ML20121A030
| ML20121A030 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/30/2020 |
| From: | Teledyne Brown Engineering Environmental Services |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20121A027 | List: |
| References | |
| BYRON 2020-0031 | |
| Download: ML20121A030 (48) | |
Text
Table C-IX.1 QUARTERLY OSLD RESULTS FOR BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/-2 S.D. JAN-MAR APR-JUN JUL- SEP OCT-DEC BY-01-1 17 +/- 4 14 18 18 17 BY-04-1 20 +/- 5 17 21 22 20 BY-06-1 17 +/- 4 14 19 17 17 BY-08-1 (Ctrl) 17 +/- 5 13 18 18 18 BY-21-1 15 +/- 4 13 16 17 16 BY-22-1 20 +/- 3 18 22 20 21 BY-23-1 20 +/- 5 17 22 21 22 BY-24-2 18 +/- 3 16 19 19 19 BY-101-1 15 +/- 4 12 15 15 17 BY-101-2 16 +/- 3 14 16 17 16 BY-102-1 22 +/- 7 17 23 24 23 BY-102-2 21 +/- 4 19 22 21 24 BY-103-1 20 +/- 4 17 21 21 23 BY-103-2 21 +/- 4 18 21 23 22 BY-103-3 20 +/- 3 18 20 21 21 BY-104-1 22 +/- 3 20 22 22 24 BY-104-2 22 +/- 5 18 23 22 23 BY-104-3 19 +/- 4 15 20 19 20 BY-105-1 21 +/- 4 18 23 22 22 BY-105-2 22 +/- 5 19 22 21 25 BY-106-1 22 +/- 3 19 22 23 22 BY-106-2 20 +/- 4 18 22 21 21 BY-107-1 23 +/- 4 20 23 24 24 BY-107-2 22 +/- 3 20 22 23 24 BY-107-3 19 +/- 4 16 20 20 20 BY-108-1 22 +/- 3 20 23 23 23 BY-108-2 19 +/- 4 17 20 20 21 BY-109-1 20 +/- 4 18 21 22 21 BY-109-2 21 +/- 5 17 23 21 23 BY-110-1 19 +/- 2 17 19 20 20 BY-110-2 19 +/- 4 17 18 21 21 BY-111-3 21 +/- 6 17 21 23 24 BY-111-4 20 +/- 4 18 21 20 22 BY-112-3 20 +/- 4 17 21 20 22 BY-112-4 20 +/- 5 16 20 22 22 BY-113-1 21 +/- 5 18 22 24 22 BY-113-2 18 +/- 3 17 18 18 20 BY-114-1 17 +/- 3 15 18 17 16 BY-114-2 19 +/- 3 18 20 21 20 BY-115-1 20 +/- 4 17 21 21 21 BY-115-2 19 +/- 3 17 20 21 20 BY-116-1 19 +/- 4 16 20 19 19 BY-116-2 18 +/- 3 16 18 20 19 BY-116-3 19 +/- 3 17 20 19 20 BY-201-3 20 +/- 2 18 21 20 21 BY-201-4 21 +/- 3 19 22 21 21 BY-202-1 20 +/- 3 18 20 21 22 BY-202-2 22 +/- 4 19 22 24 23 BY-203-1 17 +/- 4 14 17 16 19 C-15
Table C-IX.1 QUARTERLY OSLO RESULTS FOR BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/- 2 S.D. JAN- MAR APR-JUN JUL-SEP OCT-DEC BY-203-2 18 +/- 2 17 20 19 18 BY-204-1 18 +/- 2 16 18 18 18 BY-204-2 20 +/- 3 18 22 20 21 BY-205-1 21 +/- 4 19 22 22 23 BY-205-2 19 +/- 4 17 21 19 20 BY-206-1 22 +/- 4 18 23 23 23 BY-206-2 22 +/- 3 20 23 21 22 BY-207-1 22 +/- 4 19 23 23 23 BY-207-2 21 +/- 6 17 23 23 23 BY-208-1 22 +/- 5 19 23 21 24 BY-208-2 21 +/- 5 18 24 22 21 BY-209-1 21 +/- 4 19 22 22 23 BY-209-4 22 +/- 3 20 24 22 22 BY-210-3 22 +/- 3 20 23 22 23 BY-210-4 20 +/- 3 18 21 19 21 BY-211-1 21 +/- 4 18 23 22 22 BY-211-4 21 +/- 4 18 21 22 23 BY-212-1 23 +/- 4 20 24 24 24 BY-212-4 23 +/- 3 20 24 24 23 BY-213-1 21 +/- 5 18 21 23 24 BY-213-4 22 +/- 4 19 23 22 23 BY-214-1 21 +/- 3 19 22 23 21 BY-214-4 21 +/- 4 18 22 22 22 BY-215-1 21 +/- 3 19 22 22 21 BY-215-4 21 +/- 3 19 22 22 21 BY-216-1 22 +/- 3 20 22 24 22 BY-216-2 21 +/- 3 19 22 23 21 BY-301-1 15 +/- 3 13 16 17 16 BY-301-2 18 +/- 3 16 19 18 19 BY-309-1 19 +/- 1 18 20 19 19 BY-309-2 20 +/- 4 18 22 21 21 BY-309-3 19 +/- 3 17 20 20 18 BY-309-4 18 +/- 3 15 18 17 19 BY-314-1 16 +/- 3 14 17 16 17 C-16
TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE INNER RING, OUTER RING, SPECIAL INTEREST, OTHER, AND CONTROL LOCATIONS FOR BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF MILLIREM/STD. QUARTER+/- 2 STANDARD DEVIATION COLLECTION INNER RING OUTER RING SPECIAL INTEREST OTHER CONTROL PERIOD +/-2 S.D. +/-2S.D. +/-2 S.D. +/-2 S.D. +/-2S.D.
JAN-MAR 17 +/- 3 18 +/- 2 16 +/- 3 15 +/-4 13 +/-0 APR-JUN 21 +/- 4 22 +/-3 19 +/- 4 20 +/-5 18 +/-0 JUL-SEP 21 +/- 4 21 +/-4 18 +/- 4 19 +/-4 18 +/-0 OCT-DEC 21 +/- 4 22 +/-3 19 +/- 4 19 +/-5 18 +/-0 TABLE C-IX.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF MILLIREM/STD. QUARTER+/- 2 STANDARD DEVIATION SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/-2 S.D.
