ML20127A705
| ML20127A705 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/31/1992 |
| From: | Kofron K, Stanczak P COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BW-93-0006, BW-93-6, NUDOCS 9301120045 | |
| Download: ML20127A705 (143) | |
Text
,f y ; f rf ' '
- s -
3-~
E'.
M ICommonwrith Edi:cn..
- ll7 / /
O
. f Braldwood Nuclear Power Station L
); -- -
?,
',g g c,
1 Routa #1, Box 84 -
?
Braceville. tilinois 60407
- ^
D. Telephone 815/458 2801 -
r-m.e t [.b"
' January 10,1993:
BW/93-0006 a
'l EM
,- Director, Office of Hesource Management P
United States Nuclear Regulatory Commission Washington, D.C. 20555 y
p
- ATTN:: Document Control Desk
- Gentlemen:
Enclosed for your information is the Monthly Performance Report -
l covering Braidwood Nuclear Power Station for the period December 1 through; st
- December 31,1992.
q f
f.)
s
/WD i
K. L. Kofron Im Station Manager Braldv.ood Station KLK/JUdla 4 ~
(713/ZD85G) '
TAttachments -
.cc:
- A. B. Davis, NRC, Region ill-N30_ Resident inspector Braidwood lIll. Dept. of Nuclear Safety -
s M."J. Wallace -
- E. D. Eenigenburg -
T.J.Kovach-Nuclear Fuel Services, PWR Plant Support j
llNPO Records Center m
Performance Monitoring Group, Tech Staff Braidwood Station
- Nuclear Group, Tech Staff Braldwood Station L
. R. Elliott - USNRC -
h T. W. Simpkin D. R. Eggett - Nuclear Engineering Department
- \\
(
% i
.jDRf 1;-ADOCK 05000456i - -
//
L
)-
~
PDR 4
~.
t 9
-t s - w <.
y-
+
s 69'Je
> +
j
.e>
.)
BRAIDH000 NUCLEAR P0HER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC. DOCKET NO. 050-457, LICENSE.NO.=NPF-77 i-m S
O' U
L.-
'I.-
MonthlyReportforBraidwoodVillt1
- A.
Sumary_of_0perAtinglxperlance.
Braldwood Unit i entered'the month of December, 1992,'at
.approximately 100% capable.
The Unit operated routinely.through the end of the month.-
w
-(713ZD85G)3--
1.
B.
OEERATING DATA REEORI DOCKET N0.:
50-456 UNIT:
Braldwood 1 DATE:
January-10, 1993-COMPILED BY:.
P. Stanczak TELEPHONE: _(815) 458-2801 ext. 2486-I OPERATING STATUS
- 1. Reporting Period: December, 1992 Gross Hours:
744
- 2. Currently Authorized Power Level (MHt):
3411 Design Electrical Rating (HHe-gross):
1175 Design Electrical Rating (HHe-net):
1120 Hax Dependable Capacity (HHe-gross):
1175-Max Dependable Capacity (HWe-net):
_1120
- 3. Power level to which restricted (If Any):
None
- 4. Reasons for restriction (If Any):
None THIS M0!illi 11 LID _DAIE _fuBUL&IIVE-
- 5. Report Period Hours:
744,.0 818AA -
38193,0-
- 6. Hours Reactor: Critical 7444 723L0 295]li2-
- 7. RX Reserve Shutdown Hours:
JA _
OA 0,0 _
- 8. Hours Generator on Line 744.0 _ 7143J 28915 2
- 9. Unit Reserve Shutdown Hours:
00 0.0 OJ 1
- 10. Gross Thermal Energy (MHHt)
._2395235A 21911124m0 _.66901640A
- 11. Gross Elect. Energy (MHH)
__.8329894 746fi45SA _29188648A-
- 12. Het Elect. Energy (MHH):
80916310 7147771 A _2B14259510
- 13. Reactor Service Factor:
100A 82A 76,1
- 14. Reactor Availability Factor:
1EQA 82d 76 1 1
- 15. Unit Service Factor:
100,0 AL3 74.1-
- 16. Unit Availability Factor:
100.0 BL3 74.1
- 17. Unit Capacity Factor (MDC NET):
97.1 72.7 6515
- 18. Unit _ Capacity Factor (DER. NET):
97 1 72.7 -
65,5 a
- 19. Unit Forced Outage Rate:
03
-L2; 10J
- 20. Unit Forced Outage Hours:
0.0 84.5 3235.3
- 21. Shutdown Scheduled Over Planned.10-day maintenance outage Next 6 Honths:
to replace a leaking pressurizer valve beginning on or about
. January 18,.1992.
- 22. If Shutdown at i of Reporting Period, Estimated Date
- Startup:
N/A 1
(713ZD85G)4 l
l
C.
AVERAGLDAILLijN LL EL10HEfLL&E LLOG DOCKET NO.:
50-456 UNIT:
Braldwood 1 DATE:
January 10, 1993 COMPILED BY:
P. Stancrak TELEPHONE:
(815) 458-2801 ext. 2486 MONill:
December, 1992
- 1. _
1022 16.
1118 2.
- 1136 17.
- 1138 3.
- 1136 18, 1104 4.
- 1134 19, 1054 5.
- 1134 20.
1058 6.
- 1133 21, 1031 7.
- 1135 22.
1080 8.
- 1134 23, 1065 9.
- 1135 24.
1.074 10.
1100 25.
831 11, 1074 26.
1118 12 1081 27.
1113 13.
1025 28.
1059 14.
1111 29.
- 1142 15.
- Ll34 30.
- 1135
' 31.
944 INSTRUCTIONS On this form list the average daily unit power level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month.
Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).
In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaiy.
- Due to condenser efficiency.
(713ZD85G)5
' D.'
UNIT SHUTDOWNS / REDUCTIONS DOCKET'NO.:
50-456 UNIT:
Braidwood 1" DATE:
January 10, 1993 COMPILED BY:
P. Stanczak-TELEPHONE:
(815)L458-2801 ext.-2486
' REPORT PERIOD: December, 1992 No_
DATE Tyf_E HOURS REASON METHOD. LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE
- 8 921224-S-
0
'H 5
N/A N/A.
N/A Load was reduced at the request of the' system
. load' dispatcher.
- S U M M A R'Y
- i TYPE
' REASON METHOD SYSTEM & COMPONENT' F-Forced A-Equipment Failure Maint or Test 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions forePreparation of' C-Refueling..
3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued' Licensee Event Report' E-Operator Training & License Examination 5 - Reduced Load
-(LER) File (NUREG-0161)f F-Administration' 9 - Other l
G-Oper Error H-Other 4
. (713ZD85G)11
E.
Ut[IOUE REPORTING RE0VIRE. ENTS - UNIT 1 M
1.
Safety / Relief-valve operations.
VALVES NO & TYPE PLANT DESCRIPTION DA_TI ACTUATED A_CTUATION CONDITION OF EVENT A
None.
1 4
2.
Licensee generated changes to ODCM.
See attached.
/
(713ZD85G)12
F.
LICENSEE EVENT REE0RTS - UBIL1 The'following 1s a tabular summary of all Licensee Event Reports submitted during the reporting period, December 1 through December 31, 1992.
This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
Licensee Event' Report Rep.o.tLHunter_
__DAte_
litle of occuttence 92-014 12/30/92 Inadequate Snuber Testing Program Due to Personnel Error (713ZD85G)6 o -- -
II. Monthly Report for Braidwood Unit 2 A.
SumarLof_0 petaling _.Exnerleiice Braldwood Unit 2 entered the month of December, 1992, at approximately 100% capable. On December 19, power was reduced to perform a condenser leakage inspection.
The Unit operated routinely from December 20 through the end of the month.
(713ZD85G)7 I _ _ ____________.___________________ _______ _____._________ _______________________ _____ ___ _ _
- ~f
~
B.-
QPERATitiG DATA REPORT DOCKET No.:~ 50-457-UNIT:
Braldwood 2 DATE:
January:10,'1993l COMPILED BY:
P. Stancrak-TELEPHONE: -(815) 458-2801-ext. 2486 OPERATING STATUS
- 1. Reporting Period:
December,'1992-Gross Hours:
744~
- 2. Currently Authorized Power Level _(MHt):
3411 Design Electrical Rating (HHe-gross):
1175
-Design Electrical Rating (HWe-net):
1120 Max Dependable Capacity (HWs-gross):
1175 Max Dependable Capacity (HMe. net):
1120
- 3. Power level to which restricted (If Any):
None
- 4. Reasons for restriction (if Any):
None THIS MQfLIB YR_10 Dale _CUlfULAIIYE
- 5. Report Period Hours:
744.0 8184,0 3681EJ2-
- 6. Hours Reactor Critical 744.0-8395.9 31162.5
~7. RX Reserve Shutdown Hours:
0.0 00 00 1
- 8. Hours Generator on Line 74410 8347.8 30887.8
- 9. Unit Reserve Shutdown Hours:
0.0 0.0 _
OmQ y
- 10. Gross-Thermal Energy (MHHt)
_243933L0 2665119LQ _9201214310
- 11. Gross Eleet. Energy (MHH)-
_ 82831810 _209228 hQ _2145622L Q t
- 12. Net Elect. Energy (HHH):
_111103.0 875114LQ 30114036.0 13.. Reactor Service Factor:
100.0 95.6 84.51
- 14. Reactor Availability Factor:
100.0 95.6 84e5-
- 15. Unit Service Factor:
1DQ10 9E10
~ 83 B ~
1
- 16. Unit Availability Factor:
100.0 95.0 83.3 -
-17. Unit Capacity Factor (MDC NET):-
95.7 8910 -
72.2:
- 18. Unit. Capacity _ Factor (DER NET):
-95, 1 89.0 72 9 1
- 19. Unit Forced Outage Rate:
Q10 2.9 3 2" 1
- 20. Unit Forced Outage Hours:
0.0 249.5 1197.3 j
- 21. Shutdown Schedule Over Next 6 Honths:
3rd Refuel Outage, March, 1993
- 22. If Shutdown at End of Reporting Period, Estimated Date of Startup N/A q
i
-i i
-(713ZD85G)8 L
a
C.
AYEBAGE_DMLLURIIJiET POWER LEVEL LOG DOCKET NO.:: 50-457:
UNIT: :Braidwood 2-DATE: January 10. 1993<
COMPILED BY:' P. Stanczak-TELEPHONE:
(815) 458-2801' ext. 2486-HONTH: December, 1992 1.
1071
- 16. -
1107 2.
1112 17.
1107 3.
1115 18.
1107 4.
1072 19.
1102
- 5. _
1111 20.
823 6.
1112 21, 1022 7.
109]
22.
900 8.
1096 23.
1019 9.
1109 24.
1100 10.
1101 25.
989 11.-
1110 26, 1109
'12, 1110 27.
1108~
13.
108.0 28.
1081 14.
1092
.29.
-1068 15.
1107 30.
1051 31, 1034 INSTRUCTIONS On this form list the average daily unit-power level-in MWe-Net;for each day in the reporting month. Compute to-the: nearest whole megawatt.
These figures will be used to plot a' graph for each reporting month.
Note that when maximum dependable capacity-is usedtfor~the net electrical rating of the unit there may be occasions when the-daily average power level exceeds the 100% line (or the restricted-power level line).
In such cases the average-daily unit power output-sheet should be footnoted to explain the apparent-anomaly.
(713ZD85G)9
e D.
' UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.:
50-457 ~
J-UNIT:
Braidwood 2 DATE:
January 10 L1993 COMPILED BY:
P. Stanczak:
TELEPHONE:
(815) 458-2801 ext. 2486 REPORT PERIOD: December, 1992
_4o_
DATE J1PE 110VHS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 18 921219 S
0 B
5
-N/A CD N/A Power reduced.to perform an: inspection for-condenser leakage. No leaks were found.
SUMMARY
TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure Maint or Test 1 - Manual-Exhibit-F & H S-Scheduled B-Maint or Test 2 - Manual. Scram Instructions for Preparation of.
C-Refueling 3 - Auto. Scram Data Entry Sheet
'D-Regulatory Restriction 4 - Continued-Licensee Event Report-E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161)
F-Administration.
9 - Other G-Oper Error H-Other-(713ZD85G)l3
E.
UNJOUE'REPORTXNG:REOUIREMENTS - UNIT 2
':41 1.
Safety / Relief valve operations.
VALVES NO & TYPE PLANT-DESCRIPTION DAIE
. ACTUATED AClEAJJOR CONDITION' 0F EVENT None.
2.
Licensee. generated changes to ODCM.
See attached.
1 1
' (713ZD8SG)14
. +
=
F.
LifGSEE EVENT REPORTS - URLL2 The following is a tabular summary of ali Licensee Event Reports.
submitted during the reporting period, December-1 through December 31, 1992.
This information is provided pursuant _to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
Licensee Event Report RepxLHumttet
__Dite__
ltt.le of Occ a te11ce 92-007 12/09/92 Reactor Trip Due to Main Generator Neutral Ground Back-up Relay Trip.
(713ZD85G)10
Changes to the Offsite Dose Calculation Manual Changes to the Offsite Dose Calculation Manual (ODCM) are reportable to the Nuclear Regulatory Conunission (NRC) in accordance with station Tecimical Specifications.
Chapter 10 of the ODCM was re-written for consistency and accuracy of the Braidwood Station's Radioactive Effluent Treatment and Monitoring systems. The generic section of the ODCM was revised to -
reflect the addition of the teenager as a member of the public.when determining dose to the public. Also, average meteorology information was updated using more current information which, in turn, required the recalculation of X/Q (atmospheric dispersion) values.
These revisions do not reduce the accuracy or reliability of dose calculations or setpoint determinations, and have been reviewed and found acceptable by the Onsite Review and Investigative Function.
2939/ZD81G
s.*
B AP 1205 171'-
R3vistlun 4.1 Braidwood On-site Review and Investigation Report
.OSR Humbert D*O
_Date I2'I Subject Review: BMKk OCcd Cf F S f TG CCSE ALCU L AIICid M A14VA L. (ODC Mi C hctpier (D.
NDbi
( Mk
.\\)
X 7 4 O,__
Requested by:
Disciplines requiredt MA Nuclear Power Plant Technology RB Reactor Operations OC Reactor Engin6ering DD Chesnistry KE Radiation Protection DF Instrumentation and Control KG Mechanical and Electrical Systems b8M A wshi re /63=.;P RA5
Participants:
Et\\een ROche./HfG T55 m
/2bf 2-OSR Membership Approved N.
ll W
Technical Staf f Supervisor
/
Date 10CTR50.59 Screening is Required
- - - - - - - - - - - - - - - Y/N d
If yes, attach completed documentation in accordance wi% BwAP 1205-6.
.10CTR50.59 Safety Evaluation is Requiredt - - - - - - - - - - - Y/N If yes, attach completed documentation in accordanc.
~
with BwAP 1205-6.
.(If a Safety Evaluation is Required, then Concurrence is Required by Offsite Review)
Concurrence Required by Offsite Review? (per Section C.6) - - - Y/N M
Tindings and Recommendatloast hWh%
(DC/0
(( ) m e
16 h
a 7,,-
! e ; s ' y, m, w ten A%48 F.,. I n;,
- k t,e o n jJ
<-3;p-(
(4 b Pe. :
[4 A d,- d
'~
y
..................................................................e....
On-Site Review Comittee Signature indicates concurrence.with Tindings and Recommendations and 10CFR50.59 Saf ety Evaluation.
Sigyatur Discioline(s)
Este e
tI 6
//
-Y /
Yk
/2 -2 $ ~$2.
N8jiQ AB6
_w/1.>))z.
oL 7%b
_.mLs.5in ps TC ))
la t t - L a k
/90 (It 8 lit # 9 L.-
(;Gi b -
__)
0.$~- ~
5
! 2 -l 5 'l L
-r
/2 N ' d-Approved by:
a ITATION MM AGEP DATE g pp p p \\t h e i
130(070192) 1 of 2 m 0 l'W ZWBWAP OR AIDWOOD
.f et RE vtf *
- - ~
- BwAP-1205-371:
- Rsvision 4.1 i
BRAIDWOOD CH-SITE REVIEW AHD. INVESTIGATION KZPORT.
- OSR Noi CG
'N3'
.....e eeeeeeeeeeeeeeeeenene......................
NOTE This checklist is:provided as guidance. f or OSR preparation and review.
Items should be completed as appropriate.
eeeeeeeeeeeeeeeeeeeeeeeen...........................
i Preparer Aon. N/A I.
SYNOPSIS FORMAT Putp se
'X' Executive Summary of Findings and Reconumendations
'Kl
.C References Bases of Tindings and Recommendations
- Contingency Actions. Recomumended II.
DOCUMENTATIGl.- REVIEWED: (List Applicable Sections in Synopsis)1
'~'
- UTSAR
- Tech Specs.
- A&nin Tech Requirements
'[
- Safety Evaluation Report Fire Protection Report.
- Prior 10CTR50.59 Safety Evals
+
NRC Comunitments V
- Vendor Docwnentation
~~
Special Permits / Licenses
'd
- Station Procedures f
'd
- Environmental Qualification
- Design Basis Documentation
'J Drawings
' Maint. History (TJM) l
,H
- NPRDS
=
PRA Info.
l
- Prior NED DE 40.1 Operability Evaluations III. PLANT CCNDITIONS: (Discuss Applicable items in Synopsis)'-
Applicable Modes N -
'd Work In-Progress / Planned g,
- Temporary Alteration Installed Out-of-Service -
Degraded Equipreent Log
,_l l.,
Abnormal Valve Lineupt
'l f,
-Effect on Opposite Train
- Ef fect on 02er Unit Effect.on Other Station
- Training Required
'l j
a
~
IV.
OTHER CONSIDERATIONS: -(Discuss Applicable Items in Synopsis)
X'
- Consistency (dates, document no.s, values, EID's etc.)
spelling, flow,-etc.).
Grammar (Continuity,f A/E Calculations and Assumptions
'Xl Engineering Review o
[ s] - Adequately Documented Reportability (10CTR21, 10CFR72, etc).
,4 WO 5 APPROVED Prepared by:
(Final) 130(070192) 2 of 2 JUL 011992 ZWBWAP BR AIDWOOD -
oN-SIC REVIEV t,
g 4
't'g
-%'F*"7
"*T T
4 9
g--'
eyw---t 4'
-97*--T'*---
- $'MVT-'
W
--'gg+W T
1 P'-
T-N'Tw m v-atviemy-tw D w-e q
w w
yr
- T r
BRAIDWOOD CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS BUMBER EASE 10.1 AIRBORNE RELEASES......................
I 10.1.1
System Description
I 10.1.1.1 Waste Gas Holdup System....................
1 10.1.1.2 Ventilation Exhaust Treatment System 1
10.1.2 Radiation Monitors 2
10.1.2.1 Auxiliary Building Vent Effluent Man' s...........
2 10.1.2.2 Containment Purge Effluent "eaitors.............
3 10.1.2.3 Waste Gas Decay Tank Monitors................
3 10.1.2.4 Gland Steam and CJndenser Air Ejector Monitors 4
10.1.2.5 Radwaste Building Ventilation Monitor............
4 10.1.2.6 Component Cooling Water Monitor...............
4 10.1.2.7 Miscellaneous Ventilation Monitors 5
10.1.3 Alarm and Trip Setpoints 5
10.1.3.1 Setpoint Calcul ations....................
5' 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors..........
5 10.1.3.1.2 Containment Purge Effluent Monitors.............
6 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors 6
10 l. 3. l. A Cc m re ne n V Co c lo nS V: n her Hco,4 crL G
10.1.3.2 Release Limits 6
10.1.3.3 Release Mixture.......................
8-10.1.3.4 Conversion Factors 8
10.1.3.5 HVAC Dilution Flow Rates 8
10.1.4 Allocation of Effluents from Common Release Points 9
10.1.5 Dose Projections for Batch Releases.............
9 10.2 LIQUID RELEASE 9
10.2.1
System Description
9 10.2.1.1 Release Tanks........................
.10 10.2.2 Radiation Monitors 10 10.2.2.1 Liquid Radwaste Effluent Monitors..............
10 10.2.2.2 Station 810wdown Monitor 10 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors..........
10 ll 10 i G;BBABR-JR.31
BRAIDWOOD CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) 10.2.3 Alarm and Trip Setpoints 11 10.2.3.1-Setpoint Calcul ations....................
11 10.2.3.1.).
Liquid Radwaste Effluent Monitor 11 10.2.3.1.2 Station Blowdown Monitor 11.
10.2.3.2 Discharge Flow Rates
...................12 10.2.3.2.1 Release Tank Discharge Flow Rate 12 10.2.3.3 Release Limits 14 10.2.3.4 Rel eas e Mi x t ure.......................
14 10.2.3.5 Conversion Factors 14 10.2.3.6 Liquid Dilution Flow Rates 15 10.2.4 Allocation of Effluents from Common Release Points 15 10.2.5 Projected Concentrations for Releases............
15 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM.......
17 S
1 I ty 10 11 G.BBAB4JRu31 susuuu u
CHAPTER 10 LIST OF TABLES tlLHBER EAG_E 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-18 10-2 Assumed Composition of the Braidwood Station Liquid Effluent 10-19 w
10-111 G-BBABRJR.31
- BPAIDWOOD t
CHAPTER.10 LIST OF FIGURES NUMBER PME -
10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-20 10-2 Simplified Liquid Radwaste Processing Diagram 10-H ;ta.-
10-3 Simplified Liquid Effluent Flow Diagram 10-2fJ-3 10-4 Simplified Solid Radwaste-Processing Diagram 10-0T A T 10-iv G.BBA84JR.31 rnu, - -...,.
n.-,,,
.w,-,
...~-N,,
w
BRAIDWOOD-CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES c
10.1.1
System Description
A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1.
The principal-release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack and Unit 2 Vent Stack in Figure 10-1).
In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A-1 of Appendix A).
10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor cool _ ant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by:
radiodecay prior to release to the environment.
The system is described in Section 11.3.2 of the. Byron /Braidwood UFSAR.
10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material-in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA-filters prior to release to the environment.
Such a system is 10-1 G.BBA04JR.31 tI.
BRAIDWOOD:
not considered to have any effect on noble' gas; effluents. The ventilation exhaust treatment systems are shown in Figure-10-1.
Engineered safety features atmospheric cleanup-systems are not considered to be ventilation exhaust treatment system components.
10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors 1RE-PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks.
Both vent stack monitors feature automatic isokinetic sampling, grab sampling, and tritium sampling.
In normal operation all three noble gas channels'(low, mid-range, high) are on line and active. On a high alarm the low-and mid-range noble gas channels are closed and only-the high range noble gas channel remains active. The~ iodine and particulate channels, however, continue to operate under all-conditions.
No automatic isolation or control functions are performed by these monitors.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.
i=
10-2 l
G:DBAS4JR.31 I-
BRAIDWOOD 10.1.2.2 Containment Purge Effluent Monitors Monitors IRE-PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously' monitor the effluent from the Unit I and Unit 2 containments, respectively. When airborne radioactivity in the containment purge effluent stream exceeds a specified level, station personnel will follow established procedures to terminate the-release by manually activating the containment purge valves.
Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring _the containment purge effluent.
No automatic isolation or control functions are performed by these monitors.-
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.
