ML20093D170
| ML20093D170 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/30/1984 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20093D167 | List: |
| References | |
| PROC-840630-02, NUDOCS 8407160159 | |
| Download: ML20093D170 (59) | |
Text
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- JUNE 1984 i i
1 OFFSITE DOSE CALCULATION MANUAL i 1 i I i COMMONWEALTH EDISON COMPANY i i I L
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REVISION 11 , JUNE 1984 BYRON i () ODCM LIST OF TABLES FOR BYRON SECTION 7.2 NUMBER TITLE PAGE 7.2-1 Aquatic Environmental Dose Parameters 7.2-1 7.2-2 Annual Design Objectives Set by , 10 CFR 50, Appendix I for Each Reactor 7.2-2 ! 7.2-3 Station Characteristics 7.2-3 7.2-4 Critical Ranges 7.2-4 l i 7.2-5 Terrain Correction Factors (h ) 7.2-5 7.2-6 X/Q and D/O Maxima At or Beyobd the . Unrestricted Area Boundary 7.2-6 ,. 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles 7.2-8 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors for Selected Nuclides 7.2-9 l l t I i
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i REVISION 11 i BYRON JUNE 1984 [ t i ODCM LIST OF FIGURES FOR BYRON SECTION 7.2 I; 3 NUMBER TITLE 7.2-1 Restricted Area Boundary s ; ?t I I !
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BYRON REVISION 11 JUNE 1984 p TABLE 7.2-1 'y ( b AOUATIC ENVIRONMENTAL DOSE PARAMETERS PARAMETER BYRON BASIS
- U", water usage, liters /hr 0.042 A f
U, fish consumption, kg/hr 2.4 a 10~3 8 1/M", 1/M I 1 C F", cfs 5.2 a 10' D I 3 F , cfs 4.7 x 10 E f t , hr 24 F t", hr 115 G Bg - Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, Column 2 for freshwater fish. See Table 7.1-12.
- t F , gg, F", cfs I#M o p Not Applicable. No outdoor tanks t*'
o he without overflow pipes connected to other storage tanks. t V , 9,g t,, he , f
- Basis codes:
i As Reference 6.2, Page 138. Be Reference 6.5, Table E-5. C: Conservative assumption (implies no additional dilution) . De The receiving body of water is taken as the Mississippi River, whose confluence is approximately 115 miles downstream of the plant. F is taken as the sum of the following everage flow rates: Rock River at Como, Illinois 5.0 x 103 cts per Byron Station (45 miles downstream Environmental Report, Subsection of plant) 2.4.1.2 0 Mississippi River near DeWitt, 4.7 a 10 cfs per Quad-Cities Iowa (approximately 35 miles Station Units 1 and 2 Safety upstrees of confluence with Analysis Report, Section 2.4 Rock River) E: The near-field receiving body of water is the Rock River. FI is 3 taken as the average flow of the Rock River at the site, 4.7 s 10 cfs per Byron Station Environmental Report, Subsection 2.4.1.2. F Assumption. G There are ao potable water intakes on the Rock River downstrees of the plent (per Byron Station Environmental Report, subsecgion 2.1.3.2.1). For 10 CFR 50 compliance evaluation purposes, t is taken as 115 hr, the estimated time of flow to the Mississippi River. The confluence of the Rock River with the Mississippi River is approximately 115 miles downstream of the plant (per Byron Station Environmental Report, Sub-section 2.1.3.2.1). The flow rate is estimated as 1 mph based on the data in Table 2.2-5 of the Byron Station Environmental Report. 7.2-1 s
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i BYRON REVISION 11 I JUNE 1984 O TABLE 7.2-2 L ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, , APPENDIX I, FOR EACH REACTOR l i TYPE OF DOSF ANNUAL DESIGN OBJECTIVES t 4 k Airborne Releases t Gamma Air Dose 10 mrad j ) 1 Beta Air Dose 20 mrad ! i i Whole Body Dose 5 mrem i i Skin Dose 15 mrem ; Infant Thyroid Dose 15 mrem i i Liquid Releases f Whole Body Dose 3 mrem Thyroid Dose 10 mrem f r Bone Dose 10 mrem l t Skin Dose , 10 mrem l I I l
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BYRON REVISION 11 JUNE 1984 r~w (_s) TABLE 7.2-3 STATION CHARACTERISTICS STATION: Byron LOCATION: 3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height = m 2) Diameter = m
-1 -1
- 3) Exit Speed = ms 4) Heat Content = KCal s CHARACTERISTICS OF VENT STACK RELEASE POINTS
- l E e
- 1) Release Height = 60.96 m 2) m = 2.80 ,
~1
- 3) Exit Speed = 15.34 ms
*The station has two adjacent rectangular vent stack release points of O the same height and cross section. Their conters are 15.01 m apart.
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Building Factor (D) = 60.6 m l METEOROLOGICAL DATA ,
A 250 ft. Tower is located 1036 m SW ofventstackreleasepointl Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA) Vent 250 ft 250 - 30 ft Ground 30 ft 250 - 30 ft 7.2-3 l l
I BYRON REVISION 11 l JUNE 1984 l O TABLE 7.2-4 CRITICAL RANGES I I RESTRICTED ! AREA NEAREST ** NEAREST DAIRY FARM DIRECTION BOUNDARY * (m) RESIDENT (m) RANGE ** (m) ll l N 1875 2300 ---- t NNE 1829 2900 ---- t : NE 1585 1900 3400 i ENE 1234 2100 ---- t E 1227 1900 ---- t ESE 991 2600 5100 l l SE 1006 2100 5300 : () s._ SSE 800 1300 ---- t r S 945 1100 3200 ; i SSW 975 1000 ---- t SW 1067 1300 ---- t I I WSW 1212 2700 ---- t W 1189 3100 3100 i WNW 1227 3400 5300 , NW 1300 1300 5100 , NNW 1044 1900 ---- t i l
- j.
- Approximate distance from midpoint between gaseous effluent t release points. (See FSAR Table 2.1-la (Amendment 39, l
September 1982) and ER Table 2.1-1 (Amendment 1, July 1981).) s ,
** Approximate distance from center of plant per 1983 annual l survey by Teledyne Isotopes Midwest Laboratories. ;
O - tNo dairy farm found within 5 miles (8000 m) of station. i t 1 7.2-4 ; l
-,. , _ _ _ . _ . , _ _ , _ _ _ _ . _ , _ , _ _ . - _ _ .n.._________. , __. _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ . . , _ _ - _ . . . . .
I BYRON REVISION 11 ;. JUNE 1984 ! O ! I TABLE 7.2-5 I l TERRAIN CORRECTION FACTORS int ) * (ht = 0 to Stated Range, Then ht = Given Value) RANGE ht DIRECTION (miles) (meters) t t N 0.0 [ NNE 0.0 f NE 0.0 ' ENE 0.0 t E 9.0 3.0 ESE 0.0 ; SE 5.0 11.0 SSE 4.2 9.0 [ S 4.4 9.0 j SSW 0.0 ! SW 5.0 9.0 . { l WSW 6.5 12.0
- W 7.6 14.0 i WNW 0.0
{ NW 7.3 9.0 l NNW 9.7 6.0 ; i I I
*Within 10 miles 7.2-5 l I
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(% gg. 1 4 1x s v/ s ( TABLF 7.2-6 X/O AND D/9 MAvfMA AT OR BEvnND THF tlNRf'STRICTFD ARFA BOtlNDARY DOWNWINO ELFVATFDISTACW) RFtFASF MIXFDt MODEIVENT) RFtFASF _GROUN() LFVEL RFLFASF DIRECTION RADIUSu N/Q RADluS" D/0 RADIUS" x/O D/Q RAOluS" X/Q O/Q (MFTERS) (SFC/M *3) (MFTFRS) (t/M**?) (MFTE95) (SFC/M**~ll (1/M**2) (METERS) (SEC/M.*3) (t/M**2) N 1875. 9.357-OR 1875. '.6RO 10 1875. 2.102-07 1.666-09 1875. 1.007-06 4.937-09 NNE 1829. 1.083 07 18 2') . i.018 09 1R29. 1,693-07 1.582-09 1829. 9.936-07 4.682-09 NE 1585. 9.628-03 15R5. t 062 09 1585. 1.048-07 1.5G2-09 1585. 9.067-07 4.912 09 a ENF 1609. 9.103-09 1234. 1 305-09 1234. 1.741-07 f.769-09 1234. 1.130 06 6.280-09 tD e E 1400. 1.OG7-07 1227. I 787-09 1227. 2.204-07 2.143-09 1227. 1.436-06 7.005-09 d ESE 1400. 1500. 1.06G-07 991. 2 199-09 991. 2.591-07 2.748-09 991. 1006. 1.706-06 9.462-09 h m SE 9.378-09 1006. 1.846-09 1006. 3.791-07 2.589-09 2.623-OG 1.030-08 Z SSE 1500. 7.869-08 ROO. 1.558 O') ROO. 3.376-07 2.176-09 80). 2.622-06 1.146-08 5 1800. 6.317-08 945. 7.539-10 94'i. 1.775-07 1.377-09 945. 1.390-06 7.506-09 SSW 1609. 5.441-08 975. 8.453-10 915. 1.310-07 1.191-09 975. 9.962-07 5.632-09 SW 1609. G.179-08 1067. 9.762-10 1067 1.257-07 1.465 09 1067. 8.619-07 5.159-09 1 WSW 1609. 5.523-08 1212. 7.907-10 1212. 1.244-07 1.310-09 1282. 7.873-07 4.685-09 W 1609. 5.338-08 1989. 7.1R0-10 1189. 1.310-07 1.173-09 1989. 8.107-07 4.424-09 WNW 1400. 5.222-08 1227 8.600-10 1227 1.162-07 1.1R3-09 1227. 7.074 07 3.598-09 NW 1400. 5.652-09 1128. 1.O?R-09 112R. 1.380-07 1.405-09 1128. 8.763 07 4.RO4-09 HNW 1400. R.117-09 1044. 1.591-04 1044, 2.769 07 2.540-09 1044. 1.492-06 a.173-09 i BVRON SITE MFYIOROLOGICAL DATA t/74 - 12/76 i
"The elevated (s tack ) and ground level release data are provided for $
reference purposes only. Routine dose calculations are performed yg using mixed mode (vent) release data. m Approximate distance from midpoint between gaseous effluent release 50 points to location of highest X/Q or D/Q at or beyond the unrestricted 2%H area boundary. e _ m. - . _..-._ _ _ m - _. - _ .
BYRON REVISION 11 ; JUNE 1984 TABLE 7.2-6 (Cont'd) o J BYRON 1&2 l l l AVERAGE WIND SPEEDS FOR EACH RELEASE MODE
^ ^ ( !
