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{{Adams
#REDIRECT [[BSEP 13-0042, Off-Site Dose Calculation Manual, Revision 36]]
| number = ML13128A209
| issue date = 04/29/2013
| title = Off-Site Dose Calculation Manual, Revision 36
| author name =
| author affiliation = Carolina Power & Light Co, Duke Energy Progress, Inc
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000324, 05000325
| license number =
| contact person =
| case reference number = BSEP 13-0042
| document type = Calculation, Manual
| page count = 346
}}
 
=Text=
{{#Wiki_filter:BSEP 13-0042 Enclosure 2 Offsite Dose Calculation Manual Revision 36 BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)REVISION 36 DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY Effective Date Approved By:.4 (i1~~.j0, fLo PNSC kJ LIST OF EFFECTIVE PAGES Pages i iii iv V -vi vii -ix x xi 1-1 2-1 2 2 2-4 2-5 7 2-8 16 3-1 3-2 3-3 3-4 3-5 8 3-9 3-10-3-13 3-14 3-15 21 3-22 3-23 3-24 25 3-26 3-27 3-28 29 3-30 3-31 3-32 37 3-38 3-39 40a 3-41 3-42 43 3-44 3-45 3-46 66 3-67 71 4-1 2 4-3 4-4 4-5 4-6 4-7-4-13 5-1 5-2 5-3 Revision 36 30 35 36 25 30 35 30 34 35 30 25 35 36I 25 36 35 30 25 30 25 30 25 35 30 25 35 30 27 28 25 30 25 30 25 35 30 25 36 25 26 32 30 34 35 25 30 35 Pages 6-1 ii 7-iii 7-iv -7.1.1-1 7.1.1-2 7.1.1-3 7.1.1-4 -7.3.0-4 7.3.1-1 7.3.1-2 -7.3.1-3 7.3.1-4 7.3.1-5 7.3.1-6 7.3.1-7 7.3.2-1 7.3.2-2 -7.3.2-4 7.3.2-5 -7.3.2-6 7.3.2-7 7.3.2-8 7.3.2-9 -7.3.2-10 7.3.2-11 7.3.2-12 7.3.3-1 7.3.3-2 -7.3.3-3 7.3.3-4 7.3.3-5 -7.3.3-6 7.3.3-7 7.3.3-8 7.3.4-1 -7.3.7-1 7.3.7-2 7.3.7-3 7.3.7-4 7.3.8-1 -7.3.8-2 7.3.9-1 7.3.9-2 -7.3.15-5 7.3.15-6 -7.3.15-8 7.3.15-9 -7.3.15-10 7.3.15-11 7.3.15-12
-7.3.15-13 7.3.15-14 7.3.16-1 7.3.16-2 -7.4.0-2 7.4.0-3 7.5.0-1 -B 7.3.0-10 B 7.3.1-1 B 7.3.2-1 -B 7.3.2-2 B 7.3.3-1 B 7.3.4-1 -B 7.3.6-1 B 7.3.7-1 -B 7.3.8-1 B 7.3.9-1 Revision 25 30 25 30 27 25 29 25 35 26 25 35 29 25 33 26 25 33 36 32 25 35 31 35 25 31 25 30 25 30 25 31 25 35 25 26 25 36 30 25 30 25 29 33 35 25 30 31 Pages Revision B 7.3.10-1 -B 7.3.17-1 25 A- 1 -A-22 30 A-23 25 A-24 30 A-25 -A-26 25 A-27 30 A-28 25 B-1 -B-3 30 B-4 25 B-5 -B-36 30 C-1 -D-1 25 E-1 -E-3 35 F-1 25 F-2 26 F-3 32 G-1 25 H-1 -H-2 35."- 4 ODCM (BSEP)Rev. 36 TABLE OF CONTENTS Section SECTION 1 Title Page INTRODUCTION IN T R O D U C T IO N ..................................................................................................................
1-1 SECTION 2 LIQUID EFFLUENTS IN D E X T O S E C T IO N 2 ...........................................................................................................
2-1 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS)
...................................
2-3 2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS)
.................................
2-11 SECTION 3 GASEOUS EFFLUENTS IN D E X T O S E C T IO N 3 ...........................................................................................................
3 -1 3.1 MONITOR ALARM SETPOINT DETERMINATION
...................................
3-4 3.2 COMPLIANCE WITH ODCM SPECIFICATION 7.3.7 (GASEOUS)
.........
3-17 3.3 COMPLIANCE WITH 1OCFR50 (GASEOUS)
..........................................
3-35 SECTION 4 RADIOLOGICAL ENVIRONMENTAL PROGRAM INDEX TO SECTION 4 ...........................................................................................................
4-1 SECTION 5 RADIOLOGICAL INTERLABORATORY COMPARISON STUDIES INDEX TO SECTION 5 ...........................................................................................................
5-1 5 .1 O B J E C T IV E ..............................................................................................
5 -2 5.2 PROGRAM ...............................................................................................
5-2 SECTION 6 TOTAL DOSE (40CFR190)
COMPLIANCE INDEX TO SECTIO N 6 ...........................................................................................................
6-1 6.1 INTRO DUCTIO N .......................................................................................
6-2 6.2 G ENERAL .................................................................................................
6-2 6.3 CALCULATIO NS OF TOTAL BODY DO SE ..............................................
6-3 6.4 THYRO ID DO SE .......................................................................................
6-4 SECTION 7 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS AND BASES INDEX TO SECTION 7 ............................................................................................................
7-i 7.1 USE AND APPLICATIO N ...................................................................
7.1.1-1 7.2 NOT USED .......................................................................................
7.2.0-1 7.3 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)AND APPLICABILITY
.......................................................................
7.3.0-1 ODCM (BSEP)ii Rev. 30 TABLE OF CONTENTS Section 7.4 7.5 B 7.3 APPENDIX A APPENDIX B APPENDIX C APPENDIX D APPENDIX E APPENDIX F APPENDIX G APPENDIX H Title Pacqe REPO RTING REQ UIREM ENTS .........................................................
7.4.0-1 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT S Y S T E M S ...........................................................................................
7 .5.0 -1 B A S E S ............................................................................................
B 7 .3.0 -1 METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS
.............
A-3 CALCULATIONS OF Vi AND Bi VALUES FOR THE ELEVATED P L U M E ......................................................................................................
B -4 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND T R IT IU M ...................................................................................................
C -2 LOWER LIMIT OF DETECTION (LLD) ......................................................
D-1 RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUM ENTATIO N NUM BERS .............................................................
E-1 LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS .................
F-1 ODCM SOFTW ARE PACKAG E ...............................................................
G-1 x/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STABILIZATION FACILITY ....................................................
H-2 ODCM (BSEP)iii Rev. 35 LIST OF TABLES No.SECTION 2 2.1-1 2.2-1 SECTION 3 3.1-1 3.1-2 3.1-3 3.2-1 3.2-2 3.2-3 3.2-4 3.2-5 3.3-1 THRU 3.3-19 3.3-20 3.3-21 SECTION 4 4.0-1 SECTION 7 7.3.1-1 7.3.2-1 Title Page ECs FOR SELECTED RADIONUCLIDES
...............................................
2-10 Ait VALUES FO R THE ADULT .................................................................
2-13 GALE CODE 30 MINUTE AIR EJECTOR TECHNICAL SPEC IFICATIO N .................................................................
3-12 GASEO US SO URCE TERM S ..................................................................
3-15 DOSE FACTORS AND CONSTANTS
......................................................
3-16 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT ................
3-30 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSW ICK PLANT CENTER .......................................................
3-31 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK .........................
3-32 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
...................
3-33 Pi VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
3-34 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC P LA N T .....................................................................................................
3 -4 8 INHALATION DOSE FACTORS FOR CARBON-14
.................................
3-69 INGESTION DOSE FACTORS FOR CARBON-14
...................................
3-71 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..............
4-4 RADIOACTIVE LIQUID EFFLUENT MONITORING IN ST R U M E N TA T IO N ...........................................................................
7.3.1-7 RADIOACTIVE GASEOUS EFFLUENT MONITORING IN S T R U M E N TA T IO N ..........................................................................
.7.3.2-9 ODCM (BSEP)iv Rev. 36 LIST OF TABLES No. Title Page SECTION 7 (Cont'd)7.3.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P R O G R A M .........................................................................................
7 .3 .3-3 7.3.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM FOR POTENTIAL RELEASE PATHWAYS WHICH HAVE EXCEEDED TRIGGER LEVELS .............................................
7.3.3-6 7.3.7-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P R O G R A M .........................................................................................
7 .3 .7-2 7.3.15-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...... 7.3.15-6 7.3.15-2 LIMITS FOR THE LEVEL OF RADIOACTIVITY IN ENVIRO NM ENTAL SAM PLES .........................................................
7.3.15-11 7.3.15-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE A N A LY S IS ........................................................................................
7 .3 .15-12 APPENDIX A A-1 A-2 A-3 A-4 A-5 A-6 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS
........................................................
A-5 DEPLETED IXJQ VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS
........................................
A-6 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FRO M THE TURBINE BUILDING S ............................................................
A-7 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FRO M THE TURBINE BUILDINGS
............................................................
A-8 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS
........................................
A-9 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS
......................................................
A-10 ODCM (BSEP)V Rev- 25 LIST OF TABLES No. Title Page APPENDIX A (Cont'd)A-7 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS
....................................................
A-11 A-8 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS
.....................................
A-12 A-9 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS
........................................................
A-13 A-10 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
........................................................
A-14 A-11 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
.....................................
A-15 A-12 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
........................................................
A-16 A-13 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FR O M T H E STA C K ..................................................................................
A -17 A-14 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FRO M THE STACK ..............................................................
A-18 A-15 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FR O M T H E STA C K ..................................................................................
A -19 A-16 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FR O M T H E STA C K ..................................................................................
A -20 A-17 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FRO M THE STACK ..............................................................
A-21 A-18 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FR O M T H E STA C K ..................................................................................
A -22 A-19 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ" P R O G R A M ...............................................................................................
A -2 3 ODCM (BSEP)vi Rev. 25 LIST OF TABLES No. Title Page APPENDIX A (Cont'd)A-20 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC "XOQDOQ" P R O G R A M ..............................................................................................
A -2 6 APPENDIX B B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE S IT E B O U N D A R Y .....................................................................................
B -5 B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T .....................................................................................
B -6 B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE B O U N D A R Y ..............................................................................................
B -7 B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T .....................................................................................
B -8 B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE B O U N D A R Y ...............................................................................................
B -9 B-6 JOINT FREQUENCY DISTRIBUTION FOR THE NNE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC T R IC PLA NT ...............................................................................
B-10 B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE B O U N D A R Y ........................................................................................
B -11 B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LEC T R IC P LA N T ...............................................................................
B-12 B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE B O U N D A R Y .......................................................................................
B -13 B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -14 ODCM (BSEP)vii Rev. 30 LIST OF TABLES No. Title Page APPENDIX B (Cont'd)B-1 1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE S IT E B O U N D A R Y ....................................................................................
B -15 B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE ..T R IC P LA N T ...................................................................................
B -16 B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE S IT E B O U N D A R Y ....................................................................................
B-17 B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -18 B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE S IT E B O U N D A R Y .................................................................................
B -19 B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B-20 B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE B O U N D A R Y .............................................................................................
B -2 1 B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B-22 B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW S IT E B O U N D A R Y ....................................................................................
B-23 B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B-24 B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE B O U N D A R Y .............................................................................................
B -2 5 B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -26 ODCM (BSEP)viii Rev. 30 LIST OF TABLES No. Title Paqe APPENDIX B (Cont'd)B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW S IT E B O U N D A R Y ....................................................................................
B -27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -28 B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE B O U N D A R Y .............................................................................................
B -2 9 B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T .....................
: ...............................................
B-30 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW S IT E B O U N D A R Y ....................................................................................
B -3 1 B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -32 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE B O U N D A R Y .............................................................................................
B -3 3 B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -34 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE B O U N D A R Y .............................................................................................
B -3 5 B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
B -36 ODCM (BSEP)ix Rev. 30 LIST OF TABLES No.APPENDIX C C-1 C-2 C-3 APPENDIX H H-1 Title Paqe PARAMETERS FOR COW AND GOAT MILK PATHWAYS .....................
C-14 PARAMETERS FOR THE MEAT PATHWAY ...........................................
C-15 PARAMETERS FOR THE VEGETABLE PATHWAY ................................
C-16 x/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STABILIZATION FACILITY ....................................................
H-2 ODCM (BSEP)X Rev. 35 LIST OF FIGURES No. Title Page 4.0-1 BSEP Sample Point Locations
.................................................................
4-14 7.1.1-1 Site Boundary ..................................................................................
7.1.1-5 F-1 Liquid Radwaste Effluent System ...............................................................
F-2 F-2 Gaseous Radwaste Effluent System ..........................................................
F-3 ODCM (BSEP)xi Rev. 30 INTRODUCTION The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Brunswick Steam Electric Plant (BSEP) to show compliance with 10CFR20, 10CFR50.36a, Appendix I of 1OCFR50, 1OCFR72, 40CFR190, and to assure compliance with ODCM Specifications (ODCMS).The ODCM is based on "Radiological Effluent Technical Specifications for BWR's" (NUREG 0473, Draft), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United Stated Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are provided elsewhere.
These procedures will be utilized to assure compliance with ODCMS and Test Requirements (TRs) provided in the Radioactive Effluents Control Program.The ODCM has been prepared as generically as possible to minimize the need for future revisions.
Any changes to the ODCM will be reviewed and approved as indicated in the Administrative Control section of the BSEP Technical Specifications.
The Radioactive Effluent Release Report prepared after January 1 of each year will include an assessment of the annual radiation doses to members of the public from radioactive liquid and gaseous effluents using the methodology in the ODCM for the report period. This report will be inclusive of the requirements outlined in the BSEP Technical Specifications and ODCM Specifications.
ODCM (BSEP)1-1 Rev. 34 1 INDEX 2.0 LIQUID EFFLUENT .....................................................................................................
2-3 2.1 COM PLIANCE W ITH 10CFR PART 20 (LIQUIDS)
................................................
2-3 2.1.1 Batch Releases ..........................................................................................
2-3 2.1.2 Continuous Releases .................................................................................
2-8 2.1.3 Stabilization Pond and Stabilization Facility Releases ................................
2-9 2.1.4 Groundwater Extraction System Releases .................................................
2-9 2.1.5 Marsh Releases ......................................................................................
2-10 2.2 COM PLIANCE W ITH 10CFR PART 50 (LIQUIDS)
..............................................
2-12 2.2.1 Cum ulation of Doses ................................................................................
2-12 2.2.2 Projection of Doses ..................................................................................
2-13 ODCM (BSEP)2-1 Rev. 35 LIST OF TABLES Title Table No.SECTION 2 2.1-1 2.2-1 Page ECs FOR SELECTED RADIONUCLIDES
................................................
2-11 A,t VALUES FO R THE ADU LT .................................................................
2-14 ODCM (BSEP)2-2 Rev. 35
 
===2.0 LIQUID===
EFFLUENT 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS)2.1.1 Batch Releases A batch release is the discharge of liquid waste of a discrete volume. Batch releases from the BSEP liquid radwaste system may occur from the waste sample tank, floor drain sample tank, detergent drain tank and the salt water tanks. The maximum release rate possible due to pump capacity is 200 GPM from all release tanks except the detergent drain tank, which has a maximum release rate of 50 GPM. All of the above liquid radwaste discharges go to the circulating water discharge canal. Circulating water leakage collected in the circulating water pits and low purity, low activity liquids are transferred to the salt water release tanks where they are recirculated, sampled, and released to the environment.
For any batch release, if the radwaste monitor effluent is inoperable, then two independent samples are analyzed and must be within 15% of each other before the release is approved.
The two samples may differ by more than 15% upon approval of the E&C Supervisor or equivalent.
The maximum release rate is determined so that 1OCFR Part 20 limits are not exceeded after dilution in the discharge canal.The sampling and analysis frequency and the type of analysis required by the BSEP ODCM Specifications is given in Table 7.3.3-1. All applicable instrument numbers may be found in Appendix E.1 .Prerelease The radioactive content of each batch release will be determined prior to release in accordance with Table 7.3.3-1 of the BSEP ODCM Specifications.
Compliance with 1OCFR Part 20 will be shown in the following manner: a. Minimum acceptable dilution factor: DFo Y4 Ci (Eq. 2.1-1)Where: DFo Minimum acceptable dilution factor determined from analysis of liquid effluent to be released.C, = Concentration of radionuclide i in the batch to be released, pCi/ml EC Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 1OCFR20, pCi/ml ODOM (BSEP)2-3 Rev. 30 DFB Where: (10) (DFo)(Eq. 2.1-2)DFB 1 Conservative dilution factor used by BSEP to calculate maximum release rate prior to release in order to assure compliance with 10CFR Part 20 10 A factor of 10 less than 10CFR Part 20 limits as specified in Appendix B, Table 2, Column 2. This factor represents one layer of conservatism for all releases at BSEP DFO Minimum acceptable dilution factor per Equation 2.1-1 b. Maximum release rate: MRR n -1(RPFcw) + p -l(RPFsv) (Eq. 2.1-3)2(DFB)Where: MRR = Maximum release rate of the batch to be released, GPM n = Number of operating circulating water pumps p = Number of operating service water pumps RPFcw = Minimum rated pump flow of each circulating water pump= 1.357 E5 GPM RPFsw = Rated pump flow of each service water pump 8 E3 GPM 2 = Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response DFB = Minimum acceptable dilution factor (DFo) made conservative by a factor of 10 per Equation 2.1-2 ODCM (BSEP)2-4 Rev. 30 1
: c. Monitor Alarm/Trip Setpoint: Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. An effluent concentration (EC) of 2 E-4 pCi/ml has been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that Xenon-1 35 is the controlling radionuclide.(NUREG 0133)SP -CT (ErX(n -1XRPFcw)+ (P -1XRPFSw )I RR +Bkg (Eq. 2.1-4)Where: SP = Monitor alarm/trip setpoint, cps Em = The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps/pCi/ml CT -3 E-7 [tCi/ml; engineering factor to ensure that the final concentration for the mixture of radionuclides will be less than 10CFR Part 20 limits at unrestricted areas n = Number of operating circulating water pumps p = Number of operating service water pumps RPFcw = 1.357 E5GPM RPFsw = 8 E3 GPM RR = 200 GPM; maximum design release rate Bkg = Background count rate due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid, cps SP 3 E- 7(Emr(n- 1X1.357 E5)+ (p- 1X8.0 E3)] + Bkg (Eq. 2.1-5)200 ODCM (BSEP)2-5 Rev. 25
: d. Calculated concentration at unrestricted area: Conci (C,) (MRR) (Eq. 2.1-6)(n -1) (RPFcw) + (p -1) (RPFsw)Where: Conci Calculated concentration of radionuclide i at the unrestricted area, pCi/ml C, = Concentration of radionuclide i in the batch to be released, pCi/ml MRR = Maximum release rate of the batch to be released (see Equation 2.1-3), GPM n = Number of operating circulating water pumps p = Number of operating service water pumps RPFcw = 1.357 E5 GPM RPFsw = 8 E3 GPM e. 10CFR Part 20 Prerelease Compliance Check: Before initiating the batch release, one final check for compliance with 1 OCFR Part 20 will be performed.
If the calculated dilution factor at the unrestricted area is less than or equal to 1, then 1 OCFR Part 20 limits have been met. The following equation must be true: YXi(CONCi/Eci)
< 1 (Eq. 2.1-7)Where: Conci Concentration of radionuclide i at the unrestricted area per Equation 2.1-6, pCi/mI EC = Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, pCi/ml.ODCM (BSEP)2-6 Rev. 25
: 2. Postrelease The actual concentration of each radionuclide following release from a batch tank will be calculated to show final compliance with 10CFR Part 20 as follows: a. Actual concentration at unrestricted area: Concik (Ci) N, (Eq. 2.1-8)VdIII Where: ConCik Ci Veff Vdil Where: n p RPFcw RPFsw tk Where: Concik ECi The actual concentration of radionuclide i at the unrestricted area during release k, itCi/ml= Concentration of radionuclide i in the batch released, pCi/ml= Actual volume of liquid effluent released, gal= Actual volume of dilution water during release k, gal= [n (RPFcw) + P (RPFsw)] (tW)= Number of operating circulating water pumps= Number of operating service water pumps= 1.357 E5 GPM= 8 E3 GPM= Total release time, min b. 10CFR Part 20 Postrelease Compliance Check: To show final compliance with 1 OCFR Part 20, the following relationship must hold: Xi (Concik/ECi)
_< 1 (Eq. 2.1-9)The actual concentration of radionuclide i during release k (from Equation 2.1-8), pCi/ml Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, ptCi/ml.ODCM (BSEP)2-7 Rev. 25 2.1.2.Continuous Releases 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. The Groundwater Extraction System is considered a continuous release. The potential for a continuous release exists in the service water system. Weekly tests are performed on the service water system during system operation as specified in Table 7.3.3-1 of the BSEP ODCM Specifications.
For continuous releases, the concentration of various radionuclides in the unrestricted area would be calculated using Equation 2.1-8 with C, being the concentration of radionuclide i in the continuous release stream. To show compliance with 10CFR Part 20, the sum of the concentration of radionuclide i in the unrestricted area due to both continuous and batch releases divided by that isotope's EC must again be less than 1.1. Service Water Effluent Monitor Setpoint Determination This procedure determines the monitor alarm setpoints that indicate the abnormal presence of radionuclides in the service water liquid effluents released from the site to unrestricted areas. This procedure is applicable to any service water effluent monitor.a. Determine the monitor efficiency factor, EF, in[.Ci/mI cps EF (Em) (Cf) (Eq. 2.1-10)Where: Em The detector efficiency (dpm/ml/cps) from the appropriate RST Cf Conversion factor, (1 pCi/2.22 x 106 dpm)b. Determine the monitor trigger level setpoint, TLS, in cps TLS TL/EF + Bkg (Eq. 2.1-11)Where: TL The alarm trigger level (pCi/ml) as per ODCM TR 7.3.3.2= 5.0 x 10-6 pCi/ml Bkg = Monitor background, (cps)ODCM (BSEP)2-8 Rev. 35 2.1.3.Stabilization Pond and Stabilization Facility Releases Prerelease and post-release compliance checks similar to those of Section 2.1.1 are to be performed for releases from the Stabilization Pond and Stabilization Facility.
Prerelease calculations will be based on a gamma isotopic and a tritium analysis prior to release. Post-release calculations will be based on a composite sample that is collected in proportion to flow during the release period. Analyses will be performed on the composite sample after the release is complete in accordance with Table 7.3.3-1.Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period.Typical release times are on the order of days. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste discharges.)
 
