ML20063F901
| ML20063F901 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/31/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-940131-03, NUDOCS 9402150223 | |
| Download: ML20063F901 (100) | |
Text
h --
DRESDEN Revision'1.O.
January 1994
'DRESDEN ANNEX INDEX-i., '_ f~ :.
M.
REVISION CHAPTER 10 h
.10-1 1.0 10-ii.
1.0 10-111 1.0 10-iv 1.0
.10-v 1.0 10-1 1.0 10-2 1.0' 10-3 1.0 10 1.0 10-5 1.0 10-6 1.0 10-7 1.0 10-8 1.0 10-9 1.0 10-10 1.0 l
10-11 1.0 10-12 1.0 10-13 1.0 10-14 1.0 10-15 1.0 i
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9402150223 940131 PDR ADOCK 05000237
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DRESDEN Revision 1.0 2
January 1994 i
CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING I
TABLE OF CONTENTS PAGE l
4 10.1 AIRBORNE RELEASES
)
1 1
===1.
System Description===
1 1.
Condenser Offgas Treatment System.
1 2.
Ventilation Exhaust Treatment System 1
i
~
2.
Radiation Monitors 2
1.
Unit 1 Chimney Monitor 2.
Units 2/3 Chimney Monitor 2
2 3.
Reactor Building Vent Stack Effluent Monitors 2
4.
Reactor Building Ventilation Monitors...
3 5.
Condenser Air Ejector Monitors 3
6.
Isolation Condenser Vent Monitor 3
3.
Alarm and Trip Setpoints 3
1.
Setpoint Calculations 3
1.
Reactor Building Vent Monitors 3
2.
Condenser Air Ejector Monitors 3
3.
Units 2/3 Plant Chimney Radiation Monitor 4.
2.
Release Limits 4
3.
Release Mixture 5
i 4.
Conversion Factors
-5 5.
HVAC Flow Rates....
6 1
4.
Allocation of Effluents from Common Release Points 6
5.
Dose Projections 6
O 10-11
h i
DRESDEN-Revision 1.0 January 1994
<~S CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)
PAGE 10.2 LIQUID RELEASE
.{...........
6 1.
Rystem Description......
6 1.
Unit 1 St'orage Tanks 6
2.
Units 2/3 Waste Sample Tanks 7
3.
Units 2/3' Floor Drain Sample Tanks 7
4.
Units 2/3, Waste Surge Tank 7
2.
Radiation Monitors 7
1.
Liquid Radwaste Effluent Monitor-7 2.
Units 2/3 Service Water Effluent Monitors 7
3.
Chemical Cleaning Facility Service Water Effluent Monitor 7
3.
Alarm and Trip setpoints 8
1.
Setpoint Calculations..
8 1.
Liquid Radwaste Effluent. Monitor 8
2.
Units 2/3 Service Water Effluent Monitor 8
3.
Chemical Cleaning Facility Service Water Effluent Monitor 8
2.
Discharge Flow Rates 9
1.
Release Tank Discharge Flow Rate 9-3.
Release Limits 9
4.
Release Mixture 9
5.
Conversion Factors 10 6.
Liquid Dilution Flow Rates 10 4.
Allocation of Effluents from Common Release Points 10 5.
Projected Doses for Releases 10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM.......
10 b
10-iii
DRESDEN Revision 1.0 January 1994 1
CHAPTER 10 LIST OF TABLES
[
NTWEER PAGE 10-1 Data for Determination of Dilution FlowRates(
....... 10-11 1
i b
i O
P I
I l
e O.
10-iv
- u DRESDEN.
Revision 1.O L-i <
January 1994:
CHAPTER 10-
- .y LIST OF-. FIGURES f
' i NUMBER pAgp j
~10-1
. Simplified Gaseous Radwaste_and Gaseous Effluent Flow Diagram 10-12:
1 10-2 SimplifiedhaseousRadwasteandGaseous
. 10 Effluent Flow Diagram 10-3 simplified Liquid Radwaste Processing and~
'i Liquid Efflubnt Flow; Diagram.
10-14 10-4 Simplified solid Radwaste Processing Diagram-10--15
)
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10-v
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DRESDEN Revision 1.0 January 1994 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRLORNE RELEASES 10.1.1
System Description
)
A simplified gaseous radwaste and gaseous effluent flow diagram is provided for Dresden Unit 1 in Figure 10-1 and for Dresden Units'2 and 3 in Figure 10-2.
Dresden 1 is no longer operational, but monitoring of potentially radioactive releases from'the plant chimney continues.
Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A.
The principal release points for potentially radioactive airborne effluents and their classifica*. ions are as f ollows:
For Dresden 1, the plant chimney (a stack release point).
For Dresden 2/3:
-- The ventilation chimney (a stack release point).
-- The reactor building ventilation stack (a vent release point).
lf 10.1.1.1 Condenser offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment.
The daughter products are retained by charcoal and HEPA filters.
The system is described in Section 9.2 of the Dresden UFSAR.
10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through' charcoal absorbers and/or HEPA filters prior to release to the environment.
Such a system is not considered to have any
'effect on noble gas effluents.
The ventilation exhaust treatment systems are shown in Figures 10-1 and 10-2.
Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components O
10-1
DRESDEN Revision:1.0-January 1994 10.1.2 Radiation Monitors n.
I i
10'.l.2.1 Unit 1 Chimney Monitor
%/
v Monitor 1-SPING-4A continuously monitors the final effluent from the Unit 1 chimney.
The monitor.has isokinetic sampling, gaseous grab sampling, and particulate and' iodine sampling capability.
Tritium samples are obtained using a portable sampling system.
A tap is available for obtaining a sample from the isokinetic probe.
In normal operation all three noble gas channels (low, mid-range, high) are on line and active.
No automatic isolation or control functions are performed by this monitor.
10.1.2.2 Units 2/3 Chimney Monitor Monitor 2/3-SPING-4C continuously monitors the final effluent from the Units 2/3 chimney.
The monitor has isokinetic sampling, gaseous grab sampling, particulate and iodine sampling, and postaccident sampling capability.
Tritium samples are obtained using a portable sampling system.
A tap is available for obtaining a sample from the isokinetic probe, O
k, In normal operation the two lower noble gas channels (low and s
mid-range) are on line and active.
The high range noble gas channel flow is bypassed and this channel is'in. standby.
On-a high alarm the low and mid-range noble gas channels are bypassed and only the high range noble gas. channel remains active.
No automatic isolation or control functions are performed by this monitor.
Pertinent information on this monitor is provided in.the Dresden 2/3 UFSAR Section.7.6.2.4.
In addition to the primary monitor described above, there is a backup-system consisting of two additional detectors and sample taps in series in the primary sample stream.
10.1.2.3 Reactor Building Vent Stack Effluent Monitors Monitor 2/3 SPING-4A continuously monitors the final effluent from the reactor building vent stack.
\\
The vent stack monitor has. isokinetic sampling, gaseous sampling, and iodine and particulate sampling capability.
Tritium samples are obtained using a portable sampling system.
A tap is available for obtaining a sample from the isokinetic probe.
s I
10-2 a
DRESDEN Revision
.1.
0 January 1994
,All channels are continuously on line and active.
No automatic isolation or control functions are performed by h
this monitor.
10.1.2.4 Reactor Building Ventilation Monitors Monitors 2 (3)-1735A/B continuously monitor the effluent from the Unit 2 ( 3, ) reactor building ventilation.
On high alarm, the monitord automatically initiate closure of valves A02 ( 3 ) A-5741', A02(3)B-5741, A02(3)A-5742, and A02 (3 )B-5742 thus isolating the Unit 2(3) reactor building ventilation, and initiate startup of the Unit 2/3 standby gas treatment system.
Pertinent information on these monitors is provided in Dresden UFSAR Section 7.6.2.5.
10.1.2.5 condenser Air Ejector Monitors Monitors 2 ( 3 )-1733A/B and 2 (3 )-173 8B continuously monitor gross gamma activity downstream of the Unit 2 and 3 steam jet air ejector and prior to release to the main chimney.
On high alarm monitors 2(3)-1733A/B automatically activate an interval timer which in turn initiates closure of air operated valve A02(3)-5406, thus terminating the release.
Pertinent information on these monitors is found in Dresden UFSAR Section 7.6.2.3.
10.1.2.6 Isolation Condenser Vent Monitor Monitors 2(3)-1736 A/B continuously monitor radioactivity in the effluent from the isolation condenser vent.
No control device is initiated by this monitor.
Pertinent information on this monitor is provided in Dresden UFSAR Section 7.6.2.10 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Monitors The alarm setpoint for the reactor building vent monitor is established at 4 mr/hr.
10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at s 100 pCi/Sec per MWt (A 2.5E5pci/see) and the high alarm is established at s 50pCi/sec per MWt (41.25E5pci/sec).
O 10-3
- )
1 DRESDEN Revision-1.0-l January 1994 10.1.3.1.3 Units 2/3 Plant' Chimney Radiation Monitor-l The.setpoint:is established at a count rate corresponding to 105,000 pC1/sec.,
10.1.3.2 Release Limits i
Alarm and trip setpoints of gaseous effluent monitors are
.r established to ensure that the release rate limits of RETS I
are not exceeded.
The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate, Qu.
1 (1.11) [ ( fil O sE + OrvK] ) < 500 mrem /yr (10-1) t
[ ( (E"f; I (X/ 0), 0,, exp (- A,R/3 600 u,)
+ (X/ 0),0,,exp-A,R/3 600u ) ]
I
~
y
+ (1.11 ) ( f, ) ! O,,S, + OryV, ) }
[
< 3000mremlyr a
The summations are over noble gas radionuclides i.
f Fractional Radionuclide Composition i
The release rate of noble gas radionuclide i divided by I
g the total release rate of all noble gas' radionuclides.
Qe, Total allowed Release Rate, Stack
[pCi/sec)
Release The total allowed release rate of all noble gas radionuclides released as stack releases.
On Total Allowed Release Rate, (pC1/sec)
Vent Release 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 renaining 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 end the l-RETS restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.l.3.1 of Appendix A).
Equation 10-2 is based on Equation r
l.i A-9 of Appendix A and the RETS restriction on skin dose rate 1
(3000 mrem /yr) due to noble gases released *n gaseous effluents (see Section A.1.3.2 of Appendix A).
Calibration methods and surveillance frequency for the l
monitors will be conducted as specified in the RETS.
\\~-
10-4 l
l
DRESDEN Revision 1.0 January 1994 10.1.3.3 Release Mixture In the determination of alarm and trip setpoints the radioactivity mixture in the exhaust air is assumed to have the following compositions.
Reactor building vent effluent monitors.
The mixture used for the GE monitors is taken from a representhtive isotopic analysis of the vent stack noble gas relea'ed during the calendar quarter in which the s
monitor is recalibrated.
The
- mixture" used for the SPING-4 is assumed to be a single pseudo-noble gas radionuclide.
Condenser air ejector monitor.
The mixture used for this monitor is taken from a representative isotopic analysis of noble gases collected at the recombiner outlet during the calendar quarter in which the monitor is recalibrated.
Units 2/3 plant chimney monitors.
The mixture used for the GE monitors is taken from the most recent isotopic analysis of noble gases collected from the chimney monitor during the calendar quarter in which the monitor is recalibrated.
The " mixture" used for the SPING-4 is assumed to be a single pseudo-noble gas radionuclide.
10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows.
Reactor building vent effluent monitor.
For the GE monitors, the isotopic analysis in Section 10.1.3.3 and the monitor reading (in mR/hr) at the time of the analysis are used to establish the conversion factor in mR/hr per pCi/cc.
For the SPING-4 the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.
Condenser air ejector monitor.
The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading (in mR/hr) at the time of the analysis are used to ectablish the conversion factor in rR/hr per pC1/cc.
Units 2/3 plant chimney monitors For the GE monitors, the isotopic analysis in Section 10.1.3.3 and flow and monitor reading (in CPS) at the time of the analysis are used to establish the conversion factor in CPS per pCi/cc.
For the SPING-4 the conversion I
10-5
w
_m
_m m..
g.
m.
DRESDEN Revision 1.0
. January 1994-j factor.is based on the 0.8 MeV gamma of'the pseudo-noble.
j 7
gas radionuclide.
Ls /
s 10.1. 3. S ' HVAC Flow Rates a
)[
- The HVAC exhaust. flow rates are obtained from either the- _
1 Units 2/3< process computers or the SPING-4 control station.
If the actual flows are not available,Lthe default. values are:
i-I Units 2/3 Chimney Air Flow 1.00E10 cc/ min-Units 2/3 Combined Reactor Vent 6.23E9 cc/ min Unit 1 Chimney' Air Flow 1.76E9 cc/ min t
10.1.4 Allocation of Effluents from Common Release Points Radioactive gases, particulates, and. iodines released from.
l the Unit 1 chinney originate from Unit-1 only.
However,.
radioactive gaseous effluents released from Units 2/3 are
[
comprised of contributions from both units.
Estimates of
{
noble gas contributions from Units 2 and 3 are allocated considering appropriate operating conditions and measured i
SJAE off-gas activities.
Allocation of radiciodine and radioactive particulate releases to Units 2 or 3 specifically-is not as-practical and is' influenced' greatly by in-plant leakage.
Under normal operating conditions, allocation is made;using reactor coolant iodine' activities.
- l During unit shutdowns or periods of~known major in-plant fi leakage, the apportionment is adjusted accordingly..The f
allocation of ef fluents is estinated on a monthly basis.
{
10.1.5 Dose-Projections I
E Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS.
10.2 LIQUID. RELEASES 1
10.2.1
System Description
i I
A simplified liquid radwaste and liquid effluent flow diagram is provided in Figure 10-3.
The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by.
j collecting the liquids, providing for retention or holdup,.
and'providing for' treatment by evaporator,.demineralizer and.
r filter for'the purpose of reducing the total radioactivity prior to reuse or release to the environment.
The system is' described in Section 9.3 of'the Dresden Updated Final Safety
(
Analysis Report.
l 10.2.1.1 Unit 1 Storage Tanks J"
Liquid radioactive. effluents are not released from Unit 1:
Storage tanks directly to the environment but are made through the Units'2/3 radwaste system.
i 10-6
DRESDEN Revision 1.0 January 1994 10.2.1.2 Units 2/3 Waste Sample Tanks There are three waste sample tanks (33,000 gallons each) which receive water from the liquid waste treatment system.
These tanks are transferred to the waste surge tank for discharge to the Illinois River via the discharge canal.
10.2.1.3 Units 2/3 Floor Drain Sample Tanks There are two! floor drain sample tanks (22,000 gallons each)
I which receive liquid waste from the floor drain treatment system.
These tanks are transferred to the waste surge tank for discharge'to the Illinois River via the discharge canal.
10.2.1.4 Units 2/3 Waste Surge Tank The waste surge tank receives processed water from the waste sample tanks and floor drain sample tanks.
This tank discharges to the Illinois River via the discharge canal.
10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 2/3-1721 is used to monitor all releases from the waste surge tank.
On high alarm, a grab sample of the effluent is automatically taken from the discharge side of the sample chamber after a 0 to 60 second delay determined by a locally mounted timer.
The release is terminated manually by initiating closure of the low flow (AO 2001-170) or high flow (AO-2001-195) discharge line valves.
Pertinent information on the monitor and associated control devices is provided in Dresden UFSAR Section 7.6.2.9.
10.2.2.2 Units 2/3 Service Water Effluent Monitors Monitors 2(3)-1724 continuously monitor the service water effluent.
On high alarm a grab sample is automatically taken.
Pertinent information on these monitors is provided in Dresden UFSAR Table Section 9.6.2.8.
10.2.2.3 Chemical Cleaning Facility Service Water Effluent Monitor Monitor WASMC-06641-0700 continuously monitors service water effluent from the chemical cleaning facility.
On high alarm the release is terminated by manually initiating closure of isolation valve AOS-06699-7904.
No control device is initiated by this monitor.
O l
l l
10-7
\\
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- ~-
r s
-DRESDEN
'Revisioni1.0 i
January 1994 Y
'10.2.3 Alarm and Trip Setpoints-O o(,/
10.2.3.1 Setpoint Calculations' Alarm and trip.setpoints of liquid effluent monitors at the principal release points are established to ensure that the
-l limits of 10CFR20 are not exceeded in the unrestricted area.
t 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found.by solving equation 10-3 for the total isotopic activity.
i 5
CT/{ C[/DNC) x ((40,000 + Flo) /Fl.,)
PsKx (10-3)
P Release Setpoint
[ cpm]
\\
C[
Concentration of radionuclide i in
[pci/ml]
the release tank l
i Fi, Maximum Release Tank Discharge Flow Rate
[gpm]
The flow rate from the radwaste discharge tank.
The maximum pump discharge rate of 250 gpm is used for calculating the setpoint.
1 k
K Calibration constant
[ cpm /pci/ml]
1
- DNC, Derived Water Concentration of Radionuclide i
[uCi/ml]
The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402.
When technical specifications allow, ten (10) times the DWC may be used.
3 40,000 Dilution Flow
[gpm)
Releases are not permitted if the calculated j
dilution flow is less than 40,000 gpm.
Once it has b'een determined that the dilution flow is 1 40,000 gpm, this value (40,000 gpm) is used even if the actual dilution flow is much greater..
i 10.2.3.1.2 Units 2/3 Service Water Effluent Monitor The monitor setpoint is established;at two times the background radiation value.
1012.3.1.3 Chemical Cleaning Facility Service Water Effluent Monitor
(-
The monitor setpoint is established at two times the background radiation value.
10-8
DRESDEN
' Revision 1.0 January 1994 1
10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained.
The results of the analysis of the sample det. ermine the discharge rate of each batch as follows:
i F,L, = 0.1)( 4 0, 0 0 0 /{ ( C, / DNC, ) )
(10-4)
The summation is over radionuclides i.
0.1 Reduction factor for conservatism.
F,i, Maximum Permitted Discharge Flow Rate
[gpm)
The maximum permitted flow rate from the radwaste discharge tank.
Releases are not permitted if the calculated discharge rate, FL,,
is less than 250 gpm.
[gpm) 40,000 Dilution Flow
[gpm)
C, Concentration of Radionuclide i in
[pCi/mL) h the 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
[pC1/ml) 3 of Radionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Coluno 2 to 10CFR20.1001-2402.
When technical specifications allow, ten (10) times the DWC may be used.
3 10.2.3.3 Release Limits Release limits are determined from 10CFR20.
Calculated maximum permissible discharge rates are divided by 10 to ensure that applicable derived water concentrations (DWC)
{
are not exceeded.
10.2.3.4 Release Mixture For the liquid radwaste effluent monitor, the release l
mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis.
10-9
?
F DRESDEN'-
Revision 1.0^
N January:1994 I
For<all other liquid effluent-monitors, no release mixture:
- I is used because.the setpoint_is established at "two timesL 1
,jf background.<"
10.2.3.5 Conversion Factors The'readoutifor'the' liquid radwaste. effluent monitor is in CPM.
The calibration constant is based on the detector sensitivity to Co-60.
. i c
The readoutd for the Units 2/3 cervice water effluent monitors are in pCi/mi.
The calibration constants are' based on the detec' tor sensitivity to Co-60.
]
10.2.3.6 Liquid Dilution Flow Rates
~.
The dilution flow is determined using the information in _.
l Table 10-1.
However, by procedure the maximum dilution flow used for determining liquid radwaste release rates and setpoints is 40,000 gpm.
Thus, even if the dilution flow exceeds 40,000 gpm, for conservatism, the calculations are
based on 40,000 gpm.
i 10.2.4 Allocation of Effluents from Common Release Points l
Radioactive liquid effluents released from the release tanks are comprised of contributions from all three units. sunder normal 1 operating conditions, it is. difficult to apportion-the radioactivity between the units.
Consequently, 1
'~'
allocation is normally made evenly between units 2 and 3.
10.2.5 Projected Doses for Releases-Dose's due to liquid effluents are calculated in'accordance-with the RETS.
[
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 fromJ11guid systemstis ensured.
I Figure 10-4 is a simpilfied diagram of solid radwaste processing.
