitoring 12-15 Instrumentation Surveillance Requirements 12.2-3 Radioactive Gaseous Effluent Monitoring 12-21 Instrumentation 12.2-4 Radioactive Gaseous Effluent Monitoring 12-24 Instrumentation Surveillance Requirements 12.3-1 Radioactive Liquid Waste Sampling and Analysis 12-27 Program 12.4-1 Radioactive Gaseous Waste Sampling and Analysis 12-38 Program 12.5-1 Radiological Environmental Monitoring Program 12-58 12.5-2 Reporting Levels for Radioactivity Concentrations 12-63 in Environmental Samples 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-64 O
12-iv (p:radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1959 9
BYRON STATION Table 12.0-1 COMPLIANCE MATRIX R:gulation 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 5.5.4.h l
Appendix I airbome radioactivity in effluent plume.
A-2
- a. Whole body and skin dose due to airbome A-6 N/A N/A radioactivity in effluent plume are A-7 reported only if certain gamma and beta air dose criteria are exceeded.
- 2. CDE for all organs and all four age groups A-13 12.4.3 5.5.4.1 l
due to iodines and particulates in effluent plume. All pathways are considered.
- 3. CDE for all organs and all four age groups A 29 12.3.2 5.5.4.d l
due to radioactivity in liquid effluents.
- 1. TEDE, totaling all deep dose equivalent A-38 5.5.4.c l
components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airbome and liquid-bome). CDE evaluation is made for adult only using FGR 11 database.
40 CFR 190
- 1. Whole body dose (DDE) due to direct dose, A-35 12.4.5 5.5.4.J l
(now by ground and plume shine from all sources at a refsrence, also station.
part of 10 CFR 20)
- 2. Organ doses (CDE) to an adult due to all A-13 pathways.
Technical
A-8 12.4.1 5.5.4.g l
Specifications and organ (CDE) dose rates to an adult due A-9 to radioactivity in airbome effluents.
A-28 For the organ dose, only inhalation is considered.
- 2. " Instantaneous" concentration limits for A-32 12.3.1 5.5.4.b l
liquid effluents.
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12-1 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 O
12.1 DEFINITIONS 12.1.1 ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
12.1.2 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CAllBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.
12.1.3 A CHANNEL CHECK shall be the quantative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
12.1.4 A CHANNEL OERATIONAL TEST (COT) shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.
12.1.5 DOGE EQUIVALENT l-131 shall be that concentration of I-131 (microcuries/ gram) that alone wo'Jid produce the same thyroid dcse as the quantity and isotopic mixture of I-131,1132, l-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, AEC,1962. " Calculation of Distance Factors for Power and Test Reactor Sites."
12.1.6 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise. The 25% variance shall not be applied to Operability Action statements. The bases to improved Technical Specification 3.0.2 provide clarifications to this requirement.
12.1.7 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
12.1.8 A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Tabic T1.1-1 with fuel in the reactor vessel.
12.1.9 OCCUPATIONAL DOSE means the dose received by an individualin the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from l l
background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.
12-2 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 12.1.10 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABLITY when it is capable of performing its specified safety functions (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function (s) are also capable of performing their related support function (s).
12.1.11 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, 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 compliance with 10 CFR Parts 20, 61, and 71. State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste.
12.1.12 PURGE / PURGING sha!! 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.
12.1.13 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 M Wm.
12.1.14 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
12.1.15 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and c
burial ground requirements.
12.1.16 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
12.1.17 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
l 12.1.18 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by.
the licensee.
12.1.19 VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineerea Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
12-3 (p:\\radprot\\odem\\by12R1-6. doc) e
BYRON Revision 1.6 January 199 12.1.20 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.
12.1.21 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.
12.1.22 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 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.
O O
12-4 (p:\\radprot\\odem\\by12R1-6. doc)
t BYRON j
Revision 1.6 January 1999 i
TABLE 12.1-1 FREQUENCY NOTATIONS
- i Notation Frecuency l
i l
S - Shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i
j D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
W - Weekly At least once per 7 days M - Monthly At least once per 31 days e
Q - Quarterly At least once per 92 days j
SA-Semiannually At least once per 184 days i
]
A-Annually At least once per 366 days R - Refuel Cycle At least once per 18 months i
i S/U - Startup Prior to each reactor startup N.A.
Not applicable 1
+
a l
P - Prior Prior to each radioactive release i
2 5
- Each frequency requirement shall be performed within the specified time interval with the maximum I
allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action statements. The bases to ITS 3.0.2 provide clarifications to this requirement. These l
[
frequency notations do not apply to the Radiological Environmental Monitoring Program as described in j
i Section 12.5.
t l
1 l
i lO i
l 12-5 i
(p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 199 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring instrumentation 12.2.1. A All radioactive liquid effluent monstonng instrumentation channels shown in Table 12.2-1 shall be OPERABLE.
APPLICABILITY:
At all times.
ACTIONS:
NOTES 1.
Separate Condition entry is allowed for each channel.
2.
All samples are to be analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.
3.
TLCO 3.0.c is not applicable.
4.
TLCO 3.0.d is not applicable.
l I
CONDITION REOUIRED ACTION COMPLETION TIME A.
One or more radioactive liquid A.1 Suspend the release of immediately effluent monitoring radioactive liquid effluent instrumentation channel monitored by the affected Alarm / Trip Setpoint less channel.
conservative than required.
08 A.2 Declare the channel immediately inoperable.
B.
Less than the required B.1 Enter the Condition referenced immediately radioactive liquid effluent in Table 12.2-1 for the monitoring instrumentation affected channel (s),
channels OPERABLE.
(continued) 0 12-6 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999
]
O ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME C.
As required by Required C.1 Verify at least two independent Prior to initiating a reicase 4
Action B.1 and referenced by samples are analyzed.
Table 12.21.
AND C.2 Verify at least two technically Prior to initiating a release qualified members of the facility staff Independently verify the release rate calculations.
AND 4
C.3 Verify at least two technically Prior to initiating a release d
qualified members of the facility staff independently i
verify the discharge line valving.
C.4.1 Restore the required 14 days number of channels to OPERABLE.
9.3 C.4.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability.
(continued) s 12-7 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999
(
l ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
As required by Required D.1 Verify grab samples are Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and referenced by collected and analyzed.
Table 12.2-1.
AND D.2.1 Restore the required 30 days number of channels to OPERABLE.
OB D.2.2 Supplement ine 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability (continued) l l
12-8 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
As required by Required E.1
---N OTE S---
i Action B.1 and referenced by 1.
Pump performance i
Table 12.2-1.
curves generated in place may be used to estimate flow.
2.
Only required to be performed dunng actual releases.
Estimate flow rate.
Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND E.2.1 Restore the required 30 days number of channels to
]
9_8 E.2.2 Supplement the 12 months Radioactive Effluent l
Release Report pursuant to Technical l
Specification 5.6.3 with I
the cause for failure to correct inoperability.
(continued) 12-9 (p:\\radprot\\odem\\by12R1-6. doc)
i BYRON Revision 1.6 January 1999 l
l ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action F.1.1 NOTE B.1 and referenced by Table Only required to be 12.2-1.
performed when the specific activity of the secondary activity of the secondary coolant is
>0.01 Ci/gm DOSE EQUIVALENT l-131.
Verify grab samples are Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> collected and analyzed.
O_B F.1.2 NOTE Only required to be performed when the specific activity of the l
l secondary coolant is 50.01 Ci/gm DOSE EQUIVALENT l-131.
Every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Verify grab 5.amples are collected and analyzed.
AND 30 days F.2.1 Restore the required number of channels to OPERABLE.
O_8 12 months F.2.2 Supplement the Radioactive Effluent Release Report Pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability.
(continued) l l
12-10 (p:\\radprot\\odem\\by12R1-6. doc)
.. _. ~
t BYRON Revision 1.6 January 1999 ACTIONS (continued) i i
CONDITION REQUIRED ACTION COMPLETION TIME G.
As required by Required G.1 Verify liquid grab Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and referenced by samples are collected Table 12.2-1.
and analyzed.
i AND G.2.1 Restore the required 30 days number of channels to OPERABLE.