====2.1.4 Groundwater====
 
Extraction System Releases Prerelease and post release compliance checks similar to those of Section 2.1.1 are to be performed for releases from the Groundwater Extraction System. Prerelease calculations will be based on gamma isotopic and a tritium analysis prior to release. Post-release calculations will be based on a composite sample that is collected in proportion to flow during the release period. Analyses will be performed on the composite sample in accordance with Table 7.3.3-1. Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste discharges.)
ODCM (BSEP)2-9 Rev. 35 1
 
====2.1.5 Marsh====
Releases Marsh releases from the area around the outside area of the Stabilization Pond are an ongoing release. The release from the marsh areas to Nancy's Creek are sampled in accordance with Table 4.0-1. Curies released and associated doses will be determined and included in the Annual Radioactive Release Report. Doses will be calculated by the following methodology from Regulatory Guide 1.109: RP = I1!00 UZ , Q ,BiPD o,,r exp -/P.')ap! F Where: Rapj is total annual dose to organ j of individuals of age group a from all of the nuclides i in pathway p, in mrem/year; 1100 is the factor to convert from (Cilyr)l(ft 3/sec) to pCi/liter; Uap = is a usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in kg/yr;MP is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of harvest of aquatic foods), dimensionless; F = is the flowrate of the liquid effluent in ft 3/sec;Qi = is the release rate of nuclide i, in Ci/yr;Bip = is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide;
= is the radioactive decay constant of nuclide i, in hr 1;tp = is the average transit time required for nuclides to reach the point of exposure.
For internal dose, tp is the total time elapsed between release of the nuclide and ingestion, in hours.Daipj = is the dose factor, specific to a specific age group a, radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi.Historically, only tritium has been identified in the marsh areas, therefore only tritium will be routinely used in dose calculations unless other nuclides are identified.
Due to tidal fluctuations in the marsh area the annual dose will be determined on two releases per day for the year using average activity for the year.ODCM (BSEP)2-10 Rev. 35 1 TABLE 2.1-1 ECs FOR SELECTED RADIONUCLIDES Radionuclide ECi (uCilmI)H-3 1 E-3 Na-24 5 E-5 Cr-51 5 E-4 Mn-54 3 E-5 Co-58 2 E-5 Fe-59 1 E-5 Co-60 3 E-6 Cu-64 2 E-4 Zn-65 5 E-6 Zn-69m 6 E-5 Sr-89 8 E-6 Sr-90 5 E-7 Sr-91 2 E-5 Zr-95 2 E-5 Mo-99 2 E-5 1-131 1 E-6 1-132 1 E-4 1-133 7 E-6 Cs-134 9 E-7 1-134 4 E-4 1-135 3 E-5 Cs-137 1 E-6 La-141 5 E-5 Np-239 2 E-5 Am-241 2 E-8 Noble Gases 2 E-4 ODCM (BSEP)2-11 Rev. 35 1
 
===2.2 COMPLIANCE===
 
WITH 10CFR PART 50 (LIQUIDS)2.2.1 Cumulation of Doses ODCM TR 7.3.4.1 requires that the cumulative dose contributions from liquid effluents be determined at least once per 31 days, and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. The cumulative dose contributions will consider the dose contributions from the maximum exposed individual's consumption of fish and invertebrates.
At BSEP the adult is consiLdered as the maximum exposed individual.
The dose or dose commitment limits based on 10CFR Part 50, Appendix I, are defined in ODCM Specification 7.3.4 a and b. The dose contribution for all releases for the quarter will be calculated using the following equation: DT J[J(Ai l C,k F4] (Eq. 2.2-1)Where: D, The cumulative dose commitment to the total body or any organ -t, from the liquid effluents releases, mrem tk -The length of time of release k over which Cik and Fk are averaged for each liquid release, hours C,k -The concentration of radionuclide i in the undiluted liquid effluent during release k from any liquid release, piCi/ml Fk -The near-field average dilution factor for Cik during any liquid effluent release. It is defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge to unrestricted receiving water times 1. (1 is the site-specific applicable factor for the mixing effect of the BSEP discharge structure as defined in NUREG 0133.)Ve (See Equation 2.1-8).Vdii A,, The ingestion dose commitment factor to the total body or any organ T for each identified gamma and beta emitter i (as presented in Table 2.2-1).Values are for an adult, mrem-ml per hr-pCi= 1.14 E5 (5 Bli + 21 BFi) DCFi, ODCM (BSEP)2-12 Rev. 35 1 Where: 1.14 E5 10 (oP.cj 103 Jl l87 r~5 = Maximum adult invertebrate consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr BI, = Bioaccumulation factor for radionuclide i in invertebrates from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCi/kg per pCi/L 21 = Maximum adult fish consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr BFi = Bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCi/kg per pCi/L DCFi, = Dose conversion factor for radionuclide i for adults for a particular organ -1 from Table E-11 of Regulatory Guide 1.109, Rev. 1, and BSEP File: B10-10530, Letter to J. W. Davis, "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for Am-241, mrem/pCi.2.2.2 Proiection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.5.2.The projection of doses for liquid effluents can be accomplished by projecting the dose(s) computed for the current month into the next month.The doses will be projected using Equation 2.2-1. Where possible, credit for expected operational evolutions (i.e., major planned liquid releases, etc.), can be taken in the dose projections.
This may be accomplished by using the source-term data from similar historical operating experiences where practical.
ODCM (BSEP)2-13 Rev. 35 1 TABLE 2.2-1 Ait VALUES FOR THE ADULT (MREM/HR PER MICRO-CI/ML)
Note: Nuclides not listed in this table are assigned a value of zero.Nuclide Bone Liver T.Body Thyroid Kidney Lunq GI-LLI H 3 0.OOE-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 C 14 1.45E 04 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 NA 24 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 P 32 1.67E 07 1.04E 06 6.45E 05 0.00E-01 0.00E-01 0.00E-01 1.89E 06 CR 51 0.00E-01 0.00E-01 5.58E 00 3.34E 00 1.23E 00 7.40E 00 1.40E 03 MN 54 0.OOE-01 7.06E 03 1.35E 03 0.00E-01 2.10E 03 0.OOE-01 2.16E 04 MN 56 0.OOE-01 1.78E 02 3.15E 01 0.OOE-01 2.26E 02 0.OOE-01 5.67E 03 FE 55 5.11E 04 3.53E 04 8.23E 03 0.OOE-01 0.OOE-01 1.97E 04 2.03E 04 FE 59 8.06E 04 1.90E 05 7.27E 04 0.OOE-01 0.OOE-01 5.30E 04 6.32E 05 CO 57 0.OOE-01 1.42E 02 2.36E 02 0.OOE-01 0.O0E-01 0.OOE-01 3.59E 03 CO 58 0.O0E-01 6.03E 02 1.35E 03 0.OOE-01 0.O0E-01 0.OOE-01 1.22E 04 CO 60 0.OOE-01 1.73E 03 3.82E 03 0.OOE-01 0.OOE-01 0.O0E-01 3.25E 04 NI 63 4.96E 04 3.44E 03 1.67E 03 0.OOE-01 O.0OE-01 0.O0E-01 7.18E 02 NI 65 2.02E 02 2.62E 01 1.20E 01 .OOE-01 0.OOE-O 0.OOE-01 6.65E 02 CU 64 O.0OE-01 2.14E 02 1.01E 02 0.OOE-01 5.40E 02 0.OOE-01 1.83E 04 ZN 65 1.61E 05 5.13E 05 2.32E 05 0.O0E-01 3.43E 05 0.O0E-01 3.23E 05 ZN 69 3.43E 02 6.56E 02 4.56E 01 0.OOE-01 4.26E 02 0.O0E-01 9.85E 01 BR 83 0.OOE-01 0.OOE-01 7.25E-02 0.OOE-01 0.OOE-01 0.O0E-01 1.04E-01 BR 84 0.OOE-01 O.0OE-01 9.39E-02 0.OOE-01 0.O0E-01 0.OOE-01 7.37E-07 BR 85 0.OOE-01 0.OOE-01 3.86E-03 0.OOE-01 O.0OE-01 0.OOE-01 1.80E-18 RB 86 0.OOE-01 6.24E 02 2.91E 02 0.OOE-01 0.OOE-01 0.OOE-01 1.23E 02 RB 88 0.OOE-01 1.79E 00 9.49E-01 0.OOE-01 0.OOE-01 0.OOE-01 2.47E-11 RB 89 0.OOE-01 1.19E 00 8.34E-01 O.0OE-01 0.OOE-01 0.OOE-01 6.89E-14 SR 89 4.99E 03 0.OOE-01 1.43E 02 0.OOE-01 0.OOE-01 0.OOE-01 8.OOE 02 SR 90 1.23E 05 0.OOE-01 3.01E 04 0.OOE-01 0.OOE-01 O.0OE-01 3.55E 03 SR 91 9.18E 01 0.OOE-01 3.71E 00 0.OOE-01 0.OOE-01 O.0OE-01 4.37E 02 SR 92 3.48E 01 0.OOE-01 1.51E 00 0.OOE-01 0.OOE-01 0.OOE-01 6.90E 02 Y 90 6.06E 00 0.OOE-01 1.63E-01 0.OOE-01 0.OOE-01 O.0OE-01 6.42E 04 Y 91M 5.73E-02 0.OOE-01 2.22E-03 0.OOE-01 0.OOE-01 O.0OE-01 1.68E-01 Y 91 8.88E 01 0.OOE-01 2.37E 00 .OOE-01 0.OOE-O 0.OOE-01 4.89E 04 Y 92 5.32E-01 0.OOE-01 1.56E-02 0.OOE-O 0.EOO-01 0.OOE-01 9.32E 03 Y 93 1.69E 00 0.OOE-01 4.66E-02 O.0OE-01 0.OOE-01 0.OOE-01 5.35E 04 ODCM (BSEP)2-14 Rev. 35 1 TABLE 2.2-1 (Cont'd)Nuclide Bone Liver T.Body Thyroid Kidney Lun , GI-LLI ZR 95 1.59E 01 5.11E 00 3.46E 00 0.O0E-01 8.02E 00 0.OOE-01 1.62E 04 ZR 97 8.81E-01 1.78E-01 8.13E-02 0.O0E-01 2.68E-01 0.00E-01 5.51E 04 NB 95 4.47E 02 2.49E 02 1.34E 02 0.O0E-01 2.46E 02 0.00E-01 1.51E 06 MO 99 0.OOE-01 1.28E 02 2.43E 01 0.OOE-01 2.89E 02 O.0OE-01 2.96E 02 TC 99M 1.30E-02 3.66E-02 4.66E-01 0.OOE-01 5.56E-01 1.79E-02 2.17E 01 TC 101 1.33E-02 1.92E-02 1.88E-01 0.OOE-01 3.46E-01 9.81E-03 5.77E-14 RU "103 1.07E 02 0.00E-01 4.60E 01 0.OOE-01 4.07E 02 0.OOE-01 1.25E 04 RU 105 8.89E 00 0.O0E-01 3.51E 00 0.OOE-01 1.15E 02 0.OOE-01 5.44E 03 RU 106 1.59E 03 0.OOE-01 2.01E 02 0.O0E-01 3.06E 03 0.OOE-01 1.03E 05 AG 110M 1.56E 03 1.45E 03 8.60E 02 0.OOE-01 2.85E 03 0.OOE-01 5.91E 05 SN '113 2.18E 03 8.43E 01 2.05E 03 2.96E 01 6.16E 01 0.OOE 01 3.80E 04 TE I125M 2.17E 02 7.86E 01 2.91E 01 6.52E 01 8.82E 02 0.OOE-01 8.66E 02 TE 127M 5.48E 02 1.96E 02 6.68E 01 1.40E 02 2.23E 03 0.OOE-01 1.84E 03 TE 127 8.90E 00 3.20E 00 1.93E 00 6.60E 00 3.63E 01 O.0OE-01 7.03E 02 TE I!29M 9.31E 02 3.47E 02 1.47E 02 3.20E 02 3.89E 03 0.OOE-01 4.69E 03 TE 129 2.54E 00 9.55E-01 6.19E-01 1.95E 00 1.07E 01 0.OOE-01 1.92E 00 TE 131M 1.40E 02 6.85E 01 5.71E 01 1.08E 02 6.94E 02 0.O0E-01 6.80E 03 TE 131 1.59E 00 6.66E-01 5.03E-01 1.31E 00 6.99E 00 0.O0E-01 2.26E-01 TE 132 2.04E 02 1.32E 02 1.24E 02 1.46E 02 1.27E 03 0.OOE-01 6.24E 03 1 130 3.96E 01 1.17E 02 4.61E 01 9.91E 03 1.82E 02 0.OOE-01 1.01E 02 1 131 2.18E 02 3.12E 02 1.79E 02 1.02E 05 5.35E 02 0.OOE-01 8.23E 01 1 132 1.06E 01 2.85E 01 9.96E 00 9.96E 02 4.54E 01 0.OOE-01 5.35E 00 1 133 7.45E 01 1.30E 02 3.95E 01 1.90E 04 2.26E 02 O.0OE-01 1.16E 02 1 134 5.56E 00 1.51E 01 5.40E 00 2.62E 02 2.40E 01 O.0OE-01 1.32E-02 1 135 2.32E 01 6.08E 01 2.24E 01 4.01E 03 9.75E 01 O.0OE-01 6.87E 01 CS 134 6.84E 03 1.63E 04 1.33E 04 O.0OE-01 5.27E 03 1.75E 03 2.85E 02 CS 136 7.16E 02 2.83E 03 2.04E 03 0.OOE-01 1.57E 03 2.16E 02 3.21E 02 CS 137 8.77E 03 1.20E 04 7.85E 03 0.OOE-01 4.07E 03 1.35E 03 2.32E 02 CS 138 6.07E 00 1.20E 01 5.94E 00 0.OOE-01 8.81E 00 8.70E-01 5.12E-05 BA 139 7.85E 00 5.59E-03 2.30E-01 0.OOE-01 5.23E-03 3.17E-03 1.39E 01 BA 140 1.64E 03 2.06E 00 1.08E 02 0.OOE-01 7.02E-01 1.18E 00 3.38E 03 BA 141 3.81E 00 2.88E-03 1.29E-01 0.OOE-01 2.68E-03 1.63E-03 1.80E-09 BA 142 1.72E 00 1.77E-03 1.08E-01 0.OOE-01 1.50E-03 1.OOE-03 2.43E-18 LA 140 1.57E 00 7.94E-01 2.10E-01 0.OOE-01 O.0OE-O 0.OO-01 5.83E 04 ODCM (BSEP)2-15 Rev. 35 1 TABLE 2.2-1 (Cont'd)Nuclide Bone Liver T.Body Thyroid Kidney Lun .GI-LLI LA 142 8.06E-02 3.67E-02 9.13E-03 0.OOE-01 0.OOE-01 0.OOE-01 2.68E 02 CE 141 3.43E 00 2.32E 00 2.63E-01 0.OOE-01 1.08E 00 O.0OE-01 8.86E 03 CE 143 6.04E-01 4.46E 02 4.94E-02 0.00E-01 1.97E-01 0.00E-01 1.67E 04 CE 144 1.79E 02 7.47E 01 9.59E 00 0.OOE-01 4.43E 01 O.0OE-01 6.04E 04 PR 143 5.79E 00 2.32E 00 2.87E-01 0.O0E-01 1.34E 00 0.OOE-01 2.54E 04 PR 144 1.90E-02 7.87E-03 9.64E-04 O.OOE-01 4.44E-03 0.OOE-01 2.73E-09 ND 147 3.96E 00 4.58E 00 2.74E-01 0.OOE-01 2.68E 00 0.OOE-01 2.20E 04 HF 181 1.72E 02 9.66E-01 1.94E 01 6.14E-01 8.08E-01 0.OOE-01 1.27E 04 W 187 9.16E 00 7.66E 00 2.68E 00 0.OOE-01 0.OOE-01 0.OOE-01 2.51E 03 NP 239 3.53E-02 3.47E-03 1.91E-03 0.OOE-01 1.08E-02 0.OOE-01 7.11E 02 AM 241 4.76E 05 4.44E 05 3.41E 04 0.OOE-01 2.56E 05 0.OOE 01 4.67E 04 F 18 6.66E 00 0.OOE-01 7.38E-01 0.OOE-01 0.OOE-01 0.OOE-01 1.97E-01 SB 124 2.76E 02 5.22E 00 1.09E 02 6.70E-01 0.OOE-01 2.15E 02 7.84E 03 ODCM (BSEP)2-16 Rev. 35 1 INDEX 3.0 GASEOUS EFFLUENTS
...........................................................................................
4 3.1 MONITOR ALARM SETPOINT DETERMINATION
...................................................
4 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)
........................................................
4 3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term E levated R elease .............................................................................
7 3.1.3 Condenser Air Ejector Monitor Alarm Setpoint .........................................
10 3.1.4 Condenser Off-Gas Treatment System (AOG) Monitor Alarm S etpoint D eterm ination ................................................................................
13 3.2 COMPLIANCE WITH 10CFR20 (GASEOUS)
.....................................................
17 3 .2 .1 N oble G ases .........................................................................................
..17 3.2.2 1-131, 1-133, Particulates, and Tritium ......................................................
23 3.3 COMPLIANCE WITH 10CFR50 (GASEOUS)
.....................................................
35 3.3.1 N oble G ases ...........................................................................................
35 3.3.2 1-131, 1-133, Particulates, and Tritium ......................................................
40 3 .3 .3 C arbon-14 ............................................................................................
..67 ODCM (BSEP)3-1 Rev. 36 LIST OF TABLES Title Table No.SECTION 3 3.1-1 3.1-2 3.2-1 3.2-2 3.2-3 3.2-4 3.2-5 3.3-1 3.3-2 3.3-3 3.3-4 3.3-5 3.3-6 3.3-7 3.3-8 Paqe G ASEO U S SO URC E TER M ....................................................................
3-15 DOSE FACTORS AND CONSTANTS
......................................................
3-16 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT ................
3-30 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSW ICK PLANT CENTER .......................................................
3-31 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK .........................
3-32 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
...................
3-33 Pi VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM E LE C T R IC P LA N T ...................................................................................
3-34 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -GROUND.. 3-48 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -V E G ET A B LE/A D U LT ...............................................................................
3-49 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -V E G ETA BL E/T E E N .................................................................................
3-50 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -V E G ETA B LE/C H ILD ................................................................................
3-51 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -M E A T /A D U LT ..........................................................................................
3-52 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -M E A T /T E E N .............................................................................................
3-5 3 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -M E A T /C H ILD ...........................................................................................
3-54 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -COW M IL K /A D U LT ............................................................................................
3-5 5 ODCM (BSEP)3-2 Rev. 25 LIST OF TABLES Table No. Title Paqe 3.3-9 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -COW M IL K /T E E N ..............................................................................................
3 -5 6 3.3-10 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -COW M IL K /C H IL D ...........................................................................................
3 -5 7 3.3-11 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -COW M IL K /IN F A N T ...........................................................................................
3-58 3.3-12 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -GOAT M IL K /A D U LT ............................................................................................
3 -5 9 3.3-13 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT- GOAT M IL K /T E E N ..............................................................................................
3 -6 0 3.3-14 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -GOAT M IL K /C H IL D .............................................................................................
3 -6 1 3.3-15 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -GOAT M IL K /IN F A N T ...........................................................................................
3-6 2 3.3-16 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -IN H A LA T IO N/A D U LT ...............................................................................
3-63 3.3-17 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -IN H A LA T IO N /T E E N .................................................................................
3-64 3.3-18 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -IN HA LA T IO N/C H ILD ..............................................................................
3-65 3.3-19 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -IN H A LA T IO N /IN FA N T ..............................................................................
3-66 3.3-20 INHALATION DOSE FACTORS FOR CARBON-14
.................................
3-69 3.3-21 INGESTION DOSE FACTORS FOR CARBON-14
...................................
3-71 ODCM (BSEP)3-3 Rev. 36
 
===3.0 GASEOUS===
EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This procedure determines the monitor alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrem/year to the whole body or exceeds 3000 mrem/year to the skin.(NUREG-0133)
 
====3.1.1 Setpoint====
Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)The following method applies to gaseous releases via the Units 1 and 2 Turbine Building Vents and via the Units 1 and 2 Reactor Building Vents when determining the high alarm setpoint for the Turbine Building Vent Gas Monitors and Reactor Building Vent Gas Monitors.1. Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-2):*a. Determine the gaseous source terms that are representative of the"mix" of the gaseous effluent.
Gaseous source terms are the noble gas activities in the effluent.Gaseous source terms can be obtained from: Table 3.1-2; Turbine Building Vent Release Table 3.1-2; Reactor Building Vent Release Actual release data b. Determine Si (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.Si Ai (3.1-1)Yi Ai A, The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-2, Turbine Building Vent Release; Table 3.1-2, Reactor Building Vent Release; or from analysis of gaseous effluent.*If actual plant data is used, the dose constants need to be confirmed.
ODCM (BSEP)3-4 Rev. 35
: 2. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, pCi/sec) based upon the whole body exposure limit.Qt =500 (3.1-2)Qt (x~~/Q) v, (Ki  (x/QTb The highest calculated annual average relative concentration of effluents released via the Turbine Building Vent for any area at or beyond the site boundary for all sectors (sec/m 3) from Table A-i, Appendix A 1.5 E-5 sec/m 3= The highest calculated annual average relative concentration of effluents released via the Reactor Building Vent for any area at or beyond the site boundary for all sectors (sec/m 3) from Table A-7, Appendix A= 2.5 E-6 sec/m 3 NOTE: Use the X/Q that applies to the monitor for which the alarm setpoint is being calculated.
K = The total whole body dose factor due to gamma emissions from noble gas radionuclide i (mrem/yearlptCi/m
: 3) from Table 3.1-3.3. Determine Q, based upon the skin exposure limit.Qt =3000 (3.1-3)(X/Q) E, [(LK + 1.1 M,)S,]Li + 1.1 Mj The total skin dose factor due to emissions from noble gas radionuclide i (mrem/year/[tCi/m
: 3) from Table 3.1-3.NOTE: The Turbine Building radiation monitors are designed to input the monitor high alarm setpoint in 0Ci/sec or pCi/cc. The monitor setpoint in pCi/sec can be obtained by multiplying the lowest Q, value (obtained from Sections 3.1.1.2 and 3.1.1.3)by the Tm value found in Section 3.1.1.5.b.
The pCi/cc setpoint can be obtained by dividing the pCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cpm are included for completeness and may be used if desired.ODCM (BSEP)3-5 Rev. 301
: 4. Determine Ct (the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the gaseous effluent, [iCi/sec/cfm).
Ct Qt (3.1-4)f S NOTE: Use the lower of the Qt values obtained in Sections 3.1.1.2 and 3.1.1.3.f = The maximum acceptable effluent flow rate at the point of release (cfm)based on design flow rates= 15,500 cfm (Turbine Building Vent- Recirculation Mode)= 95,000 cfm (Turbine Building Vent -Once Thru Mode)= 172,800 cfm (Reactor Building Vent)5. Determine the monitor high alarm setpoint above background:
: a. Determine CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).CR = Ct (3.1-5)Em Em = The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (p.Ci/sec/cfmocpm) from E&RC files b. Determine HSP (the monitor high alarm setpoint with background, cpm).HSP TmCR + Bkg (3.1-6)Tm = Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways.
Typical values for Tm are shown below.= 0.10 for the Unit 1 Turbine Building Vent Gas Monitor= 0.10 for the Unit 2 Turbine Building Vent Gas Monitor 0.20 for the Unit 1 Reactor Building Vent Gas Monitor= 0.20 for the Unit 2 Reactor Building Vent Gas Monitor NOTE: Tm is defined such that I Tm 5 1.ODCM (BSEP)3-6 Rev. 30 1 Bkg The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air c. The monitor high alarm setpoint including background (cpm) shall be set at or below the HSP value determined above.3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release The following method applies to gaseous releases via the stack when determining the high-high alarm setpoint for the Stack Monitor during continuous release via the stack.I1. Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-2):*a. Determine the gaseous source terms that are representative of the"mix" of the gaseous effluent.
Gaseous source terms are the noble gases radionuclide activity concentrations in the effluent.Gaseous source teams can be obtained from: Table 3.1-2; Stack Release Actual Release Data b. Determine Si (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.Si Ai (3.1-7)Xi Ai A, The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-2, Stack Release, or from analysis of gaseous effluent.2. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, pCi/sec) based upon the whole body exposure limit.*If actual plant data is used, the dose constants need to be confirmed.
ODCM (BSEP)3-7 Rev. 30 1 Qt = 500 (3.1-8)VI = The constant for noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume (mrem/year/p.Ci/sec) from Table 3.1-4 3. Determine Qt based upon the skin exposure limit.Qt =3000 (3.1-9)Q = [(Li (X/Q)5 + 1.1 B)S]L, --,/ Q + 1.1 Bi The total skin dose constant for long term releases (greater than 500 hours/year) due to emissions from noble gas radionuclide i (mrem/year/p.Ci/sec) from Table 3.1-3).NOTE: The stack radiation monitor is designed to input the monitor high-high alarm setpoint in piCi/sec or tiCi/cc. The monitor setpoint in piCi/sec can be obtained by multiplying the lowest Qt value (obtained from Sections 3.1.2.2 and 3.1.2.3 by the Tm value found in Section 3.1.2.5.b.
The pCi/cc setpoint can be obtained by dividing the pCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cps are included for completeness and may be used if desired.4. Determine Ct (the total maximum acceptable radioactivity concentration of noble gas radionuclides in the gaseous effluent, pCi/sec/cfm).
Ct t (3.1-10)f NOTE: Use the lowest of the Qt values obtained in Sections 3.1.2.2 and 3.1.2.3.f = The maximum acceptable effluent flow rate at the point of release (cfm)based on design flow rates= 86,000 cfm (stack)ODCM (BSEP)3-8 Rev. 30 1
: 5. Determine the monitor high-high alarm setpoint above background:
: a. Determine the CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).CR C, (3.1-11)Em Em The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (pCi/sec/cfmocpm) from E&RC files b. Determine HHSP (the monitor high-high alarm setpoint with background, cpm).HHSP = TrmCR + Bkg (3.1-12)Tm = Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways= 0.40 for the Stack Monitor Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air c. The monitor high-high alarm setpoint including background (cpm)shall be set at or below the HHSP value determined above.ODCM (BSEP)3-9 Rev. 25
 
