ML20148D421
| ML20148D421 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/04/1976 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20148D430 | List: |
| References | |
| NUDOCS 8010010872 | |
| Download: ML20148D421 (117) | |
Text
INFORM ATION RELEVANT TO KEEPING LEVELS OF RADIO ACTIVITY IN EFFLUENTS TO UNRESTRICTED AREAS AS LOW AS REASON ABLY ACHIEVABLE (Filed in accordance with Section 3Z.B. of 10 C FR 50, Appendix I)
DRESDEN STATION
> U NIT 1 J U N E 4,1976 COMMONWEALTH EDISON COMP ANY 80/00 lD 910> %A
DRESDEN 1
,.m FOREWORD
\A This report is filed in accordance with the provisions of Section V.B.
of Appendix I to 10 CFR 50, and in response to a letter from Mr. D. L.
Ziemann of the Nuclear Regulatory Commission (NRC) to Mr. R. L. Bolger of the Commonwealth Edison Company (CECO) dated February 19, 1976 (Attachment A).
The format of the report follows the format of enclosures 1 and 2 of the above letter, and provides such information as is necessary to evaluate the means employed for keeping levels of radioactivity in ef fluents to unrestricted areas as low as is reasonably achievable.
Proposals to modify Technical Specifications related to Appendix I will be deferred until a later date, pending receipt of additional guidance from the NRC as noted in the above letter.
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DRESDEN 1
(~S TABLE OF CONTENTS V'
P_ age
. ENCLOSURE 1 Item 1.1 1.1-1 Item 1.2 1.2-1 Item 1.3 1.3-1 Item 1.4 1.4-1 Item 1.5 1.5-1 Item 1.6 1.6-1 Item 1.7 1.7-1 ENC 1,0SURE 2 Item 2.1 2.1-1 Item 2.2 2.2-1 Item 2.3 2. 3-1 Item 2.4 2.4-1 Item 2.5 2.5-1 Item 2.6 2.6-1 Item 2.7 2.7-1 Item 2.8 2.8-1 Item 2.9 2.9-1
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Attachment A - Letter from Mr. D. L. Ziemann of the Nuclear Regulatory Commission to Mr. R. L. Bolger of the Commonwealth Edison Company, dated February 19, 1976 Attachment B - Abstracts from Semiannual Reports Attachment C - Joint Prequency Distributions of Wind Speed and Direction by Atmospheric Stability Class i
O 1
1 11 i
DRESDEN 1
() LIST OF TABLES NUMBER TITLE PAGE 1.1-1 Estimated Annual Releases of Gaseous Effluents Based on Regulatory Guide 1.CC Assumptions 1.1-4 1.1-2 Consumption Factors for Maximum Exposed Individual 1.1-5 1.1- 3 Annual Individual Doses Due to Gaseous and Particulate Effluents 1.1-6 1.1-4 Maximum Air Dose Rate 1.1-7 1.1-5 Estimated Annual Releases of Liquid Ef fluents Based on Regulatory Guide 1.CC Assumptions 1.1-8 1.1-6 Liquid Effluent Pathways and Hydrological Dispersion 1.1-9 1.1-7 Pathways Doses f rom Liquid Ef fluents 1.1-10 1.5-1 Releases of Radionuclides in Liquid Effluents,
(} Dresden 1, 1974 and 1975 1.5-2 1.5-2 Releases of Radionuclides in Airborne Ef fluents, Dresden 1,1974 and 1975 1.5-3 1.5-3 Power Generating History, Dresden 1 - 1975 1.5-4 2.1-1 Parameters for Liquid Radwaste System 2.1-3 2.1-2 Main Condenser Of f-Gas Treatrent System 2.1-4 2.1-3 Gland Seal Condenser Of f-Gas Treatment System 2.1-5 2.2-1 Distances from Reactor to Locations of Interest, to a Distance of 5 Miles 2.2-2 2.2-2 Elevation of Nearest ; teat Animal 2.2-3 2.2-3 Elevation of Nearest Residence 2.2-4
- 2. 2-4 Elevation of Nearest Garden 2.2-5 l
. 2.2-5 Elevation of Nearest Site Boundary 2.2-6 2.2-6 Elevation of Nearest Point of Occupation 2.2-7
() 2. }- 1 Summary of Atmospheric Dispersion Factors and Deposition Values for Selected Locations 2.3-2 .
iii
DRESDEN 1 p LIST OF TABLES (cont 'd)
V NUMBER TITLE FACE 2.5-1 Wind Speed Distributions 2.5-3 2 . 5-2 Wind Direction Distributions 2.5-4 2.7-1 Joint Frequencies (Windspeed-Wind Direction-Stability) at Dresden Site 2.7-3 O .
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DRESDEN 1
/~g LIST OF FIGURES
(_/
NUMBER TITLE 1.1-1 Gaseous Radwaste System - Process Flow Diagram 1.1-2 Liquid Radwaste System - Process Flow Diagram 2.1-1 Reactor Enclosure Drain Tanks aad Fuel Handling Water Treatment System P&ID )
2.1-2 Radwaste Collection Tank, Filters and Waste Demineralizer Tank P&ID 2.1-3 Waste Neutralizer Tank and Secondary Steam Generator Waste Collector Tanks P&ID 2.1-4 Turbine Building Floor Drain Tank and Laundry Waste Treatment System P&ID 2.1-5 Liquid Waste Storage and Holdup Tanks P&ID j 2.1-6 Sludge Handling, Resin Storage and Waste Concentrator P&ID
() 2.1-7 Diagram of Modified Off-Gas Piping 2.1-8 Diagram of Modified Off-Gas Piping i 2.8-1 Topographic Features Within a 10-Mile Radius of the Dresden Nuclear Power Station 2.8-2 Topographic Profiles of the Area O to 5 Miles from the Dresden Station 2.8-3 Topographic Profiles of the Area 5 to 10 Miles from the Dresden Station 1
V
DRESDEN 1
() 1.1 "Licensees should provide an evaluation showing their facility's capability to meet the requirements set forth in Section II of Appendix I to 10 CFR 50."
Response
Station Appendix I Evaluation Gen eral l Since the last stat emen t in the FSAR, the following radwaste equipment has been or will be instelled:
- a. An of f-gas system will be installed on Unit 1 by September 1, 1976 to handle gaseous radioactive wastes. This system will have f our charcoal absorption beds, totaling 26 tons of char-coal, which will delay xenon 15.91 days and krypton 21.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b. A line connecting Unit i radwaste to Unit 2/3 radwaste was in-stalled on May 23, 1975 to allow transfer of regenerate solutions from Unit 1 to Unit 2/3 radwaste. The new line will enable re-generate solutions from Unit i radwaste to be concentrated and-barreled instead of being diluted and discharged into the river.
{} Gaseous Ef fluents i Radionuclides h1 Gaseous Ef fluents Estimates of the annual release of radionuclides in gaseous ef fluents ;
have been made using the assumptions of Regulatory Cuide 1.CC (September 1975) .
Schematically, the station systems af f ecting gaseous ef fluents are shown in Figure 1.1-1. More detailed P&ID's and operating parameters are given in It em 2.1. j i
Esticated annual releeses of radionuclides in gaseous ef fluents for the )
various sources are given in Table 1.1-1. l Release Points for Gaseous Ef fluents The release points, volumetric flow rates, vent / stack elevations, and diameters are shown in Figure 1.1-1.
Atmospheric Dispersion The dispersion of airborne radionuclides and subsequent deposition in the environment have been calculated using site joint frequency data and the methods of Regulatory Guide 1.111. The "Straight-Line Airflow Model" has been used. Terrain correction (recirculation) f actors (e.g.,
O Figure 2 of Regulatory Guide 1.111 and factors of 5 and 1.5 for down-valley, and up-valley flow, respectively) have not been utilized in 1.1-1
DRESDEN 1 O thie ene1xeis.
radiological monitoring results collected in the Station since 1971, Quad-Cities Station since 1972 environs of the resden 1973, and estimated radiation doses and airborne concentrati, ons of Zion Station since radionuclides computed with the straight line model show that re-a g
of dispersion over the open terrain regions , for both con-a onsof Illinoiscircula tinuous and noncontinuous releases. H en c e. , all ported were computed using the straight line model with a KX/Q and D/Q values re-Values of O " 1*
y item 2.3 of this report.X/Q and D/Q for the various points of interest are given in Dose Assessmen t_
has been calculated using the methods Guide 1.109.
ous effluents egulatory and data given in computer code and summarized in Tabic 1.1-2. Consumption factors used Specific and 1.1-4.doses at various points of interest are given i n Tables 1.1-3 All are within Appendix 1 to 10 CFR 50 guidelines .
L_iquid Ef fluen t s 9
Radionuclides in Liquid Ef fluen ts have (Septunberbeen1975) . made using the assumptions u
e 1.CC effluentsof Regulatory Gu Schematical1y, 1.1-2. More detailed P&ID'sthe station liquid radwaste system is shown in Fi gure Item 2.1. and operating parametere are given in given in Table 1.1-5. Estimated annual releases of radionuclides in liquid effluents are Rgease Points of Liquid Ef fluents Liquid effluents are released from the plant which has an average flow of 1.33 x 105 into a discharge stream gpm.
charges into the Illinois River. This stream then dis-llydrological Dispersion sult from many pathways. Radiation doses to man uents may fromre-radionuclides in liquid For this station, dispersion factors considered are shown in Table ..
1 16the pathways and aquatic 1.1-2
DRESDEN 1
, Dose Assessment The radiological impact of radionuclides released in liquid effluents has been Guide calculated using the methods and data given in Regulatory 1.109. Consumption factors used are those given in the Hermes computer code and summarized in Table 1.1-2.
Specific doses are given in Table 1.1-7 for the various points of inter-est listed in Table 1.1-6.
All are within Appendix I to 10 CFR 50 guidelines.
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1.1-3
DRESDEN 1 TABLE 1.1-1 ESTD!ATED ANNUAL SEOUS RELEASES EFFLUENTS OF GA BASED ON REOULATORY .
ASSUMPTIONS CUIDE 1 CC (Ci/yr/reac tor)
ISOTOPE REACTOR BLDG TURBINE BLDG RADWAS TE G!AND AR 41 BLDG AIR SEAL MECHANICAL 2 5E+01 0, 0 EJECTOR
- 0. 0 VAC PUMP KR 83M 0. 0 TOTAL
- 0. 0 0.0 KR 85M 0. 0 0.0 KR 85 6. 0E+ 00 0.0 2 5E+01
- 0. 0 6.8E+ul 0.0 3. 4 E+ 01 KR 87 0.0 5. 9E+01 8.5E+0L 0.0 KR 88 6.0E+00 0.0 4.7E+03 1.2E+02 6.0E+00 1. 3E+02 0.0 0.0 0.0 KR 89 2.3E+02 1.9E+02 0. 0 4.8E+03 I
0.0 0.0 2.0E+02 3.1E+01 1.9E+02
- 0. 0 2.0E+02 0.0 0.0 3.8E+03 3.7E+02 XE 131M 0.0 8.2E+02 0. 0 0.0 XE 133M 0. 0 0.0 4.2E+03 0.0 0. 0 XE 133 0. 0 0. 0 8.2E+02 XE 135M 1.3E+02 0.0 8.6E+01
- 9. 2E+ 01 2.5E+02 3.0E+00 0. 0 XE 135 1. 0E+01 1.7E+02 8.6E+01 6.8E+01 6.5E+02 0.0 8.1E+01 0.0 XE 137 6.3E+02 2. 4 E+04 1.7E+02 0.0 4. 5 E+ 01
- 2. 4 E+ 01
- 0. 0 2.3E+03 2.7E+04 XE 138 0. 0 2.2E+02 0.0
- 1. 4 E+ 01 0.0 0.0 7.7E+02 1.4E+03 0. 0 1.0E+03 3.5E+02 I 131 0.0 0.0 1.3E+03 3.4E-01 8.0E+02 0.0 I 133 1. 9E-01 0.0 1.0E+03 1.4E-00 5.0E-02 2.7E+03
- 7. 6E- 01 2.5E-03 C 14 1. 8 E-01 0. 0 0.0 1.3E-02 0. 0 3.0E-02 CR 51 0. 0
- 0. 0 0.0 6.lE-01 MN 54 6. 0E-04 2.3E+00 6.0E-03 1.3E-02 0. 0 FE 59 9.0E-05 9.5E+00 8.0E-04 6. 0E-04 3.0E-04 0.0 CO 58 5. 0E- 04 -
0.0 9.5E+00 C0 60 1.2E-03 1.5E-04 -
- 1. 4 E-02 2.0E-02 6. 0E-04 -
0.0 ZN 65 2.0E-03 4 . 5 E- 95 -
0.0 6.9E-03 SR 89 4.0E-03 9. 0E- 04 -
1.4E-03 1.8E-04 2. 0E- 04 -
0.0 SR 90 6.0E-03 1.5E-05 -
0.0 1.8E-03 ZR 95 1.0E-05 4.5E-06 -
2.3E-02
- 8. 0E-04 2.0E-05 -
- 0. 0 SB 124 1.0E-04 3.0E-06 -
0.0 4.2E-03 4 . 0E-04 5.0E-07 i CS 134 3. 0E- 04 -
0.0 6.2E-03 CS 136 8.0E-03 5.0E-07 -
3.3E-05
- 6. 0E- 04 3. 0E- 04 -
0.0 CS 137 5.0E-05 4.5E-05 -
- 0. 0 9.0E-04 BA 140 1.1E-02 4.5E-06 -
- 7. 0E-04
- 8. 0E- 04
- 6. 0E-04 -
3.0E-06 CE 141 9.0E-05 -
8.3E-03 2.0E-04 1.1E-02 -
2.0E-06 i
6.0E-04 1.0E-06 -
6.6E-04 2.6E-05 1.0E-05
{ -
1.2E-02 i
- 1.lE-05 1.2E-02 0.0 Note: 8. 3E-04 0.0 = less
\ than 1 Ci 'yr/reac tor for
\ noble gases.