.O. 8 G.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability.
H.
Required Action and H.1 Suspend the release of Immediately associated Completion Time radioactive liquid effluent for Conditions C, D, E, F, or monitored by the G not met.
affected channel.
i f
I I
1 L
12-11 (p:\\radprot\\odemiby12R1-6.coc) i
BYRON Revision 1.6 January 1999 I
I Table 12.2-1 (Page 1 of 3)
Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS 1
Radioactivity Monitors Providing Alarm and Automatic Terminationof Release a
Uqud Raouaste Effluent une 1
C 12.2.1.B.1 (ORE-PR001) 12.2.1.B.3(a) 12.2.1.B.4(c) 12.2.1.B.5 b
Fire and Oil Sump (ORE-PR005) 1 F
12.2.1.B.1 12.2.1.B.2 12.2.1.B.3(a) 12.2.1.B.4(C) c.
Condensate Polisher Sump Discharge 1
F 12.2.1.B.1 (ORE-PR041) 12.2.1.B.2 12.2.1.B.3(a)
{
g 12.2.1.B 4(C)
(continued)
(s)
The 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:
1.
Instrument indicates measured levels above the Alarm / Trip Setpoint. or 2.
Circuit failure (monitor loss of communications - alarm only, detector loss of counts. or monitor loss of power), or 3.
Detector check source test failure, or 4
Detector channel out-of-service. or 5.
Monitor loss of sample flow (c)
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATiON, bources that have been related to the initial cahbration shall be used.
O 12-12 (p:\\radprot\\odcm\\by12R14. doc)
BYRON Revision 1.6 January 1999 Table 12.2-1 (Page 2 of 3)
Radioactive Liquid Effluent Monitonng Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS 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 1
D 12.2.1.B 1 (1 RE-PR002) 12.2.1.B.2 12.2.1 B.3(D) 12.2.1.B.4(c) b) RCFC 1B and 10 Outlet 1
D 12.2.1.B 1 (1 RE-PR003) 12.2.1.B.2 12.2.1.B.3(b) 12.2.1.B.4(c) 2). Unit 2 a). RCFC 2A and 2C Outlet (2RE-PR002) 1 0
12.2.1.B.1 O
12.2.1.B.2 12.2.1 B 3(l 12.2.1.B 4(C) b). RCFC 28 and 2D Outlet (2RE-PR003) 1 D
12.2.1.B.1 12.2.1.B.2 12.2.1.B 3(b) 12.2.1.8 4 (c) b Station Blowdown Line (ORE-PRO 10) 1 D
12.2.1.8 1 12.2.1.8 2 12.2.1.B.3(b) 12.2.1 B 4(C)
(continued)
(b)
The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alaim annuncipion occurs if any of the following Conditions exists' 1.
Instrument indicates measured leve!s above the Alarm Setpoint. or 2.
Circuit farture (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or 3.
Detector check source test failure, or 4.
Detector channel out-of-service. or 5.
Moottor loss of sample flow.
(c)
The initial CHANNEL CAltBRATlON shall be performed using one or more of the reference standards certified by the National Bureau of g
Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrate.g the system over its intended range of energy and measurement range. For subsequent CHANNEL r
CAUBR ATION, sources that have been related to the initial calibration shall be used.
12-13 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON l
Revision 1.6 January 199 Table 12.2-1 (Page 3 of 3) j Radioactive Liquid Effluent Monitoring instrumentation i
INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS 3 Flow Rate Measurement Devices a Liquid Radweste Effluent Line 1
E 12.2.1.B.1(d)
(Loop-WX001) 12.2.1.B.3 12.2.1.B.4 b-Liquid Radwaste Effluent Line (Loop-WX630) 1 E
12.2.1.B.1(d) 12.2.1.B.3 12.2.1.B.4 c.
Station Blowdown Line (Loop-CWO32) 1 E
12.2.1.B.1(d) 12.2.1.B.3 12.2.1.B.4 4.
Radioactrvity Monitors Providing Alarm and Automatic 2
G 12.2.1.B.1 Closure of Surge Tank Vent Component Cooling Water 12.2.1.B.2 12.2.1.B 3(a)
Line 12.2.1.B.4(C) a.
(ORE-PR009 and 1/2RE-PR009)
(a)
The CHANNEL OPERATIONAL TEST shall also dernonstrate that automatic isolation of this pathway and control room alarm l
annunciation occur if any of the following conditions exist:
1 1.
Instrumerd indicates measured levels above the Alarm /Tnp Setpoint, or 2.
Circuit failure (monitor loss of communicatioris - alarm only, detector loss of counts. or monitor loss of power), or 3.
Detector check source test failure or 4
Detector channel outef-servce, or 5.
Monitor loss of sample flow.
(c)
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards + Med by the National Bureau of l
Standards (NBS) or using standards that have been obtained from suppliers that participate in measure.nent assurance activ'ies with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.
(d)
CHANNEL CHECK shall consist of venfying indication of flow dunng 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 cays on which continuous, penodic, or batch releases are made.
O 12-14 (p3radprot\\odCfT Aby12R1-6. doc)
i t
BYRON Revision 1.6 January 1999 O
Table 12.2-2 l
SURVEILLANCE REQUIREMENTS NOTES 1.
Refer to Table 12.2-1 to determine which Surveillance Requirements apply to each instrument.
2.
Alarm / Trip Setpoints shall be set to ensure that the limits of Requirement 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 parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
SURVEILLANCE FREQUENCY 12.2.1.B.1 Perform a CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t
12.2.1.B.2 Perform a SOURCE CHECK.
31 days 12.2.1.B.3 Perform a CHANNEL OPERATIONAL TEST.
92 days i
12.2.1.B.4 Perform a CHANNEL CAllBRATION.
18 months 12.2.1.B.5 Perform a SOURCE CHECK.
Prior to each release l
I
- O 12-15 (p
- \\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
l 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring instrumentation 12.2.2.A All radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE.
APPLICABILITY: At alltimes.
ACTIONS NOTES 1.
Separate Condition aritry is allowed for each channel.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.o.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more gaseous effluent A.1 Suspend the release of immediately i
monitoring instrumentation radioactive gaseous channel Alarm / Trip Setpoint(s) effluent monitored by the less conservative than affected channel, required.
9.8 A.2 Declare the channel Immediately inoperable.
B.
Less than the required B.1 Enter the Condition immediately radioactive gaseous Referenced in Table effluent monitonng 12.2-3 for the affected instrumentation channels OPERABLE.
channel (s).
(continued) l O
12-16 (p:\\radprot\\odem\\by12R1-6. doc)
i i
BYRON 1
Revision 1.6 January 1999 l
i ACTIONS (continued) h 4
i i
l CONDITION REQUIRED ACTION COMPLETION TIME l:
l C.
As required by Required C.1 Verify at least two Prior to initiating a release l
Action B.1 and referenced by independent samples of l
Table 12.2-3.
the tank's contents are l
analyzed.
AND t
i C.2 Verify at least two Prior to initiating a release i
j technically qualified j
members of the facility staff independently verify j
the release rate calculations.
i E
f j
C.3 Verify at least two Prior to initiating a release j
technically qualified l
members of the facility staff independently venfy the discharge valve
]
lineup.
i M
C.4.1 Restore the require 14 days i
number of channels to 1
i OPERABLE.
9B i
l C.4.2 Supplement the 12 months Radioactive Effluent 3
Release Report pursuant to Technical Specification
{
5.6.3 with the cause for failure to correct the inoperabiliity.
l (continued) l l
l 12-17 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
I i
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETlON TIME j
1 D.
As required by Required D.1.1 Suspend PURGING via immediately Action 8.1 and referenced by this pathway.
Table 12.2-3.
DB D.1.2 Verify real time Du,ing release monitoring of radioactive effluents released via this pathway.
AND D.2.1 Restore the required 7 days number of channels to OPERABLE.
DB D.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability.
(continued)
O 12-18 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
As required by Required E.1 Estimate flow rate.
Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action B.i and referenced by Table 12.2-3.
AND E.2.1 Restore the required 30 days number of channels to OPERABLE.