====3.1.3 Condenser====
 
Air Ejector Monitor Alarm Setpoint This procedure determines the alarm setpoint for the Condenser Air Ejector Monitor that will provide reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 1OCFR100 in the event of an inadvertent release via the condenser air ejector.1 .The following method applies to gaseous releases via the Units 1 and 2 condenser air ejectors when determining the maximum allowable alarm setpoint for the Condenser Off-gas Radiation Monitors, Reference Table 3.1-1.a. Determine Q, the allowable release rate (pLCi/sec) at the air ejector for the noble gas radionuclides.
Technical Specification
 
====3.7.5 limits====
the gross radioactivity rate of noble gases measured at the main condenser air ejector to less than or equal to 243,600 VCi/sec (after 30 minutes' decay). Assume that the noble gas concentrations at the air ejector (t = 0) are representative of the GALE code. Since the holdup time between the air ejector and the stack (down the 30-minute holdup line) can vary due to operational conditions, the mix of the noble gases at the stack should be determined based on the actual decay time not to exceed 30 minutes. This mix can then be applied to the 243,600 VCi/sec limit and then back-calculated to determine the allowable release rate at the air ejector, Q. As an example, assume that the holdup time is 30 minutes. The mix of the noble gases after 30 minutes' decay (t = 30 minutes) can be determined by the following table.ODCM (BSEP)3-10 Rev. 30 1 TABLE 3.1-1 GALE CODE 30 Minute Decayed Air Ejector Release Fraction Nuclide GALE Code Steam (pCi/gm) pCi/sec* e-kt pCi/sec Fraction Rev. 0 t = 0 t = 0 t = 30m t = 30m of Mix Steam ([.Ci/gm) t = 30m t= 0 (for 3400 MWt) (for 2923 MWt)Kr-83m 1.1E-3 9.46E-4 1.52E+3 8.3E- 1 1.26E+3 2.85E-2 Kr-85m 1.9E-3 1.63E-3 2.63E+3 9.2E- 1 2.43E+3 5.50E-2 Kr-85 6.OE-6 5.16E-6 8.31E+0 1.OE+0 8.31E+0 1.88E-4 Kr-87 6.6E-3 5.67E-3 9.14E+3 7.6E-1 6.96E+3 1.57E-1 Kr-88 6.6E-3 5.67E-3 9.14E+3 8.8E-1 8.08E+3 1.82E-1 Kr-89 4.1E-2 3.52E-2 5.68E+4 1.4E-3 7.89E+1 1.78E-3 Kr-90 9.OE-2 7.74E-2 1.25E+5 1.7E-17 2.11E-12 4.76E-17 Xe-131m 4.7E-6 4.04E-6 6.51E+0 1.OE+0 6.50E+0 1.47E-4 Xe-133m 9.OE-5 7.74E-5 1.25E+2 9.9E-1 1.24E+2 2.80E-3 Xe-133 2.6E-3 2.24E-3 3.60E+3 1.OE+0 3.59E+3 8.11E-2 Xe-135m 8.4E-3 7.22E-3 1.16E+4 2.6E-1 2.99E+3 6.75E-2 Xe-135 7.2E-3 6.19E-3 9.97E+4 9.6E-1 9.60E+3 2.17E-1 Xe-137 4.7E-2 4.04E-2 6.54E+4 4.4E-3 2.90E+2 6.54E-3 Xe-138 2.8E-2 2.41E-2 3.88E+4 2.3E-1 8.87E+3 2.01E-1 TOTAL 4.43E+4 1.OOE+0 Applying this mix to 243,600 pCi/sec (after 30 minutes' delay) and back calculating to t = 0 will yield the allowable pCi/sec per noble gases at the air ejectors; i.e.:* Steam Flow = (12.782 E6 lbs/hr) (0.1260 gm/sec 1.61 E + 6gm/sec lbs/hr )ODCM (BSEP)3-11 Rev. 30 1 TABLE 3.1-1 (Continued)
GALE CODE 30 Minute Air Ejector Technical Specification Release Rate Limits Nuclide Fraction of Mix Tech Spec e-Xt Tech Spec t = 30 min (piCi/sec) t = 30 min (pCi/sec)t = 30 min t = 0 Kr-83m 2.85E-2 6.95E+3 8.3E-1 8.38E+3 Kr-85m 5.50E-2 1.34E+4 9.2E- 1 1.45E+4 Kr-85 1.88E-4 4.57E+1 1.OE+0 4.57E+1 Kr-87 1.57E-1 3.83E+4 7.6E-1 5.03E+4 Kr-88 1.82E-1 4.44E+4 8.8E-1 5.03E+4 Kr-89 1.78E-3 4.34E+2 1.4E-3 3.12E+5 Kr-90 4.76E-17 1.16E-11 1.7E-17 6.85E+5 Xe-131m 1.47E-4 3.58E+1 1.OE+0 3.58E+1 Xe-133m 2.80E-3 6.81E+2 9.9E-1 6.85E+2 Xe-133 8.11E-2 1.97E+4 1.OE+0 1.98E+4 Xe-135m 6.75E-2 1.64E+4 2.6E-1 6.40E+4 Xe-135 2.17E-1 5.28E+4 9.6E-1 5.48E+4 Xe-137 6.54E-3 1.59E+3 4.4E-3 3.58E+5 Xe-138 2.OOE-1 4.88E+4 2.3E-1 2.13E+5 TOTALS 1.00E+0 2.44E+5 1.83E+6 Therefore:
Q 1.83E+6 piCi/sec (for 30 minutes' holdup)b. Determine Cm (the total radioactivity concentration of noble gases)in the condenser air ejector gas (jiCi/sec/cfm).
Cm Q/f (3.1-13)Q = The allowable release rate (pCi/sec) at the air ejector for noble gases f = The main condenser air inleakage rate plus the radiolytic gas flow rate (cfm)ODCM (BSEP)3-12 Rev. 30 1
: c. Determine the monitor high-high alarm setpoint above background.
(1) Determine MR (the calculated monitor response attributed to the noble gas radionuclides, mR/hr).MR Cm (3.1-14)Em Emr, The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous stream [(pCilsec)I(mRIhr.cfm)]
from E&RC files (2) The monitor high-high alarm setpoint (mR/hr) should be set at or below the MR value determined above.3.1.4 Condenser Off-Gas Treatment System (AOG) Monitor Alarm Setpoint Determination This method determines the monitor alarm setpoint that includes sufficient noble gas activity to cause an alarm at the stack effluent noble gas monitor.1. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, piCi/sec) based upon the whole body exposure (see Equation 3.1-8) and skin exposure (see Equation 3.1-9).NOTE: Use the lowest of the Qt values obtained.2. Determine Q, (the site adjusted maximum release rate, pCi/sec, for effluent releases via the stack).Qs = Qt x Tm (3.1-15)Tm Fraction of radioactivity from the site that may be released via the stack to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways.
The typical value used for Tm is shown below 0.4 for the stack monitor ODCM (BSEP)3-13 Rev. 30 1
: 3. Determine HSP (high alarm setpoint in piCi/cc).HSP = QS f (3.1-16)f = Maximum design flow rate of the AOG System= 70,800 cc/sec (150 cfm)4. The monitor high alarm setpoint shall be set at or below the HSP value determined above.ODCM (BSEP)3-14 Rev. 25 TABLE 3.1-2 GASEOUS SOURCE TERMS **(Ci/year/unit)
Turbine Bldg Vent Reactor Bldg Vent Stack Radionuclide Ai (Ci/yr) Si Ai (Ci/yr) Si Ai (Ci/yr) Si Kr-83m * * -3.7E+4 2.84E-2 Kr-85m 6.8E+1 1.95E-2 6.OEO 1.72E-2 7.2E+4 5.46E-2 Kr-85 * -2.4E+2 1.86E-4 Kr-87 1.9E+2 5.45E-2 6.OEO 1.72E-2 2.05E+5 1.56E-1 Kr-88 2.3E+2 6.59E-2 6.OEO 1.72E-2 2.4E+5 1.82E-1 Kr-89 * -3.5E+3 2.64E-3 Xe-131m * -1.9E+2 1.46E-4 Xe-133m * -3.6E+3 2.78E-3 Xe-133 2.8E+2 8.03E-2 1.32E+2 3.78E-1 1.1E+5 8.24E-2 Xe-135m 6.5E+2 1.86E-1 9.2E+1 2.64E-1 8.8E+4 6.72E-2 Xe-135 6.3E+2 1.81E-1 6.8E+1 1.95E-1 2.8E+5 2.16E-1 Xe-137 *
* 1.1E+4 8.09E-3 Xe-138 1.44E+3 4.13E-1 1.4E+1 4.01E-2 2.6E+5 2.OOE-1 Ar-41
* 2.5E+1 7.16E-2 *TOTAL 3.49E+3 3.49E+2 1.31E+6* < 1.0E+1**Source terms are based upon GALE code and not actual releases.ODCM (BSEP) 3-15 Rev. 30 1 TABLE 3.1-3 DOSE FACTORS AND CONSTANTS Radio Total Whole Body Total Skin Total Body Dose Total Skin Dose Nuclide Dose Factor Dose Factor Constant For Constant for (K,) (LI + 1.1Mi) Long-Term Long-Term (mrem/yr/pCi/m
: 3) (mrem/yrl/[Ci/m
: 3) Releases Releases (Vi) (Li(x/Q)!
+ 1.1Bj)(mrem/yrli.Ci/sec) (mrem/yrlpCi/sec)
Kr-83m 7.56E-2 2.12E+1 2.70E-09 8.21 E-07 Kr-85m 1.17E+3 2.81E+3 1.14E-04 2.33E-04 Kr-85 1.61 E+ 1 1.36E+3 1.69E-06 4.57E-05 Kr-87 5.92E+3 1.65E+4 5.12E-04 1.16E-03 Kr-88 1.47E+4 1.91E+4 1.35E-03 2.30E-03 Kr-89 1.66E+4 2.91E+4 7.59E-04 1.58E-03 Xe-131m 9.15E+1 6.48E+2 2.78E-05 6.41E-05 Xe-133m 2.51E+2 1.35E+3 2.12E-05 7.04E-05 Xe-133 2.94E+2 6.94E+2 2.22E-05 4.85E-05 Xe- 135m 3.12E+3 4.41E+3 2.62E-04 4.59E-04 Xe-135 1.81E+3 3.97E+3 1.82E-04 3.61 E-04 Xe-137 1.42E+3 1.39E+4 6.42E-05 4.97E-04 Xe-138 8.83E+3 1.43E+4 8.09E-04 1.46E-03 Ar-41 8.84E+3 1.29E+4 9.71 E-04 1.69E-03 ODCM (BSEP)3-16 Rev. 30 1
 