0I INNER RING 144 12 25 20 +/-5
-I.
...... OUTER RING 128 14 24 21 +/-4 SPECIAL INTEREST 28 13 22 18 +/-4 OTHER 28 13 22 18 +/-5 CONTROL 4 13 18 17 +/-5 INNER RING STATIONS- BY-101-1, BY-101-2, BY-102-1, BY-102-2, BY-103-1, BY-103-2, BY-103-3, BY-104-1, BY-104-2, BY-104-3, BY-105-1, BY-105-2, BY-106-1, BY-106-2, BY-107-1, BY-107-2, BY-107-3, BY-108-1, BY-108-2, BY-109-1, BY-109-2, BY-110-1, BY-110-2, BY-111-3, BY-111-4, BY-112-3, BY-112-4, BY-113-1, BY-113-2, BY-114-1 , BY-114-2, BY-115-1 , BY-115-2, BY-116-1 , BY-116-2, BY-116-3 OUTER RING STATIONS - BY-201-3, BY-201-4, BY-202-1, BY-202-2, BY-203-1, BY-203-2, BY-204-1, BY-204-2, BY-205-1, BY-205-2, BY-206-1, BY-206-2, BY-207-1, BY-207-2, BY-208-1, BY-208-2, BY-209-1, BY-209-4, BY-210-3, BY-210-4, BY-211-1, BY-211-4, BY-212-1, BY-212-4, BY-213-1, BY-213-4, BY-214-1, BY-214-4, BY-215-1, BY-215-4, BY-216-1, BY-216-2 SPECIAL INTEREST STATIONS - BY-301-1, BY-301-2, BY-309-1*, BY-309-2*, BY-309-3*, BY-309-4*, BY-314-2 OTHER STATIONS - BY-01-1, BY-04-1, BY-06-1, BY-21-1, BY-22-1,BY-23-1, BY-24 CONTROL STATION - BY-08-1
- For /SFS/ Monitoring
FIGURE C-1 Surface Water - Gross Beta - Stations BY-12 and BY-29 (C)
Collected in the Vicinity of BNGS, 2000 - 2019 BY-12 Oregon Pool of Rock River, Downstream 10.0 8.0 6.0 4.0 2.0 0.0 ----------------------------1 01-25-00 01-18-05 01-12-10 01-06-15 12-31-19 BY-29 (C) Byron, Rock River Upstream 14.0 12.0 10.0 8.0 s
0 Cl. 6.0 4.0 2.0 0.0 ----------------------------1 01-25-00 01-18-05 01-12-10 01-06-15 12-31-19 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JUNE 2005 C-18
FIGURE C-2 Surface Water -Tritium - Stations BY-12 and BY-29 (C)
Collected in the Vicinity of BNGS, 2000 - 2019 BY -12 Oregon Pool of Rock River, Downstream 10000 1000 100 10 +--------+-------+--------+--------!
03-28-00 03-06-05 02-12-10 01-21-15 12-30-19 BY-29 (C) Byron, Rock River Upstream 250 200 150 100 50 0+----------------------------------1 03-28-00 03-06-05 02-12-10 01-21-15 12-30-19 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JUNE 2005 C-19
FIGURE C-3 Ground Water -Tritium - Station BY-14-1 Collected in the Vicinity of BNGS, 2000 - 2019 BY-14-1 3200 N. German Church Road Well 250 200 150
.J r,C.
100 50 o.,.__ _.;.___---1.------ --+- -- ---+--------1 01-04-00 01-01-05 12-30-09 12-28-14 12-26-19 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JUNE 2005 C-20
FIGURE C-4 Ground Water - Tritium - Stations BY-18-1 Collected in the Vicinity of BNGS, 201 O - 2019 BY-18-1 Calhoun Well 250 200 150
.J
[>
C.
100 50 0
07-01-10 11-14-12 03-31-15 08-14-17 12-29-19 C-21
FIGURE C-5 Ground Water - Tritium - Station BY-32 Collected in the Vicinity of BNGS, 2000 - 2019 BY-32 Krueger Well 250 200 150 0a.
100 50 0
01-01-00 12-31-04 12-31-09 12-31 -14 12-31-19 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JUNE 2005 C-22
FIGURE C-6 Ground Water - Tritium - Station BY-35 Collected in the Vicinity of BNGS, 2006 - 2019 BY-35 Vancko Well 250 200 150
..J
~a.
100 50 0
04-01-06 10-31 -10 06-01-15 12-31-19 C-23
FIGURE C-7 Ground Water - Tritium - Station BY-37 Collected in the Vicinity of BNGS, 2006 - 2019 BY-37 Cavage Well 250 200 150 0C.
100 50 0
04-01-06 10-30-10 05-30-15 12-28-19 Ground Water - Tritium - Station BY-38 Collected in the Vicinity of BNGS, 2006 - 2019 BY-38 Steve Storz Well 250 200 150 100 50 0-+------+------+------+------+------+
07-13-15 06-03-16 04-25-17 03-17-18 02-06-19 12-29-19 C-24
FIGURE C-8 Air Particulate - Gross Beta - Stations BY-08 (C) and BY-21 Collected in the Vicinity of BNGS, 2000 - 2019 BY-08 (C) Leaf River WNW 60.0 50.0 e 4o.o
~
..,a. 30.0 C?
w
~ 20.0 10.0 0 .0 +--- ---+--
01 00 01-03-04
--+----
01-02-08
~ - - ---+-----
01-01-12 12-31-15 12-30-19 BY -21 Byron Nearsite N 60.0 50.0 e 4o.o
~
..,a. 30.0 Ci>
w
~ 20.0 10.0 0.0 - - - 03-04 01-04-00 ----- - - - 01-12 01-02-08 - -- - -- - - 30-19 12-31-15 -
C-25
FIGURE C-9 Air Particulate - Gross Beta - Stations BY-22 and BY-23 Collected in the Vicinity of BNGS, 2000 - 2019 BY-22 Byron Nearsite SE 60.0 50.0
.., 40.0
- § 0
..,a. 30.0
'i' w
~ 20.0 10.0 0.0 + - - - - - - + - - - - - + - - - - - - - - - - + - - - - - - 1 01-04-00 01-03-04 01-02-08 01-01-12 12-31-15 12-30-19 BY-23 Byron Nearsite S 60.0 50.0 e 4o.o r,
..,a. 30.0
'i' w
~ 20.0 10.0 0.0 + - - - - - - + - - - - - + - - - - - - - - - + - - - - - - - 1 01-04-00 01 04 01-02-08 01-01-12 12-31-15 12-30-19 C-26
FIGURE C-10 Air Particulate - Gross Beta - Stations BY-24 Collected in the Vicinity of BNGS, 2000 - 2019 BY-24 Byron Nearsite SW 70.0 60.0
.., 50.0
.E o 40.0 Q.