M E.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability.
/G F.
As required by Required F.1 Verify samples are During release V
Action B.' e,nd re'erenced by continuously collected with Table ik 2-3.
auxiliary sampling equipment as required by Table 12.4-1.
AND F.2.1 Restore the required 30 days Number of Channels to OPERABLE.
F.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability.
(continued)
,n 12-19 (p3radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
I ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G.
As required by Required G.1 Verify gaseous grab Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and referenced by samples are collected Table 12.2-3.
and analyzed for principle gamma emitters at a Lower Limit of Detection (LLD) as specified in OFFSITE DOSE CALCULATION MANUAL (ODCM) Table 12.4.-1.
AND G.2.1 Restore the required 30 days number of channels to OPEP.ABLE.
O__B G.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability.
H.
Required Action and H.1 Suspend the release of Imrr.cdiately associated Completion Time radioactive gaseous for Conditions C, D, E, F, or G effluent monitored by the not met.
affected channel.
1.
O 12-20 (p:\\radprot\\odem\\by12R1-6. doc) i
BYRON Revi ion 1.6 E
Januaiy 1999 7
i Table 12.2-3 (Page 1 of 3)
Radioactive Gaseous Effluent Monitoring instrumentation REQUIRED SURVEILLANCE INSTRUMENT CHANNELS CONDITION REQUIREMENTS U 1 Plant Vent Monitonng System 1.
Noble Gas Activity Monitor-Providing Alarm a.
High Range (1RE-PR02SD) 1 G
12.2.2 B.1 12.2.2 8.2 12.2.2.B.3(b) 12.2.2.B.4(c) b.
Low Range (1RE-PR0288) 1 G
12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B 4(c) c.
lodine Sampler (IRE-PR02SC) 1 F
12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c) d.
Particulate Sampier (1RE-PR028A) 1 F
12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2 B 4(c) e.
Effluent System Flow Rate Measunng Device i
E 12.2.2.B.1 (LOOP-VA019) 12.2.2.B.3 12.2.2t i f
f.
Sampler Flow Rate Messunng Device (1FT-PR165) 1 E
12.2.2.B.1 l
12.2.2.B 3 l
l 12.2.2 B 4 (continued)
(b)
The CHANNEL OPERATIONAL TEST shall a!so demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the Alarm Setpoint, or 2.
Circutt failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or l
I 3.
Detector check source test failure, or 4.
Detector channel out of-service, or 5.
Monitor loss of sample flow.
(c)
The instal CHANNEL CALIBRATION shall be performed using one or more of the reference standards certifed by the National Bureau of Standards (NBS) or using standards that have been obtained from supplers that participate in measurement assurance activites with NBS.
These standards shall permit calibrating the system over its intended ranDe of energy and measurement range. For subsequent CHANNEL
(
CALIBRATION, sources that have been related to the inital calibration shall be used.
12-21 (p:Vadprot\\odem\\by12R1-6. doc)
J
BYRON Revision 1.6 January 1999 Table 12.2-3 (Page 2 of 3)
Radioactive Gaseous Effluent Monitoring instrumentation REQUIRED SURVEILLANCE INSTRUMENT CHANNELS CONDITION REQUtREMENTS U 2 Plant Vent Monitonng System 2.
Noble Gas Actrvty Monitor - Providing Alarm a
High Range (2RE-PR0280) 1 G
12.2.2.B 1 12.2.2.B.2 12.2.2.B2(b) 12.2.2.B.4(c) b Low Range.(2RE-PR0288) 1 G
12.2.2.B.1 12.2.2.B 2 1212.B.3(b) 12.2.2.B 4(c) c lodine Sampler (2RE-PR028C) 1 F
12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c) d.
Partculate Sampler (2RE-PR028A) 1 F
12.2.2.B.1 12.2.2.B 2 12.2.2.8.3(b)
{
)
12.2.2.B 4(c) e.
Effluent System Flow Rate Measunng i
E 12.2.2.B.1 Devce (LOOP-VA020) 12.2.2.B.3 12.2.2.B 4 f.
Sampier Flow Rate Measunng Device 1
E 12 2.2.B.1 (2FT-PR165) 12.2.2.B 3 12.2.2.B 4 3.
Refer to Techncal Requirements Manual 3 3 e for Gaseous Waste Management Explosive Gas Monitonng instrumentation (continued)
(b)
The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditons easts:
1.
Instrument od cates measured levels above the Alarm Setpoint, or 2.
Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or 3.
Detector check source test failure, or 4
Detector channel out of-service. or 5.
Monitor loss of sample flow.
(c)
The 6nitial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that partcipate en measurement assurance activtties with NBS.
These standards shall permit cahbrating the system over its intended range of energy and measurement range. For subsequent g
CAllBRATION, sources that have been related to the initial calibration shall be used.
12-22 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 Table 12.2-3 (Page 3 of 2)
Radioactive Gaseous Effluent Monitonng instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS 4
Gas Decay Tank System Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release 2
C 12.2.2.B.3(a)
(ORE-PR002A and 28) 12.2.2.B 4(c) 12.2.2.B.5 12.2.2.B 6 5
Containment Purge System 1
D 12.2.2.B.1 12.2.2.B.3(b) a Noble Gas Activity Monitor Providing Alarm 12,2.2.B Ac) 12.2.2 B 6 (1/2RE-PR001 B) b lodine SLmpler (1/2RE-PR001C) 1 F
12.2.2 B.4(c) 12.2.2.B 5 12.2.2.8 6
- c. Partculate Sampler (1/2RE-PR001 A) 1 F
12.2.2 8 4(c) 12.2.2.B 5 12.2.2 B 6 (a)
The CHANNEL OPERATIONAL TEST shall also oemonstrate that automote isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the Alarm / Trip Setpoint, or 2.
Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or 3
Detector check source test failure. or 4
Detector channel out-of-service, or 5.
Monitor loss of sample flow (b)
The CHANNEL OPERATIONAL TEST shall also demonstrate that control room starm annunciation occurs if any of the following conditions exists 1.
Instrument sndicates measured levels above the Alarm Retpoint, or 2.
Circuit faAure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or 3.
Petector check source test failure, or 4.
Detector channel out-of. service, or 5.
Monitor loss of sample flow (c)
The initia' JHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.
S 12-23 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 199 Table 12.2-4 SURVEILLANCE REQUIREMENTS NOTES 1.
Refer to Table 12.2-3 to determine which Surveillance Requirements apply to each instrument.
2.
Alarm / Trip Setpoints shall be set to ensure that the limits of 12.4.1.A and Technical Specification 5.5.12 are not exceeded. The Alarm / Trip Setpoints of these channels meeting 12.4.1.A shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
SURVEILLANCE I
FREQUENCY 12.2.2.B.1 Perform a CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 12.2.2.B.2 Perform a SOURCE CHECK.
31 days 12.2.2.B.3 Perform a CHANNEL OPERATIONAL TEST.
92 days 12.2.2.B.4 Perform a CHANNEL CALIBRATION.
18 months 12.2.2.B.5 Perform a CHANNEL CHECK.
Prior to each release 12.2.2.B.6 Perform a SOURCE CHECK.
Prior to each release O
12-24 (p:\\radprot\\odem\\by12R1-6. doc)
=.
l BYRON Revision 1 G l
January 1999 i
1 4
12.3 RADIOLOGICAL EFFLUENTS (RE) LIQUID i
12.3.2 Dose From Liquid Effluents i
12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in j
liquid effluents, from each unit, to UNRESTRICTED AREAS (see Byron Station OFFSITE I
DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F Figure F-1) shall be limited:
i 1.
During any calendar quarter to s 1.5 mrem to the whole body and to s 5 mrem to any organ, and
[
t 2.
During any calendar year to s 3 mrem to the whole body and to s 10 mrem to any i
organ.
4 i
i i
i i
t APPLICABILITY:
At all times.
l l
1
!o i
l t
l l
i 1
i I
i
.i i
i i
1 i
P l
l s
12-31 (p:\\radprotedcm\\by12R16. doc)
BYRON Revision 1.6 January 1999O ACTIONS NOTES l
1.