DOWNWIND b b DIRECTION ELEVATED MIXED MODE GROUND LEVEL ! c N 7.6 6.6 4.5 NNE 7.4 ' 6.6 4.7 NE 6.8 6.2 4.6 j i ENE 6.5 5.8 4.5 l l E 6.5 5.9 4.5 : 6.3 5.7 4.4 ESE { 4 , SE 6.0 5.4 4.0 ! SSE 6.0 5.2 3.9 l S 5.9 5.2 4.1 i SSW 6.0 5.4 4.0 j 4.6 l SW 6.6 6.0 WSW 6.8 6.2 4.8 ; W 6.7 5.8 4.1 WNW 7.0 6.1 4.2 i NW 7.0 6.0 3.9 l NNW 7.2 6.2 4.2 l a Based on Byron Site Meteorological Data, January 1974 through ; December 1976. bThe elevated and ground level values are provided for reference > purposes only. Routine dose calculations are performed using l the mixed mode values. l 7.2-7 .
/
D f -f } b i T ABLt. 7. 2 -7 D/O AT THE NEAREST MILK COW AND MEAT ANIMAL LOCATIONS WITHIN 5 MILES DOWNWIND NEAREST MitK COW D/O(1/M**2) NEAREST MEAT ANIMAL D/O(1/M**2) DIRECTION RADIUS MIXED GROUND RADIUS ELEVATEg- MIXED GROUNO ELEVATEg REtEASE RELEASh (METERSf RELEASE RELEASE RELEASEb (METERS) RELEASE N 8000. 1.096-10 1.654-10 3.889-10 1900. 9.553-10 1.637-09 4.827-09 NNE 8000. 1.154-10 1.559-10 3.534-10 2600. 6.727-10 9.430-10 2.536-09 NE 3400. 3.974-10 5.217-10 1.306-09 1800 9.298-10 1.320-09 3.956-09 y 6.303-10 7.382-10 2.003-09
. ENE 8000. 9.768-11 1.153-10 2.425-10 2400. g to E 8000. 1.320-10 1.396-10 2.679-10 1900. 1.142-09 1.234-09 3.325-09 g i ESE 5100. 2.606-10 2.858-10 5.593-10 2400. 8.078-10 8.659-10 2.079-09 ,21 C0 SE 5300. 2.142-10 2.4S7-10 5.825-10 2600. 6.320-10 7.250-10 2.016-09 O j "-*
SSE 8000. 8.492-11 8.853-11 2.167-10 2400. 5.458-10 5.505-10 1.789-09 5 3200. 2.047-10 2.643-10 9.242-10 1300. 5.683-10 8.863-10 4.3E7-09 SSW 8000. 5.310-11 5.919-11 1.460-10 2600. 3.063-10 3.337-10 1.048-09 SW 8000. 6.287-11 7.647-11 1.555-10 1400. 7.322-10 1.005-09 3.247-09 WSW 8000, 6.026-11 8.062-11 1.754-10 1400. 6.850-10 1.072-09 3.664-ON W 3100. 2.384-10 3.076-10 8.458-10 3200. 2.269-10 2.929-10 8.006-10 WNW 5300. 1.211-10 1.420-10 2.853-10 2600. 3.586-10 4.207-10 9.875-10 NW 5100. 1.403-10 1.609-10 3.538-10 2300. 4.608-10 5.327-10 1.417-09 NNW 8000. 9.475-11 1.167-10 2.374-10 2400. 6.155-10 7.804-10 1.961-09 8YRON SITE METEOROLOGICAL DATA 1/74 - 12/76 4 4
- Approximate distance from center of plant as determined by annual census.
b The elevated and ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode release data. o c Approximate distance from center of plant per ER Table 0470.2-1 @ (Amendment 2, September 19 81) . to s us WH wO co Z s V < W
m m b TABLE 7.2-8 BYRON 182 MAXIMUM OFFSITF FINITF PLUME GAMMA DOSE FACTORS FOR kR R3M DOWNWIND RESTRICTED FIFVATFD(STACK) RELEASF* MIXFD MODF(VFNT) RELFASF GROUND LEVEL RELEASF* DIRFCTION AREA BOUND RADIUS ** 5 SBAR RADIUS ** V VBAR R AD I US** G GBAR (MFTERS) (MFTERS) (MRAD /YR)/(UCI/SFC) (METERS) (MRAD /yR)/(UCi/SEC) (METFRS) (MRAD /YR)/(UCl/SFC) N 1875. 1875. 1.068 05 9.64R-07 1875. 2.360-05 2.131-06 1875. 1.079-04 9.740 06 NNE 1829. 1829. 1.192-05 1.076-06 1829. 1.901-05 1.716-06 1829. 9.390-05 8.479-06 q NE 1585. 1585. 1.074-05 9.697-07 1585. 1.846-05 1.6G7-06 1585. 9.516-05 8.593 06 III
. ENE 1234. 1234 1.132-05 1.022-06 1234. 2.034-05 1.836-06 1234 1.229-04 1.110-05 N N E 1227, 1227 1.281-05 1.157-06 1227. 2.482-05 2.241-06 1227. 1.536-04 1.387-05 o 1 ESE 991. 991 1.432-05 1.293-06 991. 3.026-05 2.733-06 991. 1.894-04 1.710-05 Z
< SE 1006. 1006. 1.251-05 1.130-06 1006. 4.172-05 3.767-06 1006. 2.811-04 2.539-05 SSE 800. 800. 1.120-05 1.011-06 800. 3.735-05 3.372-06 800. 2.846-04 2.570-05 5 945. 945. 8.389-06 7.575-07 945. 2.134-05 1.927-06 945. 1.568-04 1.416-05 SSW 975. 975. 7.085-OG 6.397-07 975. 1.572-05 1.420-06 975. 1.124-04 1.015-05 SW 1067. 1067 8.135-06 7.346-07 1067. 1.503-05 1.357-06 1067. 9.529-05 8.605-06 WSW 1212. 1212. 6.862-06 G.19G-07 1212. 1.470-O5 1.327-06 1212. 8.648-05 7.809-06 W 1189. 1189. 6.732-06 6.079-07 1989. 1.549-05 1.399-06 1189. 9.002-05 8.129-06 , WNW 1227. 1227. 6.640-OG 5.996-07 1227. 1.360-05 1.228-06 1227. 7.786-05 7.031-06 i NW 1128. 1128. 7.413-06 G.694-07 1128. 1.635-05 1.47G-06 1128. 9.772-05 8.824 06 NNW 1044. 1044, 1.074-05 9.694-07 1044 3.2G5-05 2.948 06 1044, 1.69G-04 1.531-05 BYRON SITE METEOROLOGICAL DATA t/74 - 12/76 c-a :o
*The elevated (stack) and ground level release data are provided for ygN reference purposes only. Routine dose calculations are performed using g mixed mode (vent) release data. eo
** Approximate distance from midpoint between gaseous effluent release $*
points, p y e , , - - - - . - g -- - - - - , , , --, ,
u> d V TABLE 7.2-8 (Cont'd) t BYRON 1&2 MAXIMitM OFFSITE F INT TF Pt UME GAMMA COSF FACTORS FOR KR 85M DOWNWIND RESTRICTED FtEVATFO(STACK) REtEASE* MIXfD MOOFfVENT) RELEASE GROUNO LEVEt. RELEASF* OIRECTION AREA BOUND RADIUS ** S StfA R RADIUS ** V VBAR R A D I U S*
- G GRAR (MFTERS) (MFTFRS) (MRAD /vRl/(UCI/SEC) (METERS) (MRAD /VR)/(UCl/SEC) (METFRS) (MRAD /YR)/(UCI/SFC)
N 1875. 1875. l.731-04 9.137-05 1875. 2.312-04 1.209-04 1875. 6.971-04 3.601-04 NNE 1829. 1829. 1.929-04 1.018-04 1829. 2.179-04 1.143-04 1829. 6.266-04 3.240-04
%J NE 1585. 1585. 1.809-04 9.554-05 1585. 2.117-04 1.111-O4 1585. 6.368-04 3.293-04 b3 1234. ><
- ENE 1234. 1234. 2.207-04 1.168-04 1234 2.318-04 1.259-04 7.650-04 3.948-04 y E ESE 1227.
991. 1227 991. 2.297-04 2.9G4-04 1.214-04 1.569-04 1227. 991. 2 644-04 3.331-04 1.385-04 1.747-04 1227 991. 9.340-04 1.103-03 4.814-04 5.681-04 h Z p O SE 1006. 1006. 2.697-04 1.428-04 1006. 3.675-04 1.917-04 1006. 1.569-03 8.060-04 SSE 800. ROO. 2.787-04 1.478-04 800. 3.457-04 1.80G-04 800. 1.498-03 7.684-04 5 945. 945. 2.116-04 1.122-04 945. 2.348-04 f.232-04 945. 8.918-04 4.589-04 SSW 975. 975. 1.668-04 8.844-05 975. 1.800-04 9.449-05 975. 6.584-04 3.392-04 i SW 1067. 1067. 1.795-04 9.508-05 1067. 1.803-04 9.473-05 1067. 5.698-04 2.937-04 WSW 1212. 1282. 1.345-04 7.119-05 1212. 1.579-04 8.27G-05 1212. 5.225-04 2.694-04 W 1189. 1189. 1.363-04 7.215-05 1189. 1.653-04 8.663-05 1189. 5.437-04 2.803-04 WPN 1227 1227. l.280-04 G.773-05 1227. 1.442-04 7.557-05 1227. 4.705-04 2.426-04 i NW 1128. 1128. 1.468-04 7.767-05 1128. 1.693-01 8.868-05 1128. 5.778-04 2.977-04 NNW 1044 1044. 2.172-04 1.149-04 1044, 2.891-04 1.509-04 1044. 9.390-04 4.827-04 RYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 C.a C Z t4 H vs
*The elevated (stack) and ground level release data are provided for es reference purposes only. Routine dose calculations are performed using mixed mode (vent) release data.
