ML20127C931
| ML20127C931 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/31/1985 |
| From: | Maxwell D, Scott D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 85-646, NUDOCS 8506240067 | |
| Download: ML20127C931 (119) | |
Text
OPERATING DATA REPORT DOCKET NO. 050-237 l
DATE June 1, 1985 COMPLETED BY D. C. Mamml1 TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.
Unit Name:
Dresden II 2.
Reporting Period:
May, 1985 3
Licensed Thermal Power (MWt):
2 527 4.
Nameplate Rating (Gross MWe):
828 5
Design Electrical Rating (Net MWe):
7N 6.
Maximum Dependable Capacity (Gross MWe):
812 7
Maximum Dependable capacity (Net MWe):
772 8.
If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give Reasons:
N/A
{sp.%.dA.;. 3 - : s..
r,, s.
v.
. e.,
.. ~
r 9
Power Level to Which Restricted, If Any (Net MVe): N/A 10.
Reasons For Restrictions, if A,y:
N/A This Month Yr-to-Date Cumulative 11.
Hours in Reporting Period 744 3,623 131,927 12.
Number of Hours Reactor Was Critical 655.8 1,122.8 99,858.7 13 Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 590.8 993.2 98,302.9 15 Unit Reserve Shutdown Hours o
o 0
16.
Gross Thermal Energy Generated (MWH) 1,282,531 1,997,344 193,335,402 17 Gross Electrical Energy Generated (MWH) 408,326 629,126 61,850,467 18.
Net Electrical Energy Generated (MWit) 366,017 563,900 56,432,526 19 Unit Service Factor 79.4 27.4 74.5 20.
Unit Availability Factor 79.4 2/.4 14.5 21.
Unit Capacity Factor (Using MDC Net) 67.2 20.9 57.4 22.
Unit Capacity Factor (Using DER Net) 65.3 20.3 55.8 23.
Unit Forced Outage Rate 20.6 13.4 11.2 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Snubber inspection - 6/22/85 - weekend outage.
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
N/A
~
.s.
8506240067 050531 gDR ADOCK 05000010 PDR Ibkh ///
I OPERATING DATA REPORT DOCKET NO. 050-249 DATE June 1, 1985 COMPLETED BY D. C. Shxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.
Unit Name: Dresden III 2.
Reporting Period:
May, 1985 3
Licensed Thermal Power (MWt):
? 527 4.
Nameplate Rating (Gross MWe):
A>q 5
Design Electrical Rating (Net MWe): 7 31 6.
Maximum Dependable Capacity (Gross MWe): 819 7
Maximum Dependable Capacity (Net MWe):
773
~
8.
If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give Reasons:
N/A
},. e ;
- ? v.,p
.:.:.r..
.-,.e c..,
.m
,, ~
9 Power Level to Which Restricted, if Any (Net MWe): N/
10.
Reasons For Restrictions, if Any: 9: r A This Month Yr-to-Date Cumulative 11.
Hours in Reporting Period 744 3,623 121,512 12.
Number of Hours Reactor Was Critical 691.4 3,374.7 93,232.i 13 Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On Line 659.6 3,302.0 86,474.1
' ~ ~
-15 Unit Reserve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH) 1,465,505 7,485,917 1/4,543,000 17 Gross Electrical Energy Generated (MWH) 460.943 2,380,94/
56,58/,924 18.
Net Electrical Energy Generated. (MWH) 43/,442 2,268,212 53,604,442 19 Unit Service Factor 88.1 91.1 71.2 20.
Unit Availability Factor 88.7 91.1 11.2 21.
Unit Capacity Factor (Using MDC Net) 16.1 81.0 57.1 22.
Unit Capacity Factor (Using DER Net) 74.1 78.8 55.6 23 Unit Forced Outage Rate 1.4 8.0 12.6
~
~ 124.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling and recire, piping replacement outage - Fall of 1985 - 6 months.
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
N/A o.
.e t
s
COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF May, 1985 9
HOUR MAXIMUM DAILY LOAD DAY ENDING KW 1
0700 757,300 2
0200 754,700 3
0 4
2400 296,600 5
2400 612,400 6
2300 1,082,500 7
2400 1,235,300 8
2400 1,366,500 9
2100 1,508,200 10 2400 1,536,400 11-0100.
1,489,700 J
12 2400 1,421,000
',495,400 l
13-2100-14 1200
-1,487,600
'1,487,900 15:
2400-p x
16 2400 N
1,'521,700 17 0700
~
1.555,700 1s>
, ' '01Cd (4 1,514,900 -
14 -
2400
' ] 733 g 00 "',
20 ~
, 2100 "
_, > 1',253,100
~._.p
,.,~n
);2400 ,,
1g83, Jp0 e ** v 21 a
e\\
(,
~2400 /,
1,508,700 ge r
22-s 2 -
2,y -
,1 1710 5
,s 1.,584,000,3,
1,530,604'-
t T
.;ja 17% '
3 37, yj f6100,j; 1,513,900 g
1,412,1QU
gyJ y
t lt
'2e:) 1 1800mq p._.
, 7.
,1-27
~220o 1,395,600
^ -
y
-p
, :. %'r 28 2000 1,504,900 1900 1.557,900
, jw ',
29-30 v,0100 1,554,000 I i
\\,. j:.
n.n 4
73..
31-ag { 2200 1,Mf/,600 R g
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DOCKET NO. 050-237 UNIT NAME Dresdan II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE June 1, 1985 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT HONTH May, 1985 METHOD OF LICENSEE CAUSE & CORRECTIVE NO.
DATE' TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEN COMPONENT ACTION TO (HOURS)
DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE
'l 85-05-02 F
95:55 H
2 85-023-0 High Hotwell - 1530F.
(95.9) i
- 3. Turbine control valve fast 2
85-05-18 F
57:17 A
3 85-026-0 (57.3) closure during surveillance.
i l
i I
s 1
2 4
3 F: Forced Reason:
4 Method:
Exhibit G-Instructions for 8: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (
) File D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & License Examination F-Administrative 3
G-Operational Error H-Other (Explain)
.- ~
DOCKET NO. 050-249 UNIT NAME Draedan III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE June 1, 1953 COMPLETED BY D. C. Maxwell i
TELEPHONE (815) 942-2920 REPORT MONTH May, 1985 METHOD OF LICENSEE CAUSE & CORRECTIVE NO.
DATE' TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS)
DOWN REACTOR 3 REPORT F CODE 4 CODE 5 PREVENT RECURRENCE t
None i
I i
i l
l 1
4 l
i 1
2 3
4 i
F: Forced Reason:
Method:
Exhibit C-Instructions for 8: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (
) File D-Regulatory Restriction 4-Other (Explain)
(NUREG-Ol61)
E-Operator Training & License Examination
]
F-Administrative j
C-Operational Error i
H-Other (Explain)
+
i
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 UtilT II DATE June 1, 1985 i
COMPLETED BY D, C. Maxwell TELEPHONE 815/942-2920 MONTH May, 1985 i
DAY-AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
I 724 17 768 2
130 18 102 3
0 19 0
4 0
20 136-f:
5 0
21 489 6
ns 22 631 7
428 23 737 8
699-24 717 9
688 25 565 10 721 26 '
660 11 750 27 683 12 642 28 703 13 735 29 7s1
-14'
-754 30 738 15 757 31 725 16 763 5
i i
-, ~....., _.., _.. _., _ _ _ _ _ _ _.
i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-249 UtilT IIT' DATE June 1, 1985 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH May, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
(MWe-Net) 1 0
th 664 2
0 18 714 3
0 19 668 4
65 20 731 5
468 21 749 6
636 22 758 7
587 23 755 8
640 24 683 9
687 25 688 10 720 26 663 11 646 27 669 12 663 28 690 13 667
- 29 734 14 654 30 708 15 655 31 712 16 664 W-eg,t w
'h
- ""E=+
4 J*-4 y
w.
A
=
-4 e
i DRESDEN UNIT 2
SAFETY RELATED MAINTENANCE - MAY, 1985 i
LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
' D/U to SBGT Air Preventive W.R.
- 36843 N/A N/A Checked and found SBGT air outlet valve Outlet 2-2599-5B ok.
B Shutdown Cooling Preventive W.R.
- 36983 N/A N/A Investigated and found nothing wrong.
Purp 1002-2B Local Control j 125 VDC Ground Corrective W.R.
- 38136 N/A N/A Rewired circuit #16 ground wire.
U-2 R:rctor Head Preventive W.R.
- 38053 N/A N/A Removed Rx head dryer and separator prior to refuel outage.
U-2 R: actor Head Preventive W.R. #38052 N/A N/A Replaced Rx head dryer and separator after refuel.
Annunciator 902-8 Preventive W.R. #39048 N/A N/A Investigated and found nothing wrong.
B-9 125V Battery Chrrg:r 2A Trip 2A SBLC Pump Corrective W.R.
- 39006 N/A N/A Repacked 2A SBLC piping.
Clcca 1 Piping Preventive W.R.
- 38490 N/A N/A Welded crowns on selected Class 1 piping U21d ground for the ISI inspection.
Torus Drain X313 Preventive W.R.
- 38624 N/A N/A Removed and reinstalled blind flanges A&B Flanges on the torus drains during the refueling outage.
N/A N/A Cleaned, greased and closed hatch.
D/U Equipment Preventive W.R.
- 31300 Hatch U-2 Accumulator Corrective W.R.
- 31407 N/A N/A Disassembicd and inspected valve -
46-31 (M-8) working properly.
A02-220-46 Preventive W.R. #31485 N/A N/A Changed limit switches.
r DRESDEN UNIT 2
SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Accumulator 18-23 Corrective W.R.
- 32599 N/A N/A Disassembled, inspected and tightened fittings.
M02-2301-10 Corrective W.R.
- 32618 N/A N/A Disassembled, repaired and re-asse' bled m
valve.
Oxyg:n Analyzer Preventive W.R.
- 35126 N/A N/A Inspected and cIcaned oxygen analyzer -
ok.
MSIV 2-203-2C Preventive W.R.
- 35159 N/A N/A Cleaned, lubricated and adjusted packing.
MSIV 2-203-10 Preventive W.R.
- 35160 N/A N/A Lubed stem, guides, and adjusted packing.
MSIV 2-203-1A Preventive W.R.
- 35161 N/A N/A Lubed stem, guides, and adjusted packing.
MSIV 2-203-1B Preventive W.R.
- 35178 N/A N/A Lubed stem, guides, and adjusted packing.
MSIV 2-203-IC Preventive W.R. #35179 N/A N/A Lubed stem, guides, and adjusted packing.
MSIV 2-203-2A Preventive W.R.
- 35180 N/A N/A Cleaned stem, guides, and tightened packing.
MSIV 2-203-2B Preventive W.R. #35181 N/A N/A Cleaned stem, guides, and tightened packing.
MSIV 2-203-2D Preventive W.R.
- 35182 N/A N/A Cleaned stem, guides, and tightened packing.
B Elcctromatic Corrective W.R. #35188 N/A N/A Replaced electromatic valve.
Ralief Valve 2-203-3B C Elcctromatic Corrective W.R.
- 35189 N/A N/A Replaced pilot valve.
Roliaf Valve 2-203-3C
T DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-D Electromatic Corrective W.R.
- 35190 N/A N/A Replaced electromatic valve.
Ralicf Valve 2-203-3D 2-203-3E Electro-Corrective W.R.
- 35191 N/A N/A Replaced pilot valve.
matic Relief Valve 2-220-1 Valve -
Preventive W.R.
- 35439 N/A N/A Lubed stems and adjusted packing.
Main team Line Drain 2-220-2 Valve -
Preventive W.R.
- 354,41 N/A N/A Lubed stem and adjusted packing.
Mainsteam Line Drains Wcst Torus Manway Preventive W.R.
- 35451 N/A N/A Installed inner gasket - closed cover.
1600 Targat Rock Corrective W.R. #35498 N/A N/A Replaced target rock valve.
2-203-3A Valve D-2 Target Rock Preventive W.R.
- 36190 N/A N/A Installed 0-ring, b6nhet, and torqued 2-203-A belts.
D-2 Rx Shield Preventive W.R.
- 36193 N/A N/A Installed shield blocks.
Blocks U-2 Torus to D/W Preventive W.R.
- 36424 N/A N/A Checked and adjusted vacuum breaker limit V cuum Breakers switches.
2-1600-32233 U-2 DC Motors Preventive W.R.
- 36436 N/A N/A Inspected brushes.
Rx Head Vents Corrective W.R.
- 36713 N/A N/A Tested solenoids and changed out 220-46 & 47 diaphrans.
DRESDEN UNIT 2
SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l
Cora Spray System Corrective W.R.
- 36759 N/A N/A Replaced relay coils.
HFA Ralays
~
l Sparca 5, 6, 18 &
19 SRM & IRM Cables Preventiic W.R.
M02-1501-18B Corrective W.R.
- 38048 N/A N/A Replaced valve.
Valva Rx High Pressure Preventive W.R.
- 38537 N/A N/A Installed stainless steel nipples.
Scrcm Switches 263-55A,B,C.D Torus West Drain Preventive W.R.
Valva 2-1699-58B N/A N/A Tested check valve.
In trument Line Preventive W.R. f39123 Flow Check Valve 2-263-2-17B Instrument Line Preventive W.R.
- 39124 N/A N/A Tested check valve.
Flow Check Valve 2-263-2-15B N/A N/A Tested and re-installed check valve.
Instrument Line Preventive W.R.
- 39125 Flow Check Valve 2-263-2-13-2 Instrument Line Preventive W.R.
- 39126 N/A N/A Tested and re-installed check valve.
Flow Check Valve 2-263-2-19A Instrument Line Preventive W.R.
- 39127 N/A N/A Tested and re-installed check valve.
Flow Check Valve 2-263-2-17A
DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQU1PMENT NATURE OF MAINTENANCE NIIMBER CAUSE RESULT CORRECTIVE ACTION Instru=ent Line Preventive W.R. f39128 N/A N/A Tested and re-installed check valve.
Flow Check Valve 2-263-2-15A Tcrus to D/W P-2 Preventive W.R.
- 40804 N/A N/A Replaced 0-rings, nuts and studs.
Vccuum Breakers 2-1601-32A,B,C D, E cnd -33A,B,D,E D-2 Vccuum Preventive W.R.
- 40806 N/A N/A Installed 0-rings and torque tested.
Brcrkars 2-1601-32A-F, 33A-F and 31 A'5 B In:tru=ent Line Preventive W.R.
- 39129 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-263-2-13A Instru=ent Line Preventive W.R.
- 39130 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-263-2-11 Instru=ent Line Preventive W.R.
- 39131 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-262-2-6B Instru=ent Line Preventive W.R.
- 39132 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-262-2-5B Instrument Line Preventivt W.R.
- 39133 N/A N/A Tested and re-installed valve.
Flow Chsck Valve 2-262-2-6A
DRESDEN UNIT 2
SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION In:trument Line Preventive W.R.
- 39134 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-262-2-5A Inctrument Line Preventive W.R.
- 39135 N/A N/A Tested and re-installed valve.
Flow Check Valve 2-220-5A Torus Vacuum Preventive W.R.
- 39163 N/A N/A Installed 0-rings, greased and bolted Brenkars lid down.
Bulk Torus Water Preventive W.R.
- 39223 N/A N/A Watched recorder - no problem found.
Tcmperature P-9-2-1640-2003 Shutdown Cooling Preventive W.R. #39237 N/A N/A Installed new stack and cycled motor.
Diccharge Valve 2-1001-5A Rocctor Wide Preventive W.R.
- 39240 N/A N/A Checked calibration and back-filled.
Rango GEMAC Air Operated Rx Corrective W.R. f39243 N/A N/A Installed new diaphrams and tightened Head Vcnts fittings.
2-220-46-47 D-2 250V Battery Correct ive W.R.
- 39276 N/A N/A adjusted chargers to proper voltage.
D-2 1A MSIV Inlet Corrective W.R.
- 39341 N/A N/A Tightened locknut.
Stcra Line Rod Out Block Preventive W.R.
- 39374 N/A N/A Repaired connector and cleared jumper.
Light D/U Vcnt and Purg(
Corrective W.R. f39396 N/A N/A Installed new rubber seat and retaining A02-1601-22 ring.
l l
DRESDEN UNIT 2
SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 0-2 0/G Fuel Oil Preventive W.R.
- 39426 N/A N/A Moved indicator to outside Pump Room.
Storcga Tank Ind.
2-5241-11 A02-1601-55 Corrective W.R.
- 39454 N/A N/A Rebuilt air operator.
2-202-57A Valve Corrective W.R.
- 39476 N/A N/A Replaced drive nut and bearings.
D-2 203-MSIV-1-B Preventive W.R.
- 39477 N/A N/A Replaced block and valve assemblies.
Auto Blowdown Preventive W.R.
- 39478 N/A N/A Lamped out wires, cut off plugs and Syctca Wiring removed wires.
Torus Hatch Preventive W.R.
- 39487 N/A N/A Inspected torus - all ok.
HPCI Tc=perature Preventive W.R. #39536 N/A N/A Replaced and calibrated switch.
2-2370D Switch Set Pump Flow Preventive W.R.
- 39554 N/A N/A Installed and removed temperature In c. Drain Line hoses.
2-263-239A and 403 All Rods In Preventive W.R.
- 39618 N/A N/A Jumpers removed - retrned to normal.
Intcriock LPCI H;at Corrective W.R.
- 39689 N/A N/A Installed plugs.
Exchsnger 2A-1503 (A)
RWCU Lcvel Trips Preventive W.R.
- 39715 N/A N/A Installed and removed jumper.
Outbosrd Feedwater Corrective W.R.
- 39757 N/A N/A Re-installed valve internals - replaced Ch ck Valve seal internals and 0-rings.
2-220-62A (A)
DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - MAY, 1985 il LER OR OUTAGE mal. FUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION RBM #8 Preventive W.R.
