ML003697089
| ML003697089 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/30/1999 |
| From: | Commonwealth Edison Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR | |
| Download: ML003697089 (479) | |
Text
{{#Wiki_filter:Braidwood Station Appendix F Change Summary ODCM Revision 4, August 1999 Paae or Section Change Description F-i Updated revision number. F-iii,-iv Updated page numbers. F-2 Removed reference to an old Technical Specification section. F-4 Updated nearest resident column heading to include the words, "within 6.2 miles". Updated nearest resident information for the SSE direction. Changed year to "1998" for census data. F-8 Updated nearest meat animal radius and D/Q for the SW direction. F-47 Corrected spelling of the word "restricted".
BRAIDWOOD Revision 4 August 1999 APPENDIX F BRAIDWOOb ANNEX INDEX REVISION 4 F-i
BRAIDWOOD Revision 4 August 1999 APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-I F-i i
BRAIDWOOD Revision 4 August 1999 APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and DIQ Maxima At or Beyond the Unrestricted Area Boundary F-6 F-5a X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Boundary for Selected Nuclides Area F-9 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Boundary for Selected Nuclides Area F-24 Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries - 203 and 34 Foot Elevation Data F-39
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distribution Table Summaries F-44
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class F-iii
BRAIDWOOD Revision 4 August 1999 APPENDIX F LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Bounaary F-46 F-2 Restricted Area Bounaary F-47 F-iv
BRAIDWOOD Revision 4 August 1999 APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 F. 1 !NTRODUCTION This appendix contains data relevant to the Braidwood site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment. F.2 REFERENCES
- 1. Sargent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No.
ATD-0149, Revisions 0, 1, 2, and 3, 3/30/95 for Braidwood.
- 2. "Assessment of the Impact of Liquid Radioactive Effluents from Braidwood Station on Proposed Public Water Intakes at Wilmington, Illinois",
J.C. Golden NSEP, January 1990.
- 3. 'Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation, 1988.
- 4. 'Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group, 1992.
F-1
BRAIDWOOD Revision 4 August 1999 Table F- 1 Aquatic Environmental Dose Parameters General Information There is no irrigation ocurring on the Kankakee River downstream of the station. Recreation includes one or more of the following: boating, watersKiing, swimming, and sport fishing. Downstream dams are within 50 miles of the station. One is located on the Kankakee. The other is Illinois River at Dresden Island, Marseilles and the Starved Rock. The Kankakee River flows into the Illinois River about 12 river miles downstream of the station. This is based on information in Figure 2.1-13 of the Braidwood Environmental Report and in Section 2.4.1.1 and Figure 2.4-2 of the LaSalle Environmental Report. Water and Fish Inqestion Parameters Parameter" Value U*, water usage, L'hr 0.042 UV, fish consumption, kg/hr 2.4E-3 1/Mw, 1/Ml 0.25, 1.0 P, cfs 3950 F', cfs 3950 t", h r 24.0 t*, hrc 3.0 Limits onRadioactivity in Unprotected Outdoor Tanksd Outside Temporary Tank < 10 Ci8 per Technical Specification 5.5.12 "The parameters are defined in Section A.2.1 of Appendix A. ft (hr) = 24 hr (all stations) for the fish ingestion pathway c t' (hr) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow rate of 1.4 mph is assumed) d See Section A.2.4 of Appendix A. 0 Tritium and dissolved or entrained noble gases are excluded from this limit. F-2
BRAIDWOOD Revision 4 August 1999 Table F-2 Station Characteristics STATION: Braidwood LOCATION: Braceville, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)
- 1) Release Height = _ m 2) Diameter = m
- 3) Exit Speed =_ ms-, 4) Heat Content Kcal s-1 CHARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height = 60.66 ma
- 2) Diameter = 2.80 m
- 3) Exit Speed = ms-ia CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Building Factor (D) = __60.6 ma METEOROLOGICAL DATA A 320 ft Tower is Located 573 m NE of vent stack release point Tower Data Used in Calculations Release Point Wind Speed Differential and Direction Temperature Elevated (NA)
Vent _203ft (NA) Ground 199-30ft 34 ff 199-30 ft " Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through 6.6 of Appendix B. F-3
BRAIDWOOD Revision 4 August 1999 Table F-3 Critical Ranges Unrestricted Area Restricted Area Nearest Resident Nearest Dairy Farm Boundarya Bounaary Within 6.2 miles within 6.2 Miles' Direction (m) (m) (m) N 610 305 800 None NNE 914 265 2800 None NE 792 299 1100 None ENE 701 361 1200 None E 1036 355 1200 None ESE 2713 425 3500 None SE 3414 448 4300 None SSE 3444 540 None None S 4633 530 6700 None SSW 975 540 2000 None SW 632 632 600 None WSW 555 555 800 None W 518 500 600 None WNW 503 434 600 None NW 495 428 600 None NNW 510 442 600 None a See Updated Final Safety Analysis Report Table 2.1-1a and Environmental Report. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B. b 1998 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. c 1998 annual milch animal census, by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. F-4
BRAIDWOOD Revision 4 August 1999 Table F-4 Average Wind Speeds Downwind Direction Average Wind Speed (m/sec)a Elevatedb Mixed Mode Ground Leveb N 7.6 6.0 4.7 NNE 7.5 5.8 4.4 NE 6.1 5.3 3.9 ENE 6.2 5.2 3.7 E 6.6 5.4 4.0 ESE 6.8 5.6 4.3 SE 6.2 5.3 3.9 SSE 5.8 5.2 4.1 S 5.5 4.9 3.6 SSW 5.5 5.0 3.7 SW 5.3 4.8 3.3 WSW 4.7 4.2 2.4 W 5.4 4.4 2.2 WNW 6.0 4.6 2.4 NW 6.0 4.8 3.1 NNW 6.8 5.4 3.9 a Based on Braidwood site meteorological data, January 1978 through December 1987. Reference 1 of Section F2, using Calculated in formulas in Section B. 1.3 of Appendix B. b The elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values. F-5
BRAIDWOOD Revision 4 August 1999 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Downwind Mixed Mode (Vent) Release Ground Level Release Direction Radius X/Q Radius D/Q Radius X/Q D/Q (meters) (sec/m**3) (meters) (1/m*'2) (meters) (sec/m**3) (1/m**2) N 610. 1.161E-06 610. 1.643E-08 610. 4.646E-06 3.355E-08 NNE 914. 5.076E-07 914. 7.023E-09 914. 1.783E-06 1.382E-08 NE 792. 2.990E-07 792. 4.274E-09 792. 1.738E-06 1.092E-08 ENE 701. 4,281E-07 701. 4.903E-09 701. 2.174E-06 1.310E-08 E 1036. 3.104E-07 1036. 3.780E-09 1036. 1.505E-06 8.551 E-09 ESE 2713. 1.065E-07 2713. 1.164E-09 2713. 3.990E-07 1.949E-09 SE 3414. 7.575E-08 3414. 7.225E-10 3414. 2.757E-07 1.088E-09 SSE 3444. 6.028E-08 3444. 6.345E-10 3444. 2.165E-07 1.015E-09 S 4633. 4.068E-08 4633. 2.644E-10 4633. 1,749E-07 4.520E-10 SSW 975. 1.925E-07 975. 2.843E-09 975. 1.333E-06 6.781 E-09 SW 632. 5.153E-07 632. 5.408E-09 632. 3.485E-06 1.494E-08 WSW 555. 7.821 E-07 555. 4.558E-09 555. 5.471E-06 1.853E-08 W 518. 8.901 E-07 518. 5.064E-09 518. 5.902E-06 1.830E-08 WNW 503. 1.077E-06 503. 6.100E-09 503. 6.472E-06 1.913E-08 NW 495. 1.081 E-06 495. 8.650E-09 495. 5,501 E-06 2.537E-08 NNW 510. 1.098E-06 510. 1.185E-08 510. 5.421E-06 3.023E-08 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B. X/Q is used for beta skin, and inhalation dose pathways. See Sections A.1.2, A.1.3, and A.1.4.2 of Apprendix A. D/Q is used for produce and leafy vegetable pathways. Section A. 1.4 of Appendix A. The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data. Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/Q at or beyond the unrestricted area boundary (UAB). F-6
BRAIDWOOD Revision 4 Table F-5a August 1999 X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary Downwind Mixed Mode (Vent) Release Direction Ground Level Release Radius X/Q Radius D/Q Radius X/Q (meters) (sec/m**3) (meters) (sec/m**3) D/Q (/m*'2) (meters) (1/m*'2) N 305. 3.766E-06 305. 4.266E-08 305. 1.551E-05 NNE 265. 3.841 E-06 9-627E-08 265. 3.855E-08 265. NE 299. 1.412E-06 1.445E-05 9.318E-08 299. 1,473E-08 299. ENE 361. 1.265E-06 8.827E-06 4.892E-08 361. 1.138E-08 361. E 355. 1.669E-06 6.706E-06 3.652E-08 355. 1.590E-08 355. ESE 425. 1.264E-06 8.978E-06 4.611E-08 425. 1.678E-08 425. SE 448. 1.056E-06 7.012E-06 4.132E-08 448. 1.266E-08 448. 6.269E-06 SSE 540. 5.596E-07 3.177E-08 540. 8.639E-09 540. S 530. 6.166E-07 3.673E-06 2.258E-08 530. 5.425E-09 530. SSW 540. 4.441 E-07 4.576E-06 1.745E-08 540. 6.OOOE-09 540. SW 632. 5.153E-07 3.423E-06 1.748E-08 632. 5.408E-09 632. WSW 555. 7.821E-07 3.485E-06 1.494E-08 555. 4.558E-09 555 5.471E-06 W 500. 9.431E-07 1.853E-08 500. 5.289E-09 500. 6.265E-06 WNW 434. 1.384E-06 1.932E-08 434. 7.394E-09 434. NW 428. 1.381E-06 8.361 E-06 2.399E-08 428. 1.050E-08 428. 7.070E-06 NNW 442. 1.388E-06 1.444E-08 442. 3.170E-08 442. 6.878E-06 3.766E-08 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B. The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed data. mode Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/Q beyond the restricted area boundary (RAB). at or "I F-7
BRAIDWOOD Revision 4 August 1999 Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles Downwind Nearest Milk Cow D/Q (1/m**2) Nearest Meat Animal D/Q (1/m*'2) Direction Radius Mixed Ground Release Radius Mixed Ground (meters) Release (meters) Release Release N 8000 2.694E-10 4.083E-10 4100 8.404E-10 1.347E- 09 NNE 8000 2.158E-10 3.221 E-1 0 8000 2.158E-10 3.221E-10 NE 8000 1.333E-10 2.015E-10 1400 1.999E-09 4.252E-09 ENE 8000 1.305E-10 1.987E-10 5300 2.604E-1 0 4.153E-10 E 8000 1.614E-10 2.447E-10 3700 5.792E-1 0 9.701E-10 ESE 8000 1.962E-10 2.874E-10 3700 7.121E-10 1.134E- 09 SE 8000 1.779E-10 2.395E-10 4300 4.998E-10 7.250E-10 SSE 8000 1.591E-10 2.270E-10 6600 2.218E-10 3.226E-10 S 8000 1.074E-10 1.704E-10 8000 1.074E-10 1.704E-10 SSW 8000 1.172E-10 1.757E-10 8000 1.172E-10 1.757E-10 I SW 8000 1.417E-10 1.921E-10 1900 1.341E-09 2.425E-09 WSW 8000 1.143E-10 1.943E-10 6100 1.800E-10 3.169E-10 W 8000 9.700E-1 1 1.724E-10 2500 6.142e-10 1.350E-09 WNW 8000 9.286E-1 1 1.723E-10 8000 9.286E-1 1 1.723E-1 0 NW 8000 1.255E-10 2.228E-10 8000 1.255E-1 0 2.228E-10 NNW 8000 1.639E-10 2.781 E-10 8000 1.639E-10 2.781 E-10 Braidwood Site Meteorological Data 1/78 - 12/87 F-8
BRAIDWOOD Revision 4 August 1999 Table F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 1.455E-04 1.097E-04 610. 5.333E-04 4.021 E-04 NNE 914. 914. 6.375E-05 4.807E-05 NE 914. 2.125E-04 1.602E-04 792. 792. 3.828E-05 2.886E-05 792. ENE 2.007E-04 1.513E-04 701. 701. 5.294E-05 3.992E-05 701. E 2.575E-04 1.941E-04 1036. 1036. 3.703E-05 2.792E-05 1036. ESE 1.718E-04 1.295E-04 2713. 2713. 1.129E-05 8.514E-06 SE 2713. 3.792E-05 2.859E-05 3414. 3414. 7.089E-06 5.345E-06 3414. SSE 2.141E-05 1.614E-05 3444. 3444. 6.047E-06 4.559E-06 3444. S 1.798E-05 1.356E-05 4633. 4633. 3.224E-06 2.431 E-06 4633. SSW 9.268E-06 6.988E-06 975. 975. 2.363E-05 1.782E-05 SW 975. 1.444E-04 1.088E-04 632. 632. 5.930E-05 4.472E-05 WSW 632. 3.694E-04 2.786E-04 555. 555. 8.469E-05 6.386E-05 W 555. 5.942E-04 4.480E-04 518. 518. 9.909E-05 7.471 E-05 518. WNW 6.292E-04 4.744E-04 503. 503. 1.205E-04 9.082E-05 503. NW 6.653E-04 5.016E-04 495. 495. 1.242E-04 9.366E-05 495. NNW 6.066E-04 4.574E-04 510. 510. 1.322E-04 9.969E-05 510. 6.144E-04 4.633E-04 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. Routine dose calculations are performed using mixed mode (vent) release data. F-9
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on lcm Depth at the Unrestricted Area Boundary for Kr-85m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)I(uCifsec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 9.989E-04 9.590E-04 610. 2.731E-03 2.164E-03 NNE 914. 914. 4.979E-04 4.785E-04 914. 1.222E-03 1.171E-03 NE 792. 792. 3.618E-04 3.481E-04 792. 1.173E-03 1.124E-03 ENE 701. 701. 4.452E-04 4.280E-04 701. 1.363E-03 1.305E-03 E 1036. 1036. 3.452E-04 3.320E-04 1036. 1.023E-03 9.809E-03 ESE 2713. 2713. 1.220E-04 1.174E-04 2713. 3.051E-04 2.930E-04 SE 3414. 3414. 8.179E-05 7.874E-05 3414. 1.970E-04 1.893E-04 SSE 3444. 3444. 6.958E-05 6.700E-05 3444. 1.634E-04 1.570E-04 S 4633. 4633. 4.OOOE-05 3.851E-05 4633, 1.051E-04 1.010E-04 SSW 975. 975. 2.413E-04 2.323E-04 975. 9.063E-04 8.688E-04 SW 632. 632. 5.199E-04 4.999E-04 . 632. 1.989E-03 1.905E-03 WSW 555. 555. 6.707E-04 6.444E-04 555, 3.061E-03 2.929E-03 W 518. 518. 6.908E-04 6.632E-04 518. 3.081E-03 2.947E-03 WNW 503. 503. 7.511E-04 7.204E-04 503. 3.126E-03 2.988E-03 NW 495. 495. 8,396E-04 8.059E-04 495. 2.915E-03 2.788E-03 NNW 510. 510. 9.023E-04 8.662E-04 510. 3.091E-03 2.958E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-10
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Area Bound Radius V VBAR Radius G GBAR Direction (meters) (mradlyr)I(uCilsec) (meters) (mradlyr)/(uCi/sec) (meters) 610. 1.125E-05 1.088E-05 610. 2.986E-05 2.888E-05 N 610. 914. 1.344E-05 1.300E-05 NNE 914. 914. 5.661 E-06 5.474E-06 4.053E-06 792. 1.311 E-05 1.268E-05 NE 792. 792. 4.192E-06 4.980E-06 701. 1.486E-05 1.437E-05 ENE 701. 701. 5.150E-06 3.911 E-06 1036. 1.145E-05 1.107E-05 E 1036. 1036. 4.044E-06 1.420E-06 2713. 3.702E-06 3.579E-06 ESE 2713. 2713. 1.468E-06 9.911 E-07 3414. 2.620E-06 2.534E-06 SE 3414. 3414. 1.025E-06 8.31 OE-07 3444. 2.101E-06 2.032E-06 SSE 3444. 3444. 8.593E-07 5.432E-07 5.253E-07 4633. 1.699E-06 1.643E-06 S 4633. 4633. 2.853E-06 2.759E-06 975. 1.042E-05 1.008E-05 SSW 975. 975. 5.897E-06 632. 2.227E-05 2.154E-05 SW 632. 632. 6.098E-06 7.599E-06 555. 3.400E-05 3.288E-05 WSW 555. 555. 7.858E-06 7.924E-06 7.663E-06 518. 3.388E-05 3.276E-05 W 518. 518. 8.219E-06 503. 3.430E-05 3.317E-05 WNW 503. 503. 8.499E-06 9.567E-06 9.251 E-06 495. 3.174E-05 3.069E-05 NW 495. 495. 9.909E-06 510. 3.393E-05 3.281 E-05 NNW 510. 510. 1.025E-05 Braidwood Site Meteorological Data 1/78 - 12/87 F-11
BRAIDWOOD Revision 4 Table F-7 (Continued) August 1999 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR G Radius GBAR (meters) (meters) (mrad/yr)I(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 3.313E-03 3.217E-03 610. NNE 914. 914. 8.088E-03 7.853E-03 NE 1.650E-03 1.602E-03 914. 3.649E-03 792. 792. 1.249E-03 3.543E-03 ENE 1.213E-03 792. 3.373E-03 701. 701. 1.516E-03 3.275E-03 E 1.472E-03 701. 4.077E-03 1036. 1036. 1.150E-04 3.958E-03 ESE 2713. 1.117E-03 1036. 2.954E-03 2713. 3.948E-04 2.868E-03 SE 3.834E-04 2713. 8.084E-04 3414. 3414. 2.559E-04 7.849E-04 SSE 2.486E-04 3414. 4.691 E-04 3444. 3444. 2.231 E-04 4.555E-04 S 2.167E-04 3444. 4.098E-04 4633. 4633. 1.162E-04 3.979E-04 SSW 1.129E-04 4633. 2.055E-04 975. 975. 8.253E-04 1.996E-04 SW 8.015E-04 975, 2.477E-03 632. 632. 1.758E-03 2.405E-03 WSW 1.707E-03 632. 5.625E-03 555. 555. 2.229E-03 5.462E-03 W 2.165E-03 555. 8.703E-03 518. 518. 2.276E-03 8.450E-03 WNW 2,210E-03 518. 8.931 E-03 503. 503. 2.431 E-03 8.671 E-03 NW 2.360E-03 503. 9.052E-03 495. 495. 2.792E-03 8.789E-03 NNW 2.711E-03 495. 8.646E-03 510. 510, 2.982E-03 2.896E-03 510. 8.395E-03 9.023E-03 8.761 E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-12
BRAIDWOOD Revision 4 Table F-7 (Continued) August 1999 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)l(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. NNE 7.997E-03 7.772E-03 610. 914. 914. 1.968E-02 1.911E-02 NE 4.019E-03 3.906E-03 914. 792. 792. 3.059E-03 8.899E-03 8.644E-03 ENE 2.974E-03 792. 8.441 E-03 701. 701. 3.725E-03 8.199E-03 E 3.621 E-03 701. 9.870E-03 1036. 1036. 2.878E-03 9.586E-03 ESE 2.798E-03 1036. 7.394E-03 2713. 2713. 1.022E-03 7.182E-03 SE 9.941E-04 2713. 2.215E-03 3414. 3414. 6.859E-04 2.152E-03 SSE 6.670E-04 3414. 1.396E-03 3444. 3444. 5.929E-04 1.357E-03 S 5.766E-04 3444. 4633. 4633. 3.301 E-04 1.185E-03 1.151E-03 SSW 3.21 OE-04 4633. 6.987E-04 975. 975. 2.066E-03 6.792E-04 SW 632. 2.009E-03 975. 6.466E-03 632. 4.389E-03 6.281 E-03 WSW 4.267E-03 632. 1.422E-02 555. 555. 5.589E-03 1.381E-02 W 5.433E-03 555. 2.182E-02 518. 518. 5.607E-03 2.119E-02 WNW 5.449E-03 518. 2.205E-02 503. 503. 5.947E-03 2.141E-02 NW 5.779E-03 503. 2.232E-02 495, 495. 6.814E-03 2.167E-02 NNW 6.622E-03 495. 2.097E-02 510. 510. 7.265E-03 2.036E-02 7.060E-03 510. 2.215E-02 2.151E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-13
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)/(uCilsec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 4.323E-03 4,199E-03 610. 7.655E-03 7.435E-03 NNE 914. 914. 1.692E-03 1.643E-03 914. 2.645E-03 2.569E-03 NE 792. 792. 1.305E-03 1.268E-03 792. 2.219E-03 2.155E-03 ENE 701. 701. 1.577E-03 1.532E-03 701. 3.016E-03 2.929E-03 E 1036, 1036. 9.092E-04 8.833E-04 1036. 1.387E-03 1.347E-03 ESE 2713. 2713. 1. 140E-04 1.108E-04 2713. 9.720E-05 9.442E-05 SE 3414. 3414. 4.392E-05 4.266E-05 3414. 2.983E-05 2.897E-05 SSE 3444. 3444. 3.822E-05 3.712E-05 3444. 3.079E-05 2.990E-05 S 4633. 4633. 9.027E-06 8.769E-06 4633. 6.198E-06 6.021 E-06 SSW 975. 975. 6.764E-04 6.571 E-04 975. 1.066E-03 1.036E-03 SW 632. 632. 1.750E-03 1.700E-03 632. 3.181E-03 3.089E-03 WSW 555. 555. 2.009E-03 1.951E-03 555. 4.608E-03 4.475E-03 W 518. 518. 2.170E-03 2.108E-03 518. 4.949E-03 4.807E-03 WNW 503. 503. 2.41 OE-03 2.341 E-03 503. 5.589E-03 5.428E-03 NW 495. 495. 3.227E-03 3.134E-03 495. 7.228E-03 7.020E-03 NNW 510. 510. 3.714E-03 3.608E-03 510. 7.735E-03 7.512E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-14
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)I(uCi/sec) N 610. 610. 8.576E-04 8.317E-04 610. 9. 142E-04 8.863E-04 NNE 914. 914. 1.453E-04 1.409E-04 914. 1.212E-04 1.175E-04 NE 792. 792. 1.302E-04 1.263E-04 792. 1.132E-04 1.098E-04 ENE 701. 701. 1.874E-04 1.817E-04 701. 1.634E-04 1.584E-04 E 1036. 1036. 5.480E-05 5.316E-05 1036. 3.996E-05 3.875E-05 ESE 2713. 2713. 2.691E-07 2.610E-07 2713. 1.795E-07 1.741E-07 SE 3414. 3414. 1.662E-08 1.612E-08 3414. 6.748E-09 6.546E-09 SSE 3444. 3444. 2.647E-08 2.568E-08 3444. 2.033E-08 1.972E-08 S 4633. 4633. 5.354E-10 5.193E-10 4633. 3.704E-1 0 3.592E-10 SSW 975. 975. 4.411E-05 4.278E-05 975. 3.803E-05 3.688E-05 SW 632. 632. 2.254E-04 2.186E-04 632. 1.980E-04 1.920E-04 WSW 555. 555. 2.280E-04 2.212E-04 555. 1.855E-04 1.799E-04 W 518. 518. 2.822E-04 2.738E-04 1.673E-04 518. 1.622E-04 WNW 503. 503. 3.444E-04 3.341E-04 503. 2.412E-04 2.339E-04 NW 495. 495. 5.611E-04 5.442E-04 495. 5.535E-04 5.366E-04 NNW 510. 510. 8.014E-04 7.772E-04 510. 9.221 E-04 8.940E-04 Braidwood Site Meteorological Data 1/78 12/87 F-I 5
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(Uci/sec) N 610. 610. 1.355E-04 1.065E-04 610. 4.922E-04 3.831 E-04 NNE 914. 914. 6.125E-05 4.839E-05 914. 1.988E-04 1.553E-04 NE 792. 792. 3.806E-05 3.031 E-05 792. 1.946E-04 1.520E-04 ENE 701. 701. 5.153E-05 4.083E-05 701. 2.358E-04 1.838E-04 E 1036. 1036. 3.805E-05 3.024E-05 1036. 1.677E-04 1.310E-04 ESE 2713. 2713. 1.232E-05 9.849E-06 2713. 4.412E-05 3.474E-05 SE 3414. 3414. 8.612E-06 6.883E-06 3414. 3.046E-05 2.401 E-05 SSE 3444. 3444. 6.862E-06 5.499E-06 3444. 2.387E-05 1.883E-05 S 4633. 4633. 4.603E-06 3.676E-16 4633. 1.914E-05 1.510E-05 SSW 975. 975. 2.441 E-05 1.949E-05 975. 1.504E-04 1.176E-04 SW 632. 632. 6.073E-05 4.813E-05 632. 3.620E-04 2.819E-04 WSW 555. 555. 8.569E-05 6.762E-05 555. 5.701 E-04 4.435E-04 W 518. 518. 9.576E-05 7.527E-05 518. 5.874E-04 4.565E-04 WNW 503. 503. 1.132E-04 8.870E-05 503. 6.171E-04 4.790E-04 NW 495. 495. 1.167E-04 9.171E-05 495. 5.515E-04 4.285E-04 NNW 510. 510. 1.244E-04 9.777E-05 510. 5.698E-04 4.432E-04 Braidwood Site Meteorological Data 1/78 - 12/87 F-16
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 2.561 E-04 2.223E-04 610. NNE 914. 914. 8.256E-04 7.023E-04 1.216E-04 1.063E-04 914. NE 792. 792. 3.481E-04 2.984E-04 8.185E-05 7.244E-05 792. ENE 701. 701. 3.399E-04 2.912E-04 1.055E-04 9.274E-05 701. E 1036. 1036. 4.017E-04 3.426E-04 8.032E-05 7.091E-05 1036. ESE 2713. 2713. 2.943E-04 2.524E-04 2.749E-05 2.446E-05 2713. SE 3414. 3414. 8.394E-05 7.303E-05 1.908E-05 1.697E-05 3414. SSE 3444. 3444. 5.806E-05 5.060E-05 1.562E-05 1.394E-05 3444. S 4633. 4633. 4.609E-05 4.022E-05 1.005E-05 8.929E-06 4633. SSW 975. 975. 3.632E-05 3.171E-05 5.390E-05 4.788E-05 975. SW 632. 632. 2.651 E-04 2.276E-04 1.243E-04 1.092E-04 632. WSW 555. 555. 6.091 E-04 5.186E-04 1.679E-04 1.466E-04 555. W 518. 518. 9.488E-04 8.060E-04 1.799E-04 1.560E-04 518. WNW 503. 503. 9.658E-04 8.185E-04 2.046E-04 1.763E-04 503. NW 495. 495. 1.OOIE-03 8.459E-04 2.185E-04 1.894E-04 495. NNW 510. 510. 2.027E-04 9.067E-04 7.683E-04 2.337E-04 510. 9.487E-04 8.059E-04 Braidwood Site Meteorological Data 1/78
- 12/87 F-17
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 2.824E-04 2.536E-04 610. 9.100E-04 NNE 914. 914. 1.355E-04 1.224E-04 914. 3.891 E-04 8.050E-04 3.466E-04 NE 792. 792. 9.079E-05 8.273E-05 792. 3.804E-04 3.389E-04 ENE 701. 701. 1.161E-04 1.052E-04 701. 4.450E-04 3.946E-04 E 1036. 1036. 8.914E-05 8.108E-05 1036. 3.295E-04 2.937E-04 ESE 2713. 2713. 3.072E-05 2.812E-05 2713. 9.583E-05 8.640E-05 SE 3414. 3414. 2.135E-05 1.953E-05 3414. 6.660E-05 6.011 E-05 SSE 3444. 3444. 1.740E-05 1.596E-05 34-14. 5.275E-05 4.767E-05 S 4633, 4633. 1.130E-05 1.033E-05 4633. 4.215E-05 3.809E-05 SSW 975. 975. 5.975E-05 5.460E-05 975. 2,978E-04 2.657E-04 SW 632. 632. 1.367E-04 1.238E-04 632. 6.726E-04 5.954E-04 WSW 555. 555. 1.830E-04 1.649E-04 555. 1.044E-03 9.224E-04 W 518. 518. 1.965E-04 1.762E-04 518. 1.056E-03 9.311E-04 WNW 503. 503. 2.231 E-04 1.990E-04 503. 1.088E-03 9.570E-04 NW 495. 495. 2.383E-04 2.135E-04 495. 9.911E-04 8.736E-04 NNW 510. 510. 2.563E-04 2.299E-04 510. 1.044E-03 9.221 E-04 Braidwood Site Meteorological Data 1/78 - 12/87 F-1 8
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-1 35m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 1.924E-03 1.856E-03 610. 4.403E-03 4.240E-03 NNE 914. 914. 9.071 E-04 8.750E-04 914. 1.913E-03 1.843E-03 NE 792. 792. 6.745E-04 6.509E-04 792. 1.628E-03 1.568E-03 ENE 701. 701. 8.149E-04 7.862E-04 701. 2.191E-03 2.11OE-03 E 1036. 1036. 5.710E-04 5.510E-04 1036. 1.368E-03 1.319E-03 ESE 2713. 2713. 1.557E-04 1.503E-04 2713. 2.479E-04 2.391 E-04 SE 3414. 3414. 8.843E-05 8.536E-05 3414. 1.163E-04 1. 122E-04 SSE 3444. 3444. 7.741E-05 7.472E-05 S 3444. 1.062E-04 1.025E-04 4633. 4633. 3.277E-05 3.163E-05 SSW 4633. 4.020E-05 3.879E-05 975. 975. 4.100E-04 3.957E-04 975. SW 632. 1.01IE-03 9.747E-04 632. 8.898E-04 8.587E-04 632. 2.532E-03 WSW 555. 2.439E-03 555. 1.092E-03 1.054E-03 555. 3.989E-03 W 518. 3.842E-03 518. 1.187E-03 1.145E-03 518. 4.362E-03 WNW 503. 4.200E-03 503. 1.304E-03 1.258E-03 503. 4.495E-03 NW 495. 4.327E-03 495. 1.546E-03 1.490E-03 495. 4.695E-03 NNW 510. 4.521 E-03 510. 1.673E-03 1.613E-03 510. 4.688E-03 4.514E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-19
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe- 135 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mradlyr)/(uCi/sec) N 610. 610. 1.353E-03 1.307E-03 610. 3.674E-03 3.548E-03 NNE 914. 914. 6.781 E-04 6.554E-04 914. 1.652E-03 1.596E-03 NE 792. 792. 4.952E-04 4.788E-04 792. 1.599E-03 1.545E-03 ENE 701. 701. 6.084E-04 5.880E-04 701. 1.833E-03 1.770E-03 E 1036. 1036. 4.753E-04 4.595E-04 1036. 1.395E-03 1.348E-03 ESE 2713. 2713. 1.700E-04 1.644E-04 2713. 4.326E-04 4.181E-04 SE 3414. 3414. 1.160E-04 1.121 E-04 3414. 2.914E-04 2.816E-04 SSE 3444. 3444. 9.782E-05 9.459E-05 3444. 2.377E-04 2.297E-04 S 4633. 4633. 5.868E-05 5.674E-05 4633. 1.698E-04 1.641E-04 SSW 975. 975. 3.328E-04 3.217E-04 975. 1.253E-03 1.211E-03 SW 632. 632. 7.144E-04 6.906E-04 632. 2.708E-03 2.615E-03 WSW 555. 555. 9.205E-04 8.896E-04 555. 4.150E-03 4.007E-03 W 518. 518. 9.408E-04 9.091 E-04 518. 4.151E-03 4.008E-03 WNW 503. 503. 1.018E-03 9.833E-04 503. 4.203E-03 4.058E-03 NW 495. 495. 1.139E-03 1.101E-03 495. 3.908E-03 3.773E-03 NNW 510. 510. 1.225E-03 1.183E-03 510. 4.166E-03 4.022E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-20
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. NNE 6.360E-04 6.154E-04 610. 914. 914. 2.578E-04 1.202E-03 1.164E-03 NE 2.494E-04 914. 792. 792. 1.950E-04 4.345E-04 4.205E-04 ENE 701. 1.887E-04 792. 3.640E-04 701. 2.355E-04 3.522E-04 E 2.279E-04 701. 1036. 1036. 1.407E-04 4.977E-04 4.816E-04 ESE 2713. 1.361E-04 1036. 2.400E-04 2713. 2.042E-05 1.976E-05 2.322E-04 SE 3414. 3414. 2713. 1.931E-05 1.868E-05 8.468E-06 8.195E-06 3414. SSE 3444. 3444. 6.393E-06 6.186E-06 7.384E-06 7.146E-06 3444. S 4633. 4633. 6.474E-06 6.265E-06 1.951E-06 1.888E-06 4633. SSW 975. 975. 1.457E-06 1.410E-06 SW 1.038E-04 1.004E-04 975. 632. 632. 2.577E-04 1.812E-04 1.753E-04 WSW 2.493E-04 632. 5.246E-04 555. 555. 2.977E-04 5.076E-04 W 2.881E-04 555. 7.771 E-04 518. 518. 3.247E-04 7.519E-04 WNW 3.143E-04 518. 8.444 E-04 503. 503. 3.635E-04 8.170E-04 NW 3.517E-04 503. 495. 495. 4.769E-04 9.371 E-04 9.067E-04 NNW 5.441 E-04 4.615E-04 495. 510. 510. 5.265E-04 1.167E-03 1.129E-03 510. 1.222E-03 1.182E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-21
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)I(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 4.201 E-03 4.079E-03 610. 9.169E-03 8.898E-03 NNE 914. 914. 1.982E-03 1.925E-03 NE 914. 3.986E-03 3.869E-03 792. 792. 1.504E-03 1.460E-03 792. ENE 3.379E-03 3.280E-03 701. 701. 1.805E-03 1.753E-03 701. E 4.549E-03 4.415E-03 1036. 1036. 1.262E-03 1.225E-03 1036. ESE 2.830E-03 2.747E-03 2713. 2713. 3.395E-04 3.297E-04 2713. SE 5.079E-04 4.931 E-04 3414. 3414. 1.926E-04 1.871E-04 3414. SSE 2.381E-04 2.312E-04 3444. 3444. 1.685E-04 1.636E-04 3444. S 2.185E-04 2.121E-04 4633. 4633. 7.045E-05 6.842E-05 4633. SSW 8.174E-05 7.937E-05 975. 975. 9.144E-04 8.880E-04 975. 2.091 E-03 2.030E-03 SW 632. 632. 1.991E-03 1.934E-03 632. 5.266E-03 5.072E-03 WSW 555. 555. 2.429E-03 2.359E-03 555. 8.199E-03 7.957E-03 W 518. 518. 2.609E-03 2.534E-03 518. 8.973E-03 8.708E-03 WNW 503. 503. 2.834E-03 2.751 E-03 503. 9.247E-03 8.973E-03 NW 495. 495. 3.387E-03 3.288E-03 495. 9.733E-03 9.445E-03 NNW 510. 510. 3.657E-03 3.551 E-03 510. 9.712E-03 9.425E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-22
BRAIDWOOD Revision 4 August 1999 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 610. 610. 5.141E-03 4.977E-03 610. 1.283E-02 1.242E-02 NNE 914. 914. 2.568E-03 2.485E-03 914. 5.780E-03 5.595E-03 NE 792. 792. 1.935E-03 1.873E-03 792. 5.421 E-03 5.248E-03 ENE 701. 701. 2.357E-03 2.282E-03 701. 6.445E-03 6.239E-03 E 1036. 1036. 1.803E-03 1.746E-03 1036. 4.745E-03 4.593E-03 ESE 2713. 2713. 6.281 E-04 6.080E-04 2713. 1.352E-03 1.309E-03 SE 3414. 3414. 4.128E-04 3.996E-04 3414. 8.140E-04 7.880E-04 SSE 3444. 3444. 3.580E-04 3.466E-04 3444. 7.007E-04 6.783E-04 S 4633. 4633. 1.924E-04 1.862E-04 4633. 3.770E-04 3.650E-04 SSW 975. 975. 1.289E-03 1.247E-03 975. 4.067E-03 3.937E-03 SW 632. 632. 1.991 E-03 1.934E-03 632. 9.104E-03 8.813E-03 WSW 555. 555. 2.429E-03 2.359E-03 555. 1.404E-02 1.359E-02 W 518. 518. 3.562E-03 3.448E-03 518. 1.430E-02 1.384E-02 WNW 503. 503. 3.806E-03 3.685E-03 503. 1.449E-02 1.403E-02 NW 495. 495. 4.350E-03 4.211 E-03 495. 1.371 E-02 1.327E-02 NNW 510. 510. 4.647E-03 4.498E-03 510. 1.439E-02 1.393E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-23
BRAIDWOOD Revision 4 Table F-7a August 1999 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 3.994E-04 3.012E-04 305. 1.521E-03 1. 147E-03 NNE 265. 265. 3.883E-04 2.928E-04 265. 1.406E-03 NE 299. 299. 1.555E-04 1.060E-03 1.173E-04 299. 9.211E-04 6.945E-04 ENE 361. 361. 1.372E-04 1.034E-04 361. 7.062E-04 5. 325E-04 E 355. 355. 1.785E-04 1.346E-04 355. 9.139E-04 6.891 E-04 ESE 425. 425. 1.505E-04 1.135E-04 425. 7.634E-04 5.756E-04 SE 448. 448. 1.196E-04 9.017E-05 448. 6.583E-04 4.964E-04 SSE 540. 540. 6.996E-05 5.275E-05 540. 4.053E-04 3.056E-04 S 530. 530. 6.499E-05 4.900E-05 530. 4.639E-04 3.498E-04 SSW 540. 540. 5.532E-05 4.171E-05 540. 3.829E-04 2.887E-04 SW 632. 632. 5.930E-05 4.472E-05 632. 3.694E-04 2.786E-04 WSW 555. 555. 8.469E-05 6.386E-05 555. 5.942E-04 4.480E-04 W 500. 500. 1.045E-04 7.876E-05 500. 6.646E-04 5.011 E-04 WNW 434. 434. 1.497E-04 1.129E-04 434. 8.320E-04 6.273E-04 NW 428. 428. 1.537E-04 1.159E-04 428. 7.562E-04 NNW 442. 442. 1.231 E-04 442. 5.702 E-04 1.633E-04 7.667E-04 5.781 E-04 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. Routine dose calculations are performed using mixed mode release data. F-24
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 2.263E-03 2.169E-03 305. 6.552E-03 6.259E-03 NNE 265. 265. 2.146E-03 2.056E-03 265. 5.928E-03 5.662E-03 NE 299. 299. 1.094E-03 1.050E-03 299. 4.111E-03 3.928E-03 ENE 361. 361. 9.475E-04 9.097E-04 361. 3.165E-03 3.025E-03 E 355. 355. 1.197E-03 1.149E-03 355. 4.072E-03 3.891 E-03 ESE 425. 425. 1.073E-03 1.031 E-03 425. 3.584E-03 3.427E-03 SE 448. 448. 9.074E-04 8.718E-04 448. 3.167E-03 3.029E-03 SSE 540. 540. 6.068E-04 5.836E-04 540. 2.086E-03 1.997E-03 S 530. 530. 5.227E-04 5.023E-04 530. 2.351E-03 2.249E-03 SSW 540. 540. 4.797E-04 4.613E-04 540. 1.999E-03 1.913E-03 SW 632. 632. 5.199E-04 4.999E-04 632. 1.989E-03 1.905E-03 WSW 555. 555. 6.707E-04 6.444E-04 555. 3.061 E-03 2.929E-03 W 500. 500. 7.204E-04 6.915E-04 500. 3.224E-03 3.083E-03 WNW 434. 434. 8.947E-04 8.578E-04 434. 3.764E-03 3.597E-03 NW 428. 428. 9.954E-04 9.552E-04 428. 3.505E-03 3.351 E-03 NNW 442. 442. 1.068E-03 1.025E-03 442. 3.712E-03 3.551E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-25
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR G Radius GBAR (meters) (meters) (mrad/yr)l(uCilsec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 2.521 E-05 2.437E-05 305. 7.053E-05 6.820E-05 NNE 265. 265. 2.389E-05 2.310E-05 265. 6.351 E-05 6.141 E-05 NE 299. 299. 1.248E-05 1.207E-05 299. 4.443E-05 4.296E-05 ENE 361. 361. 1,083E-05 1.047E-05 361. 3.404E-05 3.292E-05 E 355. 355. 1.366E-05 1.320E-05 355, 4.396E-05 4.251E-05 ESE 425. 425. 1.220E-05 1.180E-05 425. 3.889E-05 3.760E-05 SE 448. 448. 1.042E-05 1.008E-05 448, 3.470E-05 3.355E-05 SSE 540. 540. 7.029E-06 6.797E-06 540. 2.290E-05 2.215E-05 S 530. 530. 6.111E-06 5.909E-06 530. 2.632E-05 2.545E-05 SSW 540. 540. 5.594E-06 5.409E-06 540. 2.217E-05 2.144E-05 SW 632. 632. 6.098E-06 5.897E-06 632. 2.227E-05 2.154E-05 WSW 555. 555. 7.858E-06 7.599E-06 555. 3.400E-05 3.288E-05 W 500. 500. 8.255E-06 7.983E-06 500. 3.541 E-05 3.424E-05 WNW 434. 434. 1.009E-05 9.757E-06 434. 4.111 E-05 3,976E-05 NW 428. 428. 1.131 E-05 1.093E-05 428. 3.802E-05 3.677E-05 NNW 442. 442. 1.209E-05 1. 169E-05 442. 4.056E-05 3.922E-05 Braidwood Site Meteorological Data 1/78 - 12/87 F-26
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 7.480E-03 7.264E-03 305. 1.972E-02 1.915E-02 NNE 265. 265. 7.1 OOE-03 6.895E-03 265. 1.802E-02 1.749E-02 NE 299. 299. 3.780E-03 3.671 E-03 299. 1.225E-02 1.189E-02 ENE 361. 361. 3.246E-03 3.152E-03 361. 9.572E-03 9.294E-03 E 355. 355. 4.060E-03 3.943E-03 355. 1.220E-02 1.185E-02 ESE 425. 425. 3.644E-03 3.539E-03 425. 1.068E-02 1.037E-02 SE 448. 448. 3.081 E-03 2.992E-03 448. 9.262E-03 8.992E-03 SSE 540. 540. 2.111E-03 2.050E-03 540. 6.149E-03 5.971 E-03 S 530. 530. 1.762E-03 1.711E-03 530. 6.549E-03 6.359E-03 SSW 540. 540. 1.664E-03 1.616E-03 540. 5.727E-03 5.561 E-03 SW 632. 632. 1.758E-03 1.707E-03 632. 5.625E-03 5.462E-03 WSW 555. 555. 2.229E-03 2.165E-03 555. 8.703E-03 8.450E-03 W 500. 500. 2.375E-03 2.306E-03 500. 9.363E-03 9.090E-03 WNW 434. 434. 2.903E-03 2.818E-03 434. 1.098E-02 1.066E-02 NW 428. 428. 3.315E-03 3.219E-03 428. 1.044E-02 1.014E-02 NNW 442. 442. 3.533E-03 3.431 E-03 442. 1.090E-02 1.058E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-27
BRAIDWOOD Revision 4 Table F-7a (Continued) Augustl199 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 Downwind Restricted Mixed Mode (Vent) Release Direction Ground Level Release Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mradyr)/(uCi/sec) N 305. NNE 305. 1.790E-02 1.739E-02 265. 265. 305. 4.712E-02 NE 1.698E-02 1.650E-02 4.574E-02 299. 299. 265. 4.272E-02 ENE 9.121E-03 8.865E-03 4.146E-02 361. 361. 299. 2.947E-02 E 7.868E-03 7.647E-03 2.861 E-02 355. 355. 361. 2.281E-02 ESE 9.873E-03 9.595E-03 2.214E-02 425. 425. 355. 2.928E-02 SE 8.818E-03 8.571E-03 2.842E-02 448. 448. 425. 2.578E-02 SSE 7.516E-03 7.306E-03 2.503E-02 540. 540. 448. 2.271E-02 S 5.155E-03 5.012E-03 2.205E-02 530. 530. 540. 1.505E-02 SSW 4.382E-03 4.260E-03 1.462E-02 540. 540. 530. 1.666E-02 SW 4.092E-03 3.978E-03 1.618E-02 632. 632. 540. 1.429E-02 WSW 4.389E-03 4.267E-03 1.388E-02 555. 555. 632. 1.422E-02 W 5.589E-03 5.433E-03 1.381E-02 500. 500. 555. 2.182E-02 WNW 5.844E-03 5.680E-03 2.119E-02 434. 434. 500. 2.308E-02 NW 7.074E-03 6.873E-03 2.241E-02 428. 428. 434. 2.690E-02 NNW 8.064E-03 7.837E-03 2.612E-02 442. 442. 8-580E-03 8.338E-03 428. 2.520E-02 2.447E-02 442. 2.660E-02 2.583E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-28
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-89 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 1.243E-02 1.208E-02 NNE 265. 305. 2.613E-02 265. 1.213E-02 1.178E-02 2.538E-02 NE 299. 265. 2.655E-02 299. 6.070E-03 5.896E-03 2.579E-02 ENE 361. 299. 1.438E-02 361. 4.638E-03 4.506E-03 1.397E-02 E 355. 361. 1.132E-02 355. 5.715E-03 5.551 E-03 1.099E-02 ESE 425. 355. 1.360E-02 425. 5.133E-03 4.986E-03 1.321E-02 SE 448. 448. 425. 1.084E-02 4.043E-03 3.927E-03 1.053E-02 SSE 540. 540. 448. 8.014E-03 2.636E-03 2.561 E-03 7.784E-03 S 530. 540. 5.137E-03 530. 1.936E-03 1.880E-03 4.990E-03 SSW 540. 530. 4.055E-03 540. 1.970E-03 1.914E-03 3.938E-03 SW 632. 540. 4.039E-03 632. 1.750E-03 1.700E-03 3.922E-03 WSW 555. 632. 3.181E-03 555. 2.009E-03 1.951 E-03 3.089E-03 W 500. 500. 555. 4.608E-03 2.313E-03 2.247E-03 4.475E-03 WNW 434. 500. 5.385E-03 434. 3.129E-03 3.040E-03 5.230E-03 NW 428. 434. 7.749E-03 428. 4.11OE-03 3.993E-03 7.526E-03 NNW 442. 442. 4.671 E-03 4.537E-03 428. 9.703E-03 9.424E-03 442. 1.017E-02 9.878E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-29
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)I(uCi/sec) (mrad/yr)/(uCi/sec)
. (meters)
N 305. 305. 5.688E-03 5.515E-03 305. 8.218E-03 7.966E-03 NNE 265. 265. 6.051E-03 5.868E-03 265. 9.375E-03 9.087E-03 NE 299. 299. 2.447E-03 2.374E-03 299. 3.836E-03 3.719E-03 ENE 361. 361. 1.41OE-03 1.367E-03 361. 1.941E-03 1.882E-03 E 355. 355. 1.896E-03 1.839E-03 355. 2.575E-03 2.496E-03 ESE 425. 425. 1.516E-03 1.470E-03 425. 1.818E-03 1.762E-03 SE 448. 448. 1.032E-03 1.OO1E-03 448. 1.147E-03 1.112E-03 SSE 540. 540. 5.186E-04 5.030E-04 540. 6.013E-04 5.830E-04 S 530. 530. 3.564E-04 3.457E-04 530. 4.307E-04 4.176E-04 SSW 540. 540. 3.743E-04 3.630E-04 540. 4.345E-04 4.213E-04 SW 632. 632. 2.254E-04 2.186E-04 632. 1.980E-04 1.920E-04 WSW 555. 555. 2.280E-04 2.212E-04 555. 1.855E-04 1.799E-04 W 500. 500. 3.175E-04 3.080E-04 500. 1. 971E-04 1.911 E-04 WNW 434. 434. 5.483E-04 5.319E-04 434, 4.559E-04 4.420E-04 NW 428. 428. 8.796E-04 8.532E-04 428. 9.766E-04 9.468E-04 NNW 442. 442. 1.222E-03 1.185E-03 442. 1.523E-03 1.477E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-30
BRAIDWOOD ARuegvissio n 4 Table F-7a (Continued) t 1999 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe- 131 m Downwind Restricted Mixed Mode (Vent) Release Direction Ground Level Release Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mradAyr)(uCi/sec) N 305. 305. 3.585E-04 2.801 E-04 NNE 265. 305. 1.342E-03 265. 3.471E-04 2.71 OE-04 1.040E-03 NE 299. 265. 1.225E-03 299. 1.442E-04 9.489E-04 ENE 361. 1.135E-04 299. 8.221 E-04 361. 1.274E-04 6.377E-04 E 355. 1.002E-04 361. 355. 1.664E-04 6.227E-04 4.832E-04 ESE 425. 1.307E-04 355. 425. 1.406E-04 8.136E-04 6.311E-04 SE 448. 1.108E-04 425. 448. 1.152E-04 6.887E-04 5.349E-04 SSE 540. 9.088E-05 448. 6.093E-04 540. 6.798E-05 5.395E-05 4.733E-04 S 530. 540. 3.772E-04 530. 6.550E-05 5.172E-05 2.936E-04 SSW 540. 530. 4.533E-04 540. 5.419E-05 4.299E-05 3.523E-04 SW 632. 540. 3.656E-04 632. 6.073E-05 4.813E-05 2.846E-04 WSW 555. 632. 3.620E-04 555. 8.569E-05 6.762E-05 2.819E-04 W 500. 555. 5.701 E-04 500. 1.006E-04 7.904E-05 4.435E-04 WNW 434. 500. 6.184E-04 434. 1.391E-04 4.805E-04 NW 428. 1.088E-04 434. 7.616E-04 428. 1.429E-04 5.907E-04 NNW 442. 442. 1.521E-04 1.121 E-04 428. 6.807E-04 I. 194E-04 5.285E-04 442. 7.027E-04 5.461 E-04 Braidwood Site Meteorological Data 1/78 - 12/87 F-31
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-1 33m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)I(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 6.308E-04 5.411E-04 305. 2.1135E-03 1.798E-03 NNE 265. 265. 6.053E-04 5.184E-04 265. 1.940E-03 1.632E-03 NE 299. 299. 2.759E-04 2.399E-04 299. 1.321E-03 1.115E-03 ENE 361. 361. 2.417E-04 2.099E-04 361. 1.005E-03 8.488E-04 E 355. 355. 3.11OE-04 2.695E-04 355. 1.307E-03 1.103E-03 ESE 425. 425. 2.701 E-04 2.350E-04 425. 1. 125E-03 9.516E-04 SE 448. 448. 2.251 E-04 1.964E-04 448. 9.971 E-04 8.442E-04 SSE 540. 540. 1.413E-04 1.245E-04 540. 6.325E-04 5.379E-04 S 530. 530. 1.293E-04 1.131 E-04 530. 7.461 E-04 6.326E-04 SSW 540. 540. 1.123E-04 9.889E-05 540. 6.124E-04 5.209E-04 SW 632. 632. 1.243E-04 1.092E-04 632. 6.091 E-04 5.186E-04 WSW 555. 555. 1.679E-04 1.466E-04 555. 9.488E-04 8.060E-04 W 500. 500. 1.883E-04 1.632E-04 500. 1.014E-03 8.589E-04 WNW 434. 434. 2.477E-04 2.129E-04 434. 1.222E-03 1.031E-03 NW 428. 428. 2.634E-04 2.277E-04 428. 1.107E-03 9.360E-04 NNW 442. 442. 2.813E-04 2.434E-04 442. 1.157E-03 9.803E-04 Braidwood Site Meteorological Data 1/78 - 12/87 F-32
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 6.81 OE-04 6.050E-04 NNE 305. 2.299E-03 2.013E-03 265. 265. 6.509E-04 5.774E-04 NE 265. 2.084E-03 1.823E-03 299. 299. 2.984E-04 2.679E-04 299. ENE 1.431 E-03 1.256E-03 361. 361. 2.612E-04 2.343E-04 361. E 1.090E-03 9.571 E-04 355. 355. 3.363E-04 3.011E-04 355. ESE 1.414E-03 1.241E-03 425. 425. 2.954E-04 2.656E-04 425. SE 1.226E-03 1.079E-03 448. 448. 2.460E-04 2.216E-04 448. SSE 1.088E-03 9.581 E-04 540. 540. 1.555E-04 1.411E-04 540. S 6.963E-04 6.158E-04 530. 530. 1.408E-04 1.270E-04 SSW 530. 8.174E-04 7.209E-04 540. 540. 1.231E-04 1.117E-04 SW 540. 6.754E-04 5.974E-04 632. 632. 1.367E-04 1.238E-04 WSW 632. 6.726E-04 5.954E-04 555. 555. 1.830E-04 1.649E-04 W 555. 1.044E-03 9.224E-04 500. 500. 2.055E-04 1.842E-04 WNW 500. 1.108E-03 9.759E-04 434. 434. 2.689E-04 2.394E-04 NW 434. 1.323E-03 1.160E-03 428. 428. 2.860E-04 2.557E-04 NNW 428. 1.204E-03 1.059E-03 442. 442. 3.071 E-04 2.749E-04 442. 1.266E-03 1.1 16E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-33
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-1 35m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCilsec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 4.596E-03 4.429E-03 305. 1.180E-02 1.135E-02 NNE 265. 265. 4.387E-03 4.227E-03 265. 1.125E-02 1.082E-02 NE 299. 299. 2.254E-03 2.174E-03 299. 7.028E-03 6.764E-03 ENE 361. 361. 1.883E-03 1.816E-03 361. 5.738E-03 5.523E-03 E 355. 355. 2.326E-03 2.242E-03 355. 7.076E-03 6.811E-03 ESE 425. 425. 2.121E-03 2.046E-03 425. 6.001E-03 5.778E-03 SE 448. 448. 1.723E-03 1.662E-03 448. 4.819E-03 4.640E-03 SSE 540. 540. 1.178E-03 1.137E-03 540. 3.220E-03 3.101E-03 S 530. 530. 9.052E-04 8.734E-04 530. 2.852E-03 2.747E-03 SSW 540. 540. 9.038E-04 8.720E-04 540. 2.739E-03 2.638E-03 SW 632. 632. 8.898E-04 8.587E-04 632. 2.532E-03 2.439E-03 WSW 555. 555. 1.092E-03 1.054E-03 555. 3.989E-03 3.842E-03 W 500. 500. 1.246E-03 1.202E-03 500. 4.617E-03 4.446E-03 WNW 434. 434. 1.593E-03 1.536E-03 434. 5.652E-03 5.441E-03 NW 428. 428. 1.869E-03 1.802E-03 428. 5.820E-03 5.603E-03 NNW 442. 442. 2.013E-03 1.940E-03 442. 5.812E-03 5.596E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-34
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-i135 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)I(uCi/sec) N 305. 305. 3.039E-03 2.936E-03 305. 8.709E-03 8.406E-03 NNE 265. 265. 2.880E-03 2.781 E-03 265. 7.856E-03 7.583E-03 NE 299. 299. 1.481E-03 1.431 E-03 299. 5.482E-03 5.292E-03 ENE 361. 361. 1.284E-03 1.241 E-03 361. 4.211 E-03 4.065E-03 E 355. 355. 1.621E-03 1.567E-03 355. 5.425E-03 5.237E-03 ESE 425. 425. 1.455E-03 1.406E-03 425. 4.794E-03 4.629E-03 SE 448. 448. 1.235E-03 1.194E-03 448. 4.257E-03 4.1 lOE-03 SSE 540. 540. 8.285E-04 8.008E-04 540. 2.811E-03 2.714E-03 S 530. 530. 7.163E-04 6.923E-04 530. 3.197E-03 3.087E-03 SSW 540. 540. 6.561 E-04 6.342E-04 540. 2.709E-03 2.615E-03 SW 632. 632. 7.144E-04 6.906E-04 632. 2.708E-03 2.615E-03 WSW 555. 555. 9.205E-04 8.896E-04 555. 4.150E-03 4.007E-03 W 500. 500. 9.804E-04 9.473E-04 500. 4.340E-03 4.190E-03 WNW 434. 434. 1.21 OE-03 1.168E-03 434. 5.044E-03 4.869E-03 NW 428. 428. 1.348E-03 1.302E-03 428. 4.686E-03 4.524E-03 NNW 442. 442. 1.446E-03 1.397E-03 442. 4.987E-03 4.815E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-35
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)l(uCilsec) (meters) (mradlyr)I(uCi/sec) N 305. 305. 1.764E-03 1.707E-03 305. 3.915E-03 3.788E-03 NNE 265. 265. 1.712E-03 1.657E-03 265. 3.949E-03 3.821E-03 NE 299. 299. 8.519E-04 8.244E-04 299. 2.178E-03 2.108E-03 ENE 361. 361. 6.624E-04 6.410E-04 361. 1.748E-03 1.692E-03 E 355. 355. 8.157E-04 7.893E-04 355. 2.100E-03 2.032E-03 ESE 425. 425. 7.381E-04 7.142E-04 425. 1.690E-03 1 636E-03 SE 448. 448. 5.802E-04 5.615E-04 448. 1.259E-03 1.219E-03 SSE 540. 540. 3.822E-04 3.699E-04 540. 8.154E-04 7.890E-04 S 530. 530. 2.803E-04 2.713E-04 530. 6.471E-04 6.261E-04 SSW 540. 540. 2.864E-04 2.772E-04 540. 6.459E-04 6.250E-04 SW 632. 632. 2.577E-04 2.493E-04 632. 5.246E-04 5.076E-04 WSW 555. 555. 2.977E-04 2.881E-04 555. 7.771E-04 7.519E-04 W 500. 500. 3.453E-04 3.341E-04 500. 9.141E-04 8.844E-04 WNW 434. 434. 4.671E-04 4.520E-04 434. 1.275E-03 1.234E-03 NW 428. 428. 6.017E-04 5.823E-04 428. 1.543E-03 1,493E-03 NNW 442. 442. 6.784E-04 6.565E-04 442. 1.588E-03 1.537E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-36
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Downwind Restricted Mixed Mode (Vent) Release Direction Ground Level Release Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. NNE 1.OO1E-02 9.714E-03 305. 265. 265. 2.457E-02 2.384E-02 NE 9.553E-03 9.273E-03 265. 299. 299. 2.347E-02 2.278E-02 ENE 5.016E-03 4.870E-03 299. 361. 361. 4.169E-03 1.459E-02 1.416E-02 E 355. 4.048E-03 361. 355. 5.137E-03 1.195E-02 1.160E-02 ESE 425. 4.988E-03 355. 425. 4.679E-03 1.471E-02 1.427E-02 SE 448. 4.543E-03 425. 448. 3.827E-03 1.247E-02 1.210E-02 SSE 540. 3.716E-03 448. 540. 2.630E-03 9.982E-03 9.687E-03 S 530. 2.554E-03 540. 6.694E-03 530. 2.023E-03 1.964E-03 6.497E-03 SSW 540. 530. 5.857E-03 540. 2.021E-03 1.962E-03 5.684E-03 SW 632. 540. 5.661 E-03 632. 1.991E-03 1.934E-03 5.495E-03 WSW 555. 555. 632. 5.226E-03 2.429E-03 2.359E-03 5.072E-03 W 500. 555. 8.199E-03 500. 2.739E-03 2.659E-03 7.957E-03 WNW 434. 434. 500. 9.502E-03 3.459E-03 3.358E-03 9.221E-03 NW 428. 434. 1.164E-02 428. 4.093E-03 3.974E-03 1.130E-02 NNW 442. 442. 4.399E-03 4.271 E-03 428. 1.207E-02 1.172E-02 442. 1.204E-02 1.169E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-37
BRAIDWOOD Revision 4 August 1999 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mradlyr)I(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 305. 305. 1.160E-02 1.122E-02 305. 3.106E-02 3.006E-02 NNE 265. 265, 1.101E-02 1.065E-02 265. 2.826E-02 2.736E-02 NE 299. 299. 5.833E-03 5.646E-03 299. 1.936E-02 1.874E-02 ENE 361. 361. 5.023E-03 4.863E-03 361. 1.505E-02 1.456E-02 E 355. 355. 6.295E-03 6.094E-03 355. 1.925E-02 1.864E-02 ESE 425. 425. 5.640E-03 5.459E-03 425. 1.689E-02 1.635E-02 SE 448. 448. 4.783E-03 4.630E-03 448. 1.477E-02 1.430E-02 SSE 540. 540. 3.262E-03 3.157E-03 540. 9.781 E-03 9.468E-03 S 530. 530. 2,756E-03 2.667E-03 530. 1.066E-02 1.032E-03 SSW 540. 540. 2.580E-03 2.497E-03 540. 9.211 E-03 8.917E-03 SW 632. 632. 2.748E-03 2.660E-03 632. 9.104E-03 8.813E-03 WSW 555. 555. 3.504E-03 3.392E-03 555. 1.404E-02 1.359E-02 W 500. 500. 3.715E-03 3.596E-03 500. 1.498E-02 1.450E-02 WNW 434. 434. 4.539E-03 4.393E-03 434. 1.753E-02 1.697E-02 NW 428. 428. 5.159E-03 4.994E-03 428. 1.652E-02 1.599E-02 NNW 442. 442. 5.499E-03 5.323E-03 442. 1.734E-02 1.679E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-38
BRAIDWOOD Revision 4 August 1999 Supplemental Table A Mixed Mode Joint Frequency Distribution Table Summaries 203 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .290 .321 .441 .315 .303 .256 .292 .266 .474 .369 .202 .197 .191 .274 .463 .421 5.076 B .197 .241 .284 .208 .205 .167 .196 .220 .352 .288 .190 .192 .206 .225 .327 .335 3.833 C .321 .302 .421 .293 .201 .203 .277 .312 .437 .404 .322 .342 .373 .399 .457 .409 5.474 D 1.523 1.590 2.149 1.974 1.372 1.014 1.324 1.529 2.031 1.900 1.899 1.846 2.109 2.248 2.191 2.014 28.713 E .679 .612 .764 .976 .986 .870 1.136 1.439 2,079 1.501 1,065 .921 .993 1.133 .922 .790 16866 F .344 .278 .260 .298 .387 .496 .530 .438 .559 .526 .386 .397 .589 .688 .556 417 7148 G .166 .095 .098 .078 .156 .174 .270 .213 .186 .199 .258 .210 .253 .266 .184 .159 2.966 Total 3.520 3.439 4.418 4.143 3.611 3.180 4.025 4.418 6.118 5.187 4.322 4.104 4.714 5.231 5.100 4.545 70.076 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total
.45 .008 .016 .027 .025 .001 .000 .017 .017 .001 .001 .002 .016 .037 .026 .001 026 222 1.05 .044 .032 .042 .045 .026 .025 .036 .031 .032 .023 .033 .025 .037 .035 .040 .026 .532 2.05 .224 .266 .281 .260 .239 .213 .243 .225 .237 .220 .208 .208 .262 .244 .244 .243 3.819 3.05 .405 .426 .540 .610 .459 .334 .467 .438 .596 .383 .393 .384 .447 .437 .507 .487 7,313 4.05 .669 .622 .756 .973 .670 .453 .614 .663 .695 .543 596 .663 .678 .702 .749 .782 10829 5.05 .624 .519 .875 .926 .681 .482 .869 .639 .769 .677 .711 .681 .738 .782 .89 .808 11.470 6.05 .670 .607 .761 .675 .674 .587 .. 657 .729 .944 .825 .833 .766 .788 .975 .909 .876 12.279 8.05 .732 .789 .956 .534 .726 .919 1.073 1.227 2.070 1.858 1.268 1.131 1.378 1.598 1.381 1.041 18.680 10.05 .137 .154 .174 .094 .127 .158 .235 .423 .727 .621 .265 .216 .331 .404 .359 .245 4.667 13.05 .007 .008 .005 .002 .008 .010 .014 .028 .047 .037 .012 .012 .017 .028 .020 .012 265 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 000 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 3.520 3439 4.418 4.143 3.611 3.180 4.025 4.418 6.118 5.187 4.322 4.104 4.714 5.231 5100 45545 70,076 NOTE: Wind directions in tables are presented in "wind from" and not "wind to" direction.