Separate Condition entry is allowed for each dose.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated dose exceeding A.1 Submit Special Report to the 30 days above limits.
Commission that identifies the cause(s) for exceeding the limit (s) and defines the i
corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent j
}
releases will be in compliance with the above limits.
l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.3.2.B Determine cumulative dose contributions from hquid 31 days effluents for the current calendar quarter and the current calendar year.
O 12-32 (p:\\radprot\\odem\\by12R1-6. doc)
-. - = -.
BYRON l
Revision 1.6 e
January 1999 O
Table 12.3-1 (Page 4 of 4)
Radioactive Liquid Waste Sampling and Analysis Program i
Note 1 Lower Limit of Detection (LLD)
The LLD is defined, for purposes of these Technical Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
i 4.66 ss yy E
- V
- 2.22 x 10*
- Y
- exp (-Ahr) t i
Where:
LLD = the lower limit of detection (microCuries per unit mass or volume),
l s=
the standard deviation of the background counting rate or of the counting rate of a blank o
sample as appropriate (counts per minute),
E=
the counting efficiency (counts per disintegration),
V=
the sample size (units of mass or volume),
8 2.22 x 10 = the number of disintegrations per minute per microcurie, 1
Y=
the fractional radiochemical yield, when applicable, d
A=
the radioactive decay constant for the particular radionuclide (sec ), and l
1 At = the elapsed time between the midpoint of sample collection and the time of counting J
(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.
e O
i 12-30 (p:\\radprot\\odem\\by12R1-6. doc) i
BYRON Revision 1.6 January 1999 l
I Table 12.3-1 (Page 3 of 4)
Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD)
SAMPLING ANALYSIS TYPE OF ACTIVITY
( Cuml)(Refer to Note 1 LIQUlO RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30) 3 Continuous W(0 W(0 Pnncipal Gamma Emitters 5 x 10~'
Release (d)
Grab Sample (b)
Essential 1-131 1 x 10*
Sennce Water Reactor Dissolved and Entrained 1x104 Containment Fan Gases (Gamma Emitters)
Cooler (RCFC)
Outlet Line H-3 1 x 10 *
(b)
The pnncipal gamma emdters 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 Co-141, and Ce-144 This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identif6able, together with those of the above nuclides. shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5 6.3 in the format outlined in Regulatory Guide 121, Appendix B, Revision 1, June 1974.
(d)
A continuous reiease is the discharge of liquid wastes of a nondiscrete volume, e g, from a volume of a system that has an input flow dunng {
the continuous release.
(f)
Not required unless the Essential Service Water RCFC Outlet Radiation Monitors 1/2RE-PR002 and 1/2RE-PR003 indicates measured levels greater than 1 x 10* pCi/mi sbove background at any time during the week.
O 12-29 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON l
- Revision 1.6 January 1999 o
1 12.3 RADIOLOGICAL EFFLUENTS (RE)- LIQUID 12.3.1 Concentration Limits for Effluents 12.3.1.A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or t
entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10" Ci/ml total activity.
APPLICABILITY:
At all times.
ACTIONS
[
NOTES 1.
Separate Condition entry is allowed for each release.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Concentration of radioactive A,1 Restore the immediately material released exceeding concentration within the limit.
limit.
O.B i
i A.2 Terminate the release.
immediately I
I i
12-25 (p:\\rodprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 i
l SURVEILLANCE REQUIREMENTS NOTES
- 1. All Surveillance Requirements to be performed at frequency defined by Table 12.3-1.
- 2. 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 release are maintained within the limits of 12.3.1.A.
SURVEILLANCE FREQUENCY 12.3.1.B Sample and analyze liquid wastes.
Per Table 12.3-1 O
O 12-26 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 Table 12.3-1 (Page 1 of 4)
Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD)
SAMPLING ANALYSIS TYPE OF ACTIVITY
( C6/ml)(Refer to Note 1.
l LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30) 1.
Batch Release Tanks P
P Pnneipal Gamma Emitters 5x10 (a)
Each Batch Each Batch (b) 1-131 1 x 10
P M
Dissolved and Entrained 1 x 10
One Batch /M Gases (Gamma Emitters)
P M
H-3 1 x 10
Each Batch Composite (c)
P Q
Gross Alpha 1x10' Each Batch Composite (C)
Sr-89, Sr-90 5 x 10 '
Fe-55 1 x 10
l (continued)
(a)
A batch release is the discharge of liquid wastes of a discrete volume Pnor to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.
(b)
The pnncipal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59. Co 58, Co40, Zn45. Mo-99. Cs-134 Cs 137, Ce 141, and Ce-144 This list does not mean that only these nuclides are to be consiaered. 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 Specification 5 6 3 in the format outlined in Regulatory Guide 121, Appendix B, Revision 1, June 1974 (c)
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.
I 12-27 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
l Table 12.3-1 (Page 2 of 4)
Radioactive Liquid Waste Sampling and Analysis Program 1
I LOWER LIMIT OF l
MINIMUM DETE". TION (LLD)
SAMPLING ANALYSIS TYPE OF ACTIVITY
( Ci/ml)(Refer to Note 1, LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12 30) 2 Continuous (e)
W Pnncipal Gamma Emitters (b) 5x10#
Continuous Releases (d)
Composite (')
1131 1 x 10*
a Circulating Water M
M Dissolved and Entrained 1 x 10*
Blowdown Grab Sample Gases (Gamma Emitters) b Waste Water Continuoust')
M H-3 1 x 10*
Treatement Composite (8)
System Discharge Gross Alpha 1x10" to Fiume c Condensate Continuous (')
Q Sr-89. Sr 90 5x10*
Pohsher Sump Composde(')
Discharge Fe-55 1x10*
(continued) g (b)
The principal gamma emitters for which the LLD specification apphes include the following radionuchdes: Mn-54, Fe-59, Co 58, Co-60. Zre 65, Mo99, Cs-134 Cs-137, Co-141, and Ce-144 This hst does not mean that only these nuchdes.re to be consdered. Other gamma peaks that are identifiable, together with those of the above nuchdes, shall also be analyzed and reported in the Radioactrve Emuent Release Report pursuant to Specification 5 6.3 in the format outhned in Regulatory Guide 1.21, Appendix B, Revision 1. June 1974.
(d)
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 dunng the continuous release.
(e)
To be representative of the quantities and concentrations of radioactrve matenals in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the offluent stream Pnor to analyses, all samples taken for the composite shall be thoroughty mixed en order for the composite sample to be representative of the effluent release.
O 12-28 (p:\\radprot\\odem\\by12R1-6. doc)
.~
BYRON Revision 1.6 January 1999 O
.3 RADIOLOGICAL EFFLUENTS (RE)- LIQUID 12 j
12.3.3 Liquid Radwaste Treatment System 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and shall be used to reduce releases from each unit to UNRESTRICTED AREAS (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F Figure F-1) when the projected dose
]
would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.
l APPLICABILITY:
At all times.
f i
7 r
s i
i r
i 12-33 (p:\\radprot\\odem\\by12R1-6. doc) i
BYRON Revision 1.6 January 1999 I
I ACTIONS NOTES 1.
Separate Condition entry is allowed for each release.
2.
TLCO 3.0.c is not applicable.
J.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Radioactive liquid waste being A.1 Submit Special Report to the 30 days discharged without treatment.
Commission that includes an explanation of why liquid AEQ radwaste was being discharged without treatment, in excess of above limits.
identification of any inoperable equipment or subsystems, and 63Q the reason for the inoperability; action (s) taken to Any portion of the Liquid restore the inoperable
{
}
Radwaste Treatment System equipment to OPERABLE not in operation.
status; and a summary description of actions (s) taken to prevent recurrence.
O 12-34 (g\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 I
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.3.3.B.1 NOTE--
Only required to be performed when the Liquid l
Radwaste Treatment System is not fully utilized.
i Project doses due to liquid releases from each unit to 31 days
{
UNRESTRICTED AREAS.