~ 30.0 0
20.0 10.0 0.0 ---------------------1------1 01-04-00 01-03-04 01-02-08 01-01-12 12-31-15 12-30-19 C-27
FIGURE C-11 Air Particulate - Gross Beta - Stations BY-01 and BY-04 Collected in the Vicinity of BNGS, 2005 - 2019 BY-01 Byron N 60.0 50.0
.., 40.0
.E 0
..,a. 30.0 9
w
~ 20.0 10.0 0.0 +--- -
07-05-05
- - 04-10 12-04-07
- -- - 02-12 -------- 03-03-15
-- - -- 31-19 08-01 -17 BY-04 Paynes Point SE 60.0 50.0
.., 40.0
.E 0
..,a. 30.0 9
...~ 20.0 10.0 0.0 - - 04-07 07-05-05 -- - 04-10 -- -- - -- - - 03-15 10-02-12 - -- -- - --
08-01-17 31 -19 Regular analysis of far field air particulate & gross beta did not take place prior to 2005 C-28
FIGURE C-12 Air Particulate - Gross Beta - Station BY-06 Collected in the Vicinity of BNGS, 2005 - 2019 BY-06 Oregon SSW 60.0 50.0
.., 40.0 J§ 0Q.
.., 30.0
~
w 0 20.0 10.0 0.0 07-05-05 12-04-07 05-04-10 10-02-12 03-03-15 08-01-17 12-31-19 Regular analysis of far field air particulate & gross beta did not take place prior to 2005 C-29
Intentionally left blank APPENDIX D INTER-LABORATORY COMPARISON PROGRAM
Intentionally left blank Analytics Environmental Radioactivity Cross Check Program Table D.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to MonthNear Matrix Nuclide Units Reported Evaluation (bl Number Value (aJ Analytics Result Value March 2019 E12468A Milk Sr-89 pCi/L 87.1 96 0.91 A Sr-90 pCi/L 12.6 12.6 1.00 A E12469A Milk Ce-141 pCi/L 113 117 0.97 A Co-58 pCi/L 153 143 1.07 A Co-60 pCi/L 289 299 0.97 A Cr-51 pCi/L 233 293 0.80 A Cs-134 pCi/L 147 160 0.92 A Cs-137 pCi/L 193 196 0.98 A Fe-59 pCi/L 153 159 0.96 A 1-131 pCi/L 91.5 89.5 1.02 A Mn-54 pCi/L 149 143 1.04 A Zn-65 pCi/L 209 220 0.95 A E12470 Charcoal 1-131 pCi 77.5 75.2 1.03 A E12471 AP Ce-141 pCi 60.7 70.2 0.87 A Co-58 pCi 87.9 85.8 1.02 A Co-60 pCi 175 179 0.98 A Cr-51 pCi 165 176 0.94 A Cs-134 pCi 91.2 95.9 0.95 A Cs-137 pCi 120 118 1.02 A Fe-59 pCi 108 95.3 1.13 A Mn-54 pCi 94.2 85.7 1.10 A Zn-65 pCi 102 132 0.77 w E12472 Water Fe-55 pCi/L 2230 1920 1.16 A E12473 Soil Ce-141 pCi/g 0.189 0.183 1.03 A Co-58 pCi/g 0.209 0.224 0.93 A Co-60 pCi/g 0.481 0.466 1.03 A Cr-51 pCi/g 0.522 0.457 1.14 A Cs-134 pCi/g 0.218 0.250 0.87 A Cs-137 pCi/g 0.370 0.381 0.97 A Fe-59 pCi/g 0.263 0.248 1.06 A Mn-54 pCi/g 0.248 0.223 1.11 A Zn-65 pCi/g 0.371 0.344 1.08 A E12474 AP Sr-89 pCi 88.3 95.2 0.93 A Sr-90 pCi 11.7 12.5 0.94 A August 2019 E12562 Soil Sr-90 pCi/g 4.710 6.710 0.70 w (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:
=
A Acceptable - reported result falls within ratio limits of 0. 80-1. 20
=
W Acceptable with warning - reported result falls within 0. 70-0.80 or 1. 20-1. 30
=
N Not Acceptable - reported result falls outside the ratio limits of < 0. 70 and > 1. 30 (Page 1 of 2)
D-1
Analytics Environmental Radioactivity Cross Check Program Table D.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation !bl Number Value (a) Analytics Result Value September 2019 E12475 Milk Sr-89 pCi/L 70.0 93.9 0.75 w Sr-90 pCi/L 12.0 12.9 0.93 A E12476 Milk Ce-141 pCi/L 150 167 0.90 A Co-58 pCi/L 170 175 0.97 A Co-60 pCi/L 211 211 1.00 A Cr-51 pCi/L 323 331 0.98 A Cs-134 pCi/L 180 207 0.87 A Cs-137 pCi/L 147 151 0.97 A Fe-59 pCi/L 156 148 1.05 A 1-131 pCi/L 81.1 92.1 0.88 A Mn-54 pCi/L 160 154 1.04 A Zn-65 pCi/L 303 293 1.03 A E12477 Charcoal 1-131 pCi 95.9 95.1 1.01 A E12478 AP Ce-141 pCi 129 138 0.93 A Co-58 pCi 128 145 0.88 A Co-60 pCi 181 174 1.04 A Cr-51 pCi 292 274 1.07 A Cs-134 pCi 166 171 0.97 A Cs-137 pCi 115 125 0.92 A Fe-59 pCi 119 123 0.97 A Mn-54 pCi 129 128 1.01 A Zn-65 pCi 230 242 0.95 A E12479 Water Fe-55 pCi/L 1810 1850 0.98 A E12480 Soil Ce-141 pCi/g 0.305 0.276 1.10 A Co-58 pCi/g 0.270 0.289 0.93 A Co-60 pCi/g 0.358 0.348 1.03 A Cr-51 pCi/g 0.765 0.547 1.40 N(1l Cs-134 pCi/g 0.327 0.343 0.95 A Cs-137 pCi/g 0.308 0.321 0.96 A Fe-59 pCi/g 0.257 0.245 1.05 A Mn-54 pCi/g 0.274 0.255 1.07 A Zn-65 pCi/g 0.536 0.485 1.11 A E12481 AP Sr-89 pCi 95.9 91 .9 1.04 A Sr-90 pCi 12.3 12.6 0.97 A E12563 Soil Sr-90 pCi/g 0.392 0.360 1.09 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:
=
A Acceptable - reported result falls within ratio limits of 0.80-1 .20
=
W Acceptable with warning* reported result falls within 0. 70-0.80 or 1.20-1 .30
=
N Not Acceptable - reported result falls outside the ratio limits of < 0. 70 and > 1.30 (1) See NCR 19-27 (Page 2 of 2) 0-2
DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Table D.2 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value (a) Range Value February 2019 19-GrF40 AP Gross Alpha Sq/sample 0.184 0.528 0.158 - 0.898 A Gross Beta Sq/sample 0.785 0.948 0.474 - 1.422 A 19-MaS40 Soil Ni-63 Bq/kg 420 519.0 363 - 675 A Sr-90 Bq/kg (1) NRl3>