$0
** Approximate distance from midpoint between gaseous effluent release Y points.
i 1
/m p ,a
< TABLE 7.2-8 (Cont'd) BYRON 1&2 l MAXIMUM OFFSITE FINITF PLUMF GAMMA DOSF FACTORS FOR KR AS DOWNWIND RESIRICTfD FI FVATFD( ST ACK ) Rf t F A%F
- MIXFD MODE (VINT) RFtFASF GROtJNO t. FVE L RFLEASF*
DIRFCTION AREA BOUNO RADIUS ** 5 58AR R ADIUS ** V Vf3 A R RADIUS ** G GBAR a (MFTERS) (METER 9) ( MR AD/Y R ) / t IJC I /SF C ) (MFTERS) (MRAD /YR)/(UCI/SFC) (METERS) (MRAD /YR)/(UCI/SEC) N 1975. 1875. 2.036-06 1.260-06 1875. 2.723-06 1.686 06 1875. 7.846-06 4.857-06 t!NE 1829. 1829. 2.270-06 1.405-06 1829. 2.598-06 f.608-06 1829. 7.093-06 4.390-06 NE 1585. 1585. 2.140-06 1.325-06 1585. 2.532-06 1.5G8-06 1585. 7.221-06 4.470-06 W ) q e ENE 1234. 1234. 2.612-06 f.687-06 1234. 2.865-06 1.773-06 1234. 8.564-06 5.309-06 f%) E 1227. 1227. 2.712-06 1.678-06 1227. 3.151-06 1.951 06 1227. 1.050-05 6.502-06 o FSE 991. 991. 3.523 06 2.181-06 C91. 3.971-06 2.458-06 991. 1.222-05 7.566-06 z SE 1006. 9006, 3.204-06 1.983-06 1006. 4.330-06 2 680-06 1006. 1.749-05 1.082-05 g 800, 1.654-05 1.024-05 l SSE 800. 800. 3.322-06 2.057-06 800. 4.080 06 2.526 06 5 945. 945. 2.530-06 1.566-06 945. 2.79G-06 1.730-06 945. 9.827-06 6.083-06 SSW 975. 975. 1.989-06 1.231-06 975, 2.145-06 1.328-06 975. 7.266-06 4.498-06 ' SW 1067. 1067. 2.130-06 1.318-06 1067. 2.148-06 1.329-06 1067. 6.312-06 3.907-06 WSW 1212. 1282. 1.585-06 9.814-07 1212. 1.860-06 1.151-06 1212. 5.812-06 3.597-06 W 1189. 1189. 1.619-06 1.002-06 1189. 1.960-06 1.213-06 1189. 6.043-06 3.741-06 wtN 1227. 1227. 1.513-06 9.366-07 1227. 1.709-06 1.057-06 1227. 5.251-06 3.250-06 NW 1128. 1128. 1.733-06 1.073-06 1128. 1.999-06 1.238-06 1128. 6.410-06 3.968-06 NNW 1044. 1044. 2.568-06 1.590-06 1044. 3.374-06 2.089-06 1044. 1.032-05 6.390-06 BYRON SITE METEOROLOGICAL DATA t/74 - 12/76 E-s I C l z
*The elevated (stack) and ground level release data are provided for M5 reference purposes only. Routine dose calculations are performed using [$
mz . mixed mode (vent) release data.
- I ** Approximate distance from midpoint between gaseous effluent release r H
points. ) 1 l
p ,, (wJ I b-(v) TABLE 7.2-8 (Cont'd) BYRON 142 MATIMilM OFFSITF FINffE PtUME GAwun DOSF rACTORS FOR kR 87 OOWNWIND RESTRICTED FtEVATFDfSTACw) RFLFASF* MivfD MODF(VFNT) RFtFASE GROUND LFVFt. RFLEASE DigrCTION AREA BOUND RADIUS ** S SBAR RADIUS"" V VBAR RADIUS ** G GRAR (METERS) (METERS) ( MR AD / Y R ) /( UC I / SE C ) (METERS) (MRAD /VR)/(UCI/SFC) (METERS) (MRAD /YR)/(UCI/SEC) N 8875. 1875. 5.961-04 4.327-04 1875. 7.713-04 5.596-04 1875. 2.020-03 1.459-03 NNE 1829. 1829. 6.620-04 4.806-04 1829. 7.400-04 5.417-04 1829. 1.807-03 1.305-03 4 NE 1585. 1585. 6.270-04 4.551-04 1585. 7.268-04 5.278-04 1585. 1.848-03 1.335-03 t2
- ENE 1234. 1234 7.768-04 5.640-04 1234, 8.465-04 6.151-04 1234. 2.256-03 1.629-03 N E
ESE 1227. 999. 1227 991. 8.045-04 1.053-03 5.841-04 7.646-04 1227. 999. 9.119-04 1.178-03 6.623-04 8.562-04 1227. 991. 2.713-03 3.265-03 f.958-03 2.357-03 h l4 g 9 SE 1006. 1006. 9.613-04 6.9RO-04 1006. 1.248-03 9.055-04 1006. 4.539-03 3.277-03 SSE 800. 800. 1.005-03 7.299-04 800. 1.214-03 8.819-04 800. 4.446-03 3.209-03 5 945. 945. 7.550 04 5.4R2-04 945. R.365-04 6.079-04 945, 2.654-03 1.916-03
%SW 975. 975. 5.964-04 4.330-04 975. 6.421-04 4.666-04 975. l.964-03 1.418-03 SW 1067. 1067. G.340-04 4.619-04 1067. 6.471-04 4.703-04 1067, 1.696-03 1.225-03 WSW 1212. 1282. 4.785-04 3.474-04 1282. 5.538-04 4.021-04 1212. 1.555-03 f.123-03 W 1989. 1189. 4.779 04 3.469-04 1189. 5.759 04 4.182-04 1189. 1.620-03 1.170-03 WNW 1227. 1227 4.526 04 3.286-04 1227. 5.040-04 3.660-04 1227. 1.388-03 1.002-03 NW 1928. 1128. 5.203-04 3.778-04 8128. 5.944-04 4.316-04 1128. 1.723-03 1.244-03 NNW 1044. 1044 7.732-04 5.614 04 1044. 9.980-04 7.242-04 1044. 2.811-03 2.029-03 BVRON SITE METEOROLOGICAL DATA t/74 - 12/76 c.4 se c trj z <:
*The elevated (stack) and ground level release date are provided for MH reference purposes only. Routine dose calculations are performed using e0 mixed mode (vent) release data. g@
a
** Approximate distance from midpoint between gaseous effluent release points. e
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f) ( p k) V) U TABLE 7.2-8 (Cont'd) BYRON 182 MAM1 MUM OFFSITF FINITF PttlME GAMMA DOSF FACit)RS FOR kR 89 DOWNWIND RESTRICTFD t t FVATFD( ST ACK ) RFLEASF* MIXFD MOOF1VFN1) RFtFASF CROUNO LEVFL RFtEASF* DIRECTION AREA BOUND R ADIUS ** S SBAR RADIUS ** V VBAR RADIUS ** G GBAR i (METERS) (MFTFRS) (MRAD /vR)/(UCI/SEC) (METFRS) ( MR A D / Y R ) / ( tsC I / SE C ) (METERS) (MRAD /YR)/(UCf/SEC) N 1875. 1875. 4.111-04 3.010-04 1875. 4.062-04 2.974-04 1875. 5.990-04 4.364-04 NNE 1829. 1829. 4.422-04 3.237-04 1829. 4.105-04 3.007-04 1829. 5.406-04 3.939-04 y NE 1585. 1585. 4.341-04 3.178-04 1585. 4.221-01 3.093-04 1585. 6.219-04 4.532-04 tIf e FNE 1234. 1234. 6.185 04 4.529-04 1234 5.854-04 4.292-04 1234. 9.721-04 7.080-04 K M E 1227, 1227. 6.462-04 4.731-04 1227. 5.8R3-04 4.313-04 1227. 1.008-03 7.343-04 W
' ESE 991. 991. 9.327-04 6.830-04 991. 8.83R-04 6.4R2-04 991. 1.599-03 1.165-03 b $ SE SSE 1006.
800. 1006. 800. S.489-04 9.994-04 6.216-04 7.319-04 1006. 800. 8.017-04 9.545-04 5.923-04 7.001-04 1006. 800. 1.616-03 2.238-03 1.177-03 1.630-03 5 945. 945. G.409-04 4.693-04 945. 6.336-04 4.646-04 945. 1.433-03 1.043-03 SSW 975. 975. 5.305-04 3.885-04 975. 4.9?9-04 3.622-04 975. 1.049-03 7.640-04 SW 1067. 10G7. 5.759 04 4.217-04 1067. 5.305-04 3.889-04 1067. 8.888-04 6.473-04 WSW 1212. 1212. 4.259-04 3.118-04 1212, 4.363-04 3.196-04 1212. 7.908-04 5.759-04 W 1189. 1189. 3.744-04 2.742-04 1189. 3.891-04 2.851-04 1189. 7.491-04 5.455-04 WNw 1227. 1227. 3.884-04 2.844-04 1227. 3.632-04 2.662-04 1227. 5.733-04 4.176-04 NW 1128. 1928, 4.680-04 3.427-04 1128. 4.492-04 3.292-04 1128. 8.016-04 5.839-04 NNw 1044 1044. 7.275-04 5.327-04 1044 7.938-04 5.812-04 1044. 1.573-03 1.145-03 . BYROH SITE METEOROLOGICAL DATA 1/74 - 12/76 i c4 C z
*The elevated (stack) and ground level release data are provided for M$
reference purposes only. Routine dose calculations are performed using [g mixed mode (vent) release data. cm z
** Approximate distance from midpoint between gaseous effluent release g points.
-s I [%)
( V) '(_/ I, TABLE 7.2-8 (Cont'd) l BYRON 1Fw 2 4 NATIMllM OFF",ITF FINilf PLtlMF GAMMA DOSF FACTORS FOR KR 00 i DOWNWIND RFSTRICTED ELFVAtFDISTACKl RELEASF* MIXFD MODE (VENT) RFLfASE GROUND LFVEL RFLEASE* DIRFCTION AREA COUND RADIUSMN 5 SBAR RADIUS *2 V VRAR RADIUS ** G GBAR .i (MFTERSS (MFTFRS) ( MR AD/ V R ) /( UC I / S F C ) (MFTERS) (MRAD /vRl/lUCI/SFC) (MFTFRS) ( MR AD/ Y R ) /( UC I / 5F C ) j N 1875. 1875. 1.125-05 7.999-06 1875. 7.479-06 5.312-06 1875. 4.324-06 3.054-06 1 NNE 1829. 1829. 1.194 05 8.481-06 1829. 8.361-06 5.945-06 1829. 5.383-06 3.802-06 q NE 1585. 1585. 1.460-05 1.038-05 1585. 1.163-05 R.268-06 1585. 9.069-06 6.405-OG tgf a . ENE 1234 1234. 3.604-05 2.562-05 1234. 2.752-05 1.957-05 1234. 2.745-05 1.938-05 >< N E 1227. 1227. 4.020-05 2.857-05 1227. 3.081-05 2.190-05 1227. 3.305-05 2.334-05 W l 8 ESE 991. 991. 8.655-05 6.154-05 991. 6.939-05 4.938-05 998. 7.290-05 5.146-05 O SE 1006, 1006. 6.896-05 4.903-05 1006. 5.360-05 3.814-05 1006. 6.719-05 4.743-05 [ SSE 800. POO. 1.246-04 8.864-05 800. 9.173-05 6.532-05 800. 1.368-04 9.654-05 i 5 945. 945. 5.623-05 3.999-05 945. 4.379-05 3.117-05 945. 6.024-05 4.250-05 SSW 975. 975. 4.486-05 3.190-05 975. 3.367-05 2.396-05 975. 3.851-05 2.717-05 SW 1067. 1067. 4.947-05 3.517-05 1067. 3.940-O5 2,800-05 1067. 3.895-05 2.749-05 WSW 1212. 1212. 2.878-05 2.046-05 1212. 2.504-05 1.779-05 1212. 2.607-05 1.840-05 W 1989, 1989. 2.728-05 1.939-05 1989. 2.031-05 1.445-05 1989. 1.678-05 1.184-05 WNW 1227. 1227 2.812-05 1.999-05 1227. 1.958-05 1.393-05 1227. 1.374-05 9.700-06 NW 9128, 1128. 3.999-05 2.844-05 1128. 2.696-05 1.919 05 1128. 1.820-05 1.285-05 t#JW 1044. 1044. 7.876-05 5.601-05 1044. 5.964-05 4.241-05 1044 4.889-05 3.450-05 BYRON SITE METEOROLOGICAL OATA t/74 - 12/76 I 4m Cg
*The elevated (stack) and ground level release data are provided for $H reference purposes only. Routine dose calculations are performed using g$