- 39869 N/A N/A Replaced and calibrated meter.
- 40031 N/A N/A Checked and replaced coil and auxiliary S:t Br aker contacts.
7 "B" Prm.
Preventive W.R.
- 40032 N/A N/A Replaced fuse.
Channal Hi V61t P.S. 2-1705 Stcndby Gas Treat-Preventive W.R.
- 40071 N/A N/A Removed canister and blind flange.
ment System Char-coal Filters Standby Gas Preventive W.R.
- 40072 N/A N/A Removed canister sent to be analyzed.
Trcitment Char-cos.1 Filters Rx R cire. System Preventive W.R.
Sida Rx R: circ. System Preventive W.R.
d40081 N/A N/A Replaced decon flange - installed new Decon Flange B gasket.
Sida IRM Chrnnei 11 Preventive W.R.
- 40084 N/A N/A Replaced pre-regulator.
U-2 250 Charger Preventive W.R.
- 40228 N/A N/A Replaced fuse - tightened connections -
all ok.
DRESDEN UMIT 3 SAFETY RELATED MAINTENANCE - MAY. 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION SRM #22 and 23 Corrective W.R.
- 39654 N/A
';/ A Replaced SRM #22 and #23 monitors.
Div. I Torus Preventive W.R.
- 40507 N/A N/A Tightened contacts and re-calibrated TE1641-205 Te=p.
Div. I torus temperature recorder.
R: cord;r LPRM 48-09C Level Preventive W.R.
- 40801 N/A N/A Re-calibrated LPRM 48-09.
LPCI H2at Exchan-Corrective W.R. #38698 N/A N/A Re-calibrated CCSW 3C and 3D pumps and g;r CCSW Flow apolled anti-stat. to contacts.
Meter (B Loop) 3-0540-1B LPRM 32-09B Gr. 2 Preventive W.R.
- 37926 N/A N/A Re-calibrated LPRM 32-09B.
Torus Level Ind.
Preventive W.R.
- 37917 N/A N/A Re-calibrated torus level indicator 1602-3 1602-3.
U-3 Turbine Modification W.R.
- 34652 N/A N/A Repairs made per traveler #7.
U-3 Scram Pilot Preventive W.R. #27766 N/A N/A Overhauled valves - replaced coils - all ok.
Valves A TIP Ball Valve Corrective W.R.
- 40885 N/A N/A Repaired spring - working properly.
- 40906 N/A N/A Conpleted DIP 700 13 and 15 - all ok.
- 40908 N/A N/A Completed DIP 700 13 and 15 - all ok.
M03-2301-10 Valve Preventive W.R.
- 40930 N/A N/A Re-installed key, pinion gear and motor -
all ok.
Rx Bldg. Inter-Preventive W.R.
- 40947 N/A N/A Taped up wire insulation.
lock Door
DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - MAY, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION APRM Channel 3 Preventive W.R. f40954 N/A N/A Replaced K looks good.
EPCI Booster Preventive W.R.
- 40957 N/A N/A Tightened coupling bolts and greased.
Pu=p EPCI Main Pu=p Preventive W.R. f40966 N/A N/A Replaced coupling - installed new keeper and plate.
HPCI Cast Oil Preventive W.R.
- 41050 N/A N/A Removed filter and cleaned 5 cleans.
Filter Accusulator 30-51 Preventive W.R. #41082 N/A N/A Replaced male adapter and cap.
Prcssure Tap Torus Level Wide Preventive W.R.
f41099 N/A N/A Checked calibration of alarms - all ok.
Rang 2
i DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - MAY. 1985 l
r LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION j
SBCT B Heater Preventive W.R. #31265' N/A
.N/A Burnished relay contacts and' adjusted.
[
"CT" Contact contact wire.
[
7541-485 t
?
N/A N/A Replaced terminal blocks and fuse holders.
Standby Gas Treat-Preventive W.R. #34741 ment 2223-288 l Computer UPS 250V Preventive W.R. #3573f-N/A N/A Set float voltage to required level.
Battery N/A N/A Replaced magnetic ASM's and addition of "A" SBGTS Logic Preventive W.R. #36717 (Slaves 1-11) coil.
'f 1
I I
i I
i
UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period of May, 1985 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circum-stances resulting in its actuation.
Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2
05-01-85 to 05-31-85 None 3
05-01-85 to 05-31-85 203-3C 1
Low Actuated 5-3-85 Pressure to verify alarm 1
annunciated correctly.
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1 4
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t 6
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SUMMARY
OF OPERATING EXPERIENCE UNIT TWO MAY, 1985
'05-01 to 05-06 Unit 2 entered the month operating at a power level of 755 MWe and operated until 0535 hours0.00619 days <br />0.149 hours <br />8.845899e-4 weeks <br />2.035675e-4 months <br /> of May 2nd, when the unit was manually scrammed by the NSO because of a high Hotwell temperature of 1530F.
Several off-gas fires had been occurring and the NSO correctly manually scrammed the Reactor to prevent any possible off-gas problems. The Maintenance Departments completed "arious pump and valve planned work and also performed recated shutdown surveillances.
The Reactor was brought ccitical on May 4th at 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> and the turbine was syrebronized to the system at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> of May 6th.
05-06 to 05-18 The unit operated continuously, reaching a power level of 803 MWe, until 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> of May 18th, when a Reactor scram and Turbine trip occurred because of fast closure of the #3 control valve during surveillance.
05-19 to 05-31 The Reactor was brought critical at 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> of the 19th and the Turbine was synchronized to the system at 1347 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.125335e-4 months <br /> of the 20th. The unit operated continuously during the remainder of the month reaching a power level of 790 MWe with an availability of 79.41% and a capacity factor of 65.76%.
i
)
i
SUMMARY
OF OPERATING EXPERIENCE UNIT THREE MAY, 1985 05-01 to 05-03 Unit 3 was off-line and in the shutdown mode to repair the feedwater heaters and to take recirculation pipe measurements.
05-03 to 05-31 The Reactor was brought critical at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> of the 3rd and the Turbine was synchronized to the system at 1227 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.668735e-4 months <br /> of the 4th.
Unit 3 operated continuously the remainder of the month (with normal power reductions for weekend surveillances) reaching a power level of 795 M'Je with an svailability of 88.65% and a capacity factor of 74.42%.
i 1
ODCM REQUIREMENTS Revision to the Off-Site Dose Calculation Manual Amendment No. 83 to Provisional Operating License No. DPR-19 for Dresden Unit 2 and Amendment No. 77 to Facility Operating License No. DPR-25 for Dresden Unit 3 were issued by the Nuclear Regulatory Commission (NRC) in 3
l November, 1984, and became effective March 15, 1985. The amendments consisted of changes to the Technical Specifications for Units 2 and 3 developed for the purpose of keeping releases of radioactive material to unrestricted areas during normal plant operations, including expected operational occurrences, as low as reasonably achievable.
In its review process of the amendments, the NRC contracted EG6G Idaho, Inc., to perform a Technical Evaluation of the proposed Technical Specifi-cation changes. The revised sections of the Technical Specifications were prepared to ensure that the Dresden Station Technical Specifications were in conformance with the NRC staff's model Radiological Effluent Technical Specifications (RETS) for BWR's, NUREG-0473, Revision 2. February 1, 1980.
- In a letter to D. L. Farrar of Commonwealth Edison Company, dated November 16, 1984, the NRC staff documented their approval of the proposed RETS. In addition, since the Commonwealth Edison Company Off-Site Dose Calculation Manual was provided to the NRC staff as a reference document in support of the RETS submittal, the NRC reviewed this document as well, and j
in the same letter made the following comments:
" Based on our review, as supported by a Technical Evaluation performed by our contractor EG&G Idaho, Inc., we conclude that the proposed Radiological Effluent Technical Specifications (RETS) meet the intent of the NRC staff's model RETS for BWR's, NUREG-0473. Revision 2, February 1, 1980.
In addition, you have provided as a reference document in a submittal dated March 1983, I
an "Off-Site Dose Calculation Manual" (ODCM). We find that this j
ODCM generally uses documented and approved methods that are con-sistent with the methodology and guidelines in NUREG-0133 and, therefore, is an acceptable reference. Discrepancies found in our review should, however, be corrected within the next 90 days in the next revision of the ODCM."
i The discrepancies referred to above with respect to the ODCM were further delineated in the Technical Evaluation Report received as an attachment f
to the November 16, 1984 letter.
In response to the identified discrepan-cies, Commonwealth Edison Company revised appropriate sections of the ODCM and incorporated these changes into Revision 11 of the ODCM. Revision 11 was reviewed at Dresden Station through the On-Site Review process, and accepted for implementation on March 29, 1985.
l Pursuant with Section 6.8.B. of the newly-adopted revised Technical Specifi-cations for Dresden Unit 2 and Dresden Unit 3, the documentation is provided in this Monthly Operating Report in support of the adopted changes to the ODCM.
1 I
i
1 l
_2-L 1.
Attachment A: Response to NRC November 16, 1984 comments on Dresden ODCM.
i 2.
Attachment B: Dresden Nuclear Power Station (DNPS) On-Site Review Forms for DOSR 85-7.
I 3.
Attachment C: Copy of ODCM, Sections 7.2 and 8.0, Representing Revision 11.
l l
l l
l i
l
s Attachcant A Draft 2 11 arch 21,1985 Page 1 of 3 RESPONSE TO NRC NOVEMBER 16, 1984 CO?O;ENTS ON DRESDEN ODCM O
%e 4
o
DrOft 2 March 21, 1985 Pcga 2 of 3 Comment
Response
1.a.
The dose rate to an adult Inhalation dose rate to an (instead of a child) via infant has been substituted the inhalation pathway is for inhalation dose rate to used to assure that the an adult.
The infant dose limit of 1500 mrem / year in rate is comparable in magni-I Specification 3.8.A.I.b is tude to the child dose rate.
not exceeded.
Because of the nature of existing computer software, the change to infant can be-implemented more readily s
than a change to child.
1.b.
The dose projections to The text has been revised determine when to use the to include a procedure for liquid waste treatment dose projection.
See Sec-system, required by tion 2.2.1.2 (p. 2.2.-3) of Specification 4.8.D.3, are Rev. 11.
not included.
2.
The ODCM description'for The ODCM description has been the main chimney's noble revised to be consistent with gas monitoring system Table 3.2.5 of the Technical appears to be inconsistent Specifications.
See Sec-with Table 3.2.5 of the tion 8.1 of Rev. 11 of the Technical Specifications.
ODCM.
3.
The listing of sampling Sampling of public water is locations in Table 8.4-1 no longer required.
See does'not include samples Table 4.8.4 of Amendment 83 of public water from two to the Dresden 2 Tech locations as requred by Specs and Table 4.8.4 of Table 4.8.4 of the pro-Amendment 77 to the Dres-posed RETS.
den 3 Tech Specs.
4.
The 42 TLD location's are The title of Fig. 8.4-1 has not identified in been revised to indicate that Figures 8.4-1 or 8.4-2.
there are TLD's at the fixed air sampling sites.
- Also, the number designating location 13, which was inadvertently omitted, has been added.
There are actually 43 TLD locations, which are shown as followsi e
Fig. 8.4-1 shows 17 TLD locations at' fixed air sampling cites and 16 outer ring locations.
Droft 2 March 21, 1985 Pcga 3 of 3 Comment
Response
4.
(Cont'd) e Fig. 8.4-2 shows 10 inner ring locations.
5.
The maps of Figures 8.4-1 Figures 8.4-1 and 8.4-2 have and 8.4-2 do not include been revised and Figure 8.4-3 the environmental sample has been added so that all locations 17 through 38 environmental sampling locations in Table 8.4-3.
are now shown.
6.
Block diagrams are not These diagrams have been included showing:
the added.
See Figures 8.1-1, i
liquid and gaseous rad-8.1-2, 8.2-1, and 8.3-1.
. waste treatment systems, the liquid and gaseous rad-waste release pathways, or the solid radwaste system.
7.
The value for the fish The fish population of the consumption rate on Illinois River is low so the page 7.2-1 should be re-NRC Staff earlier agreed to evaluated.
allow use of a fish consumption rate lower than that in Regulatory Guide 1.109.
l a
+
De e
e The Licensee's proposed RETS for Creseen Station Cnits 2 and 3 submitted Stay 3,1984 meets the Intent of the NRC staf f's
" Standard Radiological Effluent Technical Specifications for Boiling Water Reactors," NUREG-0473.
The Licensee's 00C:1 reculved by the NPC April 19, 1983[23]
e generally uses documented and approved methods that are consistent with the methodology and guidelines in NUREG-0133, with the fqllowing exceptions:
l 1.
The outstanding issues noted in references 24 and 25 that apply t'o the generic Sections of the CEC CCC:'. The most significant of these issues are:
a.
The dose rate to an adult (Instead of a child) via the inhalation pathway is used to assure that the limit of 1500 nren/ year in Specification 3.e.A.1.b is not
- exceeded, i
4 b.
The dose projections to deterni,e when to use the IIqu!d waste treatment system, equired by Specifiestion 4.8.E.3, are not included,.
2.
The COC'2 description for the main chinney's noble gas monitoring system appeers to be incenststent with Table 3.2.5 of the Technical Specifications.
3.
The listing of sarpling Iccations in Table f.4-1 does not include senples cf public weter fron t.o Iccations as required by Table 4.e.4 of the prepcsod FETS.
4 The 42 TLD Iccations are not identified in Flcures 2.4-1 or 6.4-2.
5.
The caps of Figures !.4-1 snt 5.J-2 do not includo !!e environrental serple locations 17 ti rcush It Ir. 73tle f.J-7.
27
6.
Block diagrams are not included showing: the liquid and gaseous radwaste treatrent systems, the liquid and gaseous radwaste release pathways, or the solid radweste system.
7 The value for the fish consunption rate on page 7.2-1 should be reevaluated.
s
~*
e The Licensee's proposed PCP submitted tr y 3,1984 meets the a
Intent of the !!RC's present guidelines.
A correspondance between (a) NUREG-0473, (b) the Licensee's current RETS, and (c) the Licensee's proposed RETS is shown In Table 1.
T 9
9 G
e
[
28
DAP 10-1 i
Attachment B Revision 6 (RESDEN NUCLEAR POWER STATION ASSIGNMENT FORM Date Assigreent Made 3/19/85 Assigned Review Naber 85-7 SLBJECT TO BE REVIEWED:
In conjunction with the recent irplcmentation of the RETS (Radiological Effluent Technicc.1 Specificaticas), the IMC noted that certain discrepancies in the 00C4 (Off-Site Dose Calculation Manual) as identified by their review
'needed to be corrected. The purpose of this review is to examine the proposed changes, jointly cmpleted by S & L, TSN and Dresden Station personnel, to ensure they are consistent with station programs and other procedures.
PERSONNEL ASSIGNED TO MAXE REVIEW AND INVESTIGATION:
T. Ctesla h7PP, I 8 C, $4 & FS J. Brunner NPPP, T & C. M & ES hoe Discipline Name
. Discipline S. Mcdonald R&C name Discipline Name Discipline j
DATE FIIE)INGS AND REC (PtMENDATIONS ARE TO 8E REPORTED:
3/28/85 DATE REVIEW IS TO 8E COMPLETED:
3/26/85 1
/ SMb s7/^
5dpErinteyceryp -
~
Dresd,en lluc1Mr Power Station
~
DISCIPLINES:
IFFT - Ikclear Power Plant Technology
. AD
- Reactor Operations RE
- Reactor Engineering RSC - Radiation Protection and Control I4C - Instraeritstion and Control M&E5 - Mechanical and Electrical Systems g
(Form 10-1A)
,l
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DAP 10-1 Revisica 6 D.O.S.R. REPORT FORM Assigned Review Number 85-7 SUBJECT OF REVIEW:
The purpose of this review was to examine changes to Sections 7.2 and 8.2 of the Offsite Dose Calculation Manual (Orni). These sections contain infomation specific for Dresden Station for use in determining offsite doses resulting frtn plant effluent releases. The changes were generated in response to questions raised by the tac through its technical reviewer, EX3 & G, Idaho, Inc., which was contracted to revicw both the ODO! and the Radiological l
Effluent Technical Specifications (RETS) sutrittals.
I l
FINDINGS AND RECOMMENDATIONS:
A meeting was held on Monchy, March 25, 1985 to review the proposed changes to the C001. Attendees included the participants listed below and various subject experts to assist in the review, per DAP 10-1. A list of attendees is included as Attachment C.
t j
As a result of the meeting, the modified sections of the 0001 were detezmined to be acceptable by all individuals present, and the unaninous rectrrendation was to adopt hanges to the OD01.
WRITTEN BY:
__ -[M
~
' ~ (/ a.s. y;c4 FARTICIPANTS:
(tA' O M O.,wyl
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-2 W 'I.% #(ES
\\1J.4Y dse k MC/M, M/ZS 10 la Approved 2
af~
e StTtioySperintendent Date Review Completed 11!I [
'i Attachments: Att. A: Irtter Frcn !EC to D.L. Farrar Dated Nov. 16, 1984.
Att. B: ODCM Rev.fgl,PiWe vevig,?F " c"tTion? DWsT.
Sections 7 2 and 8.0 DatereportsN*th*Su^pNvis58 t
Sc-o e
un Manager-Nuclear Stations and Quality Assurance:
(Form 10-18) 0051c (FINAL) 9 of,
_g
- g y
7' t
t
' '[f
'A*;achanit du.
7.