[/ Tree. Rodia t Monitors 1(2) RE'AR 1 and 1(2) R 2 monitor the containment atmosphere. On high alarm during a containment purge, these monitors will automatically terminate-the purge..-
10.1.2.3 Waste Gas Decay Tank Monitors Monitors ORE-PR002A/B continuously monitor the noble gas activity released from the gas decay tanks.
On high alarm, the monitors automatically initiate closure of the valve OGh thus terminating the release.
S 10-3 0-BBAB&JR.31
~
BRAIDWOOD Pertinent information~on'these monitors and asso'ciated control devices is provided in Byron /Braidwood UFSAR Table 11.5-1.
10.1.2.4 Gland Steam and condenser Air Ejector Monitors Monitors 1RE-PR027 and 2RL-PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively.
No control device is initiated by these channels.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1, 10.1.2.5 Radwaste Building Ventilation Monitor in t h e]
Monitor ORE-PR026 continuously monitors radioactivit radwaste building ventilation system.
No control device is initiated by this channel.
Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Tables 11.5-1, 10.1.2.6 Component Cooling Water Monitor Monitors ORE-PR009 (common), 1RE-PR009 (Unit.1), and 2RE-PR009 (Unit 2) continuously monitor the component cooling water heat-exchanger outlets. On high alarm ORE-PR009 initiates closure of both component cooling water surge tank (CCWST) vents, IRE-PR009 initiates closure of the Unit 1 CCWST vent, and.2RE-PR009 initiates closure of the Unit 2 CCWST vent.
10-4 G:BBAB4JR.31
l BRAIDWOOD Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-1.
10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods.
No control device is initiated by this channel.
Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1.
10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 5% of the maximum permissiblehI At/0h release rate for the high alarm and 1/2% of the maximum release rate for the alert alarm.
The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissiblef9
' #b release rate for the high alarm and of the maximum release rate for the alert alarm.
U 10-5 G.BBAB4JR.31
o BRAIDWOOD-10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.25 times the analyzed containment noble gas activity during purge.
However, per procedureT-the-totitL_ station 7elease rate is limited to approximateli'3% of the maxiiEUdrpermiss,ible release i
rate ~during this evolution.
N.
10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors gg The setpoints are established at 1.25 timcs the analyzed waste
\\ f 0,
gas tank activity during release.
/
'S h (/ '- limited togpproximatelTX3%ENETnYk'imtmrpereksi However_perprocedure -thegotaLnat4on:tcinasa nte-is -
b
/
r f
rJteed68fng t_hi_s evolution.
(See Section 10.1.3.2) 10.1.3.2 R lease Limits Alarm and trip setpoints of gaseous effluent monitors are I
established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Q.
ty (1.11)Q, E (Kf ) s 500 mrem /yr (10-1) t i
10-6 G BBADR-JR.31
- /0, /, 3, /. 4 (OmPone n t Cwhng N8er Mon,4cys
. l 7~h e se-spoint.
is based an f-he fedt0 n u clide mt4 Jn Table io-a, The am -lohcui cdwl.Jef ccjec+or ces p use is a'mded h
cL
'ID O b h ct i n f k d'
%y ni
- sdpomt,
[ Kee Se c-Ii on
/0, ;2,33 Sor.
fhe_
ConverS/vo
-..-f u c :fo r, -.)--
.wwww
-r
-#enh-
-nc.s
,a.Ae w
...,y-g sw
.6, 4
=me,-w.
..e e,
--a,em--ww w i m-a--=P4e at
- .aese -s a ftw%es =Me etiumie m
w
.---.mese--wa-g s
a e
w-w
+ -.
ww.ars4
- - m
- smN swe 4%N'
,--hmed.i asAen
.-m.
y m
a d
-e.~
E BRAIDWOOD k
Q,, E ((f,)[G(X/Q), exp(-X,R/3600u,)
(10-2) r
+ 1.1 3000 mrem /yr I
The summations are over noble gas' radionuclides 1.
f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
Q, Total Allowed Release Rate,
[pci/sec) i Vent Release The total allowed release rate of all noble gas radionuclidar released as vent releases.
e'P(- A; R/kva,) is sd nu1 iv w kr - cd etunT' The remaining parameters in Equation 10-1 have the-same definitions as in Equation A 8 of Appendix'A. The remaining parameters in Equation 10-2 have the_same definition as-in Equation A-9 of Appendix A.
Equation 10-1 is based on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr)Edue.to
^
noble gases released in gaseous effluents (see Section A.I.3.1-of.AppendixA).
Equation 10-2 is based on Equation A-9 of-Appendix A and the 10 CFR 20 restriction.on skin dose rate-10-7 0:BBAB4Jil31 5
BRAIDWOOD (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).
Since the solution to Eqn 10-2 is more conservative than the.
solution to Eqn 10-1, the value of Eqn 10 2 (3.09 x 10
('
5 pCi/sec) is used as the limiting noble gas release rate.
relea se en 4 h During evolutions involving releases from the containment or waste gas decay tanks, the tehl st:th b elease rate is b
8 procedurally limited to 1 x 10 pCi/sec (less than 1/3 the maximum permissibigs release rate).
QS4dson)
Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS.
10.1.3.3 Release Mixture In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1.
10.1.3.4 Conversion Factors The response curves used to determine the monitor count rates.
are based on the sensitivity to XE133 for conservatism.
10.1.3.5-HVAC filut-4 Flow Rates The plant vent stack flow rates are obtained from 1/2 PR28J. However, if the readout indicates "0" flow, the following minimum rated fan flow values are _ currently used; 10-8 O BBADRJR 31 i
BRAIDWOOD 8
6.15 x 10 cc/sec Unit 1 4.55 x 10' cc/sec Unit 2 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas de:ay tanks are comprised of contributions from both units.
Consequently, allocation is made evenly between units.
10.1.5 Dose Projections for Batch Releases Dose projections are not made prior to release. Doses are calculated after_ purging the containment or venting the_ waste gas decay tanks.
Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50.
10.2 LIQUID RELEASES 10.2.1
System Description
A simplified liquid effluent flow diagram is provided in Figure 10-2.
A simplified liquid waste processing diagram-is provided in Figure 10-3.
The liquid radwaste treatment system is designed.and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for-treatment by demineralizer or a concentrator for.the purpose of reducing the total radioactivity prior to release to the-10-9 0.BBABR JR.31 i
4 i
BRAIDWOOD environment. The system is described in Section 11.2.2 of the Byron /Braidwood Updated Final Safety Analysis Report.
10.2.1.1 Release Tanks There are two radwaste release tanks (0WX0li - 33100 gallon capacity, and OWX26T - 33750 gallon capacity) which receive liquid waste before discharge to the Kankakee river.
10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Ef fluent Monitors Monitor ORE PR001 is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves 0WX-353 and OWX-896 to terminate the release.
Pertinent information on the monitor and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.2.2 Station Blowdown Monitor Monitor ORE-PR010 continuously monitors the([hbirculating water blowdown. No control device is initiated by this channel.
Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors 10-10 0.BBAB4JR.31
d 4
m BRAIDWOOD Monitors IRE-PR02, 2RE-PR002, 1RE-PR003, and 2RE-PR003 continuously monitor the RCFC and ESSW outlet lines.
No control device is initiated by these channelse Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the enrestricted area.
10.2.3.1.1 Liquid Radwaste Effluent Monitor During release the setpoint is established at 1.5 times'the analyzed tank activity plus the background reading.
However, pe pr ceDEcuaximum;revelse rate is limited to m-a value,that -will.. -result in less than 50% MPC'at-the d ge point.
(See Section 10.2.3.2).
'A 10.2.3.1.2 Station Blowdown Monitor The monitor _setpoint is found by solving equation 10-3, 10-11 0,BBAB4JR 31
.,.o.-,,...
1
~
i BRAIDWOOD h
W + (1.25 x C ) xFL, / FW '+ F,
(10-3)
I P s: C P
Release Setpoint
[pCi/mt) 1.25 Factor to account for minor fluctuations in count rate.
C'"
Concentration of activity in the
[pC1/mt) circulating water blowdown at the time of discharge.
(" Background reading")
C' Analyzed activity in the release tank
[pci/mt)
W F
Circulating Water Blowdown Rate
[gpm)
F[,
Maximum Release Tank Discharge Flow Rate-
[gpm):
The flow rate from_the radwaste discharge tank.
10.2.3.2 Discharge Flow Rates 10.2'.3.2.1 Release Tank Discharge Flow Rate-10-12 0 DBAB4JR 31
l BRAIDWOOD Prior to each batch release, a grab sample is obtained.
The results of the analysis of the waste sample determine the discharge rate of each batch as follows.
C;r 0.5(F[,t E C, NPC,))
(10-4)
FL, o
/
The summation is over radionuclides 1.
0.5 Factor for conservatism FL, Maximum Permitted Discharge Flow Rate
[gpm]
The maximum permitted flow rate from the radwaste discharge tank based on radiological limits.(not chemistry limits which may be more restrictive)
Ff,,
Circulating Water Blowdown Rate
[gpm]
1 Cf Concentration of Radionuclide i.in
[pci/m]
the Release Tank The concentration of radioactivity in 10-13 0:BBAB4JR.31
BRAIDWOOD i
the radwaste discharge tank based on measurements of a sample drawn from the tank.
- MPC, Maximum Permissible (pCi/mt)
Concentration of Radionuclide i 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20. Discharge rates and setpoints are adjusted to ensure that 50% of applicable maximum permissible concentrations (MPC) are not exceeded.
( See secoon to.a. 2. 2 10.2.3.4 Release Mixture For monitors ORE-PR001 and ORE-PR010 the release mixture used for the setpoint determination is the radionuclide mix.
identified in the grab sample isotopic analysis or the mix in-Table 10-wMeever is ere censervat4v4 For monitors IRE-PR001, 1RE-PR002, 2RE-PR001, and 2RE-PR002,.
the release mixture is the radionuclides which are listed in Table 10-2.
Each nuclide in the mix is at a concentration which is 10% of the MPC value given in 10 CFR 20 Appendix B.
Table-II, Column 2.
10.2.3.5 Conversion Factors The readouts for the liquid efflue'nt monitors are in pCi/mt.'
The cpm to pCi/mi conversion is based on the detector sensitivity to Cs-137.
10-14 G:BBABf4JR.31
l BRAIDWOOD 10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are obtained from circulating water blowdown transmitter loop 0FT-CWO32.
10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (0WX0lT or OWX26T) are comprised of contributions from both units.
Under normal operating conditions, it is-difficult to apportion the radioactivity between the units.
Consequently, allocation is made evenly between units.
10.2.5 Projected Concentrations ror Releases After determining F[,fron Equation 10-4,10 CFR 20 compliance is verified using Equatio1s 10-5 and 10-6.
g'--
l I
Cj-C Fh/(FL,+Fb)]
(10-5)
{ ( C$/MPC, } so.5 (10-6)
The summation is over radionuclides 1.
-C$
Concentration of Radionuclide i (pCi/
in the Unrestricted Area 10-15.
G:BBAB4JR.31
l BRAIDWOOD The calculated concentration of radionuclide i in the unrestricted area as determined by Eq'ation 10-5.
ed
- MPC, Maximum Permissible Concentration
[pCi/ml]
of radionuclide i FL Maximum Release Tank Discharge
[gpm]
flow Rate F[i circulating Water Blowdown Rate
[gpm]
0.5 Factor for conservatism mw---v-e=
n E
)
e
~
'Cl!Ulk g'
Q fl i t'th Ek 00 0
(
(L ii S C' Oh$(Ill0 $
\\
in oc Rein <se Lt
\\,
T he e e nc t ni r %+,c n c> 4 r u d e e a ti s ve 4 10 y
\\
C-T Mk W M fC.
Ok l5 C h (L P 3 Ch(L h K b 6 Led On
/77 F al a r ( rne m t pp gt S u. 04 p / t d raw n
-(r c o, The
- yggng, N
10-16
~~
G BBABRJR.31
BRAICWOOD 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains.the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.
Figure 10-4 is a simplified diagram of solid radwaste processing.
r 10-17 0.BBAB&JR.31 u
w-w c.
y
BRAIDWOOD Table 10 1 Assumed Composition of the Braidwood Station Noble Gas Effluent Percent of Isotope Total Annual Release Ar-41 00.89 Kr-85m 00.18 Kr-85 24.9 h0 Kr-87 Kr-88 00 28 Xe-131m 01.4 Xe-133m 00.57 Xe-133 71.1 Xe-135
'00.53 Xe-138 00.04 10-18 G BBAB4JFt31 '
BRAIDWOOD Table 10-2 Assumed Composition of the Braidwood Station Liquid Effluent Isotope Concentration Isotope Concentration (pCi/ml)
(pCi/ml)
Ru-103 8.00E - 06 Mn-54 1.00E - 05 Ag-110m 3.00E - 06 Fe-59 5.00E - 06 Te-127 2.00E - 05 Co-58 9.00E - 06 Te-129m 2.00E - 06 Co 60 3.00E - 06 Te-131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr-95 6.00E - 06 l-130 3.00E - 07 Nb-95 1.00E - 05 1-131 3.00E - 08 Mo-99 4.00E - 06 1-132 8.00E - 07 I-133 1.00E - 07 1-135 4.00E - 07 Cs-134 9.00E - 07 Cs-136 9.00E - 06 Cs-137 2.00E - 06 Ce-144 1.00E - 06
_Np 239 1.00E - 05 10-19 G.88AB4JR.31 4
BwAP 1305-371 Revision 4.1 Braldwood On-site Review and Investigation Report 9 h "l N-Date: 12 29 92.
OSR Number Subject Reviews ObiE bMf b NM}
b*"^
^ '^
^ " "
O.Y.
44rd W Requested by:
A Disciplines Required jR A Huclear Power Plant Technology DB Reactor Operations DC Reactor Engineering DD Chemistry
$E Radiation Protection DF Instrwnentation and Control OG Mechanical and Electrical Systems 7b
Participants:
k 'EN O t~r+k pex Ane % rv t t f P '1 '7 L OSR Hembership Approved d
ogtAW Technical Staff Supervisor
/
Date 10CTR50.59 Screening is Required: - - - - - - - - - - - - - - - Y (fi) k\\
If yes, attach completed documentation in accerdance with BwAP 1205-6.
10CFR50.59 Safety Evaluation is Required: - - - - - - - - - - - Y (ii)
N If yes, attach completwd docurnentation in accordance with BwAP 1205-6.
(If a Safety Evaluation is Required, then Concurrence is Required by Offs 1te Review)
Concurrence Required by Offsite Review? (per Section C.6)
--Yh N
rindings and Recommendations doAdc h dk w Wroler,aa\\ mio:enakin wh:c k M rn r, W t k e l.
F]th valgh.
sa J
Added %e rrwnc/ as me m ber d 4he n hiic Odded ne m > Italtoic'$ o m i N/o lJG a
Uti. CM de/ Acae 4 4tt kervm Aut n net r 4 A tv Cen w ra b 3 ew a
ik fik 4Td*3f5-h'/'ns M ed/
Ta M et -
On-Site Review Committee Signature indicates concurrence with Findings and l
Recommendations and 10CTR50.59 Safety Evaluation.
Slonat res Disciplincl.sl Date Ml29,ht -
~
hk AhEdo
>> A,/q San S MIL E
12-30 'I n-n
'Ib Approved by:
S$TIONMANAGER DAIE APPROVED l
130(070192) 1 of 2 0 1 1992 ZWBWAP om.AIDWOOD BR nc neview
DwAP 1205-371' Revision 4.1 BRAIDWOOD ON-SITE REVIEW AND INVESTIGATIN REPCRT OSR No.
1101E
- This checklist is provided as guidance for OSR
- preparation and review.
Items should be
- completed as appropriate.
Preparer App. N/A 1.
SYNOPSIS FORMAT X'
- Purpose X'
- Executive Summary of Findings and Recommendations
/"
- References
/'
- Bases of Findings and Recommendations
/l
- Contingency Actions Recommended II.
DOCUMENTATION REVIEWED: (List App 11 cable Sections in Synopsis)
N
'/
- UrSAR J
- Tech Specs. V l/
- Admin Tech Requirements
,/
- Safety Evaluation Report
- Fire Protection Report
,s,
- Prior 10CFR50.59 Safety Evals v
- NRC Commitments
/
- Vendor Documentation ll
'/
- Special. Permits / Licenses __
- Station Procedures
- Environmental Qualifiestion 1
i
- Design Basis Documentation
,.4
- Drawings
- Maint. History (TJM)
- HPRDS s/
- PRA Info.
/
- Prior NED QE 40.1 Operability Evaluations III. PLANT CONDITIONS: (Discuss Applicable, Items-in Synopsis) f
- Applicable Modes
- Work In-Progress / Planned v
f
- Temporary Alteration Installed
- Out-of-Ssrvice
- Degraded Equipment Log
/
- Abnormal Valve Lineups
/l
- Effect on Opposite Train'
- Ef f ect on Other Unit
. - Effect on Other Station ll l[
- Training Required
/
's IV.
OTHER CONSIDERATIONSr (Discuss Applicable Items in Synopsis) s X
- Consistency (dates, document no.s, values, EID's etc.).
K'
- Grammar (Continuity, spelling, flow, etc.)
[y) - Engineering Review of A/E Calculations and Assumptions Adequately Documented
/
- Reportability (10CTR21, 10CTR72, etc)
Y~ l SN
)
APPROVED Prepared by' (rinal) 130(070192) 2 of 2 JUL 011992 ZWBWAP BR AIDWOOD.
oN-SUE PEVIEW
. ~
~,-
REVISION 0.K.
JANUARY 1993 GENERIC LIST OF TABLES - APPENDICES NUMDER TITLE EAGE A-1 Release Point Classifications A-58 A-2 Nearest Downstream Community A-59 Water Systems Affected B-1 Portion of an Example Joint B-34 Frequency Distribution C-1 Illustration of Model for Calculating C-8 Dose Due to Radioactivity Rb. eases C-2 Illustration of Model for Dilution of C9 Tank Discharges D-1 Inhalation Dose Factors for Adults D-2 D-la Inhalation Dose Factors for Teenager D-4a D-2 Inhalation Dose Factors for Children D-5 D-3 Inhalation Dose Factors for Infants D-8 D-4 Ingestion Dose Factors for Adultu D-ll D-4a Ingestion Dose Factors for Teenager D-13a D-5 Ingestion Dose Factors for Infants D-14 D-6 Miscellaneous Dose Assessment Factors D-17 Environmental Parameters D-7 Miscellaneous Dose Assessment Factors D-19 Consumption Rate Parameters D-8 Stable Element Transfer Data D-21 D-9 Atmospheric Stability Classes D-23' D-10 Vertical Dispersion Parameters D-25 D-11 Maximum Permissible Concentrations (MPCs) of D-27 Dissolved or Entrained Noble Gases Released from the site to Unrestricted Areas in Liquid Waste D-12 Radiological Decay-Constants (1 )
D-28 1
D-13 Bioaccumulation Factors Bi to be Used in the D-32 Absence of Site-Specific Data D-14 Beta Air and Skin Dose Factors for. Noble Gases D-34 D-15 External Dose Factors for Standing on.
D-35 Contaminated Ground D-16 Sector Code Definitions D-38 TOC-14
REVISICN O.X JANUARY 1993
-Inhalation i
Milk ingestlen 5 Ing e stio n ->
Animals Meat inge ntlen-D Air ->
+ Man-
~
- D e p o sitio n -+ Vegetallen,,,, Ing e stle n 4
I Radiation 5
De pe ellten -+ sell
- Radiation U
All of these pathways are considered in Regulatory Guide 1.109 (Reference 6).
In the station's calculations, only the solid-line pathways are considered.
The dashed-line pathway (uptake of radioactivity by vegetation from soil) is omitted.
3-5
.---e n
s-a w4,-
-. =.
.. _= -
REVISION-0.K JANUARY 1993 Petsble 5 water Ingest on y.
i supply 4ustic
-Ingestion y
-U p t a k e ---+ feeds Milk Ingentlen..+
--In g e s t i o n -- ~~~ --~ ~ ---~~ + Animals 4"v.
e-Ingestion +
g%
ii Meat alngestion.-+
t Water +
l
+ Man
--Irrigation-+ Yagetallen [ -i n g e s tio n - - - - - - - - - - - - - - - - - - - - - - - --+
4 I
- - Ir rig alle n -.+ sell
-- De po sitten.-, shoreline
.. R a d i a t t e n - ------- ----- - ------ ----- - - -->
sediment All of these pathways are considered in Regulatory.
Guide 1.109 (Reference 6).
In the station's' calculations, j
only the solid-line pathways (ingesting of potable water
.and aquatic foods) are considered.
3-6 e4
_e>**
T V' f
~
Y T-r'-e?
r
REVISICN O.K JANUARY 1993 pinhalja Inhalation Dose Commitment
[mrC2.]
Dose commitnient to organ j of an individual in age group a due to inhalation of non-noble-gas radionuclides released in gaseous i
effluents.
Inhaled Radioactivity (pCi]
Ila Activity of radionuclide i inhaled by an individual in age group a in the time period under consideration.
DFA ja Inhalation Dose Factor
[ mrem /pCi]
l Dose commitment to organ j of an individual in age group a per unit of activity of radio-nuclide i inhaled.
The amount of radioactivity inhaled Ila (pC1) is the product of 3
radioactivity concentration in air (pci/m ), breathing rate Ra 3
(m /yr), and the time period of concern [yr).
The radioac-tivity concentration is the product of radioactivity release 3
rate (pCi/sec] and relative concentration factor X/Q [sec/m ),
The Inhalation Dose Commitment Factor Values of the inhalation dose commitment factor are the same for all stations.
This is because the factor is defined as a dose rate per unit of radioactivity intake.
The station-specific aspects of the calculation of inhalation dose concern the quantity of radioactivity inhaled.
Values of the inhalation dose commitment factor are provided in-Tables D-1, D-la, D-2, and D-3 of Appendix D of this manuc1 as follows:
For various potential effluent non-noble-gas radio-nuclides.
For four age groups:
Adult (17 years and older).
Teenager (11 years to 17 years).
Child (1 to 11 years).
4-25
m.
REVISION O.X JANUARY 1993 e
Leafy vegetables.
Produco (nonleafy vegetables, fruit, and grain).
Milk.
o Mont.
t Equation A-lC of Appendix A is used to calculate the dose cocmPcwvt due to ingestion of food containing non-noble-gas radionuclides released in ghseous effluents.
The dose commit-ment due to ingcstion of a single radionuclide i may be represented as follows:
f00d D
ja " I la DFI ja (4~11) i f
d D
ja Food Pathways Dose Commitment
[mreni)
Dose commitment to organ j of an individual in age group a due to ingestion via food pathways of non-noble-gas radionuclides released in gaseous effluents.
Iia Ingested Activity
.[pCi]
Activity of radionuclide i ingested by an individual in age group a in the time period under consideration.
DFI ja Ingestion Dose Commitment Factor
[ mrem /pCi]
i Dose commitment to organ j of an individual in age group a per-unit of activity of radionuclide i ingested.
Values of the ingestion dose commitment factor are the same for-all stations.
This is because the factor is defined as a dose rate per unit of radioactivity intake.
The station-specific aspects of the calculation of ingestion dose concern the quan-tity of radioactivity ingested.
Values of the ingestion dose commitment factor:are provided in Tables D-4, D-4a, D-4b and D-5 of Appendix D of th s manual for var ous radionuclides, for-i i
4.-n
REVISION O.K JANUARY 1993 members of the public, and for the same organs as the inhalation dose commitment factor is provided for.