mixed mode (vent) release data. gg
** Approximate distance from midpoint between gaseous effluent release a.
i points. p l 1 i _ _ _ . ~ _. - -- , . _. ,_
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p p n TABLE 7.2-8 (Cont'd) BVRON 142 MA X Iestris or F S I T E FINTTF PLUME CAesetA DOSF FACTORS FOR XT133M DOhNWIND RESTRICTED ftFVAffD($ TACK) RFt E ASE
- MIurD MOOfivfNT) RELEASF GROUND LEVEL. REtFASE*
DIDFCTION AREA BOUNO R Au l us ** 5 5840 R A o l us*
- V VBAR RADIUS #2 G C5AR (METFRSD IMFTERS) (MRAD /VRl/(UCI/SECD (METER %) (MRAD /vRB/(UCI/SFC) (MfTERS) (MRAD /YR)/(UCI/SFC)
N 1875. 1875. 3.363-05 9.394-05 1875 5.333-05 1.932-05 1875. 1.943-04 6.183-05 NNE 1829. 1929. 3.752-05 1.556-05 1829. 4.741-05 f.800-05 1829. 1.731-04 5.493 05 NE 9585. 1595. 3.478-05 1.454-05 1585. 4.620-n5 9.750-05 1585. f.752-04 5.574-05 tIf g >< ENE *234. 1234 4.075-05 t.757-05 1234. 5.t42-05 1.967-05 1234. 2.145-04 6.680-05 1227. 2.676-04 8.228-05 W M E 8227. 8227. 4.338-05 1.836-05 1227. 5.919-05 2.194-05 2.740 05 991. 3.175-04 9.660-05 h y ESE SE 998. 1006. 991. t006. 5.398-05 4.868-05 2.352-05 2.135-05 999. 1006. 7.295-05 8.827-05 3.089-05 1006. 4.672-04 9.392-04 800. 800. 4.869-05 2.190-05 800. 8.037-05 2.878-05 800. 4.516-04 1.323-04 SSE 945. 945. 3.706-05 t.669-05 945, 5.I19-05 9.927-05 945. 2.580-04 7.798-05 5 5.737-05 975. 975. 2.955-05 9.387-05 975. 3.875-05 1.474-05 975. 1.877-04 SSW 4.964-05 SW 1067. 1067. 3.218-05 1.419-05 1067. 3.809-05 9.469-05 10G7. 1.613-04 1292 1292. 2.468-05 1.066-05 1252 3.466-05 1.296-05 1212. f.476-04 4.555-05 l wSW 4.735-05 W 1189. 1989. 2.505-05 1.086-05 1989. 3.649-05 1.362-05 1989. 1.532-04 1227. 1227. 2.368-05 1.018-05 1227. 3.t90-05 9.18R-05 1227. 1.334-04 4.194-05 WNw NW 1928. 1928. 2.695-05 t.165-05 1928. 3.763-05 1.394-05 1128. 1.645-04 5.042-05 NNw 1044. 1044. 3.966-05 1.722-05 1044. 6.793-05 2.403-05 1044. 2.741-04 8.213 05 l BvROta SITE METEOROLOGICAL DATA t/74 - 12/7G C4 C 2
*The elevated (stack) and ground level release data are provided for tsi g reference purposes only. Routine dose calculations are performed using g mixed mode (vent) release data, mz
** Approximate distance from midpoint between gaseous effluent release g H
points.
U V V t TABLE 7.2-8 (Cont'd) BvRON t&2 l MaulMues OrFSITF F INITE Pitmet GAMetA Dost F ACTORS F OR nr133
- DOWNW190 RESTRICTED _Ft FV A f f DI ST AcaC l RftEASF* MIufD MODElvfNil RFLEA%F GROUND LEVEL RELFASE*
l Di cEf T IOmf ARE A 80UDO RADIUS ** 5 5BAR R AD I US*
- V VBAR RADIUS ** G GBAR t esF T E RS ) (METERS) (esRAD/vRl/fuCI/SECB (MffFRS) (MRAD /vRl/fuCI/SEC) (METERS) (MRAD /VRl/(UCI/SEC)
N 1875. 1875. 3.840-05 1.340 05 1875. 5.*t39-05 9.898-05 1875. 2.794-04 6.492-05
; NNE 1929. 1829. 4.286-05 9.49G-05 1829 5.269-05 1.731-05 1829. 1.959-04 5.833-05
-4 NE 1585. 1585. '3.998-05 f.400-05 1585. 5.143-05 1.689-05 1585. f.984-04 5.917-05 tIf 1.686-05 1234. 5.67t-05 1.869-05 1234. 2.420-04 7.I19-05 K
- ENE 1234 1234. 4.709-05 E 1227. 1227. 4.980-05 t.764-05 1227. 6.529-05 2.tt1-05 1227. 3.006-04 8.769-05 [
p ESE 991. 991. 6.263-05 2 259-05 991. 8.019-05 2.6tt-05 999. 3.550-04 f.028-04 g " <D SE 1006. tOO6. 5.653-05 2.049-05 1006. 9.677-05 3.085-05 1006. 5.192-04 1.482-04 SSE 800. 800. 5.700-05 2.099-05 800. 8.759-05 2.759-05 800. 4.987-04 1.406-04 . 5 945. 945. 4.348-05 1.603-05 945. 5.614-05 1.829-05 945. 2,878-04 8.294-05 i SSW 975. 975. 3.458-05 1.266-05 975. 4.257-05 f.397-05 975. 2.102-04 6.104-05 SW 1067. 1067. 3.747-05 1.3G2-05 1067 4.193 05 1.383-05 1067 1.812-04 5.290-05 1 1212. 1.660-04 4.857-05 j WSW 1212. 1212. 2.855-05 1.024-05 1212. 3.836-05 1.248-05 W 1189. 1189. 2.893-05 1.042-05 1189. 4.030-05 1.3G9-05 1989. 1.724-04 5.046-05 j
' W9W 9227. 1227. 2.729-05 9.752-06 1227. 3.529-05 1.145-05 1227. 1.500-04 4.385-05 NW 1128. 1128, 3.111-05 1.116-05 1928. 4.149-05 1.341-05 1128. f.843-04 5.362-05 NNW 1044. 1044. 4.589-05 1.650-05 1044 7.478-05 2.349-05 1044 3.053-04 8.751-05 l ) ! RVRON SITE MFTEOROLOGICAL DATA t/74 - 12/7G 1
- C4 i C i j
*The elevated (stack) and ground level release data are provided for Es J reference purposes only. Routine dose calculations are performed using J eo mixed mode (vent) release data.
I ** Approximate distance from midpoint between gaseous effluent release f* l points. p t i l f i
% p s %) U TABLE 7.2-8 (Cont'd)
BVRON 1&2 MatIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XEt35M , DowtNIND RESTRICTfD ftfVATEDISTACM) RFt F ASF
- MIXFD MOOF(VFNT) RflFASF GROUfJD L EVE L RFtFASF*
DIRFCT10N AREA B00f40 RADluS** 5 SBAR R AD I US *
- V VBAR RADIUSA* G GHAR (MFTERS) IMFIFRS) ( MR AD/ V R l / ( Ui /SF C I (METERS) ( MR AD/ Y R )/ ( UC I /SF C ) (METERS) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. 2.796-04 f.722-04 1875. 3.384-04 2.079-04 1875. 8.143-04 4.977-04 NNE 1829. 1829. 3.068-04 1.890-04 1829. 3.264-04 2.007-04 1829. 7.058-04 4.315-04 4 NE 1585. 1585. 2.939-04 f.811-04 1585. 3.169-04 1.949-04 1585. 7.313-04 4.472-04 tIf 1234. 3.860-04 2.375-04 9.739-04 5.951-04 >4
- ENE 1234. 1234. 3.759-04 2.318-04 1234.
E 1227. 1227 991. 3.865-04 5.161-04 2.382-04 3.183-04 1227. 991. 4.000-04 5.411-04 2.460-04 3.329-04 1227. 991. 1.093-03 1.468-03 6.676-04 8.960-04
$gg
- p. ESE 991.
e SE 1006. 100G. 4.750 04 2.930-04 1006. 5.507-04 3.383-04 1006. f.848-03 1.127-03 SSE 800. 800. 5.132-04 3.167-04 800. 5.734-04 3.523-04 800. 2.056-03 f.254-03 5 945. 945. 3.696-04 2.275-04 945. 3.920-O4 2.411-04 945. 1.245-03 7.597-04 SSW 975. 975. 2.949-04 1.820-04 975. 3.006-04 f.849-04 975. 9.205-04 5.619-04 SW 1067. 1067. 3.176-04 f.959-04 1067. 3.096-04 t.905-04 10G7. 7.812-04 4.771-04 WSW 1212. 1212. 2.419-04 1.492-04 1212, 2.676-n4 8.645-04 1212. 7.102-04 4.338-04 W 1189. 1989. 2.263-04 1.39G-04 1189. 2.643-04 v.625-04 1189. 7.371-04 4.502-04 wfN 1227. 1227. 2.227 04 1.373-04 1227. 2.357-04 8.449-04 1227. 6.060-04 3.700-04 NW 1128. 1128. 2.585-04 1.594-04 ft28. 2.829-04 f.739-04 1128. 7.847-04 4.791-04 NNW 1044. 1044. 3.874-04 2.390-04 1044 4.800-04 2.984-04 1044 1.358-03 8.285-04 i BvRON SITE METEOROLOGICAL DATA 1/74 - 12/76 e c.a C z
*The elevated (stack) and ground level release data are provided for mg reference purposes only. Routine dose calculations are performed using gg
! mixed mode (vent) release data, co z
** Approximate distance from midpoint between gaseous effluent release "g points. H
, . - c- r, , - - -
/7 /~ G k)T TABLE 7.2-8 (Cont'd)
RfRON t&2 MAXIMUM OFFSifF FINITE PLUME GAMMA DOSF Fact 0RS FOR XF135 OOWFNI ND RESTRICTED FLEVATFDISTACKl RFLEASF* MIXfD MODE (VENT) RFtEASF GROUND LEVEL RFLFASF* OTRFCTION ARFA BOUND RADIUS ** S SBAR R AO ! U 9t
- V VBAR RADIUS #R G GBAR (METFRS) (METERSI (NRAD/vR)/luCI/SFC) (MFTERS) IMRAD/)R)/fUCl/SEC) (MFTFRS) (MRAO/YR)/(UCI/SFC)
N 1875. 1875. 2.405-04 1.297-04 1873. 3.197-04 1.721-04 1875. 9.558-04 5.129-04 NNE 1829. 1929. 2.689-04 1.44G-04 1829. 3.023-04 1.628-04 1829. 8.615-04 4.624-04 NE 1585. 1585. 2.515-04 1.356-04 1585. 2.937-04 1.5R2-04 1585. 8.750-04 4.697-04 W . Q N
- ENE 1234 1234. 3.067-04 1.655-04 1234. 3. ~121 - 04 1.799-04 1234. 1.044-03 5.601-04 M E 1227. 1227. 3.190-04 f.721-04 1227.