- l
]
i e
10-10 i
i
DRESDEN Revision 1.0 January 1994 TABLE 10-1 Data for. Determination of Dilution Flow Rates Closed Cycle Dilution Flow Determination (Gate 4451 cut of water, Gate 4452 full closed) 6" 50,000 15" 100,000 21" 150,000 30" 200,000' 36" 250,000 40" 300,000 0.0,W 350,000 Open Cycle Dilution Flow Determination (Gate 4450 full open, Gates 4451 and 4452 full closed) 6" 168,000 12" 335,000 19" 404,000*
26" 580,000*
35*
740,000*
0.0.W 900,000*
- These dilution flows have 100,000 gpm subtracted from them for conservatism, Lake Bypassed Dilution Flow (Gates 4450 and 4452 full open, Gate 4451 Full Closed)
De-Icing Valves De-Icing Valves Cire. Water Closed Open Pump Running Flow in gpm Flow in gpm 2
380,000 300,000 3
480,000 380,000 4
760,000 600,000 5
860,000 780,000 6
960,000 890,000 a
e 10-11 I
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194,200 CFM _
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.: { - DRESDEN Revision 1.0 January 1994 ..,-) DRESDEN ANNEX INDEX-RAGE REVISION t CHAPTER 11 11-i 1.0 l 11-11 1.0 i 11-111 1.0 3 11-iv 1.0 11-1 1.0 11-2 1.0 11-3 1.0 i 11-4 1.0 11-5 1.0 11-6 1.0 11 *7 1.0 l 11-8 10 l 11-9 1.0 -: i 11-10 1.0 11-11 1.0 11-12 1.0 5 11-13 1.0 11-14 1.0 i f r . j- - i i ( 11-1 4 .y.... y 7
s DRESDEN Revision 1.0 January 1994 CIIAPTER 11 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM TABLE OF CONTENTS 22EE 11 RADIOLOGICAL ENVIRO 11 MENTAL MOIIITORING PROGRAM 11-1 O O 11-11 vc-re-...
.t / ~'.'; ~ January 1994. DRESDEN Revision 1.0 -e. CHAPTER 11 LIST OF TABLES l NUMPER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 -l 11-2 Reporting Levels for Radioactivity Concentrat' ions in Environmental Samples 11-B 11-3 Detection Capabilities for Environmental Sample Analysis 11 ' .q 11-111 1 .. __________.____i__.____.__
o DRESDEN Revision 1.0 January 1994 CHAPTER 11 LIST OF FIGURES NUMPER TITLE PAGE 11-1 Fixed Air Sampling and TLD Sites and outer; Ring TLD Locations 11-12 11-2 Inner Rin'g TLD Locations and Near 11-13 Station Water Sample Locations 11-3 Milk Sample Locations and More Distant Water Sample Locations 11-14 O~ r l l G; 11-iv l f
er e i k-DRESDEN' Revision 1.0' January 1994 ? ~ i / [- CHAPTER 11-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The parameters for the' radiological environmental monitoring program'to t be performed in the environs around Dresden Nuclear Power Station are i given in Table 11-1. l 1 Figure 11-1 shows the Ib fixed air sampling sites and TLD locations; also shown are the outer ring TLD locations. Figure 11-2 shows near station water sample lo'ations and the inner ring TLD locations. The l c TLDs are coded as follows: l XYY-N j X= 1, means inner ring; { X=2, means. outer ring; and
- i YY-N is an identification code.
Figure 11-3 shows the milk sample locations and more distant water-sample locations. I The reporting levels for radioactivity concentrations in environmental 1! samples are given in Table 11-2. The practical lower limits of l detection for this program are given in Table 11-3. l l l ? l i t ~ l i 'J t. 11-1 s .a
DRESDEN Revision 1. O January 1994 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samule Samolina or Monitoriner Locations
- Collection Frecuency of Analvris b
1. Airborne a. Onsite and Near Field Continuous sampler operation Radiciodine Canister: with particulate filter Radiciodine and D-01 Onsite Station 1, 0.6 mi WNW exchange weekly and radio-I-131 analysis bi-Particulates (1.0 km P) iodine canister exchange weekly" D-02 Onsite Station 2, 0.3 mi NE biweekly * (0.5 km C) D-03 Onsite Station 3, 0.4 mi S Particulate Samolon (0.6 km J) D-04 Collins Road, 0.9 mi W Gross beta analysis (1.4 km N) following filter D-05 Bennitt Farm, 0.9 mi NE change * (1.4 km D) D-06 Will County Road, 1.4 mi SE (2.2 km G) Samnlino Tra,in: Test and maintenance weekly b b. Far Field Continuous sampler operation Radiciodine Canister: with particulate filter D-07 Clay Products, 2.0 mi S exchange weekly and radio-I-131 when analyses (3.2 km J) iodine canister exchange are made* D-08 Prairie Parks, 4.0 mi SW biweekly * -(6.4 km L) 11-2 ~
- s -
D*s-iDEN Revisic2 20~ r ' January 1994 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samnle Samulinc or Monitorina Locat iens' Collection Frecuen&/ of Analysis 1. Airborne.(Cont'd) D-09 Cdal City, 7.5 mi S (12.0 km J) Particulate Samoler: D-10 Goose Lake Village, 3.8 mi SSW (6.1 km K) Gross beta when analy-D-11 Morris, 8.0 mi WSW (12.9 km M) ses are made** D-12 Lisbon, 10.0 mi IM (16.1 km Q) D-13 Minooka, 4.5 mi N (7.2 km A) Samnlina Train: D-14 Channahon, 3.5 mi NE (5.6 km C) D-15 Joliet, 12.5 mi ENE (20.1 km D) Test and maintenance D-16 Elwood,. 8.0 mi E (12.9 km E) weekly D-17 Wilmington, 8.0 mi SE (12.9 km G) 2. Direct Radiation a. At Air Samulinc Sites Quarterly Gamma dose quarterly Same locations as fixed air sampling locations in Item 1. b. Inner Rina' D-101-1, 1.O mi N (1.6 km A) D-101-2, 1.0 mi N (1.6 km A) D-102-1, 1.3 mi NNE (2.1 km B) D-102-2, 1.3 mi NNE (2.1 km B) D-103-1, 1.2 mi NE (1.9 km C) D-103-2,- 1.2 mi NE (1.9 km C) D-104-1, 1.5 mi ENE (2.4 km D) l 'D-104-2, 1.5 mi ENE (2.4 km D) l D-105-1, 1.4 mi E (2.3 km E) D-105-2, 1.4 mi E (2.3 km E) D-106-1, 0.9 mi ESE (1.4 km F) D-106-2, 0.9 mi ESE (1.4 km F) D-107-l', 1.3 mi SE (2.'1 km G) D-107-2, 1.3 mi SE (2.1 km G) D-108-1, 1.9 mi SSE _(3.1 km H) D-10 6-2,. 1.9 mi SSE (3.1 km H) 11-3 l
DRESDEN Revision 1. 0 January 1994 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Sarmlinc or Monitorino Locations
- Collection Frecuency of Analysis 2.
Direct Radiation (Cont'd) D-109-1, 0.8 mi S (1.3 km J) D-109-2, 0.8 mi S (1.3 km J) D-110-1 0.6 mi SSW (1.0 km K) D-110-2, 0.6 mi SSW (1.0 km K) D-110-3 0.5 mi SSW (0.81 km K) D-110-4, 0.5 mi SSW (0.81 km K) D-111-1, 0.6 mi SW (0.97 km L) D-111-2, 0.6 mi SW (0.97 km L) D-112a-1, 0.8 mi WSW (1.3 km M) D-112a-2, 0.8 mi WSW (1.3 km M) D-112b-1, 0.9 mi WSW (1.4 km M) D-112b-2, 0.9 mi WSW (1.4 km M) D-113-1, 0.9 mi W (1.4 km N) D-113-2, 0.9 mi W (1.4 km N) D-114-1, 1.O mi WNW (1.6 km P) D-114-2, 1.0 mi WNW (1.6 km P) D-115-1, 0.8 mi NW (1.3 km-Q) D-115-2,
- 0. 8 mi NW (1.3 km Q)
D-116-1, 1.0 mi NNW (1.6 km R) D-116-2, 1.0 mi NNW (1.6 km R) b c. Outer Rina D-201-1, 4.5 mi N (7.2 km A) D-201-2, 4.5 mi N (7.2 km A) D-202-1, 5.0 mi NNE (8.0 km B) D-202-2, 5.0 mi NNE (8.0 km B) D-203-1, 4.5'mi NE (7.2 km A) D-203-2, 4.5 mi NE (7.2 km A) D-204-1, 5.0 mi ENE (8.0 km D) D-204-2, 5.0 mi ENE (8.0 km D) D-205-1, 4.2 mi E. (6.8 km E) D-205-2,- 4.2 mi E (6.8 km E) 11-4 O O O g 4 f=
q:. .j \\ J'. D 6 EN Revisi 1,-l.Oc January 1994 Table 11-1-(Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and' Frequency and/or Samnie Samnlina or Monitorina Locations
- Collection Frecuency of Analysis 2.
E rect Radiation (Cont'd) D-206-1, 3.5 mi ESE (5.6 km F) D-206-2, 3.5 mi ESE (5.6 km F) D-207-1, 4.5 mi SE (7.2 km G) D-207-2, 4.5 mi SE (7.2 km G) D-208-1,' 5.0 mi SSE (8.0 km H) D-208-2, 5.0 mi SSE (8.0 km H) D-209-1, 5.0 mi S (8.0 km J) D-209-2, 5.0 mi S (8.0 km J) D-210-1, 4.8 mi SSW (7.7 km K) D-210-2, 4.8 mi SSW (7.7 km-K) D-211-1, 5.O mi SW (8.O km L) D-211-2, 5.0 mi'SW (8.0 km L) D-212-1, 4.8 mi WSW (7.7 km M) D-212-2, 4.8 mi WSW (7.7 km M) D-212-3, 6.0 mi WSW (9.7 km M) D-212-4, 6.0 mi WSW (9.7 km M) D-213-1, 4.5 mi W (7.2 km N)- D-213-2, 4.5 mi W (7.2 km N) D-214-1,
- 4. 5 mi h7M.
(7.2 km P) D-214-2,
- 4. 5' mi WIM.(7.2 km P)
D-215-1, 5.1 mi IM (8.2 km Q) D-215-2,- 5.1 mi IM (8.2 km Q) t D-216-1, 4.8 mi m M (7.7 km R) D-216-2,
- 4. 8 mi NIM (7.7 km R)-
3. Waterborne- a. Surface D-21, Illinois River at EJ&E RR Weekly Gamma isotcpic on . Bridge, 1 mi W-(1.6 km N) monthly composite D-22 Illinois River at Morris Water Works, 8 mi W (12.9 km N) b. Lake Water D-28, Dresden Pool at Illinois River, Weekly Gantna isotopic and 0.5 mi W (0.8 km N)- gross beta analysis D-34A, Cooling Lake, Dresden Road. Crossing, 2.6 mi S (4.2 km J) 'D-34B, Cooling Lake,--County Line Crossing,.3.O mi SSE (4.8 km H) 11 - u 2- ~. -. ^
DRESDEN Revision 1. 0 January 1994' Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency W /or Samnle Samnlina or Monitorina Locations
- collection Frecuency of Analysis 3.
Hfit erborne, (Cont'd) c. Ground / D-23, Thorsen Well, 0.7 mi S Quarterly Gross beta, gross ~Well Water (1.1'km J) alpha and tritium D-35, Dresden Lock & Dam, 0.5 mi W (0.8 km N) d. Coolina Water D-18, Inlet, Unit 1, at Station Weekly ,_. Gross beta analys'is Samnle D-19, Discharge, Unit 1, at Station weekly D-20, Discharge, Unit 2/3, at Station e. Shoreline sediments D-27, Dresden Lock & Dam, 0.5 mi W Annually Gamma isotcpic (0.8 km N) annually 4. IncestionS a. Milk D-25, Vince Biros Farm, 11.5 mi SSW Weekly: May to October I-131 analysis on each (18.5 km K) Monthly: November to sample D-26, Halpin's Dairy, 6.1 mi S April (9.8 km J) b. Fish D-28, Dresden Pool of Illinois Semiannually Gamma isotopic analy-River, 0.5 mi W (0.8 km N) sis on edible portions of each sample. 5. Land Use census a. Milch Animals 1. Site boundary to 2 miles Annually during Enumeration by a grazing season door-to-docr or equivalent counting technique. 2. 2 to 5 miles Annually during Enumeration by using grazing season referenced information from county agricultural agencies or other reliable sources. 11-6 O O' O
' ~; D6.4 DEN RevisionMO, January 1994 - Table 11-1 (Cont'd) Radiological Environmental Monitoring Program . Exposure Pathway - Sampling or Type and Frequency and/or Samnle Samolinc or Monitorina Locations' collection Frecuency - of Analysis
- 5. L Land the census '
3. At dairies listed in Item 4.a. Annually during grazing season Inquire as to feeding (Cont'd) practices: a. Pasture only. ,,_ b. Feed.and chop only. c. Pasture and feed; if both, ask farmer to esti-mate fraction of food from pasture: <25%, 25-50%, 5 0 - 7 5.%, or >75%. b. Nearest Resident In all 16 sectors up to 5 miles. Annually See Table D-16 for definitions of sector codes used with kilometer distances. See Figure 11-1, Fixed Air' Sampling and TLD Sites and Outer Ring TLD Locations." b
- - Biweekly means every two weeks.
A gamma isotopic analysis'shall'be performed wherever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the preceding calendar quarter for the sample-location. Far. field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed 'as having its origin ~ in airborne ef fluents released from the _ station, or at the discretion'of the Emergency Preparedness Director. f See. Figure 11-2,." Inner Ring TLD Locations and Near Station Water' Sample Locations." See Figure 11-3,' ." Milk Sample Locations and More. Distant Water Sample Locations." - 8 11-7 mm
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DRESDEN Revision 1 - O January 1994 Table 11-2 Reporting Levels for Radioactivity Concentrations in Environment.al Samples Water Airborne Particulate Fish Milk Food Products 3 Analysis frCi/L) or Cases f rCi/m ) frCi/ka. wet) frCi/L) (rCi/ka. wet) H-3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 20,000 Zn-65 300 20,000 l Zr-Mb-95 400 I i I-131 2 0.9 3 100 l l Cs-134 30 10 1,000 60 2,000 l Cs-137 50 20 1,000 70 2,000 Ba-La-140 200 300 l
- For drinking water samples.
This is 40 CFR Part 141 value. l i 1 I i 11-8 O O O.
-_s i > -,( 't s' (Revisici t'b.' D L CEN January 1994 q s Table 11-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)* i Water-Airborne Particulate Fish Milk-Sediment i Analysis (nCi/L) or Cases f rci /m l (DCi/ko. wet) frCi/L) frC1/ka. drv) b Gross beta 5-0.01 1,000 5 - 2,000 l Ganuna isotopic 20 0.01 200 20 200 ~ I-131 5 0.10 100* 5 4 l Cs-134 10. 100 10 Cs-137 10 100 5 I H-3 200 t t 1 ' J-i k 1. i 11-9 -w'e ,w.--.*---.w.se ,r -ww.-..<we.r-.+**m.inr-r.w.-nm .w w. m e < si-e.ase..-+-sur-.=w=w.=.-se--w ww arv,.= 4...-.-eiswr+, = ..m.1-wwvm e.m ~.--,si.e-- ewemerwwar,w we=r<ww ri-m1.=w-awv<- a....e-. w.-sm.' w.-.re-.*.,.r%:- --~.--m
DRESDEN Revision 1.0 January 1994 Table 11-3 (Cont'd) Detection capabilities for Environmental Sample Analysis Notes: 1. Other radionuclides which are measurable and identifiable l by gamma ray spectrometry, together with the nuclides indicated in Table 11-3, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analy-ses shall not be reported as being present at the LLD level for that nuclide. Footnotes:
- The LLD is the smallest concentration of radicactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observa-tion represents a "real" signal.
For a particular measurement system (which may include radiochemical separation) (4.66). (S ) n LLD = (A) (E) (V) (2.22) (Y) (exp(-AAt)) (t) LLD is the a nriori lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume), S is the square root of the background count or of a blank sample n count; it is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts). E is the.oanting efficiency (as counts per disintegration). A is the number of gamma rays emitted per disintegration for gamma ray l: radionuclide analysis (A = 1.0 for gross alpha and tritium measurements). V is the sample size (in units of mass or volume). I l 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional rad'iochemical yield when applicable (otherwise Y 1.0). = A is the radioactive decay constant for the particular radionuclide L (in units of reciprocal minutes). At is the elapsed time between the midpoint of sample collection and 0.0 for environmental samples the start time of counting. (at = and for gross alpha measurements.) l l 11-10
- e DRESDEN Revision 1.0 January.1994 A Table 11-3 (Cont'd) i ,) Detection Capabilities for Environmental Sample Analysis 'I 11ctes (Cont'd): .i t is.the duration of the count (in units of minutes). i The value of S, used in,the calculation of the LLD for a detection l system shall be based on an actual observed background count or a blank -sample count (as appropriate) rather than on an-unverified i theoretically predicted value. Typical values of E, V, ' Y., t, and At' shall be used in the calculation. For gamma ray radionuclide analyses the ba'ckground counts are determined from the total counts in the channels which are within plus' or minus one FWHM (full width at half maximum) of the gamma ray l. photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall be used in the calculation. The LLD for all measurements is defined as an a triori (before the fact) limit representing the capability of a measurement system and not i as an a nosteriori (after the fact) limit for a particular sample I measurement. i ) 6 Referenced to Cs-137. For thyroid, i d 0.5 pCi/L on samples collected during the pasture season.
- i i
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E TLD Location -m um-NEAR STATION WATER SAMPLE LOCATIONS i 11-13
Revision 1.C January 1994 0 I + u.s. s s 4. Nhl [] Q'Joliet \\%.