===3.2 COMPLIANCE===
 
WITH ODCM Specification 7.3.7 (GASEOUS)3.2.1 Noble Gases The gaseous effluent monitors' setpoints are utilized to show compliance with ODCM Specification (ODCMS) 7.3.7 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet ODCMS 7.3.7 limits may not be exceeded.
Therefore, the following methodology has been provided in the event that if the alarm/trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded ODCMS 7.3.7.The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin.Based upon NUREG 0133, the following are used to show compliance with ODCMS 7.3.7.YK IV, Q,&#xfd; + K (Q/Q)v Qv 1 _ 500 mrem/yr (3.2-1)1. { [L(xIQ). + 1. IBJQ + (Li + 1.IM) (X/Q )v Q }_ 3000 mrem/yr (3.2-2)where: Ki The total body dose factor due to gamma emissions for noble gas radionuclide i, mrem/year per pCi/m 3 Li The skin dose factor due to beta emissions for noble gas radionuclide i, mrem/year per pCi/m 3 M = The air dose factor due to gamma emissions for noble gas radionuclide i, mrad/year per PCi/m 3 V i  The constant for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem/year per P.Ci/sec Bi The constant for long-term releases (greater than 500 hours/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad/year per pCi/sec ODCM (BSEP)3-17 Rev. 30 1 1.1 The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad The release rate of noble gas radionuclide i in gaseous effluents from free-standing stack, pCi/sec Q =v The release rate of noble gas radionuclide i in gaseous effluents from all vent releases, pCi/sec At the Brunswick Steam Electric Plant (BSEP), gaseous releases may occur from: 1.2.3.The Turbine Building vent*The Reactor Building vent The stack Releases from the Turbine Building are ground level. The sources of these releases are steam leakage through valve stems, pump seals, and flanged connections.
Releases from the Reactor Building are considered mixed mode in nature, and the source is also leakage through valve stems, pump seals, and flanged connections.
Releases from the stack are considered elevated.
Their sources are the main condenser's steam jet air ejectors, Radwaste Building and AOG Building ventilation system exhausts, mechanical vacuum pump exhausts during startup, and gland seal off-gases.
Noble gas releases may occur from all three points. To show compliance with ODCMS 7.3.7, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release points for BSEP.For the total body dose: LVi Q,. + Y-i Ki L(xIQ)rb6,b
+ (X/Q)Ib Qp ]  500 mrem/yr (3.2-3)*Any effluents due to exfiltration from planned openings in the Turbine Building, Radwaste Building or AOG Building are combined with the Turbine Building's vent releases.ODCM (BSEP)3-18 Rev. 30 1 For the skin dose: 5i [L (xIQ)s + 1. 1BjQ, + [LL + 1. IM,][ I Q,, + xIQb Q,, ] < 3000 mrem/yr Where: (3.2-4)0,i -Qith -(x/QX -)Release rate of radionuclide i from the stack, pCi/sec Release rate of radionuclide i from the two Reactor Buildings, iaCi/sec Release rate of radionuclide i from the two Turbine Buildings, paCi/sec Annual average relative concentration for releases from the stack, sec/ m 3 Annual average relative concentration for releases from the Reactor Buildings, sec/m 3 Annual average relative concentration for releases from the Turbine Buildings, sec/ m 3 All other terms remain the same as those defined previously.
The determination of controlling location for implementation of ODCMS 7.3.7 for noble gases is a function of the radionuclide mix, the isotopic release rate, and the meteorology.
The incorporation of these variables into Expressions 3.2-3 and 3.2-4 result in the following expressions for the controlling locations for the BSEP. This location is 0.7 miles, the NE site boundary.(X/Q)tb ODCM (BSEP)3-19 Rev. 30 1 For the total body: QV, ++/-Z, K, (1.9 x I0-6 Q,,' + 6.0 x 10-6 Q 1 ,, ) 500 mrem/yr (3.2-5)For the skin:&#xa3;,(3.2xIO0 8 Li+I.-B,)Q, ++/-, I .i , ( 1.9 X 1 , + 6. e x 10-6 o 3,0  0OO 0 inre n /vr (3 .2-6 )[(L+i.I O&deg;,+ Qi -]The radionuclide mix was based upon source terms calculated using the NRC GALE code. They are presented in Table 3.2-1 as a function of release point. It should be noted, however, that the releases in Table 3.2-1 do not reflect the actual BSEP release data to date. The releases to date have been substantially less. This table was used as a calculational tool to determine the controlling location.The X/Q values utilized in the equations for implementation of 10CFR20 are based upon the maximum long-term annual average (X/Q) in the unrestricted area. Table 3.2-2 presents the distances from the Reactor and Turbine Buildings to the nearest unrestricted area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Table 3.2-3 presents the distances and directions from the stack to the same site boundaries of Table 3.2-2. Note that only distance has changed in relation to Table 3.2-2.Long-term annual (X/Q) values for the stack, Reactor Building, and Turbine Building release points from BSEP to the special locations in Table 3.2-2 are presented in Appendix A. A description of the derivation is also provided in this appendix.
Z/Q values at the limiting site boundary for releases from the Turbine Building, Reactor Building, and stack were obtained from Tables A-I, A-7, and A-1 3, respectively, of the appendix.To determine the controlling location for implementation of 10CFR20, the two or three highest site boundary x/Q values for each release point were utilized in conjunction with the radionuclide mix and release rate for each release point. Since mixed mode and elevated releases occur from BSEP, their maximum X/Q value may not decrease with distance; i.e., the site boundary may not have the ODCM (BSEP)3-20 Rev. 30 1 highest X/Q values. Therefore, long-term annual average x/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 of Appendix A. The highest two or three X/Q values for each release point at a distance greater than the site boundary were used in conjunction with the radionuclide mix to determine the controlling location.
A particular combination of release point mix and meteorology dominates in the determination of the controlling location.
For BSEP, it is the stack, and the dominant factor in determining a control location becomes the V, values.The controlling location is at the ENE at the site boundary due to its higher Vi values.Values for Ki, Li, and Mi, which were used in the determination of the controlling locations and which are to be used by BSEP in Expressions 3.2-5 and 3.2-6 to show compliance with ODCMS 7.3.7, are presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1.The values have been multiplied by 106 to convert picocuries' to microcuries-1 for use in Expressions 3.2-5 and 3.2-6.Values for Vi and Bi for the finite plume model can be expressed as shown in Equations 3.2-7 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN. Values for Vi and Bi for each of the 16 sectors are presented in Appendix B.Bi K , AzI, V El (3.2-7)B,-, T_ _(.27 I The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (pj) and atmospheric stability class "K" for a particular wind direction K = A numerical constant representing unit conversions 260 mrad (radians)(m 3)(transformation) 16 sectors x x sec(Mev)(Ci) 2n radians 106 Ci 3.15 x10 7 sec pCi yr 2.1 x 10 4 mrad (M 3) (transformation)
/ year (Mev) (pCi)ODCM (BSEP)3-21 Rev. 30 1 rd The distance from the release point to the receptor location, meters S = The mean wind speed assigned to the jth wind speed class, meters/sec fjk = The joint frequency of occurrence of the jth wind speed class and the kth stability class (dimensionless)
Ali = The number of photons of energy corresponding to the Ith energy group emitted per transformation of the ith radionuclide, number/transformation El The energy assigned to the Ith energy group, MeV Pa = The energy absorption coefficient in air for photon energy Ei, meters'1 The Vi factor is computed with conversion from air dose to tissue depth dose, thus;Vi = 1 .K/r, E, fk A,, V&#xfd; Etl e-" TTd (3.2-8)Where: I.T = The tissue energy absorption coefficient for photons of energy El, cm 2/gm Td = The tissue density thickness taken to represent the total body dose (5 gm/cm 2)1.1 = The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad ODCM (BSEP)3-22 Rev. 25 3.2.2 1-131, 1-133, Particulates, and Tritium*The dose rate in unrestricted areas resulting from the release of radioiodines and particulates with half-lives greater than 8 days is limited to 1500 mrem/year to any organ. Based upon NUREG 0133, the following is used to show compliance with ODCMS 7.3.7.X, Pi (Ws Qj, + WV Q, )- 1500 mrem/yr (3.2-9)Where: P,= Dose parameter for radioiodines and particulates with half-lives greater than 8 days based upon the critical organ and the most restrictive age group (infant)mrem/year per PCi/m 3 for inhalation pathways and for tritium mrem/year per p.Ci/sec per m-2 for food and ground plane pathways= The release rate of radionuclide i in gaseous effluents from free-standing Qi, stack, pCi/sec Q'. The release rate of radionuclide i in gaseous effluents from all vents releases, &#xfd;tCi/sec W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all vent releases= sec/m 3 for the inhalation pathway= meters 2 for the food and ground plane pathways*For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.ODCM (BSEP)3-23 Rev. 35 Ws The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to stack releases= sec/m 3 for the inhalation pathway= meters 2 for the food and ground plane pathways Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines and particulates may also be released from other sources such as decontamination and waste processing.
Effluents from the decontamination and waste processing facilities in the Radioactive materials Container and Storage Building, Low Level Warehouse, and hot shop, and any building exfiltration are combined with the Turbine Building's vent releases.
To show compliance with ODCMS 7.3.7, Expression 3.2-9 is modified to incorporate the various release points for BSEP: Y-I PI (WS Qi&#xfd; + Wrb Qi + Wtb Qi )-< 1500 mrem/yr (3.2-10)Where: W = The annual average dispersion parameter for the stack Wrb = The annual average dispersion parameter for the Reactor Buildings Wtb = Annual average dispersion parameter for the Turbine Buildings Qj = Release of radionuclide i from the two Reactor Buildings, pCi/sec Q = Release of radionuclide i from the two Turbine Buildings, pCi/sec ODCM (BSEP)3-24 Rev. 30 1 Qi&#xfd;= Release of radionuclide i from the stack, pCi/sec All other terms are the same as those defined previously.
In the calculation to show compliance with ODCMS 7.3.7, only the child inhalation pathway needs to be assessed.
However for purposes of conservatism, the infant inhalation, ground plane, cow milk, and goat milk pathways are considered for BSEP. In determining the dose at a particular location, W is a function of pathway. For the food and ground plane pathways, W is in terms of D/Q (i.e., deposition).
If the inhalation pathway is considered, W is in terms of X/Q. Incorporation of the various pathways into Expression 3.2-10 results in the following:
x [ (X/Q),Q* + (X/Q)r Q. + (Yx/Q)X Q i +X( M (3.2-11)[D/), i&#xfd;+ (D/Q)r Qb + (D/Q),b Qi, ]<1500 mrem/yr Where: Pi, Dose parameter for radionuclide i for the inhalation pathway, mrem/year per pCi/sec 3 Pi, Dose parameter for radionuclide i for the ground plane pathway, mrem/year per pCi/sec per M-2 Pi" Dose parameter for radionuclide i for either the cow milk or goat milk pathway, mrem/year per pCi/sec per M-2 (x/Q)' = Annual average relative concentrations for releases from the Reactor Buildings, sec/m 3 (QXb = Annual average relative concentrations for releases from the Turbine Buildings, sec/m 3 (x/Q)5 = Annual average relative concentrations for releases from the stack, sec/m 3 ODCM (BSEP)3-25 Rev. 30 1 (D/Q), =(D/Q),b =(D/Q), =Annual average deposition for releases from the Reactor Buildings, m-2 Annual average deposition for releases from the Turbine Buildings, m-2 Annual average deposition for releases from the stack, m-2 In the case of tritium, the W parameter for the food pathway (cow or goat milk) is based upon x/Q. Since tritium is a weak beta emitter, the ground plane contribution is zero for tritium. Therefore, the left-hand side of Expression 3.2-10 can be written as the following:
For tritium: DT (PVI +PT" )[ (Z/Q), QT, + (Z/Q)rb QrT, + (XIQ),h ](3.2-12)Where: PT PT,, QT'= Dose rate due to tritium releases, mrem/year= Dose parameter for tritium for the inhalation pathway, mrem/year per pCi/m 3= Dose parameter for tritium for the milk pathway, mrem/year per pCi/m 3= Release rate of tritium from the stack, pCi/sec= Release rate of tritium from the two Reactor Buildings, pCi/sec= Release rate of tritium from the two Turbine Buildings, pCi/sec ODCM (BSEP)3-26 Rev. 25 Since P,, for tritium equals 647 and PM equals 2380, Equation 3.2-12 reduces to: T = (zxQL0' ++ , (3.2-13)To show compliance with ODCMS 7.3.7, Expressions 3.2-11 and 3.2-13 are evaluated first at the limiting site boundary.
It should be noted that the sum of the dose rates from radioiodines and particulates and from tritium must be summed and their combined dose rates be less than 1500 mrem/year to show compliance with ODCMS 7.3.7. If the 1500 mrem/year limit is exceeded at the limiting site boundary when all pathways are considered present at the site boundary but the inhalation pathway contributes less than 1500 mrem/year, then Expressions 3.2-11 and 3.2-13 are evaluated at the limiting real pathway location.
The limiting site boundary location is 0.7 miles NE. Expression 3.2-11 becomes: or radioiodines and particulates: , P, (4.6x10-8 O, +2.3 x1 6 Q, + 4.3xI0 6 O,)+, (p i,+ )(2.7 x10-9 Q, + 1.7 x10-8 Q, + 1.8x10-8 Q, )<- 1500 mrem/yr (3.2-14)For BSEP, the limiting "hypothetical" real pathway location is the cow milk pathway 4.75 miles NE. At this location, Expression 3.2-11 becomes: 2 (x108Q, + 1.9x10-7 Q + 13.2x0-7 Qi,, ) + 5i (p +Y-, 1&#xfd;, (2.4 xp, 10P,,3.(2.9 x 10-'I) Q, + 7.0x I0- Q,,, + 7.2 x 10-'&deg; Q,, ) 1500 inrein/yr (3.2-15)ODCM (BSEP)3-27 Rev. 35 For tritium, at the limiting site boundary, Equation 3.2-13 becomes: For tritium: D7. = 3.0x10 3 (4.6xlo-go0 7 +2.3x10-6Qh
+04.3x10-6 QOT)(3.2-16)At the "hypothetical" limiting real pathway location, Equation 3.2-13 becomes: For tritium: D7. 3.0 x.10' (2.4xO-8 Q, ,+1.9xO 7 QT + 3.2 x10 7 QT)(3.2-17)The determination of controlling location for implementation of ODCMS 7.3.7 for radioiodines and particulates is a function of the same two parameters as for noble gases plus a third receptor pathway location.
The radionuclide mix was again based upon the source terms calculated using the GALE code. The mix and the source terms are presented in Table 3.2-1 as a function of release point.In the determination of the controlling site boundary location, the highest two or three site boundary X/Q and D/Q values for each release point were utilized in conjunction with the radionuclide mix and the release rate for each release point. At BSEP, the release rate which dominates comes from the stack. The higher values for x/Q and D/Q for the NE sector at the site boundary make it the dominant meteorological sector and the control location.In the determination of receptor controlling location, the highest two or three D/Q values from each release point to the pathway locations of Table 3.2-2 are utilized in conjunction with the radionuclide mix and release rate for each release point. For BSEP, the controlling location is a hypothetical cow milk pathway 4.75 miles NE of the Reactor Building and Turbine Buildings.
ODCM (BSEP)3-28 Rev. 30 1 Values for Pi were calculated for an infant for various radionuclides for the inhalation, ground plane, cow milk, and goat milk pathways using the methodology of NUREG 0133. The Pi values are presented in Table 3.2-5.The values of Pi reflect, for each radionuclide, the maximum organ dose factor for each individual pathway of exposure.
Because the goat milk pathway is not present at BSEP, the cow milk pathway Pi values were utilized in the determination of the various controlling locations.
However, Pi values are presented in Table 3.2-5 for completeness.
Appendix C presents the methodology which was utilized in calculating Pi values.Annual average D/Q values at the special locations for the stack, Reactor Building, and Turbine Building release points, respectively, which were utilized in Expressions 3.2-14 through 3.2-17 were obtained from the tables presented in Appendix A. The X/Q values in Expressions 3.2-14 through 3.2-17 were also obtained from the tables presented in Appendix A. D/Q values at the limiting site boundary location and the limiting real pathway location for releases from the Turbine Buildings, the Reactor Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A. X/Q values at these same locations for these same release points were obtained from Tables A-i, A-7, and A-13 of Appendix A. A description of the derivation of the X/Q and D/Q values is provided in Appendix A.ODCM (BSEP)3-29 Rev. 30 1 TABLE 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT *(Ci/yr per unit)Isotope Turbine Building Reactor Building Stack (Ground Level) (Mixed Mode) (Elevated)
Kr-83m 0 0 3.7E+4 Kr-85m 6.8E+1 6.OE+0 7.2E+4 Kr-85 0 0 2.4E+2 Kr-87 1.9E+2 6.OE+0 2.05E+5 Kr-88 2.3E+2 6.OE+0 2.4E+5 Kr-89 0 0 3.5E+3 Xe-131m 0 0 1.9E+2 Xe-133m 0 0 3.6E+3 Xe-133 2.8E+2 1.3E+2 1.1 E+5 Xe-135m 6.5E+2 9.2E+1 8.8E+4 Xe-135 6.3E+2 6.8E+1 2.8E+5 Xe-137 0 0 1.1E+4 Xe-138 1.4E+3 1.4E+1 2.6E+5 Ar-41 0 2.5E+1 0 1-131 1.9E-2 3.4E-1 5.1E+0 1-133 7.6E-2 1.4E+0 2.0E+1 Cr-51 1.3E-4 6.OE-4 9.OE-3 Mn-54 6.OE-6 6.OE-3 3.6E-2 Fe-59 5.OE-6 8.OE-4 1.5E-2 Co-58 6.OE-6 1.2E-3 4.5E-3 Co-60 2.OE-5 2.OE-2 9.OE-2 Zn-65 2.OE-6 4.OE-3 1.OE-3 Sr-89 6.OE-5 1.8E-4 5.OE-4 Sr-90 2.OE-7 1.OE-5 3.OE-4 Zr-95 1.0E-6 8.OE-4 5.OE-5 Sb-124 3.OE-6 4.OE-4 5.OE-5 Cs-134 3.OE-6 8.OE-3 4.5E-3 Cs-136 5.OE-7 6.OE-4 4.5E-4 Cs-137 6.OE-6 1.1E-2 9.OE-3 Ba-140 1.1 E-4 8.OE-4 1.OE-4 Ce-141 6.OE-6 2.OE-4 2.6E-3 C-14 0 0 9.5E+0 H-3 0 3.6E+1 0*Calculations based upon GALE code and not actual releases.ODCM (BSEP)3-30 Rev. 27 1 TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi)Sector Site Milk Cow Milk Goat Meat Nearest Nearest Boundary Animal Resident Garden NNE 0.7 -0.8 --NE 0.7 4.75* -ENE 0.7 ---E 0.7 ----ESE 0.7 ---1.5 SE 0.7 ---0.9 SSE 0.7 ---1.0 S 0.8 ---1.1 1.1 SSW 0.8 ---1.2 1.9 SW 0.7 ---1.0 1.5 WVSW 0.7 ---1.2 1.2 W 0.7 ---0.8 0.8 WNW 0.6 ---0.8 1.0 NW 0.6 --0.9 4.8 NNW 0.6 ---0.8 4.4 N 0.7 ---0.7 1.0* A "hypothetical" cow milk pathway is located at this point in accordance with 5.3.1 of NUREG 0133.ODCM (BSEP)3-31 Rev. 28 1 TABLE 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTIONS FROM THE STACK Based on Center of Brunswick Plant From Stack to Site Boundaries of Table 3.2-2 Direction Site Boundary Distance (Mi)NNE 0.7 NE 0.7 ENE 0.7 E 0.7 ESE 0.7 SE 0.7 SSE 0.7 S 0.8 SSW 0.8 SW 0.7 WSW 0.7 W 0.7 WNW 0.6 NW 0.6 NNW 0.6 N 0.7 Direction Distance (Mi)NNE 0.7 NE 0.7 ENE 0.7 E 0.6 ESE 0.6 SE 0.6 SSE 0.6 S 0.6 SSW 0.7 SW 0.7 WSW 0.7 W 0.8 WNW 0.7 NW 0.7 NNW 0.7 N 0.8 ODCM (BSEP)3-32 Rev. 25 TABLE 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*
Radionuclide Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per pCi/m 3) pCi/m 3) pCi/m 3) pCi/mr 3)Kr-83m 7.56E-02**
--- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03* The listed dose factors are for radionuclides that may be detected in gaseous effluents.
** 7.56E-02 = 7.56 x 10.2 ODCM (BSEP) 3-33 Rev. 25 TABLE 3.2-5 Pi VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC PLANT*Isotope Inhalation Ground Plane Cow Milk Goat Milk H-3 6.47E+2 0 2.38E+3 4.86E+3 P-32 2.03E+6 0 1.60E+ 11 1.93E+11 Cr-51 1.28E+4 6.67E+6 4.79E+6 5.65E+5 Mn-54 1.OOE+6 1.09E+9 3.89E+7 4.68E+6 Fe-59 1.02E+6 3.92E+8 3.93E+8 5.11 E+6 Co-58 7.77E+5 5.29E+8 6.06E+7 7.28E+6 Co-60 4.51 E+6 4.40E+9 2.1OE+8 2.52E+7 Zn-65 6.47E+5 6.89E+8 1.90E+10 2.29E+9 Rb-86 1.90E+5 1.28E+7 2.22E+10 2.67E+9 Sr-89 2.03E+6 3.16E+4 1.27E+10 2.66E+10 Sr-90 4.09E+7 1.21E+11 2.55E+11 Y-91 2.45E+6 1.52E+6 5.26E+6 6.32E+5 Zr-95 1.75E+6 3.48E+8 8.28E+5 9.95E+4 Nb-95 4.79E+5 1.95E+8 2.06E+8 2.48E+7 Ru-103 5.52E+5 1.55E+8 1.05E+5 1.27E+4 Ru-106 1.16E+7 2.99E+8 1.44E+6 1.73E+5 Ag-110m 3.67E+6 3.14E+9 1.46E+10 1.75E+9 Sn-113 2.30E+5 5.19E+7 2.25E+7 2.25E+6 Te-127m 1.31E+6 1.18E+5 1.04E+9 1.24E+8 Te-129m 1.68E+6 2.86E+7 1.40E+9 1.68E+8 Cs-134 7.03E+5 2.81E+9 6.79E+10 2.04E+11 Cs-136 1.35E+5 2.13E+8 5.76E+9 1.73E+10 Cs-137 6.12E+5 1.15E+9 6.02E+10 1.81E+11 Ba-140 1.60E+6 2.94E+7 2.41E+8 2.89E+7 Ce-141 5.17E+5 1.98E+7 1.37E+7 1.65E+6 Ce-144 9.84E+6 5.84E+7 1.33E+8 1.60E+7 1-131 1.48E+7 2.46E+7 1.06E+12 1.27E+12 1-132 1.69E+5 1.78E+6 1.39E+2 1.64E+2 1-133 3.56E+6 3.54E+6 9.80E+9 1.18E+10 1-135 6.96E+5 3.67E+6 2.27E+7 2.68E+7 Hf-1 81 6.73E+5 4.02E+8 6.55E+5 7.86E+4 Am-241 4.41 E+5 4.96E+7 6.01E+7 7.21 E+6*Units are mrem/yr per pCi/mr 3 for H-3 and the inhalation pathway and mrem/yr per pCi/sec per m-2 for the food and ground plane pathways.ODCM (BSEP) 3-34 Rev. 25
 