\
t 1.1-4 V
DRESDEN 1 TABLE 1.1-2 CONSUMPTION FACTORS FOR MAXIMUM EXPOSED INDIVIDUAL PATHWAY CHILD TEEN ADULT UNITS s Fruits, Vegetables & 520.0 630.0 520.0 kg/yr Gtaina 1.eafy Vegetables b 11.7 18.8 27.4 kg/yr Milkb 366.0 435.0 320.0 1/yr Meat & Poultryb 30.0 50.0 80.0 kg/yr Sport Fishe - -
1.2 kg/yr Drinking Waterc - + - -
440. 1/yr Shoreline Activitiesc - -
- 15. hr/yr Boating /Swimminge - -
29/6 hr/yr Inhalationa ,b 2700. 5100. 7300. M3/y-1900. (Infant)
- a. From Regulatory Guide 1.109. Table A-2
- b. Calculated from HERMES -- A digital computer code fo; estimating
. regional radiological effects from the Nuclear Power 7adustry, 1971 HEDL-TME-71-168
- c. From HERMES as used in Commonwealth Edison's annual and semiannual reports on station radioactive waste, environmental monitoring, and occupational personnal radiation exposure i
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DRESDEN 1 i
TABLE 1.1- 4 i MAXIMUM AIR DOSE RATE LOCATION 8 (mrad /yr) y (mrad /yr)
Point of highest 8 dose (0.37 Mi SE) 0.061 0.351 Point of highest Y dose (0.33 Mi NNE) 0.045 0.533 ,
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1.1-8
DRESDEN 1 O TABLE 1.1-6 LIQUID EFFLUENT PATHWAYS AND HYDROLOGICAL DISPERSION PATHWAYS PRINCIPAL ASSUMPTION / LOCATION DILUTION FACTOR Consumption of fish Fish live in discharge canal 1:1 Shoreline activities Near vicinity of discharge canal 1:5 Swimming / Boating Near vicinity of discharge canal 1:5 Irrigation of crops None identified -
ib ,,;e:,,al n 4 S ,, ply I: @
M rtaking-water Peoria, Illinois it '
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. - - _ - _ = . . - . . - . . . - - . ~ . - - - - - - - . . ~ . ~ -
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l TABLE 1.1-7 PNDIWAYS DOSES FROM LIQUID EFFLUENTS l i ;
t BODY SKIN T11YROID BONE GI-TRACT :
j PATIIWAY (mrem /yr) (mrem /yr) (mrem /yr) (mrem /yr) (mrem /yr)
Consumption of fish 3.00E-02 -
5.52E-03 2.51E-02 9.77E-04 Shoreline activities 9.48E-05 1.llE-04 9.48E-05 9.48E-05 9.48E-05 j Swimming / Boating 5.34E-06 7.13E-06 5.34E-06 5.34E-06 5.34E-06
! i Drinking water 1.68E-04 -
5.14E-03 1.39E-04 2.27E-05 e
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STEAM JET AIR CATALYTIC fU
(~_ EJECTOR REC 0MBINER SEPARATOR fjs]
30 min, delay TURBINE GLAND SEAL SYSTEM 2 min, delay i
MECHANICAL l
VACUUM PUMP
=
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BUILDING l _____..
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7 p W I U4 T -
- i
- 2 27 SCFM 300' High lZ TEMPERATURE .:_,:r4 3.5' Diameter CHARC0AL ADSORBER 4: 3
_ Exit Orifice 200 SCFM 39,120 SCFM 7200 SCFM G
3700 SCFM
=
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! TI APERTURE
=
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Also Ay,g,j,lc On Aperture Card
'ER DRESDEN STATION Unit 1 FIGURE 1.1-1 GASE0US RADWASTE SYSTEM PROCESS FLOR DIAGRAM
,4 nR7% -Ol 30lVV*' _ _
a %
SURGE TANK REACTOR bATER
- - ---+ - - - - - - - - - - - - - -
C l SECONDARY STEAM GEN. "A" WASTE l
I
- 2000 gpd i COLLECTION TANK 1
5000 gal. i i
l 1
TURBINE BUILDING I FLOOR DRAIN TANK ~*. 5000 gpd I 5000 gal . RADWASTE I 9000 gpd COLLECTION TANK '
WASTE FILTER 150 25,000 gal . gpm REALTOR BUILDING 1000 gpd DRAINS URC FACILITY - 1000 gpd
( DECON DRAINS MISC. CHEM, +
WASTE SECONDARY STEAM 1500 gpd WASTE NEUTRALIZt'R GEN. "B" WASTE TANKS COLLECTION TANK LABORATORY DRAIN 10,100 gal. 5000 cal .
TANK + '
1000 gal.
I LAUNDRY LAUNDRt DRAIN 200 FACILITY TANK L AL'NDRY FILTERS gpm 1000 gal.
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150 "A" & "B" WASTE EASTE DEMINERALIZER HOLOUP TANKS (2) gg 25,000 gal. ea.
TI APERTURE 100% Recycle CARD w
Also AvaMahle On Aperture Card D
D' t
i "C" WASTE UNIT 2/3 Discharge 250 gpd ll2 '
H0 LOUP TANK CHEMICAL WASTE ,
- S l >l 25,000 gal . PROCESS STREAM i
,g ,
, l l
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'1250 gpd (83%) l, [ 8, l hl LAUNDRY dOLDUP Discharge 3000 gpd (100%)
l>E <
l' '
alg l >
TANK 5 (2)
'i; ;l 1000 gal. ea.
ll l l 5
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i DRESDEN STATION ,
Unit 1 ,
FIGURE 1.1-2 LIQUID RADWASTE SYSTEM ,
PROCESS FLOW DIAGRAM l 8010 010 8 7 2 - g -
l
! . I I i l i I DRESDEN 1 h 1.2 "Radioactive Source Terms used in the evaluation should be con-sistent with the parameters and methodology set forth in Draft i Regulatory Guide 1.CC. Note: For BWRs, gaseous releases from i
.the containment building and auxiliary building should be com- .;
bined to form reactor building release for pre-Bh'R/6 Mark III ;
Containment designs." (
Response
The source terms used in Item 1.1 have been generated using parameters !
i and methodology which are consistent with draf t Regulatory Guide 1.CC. .
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1.2-1
DRESDEN 1
() 1.3 "Meteorology / Hydrology information used in the calculation of doses should be consistent with Draf t Regulatory Guides 1.DD and 1.EE."
Res ponse:
Atmospheric transport and dispersion calculations were performed using data and methodology consistent with draf t Regulatory Guide 1.DD.
The aquatic dispersion of liquid effluents assumed complete mixing in the receiving body of water (the Illinois River) ior to arrival at the first public potable water supply which is miles downstream of ,
the discharge. #8
.? Y The Illinois Nitrogen Corporation, located approximately jar miles down- ,
stream, uses water from the Illinois River for both its process and I potable water requirements. Because of the water's passage over a dam prior to reaching the water intake, however, complete mixing is assured.
No aquatic dispersion was assumed for the fish consumption pathway ,
(i.e. , calculations are performed in the discharge canal environment). '
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4
- 1. 3-1
1
! DRESDEN 1 l.4 "Dose Calculations should be consistent with Draft Regulatory l l Guide 1. AA. " !
, I 1
1 Response: '
l All dose calculations were performed in a manner consistent with Regula- l tory Guide 1.109 assumptions. (Regulatory Guide 1.109 and draft Regu- l latory Guide 1.AA are essentially identical.) l t
t d
1 I i
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l 1.4-1 !
r DRESDEN 1 I t
, 1.5 "Effluent Release Data from previous reactor operation should be '
provided, if available -for use in evaluating the source term l calculations. Such data should include at least one full year of effluent release data tabulated by effluent release point, ,
month, mode of operation (e.g. , full power operation, refueling shutdown), excluding the first year of reactor operation."
P.esponse:
i Annual releases for the years 1974 and 1975 are summarized in Tables 1.5-1 and 1.5-2. These data have been abstracted from station semiannual operating reports, portions of which have been duplicated for completeness in Attachment B.
I Fully detailed release data versus mode of plant operation are not avail ' ;
able. However, the power generating history contained in Table 1.5-3 l provides some information regarding station operation. [
t
([3) l L
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1.5-1 i l
. _ _ . _ _ ._ . . _ _ . - . ._ m-. _ __ _ - . , _ . . . _ _ _ . - .. .__
i 4
I DRESDEN 1 l !
TABLE 1.5-1 l
$ RELEASES OF RADIONUCLIDES _IN LIQUID EFFLUENTS, !
DRESDEN 1, 1974 and 1975 '
I 1974 1975 j lat HALF 2nd HALF 1st HALF 2nd HALF ;
i i i Volume of Liquid Waste i I
to Discharge Canal (1) 4.2 E+06 2.57 E+06 2.5 E+06 3.1 E+06 I l Volume of Dilution f Water (1) 1.1 E+ 11 1.47 E+11 1.4 E+11 1.3 E+11 ,
I i i Isotopes Released, less '
Tritium (C1) l l Cr-51 shutdown 3.8 E-03 l Mn-54 shutdown 3.59 E-02 4.7 E-02 1.5 E-02 j Co-58 shutdown 6.03 E-03 5.1 E-02 4.2 E-02 ;
2.3 E-O' 2.0 E-01 Co-60 shutdown 7.24 E-01
- l Sr-89 shutdown 9.82 E-03 1.1 Ea 1.0 E-02 i Sr-90 shutdown 1.92 E-03 9.7 E-bs 7.4 E-02 '
i Zr-95 shutdown 6.6 E-04 i l Nb-95 shutdown 8.7 E-03 1.8 E-03 {
I-133 3.41 E-02 '9.6 E-04 l shutdown Cs-134 shutdown 6.72 E-01 3.5 E-02 1.8 E-02 i
} Cs-136 shutdown 2.4 E-04
- Cs-137 shutdown 1.37 E+00 4.5 E-02 3.3 E-02 ;
Ba-140 shutdown 2.62 E-02 8.6 E-04 i La-140 shutdown 3.02 E-02 9.9 E-04 [
l s Fe-59 shutdown 2.21 E-03 t l
I-133 shutdown 2.28 E-02 [
Ru-103 shutdown 3.6 E-04
~
I Xe-135 shutdown 6.1 E-03 L
! I I i l Tritium Released (C1) 18 8.36 E-01 2.4 E-01 2.9 E-02 l l 2 :'
1
' l t
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l
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l 1.5-2 l 4 '
DRESDEN 1 l TABLE 1.5-2
, t RELEASES OF RADIONUCLIDES TM AIRBORNE EFFLUENTS
{
DRESDEN 1. 1974 AND 197}
l 1974 1975 1 1st HALF 2nd HALF _ let HALF 2nd HALF 4
- Isotopes Released (C1) ;
Noble Cases ;
2 Kr-85m shutdown 1.61 E+03 6.9 E+03 4.8 E+03 [
Kr-87 shutdown 1.14 E+04 3.8 E+04 1.7 E+04 i 4
Kr-88 shutdown 5.66 E+03 3.1 E+04 1.5 E+04 [
Xe-133 shutdown 2.10 E+03 1.8 E+04 6.9 E+03 I Xe-135 shutdown 1.00 E+04 4.7 E+04 2.6 E+04 ;
Xe-135m shutdown 1.96 E+04 7.1 E+04 2.2 E+04 [
Xe-138 shutdown 4.74 E+04 1.5 E+05 6.6 E+04 !
l !
t !
Iodines j t
j Q I-131 < 0.016 4.11 E-01 4.8 E-01 1.2 E-01 l
~
U 1-133 4.41 E+00 1.9 E+00 4.6 E-01 !
I-135 8.66 E+00 ,2.2 E+00 5.4 E-01 [
i t Particulates ;
l Ha '4 shutdown 8.0 E-04 6.2 E-04 j Co-58 shutdown 5.5 E-03 6.2 E-03 9.5 E-03 [
Co-60 shutdowr, 4.54 E-02 4.6 E-03 3.0 E-02 i Sr-89 shutdown 7.81 E-02 1.9 E-01 3.2 E-02 !
Sr-90 shutdown 1.00 E-03 6.0 E-04 9.7 E-05 1-131 shutdown 3.29 E-02 5.7 E-03 9.8 E-04 f Cs-134 shutdown 2.2 E-03 3.5 E-04 !
Cs-137 shutdown 3.6 E-03 6.5 E-03 7.1 E-03 i Ba-140 shutdown 7.44 E-02 4.3 E-02 1.6 E-02 !
j Np-239 shutdown 3.01 E-02
?
(
I j !
!O l
f 1.5-3
DRESDEN 1 g
I TABLE 1.5-3 i POWER CENERATING HISTORY. DRESDEN 1 - 1975 5 l
1 l i
l MONTH UNIT AVAILABILITY, %- AVERAGE GROSS LOAD. MWe** l January 80.8 130 1
February 99.8 156 i March 58.5 157 i
April 64.0 111***
May 90.2 171 June 98.3 150 July 100.0 144 August 100.0 151 September 1.8 121 !
October 0 Refueling November 0 9/1-12/31 December 0 l
N "#" '" #8 # " "*
- Unit Availability Hours in Reporting Period x 100
- Unit 1 Gross Design Capability 210 MWe
- For period 3/18-4/9. Unit 1 down for piping inspection l
O l
I 1.5-4 l l l
I DRESDEN 1 1.6 "The above evaluations should be accompanied by the information requested in Enclosure 2. Exceptions from the information ,
requested will be considered on a case-by-case basis." l
Response
l l
l !
! The information requestei in Enclosure 2 to the NRC letter'is con- !
l tained in Items 2.1 through 2.9 of this report. '
1 I s
i l
l l
1 I O 1
l l I I I l
l l
i i O I
f 1.6-1 l
DRESDEN 1
() 1.7 "The staff is perparing standard Technical Specifications and will issue further guidance to licensees regarding ch2nges to Technical Specifications to implement the Appendix I objec-tives. Proposed revisions to Technical Specifications by licensees based on the limiting conditions for operation set forth in Section IV of Appendix I should be withheld pending further guidance from the staff."
Response
Proposals to modify Technical Specifications related to Appendix I will 4
be deferred until receipt of additional guidance from the NRC.
k O
O 1.7-1
r i
DRESDEN 1
() 2.1 "Provide the information requested in Appendix D of Draft Regulatory Guide 1.CC. "
l Response: '
General l
- a. The maximum design core thermal power is 700 MWt. ,
- b. The equilibrium core contains 102,804 pounds of uranium and 440 pounds of plutonium. Reload fuel is of about 2.4% enrichment. The plant is not licensed for plutonium t eload,
- c. The methods and parameters of Regulatory Guide 1.CC were utilized in estimating the source terms in the primary coolant.
- d. The estimated release of tritium in liquid ef fluents is 1 Ci/yr, and tt gaseous effluents, 16.5 Ci/yr.
Nuclear Steam Supply System 0
- a. The primary steam flow rate is 1.6 x 10 lb/hr.
- b. At full power the primary system contains 4.18 x 105pounds of l reactor coolant.
[}
Rcactor Coolant Cleanup System
- a. The average flow rate is 80 gnm.