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,o o s so uo .? ? orrsas Don eneuunoN nNun = = - - DRESDEN STATION UNITS 1,2, & 3 - FIGURE 114 Sampling Location MILK SAMPLE LOCATIONS AND MORE DISTANTWATER SAMPLE LOCATIONS .11-14
4* y. DRESDEN Revision 1.O January 1994 T l CIIAPTER 12.0 ) SPECIAL NOTE i Until the Unit 2 & 3 Radiological Effluent Technical Specifications-have been approved by the-Nuclear Regulatory Commission, the requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur. l' l 12-i .--_-__:_;-_=________-__________-__--_____________.
k ] DRESDEN Revision 1.0 January 1994 i DRESDEN ANNEX INDEX PAGE REVISIQH PAGE REVISION CHAPTER 12 12 - i 1.0 12 - 46 1.0 12 - ii 1.0 12 - 47 1.0 12 - iii 1.0 12 - 48 1.0 12 - iv 1.0 12 - 49 1.0 12 - v 1.0 12 - 50 1.0 12 -1 1.0 12 - 51 1.0 12 - 2 1.0 12 - 52 1.0 12 - 3 1.0 12 - 53 1.0 12 - 4 1.0 12 - 5 1.0 12 - 6 1.0 12 - 7 1.0 12 - 8 1.0 12 - 9 1.0 12 - 10 1.0 12 - 11 1.0 12 - 12 1.0 12 - 13 1.0 12 - 14 1.0 12 - 15 1.0 12 - 16 1.0 12 - 17 1.0 12 - 18 1.0 12 - 19 1.0 12 - 20 1.0 12 - 21 1.0 12 - 22 1.0 12 - 23 1.0 12 - 24 1.0 12 - 25 1.0 12 - 26 1.0 12 - 27 1.0 12 - 28 1.0 12 - 29 1.0 12 - 30 1.0 12 - 31 1.0 12 - 32 1.0 12 - 33 1.0 12 - 34 1.0 12 - 35 1.0 12 - 36 1.0 12 - 37 1.0 12 - 38 1.0 12 - 39 1.0 12 - 40 1.0 12 - 41 1.0 12 - 42 1.0 12 - 43 1.0 12'- 44 1.0 12 - 45 -1.0 l l 12-ii
DRESDEN Revision'1.0 January'1994 . -CHAPTER 12.. RADIOACTIVE EFFLUENT TECHNICAL STANDARDS ,( g -(RETS) N TABLE OF-CONTENTS PAGE 12.1. DEFINITIONS 12-1 1 -12.2 INSTRUMENTATION 12 A. RadioactivejLiquid Effluent Instrumentation 12-5 1. Operability 12-5 + 2. Surveillance 12-5 B. Radioactive' Gaseous Effluent Instrumentation 12-5 l. Operability 12 - 2. Surveillance 12 - C. Liquid and Gaseous Effluent 12 ' Instrumentation Bases 12.3 LIQUID EFFLUENTS 12-19 A. Liquid Effluents Limits and Reporting 12-19 Operability 1. Concentration in Unrestricted Areas 12 ! 2. Dose from Liquid Effluents 12-19; j 3. Dose Projections =12-20 4. Liquid Radioactive Waste Treatment System 12-21 5. System Operability and Plant Operations. 12-21 B. Liquid Effluents Surveillance-21 1. Concentration in Unrestricted Areas 12-21 2. Dose from Liquid Effluents 12-22 3. Dose Projections 12-22 s C.. Liquid Effluents Bases 27-12.4 GASEOUS EFFLUENTS 12-29 A. Gaseous Effluents Limits and Reporting 12-29f Operability 1. Dose Rate 12-29 2. Noble Gas Dose 12-29 3. Iodine-131, Iodine-133, Tritium and Particulates Dose 12 ; 4. Off Gas Treatment 12-31 5. Main Condenser Air Ejector 12-32 6. System Operability and. Plant Operations 12-32' B. Gaseous Effluents Surveillance 12-33; 1. Dose Rate 12-33 2 -. Noble Gas. Dose 12233 3. Iodine-131, Iodine-133, Tritium and Particulates ~. Dose 12-33 -4. -Off-Gas Theatment 12233 5. Noble Gases at the Main Condenser Air Ejector 12 > C. Gaseous Effluents Bases 12-38 t y j 12-iii -0 r
DRESDEN Revision 1.0 January 1994 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS CONTINUED i PAGE 12.5 RADIOLOGICAL ENVIRONMENTAL ISONITORING PROGRAM 12-40 A. Radiological Environmental Monitoring Program 12-40 B. Radiological Environmental Monitoring Program Surveillance 12-41 C. Radiological Environmental Monitoring Program Bases 12-48 l 12.6 RECORDKEEPING AND' REPORTING 12-49 1. Station Operating Records 12-49 2. Reports 12-49 1. Radioactive Effluent Release Report 12-49 2. Annual Radiologica) Environmental Operating Report 12-49 3. Non-Routine Environmental Reports 12-51 3. Offsite Dose Calculation Manual (ODCM) 12-51 4. Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12-52 g O! 12-iv
r DRESDEN . Revision 1 0 January 1994 i CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL' STANDARDS -(RETS) t LIST OF TABLES I lEZNBER TITLE PAGE i 1 f 12.1-1 Surveillance Frequency Notation 12-4 '? ) 12.2-1 Radioactive Liquid Effluent Monitoring. Instrumentation 12-7 t i 12.2-2 Radioactive Liquid Effluent Monitoring l Instrumentation Surveillance Requirements 12-9 j i 12.2-3 Radioactive Gaseous Effluent Monitoring l Instrumentation 12-12 } 12.2-4 Radioactive Gaseous Ef fluent Monitoring i Instrumentation Surveillance Requirements 12-15 [ 12.3-1 Allowable Concentration of Dissolved I or. Entrained Noble Gases Released from the Site. to Unrestricted Areas in Liquid Waste. 12-23 12.3-2 Radioactive Liquid Waste Sampling and Analysis ? Program 12-24 12.4 Radioactive Gaseous Waste Sampling and. Analysis Program 12-35 12.5-1 Radiological Environmental Monitoring Program 12-43
- f 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-44 12.6-1 Practical Lower Limits of Detection (LLD) for Standard Radiological Envircnmental Monitoring l
Program 12-45 r t f t i i 12-v i
DRESDEN Revision 1.0 January 1994 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINITIONS 1. Channel Functional Test (Radiation Monitor) - Shall be the injection of a simulated signal 4nto the channel as close to the -ensor as practicable to verify operability including alarm and/oy trip functions. 2. Dose Enuivalent I-131 - That concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, I-134, and I-135 actually presen.. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID ~14844, " Calculation of Distance Factors for' Power and Test Reactor Sites". 3. Hot Standby - Hot standby means operation with the reactor critical, system pressure less than 600 psig, the main steam isolation valves closed. 4. Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action. 5. Instrument Calibratiqn - An instrument calibration means the adjustment of an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument, including actuation, alarm, or trip. 6. Instrument Check - An instrument check is qualitative determination of acceptable operability by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable. 7. Instrument Functional Test - An instrument functional test means the injection of a simulated signal into the instrument primary sensor to verify the proper instrument response alarm and/or initiating action. 8. Member of the Public - an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose. 9. Mode - The reactor mode is that which is established by the mode-selector-switch.
- 10. The offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses regulating from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM 12-1
g. ~
- .b _
DRESDEN -Revision'1.0' _ January 1994 -12.1 DEFINITIONS'(Cont'd) b 'shall.also contain (1) the Radioactive Effluent Controls and Radiological. Environmental Monitoring: Programs described in Section 12.5 and.(2) descriptions of the information that should be included in the' Annual Radiological Environmental' 1 Operating and Radioactive Effluent Release Reports. required by Sections 12.6.2.2.1 and 12-.6.2.l. i
- 11.. Onerable - A system, subsystem, train,-component:or device-shall be OPERABLE or have OPERABILITY when it is capable of l
performing its specified function (s). Implicit in this definition shall be the assumption that'all necessary
- j attendant instrumentation, controls, a normal and an i
emergency electrical power source, cooling or seal water,.. i lubrication or other auxiliary equipment that.are required l for the system, subsystem, train, Component or device to l perform its' function (s) are clso capable of performing their related support function (s). .j
- 12. Oneratina - Operating means that a system, subsystem, t' rain, il component or_ device is performing its intended function in its required manner.
'l l .13. Oneratina Cvcle - Interval between the end of one refueling outage and the end of'the subsequent refueling outage, i
- i
- 14. The-Process Control Procram (PCP) shall.contain-the current'
~ formulas, sampling, analyses, test, and determinations to be O made to ensure that processing and packaging.ofLsolid: radioactive wastes based on demonstrated processing of i actual or-simulated wet solid. wastes will'be accomplished in-j such a way as;to assure compliance with 10:CFR. Parts.20,1 61, j and 71, State regulations, burial ground requirements, and. other' requirements governing the disposal of solid l radioactive waste. 1
- 15. Rated The_ mal Power.- Rated thermal power means a i
steady-state power" level of 2527 thennal megawatts. .!s
- 16. Reactor Power Oneration - Reactor power operation is any l
operation with the mode switch in the "Startup/ Hot l Standby" or "Run" position with the reactor critical and above.1% 1 rated thermal power. z! I 1. Startup/ Hot Standby. Mode - In this. mode,-the reactor-protection scram trips, initiated by? condenser low i vacuum and main steamline_ isolation valve. closure, and-j by-passed when reactor pressure is less than 600'psig;- the low pressure main steamlineLisolation valve closure trip is bypassed, the reactor protection- -j system is energized with.IRM neutron-monitoring system-trips and control rod withdrawal' interlocks in;
- i service.
1 2. Run Mode - In this. mode, the reactor protection-is l energized with APRM protection and RBM interlocks in [ service. 12-2 i .i .. f
DRESDEN Revision 1.0 January 1994 12.1 DEFINITIONS (Cont'd)
- 17. Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the RETS are those measured by the reactor vessel steam space detector.
- 18. Refuelina Outace - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the plant subsequent to that refueling.
For. the purposejof designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need_not be performed until the next regularly scheduled outage.
- 19. Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
When the mode switch is placed in the shutdown position a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection system trip systems are de-energized. 1. Hot Shutdown means conditions as above with reactor coolant temperature greater than 2120F. 2. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 212 F.
- 20. Source Check - The qualitative assessment of instrument response when the sensor is exposed to a radioactive source.
- 21. Surveillance Interval - Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
- 22. Definitions Related to Estimatina Dose to the Public Usina the ODCM Comnuter Procram:
1. Actual - Refers to using known. release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12. 2. Projected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are i NOT incorporated into the database. O 12-3 1
,, ~.. -...... i 4; :. il DRESDEN ,. Revision 1.0? l January-1994 j .~ -} f ~ a TABLE 12.l-1 SURVEILLANCE FREQUENCY NOTATION i f f f NOTATION-FREOUENCY l' S At least once per 8 hours i j l D -At least once per 24 hours i T At.least once per 72 hours l W At least once per 7 days 7, i a 2. M-At least onct, per 31' days O At-least once per-92 days j t l SA At least once per 184 days -i A At least once per 366 days j R At least once per refuel outage
- {
S/U Prior to each reactor:startup-j, ~ N.A. Not applicable E At least once per 550' days'fUnits'2 & i
- 3) and 18 months forLUnit'l-1 I
.: t
- I i
.- t i ^ q 1 .i 1 l 'i .j 12-4. u-
O DRESDEN Revision 1.0 January 1994 12.2 INSTRUMENTATION A. Radioactive Licuid Effluent Instrumentation l 1. Radioactive Licuid Effluent Instrumentation Operability 1. The effluent monitoring instrumentation shown in Table 12.2-1 shall be operable with alarm trip setpoints set to insure that the limits of Section 12.3.A are not exceeded. The alarm setpoints shall be determined in accordance with the ODCM. 2. With a radioactive liquid effluent monitoring l instrument alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative. 3. With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 12.2-1. Return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER. 4. In the event operability requirements and associated j action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.
- 2. Radioact ive Licuid Ef fluent Instrumentation Surveillance g
1. Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequencies shown in Table 12.2-2. B. Radioactive Gaseous Effluent Instrumentation l
- 1. Fadioactive Gaseous Effluent Inst rumentation Onerability 1.
The effluent monitoring instrumentation shown in Table l 12.2-3 shall be operable with alarm / trip setpoints set to ensure that the limits of Section 12.4.A are not exceeded. The alarm / trip setpoints shall be determined in accordance with the ODCM. 2. With a radioactive gaseous effluent monitoring l instruments alarm / trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative. O 12-5 1
p:- ' t* DRESDEN TRevision'l.0z January 1994 j L .1 12.2.B.l' Radioactive Gase'ous Effluent Instrumentation Onerability 'I (Cont ' d).. 3. With one'or more radioactive gaseous effluent monitoring llI instruments inoperable,.take the action shown-in Table 12.2-3. ' Return the instrument to' operable status within. ~ 30 days and,-if unsuccessful, explain in the next Radioactive Effluent Release Report why the i inoperability was not corrected in a timely manner. l ThisijsinlieuofanLER. 1 f' 4. The unit 2/3 plant chimneyigas sampling-system may be' L}L out of' service for 48 hours for. the purpose of servicing. ) the high range noble gas monitor _as.long as the following conditions are satisfied: 1. Both units are.at steady state conditions with,the li recombiners and charcoal absorbers in service for
- l the operating unit (s).
t [jl 2. The dose rate in unrestricted areas must be shown~. by calculation to be less than the limits of 12.4.A. assuming the charcoal absorbers are bypassed on both units. 1 I 3. Both offgas monitors on Unit-2 and Unit 3 must-be. jgt operational ~and the monitor reading correlated to the chimney release rate based on the conservative l assumption of both units' charcoal absorbers being l bypassed. 4. If the-provisions of.12.4.A.l.1,.12.4.A.l.2, or lij 12.4.A.l.3 cannot be met, an' orderly load' reduction of the unit (s) shall be initiated ~inmediately. 1 5. In the event operability requirements and associated ll: l action requirements cannot-be satisfied because of-- circumstances in excess of those. addressed in thisE Section, provide a 30-day written'reportito the NRC1and O no changes are required in the operational condition'of the plant,.and.this does.not prevent the plant.from i entry into any operation mode. h[
- 2. Radioactive Gaseous Effluent Instrumentation surveillance Each radioactive gaseous ~ radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check,, instrument check,.
calibration, and functional test operations at the 'frequencyLshown in Table.12.2-4. l l l I i s i i 12-6 l i
J DRESDEN Revision 1.0 January 1994 ) J TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Minimum Total i Channels No of Instrument Operable Channels Action 1. Service Water Effluent 1 1 10 Gross Activity Monitor 2. Discharge Canal 1 1 12 Sampler ACTIONS ACTION 10 - With less than the minimum number of operable channels,. releases via this pathway may continue, provided that at least once per 24 hours grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10-7 pCi/ml. ACTION 12 - Operability is verified prior to performing and once a day during planned discharge. l ? 12-7
.. -. ~.... _. - -.. ._m. r v. l 'DRESDEN Revision 1.01 j) r. January 1994 -7..
- j 6
- h V("Y
. TABLE 12.2-1 ] l RADIOACTIVE LIQUID EFFLUENT MONITORING: INSTRUMENTATION .i .I UNITS 2 & 3 i i 1 i j Minimum Total Channels' No. of Instrument-Operable. Channels Action. ] .i 1. Service Water Effluent 1 1 10 1 Gross Activity Monitor l l] 1 2. Liquid Radwaste Effluent-1 1 11 . Gross Activity Monitor n -i ACTIONS 'I t ' ACTION 10 - With less than the-minimum number. of operable channels, l.! releases via this pathway may continue,.provided:that at l least once per 12 hours grab' samples'are collected and analyzed for beta or gamma activity at an.LLD of less than. l or equal to 10" uCi/ml. l 1i ACTION 11 - With less than a minimum' number of operable channels, l,.-j i effluent releases-via this pathway may continue, provided 1 j-that prior to initiating-a release, at least 2 independent ~ samples are analyzed,- and at least'2 members of'the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluent via this pathway. kl J~ i l' r I i i e t[ .s a b 1 12 L' _...u, a
DRESDEN Revision 1.0-January 1994 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 IFunctional Calibration Instrument Source Instrument Test (b)(f) Check (f) Check 1. Service Water Effluent Gross Q (a,f,e) E (c) D E Activity Monitor 2. Discharge Canal (g) Sampler O I i I 12-9
~. ~ 1. -DRESDEN- ' Revision 1.0 ~ -i January-1994 -l "I TABLE 12.2-2 i i RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .[ UNITS.2 & 3 I ? l 3 unctional-Calibration-' Instrument ' Source ~ ~ F Instrument , Test (a) ( f) (b) (f) Check (f) Check -l l 1 1. Liquid'Radwaste Effluent Gross Q (e) E (c) D E(d) i Activity Monitor .i 2. Service Water Effluent Gross Q (e) E (c) D E Activity Monitor .j ? -i -t 9 t ,i p t:! l i -j i i t .t 1 t b j i i i 6 12-10 4 1
DRESDEN Revision 1.0 January 1994 TABLE 12.2-2'(Cont'd) g! RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The Instrument Functional Test shall also demonstrate that control room alatm annunciation occurs, if any of the following conditions exist! where applicable. 1. Instrument indicated levels above the alarm setpoint. 2. Circuit failure. 1 3. Instrument indicates a downscale failure. 4. Instrument controls not set in OPERATE mode. (b) Calibration shall include performance of a functional test. (c) Calibration shall include performance of a source check. (d) Source check shall consist of observing instrument response during a discharge. (e) Functional tests may be performed by using trip check and test circuitry associated with the monitor chassis. (f) Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. (g) Operability is verified prior to performing discharge and once a day during planned discharge. I r ? 'I O 12-11
-DRESDEN-Revision 1.0. - l i January 1994 [ TABLE 12.2-3 I -\\ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNIT 1 P } Minimum . Total -Applicable. Channels No..of . Operational-i Instrument Operable. Channels. Modes Action -l O 1. Main Chimney SPING Noble Gas 1 3 28 i Monitors ~ 27 2. Main Chimney Particulate 1 1 Samplers t 3. Main Chimney Iodine Samplers 1. 1 27 i 1 t 'I -j ? ? h r -I i l l .i t 4 -. i 'l s l l 12 L y 6 v e -. e
~. DRESDEN Revision 1.0 January 1994 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 i Minimum-Total Applicable i Channels No. of Operational Instrument Operable Channels Modes Action 1. Main Chimney Noble Gas /SPING/ 1 3 20 GE Low Range Activity Monitor 2. Main Chimney SPING Noble Gas 1 1 26 Monitors Mid, Hi Range 3. Main Chimney Iodine Sampler 1 1 22 4. Main Chimney Particulate Sampler 1 1 22 5. Main Chimney Flow Rate Monitor 1 1 21 6. Main Chimney Sampler Flow Rate 1 1 21 Monitor 7. Reactor Building Vent Exhaust 1 2 24 Duct Radiation Monitor 8. Reactor Building Vent SPING 1 1 25 Noble Gas Monitor Low, Mid, High Range 9. Reactor Building Vent Flow 1 1 21 i Rate Monitor
- 10. Reactor Building Vent Sampler 1
1 21 I Flow Rate Monitor i
- 11. Reactor Building Vent Iodine 1
1 22 l Sampler
- 12. Reactor Building vent 1
1 22 Particulate Sampler l l t l t l 12-13 i
.~ .1 i DRESDEN Revision'l'.0 January 1994' l TABLE-12.2-3-(Cont'd) Li "' m~ ~ t ~ . RADIOACTIVE GASEOUS ~ EFFLUENT MONITORING INSTRUMENTATION ACTIONS AND TABLE NOTATIONS f ACTION 20 " With less than the minimum channels operable, effluent ] =. releasesvia this pathway may continue for up to 30 days provided' grab samples are taken'at least once every'8. hours and analyzed for noble gas within 24 hours. In. addition,} restore the inoperable equipment to operable { status within 7 days, or. prepare and submit a report'to i the commission within the next.30 days outlining the plans, actions taken and procedures to be used to provide- .for the loss of sampling capability. t ACTION 21 - With the number of operable channels less than the l! minimum required, effluent releases via this pathway may a continue provided that the flow rate'is estimated at i least once per 4 hours. ACTION 22 - With less than-the' minimum channels operable, effluent 'l.; releases via this pathway may continue provided samplesL i are continuously collected with auxiliary sampling equipment,.as required in Table 12.4-1. i ACTION 24 - With less than the minimum channels operable, immediately .l-l suspend release of radioactive effluents via this 3', pathway.. ACTION 25 - With less than the minimum channels. operable, effluent ]u releases via this pathway may continue provided that the. minimum number of operable channels for'the Reactor i Building Vent Exhaust Duct Radiation Monitor.are. T operable. /- ACTION 26-With less than the minimum channels operable, effluent ll~L releases via this pathway-may continue provided-the low-range monitor is operable and on scale. Restore the l inoperable equipment to operable status within 21 days, l or prepare and submit a report toLthe_ commission pursuant' to specification 6.6.B within the next 30 days outlining. the plans, actions taken and procedures to be used to provide for the loss of sampling capability of the system. 1 ACTION 27-The main chimney SPING' monitor may be.out-of-service for l calibration and maintenance provided that particulate and l iodine samples are taken and analyzed. The samples shall be collected using alternate-filter. holders and pumps. i connected to the main chimney sample stream. ACTION 28 - With less than the minimum channels operable, effluent releases via this' pathway may continue provided daily. noble gas samples-are taken and' analyzed daily. Restore I the inoperable equipment to operable status within 30 days. If service can not he' returned, document equipment: availability difficulties within the Radioactive Effluent Release Report for the period including actions taken in response to the equipment and procedures used to provide for the loss of sampling capability of the system. 1 At all times i 1 12-14 i I 1
i -DRESDEN Revision 1.O j January 1994 ] TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Applicable Furictional Calibration Instrument' Source Operational Instrument Test (a)(e) (b) Check Check Modes 1. Main Chimney SPING Q E D M Noble Gas Monitor Low Range O O 12-15
. - ~. _... .j -.DRESDEN ' Revision:1.O~ ij ' January 1994 .c t TABLE 12.~2-4' RADIOACTIVE GASEOUS EFFLUENT MONITORING-- INSTRUMENTATION SURVEILLANCE REQUIREMENTS t UNITS 2 & 3 .i Applicable-Furictional Calibration-Instrument ' Source Operational. Instrument Test (a ) (e) (b) (e) - . Check (e) Check-Modes- .l. Main Chimney Noble O E D. M . Gas Activity Monitor 2. Main Chimney-SPING Q E D M
- ~
Noble Gas Monitor Lo, Mid, High Range 3 Main Chimney N.A. N.A. D(c) N.A. ] Particulate and Iodine Sampler 4. Main Chimney Flow .O E D N.A. .l Rate Monitor 5. Main Chimney Sampler O(d) E D N.A. Flow Rate Monitor 6. Reactor Bldg Vent. Q E D, O Exhaust Duct Radiation Monitor 7. Reactor Bldg Vent Q E D ~ M 'j SPING Noble Gas i Monitor Lo, Mid, High Range 8. Reactor Bldg Vent Q E D N.A. Flow Rate Monitor. 9. Reactor Bldg Sampler Q(d)~ E D -N.A. Flow Rate Monitor
- 10. Reactor Bldg Vent N.. A.