12.3.3.B.2 Verify the installed Liquid Radwaste Treatment Per the applicable System is OPERABLE by meeting the requirements of Surveillance Requirements 12.3.1.A and 12.3.2.A.
f D
i i
D 12-35 (p:\\radprot\\odcm\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
l 12.4 RADIOLOGICAL EFFLUENTS (RE)- GASEOUS 12.4.1 Dose Rate for Gaseous Effluent 12.4.1. A The dose rate in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-1) shall be limited to:
1.
For noble gases: s 500 mrem /yr to the whole body and s 3000 mrem /yr to the skin, and 2.
For lodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives > 8 days: s 1500 mrem /yr to any organ.
APPLICABILITY:
At all times.
ACTIONS NOTES 1.
Separate Condition entry is allowed for each dose rate.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
l l
CONDITION REQUIRED ACTION COMPLETION TIME A.
Dose rate exceeding above A.1 Restore the release rate to Immediately limits.
Within limits.
O 12-36 (p:Vadprot\\odemiby12R1-6. doc)
t BYRON Revision 1.6 January 1999 i
i a
SURVEILLANCE REQUIREMENTS j
4 0
l SURVEILLANCE FREQUENCY i
J 12.4.1.B.1 Determine dose rate due to noble gases within limits.
Per Table 12.4-1 I
i j
12.4.1.B.2 Determine dose rate due to 1-131,1-133, tritium and all Per Table 12.4-1 4
other radionuclides in particulate form with half-lives
{
l
> 8 days within limits.
i 1
i i
1 O
i f
i I
f 12-37 i
(p:Vadprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 Table 12.4-1 (Page 1 of 3)
Radioactive Gaseous Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD)
GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY
( Ci/m!)(Refer to Note 1, TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30) 1.
Waste Gas Decay P
P Pnncipal Gamma Emitters 1x10*
Tank Each Tank Each Tank (a)
Grab Sample 2.
Containment Purge P
Each PURGE (b)
Pnncipal Gamma Emitters 1 x 10*
Each PURGE (b)
Grab Sample (a)
Grab Sample H-3 1 x 10 '
(continued)
(a)
The pnncipal gamma emitters for which the LLD specification applies include the following radionuchdes: 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-99,6-131, Cs 134. Cs-137, Ce-141, and Co-144 in iodine and particulate releases. Th:s hst 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 Specifcation S 6 3, in the format outlined in Regulatory Guide 121, Appendix B, Revtsson 1 June 1974.
(b)
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 O
12-38 (p:\\radprot\\odCm\\by12R1-6. doc)
I
BYRON Revision 1.6 January 1999 Table 12.4-1 (Page 2 Of 3)
Radioactive Gaseous Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD)
SAMPLING ANALYSIS TYPE OF ACTIVITY
( Ci/ml)(Refer to Note 1, l
GASEOUS RELEASE FREQUENCY FREQUENCY ANALYSIS Page 12-40)
TYPE s
i 3 Auxiliary Building Vent M(c)(d)
M Pnncipal Gamma Emitters 1 x 10'
{
Stack (Units 1 and 2)
Grab Sample (a) 3 H-3 1 x 10 4
Continuous (')
Wl0 1131 1 x 10"'
I Charcoal Sample l
1-133 1 x 10""
ContinuousW Wl9 Pnncipal Gamma Emitters 1 x 10'"
Charcoal Sample (a) 1 Continuous (')
Q Gross Alpha 1 x 10~"
i Composite Particulate Sample Continuous (')
Q Sr-89, St-90 1 x 10'"
Composite Particulate Sample Continuous N.A.
Noble Gases; 1x16' Noble Gas Gross Beta or Gamma Monitor (a)
The pnncipal gamma emitters for which the LLD specification apphes include the following radionuclides: Kr-87, Kr-88. Xe-133, Xe-133m, Xe-135, and Xe-138 in nob 6e gas releases and Mn-54. Fe-59. Co-58 Co-60, Zn-65, Mo-99,1-131 Cs-134, Cs-137 Ce-141. and Co.144 in iodine and particulate releases. This list does not mean that only these nuchdes 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 Specification 5 6 3. In the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
(c)
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.
(d)
Tritium gran samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
(e)
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time penod covered by each dose or dose rate calculation made in accordance with 12.4.1,12.4.2, and 12.4 3.
(f)
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 sampier. 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 penod 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.
v 12-39 (p:\\radprot\\odcm\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
Table 12.4-1 (Page 3 of 3)
Radioactive Gaseous Waste Sampling and Analysis Program Note 1 Lower Limit of Detection (LLD)
The LLD is defined, for purposes of these Technical Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD-E
- V
- 2.22 x 10'
- Y
- exp(-AAr)
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 o
sample a.; appropnate (counts per minute),
E=
the counting efficiency (counts per disintegration),
V=
the sample size (units of mass or volume),
6 2.22 x 10 = the nurnber of disintegrations per minute per microcurie, Y=
the fractional radiochemical yield, when applicable, A=
the radioactive decay constant for the particular radionuclide (sec-1), 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 ut,ed 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.
O 12-40 (p:\\radprot\\odem\\by12R1-6. doc)
I i
BYRON i
Revision 1.6 January 1999 O
12.4 RADIOLOGICAL EFFLUENTS (RE)- GASEOUS 12.4.2 Dose - Noble Gases 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 / UNRESTRICTED AREA boundary (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F Figure F-1) shah be limited to:
1)
During any calendar quarter: s 5 mrad for gamma radiation and s 10 mrad for beta radiation, and 2)
During any calendar year: s 10 mrad for gamma radiation and s 20 mrad for beta radiation.
APPLICABILITY:
At all times.
I h
O i
OL) 12-41 (p:Vadprot\\odem\\by12R1-6. doc) l
\\
\\
BYRON Revision 1.6 January 1999 ACTIONS NOTES 1.
Separate Condition entry is allowed for each air dose.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated air dose exceeding A.1 Submit a Special Report to the 30 days limit.
Commirsion that identifies the cause(s) for exceeding the limits (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 REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.2.B Determine cumulative dose contributions for noble 31 days gases for the current calendar quarter and current calendar year.
O 12-42 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 -
12.4 RADIOLOGICAL EFFLUENTS (RE)- GASEOUS 12.4.3 Dose - I-131,1-133, Tritium, and Radioactive Matenal in Particulate Form.
12.4.3. A The dose to a MEMBER OF THE PUBLIC from I-131,1-133, tritium, and all radionuclides in particulate form with half-lives > 8 dcys in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA boundary (see BYRON Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F. Figure F-1) shall be limited to:
1)
During any calendar quarter: s 7.5 mrem to any organ, and 2)
During any calendar year. s 15 mrem to any organ.
APPLICABILITY:
At all times.
D j
D 12-43 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 199 ACTIONS l
NOTES 1.
Separate Condition entry is allowed for each calculated dose.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated dose exceeding A.1 Submit a Special Report to the 30 days limit.
Commission that identifies the cause(s) for exceeding the limit 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.
O 12-44 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.3 B Determine cumulative dose contributions for lodine.
31 days 131 and 133, tritium, and radionuclides in particulate form with half lives > 8 days for the current calendar quarter and current calendar year.
i
(
i i
O 12-45 (p:Vadprot\\odem\\by12R1-6. doc)
~
BYRON Revision 1.6 January 1999 12.4 RADIOLOGICAL EFFLUENTS (RE)- GASEOUS 12.4.4 Gaseous Radwaste Treatment System 12.4.4. A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and shall be used to reduce activity in releases, from each unit, of gaseous effluents when the projected doses at and beyond the SITE BOUNDARY / UNRESTRICTED AREA boundary (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F. Figure F-1) in 31 days would exceed:
1) 0.2 mrad to air from gamma radiation, 2) 0.4 mrad to air from beta radiation, or 3) 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY:
At all times.
O O
12-46 (p:Vadprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 ACTIONS NOTES 1.
Separate Condition entry is allowed for each gaseous release.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
-NOTE A.1 Submit a Special Report to the 30 days Only applicable if radioactive Commission that includes the gaseous waste being following information:
discharged without treatment.
a.
Identification of any inoperable equipment or Gaseous releases in excess subsystems, and the reason v
of limit.