F-39
BRAIDWOOD Revision 4 August 1999 In order to determine the final mixed mode values, 70.076% of the elevated value (presented in the 250 FT Mixed Mode table) and 29.924% of the ground level value (presented in the 30 FT Mixed Mode table) are used to calculate the final values. F-40
BRAIDWOOD Revision 4 August 1999 A - Continued Supplemental Table Mixed Mode Joint Frequency Distribution Table Summaries 203 Foot Elevation Data Summary Table of Percent by Speed and Class Class A B C D E F G Speed
.45 .006 .005 .006 .075 .052 .048 .030 1.05 .014 .025 .027 .200 .108 .071 .086 2.05 .175 .197 .378 1.756 .659 .372 .283 3.05 .500 .593 .836 3.100 1.206 .683 .393 405 .803 .697 1.005 4.441 2.225 1.083 .575 5.05 .880 .674 .921 4.456 2.845 1.230 .464 6.05 .885 .588 .806 4.760 3.357 1.417 .466 805 1.469 .854 1.160 7.631 5.000 1.976 .591 1005 .325 .190 .320 2.165 1.332 .259 .076 13.05 .018 .011 .015 .129 .081 .009 .002 1800 .000 .000 .000 .000 .000 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F-41
BRAIDWOOD Revision 4 August 1999 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 34 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .068 071 .077 .054 .100 .075 .110 .135 B .054 .044 .278 .215 .062 050 .127 .270 .257 .176 2 125
.059 .031 .035 .049 .061 .083 .172 C .123 .058 .045 .121 .178 .150 .098
.067 .056 .098 .059 .044 .049 .091 1.357
.124 .212 .133 .121 .082 .212 .278 D .453 .551 .613 .453 .420 .219 .164 2.005
.423 .641 .926 1.487 1.230 .697 E .304 .387 .717 1.084 1.496 1.044 .889 13.125
.249 .180 .230 .368 .580 1.093 1.991 1.311 .435 .346 .299 .343 .227 F .044 .063 .050 .059 .086 .160 .317 8659
.161 .137 .339 .306 .077 .133 G .022 .006 .144 .130 .074 .050 2,014
.013 .025 .035 .059 .061 .037 .102 .079 .024 .058 .039 .038 .026 .017 641 Total 1.012 1.177 1.159 .860 .950 1.181 1.705 2.535 4.580 3.397 1.475 1.430 2.027 2.729 1.997 1.709 29.924 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total
.45 .014 .002 .014 .018 .010 .009 .004 .008 1.05 .001 .001 .000 .000 .005 .000
.014 .016 .027 .048 .065 .061 .008 000 096
.030 .025 .013 .010 .010 .018 .019 2.05 .051 .052 .093 .181 .018
.248 .259 .165 .099 .072 .055 .051 .018 .017 .408 3.05 .121 .145 .087 .119 .138
.172 .202 .189 .251 .309 .248 .269 .103 .077 1.849 4.05 .222 .166 .260 .234 .213
.158 .155 .187 .158 .173 .215 .174 .151
.319 .364 .490 .509 .246 .222 .241 3.325 505 .130 .134 .156 .243
.123 .152 .191 .296 .385 .600 .521 .237 .220 4.139 6.05 .236 .146 .233 .287
.141 .152 .186 .089 .098 .128 .310 .270 .214 4.075
.435 .718 .639 .216 .167 .244 8.05 .250 .325 .268 .038 .388 .340
.017 .066 .238 .667 1.498 1.032 .420 .247 4 499 10.05 .111 .321 .544 .922
.168 .050 .001 .000 .001 .032 .648 .498 7.748
.214 .679 .302 .102 .117 .269 .371 13.05 .023 .029 .006 .000 .000 .183 .199 2.799
.000 .005 .076 .214 .102 .024 .082 18.00 .000 .000 .107 .131
.000 .000 .000 .000 .000 .014 .027 .015 .076 .891 99.00 .002 .004 .012 .011 .017
.000 .000 .000 .000 .000 .000 .000 .000 .010 .096
.000 .000 .000 .000 .000 .000 .000
.000 .000 .000 Total 1.012 1.177 1.159 .860 .950 1.181 1.705 2.535 4.580 3.397 1.475 1.430 2.027 2.729 1.997 1.709 " 29.924 NOTE: Wind directions in tables are presented in "wind from' and not "wind to" direction.
F-42
BRAIDWOOD Revision 4 August 1999 A - Continued Supplemental Table Mixed Mode Joint Frequency Distribution Table Summaries 34 Foot Elevation Data Summary Table of Percent by Speed and Class Class A B C D E F G Speed
.45 .000 .000 .000 .008 .015 .031 .044 1.05 .001 .001 .003 .049 .126 .151 .076 2.05 .017 .020 .029 .335 .690 .631 .226 3.05 .127 .103 .157 1.118 1.175 .491 .155 4.05 .277 .192 .291 1.688 1.211 .383 .098 5.05 .332 .209 .274 1.870 1.179 .176 .035 6.05 .381 .219 .358 2.236 1.223 .076 .005 8.05 .735 .445 .632 3.993 1.844 .098 .001 10.05 .214 .126 .211 1.358 .837 .053 .000 13.05 .038 .040 .044 .424 .320 .024 .000 18.00 .001 .002 .004 .049 .040 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F-43
BRAIDWOOD Revision 4 August 1999 Supplemental Table B Ground Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .379 .415 .470 .394 .420 291 .417 .418 .728 .637 .248 .229 .358 .572 .648 .609 7.230 B .280 .280 .336 .241 .229 .206 .265 .332 .539 .411 .256 .206 .340 .407 .441 .431 5.203 C .385 .373 .501 .358 .245 .226 .388 .471 .685 .521 .462 .380 .598 .888 .624 .619 7.504 D 2.098 2.216 2.532 2.483 1.766 1.392 2.034 2.692 3.611 3.198 2.674 2.392 3.065 3.678 3.083 2.925 41.820 E .968 1.029 .914 1.221 1.210 1.387 1.849 2.754 4.116 2.772 1.298 1.258 1.197 1.411 1.052 1.068 25.502 F .339 .347 .302 .382 .552 .788 .729 .605 .949 .850 .366 .630 .795 .765 .441 .313 9.153 G .147 .074 .128 .163 .228 .358 .330 .229 .404 .300 .133 .268 .248 .233 .191 .157 3.588 Total 4.595 4.740 5.183 5.242 4.650 4.647 6.012 7.502 11.013 8.687 5.435 5.359 6.600 7.753 6.460 6.122 100,000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total
.45 .194 .111 .128 .160 .078 .087 .042 .126 .083 .013 .078 .004 .037 .051 .101 .054 1.328 1.05 .219 .263 .364 .579 .686 .517 .311 .267 .218 .181 .174 .198 .257 .264 .275 .269 5.038 2.05 .630 .645 .996 1.658 1.833 1.698 1.367 .962 .771 .631 .561 .842 1,076 1.169 .952 .780 16.571 3.05 .949 1.045 1.179 1.382 1.085 1.218 1.744 1.581 1.820 1.435 1.128 1.533 1.442 1.369 1.174 1.070 21156 4.05 .915 .902 1.015 .839 .577 .624 1.228 1.593 2.123 2.039 1.256 1.084 1.167 1.180 1.189 1.215 186947 5.05 .650 .641 .667 .416 .260 .292 .641 1.128 1.881 1.520 .937 .609 .884 1.104 .995 .959 13.582 6.05 .495 .462 .432 .159 .113 .143 .395 .758 1.435 1.236 .598 .445 .644 .936 .770 .751 9.771 8.05 .408 .472 .346 .046 .018 .067 .247 .785 1.782 1.226 .573 .436 .706 1.160 .806 .738 9815 10.05 .113 .170 .050 .001 .000 .001 .032 .214 .679 .302 .102 .116 .269 .372 .183 .201 2.805 13.05 .023 .029 .006 .000 .000 .000 .005 .076 .214 .102 .024 .082 .107 .131 .015 .076 .889 18.00 .000 .000 .000 .000 .000 .000 .000 .014 .027 .002 .004 .012 .011 .017 .000 .010 .096 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 4.595 4.740 5.183 5.242 4.650 4.647 6.012 7.502 11.013 8.687 5.435 6.359 6.600 7.753 6.460 6.122 100.000 NOTE: Wind directions in tables are presented in "wind from" and not "wind to" direction.
F-44
BRAIDWOOD Revision 4 Supplemental Table B -Continued August 1999 Ground Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Speed and Class Class A B C D Speed G
.45 .027 .018 .021 .197 .339 .388 .338 1.05 .102 .093 .145 1.038 1.463 1.379 2.05 .426 .498 .818
.798 4.865 5.159 3.380 3.05 1.147 1.009 1.448 1.493 8.268 6.225 2.342 4.05 1.618 1.158 .672 1.699 8.574 4.598 1.059 5.05 1.446 .969 .244 1.213 6.908 2.689 .304 8.05 1.155 .861 .055 1.007 5.053 1.763 .118 8.05 1.054 .629 .870 5.084 .014 2.068 .107 .002 10.05 .215 .128 .212 1.360 .839 .053 .000 13.05 .038 .040 .044 .423 .320 .024 .000 18.00 .001 .002 .004 .049 .040 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F-45
BRAIDWOOD Revision 4 August 1999 Liquid Effluent Release Point Kankakee River UNRESTRICTED AREA BOUNDARY UNRESTRICTED AREA BOUNDARY OFFSITE DOSE CALCULATION
+- N MANUAL BRAIDWOOD STATION FIGURE F-1 UNRESTRICTED AREA BOUNDARY F-46
BRAIDWOOD Revision 4 August 1999 N
- Low Level Radwaste Storage Building (I Service Building Truck Bay) OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION
** DAW Storage Area I Area Boundary FIGURE F-2
-Restricted OSGSF Old Steam Generator Storage Facility RESTRICTED AREA BOUNDARY F-47
QUAD CITIES STATION Quad Cities Station Chapter 10 Change Summary ODCM Revision 1.9, September 1999 Page or Section Change Description 10 i Updated revision number. 10-7 Removed footnote (and reference to it) that described the ten times IOCFR20 value can only be used post tech spec approval. These tech spec changes have been approved (1996). Improved spacing on page. Changed default value to 1 X 10.5 uCi/mL from 1 X 10 6 uCi/mL. This can be done since we are using the ten times 10CFR20 value now. In addition, the 1 X 10. uCi/mL value has been in use (per QCCP 0300-03/now QCRP 6410-02) since tech spec approval. It should also be noted that the only reason we need to use a default value when calculating alarm setpoints is because there is normally no detectable radioactivity in the service water, but the setpoints must be based on some value. The 10CFR20 value for Cs-137 is 1 X 106 uCi/cc. Utilizing the allowed ten times value; this becomes 1 X 10. uCi/cc. 10-8 Removed footnote (and reference to it) that described the ten times 10CFR20 value can only be used post tech spec approval. These tech spec changes have been approved.
QUAD CITIES Revision 1.9 ( QUAD CITIES ANNEX INDEX September 1999 I PAGE CHAPTER 10 10-i 10-ii 1.9 10-iii 1.9 10-iv 1.9 10-v 1.9 10-1 1.9 10-2 1.9 10-3 1.9 10-4 1.9 10-5 1.9 10-6 1.9 10-7 1.9 10-8 1.9 10-9 1.9 10-10 1.9 10-11 1.9 10-12 1.9 10-13 1.9 10-14 1.9 I 1.9 104
QUAD CITIES Revision 1.9 September 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS NUMBER 10.1 AIRBORNE RELEASES 1Ae PAGE 0.1 ...................................................................................... PAG 1
- 1. System Description...............................................................
.......... .1
- 2. Ventilation Exhaust Treatment System ...............................................................
1
- 2. Radiation Monitors ..................... ......................... 1
- 1. Plant Chimney Monitor .......
- 2. ............................... ............................ 1 Reactor Building Vent Stack Effluent Monitor........................................2
- 3. Reactor Building Ventilation Monitors ........
- 4. ....................
Condenser Air Ejector Monitors ..... ..
....................... ......................... 2
- 3. Alarm and Trip Setpoints......................................................................
- 1. Setpoint Calculation .................................................................. 3
- 1. Reactor Building Vent Stack Monitors
- 2. Condenser Air Ejector Monitors
............................. ....................... 33
- 3. Plant Chimney Radiation 3 Monitor ................... ....... 3
- 2. Relea sei mitss....................................
- 3. . .. . . . .... 3 Release M ixture .. ...............................................
- 4. ........................................ 4 Conversion Facto ..........................................................................
rs
- 5. HVAC Fo limits R t.............................................5
................................................... 4
- 4. Allocation of Effluents from Common Release Points ......................................................
5
- 5. Dose Projections ...............................................................................................................
5 10-ii
QUAD CITIES Revision 1.9 September 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) NUMBER PAGE 10.2 LIQ UID RELEASES ................................................................................................................. 6
- 1. System Description ........................................................................................................ 6
- 1. River Discharge Tank ....................................................................................... 6
- 2. Radiation Monitors .......................................................................................................... 6
- 1. Liquid Radwaste Effluent M onitor ...................................................................... 6
- 2. Service W ater Effluent M onitors ...................................................................... 6
- 3. Alarm and Trip Setpoints .............................................................................................. 6
- 1. Setpoint Calculations ......................................................................................... 6
- 1. Liquid Radwaste Effluent M onitor ........................................................ 6
- 2. Service W ater Effluent M onitors .......................................................... 7
- 2. Discharge Flow Rates ........................................................................................ 8
- 1. Release Tank Discharge Flow Rate ..................................................... 8
- 3. Release Lim its ................................................................................................... 8
- 4. Release Mixture ................................................................................................. 9
- 5. Conversion Factors ............................................................................................ 9
- 6. Liquid Dilution Flow Rates ............................................................................... 9
- 4. Allocation of Effluents from Common Release Points ................................................... 9
- 5. Projected Concentrations for Releases ........................................................................ 9 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM ......................................... 10 10-iii
QUAD CITIES Revision 1.9 September 1999 LIST OF TABLES
- None -
10-iv
QUAD CITIES Revision 1.9 September 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-11 10-2 Simplified Liquid Radwaste Processing Diagram 10-12 10-3 Simplified Liquid Effluent Flow Diagram 10-13 10-4 Simplified Solid Radwaste Processing Diagram 10-14 10-v
QUAD CITIES Revision 1.9 September 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1. Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal release points for potentially radioactive airborne effluents and their classifications are as follows:
-The ventilation chimney (a stack release point).
-The reactor building ventilation stack (a vent release point).
10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3.2.1.1 of the Quad Cities UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 10.1.2 Radiation Monitors 10.1.2.1 Plant Chimney Monitor Monitors 1(2)-1730NB continuously monitor the final effluent from the chimney. The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, and tritium sampling capability. 10-1
QUAD CITIES Revision 1.9 September 1999 The chimney effluent is also monitored by a separate particulate, iodine, and noble gas (SPING-4) system and a Victoreen system. The SPING/Victoreen system has high range capabilities to deal with accident conditions including postaccident sampling capability. The Victoreen sampling system automatically begins taking samples after a high signal has been received on the SPING-4 low range noble gas monitor. Output from the SPINGNictoreen system is obtainable in the control room. No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in the Quad Cities UFSAR Section 11.5.2.3. 10.1.2.2 Reactor Building Vent Stack Effluent Monitor The combined reactor building ventilation is also monitored by a SPING-4. This monitor has high range capabilities to deal with accident conditions. The SPING-4 noble gas detectors have ranges that envelope the range for the reactor building vent effluent trip point. The vent stack monitor has isokinetic sampling and iodine and particulate sampling capability. No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the Quad Cities UFSAR Section 11.5.2.4. 10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)-1735A/B continuously monitor the effluent from the Unit 1(2) reactor building. On high high alarm, the monitors automatically initiate closure of valves A01 (2)A-5741, A01 (2)B-5741, A01 (2)A-5742, and A01 (2)B-5742 thus isolating the Unit 1(2) reactor building, and initiate startup of the Unit 1(2) standby gas treatment system, and isolates control room HVAC. In addition to the above monitors, there is continuous iodine and particulate sampling of the reactor building exhaust. Pertinent information on these monitors is provided in Quad Cities UFSAR Section 11.5.2.4. 10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)-1733A1B continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main chimney. On high high alarm the monitors automatically activate an interval timer which in turn initiates closure of air operated valve A01 (2)-5406, thus terminating the release. In addition, monitors 1(2)-1741 continuously monitor the final offgas effluent prior to entering the chimney, and monitors 1(2)-1738 continuously monitor gross gamma activity downstream of the steam jet air ejector. No control device is initiated by these monitors. 10-2
QUAD CITIES Revision 1.9 September 1999 Pertinent information on these monitors is found in Quad Cities UFSAR Sections 11.5.2.1 and 11.5.2.2. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Stack Monitors The setpoint for the reactor building vent stack monitor is conservatively set at 2 mr/hr above background. The reactor building ventilation stack release rate, Qt, at 2 mr/hr is calculated to be 14,400 jgCVsec. Qt, is then substituted into Equations 10-1 and 10-2 to determine Qt. 10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at <100 gCVsec per MWt (=2.5E5 g+/-CVsec) and the high alarm is established at <50 l.CVsec per Mwt (=1.25E5 gCVsec). 10.1.3.1.3 Plant Chimney Radiation Monitor The setpoints for the plant chimney radiation monitor are conservatively set at 10,000 laCi/sec and 20,000 jiCVsec (high and high-high alarms respectively). At this level the combined release from chimney and vent is approximately 10% of the RETS limit. This is determined by solving Equations 10-1 and 10-2 below. 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limit Q" is found by solving Equations 10-1 and 10-2. (1.11) Z {fi [Qts Si + Qt' V]} < 500 mrem/yrl (10-1) Z {-Lfi [ (X/Q). Qt exp (-XýR/3600u,) + (X/Q),Qt, exp (-X*R/3600u,)] (10 - 2)
+ (1.11) (fl)[QtsS, + QVI]} < 3000 mrem/yr The summations are over noble gas radionuclides i.
f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides. 10-3
QUAD CITIES Revision 1.9 September 1999 Qts Total Allowed Release Rate, Stack Release [lCi/sec] The total Allowed release rate of all noble gas radionuclides released as stack releases. Q1, Total Allowed Release Rate, Vent Release [ACVsecJ The total allowed release rate of all noble gas radionuclides released as vent releases. The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A. Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem/yr) due to noble gases released in gaseous effluents (see Section A.1 .3.1 of Appendix A). Equation-10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem/yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A). The value of Equation 10-1 (2.3 x 11063Ci/sec) is used as the limiting noble gas release rate. Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. 10.1.3.3 Release Mixture In the determination of alarm and trip set points the radioactivity mixture in the exhaust air is assumed to be the same as the analysis of a representative sample of noble gases collected at the recombiner during the calendar quarter in which the monitor is recalibrated. 10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows. Reactor building vent effluent monitor. The monitor setpoint is established at 2 mr/hr above background. For the purpose of setpont determination it is assumed that the background is 1 mr/hr. There is sufficient conservatism in the setpoint calculation to accommodate routine variations in the background. However, the isotopic analysis in Section 10.1.3.3 is used to confirm that the setpoint is conservative. Condenser air ejector monitor. The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading at the time of the analysis are used to establish the conversion factor. 10-4
QUAD CITIES Revision 1.9 September 1999 Plant chimney monitor. Calibration of the plant chimney monitor consists of recirculating an amount of off-gas (see 10.1.3.3) through the noble gas monitors and a Marinelli beaker. After readings have stabilized, the Marinelli beaker is removed and gamma isotopic analysis performed. The efficiency is determined from a plot of average gamma energy of the off-gas sample and net monitor readings. 10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates may be obtained from the process computers, indication in the control room, or fan combinations. Setpoints were calculated using the following values: Chimney Air Flow .............................................................................. 350,000 cfm Combined Reactor Vent* (1 fan) ....................................................... 48,000 cfm Combined Reactor Vent* (2 fans) ..................................................... 96,000 cfm
- per unit 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-plant leakage, power history, and other variables. Consequently, allocation is normally made evenly between the units. During extended unit shutdowns or periods of known differences, the apportionment is adjusted accordingly. The allocation of effluents is estimated on a monthly basis.
10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS. 10-5
QUAD CITIES Revision 1.9 September 1999 10.2 - LIQUID RELEASES 10.2.1 System Description Simplified liquid radwaste and liquid effluent flow diagrams are provided in Figures 10-2 and 10-3. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2 of the Quad Cities UFSAR. 10.2.1.1 River Discharge Tank There is one river discharge tank (65,000 gallons capacity) which receives water for discharge to the Mississippi River. This is the only release path in use. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 1/2-1799-01 is used to monitor all releases from the river discharge tank. On high alarm the release is terminated manually. Pertinent information on the monitor and associated control devices is provided in Quad Cities UFSAR Sections 11.5.2 and 11.5.3. 10.2.2.2 Service Water Effluent Monitors Monitors 1 (2)-1799-01 continuously monitor the service water effluent. No control device is initiated by these monitors. Pertinent information on these monitors is provided in Quad Cities UFSAR 11.5.3. 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area. Currently these setpoints are based on the most conservative releases during the previous 18 months. If it is determined that this is no longer conservative, the setpoints are reevaluated. 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity. 10-6
QUAD CITIES. Revisio n 1.9 Septembe r 1999 P < (K) x [Z CT / Z (CiT/ 1 O*DWCi)] x [(0.5-FAVG + Fr'm) /F'n,,] + B (10-3) P Release Setpoint [cpm] C IT Concentration of radionuclide i in [1iCVml] the release tank. Frex Maximum Release Tank Discharge Flow Rate [gpm] The flow rate from the radwaste discharge tank. K Calibration constant [cp m/Acwml DWC1 Derived Water Concentration of radionuclide i [J.LCVmII From Appendix B, Table 2, Column 2 to 10CFR20o.1001-20.2402. 10 Multiplier granted in Technical Specifications applied to the DWC I FdAVG Average dilution flow of initial dilution [gpm] stream B Background Count Rate [cpm] 10.2.3.1.2 Service Water Effluent Monitors I The monitor setpoint is found by solving equation 10-4. P < (K)x [Z Ci / Z (C /10*DWC 1 )]x ((FdAVG + Fr.) / Fr.J+B (10-4) C, Concentration of radionuclide i in service water Ifthere is no detectable activity then .Ca_ (CV1 0*DWCj ) is assumed to be 1 x 10ACVml. I F',.= Maximum discharge rate of service water for one unit. [gpm] All other terms are as defined in equation 10-3. 10-7
QUAD CITIES Revision 1.9 September 1999 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. The results of the analysis of the sample determine the discharge rate of each batch as follows: F = 0.1 (0.5 Fd / Z (C,/ 10*DWCI)) (10-5) The summation is over radionuclides i. 0.1 Reduction factor for conservatism. FFrnax r, Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the radwaste discharge tank. Fd Dilution Flow (gpml Ci Concentration of Radionuclide i in the Release Tank CVm11 The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. DWCi Derived Water Concentration of radionuclide i SCirmi (JA From Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. 10 Multiplier granted in Technical Specifications applied to the DWC 10.2.3.3 Release Limits Release limits are determined from RETS. Calculated maximum permissible discharge rates are divided by 10 and dilution flows are divided by 2 to ensure that releases are well below applicable limits. (The factor of 2 used in the dilution flows accounts for discharging the RDT tank to the south diffuser pipe). 10-8
QUAD CITIES Revision 1.9 September 1999 10.2.3.4 Release Mixture For the liquid radwaste effluent monitor tthe release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis plus four additional radionuclides. The additional radionuclides are H-3, Fe-55, Sr-89, and Sr-90. The quantities to be added are determined using scaling factors derived from station release data for the previous six months. 10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs-137. 10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using Equation 10-6 below. Fd -(NT x Fcw + Nsw x Fsw - Flc-) (10-6) S= Dilution flow [gpm] Nc = Number of circulating water pumps on. F" = 157000 gpm Flow with one circulating water pump on. Nsw = Number of service water pumps on F'w = 13800 gpm Flow with one service water pump on FicE = Deicing flow 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluent released from the release tank is comprised of contributions from both units. Allocation of waste is achieved by comparing the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks. Liquid effluents from laundry and chemical waste are allocated evenly between units. During extended unit shutdown or periods of significant plant input differences, the apportionment is adjusted accordingly. The allocation of the effluents is made on a monthly basis. 10.2.5 Projected Concentrations for Releases If total DWC is greater than 25, the projected dose due to liquid effluent releases is calculated. Otherwise, the releases from the previous month are used to estimate the projected dose for the coming month using the methodology in Section A.2 of Appendix A. (See Section A.2.1 of Appendix A). 10-9
QUAD CITIES Revision 1.9 Septemoer 1999 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. Figure 10-4 is a simplified diagram of solid radwaste processing. 10-10
QUAD CITIES Revision 1999 1.9 September
-- ---- !ý!
I -WA-~ *tMu DOM CALCULAMN MMIjA Lft UN&HN..Ltm. ae um !J.E..
& ug mwgo mns" 7-T : AMt ran gn 86FDASOW RADWAMj
-- -tj Obw am AMLSOW WO&AW~A 10-1 1
QUAD CTES Revision 1.9 September 1999 3 OFFSnII DOSE CALCULATION MANUAL QUADCITIES STATION FIGURE 10-2 SIMPLIFIED UQUID RADWASTE 10-12 PROCESSING DIAGRAM
QUAD CMES Revision 1.9 September 1999 i, V OFFSITE DOSE CALCULATION MANUAL QUAD-CIIES STATION FIGURE 10-3 SIMPMFIED UQUID EFFLUENT FLOW DIAGRAM 10-13
QUAD CITIES Revision 1.9 September 1999 1211
-1 7
I - - - I I I I I w 0 z H1 d I til Sal II z I ill 12,11a 0 0 U C I I
-- j
-i OFFSITE QUADWE DOSE CALCULATION MANUAL STATION FIGURE 10-4 SIMPLIFIED SOLID RADWASTE PROCESSING DIAGRAM 10-14
Quad Cities Station Chapter 11 Change Summary ODCM Revision 2.0, April 1999 Page or Section Change Description 11-6 Sediment sample location Q-28, which was located 3.3 miles SSW of the liquid discharge point has been deleted and replaced by a new location, Q 39, which is located 0.8 miles SSW of the liquid discharge point. This point was moved based on a SNO concern at LaSalle County Station that their sediment location was too far away from the discharge point to provide any useful data. The requirement is to have the sample point within 6.2 miles.
Quad Cities Station Chapter 11 Change Summary ODCM Revision 2.1, September 1999 Page or Section Change Description II i Updated revision number. 11-2 Editorial change to clarify that the radioiodine canisters are changed out bi-weekly. Section 12.5 of the ODCM describes the generic requirements for the REMP program. This section describes the bi-weekly change out of the radioiodine canisters. QCNPS is sampling the radioiodine canisters bi-weekly. 11-7 Editorial change clarify that Food Products are collected once annually. Section 12.5 of the ODCM describes the generic requirements for the REMP program. This section directs that food products be sampled once per year. QCNPS is sampling food products once per year. 11-9 Changed Figure 11-1 to delete TLD's Q-207-2 and Q-209-2.Sampling. The following Outer Ring TLD locations have been deleted due to the fact that they are not required. It is required that there is one TLD in each of the sixteen sectors per the generic requirements described in section 12.5 of the ODCM. After deletion of these two TLD locations, there will be two locations in each sector: Q-207-2 Q-209-2
(. CHAPTER 11 Quad Cities Annex Revision 2.1 Q:\CHEM\QCIIR2_1.DOC
QUAD CITIES Revision 2.1 September 1999 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents PAGE Radiological Environmental Monitoring Program 11-1 List of Tables NUMBER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 List of Figures NUMBER TITLE PAGE 11-1 Fxed Air Sampling Sites and Outer Ring TLD Locations 11-9 11-2 Inner Ring TLD Locations 11-10 11-3 Milk, Fish, Water, and Sediment Sample Locations 11-11 Q:\CHEM\QC1IR2_I.DOC 11 -ii
QUAD CITIES Revision 2.1 September 1999 CHAPTER 11 RadiologicalEnvironmental MonitoringProgram The radiological environmental monitoring program for the environs around Quad Cities Station is presented in Table 11-1. Figures 11-1 through 11-3 show sampling locations and monitoring locations. As part of the recent Technical Specification upgrade, the specifications which govern the Quad Cities Radiological Environmental Monitoring Program (REMP) were removed from the Technical Specifications and relocated within the Quad Cities Chapter 11 and 12 of the ODCM. Quad Cities Station will implement the Uniform Radiological Environmental Monitoring Prograri, which is described in Chapter 12 of the ODCM and detailed in this Chapter within Table 11-1, during the first sampling period of 1999. Figures generally denoting Quad Cities Station sample locations are contained herein. (Figures 11-1, 11-2, and 11-3). Q: \CHEM\QC11R2_1.DOC 11-1
Revib,-,, 2.1 QUAD CITIES September 1999 Table 11-1 Radiological Environmental Monitoring Program Sampling or Type and Frequency Exposure Pathway Sample or Monitoring Location Collection Frequency of Analysis and/or Sample S.- .-.--
. I ....---
Continuous sampler Radioiodine Canisters:
- 1. Airborne operation with sample
- a. Indicators-Near Field collection weekly, or more 1-131 analysis bi-weekly on Radioiodine and frequently if required by near field and control Particulates Q-01 Onsite No. 1 0.5 mi N (0.8 km A) dust loading. samples'.
Q-02 Onsite No. 2 0.4 mi ENE (0.7 km D) 0-03 Onsite No. 3 0.6 mi S (1.0 km J) Particulate Sampler: 0-04 Nitrin 1.7 mi NE (2.7 km C) Gross beta analysis following 2 weekly filter change and gamma isotopic analysis 3
- b. Indicators-Far Field quarterly on composite filters by location on near field and Q-37 Meredosia Road 4.4 mi ENE (7.1 km D) control samples.
Q-38 Fuller Road 4.7 mi E (7.6 km E) 0-13 Princeton 4.7 mi SW (7.6 km L) Q-16 Low Moor 5.7 mi NNW (9.2 km R)
- c. Control Q-7 Clinton 8.9 mi NE (14.3 km C)
Q:\CHEM\QCIIR21 .DOC 11-2
Revis, 2.1 QUAD CITIES September 1999 Table 11-1 (Con't) Radiological Environmental Monitoring Program Exposure Pathway Exposure Pathway Sampling or Type and Frequency and/or Sample ,Sample or Monitoring Location Collection Frequency of Analysis
- 2. Direct Radiation a.lndicators-lnner Ring* Quarterly Gamma dose on each TLD Q-101-1, 0.6 mi N (0.9 km A) quarterly Q-101-2, 0.9 mi N (1.4 km A) 0-102-1, 1.3 mi NNE (2.2 km B)
Q-102-3, 1.4 mi NNE (2.3 km B) 0-103-1, 1.2 mi NE (1.9 km C) Q-103-2, 1.2 mi NE (1.9 km C) 0-104-1, 1.1 mi ENE (1.9 km D) 0-104-2, 0.9 mi ENE (1.4 km D) Q-105-1, 0.8 mi E (1.2 km E) 0-105-2, 0.8 mi E (1.2 km E) Q-106-2, 0.7 mi ESE (1.1 km F) 0-106-3, 0.7 mi ESE (1.2 km F) Q-107-2, 0.7 mi SE (1.2 km G) 0-107-3, 0.8 mi SE (1.2 km G) 0-108-1, 1.0 mi SSE (1.5 km H) Q-108-2, 0.9 mi SSE (1.4 km H) Q-109-1, 0.9 mi S (1.4 km J) Q-109-2, 1.2 mi S (1.9 km J) Q-111-1, 2.6miSW (4.2kmL) Q-111-2, 2.5 mi SW (4.0 km L) Q-112-1, 2.5 miWSW (4.0 km M) Q-112-2, 2.2 mi WSW (3.6 km M) Q-113-1, 2.5miW (4.1 kmN) Q-113-2, 2.5 miW (4.1 kmN) Q-114-1, 2.1 miWNW (3.5kmP)
'Q-114-2, 2.5 mi WNW (4.0 km P)
Q-115-1, 2.6 miNW (4.2kmQ) Q-115-2, 2.3 mi NW (3.6 kmO ) Q-116-1, 2.3miNNW (3.7km R) Q-1116-3, 2.4 mi N (3.9 km R)
* = Inner Ring TLDs are not placed within sector K because of the river at this range.
I Q:\CHEM\QCIIR2_1.DOC 11-3
QUAC. IES Rev7' -q 2.1 Septemb,*1 1999 Table 11-1 (Con't) Radlolo ical Environmental Monitori Poram -l E x p o s u re Pa thw a-y~ ~--
~r. -- _ . . a mpm,
_.W0rSa-peto
.-- Ni-
-e -r M- n-t r-nq- o a-. i n. . . Co lleSampling c tio n Fre qor ue n cy Type and Frequency
- 2. Direct Radiation b. In~dicators-Outer Ring -..----- r----------..--.~alss--
(Cont'd) Q-201-1, 4.2 mi N (6.7 km A) Q-201-2, 4.2 mi N (6.7 km A) Q-202-1, 4.4 mi NNE (7.0 km B) 0-202-2, 4.8 ml NNE (787 km B) 0-204-1, 4.7 ml NE (7.5 km C) 0-203-2, 5.0 mi NE (8.0 km C) Q-204-1, 4.7 mi ENE (7.5 km D) Q-204-2, 4.5 mi ENE (7.2 km D) Q-205-1, 4.7 ml E (7.5 km E) Q-205-4, 4.8 mi E (7.7 km E) Q-206-1, 4.8 mi ESE (7.7 km F) Q-206-2, 4.8 mi ESE (7.7 km F) 0-207-1, 4.7 mi SE (7.6 km G) Q-207-4, 4.7 mi SE (7.6 km G) 0-208-1, 4.3 ml SSE (6.8 km H) Q-208-2, 4.9 ml SSE (7.9 km H) Q-209-1, 4.7 mi S (7.6 km J) Q-209-4, 4.7 mi S (7.6 km J) Q-210-1, 4.1 mi SSW (6.5 km K) Q-210-4, 4.1 mi SSW (6.5 km K) Q-211-1, Q-211-2, 4.5 mi SW 4.5 mi SW (7.3 (7.3 km L) km L) Q-212-1, 5.4 mi WSW (8.7 km M) Q-212-2, 4.4 mi WSW (7.2 km M) Q-213-1, 4.3 mi W Q-213-2, 4.8 mi W (6.9 km N) (7.8 km N) Q-214-1, 4.7 ml WNW 0-214-2, (7.5 km P) 4.4 mi WNW (7.1 km P) Q-215-1, 5.0 ml NW (8.0 km Q) 0-215-2, 4.2 mi NW (6.7 km Q) Q-216-1, 4.6 mi NNW (7.4 km R) _ -216-2, 4.3 mi NNW (7.0 km R) Q: \CHEM\QCIIR2_1. DOC 11-4
QUAD ' ES ReV 12.1 Septembbif 1999 Table 11-1 (Con't) Radiological Environmental Monitoring Program Exposure and/or Sample Pathway Sample or Monitoring Location a, Collection Frequency o Type and Frequency of Analysis r---------------------------------- =------------ ---------------- r
- 2. Direct Radiation c. Other (Cont'd)
Indicators One at each of the airborne location given in part 1.a and 1.b. 0-301-1, Public Observation Tower
- d. Controls One at each airborne control location given in part 1.c.
- 3. Waterborne
- a. Ground/Well a. Indicators Quarterly Gamma isotopic 3 and tritium analysis quarterly.
0-35, McMillan Well 1.5 mi S(2.4 km J) Q-36, Cordova Well 3.3 mi SSW (5.3 km K)
- b. Drinking Water a. Indicator Weekly grab sample Gross beta and gamma There are no drinking water pathways within 6.2 mi isotopic analysis on downstream of Station. monthly composite; tritium analysis on quarterly composite.
- c. Surface Water a. Indicator Weekly grab sample Gross beta and gamma isotopic analysis on Q-33 Cordova, 3.3 mi SSW (5.3 km K) monthly composite; tritium analysis on quarterly I
composite. I Q:\CHEM\QCIIR2_1.DOC 11-5
0~nc h ) I QUAD CITIES ,,VIVat , September 1999 Table 11-1 (Con't) Radiological Environmental Monitoring Program Exposure Pathway, Sampling or Type and Frequency and/or Sample Sample or Monitoring Location C Collection Frequency of Analysis I L--------------------------------------------------------- L----------------------------- -- - - - - - - -
- 3. Waterborne (Con't) d.Control a. Control Weekly grab sample Gross beta and gamma isotopic analysis on monthly Q-34 Camanche 4.4 NNE (7.1 km C) composite; tritium analysis on quarterly composite. 0 e.Sediments Gamma isotopic analysis 3
- a. Indicators Semiannually semiannually.
Q-39 Cordova, Downstream on Mississippi
- 4. In-gestion River 0.8 mi SSW (1.3 km K)
- a. Milkk Gamma isotopic 3 and 1-131
*a. Indicators Biweekly: May through analysis 4 biweekly May October or monthly: through October, monthly Q-26 Bill Stanley Dairy, 3.5 ml ESE (4.8 km F) November through April November through April.
There are no other participating dairies within 6.2 miles.
- b. Controls There are no control dairies within 9.3 to 18.6 miles.
Q: \CHEM\QC11R2_1. DOC 11-6
Revi .... 2.1 QUAD CITIES September 1999 Table 11-1 (Con't) Radiological Environmental Monitoring Program Exposure Pathway Sampling or I I I Type and Frequency and/or Sample Sample or Monitorinq Location Collection Frequency I of Analysis
- L-------------------
3
- b. Fish a. Indicator Two times annually Gamma isotopic analysis on edible portions Q-24 Pool #14 of Miss. River, 0.5 mi SW (0.8 km L)
- b. Control Q-29 Missippi River-Upstream 1.0 mi N (1.6 kmA)
- c. Food Products a. Indicators Once annually. Gamma isotopic analysis 3 on I edible portions.
Two sample locations from each of the four major quandrants within 6.2 mi. Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.
- b. Controls Two samples grown within 9.3 to 18.6 mi.
Q:\CHEM\QC11R2_1.DOC 11-7
QUAD CITIES Revision 2.1 September 1999 Table 11-1 (Con't) Radiological Environmental Monitoring Program Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Health Physics Support Supervisor. 2 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. 3 Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. 4 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. Q: \CHEM\QC11R2.1. DOC 11-8
Quad Cities Revision 2.1I September 1999 Figure 11-1 Quad Cities Outer Ring TLD's and Air Sampling Sites 0202.2 31"4 223.1 1 2124 uA E h4m I " 3344.: 20342020" M4 o ne P I' X943 r 210 -i.1
= Air Sampling Sites
- = Outer Ring llD Locations 11-9
Quad Cities Revision 2.1 September 1999 Figure 11-2 Quad Cities Inner Ring TLD Locations ti" 1%4 I
£e au Em
-. 114-1 P1w 4r" . . . 113-2 3.4 M54 lu-I -54 i0t I
11-10
Quad Cities Revision 2.1 September 1999 Figure 11-3 Milk, Fish, Water and Sediment Sampling Locations Clinton Low
- Garden Moor Plain Albany WHITESIDE COUNT" OCK ISLA COUNTY Port Byron
= Milk, Fish, Water and Sediment Sample Locations 11-11
Quad Cities Station Chapter 12 Change Summary ODCM Revision 2.0, September 1999 Page or Section Change Description 12-52 thru Editorial change. There were some minor word processing formatting 12-53 errors in the previous revision.
QUAD CITIES Revision 2.0 September 1999 CHAPTER 12 Quad Cities Annex Index Revision 2.0 12-i Q:\CHEM\QC12R2_0.L)OC
QUAD CITIES Revision 2.0 September 1999 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) Table of Contents PAGE 12.0 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS 12-1 12.1 DEFINITIONS 12-4 12.2 INSTRUMENTATION 12-9
- 1. Radioactive Liquid Effluent Instrumentation 12-9
- 2. Radioactive Gaseous Effluent Instrumentation 12-12 12.3 LIQUID EFFLUENTS 12-17
- 1. Concentration 12-17
- 2. Dose 12-21
- 3. Liquid Radwaste Treatment System 12-23 12.4 GASEOUS EFFLUENTS 12-24
- 1. Dose Rate 12-24
- 2. Dose-Noble Gases 12-27
- 3. Dose-Radioiodine-131 and 133, Tritium and Radionuclides in Particulate Form 12-29
- 4. Off-Gas System 12-31
- 5. Total Dose 12-33
- 6. Dose Limits for Members of the Public 12-35 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-36
- 1. Monitoring Program 12-36
- 2. Land Use Census 12-49
- 3. Interlaboratory Comparison Program 12-50 12.6 REPORTING REQUIREMENTS 12-51
- 1. Radioactive Effluent Release Report 12-51
- 2. Annual Radiological Environmental Operating Report 12-52
- 3. Offsite Dose Calculation Manual (ODCM) 12-53
- 4. Major Changes to Radioactive Waste Treatment Systems 12-54 (Liquid and Gaseous) 12-ii Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) LIST OF TABLES NUMBER TITLE PAGE 12.0-1 Effluent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 12.1-1 Surveillance Frequency Notation 12-7 12.1-2 Operational Modes 12-8 12.2-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-10 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12-11 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-13 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-15 12.3-1 Allowable Concentration (AC) of Dissolved or Entrained Noble Gases Release from the Site to Unrestricted Areas in Liquid Waste 12-18 12.3-2 Radioactive Liquid Waste Sampling and Analysis Program 12-19 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-25 12.5-1 Radiological Environmental Monitoring Program 12-39 12.5-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples 12-45 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-46 12-iii Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS Chapter 12 of the Quad Cities Station ODCM is a compilation of the various regulatory requirements, surveillance and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for Quad Cities Station. To assist in the understanding of the relationship between effluent regulations, ODCM equations, RETS (Chapter 12 section) and related Technical Specification requirements, Table 12.0-1 is a matrix which relates these various components. The Radiological Environmental Monitoring Program fundamental requirements are contained within this chapter, with Quad Cities specific information in Chapter 11 and with a supplemental matrix in Table 12.0-2. 12-1 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 Table 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification 10 CFR 50 1. Gamma air dose and beta air dose due A-1 12.4.2 6.8.D.4.h Appendix I to airborne radioactivity in effluent A-2 plume.
- a. Whole body and skin dose due to A-6 N/A N/A airborne radioactivity in effluent A-7 plume are reported only if certain g#mma and beta air dose criteria are exceeded.
- 2. CDE for all organs and all four age A-1 3 12.4.3 6.8.D.4.1 groups due to iodines and particulates in effluent plume. All pathways are considered.
- 3. CDE for all organs and all four age A-29 12.3.2 6.8.D.4.d groups due to radioactivity in liquid effluents.
10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 12.4.6 6.8.D.4.c components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 data base. 40 CFR 190 1. Whole body dose (DDE) due to direct A-35 12.4.5 6.8.D.4.j (now by dose, ground and plume shine from all reference, sources at a station. also part of 10 CFR 20) 2. Organ doses (CDE) to an adult due to A-13 all pathways. Technical 1. "Instantaneous" whole body (DDE), A-8 12.4.1 6.8.D.4.g Specifications skin (SDE), and organ (CDE) dose A-9 rates to an adult due to radioactivity in A-28 airborne effluents. For the organ dose, only inhalation is considered.
- 2. "Instantaneous" concentration limits for A-32 12.3.1 6.8.D.4.b liquid effluents.
Technical 1. Radiological Effluent Release Report NA 12.6.2 6.9.A.4 Specifications 12-2 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 Table 12.0-2 REMP Compliance Matrix Regulation Component RETS Technical Specification 10CFR50 Implement environmental monitoring program. 12.5.1 N/A Appendix I Section IV.B.2 and Technical Specifications 10CFR50 Land Use Census 12.5.2 N/A Appendix I Section IV.B.3 and Technical Specifications Technical Interlaboratory Comparison Program 12.5.3 N/A Specifications 10CFR50 Radiological Environmental Operating Report 12.6.1 6.9.A.3 Appendix I Section IV.B.2 and Technical Specifications 12-3 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.1 DEFINITIONS
- 1. Channel Calibration - A Channel Calibration shall be the adjustment, as necessary, of the Channel output such that it responds with the necessary range and accuracy to known values of the parameter which the Channel monitors. The Channel Calibration shall encompass the entire Channel including the sensor and alarm and/or trip functions, and shall include the Channel Functional Test. The Channel Calibration may be performed by any series of sequential, overlapping or total Channel steps such that the entire Channel is calibrated.
- 2. Channel Check - A Channel Check shall be the qualitative assessment of Channel behavior during operation by observation. This determination shall include, where possible, comparison of the Channel indication and/or status with other indications and/or status derived from independent instrument Channels measuring the same parameter.
- 3. Channel Function Test - A Channel Functional Test shall be:
- a. Analog Channels - the injection of a simulated signal into the Channel as close to the sensor as practicable to verify Operability including alarm and/or trip functions and Channel failure trips.
- b. Bistable Channels - the injection of a simulated signal into the sensor to verify Operability including alarm and/or trip functions.
The Channel Functional Test may be performed by any series of sequential, overlapping or total Channel steps such that the entire Channel is tested.
- 4. Dose Equivalent 1-131 - Dose Equivalent 1-131 is that concentration of 1-131 (microcurie/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors For Power and Test Reactor Sites."
- 5. Frequency - Table 12.1-1 provides the definitions of various frequencies for which surveillance, sampling, etc. are performed unless defined otherwise. (The bases to Upgraded Technical Specification 4.0.8 provides clarifications to this requirement.)
- 6. Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
- 7. Member(s) of the Public - Member(s) of the Public means any individual except when that individual is receiving an occupational dose.
- 8. Mode-Reactor modes are described in Table 12.1-2.
- 9. Occupational Dose-Occupational dose means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.
12-4 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999
- 10. Offsite Dose Calculation Manual (ODCM) - The Offsite Dose Calculation Manual shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sections 12-5 and (2) descriptions of the information that should be included in the Radioactive Effluent Release Reports and in the Annual Radiological Environmental Operating Reports required by Sections 12.6.2.1 and 12.6.2.2.
- 11. Operable - Operability - A system, subsystem, train, component, or device shall be Operable or have Operability when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that is necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
- 12. Operating - Operating means that a system, subsystem, train, component or device is performing its intended functions in its required manner.
- 13. Operating Cycle - Operating Cycle is the interval between the end of one Refueling Outage for a particular unit and the end of the next subsequent Refueling Outage for the same unit.
- 14. Process Control Program (PCP) - The Process Control Program shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste.
- 15. Protective Instrumentation Definitions - Protective instrumentation definitions are as follows:
- a. Channel - A Channel is an arrangement of a sensor and associated components used to evaluate plant variables and produce discrete outputs used in logic. A Channel terminates and loses its identity where individual Channel outputs are combined in a logic.
- b. Trip System - A Trip System means an arrangement of instrument Channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function. A Trip System may require one or more instrument Channel trip signals related to one or more plant parameters in order to initiate Trip System action.
Initiation of Protective Action may require the tripping of a single Trip System or the coincident tripping of two Trip Systems.
- c. Protective Action - An action initiated by the protection system when a limit is reached.
A Protective Action can be at the Channel or system level.
- d. Protective Function - A system protective action which results form the Protective Action of the Channels monitoring a particular plant condition.
12-5 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 _. September 1999
- 16. Rated Thermal Power - Rated Thermal Power means a steady-state power level of 2511 thermal megawatts.
- 17. Reactor Power Operation - Reactor Power Operation is any operation with the mode switch in the Startup/Hot Standby or Run position with the reactor critical and above 1% Rated Thermal Power.
- 18. Reactor Vessel Pressure - Reactor Vessel Pressures listed in the Technical Specifications, unless otherwise indicated, are those measured by the reactor vessel steam space detector.
- 19. Refueling Outage - Refueling Outage is the period of time between the shutdown of the unit prior to a refueling and startup of the plant subsequent to that refueling.
For the purpose of designating frequency of testing and surveillance, a Refueling Outage shall mean a regularly scheduled Refueling Outage; however, where such outages occur within 8 months of the completion of the previous Refueling Outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
- 20. Site Boundary - Site Boundary shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
- 21. Unrestricted Area - Unrestricted Area means an area, access to which is neither limited nor controlled by the licensee.
- 22. Source Check - Source Check is the qualitative assessment of instrument response when the sensor is exposed to a radioactive source.
- 23. Definitions Related to Estimatinq Dose to the Public Using the Appendix I Computer Program:
- a. Actual - Refers to using known release data to project the dose to the public for the previous month. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.
- b. Proiected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. This data is NOT incorporated into the database.
12-6 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY* S (Shiftly) At least once per scheduled shift D (Daily) At least once per 24 hours W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days 0 (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days E (Sesquiannually) At least once per 18 months (550 days) S/U (Startup) Prior to reactor startup NA (Not Applicable) Not Applicable Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The bases to Upgraded Technical Specification 4.0.B provides clarifications to this statement. These definitions do not apply to the Radiological Environmental Monitoring Program (Section 12.5). 12-7 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.1-2 OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR MODE POSITION' COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature
- 2. STARTUP Startup/Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown(a,e) > 212°F
- 4. COLD SHUTDOWN Shutdown(a*,e) _-212°F
- 5. REFUELING(0) Shutdown or Refuel(a(d) < 140°F TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run or Startup/Hot Standby position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.10.1. (c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed. (d) See Technical Specification Special Test Exceptions 3.12.A and 3.12.B. (e) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided the one-rod-out interlock is OPERABLE. (f) When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be inoperable. 12-8 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Instrumentation Operability Requirements 12.2.1.A The effluent monitoring instrumentation shown in Table 12.2-1 shall be OPERABLE with alarm setpoints set to ensure that the limits of 12.3.1 .A are not exceeded. The alarm setpoints shall be determined in accordance with the ODCM. Applicability: Applies to radioactive effluents from the plant. Action:
- 1. With a radioactive liquid effluent monitoring instrument alarm/trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
- 2. With one or more radioactive liquid effluent monitoring instruments INOPERABLE, take the ACTION shown in Table 12.2-1. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. In the event a limiting condition for operation and associated action requirements cannot be satisfied because of circumstances in excess specifications, provide a 30-day written report of those addressed in the to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surveillance Requirements 12.2.1 .B Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequencies shown in Table 12.2-2. Applicability: Applies to the periodic measurements of radioactive effluents. Bases 12.2.1 .C The radioactive liquid effluent instrumentation is provided to monitor the release of radioactive materials in liquid effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of RETS and 10 CFR 20. 12-9 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0
-. September 1999 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum No.
of Operable Total No. Channels of Channels Parameter Action['] 1 Service Water A Effluent Gross Activity Monitor Liquid Radwaste C Effluent Flow Rate Monitor Liquid Radwaste B Effluent Gross [1] Notes Activity Monitor Action A: With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10.7 ACVml. Action B: With less than the minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least 2 independent samples are analyzed in accordance with Section 12.3.A.1, and at least 2 members of the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluents via this pathway. Action C: With less than the minimum number of operable channels, releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be utilized to estimate flow. 12-10 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Functional Source Instrument Check(1) Calibration(1 )(3M Test(1 )(2) Check(1) Liquid Radwaste Effluent D E Q (7) (5)(6) Gross Activity Monitor Service Water Effluent D E Q (7) (5) Gross Activity Monitor Liquid Radwaste Effluent' (4) E NA NA Flow Rate Monitor Notes (1) D= once per 24 hours Q= once per 92 days E= once per 18 months (550 days) (2) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
- a. Instrument indicates levels above the alarm setpoints.
- b. Circuit failure.
- c. Instrument indicates a downscale failure.
- d. Instrument controls not set in OPERATE mode.
(3) Calibration shall include performance of a functional test. (4) Instrument Check to verify flow during periods of release. (5) Calibration shall include performance of a source check. (6) Source check shall consist of observing instrument response during a discharge. (7) Functional test may be performed by using trip check and test circuitry associated with the monitor chassis. 12-11 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Instrumentation Operability Requirement 12.2.2.A The effluent monitoring instrumentation shown in Table 12.2-3 shall be alarm/trip setpoints set to ensure that the limits of Section 12.4 are not OPERABLE with exceeded. The alarm/trip setpoints shall be determined in accordance with the ODCM. Applicability: As shown in Table 12.2-3. Action:
- 1. With a radioactive gaseous effluent monitoring instrument alarm/trip set conservative than required, without delay suspend the release point less of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
- 2. With one or more radioactive gaseous effluent monitoring instruments take the action shown in Table 12.2-3. Exert best efforts to return the inoperable, instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.
- 3. In the event a limiting condition for operation and associated action requirement cannot be satisfied because circumstances in excess of those addressed specifications, provide a 30-day written report to the NRC and no changes in the required in the operational condition of the plant, and this does not prevent are the plant from entry into an operational mode.
Surveillance Requirements 12.2.2.B Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequency shown in Table 12.2-4. Bases 12.2.2.C The radioactive gaseous effluent instrumentation is provided to monitor release of radioactive materials in gaseous effluents during releases. the setpoints for the instruments are provided to ensure that the alarms willThe alarm occur prior to exceeding the limits of RETS and 10 CFR 20. 12-12 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum No. of Operable Total No. Channels(1 ) of Channels Parameter Action (2) 1 2 SJAE Radiation Monitors D 1 2 Main Chimney Noble A Gas Activity Monitor 1 Main Chimney Iodine C Sampler 1 Main Chimney C Particulate Sampler 1 Reactor Bldg. Vent B Sampler Flow Rate Monitor 1 Reactor Bldg. Vent C Iodine Sampler 1 1 Reactor Bldg. Vent C Particulate Sampler 1 1 Main Chimney Sampler B Flow Rate Monitor 1 1 Main Chimney Flow B Rate Monitor 1 2 Reactor Bldg. Vent E Noble Gas Monitor 1 1 Main Chimney F High Range Noble Gas Monitor Notes (1) For SJAE monitors, applicable during SJAE operation. For other instrumentation, applicable at all times. (2) Action A: With the number of operable channels less than the minimum requirement, effluent releases via this pathway may continue, provided grab samples are taken at least once per 8 hour shift and these samples are analyzed within 24 hours. 12-13 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.2-3 (Con't) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Action B: With the number of operable channels less than the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours. Action C: With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1. Action D: With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours provided at least one chimney monitor is operable; otherwise, be in STARTUP in 12 hours. Action E: With less than the minimum channels operable, immediately suspend release of radioactive effluents via this pathway. Action F: With less than the minimum channels operable, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours, and: (1) either restore the inoperable channel(s) to operable status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status. 12-14 Q:\CHEM\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibra- Functional Source Instrument Mode(2) Check(1) tion(1 )(4) Test(1 (3) Check(1) Main Chimney Noble Gas B D E a M Activity Monitor Main Chimney Sampler B D E Q[61 NA Flow Rate Monitor Reactor Bldg. Vent Sampler B D E Q[6] NA Flow Rate Monitor Main Chimney Flow Rate B D E NA NA Monitor Reactor Bldg Vent B D E Q Q Activity Monitor SJAE A D E Q E Main Chimney Iodine and B D151 NA NA NA Particulate Sampler Reactor Bldg. Vent Iodine B D151 NA NA NA and Particulate Sampler Main Chimney High Range B D(51 E 0 M Noble Gas Monitor Notes (1) D = once per 24 hours M= once per 31 days 0 = once per 92 days E= once per 18 months (550 days) (2) A= during SJAE operation B= at all times (3) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable:
- a. Instrument indicates levels above the alarm setpoint
- b. Circuit failure
- c. Instrument indicates a downscale failure
- d. Instrument controls not set in OPERATE mode 12-15 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.2-4 (contfd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (4) Calibration shall include performance of a functional test. (5) Instrument check to verify operability of the instrument; that the instrument is in place and functioning properly. (6) Functional test shall be performed on local switches providing low flow alarm. 12-16 Q:\CHEMV\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1 .A. The concentration of radioactive material released from the site to unrestricted areas (at or beyond the site boundary, see Quad Cities Station ODCM Annex, Appendix F, Figure F-i) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402 with the Table 12.3-1 values representing the AC's for noble gases. Applicability: At all times Action: With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits. Surveillance Requirements 12.3.1 .B The concentration of radioactive material in unrestricted areas shall be determined to be within the prescribed limits by obtaining the representative samples in accordance with the sampling and analysis program specified in Table 12.3-2. The sample analysis results will be used with the calculational methods in the ODCM to determine that the concentrations are within the limits of Specification 12.3.A. Bases 12.3.1 .C This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. The concentration limit for noble gases was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2. 12-17 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.3-1 ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(LuCi/ml)* 4 Kr-85m 2x1 0-Kr-85 5x1 04 KF-87 ý4x10s5 Kr-88 9xl 0"5 Ar-41 7x1 0-5 Xe-131m 7xl 04 Xe-1 33m 5x 0-4 Xe-133 6x1 04 Xe-135m 2x1 0-4 Xe-1 35 2xl 04
- Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, density = 1.0 g/cc and Pw/Pt = 1.0.
12-18 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF LOWER LIMIT OF TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS DETECTIONa A._ ___(LLD) (pICVmI) A. Prior to Each Batch Prior to Each Batch Principal Gamma 5x10-7 Batch Waste Release Emitters" Tanks 1-131 1x10" Prior to Each Batch M Gross Alpha lx10-7 Compositeb H-3 lx10 Prior to Each Batch Q Fe-55 lx106 Compositeb Sr-89, Sr-90 5x10"8 Prior to One Batch/M M Dissolved & Entrained lx10-5 Gasesf (Gamma Emitters) B. Mc (Grab Sample) Mc 1-131 1x10-6 Plant Continuous Releases 7 Principle Gamma 5x10 Emitterse Dissolved and lxi 0 5 Entrained Gasesf (Gamma Emitters) H-3 1x10" Gross Alpha 1x10"7 QC (Grab Sample) QC Sr-89, Sr-90 5x10-8 Fe-55 1x1 0.6 12-19 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12-3-2 (Continued) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The LLD is defined in Notation A of Table 12.5-3.
- b. A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. If the alarm setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the frequency of analysis shall be increased to daily until the condition no longer exists.
- d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated then thoroughly mixed to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the release.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-1 34, Cs-1 37, Ce-1 41, and Ce-144. Other peaks which are measurable and identifiable by gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on a sample.
Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
- f. The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-1 35, and Xe-138. Other dissolved and entrained gases (gamma emitters) which are measurable spectrometry, together with the above nuclides, shall also and identifiable by gamma-ray be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
12-20 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.3 LIQUID EFFLUENTS 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment above background to a member of the public from radioactive materials in liquid effluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following:
- 1. During any calendar quarter:
(a) Less than or equal to 3 mrem to the whole body. (b) Less than or equal to 10 m rem to any organ. Applicability. At all times
- 2. During any calendar year:
(a) Less than or equal to 6 mrem to the whole body. (b) Less than or equal to 20 mrem to any organ. Action:
- 1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with 12.3.2.A. This is in lieu of a Licensee Event Report.
- 2. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the limits of Specification 12.3.2.A., prepare and submit a Special Report to the Commission within 30 days an limit the subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.
This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
- 3. With the projected annual whole body or any internal organ dose computed at the nearest downstream community water system is equal to or exceeds 2 mrem from all radioactive materials released in liquid effluents from the Station, prepare and submit a Special Report within 30 days to the operator of the community water system. The report is prepared to assist the operator in meeting the requirements of 40 CFR 141: EPA Primary Drinking Water Standards. A copy of this report will be sent to the NRC. This is in lieu of a Licensee Event Report.
12-21 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.3 LIQUID EFFLUENTS 12.3.2 Dose (Cont.) Surveillance Requirements 12.3.2.B.1. The dose contributions from measured quantities of radioactive material shall be determined by calculation at least once per 31 days and a cumulative summation of these total body and organ doses shall be maintained for each calendar quarter. 12.3.2.B.2 Doses computed at the nearest community water system will consider only the drinking water pathway and shall be projected using the methods prescribed in the ODCM at least once per 92 days. Bases 12.3.2.C This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977. NUREG-01 13 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113. 12-22 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.3 LIQUID IEFFLUENTS 12.3.3 Liquid Radwaste Treatment System Operability Requirements 12.3.3.A At all times during processing prior to discharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to liquid effluent releases to unrestricted areas (see Appendix F, Figure F-i), when averaged over 31 days, exceeds 0.13 mrem to the total body or 0.42 mrem to any organ Action:
- 1. If liquid waste has to be or is being discharged without treatment as required above, prepare and submit te the Commission within 30 days, a report which includes the following information:
- a. Identification of the defective equipment.
- b. Cause of the defective equipment.
- c. Action(s) taken to restore the equipment to an operating status.
- d. Length of time the above requirements were not satisfied.
- e. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.
- f. Action(s) taken to prevent a recurrence of equipment failures.
- 2. In the event a limited and/or associated action requirements identified in Sections 12.3.3.A cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surveillance Requirements 12.3.3.B Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in accordance with ODCM. Bases 12.3.3.C The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50. 12-23 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operability Requirements 12.4.1 .A The dose rate in unrestricted areas (at or beyond the site boundary, see Quad Cities Station ODCM Annex, Appendix F, Figure F-i) due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
- 1. For Noble Gases:
(a) Less than 500 mrem/year to the whole body. (b) Less than 3000 mrem/year to the skin.
- 2. ýFor iodine-131, for iodine 133, and for all radionuclides in particulate form with half-lives greater than 8 days less than 1500 mrem/year.
Action: If the dose rates exceed the above limits, without delay decrease the release rates to bring the dose rates within the limits, and to provide prompt notification to the Commission (12.6) Surveillance Requirements 12.4.1 .B The dose rates due to radioactive materials released in gaseous effluents from the site shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.4-1. The dose rates are calculated using methods prescribed in the Offsite Dose Calculation Manual (ODCM). Bases 12.4.1 .C This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on the site will be within the annual dose limits of 10CFR20. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to a dose rate of 500 mrem/year to the total body or to not less than or equal to a dose rate of 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to not less than or equal to a dose rate of 1500 mrem/year. For purposes of calculating doses resulting from airborne releases the main chimney is considered to be an elevated release point, and the reactor vent stack is considered to be a mixed mode release point. 12-24 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF DETECTIONa TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD) (g.CVml) A. Main Chimney M Mb Principal Gamma 1xl 0-4 Reactor Bldg. Grab Sample Emitters' Vent Stack M Tritium 1x10s B. All Release Continuous (d) Wc 1-131 1012 Types as Listed Charcoal in A Above Sample 1-133 1x1010 Continuous (d) WC Principal Gamma Particulate Emitterse 1x10"-1 Sample (1-131, others) Continuous (d) Q SR-89 lxi1" Composite Particulate Sample SR-90 1lx10" Continuous (d) M Gross Alpha 1x10"11 Composite Particulate Sample C. Main Chimney Continuous (d) Noble Gas Noble Gases lx10e Monitor D. Reactor Bldg. Continuous (d) Noble Gas Noble Gases lx104 Vent Stack Monitor 12-25 Q:\CHEM\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.4-1 (Continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Notation A of Table 12.5-3.
- b. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal power in 1 hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor ol 3. _
- c. Samples shall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. Sampling shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10.
- d. The ratio of sample flow rate to the sampled stream flow rate shall be known.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-1 38 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-1 34, Cs-1 37, Ce-141, and Ce-1 44 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
12-26 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.2 Dose - Noble Gases Operability Requirements 12.4.2.A The air dose in unrestricted areas (at or beyond the site boundary) due to Noble Gases released in gaseous effluents from the unit shall be limited to the following:
- 1. For gamma radiation:
(a) Less than or equal to 5 mrad during any calendar quarter. (b) Less than or equal to 10 mrad during any calendar year.
- 2. For Beta radiation:
(a) Less than or equal to 10 mrad during any calendar quarter. (b) Less than or equal to 20 mrad during any calendar year. Action:
- 1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to ensure that future releases are in compliance with 12.4.2.A.
This is in lieu of a Licensee Event Report.
- 2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding the limits of Specification 12.4.2.A, prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the doses or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposure to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the.ODCM. This report is in lieu of a Licensee Event Report.
Surveillance Requirements 12.4.2.B The air dose due to releases of radioactive noble gases in gaseous effluents shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in sections A and B of Table 12.4-1. The allocation of effluents between units having shared effluent control systems and the air doses are determined using methods prescribed in the ODCM at least once every 31 days. 12-27 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.2 Dose - Noble Gases (Cont.) Bases 12.4.2.C This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual thwough the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-01 33 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 12-2e Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.3 Dose - Radioiodine - 131 and 133, Tritium and Radionuclides in Particulate Form Operability Requirements 12.4.3.A The dose to a member of the public in unrestricted areas (at or beyond the site boundary) from iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit shall be limited to the following:
- 1. Less than or equal to 7.5 mrem to any organ during any calendar quarter.
- 2. Less than or equal to 15 mrem to any organ during any calendar year.
Apoficability: At all times Action:
- 1. With the calculated dose from the release of iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with 12.4.3.A This is in lieu of a Licensee Event Report.