===3.3 COMPLIANCE===
 
WITH 10CFR50 (GASEOUS)3.3.1 Noble Gases 1. Cumulation of Doses Section lI.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad.Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following expressions:
During any calendar quarter, for gamma radiation:
3.17x10I {.., {MV[%/Q[,.Q,, +(%/q),,q,,]+
BQ, + bq, }Smrad (3.3-1)During any calendar quarter, for beta radiation:
3.17 x10 8 -IN [X/Q) Q,,.+ (z/q),. q,, + (/Q ,. Q, + (z/q), q , ]< 10mrad (3.3-2)During any calendar year, for gamma radiation:
3.17 x I O., IMj, [(7/0),, + (X/q), q, I+ B, Q, + b, q, }_ 10 mrad (3.3-3)During any calendar year, for beta radiation:
3.17 x 10-8 Y1N, [(X/Q),, Q,. + ('/q), q , + (I/Q), Q,, + (;/q), q,, ]<_ 20 mrad (3.3-4)Where: M = The air dose factor due to gamma emissions for each identified noble gas radionuclide i, mrad/year per V.Ci/m 3 N, = The air dose factor due to beta emissions for each identified noble gas radionuclide i, mrad/year per PtCi/m 3.= The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater than 500 hrs/year), sec/m 3 ODCM (BSEP)3-35 Rev. 25 (Z'/q), = The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases (equal to or less than 500 hours/year), sec/m 3 (J/Q). = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term, free-standing stack releases (greater than 500 hours/year), sec/m 3 (%/q)~. = The relative concentration for areas at or beyond the unrestricted area boundary for short-term, free-standing stack releases (equal to or less than 500 hours year), sec/m 3 q,, The average release of noble gas radionuclide i in gaseous effluents for short-term stack releases (equal to or less than 500 hours/year), pCi qj, The average release of noble gas radionuclide i in gaseous effluents for short-term vent releases (equal to or less than 500 hours/year), pCi , = The average release of noble gas radionuclide i in gaseous effluents for long-term, free-standing stack releases (greater than 500 hours/year), pCi ,, = The average release of noble gas radionuclide i in gaseous effluents for long-term vent releases (greater than 500 hours/year), pCi Bi = The constant for long-term releases (greater than 500 hours/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per pCi/sec b = The constant for short-term releases (equal to or less than 500 hours/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per pCi/sec 3.17 x 10.8 = The inverse of the number of seconds in a year For BSEP all releases are considered long-term.
The incorporation of the stack, Reactor Building, and Turbine Building release points into Expressions 3.3-1 through 3.3-4 results in the following expressions for two units to show compliance with 1OCFR50.ODCM (BSEP)3-36 Rev. 25 During any calendar quarter or year: Gamma radiation:
3.17 x1o-, {M, [,i + + (X1Q)(Q"Q
]+ B,Q,,< 10 mrad per quarler or 20 tarad per year Beta radiation:
3.17 xlO-XN, [ (X/Q)r,(Q,,,, + Q),,,)+ ( Z/Q),h(,e,,Q
+ Qi,, -) + (7z/Q),Q,, i< 2)Onradperquarieror4Omradperjyear (3.3-5)(3.3-6)Where: (X/Q)rb Annual average relative concentration for releases from the Reactor Building, sec/m 3 (/Q),6= Annual average relative concentration for releases from the Turbine Building, sec/m 3 (/Q),= Annual average relative concentration for releases from the stack, sec/m 3 Q = Release of radionuclide i from Reactor Buildings 1 and 2, respectively, [tCi Q ,= Release of radionuclide i from Turbine Buildings 1 and 2, respectively, PiCi ,, = Release of radionuclide i from the stack, pCi At BSEP, the limiting location for noble gases is 0.7 miles NE. Substitution of the appropriate X/Q values into Expressions 3.3-5 and 3.3-6 results in the following:
ODCM (BSEP)3-37 Rev. 25 During any calendar quarter or year: Gamma radiation:
3.I7xIT 8 X,- {M,[.9 X10-6(Qi,h
+~h ++/-6. 0 x10-6 ( + Q + )JB,Q,< 10 mrad per quarter or 20 mrad per year (3.3-7)Beta radiation:
3.17 x1O ,N, [I.9x1O6 (Q,, +Q,,, )+6.O0xO-6 (Qi+Q,,,)+
3.2 X10Q]< 20 mrad per quarter or 40 mrad per year (3.3-8)The determination of the controlling locations for implementation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology.
The incorporation of these parameters into Expressions 3.3-1 through 3.3-4 resulted in the expressions for the controlling locations as presented in Expressions 3.3-7 and 3.3-8. The radionuclide mix was based upon source terms calculated using the NRC GALE Code and is presented in Table 3.2-1 as a function of release point.The two or three highest site boundary (y/Q) values for each release point were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location.
Since mixed mode and elevated releases occur from BSEP and their maximum ZIQ values may not decrease with distance (i.e., the site boundary may not have the highest xIQ values); X/Q values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest x/Q values were considered in conjunction with the radionuclide mix and releases to determine the controlling location.In the determination of the controlling location, annual average x/Q values are utilized.
These values are presented in tables in Appendix A. x/Q values at the limiting site boundary location for releases from the Turbine Buildings, Reactor Buildings, and stack were obtained from Tables A-i, A-7, and A-1 3, respectively, of Appendix A. A description of the derivation of x'Q values is also presented in Appendix A.ODCM (BSEP)3-38 Rev. 30 1 A particular combination of release point mix and meteorology dominates in the determination of the controlling location.
For BSEP the controlling release point is the stack. The dominate factor in determining a control location becomes the Bi values. The NE sector at the site boundary is the control location because of its higher Bi values.Values for Mi and Ni, which were used in the determination of the controlling location and which are to be used by BSEP in Expressions 3.3-7 and 3.3-8 to show compliance with 10CFR50 were presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 106 to convert from picocuries to microcuries.
The following relationship should hold for BSEP to show compliance with ODCM Specification 7.3.8.For the calendar quarter: D7y 10mrad (3.3-9)DP3 -< 20mrad (3.3-10)For the calendar year: Dy _ 20mrad (3.3-11)DP -< 40mrad (3.3-12)Where: Dy The air dose from gamma radiation, mrad DP3 = The air dose from beta radiation, mrad The quarterly limits given above represent one-half the annual design objective of Section ll.B.1 of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-9 through 3.3-12 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.ODCM (BSEP)3-39 Rev. 25 3.3.2 1-131, 1-133, Particulates, and Tritium*1. Cumulation of Doses Section II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ.Based upon NUREG 0133, the dose to an organ of an individual from radioiodines and particulates, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:
During any calendar quarter or year: 3.17x10-8  11R, (W,Q, +w.qj, + W ,Q,. +w,,qj ) (3.3-13)< 7.5 mrem per quarler or 15 mrem per calendar year Where: , = Release of radionuclide i for long-term, free-standing stack releases (greater than 500 hours/year), jtCi Release of radionuclide i for long-term vent releases (greater than 500 hours/year), [tCi qj, Release of radionuclide i for short-term, free-standing stack releases (equal to or less than 500 hours/year), piCi q, = Release of radionuclide i for short-term vent releases (equal to or less than 500 hours/year), &#xfd;iCi W = Dispersion parameter for estimating dose to an individual at the controlling location for long-term, free-standing stack releases (greater than 500 hours/year)
= sec/m 3 for the inhalation pathway and tritium= meters 2 for the food and ground plane pathway*For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.ODCM (BSEP)3-40 Rev. 25 W, The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases (greater than 500 hours/year)
= sec/im 3 for the inhalation pathway and tritium= meters 2 for the food and ground plane pathway W = Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases (equal to or less than 500 hours/year)
= sec/m 3 for the inhalation pathway and tritium= meters 2 for the food and ground plane pathway W = The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hours/year)
= sec/m 3 for the inhalation pathway and tritium= meters-2 for the food and ground plane pathway 3.17 x 108 = The inverse of the number of seconds in a year Ri The dose factor for each identified radionuclide i of the organ of interest, mrem/yr per jiCi/sec per m-2 or mrem/yr per ptCi/m 3 Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines and particulates, may also be released from other sources such as decontamination facility in the Hot Shop. Effluents from the decontamination facilities in the Radioactive Materials Container and Storage Building and hot shop, and any building exfiltration are combined with the Turbine Building's vent releases.
At BSEP all releases are considered long-term in duration.
Therefore, incorporating the various release points into Expression 3.3-13 results in the following expression to show compliance with 10CFR50 for a particular organ: 3.17 x 10 -E, R, WvQ , + WH, (Q, +Q", .) + W" (Q"" +Q"" (3.3-14)< 15.0 mrem per quarter oi" 30 mremn per year ODCM (BSEP)3-41 Rev. 30 1 Where: W = Dispersion parameter for releases from the stack Wrb = Dispersion parameter for releases from the Reactor Building Wtb = Dispersion parameter for releases from the Turbine Building S = Release of radionuclide i from the stack, pCi 00Q,. = Release of radionuclide i from Reactor Buildings 1 and 2, respectively, .ICi Q,,,,Q,, = Release of radionuclide i from Turbine Buildings 1 and 2, respectively, PCi In determining the dose at a particular location, W (as in Section 3.2.2) is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of x/Q.Incorporation of the various pathways into Expression 3.3-14 results in the following:
3.17 xIO-Y,+ Ri,, + R, +/- RB) [(D/QB)Q, + (D/Q.),. (Qr, +Q, ) + (D/Q),h(Q,,, + Q,, )] +R,, [(%/Q), Q,' + (X/Q.),rh (Q,,,, + Q,,, ) + (71Q), (Q,,, + Q',, )]< 15 inrem (per quarter) or 30 mrem (per year)(3.3-15)Where:Dose factor for an organ for radionuclide i for the ground plane exposure pathway, mrem/yr per pCi/sec per M2 R = Dose factor for an organ for radionuclide i for either the cow milk or goat milk pathway, mrem/yr per pCi/sec per M-2 ODCM (BSEP)3-42 Rev. 25 R,, Dose factor for an organ for radionuclide i for the vegetable pathway, mrem/yr per VtCi/sec per M-2 Ri, Dose factor for an organ for radionuclide i for the meat pathway. mrem/yr per paCi/sec per M2 R,, Dose factor for an organ for radionuclide i for the inhalation pathway, mrem/yr per pLCi/m 3 (D!Q)),b Annual average deposition for releases from the Reactor Buildings, m-2 (D/Q),b Annual average deposition for releases from the Turbine Buildings, m-2 (D/Q), Annual average deposition for releases from the stack, m 2 As discussed in Section 3.2.2, for tritium the parameter W for the food pathway is based upon x/Q. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression 3.3-15 may be modified for tritium as: For tritium: 3.17 x IO 8-(Rr, +R,. + RT, (31)D [(/. + (X/Q)r(QTr, + QQ 7"; ) +
O T )] (3.3-16)Where: DT Dose resulting from tritium, mrem Rrk = Dose factor for an organ for tritium for the milk pathway, mrem/yr per PCi/m 3 ODCM (BSEP)3-43 Rev. 25 RT, = Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per PCi/m 3 R Th = Dose factor for an organ for tritium for the beef pathway, mrem/yr per PCi/m 3 R T, = Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per&#xfd;,Ci/m 3 7 = Release of tritium from the stack, pCi 1 ,h2 Release of tritium from Reactor Buildings 1 and 2, respectively, pCi Q, 0 Release of tritium from Turbine Buildings 1 and 2, respectively, pCi To show compliance with 1OCFR50, Expression 3.3-15 is evaluated at the controlling pathway location.
At BSEP the controlling location is a milk cow 4.75 miles in the NE sector. Expression 3.3-15 becomes: 3.17 x 10-83 ( (R +Rj. J2.9x1O-1&deg;Qj, +7.0x10-1 0 (Q., +Qirb2 )+7.2x10-1&deg; (Q, +Q.2 ) I+R,, [2.4x10-8 Q,. +1.9x10-7 (Q',,, +Q.2 )+3.2x10-7 (Q.,, + Q2)}<15 mrem/quarter or 30 mrem/year (3.3-17)For tritium, Equation 3.3-16 reduces to: DT =3.17 x10 8 (R:,., + R, )[2.4xXO-1Q
-+1.9x 0- (QT; M + Q, 7.I)+3.2x10
-(Qr,, + QT,, 2 (3.3-18)Airborne Tritium Releases from the Stabilization Pond and Stabilization Facility Airborne releases of tritium from the Storm Drain Stabilization Pond (SDSP) and Storm Drain Stabilization Facility (SDSF) by evaporation are routinely calculated and dose rates determined based on the following equation: 4 ')(.3.2-19)
Where: DT = Dose rate from the SDSP or SDSF tritium airborne release, mrem/year RTJ = Dose parameter for tritium for the inhalation pathway, mrem/year per PCi/m 3 RTV = Dose parameter for tritium for the ingestion pathway, mrem/year per pCi/m 3 X/Q = Annual average relative concentrations for releases from the SDSP or SDSF to the nearest resident.QT = Release rate of tritium from the SDSP or SDSF, pCi/sec.Note: The nearest resident from the center of the SDSP is typically to the NW at approximately 0.3 miles. The nearest resident from the center of the SDSF is typically to the NNW at approximately 0.5 miles.ODCM (BSEP)3-44 Rev. 35 The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is a function of: a. Radionuclide mix and isotopic release b. Meteorology
: c. Exposure pathway d. Receptor's age The incorporation of these parameters into Expression 3.3-14 results in the respective equations at the controlling location.In the determination of the controlling location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in Table 3.2-1 as a function of release point.In the determination of the controlling location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated.
These include cow milk, goat milk, beef and vegetable ingestion, and inhalation ground plane exposure.
An infant was assumed to be present at all milk pathway locations.
A child was assumed to be present at all vegetable garden and beef animal locations.
The ground plane and inhalation pathways were considered present everywhere a residence was present.For the determination of the controlling location, the highest D/Q values for each release point and release mode for the vegetable garden, cow milk, and goat milk pathways were selected.
At BSEP, no cow milk or goat milk pathways are present. In accordance with NUREG 0133, dose to a"hypothetical" cow milk pathway located 4.75 miles NE was evaluated against existing vegetable garden pathways.
The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1. Based upon these calculations, it was determined that the controlling receptor pathway is the "hypothetical" cow milk-infant pathway in the NE sector, at 4.75 miles.ODCM (BSEP)3-45 Rev. 301 Tables 3.3-1 through 3.3-19 present Ri values for the total body, GI tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, and vegetable and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.
These values were calculated using the methodology described in NUREG 0133 using a grazing period of eight months. A discussion of their calculation is presented in Appendix C.In the determination of the controlling location annual average D/Q and X/Q values are utilized.
D/Q values at the limiting real pathway locations for releases from the Turbine Buildings, Reactor Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A.X/Q values at the same location for these same release points were obtained from Tables A-i, A-7, and A-1 3 of Appendix A. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.Long-term D/Q values for the stack, Reactor Buildings, and Turbine Buildings are provided for the midpoints of the following distances:
0.0-0.5 mi. 0.5-1.0 mi. 1.0-1.5 mi. 1.5-2.0 mi.2.0-2.5 mi. 2.5-3.0 mi. 3.0-3.5 mi. 3.5-4.0 mi.[4.0-4.5 mi. J 4.5-5.0 mi.These values appear in tables in Appendix A. These tables may be utilized if an additional special location arises which is different from one presented in the special locations of Appendix A.The following relationships should hold for BSEP to show compliance with BSEP ODCM Specification 7.3.9.For the calendar quarter: DT  15 mrem (3.3-19)For the calendar year: DT _< 30 mrem (3.3-20)Where: Dt = The dose to any organ -from radioiodines and particulates, mrem ODCM (BSEP)3-46 Rev. 25 The quarterly limits given above represent one-half the annual design objective of Section I1.C of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-19 or 3.3-20 are exceeded, a special report pursuant to Section IV.A of Appendix I of 1 OCFR50 must be filed with the NRC.2. Projection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.11.2.The doses will be projected using Expressions 3.3-17. When the operational conditions are expected to be the same as for the current month, the source term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
This may be accomplished by using projected reactor-days of operation.
For example: If Unit 1 had 28 reactor-days of operation and the dose to the bone was 0.05 mrem (remember there are 6 organs to consider) and Unit 2 was down at 0 reactor-days, then obtain from Planning & Scheduling the projected number of reactor-days for both Units 1 and 2 in the upcoming month.Suppose that the projected reactor-days for Unit I will be 10 reactor-days and for Unit 2, 21 reactor-days.