N.A. D{c) N.A. Particulate and Iodine Sampler l )'l 1'l 12-16 l
DRESDEN Revision 1.0 January 1994 TABLE 12.2-4 (Cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS ~1 (a) The Instrument Fsnctional Test shall also demonstrate that control room alasm annunciation occurs, if any of the following conditions exist,; where applicable. 1. Instrument indicates levels above the alarm setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in OPERATE mode. (b) Calibration shall include performance of a functional test. (c) Instrument check to verify operability of sampler; that the sampler is in place and functioning properly. (d) Functional test shall be performed on local switches providing low flow alarm. (e) Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. At all times. I O 12-17
c,. i DRESDEN.- ' Revision 1.OL January 1994 12,2.C 'Licuid And Gaceous' Effluents' Instrumentation Bases .I 1. The radioactive' liquid and; gaseous effluent instrumentation is provided.to monitor the release;of radioactive materials:in liquid and gaseous' effluents' i during releases. The alarm setpoints for the. -instruments are provided to ensure that the alarms will occur prior to exceeding-the limits of RETS, l R 1 L .i q t i ~i 'L f' I 'i i 5 i \\ f 'i 12-18 .I i
1 DRESDEU Revision 1.0 January 1994 12.3 LIOUID EFFLUENTS 12.3.A Licuid Effluents Limits and Penortina Onerability 1. Concentration in Unrestricted Areas The concentration of radioactive material released from the site to unrestricted areas (at or beyond the site boundary, Dresden Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.24022, with the Table 12.3-1 values for nchle gases. With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits. 2. Dose from Liauid Effluents The dose or dose commitment above background to a member of the public from radioactive materials in liquid effluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following: 1. During any Calendar Quarter: g l (1) Less than or equal to 3 mrem to the whole body. (2) Less than or equal to 10 mrem to any organ. 2. During any Calendar Year: } (1) Less than or equal to 6 mrem to the whole body. (2) Less than or equal _to 20 mrem to any organ. 3. With the calculated dose from the release of l radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) and defines the corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with Sections 12.3.A.2.1 and 12.3.A.2.2. This is in lieu of a Licensee Event Report. h 2Upon technical specification approval, ten (10) time's the Appendix B value may be used to determine the maximum instantaneous liquid release. 12-19
l: DRESDEN Revision 1.0 -January 1994 s 12.3.-A Licuid Effluents Limits'and Renortina Onerability [- (Cont'd) 1 4. With the calculated dose from the release of radioactive. materials in liquid effluents exceeding the limits of Sections 12.3.A.2.1 or 12.3.A.2.2., prepare and-submit a Special.Reporti to the Commission within 30-days and limit.the subsequent releases such.that'the dose or' dose ?ommitment to a member of.the public from all dranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to'less than or equal to 75 mrem) over 12 consecutive months. This Special Report'shall include an analysis which demonstrates that radiation' exposures to'all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special. Report shall use methods prescribed in the ODCM..This report is in lieu-of a Licensee Event Report. 5. When the projected annual whole body or:any -l. internal organ dose computed at.the. nearest LO downstream community water system is equal to or-exceeds 2 mrem from all radioactive materials released in liquid effluents-from the Station,- prepare and submit a Special Report within'30 days to the operator of the community: water-system. The' report'is1 prepared to~ assist the operator in meeting the requirements of'40 CFR-Part 141, EPA Primary Drinking Water: Standards. j: A copy of this report will be sent to the NRC. This is in lieu of a Licensee Event Report.. 3. Dose Proiections At all times during processing prior to discharge'to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose i due to liquid effluent releases to unrestricted. areas -i (Dresden Station ODCM Annex, Appendix F, Figure.F-1);f '{ when averaged over 31 days,. exceeds 0.13 mrem to the total body or 0.42 mrem to any organ. l i 'l I i O 12-20 .l
DRESDEN Revision 1.0 January 1994 12.3.A Licuid Effluents Limits and Renortina Onerability (Cont'd) 4. Licuid Radioactive Waste Treatment System If liquid waste has to be or is being discharged without treatment as required above, prepare and submit to the Commission with 30 days, a report which includes the following information. 1. Identification of the defective equipment. 2 Cause of the defect in the equipment. l 3. Action (s) taken to restore the equipment to an l. operating status. 4. Length of time the above requirements were not j satisfied. 5. Volume and curie content of the waste discharged l ahich was not processed by the appropriate equipment but which required processing. 6. Action (s) taken to prevent a recurrence of equipment failures. This is in lieu of a Licensee Event Report. 5. System Onerability and Plant Onerations In the event a limit and/or associated action requirements identified in Sections 12.3.A and 12.3.B cannot be satisfied bec2use of circumstances in excess of those addressed in tnic Section, no changes are required in the operar.lonal condition of the plant, and this does not provent the plant from entry into any operational moda. 12.3.B Licuid Effluents Surveillance 1. Concentration in Unrestricted Areas The concentration of radioactive material in unrestricted areas shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.3-2. The sample j analysis results will be used with the calculational methods in the ODCM to determine that the concentrations are within the limits of Section 12.3.A.l. O 12-21
DRESDEN Revision 1;0' January.1994 l .12.3.B Licuid Effluents Surveillance' :(Cont ' d) ,l () .2. Dose from Licuid Effluents -] The dose contribution from' measured quantities of radioactive material shall be determined:by' ,j calculation'at least once per'31 days and cumulative j summation of these total body and organ dosed shall be maintained'for each calendar. quarter. e 1 Doses computed at the nearest community water system. will consider only the; drinking water pathway and 'shall be projected using the methods prescribed'in' ODCM, at least once per 92 days. 3. Dose Proiections Doses due tX) liquid releases to unrestricted areas (at' or beyond the site boundary) shall be projected at. j least once per 31 days in accordance with the ODCM. i e ? EN .'I i f f 5 Y 1 P 1 i l s ,1 l 12-22 1
- .i
.l
DRESDEN Revision 1.0 January 1994 TABLE 12.3-1 ALLOWABLE CONCENI' RATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIOUID WASTE NUCLITE AC(uCi/ml)* l Kr-85m 2 x 10-8 Kr-85 5 x 10-8 Kr-87 4 x 10~5 j Kr-88 9 x 10-5 Ar-41 7 x 10-5 Xe-131m 7 x 10-' Xe-133m 5 x 10-d Xe-133 6 x 10-' i Xe-135m 2 x 10-d Xe-135 2 x 10-4 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0. O 12-23
DRESDEN-. Revision 1.0-. i January 1994'
- TABLE 12.3-2 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1.
1 LOWER LIMIT OF-TYPE OF. ACTIVITY. DETECTION-LIOUID RELEASE SAMPLItJG MINIMUM Af1ALYSIS-ANALYSIS ( LLD) ") TYPE FREQUErJCY ( 6 ) FREQUEtJCY ( 6 ) .(pCi/ml) A. Service M M I-131 1 x10-' Water .Releanes (4) M M Principal Gamma 5 x10-' ' (Grab Gample) Emitters 'M M M Dissolved & I x10-$ ' (Grab Sample) Entrained Gasec'" - Gamma Emmitters'" M M 11 - 3 1x10'5 (Grab Sample) (Composite) Gross Alpha 1x10" ' O O Sr-89, Sr 5 x10 (Grab Gample) Fe-55 (Gamma Emitters) 1x10 ' ,' ) LOWER LIMIT OF TYPE OF ACTIVITY DETECTIOt1 LIQUID RELEASE SAMPLItJG MI!JIMUM ANALYSIS ANALYSIS ( LLD) "' TYPE FREQUEf JCY ( 6 ) FREDUENCY(6) (pCi/ml)- B, Above T-T Principal Gamma 5x 1'0 Ground Emitters
- Liquid Storage Dissolved &
. Ix10-8 Tanka Entrained Casen'" (7) Gamma Emmittern* L l' l 12-24 m_____________________
- __________z_ ______
__________1_________________________________
DRESDEN Revision 1.0 January 1994 TABLE 12.3-2 RADIOACTIVE LTOUID WASTE 9AMPLitVJ A!!D AtlALYDTR PPOGPAM Ut1ITS 2 & 3 LOWER LIMIT OF TYPE OF ACTIVITY DETECTIOri LIOUID REL.. EASE S AM PLItJG a MItJIMUM ATJALYSIS ATJALYSI S ( LLD) "' TYPE FR EQU EtJCY ( 6 ) FREQU E!!CY ( 6 ) (pCi/ml) A. Batch Priot to Ptiot to Pt incipal Ganma 5x10" Release Each Hatch Each Hat ch Emi t t e r s ( 5 ) 1 x10 Tanke I-131 Prior to M Gross Alpha 1x10" Each liatch Composite (2) H-3 1x10-5 Priat to O Fe-55 1x10-* 4 Each Batch Composite (2) St -89, Sr-90 5x10 4 Ptlot to M Dissolved Enttained 1x10 One Batch /M Gases (6) (Gamma Emmitters) R. Plant M* M'" I-131 1 x10-* l Continuous (Grab qample) i R.> eases (.1 ) M* M* Principal Canna 5x10" (Grab Sample) Emittern
- M*
M"' Dissolved & 1 x10-5 (Gr ab Cample) Entrained Gasos* Gamma Emmitters* l 4 M'" M"' H-3 1x10 (Grab Sampl e) Gronn Alpha 1x10' O'" O'" St-89, Sr-90 5x10" (Grab Sample) Fe-55 (Gamma Emitt+rn) 1 x 10 -' LOWER L.IMIT OF TYPE OF ACTIVITY Dr:TECTIOfl L10UID RELEASE CAM PLl tJG MItJIMUM A!U LYSIS Af1ALYSIS (LLD)'" TYPE FREQUEtJCY ( 6 ) FREQUEIJCY ( 6 ) (pCi/ml) C. T T Principal Gamma 5x10" Above Emitterc i5' Gt ourid Liquid Dinsolved & 1 x10'5 Storage Entrained Cases"' Tankr. (7) Gamma Emmittets* O 12-25
c j 2 DRESDEN Revision 1.0 1 January 1994 . TABLE 12.3-2 (Cont'd) 7.t TABLE NOTATION-l. The LLD is defined in the.ODCM. 2. A composite sample is one in which the quantity of' liquid samples. i is proportional to the quantity of liquid: waste 1 discharged-and'in which the methodlof sampling employed results in a specimen.which is representative of the liquids released. 3. If the alarm setpoint.cf the service water effluent monitor as determined in the ODCM is exceeded, the frequency of: analysis shall be increased to daily until the condition'no longer. exists. 4. A batch' release is the discharge of liquid wastes of a discrete. volume. Prior to sampling for analyses, each' batch shall be isolated and then thoroughly mixed to assure representative sampling. A continuous' release is the discharge of liquid wastes-of a nondiscrete volume; e.g., from a volume or-system that has an input flow.during the release. 5. The principal gamma emitters for which the LLD specification [ applies exclusively are the following radionuclides: Mn-54, 'Fe-59, Co-60, Zn-65,-Co-58, Mo-99, Cs-134, Cs-137, Ce-141,.and j Ce-144. Other peaks which are measurable and identifiable lar l gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on a sample. Nuclides which are below the'LLD for the analyses shall not be reported as being.present at the LLD level for that nuclide. 6. The dissolved and entrained gases (gamma emitters) for which the -i LLD specification applies exclusively are the following radionuclides:.Kr-87,-Kr-88, Xe-133, Xe-133m,-Xe-135, and Xe-138. Other dissolved and entrained' gases (gamma emitters) which are measurable and identifiable by gamma ray spectrometry, together . ]~ with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample Nuclides which are below the LLD'for-the analyses shall.not be reported as being present at the LLD level for that nuclide. ? 7. A sample (s) from: Unit 1: Each of the above-grade liqpid waste tanks,. l Units 2 & 3: The Waste Sample Tanks, Floor" Drain Sample Tanks and the Waste Surge Tanks, shall be taken, analyzed, and recorded every 72 hours. If no j additions to a tank have been made since the last sample, the tank need not.be sampled until the next addition. v i 2 12-26 f =,
DRESDEN Revision 1.0 January 1994 9 12.3.C LIOUID EFFLUENTS BASES l 1. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402, i l 2. Dose t This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The operational requirements implements the guides set forth in Section II.A of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure'that the releases of radioactive material in liquid effluents sill be kept "as' low as reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Acuatic Dispersion of Effluents from Accidental and Routine 'eactor Releases for the Purpose of Implementing Appendix April.1977. NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113. 3. Licuid Waste Treatment g The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section ll.D of Appendix I to 10 CFR Part 50. O. 12-27
'DRESDEN-Revision-1.0 January 1994 l 12.3.C LIOUID EFFLUENTS BASES - (Continued) 4. Nechanical vacuum Pumn The' purpose of isolating the mechanical vacuum line is to limit release of activity from the main condensor..During } an accident, fission products would be transported.'from~the reactor through the main steam line~to the main condencer. l The fission product radioactivity would be sensed by the main steamlina radioactivity monitors which initiate isolation. l i r f h 1 Q
- l l
.. ) I .i I y.r I! -i i 12-28
- 3
DRESDEN Revision 1.0 January 1994 12.4 GASEOUS EFFLUENTS A. Gaseous Effluents Limits and Recortina Onerability l 1. Dose Rate The dose rate in unrestricted areas at or beyond the site boundary (Dresden Station ODCM Annex, Appendix F, Figure F-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the folloding. l 1. For Noble Gases: (1) Less than a dose rate of 500 mrem / year to the l-whole body. (2) Less than a dose rate of 3000 mrem / year to the l skin. 2. For iodine-131, for iodine-133, tritium and for'all l radionuclides in particulate form with half-lives greater than 8 days, less than a dose rate of 1500 mrem / year. 3. If the dose rates exceed the above limits, without l delay decrease the release rates to bring the dose rates within the limits, and provide notification to the Commission (per 10 CFR Part 20.2203). 2. Doble Gas Dose The air dose in unrestricted areas at or beyond the site boundary due to noble gases released in gaseous effluents from the unit shall be limited to the following: 1. For Gamma Radiation l (1) Less than or equal to 5 mrad during any calendar quarter. (2) Less than or equal to 10 mrad during any calendar year. 2. For Beta Radiation (1) Less than or equal to 10 mrad during any calendar quarter. (2) Less than or equal to 20 mrad during any calendar year. l 3. With the calculated air dose from radioactive noble 1 gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with Sections 12.4.A.2.1 and 12.4.A.2.2. This is in lieu of a Licensee Event Report. g 12-29
DRESDEN Revision 1.0 January 1994~ 12.4. A - Gaseous - Ef fluent s Limit s and-Recortina Onerability ' (Cont 'd) p m 4. With'the calculated air dose from radioactive noble l. gases in gaseous effluents exceeding the limits of Sections 12.4.A.2.1 or 12.4.A.2.2, prepare and submit a Special Report to the Commission within 30 days and limit the subsequent-releases such~that the doses or dose commitment to a member-of thel public from all uranium fuel cycle sources is limited to less than or equal.to 25 mrem to the total body or any.org< (except thyroid, which is limited to less than or equal to 75 mrem)'over 12-consecutive months. This Special Report shall-include an analysis which demonstrates that-radiation exposures to all members of the public from all uranium fuel cycle sources:(including ~all. effluent pathways and direct radiation) are less than 40 CFR Part 190 Standard. Otherwise, obtain a variance.from the Commission to. permit releases which exceed the 40CFR Part 190 Standard. The radiation exposure analysis contained in the-Special Report shall use the methods prescribed in the ODCM. This report is in' lieu of a Licensee-Event Report. 3. Iodine-131. Iodine-133. Tritium. and Particulate Dose The dose to a member of the public in unrestricted areas at or beyond the site boundary from iodine-131, - (~') iodine-133, tritium, and all radionuclides in particulate z \\j form with half-lives greater than 8 days in gaseous effluents released from the unit shall be limited to the following. 1. Less than or equal to 7.5 mrem to any organ during l any calendar quarter. 2. Less than or equal to 15 mrem to any-organ _during -l, any calendar year. 3. With the calculated dose from the release of. ] iodine-131, iodine-133, tritium, and all-radionuclides in particulate form with hal'f-lives greater than 8 daysLin gaseous effluents exceeding any of the above limits, prepare and; submit.to the-Commission within 30 days, a Special. Report.which identifies the cause(s) for exceeding the limit and'.
- defines the corrective actions taken-to ensure that.
future releases are in compliance with Seution 12.4.A.3.1 and 12.4.A.'3.2. This is in' lieu of a Licensee' Event Report. 4. With the calculated dose from theLrelease of iodine-131, iodine-133, tritium, and all radionuclides in particulate form ~with half-lives greater than 8 days in gaseous effluents exceeding the limits of Sections 12.4.A.3.1. or 12.4.A.3.2., Os prepare and submit a Special Report to the-Commission within 30 days and limit subsequent releases such that the dose or dose commitment to a 12-30
DRESDEN Revision 1.0 January 1994 12.4.A Gaseous-Effluents Limits and Reportina Coerability (Cont'd) member of the public from all uranium fuel sources-is limited to less than or equal to 25 mrem to the total body or organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that rad.iation exposures to all members of the public from all uranium fuel cycle sources (including all dffluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee-Event Report. 4. Off-Gas Treatment 1. At all times during processing for discharge to the l environs, process and control equipment provided to reduce the amount of concentration of radioactive materials shall be operated. 2. The above specification shall not apply for the l Off-Gas Charcoal Adsorber Beds below 30 percent of rated thermal power. Or 3. The recombiner shall be operable whenver the reactor is operating at a pressure greater than 900 psig. 4. The recombiner may be inoperable for 48 hours. 5. With either the recombiners inoperable, or all charcoal beds by-passed for more than 7 days in a calendar quarter while operating above 30 percent of the rated thermal power, prepare and submit to the Commission within 30 days a Special Report which includes the following information. a. Identification of the defective equipment. b. Cause of the defect in the equipment. c. Action (s) taken to restore the equipment to an operating status. d. Length of time the above requirements were not satisfied, e. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing. l I 12-31
I5 _ ) i DRESDEN-Revision 1.0 j January 1994 12.4.A Gaseous-Effluents Limits and Penortina Onerability' (Cont ' d)' ) f. Action (s) taken to prevent a recurrence.of . equipment failures. This:is in lieu of a' Licensee Event Report. l n 5. Main condenser Air Eiector. I -The release rate of the sum of the activities from the. 'I noble bases measured at'the main condenser. air ejector' -{ shall be limited to 100 microcuries/sec' per MWt '(af ter: 30. minutes decay) at all times. With the release rate of the sum of the activities from noble' gases at the-main condenser air ejector exceeding 100 microcuries/sec per i MWt~(after 30 minutes decay), restore the release rate to within'its' limits within 72 hours, or be in'at least HOT' STANDBY within the next 12 hours. 6. System Onerability and Plant Onerations -} r In the event a-limit and/or associated action I requirements identified in Sections:12.4.A and 12.4.B cannot be satisfied because of circumstances'in excess'of. those addressed in this Section, no changes are required-in the operational condition of the plant, and this does not prevent the plant from entry into any operational'- j mode. j-t i t i a i -i l -j 12-32 1 i
DRESDEN Revision 1.0 January 1994 12.4.B Gaseous Effluents Surveillance 1. Dose Pate The dose rates due to radioactive materials released in gaseous effluents from the site shall be determined to be within the prescribed limits by obtaining representative I samples in accordance with the sampling and analysis program specified in Table 12.4-1. The dose rates are calcu{atedusingmethodsprescribedintheODCM. 2. Noble Gas Dose The air dose due to releases of radioactive noble gases in gaseous effluents shall be determined to be within the prescribed limits by obtaining representative samples in i accordance with the sampling and analysis program specified in Sections A and B of Table 12.4-1. The allocation of effluents between units having shared effluent control system and the air doses are determined using methods prescribed in the ODCM at least once ever 31 days. 3. Iodine-131. Iodine-133. Tritium and Particulate Dose The dose to a member of the public due to releases of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the prescribed limits by obtaining representative samples.in accordance with the sampling and analysis program specified in Table 12.4-1. For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be estimated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses when possible. The allocation of effluents between units having shared effluent control systems and the doses are determined using the methods prescribed in the ODCM at least once every 31 days. 4. Off-Gas Treatment Doses due to treated gases released to unrestricted areas at or beyond the site boundary shall be projected at least once per 31 days in accordance with the ODCM. 1 l 12-33 i
'DRESDEN Revision 1.0. January.1994 12.4.B Gaseous Effluents SurveillanceD-Continued- ). 5. Noble Gases at the' Main-Condenser Air Eiector I The-radioactivity release-rate of noble gases atz(near). j the outlet of the main condenser air. ejector shall' be continuously monitored. The release rate of the sum of 1 the activities from noble 1 gases from the main' condenser
- l air ejector shall be determined to be within the.. limits.