REVISION 11
' eg e l,
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' MARCH 1985 a~
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' DRESDEN
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.G)CM LIST OF TABLES FOR DRESDEN SECTION 7.2
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ic
, NUMBER TITLE N
's PAGE
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7.'2-1 Aquatic Environmental dose Paran'sters 7.2-1 7.2-20, ~
' Annual Design Objectives Set by 1
i
-10 CFR'50 '
I 4.x Each
),, Wear: tor \\, Appendb:
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s 7.2-3 Staticti_Chiracterfstles ] ^
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7.2-1 7.2-4
.? CriticCnhaages-pA a 7.2-4 7.2-5
',j Urait!!CorrectioS Factors (hg}a >
7.2-5 s
. 7.2 x 1,,' X/Q and D/Q4 Maxista at or Beyof.d t.hp 0 ' "
^ Unresticicted. Area R<.xndsry, Dresden 1, 17.2-6 2
i 7.2-7
' D/Q at' the Nearest Milk. Cow and Meati b Animal % Locations within 5 M!les, Dresden Y X
' (
7.2-8 1-3 7.2-8 g
(Maximum Offsite Finite Pl.ume Gamma Dose Factcra for SelectdNucliders,
'Dresden 1 p3,
).
(,
7.2-9 y
7.2-9
\\
% X/Q and D/Q Maxida at or Beyond the
- \\ g s.
1,hirenricted Arei Moundary, r~
R esden 2/3' 7d-24
?.2-10
, D/Qiat the Nearest: Milk Cow and Meat i
Ss hqimal Locations.Within 5 Miles,
'Diesden 2/3 d
-i 7.2-26 7.2-11
, 4 Maximum Offsite ' Finite Plutte' Garana Dose Factors for Selected Nuclides, Dresder:(2/5 7.2-27 1
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REVISION 11 DRESDEN MARCH 1985 O
ODCM LIST OF FIGURES FOR DRESDEN SECTION 7.2 NUMBER TITLE
- 7. 2 -1 Unrestricted Area Boundary 7.2-2 Locations of Fixed Environmental Radiological Monitoring Stations
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I 7.2-11
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DRESDEN REVISION 11 MARCH 1985 TABLE 7.2-1 O
AQUATIC ENVIRONMENTAL DOSE PARAMETERS
,.8 PARAMETER DRESDEN U", water usage, liters /hr 0.042 I
U, fish consumption, kg/hr 2.4 x 10-4 1/M" 1
a 1/M' 1
F",
ft /sec 4
1.37 x 10 f
F, ft /sec 4
1.08 x 10 o
t',
hr*
24 t", hr *
- 106 By Column 2 for freshwater fish. Regulatory Guide 1.109, Revision 1, October 1 See Table 7.1-12.
D c,
F, ft /sec F",
ft /sec o
1/M Not applicable.
No outdoor tanks without overflow pipes connected y
t, hr o
to other storage tanks.
D V, gal t, hr o
- tf (hr) = 24 hr (all stations) for the fish ingestion pathway
- t" (hr) = 106 (distance to Peoria is 106 miles; flow rate of 1 mph assumed)
- )
7.2-1
.. - - ~ _. _ _ -
DRESDEN REVISION 11 MARC 0 1985 0
3 TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I FOR EACH REACTOR TYPE OF DOSE ANNUAL DESIGN OBJECTIVES Airborne Releases Gamma Air Dose 10 mrad Beta Air Dose 20 mrad G,
Whole Body Dose 5 mram v
Skin Dose 15 mrem
~
Infant Thyroid Dose 15 mram Liquid Releases Whole Body Dose 3 mram Thyroid Dose 10 mram Bone Dose 10 mram Skin Dose 10 mram e
7.2-2 i
L
DRESDEN REVISION 11 MARCH 1985 TABLE 7.2-3 OSTATI0a:oresee# aecie r co er stetio-LOCATION: Morris, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT U1 94.4
~
U1 1.37
- 1) Release Height = _U2/3 95 0 m
- 2) Diameter =
U2/3 3.35 m
U1 14.4
- 2) Exit Speed
= U2/3 21.4 ms'l
- 4) Heat Content =
4E3 KCal s-1 CHARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height -
48 m
- 2) Ofameter =
2.74 m
- 3) Exit Speed 17.6 ms-1
=
C.
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Butiding Factor (D) =
36 m
METEOROLOGICAL DATA A
400 ft.
Tower is Located 800 m
WSW of elevated release point Tower Data Used in Calculations Release Point Wind Speed and Differential Direction Temperature Elevated 300 ft.
300-35 ft.
Vent 150 ft.
150-35 ft.
Ground 35 ft.
150-35 ft.
7.2-3
DRESDEN REVISION 11 MARCH 1985
)
TABLE 7.2-4 CRITICAL RANGES PRACTICAL SITE NEAREST NEAREST DAIRY FARM BOUNDARY
- RESIDENT **
RANGE ***
DIRECTION (m)
(m)
(m)
N 768 1609 NNE 1207 1287 NE 1100 1126 8000 ENE 1244 1244 E
1000 3379 ESE 988 2092 SE 1000 1448 SSE 792 1287 S
841 1126 SSW 853 4988 SW 1024 6114 WSW 1170 3218 W'
1756 4827 WNW 1219 5471 NW 756 1609 NNW 671 1609
- Nearest land in unrestricted area
- Estimated range
- Within 5 miles D
7.2-4
u n
~J TABLI: 7.2-5 TERRAIN CORRECTION FACTORS (h ) - DRESDEN NUCLEAR POWE b
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DRESDEN REVISION 11 MARCH 1985
()
TABLE 7.2-6 (Cont'd)
Dresden 1 AVERAGE WIND SPEEDS FOR 2ACH RELEASE MODE DOWNWIND AVERAGE ffIND SPEED (m/sec)
DIRECTION ELEVATED MIXED MODE GROUND LEVEL N
6.8 5.4 4.8 NNE 6.8 5.1 4.4 NE 6.6 4.9 4.1 ENE 6.4 5.0 4.4 E
6.3 5.4 4.9 ESE 6.2 5.1 4.6 SE 5.9 4.9 4.3 SSE 5.6 4.6 3.9 5
5.6 4.3 3.7 Ssw 5.9 4.7 3.9 SW 5.3 4.2 3.4 WSW 5.1 4.1 3.5 W
5.7 47 4.0 WNW 5.7 4.6 3.6 NW 5.3 4.6 4.0 NNW 6.2 5.0 4.4 C
7.2-7 e
DRESDEN REVISION 11 MARCH 1985 0
00 00000 000.O.mo.
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i TABLE 7.2-8 DRESDEN 1 Itamletes GFFSITE FlestTE PttesE eassen DOSE Facient Fee att e2ee esteeplee MSTRIC7ES ELEVATES (5faCat) SELEASE 085RE0 elesE(VEssT) SELEASE meteep LEVEL eELEASE DISECTISB8 ASEA estem sanswa 3
gaae SADIUS V
WSAA~
eASIt85 8
mat (IE7E85) (IIETEe5) (MAD /ve)/(uct/SEC) 18ETERS) (mao /ve)/(uct/SEC) (IIETESS) (seAp/ve)/(UCI/5EC)
N 995.
995.
3.997-08 3.244-07 695 1.088-04 9.825-08 995 4.897-04 4.300-05 M
8esE S24.
S24.
3.900-06 3.922-07 S24.
2.SS2-04 2.304-05 524.
e.408-04 7.593-05 h
set 400.
488.
4.484-08 4.0e9 07 488.
2.54S-04 2.290-05 488.
9.087-04 e.206-05 t'B Og.
B EDIE 480.
480.
2.542-06 2.290-67 480 1.170-04 1.096-05 400.
S.S43-04 S.005-05 IA
$O E
S38 536.
3.479-06 3.334-07 536.
8.073-04 9.884-06 536.
5.274-04 4.764-05 h
ESE 597.
597.
3.882-06 3.905-07 597.
5.274-05 4.763-06 997 3.739-04 3.376-05 SE 997.
597.
S.143-04 4.SS2-07 597 4.664-05 4.230-06 597.
4.069-04 3.eGS-05 2
SSE S34 434.
4.206-06 3.862-07 S34.
3.486-05 3.148-05 634.
3.374-04 3.047-06 5
953.
SS3.
3.70t-06 3.342-07 eS3.
1.514-05 1.367-06 SS3 1.304-04 9.t78-06 SSW SGS.
SGS.
2.648-06 2.390-07 SSS.
1.727-05 1.960-06 086.
1.310-04 9.190-05 SW 1024 1024 2.493-06 2.252-07 1024 1.269-05 1.144-06 9024.
1.145-04 1.034-06 tf5W 1219.
1219.
2.673-06 2.414-07 1219.
1.110-05 1.003-08 1299.
8.044-05 7.824-06 tt 1994.
1994.
2.792-06 2.449-07 1914 S.812-06 7.957-07 1994.
S.928-05 S.351-OS teet 1329.
9329.
2.338-06 2.t$2-07 1329.
t.918-06 1.732-06 1329.
9.375-04 9.242-05 per 792.
792.
3.350-06 3.029-07 792.
3.101-05 2.000-06 792.
2.415-04 2.le9-06 seaf 870.
878.
2.447-06 2.210-07 878.
S.148-05 4.668-08 e78.
2.e99-04 2.548-06 ORE 5DEte-1 S7TE 8EE7EOSOLOGICAL DATA f/74 12/75 I
a ta -
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90 to E as 1
UI H H
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TABLE 7.2-8 (Cont'd)
ORE 5 DEN 1 tsamleaJet OFFSITE FINITE Ptimet Gasosa DOSE FACTORS FOR ett 85M DoeRaf f te RESTRIC7ED ELEVATED ($f ACM) RELEASE IsixED te00E(VENT) RELEASE DIRECTION AREA souse RADIUS 5
Salk RAOlus W
VSAR~
RADlus GaA2 GSOUse L EVEL Bf L E ASE~
- (ISETERS) (TEETER $ ) (seeAD/vt)/f tJCt/5EC ) (seE TE RS ) (setaD/vR)/(uct/5EC) (seE TERS N
$95 695.
2.956-04 1.577-04 695.
7.855-04 4.084-04 495 2.482-03 1.260-03 IedE 524 524.
3.762-04 2.004-04 524.
1.480-03 7.596-04 524 3.882-03 f.977-03 o
p NE 453.
das.
3.963-04 2.115-04 443.
1.475-03 7.590-04 458.
4.194-03 2.135-03 I
ENE 488.
484.
2.725-04 9.455-04 444.
7.701-04 3.977-04 488 2.592-03 f.32t-03 M
E 536.
536.
3.333-04 1.769-04 536 7.813-04 4.050-04 536.
2.570-03 8.313-03 o
ESE 597.
597.
2.769-04 1.477-04 597 4.820-04 2.516-04 597.
1.495-03 9.696-04 7
pg SE 597.
597.
2.815-04 1.500-04 597 4.656-04 2.435-04 597.
2.063-03 1.056-03
$$E 634 634 2.404-04 1.283-04
- 634, 3.787-04 1.985-04 634.
f.764-03 9.033 04 5
353.
853.
1.558-04 8.294-05 853 2.010-04 1.057-04 e53.
7.697-04 3.968-04 55w 866.
864 3.2s4-04 6.839-05 866 1.925-04 1.009-04 464.
7.as7-04 4.028-04 Sw 1024.
1024 1.285-04 4.470-05 1024 1.675-04 8.819-05 1024 7.409-04 3.822-04 trSw 1299.
8289.
1.964-04 6.995-05 1219.
1.589-04 S.342-05 1219 5.640-04 2.91t*04 W
't914.
1994 7.798-05 4.139-05 1944 1.145-04 6.016-05 1994 4.146-04 2.145-04 WNW 9329.
1329 S.744-05 4.658-05 1329 1.785-04 9.304-05 1329.
8.196-04 4.287-04 NW 792.
792.
2.180-04 1.162-04 792.
3.347-04 1.753-04 792.
1.294-03 6.637-04 todw 373.
878.
1.899-04 1.013-04 878.
4.386-04 2.282-04 878.
1.533-03 7.862-04 ORESDEN-1 SITE IsETEOROLOGICAL DAI A t/74 12/75 A
OH D: CA H
HO eZ co Ue H H
e e.:
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O TABLE 7.2-8 (Cont'd) 04E5 DEN 1 atAztesues DFF51TE FINITE PLUsef CAMMA DOSE F ACTORS foe arR 85 DOWNWitG RESTRIC7ED ELEVATED (5TACM) REL E ASE MisED N00E(VENT) RELEASE GROUDO LEVEL #ELEASE DIRECTION AREA SOUpe RADIUS 5
58AR FAD!us RAOlUS G
G8AR V
veAa (seETE RS) (TEETER 5) (esRAD/va)/(UCf/5EC) (seE TE RS ) (esR AD/vR)/(Oci/
N 695.
495 3.905-06 2.417-06 695.
9.505-06 5.884-06 695.
2.744-05 1.699-05 4
teet 524.
524.
4.965-06 3.073-06 524.
t.767-05 1.093-05 524.
4.382-06 2.669-05 NE 483.
488.
5.262-06 3.257-04 488.
t.765-05 1.093-05 488.
4.670-05 2.899-05 f
ENE 488.
488.
3.589-06 2.222-06 488.
9.239-06 5.719-06 488.
2.881-05 8.783-05 M
Oy e
E 538.
536.
4.380-06 2.7tt-06 536.
9.386-06 5.810-06 536.
2.847-05 f.763-05 m
M ESE 597 597 3.647-06 2.258-06 597.
5.829-06 3.604-06 597.
2.809-05 1.306-05 U
SE 597 597.
3.789-06 2.302-06 597 5.725-06 3.543-06 597.
2.305-05 1.427-05 SSE 634 634.
3.197-06 1.979-06 634 4.708-06 2.914-06 634 1.980-05 f.225-05 5
853
- 853, 2.077-06 9.285-06 853.
2.552-06 1.560-06 853 S.768-C6 5.423-06 55W 866 866.
1.685-06 1.043-06 864 2.415-06 1.497-06 866 S.99F 06 5.570-06 SW 9024 1024 1.687-06 9.003-06 1024 2.115-06 1.309-06 1024 S.638-06 5.347-06 W5W 1219 1289.
1.550-06 9.658-07 12t9 2.041-06 1.263-06 1219 6.568-06 4.065-06 w
1984 1984 f.095-06 6.776-07 1914 l.503-06 9.305-07 1994 4.852-06 3.003-06 WNW 1329.
1329.
1.948-06 7.108-07 1329 2.214-06 1.370-06
- 1329, 9.493-04 5.876-06 NW 792.
792.
2.919-06 f.807-06 792.
4.180-06 2.587-06 792 1.459-05 9.029-06 tedW 878.
878 2.548-06 1.573-06 878 5.398-06 3.342-06 878 1.731-05 1.072-05 DRE5CEN-1 SITE 8eETEOROLOGICAL DATA t/74 - 12/75 wh nH EC W M
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/
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SN18tN 1 stastates ef fSITE Flut1E PttsE Sagnes amas FACTees FM me to BMee SESTSIC789 ELEtPATEDiSfacul NEEAM misEs m(wtest) aELEASE M LEwfL SELEASE 8IMC7 tens Act4 mense eseawa z
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(W7EsS) (eEftes) (emas/Tel/(UCf/SEC)
(_ MTES$) (sees /ve)/(teCI/SEC) (GEffes) (m/ve)/(uct/SEC) se ces.
095.
2.904-04 1.887-04 GSS.
4.013-04 3.860-04 OSS.
S.479-04 3.36e-04 4
gaf S24.
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4.000-04 4.303-04 S24 e.364-04 S.961-04 524 1.193-03 S.408-04 M
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S.981-04 4.276-04 400 S.119-04 S.778-04 400 l.233-Os S.962 04 O
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4.262-04 2.067-04 408.
S.917-04 4.182-04 408 3.024-04 S.368-04 N
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4.082-04 2.934-04 526.
S.983-04 4.645-04 536.
1.007-02 7.900-04 8e U'
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2.938-04 2.085-04 907.
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9.267-06 S.625-OS 1299.
S.000-06 4.984-06 tr
- 9994, 1994 1.370-06 9.Ste-07 1914 S.320-OS 9.414-07 9914 9.273-07 S.569-07 tant '
1329 1329 9.220-06 S.e87-06 1329.
S.500-06 S.12e-08 1329.
7.307-06 S.949-06 ear 792.
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9.326-06 S.647-05 792.
3.220-04 8.640-06 test 878.
370 7.594-06 S.!st-OS 870.
1.949-04 S.244-06 878.
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TABLE 7.2-8 (Cont'd)
DetSDEN $
mas t amme OF F S I T E F tWI T E Pt tast c amma DO5r yacioes Foe atistes Downertte RESTRICTED Ettv4YTO(5TAcw) aftta$t sef sip asooE(vf asi) ett ta5g sectas) tyvgt ogt gra5L D!afCTIOpf ASEA SOtse Racists 5
5444 RAOltt5 W
WBAR SADIUS G
63A3 (asETras) (asETERS) (HRAD/Ta)/(UCI/5tC) (saf ff AS ) (assaO/va p/(uct/5f C) (antites) (essAC/ve)/(uct/Stc) se 595.
695.
9.434-06 3.707-08 695.
8.875-04 9.318-05 695.
4.669-04 a.495-05
[
DedE 524 524.
3.120-05 4.681-06 524.
2.716-04 3.868-05 524 7.999-04 1.060-04 O
u Def 488 448.
3.233-05 4.923-06 488.
2.683-04 3.840-05 458 S.632-04 1.158-04 i
EME das.
488.
7.893-Os 3.394-06 438.
1.225-C4 1.836-05 488 5.256-04 7.840-05 g
y E
536 536.
9.904-04 4.070-06 536.
8.126-04 9.757-05 536 5.003-04 6.849-05 ESE 597 597.
9.072-06 3.475-06 597.
5.538-05 9.534-06 597 3.587-04 4.997-05 P3 SE 597 597 1.034-05 3.652-04 597.
5.030-05 8.976-06 597 3.924-04 5.464-05 SSE 634 634.
S.804-06 3.130-06 634 3.781-05 7.032-06 634 3.288-04 4.619-05 5
353 853.
8.630-06 2.t24-06 853.
1.751-05 3.531-06 353.
1.310-04 9.981-05 55w 866.
856.
4.949-04 8.685-06 866.