- b. Reactor coolant cleanup is via deep bed deminetalizers.
- c. The reactor coolant demineralizers are not regenerated. Spent resins i
are sluiced to the radwaste processing system. Af ter excess liquid I is decanted, the spent resins are sent to the solid radwaste system.
i Condensate Demineralizers
- a. The average total flow through the condensate polishers is 1.6 x 106 lbs/hr.
i
- b. Condensate is polished using deep bed demineralizers. These de-mineralizers are not regenerated.
I
- c. Ultrasonic resin cleaning (URC) is utilized. Each URC operation results in about 12,000 gallons of liquid waste. ,
I t
Liquid Waste Processing Systems 3
- a. Sources, flow rates, expected activities, holdup tines, tank cap-acities, decontamination f actors, stream fractions, etc., for each principal radwaste stream are given in Table 2.1-1.
4 e i 2.1-1
DRESDEN 1 O b. Piping and instrumentation diagrams (P&ID's) are presented in Figures 2.1-1 through 2.1-6. Schematic flow diagrams were given ,
earlier in Item 1.1.
Fhin Condenser and Turbine Gland Seal Air Removal Systems
- a. Of f-gases from the main condenser air ejector are held up for 20 minutes prior to processing by the off-gas treatment system.
- b. The principal parameters associated with the system for processing of f-gas f rom the main condenser are outlined in Table 2.1-2.
The mechanical vacuum pump discharges directly to the environment without treatment.
- c. Charcoal tonnage and other operating characteristics of the of f-gas system are given in Table 2.1~2.
- d. Cryogenic distillation is not utilized.
- e. A steam flow of 16,000 lb/hr is provided to the turbine gland seal, for use as sealing steam. The so: rce of this steam is secondary steam.
() f. The design holdup time, iodine partition f actor, and other informa-tion dealing with the treatment system to reduce releases from the gland seal system are given in Table 2.1-3.
- g. P&ID's for the main condenser of f-gas treatment system and gland seal system are given in Figures 2.1-7 and 2.1-8.
Valtilation and Exhaust Systems
- a. Filters and other systems to reduce radioactivity in gaseous ef flu-ents have been presented earlier in Item 1.1 of this report.
- b. Estimated releases of iodines, noble gases, and particulates were given earlier in Item 1.1.
- c. Release points were described in It em 1.1.
- d. The reactor "sphere" is continuously ventilated.
Solid Waste Processing System In a meeting held at the NRC Region III Of fice on Tuesday, March 30, 1976 Commonwealth Edison Co. was advised by NRC representatives that this section of Draf t Regulatory Guide 1.CC has not been incorporated into Regulatory Guide 1.112, and is not required for the Appendix I evaluat ion.
{} 1 2.1-2
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I DRESDEN 1 O TABLE 2.1-2 i
MAIN CONDENSER OFF-CAS TREATTENT SYSTEM j Number of condenser shells 1 l
Expected air in-leakage (cfm) per shell 25 !
t Charcoal in delay system, tons 26 Operating tempere*.ure. 'T 40 '
Dew point temperature, 'T -40 Dynamic adsorption coef ficients Xe cm /gr 840 Kr em3/gr 40 Iodine source term for the condenser Incoming iodine to the !
condenser is assumed i to be 5% volatile and l 95% nonvolatile. None )
of the nonvolatile and !
15% of the volatile !
iodine are expected to O
se remevea xa the sais. !
A net fraction of 0.0075 :
of iodine entering the l condenser is removed !
by the SJAE. Virtually I all of this is removed by the of f-gas chat- !
coal adsorber. ;
i l
l O
2.1-4
_ . _ ...__.~...___._________________.___-_.-__._..-__-__-_..__.._.-.m___
i i
i DRESDEN 1 i
i !
j TABLE 2.1-3
!g.- CLAND SEAL CONDENSER OFF-CAS TREATMENT SYS_ TEM l Design holdup time (min) 2 l j
- Iodine partition f actor in gland seal condenser 0.01 .
l 1 -!
4 i
l Fraction of partitioned radioiodine released through i
] gland seal condenser vent 100% j I
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O 3 g,y , Unit 1 ! o l FIGURE 2.1-2 M C"" C T' RADWASTE COLLECTION TANK FILTERS AND WASTE DEMINERALIZER TANK P&lD
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3 l A DRESDEN STATION Unit 1 A . 4 , FIGURE 2.1-8 DIAGRAM 0F MODIFIED 0FF-GAS PIPING 8010 010 8 72 - ICA
DRESDEN 1 2.2 "Provide, in tabular form, the distances from the centerline of d the first nuclear unit to the following for each of the 22-1/2 degree radial sectors centered on the 16 cardinal compass directions. a) nearest milk cow (to a distance of 5 miles) b) nearest meat animal (to a distance of 5 miles) c) nearest milk goat (to a distance of 5 miles) d) nearest residence (to a distance of 5 miles) e) nearest vegetable garden greater than 500 ft2 (to a distance of 5 miles) f) nearest site boundary For radioactivity releases from stacks which qualify as ele-vated releases as defined in Draf t Regulatory Guide 1.DD, identify the locations of all milk cows, milk goats, meat animals, residences, and vegetable gardenr, in a similar manner, out to a distance of 3 miles for each radial sector."
Response
Distances from the centerline of the first nuclear unit to the loca-tions of interest for purpose of dose assessment for each of the 16 cardinal compass directions are tabulated in Table 2.2-1. Distances to the nearest site boundary are measured from the Unit 1 station c himney. Elevation of the locations of interest are tabulated in Tables 2.2-2 through 2.2-5. O
~
2.2-1
o o O I TABLE 2.2-1 i DISTANCES FROM REACTOR TO LOCATIONS OF INTEREST, TO A DISTANCE OF 5 MILES l Jh/4h . NEAREST NEAREST POINT NEAREST MILK NEAREST - NEAREST SITE BOUNDARY OF OCCUPATION NEAREST ANIMA NEAREST RESIDENCE *** CARDEN ! SECTORS (meters)* (meters)* MILK COW (miles) MILK GOAT (miles) (miles) f N 695 792 None None None 1.0 None ' I NNE 524 1158 None None None 2.0 None ! NE 488 1146 None 1.0** None 1.5 ,. -l . 5* * /
. 8 : _, ,
l ENE 488 1158 None None None 1.0 None E 536 853 None None None 0.75 None d ! w E!
'w ESE 597 841 None None None 1.0 None @ ,
I LTJ
" SE 597 878 None None None 0.75 None Z w
SSE 634 634 None i
.. Non e None 0.75 -
None S 853 853 None (l.5** None g None SSW 866 866 None None None 1.0 , None ' SW 1024 1024 None None None 3.0 > t 4. 0' ' ')
\ N~+. -
WSW 1219 1219 None None - None- 3.0 i None W 1914 1914 None ; 1.25**) None. 1. 0 None WNW 1329 1329 None None None 2.5 None
'T NW 792 792 None 1. 0** >
None 1.25 None i NNW 878 878 None None None 1.0 l None y 1 - l
- Measured from Unit 1 Station Chimney. ,/ '^
** O 'y location within 3 miles. /
*** It may be assumed that additional locations exist out to 3 miles,.( '
- t. .
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - ._- . . _ _ _ _ . . ~ - - . . _ - - . . . . - . . , - . _. -, .
DRESDEN 1
\ ')
\> TABLE 2.2-2 ELEVATION OF NEAREST MEAT ANIMAL DISTANCE ELEVATION DIRECTION (miles) .{ft MSL) N --- --- NNE --- --- NE 1.0 610 ENE --- --- E --- --- ESE --- --- SE --- --- l SSE --- --- ; S 1.5 550 O LJ SSW --- --- SW --- --- WSW --- --- W 1.25 520 1 I l WNW --- -_- NW 1.0 510 NNW --- --- 0 2.2-3
f l l DRESDEN 1 l l ( TABLE 2.2-3 ELEVATION OF NEAREST RESIDENCE DISTANCE ELEVATION DIRECTION (miles) (ft MSL) l N 1.0 600 NNE 2.0 600 NE 1.5 610 i ENE 1.0 610 , E 0.75 510 l ESE 1.0 510 l SE 0,75 510 j I SSE 0.75 510 l S 1.0 510 C:) SSW l.0 520 SE 3.0 520 WSW 3.0 500 W 1.0 520 , WNW 2.5 500 NW l.25 520 NNW 1.0 520 0 2.2-4
DRESDEN 1 l 1 () TABLE 2.2-4 ELEVATION OF NEAREST GARDEN l DISTANCE ELEVATION DIRECTION (miles) (ft MSL) i N --- --- NNE --- --- NE 1.5 610 ENE --- --- E - - - --- l ESE --- --- i SE --- --- SSE --- --- s --- ... l SSW --- --- SW 4.0 520 WSW --- --- W --- --- l WNW --- --- NW --- --- l l NNW --- --- j 1 1 2.2-5 j
DRESDEN 1 ()
- TABLE 2.2-5 ELEVATION OF NEAREST SITE BOUNDARY DISTANCE ELEVATION DIRECTION (meters) (ft MSL)
N 695 505 NNE 524 505 NE 488 505 ENE 488 505 E 536 505 ESE 597 510 SE 597 510 SSE 634 510 S 853 510 SSW 866 520 SW 1024 520 WSW 1219 520 W 1914 520 WNW 1329 510 NW 792 510 NNW 878 510 0 2.2-6
DRESDEN 1
) TABLE 2.2-6 ELEVATION OF NEAREST POINT OF OCCUPATION DISTANCE ELEVATION DIRECTION (meters) (ft MSL)
N 792 510 NNE 1158 505 NE 1146 505 ENE 1158 505 E 853 505 ESE 841 505 SE 878 505 SSE 634 510 S 853 510 \ SSW 866 520 SW 1024 520 WSW 1219 520 W 1914 520 WNW 1329 510 NW 792 510 NNW 878 510 O 2.2-7
DRESDEN 1 () 2.3 "Based on censiderations in Draft Regulatory Guide 1.DD, pro-vide estimates of relative concentration (X/Q) and deposition (D/Q) at locations specified in response to item 2 above for each release point specified in response to item 1 above."
Response
Values for relative concentration (X/Q) and deposition (D/Q) have been calculated for the locatiens listed in Item 2.2. Selected values for each are tabulated in Table 2.3-1. The calculations made use of joint trequency distribution data as discussed in Item 2.5. O d 2.3-1
DRESDEN 1 TABLE 2.3-1 O -
SUMMARY
OF ATMOSPHERIC DISPERSION FACTORS AND DEPOSITION VALUES FOR SELECTED LOCATIONS
- LOCATION X/Q (sec/m3) D/Q (1/m2 ) ,
Nearest meat animal
. (1.00 mi NE) 3.0E-08 1.2E-09 Nearest residence '
L (0. 75 mi SE) 3.0E-08 1.9E-09 Nearest vegetable garden (1.50 mi 12) 3.4E-08 8.7E-10 , Nearest site boundary * (0.30 mi NE) 2.3E-08 2.8E-09 . O d
- Calculated using the methodology of Regulatory Guide 1.111, "Methods of Est'imating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-k'ater Cooled Reactors."
.O 4
2.3-2 . i 4 ,
DRESDEN 1 (s s_,1 2.4 "Provide a detailed description of the meteorological data, models and parameters used to determine the X/Q and D/Q values. Include information concerning the validity cr.d accuracy of the models and assumptions for your site and the representativeness of the meteorological data used."
Response
The meteorological data utilized in the x/Q and D/Q calculations are as discussed in Item 2.5. The models and parameters utilized are those described in Regulatory Guide 1.111 (essentially identical to draf t Regulatory Guide 1.DD), with the exceptions noted in Item 1.1. A discussion of the representativeness of the meteorological data is contained 17 Item 2.5. l l 2.4-1
DRESDEN 1 2.5 "If an onsite program commensurate with the recommendations and
-({} intent of Regulatory Guide 1.23 exists:
a) Provide representative annual and monthly, if available, joint frequency distribution of wind speed and direction by atmospheric stability class covering at least the most recent one year period of record, preferably two or more years of record. Wind speed and direction should be mea-a sured at levels applicable to release point elevations and stability should be determined from the vertical temperature gradient between measurement levels that represent conditions into which the effluent is released. b) Describe the representativeness of the available data with respect to expected loag-term conditions at the site." Response : i
- a. Joint f requency distributions of wind speed and directions, by atmospheric stability class, covering the years 1974,1975, and combin ed 1974-1975, are contained in Attachment C. Wind speed and direction are measured at the 35-foot, 150-foot, and 300-foot levels of the Dresden Station meteorological tower. Atmospheric stability ,
is determined based on the temperature dif ference between the 35-foot and 150-foot, and 35-foot and 300-foot levels of the tower. { a The data contained in Attachment C provide annual joint frequency for the years 1974, 1975 and for the entire period 1974-75 using wind statistics at the 35-foot, 150-f oo t , and 300-foot tower levels. t
- b. The 2-year (January 1974 - December 1975) onsite meteorological !
records are used for evaluating the annual joint frequency distri- ; bution of wind speed and direction by atmospheric stability classes. The frequency distributions are given in Attachment C. Results of comparisons of wind speed, wind direction, and stability between i that at Dresden Station and that at Argonne National Laboratory 1
! (ANL) are shown in Tables 2.5-1, 2.5-2, and 2.5-3.