of 12l4.A at the following frequencies by-performing an j ' isotopic analysis of a representative sample of gases
- E taken at the recombiner: outlet, or'at the air ejector-outlet if the recombiner is by-passed.
l. At least once per 31 days. ' i i t i 2. Within'4 hours following an increase, as indicated by the main condenser air ejector' noble; gas. 3 activity monitor, or greater than 50%, after factoring out increases due to changes in thermal power level and off-gas flow, in the nominal steady -state fission gas release from theiprimary coolant. .i P !o I i ? ?I 'f i i ' I i I f .I 12-34 ~ i d 5 -~r r v.,- - -. +4 e m ..-e u w m
1 DRESDEN Revision 1.0 January 1994 Table 12.4-1 j RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 j I LOWER LIMIT OF GASEOUS SAMPLING MINIMUM TYPE OF DETECTION RELEASE FREQUENCY ANALYSIS ACTIVITY (LLD) '" TYPE FREQUENCY ANALYSIS (pCi/ml) A. Main Principal Gamma 1x10-' M Chimney Emitters ) (Grab M Tritium 1x10-' Sample) Noble Gases '" 1x10-*
- g...i (continuous)
.M"'" I-131 1x10-22 Iodine Sample I-133 1x10* M Principal Gamma Partic late 1* 10 - ' (Continuous) Emitters $51 3 m Q Q Composite Sr-89, Sr-90 1x10' i 8 (Continuous) Particulate Gross Alpha Sample f Y O 12-35
a DRESDEN Revision 1.0~ January 1994 l.; Table 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING MJD ANALYSIS PROGRAM 4 UNITS 2 & 3 l
- t f
) LOWER LIMIT GASEOUS S AMPLI!JG MIIJIMUM TYPE OF ACTIVITY OF DETECTION i RELEASE FREQUEf1CY Af3ALYSIS Af4ALYSIS (LLD)'" TYPE FREQUEIJCY (pCi/ml) A. Main I Chimney React or M fF Principal 1 x 10'. Gamma Emi t t e r s '" 1x10 .j Bldd. (Grab Sample) M Ttitium Vent: St ack 'E B. Al1 W "" I-131 1x10-" j - Cont inuous,' Rel"ase Iodine Sample 1-133 1x1026 Typer W* Ptincipal Gamma as List ed Cont inuonn"' Pa r t i cu lat e Emittets 'M 1 x 10'" in A Sample (1-131, others)-- l above l Cont inuoun "Y"". Sr-89 1x10"2 Particulate Sr-90 1x10 n Sample Q
- I con t i nu ou o '"
Composite Gross Alpha 1x10-" Particulate Samp3e C. M,iin IJoble Gaa ""a d"*" Chimnev Monitor D. Reactor Bida. V ent-Con t. i nu ou n "2 'Y Noble Gasen 1x10-* ,j Monator St d t Ji E.' M W,S W'" 1-131 1 x10. iz. { Cont i nuoun "' Procean l o<h.ne Sample 1-133 1 x 10 - s Exhaunt i
- f. amp 3 e r W
PIincipal Gamma .Continuouc"' Particulate . Emitters
- 1x10-"
I Sample (I-131, others)- F. MVRS Wi" .1-131 1x10a2 -
- t Continuou"a, i
HVAC Iodine Sample I-133 1 x10- Exhaust Sample W) Principal Gamma Cont i nuou s Particulate Emitters 'M 1x10-" Sample (I-131, ot hers) -i i i 12-36 2 i
.1 DRESDEN Revision 1.0 January 1994 i TABLE 12.4-1 (Cont'd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i TABLE NOTATION 1. The lower limit f detection (LLD) is defined in the ODCM. 7 SamplingandanaIysesshallalsobeperformedfollowingshutdown, 2. startup, or a thermal power change exceeding 20 percent of rated thermal power in 'l hour unless (1) analysis shows that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. 3. Samples snall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. SampJing shall also be performed within 24 hn"-s following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement doer not apply if 1) analysis shows.that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. 4. The ratio of sample flow rate to the sampled stream flow rate shall be known. 5. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions, and Mn-54, Fe-59, Co-60, 2n-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall'not be reported as being present at the LLD level for the nuclide. 6. Analysis frequency shall be increased to 1/ week if release rates exceed 1% of any applicable limit referenced in the ODCM, when added to Units 2 and 3 airborne effluents. O 12-37
L{ 'l 'JRESDEN Revision-l.0~ -January 1994 q 12.4.C Gaseous Effluents Bases l 1. Gaseous Effluents - Dose This Section is provided to ensure that the dose at unu unrestricted area boundary.from gaseous effluents from the units on site will be within the annual dose limits of 10CFR20 for unrestricted areas. These limits provide reasonable hssurance that radioactive material discharged-in i gaseous effluents will not result in the exposure of an j individual in an unrestricted area to annual average concentrations exceeding the limits specified in' Appendix B, Table 2 of 10CFR20.1001-2402. The release rate limits restrict, at all times, the corresponding gamma and beta l dose rates above background to an individual at or beyond' the unrestricted area boundary to less than or equal,to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also-i ~ restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to'less than:or j equal to 1500 mrem / year. For purposes of calculation doses t resulting from airborne releases, the main chimney is considered to be an elevated release point and the. reactor building vent stack is considered to be a mixed mode release point. j 2. Dose. Hoble Gases l /"'s This Section is provided to implement the requirements of j ' (,,/ Sections II.B, III.A and IV.A of. Appendix I, 10 CFR Part-50. 4 The Operability Requirements implement the guides set'forth in Section II.3 of Appendix I. The statements provide the required operating flexibility and at the same time. implement the guides-set forth in Section IV.A of Appendix.I to assure that the releases of radioactive material in -r gaseous effluents will be kept "as low as is reasonably [ achievable." The surveillance requirements implement the l requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is:to be shown by j calculational procedures based on models.and data such-that the actual' exposure of an individual through the appropriate i pathways is unlikely to be substantially underestimated. The dose calculations est'ablished in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaceous effluents will be-consistent with the methodology.provided in Regulatory Guide 3 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the-Purpose of Evaluating-Compliance with 10 CFR Part 50, Appendix I,"=Revisionfl, '1 October 1977 and Regulatory Guide 1.111, " Methods for 1 Estimating Atmospheric Transport and Dispersion of Gaseous
- l
-Effluents in Routine Releases from Light-Water Cooled Reactors,," Revision 1,-July 1977. NUREG-0133 provides i methods for dose calculations consistent with Regulatory ~ Guides'1.109 and 1.111. ~ i s i 32-38 i =.
DRESDEN Revision 1.0 January 1994 12.4.C Gaseous Effluents Bases (Cont'd) 3. Dose, Fadiciodines. Radioactive Material in Particulate Form and Radionuclides Other than Noble Gases This Section is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Operability Requirements are the guides set forth in Section II.C of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably-achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate limits for radiciodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these. limits were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man.
4. Gaseous Waste Treatment The operability of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures that the system will be available for-use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be operable when specified provides. reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. O 12-39
.~ DRESDEN Revision 1.0 Januaryzl994 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l A. Radiolonical Environmental Monitorina Procram 1. The Radiological Environmental Monitoring Program -l ; given in Table 12.5-1 shall be conducted except as specified below. j 2. With the Radiological Environmental Monitoring Program l: ! not bsing conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual. 1 Radiological Environmental Operating Report., a descri'ption of the reasons for not conducting the program as required and the plans for-preventing a. recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous' conditions, seasonal unavailability, contractor omission which~is corrected
- I as soon as discovered, malfunction of sampling equipment, or if a person who participates in she program goes out of business.
If the equipment malfunctions,. corrective actions shall be completed as l soon.as practical. If a person supplying samples goes out of business, a replacement supplier will~be found as soon as possible. All deviations from the~ sampling schedule shall be-describe in the Annual Report. f 3. When the level of radioactivity in an environmental sampling medium at one or more of the locations- . /(,)% specified in the Table 12.5-1 exceeds the limits of the Table 12.5-2 when averaged over any calendar r quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of.any i release conditions, environmental factors or other aspects which caused the limits of the Table 12.5-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result'of-i plant effluents; however in such an event the i condition shall be reported and described in the Annual Radiological Environmental Operating Report. 4 4. With milk samples unavailable from one or more of,the sample locations required by Table 12.5-1, identify locations for obtaining replacement' samples:and. add them to the Radiological Environmental Monitoring Program within 30 days. The locations from which samples were unavailable may then be deleted ~from the l monitoring program. In lieu of Licensee. Event Report,: i identify the cause of the unavailability of-samples and identify.the new location (s) for obtaining replacement samples'in the Annual Radiological Environmental Operating Report and also.includeLin the, report a revised figure (s) and table' reflecting the new location (s). 1 t 12-40
DRESDEN Revision 1.0 January 1994 1 ] 12.5.A Radioloaical Environmental Monitorina Procram (Cont'd) 5. A census of nearest residences and of animals l1 producing milk for human consumption shall be conducted annually (during the grazing season for i animals) to determine their location and number with respect to the site. The nearest residence in each of the 16 meteorological sectors shall also be determined within a distance of five miles. The census'shall be condudted under the following. conditions: 1. Within a 2-mile radius frcm the plant site, j' enumeration of animals and nearest residences by. a door-to-door or equivalent counting technique. 2. Within a 5-mile radius, enumeration of animals by l using referenced informaticn from country agricultural agents or other reliable sources. 6. With a land use census identifying location (s) of l animals which yield (s) calculated dose or dose commitment greater than the values currently being calculated in Section 12.4.A.3, the new location (s) shall be added to the Radiological Environmental Monitoring Program within 30 days, if possible. The sampling location, having the lowest calculated dose or dose commitment (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. 7. Radiological analyses shall be performed on samples l-representative of those in Table 12.5-1, supplied as a part of the Interlaboratory Comparison Program which has been approved by the NRC. 8. With analyses not being performed as required, report l the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 9. System Operability and Plant Operations . l In the event a limit and/or associated action requirements identified in Sections 12.5.A and 12.5.B cannot be satisfied because of circumstances in excess of those addressed in these Sections, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode. l B. Radiolecical Environmental Monitorina Surveillance l 1. The radiological environmental monitoring samples shall be collected pursuant to Table 12 5-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 12.5-3. ~ 12-41
0 1 'DRESDEN
- Revision-1.0;
{ ' January 1994 12.5.B Radioloaical Environmental Monitorina Surveillance (Cont'di n- ".. k,) 2. The1results of analyses performed on radiological-l- environmental monitoring samples.shall be-summarized in the-Annual Radiological Environmental Operating Report. ^ 3. The land use census shall'be conducted at least once l-per twelve months between the dates.of. June 1 and' Octobqr 1 by a door-to-door survey,. aerial survey,. road survey, or by consulting local agriculture authorities. 4. The results of the land use census shall be included j in the Annual Radiological Environmental Operating Report. 5. The results of the'e.nalyses performed.as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental' Operating Report,. The analyses shall be done in accordance with ODCM Table 11-1. 4 4 l / i 't r 12-42 l 1 f N w a ~ -. n a
DRESDEN Revision 1.0 January 1994 TABLE 12.5-1 EDIOLOGICAL Eh".IIRONMENTAL MONITORING PROGRAM MINIMUM NUMBER OF EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS 1.
AIRBORNE A. Particulates 17 lochtions continuous operation Gross beta and l of sampler for a week gamma isotopic as specified in ODCM Table 11-1. B. Radiciodine 17 locations continuous operation I-131 as specified of sampler for two in ODCM Table weeks 11-1. 2. DIRECT 42 locations Quarterly RADIATION (Minimum of two TLDs per packet) 3. WATERBORNE A. Surface Water 2 locations Monthly composite of Gamma Isotopic weekly collected analysis of each samples composite sample B. Sediment I downstream Annually Gamma Isotopic location in analysis of each receiving body of sample water C. Plant Cooling Water Intake, Discharge Weekly Composite Gross Beta analysis of each sample 4. INGESTION A. Milk 2 locations At least once weekly I-131 analysis of when animals are on each sample pasture; at least + once per month at other times B. Fish I location in Semiannually Gamma Isotopic receiving body of analysis on edible water portions
- Sample locations are described in ODCM Chapter 11.
O 12-43
L DRE.2bdN : - Revision 1. January 1994 r Table 12.5-2 REPORTIIIG LEVELS FOR. RADIOACTIVITY-COIICENTRATIONS III EIP/IRONMENTAL SAMPLES . - f; FOOD ANALYSIS ~ WATER: AIRBORNE PARTICULATE FISH MILK PRODUCTS l - (pCi / l) - - OR GASES (pCi /m') (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) i-i H-3 2 X.10' A.= w a,a (see. Note 1) Mn-54 1 X 10' 3 X 10' Fe 4 X 10: 1 X 10' t Co-58 l' X ' 10' 3 X 108 Co-60 3'X 10' 2 X 10' Zn-65 3 ' X.102. 2 X 104 Zr-Ub-95' 4.X 102 I-131' 2 0.9 3 1 X 102 Cs-134 30' 10 1 X 10' 60 2 X 10' Cs-137 '50 20 1 X 10' 70 2 X 105 - 7 Ba-La-.14 0 : L2.X 10 2 ' 3 x 102 t ? ._ Mote: -1).1: For. drinking water samplen. This is 40 CFR Part 141 value. c ~ 12-44I i 1 w e-M m m.et m"'esi-*"te+>as T-M-*--?-9 Tens =wenE di'ADw' wT' Jasete e3T
- 75WR1'rw*4h'48' WWW-'M'M'*
Af*ME*h.Pd-'eh-M - 9*m m trte T' D-Y-*p'W WL' 4'r We 'e ' 4 19 eg -re+.+ee+1eM -vt ev *e e'ta + e+ as mee-M e. tlre see n <r +ww e ov e-so.-"'oin+=- w-w m e <sieti+ =rer+m eis w + - -naet=me e e e-w.e wa em em+wie**=e-e sseri
DRESDEli Revision 1.0 January 1994 Table 12.5-3 PRACTICAL LOWER LIMITS OF DETECTIOIT (LLD) FOR STAllDARD RADIOLOGICAL EIlVIROIIMENTAL MOIIITORING PROGRAM i (LLD) * -SAMPLE MEDIA AllALYSIS (4.660) UNITS Airborne " Particulate" Gross Beta; O.01 pCi /m' (C ) 3 Gamma Isotopic 0.01 pCi/m (C) Airborne I-131 Iodine-131 0.10 pCi / m' (C ) Milk /Public Water I-131 5* pCi/1 Cs-134 10 pCi/1 Cs-137 10(C) pCi/1 Tritium 200 pCi/1 Gross Beta 5 pCi/1 Gamma Isotopic 20 pCi/1/nuclide Sediment Gross Beta"" 2 pCi/g dry Gamma Isotopic 0.2 pCi/g dry Fish Tissue .I-133-Thyroid 0.1 pCi/g wet Cs-134, 137 0.1 pCi/g wet is) 1.0 pCi/g wet Gross Beta Gamma Isotopic 0.2 pCi/g wet Hote: A. 0.5 pCi/1 on milk samples collected during the pasture season. B. Reference to Cs-137 C. 5.0 pCi/1 on milk samples (Notes continued next two pages) 12-45 9 9 9.