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 recurrence.
i 12-47 (p:Vadprot\\odem\\by12R1-6. doc)
BYRGN Revision 1.6 I
SURVElLLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.4.B.1 NOTE Only required to be performed when the Gaseous Radwaste Treatment Systems are not being fully utilized.
Project doses due to gaseous releases from each unit 31 days to areas at or beyond the SITE BOUNDARY / UNRESTRICTED AREA boundary.
12.4.4.B.2 Verify the installed VENTILATION EXHAUST Perthe applicable TREATMENT SYSTEM and WASTE GAS HOLDUP Surveillance SYSTEM are OPERABLE by meeting Surveillance Requirements Requirements 12.4.1.B and 12.4.2.8 or 12.4.3.8.
O O
(p:Vadprotiodem\\by12R1-6. doc)
l b
BYRON Revision 1.6 i
January 1999 i
i 12.4 RADIOLOGICAL EFFLUENTS (RE)- GASEOUS 4
4 12.4.5 Total Dose i
j 5
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 the uranium fuel cycle sources shall be
)
limited to s 25 mrem to the whole body or any organ (except the thyroid) and s 75 mrem to j
the thyroid.
I APPLICABILITY:
At all times, 4
4 ACTIONS NOTES i
1.
Separate Condition entry is allowed for each calculated dose.
2.
TLCO 3.0.c is not applicable.
3.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated doses exceeding A.1 -
--NOTE twice the limits for:
Calculations to include direct 12.3.2.A.1 radiation contributions from the l
12.3.2.A.2 units and from outside storage 12.4.2.A.1 tanks.
j 12.4.2.A.2 12.4.3.A.1 or 12.4.3.A.2 Determine if the 12.4.5.A limits 15 days have been exceeded.
i (continued) i
- p-12-49
.(p:\\radprot\\odem\\by12R1-6. doc) t
BYRON Revision 1.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action of Condition B.1 Submit a Special Report to the 15 days A determines the 12.4.5.A Commission (Refer to Note 1, limits have been exceeded.
Page 12-51).
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.5.B.1 NOTE Only applicable if Condition A is entered.
Determine cumulative dose contributions from direct in accordance with the radiation from the units and from radwaste storage tanks.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 12.4.5.B.2 Determine cumbNtive dose contnbutions from liquid and Per the applicable gaseous effluents tri accordance with Surveillance Surveillance Requirements Requirements 12.3.2.B,12.4.2.B and 12.4.3.B and in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
12.4.5.B.3 inspect the Old Steam Generator Storage Facility 92 days (OSGSF) sump for the presence of liquid and the appearance that seepage has occurred.
12.4.5.B.4 NOTE Only required to be performed if 12.4.5.B.3 identifies both the presence of liquid and indications of seepage.
Sample and analyze the liquid from the OSGSF sump.
92 days 12-50 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 n
v NOTE 1 The Special Report shall define the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the 12.4.5.A limits and includes the schedule for achieving conformance with the 12.4.5.A limits. The Special Report, as defined by 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC from the uranium cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive materialinvolved, and the cause of the exposure levels or concentrations.
If the estimated dose (s) exceeds the 12.4.5.A limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely response and a variance is granted until staff action on the request is complete.
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l 12-51 l
(p:\\radprot\\odem\\by12R16. doc) 4
BYRON Revision 1.6 January 1999 O 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Radiological Environmental Monitoring Program 12.5.1. A The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 12.5-1.
APPLICABILITY:
At all times.
ACTIONS NOTES 1.
TLCO 3.0.c is not applicable.
2.
TLCO 3.0.d is not applicable.
l I
CONDITION REQUIRED ACTION COMPLETION TIME A.
REMP not being conducted A.1 Submit in the Annual Radiological 12 months as specified in Table Environmental Operating Report, 12.5-1.
as required by Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing recurrence.
(continueti) 0 12-52 (p:\\radprot\\odem\\by12R1-6. doc)
l BYRON Revision 1.6 I
January 1999 i
ACTIONS (continued) l l
CONDITION REQUIRED ACTION COMPLETION TIME l
NOTE l
B.
Level of radioactivity as a B.1 The methodology and result of plant effluents in an parameters used to estimate environmental sampling the potential annual dose to medium at a specified a MEMBER OF THE l
location exceeding the PUBLIC shall be indicated in reporting limits of Table this report.
12.5-2 when averaged over any calendar quarter.
Submit a Special Report to 30 days the Commission that l
identifies the cause(s) for j
exceeding the limit (s) and l
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 yearlimits of 12.3.2.A,12.4.2.A, and s
l 12.4.3.A.
(continued) l 3
12-53 (p:\\radprot\\odem\\by12R1-6. doc) -
BYRON Revision 1.6 January 1999 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
More than one of the C.1 NOTE radionuclides in Table 12.5-2 The methodology and parameters are detected in the sampling used to estimate the potential medium.
annual dose to a MEMBER OF THE PUBLIC shall be indicated in AND this report.
Ci C2
+
+. 2 1.0 Submit a Special Report to the RL, RL2 Commission that identifies the 30 days cause(s) for exceeding the limit (s) where; and defines the corrective actions C = cot;c",ntration to be taken to reduce radioactive RL = reporting level.
effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of 12.3.2.A, 12.4.2.A, and 12.4.3.A.
(continued) e 12-54 (p:\\radprot\\odem\\by12R1-6. doc) l 3
BYRON Revision 1.6 January 1999 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Radionuclides other than D.1 NOTE those in Table 12.5-2 are The methodology and parameters detected.
used to estimate the potential annual dose to a MEMBER OF AND THE PUBLIC shall be indicated in this report.
Are the result of plant effluents.
Submit a Special Report to the AND Commission that identifies the 30 days cause(s) for exceeding the limit (s) l The potential annual dose to and defines the corrective actions a MEMBER OF THE PUBLIC to be taken to reduce radioactive from all radionuclides is equal effluents so that the potential to or greater than the annual dose to a MEMBER OF calendar limits of 12.3.2.A, THE PUBLIC is less than the 12.4.2.A and 12.4.3.A.
calendar year limits of 12.3.2.A, 12.4.2.A. and 12.4.3.A.
E.
Measured levels of E.1 Report and describe the condition 12 months radioactivity not the result r'f in the Annual Radiological plant effluents.
Environmental Operating Report required by Specification 5.6.2.
(continued)
)
i 12-55 (p:\\radprot\\odcm\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 l
l ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F.
Milk or fresh leafy F.1 Identify specific locations for 30 days vegetable samples obtaining replacement samples 1
unavailable from one or more and add them to the REMP given of the sample locations in the OFFSITE DOSE required by Table 12.5-1.
CALCULATION MANUAL (ODCM).
AND F.2 Submit controlled version of the 180 days ODCM to the NRC including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples, deleting the specific locations from which samples were unavailable and justifying the selection of the new q
g location (s) for obtaining samples.
12-56 (p:\\radprot\\odem\\by12R1-6. doc)
l BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.5.1 B The radiological environmental monitoring samples Per the applicable shall be collected pursuant to Table 12.5-1 from the Table (s) 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.
D l
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I 12-57 (p:\\radprotbacm\\by12R1-6. doc) i
BYRON Revision 1.6 January 1999 l
I Table 12.5-1 (Page 1 of 5)
Rarisological Environmental Monitofing Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS (a)
FREQUENCY TYPE /FREOUENCY OF ANALYSIS SAMPLE 1.
Airbome Samples from a total of eight locations:
Continuous Epdknodine Catster Radosod!ne and sampler operaten 1-131 anatysis tx-weekly on nept feld Partculates a.
Indicator Near Feld with sample samples and control.(b) collection weekly Four samples from locatons within 4 (or more frequently EEtculate Samoler:
km (2.5 mi)in different sectors.
if required due to Gross beta analysis following weekly dust loading).
filter change (C) and gamma isotopic b.
Indicator - Far Field analysis (d) quarterly on composite filters by location on near feld samples and Three additonal locations within 4 to 10 control,(b) km (2 5 to 6 2 mi)in different sectors.
c.