19-MaW40 Water Am-241 Bq/L 0.764 0.582 0.407 - 0.757 N(4l Ni-63 Bq/L 4.72 5.8 4.1 - 7.5 A Pu-238 Bq/L 0.443 0.451 0.316 - 0.586 A Pu-239/240 Bq/L -0.00161 0.0045 (2) A 19-RdF40 AP U-234/233 Sq/sample 0.1138 0.106 0.074 - 0.138 A U-238 Sq/sample 0.107 0.110 0.077 - 0.143 A 19-RdV40 Vegetation Cs-134 Sq/sample 2.14 2.44 1.71 - 3.17 A Cs-137 Sq/sample 2.22 2.30 1.61 - 2.99 A Co-57 Sq/sample 2.16 2.07 1.45 - 2.69 A Co-60 Sq/sample 0.02382 (1) A Mn-54 Sq/sample -0.03607 (1) A Sr-90 Sq/sample -0.1060 (1) N<bJ Zn-65 Sq/sample 1.35 1.71 1.20 - 2.22 w August2019 19-GrF41 AP Gross Alpha Sq/sample 0.192 0.528 0.158 - 0.898 w Gross Beta Sq/sample 0.722 0.937 0.469 - 1.406 A 19-MaS41 Soil Ni-63 Bq/kg 436 629 440 - 818 N(6l Sr-90 Bq/kg 444 572 400 - 744 w 19-MaW41 Water Am-241 Bq/L NR(7l Ni-63 Bq/L 7.28 9.7 6.8 - 12.6 w Pu-238 Bq/L 0.0207 0.0063 (2) A Pu-239/240 Bq/L 0.741 0.727 0.509 - 0.945 A 19-RdF41 AP U-234/233 Sq/sample 0.0966 0.093 0.065-0.121 A U-238 Sq/sample 0.0852 0.096 0.067-0.125 A 19-RdV41 Vegetation Cs-134 Sq/sample 0.0197 (1) A Cs-137 Sq/sample 3.21 3.28 2.30-4.26 A Co-57 Sq/sample 4.62 4.57 3.20 - 5.94 A Co-60 Sq/sample 4.88 5.30 3.71 - 6.89 A Mn-54 Sq/sample 4.54 4.49 3.14 - 5.84 A Sr-90 Sq/sample 0.889 1.00 0.70-1 .30 A Zn-65 Sq/sample 2.78 2.85 2.00 - 3.71 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DDEIMAPEP evaluation:
A= Acceptable - reported result falls within ratio limits of0.80-1.20
=
W Acceptable with warning- reported result falls within 0. 70-0.80 or 1.20-1 .30
=
N Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (1) False positive test (2) Sensitivity evaluation (3) See NCR 19-12 (4) See NCR 19-13 (5) See NCR 19-14 (6) See NCR 19-25 (Page 1 of 1)
(7) See NCR 19-26 D-3
ERA Environmental Radioactivity Cross Check Program Table D.3 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation Cb>
Number Value<*> Limits Value April 2019 Rad-117 Water Ba-133 pCi/L 26.3 24.1 18.6 - 27.8 A Cs-134 pCi/L 15.2 12.1 8.39- 14.4 Nc1>
Cs-137 pCi/L 33.6 33.1 28.8- 39.4 A Co-60 pCi/L 11.9 11.5 8.67 - 15.5 A Zn-65 pCi/L 87.1 89.2 80.3 - 107 A GR-A pCi/L 19 19.3 9.56- 26.5 A GR-B pCi/L 20.2 29.9 19.1-37.7 A U-Nat pCi/L 55.5 55.9 45.6 - 61.5 A H-3 pCi/L 21500 21400 18700 - 23500 A Sr-89 pCi/L 44.9 33.3 24.5 - 40.1 Nc2>
Sr-90 pCi/L 24.5 26.3 19.0 - 30.7 A 1-131 pCi/L 28.9 28.4 23.6- 33.3 A October 2019 Rad-119 Water Ba-133 pCi/L 42.7 43.8 35.7 - 48.8 A Cs-134 pCi/L 53.5 55.9 45.2 - 61.5 A Cs-137 pCi/L 77.7 78.7 70.8- 89.2 A Co-60 pCi/L 51.5 53.4 48.1 - 61.3 A Zn-65 pCi/L 36.6 34.0 28.5 - 43.1 A GR-A pCi/L 40.5 27.6 14.0 - 36.3 NC3l GR-B pCi/L 36.3 39.8 26.4-47.3 A U-Nat pCi/L 27.66 28.0 22.6 - 31.1 A H-3 pCi/L 22800 23400 20500 - 25700 A Sr-89 pCi/L 47.1 45.5 35.4 - 52.7 A Sr-90 pCi/L 32.5 26.5 19.2 - 30.9 NC4l 1-131 pCi/L 26.0 23.9 19.8 - 28.4 A December 2019 QR 120419D Water Sr-90 pCi/L 20.1 18.6 13.2- 22.1 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(b) ERA evaluation:
A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 19-10 (2) See NCR 19-11 (3) See NCR 19-23 (4) See NCR 19-24 (Page 1 of 1)
D-4
APPENDIX E EFFLUENT REPORT
Intentionally left blank TABLE OF CONTENTS
SUMMARY
........................................................................................................................... 1 INTRODUCTION ................................................................................................................. 2 1.0. EFFLUENTS ..................................................................................................... 3 1.1. Gaseous Effluents to the Atmosphere .................................................. 3 1.2. Liquids Released to Rock River ............................................................ 3 2.0. SOLID RADIOACTIVE WASTE ....................................................................... 4 3.0. DOSE TO MAN ................................................................................................. 4 3.1. Gaseous Effluent Pathways .................................................................. 4 3.1.1. Noble Gases ............................................................................ 4 3.1.1.1. Gamma Dose Rates .................................................. 4 3.1.1.2. Beta Air and Skin Dose Rate .................................... 4 3.1.2. Radioactive Iodine & Particulate ............................................. 5 3.1.3. Gaseous Total Dose ................................................................ 5 3.2. Liquid Effluent Pathways ....................................................................... 6 3.3. Total Dose ............................................................................................. 6 3.4. Assessment of Dose to Member of Public ............................................ 6 4.0. SITE METEOROLOGY .................................................................................... 7 E-1
Table of Contents (cont.)