991. 3.6G1-04 4.604-04 1.972-04 2.480-04 1227. 991. 1.277-03 1.499-03 6.849-04 8.037-04 h Z y ESE 991. 999. 4.121-04 2.224-04 o SE 1006. 1006. 3.749-04 2.024-04 1006. 5.064-04 2.724-04 100G. 2.135-03 1.144-03 SSE 800. 800. 3.875-04 2.092-04 800. 4.754 04 2.5d9-04 800. 2.025-03 1.085-03 S 945. 945. 2.94R-04 1 591-04 945. 3.243-04 1.747-04 945 1.208-03 6.479-04 SSW 975. 975. 2.322-04 1.253-04 975. 2.488-04 1.340-04 975. 8.930-04 4.789-04 SW 1067 1067. 2.495-04 1.347-04 TOG 7 2.492-04 1.343 04 1067. 7.741-04 4.152 04 WSW 1212. 1212. 1.866-04 1.007-04 1212. 2.176-04 1.172-04 1212. 7.108-04 3.813-04 W 1189. 1189. 1.898-04 1.024-04 11R9. 2.283-04 1.230-04 1989. 7.393-04 3.966-04 WNW 1227. 1227 1.778-04 9.593-05 1227. 1.991-04 1.072-04 1227. 6.410-04 '.439-04 NW 1123. 1128. 2.038-04 1.100-04 1928. 2.333-04 1.257-04 1928. 7.849-04 4.210-04 NNW 1044 1044. 3.015-04 1.627 04 1044. 3.966-04 2.134-04 1044. 1.270-03 6.806-04 OtRON SITE METEOROLOGICAL DATA t/74 - 12'76 C.a C z
*The elevated (stack) and ground level release data are provided for "$
1 reference purposes only. Routine dose calculations are performed using mixed mode (vent) release data. mz i ** Approximate distance from midpoint between gaseous effluent release "r H points.
(m \ t p >p> LJ \ \J t TABLE 7.2-8 (Cont'd) BVRON 142 MAv.IMUM OFFSITE FINITF PLUME GAMMA DOSF FACTORS FOR XE137 DOwtN I ND RESTRICTFD FI FV At FD(ST ACk t RE LE ASE
- MINFD MODF(VENTI RELEASF GROUND LEVEL RELEASF*
DIRFCTION AR!A BOUND RADIUSSR S 5BAR RADIUS ** V VBAR RADIU5NX G GP.AR (MFTERS) (MFIFRS) (MRAD /vRl/fuCf/SFC) (MFTERS) ( MR AD/ YR ) / d OC I /SE C ) (METERS) (MRAD /YR)/(UCI/SFC) N 1875. 1875. 6.446-05 4.157-05 1875. 6.532-05 4.251-05 1875. 1.103-04 7.093-05 NNE 1829. 1829, 6.951-05 4.483-05 1829. 6.574-05 4.241-05 1829, 9.777-05 6.288-05 q NE 1585. 1595. 6.795-05 4.382-05 1585. 6.656-05 4.294-05 1585. 1.097-04 7.055 05 tIf e ENE 1234. 1234. 9.459-05 6.101-05 1234. R.954-05 5.779-05 1234. 1.663-04 1.OG9-04 >< M E 1227. 1227. 9.829-05 6.335-05 1227. 8.967-05 5.787-05 1227. 1.718-04 1.105-04 W p ESE SE 991. 1006. 991. 1006. 1.392-04 1.274-04 8.980-05 8.220-05 991. 1006. 1.318-04 1.2 0-04 R.509-05 7.874-05 991, 1006. 2.672-04 2.747-04 1.718-04 1.766-04 h SSE 800. 800. 1.477-08 9.525-05 800. 1.41G-04 9.140-05 800. 3.742-04 2.405-04 S 945. 945. 9.657-05 6.229 05 945. 9.542-05 6.158 05 945. 2.396-04 1.540-04 SSW 975. 975. 7.956-05 5.131-05 975. 7.40G-05 4.780-05 975. 1.762-04 1.133-04 SW 10G7. 10G7. 8.635-05 5.570-05 1067. 7.444-05 5.126-05 1067. 1.488-04 9.566-05 WSW 1212. 1212. G 460-05 4 167 05 1212. 6.650-05 4.290-05 1212. 1.335-04 8.585-05 W 1189. 0189. 5.686-05 3.667-05 1189. 6.009 05 3.876-05 1989. 1.295-04 8.323-05 WNW 1227. 1227. 5.870-O5 3.786-05 1227. 5.565-05 3.591-05 1227. 9.980-05 6.416-05 NW 1128. 1128. 7.014-05 4.524-05 1128. 6.848-05 4.418-05 1128. 1.380-04 8.876-05 NNW 1044. 1044. 1.081-04 6.974-05 1044 f.210-04 7.804-05 1044. 2.661-04 1.711-04 RvRON SITE METEOROLOGICAL DATA t/74 - 12/76 Q C z trJ H
*The elevated (stack) and ground level release data are provided for m reference purposes only. Routine dose calculations are performed using mixed mode (vent) release data.
$5 g2
** Approximate distance from midpoint between gaseous effluent release e points. "
o m 4 TABLE 7.2-8 (Cont'd) BYRON 152 MAXIMUM OFFSITF FINIT[ PtOME GAMMA 00%F F ACTORS F OR XFt3R DOWfMIND RESTRICTED FtFVATEDESTACKl REL E ASF
- Mi>FD MODE (VfNT) RELEASF GROUND LEVEL RELEASE DIRFCTION ARE4 BOUND RADIUS"" 5 SBAR RADIUS ** V VRAR RADIUS ** G G8AR IMFTER%t (METERS) IMRAD/VRl/(UCt/SEC) (MFTERS) (MRAD /YRl/(UCt/SFCI (METERS) (MRAD /YR)/(UCt/SFC) i N 1875. 1875. 6.240 04 4.500-04 1875. 7.439-04 5.360-04 1875. 1.674-03 1.19R-03 NNE 1829. 1R29, 6.84t-04 4.933-04 1829. 7.254-04 5.233-04 1829. 1.453-03 1.040-03 4 NE 1585. 15AS. 6.543-04 4.719-04 1585. 7.055-04 5.091-04 1585. 1.503-03 1.076-03 tIf
- FNE 1234. 1234 8.415-04 6.071 04 1234 8 . e'.9 3 - 04 6.27R-04 1234 2.004 03 1.434-03 K E 1227. 1227. S.652-04 6.242-04 8.362-04 1227.
999. 8.955-04 9.220-03 6.465-04 8.809-04 1227. 999. 2.238-03 3.025-03 1.601-03 2.163-03 y ESE 99f. 991. 1.159-03 Z u SE 1006. 1006. 1.067-03 7.703-04 1006. f.224-03 8.832-04 1006. 3.766-03 2.693-03 SSE 800. 800. 1.155-03 8.336-04 800. 1.2n8-03 9.298-04 800. 4.217-03 3.014-03 ) S 945. 945. 8.264-04 5.965-04 945. 8.839-04 6.382-04 945. 2.567-03 1.835-03 SSW 975. 915, 6.624-04 4.782-04 975. 6.789-04 4.903-04 975. l.901-03 1.359-03 SW 1067. 1067 7.136-04 5.150-04 1067. 7.000 04 5.055-04 1067 1.613-03 1.154 03 WSW 1212. 1212. 5.430-04 3.917-04 1212. 5 991-04 4.322-04 1212. 1.466-03 1.048-03
- W 1189. 1989. 5.063-04 3.653-04 1189. 5.893-04 4.251-04 1189. 1.520-03 1.087-03
! WNW 1227. 1227. 4.997-04 3.605-04 1227. 5.270-04 3.802-04 1227. 1.246-03 8.911-04 ) NW t128. I128. 5.810-04 4.192-04 1128. 6.331-04 4.568-04 1128. 1.622-03 t.160-03 NNW 1044. 1044. 8.715-04 6.290-04 1044 1.077-03 7.764-04 1044. 2.807-03 2.007-03 BVRON SITE METEOROLOGICAL DATA t/74 - 12/76 r C gg
*The elevated (stack) and ground level release data are provided for
! reference purposes only. Routine dose calculations are performed using m , mixed mode (vent) release data. 55
** Approximate distance from midpoint between gaseous effluent release points.
ZZH w
O O O i l TABLE 7.2-8 (Cont'd) ) BYRON 182 MAuIMUM OFF%ITE FINITE PtUME CfMMA DOSE FACTOR % FOR AR 41 i DOWW IND RESTRICTED ELEVATED (STACK) RELEASE
- MIXED MODE (VFNT) RELEASE GROUND LEVEL RELEASE
- OIRFCTION AREA BOUND RADIUS ** 5 SBAR RADIUS ** V VRAR RADIUS ** G GHAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METER %) (MRAD /vR)/tUCI/SEC) (METERS) (MRA3/YR)/(UCI/SEC)
N 1875. f875. 9.166 04 6.462-04 1875. 1.194-03 8.420-04 1875. 3.209-03 2.262-03 NNF 1829. 1829. 1.019-03 7.187-04 1829. 1.851-03 8.116-04 1829. 2.878-03 2.029-03 4 NE 1585. 1585. 9.617-04 6.780-04 1585. 1.121-03 7.903-04 1585. 2.936-03 2.070-03 W 2
- ENE 1234. 1234 1.186-03 8.362-04 1234. 1.299-03 9.155-04 1234 3.564-03 2.512-03
{ E 1227. 1227. l.232-03 1.602-03 8.687-04 1.130-03 1227. 991. 1.406-03 1.808-03 9.914 04 1.274-03 1227. 991. 4.311-03 5.133-03 3.039-03 3.619-03 h Z j u ESE 991. 991. j t.J SE 1006. 1006. 1.460-03 1.029-03 1006. 1.929-03 1.360-03 1006. 7.203-03 5.078-03 i SSE 800. 800. 1.517-03 1.069-03 800. 1.861-03 1.313-03 800, 6.975-03 4.917-03 S 945. 945. 1.145 03 8.072-04 945. 1.281-03 9.034-04 945, 4.157-03 2.930-03 SSW 975. 975. 9.040 04 6.373-04 975. 9.832-04 6.938-04 975. 3.076-03 2.168-03
; SW 1067. 1067. 9.698-04 6.837-04 1067. 9.888-04 6.971-04 1067. 2.663-03 1.877-03
) WSW 1212. 1212. 7.269-04 5.125-04 1212. 8.472-04 5.973-04 1212. 2.445-03 1.724-03 W 1989. 1989. 7.302-04 5.148-04 1189. 8.847-04 6.237-04 1189. 2.547-03 1.795-03 l WNW 1227. 1227. 6.903-04 4.867-04 1227. 7.726-04 5.447-04 1227. 2.190-03 1.544-03 i NW 1128. 1928. 7.918-04 5.582-04 1928. 9.099-04 6.415-04 1128, 2.705-03 1.907-03 < NNW 1044 1044 t.175-03 8.284-04 1044. 1.530-03 1.078-03 1044. 4.395-03 3.099-03 i
- BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76
) c4 i C i *The elevated (stack) and ground level release data are provided for $s j reference purposes only. Routine dose calculations are performed using gy j mixed mode (vent) release data. eo j ** Approximate distance from midpoint between gaseous effluent release I* ] points. p i 1
REVISION 11 JUNE 1984 W O
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BYRON REVISION 11 j JUNE 1984 ; (3/
% I ODCM TABLE OF CONTENTS FOR BYRON SECTION 8.0 PAGE 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID LFFLUENT MONITOR .