Examination of wind speed distributions in Table 2.5-1 shows that wind speeds recorded at Dresden for 1974 and 1975 are quite similar overall. Comparison of these data to the 19-foot level of ANL shows a similar distribution of windsieeds except for a slightly higher frequency of occurrence of calms at ANL for the period 1950-64. The 150-foot level of ANL data exhibits a relatively low frequency of calms and a relatively greater frequency of occurrence of the higher wind speed classes. Wind direction distributions (Table 2.5-2) for the 1974 and 1975 Dresden meteorological data and those for the 19-foot and 150-foot tower levels of ANL are generally well correlated. While the pre-vailing wind direction at Dresden for 1974-75 is south, the pre-i i () valling direction recorded at ANL is west at the 19-foot level and south at the 150-foot icvel. The uniform distribution of wind i 2. 5-1
DRESDEN 1 directions at Dresden and ANL indicated favorable dispersive char-acteristics for the region with little likelihood of effluent chan-neling along any particular sector. Stability class distributions for Dresden and ANL data show general overall similarities, with the exception of stability class A. A significant decrease of stability class A frequency has been recorded for 1975 Dresden data; i.e., 7.35% versus 15.16% for 1974, and 12.90% for ANL (1965-70) . The notably low frequency of stability A for 19). Dresden data may be due to particular persistent synoptic and local meteorological conditions which would lead to stable temperature stratifications. In summary, it is felt that meteorol.ogical data recorded at Dresden for 1974 and 1975 is representative of expected long-term conditions at and near the site with respect to atmospheric transport and dif fusion of gaseous releases. Table 2.5-1 shows wind speed distribution (in percent) for Dresden and Argonne National Laboratory (ANL). The ANL data represent averages of a 15-year climatology (1950-1964) . Table 2.5-2 shows wind direction distributions in percent for Dresden (1974 and 1975) and for ANI (15-year record) . () Table 2.5-3 compares 1974 and 1975 Dresden site stability data to a 5-year average of ANL stability data. O 2.5-2
DRESDEN 1 O TABLE 2.5-1 WIND SPEED DISTRIBUTIONS DAESDEN SITE 1974 1975 ANL SPEED 35-f oo t 35- f oo t 19-foot 150 -foo t C 0,00 0.00 3.086 0.769 1-3 7.40 5.23 14.716 3.285 4-7 32.73 40.66 36.131 14.191 8-12 34.25 31.28 31.151 38.324 13-18 19.68 15.~53 12.423 30.146 19-24 4.91 5.74 1.918 9.639 25-31' O.80 1.37 0.240 2.483 32-38 0.20 0.20 0.003 0.444 39-46 0.00 0.00 0.000 O.062 46 0.00 0.00 0.000 0.002 O l ( 2.5-3
DRESDEN 1 ( TABLE 2.5-2 WIND DIRECTION DISTRIBUTIONS DRESDEN SITE-1974 1975 ANL DIRECTION
- 35-foot 35-foo t 19-foo t 150,foo t N 3.62 4.49 6.600 6.488 NNE 3.14 4.19 5.996 5.266 NE 3.77 4.47 4.399 4.362 ENE 3.97 4.59 4.795 4.680 E 5.91 7.27 5.519 6.128 ESE 6.43 6.39 3.178 3.362 SE 5.57 5.48 3.232 3.357 SSE 7.42 7.35 4.026 4.448 S 9.40 9.99 8.154 9.876 SSW 10.02 7.88 9.382 9.717 SW 7.92 7.46 7.667 7.635 WSW 5.74 5.12 6.899 7.072 W 7.74 7.56 10.571 9.779 WNW 7.45 ----
6.189 4.878 NW 7.30 5.96 4.725 4.946 NNW 4.57 5.91 5.329 --- O
*22.5' sectors for Dresden; 10' sectors for ANL, i.e. , N = 350-360-10; NNE = 020-030; NE = 040-0? , etc.
O 2.5-4
~
DRESDEN 1 O TABLE 2.5-3 STABILITY CLASS DISTRIBUTIONS DRESDEN SITE STABILITY 1974 1975 ANL* CLASS AT = 150-35 AT = 150-35 AT = 144-34 1 (A) 15.16 7.35 12.90 2 (B) 2.93 2.22 4.73 3 (C) 2.79 2.52 1.18 4 (D) 19.59 23.85 30.91 5 (E) 41.25 36.88 34.31 6 (F) 14.49 20.74 10.60 7 (G) 3.76 6.45 5.,37 o U 1 l l
*ANL Record 1/1/65 - 3/31/70 0
2.5-5 l .
DRESDEN 1 2.6 "If recent onsite meteorological data are not .available, or if O the meteorological measurements program does not meet the recom-mendations and intent of Regulatory Guide 1.23: a) Provide the best available meteorological data in the format described in item 5.a above. b) Describe the representativeness of the available data with respect to onsite and near site atmospheric transport and diffusion conditions, and with respect to expected long j term conditions at and near the site. c) Provide a description of the meteorological measurements used for collection of the data presenced. This descrip- i tion should include the location of the sensors wi ht respect , to the power . plant (s) and other prominent topographic features (including buildings) and accuracy of the instru-mentation. 4 d) Provid a commitment to establish a program to meet the - recommendations and intent of Regulatory Guide 1.23, or 1 provide sufficient justification to allow the present : j program to remain unchanged." a 1 Response: i
) Not applicable (see Item 2.5). -
y . i \ l 4 l ! I k i 1 i l 4 4 l 4 4 ' \ I
- 2.6-1 l
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DRESDEN 1 2.7 "Describe airflow trajectory regimes of importance in transport-(s' ing ef fluents to the locations foe which dose calculations are made." Response: i A description of the airflow regime surrounding the Dresden Station site and its effects on plant effluent dispersion is presented. To assist in the determination of the effects of topography on the airflow regimes surrounding the plant, referenca is made to the topographic cross sections for each of the 16 compass-point directions radiating (out of 10 miles distance) from the site, provided in Item 2.8. The source of the Illinois River is located at the confluence of the Des Plaines River and the Kankakee River. The Dresden Station is situated on a parcel of land bordered by the south shoreline of the lilinois , River and the west shoreline of the Kankakee River. The Kankakee ' plain where the plant is situated is a level to gently undulating plain that occupies the position of a basin between higher moraine country to the east and west. The plant is located at an elevation of approximately 517 feet; the elevation in the immediate vicinity of the site varies from 509 to 526 feet above sea level. The primary topographic features in the area are the Kankakee Bluf fs, elevation 591 to 624 feet, located just northeast of the station on the north (opposite) bank of the Illinois River. () The behavior of an effluent approaching a bluff depends on the stability of the air at the time and the steepness of the bluf f. For example, when the air is unstable, effluent moves up and over the bluff, but when the air is very stable, the bluff acts as a barrier to deflect the ef fluen t. The 2-year (January 1974 - December 1975) onsite meteorological measurements indicate the prevailing winds occur from the S and SSW se c to rs , under the stable atmospheric conditions (including neutral case, see Table 2.7-1) at a f requency occurrence of 12.55%. In view of the very gentle slope of the bluff, and the less frequent occurrence of prevailing winds in this sector, the topographic influences on transporting effluents can be neglected. Analytical determination of the eddy flows and other small scale cir-culations embedded in the mainstream when in contact with topographic obstacles requires a sophisticated mesoscale modaling approach. From the existing state of knowledge, most estimates of atmospheric dilution factors will be determined with only a rudimentary consideration given , to the ef fects of topography. The relative percentage f requencies of occurrence f or the seven Pasquill stability classes based on 2 years (January 1974 - December 1975) of ; onsite meteorological measurements at the 35-foot level with respect ' i to all directions are listed in Item 2.5 and summarized below: A B C D E F G O 10.6 2.5 2.6 21.9 38.7 18.1 5.3 4 2.7-1 l
DRESDEN 1 O The unstable (A, B, and C) and neutral (D and E) classes experience a greater f requency of occurrence, 76.3%, than the frequency occurrence of both F and G classes, 23.4%. Accordingly, good mixing conditions in the lower layers are prevalent throughout the year. Airflow trajectory regimes surrounding the Dresden Station are dependent on the prevailing meteorological conditions and the mechanical turbulence generated by the main airflow in the vicinity of terrain features. As previously indicated, good annual mixing conditions and favorable wind speed conditions exist over the plant site environs. Therefore, no significant eff ect of topography on atmospheric dispersion parameters (i.e. , mixing heights, transport wind speed) and/or drainage flow are anticipated due to the modest relief of the area. l O . l O , l 2.7-2 l j
e e
~
. O i, TABLE 2. 7-1 JOINT FREQtTNCIES (VINDSPEED-WIND DIRECTION-STABILITY) AT DRESDEN SITE (35-f t LEVEL - DATA TROM 1/1/74 - 12/31/75)
(FREQt'ENCY OF OCCL'RRENCE IN PERCUT OF TOTAL OBSERVATIONS) STABis.17Y CLASS DIRECliON CLASS TOTAL N NNE NE ENE E ESE SE SSE S SSW SW WSW W WW NW NNW l A .74 .68 .71 .49 .57 .59 .45 33 .53 .78 .63 .44 .93 .10 .04 .57 10.58 B .21 .06 .10 .09 .18 .10 .15 . D6 .14 .19 .13 .14 .25 .21 .28 .21 2.50 ! C .32 .17 .11 .10 .18 .07 .15 .05 .19 .15 .14 .15 .21 .19 .2i .18 2.57 l l u *' y D 1.05 1.02 1.22 1.31 1.79 1.06. 1.23 1.45 1.81 1.31 1.18 2.21 1.32 1.08 1.54 1.38 21.98 o E 1.25 1.36 1.54 1.78 2.49 2.18 2.09 3.13 4.54 3.28 3.06 2.12 2.73 2.76 2.45 1.98 38.74 E w F .44 35 42 .50 1.36 1.86 1.19 2.05 .2.02 2.21 1.59 1.03 . 66 .69 .71 .81 18.09 i G .10 .10 .07 .02 .11 . 56 .25 .28 .52 .82 .93 .41 .41 .26 .29 l .19 5.32 1 TOTAL 4.11 3.74 4.17' 4.31 6.68 6.42 5.51 7.35 9.75 8.74 7.66 5.37 7.60 6.53 6.52 5.32 99.78 1 1 l
-l
DRESDEN 1 2.8 "Provide a map showing the detailed topographical features () I ] (as modified by the plant) on a large scale, within a 10-mile radius of the plant and a plot of the maximum topograhic elevation versus distance from the the center of the plant in each of the sixteen 22-1/2 degree cardinal compass point sectors (centered on true north), radiating from the center i of the plant, to a distance of 10 miles."
Response
A map showing the detailed topographic features around the plant to a distance of 10 miles is shown in Figure 2.8-1. A plot of the maximum topographic elevation versus distance in each of the 16 cardinal compass points is shown in Figures 2.8-2 and 2.8-3. 1 O . 3 I i i f I r 6 i
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ll
DRESDEN 1 2.9 "Provide the dates and times of radioactivity releases from O 1==er itt #e eerce 6x erce 1ec tie 6 ea e ct" 1 ei #t operation and, if available, appropriate hourly meteorological data (i.e. wind direction and speed, and atmospheric stability) during each period of release.
Response
Not applicable. O . I l O l l i 2.9-1
. _ _ _ _ _ . . _ .....=______ ____ _ . _ . . _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ __
DRESDEN 1 l
, ATTACHMENT A l
1 i 1 I l 1 I I LETTER FROM MR. D. L. ZIEMANN OF THE 1 NUCLEAR REGULATORY COMMISSION O to na a t sotoca or rue COMMONWEALTH EDISON COMPANY j
} DATED FEBRUARY 19, 1976 l
- l i
i A l i f IO, i j .)
- - -_. ~ _ . . - - . - -. . - .
I 638tCt. UNITED STMES ne d NUCLEAR REGULATORY COMMISSION f j, , ,,.ij WASHINoTOrd, O. C. 00555 h/ February 19, 1976
- Docket Nos. 50-10/237/249 .
1 I I Co=monwealth Edison Co=pany ; l ATTH: Mr. R. L. Bolger , Assistant Vice President , Post Office Box 767 i Chicago, Illinois 60690 Gentlemen: , J RE: ' DRESDEN NUCLEAR POWER STATION, UNITS 1/2/3 LICENSE NOS.: DPR-2/lc/25. > OUAD-CITIES _1271TS 1/2. LASAILLLNITS 1/2 m AND ZIO:4 OWITs u1,. , On May 5, 1975, the Co sission puolisned Appencix 1 to 10 cra Part 50 , which sets forth numerical guides for design objectives and limiting t conditions for operation to neet the criterion "as 1:w as practicable" '
- regarding releases of rawicactive naterials in effluents from light-l .. water-cooled nuclear reactors. Section V.B o'T Appendix I requires the holders of permits. or licenses authorizing tne operation of light-i water-cooled reactors, for wnich application was filed prior to Janu~ary 2,.
1971, to file witn the Ccamission by June 4,1976: , () 1. Such information as is necessary to evaluate,the =eans employed for keeping le'vels of radioactivity in effluents to unrestri:ted a,reas as low as practicable ,. in:luding all suon information as ! is required by paragra;ns 50 34a(b) and(c) no: already contained in his applicatica; and .
- 2. Plans and proposed Technical Specifications developed for the r purpose of keeping relea:es of radioactive materials in unrestricted areas during nor:al reactor operaticns, including expected operational occurrences, as low as practicable.
In a letter. to you from D. Muller dated July 3,1975, we indicated ) l that the ' staff was in the process of developing guidance for licen:ees ; required to file information with the Cennission under the provisions , of Secticn V.3 of Appendix I. This guidance is set forth in Enclosure 1. l i Enclosure 1 =akes reference to proposed Regulatory Guides 1. AA, thru 1.FF. These cuides have been puolisned in draft form and are available in the Cor.nission's public document roca. Ccpies of these guides are bein; j forwarded to you uncer separate cover. We are preparing additier.al guitar. e
; regarding the'fornulation of Technical Specificati:ns to implement A;;en:it:
) I which will be forwarded to you in the near future. It is ree ::entes . j that proposals to :odify Tecnni:al Specifications related to A;pendix I be defarred pending the completion of this guidance in order to oo: sin 0* a consistent for:at for radiological effluent release Technical Specift:sti:ns. S
, A-1
-.- ~ - - , - , . . , , - -.mr.- , - -
.__y. . ., - -.
. Coaunonwealth Edison Company ,
February 19, 1976 O - Enclosure 2 provides a list of information we will need to evaluate , your facility. ' The staff is in the process of determining whether plants for which application was filed prior to January.2, 1971, can be treated in a manner similar to ,the treatment given to later plants in the Commission's September 4, 1975, Amendment to Appendix I. On this basis , the information - called for by Enclosures 1 and 2 would be sufficient to determine compliance with the criteria set forth in Section II, paragraphs A, 3
'and C of Appendix I and the design objectives set forth in the Concluding State:ent of Position of the Regulatory Staff in, Docket RM-50-2, unich is reproduced as an Annex to Appendix I-as amended
. September Li, 1975 If further information is required to satisfy a plant specific assessment under Section II.D of Appendix I, we will' so inform you at a later tice'.