APPENDIX E-1 DATA TABLES AND FIGURES Station Releases Table 1.1-1 Gaseous Effluents ............................... ....................................... .. E-1-1 Table 1.2-1 Liquid Effluents ......... .... .. .............................................................. E-1-3 Table 3.1-140CFR190 Maximum Doses Resulting from Liquid Releases ...... E-1-5 Table 3.2-1 40CFR190 Maximum Doses Resulting from Gaseous Releases. E-1-6 Table 3.3-1 40CFR190 Uranium Fuel Cycle Report-Total Dose ................... E-1-8 Table 3.4-1 Maximum Doses Resulting from Airborne Releases Based On Concurrent Meteorological Data ..... ..... ...... .... ........... .. ....... ... E-1-10 ii E-2
SUMMARY
Calculations based on gaseous and liquid effluents and meteorological data indicate that public dose due to radioactive material attributable to Byron Station during the period does not exceed regulatory or Offsite Dose Calculation Manual (ODCM) limits.
The Total Effective Dose Equivalent (TEDE) due to licensed activities at Byron Station calculated for the maximum exposed individual for the period is 2.54E-01 mrem. The annual limit on TEDE is 100 mrem.
The assessment of radiation doses to the public is performed in accordance with the ODCM. The results of these analyses confirm that the station is operating in compliance with 10CFR50 Appendix I, 10CFR20 and 40CFR190.
There were no additional operational controls implemented which affected the areas of radiological effluents in 2019.
There were no measurements which exceeded the reporting levels, including any which would not have been attributable to station effluents.
The results of the current radiological environmental monitoring program are approximately the same as those found during the pre-operational studies conducted at Byron Station.
E-3
INTRODUCTION Liquid effluents from Byron Station are released to the Rock River in controlled batches after radioassay of each batch. Gaseous effluents are released to the atmosphere and are calculated on the basis of analyses of weekly grab samples and grab samples of batch releases prior to the release of noble gases as well as continuously collected composite samples of iodine and particulate radioactivity sampled during the course of the year. The results of effluent analyses are summarized on a monthly basis. Airborne concentrations of noble gases, 1-131, and particulate radioactivity in offsite areas are calculated using isotopic composition of effluents and meteorological data. C-14 concentration in offsite areas is calculated based on industry-approved methodology for estimation of the amount released and meteorological data.
Environmental monitoring is conducted by sampling at indicator and control (background) locations in the vicinity of Byron Station to measure changes in radiation or radioactivity levels that may be attributable to station operation. If significant changes attributable to Byron Station are measured, these changes are correlated with effluent releases. An environmental monitoring program is conducted which also includes all potential pathways at the site. Gaseous pathways include ground plane (direct), inhalation, vegetation, meat, and milk. Liquid pathways include potable water and freshwater fish. The critical pathway for 2019 gaseous dose was vegetation. The critical pathway for 2019 liquid dose was freshwater fish.
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1.0 EFFLUENTS 1.1 Gaseous Effluents to the Atmosphere Measured concentrations and isotopic composition of noble gases, radioiodine, tritium and particulate radioactivity released to the atmosphere during the year are listed in Table 1.1-1.
A total of 6.62E-01 curies of fission and activation gases were released with a maximum average quarterly release rate of 2.41 E-02 µCi/sec.
A total of 1.06E-06 curies of 1-131 were released during the year with a maximum average quarterly release rate of 1.35E-07 µCi/sec.
A total of O.OOE+OO curies were released as airborne particulate matter with a maximum average quarterly release rate of O.OOE+OO µCi/sec.
A total of 8.53E+OO curies of other (C-14) radioisotopes were released with a maximum average quarterly release rate of 2.82E-01 µCi/sec.
A total of 5.17E+01 curies of tritium were released with a maximum average quarterly release rate of 2.69E+OO µCi/sec.
Gross alpha-emitting radionuclides were below detectable limits.
1.2 Liquids Released to Rock River A total of 3.00E+10 liters of radioactive liquid wastes containing 1.1 ?E-02 curies of fission and activation products were discharged with a maximum quarterly average concentration of 1.37E-13 µCi/ml.
A total of 2.12E+03 curies of tritium were discharged with a maximum quarterly average concentration of 1.99E-05 µCi/ml.
A total of 1.28E-04 curies of dissolved and entrained gases were discharged with a maximum quarterly average concentration of 2.16E-15 µCi/ml.
Gross alpha-emitting radionuclides were below detectable limits.
Quarterly release totals of principal radionuclides in liquid effluents are given in Table 1.2-1.