To calculate the projected dose "x": 28/2 + 0/2 10/2 + 21/2 0.05 x x = 0.06 mrem to the bone This projected dose to the bone is less than 0.6 mrem dose limit to any organ. If the dose to the bone or any other organ exceeds 0.6 mrem, the Turbine Building ventilation exhaust treatment system must be operational in the ensuing month.ODCM (BSEP)3-47 Rev. 25 TABLE 3.3-1 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Ground Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin CR 51 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 5.51E 06 MN54 1.34E09 1.34E09 1.34E09 1.34E09 1.34E09 1.34E09 1.34E09 1.57E09 FE 59 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 3.23E 08 CO 58 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 4.44E 09 CO 60 2.15E10 2.15E10 2.15E10 2.15E10 2.15E10 2.15E10 2.15E10 2.52E10 ZN 65 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 8.61E 08 RB 86 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 1.03E 07 SR 89 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.58E 04 Y 91 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.22E 06 ZR 95 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.89E 08 NB95 1.36E08 1.36E08 1.36E08 1.36E08 1.36E08 1.36E08 1.36E08 1.60E08 RU103 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.27E 08 RU106 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 5.03E 08 AG110M 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.06E 09 SN113 1.44E 07 6.28E 06 1.22E 07 6.21E 06 1.OOE 07 1.33E 07 8.14E 06 4.09E 07 TE127M 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 1.08E 05 TE129M 2.00E 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.34E 07 1131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1132 1.24E06 1.24E06 1.24E06 1.24E06 1.24E06 1.24E06 1.24E06 1.46E06 1133 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 3.OOE 06 1 135 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.99E 06 CS134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.96E 09 CS136 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.69E 08 CS137 1.03E10 1.03E10 1.03E10 1.03E10 1.03E10 1.03E10 1.03E10 1.20E10 BA140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.34E 07 CE141 1.36E07 1.36E07 1.36E07 1.36E07 1.36E07 1.36E07 1.36E07 1.53E07 CE144 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 8.03E 07 HF181 1.97E 08 1.63E 08 2.30E 08 1.70E 08 1.76E 08 2.33E 08 1.82E 08 2.82E 08 AM-241 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 7.45E 08*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-48 Rev. 25 TABLE 3.3-2 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Vegetable AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.28E 03 2.28E 03 0.OOE 01 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 P 32 5.91E 07 1.72E 08 1.53E 09 9.51E 07 0.00E 01 0.00E 01 0.00E01 0.00E 01 CR 51 4.60E 04 1.16E 07 0.OOE 01 0.OOE 01 1.01E 04 2.75E 04 6.10E 04 0.00E 01 MN 54 5.83E 07 9.36E 08 0.00E 01 3.05E 08 9.09E 07 0.O0E 01 0.OOE 01 0.OOE 01 FE 59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 0.OOE 01 0.O0E 01 8.17E 07 0.OOE 01 00 58 6.71 E 07 6.07E 08 0.OOE 01 2.99E 07 0.OOE 01 0.O0E 01 0.OOE 01 0.OOE 01 CO 60 3.67E 08 3.12E 09 0.00E 01 1.66E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 5.77E 08 8.04E 08 4.01E 08 1.28E 09 8.54E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.03E 08 4.36E 07 0.OOE 01 2.21E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 2.87E 08 1.60E 09 1.OOE 10 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 1.64E 11 1.93E 10 6.70E 11 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 1.34E 05 2.76E 09 5.01E 06 O.OOE 01 0.OOE 01 O.OOE 01 O.OOE 01 0.OOE 01 ZR 95 2.51E 05 1.17E 09 1.16E 06 3.71E 05 5.82E 05 0.OOE 01 0.OOE 01 0.OOE 01 NS 95 4.19E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.04E 06 5.53E 08 4.74E 06 0.OOE 01 1.81E 07 0.OOE 01 0.O0E 01 0.OOE 01 RUI06 2.46E 07 1.26E 10 1.94E 08 0.OOE 01 3.75E 08 0.O0E 01 0.O0E 01 0.OOE 01 AGlIOM 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.06E 07 O.OOE 01 O.OOE 01 0.OOE 01 SN 113 1.36E 07 2.53E 08 1.44E 07 5.60E 05 4.09E 05 1.96E 05 O.0OE 01 O.0OE 01 TEI27M 6.12E 07 1.68E 09 5.02E 08 1.80E 08 2.04E 09 1.28E 08 0.OOE 01 0.OOE 01 TE129M 4.71E 07 1.50E 09 2.98E 08 1.11E 08 1.24E 09 1.02E 08 0.OOE 01 0.OOE 01 I 131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 0.OOE 01 0.OOE 01 1132 5.21E 01 2.80E 01 5.57E 01 1.49E 02 2.37E 02 5.21E 03 O.OOE 01 0.OOE 01 1133 1.12E 06 3.30E 06 2.11E 06 3.67E 06 6.40E 06 5.39E 08 0.OOE 01 0.OOE 01 1,135 3.91E 04 1.20E 05 4.05E 04 1.06E 05 1.70E 05 7.OOE 06 0.OOE 01 0.OOE 01 CS134 8.83E 09 1.89E 08 4.54E 09 1.08E 10 3.49E 09 0.OOE 01 1.16E 09 0.OOE 01 CS136 1.19E 08 1.88E 07 4.19E 07 1.66E 08 9.21E 07 0.OOE 01 1.26E 07 0.OOE 01 CS137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 0.OOE 01 1.02E 09 0.OOE 01 BA140 8.40E 06 2.64E 08 1.28E 08 1.61E 05 5.47E 04 0.OOE 01 9.22E 04 0.OOE 01 CE141 1.48E 04 4.99E 08 1.93E 05 1.31E 05 6.07E 04 0.OOE 01 0.OOE 01 0.OOE 01 CE144 1.69E 06 1.06E 10 3.15E 07 1.32E 07 7.80E 06 0.OOE 01 0.OOE 01 0.OOE 01 HF 181 1.08E 06 7.06E 08 9.51E 06 5.36E 04 4.48E 04 3.41E 04 0.OOE 01 0.OOE 01 AM 241 4.12E 09 5.65E 09 5.75E 10 5.37E 10 3.10E 10 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-49 Rev. 25 TABLE 3.3-3 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Vegetable AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.61E 03 2.61E 03 0.OOE 01 2.61E 03 2.61E 03 2.61E 03 2.61E 03 2.61E 03 P 32 6.80E 07 1.47E 08 1.75E 09 1.09E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 6.11E 04 1.03E 07 0.OOE 01 0.OOE 01 1.34E 04 3.39E 04 8.72E 04 0.00E 01 MN 54 8.79E 07 9.09E 08 0.OOE 01 4.43E 08 1.32E 08 0.OOE 01 0.00E 01 0.00E 01 FE 59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 0.00E 01 0.OOE 01 1.30E 08 0.OOE 01 CO 58 9.79E 07 5.85E 08 0.OOE 01 4.25E 07 0.OOE 01 0.OOE 01 0.00E 01 0.00E 01 CO 60 5.57E 08 3.22E 09 0.OOE 01 2.47E 08 0.00E 01 0.00E 01 0.O0E 01 0.OOE 01 ZN 65 8.68E 08 7.88E 08 5.36E 08 1.86E 09 1.19E 09 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.30E 08 4.09E 07 0.OOE 01 2.76E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 4.36E 08 1.81E 09 1.52E 10 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 2.05E 11 2.33E 10 8.32E 11 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 2.06E 05 3.15E 09 7.68E 06 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 1.02E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.90E 06 5.66E 08 6.78E 06 0.OOE 01 2.39E 07 0.OOE 01 0.OOE 01 0.OOE 01 RU106 3.93E 07 1.50E 10 3.12E 08 0.OOE 01 6.02E 08 0.OOE 01 O.0OE 01 0.OOE 01 AG110M 9.39E 06 4.34E09 1.63E 07 1.54E 07 2.95E 07 0.OOE 01 0.O0E 01 0.OOE 01 SN 113 2.02E 07 2.29E 08 1.91E 07 8.03E 05 5.65E 05 2.63E 05 0.OOE 01 0.OOE 01 TE127M 9.44E 07 1.98E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 0.O0E 01 0.OOE 01 TE129M 6.79E 07 1.61E 09 4.29E 08 1.59E 08 1.79E 08 1.38E 08 0.O0E 01 0.OOE 01 1131 5.77E 07 2.13E 07 7.68E 07 1.07E 08 1.85E 08 3.14E 10 0.OOE 01 0.OOE 01 1132 4.72E 01 5.72E 01 5.02E 01 1.31E 02 2.07E 02 4.43E 03 0.OOE 01 0.O0E 01 1133 1.01E 06 2.51E 06 1.96E 06 3.32E 06 5.83E 06 4.64E 08 0.OOE 01 0.OOE 01 1135 3.49E 04 1.04E 05 3.66E 04 9.42E 04 1.49E 05 6.06E 06 0.OOE 01 0.OOE 01 CS134 7.54E 09 2.02E 08 6.90E 09 1.62E 10 5.16E 09 0.OOE 01 1.97E 09 0.OOE 01 CS136 1.13E 08 1.35E 07 4.28E 07 1.68E 08 9.16E 07 0.OOE 01 1.44E 07 0.OOE 01 CS137 4.90E 09 2.OOE 08 1.06E 10 1.41E 10 4.78E 09 0.OOE 01 1.86E 09 0.OOE 01 BA140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 0.O0E 01 1.14E 05 0.OOE 01 CE141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 0.OOE 01 0.OOE 01 0.OOE 01 CE144 2.71E 06 1.27E 10 5.04E 07 2.09E 07 1.25E 07 0.OOE 01 0.OOE 01 0.OOE 01 HF 181 1.54E 06 6.90E 08 1.38E 07 7.58E 04 6.32E 04 4.63E 04 0.OOE 01 0.OOE 01 AM 241 4.97E 09 6.80E 09 6.89E 10 6.50E 10 3.72E 10 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per &#xfd;.LCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-50 Rev. 25 TABLE 3.3-4 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Vegetable AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 4.04E 03 4.04E 03 0.OOE 01 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 P 32 1.42E 08 1.01E 08 3.67E 09 1.72E 08 0.00E 01 0.00E 01 0.OOE 01 0.OOE 01 CR 51 1.16E 05 6.15E 06 0.OOE 01 0.OOE 01 1.76E 04 6.44E 04 1.18E 05 0.OOE 01 MN 54 1.73E 08 5.44E 08 0.O0E 01 6.49E 08 1.82E 08 0.OOE 01 0.OOE 01 0.OOE 01 FE 59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 0.OOE 01 Q.O0E 01 1.84E 08 0.OOE 01 CO 58 1.92E 08 3.66E 08 O.OOE 01 6.27E07 0.OOE01 0.OOE 01 0.OOE 01 O.OOE 01 CO 60 1.11E 09 2.08E 09 0.OOE 01 3.76E 08 0.OOE 01 0.OOE 01 0.00E 01 0.OOE 01 ZN 65 1.70E 09 4.81E 08 1.03E 09 2.74E 09 1.73E 09 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 2.81E 08 2.94E 07 0.OOE 01 4.56E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 1.03E 09 1.40E 09 3.62E 10 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 3.49E 11 1.86E 10 1.38E 12 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 4.89E 05 2.44E 09 1.83E 07 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 7.44E 05 8.71E 08 3.80E 06 8.35E 05 1.20E 06 0.OOE 01 0.OOE 01 O.0OE 01 NB 95 1.12E 05 2.91E 08 4.04E 05 1.57E 05 1.48E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 5.86E 06 3.94E 08 1.52E 07 0.OOE 01 3.84E 07 0.0OE 01 0.OOE 01 0.OOE 01 RU106 9.38E 07 1.17E 10 7.52E 08 0.OOE 01 1.02E 09 0.OOE 01 0.OOE 01 0.OOE 01 AG110M 1.87E 07 2.78E 09 3.46E 07 2.34E 07 4.35E 07 0.O0E 01 O.OOE 01 0.OOE 01 SN 113 3.98E 07 1.46E 08 3.64E 07 1.18E 06 8.09E 05 4.82E 05 0.00E 01 0.OOE 01 TE127M 2.26E 08 1.54E 09 1.90E 09 5.12E 08 5.42E 09 4.55E 08 0.OOE 01 0.OOE 01 TE1 29M 1.55E 08 1.22E 09 9.98E 08 2.79E 08 2.93E 09 3.22E 08 0.OOE 01 0.OOE 01 1131 8.16E 07 1.23E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 0.OOE 01 0.OOE 01 1132 7.53E 01 1.93E 02 8.91E 01 1.64E 02 2.51E 02 7.60E 03 0.OOE 01 0.OOE 01 1133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.36E 06 8.21E 08 0.OOE 01 0.OOE 01 1135 5.54E 04 8.92E 04 6.50E 04 1.17E 05 1.79E 05 1.04E 07 0.OOE 01 0.OOE 01 CS134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 0.OOE 01 2.84E 09 0.OOE 01 CS136 1.43E 08 7.77E 06 8.04E 07 2.21E 08 1.18E 08 0.OOE 01 1.76E 07 0.OOE 01 CS137 3.52E 09 1.50E 08 2.49E 10 2.39E 10 7.78E 09 O.0OE 01 2.80E 09 0.OOE 01 BA140 1.61E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 O.0OE 01 1.44E 05 0.OOE 01 CE141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05 0.OOE 01 0.OOE 01 0.OOE 01 CE144 6.49E 06 9.94E 09 1.22E 08 3.81E 07 2.11E 07 0.OOE 01 0.OOE 01 0.OOE 01 HF 181 3.15E 06 3.17E 08 3.13E 07 1.22E 05 9.78E 04 1.03E 05 0.00E 01 0.OOE 01 AM 241 7.12E 09 5.34E 09 9.50E 10 8.17E 10 4.35E 10 0.OOE 01 0.OOE 01 O.0OE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-51 Rev. 25 TABLE 3.3-5 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Meat AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 3.27E 02 3.27E 02 0.00E 01 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 P 32 1.18E 08 3.43E 08 3.05E 09 1.89E08 0.O0E 01 0.O0E 01 0.00E 01 0.00E 01 CR 51 4.27E 03 1.08E 06 0.00E 01 0.00E 01 9.42E 02 2.56E 03 5.67E 03 0.OOE 01 MN 54 1.06E 06 1.71E 07 0.OOE 01 5.57E 06 1.66E 06 0.00E 01 0.OOE 01 0.00E 01 FE 59 1.43E 08 1.25E 09 1.59E 08 3.74E 08 0.00E 01 0.00E 01 1.04E 08 0.00E 01 GO 58 2.43E 07 2.20E 08 0.OOE 01 1.08E 07 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 CO 60 1.03E 08 8.76E 08 0.00E 01 4.66E 07 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 3.58E 08 4.98E 08 2.49E 08 7.91 E 08 5.29E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.42E 08 6.OOE 07 0.OOE 01 3.04E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 5.23E 06 2.92E 07 1.82E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 2.02E 09 2.38E 08 8.22E 09 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE01 0.OOE 01 Y 91 1.80E 04 3.71E 08 6.75E 05 0.OOE01 0.OOE 01 0.OOE01 O.OOE0 0.OOE 01 ZR 95 2.43E 05 1.14E 09 1.12E 06 3.59E 05 5.64E 05 O.OOE 01 0.OOE 01 0.OOE 01 NB 95 4.12E 05 4.65E 09 1.38E 06 7.66E 05 7.58E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.72E 07 7.38E 09 6.32E 07 0.OOE 01 2.41E 08 0.OOE 01 0.OOE 01 0.OOE 01 RU106 2.19E 08 1.12E 11 1.73E 09 0.OOE 01 3.35E 09 0.OOE 01 .OOE 01 0.OOE 01 AG110M 2.34E 06 1.61E 09 4.27E 06 3.95E06 7.76E06 O.OOE 01 O.OOE 01 0.OOE 01 SN 113 2.80E 07 5.19E 08 2.97E 07 1.15E06 8.40E 05 4.03E 05 O.OOE 01 0.OOE 01 TE127M 1.OOE 08 2.76E 09 8.22E 08 2.94E 08 3.34E 09 2.10E 08 0.OOE 01 0.OOE 01 TE129M 1.17E 08 3.73E 09 7.40E 08 2.76E 08 3.09E 09 2.54E 08 0.OOE 01 0.OOE 01 1131 5.77E 06 2.66E 06 7.04E 06 1.01E07 1.73E 07 3.30E 09 O.OOE 01 0.OOE 01 1133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E 01 0.OOE 01 0.OOE 01 1135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 0.OOE 01 0.OOE 01 CS134 7.81E 08 1.67E 07 4.01E 08 9.55E08 3.09E 08 0.OOE 01 1.03E 08 0.OOE 01 CS136 2.14E 07 3.33E 06 7.53E 06 2.97E 07 1.65E 07 0.OOE 01 2.27E 06 0.OOE 01 CS137 4.99E 08 1.47E 07 5.57E 08 7.61E 08 2.58E 08 0.OOE 01 8.59E 07 0.OOE 01 BA140 1.20E 06 3.77E 07 1.83E 07 2.30E 04 7.82E 03 0.OOE 01 1.32E 04 0.OOE 01 CE141 6.46E 02 2.18E 07 8.42E 03 5.69E 03 2.65E 03 0.OOE 01 0.OOE 01 0.OOE 01 CE144 4.70E 04 2.96E 08 8.75E 05 3.66E 05 2.17E 05 0.OOE 01 0.OOE 01 0.OOE 01 HF 181 1.52E 06 9.97E 08 1.34E 07 7.57E 04 6.33E 04 4.81E 04 O.OOE 01 0.OOE 01 AM 241 1.80E 07 2.47E 07 2.52E 08 2.35E 08 1.36E 08 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per [LCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-52 Rev. 25 TABLE 3.3-6 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Meat AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.95E 02 1.95E 02 0.OOE 01 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 P 32 9.98E 07 2.16E 08 2.58E 09 1.60E 08 0.00E 01 0.OOE 01 0.OOE 01 0.OOE 01 CR 51 3.42E 03 5.75E 05 0.OOE 01 0.OOE 01 7.49E 02 1.90E 03 4.88E 03 0.OOE 01 MN 54 8.43E 05 8.72E 06 0.OOE 01 4.25E 06 1.27E 06 0.00E 01 0.00E 01 0.OOE 01 FE 59 1.15E 08 7.02E 08 1.27E 08 2.97E 08 0.00E 01 0.00E 01 9.36E 07 0.OOE 01 CO 58 1.93E 07 1.15E 08 0.OOE 01 8.36E 06 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 CO 60 8.15E 07 4.71E 08 0.OOE 01 3.62E 07 0.00E 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 2.83E 08 2.57E 08 1.75E 08 6.07E 08 3.89E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.19E 08 3.76E 07 0.OOE 01 2.54E 08 0.O0E 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 4.40E 06 1.83E 07 1.54E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 1.31E 09 1.49E 08 5.32E 09 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 1.52E 04 2.33E 08 5.68E 05 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 1.95E 05 6.53E 08 8.97E 05 2.83E 05 4.16E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 3.29E 05 2.55E 09 1.08E 06 5.97E 05 5.79E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.20E 07 4.30E 09 5.15E 07 0.OOE 01 1.82E 08 0.OOE 01 0.OOE 01 0.OOE 01 RU106 1.84E 08 7.OOE 10 1.46E 09 O.0OE 01 2.81E 09 0.OOE 01 0.OOE 01 0.OOE 01 AG110M 1.86E 06 8.59E 08 3.23E 06 3.06E 06 5.83E 06 0.OOE 01 0.OOE 01 0.OOE 01 SN 113 2.22E 07 2.51E 08 2.09E 07 8.80E 05 6.19E 05 2.89E 05 0.OOE 01 0.OOE 01 TE127M 8.25E 07 1.73E 09 6.94E 08 2.46E 08 2.81E 09 1.65E 08 0.OOE 01 0.OOE 01 TE129M 9.81E 07 2.33E 09 6.20E 08 2.30E 08 2.59E 09 2.OOE 08 0.OOE 01 0.OOE 01 1131 4.40E 06 1.62E 06 5.85E 06 8.20E 06 1.41E 07 2.39E 09 O.0OE 01 0.OOE 01 1133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.1OE-01 5.65E 01 0.OOE 01 0.OOE 01 1135 4.88E-17 1.46E-16 5.11E-17 1.32E-16 2.08E-16 8.46E-15 0.O0E 01 0.OOE 01 CS134 3.48E 08 9.34E 06 3.19E 08 7.51E 08 2.39E 08 0.OOE 01 9.11E 07 0.OOE 01 CS136 1.55E 07 1.86E 06 5.87E 06 2.31E 07 1.26E 07 0.OOE 01 1.98E 06 0.OOE 01 CS137 2.14E 08 8.75E 06 4.62E 08 6.15E 08 2.09E 08 0.OOE 01 8.13E 07 0.OOE 01 BA140 9.76E 05 2.34E 07 1.51E 07 1.86E 04 6.29E 03 0.OOE 01 1.25E 04 0.OOE 01 CE141 5.42E 02 1.35E 07 7.07E 03 4.72E 03 2.22E 03 .OOE 01 O.0OE 01 0.OOE 01 CE144 3.96E 04 1.85E 08 7.37E 05 3.05E 05 1.82E 05 0.OOE 01 O.OE 01 0.OOE 01 HF 181 1.23E 06 5.50E 08 1.10E 07 6.0SE 04 5.04E 04 3.69E 04 O.0OE 01 0.OOE 01 AM 241 1.13E 07 1.55E 07 1.57E 08 1.48E 08 8.49E 07 0.OOE 01 O.0OE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-53 Rev. 25 TABLE 3.3-7 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Meat AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.36E 02 2.36E 02 0.OOE 01 2.36E 02 2.36E 02 2.36E 02 2.36E 02 2.36E 02 P 32 1.87E 08 1.34E 08 4.86E 09 2.27E 08 0.00E 01 0.00E 01 0.OOE 01 0.00E 01 CR 51 5.33E 03 2.83E 05 0.OOE 01 0.OOE 01 8.09E 02 2.96E 03 5.40E 03 0.OOE 01 MN 54 1.30E 06 4.08E 06 0.OOE 01 4.86E 06 1.36E 06 0.00E 01 O.OOE 01 O.OOE 01 FE 59 1.82E 08 3.80E 08 2.25E 08 3.65E08 0.OOE 01 O.OOE 01 1.06E 08 O.OOE 01 CO 53 2.99E 07 5.70E 07 0.00E 01 9.76E 06 0.OOE 01 0.OOE 01 0.00E 01 0.00E 01 CO 60 1.27E 08 2.38E 08 0.00E 01 4.30E 07 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 4.35E 08 1.23E 08 2.62E 08 6.99E 08 4.40E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB '36 2.21E 08 2.32E 07 0.OOE 01 3.60E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 8.31E 06 1.13E 07 2.91E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 1.74E 09 9.26E 07 6.87E 09 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 2.87E 04 1.43E 08 1.07E 06 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 3.12E 05 3.65E 08 1.59E 06 3.50E 05 5.01E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 5.17E 05 1.34E 09 1.86E 06 7.23E 05 6.80E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 3.58E 07 2.41E 09 9.31E 07 0.OOE 01 2.34E 08 0.OOE 01 0.OOE 01 0.OOE 01 RU106 3.43E 08 4.27E 10 2.75E 09 0.OOE 01 3.71E 09 0.O0E 01 0.OOE 01 0.OOE 01 AGi10M 2.89E 06 4.30E 08 5.36E 06 3.62E 06 6.74E 06 0.O0E 01 0.O0E 01 0.OOE 01 SN 113 3.43E 07 1.25E 08 3.14E 07 1.01E 06 6.97E 05 4.15E 05 0.OOE 01 0.OOE 01 TE127M 1.55E 08 1.06E 09 1.31E 09 3.52E 08 3.73E 09 3.13E 08 0.OOE 01 O.0OE 01 TE129M 1.81E 08 1.42E 09 1.17E 09 3.26E 08 3.43E 09 3.77E 08 0.OOE 01 0.OOE 01 1131 6.20E 06 9.72E 05 1.09E 07 1.09E 07 1.79E 07 3.61E 09 0.OOE 01 0.OOE 01 1133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E 02 0.OOE 01 O.0OE 01 1135 7.87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 0.OOE 01 0.OOE 01 CS 134 1.95E 08 4.93E 06 5.63E 08 9.23E 08 2.86E 08 0.OOE 01 1.03E 08 0.OOE 01 CS 136 1.80E 07 9.78E 05 1.01E 07 2.78E 07 1.48E 07 0.OOE 01 2.21E 06 0.OOE 01 CS 137 1.20E 08 5.10E 06 8.51E 08 8.15E 08 2.65E 08 0.OOE 01 9.55E 07 0.OOE 01 BA 140 1.63E 06 1.42E 07 2.80E 07 2.45E 04 7.97E 03 0.OOE 01 1.46E 04 0.OOE 01 CE 141 9.86E 02 8.28E 06 1.33E 04 6.64E 03 2.91E 03 0.OOE 01 0.OOE 01 0.OOE 01 CE 144 7.42E 04 1.14E 08 1.39E 06 4.36E 05 2.41E 05 0.OOE 01 0.OOE 01 O.0OE 01 HF 181 2.02E 06 3.31E 08 2.01 E07 7.79E 04 6.26E 04 6.56E 04 0.OOE 01 .OOE 01 AM 241 1.27E 07 9.49E 06 1.69E 08 1.45E 08 7.74E 07 0.OOE 01 0.OOE 01 0.00E 01*R Values in units of mrem/yr per piCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-54 Rev. 25 TABLE 3.3-8 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Cow Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 7.69E 02 7.69E 02 0.OOE-01 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 P 32 4.32E 08 1.26E 09 1.12E 10 6.95E 08 0.00E-01 0.00E-01 0.00E-01 0.OOE-01 CR 51 1.73E 04 4.36E 06 0.OOE-01 0.OOE-01 3.82E 03 1.04E 04 2.30E 04 0.OOE-01 MN 54 9.76E 05 1.57E 07 0.OOE-01 5.11E 06 1.52E 06 0.OOE-01 Q.O0E-01 0.00E-01 FE 59 1.60E 07 1.39E 08 1.77E 07 4.17E 07 O.0OE-01 0.OOE-01 1.17E 07 0.OOE-01 CO 58 6.28E 06 5.68E 07 0.OOE-01 2.80E 06 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 CO 60 2.24E 07 1.91E 08 0.OOE-01 1.02E 07 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZN 65 1.38E 09 1.92E 09 9.59E 08 3.05E 09 2.04E 09 0.OOE-01 0.O0E-01 0.OOE-01 RB 86 7.54E 08 3.19E 08 0.OOE-01 1.62E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 2.50E 07 1.40E 08 8.70E 08 0.OOE-01 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 SR 90 7.59E 09 8.94E 08 3.09E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 1.37E 02 2.81E 06 5.11E 03 0.OOE-01 0.OOE-01 0.00E-01 0.OOE-01 0.OOE-01 ZR 95 1.22E 02 5.71E 05 5.62E 02 1.80E 02 2.83E 02 0.O0E-01 0.OOE-01 0.00E-01 NB 95 1.48E 04 1.67E 08 4.95E 04 2.75E 04 2.72E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 2.63E 02 7.14E 04 6.11E 02 0.OOE-01 2.33E 03 0.OOE-01 0.OOE-01 0.O0E-01 RU 106 1.60E 03 8.17E 05 1.26E 04 0.OOE-01 2.44E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 2.04E 07 1.40E 10 3.71E 07 3.44E 07 6.76E 07 0.OOE-01 0.00E-01 0.OOE-01 SN 113 1.32E 06 2.44E 07 1.40E 06 5.41E 04 3.96E 04 1.90E 04 0.OOE 01 0.OOE 01 TE127M 4.11E 06 1.13E 08 3.37E 07 1.21E 07 1.37E 08 8.62E 06 0.OOE-01 0.OOE-01 TE129M 6.19E 06 1.97E 08 3.91E 07 1.46E 07 1.63E 08 1.34E 07 0.OOE-01 0.OOE-01 1131 1.59E 08 7.32E 07 1.94E 08 2.77E 08 4.76E 08 9.09E 10 0.OOE-01 0.OOE-01 1132 1.03E-01 5.51E-02 1.10E-01 2.93E-01 4.67E-01 1.03E 01 0.OOE-01 0.OOE-01 1133 1.40E 06 4.13E 06 2.64E 06 4.59E 06 8.01E 06 6.75E 08 0.OOE-01 0.OOE-01 1135 9.03E 03 2.76E 04 9.34E 03 2.45E 04 3.92E 04 1.61E 06 0.OOE-01 0.OOE-01 CS 134 6.71E 09 1.44E 08 3.45E 09 3.21E 09 2.66E 09 0.OOE-01 8.82E 08 O.OOE-01 CS 136 4.73E 08 7.46E 07 1.66E 08 6.57E 08 3.65E 08 0.OOE-01 5.01E 07 0.OOE-01 CS 137 4.22E 09 1.25E 08 471E 09 6.44E 09 219E 09 0,OOE-01 7.27E 08 0,00E-01 BA 140 1.12E 06 3.53E 07 1.71E 07 2.15E 04 7.32E 03 0.OOE-01 1.23E 04 0.OOE-01 CE 141 2.23E 02 7.52E 06 2.91E 03 1.97E 03 9.14E 02 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 1.15E 04 7.26E 07 2.15E 05 8.97E 04 5.32E 04 0.O0E-01 0.OOE-01 0.OOE-01 HF 181 6.68E 02 4.39E 05 5.91E 03 3.33E 01 2.79E 01 2.12E 01 0.OOE 01 0.OOE 01 AM 241 1.27E 06 1.74E 06 1.77E 07 1.66E 07 9.56E 06 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-55 Rev. 25 TABLE 3.3-9 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Cow Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.OE 03 1.OOE 03 0.OOE-01 1.OOE 03 1.OE 03 1.OOE 03 1.OOE 03 1.OOE 03 P 32 8.OOE 08 1.73E 09 2.06E 10 1.28E 09 0.00E-01 