- 2. With the calculated dose from the release of iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding the limits of Section 12.4.3.A, prepare and submit a Special Report to the Commission within 30 days and limit subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
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QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.3 Dose - Radioiodine - 131 and 133, Tritium and Radionuclides in Particulate Form (Cont.) Surveillance Requirements 12.4.3.B.1 The dose to a member of the public due to releases of iodine-131, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.4-1. 12.4.3.B.2 For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be estimated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses when possible. The allocation of effluents between units having shared effluent control systems and the doses are determined using the methods prescribed in the ODCM at least once every 31 days. Bases 12.4.3.C This specification is provided to implement the requirements of Sections Ii.C, lll.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section lv.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept mas low as is reasonable achievable." The ODCM calculational methods specified in the surveillance requirements implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix In,Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodine, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these specifications were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man. 12-30 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.4 Off-Gas System Operability Requirements 12.4.4.A At all times during processing for discharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated. Applicability and Action: The above specification shall not apply for the Off-Gas Charcoal Adsorber Beds below 30 percent of rated thermal power.
- 1. The release rate of the sum of the activities from the noble gases measured at the main condenser air ejector shall be limited to less than or equal to 100 microcuries/sec per MWt (after 30 minutes decay) at all times. With the release rate of the sum of the activities from noble gases at the main condenser air ejector exceeding 100 microcuries/sec per MWt (after 30 minutes decay), restore, the release rate to within its limits within 72 hours, or be in at least STARTUP with the main steam isolation valves closed within the next 8 hours.
- 2. With all charcoal beds bypassed for more than 7 days in a calendar quarter while operating above 30 percent of rated thermal power, prepare and submit to the Commission within 30 days a special report which includes the following information:
- a. Identification of the defective equipment.
- b. Cause of the defective equipment.
- c. Action(s) taken to restore the equipment to an operating status.
- d. Length of time the above requirements were not satisfied.
- e. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.
- f. Action(s) taken to prevent a recurrence of equipment failures.
- 3. In the event a limit and/or associated action requirement identified in Section 12.4.4.A cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surveillance Requirements 12.4.4.B.1 Doses due to treated gases released to unrestricted areas at or beyond the site boundary shall be projected at least once per 31 days in accordance with the ODCM. 12-31 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.4 Off-Gas System (Continued) 12.4.4.B.2 The radioactivity rate of noble gases at (near) the outlet of the main condenser air ejector shall be continuously monitored in accordance with Specification 12.2.2.A. The release rate of the sum of the activities from noble gases from the main condenser air ejector shall be determined to be within the limits of Specification 12.4.4.A at the following frequencies by performing an isotope analysis of a representative sample of gases taken at the recombiner outlet, or at the air ejector outlet if the recombiner is bypassed.
- a. At least once per 31 days.
- b. Within 4 hours following an increase, as indicated by the main condenser air ejector noble gas activity monitor, of greater than 50%, after factoring out increases due to changes in thermal power level and off-gas flow, in the nominal steady-state fission gas release from the primary coolant.
Bases 12.4.4.C The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable". This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10CFR50, and the design objectives given in Section 11.0 of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.3 and 11.0 of Appendix I, 10CFR50, for gaseous effluents. 12-32 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.5 Total Dose Operability Requirements 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Applicability: At all times. Action:
- 1. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2, 12.4.2, or 12.4.3, calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5.A have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. Surveillance Requirements 12.4.5.1 .A Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2, 12.4.2, and 12.4.3, and in accordance with the methodology and parameters in the ODCM. 12.4.5.2.B Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5.A. 12-33 Q:\CHEM\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.5 Total Dose (Cont.) Bases 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 ifthe individual reactors remain within twice the dose design objectives of Appendix I, and ff direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. Ifthe dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 12-34 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.4 GASEOUS EFFLUENTS 12.4.6 Dose Limits for Members of the Public Operability Requirements 12.4.6.A The licensee shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem in a year. In addition, the dose in any unrestricted area from external sources does not exceed 2 mrem in any one hour. The Effluents Program shall implement monitoring, sampling, radioactive liquid and gaseous effluents in accordance with and analysis of 1 OCFR20.1302 and with the methodology and parameters in the ODCM. Applicability: At all times. Actionr.
- 1. Ifthe calculated dose from the release or exposure of radiation exceeds the 100 mrem/year limit for the MEMBER OF THE meets or PUBLIC, prepare and submit a report to the Commission in accordance with 10CFR20.2203.
- 2. If the dose in any unrestricted area from external sources of radiation meets or exceeds the 2 mrem in any one hour limit for the MEMBER PUBLIC, prepare and submit a report to the Commission OF THE in accordance with 10CFR20.2203.
Surveillance Requirements 12.4.6.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC determine compliance with the 100 mrem/year limit in accordance annually to In addition, evaluate and/or determine if direct radiation exposures with the ODCM. exceed 2 mrem in any hour in unrestricted areas. Bases 12.4.6.C This section applies to direct exposure of radioactive materials radioactive materials released in gaseous and liquid effluents. as well as forth the 100 mrem/year dose limit to members of the public; 10CFR20.1301 sets hour limit in the unrestricted area; and reiterates that the 2 mrem in any one meet the 40CFR190 standards. 10CFR20.1302 provides licensee is also required to options to determine compliance to 10CFR20.1301. Compliance to the above based on 10CFR20, 40CFR190 and Quad Cities Station operability requirement is Technical Specifications. 12-35 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.5 RADiOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1 .A The environmental monitoring program given in Table 12.5-1 shall be conducted as specified below. Applicability: At all times Action:
- 1. With the radiological environmental monitoring program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person/business who participates in the program goes out of business or can no longer provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule willi be described in the Annual Radiological Environmental Operating Report.
- 2. With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in the ODCM exceeding the limits of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3.
When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) + ... >1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
*The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
12-36 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.5. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) If the sample type or sampling location(s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program as soon as practicable. The specified locations from which samples were unavailable may then be deleted from the monitoring program. Prepare and submit controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples. Surveillance Requirements 12.5.1 .B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3. Bases 12.5.1 .C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmennal exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based o on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques ," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 12-37 Q:\CHEM\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or, reservoirs (not well water) which is used for drinking. 12-38 Q:\CHEM\QC 12R2_0.DOC
I QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/OR SAMPLE AND SAMPLE LOCATIONS(1 ) FREQUENCY FREQUENCY OF ANALYSIS
- 1. Airborne Samples from a total of eight locations: Continuous particulate sampler Radioiodine Canister:
Radioiodine and operation with sample collection 1-131 analysis biweekly Particulates a. Indicator- Near Field weekly, or more frequently if on near field samples and required due to dust loading,and control. (2) Four samples from locations within 4.0 km radioiodine canister collection (2.5mi) in different sectors. biweekly. Particulate Sampler: Gross beta analysis
- b. Indicator- Far Field following weekly filter change") and gamma Three additional locations within 4.0 to 10 km isotopic analysis(4)
(2.5 to 6.2 mi.) in different sectors. quarterly on composite filters by location on near
- c. Control field samples and control.(2)
One sample from a control location within 10 to 30 km (6.2 to 18.6 mi.). 12-39 Q:\CHEM\QC12R2_0.DOC
I QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY FREQUENCY OF ANALYSIS
- 2. Direct Radiation*b) Forty routine monitoring stations either with a Quarterly Gamma dose on each thermoluminescent dosimeter (TLD) or with one TLD quarterly.
instrument for measuring dose rate continuously, placed as follows:
- a. Indicator- Inner Ring (100 Series TLD)
One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 3 miles);
- b. Indicator- Outer Ring (200 Series TLD)
One in each meteorological sector, within 6.0 to 8.0 km (3.7 to 5.0 mi); and
- c. Other One at each Airborne location given in part 1.a. and 1 .b.
The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. (300 Series TLD) 12-40 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY FREQUENCY OF ANALYSIS
- 2. Direct RadiationIb) d. Control Quarterly Gamma dose on each (Cont'd) TLD quarterly.
One at each Airborne control location given in part 1.c
- 3. Waterborne a. Indicator Quarterly Gamma isotopic(4) and
- a. Ground/Well tritium analysis quarterly.
Samples from two sources only if likely to be affected.(')
- b. Drinking(7) a. Indicator Weekly grab samples. Gross beta and gamma isotopic analyses(4) on One Sample from each community drinking monthly composite; water supply that could be affected by the station tritium analysis on discharge within 10 km (6.2 mi) downstream of quarterly composite.
discharge.
- c. Surface If no community water supply (Drinking Water) Weekly grab samples. Gross beta and gamma 4
Water(7) exists within 10 km downstream of discharge isotopic analyses(` ) on then surface water sampling shall be performed. monthly composite; tritium analysis on
- a. Indicator quarterly composite.
One sample downstream
- d. Control Sample a. Control Weekly grab samples. Gross beta and gamma isotopic analyses(4) on One surface sample upstream of discharge. monthly composite; tritium analysis on quarterly composite.
12-41 Q:\CHEM\QC12R2_0.DOC
i QUAD CITIES Revision 2.0 TABLE 12.5-1 (Continued) September 1999 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY FREQUENCY OF ANALYSIS
- e. Sediment a. Indicator Semiannually. Gamma isotopic analysis (4) semiannually.
area At least one sample from downstream(7) within 10 km (6.2 mi).
- 4. Ingestion a. Indicator Biweekly (9) when animals are on Gamma isotopic(4) and pasture (May through October), 1-131(l°) analysis on each
- a. Milk (8) Samples from milking animals from a maximum monthly at other times sample.
of three locations within 10 km (6.2 mi) distance. (November through April).
- b. Control One sample from milking animals at a control location within 15 to 30 km (9.3 to 18.6 mi).
- b. Fish a. Indicator Two times annually. Gamma isotopic analysis(4) on edible Representative samples of commercially and portions recreationally important species in discharge area.
- b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.
12-42 0:\CHEM\QC12R2 0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/OR SAMPLE AND SAMPLE LOCATIONS(1 ) FREQUENCY FREQUENCY OF ANALYSIS
- a. Indicator Annually Gamma isotopic(4)
- c. Food Products analysis on each sample.
Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi): 1 At least one root vegetable sample( ") At least one broad leaf vegetable (or vegetation)(")
- b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).
12-43 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 1.1-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Radiation Protection Director. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (7) The "downstream" sample shall be taken in an area beyond but near the mixing zone. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence. (8) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling may be discontinued. (9) Biweekly refers to every two weeks. (10) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. (11) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container. 12-44
Revision 2.0 QUAD CITIES September 1999 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/I) OR GASES (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) H-3 20,000(1) Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2(2) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used. (2) If no drinking water pathway exists, a value of 20 pCi/I may be used. 12-45 Q:\CHEM\QC1 2R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS"' LOWER LIMIT OF DETECTION (LLD)(2)(3) WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/I) OR GASES (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry) Gross Beta 4 0.01 1000 H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 (6) 1/15(') 0.07 100 0.5/5(5) 60 Cs-134 15 0.01 100 15 60 150 18 0.01 100 18 80 180 Cs-137 Ba-La-140 15 15 12-46 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered. identifiable, together with those of the above nuclides, shall also be analyzed Other peaks that are and reported in the Annual Radiological Environmental Operating Report. (2) Required detection capabilities for thermoluminescent dosimeters used measurements shall be in accordance with the recommendations of Regulatory for environmental Guide 4.13. (3) The Lower Umit of Detection (LLD) is defined, for purposes of these specifications, concentration of radioactive material in a sample that will yield a net count, as the smallest that will be detected with 95% probability with only 5% probability of falsely above system background, concluding that a blank observation represents a "realm signal. For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:
- 4. 6 6 Sb+ 3
/tb LLD =
(E) (V)(2.22) (Y)(exp (-XAt)) 4.66 Sb LLD (E) (V)(2.22) (Y)(exp (-XAt)) Where: 4.66 Sb>> 3 /tb LLD = the "a priori" Lower Limit of Detection (picoCuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate sample, as appropriate (counts per minute), of a blank
-v Total Counts th E = the counting efficiency(counts per disintegration),
V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picoCurie, Y = the fractional radiochemical yield, when applicable, x = the radioactive decay constant for the particular radionuclide (sec1 ), 12-47 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS tb = counting time of the background or blank (minutes), and
,&t = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).
Typical values of E, V,,Y, and At should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an 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, 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. (4) If no drinking water pathway exists, the value of 15 pCi/I may be used. (5) A value of 0.5 pCi/i shall be used when the animals are on pasture (May through October) and a value of 5 pCi/I shall be used at all other times (November through April). (6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide. 12-48 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.5.2 Land Use Census Operability Requirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors* of the nearest milk animal, the nearest residence**, and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence. Applicability: At all times. Action:
- 1. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiologieal Environmental Monitoring Program given in Chapter 11. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.
*This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.
"**The nearest industrial facility shall also be documented if closer than the nearest residence.
Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations. 12-49 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 .5.3 Interlaboratory Comparison Program Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1. Applicability: At all times. Action:
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
Surveillance Requirements = 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. Bases 12.5.3.C The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. 12-50 Q:\CHEM\QC12R2_O.DOC
QUAD CITIES Revision 2.0 September 1999 12.6 REPORTING REQUIREMENTS Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:
- Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 6.4 of the Technical Specifications) are being met (all equipment failing to meet surveillance requirements and the corrective action taken shall be recorded);
-Records of radioactive shipments; Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant:
-Records of offsite environmental monitoring surveys;
-Records of radioactivity in liquid and gaseous wastes released to the environment;
-Records of reviews performed for changes made to the Offsite Dose Calculation Manual.
12.6.1 Radioactive Effluent Release Report* Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted prior to April 1 of the following year. The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3. The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications.
*A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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QUAD CITIES Revision 2.0 September 1999 12.6.2 Annual Radiological Environmental Operating Report* Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted prior to May 1 of each year. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3. The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."
*Asingle submittal may be made for a multiple unit station.
12-52 Q:\CHEM\QC12R2_0.DOC
QUAD CITIES Revision 2.0 September 1999 12.6.3 OFFSITE DOSE CALCULATION MANUAL (ODCM) The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in Sections 12.2-12.5 and (2) descriptions of the information that should be included in the Radioactive Effluent Release Reports and in the Annual Radiological Environmental Operating Reports required by sections 12.6.2. The ODCM shall be subject to review and approval by the Commission prior to implementation. Changes to the ODCM:
- 1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.14.A. This documentation shall contain:
- a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 2. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.
- 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
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QUAD CITIES Revision 2.0 September 1999 12.6.4 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID AND GASEOUS) A. Licensee initiated major changes to the radioactive waste systems may be made provided:
- 1. The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the onsite review function. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;
- b. Sufficient detailed information to support the reason for the change;
- c. A detailed description of the equipment, components, and process involved and the interfaces with other plant systems;
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and (or quantity of solid waste that differ from those previously predicted in the license application and amendments);
- e. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes were made;
- f. An estimate of the exposure to plant operating personnel as a result of the change; and
- g. Documentation of the fact that the change was reviewed and found acceptable by the onsite review function.
- 2. The change shall become effective upon review and acceptance by onsite review function.
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Q"An t'I'rice Revision June 19961.8 APPENDIX F Quad Cities Annex Index PAGE REMMLQN PAGE REM F-i 1.8 F-36 1.8 F-ii 1.8 F-37 1.8 F-iii 1.8 F-38 1.8 F-iv 1.8 F-39 1.8 F-1 1.8 F-40 1.8 F-2 1.8 F-41 1.8 F-3 1.8 F-42 1.8 F-4 1.8 F-43 1.8 F-5 1.8 F-44 1.8 F-6 1.8 F-45 1.8 F-7 1.8 F-46 1.8 F-8 1.8 F-47 1.8 F-9 1.8 F-48 1.8 F-10 1.8 F-49 1.8 F-11 1.8 F-12 1-.8 F-13 1.8 F-14 1.8 F-15 1.8 F-16 1.8 F-17 1.8 F-18 1.8 F-19 1.8 F-20 1.8 F-21 1.8 F-22 1.8 F-23 1.8 F-24 1.8 F-25 1.8 F-26 1.8 F-27 1.8 F-28 1.8 F-29 1.8 F-30 1.8 F-31 1.8 F-32 1.8 F-33 1.8 F-34 1.8 F-35 1.8 ESPOJ/odcm/quad/fr1..f F-i
QUAD CITIES Revision 1.8 June 1996 APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES UNITS 1 and 2 TABLE OF CONTENTS PAGE INTRODUCTION F-1 F.1 REFERENCES F-1 F.2 ESPOJ/odcm/quad/frl-8f F-ii
I QUAD CITIES Revision 1.8 June 1996 APPENDIX F LIST OF TABLES NUMBER TITLE PA( F-1 Aquatic Environment Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary F-6 F-5a X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors on 1 cm Depth at the Unrestricted Area Boundary for Based Selected Nuclides F-9 F-7a Maximum Offsite Finite Plume Gamma Dose Factors on 1 cm Depth at the Restricted Area Boundary for Based Selected Nuclides F-24 F-8 Parameters for Calculation of N-16 Skyshine Radiation from Quad Cities F-39 Supplementa I Tables I) A Elevated Level Joint Frequency Distribution Table Summary
- 296 Foot Elevation Data
-Summary Table
-Summary Table of of Percent by Direction and Class Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Mixed Mode Joint Frequency Distribution Table Summary
- 196 Foot Elevation Data
-Summary Table of Percent by Direction and Class F-AZ
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class C Ground Level Joint Frequency Distribution Table Summary
- 33 Foot Elevation Data
-Summary Table of Percent by Direction and Class F-46
-Summary Table of
-Summary Table of Percent by Speed Percent by Direcion andand Speed Class ESPOJ/odcm/quad/frl..aJ F-iii
QUAD CITIES Revision 1.8 June 1996 APPENDIX F LIST of FIGURES T iTLE PAGE NUMBER F-48 F-1 Unrestricted Area Boundary F-49 F-2 Restricted Area Boundary ESPOJ/odcm/quad/frl-8f F-iv
QUAD CITIES Revision 1.8 June 1996 APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES UNITS I and 2 F.1 INTRODUCTION This appendix contains data relevant to the Quad Cities site. Included are a diagram of the unrestricted area boundary and tables of values of parameters used in offsite dose assessment F.2 REFERENCES
- 1. Sargent & Lundy, Analysis and Technology Division, Quad Cities Calculation No. ATD-0148, Revision 0, 1 and 2.
I 2. Sargent & Lundy, "N-16 Skyshine Ground Level Dose from Quad Cities Turbine Systems and Piping," Revision 0.
- 3. "Quad Cities Public Water Supply" letter from B.S. Ferguson (NSEP) to G. Wassenhove U.S.
Army Corps of Engineers, February 16, 1989.
- 4. 'Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations", NUTECH Engineering Group, 1992.
- 5. 'Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations", NUS Corporation, 1988.
)J ESPOJ/odcm/quad/fr*Sf F-1
QUAD CITIES Revision June 19961.8 Table F-1 Aquatic Environment Dose Parameters General Informationa Existence of irrigation not mentioned in Quad Cities Final Safety Analysis Report (FSAR), UFSAR, or Plant Design Analysis. Recreation includes one or more of the following: boating, water skiiing, swimming and sport fishing. The station liquid discharge flows into the Mississippi River. Mississippi River Lock and Dam Number 14 is located between the station discharge and the E. Moline intake (see Figure 12 of the Quad Cities Unit 1 Plant Design Analysis, Volume II, and Figure 2.4.1 of the Quad Cities Safety Analysis Report.) Water and Fish Ingestion Parameters Paramete Value 1/Mw, I/IM 1.0 Fw, cfs 5.75E4 Ff, cfs 5.75E3 e, hr- 24.0 tr, hrd 8.0 Limits on Radioactivity in Unprotected Outdoor Tanks Not Applicable (See Section A.2.4 of Appendix A) a Quad Cities Updated Final Safety Analysis Report (USFAR) updated through Amendment 5 (9-3-87) Section 1.5.2 and Quad Cities Plant Design Analysis, Section 4.4 b The parameters are defined in Section A.2.1 of Appendix A. It (hr) 24 hr (all stations) for the fish ingestion pathway d r (hr) = 8 hr (Distance to the nearest public potable water intake, E. Moline, is 16 miles; flow rate of 2 mph is assumed) ESPOJ/odcm/quad/frl-8f F-2
QUAD CITIES Revision 1.8 June 1996 r ,) Table F-2 Station Characteristics Station: Quad Cities Nuclear Power Station Location: Cordova, Illinois Characteristics of Elevated Release Poi
- 1) Release Height = 94.49 m8 2) Diameter = 35_m
- 3) Exit Speed = 16.0 ms1a 4) Heat Content = 68 kCall s-a Characteristics of Vent Stack Release Point
- 1) Release Height= 4.-,5_ma 2) Diameter = 2.74 m
- 3) Exit Speed = 14.8 m rMs-11 Characteristics of Ground Level Release j) 1) Release Height =0 m
- 2) Building Factor (D) = 43.4 ma Meterological Data A -2296ft Tower is Located 12 m -$,5 of Elevated Release Point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Vent 296 ft 196-33 t Ground 33 ft 196-33 ft Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F7. See Sections
)t B.3,through B.6 of Appendix B.
ESPOJ1OdCnifquadffr18f F-3
QUAD CITIES Revision 1.8 June 1996 Table F-3 Critical Ranges Unrestricted Area Restricted Area Nearest Dairy Farm Boundarya Boundaryb Nearest Resident within 5 Milesd Direction (m) (m) (m) (m) N 864 219 800 None NNE 1029 224 1200 None NE 1212 265 2000 None ENE 1367 393 2000 None E 1170 867 3600 None ESE 1170 924 4800 5600 SE 1189 1010 4000 None SSE 1422 1059 1600 None S 1198 762 1200 None SSW 2140 335 4800 None SW 1372 232 4800 None WSW 823 189 3200 None W 713 189 3600 None WNW 713 183 3600 None NW 823 210 3600 None ! NNW 1481 224 2800 None a Nearest land in unrestricted area. Used in calculating the meteorological dose factors in Tables and F-7. See Sections B.3 through B.6 of Appendix B. b These values are to the edge of the Mississippi River, where applicable. C The distances are rounded to the nearest conservative 100 meters. d Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is used when there are no dairies within 5 miles.
/
ESPOJ/odcrnquadffrl-f F-4
QUAD CITIES Revision 1.8 June 1996 Table F-4 Average Wind Speeds Average Wind Speed (m/sec)" Downwind Direction Mie M N 6.9 5.0 2.6 NNE 6.2 4.6 2.8 NE 5.3 3.7 2.4 ENE 6.0 4.4 2.8 E 6.9 5.0 3.2 ESE 7.1 5.2 3.7 SE 6.5 4.9 3.6 SSE 5.7 4.5 3.5 S 5.6 4.4 3.4 SSW 5.6 4.4 3.3 SW 5.8 4.6 3.0 5 WSW W 6.0 6.1 4.7 4.8 3.4 3.1 WNW 6.0 4.5 2.6 NW 5.9 4.4 2.4 NNW 6.5 4.7 2.5 Based on Quad Cities site meteorological data, January 1978 through December 1987 data for ground level and mixed mode release analysis and 1982-1987 data for elevated releases. Calculated in Reference I of Section F.2 using formulas in Section B.1.3 of Appendix B. ESPOJ/odcm/quad/frl.8f F-5
QUAD CITIES Revision 1.8 I June 1996 Table F-5 X/Q and DIQ Maxima at or Beyond the Unrestricted Area Boundary Mixed Noda(Vent) Release Ground Level Release Dowiwind Eleveted(Stack) Release Radius X/Q O/C Direction Radiw X/O Radius 0/0 Radius X/Q 0/O (meters) (sec/m**3) (1/0*'2) (meters) (sec/m*3) (I/r$*2) (meteri ) (aec/m"*3) (meters) (1/o*'2) 864. 3.817E-06 1.105E-08 N "4400. 1.344E-08 864. 9.643E-10 864. 3.427E-07 2.869E-09 2.597E-06 1.052E-08 1029. 1.407E-09 1029. 2.219E-07 3.049E-09 1029. NNE 4023. 1.703E-08 1212, 2.249E-06 6.701E-09 4828. 1.287E-08 1212. 7.019E-10 1212. 1.321E-07 1.299E-09 ENE 6.723M-10 1367. 1.213E-07 1.319E-09 1367. 1.446E-06 4.8061-09 "4400. 1.091E-08 1367. 1170. 2.215E-07 2.811E-09 1170. 2.212E-06 9.318E-09 E 3600. 1.513E-08 1170. 1.139E-09 ESE 1.536E-09 1170. 2.332E-07 3.437E-09 1170. 2.094E-06 1.047E-08 3600. 2.126E-08 1170. 6.450E-09 1.082E-09 1189. 1.439E-07 2.384E-09 1189. 1.255E-06 SE 4023. 1.7581E-08 1189. 3.222E-09 1422. 6.915E-10 1422. 8.279E-08 1.1671-09 1422. 6.885E-07 SSE 4023. 1.259E-08 1198. 8.371E-07 3.350E-09 S 4.437E-10 1198. 6.887E-08 9.516E-10 SSW "4400. 1.005E-08 1500. 2140. 5.104E-08 4.693E-10 2140. 4.296E-07 1.380M-09 "4400. 8.621E-09 2140. 3.110E-10 SW 4.856E-10 1372. 1.006E-07 1.116E-09 1372. 1.224E-06 3.856E-09 WSW "4400. 1.102E-08 1500. 823. 2.158E-07 2.298E-09 823. 2.96%U-06 1.093E-08 "4400. 1.123E-08 1500. 4.674E-10 W 4.704E-10 713. 3.445E-07 2.737E-09 713. 5.271E-06 1.522E-08 4828. 1. 139E-08 1500. 7.554E-06 1.788E-08 4.025E-10 713. 5.025E-07 2.816E-09 713. MU 4828. 9.486E-09 1500. 1.144E-08 WNW 5.475E-10 823. 2.981E-07 2.009E-09 823. 4.739E-06 NW 4828. 9.752E-09 823. 1.928E-06 4.543E-09 6.127E-10 1481. 1.712E-07 1.202E-09 1481. NNW "4400. 1.045E-08 1481. QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 B. Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix and A.1.4.2 of Appendix A. XJQ is used for beta air, beta skin, and inhalation dose pathways. See Sections A.1.2, A.1.3, D/Q is used for produce and leafy vegetable pathways. See Section A.1.4 of Appendix A. to location of highest XIQ or D/Q at or Radius is the approximate distance from midpoint between gaseous effluent release points beyond the unrestrited area boundary (UAB) ESPO *-cm/quadtfYr-8f
I QUALiý;FIES Revision i June 1996 Table F-Sa X/Q and DIQ Maxima at or Beyond the Restricted Area Boundary Downuind Elevated(Stack) Retease Mixed Node(Vent) Release Ground Level Retease Direction Radius X/Q." Radius D/O Radius X/Q D/Q Radius X/Q D/Q (meters) (sec/u**3) (meters) (1/m*2) (meters) (sec/m**3) 1/,m**2) (meters) (sec/0*3) 01/m**2) N 4400. 1.344E-08 420. 1.244E-09 219. 3.171E-06 1.377E-08 219. 3.908E-05 8.926E-08 NNE 480. 2.173E-08 420. 2.103E-09 224. 2.086E-06 1.548E-08 224. 3.155E-05 1.096*-07 NE 4828. 1.287E-08 420. 1.006E-09 265. 1.070E-06 6.653E-09 265. 2.583E-05 7.200E-08 ENE 4400. 1.091E-08 420. .1.010E-09 393. 5.774E-07 5.329E-09 393. 9.932E-06 3.539E-08 E 3600. 1.513E-08 867. 1.319E-09 867. 3.073E-07 3.999E,09 867. 3.485E-06 1.525E-08 ESE 3600. 2.126E-08 924. 4.688E-09 924. 2.949E-07 4.507E-09 924. 2.997E-06 1.544E-08 SE 4023. 1.758E-08 1010. .1.126E-09 1010. 1.657E-07 2.875E-09 1010. 1.611E-06 8.445E-09 SSE 4023. 1.259E-08 1059. 7.178E-10 1059. 1.024E-07 1.611E-09 1059. 1.080E-06 5.287E-09 S "4400. 1.005E-08 1500. 4.437E-10 .762. 1.070E-07 1.511E-09 762. 1.672E-06 7.035E-09 SSW 4400. 8.621E-09 420. 4.004E-10 335. 4.092E-07 3.719E'09 335. 7.714E-06 2.774E-08 SW "4400. 1.102E-08 1500. 4.856E-10 232. 1.173E-06 7.186E-09 232. 2.231E-05 6.181E-08 W
"4400. 1.123E-08 1500. 4.674E-10 189. 2.260E-06 1.271E-08 189. 3.588E-05 1.002E-07 4828. 1.139E-08 1500. 4.704E-10 189. 3.196E-06 1.355E-08 189. 5.242E-05 1.109E-07 WNW 4828. 9.486E-09 420. 4.079E-10 183. 5.215E-06 1.491E-08 183. 8.197E-05 1.362E-07 MW 4828. 9.752E-09 420. 6.595E-10 210. 2.909E-06 1.002E-08 210. 5.006E-05 9.064E-08 NNW "4400. 1.045E-08 420. 1.027E-09 224. 3.092E-06 1.192E-08 224. 4.464E-05 8.717E-08 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-8f F-7
QUAD CITIES Revision 1.8 June 1996 Table F-6 DIQ at the Nearest Milk Cow and Meat Animal Locations within 5 miles Nearest Milk Cow D/Q(I/m**2) Nearest Meat Animal D/Q(I/m**2) Downwind Radius Elevated Mixed Ground Radius Elevated Mixed Ground Direction (meters) Release Release Release (meters) Release Release Release 2.350E-10 4000 2.024E-10 3.355E-10 8.079E-10 N 8000 1.019E-10 1.079E-10 2.662E-10 5.642E-10 1.475E-10 2.977E-10 5600 2.357E-10 NNE 8000 1.354E-10 9.377E-1 1 2.488E-10 9.377E-1 1 2.488E-1 0 8000 9.339E-1 1 NE 8000 9.339E-1 1 2.262E-10 5.451 E-1 0 9.792E-1 I 2.187E-10 4800 1.946E-10 ENE 8000 9.066E-1 1 3.775E-10 8.126E-10 1.620E-10 3.260E-10 4800 2.934E-10 E 8000 1.364E-10 4.692E-10 9.129E-10 3.656E-10 6.942E-10 4800 4.243E-10 ESE 5600 3.436E-10 2.544E-10 2.319E-10 7600 1.680E-10 1.587E-10 SE 8000 1.542E-10 1.454E-10 5.391E-10 1.567E-10 4000 2.748E-10 2.840E-10 SSE 8000 1.026E-10 9.303E-1 I 1.023E-09 1.220E-10 2400 3.247E-10 4.141 E-10 S 8000 7.650E-1 1 6.524E-11 1.351E-10 1.351E-10 8000 6.616E-1 I 6.303E-1 1 SSW 8000 6.616E-1 1 6.303E-1 I 6.0711E-10 1.766E-10 4000 2.227E-10 2.662E-10 SW 8000 8.419E-1 1 8.742E-11 5.348E-10 2.146E-10 4800 1.799E-10 2.317E-10 WSW 8000 8.454E-1 1 1.002E-10 9.823E-10 2.374E-10 3600 2.429E-10 3.461 E-10 W 8000 8.206E-1 1 9.545E-1 1 5.284E-10 2.788E-10 5600 1.173E-10 1.585E-10 WNW 8000 6.761E-11 8.7 18E-1 1 3.357E-10 2.249E-10 6400 1.007E-10 1.131E-10 NW 8000 7.046E-1 1 7.767E-1 I 9.803E-1 0 2.369E-10 3600 2.444E-10 3.316E-10 NNW 8000 7.938E-1 1 9.082E-11 Quad Cities Site Meteorological Data 1/78 - 12/87 Note Based on Reference 2 of Section F 2 and the formulas in Section B.4 of Appendix B. ESP' :/'dcm/quad/frl-8f F
I QUAD FES Revision 1.8-I June 1996 Table F-7 Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m Downwind Unrestricted Etevated(Steck) Release Mixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius a GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (wad/yr)/(uCi/sec) (meters) (mred/yr)/(uCilsec) N 864. 86. 1.193E-06 8.998E-07 864. 4.094E-05 3.087E-05 864. 3.885E-04 2.929E-04 NNE 1029. 1029. 1.785E-06 1.346E-06 1029. 2.796E-05 2.108E-05 1029. 2.651E-04 1.999E-04 NE 1212. 1212. 9.747E-07 7.349E-07 1212. 1.639E-05 1.236E-05 1212. 2.162E-04 1.630E-04 ENE 1367. 1367. 9.035E-07 6.812E-07 1367. 1.409E-05 1.063E-05 1367. 1.373E-04 1.036E-04 E 1170. 1170. 1.378E-06 1.039E-06 1170. 2.602E-05 1.962E-05 1170. 2.220E-04 1.674E-04 ESE 1170. 1170. 1.7M5E-06 1.338E-06 1170. 2.752E-05 2.075E-05 1170. 2.113E-04 1.593E-04 SE 1189. 1189. 1.286E-06 9.695E-07 1189. 1.74BE-05 1.318E-05 1189. 1.248E-04 9.407E-05 SSE 1422. 1422. 9.303E-07 7.014E-07 1422. 9.663E-06 7.286E-06 1422. 6.648E-05 5.012E-05 S 1198. 1198. 4.932E-07 3.719E-07 1198. 8.591E-06 6.478E-06 1198. 8.157E-05 6.150E-05 SSW 2140. 2140. 6.664E-07 5.025E-07 2140. 5.469E-06 4.124E-06 2140. 3.670E-05 2.767E-05 S5 1372. 1372. 6.134E-07 4.625E-07 1372. 1.175E-05 8.862E-06 1372. 1.164E-04 8.775E-05 WSW 823. 823. 4.376E-07 3.300E-07 823. 2.665E-05 2.010E-05 823. 3.016E-04 2.274E-04 V 713. 713. 4.936E-07 3.722E-07 713. 4.059E-05 3.060E-05 713. 5.263E-04 3.968E-04 WNW 713. 713. 4.839E-07 3.648E-07 713. 5.484E-05 4.135E-05 713. 7.361E-04 5.550E-04 MW 823. 823. 8.023E-07 6.049E-07 823. 3.493E-05 2.634E-05 823. 4.707E-04 3.549E-04 NNU 1481. 1481. 9.575E-07 7.220E-07 1481. 1.950E-05 1.470E-05 1481. 1.814E-04 1.368E-04 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 Note: Based on References 1 and 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. ESPOJ/odcm/quad/frl-Ff F-9
QUAD CITIES Revision 1.8 I June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Dowunind Unrestricted Etevated(Stack) Release Nixed Node(Vent) Release Ground Level Release S SBAR Radius V " AR Radius G GBAR Direction Area Bound Radius (meters) (meters) (mrad/yr)/(uCi/seC) (meters) (urad/yr)/(uCi/seC) (metbrs) (Crad/yr)/(uCi/sec) 864. 1.266E-04 1.225E-04 864. 4.908E-04 4.728E-04 8B4. 2.089E-03 2.000E-03 N 864. 1029. 4.358E-04 4.204E-04 1029. 1.591E-03 1.525E-03 NNE 1029. 1029. 1.322E-04 1.278E-04 1212. 1.383E-03 1.326E-03 MiE 1212. 8.48E-05 8.172E-05 1212. 2.793E-04 2.694E-04 ENE 1212. 1367. 9.249E-04 8.872E-04 1367. 5.783E-05 5.593E-05 1367. 2.056E-04 1.983E-04 E 1367. 1170. 1.393E-03 1.336E-03 1170. 1170. 8.118E-05 7.850E-05 1170. 3.308E-04 3.187E-04 1170. 3.662E-04 3.530E-04 1170. 1.337E-03 1.282E-03 ESE 1170. 1170. 1.067E-04 1.032E-04 1189. 8.091E-04 7.760E.04 1189. 9.118E-05 8.820E-05 1189. 2.618E-04 2.525E-04 SE 1189. 1422. 4.523E-04 4.340E-04 1422. 5.797E-05 5.606E-05 1422. 1.518E-04 1.464E-04 SSE 1422. 1.417E-04 1198. 5.192E-04 4.978E-04 1198. 5.611E-05 5.428E-05 1198. 1.469E-04 S 1198. 2140. 2.77ME-04 2.663E-04 2140. 3.024E-05 2.924E-05 2140. 7.862E-05 7.579E-05 SSW 2140. 1372. 7.514E-04 7.204E-04 1372. 5.402E-05 5.226E-05 1372. 1.697E-04 1.636E-04 WSW 1372. 3.372E-04 823. 1.633E-03 1.564E-03 uSu 823. 823. 8.767E-05 8.484E-05 823. 3.499"-04 713. 2.573E-03 2.461E-03 w 713. 1.112E-04 1.076E-04 713. 4.644E-04 4.473E-04 713. 713. 3.454E-03 3.302E-03 WNW 713. 1.000E-04 9.678E-05 713. 5.046E1-04 4.854E-04 713. 823. 2.406E-03 2.302E-03 823. 9.794E-05 9.4761-05 823. 3.993E-04 3.846E-04 Mw 823. 1481. 1.147E-03 1.099E-03 1481. 6.223E-05 6.018E-05 1481. 2.449E-04 2.360E-04 WNWI 1481. QUAD CITIES SITE NETEOROLOGICAL DATA 1/78 - 12/87 ESpr. ""dcm/quad/frl-8f F.-'
L I QUAD CITIES Revision 1.8 June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Dowrnwnd Unrestricted Elevated(Stack) ReLease Mixed Node (Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VAR Radius G G8AR (meters) (meters) (urad/yr)/(uCI/sec) (meters) (wu'ad/yr)l(uCilsec) (meters) (mrad/yr)/(uCi/sec) N 864. 864. 1.753E-06 1.695E-06 864. 5.814E-06 5.622E-06 864. 2.347E-05 2.269E-05 NNE 1029. 1029. 1.834E-06 1.773E-06 1029. 5.237E-06 5.064E-06 1029. 1.792E-05 1.733E-05 NE 1212. 1212. 1.185E-06 1.146E-06 1212. 3.399E-06 3.287E-06 1212. 1.595E-05 1.542E-05 ENE 1367. 1367. 8.083E-07 7.817E-07 1367. 2.473E-06 2.391E-06 1367. 1.072E-05 1.037E-05 E 1170. 1170. 1.116E-06 1.079E-06 1170. 3.908E-06 3.779E-06 1170. 1.578E-05 1.525E-05 ESE 1170. 1170. 1.461E-06 1.413E-06 1170. 4.335E-06 4.192E-06 1170. 1.510E-05 1.460E-05 SE 1189. 1189. 1.259E-06 1.217E-06 1189. 3.118E-06 3.015E-06 1189. 9.186E-06 8.883E-06 SSE 1422. 1422. 8.057E-07 7.791E-07 1422. 1.829E-06 1.769E-06 1422. 5.211E-06 5.039E-06 S 1198. 1198. 7.916E-07 7.655E-07 1198. 1.774E-06 1.716E-06 1198. 5.956E-06 5.760E-06 SSW 2140. 2140. 4.230E-07 4.090E-07 2140. 9.632E-07 9.314E-07 2140. 3.375E-06 3.264E-06 SW 1372. 1372. 7.572E-07 7.322E-07 1372. 2.039E-06 1.971E-06 1372. 8.743E-06 8.454E-06 WSW 823. 823. 1.239E-06 1.198E-06 823. 4.157E-06 4.020E-06 823. 1.828E-05 1.768E-05 W 713. 713. 1.570E-06 1.519E-06 713. 5.41E-06 5.300E-06 713. 2.847E-05 2.753E-05 WNW 713. 713. 1.414E-06 1.367E-06 713. 5.906E-06 5.711E-06 713. 3.816E-05 3.690E-05 NW 823. 823. 1.372E-06 1.327E-06 823. 4.734E-06 4.578E-06 823. 2.700E-05 2.610E-05 NNW 1481. 1481. 8.575E-07 8.292E-07 1481. 2.931E-06 2.834E-06 1481. 1.350E-05 1.305E-05 QUAD CITIES SITE METEOROLOGICAL DATA,1/78 - 12/87 ESPOJ/odcmnquad/frl-Ff F-1 1
QUAD CITIES Revision 1.8 I June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Dmmsuind Unrestricted Eievated(Stack) Retease Nixed Node(Vent) ReLease Ground Level ReLease Direction Area Bound Radius S SBM Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uci/sec) (meters) (mred/yr)/(uCi/sec) (meters) (Cmad/yr)/(uCi/sec) N a". 864. 6.162E-04 5.987E-04 864. 1.698E-03 1.649E-03 864. 5.808E-03 5.639E-03 1029. 6.389E-04 6.207E-04 1029. 1.557E-03 1.512E-03 1029. 4.508E-03 4.377E-03 NNE 1029. 3.633E-03 1212. 4.118E-04 4.001E-04 1212. 9.907E-04 9.622E-04 1212. 3.742E-03 NE 1212. 1367. 2.753E-04 2.675E-04 1367. 7.1288-04 6.923E-04 1367. 2.504E-03 2.432E-03 ENE 1367. 3.929E-03 3.815E-03 1170. 3.853E-04 3.743E-04 1170. 1.146E-03 1.113E-03 1170. E 1170. 3.695E-03 1170. 5.023E-04 4.880E-04 1170. 1.270E-03 1.234E-03 1170. 3.806E-03 ESE 1170. 2.225E-03 1189. 1189. 4.324E-04 4.201E-04 1189. 9.253E-04 8.986E-04 1189. 2.291E-03 SE 1.256E-03 1.220E-03 1422. 1422. 2.723E-04 2.646E-04 1422. 5.290E-04 5.137E-04 1422. SSE 1198. 1.424E-03 1.383E-03 S 1198. 1198. 2.704E-04 2.628E-04 1198. 5.202E-04 5.052E-04 1.354E-04 1.315E-04 2140. 2.615E-04 2.540E-04 2140. 7.068E-04 6.863E-04 SSW 2140. 2140. 1372. 2.581E-04 2.507E-04 1372. 5.872E-04 5.702E-04 1372. 2.001E-03 1.943E-03 Su 1372. 823. 4.588E-03 4.454E-03 WSW 823. 823. 4.379E-04 4.255E-04 823. 1.238E-03 1.202E-03 713. 5.602E-04 5.443E-04 713. 1.632E-03 1.585E-03 713. 7.313E-03 7.101E-03 U 713. 9.525E-03 713. 5.039E-04 4.896E-04 713. 1.729E-03 1.679E-03 713. 9.810E-03 kul 713. 6.654E-03 6.461E-03 823. 823. 4.859E-04 4.721E-04 823. 1.388E-03 1.348E-03 823. MW 1481. 2.955E-03 2.869E-03 NNU 1481. 1481. 2.903E-04 2.820E-04 1481. 8.192E-04 7.955E-04 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87
'OJ/odcm/quad/frl-8f 12
QUAD CITIES Revision 1.8 June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Dowmrind Unrestricted Elevated(Stack) Release Mixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GSAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (Crad/yr)/(Cil/sec) (meters) (mrad/yr)/(uCi/sec) N 864. 864. 1.594E-03 1.551E-03 864. 4.2201-03 4.1041-03 864. 1.481E-02 1.438E-02 NNE 1029. 1029. 1.665E-03 1.621E-03 1029. 3.885E-03 3.779M-03 1029. 1.143E-02 1.111E-02 NE 1212. 1212. 1.083E-03 1.054E-03 1212. 2.515E-03 2.4"7E-03 1212. 9.828E-03 9.548E-03 ENE 1367. 1367. 7.271E-04 7.078E-04 1367. 1.805E-03 1.756E-03 1367. 6.5991-03 6.411E-03 E 1170. 1170. 1.002E-03 9.755E-04 1170. 2.853E-03 2.775E-03 1170. 1.001E-02 9.728E-03 ESE 1170. 1170. 1.301E-03 1.266E-03 1170. 3.165E-03 3.0781-03 1170. 9.639E-03 9.364E-03 SE 1189. 1189. 1.124E-03 1.094E-03 1189. 2.307E-03 2.244E-03 1189. 5.837E-03 5.671E-03 SSE 1422. 1422. 7.148E-04 6.957E-04 1422. 1.340E-03 1.303E-03 1422. 3.258E-03 3.165E-03 S 1198. 1198. 7.126E-04 6.937E-04 1198. 1.312E-03 1.276E-03 1198. 3.701E-03 3.596E-03 SSU 2140. 2140. 3.636E-04 3.539E-04 2140. 6.814E-04 6.628E-04 2140. 1.963E-03 1.908E-03 WSW 1372. 1372. 6.784E-04 6.604E-04 1372. 1.485E-03 1.444E-03 1372. 5.313E-03 5.161E-03 823. 823. 1.144E-03 1.114E-03 823. 3.068E-03 2.964E-03 823. 1.1601-02 1.127E-02 swu W 713. 713. 1.459E-03 1.420E-03 713. 4.024E-03 3.913E-03 713. 1.827E-02 1.774E-02 "WNU 713. 713. 1.313E-03 1.278E-03 713. 4.274E-03 4.156E-03 713. 2.451E-02 2.379E-02 823. 823. 1.265E-03 1.231E-03 823. 3.452E-03 3.357E-03 823. 1.699E-02 1.650E-02 "NW 1481. 1481. 7.588E-04 7.386E-04 1481. 2.083E-03 2.026E-03 1481. 8.020E-03 7.791E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl.-f F-1 3
QUAD CITIES Revision June 19961.8 Table F-7 (Continued) Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Nixed Node(Vent) ReLease Ground LeveL ReLease Dowrwind Unrestricted ELevated(Stack) Retease Radius G GBAR S SOAR Radius V VBAR Direction Area Bound Radius (mrad/yr)/(uCi/sec) (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (.rad/yr)/CuCi/sec) (meters) 864. 7.380E-04 7.172E-04 a"4. 1.425E-03 1.385E-03 1029. 864. 2.034E-03 1.603E-03 1.976E-03 1.557E-03 N 864. 6.261E-04 6.085E-04 1029. 1.149E-03 1.116E-03 NNE 1029. 1029. 5.081E-04 4.936E-04 1212. 7.823M-04 7.598E-04 1212. 3.167E-04 3.078E-04 1212. 5.059E-04 4.914E-04 ME 1212. 1367. 3.701E-04 3.595E-04 1367. ENE 1367. 1367. 2.047E-04 1.989E-04 1170. 1.310E-03 1.273E-03 3.698E-04 3.594E-04 1170. 8.126E-04 7.894E-04 E 1170. 1170. 9.740E-04 9.462E-04 1170. 1.566E-03 1.522E-03 5.046E-04 4.904E-04 1170. ESE 1170. 1170. 1189. 6.659E-04 6.469E-04 1189. 9.264E-04 8.998E-04 1189. 4.116E-04 4.000E-04 3.822E-04 3.712E-04 SE 1189. 1.946E-04 1422. 2.810E-04 2.730E-04 1422. SSE 1422. 1422. 2.003E-04 3.175E-04 3.084E-04 1198. 4.622E-04 4.490E-04 S 1198. 1198. 2.189E-04 2.127E-04 1198. 7.304E-05 2140. 8.761E-05 8.510E-05 5.751E-05 5.588E-05 2140. 7.519E-05 SSW 2140. 2140. 3.241E-04 3.149E-04 1372. 4.4416-04 4.313E-04 1372. 1.914E-04 1.860E,04 1372. 2.203E-03 2.140E-03 SL 1372. 823. 1.113E-03 1.081E-03 823. WSW 823. 823. 4.790E-04 4.655E-04 1.524E-03 713. 3.460E-03 3.361E-03 6.760E-04 6.5691-04 713. 1.569E-03 W 713. 713. 713. 1.513E-03 1.470E-03 713. 4.161E-03 4.041E-03 WNW 713. 713. 6.075E-04 5.904E-04 823. 2.198E-03 2.135E-03 5.447E-04 5.293E-04 823. 1.114E-03 1.082E-03 MU 823. 823. 3.8068-04 3.697E-04 1481. 3.958E-04 3.844E-04 1481. 2.270E-04 2.206E-04 1481. NNU 1481. QUAD CITIES SITE NETEOROLOGICAL DATA 1/78 - 12/87 F'zPOJ/odcm/quad/fr1-84 P-14
K QUAD CITIES Revision 1.8 June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-S0 Dounwind Unrestricted Elevated(Stack) Release Mixed Mode(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VIAR Radius G GBA (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 864. 864. 1.025E-04 9.947E-05 864. 1.001E-04 9.715E-05 .864. 3.226E-05 3.128E-05 NNE 1029. 1029. 4.9531-05 4.807E-05 1029. 4.309E-05 4.181E-05 1029. 1.549E-05 1.502E-05 WE 1212. 1212. 1.210E-05 1.174E-05 1212. 7.167E-06 6.953E-06 1212. 2.958E-06 2.869E-06 ENE 1367. 1367. 8.572E-06 8.320E-06 1367. ?.121E-06 6.908E-06 1367. 3.357E-06 E 3.255E-06 1170. 1170. 2.876E-05 2.792E-05 1170. 3.061E-05 2.970E-05 1170. 1.687E-05 1.636E-05 ESE 1170. 1170. 4.141E-05 4.019E-05 1170. 3.846U-05 3.731E-05 1170. 2.748E-05 2.665E-05 SE 1189. 1189. 2.685E-05 2.606E-05 1189. 2.120E-05 2.056E-05 1189. 1.306E-05 1.267E-05 SSE 1422. 1422. 5.661E-06 5.494E-06 1422. 4.092E-06 3.970E-06 1422. 2.460E-06 2.385E-06 S 1198. 1198. 9.811E-06 9.523E-06 1198. 7.891E-06 7.6561-06 1198. 6.776E-06 6.571E-06 SSW 2140. 2140. 5.194E-07 5.040E-07 2140. 2.996E-07 2.907E-07 2140. 1.827E-07 1.772E-07 1372. 1372. 6.788E-06 6.588E-06 1372. 6.147E-06 5.963E-06 1372. 3.347E-06 3.246E-06 VSW WU 823. 823. 5.697E-05 5.530E-05 823. 8.16S-05 7.923E-05 823. 8.406E-05 8.151E-05 W 713. 713. 1.054E-04 1.023E-04 713. 1.550E-04 1.504E-04 713. 1.486E-04 1.441E-04 WNW 713. 713. 9.3671-05 9.092E-05 713. 1.286E-04 1.247E-04 713. 1.211E-04 1.174E-04 NW 823. 823. 6.316E-05 6.131E-05 823. 6.467E-05 6.275E-05 823. 3.606E-05 3.497E-05 NNW 1481. 1481. 8.234E-06 7.992E-06 1481. 6.106E-06 5.924E-06 1481. 1.127E-06 1.093E-06 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcmiquad/frl.rf F-1 5
Revision June 19961.8 QUAD CITIES I Table F-7 (Continued) Depth at the Unrestricted Area Boundary for Xe- 31m Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Mixed Node(Vent) Release Ground Level Release Dowunind Unrestricted Elevated(Stack) Release Radius G GOAR S SSAR Radius V VBAR Direction Area Bound Radius (meters) (mred/yr)/(uCi/sec) (meters) (meters) (mrad/yr)/CuCi/sec) (meters) (mrad/yr)/(uCi/sec) 864. 3.647E-06 3.3271-06 864. 4.407E-05 3.544E-05 2.595E-05 864. 1029. 3.834E-04 2.633E-04 2.985E-04 2.0571-04 N 864. 1029. 4.237E-06 3.798E-06 1029. 3.179E-05 NNE 1029. 1212. 1.947E-05 1.596E-05 1212. 2.2791-04 1.782E-04 NE 1212. 1212. 2.5871-06 2.338E-06 1367. 1.466E-04 1.149E-04 1.747E-06 1367. 1.602E-05 1.302E-05 ENE 1367. 1367. 1.965E-06 2.266E-05 1170. 2.2371-04 1.750E-04 2.839E-06 2.511E-06 1170. 2.808E-05 E 1170. 1170. 2.997E-05 2.426E-05 1170. 2.1181-04 1.657E-04 1170. 3.680E-06 3.262E-06 1170. ESE 1170. 1.963E-05 1.599E-05 1189. 1.267E-04 9.918E-05 1189. 2.967E-06 2.654E-06 1189. SE 1189. 1.114E-05 9.095E-06 1422. 6.993E-05 5.482E-05 1422. 1.993E-06 1.769E-06 1422. SSE 1422. 1198. 1.013E-05 8.309E-06 1198. 8.492E-05 6.642E-05 S 1198. 1198. 1.599E-06 1.463E-06 2140. 4.359E-05 3.4221-05 1.050E-06 2140. 6.337E-06 5.1"4E-06 SSW 2140. 2140. 1.206E-06 1.082E-05 1372. 1.252E-04 9.792E-05 1.650E-06 1.4931-06 .1372. 1.332E-05 SW 1372. 1372. 2.888E-05 2.335E-05 823. 2.959E-04 2.304E-04 823. 2.220E-06 2.075E-06 823. 823. 713. 4.243E-05 3.407E-05 713. 4.991E-04 3.877E-04 W 713. 713. 2.761E-06 2.5891-06 713. 6.941E-04 5.386E-04 2.357E-06 713. 5.524E-05 4.391E-05 713. 713. 2.521E-06 2.9771-05 823. 4.622E-04 3.593E-04 WNW 2.732E-06 2.507E-06 823. 3.710E-05 823. 823. 1.759E-05 1481. 1.999E-04 1.561E-04 MW 1.868M-06 1481. 2.184E-05 1481. 1481 . 2.099E-06 NNW QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87
, POJ/odcm/quad/frl-8f ":-16
', / OAD CITIES RevisTon 1.8 June 1996 STable F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-I33m Downwind Unrestricted ELevated(Stack) Release Nixed Hode(Vent) Release Ground Level Release Direction Areo Bound Radius S SBAR Radius V VBAR Radius G GOAR (meters) (meters) (urad/yr)/(uCf/sec) (meters) (Crad/yr)/CuCi/sec) (meters) (mrad/yr)/(uCi/sec) N 864. 864. 1.894E-05 1.812E-05 1.039E-04 9.305E-05 86.4. 864. 6.441E-04 5.482E-04 NIE 1029. 1029. 2.025E-05 1.928E-05 1029. 8.483E-05 7.710E-05 1029. 4.614E-04 3.957E-04 HiE ENE 1212. 1212. 1.285E-05 1.226E-05 1212. 5.369E-05 4.897E-05 1212. 4.033E-04 3.465E-04 E 1367. 1367. 9.011E-06 8.562E-06 1367. 4.123E-05 3.733E-05 1367. 2.642E-04 2.277E-04 1170. 1170. 1.267E-05 1.202E-05 1170. 6.835E-05 6.1471E-05 1170. 3.977E-04 3.419E-04 ESE SE 1170. 1170. 1.660E-05 1.576E-05 1170. 7.460E-05 6.727E-05 1170. 3.783E-04 3.255E-04 SSE 1189. 1189. 1.402E-05 1.334E-05 1189. 5.149E-05 4.671E-05 1189. 2.278E-04 1.962E-04 S 1422. 1422. 9.051E-06 8.594E-06 1422. 2.975E-05 2.704E-05 1422. 1.270E-04 1.096E-04 SSW 1198. 1198. 8.431E-06 8.074E-06 1198. 2.808M-05 2.563E-05 1198. 1.505E-04 1.293E-04 Sw 2140. 2140. 4.938E-06 4.658E-06 2140. 1.613E-05 1.459E-05 2140. 8.011E-05 6.932E-05 WSW 1372. 1372. 8.224E-06 7.852E-06 1372. 3.413E-05 3.088E-05 1372. 2.212E-04 1.900E-04 823. 823. 1.283E-05 1.234E-05 823. 7.137E-05 6.430E-05 823. 4.990E-04 4.250E-04 W 713. 713. 1.619E-05 1.558E-05 713. 9.876E-05 8.833E-05 713. 8.170E-04 6.918E-04 WNW 713. 713. 1.461E-05 1.405E-05 713. 1.166E-04 1.029E-04 713. 1.121E-03 9.465E-04 823. 823. 1.457E-05 1.396E-05 823. 8.573E-05 7.661E-05 823. 7.625E-04 6.468E-04 WNW 1481. 1481. 9.664E-06 9.184E-06 1481. 5.202E-05 4.667E-05 1481. 3.480E-04 2.982E-04 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-8f F-1 7
QUAD CITIES Revision 1.8 I June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Dowinwind Unrestricted ELevated(Stack) ReLease Nixed Nede(Vent) ReLease Ground Level G ReleaseGBAR Radius Direction Area Bound Radius S SOAR Radius V VBAR (meters) (mrad/yr)/(uCi/sec) (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/seC) N 864. 864. 1.741E-05 1.678E-05 864. 1.161E-04 1.068E-04 864. 7.126E-04 5.171E-04 6.308E-04 4.609E-04 1.810E-05 1029. 9.493E-05 8.825E-05 1029. NNE 1029. 1029. 1.88W-05 1212. 4.541E-04 4.054E-04 WE 1212. 1.186E-05 1.140E-05 1212. 5.974E-05 5.567E-05 1212. 1367. 2.989E-04 2.675E-04 ENE 1367. 8.561E-06 8.203E-06 1367. 4.602E-05 4.266E-05 1367. 1170. 4.47BE-04 4.OOOE-04 E 1170. 1170. 1.214E-05 1.162E-05 1170. 7.658E-05 7.065E-05 ESE 1170. 8.356E-05 7.724E-05 1170. 4.264E-04 3.811E-04 1170. 1170. 1.606E-05 1.538E-05 2.301E-04 1.286E-05 1189. 5.7571E-05 5.344E-05 1189. 2.572E-04 SE 1189. 1189. 1.340E-05 1.438E-04 1.289E-04 8.767E-06 8.399E-06 1422. 3.309E-05 3.076E-05 1422. SSE 1422. 1422. 1198. 1.695E-04 1.513E-04 1198. 7.778E-06 7.503E-06 1198. 3.131E-05 2.919E-05 S 1198. 2140. 9.115E-05 8.184E-05 2140. 4.975E-06 4.743E-06 2140. 1.79OE-05 1.657E-05 SSW 2140. 1372. 2.491E-04 2.224E-04 1372. 7.778E-06 7.484E-06 1372. 3.803E-05 3.523E-05 SU 1372. 7.348E-05 823. 5.527E-04 4.896E-04 823. 823. 1.135E-05 1.099E-05 823. 7.956E-05 WSW 713. 1.096E-04 1.006E-04 713. 8.936E-04 7.872E-04 W 713. 713. 1.419E-05 1.375E-05 1.070E-03
,NU 713. 1.283E-04 1.166E-04 713. 1.2181-03 WNW 713. 713. 1.281E-05 1.241E-05 7.389E-04 1.262E-05 823. 9.513E-05 8.731E-05 823. 8.374E-04 MW 823. 823. 1.308E-05 1481. 3.907E-04 3.480E-04 1481. 9.317E-06 8.932E-06 1481. 5.833E-05 5.3729-05 NNW, 1481.
QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87
'OJ/odcm/quadfrt1-8f
-18
I QUAD CITIES Revision 1.8 June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m Downwind Unrestricted Elevated(Stack) ReLease Mixed NodeCVent) Retease Direction Area Bound Radius Ground Level ReLease S SSAR Radius V VBAR Radius (meters) (meters) CmrlK/yr)/(Cci/sec) G GBAR (meters) (mrad/yr)I(uCi/sec) (meters) (mrad/yr)/uCsi/sec) N 864. 864. 2.899M-04 2.803E-04 8a". 8.530M-04 8.236E-04 2.453E-03 2.363E1-03 NNE 1029. 1029. 2.877E-04 2.781E-04 1029. 864. 7.645E-04 7.384E-04 1029. 1.941E-03 1.870E-03 NE 1212. 1212. 1.756E-04 1.697E-04 1212. 4.44"7-04 4.296E-04 1212. 1.382E-03 1.332E-03 ENE 1367. 1367. 1.163E-04 1.125E-04 1367. 3.217E-04 3.107E-04 1367. 9.117E-04 8.789E-04 E 1170. 1170. 1.741E-04 1.683E-04 1170. 5.632E-04 5.438E-04 1170. 1.662E-03 1.602E-03 ESE 1170. 1170. 2.308E-04 2.231E-04 1170. 6.317E-04 6.100E-04 1170. 1.681E-03 1.620E-03 SE 1189. 1189. 1.959E-04 1.894E-04 1189. 4.536E-04 4.381E-04 1189. 1.003E-03 9.670E-04 SSE 1422. 1422. 1.166E-04 1.127E-04 1422. 2.398E-04 2.316E-04 1422. 5.084E-04 4.901E-04 S 1198. 1198. 1.163E-04 1.124E-04 1198. 2.423E-04 2.340E-04 1198. 5.714E-04 5.507E-04 SSW 2140. 2140. 5.156E-05 4.984E-05 2140. 1.028E-04 9.925E-05 2140. 2.160E-04 2.082E-04 SW 1372. 1372. 1.099E-04 1.063E-04 1372. 2.682E-04 2.590E-04 1372. 7.263E-04 7.000E-04 WSW 823. 823. 1.979E-04 1.914E-04 823. 6.335E-04 6.118E-04 823. 2.055E-03 1.979E-03 W 713. 713. 2.585E-04 2.499E-04 713. 8.524E-04 8.229E-04 713. 3.381E-03 3.255E-03 "WNW 713. 713. 2.323E-04 2.246E-04 713. 8.874E-04 8.564E-04 NW 823. 713. 4.500E-03 4.332E-03 823. 2.227E-04 2.153E-04 823. 6.913E-04 6.674E-04 NNW 1481. 823. 2.772E-03 2.670E-03 1481. 1.264E-04 1.222E-04 1481. 3.575E-04 3.452E-04 1481. 9.461E-04 9.117E-04 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESP OJ/odcm/quad/frl.81f F-19
Revision June 19961.8 QUAD CITIES I Table F-7 (Continued) for Xe-135 Based on 1 cm Depth at the Unrestricted Area Boundary Maximum Offsite Finite Plume Gamma Dose Factors Nixed Node(Vont) ReLease Ground Level G Release GBAR VBAR Radius Downwind unrestricted ELevated(Stack) ReLease Radius V (mrad/yr)l(uCi/sec) S SSAR (meters) Direction Area Bound Radius (meters) (mrad/yr)I(uWilSec) (meters) (meters) (omryo/yltULilse;, 864. 5.847E-04 6.779E-04 6.555E-04 $64. 1029. 2.851E-03 2.103E-03 2.178E-03 2.753E-03 864. 1.7875E-04 1.729E-04 1.807E-04 1029. 6.045E-04 N 1029. 1.867E-04 3.894E-04 3.766E-04 1212. 1.917E-03 1.851E-03 "NNE 1029. 1212. 1.196E-04 1. 158E-04 1212. 1.285E-03 1.242E-03 NE 1212. 1367. 2.860E-04 2.766E-04 1367. 1367. 1367. 8.192E-05 7.928E-05 4.571E-04 4.420E-04 1170. 1.913E-03 1.848E-03 EME 1.145E-04 1.1085E-04 1170. 1.833E-03 1.771E-03 1170. 1170. 5.067E-04 4.900E-04 1170. E 1.504E-04 1.456E-04 1170. 1.113E-03 1.075E-03 1170. 1170. 1189. 3.627E-04 3.508E-04 1189. ESE SE 1189. 1189. 1.287E-04 1.246E-04 2.113E-04 2.044E-04 1422. 6.264E-04 6.052E-04 8.204E-05 7.939E-05 1422. 7.175E-04 6.931E-04 SSE 1422. 1422. 1198. 2.044E-04 1.97M5-04 1198. 1198. 7.961E-05 7.705E-05 3.955E-04 3.812E-04 S 1198. 1.103E-04 1.067E-04 2140. 2140. 4.304E-05 4.165E-05 2140. 1.046E-03 1.010E-03 SSW 2140. 1372. 2.359E-04 2.282E-04 1372. SW 1372. 1372. 7.655E-05 7.409E-05 4.833E-04 4.674E-04 823. 2.225E-03 2.149E-03 1.242E-04 1.202E-04 823. 3.4785-03 3.358E-03 823. 823. 713. 6.395E-04 6.183E-04 713. 713. 1.573E-04 1.522E-04 713. 4.6605-03 4.498E-03 WSW 713. 713. 6.923E-04 6.693E-04 713. 713. 1.415E-04 1.370E-04 5.510E-04 5.328E-04 823. 3.277E-03 3.164E-03 WNW 1.384E-04 1.340E-04 823. 1.605E-03 1.550E-03 M'U 823. 823. 3.406E-04 3.293E-04 1481. 8.796E-05 8.512E-05 1481. NNU 1481 . 1481. QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 "oOJiodcm/quasdfrl-8f
I QUAD CITIES Revision 1.8 June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 Domnuind Unrestricted Elevated(Stack) Release Mixed Node(Vent) ReLease Ground Level ReLease Direction Area Bound Radius S SBAR Radius V VBAR Radius G GSAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (wmad/yr)/(uCi/sec) (meters) (mred/yr)/(uCi/sec) N 864. 864. 9.587E-05 9.280M-05 864. 2.169E-04 2.100E-0k 864. 3.650E-04 3.532E-04 MNE 1029. 1029. 8.396E-05 8.127E-05 1029. 1.789E-04 1.731E-04 1029. 2.883E-04 2.789E-04 WE 1212. 1212. 4.406E-05 4.265E-05 1212. 8.327E-05 8.059E-05 1212. 1.506E-04 1.457E-04 ENE 1367. 1367. 2.876E-05 2.784E-05 1367. 6.062E-05 5.866E-05 1367. 9.706E-05 9.392E-05 E 1170. 1170. 5.014E-05 4.854E-05 1170. 1.280E-04 1.239E-04 1170. 2.375E-04 2.298E-04 ESE 1170. 1170. 6.821E-05 6.603E-05 1170. 1.5171E-04 1.4681-04 1170. 2.747E-04 2.658E-04 SE 1189. 1189. 5.604E-05 5.425E-05 1189. 1.044E-04 1.010E-04 1189. 1.631E-04 1.578E-04 SSE 1422. 1422. 2.842E-05 2.751E-05 1422. 4.591E-05 4.443E-05 1422. 6.975E-05 6.749E-05 S 1198. 1198. 3.027E-05 2.930E-05 1198. 5.064E-05 4.901E-05 1198. 8.267E-05 7.999E-05 SSW 2140. 2140. 8.925E-06 8.639E-06 2140. 1.344E-05 1.301E-05 2140. 1.753E-05 1.696E-05 SI 1372. 1372. 2.697E-05 2.611E-05 1372. 5.261E-05 5.091E-05 1372. 8.334E-05 8.064E-05 WSW 823. 823. 6.236E-05 6.037E-05 823. 1.682E-04 1.628E-04 823. 3.760E-04 3.638E-04 U 713. 713. 8.655E-05 8.378E-05 713. 2.349E-04 2.2741-04 713. 5.968E-04 5.775E-04 WNU 713. 713. 7.7Tr7-05 7.529E-05 713. 2.298E-04 2.224E-04 713. 7.3541E-04 7.115E-04 NW 823. 823. 7.090E-05 6.863E-05 823. 1.705E-04 1.650E-04 823. 3.973E-04 3.845E-04 WNW 1481. 1481. 3.192E-05 3.090E-05 1481. 6.298E-05 6.095E-05 1481. 7.935E-05 7.678E-05 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 E S P OJ/odcm/quadlfrl-8f F-21
QUAD CITIES Revision 1.8 I June 1996 Table F-7 (Continued) Unrestricted Area Boundary for Xe-138 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Nixed Node(Vent) ReLease Ground Level Release OomMind Unrestricted ELevated(Stack) ReLease Radius G GAR Bound Radius S SBAR Radius V VBAR Direction Area (meters) (nrad/yr)/(uCi/sec) (meters) (meters) (mred/yr)/(uCi/seC) (meters) (wrad/yr)/(uCi/sec) 864. 1.909E-03 5.007E-03 3.874E-03 3.991E-03 4.860E-03 7.602E-04 7.388W-04 864. 1.7281-03 1.854E-03 1.679E-03 1029. N 864. 1029. 1029. 7.527E-04 7.315E-04 1029. 1.005E-03 9.759E-04 1212. 2.814E-03 2.731E-03 NNE 1212. 1212. 4.600E-04 4.471E-04 1.859E-03 1.804E-03 NE 1212. 1367. 7.202E-04 6.995E-04 1367. ENE 1367. 1367. 3.014E-04 2.929E-04 1.258E-03 1.222E-03 1170. 3.418E-03 3.318E-03 4.505E-04 4.378E-04 1170. 3.473E-03 3.371E-03 E 1170. 1170. 1170. 1.414E-03 1.373E-03 1170. 1170. 1170. 5.943E-04 5.775E-04 9.929E-04 1189. 2.076E-03 2.015E-03 ESE 4.916E-04 1189. 1.022E-03 SE 1189. 1189. 5.059E-04 1422. 1.049E-03 1.018E-03 2.910E-04 1422. 5.384E-04 5.229E-04 1.174E-03 1.139E-03 1422. 1422. 2.995E-04 1198. SSE 5.469E-04 5.312E-04 S 1198. 1198. 3.027E-04 2.941E-04 1198. 2.269E-04 2.204E-04 2140. 4.390E-04 4.262E-04 1.297E-04 1.260E-04 2140. 1.480E-03 1.436E-03 SSW 2140. 2140. 6.005E-04 5.832E-04 1372. 2.843E-04 2.763E-04 1372. 4.220E-03 4.095E-03 SW 1372. 1372. 823. 1.428E-03 1.387E-03 823. WSW 823. 823. 5.252E-04 5.104E-04 1.859E-03 713. 6.917E-03 6.712E-03 713. 1.914E-03 W 713. 713. 6.885E-04 6.691E-04 1.974E-03 1.917E-03 713. 9.182E-03 8.910E-03 6.188E-04 6.014E-04 713. 5.640E-03 5.474E-03 "WNW 713. 713. 823. 1.550E-03 1.505E-03 823. MU 823. 823. 5.894E-04 5.728E-04 7.909E-04 7.681E-04 1481. 1.903E-03 1.847E-03 3.244E-04 3.152E-04 1481. WNIN 1481. 1481. WQAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPO "cm/quad/frl-8f
I QUAD IES Revision 1 8U June 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 DonwwInd Unrestricted Etevated(Stack) Release Mixed Nods(Vent) Release Ground Level Reteese Direction Area Bouid Radius S SBAR Radius V VIMR Radius G GBAR (meters) (meters) (Cred/yr)I(uCi/sec) (meters) (mrsd/yr)/(uCi/swc) (moters) (mrd1/yr)/(uCi/sec) N 8a4. 864. 9.169E-04 8.875E-04 864. 2.639E-03 2.555E-03 864. 9.453E-03 9.150E-03 NNE 1029. 1029. 9.534E-04 9.229E-04 1029. 2.410E-03 2.333E-03 1029. 7.295E-03 7.061E-03 NE 1212. 1212. 6.143E-04 5.947E-04 1212. 1.545E-03 1.496E-03 1212. 6.170E-03 5.973E-03 ENE 1367. 1367. 4.130E-04 3.998E-04 1367. 1.116E-03 1.080M-03 1367. 4.131E-03 3.999E-03 E 1170. 1170. 5.748E-04 5.564E-04 1170. 1.782E-03 1.725E-03 1170. 6.371E-03 6.167E-03 ESE 1170. 1170. 7.494E-04 7.254E-04 1170. 1.976E-03 1.913E-03 1170. 6.1488-03 5.951E-03 SE 1189. 1189. 6.447E-04 6.241E-04 1189. 1.435E-03 1.389E-03 1189. 3.710E-03 3.591E-03 SSE 1422. 1422. 4.090E-04 3.959E-04 1422. 8.282E-04 8.017E-04 1422. 2.052E-03 1.9868-03 S 1198. 1198. 4.040E-04 3.910E-04 1198. 8.103E-04 7.843E-04 1198. 2.334E-03 2.259E-03 SSW 2140. 2140. 2.070E-04 2.004E-04 2140. 4.157E-04 4.024E-04 2140. 1.195E-03 1.157E-03 SW 1372. 1372. 3.864E-04 3.740E-04 1372. 9.192E-04 8.898-04 1372. 3.318E-03 3.212E-03 WSW 823. 823. 6.504E-04 6.296E-04 823. 1.917E-03 1.856E-03 823. 7.433E-03 7.196E-03 U 713. 713. 8.303E-04 8.037E-04 713. 2.525E-03 2.445E-03 713. 1.179E-02 1.141E-02 WNW 713. 713. 7.474E-04 7.235E-04 713. 2.689E-03 2.603E-03 713. 1.583E-02 1.532E-02 NW 823. 823. 7.219E-04 6.988E-04 823. 2.157E-03 2.088E-03 823. 1.085E-02 1.050E-02 NNU 1481. 1481. 4.362E-04 4.222E-04 1481. 1.291E-03 1.249E-03 1481. 4.963E-03 4.805E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl.6f F-23
QUAD CITIES Revision June 19961.8 STable F-7a at the Restricted Area Boundary for Kr-83m Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth Ground fius Levet G ReleaseGBAR Etevated(Stack) Retease Nixed Node(Vent) Release Downwind Restricted Radius V VBAR Reters) (mrad/yr)l(uCi/sec) S SOAR Direction Area Bound Radius (meters) (mradyr)/(uCIlsec) imet (meters) (meters) (.rad/yr)/(uCi/sec) 219. 3.034E-03 2.2881-03 2.757E-04 2.079E-04 1.613E-04 224. 2.773E-03 2.091E-03 219. 219. 6.431E-07 4.849E-07 219. 224. 2.140E-04 1.770E-03 N 224. 7.975E-07 6.013E-07 1.165E-04 8.782E-05 265. 2.3482-03 NNE 224. 265. 7.696E-04 265. 265. 5.110E-07 3.853E-07 6.930E-05 5.225E-05 393. 1.021E-03 RiE 7.578E-07 393. 867. 3.636E-04 2.742E-04 ENE 393. 393. 1.005E-06 867. 3.734E-05 2.816E-05 E 867. 1.516E-06 1.1432-06 2.711E-05 924. 3.118E-04 2.351E-04 867. 924. 3.596E-05 1.236E-04 ESE 924. 1.867E-06 1.408E-06 2.064E-05 1.556E-05 1010. 1.6405-04 924. 1010. 1.089E-04 8.211E-05 SE 1010. 1010. 1.3085-06 9.866W-07 1.272E-05 9.592E-06 1059. 6.600E-07 1059. 762. 1.7255-04 1.300E-04 SSE 1059. 1059. 8.754E-07 762. 1.388E-05 1.046E-05 762. 4.368E-07 3.294E-07 3.513E-05 335. 7.271E-04 5.483E-04 S 762. 335. 4.659E-05 1.386E-03 335. 3.150E-07 2.375E-07 8.5585-05 232. 1.838E-03 SSW 335. 232. 1.135E-04 2.043E-03 232. 3.086E-07 2.327E-07 1.502E-04 189. 2.710E-03 SW 232. 189. 1.991E-04 3.612E-03 2.723E-03 189. 3.671E-07 2.768E-07 2.4985-04 1.884E-04 189. 189. 189. 3.890E-03 tiW 189. 4.2985-07 3.241E-07 3.557E-04 2.682E-04 183. 5.159E-03 189. 183. 3.537E-03 2.667E-03 183. 3.9285-07 2.962E-07 1.742E-04 210. 183. 210. 2.310E-04 3.330E-03 2.5115-03 WNW 210. 4.1845-07 3.155E-07 1.945E-04 224. 210. 224. 2.580E-04 WNW NMW 224. 4.846E-07 3.654E-07 224. QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 I of ':w .. .I .i i, - t*.. , . ,e.t~ons £. 5 and B 6 of Appendix B. Note Based on Relererc ESPOY -4*
*m/quad/frl-8f F-2,'
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Douwuind Restricted ELevated(Stack) ReLease Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uci/sec) N 219. 219. 4.678E-04 4.528E-04 219. 2.202E-03 2.117E-03 219. 1.154E-02 1.100E-02 NNE 224. 224. 5.607E-04 5.427E-04 224. 2.271E-03 2.187E-03 224. NE 265. 1.119E-02 1.068E-02 265. 3.522E-04 3.409E-04 265. 1.370E-03 1.320E-03 265. 9.701E-03 9.261E-03 ENE 393. 393. 1.843E-04 1.784E-04 393. 7.728E-04 7.43E-04 393. 4.697E-03 4.490E-03 E 867. 867. 1.074E-04 1.038E-04 867. 4.558E-04 4.391E-04 867. 2.075E-03 1.988E-03 ESE 924. 924. 1.327E-04 1.283E-04 924. 4.697E-04 4.527E-04 924. 1.831E-03 1.754E-03 SE 1010. 1010. 1.058E-04 1.023E-04 1010. 3.100E-04 2.990E-04 1010. SSE 1.008E-03 9.667E-04 1059. 1059. 7.523E-05 7.278E-05 1059. 2.050E-04 1.977E-04 1059. 6.733E-04 6.454E-04 S 762. 762. 8.422E-05 8.150E-05 762. 2.332E-04 2.250E-04 762. SSW 9.467E-04 9.066E-04 335. 335. 1.614E-04 1.562E-04 335. 5.473E-04 5.273E-04 335. 3.128E-03 2.987E-03 SW 232. 232. 2.814E-04 2.723E-04 232. 1.105E-03 1.064E-03 232. WSW 7. 183E-03 6.852E-03 189. 189. 3.592E-04 3.477E-04 189. 1.694E-03 1.629E-03 189. 1.012E-02 9.646E-03 W 189. 189. 4.016E-04 3.888E-04 189. 1.938E-03 1.863E-03 189. 1.299E-02 1.238E-02 MNW 183. 183. 3.732E-04 3.613E-04 183. 2.246E-03 2.155E-03 183. NMW 1.797E-02 1.711E-02 210. 210. 3.616E-04 3.500E-04 210. 1.766E-03 1.697E-03 210. 1.297E-02 1.236E-02 WNW 224. 224. 3.668E-04 3.551E-04 224. 1.932E-03 1.856E-03 224. 1.251E-02 1.192E-02 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quadlfr1.8f F-25
Revision June 19961.8 I QUAD CITIES Table F-7a (Continued) Area Boundary for Kr-85 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted ELevated(Stack) Retease Nixed Node(Vent) Release Ground Level dius G Release GBAR Doomwind Restricted V VBAR Ratters) (mad/yr)/(uCi/sec) Direction Area Bound Radius S SBAR Radius (meters) (meters) (mrad/yr)/(uCI/sec) (meters) (mradl/yr)/(uCi/sec) (mew 219. 1.241E-04 1.2001-04 219. 219. 6.596E-06 6.379E-06 219. 2.551E-05 2.467E-05 224. 1.201E-04 1.162E-04 N 224. 2.675E-05 2.587E-05 NNE 224. 224. 7.986E-06 7.7231-06 1.583E-05 265. 1.047E-04 1.012E-04 4.900E-06 265. 1.637E-05 NE 265. 265. 5.068E-06 393. 5.108E-05 4.939E-05 2.542E-06 393. 9.149E-06 8.847E-06 ENE 393. 393. 2.629E-06 867. 2.311E-05 2.235E-05 1.434E-06 867. 5.373E-06 5.196E-06 E 867. 867. 1.483E-06 5.374E-06 924. 2.041E-05 1.973E-05 1.823E-06 1.7635-06 924. 5.557E-06 ESE 924. 924. 3.696E-06 3.574E-06 14010. 1.134E-05 1.096E-05 1010. 1.464E-06 1.415E-06 1010. SE 1010. 1059. 2.466E-06 2.384E-06 1I059. 7.598E-06 7.347E-06 SSE 1059. 1059. 1.050E-06 1.016E-06 762. 1.056E-05 1.021E-05 S 762. 2.808-06 2.715E-06 762. 762. 1.194E-06 1.155E-06 335. 3.389E-05 3.277E-05 SSW 335. 6.504E-06 6.290E-06 335. 335. 2.320E-06 2.243E-06 232. 7.734E-05 7.479E-05 Sw 232. 1.301E-05 1.258E-05 232. 232. 4.038E-06 3.905E-06 189. 1.086E-04 1.050E-04 189. 1.978E-05 1.913E-05 WSW 189. 189. 5.147E-06 4.977E-06 189. 2.251E-05 2.176E-05 189. 1.394E-04 1.348E-04 189. 189. 5.740E-06 5.551E-06 183. 1.927E-04 1.864E-04 183. 2.578E-05 2.493E-05 183. 183. 5.334E-06 5.158E-06 210. 1.396E-04 1.350E-04 NW 4.988E-06 210. 2.051E-05 1.983E-05 210. 210. 5.158E-06 224. 1.347E-04 1.303E-04 224. 2.234E-05 2.160E-05 NNW 224. 224. 5.197E-06 5.025E-06 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 "6 r *J/odcm/quad/fr1-8f
K> QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Downwind Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area, Bound Radius S SBAR Radius V VRAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCj/sec) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 219. 219. 2.415E-03 2.346E-03 219. 7.757E-03 7.533E-03 219. 3.450E-02 3.350E-02 NNE 224. 224. 2.948E-03 2.86E-03 224. 8.289E-03 8.050E-03 224. 3.368E-02 3.270E-02 NE 265. 265. 1.888E-03 1.834E-03 265. 5.102E-03 4.955E-03 265. 2.884E-02 2.800E-02 ENE 393. 393. 9.666E-04 9.391E-04 393. 2.802E-03 2.721E-03 393. 1.382E-02 1.342E-02 E 867. 867. 5.225E-04 5.076E-04 867. 1.601E-03 1.555E-03 867. 5.968E-03 5.794E-03 ESE SE 924. 924. 6.370E-04 6.188E-04 924. 1.650E-03 1.603E-03 924. 5.283E-03 5.129E-03 SSE 1010. 1010. 5,090E-04 4.945E-04 1010. 1.107E-03 1.075E-03 1010. 2.886E-03 2.802E-03 S 1059. 1059. 3.643E-04 3.539E-04 1059. 7.298E-04 7.088E-04 1059. 1.911E-03 1.856E-03 SSW 762. 762. 4.232E-04 4.112E-04 762. 8.482E-04 8.237E-04 762. 2.691E-03 2.613E-03 SW 335. 335. 8.550E-04 8.307E-04 335. 2.001E-03 1.943E-03 335. 9.243E-03 8.974E-03 WSW 232. 232. 1.501E-03 1.459E-03 232. 4.021E-03 3.905E-03 232. 2.143E-02 2.081E-02 189. 189. 1.909E-03 1.855E-03 189. 6.096E-03 5.9201-03 189. 3.040E-02 2.952E-02 W 189. 189. 2.1291E-03 2.068E-03 189. 6.898E-03 6.699E-03 189. 3.912E-02 3.798E-02 WNW 183. 183. 1.976E-03 1.920E-03 183. 7.817E-03 7.592E-03 183. 5.420E-02 5.262E-02 210. 210. 1.908E-03 1.853E-03 210. 6.257E-03 6.076E-03 210. 3.8789-02 3.765E-02 WNW 224. 224. 1.909E-03 1.855E-03 224. 6.787E-03 6.591E-03 224. 3.727E-02 3.619E-02 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/fr1-8f F-27
Revision June 19961.8 QUAD CITIES Table F-7a (Continued) at the Restricted Area Boundary for Kr-88 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth Nixed Node(Vent) ReLease Ground Level ReLease Dounwind Restricted ELevated(Stack) ReLease V VBAR Radius G GBAR Direction Area Bound Radius S SBAR. Radius (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)l(uCtisec) 219. 219. 6.197E-03 6.033E-03 219. 1.878E-02 1.826E-02 M1. 224. 8.281E-02 8.040E-02 8.036E-02 7.8038-02 N 224. 2.013E-02 1.958E-02 224. 224. 7.596E-03 7.395E-03 265. 6.946E-02 6.742E-02 NNE 4.761E-03 265. 1.250E-02 1.215E-02 NE 265. 265. 4.891E-03 6.673E-03 393. 3.360E-02 3.262E-02 2.512E-03 2.445E-03 393. 6.861E-03 ENE 393. 393. 3.952E-03 3.844E-03 867. 1.491E-02 1.448E-02 867. 1.354E-03 1.318E-03 867. 1.280E-02 E 867. 924. 4.083E-03 3.971E-03 924. 1.318E-02 924. 924. 1.646E-03 1.602E-03 2.672E-03 1010. 7.268E-03 7.061E-03 ESE 1.286E-03 1010. 2.747E-03 SE 1010. 1010. 1.321E-03 I.T77E-03 1059. 4.843E-03 4.705E-03 9.262E-04 1059. 1.828E-03 SSE 1059. 1059. 9.514E-04 2.052E-03 762. 6.758E-03 6.563E-03 1.107E-03 1.078E-03 762. 2.109E-03 S 762. 762. 4.767E-03 335. 2.238E-02 2.172E-02 335. 2.223E-03 2.164E-03 335. 4.901E-03 4.997E-02 SSW 335. 232. 9.782E-03 9.512E-03 232. 5.149E-02 232. 232. 3.884E-03 3.782E-03 189. 7.2708-02 7.054E-02 SU 189. 1.477E-02 1.436E-02 189. 189. 4.927E-03 4.797E-03 1.622E-02 189. 9.350E-02 9.072E-02 USW 5.348E-03 189. 1.669E-02 W 189. 189. 5.494E-03 1.836E-02 183. 1.295E-01 1.257E-01 4.961E-03 183." 1.889E-02 183. 183. 5.096E-03 1.475E-02 210. 9.319E-02 9.042E-02 WNW 4.787E-03 210. 1.517E-02 MW 210. 210. 4.917E-03 1.598E-02 224. 8.972E-02 8.7068-02 4.7788-03 224. 1.644E-02 NNW 224. 224. 4.908E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 "POJ/odcm/quad/fr1-8f r--28
QGAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depti -at the Restricted Area Boundary for Kr-89 Downwind Restricted Elevated(Stack) Release Nixaed NodeCVent) Release Ground Level Release uirection Area Bound Radius s SBAR Radius V VRAR Radius G GBAR (metors) (meters) (Crad/yr)/(uCi/sec) (meters) (mr'd/yr)/(uiI/sec) (meters) (nrad/yr)/(uCi/sec) N 219. 219. 4.468E-03 4.343E-03 219. 1.234E-02 1.199E-02 219. 3.852E-02 3.741E-02 NNE 224. 224. 5.294E-03 5.145E-03 224. 1.371E-02 1.332E-02 224. 4.217E-02 4.096E-02 NE 265. 265. 3.186E-03 3.096E-03 265. 7.526E-03 7.311E-03 265. ENE 2.9075-02 2.824E-02 393. 393. 1.463E-03 1.421E-03 393. 3.687E-03 3.582E-03 393. 1.142E-02 1.109E-02 E 867. 867. 6.059E-04 5.8885-04 867. 1.457E-03 1.415E-03 867. 2.884E-03 2.801E-03 ESE 924. 924. 7.398E-04 7.189E-04 924. 1.526E-03 1.483E-03 924. SE 2.824E-03 2.743E-03 1010. 1010. 5.412E-04 5.260E-04 1010. 9.2165-04 8.953E-04 1010. SSE 1.409E-03 1.369E-03 1059. 1059. 3.421E-04 3.324E-04 1059. 5.267E-04 5.117E-04 1059. 8.474E-04.8.231E-04 S 762. 762. 4.708E-04 4.575E-04 762. 7.716E-04 7.496E-04 762. 1.441E-03 1.399E-03 SSW 335. 335. 1.328E-03 1.291E-03 335. 2.813E-03 2.733E-03 335. 8.950E-03 8.692E-03 SW 232. 232. 2.630E-03 2.556E-03 232. 6.447E-03 6.263E-03 232. 2.394E-02 2.325E-02 189. 189. 3.460E-03 3.362E-03 189. 1.036E-02 1.0071E02. 189. 3.848E-02 3.7375-02 U 189. 189. 3.883E-03 3.773E-03 189. 1.15SE-02 1.125E-02 189. 4.850E-02 4.710E-02 WNW 183. 183. 3.624E-03 3.523E-03 183. 1.268E-02 1.232E-02 183. 6.720E-02 6.527E-02 210. 210. 3.446E-03 3.349E-03 210. 9.860E-03 9.5785-03 210. 4.213E-02 4.092E-02 NNW 224. 224. 3.469E-03 3.371E-03 224. 1.052E-02 1.022E-02 224. 3.886E-02 3.775E-02 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcmlquadlfrl-8f F-29
Revision June 19961.8 I QUAD CITIES Table F-7a (Continued) Depth at the Restricted Area Boundary for Kr-90 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Nixed Node(Vent) Release Ground Level Radius G ReteaseGBAR Downwind Restricted Elevated(Stack) Release S SBAR Radius V VBAR (meters) (mred/yr)/(uCilsec) Direction Area Bound Radius (ieters) (meters) (maed/yr)/(uCi/sec) (meters) (mrad/yr)/(uilsec). 219. 2.813E-03 2.730E-03 219. 5.516E-03 5.351E-03 219. 224. 8.230E-03 1.051E-02 7.977E-03 1.019E-02 N 219. 2.892E-03 224. 5.985E-03 5.807E-03 NNE 224. 224. 2.979E-03 265. 4."7E-03 4.330E-03 1.349E-03 265. 2.265E-03 2.197E-03 NE 265. 265. 1.390E-03 393. 1.12&'-03 1.094E-03 4.751E-04 393. 8.252E-04 8.005E-04 7.612E-05 ENE 393. 393. 4.894E-04 1.043E-04 867. 7,&51E-!15 8.398E-05 8.151E-05 867. 1.075E-'. 9.038E-05 E 867. 867. 1.034E-04 924. 9.321E-05 9.702E-05 9.416E-05 924. 1.066E-04 3.214E-05 3.117E-05 ESE 924. 924. 4.494E-05 4.360E-05 1010. SE 1010. 5.060E-05 4.911E-05 1010. 1.452E-05 1.408E-05 1010. 1059. 1.841E-05 1.786E-05 1059. SSE 1059. 1059. 2.124E-05 2.061E.05 762. 6.452E-05 6.256E-05 762. 5.625E-05 5.460E-05 762. 5.725E-05 5.555E-05 S 762. 335. 1.528E-03 1.481E-03. 4.663E-04 335. 7.966E-04 7.728E-04 335. 335. 4.803E-04 232. 5.711E-03 5.536E-03 232. 1.374E-03 1.334E-03 232. 2.739E-03 2.657E-03 1.242E-02 232. 189. 1.282E-02 WSW 2.114E-03 2.052E-03 189. 5.336E-03 5.1T77-03 1.296E-02 189. 189. 189. 1.337E-02 2.413E-03 2.342E-03 189. 5.761E-03 5.589E-03 1.582E-02 W 189. 189. 183. 1j,433E-02 2.295E-03 2.228E-03 183. 5.876E-03 5.700E-03 8.487E-03 8.226E-03 WNWW 183. 183. 4.131E-03 4.008E-03 210. 210. 2.006E-03 1.948E-03 210. 7.350E-03 7.124E-03 210. 224.- 4.283E-03 4.155E-03 224. NNW 224. 224. 2.057E-03 1.997E-03 QUAD CITIES SITE HETEOROLOGFCAL DATA 1178 - 12/87
-30 ,OJ/odcm/quad/frl-8f
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m Downwind Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mred/yr)/(uCilsec) (meters) (wrad/yr)/(uCf/sec) (meters) (mrad/yr)/(uCi/sec) N 219. 219. 1.042E-05 9.918E-06 219. 2.625E-04 2.076E-04 219. 2.654E-03 2.051E-03 NINE 224. 224. 1.252E-05 1.198E-05 224. 2.145E-04 1.718E-04 224. 2.425E-03 1.876E-03 NE 265. 265. 7.875E-06 7.538E-06 265. 1.202E-04 9.671E-05 265. 2.083E-03 1.612E-03 ENE 393. 393. 4.703E-06 4.384E-06 393. 7.093E-05 5.693E-05 393. 9.278E-04 7.200E-04 E 867. 867. 3.490E-06 3.120E-06 867. 3.954E-05 3.186E-05 867. 3.518E-04 2.746E-04 ESE 924. 924. 4.296E-06 3.843E-06 924. 3.871E-05 3.131E-05 924. 3.029E-04 2.366E-04 SE 1010. 1010. 3.290E-06 2.964E-06 1010. 2.310E-05 1.881E-05 1010. 1.626E-04 1.271E-04 SSE 1059. 1059. 2.305E-06 2.082E-06 1059. 1.463E-05 1.196E-05 1059. 1.091E-04 8.534E-05 S 762. 762. 2.145E-06 2.003E-06 762. 1.607E-05 1.317E-05 762. 1.675E-04 1.305E-04 SSW 335. 335. 3.679E-06 3.508E-06 335. 4.813E-05 3.873E-05 335. 6.527E-04 5.056E-04 Su 232. 232. 6.212E-06 5.962E-06 232. 1. 120E-04 8.931E-05 232. 1.615E-03 1.248E-03 WSW 189. 189. 7.908E-06 7.594E-06 189. 1.908E-04 1.513E-04 189. 2.355E-03 1.819E-03 U 189. 189. 8.855E-06 8.500E-06 189. 2.355E-04 1.861E-04 189. 3.123E-03 2.410E-03 "WNW 183. 183. 8.223E-06 7.895E-06 183. 3.251E-04 2.549E-04 183. 4.444E-03 3.427E-03 NU 210. 210. 7.998E-06 7.672E-06 210. 2.181E-04 1.722E-04 210. 3.085E-03 2.381E-03 "NNU 224. 224. 8.159E-06 7.817E-06 224. 2.429E-04 1.916E-04 224. 2.919E-03 2.255E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-8Ff F-31
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Domunind Restricted Elevated(Stack) Release Nixed Noca(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad/yr)/(uCi/sec), (meters) (Crad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCllsec) N 219. 219. 6.658E-05 6.434E-05 219. 5.2778-04 4.625E-04 219. 4.053E-03 3.384E-03 NNE 224. 224. 7.985E-05 7.715E-05 224. 4.8778-04 4.348E-04 224. 3.778E-03 3.168E-03 WE 265. 265. 5.019E-05 4.850E-05 265. 2.852E-04 2.557E-04 265. 3.261E-03 2.737E-03 ENE 393. 393. 2.690E-05 2.586E-05 393. 1.642E-04 1.467E-04 393. 1.501E-03 1.268E-03 E 867. 867. 1.646E-05 1.566E-05 867. 9.481E-05 8.511H-05 867. 6.083E-04 5.203E-04 ESE 924. 924. 2.032E-05 1.934E-05 924. 9.575E-05 8.628E-05 924. 5.291E-04 4.534E-04 SE 1010. 1010. 1.609E-05 1.534E-05 1010. 6.073E-05 5.510E-05 1010. 2.878E-04 2.472E-04 SSE 1059. 1059. i.143E-05 1.091E-05 1059. 3.962E-05 3.606E-05 1059. 1.930E-04 1.658E-04 S 762. 762. 1.234E-05 1.187E-05 762. 4.437E-05 4.047E-05 762. 2.848E-04 2.429E-04 SSW 335. 335. 2.311E-05 2.231E-05 335. 1.142E-04 1.023E-04 335. 1.033E-03 8.694E-04 Sw 232. 232. 4.001E-05 3.868E-05 232. 2.450E-04 2.173E-04 232. 2.486E-03 2.079E-03 uSu 189. 189. 5.105E-05 4.935E-05 189. 3.945E-04 3.472E-04 189. 3.580E-03 2.986E-03 U 189. 189. 5.708E-05 5.*518-05 189. 4.687E-04 4.101E-04 189. 4.695E-03 3.908E-03 WiU 183. 183. 5.304E-05 5.127E-05 183. 5.955E-04 5.143E-04 183. 6.617E-03 5.496E-03 MW 210. 210. 5.142E-05 4.970E-05 210. 4.308E-04 3.766E-04 210. 4.658E-03 3.881E-03 NNW 224. 224. 5.221E-05 5.045E-05 224. 4.7568-04 4.152E-04 224. 4.437E-03 3.701E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87
- "OJ/odcm/quad/tr1.'f ."-'%, 32
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133 Downwind Restricted Elevated(Stack) Release Node(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (Crad/yr)/(uCi/sec) (meters) (mred/yr)I(uCi/sac) (meters) (mrad/yr)I(uCIlsec) N 219. 219. 5.703E-05 5.546E-05 219. 5.688&-04 5.135E-04 219. 4.269E-03 3.7061-03 NNE 224. 224. 6.743E-05 6.556E-05 224. 5.298E-04 4.848E-04 224. 4.024E-03 3.509E-03 NE 265. 265. 4.182E-05 4.065E-05 265. 3.080M-04 2.829E-04 265. 3.486E-03 3.043E-03 ENE 393. 393. 2.317E-05 2.242E-05 393. 1.799M-04 1.650E-04 393. 1.631E-03 1.433E-03 E ,867. 867. 1.536E-05 1.473E-05 867. 1.062E-04 9.783E-05 867. 6.789E-04 6.037E-04 ESE 924. 924. 1.920E-05 1.843E-05 924. 1.074E-04 9.924E-05 924. 5.924E-04 5.276E-04 SE 1010. 1010. 1.509E-05 1.4511-05 1010. 6.799E-05 6.313E-05 1010. 3.236E-04 2.888E-04 SSE 1059. 1059. 1.062E-05 1.022E-05 1059. 4.413E-05 4.107E-05' 1059. 2.169E-04 1.936E-04 S 762. 762. 1.084E-05 1.050E-05 762. 4.943E-05 4.607E-05 762. 3.163E-04 2.805E-04 SSW 335. 335. 1.936E-05 1.881E-05 335. 1.245E-04 1.14"E-04 335. 1.111E-03 9.723E-04 SW 232. 232. 3.329E-05 3.2381-05 232. 2.642E-04 2.407E-04 232. 2.632E-03 2.289E-03 WlSW 189. 189. 4.249E-05 4.133E-05 189. 4.234E-04 3.833E-04 189. 3.761E-03 3.261E-03 189. 189. 4.774E-05 4.643E-05 189. 5.008E-04 4.512E-04 189. 4.897E-03 4.235E-03 NNW 183. 183. 4.433E-05 4.312E-05 183. 6.291E-04 5.606E-04 183. 6.857E-03 5.916E-03 WNW 4.219E-03 210. 210. 4.319E-05 4.201E-05 210. 4.604E-04 4.145E-04 210. 4.873E-03 NNW 224. 224. 4.440E-05 4.318E-05 224. 5.100E-04 4.588E-04 224. 4.661E-03 4.042E-03 QUAD CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-8f F-33
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-1 35m Douruind Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground LeveL ReLease Direction Area Bound Radius S SBAR Radius V VSAR Radius G GBAR (meters) (meters) (Crad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)luCit/sec) N 219. 219. 1.214E-03 1.174E-03 219. 4.549E-03 4.389E-03 219. 2.009E-02 1.932E-02 NNE 224. 224. 1.459E-03 1.410E-03 224. 4.840E-03 4.672E-03 224. 2.021E-02 1.944E-02 NE 265. 9.1"4E-04 8.842E-04 265. 2.869E-03 2.7T01-03 265. 1.633E-02 1.571E-02 ENE 393. 393. 4.59O0-04 4.4381-04 393. 1.556E-03 1.502E-03 393. 7.406E-03 7.129E-03 E 867. 867. 2.433E-04 2.352E-04 867. 8.314E-04 8.027E-04 867. 2.784E-03 2.682E-03 ESE 924. 924. 2.992E-04 2.893E-04 924. 8.543E-04 8.249E-04 924. 2.504E-03 2.412E-03 SE 1010. 1010. 2.344E-04 2.267E-04 1010. 5.597E-04 5.405E-04 1010. 1.326E-03 1.278E-03 SSE 1059. 1059. 1.624E-04 1.570E-04 1059. 3.536E-04 3.415E-04 1059. 8.534E-04 8.225E-04 762. 762. 1.912E-04 1.849E-04 762. 4.304E-04 4.157E-34 762. 1.244E-03 1.199E-03 SSW Sw 335. 335. 4.057E-04 3.923E-04 335. 1.118E-03 1.0791-03 335. 5.101E-03 4.910E-03 WSW 232. 232. 7.328E-04 7.086E-04 232. 2.329E-03 2.248E-03 232. 1.240E-02 1.193E-02 US 189. 189. 9.402E-04 9.092E-04 189. 3.601E-03 3.475E-03 189. 1.8171E-02 1.748E-02 189. 189. 1.051E-03 1.016E-03 189. 4.093E-03 3.948E-03 189. 2.348E-02 2.258E-02 NW 183. 183. 9.72E-04 9.450E-04 183. 4.652E-03 4.485E-03 183. 3.266E-02 3.140E-02 NI* 210. 210. 9.436E-04 9.124E-04 210. 3.659E-03 3.5301-03 210. 2.248E-02 2.162E-02 224. 224. 9.519E-04 9.205E-04 224. 3.971E-03 3.8301-03 224. 2.134E-02 2.052E-02 QUAD CITIES SITE NETEOROLOGICAL DATA 1178 - 12/87 "OJ/odcm/quad/fr1-8f ,.- 34 2
I QUAD ,-.iES Revision 1.u June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Dowuuind Restricted Elevated(Stack) Release Nixed Nede(Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GSAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (Caed/yr)/(uCi/sec) (meters) (wrad/yr)/(uCi/sec) N 219. 219. 6.602E-04 6.390E-04 219. 2.996E-03 2.896E-03 219. 1.525E-02 1.471E-02 NNE 224. 224. 7.921E-04 7.667E-04 224. 3.110E-03 3.007E-03 224. 1.481E-02 1.429E-02 NE 265. 265. 4.981E-04 4.821E-04 265. 1.883E-03 1.820E-03 265. 1.289E-02 1.244E-02 ENE 393. 393. 2.606E-04 2.522E-04 393. 1.061E-03 1.026E-03 393. 6.287E-03 6.069E-03 E 867. 867. 1.513E-04 1.465E-04 867. 6.281E-04 6.074E-04 867. 2.823E-03 2.727E-03 ESE 924. 924. 1.870E-04 1.809E-04 924. 6.486E-04 6.272E-04 924. 2.493E-03 2.4088-03 SE 1010. 1010. 1.493E-04 1.445E-04 1010. 4.291E-04 4.150-E04 1010. 1.379E-03 1.332E-03 SSE 1059. 1059. 1.064E-04 1.030E-04 1059. 2.847E-04 2.753E-04 1059. 9.226E-04 8.912E-04 S 762. 762. 1.193E-04 1.155E-04 762. 3.233E-04 3.1288-04 762. 1.288M-03 1.244E-03 SSu 335. 335. 2.284E-04 2.211E-04 335. 7.523E-04 7.275E-04 335. 4.170E-03 4.025E-03 SI 232. 232. 3.9788-04 3.850E-04 232. 1.511E-03 1.461E-03 232. 9.511E-03 9.1T77-03 USW' 189. 189. 5.078E-04 4.915E-04 189. 2.308E-03 2.231E-03 189. 1.335E-02 1.288E-02 189. 189. 5.676E-04 5.493E-04 189. 2.634E-03 2.546E-03 189. 1.710E-02 1.650E-02 UNU 183. 183. 5.274E-04 5.105E-04 183. 3.034E-03 2.931E-03 183. 2.361E-02 2.2T7E-02 NU 210. 210. 5.110E-04 4.946E-04 210. 2.401E-03 2.320E-03 210. 1.712E-02 1.651E-02 WNW 224. 224. 5.180E-04 5.014E-04 224. 2.624E-03 2.536E-03 224. 1.653E-02 1.595E-02 QUA=CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-8f F-35
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Dowuind Restricted Elevated(Stack) Release Nixed Nods(Vent) Retease Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius a GBAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (wrad/yr)/(uCi/sec) (meters) (wrad/yr)/(uCi/sec) N 219. 219. 5.305E-04 5.135E-04 219. 1.716E-03 1.661E-03 219. 5.932E-03 5.740E-03 NNE 224. 224. 6.272E-04 6.071E-04 224. 1.882E-03 1.821E-03 224. 6.4091-03 6.201E-03 NE 265. 265. 3.789E-04 3.668E-04 265. 1.042E-03 1.009E-03 265. 4.545E-03 4.397E-03 ENE 393. 393. 1.781E-04 1.724E-04 393. 5.246E-04 5.0772-04 393. 1.8361-03 1.776E-03 E 867. 867. 7.904E-05 7.651E-05 867. 2.211E-04 2.140E-04 867. 4.987E-04 4.825E-04 ESE 924. 924. 9.700E-05 9.389E-05 924. 2.310E-04 2.235E-04 924. 4.7%E-04 4.638E-04 SE 1010. 1010. 7.200E-05 6.970E-05 1010. 1.412E-04 1.367E-04 .1010. 2.422E-04 2.343E-04 SSE 1059. 1059. 4.623E-05 4.475E-05 1059. 8.205E-05 7.941E-05 1059. 1.473E-04 1.425E-04 S 762. 762. 6.100E-05 5.905E-05 762. 1.156E-04 1.119E-04 762. 2.425E-04 2.347E-04 SSW1 335. 335. 1.602E-04 1.551E-04 335. 3.9462-04 3.819E-04 335. 1.398E-03 1.353E-03 232. 232. 3.111E-04 3.011E-04 232. 8.871E-04 8.591E-04 232. 3.675E-03 3.556E-03 WSW 189. 189. 4.072E-04 3.942E-04 189. 1.420E-03 1.375E-03 189. 5.804E-03 5.616E-03 189. 189. 4.573E-04 4.4271E-04 189. 1.597E-03 1.545E-03 189. 7.377E-03 7.137E-03 183. 183. 4.265E-04 4.128E-04 183. 1.768E-03 1.710E-03 183. 1.024E-02 9.911E-03 NU 210. 210. 4.075E-04 3.944E-04 210. 1.371E-03 1.327E-03 210. 6.515E-03 6.303E-03 NNW 224. 224. 4.118E-04 3.986E-04 224. 1.471E-03 1.423E-03 224. 6.038E-03 5.842E-03 WAD CITIES SITE NETEOSOLOGICAL DATA 1178 -'12/87 ESPOJ/bdcm/quad/frl-8f
I QUAD UTIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Dowunund Restricted
- ELevated(Stack) Release Nixed Node(Vent) Release around Level Release Direction Area Sound Radius S SBAR Radius V VWAR Radius G GBAR (meters) (meters) (Crad/yr)/(uCi/sec) (meters) (mracd/yr)/(uCl/sec) (meters) (mrad/yr)/(uCi/sec)
N 219. 219. 3.270E-03 3.178E-03 219. 1.021E-02 9.910E-03 219. 4.159E-02 4.035E-02 NNE 224. 224. 3.963*-03 3.852E-03 224. 1.104E-02 1.072E-02 224. 4.199E-02 4.074E-02 NE 265. 265. 2.510E-03 2.439E-03 265. 6.608E-03 6.418E-03 265. 3.3781E-02 3.277M-02 ENE 393. 393. 1.24W-03 1.213E-03 393. 3.539E-03 3.438E-03 393. 1.530E-02 1.484E-02 E 867. 867. 6.389E-04 6.209E-04 867. 1.867E-03 1.813E-03 867. 5.743E-03 5.574E-03 ESE 924. 924. 7.796E-04 7.576E-04 924. 1.919E-03 1.863E-03 924. 5.180E-03 5.028E-03 SE 1010. 1010. 6.106E-04 5.934E-04 1010. 1.265E-03 1.229E-03 1010. 2.748E-03 2.667E-03 SSE 1059. 1059. 4.239E-04 4.119E-04 1059. 7.997E-04 7.767E-04 1059. 1.765E-03 1.713E-03 S 762. 762. 5.089E-04 4.946E-04 762. 9.819E-04 9.538E-04 762. 2.564E-03 2.489E-03 SSW 335. 335. 1.106E-03 1.075E-03 335. 2.550E-03 2.4775-03 335. 1.055E-02 1.024E-02 Su 232. 232. 2.005E-03 1.949E-03 232. 5.305E-03 5.152E-03 232. 2.566E-02 2.490E-02 WSW 189. 189. 2.567E-03 2.494E-03 189. 8.156E-03 7.920E-03 189. 3.7TOE-02 3.657E-02 U 189. 189. 2.866E-03 2.785E-03 189. 9.217E-03 8.950E-03 189. 4.8711E-02 4.725E-02 "WUN 183. 183. 2.663E-03 2.589E-03 183. 1.037E-02 1.007E-02 183. 6.7M5E-02 6.573E-02 NU 210. 210. 2.568E-03 2.495E-03 210. 8.229E-03 7.991E-03 210. 4.651E-02 4.512E-02 NNU 224. 224. 2.5746-03 2.501E-03 224. 8.896M-03 8.638E-03 224. 4.411E-02 4.279E-02 OUM) CITIES SITE METEOROLOGICAL DATA 1/78 - 12/87 ESPOJ/odcm/quad/frl-Sf F-37
I QUAD CITIES Revision 1.8 June 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downiind Restricted Elewated(Stack) Release Mixed Nods(Vent) Release Ground Level Release Direction Area Bound Radius S S8AR Radius V VBAR Radius G GBAR (meters) (meters) (Cad/yr)/(uCi/sec) (meters) (wrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCi/sec) N 219. 219. 3.559E-03 3.45E-03 219. 1.194E-02 1.156E-02 219. 5.457E-02 5.282E-02 NNE 224. 224. 4.337E-03 4.198E-03 224. 1.270E-02 1.229E-02 224. 5.307E-02 5.137E-02 NE 265. 265. 2.774E-03 2.685E-03 265. 7.812E-03 7.562E-03 265. 4.566%-02 4.420E-02 EVE 393. 393. 1.426E-03 1.380E-03 393. 4.305E-03 4.167E-03 393. 2.197E-02 2.126E-02 E 867. 867. 7.769E-04 7.520E-04 867. 2.4781-03 2.398E-03 867. 9.588E-03 9.281E-03 ESE 924. 924. 9.478E-04 9.174E-04 924. 2.556E-03 2.474E-03 924. 8.4T/E-03 8.205E-03 SE 1010. 1010. 7.575E-04 7.332E-04 1010. 1.712E-03 1.6571-03 1010. 4.649E-03 4.500E-03 SSE 1059. 1059. 5.428E-04 5.255E-04 1059. 1.134E-03 1.097E-03 1059. 3.089E-03 2.990E-03 S 762. 762. 6.285E-04 6.083E-04 762. 1.309E-03 1.268E-03 762. 4.341E-03 4.202E-03 SSW 335. 335. 1.260E-03 1.219E-03 335. 3.072E-03 2.974E-03 335. 1.467E-02 1.420E-02 S9 232. 232. 2.206E-03 2.136E-03 232. 6.168E-03 5.971E-03 232. 3.391E-02 3.282E-02 USu 189. 189. 2.808E-03 2.718E-03 189. 9.356E-03 9.056E-03 189. 4.8001-02 4.646E-02 w 189. 189. 3.129E-03 3.029E-03 189. 1.060E-02 1.026E-02 189. 6.176E-02 5.979E-02 WNW 183. 183. 2.907E-03 2.814E-03 183. 1.206E-02 1.167E-02 183. 8.559E-02 8.285E-02 MU 210. 210. 2.806E-03 2.716E-03 210. 9.6301-03 9.321E-03 210. 6.140E-02 5.944E-02 NNU 224. 224. 2.812E-03 2.722E-03 224. 1.045E-02 1.012E-02 224. 5.906E-02 5.717E-02 MWD CITIES SITE METEOROLOGICAL DATA 1/178 - 12/87 ESPOJ16dcn,/quad*fr-8f F-30 I
QUAD CITIES Revision 1.8 June 1996 Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From Quad Cities Location Activity Occupancy Occupancy Shielding Distance Number Hours Factor Factor Rk k OHk' OFk SFk (M) I Living at home 8616 0.9836 0.7 800b (nearest resident) 2 Fishing 36 0.00410 1.0 233c 3 Fishing 51 0.00586 1.0 344c 4 Fishing 31 0.00351 1.0 361c 5 Fishing 26 0.00293 1.0 680C Mh = 5" K = 3.80E-05 mrem/(MWe-hr) These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters cou,,d be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location.
"a The amount of time in a year that a maximally exposed fisherman would spend fishing near the s is estimated as 12 hours per week for 8 months per year. This yields an estimate of:
[12 hours/week] [(8 months/yr)/(12 months/yr)] x (52 weeks/yr] = 416 hours/yr The remaining time is assumed to be spent at the nearest residence. b Distance to nearest residence (See Table F-3). I C Estimated from drawings of the site. d The OFk is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OHa/8760 hours = OFk rounded to the 0.01 digit. Multiplication factor for hydrogen addition. Refer to equation A-34 of Appendix A. ESPOJ/odcm/quad/frl-8f F-39
QUAD CITIES Revision 1.8 June 1996 Supplemental Table A Elevated Level Joint Frequency Distribution Table Summary 296 Foot Elevation Data Summary Table of Percent by Direction and Class Claus N NNE NE ENE. E ESE SE SSE S SSW SW WSW 1 WNW N"W NNW Total A .076 .064 .045 .031 .086 .064 .164 .192 .236 .574 .211 .229 .457 .571 .360 .179 3.541 B .060 .075 .073 .060 .050 .064 .129 .189 .249 .385 .183 .199 .273 .324 .218 .158 2.690 C .147 .136 .185 .155 .151 .151 .168 .343 .391 .529 .312 .281 .478 .658 .440 .309 4.832 D 2.472 2.105 2.729 2.803 2.669 2.152 2.062 2.103 2.755 3.314 2.630 2.527 3.654 5.503 4.501 3.027 47.006 E 1.175 1.004 1.363 1.533 1.992 1.651 1.775 2.131 3.111 3.193 2.229 1.520 1.773 1.916 1.871. 1.219 29.457 F .287 .267 .324 .324 .601 .815 .936 .979 1.128 1.010 .593 .365 .352 .469 .397 .353 9.200 o .042 .069 .060 .083 .117 .168 .400 .517 .574 .482 .294 .136 .111 .097 .076 .045 3.273 Total 4.260 3.720 4.778 4.989 5.666 5.066 5.634 6.454 8.445 9.487 6.453 5.258 7.097 9.538 7.864 5.291 100.000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW V WNW NN 1 NNW Total
.45 .006 .009 .010 .005 .013 .007 .005 .002 .004 .005 .000 .006 .001 .000 .003 .005 .082 1.05 .021 .025 .025 .035 .029 .023 .029 .026 .022 .032 .038 .038 .041 .038 .031 .031 .485 2.05 .182 .182 .196 .192 .216 .199 .220 .190 * .208 .325 .397 .299 .221 .239 .193 .188 3.650 3.05 .428 .366 .451 .407 .441 .406 .453 .384 .434 .787 .752 .473 .476 .500 .481 .393 7.632 4.05 .552 .561 .627 .643 .624 .596 .598 .608 .643 1.136 .897 .589 .563 .636 .650 .681 10.634 5.05 .684 .649 .752 .722 .803 .664 .756 .759 .331 1.264 1.130 .674 .692 .385 .977 .80t 13.043 6.05 .712 .602 .725 .749 .939 .712 .913 .967 1.229 1.448 1.130 .812 .948 1.248 t.199 1.029 15.361 8.05 1.143 .796 1.190 1.247 1.481 1.515 1.714 2.013 2.538 2.516 1.459 1.341 2.022 2.883 2.324 1.494 27.676 10.05 .363 .314 .548 .611 .653 .671 .793 .979 1.544 1.250 .464 .588 1.254 1.804 1.347 .514 13.697 13.05 .149 .173 .218 .324 .375 .245 .141 .440 .866 .596 .144 .321 .653 1.078 .568 .136 6.428 18.00 .016 .042 .035 .054 .086 .028 .013 .084 .123 .125 .042 .116 .212 .218 .062 .019 1.276 99.00 .001 .001 .000 .009 .001 .000 .000 .001 .003 .004 .000 .003 .012 .009 .000 .000 .037 Total 4.260 3.720 4.778 4.989 5.666 5.066 5.634 6.454 8.445 9.487 6.453 5.258 7.097 9.538 7.864 5.291 100.000 NOTE: Wind directions in tables are presented in "wind from" and not "wind to" direction.
ESPOJ/odcm/quadfrl-8f F-40
I QUAD CITIES Revision 1.8 June 1996 Supplemental Table A -Continued Elevated Level Joint Frequency Distribution Table Summary 296 Foot Elevation Data Ssumary Table of Percent by Speed and Class Class A B C 0 E F a speed
.45 .000 .006 .003 .016 .031 .019 .007 1.05 .003 .006 .006 .158 .170 .089 .053 2.05 .066 .045 .119 1.692 1.012 .478 .237 3.05 .176 .185 .308 3.840 1.925 .777 .422 4.05 .289 .299 .522 5.012 2.924 1.105 .484 5.05 .369 .362 .716 5.799 3.931 1.367 .498 6.05 .571 .400 .736 6.691 4.835 1.596 .532 8.05 .998 .718 1.272 12.230 8.759 2.859 .841 10.05 .568 .391 .661 7.034 4.032 .804 .186 13.05 .391 - .214 .385 3.767 1.557 .100 .013 18.00 .085 .056 .101 .753 .274 .007 .000 99.00 .006 .009 .004 .012 .006 .000 .000 ESPOJ/odcm/quad/frl-8f F-41
IQUAD CmES Revision 1.8 June 1996 Supplemental Table B Mixed Mode Joint Frequency Distribution Table Summaries 196 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW 4 WSW W WNW NW NN4W Total A .158 .151 .168 .127 .107 .161 .192 .324 .365 .741 .187 .212 .416 .453 -.539 .252 4.552 a .049 .044 .070 .046 .043 .087 .073 .068 .100 .212 .080 .060 .117 .177 1.156 .078 1.459 C .130 .135 .172 .194 .185 .164 .170 .211 .283 .494 .269 .242 .395 .421 .350 .247 4.063 0 1.397 1.290 1.866 2.073 1.889 1.508 1.388 1.441 1.735 2.308 1.967 1.899 2.881 3.767 2.712 1.908 32.028 E 1.025 .905 1.323 t.778 2.029 1.551 1.643 1.947" 2.558 3.048 2.280 1.841 2.437 2.656 '2.102 1.157 30.281 F .342 .319 .433 , .501 .726 .863 .776 .936 1.291 1.051 .506 .337 .415 .475 .374 .311 9.655 Q .125 .127 .167 .203 .380 .598 .843 .980 .955 .767 .306 .174 .203 .148 .102 .118 6.196 Total 3.225 2.970 4.200 4.922 5.359 4.932 5.086 5.907 7.287 8.620 5.596 4.765 6.865 8.097 6.334 4.071 88.234 Summary Table of Percent by Direction and Speed N NNE NE ENE a ESE SE SSE S SSW Sw WSW V WNW NW NNW Total Speed
.006 .015 .006 .006 .006 .006 .008 .010 .012 .008 .018 .009 .002 .015 .000 .006 .131
.45
.035 .064 .050 .048 .062 .058 .079 .060 .075 .097 .064 .054 .064 .052 .050 .959 1.05 .046 2.05 .305 .265 .255 .356 ;348 .342 .367 .391 .385 .621 .719 .499 .445 .383 .362 .331 6.372 3.05 .520 .477 .702 .680 .787 .767 .699 .711 .744 1.289 1.295 .769 .790 .792 .810 .607 12.440 4.05 .761 .665 .769 .981 .975 .886 1.081 1.172 1.228 1.725 1.389 1.000 1.217 1.191 1.132 .809 16.983
.607 .611 .848 .963 1.069 1.014 1.116 1.138 1.376 1.673 .991 .912 1.306 1.603 1.240 .796 17.265 5.05 6.05 .426 .372 .645 .684 .801 .760 .850 .899 1.266 1.303 .563 .631 1.099 1.435 1.024 .656 13.415 4.05 .412 .399 .650 .832 .821 .782 .721 .953 1.406 1.337 .453 .603 1.272 1.745 1.208 .643 14.237 10.05 .113 .086 .226 .302 .389 .249 .147 .417 .661 .520 .056 .220 .509 .702 .412 .156 5.165 13.05 .028 .045 .034 .068 .111 .064 .036 .133 .144 .068 .014 .053 .160 .163 .094 .016 1.232 18.00 .000 .000 .002 .001 .003 .000 .000 .004 .004 .001 .001 .005 .008 .004 .000 .001 .034 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .ooo Total 3.225 2.970 4.200 4.922 5.359 4.932 5.066 5.907 7.267 8.620 .5.596 4.765 6.665 6.097 6.334 4.071 88.234 NOTE: Wind directions in tables are presented in "wind from" and not "wind to" direction.
In order to deteirnwr* trt% ar,,J. rMAij r.1KAI VJILjt, 88 234% of the elevated value (presented in the 296 FT Mixed Mode table) and 11 /b(, '. ul1 hit ,j A .q .. ,
... . , .. . ; It v J I I M.Aed Mode table) are used to calculate the final values.
E!c POJ/odcm/quad~r1-.8
QU, ;ITIES Revisioi j June 1996 Supplemental Table B - Continued Mixed ILode Joint Frequency Distribution Table Summaries 196 Foot Elevation Data Su mma ry Table of Percent by Speed and Clase Class A B It D E F Speed
.45 .000 .000 .000 .023 .056 .014 .039 1.05 .002 .002 .008 .249 .307 .166 .224 2.05 .089 .050 .184 2.680 1.748 .785 .837 3.05 .358 .180 .684 4.451 3.666 1.724 1.378 4.05 .794 .331 .869 5.305 5.832 2.387 1.466 5.05 .885 .309 .724 5.544 6.119 2.367 1.317 6.05 .850 .190 .640 4.731 4.847 1.458 .699 8.05 1.026 .281 .610 5.969 5.482 .655 .216 10.05 .459 .102 .267 2.423 1.798 .096 .020 13.05 .089 .014 .077 .636 .411 .004 .000 18.00 .001 .000 .000 .Ol8 .015 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 ESPOJ/odcm/quad/trI-8IF-4 F-43
QUAD CITIES Revision 1.8 June 1996 Supplemental Table B - Continued Mixed Mode Joint Frequency Distribution Table Summaries 33 Foot Elevation Data Summary Table of Percent by Direction and Class Clase N NNE NE ENE E ESE SE SSE S SSW SW :WSW W NW NW NNW Total A .022 .020 .015 .017 .018 .036 .033 .064 .067 .131 .026 .4023 .079 .076 .069 .037 .732
* .006 .006 .008 .005 .006 .011 .013 .009 .012 .027 .008 .010 .018 .026 1.O27 .009 .202 C .016 .019 .017 .024 .023 .023 .025 .028 .041 .057 .024 .026 .063 .069 .041 .028 .527 D .186 .203 .226 .328 .270 .190 .152 .170 .213 .268 .224 .335 .547 .815 .405 .247 4.779 E .097 .102 .171 .. 263 .290 .277 .245 .345 .394 .383 .225 .252 .453 .379 * .245 .126 4.247 F .012 .026 .048 .048 .084 .116 .099 .A17 .104 .059 .022 .022 .045 .036 .018 .014 .868 o .003 .006 .007 .017 .058 .133 .052 .053 .036 .009 .006 .003 .013 .006 .005 .002 .410 Total .341 .382 .493 .702 .749 .786 .619 .787 .868 .934 .535 .672 1.218 1.408 .810 .463 11.766 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW Sw WSW W WNW NW NNW Total .45 .000 .000 .000 .001 .000 .001 .001 .001 .003 .000 .001 .001 .000 .001 .000 .000 .010 1.05 .004 .005 .008 .012 .020 .036 .030 .036 .031 .009 .012 .010 .009 .005 .005 .005 .239 2.05 .029 .031 .056 .058 .107 .167 .131 .163 .160 .091 .077 .078 .092 .072 .038 .032 1.381 3.05 .047 .058 .090 .121 .126 .153 .149 .173 .206 .245 .173 .139 .231 .159 .097 .066 2.234 4.05 .066 .078 .106 .151 .123 .137 .132 .159 .175 .2383 .144 .137 .247 .275 .176 .114 2.503 5.05 .060 .069 .089 .115 .101 .096 .073 .094 .121 .163 .075 .105 .214 .291 .174 .111 1.961 6.05 .044 .055 .056 .064 .091 .090 .050 .077 .091 .068 .024 .063 .136 .244 .140 .076 1.390 8.05 .051 .040 .056 .109 .116 .074 .040 .076 .071 .064 .014 .047 .156 .240 .145 .046 1.343 10.05 .025 .040 .032 .049 .042 .028 .009 .008 .009 .011 .014 .080 .093 .110 .035 .010 .594 13.05 .006 .006 .000 .002 .022 .003 .004 .000 .000 .000 .000 .014 .034 .011 .000 .003 .105 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .006 .000 .000 .000 .006 99.00 .000 .000 .000 .000 .000 .000 .000 .090 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total .341 .382 .493 .702 .749 .786 .619 .767 .865 .934 .535 .672 1.218 1.408 .810 .463 11.766 NOTE Wind dit,,diKis in t~teia rr virwtiri so, t v, jrj nol 'ind to" direCtion.
ESP0J/odcmtquad/fr1-8f F-44, ( , "N'
I QL CITIES RevisiL .8 June 1996 Supplemental Table B - Continued Mixed Mode Joint Frequency Distribution Table Summaries 33 Foot Elevation Data Summary .Table of Percent by Speed end Clase Class A a b D E F G Speed
.45 .000 .000 .000 .000 .001 .002 .007 1.05 .008 .000 .000 .008 .042 .078 .103 2.05 .018 .006 .010 .149 .509 .457 .231 3.05 .095 .023 .068 .644 1.105 .244 .055 4.05 .197 .053 .128 1.080 .981 .059 .004 5.05 . 177 .044 .122 .981 .617 .017 .002 6.05 .131 .035 .075 .767 .373 .004 .005 6.05 .093 .027 .090 .742 .383 .005 .002 10.05 .012 .011 .031 .340 .199 .002 .000 13.05 .001 .001 .003 .067 .032 .000 .000 16.00 .000 .000 .000 .000 .006 .000 .000 93.00 .000 .000 .000 .000 .000 .000 .000 ESPOJ/odcm/quaditrI-8F F-45
I .QUAD CITIES Revision 1.8 June 1996 Supplemental Table C Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW V WNW NW NNW Total A .180 .185 .133 .155 .133 .224 .243 .352 .363 .856 .294 .247 .556 .539 .. 516 .303 5.280 8 .058 .058 .071 .048 .044 .095 .093 .079 .087 .222 .122 .083 .164 .180 .168 .085 1.658 C .151 .189 .195 .201 .187 .195 .211 .220 .267 .527 .350 .313 .454 .527 .342 .253 4.582 D 1.614 1.666 1.966 2.403 2.014 1.814 1.586 1.537 1.562 2.410 2.476 2.451 3.540 4.726 2.898 2.124 36.786 E .946 1.011 1.561 2.128 2.275 2.129 1.985 2.335 2.585 3.085 2.739 2.277 3.197 3.168 1.953 1.169 34.543 F .255 .383 .631 .574 .863 1.222 1.085 1.175 1.016 .716 .491 .403 .619 .564 .296 - .227 10.523 a .O88 .151 .205 .279 .886 1.841 .863 .691 .457 .212 .241 .126 .265 .175 .082 .068 6.626 Total 3.291 3.644 4.763 5.788 6.402 7.519 6.065 6.389 6.337 8.030 6.712 5.900 8.795 9.879 6.255 4.229 100.000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW V WNW NW NNW Total
.45 .047 .055 .086 .089 .083 .095 .132 .146 .115 .070 .123 .083 .073 .068 .054 .039 1.356 1.05 .214 .257 .417 .419 .723 .991 .860 .898 .730 .593 .782 .583 .504 .394 .214 .172 8.753 2.05 .612 .713 1.138 1.109 1.629 2.537 1.901 1.965 1.826 1.789 2.096 1.700 1.967 1.611 .987 .663 24.241 3.05 .713 .826 1.061 1.281 1.341 1.609 1.443 1.476 1.601 2.434 2.038 1.534 2.336 2.005 1.285 .935 23.916 4.05 .624 .701 .876 1.103 .983 ,881 .925 .985 1.051 1.814 1.041 .974 1.629 1.905 1.395 .974 17.860 5.05 .489 .473 .576 .719 .607 .595 .429 .481 .576 .881 .452 .493 1.068 1.617 1.034 .751 11.259 6.05 .265 .323 .317 .471 .454 .446 .257 .278 .305 .299 .124 .296 .632 1.188 .717 .437 6.806 8.05 .263 .205 .238 .504 .481 .296 .102 .153 .124 .133 .037 .133 .413 .910 %504 .228 4.723 10.05 .056 .085 .056 .091 .073 .064 .012 .006 .010 .015 .019 .091 .114 .170 .066 .027 .956 13.05 .008 .008 .000 .002 .029 .006 .004 .000 .000 .000 .000 .014 .035 .012 .000 .004 .120 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .006 .000 .000 .000 .006 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 3.291 3.644 4.763 5.788 6.402 7.519 6.065 6.389 6.337 8.030 6.712 5.900 8.795 9.879 6.255 4.229 100.000 NOTE Wind directions in hIDleS afe presented in "wind from" and not "wind to" direction.
ESPOJo6dcm/quad'r1-81 F-46
I QU. ITIES Revisio June 199b Supplemental Table C - Continued Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data Susimary Table of Percent by Speed and Cleas Class A B C 0 E F a Speed
.45 .000 .000 .002 .056 .299 .375 .626 1.05 .041 .012 .054 .902 2.390 2.569 2.786 2.05 .439 .158 .553 5.844 9.138 5.363 2.747 3.05 1.285 .481 1.321 8.821 9.831 1.773 .404 4.05 1.544 .462 1.109 8.235 6.180 .307 .023 5.05 1.012 .255 .765 5.683 3.435 .097 .012 6.05 .618 .182 .388 3.856 1.721 .017 .025 8.05 .313 .089 .328 2.755 1.215 .017 .006 10.05 .027 .017 .058 .556 .294 .004 .000 13.05 .002 .002 .004 .077 .035 .000 .000 11.00 .000 .000 .000 .000 .006 .000 .000
$9.00 .000 .000 .000 .000 .000 .000 .000 ESPOJ/odct/quatirI-8tf F-47
I QUAD CITIES Revision 1.8 June 1996
&IwUI lefmNI IDOeCAbo8 P001!