2.018-05 3.694-06 866.
9.343-04 9.980-05
$w 1024 1024 4.746-06 1.5 5-06 1024 1.482-05 2.965-06 1024 f.288-04 1.828-05 wSw 1219.
1289 4.983-04 8.590-06 1219.
1.4t?-05 2.849-04 1219.
9.201-05 9.378-05 w
1994 1984 4.239-06 1.189-06 1984.
3.108-05 2.962-06 1984 6.398-05 9.838-06 wedw 1329.
1329.
3.827-04 8.890-04 1329.
2.245-05 3.777-06 1329 1.430-04 2.082-05 per 792.
792.
7.564-06 2.818-06 792.
3.494-05 6.353-06 792.
2.373-04 3.354-OS peer 873.
373.
6.195-06 2.488-06 878.
5.796-05 9.504-06 878.
2.807-04 3.982-05 j
i DRESDEN-t SITE asfTromotoGICAL DATA t/74 - 12/75 i
~
- C tts M
HO SD lC m
(Is H H
l
9 9
y t
5 TABLE 7.2-8 (Cont'd) y l
I l
Oe(50em 1 antitIames etF5ITE F1et1f Pttout Saagne east Faciens Fes att3 age i
i OOnemplee mE57eIC7ED Ettwatte(5Yacesi ettiast mIata usettvaut) etLaalt eneume tiVfL SELEa5E OtefCTless ASEA game maeswa 5
suam 840Eus v
M maOIv5 4
ceae (8E7te5) (anE7tes) (enAS/ve)/(WCI/Mc) (astfre5) (amas/ve)/fuct/stc) (auf fte5) (spee/ve)/(uct/5EC) le 998.
898.
4.S79-06 2.310-06 995.
2.949-04 S.979-06 995.
7.7th-04 2.215-04
[
8edE S24 524 S.706-05 2.901-06 524.
4.590-04 1.353-04 534.
9.2SF-03 3.S37-04 U
u taE 448.
486 5.092-05 3.006-08 484 4.9"*-04 S.340-04 488.
1.384-03 3.427-04 h
8 ESE 408.
484.
4.104-05 2.H38-OS 440 2.884-04 S.530-06 4e6.
e.449-04 2.364-04 (A
H E
S36.
834 S.036-06 2.547-05 636 2.009-04 S.807-06 536.
3.190-04 2.314-04 O
ESE 597 597 4.293-06 2.154-05 597 1.148-04 4.052-06 597.
S.936-04 8.703-04 M
SE 997 S97 4.508-06 2.283-06 997 t.000-04 3.920-06 597 4.489-04 3.861-04 SSE 434 434 3.894-06 f.900-05 434 S.449-06 3.169-06 834.
S.487-04 0.990-04 5
353.
353
- 2. SOS-CS 8.248-05 863.
.4.270-OS 1.679-06 SS3.
eSt.
2.075-06 1.090-06 SSS.
4.443-06 1.642-05 Se4 2.364-04 7.006-06 Sw 1024 1024 1.947-05 9.949-05 1024 3.543-06 1.403-06 1024.
2.146-04 S.734-06 W5w 1219 1219 1.962+0S 9.387-05 1219 3.437-05 S.360-05 9289 f.640-04 S.106-06 U
1994 1994 1.449-05
$.890-08
- 1914, 2.EIO-OS 1.003-06 1984 1.879-04 3.740-OS tapes 1229 9329 l.442-05 S.933-06 1329 4.
98-08 1.567-0S 1329.
2.473-04 7.444-06 per 792.
792.
3.474-OS 8.730-05 792 7.664-06 2.837-OS 792.
3.900-04 9.167-04 tear 374 370.
2.964-06 f.903-06 378 1.836-04 3.954-05 878 4.730-04 1.387-04 Oet'mDEW-1 SI7E aut7teeOLOGICAL DATA t/74 - 12/7S e-Es ta w
HD WZ ce U' H H
e:
TABLE 7.2-8 (Cont'd)
Def$ctw 1 It&RIBEms OFF51TE FIte1TE Pttnet Caansa DOSE FACTORS FOR Xf $33 DOteeftee RESTRICTED ELEVATED STACx) attrast entst0 m0Dr(vfwY) #fLEASE
_GmCute t tvf L att f ASE DSREC710se ASEA 90Lae (1clus 5
55Aa SAD!uS W
WAS SADIUS G
GIAS (IstTERS) (utTE g (aseAD/ve)/(UCt/src) (seETras) (aseAC/ve)/(UCI/SEC) (asETES$) (assas/ra)/(UCI/Stc) u s95.
s95.
4.s27-OS t.820-Os s95 2.342-04 8.s9a OS s95.
8.484-04 2.M o-04 M
Dest 524 524.
5.741-05 2.275-0S 524.
4.884-04 1.M4 04 524 9.344-03 3.744-04 O
b 9dE 408 488.
4.954-05 2.427-05 458.
4.859-04 1.353-04 468.
1.498-03 4.049-04 8
ENE 488.
488.
4.196-OS 1.634-05 488 2.334-04 4.719-05 488.
9.379-04 2.490-04 H
E 534 534.
5.065-05 2.007-05 534.
2.248-04 S.608-05 536.
8.909-04 2.444-04 03 ESE 597 597 4.354-05 1.705-OS 597 9.228-04 3.321-05 597.
4.583-04 1.809-04 M
mc SE 597 597 4.sta-05 1.783-0S 597 1.154-04 3.561-05 597 7.197-04 1.978-04 SSE
$34 634 3.951-05 3.527-05 434 9.042-CS 2.910-05 434 5.048-04 1.893-04 5
353
- 853, 2.788-05 3.029-c3 353.
4.600-05 1.534-05 353.-
2.534-04 7.359-05 55W S48 SES.
2.148-OS 8.238-06 444 4.808-05 1.541-05 864.
2.627-04 7.555-05 Sw
$024 1024 2.058-05 7.866-06
- 1024, 3.860-05 1.283-05 1024 2.445-04 7.183-05 WSW 1219
- 1289, 2.040-05 7.751-06 1219.
3.725-OS 9.243-05 1219.
1.855-04 S.457-OS w
1984 1994 1.555-05 S.718-06 1914 2.863-05 9.470-06 1984 9.330-04 3.975-OS iseef 1329.
1329.
3.534-CS 5.798-04 1329 4.S43-05 9.528-05
- 1329, 2.770-04 7.933-05 Nei 792.
792 3.553-05 1.384-05
-792.
S.238-05 2.435-05 792.
4.482-04 1.243-04 Dent 878.
878.
3.040-05 9.895-05 87s.
1.232-04 3.749-05 878.
5.228-04 1.479-04 DRESDEN-1 SITE seETEOeOLOGICAL DATA t/74 - 12/75 e- -
2C 03 sw HO SO 2; cn LN H H
s_:
m O
O TABLE 7.2-8 (Coent'd)
)
S==0 i
enagem 979sevt pgensTE ptte som 0338 7 egg pW af ty SSISuSIS SESve8CTSS tttuateS(SteESil SELEeSE eBase W(ggest) SEtsman 98SECTBee ASEA SASS z
Esa3 Smartp5 y
gSe
- m LgtEL maammes Gml 4W 70359 8 6 9/4 WE/ SOC) GWTESSD fWsSD/4W8/SSC) 45 7035) ( M D/ftsC8/SEC) e mas Is GSS.
008.
S.433-90 3.483-94 905.
9.SSS-e8 S.SST-ee 800.
3.989-90 3.938-03 a
som Sae.
334 7.SS3-ee 4.739-ee S84.
9.e87-98 9.008-e3 Ste.
S.308-es 3.338-e8 ty o
IE 400.
400.
7.835-ee 4.717-90 408.
l.S35-93 1.891-98 400.
S.GSS-48 3.487-98 M
Sam 488.
400.
S.087-04 3.988-98 408.
9.es4-93 S.300-04 400.
3.987-98 3.983-90 g
h,
.E SS.
536.
. 998-e3 S.99.9-94 3.797-90 S38 S.438-ee 4.998-94 538.
S 7.19 938.
3.388-90 S.408-.8
- 3. 3. -.4
.39.-08
-.4 39.
3..
-98 9.
-93 SE 987 SS7.
3.974-ee 3.998-94 SST.
7.484-94 4.900-04 897.
2.830-98 3.733-93 M
SSE S34 434 4.308-94 3.983-94 434.
S.904-04 3.753-94 S34 3.388-40 9.435-03 5
SS3.
SS3.
3.430-94 9.838-Se 353.
3.t33-04 9.903-94 883 3.489-e3 S.339-04 SSW SSS.
SSS.
3.409-98 f.439-44 SSE.
3.333-94 1.773-04 SSS.
- 9. m -ee 5.738-ee Sep 9084 9004 3.t08-94 9.388-98 9004.
3.499-98 9.693-94 9004.
S.437-94 S.943-04 WWW 93t9.
13 99.
9.908-94 8.964-44 1899.
3.336-94 1.433-98 tatt.
S.300-98 4.989-06 W
9994.
9964.
9.889-9e S.eBS-et 9994 1.408-94 9.334-05 9994.
4.734-4e 3.808-04 War 9339.
9730.
9.SSS-ee 9.8 93-M 1339.
3.983-06 S.540-04 8338.
9.799-94 S.978-04' em 793.
793.
3.733-04 3.388-98 7e3.
S.937-94 3.999-04 793.
9.747-03 9.006-03 ISer 879.
370.
3.399-ee 3.853-94 878.
S.939-94 3.799-04 879.
2.808-90 3.338-03 SSESSS86-9 SITE WYSESOLSSOCat. Sata S/74 - 93/75 L.
5%og HO 99 3 e
WH i
H l
3 TAaLE 7.2-a (cont'd) 4 t
l Ge.W..t t l
i seasseams appSSTE plastTE Pttaut Saamas Sew Facteeg pas af t33 StumIse et17eIC7ts gttwaite(51acu) agtga y agage am(wgatt) agtta5E M ttWL Sitf alf SISECTIest aeta estae Sa5Hf5 5
Was emetv5 w
iftee-SaSawa 5
Mas
(
_ aetimes) (aIETEes) (emas/ vel /fuct/SEC)
(uf f te5) (amas/ vel /fesct{ tty _festiges) (emap/ve)/fuct/Sec)
N ett.
ett.
4.149-04 2.304-O4 ett.
t.Ces-03 S.est-04 egg.
3.349-03 9.700-03 4
sesE S24 524.
S.382-04 2.874-04 S24 2.047-03 1.007-03 S24.
S.244-03 2.807-03 O
g asE 408.
det.
S.892-04 3.038-04 400 2.044-03 1.006-03 448.
S.476-03 3.037-03 g
g tesE 4ee.
448.
3.344-04 2.080-04 444 1.063-03 S.700-04 ese.
3.904-03 8.375-03 u
E S36 338 4.442-04 2.533-04 S36.
1.000-03 S.GO2-04 S38.
3.474-03 1.860-03 O
O ESE 997.
Se7.
3.982-04 2.994-04 997.
S.464-04 3.544-04 997.
2.570-03 1.377-03 84 gg SE 997.
997.
3.900-04 2.957-04 S97.
S.400-04 3.409-04 SS7.
2.803-03 9.500-03 2:
SSE 634.
434 3.499-04 1.849-04 634 S.206-04 2.848-04 634 2.403-03 8.2e7-03 5
SS3.
e53.
2.221-04 9.309-04 e53.
2.83t-04 S.S27-04 SS3.
1.057-03 S.667-04 55s
- ses, see.
1.387-04 9.824-06 864 2.700-04 3.459-04 ses.
3.000-03 S.792-04 Sw 9024.
1024.
1.729-04 9.352-OS 1024 2.399-04 1.272-04 1024.
3.032-03 S.530-04 W5W 1299.
1299.
f.643-04 a.904-OS 12tt.
2.2SS-04 1.217-04 12 99.
7.845-04 4.300-04 W
1984 1984 9.937-04 S.942-06 1994 9.645-04 e.e47-06 1994 S.7ee-04 3.107-04 tsar 1229.
1329.
9.237-04 S.489-05 4329.
2.513-04 1.362-04 1329 1.136-03 S.087-04 per 792.
792.
3.100-04 3.682-04 792.
4.693-04 2.S28-04 792.
8.747-03 9.470-04 Beet 378.
370.
2.700-04 1.465-04 878.
S.152-04 3.300-04 878 2.000-03 1.124-03 DeE5 Dest-8 SITE IEETEtaeLOSICat Data 1/74 - 32/7S L
N te -
M HO to E se Us M 9-8
O TABLE 7.2-8 (Cont'd) 4 f
l t
SSESS898 8 mastem GFFStet Flee 878 88LtM em SAM F4CVW fm 38137_
Bessies GES799C799 ELitetED($7 aces) SEtta$f' 38330 M (weeft) estE4Sg m tgwgt egttag SISEC7tet eeEA M 5
Maf5 W
maa -
O m
8W7945) (E ftell ( M /Tel/fastt/SGC) (WT885) (M/ve)/(4fCI/$fC) (W 9E85) ( m /TS)/feact/SEC) se 885.
Ges.
8.e80-04 9.99e-04 est.
3.389-04 3.922-04 Set.
S.9e8-04 5.729-04 4
tee S24.
324 2.746-04 8.779-94 524 4.e98-04 3.134-04 S24 9.386-03 8.908-94
+
IEE 408.
400.
2.046-04 9.727-04 400.
4.000-04 2.908-04 4e8.
9.433-03 9.300-04 y
N O
EM 408.
400.
2.021-64 9.300-04 488.
3.342-04 2.083-04 4es.
9.4eS-04 S.OS4-04 M
b E
S36.
S35.
2.300-04 f.483-04 536.
2.748-04 2.484-04 S38.
3.038-03 6.9e5-04 g
e ESE So?.
Bef.
t.949-04 9.998-04 907.
2.708-94 3.749-04 Se7 7.t42-64 4.Se8-04 SE 997.
Bef.
1.678-04
$.088-04 987 2.340-04 1.598-04 Se7 7.299-04 4.603-04 M
m SSE S34.
634.
1.33e-04 a.ee5-05 634 l.832-04 1.103-04 434 S.77e-04 3.794-04 5
SS3.
363.
7.433-08 4.093-06 SS3.
S.339-OS S.302-06 382.
2.222-04 1.429-04
$$w seS.
388.
7.074-05
- 4. Set-OS 846.
7.878-OS S.088-06 See.
9.986-04 9.290-04 Sar 9034.
9G34.
S.Ste-OS 3.972-05 toad.
S.486-OS 4.987-06 9024.
9.939-04 9.832-05 tr$af
$2 99.
1299.
4.499-08 2.000-05 12t9.
5.196-06 3.332-OS 1299.
9.922-04 7.287-08 tr 1994.
3934 S.964-05 S.364-06 19 84 2.408-06 1.613 6 99 94.
S.e47-OS 3.846-06 tear 1329.
1329.
3.828-05 3.347-OS 1329.
S.198-06 3.388-06 1329.
8.487-04 9.988-08 tes 792.
792.
9.000-04 S.964-OS
.792, 9.433-04 9.299-OS 792.
3.989-04 2.989-04 Seer 878.
370.
9.545-05 6.983-08 87s.
S.643-04 S.000-04 879.
4.397-04 2.824-04 seE3 Dest-1 SITE DIEffenstaSICAL 94T4 t/74 - 12/75 L
M as -
>4 (JI N H
w e.:
I TABLE 7.2-8 (Cont'd)
DetSDEM 1 unasteaJun OFF1112 FINiit Pitant CMene OtMt FacToes FOR st 138 DOttes18e SESTSICTED ELEvatto(stacun attrast utsto aur>t tytw?) artts5L r:aru mm t ryg t ett r ast O!SECTION ASEA SOLM3 BADIUS 5
SAit RAD 1us v
WSAR RADju$
G G3A3
( enET E as) (asE TERS ) (aseAD/va)/(UCI/5tC) (ant it ts ) (setAD/ val /(UCt /stc)
(_ent1Eas) t am&D/ve)/(tJC t /5f c)
M 895.
495.
1.393-03 1.08S-03 495 2.434-03 9.754-03 SSS.
7.268-03 S.893-03 4
tesE S24.
524 0.909-03 f.298-03 524 3.642-03 2.453-03 524 1.094-02 7.829-03 O
NE 498.
484.
8.890-03 1.377-03 484.
3.604-03 3.595-03 488.
1.154-02 S.257-03 ENE 488.
488.
9.409-03 8.027-03 488
- 2. 3S t-03 1.697-03 488.
7.354-03 S.254-03 g
u E
S34.
536.
8.647-03 9.200-03 534 2.629-03 1.898-03 534.
7.709-03 S.530-03 g
M ESE 597 597.
8.355-03 S.872-04 597.
4.920-03 1.388-03 597.
S.590-C3 3.996-C3 SE 597 597.
1.271-03 S.2SS-04 597.
1.728-03 9.250-03 597.
S.877-03 4.201-03
~4 O
in
$$E 534 534 1.054-03 7.899-04 534.
1.481-03 1.039-03 E34 4.884-C3 3.490-03 5
853.
853.
S.432-04 4.682-04 853.
7.287-04 S.279-04 SS3 2.927-03 8.522-03 55w 864 848 S.909-04 4.302-04 864.
4.675-04 4.832-04 See.
1.545-03 9.398-03 SW 1024 1024 5.844-04 3.744-04 1024.
S.078-04 4.408-04 8024 1.750-03 9.2S2+03 tr$w 1219 1299.
4.689-04 3.3SO W 1219.
S.408-04 3.918-04 1219.
1.388-03 9.928-04 w
$314 1994 2.548-04 f.852-04 1914.
3.32S-04 2.448-04
- 1914, 9.764-04 6.992-04 tNo 1329 1329 3.753-04 2.731-04 4329.
S.ESO-04
- 4. C40-04
- 1329, 2.0f0-03 1.437-03 Nw 792.
792 9.170-04 S.679-04 792.