The ingested activity Iia is calculated by an equation of the following form (see Equations A-19 through A-22 of Appendix A):
1,=Ci Ua (tr/365) f (4-12) 1 Ci Food Product Radioactivity IPCi/L or pCi/kg]
Concentration Average concentration of radionuclide i in the food product during the time period of interest.
The units are pCi/L for milk and pCi/kg for leafy vegetables, produce, and meat.
U Food Product Consumption Rate (L/yr or kg/yr) a Annual consumption (usage) rate of the food product for individuals in age group a.
The units are L/yr for milk and kg/yr for leafy vegetables, produce, and meat, t
Time period of Interest (days) r Time period of release or exposure.
1/365 Conversion Constant (yr/ day)
Converts days to years, f
Food Product Affected Fraction Fraction of the consumed food product that is affected by radioactivity released from the plant.
For milk and meat, f is taken as 1.
For leafy vegetables, it is taken as f,
y and for produce it is taken as fp.
The food product radioactivity concentration is calculated from measurements of radioactivity in station releases.
The differ-ent equations used for radioactivity concentration in vegeta-tion, milk, and meat are discussed below.
4-28 a
REVISION OcK JANUARY 1993 f
The average concentration C i in feed [pci/kg).
e The animal's feed consumption rate Wg [kg/ day).
The fraction Fy of an animal's daily intake of radio-activity that appears in meat (pCi/kg in meat per pCi/ day ingested by the animal) (days /kg).
e A factor to account for radiodecay between the slaugh-ter of the animal and the consumption of its meat.
4.3 LIQUID RELEASES The evaluation of doses and dose rates due to radioactivity in liquid effluents is required to assess compliance with provi-sions of RETS related to 10 CFR 50, Appendix I.
Some of the radioactivity released in liquid effluents from a nuclear power station may be ingested by persons who drink water or consume fish from a body of water receiving station liquid discharges.
The stations obtain the dose commitment due to radioactivity in liquid releases as the sum of dose commitments from the drinking water and fish pathways.
The dose commitment is calculated for an adult.
Equations A-30 and A-31 of Appendix A Gre used to calculate dose commitments for the members of the public due to consumption of drinking water and fish.
The total dose commitment for the liquid pathway due to a radionuclide i is as follows:
f D119ja " I"ia DFl ja + I ia DFl ja (4-13) i i
119 Dose Commitment for a Member of the
[ mrem)
D 3
public Due to Radioactivity in Liquid Effluents l
l l
l u
4-31
.~
_]
REVISICN O.X JANUARY 1993 Dose commitment to organ j of a member of the public of age group a consuming drinking water and fish containing radioactivity released in liquid effluents.
W f
I ins I ia t.ngested Activity (pCi]
Activity of radionuclide i ingested by an individual in age group a in the time period under consideration due to consupption of W
drinking water (I ia) Of fi8.h (I 1a)*
DFl ja Ingestion Dose Factor
[ mrem /pCi]
i Dose commitment to organ j of an individual in age group a per unit of activity of radio-nuclide i ingested.
The ingested activity is calculated as follows:
W W
W I ia = U C i t (4-14) f f
I ia = U Cf t
(4-15) i W
f U,U Usage Factor
[L/hr, kg/hr)
W f
Consumption rate of water (U ) or fish (U )
by individual in age group a.
W f
C i, C i Concentration of
[pCi/L, PCi/kg)
Radioactivity Concentration of radiopuclide i in drinking water (C i) or fish (C i) due to release in W
liquid effluents, t
Time period of Concern
[hr)
Time period during which the release and consumption occur.
W The radioactivity concentration in water'C i [pCi/L] is obtained by dividing the radioactivity release [pci) by the volume of water [L] in which the release is diluted (e.g.,
the 4-32
.~
l
REVISICN G.K JANUARY 1993 Stations entitle this report, " Annual Radiological Environmental Operating Report where is the year covered in the report.
All stations except Dresden must submit it prior to May 1 of each year; Dresden must submit it by March 31.
The report contains results for the preceding calendar year.
There are slight variations from station to station in the required content of this report (see the station RETS).
However, items required at one or more station (s) include the following:
An assessment of the radiation doses from radioactive liquid and gaseous effluents during the previous calendar year.
An annual summary of hourly meteorological data collected over the previous year, which may be on magnetic tape.
An assessment of radiation doses from the station and nearby uranium fuel cycle sources to the likely most exposed member of the public.
The purpose is to show conformance with 40 CFR 190.
A summary description of the radiological environmental monitoring program.
Results of the analyses of a11' radiological environ-mental samples and of all environmental radia-tion measurements.during the report period.
A summary and tabulation of the above results.in a particular format.
The stations use a format like that shown in Figure 7-1.
This format involves use of the indicator / control concept.(see Section 5.3).
For each sample type and analysis, the summary table includes one column which contains the mean and range of results at indicator locations and another column which contains the mean and range of results at. control locations.
Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period.
Results of the annual land use census.
7-3
?
m :' M 4
5 *.
REVISION O.K JANUARY 1993 j
implements the pCp for solid radwaste.
It measures hydrogen or oxygen concentration in off-gas.
It also measures tank radioactivity and BWR off-gas radioactivity.
The station maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS.
In the event that any RETS requirements are violated, the station is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC.
The station assembles the Semiannual Radioactive Effluent Release Report, issues the report, and distributes it in accordance with Reference 42.
The station also issues the Annual Radiological Environmental Operating Report.
The report is assembled by the environmental contractor.
NSEP reviews the report prior to issuance and distributes the report after it is issued.
8.2 METEOROLOGICAL CONTRAC'IOR The meteorological contractor operates and maintains the meteorological tower instrumentation at each station.
The contractor collects and analyzes the data and issues periodic reports (weekly, monthly and semiannually) to NSEP.
The contractor prepares the meteorological data summary required for the annual report and also computes and plots the isopleths contained in the annual report (see Section 7.2).
8.3 ENVIRONMENTAL CONTRACTOR The environmental contractor collects environmental samples and performs radiological analyses as specified in the station's 8-2 P
REVISIEN O.K JANUARY 1993 radiological environmental monitoring program (see Chapter 11).
The contractor issues monthly reports of results to NSEp.
The contractor participates in an Interlaboratory Comparison Program and reports results in the Annual Radiological Environmental Operating Report.
The contractor performs the annual land use census.
The contractor also assembles the Annual Radiological Environmental Operating Report and submits it to NSEP.
8.4 CORPORATE DEPAJATMENTS The NSEP administers the offsite dose assessment program.
The department issues and maintains the ODCM (sometimes with assistance from an engineering consultan't) as well.as some of the proc 3dures associated with implementation of the ODCM.
The department supervises the meteorological and environmental contractors by receiving and reviewing their periodic reports.
It reviews the monthly radiation dose calculations performed by the stations.
It reviews the Annual Radiological Environmental Operating Report, which is assembled by the environmental contractor, and distributes it on behalf of the station.
The Production Engineering and Information Systems Department writes and maintains the computer program used by the stations for offsite dose calculation and projection.
Instructions for using this program are presented in Reference 1.
B-3 y Oh
REVISION 0.K JANUARY 1993 40.
Commonwealth Edison Company, Information Relevant to Keepino Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable.
La Salle County Station. Units 1 and 2, June 4, 1976.
41.
U.S. Nuclear Regulatory Commission, Branch Technical
?osition, Radiological Assessment Branch, Revision 1, November 1979.
(This is a branch position on Regulatory Guide 4.8.)
42.
Commonwealth Edison Company, Technical Services Emeroency Plannina Department. Distribution of Monthly. Semiannual, and Annual Radiolooical and Meteoroloaical Reports, EP-ADMIN-7.
43.
U.S. Nuclear Regulatory Commission, Calculation of Beleases of_ Radioactive Materials in Gaseous and Llauld Effluents from Pressurized Water Reactors (PWR-GALE Code),
NUREG-0017, April 1976.
44.
U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Licuid Effluents from Boilina Water Reactors (BWR-GALE Code),
NUREG-0016, April 1976.
45.
Sargent & Lundy, N-16 Skyshine from BWR Turbine Systems and Pipino, NSLD Calculation No. D2-2-85, Rev.
O, 2/1/85.
45a. Sargent & Lundy Calculation ATD-0138, Rev. O, "N-16 Skyshine Ground Level Dose from Dresden Turbine Systems and Piping," July 14, 1992.
45b. Sargent & Lundy Calculation ATD-0139, Rev. O, "N-16 Skyshine Ground Level Dose from LaSalle Turbine Systems and Piping," July 28, 1992.
45c. Sargent & Lundy Calculation ATD-0140, Rev. O, "N-16 Skyshine Ground Level Dose from Quad Cities Turbine Systems and Piping," July 28, 1992.
46.
U.S. Nuclear Regulatory Commission, Methods for Remonstratina LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, February 1980.
47.
International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.
48.
U.S. Nuclear Regulatory Commission, Ace-Specific Radiatian Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172, 1977.
R-5 e
e
REVISION 0.K JANUARY 1993 49.
W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Forace-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.
50.
E. C. Eimitis and M. G. Konicek, Derivations of Continuong Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).
51.
D. C. Kocher, Editor, Huclear Decav Data for Bedionuclides Occurrina in Routine Releases from Nuclear Fuel Cycle Facilities, ORNL/NUREG/TM-102, August 1977..
52.
R. L. Heath, Gamma-Ray Spectrum Cataloa, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.
53.
S. E. Thompson, Concentration Factors of Chemical Elements in Edible Acuatic Oraanisms, UCRL-50564, Rev.
1, 1972.
54.
U.S. Nuclear Regulatory Commission, Instruction Concernina Risks from Occupational Radiation Exposurq, Regulatory Guide 8.29, July 1981.
55.
Dresden Nuclear Power Station, Radioactive Waste and Environmental Monitorina, Annual Report 1987, March 1988.
56a. Sargent & Lundy Calculation ATD-0173, Rev.
O, Dated 9/21/92, " Annual Dose to Members of the Public Due to the LaSalle IRSF."
56b. Sargent & Lundy Calculation ATD-0174, Rev.
O, Dated 9/21/92, " Annual Dose to Members of the Public Due to the Zion IRSF."
56c. Sargent & Lundy Calculation ATD-0175, Rev.
O, Dated 9/21/92, " Annual Dose to Members of the Public Due to the Quad Cities IRSF."
56d. Sargent & Lundy Calculation ATD-0176, Rev.
O, Dated 9/21/92, " Annual Dose to Members of the Public Due to the Dresden IRSF."
57a. Sargent & Lundy Calculation ATD-0180, Rev.
O, Dated 9/25/92, " Dose Information Around Braidwood DAW Sea / Land Van Storage Area."
57b. Sargent & Lundy Calculation ATD-0181, Rev. O, Dated 9/25/92, " Dose Information Around Byron DAW Sea / Land Van Storage Area."
57c. Sargent & Lundy Calculation ATD-0182, Rev. O, Dated 9/25/92, " Dose Information Around Dresden DAW Sea / Land Van Storage Area."
57d. Sargent & Lundy Calculation ATD-0183, Rev.
O, Dated 9/25/92, " Dose Information Around LaSalle DAW Sea / Land Van Storage Area."
R-6
____._____________m.__
REVISION 0.K JANUARY 1993 69.
G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Ray Exoosures Due to Finite Plumes, Health Physics 41, 319 (1981).
70.
Reserved reference number.
71.
Reserved reference number.
72.
W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (CECO) dated January 3, 1972.
73.
Electric Power Research Institute, Radioloaical Effects of Hydrocen Water Chemistry, EPRI NP-40ll, May 1985.
74.
U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statement on Uranium Millina, NUREG-0511, April 1979.
75.
U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle. Part I - Fuel Supply, EPA-520/9-73-003-B, October 1973.
76.
U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Licht Water Cooled Reactors, NUREG-0002, August 1976.
77.
U.S. Nuclear Regulatory Commission, Democranhic Statistics Pertainino to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.
78.
Nuclear News 31, Number 10, Page 69 (August 1988).
79.
General Electric Company, Irradiated Fuel Storace at Morris Operation. Operatino Experience Report. January 1972 throuch December 1982, K. J. Eger, NEDO-20969B.
80.
U.S. Nuclear Regulatory Commission, Generic Letter 89-01,
" Guidance For The Implementation of Procrammatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Procram", January 1989.
81.
" Assessment of the Impact of Liould Radioactive Effluents from Braidwood Station on Proposed Public Water Intakes at Wilminoton. Illinois", J.C. Golden, NSEP, January 1990.
82.
NRC Safety Evaluation Report (SER)/ Idaho National Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision O.A, December 2, 1991.
R-8 O
n
REVISION 0.K JANUARY 1993 is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:
Stack (or Elevated) Release Point (denoted by the symbol S or subscript s)
Ground Level Release Point (denoted by the symbol G or subscript g)
Vent (or Mixed Mode) Release Point (denoted by the symbol V or subscript v)
The release point classifications of routine release points at the nuclear stations are stated in Table A-1 of this appendix.
Releases from points not listed in Table A-1 are considered ground level releases.
A.l.2 Dose Due to Nable Gas Radionuclides A.l.2.1 Gamma Air Dose Requirement Standard Technical Specifications (References 2 and 3) limit the gamma air dose due to noble gas effluents released from each reactor unit to area at and beyond the site boundary to the following (see Specification 3.11.2.2):
Less than or equal to 5 mrad per calendar quarter.
Less than or equal to 10 mrad per calendar year.
This provision is related to one of.the design objectives of 10 CFR 50, Appendix I.
Section 12.4 of each station's RETS contain a somewhat similar l
provision.
A-2 w
REVISION 0.K JANUARY 1993 Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression:
GAi ig }-
(A-1)
Dy = (3.17E-8)E{ S Aiis+VAi iy +
The summation is over noble gas radionuclides i.
Dy Gamma Air Dose
[ mrad]
Dose to air due to gamma radiation from noble gas radionuclides released-in gaseous effluents.
3.1"E-8 Conversion Constant-
[yr/sec]
Converts seconds to years.
Si, Vi, Gi Gamma Air Dose Factor
[(mrad /yr)/
(pCi/sec)]'
Gamma air dose rate at a specified location per unit of radioactivity release rate for radionuclide i released from a stack, vent, or ground level release point, respec-tively.
See Section 4.2.1.1, Section B.5 of Appendix B, and Table F-7 of Appendix F.
Ais, Aiv, Aig Cumulative Radionuclide Release
[pCi]
Measured cumulative release of radionuclide i over the time period of. interest from a stack, vent, or ground level release point.
l l
A-3
REVISION 0.K JANUARY 1993 Application Standard Technical Specifications (References 2 and 3) require-determination of cumulative gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days'(see Specification 4.11.2.2).
Sections 12.4 of each station's RETS contain a somewhat similar provision.
The dose factors in Table F-7 of Appendix F are-used for the determinations required by these specifications.
These values were calculated for the site boundary in each sector and are judged to be very good approximations to the maximum offsite values.
After doses for all sectors are determined, the highest dose is compared with the RETS limit on gamma air dose.
For a release attributable to a processing or effluent-system shared by more than one reactor unit, the dose due to an indivi-dual unit is obtained by proportioning the effluents among the units sharing the system.
The allocation procedure is speci-fied in Chapter 10 of this manual.
l A-4
~
l
.~
REVISION.-0.K.
. JANUARY 1993<
=
A.1.2.2 Beta Air Dose
- Requirement-Standard Technical Specifications (References 2--and 3) limit.
the beta air dose due to-noble gases in-gaseous effluent's released from each reactor unit to areas at and.beyond the site boundary to the following (see Specification:3.11.'2.2):
Less than or equal to 10 mrad' per: calendar quarter..
Less than or equal to 20 mrad per: calendar year.
e This provision is related to one of the design objectives-of 10 CFR 50, Appendix'I.
Section 12.4 of each station's-RETS contain a somewhat similar=
provision.
Equation
-The beta' air-dose-'due'to noble gases released in gaseous-effluents is-calculated by the'following. expression:
L [(X/Q)3A' ig. + (X/Q)yA'iy (A-2)
~
Da
= (3.17E-8)E(-
i
+ (X/Q)g 'ig) )
A-i
~
A-5 4
e ap-N-'
=y,
,m, ww.,-me.
<*.-e-.
+
w g-e,.
- wi, o y w
+ - -.
w-4+-wr-r 4-
.,+-a ry.,49..g 4 r-
- i4 r s,,y e-w, w:y ++w -w 1pm -.
1
REVISICN 0.K JANUARY.1993 exp(-l R/3600u )
(A-5)
A'ig = Aig i
g Cumulative Radionuclide
[pCi]
- Ais, Aiy, Release.
Aig Defined in Section A.l.2.1.
Ai Itadiological Decay Constant
[hr~1]
Radiological decay constant for radionuclide i.
See Table D-12 of Appendix D.
R Downwind Range (m]
Distance from the release point to_the dose point.
See Tables F-5, F-6, and F-7.
3600 Conversion Constant
[sec/hr)
Converts hours to seconds.
Average Wind Speed (m/sec]
u,u su,g y
Average wind speed for a stack, vent, or ground level release.
See Section B.l.3 of Appendix D and Table F-4 of Appendix F.
Application Standard Technical Specifications (References 2 and 3) require determination of cumulative beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days'(see Specification 4.11.2.2).
Section 12.4 of each station's RETS'contain a somewhat similar provision.
A-7
=
REVISION OoK JANUARY 1993-Beta _ air dosefis determined'for each sector using 'the highest calculated offsite value of X/Q for that sector.- Thisivalue-
- and the distance R to'which it-pertains are provided in Table F-5 of Appendix F.
The highest-dose is~ compared with the-Technical Specifications limit on beta air dose.-
For-a release attributable to a processing-or-effluent' system shared by more than one reactor unit, the dose due to.an indivi-dual unit is obtained by proportioning the eff16ents among the.
units sharing the system.
The allocation procedure is speci-fled in Chapter 10 of this manual.
A.1.2.3 Whole Body Dose Requirenent I-Standard Technical-Specifications (References 2 and 3) limit tha annual dose-commitment to any_ member of the public due:to releases of radioactivity and to radiation.from-uranium fuel cycle sources to less than or equal.to 25 mrem-to the whole body (see Specification 3.11.4).. The limit applies to the. sum of doses due to radioactive effluents (airborne and liquid)-and doses due to 6irect radiation.from noneffluent sources-(e;g.,
sources contained in-systems on site).
This specification is related.to a dose limit of 40 CFR'190. - See Section A.3 for further discussion.
Section 12.4 of each station's RETS contain a somewhat similar provision.
{
A-8 r=r---
e se e
6 9,v ee w
- -rawe-,
- e w
-awe
-=--m
--e t-.w=
m
.--we---.
e w-w
- * - - = -
c e
++**r-
REVISIO] 0.K JANUARY 1993 Equation The part of whole body dose due to gamma radiation from. noble gases released in gaseous effluents is calculated by the follow-ing expression:
Dwb = (0.7)(1.ll)(3.17E-8)
(A-6) iiv+DAI ig )
I E{ S Ais+
A i
The summation is over noble gas radionuclides i.
Whole Body Dose
[ mrem]
Dwb Dose to the whole body due to gamma radiation from noble gas radionuclides released in gaseous effluents.
0.7 Shielding Factor Dimensionless factor which accounts for shielding due to occupancy of structures.
1.11 Conversion Constant (mrem / mrad)
Converts rads in air to rems in tissue.
3.17E-8 Conversion Constant
[yr/sec]
Converts seconds to years.
5,V,di Gamma Whole Body Dose Factor
[(mrad /yr)/
1 i
(pCi/sec)]
Gamma whole body dose rate at a specified location per unit of radioactivity release rate for radionuclide i released from a stack, vent, or ground level release point.
A-9 e
,w v
REVISION 0.K JANUARY 1993 The attenuation of gamma radiation due to pasaggethrough5cmofbodytissueof1 g/cm -density is taken into account in calculating this quantity.
See Section 4.2.1.3, Section B.6 of-Appendix B, and Table F-7 of Appendix F.
Cumulative Radionuclide Release
[pCi]
Ais, Aiy, Aig Defined in Section A.l.2.1.
Application The standard Technical Specifications require calculation of whole body dose due to airborne effluents'only in connection with assessment of compliance with 40 CFR 190.
Because of the low dose limits associated with 10 CFR 50, stations are not-required to assess compliance with 40 CFR 190 unless a 10 CFR 50 limit is exceeded by a specified amount (see Section A.3).
When 40 CFR 190 assessments are made, whole body doses due to other sources (e.g.,
inhalation, ingestion, ground radiation and direct radiation from contained sources) must also be considered.
See'Section A.3.1 for further discussion.
A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose.
However, this component is evaluated for reference as there-is a skin dose guideline contained in 10CFR50, Appendix I.-
In tha unlikely eve : where the beta air dose guideline is exceeded, the skin dota will require evaluation.
l l
A-10
REVISION 0.K JANUARY 1993 K
Application The skin dose is calculated for reference only.
A.l.3 Dose Rate Due to Noble Gas Radionuclides A.l.3.1 Whole Body Dose Rate Requirement Standard Technical Specifications (References 2 and 3) limit the whole body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem /yr at all times (see Specification 3.11.2.1).
This provision is related to the requirements of 10 CFR 20.105 and 20.106.
Section 12.4 of each station's RETS contain a somewhat similar provision.
A-12
REVISION 0.K JANUARY 1993=
l Equation l
1 The whole body dose rate due to noble gases released in gaseous effluents is calculated by the following expression:
wb " (1 ll)UI 5 0 s + V Q v + C Q g )
(A-8)
D 11 ii ii The summation is over noble gas radionuclides i,-
b Whole Body Dose Rate
[ mrem /yr) wb Dose rate to the whole body due to gamma radiation from noble gas radionuclides released in gaseous effluents.
Q s, Q v, Q g Release Rate
[pCi/sec]
i i
i Measured release rate of radionuclide i from a stack, vent, or ground level release point.
The remaining parameters have the same definitions'as used in the equation for whole body dose in Section A.1.2.3.
Application Standard Technical Specifications (References 2 and 3) require:
the dose rate due to noble gases-in gaseous effluents to be determined to be within the above limit.in accordance with methodology specified in the ODCM (see Specification
~
l 4.11.2.1.1).
The Section 12.4 of-each station's RETS contain a somewhat similar provision.
i 1
A-13
? REVISION 0.Kf
- JANUARY 1993:
ToLcomply with:this specification,neachistation1useslan1 effluent-radiation'monitorLsetpointLeorresponding to an'offsite whole body _doseJrate'at ortbelow the.limiti(see-Chapterfl0).
In addition, each! station: assesses' compliance by) calculating offsite'whole body dose. rate on the basis of samples obtsined
~
periodically.in accordance with station' procedures.
A.1.3.2 Skin Dose Rate-
. Requirement Standard Technical. Specifications (References 2 and 3) limit the skin dose rate due to noble gases in gaseous effluents released from-a site to areas at and:beyond;the site boundary to~1ess than or equal to 3000 mrem /yr at allitimes_(see Specificationi3.11.2.1).
ThisLprovision;is related'to requirements.of 10LCFR 20.105 and 20.106.
Section 12.4Jof each. station's RETS contain a somewhat similar-provision.-
.i l
I A-14 lL c
, -. _..... _. ~. _.,
REVISION oak JANUARY-1993.
The remaining parameters have the same definitions as used in the equation for skin dose in Section A.l.2.4.