ALARM AND TRIP SETPOINTS, AND ENVIRONMENT--- RADIOLOGICAL MONITORING 8.1-1 l 8.1 GASEOUS RELEASES 8.1-1 8.1.1 System Design 8.1-1 8.1.1.1 Gaseous Radwaste Treatment System 8.1-1 8.1.1.2 Ventilation Exhaust Treatment System 8.1-1 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Station Vent Stack Monitors 8.1-3 8.1.4 Containment Purge Effluent Monitors 8.1-4 8.1.5 Gas Decay Tank Monitors 8.1-5 8.1.6 Allocation of Effluents from Common Release Points 8.1-6 ! 8.1.7 Symbols Used in Section 8.1 8.1-7 i 8.1.8 Constants Used in Section 8.1 8.1-8 i 8.2 LIQUID RELEASES 8.2-1 [ (_ / 8.2.1 System Design 8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Liquid Radwaste Effluent Monitor 8.2-3 8.2.4 Station Blowdown Monitor 8.2-4 l 8.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors 8.2-5 8.2.6 Administrative and Procedural Controls for Radwaste Discharges 8.2-6 8.2.7 Determination of Initial Dilution Stream l Flow Rates 8.2-6 8.2.8 Allocation of Effluents from Common Release Points 8.2-7 l 8.2.9 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 h O 8-1 I
i BYRON REVISION 11 l JUNE 1984 O ODCM LIST OF TABLES FOR BYRON SECTION 8.0 l i I NUMBER TITLE PAGE i r 8.4-1 Environmental Radiological Monitoring l I Program 8.4-2 l 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 I i 1 ; I 9 4 t J 4 O i I l 4 ! i i l l f 1 [ i 9 i [ i . i i 1 t 8-11 ! i ; ] ! f
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i I i BYRON REVISION 11 ' JUNE 1984 O , ODCM LIST OF FIGURES FOR BYRON SECTION 8.0 l t NUMBER TITLE i
, 8.1-1 Simplified HVAC and Gaseous Effluent Flow ! , Diagram ,
i 8.2-1 Liquid Release Flowpath ! 8.4-1 Onsite Air Sampling Locations i 8.4-2 Offsite Air Sampling Locations [ l 8.4-3 Inner Ring and Outer Ring TLD Locations ( i
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BYRON REVISION 11 JUNE 1984 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design 8.1.1.1 Gaseous Radwaste Treatment System i A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the , primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. Refer to Figure 8.1-1 for a simplified l system flowpath diagram. , O : x_/ 8.1.1.2 Ventilation Exhaust Treatment System i A ventilation exhaust treatment system shall be any system i designed and installed to reduce gaseous radiciodine or ! l radioactive material in particulate form in effluents by l passing ventilation or vent exhaust gases through charcoal l adsorbers and/or HEPA filters for the purpose of removing l iodines or particulates from the gaseous exhaust stream - j I prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). [ Engineered Safety Feature (ESF) atmospheric cleanup systems l are not considered to be ventilation exhaust treatment system j components. ! t 8.1.2 Alarm and Trip setpoints !
/~) \ ,/
Alarm and trip setpoints of gaseous effluent monitors at ! the principal points of release of ventilation exhaust air , 8.1-1 l
[ BYRON REVISION 11 I JUNE 1984 l containing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded. The set- , points are found by solving Equations 2.6* and 2.7** for each lf class of releases. For this equation, the radioactivity mixture in the exhaust i air is assumed to have the composition of gases listed in ; Table 3.5-7 of the Environmental Report Operating License l Stage. According to subsection 3.5.3.4 of the report, releases , of radionuclides in gaseous effluents were calculated using I the PWR-GALE computer program and the parameters listed f in Table 3.5-5. Equation 2.6* is rewritten using the fractional composition of ll each nuclide, fg, and a total release rate, Q t , f r station vent ( stack releases (the principal point of release of ventilation j exhaust air containing radioactivity): l 1.11 b Q tv b*f) i i
< 500 mrem /yr (8.1) i .
fg Fractional Radionuclide Composition ! The release rate of radionuc.'.ide i divided by the total release of all radionuclides. l c Q tv Total Release Rate, Vent Release (UCi/sec) The release rate for all radionuclides due to f a station vent stack release. l Oiv " Otvf i (8.2) Equation 8.1 can be solved for Q tv for release limit } determinations. Similarly, Equation 2.7** can be rewritten: ! i g (X/Q), Otv f i eMP (- At R/3600 uy ) + I 1.11 V g Q tv I i
< 3000 mrem /yr (8.3)
- Equation 2.9 of Revision 2.
- Equation 2.10 of Revision 2.
8.1-2 j h
BYRON REVISION 11 JUNE 1984 Equation 8.3 can be solved for Qtv and a corresponding release limit can be determined. The most conservative release
' limit from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm and trip setpoints for a vent release.
The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded. Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.3-9 of the Technical Specifications. l Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications. 8.1.3 Station vent Stack Monitors Detectors 1RE-PR028A, B, C, D, and E (particulate, low gas, s iodine, high gas, and background subtraction channels, respec-tively) and 2RE-PR028A, B, C, D, and E monitor station vent stack effluent from the auxiliary building vent stacks. The particulate detector utilizes a beta scintillator and has a range of 10 -11 to 10-5 pCi/cc. The low and high gas detectors utilize beta scintillators and have ranges of 10~0 to 10-2 pCi/cc and 10 -2 to 10 2 pCi/ce, respectively. The iodine detector utilizes a NaI(Tl) scintillator and has a range of 10 ~11 to 10-5 pegfee, Both vent stack effluent monitors feature automatic isokinetic sampling, automatic ganeous composite grab sampling, and tritium sampling. The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on V the 477-foot elevation. 8.1-3
BYRON REVISION 11 JUNE 1984 Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main centrol room. A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors. The power supply unit is located on the monitor skids. The monitors are powered by local 120-vac instrumentation buses. Alarm setpoint determination is addressed in Subsection 8.1.2. The release limits (pCi/sec) obtained from Equations 8.1 and 8.3 are divided by the normal auxiliary building vent O v stack flow rates (cc/sec) to obtain the pCi/cc alarm setpoint values. Readouts for the vent stack monitors are in pCi/cc. The cpm to pCi/cc conversion is accomplished by use of conversion factors in the radiation monitoring system software. 8.1.4 Containment Purge Effluent Monitors Detectors 1RE-PR001A, B, and C (particulate, gas, and iodine channels, respectively) and 2RE-PR001A, B, and C monitor containment purge effluent discharge to the auxiliary building vent stacks for Units 1 and 2, respectively. The particulate detector utilizes a beta scintillator and has a range of 10 -11 to 10-5 pC1/cc. The gas detector utilizes a beta scintillator and has a range of 10-6 to 10-2 pegjee, The iodine detector utilizes a NaI(Tl) scintillator and has a range of 10~11 to 10-5 pegjee, 8.1-4
BYRON REVISION 11 JUNE 1984 I U l The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 475-foot elevation. t Each monitor has a microprocessor (RM-80' which utilizes i digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, , are displayed on a CRT display (RM-ll) in the main control room. , A power. supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors. The power supply unit is located on the monitor skids. The monitors l are powered by local 120-Vac instrumentation buses, m A containment atmosphere sample is obtained and analyzed prior to each containment purge release. The isotopic analysis results of this sample are used to determine the maximum allowed containment purge flow rate and as a basis for deter-mining the containment purge effluent monitor setpoints. 8.1.5 Gas Decay Tank Monitors Detectors ORE-PR002A and B (low range gas and high range gas, respectively) monitor the radiation level of the gas decay tank discharge to the auxiliary building vent stacks. Detectors ORE-PR002A and B are interlocked with valve OGWRCV014. Automatically, on a high radiation and/or instrument failure signal from the detectors, vent valve OGWRCV014 closes to isolate the gas decay tank discharge line. (vb 8.1-5
BYRON REVISION 11 ! JUNE 1984 [ () Both the low range and high range gas detectors utilize l beta scintillators and have ranges of 10-6 to 10 -2 pCi/cc and 10 -2 to 10 2 pCi/cc, respectively. i 1 { The monitor skid with associated pump, detectors, and local l controls is located in the auxiliary building on the 346- : foot elevation. i The monitor has a microprocessor (RM-80) which utilizes f digital processing techniques to analyze data and control ; monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room. A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and i provides the high voltage for the detectors. The power () supply unit is located on the monitor skid. The monitor is powered by local 120-Vac instrumentation buses. A grab sample from the gas decay tank to be released is obtained and analyzed prior to each gas decay tank discharge. The isotopic analysis results of this sample are used to i determine the maximum allowed gas decay tank discharge line , flow rate and as a basis for determining the gas decay tank monitor interlock and high alarm setpoints. 8.1.6 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation system, and the gas decay tanks are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation will normally be made evenly bethren units. [\-)\ ! 8.1-6 ,
i i . i BYRON REVISION 11 ! JUNE 1984 : 8.1.7 Symbols Used in Section 8.1 l , SYMBOLS NAME UNIT 1 Q tv Total Release Rate, Vent Release (pCi/sec) j l Vg Gamma Whole Body Dose Constant, Vent Release (mrad /yr per pCi/sec) I t f Fractional Radionuclide Composition i i E Beta Skin Dose Constant (mrem /yr per pCi/m ) i (X/Q)y Relative Effluent Concentration, ; 3 Vent Release (sec/m ) l, A g Radiological Decay Constant (hr-1) V R Downwind Range (m) lI i uy Average Wind Speed, Vent Release (m/sec) i Release Rate, Vent Release (pCi/sec) Q iy lf f Gamma Dose Constant, Vent Release (mrad /yr per pCi/sec) Vg ll i l t i
~
8.1-7 l
. - ~ . . - .-. . - . . . . . - - - . . _ _ . - - - - . - - _. . - - .
I l l t BYRON REVISION 11 JUNE 1984 g 8.1.8 Constants Used in Section 8.1 l I NUMERICAL VALUE NAME UNIT ' l 1.11 Conversion Constant (mrem / mrad) j 3600 Conversion Constant (sec/hr) , l 1 f i l l i i 1 t f t t [ I l l i l t : i
\
! t Ii 8.1-8 l [, l _ _ _ . - _ , , _ - . ~ . - - . , , - - , - . . - , . ,
. , . . - . - . - . . ~ . - . . _ , . . - , , - . - . _ - - . - , , _ _
REVISION 11 i JUNE 1984 tu i, a e a
.- Elev 200'0" 2 * *
- above Grade 3 000 Containment Unit 1 ,3 g g b .