1.188-03 S.594-04 792.
3.Ste-03 2.584-03 teed 873.
878.
8.16S-04 S.948-04 478.
1.360-03 S.315-04 878.
4.155-03 2.949-03 Det%CEM-1 SITE seETEOSOLOGICAL DATA t/74 - 12/7S OH 3: 03 M
- O WZ cn UD P H
e t_."
g
)
O TABLE 7.2-8 (Cont'd) 08E508N 9 anastasuas OSF51TE FIss11E Pttast saamaa ec5E FaCTon$ Foa Aa 4 8 COwedite RESTRICTED EttvaTED(Stux) attEASE stato ascof(vissT) attrast escope LEvrt arttASE clatCTItm AaEA SOwe NacItr5 5
555R RAD!us v
WSAC SAclus G
GaAa (sIETE ts ) (asE T E as) (assac/ft)/(UCI/5EC) (est f r es ) (senac/va l/(ut t/5tc) (astfits) (assAD N
99S.
89S.
1.874-03 1.329-03 695.
3.948-03 2.778-03 695.
8.325-02 7.93S-03 4
fedE S24.
524.
2.446-03 f.725-03 S24.
7.520-03 S.019-03 S24.
f.779-C2 8.248-02 t2 h
NE 488.
488.
2.5S4-03 1.308-03 488.
7.934-03 S.029-03 484.
9.915-02 8.350-02 h
Esse 44a.
ess.
1.779-03 S.254-03 asa.
3.920-03 2.764-03 44..
1.187-02 s.370-03 sJ E
S36 534.
2.848-03 1.S95-03 S34.
4.064-03 2.465-03 534.
1.884-02 8.346-03 C3 b8 ta E5E S97 SS7 3.774-03 1.258-03 597.
2.638-03 1.860-03 197.
S.694-03 S.129-03 M
SE 597.
S97 1.764-03 3.247-c3 597 2.150-03 1.7St-03 597.
9.425-C3 S.545-03 SSE S34 434.
1.504-03 1.060-03 S34 2.C94-03 1.479-03 S34.
3.020-03 S.454-03 5
353.
353.
9.S28-04 S.786-04 353.
t.t20-03 7.894-04 SS3.
3.584-03 2.477-03 55W 864
- See, a.033-04 S.643-04 364 1.034-03 7..sO7-04 864.
3.484-03 2.459-03 SW 1024 8024 7.447-04 S.250-04
- 1024, 9.225-04 6.503-04 1024.
3.277-03 2.310-03 wsw 12tt.
1219.
S.987-04 4.925-04 1219.
S.603-04 S.065-04 3289.
2.520-03 1.777-03 w
1914 1914.
4.427+04 3.121-04 1984 S.SSS-04 4.170-04 8984 8.848-03 8.382-03 tedw 1329.
1329.
S.359-04 3.778-04 1329 9.064-04 S.390-04 1229.
3.648-03 2.572-03 NW 792.
792.
1.3SS-03 9.542-04 792.
1.819-03 1.293-03 792.
S.378-03 4.842-03 pedw 378.
873.
1.122-03 S.336-04 878 2.228-03 1.565-03 878.
S.900-03 4.4s64-03 Def5 DEN-1 SITE asETED80 LOGICAL DATA t/74 - 12/75 o-
- 03 H
HO WE cn Ut H H
9
i 1
l DRESDEN REVISION 11 i
M ACE 1985
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TABLE 7.2-9 (Cont'd)
DRESDEN 243 AVERAGE WIND SPEEDS FOR EACH RELEASE MODE DOWNNIND AVERAGE W':ND SPEED Im/mme)
DIRECTION ELEVATED M:.'XED MODE
-CROUND LEVEL M
6.8 5.4 4.8 NME 6.8 5.1 4.4 NE 6.4 4.9 4.1 ENE 6.4 5.0 4.4 E
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DaE5 DEN 263 etArtMLee OFF5ITE FINITE PLUME GatesA DOSE FACTORS FOR NR 85N t
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VSAR RADIUS O
G8AR (BeETERS ) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (900AO/VR)/(UCf/5EC) (METE N
768 764.
2.664-04 1.421-04 768.
1.124-03 5.313-04 768.
2.165-03 1.109-03 4
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3.012*04 1.607 04 654.
1.765-03 9.078-04
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680.
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1.761-03 9.061-04 610.
3.148-03 9.606-03 p
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2.197-04 1.172 04 680.
9.538-04 4.932-04 610.
l.939-03 9.907-04 M
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2.708-04 1.445-04 658.
1.001-03 5.189-04 658.
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9.191-04 4.725-04 NW 756.
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- 671, 2.460-04 1.313-04 671 1.019-03 5.278-04 679.
2.166-03 1.108-03 DRE50EN-263 SITE NETEDRDLOGICAL DATA t/74 12/7'5 e-II: 03 H
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DRE50EN 263 1
88AXI8ENI OFFSITE FINITE PLuetE GA45tA DOSE FACTORS FOR 8tR SS 00WNWlpe RESTRICTED ELEVATED (STACM) RELEASE 80!XED 800DE(VENT) RELEASE GROUSE LEVEL RELEASE otRECTION AREA SOUND RADIU5 5
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VBAR RADIUS e
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768 768.
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3.044-04 1.884-04 756.
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1.544-05 9.570-04 M
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DRESDEN 243 MAXIMUI4 OFFSITE FINITE PLUME GA494A DOSE FACTORS FOR 0(R 90 DOWNWIDE RESTRICTED ELEVATED (STACM) RELE'ASE
_ MINED IIODE(VENT) RELEASE GROUSE LEVEL RELEASE DIRECTION AREA 80U00 RADIUS S
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GSAR (ISETERS ) (00ETERS) (BIRAD/YR)/(UCI/SEC) (METERS) (BIRAD/YR)/(UCI/SEC) _(tee TER$) (IIR N
768 768.
1.894-04 1.361-04 768.
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- 658, 3.187-04 2.205-04 650.
5.358-04 3.788-04 458.
5.288-04 3.729-04 NE 610.
610.
3.247-04 2.329-04 StO.
5.349-04 3.783-04 610.
5.468-04 3.856-04 tu y.
t3 ENE
- 610, 610.
2.303-04 1.652-04 610.
4.099-04 2.899-04 680.
4.154-04 2.929-04 l'3 w
E 658
- 658, 2.259-04 1.620-04 650 4.612-04 3.261-04 658.
4.923-04 3.473-04 M
W ESE 707 707.
l.683-04 1.206-04 707.
2.758-04 1.952-C' 707.
2.834-04 2.000-04 gy SE 707.
707 1.418-04 1.016-04 707 2.175-04 1.540-04 707.
2.515-04 f.775-04 Zm SSE 792.
792 7.471-05 5.35r-05 792.
1.046-04 7.407-05 792.
1.078-04 7.608-05 5
341.
- 841, 5.328-05 3.815 05 341.
4.815-05 3.415-05
- 341, 4.654-05 3.287-05 SSW B53.
353 5.407-05 3.875-05 853.
5.763-05 4.002-05 353 5.006-05 3.536-05 SW 1024 1024.
2.035-05 1.500-05 1024 2.058-05 1.458-05 1024.
l.554-05 1.097-05 WSW 1170.
1170 t.151-05 a.244-06 1170.
9.796-06 6.947-06 1170.
7.563-06 5.342-06 W
1756 1756 2.229-06 1.595-04 1756 1.961-06 1.389-06 1758 1.672-06 1.182-06 WNW 1219 1219.
1.208-05 8.655-06 1299.
1.400-05 9.965-06 1219.
1.193-05 S.427-06 NW
- 756, 756 S.722-05 6.254-05 756.
1.454-04 1.029-04 756.
1.499-04 1.058-04 NNW 671.
679.
1.769-04 1.269-04 671.
3.963-04 2.814 04 671.
4.193-04 2.956-04 DRESDEN-263 SITE 80ETEOROLOGICAL DATA 9/74 12/75 OH, D2 (A H
.Z Ut 8-8 H
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TABLE 7.2-11 (Cont'd) i DRE50EN 263 MAXIMUM OFFSITE FINITE PLueet GAameA DOSE FACTORS FOR XE13tM DOWNWIDO RESTRICTED _ ELEVATED (STACM) RELEASE MIXEO 9000E(VENT) RELEASE
. GROUSE) 8.EVEL RELEASE l
DIRECTION AREA 50060 RADIUS 5
5BAR.
RADIUS V
V8AR RADIUS GC GSAR (METERS) (seE T E RS ) (DeRAD/VR)/(UCI/SEC) '(METERS) (teRAD/YR)/(UCI/SEC) (ME i
N 768.
768.
6.724-06 3.366-06 768.
f.687-04 2.598-05 768 4.032-04 5.663-05 4
PME 658.
658.
9.462-06 3.749-06 658.
3.112-04 4.507-05 658.
5.764-04 7.915-05 O
NE 610.
610.
1.028-05 3.999-06 680.
3.063-04 4.458-05 610.
6.267-04 8.604-05 f
ENE 610.
810.
6.773-06 2.716-06 610.
1.469-04 2.235-05 610 3.807-04 5.250-05 w
E 658.
- 658, 8.421-06 3.368-06 658.
1.435-04 2.248-05 658 3.703-04 5.169-05 O
A ESE 707.
707.
8.003-06 2.975-06 707.
9.026-05 1.477-05 707 2.800-04 3.946-05 DJ SE 707.
707.
8.998-06 3.107-06 707.
7.957-05 1.347-05 707 3.063-04 4.394-05 Z
SSE 792.
792.
7.629-06 2.564-06 792.
5.986-05 1.046-05 792 2.367-04 3.382-05 5
841.
841.
6.705-06 2.152-06 841.
3.782-05 6.758-06
- 849, 1.338-04 1.951-05 SSW 853.
853 4.983-06 1.703-06
- 853, 4.270-05 7.221-06 853.
1.394-04 2.024-05 SW 1024.
- 1024, 4.730-06 1.611-06
- 1024, 3.100-05 5.625-06 1024.
1.218-04 1.82" 05 W5W
$170.
1970.
4.985-06 f.639-06 1870.
3.118-05 5.730-06 1170.
9.791-05 1.461-05 W
'1756.
1758.
4.363-06 f.260-06
- 1756, 2.515-05 4.474-06
- 1756, 7.246-05 1.106-05 WNW
$219.
1219.
3.993-06 1.277-06 1219.
4.915-05 7.928-06 1219.
1.622-04 2.345-05 NW 756.
756.
7.736-06 2.923-06 756.
7.484-05 1.262-05 756.
2.541-04 3.583-05 9WW 671.
671.
7.422-06 3.056-06 671.
f.492-04 2.311-05 671.
4.153-04 5.763-05 DRESDEN-263 SITE METEOROLOGICAL OATA t/74 - 12/75 m-33 in.
H HO W 2:
cn
@H H
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- - - - - ~ ~ - -
TABLE 7.2-11 (Cont'd)
ORESDEN 283 04AXImuN OFF5ITE FINITE PLUIsf GA8884 005E FACTORS FOR xEI330s 00WNWI9e RESTRICTED ELEVATEO(5TACst) RELEASE MINED 8000E(VENT) SELEASE 9Acule LEVEL RELEASE l
OIRECTION AREA SOUfe RADIUS 5
58Ill RADIUS V
VSAR ~
RADIUS G
GBAR
+
]
(ISETERS )
(, IEETERS) (88 RAD /vR)/(UCI/SEC) (seETERS) JIIRAD/YR)/(UCI/SEC),(TEETERS) (IMAD/VR)/(UCI/SEC)
N 768 768 4.154-06 2.005-05 768.
3.092-04 9.873-05 768.
4.724-04 t.950-04
{
q NNE G58
- 458, 4.634-05 2.342-05 450.
5.353-04 1.604 04 658.
S.347-04 2.848-04 t2 NE
$90.
490.
4.934-05 2.484-06 Sto.
5.295-04 1.599-04 810.
1.020-03 2.876-04 PJ ENE S10.
690.
3.359-05 9.703-05 Sto.
2.444 04 S.428 05 Sto.
6.229-04 1.745-04 I
E
$54
- 858, 4.163-05 2.109-05 858.
2.843-04 a.726 05 858.
S.139-04 1.766-04 j
y ESE 707 707.
3.872-05 f.829-05
- 707, 1.770-04 5.996-05
- 707, 4.689-04 1.364-04 SE 707 707.
3.826-05 1.370-05 707 1.817-04 5.833-05 707.
5.124-04 1.490-04 at ful SSE 792 792.
3.153-05 1.530 05 792.
1.257-04 4.489-05 792.
4.018-04 1.108-04 5
841 841.
2.642 05 1.245-05
- 841, 8.130-05 2.953-05
- 341, 2.321-04 7.022-05 SSW 853
- 353, 2.097-05 1.022-05 453 S.655-05 3.013 05 853.
2.405-04 7.240-06 i
SW 1024 1024.
1.982-05 9.859-06 1024 S.748-05 2.486-05 1024 2.ISS-04 6.734-05 W$W t170.
t170.
2.013-05 9.707-06 1170 S.887-05 2.553-05 1170.
1.739-04 5.395-06 W
1758 1758.
1.538-05 7.118-06
- 1754, 5.387-05 t.943-05 1756.
1.317-04 4.180-05 WNW 1219 1299.
f.570-05 7.505-04 1219 9.475-05 3.149-05 1219.
2.786-04 S.359-05 NW 758 756.
3.605-05 1.803-05
- 756, 1.514-04 5.254-05 758 4.258-04 1.239-04 Desw G71 471.
3.778-05 1.926-05
- 671, 2.760-04 B.886-05 671.
S.543-04 f.955-04 i
ORE 50EN-283 SITE 18ETEOROLOGICAL DATA t/74
.12/75
$33 03 1
M HO W 25 as MHH L
i
I i
't
- i i
I TABLE 7.2-11 (Cont'd) i DRESOEN 243
(
_4tAKIISR8 0FFSITE FINITE PLUISE GAegeA DOSE FACTORS FOR XE t33 DetterIpe RESTRICTE0 ELEVATEO(STACK) RELEASE MINEO agoOE(VENT) RELEASE GROUpe LEVEL RELEASE i
I DIRECTION AREA SOUfe RADIU5 5
5SAR RA0luS V
VSAR RADIUS S
GSAR (seETERS) (seETERS) (81 RAD /ve)/(UCI/SEC) (TEETERS) (81 RAD /va)/(UCI/SEC) (IIETE N
768.
744.
4.219-05 1.455-05 768.
3.432-04 0.017-04 768.
7.419-04 2.077-04 q
- dE 858.
654.
4.473-05 1.940-05
- 858, 5.841-04 1.559-04 SSs.
1.025-03 2.892-04 0
NE-690.
Sto.
4.992-05 1.640-05 Sto.
5.700 04 1.647-04 480.
f.194-03 3.085-04 N
ENE S00.
SiO.
3.385-06 1.334-05
- 410, 2.930-04 S.604-05 810.
S.006-04 1.873-04 i
g E
658.
SSS.
4.191-05 1.653-06
- 658, 2.945-04 8.866-05 858.
S.733-04 1.s72-04 g"
ESE 707.
707.
3.730-05 1.453-05 707.
1.975-04 S.069-05 707.
5.170-04 1.450-04 tag SE 707.
- 707, 3.925-05 1.509-06 707.
1.804-04 5.836-05 707.
5.849-04 1.584-04 21 SSE 792.
792 3.243-05 1.248-05
- 792, t.406-04 4.461-05 792.
4.458-04 1.265-04 5
841.
841.
2.749*05 1.042 841.
9.198-05 2.924-05
- 841, 2.548-04 7.453-05 SSW 853.
- 853, 2.164-05 S.320-08 453.
9.704-05 3.034-05
- 853, 2.443-04 7.70s-05 SW 1024.
1024 2.048-05 7.847-04
- 1024, 7.452-05 2.475-05
- 1024, 2.445-04 7.183-05 tfSW t170.
I170.
2.095-05 7.901-04 1170.
7.787-05 2.532 05 1170.
t.965-04 5.759-05 W
1758
- 1754, 1.450-05 6.124-06 1758.
S.075-05 1.948-05 1758 1.493 04 4.444-05 WNtf
$289, 1219 1.638-05 S.207-OS 12t9 1.065-04 3.254-05
- 1219, 3.115-04 S.935-05' Ntt 754 756 3.875-05 1.436-05
.756, 1.593-04 5.282-05 754 4.700-04 1.320-04 peat 479.
671 3.792-05 1.502-05 671 3.056-04 9.091-05 67I.
7.516-04 2.043-04 DRESDEN-243 SITE GIETEOROLOGICAL DATA t/74 - 12/75 o-Sxt in H
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i TABLE 7.2-11 (Cont'd) i ORESDEN 243 I
alAMINUM OFF5tTE FINITE PLUME GAIM8A OOSE FACTOR $_FOR XEt350s DOWNWIDE) RESTRICTED ELEVATED (STACW) RELEASE
_ IIINEO IIODE(VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUDE) RADIUS 5
58A4 RAOIUS V
VBAR RAO!US G
CSAR (TEETERS) (IIETERS) (IIRAD/VR)/(UCI/5EC) (88tTERS) (tIRAD/VR)/(UCI/5EC) (TEETE y
N 768.
768.
4.998-04 3.091-04 168 1.844-03 1.006 03 768 3.019-03 t.839-03 NNE SSS.
453.
5.955-04 3.883-04
- e54, 2.074-03 1.268-03 454 3.740-03 2.276-03 C3 u
NE S10.
StO.
5.891-04 3.543-04 810.
2.029-03 1.241-03 SiO.
3.961-03 2.410-03 i
ENE 590.
SIO.
4.425-04 2.737-04 610 1.291-03 7.910-04 StO.
2.520-03 1.534-03 W
g E
658.
658.
5.255-04 3.250-04
- 658, t.462-03 S.961-04
- 658, 2.709-03 f.650-03 ESE 707.