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2.0 SOLID RADIOACTIVE WASTE Solid radioactive wastes were shipped by truck. For detail, refer to Byron Station 2019 Annual Radiological Effluent Release Report.
3.0 DOSE TO MAN 3.1 Gaseous Effluent Pathways Table 3.2-1 summarizes the doses resulting from releases of airborne radioactivity via the different exposure pathways.
3.1.1 Noble Gases 3.1.1.1 Gamma Dose Rates Offsite Gamma air and whole body dose rates are shown in Table 3.2-1 and were calculated based on measured release rates, isotopic composition of the noble gases, and average meteorological data for the period. Dose rates based on concurrent meteorological data are shown in Table 3.4-1. Based on measured effluents and average meteorological data, the maximum gamma air dose was 1.851 E-04 mrad based on measured effluents and average meteorological data, and 2.68E-05 mrad based on measured effluents and concurrent meteorological data. (Table 3.4-1 ).
3.1.1.2 Beta Air and Skin Dose Rates The range of beta particles in air is relatively small (on the order of a few meters or less); consequently, plumes of gaseous effluents may be considered "semi-infinite" for purpose of calculating the dose from beta radiation incident on the skin. However, the actual dose to sensitive skin tissues is difficult to calculate due to the effect of the beta particle energies, thickness of inert skin and clothing covering sensitive tissues. For purposes of this report the skin is taken to have a thickness of 7.0 mg/cm 2 and an occupancy factor of 1.0 is used. The skin dose based on measured effluents and average meteorological data was 1.122E-04 mrem, and 2.92E-05 mrem based on measured effluents and concurrent meteorological data.
The maximum offsite beta air dose for the year based on measured effluents and average meteorological data was E-6
2.0SE-05 mrad. The beta air dose based on measured effluents and concurrent meteorological data was 1.21 E-05 mrad.
3.1.2 Radioactive Iodine & Particulate The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine. 1-131 released during routine operation of the station may be made available to man resulting in a dose to the thyroid. C-14 is also included in this category. C-14 exhibits a capacity to concentrate in bone. C-14 is released in gaseous form and is absorbed into vegetation through photosynthesis. The principal pathways of interest for C-14 are the consumption of vegetation by humans and milk from which animals have ingested C-14 through the consumption of vegetation. With the addition of C-14 to plant effluents, human dose in this category is primarily driven by the release of C-14 from the plant.
The hypothetical dose to the maximum exposed individual living near the station via ingestion of milk and vegetation was calculated. The source of milk and vegetation was assumed to be at the nearest site boundary with the cows pastured and vegetation grown from May through October. The maximum dose from radioactive iodine and particulate (including C-14) to any organ was 6.95E-01 mrem (child/bone) based on measured effluents and average meteorological data and 5.39E-01 mrem based on measured effluents and concurrent meteorological data.
The maximum dose from radioactive iodine and particulate (including C-14) to the whole body was 1.42E-01 mrem (child) based on measured effluents and average meteorological data and 1.1 OE-01 mrem based on measured effluents and concurrent meteorological data.
3.1.3 Gaseous Total Dose The maximum total dose from gaseous releases to any organ was 6.95E-01 mrem (child/bone) based on measured effluents and average meteorological data, and 5.39E-01 mrem (child/bone) based on measured effluents and concurrent meteorological data.
The maximum total dose from gaseous releases to the whole body was 1.42E-01 mrem (child) based on measured effluents and average meteorological data, and 1.1 OE-01 mrem (child) based on measured effluents and concurrent meteorological data.
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3.2 Liquid Effluent Pathways The principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water and eating aquatic foods. Liquid dose was calculated based on the ingestion of potable water and sport fish. It should be noted, however, there were no communities within 10 km downstream of the plant using the Rock River for drinking water. NRG-developed equations were used to calculate the doses to the whole body, bone, liver, thyroid, kidney, lung, lower GI tract, and skin. Specific parameters for use in the equations are given in the Exelon Offsite Dose Calculation Manual (ODCM). The maximum dose from liquid releases to any organ was 1.45E-01 mrem (adult/gilli). The maximum dose from liquid releases to the whole body was 1.34E-01 mrem (adult).
3.3 Total Dose The maximum total dose to any organ via both gaseous and liquid effluents to any organ is 7.29E-01 mrem (child/bone). The maximum dose to the whole body via both gaseous and liquid effluents is 2.54E-01 mrem (child).
3.4 Assessment of Dose to Member of Public Byron Station did not exceed any of the dose limits as shown below based on concurrent or historical meteorological data.
- The RETS limits on dose or dose commitment to a member of the public due to radioactive materials in liquid effluents from each reactor is 1.5 mrem to the whole body or 5 mrem to any organ during any calendar quarter and 3 mrem to the whole body or 10 mrem to any organ during a calendar year.
- The RETS limits on air dose in noble gases released in gaseous effluents to a member of the public from each reactor is 5 mrad for gamma radiation or 10 mrad for beta radiation during any calendar quarter and 10 mrad for gamma radiation or 20 mrad for beta radiation during a calendar year.
- The RETS limits on dose to a member of the public due to radioactive iodine & particulate with half-lives greater than eight days in gaseous effluents released from each reactor is 7.5 mrem to any organ during any calendar quarter and 15 mrem during a calendar year.
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- The 10CFR20 limit on Total Effective Dose Equivalent to individual members of the public is 100 mrem during a calendar year.
- The 40CFR190 limits on individual members of the public is 25 mrem to the whole body, 25 mrem to any organ (except thyroid), and 75 mrem to the thyroid.
4.0 SITE METEOROLOGY Detailed records of the site meteorological measurements taken during each calendar quarter of the year are maintained by the meteorological vendor, retained on site, and are available upon request. The data are presented as cumulative joint frequency distributions of the wind direction for the 250' level and wind speed class by atmospheric stability class determined from the temperature difference between the 250' and 30' levels. Data recovery for all measurements on the meteorological tower was 99.8% during 2019.