Within 30. days of the receipt of this letter, you should inform us of the seasures you intend to adopt or propese to meet the requirements of paragraph 50 34a. We.suggest that a meeting between your staff and the NRC staff be arranged shortly thereafter to discuss the submittal of data,and cathcos of evaluation. Sincerely. 4 1 t [O M /s 4MY.m i
- Dennis ~L. Zie:an Chief '
Operating Reactora Branch d2 Division of Operating Reactors
Enclosures:
- l. Guidance to Holders of Permits to Construct or Licenses to Operate Light-Water-Cooled Reactors for which Application was Filed Prior to 1/2/71 to Meet the Requirements of Appendix I to 10 CFR Part 50
- 2. Additional Information fleeded fren Holders *
, of Permits or Licenses to Construct or Operate Light-Water-Cooled Reacters for Which Application was Filed Prior to 1/2/71 cc: with enclosures '
See next page O A-2
ENC 1.0S t*RI'1 Cuidance to Holders of Per=its to construct or Licenses to Operate Light *4ater-Cooled Reactors for "hich Applica:Len p was Filed Prior to January 2, 1971 to Meet the Require =ents d , of Appendix I to 10 C.*'R Part 50 M Licensees should provide an evaluation shoving their facility's capability to ccer the require =ents set forth in Section II of ' Appendix'I to 10 CFR Part 50
,2, Radioactive _ Source Ter=s used in the evaluation should be consistent vith the para =eters and =cchodology set forth in Draft Regulatory
~
l , }Cuides 1.BB or 1.CC (as appropriate). Note: For BWRs gaseous releases frc= [the c.ontain=ent building and auxiliary building should be ce=bined to form reactor building release for pre-3'JR/6 Mark I!I Contain=ent de, signs. O ~ p, }!eteorolotv/F. drolegv infor=ation used in the calculation of 9 doses should be consistent with Draft Regulatory Cuides 1.0D and 1.EE. j, Dose Calculations should be consistent with Draft Regulatory Guide 1.AA.
- 5. Effluent Release Data fr = previ us reactor operation should be provided, if available, for use in evaluating the source ter=
calculations. Such data should include at least one full year of affluent release data tabulated by effluent release point, =occh,
^
- r. ode of operation (e.g., full pcVer operation, refueling shutdcyn),
_excludint the first year of reactor operatien. O . e A-3 .
._ . - _ _ ~ - _ .
.. ~. ._.. . _ . . - -. . . .
~
2
- 6. The above evaluations should be acco=pania.d by the infor=ation O requested in E= closure 2 Exceptions from th's infor=stion requested will be considered on a case-by-case basis. ,
/ .
i .
- 7. The staff is preparing str.ndard Technical Specifications and will -
. issue further guidance to licensees regarding changes to Technica*. j Specifications to 1 ple ent the Appendix I objectives. Proposed l !
revisions to Technical Specifications by licensces based on the finiting conditicns for operation set forth in Section IV of - Appendix I should' be withheld pending further guidance from the staff. 1 1 1 I 4
.O -
l i , i l i l I J 5 i1 O 1 e 3 A.4
- DCDSU:E 2 e Mtienal Irfc=atien !'eeded frem Holders of. !
Permits er Licenses to Cons = ct er Operate i Q , Light ' dater-Coolei Reac:crs for 'Aich Applicatien was Filed Pricr to Jaw / 2,1971 t . . ,
- 1. Provide the irfomation requested in Appendix D of Draft Regulatory r
. Guide 1.E3 cr 1.CC, as appropriate.
- 2. Provide, in tabular fc=, the distances frem the centerline of the first !
i ruclear unit to the followir.g for each of the 22-1/2 degee radial se:ters centered en the 16 ca Minal ccrpass directions. a) -nearest tilk cow (to a distance of 5 ""es) - b) nearest meat aninal (to a distance of 5, miles) c) nearestmilkgeat'(toadistanceof5b.iles) ' i i d) nearest residence (to a distance of 5 miles) - 3 j Q e) nearest vegetable sam en peater than SCO ft2 (to a distance cf I 5 miles) . .
, f) nearest site beundar/ '
I , i a j For radlea:t:.vity releases frem stacks which qualify as elevated releases ; i 1 as defined in Draft Regulatcry Guide 1.ED, identify the locatiens of all I milk cows, milk seats, meat ani als, residences, and vegetable gardens, in a similar manner, cut to a distance of 3 miles for each radial se:ter. i
- 1 3 Based en consideratiens in Draft Regulater/ Guide 1.DD, provide est'i ates i -
1
, ' of relative concentratien (X/Q) and deposit 1cn (D/Q) at locatiens speci-i fled in respense to item 2 above for each release point 7e:ified in respense to item 1 above.
1 . i O 4 4 d A-5
-- .,. --n-- ,. - --_~
.- 2 --
3 4. Provide a detailed descriptien of the metecro"legical data, codels and - (G. parameters used to detemine the X/Q ard D/Q values. Include infe:-atien conceming the validity and accuracy of the rodels ard ass =ptiens for ycur. site ard the representativeness of the metecrolegical data used. f 5 If an ensite pregam cemensrate with the re:emeniatiens ar.d intent of - Regalatory Guide 1.23 exists: , a) Provide representativ'e a=ual and centhly,. if available, jcint frequen:y distributiens of wird speed ar.d directicn by atrcspheric stability class coverir; at least the rest recent ene year peri:d of reccrd, preferably two er rare yesrs of recced. Wind speel ard directicn should be measured ad levels applicable to release peint q elevatiens r.d stability should be dete=ined .5= the vertical O tecperatre radient between measurer.ent levels that represer.: cen-ditiens into which the effluent is released. b) Describe the represer.tativeness of the availab'le data with respt: 0 to expected ler6-te:n conditiens at the site,
- 6. if recent ensite ratecrolesical data are rct available, er if the meteorolegical measure ents prepsm dces not meet the recere.I.dati:ns ard intent of Reg 21atory Gaide 1.23: -
a) Provide the best available metecrolegical data in the fo: rat 1 described in item 5.a above. Oa
\
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1 ~ 1 r
~
b) Describe the representativeness of the a'/ailable data with respect i O . to onsite end near site atr.ospher1= trem pore ena e1rfas1 n ! conditiens, and with respect to expected 1cng tenn conditiens at and
~
- W.ar the site.. . .
t c) Provif.e a descriptien of the retecrological reasurements use:1 for 2 collectica of the data presen:cd. This descriptien sh:uld include
. the locatien of the sensors with respect to the pcwer plant (s)
- and other pror.inent tcpegaphic featu es (includi".g buildings) a-d accuracy of the inst:. $ntatien. .
d) Provide a ec.r.itment to establish a pregan to reet the recc. .er.1?.ticr.s
- ' ard intent of Regalatery Guide 1.23, er provide sufficient justifi-catic'n to a"ow the present pregan to rerain uncl2.njed.
O 7 oes rite aenow traae:te., reg 1=es of wer:ance in transporti .g i effluents to the locatiens fer which dose calculatiens are m de. i -
- 8. Provide a mp showing the detailed topographical features (as trxiified i
, by the plant, en a large scale, within a 10-c.ile radius of the plant ani !
.a plot of the n$ci= tcperaphic elevation versus distance from the center of the plant in each of the sixteen 22-1/2 degree cardinal ecbpass p: int
' sectors (centered en trae north), radiatir6 frc:a the center of the plant, 2
l to a distance of 10 miles. i 1 1 1 l l I 1, O i , t
) ,
i ! A-7 ,
4 7, 9. Provide the dates and tir.cs of raf.icactivity releases from inte .itte.t V sources by source 10:atien based en actual plant epc.~1tien e.d,1* available, appropriate heurly meteoroles;ical data (i.e., vind di e:ti:n an1 speed, ar.d at;-Us;heric stability) durir.i; each pericd of releue. l l
)
l l o
~A l
I l l l l l d 1 A-8 .
l ' i j DRESDEN 1 I I-I i ATTACHMENT B i I L 5 i i i I 1 i 1 k i 1 e i ABSTRACTS FROM SEMIANNUAL REPORTS i O * [ l l I l 9 d 4
~
TABLE -1 REPORT OF RADIOACTIVE EFFLUENTS (From Dresden Semiannual Report, August 1974) Docket No. 50-10 FACILITY: DRESDEN - Unit 1 YEAR: 1974-Six Month 1.1 Gaseous Effluents Units Jan. Feb. Mar. Apr. _ May Jun. Total
- 1. Gross Radioactivity Releases ,
a) Total Release Ci Shutdown Shutdown Shutdown Shutdown Shutdown Shutdown NA b) Maximum Release Rate mci /sec c) Isotopes Released Ci Xc-133 Xe-135 , Xc-138 Kr- 85m l w Fr- 87 fO Kr- 83 Shutdown Shutdown Shutdown Shutdown 1 d) Percent of Chimney Limit % Shutdown Shutdown NA l
- 2. lodine Releases l .
a) Isotopes Released Ci I-131 0.002 0.002 0.003 0.003 0.003 0.003 <.016 I-133 I-135 b) Percent of Chimney Limit % <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 l l TAM F 1.!-; (Co.a t 'd)
O O O l
=
l 1 TABLE 1.1-1 (Cont'd) I . REPORT OF RADIOACTIVE EFFLUENTS Docket No. 50-10 FACILITY: DRESDEN - Unit 1 YEAR: 1974 Six Month 1.1 Caseous Effluents Units Jan. Feb. Mar. Apr. May Jun. Total
- 3. Particulate. Releases a) Gross Beta-Cama Ci 0.009 0.003 0.003 0.004 0.031 0.014 0.064 b) Gross Alpha Ci Not Required c) Isotopes Released Ci ? ot Required Cr- 51 Mn- 54 Co- 58 Co- 60 Sr- 89 as Sr- 90 0 Mo- 99 I-131 Cs-134 Cs-136 Cs-137 Ba-140 Np-239 d) % of Chimney Limit % 0.2 <0.1 <0.1 <0.1 0.5 <0.2 NA 4 Sum of Iodines & Particulates a) % of Chimney Limit % 0.4 <0.1 <0.1 0.1 0.5 0.3 NA
- 5. Tritium Release Curies Not Required NA - Not Applitabic
-s --m
O O O TABLE 1.2-1 REPORT OF RADIOACTIVE EFFLUENTS (From Dresden Semiannual Report, August 1974) Docket No. 50-10 FACILITY: DRESDEN - Unit 1 YEAR: 1974 Six Month 1.2 Liquid Effluents Units Jan. Feb. Mar. Apr. May Jun. Total
~
- 1. Gross Radioactivity a) Total Release Curies 0.119 1.232 0.870 0.687 0.508 0.487 3.90 l b) Average Concentration Released DCi/ml 2.7 E -08 6.3 E -08 3.4 E -08 2.6 E -08 1.9 E -08 1.9 E - 08 ,
c) Maximum Concentration Released UCi/mi 6.1 E -08 1. 7 E -0 7 5.2 E -08 6.2 E -08 7.8 E -08 8.2 E -08 c) I of Tech Spec Limit % 27.4 44.0 34.4 26.3 18.8 10.6
- 2. Tritium 0 a) Total Release Curies 0.05 9.30 6.16 2.40 0.18 0.14 18 b) Average Concentration Released pCi/ml 3.8 E -08 4.8 E -07 2.4 E -07 9.2 E -08 6.5 E -09 5.2 E -09
- 3. Dissolved Noble Cases **
a) Total Release Curies ND ND ND ND ND ND b) Average Concentration Released pCi/ml ND ND ND ND ND No t
- 4. Gross Alpha Radioactivity a) Total Release Curies 0 7.0 E -02 1.7.E 7.2 E -05 3.6 E -04 1.1 E -04 0.07 b) Average Concentration
- Released pCi/ml O '1.4 E -08 6.7 E -16 2.7 E -15 1.3 E -11 1.5 E -11 NR - Not Required ND - Not Detectable
. . - _ - - . _ . , , , . _ _ , , . ,.- ,n-.,
O o o I i TABLE 1.2-1 (Cont'd) i REPORT OF RADIOACTIVE EFFLUENTS l Docket No. 50-10 l FACILITY: DRESDEN - Unit 1 YEAR: 1974 Six Month l.2 Liquid Effluents Units Jan. Feb. Mar. Apr. May Jun. Total ! 5. Volume of Liquid Waste ! to Discharge Canal Liters 1.1 E +04 1.6 E +06 1.2 E +06 7.2 E +05 4.5 E +05 3.1 E +05 4. 2 E +06
- 6. Volume of Dilution Water Liters 4.4 E +05 5.2 E +09,,2.5 E +10 2.6 E +10 2.7 E +10 2.6 E +10 1.1 E +07
- 7. Isotopes Released Curies Cs-134
! Cs-137 l Ba-La-140 1-131 w T-132 E I-133
- Co- 58 Co- 60 I Cr- 51 NOT REQUIRED l Mn- $4 l
Ma- 56 Zn- 65 Sr- 89 Sr- 90 I Cu- 64 l Na- 24 W-187 l Tc- 99m Mo- 99 As- 76 Np-239 ZrNb-95 Fe- 59 Ce-141 Cc-144 l Sh-124 1
______.__.__________m t l REPORT OF RADIOACTIVE EFFLUENTS l (From Dresden Semiannual Report Errata, March 1975) L ..-. ..,J Dreefee % clear Fower Station - t'ait 1 0,g t 3 p:, , 30-17 . _YTM s 1974 t"u175 Jt'LY Air.J5T , TEFTTELA (CO3CR l
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~ O . O- O ; 1 , TABLE 1.1-1 4 REPORT OF RADIOACTIVE EFFLUENIS (From Dresden Semiannual Report, August 1975) Docket No. 50-10 EACILITY: DRESDEN NUCLEAR POWER STATION - Unit 1 YEAR: 1975 Six Month Caseous Effluents Units Jan. Feb. Mar. Apr. May June Total 1 j 1. Cross Radioactivity Releases a) Total Release Curies 3.3 E+04 6.2 E+04 5.9 E+04 4.1 E+04 9.9 t+04 6.6 E+04 3.'6 E+05 +
'b) Maximum Release Rate pCi/sec 3.5 E+04 4.6 E+0/ 4.1 E+04 9.2 Et04 6.2 E+04 4.4 E+04 9.2 E+04 c) Isotopec Released Curies Kr- 85m 7.0 E+02 1.2 E+03 1.3 EiO3 .9 E+03 1.6 E+03 1.2 E+03 6.9 E+03 Kr- 87 8.1 E+03 6.8 E+03 4.6 E+03 7.6 E+03 3.0 E+') , 7.4 E+03 3.8 E+04 Kr- 88 2.1 E+o3 4.4 E+03 6.8 E+03 3.4 E+03 8.2 E+03 6.3 E+03 3.1 E+04 Xe-133 1.4 E+03 2.6 E+03 3.6 E+03 1.4 E+03 5.1 E+03 3.6 E+03 1.8 E+04 i Xe-135 4.2 E+03 8.4 E+03 9.2 E+03 5.4 E+03 1.1 E+04' 8.6 E+03 4.7 E+04 Xe-135m 9.0 E+03 1.1 E+04 9.9 E+03 7.2 E+03 2.1 E+04 1.2 E+04 7.1 E+04 Xe-138 1.3 E+04 2.6 E+04 2.1 E+04 1.8 E+04 4.4 E+04 2.6 E+04 1.5 E+05-
? d) % of Chimney Limit % 2.2 4.57 3.93 2.80 6.60 4.54 tut
- c) Average Release Rate l pCi/sec 1.2 E+04 2.56E+04 2.20E+04 1.6 E+04 3.7 E+04- 2.5 E+04 2.3 E+04
- 2. Iodine Releases a) Isotopes Released Curies
- I-131 1.7 E-01 6.90E-02 1.39E-01 9.0 E-03 4.9 E-02 4.8 E-02 4.8 E-01 1-133 6.9 E-01 3.08E-01 5.04E-01 3.6 E-02 2.2 E-02 1.7 E-Ol' 1.9 E+00 I-135 7.3 E-01 3.98E-01 6.80E-01 6.80E-01 2.0 E-02' 1.9 E-01 .2.2 E+00 b) % of chimney Limit % 2.6 1.20 2.17 0.12 0.75 0.79 NA
- c) Average Release Rate - pCi/sec 6.3 E-02 2.9 E-02 5.2 E-02 3.0 E-03 7.0 E-03 1.9 E-02 #
3.1 E-02 d
~
ND = Not Determined NA = Not Applicable - , i~ l P 0
- - - - - - - . - , - - _-.--<,m-- - ,- , r- .-_ ,.,. ,or , -.