U M a0 iRg.PR028 2RE.PRC28 i iG _ 3 000 l l H C 43 900 m rTT-4 M C H C m W
~
F 0 43900
== 400 1 R E - PR 001 3 & Containmene Q N O _
l Unet2 U F 43 900 l 2RE.PR001 Stac.1 Staca 2 Fuetmandhng H 21 000 159 000 b ___.f___ Mcw Ausehery 162 300 tpwelding h Acce.. stes, g 133 000 h M V n e....e.. 4c,d B ! e 20 tonly dunng dischatgeI
,g,, _
lant. ORE-PR002 159 000 Nont.iteved 900 ausshary buelding tant v.nt.
. EnE 1 000 Fmered g yg susthery budd*ng i.n. .eni.
H 14 105
$.. e . ..
.ndi.0... .ne.
a g , 18 su H 4 250 uva*r F E EC _4 p. BYRON STATION FIGURE 8.1-1 [D 's) SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 10F 2)
- -_- ~
l I REVISION 11 f JUNE 1984 1 L l i b- i Gland steam condenser y y 1.400 g y N 1.432 H C C H Sleem jet % 32 S F1 R l air elector j gy y g Stack 1 Stack 2 Gland steam m 1.400 N 1.432 _ condenser V U F 0 32 Steam let % air ejector p 8,630 h n p S .. r....e .
, v e
,[(,~n 3.100 Volume reduction a H C C H E 13 C Charcoal filter F Refueling G Noble gas radiation monitor (offline)
H HEPA fitter M Three-channel radiation monitor l for particulate, lodine, and l noble gas (offline) N Normal operation P Particulate monitor (offline) R Hydrogen recombiner S Normal range stack radiation monitor (particulate, lodine, and noble gas) W Wide-range stack noble gas radiation monitor All flow rates are cubic feet per minute l BYRON STATION l FIGURE 8.1-1 SIMPLIFIED HVAC AND l GASE0US EFFLUENT FLOW DIAGRAM . (SHEET 2 0F 2)
f l BYRON REVISION 11 JUNE 1984 l (x- ! 8.2 LIQUID RELEASES l 8.2.1 System Design ; A liquid radwaste treatment system shall be a system designed , and installed to reduce radioactive liquid effluents by ! collecting the liquids, providing for retention or holdup, ! and providing for treatment by demineralizer or a concentrator l for the purpose of reducing the total radioactivity prior to release to the environment. Refer to Figure 8.2-1 for ; a simplified system flowpath diagram. 8.2.2 Alarm Setpoints Alarm setpoints of liquid effluent monitors at the principal j release points are established to ensure that the limits ! t of 10 CFR 20 are not exceeded in the unrestricted area. {~N
\
l Prior to each batch release, a grab sample from the release i tank is obtained and analyzed. Equation 8.4 is evaluated for each radionuclide identified in the grab sample isotopic analysis results to determine the maximum allowable flow rate f in the liquid radwaste discharge line. l . MPC i xF act F ,r,x = + K (8.4) C i F[,, Maximum Permissible Flow Rate, l Radwaste Discharge (gpm) t The maximum flow rate permitted in the liquid radwaste discharge line that meets 10 CFR 20 limits. i l - ("
\/ 8.2-1
t r BYRON REVISION 11 JUNE 1984 , d F A tual Flow Rate, Initial Dilution act Stream (gpm) The actual flow rate of the initial i dilution stream which carries the radionuclides to the unrestricted area boundary. { l MPC f Maximum Permissible Concentration of Radionuclide i in the Unrestricted 7 Area (10 CFR 20, Appendix B, Table II, Column 2) (pCi/ml) Cg Concentration of Radionuclide i in the Release Tank (pCi/ml) K Conservatism Constant Determined ( (,j by Station Procedures for Liquid i Releases; K> 1.0. Division by K allows station management to , provide a margin of conservatism i for liquid batch releases. After determining F ax from Equation 8.4, 10 CFR 20 compliance is verified using Equations 8.5 and 8.6. max (8.5) C"i = Ci p r
,p d max act
. - t C"= Concentration of Radionuclide i in the Unrestricted Area. (pci/ml)
] Cf i
MPC i
<l (8.6) b("%
8.2-2
BYRON REVISION 11 JUNE 1984
\
J The alarm setpoints for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample. The alarm setpoints are set so that any deviations from the isotopic analysis results will result in the automatic ter-mination of the release. Readouts for the liquid effluent monitor are in pCi/ml. The cpm to pCi/ml conversion is accom-plished by use of conversion factors in the radiation monitoring system software, f 8.2.3 Liquid Radwaste Effluent Monitor l l Radiation monitor ORE-PR001 monitors liquid radwaste effluent l and is interlocked with release tank discharge valve 0WX353. On high radiation in the liquid radwaste effluent, the ( ,) release tank discharge valve is closed automatically. The release tank (0WX0lT) holds 30,000 gallons and is located in the turbine building on the 401-foot elevation. The monitor utilizes a NaI(Tl) detector with a range for
-8 -2 gamma radiation of 10 Ci/ml to 10 Ci/ml. The monitor skid and associated features are located in the turbine building on the 401-foot elevation.
The monitor has a microprocessor (RM-80) which utilizes l digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room. O O 8.2-3
i i BYRON REVISION 11 JUNE 1984 I
\
s/ 'A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and f provides the high voltage for the detector. The power l supply is located on the monitor skid. The monitor is powered l from local 120-Vac instrumentation buses. f i A discussion of alarm setpoints for ORE-PR001 is included j in Subsection 8.2.2. ; 8.2.4 Station Blowdown Monitor ! l l Radiation monitor ORE-PR010 continuously monitors the circulating water blowdown for radioactivity. The monitor utilizes a l
-8 NaI(Tl) detector with a range for gamma radiation of 10 uCi/ml
-2 to 10 Ci/ml. The monitor skid and associated features are located in the turbine building on the 364-foot elevation. l The monitor has a microproc'essor (RM-80) which utilizes !
digital processing techniques to analyze data and control ; monitor functions. Monitor data, including current radiation i levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control i room. l A power supply unit furnishes the positive and negative ; voltages for the circuits, relays, and alarm lights and provides high voltage for the detector. The power supply l is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses. ' The alarm setpoints for the station blowdown monitor are i determined prior to each release and are based on the isotopic ! analysis results of the release tank grab sample and the l actual dilution flow rates. The alarm setpoints are set so ! O r 8.2-4 ; s-,., - _ , - - . , . - . . w y-- - -- , - *ea- - -
i BYRON REVISION 11 JUNE 1984 , that any deviations from the isotopic analysis results or from the specified dilution flow rate will result in an alarm , from the monitor. Between batch releases, the station blowdown monitor alarm setpoints are set based upon the I-131 MPC and the average dilution flow rate. 8.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors j l i Radiation monitors 1RE-PR002, 2R2-PR002, 1RE-PR003, and , 2RE-PR003 monitor the RCFC and essential service water outlet lines for radioactivity. The monitor utilizes a NaI(Tl)
-8 detector with a range for gamma radiation of 10 Ci/ml
-2 to 10 pCi/ml. The monitor skid and associated features are located in the auxiliary building on the 401-foot ,
elevation. O The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room. A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and l provides high voltage for the detector. The power supply is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses. During initial unit startup, alarms are set at twice background. 8.2-5 i
BYRON REVISION 11 f JUNE 1984 8.2.6 Administrative and Procedural Controls for Radwaste l Discharges Administrative and procedural controls have been designed , to ensure proper control of radioactive liquid radwaste , discharge in order to preclude a release in excess of 10 CFR 20 limits. The discharge rate for each batch is calculated by radiation chemistry personnel (Equation 8.4) and then provided to operating staff personnel. All liquid radwaste discharges will be from the release tank OWX01T. ; on high radiation in the liquid radwaste effluent, the release tank discharge valve 0WX353 is closed automatically. The proper valve lineup is performed by the operator prior to each batch discharge, per station procedures. The actual discharge is authorized by the shift engineer. {-);
\~
The system is equipped with a radiation trip point which alarms and initiates automatic valve closure on the radwaste discharge line to prevent the violation of 10 CFR 20 limits. 8.2.7 Determination of Initial Dilution Stream Flow Rates For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine the flow rate of the initial dilution stream. This instrumen-tation will be operated and maintained as prescribed by the Technical 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. 8.2-6
.. =
l l BYRON REVISION 11 - JUNE 1984 l (~)h (_ [ 8.2.8 Allocation of Effluents from Common Release Points' ! L Radioactive liquid effluents released from the release tank (0WX01T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation 7 will normally be made evenly between units. 8.2.9 Symbols Used In Section 8.2 l SYMBOL ! NAME UNIT a C Concentration of Radionuclide i (pCi/ml) ! in the Unrestricted Area i Cf Concentration of Radionuclide i (ECi/ml) ! in the Release Tank MPC i Maximum Permissible (UCi/ml) Concentration of Radionuclide i in the Unrestricted Area F,,x Maximum Permissible Flow (gpm) Rate, Radwaste Discharge F F act
^ "" **' 9E*
Initial Dilution Stream t K Conservatism Constant Determined by Station Procedures for Liquid Releases; K> 1.0 i i
/~N l Y
8.2-7 h
~ _ .- _ _
REVISION ll , 1R E-PR002
] Unit 1 ,
[G RCFC A & C
- Chiller condensers 5
1 R E-PR003
- Unit 1 '
RCFC B & D - Chiller condensers i 2RE-PR002 j Unit 2 RCFC A & C : Chiller condensers 2RE-PR003 Unit 2 RCFC B & D : Chiller condensers N i ORE-PR001 ? L Station Blowdown i Release tank 7 OWX0lT (Flowrate Determined By (Flowrate Measured By Station Prior to Each Release) Station Prior to Each Release) ORE-PRO 10 L If Rock River l BYRON STATION L = Liquid Process Radiation Monitor RCFC = Reactor Containment Fan Cooler FIGURE 8.2-1 < ( *In each unit, only the A & C or B & D chiller condensers are operating at one time. I
BYRON REVISION 11 - JUNE 1984 O 8.3 t SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM l The process control program (PCP) shall contain the sampling, f analysis, and formulation determination by which solidification l l of radioactive wastes from liquid systems is ensured. J t l
- t
?