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Intentionally left blank APPENDIX E-1 DATA TABLES AND FIGURES
Intentionally left blank Table 1.1-1 RG 1.21 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2019 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci 4.19E-04 7.29E -02 1. 52E-01 l. lGE-01 3.41E-01
- 2. Avg. Release Rate uCi/sec 5.39E-05 9.27E-03 1.91E-02 l.46E-02 1.08E-02 Iodine-131
- 1. Total Release Ci (1) (1) (1) (1) (1)
- 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)
Particulates Half Life>= 8 days
- 1. Total Release Ci (1) (1) (1) (1) (1)
- 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)
Others
- 1. Total Release Ci 1.01E+00 1.18E+00 1.09E+00 l.12E+00 4.40E+00
- 1. Total Release Ci 2.03E+00 4.56E+00 2.79E+00 5.34E+00 1.47E+01
- 2. Avg. Release Rate uCi/sec 2.62E-01 5.80E-01 3.SlE-01 6.72E-01 4.67E-01 Gross Alpha Radioactivity
- 1. Total Release Ci (1) (1) (1) (1) (1)
- 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)
(l)Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 E-1-1
Table 1.1-1 (cont.)
RG 1.21 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2019 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci 6.83e-02 1.06E-01 7.14E-02 7.56E-02 3.21E-01
- 2. Avg. Release Rate uCi/sec 8.78E-03 1.35E-02 8.98E-03 9.SlE-03 1.02E-02 Iodine-131
- 1. Total Release Ci (1) 1.06E-06 (1) (1) 1.06E-06
- 2. Avg. Release Rate uCi/sec (1) 1. 35E-07 (1) (1) 3.37E-08 Particulates Half Life>= 8 days
- 1. Total Release Ci (1) (1) (1) (1) (1)
- 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)
Others
- 1. Total Release Ci 1.04E+00 8.44E-01 1.12E+00 1.12E+00 4.13E+00
- 1. Total Release Ci 7.55E+00 6.49E+00 6.88E+00 1.61E+01 3.70E+01
- 2. Avg. Release Rate uCi/sec 9.71E-01 8.25E-01 8.65E-01 2.02E+00 1.17E+00 Gross Alpha Radioactivity
- 1. Total Release Ci (1) (1) (1) (1) (1)
- 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) (1)
(l)Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 E-1-2
Table 1.2-1 RG 1.21 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2019 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products
- 1. Total Release Ci 1. 97E-03 2.08E-03 1.16E-03 6.SSE-04 S.86E-03
- 1. Total Release Ci 4.58E+02 1.97E+02 6.39E+01 3.42E+02 1.06E+03
- 2. Avg. Diluted Cone. uCi/ml 1.99E-05 1.16E-05 6.73E-07 8.91E-06 1.01E-05 Dissolved and Entrained Gases
- 1. Total Release Ci 1.03E-05 9.12E-06 (1) 4.46E-05 6.40E-05
- 2. Avg. Diluted Cone. uCi/ml S.SlE-16 6.00E-16 (1) 2.16E-15 8.40E-16 Gross Alpha Radioactivity
- 1. Total Release Ci (1) (1) (1) (1) (1)
Volume of liquid waste liters 3.66E+09 3.59E+09 3.98E+09 3.7SE+09 1.50E+10 Volume of dil. water liters 3.66E+09 3.59E+09 3.98E+09 3.74E+09 1.50E+10 (l)Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 E-1-3
Table 1.2-1 (cont.)
RG 1.21 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2019 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products
- 1. Total Release Ci 1.97E-03 2.08E-03 1.16E-03 6.SSE-04 5.86E-03
- 2. Avg. Diluted Cone. uCi/ml 1.05E-13 1.37E-13 5.14E-14 3.17E-14 7.69E-14 Tritium
- 1. Total Release Ci 4.58E+02 1.97E+02 6.39E+01 3.42E+02 1.06E+03
- 2. Avg. Diluted Cone. uCi/ml 1. 99E-05 1.16E-05 6.73E-07 8.91E-06 1.01E-05 Dissolved and Entrained Gases
- 1. Total Release Ci 1.03E-05 9.12E-06 (1) 4.46E-05 6.40E-05
- 2. Avg. Diluted Cone. uCi/ml 5.SlE-16 6. 00E-16 (1) 2.16E-15 8.40E-16 Gross Alpha Radioactivity
- 1. Total Release Ci (1) (1) (1) (1) (1)
Volume of liquid waste liters 3.676+09 3.59E+09 3.98E+09 3. 75E+09 1.50E+10 Volume of liquid waste liters 3.676+09 3.59E+09 3.98E+09 3.74E+09 1.50E+10 (l)Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 E-1-4
Table 3.1-1 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE
SUMMARY
Units 1 & 2 Report for: 2019 Unit Range - From: 1 To: 2 Liquid Receptor
=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============ ANNUAL 2019 Age grp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 2.50E-02 1.34E-01 1.32E-01 1.32E-01 1.32E-01 1.45E-01 0.00E+00 1.34E-01 TEEN 2.59E-02 1.01E-01 9.88E-02 9.88E-02 9.88E-02 1.08E-01 0.00E+00 1.01E-01 CHILD 3.41E-02 1.12E-01 1.10E-01 1.10E-01 1.10E-01 1.13E-010.00E+001.12E-01 INFANT 1.91E-04 4.89E-02 4.89E-02 4.89E-02 4.89E-02 4.89E-02 0.00E+00 4.89E-02
SITE DOSE LIMIT ANALYSIS----------------------------- ANNUAL 2019 ======
Age Dose Limit Max% of Annual - Limit Group Organ (mrem) (mrem) Limit 2019 - Admin. Any Organ ADULT GILLI 1.45E-01 7.50E+00 1. 93E+00 2019 - Admin. Total Body ADULT TBODY 1. 34E-01 2.25E+00 5.94E+00 2019 - T.Spc. Any Organ ADULT GILLI 1.45E-01 1.00E+01 1.45E+00 Critical Pathway: Fresh Water Fish - Sport (FFSP)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 9.08E+01 CR-51 1. 72E-02 MN-54 4.59E-02 FE-59 3.74E-02 C0-58 3.74E+00 C0-60 2.59E+00 NI-63 2.49E-01 ZR-95 4.87E-04 NB-95 2.51E+00 SB-125 3.39E-03 2019 - T.Spc. Total Body ADULT TBODY 1.34E-01 3.00E+00 4.45E+00 Critical Pathway: Fresh Water Fish - Sport (FFSP)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 9.86E+Ol CR-51 7.44E-05 MN-54 3.lOE-03 FE-59 4.67E-03 C0-58 4.49E-01 C0-60 3.30E-01 NI-63 6.28E-01 ZR-95 l .13E-07 NB-95 2.42E-04 SB-125 7.95E-05 E-1-5
Table 3.2-1 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE
SUMMARY
Units 1 & 2 Report for: 2019 Unit Range - From: 1 To: 2
=== I&P DOSE LIMIT ANALYSIS============================== ANNUAL 2019 Age Dose Limit Max% of Annual - Limit Group Organ (mrem) (mrem) Limit 2019 - Admin. Any Organ CHILD BONE 6.95E-01 1.13E+01 6.18E+00 2019 - Admin. Total Body CHILD TBODY 1.42E-01 1.05E+01 1.35E+00 2019 - T.Spc. Any Organ CHILD BONE 6.95E-01 1.50E+01 4.63E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)
Nuclide Percentage H-3 0.00E+00 C-14 1.00E+02 I-131 2.71E-05 2019 - T.Spc. Total Body CHILO TBODY 1.42E-01 1.50E+01 9.46E-01 Receptor: 5 Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Critical Pathway: Vegetation Major Contributors (0% or greater to total)
Nuclide Percentage H-3 2.06E+00 C-14 9.79E+01 I-131 7.64E-05 E-1-6
Table 3.2-1 (cont.)