Application Standard Technical Specifications (References 2 and 3) require:
the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM (see Specifiestion 4.11.2.1.1).
Section 12.4 of each station's RETS contain a somewhat similar provision.
To comply with this specification, each station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10).
In addi-tion, each station assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with station procedures.
l l
~
A-16
REVISIO] 0.K JANUARY 1993 A.1.4 1}ose Due to Non-Noble-Gas Radionuclides-Requirement Standard Technical Specifications (References 2 and 3) provide-the following limits on the dose to a member of the public from specified non-noble-gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the site boundary (see Specification 3.11.2.3):
Less than or equal to 7.5 mrem to any organ during any calendar quarter.
Less than or equal to 15 mrem to any organ during any calendar year.
This provision is related to one of the design objectives of 10 CFR 50, Appendix I.
Section 12.4 of each station's RETS contain a somewhat similar provision.
l' l
l
~
l-A-17 l
l-
REVISION 0.K-JANUARY-1993 In the standard specification (References 2 and 3) and-the specifications of all stations except-LaSalle and-Zion, the-specified non-noble-gas radionuclides are o
Iodine-133.
All radionuclides in particulate form with half-lives greater than 8 days.
For LaSalle and Zion, the specified radionuclides are:
e 'Radioiodines with half-lives greater than 8 days.
Radioactive materials in particulate form with e
half-lives greater than 8 days.
Radionuclides, other than noble gases, with half-lives-greater tnan 8 days.
This section provides expressions used to calculate dose to an organ due to non-noble-gas radionuclides released in gaseous effluents.
The following organs are considered:
Total body.
Bone.
e Liver.
e Thyroid.
Kidney.
Lung.
GI-LLI (gastrointestinal tract and lower large intestine).
A-18 4
REVISION 0.K JANUARY 1993-Equation The dose calculated includes dose commitment (see Section 4.1.1) incurred due to releases in the time period under con-sideration.
Specifically, dose is calculated as the sum of three -contributions:
i f
ja = Dgnd$ + D nhalja + D oodja (A-13)
NNG D
NNG Dose Due to Non-Noble-Gas
[ mrem]
D ja Radionuclides Sum of the dose and dose commitment to organ j of an individual of age group a due to non-noble-gas radionuclides released in gaseous effluents during a specified time period.
Dgnd Ground Deposition Dose
[ mrem]
Dose to organ j due to ground deposition of non-noble-gas radionuclides released in gaseous effluents.
See Equation A-14 in Section A.l.4.1.
D nhal Inhalation Dose
[ mrem]
i ja Dose commitment to organ j of.an individual of age group a due to inhalation of non-noble-gas radionuclides released in gaseous effluents.
See Equation A-17 in Section A.l.4.2.
f00d Food Pathways Dose
[ mrem]
D ja Dose commitment due to ingestion via food pathways (leafy vegetables, produce, milk, and meat) of non-noble-gas radionuclides released in gaseous effluents.
See Equation A-18 in Section A.l.4.3.
Application Standard Technical Specifications (References 2 and 3) require cumulative dose contributions for the current calendar quar _er and the current calendar year for the specified.non-noble-gas radionuclidesxin airborne effluents to be determined at least l
~
A-19
REVISION 0.K
-JANUARY-1993-once per.31 days (s6e_ Specification 4.11.2.3).
Section-12.4 of each station's RETS contain a somewhat similar provision.
l To comply with this specification, each station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its Technical Specifications.
For each organ of each age group considered, the dose for each pathway is calculated in every sector (except Zion sectors over Lake Michigan)'.
The calculation is based on the location assumptions discussed j
below in conjunction with the pathway equation's.- For each i
organ of each age group, the doses are summed in each sector i
over all pathways (ground, inhalation, and four food.
pathways).
The result for the sector wit'h the highest total dose is compared to the limit.
For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.
The allocation procedure'is specified in Chapter 10 of this manual.
A-20
REVISION 0.K JANUARY.1993-A.l.4.2 Inhalation The dose commitment due to inhalation is claculated by the following expression:
i (A~17)
D nhalja = (3.17E-8)(lE6)(R )
a x I{ DFA jal(X/0)s 'is + (X/0)vA'iv h
i
+ (X/Q)gA'ig) )
The summation is over non-noble-gas radionuclides i.
D nhal Inhalation Dose Commitment
[ mrem]
i ja Dose commitment to organ j of an individual in age group a due to inhalation of non-noble-gas radionuclides released in gaseous effluents.
3.17E-8 Conversion Constant
[ yrs /sec]
Converts seconds to years.
lE6 Conversion Constant
[pCi/pCi]
Converts pCi to pCi. -
3 i
[m /yr]
R Individual Air Intake Rate' a
Air intake rate for individuals in age group a.
See Table D-7 Appendix D.
Inhalation Dose Commitment Factor
[ mrem /pCi]
DFA ja i
Dose commitment to organ j of an individual in age group a per unit of activity of radionuclide i inhaled.
See Tables D-1 through D-3 Appendix.D.
3 (X/Q)3, Relative Effluent Concentration
[sec/m )
(X/Q)y, (X/Q)g Radioactivity concentration at a specified location per unit of radioactivity release rate.
See Section 4.1.6, Section B.3 of Appendix B, and Table F-1 of Appendix F.
~
A-23
REVISION ~0.K JANUARY 1993 DFA ja Ingestion Dose Commitment Factor
[ mrem /pCi]-
i Dose commitment to organ j of an individual in, age group a per unit of activity of. radio-nuclide i ingested.
Seo Tables D-4, D-4a,.
D-4b and D-5 of Appendix D.
iVia'iP Rate of Ingestion of Activity
[pC1/yr]
Activity of radionuchide i ingested. annually iMia*1 la by an individual in age group a from, respec-tively, the following:
e Leafy vegetables.
e Produce (nonleafy vegetables, fruits, and grain),
o Milk.
e Meat (flesh).
Calculated as follows:
V (g_19)
V C i tV
=U f
a V
P P
iP
=U fp C i (A-20) a M
M iMia = U a Ci (A-21)
F fFia " U a. C i (g_22)
V U
Food Product Consump-
[kg/yr]
a tion Rate UP
[kg/yr]
a M
[L/yr]
U a
UF
[kg/yr]
a Annual consumption (usage) rate of leafy vegetables, produce, milk, or meat, respectively, for individuals in age group a.
See. Table D-7 of Appendix D.
fy Food Product Affected Fraction fp Fraction of ingested leafy vegetables (V)-or produce (P) grown in the garden of interest.
See Table D-6 of Appendix D.
L A-25 l
l
.~
REVISIOJ 0.K
' JANUARY 1993 V
C i Food Product Radic2ctivity
[pCi/kg).
Concentration
[pCi/kg]
i
[pCi/L).
i
[pCi/kg]
C i P
C i and C i represent, respectively, the average concentration of radionuclide i in leafy vegetables.and produce grown in the garden of interest.
Calculated from the amount of radioactivity released and the relative deposition factor D/Q at the-gar 6en of interest.-
SeeSegtionA.g.4.3.1below for the equation.
i and C.i represent, respectively, the average concentration of radionuclide i in milk'and meat from the producer of interest.
Calculated from the amount of radioactivity released and the relative deposition factor D/Q at the locations of the producers of interest.
See Sections A.l.4.3.2 and A.1.4.3.3 below for equations.
Application The dose due to ingestion of leafy vegetaties and produce is calculated in each sector for a hypothetical garden assumed to be located at the location of highest offsite D/Q (see Table F-5 of Appendix F).
The dose due to ingestion of milk and meat is calculated in each sector for the location of'the nearest producer as specified in Table F-6 of Appendix F.
If there is no actual milk or meat producer.within'5 miles of the station, one is assumed to be located at 5 miles (except that no food pathway calculations are made for, Zion sectors in which'the offsite regions near the station are over Lake Michigan).
A.1.4.3.1 Vegetation Y ), pro-The radioactivity concentration in leafy vegetables (C i
P ), or other vegetation is calculated by the following duce (C i
expression:
A-26
REVISIOJ 0.K JANUARY 1993-C _= [(d )(r)/(Y )(AEi)]
(A-23) i i
y
[exp(l t )3(f )
Ei e)]
x.[1 - exp(-l t
ih f
Ci Food product Radioactivity
[pCi/kg]
Concentration Average concentration lof radionuclide i in leafy vegetables, produce, or other-vegetation.
2 Deposition Rate
[(pCi/hr)/m )
di Rate at which radionuclide i is deposited onto the ground.
Calculated from the amount of radioactivity released and the relative deposition factor D/Q at the location of interest.
See Section A.l.4.1 for an equa-tion.
See the Subsection " Application" in Section A.1.4.3 for the location assumptions used in determining d.
i r
Vegetation Retention Factor Fraction of deposited activity = retained on vegetation.
See Table D-6 of Appendix-D.
2 Y
Agricultural productivity
-[kg/m ]
y Yield The quantity of vegetation produced per unit area of the land on which the vegetation is grown.
1Ei Effective Decay Constant
[hr-1]
Effective removal rate constant for radio-nuclide i from vegetation:
(A-24) 1Ei " Ai+Aw li Radiological Decay Constant
[hr-1]
Radiological decay constant for radionuclide i.
See Table D-12 of Appendix D.
l Weathering Decay Constant
[hr-1]-
y Removal constant for physical loss by weathering.
See-Table D-6 of Appendix D.
A-27 v --
REVISION 0.K JANUARY 1993 t
Effectiva Veg;taticn
[hr]
g Exposure Time Time that vegetation is exposed'to.
contamination during the growing season.
See Table D-6 of Appendix D.
Harvest to Consumption
[hr) t3 Time Time between harvest and consumption.-
See Table D-6 of Appendix D.
fg Seasonal Growing Factor Factor which accounts for the seasonal growth of vegetation.
It has-the value 1 during the growing season, O otherwise.
See Table D-6 of Appendix D.
A.l.4.3.2 Milk The radioactivity concentration in milk is calculated by the following expressions:
i Wg exp(-A tg)
(A-25)
C i = Fg 'Cf M
i f
S 8
C i =f f
C91 + (1 - f')C i + fa(1 - f )C 1 (A-26)'
a g
a g
M Milk Radioactivity Concentration
[pCi/L] _
C i Average concentration of radionuclide i in milk from the producer of. interest.
Milk Fraction
[ days /L].
FM Fraction of an animal's daily intake of radionuclide i which appears.in each liter of milk (PCi/L in milk per pCi/ day.
ingested by the animal).
See Table D-8 of Appendix D.
Cf Feed Concentration
-[pCi/kg) i Average concentration of radionuclide i in animal feed.
h l
L A-28
REVISICOLO.K; JANUARY 1993'
_ kg/ day]!
(
-Wg
-Feed Consumption Amount of1 feed consumed by the animal each day.
See Table D-6 of-Appendix D.
1 Radiological Decay' Constant
[hr-1) 1 Radiological' decay-constant for. radio-nuclide i.
See. Table _D-12 of Appendix D.
tM-Milk Transport Time
[hr)
Average time-from the production;of milk to-its consumption.-
See Table.
D-6 of Appendix D.
f, Pasture Time-Fraction Fraction-of time'that animals graze on pasture.
See Table D-6 of Appendix D.
f Pasture Grass Fraction g
Fraction of daily feed that is pasture grass when animals-graze.on pasture.
See Table D-6 of Appendix D.
C9 pasture Grass Concentration
- (PCi/kg] -
1 Concentration of radionuclide i-in pasture __
grass.
Calculated.using Equation A-23 with the seasonal growing ~ factor ff = 1 and with parameter' values specified for the pasture grass and milk _ pathways-in Table D-6 of Appendix D.
Stored Feed Concentration'
-[pCi/kg]
Csi Concentration-of radionuclide:i;in stored:
feed.. Calculated using EquationLA-23'for-C -with the_ seasonal growing factorJff.=1-iand parameter values specified for the stored feed and milk pathways in Table-D-6'of Appendix-D.=
s LA.l.4.3.3 Meat The radioactivity concentration-in meat:is calculated by the following. expression:
f i, pF C i Wg exp(-l t )
(A-27)
CF is L
L A-29
~
~,..
REVISION 0.K JANUARY 1993 CF Meat Radioactivity Concentration
[pCi/kg) i Average concentration of radionuclide i in meat from the producer of interest.
Fy Meat Fraction
[ days /kg)
Fraction of an animal's daily intake of radionuclide i which-appears in each kilo gram of flesh (pCi/kg in meat per pCi/ day ingested by the animal).
See Table D-8 of Appendix D.
Cf Feed Concentration
[pCi/kg) i Average concentration of radionuclide i in animal fe Calculated using the equationforCgd.i in the preceding sub-section with parameter values specified for the meat pathway in Table D-6 of Appendix D.
Feed Consumption
[kg/ day)
Wf Amount of feed consumed by the animal each day.
See Table D-6 of Appendix D.
Radiological Decay Constant
[hr-1]
11 Radiological decay constant.for radio-nuclide i.
See Table D-12 of Appendix D.
t Slaughter to Consumption Time
[hr]
s Time from slaughter to consumption.
See Table D-6 of Appendix D.
A.l.5 Dose Rate Due to Non-Noble-Gas Radionuclides Requirement Standard Technical Specifications (References 2~and 3) limit the dose rate to any organ due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 1500 mrem /yr (see Specification 3.11.2.1)~.
This provision is related to the requirements of 10 CFR 20.105 and 20.106.
The Bases section of-the Standard Technical Specifications states that it restricts the thyroid dose rate to a child via the inhalation pathway to 1500 mrem /yr.
A-30
REVISION 0.K JANUARY 1993:
Section 12.4 of aach station's RETS contain somewhat similar provisions.
In accordance with the guidance in the Bases section of their I
RETS, all stations consider the child to be the receptor in calculating dose commitment to the thyroid due to inhalation of non-noble-gas radionuclides in gaseous effluents.
Each station calculates doses for all members of the public then determines the maximum dose.
The member of the public who' receives the maximum dose will be reported.
In the standard specifications and the RETS of all stations except LaSalle'and Zion, the specified non-noble-gas radionuclides are Iodine-131.
Iodine-133.
All radionuclides in particulate form with half-lives greater than 8 days.
For Zion, the specified. radionuclides are as above except that tritium is omitted.
~
A-31 e-W v
REVISION 0,K JANUARY 1993 For LaSalle, the specified radionuclides are Radioiodines with half-lives greater than 8 days.
Radioactive materials in particulate form with i
half-lives greater than 8 days.
l Radionuclides, other than noble gases, with half-lives e
greater than 8 days.
Equation The dose rate to a child thyroid due to inhalation is calcu-lated by the following expression:
ib nhalja = (lE6)(R )E( DFA ja[(X/Q)s0'is (A-28) a i
(X/Q)gQ'ig) }
+ (X/Q)yQ'iy
+
The summation is over non-noble-gas radionuclides i.
b nhal Inhalation Dose Rate
[ mrem /yr]
i ja Rate of dose commitment to organ j of'an individual in age group a due to inhalation of non-noble-gas radionuclides released in gaseous effluents; j and a are chosen-to correspond to a child thyroid.
Q'is.
Radionuclide Release Rate,
[pCi/sec)
Q'iv.
Adjusted for Radiodecay O'ig Measured release. rate of radionuclide i from a stack, vent, or ground level release point, reduced to account for radio-decay in transit from the release point to the dose point.
See Section A.l.3.2.
The other parameters are defined in Section A.l.4.2.
A-32 t
REVISION 0.K JANUARY 1993 Application Standard Technical Specifications (References 2 and 3) require the dose rate due to non-noble-gas radioactive materials in air-borne effluents to be determined to be within the above limit in accordance with a sampling and analysis program specified in the Technical Specifications (see Specification 4.11.2.1.2)._
Section 12.4 of each station's RETS contain a somewhat similar provision.
To comply with this specification, each station obtains and analyzes samples in accordance with the sampling and analysis program in its RETS.
The child thyroid dose rate due to inhalation is calculated in each sector at the location of the highest offsite X/Q.
The result for the sector with the highest child thyroid inhalation dose rate is compared to the limit.
A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement Standard Technical Specifications for a pressurized water reactor (References 2 and 3) require that the ventilation exhaust l
l l
l A-33
REVISIO~.1 0.K JANUARY 1993 treatment system and the waste gas holdup system be used when projected offsite doses in 31' days due to gaseous effluent releases, from each reactor unit, exceed any of the following limits (see Specification 3.11.2.4):
0.2 miad to air from gamma radiation.
0.4 mrad to air from beta radiation.
0.3 mrad to any organ of a member of th.e public.
e This provision is related to the requirements of 10 CFR 50, Appendix I.
4 The RETS of some stations contain a somewhat similar provision.
For exact requirements, see the following sections:
Braidwood 1/2:
12.4.4 e
Byron 1/2:
12.4.4 La Salle 1/2:
12.4.5 These stations are required to project doses due to gaseous releases from the site et least once per 31 days.
In addition, Dresden 2.3 and Quad Cities 1/2 are required to operate the off-gas treatment system at certain times.
In conjunction with this requirement, Dresden and Quad Cities-are c
required to project offsite doses due to gases treated by the off-gas treatment system at least once per 31 days (see Dresden and Quad Cities Section 12.4.4).
A-34 m-
_____-_______.m._.a.-___2--._
_-_m._m__-
-___m.__
_ _ _ _ _ _ _ - _ _ -. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. ~. - _
m.___
REVISION 0.K JANUARY 1993 Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2, and A-13.
Projected cumulative radionuclide releases are used in place of measured cumulative releases Als' Alv, and Aig.
Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an indivi-dual unit is obtained by proportioning the effluents among the units sharing the system.
The allocation procedure is speci-fled in Chapter 10 of this nianual.
A.2 LIQUID RELEASES (10 CFR 20 AND 10 CFR 50, APPENDIX I)
A.2.1 Dose Requirement Standard Technica? Specificationa (References 2 and 3) provide the following limits on the done or dose commitment to a member of the public from radioactive materials in liquid effluents areas (see released from each reactor unit to unrestrit Specification 3.11.1.2):
During any calendar quarter, less than or equal to 1.5 mrem to the whole body and less than or equal to 5 mrem to any organ.
During any calendar year, less than or equal to 3 mrem to the whole body and less than or equal to 10 mrem to any organ.
This provision is related'to one of the design Objectives of 10 CFR 50, Appendix I.
A-35
~~
. ~,
e
REVISICN 0.X JANUARY 1993 Section 12.3 of each station's RETS contain a somewhat similar provision.
i Equation The dose commitment from radioactive materials in liquid offlu-
)
ents is calculated for all age groups.
The dono commitment is obtal.ied as the sum of contributions from consumption of drinking water and fish:
fish),
(A-29)
D119
= Dwater 4 D 33 ja Dwaterja= (1 lE-3)(8760)(U M /F")
(A-30)
W W x E{ A DFI jaexp(-X tW))
i i
i ff f
fi8hja - (1.1E-3)(8760)(U M /F )
(A-31)
D El A B DFl jnexp(-l tf))
ii i
i Z
The summations are over index i (radionuclides).
D119 Dose Commitment Due to Radioactivity
[ mrem) ja in Liquid Effluents Dose commitment to organ j of age group a consuming water and fish containing radio-activity released in liquid effluents.
~
A-36 t
REVISION 0.K JANUARY 1993 Dwator Dose Commitment Due to Con:umption
[trem) ja of Drinking Water Dose cohditment to organ j of age group a consuming water containing radio-activity released in liquid effluents.
fish),
Dose Commitment Due to Consumption
[ mrem)
D of Fish Dose commitment to organ j of age group a consuming fish containing radioactivity released in liquid effluents.
Usage Factor
[L/hr, kg/hr)
D ' U, a
W f
Consumption rate of water (U ) or fish (U ).
a See Table D-7 of Appendix D.a W
f Dilution Factor 1/M, 1/M Measure of dilution. prior to withdrawal of potable water or fish.
See Table F-1 of Appendix F.
F Average Flow Rate (cfs)
W Average flow rate of receiving body of water at point where potable water is taken.
Seo Table F-1 of Appendix F.
f Near-Field Flow Rates
-[cfs)
F Near-field flow rate of receiving body of water (in region where fish are taken)..
See Table F-1 of Appendix F.
Radionuclide Release (pCi)
Ai Measured amount of radionuclide i released in liquid effluents during the time period under construction.
DFI ja Ingestion Dose Factor (mrem /pCi]
i Dose commitment to organ j.of an individual in age group a per unit of activity of radionuclido i ingested.
See Table D-4, D-4a, D-4b, D-5 of Appendix D.
11 Decay Constant (hr-1)-
Radiological decay constant-of radionuclide i.- See Table D-12 of Appendix D.
~
A-37 t
e-2-m
REVISION 0.X JANUARY 1993 t", tf Elapsed Time
[hr)
Average elapsed time between release and i
consumption of potable water or fish.
See Table F-1 of Appendix F.
Bioaccumulation Factor
[L/kg)
Di Equilibrium ratio of the concentration of radionuclide i in fish (pci/kg) to its i
concentration in water (PCi/L).
See Table D-13 of Appendix D.
1.lE-3 Conversion Constant
[(pCi/ liter) per (pCi/yr)/(cfs))
Factor to convert to pCi/ liter from (pC1/yr)/(cfs).
8760 Conversion Constant
[hr/yr)
Number of hours per year.
Application Standard Technical Specifications (References 2 and 3) require determination of cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days (see Specification 4.11.1.2).
Section 12.3 of each station's RETS contain a somewhat similar provision.
For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.
The allocation procedure.
is specified in Chester 10 of this manual.
A-38
REVISION 0.K JANUARY 1993 A.2.2 Maximum Permissible Concentration Requirement Standard Technical Specifications (References 2 and 3) provide that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited as follows (see Specification 3.11.1.1):
For radionuclides other than dissolved or entrained noble gases, to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases, to 2E-4 pCi/mL total activity.
This provision is related to the requirements of 10 CFR 20.106.
Section 12.3 of each station's RETS contain a somewhat similar provision.
For the concentration of dissolved or entrained noble gases, the RETS of Braidwood and Byron specify the same limit (2E-4 pCi/mL) as the standard Technical Specifications.
The RETS of the remaining stations specify different values (see Table D-ll of Appendix D).
The limit for the concentration of a radionuclide in liquid released to the unrestricted area is called its maximum permissible concentration (MPC).
l 1
A-39
't w
e
JANUARY 1993 Application Standard Technical Specifications (References 2 and 3) require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits (see Specifications 4.11.1.1.1 and 4.11.1.1.2).
Section 12.3 of each station's RETS contain a somewhat similar provision.
To comply with this provision, each station obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS.
Radioactivity concentrations in tank effluents are determined in accordance with Equation A-33 in the next section.
Comparison with the MpC limit is made using Equation A-32.
A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g.,
a radwaste discherge tank),
the concentration of a radionuclide in the offluent is calculated as follows:
t d
pr)
(A-33) ci = (C g)(pr)f(p A-41
REVISICN 0.K JANUARY 1993 Concentraticn in Liquid Efflu:nt (pCi/mL)
Ci to the Unrestricted Arca Concentration of radionuclide i in liquid released to the unrestricted area.
Ct Concentration in the Discharge Tank (pCi/mL) i Measured concentration of radionuclide i in the discharge tank.
F Flow Rate, Tank Discharge (cfs) f I
J Measured flow rate of liquid from the discharge tank to the initial dilution stream.