Control One sample from a controllocaton within 10 to 30 km (6 2 to 18 6 mi)
(continued)
(a)
Specife parameters of distance and directen from the centerline of the midpoint of the two units and additional desenpton where pertinent, shall be provided for each and every sampie locaten in Table 11 1 of the ODCM Station Annexes. Refer to NUREG-0133," Preparation of Radiological Effluent Techncal Specifcatons for Nuclear Power Plants," October 1978, and to Radological Assessment Branch Technical Position, Revison 1, November 1979 (b)
Far field samples are analyzed when the respective near field sample results are inconsistent with prevous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Health Physcs Support Director.
(c)
Airbome partculate sampie filters snall be analyzed for gross beta radioacuvity 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 daughter decay. If gross beta actrvity in air partculate samples is greater than 10 times the yearty mean of control samples, gamma isotope analysis shall be performed on the ind:vidual samples (d)
Gamma isotopic anatysis means the identification and quantifcation e' gamma emitting radionuclides that may be attnbutable to the effluents from the station.
O 12-58 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 2 Of 5)
Radiological Environmental Monitonng Program SAMPLING AND l
EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS (a)
FREQUENCY TYPE / FREQUENCY OF ANALYSIS SAMPLE
- 2. Direct Radiation (*)
Forty routine monitonng stations erther with a Quarterty.
Gamma dose on each TLD quarterty.
thermoluminescent dosimeter (TLD) or with I
one instrument for measunng dose rate continuously, placed as fullows.
a.
Indicator - Inner Ring (100 Senes TLD)
One in each meteorological sector, in the generalarea of the SITE BOUNDARY; b.
Indicator - Outer Ring (200 Senes TLD)
One in each meteorological sector, within 6 to 8 km (3 7 to 5 0 mi); and
- c. Other f
I One at each Location given in part 1.a and 1.b.
The balance of the TLDs to be placed at special interest locations beyond the restncted locations beyond the Restncted Area where either a MEMBER OF THE PUBLIC or Commonweaith Edison employees have routine access (300 Senes TLD).
d Control One at each Airbome controllocation grven in part 1.c.
l (continued)
(a)
Specifc parameters of distance and directen from the centerline of the midpoint of the two units and additional desenption where pertinent, shall be prowded for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133," Preparation of Radiological Effluent Techncal Specifcations for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979 (0)
One or more instruments such as a pressunzed ion chamber, for measunng and recording dose rate continuuusly may be used in place of, or in additon to, integrating dosimeters. Film badges shall not be used as dosameters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitonng stations may be reduced according to geographicallimitations; e g.. if a statKm is i
ad}acent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the charactenstics of the specific system used and should be selected to obtain optimum dose information with minimal fading l
12-59 (p;\\radprot\\odem\\by12R1-6. doc) l
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 3 of 5)
Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS (a)
FREQUENCY TYPE / FREQUENCY OF ANA'., SIS SAMPLE 3 Waterbome a Ground /Well
- a. Indicator Quarterty Gamma isotopic (d) and tr*. lum analysis quarterty.
Samples from three sources only if likely to be affected.(0 b Dnnking(g)
- a. Indcator Weekly grab Gross beta and gamma isotope samples analyses (d) on monthly composite; Some sample from each community tntium analysis on quarterly composite.
dnnking water supply that could be affected by the stat:on discharge within 10 km (6.2 mi) downstream of discharge.
- c. Surface Water (g)
If no community water supply (Dnnking Weekly gram Gross beta and gamma isotopic Water) exists within 10 km downstream of samples analyses (d) on monthly composde; discharge then surface water sampling shall tntium analysis on quarterly composte.
be performed a Indcator One sample downstream.
- d. Control Sample (g) a Control Weekly grab Gross beta and gamma isotope samples analyses (d) on monthly composite; One surface sample upstream of tntium analysis on quarterty composite.
discharge
- e. Sediment a.
Indicator Semiannually Gamma isotopic aru ps(d) semiannually.
At least one sample from downstream (9) area within 10 km (6 2 mi) distance (continued)
(a)
Specifc parameters of d$tance and direction from the centerline of the midpoint of the two units and additonal desenption where pertinent, shall be provided for each and every sample locaton in Table 11-1 of the ODCM Staten Annexes. Refer to NUREG-0133,"Preparaton of Radmiogeal Effluent Techncal Specifcatens for Nuclear Power Plants," October 1978. and to Radiologeal Assessment Branch Techncal Positen, Revision 1, November 1979.
(d)
Gamma isotopc analysis means the K$entification and quantification of gamma emitting radionuchdes that may be a*tnbutable to the effsuents from the station.
(f)
Groundwater samples shall be taken when this source is tapped for dnnking or irngation purposes in areas where the hydraute gradient or recharge properties are suitable for contamination.
(g)
The " downstream" sample shall be taken in an area beyond but near the mixing zone. The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough up upstream to be beyond the staten influence.
O 12-60 (p:\\radprotiodcm\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 V
Table 12.5-1 (Page 4 of 5)
Radiological Environmental Monitonna Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS (a)
FREQUENCY TYPE / FREQUENCY OF ANALYSIS SAMPLE I
4 Ingestion
- a. Milk (h) a.
Indcator Brweekly(i) when Gamma isotopic (d) and 1-1310) analysis animais are on on each sample.
Samples from milking pasture (May animals from a maximum of through October),
three locaticns within monthly at other 10 km (6 2 mi) distance.
times (November through Apn!)
b Control One sample from milking animals at a control location witNn 15 to 30 km (9 3 to 18 6 mi).
- b. Fish a.
Indcator Two timas Gamma isotopic analysis (d) on edible annually portions.
Representative samples of commercially and recreationally important species in discharge area
- b. Control Representative samples of commercially and recreationally important soecies in control locations upstream of discharge (continued)
(D)
Specife parameters of distance and direction from the centerline of the midpoint of the two units and additional desenption where pertinent, shall be provided for each and every sample location n Table 11 1 of the ODCM Station Annexes. Refer to NUREG-0133 " Preparation of Radiolog cal Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radological Assessment Branch Technical Positen, Revison 1, November 1979.
(d)
Gamma isotopc analysis means the identification and quantificaton of gamma emitting radionuclides that may be attnbutable to the effluents from the staten.
(h)
If milking animais are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all mi:k sampling shall be discontinued.
(i)
Btweekty refers to every two weeks Q) 1131 analysis means the analytical separation and counting procedure are specific for this radonuclide.
O 12-61 (p:\\radprot\\odem\\by12R1-6. doc)
i BYRON Revision 1.6 January 1999 I
I Table 12.5-1 (Page 5 of 5)
Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS (a)
FREQUENCY TYPE / FREQUENCY OF ANALYSIS SAMPLE 4 Ingestion (continued)
- c. Food Products a Indcator Annually.
Gamma isotopic (d) analysis on each sample.
Two representative samples from the pnncipal food pathways grown in each of four major quadrants within 10 km (6.2 mi)~
At least one root vegetable sample (N)
At least one broad leaf Vegetable (or vegetation) l h
(k).
4 b.
Control Two representative samples similar to indcator samples grown within 1S to 30 km (9 3 to 18 6 mi)
(a)
Specife parameters of distance and direction from the centerline of the midpoint of the two units and additional desenption where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG4133,"Preparaton of Radiological Effluent Techncal Specifcations for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Techncal Pos. tion, Revision 1, November 1979.
(6)
Gamma isotopic analyss means the identification and quantification of gamma emitting radionuclides that may be attnbutable to the effluents from the station, (k)
One sample shall consist of a volume /weght of sample large enough to fill contractor specified container.
O 12-62 (p:\\radprot\\odern\\by12R1-6. doc)
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BYRON Revision 1.6 January 1999
)
Table 12.5-2 (Page 1 of 1)
Reporting Levels for Radioactivity Concentrations in Environmental Samples AIRBORNE PARTICULATE FISH (pCi/kg. wet)
FOOD
[
ANALYSIS WATER (pCl/l)
OR GASES MILK (pCill)
PRODUCTS
[
(pCi/m')
(pCi/kg. wet)
Mn-54 1.000 30.000 Fe-59 400 10.000 Co-58 1.000 30.000 Co40 300 10.000 Zn-65 300 20.000 Zr-Nb-95 400 1-131 2(b) og 3
1og Cs 134 30 10 1.000 60 1.000 Cs-137 50 20 2.000 70 2.000 Ba-La-140 200 300 L
(a)
For dnnking water samples This is 40 CFR Part 141 value. If no dnnking water pathway exists. a value of 30,000 pCill may be used.