S_ a
*I= mF0.0" 64t OFFSITE DOSE CALCULATION MANUAL QUAD CITIES STATION SUnrestricted Area Boundary QUAD CITIES STATION FIGURE F-1 ESPOJ/odcm/quad/fr1-f 0 Meteorological Tower F-48 UNRESTRICTED AREA BOUNDARY j.
I QUAD CITIES Revision 1.8 June 1996 SRestriced Area 6*0Ira,=,- OFFSITE DOSE CALCULATION MANLAL QUAD CITIES STATION U FIGURE F-2 ! INDS 2MI FEET I I RESTRICTED AREA BOUNDARY GRAPHIC SCALE ESPOJ/adcmlauad/frl-8f F-49
BYRON STATION BYRON Revision 1.4 October 1998 BYRON ANNEX INDEX CHAPTER 10 REVISION 1.4 (p:radprot\odcm~byl OR1 -4.doc) 10-i
I BYRON Revision 1.4 October 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS NUMBER PAGE 10.1 AIRBORNE RELEASES 10-1
- 1. System Description 10-1
- 1. Waste Gas Holdup System 10-1
- 2. Ventilation Exhaust Treatment System 10-1
- 2. Radiation Monitors 10-1
- 1. Auxiliary Building Vent Effluent Monitors 10-1
- 2. Containment Purge Effluent Monitors 10-2
- 3. Waste Gas Decay Tank Monitors 10-2
- 4. Gland Steam and Condenser Air Ejector Monitors 10-2
- 5. Radwaste Building Ventilation Monitor 10-3
- 6. Miscellaneous Ventilation Monitors 10-3 I
- 3. Alarm and Trip Setpoints 10-3
- 1. Setpoint Calculations 10-3
- 1. Auxiliary Building Vent Effluent Monitors 10-3
- 2. Containment Purge Effluent Monitors 10-3
- 3. Waste Gas Decay Tank Effluent Monitors 10-3 I
- 2. Release Limits 10-4
- 3. Release Mixture 10-5
- 4. Conversion Factors 10-5
- 5. HVAC Dilution Flow Rates 10-5
- 4. Allocation of Effluents from Common Release Points 10-5
- 5. Dose Projections for Batch Releases 10-5 (p:\radprot\odcm\by1 ORI -4.doc) 10-ii
BYRON Revision 1.4 October 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) NUMBER PAGE 10.2 LIQUID RELEASES 10-5
- 1. System Description 10-5
- 1. Release Tanks 10-6
- 2. Turbine Building Fire and Oil Sump 10-6
- 3. Condensate Polisher Sump 10-6
- 2. Radiation Monitors 10-6
- 1. Liquid Radwaste Effluent Monitors 10-6
- 2. Station Blowdown Monitor 10-6
- 3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX) Outlet Line Monitors 10-6
- 4. Turbine Building Fire and Oil Sump Monitor 10-7
- 5. Condensate Polisher Sump Monitor 10-7
- 6. Component Cooling Water Monitor 10-7
- 3. Alarm and Trip Setpoints 10-7
- 1. Setpoint Calculations 10-7
- 1. Station Blowdown Monitor 10-8
- 1. Release Mixture 10-8
- 2. Liquid Radwaste Effluent Monitor 10-8
- 1. Release Tank Discharge Flow Rate 10-8.
- 2. Release Mixture 10-9
- 3. Liquid Dilution Flow Rates 10-9
- 4. Projected Concentrations for Releases 10-9
- 3. Other Liquid Effluent Monitors 10-10
- 4. Conversion Factors 10-10
- 4. Allocation of Effluents from Common Release Points 10-10 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM 10-10 (p:\radprot\odcm\by1 OR1 -4.doc) 10-iii
BYRON Revision 1-4 October 1998 CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the Byron Station Noble Gas Effluent 10-11 10-2 Assumed Composition of the Byron Station Liquid Effluent 10-12 (p:\radprot'odcm\by1 OR 1 -4.doc) 10-iv
BYRON Revision 1.4 October 1998 CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-13 10-2 Simplified Liquid Radwaste Processing Diagram 10-15 10-3 Liquid Release Flowpath 10-16 (p:\radprot\odcm*by1 ORI -4.doc) 10-v
BYRON Revision 1.4 October 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified HVAC and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Vent Stack 1 and Vent Stack 2 in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A-1 of Appendix A). 10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Chapter 11 of the Byron/Braidwood UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect- on( noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors 1RE-PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks. Both vent stack monitors feature automatic isokinetic sampling, noble gas monitoring, grab sampling, iodine and particulate sampling and tritium sampling. No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in Byron/Braidwood UFSAR Chapter 11. (p:radprot1cdcm~by1 OR 1-4.doc) 10-1
BYRON Revision 1.4 October 1998 10.1.2.2 Containment Purge Effluent Monitors Monitors 1RE-PRO01 (Unit 1) and 2RE-PRO01 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 containments, respectively. When airborne radioactivity in the containment purge effluent stream exceeds a specified level station personnel will follow established procedures to terminate the release by manually activating the containment purge valves. Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent. No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in Byron/Braidwood UFSAR Chapter 11. Monitors 1(2)RE-ARO1 1 and 1(2)RE-AR01 2 monitor the containment atmosphere. On high alarm during a containment purge, these monitors will automatically terminate the purge. 10.1.2.3 Waste Gas Decay Tank Monitors Monitors ORE-PRO02A/B continuously monitor the noble gas activity released from the gas decay tanks. On high alarm, the monitors automatically initiate closure of the valve OGW1 04 thus terminating the release. Pertinent information on these monitors and associated control devices is provided in Byron/Braidwood UFSAR Chapter 11. 10.1.2.4 Gland Steam and Condenser Air Ejector Monitors Monitors 1 RE-PR027 and 2RE-PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. Pertinent information on these monitors is provided in Byron/Braidwood UFSAR Chapter 11. (p:'adprot\odcm~byl ORI -4.doc) 10-2
BYRON Revision 1.4 October 1998 10.1.2.5 Radwaste Building Ventilation C.'., Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. On high alarm, ORE-PR026 initiates isolation of the radwaste building ventilation system. Pertinent information on this monitor is provided in Byron/Braidwood UFSAR Chapter 11. 10.1.2.6 Miscellaneous Ventilation Monitors Monitor ORE-PRO03 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel. Pertinent information on this monitor and associated devices is provided in Byron/Braidwood UFSAR Chapter 11. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculation 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 2.5% of the maximum permissible release rate for the high alarm and 0.25% of the maximum release rate for the alert alarm. The setpoints for the high range noble gas channel are conservatively established at Ci 50% of the maximum permissible release rate for the high alarm and 5% of the maximum release rate for the alert alarm. 10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.25 times the containment noble gas activity during purge. 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.25 times the analyzed waste gas tank activity during release. (p:\radprot\odcm'byl ORI -4.doc) 10-3
BYRON Revision 1.4 October 1998 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS Section 12.4 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, oty. (l.1l)QtvZ(ViFj} < 500 mrem/yr (10-1) QtvZ{ (f i) [Li (X/Q) vexp (-AiR/3 600 Uiv) (10-2)
+ 1.11 Vii} < 3000 mrem/yr The summations are over noble gas radionuclides i.
fi Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides. Qt, Total Allowed Release Rate, Vent Release [.Ci/sec] The total allowed release rate of all noble gas radionuclides released as vent releases. The remaining parameters in Equation 10-1 have the same definitions as in Equation A 8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A. Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem/yr) due to noble gases released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem/yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A). Since the solution to Equation 10-2 is more conservative than the solution to Equation 10-1, the value of Equation 10-2 (1.02 x 107 4.Ci/sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas decay tanks, the total station release rate is procedurally limited such that the maximum permissible release rate is not exceeded. (p:\radprot~odcm\byl ORI -4.doc) 10-4
BYRON Revision 1.4 October 1998 10.1.3.3 Release Mixture ' In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1. 10.1.3.4 Conversion Factors. The response curves used to determine the monitor count rates are based on the sensitivity to Xe-1 33 for conservatism. 10.1.3.5 HVAC Dilution Flow Rates The plant vent stack flow rates are obtained from the RM-1 1 console in the control room. If the values cannot be obtained from RM-11, flow rates can be estimated from the operating fan combinations. 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, allocation is made evenly between units. 10.1.5 Dose Projections for Batch Releases The IOCFR20 dose limits have been converted into a station administrative release rate limit using the methodology in the ODCM. Compliance is verified prior to each release. Doses are calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50. 10.2 LIQUID RELEASE 10.2.1 System Description A simplified liquid release flowpath diagram is provided in Figure 10-3. A simplified liquid radwaste processing diagram is provided in Figure 10-2. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Chapter 11 of the Byron/Braidwood Updated Final Safety Analysis Report. 10.2.1.1 Release Tanks There are two radwaste release tanks (OWXOIT and OWX26T 30,000-gallon capacity each) which receive liquid waste before discharge to the Rock River. (p:\adprot\odcm\byl OR 1-4doc) 10-5
BYRON Revision 1.4 October 1998 10.2.1.2 Turbine Building Fire and Oil Sump The turbine building fire and oil sump receives water from selected turbine building sumps, the tendon tunnel sumps, and the diesel fuel oil storage sumps, all of which are normally non-radioactive but potentially contaminated. The effluent from this sump is monitored, and if radioactive contamination exceeds a predetermined level pump operation is automatically terminated. The water may then be sent to the liquid radwaste treatment system. 10.2.1.3 Condensate Polisher Sump The condensate polisher sump receives waste water from the condensate polisher system which is normally non-radioactive but potentially contaminated. The effluent from this sump is monitored and if radioactive contamination exceeds a predetermined level sump discharge is terminated and major condensate polisher inputs to the sump are automatically isolated. The water may then be sent to the liquid radwaste treatment system. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitors. Monitor ORE-PRO01 is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves OWX-353 and OWX-869 to terminate the release. Pertinent information on the monitor and associated control devices is provided in Byron/Braidwood UFSAR Chapter 11. 10.2.2.2 Station Blowdown Monitor Monitor ORE-PR010 continuously monitors the recirculating water blowdown. No control device is initiated by this channel. Pertinent information on this monitor is provided in Byron/Braidwood UFSAR Chapter 11. 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (SX) Outlet Line Monitors Monitors 1RE-PR002, 2RE-PROO2, 1RE-PR003, and 2RE-PRO03 continuously monitor the RCFC and SX outlet lines. No control device is initiated by these channels. Pertinent information on these monitors is provided in Byron/Braidwood UFSAR Chapter 11. (p:\radprot\odcm\by1 OR1 -4.doc) 10-6
BYRON Revision 1.4 October 1998 10.2.2.4 Turbine Building Fire and Oil Sump Monitor C' Monitor ORE-PRO05 continuously monitors the fire and oil sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps, close valve 0OD030, and terminate the release. Pertinent information on this monitor is provided in Byron/Braidwood UFSAR Chapter 11. 10.2.2.5 Condensate Polisher Sump Monitor Monitor ORE-PRO41 continuously monitors the condensate polisher sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release. Pertinent information on this monitor is provided in Byron/Braidwood UFSAR Chapter 11. 10.2.2.6 Component Cooling Water Monitor Monitors ORE-PRO09 (common), 1RE-PRO09 (Unit 1), and 2RE-PRO09 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PRO09 initiates closure of both component cooling water surge tank (CCWST) vents, 1 RE-PRO09 initiates closure of the Unit 1 CCWST vent, and 2RE-PRO09 initiates closure of the Unit 2 CCWST vent. Pertinent information on this monitor is provided in Byron/Braidwood UFSAR Chapter 11. 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation C Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area. Setpoint calculations normally consist of identified release mixtures, dilution factors, conversion factors (detector sensitivity), and conservatism factors. (p:\radprot\odcmýby1 CR1 -4.doc) 10-7
BYRON Revision 1.4 October 1998 10.2.3.1.1 Station Blowdown Monitor During release, the monitor setpoint is found by solving equation 10-3. P < CCW + (1.50 X CT) x (Frmax/(FCW + Frmax)) (10-3) P Release Setpoint [4.Ci/ml] 1.50 Factor to account for minor fluctuations in count rate CCW Concentration of activity in the circulating water blowdown [jCi/ml] at the time of discharge ("Background reading") c Analyzed activity in the release tank [RCi/ml] excluding tritium Fe Circulating Water Blowdown Rate [gpm] Frmax Maximum Release Tank Discharge Flow Rate [gpm] The flow rate from the radwaste discharge tank. 10.2.3.1.1.1 Release Mixture The release mixture used for the setpoint determination is the radionuclide mix identified in the release tank grab sample isotopic analysis. 10.2.3.1.2 Liquid Radwaste Effluent Monitor During release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading. However, per procedure, the maximum discharge flow rate is limited to a value that will result in less than 50% of 10*DWC at the discharge point. (See Section 10.2.3.1.2.1) 10.2.3.1.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. The results of the analysis of the waste sample determine the discharge rate of each batch as follows: Fa, = 0.5(F,,/2(C, /I10*DWCJ) (10-4) The summation is over radionuclides i. max Maximum Permitted Discharge Flow Rate The maximum permitted flow rate from the radwaste discharge tank based on radiological limits (not chemistry limits which may be more restrictive) [gpm] d Faa Circulating Water Blowdown Rate [gpm] Ci Concentration of Radionuclide i in the Release Tank [.lCi/ml] The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. (p:radprot\odcm~by OR1 -4.doc) 10-8
BYRON Revision 1.4 October 1998 DWCi Derived Water Concentration [gCi/mlI The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. 10 Multiplier 10.2.3.1.2.2 Release Mixture The release mixture used for the setpoint determination is the radionuclide mix identified in the release tank grab sample isotopic analysis. 10.2.3.1.2.3 Liquid Dilution Flow Rates Dilution flow rates are obtained from the main control board in the control room. If this information is unavailable, releases may continue for up to 30 days provided the dilution flow rates are estimated every 4 hours during the release, in accordance with Technical Requirements Manual Table T3.1 l.a-I (ATR Table 3.3-12). 10.2.3.1.2.4 Projected Concentrations for Releases After determining Fm- Ofrom Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6.
= CT [Fma, / (Fm + Fa)] (10-5)
C*/I0*DWCi 1* 1 G2{ (10-6) The summation is over radionuclides i. C. Concentration of Radionuclide i in the Unrestricted Area [.CVmLI The calculated concentration of radionuclide i in the unrestricted area as determined by Equation 10-5. C1 Concentration of Radionuclide i in the [p.Ci/mL] Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. DWCI Derived Water Concentration [p.Ci/ml] The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. 10 Multiplier Fmax Maximum Release Tank Discharge fgpm] Flow Rate F* Circulating Water Blowdown Rate [gpm] (p:radprot\odcm\byl ORI -4.doc) 10-9
BYRON Revision 1.4 October 1998 10.2.3.1.3 Other Liquid Effluent Monitors For all other liquid effluent monitors, including ORE-PRO01 and ORE-PR01 0 when not batch releasing, setpoints are determined such that the concentration limits do not exceed 10 times the DWC value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402 in the unrestricted area. Release mixtures are based on a representative isotopic mixture of the waste stream or inputs to the waste stream, or defaulted to the mix listed in Table 10-2. 10.2.3.1.4 Conversion Factors The readouts for the liquid effluent monitors are in uCi/ml. Conversion factors are determined for each monitor (CPM/uCi/ml). 10.2.4 Allocation of Effluents from Common Release Points. Radioactive liquid effluents released from either release tank (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is made evenly between units. 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. (p:\radprot\odcm\by1OR 1-4.doc) 10-10
BYRON Revision 1.4 October 1998 Table 10-1 Assumed Composition of the Byron Station Noble Gas Effluent Percent of Isotope Effluent Ar-41 00.89 Kr-85m 00.18 Kr-85 24.9 Kr-87 0.04 Kr-88 00.28 Xe-131m 01.4 Xe-1 33m 00.57 Xe-133 71.1 Xe-1 35 00.53 Xe-I 38 00.04 C (p:Vadprotk.dcmtby1OR1 -4.doc) 10-11
BYRON Revision 1.4 October 1998 Table 10-2 Assumed Composition of the Byron Station Liquid Effluent Isotope Concentration Isotope Concentration (pLCi/mi) (l+/-Ci/ml) Ru-1 03 8.00E - 06 Mn-54 1.OOE - 05 Ag-110m 3.OOE - 06 Fe-59 5.OOE - 06 Te-127 2.OOE - 05 Co-58 9.OOE - 06 Te-129m 2.00E- 06 Co-60 3.OOE - 06 Te-1 31 m 4.OOE - 06 Rb-86 2.OOE - 06 Te-132 2.OOE - 06 Zr-95 6.OOE - 06 1-130 3.OOE - 07 Nb-95 1.00E - 05 1-131 3.OOE - 08 Mo-99 4.OOE - 06 1-132 8.OOE - 07 1-133 1.00E - 07 1-135 4.OOE - 07 Cs-1 34 9.OOE - 07 Cs-1 36 9.OOE - 06 Cs-1 37 2.OOE - 06 Ce-144 1.00E - 06 Np-239 1.OOE - 05 (p:\radprot\odcm\by1 OR1 -4.doc) 10-12
BYRON Revision 1.4 October 1998 (7 m - C O~Fla DO= CACW1I NIUMAL BR STATION FIGURE 10-1 ( SIMPUJFIED HVAO AND GASEOUS (p:\radprot\odcmtbyl OR1 -4.doc) EFFLUENT FLOW OLAGRAM 10-13 (S4EET I OF2)
BYRON BYRONRevision 1.4 October 1998 Hmm A oinmmmpomq tip mmý Immummfa "a 4. OwRNM 0=S CALCLA7lO MAIN& Volumm am 10 BYON STA7=O W v~pampamommo FDURE. 10-1 SIMPUFIED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2) (p:radprat'cdcm~byl ORI -4.doc) 10-14
ii lIlE !lit I I iI l CL
BYRON Revision 1.4 October 1998 OWFFBE DOSE CALCULATION MANUAL BYRON STATION FI=URE I0-3 LWU RELEASE FLOWPATH (p:\radprot~odcm'byl OR1.4.doc) 10-16
BYRON Revision 1.6 October 1998 BYRON ANNEX INDEX Chapter 11 Revision 1.6 (p:Nradprot'odcm\byl IR I-6.doc) 11-i
BYRON Revision 1.6 October 1998 CHAPTER11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM C TABLE OF CONTENTS PAGE 11.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 ( ( (p:Vradprot~odcmbyl 1RI1-6.doc) 11-ii
BYRON Revision 1.6 October 1998 CHAPTER 11 LIST OF TABLES NUMBER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 (p:Vadprot\odcm\by1 1 Ri -6.doc) 11-iii
BYRON Revision 1.6 October 1998 CHAPTER 11 LIST OF FIGURES C NUMBER TITLE PAGE 11-1 Onsite Air Sampling Locations 11-10 11-2 Offsite Air Sampling Locations 11-11 11-3 Inner Ring and Outer Ring TLD Locations 11-12 11-4 Ingestion and Waterbome Exposure Pathway Sample Locations 11-13 C (p:\radprot\odcm\by1 1R 1-6.doc) 11-iv
BYRON Revision 1.6 October 1998 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program for the environs around Byron Station is given in Table 11-1. Figures 11-1 through 11-4 show sampling and monitoring locations. (p:\radprot\odcm\byr1 1R1 -6.doc) 11-1
BYRON Revision 1.6 October 1998 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency Sampling or Monitorinq Locations Collection Frequency of Analysis and/or Sample
- 1. Airborne Radioiodine and a. Indicators-Near Field Continuous sampler operation Radioiodine Canister:
with particulate sample 1-131 analysis biweekly Particulates BY-21, Byron Nearsite N, collection weekly, or more on near field and control 0.3 mi N (0.5 km A) frequently if required by dust samples.1 BY-22, Byron Nearsite ESE, loading, and radioiodine canister 0.4 mi ESE (0.6 km F) collection biweekly. Particulate Sampler: BY-23, Byron Nearsite S, 0.6 mi S (1.0 km J) Gross beta analysis BY-24, Byron Nearsite SW, followinT weekly filter 0.6 mi SW (1.0 km L) change and gamma 3 isotopic analysis quarterly on composite filters by location on near field and control samples.
- b. Indicators-Far Field BY-i, Byron, 3.0 mi N (4.8 km A)
BY-4, Paynes Pt., 5.0 mi SE (8.0 km G) BY-6, Oregon, 4.7 mi SSW (7.5 km K) (p:\radp(qtodcm~byr1 1RI-6.doc) 11
BYRON Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis
- 1. Airborne (Cont'd) c. Controls BY-8, Leaf River, 6.8 mi WNW (10.9 km P)
- 2. Direct Radiation a. Indicators-Inner Ring Quarterly Gamma dose quarterly BY-101-1, 0.3 mi N (0.5 km A)
BY-101-2, 0.3 m! N (0.5 km A) BY-1 02-1, 0.9 mi NNE (1.5 km B) BY-102-2, 1.0 mi NNE (1.5 km B) BY-103-1, 1.7 ml NE (2.8 km C) BY-103-2, 1.7 mi NE (2.7 km C) BY-104-1, 1.5 mi ENE (2.4 km D) BY-104-2, 1.5 mi ENE (2.4 km D) BY-105-1, 1.3 mi E (2.1 km E) BY-105-2, 1.3 m! E (2.1 km E) BY-106-1, 1.4 mi ESE (2.3 km F) BY-106-2, 1.4 mi ESE (2.3 km F) BY-107-1, 1.4 mi SE (2.2 km G) BY-107-2, 1.4 mi SE (2.2 km G) BY-108-1, 0.7 mi SSE (1.1 km H) BY-1 08-2, 0.6 mi SSE (1.0 km H) BY-109-1, 0.6 mi S (1.0 km J) BY-109-2, 0.6 mi S (1.0 km J) BY-110-1 0.6 mi SSW (1.0 km K) BY-110-2, 0.6 mi SSW (1.0 km K) BY-111-3, 0.7 mi SW (1.1 km L) BY-111-4, 0.8 ml SW (1.3 km L) BY-112-3, 0.8 mi WSW (1.2 km M) BY-112-4, 0.8 mi WSW (1.2 km M) (p:\adprot~odcm'byr1 IR1 -6.doc) 11-3
BYRON Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency Collection Frequency of Analysis and/or Sample Sampling or Monitoring Locations
- 2. Direct Radiation BY-113-1,0.7miW (1.1 kmN)
(Cont'd) BY-113-2, 0.7 mi W (1.1 km N) BY-114-1, 0.8 mi WNW (1.2 km P) BY-114-2, 0.8 mi WNW (1.3 km P) BY-115-1, 1.0 mi NW (1.6 km Q) BY-115-2, 1.0 mi NW (1.7 km Q) BY-116-1, 1.4 mi NNW (2.3 km R) BY-116-2, 1.4 mi NNW (2.3 km R)
- b. Indicators-Outer Ring BY-201-3, 4.5 mi N (7.1 km A)
BY-201-4, 4.4 mi N(7.1 km A) BY-202-1, 4.3 mi NNE (6.9 km B) BY-202-2, 4.8 mi NNE (7.6 km B) BY-203-1, 4.8 mi NE (7.7 km C) BY-203-2, 4.7 mi NE (7.5 km C) BY-204-1, 4.2 mi ENE (6.6 km D) BY-204-2, 4.1 mi ENE (6.5 km D) BY-205-1, 3.8 mi E (6.2 km E) BY-205-2, 3.8 mi E (6.2 km E) BY-206-1, 4.1 mi ESE (6.5 km F) BY-206-2, 4.4 mi ESE (7.0 km F) BY-207-1, 4.2 mi SE (6.7 km G) BY-207-2, 3.6 mi SE (5.8 km G) (p:Vadqpmhdcm~byr1 1Ri -6.doc) it`ý
BYkvN Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis
- 2. Direct Radiation BY-208-1, 4.0 mi SSE (6.4 km H)
(Cont'd) BY-208-2, 3.7 ml SSE (5.9 km H) BY-209-1, 3.7 mi S (5.9 km J) BY-209-4, 3.7 mi S (5.9 km J) BY-210-3, 3.9 mi SSW (6.2 km K) BY-210-4, 3.9 ml SSW (6.2 km K) BY-211-1, 4.9 ml SW (7.9 km L) BY-211-4, 4.9 mi SW (7.8 km L) BY-212-1, 4.7 mi WSW (7.4 km M) BY-212-4, 4.7 mi WSW (7.4 km M) BY-213-1. 4.7 mi W (7,5 km N) BY-213-4, 4.6 mi W (7.4 km N) BY-214-1, 4.6 mi WNW (7.4 km P) BY-214-4, 4.9 mi WNW (7.8 km P) BY-215-1, 5.3 mi NW (8.4 km Q) BY-215-4, 5.2 mi NW (8.3 km Q) BY-216-1, 4.6 mi NNW (7.3 km R) BY-216-2, 4.8 mi NNW (7.6 km R)
- c. Indicators-Other I One at each airborne location given In part l.a and 1.b.
- d. Control One at each airborne control location given In part I.c.
(p:\radprot~odcmlbyr1 1RI-6.doc) 11-5
BYRON Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency Collection Freguency of Analysis and/or Sample Sampling or Monitoring Locations
- 3. Waterborne Gamma isotopic 3 and
- a. Ground/Well a. Indicators Quarterly trtium analysis quarterly.
BY-14, ComEd Offsite Well 0.5 mi ESE (0.7 km F) BY-1 8, McCoy Farmstead 0.7 mi SW (1.2 km L) BY-32, Wolford Well 1.8 mi W (2.9 km N)
- b. Drinking There is no drinking water pathway within 6.2 mi downstream of the station.
- c. Surface BY-12, Oregon Pool of Rock River, Weekly grab samples. Gross beta and qamma isotopic analysis on Downstream of Discharge, monthly composite; 4.5 mi SSW (7.3 km K) tritium analysis on quarterly composite.
Weekly grab samples. Gross beta and gamma
- d. Control BY-29, Byron, Upstream of Intake isotopic analysis on 3.0 mi N (4.8 km A) monthly composite; tritium analysis on quarterly composite.
Gamma isotopic 3
- e. Sediment BY-12, Oregon Pool of Rock River, Semiannually Downstream of Discharge, analysis semiannually.
4.5 mi SSW (7.3 km K) (p:'adprot'xdcm~byr1 1R I-6.doc)
BYRON Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sampling or Monitoring Locations Collection Frequency of Analysis
- 4. Ingestion
- a. Milk a. Indicators Biweekly: May through Gamma isotopic 3 and October; monthly: 1-131 analysis 4 on each November through April. sample.
BY-20, K. Reeverts Dairy Farm, 2.0 mi NE (3.2 km C) BY-30, Don Roos Dairy, 5.3 mi SE (8.4 km G)
- b. Controls BY-26, Glen Gazzard's Dairy, 12.0 mi N (19.2 km A)
- b. Fish a. Indicator 3
BY-31, Rock River in vicinity of Discharge, Two times annually Gamma isotopic 2.2 mi WNW (3.5 km P) analysis on edible portions.
- b. Control BY-29, Byron, Upstream of Intake 3.0 mi N (4.8 km A) 3
- c. Food Products a. Indicators Annually Gamma isotopic analysis on each Two samples from each of the four sample.
major quadrants within 6.2 miles of the station. (p:radprot~odcm\byr1 I R1 -6.doc) 11-7
BYRON Revision 1.6 October 1998 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Sampling or Type of Frequency Exposure Pathway of Analysis Collection Frequency and/or Sample Sampling or Monitoring Locations Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.
- b. Control Two samples within 9.3 to 18.6 miles of the station.
(p:\raddtodcmIW 1IR1-6.doc) '-N V,.
BYRUN Revision 1.6 October 1998 TABLE 11-1 (Cont'd) Radiological Environmental Monitoring Program 1 Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Radiation Protection Director. 2Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. 3Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station. 41-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. (p:*radprot\odcm\byr1 1R1-6.doc) 11-9
Revision 1.6 October 1998 BYRON a S *
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Byron Station Chapter 12 Change Summary ODCM Revision 1.6, January 1999 Page or Section Change Description 12-ii Updated revision number. 12iii-12iv Updated page number references. 12-1 Change Tech Spec references from Current Tech Spec (CTS) to Improved Tech Spec (ITS). 12-2 thru 12-4 Updated Definitions to fully align with Improved Technical Specification and Technical Requirements Manual Definitions. 12-5 Changed bases reference from CTS to ITS. 12-6 thru 12-70 Format Changes. Format was updated to comply with ITS format, as documented in the Technical Requirements Manual Chapters 3.11 and 3.12. 12-50 Old Steam Generator Storage Facility (OSGSF) Surveillance broken apart into two separate actions. Surveillance had required initial survey of OSGSF, quarterly check of sump level, and requirement to remove water if identified. Initial Survey completed and within requirements, so it has been removed. Surveillance 12.4.5.B.3 now only requires a quarterly sump level check. New Surveillance (12.4.5.B.4) requires any water identified to be sampled and analyzed. 12-71 Annual Radiological Environmental Operating Report due date extended from May 1st to May 1 5 th, as specified in ITS 5.6.2. 12-73 Technical Specification reference updated to reflect ITS. 12-74 Records Retention requirements removed from Tech Specs, and placed in UFSAR Chapter 17. Reference updated to reflect change. Reference to On-site review and investigative function removed, replaced with Independent Technical Review and PORC. 12-75 Reference to On-site review and investigative function removed, replaced with Independent Technical Review and PORC.
BYRON Revision 1.6 January 1999 CHAPTER 12.0 SPECIAL NOTE The transfer of the Byron Radiological Effluent Technical Specifications to the ODCM was approved by the Nuclear Regulatory Commission in Technical Specification Amendment 46, dated April 13, 1992. 12-i (p:radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999. BYRON ANNEX INDEX CHAPTER 12 Revision 1.6 C 12-ii (p:radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-2 12.2 INSTRUMENTATION 12-6
- 1. Radioactive Liquid Effluent Monitoring Instrumentation 12-6
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-16 12.3 RADIOLOGICAL EFFLUENTS - LIQUID 12-25
- 1. Concentration Limits for Effluents 12-25
- 2. Dose From Liquid Effluents 12-31
- 3. Liquid Radwaste Treatment System 12-33 12.4 RADIOLOGICAL EFFLUENTS - GASEOUS 12-36
- 1. Dose Rate for Gaseous Effluents 12-36
- 2. Dose - Noble Gases 12-41
- 3. Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form 12-43
- 4. Gaseous Radwaste Treatment System 12-46
- 5. Total Dose 12-49 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-52
- 1. Radiological Environmental Monitoring Program 12-52
- 2. Land Use Census 12-66
- 3. Interlaboratory Comparison Program 12-69 12.6 REPORTING REQUIREMENTS 12-71
- 1. Annual Radiological Environmental Operating Report 12-71
- 2. Annual Radioactive Effluent Release Report 12-73
- 3. Offsite Dose Calculation Manual (ODCM) 12-74
- 4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-75 12-iii (p:radprot\odcm\byl2R1 -6.doc)
BYRON Revision 1.6 January 1999 CHAPTER 12 C'. RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) LIST OF TABLES TABLE TITLE PAGE 12.0-1 Compliance Matrix 12-1 12.1-1 Frequency Notations 12-5 12.2-1 Radioactive Liquid Effluent Monitoring 12-12 Instrumentation 12.2-2 Radioactive Liquia Effluent Monitoring 12-15 Instrumentation Surveillance Requirements 12.2-3 Radioactive Gaseous Effluent Monitoring 12-21 Instrumentation 12.2-4 Radioactive Gaseous Effluent Monitoring 12-24 Instrumentation Surveillance Requirements 12.3-1 Radioactive Liquid Waste Sampling and Analysis 12-27 Program 12.4-1 Radioactive Gaseous Waste Sampling and Analysis 12-38 Program 12.5-1 Radiological Environmental Monitoring Program 12-58 12.5-2 Reporting Levels for Radioactivity Concentrations 12-63 in Environmental Samples 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-64 12-iv (p:radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 BYRON STATION Table 12.0-1 COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification 10 CFR 50 1. Gamma air dose and beta air dose due to A-1 12.4.2 5.5.4.h Appendix I airborne radioactivity in effluent plume. A-2
- a. Whole body and skin dose due to airborne A-6 N/A N/A radioactivity in effluent plume are A-7 reported only if certain gamma and beta air dose criteria are exceeded.
- 2. CDE for all organs and all four age groups A-1 3 12.4.3 5.5.4.i due to iodines and particulates in effluent plume. All pathways are considered.
- 3. CDE for all organs and all four age groups A-29 12.3.2 5.5.4.d due to radioactivity in liquid effluents.
10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 5.5.4.c I components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 database. . 40 CFR 190 1. Whole body dose (DDE) due to direct dose, A-35 12.4.5 5.5.4.j I (now by ground and plume shine from all sources at a reference, also station. part of 10 CFR 20) 2. Organ doses (CDE) to an adult due to all A-13 pathways. Technical 1. "Instantaneous" whole body (DDE), skin (SDE), A-8 12.4.1 5.5.4.g Specifications and organ (CDE) dose rates to an adult due A-9 I to radioactivity in airborne effluents. A-28 For the organ dose, only inhalation is considered.
- 2. "Instantaneous" concentration limits for A-32 12.3.1 5.5.4.b liquid effluents. I 12-1 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 12.1 DEFINITIONS 12.1.1 ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. 12.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated. 12.1.3 A CHANNEL CHECK shall be the quantative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. 12.1.4 A CHANNEL OERATIONAL TEST (COT) shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy. ( 12.1.5 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1 133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TID-14844, AEC, 1962. "Calculation of Distance Factors for Power and Test Reactor Sites." 12.1.6 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise. The 25% variance shall not be applied to Operability Action statements. The bases to Improved Technical Specification 3.0.2 provide clarifications to this requirement. 12.1.7 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. 12.1.8 A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table TI .1-1 with fuel in the reactor vessel. 12.1.9 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from ( background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. 12-2 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 12.1.10 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABLITY when it is capable of performing its specified safety functions(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). 12.1.11 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71. State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste. 12.1.12 PURGE/PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. 12.1.13 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MWth. 12.1.14 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. 12.1.15 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements. 12.1.16 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. 12.1.17 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. 12.1.18 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee. 12.1.19 VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to. reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. 12-3 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999, 12.1.20 VENTING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 12.1.21 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. 12.1.22 Definitions Peculiar to Estimating Dose to Members of the Public using the ODCM Computer Program.
- a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.
- b. PROJECTED - PROJECTED refers to using known release data from the previous time period or estimated release data to forecast a future dose to members of the public. This data is not incorporated into the database.
12-4 (p:Xradprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 TABLE 12.1-1 FREQUENCY NOTATIONS* Notation Frequency S - Shiftly At least once per 12 hours D - Daily At least once per 24 hours W - Weekly At least once per 7 days M - Monthly At least once per 31 days
* - Quarterly At least once per 92 days SA - Semiannually At least once per 184 days A - Annually At least once per 366 days R - Refuel Cycle At least once per 18 months S/U - Startup Prior to each reactor startup N.A. Not applicable P - Prior Prior to each radioactive release
*Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action statements. The bases to ITS 3.0.2 provide clarifications to this requirement. These I frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.
12-5 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1990.--,- 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation 12.2.1 .A All radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE. APPLICABILITY: At all times. ACTIONS: NOTES
- 1. Separate Condition entry is allowed for each channel.
- 2. All samples are to be analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.
- 3. TLCO 3.0.c is not applicable.
- 4. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radioactive liquid A.1 Suspend the release of Immediately effluent monitoring radioactive liquid effluent instrumentation channel monitored by the affected Alarm/Trip Setpoint less channel. conservative than required. OR A.2 Declare the channel Immediately inoperable. B. Less than the required B.1 Enterthe Condition referenced Immediately radioactive liquid effluent in Table 12.2-1 for the monitoring instrumentation affected channel(s). channels OPERABLE. (continued) ( 12-6 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Verify at least two independent Prior to initiating a release Action B.1 and referenced by samples are analyzed. Table 12.2-1. AND C.2 Verify at least two technically Prior to initiating a release qualified members of the facility staff independently verify the release rate calculations. AND C.3 Verify at least two technically Prior to initiating a release qualified members of the facility staff independently verify the discharge line valving. AND C.4.1 Restore the required 14 days number of channels to OPERABLE. OR C.4.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability. (continued) 12-7 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) A CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Verify grab samples are Every 12 hours Action B.1 and referenced by collected and analyzed. Table 12.2-1. AND D.2.1 Restore the required 30 days number of channels to OPERABLE. OR D.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability (continued) ( 12-8 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 ---- NOTES-Action 8.1 and referenced by 1. Pump performance Table 12.2-1. curves generated in place may be used to estimate flow.
- 2. Only required to be performed during actual releases.
Estimate flow rate. Every 4 hours AND E.2.1 Restore the required 30 days number of channels to OPERABLE. OR E.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability. (continued) 12-9 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action F.1.1 ---- NOTE----- B.1 and referenced by Table Only required to be 12.2-1. performed when the specific activity of the secondary activity of the secondary coolant is
>0.01 I.Ci/gm DOSE EQUIVALENT 1-131.
Verify grab samples are Every 12 hours collected and analyzed. OR F.1.2 -- NOTE----.. Only required to be performed when the specific activity of the secondary coolant is
<0.01 4Ci/gm DOSE
( EQUIVALENT 1-131. Verify grab samples are Every 24 hours collected and analyzed. AND 30 days F.2.1 Restore the required number of channels to OPERABLE. OR 12 months F.2.2 Supplement the Radioactive Effluent Release Report Pursuant to Technical Specification 5.6.3 with the cause for failure to correct inooerabilitv. (continued) 12-10 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Verify liquid grab Every 12 hours Action B.1 and referenced by samples are collected Table 12.2-1. and analyzed. AND G.2.1 Restore the required 30 days number of channels to OPERABLE. OR G.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct inoperability. H. Required Action and H.1 Suspend the release of Immediately associated Completion Time radioactive liquid effluent for Conditions C, D, E, F, or monitored by the G not met. affected channel., 12-11 (p:kradprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-1 (Page 1 of 3) Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS Radioactivity Monitors Providing Alarm and Automatic Termination of Release
- a. Uquid Radwaste Effluent Line C 12.2.1.B.1 (ORE-PR001) 12.2.1 .B. 3 (a) 12.2.1.6.4(c) 12.2.1.B.5
- b. Fire and Oil Sump (ORE-PR005) F 12.2.1.B.1 12.2.1.B.2 12.2.1.B. 3 (a) 12.2.1.B.4(c)
- c. Condensate Polisher Sump Discharge F 12.2.11.8.1 (ORE-PRO41) 12.2.1..B.2 12.2.1 .B. 3 (a) 12.2.1.B.4(c) (
(continued) (a) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm/Trip Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(C) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. { 12-12 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-1 (Page 2 of 3) Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
- a. Essential Service Water 1). Unit 1 a). RCFC 1A and 1C Outlet 1 0 12.2.1.B.1 (1 RE-PR002) 12.2.1 .B.2 12.2.1 .B. 3 (b) 12.2.1 .B.4(c) b). RCFC 1Band 1D Outlet 0 12.2.1.B.1 (1 RE-PRO03) 12.2.1.B.2 12.2.1 .B. 3 (b) 12.2.1.B. 4 (c) 2). Unit 2 a). RCFC 2A and 2C Outlet (2RE-PRO02) 1 D 12.2.11.B.1 12.2.1.B.2 12.2.1.B. 3 (b) 12.2.1 .. 4 (c) b). RCFC 2B and 2D Outlet (2RE-PRO03) D 12.2.1.B.1 12.2.1.B.2 12.2.1 .B.3(b) 12.2.1.13.4 (c)
- b. Station Blowdown Line (ORE-PRO10) 1 D 12.2.1.B.1 12.2.11.6.2 12.2.1.B. 3 (b) 12.2.1.B. 4 (c)
(continued) (b) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. 12-13 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 199*, Table 12.2-1 (Page 3 of 3) Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS
- 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent Line 1E 12.2.1E..(d)
(Loop-WX001) 12.2.1 .B.3 12.2.11.B.4
- b. Liquid Radwaste Effluent Une (Loop-WX630) 1E 12.2.1E.B.(d) 12.2.1.B.3 12.2.1.B.4
- c. Station Blowdown Line (Loop-CW032) E12.2.1.B.(d) 12.2.1 .B.3 12.2-1.8.4
- 4. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent Component Cooling Water 2 G 12.2.1.B.1 12.2.1.B.2 (
Line 12.2.1 .B. 3 (a) 12.2.1.B.4(c)
- a. (ORE-PRO09 and 1/2RE-PRO09)
(a) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist:
- 1. Instrument indicates measured levels above the Alarm/Trip Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (d) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. 12-14 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-2 SURVEILLANCE REQUIREMENTS NOTES
- 1. Refer to Table 12.2-1 to determine which Surveillance Requirements apply to each instrument.
- 2. Alarm/Trip Setpoints shall be set to ensure that the limits of Requirement 12.3.1 .A are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
SURVEILLANCE FREQUENCY 12.2.1 .B.1 Perform a CHANNEL CHECK. 24 hours 12.2.1..B.2 Perform a SOURCE CHECK. 31 days 12.2.1.B.3 Perform a CHANNEL OPERATIONAL TEST. 92 days 12.2.1.B.4 Perform a CHANNEL CALIBRATION. 18 months 12.2.1.B.5 Perform a SOURCE CHECK. Prior to each release 12-15 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation 12.2.2.A All radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE. APPLICABILITY: At all times. ACTIONS NOTES
- 1. Separate Condition entry is allowed for each channel.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.o.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME ( A. One or more gaseous effluent A.1 Suspend the release of Immediately monitoring instrumentation radioactive gaseous channel Alarm/Trip Setpoint(s) effluent monitored by the less conservative than affected channel. required. OR A.2 Declare the channel Immediately inoperable. B. Less than the required B.1 Enter the Condition Immediately radioactive gaseous Referenced in Table effluent monitoring 12.2-3 for the affected instrumentation channels OPERABLE. channel(s). (continued) 12-16 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. As requirea Dy Requirea CA1 Verify at least two Prior to initiating a release Action B.1 and referenced by independent samples of Table 12.2-3. the tank's contents are analyzed. AND C.2 Verify at least two Prior to initiating a release technically qualified members of the facility staff independently verify the release rate calculations. AND C.3 Verify at least two Prior to initiating a release technically qualified members of the facility staff independently verify the discharge valve lineup. AND C.4.1 Restore the require 14 days number of channels to OPERABLE. OR C.4.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperabililty. (continued) 12-17 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1.1 Suspend PURGING via Immediately Action B.1 and referenced by this pathway. Table 12.2-3. OR D.1.2 Verify real time During release "monitoringof radioactive effluents released via this pathway. AND D.2.1 Restore the required 7 days number of channels to OPERABLE. OR D.2.2 Supplement the Radioactive Effluent 12 months (7. Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability. (continued) ( 12-18 (p:radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Estimate flow rate. Every 4 hours Action B.1 and referenced by Table 12.2-3. AND E.2.1 Restore the required 30 days number of channels to OPERABLE. OR E.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability. F. As required by Required F.1 Verify samples are During release Action B.1 and referenced by continuously collected with Table 12.2-3. auxiliary sampling equipment as required by Table 12.4-1. AND F.2.1 Restore the required 30 days Number of Channels to OPERABLE. OR F.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability. (continued) 12-19 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999, ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Verify gaseous grab Every 12 hours Action B.1 and referenced by samples are collected Table 12.2-3. and analyzed for principle gamma emitters at a Lower Limit of Detection (LLD) as specified in OFFSITE DOSE CALCULATION MANUAL (ODCM) Table 12.4.-i. AND G.2.1 Restore the required 30 days number of channels to OPERABLE. OR G.2.2 Supplement the 12 months Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 with the cause for failure to correct the inoperability. H. Required Action and H.1 Suspend the release of Immediately associated Completion Time radioactive gaseous for Conditions C, D, E, F, or G effluent monitored by the not met. affected channel. 12-20 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-3 (Page 1 of 3) Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED SURVEILLANCE INSTRUMENT CHANNELS CONDITION REQUIREMENTS U-1 Plant Vent Monitoring System 1 Noble Gas Activity Monitor - Providing Alarm
- a. High Range (1RE-PRO28D) 1 G 12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- b. Low Range (1RE-PR028B) 1 G 12.2.2.8.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- c. Iodine Sampler (1RE-PR028C) F 12.2.2,.1 12.2.2.B.2 12.2.2.B.3(b) 12,2.2.B.4(c)
- d. Particulate Sampler (1 RE-PR028A) F 12.2.2.8.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- e. Effluent System Flow Rate Measuring Device E 12.2.28.1 (LOOP-VA01 9) 12.2.2.B.3 12.2.2.B.4
- f. Sampler Flow Rate Measuring Device (1FT-PR165) 1 E 12.2.2.B.1 12.2.2.B.3 12.2.2.B.4 (continued)
(b) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. 12-21 (p:\radprot\odcm~by1 2R1 -6 .doc)
BYRON Revision 1.6 January 1999C. Table 12.2-3 (Page 2 of 3) Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED SURVEILLANCE INSTRUMENT CHANNELS CONDITION REQUIREMENTS U-2 Plant Vent Monitoring System
- 2. Noble Gas Activity Monitor - Providing Alarm
- a. High Range (2RE-PRO28D) G 12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- b. Low Range (2RE-PRO28B) 1 G 12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- c. Iodine Sampler (2RE-PRO28C) F 12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c)
- d. Particulate Sampler (2RE-PRO28A) F 12.2.2.B.1 12.2.2.B.2 12.2.2.B.3(b) 12.2.2.B.4(c) (!
- e. Effluent System Flow Rate Measuring 1 E 12.2.2.B.1 Device (LOOP-VA020) 12.2.2.B.3 12.2.2B.4
- f. Sampler Flow Rate Measuring Device E 12.2.2.B.1 (2FT-PRI 65) 12.2.2.B.3 12.2.2.B.4
- 3. Refer to Technical Requirements Manual 3.3.e for Gaseous Waste Management Explosive Gas Monitoring Instrumentation (continued)
(b) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. I 12-22 (p:\radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-3 (Page 3 of 3) Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CONDITION SURVEILLANCE CHANNELS REQUIREMENTS
- 4. Gas Decay Tank System Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 2 C 12.2.2.B.3(a)
(ORE-PRO02A and 2B) 12.2.2.B.4(c) 12.2.2.8.5 12.2.2.B.6
- 5. Containment Purge System 1 D 12.2.2.B.1 12.2.2.B.3(b)
- a. Noble Gas Activity Monitor Providing Alarm 12.2.2.B.4(c)
(1/2RE-PRO01 B) 12.2.2.B.6
- b. Iodine Sampler (1/2RE-PROOIC) F 12.2.2.B.4(c) 12.2.2.8.5 12.2.2.B.6
- c. Particulate Sampler (1/2RE-PRO01A) 1 F 12.2.2.B.4(c) 12.2.2.B.5 12.2.2.B.6 (a) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm/Trip Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(b) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the Alarm Setpoint, or
- 2. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- 3. Detector check source test failure, or
- 4. Detector channel out-of-service, or
- 5. Monitor loss of sample flow.
(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. 12-23 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.2-4 SURVEILLANCE REQUIREMENTS NOTES
- 1. Refer to Table 12.2-3 to determine which Surveillance Requirements apply to each instrument.
- 2. Alarm/Trip Setpoints shall be set to ensure that the limits of 12.4.1.A and Technical Specification 5.5.12 are not exceeded. The Alarm/Trip Setpoints of these channels meeting 12.4.1.A shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
SURVEILLANCE FREQUENCY 12.2.2.1.1 Perform a CHANNEL CHECK. 24 hours 12.2.2.B.2 Perform a SOURCE CHECK. 31 days 12.2.2.B.3 Perform a CHANNEL OPERATIONAL TEST. 92 days 12.2.2.B.4 Perform a CHANNEL CALIBRATION. 18 months 12.2.2.B.5 Perform a CHANNEL CHECK. Prior to each release 12.2.2.B.6 Perform a SOURCE CHECK. Prior to each release 12-24 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 12.3 RADIOLOGICAL EFFLUENTS (RE) - LIQUID 12.3.1 Concentration Limits for Effluents 12.3.1 .A -The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-i) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 104 tpCi/ml total activity. APPLICABILITY: At all times. ACTIONS NOTES
- 1. Separate Condition entry is allowed for each release.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of radioactive A.1 Restore the Immediately material released exceeding concentration within the limit. limit. OR A.2 Terminate the release. Immediately 12-25 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS NOTES
- 1. All Surveillance Requirements to be performed at frequency defined by Table 12.3-1.
- 2. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of 12.3.1 .A.
SURVEILLANCE FREQUENCY 12.3.1..B Sample and analyze liquid wastes. Per Table 12.3-1 12-26 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.3-1 (Page 1 of 4) Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD) SAMPLING ANALYSIS TYPE OF ACTIVITY (,.Ci/ml) (Refer to Note 1, LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30) 1 Batch Release Tanks "P P Principal Gamma Emitters 5 x 1o07 (a) Each Batch Each Batch (b) 1-131 1 x 10-6 P M Dissolved and Entrained 1 x 10"5 One BatchlM Gases (Gamma Emitters) P M H-3 1x 10 5 Each Batch Composite(c) P Q Gross Alpha 1 x 10*7 Each Batch Composite(c) Sr-89, Sr-90 5x10 4 Fe-55 1x 10 (continued) (a) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. (b) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54. Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (c) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results ina specimen that is representative of the liquids released. 12-27 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.3-1 (Page 2 of 4) *. Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD) SAMPLING ANALYSIS TYPE OF ACTIVITY (liCilml) (Refer to Note 1, LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30)
- 2. Continuous(e) W Principal Gamma Emitters(b) 5 x 107 Continuous Releases(d) Composite(e) 1-131 1x 10 5
- a. Circulating Water M M Dissolved and Entrained 1 x 10-Blowdown Grab Sample Gases (Gamma Emitters)
- b. Waste Water Continuous(e) M H-3 1 x 10-6 Treatement Composite(e) 7 System Discharge Gross Alpha 1 x 10-to Flume
- c. Condensate Continuous(e) Q Sr-89, Sr-90 5 x 10.8 Polisher Sump Composite(e)
Discharge Fe-55 1 x 10e (b) (continued) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn C 65, Mo-99, Cs-134, Cs-137, Ce-1i41, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (d) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. (e) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed In order for the composite sample to be representative of the effluent release. 12-28 (p:\radprot\odcmby1 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.3-1 (Page 3 of 4) Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD) SAMPLING ANALYSIS TYPE OF ACTIVITY (p.Ci/ml) (Refer to Note 1, LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30)
- 3. Continuous W(f) W() Principal Gamma Emitters 5 x 10-7 Release(d) Grab Sample (b)
Essential 1-131 1 x 10"6 Service Water Reactor Dissolved and Entrained 1 x 10" Containment Fan Gases (Gamma Emitters) Cooler (RCFC) Outlet Line H-3 1 x 10-5 (b) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-1 41, and Ce-1 44. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (d) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during F the continuous release. (f) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors 1/2RE-PR002 and 112RE-PRO03 indicates measured levels greater than 1 x 1e pCi/ml above background at any time during the week. 12-29 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.3-1 (Page 4 of 4) Radioactive Liquid Waste Sampling and Analysis Program Note 1: Lower Limit of Detection (LLD) The LLD is defined, for purposes of these Technical Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = LLD 4.66 sb E* V *2.22 x 106*Y* exp (-TAr) Where: LLD = the lower limit of detection (microCuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V= the sample size (units of mass or volume), 2.22 x 1Or = the number of disintegrations per minute per microCurie, Y= the fractional radiochemical yield, when applicable, X= the radioactive decay constant for the particular radionuclide (sec"), and A- = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and A- should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. 12-30 (p:\radprot\odcm~by1 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.3 RADIOLOGICAL EFFLUENTS (RE) - LIQUID 12.3.2 Dose From Liquid Effluents 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents, from each unit, to UNRESTRICTED AREAS (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-I) shall be limited:
- 1. During any calendar quarter to < 1.5 mrem to the whole body and to < 5 mrem to any organ, and
- 2. During any calendar year to
- 3 mrem to the whole body and to < 10 mrem to any organ.
APPLICABILITY: At all times. 12-31 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 C ACTIONS NOTES
- 1. Separate Condition entry is allowed for each dose.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose exceeding A.1 Submit Special Report to the 30 days above limits. Commission that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. ( SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.3.2.B Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year. 12-32 (p:Xradprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.3 RADIOLOGICAL EFFLUENTS (RE) - LIQUID 12.3.3 Liquid Radwaste Treatment System 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and shall be used to reduce releases from each unit to UNRESTRICTED AREAS (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-I) when the projected dose would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period. APPLICABILITY: At all times. 12-33 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS NOTES
- 1. Separate Condition entry is allowed for each release.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive liquid waste being A.1 Submit Special Report to the 30 days discharged without treatment. Commission that includes an explanation of why liquid AND radwaste was being discharged without treatment, In excess of above limits, identification of any inoperable equipment or subsystems, and AND the reason for the inoperability; action(s) taken to Any portion of the Liquid Radwaste Treatment System not in operation. restore the inoperable equipment to OPERABLE status; and a summary ( description of actions(s) taken to prevent recurrence. 12-34 (p:Vradprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.3.3.13.1 ------- NOTE Only required to be performed when the Liquid Radwaste Treatment System is not fully utilized. Project doses due to liquid releases from each unit to 31 days UNRESTRICTED AREAS. 12.3.3.B.2 Verify the installed Liquid Radwaste Treatment Per the applicable System is OPERABLE by meeting the requirements of Surveillance Requirements 12.3.1.A and 12.3.2.A. 12-35 (p:\radprot\odcm\byl2Rl-6.doc)
BYRON Revision 1.6 January 1999 3/4 12.4 RADIOLOGICAL EFFLUENTS (RE) - GASEOUS 12.4.1 Dose Rate for Gaseous Effluent 12.4.1 .A The dose rate in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-I) shall be limited to:
- 1. For noble gases: < 500 mrem/yr to the whole body and < 3000 mrem/yr to the skin, and
- 2. For Iodine-1 31 and 133, for tritium, and for all radionuclides in particulate form with half-lives > 8 days: < 1500 mrem/yr to any organ.
APPLICABILITY: At all times. ACTIONS NOTES
- 1. Separate Condition entry is allowed for each dose rate.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeding above A.1 Restore the release rate to Immediately limits. within limits. 12-36 (p:Xradprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.1..B.1 Determine dose rate due to noble gases within limits. Per Table 12.4-1 12.4.1..B.2 Determine dose rate due to 1-131, 1-133, tritium and all Per Table 12.4-1 other radionuclides in particulate form with half-lives
> 8 days within limits.
12-37 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 (. Table 12.4-1 (Page 1 of 3) Radioactive Gaseous Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD) GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (jICi/ml) (Refer to Note 1, TYPE FREQUENCY FREQUENCY ANALYSIS Page 12-30) 1 Waste Gas Decay P P Principal Gamma Emitters 1 x 104 Tank Each Tank Each Tank (a) Grab Sample
- 2. Containment Purge P Each PURGE(b) Principal Gamma Emitters 1 x 10-4 Each PURGE(b) Grab Sample (a)
Grab Sample 7 H-3 1 x 10-(continued) (a) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe 135, and Xe-1 38 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-1 34, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5.6.3, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (b) Sampling and analysis shall also be performed following shutdown, startun, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. 12-38 (p:Vradprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.4-1 (Page 2 of 3) Radioactive Gaseous Waste Sampling and Analysis Program LOWER LIMIT OF MINIMUM DETECTION (LLD) SAMPLING ANALYSIS TYPE OF ACTIVITY (pCi/ml) (Refer to Note 1. GASEOUS RELEASE FREQUENCY FREQUENCY ANALYSIS Page 12-40) TYPE
- 3. Auxiliary Building Vent M(c)(d) M Principal Gamma Emitters 1 x o04 Stack (Units 1 and 2) Grab Sample (a) 7 H-3 1 x 10 Continuous(e) W(f) 1-131 1 x 10-12 Charcoal Sample 1-133 1 x 10"'0 Continuous(e) W(f) Principal Gamma Emitters 1 x 10"*
Charcoal Sample (a) Continuous(e) Q Gross Alpha 1 x 10"11 Composite Particulate Sample Continuous(e) Q Sr-89, Sr-90 I x 10"1, Composite Particulate Sample Continuous N.A. Noble Gases; 1 x i0" Noble Gas Gross Beta or Gamma Monitor (a) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe 135, and Xe-1 38 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-1 34, Cs-1 37, Ce-1 41, and Ce-1 44 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 5.6.3. in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (c) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. (d) Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. (e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with 12.4.1, 12.4.2, and 12.4.3. (f) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. 12-39 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.4-1 (Page 3 of 3) C Radioactive Gaseous Waste Sampling and Analysis Program Note 1: Lower Limit of Detection (LLD) The LLD is defined, for purposes of these Technical Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD =4.66 Sb EV* 2.22 x lO 6
- Y* exp (-4Ar)
Where: LLD = the lower limit of detection (microCuries per unit mass or volume), Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), V= the sample size (units of mass or volume), ( 2.22 x 1O6 = the number of disintegrations per minute per microCurie, Y= the fractional radiochemical yield, when applicable, X= the radioactive decay constant for the particular radionuclide (sec-1), and A- = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and Ac should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. 12-40 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.4 RADIOLOGICAL EFFLUENTS (RE) - GASEOUS 12.4.2 Dose - Noble Gases 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY/UNRESTRICTED AREA boundary (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-1) shall be limited to:
- 1) During any calendar quarter: < 5 mrad for gamma radiation and < 10 mrad for beta radiation, and
- 2) During any calendar year: < 10 mrad for gamma radiation and < 20 mrad for beta radiation.
APPLICABILITY: At all times. 12-41 (p:\radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 .. ACTIONS NOTES
- 1. Separate Condition entry is allowed for each air dose.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated air dose exceeding A.1 Submit a Special Report to the 30 days limit. Commission that identifies the cause(s) for exceeding the limits(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.2.1 Determine cumulative dose contributions for noble 31 days gases for the current calendar quarter and current calendar year. ( 12-42 (p:Vradprot\odcm\by1 2R1-6.doc)
BYRON Revision 1.6 January 1999 12.4 RADIOLOGICAL EFFLUENTS (RE) - GASEOUS 12.4.3 Dose 131, 1-133, Tritium, and Radioactive Material in Particulate Form 12.4.3.A The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY/UNRESTRICTED AREA boundary(see BYRON Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-I) shall be limited to:
- 1) During any calendar quarter: < 7.5 mrem to any organ, and
- 2) During any calendar year: < 15 mrem to any organ.
APPLICABILITY: At all times. 12-43 (p:\.radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS NOTES
- 1. Separate Condition entry is allowed for each calculated dose.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose exceeding A.1 Submit a Special Report to the 30 days limit. Commission that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken (. to assure that subsequent releases will be in compliance with the above limits. 12-44 (p:Xradprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.3.B Determine cumulative dose contributions for Iodine- 31 days 131 and 133, tritium, and radionuclides in particulate form with half-lives > 8 days for the current calendar quarter and current calendar year. 12-45 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 C, 12.4 RADIOLOGICAL EFFLUENTS (RE) - GASEOUS 12.4.4 Gaseous Radwaste Treatment System 12.4.4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and shall be used to reduce activity in releases, from each unit, of gaseous effluents when the projected doses at and beyond the SITE BOUNDARY/UNRESTRICTED AREA boundary (see Byron Station OFFSITE DOSE CALCULATION MANUAL (ODCM) Annex, Appendix F, Figure F-1) in 31 days would exceed:
- 1) 0.2 mrad to air from gamma radiation,
- 2) 0.4 mrad to air from beta radiation, or
- 3) 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times. 12-46 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS NOTES
- 1. Separate Condition entry is allowed for each gaseous release.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. ---- NOTE---- A.1 Submit a Special Report to the 30 days Only applicable if radioactive Commission that includes the gaseous waste being following information: discharged without treatment.
- a. Identification of any inoperable equipment or Gaseous releases in excess subsystems, and the reason of limit. for the inoperability,
- b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
- c. Summary description of action(s) taken to prevent recurrence.
12-47 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.4.8.1 ----- NOTE-------......------------ Only required to be performed when the Gaseous Radwaste Treatment Systems are not being fully utilized. Project doses due to gaseous releases from each unit 31 days to areas at or beyond the SITE BOUNDARY/UNRESTRICTED AREA boundary. 12.4.4.B.2 Verify the installed VENTILATION EXHAUST Per the applicable TREATMENT SYSTEM and WASTE GAS HOLDUP Surveillance SYSTEM are OPERABLE by meeting Surveillance Requirements Requirements 12.4.1.B and 12.4.2.B or 12.4.3.B. ( 12-48 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.4 RADIOLOGICAL EFFLUENTS (RE) - GASEOUS 12.4.5 Total Dose 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from the uranium fuel cycle sources shall be limited to < 25 mrem to the whole body or any organ (except the thyroid) and < 75 mrem to the thyroid. APPLICABILITY: At all times. ACTIONS NOTES
- 1. Separate Condition entry is allowed for each calculated dose.
- 2. TLCO 3.0.c is not applicable.
- 3. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses exceeding A.1 NOTE twice the limits for: Calculations to include direct 12.3.2.A.1 radiation contributions from the 12.3.2.A.2 units and from outside storage 12.4.2.A.1 tanks. 12.4.2.A.2 12.4.3.A.1 or 12.4.3.A.2 Determine if the 12.4.5.A limits 15 days have been exceeded. (continued) 12-49 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action of Condition B.1 Submit a Special Report to the 15 days A determines the 12.4.5.A Commission (Refer to Note 1, limits have been exceeded. Page 12-51). SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.4.5.B.1 NOTE--- Only applicable if Condition A is entered. Determine cumulative dose contributions from direct In accordance with the radiation from the units and from radwaste storage tanks. OFFSITE DOSE CALCULATION MANUAL (ODCM) Ac k 12.4.5.B.2 Determine cumulative dose contributions from liquid and Per the applicable gaseous effluents in accordance with Surveillance Surveillance Requirements Requirements 12.3.2.8, 12.4.2.8 and 12.4.3.8 and in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). 12.4.5.1.3 Inspect the Old Steam Generator Storage Facility 92 days (OSGSF) sump for the presence of liquid and the appearance that seepage has occurred. 12.4.5.B.4 -NOTE Only required to be performed if 12.4.5.B.3 identifies both the presence of liquid and indications of seepage. Sample and analyze the liquid from the OSGSF sump. 92 days 12-50 (p:\radprot\odcm\by12R1-6.doc)
BYRON Revision 1.6 January 1999 NOTE 1 The Special Report shall define the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the 12.4.5.A limits and includes the schedule for achieving conformance with the 12.4.5.A limits. The Special Report, as defined by 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC from the uranium cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the 12.4.5.A limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely response and a variance is granted until staff action on the request is complete. 12-51 (p:Vradprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999(,, 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Radiological Environmental Monitoring Program 12.5.1 .A The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 12.5-1. APPLICABILITY: At all times. ACTIONS NOTES
- 1. TLCO 3.0.c is not applicable.