.k DRESDEN Revision:1.0 l ~ January 11994 4 i J Table 12.5-3 (Cont'd) e -PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM { TABLE NOTATION i D. The LLD is the smallest concentration of radioactive material-in a-sample that-will be detected with 95 percent probability with only 5% probabili!ty of falsely concluding that a blank ~ observation represents a "real" signal. For a particular measurement system (which may include radiochemical c) separation)~ 4.66 - ( Sn) LLD = ( A) (E) (V) (2.22) (Y). (exp (-AAt)) (t) Where: 1 LLD is the "A priori" lower limit of detection for a blank sample or' l background analysis as defined above~(as pCi per unit' mass or volume) Sn .is the square root of the' background count or of a-blank sample count; is the estimated standard error of a; background count or.a. blank sample count as appropriate (in units of counts). ~! E is the counting efficiency (as counts per disintegration). A 'is the number of gamma rays omitted per disintegrat'on for gamma: I i ray radionuclide analysis (A.= 1.0 for gross alpha and tritium i measurements). V is the sample size (in-units of mass or volume). 2.22 is the number of disintegrations per minute-per picocurie:. Y is the fractional radiochemical yield when applicable [(otherwise-Y=1.0). I A is the radioactive decay' constant for the:particular radionuclide j (in units of reciprocal minutes). 1 i At is'the elapsed-time between the midpoint of sample collection'and. the start t-ime of counting. -.(t = 0.0.for environmental samples and for gross alpha measurements). t .is the duration of the. count (in units of_' minutes).. J 5 The value of "Su" used in the calculation of the.LLD'for a detection ~ system shall be based on an. actual observed background count or -- a - blank sample count (as appropriate) rather than on an unverified theoretically predicted-value. Typical values of "E", "V", "Y", "t" and "At" shall IM9 used in the calculation. 12-46 .1 - l
DRESDEN Revision 1.0 January 1994 Table 12.5-3 (Cont'd) PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD RADIOLOGICAL EIWIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS For gamma ray radionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus and FWHM (Full Width at Half Maximum) of the gamma ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall'be used in the calculation. The LLD for all measurements is defined as an "A priori"~(before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular sample measurement. E. Other radionuclides which are measurable and identifiable by gamma ray spectrometry, together with the nuclides indicated in Table 12.5-3, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. O O 12-47
DRESDEN Revision 1.0 ? January.1994 J -sc-12.5.C Radioloaical Environmental Monitorina Procram Bases 1. Monitorina Procram The radiological environmental monitoring program required -i by this Section provides measurements of radiation and of -i radioactive materials in those exposure pathways and for 1 L those radionuclides, which lead to the highest potential l L radiation exposures of individuals resulting from.the station opefation. This monitoring program thereby ) supplements-the radiological effluent monitoring program by-verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than a expected on'the basis of the effluent measurements and L modeling of the environmental exposure pathways. -Program changes may be' initiated based on operational experience. 1 The detection capabilities required by Table 12.5-3 are state-of-the' art for routine environmental measurements'in j industrial laboratories. The specified? lower limits of detection for I-131-in water, milk and'other food products _ correspond to -pproximately-one-quarter of the: Appendix I to' l 10 CFR Part 50 design objective dose-equivalent'of 15 mrem / year fo) atmospheric releases and 10 mrem / year for L liquid releases to the most sensitive organ'and individual. s They are based on the assumptions given in-Regulatory Guide 1.109, "Calculetion of Annual Doses to. Man from Routine. Releases of Reactor Effluents for the Purpose of Evaluating 'l Compliance with 10 CFR Part 50, Appendix I", October 1977, i except the change for an infant consuming 330 liter / year of drinking water instead of 510 liters / year. ,b b 2. Land Use Census This Section is provided to ensure that. changes in.the use l L of unrestricted areas are identified and that modifications-. ~j to the monitoring program are made if required by the' results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to110 CFR'Part 50. j 3. Interlaboratorv Comnarison Procram The requirement for participation in the-Interlaboratory- ~i Comparison Program is provided to ensure that independent' checks on the precision and accuracy of the measurements of radioactive material in environmental sample _ matrices are perf ormed as - part of the quality assurance" program' for - environmental monitoring in order to. demonstrate that the-results are reasonably valid. 12-48 .. ] ) w
DRESDEN Revision 1.0 January 1994 12.6 PECORDMEEPIMG AND REPORTING 1. Station Operatiac Records 1. Records and/or logs relative to the following items l shall be kept in a manner convenient for review and shall be retained for at least five years. l'. Records and periodic checks, inspection and/or l calibrations performed to verify the surveillance requirements (See the applicable surveillance in the Instrumentation, Liquid Effluents, Gaseous Effluents, and Radiological Environmental Monitoring Sections) are being met. All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded. 2. Records of radioactive shipments. l 2. Records and/or logs relative to the following items l' shall be recorded in a manner convenient for review and shall be retained for the life of the plant. 1. Records of off-site environmental monitoring l surveys. 2.. Records of radioactivity in liquid and gaseous l wastes released to the environment. 3. Records of reviews performed for changes made to l the ODCM. 2. Renorts 1. Radioactive Effluent Release Report j The Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted to the Commission prior to April 1 of each year. The report shall include a lA summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR Part 50.36a and Section IV.B.4 of Appendix I to 10 CFR Part 50. 2. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of l each year. The report shall include summaries, 3 interpretations, and analysis of trends of the resu'lts of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives in (1) the ODCM and (2) Sections IV.B.2., IV.B.3, and IV.C of Appendix I 12-49
-. -. -. -. ~. y-DRESDEN Revision 1.0 ' January'1994' i 12.6.2 Resorts - Continued ./ lq to 10 CFR Part 50. A detailed listing of the requirement of'the report is :given below: l t (a) Results-of environmental; sampling-summarized on a quarterly basis following the format of Regulatory Guide 4.8 Table 1.(December 1975);- (individual sample results will b'e retained at' j the station); 1 In the' event that some'results are not available i for inclusion with the-report, the report'shall e be submitted noting and explaining the reasons for the. missing results. Summaries, interpretations, and analysis.of-trends of the-7 results are to be-provided. (b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of l radioactivity including the maximum noble gas gamma and beta air' doses in the unrestricted-.. I area. The assessment of radiation doses 1shall be performed ~in accordance with the-ODCM. (c) Results of the census'to determine the~ locations of animals producing milk for human consumption, and the pasture season ~ feeding practices at dairies in the monitoring _ program. (d) The reason for'the omission if the nearest dairy to the station is not in the monitoring program. (e) An annual summary of meteorological conditions concurrent with the releases.of1 gaseous effluents j in the form of joint frequency distributions of 1 wind speed, wind direction, and atmospheric. stability.. (f: The results of the interlaboratory comparison 'i program described in Section 12:.5. A.7. (g) The results of the 40 CFR:Part 190 uranium fuel cycle dose analysis-for each calendar year. I (h)- A summary of the monitoring program, including _ 1 maps. showing sampling locations'and tables giving.: -distance and-directionLof sampling locations fromi i the station. a i 1'l j c u k 12-50 1
o DRESDEN Revision 1.0 January-1994 3. Non-Routine Environmental _ Report (a) If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and'if the radioactivity is attributable to plant operation, a written report shall be submitted to the' Regional Administrator of NRC Regional Office, with a copy of the Director, Office of Nuclear Reactor Regulation', within 30 days from the end of the quarter. When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall have been exceeded if SC / (RL) p is equalito or i greater than 1 where C is the concentration of. the i" radionuclide in the medium and RL is the reporting level of radionuclide i. (b) If radionuclides other than those in Table 12.5-2 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective coses of 10 CFR ~ Part 50, Appendix I. (c) This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous affect. 12.6.3. Offsite Dose Calculation Manual (ODCM) 1. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and ligtid effluents and in the calculation of gaseous and liquid effluent monitoring Alarm / Trip setpoints and in the conduct of.the Radiological Environmental Monitoring. Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring l Programs required by Technical Specification Sections 6.2.F and 6.2.G and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications Sections 6.6.C.1 and 6.6.C.2. Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133. The ODCM shall be subject to review and approval by. the Commission prior to initial implementation. O 22-51
=y DRESDEN' Revision l.0-January 1994-112.6.3 offsite Dose calculation Manual loDcM)-(cont'd) T/~ -i (.; 2. Changes to the ODCM: (1) Shall be documented and records of reviews l performed shall be retained as required by. 4 Specification 6.5.B. This documentation shall contain: (a) Sufficient information to support the- 'I change together with appropriate analyses 1 or evaluations justifying-the change (s); and (b) A determination that the change will i maintain the level of radioactive-effluent-control required by 10 CFR Part. 20.1302,~40 CFR Part 190, 10 CFR Part 50.36a, and-Appendix I to.10 CFR Part 50 and not adversely impact the accuracy or-reliability of effluent, dose or set point calculations. (2) Shall be effective after. review and: acceptance by~ j the Onsite Review & Investigative Function'and the approval of the Station-Manager, on the date specified by'the Onsite Review and Investigative Function. (3) Shall.be submitted to the Commission in the form I -\\ of a complete,. legible copy of the entire ODCM as a part of.or concurrent with the' Semiannual Radioactive Effluent Release Report for the period of the report-in which'any change to the ODCM was made effective. :Each change shall be 4 identified by markings in1the margin.of the: affected pages, clearly. indicating the areaaof a the page that.was changed, and shall. indicate the t date (e.g., month / year) the-change.was implemented. 12.6.4-Maior Chances to Radioactive Waste Treatment Systems ~(Licuid j and Gaseous) NOTE: This information may be submitted as part of the-annual FSAR update. 1. ' Licensee. initiated major. changes to the radioactive h waste systems may be made.provided: 1 ) 'I ? s i i 12-52 a
a DRESDEN Revision 1.0 January 1994 12.6.4 Maior Chances to Radioactive Waste Treatment Systems (Licuid and Gaseous) (Cont'd) The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the On-Site Review and Investigative Function. The discussion of each change shall contain: (1) A summary of the evaluation that led to the determination that the change could be made in hecordance with 10 CFR Part 50.59; (2) Sufficient detailed information to support the reason for the change; (3) A detailed description of the equipment, components, and process 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; (5) A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the period in which the changes were made; (6) An estimate of the exposure to plant operating p*csonnel as a result of the change; and (7) Documentation or the fact that the change was reviewed and found acceptable by the On-Site Review and Investigative Function. 2. The change shall become effective upon review and acceptance by the On-Site Review and Investigative Function. O 12-53 1 l \\
^ r 3: DRESDEN Revision 1.0 January'1994- [ DRESDEN ANNEX INDEX '.\\.) PAGE REVISION EAGE REVISION APPENDIX F F-i 1.0 F-43 1.0 P-ii 1.0 F-44 1.0-F-iii 1~0 ) F-45 1.0 F-iv 1.0 F-46 1.0 F-1 1.0 F-47 1.0 F-2 1.0 F-48 1.0 F-3 1.0 F-49 1.0 F-4 1.0 F-5 1.0 F-6 1.0 F-7 1.0 F-8 1.0 F-9 1.0 F-10 1.0 F-11 1.0 F-12 1.0 F-13 1.0 F-14 ' 1. 0 F-15 1.0 F-16 1.0 F-17 1.0 F-18 1.0 s / F-19 1.0 F-20 1.0-F-21 1.0 F-22 1.0 F-23 1.0 I F-24 1.0 i F-25 1.0 F-26 1.0 F-27 1.0 F-28 1.0 F-29 1.0 F-30 1.0 F-31 1.0 F-32 1.0 P-33 1.0 F-34 1.0 F-35 1.0 F-36 1.0 F-37 1.0 i F-38 1.0 ) F-39 1.0 J F 1.0 F 1.0 F-42 1.0 F-1 +
F- ~ ] DRESDEN Revision 1.0 January 1994 APPENDIX F STATION-SPECIFIC DATA FOR DRESDEN UNITS 1, 2, AND 3 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 DRESDEN 1 DRESDEN 1, 2, 3 k O O F-ii
5.c 'DRESDEN Revision 1.0 .f January 1994-L +- APPENDIX F ~ LIST OF TABLES i 1 1RR4BER TITLE PAGE i i F-1 Aquatic Environmental Dose, Parameters' F-2 l} F-2 Station Characteristics F-3 l F-3 Critical Ranges F-4' f i F-4 Average Wind Speeds F-5. F-5 X/Q and D/0 Maxima At or Beyond the I Unrestricted Area Boundary F-6 't I F-Sa X/Q and D/0 Maxima At or Beyond the Restricted Area Boundary F-7. F-6 D/O at the Nearest Milk Cow and Meat Animal f Locations Within 5 Miles F-8 j t F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1-cm Depth at the Unrestricted Area Boundary ~mr Selected Nuclides F 1 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary fnr Selected Nuclides F-24~ j F-8 Parameters for Calculation of N-16 Skyshine _i Radiation from Dresden 2/3 F-39 ~~ Supplemental Tables i A Elevated Level Joint Frequency Dictribution' ] Table Summary - 300 Foot Elevation Data F-40 l -Summary Table of Percent by Directjon and Class [ -Summary Table of Percent by Direction and Speed i -Sammary Table of Percent by Speed and Class ? B Mixed Mode Joint Frequency Distribution el Table Summaries - 150 and 35 Foot Elevation Data F-42 -Summary Table of Percent by Direction and Class -Summary Table of Percent by Direction and Speed l -Summary Table of Percent.lyy Speed and Class-i 'C Ground Level Joint Frequency Distribution Table Summary - 35 Foot Elevation Data F-46 -Summary, Table of Percent by Direction and Class 2 -Summary Table of Percent by Direction.and Speed I
- p..
-Summary Table of Percent by Speed and Clas- .i i Ll ..c- -- m - s
DRESDEN Revision 1.O: ~ January 1994 APPENDIX F LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Boundary F-48 F-2 Restricted.$rea Boundary F-49 4 9 i O P l O F-iv t 9
b .i DREsDEN Revision 1.0 ' January 1994- -APPENDIX F i STATION-SPECIFIC DATA FOR DRESDEN- .j UNITS 1, 2, AND 3 i i F.1 INTRODUCTION ~ i This appendix containsi data relevant to the Dresden site. Included are + a diagram of the unrestricted area boundary.~and tables of values of parameters used in offsite dose assessment. F.2 REFERENCES FoR DRESDEN 1 1. " Determination of Radial Distances from Exhaust Stack to Closest Offsite Location," Sargent and Lundy, Analysis and Technology'- Division, Dresden Calculation ATD-0033, Revision 0, December 26, 1991. 2. " Radial Distance to Restricted Area Boundary," Sargent and Lundy, Analysis and Technology Division, Dresden Calculation ATD-0093, Revision 0, April 24, 1992. 3. " CECO ODCM Appendix F Tables for Dresden 1," Sargent & Lundy, Analysis and Technology Division, Dresden Calculation ATD-0125,
- - i 3
A Revision 0, June 11, 1992. REFERENCES FoR DRESDEN 1, 2, and 3 1. Sargent & Lundy, Nuclear Safeguards and Licensing Division, Calculation, " Appendix I Technical Specification Tables," Revision-2, July 10, 1979. 2. Sargent and Lundy, Analysis and Technology Division, Dresden Calculation ATD-0033, Revision 0, December 26, 1991. 3. " Verification of Environmental Parameters used for Commonwealth Edison company's offsite Dose Calculation," NUS Corporation, 1988. 4. " Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculation," NUTECH, 1992. l, I F-1 .j l l
DRESDEN Revision 1.0 January 1994 Table F-1 Aquatic Environmental Dose Parameters for Dresden 1, 2, 3 General Information* The station liquid discharge flows into the Illinois River. The nearest public potable water intake is at Peoria, 106 river miles downstream of the station. There is no irrigatio'n occurring on the Kankakee, Des Plaines, or Illinois Rivers downstream of the station. Recreation includes one.or more of the following: boating, waterskiing, swimming, and sport fishing. {: Downstream dams on the Illinois River within 50 miles of the station are located as follows: At Dresden Island At Marseilles At Starved Rock i l This is based on information in Figure 2.2.6-1 of the Dresden Updated Final Safety Analysis Report (update through Rev. 5, June 1987) and in Section 2.4.1.1 and Figure 2.4-2 of the LaSalle Environmental Report. Water and Fish Incestion Parameters Parame t e r Value j l 1/M*, 1/M' l.0 F*, cfs 1.85E4 f F, cfs 1.04E4 t', hr" 24.0 d t", hr 106.0 Limits on Padioactivity in Unnrotected Outdoor Tanks
- 1 Refer to Section 3.8 of the Technical Specifications of Units 1, 2, and 3.
- This is based on information in the Dresden Station Safety Analysis Report (SAR), Section 2.5, Dresden Station Water Flow Schematic, and Braidwood and LaSalle Stations' collective data.
'The parameters are defined in Section A.2.1 of Appendix A. "t' (hr) = 24 hr (all stations) for the fish ingestion pathway "t" (hr) = 106 (distance to Peoria is 106 miles; flow rate of 1 mph assumed)
- See Section A.2.4 of Appendix A.
O F-0 ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
7.- DRESDEN-Revision l'.0 January.1994 l e- -l .p. F Table F-2 e
- A t
Station Characteristics for Dresden 1, 2, 3-f i f STATION: Dresden. Nuclear Power Station _ LOCATION: Morris, Illinois l CHARACTERISTICS OF ELEVATED RELEASE POINT l i U1, 91.44 m U1 1.40 m j a
- 1) Release Height = U2/3 94.49 m'
- 2) Diameter = U2/3 3.35 m 4
U1 17.9 ms
- i
- 3) Exit Speed = U2/3 16.06 ms
- 4) Heat Content = 70 KCal s
- 4 d
i CHARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height =
4 8. 77 m*
- 2) Diameter =
2.74 m-4
- 3) Exit Speed 12.0 ms *
= t CHARACTERISTECS OF GROUND-LEVEL RELEASE i
- 1) Release lieight =0 m
- 2) Building Factor (D) 42.08 m*
j = METEOTsOLOGICAL DATA -l A afH ft Tower is Located 800 m WSW of elevated release pointL Tower Data Used in Calculations i t
- 5 Wind Speed and Differential l
Release Point Direction Temnerature 't Elevated 300 ft -300-35'ft I vent-150 ft 150-35 ft l Ground 35 ft -150-35 ft } I "Used in calculating the meteorological and dose factors in -1 Tables F-5, F-6, and F-7 See Sections B.3 through B.6 of Appendix B. -1 l k i i + 5 F-3
/' DRESDEN Revision 1.0 January 1994 Table F-3 Critical Ranges Unrestricted Area Restricted Nearest Nearest Dairy Farm Boundary
- Area Boundary Resident' Within 5 Miles c Direction (m)
(m) (m) (m) N 768 i 500 1900 None NNE 1207 800 1300 None NE 1100 600 3700 None ENE 1244 600 1300 None E 1000 600 2300 None ESE 988 988 1600 None SE 1000 1000 1000 None SSE 792 792 800 Mone S 841 841 850 None SSW 853 853 5300 None SW 1024 500 6000 None WSW 1170 500 9300 None W 1756 1400 5600 None WNW 1219 600 6000 None NW 756 500 4200 None NNW 671 500 1300 None O Nearest land in unrestricted area. Used in calculating the meteorological dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B. 1992 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. 1992 annual milch animal census, by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is used when there are no dairies within 5 miles. O F-4
i DRESDEN . Revision-1.0 January 1994 i l* Table F-4 -Average Wind' Speeds for Dresden 1,.2, and 3 Downwind Averace Wind Sneed'(m/sec)* Direction' Elevated Mixed Mode' Ground Level l N '7.3 5.5 4.3 i NNE . 7. 4 5.3 4.1 NE 6.9 5.0 3.7 + ENE 6.4 4.9 4.0 .} E 7.1 5.3 4.1 ESE 7.2 5.3 4.1 0 SE 6.4 5.1 3.7 SSE 6.4 4.8 3.4 S 5.9 4.4 3.1 SSW 5.9 4.5 3.0 l SW 5.7 4.4 3,0 WSW 5.1 4.0 2.8 W 5.5 4.4 3.2 't WNW 5.9 4.4 3.0 i NW 5. 7. 4.4 3.4 NITA 6.'3 4.9 3.8' l' t
- Based on Dresden site meteorological data, January 1978 through December 1987.
Calculated in References 1 and 2 of l Section F.2 using formulas in Section B.1.3 of Appendix B. b'The mixed mode values apply only to'Dresden 2/3. Mixed mode values are not needed for Dresden 1 since there is no mixed mode release point. =, .O F-5 1 J l
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Dresden Revision 1.0-January 1994 Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles Downwind Nearest Milk Cow D/Q(1/m**2) Wearest Meat Animal D/QC1/m**2) Direction Radius Elevated Mixed Ground Radius Elevated Mixed Ground (meters) Release Release Release (metera) Release Release Release N B000. 1.073E-10 1.533E-10 3.231E-10 7200. 1.277E-10 1.840E-10 3.906E-10 '~ NNE 8000. 1.103E-10 1.411E-10 2.954E-10 8000. 1.103E 10 1.411E-10 2.954E-F NE 8000. 9.092E-11 1.115E-10 2.434E-10 4300. 2.249E-10 3.181E-10 7.366E ' ENE 8000. 8.435E-11 9.923E-11 1.792E-10 8000. 8.435E-11 9.923E-11 1.792r E 8000. 1.282E-10 1.521E-10 3.011E-10 8000. 1.282E-10 1.521E-10 3.011~ ESE 8000. 1.241E-10 1.363E-10 2.759E-10 5600. 2.158E-10 2.509E-10 5.228' SE 8000. 1.146E-10 1.308E-10 2.665E-10 6300. 1.146E-10 1.308E-10 2.( SSE 8000. 1.126E-10 1.213E-10 2.303E-10 8000. 1.126E-10 1.213E-10 2.3b S 8000. 7.75BE 11 8.690E-11 1.703E-10 6900. 9.850E-11 1.117E-10 2.22'. SSW 8000. 7.408E-11 7.845E-11 1.640E-10 5300. 1.392E-10 1.571E-10 3.428E-tv SW 8000. 8.618E-11 8.357E-11 1.870E-10 500. 8.656E-10 4.52SE-09 2.096E-08 WSW 8000. 9.051E-11 7.512E-11 1.615E-10 500. 7.775E-10 3.546E-09 1.810E-08 W 8000. T.826E-11 9.150E-11 2.177E-10 500. 6.483E-10 5.237E-09 2.439E-08 WNW 8000. 5.945E-11 8.480E 11 2.401E-10 500. 6.046E-10 5.464E-09 2.691E-08 NW
- B000, 6.284E-11 7.514E-11 1.832E-10 500.
6.85BE-10 4.630E-09 2.054E-08 NNW 8000. 7.599E-11 1.095E-10 2.688E-10 500. 7.390E-10 7.562E-09 3.013E-08 DRESDEN SITE METEOROLOGICAL DATA 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Section B.4 of Appendix B. F-8
.g. .q t.: ^ d' fib dsion 1.01 Dr . n January'1994i Table F-7 Mar.imum'Offsitc Finite Plume Gamma Dose Factors Based on 1.cm Depth at the Unrestricted Area. Boundary for Kr-83m Downwind Unrestricted Elevated (Stack) Releaso Miwed Mode (Vent) Release Direct ion At ea Doutw1 Radius 5 SCAR Radius V VBAR -(meters) (meters) (nrad/yr)/(uCt/naci imeters) (mrad /yr)/(uCl/sec) H 768. 768. 1.111E-06 8.377F-07 768. 5.804E-OS 4.377E-OS ~ NNE 1207. 1207. 1,254E-06 9.453E-07 1207. 2.90lE-05 2.188E'-T5 s NE 1t00. 1100. 1.062E-06 8.OlOE-07 1100. 2.86tE-05 2.157E-05 ENE 1244. 1244. 1.Of8E-06 7.677E-07 1244 .t.595E-05 1.202E-OS E 1000. 1000. 1.301E-06 9.80nE-07 1000. 3.900E-05 2.94tE ESE 988. 988. 1.336E-06 1.OO7E-06 988. 3.237E-05 2.44tE-05 SE 1000. 1000. 1.414E-06.1.066E-06 1000.- 2.828E-05 2.133E-05 SSE 792. 792. 1.538E OS 1.tGOE-06 792. 3.462E-05 2.610E-05 5 841. 841. 1.095E-06 d.n59E-07 841. 2.335E-05 1.76tE-05 SSW ^853. 853. 1.OO9E-06 7.60GE-07 853. 2.332E-05 1.759E-05 SW. 1024. 1024. 8.474E-07 6.389E-07 1024 l.920E-05 1,448E-05 W5W
- 1870, 1970.