(b)
If no dnnking water pathway exists. a value of 20 pCi/l may be used.
/
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s.)
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I
BYRON Revision 1.6 January 1999 I
I Table 12.5-3 (Page 1 of 2)
Detection Capabilities for Environmental Sample Analysis (a)
Lower Limit of Detection (LLD)(b) (Refer to Note 1. Page 12-65)
AIRBORNE PARTICULAT SEDIMENT E OR GAS FISH (pCi/kg, FOOD (pCvkg, dry)
ANALYSIS WATER (pCA)
(pCVm')
wet)
MILK (pCvi)
PRODUCTS (pCi/kg. wet)
Gross Beta 4
0 01 1000 H3 2000(e)
Mn-54 15 130 Fe-59 30 260 Co-58.60 15 130 Zn45 30 260 Zr-Nt>-95 15 l-131 1/15(c) 0 07 100 05/5W 60 Cs 134 15 0 01 100 15 60 150 Cs-137 18 0 01 100 18 80 180 Ba-La.140 15 15 (a)
This bst does not mean that only these nuchdes are to be cons 4ered Other peaks at are identifiable, together with those of the above nucides. Shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specerication 56.2.
(b)
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 413.
(c)
If no dnnking water pathway exists, the value of 15 pCd may be used (d)
A value of 0 5 pCd shall be used when the animals are on pasture (May througn October) and a value of 5 pCd shall be used at all other times (Novemberthrough Apol).
(e)
This LLD is the minimum allowable, however, vendors performing environmental sample analyses offsite will be required to meet an LLD of 200 pCd.
O 12-64 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 Table 12.5-3 (Page 2 of 2)
Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)
Note 1: Lower Limit of Detection (LLD) i The LLD is defined. for purposes of these Technical Requirements, as the smallest concentration of radioactive matenal in a sample that will yield a not l
count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation l
represents a "real" sgnal.
l l
Fct a particular measurement system, which may include radiochemical separation:
4'66 s*
LLD= E
- V
- 2.22
- Y
- exp(-M r)
Whers LLD = the "a pnon" lower limit of detection (picoCunes per unit mass or volume),
s, =
the standard deviation of the background counting rate or of the counting rate of a blank sample as appropnate (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 picoCune, Y=
the fractional radiochemical yield, when applicable, 1
A. =
the radioactive decay constant for the particular radionuclide (sec"), and at =
the elapsed time between the midpoint of sample collection and the time of countirg (sec).
Typicti values of E, V, Y, and At should be used in the calculation.
i 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 rnessurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
i l
Occmonally, background fluctuations, unavoidable small sample sizes. the presence of interfenng nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contnbuting fadors shall be identified and described in the Annual Radiological Environmental
)
Oper: ting Report pursuant to Technical Specification 5 6.2.
1
)
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BYRON Revision 1.6 January 1999O 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.2 Land Use Census 12.5.2.B The Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors (Refer to Note 1, Page 12-68) of the nearest milk animal, the nearest residence (Refer to Note 2, Page 12-68), and a enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.
APPLICABILITY:
At all times.
ACTIONS NOTES
- 1. TLCO 3.0.c is not applicable.
- 2. TLCO 3.0.d is not applicable.
I CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated dose or dose A.1 identify the new location (s) in the 12 months commitment greater than the next Annual Radiological value currently calculated in Environmental Operating Report 12.4.3.A.1 pursuant to Technical Specification 5.6.2.
(continued) 9 12-66 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Identification of a location B.1 Add the new location (s) to the 30 days that yields a calculated dose Radiological Environmental or dose commitment (via the Monitoring Program (REMP) given same exposure pathway) in the OFFSITE DOSE 20% greater than at a CALCULATION MANUAL location from which samples (ODCM) (Refer to Note 3, Page are currently being obtained, 12-68).
in accordance with 12.5.1.A.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
- 12. 5.2.B The Land Use Census (Refer to Note 4, Page 12-68) shall 12 months be conducted during the growing season (01 JUN - 01 OCT).
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BYRON Revision 1.6 January 1999 Note 1:
This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sectors will be over water.
Note 2:
The nearest industnal facility shall also be documented if closer than the nearest residence.
Note 3:
The sampling location (s), excluding the control station 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 Technical Specification 5.5.1.c, submit in the next Annual Radiolog: cal 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.
Note 4:
The Land Use Census shall use information that will provide the best results, such as by a door-to-door survey, aenal survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
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O 12-68 (p:\\radprot\\odem\\by12R1-6. doc)
i BYRON Revision 1.6 January 1999 l
12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.3 Interlaboratory Companson Program 12.5.3. A Analyses shall be performed on radioactive materials, supplied as part of an interlaboratory Comparison Program that corresponds to samples required by Table 12.5-1.
APPLICABILITY:
At all times.
ACTIONS NOTES 1.
TLCO 3.0.c is not applicable.
2.
TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Analyses NOT being A.1 Report the corrective actions to 12 months performed per Table 12.5-1.
preclude recurrence in the Annual 1
Radiological Operating Report to the Commission pursuant to Technical Specification 5.6.2.
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12-69 (p:\\radprot\\odemby12R1-6. doc)
BYRON Revision 1.6 January 1999O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.5.3.B Summarize the results obtained as part of the 12 months Intertaboratory Companson Program in the Annual l
Radiological Environmental Operating Report to the Commission pursuant to Technical Specification 5.6.2.
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12-70 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radioloaical Environmental Operatino Reoort' Routine Annual Radiological Environmental Opewting Report covering the operation of the Unit (s) during the previous calendar year shall be subrniued prior to May 15 of each year.
l The Annual Radiological Environmental Operatira Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities forthe report period, including a comparison with operat.onal controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The Annual Radiological Environmental Operating Report shall include the results of all radiological enviroamental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Chapter 11 of 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 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; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.
'A single submittal may be made for a multiple unit station.-
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12-71 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 199 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.1 Annual Radioloaical Environmental Operatina Report (Cont'd)
The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the 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, 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.
The Annual Radiological Environmental Operating Report shall also include 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 report shall also inciude an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190,
" Environmental Radiation Protection Standards for Nuclear Power Operation."
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12-72 (p:\\radprot\\odem\\by12R1-6. doc)
1 BYRON Revision 1.6 January 1999 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 May 1 of the following year.
The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,Measunng 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.
For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).
The Annual Radioactive Effluent Release Reports shallinclude a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in 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 Section 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 ITS 5.5.12.
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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.
O 12-73 (p:\\radprot\\odem\\by12R1-6. doc)
BYRON Revision 1.6 January 1999O 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.3 Offsite Dose Calculation Manual (ODCM) 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:
a.
Shall be documented and records of reviews performed shall be retained as required by UFSAR Chapter 17. This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s); and 2.
A determination that the change will maintain the level of radioactive affluent control required by 10 CFR Part 20,40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the Independent Technical Review and PORC and the approval of the Plant Manager on the date specified by the independent Technical Review and PORC.
c.
Shall be submitted to the Commission in the form of the complete, legible copy of the entire ODCM, or updated pages if the Commission retains a controlled copy. If an entire copy of the ODCM is submitted, it shall be submitted 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 indicate the date (e.g.,
month / year) the change was implemented.
O 12-74 (p:\\radprot\\odcm\\by12R1-6. doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.4 Maior Chances to Liauid and Gaseous Radwaste Treatment Systems *"
Licensee-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 independent Technical Review and PORC. The discussion of each change shall contain:
1)
A summary of the evaluation that led to the determination that the change could 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 desenption 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 License application and amendments thereto; 5)
An evaluation of the change, which shows the expected maximum exposures to a D
MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto; 6)
A companson 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 Independent Technical Review and PORC.
b.
Shall become effective upon review and acceptance by the Independent Technical Review l
and PORC.
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- " Licensees may choose to submit the information called for in this standard as part of the annual FSAR update.
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