40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE
SUMMARY
Units 1 & 2 Report for: 2019 Unit Range - From: 1 To: 2
=== NG DOSE LIMIT ANALYSIS=============================== ANNUAL 2019 Dose Limit Max% of Annual - Limit (mrad) (mrad) Limit 2019 - Admin. Gamma 1.85E-04 7.50E+00 2.47E-03 2019 - Admin. Beta 2.05E-05 1. 50E+01 1.37E-04 2019 - T.Spc. Gamma 1.85E-04 1.00E+01 1.85E-03 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage AR-41 9.62E+01 KR-85M 3.53E-03 XE-135 1. 73E-01 XE-133M 6.55E-03 KR-88 2.35E-02 XE-131M 4.95E-05 XE-133 3.63E+00 2019 - T.Spc. Beta 2.05E-05 2.00E+01 1.02E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 800 (meters) Compass Point: SSE Nuclide Percentage AR-41 7.54E+01 KR-85M 1. 26E-02 XE-135 4.93E-01 XE-133M 6.59E-02 KR-88 1.01E-02 XE-131M 7.84E-04 XE-133 2.40E+01 E-1-7
Table 3.3-1 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Units 1 & 2 Report for: 2019 Unit Range - From: 1 To: 2
=== MAXIMUM DOSE ANALYSIS================================ ANNUAL 2019 Age Dose Dose Type Group Organ (mrem)
Any Organ CHILD BONE 7.29E-01 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Liquid Dose: 8.SlE-02 % of Total: 1.04E+01 Critical Pathway: Fresh Water Fish - Sport (FFSP)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 0.00E+00 CR-51 0.00E+00 MN-54 0.00E+00 FE-59 2.SSE-02 C0-58 0.00E+00 C0-60 0.00E+00 NI-63 1.00E+02 ZR-95 2.83E-06 NB-95 3.76E-03 58-125 2.22E-03 Gaseous Dose: 7.33E-01 % of Total: 8.9SE+01 Critical Pathway: Vegetation (VEG)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 0.00E+00 C-14 1.00E+02 I-131 2.71E-05 E-1-8
Table 3.3-1 (cont.)
40CFR190 URANIUM FUEL CYCLE DOSE REPORT Units 1 & 2
=== MAXIMUM DOSE ANALYSIS================================ ANNUAL 2019 Age Dose Dose Type Group Organ (mrem)
Total Body CHILD TBODY 2.54E-01 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 800 (meters) Compass Point: SSE Liquid Dose: 1.12E-01 % of Total: 4.43E+01 Critical Pathway: Fresh Water Fish - Sport (FFSP)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 9.79E+01 CR-51 9.73E-05 MN-54 3.96E-03 FE-59 6.23E-03 C0-58 5.82E-01 C0-60 4.29E-01 NI-63 1.03E+00 ZR-95 1.68E-07 NB-95 3.18E-04 SB-125 1.41E-04 Gaseous Dose: l.50E-01 % of Total: 5.62E+01 Critical Pathway: Vegetation (VEG)
Major Contributors (0% or greater to total)
Nuclide Percentage H-3 2.06E+00 C-14 9.79E+01 I-131 7.64E-05 E-1-9
Table 3.4-1 The following are the maximum annual calculated cumulative offsite doses resulting from Byron airborne releases in 2019 based on concurrent meteorological data:
Unit 1:
Dose Maximum Value Sector Affected gamma air 11> 1.40 x10-5 mrad East beta air 12> 6.30 x10-5 mrad East whole body 13> 5.63 x10-2 mrem East skin 14> 1.53 x10-5 mrem East organ 15> (child-bone) 2.78 x10- 1 mrem East Unit 1 Compliance Status 10 CFR 50 Appendix I Yearly Objective % of Appendix I gamma air 10.0 mrad 0.00 beta air 20.0 mrad 0.00 whole body 5.0 mrem 1.13 skin 15.0 mrem 0.00 organ 15.0 mrem 1.85 Unit 2:
Dose Maximum Value Sector Affected gamma air 11> 1.28 x10-5 mrad East beta air 12> 5.82 x10-5 mrad East whole body 13 > 5.40 x10-2 mrem East skin 14> 1.39 x10- 5 mrem East organ 15> (child-bone) 2.61 x10- 1 mrem East Unit 2 Compliance Status 10 CFR 50 Appendix I Yearly Objective % of Appendix I gamma air 10.0 mrad 0.00 beta air 20.0 mrad 0.00 whole body 5.0 mrem 1.08 skin 15.0 mrem 0.00 organ 15.0 mrem 1.74 (11 Gamma Air Dose - GASPAR II, NUREG-0597
( 21 Beta Air Dose - GASPAR II, NUREG-0597
( 31 Whole Body Dose - GASPAR II, NUREG-0597 (41 Skin Dose - GASPAR II, NUREG-0597
( 51 Inhalation and Food Pathways Dose - GASPAR II, NUREG-0597 Data recovery: 99.8%
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APPENDIX F METEOROLOGICAL DATA
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