8.268E-07 6.234E-07 1170. 1.520E-05 1.146E-05 W 175G. 1756. 8.303E-07 6.261E-07 1756. 1.322E-05 9.966E-06 WNW 1219. 1219. 6.944E-07 5.23GE-07 1219. 2.19tE-05 1.652E-05 NW 756. 756. 7.464E-07 5.628E-07 756. 3.036E-05 2.289E-05 NNW 671. 671. 7.749E-07 5.843E-07 671. 5.274E-05 3.977E-05' Os t s< ten s i te Meteorological. Da ta 1/78 - 12/87 Note: Based-on References 1 and 2^.of Section F.2'and the forculas in Sections B.5_and'.B.6 of Appendix B. .F. = - - =. -. -.. - =.. - -, a. - a.
Dresden Revision: 1.0' . January 1994 Table F-7 (Continued) M2ximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Downwind Unrestricted Elevated (Stack) Release Miwed Mode (Vent) Release Ofrection Area Bound Radius 5 SBAR Radius V VBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) Imrad/yr)/(uCt/sec) H 768. 768. 1.399E-04 1.354E-04 768. 6.020E-04 5.795E-OF"' NNE 1207. 1207. 9.359E-05 9.053E-05 1207. 3.303E-04 3.181E-04 NE 1100. 1100. 9.061E-05 8.765E-OS 1100. 3.296E-04 3.175E-04 ENE 1244. 1244 7.359E-05 7.118E-05 1244. 2.088E-04 2.012E-04 E 1000. 1000. 1.064E-04 1.030E-04 1000. 4.299E-04 4.140E-04 ESE 988. 988. 9.782E-05 9.462E-05 988. 3.568E-04 3.436E-04 SE 1000. 1000. 9.428E-05 9.118E-05 1000. 3.260E-04 3.140 E -04 SSE 792. 792. 1.046E-04 1.012E-04 792. 3.889E-04 3.745E-04 5 841. 841. 8.695E-05 8.41tE-05 841. 3.045E-04 2.934E-04 SSW 853. 353. 8.163E-05 7.896E-05 853. 2.929E-04 2.823E-04 SW 1024 1024 7.42SE-05 7.182E-05 1024 2.735E-04 2.637E-04 W5W 1170.
- 1170, 7.278E-05 7.041E-05 1170.
2.394E-04 2.309E-04 W 1756. 1756. 4.764E-05 4.607E-05 1756. 1.734E-04 1.671E-04 WNW 1219. 1219. 5.561E-05 5.379E-05 1219. 2.513E-04 2.420E-04 NW 756.
- 756, 9.757E-05 9.441E-05 756.
3.808E-04 3.669E-04 NPN 671. 671. 1.240E-04 1.2OOE-04 671. 5.578E-04 5.371E-04 Dresden Site Meteorological Data 1/78 - 12/87 F-10
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s ,e 4 Drdusen hvision 1.0t January 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Otrection Area Bound Radius S 58AR Radius V Vi3AR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uct/sec) N 768.
- 768, is568E-04 1.522E-04 768.
2.579E-04.2.501E NNE 1207. 1207. 3.689E-05 3.58tE-05 1207. 3.215E-OS 3.118E-05 NE 1100. 1100. 3.809E-05 3.697E-05 1100. 3.434E-05 3.33tE-05 ENE 1244 1244 1.660E-05 1.61tE-05 1244. 1.571E-05 1.524E-05 E 1000. 1000. 5.92SE-05 5.75tE-05 1000. 7.864E-05 7.628E-05 ESE 988. 988. 5.808E-05 5.637E-05 988. 6.960E-05 6.751E-05 SE 1000. 1000. 4.406E-05 4.276E-05 1000. 5.157E-05 5.OO3E-05 SSE 792. 792. 8.809E-05 8.550E-05 792. 1.063E-04 1.032E-04 5 841. 841. 4.794E-05 4.653E-05
- 841, 5.718E-05 5.547E-05 SSW 853.
853. 4.498E-OS 4.366E-05 853. 5.154E-05 5.OOOE-05 SW 1024. 1024. 2.322E-05 2.254E-05 1024. 2.362E-05 2.292E-05 WSW 1170. 1170. 1.048E-05 1.018E-05 1170. 8.515E-06 8.260E-06 W 1756. 1756. 1.866E-06 f 8tfE-06 1756. 1.530E-06 1.484E-06 WNW 1219. 1219. 1.14tE-05 1.108E-05 1219. 1.162E-05 1.127E-05 NW -756. 756. 7.050E-05 6.843E-05 756. 9.619E-05 9.331E-05 NNW 671. 671. 1.395E-04 1.354E-04 671. 2.516E-04 2.440E-04 Dresden Site Meteorological Data 1/78 - 12/87 F-15
Dresden Revision 1.0 January 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m I l Downwind Unrestricted Elevated (Stack) Release Mtwed Mode (vent) Release Ofrectton Area Bound Radius 5 5BAR Radius V VBAR (meters) (meters) (mrad /yr )/(tJC 1/sec ) (meters) (mrad /yr)/(uC1/sec) N 768. 768. 3.860E-06 3.549E-06 768. 5.875E -05 4. fi99E-05 NNE 1207. 1207. 2.996E-06 2.686E-06 1207 3.052E-05 2.450E-05 NE 1100. 1100. 2.780E-06 2.510E-06 1100. 3.055E-05 2.453E-05 ENE 1244. 1244. 2.389E-06 2.138E-06 1244. 1.775E-OS 1.433E-05 E 1000. 1000. 3.301E-06 2.974E-06 1000. 4.098E-05 3.284E-05 ESE 988. 988. 3.141E-06 2.814E-06 988. 3.367E-05 2.700E-05 SE 1000. 1000. 3.130E-06 2.790E-06 1000. 2.958E-05 2.377E-05 SSE 792. 792. 3.440E-06 3.077- -06 792. 3.584E-05 2.877E-05 5 841 841. 2.742E-C6 2.4E ~-06 841. 2.515E-05 2.034E-05 55W 853. 853. 2.552E-06 2.299E-06 853. 2.495E-05 2.014E-05 SW 1024. 1024. 2.264E-06 2.047E-06 1024. 2.129E-05 1.730E-05 WSW 1170. 1170. 2.221E-06 2.OOBE-06 1170. 1.748E-05 1.427E-05 W 1756. 1756. 1.707E-06 1.508E-06 1756. 1.464E-05 1.183E-05 WNW 1219. 1219. 1.748E-06 1.573E-06 1219. 2.310E-05 1.855E-05 NW 756. 756. 2.670E-06 2.45BE-06 756. 3.276E-05 2.642E-05 NPN 671. 671. 3.255E-06 3.02OE-06 671. 5.352E-05 4.285E-05 Dresden Site Meteorological Data 1/78 - 12/87 F-16
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Dresden Revision'l~.0. January 1994 Table F-7 (Continued) Mr.ximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Doundary for Xe-133 Downw i nd (Jnre s 4 r i c t ed Elevated (Stack) Release Mixed Mode (Vent) Release Otrection Area Hound Radius S SBAR Radius V VBAR (metersi tmeters) tmrad/yr)/(uC1/sec) (meters) (mrad /yr)/(uCt/sec) N 768. 768. 1.874E-05 1.809E-05 768. 1.481E-04 1.356E-04 NNE 1207. 1207. 1.362E-05 1.3 ORE-05 1207 7.994E-OS.7.347E 05*' NE 1100. 1100. 1.279E-05 f.230E-05 1100. 7.969E-05 7.322E-05 ENE 1244. 1244. 1.062E-05 1.019E-05 1244. 4.887E-05 4.512E-05 E
- 1000, 1000.
1.507E-05 1.448E-05 1000. 1.055E-04 9.682E-05 ESE 988. 988. 1.40GE-05 1.350E-05 988. 8.706E-05 7.992E-05 SE 1000. 1000. 1.367E-05 1.311E-05 1000. 7.806E-05 7.179E-05 SSE 792. 792. f.49tE-05 1.430E-05 792. 9.314E-05 8.555E-05 S L41. 841. 1.201E-05 1.tS4E-05 841 6.991E-05 6.460E-05 SSW 853. 853. 1.126E-05 1.082E-05 853. 6.822E-05 6.295E-05 SW 1024. 1024. 1.031E-05 9.919E-06 1024. 6.164E-05 5.715E-05 WSW 1170. 1170. 1.020E-05 9.811E-06 1t70. 5.274E-05 4.906E-05 W 1756. 1756. 7.325E-06 7.OO9E-06 1756. 4.04fE-05 3.732E-05 WNW 1219. 1219. 7.875E-06 7.566E-06 1219. 6.054E-05 5.564E-05 NW 756. 756. 1.282E-05 1.237E-05 756. 8.885E-05 8.193E-05 NNW 671. 671. 1.609E-05 1.556E-05 671. 1.356E-04 1.242E*04 Dresden Site Meteorological Data 1/78 - 12/07 F-18 e e e..
,n, b Drkden Iw/ision140 January 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius S SBA1 Radius V VBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uCt/sec) N 768. 768. 3.231E-04 3.124E-04 768. 1.124E-03 1.085E-03' " NME 1207. 1207. 2.031E-04 1.964E-04 1207. 5.521E-04 5.329E-04 NE. 1100. 1100. 1.979E-04 1.914E-04 1100. 5.168E-04 5.279E-04 ENE 1244. 1244. 1.536E-04 1.485E-04 1244 3.362E-04 3.247E-04 E 1000. 1000. 2.367E-04 2.288E-04 1000. 7.411E-04 7.153E-04 ESE 988. 988. 2.177E-04 2.10SE-04 988. 6.173E-04 5.958E-04 SE 1000. 1000. 2.OB4E-04 2.015E-04 1000. 5.726E-04 5.528E-04 SSE 792. 792. 2.399E-04 2.320E-04 792. 7.020E-04 6.7772-04 5 841. ~B41. 1.838E-04 1.777E-04 841. 5.365E-04 5.180E-04 SSW 853. 853. 1.76tE-04 f.702E-04 853. 5.143E-04 4.956E-04 SW 1024. 1024. 1.595E-04 1.542E-04 1024. 4.54BE-04 4.392E-04 WSW 1170. 1170. 1.518E-04 1.468E-04 1170. 3.897E-04 3.764E-04 W 1756. 1756. 8.725E-05 8.434E-05 1756. 2.491E-04 2.405E-04 WNW 1219. 1219. 1.152E-04 1.114E-04 1219. 4.090E-04 3.949E-04 NW 756. 756. 2.251E-04 2.177E-04 756. 6.857E-04 6.621E-04 NNW 671. 671. 2.899E-04 2.803E-04 671. 1.043E-03 1.OO7E-03 Dresden Site Meteorological Data 1/78 - 12/87 k F-19
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O O p ~ ~ W Drb den w/ision '110 : January 1994. Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 i Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Directton Area Dound Radius S 58AR Radius V VBAR Imeters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uCt/sec) - N 768. 768. 1.107E-04 f.071E-04 768. 3.275E-04 3.170E-04 NNE 1207. 1207. 6.023E-05 5.83OE-OS 1207. 1.264E-04 1.223E-04 NE 1100. 1100. 5.847E-05 5.659E-05 1100. t.267E-04 1.226E-04 ENE 1244. 1244. 4.063E-05 3.933E-OS 1244 7.244E-OS 7.01tE-OS E 1000. 1000. 7.256E-05 7.024E-05 1000. 1.894E-04 1.033E-04 ESE 988. 988. 6.769E-05 6.552E-05 988. 1.588E-04 1.537E-04 SE .1000. 1000. 6.336E-05 6.133E-05 1000. 1.436E-04 1.389E-04 SSE 792. 792. 7.937E-05 7.683E-05 792. 1.916E-04 1.855E-04 5 841. 841. 5.651E-05.5.470E 841. 1.378E-04 1.334E-04 SSW 853. 853. 5.384E-05 5.212E-05 853. 1.293E-04 1.251E-04 SW 1024. 1024. 4.546E-05 4.400E-05 1024 1.042E-04 1.OO9E-04 WSW 1970. 1170. ' 3.874E-05 3.750E-05 1170. 7.913E-05 7 658E-05 W-1756. 1756; 1.752E-05 1.696E-05 1756. 3.873E-05 3.748E-05 WNW 1219. 1219. 2.999E-05 2.903E-05 1219. 8.360E-05 8.09tE-05 NW .756. 756. 7.264E-05 7.03tE-05 756. 1.876E-04 f.8tGE-04 NNW 671. 671. 9-950E-05 9.632E-05 671. 3.095E-04 2.995E-04 ' t Dresden Site Meteorotogical Data 1/78 - 12/87 i l l-l l l i F-21. l rg - n-1e W-g-y w-y+ w y --yy--- >-my w-'S 1r 4 y- .4', w e-wP1e w rw-1rww w y w e-
Dresden Revision'1.0-January 1994' Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius S 5BAR Radius V VBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uct/sec) N 768. 768. 8.543E-04 8.302E-04 768. 2.494E-03 2.422E-03 NNE 1207. 1207. 5.254E-04 5.106E-04 1207. 1.219E-03 1.184E-03 NE 1100. 1100. 5.164E-04 5.019E-04 1100. 1.212E-03 1.177E-03 ENE 1244 1244. 3.998E-04 3.8SSE-04 1244 7.482E-04 7.267E-04 E 1000. 1000. 6.190E-04 6.015E-04 1000. 1.640E-03 1.593E-03 ESE 988. 988. 5.683E-04 5.523E-04 988. 1.367E-03 1.327E-03 SE 1000. 1000. 5.447E-04 5.294E-04 1000. 1.273E-03 1.237E-03 SSE 792. 792. 6.340E-04 6.161E-04 792. 1.569E-03 1.524E-03 5 841. 841. 4,874E-04 4.737E-Q4 841. 1.203E-03 1.168E-03 SSW 853. 853. 4.667E-04 4.535E-04 853. 1.149E-03 1.116E-03 SW 1024. 1024. 4.199E-04 4.081E-04 1024 1.014E-03 9.8526-04 WSW 1170. 1170. 3.977E-04 3.865E-04 1170. 8.710E-04 8.460E-04 W 1756 1756. 2.229E-04 2.166E-04 1756. 5.469E-04 5.312E-04 i WNW 1219. 1219. 3.015E-04 2.930E-04 1219. 9.027E-04 8.767E-04 NW 756. 756. 6.013E-04 5.844E-04 756. 1.538E-03 1.494E-03 l NNW 671. 671. 7.735E-04 7.517E-04 671. 2.320E-03 2.253E-03 Dresden Site Meteorological Data 1/78 - 12/87 1 1 i i 1 l i L F-22 l e e 9.
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n! { / ~ Dr oen t h /ision 1.0 -Januarys1994~ l Table F-7a (Continued) . Maximum [Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for-Xe-131m Downwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius 5 5BAR Radius V VBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec) N 500. 500. 5.273E-06 4.926E-06 500. 1.048E-04 8.3'37E di NNE 800. 800. 3.794E-06 3.475E-06 800. 5.145E-05 4.115E-05 'NE 600. 600. 4.212E-06 3.897E-OG -600. 6.745E-05 5.381E-05 ENE 600. 600. 3.774E-06 3.496E-06 600. 4.620E-05 3.703E-05 E 600. 600. 4.659E-06 4.288E-06 600. 8.062E-05 6.425E-OS ESE 988. 988. 3.141E-OG 2.814E-OG 988. 3.367E-05 2.700E-05 SE 1000. 1000. 3.130E-06 2.790E-06 1000. 2.958E-05 2.377E-05 SSE-792. 792. 3.440E-06 3.070E-06 792. 0.584E-05 2.877E-05 5 841. 841. 2.742E-06 2.468E-06 841. 2.515E-05 2.034E-05 SSW 853. 853. 2.552E-06 2.299E-06
- 853, 2.495E-05 2.014E-05 SW 500.
500. 3.936E-06 3.632E-06 500. 5.tGOE-05 4.159E-05 WSW 500. 500. 4.158E-06 3.863E-06 500. .4.640E-05 3.762E-05. W 1400. 1400. 1.862E-06-1.671E-06 1400. 1.817E-05 1.470E WNW 600. 600. 2.780E-06 2.577E-06 600. 5.684E-05 4.533E-05 NW 500. 500. 3.632E-06 3.392E-06 500. 5.65tE-05 4.533E-05 NNW 500. 500. 4.071E-06 3.813E-06 500. 7.937E-05 6.331E-05 Dresden Site Meteorological Oata 1/78 - 12/87 l F-31 . --._-. -... - -.. w.,. -.~ a. a.- ~... - a..=.=--.. .~ -....:-.-.a.-- =.. -.
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Dresden Revision l'.0 January 1994-Table F-7a (Continued) Mnximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m Downwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius S SBAR Radius V VBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) N 500. 500. 5.089E-04 4.921E-04 500. 1.946E-03 t '. 8 7 8 t -'03' NNE 800. 800. 3.146E-04 3.042E-04 000. 9.632E-04 9.297E-04 NE 600. 600. 3.813E-04 3.687E-04 600. 1.235E-03 1.192E-03 ENE 600. 600. 3.419E-04 3.305E-04 600. 9.252E-04 8.93tE-04 E 600. 600. 4.096E-04 3.96tE-04 600. 1.455E-03 1.404E-03 ESE 988. 988. 2.177E-04 2.105E-04 988. 6.173E-04 5.958E-04 SE 1000. 1000. 2 084E-04 2.015E-04 1000. 5.726E-04 5.528E-04 S5E 792.
- 792, 2.399E-04 2.32OE-04 792.
7.020E-04 6.777E-04 5 841. 848. 1.838E-04 1.777E-04 841. 5.365E-04.5.180E-04 SSW 853. 853. 1.761E-04 1.702E-04 853. 5.143E-04 4.966E-04 SW 500. 500. 3.512E-04 3.396E-04 500. 1.146E-03 1.106E-03 W5W 500. 500. 3.892E-04 3.763E-04 500. 1,145E-03 1.tOSE-03 W 1400. 1400. 1.136E-04 1.099E-04 1400. 3.424E-04 3.306E-04 WNW 600. 600. 2.523E-04 2.439E-04 600. 1.055E-03 1.019E-03 NW 500. 500. 3.513E-04 3.397E-04 500. 1.168E-03 1.127E-03 NNW 500. 500. 3.966E-04 3.835E-04 500. 1.516E-03 1.463E-03 Dresden Site Meteorological Data 1/78 - 12/87 l F-34 O O O.
L 'Dresden Renfision' 1. 0 . January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted' Area Boundary for Xe-135 Oownwind controlled Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius' S SBAR Radius V VBAR (meters) (meters) (mead /yr)/(UC1/sec) (meters) (mrad /yr)/(uCf/sec) N 500. 500. -2.950E-04 2.855E-04 500. 1.346E'03 1. 301 E -O'3 NNE 800. 800. 1 903E-04 1.842E*O4 800. 7.228E-04 6.989E-04 NE 600. 600. 2.236E-04 2.164E-04 600. 9.059E-04 8.758E-04 ENE 600. 600. 2.Ot7E-04 1.952E-04 600. 6.760E-04 6.536E-04 E
- 600, 600.