F Flow Rato, Initial Dilution (cfs) d Measured flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary (e.g.,
circulating cooling water or blowdown from a cooling tower or lake).
A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, standard Technical Specifications (References 2 and 3) limit the quantity of radio-activity which may be stored in unprotected outdoor tanks (see Specification 3.11.1.4).
Unprotected tanks-are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and sur-rounding area drains connected to the liquid radwaste treatment system.
The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations would be less than the limits of 10 CFR 20, Appendix B, Table II, Column 2 at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
A-42 n._-
REVISION 0.K JANUARY 1993 A.2.5 Operability and Use of the Liquid Radwaste Treatment j
System Requirement j
Standard Technical Specifications (References 2 and 3) require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radio-i activity when projected doses due to the liquid effluent from each reactor unit to unrestricted areas exceed either of the following (see Specification 3.11.1.3):
0.06 mrem to the whole body in a 31 day period.
t 0.2 mrem to any organ in a 31 day period.
This provision is related to requirements of 10 CFR 50, Appendix I.
Section 12.3 of each station's RETS contain a somewhat similar provision.
Each station except Zion is required to project doses due to liquid releases at least once per 31 days.
Zion is required to project doses due to liquid releases at least once per month.
Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-29.
Projected radionuclide releases are used in place of measured releases A.
1 l
l l
A-44
~
l 1
REVISION 0.K JANUARY 1993 A.2.6 Drinking Water Five stations (Braidwood, Dresden, LaSalle, Quad Cities, and Zion) have requirements for calculation of drinking water dose that are related to 40 CFR 141, the Environmental Protection Agency National Primary Drinking Water Regulations.
These are discussed in Section A.4.
A.2.7 Non-routine liquid release pathways a
cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material.
are non-routine and will be treated on a case specific basis if and when they occur.
Since each station'has sufficent capacity to delay a liquid relaese for reasonable periods of time, it is' expected that planned releases will not take place under these circumstances.
Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways.
A.3 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (40 CFR 190)
Requirement Standard Technical Specifications (References 2 andL3) limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following (see Specification 3.11.4):
Less than or equal to 25 mrem to the whole body, Less_than or equal to 25 mrem to'any organ except the thyroid.
Less than or equal to 75 mrem to the thyroid._
~
A-45
.n t
REVISION 0.[K-APRIL 1991
,TANUAq l993 This' provision implements a' requirement of 40 CFR 190.
Each station's RETS contain a somewhat similar. provision.. For_
exact requirements, see the following sections:
e Braidwood 1/2:
12.4 e
Byron 1/2:
12.4 e
LaSalle 1/2:
12.4 e
Dresden 1:
12.4 o
Dresden 2/3:
12.3 and 12.4 e -Quad-Cities 1/2:
12.3-and 12.4 e
Zion :1/2:
12.3-and 12.4
-i e
l t
j<
P A-45a l
l.
e
f.
- . w.;
w e
.e
,,m-m:-
4
-+-w sr
,tv ve g w, e-=
g--'t-g
-4rr-g-
3'-H m, r--6 v
+=w g
y w
REVISION 0.K JANUARY 1993 When Compliance Assessment is Required.
In both the standard Technical Specifications and the RETS of each station, calculations of total dose are required only when calculated doses from releases exceed certain levels.
In the standard Technical Specifications (References 2 and 3), these levels are twice the following limits:
Tne RETS limits on dose or dose commitment due to radio-active materials in liquid effluents from each reactor unit (1.5 mrem to the whole body or 5 mrem to any organ during any calendar quarter; 3 mrem to the whole body or 10 mrem to any organ during any calendar year).
The RETS limits on air dose in noble gasea released in gaseous effluents from each reactor unit (5 mrad for gamma radiation or 10 mrad for beta radiation during any calendar quarter; 10 mrad for gamma radiation or 20 mrad for beta radiation during any calendar year).
The RETS limits on dose due to iodine-131, iodine-133, e
tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.
released from each reactor unit (7.5 mrem to any organ during any calendar quarter; 15 mrem to any organ during any calendar year).
There are similar criteria for the stations.
See the station RETS for exact requirements.
Comparison with 10 CFR 50, Appendix I.
The differences between the dose limits in 40 CFR 190 and those in 10 CFR 50, Appendix I include the fol, lowing:
10 CFR 50, Appendix I deals only with radiation due to radioactivity released beyond the boundary of a site.
A-47 i
p.er*
r i
i s, qd
REVISICN 0.K
' JANUARY 1993 Deff Dose to Organ j.Due to Radiation (mrem]
j from Gaseous and Liquid; Effluents I
Sum of dose-and dose' commitment to organ j due to_ release of radioactive materials in gaseous and-liquid
+
effluents from the station.
Drad Dose to Organ j due to Noneffluent
[ mrem]
j Sources of Radiation o
Dose to Organ j due to noneffluent sources of radiation associated with the station (see Section A.3,.2).
Doth Dose to Organ j Due.to Radiation.
(mrem]
j from Other Operations Sum of dose and dose commitment to organ j of any member of the public.in the vicinity of the station due to operations of the uranium fuel cycle other than those of the station.
Application
~
When dose due to the uranium fuel cycle is required, an initial dose estimate is obtained using Equation A-34 astfollows:
For a' member of the public in each sector, thezdose (including cose commitment).due to all-effluent-pathways (ai.: borne and;11guid) is obtained for each organ (whole body, skin, thyroid, etc.)-(see Section, A.3.1).
To this number is added the~ maximum dose to'thatjorgan e
due to confined sources of radiation (see:Secti'on A.3.2) and the-dose to that organiin thatl sector:due to-other sources of the uranium. fuel cycle'(see Section-A.3.3).
For each target' organ, the doses due to:all pathways:
are summed to yield'a total ~ dose'in each' sector.
For each. target organ, the maximum.of the 16; sector:
e values is-determined, and'thisimaximum:is compared withL
~
-the 40 CFR.190 limit..
If the initial dose' estimate exceeds the 40 CFR 190J11mit,.the, assumptions involved are: examined intaccordance'with the
}
A-49' o
..e,.
...w.,
e u-.y.
.-y,
.-7
--my 3m.
REVISION 0.K JANUARY 1993 guidelines in Reference 46, and, if necessary, the calculation is revised.
A.3.1 Initial Estimate of Dose Due to Effluents from a Station Radiation dose and dose commitment due to radioactivity in gaseous and liquid effluents are evaluated using the equations given in Sections A.1 and A.2.
For each receptor (member of public), the sum of dose and dose commitment to*each organ is obtained in each sector by summing the contributions from all applicable pathways.
Assumptions for various pathways are as described below.
Whole body dose is obtained in each sector as the sum of the following:
Whole body dose due to gamma radiation from noble gases in the plume for a receptor located at the site boundary in the sector (see Equation A-6 and Table F-7 of Appendix F).
Whole body dose due to ground deposition for receptor at the point of maximum offsite D/O in the sector (see Equation A-14 and Table F-5 of Appendix F).
Whole body dose commitment due to inhalation of airborne effluents at the point of maximum offsite X/O in the sector (see Equation A-17 and Table F-5 of Appendix F).
Whole body dose commitment due to ingestion of leafy vegetables and produce from a hypothetical garden located at the point of maximum offsite D/Q in the sector (see Equation A-18 and Table F-5 of Appendix F).
Whole body dose commitment due to consumption of_ milk fram the nearest milk producer in the sector (see Equation A-18 and Table F-6 of Appendix F).
Whole body dose commitment due to consumption of meat from the nearest meat producer in the sector (see Equation A-18 and Table F-6 of Appendix F).
For the Braidwood and Zion sites, whole body dose commitment due to consumption of drinking water from the community water supplies nearest the stations A-50
, - - -, - - ~,,
g w
-n-r-,-,,
- r r
REVISION OcK JANUARY 1993 (see Equation A-30).
This pathway is not considered for the other four nuclear stations because their nearest downstream community water supply locations are so fcr distant that it is unlikely that a nearest resident to a station would be regularly consuming water containing radioactivity from station effluents.
Whole body dose commitment due to consumption of fish from the "near-field" location (see Equation A-31).
The organ dose is obtained in each sector as the sum of the following:
Organ dose due to the gamma radiation from plume for a receptor located at the site boundary in the sector.
The organ dose is assumed equal to the whole body dose (see Equation A-6 and Table F-7 of Appendix F).
Organ dose due to ground deposition for a receptor at the point of maximum offsite D/O in the sector (see Table F-5 of Appendix F).
The organ dose is assumed equal to the whole body dose (see Equation A-14).
Organ dose commitment due to inhalation of airborne offluents at the point of maximum offsite X/Q in the sector (see Equation A-17 and Table F-5 of Appendix F).
Organ dose commitment due to ingestion of leafy vegeta-bles and produce from a hypothetical garden located at the point of maximum offsite D/Q in the sector (see Equation A-18 and Table F-5 of Appendix F).
Organ dose commitment due to consumption of milk from the nearest milk producer in the sector (see Equation A-18 and Table F-6 of Appendix F).
Organ dose commitment due to consumption of meat from the nearest meat producer in the sector (see Equation A-18 and Table F-6 of Appendix F).
For the Zion site, organ dose commitment due to consump-tion of drinking water (see Equation A-30).
This path-way is not considered for other nuclear stations because their nearest downstream community water supply locations are so far distant that it is unlikely that a nearest resident to a station would be regularly consum-ing water containing radioactivity from station effluents.
Organ dose commitment due to consumption of fish from the "near-field" location (see Equation A-31).
A-51 m
o
REVISION 0.K JANUARY 1993 A.3.2 Dose Due to Contained Sources There are presently two " contained" sources of radioactivity which are of concern in offaite radiological dose assessments.
The first source is due to gamma rays from nitrogen-16 carried over to the turbine in BWR steam.
The second source is due to
[
gamma rays associated with radioactive material resident in onsite radwaste storage facilities.
Gamma radiation from these sources contributes to the whole body dose.
A.3.2.1 BWR Skyshine The contained onsite radioactivity source which results in the most significant offsite radiation levels at nuclear power stations is skyshine due to nitrogen-16 (N-16) in turbines and steamlines at boiling water reactors (BWRs).
The N-16 that gives rise to BWR skyshine is produced by neutron activation of 0-16 (oxygen-16) in reactor coolant as the coolant passes through the core.
The N-16 travels with steam to the turbine while decaying with a half-life of about 7 seconds and producing 6MeV to 7MeV gamma rays.
Typically, offsite dose points are shielded from a direct view of components containing N-16, but there can be skyshine radiation at offsite locations due to scattering of gamma rays off the I
mass of air above the steamlines and turbine (see Figure A-1).
The offsite dose rate due to skyshine has been found to depend on several factors:
The dose rate decreases as distance from the-station increases.
The dose rate increases non-linearly as the level of power being generated increases.
The dose rate increases if a nuclear power station adds hydrogen to its reactor coolant, an action sometimes taken in order to improve coolant chemistry (see Reference 39).
A-52
.. _ -. = _ _
- REVISION 0.K JANUARY'1993 l)
To calculate offsite dose in a given time period due to l
skyshine, a nuclear power station must keep track of the following:
The total gross energy Eh produced with hydrogen being added.
The total gross energy Eo produced without hydrogen-being added.
s The turbines at BWR sites are sufficiently close to each other that energy generated by the two units at each site may.-be summed.
An initial estimate of BWR skyshine dose is calculated per the following equation:
n + M E ) x E( OF SF erp(-0.007R ))
(A-35)
Daky (K) (E hh k
k k
=
j This equation applies for each organ J.
The summation is over all locations k occupied by a hypothetical maximally' exposed member of the public characterized by the parameters specified in Table F-8.
The parameters in Equation A-35 are defined as-follows:
Dsky Dose Due to,N-16 Skyshine
[ mrem]
j Gamma dose to organ j due to BWR N-16 i
skyshine for the time period of interest.
The dose is assumed to be the same for all organs and;the whole body.
~
A-53 t
- v-y w w--
-v
<ge e *m e.-tw e --
"*r---
e
-*me-r-*~to -
ev-----
- T---
--'w--
r e
v.
w,
---w------=r-
--*-*e-
---ece =+
REVISIGN'O.K JANUARY 1993
)
K Empirical Constant
[ mrem /(MWe-hr))
A constant determined by fitting data measured at the each station.
See Table F-8 of Appendix F for Dresden, LaSalle and Quad Cities Stations.
E Electrical Energy Generated Without (MWe-hr) n Hydrogen Addition Totel gross electrical energy generated without hydrogen addition in the time period of interest.
Electrical Energy Generated with
[MWe-hr)
Eh Hydrogen Addition Total gross electrical energy generated with hydrogen addition in the time period of interest.
Multiplication Factor for Hydrogen Addition _
Mh Factor by which offsite dose rate due to skyshine is multiplied when there is hydro-gen addition.
Hydrogen addition increases main steam line radiation levels by up to a factor of approximately 5-(see Page 8-1 of Reference 39).
Mh is station specific.
OFk Occupancy Factor The fraction of time that the hypothetical subject of the calculation spends at location k in the time period of interest.
See Table F-8 of Appendix F.
Shielding Factor SFk A dimenionless factor which accounts for shielding due to occupancy of structures.
SFk = 0.7 if there is a structure at location k; SFk = 1.0 otherwise See Table F-8 of Appendix F.
0.007 Empirical Constant (m~1)
A constant determined by fitting data measured at the Dresden Station (see Reference 45).
Distance-
[m]
Rk Distance from the turbine to location k.
See Table F-8 of Appendix F.
~
A-54
.u
- ~, -
=g
,y r
..y--.
REVISION ~0aK JANUARY 1993 A.3.2.2 Radwaste Storage Facility Skyshine Buildings to house radioactive waste are in place'.to hbid:this material prior-to shipping to an offsite disposal site, When these buildings are employed for their intended use, a skyshine dose assessment wil1~be required to complete the 10CFR20 and 40CFR190 dose assessment.
k 1
r-q
- A-54a.
g---
9 9
REVISION 0.K JANUARY 1993 Air or' Water for Occupational Exposure," NBS Handbook 69 as amended August 1963, U.S. Department of Commerce.
If two or more radionuclides are present, the sum of their annual dose equivalent to the total body or to any organ shall not exceed 4 millirem / year.
TABLE A -- AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM /YR PCi per Radionuclide Critical Organ liter Tritium Total body 20,000 Strontium-90 Bone marrow 8
A.4.2 Station Requirements Four stations have requirements for calculation of drinking water dose that are related to 40 CFR 141.
The requirements are as follows:
Dresden and Quad Cities The surveillance requirement in Section 12.3 requires that doses at the nearest community water system be projected using methods prescribed in the ODCM at least once per 92 days.
When the projected annual whole body or internal organ dose at the neareut downstream community water system is equal to or exceeds 2 mrem from all radioactive materials released in liquid effluents from the station, a special report to the operator of the community water system is required.
The report is prepared to assist the operator in meeting the requirements of 40 CFR 141.
e LaSalle Action a of Section 12.3 requires a report to the NRC of radiological impact on finished drinking water supplies at the nearest downstream drinking water.
source whenever the calculated dose from the release of radioactive materials in liquid effluents from either unit exceeds the limits, 1.5 mrem.
l A-56 1
i
REVISICN 0.K JANUARY 1993 Table A-1 Release Point Classifications Release Release Point Station P.D.,imi._
ClassificatlRDa Braidwood 1 & 2 Vent Stacks Vent (Mixed Mode)
Byron 1 & 2 Vent Stacks Vent (Mixed Mode)
Dresden 1 Plant Chimney Stack (Elevated)
Dresden 2 & 3 Chimney Stac[(Elevated)
Reactor Bcilding Vent (Mixed Mode)
Ventilation Exhaust Stack LaSalle 1 & 2 Main Station Stack (Elevated)
Vent Stack Standby Gas Stack (Elevated) b Treatment Stack Quad Cities 1 & 2 Chimney Stack'(Elevated)
Reactor Building Vent (Mixed Mode)
Ventilation Exhaust Stack Zion 1 & 2 Vent Stacks Ground-aThese classifications are based on Sargent & Lundy NSLD.
Calculation No. CEC-4-88, Rev.
O, 10/19/88.
The defini-tions of release point classifications (stack, vent, and ground level) are-given in Section 4.1.4.
bThe LaSalle standby gas treatment stack is located inside the main station vent stack.
A-58 T
REVISIEN 0.K JANUARY 1993 Table A-2 Nearest Downstream Consuunity Water Systems Characteristics of Nearest Affected Downstream Community Water Sunolv Other CECO Nuclear CECO Nuclear Facilities Location Stations Upstream of and Upstream of a
Station Station platangg
. Water Sunoly Braidwood None Wilmington, None 5 river miles D
Byron None None within NA 115 river milesc Dresden Braidwood
- Peoria, Braidwood 106 river LaSalle miles LaSalle Braidwood
- peoria, Braidwood Dresden 97 river Dresden miles Quad Cities None E. M311ne, Nonec 16 river miles Zion None Lake County None
- Intake, 1.4 miles aTable E-2 of Appendix E provides the bases of the location and distacce data.
bNA = not applicable.
For purposes of the calculations of this manual, there are no community water supplies which are considered to be affected by liquid effluents from the Byron Station.
This is based on the absence of community water supplies between the station liquid discharge to the Rock River-and the confluence of the' Rock and Mississippi Rivers, 115 miles downstream.
A-59 L
m-_.
REVISION UoK JANUARY 1993 Tablo A-2 (continued)
Nearest Downstream Consuunity Water Systems Byron Station discharges its radioactive liquid effluents to C
the Rock River.
There are no community water supplies on the Rock River downstream of the station discharge.
The Rock River flows into the Mississippi River 115 miles downstream of the station discharge.
The confluence point is below the intake of the E. Moline water supply, which is affected by discharges from Quad Cities.
4
~
A-60
REVISION 0.K JANUARY 3993 APPENDIX D GENERIC DATA e
D.1 INTRODUCTION This appendix contains offsite dose assessment data common to one or more of the stations.
D.2 DOSE COMMITMENT FACTORS Dose commitment factors are given in Tables D-1 through D-5_as follows:
^
Pathway infant Child Teenacer Adult Inhalation Table D-3 Table D-2 Table D-la Table D-1 Ingestion Table D-5 Table D-4b Table D-da
-Table D-4 These tables are from Regulatory Guide 1.109 (Reference 6).
Each table provides dose factors for seven organs for each of 73 radionuclides.
For radionuclidus not found in these tables, dose factors will be derived from ICRP 2-(Reference 47) or NUREG-0172 (Reference 48).
D-1
(
L
REVISION 0.K JANUARY 1993 Table D.la Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) suCLICE B0NE LivtR f.e0CY fatR010 al0MEY Lu9C Cl-LLt M
J NO Dafa 1.59E-CF 1.51E.07 1.59E-07 L.$9f.07
.l.19E-C7 1.59E-07 C la
).2bE-C6 6.091-07
- 6. 09E.0 7 6.09E-07 6.09E.07 6.09E.17 6.09E-07 Na 24 t.72E-06 l.72E-06 1.7JE-06 1.72E-06 1.72E-06 1 72E-06 1 72E-06
- 12 2 36E-C4 1.lft-03 B. sSE-9 6 NO DATA NO Daft No usta 1.168-05 CR St 40 O&fa NO Uaft 1.69F=0D 9.s7E-09 1.944.e9 2 62E-06 3.75E-Of MN St NO Cafa 6.318 06 t.Ost-06 NO DAT4 t.49E=n6 2 48E-04 8 35E-06
- N
$6 NO Data 2.12c-13 3.tSE.tl 40 Osta 2 24E.tn 1.90E-C6 7.tBE-06 FE SS 4 18E-C6 2 90t=06 6.93E-0F NO Cata NO LaT4 L.SSE-05 7.99E-07 FE %)
1 19E-C6 4.62d=06
- 1. 71E -0 6 NO Defa 90 0af4 1 9tt-04 2 21E.05 CD 58 40 Data 2.297-C7 3.47E-37 40 CATA NO Daft 1 6tE-C4 1.19E-0S CD oO 10 Cafa 1.812-C6 2.458-06 90 0&f 4 NC Cafa 1.09E-0) 1 24E-05 NI 6) 7.2SE-CS 5.*3E.06 2 6FE-06 40 Data NO O&fa 3.84E-OS 1.77E-04 91 6',
2.731-19 3.m6Sall 1.59E-tt 40 Data NO Caft 1.tTE-06 4.59E.04 CU 64 40 Data 2.S4t-10.t.06EatC
%0 DAT4 4.01E = 10 1 591-06 f. 6 8 E.06 2N 6's 4 82E*C6 letfE*05 f.80 E -0 6 10 Daf4 1 00E.95 t.SSE*04 S.83E.06 IN 64 6.04E-12 1 158-11 4.0ft-13 NO Daft f.13E.t2 1 94E.0T S.56E-04 GR 8)
NO 06f1 NO Daft 4.300 08 to Caf4 NC DaT4 Mn cafe tf E.24 DR 84 NO Data MU 06f4 S.4LE-04 90 Data NC CATA NO Caf4 tf E-24 PR ts NO Data NO 04f4 2 29E.09 40 DaT4 NO 04f A NO DATA LT E-24 RS 86 90 06f4 2.)tt=0S t.0$t-03 40 04T4 NC CATA NO DATA 2 21E-06 29 88 40 Data 6.82E-08 3.40E-04 40 0474 NO DATA NO DATA
- 3. 65 E.15 AS $1 90 Otta 4.4CE-08 2.9tE.08 NO paft
%C D&T4 NO O&fa 4.22E.tf
%R 59 S.43E-CS NO 04f4
- 1. 5 6 k.0 6 NO 06f4 NC DA T A S.02E*C4 4.64E.0$
St 90 1.3SE-02 NO Data 8.3SE.04 NO 04f4 NC DafA 2 06E-03 9.56E-05 SR 91 1 10E-08 NO Cata 4.19E-10 NO 04fA NO D&fa T.59E-06 3.2 4 E.05 SR 92 1.19E-C9 NO Cafa S. C a t -i l NO DATA NO D&fa 5.43E-06 1.49E.05 Y 90 1.FJE-07 NO 0414 1.00E-Os 40 OsfA No cata 3.66E.05 6.99E.05 Y 91 4.63E-11 40 DATA 1.77E-12 40 DAfa NO 0&TA 4.00E-07 3.77E-09 Y 91 8.26t*05 NO D&fa 2.2tt.06 NO Daft NO DATA 3.6fE*04 S.11E.05 Y 9&
R.84E-09 NO Defa S.36E-11 NO O&fa ft0 DATA 3.35E-06 2.06k.05
--~..............................