I i l i O , t t i i t 4 [, l i i I l [ A 9 O 8.3-1 t i i
I l BYRON REVISION 11 - JUNE 1984 ! O i 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING i The environmental radiological monitoring program for the environs around Byron Station is given in Table 8.4-1. 1 Reporting levels and lower limits of detection for this t program are given in Tables 8.4-2 and 8.4-3, respectively. [ Figures 8.4-1, 8.4-2, and 8.4-3 show sampling and monitoring I locations. ! r f I i I i O : r i I r r O . 8.4-1
p e U O\ O TABL E 8.4-1 ENVIRONMENTAL RADIOLOGICAL MONI MRING PROCRAM* EXPOSURE PATWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPI.INC OR MONIE RING LOCATIONS COLI.ECTION FREQUENCY OF ANALYSIS
- 1. Direct Radiation Indicatore Quarterly Camma dose quarterly
- a. Inner Ring 10L-1, 1.2 mi leIE 101-2, 1.2 mi NME 102-1, 1.0 mi NME 102-2, 1.0 mi leIE 103-1, 1.7 mi NE i
103-2, 1.6 mi NE 104-1, 1.4 mi ENE l 104-2, 1.4 mi ENE 105-1, 1.3 mi E 105-2, 1.3 mi E 106-1, 1.4 mi ESE 106-2, 1.4 mi ESE 107-1, 1.4 mi SE 107-2, 1.4 mi SE 108-1, 0.6 mi SSE 108-2, 0.6 mi SSE g k 109-1, 0.6 mi S 109-2, 0.6 mi S $ l 110-1, 0.6 mi SSW 110-2, 0.6 mi SSW
." 111-1, 0.9 mi SW 7 111-2, 0.8 mi SW N 112-1, 0.8 mi WSW 112-2, 0.7 mi WSW
!!3-1, 0.7 mi W 113-2, 0.7 mi W 114-1, 0.8 mi WNW 114-2, 0.8 mi WNW 115-1, 1.0 mi NW 115-2, 1.0 mi NW 116-1, 1.4 mi NNW 116-2, 1.4 mi NNW 4
- b. Outer Ring 201-1, 4.8 mi N 201-2, 5.2 mi N 202-1, 4.5 mi NNE 202-2, 5.2 mi leIE i 203-1, 5.1 mi NE 43 203-2, 5.1 mi NE $Q 204-1, 4.2 mi ENE My 204-2, 4.1 mi ENE g 205-1, 3.9 mi E co z 205-2, 4.1 mi E "g w
. - , , .- , . _ - - - , ~ _ _ -- ._ . . ,, ., . . , , , ,,., ,,
( V) V lV h TABLE 8.4-1 (Cont'd) EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE _ SAMPLING OR MONITORINC LOCATIONS COLLECTION FREQUENCY OF ANALYSIS i 1. Direct Radiation (Cont'd)
~~~
Indicators (Cont'd)
- b. Outer Ring (Cont'd) 206-1, 4.2 mi ESE 206-2, 4.3 mi SE 207-1, 4.2 mi SE 207-2, 3.7 mi SE 208-1, 4.1 mi SSE 208-2, 3.8 mi SSE 209-1, 3.8 mi S 209-2, 3.9 mi SSW 210-1, 3.6 mi SSW 210-2, 3.6 mi SW 211-1, 5.2 mi SW i 211-2, 4.8 mi WSW 212-1, 4.9 mi WSW 212-2, 5.1 mi W l
213-1, 5.0 mi W 213-2, 5.2 mi WWW 214-1, 4.8 mi WNW 214-2, 5.2 mi NW w i 0 215-1, 5.4 mi NW $ 7 215-2, 5.2 mi NW jj L3 216-1, 4.8 mi NNW 216-2, 5.1 mi NNW
- c. Special Interest At each of the airborne pathway indicator locations specified in Part 2 of this table.
Controla At each of the airborne pathway control locations specified in Part 2 of this table. 4
- 2. Airborne L4 W CM Radioiodine and Indicators Continuous sampler operation Radioiodine Canister: Z<
Particulates a. Near Site Boundary with sample collection 1-131 analysis biveekly. "E BY-21, North Parking Lot, 0.27 mi N weekly, or more frequently ['8 as z BY-22, CECO Real Estate Office, 0.30 mi E if required by dust loading. Particulate Sampler: BY-23, South of Plant on Deerpath Road, s. Croom beta radioactivity ". > 0.59 mi S analysis follo BY-24, Met Tower, 0.66 mi SW filter change.ging 4 b. Near Community with Highest Calculated b. Camma isotopic analysis i Annual Average Ground Level D/Q . of composite (by BY-1, Byron, 3.5 mi NNE location) quarterly.# o
f) t t t j C/ Kj i TABLE 8.4-1 (Cost'd) EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OK SAMP12 SAMPLING OR MONITORINC LOCATIONS CGLLECTION FREQUENCY OF ANALYSIS
- 2. Airborne (Cont'd) Indicators (Cont'd)
- c. Other BY-2, Stillman Valley, 6.2 mi NE BY-3, Nearsite - East, 3.8 mi E BY-4, Paynes Pt., 4.5 mi SE BY-5, Nearsite - Sa. h, 3.6 mi S BY-6, Oregon, 4.6 at SSW controls BY-7, Mt. Morris, 7.8 mi WSW BY-8, Leaf River, 7.0 mi NW
- 3. Waterborne
- a. Surface Indicators Weekly callection composited Casmsa isotopic analysis' BY-9, Woodland Creek, 2.3 mi W monthly. monthly. Composite for BY-!!, Byron Discharge.*i; 6 diver, at Station tritium analysis quarterly.
BY-12, Oregon Pool of do k River, Downstress of Discharge, 4.5 mi SSW Controls BY-10, Byron Intake Pipe / River, at Station to ,co BY-13, Oregon Pool of Rock River, y a Upstream of Intake, 4.3 mi SSW g
- b. Cround Indicatora Quarterly Causea isotopic" and BY-18, Onsite Well, at Station tritium analysis quarterly.
Controls BY-14, Ceco Real Estate Office, 0.3 mi E
- c. Sediment from Shoreline Indicators Semiannually Camma isotopic analysis
- BY-12, Oregon Pool of Rock River, semiannually.
Downstream of Discharge, 4.5 mi SSW Controle BY-13, Oregon Pool of Rock River, Upstream of Intake, 4.3 mi SSW
- 4. Insestion
- a. Milk Indicatore BY-15, Croenhagen/Oltmann Farm, 2.0 mi S Semimonthly when animals are Casmaa isotopic" and I-131 BY-16, Ashelford Farm, 2.7 mi W on pasture, monthly at other analysis semisonthly when y BY-20, Meyers Farm, 5.0 mi SE times. animals are on pasture, g monthly at other ttees. to w Controls g3 BY-17, Bosecker/Lingel Farm, 7.0 mi NE $
"w H m
m em
) \ l )
k'sm v/ -
/ \
V / TABLE 8.4-1 (Cont'd) EXPOSURE PATHWAY SAMPLING OR AND/OR SAMPI.E TYPE AND FREQUENCY SAMPLING OR MONITORING LOC.*.TIONS COLLECTIOh FREQUENCY OF ANALYSIS
- 4. Insestion (Cont'd)
- b. Fish and Invertebrates Indicators Three times per year (spring, Camma isotopic analysis
- Representative samples of BY-12, Oregon Pool of Rock River, summer, and fall). on edible portions, commercially and Downstream of Discharge, 4.5 mi SSW recreationally important species. Controls BY-13, Oregon Pool of Rock River, Upstream of Intake, 4.3 mi SSW
- c. Food Products Indicators Representative samples From any area within 10 miles of the plant that At time of harvest. Camma isotopic snalysis*
of the principal classes is irrigated by water in which plant wastes have on edible portions. of food products, been discharged. Samples of three dif ferent From nearest each of two different of fsite Monthly when available and Camma isotopic" and 1-131 kinds of broadleaf locations of highest predicted annual average required; required only if analysis. vegetation, ground level D/Q (see Table 7.2-6). milk sampling is not performed. Controls to ac m One sample each of
- From a location 9.3 to 18.6 miles from the Monthly when available and Camma isotopic
- and 1-131 5
- a. broadleaf vegetation station in direction of lowest predicted required; required only if analysis.
- di similar to that collected annual average ground level D/Q (see Table milk sampline is not for the above require- 7.2-6). performed.
ment. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampl-ing equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. The cause of the unavailability of samples for that pathway and the new location (s) for obtaining replacement samples shall be identified in a Special Report to the Nuclear Regulatory Commission within 30 days. The report shall also include a revised figure (s) and table for the ODCM reflecting the new location (s). b Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more af ter sampling to allow for redon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamaa isotopic analysis shall be performed on the individual samples. c4
*Camma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the ef fluents from the facility. @
. M ><
(n d ""* If harvest occurs nese than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling gg shall be monthly. Attention shall be paid to including samples of tuberous and root food products. *= w H
.u e
'l
- O O O
! TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES i REPORTING LEVELS . WATER FISH MILK FOOD PRODUCTS
- ANALYSIS (pCi/1) AIRBORNE OR GASES PARTICUy)TE (pCi/m (pCi/kg, wet) (pCi/L) (pCi/kg, vet) 1.W .
l H-3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 , i *< Co-60 300 10,000 $
. z j . 2n-65 300 20,000 1
! Zr-Nb-95 400 i I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 j Cs-137 50 20 2,000 70 2,000
- Ba-La-140 200 300 1
4 l *For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/t may be used. ] M-m wH eO co Z b W e l a
O O O TABLE 8.4-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS' LOWER LIMIT OF DETECTION (LLD) WATER FISH MILK FOOD PRODUCTS SEDIMElfr ANALYSIS (pCi/E) AIRBORNE PARTICp) TE (pCi/kg, wet) OR CAS (pCi/m (pCi/t) (pCi/kg, wet) (pCi/kg, dry) Cross Beta 4 0.01 H-3 2000* Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 E
- o co O Zn-65 30 260 Z l
4 Zr-Nb-95 15 d I-131 I 0.10 1 60 Cs-134 15 0.05 130 15 60 150 CS-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Ca 2
*If no drinking water pathway exists, a value of 3000 pCi/E may be used. t=2
*O 5
0
t I BYRON REVISION 11 JUNE 1984 ; TABLE 8.4-3 (Cont'd) l This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental ; Operating Report. b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. i The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net i count, above system background, that will be detected with 95 percent , probability with only 5 percent probability of falsely concluding that a ! blank observation represents a "real" signal. l t For a particular measurement system, which may include radiochemical separation: I 4.66 s LLD = E + V
- 2. 22
- Y + exp (- Mt) i where:
LLD = the "a priori" lower limit of detection (picoCuries per unit mass or volume), t s = the standard deviation of the background counting rate or of b the counting rate of a blank sample as appropriate (counts per ; minute), l E = the counting efficiency (counts per disintegration), f V = the sample size (units of mass or volume), ! ! 2.22 = the number of disintegrations per minute per picocurie, i i Y = the fractional radiochemical yield, when applicable, f i ! A = the ydioactive decay constant for the particular radionuclide, (sec ), and l At = the elapsed time between sample collection, or end of the sample ' collection period, and time of counting (sec). 1 l Typical values of E, V, Y, and at should be used in the calculation. P It should be recognized that the LLD is defined as an a, priori (before the fact) limit representing the capability of a measurement system , and not as an a_ posteriori (after the fact) limit for a particular ; measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally ( i 8.4-8 i j i
.- - . . _ _ _ . . _ , _ , _ _m.. , . _
__._,.___.._-.j
t BYRON REVISION 11 JUNE 1984 TABLE 8.4-3 (Cont'd) i i I i background fluctuations, unavoidable small sample sizes, the presence ; of interfering nuclides, or other uncontrollable circumstances may ! render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. ! d LLD for drinking water samples. If no drinking water pathway exists, an j LLD of 60 pCi/t may be used. ; F i i ( r i k t i i
- L t
i l l l r P f I f l i j 8.4-9 f
REVISION 11 i JUNE 1984 l
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