707.
4.506-04 2.786-04 707 1.130-03 5.930-04 707 2.067-03 1.260-03 p1 SE 707.
707.
4.212-04 2.803-04 707 l.014-03 6.220 04 707.
2.170-03 1.322-03 Z
SSE 792.
792.
3.283-04 2.029-04 792 7.645-04 4.693-04
- 792, t.659-03 f.012-03 5
841.
- 341, 2.573-04 1.652-04 841.
5.243-04 3.220-04 841 f.045-03 S.377-04 55w
- e53, 353, 2.445-04 t.511-04 e53 4.961-04 3.045-04
- e53, 9.624-04 5.873-04 SW 1024 1024.
2.Itt-04 1.305-04 1024 4.272-04 2.625-04 1024 8.437-04 5.153-04 WSW
- t170, t170.
2.011-04 1.243-04 1170 4.022-04 2.473-04 1170.
7.184-04 4.390-04 w
- 1756, 1758.
1.206-04 7.448-05
- 1756, 2.917-04 f.791-04 1754.
5.5tp-04 3.369-04 WNW 1219 1219 1.723-04 1.065.04 1299 5.009 04 3.070-04 1219.
1.129-03 8.888-04 Nw 754.
754.
3.936-04 2.434-04 754 9.249-04 5.676-04 754 1.878-03 1.144-03 fe4W 671.
671.
4.519-04 2.795-04 671.
1.510-03 9.247-04 871.
3.035-03 1.848-03 ORE 50EN-243 SITE 80ETEOROLOGICAt. DATA t/74 - 12/75 OH
$4 03 H
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TABLE 7.2-11 (Cont'd) i i
DRESDEN 243 MAXIIeuel OFFSITE FINITE PLUME GAGRGA DOSE FACTORS FOR NE135 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA B0U00 UEADIU5 5
5sAR RADIUS V
VSAR RADIUS G
GSAR (atETERS ) (IAETERS) (MRAD /t2)/tuCI/SEC) (METERS) (IIRAD/YR)/(UCI/SEC) (METER N
768 768 3.778-04 2.044-04 768 1.550-03 S.328-04 768.
2.948-03 f.579-03 4
NNE 650.
454.
4.259-04 2.305-04 658.
2.445-03 1.311-03
- 458, 3.943-03 2.ti1-03 NE 610.
800.
4.503-04 2.438 04 SIO.
2.439-03 1.30s-03 StO.
4.284-03 2.294-03 N
ty ENE StO.
810.
3.103-04 1.679-04 610.
1.317-03 1.073-04 810.
2.639-03 f.413-03 b
g E
GSS.
SSS.
3.834-04 2.074-04 658.
1.382-03 7.423-04 658.
2.662-03 1.424-03 m
ESE 707.
707.
3.310 04 1.791-04 707.
9.677-04 5.202-04' 707.
2.065-03 1.106-03 SE
- 707, 707.
3.354-04 1.815-04 707.
9.157-04 4.925-04 707.
2.251-03 1.206-03 2:
SSE 792.
792.
2.734-04 1.478-04 792.
7.331-04 3.945-04 792.
1.801-03 9.454-04 pg 5
841.
841.
2.251-04 1.217-04 841.
4.856-04 2.814-04 841.
1.077-03 5.776-04 SSW 853.
- 353, 1.839 04 9.944-05 853.
4.566-04 2.617-04 853.
1.102 03 5.908-04 SW
- 1024, 1024 1.724-04 9.335-05 1024.
4.088-04 2.201-04 1024.
l.032-03 5.539-04 WSW t170.
- I170, f.727-04 9.338-05 t170.
4.182-04 2.252-04 1170.
8.287-04 4.448-04 W
1754.
- 1754, 9.232-04 8.860-05 8754.
3.147-04 1.894-04 1754.
S.470-04 3.473-04 WNW 1219.
1219 1.343-04 7.263 05
- 1219, 5.031-04 2.704-04 1219.
1.288 03 8.800-04 NW 754.
754.
3.246-04 1.758-04 758.
8.522-04 4.584-04
- 754, 1.875-03 f.005-03 NNW
$71.
678.
3.496-04 f.891-04 671.
1.403-03 7.536-04 871.
2.940-03 1.574-03 DRESDEN-243 SITE 80ETEOROLOGICAL DATA t/74 - J2/75 OH
$O 03 H
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TABLE 7.2-11 (Cont'd)
/
/
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I DRESOEM 243 o
IIAXIMun OFFSITE FINITE PLtNIE GA8804 DOSE FACTORS FOR ME137 DOWNWIIe RESTRICTED ELEVATED (STACK) RELEASE MIXED 9100E(VENT) RELEASE GROUDG LEVEL RELEASE DIRECTION AREA 80Ufe RADIU5 5
SSAR RAOtus V
veAf RADIUS G
GGAR (80ETERS ) (IEETERS) (seRAD/va)/(UCI/5EC) (IEETERS) (senAD/YR)/(UCI/SEC) (seETER N
768 788 1.593-04 1.032-04 768 4.700-04 3.030-04 788.
7.334-04 4.714-04 q
DedE 858.
558 2.01s-04 f.303 04 S5S.
5.790 04 3.726-04 SSS.
8.999-04 5.784-04 O
[
NE StO.
- 680, 1.964-04 1.272-04 Sto.
5.585-04 3.542-04 810.
9.391-04 S.035-04 M
l DJ EM G10.
610.
1.492-04 9.664-05 Sto.
3.819-04 2.459-04 810.
S.248-04 4.014-04 E'3 I
E SSS.
SSS.
1.712-04 f.109-04
- 658, 4.389-04 2.826-04 658.
G.998-04 4.497-04 y
ESE 707.
707 1.445-04 9.357-05 707 3.344-04 2.166-04 707.
5.146-04 3.304-04 tus SE 707.
707.
1.297-04 8.403-05 707.
2.920-04 1.881-04 707.
5.232-04 3.344-04 Z
g SSE 792.
792.
9.448-05 S.132-05 792.
2.033-04 1.310-04 792.
3.669-04 2.358-04 l
+
5 849.
841.
7.588-05 4.913-05 841.
1.353-04 8.718-05 849.
2.294-04 1.475-04 55W 853
- 853, 7.220-05 4.476-05
'853.
t.309-04 S.431-05 853.
2.024-04 1.301-04 SW 1024
- 1024, 5.502 05 3.563-05 1024.
9.985 05 S.434-05 1024.
f.529-04 9.832-05 i
W5W t170.
1170.
4.749-05 3.074-05 t170.
S.429-05 5.432-05 1170.
1.242-04 7.986-05 W
1758.
- 1754, 2.316-05 1.498-05 1758.
4.821-05 3.105-05 1758 7.229-05 4.849-CS WNW 1219 1219.
4.222-05 2.733-05 12t9.
1.045-04 S.730-05 1219 1.850-04 1.090-04 NW
- 756, 758, t.137-04 7.366-05
-754, 2.543-04 f.638-04
- 756, 4.382-04 2.817-04 fedW G71.
47 't.
1.425-04 9.232-05 479.
4.378-04 2.817-04 471.
7.563-04 4.861-04 DRESOEN-283 SITE 8eETEOROLOGICAl. DATA t/74 - 12/75 i
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DRESDEN REVISION 11 MARCH 1985
- Sh
- D 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, I
MODELS FOR SETTING GASEOUS AND LIQUID
. '8 EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING TABLE OF CONTENTS 4
PAGE 8.1 GASEOUS RELEASES l
8.l-1 8.1.1 Main Chimney Releases 8.1-3 8.1.1.1 Unit 1 Chimney Particulate, Iodine, and Noble Gas Monitor 8.1-3 8.1.1.2 Units 2/3 Chimney Particulate, Iodine, and Noble Gas Monitors 8.1-3 8.1.1.3 SJAE Off-Gas Monitors 8.1-6 8.1.1.3.1 Unit 1 8.1-7 i
8.1.1.3.2 Units 2/3 SJAE Off-Gas Monitors 8.1-7 8.1.1.4 Allocation of Effluents from Common Release Points 8.1-8 l
, < ^
8.1.2 Units 2/3 Reactor Building Ventilation Stack Releases
,~,
8.1-8 8.1.2.1 Ventilation Stack Monitors 8.1-8 8.1.3 Chemical Cleaning Facility 8.1-11 i
8.1.4 Symbols' Used in Section 8.1 8.1-13 8.1.5 Constants Used in Section 8.1 8.1-15 8.2 LIQUID RELEASES 8.2-1 8.2.1 Units 2/3 Effluent Line Activity Monitor 8.2-2 8.2.2 Allocation of Effluents from Common Release Points 8.2-4 8.2.3 Administrative and Procedural Controls
.l for Radweste Discharges 8.2-4 8.2.4 Service Water Header Releases 8.2-5 8. 2. 4.1 Units 2/3 Service Water Effluent Monitors 8.2-5 8.2.5 Chemical Cleaning Facility Service Water Effluent Monitor 8.2-5 8.2.6 Determination of Initial Dilution Stream Flow Rates 8.2-6 8.2.7 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 8-i b
~
DRESDEN REVISION 11 MARCH 1985 O
ODCM LIST OF TABLES FOR DRESDEN SECTION 8.0 NUMBER TITLE PAGE 8.4-1 Environmental Radiological Monitoring l
4 Program 8.4-2 8.4-2 Reporting Levels For Radioactivity Concentrations in Environmental Samples 8.4-6 8.4-3 Detection Capabilities for Environmental Sample Analysis 8.4-7 e
e 8-11
-.-s_._
DRESDEN REVISION 11 MARCH 1985 ODCM LIST OF FIGURES FOR DRESDEN SECTION 8.0 NUMBER TITLE 8.1-1 Simplified HVAC and Gaseous Effluent Flow Diagram (Unit 1) 8.1-2 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram (Units 2 & 3) 8.2-1 Simplified Liquid Radwaste Processing and Liquid Effluent Flow Diagram 8.3-1 Simplified Solid Radwaste Processing Diagram 8.4-1 Fixed Air Sampling and TLD Sites and Outer Ring TLD Locations 8.4-2 Inner Ring TLD Locations and Near Station Water Sample Locations 8.4-3 Milk Sample Locations and More Distant Water Sample Locations e
\\
m.
6 8-111
j
~
MARCH 1985
{
8.0 RADIOACTIVE EFFLUENT TREATMENP SYST::MS, MODELS FOR SETTING GASEOUS AND LIOnID EFFLUENT MONITOR ALARM AND TRIP SETPOINFS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air contain-ing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded.
The setpoints are found by solving Equations 2.9 and 2.10 for each class of release.
For this evaluation, the radioactivity mixture in the exhaust j
air is assumed to have the composition of gases listed in f
Table 3-3 from "fechnical Derivation of BWR 1971 Design Basis
{m Radioactive Material Source Terms," NEDO-10871, March 1973,
)
General Electric Company.
This mixture of radioactive gases is representative of the activity found at the point of release from the fuel with no radioactive decay accounted for.
Equation 2.9 is rewritten using the fractional composition of each nuclide, f, and a total release rate, O, f r each t
t class:
1.11 Qts @i
- f I + Otv. N
- f ) +O N*f)
<500 i
i i
tg i
i (8.1) f g Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.
Qts Total Release Rate, Stack Release (DCi/sec)
The release rate for all radionuclides due to a stack release.
8.1-1
DRESDIDI REVISION 11 MARCH 1985 h
Q Total Release Rate Vent Release (UCi/sec) tv The release rate for all radionuclides due to a vent release.
Q Total Release Rate, (WCi/sec) tg g
Ground Ievel Release The release rate for all radionuclides due to a ground leve). release.
Ois'" Ots f (8.2)
Q,*Qtv i (8.3) i f
Qig = Qtg i (8.4) f Equation 8.1 can be solved for Q f r each class of release t
(-
for release limit determinations.
4 Similarly, Equation 2.10 can be rewritten:
1 E
(X/Q), Q f
ts i eXp (-l R/3600u,) + (X/Q),Qtv i i
i f
esp (-l V3600u ) + (X/Q)g Q f
i y
tg i **P (- 1 1R/3600u )
+ 1.11 g
l (S o fg ta i
- Y 0 f
f
< 3000 i tv i + G Qg tg i)
-J i
(8.5)
Equation 8.5 can be solved for Q for each class of release t
and a corresponding release limit be determined.
The most conservative release limit determined from Equations 8.1 and 8.5 will be used in selecting the appropriate alarm and trip setpoints for each class of release.
The' exact settings will be selected to ensure that 10 CFR 20 h
limits are not exceeded.
a 8.1-2
i j
DRESDEN REVISION 11 MARCH 1985
- ( h Surveillance frequencies for gaseous effluent monitors will be as stated in the Technical Specifications.- Calibration methods for gaseous effluent radioactivity monitors will be consistent with the definitions found in Section 1.0 of the Technical Specifications.
Figures 8.1-1 and 8.1-2 are simplified diagrams of gaseous radwaste j
processing and gaseous effluent flow.
t 8.1.1 Main Chimney Releases I
8.1.1.1 Unit 1 Chimney Particulate, Iodine, and Noble Gas Monitor i
Noble gases (N.G. 's) released from the Unit 1 chimney are monitored I
primarily by a microprocessor-controlled offline system which provides continuous monitoring of an effluent sample stream taken 4
l y,
from a point high in the chimney where good mixing is ensured.
l,/
The affluent gas sample is drawn past several detectors viewing a sample volume.
The low and medium range N.G. detectors view the same volume, while the high range N.G. detector views externally a section of one inch stainless steel tubing as its sample volume.
The low range is monitored by a beta scintillation detector (Eber-i line Model RDA-3A), while both the medium and high range measurements are performed by an energy-compensated GM detector (Eberline
(
Part Number TUGMS).
Background subtraction is provided for all three ranges.
Sample flow is provided by a stainless steel diaphragm vacuum pump and an air flow regulator.
Sasple flow is set at approximately 60 liters per minute and monitored by a solid-state flow sensor.
In addition to the noble gas monitoring, the gas sample is routed through a filter paper, on which particulates are deposited, then through a charcoal cartridge which traps iodines.
)
A backup system is available for the Unit I chimney and can provide continuous monitoring of the same sample stream.
The backup system utilizes a sodium iodide detector in a shielded sample S
8.1-3 i
e
%m
- s w --
)
DRESDEN REVISION 11 MARCH 1985 h,
chamber to monitor for noble gases.
Flow is provided by a sample pump with a constant flow regulator.
The backup system also provides the sample media to collect particulates and iodines.
l The microprocessor-controlled gaseous effluent monitoring systen (Eberline SPINGN) is located in the sphere and turbine building 4
vent fan exhaust room.
The monitoring system's control terminal, strip chart recorder and annunciating panel are located in the control room on Panel 923-7.
Each N.G. channel has a strip chart recorder with a log-scale display ranging from 10 counts per minute to 1,000,000 counts per minute.
The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector.
Changes in detector operational status are automatically printed and audibly acknowledged.
The SPING-4 microprocessor's memory has battery backup to maintain j
all operating parameters and history files for any detector in the event of a system power loss.
c i..e
- w The backup monitoring system is located in the sphere and turbine building vent fan exhaust room next to the SPING-4.
The backup system's recorder, high radiation annunciation, and radiation monitor are provided in the Unit 1 control room.
The monitor and
}
recorder have log-scale displays with a range of 10 to 10,000,000 counts per minute.
The SPING-4 monitoring systen is supplied with 120-Vac.
~
The Eberline SPING-4 effluent monitoring system's part number is SPING-4 (RM 2/3-1798).
The backup syrten receives its power from the essen-tial service auxiliary buses.
Th'e detector equipment part number is RE-128.
Unit 1 chimney ficw is currently based on rated fan
- flow, h
i i
8.1.1.2 Units 2/3 Chimney Particulate, Iodine, and Noble Gas Monitors l
Noble gases (N.G. 's) released from the Unit 2/3 chimney are monitored 8.1-4 u-
^
- C
. _ _,-m.
m.
_.m_.
i i
DRESDEN REVISION 11 MARCH 1985 O
primarily by a microprocessor-controlled offline system which provides continuous monitoring of an effluent sample stream taken from a point high in the chimney where good mixing is ensured.
The effluent gas sample is drawn past several detectors viewing a sample volume.
The low and medium range N.G. detectors view the same volume, while the high range N.G. detector views externally a section of one inch stainles,s steel tubing as its sample volume.
The low range is monitored by a beta scintillation detector (Eberline Model RDA-3A), while both the medium and high range measurements are performed by an energy-compensated GM detector (Eberline i
part number TUGMS).
Background subtraction is provided for all i
three ranges.
Sample flow is provided by a stainless steel diaphragm
]
vacuum pump and an air flow regulator.
Sample flow is set at approximately 60 liters per minute and monitored by a solid-state I
flow sensor.
In addition to the monitoring system described above, two thallium-activated sodium iodide detectors (RE-1730A l
and RE-17308) from the originally installed General Electric system
~
j are in series with the sample stream and provide an online backup j
to the primary SPING-4/Victoreen) effluent monitoring system.
The primary effluent monitoring system has postaccident sampling
{
capabilities.
In addition to the N.G. monitoring, the gas sample
{
is routed through a filter paper on which particulates are deposited, then through a charcoal cartridge which traps lodines, i
A separate backup monitoring path is available and can provide continuous monitoring of the same sample stream while the primary monitoring system is out of service.
The backup path provides the sample media to collect particulates and iodines and also utilizes the two G.E. noble gas monitors discussed above.
No postaccident sampling capabilities are available when the backup monitoring path is in service.
The microprocessor-controlled gaseous effluent monitoring system (Eberline SPING-4) is located in the max recycle demineralizer 8.1-5 l
j 1
DRESDEN REVISION 11' MARCH 1985 The monitoring system's control terminal, strip chart area.
recorder and annunciating panel are located in the control room on Panel 9 23-7.