(
D-4a
{
1
,e
-.-__._.____-____-__----__-__.___--._.__-_-__a.-
---_____-.._._--___-._a___--._
~.-_--___._-A
1 REVISION 0.K JANUARY 1993 Table D-la (cont'd.)
Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) vuCLICE SONE LivF4 f. d ODY THva010 KIONEY LU40 Cl-LLI v 9) 1.49E-08 NO OtfA
- 4. 6 S E -10 40 DATA NO DATA 1.04f-05 f.24E-OS tt 95 1.82E-05 S.F3t=06
- 3. 94 E -0 6 40 Daft 8.42E-06' '3.36E-04 1.86E=0S ta 17 1.72E-05 3.40E-09
- 1. 5 7 E -09 40 OATA S.1SE-09 L.62E-05 7.88E-05 NS 95 2.32E-06 1 29E-06
- 7. 00 E-0 7 NO DafA 1.2SE-06 9.39E-OS 1.2tE-05 mo 99 740 Data 2.llE-08 4 0 lE -0 9 40 DATA S.14E-08 1.92E-CS 1.16E-OS 1C 998 1.flE-13 4.8 3E-l l e.24E-12 wo DATA 7.20E-12 1 44E-07 7.66E-07 TCl01 f.40E-15 1 0SE-14 1.03E-13 NO DATA 1 90E-11 8.34E-00 L.09E-16 nul0J 2 63E-07 40 DATA 1.12 E -0 7 40 OATA 9 29E-07 9.79E-05 L.36E-OS tul0S 1.40E-10 Nu OATA S.42E-L1 40 Data
't.74E-10 2.27E-06 1.13E-05 aUl06 1 23E-05 NO DATA
- 2. 7 3 E -0 7 S.48E-07 8 17E-06
- 2. 0 7f-04 1.996-01 TEtt?
2.SLE-10 1 14F-10 S.52Ealt 1 771-10 9 10E-10 1.40E-06 1 0lf-0$
TE129m 1.74E-06 8 23E-OF
- 2. 81 E-0 7 S.72E-07 6 49E-06 2.47E-04 S.06E-05 fE129 8.87E-12 4.22E-12 2.20E-12 6.4RE-12 3.SIE-Il 4.12E-07 2.02E-07 TEt31m 1 23E-08 7.51E-09 S.0 3 E -0 9 9.06E-09 S.49E*00 2.97E-05 7.76E-OS TEl31 1 9 7E-12 1 04E-12 6.30E-13 1.SSE-12 7.72E-12 2 92E-07 L.89E-09 TEt)2 4.50E-CO 1.e1E*08
- 2. 74 E -0 8 3 07f-00 2.44E-07 S.6tE-0S S.79E-OS I 130 7.80E-07 2 24E-06 8.96E -0 7 1 86E-04 3.44E-06 WO DATA 1.14E-04 1 131 4.4 3 E -06 6.14E-06
- 1. 9 7E -0 7 1 89E-05 8.6SE-07 h0 DATA L.59E-07 I til 1.S2E-06 2 36E-06 7 78E-07 3 6SE-04 4.49E-06 h0 047A 1.29E-06 1 134 1 1tE-07 2 90E-07
- 6. 86E-0 5 40 DATA 4.69E-05 L.83E*05 1.22E-04 C5tS6
- 6. 44 E -06 2.42d-05
- 1. 7 t E-O S 90 DATA 1.38E-05 2.22E-66 1 16E-06 1-C1137 8.38E-05 1 06 E-04 3.89E-05 40 OATA 3.80E-05 1.51E-05 1.06E.06 C1138 S.82E-08 1 07E-07 S. S 8 E-0 8 NO DATA 4.28E-08 9.84E-09 3.38E-11 BAlber 1.67E-10 1.18E-13 4.87E-12 40 0474 1.11E-13 8.08E-07 8.06E-07 j
D-4b l
6 1
~_. _ _.
REVISION OeK JANUARY 1993 Table D-la (cont'd.)
Inhalation Dose Factors for Teenager (mrem per PCi Inhaled)
)
i NvCLipt BONE LivfA f. J0 DY THve0lc mIONEY LUNC Cf.it!
salto 4.84E-06 4.J87 09 4.40E-07 NO Defa 2.8SE.69 2.S4E.94 2.86E 05 04141 1 78E-11 1 42F.l*
b.9 AE-t A NO Cafa I.23E-14 4.tlE-07 9.33E.14 84142 4 42E-12 6.6)E 13 2.84E-13 40 06ft 5.92E-tS 2.19E-07 S.99E-20 tal40 s.9tE*08 2.99:.08 7.82C-09 90 Cafe
%0 04f4 2.68E.05 6.09E-05 L4142 1 20E-10 S.JII.ll 1.32E-11 NO Defa 40 DefA 1.27E-06 1 50E*06 CEl4!
3.SSE-06 2.37:-06
- 2. 7 t E -0 7 40 Daf4 1 111 06 7.67E nl 1.58t=0S CEl4) 3.J2E*04 2 42E-08
- 1. 2 8 E -0 5 40 DAfa
- 1. 51 E -04 ' t.67E-03 1.08E.04
- 14) 1 67E*06 6.64E-07
- 8. 2 8 E-0 8 40 Daft 3 86E.07
- 6. 04 E.P S 2.67E.0S val 46 1.J7E-12 2.2C4-12 2.72E-13 40 DefA 1.26E.12 2.89E*C7 2.94E.16 N0!=7 9 83E-C7 1 072-06 6.41E-08 40 0474 6.2SE.C7 4.4SE.95 2.28F-05 w 187
- 1. S OE - 01 1 228-C4 4.29E*LO 40 0474 4C 047A S.92E-04 2 21E 05 NP239 4 23E-08 3.49E-09 2 2tE-09 40 D&f6 1 2SE-08 A.119-04 1 6SE-05
+
9 i
D-4c
, - ma
I REVISION 0.K JANUARY 1993 Table D.4a Ingestion Dose Factors for Teenager
)
(mrem per PCI Ingested)
)
I S
NUCLICE 80N8 L Ivr e f.norv fHva010 K l Dht v ' '
LUNG Ct.LLI H
l 40 DATA 1 069 07
- 1. De f.0 7 1 06f.07 1.964*07 1 06f.07 1 06t.07 L
4 364 06 8.12F.47 8 12 E.0 7 8.12F.07 8.128 0 7 ' P.12 E.07 8 12F.07 na 24 2 30E-06 2 30E.96 2 3CE.06 2.30t.06 2.10t 06 2.14t 36 2 30t.06
- 32 2.76C 04 1 11.05 1 07E.05 40 DATA 40 DafA 40 DATA 2 32E.01 CA St 40 D&fA 40 DafA 3 608 09. 2 004 09 7.89t.10 S.14t=09 6.09t.0 7.
- 4 14 40 CAIA SeiOE*0s 1.lft*06 40 Defa.
1.76t.06 NO 04f4 1.215 0S NN $6 N3 OATA 1 38[.07 2.814 08 N0 OATA 2.00E.0 7 mc Defa 1.04E.09 FF $3 3.786 06 2 68F.06 6.2St.07 40 Defa Mc n&TA t.76t.04 1 16t.06 FE $9 S.87E.06 1 4 f1 0S S. 2 9t.0 6 40 Defa 40 DefA 4.12E 04 8.24E.09 CO 98 40 D A T A, 4.726 07 2.24E.06 40 DATA 40 94fA NO DAfa 1.34f.0S CU 60 wo DAf4
- 2. Sit.06 e.3)E.06 40 DATA 40 DATA 40 DATA 3.66E.05 MI 63 1 7 78.D4 1.J10 01 e.00E.06 90 DATA WO DATA 40'DafA 1.99E.06 Ni el 7.49t*07 9.97t.0d 4.3et.00 40 Defa 90 Data en DATA S. L 94 06 Cu 64 40 04fA 1 15E.07 S.4 t E.0 8 90 Defa 2.916 07 he Dora 4.923.D6 2N eb S.76f*06 2.00f CS
- 9. 3 )E.0 6 40 UAf4 1.20E *99 NO Defa 8.47f.04 gN 47 1 47t*08 2 60d.08 1 968 01 90 DATA t.aSt.08 40 DATA S.168 00 AR 86 40 DafA 40 O&f a
%. 7 4 E.0 8 40 DATA 40 DAfa 40 DATA LT t.24 84 86 NO DATA - 40.0&fA 7.22E.08 40 Data
- C DATA 40 Defa Lt.E.24 6A 84 40 OATA NO DATA 3 0Sf.09 40 DAfa.
NO Data NO DATA Lt E-24 4A 46-40 DATA 2.18E 0% 1 40t.0 5 40 04f4 NO Data 40 CATA 4.48f.06 A8 48 40 Defa 8.$2E.08
- 4. Se t.0 0 NO DAf4 40 DATA 40 Data 7.30f.tl A8 A9 40 DATA S.$0t.00 A.891 08 : 40 DAT A NO DATA 40 DATA 8.4)f tr SA R1 4.40t.04-NO O&fa 1.26t.05 40 DATA 40 DATA 40 04ft t.24t.09 54-90 8 308 03 40 OATA 2.0SE.03 MO 04fA 90 DATA NO Data' 2.llg.04 40 OATA 40 DATA to CATA 3.66E.09 SA 11 0.078 06 40 OATA 3.218 07 '
NO DefA h6 DefA f.??t.09 SR 92 3 0St.04 40 DATA
!.30E.07-90 0&fA Y 90 1.37E.08 40 OATA 3.618 10 40 Data NO DATA
=0 DATA 1 13t.04 Y 98# 1 29E.10 40.0&fA 4.938 12. 20 DATA 40 DATA me Defa 6.098 09 f 91
-2 0!E.07 90 DATA S.316 09 40 OATA - 40 DafA-NO DATA 4.24f OS Y 92 1 218 09 NO DATA ~ 3. SCE.11 40 DATA NO DafA-40 DefA 3.328 05 D-13a
.ea n
p.s.=-
i e
ga+.--v-e.-,
.w e,
-i..~-e r
y y-,-~.,.r.-,,.,,-#.-p y%.
,..a wr, 4
-,e----.
RENTISION 0.K JANUARY 1993 Table D-4a (cont'd.)
Ingestion Dose Factors for Teenager (mrom per pCi Ingested)
NUCLICE BONE LIVER f. 400Y TMYA0fD E10NEY L VNC Cl-LL y 93 3.83E-C9 NO Daft t.0SE-10 40 DATA NO DATA
=0 DATA 1.17E-04 la 9$
4 12E-04 1.30C-08 4.94E-09 40 DATA t.916-08 40 Daft 3.00E-OS fa 9f 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.tlE-10 NO DATA 1 27E-04 se 95 0.22E.09 4.>el-09
- 2. s t E -09 NO DATA
- 4. 42 E -09 40 DATA 1.95E-OS MO 91 NO DATA 6.03E-06 1.13F-06 NO DATA 1 38E-05 NO DATA 1.08E=0S TC 99m 3.42E-10 9 26E-10
- 1. 2 0E -0 8 NO DATA 1 18E-08 S.14E-10 6.0$E-07 fCt01 3.60E-10 1.12E-10 S. 0 3 E -0 9 NO DATA 1.2 6E -09 3.12E-10 8.75E-17 Rut 03 2.SSE-07 NU O&ta
- 1. 09 E -0 7 NO DATA 8.99E-07 NO DATA 2.13E-05 du105 2.18E-04 NO DATA 8.4 6 E -0 9 40 DATA 2 75E-07 40 DATA teF6E-05 tut 06 3.12E-06 NO DATA 4.944-07 NO DATA F.16E*06 NO DATA 1 88E-04 ACit0* 2.0SE-07 t.94E-07 1.18 E-0 7 NO DATA 3 70E-07 k0 DATA S.4SE-05 TEl2S" 3.83E=06 1 384-06 S.12 E -0 7 1 07E-06 40 O&ta 20 CATA t.13E-DS TF127m 9.67E-06
- 3. 4 s E.06 1.1$ E-0 6 2.30E-06 1.92 t -05 20 DATA 2.4tE-05 TE127 1.SSE-07 S.40E-08
............................a....
TE129 4.48E-08 1 6FF=04
- 1. 01E -0 8 3.20E-08 1 88E-07 40 DATA 2.4SF-07 fE131*
2.44E-06 1.!TE-06 9.76E-07 1.T6E-06 1 22E-OS
=0 DATA 9.39E-05 TE131 2.79E-08 1.tSE-08 8.72E-09 2.!SE-08 1 22E-0F 40 DafA 2.29C-09 IE132 3.49E-06 2 2tF-04 2.08E-06 2.33E-06 2 12E -OS 40 DATA 7.00E-OS i 130 1.03E-06 2 98E-06 1.11E-06
- 2. 41E -04 4.59E-06 NO DATA 2.29E-06 I t il S.8SE-06 0 11E-96
- 2. 62 E -0 7
- 2. 46E-O S 1.lSE-06 NO DATA 3.18E-07 1 133 2.0lE-06 1.4tt-06
- 1. 04 E -0 6 4.76E-04 S.98E-04 ho DATA 2.58E-06 1 13, 1 46E-07 1.87E-07
- 1. 3 9 E -0 7 6.4SE-06 6.10E -0 7 40 DATA S.10E-09 1 135 6.10E-07 1 57E-06 S. 82 E -0 7 1.0tE-04 2 48E-06 kn DATA 1 74E-06 C1134 8.37E-0$
t.97E-04 9.14 E -0 5 NO DATA 6.26E-05 2.39E-05 2.4SE-06 C5136 8.59E-06 3.J8E-05 2.2 7 E -0 5 NO DATA 1 84E-OS 2 90E-06 2.72E-06 C5137 1.12E-04 1 49E-04 S.19E -0 5 40 DATA S.07E-OS 1.97E-05 2.12E-06 C1138 7.76E-08 1 49E-07
- 4. 0 $f-0 9 NO CafA 9.22E=ll 4.F4E-tt 1.24E-06 D-13b T
'-v-y
REVISION-OeK LJANUARY 1993-Table D-4a (cont'd.)
Ingestion Dose Factors for Teenager
.(mrem per-pCi Ingested)
(.
NUCLitt SONE Livra f.40CY TMy&OIC
.lONEY LUNG
~Gl.LLI
...................................................n......
84160 2.04E.cs 3.44E.05 1.44E.06 NO JATA 1.196 00 2.16E*08 4.3st.05 kat41 6.7tt.08 1.01:.14 2.24E.09 NO DATA-4.65E.lt..).63E.11 1.63E.13 A4162 2.99C.08 2.19E.lt 1 04E.09 40 D AT A 2.53t it - ~1.99E.11 9.18E.20 Lat60 3.48!.09 1.ftt.09 A.552 10 NO CATA NC OATA 40 OATA 9.82 E.. %
Lat*2 1 79E.10 7.91E.it 1.90E.11 NO DATA NO DATA ho OATA 2.42E.C.
Ctt61 1.13E.08 8.80E.09
- 1. 02 E.0 9 NO O&fA - 4. t eE.09 NO DafA 2.54E.(
CEt4) 2.35E.09 L.71L.06
- 1. 9 t t.10 40 UATA f.6ft.10 NO DATA 5.14E..%
CE144 6.96E.07 2.48E.07 3 74E.00 40 CATA t.72E.07 %0 OATA-
- 1. f S F. 0 '-
Pat 4) 1 3tt.08 S.23C 09
- 6. 52 E.10 NO OATA E0 40 Defa
- 4. s t E.F.
...........................................3.349:
Pet 44 4.3CE.tt.1.762 11 2 18 E.12 No.0&f4 1.01E.It NO 0474 4.74E.14 N0147 9.18E*09 1 02F.00 -6.11E.10 40 OATA S.99E.09 kn DATA 3 6tE.05
. 487 1 46E.07 L.19E.07 4.1FE.08 40 04f4 anc Safa 40 CATA 3.22E.05 18234 1 76E.09 1.66E-to 9.22E tl 40 DATA S.28t.10 40 CATA
~2.67E.09.
D-13c p **
-s v-w w
y
REVISION 0.X JANUARY 1993 Table D Miscellaneous Dose-Assessment Factors -
Environmental Parameters Parameter and Value Basisa B
f
= 0.76 p
B fy
= 1.0.
= 0 for pasture grass (milk and meat pathways)
B th
= 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (1 day for leafy vegetables)
B th
= 1440 hr (60 days for produce or leafy vegetables).
B th
= 2160 hr for stored feed (milk and meat pathways)
B
~
th t
= 720 hr (30 days for milk and meat)
B e
t
= 1440 hr (60 days for produce or leafy vegetables)
B g
C fg
= 1.0 May-October
= 0.0 November-April C
ff C
f
= 0.5 g
B A
= 0.0021 hr 1 g
Y
= 2.0 kg/m for leafy vegetables and produce pathways B
2 y
2 Y
= 0.7 kg/m for milk and meat pathways B
y B
t
= 480 hr (20 days) s B
r
= 1.0 (iodines)
B
= 0.2 (others)
D Wg
= 50 kg/ day B
= 48 hr (2 days) tM
= 175,200 hr (20 years)
E tb C.
f
= 1.0 May-October a
f
= 0.0 November-April C
a D-17 9 es
0 l REVISION:-0SK1
':: JANUARY-s1993.:-
Table-D-65(Cont'd)..
r aBasis key:-
3: - Reference 6, Table E-15.-
C:
Typical for climate of Illinois:and vicinity.
D:
Reference-6, Table-'E-3.
E:
The parameter tb is takcn.as'the midpoint of. plant' operatinT life (per Reference 6, Appendix C,::SectionL1)~.-
?--
f h.
D.-
i
+
, -. ~
s,, m L,
REVISION 00K JANUARY 1993 This page initially left blank.
D-20
_SD'*'
a w--+
-e-y w
W
--w--
y t-
REVISION 0.K JANUARY 1993 Tcblo D-13 Bioaccumulation Factors (B ) to be Used i
in the Absence of Site-Specific Data Bi for Freshwater Fish Element (DCi/ko per DCi/L)
H 9.0E-01 C
4.6E+03 Na 1.0E+02 D
P 3.0E+03 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Ce 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01 Y
'2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Te 4.0E+02 I
1.5E+01 Cs 2.0E+03-Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00-b = Refer to Reference 82.
D-32 O"
REVISION O.K.
JANUARY'1993 Interim Radwaste Storage Facilities Interim Radwaste Storage facilities (IRSF) have been constructed at four stations - Dresden, LaSalle, Quad Cities and Zion.
These facilities were designed to serve as temporary repositories of solidified radwaste before shipinent of fsite.
The surface dose rate of these containers may be as high as 15:
R/hr.
Consideration is also being given to store containers of compacted dry active waste (DAW) in Sea-Land containers at all nuclear power plant sites.
These may have surface dose rates as high as 8 mR/hr at a distance of 2-meters from the container surface.
Both the IRSF and DAW will contribute direct radiation to points in the controlled and unrestricted areas.
Thus a dose assessment is required to assure site compliance to the regulations of 40 CRF 190.
1 The dose due to IRSF's have been calculated in References 56a, b, c and d.
In these calculations, the containers were assumed to have a contact dose rate of 15 R/hr; consideration was giveni to accessible sites outside of the restricted area boundary, but near the IRSF.
Although some of these sites are less than 200 meters from the IRSF, the annual doses'are less than 10% of the 40 CFR 190 limit of 25 mrem / year when realistic occupancy factors are considered.
The above calculations are, of course,. estimates as the inventories, nuclide mixes, decay times, container self-shielding, and other factors affect the corresponding out-of-building dose rate.
As the IRSF's become operational, the above estimates will be re-evaluated.
A correlation of l
in-IRSF' dose rate (area radiation monitor reading) with measured L
out-of-IRSF will be evaluated as a better means of quantifying l
the IRSF offsite dose rate.
E-8
REVISION O.K JANUARY 1993 Interim Radwaste Storage Facilities (cont'd.)
The dose due to storage of Dry Active Waste (DAW) on site in arrays of Sea / Land Vans has been evaluated.
For a design basis source of 8 mR/hr at a distance of 2 meters, calculations (References 57a, b, c and d) show that a dose rate of 1 mrom per year will not be exceeded at the restricted area boundary for realistic combinations of IJAW locations and occupancy factors.
Since occupancy at the points of maximum offsite exposure is likely to be much less than 100%, doses due to the interim radwaste storage facilities are judged negligible in comparison with 40 CFR 190 limits.
E.4 BASES OF OIAPTER 4, INTRODUCTION TO METHODOLOGY Most of the material in this chapter is based on Appendix A.
Additional information on bases is provided below.
E.4.1 Introduction of Time Factors In explaining the equations of Appendix A, a factor t (represen-ting the time period of concern) is sometimes added to the l
l I
E-8a l
y b'
REVISION O.K JANUARY 1993 in Equation A-17 of Appendix A are identical to the inhalation dose factors provided in Tables E-7, E-9, and E-10 of Regulatory Guide 1.109.
E.9.17 Food Pathways Doses (Section A.l.4.3 of Appendix A and Section B.10 of Appendix B)
The dose commitment due to food pathways is calculated by Equations A-18 through A-27 of Appendix A.
These equations are discussed in Section 4.2.4.
They are like Equa$ ions 14 and C-5 through C-13 of Regulatory Guide 1.109 except as follows:
The treatment here neglects the pathway of uptake of radionuclides from soil by edible vegetation (the Biy term in Equation C-5).
The reasons are discussed in Section E.3.1.
In this manual the equations provided for calculating food pathways dose commitments due to ingestion of carbon-14 and tritium are the same as-the-equations for dose commitments due to particulate and iodine radio-nuclides.
In contrast, Regulatory Guide 1.109 pro;.jes special equations for carbon-14 and tritium (Equations C-8 and C-9).
The decision not to use the Regulatory Guide 1.109 equations was based on the judgment that the
~
added complexity of using the special equations was not justified by the small dose commitments expected due to carbon-14 and tritium.
(Note:
At present, no station calculates doses due to carbon-14 releases.
See Section E.4.5 for the reasons.)
Regulatory Guide 1.109 states,_"For radioiodines, the model considers only the elemental fraction of the-effluent.
The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine.
Measurements at operating facilities indicate that about half the radiciodine emissions may be considered nonelemental."
Using this rationale, RG 1.109 then halves the deposition rate equation for-radioiodines entering the food pathways.- This ODCM, however, does not include this one-half factor, and thus is conservative be a factor of 2 for the radiciodine food pathway doses.
The dose calculations for particulates_and radioiodines account for doses resulting from dry deposition of radioactive materials E-26
REVISION O.K JANUARY 1993 In both models, the decay time between releases of radioactivity and its consumption in fish'is taken as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This is the value recommended for the maximally exposed individual in Table E-15 of Regulatory Guide 1.109 (see parameter t ).
p E.10.2 Concentration Due to Tank Discharges (Section A.2.3 of Appendix A)
The concentration of radioactivity in tank discharges is calculated by Equation A-33 of Appendix A.
The basis of this equation is explained in Section C.2 of Appendix C.
E.11 BASES OF CALCULATIONS OF TOTAL DOSE FOR THE URANIUM FUEL CYCLE (SECTION A.3)
E.ll.1 Initial Estimate of Dose Due to Contained Sources at a Station (Section A.3.2_of Appendix A)
Annual radiation doses due to contained sources of radioactivity at the stations are judged to be negligible in comparison with applicable limits except for doses due to BWR turbine skyshine.
This judgement is based on the considerations discussed in Section E.3.3.
L The dose due to N-16 skyshine is calculated by Equation A-35 of Appendix A.
This equation is based on the following:
Measurements of dose rate due to skyshine_made st.
Dresden, Quad Cities and LaSalle.
I An empirical' fit to the above data (References 45a, b l
and c).
Measurements of the radiological effects of hydrogen addition to primary coolant at Dresden 2 (Reference 73).
E-29 w-,
e--
n-u
REVISION O.K JANUARY 1993 Guidelines for BWR hydrogen water chemistry instclla-tions prepared by the Hydrogen Installation Subcom-mittee of the BWR Owners Group-for Intergranular Stress Corrosion Cracking (Reference 39).
References 45a, b and c provide-a mathematical expression for calculating an upper bound to skyshine dose when there is no hydrogen addition to primary coolant.
When there is hydrogen addition, the dose is multiplied by a factor of 5.