- 2. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. REMP not being conducted A.1 Submit in the Annual Radiological 12 months as specified in Table Environmental Operating Report, 12.5-1. as required by Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing recurrence. (continued) ( 12-52 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME
- - NOTE-----
B. Level of radioactivity as a B.1 The methodology and result of plant effluents in an parameters used to estimate environmental sampling the potential annual dose to medium at a specified a MEMBER OF THE location exceeding the PUBLIC shall be indicated in reporting limits of Table this report. 12.5-2 when averaged over any calendar quarter. Submit a Special Report to 30 days the Commission that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of 12.3.2.A, 12.4.2.A, and 12.4.3.A. (continued) 12-53 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999(... ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. More than one of the C.1 ---- NOTE radionuclides in Table 12.5-2 The methodology and parameters are detected in the sampling used to estimate the potential medium. annual dose to a MEMBER OF THE PUBLIC shall be indicated in AND this report. C, C2 S+ + ... > 1.0 Submit a Special Report to the RL1 RL2 Commission that identifies the 30 days cause(s) for exceeding the limit(s) where; and defines the corrective actions C = concentration to be taken to reduce radioactive RL = reporting level, effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of 12.3.2.A, 12.4.2.A, and 12,4.3.A. (continued) (I 12-54 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Radionuclides other than D.1 ---.. NOTE---- those in Table 12.5-2 are The methodology and parameters detected. used to estimate the potential annual dose to a MEMBER OF AND THE PUBLIC shall be indicated in this report. Are the result of plant effluents. Submit a Special Report to the AND Commission that identifies the 30 days cause(s) for exceeding the limit(s) The potential annual dose to and defines the corrective actions a MEMBER OF THE PUBLIC to be taken to reduce radioactive from all radionuclides is equal effluents so that the potential to or greater than the annual dose to a MEMBER OF calendar limits of 12.3.2.A, THE PUBLIC is less than the 12.4.2.A, and 12.4.3.A. calendar year limits of 12.3.2.A, 12.4.2.A, and 12.4.3.A. E. Measured levels of E.1 Report and describe the condition 12 months radioactivity not the result of in the Annual Radiological plant effluents. Environmental Operating Report required by Specification 5.6.2. (continued) 12-55 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME F. Milk or fresh leafy F.1 Identify specific locations for 30 days vegetable samples obtaining replacement samples unavailable from one or more and add them to the REMP given of the sample locations in the OFFSITE DOSE required by Table 12.5-1. CALCULATION MANUAL (ODCM). AND F.2 Submit controlled version of the 180 days ODCM to the NRC including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples, deleting the specific locations from which samples were unavailable and justifying the selection of the new location(s) for obtaining samples. C' 12-56 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.5.1B The radiological environmental monitoring samples Per the applicable shall be collected pursuant to Table 12.5-1 from the Table(s) specific locations given in the table and figure(s) in the ODCM and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3. 12-57 (p:Xradprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 1 of 5) Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS(a) FREQUENCY TYPE/FREQUENCY OF ANALYSIS SAMPLE 1 Airborne Samples from a total of eight locations: Continuous Radioiodine Canister: Radioiodine and sampler operation 1-131 analysis bi-weeldy on near field Particulates a. Indicator - Near Field with sample samples and control.(b) collection weekly Four samples from locations within 4 (or more frequently Particulate Sampler: km (2.5 mi) in different sectors, if required due to Gross beta analysis following weekly dust loading), filter change(c) and gamma isotopic
- b. Indicator - Far Field analysis(d) quarterly on composite filters by location on near field samples and Three additional locations within 4 to 10 control.(b) km (2.5 to 6.2 mi) in different sectors.
- c. Control One sample from a control location C
within 10 to 30 km (6.2 to 18.6 mi). (continued) (a) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical I Position, Revision 1, November 1979. (b) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Health Physics Support Director. (c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and daughter decay. Ifgross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (d) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. ( 12-58 (p:\radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 2 of 5) Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS(a) FREQUENCY TYPE/FREQUENCY OF ANALYSIS SAMPLE
- 2. Direct Radiation(e) Forty routine monitoring stations either with a Quarterly. Gamma dose on each TLD quarterly.
thermoluminescent dosimeter (TLD) or with one instrument for measuring dose rate continuously, placed as follows:
- a. Indicator - Inner Ring (100 Series TLD)
One in each meteorological sector, in the general area of the SITE BOUNDARY;
- b. Indicator - Outer Ring (200 Series TLD)
One in each meteorological sector, within 6 to 8 km (3.7 to 5.0 mi); and
- c. Other One at each Location given in part 1.a and 1.b.
The balance of the TLDs to be placed at special interest locations beyond the restricted locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access (300 Series TLD).
- d. Control One at each Airborne control location given in part 1 .c.
(continued) (a) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., if a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. 12-59 (p:Xradprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 3 of 5) Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS(a) FREQUENCY TYPE/FREQUENCY OF ANALYSIS SAMPLE
- 3. Waterbome
- a. Ground/Well a. Indicator Quarterly Gamma isotopic(d) and tritium analysis quarterly.
Samples from three sources only if likely to be affected.(f)
- b. Drinking(g) a. Indicator Weekly grab Gross beta and gamma isotopic samples analyses(d) on monthly composite; Some sample from each community tritium analysis on quarterly composite.
drinking water supply that could be affected by the station discharge within 10 km (6.2 mi) downstream of discharge.
- c. Surface Water(g) Ifno community water supply (Drinking Weekly grab Gross beta and gamma isotopic Water) exists within 10 km downstream of samples analyses(d) on monthly composite; discharge then surface water sampling shall tritium analysis on quarterly composite.
be performed.
- a. Indicator One sample downstream.
- d. Control Sample(g) a. Control Weekly grab Gross beta and gamma isotopic samples analyses(d) on monthly composite; One surface sample upstream of tritium analysis on quarterly composite.
discharge.
- e. Sediment a. Indicator Semiannually Gamma isotopic analysis(d) semiannually.
At least one sample from downstream(g) area within 10 km (6.2 mi) distance. (continued) (a) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (d) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (I) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (g) The "downstream" sample shall be taken in an area beyond but near the mixing zone. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough up upstream to be beyond the station influence. 12-60 (p:Xradprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 4 of 5) Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS(a) FREQUENCY TYPE/FREQUENCY OF ANALYSIS SAMPLE
- 4. Ingestion
- a. Milk (h) a. Indicator Biweekly(!) when Gamma isotopic(d) and 1-1310) analysis animals are on on each sample.
Samples from milking pasture (May animals from a maximum of through October), three locations within monthly at other 10 km (6.2 mi) distance, times (November through April).
- b. Control One sample from milking animals at a control location within 15 to 30 km (9.3 to 18.6 mi).
- b. Fish a. Indicator Two times Gamma isotopic analysis(d) on edible annually, portions.
Representative samples of commercially and recreationally important species in discharge area.
- b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.
(continued) (a) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (d) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (h) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling shall be discontinued. (i) Biweekly refers to every two weeks.
- 0) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.
12-61 (p:\radprot\odcm\by1 2R1 -6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-1 (Page 5 of 5) 9C71. Radiological Environmental Monitoring Program SAMPLING AND EXPOSURE NUMBER OF REPRESENTATIVE COLLECTION PATHWAY AND/OR SAMPLES AND SAMPLE LOCATIONS(a) FREQUENCY TYPE/FREQUENCY OF ANALYSIS SAMPLE
- 4. Ingestion (continued)
- c. Food Products a. Indicator Annually. Gamma isotopic(d) analysis on each sample.
Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi): At least one root vegetable sample.(k) At least one broad leaf Vegetable (or vegetation) (k). (I..
- b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).
(a) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-O1 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (d) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (k) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container. ( 12-62 (p:Vadprot\odcm\byl 2R1,-6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-2 (Page 1 of 1) Reporting Levels for Radioactivity Concentrations in Environmental Samples AIRBORNE PARTICULATE FISH (pCi/kg, wet) FOOD ANALYSIS WATER (pCi/i) OR GASES MILK (pCi/l) PRODUCTS (Pci/mn3) (pCi/kg, wet) 20,000(a) H-3 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-1 40 200 300 (a) For drinking water samples. This is 40 CFR Part 141 value. Ifno drinking water pathway exists, a value of 30,000 pCiI may be used. (b) If no drinking water pathway exists, a value of 20 pCi/A may be used. 12-63 (p:\radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-3 (Page 1 of 2) Detection Capabilities for Environmental Sample Analysis(a) Lower Limit of Detection (LLD)(b) (Refer to Note 1, Page 12-65) AIRBORNE PARTICULAT SEDIMENT E OR GAS FISH (pCi/kg, FOOD (pCi/kg, dry) ANALYSIS WATER (pCi/I) (pCi/m3) wet) MILK (pCi/i) PRODUCTS (pCi/kg, wet) Gross Beta 4 0.01 1000 H-3 2000(e) Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 11 5 (c) 0.07 100 0 .5/ 5 (d) 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-1 40 15 15 (a) This list does not mean that only these nuclides are to be considered. Other peaks at are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2. (b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. (c) If no drinking water pathway exists, the value of 15 pCi/I may be used. (d) A value of 0.5 pCi/I shall be used when the animals are on pasture (May through October) and a value of 5 pCi/I shall be used at all other times (November through April). (e) This LLD is the minimum allowable, however, vendors performing environmental sample analyses offsite will be required to meet an LLD of 200 pCi/I. 12-64 (p:\radprot\odcm\by12R1-6.doc)
BYRON Revision 1.6 January 1999 Table 12.5-3 (Page 2 of 2) Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) Note 1: Lower Limit of Detection (LLD) The LLD is defined, for purposes of these Technical Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: Sb LLD -4.66 E *V *2.22* Y
- exp (-2AT)
Where: LLD = the "a priori" lower limit of detection (picoCuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), V= the sample size (units of mass or volume), 2.22 the number of disintegrations per minute per picoCurie, Y= the fractional radiochemical yield, when applicable, I= the radioactive decay constant for the particular radionuclide (sec"), and A= the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and A%should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an 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, 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 pursuant to Technical Specification 5.6.2. 12-65 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.2 Land Use Census 12.5.2.B The Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors (Refer to Note 1, Page 12-68) of the nearest milk animal, the nearest residence (Refer to Note 2, Page 12-68), and a enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence. APPLICABILITY: At all times. ACTIONS NOTES
- 1. TLCO 3.0.c is not applicable.
- 2. TLCO 3.0.d is not applicable.
( CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose or dose A.1 Identify the new location(s) in the 12 months commitment greater than the next Annual Radiological value currently calculated in Environmental Operating Report 12.4.3.A.1 pursuant to Technical Specification 5.6.2. (continued) 12-66 (p:Xradprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 ACTIONS (continued) CONDITION I REQUIRED ACTION I COMPLETION TIME B. Identification of a location B.1 Add the new location(s) to the 30 days that yields a calculated dose Radiological Environmental or dose commitment (via the Monitoring Program (REMP) given same exposure pathway) in the OFFSITE DOSE 20% greater than at a CALCULATION MANUAL location from which samples (ODCM) (Refer to Note 3, Page are currently being obtained, 12-68). in accordance with 12.5.1 .A. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.5.2.8 The Land Use Census (Refer to Note 4, Page 12-68) shall 12 months be conducted during the growing season (01 JUN - 01 OCT). 12-67 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 Note 1: This requirement may be reduced according to geographical limitations; e.g. at a lake site where(. some sectors will be over water. Note 2: The nearest industrial facility shall also be documented if closer than the nearest residence. Note 3: The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 5.5.1.c, submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations. Note 4: The Land Use Census shall use information that will provide the best results, such as by a door to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. (. 12-68 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.3 Interlaboratory Comparison Program 12.5.3.A Analyses shall be performed on radioactive materials, supplied as part of an Interlaboratory Comparison Program that corresponds to samples required by Table 12.5-1. APPLICABILITY: At all times. ACTIONS NOTES
- 1. TLCO 3.0.c is not applicable.
- 2. TLCO 3.0.d is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses NOT being A.1 Report the corrective actions to 12 months performed per Table 12.5-1. preclude recurrence in the Annual Radiological Operating -Report to the Commission pursuant to Technical Specification 5.6.2. 12-69 (p:\radprot\odcm\byl 2R1-6.doc)
BYRON Revision 1.6 January 1999 C-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 12.5.3.B Summarize the results obtained as part of the 12 months Interlaboratory Comparison Program in the Annual Radiological Environmental Operating Report to the Commission pursuant to Technical Specification 5.6.2. (. 12-70 (p:\radprot\odcm\byl2R1-6.doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating Report* Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted prior to May 15 of each year. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period
,pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.
*A single submittal may be made for a multiple unit station.
12-71 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.1 Annual Radiological Environmental Operating Report (Cont'd) The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190; "Environmental Radiation Protection Standards for Nuclear Power Operation." 12-72 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.2 Annual Radioactive Effluent Release Report** Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted prior to May 1 of the following year. The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde). The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the POP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3. The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of ITS 5.5.12. A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. 12-73 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.3 Offsite Dose Calculation Manual (ODCM) 12.6.3.1 The ODCM shall be approved by the Commission pror to implementation. 12.6.3.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by UFSAR Chapter 17. This documentation shall contain:
- 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s); and
- 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the Independent Technical Review and PORC and the approval of the Plant Manager on the date specified by the Independent Technical Review and PORC.
- c. Shall be submitted to the Commission in the form of the complete, legible copy of the entire ODCM, or updated pages if the Commission retains a controlled copy. If an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Annual Radioactive ..
Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented. 12-74 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.6 January 1999 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.4 Major Changes to Liquid and Gaseous Radwaste Treatment Systems*** Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Independent Technical Review and PORC. The discussion of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
- 4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto;
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by the Independent Technical Review and PORC.
- b. Shall become effective upon review and acceptance by the Independent Technical Review and PORC.
***Licensees may choose to submit the information called for in this standard as part of the annual FSAR update.
12-75 (p:\radprot\odcm\byl 2R1 -6.doc)
BYRON Revision 1.3 March 1996 BYRON ANNEX INDEX PAGE REVISION PAGE REVISION APPENDIX F F-i 1.3 F-43 1.3 F-l 1.3 F-44 1.3 F-iv 1.3 F-45 1.3 F-1 1.3 F-46 1.3 1.3 F-47 1.3 1.3 F-3 1.3 F-4 1.3 F-5 1.3 F-6 1.3 F-7 1.3 F-8 1.3 F-9 1.3 F-10 1.3 F-11 1.3 F-12 1.3 F-13 1.3 F-14 1.3 F-15 1.3 F-16 1.3 F-17 1.3 F-18 1.3 F-19 1.3 F-20 1.3 F-21 1.3 F-22 1.3 F-23 1.3 F-24 1.3 F-25 1.3 F-26 1.3 F-27 1.3 F-28 1.3 F-29 1.3 F-30 1.3 F-31 1.3 F-32 1.3 F-33 1.3 F-34 1.3 F-35 1.3 F-36 1.3 F-37 1.3 f:-38 1.3 F-39 1.3 F-40 1.3 F-41 1.3 F-42 1.3 F.j
BYRON Revision 1.3 March 1996 APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS I AND 2 TABLE OF CONTENTS F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 (7 CA;;
BYRON Revision 1.3 March 1996 APPENDIX F UST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F-4 F-3 Critical Ranges F-5 F-4 Average Wind Speeds F-6 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-7 F-5a X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary " F-8 F-6 DlQ at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-9 F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-1 0 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F-25 Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries - 250 and 30 Foot Elevation Data F-40
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distribution Table Summaries F-44
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class F-I16
BYRON Revision 1.3 March 1996 APPENDIX F LIST OF FIGURES NUMBER LEAGE F-1 Unrestricted Area Boundary F-46 F-2 Restricted Area Boundary F-47
BYRON Revision 1.3 March 1996 APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the Byron site. Included is a figure showing the unrestricted area boundary and values of parameters used In offsite dose assessment. Dose factors are changed from previous revisions only If a higher value is justified based on new census data. Nearest resident, milk cow, and meat animal ranges are changed from previous revisions only If a more conservative value is justified based on new census data. Original tables were based upon the 1993 Annual Land Use Census performed by Teledyne Isotopes Midwest Laboratories. F.2 REFERENCES "1. Sargent & Lundy, Analysis and Technology Division Byron Calculation No. ATD-0150, Revisions 0, 1, and 2.
- 2. "Irrigation from the Rock River" letter from G.P. Lahti (Sargent & Lundy) to J.C. Golden (NSEP), June 4, 1990.
- 3. "Verification of Environmental Parameters used for Commonwealth Edison Company's Offskte Dose Calculations," NUS Corporation, 1988.
- 4. "Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group, 1992.
F.1
BYRON Revision 1.3 March 1996 Table F-I Aquatic Environmental Dose Parameters General Information" There are no pubic potable water intakes on the Rock River downstream of the station. There is no Irrigation occurring on the Rock River downstream of the station. K, aduuiu ;COM,00 wilt$ W, 1-1-,ui6 .* ul e ,,;*
'gu u - :io IIIg, Wi ,ua itj, tswifluIi ,iiJ, baiu SPIL uishlrmg.
According to Section 2.4.1.2 and Figure 2.4-5 of the Byron Environmental Report, there are four downstream dams on the Rock River within approximately 50 miles of the station one at Oregon, Dixon, and two at Sterling. Water and Fish Innestion Parameters Parameterb Value MW, VW 1.0 Fw, cfs." 6.55E4 F, cfs 6.25E3 tf. hre 24.0 f", hrd 115 Urnits on Radioactivity in UnDrotected Outdoor Tanks Outside Temporary Tank < 10 Cr (per Technical Specification 3.11) .. a This is based on information in the Byron Environmental Report, Figure 3.3-1 and Section 2.1.3.2.1. b The parameters are defined in Section A.2.1 of Appendix A. t' (hr) = 24 hr (all stations) for the fish ingestion pathway Ir -r. 41.
BYRON Revision 1.3 March 1996 Table F-I (Conrd) Aquatic Environmental Dose Parameters Notes (Cont'd): Ct (hr) w 115 hr (Rock River flows into Mississippi River about 115 miles downstream of the station at the rate of 1 mph based on the data in Table 2.2-5 of the Byron Station Environmental Report). See Section A.2.4 of Appendix A. Tritium and dissolved or entrained noble gases are excluded from this limit. F-3
BYRON Revision 1.3 March 1996 Table F-2 Station Characteristics STATION: Byron LOCATION: 3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not applicable (NA)
- 1) Release Height -= m 2) Diameter = m
- 3) Exit Speed = ms" 4) Heat Content = KCal S"-"
CHARACTERISTICS OF VENT STACK RELEASE POINTS*
- 1) Release Height - 60*66 m" 2) Effective Diameter = 2.80 m
- 3) Exit Speed - 13_00 ms"a "The station has two adjacent rectangular vent stack release points of the same height and cross section. Their centers are 15.01 m apart. (
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Building Factor (D) , 60.6 m METEOROLOGICAL DATA A 250 ft Tower is located 1036 m SW of vent stack release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA)
Vent 250 ft 250 - 30 Ground 30 ft 250 - 30 ft "Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.
BYRON Revision 1.3 March 1996 Table F-3 Critical Ranges Unrestricted Area Restricted Nearest Nearest Dairy Farm I Boundary* Area Boundary Residente Within 5 Milesb Direction (m) - (mL (m) N 1875 777 4300 None 1829 538 1600 None NNE 4nnf%
. 1 IGG,; ,nnfn 1234 474 2100 None ENE 1227 468 2100 None E
991 480 2300 None ESE SE 1006 427 1200 None SSE 80 410 1000 None 945 295 800 7700 IS SSW 975 299 1000 None SW 1067 451 1200 None WSW 1212 386 2700 None 2700 4000 1w 1189 379 1200 5300 WNW 1227 385 1128 -445 1600 4800 NW NNW 1044 658 2100 None "See Updated Final Safety Analysis Report Table 2.1-la and Environmental Report. Used In calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B. b The distances are rounded to the nearest conservative 100 meters. F-5
BYRON Revision 1.3 March 1996 Table F-4 Average Wind Speeds Avemae Wind Speed (misec" Downwind Direcion Elevatedb Mixed Mode Ground Levei N 7.9 6.3 4.2 NNE 7.6 6.3 4.5 NE 6.8 5.8 4.1 ENE 6.6 5.6 4.0 E 6.9 5.9 4.5 ESE 6.9 5.9 4.5 SE 6.5 5.7 4.0 SSE 6.2 5.4 3.7 S 6.3 5.4 4.0 SSW 6.0 5.3 3.9 SW 6.1 5.4 4.2 WSW 6.4 5.6 4.1 W 6.8 5.5 3.4 WNW 7.1 5.7 3.7 NW 7.1 5.7 3.8 NNW 7.7 6.0 4.1 OBased on Byron site meteorological data, January 1978 through December 1987. Calculated in Reference 2 of Section F.2 using formulas in Section B.1.3 of Appendix B. bThe elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values. l "z,
SBYRON (evision 1.3 March 1996 Table F-5 XIQ and DIQ Maxima at or Beyond the Unrestricted Area Boundary Downwind Mixed Mode(Vent) Retease Ground Levet Release Direction Radius X/Q Radius D/O Radius X/Q D/O (meters) (sec/m**3) (meters) (1/m**2) (meters) (secllm**3) (1/I**2) N 1875. 1.988E-07 1875. 1.983E-09 1875. 8.676E-07 4.671E-09 NNE 1829. 1.6771-07 1829. 1.927E-09 1829. 7.5311-07 4.2711-09 NE 1585. 1.530E-07 1585. 1.821E-09 1585. 7.876E-07 4.388E-09 ENE 1234. 1.353E-07 1234. 1.764E-09 1234. 8.808E-07 5.036E-09 E 1227. 1.688E-07 1227. 2.335E-09 1227. 1.143E-06 6.226E-09 ESE 991. 2.519E-07 991. 3.540E-09 991. 1.692E-06 9.896E-09 SE 1006. 3.020E-07 1006. 3.578E-09 1006. 2.480E-06 1.1181-08 SSE 800. 4.497E-07 800. 3.761E-09 800. 4.152E-06 1.420E-08 S 945. 2.2491-07 945. 2.792E-09 945. 1.946E-06 9.364E-09 SSW 975. 1.476E-07 975. 1.970E-09 975. 1.305E-06 6.672E-09 SU 1067. 1.148E-07 1067. 1.786E-09 1067. 9.279E-07 5.316E-09 WSW 1212. 1.199*-07 1212. 1.903E-09 1212. 7.646E-07 5.002E-09 V 1189. 1.758E-07 1189. 1.870E-09 1189. 9.348E-07 5.330E-09 WNW 1227. 1.205E-07 1227. 1.292E-09 1227. 6.543E-07 3.745E-09 MW 1128. 1.686E-07 1128. 1.719E-09 1128. 8.807E-07 4.984E-09 NNW 1044. 3.047E-07 1044. 3.223E-09 1044. 1.432E-06 8.871E-09 Byron Site Meteorotogicat Data 1/78 - 12187 Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B. X/Q is used for beta skin, and inhalation dose pathways. See Sections A.1.2, A.1.3, and Ak.1.4.2 of Apprendix.A. D/Q Is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A. The ground level release date are provided for reference purposes only. Routine dose calb-ulations are performed using mixed mode data. Radius Is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/Q at or beyond the unrestricted area boundary (MAB). F-7
Revision 1.3 March 1996 Table F-h8 XIQ and DIQ Maxima at or Beyond the Restricted Area Boundary Nixed Node(Vent) Release Oround Level Release Dowowind XIQ DIG Direction Radius X/O Radius 0/0 Radius (meters) (seclW*3) (110"2) (meters) (seeil"3) (meters) (1I/m*2) 6.35?E-07 TM7. 7.004E-09 777. 3.290E-06 2.036E-08 N 777. 538. 5.T77E-07 538. 1.046E-08 538. 5.086E-06 3.193E-08 NNE 528. 4.3T1E-06 2.6461-08 NE 528. 6.803E-07 528. 1.792M-09 474. 5.341E-07 474. 5.94TE-09 474. 4.0141-06 2'.346E-08 ENIE 5.359E-06 2:.9301-08 468. 6.6981-07 468. 7.930E-09 468. E 5.434E-06 3.144E-08 480. 7.3771-07 480. 8.963E-09 480. ESE 427. 1.024E-05 4.352E-08 SE 427. 1.126E-06 427. 1.063E-08 1.3491-06 410. 8.74E-09 410. 1.305E-05 4.044E-08 SSE 410. 1.3911-05 .;.771-08 S 295. 1.4411-06 295. 1.171E-08 295. 9.3823-07 299. 8.293E-09 299. 9.3T6E-06 4,.197-08 SSWl 299. 3.949E-07 451. 9.065E-09 451. 3.666E-06 ;.095E-08 SW 451. 6.0981-07 386. 7.4251-09 386. 4.699E-06 .1.0881-08 11311 386. 1.041E-06 379. 8.1161-09 379. 6.009E-06 31.2751-08 11 379. 7.4541-07 385. 6.081E-09 385. 4.382E-06 3.370E-08 V"K 385. 445. 7.394E-07 445. 6.1171-09 445. 4.068E-06 1.1984-08 NW 2.980E-06 1.8T4E*-O 658. 6.123E-07 658. 6.1771-09 658. lNW Byron Site Meteorological Date 1/78 - 12/8T In Sections B.3 and 5.4 of Appendlit B. Note: Based on Reference 2 of Section F.2 and the formulas using mixed mode level release data are provided for reference purposes only. Routine dose caklulations are performed The ground data. of highest X/Q or 13Q at between gaseous effluent release points to the location Radius Is the approximate distance from the midpoint or beyond the restricted area boundary (RAB). F-8
b..iON ReviL 1.3 March 1996 Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles Nearest Milk Cow D/Q(1/m**2) Nearest Meat Animal D/Q(I/m**2). Downwind Ground Radius Mixed Ground Direction Radius Mixed (meters) Release Release (meters) Release Release 8000 1.895E-10 3.643E-10 4800 4.499E-10 9.079E-10 2.677E-09 N 2400 1.282E-09 8000 1.835E-10 3.192E-10 5.027E-10 NNE 5500 2.799E-10 3000 7.187.E-10 1.462E-09 7.603E-10 NE 3700 3.792E-10 8000 1.096E-10 1.928E-10 9.770E-10 ENE 3600 5.164E-10 8000 1.417E-10 2.361 E-1 0 2.209E-09 E 2400 1.082E-09 8000 1.614E-10 2.635E-10 2.085E-09 ESE 2700 9.439E-1 0 8000 1.698E-10 3.050E-1 0 5.968E-1 0 SE 5100 2.923E-1 0 SSE 8000 1.387E-10 2.664E-10 1.014E-08 900 2.967E-09 7700 1.381E-10 2.477E-1 0 7.563E-1 0 S 3500 3.645E-10 8000 9.795E-1 1 1.729E-10 3.574E-10 SSW 5100 2.006E-10 8000 9.554E611 1.596E-10 1.270E-09 SW 2700 6.571E-10 8000 1.202E-1 0 1.858E-10 1.310E-09 WSW 2700 5.945E-10 4000 3.281 E-10 6.590E-1 0 2.968E-10 IW 5300 1.464E-10 5300 1.464E-10 2.968E-1 0 2.674E-1 0 WNW 1.339E-10 SNW 4800 1.978E-10 4.088E-10 2.571 E-1 0 6100 2200 1.092E-09 2.596E-09 NNW 8000 1.349E-10 Byron Site Meteorological Data 1/78 - 12/87 B. Note: Based on Reference 2 in Section F.2 and the formulas in Section B.4 of Appendix Approximate distance from the station as determined by annual census. The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode release data. F-9
BYRON Revision 1.3 March 1996
*v.
Table F-7 Area Boundary for Kr-83m Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Downwind Unrestricted Nixed Node(Vent) Release Grotard Level a Release GBAR Direction Area Bound Radius V VYAR Radius (mrad/yr)/(uC1/sIc) (meters) (meters) (mrad/yr)/CuCl/sc) (meters) 9.565E-05 7.212E-05 N 1875. 1875. 2.330E-05 1.757E-05 1875. 1829. 8.084E-05 6.095E-05 NNE 1829. 1829. 1.937E-05 1.460E-05 1.773-E05 1.336E-05 1585. 8.469E-05 6.386E-05 NE 1585. 1585. 1.672E-05 1.260E-05 1234. 1.002E-04 7.555E-05 ENE 1234. 1234. 1227. 2.049E-05 1.545E-05 1227. 1.252E-04 9.441E-05 E 1227. 991. 1.925E-04 1.451E-04 ESE 991. 991. 3.142E-05 2.369E-05 SE 3.694E-05 2.785E-05 1006. 2.683E-04 2.023E-04 1006. 1006. SSE 800. 5.135E-05 3.872E-05 800. 4.267E-04 3.217E-04 800. 945. 2.121E-04 1.600E-04 S 945. 945. 2.723-E05 2.053E-05 SSW 975. 1.795E-05 1.353E-05 975 1.407E-04 1.061E-04 975. 1067. 9.817E-05 7.402E-05 1067. 1067. 1.379E-05 1.040E-05 SW 1.483E-05 1.118E-05 1212. 8.590E-05 6.477E-05 1212. 1212. W 2.193E-05 1.654E-05 1189. 1.100E-04 8.293E-05 1189. 1189. 1.514E-05 1.141E-05 1227. 7.802E-05 5.883E-05 WNW 1227. 1227. 2.112E-05 1.593E-05 1128. 1.033E-04 7.789E-05 NW 1128. 1128. 3.852E-05 2.904E-05 1044. 1.691E-04 1.275E-04 NNW 1044. 1044. Byron Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. Approximate distance from midpoint between gasous effluent release points. F-1O
SBYRON revision 1.3 March 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Downwind Unrestricted Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius a GBAR (meters) (meters) Curad/yr)/(uCflsec) (meters) (mrad/yr)/(uCl/aec) N 1875.. 1875. 2.177E-04 2.094E-04 1875. 6.403E-04 6.143E-04 NNE 1829. 1829. 2.076E-04 1.999M-04 1829. 5.544E-04 5.319E-04 HE 1585. 1585. 2.022E-04 1.9471-04 1585. 5.773E-04 5.539E-04 ENE 1234. 1234. 1.9841-04 1.911E-04 1234. 6.395E-04 6.133E-04 E 1227. 1227. 2.331E-04 2.245E-04 1227. 7.9685-04 7.6405-04 ESE 991. 991. 3.260E-04 3.138E-04 991. 1.136E-03 1.0881-03 9E 1006. 1006. 3.7101-04 3.571E-04 1006. 1.584E-03 1.5171-03 SSE 800. 800. 4.393E-04 4.223E-04 800. 2.2735E03 2.1754-03 S 945. 945. 2.8131-04 2.708W-04 945. 1.2401-03 1.1881-03 SSia 975. 975. 2.079E-04 2.0021-04 975. 8.6315-04 8.272E-04 SW1 1067. 1067. 1.688-04 1.6274-04 1067. 6.286E-04 6.0271-04 WSW 1212. 1212. 1.7515-04 1.6871-04 1212. 5.594E-04 5.366E-04 v 1189. 1189. 2.092E-04 2.013E-04 1189. 6.723E-04 6.446E704 UNW 1227. 1227. 1.464E-04 1.409M-04 1227. 4.690E-04 4.4961-04 NU 1128. 1128. 1.926E-04 1.852E-04 1128. 6.017*-04 5.766E-04 NNW 1044. 1044. 3.126E-04 3.005E-04 1044. 9.676E-04 9.272n-04 Byron Site Meteorological Data 1/78 - 12/87 F-Il
BYRON Revision 1.3
- 7' March 1996 Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestrlcted Area Boundary for Kr-86 Downwind Unrestricted Mixed Node(Vent) Relesse Ground Level Release Direction Area Bound Radius V VSAR Radius a GUAN (meters) (meters) (mrad/yr)/(uCl/*ec) (meters) (mrad/yr)I(uCi/sec ) N 1875. 1875. 2.53SE-06 2.452E-06 1875. 7.318E-06 7.0T7E-16 NINE NE 1829. 1829. 2.469E-06 2.388M-06 1829. 6.3821-06 6.1TIE-04 ENE 1585. 1585. 2.415E-06 2.335E-06 1585. 6.622E-06 6.403E*-6 E 1234. 1234. 2.3671-06 2.2891-06 7.225E-06 6.986E-(6 1227. 1227. 2.781E-06 2.695E-06 1234. ESE 1227. 9.101E-06 8.801E-06 SE "991. "991. 3.828E-06 3.702E-06 "991. 1.27OE-05 1.2283-15 1006. 1006. 4.3641-06 4.220E-06 1006. 1.8031-05 1.7431-15 SSE 800. 800. 5.153E-06 4.983E-06 800. S 2.5773-05 2.492E-'05 945. 945. 3.3211-06 3.211E-06 945. 1.404E-OS 1.358E-CJ SSW 975. 975. 2.493E-06 2.411E-06 975. 9.86911-06 9.5439-[*[6 St/ 1067. 106?. 2.018E-06 1.51E-06 1067. .7.232E-06 6.993ME SW 1212. 1212. 2.070E-06 2.002E-06 1212. 6.309M-06 6.100E-i:6 1189. 1189. 2.436E-06 2.356E-06 1189. 7.4T2E-06 7.225E-I:6 1227. 1227. 1.708E-06 1.652E-06 1227. 5.191E-06 5.019E-C6 NW 1128. 1128. 2.238E-06 2.164E-06 1128. 6.678E-06 6.458E-C6 RUM 1044. 1044. 3.579E-06 3.461E-06 1044. 1.07IE-05 1.036E-11S Byron Site Meteorological Data 1/78 - 12/87 F-12
-Th
BYRON
.ievision 1.3 March 1996 Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Urn restricted Area Boundary for Kr-87 Downwind Unrestricted Mixed Node(Vent) Release ground Level Relisse Direction Area Bound Radius V VBAR Radius 0 GSRA (meters) (meters) (mrad/yr)/CuCIsec) (meters) (mrad/yr)/(tCI/sec) N 1875. 1875. 7.122E-04 6.916E-04 1875. 1.811E-03 1.758E-03 NlNE 1829. 1829. 6.8911-04 6.692E-04 1829. 1.555E-03 1.510E-03 NE 1585. 1585. 6.817E-04 6.620E-04 1585. 1.622E-03 1.574E-03 ENE 1234. 1234. 6.838E-04 6.641E-04 1234. 1.822E-03 1.769E-03 E 1227. 122?. 7.930E-04 7.701E-04 1227. 2.214E-03 2.149E-03 ESE "991. 991. 1.126E-03 1.094E-03 "991. 3.256E-03 3.162E-03 SE 1006. 1006. 1.264E-03 1.22?E-03 1006. 4.3561-03 4.229E-03 SSE 800. 800. 1.455E-03 1.413E-03 800. 6.185E-03 6.005E-03
$ 945. 945. 9.680E-04 9.401E-04 945. 3.451E-03 3.350E-03 SSW
'SW 975. 975. 7.216E-04 7.008E-04 975. 2.3741-03 2.305E-03 1067. 106?. 5.921E-04 5.756E-04 1067. 1.7255-03 1.675E-03 WI 1212. 1212. 6.1321-04 5.955E-04 1212. 1.613E-03 1.566E-03 1189. 1189. 7.081E-04 6.8T7l-04 1189. 1.971E-03 1.914E-03 1227. 1227. 4.978E-04 4.834E-04 122?. 1.381E-03 1.341E-03 Nu 1128. 1128. 6.5175-04 6.329E-04 1128. 1.7531-03 1.702E-03 NW 1044. 1044. 1.040E-03 1.010E-03 1044. 2.8261-03 2.744E-03 Byron Site Meteorological Oata 1/78 - 12/8?
F-13
BYRON Revision 1.3 March 1996 Table F-7 (Continued) Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Doenwind Unrestricted Mixed Hode(Vent) Retease ground Level Retesse Direction Area Bound Radius V VBAR Radius a OSAR (meters) (meters) (urad/yr)l(uCllsec) (meters) (wesd/yr)l(uCtl8et-) N 1875. 1875. 1.781E-03 1.732E-03 1875. 4.631E-03 4.499E,0 NNE 1829. 1829. 1.744E-03 1.696E-03 1829. 4.012E-03 3.898103 NE 1585. 1585. 1.725E-03 1.677E-03 1585. 4.174E-03 4.056E1,03 ENS 1234. 1234. 1.721E-03 1.674E-03 1234. 4.617E-03 4.4851E 03 E 1227. 122T. 2.008E-03 1.952E-03 1227. 5.701E-03 5.5381E03 ESE "991. "991. 2.794E-03 2.71TE-03 991. 8.165E-03 7.931E1-03 SE SSE 1006. 1006. 3.153E-03 3.066E'03 1006. 1.124E-02 1.092E02 800. 800. 3.656E-03 3.554E-03 800. 1.601E-02 1.555E-02 S 945. 945. 2.414E-03 2.345E-03 945. 8.831E-03 8.577T03 WSW 975. 975. 1.821E-03 1.T71E-03 975. 6.146E-03 5.9701"03 1067. 106T. 1.486E-03 1.445E-03 1067. 4.4881-03 4.3601..03 W 1212. 1212. 1.525E-03 1.483E-03 1212. 4.060E-03 3.944E03 1189. 1189. 1.7561-03 1.707E-03 1189. 4.882E-03 4.743E..03 WNW 1227. 1227. 1.235E-03 1.201E-03 3.406E-03 3.3091.03 NU 1128. 1128. 1.611E-03 1.567E-03 1128. 4.344E-03 4.2191.03 NNW 1044. 1044. 2.548E-03 2.47M5-03 1044. 6.9741-03 6.773. 03 Byron Site Meteorotolicet Date 1/78 - 12187 F-14
*BYRON ýevision 1.3 March 1996 Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Usirestricted Area Boundary for Kr-89 Downwind Unrestricted Mixed Node(Vent) Release around Level Release V VWAR Radius a SOAR Direction Area Bound Radius (meters) (mred/yr)/(uCt/sec) (meters) (meters) (mred/yr)/(uCl/sec) N 1875. 1875. 3.874E-04 3.764E-04 1875. 5.119E-04 4.972E-04 NNE 1829. 1829. 3.9171-04 3.805E-04 1829. 4.514E-04 4.384E-04 ME 1585. 1585. 4.092E-04 3.975E-04 1585. 4.994E-04 4.851E-04 ENlE 1234. 1234. 4.909E-04 4.769E-04 1234. 7.066E-04 6.863E-04 E 1227. 1227. 5.876E-04 5.709E-04 1227. 8.980E-04 8.7231-04 ESE 991. 991. 1.001E-03 9.729E-04 991. 1.662E-03 1.614E-03 1006. 1006. 1.052E-03 1.022E-04 1006. 1.834E-03 1.7821-03 SE SSE 800. 800. 1.274E-03 1.237E-03 800. 2.736E-03 2.6571-03 S 945. 945. 8.388E-04 8.149E-04 945. 1.633E-03 1.586E-03 975. 975. 6.103E-04 5.9291-04 975. 1.1381-03 1.105E-03 1067. 1067. 4.8T7E-04 4.738E-04 1067. 8.395E-04 8.154E-04 1212. 1212. 4.7481-04 4.612E-04 1212. 7.5701E-04 7.353E-04 1189. 1189. 5.142E-04 4.995E-04 1189. 8.4901-04 8.24E-04 WNW 3.5901-04 3.488E-04 1227. 5.905E-04 5.735E-04 1227. 1227. IN 1128. 5.2051-04 5.0571-04 1128. 8.806E-04 8.553E-04 1128. NNW 1044. 1044. 9.4081-04 9.139E-04 1044. 1.7381-03 1.688E-03 Byron Site Neteorotoglcel Deta 1/78 - 12/87 F-15
BYRON Revision 1.3 March 1996 'II Table F-7 (Continued) Maximum OffsIte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Downwind Unrestricted Mixed Node(Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius 0 GBAR (maters) (maters) (mrad/yr)/(uCi/sec) (meters) (mradfyr)/(uCI/iec) N 1875. 1875. 5.72E9-06 5.558E-06 1875. 2.4991-06 2.423E-06 NNE 1829. 1829. 6.704E-06 6.504E-06 1829. 3.5501-06 3.443E-06 NE 1585. 1585. 8.897E-06 8.631E-06 1585. 5.093E-06 4.939E-06 ENE 1234. 1234. 2.065E-05 2.004E-05 1234. 1.415E-05 1.372E-05 E 122?. 1227. 3.1115-05 3.0181-05 1227. 2.640E-05 2.560t-05 ESE "991. "991. 8.428E-05 8.175E-05 991. 7.903E-05 7.663i-05 SE 1006. 1006. 7.483E-05 7.259E-05 1006. 6.589E-05 6.389E-05 SSE 800. 800. 1.281E-04 1.242E-04 800. 1.3671E-04 1.325E-04 S 945. 945. 6.382E-05 6.191E-05 945. 6.374E-05 6.181E-05 SSWp 975. 975. 4.060E-05 3.9381-05 975. 3.621E-05 3.511E-05 Sw 1067. 1067. 2.851E-05 2.765E-05 1067. 2.698E-05 2.616E- 05 WSW 1212. 1212. 2.087E-05 2.025E-05 1212. 1.563E-05 1.516E-05 W 1189. 1189. 2.105E-05 2.042E-05 1189. 8.775E-06 8.509E-06 WNW 1227. 1227. 1.541E-05 1.495E-05 1227. 8.279E-06 8.0281E06 NW 1128. 1128. 2.698E-05 2.618E-05 1128. 1.614E-05 1.565E 05 NEW 1044. 1044. 6.070E-05 5.888E-05 1044. 4.455E-05 4.3201-05 Byron Site Meteorological Data 1/78 - 12/87 F-16
-Th
SBYRON B Oevision 1.3 March 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrstricted Area Boundary for Xe-131m Downwind Unrestricted Mixed Node(Vont) Retease Oround Level Reeasest Direction Area Bound Radius V VBAR Radius a CHAR (moters) (raters) (wred/yr)/(uCilsec) (meters) (mrad/yr)/(ust,'sec) N 1875. 1875. 2.3851-05 1.8971-05 1875. 9.75TE-05 7.6!;0E-05 NHE 1829. 1829. 2.062E-05 1.650E-05 1829. 8.424E-05 6.608E-05 NE 1585. 1585. 1.931E-05 1.548E-05 1585. 8.807E-05 6.916E-05 ENE 1234. 1234. 1.8141-05 1.458E-05 1234. 1.003E-04 T.8!;0E-05 E 122T. 1227. 2.206E-05 I.TOE-05 1227. 1.2901-04 1.0119E-04 ESE "991. 991. 3.255E-05 2.600E-05 "991. 1.885E-04 1.4'2E-04 SE 1006. 1006. 3.838E-05 3.061E-05 1006. 2.7411-04 2.1";9E-04 SSE 800. 800. 5.2875-05 4.185E-05 1800. 4.3081-04 3.3;1E-0o4 S 945. 945. 2.861E-05 2.284E-05 945. 2.140E-04 1.6s'0E-04 SSW 975. 975. 1.939E-05 1.557E-05 975. 1.451E-04 1.12;4E-04 SW 1067. 1067. 1.511E-05 1.216E-05 1067. 1.030E-04 8.0(,0E-05 1212. 1212. 1.568E-05 1.261E-05 1212. 8.542E-05 6.6S'4E-05 VII 1189. 1189. 2.220E-09 1.768E-05 1189. 1.056E-04 8.2t2E-05 1227. 1227. 1.534E-05 1.2221-05 1227. 7.423E-05 5.(1'6E-05 NW 1128. 1128. 2.1191-05 1.684E-05 1128. 9.904E-05 7.7!;6E-05 NNW 1044. 1044. 3.7491-05 2.966E-05 1044. 1.6101-04 1.2!;7E-04 Byron Site Neteorological Date 1/78 - 12/87 F-17
BYRON Revision 1.3 March 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Downwind Unrestricted Mixed Mode(Vent) Release around Level Release VBAR Radius 0 G081 Direction Area sound Radius V (meters) (wad/yr)/(uCWi/iec) (meters) (meters) (w'ed/yr)/(uCI/sec) N 1873. 1875. 5.052E-05 4.463E-05 1873. 1.T779-04 1.53(4-04 1829. 1829. 4.621E-05 4.113E-05 1829. 1.541E-04 1.331E-04 NNE 1.606E-04 1.38VE-04 NE 1585. 1585. 4.420E-05 3.946E-05 1585. 1234. 1234. 4.244E-05 3.T990-05 1234. 1.7999-04 11.5411-04 ENE 2.292E-04 1.971E-04 E 1227. 1227. 5.0721-05 4.530E-05 1227. ESE "991. "991. 7.221E-05 6.419E-05 "991. 3.291E-04 2.8211-04 1006. 1006. 8.369E-05 7.422E-05 1006. 4.733E-04 4.0411-04 SE 6.0811E-04 SSE 800. 800. 1.0681-04 9.3701-05 800. 7.166E-04 945. 945. 6.2951-05 5.5891-05 945. 3.6931-04 3.15E-04 S 2.1*i-04 SSW 975. 975. 4.488E-05 4.011E-05 975. 2.539E-04 1067. 3.574E-05 3.2031-05 1067. 1.825E-04 1.561?E-04 Sm 1067. 1.549E-04 1.336E-04 1212. 1212. 3.6971-05 3.312E-05 1212. WSW' 1189. 1.883E-04 1.6199M-04 1189. 1189. 4.7611-05 4.218E-05 1227. 1227. 3.316E-05 2.9371-05 1227. 1;318E-04 1.13:1-04 NW 1128. 4.462E-05 3.9381-05 1128. 1.731E-04 1.48#E-04 1128. 2.397E NNW 1044. 1044. 7.543E-05 6.613E-05 1044. 2.8009-04 Byron Site Meteorological Date 1178 - 12/87 F-I18
BYRON ,evislon 1.3 March 1996 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Uniestricted Area Boundary for Xe-I33 Downwind Unrestricted Mixed Node(Vent) Release Oround Level Releaase Direction Area Bound Radius V VBAR Radius 0 SOAR (meters) (meters) (mrad/yr)/(uCl/sec) (meters) (m-ad/yr)/(ul/sec) N 1875. 1875. 5.651E-05 5.145E-05 1875. 2.014E-04 1,806E-04 NNE 1829. 1829. 5.150E-05 4.714E-05 1829. 1.746E-04 1,566E-04 NE 1585. 1585. 4.921E-05 4.513E-05 1585. 1.820E-04 1,631E-04 ENE 1234. 1234. 4.702E-05 4.3201-05 1234. 2.030E-04 1.816E-04 E 1227. 1227. 5.610E-05 5.145E-05 1227. 2.582E-04 2.306E-04 ESE 991. 991. 7.996E-05 7.309E-05 991. 3.684E-04 3.281E-04 SE 1006. 1006. 9.261E-05 8.450E-05 1006. 5.287E-04 4.702E-04 SSE 800. 800. 1.173E-04 1.061E-04 800. 7.899E-04 6.981E-04 S 945. 945. , 6.9501-05 6.3471-05 945. 4.122E-04 3.665E-04 SSWE 975. 975. 4.942E-05 4.534E-05 975. 2.848E-04 2,538E-04 SW 1067. 1067. 3.944E-05 3.627E-05 1067. 2.054E-04 1.,834E-04 WSW 1212. 1212. 4.094E-05 3.764E-05 1212. 1.751E-04 1.5691-04 I 1189. 1189. 5.29SE-05 4.825E-05 1189. 2.119E-04 1.893E-04 WNW 1227. 1227. 3.679E-05 3.354E-05 1227. 1.481E-04 1,,322E-04 NI( 1128. 1128. 4.943E-05'4.494E-05 1128. 1.938E-04 1.,726E-04 NNW 1044. 1044. 8.376E-05 7.580E-05 1044. 3.130E-04 2,,86-04 Byron Site Meteorological Date 1/78 - 12/87 F-19
BYRON Revision 1.3 March 1996 f I.,
*v. Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Xe-135m DowwInd Unrestricted Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius V VAR Re Ilug a PAR (metrls) (meters) (eradlyr)l(Clucis) (m tars) (mradfyr)I;uClIlec) 1875. 1875. 3.355E-04 3.238E-04 Ii875. 7.S74E-04 7.301E-04 "NI N 829. 6.353E-04 6.124E-04 NNE 1829. 1829. 3.191*-04 3.080E-04 NE 1585. 1585. 3.171E-04 3.061E-04 585. 1:, 6.6451-04 6.4061-04 ENE 1234. 1234. 3.275E-04 3.162E-04 1;234. 7.919E-04 7.633E-04 E 1227. 1227. 3.794E-04 3.663E-04 227. 9.3821-04 9.0431-04 991. 5.7223-04 5.524E-04 1;991. 1.5021-03 1.448E-03 ESE 991. 1006. 1006. 6.2803-04 6.062E-04 006. 1.826E-03 1.759E-03 SE 800. 2.546E-03 2.452E-03 SSE 800. 800. 7.1391-04 6.889E-04 945. 4.850E-04 4.682E-04 1'945. 1.505E-03 1.450E-03 IS 945.
.975. 975. 3.539E-04 3.416E-04 975. 1.019E-03 9.817E-04 SSW 067. 7.3M63-04 7.111E-04 St/ 1067. 1067. 2.924E-04 2.823E-04 1212. 3.058E-04 2.952E-04 1(212. 7.396E-04 T.129E-04 1212. 1;189.
1189. 1189. 3.530E-04 3.407E-04 9.316E-04 8.976E-04 2.475E-04 2.389E-04 122T. 6.545E-04 6.307E-04 122T. 1227. 1;128. Nu* 1128. 1128. 3.325E-04 3.208E-04 8.492E-04 8.183E-04 NNW 1044. 1044. 5.542E-04 5.346E-04 044. 1.425E-03 1.3731-03 Byron Site Meteorological Data 1/78 - 12/87 F-20
BYRON
.'evision 1,3 March 1996 Table F-7 (Continued) 1 cm Depth at the Untestricted Area Boundary for Xe-135 Maximum Offsite Finite Plume Gamma Dose Factors Based on Downwind Unrestricted mixed Node(Vent) Retease Ground Level Retlise V VBAR Radius a GEAR Direction Area Bound Radius (mrters) (meters) (mrad/yr)I(UCiISec) (miters) (rad/yr0)I'C/seec) 1875. 2.998E-04 2.898E-04 1875.