Each channel has a strip chart recorder with a log-scale display ranging from 10 counts per minute to 1,000,000 counts per minute.
The control terminal provides immed(ate access to current detector activity, operating parameters, and history files for any detector.
Changes in detector operational status are automatically printed and ' audibly acknowledged.
i The backup monitoring system's (G.E. detectors and electronics) recorder, high radiation annunciators and log count process radiation monitors are located in the main control room on Panel 923-7.
The backup monitors and record.er have log-scale displays with a range of 0.1 to 1,000,000 counts per second.
The backup monitors are powered with 24-vde from the station's battery system.
!le-The SPING-4 microprocessor's memory has battery backup to maintain all operating parameters and history files for any of its detectors in the event of a system power loss.
i A safety-related bus supplies 120-vac to the primary effluent monitoring system.
The Eberline SPING-4 effluent monitoring system's part number is RM 2/3 1796.
Unit 2/3 chimney flow is derived from a Rosemount differential pressure transmitter and can be obtained from either the SPING-4 or the Units 2 and 3 process computers.
8.1.1.3 SJAE Off-Gas Monitors i
The major source of radioactive noble gases is from each unit's off-gas system.
Each unit's off gas system has its own radia-tion detection instrumentation capable of isolating the offgas release pathway.
-s 8.1-6
~ ~ ~ ~
_ -. _. _ _ _ - - - _ - -, + -. - - _ _
~
DRESDEN REVISION 11 MARCH 1985 8.1.1.3.1 Unit 1 Unit 1 is not operational so there is no off-gas.
8.1.1.3.2 Units 2/3 SJAE Off-Gas Monitors Off-gas from the main condenser is monitored for gross gamma activity downstream of the SJAE's and prior to release to the main chimney.
Two gamma-sensitive ionization chambers located adjacent to and near the beginning of the off-gas holdup lines provide continuous monitoring of the steam jet air ejector off-gas radioactivity levels.
Off gas monitoring for each unit is performed in two channels.
Each channel includes a gamma-sensitive ionization chamber detector and a logarithmic radiation monitor.
The detector equipment part numbers are RE2(3)-1733A and RE2(3)-1733B.
The two channels share a common two-pen recorder and a trip aux-iliaries unit whose output feeds an interval timer with a variable setting ~ of 0 to 15 minutes.
A high radiation condition in the holdup pipe will result in activation of the interval timer.
When the pre-selected time interval has elapsed, the timer provides a signal to the solenoid-operated valves which control the air supply to the air-operated isolation valve A02(3)-5406.
Closure of the isolation valve located at the off gas inlet to the chimney prevents the release of radioactive off gas to the chi'mney.
The system radiation monitors, recorders, alarm annunciators, and interval timers are located on the panels in the control The monitors and recorders have logarithmic scale dis-room.
plays with a range of 1 - 106 counts per second.
)
Each monitor is supplied with 120-Vac,from a different reactor protection system bus.
120-Vac is supplied to the interval timers
(
j from the essential service bus.
8.1-7 y
DRESDEN REVISION 11 MARCH 1985
(
8.1.1.4 Allocation of Effluents from Common Release Points l
Radioactive gases, particulates, and iodines released from the Unit 1 chimney originate from Unit 1 only.
However, radioactive gageous effluents released from the Units 2/3 chimney are com-i prised of contributions from both units.
Estimates of noble gas contributions from Units 2 and 3 will be allocated considering appropriate operating conditio*ns and measured SJAE off-gas activities.
Allocation of radiolodine and radioactive particulate releases to Units 2 or 3 specifically is not as practical and is influenced greatly by in-plant leakage.
Under normal operating conditions, allocation will be made using reactor coolant iodine activities.
During unit shutdowns or periods of known major in plant leakage, the apportionment will be adjusted accordingly.
The allocation of effluents will be D-b estimated on a monthly basis.
8.1.2 Units 2/3 Reactor Building Ventilation Stack Releases 8.1.2.1 ventilation Stack Monitors i
The reactor building ventilation exhaust monitoring sys' tem provides-continuous monitoring of reactor building effluent gases.
Upon indication of abnormal radiation levels in the effluent gases, the reactor building ventilation system is isolated, and standby gas treatment is initiated.
Two instrumentation channels provide continuous monitoring for both Units 2 and 3 reactor building exhaust gases with two sensor-converter units located in the exhaust ducts just upstream of the ventilation exhaust isolation valves.
The sensor is a Geiger-i Mueller tube, polarized by high voltage from the power supply.
[
The output signal from each sensor converter is applied to an indicator and trip unit, where it is amplified and used to drive q
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MARCH 1985 i
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a meter'.
This unit' also provides trip functions' for,2pscale
-/
and downse' ale alarms through auxiliary units.
j A downscale trip in either channel annunciates a Icw cadiation (malfunction) ' alarm. / *n} oje,cale trip in either channp1'lititiates a reactor building v;ntillatio,n system high-high radiation alarm.
e Control logic is s'uch that one channel high level trip or two l
channe$ low level trips will shut down and isolate theyreactor building ventilation egistem for both units and initiate 'the standby I
gas treatment mystem.
Eachsreactor build ng a ventilation system is <1solated by closure of two ai'r'-operated butterily valv6s (A02(3) A 57N1 and A02(3)B-1 5741) slocated in series \\ ownstream 'of the reactor building ventila-d tion supply fans and by closure of two air-operated butterfly i
r valves (A02(3) A-5742 and A02 (3)B-5742) located in se, ries downstrearv oftheradiatidnsensorsandtfstreamofthehxhaustfanc.
.a The exhaust duct monitors provide a signal to a t,wo-pen recorder i
which will annun,ciate a high radiation condition in the exhaust s
i duct.
This is an alarm only*and does not initiate corrective The c'ecorder, controls, ladicator and trip units, alarms, l
J action.
.andannunciatorsarelocatedonpInelsinthemaincontrolroom.
The power supply to each sensor channel is supplied from a different power scurce.
The A channel is fed from the 120-Vac A reactor pr.otection system, and the B channel is fed from 120-Vic B reactor i
. protection system.
i i
~
Theindicatingmetershavealogarithmicscalewitharangh;?of c
i 0.01 to 100 mR/hr.
The sensor and converter units have equip-Cent part numbers RE2(3)-1735A and REi(3)-1735B.
1 l
N l e
In addition to the "radiatkon monitors installed in the exhaust,,
I ducts, two additional mon $.toring systems are available.
The l
s I
s 8.1-9 J
k' t
-n, v.
DRESDEN REVISION 11 s
N' MARCH 1985 first system consists of the Units 2 and 3 reactor building vent sampling stations.
This offline system routes the sample stream through a filter paper on which particulates are deposited, then through a charcoal cartridge which traps iodines.
Taps are also provided for obtaining a grab sample for N.G. determination.
The reactor building vent sampling stations receive power from the essential service system bu's an.d are physically located in the turbine building on the third floor mezzanine above the Unit l
2 turbine.
1 The second system (Eberline SPING-4) provides trending capabilities for the combined reactor building. effluents.
This system provides i
continuous monitoring of an effluent sample stream taken from a point in the stack where good mixing is ensured.
The effluent gas sample is drawn past several detectors viewing a sample volume.
The low and medium range N.G. detectors view the same volume, while the high range N.G. detector views externally a section s-of one inch stainless steel tubing as its sample volume.
The low range is monitored by a beta scintillation det4ctor (Eberline Model RDA-3A), while both the medium and high range measurements are performed by an energy compensated GM detector (Eberline Part Number TUGM5).
Background subtraction is proivded for all
~'#
three ranges.
Sample flow is provided by a stainless steel diaphragm vacuum pump and an air flow regulator.
Sample flow is set at cyproximately 60 liters per minute and monitored by a solid-state flow sensor.
In addition to the noble gas monitoring, the gas cample is routed through a filter paper on which particulates are deposited, then through a charcoal cartridge which, traps iodines.
The microprocessor-controlled gaseous effluent monitoring system l
(Eberline SPING-4) is located in the turbine building second
[3 floor mezzanise above the Unit 2 turbine.
U#
The monitoring system's control terminal, strip chart recorder and annunciating panel are located in the control room on Panel 923-7.
Each N.G. channel 8.1-10
DRESDEN REVISION 11 MARCH 1985 has a strip chart recorder with a log-scale overlay ranging from 10 counts per minute to 1,000,000 counts per minute.
The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector.
Changes
. in detector operational status are automatically printed a.nd audibly acknowledged.
The SPING-4 microprocessor's m'emory has battery backup to maintain all operating parameters and history files for any detector in the event of a system power loss.
A safety-related bus supplies 120-Vac to the SPING-4 monitoring system.
The Eberline SPING-4 effluent monitoring system's part number is SPING-4 (RM 2/3-1797).
The 2/3 reactor building stack flow is derived from a Rosemount differential pressure transmitter and can be obtained from either the SPING-4 or the Units 2 and 3 process computer.
8.1.3 Chemical cleaning Facility The Dresden Unit 1 chemical cleaning was performed by passing IT Corporation solvents NS-1 & 2 through the primary system in l
order to remove radioactive contaminants.
The contaminated solutions resulting from the process were pumped to the chemical cleaning facility and collected in two receiving tanks.
The next phase of the process involves concentrating the waste solutions with the use of evaporator equipment and solidifying the wastes via appropriate methods.
The chemical cleaning process did not involve the fuel and control rod drives and blades.
For this reason, in combination with the fact that water has been drained from the primary system, detectable amounts of radioactive noble gases were not expected to be released from the chemical cleaning facility during the l
8.1-11 c
DRESDEN REVISION 11 MARCH 1985 chemical cleaning process.
Monitoring capabilities for sampling for particulates was established.
i i
~
An estimated 1000 Curies of activity are expected to be removed from the primary and unloading heat exchanger systems at the completion of the process.
The predominant radioisotope detected has been Co-60.
N. s I
l e
8.1-12 u.
~-
~
DRESDEN REVISION 11 MMtCH 1985 8.1. 4 Symbols Used in Section 8.1 SYMBOL NAME UNIT Q
htal Release Rate, Stack ts (uCi/sec)
Release If Gamma Whole Body Dose Constant, (mrad /yr per UCi/sec)
Stack Release f g Fractional Radionuclide Composition Q
Total Release Rate, Vent Release (uCi/sec) tv Vf Ganana Whole Body Doie Constant, Vent (inrad/yr per Release UCi/sec)
( ^',
Q LJ tg Total Release Rate, Ground Level (uCi/sec)
Gg Gamma Whole Body Dose Constant, (mrad /yr per Ground Level Release UCi/sec)
Q Release Rate at Nuclide i, Stack (WCi/sec) is Release Q,
Release Rate of Nuclide i, Vent g
(uCi/sec) i Release Q
Release Rate of Nuclide i, Ground gg (UCi/sec) i Level Release l
L Beta Skin Dose Constant g
(mrem /yr per UCi/m )
(X/Q),
Relative Effluent Concentration, (sec/m )
m Vent Stack Release l
i A g Radiological Decay Constant (hr~1) 8.1-13 L
DRESDEN REVISION 11 MARCH 1985
[
SYMBOL NAME UNIT R
Downwind Range (m) u, Average Wind Speed, Stack Release (m/sec)
(X/Q),
Relative Effluent Concentration, (sec/m )
Vent Release u,
Average Wind Speed, Vent Release (m/sec)
(X/Q)g Relative Effluent Concentration Ground (sec/m )
3 Level. Release ug Average Wind Speed, Ground Level Release (m/sec)
S g-Gamma Dose Constant, Stack Release (mrad /yr per
[Sl pCi/sec)
Vg Gamma Dose Constant, Vent Release (mead /yr per pCi/sec)
Gg Gaauna Dose Constant, Ground Level (mrad /yr per Release pCi/sec) l l
l N
s i
8.1-14 g
DRESDEN REVISION 11 MARCH 1985 8.1.5 Constants Used In Section 8.1 NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (ares /arad) a 3600 Conversion Constant (sec/br)
/
m m
g h
4 i
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0 8.1-15
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REVISION 11 MARCH 1985
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DRESDEN REVISION 11 MARCH 1985 8.2 LIQUID RELEASES Alarm setpoints of liquid effluent monitor's of the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area.
The concentration limit (Cig,) in the discharge line prior to dilution in the initial dilution stream is:
d r
8'"
- Clia = MPC r
. y max (8.6)
C Limiting Concentration in y g, Discharge Line (pci/al)
The maximum concentration in the discharge line permitted to be discharged to the initial dilution stream.
r, MPC Weighted Maximum Permissible (uci/ml)
Concentration n
4 EC g L Ag MPC = i"1 i"1 or n
C n
A g
g i1 i1 (8.7) where C
= WCi/ml of nuclide i; g
~
MPCg = maximum permissible concentration pCi/ml of nuclide is and Ag
= DCi of nuclide i released in time t.
i E
F Maximum Flow Rate, (ft /sec)
Radwaste Discharge The maximum flow rate of radwaste from the discharge tank to the initial dilution stream.
8.2-1 l
DRESDEN REVISION 11 i
MARCH 1985
,i F,,
Average Flow Rate, Initial (ft /sec)
Dilution Stream 4
The average flow rate of the initial dilution stream *w'hich carries the radionuclides to the unrestricted area boundary, i
Surveillance frequencies for the liquid effluent monitors will be as stated in Tables 4.2-3 (Unit 1) and 4.2-2 (Units 2/3) of the Technical Specifications.
Calibration methods for the radiation monitors will be consistent with the definition in Section 1.0 of the Technical Specifications.
l Figure 8.2-1 is a simplified diagram of liquid radwaste processing and liquid effluent flow.
8.2.1 Units 2/3 Efflueht Line Activity Monitor Liquid radwaste discharges are monitored with an offline system j
in which a continuous sample stream feeds a sample chamber moni-l tored with a 5-inch x 4-inch NaI detector.
Pressure maintained in the discharge line during effluent release provides the driving l
force for the sample stream which is collected in a holding tank after passing through the sample chamber.
The sample stream inlet is located in the radwaste discharge line immediately upstream of the high and low flow branches used for effluent flow rate control.
Pulses from the detector's photomultiplier tube are amplified by a pre-amp powered from the monitoring system high voltage power supply.
The detector signal feeds a single channel analyzer
)
in which counts are accumulated over a specified period of time.
At the end of each counting interval, the sample count is printed 8.2-2
DRESDEN REVISION 11 MARCH 1985 out at the monitoring system console, and.a new count is auto-matically initiated.
The counting channel also feeds a comparator which is equipped with a relay to activate the h'igh radiation / loss-of-power alarm on the radwaste control panels.
The alarm setpoint for this function is determined by analyzing the activity of each liquid radwaste batch prior to discharge.
This information is then considered in conjunction with dilution flow rate for determination of an alarm level that ensures the discharge will be terminated prior to exceeding the concentration limits expressed in Equation 8.6.
J Upon. activation of the high radiation / loss-of power alarm, a 4
grab sample of the effluent is automatically taken from the discharge side of the sample chamber af ter a 0 - 60 second delay
(;
determined by a locally mounted timing device.
The liquid effluent L
release is terminated by manually initiating the closure of the low flow (A0 2001-170) or high flow (A0 2001-195) discharge line valves.
1 The sodium iodide detector, sample chamber, grab sample chamber,
{
sample receiver tank, and sample return pump are located on the 517 foot elevation of the radwaste building.
The interval j
timer and solenoid-operated valve controlling grab sample ini-i tiation are supplied with 120-vac from distribution panel 37-4.
i a
)
The monitoring console, including high voltage supply, single
)
{
channel analyzer, comparator for alarm annunciation, scaler,
{
and printer (0 - 999,999 counts) are located in the radwaste control room.
Equipment in the monitoring console is supplied l
with 120-Vac'from distribution panel 35-3.
8.2-3
DRESDEN REVISION 11 MARCH 1985 8. 2. 2' Allocation of Effluents from Common Reletie Points i
Radioactive liquids effluents released from the radwaste treatment system are comprised of contributions from all three units.
Under normal operating conditio'ns, it is difficult to apportion the radioactivity between the units.
Consequently, allocation will normally be made evenly between units.- During refueling outages or periods of known major.in-plant leakage, the apportion-ment will be adjusted accordingly.
The allocation of the effluents will be estimated on a monthly basis.
8.2.3 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been implemented to ensure proper control of radioactive liquid radwaste discharges to preclude a release in excess of 10 CFR 20 limits.
The discharge rate for each batch is calculated and independently verified by two operating staff personnel.
The discharge valve is locked closed at all times except during the discharge.
All other lines, which tie in'with tne discharge line, are locked closed.
The high and low flow control valves are selected by a key-lock sw' itch which allows the use of only
)
one of the two flow control valves at any one time.
The key to this switch and the locked valves is under the administrative control of the radwaste foreman.
l l
A documented valve checklist is prepared for each batch discharge The proper valve lineup is checked by the operator and the radwaste foreman, prior to release.
If any sudden significant increase in the radiation monitor occurs during the discharge, the release is terminated.
These controls are documented in Station Operating Ond Administrative Procedures, n.
8.2-4
i DRESDEN REVISION 11 MARCH 1985 8.2.4 Service Water Header Releases 8. 2. 4.1 Units 2/3 Service Water Effluent Monitors 1
Each unit's main service water e'ffluent header is continuously 7
l monitored for radioactivity.
The monitoring channel for each
^
unit consists of a NaI-Tl scintillation detector, pulse pre-l amplifier, and process radiation monitor.
The system's detec-tors (RE2(3)-1734) are located next to a vertical section of each unit's main service water effluent header.
The service water effluent monitor on each unit provides a signal to a recorder and trip auxiliary which initiates a high radiation alarm.
The process radiation monitor, recorder, alarm, and t
annunciator are located on the panels in the main control room.
]
The monitors and recorders have logarithmic scales with a range
~1 6
of 10 to 10 counts per second.
The monitors are supplied with 24-voc from the' station's battery system.