The value of this factor is based on data and guidelines in References 73 (see Page 4-13) and 39 (see Page 8-1).
Because of natural background radiation, it was only possible to measure skyshine dose rate only to about 600 meters from the turbines.
Beyond this distance, skyshine dose rate was so small that it was masked by fluctuations in the background radiation level (see References 45a, b and c).
Despite this, Equation-A-35 of Appendix A is put forth here for use at larger distances.
This is done because estimates of skyshine dose.at-distances above 600 meters are sometimes needed and because Equation A-35 of Appendix A is consistent with measurements at lower distances.
E.11.2 Initial Estimate of Dose Due to Other Facilities of the Uranium' Fuel Cycle-(Section A.3.3 of Appendix A)
In evaluating compliance with 40 CFR 190, radiation doses from other uranium fuel cycle facilities are treated as negligible E-30
BRAIDWOOD
' REVISION O.K.
^
JANUARY 1993 GENERIC BRAIDWOOD ANNEX INDEX PAGE BEYISION APPENDIX F F-i O.K F-ii O.A F-iii O.A F-iv O.A
~
F-1 0
F-2 0.K F-3 0.K F-4 0.A F-5 O.K F-6 0.K F-7 O.K F O.K F-9 O.K F-10 0.K F-ll O.K F-12 O.K F-13 0.K F-14 O.K
}
F-15 O.K F-16 O.K F-17 O.K F-18 O.K F-19 0.K F-20 0.K F-21 O.K F-22.
O.K F-23 0
F-i
,ek
~
BRAI'DWOOD -
. REVISION O.K JANUARY'1993 Table F-1 Aquatic Environment Dose Parameters a
Value Parameter f
1/M", 1/M 0.25, 1.0 F",
cfs 5.63E3 F,
cfs 5.63E3 f
b 24-tf, hr t", hrc 3
d Limits on Radioactivity in Unorotected Outdoor Tanks Primary Water Storage Tank 1 2000 Cie.
Outside Temporary Tank i
10 Cie (per Technical Specification 3.11.1.4) a The parameters are defined in Section A.2.1-of Appendix A.
tf (hr) = 24 hr (all stations) for the fish ingestion pathway b
c t" (hr) = 3 hr-(distance to' Wilmington is 4 river. miles; flow-rate of 1.4 mph ~ assumed)-
d See Section A.2.4 of Appendix A.
e Tritium and dissolved or entrained noble _ gases are excluded from this limit.
F-2
~
BRAIDWOOD REVISION O.K JANUARY 1993-Table F-2 Station Characteristics STATION:
Braidwood LOCATION:
Braceville, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)
- 1) Release Height =
m
- 2) Diameter =
m ms-1
- 4) Heat Content =
KCal s-1
- 3) Exit Speed
=
CHARACTERISTICS OF VENT STACK RELEASE POINT a
- 1) Release Height = 60.66 m
- 2) Effective Diameter = 2.80 m
- 3) Exit Speed 11.00 ms-l*
=
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
a
- 2) Building Factor (D)
= 60.6 m
METEOROLOGICAL DATA A
320 ft Tower is Located 573m HE_ of vent stack release point Tower Data Used in Calculations Wind Speed and Differential F01 ease Point Dirac_ tion-Temperature Elevated (NA)
(NA)
Vent 203 199-30 ft Ground 34 199-30 ft I
aUsed in cafculating the meteorological and dose f actors in Tables F-5,'F-6, F-7.
See Sections B.3 through B 6 of Appendix B.
i-F-3 9
O
I BRAIDWOOD REVISION 0.K JANUARY 1993 Table F.-4 Average Wind Speeds Downwind Averace Wind Speed (m/secia Direction Elevated Mixed Mode Ground Level N
7.6 6.0 4.7 NNE 7.5 5.8 4.4 NE 6.1 5.3 3.9 ENE 6.2 5.2 3.7 E
6.6 5.4 4.0 ESE 6.8 5.6 4.3 SE 6.2 5.3 3.9 SCE 5.8
-5.2 4.1 S
5.5 4.9 3.6 SSW 5.5 5.0 3.7 SW 5.3 4.8 3.3 WSW 4.7 4.2 2.4 W
5.4 4.4 2.' 2 WNW 6.0 4.6 2.4 NW 6.0 4.8 3.1 NNW 6.8 5.4 3.9 abased on Byron site meteorological data, January 1978 through December 1987.
Calculated in Reference 1 of Section F.2, using.
formulas in Section B.l.3 of Appendix B.
bThe elevated and ground level values are provided-for reference purposes only.
Routine dose calculations are performed using the mixed mode values.
F-5 O
K. 3 9
s n
O9 e.
o l.
s i
f N
o oa t'
OY pt a
IR 4
ra c
SA ud o
IU B
p l
VN e
EA d
es o
RJ n
ca t
a ne y
el s
r re t
a 8388999909888888 3
000000001 0000000 er n
d B
f i
)
2 n
EEEEEEEEEEEEEEEE e) o u
0*
522Ot 9850t 030373 548t 282731 32 s
rt p
589t o
e/m 3303590.O.57598950 n
n sD/
B e.
o re a
1 t 1 f 23 e
(
31 1 1 81t f 461 i
ov s
a 6666677776666666 t
f(
ay l
e
)
0000000000000000 c
er e
R 3
EEEEEEEEEEEEEEEE e
de l a r
l A
2428 S
ed ed 86000767394t eOm 3737074S42449690 do rn v//
73588444 d
eXc 6771 5 9 7.t.
355655 8
i v
to 7
n im u
e L
e 21 3221 1
s 4l 1
/
(
2 od nb t
d c
n s
re e
1 u
)
oss a
px u a, ir rur 0421 634435538350 437231 091 l
i l e 9031 1
t Gie 4 1 8
u em fr dt 6977074469655545 7
2334 m
r f a s
ae 1
/
ed e
Rm r
ag 1
r o
n
(
n 8999990009999998 e
t f
ai se 0900000 0000001 1 1 U
2 a
ts ut
)
EEEEEEEEEEEEEEEE O
e au oc 5
3343045543974O05 h
d ei e
O*
h
/m 4270862444776O58 l
-F D/
6029712368470.t 61 a
t d
sr c
ee at6 t
t
. 7622545681 i
1 74431 g
d sm gs-e
(
D e d s
o n
ar eF O
l a
l l ss o
a eo nr n
O b
e
)
y eur 0421 634435538350 r
lf en o
W a
437231 091 o
2 er eu 9031 1
D T
Rie 1 1 e
e dt 6977074469655545 re w
t I
1 2334 e
F
.p te B
) ae A
tRm M
l e h.
n
(
R
'r B
677777B8B7777666 e
n ee bt e
o V*
1
(
3 000000O0O0000000 o
vr t
i EEEEEEEEEEEEEEEE S
i ea td e
- 08256606 t
l nn t
d a
oOm 967353t t
5577966261 338789 d
c s
io M//
092005009238000 oo e
dn oy Xc 1
524317641 5881 1 1 w
S no pe a
d e
e s f
d ui db m
n
(
i i
i a
f ot i,
x p
r o
ra mr
)
ss a
ur O421 634435538350 B
gl o
437231 091
? 1 9031 1
u m
M ie 1
dt 6977074469655545 1 2334 dc ot ae Q
Rm e
nl ra c
aa f
/
(
D n
n c
Q do e
)
e/
d ni E
E E
E W
W W W
r ke c D.
it' NNENESES5SWSWNWN e
cs n.
n wc NNE ESS SSW WNN wr ao ar a
e-f t
- *o i -
e.
td to Q
s
/
( e iQ X
nx n
d/
oi di X
d et e
dn tu tt ee ao as sp vR
- m. e ap e
ih BA l
xg e.
oi
.y rh
- ~e el p
t hn pf o
To Ao N
a b
i
K. 3 9
O9 1
NOY IR SA IU VN s
2 EC s
e.
RJ e
sa t
l ot n
i pa e
rd m
M s
u d
5 u
pe n
s s
e n
n ea m
i n
e ce A
h o
c nl
(
t
)
i ee 2
e 90oo090oo00oo090 01 t
l rr 1
i 01
- ds 01 t t 1 1 t t 1 t t 1 W
c a
e
- na mue EEEEEEEEEEEEEEEE e
u fe 1
/ol 9t 640342700t 5G93 t re 0690235884406085 S
n ed s
n (GR 631 281 7467736747 n
ro 0
n a
m 7
o O
. 241 4321 1 2
/
4 6456t 9
i D
7 i
r 4
t 9O0O0O0o0000ot 00 8
y od R
1 t 1 t 1 t t 1 1 1 t t1 1
/
e 0t ads s
b fe E
l a
Q c
mea EEEEEEEEEEEEEEEE a
x xe O64 9342330270773 l
d di o
i t 3t 66566952 L
nil O4591 2841 26 u
e em e
AMe O.1 61 2. t. 0.O.01 m
n d
l R
971 r
i ig b
l t
1 4234723t 1 31 1 a
a o
m vn a
e
)
f r
oi T
m Mss i
ur e
rs ti e 221 7623255856565 n
sdt 079 6000744257434 e
t pu R
6 A
eae 7436574400892070 h
e E
rRm 3554437588456828 t
d ed F
a
(
1 re r
7 t
e a
N d
s am e
D e
t
)
e o00O9o0o0oO0oo0o g
n a
r p F e
O l
M 2ds o
a ao 0t 1 t 1 t l 1 t t 1 t t 1 1 l O
b
- na - - - - - - - - - - - - - - - -
l t
tf t
- u&
EEEEEEEEEEEEEEEE o
W a
n ar n
d 2
D T
mot 285735t 770247653 r
n
/ re 4896447484020075 o
a de a
GR 01 99083267997737 e
I F
l p
l 1
a
(
t A
Q 43t 1 t 2221 1 1 t 1 1 22 e
p e
p R
w
/
M n
se 1 o0 B
o D
o00O000oo0Oot e
o f
ar f
e t 1 1 t 1 1 1 t t 1 t t f 1 t 1 C
wds - - - - - - - - - - - - - - - -
t i
o ea o
oea EEEEEEEEEEEEEEEE t
l i
k Cwe 87t 3832630428733 S
6329846766030932 c
r es r
t l 61 36 d
e e
rn e
l kMe 61 321 9750141.
o S
t o
t o
i t
R 6t 1 11 t 1 1 991 1 i
231 f M
M w
n li n
d f
e et e
)
l s
eie 5555055555555535.
a o
c va c
t ss t
sur r
el e
rdt 4444444444444424 B
1 m
l u
'm aae 0000500000000070 r
eRm 8888388888888878 o
c o
e.
r dl r
a N
(
e cB f
na f
N n
n uc do ex e
o e
e ni ri c
re c
it h
wc E
E E
E W
W W
W ed n
gs n
t ne NNENESESSSWSWNWN f n a
o a
wr NNE ESS SSW WNN ee t
dd t
t t
DO Rp s
n s
a p i ae i
nA d
n d
Q o
di
/
f e
et e.
D do t
tu t) e a
ao a3 s4 m
vR m8 a
i e
i 9 BB x
l x1 o
e.
o r
.y ry e
p el pl t
p hn pu o
A To AJ N
a b
c g
- ?
i
m 1
~
u f
s K. 3 9
s 09 e
<1 si N
oa OY pt IR ra SA ud IU p
VN e
EA es RJ ca ne el s
5 re t'
er n'
4555566665544444 m
0000000000000000 B
f' i'
e) o '-
)
3 c
8 Re EEEEEEEEEEEEEEEE s
rt p ~'
A s 6476452028t 09743 eB/
967579 07504421 79 n
n J
r sGt 21 821 223251 55644 o
re
'e e C 1 111 i
ov sV K
54649542391 -
t f(
a e u 1
t
(
4444455564444444 c
h
r e /
0000000000000000 R
e de l'
9 o
-e a - - - -
l y
EEEEEEEEEEEEEEEE S
ed e'
f eG/
357582t884262364 do
'r' 94964639564 32071 vd n
im 0,5771724732601 s
e e 31 7
i v'.
t
r L
r e
5222t321 9t 366666 8
/
od n
o s
d
(
2 s
re e
t n
1 a
px u'
c u
)
a oss rur 0429 63443553e350 4
l i
l u
em f'
43723t 091 m
F Gie 903t 1
1 1 dt 697707446965S545 8
r f
a'g e
7, 1 2334
.ae
/.
r e
Rm t.
o n
l s
(
e o
556566667655555'5 f
ai s
t; ts u
D 0000000000000000.
D.
e au o'
..c a:
)
EEEEEEEEEEEEEEEE 7
eRe m
eB/
34089426346802l t
.d.
e' sAs 6917843942578783 h
d s
s
1 l
F a
m eVt 553297748741.49.O.2 ee a8' c-sm g-l t - c d
e u 31 91 82.t9 751 22233 a
i D
eG R'
t g
n ar F"
a eo
'n O
l 4555556665555444 o
/
000000000000000C l
O b
)
)
t r
o-lf e
e W
a r
m n
y EEE5EEEEEEEEEEEE 2
er e
D T.
u eV/
5588399743009S22 o
re w
I V d 5729026426300042 e.
(
e 438211 0023009223 F
p t
t l
A P
e" s
r e
l e
~
s t63531 7632699t1 1
R d
e t
n ee b
o'(
e o
vr B
e M'
t i
...... /........
i i
e a.
t t
)
dss n 2 eur 042s634435538350 S.
t l
'i i
90311 437231 091 dt 6977074469655545 d
c
.s n
wl e 1 1 2334 '
o e
dn d t
i Moe 1
. R. (m o.
S no p
F w
d ui d.
ot i
5 y
d' l
f .
ed' e
o ra m
r t n) r i or 0421 634435538350 B.
B gl a
cus 90311 437231 091 1
u m
d rBe 1 16977074469655545 x
dc. o n
t t
1 2334 ei nl r
u sae eem cd aa f
o rr(
B nA nn c
U ee
)'
e n
Is
'e do rp ke c
t ni
. EEE' EEE. WWW. WWw ep cs n
wc NNNNESSS5'S5SWNNN fA
'a o a
i t i
-E, S
ne N - E' E
S' S
W WL N e
td t
i lwr Rf s
s oi o: ( e i
DD n
n d
o6
.di.
l
.;et
'e dB.tu t
e ao a
sd vR m
_'e; an e'
i i
Ba l[
xo
- e. y.
r e~
el p
t~~
.hn.
p o~
.To A
N a
b g
4 iL
- !I
~ ;,
BRAIDWOOD
- REVISIONi0.KL
- ' JANUARY 1993?
Table F-7;(Cont'd) l Site Boundary Finite Plume Gaus8a Dose Factors for Kr-85sa
.I
' I Oownwind unrestrseted-est=.d esod.(venti net....
cround e..v.I a.t....
l Dir ctton Area Sound-Radius-
.V VBAR Radius'
-G G8AR (m.t rs) -(m.ters).(ared/yr)/(uct/sec) (see t.rs ) (mrad /yr)/(uCt/s.c)
.N' 610.
610.
9.989E-04 8.285E-04 610.
'2.73tE-03 2.242E.
- NNE 914 1984.
4.979E*04 4.143E-04 994.-
~1.222E-03 t.OO8E-03 NE 792.
792.
3.618E-04 3.023E-04 792.
1.173E-03 9.673E-04 I
ENE 701.
70s.
4.452E-04 3.7 TOE-04 708.
.t.363E-03 1.12tE-03 E
1036.
1036.
3.452E-04>2.882E-04 1036.
1.023E*03 8.44tE-04 ESE J2713.
2713.
" t. 220E-04 ' t.021E -04 '
2783.
3.05IE-04 2.533E-04 SE 13414.
.3414.
8.979E-OS 6.847E-05 3484.
1.970E-04 f.638E-04
- SSE, 3444.
3444.
.6.958E-05 5.828E-05 3444.
1.634E-04 1.359E-04 S
4633.
4633.-
4.OOOE-05 3.349E-05 4633.
1.05tE-04 8.742E-05 t$$W
-975.
975.
2.483E-04 2.OteE-04
-975.
9.063E -04.. 7. 480E -04 '
2 SW 625.
625.
"5.268E-04 4.392E-04 625.
2.Ot9E-03 1.659E-03 WSW-533.
533.
7.03tE-04.5.846E-04 533.
3.226E-03 2.646E-03 4
P W
'518.
-518.
L6.908E-04 5.729E-04
'518.
'3.08tE-03 2.524E-03 WNW' 503.
- 503.
'725ttE-04 6.2 TOE-04
-. 503.
-3.126E-03 2.557E-03 NW
.. ' 4 95.
.495; 8.396E-04.6.959E-04 495.
2.915E-03 2.388E-03
- NNW.'
510.
cStO.
9.023E-04'7.48tE-04 510.
3.09tE-03 2.536E-03 1
Braldwood Set. M.t.orologicat Data' 1/78 12/87 b
f s
l i
9 1
j
.F,9-N
?
'y-ri-.
9 m.
~
ts h
~
t'
- g m,.
O@.
.5
' i g'.
- O >i _-
sR
~
_m HD ig[
- n va.
+
- 8.888888888888888.:
in -
u
.4
=. w w w w w w w w w,w w w. w. w w. w,-
W
-- no Son c.
. 5s3 n... n.. n - - n, n. t..
o....
a w
. n...
w.
en--.-nnnna.
'o
! 1 8 8 8 8 8. 8. 8 8 8 8 8. 8. 8. 8 8 8..
u A WWwwww ww'
> 1. -. n8wwww.w.w.. o. n. e... n......
.n
.as k...n.-.....o..n
.. -.,. o n
,e-.
a n.
w a
a----enn--onenne o.
u o
a-o,......,....
a
- -. o n - -,n e e n. n e. o n-en.
a.
k
.. - - o -. n.. n n S, e -
e.1 --
-nnn.
e s
,o L E
.. W w, 8. 8. 8 8 8 5 5 5 8. 8. 8 8 8. 8. 8 8
e wwww www a
E,...n.-n wwwwww
.v1 0
..Y
- n.. n e. e. 8. n,.
n.n
.n.e..n....-...ne..-
,. a, -.n o.-
o-
.Es.
O a
re r
- i. 8 8 8 8 8. 8. 8. 5 5. 8 8. 8 8. 8 8 8. '
g h>
F b--
l > s> o w w 8 w w w w w w w. w w,n t m e w
www
-.....cn.nne nn e
Sno.
ncen
. w. -
--o noe
.-ne
' a
~4 k-- *W 4. 4 : : d d 4 6 4 e'4 4 4 1-
~
a s
i2 A a,
.t e
-m 1....
o w n o. e n........ S.- -
n--,ncen.ne.o e.
24 c-o-,,n-- a n n,. n. n -
-w-m mI
~
W
.g
-w
'S
-. i
=o,................
.L U
n-en..n enenCo
- o. n. --ann,.rnn S -
n
. e e.. o r
.me e
- s -
.I
.og~
,Lw l
1g-e a
w..
ZZWeme
- com, an,
. www,,,
w w ee ~
.gX 2
'g l
Q
- (
i
=
r~
d
,-~
~._>51 j
-MM em-1 O Ch I
e=t
- EON H 2:
to 4 HD' 2:
>4 41 p: *2 menne,wwwmennnnn C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.-
au p
er di wwwwwwwwwwwwwwww OO-momomo.e-ewank we e c - - o e-p n e nnnO-ee l
em%
eD-
- m.. p e. o. e. C. e. >.. p @ o. a. w. &.
y a
u M
e 3 emenNewn-nwem666
- =
e nnenne,wwennnnnn y
0000000000000000 et =
O L
- > WwwWWWWwwwwwWWWW W
EON e e n r= w w - e p > w e - N e n
> V evMNpemeOp*mMcwN C. e. n. o. m. O. e. O. O. v. e. *. m. o. s. o.
to e e y
w 6E ennwnewwNNO@e@e@
e O
w N
M
^
-O Oee
=.. * -...
c 8
L 36 Own-engwnmenenco A
o-e
--pCn--wn>nn-Om-em emonorwwereceeve m
eo annns aa N
^ m@
C.
9 nnnnwwwwwennnenn e
0000000000000000 a
U A e
U C
eke wwwwwwwwwwwwwwww O
g og es
-mmoe--evomnem*e g
e IO N eno-n--nonnnem*e I
-$>=
e U
- e. w. O. n. e. v. N. m. O.. m. o. e. o.w.e.
u
,-t U
v O
e 3 M***@nn-* Men *NNN g
E-1
- O Q
u w
t'-
s emnnnwwwwwennnnn N-l 0000.000000000000 L
e O
b L
3 C
A wwwwwwwwwwwwwwww O'
e>%
n o oi e O s m - n n n O e - a n -
g
> t -cw-owenemewwmme o
Q-M
- n. e.n e..e.e. n.u.n.n. N,w n.e.
p w
e H
m af g
e 6 -
M
.Q 4
M*--*nnN-e-NNNNN-I' 8
e EQ Q
4 b
y eme
'd.
e3L Own=enwwecomenco.
--e Cl',
x-9
--pOn-*wMonn-OP*
-V*
we>60Mwwemeccow@
.g 2ef
-Nnnv N
Nn 3
V' S
eV g
- cm L
U3e g
-OL Ogn-enwwnmenenco e
mon--wnenn*Om*
D:
L e e. e-F M h o o w w o m e m m e w c C
- Nnnw g
ggg o
uuw C4 a
- 3.
Eb
@a t
www www 333 3
- d
~ 3S 2E22Wmmmmemm3 Z
m-C w w e c 3
3L 3
w O-QC i
I
i_ '- M (9 em-e
~ O m.
r=4 IEl -
O ><
- M MMD bk e
nemmmmenwmnnnnun 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0..
=
CD o
oc a6 wwwwwwwwwwwwwwww 4 e e r-m e - e v - - e m e n o e et I
ees ooaenn-me-oe-n-n W
eD-5.k.m.e.w. m.N.O. O.e.n e.m.m.e.m, g
a p e p => wee---ec w
W e s nmmmmmmmenNnnnnN 0000000000000000 O
2 a
L N
a=
> wwwwwwwwwwwwwwww eos em*OweeeoemOcn>m
> c emvem-memowoome-g
- m. e. w. e. m. n. n.
. m. w. w. m. a n. O. N.
e a w
W s
6 O
e -- e e m e n - - e e - n a n n a e
s w
y u
ae g
63L Own-enwwncomenco k
o-e
- - m O M - - w M r-n n - O m -
De em&WOmvwomempowe e
e
-Nmme t-y al s
m O
w g
?
.0000000000000000 D'
~
e-wwwwwwwwwwwwww'ww O
U g
s er e m
nemon e a c w r-O m m e 8 n e m o n e O
ces emewo--es u
mes
- m. w. e. n. o. m. e.. m. e. m. o. e.. e. n.
N a
e>-
.y vm
- o g
e 3 onnenecem-novece E
i c
y b
C mnennmewwmmmmmmm A +
0000000000000000 I
a-
.o b
w L
C A.wwwwwwwwwwwwwwww Q
e>s r-e e in e n m m - e r-o r- > w wi C
> v m-onononoewmov-e g
w e o. O N. e. o. e. e. m. O. w. e. e. m..e. N.
r=t
- e e
b e
L Nwmen-emmawmapeb 1
g g
- E Q
Q s
.e.