1829. 8.831E-04 7.6725-04 3.532E-04 r.4121-04 N 1875. 1829. 2.878E-04 2.783E-04 NNE 1829. 1585. 7.977M-04 r.7T07-E4 1585. 1585. 2.805E-04 2.713E-04 3.475E-04 RE 2.658E-04 1234. 8.7TM5-04 ENE 1234. 1234. 2.749E-04 1227. 1.0991-03 1.061E-03 1227. 1227. 3.2331-04 3.126E-04 1.496E-03 E 4.486E-04 4.33TE-04 991. 1.549E-03 ESE 991. 991. 1006. 2.178E-03 2.104E-03 SE 1006. 1006. 5.1121-04 4.942E-04 5.006E-03 6.045E-04 5.843E-04 800. 3.113E-03 SSE 800. 800. 945. 1.701E-03 1.643E-03 S 945. 945. 3.878E-04 3.749E-04 1.150E-03 2.7SE-04 975. 1.190E-03 ss*e 975. 975 2.880E-04 1067. 8.696E-04 8.400E-04 1067. 1067. 2.33TE-04 2.260E-04 7.407E-04 SI' 2.415E-04 2.335E-04 1212. 7.667E-04 1212. 1212. 1189. 9.146E-04 8.8351-04 US" 1189. 2.873E-04 2.7781-04 v 1189. 1227. 6.366E-04 6.1501-04 1227. 1227. 2.012E-04 1.945E-04 8.175E-04 7.8961-04 VWI 1128. 1128. 2.641E-04 2.553E-04 1128. MN NV 4.124E-04 1044. 1.313E-03 1.268E-03 1044. 1044. 4.267E-04 Byron Site oeteorologicat Date 1178 - 12/87 F-21
BYRON Revision 1.3 March 1996 ,f. Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Xe-137 Downwind Unrestricted Nixed Noda(Vent) Release Ground Level Release Direction Area Bound Radius V VWAR Radius a. IAR (meters) (meters) (mred/yr)/(uCIsec) (meters) (wred/yr)/(uCitile) N 1875. 1875. 6.403E-05 6.1971-05 1875. 9.59TE-05 9.28;'&-05 NNE 1829. 1829. 6.3585-05 6.153E-05 1829. 8.275E-05 8.0011E-05 NE 1585. 1585. 6.960E-05 6.348E-05 1585. 9.063E-05 8.771)E-05 ENE 1234. 1234. 7.607E-05 7.362E-05 1234. 1.243E-04 1.2011-E04 E 1227. 1227. 9.065E-05 8.775E-05 1227. 1.555E-04 1.501,E-04 ESE 991. 991. 1.509E-04 1.461E-04 991. 1006. 2.805E-04 2.71*,-04 SE 1006. 1006. 1.596E-04 1.544E-04 3.1"4E-04 3.04;#-04 SSE 800. 800. 1.905E-04 1.843E-04 800. 4.627E-04 4.4T,'E-04 S 945. 945. 1.2671-04 1.226E-04 945. 2.775E-04 2.68.;E-04 SSW 975. 975. 9.229E-05 8.932E-05 975. 1.933E-04 1.871E-04 S" 1067. 1067. T.424E-05 T.185E-05 1067. 1.418E-04 1.3r.2-04 1212. 1212. T.355E-05 7.1181-05 1212. 1.309E-04 1.266E-04 1189. 1189. 8.087E-05 7.8271E-05 1189. 1.518E-04 1.4611-04 WNW 1227. 1227. 5.651E-05 5.469E-05 '1227. 1.056E-04 1.02'E-04 Nu 1128. 1128. 8.102E-05 7.841E-05 1128. 1.535E-04 1.4814E-04 NNW 1044. 1044. 1.454E-04 1.4071-04 1044. 2.944E-04 2.84VE-04 Byron Site Neteorologfceat Date 1/78 - 12/87 F-22 Th
BYRON (evision 1.3 March 1996 V.I. Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unirestricted Area Boundary for Xe-138 Downwind Unrestricted Mixed Node(Vent) Release Cround Level Reletse Direction Area Bound Radius V WBAR Radius a GBAR (meters) (meters) (mrad/yr)/(uCilsec) (meters) (wad/yr)l(uI:i/sec) tt N 1875. 1875. 7.317E-04 7.106E-04 1875. 1.559E-03 1.513E-03 NNE 1829. 1829. 7.040E-04 6.836E-04 1829. 1.310E-03 1.2711-03 NE 1585. 1585. 7.054E-04 6.8501-04 1585. 1.371E-03 1.3301-03 ENE 1234. 1234. 7.357E-04 7.145E-04 1234. 1.634E-03 1.586E-03 E 122?. 1227. 8.489E-04 8.244E-04 1227. 1.936E-03 1.879E-03 ESE 991. 991. 1.282E-03 1.245E-03 "991. 3.103E-03 3.0121E-03 SE 1006. 1006. 1.402E-03 1.362E-03 1006. 3.755E-03 3.644E-03 SSE 800. 800. 1.5891-03 1.543i-03 800. 5.212E-03 5.058E-03 S 945. 945. 1.089E-03 1.058E-03 945. 3.103E-03 3.012E-03 SSW 975. 975. 7.991E-04 7.761E-04 975. 2.1071-03 2,046E-03 StW 1067. 1067. 6.618E-04 6.427E-04 1067. 1.531W-03 1,487E-03 WSW 1212. 1212. 6.871E-04 6.674E-04 1212. 1.535E-03 1,4901-03 V 1189. 1189. 7.811E-04 7.586E-04 1189. 1.925E-03 1,869E-03 WNW 1227. 1227. 5.482E-04 5.324E-04 1227. 1.351E-03 1.311E-03 NIU 1128. 1128. T.355E-04 7.142E-04 1128. 1.756E-03 1.7041E03 NNW 1044. 1044. 1.215E-03 1.180M-03 1044. 2.955E-03 2.868E-03 Byron Site Meteorotoglcet Data 1/78 - 12/87 F-23
BYRON Revision 1.3 March 1996 I - Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 Downwind Unrestricted Mixed Node(Vent) Release Ground Level Rteleme Direction Area Bound Radius V VUAR Radius 0 I.AR (meters) (meters) (mradI/yr)I(uCAIsec) (motors) (nrad/yr)f(uCtI/sac) N 1875. 1875. 1.120E-03 1.084E-03 1875. 2.935E-03 2.I42E-03 NNE 1829. 1829. 1.085E-03 1.050E-03 1829. 2.5311-03 2.43501-03 NE 1585. 1585. 1.071E-03 1.037E-03 1585. 2.6371-03 2.U531-03 ENE 1234. 1234. 1.0691-03 1.035E-03 1234. 2.943E-03 2.049E-03 E 1227. 122T. 1.244E-03 1.205E-03 1227. 3.609E-03 3.493E-03 ESE "991. "1. 1.753E-03 1.697E-03 991. 5.2401-03 5.'172E-03 SE 1006. 1006. 1.975E-03 1.912E-03 1006. 7.123E-03 6.1,95E-03 SSE 800. 800. 2.290E-03 2.216E-03 800. 1.0151-02 9.128E-03 S 945. 945. .1.510E-03 1.462E-03 945. 5.616E-03 5.136E-03 SSW 975. 1.128E-03 1.092E-03 975. 3.884E-03 3.039E-03 SI 106t. 106?. 9.228E-04 8.933E-04 1067. 2.826E-03 2.135E-03 USW 1212. 1212. 9.527E-04 9.2221-04 1212. 2.594E-03 2.! 11E-03 I 1189. 1189. 1.105E-03 1.070E-03 1189. 3.148E-03 3.(471-03 WUNW 1227. 122?. .7.65E-04 7.5171-04 1227. 2.2011-03 2.131E-03 Nu 1128. 1128. 1.016E-03 9.837E-04 1128. 2.803E-03 2.1'13E-03 NNW 1044. 1044. 1.621E-03 1.570E-03 1044. 4.510E-03 4.'66E-03 Byron Site Meteorological Data 1/78 - 12187 F-24
RON ,,R
, .ion 1.3 March 1996 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restdr:ted Area Boundary for Kr-83m Downwind Restricted Mixed Node(Vent) Release Ground Level Retense V VBAR Radius a GBAR Direction Area Bound Radius (meters) (mradlyr)/(A:9/sec)
(meters) (meters) (mrad/yr)/(uCl/sec) 3.877*-04 2.924E-04 N NNE 77. 538. T/. 538. 7.9871-05 1.059E-04 6.022E-05 7.984E-05 777. 538. 5.665E-04 4,272E-04 528. 8.271E-05 6.2361-05 528. 4.960E-04 3.740E-04 NE 528. 3.473E-04 474. 474. 6.500E-05 4.901E-05 474. 4.605E-04 EINE 468. 5.8671-04 4.424E-04 E 468. 468. 8.031E-05 6.056E-05 480. 480. 8.9354-05 6.737E-05 480. 6.039E-04 4.553E-04 ESE 427. 1.044E-03 7, 870-04 SE 427. 427. 1.2801-04 9.653E-05 410. 410. 1.3TE'-04 1.0381-04 410. 1.210E-03 9.1251-04 SSE 295. 1.295E-03 9.767E-04 S 295. 295. 1.466*-04 1.106E-04 299. 299. 9.8951-05 7.461E-05 299. 9.128E-04 6 883E-04 SSW 451. 4.002E-04 3.017E-04 SW 451. 451. 4.721E-05 3.560E-05 386. 7.311E-05 5.513E-05 386. 5.291E-04 3.989E-04 us' 3Q6. 379. 6.4761-04 4.8831-04 w 379. 379. 1.136E-04 8.566E-05 385. 385. 7.998E-05 6.0311-05 385. 4.644E-04 3.501E-04 UWN 445. 4.352E-04 3.281E-04 NW 445. 445. 8.088E-05 6.098"-05 658. 658. 7.5481-05 5.691E-05 658. 3.4861-04 2.629E-04 NNW Byron Site Meteorotlogical Data 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. Approximate distance from midpoint between gaseous effluent release points. F-25
BYRON Revision 1.3 March 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Reotricted Area Boundary for Kr-4Sm Doo*ind Restricted Nixed Node(Vent) Release Oround Level Release Direction Area Bound Radius V VBAR Radius a GOAR (meters) (meters) (urad/yr)/(uCl/sec) (meters) (wred/hr)/(uCI/sec) N M*I. 777. 5.990E-04 5.755E-04 T77. 2.0151!-03 1.929M-03 NNE 538. 538. 8.304E-04 7.980E-04 538. 2.73211-03 2.614E-03 NE 528. 528. 6.9811-04 6.712E-04 528. 2.4411"-03 2.335E-03 ENE 474. 474. 5.790E-04 5.569E-04 474. 2.22511-03 2.1299-03 E 468. 468. 6.8411-04 6.578E-04 468. 2.7911*-03 2.669E-03 ESE 480. 480. 7.37M1-04 T.0921-04 480. 2.8931"-03 2.7674-03 SE 427. 427. 9.807E-04 9.423E-04 427. 4.78M--03 4.569E-03 SSE 410. 410. 9.459E-04 9.080E-04 410. 5.3231--03 5.084E-03 S 295. 295. 1.046E-03 1.005E-03 295. S.47*-.-03 5.226E-03 ISS 299. 299. 7.854E-04 7.549E-04 299. 3.979*1-03 3.801E-03 451. 4.441E-04 4.273E-04 451. .1.96Z'.-03 1.876E-03 Sw 451. US9 386. 386. 6.265E-04 6.0254-04 386. 2.4851!-03 2.376E-03 a 379. 379. 7.7311-04 7.421E-04 379. 2.912-.-03 2.7841-03
*wI' 385. 385. 5.485E-04 5.2664-04 385. 2.058-"03 1.9671-03 NW 445. 445. 5.566E-04 5L3441-04 445. 1.973:-03 1.8864-03 NNW 658. 658. 5.330E-04 5.118E-04 658. 1.750!-03 1.675E-03 Byron Site Neteorotogfcal Date 1/78 - I?2S8
.- e-F-26
-YRON I ion 1.3 March 1996 Table F-Ta (Continued)
Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-45 Downw*nd Restricted Mixed Node(Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius a OUR (meters) (meters) (wrad/yr)/(uCi/sec) (meters) (wred/yr)I(uCilt;ec) N T7. T7. 6.818E-06 6.593E-06 M. 2.201E-05 2.134E-05 NNE 538. 538. 9.568E-06 9.252E-06 538. 2.971E-05 2.8ra;E-05 NE 528. 528. 8.107E-06 7.840E-06 528. 2.658E-05 2.5711E-05 ENE 474. 474. 6. 771E-06 6.547E-06 474. 2.418E-05 2.3311E-05 E 468. 468. 7.994E-06 7.730E-06 468. 3.044E-05 2.94-E-05 ESE 480. 480. 8.548E-06 8.266E-06 480. 3.1471-05 3.04.1;E-05 SE 427. 427. 1.133E-05 1.095E-05 427. 5.222E-05 5.05(1E-05 SSE 410. 410. 1.090E-05 1.054E-05 410. 5.839E-05 5.64" -05 S 295. 295. 1.201E-05 1.168E-05 295. 5.918E-05 5 .72;E-05 SSW 299. 299. 9.1771-06 8.874E-06 299. 4.315E-05 4. 1i.;E-05 Sy/ 451. 451. 5.220E-06 5.04BE-06 451. 2.1531-05 2.08;'E-05 WSW 386. 386. 7.292E-06 7.051E-06 386. 2.68711-05 2.59IE-05 379. 379. 8.828E-06 8.537E-06 379. 3.134E-05 3.031E-05 RW 385. 385. 6.276E-06 6.069E-06 385. 2.212E-05 2.13VE-05 445. 445. 6.362E-06 6.152E-06 445. 2.130E-05 2.0611E-05 NNW 658. 658. 6.046E-06 5.841E-06 658. 1.9071-05 1.8.441-05 Byron Site Meteorologicat Data 1/78 - 12/87 F-27
BYRON Revision 1,3 March 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Rfistdcted Area Boundary for Kr-87 Downwind Restricted Mixed Node(Vent) Retease Ground Levwt Retease Direction Area Bound Radius V VBAR Radius 13 GSAR (moters) (meters) (mradlyr)l(uCilsec) (meters) (wr#deyr)/(uCI/sec) N M. T7. 538. 2.002E-03 2.849E-03 1.944E-03 2.761E-03 M. 538. 5.94;E-03 8.12UE-03 5.769E-03 7.884E-03 NOE 538. ME 528. 528. 2.424E-03 2.354E-03 528. 7.23'E-03 7.027E-03 ENE 474. 474. 2.0431-03 1.984E-03 474. 6.61:%E-03 6.421E-03 E 468. 468. 2.396E-03 2.327E-03 466. 8.191E-03 7.959E-03 ESE 480. 480. 2.576E-03 2.501E-03 480. 8.56LE-03 8.316E-03 SE 427. 427. 3.393E-03 3.295E-03 427. 1.397E-02 1.353E-02 SSE 410. 410. 3.189E-03 3.097E-03 410. 1.53,E-02 1.486E-02 Sm 295. 295. 3.653E-03 3.547E-03 295. 1.62?E-02 1.575E-02 299. 299. 2.789E-03 2.?091-03 299. 1.174E-02 1.140E-02 SSW 1.541E-03 451. 5.707E-03 5.543E-03 SV 451. 451. 1.586E-03 386. 386. 2.232E-03 2.168E-03 386. 7.":E-03 7.227E-03 379. 379. 2.657E-03 2.580E-03 379. 8.79!E-03 8.534E-03 WNW 385. 385. 1.894E-03 1.839E-03 385. 6.22?E-03 6.0481-03 NW 445. 445. 1.9071-03 1.852E-03 445. 5.9191-03 5.7471-03 NIN 658. 658. 1.763E-03 1.731E-03 658. 5.192E-03 5.041E-03 Byron Site Meteorotogicat Data 1178 - 12/87 1*, F-28
YRON R. Jion 1.3 March 1996 Table F-Ta (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 Downwind Restricted Mixed mode(Vent) Retease Ground Lever Retaose Direction Area Bound Radius V VBAR Radius a GEAR (meters) (meters) (mr-d/yr)/(uCiIsec) (meters) (mrad/yr)/(tCIIsec) 1.449E-02 1.4014-02 N NWE M. 538. T1. 538. 4.873E-03 6.949E-03 4.7371-03 6.7561-03 7m7. 538. 1.964E-02 1.9071-02 528. 528. 5.936E-03 5.771E-03 528. 1.755E-02 1.704E-02 9NI 474. 474. 5.0091-03 4.870E-03 474. 1.599E-02 1.5531-02 E 468. 468. 5.889E-03 5.726E-03 468. 1.9989-02 1.940E-02 480. 6.284E-03 6.109E-03 480. 2.076E-02 ;:.016E-02 ESE 480. .;.313E-02 SE 427. 427. 8.282E-03 8.050E-03 427. 3.413E-02 410.' 7.8389-03 7.6181-03! 410. 3.785E-02 .. 6741-02 SSE 410. 3.917E-02 N.802E-02 295. 295. 8.882E-03 8.634E-031 295. S 299. 2.846E-02 2.763E-02 SSW 299. 299. 6.8291-03 6.6391-03 451. 3.896E-03 3.788E-03 451. 1.403E-02 !.363E-02 451. 1.787E-02 '1.7354-02 SW 386. 386. 5.4211-03 5.276E-03 386. 379. 6.431E-03 6.251E-03 379. 2.0911-02 ;.036E-02 379. U 385. 385. 4.584E-03 4.455E-03 385. 1.483E-02 1'.4OE-02 445.. 445. 4;622E-03 4.492E-03 445. 1.419E-02 1.378E-02 NW 1.258E-02 '1.2221-02 NIIW 658. 658. 4.324E-03 4.2031-03 658. Byron Site Meteorological Data 1/78 - 12/87 F-29
BYRON Revision 1.3 March 1996 Table F-Ta (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the REstricted Area Boundary for Kr49 Donmwind Restricted Mixed Hode(Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius 0 GBAR (moters) (meters) (madI/yr)/(uCl/sec) (meters) (mrad/yr)/(uCi/sec) N T.7. T7. 2.235E-03 2.171E-03 4.6691-03 4.535E-03 NNE 538. 538. 3.7495-03 3.641E-03 538. 7.948E-03 7.T2E-03 NE 528. 528. 3.089E-03 3.001E-03 528. 6.6261-03 6.4361-03 ENE 474. 474. 2.6451-03 2.569E-03 474. 6.153E-05 5.976E-03 E 468. 468. 3.102E-03 3.014E-03 468. 7.427E-05 7.213E-03 ESE 480. 480. 3.404E-03 3.306E-03 480. 7.840E-05 7.614E-03 SE 427. 427. 4.486E-03 4.358E-03 427. 1.176E-02 1.142E-02 SE 410. 410. 3.890E-03 3.7795'03 410. 1.1413-02 1.108E-02 S 29M. 295. 5.5181-03 5.360E-03 295. 1.743E-02 1.693E-02 ISSV 299. 299. 4.137E-03 4.0191-03 299. 1.248E-02 1.212E-02 451. 451. 2.136E-03 2.075E-03 451. 5.197E-05 5.047E-03 WV 386. 386. 3.333E-03 3.238E-03 386. 8.487E-03 8.243E-03: 379. 379. 3.8323-03 3.722E-03 379. 1.037E-02 1.007E-02 385. 385. 2.751E-03 2.6723-03 385. 7.432E-03 .7.21-03 lWV Nu 445. 445. 2.651E-03 2.5763-03 "445. 6.506E-03 6.3191-03 NNW 658. 658. 2.158E-03 2.097E-03 658. 4.7385-03 4.602E-03 Byron Site Neteorotogiclt Date 1/78 - 12/87 F-30
'YRON R ion 1.3 March 1996
,V. Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restiicted Area Boundary for Kr-90 ow*wind Restricted Mixed Hode(Vent) Retease Ground Lever Retesse V VBAR Radius a GBR Direction Area Bound Radius (meters) (mrad/yr)l(uCi/sec) (meters) (meters) (m-ad/yr)/(uCl/Iec) N NNE M. 538. M. 538. 2.920E-04 9.216E-04 2.833E-04 8.940E-04 T17. 538. 2.777E-04 1.070E-03 2.695E-04 1.03SE-03 528. 528. 6.9271-04 6.720E-04 528. 8.049E-04 7.80SE-04 NE 7.971E-04 ENE 474. 474. 6.455E-04 6.262E-04 474. 8.222E-04 E 468. 468. 8.493E-04 8.239E-04 468. 1.189E-03 1.155E-03 ESE 480. 480. 9.079E-04 8.807E-04 480. 1.223E-03 1.1851-03 SE 427. 427. 1.268E-03 1.230E-03 427. 1.855E-03 1.793E-03 SSE 410. 410. 1.055E-03 1.024E-03 410. 1.699E-03 1.643E-03 295. 295. 2.202E-03 2.136E-03 295. 4.311E-03 4.17;E-03 S 3.01?E-03 299. 299. 1.624E-03 1.575E-03 299. 3.114E-03 SSI 5.393E-04 451. 8.701E-04 8.4111-04 Sw 451. 451. 5.560E-04 386. 386. 1.053E-03 1.021E-03 386. 1.7015-03 1.641-03 379. 379. 1.099E-03 1.066E-03 379. 1.6101-03 1.561E-03 WN 385. 385. 8.138E-04 7.894E-04 385. 1.195E-03 1.153E-03 UNU 445. 445. 6.789E-04 6.585E-04 "445. 9.080E-04 8.80ZE-04 NiN 658. 658. 3.3571-04 3.256E-04 658. 3.703E-04 3.590E-04 Byron Site Neteorotogfeat Date 1/78 - 12/87 F-31
BYRON Revision 1.3 March 1996 .A Table F-Ta (Continued) Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-I31m Downwind Restricted Nixed Node(Vent) Release around LeveL Rulease Direction Area Bound Radius V VWAR Radius a GBAR (meters) (meters) (mredlyr)I(uClles) (meters) (mred/yr)V(uCt/sec) N *T17 M. 7.60SE-0O 5.999E-05 3.5871-01 2.79M-04 NHE 538. 538. 1.0131-04 8.007E-05 538. 5.146E-01 4.000E-04 NE 528. 528. 8.079E-05 6.401E-05 528. 4.534E-01, 3.526E-04 ENUE 474. 474. 6.397E-OS 5.081E-05 474. 4.180E-04, 3.249E-04 E 468. 468. 7.840E-05 6.215E-05 468. 5.378E-04 4.1771-04 ESE 480. 480. 8.6411-05 6.842E-05 480. 5.499E-04. 4.272E-04 SE 427. 427. 1.224E-04 9.663E-05 427. 9.5851-0* 7.4361-04 SSE 410. 410. 1.316E-04 1.034E-04 410. 1.120E-0.1 8.6M71-04 295. 295. 1.379E-04 1.086E-04 295. 1.157E-0!* 8.9571-04 SSW 299. 299. 9.485E-05 7.499E-05 299. 8.215E-04 6.366E-04 WSW 451. 451. 4.713E-05 3.751E-05 451. 3.7281E-0 2.897M-04 Sws 386. 386. 7.0421-05 5.586E-05 386. 4.741E-04 3.682E-04 V WN 379. 379. 1.053E-04 8.276E-05 379,. 5.723E-04. 4.441E-04 mu 385. 385. 7.411E-05 5.829E-05 385. 4.08600, 3.169E-04 445. 445. 7.532E-05 5.9231-05 445. 3.871E-04, 3.009E-04 NWN 658. 658. ?.089E-05:, S.SSOE-0 658. 3.187E-0t. 2.480E-04 Byron Site Neteorotogicet Data 1/78 - 12/87 F-32
'RON i 4fon 1.3 March 1996 Table F-Ta (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Downwind Restricted Mixed Node(Vent) Retease Ground Level Reteaiue Rac dius G 3BAR Direction Area Bound Radius V VBAR (meters) (meters) (mad/yr)/(uCi/sec) (met era) (wad/yr)/(uC I/sec) 777. 6.051E-04 5.'1521-04 N 777. 7M7. 1.485E-04 1.296E-04 38. 8.473E-04 7.1824-04 NiNE 538. 538. 2.0174-04 1.766E-04 HE 528. 528. 1.653E-04 1.452E-04 28. 7.508E-04 6.:3714-04 ENE 474. 1.340E-04 1.182E-04 474. 6.889E-04 5.1140E-04 E 474. 468. 8.788E-04 7.4384-04 468. 468. 1.612E-04 1.418E-04 480. 480. 480. 1.755E-04 1.541E-04 9.024E-04 7.(5444-04 ESE 4F27. 1.544E-03 1.303E-03 SE 427. 427. 2.410E-04 2.105E-04 410. SSE 410. 410. 2.464E-04 2.136E-04 1.77T4-03 1.,493E-03 295. 295. 2.641E-04 2.298E-04 "95. 1.822E-03 1.1531E-03 S 299. 299. 1.8971-04 1.662E-04 199. 1.306E-03 1.100E-03 SSW 6.134E-04 5.199E-04 451. 451. 1.008-04 8.916E-05 M51. 386. 386. 1.459E-04 1.284E-04 186. 7.755E-04 6.5651-04 WSW 379. 379. 1.9851-04 1.722E-04 179. 9.2461-04 7.80?E-04 M 385. 385. 1.402E-04 1.2171-04 385. 6.573E-04 5.546E-04 NU 445. 445. 1.425E-04"1.23TE-04 445. 6.2701-04 S.'296-04 658. 658. 1.353E-04 1.176E-04 658. 5.3211-04 4.5221-04 NNV Byron Site Meteorotoglceal Date 1/78 - 12/87 F-33
BYRON RevIsion 1.3
- v. March 1996 Table F-7a (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-I33 Dowmnind Restricted Mixed Node(Vent) Release Direction Area Sound Radius Ground Levt Release V VWAR Radius 11 GDAR (meters) (meters) (rsdI/yr)/(ucI/sec) (meters) (wrd'yr)/(uCIlsec) N T77. m. 1.640*-04 1.478E-04 NNE Mr7. 6.69'14-04 5.9268-04 538. 538. 2.206E-04 1.991E-04 538. 9.27n.E-04 8.176E-04 NE 528. 528. 1.8076-04 1.636E-04 528. 474. 8.2311E-04 T.2714-04 E 474. 1.459E-04 1.324E-04 474. 7.5441-04 6.653E-04 468. 468. 1.752E-04 1.586E-04 468. ESE 480. 9.594E-04 8.4486-04 480. 1.915E-04 1.732E-04 480. 9.865E-04 8.6936-04 SE 427. 427. 2.615E-04 2.3571-04 427. 1.674E-03 1.4701-03 SSE 410. 410. 2.657E-04 2.379f-04 S 410. 1.909E-03 1.671E-03 SWv 295. 295. 2.831E-04 2.541E-04 295. 1.954E-03 1.70E8-03 299. 299. 2.034E-04 1.834E-04 299. 451. 1.4071-03 1.233E-03 451. 1.097E-04 9.976E-05 451. 6.715E-04 5.920E-04 386. 386. 1.584E-04 1.435E-04 386. 8.466E-04 T.4556-04 WN 379. 379. 2.144E-04 1.922E-04 379. 1.003E-03 8.8121-04 KV UNN 385. 385. 1.512E-04 1.356E-04 385. 7.1161.*04 6.246E-04 Nin 445. 445. 1.5416-04 1.382E-04 445. 6.8051!-04 5.979E-04 658. 658. 1.486E-04 1.335E-04 658. 5.86W[-04 5.180E-04 Byron Site Neteorologicea Date 1/78 - 12/87 F-34
YRON FV .,ion March 1.3 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m Downwind Restricted Mixed Node(Vent) Retease around Level Retease Radius a GBAR Direction Area Bound Radius V VBAR (meters) (meters) (mrad/yr)I(uCi/sec) (meters) (Crad/yr)/(uCI/sec) 3.1701-03 3.053E-03 N NNE M. 538. 7M7. 538. 1.114E-03 1.604E-03 1.0743-03 1.548E-03 M. 538. 4.526E-03 4.35BE-03 528. 1.341E-03 1.294E-03 528. 3.963E-03 3.817E-03 NE 528. 474. 3.655E-03 3.519E-03 ENE 474. 474. 1.127E-03 1.087E-03 468. 1.313E-03 1.2673-03 468. 4.3891-03 4.226E-03 E 468. 480. 4.682E-03 4.508E-03 ESE 480. 480. 1.445E-03 1.394E-03 427. 1.901E-03 1.833E-03 427. 7.254E-03 6.984E-03 SE 427. 410. 7.557E-03 7.273E-03 SSE 410. 410. 1.722E-03 1.661E-03 295. 2.104E-03 2.029E-03 295. 9.119E-03 8.7M5E-03 S 295. 299. 6.478E-03 6.235E-03 SSW 299. 299. 1.569E-03 1.514E-03 451. 8.760E-04 8.455E-04 451. 2.94SE-03 2.839E-03 Sm 451. 386. 4.307E-03 4.147E-03 386. 386. 1.289E-03 1.244E-03 379. 1.552E-03 1.496E-03 379. 5.247E-0; 5.050E-03 379. 385. 3.752E-03; 3.611E-03 385. 385. 1.107E-03 1.067E-03 445. 1.103E-03 1.064E-03 445. 3.446E-03; 3.317E-03 NUi 445. 658. 2.8661-03 2.760E-03 NNW 658. 658. 1.013E-03 9.7703-04 Byron Site Meteorotogical Data 1/78 - 12/87 F-35
BYRON Revision 1.3 March 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-I35 DournInd Restricted Mixed Noda(Vent) Release Ground Levil Release Direction Area Bound Radius V VBAR Rim lug GOUAR (meters) (mters) (mrad/yr)/(uCi/sec) (metere) (mraly1')luCt/IIsec) N T77. T77. 8.146E-04 7.873E-04 M77. 2.7151-03 2.622E-03 NHE 538. 538. 1.1311-03 1.093E-03 538. 3.66Z-03 3.5351-03 NE 528. 528. 9.534E-04 9.2151-04 528. 3.27SE-03 3.162E-03 ENE 474. 474. 7.918E-04 7.654E-04 474. 2.98.)-03 2.879E-03 E 468. 468. 9.350E-04 9.038E-04 468. 3.7451E-03 3.616E-03 ESE 480. 480. 1.006E-03 9.723E-04 480. 3.87TE-03 3.743E-03 SE 427. . 427. 1.3358-03 1.290E-03 427. 6.41)E-03 6.1881-03 SSE 410. 410. 1.286E-03 1.243E-03 410. 7.141E-03 6.892E-03 S 295. 295. 1.4201-03 1.373E-03 295. 7.281E-03 7.030E-03 SSW 299. 299. 1.0701E-03 1.035E-03 M9. 5.30PE-03 5.125E-03 451. 451. 6.081E-04 5.878E-04 451. 2.6IE-03 2.5501-03 WSV 386. 386. 8.542E-04 8.2571-04 386. 3.3191-03 3.205E-03 NU 379. 379. 1.0471-03 1.0111-03 379. 3.8771-03 3.7421-03 385. 385. 7.428E-04 T.178E-04 585. 2.7371-03 2.642E-03 NN 445. 445. 7.543E-04 7.288E-04 445. 2.631E-03 2.540E-03 UN' 658. 658. 7.2308-04 6.987E-04 658. 2.351E-03 2.270E-03 Byron Site Neteorologlcel Date 1/78 - 12/87 S':.4 F-36
BYRON Revision 1.3 March 1996 Table F-7a (Continued) Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Restricted Mlixed Node(Vent) Retease Ground Level Retellse V VBAR Radius a GUAR Direction Area Bound Radius (meters) (caters) Cmrad/yr)/CuCilsec) (meters) (mradlyr)/(uI:l/sec) N 777. 538. TIT. 538. 3.338E-04 5.395E-04 3.230E-04 5.221E-04 M. 538. 7.619E-04 1.250E-03 7,372E-04 1.209E-03 NNE 528. 1.050E-03 1.016E-03 528. 528. 4.433E-04 4.290E-04 9.413E-04 NE 3.643E-04 474. 9.728E-04 ENE 474. 474. 3.764E-04 468. 1.168E-03 1,130E-03 E 468. 468. 4.417E-04 4.275E-04 4.703E-04 480* 1.237E-03 1.197E-03 ESE 480. 480. 4.860E-04 427. 1.856E-03 1.796E-03 SE 427. 427. 6.397E-04 6.190E-04 5.393E-04 410. 1.813E-03 1.755E-03 19 SSESE 410. 410. 5.573E-04 2.671E-03 2.584E-03 295. 295. 7.699M-04 7.450E-04 295. 1.8401-03 SSW 5.555E-04 299. 1.901E-03 299. 299. 5.740E-04 451. 8.062E-04 7.8011-04 SW 451. 451. 3.015E-04 2.9181-04 386. 4.6781-04 4.527E-04 386. S1.303E-03 1.261E-03 ssit 386. 379. 1.602E-03 1.550E-03 WNW 379. 379. 5.469E-04 5.292E-04 3.793E-04 385. 1.148E-03 1.111-E03 385. 385. 3.920E-04 445. 1.012E-03 9.792E-04 iiW UNU 445. 445. 3.807E-04 3.684E-04 3.194E-04 3.090E-04 658. 7.568E-04 7.322E-04 658. 658. NINU Byron Site Heteorological Data 1/78 - 12/87
BYRON Revision 1.3 March 1996 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Re-stricted Area Boundary for Xe-I38 around Level itetease Downwind Restricted Mixed Node(Vent) Retease Radius 0 GBAR Direction Area Sound Radius V VBAR (meters) (mrad/yr)/(uCI/sec) (meters) (wed/yr)l(uCI/sec) (meters) N NNE 77*. 538. 77. 538. 2.446E-03 3.565E-03 2.375E-03 3.462E-03 M. 538. 6.STE-()3 9.4071-!)3 6.383E-03 9.129E-03 528. 528. 3.004E-03 2.9171-03 528. 8.231E-13 7.98M-03 NE 7.361E-03 ENE 474. 474. 2.542E-03 2.469E-03 474. 7.585E-03 468. 468. 2.950E-03 2.8648-03 468. 9.089"NE- 8.820E-03 E 480. 3.242E-03 3.148E-03 480. 9.708W-03 9.421E-03 ESE 480. 427. 427. 4.245E-03 4.122E-03 427. 1.497E-02 1.453E-02 SE 3.820E-03 3.7093-03 410. 1.552E-02 1.506E-02 SSE 410. 410. S 295. 295. 4.720E-03 4.583E-03 295. 1.888E-D2 1.832E-02 299. 299. 3.5483-03 3.445E-03 299. 1.341-12 1.301E-02 SSW 6.108E-03 5.9281-03 451. 451. 1.990E-03 1.9331-03 451. 386. 386. 2.911E-03 2.8271-03 386. 8.964E-03 8.699E-03 379. 379. 3.444E-03 3.344E-03 379. 1.092E-02 1.0603-02
.1ra 385. 385. 2.461E-03 2.389E-03 385. 7.8140-03 T.582E-03 WNW 445. 445. 2.446E-03 2.375E-03 445. 7.166E-03 6.954E-03
.NW 658. 2.224E-03 2.159E-03 658. 5.956E-03 5.780E-03 NNW 658.
Byron Site Neteorotogicat Date 1/78 - 12/87
'*, F-38 Th
BYRON Revision 1.3 March 1996 Table F-7a (Continued) Ar-41 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restiicted Area Boundary for Domiwnd Restricted Nixed Node(Vent) Release around Level 0 Rltease cAR VBAR Radius Direction Area Bound Radius V (moters) (meters) (wad/yr)i(uCI/sec) (motors) (mrad/yr)AI/(UtlC) 3.113E-03 3.013E-03 M. 9.4381-0; 9.136E-03 N 777. 777. 538. 1.286E-0;': 1.244E-02 NNE 538. 538. 4.416E-03 4.275E-03 528. 1.147E-0;: 1.1101-02 RE 528. 528. 3.7551-03 3.635E-03 474. 1.0471-01: 1.013E-02 EIE 474. 474. 3.160E-03 3.059E-03 468. 1.3044-0;i 1.2621-02 E 468. 468. 3.711E-03 3.592E-03 480. 1.3581-0;! 1.314E-02 ESE 480. 480. 3.982E-03 3.8551-03 427. 2.2241-0!; 2.152E-02 SE 427. 427. 5.255E-03 5.086E-03 410. 2.4571-0;' 2.379M-02 SSE 410. 410. 4.973E-03 4.814E-03 295. 2.571E-0;! 2.489E-02 S 295. 295. 5.6451-03 5.464E-03 299. 1.865E-0!; 1.805E-02 SSW 299. 299. 4.306E-03 4.1681-03 451. 9.1181-0:1 8.8261-03 SW 451. 451. 2.450E-03 2.371E-03 386. 1.1741-0:! 1.1371-02 WSW 386. 386. 3.4371-03 3.327E-03 379. 1.382E--0: 1.3381-02 w 379. 379. 4.1086-03 3.9761-03 385. 9.788E-0:; 9.475E-03 WNW 385. 385. 2.926E-03 2.833E-03 445. 9.334E-0.1 9.0361-03 IN 445. 445. 2.952E-03 2.857E403 658. 8.224E-0:1 7.961E-03 UUN 658. 658. 2.76911-03 2.681E-03 gVglw Byron Site Meteorologicat Data 1178 - 12/87
BYRON Revision 1.3 March 1996 Supplemental Table A Mixed Mode Joint Frequency Distribution Table Sumrmr~les 250 Foot Elevation Data Summary Table of Percent by Direction and Claas Class N NNE NE ENE I ESE SE SSE S SSW SW WSW i WNW NW NNW' Total A .252 .214 .229 .246 .231 .171 .178 .162 .291 .322 .310 .232 .211 .249 .286 .204 3.789 8 .158 .133 .133 .134 .088 .074 .069 .107 .156 .202 .174 .149 .139 .136 .170 .161 2.179 C .217 .153 .133 .190 .153 .096 .126 .172 .238 .276 .252 .172 .223 .259 .313 .233 3.25? D 2.282 1.781 1.668 2.200 1.661 1.053 1.130 1.665 2.243 2.433 2.265 1.833 2.399 2.669 2.856 2.436 32.575 E 1.052 .909 .837 1.019 1.303 .911 1.120 1.405 2.257 2.475 2.028 1.699 1.601 1.728 1.908 1.293 23.437 F .360 .320 .301 .267 .442 .459 .561 .657 1.015 1.056 .683 .450 .436 .516 .635 .461 8.608 0 .218 .141 .134 .113 .160 .199 .289 .323 .315 .342 .333 .241 .139 .153 .181 .196 3.469 Total 4.539 3.652 3.464 4.158 4.040 2.962 2.474 4.492 6.515 7.106 6.045 4.673 5.148 5.710 6.350 4.966 77.315 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE I ESE SE SSE S SW SW WSW WtNW Nki NNV Total
.45 .000 .021 .006 .000 .006 .000 .000 .000 .010 .019 .014 .006 .030 .000 .016 .017 .144 1.05 .049 .040 .037 .020 .034 .026 .021 .015 .019 .040 .038 .056 .041 .060 .067 .037 .890 2.09 .233 .179 .209 .226 .174 .146 .157 .148 .177 .201 .214 .196 .245 .270 .247 .198 .3.220 3.05 .446 .368 .428 .487 .404 .306 .335 .377 .395 .464 .496 .436 .431 .466 .507 .467 6.813 4.05 .612 .561 .478 ".493 .425 .338 .379 .406 .486 .5684 .689 .571 .570 .593 .643 .593 8.420 5.05 .772 .636 .537 .591 .475 .373 .400 .497 .690 .749 .092 .720 .715 .879 .976 .751 10.655 6.05 .753 .625 .574 .648 .543 .391 .473 .632 .799 .976 1.000 .826 .863 .997 1.264 .994 12.358 8.05 1.174 .893 .775 1.027 1.206 .794 .961 1.257 1.986 2.289 1.783 1.299 1.471 1.608 1.780 1.403 21.708 10.05 .421 .282 .277 .591 689 .485 .633 .932 1.573 1.492 .774 .479 .646 .694 .720 .448 11.268 12.05. .070 .046 .063 .075 ;085 .104 .095 .228 .279 .291 .146 .085 .132 .143 .137 .058 2.1238 18.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 4.539 3.652 3.484 4.158 4.040 2.962 3.474 4.492 6.515 7.106 6.045 4.672 5.148 5.710 6.350 4.966 77.3.16 NOTE: Wind directions in tables are presented in 'wind from" and not "wind to" direction.
In order to determine the final mixed mode values, 77.315% of the elevated value (presented In the 250 FT Mixed Mode table) and 22.685% of the ground level value (presented In the 30 FT Mixed Mode table) are uied to calculate the final values. F-40
BYRON Revision 1.3 March 1996 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 250 Foot Elevation Data Summery Table of Peroent by Speed and Class Class A B C E F Speed
.45 .000 .000 .001 .0o9 .041 .. 022 .031 1.05 .007 .006 .020 .2259 .160 .076 .097 2.05 .116 .079 .128 1.518 .812 .941 .214 3.05 .364 .268 .367 3.212 1.5835 .616 .428 4.05 .599 .293 .453 3.627 2.053 .831 .493 5.05 .601 .363 .513 4.424 3.032 1.210 .511 6.05 .597 .374 .519 4.943 3.975 1.481 .464 8.05 .901 .496 .769 8.786 7.260 2.652 .344 10.05 .474 .243 .397 4.699 3.830 1.263 .362 13.05 .107 .057 .079 1.027 .740 .105 .024 18.00 .000 .000 .000 .000 .000 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F.M1
BYRON Revision 1.3 March 1996 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 30 Foot Elevation Data Summary Table of Percent by Direction and Claus close N NNE NE ENE E ESE S SSE S SSW SW IWS V WNW NW NNW Total A .046 .051 .047 .035 .045 .030 .036 .o47 .085 .135 .096 .072 .068 .067 .083 .056 1.023 a .035 .023 .029 .031 .023 .011 .016 .026 .053 .077 .055 .043 .031 .046 .043 .041 .594 C .o46 .034 .046 .051 .034 .026 .026 .035 .073 .096 .072 .050 .060 .068 .089 .057 .866 o .714 .465 .502 .604 .443 .329 .328 .560 .848 .630 .688 .499 .810 .984 .921 .725 10.251 E .236 .198 .155 .234 .370 .265 .391 .825 1A190 .987 .631 .328 .378 .404 .414 .282 7.310 F .062 .041 .020 .042 .1568 .133 .166 .360 .385 .162 .071 .056 .063 .075 .086 .101 2.012 a .019 .009 .007 .014 .052 .055 .086 .093 .107 .054 .017 .006 .013 .016 .032 .049 .630 Total 1.156 .8321 .08 1.011 1.127 .872 1.073 1.947 2.741 2.341 1.636 1.055 1.424 1.681 1.666 1.314 22.6865 Summary Table of Percent by Direction and Speed Speed N NNE NE EN! E ESE SE SSE 5 SSW SW WSW V WNW NW NNW Total
.45 .005 .005 .003 .000 .000 .000 .001 .001 .001 .002 .004 .002 .003 .002 .003 .013 .047 1.05 .015 .004 .007 .005 .009 .004 .004 .006 .008 .009 .012 .012 .014 .022 .037 .038 .207 2.05 .067 .034 .016 .030 .067 .045 .044 .048 .097 .108 .099 .071 .084 .101 .134 .130 1.177 3.05 .136 .109 .086 .109 .222 .1568 .165 .225 .296 .205 .166 .111 .116 .132 .164 .145 2.524 4.05 .174 .152 .128 .160 .265 .168 .221 .372 .429 .246 .207 .155 A161 .156 .214 .195 3.392 5.05 .151 .113 .122 .161 .184 .110 .173 .364 .416 .271 .212 .149 .144 .164 .209 .192 3.136 6.05 .129 .094 .102 .128 .155 .104 .139 .296 .290 .296 .224 .119 A56 .172 .183 .160 2.861 6.05 .232 .142 .192 .252 .184 .167 .206 .437 .722 .651 .417 .222 .284 .411 .881 .253 5.156 10.05 .131 .115 .132 .128 .020 .0865 092 .166 .11 .409 .221 .125 .242 .321 .272 .145 2.976 13.05 .050 .060 .033 .027 .001 .030 .025 .028 .072 .122 .080 .063 180 .162 .063 .041 1.064 16.00 .017 .001 .004 .000 .000 .001 .001 .002 .000 .008 .004 .026 .045 .038 .001 .002 .150 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .000 .000 .000 .002 Total 1.156 .611 .809 1.011 1.127 .872 1.07T 1.947 2.741 2.241 1.626 1.055 1.424 1.691 1.666 1.314 22.665 NOTE: Wind directions in tables are presented In "wind from" and not "Wind to" direction.
F-42
"*-YRON Fl,. ion 1.3 March 1996 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 30 Foot Elevation Data Summary Table of Percent by Speed and Class Class A 8 C D E P 0 Speed
.45 .000 .000 .000 .003 .007 .015 .022 4.05 .000 .000 .000 .006 .047 .083 .066 2.05 .002 .002 .009 .092 .479 .420 .174 3.05 .050 .028 .034 .521 1.110 .590 .192 4.05 .130 .078 .102 1.213 1.251 .483 .129 6.05 .157 .087 .137 1.368 1.109 .246 .032.
6.05 .140 .079 .120 1.362 1.058 .095 .006 8.05 .289 .173 .251 2.061 1.514 .062 .007 10.05 .177 .116 .142 1.912 .664 .006 .000 13.05 .076 .031 .053 .735 .159 .001 .000 16.00 .004 .000 .018 .117 .012 .0G0 .000 99.00 .000 .000 .001 .001 .000 .000 .000 F-43
BYRON Revision 1.3 March 1996 Supplemental Table B Ground Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Direotion and Class Clgag N NNE NE ENE a ESE SE SSE S SSW SW WSW V WNW NW NNW Total A .289 .317 .301 .244 .249 .100 .196 .197 .325 .454 .408 .318 .266 .342 .383 .302 4.792 B .190 .187 .170 .158 .125 .065 .079 .130 .193 .268 .227 .193 .171 .192 .202 .210 2.767 C .269 .226 .252 .218 .190 .116 .152 .189 .302 .364 .306 .218 .272 .317 .397 .328 4.116 D 3.298 2.327 2.336 2.684 1.992 1.334 1.365 2.172 3.012 3.140 2.915 2.275 3.055 3.615 3.969 3.357 42.847 E 1.466 1.198 .988 1.331 1.661 1.226 1.472 2.553 3.628 3.107 2.414 1.710 1.995 1.980 2.316 1.719 30.766 F .504 .316 .185 .276 .699 .648 .603 1.293 1.732 .881 .499 .408 .476 .499 *.646 .751 10.613 0 .202 .091 .061 .099 .253 .250 .355 .400 .624 .396 .189 .078 .131 .160 .312 .520 4.091 Total 6.217 4.663 4.304 M .011 5.160 3.630 4.424 6.933 9.826 S.609 6.929 6.200 6.367 7.106 8.225 7.186 100.000. Summary Table of Percent by Direction and Speed Speed N NINE NE ENE E ESE SE SSE S SSw SW WSW t WNW NW NNW Total
.49 .098 .099 .076 .030 .009 .000 .014 .032 .046 .045 .040 .030 .067 .042 .138 .211 .978 1.05 .308 .154 .125 .137 .121 .093 .090 .090 .127 .137 .205 .229 .265 .339 .503 ..536 3.450 2.05 .939 .602 .458 .594 .643 .606 .596 .605 1.00 1.072 1.002 .839 .905 .995 1.305 1.265 13.635 3.05 1.164 1.030 .779 .981 1.468 1.075 1.093 1.478 1.982 1.467 1.292 .930 1.005 1.157 1.388 1.186 19.476 4.05 1.179 1.024 .076 .995 1.243 .831 1.027 1.727 2.110 1.421 1.240 .997 1.024 1.035 1.342 1.214 19.286 5.05 .839 .631 .6568 .798 .724 .474 .652 1.254 1.636 1.250 1.038 .781 .813 .906 1.141 .971 14.566 6.05 .612 .467 .496 .689 .417 .313 .418 .803 1.153 1.094 .8659 .546 .786 .813 .867 .761 10.995 6.05 .755 .437 .612 .695 .310 .313 .405 .735 1.319 1.461 .896 .505 .915 1.177 1.090 .797 12.516 10.05 .253 .157 .183 .165 .032 .093 .103 .160 .374 .511 .270 .164 .350 .436 .378 .203 3.667 13.05 .053 .061 .034 .027 .001 .031 .025 .028 .072 .138 .081 .064 .190 .166 .071 .041 1.081 18.00 .016 .001 .004 .000 .000 .001 .001 .002 .000 .008 .004 .026 .045 .038 .001 .002 .150 09.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .000 .000 .000 .002 Total 6.217 4.663 4.304 5.011 5.169 3.630 4.424 6.933 9.862 6.609 6.929 5.200 6.367 7.105 8.225 7.186 100.000 NOTE: Wind directions in tables are presented In "wind from' and not 'wind to" direction.
40,F-44
77YRON F -on 1.3 "March 1996 Supplemental Table B -Continued Ground Level Joint Frequency Distribution Table Summaries Summary Table of Peroent by Speed and Clse Class A B C 0 a F I Speed
.45 .004 .001 .000 .095 .257 .275 .846 1.05 .018 .012 .027 .08 31.035 1.080 .780 2.05 .286 .171 .246 3.255 5.025 3.228 1.419 3.05 .744 .426 .816 6.258 7.173 8.272 .985 4.05 .992 .581 .781 8.165 6.404 1.902 .460 5.05 .909 ..
506 .808 7..02 4.257 .607 .077 6.05 .712 .388 .612 6.167 2.938 .164 .012 8.05 .819 .500 .785 7.616 2.724 .081 .011 10.05 .230 .150 .196 2.606 .667 .009 .000 12.05 .075 .032 .058 .755 .161 .001 .000 18.00 .004 .000 .018 .117 .012 .000 .000 99.00 .000 .000 .001 .001 .000 .000 .000 F-45
BYRON Revision 1.3 March 1996
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DRESDEN STATION Dresden Station Chapter 10 Change Summary ODCM Revision 2.0, March 1999 Page or Section Change Description 10-i Updated revision number. 10-7 In section 10.2.1.3 changed wording to reflect the fact that the Floor Drain Sample Tanks can be directly discharged into discharge canal. In section 10.2.2.1 changed the wording from "The monitor is used to monitor all releases..." to "The monitor is used to monitor releases...". Monitor operability requirements are given in ODCM Table 12.2-1, and there are allowances for discharges without a monitor operable. In section 10.2.2.1 added wording about the other possible discharge pathways which could be monitored by liquid radwaste effluent monitor prior to being discharged into the discharge canal. 10-13 Revised Figure 10-3 to show the presence of "portable waste treatment systems". Portable treatment systems have the flexibility to connect at various locations in the radwaste system for discharge to the river.
Dresden Station Chapter 10 Change Summary ODCM Revision 2.1, July 1999 Page or Section Change Description 10-i Updated the revision number, date and file designator. 10-ii Added Table of Contents entry to Section 10.1.2.7. "Chemical Cleaning Building Chimney Monitor." 10-iii Deleted Table of Contents entries to Section 10.2.2.3. "Chemical Cleaning Facility Service Water Effluent Monitor" and Section 10.2.3.1.3.
"Chemical Cleaning Facility Service Water Effluent Monitor."
10-1.1 In Step 10.1.1., "System Description," added the Chemical Cleaning Building Chimney as a principal release point for Unit 1. 10-3 Added Section 10.1.2.7, "Chemical Cleaning Building Chimney Monitor." 10-6 In Step 10.1.3.5, "HVAC Flow Rates," changed Unit 1 Chimney Air Flow value from 1.76E9 cc/min to 9.46E8 cc/min. 10-6 In Step 10.1.3.5, "HVAC Flow Rates," added entry for "Unit 1 Chemical Cleaning Chimney Air Flow" with a value of 1.61 e9 cc/min. 10-6 In Step 10.1.4, "Allocation of Effluents from Common Release Points," added first paragraph regarding origination of effluents into the Chemical Cleaning chimney. 10-7 Deleted Step 10.2.2.3, "Chemical Cleaning Facility Service Water Effluent Monitor." 10-9 Deleted Step 10.2.3.1.3, "Chemical Cleaning Facility Service Water Effluent Monitor."
Dresden Station Chapter 10 Change Summary ODCM Revision 2.1, July 1999 Paue or Section Change Description 10-11 Revised Figure 10-1, "Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram," to remove Turbine Building, Reactor Sphere, Blowdown Flash Tank, Process Lab, Shop Decon Areas, Radwaste Building and Decon Building which are no longer effluent pathways for Unit 1. The Fuel Building Ventilation was added as a effluent pathway. A flow control damper connected to the Fuel Building (K- 131), Fuel Building Ventilation and Wet Laundry Facility output was added. Flow rates for the Chemical Cleaning Facility, Wet Laundry Facility and Gaseous Monitoring System were added. 10-13 Revised Figure 10-3, "Simplified Liquid Radwaste Processing and Liquid Effluent Flow Diagram," to remove Unit 1 Chemical Cleaning Facility Service Water System and Unit 1 Service Water System.
DRESDEN Revision 2.1 July 1999 I DRESDEN ANNEX INDEX CHAPTER 10 REVISION 2.1 d10r2-1 .doc I 10-i
DRESDEN Revision 2.1 July 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE 10.1 AIRBORNE RELEASES ........................................................................................................... 10-1
- 1. System Description ........................................................................................................... 10-1
- 1. Condenser Offgas Treatment System ................................................................... 10-1
- 2. Ventilation Exhaust Treatment System ................................................................. 10-1
- 2. Radiation Monitors .......................................................................................................... 10-2
- 1. Unit 1 Chimney Monitor .......................................................................................... 10-2
- 2. Units 2/3 Chim ney Monitor .................................................................................... 10-2
- 3. Reactor Building Vent Stack Effluent Monitors ...................................................... 10-2
- 4. Reactor Building Ventilation Monitors ................................................................... 10-3
- 5. Condenser Air Ejector Monitors ............................................................................ 10-3
- 6. Isolation Condenser Vent Monitor ......................................................................... 10-3
- 7. Chem ical Cleaning Building Chim ney Monitor .............................................. 10-3
- 3. Alarm and Trip Setpoints ................................................................................................. 10-3
- 1. Setpoint Calculations ............................................................................................. 10-3
- 1. Reactor Building Vent Monitors .................................................................... 10-3
- 2. Condenser Air Ejector Monitors .................................................................. 10-3
- 3. Units 2/3 Plant Chim ney Radiation Monitor ................................................. 10-3
- 2. Release Limits ....................................................................................................... 10-4
- 3. Release Mixture .................................................................................................... 10-5
- 4. Conversion Factors .............................................................................................. 10-5
- 5. HVAC Flow Rates ................................................................................................. 10-6
- 4. Allocation of Effluents from Com mon Release Points ....................... .............................. 10-6
- 5. Dose Projections ............................................................................................................. 10-6 dlOr2-1 .doc 10-ii
DRESDEN Revisior 2'. July 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS(Cont'd) PAGE 10.2 LIQUID RELEASE .................................................................................................................... 10-6
- 1. System Description ......................................................................................................... 10-6
- 1. Unit 1 Storage Tanks ............................................................................................ 10-6
- 2. Units 2/3 Waste Sample Tanks ............................................................................. 10-6
- 3. Units 2/3 Floor Drain Sam ple Tanks ..................................................................... 10-7
- 4. Units 2/3 Waste Surge Tank .................................................................................. 10-7
- 2. Radiation Monitors .......................................................................................................... 10-7
- 1. Liquid Radwaste Effluent Monitor .......................................................................... 10-7
- 2. Units 2 & 3 Service W ater Effluent Monitors ......................................................... 10-7
- 3. Alarm and Trip Setpoints ................................................................................................. 10-8
- 1. Setpoint Calculations ............................................................................................ 10-8
- 1. Liquid Radwaste Effluent Monitor ................................................................ 10-8
- 2. Units 2 & 3 Service Water Effluent Monitor ................................................. 10-9
- 2. Discharge Flow Rates ........................................................................................... 10-9
- 1. Release Tank Discharge Flow Rate ............................................................ 10-9
- 3. Release Lim its ...................................................................................................... 10-10
- 4. Release Mixture ................................................................................................... 10-10
- 5. Conversion Factors .............................................................................................. 10-10
- 6. Liquid Dilution Flow Rates .................................................................................... 10-10
- 4. Allocation of Effluents from Com mon Release Points .................................................... 10-10
- 5. Projected Doses for Releases ....................................................................................... 10-10 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM ....................................... 10-10 dl 0r2-1 .doc 10-iii
DRESDEN Revision 2.1 July 1999 CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-11 10-2 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-12 10-3 Simplified Liquid Radwaste Processing and Liquid Effluent Flow Diagram 10-13 10-4 Simplified Solid Radwaste Processing Diagram 10-14 dlOr2-1 .doc 1 0-iv
DRESDEN Revision 2 1 July 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram is provided for Dresden Unit 1 in Figure 10-1 and for Dresden Units 2 and 3 in Figure 10-2. Dresden 1 is no longer operational, but monitoring of potentially radioactive releases from the plant chimney continues. Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal release points for potentially radioactive airborne effluents and their classifications are as follows: For Dresden 1:
-- The Chemical Cleaning Building Chimney (a vent release point)
-- The plant chimney (a stack release point).
For Dresden 2/3:
-- The ventilation chimney (a stack release point).
-- The reactor building ventilation stack (a vent release point).
10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3 of the Dresden UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figures 10-1 and 10-2. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. dlOr2-1 .doc 10-1
DRESDEN Revision 2.1 July 1999 10.1.2 Radiation Monitors 10.1,2.1 Unit 1 Chimney Monitor The SPING continuously monitors the final effluent from the Unit 1 chimney. The monitor has isokinetic sampling, gaseous grab sampling, and particulate and iodine sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe. In normal operation all three noble gas channels (low, mid-range, high) are on line and active. No automatic isolation or control functions are performed by this monitor. 10.1.2.2 Units 2/3 Chimney Monitor The SPING continuously monitors the final effluent from the Units 2/3 chimney. The monitor has isokinetic sampling, gaseous grab sampling, particulate and iodine sampling, and postaccident sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe. In normal operation the two lower noble gas channels (low and mid-range) are on line and active. The high range noble gas channel flow is bypassed and this channel is in standby. At a predetermined threshold the low and mid-range noble gas channels are bypassed and only the high range noble gas channel remains active. No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the Dresden UFSAR Section 11.5. In addition to the primary monitor described above, there is a backup system consisting of two additional detectors and sample taps in series in the primary sample stream. 10.1.2.3 Reactor Building Vent Stack Effluent Monitors The SPING continuously monitors the final effluent from the reactor building vent stack. The vent stack monitor has isokinetic sampling, gaseous sampling, and iodine and particulate sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe. All channels are continuously on line and active. No automatic isolation or control functions are performed by this monitor. dl 0r2-1 .doc 10-2
DRESDEN Revision 2.1 July 1999 10.1.2.4 Reactor Building Ventilation Monitors The monitor (located in the ventilation exhaust duct) monitors the effluent from the Unit 2(3) reactor building ventilation. On high alarm, the monitors automatically initiate isolation of the Unit 2(3) reactor building ventilation, and initiate startup of the Unit 2/3 standby gas treatment system. Pertinent information on these monitors is provided in Dresden UFSAR Section 11.5. 10.1.2.5 Condenser Air Ejector Monitors The monitors continuously monitor gross gamma activity downstream of the Unit 2 and 3 steam jet air ejector and prior to release to the main chimney. At the trip setpoint the monitors automatically activate an interval timer which in turn initiates closure of an air operated valve, thus terminating the release. Pertinent information on these monitors is found in Dresden UFSAR Section 11.5. 10.1.2.6 Isolation Condenser Vent Monitor The monitor continuously monitors radioactivity in the effluent from the isolation condenser vent. No control device is initiated by this monitor. Pertinent information on this monitor is provided in Dresden UFSAR Section 11.5. 10.1.2.7 Chemical Cleaning Building Chimney Monitor The monitor has charcoal and particulate filters which are used to sample for iodine and particulates. No automatic isolation, control functions or alarm functions are performed by this monitor. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Monitors The alarm setpoint for the reactor building vent monitor is established at 10 mr/hr. 10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at < 100 piCi/Sec per MWt (_-2.5E5PCi/sec) and the high alarm is established at _ 5*pCi/sec per MWt (_-1.25E5 1 tCi/sec). 10.1.3.1.3 Units 2/3 Plant Chimney Radiation Monitor The setpoint is established at a count rate corresponding to no greater than 105,000 pCi/sec. dlOr2-1 .doc 10-3
DRESDEN Revision 2.1 July 1999 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate, Q,,. (1- I) YX{ f[QsS_ + Q*,Vj]} < 500mremlyr (10-1) Y. {(Lifi[(X/Q)s Q, exp(-XiR/3600u,)
+ (X/Q),Qexp-(XiR/3600uv)] (10-2)
+1.11 )(f)[QtA, + Q*V,]
< 3000mrem/yr The summations are over noble gas radionuclides i.
Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides. Qt, Total allowed Release Rate, Stack Release [gCi/sec] The total allowed release rate of all noble gas radionuclides released as stack releases. Qt, Total Allowed Release Rate, Vent Release [p.Ci/sec] The total allowed release rate of all noble gas radionuclides released as vent releases. Refer to Section A.1 of Appendix A for the definitions of the remaining parameters. Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem/yr) due to noble gases released in gaseous effluents (see Section A. 1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem/yr) due to noble gases released in gaseous effluents (see Section A. 1.3.2 of Appendix A). Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. dl0r2-1 .doc 10-4
DRESDEN Revision 2 July 1999 10.1.3.3 Release Mixture In the determination of alarm and trip setpoints the radioactivity mixture in the exhaust air is assumed to have the following compositions. Reactor building vent effluent monitors. The mixture used for the GE monitors is taken from a representative isotopic analysis of the vent stack noble gas released since the last calibration, or based on nominal response of detector. The "mixture" used for the SPING is assumed to be a single pseudo-noble gas radionuclide. Condenser air ejector monitor. The mixture used for this monitor is taken from a representative isotopic analysis of noble gases collected at the recombiner outlet during plant operation, since the last alarm setpoint calculation. Units 2/3 plant chimney monitors. The mixture used for the GE monitors is taken from the most recent isotopic analysis of noble gases collected from the chimney monitor which corresponds to an above background recorder reading. The "mixture" used for the SPING is assumed to be a single pseudo-noble gas radionuclide. 10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows. Reactor building vent effluent monitor. For the GE monitors, the isotopic analysis in Section 10.1.3.3 and the monitor reading (in mR/hr) at the time of the analysis or nominal response of detector are used to establish the conversion factor in mR/hr per ViCi/cc or iCi/M 3
. For the SPING the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.
Condenser air ejector monitor. The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading (in mR/hr) at the time of the analysis are used to establish the conversion factor in mR/hr per pCi/cc or p.Ci/ft3 . Units 2/3 plant chimney monitors For the GE monitors, the isotopic analysis in Section 10.1.3.3 and flow and monitor reading (in CPS) at the time of the analysis are used to establish the conversion factor in CPS per liCi/cc or p.iCi/ft3 . For the SPING the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide. dl 0r2-1 .doc 10-5
DRESDEN Revision 2.1 July 1999 10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates are obtained from either the Units 2/3 process computers or the SPING control station. For the 2/3 Chimney, additional process flow rates must be added to obtain the total chimney flow (see Figure 10-2). Unit operation may affect actual flow rates which therefore may differ from values listed. If the actual flows are not available, the following default values based on design flow can be used: Units 2/3 Chimney Air Flow 1.25E10 cc/min Units 2/3 Combined Reactor Vent 6.23E9 cc/min Unit 1 Chimney Air Flow 9.46E8 cc/min Unit 1 Chemical Cleaning Chimney Air Flow 1.61 E9 cc/min I 10.1.4 Allocation of Effluents from Common Release Points Radioactive particulates and iodine released from the Unit 1 Chemical Cleaning Chimney originate from the Chemical Cleaning Building and Interim Radwaste Storage Facility. Radioactive gases, particulates, and iodines released from the Unit 1 chimney originate from Unit 1 only. However, radioactive gaseous effluents released from Units 2/3 are comprised of contributions from both units. Estimates of noble gas contributions from Units 2 and 3 are allocated considering appropriate operating conditions and measured SJAE off gas activities. Allocation of radioiodine and radioactive particulate releases to Units 2 or 3 specifically is not as practical and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation is made using reactor coolant iodine activities. During unit shutdowns or periods of known major in-plant leakage, the apportionment is adjusted accordingly. The allocation of effluents is estimated on a monthly basis. 10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS. 10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid radwaste and liquid effluent flow diagram is provided in Figure 10-3. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by evaporator, demineralizer, filter, and further vendor processing systems for the purpose of reducing the total radioactivity prior to reuse or release to the environment. The system is described in the Dresden UFSAR Section 11.2. 10.2.1.1 Unit 1 Storage Tanks Liquid radioactive effluents are not released from Unit 1 Storage tanks directly to the environment but are made through the Units 2/3 radwaste system. 10.2.1.2 Units 2/3 Waste Sample Tanks There are three waste sample tanks (33,000 gallons each) which receive water from the liquid waste treatment system. These tanks are transferred to the waste surge tank for discharge to the Illinois River via the discharge canal. dl0r2-1 .doc 10-6
DRESDEN Revision 2 1 July 1999 10.2.1.3 Units 2/3 Floor Drain Sample Tanks There are two floor drain sample tanks (22,000 gallons each) which receive liquid waste from the floor drain treatment system. These tanks are transferred to the waste surge tank or discharged to the Illinois River via the discharge canal. 10.2.1.4 Units 2/3 Waste Surge Tank The waste surge tank receives processed water from the waste sample tanks and floor drain sample tanks. This tank discharges to the Illinois River via the discharge canal. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor . X The monitor is used to monitor releases from the waste surge tank, floor drain sample tanks or portable waste treatment system tanks. On high alarm, a grab sample of the effluent is automatically taken from the discharge side of the sample chamber after a 0 to 60 second delay determined by a locally mounted timer. The release is terminated manually by initiating closure of the low flow or high flow discharge line valves. Pertinent information on the monitor and associated control devices is provided in the Dresden UFSAR Section 11.5. 10.2.2.2 Units 2 & 3 Service Water Effluent Monitors The monitors continuously monitor the service water effluent. On high alarm a grab sample is taken. Pertinent information on these monitors is provided in the Dresden UFSAR Section 11.5.. dlr2-1 .doc 10-7
DRESDEN Revision 2-1 July 1999 10.2.3 Alarm-and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10CFR20 are not exceeded in the unrestricted area. 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity. P < K x (Y Cfl/-( CT /DWC,)) x ((Fd + Fa. )IF,,ax ) (10-3) P Release Setpoint [cpm] ci, Concentration of radionuclide i in [i*Ci/ml] the release tank Fr Maximum Release Tank Discharge Flow Rate [gpm] The flow rate from the radwaste discharge tank. The maximum pump discharge rate of 250 gpm is used for calculating the setpoint. K Calibration constant [cprn/ltCi/ml] DWCG Derived Water Concentration (also referred to as Effluent Concentration Limit, ECL) of Radionuclide i [PCi/ml] The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. When technical specifications allow, ten' (10) times the DWCi may be used. Fd Dilution Flow [gpm] Dresden Station may use ten (10) upon Technical Specification approval. Until then, one (1) times the DWC must be used. dlOr2-1 .doc 10-8
DRESDEN Revision 2 July 1999 10.2.3.1.2 Units 2 & 3 Service Water Effluent Monitor The monitor setpoint is established at two times the background radiation value. 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. The results of the analysis of the sample determine the discharge rate of each batch as follows: Fm= 0.1(Fd/I(C/DWC,)) (10-4) The summation is over radionuclides i. 0.1 Reduction factor for conservatism. Fmnax Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the radwaste discharge tank. Releases are not permitted if the calculated discharge rate, Fmx, is less than 250 gpm. Fd Dilution Flow [gpm] C1 Concentration of Radionuclide i in [g.Ci/ml] the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. DWC, Derived Water Concentration of Radionuclide i [[.Ci/ml] The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. When technical specifications allow, ten2 (10) times the DWCj may be used. 2 Dresden Station may use ten (10) upon Technical Specification approval. Until then, one (1) times the DWC must be used. dlOr2-1 .doc 10-9
DRESDEN Revision 2.1 July 1999 10.2.3.3 Release Limits Release limits are determined from 10CFR20. Calculated maximum permissible discharge rates are divided by 10 to ensure that applicable derived water concentrations (DWC) are not exceeded. 10.2.3.4 Release Mixture For the liquid radwaste effluent monitor, the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis. For all other liquid effluent monitors, no release mixture is used because the setpoint is established at "two times background." 10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Co-60. The readouts for the Units 2 & 3 service water effluent monitors are in [ICi/ml. The calibration constants are based on the detector sensitivity to Co-60. 10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using the installed flowmeter in the discharge canal. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the release tanks are comprised of contributions from all three units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is normally made evenly between units 2 and 3. 10.2.5 Projected Doses for Releases Doses due to liquid effluents are calculated in accordance with the RETS. 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. Figure 10-4 is a simplified diagram of solid radwaste processing. dl 0r2-1 .doc 10-10
D":*'DEN r sion 2.1 Jly 1999 300' HIGH 4.5' DIAMETER EXIT ORIFICE 3,700 CFM (2) (1) L VENTILATION 29,715 CFM WET LAUNDRY 1 3.435 CFM Gaseous Monitoring System FACILITY N
- FLOW ONTRO CONTROL DAMPER PLANT GRADE ELEVATION 517' ABOVE MSI.
LEGEND AND NOTES 4 - HEPA FILTER
*- PARTICULATE SAMPLE OFFSITE DOSE CALCULATION MANUAL Q IODINE SAMPLE DRESDEN STATION UNIT 1 P I LN FLOW THROUGH RADIATION MONITOR: FIGURE 10-1 H P=PARTICULATE I=IODINE (1) 8.000 CFM summer LN, MN, HN,=LOW. MEDIUM & HIGH 4,000 CFM winter RANGE NOBLE GAS SIMPLIFIED GASEOUS RADWASTE AND GASEOUS EFFLUENT FLOW DIAGRAM (2) Normally Operated in Winter Only NOTES:
- 1. UNIT 1 IS NOT OPERATIONAL
- 2. ALL FLOW RATES ARE DESIGN FLOW RATES, NOT ACTUAL d10r2-1 .doc 10-11
"-"SDEN Revisio' -!
July 19,.. 28.760 CFM Sys High to mUnit3 Radiation F SampingEM 1000CFMI i . ---
. .. I f,,,T 310' Above Grade V Exit Diameter Radgal System Unit 2 G)iVentilation Radwasle--"
Solidification 16.000 CFM Unit 3 Turbine and Oft-Gas 174,200 CFM SSldg Recombiner Radwast Blg Maximm 6.70 CFMRoomsMI nil 2 Tubne LN Ra eBd Unit 2 Turbine Rawat BdgIdg and Off-Gas 177.200 CFM L Recmbiner 9'iaee 160' Diab eGra 90Above Grade I3 FE tD410 CFM Bldg Fier Off-Gas 5,500 CFM M RoomS Bypass (2 min. delay) Unit 3 Turbine C ~ m~e Log iUn
-- 1 Bypass
- A Toem
[ ,mbient tfG Unit 2
---- JIi Recombined Unt Dryer c harcoal Abso" ber IL on l-e adfl Dryer (30 I /
Conde I Air Ejector Minute Delay) (30(Several Days Delay) 20E hfs when recomblner In Hold Up F S6 30minl. when tooombiner out 2 rain. S4,000 CFMBldg VenStacktion Auxiliary Primary Containment Vent System (APCVS) mechanical Vacuum PumpG I' I I Condenser "*" - Same F tram Seat Ambient Atr Processing as S] earn Seat -(Turbine'Bld) L _ Unit 2 4,000 CFM Unit3 Isolation- Plant GraUo3 Condenser > I HP CI G la n d 4, 0 F P a tG a I -- -- P rlm n .t I --... str**ea-,m
-Jý Sea Seal -SGTS -- - - J 5 Elevtio 1r' Abovi Stea
- -. - - - Un-t2 .
19--
--- 7--- MSL Cold Hot Dryweall - - ----- -
Leg Leg
- Unit 2 1 "0.000 C-M Unit3 110000CFM
-- Drywall Purge I .
Unit 2 Legend and Notes I HEPA Filer Particulate Sample OFFSITE DOSE CALCULATION MANUAL UrRadiation Detector DRESDEN STATION UNITS 2 & 3 Iodine Sample Normally continuous flow
- Charcoal Flow through radiation monitor: path during power generation FIGUHE 10-2 P = Particulate . Occasional Flow Path PI = Iodine FE SIMPLIFIED GASEOUS RADWASIE AND LN, MN & HN - Low, medium T fI Flow Element GASEOUS EFFLUENT FLOW DIAGRAM Grab Sample Tap 6
& high range noble gas Note: All Il0w rates are design (low rates, not actual dlr2-1 .doc 10-12
'.SDEN Revisior July 196.
ILLINOIS RIVER a*r NOTES (1) PORTABLE WASTE TREATMENT SYSTEMS CAN BE CONNECTED AT VARIOUS LOCATIONS ge.. C WITHIN THE RADWASTE SYSTEM (2) OfLY PRINCIPLE PROCESSING PATHS ARE SH-COWN
.ST E TR IFATHFNT I
" "i I PORTARLI= WA I SYSTEPI I I UNIT 2/3 RAOWASTE CANAL UNIT 2/3 RADWASTE UNIT I RAOW/ASTE LEGEND
(:? GRAB SAMPLE TAP FLOW THROUGH RADIATION HONITOR CONTINJOUS OR FREOVENT FLOW PATH OCCASIONAL
-- FLOW PATH RETURN TO LAKE dlOr2-1.doc 10-13
A.-,
".SDEN Revisior July 199.
Cement E v a p o ra to r Li n e St r 10 hi Sludges " Liner 10 Store Ship Resins C Store ", Ship Filters Store Ship OFFSITE DOSE CALCULATION MANUAL DRESDEN STATION UNITS 2 AND3 FIGURE 10-4 SIMPLIFIED SOLID RADWASTE PROCESSING DIAGRAM dlr2-1 .doc
-I 10-14
DRESDEN I Revision 1.4 May 1998 CHAPTER 11 DRESDEN ANNEX INDEX Revision 1.4 I dnllrl-4.doc 11-i I
DRESDEN Revision 1.4 May 1998 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER TITLE PAGE 11 Radiological Environmental Monitoring Program 11-1 LIST OF TABLES NUMBER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER TITLE PAGE ( 11-1 Fixed Air Sampling and TLD Sites and Outer Ring TLD Locations 11-9 11-2 Inner Ring TLD Locations and Near Station Water Sample Locations 11-10 dnl I rl-4.doc 11-ii
DRESDEN Revision 1.4 May 1998 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program for the environs around Dresden Station is given in Table 11-1. Figures 11-1 and 11-2 show general sampling and monitoring locations. dnl 1rl-4.doc 11-1
DRESDEN Revision 1.4 May 1998 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location8 Collection Frequency of Analysis
- 1. Airborne Continuous sampler Radioiodine Canisters:
operation with particulate Radioiodine and a. Indicators-Near Field sample collection weekly, 1-131 analysis biweekly on Particulates or more frequently if near field and control D-04, Collins Road, 0.9 mi W (1.4 km N) required by dust loading, samples 1. D-06, Will County Road, 1.4 mi SE* (2.2 km G) and radioiodine canister D-07, Clay Products, 2.0 mi S (3.2 km J) collection biweekly. Particulate Sampler: D-45, McKinley Woods Rd, 1.5 mi ENE (2.4 km D) I D-53, Grundy County Road, 2.1 mi SSE* D-06 will be deleted once operational status of D-53 has been (3.2 km H) Gross beta analysis followin weekly filter changeeand gamma i established, isotopic analysis3 quarterly on composite filters by
- b. Indicators-Far Field location on near1field and control samples.
(6.4 km L) D-08, Prairie Parks, 4.0 ,j SW D-10, Goose Lake Village, 3.8 mi SSW (6.1 km K) D-13, Minooka, 4.5 mi N (7.2 km A) D-14, Channahon, 3.5 mi NE (5.6 km C)
- c. Controls D-12, Lisbon, 10.0 mi NW (16.0 km Q)
- d. SOecialt D-01, Onsite Station 1, 0.6 mi NW (1.0 km Q)
D-02, Onsite Station 2, 0.3 mi NE (0.5 km C) D-03, Onsite Station 3, 0.4 mi S (0.6 km J) dnl lrl-4.doc 11-2
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitorinq Location 6 Collection Frequency of Analysis
- 2. Direct Radiation a. Indicators-Inner Ring Quarterly Gamma dose on each TLD D-101-1, 1.0 mi N (1.6 km A) quarterly.
D-101-2, 1.0 mi N (1.6 km A) D-102-1, 1.3 mi NNE (2.1 km B) D-102-2, 1.3 mi NNE (2.1 km B) D-103-1, 1.2 mi NE (1.9 km C) D-103-2, 1.2 mi NE (1.9 km C) D-104-1, 1.5 mi ENE (2.4 km D) D-104-2, 1.5 mi ENE (2.4 km D) D-105-1, 1.4 mi E (2.2 km E) D-105-2, 1.4 mi E (2.2 km E) D-106-1, 0.9 mi ESE (1.4 km F) D-106-2, 0.9 mi ESE (1.4 km F) D-107-1, 1.3 mi SE (2.1 km G) D-107-2, 1.3 mi SE (2.1 km G) D-108-1, 1.9 mi SSE (3.0 km H) D-108-2, 1.9 mi SSE (3.0 km H) D-109-1, 0.8 mi S (1.3 km J) D-109-2, 0.8 mi S (1.3 km J) D-110-3, 0.8 mi SSW (1.3 km K) D-110-4, 0.8 mi SSW (1.3 km K) D-111-1, 0.6 mi SW (1.0 km L) D-111-2, 0.6 mi SW (1.0 km L) D-112a-1, 0.8 mi WSW (1.3 km M) D-112a-2, 0.8 mi WSW (1.3 km M) D-113-1, 0.9 mi W (1.4 km N) D-113-2, 0.9 mi W (1.4 km N) D-114-1, 1.0 mi WNW (1.6 km P) D-114-2, 1.0 mi WNW (1.6 km P) D-115-1, 0.8 mi NW (1.3 km Q) D-115-2, 0.8 mi NW (1.3 km Q) D-116-1, 1.0 mi NNW (1.6 km R) D-116-2, 1.0 mi NNW (1.6 km R) dnl lrl-4.doc 11-3
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location 6 Collection Frequency of Analysis
- 2. Direct Radiation b. Indicators-Outer Ring (Cont'd) D-201-1, 4.5 mi N (7.2 km A)
D-201-2, 4.5 mi N (7.2 km A) D-202-1, 5.0 mi NNE (8.0 km B) D-202-2, 5.0 mi NNE (8.0 km B) D-203-1, 4.5 mi NE (7.2 km C) D-203-2, 4.5 mi NE (7.2 km C) D-204-1, 5.0 mi ENE (8.0 km D) D-204-2, 5.0 mi ENE (8.0 km D) D-205-1, 4.2 mi E (6.7 km E) D-205-2, 4.2 mi E (6.7 km E) D-206-1, 3.5 mi ESE (5.6 km F) D-206-2, 3.5 mi ESE (5.6 km F) D-207-1, 4.5 mi SE (7.2 km G) D-207-2, 4.5 mi SE (7.2 km G) D-208-1, 5.0 mi SSE (8.0 km H) D-208-2, 5.0 mi SSE (8.0 km H) D-209-1, 5.0 mi S (8.0 km J) D-209-2, 5.0 mi S (8.0 km J) D-210-1, 4.8 mi SSW (7.7 km K) D-210-2, 4.8 mi SSW (7.7 km K) D-211-1, 5.0 mi SW (8.0 km L) D-211-2, 5.0 mi SW (8.0 km L) D-212-3, 6.0 mi WSW (9.7 km M) D-212-4, 6.0 mi WSW (9.7 km M) D-213-1, 4.5 mi W (7.2 km N) D-213-2, 4.5 mi W (7.2 km N) D-214-1, 4.5 mi WNW (7.2 km P) D-214-2, 4.5 mi WNW (7.2 km P) D-215-1, 5.1 mi NW (8.2 km Q) D-215-2, 5.1 mi NW (8.2 km Q) D-216-1, 4.8 mi NNW (7.7 km R) D-216-2, 4.8 mi NNW (7.7 km R) dnl 1r1 -4.doc 1.
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location 6 Collection Frequency p Analysis
- 2. Direct Radiation c. Other (Cont'd)
Indicators One at each of the airborne location given In part l.a and 1.b.