! O O O TAl1LE 1.1-1 (, Con t ' el) REPORT OF RADIOACTIVE EFFLUI:NTS Docket No. 50-10 FACILITY: DRESDEN NUCLEAR POWER STATION - Unit 1 YF.AR: 1975 Six Month Gaseous Effluents (Cont'd) Units .lan. Feb. Mar. Apr. May June Total
- 3. Particulate Relt.ses a) Gross Radioactivity (b-Y) Curies 5.0 E-02 3.5 E-02 5.4 E-02 5.9 E-02 2.0 E-02 4.5 E-02 2.6 E-01 b) Gross Alpha Radioactivity Curies ND ND ND ND ND ND ND c) Isoccpes Rel_ased Mn- 54 3.0 E-04 1.0 E-04 1.0 E-04 1.0 E-04 1.0 E-04 1.0 E-04 8.0 E-04 Co- 58 1.5 E-03 4.0 E-04 3.7 E-03 3.0 E-04 -
3.0 E-04 6.2 E-03 Co- 60 1.0 E-03 3.0 E-04 2.0 E-03 7.0 E-04 - 6.0 E-04 4.6 E-03 Sr- 89 3.5 E-02 2.4 E-02 2.9 E-02 4.8 E-02 1.7 E-02 3.9 E-02 1.9 E-01 S r- 90 1.0 E-04 i.0 E-04 1.0 E-04 1.0 E-04 1.0 E-04 1.0 E-04 6.0 E-04 I -131 1.1 E-03 5.0 E-04 2.5 E-03 9.0 E-04 - 7.0 E-04 5.7 E-03 Cs-134 6.0 E-04 1.0 E-04 9.0 E-04 3.0 E-04 1.0 E-04 2.0 E-04 2.2 E-03 y Cs-137 1.6 E-03 8.0 E-04 1.9 E-03 1.1 E-03 3.0 E-04 8.0 E-04 6.5 E-03 g Ba-140 9.2 E-03 9.1 E-03 1.4 E-02 4.6 E-03 2.2 E-03 3.7 E-03 4.3 E-02 d) % of Chimney Limit % 0.75 0.60 0.83 0.92 0.32 0.71 NA c) Average Release p Ci/sec 1.8 E-02 1.5'E-02 2.0 E-02 2.0 E-02 2.0 E-02 1.7 E-02 1.6 E-02 4 Sum of Iodines & Particulates a) % of Chimney Limit % 3.38 1.80 3.00 1.04 1.07 1.50 NA
- 5. Tritium Release Curies 1.7 E+00 1.7 E+00 2.6 E-01 7.4 E+00 8.3 E+00 6.4 E+00 2.6 E+01 ND = Not Determined 'NA = Not Applicable
O O O TABLE 1.2-1 REPORT OF RADIOACTIVE EFFLUENTS (From Dresden Semiannual Report, Aug us t 1975) Docket No.: 50-10 FACILITY: DRESDEN NUCLEAR POWER STATION - Unit 1 YEAR: 1975 Six Month Liquid Eff1'uents _ Units Jan. Feb. Mar. Apr. May June Total
- 1. Cross Radioactivity (R-y) a) Total Release Curies 7.0 E-02 5.9 E-02 7.4 E-02 6.5 E-02 8.3 E-02 8.9 E-02 4.4 E-01 b) Aver. Concentration Released pCi/ml 3.2 E-09 3.0 E-09. 3.4 E-09 2.5 E-09 3.1 E-09 4.1 E-09 3.2 E-09 c) Max. Concentration "cleased pCi/ml 8.5 E-08 3.9 E-08 4.0 E-08 3.6 E-08 3.6 E-08 5.3 E-03 5.3 E-08 d) % of Tech Spec Limit % 3.22 3.01 3.44 2.49 3.16 4.12 NA
- 2. Tritium a) Total Release Curies 2.3 E-05 1.5 E-06 1.1 E-04 1.7 E-03 1.3 E-01 1.1 E-01 2.4 E-01 b) Aver Concentration Released pCL/ml 1.1 E-12 7.9 E-14 5.1 E-12 6.6 E-Il 4.8 E-09 5.0 E-09 1.6 E-09 c) % of Tech Spec Limit I m
E . 7 3. Dissolved Noble Cases a) Total Release Curies ND ND ND ND ND ND ND b) Aver Concentratien Released pCi/ml c) % of Tech Spec Limit %
- 4. Cross Alpha Radioactivity ,
a) Total Release Curies 9.3 E-06 2.0 E-05 6.3 E-04 2.7 E-05 7.6 E-05 8.3 E-05 8.5 E-04 b) Aver Concentration Released pCi/ml- 4.3 E-13 1.0 E-12 2.9 E-Il 5.2 E-11 2.8 E-12 3.8 E-12 1.5 E-ll
- 5. Volume of Liquid Waste to Liters 2.0 E+05 3.1 E+05 4.9 E+05 4.3 E+05 5.6 E+05 4.6 E+05 2.5 E+06 Discharge Canal
- 6. Volume of Dilution Water Liters 2.2 E+10 2.0 E+10 2.2 E+10 2.6 E+10 2.7 E+10 2.2 E+10 1.4 E+11 IID = Not Determined NA - Not Applicable
O O o. i 4 TABLE 1.2-1(Cont'd) REPORT OF RADI0 ACTIVE EFFLUENTS Docket No.: 50-10 i YEAR: 1975 FACILITY: DRESDEN NUCLEAR POWER STATION - Unit 1 Six Month i Feb. Mar. Apr. May June Total j Liquid Effluents (Cont'd) Units Jan.
- 7. Isotopes Released Curies Cr- 51 - -
3.8 E-03 - - - 3.8 E-03 , Mn- 54 4.7 E-03 6.4 E-03 1.1 E-02 1.S E-02 4.8 E-03 5.2 E-03 4.7 E-02 Co- 58 4.4 E-03 2.1 E-03 2.0 E-02 1.5 E-02 4.4 E-03 4.7 E-03 5.1 E-02 , Co- 60 4.6 E-02 3.6 E-02 1.3 E-02 1.7 E-02 5.9 E-02 6.3 E-02 2.3 E-01 Sr- 89 2.3 E-04 6.0 E-04 1.2 ' 03 3.8 E-03 2.3 E-03 2.5 E-03 1.1 E-02 Sr- 90 4.0 E-05 5.0 E-05 3.0 E-05 2.1 E-04 3.1 E-04 3.3 E-04 9.7 E-04 Zr- 95 - Nb- 95m - - - -- Nb- 95 - - - - 4.2 E-03 4.5 E-03 8.7 E-03 6.2 E-04 3.4 E-04 9.6 E-04 i' - - - I -131 Cs-134 5.1 E-03 4.3 E-03 7.8 E-03 9.4 E-03 4.2 E-03 4.5 E-03 3.5 E-02 O 2.4 E-04 Cs-136 2.4 E-04 - - - - - Cs-137 8.4 E-03 9.0 E-03 1.5 E-02 4.6 E-03 3.8 E-03 4.0 E-03 4.5 E-02 Ba-140 - - 8.6 E-04 - - - 8.6 E-04 La-140 - - 9.9 E-04 - - - 9.9 E-04 ND = Not Determined NA = Not Applicable e 4 a 4 __ _ _ _ . _ _ ._ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ --m - _ _ _-. ___ -+. -~ ,. -
l'% pO .) 0 TABLE 1.1-1 REPORT OF RADIOACTIVE EFFLUENTS (From Dresden Semiannual Report, February 1976) - r/Ilt1TI: D'tcD33 NUCLEAR POTc.R STATIt.N - I!:IT 1 DjCKET POS._. <0 - 10 YEAH 197T l T. Ca 4ous t'rluents i' NITS Jul y _Aingust Scr e embe r October November December 6 MO. TOTA!. TECH. SPEC. FEF.
- 1. Cross nadlor.ctivity Releases n) Total Erlease curies 6.l.E*0h 9.lE+04 2.0E+03 Unit Off Unit Off Unit Off 1.6E+05 bl %ximu, Relca::a Rate LtC1/ sac _ 3.85 0h 4.5E+04 2.0 E +o4 h .5E+0f c) Isotopes Released Er-(Sb _ __ _ curies . 1.8E+03 2.9E+03 _ 6.4E401 -- -- --
h .C+ 03 curies 8.6E+03 Krd H. 2r+0 3 1.RE*02 -- --- -- 1.7E+0h Kr-P6 curies 5. 7E +0 3 9.tE*03 2.0E+02 - -
- 1.gE+0b Ie-333 curies 2.60+0L 4.2E+03 9.2E*01 -- -- --
Jg*L
- Je-335 curies 1.6E+04 I.Or+04 1.4E+02 -- -- -
l.d+0'.t Ie-13$a g curies _ 8.82+03_ I.3E+04 2.8E+02 -- -- 2.2E+da 4.a Ie-138 _, curies 2.7E+04 3.8E+04 8.GE+02 -- -- -- 6.6e+di ,, d) Percent of Chimney Limit $ h.3 6.1 5.1 t!n t t of f Unit Off Unit Off _._1 8 _,. 2.9E+04 " "
'I A") ESP. Release Rate- .uC1/ceo_ ?lhoh 3.4E+04 a ** w a 1,gg._al
- 2. Imline Releases a) Iro*cpes Released I-131 curies 2.92-02 7.5E-02 1.OE-02 3.00-03 7 .6f.-0 3 Jgh.
l E-M I-133 curies l hE-01 3.22-01 -- -- -- -
. hd-EL -._ -
1-135 curies 1.7E-01 3.7E-0. '- - - T.12-01 b) Porcent of Chianay 1.imit % 0.5 l 1.2
. o 0.2 < 0.1 <0.1 < 0.1 0.3 e) Average Release Rate. tC1/seo 1.1E-02 l 2.8E-02 4.0E-0 3 1.0 E-03 1.0E-03
. 1.0E- LO M -03 -
, .n -. -
O O TA!!LE 1.1-1 (Cont'd) NFPORT OF PADIDACTIVE EFF1.UENTS ff.CILitI: DRESDr.N NUCLEAR F0WER STATION - (HIT 1 Do m T NOS.: yn _M YEAR: 1975 . I. Caseou.' Effluents (continued) tl NITS July Aurunt Se pt embe r October Nnvember Deo mber 6 MO. TOTAL TECM. SPEC. RIF. J. Ferticulste Releases I a) GrossRadioactivity((() curies 2.2E-02 1 3.0E.02 2.7E-02 ' 7.00 03 7.6E-03 5.55-03 9.9E-02 4 b) Cross Alpha Radioactivity cur te_a_ c) Isotopes Released j 6 Cr-51 curies 8 q7_tp curies _ 6.2E-Oh_l8.9E-Of,_ 1.'S -02 h.1E-03 5.3C-03 *:.7E-03 3.m-02 Sr## _ curies 1.5E-02 : 1.63-02 5.aE-0!a ' 9.3E-05 6.1E-06 3.35-06 3 2J-c2 Sr-90 cu rj e,_ 1.0s-05 2.hE-0< . 3.C-05 1.1E 05 3.85-05 5.5E 06 9.71-05 Ifo-99 curies i I-131 curies 9.cE 4 9.Ci d to 4 Co _1% , _ curies h /A.4)$ 2.92-0! 1.9E-0) 13 0:4-Oh 7.1E-Oh 1.5E-O'i 3.5E-03
- curies 3.(2-OL L.SE-03 9.3E-OL 5.0E-Oh 3.3E-0L -
cs-137 5.1E-Of4 7 .12 -03 I'4-140 curies 5 6J-03 . 1.0E-00 1.6E-02 La-11.0 curies Np.239, .curien _ l Tc-9% curies I __ Co 58 2.LE-Oh ! 8.%Cfi 6.0L-03 1.<K-0) 8. E-Ob 8.6E-05 9 51-03 En 5L 1.!J:-OL 2.hE-ch 2.hE-Ola 6.21-OL d) Fercent of Chimney Limit % 03 0.5 0.5 0.1 0.1 < 0.1 0.3 e) Average Release uC1/sec 8.E -03 1.!E-02 1.1E-02 3,07 01 3.03-03 2.1E-03 6.2E-03 I
-l --
L. Sun of Iodines 4: Particulates l ' m) Percent of Chimney Limit 5 0.8 l 1.6 0.6 0.2 0.2 0.1 0.6
- 5. Caseous Tritium e a) Total Release Curies 7,p ,_g1 l1.0E00 1.8300 2.7E00 2.62-01 9.6E-01 8.2E 00 b) Average Release Rate LC1/sec 7,7g_ct l6.9E-01 6.U -01 9.95-Cl 1.0E-01 3.6E-01 5.2E-01
.- - - -- - = ._
i k , TABLE 1.2-1 *
-REP_O_RT OF RADIOACTIVE EFFLUENTS .