2.405E*04 2.327E*04 600. 1.061E-03 1.026E-03 ESE 988. 988. 1.380E-04 1.335E-04 988. 4.921E-04 4.758E-04 SE 1000. 1000. 1.329E-04 1.287E-04 1000. 4.493E-04 4.344E-04 SSE 792. 792. 1.475E-04 1.427E-04 792. 5.356E-04 5.179E-04 S 841 841. 1.235E*04 1.195E-04 841. 4.212E-04 4.073E-04 'SSW. 853. 853. 1.157E-04 1.120E-04 853. 4.047E-04 3.914E-04 SW 500. 500. 2.061E-04 1.995E-04 500. 8.245E-04 7.973E-04 WSW 500. 500. 2.260E-04 2.187E-04 500. 8.tOOE-04 7.834E-04 W 1400. 1400. 8.203E-05 7.939E-05 1400. 3.042E-04 2.942E-04 WNWL 600. 600. 1.495E-04 1.447E-04 600. 7.609E-04 7.356E-04 NW - 500. 500. 2.028E-04 1.963E 04 500. 8.358E-04 8.082E-04 NNW 500. 500. 2.309E-04 2.235E-04 500. 1.066E-03 1.03tE-03 Oresden Site Meteorological Data 1/78 - 12/87 F-35 .. - ~.a .. = a.
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.~ CD- }' ~ Dreuden hevision 1[0 January 1994L Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Downwind Controtled Elevated (Stack) Release Mixed Mode (Vent) Release Direction Area Bound Radius S 58AR. Radius V VBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) .~ N 500. 500. 1.362E-03 1.323E-03 500. '4.320E-03 4.195E-03 NNE 800. 800. 8.282E-04 8.048E-04 800. 2.139E-03 2.077E-03 NE 600.
- 600, t.Ot6E-03 9.874E-04 600.
.2.752E-03 2.673E-03 ENE 600. 600. 9.157E-04 8.900E-04 600. 2.076E-03 2.Ot7E-03 E 600. 600. 1.09tE-03 1.060E-03 600. -3.230E-03 3.137E-03 ESE 988. 988. 5.683E-04 5.523E-04 988. 1.367E-03 1.327E-03 SE 1000. 1000. 5.447E-04 5.294E-04 1000. 1.273E-03 1.237E-03 SSE 792. 792. 6.340E-04 6.16tE-04 792. 1.569E-03 1.524E-03 5 841. 841. 4.874E-04 4.737E-04 841. 1.203E-03 1.168E SSW 853. 853. 4.667E-04 4.535E-04 853. 1.149E-03 1.it6E-03 SW 500. 500. 9.489E-04 9.222E-04 500. 2.575E-03 2.501E-03 WSW 500. 500. 1.055E-03 '.02?E-03
- 500, 2.587E-03 2.513E-03.
W 1400. 1400. 2.952E-04 2.868E-04 1400. 7.569E-04 7 35tE-04 WNW 600. 600. 6.796E-04 6.605E-04 600. 2.349E-03 2.28tE-03 NW 500. 500. 9.496E-04 9.229E-04 500. 2.623E-03 2.547E-03 NNW 500. 500. 1.067E-03 1.037E-03 500. 3.375E-03 3.278E-03 Dresden Site Meteorological Data 1/78 - 12/87 s ,F-37 ~ ~.. - ..m..
Dresden Revision 1.0-January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma. Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downwind Contr ol led E l eva t e<l( S t ack ) Release Mixed Mode (Vent) Release Directton Area Hounr1 Rar16 us S SOAR Radius V VBAR (mators) ( me t e r a; ) (mrad /yrl/(uCi/sec) (meters) ( mrad /yr )/( uC 1/sec ) s... N 500. 500. 1.570E-03 1.520E-03 500. 5.243E-03 5.075E-03 NNE 800. 800. 9.813E-04 9.499E-04 800. 2.799E-03 2.709E-03 NE 600. 600. 1.180E-03 1.142E-03 600. 3.532E-03 3.419E-03 ENE 600. 600. 1.075E-03 1.040E-03 600. 2.660E-03 2.575E-03 E 600. 600. 1.266E-03 1.226E-03 600. 4.099E-03 3.9G8E-03 ESE. 988. 988. 7.Ot3E-04 6.789E-04 988. 1.884E-03 1.824E-03 SE 1000. 1000. 6.767E-04 6.550E-04 1000. 1.740E-03 1.684E-03 SSE 792. 792. 7.637E-04 7.393E-04 792. 2.092E-03 2.025E-03 5 841. 841. 6.416E-04 6.210E-04 841. 1.652E-03 1.599E-03 SSW 853. 853. 6.026E-04 5.833E-04 853. 1.580E-03 1.529E-03 SW 500. 500. 1.114E-03 1.079E-03 500. 3.282E-03 3.177E-03 WSW 500.
- 500, 1.227E-03 1.188E-03 500.
3.243E-03 3.139E-03 W 1400. 1400. 4.144E-04 4.011E-04 1400. 1.163E-03 1.126E-03 WNW 600. 600. 8.045E-04 7.788E-04 600. 2.979E-03 2.884E-03 NW 500. 500. 1.098E-03 1.063E-03 500. 3.298E-03 3.192E-03 NNW 500. 500. 1.240E-03 1.2OOE-03 500. 4.177E-03 4.043E-03 Dresden Site Meteorological Data 1/78 - 12/87 F-38
DRESDEN Revision 1.0 January 1994- 'A Q Table F-8 Pararneters for Calculations of N-16 Skyshine Radiation From Dresden 2/3 i ~ Location ActMty Occupancy Occupancy Shielding Distance Number Hours Factor Factor R, k O H," O F, SF, (m) 1 Living at home 8344 0.95 0.7 800f (nearest resident) 2 Fishing 416 0.05 1.0 610' K = 3.60E-05 mrem /(MWe-hr) These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location. O The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours per week for 8 months per year. This yields an estimate of: [12 hours / week] [(8 months /yr)/(12 months /yr)] x [52 weeks /yr] = 416 hours /yr The remaining time is assumed to be spent at the nearest residence. Distance iu nearest residence (See Table F 3). Estimated frorr a drawing of the site. The OF,is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OH,/8760 hours = OF, rounded to the 0.01 digit. l O i F-39 i
DRESDEN Revision 1.0 January 1994 SupplementalTable A Elevated Level Joint Frequency Distribution Table Summary 300 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .237 .222 .188 .164 .115 .096 .105 .102 .152 .146 .167 .131 .207 .314 .367 .344 3.057 8 .206 .200 .176 .155 .123 146 .151 .162 .252 .263 .241 .209 .256 .285 .287 .311 3.422' C .289 .246 .260 .236 .225 .194 .240 .268 .338 441 .350 . 362 .515 .475.469 .462 5.368 D 2.028 1.971 2.457 2.687 2.343 1.689 1.747 2.186 3.098 3.087 2.485 2.307 3.602 3.350 2.953 2.887 40.876 E 1.342 1.352 1.520 1.778 1.954 1.906 1.965 2.433 3.771 3.815 2.856 1.904 2.374 2.231 2.033 1 550 34.782 F .494 .476 .397 .244 .257 .463 .777 .745 .816 .938 1.089 1.076 .793 .587 .644 .450 10.246 G .146 .141 .083 .039 .034 .026 .112 .156 .128 .189 .288 .275 .256 .135 .125 .117 2.250 Total 4.742 4.607 5.080 5.304 5.050 4.520 5.098 6.052 8.554 8.879 7.475 6.263 8.002 7.376 6.878 6.119 100.000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW Total d5 .033 .021 .017 .006 .007 .000 .000 007 .010 .000 .000 .000 .006 .000 .000 .000 .109 1. 035 .035 .031 .051 .052 .O37 .035 .026 .043 .033 .031 .035 .027 .026 .033 .034 .565 2.05 .240 .209 .213 .244 .265 .223 .216 .220 .221 .171 .235 .249 .223 .240 .229 .210 3.608 3.05 413 .474 .462 .559 .536 .481 .484 .474 482 .413 .496 .575 .596 .433 .416 .416 7.710 4.05 .652 .572 .744 .896 .759 .520 .700 .726 .749 .620 .647 .754 .771 .627 .678 .608 11 024 5.05 .638 .640 .751 1.062 .785 .563 .778 .797 .771 .794 .729 .724 .840 .692 .847 .739 12.151 6.05 .710 .605 .853 .940 .818 .654 .762 .829 .974 1.065 .913 .869 1.050 .912 1.017 .862 13.834 8.05 1.133 1.167 1.237 1.078 1.077 1.192 1.375 1.555 2.228 2.493-2.202 1.632 1.994 2.028 2.036 1.828 26.254 10.05 559 .552 .554 .386 .508 .506 .515 .850 1.612 1.793 1.286 .848 1.253 1.396 1.082 .924 14.623 13.05 252 .269 .174 .072 .221 .311 .194 .449 1.140 1.189 .761 .415 .887 .780 .476 .385 7.972 10.00 .074 .064 .046 .008 .021 .033 .038 .117 .305 .293 .159 .146 .326 .214 .063 .110 2.017 99.00 .004 .000 .000 .000 .000 .001 .000 .001 .020 .014 .017 .015 .028 .028 .001 .002 .132 Total 4.742 4.607 5.080 5.304 5.050 4.520 5.098 6.052 8.554 8.879 7.475 6.263 8.002 7.376 6.878 6.119 100.000 NOTE: Wind directions in tables are presented in " wind from" and not " wind tO" direction. F-40 0 0 0.
p [ DF4wdEN \\> Revision 1.0 January 1994 SupplementalTable A-Continued Elevated Level Joint Frequency Distnbution Table Summary 300 Foot Elevation Data Summary Table of Percent by Speed and Class Class A B C D E F G = Speed .45 .000 .000 .001 .019 .041 .033 .014 1.05 .005 .008 .026 .188 .203 .107 .027 2.05 .078 .132 .229 1.618 .979 .454- .118 3,05
- 279
.358 .624 3.471 1.971 .744 .263 4.05 .502 .572 .830 4.500 3.159 1.166 .295 5.05 465 .513 .730 4.832 4.013 1.287 .311 6.05 .464 .487 .683 5.529 4.808 1.541 .322 8.05 .687 .768 1.127 9.927 9.863. 3.289 .593 10.05- .331 .353 .627 5.846 5.844 1.371 .250 13.05 .222 .202 .370 34766 3.118 .240 .054 18.00 .024 .030 .115 1.115 .720 .013 .001 99.00 .000 .000 .007 .065 .060 - .000 .000 F-41
DRESDEN Revision 1.0 January 1994 Supplemental Table B Mixed Mode Joint Frequency Distribution Table Summaries 150 Foot ElevatiOri Data Summary Table of Percent by Direction and Class Citss N NNE NE ENE E ESE SE SSE S SSW SW 3 WSW W WNW NW NNW Total A .609 .428 .323 .250 .369 .452 .457 .508 .703 .775 .741 .777 .698 .809 .949 .972 9.821 B .096 .098 .107 .086 .104 . 129 .110 .157 .157 .192 . *G3 .184 .193 .143 .144 .146 2.210 C .125 .116 .125 .121 .112 . 130 .102 .127 .163 .200 .162 .121 .198 .177 .165 .150 2.295 0 1.083 .984 1.267 1.306 1.295 .929 .875 1.120 1.395 1.253 .982 .897 1.489 1.173 1.335 1.316 18.699 E 1.434 1.483 1.944 2.233 2.262 2.055 1.655 2.545 3.353 2.529 1.988 1.218 2.653 23 113 ~9.091 "1.702 33.259 F .446 .434 .397 .301 .451 .687 .867 .643 1.036 1.224 1.167 .609 .864 .699 .539 .417 10.781 G .200 .123 .094 .084 .069 . 105 .366 .230 .187 .269 .557 .633 .318 .207 .208 .167 3.816 Total 3.993 3.665 4.256 4.381 4.662 4.488 4.433 5.332 6.995 6.441 5.760 4.440 6.413 5.322 5.430 4.870 80.882 Summary Table of Percent by 01rection and Speed Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW Total .45 .018 .007 .051 .007 .006 .004 .006 .018 .005 .007 .017 .006 .007 .017 .006 .016 .198 1.05 .051 .070 .064 .060 .057 .056 .049 .056 .047 .062 .053 .058 .067 .060 .058 .064 .934 2.05 .361 .306 .365 .421 .392 .371 .340 .315 .397 .349 .380 .388 .432 .347 .339 .324 5.828 3.05 .664 .674 .698 .841 .796 .687 .763 758 .789 .708 .763 .713 .738 .593 .614 .579 11.379 4.05 .799 .731 .854 1.101 1.045 .877 .943 .990 1.074 1.024 .922 .757 .972 .790 .847 .891 14.617 5.05 .803 .649 .799 .958 .993 1.025 .984 1.109 1.238 1.225 1.126 .862 1.146 .910 1.086 1.024 15.937 6.05 .514 .475 .591 .504 .582 685 .650 .788 1.151 1.084 .937 .584 .998 .849 .906 .761 12.060 8.05 .609 .549 .672. .429 .598 609 .534 .939 1.646 1.404 1.175 .809 1.436 1.219 1.161 .938 14.72G 10.05 .157 .180 .151 .057 .175 . 161 .151 .328 .565 .518 .345 .232 .556 .481 .382 .246 4.685 13.05 .015 .024 .012 .003 .018 .014 .012 .031 .084 .061 .040 .030 .061 .056 ,032 .027 .519 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 99.OO .000 ' .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 3.993 3.665 4.256 4.381 4.662 4.488 4.433' 5.332 6.995 6.441 5.760 4.440 6.413 5.322 5.430 4.870' 80.882 NOTE: Wind directions in tables are presented in " wind from" and not " wind tO" direction. In Order 10 determine the final mixed mode values,80.882% of the elevated value (presented in the 250 FT Mixed Mode table) and 19.118% of the ground level value (presented in the 30 FT Mixed Mode table) are used 10 calculate the final values. F S S G. 4 + -g 1 a.- v
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DRESDEN-Revision 1.0. January 1994 Supplemental Table B - Continued Mixed Mode Joint Frequency Distribution Table Summaries 35 Foot Elevation Data j Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW W5W W WNW NW NNW Total A .090 .090 .064 .038 .051 .064 .066 .093 .205 .246 .208 .171 .187 .243 .224 .180 2.219 B .019 .017 .019 .010 .014 .015 .014 .029 .047 .065 .036 .044 .068 .062 .039 .029 .528 C .022 .022 .O23 .O12 .Of6 .019 .013 .033 .060 .077 .040 .040 .064 . 08 6, g .057 .045 .632 D .286 .274 .251 .181 .274 .191 .176 .339 .577 .455 .308 .309 .573 .513 .416 .394 5.517 .537 .387 8.433 E .295 .3f8 .345 .293 .481 .444 .372 .726 1.028 .719 .473 .371 .907 F .035 .041 .027 .014 .054 .138 .086 .123 .159 .164 .161 .077 .128 . O' e .063 .061 1.420 G .005 .002 .005 .001 .009 .055 .016 .013 .033 .054 .079 .022 .017
- ,16
.023 .018 .369 Total .752 .764 .734 .550 .899 .927 .743 1.357 2.109 1.780 1.305 1.034 1.944 1.746 1.359 1.115 19.118 Summary Table of Percent by Direction and Speed f Speed N NNE NE ENE E ESE SE SSE 5 55W SW W5W W WNW NW NNW Total I .45 000 .001 .000 .001 .000 .000 .004 .000 .000 .000 .003 .003 .007 .003 .000 .000 .023 1.05 004 .002 .002 .002 .002 .001 .003 .006 .008 .011 .007 .004 .004 .005 .004 .004 .069 2.05 053 .064 .047 .037 057 .076 .037 .060 .078
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.081 .040 .OG4 .057 .069 .068 .985 I 3.05 .128 .145 .156 162 .2O3 .261 .122 .175 .189 .178 .184 .095 .202 .182 .162 .181 2.727 l 4.05 .152 .142 .200 .161 .192 .193 .163 .238 .251 .213 .189 .146 .273 .220 .233 .210 3.176 l 5.05 .107 .098 .117 .096 .422 .117 .112 .176 .220 .179 .157 .130 .229 .216 .199 .151 2.425 l 6.05 .105 .080 .090 .041 .098 .086 .076 .150 .203 .208 .138 .123 .228 .201 .181 .125 2.133 i 8.05 .159 .196 .104 .040 .190 .133 .151 .332 .549 .459. .309 .244 .587 .528 .372 .240 4.592 10.05 .037 .034 .016 .010 .031 .049 .062 .166 .422 .336 .167- .141 .226 .247 .109 117 2.170 13.05 .008 .000 .002 .000 .003 .009 .013 .050 173 .087 .064 .091 .107 .076 .029 .019 .733 18.00 000 .000 .000 .000 .000 .000 2000 .004 .016 .012 .006 .018 .084 .Of2 .001 .000 .082 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .001 .000 .000 .000 .001 i Total .752 .764 .734 .550 .899 .927 .743 1.357 2.109 1.780 1.305 1.034 1.944 f.74G 1.359 1.115 19.118 l NOTE: Wind directions in tables are presented in " wind from" and not " wind to" direction. r F-44 9 9 e..
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DRESDEN R; vision 1.0 January 1994 SupplementalTable C Ground Level Joint Frequency Distribution Table Summary DRESDEN OFD 1978-1987 GRoUNO LEVEL (35 FT) Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW Total A .688 .524 .386 .304 .405 .510 .547 .580 .888 1.027 .915 .946 .913 1.070 1.259 1.093 12.055 B .129 .119 .126 .094 .122 .140 .121 .187 .216 .255 .168 .237 .249 .224 .195 .152 2.733. C .146 .136 .143 .127 .127 .155 .112 .169 .220 .273 ,182 .160 .254 .286.-.<220 .203 2.919 0 1.337 1.295 1 944 1.343 1.569 - 1.166 1.044 1.517 1.913 1.732 1.218 1.163 2.085 1.788 1.814 1.707 24.236 E 1.744 1.823 2.399 2.168 2.907 2.736 2.170 3.654 3.985 3.034 2.273 1.533 3.470 3.018 2.679 2.131 41.723 F 429 .442 .389 .266 .618 1.217 .778 .956 1.166 1.166 1.165 .597 .971 .793 .631 .588 12.171 G .120 .082 .056 .054 .121 .551 .170 .188 .327 .483 .643 .197 .178 .262 .390 .338 4.163 Total 4.593 4.424 5.043 4.356 5.871 6.475 4.942 7.252 8.715 7.968 6.564 4.833 8.121 7.442 7.189 6.212 100.000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total .45 .078 .056 .077 .053 .029 .091 .058 .014 .052 .020 .070 .O34 .049 .049 .058 .050 .838 1.05 .361 .229 .265 .227 .240 .216 .234 .251 .267 .259 .246 .182 .231 .265 .299 .287 4.058 2.05 1.046 1.188 1.118 .939 1.244 1.445 .921 1.150 1.236 1.363 1.216 .807 1.109 1.051 1.272 1.264 18.369 3.05 1.096 1.186 1.370 1.484 1.764 2.167 1.228 1.594 1.597 1.470 1.477 .932 1.624 1.476 1.383 1.496 23.345 4.05 .884 .799 1.177 .983 1.208 1.227 1.084 1.531 1.592 1.357 1.143 .896 1.559 1.330 1.407 1.263 19.439 5.05 .501 .421 .571 .422 .632 .615 .624 .976 1.196 .984 .844 .707 1.146 1.135 1.047 .779 12.600 6.05 .335 .237 .301 .160 .393 .379 365 .704 .926 .962 .625 .541 .979 .838 .815 .504 9.064 8.05 246. .275 .146 .077 .324 .273 .343 .785 1.173 t.062 .680 477 1.063 .949 .761 .428 9.062 10.05 .037 .034 .016 .010 .033 .055 .072 .194 487 .391 .192 .150 .237 .261 .117 .122 2.409 13.05 .008 .000 .002 .000 .003 .009 .013 .050 .173 .087 .064 .091 .107 .076 .029 .019 732 18.00 .000 .000 .000 .000 .000 .000 .000 .003 .016 .012 .006 .017 .014 .012 .OOt .000 .082 99.00 .000 .000 .000 .000- .000 .000 .000 .000 .000 .000 .000 .000 .001 .000 .000 .000 .001 Total 4.593 4.424 5.043 4.356 5.871 6.475 4.942 7.252 8.715 7.968 6.564 4.833 8.121 7.442 7.189 6.212 100.000 NOTE: Wind directions in tab!es are presented in " wind from" and not " wind to" direction. F-46
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