1 j
.The constant background radiation of variable intensity to which
{
the detectors are subjected precludes the calculation of alarm setpoints for the monitors based upon isotopic concentrations.
Monitor alarms will be set at twice the upper and lower values of the normal range within which the. monitors function.
8.2.5 Chemical Cleaning Facility Service Water Effluent Monitor 4
Continuous monitoring of the chemical cleaning facility's service j
water is provided by an offline sampling system located in the cervice water building.
The effluent water is monitored by a sodium iodide detector which is shielded to reduce background.
A logarithmic scale rate scale rate meter with a range of 6
~10 - 10
,g h
counts per minute is provided locally.
Additionally, a count totalizer and instrument high radiation and downscale i
I' 8.2-5 g.
- ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~
1 DRESDEN REVISION 11 MARCH 1985 alarms are provided locally.
High radiation, downscale, and loss of sample flow alarms are also provided in the control room.
i Continuous recording (logscale 10 - 106 cpm) of effluent activity is also provided in the control room.
The monitoring system assembly, identification number NASMC-06641-0700, is supplied with 100-vac from motor control center 9-B.
No automatic isolation is associated with the above system.
Upon detection of an abnormal radioactive discharge level, isolation is achieved with cooling water return isolation valve AOS-06699-7404.
i 8.2.6 i
Determination of Initial Dilution Stream Flow Rates For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine j _
the flow rate of the initial dilution stream.
This instrumenta-tion will be operated and maintained as prescribed by the Tech-nical Specifications.
,For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve position indication.
s 8.2-6
s DRESDEN REVISION 11 MARCH 1985 8.2.7 Symbols Used In Section 5.2 SYMBOL NAME i
UNIT C
Liquid Release Limit lim (pci/ml)
MPC Weighted Maximum Permissible (pCi/ml)
Concentration C
Nuclide Concentration i
(pCi/ml)
MPC Maximum Permissible g
Concentration (pCi/ml) 1 A t Nuclide Quantity Released (pCl)
F,,,
Maximum Flow Rate, Radwaste (ft /sec) 3
,)
Discharge d
F y,
Average Flow Rate, Initial (ft 7,,e) 3 Dilution Stream i
Cd Concentration, Liquid Effluent
. (pCi/ml) in the Discharge Line l
I 8.2-7 r-
O ILLINDIS RIVER p-l
\\'
f I
1 e
ma l
1
'EE!2 -+ E
~
W
~+ LT="E aWiN=
Y a *
+,2 5 = % -*
r-Gil :
-+
W _....I...I.....i...........
g
[
'="=='a==
am.u-fal i
L".."J.'.pT.'M
=
,/
ft 4
= -3.
~
g T e m:,
. "g' i
ni f
i
=u2-.s
/
[l
~
e f
d'}--
i y
6
.=. >, I i
=
. ur-g 4
f ei6 s
L
/
DRESDEN STATION u== = =us 6
UNITS I,2 AND 3
{E;
+ =. = _.
n.
FIGURE 8.2-1 H!
I " "' '"
SIMPLiflED L10Ul0 RADWASTE 8'35 E="ME==
PROCESSING AND
~~~~"""..g._--"""."
L10010 EFFLUENT FLOW DI AGRAM gO
,c "
g H
DRESDEN REVISION 11 MARCH 1985 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM i
The process control program (PCP) shall contain the samplir.g, analysis, and formulation determination by which solidification of radioactive waster from liquid systems is ensured.
Figure 8.3-1 is a siaplified diagram of solid radwaste processing.
I i
l l
D 8.3-1 og.p-
,y,#-s=
V W LT "fe"
=
.N /
TatW p
u ahq=
r a
r i
r a
sus usu==
r r
i i
WW
""MT *"
l
=
DRESDEN STATION UNITS 2 AND 3 ll FIGURE 8.3-1 SIWLIFIED SOLID RADWASTE ti;@
PROCESSING DIAGRAM m
"U l
DRESDEN REVISION 11 MARCH 1985
{
8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around Dresden Nuclear Power Station is given in Table 8.4-1.
Figure 8.4-1 shows the 17 fixed air sampling sites and TLD locations; also shown are the outer ring TLD locations.
Figure 8.4-2 shows near station water sample locations and l.
the inner ring TLD locations.
t XYY-N, The TLD's are coded as follows:
Where:
X=1, means inner ring; X=2, means outer ring; and YY-N is an identification code.
Figure 8.4-3 shows the milk sample locations and more distant water sample locations.
The reporting levels for radioactivity concentrations in environmental samples are given in Table 8.4-2.
The prac-tical lower limits of detection for this program are given in Table 8.4-3.-
l b
x 8.4-1
(-
TABLE 8.4-1 ENVIRONMENTAL RADI0tACICAL NONITORING PROGRAM EEPOSURE PATNWAY AND/OR SAMPLE SAMPLING OR TYPE AND FREQUENCY SAMPLINC OR MONITORINC LOCATIONS COLLECTION PREQUENCY OF ANALYSIS 1.
Airborne a.
Onsite or Near Field" Radiciodine Canister Radiolodine and D-01, Onsite Station 1, 0.6 mi NW Continuous sampler I-131 analysis Particulates D-02, Onsite Station 2, 0.3 al NE operation with sample biweekly D-03, Onsite Station 3, 0.4 mi S collection weekly D-04, Collins Road, 0.9 mi W D-05, Bennitt Farm, 0.9 mi NE Particulate Samplers D-06,. Pheasant Trail, 0.9 mi SE Cross beta analysis followfngfilter 1
change b.
Far Field" Sampling Train s.
D-07, Clay Products, 2.0 ml 8 E-d
. D-08, Prairie Parks, 4.0 mi SW Test and maintenance D-09, Coal City, 7.5 mi S weekly g
D-10, Coose Lake
- Village, 3.8 mi SW D-II, Morris, 8.0 mi W 1
D-12, Lisbon, 10.0 mi NW D-13, Minooka, 4.5 mi N i
D-14, Channahon, 3.5 mi NE D-15, Joliet, 12.5 al NE D-16, Elwood, 8.0 mi E i
D-17, Wilmington, 8.0'ai SE a::
O TABLE 8.4-1 (Cont'd)
EXPOSURE FATWAY SAMPLING DR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 2.
Direct Radiation a.
At Air Sampilns Sites Quarterly Caumna dose quarterly Same locations as flued air samplinE locations in Item 1.
b.
Inner Rinac 101-1, 1.0 mi N 101-2, 1.0 mi N 102-1, 1.3 mi NE 102-2, 1.4 mi NE 105-1, 0.9 mi SE 105-2, 0.9 mi SE 109-1, 0.8 mi S 109-2, 0.8 mi S
!!0-1, 0.5 mi SW ca 110-2, 0.6 mi SW
'y 111-1, 0.7 mi SW u
111-2, 0.7 mi SW G
112-1, 0.9 mi SW E
112-2, 0.9 mi SW
!!3-1, 0.9 mi W 113-2, 0.9 mi W 114-1, 0.8 mi W 114-2, 0.8 mi W 115-1, 1.0 mi W
!!5-2, 1.0 mi W c.
Outer Ring
- 201-1, 4.5 mi N h
201-2, 4.5 mi N 202-1, 5.0 mi NME g N 202-2, 5.0 mi NNE O.$
E 203-1, 4.5 mi NE 203-2, 4.5 mi NE
1 TABLE 8.4-1 (Cont'd)
REPOSURE PATNWAY AND/OR SAMPLE SAMPLING OR TYPE AND FREQUENCY 8ANFLING OR DENIITORING LOCATIONS COLIACTION FREQUENCY OF ANALYSIS 2.
Direct Radiation c.
Outer Ring (Cont'd)
(Cont'd) 204-1, 5.0 mi ENE 204-2, 5.0 mi ENE 205-1, 4.2 mi E 205-2, 4.2 mi E 206-1, 3.5 mi ESE 206-2, 3.5 al Est 207-1, 4.5 mi SE 207-2, 4.5 mi SE 208-1, 5.0 ml 88E 208-2, 5.0 mi SSE 209-1, 5.0 mi 8 209-2, 5.0 mi 8 210-1, 4.8 mi SR 210-2, 4.8 al SE
,os 211-1, 5.0 at 88 f
211-2, 5.0 mi SE l
212-1, 4.8 mi WSW g
212-2, 4.8 mi WSW g
213-1, 4.5 mi W 213-2, 4.5 mi W 214-1, 4.5 al WNW
~
214-2, 4.5 mi WNW 215-1, 5.1 mi NW 215-2, 5.1 al NW 216-1,,4.8 mi NNW
-216-2, 4.8 mi NNW ce 1A
i TABLE 8.4-1 (Cont'd)
EXPOSURE PATNWAY AND/OR SAMPLE SAMPLING OR TYPMANDFREQUENCY SAMPLINC OR MMlITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 3.
Waterborne *'d a.
Surface D-21, Illinois River at Weekly collection Camma isotopic EJ&E RR Bridge, I mi W composited monthly monthly D-22, Illinois River at Morris, Quarterly Tritium and gross 8 mL W beta quarterly D-31, Coose Lake Corp. of England, quarterly Tritium and gross 2.0 mi S beta quarterly D-33, Pond West of MFRP, 0.8 mi S Quarterly Tritium and gross beta quarterly g(
b.
Lake Water i
D-34A&B, Dresden Road and County Weekly Canuma isotopic and EI a;
Road gross beta analysis weekly c.
Well Water D-23, Thorsen Well, 2.0 mi 8 Quarterly Cross beta, gross alpha and tritium quarterly d.
Cooling D-18, Inlet, Unit 1, at Station Weekly collection Crose beta analysis i
Water D-19, Discharge, Unit 1, at Station Sample D-20, Discharge, Unit 2/3, at Station weekly e.
Sediment D-27, Dresden Lock & Dam, 0.5 mi W Annually Camma isotopic gR' from Shoreline annually g$,
hO<
l l
l l
I
/
, TABLE 8.4-1 (Cont'd)
EEPOSURE PATHWAY AND/OR SAMPLE SAMPLING OR TYPE AND FREQUENCY SAMPLINC OR MONITORING IACATIONS COLLECTION FREQUENCY OF ANALYSIS 4.
Intestion j
a.
Milk D-24, Clow Farm, 5.0 mi NE
'i Weekly collection I-131 analysis when animals in on all samples pasture (May to Oct.);
monthly, November j
to March D-25, Vince Biros Farm, !!.5 mi SW D-26, Trotter's Dairy, 6.1 mi 8 b.
Fish D-28, Dresden Pool of Illinois River, Semiannually Gamma isotopic O.5 mi W j
analysis on edible portions of each sample L
A E
i
- See Figure 8.4-1 b
A gessna isotopic analysis shall be performed whenever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the preceding calendar quarter for the sample location
- See Figure 8.4-2 g
See Figure 8.4-3 E
EO 4
e M>*
f
TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WhTER ANALYSIS (pC1/1)
AIRBORNE PARTICUgTE FISH MILK FOOD PRODUCTS OR GASES (pCi/m )
(pC1/kg, wet)
(pC1/2)
(pCl/ke, wet)
H-3 20,000a Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 20,000 In-65 300 h
i 20,000 A
w Zr-Nb-95 400 N
- s I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 2,000 Cs-137 50 20 1,000 70 2,000 Ba-La-140 200 300
- For drinking water samples.
This is 40 CFR Part 141 value, au YV l
e,
[
j
TABLE 8.4-30 i
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a
LOWER LIMIT OF DETECTION (LLD)D MATER AIRBORNEPARTICgLATE FISH MILK SEDIMENT ANALYSIS (pCi/t )
OR GAS (pCi/m )
(pC1/kg, wet)
(pC1/1)
(pCi/kg, dry)
Gross B.ta" 5
0.01 1,000 5
2,000 Gamma Isotopic 20 0.01 200 20 200 I-131 5
0.10 100 5*
d Cs-134 10 100 10 Cs-137 10 D
100 5
g
.i H-3 200 E
=
e i
e 8
1 I!
-e_e.. s
- i.. e,.,ou _ 1.,.....
Eb t
__.~
DRESDEN REVISION 11 MARCH 1985
'(
TABLE 8.4-3 (Cont'd),
i 5
Other radionuclides which are measurable and identifiable a.
by gamma-ray spectrometry, together with the nuclides indicated in Table 8.4-3, shall also be identified and reported when an actual analysis is performed on a sample.
Nuclides which are below the LLD for the analyses shall not be reported as being present at' the LLD level for that nuclide.
b.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 54 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radio chemical separation) 4.66.' (S )
b (A) (E) (V). (2.22). (Y) (exp (,-lat)). (t)
)
Where LLD is the "A priori" lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume).
is the square root of the background count or of a blank S
le count;'it is the estimated standard error of a background s
count or a blank sample count as appropriate (in units of counts),
i E is the counting efficiency (as counts per disintegration).
A is the number of gamma-rays emitted per disintegration for gamma-ray radionuclide analysis (A = 1.0 for gross alpha and tritium measurements),
v is the sample size (in units of mass or volume).
2.22 is the number of disintegrations per minute per picoeurie.
{
Y is tne fractional radio-chemical yield when applicable i
(otherwise Y = 1.0).
Lambda is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes).
i
- 1 i
8.4-9
I DRESDEN m
REVISION 11 U
MARCH 1985 TABLE 8.4-3 (Cont'd) t Delta t is the elapsed time betweed the mid collection and the istart time of counting. point of sample (At = 0.0 for environmental samples and for gross alpha measuretsents).
t is the duration of the count *(in units of minutes).
. The value of "S " used in the calculation of the LLD for a detection systeN shall be based on an actual observed background i
count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value.
Typical values of "E",
"V",
"Y",
"t", and " delta t" shall be used f
in the calculation.
\\
For gamma-ray radionucl'ide analyses the background counts i
are determined from the total counts in the channels which are within plus or minus one FWHM of the gamma-ray photopeak energy n(Full Width at Half Maximum) titative analysis for that radionuclide.ormally'used for the quan-Typical values of the
(}
FWEM shall be used in the calculation.
s The LLD for all measurements is defined as an "A priori" (before the f act) of a measurement system and not as an "a posteriori" limit repres (after the fact) limit' for a particular sample measurement.
1 Referencedf to Cj?l37.
- c.
d.
For thyrol'd.
0.5 pCi/t ons samples collected during the pasture, se'ason, e.
t
' l 4
k
{
e
+
+
m
,4
'~
0,4-10
~
REVISION 11 MARCH 1985 O
/
IkT e
o
\\s < + NNN 8
s f
$"*',.h/
I E'. j.{ ff' g+ 1s 1
12
.m.,
2,
,2;>
- 2rr / /
- 2m.2 g 13 em.,
/2,<-, 22 g 34
,, 20's 20s2 f /,232
,.,.s
!,,,., 1 8 N
we
~'
h "h *6 m-8 oso.wy y 2ir 2 2s2 miM._10 7
}
Moms 2n-2 y.,.
e.207-2 o,
a g206120s.,
210 2 y
- 'S' 17 g
arr.113 g*2 9M Coal City q?
%9 4,,
4 h
0 5
to Miles DRESDEN STATION UNITS 1. 2 & 3 FIGURE 8.4-1 FIXED AIR SAMPLING AND TLD SITES i -
AND OUTER RING TLD LOCATIONS 337 j '..
r;
REVISION 11 MARCH 1985
~
O
-P
]
4 e
1 o'
O
=
3
'/
=
ff CECO Row g
102-2 p
-5 115-1 115-2 50113 i:
g
,9 j so**
mi-2 m,
- Cemetery
]RW Towpath Road N
. en island Lock A
gnot* pp and Dam rr 27 ess m iic2
' " & 35 D.20 *.
M.
- D.21 1
D 19 Dhrine k+g
[
Dresden Nuclear
=
3 ="y Power Station
!p s
8-l g:F D 18e t4 9
112-2 I
OO@
255 2
- 1 iO3-i
){
g E
j 1052 Gooe*
1,n 2,3g,3 us;d Lake O
g c a'a-
==
=
Road o
Joliet Prairie o
.O state C
109-1
}
Yacht D.33 a
e g,
Cium ff h
k General Electric Co.
E os-2 o
i
=3 c3 j
4 23 0
1/2 1 Mile e
o o
0 1
t 2 Kilometers e
e
,'N DRESDEN STATION UNITS 1. 2 & 3 i:.
FIGURE 8.4-2
/
INNER RING TLD LOCATIONS AND NEAR STATION WATER I
M SAMPLE LOCATIONS 1
REVISION 11 MARCH 1985 3
o N
o I
U s
%s
.S. 6 l-80 v
9 n
i e
D.24*
5
)
s-so D 23 A
D.34 D 22 A&B D.31 Morris D
- D.26
)
s lit.113 e
- D.25 Coal City 4,,
4 0
5 to Miles
?
'?
20 xinometers e
UNITS 1. 2 & 3 i
FIGURE 8.4-3
}
MILK SAMPLE LOCATIONS AND ) ORE DISTANT WATER SAMPLE LOCATIONS
~..
. ~....
N Commonwealth Edison l
7 Dresden Nuc'rzt Power St; tion
(
RA #1
\\
Morris, Illinois 60450 Telephone 815/942-2920 June 1, 1985 DJS LTR: 85-646 Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention:, Document Control Desk
Dear Sir:
Enclosed, please find Dresden Station's operating data for last month. This information is supplied to your office per the instruc-
-tions set forth in Regulatory Guide 1.16.
Sincerely, D.
. Scott Station Manager Dresden Nuclear Power Station DJS:DCM:hjb Enclosure cc: Region III, Regulatory Operations, U.S. NRC Chief, Division Nuclear Safety, State of IL U.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuclear Fuel Services Manager Nuc. Sta. Div. Vice Pres.
Manager, Tech. Nuc. Sta.
Tech. Staff AE On-Site.NRC Inspector Sta. Nuc. Eng. Dept.
Comptroller's Office PIP Coordinator-IhTO Records Center File /NRC Op. Data File / Numerical TE14 Ilr
,