- d. Controls One at each airborne control location given in part 1.c.
dnl 1ri -4.doc 11-5
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency 6 Collection Frequency of Analysis and/or Sample Sample or Monitorinq Location
- 3. Waterborne a.. Ground/Well a. Indicators Quarterly Gamma isotopic 3 and tritium analysis quarterly.
D-23, Thorsen Well, 0.7 mi S (1.1 km J) D-35, Dresden Lock & Dam, 0.5 mi NW (0.8 km Q)
- b. Drinkinq Water There is no drinking water pathway within 6.2 mi downstream of station.
- c. Surface Water a. Indicator Weekly grab sample Gross beta and gamma isotopic analysis on D-51, Dresden Lock & Dam, 0.5 mi NW (0.8 km Q) monthly composite; tritium analysis on quarterly composite.
- d. Control a. Control Weekly grab sample Gross beta and I amma isotopic analysis on D-52, DesPlaines River, 0.9 mi ESE (1.4 km F) monthly composite; tritium analysis on quarterly composite.
Semiannually Gamma isotopic analysis3
- e. Sediments a. Indicator semiannually.
D-27, Dresden Lock & Dam, 0.5 mi NW (0.8 km Q) dnl lrl-4.doc 11'
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location6 Collection Frequency of Analysis
- 4. Ingestion
- a. Milk a. Indicators Biweekly: May through Gamma isotopic(3) and 1-131 October; Monthly: analysis(4) on each sample.
There are no dairies within 6.2 miles of the station. November through April
- b. Control D-25, Vince Biros Farm, 11.5 mi SW (18.5 km L)
- a. Indicator
- b. Fish' Gamma isotopic analysis 3 D-28, Dresden Pool of Illinois River, Two times annually on edible portions of each 0.5 mi NW (0.8 km Q)
- b. Control D-46, DesPlaines River upstream of discharge, 0.9 mi E (1.4 km E)
- a. Indicators
- c. Food Products Two samples from each of the four major quadrants within 6.2 miles of the station. Gamma isotopic analysis 3 Annually each sample.
Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken, if available.
- b. Controls Two samples within 9.3 to 18.6 miles of the station.
dnllr1-4.doc 11-7
DRESDEN Revision 1.4 May 1998 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program 1 Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Radiation Protection Director. 2 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. 3 Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. 4 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. s The fish monitoring locations are not identified exactly on the map. The points, D-28 and D-46, represent the general area where the samples are taken. 6 Distances provided for sampling/monitor locations are approximate. 7 The analysis requirements listed are for the REMP-required samples only. The special samples require only quarterly gamma isotopic analyses on the composite filters. 8 These sampling locations do not constitute REMP samples, but are special samples required per Section 11.5.1.10 of the UFSAR. They may be discontinued pending revision of the aforementioned section. dnl 1rl-4.doc
DRESDEN Revision 1.4 May 1998 0 10I Miles 0 10 r 20 Kilometgru OFFSITE DOSE CALCULATION MANUAL I. DRESDEN STATION UNITS 1, 2, & 3 FIGURE 11-1
- Air Sampling Location FDIED AIR SAMPLING AND TLD SITES AND
- TLD Location OUTER RING L.D LOCACnONS dnl lrl-4.doc 11-9
DRESDEN Revision 1.4 May 1998 L C
.0 V
0 CECo Row 116-1 116-2
*l 114-1 115-101 &3z t a. 1142 115-28& 51 or~ I Dreden Road q 013. Power mu o 113-2 0111°
. e *h e 110Sd Iuu ;ac all 1TLDI
- 110t4 10 1 hi zWaMa OFFSIE DOSE CALCULATION ANUAL DRESDEN STATION UNIT 1, 2, E TLD
- Sediment FRGJRE 11-2 41 Water MANER T 7WG XLOCAllS AMD "NEAR SgrATON WATER SMP. LOCAMOS KI dn11rl-4.doc 11-10
Dresden Station Chapter 12 Change Summary ODCM Revision 1.9, March 1999 Page or Section Change Description 12-ii Updated revision number, date and file designator. 12-8 Added information in Action 11 concerning allowable discharge cases when the monitor is "operable" but conditions cannot be established in which to utilize it (e.g., low counts, low flow, etc.). Required actions are the same as what was previously present for an inoperable monitor.
Dresden Station Chapter 12 Change Summary ODCM Revision 1.10, July 1999 Page or Section Change Description 12-i Updated revision number, date and file designator. 12-ii Updated the revision number. 12-7 Deleted Unit 1 portion of Table 12.2-1, "Radioactive Liquid Effluent (of Rev 1.9) Monitoring Instrumentation." Liquid discharges are no longer completed at Unit 1. 12-7 In Table 12.2-1, "Radioactive Liquid Effluent Monitoring Instrumentation," added note (1) to Liquid Radwaste Effluent Gross Activity Monitor. The (1) notation was also added to previously existing text beyond the first paragraph of Action 11. 12-7 In Action 10, changed LLD requirement from 10-7 uCi/ml to 5x 10.7 uCi/ml based on use of germanium detector to analyze isotopic activity. 12-9 Deleted Unit 1 portion of Table 12.2-2, "Radioactive Liquid Effluent (of Rev 1.9) Monitoring Instrumentation Surveillance Requirements." Liquid discharges are no longer completed at Unit 1. 12-9 In Table 12.2-2 Table Notations, deleted note (g) regarding operability verification of Unit 1 Discharge Canal Sampler. This note is no longer applicable with the deletion of Unit 1 portions of Tables 12.2-1 and 12.2-2. 12-36 In Table 12.4-1, "Radioactive Gaseous Waste Sampling and Analysis Program, Unit 1," added Row B., "Chem Cleaning Chimney". 12-40 Added note (7) to Table 12.4-1. This note supports the addition of the Chem Cleaning Chimney in previous change (page 12-36). NOTE: Chapter 12, Rev. 1.10, July 1999 was completed, reviewed and PORC approved, but was not distributed into the controlled copies of the ODCM. This information has been included in the January 2000 Chapter 12, Rev. 1.11 controlled copy distribution. Rev. 1.10 PORC approved documentation is attached.
Revision 47 -t-9--,+ 1.10 ps~ o S 0'r DRESDEN
-Ninth 1999 0 34t;ýot:01%,
g:Vnurphy\odcm\annex~dresden\dn 12r1 -8.doc 12-7
Q~zcvDRESDEN 00CM~c Revision 4 §r+-lC Mereh 1999 (/or / TLAý ,,rl g:'murphy~odcm~annex\dresdendn 12r1 -8.doc 12-9
9Oc,4 /ZL*Z,A) DRESDEN Revision 4-1-4 A. 1O f14& / £5c 1* SMar 1999 Ta~~j e~'( '0RoC TABLE 12.2-2 (Cont'd) RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
- 1. Instrument indicated levels above the alarm setpoint
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in OPERATE mode.
(b) Calibration shall include performance of a functional test. (c) Calibration shall include performance of a sburce check. (d) Source check shall consist of observing instrument response during a discharge. (e) Functional tests may be performed by using trip check and test circuitry associated with the monitor chassis. Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months.
/ Orabi is erifi pri rto erfor ing isc rge nd o/c e day urin plan ed d' chare g:\murphykodcmr\annex'dresden\dn1 2r0 -8.doc 12-11
e.C -E,IZ 6 15'zS.ZCv
*t DRESDEN Revision 4 g- . \b Me 1999
/3 o, /S TABLE 12.4-1 01" RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 g:Vnurphy\odcm\annex\dresden'dn1 2rl-8.doc 12-38
DRESDEN Revision +4 R*i. P4&_,., / O ,4: .Marh 1999 TABLE 12.4-1 (Cont'd) Z-0 c,0 ,OP RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (2) Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal power in 1 hour unless (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. Samples shall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. Sampling shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. (4) The ratio of sample flow rate to the sampled stream flow rate shall be known. (5) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-1 38 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for the nuclide. Analysis frequency shall be increased to 1/week if release rates exceed 1% of any applicable limit referenced in the ODCM, when added to Units 2 and 3 airborne effluents. (7) Gaseous Discharge from the Chemical Cleaning Building is continuously sampled through a particulate filter and iodine cartridge which are counted weekly. Sampling is not required if the Chemical Cleaning and Interim Radwaste Storage Facility (IRSE) ventilation systems are not running. g:\murphy\odcrn\annex'.dresden\dnl2rl-8.doc 1-2-42
6'.Dc Z94OAJ DRESDEN Revision +*i " .
-Mareh 1999 P4C4 /* Oi 1*
TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 Minimum Total Channels No. of Instrument Operable Channels Action 1 Service Water Effluent 10 Gross Activity Monitor
- 2. Liquid Radwaste Effluent 1,1 11 Gross Activity Monitors ACTIONS ACTION 10 With less than the minimum number of operable channels, releases via this pathway
.- may continue, provided that at least once per 12 hours grab samples arecollected and analyzed for beta or gamma activity at an LLD of less than or equal t ui/ml',
(The grab sample should normally be taken at the Service Water Monitor or at a location which would be representative of the Service Water which is monitored.) ACTION 11 - With less than a minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least 2 independent samples are analyzed, and at least 2 members of the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluent via this pathway.
~Effluent release via this pathway may continue when either.
- 1. The flow through the monitor cannot be established and maintained within design parameters, or
- 2. Effluent activity is below the range of detection for the monitor.
Provided that prior to initiating a release, at least 2 independent samples are analyzed, and at least 2 members of the facility staff independently verify the release calculations and discharge valving. Otherwise suspend release of radioactive effluent via this pathway. g:Vnurphy\odcmkannex\dresden\dn 12r1 -8.doc 12-8
Revision 1.9 March 1999 CHAPTER 12.0 SPECIAL NOTE The requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur. The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM for Unit 1 has been approved by the Nuclear Regulatory Commission in Amendment 39. The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM for Units 2 and 3 has been' approved by the Nuclear Regulatory Commission in Amendments 150 and 145. g:*murphy~odcm~annexkdresdendn 1 2rl -8.doc 12-i
DRESDEN Revision 1.9 March 1999 DRESDEN ANNEX INDEX C CHAPTER 12 Revision 1.9
-(-.
I g:mnurphy~odcm~annexdresdenfdnl12r1-8.doc 12-0i
DRESDEN Revision 1.9 March 1999 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION 12-5 A. Radioactive Liquid Effluent Monitoring Instrumentation 12-5
- 1. Radioactive Liquid Effluent Monitoring Instrumentation Operability 12-5
- 2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance 12-5 B. Radioactive Gaseous Effluent Monitoring Instrumentation 12-5
- 1. Radioactive Gaseous Effluent Monitoring Instrumentation Operability 12-5
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance 12-6 C. Liquid and Gaseous Effluents Instrumentation Bases 12-19 12.3 LIQUID EFFLUENTS 12-20 A. Liquid Effluents Limits and Reporting Operability 12-20
- 1. Concentration in Unrestricted Areas 12-20
- 2. Dose from Liquid Effluents 12-20
- 3. Dose Projections 12-21
- 4. Liquid Radioactive Waste Treatment System 12-22
- 5. System Operability and Plant Operations 12-22 B. Liquid Effluents Surveillance 12-22
- 1. Concentration in Unrestricted Areas 12-22
- 2. Dose from Liquid Effluents 12-23
- 3. Dose Projections 12-23 C. Liquid Effluents Bases 12-30
- 1. Concentration 12-30
- 2. Dose 12-30
- 3. Liquid Waste Treatment 12-30
- 4. Mechanical Vacuum Pump 12-31 12.4 GASEOUS EFFLUENTS 12-32 A. Gaseous Effluents Limits and Reporting Operability 12-32
- 1. Dose Rate 12-32
- 2. Noble Gas Dose 12-32
- 3. Iodine-131, Iodine-133, Tritium and Particulate Dose 12-33
- 4. Off-Gas Treatment 12-34
- 5. Main Condenser Air Ejector 12-35
- 6. System Operability and Plant Operations 12-35 B. Gaseous Effluents Surveillance 12-36
- 1. Dose Rate 12-36
- 2. Noble Gas Dose 12-36
- 3. lodine-131, Iodine-1 33, Tritium and Particulate Dose 12-36
- 4. Off-Gas Treatment 12-36
- 5. Noble Gases at the Main Condenser Air Ejector 12-37 g:\murphy\odcmrannex\dresdendn12r1 -8.doc 12-iii
DRESDEN Revision 1.9 March 1999 CHAPTER 12 C" RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS CONTINUED PAGE 12.4 GASEOUS EFFLUENTS (Cont'd) C. Gaseous Effluents Bases 12-43
- 1. Gaseous Effluents, Dose 12-43
- 2. Dose, Noble Gases 12-43
- 3. Dose, Radioiodines, Radioactive Material in Particulate Form and Radionuclides Other than Noble Gases 12-44
- 4. Gaseous Waste Treatment 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-45
- 1. Monitoring Program 12-45
- 2. Land Use Census 12-59
- 3. Interlaboratory Comparison Program 12-60
.C*'
12.6 RECOROKEEPING AND REPORTING 12-61
- 1. Station Operating Records 12-61
- 2. Reports 12-61
- 1. Radioactive Effluent Release Report 12-61
- 2. Annual Radiological Environmental Operating Report 12-61
- 3. Non-Routine Environmental Report 12-62
- 3. Offsite Dose Calculation Manual (0DCM) 12-63
- 4. Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12-64 g:Vnurphykolcm~annexdresden~n12rl-8.doc (
12-iv
DRESDEN Revision 1.9 March 1999 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS) LIST OF TABLES NUMBER TITLE PAGE 12.1-1 Surveillance Frequency Notation12-3 12.1-2 Operational Modes 12-4 12.2-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-7 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12-9 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-12 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-16 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 12-24 12.3-2 Radioactive Liquid Waste Sampling and Analysis Program 12-25 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-38 12.5-1 Radiological Environmental Monitoring Program 12-48 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-54 Reporting Levels 12.5-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection 12-55 g:%murphy~odcm~annexdresden~dn12r1-8.doc 12-v
DRESDEN Revision 1.9 March 1999 12.1 DEFINITIONS (Cont'd)
- 10. The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring AlarmfTrip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in Section 12.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Sections 12.6.2.1 and 12.6.2.2.
- 11. Operable - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its specified safety function(s) are also capable of performing their related support function(s).
- 12. The Process Control Program (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
- 13. Public Dose means the dose received by a member of the public from exposure to radiation or radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. Public dose does not include occupational dose or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released in accordance with IOCFR35.75, or from voluntary participation in medical research programs.
- 14. Rated Thermal Power - Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2527 thermal megawatts.
- 15. Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup/Hot Standby" or "Run" position with the reactor critical and above 1% rated thermal power.
- 16. Source Check - The qualitative assessment of Channel response when the Channel sensor is exposed to a radioactive source.
- 17. Definitions Related to Estimating Dose to the Public Using the ODCM Computer Program:
- 1. Actual - Refers to using known release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.
- 2. Projected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are NOT incorporated into the database.
g:\murphylodcmkannex\dresdendn12r1-8.doc 12-2
DRESDEN Revision 1.9 March 1999 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY* S (Shiftly) At least once per 12 hours D (Daily) At least once per 24 hours T At least once per 72 hours W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days E (Sesquiannually) At least once per 18 months (550 days) S/U (Startup) Prior to each reactor startup NA (Not Applicable) Not applicable
- Each surveillance requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The bases to.
Specifications 4.0.B provides clarification to this statement. These definitions do Technical not apply to the Radiological Environmental Monitoring Program (Section 12.5). g:Vnurphyodcn~annexklresden~dn12r1.8.doc 12-3
DRESDEN Revision 1.9 March 1999 TABLE 12.1-2 OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR MODE POSiTION(' COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature
- 2. STARTUP Startup/Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown(,-) > 212°F 8
- 4. COLD. SHUTDOWN Shutdown(* be) < 212°F
- 5. REFUELING(c) Shutdown or Refue0.d) < 140°F TABLE NOTATIONS (a)The reactor mode switch may be placed in the Run, Startup/Hot Standby, or Refuel position to test 7-the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.10.1. ( Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed. (d)See Technical Specification Special Test Exceptions 3.12.A and 3.12.B. (0)The reactor mode switch may be placed in the Refuel position while a single control rod is being moved provided the one-rod-out interlock is OPERABLE. ( When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be inoperable. g:VnurphykodcfannexVresdenldn1 2r0-8.doc 12-4
DRESDEN Revision 1.9 March 1999 12.2 INSTRUMENTATION A. Radioactive Liquid Effluent Monitorina Instrumentation
- 1. Radioactive Liquid Effluent Monitoring Instrumentation Operability
- 1. The effluent monitoring instrumentation shown in Table 12.2-1 shall be operable with alarm trip setpoints set to insure that the limits of Section 12.3.A are not exceeded. The alarm setpoints shall be determined in accordance with the ODCM.
- 2. With a radioactive liquid effluent monitoring instrument alarm/trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
- 3. With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 12.2-1. Return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.
- 4. In the event operability requirements and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the "
specifications, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.
- 2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance
- 1. Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequencies shown in Table 12.2-2.
B. Radioactive Gaseous Effluent Monitoring Instrumentation
- 1. Radioactive Gaseous Effluent Monitoring Instrumentation Operability
- 1. The effluent monitoring instrumentation shown in Table 12.2-3 shall be operable with alarm/trip setpoints set to ensure that the limits of Section' 12.4.A are not exceeded. The alarm/trip setpoints shall be determined in accordance with the ODCM.
- 2. With a radioactive gaseous effluent monitoring instruments alarm/trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
g:\rnurphy\odcm\annexWresdenkdn1 2r1-8.doc 12-5
DRESDEN Revision 1.9 March 1999 12.2.B.1 Radioactive Gaseous Effluent Monitoring Instrumentation Operability (Cont'd)
- 3. With one or more radioactive gaseous effluent monitoring instruments inoperable,.
take the action shown in Table 12.2-3. Return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.
- 4. The Unit 2/3 plant chimney gas sampling system may be out of service for 48 hours for the purpose of servicing the high range noble gas monitor as long as the following conditions are satisfied:
- 1. Both units are at steady state conditions with the recombiners and charcoal absorbers in service for the operating' unit(s).
- 2. The dose rate in unrestricted areas must be shown by calculation to be less than the limits of 12.4.A assuming the charcoal absorbers are bypassed on both units.
- 3. Both offgas monitors on Unit 2 and Unit 3 must be operational and the monitor reading correlated to the chimney release rate based on the conservative assumption of both units' charcoal absorbers being bypassed.
- 4. If the provisions of 12.4.A.1.1, 12.4.A.1.2, or 12.4.A.1.3 cannot be met, an orderly load reduction of the unit(s) shall be initiated immediately.
- 5. In the event operability requirements and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in this Section, provide a 30-day written report to the NRC and no changes are required in the (
operational condition of the plant, and this does not prevent the plant from entry into any operation mode.
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequency shown in Table
.12.2-4.
g:\murphykodcmrannex'resden~dn12rl-8.doc 12-6
DRESDEN Revision 1.9 March 1999 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Minimum Total Channels No. of Instrument Operable Channels Action Discharge Canal 1 1 12 Sampler* ACTIONS ACTION 12- Operability is verified prior to performing and once a day during planned discharge.
- When Instrument is unavailable and associated actions cannot be performed, then discharges may not be made.
g:*'nurphylodcm~annex%dresdenldn1 2r -8.doc 12-7
DRESDEN Revision 1.9 March 1999 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION C UNITS 2 & 3 Minimum Total Channels No. of Instrument Operable Channels Action
- 1. Service Water Effluent 1 1 10 Gross Activity Monitor
- 2. Liquid Radwaste Effluent 1 1 11 Gross Activity Monitor ACTIONS ACTION 10 - With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10-7 uCi/mI.
(The grab sample should normally be taken at the Service Water Monitor or at a .... location which would be representative of the Service Water which is monitored.) ACTION 11 - With less than a minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least 2 independent samples are analyzed, and at least 2 members of the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluent via this pathway. Effluent release via this pathway may continue when either.
- 1. The flow through the monitor cannot be established and maintained within design parameters, or
- 2. Effluent activity is below the range of detection for the monitor.
-4]
Provided that prior to initiating a release, at least 2 independent samples are analyzed, 3.. and at least 2 members of the facility staff independently verify the release calculations and discharge valving. Otherwise suspend release of radioactive effluent via this pathway. g:\murphy\odcm\annex'dresden\dn12r1 -8.doc 12-8
DRESDEN Revision 1.9 March 1999 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Functional Calibration(b)(" Instrument Source Instrument Test Check(O Check Discharge Canal Sampler* (g)
- When Instrument is unavailable and associated actions cannot be performed, then discharges may not be made.
g:ýmurphy~odcmaannex.dresden~dn1 2r1-8.doc 12-9
DRESDEN Revision 1.9 March 1999 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING ( INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 Functional Calibration(b)(n Instrument Source Instrument Testfa)(f Check") Check
- 1. Liquid Radwaste Effluent Gross QCO) E(C) D El" Activity Monitor
- 2. Service Water Effluent Gross Q(e) E(c) D E Activity Monitor
-C-ii g:\murphy~odcm~annexIdresdenWn 12r1-8.doc 12-10
DRESDEN Revision 1.9 March 1999 TABLE 12.2-2 (Cont'd) RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
- 1. Instrument indicated levels above the alarm setpoint
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in OPERATE mode.
(b) Calibration shall include performance of a functional test. (C) Calibration shall include performance of a source check. (d) Source check shall consist of observing instrument response during a discharge. (6) Functional tests may be performed by using trip check and test circuitry associated with the monitor chassis. Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. (9) Operability is verified prior to performing discharge and once a day during planned discharge. g:'nurphylodcmn annex~lresdenkdn1 2r1-8.doc 12-11
DRESDEN Revision 1.9 March 1999 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (" UNIT 1
- Minimum Total Applicable Channels No. of Operational Instrument Operable Channels Modes Action
- 1. Main Chimney SPING Noble Gas 1 3 28 Monitors
- 2. Main Chimney Particulate 1 1 27 Samplers
- 3. Main Chimney Iodine Samplers 1 I 27
- At all times.
C. I 12-12
DRESDEN Revision 1.9 March 1999 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 Minimum Total Applicable Channels No. of Operational Instrument Operable Channels Modes Action
- 1. Main Chimney Noble Gas/SPINGI 1 3. 20 GE Low Range Activity Monitor
- 2. Main Chimney SPING Noble Gas 1 26 Monitors Mid, Hi Range 1
- 3. Main Chimney Iodine Sampler 1 22 1
- 4. Main Chimney Particulate Sampler 1 22 1
- 5. Main Chimney Flow Rate Monitor 1 21 1
- 6. Main Chimney Sampler Flow Rate 1 21 Monitor
- 7. Reactor Building Vent Exhaust See Technical Specifications Section 3/4.2 Duct Radiation Monitor
- 8. Reactor Building Vent SPING 1 25 I
Noble Gas Monitor Low, Mid, High Range
- 9. Reactor Building Vent Flow 1 21 I
Rate Monitor
- 10. Reactor Building Vent Sampler 1 21 Flow Rate Monitor 1
- 11. Reactor Building Vent Iodine 22 1 I Sampler
- 12. Reactor Building Vent 22 1 1 Particulate Sampler
- 13. Offgas Radiation Activity 29 1 2 Monitor
- At all times.
"DuringSteam Jet Air Ejector operation.
g:ru rphy~odcm~annex~dresden dn 120 -8.doc 12-13
DRESDEN Revision 1.9 March 1999 TABLE 12.2-3 (Contd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTIONS AND TABLE NOTATIONS C.! ACTION 20 - With less than the minimum channels operable, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once every 8 hours and analyzed for noble gas within 24 hours. (The SPING has one low range noble gas channel, Channel 5, while the GE Low Range Activity Monitor has two low-range noble gas channels. The grab samples are usually taken at either the SPING, if it is aligned in the flow path, or at the GE Low Range Activity Monitor Skid.) ACTION 21 - With the number of operable channels less than the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours. (The Main Chimney Flow Rate Monitor and the Reactor Building Vent Flow Rate. Monitor are used for flow through the ChimneyNent Channel 10 of the SPING gives the ChimneyNent flow rate. This value can also be obtained from Point History. The Main Chimney Sampler Flow Rate Monitor and the Reactor Building Vent Sampler Flow Rate Monitor are used for the flow through the SPING or backup sampler. Channel 15 of the SPING gives the sampler flow rate for the SPING. The U2, U3 and GE Backup systems each have a flow rate monitor.) ACTION 22 - With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1. (7 (The normal sampler for 2/3 Main Chimney is the 2/3 Main Chimney SPING while for the 2/3 Reactor Building Vent it is the 2/3 Reactor Building Vent SPING. If the 2/3 Chimney SPING is not operational, the normal backup is the GE Low Range Activity Skid. This skid collects an Iodine and Particulate sample. If the 2/3 Reactor Building Vent SPING is not operational, the normal backups are the U2 and U3 Reactor Building Vent Samplers. The sampler for each vent collects an Iodine and Particulate sample. If the normal backup sampler is not available, use of an alternate sampler should be used as long as it pulls from the same process stream.) ACTION 25 - With less than the minimum channels operable, effluent releases via this pathway may continue provided that the minimum number of operable channels for the Reactor Building Vent Exhaust Duct Radiation Monitor are operable. (These are Channels 5 (low-range), 7 (mid-range) and 9 (high-range) on the 2/3 Reactor Building Vent SPING.) g:\murphy*odcm annexdresden~ln 2r1 -8.doc ( 12-14
DRESDEN Revision 1.9 March 1999 ACTION 26- With less than the minimum channels operable, effluent releases via this pathway may continue provided the low range monitor is operable and on scale. Restore the inoperable equipment to operable status within 21 days, or prepare and submit a report to the Commission pursuant to Technical Specification 6.9.B within the next 30 days outlining the plans, actions taken and procedures to be used to provide for the loss of sampling capability of the system. (These are Channels 7 (mid-range) and 9 (high-range) on the 2/3 Main Chimney SPING.) ACTION 27- The main chimney SPING monitor may be out-of-service for calibration and maintenance provided that particulate and iodine samples are taken and analyzed. The samples shall be collected using alternate filter holders and pumps connected to the main chimney sample stream. (The normal Iodine and Particulate sampler for D1 Main Chimney is the D1 Main Chimney SPING. If the D1 Chimney SPING is not operational, the normal backup is a sample pump attached to the sample stream from the Main Chimney. The sample pump collects an Iodine and Particulate sample.) ACTION 28 - With less than the minimum channels operable, effluent releases via this pathway may continue provided daily noble gas samples are taken and analyzed daily. Restore the inoperable equipment to operable status within 30 days. If service can not be returned, document equipment availability difficulties within the Radioactive Effluent Release Report for the period including actions taken in response to the equipment and procedures used to provide for the loss of sampling capability of the system. (The normal noble gas monitors are Channels 5 (low-range), 7 (mid-range) and 9 (high-range) on the D1 Chimney SPING. Grab samples can either be taken off of the SPING or taps on the piping for the sample stream.) ACTION 29 - With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours provided the off gas system is not bypassed and at least one chimney monitor is operable; otherwise, be in HOT STANDBY in 12 hours. w 'V g:vnurpny~o:crmannex*dresdenkn 12r -8.doc 12-15
DRESDEN Revision 1.9 March 1999 TABLE 12,2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Applicable Functional Calibration (b Instrument Source Operational Instrument Testfa)() Check Check Modes
- 1. Main Chimney SPING Q E D M Noble Gas Monitor Low Range
- At all times.
g:\murphydcrncmannex~dresden~dn12r1-8.doc 12-16
DRESDEN Revision 1.9 March 1999 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 Applicable Functional Calibration(b)(0) Instrument Source Operational Instrument Testa)(o) Check (8) Check Modes
- 1. Main Chimney Noble Q E D M Gas Activity Monitor
- 2. Main Chimney SPING Q E D M Noble Gas Monitor Lo, Mid, High Range
- 3. Main Chimney NA NA D(c) NA
- Particulate and Iodine Sampler
- 4. Main Chimney Flow Q E D NA Rate Monitor
- 5. Main Chimney Sampler Q(d) E D NA Flow Rate Monitor
- 6. Reactor Bldg Vent See Technical Specifications Section 3/4.2 Exhaust Duct Radiation Monitor
- 7. Reactor Bldg Vent Q E D M SPING Noble Gas Monitor Lo, Mid, High Range "8. Reactor Bldg Vent Q E D NA Flow Rate Monitor
- 9. Reactor Bldg Sampler Q(d) E D NA Flow Rate Monitor
- 10. Reactor Bldg Vent NA NA D(c) NA Particulate and Iodine Sampler
- 11. Off Gas Radiation Q E D E Activity Monitor
- At all times.
During Steam Jet Air Ejector operation. g:Vnwuphy~odcm~annexkdresden~dn12rl -8.doc 12-17
DRESDEN Revision 1.9 March 1999 TABLE 12.2-4 (Cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
- 1. Instrument indicates levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in OPERATE mode.
(b) Calibration shall include performance of a functional test (C) Instrument check to verify operability of sampler, that the sampler is in place and functioning properly. (d) Functional test shall be performed on local switches providing low flow alarm. Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. (7... g:'nurphyxodcm~annex'dresdendn12rl -8.doc 12-18
DRESDEN Revision 1.9 March 1999 12.2.C Liquid And Gaseous Effluents Instrumentation Bases
- 1. The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid and gaseous effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of RETS.
g:Vmurphy~odcm~annex~dresdendn12r1-8.doc 12-19
DRESDEN Revision 1.9 March 1999 12.3 LIQUID EFFLUENTS 12.3.A Liquid Effluents Limits and Reportinq Operability (
- 1. Concentration in Unrestricted Areas The concentration of radioactive material released from the site to unrestricted areas (at or beyond the site boundary, Dresden Station ODCM Annex, Appendix F, Figure F-i) shall be limited to the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402', for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the values listed in Table 12.3-1.
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, without delay decrease the release _{ rate of radioactive materials and/or increase the dilution flow rate to restore the . concentration to within the above limits.
- 2. Dose from Liquid Effluents The dose or dose commitment above background to a member of the public fr6m radioactive materials in liquid effluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following:
- 1. During any Calendar Quarter.
(1) Less than or equal to 3 mrem to the whole body. C (2) Less than or equal to 10 mrem to any organ.
- 2. During any Calendar Year.
(1) Less than or equal to 6 mrem to the whole body. (2) Less than or equal to 20 mrem to any organ.
- 3. With the calculated dose Srzm the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) and defines the corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with Sections 12.3.A.2.1 and 12.3A2.2. This is in lieu of a Licensee Event Report
'Upon technical specification approval, ten (10) times the Appendix B value may be used to determine the maximum instantaneous liquid release.
g:Vnurphykodcmnannex'resdenldn12rl-8.doc 12-20
DRESDEN Revision 1.9 March 1999 12.3.A Liquid Effluents Limits and Reportinq Operability (Cont'd)
- 4. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the limits of Sections 12.3.A.2.1 or 12.3.A.2.2.,
prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal tc 75 mrem) over 12 consecutive months. This Special Report shall inc. ide an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
- 5. When the projected annual whole body or any internal organ dose computed at the nearest downstream community water system is equal to or exceeds 2 mrem from all radioactive materials released in liquid effluents from the Station, prepare and submit a Special Report within 30 days to the operator of the community water system. The report is prepared to assist the operator in meeting the requirements of 40 CFR Part 141, EPA Primary Drinking Water Standards. A copy of this report will be sent to the NRC. This is in lieu of a Licensee Event Report
- 3. Dose Proiections At all times during processing prior to discharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to liquid effluent releases to unrestricted areas (Dresden Station ODCM Annex, Appendix F Figure F-i), when averaged over 31 days, exceeds 0.12 mrem to the total :ody or 0.40 mrem to any organa.
"These values represent 2% of the annual dose limits of Appendix I to 10CFR50.
g:\nurphy\odcmrannexdresden~dn12rl-8.doc 12-21
DRESDEN Revision 1.9 March 1999 12.3.A Liquid Effluents Limits and Reporting Operability (Cont'd)
- 4. Liquid Radioactive Waste Treatment System If liquid waste has to be or is being discharged without treatment as required
( above, prepare and submit to the Commission with 30 days, a report which includes the following information.
- 1. Identification of the defective equipment.
- 2. Cause of the defect in the equipment.
- 3. Action(s) taken to restore the equipment to an operating status.
- 4. Length of time the above requirements were not satisfied.
- 5. Volume and curie content of the waste discharged which was not processed by the appropriate equipment but which required processing.
- 6. Action(s) taken to prevent a recurrence of equipment failures.
This is in lieu of a Licensee Event Report.
- 5. System Operability and Plant Operations In the event a limit and/or associated action requirements identified in Sections 12.3.A and 12.3.8 cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.
12.3.B Liquid Effluents Surveillance
- 1. Concentration in Unrestricted Areas The concentration of radioactive material in unrestricted areas shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.3-2.
The sample analysis results will be used with the calculational methods in the ODCM to determine that the concentrations are within the limits of Section 12.3.A.1. g:\murphy'odcma\annex'lresdendnl12rl-8.doc 12-22
DRESDEN Revision 1.9 March 1999 12.3.B Liquid Effluents Surveillance (Cont'd)
- 2. Dose from Liquid Effluents The dose contribution from measured quantities of radioactive material shall be determined by calculation at least once per 31 days and cumulative summation of these total body and organ dosed shall be maintained for each calendar quarter.
Doses computed at the nearest community water system will consider only the drinking water pathway and shall be projected using the methods prescribed in ODCM, at least once per 92 days.
- 3. Dose Proiections Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in accordance with the ODCM.
g:Vnurphykodcmtannex~dresdendn1l2r14.doc 12-23
DRESDEN Revision 1.9 March 1999 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(.Ci/ml)* Kr-85m 2 x 10-4 Kr-85 5x 10-4 Kr-87 4 x 10"5 Kr-88 9 x 10s Ar-41 7 x 10 Xe-131m 7 x 10-4 4 Xe-133m 5x 10 Xe-133 6x 10-4 Xe-135m 2x 104 Xe-1 35 2 x 104 Computed from Equation 20 of ICRP Publication 2 (1959). adjusted for infinite cloud submersion in W - ,-, water, and R = 0.01 rem/week, density = 1.0 g/cc and Pw/Pt = 1.0. (: -? . g:\m~urp hy*olcm~annex~dresden~dn 12rl-8.doc 12-24
DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)(1' (pCi/mi) TYPE FREQUENCY( 6) FREQUENCY(6) Above See TS 314.8.J See TS 3/4.8.J Principal Gamma 5x1O-7 Ground Emitters 5s) Liquid Storage Dissolved & Entrained .1x10 4 Tanks Gases(6) (Gamma Emitters) m-km imwk~-innnny~tracan~nl'r1 ..Q 4-, 12-25
DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNITS 2 & 3 C LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)(10 (pCi/ml) TYPE FREQUENCY(6) FREQUENCY(6) A. Batch Prior to Prior to Principal Gamma 5x10"7 Release Each Batch Each Batch Emitters'5 ) Tanks 1-131 1x10 4 Prior to M Gross Alpha 1x10"7 Each Batch Composite(2) H-3 1X10"4 Prior to Q Fe-55 1x10 4 Each Batch Composite (2) Sr-89, Sr-90 5x10" Prior to M Dissolved & Entrained lx10is One Batch/M Gases (6)(Gamma Emitters) .____ B. Plant M(3) Mm3) 1-131 1x104 Continuous (Grab Sample) Releases(4 ) MM 3
) M(3) Principal Gamma 5x10"7 (Grab Sample) Emitters(5)
M(3) M(3) Dissolved & Entrained lx10"6 (Grab Sample) Gases(6 ) (Gamma Emitters) 3 M( ) M(3) H-3 lxi10" (Grab Sample) " Gross Alpha lX10-7 Q(3) Q(3) Sr-89, Sr-90 5x10 .. (Grab Sample) _ "___ Fe-55 lx10 4 C. Above Ground See TS 3/4.8.J See TS 3/4.8.J Principal Gamma 5x10"7 Liquid Storage Emitters'5) Tanks Dissolved &Entrained lx10"5 Gases(O (Gamma Emitters) g:\murphy~odcm~annex'dresdenldn12rl-8.doc 12-26
DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 (Cont'd) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (11 The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = 4.66Sh E - V - 2.22 x 106'- Y - exp (-4At) Where: LLD = the lower limit of detection (microCuries per unit mass or volume), sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, A.= the radioactive decay constant for the particular radionuclide (sec .1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and At should be used in the calculation. Alternate LLD Methodoloqy An alternate methodology for LLD determination follows and is similar to the above LLD equation: (2.71 + 4.654B)- Decay LLD = E q b Y t (2.22E06) g:murphy odam~annexdresdenkdn 1201-8.doc 12-27
DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 (Continued) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where: B = background sum (counts) E = counting efficiency, (counts detected/disintegrations) q = sample quantity, (mass or volume) b = abundance, (if applicable) Y = fractional radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microCurie (2.71 + 4.654B) = k2 + (2k 4l2 4 B), and k = 1.645. (k--value of the t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result -,. represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.) Decay = ex& [XRT/(1 -ex'r)] [XTd /(1 -e4.Td)], (if applicable) X = radioactive decay constant, (units consistent with At, RT and Td) At = 'delta r, or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with X) RT = elapsed real time, or the duration of the sample count, (units consistent with X)
"Td sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with X)
The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this alternate method will result in a more accurate determination of the LLD. It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement. g:\murphy~odc\2annex~dresden~dn12rl-8.doc 12-28
DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 (Cont'd) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (2) A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. (3) If the alarm setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the frequency of analysis shall be increased to daily until the condition no longer exists. (4) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the release. (5) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Other peaks which are measurable and identifiable by gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on i sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. (6) The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-1 38. Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. g:\murphy\odcm\annex\dresdenldn 12r -8.doc 12-29
DRESDEN Revision 1.9 March 1999 12.3.C LIQUID EFFLUENTS BASES
- 1. Concentration .
This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001 20.2402.
- 2. Dose This specification is provided to implement the requirements of Sections II.A, IIL.A and IV.A of Appendix I, 10 CFR Part 50. The operational requirements implements the guides set forth in Section IL.A of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable". The dose calculations in the ODCM implement the requirements in Section IiI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actua exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I",April 1977.
NUREG-01 13 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113.
.3. Liquid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.0 of Appendix I to 10 CFR Part 50.
( g:'imuphy'*lcnnex~dresden~ln 12rl-8.doc 12-30
DRESDEN Revision 1.9 March 1999 12.3.C LIQUID EFFLUENTS BASES - (Continued)
- 4. Mechanical Vacuum Pump The purpose of isolating the mechanical vacuum line is to limit release of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam line to the main condenser. The fission product radioactivity would be sensed by the main steamline radioactivit/ monitors which initiate isolation.
g:Vmurphy\odcm~annex~dresden~ln12rl -8.doc 12-31
DRESDEN Revision 1.9 March 1999 12.4 GASEOUS EFFLUENTS A. Gaseous Effluents Limits and Reportinq Operability (
- 1. Dose Rate The dose rate in unrestricted areas at or beyond the site boundary (Dresden Station ODCM Annex, Appendix F, Figure F-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following.
- 1. For Noble Gases:
(1) Less than a dose rate of 500 mrem/year to the whole body. (2) Less than a dose rate of 3000 mremryear to the skin.
- 2. For iodine-1 31, for iodine-1 33, tritium and for all radionuclides in particulate form with half-lives greater than 8 days, less than a dose rate of 1500 mrem-year.
- 3. Ifthe dose rates exceed the above limits, without delay decrease the release rates to bring the dose rates within the limits, and provide notification to the Commission (per 10 CFR Part 20.2203).
- 2. Noble Gas Dose The air dose in unrestricted areas at or beyond the site boundary due to noble gases released in gaseous effluents from the unit shall be limited to the following:
- 1. For Gamma Radiation (
(1) Less than or equal to 5 mrad during any calendar quarter. (2) Less than or equal to 10 mrad during any calendar year.
- 2. For Beta Radiation (1) Less than or equal to 10 mrad during any calendar quarter.
(2) Less than or equal to 20 mrad during any calendar year.
- 3. With the calculated air dose from radioactive noble gases in gaseous -- .
effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to ensure that future releases are in compliance with Sections 12.4.A.2.1 and . 12.4.A.2.2. This is in lieu of a Licensee Event Report. n *n mv lr~nrxd nd 12r1 -8 doc: 12-32
DRESDEN Revision 1.9 March 1999 12.4.A Gaseous Effluents Limits and Reporting Operability (Cont'd)
- 4. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding the limits of Sections 12.4.A.2.1 or 12.4.A.2.2, prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the doses or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
- 5. Process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to gaseous effluents released to the unrestricted areas, when averaged over 31 days, exceeds 2% of the annual dose limits of Appendix I to 10CFR50.
- 3. iodine-1 31, Iodine-1 33, Tritium, and Particulate Dose The dose to a member of the public in unrestricted areas at or beyond the site boundary from iodine-1 31, iodine-I 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit shall be limited to the following.
- 1. Less than or equal to 7.5 mrem to any organ during any calendar quarter.
- 2. Less than or equal to 15 mrem to any organ during any calendar year.
- 3. With the calculated dose from the release of iodine-131, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to ensure that future releases are in compliance with Section 12.4.A.3.1 and 12.4.A.3.2. This is in lieu of a Licensee Event Report.
- 4. With the calculated dose from the release of iodine-131, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding the limits of Sections 12.4.A.3.1. or 12.4.A.3.2.,
prepare and submit a Special Report to the Commission within 30 days and limit subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel sources g:*murphy\odcm'annex~lresden\dn12r1 -8.doc 12-33
DRESDEN Revision 1.9 March 1999 12.4.A Gaseous Effluents Limits and Reporting Operability (Cont'd) is limited to less than or equal to 25 mrem to the total body or organ (except ( the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
- 5. Process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to gaseous effluents released to the unrestricted areas, when averaged over 31 days, exceeds 2% of the annual dose limits of Appendix I to 10CFR50.
- 4. Off-Gas Treatment At all times during processing for discharge to the environs, process and control equipment provided to reduce the amount of concentration of radioactive materials shall be operated.
- 2. The above specification shall not apply for the Off-Gas Charcoal Adsorber Beds below 30 percent of rated thermal, power. (7
- 3. The recombiner shall be operable whenever the reactor is operating at a pressure greater than 900 psig.
- 4. The recombiner may be inoperable for 48 hours.
- 5. With either the recombiners inoperable, or all charcoal beds by-passed for more than 7 days in a calendar quarter while operating above 30 percent of the rated thermal power, prepare and submit to the Commission within 30 days a Special Report which includes the following information.
- a. Identification of the defective equipment
- b. Cause of the defect in the equipment
- c. Action(s) taken to restore the equipment to an operating status.
- d. Length of time the above requirements were not satisfied.
- e. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.
g:*,urphy~odcmn.an nex~d resdenln1 12rl -8.doc ( 12-34
DRESDEN Revision 1.9 March 1999 12.4.A Gaseous Effluents Limits and Reporting Operability (Cont'd)
- f. Action(s) taken to prevent a recurrence of equipment failures.
This is in lieu of a Licensee Event Report.
- 5. Main Condenser Air Eiector The release rate of the sum of the activities from the noble gases measured at the main condenser air ejector shall be limited to < 100 microcuries/sec per MWt (after 30 minutes decay) when in modes 1,23, and 3a. With the release rate of the sum of the activities from noble gases at the main condenser air ejector effluent (as measured prior to the offgas holdup line) > 100 microcuries/sec per MWt, after 30 minutes decay, restore the release rate to within its limits within 72 hours, or be in at least STARTUP with the main steam isolation valves closed within the next 8 hours. (Refer to Technical Specification 3.8.1.)
- 6. System Operability and Plant Operations In the event a limit and/or associated action requirements identified in Sections 12.4.A and 12.4.B cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational conditiori of the plant, and this does not prevent the plant from entry into any operational mode.
"aWhenthe main condenser air ejector is in operation.
g:\nurphyocm annexdresden~ln12r1-8.doc 12-35
DRESDEN Revision 1.9 March 1999 12.4.B Gaseous Effluents Surveillance SDose Rate C The dose rates due to radioactive materials released in gaseous effluents from the site shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.4-1. The dose rates are calculated using methods prescribed in the ODCM.
- 2. Noble Gas Dose The air dose due to releases of radioactive noble gases in gaseous effluents shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Sections A and B of Table 12.4-1. The allocation of effluents between units having shared effluent control system and the determination of cumulative and projected dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.
- 3. Iodine-1 31, lodine-133, Tritium and Particulate Dose The dose to a member of the public due to releases of iodine-131, iodine-133, Iitium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.4-1.
For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be estimated .= by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses when possible. The allocation of effluents between units having shared effluent control system and the determination of cumulative and projected dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.
- 4. Off-Gas Treatment Doses due to treated gases released to unrestricted areas at or beyond the site .. ; -,
boundary shall be projected at least once per 31 days in accordance with the ODCM. g:\rmurphy~odcmannex~dresden~dn12r1-8.doc 12-36
DRESDEN Revision 1.9 March 1999 12.4.8 Gaseous Effluents Surveillance - Continued
- 5. Noble Gases at the Main Condenser Air Eiector The release rate of noble gases from the main condenser air ejector shall be continuously monitored. The release rate of the sum of the activities from noble gases from the main condenser air ejector shall be determined to be within the limits of 12.4.A.5 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the recombiner outlet, or at the air ejector outlet ifthe recombiner is by-passed.
- 1. At least once per 31 days.
- 2. Within 4 hours following determination of an increase of greater than 50%.
(Refer to Technical Specification 4.8.1.) g:Vnurphy~odcm~annex~lresden~dn1 2r0-8.doc 12-37
DRESDEN Revision 1.9 March 1999 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNIT I GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION (LLD)(') TYPE FREQUENCY (pCiVml) A. Main M M Principal Gamma 1x1O4 Chimney (Grab Sample) Emitters (5) Tritium 1X10"6 Noble Gases lx10-6 46 M (3) 1-131 lXl0"12 M( , ) (Continuous) Iodine Sample 1-133 lx10"10 M(6) M (3) Principal Gamma 1x10-1 (Continuous) Particulate Sample Emitters (5) Q Q Sr-89, Sr-90 1x10"I1 (*: (Continuous) Composite Gross Alpha Particulate Sample 1 1 _1 ( g:\murphy~odcmrannex~dresden'dn1 2rl -8.doc 12-38
DRESDEN Revision 1.9 March 1999 Table 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNITS 2 & 3 LOWER LIMIT GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION TYPE FREQUENCY (LLD)(') (pCi/ml) A. Main M M(2) Principal Chimney (Grab Sample) Gamma Emitters(5 ) lx10"4 Reactor Bldg. M Tritium 1x104" Vent Stack B. All Continuous(4) W[3) 1-131 1x10-12 Release Iodine Sample 1-133 lx10-10 Types as Listed in A above Continuous(4) W(3 ) Principal Gamma lxi0-11 Particulate Sample Emitters 0) Continuous(l) Q Sr-89 lx1O"11 Composite Particulate Sample Sr-90 lx1041 Continuous('4 Q Gross Alpha 1x10-11 Composite Particulate Sample C. Main Confinuous(4) Noble Gas Monitor Noble Gases 1X10"6 Chimney D. Reactor Coninuous(4) Noble Gas Monitor Noble Gases lX10"4 Bldg. Vent Stack g:\murphy~odcm~annex~resden'dn12rl-8.doc 12-39
DRESDEN Revision 1.9 March 1999 TABLE 12.4-1 (Contrd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM C TABLE NOTATION (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = 4.66S, E - V - 2.22 x 106 ;Y - exp (-XAt) Where: LLD = the lower limit of detection (microCuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per microCurie, C Y = the fractional radiochemical yield, when applicable, X= the radioactive decay constant for the particular radionuclide (sec .1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and At should be used in the calculation. Alternate LLD Methodology An alternate methodology for LLD determination follows and is similar to the above LLD equation: (2.71 + 4.654B)* Decay LLD = E q b Y t (2.22E06) g:nu rphy'olcm~an nex~resden~dnl 2r-8.doc 12-40
DRESDEN Revision 1.9 March 1999 TABLE 12.4-1 (Continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where: B = background sum (counts) E = counting efficiency, (counts detected/disintegrations) q = sample quantity, (mass or volume) b = abundance, (if applicable) Y fractional radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microCurie (2.71 + 4.6541B) = k2 + (2k *42 4 B), and k = 1.645. (k--value of the t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.) Decay = e11 [.RT/(1-exRT)] [xTd/(1-e'Td)], (if applicable) X = radioactive decay constant, (units consistent with At, RT and Td) At = *delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample. (units consistent with X) RT = elapsed real time, or the duration of the sample count, (units consistent with X)
"Td= sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with X)
The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this alternate method will result in a more accurate determination of the LLD. It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement. g:Vnurphy~odcm~annexlresden~ln1 2r1 -8.doc 12-41
DRESDEN Revision 1.9 March 1999 TABLE 12.4-1 (Cont'd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM. TABLE NOTATION (2) Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal power in 1 hour unless (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. (3) Samples shall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. Sampling shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. (4) The ratio of sample flow rate to the sampled stream flow rate shall be known. (5) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-i 33, Xe-I 33m, Xe-1 35, and Xe-I 38 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the ( analyses shall not be reported as being present at the LLD level for the nuclide. (6) Analysis frequency shall be increased to I/week if release rates exceed 1% of any applicable limit referenced in the ODCM, when added to Units 2 and 3 airborne effluents. a:nurohvyodcm'annex~dresdendn1 2rl-8.doc 12-42
DRESDEN Revision 1.9 March 1999 12.4.C Gaseous Effluents Bases
- 1. Gaseous Effluents, Dose This Section is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on site will be within the annual dose limits of IOCFR20 for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20.1001-2402. The release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculation doses resulting from airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release point
- 2. Dose, Noble Gases This Section is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.3 of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section ilI.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion and of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1,
July 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. g:\murphy*odcm'annex~dresden1dn1 2r0-8.doc 12-43
DRESDEN Revision 1.9 March 1999 12.4.C Gaseous Effluents Bases (Contd)
- 3. Dose, Radioiodines, Radioactive Material in Particulate Form and Radionuclides Other (
than Noble Gases This Section is provided to implement the requirements of Sections ll.C, ilI.A and lV.A of Appendix I, 10 CFR Part 50. The Operability Requirements are the guides set forth in Section II.C of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section IIL.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109.
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"
Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate limits for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these limits were: 1) * . individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man.
- 4. Gaseous Waste Treatment The operability of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment The requirement that the appropriate portions of this system be operable when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.
g:\murphyodcnfannex~dresdenfdnf 2r1 -8.doc 12-44
DRESDEN Revision 1.9 March 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 " Monitoring Program Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Aoplicability: At all times. Action:
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule ifspecimens are unobtainable due to hazardous conditions, seasonal availability, malfunction of sampling equipment ifa person/business who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report
- 2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.B, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.A.2, 12.4.A.2, or 12.4.A.3. When more than one of the radionuclides in Table 12.5-2 are detected in the sampling medium, this report shall be submitted if.
concentration (1) . concentration (2) + ...> 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.A.2, 12.4.A.2, or 12.4.A.3. This report is not required ifthe measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
g:\murphy~odcm~annexlresden~dn12rl-8.doc 12-45
DRESDEN Revision 1.9 March 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)
- 3. If the sample type or sampling location(s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Prepare and submit controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples. Surveillance Requirements 12.5.1.8 The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure(s) in the ODCM.and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3. Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). g:Vnurphy\odcm\annex'dresden~dn1 2r1-8.doc 12-46
DRESDEN Revision 1.9 March 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Interpretations 12.5. 1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking. g:Vnurphy\odcm\annex~dresden~dn12r1 -8.doc 12-47
DRESDEN Revision March 19991.9 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND EXPOSURE PATHWAY FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS") FREQUENCY ANALYSIS Samples from a total of eight locations: Continuous particulate sampler Radioiodine Canister:
- 1. Airborne 1-131 analysis biweekly Radioiodine and operation with sample collection
- a. Indicator- Near Field weekly, or more frequently if on near field samples and Particulates required due to dust loading, and control.(2 )
Four samples from locations within 4 km (2.5 mi) radioiodine canister collection in different sectors. biweekly. Particulate Sampler: Gross beta analysis
- b. Indicator- Far Field following weekly filter change(I3 and gamma isotopic analysis14)
Four additional locations within 4 to 10 km (2.5 to 6.2 mi) in different sectors. quarterly on composite filters by location on near
- c. Control field samples and control.(2)
One sample from a control location within 10 to 30 km (6.2 to 18.6 mi). 9:VnufphyoftmonrwxdresdonWni2ri-8.doO
DRESDEN Revision 1.9 March 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/ OR SAMPLE AND SAMPLE LOCATIONS") FREQUENCY FREQUENCY OF ANALYSIS
- 2. Direct Forty routine monitoring stations either with a Quarterly Gamma dose on each Radiation(5) thermoluminescent dosimeter (TLD) or with one TLD quarterly.
instrument for measuring dose rate continuously, placed as follows:
- a. Indicator- Inner Ring (100 Series TLD)
One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 2 miles);
- b. Indicator- Outer Ring (200 Series TLD)
One in each meteorological sector, within 3.2 to 10 km (2 to 6.2 mi); and
- c. Other One at each Airborne location given in part l.a. and 1.b.
The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.
, (300 Series TLD) 9:Vnurphyiocm~winbxids~den~dn12r1-8.doa 12-49
DRESDEN Revision March 19991.9 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND COLLECTION TYPE AND EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONSM 13 FREQUENCY FREQUENCY OF AND/ OR SAMPLE ANALYSIS Quarterly Gamma dose on each
- 2. Direct d. Control TLD quarterly.
Radiation(5 ) (Cont'd) One at each Airborne control location given in part 1.c Quarterly Gamma isotopic0) and
- 3. Waterborne a. Indicator tritium analysis quarterly.
- a. Ground/ Well Samples from three sources only if likely to be affected.(6)
Weekly grab samples. Gross beta and gamma
- b. Drinking(7) a. Indicator isotopic analyses(4) on monthly composite; One Sample from each community drinking tritium analysis on water supply that could be affected by the quarterly composite.
station discharge within 10 km (6.2 mi) downstream of discharge. Weekly grab samples. Gross beta and gamma
- c. Surface If no community water supply (Drinking Water) isotopic analyses(4) on Water(7) exists within 10 km downstream of discharge monthly composite; then surface water sampling shall be performed. tritium analysis on quarterly composite.
- a. Indicator One sample downstream Weekly grab samples. Gross beta and gamma
- d. Control a. Control isotopic analyses(4) on Sample(7 ) monthly composite; One surface sample upstream of discharge. tritium analysis on quarterly composite.
"hy1odrn1nrannxiredwseI12r1-8doO
'1,
DRESDEN Revision 1.9 March 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/ OR SAMPLE AND SAMPLE LOCATIONS") FREQUENCY FREQUENCY OF ANALYSIS
- e. Sediment a. Indicator Semiannually. Gamma 4isotopic 7 analysis ) semiannually.
)area At least one sample from downstreamM within 10 km (6.2 mi).
- 4. Ingestion a. Indicator Biweekly (9)when animals are on Gamma isotopic(4) and pasture (May through October), 1-131(10) analysis on each
- a. Milk (8) Samples from milking animals from a monthly at other times sample.
maximum of three locations within 10 km (November through April). (6.2 mi) distance.
- b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi).
- b. Fish a. Indicator Two times annually. Gamma isotopic analysis(4) on edible Representative samples of commercially and portions recreationally important species In discharge area.
- b. Control Representative samples of commercially and recreatlonally important species Incontrol locations upstream of discharge.
a.,%ffwmhvodmannoxWroadenidnl2rl-g-doe 44 12-51
DRESDEN Revision1999 March 1.9 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TYPE AND
' .... ... . . .*EEMWA-rn,-
. NUM ~~~~ RA21 F~u~.-.
- Q I QA UPI
~ AND COLLECTION INGI ~ -TP ANDl~4IEV EXPOSURE PATHWAY NUMtrAK ND SAMPLE KSPLEILýCANTiNlvrr FREQUENCY FREQUENCY AND LOCATIONSM ANALYSIS OF AND/ OR SAMPLE Gamma isotopict4 )
analysis on each sample. __ _ __ __ _ __ _ - I
- c. Food Products a. Indicator /'11 II I I1,1 g I1*
Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi): At least one root vegetable sample(") At least one broad leaf vegetable (or vegetation)(1"
- b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi). -j I,.
g:mwpdaiianpexkSSdSflfl12f14.dOO l j2
DRESDEN Revision 1.9 March 1999 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 1.1-1 of the ODCM Station Annexes. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Radiation Protection Director. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (7) The "downstream" sample shall be taken in an area beyond but near the mixing zone. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence. (8) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling may be discontinued. (9) Biweekly refers to every two weeks. (10) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. (11) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container. g:\murphy:odcmrannex~dresden\dn12r1-8.doc 12-53
DRESDEN Revision March 1.9 1999 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS wet) WATER (pCi/kg, wet) (pCi/I) (pCilkg, ANALYSIS (pCi/I) OR GASES (pCilm 3) H-3 20,000(') Mn-54 1,000 30,000 10,000 Fe-59 400 30,000 Co-58 1,000 10,000 Co-60 300 20,000 Zn-65 300 Zr-Nb-95 400 2(2) 0.9 3 100 1-131
. AAA 4 Ann Cs-134 30 10 1,00 ouI,uu 20 2,000 70 2,000 Cs-137 50 200 300 Ba-La-140 exists, a value of 30,000 pCi/I (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway may be used.
(2) If no drinking water pathway exists, a value of 20 pCi/I may be used. g:,ph y k nexdresdenWd n:,12t41.do .
,Th
DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISM 1' 2 LOWER LIMIT OF DETECTION (LLD)' )(3) WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/I) OR GASES (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry) Gross Beta 4 0.01 1000 H-3 2,000(l) Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131(6) 1/15(4) 0.07 100 0.5/5(5) 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 g:nmurphy~odcm~annexresdenWn12rl-8.doc 12-55
DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended 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. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. (3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will-be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "rear signal. For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows: 4.66 Sb + 3/tb LLD = (E) (V) (2.22) (Y) (exp (-XAt)) 4.66 Sb LLD .. (E) (V) (2.22) (Y) (exp (-X;t)) Where: 4.66 Sb >> 3/t, LLD = the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute), JTotal Counts tb E = the counting efficiency(counts per disintegration), V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picoCurie, Y = the fractional radiochemical yield, when applicable, S = the radioactive decay constant for the particular radionuclide (sec"), g:\murphy\odcm\annex~dresdendn1 2r1-8.doc 12-56
DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS t = counting time of the background or blank (minutes), and t= the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec). Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an 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, 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. Alternate LLD Methodology -. An alternate methodology for LLD determination follows and is similar to the above LLD equation: (2.71 + 4.654IB)o Decay LLD = __ __ __ _-_-__ -__ EqbYt(2.22E06) Where: B = background sum (counts) E = counting efficiency, (counts detected/disintegrations) q = sample quantity, (mass or volume) b = abundance, (ifapplicable) Y = fractional radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microCurie (2.71 + 4.654B) = k2 + (2k 4 2 4 B), and k = 1.645. (k--value of the t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.) Decay = ex [XRT/(1 -ekeT)] [LTd /(1 -e-4Td)], (ifapplicable) g:\murphy\odcm~annex~dresden~dn12r1-8.doc 12-57
DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS X = radioactive decay constant, (units consistent with At, RT and Td) At = "delta t, or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with X) RT = elapsed real time, or the duration of the sample count, (units consistent with X) T= sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with X) The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this alternate method will result in a more accurate determination of the LLD. It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement (4) If no drinking water pathway exists, the value of 15 pCi/I may be used. (5) A value of 0.5 pCi/I shall be used when the animals are on pasture (May through October) and a value of 5 pCi/I shall be used at all other times (November through April). (6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide. (7) This LLD is the minimum allowable, however, vendors performing environmental sample analyses off-site will be required to meet an LLD of 200 pCi/I. g:Wrurphykodcm~annex'dmresdenldn1 2r1-8.doc 12-58
DRESDEN Revision 1.9 March 1999 12.5.2 Land Use Census Operability Requirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors* of the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence. Applicability: At all times. Action:
- 1. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter
- 11. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring-program after October 31 of the'year in which this Land Use Census was conducted.
Submit in the next Annual Radiological Environmental Operating Report documentation for a change in theODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.
*This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.
"The nearest industrial facility shall also be documented ifcloser than the nearest residence.
Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. Land Use Census shall be included in the Annual Radiological Environmental The results of the Operating Report. 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Program given in the ODCM are made if required by the results of this census. Monitoring NI This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations. g:*murphykodcnannexdresdenrdn12rl-8.doc 12-59
DRESDEN Revision 1.9 March 1999 12.5.3 Interlaboratory Comparison Program Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1. Applicability: At all times. Action:
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. Bases 12.5.3.C The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks. on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
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DRESDEN Revision 1.9 March 1999 12.6 RECORDKEEPING AND REPORTING 12.6.1. Station Operating Records
- 1. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years.
- 1. Records and periodic checks, inspection and/or calibrations performed to verify the surveillance requirements (See the applicable surveillance in the Instrumentation, Liquid Effluents, Gaseous Effluents, and Radiological Environmental Monitoring Sections) are-being met All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.
- 2. Records of radioactive shipments.
- 2. Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant
- 1. Records of off-site environmental monitoring surveys.
- 2. Records of radioactivity in liquid and gaseous wastes released to the environment.
- 3. Records of reviews performed for changes made to the ODCM.
12.6.2. Reports
- 1. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted to the Commission prioi to April 1 of each year. The report shall Include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent-with the objectives outlined in the ODCM and PCP and (2) In conformance with 10 CFR Part 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
- 2. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May I of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives in (1) the ODCM and (2) Sections IV.B.2., IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. A detailed listing of the requirement of the report is given below g:mnuf~y~dcmannex~dmsden~In12r1-8.doc 12-61
DRESDEN Revision 1.9 March 1999 12.6.2 Reports - (Cont'd) (a) Results of environmental sampling summarized on a quarterly basis ( following the format of Regulatory Guide 4.8 Table 1 (December 1975); (individual sample results will be retained at the station); In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. Summaries, interpretations, and analysis of trends of the results are to be provided. (b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the ODCM. (c) Results of the census to determine the locations of animals producing milk for human consumption, and the pasture season feeding practices at dairies in the monitoring program. (d) The reason for the omission if the nearest dairy to the station is not in the monitoring program. (e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. (f) The results of the interlaboratory comparison program described in ( Section 12.5.3. (g) The results of the 40 CFR Part 190 uranium fuel cycle dose analysis for each calendar year. (h) A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the station.
- 3. Non-Routine Environmental Report (a) If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional Administrator of NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter. When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall have been exceeded if ZC/(RL)i is equal to or greater than 1 where C is the concentration of the ih radionuclide in the medium and RL is the reporting level of radionuclide i.
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DRESDEN Revision 1.9 March 1999 12.6.2 Reports - (Cont'd) (b) If radionuclides other than those in Table 12.5-2 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I. (c) This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous affect 12.6.3. Offsite Dose Calculation Manual (ODCM)
- 1. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring AlarmtTrip setpoints and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in Section 12.2 - 12.5 and (2),
descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Sections 12.6.2.1 and 12.6.2.2. The ODCM shall be subject to review and approval by the Commission prior to initial implementation.
- 2. Changes to the ODCM:
(1) Shall be documented and records of reviews performed shall be retained as required by Technical Specification 6.14.A. This documentation shall contain: (a) Sufficient information to support the change together with appropriate analyses or evaluations justifying the change(s); and (b) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20.1302, 40 CFR Part 190, 10 CFR Part 50.36a, and Appendix I to 10 CFR . Part.50 and not adversely impact the accuracy or reliability of effluent, dose or set point calculations. (2) Shall be effective after review and acceptance by Independent Technical Review and PORCIStation Manager, on the date specified by the revision package. g:nWu*hy~odcm~annexrdresdenwln12ri-8.doc 12-63
DRESDEN Revision 1.9 March 1999 12.6.3 Offsite Dose Calculation Manual (ODCM)-(Contfd) (3) Shall be submitted to the Commission in the form of a complete, legible ( copy of the entire OCM or updated pages, if the Commission retains a controlled copy. If an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented. 12.6.4. Maior Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) NOTE: This information may be submitted as part of the annual FSAR update. Licensee initiated major changes to the radioactive waste systems may be made provided: The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by Independent Technical Review. The discussion of each change shall contain: (1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; (2) Sufficient detailed information to support the reason for the change; (3) A detailed description of the equipment, components, and process .. involved and the interfaces with other plant systems; (4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments; (5) A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the period in which the changes were made; (6) An estimate of the exposure to plant operating personnel as a result of the change; and (7) Documentation of the fact that the change was reviewed and found acceptable by Independent Technical Review.
- 2. The change shall become effective upon review and acceptance by Independent Technical Review.
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