4 (From Dresden Semiannual Report, February 1976) FIC1!.tTJ: DRESD;N *:UCLEAR PO*4ER STATIW - 12:IT 1 DorKET Nos.: 50 - 10 YEAR: 1975 II. Ligtid iffluents UNITS JuiY August Septenber ' October November December 6 MO. TOTAL TECit. SPEC. T.EF. l 4
- 1. GrossRadioactivity(8-[)
a) Total Reicasa Curies '1.2E-01 6.5E-02 7.4E-02 5.1E.02 h.%:-02 h.hE-02 h.02-01 b) Average Concontration Released uel/mi L.hE-09 I.4E-09 ?.8E t . o r-09 8.7':-09 2.0';-09 3 15-07 c) Patinum Cecentration Relear.ed uct/a1 L.lE-OS 4.1E-OS 5.4E-08 4.27-OS 2.8:-03 3.BE-03 5.hE-OS d) Percent of_ Tech Spec Limit % h.h 2.4 2.8 1.9 8.2 2.0 3.1
- 2. Tritium
; e) Totml Release ,
Curies 1.9E-03 1.9E-02 6.02-O?: h.65-0) 5.!u-da 2.02-03 2.9E-02
. b) Average Ccarentration Released uci/ml 5.0E-06 7.0E-10 2.33-11 1.7E-10 9.83-11 p 1g-11 2.2g-10 I
g 7 c) Fercent of Tech Spec Limit u
- 5. Dissolv-d foble Cases a) Total :talanse Curtes ND ND ND ND ?:D i;D c b) Arorage Concentration Released uci/n1 c) Percent of Tech Spec Limit Ja . Cross _ Alp Padlonctivity a) Total, Release _ ,, . Curie _s 1.55-Oh 7.9E-05 1.3c.94 2.4E-05 3.37-05 3.05-05 h.TE-Oh b) Avert.ge Concentration Released u c1/m1 S.6E-12 2.9E-12 5.0E-12 8.9E-13 1.h3-12 3.5E-12 (3.93-12 _
1 Yohane of Liquid Waste to Liters 3 6E+05 3.2r+05 3.0E+05 3.0Em$ B.02+07 1.0E*05 3 1L+06 Discharre Canal e -,_
, 6. Yolume of Dilution Water Liters 2.7E+10 2.7E+10 2.6E+to 2.7F+IO ?.Tr+00 2.2E+10 1. 3E+11
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r'% DRESDEN NUCLEAR POWER STATION JANUARY - DECEMBER 1974 WING ELEVATION 35 FT STABILITY BASED ON 150-35 OELTA T NUMBER OF OBSERVATIONS = 5698 - - - - - - SPEED DIRECTION CLASS STABILITY CLASS -- CL ASS - - - - N NNE - NE -ENE -E- ESE SE. SSE S SSW SW WSW W WNW NW -NNW TOTAL EU - MU SU N SS NS ES TOTAL-EU .02 .02 .02 .45 .G2 0.00 0.0C 0 00 .02 .05 .16 .11 .12 0.00 .04 .05 '. 6 8 .68 Mu .02 0.00 0.00 0.00 0.00 0.CG .02 0.C0 0.00 .02 0.00 .02 0.00 .02 0.00 0.00 .10 .10 SU .05 0.00 .02 0.00 0.00 0.00 0.0C 0.G0 0.00 0.00 .05 0.00 .02 .02 .02 0.00 .18 .18 -- 3 N .C7 .07 .11 .C4 3.C0 .J5 .04 .07 .04 .12 .11 .11 .04 .04 .G4 .09 1.04 1.04- -- - - SS .C4 .21 .14 .12 .11 .12 .14 .16 .23 .18 .32 .16 .16 .18 .12 .11 2.50 2.50 MS .G4 .J4 0.JC .05 .C7 .12 .11 .19 .14 .28 .35 .16 .04 .11 .14 .09 1.93 1.93 ES .G* .05 J.JC .C 2 3. C 0 .02 .04 .12 .04 .12 .05 .14- .19 .05 .05 .04 .97 - .97 7.40-
--- --- - - E U .32 .23 .35 .12 .14 . 19 .21 .16 .19 .11 .14 .16 -.26- .19 - .32 .21 3.30 3.30 - - --- -,
Mu .14 .04 .J5 0.00 .04 .02 .05 .02 .02 .04 .04 0.00 .07 .09 .09 .07 .79 .78 Su .18 .49 .09 .c2 .C4 0.30 .05 .C5 .02 .05 .07 .07 .L- .07 .C7 .05 .96 .96 - - 7- N .39 .39 .44 .26 .33 .25 .37 44 .44 .49 .47 .32 .33 .32 .28 .28 5.92 5.82 -- SS .47 .46 .58 .63 .93 .93 .61 1.07 1.09 .95 .95 .67 .84 . 70 .75 .44 12.07 12.07 MS .25 .14 .11 .16 .47 1.12 .21 .84 .86 .82 .67 .53 .47 .16 .26 .42 7.49 7.49 - - - - - --ES .05 .02 .02 0.GC -.C7 .25 . C9 . C 2 - .16 -.46 .60 .21 .25' .C5 -.c4 .02 2 31 - -- 2.31 32 734 Eu .56 .21 .67 .J5 -.25 .33 .26 .28 .40 .74 .33 .09 .37 .68 .65 .26 6.43 6.43 - Mu .11 0.00 .J2 .C. .09 .07 .12 .C7 .05 .G9 .09 .34 .12 .07 .16 .09 1.23 1.23 SU .11 .07 .32 .05 .G7 0.00 .37 .02 .07 .07 .05 .07 .09 .12 .C4 .04 .96 .96 --- S-12 m .12 .05 .16 .44 .54 .6C .61 .58 .63 .39 .33 .37 .75 .65 .75 .28 7 25 7.25 -- - SS .30 .37 .*6 1.26 1.42 1.0C .9C 1.C0 1.02 .86 .98 .68 1.12 1.16 1.11 .90 14.54 14.54 MS .03 .35 .J7 .02 .30 .37 .16 .33 .37 .63 .30 .28 .18 .11 .G5 .C9 3.36 3.36 _ _ . ES 3.00 0.0G 0.JC 0.Ga 3.J0 0.30 0.00 .G2 .05 .18 .21 .02 0.00 0.00 0.00 0.00 .48 .48 34.25-
- - - - - - Eu .11 .33 .45 .14 .35 .19 .12 .18 .25 -.35 .12 .33 .28 '. 4 9 .60 .23 4.09 4.09 -,
Mu .02 0.40 G.JG .05 0.C0 .J2 .02 0.00 .05 .05 .02 .16 .05 .04 .12 .c4 .64 .64 . SU 0.00 .04 .'0 2 .02 .04 0.JO .02 0.C0 .11 .02 .02 .07 .02 .09 .09 .05 .61 .61
-- 13-13 N .C2 .44 .04 .02 .11 .19 - . 4C .21 .49 .39 .37 .23 .82 .33 .54 .21 4.41 --
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- E S 4. G C 2.GJ J.34 0.C0 0.00 0.00 0.00 0.C0 0.00 0.C0 0.00 0.04 0.00 0.00 0.00 0.C0 0.00 0.00 19.684 Eu .02 .04 0.00 0.00 .CZ .09 .02 .02 0.00 .02 .02 .02 .12 .25 0.00 .02 .66 .66 - --
Nu 0.JO .02 G.J0 0.00 0.00 0.00 0.00 0.00 .05 .05 0.00 0.00 .02 .02 .02 0.00 .18 .28 Su 0.0G C.0C Q.JC 0 02 0 00 0 00 .04 0 00 .02 .02 0.00 0.00 0.00 0.00 0.C0 0.00 .08 .08 24 N 0.00 .04 .02 0.00 0.00 .02 .07 .c4 .16 .18 .11 .11 .11 .07 .C4 0.00 .97 - --
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- ES .02 0.0C 0.0J .G2 .05 0.00 .04 0.C0 .04 0.C0 0.00 0.00 .02 .C4 .04 0.00 .27 - -
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MU 0.0G .04 0.dJ 0.00 0.00 0.00 0.00 0.00 .04 .05 .04 .0* .04 .07 .07 .05 .44 .44 SU 0.G0 0.CC .05 0.00 0.00 0.00 .04 0.00 .04 .05 0.00 .02 0.00 .04 .02 .04 .30 .30 --1G-24 N 0.C0 .05 .34 .C4 0.C0 .05 .10 .11 .16 .23 .18 .12 .33 .25 .14 .11 1.97 1.97 , SS 0.60 .G* .26 0.00 .16 .23 .26 .39 .60 1.18 .53 .23 .21 .58 .33 .21 5.26 5.26 MS 0.00 0 03 C.JG 0.00 .02 .02 .04 .18 .11 .14 .11 0.00 0.00 .C2 0.C0 0 00 .64 .64
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, NUMBER OF OBSERVATIONS s 7359 SPEED DIRECTION CLASS STABILITY CLASS ,
- CLASS -N NNE- NE ENE E ESE SE SSE S SSW- SW WSW W WNW - NW NNW-TOTAL EU MU SU N SS - NS ES TOT AL-- 9 EU .04 0.00 0.0d 0.00 0.00 0.00 0.00 0 00 .03 0.00 .03 0.00 0.00 0.00 .01 .01 .12 .12 MU 0.00 0.00 0.0J 0.03 .01 .03 0.0C 0.00 0.00 0.00 0.00 0.00 0.00 .01 '. 01 0.00 .06 .06 50 G.C0 0.00 C.00 0.G0 0.00 0.00 .01 0.00 0.00 0.00 .01 .01 0 00 0.0c .01 .04 .08 .08 - 1-3 N .06 .05 .J3 .C4 .05 .01 .07 .05 .07 .G7 .11 .01 .04 .01 .12 .04 .85 .85 -- SS .01 0.00 .01 .04 .C8 .01 .12 .05 .01 .0* .05 .04 .07 .c4 .04 .04 .65 .65 MS .C1 0.G0 .01 0.00 .03 .31 .01 .C1 .03 0.00 .03 0.40 .03 .04 .w3 0.C0 .24 .24 -- -- ES .G3 0.JG G.JO 0.G0 0.00 0.00 0.00 .C1 .01 .03 0.00 0.J0 0.00 .03 0.00 .03 .14 .14 2.14 - - - - - - - Eu .12 .08 .05 .04 .04 .03 .04 .04 .01 .G3 .04 .04 .J8 .07 .05 .10 .86 .86 -- HU .C4 0.00 .03 .C5 .03 .04 .05 .04 .01 0.00 0.00 0.00 0.00 .05 .03 .01 .38 .38 SU .10 .G5 .04 .C8 .03 .07 .10 .03 .05 .05 .07 .04 .14 .08 .C7 .04 1.34 1.04 -- 7 - N .35 .43 .45 .31 .26 .29 .35 .39 .31 .41 .38 .38 .53 .31 .29 .29 5.79 5.79 SS .14 .19 .13 .29 .24 .16 .22 . 24' .23 .20 .24 .20 .30 .22 .15 .19 3.39 3.39 MS 0.GG .07 .05 .11 .37 .07 .07 .12 .12 .04 .10 .08 .14 .10 .11 .07 1.32 1.32 = ~ ES .C1 0.CG . 01 0.CJ .C1 .03- .04 0.03 .03 .04 .05 .01 .03 .03 .05 -.04 .38 - - - - -
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- - - - - . EU .08 .14 .12 .2J .12 .10 .12 .07 .05 .03 .12 .05 .05 .08 .CF .15 1.55 1.55 - MU .G4 .04 .03 .01 .03 .04 .08 0.00 .07 .05 .04 .04 .07 .05 .10 .16 .55 .85 Sts .11 .12 .11 .44 .04 .12 .11 .05 .11 .05 .15 .07 .12 .14 .19 .19 1.72 1.72 __ 8-12 N - .77 .53 .86 .87 .49 - .57 . 64 - .77 .96 .71 .50 .50- .61 .84 .79 -.57 11.33- -- --- 11 03- -- ----* SS .38 .38 .*8 .*9 .33 .53 .42 .42 .52 .60 .63 .68 45 .53 46 .54 7.87 7.87 MS .19 .16 .05 .05 .19 .07 .23 .27 .11 .22 .30 .27 .31 .ie .23 .14 2.97 2.97 ;
-- ES .C3 .03 .01 .G1 J.CG 0.0G .01 0.00 0.00 -.07 .08 .11 .08- .G5 .03 0.00 .51 .51 26.58 -
-- EU .20 .16 .2J .33 .12 .14 . 15 .19 .04, .15 -.19 .03 - .11 - .30 . 31 -.22 2.84 2. 8 4 -- - -
PU .10 .05 .03 .04 .01 .11 ,07 .09 .04 .11 .11 .01 .05 .11 .14 .16 1.22 1.22 Su .G4 .04 .JF .C4 .15 .08 .11 .C8 .14 .15 .18 . 12 .12 .20 .22 .23 1.97 1.97 , -- 13-18 N .33 .53 .42 1.C1 .88 .48 .49 1.14 1 18 1161.03 .64 1.11 1.37 1.37 .48 13.62 13.62 - - - - - SS .45 .50 .16 .18 .73 .84 .98 .90 1.60 1.35 1.20- .84 .64 .56 .56 .42 11.91 11.91 MS .37 .12 0.JG 0.0c .14 .29 .18 .24 .26 .52 .53 .38 .35 .19 .10 .12 3.79 3.79 - - - - - ES .01 .G3 0.3G 0.sc 0.C0 0.00 0.0C 0.00 .03 .07 .14 .08 .33 .01 .01 .01 .42 - - - - - -
.42 35.77-
-- EU .C7 .24 .1J .11 .C7 .08 .03 .C4 .05 .10 .05 0.00 .03 .08 .10 .07 1.22 1.22 --
HU 0.C0 .05 .J1 .03 .05 .01 .01 .04 .01 .11 .04 .05 0.00 .10 .C4 .04 .59 .59 SU 0.G0 .04 0.00 0.00 .05 0.00 .03 .07 .07 .14 .15 .04 .01 .07 .10 .05 .82 .82
- 19 24 N .15 .22 .13 .18 .22 .20 . 31 48 .92 .90 .49 .84 .80 .67 '.77 .35 7.60 - -
7 60 - , SS .11 ..C7 .03 .G3 .01 .14 .29 .34 .68 .76 .58 .27 .37 .33 .16 .10 4.27 4.27 MS .10 .04 J.00 0.C0 .C1 .04 .05 .C7 .07 .14 .45 .19 .05 .03 .C1 .03 1.28 1.28
--- ES 0.00 .G1 0.00 0.G0 0.C0 0.00 0.00 0.C0 0.00 .01 .04 .04 0 00 .01 0.C0 0.00 .11 .11 15.89-
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Mu 0.00 .G1 .J1 0.J0 .01 0.00 .01 0.00 .01 .07 .03 .01 0.00 .01 .03000 .20 .20 SU J.00 0 00 .J4 0.00 0.00 0.00 .01 0.03 .04 .05 .03 .01 0.00 0.00 .C4 0.00 .22 .22
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- CLCSS -- N NNE NE- ENE E ESE SE SSE S SSW SW NSW W WNW NW -NNW TOTAL EU MU SU N - SS -- MS ES - TOT AL--
-- EU .01 .01 .01 .02 .51 .01 0 00 .01 .G1 .02 .08 .06 .06 .01 .01 .02 .35 .35 Mu .41 .01 J.JO 0.0C 3.00 0.00 .01 0.00 0.00 .01 0.00 .81 . 01 .01 .01 .01 .09 . 09 SU .03 0.00 .01 0.00 0.00 0.0C 0.00 0.00 0.00 0.00 .02 0 00 . 01 .01 .01 0.08 .09 .89
-- 1 3 N .C4 .06 .1C .03 .01 .03 .01 .04 .03 .07 .35 .06 . 01 .01 .G5 .08 .68 .68 -- - - - - -
SS .C5 .11 .15 .1C .GT .07 .13 .12 .15 .15 .24 .11 . 12 .13 .11 .12 1.93 1.93 MS .05 .C4 .J2 .08 .37 .15 .10 .14 .19 .23 .27 .0T .05 .10 .12 .10 1 78 1 78
-- ES .G3 .44 .J1 .02 .04 .07 .04 .09 .08 .20 .15 .13 . 13 .07 .09 .05 1.24 1 24 6.16 -
EU .19 .13 .20 .13 .11 .11 .13 .10 .10 .08 .07 .10 . 19- .15 .16 .15 2. 0 7 2. 0 7 - -- -- - ~ -- -- Mu .04 .C2 .JT .02 .C4 .04 .02 .01 .01 .04 .01 .01 . 10 .04 .06 .04 .61 .61 SU .13 .08 .JT .C2 .04 .01 .04 .02 .01 .03 .04 .05 . 07 .04 .04 .04 .73 .73
--4=T- N .39 .38 .55 .52 43 .25 .32 .35 .40 .28 .28 .19 .24 .28 .34 .43 5.63 5.63 --
SS .55 .60 .80 .93 .99 .94 .79 1.13 1.36 1.00 .94 .63 .82 .TO .T4 .T2 13.64 13.64 MS .31 .22 .32 .36 1 05 1.44 .T8 1 19 .97102 .T9 .62 . 54 .45 .48 .57 11.11 11.11
-- ES .CT .06 .J6 0.0C .07 .46 .19 .14 .34 47 .57 .24 -.285 18 .20 .14 3.47 - - - - -- 3.47 37.26
- - - - - - EU .40 .24 .47 .28 .1T .24 .21 .12 .24 .38 .21 .10 . 28 .49 .44 .22 4.49 4.49 --
MU .09 .01 .J3 .G4 .C9 .04 .10 .04 .06 .05 .07 .84 . 08 .10 .08 .06 .98 .9S SU .15 .GT .J2 .06 .09 .04 .CT .01 .09 .06 .03 .05 . 07 .07 .07 .35 1.00 1.88 l
.49 .64 .80 .49 49 40 .52 .34 .33 .29 67- .53 . 57 .49 T.90 --
-T.98 - ---;
--_G.12 N . 49 .40 .