H a
.g eee
&3L Own=enwwmmmmenco e
E a-e
--mom--=m8nm-Om-
- H
- V *- eeoeO5wwememmewe b
Xee anmMw CE E w
D et e
wC=
m o 3 e-L 80
-0L Own-emwwmemmemeO e
Lee
--mom--wnr=nm*-Om-eebWDhwwe@wWMWw@
D eee
-annw eoe 0
6Lw g
e e
E2 a
www www >>> >=
.H 2g22Wmemeemm3g2 30 g
w - w w,
go O*
CO e
M
r bC M
+m O C4 d
> $0 ><
M sg to dC HD
>Z 14 aC.
C4 r3 MMMMMM M M M M M O c c o,0 0 0 0 0 0 0 000000 000 m
u wwwwwwwwwwwwwwww We momeOO-wMMemOMoe 30 ee
-e-0O*eeee1ntoMoe I
ee%
a w c. e. M. n. e M. N. e. N. e.
3 e. n. m. e..
W e0-e g
n-n-enneenwwwee g
MMMMMOOO@MMMMMMM.
M e
0000000000000000 a
O L
w w W w w W w w w n. W W W W W W
... e n o n w e e' n m a, n e w N
a=
h eO~
e w O. M..,e. 8. 8...e n n
-en v.
- e. e. n.
0 n.
.. n. r.
a e
n u
a u e
e nnM-enne-Mewee-o a
u O.wn.OM--wn-nM S.O tonwwMopMcMe O
L3L m
0 v. e
.e.--0-www.ec.
w.
e-
-~Mn.
a at
~
~e8 8888388888888888.'
L, o y
0
..,w wwww w ww ww
..e 0 Ommenewecemon, O
C ewe v en ee e OO.e.ow en e m -e. m. e. #. O. m. n.
L{
O.
y e e,s a
o w. M e. m. m. e.
.e.
L y
A g
e 3
M**-5mMMNe***NNM 9'g O
Q N
M M M M w w e e 8. T M M M M M M
.O m.
t%
N 00000000 0000000 8
I o
w wwwwwwwwwwwwwwww C
h MNehnOnnhwomOObv 0
- C
,e > %
n p o m p w a n n e. e m s - N -
e U
M. e. n. e. O.
. M. e c. e. r.
.. w. n. e.
I g
M
- e i-4 A
g g
e w--~e-wMme-nnnMM y
' M Q
b M
gap e
Own-eMwwMecMeMmO
,4 e3A
--MOM--wM*nM*Cm-U-
m-e emMNONwwemeOmOwO-
- V. *I
- .4
-nMMw-3 b
a v.
m O
o3 O w n - so M v v M e e M e M m O e
a-oo
- - m O M *- - w n 5 n M - O p.
PD L eo e embbokwvemempows N
O eS@
~NMMv-sea OQ I~
t5
@a ww.
>>> a,a g
go Zg22WemeWeem,ogZg w w.,
,e 0-00 9'
. M. f9 m
om e4 '
EON N 0:
trJ aC '
H.>W D: P3 wwcweneeOcwwwwww 00000000..0000000
=
e y
O ae wwwwwwwwwww.awwww ne eOOnNnN>rcOweOOn a
eeN wwNOMwOweee*neo-I 80-
- m. o. d.e.w. e.e.n.. N.o. m.v.o.e.m.
u e
u e 3 h***M=c=nMe*-Nwb M
w e
N vvwweneeCowwwwww 00000000..0000000 W
a a
L O
=
> wwwwwwwwwwwwwwww W
EON N N N w e en e n v n w e m N e
- V wemmmmenOOMNo~mN
- N. *. e. m. 6. >. O. m. e. O. N. e. w. e. n.
- e m
30 s
6 M
E m=**n*@NnnNN*Nem e
N w
O N
JJ O
ea L DL OwN-enwenemmempo e
~~ MOM *,wn>Nm*Cm-g O-9 emn*Om womecocwo e
b u-ee
-Nnnw n
a$
g a
a wwwwomeeOcwwwww3 D
E 00000000..000000 a
e o
. as eme wwwwwwwwwwwwwwww 0
C e as e so e m - N w m o N n an - e N w e gg O
ee%
ew----Nnom~eneNe
-s
- m. N. =.c.e. n. w. N. e. o. O. N.e. m. m. e.
e>=
y U
u V
e 3
N**-wN*NwnNNNNwe g
E M
g
" ~
Q C
wwwwc*mecewwwwww 1
00000000. 0000000 p
e e e
o g
a a
8 I
L b
C A
wwwwwwwwwwwwwwww L
3 9)N -eMNwO*Now=McNw=w O
> V menommmewo*wnNw-*
O Q
- o. w. n. e. w. e. s.e. n.e. n. e. s.w. e. O.
- e C
- e M
g e
L 04 E e * -
- eft N
- N O w N N N M O e 1
g S
w
.?
M Q
e' H
vee a
- 3L Own-emwwMmeneMeO m
.g m~e
--mon **wmoNn-Om*
O
-V*
em>&Obwwomecepwm eet Ee9
- NMMw at g
3 w
V V
g
.e.
e N
U e
..... +.........-
L L
O w N = e n w e m m e n e n in o e
W Lee
--mon--wnnNp*Om-g e m o b O e w w e,to e m p o w e C
ese
~Nnn D
eeE LLw O
C4 E
O C e
FS a
www www 333 33 2g22WWeememe3g2 30
.W w w e e 3 g-
,e
-o-OQ k
l V. M
- m Qm ed 3
O >%
4 H
03 sc HDbk I
=n w,,,,,,Oecwwwwww
- o. o. o. c. o. o. o. o. o. o. o. o. o. o. O. C.
y w w w w w w w w w w w w. w, w w w ae e-.. o n - e e n e n
-nn we
. co s n e n n. e n e c w e r- - e o w 5 t=
o n N T.e w o.*.0.. *' -.
co-M C
U g
e 3 - e e n o.- -. e w - - - - - -
i w w w w w e e nn e w w w w w w w e s
- o. o. o. o. o. o. O. O. o. o. o. o. o. o. o. o.
o a
a M
L w w w w w w w w w w w w w,w w w.
n...-ne,., woe
.os
- e. e. n. o.,.o. n.. o. w n. n -,
u n.,e--
v.
.--n-,nn--no
.e.e.
. c. o. o.
o p
t.
W s
o..
i m
g,,
- o......,.,.........-- on--wn-~n-o.o u
uv wn-en neen.n.
O o -.u a
ee~~o-ww=*eceeve u.
- v. t
-nnn.
-s a
N e
eccco888.8.8.ocene8
- o. o. o. o. o.
- o. o. o. o. o.
a 0
o v
a o
w w w w w w w w w w w w. w w w w
.a.
n,. n.. n. n,,a n 8. o e.
a
.=.
m..n..e o.onn. n.. s. o.. o.. e...
n
..~
a
. n.
u o
o,
. s
-n---wnn-aananne u
F m
-6
,. 8 8.. 8 8 8......,wo. o. o. o. o. o. o c=4
- o. o.
- c. o.
e o
g o
o 6
wwww w
h wwwwwwwwwwww.enew 0
A Q
c >
8 on8.nennnn-e g
e>s en vo e
n.....n-wovensnew. c a. o. e... o. n.
h
> v w
n 3
e e
u O
O v a venen-owneso---
x H
O w
M e
M s
a b
m vom own*eMwwneeM nco a
g e s t.
--con--wnsan-oe.
H e m-
-v-e a r-r o m w w e e e m c o w e v
g y
-nnnw
,g XSg C
5 i
d e
m g
o w ~ *o= e n w w M c @ n o e neo gD L
-*m n--wnmnn-oe-L to e ennn,moeoevc
- we e @ W 5 o fa=
M e.g S$s D
b L=
c cw D
C g
o eo r
CQ c-www www 333 p3 C
EU 2E22Wmmmemem3 Z4 e
w w e o a a
>L O-
- a oo
-^M
"'"'~ ~~ "
-n---
r-MM om Om r1 E~
.H%
t/J aC HD-
>2 b3aC ww,weece w vw g
oo0000o000000000 a
M U
= i e *
- s * *
- e * * * * **
M ae wwwwwwwwwwwwwwww
=m connew-osnnnne-nn H
e s seNoe-ce-n-e-n=e N e.o..c.e.n.e..w.n..m.o.e.m.
I
- =
e o 3
T--n=ennn-newoww e
-e s wwwewcoccewnwn,w o0000000oo00o000 4
W a
a w' w' w' w' w' w' w' w' w' w' w' w' w' w' w' w' O
44 ec% e - e o e e o e n - e w e - r-r-V one-wmoommeom em
- n. w. n. o. e. n. m. o. e. o.. o. e.. o. w.
o e D3 w
L W
E emmwnemwnNe*p-me e
E, ~
k o
a U
5me L 36 own-cMeencemenco g
O-e
= - m o n e - w M e-n n -
m-b V-emerobvwomome we e
ee
-Nnnw e
N 28
^
g
=
D m
3888888888833333 L8 e'o e e e i
- * * * * *
- i i e +
U C
wwwwwwwwwwwwwwww s a. a
,n-,eomenoome,nn O g Q
a N
mee-memnmewn-NnN a
w.
w e
- w
.o. n. e r..o. n. n.c. o,o, n,n.
p U
e4
-e 3
->cew--mend-*--*
l Q
g a
- h Q s vw vocococwwwwwe g
-. o.. o. o. o o. o. o. o. o. o. o. o. o. o.
o a
a DW i
L C
> wwwwwwwwwwwwwwww e>N
-econmencoopeece 0
Q O
> V e~e nwoeopeemwem e
He M
- e
- o. n... o.d.e. m o. n.n. e. n. o.e n..
p
.g e
L a
n-e-en---m---nna E
w Q
e.
b O w
a M
Vea e3L - own-onewnoemenco m
.g X-e
-* mon-*wnran-oe-O
- U*
emb&oMwwomemmewm V
-nnnw
.c4 Ieg 3'
b V
V e
a
- =
y g
L L
own=enwvemeneneo e
2 ces
--mon--ennan-om-e e e r-r- o r-w w o o o c e e w e
~
- O ese
-NMmv 3
eeE bLw O
C4 E
o e c
-w www www >>>
3
.,4 30 ZZ22Wemmmmem3 Z Z w. W W
M 3
g go m QQ l
t
b L hf. M -
em
'os r-e Z
O b8 N o:
t/J 4 H:3
>z h1 4 D: 4 sww weccewwwwwww 0000000000000000 o
s M
ae wwwwwwuwwwwwwwww am
-M*NNPON050T*h-c g-e nonmomeow newegn w w w e. e n. w. c. e.. n. o. w. c. o. w.
H e -
l g
y-M
-e 3 ennnnewnn=weeeee 0,
e s,wwwwcecowwnnnwn 0000000000000000 a
a L
9
- > wwwwwwwwwwWwwwww O
eos
-vocnoommonwo-,
> V eoemeee-r-nOee-w w
.m.e.w. n.e. e.n. n.p e.
.O.O.C O.
e e 93 E
ennwnmeevne---m-..
e-w-
t e
N w
w N
O
~
6 e ~e y
L3L Own*eneencemenco e
y o-e
--mon--wnnnn-Oe M
t *- eme-bomwwomeppewe e
e
=-nnns e-aI s
~
a C g tra geeeeeooeepwwwww e
00000000000.00000 O
o e
M Q ene wwwwwwwwwwwwwwww.
O e4 e.
e-n w w P-n e e t-n e o e n r-g e a> N e n -- O e t-noentenm5 O M
.o > -
- e..n.e.
.. o.n. e..w. n.n.w.e r.
e
- p y
Q n
e 3
-meeen--wwm-----
w O
N wTOwe@@@OOTwwwww 1
'Q b Q 0,000000000000000
^
a L
o N
i C
> wwwwwwwwwwwwwwww L
b e>N wom-wncoceewo-nn o
3
> c n e e-e - e-n w n e e n e n a: e o
- e. n. o.. m. o.. e-. m. n e. m. e. n. o.
Q C
e L
w e
m M M e
nem-enne-e---NNn f
g
.O b
m m
p e use eDL Own=enwwncenenpo e
y m-e
- - m o n - - w n e-n n - O m -
.e4
-V-eerrOew,eeeeecwc c
xee
-nnn aE g
'd
$Ed V
e e
........ - - + -....
L U3e
- oL Own=eMwwnoonenpo 53 -
Lee ~~ mon--wnman-Om-g e m P-P O t-w w e e e o e o w e C
eee
-nnns c
ese L L-U C*
O 3
E:l1 Co NNN www 30 2222wemememv3 y
Ce 2
W w
3 3 g
to o-00 p
es e
~
w g->
m J
K. 9 3
O9 1
NF OY IR SA IU VN EA RJ 3333345554333333 0000000000000000 t
c e
Re EEEEEEEEEEEEEEEE S
A s 868624t 6831 3t 083 i
e8/
6952474964553400 1
a c
. 079341 56799 3
sCt 65381 129838233333 e u 31 1 1 l
(
e e /
3333344453333333 0000000000000000 X
R
)
.r l
y EEEEEEEEEEEEEEEE r
eG/
338t 8932Ot 062558 o
v d 01 2967662t 866998 e a 4961 341 0 0. O.5 2 3 4 6 6 f
7 r
L. m 41 1 21 21 141 244444 8
/
s d
(
2 n
r u
1
)
o oss t
rur 0429 634435538350 1 437231 091 9031 Gie 1 1 c
dt 6977074469655545 8
1 2334 7
a a
ae
/
F Rm 1
(
e 3444445554444333 a
)
0000000000000000 t
d
..)
s c - - - - - - - - - - - - - - - -
a o
eRe EEEEEEEEEEEEEEEE O
D sA s 9466762609432039 tn aB/
0952802953773999 l
eVl 6568734474569023 a
o a c
C l
C s e u f 75641 76237991(
8 1
ig
(
s R
(
u
/
3444445554433333 o
1 0000000000000000 l
D a
)
)
t r
o 7 G eV/
4t 59O73t 7O447463 o
' F O
n y
EEEEEEEEEEEEEEEE r
O F
e V
d 2744t 5447O3S8047 e
W 356 t
(
a 907175872.t 0. t M
1 m
D e
e e
r 96851 873491 1 1 l 1 I
u d
a 1
l o
(
A b
l e
M t
R P
)
a i
dss B
T ~e eur 0429 63443553835O S
437231 09t 9031 1
xie 1 1 t
idt 6977074469655545 d
1 2334 o
i Mae n
Rm ow
(
o i
d t
F ed.
e t n) r cus y
ior 0421 63443553835O B
1 437231 09t 9031 r
rBe 1 86977074469655545 t
t a
sae 1 2334 d
eem n
rr(
nA u
U o
n do B
nt it EEE EEE WWW WWW e
wc NNNNESS$5SSSWNNN t
wr
~ N ne N
E E
S W
W i
oi l
DO S
1 I
4 i
i 6
t i
K. 3 9
O9 1
N' -
+
RJ s
L 3333344443333333 0000000000000000 t
5 c - - - - - - - - - - - - - - - -
3 Re EEEEEEEEEEEEEEEE A s 47390484902068t 9 1
eB/
0954866f 36290401 6 4.O. 4 0 3 6 5 5 3 5 sGl 1 3351 e
a C 233333 e u 31 1 1 1 322t f X
l
(
e /
3333344443333333 0000000000000000 r
R
)
r - - - - - - - - - - - - - - - -
o l
y EEFEEEEEEEEEEEEE f
eG/
429356478389t 386 v d 7593921 795465006 291 665,8339362731 e a 7
s L
r 1 1 1 42211 244434 8
r m
31
.(
/
d o
n 2
1 t
u
+........
)
c oss rur 0421 634435538350 y
a Gie 1 437231 098 9031 1 1 F
dt 6977074469655545 8
ae 1 2334 7
Rm
/
)
e t
(
d s 3444445554444443 a
o 0000000000000000 t
.)
t D c - - - - - - - - - - - - - - - -
a f
n eRe EEEEEEEEEEEEEEEE O
sA s 55O7027O83486367 o a aB/
44OS343O72366943 l
C s eVt 1
s 7 2. t 04839811 9660 a
-c c
9 l
(
n 1
54541 9842687891 i
eu f
a g
D R
(
7 G
/
3444444554444333 o
F 00000C0000000000 O
l
)
)
t r
o O
F e n
y EEEEEEEEEEEEEEEE r
W 8
eV/
3t 24300288728B95 o
V d 5858506862340t 32 e
D e u s
I
(
a 3790771 7 8 3 2 6 4. O.12 t
l l e r e
A b P d m 1 64641 1 953799119 M
R' o
(
a M
e
'B~
T e t
)
i t
dss eur 0421 634435538350 S
1 437231 091 i
xie 1 1 903f n
idt 6977074469655545 d
1 2334 o
i Mae Rm o
F
. (
w d
d i
ed' y
t n) a r
cus r
a ior 0421 634435538350 B
8 437231 091 9031 rBe 1 1 d
6977074469655545 t
t n
sae 1 2334 u
eem rr(
o nA B
U n do'
- WWW e
ni E E E'
. EEE WWW it t
w c
N N N N 'E S S S 5 $ S S W N N N i
S wr
' W ' N t e N
E E
S S'- W 1
oi DD g
' ?
l
.p
N W
K. 9 3
y 091 NOY IR SA IU VN EA RJ 3444456664444443 0000000000000000 i
7 c
3 R-EEEEEEEEEEEEEEEE 1
A s 9257479855374955 t 881 331 9
- ! 3595383 eS/
990 sGt O.60206442551 1
e e c 3342155f1 477791 X
e u 1
n t
e /
3444456664444433 0000000000000000 r
R
)
o e
r, l
y EEEEEE*EEEEEEEEE f
eC/
25070t 3472344t 72 w
v d 044703975t 794762 236949344.S.344312 s
e.
e w
7 t
c r
a 14342l661 t 588911 8
/
c o
d
-(
2 t
n n
1 u
)
w c
oss a
rue 042t 634435538350 437231 091 9031 F
Gie 1
1 1 dt 6977074469655545 8
2334 7
+
oe 1
/
e Re 1
+
Ws f
o 4444456665444444 e
0000000000000000 t
t D
)
c - - - - - - - - - - - - - - - -
a n
eme EEEEEEEEEEEEEEEE D
-y 53732# 240643t 32 o a sas 1
C s eB/ 9959938659205e41 t
u eWt 31 691 71 26727 7.O.06 a
0
+
c
(
m t -c 2
y a
e u 52f 11 176f 8222344 ig
- m D
R
(
7 G
/ 4444454664444444 o
F w
O 0000000000000000 O
F-t
)
l y
e t
c - - - - - - - - - - - - - - - -
o n
y EEEEEEEEEEEEEEEE r
W m
eV/
09057284t 959759t o
D e u v d 6755046053294364 e
+
l l
(
n 359340439061 2674 t
I s
A b P d
m 62121 2871 1 233345 e e e
t R
a o - (
e B
e T e t
t
)
i t
dss i
eur 0421 634435539350 S
9031 1 437231 091 nl e 1 1 n
idt 6977074469655545 do 2334 ~
o i
Nee 1
F Rm w
(
d d-y ed
'te r
t n) r eus t or 042t 634435538350 B
a d
rSe 1 1 90311 437231 091 6977074469655545 t
t n
see 1 2334 g
u eem o
rr(
nA B
Jt n
e so urt t
it EEE EEE WWW wWW i
wc NNNNESSS55SSweNN y
s 4
E E
S 5 W W
N e
S s
9 I
wr oi e
DD p
y y
l 9
i tR. ' ' L (i
i4 7j a Il 1r t
T
,y
7 I
'MM
.em u
Om t
e4 E
O >4 I
H guj I
$4HQ
$2 faf. P3 memme...cMmenMme 0000000000000000 a
W "R e 8. %. *$. $ O. e n S. X
..n..n m
. 5~-
.cc-n s
b i 8 AAAAadaes-Juesii M
i 5 8.88.8.8.5.3.58.8.88.8.8.88 u
04 ** *
.f * *
- x*WW s 1
- I.*E.3.g *5 2.".
.S.g *E.E.X.E..
u o
o n
n e n n n v.>..eer
> enn a
y u
a t
it d e u,.: X' d a J, A s i a a A
- a E
.e 0 0 -.. n.. n. n.. S,e-W II
-nnn.
m
=
8.8,888.835.8.8.8.88.888 e
6
.o "
g O
n-Be$NINE**"*8noe8.8eNNE.N*
$U $
~3
~
$E6
-c g
e 6
- 3. Is8n---. n--en-nnnnn 8
F w
w
- nnnen.....nnemee g
0000000000.000000 6
d' a
a a
6 0 6
- W"WWWWWW WWW 1 5.4 WW*H Es s:8s :::
g b l a:
mA S > 4 *.:.:
- d.: ' d i d a d s d i.
R
.h ak
&~
g.
Ut a
eereOr..N.,E.E.R*"S,9-9 352" :
u cc e
II-
-ann m
c.
. =.
.s 1
b.
e O R' W 4 4 W W W 4 4 4 ' d 18 "5 = d 4 4.:
D,.-
C
.eerOc.-.n.,e.n-S.c
- e. n u
ce
-nnn g.
ggg p.
=
g-
~
h..
e z..>
II.wm weWemmeg3 2
y g.
m O
.o
?j
".i
_W 6
MM em O@
e4 2ON H DG W *C eA 8%
a: n nnnnnnewwnnnnnNn 0000000000000000 au tx 6 wwwwwwwwwwwwwwww e n - p g o b *O n c e m e nn e e n e e - n N an
- e
-e-eehen g
ee%
e0-O. e. @. w. O.. e. e. N. w. e. n. n. n.. n.
T e u a 3
-9weweeenne=*-**
y w
4 e
N Nnnnnnevvmennnnn 0000000000000000 2
a L
g wwwwww8w*wwwwwwww n O - en o n Ot wnCe m e n w w o v o w w w e n w n. e 0
e0%
n
> c w
n, t T. w. t. n. *. O. b. O. n. w. w. w. n. w.
e e w
a.
M t
=emew-senwe**---
e N
w W
O O w N - e n,...encemenco u
Ls6 U
O-e
- pon*-TnbNn-Oe--
I, o p t-h o k e w e e e c e e v e e
N
-nnne e
N ae w
888.88.55558888.888 GQ N
e O
u em6 wwwwwww wwwwwwww O
M mee Omese->
m e n. n en n e e C
ees e sc e o n e - h e r n n e O en n.=.e. c.e n.e..w o. n.e o. n.n. e.
e N
.e. >-
y u
vE e 3 en-n-enne-Nnnnnn
=.e N
a -
N MnnnMwwwwMnnMann O
N 0000000000000000 Q
Q o
0 b
LA wWWwwwwwWWwwww w W
l E>s -monn-eOwecen8 m g
g
> V
= e n c o n n e n e en t-e w
I e. c. e. n. e. n. a c. e. n. m. e. nn. e. n. e.
e -
I O
g n-n-own--nnnnev H
M g
e M
D:
Q Ng i.a p Own-engwnnemenco e
Hy st - - c o n a - e n,- n n - O e.
N
-V*
eem>05**eeoem0ee
'C Eeg
-nnne ee4 E.
N V
e a
U m
L 6
Owneenwwnmensinec e
1 Lee
--eon *=wn>nH=Oc*
e e 6 t-O 6 *
- e e e e e e v W g
D mo@
annT C
eea D
NA*
5[
O A
E-*
www www DDD DD u
2222WedeWedeD Eg y
6 Z w w e e D
,4 LO O
e 4-e O
- k