SS .52 .43 . 3. .T1 1.17 .88 .T3 .85 1.30 .85 1 04 .66 1.02 1.08 1.C4 .88 13.49 13.49 MS .GT .Os .08 .06 .23 .26 .27 .43 .54 .T1 .43 .30 . 23 .12 .10 .13 4.04 4.04 ES 4.GC 0.00 d.JD 0.G0 0.00 . 03 .02 .05 .10 .15 .21 .04 8.00 .01 9.00 0.08 .61 -- -
.61 J2.51-EU .12 .26 .C3 .G9 .24 .18 - . 0 8 - . C 9 .16 -.24 .18 -- .16 . 16 433 .39 .16 2.67 2.47- - -- -- ;
70 .03 .01 J.00 .03 .C4 .02 .01 0.00 .03 .G5 .04 .07 . 03 .04 .12 .10 .62 .62 SU .01 .02 .01 .02 .05 .01 .02 .C2 .08 .04 .03 .04 . 04 .06 .08 .07 .60 .40
--13-18 N .13 .15 .37 .17 .42 .22 .35 .46 .5T .38 .29 .32 . 72 .35 .54 .27 5.41 5 41 .-
SS .13 .20 .19 .04 .25 .23 .30 .61 .99 .94 .54 .52 . 48 .65 .52 .26 6.85 6.45
.C1 0.JC 0.00 .01 .01 .J4 .20 .17 .19 .07 .04 . 04 .01 .01 .01 .82 .82 MS .01
-- -- -- ES C. 0 C C.00 J.C0 0.0L 0.C0 0.00 0.00 0.0 0 0.0 0 8.6 0 0.0 0 0.0 0 0.00 0.C 0 8.0 0 0. 0 0 0 . 0 0 - -- -- - -- - 0.88 17.17-
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----- EU .02 .04 3.0J 0.CO .02 .05 03 .C1 .02 .05 .07 .01 . 16- .12 .04- .82- .66 .66 - - - - - -
MU 0.CJ .01 C.03 0.00 0.00 0.00 .01 .01 .04 .04 .01 .01 . 02 .82 .01 0.00 .18 .18 SU 0.C0 0 00 J.JJ 0.C0 0.00 .01 .02 0.00 .01 .01 .01 0.00 . 01 .01 .01 .02 .11 .11 24 N 0.C0 .03 .31 .01 .13 .0F .06 .19 .27 .18 .15 .17 . 40 .13 .04- .11 1.95 - - - -- - - 1. 9 5 - - - SS 0.CG .35 .J4 0.CC .G1 .06 .13 .35 .60 .26 .18 .17 . 19 .18 .04 0.08 2.26 2.26 MS 0.CJ 0 03 J.30 C.00 0.00 0.80 8.00 .09 .06 .04 .01 8.03 8.00 .01 8.00 8.00 .21 .21
- - - ES 0.04 0.03 C.JO 0.0G 0.C0 0.00 8.80 0.00 0.00 0.00 0.00 0.08 8.80 8.00 8.00 0.08 8.00 0.80 5.37-EU 0.00 0 00 4.JG 0 00 .02-0.00 0.00 0.00 0.00 .81 .01 .01 . 07 0.80 8.G0 0.00 - .12 .12- - - - - - -
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Mu 0.00 0.00 G.33 0.00 .G1 0.00 0.pt C.00 0.00 0.05 0.00 0.00 . 01 0.00 0.C0 8 00 .82 .82 SU 0.0G 0.00 0 00 0.00 0.C0 0.00 0.00 0.00 0.00 .01 .01 .01 . 01 5.08 8.00 8.88 .44 .84
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SS 0.00 3.30 3.30 0.00 0.G0 0.00 .01 .06 .13 .06 .10 .03 . 10 .02 0 00 0.00 .51 .51 MS 0.G0 0.33 0.J4 0.04 0.00 0.00 0.00 0.C0 .04 .31 .01 8.80 8.00 0.00 0.G0 0.00 .86 .86 ES 0.0 0 0.00 4.00 0.0 0 -J.0 0 0.00 0.00 0.00 0.00 8.00 0.00 0.00 0.00 8.08 0 00 0.08, 8.00, 0.88 1.11 - - _ - - , - - - . - - - - _ - - - - _ - - - - - - - - - - - - - - - - - _ - - - - - - - -- ww n w ~ < - - - - - - - - ---
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, NUMBER OF OBSERVATIONS = 13449 SPEED DIEECTION CLASS STABILITY CLASS -CLASS ~~-N. NME - hE EhE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL- EU NU SU - N $$ - NS - ES - TOT AL--
1 Eu .03 .02 .31 0.00 .01 0.00 .01 0.00 .02 .01 .06 .02 .01 .02 0,.08 .02 .24 .24 MU .01 .01 0.00 0.0G 0.00 0.00 0.00 C. 0 0 0. 0 0 0.00 0.00 0.00 .01 0.00 .01 .01 .05 .95 , SU .01 .01 0.30 0.00 0.00 0.00 0.00 C.00 0.00 0.00 .01 .01 0.00 0.00 0.00 0.00 .04 .04 - - 3 m .03 .01 .25 .04 .01 .03 0.OG .03 .01 .04 .03 .04 .01 0.CC .02 .03 .38 .38 - ' --- SS .07 .02 .J6 .Js .C4 .01 .06 .09 .06 .07 .06 .06 .05 .10 .C5 .04 .98 .88 MS .C2 .01 .01 .05 .C3 .03 .04 .03 .05 .G2 .03 .04 .01 .03 .06 .02 .48 .48 - - - - ES .G1 .01 0.30 .C1 .04 0.0G .04 .01 .0* .02 .01 .03 .01 .03 .C3 .02 .31 -
.31 2.38 - - - - - - EU .12 .08 .14 .06 .07 .11 .09 .08 .08 .05 .10 .11 .15 .14 .14 . 0 9 - 1. 5 7 1. 5 7 -- - -- - - -- - - - -
Mu .03 .02 .34 .G4 .03 .33 .02 .02 .01 .02 .01 .02 .04 .02 .~ 0 3 .04 .42 .42 , SU .04 .07 .37 .03 .03 .01 .01 .01 .02 .01 .02 .06 .06 .04 .C2 .05 .55 .55 -- T . N . 32 .2o .20 .31 .28 .13 .18 .20 .31 .16 - .25 .09 .1T .13 .17 .25 3.41 3.41 - SS .33 .2T .41 .55 .51 .45 .53 . 4 7' .76 .64 .54 .46 .43 .42 .39 .57 T.73 T.73 MS .19 .09 .16 .29 .31 .42 .62 .41 .39 .44 .39 .29 .34 .26 .27 .18 5 05 5.85
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-2.85-28.76-2- - EU .25 .19 .33 .13 .14 .18 .19 .C9 . 21 .19 .12 .08 .27 .24 .25 .13 2 99 2.99 -- '
Mu .C6 .02 .45 .02 .05 .01 .08 .04 -25 .06 .05 .04 .08 .06 .07 .04 .78 .78 SU .12 .08 .03 .06 .C3 .03 .04 .04 .07 .06 .C3 .06 .05 .05 .C6 .05 .66 .86 i*
C- 12 N- .47 .40 45 .53 .61- .45 36--.51 .46 .45 .26 .27 .35 . .- 3 6
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SS .64 .45 .61 .97 .98 .92 .82 .93 1.38 1.13 1.19 .74 .79 .96 .68 .78 14.17 16.17 MS .41 .16 .22 .27 .65 .35 .63 .81 .91 1.02 .90 .55 .54 .34 .24 .37 8.87 8.87 i
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Mu .L4 .0 3 G.JG .04 .03 .04 .02 .C1 .48 .04 .05 .07 .07 .06 .11 .09 78 .78 Su .05 .02 .01 .08 .34 .02 .03 .03 .07 .46 .01 *.04 .06 .07 .09 .05 .73 .73 -- 13 N .16 .2C .26 .34 .49 .27 .34 .37 .51 .52 .39 .34 .TT .50 .53 .42 6.41 6.41
. SS .29 .24 .22 .15 .54 .57 .51 .69 .92 1.00 . 91* .78 4? .93 .83 .66 10.16 10.16 MS .C5 .13 .03 .01 .05 .18 .15 .25 .60 .59 .50 .3T .46 .06 .12 .11 3.46 3.46
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O O O < ORESDEN NUCLE AR POWER S ATIbH kNb4RY 1974 bECEMBER 1975 , WIND ELEVATION 300 FT STABILITY BASED ON 300-35. DELTA T NUMBER OF OBSERVATIONS = 15155 SPEED DIRECTION CLASS STABILITY CLASS
-- CLS$5 --.N NNE - NE - ENE E ESE SE SSE S SSW SW WSW W WNW NW - NNW TOT AL - EU HU SU N SS- -MS ES TOTAL-EU .02 0.00 0.30 0.04 0.00 0 00 0.00 0.C0 .01 0.00 .01 0.00 0.00 0.00 .01 .01 .06 .06 Mu .01 0.00 0.00 0.0J .01 .01 0.00 0.00 0.00 .01 0.00 .01 0.00 .01 .01 .01 .08 .08 50 .01 .01 .01 .01 0.00 0.00 . 01 0.03000 0.00 .01 .02 0.00 .01 .01 .03 .13 .13 .--_ 1 - 3 N .06 .03 .03 .05 .07 .02 .06 .05 .06 .08 .08 .02 .04 .C3 .07 .05 .80 .60 -
SS .C1 .C2 .31 .03 .C5 .01 .07 .05 .03 .G3 .04 .0J .03 .02 .C4 .03 .50 .50 MS .C1 0.JC .J2 0.0C .01 .31 .01 .02 .02 0.00 .02 0 00 .03 .02 .01 .01 .19 .19
- - - - - - - ES-.01 0.00 C.JG 0.4C 4.00 0.00 0.CC .01 .01 .C1 0.00 0.00 0.00 .01 0.00 .01 .06 . 0 f. 1.82 EU .11 .06 .J8 .02 -.03 .03 .02 .03 .01 .03 .02 .03 .07 .05 .07 .07- .73 .73 - - - - - .- - - --
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--- 4 N .33 .37 .*C .45 .35 .36 .40 .40 .44 .38 .38 .36 .43 .32 .27 .40 6.04 6.04 ->
SS .13 .15 .22 .31 .19 .22 .4C .36 .28 .21 .22 .18 .33 .28 .20 .19 3.87 3.87 MS .03 .06 .05 .11 .06 .08 .11 .13 .12 .G9 .11 .09 .15 . 15 .13 .07 1.54 1 54 ES .01 .01 .J3 ..J1 .b1 . 01 . C 3 . 01 .02 .03 .03 .01 .03 .03 .03 -.02 .32--- -
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- 11.73 --- 3 SS .35 .34 .48 .63 .50 .57 .81 .61 .63 .66 .73 .58 .64 .56 .48 .42 8.99 8.99 !
MS .14 .13 .JT .65 .17 .13 .24 .32 .18 .30 .26 .27 .36 .20 .16 .11 3.09 3.49 f - - - - ES .G5 .31 .J1 .03 .C1 0 00 .32 .01 .01 .05 .10 .15 .13 .07 .04 .05 .74 --
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