0.00E-01 0.O0E-01 0.00E-01 CR 51 3.02E 04 5.08E 06 0.OOE-01 0.OOE-01 6.63E 03 1.68E 04 4.32E 04 0.OOE-01 MN 54 1.69E 06 1.75E 07 0.OOE-01 8.52E 06 2.54E 06 0.OOE-01 0.OOE-01 0.OOE-01 FE 59 2.79E 07 1.71E 08 3.10E 07 7.23E 07 0.OOE-01 0.OOE-01 2.28E 07 0.OOE-01 CO 58 1.09E 07 6.50E 07 0.OOE-01 4.72E 06 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CO 60 3.88E 07 2.25E 08 0.00E-01 1.72E 07 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZN 65 2.38E 09 2.16E 09 1.47E 09 5.11E 09 3.27E 09 0.OOE-01 0.OOE-01 0.O0E-01 RB 86 1.39E 09 4.37E 08 0.OOE-01 2.95E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 4.59E 07 1.91E 08 1.60E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 1.08E 10 1.23E 09 4.37E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 2.52E 02 3.85E 06 9.40E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 2.13E 02 7.16E 06 9.83E 02 3.10E 02 4.56E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 2.58E 04 2.OOE 08 8.45E 04 4.68E 04 4.54E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 4.65E 02 9.08E 04 1.09E 03 0.OOE-01 3.83E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 2.93E 03 1.11E 06 2.32E 04 0.OOE-01 4.48E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 3.53E 07 1.63E 10 6.14E 07 5.81E 07 1.11E 08 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 2.28E 06 2.58E 07 2.15E 06 9.06E 04 6.37E 04 2.97E 04 0.OOE 04 0.OOE 01 TE127M 7.39E 06 1.55E 08 6.22E 07 2.21E 07 2.52E 08 1.48E 07 0.OOE-01 0.OOE-01 TE129M 1.13E 07 2.69E 08 7.15E 07 2.65E 07 2.99E 08 2.31E 07 0.OOE-01 0.OOE-01 1131 2.65E 08 9.75E 07 3.52E 08 4.93E 08 8.48E 08 1.44E 11 0.OOE-01 0.OOE-01 1132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E 01 0.OOE-01 0.OOE-01 1133 2.49E 06 6.19E 06 4.82E 06 8.18E 06 1.43E 07 1.14E 09 0.OOE-01 0.OOE-01 1135 1.58E 04 4.74E 04 1.66E 04 4.27E 04 6.75E 04 2.75E 06 0.OOE-01 0.OOE-01 CS 134 6.54E 09 1.75E 08 5.99E 09 1.41E 10 4.48E 09 0.OOE-01 1.71E 09 0.OOE-01 CS 136 7.48E 08 8.97E 07 2.83E 08 1.11E 09 6.07E 08 0.OOE-01 9.56E 07 0.OOE-01 CS 137 3.96E 09 1.62E 08 8.54E 09 1.14E 10 3.87E 09 0.OOE-01 1.50E 09 0.OOE-01 BA 140 1.99E 06 4.77E 07 3.09E 07 3.79E 04 1.28E 04 0.OOE-01 2.55E 04 0.OOE-01 CE 141 4.09E 02 1.02E 07 6.33E 03 3.56E 03 1.68E 03 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 2.12E 04 9.93E 07 3.95E 05 1.63E 05 9.76E 04 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 1.18E 03 5.28E 05 1.06E 04 5.81E 01 4.84E 01 3.55E 01 0.00E 01 0.OOE 01 AM 241 1.74E 06 2.38E 06 2.42E 07 2.28E 07 1.31E 07 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-56 Rev. 25 TABLE 3.3-10 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Cow Milk AGE GROUP = Child Nuclicle T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.58E 03 1.58E 03 0.OOE-01 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 P 32 1.96E 09 1.41E 09 5.09E 10 2.38E 09 Q.O0E-01 0.OOE-01 0.OOE-01 0.OOE-01 CR 51 6.17E 04 3.27E 06 0.00E-01 0.OOE-01 9.36E 03 3.42E 04 6.25E 04 0.O0E-01 MNI 54 3.39E 06 1.07E 07 O.OOE-01 1.27E 07 3.57E 06 0.00E-01 0.OOE-01 0.OOE-01 FE 59 5.79E 07 1.21E 08 7.18E 07 1.16E 08 O.OOE-01 OQE-01 3.37E 07 0.OOE-01 CO 58 2.21E 07 4.20E 07 0.00E-01 7.21E 06 0.OOE-01 0.OOE-01 0.00E-01 0.00E-01 CO 60 7.90E 07 1.48E 08 0.00E-01 2.68E 07 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZN 65 4.79E 09 1.35E 09 2.89E 09 7.70E 09 4.85E 09 O.QOE-01 0.O0E-01 0.OOE-01 RB 86 3.36E 09 3.52E 08 0.OQE-01 5.47E 09 Q.O0E-01 0.O0E-01 0.OOE-01 0.OOE-01 SR 89 1.13E 08 1.54E 08 3.97E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 O.0OE-01 SR 90 1.87E 10 9.95E 08 7.38E 10 0.OOE-01 0.OOE-01 0.OOE-01 O.0OE-01 0.OOE-01 Y 91 6.21E 02 3.09E 06 2.32E 04 0.OOE-01 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 ZR 95 4.47E 02 5.23E 05 2.28E 03 5.02E 02 7.18E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 5.31E 04 1.37E 08 1.91E 05 7.42E 04 6.98E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 9.88E 02 6.65E 04 2.57E 03 0.OOE-01 6.47E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 7.14E 03 8.90E 05 5.72E 04 0.OOE-01 7.72E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 7.19E 07 1.07E 10 1.33E 08 9.OOE 07 1.68E 08 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 4.61E06 1.69E07 4.22E08 4.13E07 4.37E08 3.66E07 0.O0E01 0.00E01 TE1 27M 1.82E 07 1.24E 08 1.53E 08 4.13E 07 4.37E 08 3.66E 07 0.OOE-01 0.OOE-01 TE129M 2.74E 07 2.15E 08 1.76E 08 4.92E 07 5.18E 08 5.68E 07 0.OOE-01 0.OOE-01 1 131 4.88E 08 7.64E 07 8.54E 08 8.59E 08 1.41E 09 2.84E 11 0.OOE-01 0.O0E-01 1 132 3.89E-01 9.95E-01 4.60E-01 8.45E-01 1.29E 00 3.92E 01 0.OOE-01 0.OOE-01 1133 5.48E 06 5.84E 06 1.17E 07 1.45E 07 2.41E 07 2.69E 09 Q.O0E-01 0.OOE-01 1135 3.35E 04 5.39E 04 3.93E 04 7.07E 04 1.08E 05 6.26E 06 0.OOE-01 0.0OE-01 CS 134 4.78E 09 1.22E 08 1.38E 10 2.27E 10 7.03E 09 0.OOE-01 2.52E 09 0.OOE-01 CS 136 1.14E 09 6.17E 07 6.39E 08 1.76E 09 9.36E 08 0.OOE-01 1.40E 08 0.OOE-01 CS 137 2.91E 09 1.23E 08 2.06E 10 1.97E 10 6.42E 09 0.OOE-01 2.31E 09 0.OOE-01 BA 140 4.36E 06 3.78E 07 7.47E 07 6.54E 04 2.13E 04 0.OOE-01 3.90E 04 0.OOE-01 CE 141 9.73E 02 8.17E 06 1.31E 04 6.55E 03 2.87E 03 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 5.20E 04 7.96E 07 9.74E 05 3.05E 05 1.69E 05 0.OOE-01 0.00E-01 0.OOE-01 HF 181 2.53E 03 4.16E 05 2.51E 04 9.79E 01 7.86E 01 8.24E 01 0.OOE 01 0.OOE 01 AM 241 2.55E 06 1.91E 06 3.40E 07 2.92E 07 1.56E 07 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per iaCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-57 Rev. 25 TABLE 3.3-11 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Cow Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.40E 03 2.40E 03 0.OOE-01 2.40E 03 2.40E 03 2.40E 03 2.40E 03 2.40E 03 P 32 4.06E 09 1.42E 09 1.05E 11 6.17E 09 0.00E-01 0.00E-01 O.0OE-01 0.OOE-01 CR 51 9.77E 04 2.85E 06 0.OOE-01 0.00E-01 1.39E 04 6.38E 04 1.24E 05 0.OOE-01 MN 54 5.37E 06 8.71E 06 O.0OE-01 2.37E 07 5.25E 06 0.O0E-01 0.OOE-01 0.OOE-01 FE 59 9.23E 07 1.12E 08 1.34E 08 2.34E 08 0.OOE-01 0.00E-01 6.92E 07 0.OOE-01 CO 58 3.60E 07 3.59E 07 0.OOE-01 1.44E 07 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CO 60 1.29E 08 1.30E 08 0.00E-01 5.47E 07 0.OOE-01 O.0OE-01 0.OOE-01 0.OOE-01 ZN 65 6.14E 09 1.12E 10 3.88E 09 1.33E 10 6.45E 09 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 6.86E 09 3.55E 08 0.OOE-01 1.39E 10 O.0OE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 2.17E 08 1.55E 08 7.55E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 2.05E 10 1.OOE 09 8.04E 10 0.OOE-01 0.OOE-01 O.0OE-0 0.EOO-01 0.OOE-01 Y 91 1.16E 08 3.12E 06 4.36E 04 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 7.01E 02 4.92E 05 4.05E 03 9.88E 02 1.06E 03 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 8.48E 04 1.24E 08 3.56E 05 1.47E 05 1.05E 05 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 1.74E 03 6.33E 04 5.21E 03 0.OOE-01 1.08E 04 .OOE-01 O.0OE-O 0.OOE-01 RU 106 1.47E 04 8.95E 05 1.18E 05 0.OOE-01 1.39E 05 0.OOE-O 0.EOO-01 0.OOE-01 AG110M 1.19E 08 9.32E 09 2.46E 08 1.80E 08 2.57E 08 .OOE-01 O.0OE-0 0.OOE-01 SN 113 6.66E 06 1.37E 07 6.46E 06 2.45E 05 1.32E 05 9.34E 04 O.OOE 01 0.OOE 01 TE127M 3.75E 07 1.25E 08 3.1OE 08 1.03E 08 7.64E 08 8.96E 07 O.0OE-01 0.OOE-01 TE129M 5.57E 07 2.16E 08 3.62E 08 1.24E 08 9.05E 08 1.39E 08 0.OOE-01 0.OOE-01 1131 9.23E 08 7.49E 07 1.78E 09 2.10E 09 2.45E 09 6.90E 11 0.00E-01 0.OOE-01 1132 6.90E-01 1.57E-00 9.55E-01 1.94E 00 2.16E 00 9.09E 01 0.OOE-01 0.OOE-01 1133 1.05E 07 6.09E 06 2.47E 07 3.60E 07 4.23E 07 6.55E 09 0.OOE-01 0.OOE-01 1135 5.93E 04 5.83E 04 8.17E 04 1.63E 05 1.81E 05 1.46E 07 0.OOE-01 0.OOE-01 CS 134 4.19E 09 1.13E 08 2.23E 10 4.15E 10 1.07E 10 0.OOE-01 4.38E 09 O.0OE-01 CS 136 1.37E 09 5.58E 07 1.25E 09 3.67E 09 1.46E 09 0.OOE-01 2.99E 08 0.OOE-01 CS 137 2.72E 09 1.20E 08 3.28E 10 3.84E 10 1.03E 10 0.OOE-01 4.18E 09 0.OOE-01 BA 140 7.91E 06 3.77E 07 1.54E 08 1.54E 05 3.65E 04 0.OOE-01 9.43E 04 O.0OE-01 CE 141 1.87E 03 3.21E 06 2.60E 04 1.59E 04 4.90E 03 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 7.82E 04 8.01E 07 1.40E 06 5.71E 05 2.31E 05 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 4.23E 03 3.94E 05 4.78E 04 2.26E 02 1.32E 02 1.91E 02 0.OOE 01 0.OOE 01 AM 241 2.72E 06 1.92E 06 3.65E 07 3.17E 07 1.64E 07 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per P.Ci/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-58 Rev. 25 TABLE 3.3-12 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Goat Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.57E 03 1.57E 03 0.OOE-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 P 32 5.19E 08 1.51E 09 1.34E 10 8.34E 08 O.QOE-01 0.OOE-01 O.COE-01 0.OOE-01 CR 51 2.08E 03 5.23E 05 0.OOE-01 O.QOE-01 4.58E 02 1.24E 03 2.76E 03 0.00E-01 MN 54 1.17E 05 1.88E 06 0.OOE-01 6.14E 05 1.83E 05 0.00E-01 0.OOE-01 0.00E-01 FE 59 2.08E 05 1.81E 06 2.31E 05 5.42E 05 0.O0E-01 0.O0E-01 1.51E 05 0.00E-01 CO 58 7.54E 05 6.82E 06 0.00E-01 3.36E 05 0.00E-01 0.OOE-01 0.OOE-01 0.OOE-01 CO 60 2.69E 06 2.29E 07 0.OOE-01 1.22E 06 0.00E-01 0.00E-01 0.00E-01 0.OOE-01 ZN 65 1.65E 08 2.31E 08 1.15E 08 3.66E 08 2.45E 08 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 9.05E 07 3.83E 07 0.OOE-01 1.94E 08 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 SR 89 5.24E 07 2.93E 08 1.83E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 1.59E 10 1.88E 09 6.49E 10 0.OOE-01 0.OOE-01 0.OOE-01 O.00E-01 0.OOE-01 Y 91 1.64E 01 3.37E 05 6.13E 02 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 1.46E 01 6.85E 04 6.74E 01 2.16E 01 3.39E 01 0.OOE-01 0.OOE-01 O.00E-01 NB 95 1.78E 03 2.01E 07 5.94E 03 3.31E 03 3.27E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU '103 3.16E 01 8.56E 03 7.33E 01 0.OOE-01 2.80E 02 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 1.92E 02 9.81E 04 1.52E 03 0.OOE-01 2.93E 03 0.OOE-01 0.OOE-01 0.OOE-01 AG-110M 2.45E 06 1.68E 09 4.46E 06 4.12E 06 8.11E 06 0.OOE-01 0.O0E-01 0.OOE-01 SN 113 1.32E 05 2.44E 06 1.40E 05 5.41 E 03 3.96E 03 1.90E 03 0.OOE 01 0.OOE 01 TE127M 4.93E 05 1.36E 07 4.05E 06 1.45E 06 1.64E 07 1.03E 06 0.OOE-01 O.0OE-01 TEI29M 7.43E 05 2.36E 07 4.69E 06 1.75E 06 1.96E 07 1.61E 06 0.OOE-01 O.0OE-01 1131 1.91E 08 8.78E 07 2.33E 08 3.33E 08 5.71E 08 1.09E 11 0.OOE-01 0.OOE-01 1132 1.23E-01 6.61E-02 1.32E-01 3.52E-01 5.61 E-01 1.23E 01 0.OOE-01 0.OOE-01 1133 1.68E 06 4.95E 06 3.17E 06 5.51E 06 9.61E 06 8.1OE 08 0.OOE-01 0.OOE-01 1135 1.08E 04 3.32E 04 1.12E 04 2.94E 04 4.71E 04 1.94E 06 0.OOE-01 0.OOE-01 CS 134 2.01E 10 4.31E 08 1.03E 10 2.46E 10 7.97E 09 0.OOE-01 2.65E 09 0.OOE-01 CS 136 1.42E 09 2.24E 08 4.99E 08 1.97E 09 1.10E 09 0.OOE-01 1.50E 08 0.OOE-01 CS 137 1.27E 10 3.74E 08 1.41E 10 1.93E 10 6.56E 09 0.OOE-01 2.18E 09 O.0OE-01 BA 140 1.35E 05 4.23E 06 2.06E 06 2.58E 03 8.78E 02 0.OE-01 1.48E 03 O.0OE-01 CE 141 2.68E 01 9.03E 05 3.49E 02 2.36E 02 1.10E 02 0.OOE-01 0.OOE-01 O.0OE-01 CE 144 1.38E 03 8.71E 06 2.58E 04 1.08E 04 6.39E 03 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 8.02E 01 5.26E 04 7.09E 02 3.99E 00 3.34E 00 2.54E 00 0.OOE 01 0.OOE 01 AM 241 1.52E 05 2.09E 05 2.12E 06 1.99E 06 1.15E 06 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-59 Rev. 25 TABLE 3.3-13 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.04E 03 2.04E 03 O.0OE-01 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 P 32 9.60E 08 2.08E 09 2.48E 10 1.53E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CR 51 3.63E 03 6.10E 05 0.OOE-01 0.OOE-01 7.95E 02 2.02E 03 5.18E 03 0.OOE-01 MN 54 2.03E 05 2.10E 06 0.OOE-01 1.02E 06 3.05E 05 0.OOE-01 0.OOE-01 0.OOE-01 FE 59 3.63E 05 2.22E 06 4.03E 05 9.40E 05 0.OOE-01 0.OOE-01 2.96E 05 0.OOE-01 CO 58 1.30E 06 7.80E 06 0.OOE-01 5.66E 05 0.O0E-01 0.OOE-01 0.OOE-01 0.OOE-01 CO 60 4.66E 06 2.69E 07 0.OOE-01 2.07E 06 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 ZN 65 2.86E 08 2.60E 08 1.77E 08 6.13E 08 3.93E 08 0.OOE-01 0.OOE-01 O.0OE-01 RB 86 1.66E 08 5.24E 07 0.OOE-01 3.54E 08 O.0OE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 9.65E 07 4.01E 08 3.37E 09 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 O.0OE-01 SR 90 2.27E 10 2.58E 09 9.18E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 3.02E 01 4.62E 05 1.13E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 2.56E 01 8.59E 04 1.18E 02 3.72E 01 5.47E 01 0.OOE-01 0.O0E-01 0.OOE-01 NB 95 3.09E 03 2.40E 07 1.01E 04 5.62E 03 5.45E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 5.58E 01 1.09E 04 1.30E 02 0.OOE-01 4.60E 02 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 3.51E 02 1.34E 05 2.79E 03 O.0OE-01 5.38E 03 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 4.24E 06 1.96E 09 7.37E 06 6.97E 06 1.33E 07 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 2.28E 05 2.58E 06 2.15E 05 9.06E 03 6.37E 03 2.97E 03 0.OOE 01 0.OOE 01 TE127M 8.87E 05 1.86E 07 7.46E 06 2.65E 06 3.02E 07 1.77E 06 0.OOE-01 0.O0E-01 TE129M 1.36E 06 3.22E 07 8.58E 06 3.19E 06 3.59E 07 2.77E 06 0.OOE-01 0.OOE-01 1131 3.18E 08 1.17E 08 4.22E 08 5.91E 08 1.02E 09 1.73E 11 O.0OE-01 0.OOE-01 1132 2.19E-01 2.66E-01 2.33E-01 6.11E-01 9.62E-01 2.06E 01 0.OOE-01 0.OOE-01 1133 2.99E 06 7.43E 06 5.79E 06 9.81E 06 1.72E 07 1.37E 09 O.0OE-01 0.OOE-01 1135 1.90E 04 5.63E 04 1.99E 04 5.13E 04 8.1OE 04 3.30E 06 O.0OE-01 0.OOE-01 CS 134 1.96E 10 5.26E 08 1.80E 10 4.23E 10 1.34E 10 0.OOE-01 5.13E 09 0.OOE-01 CS 136 2.25E 09 2.69E 07 8.50E 08 3.34E 09 1.82E 09 0.OOE-01 2.87E 08 0.OOE-01 CS 137 1.19E 10 4.85E 08 2.56E 10 3.41E 10 1.16E 10 O.0OE-01 4.51E 09 0.OOE-01 BA 140 2.39E 05 5.72E 06 3.71E 06 4.55E 03 1.54E 03 O.0OE-01 3.06E 03 0.OOE-01 CE 141 4.91E 01 1.22E 06 6.40E 02 4.27E 02 2.01E 02 0.O0E-01 0.OOE-01 0.OOE-01 CE 144 2.55E 03 1.19E 07 4.74E 04 1.96E 04 1.17E 04 0.OOE-01 0.OOE-01 O.0OE-01 HF 181 1.41E 02 6.34E 04 1.27E 03 6.97E 00 5.81E 00 4.26E 00 0.OOE 01 0.OOE 01 AM 241 2.09E 05 2.86E 05 2.90E 06 2.74E 06 1.57E 06 0.OOE 01 0.OOE 01 O.0OE 01*R Values in units of mrem/yr per pCi/mr 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-60 Rev. 25 TABLE 3.3-14 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Goat Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 3.23E 03 3.23E 03 0.OOE-01 3.23E 03 3.23E 03 3.23E 03 3.23E 03 3.23E 03 P32 2.35E 09 1.69E 09 6.11E 10 2.86E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 7.40E 03 3.93E 05 0.00E-01 0.OOE-01 1.12E 03 4.11E 03 7.50E 03 0.00E-01 MN 54 4.07E 05 1.28E 06 0.OOE-01 1.53E 06 4.29E 05 0.O0E-01 0.00E-01 0.00E-01 FE 59 7.52E 05 1.57E 06 9.34E 05 1.51E 06 0.OOE-01 0.00E-01 4.38E 05 0.00E-01 CO 58 2.65E 06 5.05E 06 0.OOE-01 8.65E 05 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 CO 60 9.48E 06 1.78E 07 0.00E-01 3.21E 06 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 ZN 65 5.74E 08 1.62E 08 3.47E 08 9.24E 08 5.82E 08 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 4.04E 08 4.22E 07 0.OOE-01 6.57E 08 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 2.38E 08 3.23E 08 8.34E 09 0.OOE-01 0.O0E-01 0.OOE-01 0.OOE-01 O.0OE-01 SR 90 3.93E 10 2.09E 09 1.55E 11 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 0.OOE-01 Y 91 7.45E 01 3.71 E 05 2.79E 03 0.OOE-01 0.OOE-01 0.O0E-01 0.0OE-01 0.OOE-01 ZR 95 5.36E 01 6.28E 04 2.74E 02 6.02E 01 8.62E 01 0.O0E-01 0.OOE-01 0.OOE-01 NB 95 6.37E 03 1.65E 07 2.29E 04 8.91E 03 8.37E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 1.19E 02 7.98E 03 3.09E 02 0.OOE-01 7.77E 02 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 8.56E 02 1.07E 05 6.86E 03 0.OOE-01 9.27E 03 0.O0E-01 0.OOE-01 O.0OE-01 AG110M 8.63E 06 1.28E 09 1.60E 07 1.08E 07 2.01E 07 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 4.61E 05 1.69E 06 4.22E 05 1.36E 04 9.38E 03 5.59E 03 0.OOE 01 0.OOE 01 TE127M 2.18E 06 1.49E 07 1.84E 07 4.95E 06 5.24E 07 4.40E 06 0.OOE-01 0.00E-01 TE129M 3.28E 06 2.58E 07 2.12E 07 5.91E 06 6.21E 07 6.82E 06 0.OOE-01 0.O0E-01 1131 5.85E 08 9.17E 07 1.02E 09 1.03E 09 1.69E 09 3.41E 11 0.OOE-01 0.OOE-01 1132 4.67E-01 1.19E 00 5.52E-01 1.01E 00 1.55E 00 4.71E 01 0.OOE-01 0.O0E-01 1133 6.58E 06 7.OOE 06 1.41E 07 1.74E 07 2.90E 07 3.23E 09 0.OOE-01 0.OOE-01 1135 4.01E 04 6.47E 04 4.72E 04 8.49E 04 1.30E 05 7.52E 06 0.OOE-01 0.OOE-01 CS 134 1.43E 10 3.67E 08 4.14E 10 6.80E 10 2.11E 10 0.OOE-01 7.56E 09 0.OOE-01 CS 136 3.41E 09 1.85E 08 1.92E 09 5.27E 09 2.81E 09 O.0OE-01 4.19E 08 0.OOE-01 CS 137 8.72E 09 3.70E 08 6.17E 10 5.91E 10 1.93E 10 0.OOE-01 6.93E 09 0.OOE-01 BA 140 5.23E 05 4.54E 05 8.96E 06 7.85E 03 2.56E 03 O.0OE-01 4.68E 03 0.OOE-01 CE 141 1.17E 02 9.81E 05 1.53E 03 7.36E 02 3.45E 02 O.0OE-01 0.OOE- 0.OOE-01 CE 144 6.24E 03 9.55E 06 1.17E 05 3.66E 04 2.03E 04 0.OOE-01 0.OOE-01 O.0OE-01 HF 181 3.04E 02 4.99E 04 3.02E 03 1.17E 01 9.43E 00 9.89E 00 0.OOE 01 0.OOE 01 AM 241 3.06E 05 2.29E 05 4.08E 06 3.50E 06 1.87E 06 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-61 Rev. 25 TABLE 3.3-15 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Goat Milk AGE GROUP = Infant Nuclcide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 4.90E 03 4.90E 03 0.OQE-01 4.90E 03 4.90E 03 4.90E 03 4.90E 03 4.90E 03 P 32 4.88E 09 1.70E 09 1.26E 11 7.40E 09 0.00E-01 0.00E-01 0.00E-01 0.OOE-01 CR 51 1.17E 04 3.42E 05 0.00E-01 0.00E-01 1.67E 03 7.65E 03 1.49E 04 0.OOE-01 MN 54 6.45E 05 1.04E 06 0.O0E-01 2.84E 06 6.30E 05 0.00E-01 0.00E-01 0.00E-01 FE 59 1.20E 06 1.45E 06 1.74E 06 3.04E 06 O.00E-01 0.00E-01 9.00E 05 0.00E-01 CO 58 4.31E 06 4.31E 06 0.00E-01 1.73E 06 0.OOE-01 0.OOE-01 0.O0E-01 0.OOE-01 CO 60 1.55E 07 1.56E 07 0.OOE-01 6.56E 06 0.00E-01 0.00E-01 0.00E-01 0.OOE-01 ZN 65 7.36E 08 1.35E 09 4.66E 08 1.60E 09 7.74E 08 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 8.23E 08 4.26E 07 0.OOE-01 1.67E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 4.55E 08 3.26E 08 1.59E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 4.30E 10 2.11E 09 1.69E 11 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 1.39E 02 3.75E 05 5.23E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 8.41E 01 5.90E 04 4.85E 02 1.19E 02 1.28E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 1.02E 04 1.48E 07 4.27E 04 1.76E 04 1.26E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 2.09E 02 7.60E 03 6.25E 02 0.OOE-01 1.30E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 1.77E 03 1.07E 05 1.41E 04 O.OOE-01 1.67E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 1.43E 07 1.12E 09 2.95E 07 2.16E 07 3.08E 07 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 6.66E 05 1.37E 06 6.46E 05 2.45E 04 1.32E 04 9.34E 03 0.OOE 01 0.OOE 01 TE127M 4.51E 06 1.50E 07 3.72E 07 1.23E 07 9.16E 07 1.08E 07 0.OOE-01 0.OOE-01 TE129M 6.69E 06 2.59E 07 4.34E 07 1.49E 07 1.09E 08 1.67E 07 0.OOE-01 0.OOE-01 1131 1.11E 09 8.99E 07 2.14E 09 2.52E 09 2.94E 09 8.28E 11 0.OOE-01 0.OOE-01 1132 8.28E-01 1.88E 00 1.15E 00 2.33E 00 2.59E 00 1.09E 02 0.OOE-01 0.OOE-01 1133 1.27E 07 7.31E 06 2.97E 07 4.32E 07 5.08E 07 7.86E 09 0.O0E-01 0.OOE-01 1135 7.11E 04 7.06E 04 9.81E 04 1.95E 05 2.17E 05 1.75E 07 0.OOE-01 0.OOE-01 CS 134 1.26E 10 3.38E 08 6.68E 10 1.25E 11 3.21E 10 0.OOE-01 1.31E 10 0.OOE-01 CS 136 4.11E 09 1.67E 08 3.75E 09 1.10E 10 4.39E 09 0.OOE-01 8.98E 08 0.OOE-01 CS 137 8.17E 09 3.61E 08 9.85E 10 1.15E 11 3.10E 10 0.OOE-01 1.25E 10 0.OOE-01 BA 140 9.50E 05 4.53E 06 1.84E 07 1.84E 04 4.38E 03 0.OOE-01 1.13E 04 0.OOE-01 CE 141 2.24E 02 9.85E 05 3.13E 03 1.91E 03 5.88E 02 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 9.39E 03 9.61E 06 1.67E 05 6.86E 04 2.77E 04 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 5.08E 02 4.72E 04 5.74E 03 2.71E 01 1.58E 01 2.30E 01 0.OOE 01 0.OOE 01 AM 241 3.26E 05 2.30E 05 4.38E 06 3.80E 06 1.97E 06 0.OOE 01 0.OOE 01 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-62 Rev. 25 TABLE 3.3-16 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Inhalation AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.26E 03 1.26E 03 0.O0E-01 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 P 32 5.OOE 04 8.63E 04 1.32E 06 7.70E 04 0.00E-01 0.O0E-01 0.00E-01 0.OOE-01 CR 51 9.99E 01 3.32E 03 0.OOE-01 0.O0E-01 2.28E 01 5.94E 01 1.44E 04 0.OOE-01 MN 54 6.29E 03 7.72E 04 0.00E-01 3.95E 04 9.83E 03 0.O0E-01 1.40E 06 0.OOE-01 FE 59 1.05E 04 1.88E 05 1.17E 04 2.77E 04 0.OOE-01 0.OOE-01 1.01E 06 0.00E-01 CO 58 2.07E 03 1.06E 05 0.OOE-01 1.58E 03 0.OOE-01 0.OOE-01 9.27E 05 0.OOE-01 CO 60 1.48E 04 2.84E 05 O.0OE-01 1.15E 04 0.OOE-01 0.O0E-01 5.96E 06 0.OOE-01 ZN 65 4.65E 04 5.34E 04 3.24E 04 1.03E 05 6.89E 04 0.OOE-01 8.63E 05 0.OOE-01 RB 86 5.89E 04 1.66E 04 0.O0E-01 1.35E 05 0.OOE-01 0.O0E-01 0.OOE-01 0.OOE-01 SR 89 8.71E 03 3.49E 05 3.04E 05 0.OOE-01 0.O0E-01 0.OOE-01 1.40E 06 0.OOE-01 SR 90 6.09E 06 7.21E 05 9.91E 07 0.00E-01 0.OOE-01 0.O0E-01 9.59E 06 0.OOE-01 Y 91 1.24E 04 3.84E 05 4.62E 05 0.O0E-01 0.OOE-01 0.OOE-01 1.70E 06 0.OOE-01 ZR 95 2.32E 04 1.50E 05 1.07E 05 3.44E 04 5.41E 04 0.O0E-01 1.77E 06 0.OOE-01 NB 95 4.20E 03 1.04E 05 1.41E 04 7.80E 03 7.72E 03 0.OOE-01 5.04E 05 0.OOE-01 RU 103 6.57E 02 1.10E 05 1.53E 03 0.OOE-01 5.82E 03 0.OOE-01 5.04E 05 0.OOE-01 RU 106 8.71E 03 9.11E 05 6.90E 04 0.OOE-01 1.33E 05 0.OOE-01 9.35E 06 0.OOE-01 AG110M 5.94E 03 3.02E 05 1.08E 04 9.99E 03 1.97E 04 0.OOE-01 4.63E 06 0.OOE-01 SN 113 6.48E 03 2.48E 04 6.87E 03 2.66E 02 1.97E 02 9.33E 01 2.99E 05 0.OOE 01 TE127M 1.57E 03 1.49E 05 1.26E 04 5.76E 03 4.57E 04 3.28E 03 9.59E 05 0.OOE-01 TE129M 1.58E 03 3.83E 05 9.75E 03 4.67E 03 3.65E 04 3.44E 03 1.16E 06 0.OOE-01 1131 2.05E 04 6.27E 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07 0.OOE-01 0.OOE-01 1132 1.16E 03 4.06E 02 1.16E 03 3.25E 03 5.18E 03 1.14E 05 0.OOE-01 0.OOE-01 1133 4.51E 03 8.87E 03 8.63E 03 1.48E 04 2.58E 04 2.15E 06 0.OOE-01 0.OOE-01 1135 2.56E 03 5.24E 03 2.68E 03 6.97E 03 1.11E 04 4.47E 05 0.OOE-01 0.OOE-01 CS 134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 0.OOE-01 9.75E 04 0.OOE-01 CS 136 1.10E 05 1.17E 04 3.90E 04 1.46E 05 8.55E 04 0.OOE-01 1.20E 04 0.OOE-01 CS 137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 0.OOE-01 7.51E 04 0.OOE-01 BA 140 2.56E 03 2.18E 05 3.90E 04 4.90E 01 1.67E 01 0.OOE-01 1.27E 06 0.OOE-01 CE 141 1.53E 03 1.20E 05 1.99E 04 1.35E 04 6.25E 03 0.OOE-01 3.61E 05 0.OOE-01 CE 144 1.84E 05 8.15E 05 3.43E 06 1.43E 06 8.47E 05 0.OOE-01 7.76E 06 O.0OE-01 HF 181 5.16E 03 1.29E 05 4.56E 04 2.57E 02 2.15E 02 1.63E 02 5.99E 05 0.OOE 01 AM 241 5.37E 08 3.68E 05 1.34E 10 9.04E 09 4.03E 09 0.OOE 01 4.85E 08 0.OOE 01*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-63 Rev. 25 TABLE 3.3-17 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Inhalation AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.27E 03 1.27E 03 0.00E-01 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 P 32 7.15E 04 9.27E 04 1.89E 06 1.09E 05 0.OOE-01 0.O0E-01 0.00E-01 0.OOE-01 CR 51 1.35E 02 3.OOE 03 0.OOE-01 0.OOE-01 3.07E 01 7.49E 01 2.09E 04 0.OOE-01 MN 54 8.39E 03 6.67E 04 0.00E-01 5.10E 04 1.27E 04 0.OOE-01 1.98E 06 0.OOE-01 FE 59 1.43E 04 1.78E 05 1.59E 04 3.69E 04 0.OOE-01 0.OOE-01 1.53E 06 0.00E-01 CO 58 2.77E 03 9.51 E 04 0.OOE-01 2.07E 03 0.00E-01 0.OOE-01 1.34E 06 0.OOE-01 CO 60 1.98E 04 2.59E 05 0.00E-01 1.51E 04 0.00E-01 0.OOE-01 8.71E 06 0.OOE-01 ZN 65 6.23E 04 4.66E 04 3.85E 04 1.33E 05 8.63E 04 0.OOE-01 1.24E 06 0.OOE-01 RB 86 8.39E 04 1.77E 04 0.O0E-01 1.90E05 O.OOE-O1 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 1.25E 04 3.71E 05 4.34E 05 0.O0E-01 0.OOE-01 0.OOE-01 2.41E 06 0.OOE-01 SR 90 6.67E 06 7.64E 05 1.08E 08 0.OOE-01 0.OOE-01 0.OOE-01 1.65E 07 0.OOE-01 Y 91 1.77E 04 4.08E 05 6.60E 05 0.O0E-01 0.OOE-01 0.OOE-01 2.93E 06 0.OOE-01 ZR 95 3.15E 04 1.49E 05 1.45E 05 4.58E 04 6.73E 04 0.OOE-01 2.68E 06 O.0OE-01 NB 95 5.66E 03 9.67E 04 1.85E 04 1.03E 04 9.99E 03 0.OOE-01 7.50E 05 O.0OE-01 RU "103 8.95E 02 1.09E 05 2.10E 03 0.OOE-01 7.42E 03 0.OOE-01 7.82E 05 0.OOE-01 RU -106 1.24E 04 9.59E 05 9.83E 04 0.OOE-01 1.90E 05 O.0OE-01 1.61E 07 0.OOE-01 AG110M 7.98E 03 2.72E 05 1.38E 04 1.31E 04 2.50E 04 0.OOE-01 6.74E 06 O0O0E-01 SN 113 8.69E 03 2.03E 04 8.19E 03 3.45E 02 2.46E 02 1.13E 02 4.27E 05 0.OOE 01 TE127M 2.18E 03 1.59E 05 1.80E 04 8.15E 03 6.53E 04 4.38E 03 1.65E 06 0.OOE-01-rE129M 2.24E 03 4.04E 05 1.39E 04 6.57E03 5.18E 04 4.57E 03 1.97E 06 0.OOE-01 1131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 0.OOE-01 O.0OE-01 1132 1.57E 03 1.27E 03 1.59E 03 4.37E 03 6.91E 03 1.51E 05 0.OOE-01 0.OOE-01 133 6.21E 03 1.03E 04 1.21E 04 2.05E 04 3.59E 04 2.92E 06 0.OOE-0 0.EOO-01 1135 3.48E 03 6.94E 03 3.69E 03 9.43E 03 1.49E 04 6.20E 05O.OOF-01 0.OOF-01 CS 134 5.48E 05 9.75E 03 5.02E 05 1.13E 06 3.75E 05 0.OOE-01 1.46E 05 O.0OE-01 CS 136 1.37E 05 1.09E 04 5.14E 04 1.93E 05 1.10E 05 O.0OE-01 1.77E 04 0.OOE-01 CS 137 3.11E 05 8.48E 03 6.69E 05 8.47E 05 3.04E 05 O.0OE-01 1.21E 05 0.OOE-01 BA 140 3.51E 03 2.28E 05 5.46E 04 6.69E 01 2.28E 01 0.OOE-01 2.03E 06 0.OOE-01 CE 141 2.16E 03 1.26E 05 2.84E 04 1.89E 04 8.87E 03 0.OOE-01 6.13E 05 O.0OE-01 CE 144 2.62E 05 8.63E 05 4.88E 06 2.02E 06 1.21E 06 0.OOE-01 1.33E 07 0.OOE-01 HF 181 7.05E 03 1.21E 05 6.32E 04 3.48E 02 2.90E 02 2.12E 02 9.39E 05 0.OOE 01 AM 241 5.68E 08 3.90E 05 1.42E 10 9.60E 09 4.26E 09 0.OOE 01 8.40E 08 0.OOE 01*R Values in units of mrem/yr per pCi/mr 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP)3-64 Rev. 25 TABLE 3.3-18 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Inhalation AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.12E 03 1.12E 03 0.OOE-01 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 P 32 9.86E 04 4.21E 04 2.60E 06 1.14E 05 0.00E-01 0.O0E-01 0.00E-01 0.00E-01 CR 51 1.54E 02 1.08E 03 0.00E-01 0.OOE-01 2.43E 01 8.53E 01 1.70E 04 0.OOE-01 MN 54 9.50E 03 2.29E 04 0.OOE-01 4.29E 04 1.OOE 04 0.OOE-01 1.57E 06 0.OOE-01 FE 59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 0.OOE-01 0.OOE-01 1.27E 06 0.OOE-01 CO 58 3.16E 03 3.43E 04 0.OOE-01 1.77E 03 0.OOE-01 0.OOE-01 1.10E 06 0.OOE-01 CO 60 2.26E 04 9.61E 04 0.OOE-01 1.31E 04 0.O0E-01 0.OOE-01 7.06E 06 0.OOE-01 ZN 65 7.02E 04 1.63E 04 4.25E 04 1.13E 05 7.13E 04 0.OOE-01 9.94E 05 0.O0E-01 RB 86 1.14E 05 7.98E 03 0.OOE-01 1.98E 05 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 1.72E 04 1.67E 05 5.99E 05 0.OOE-01 0.OOE-01 0.OOE-01 2.15E 06 0.00E-01 SR 90 6.43E 06 3.43E 05 1.01E 08 0.O0E-01 0.OOE-01 0.OOE-01 1.47E 07 0.OOE-01 Y 91 2.43E 04 1.84E 05 9.13E 05 0.OOE-01 0.OOE-01 0.OOE-01 2.62E 06 0.OOE-01 ZR 95 3.69E 04 6.1OE 04 1.90E 05 4.17E 04 5.95E 04 0.OOE-01 2.23E 06 0.OOE-01 NB 95 6.54E 03 3.69E 04 2.35E 04 9.16E 03 8.61E 03 0.OOE-01 6.13E 05 0.OOE-01 RU 103 1.07E 03 4.47E 04 2.79E 03 0.OOE-01 7.02E 03 0.OOE-01 6.61E 05 0.OOE-01 RU 106 1.69E 04 4.29E 05 1.36E 05 0.OOE-01 1.84E 05 0.OOE-01 1.43E 07 0.OOE-01 AG110M 9.13E 03 1.OOE 05 1.68E 04 1.14E 04 2.12E 04 0.OOE-01 5.47E 06 0.OOE-01 SN 113 9.84E 03 7.45E 03 9.01E 03 2.91E 02 2.03E 02 1.19E 02 3.40E 05 O.OOE 01 TE127M 3.01E 03 7.13E 04 2.48E 04 8.53E 03 6.35E 04 6.06E 03 1.48E 06 0.OOE-01 TE129M 3.04E 03 1.81E 05 1.92E 04 6.84E 03 5.02E 04 6.32E 03 1.76E 06 O.0OE-01 1131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 0.OOE-01 0.OOE-01 1132 1.87E 03 3.20E 03 2.11E 03 4.06E 03 6.24E 03 1.93E 05 0.OOE-01 0.OOE-01 1133 7.68E 03 5.47E 03 1.66E 04 2.03E 04 3.37E 04 3.84E 06 0.OOE-01 0.O0E-01 1135 4.14E 03 4.43E 03 4.91E 03 8.72E 03 1.34E 04 7.91E 05 0.OOE-01 0.OOE-01 CS 134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.30E 05 0.OOE-01 1.21E 05 0.O0E-01 CS 136 1.16E 05 4.17E 03 6.50E 04 1.71E 05 9.53E 04 0.OOE-01 1.45E 04 0.OOE-01 CS 137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 0.00E-01 1.04E 05 0.OOE-01 BA 140 4.32E 03 1.02E 05 7.39E 04 6.47E 01 2.11E 01 0.OOE-01 1.74E 06 0.OOE-01 CE 141 2.89E 03 5.65E 04 3.92E 04 1.95E 04 8.53E 03 0.OOE-01 5.43E 05 0.OOE-01 CE 144 3.61E 05 3.88E 05 6.76E 06 2.11E 06 1.17E 06 0.O0E-01 1.19E 07 O.0OE-01 HF 181 8.50E 03 5.31E 04 8.44E 04 3.28E 02 2.64E 02 2.76E 02 7.9SF 05 0.OOE 01 AM 241 4.59E 08 1.75E 05 1.10E 10 6.81E 09 2.82E 09 0.OOE 01 7.47E 08 0.OOE 01*R Values in units of mrem/yr per pCi/rn 3 for inhalation and tritium, and in units of m 2-mrem/yr per pCi/sec for all others.ODCM (BSEP) 3-65 Rev. 25 TABLE 3.3-19 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*PATHWAY = Inhalation AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 6.46E 02 6.46E 02 0.OOE-01 6.46E 02 6.46E 02 6.46E 02 6.46E 02 6.46E 02 P 32 7.73E 04 1.61E 04 2.03E 06 1.12E 05 0.OOE-01 0.O0E-01 0.00E-01 0.OOE-01 CR 51 8.93E 01 3.56E 02 0.00E-01 0.OOE-01 1.32E 01 5.75E 01 1.28E 04 0.OOE-01 MN 54 4.98E 03 7.05E 03 0.OOE-01 2.53E 04 4.98E 03 0.O0E-01 9.98E 05 0.OOE-01 FE 59 9.46E 03 2.47E 04 1.35E 04 2.35E 04 0.00E-01 0.00E-01 1.01E 06 0.00E-01 CO 58 1.82E 03 1.11E 04 0.00E-01 1.22E 03 0.00E-01 0.OOE-01 7.76E 05 0.OOE-01 CO 60 1.18E 04 3.19E 04 0.OOE-01 8.01E 03 0.OOE-01 0.OOE-01 4.50E 06 0.OOE-01 ZN 65 3.1OE 04 5.13E 04 1.93E 04 6.25E 04 3.24E 04 0.OOE-01 6.46E 05 0.OOE-01 RB 86 8.81E 04 3.03E 03 0.OOE-01 1.90E 05 O.0OE-01 0.OOE- 0.OOE-01 0.OOE-01 SR 89 1.14E 04 6.39E 04 3.97E 05 0.OOE-01 0.OOE-01 0.OOE-01 2.03E 06 0.OOE-01 SR 90 2.59E 06 1.31E 05 4.08E 07 0.O0E-01 0.OOE-01 0.OOE-01 1.12E 07 0.OOE-01 Y 91 1.57E 04 7.02E 04 5.87E 05 0.OOE-01 0.OOE-01 0.OOE-01 2.45E 06 0.OOE-01 ZR 95 2.03E 04 2.17E 04 1.15E 05 2.78E 04 3.10E 04 0.OOE-01 1.75E 06 0.00E-01 NB 95 3.77E 03 1.27E 04 1.57E 04 6.42E 03 4.71E 03 0.OOE-01 4.78E 05 0.OOE-01 RU 103 6.78E 02 1.61E 04 2.01E 03 0.OOE-01 4.24E 03 0.OOE-01 5.51E 05 0.OOE-01 RU 106 1.09E 04 1.64E 05 8.67E 04 0.OOE-01 1.06E 05 0.OOE-01 1.15E 07 0.OOE-01 AG110M 4.99E 03 3.30E 04 9.97E 03 7.21E 03 1.09E 04 0.OOE-01 3.66E 06 0.OOE-01 SN 113 4.89E 03 2.29E 03 4.68E 03 1.74E 02 9.94E 01 6.73E 01 2.30E 05 0.OOE 01 TE127M 2.07E 03 2.73E 04 1.66E 04 6.89E 03 3.75E 04 4.86E 03 1.31E 06 0.OOE-01 TE129M 2.22E 03 6.89E 04 1.41E 04 6.08E 03 3.17E 04 5.47E 03 1.68E 06 0.OOE-01 1131 1.96E 04 1.06E 03 3.79E 04 4.43E 04 5.17E 04 1.48E 07 0.OOE-01 0.OOE-01 1132 1.26E 03 1.90E 03 1.69E 03 3.54E 03 3.94E 03 1.69E 05 0.OOE-01 0.OOE-01 1133 5.59E 03 2.15E 03 1.32E 04 1.92E 04 2.24E 04 3.55E 06 0.OOE-01 0.OOE-01 1135 2.77E 03 1.83E 03 3.86E 03 7.59E 03 8.46E 03 6.95E 05 0.OOE-01 0.OOE-01 CS 134 7.44E 04 1.33E 03 3.96E 05 7.02E 05 1.90E 05 0.OOE-01 7.95E 04 0.OOE-01 CS 136 5.28E 04 1.43E 03 4.82E 04 1.34E 05 5.63E 04 0.OOE-01 1.17E 04 0.O0E-01 CS 137 4.54E 04 1.33E 03 5.48E 05 6.11E 05 1.72E 05 0.OOE-01 7.12E 04 0.OOE-01 BA 140 2.89E 03 3.83E 04 5.59E 04 5.59E 01 1.34E 01 0.OOE-01 1.59E 06 0.OOE-01 CE 141 1.99E 03 2.15E 04 2.77E 04 1.66E 04 5.24E 03 0.OOE-01 5.16E 05 0.OOE-01 CE 144 1.76E 05 1.48E 05 3.19E 06 1.21E 06 5.37E 05 0.OOE-01 9.83E 06 0.OOE-01 HF 181 5.05E 03 1.90E 04 5.65E 04 2.66E 02 1.59E 02 2.26E 02 6.73E 05 0.OOE 01 AM 241 1.83E 08 6.69E 04 4.41E 09 2.73E 09 1.11E 09 0.OOE 01 5.68E 08 0.OOE 01*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium, and pCi/sec for all others.in units of m2-mrem/yr per ODCM (BSEP)3-66 Rev. 25 3.3.3 Carbon-14 Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere.
The concentration of C-14 in the atmosphere was increased significantly in the 1950s and 1960s due to nuclear weapons testing. Commercial nuclear reactors also produce C-14, but in amounts much less than those produced naturally or as a result of weapons testing. Regulatory Guide 1.21 Revision 1 (1974), to which the Brunswick Steam Electric Plant (BSEP) is committed, did not address C-14. However, since that time analytical methods for determining C-14 have improved and Revision 2 (2009) states that Licensees should evaluate whether C-14 is a principal radionuclide for gaseous effluents.
Improvements in fuel performance have resulted in a decrease in radioactive effluents from BSEP to the point that C-14 is now considered a principal radionuclide.
In Boiling Water Reactors (BWRs), such as BSEP, the gaseous C-14 releases are primarily in the form of carbon dioxide. The dose contribution of C-14 in liquid radioactive waste is minimal, therefore, evaluation of C-14 in liquid discharges is not required.The C-14 curies released may be determined by any of the following methodologies:
: a. Use BSEP's Updated Final Safety Analysis Report (UFSAR) C-14 release rate of 9.5 Ci/yr per unit assuming 80% plant capacity factor (292 Effective Full Power Days (EFPD)) and scale it using actual EFPD for each unit. The curies per year will be allotted based on ODCM allocation fractions of 0.40 for the Stack, 0.20 for each Reactor Building, and 0.10 for each Turbine Building and attributed to each quarter for reporting in the Annual Radioactive Effluent Release Report.b. Use of historical values (with power up-rate adjustment) as indicated in NUREG/CR-4245 (1985).c. Use of actual sample data obtained during the reporting period.d. Use of Electric Power Research Institute's, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" methodology.
The Annual Land Use Census will be used to determine the critical receptor.
Typically, there are no meat or milk pathways within 5 miles of BSEP, therefore, unless other pathways are identified, the reported dose to the individual will be determined from inhalation and vegetable consumption.
Regulatory Guide 1.109 Revision 1 methodology will be used to determine the dose. The dose rate and subsequent dose to an individual from C-14 intake depends on the specific activity of the food from each source and the amount of the ingested C-14 which is retained over the period under consideration.
Atmospheric Carbon Dioxide (C02) is incorporated in cellular material by the photosynthetic action of plants. Plants and grasses equilibrate with the C-14 C02 of the air. The portion of the curies released that is determined to be carbon dioxide is 90%. This value is based on conservative historical values from NUREG/CR-4245 (1985). The growing season may be utilized and can be derived from the North Carolina Cooperative Extension Service, current data available indicates that average growing season is 238 days. BSEP gaseous releases are continuous and no credit is taken for releases in non-daylight hours where photosynthetic action of plants is minimal or non-existent.Carbon-14 releases are typically tabulated at the end of the yearly reporting period and included in the Annual Radioactive Effluent Release Report, however, special circumstances as determined by E&C Management may require that C-14 releases be assessed on a more frequent basis. Once the C-14 dose is determined it is included in the Annual Radioactive Effluent Release Report.ODCM (BSEP)3-67 Rev. 36 1
: 1. Annual Dose from Inhalation of Carbon-14 in Air a. The annual average airborne concentration of C-14 may be determined as follows: Xc = (3.17 x 10') (Q ) -Y (3.3-21)Where: X, is the annual average concentration of C-14 in air, pCi/mi 3;3.17 x 104 is the number of pCi/Ci divided by the number of sec/year;Qc is the release rate of C-14 to the atmosphere, in Ci/yr; and For Reactor and Turbine Buildings using methodology
: a. listed under Section 3.3.3 to determine the C-14 curies released: QC =
release point FFPD for applicable Unit fr 292 days For Stack using methodology
: a. listed under Section 3.3.3 to determine the C-14 curies released: Qc = ( Ci~ ) EFPD of Unit Iland Unit 2 y yrr(, 292 da, s + 292 days is the annual average atmosphere dispersion factor, in sec/i 3.b. The annual dose associated with inhalation of C-14 may be determined as follows: D = [(BR)a ] (X:) (DFAcja) (3.3-22)Where: Dc' is the C-14 annual dose to organ j of an individual in age group a, in mrem/yr;(BR), is the breathing rate of the receptor of age group a, in m 3/yr, reference ODCM Section C.2.1 for these values;X, is the annual average concentration of C-14 in air, in pCi/m 3.DFAcja is the C-14 inhalation dose factor for organ j, and age group a, in mrem/pCi, reference Table 3.3-20 for values.ODCM (BSEP)3-68 Rev. 36 1 Table 3.3-20 Inhalation Dose Factors for Carbon-14 (DFA)(mrem/pCi)
Age G(oup Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Teenager 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Child 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 SInfaEnt I 1.89E-05 I_3.79E-06 Ij3.79E-06 3.79E-06 I 3.79E-06 I 3.79E-06 3.79E-06 Note: These values are from Regulatory Guide 1.109 Revision 1 Tables E-7 through E-10.2. Concentration of Airborne Carbon-14 in Vegetation
: a. The annual concentration of Carbon-14 in vegetation may be determined as follows: C,= (3.17 x 107) (p)(Oc) LQj)(,- (3.3-23)WIVhere: C 4 is the concentration of Carbon-14 in vegetation in pCi/kg;Q, is the annual release rate of Carbon-14, in Ci/yr;p is the fractional equilibrium ratio, dimensionless (0.9 based off conservative historical values from NUREG/CR-4245 (1985));is the annual average atmosphere dispersion factor, in sec/i 3;0.11 is the fraction of total plant mass that is natural carbon, dimensionless, from RG 1.109 Revision 1 Appendix C;0.16 is equal to the concentration of natural carbon in the atmosphere in g/m 3 from RG 1.109 Revision 1 Appendix C; and 3.17 x 10 7  is equal to (1.0 x 1012 pCilCi)(1.0 x 103 g/kg) 315 x 0 SeCyr 3. Concentration of Airborne Carbon-14 in Milk a. The concentration of Carbon-14 in milk is dependent on the amount and contamination level of the feed consumed by the animal. The C-14 concentration in milk may be determined as follows: C 14= (F.)(CI4')(QF)
(3.3-24)Where:-M (BSEP) 3-69 Rev. 36 OD(
is the C-14 concentration in milk, in pCi/liter; F, is the average fraction of the animal's daily intake of C-14, which appears in each liter of milk, in days/liter.
Cow = 0.012 days/liter from Table E-1 of RG 1.109 Revision 1 and Goat = 0.10 days/liter from Table E-2 of RG 1.109 Revision 1;C 4 is the concentration of C-14 in the animal's feed, in pCi/kg;QF is the amount of feed consumed by the animal per day, in kg/day, see ODCM Table C-1.4. Concentration of Airborne Carbon-14 in Meat a. The concentration of Carbon-14 in meat is dependent on the amount and contamination level of the feed consumed by the animal. The C-14 concentration in meat may be determined as follows: F Where: S14is the concentration of C-14 in animal flesh, in pCi/kg;Ff is the fraction of the animal's daily intake of C-14, which appears in each kilogram of flesh, in days/kg. Value for C-14 is 0.031 days/kg from Table E-1 in RG 1.109 Revision 1;C 1 4 is the concentration of C-14 in the animal's feed, in pCi/kg;QF is the amount of feed consumed by the animal per day, in kg/day, see ODCM Table C-1.5. Annual Dose from Atmospherically Released Carbon-14 in Foods a. The annual dose associated with the ingestion of Carbon-14 in food may be determined as follows:=DFIcja [U. &#xfd; C 1 4 + U C 4 -+ U II +U f CL f (3.3-26)Where: D D is the annual dose to organ j of an individual in age group a from Ja dietary intake of atmospherically released C-14, in mrem/yr;DFlcja is the dose conversion factor for the ingestion of C-14 for organ j, and age group a, in mrem/pCi, reference Table 3.3-21;ODCM (BSEP)3-70 Rev. 36 1 U' the ingestion rate of produce (non-leafy vegetables, fruit, and grains) for individuals in age group a, in kg/yr, see ODCM Table C-3;U ' the ingestion rate of milk for individuals in age group a, in liters/year, see ODCM Table C-1 (Uap);U a the ingestion rate of meat for individuals in age group a, in kg/yr, see ODCM Table C-2 (Uap);U '_ the ingestion rate of leafy vegetables for individuals in age group a, in kg/yr, see ODCM Table C-3;f 9  is the fraction of produce ingested grown in garden of interest, 0.76 from Table E-15 of RG 1.109;is the fraction of leafy vegetables grown in the garden of interest, 1.0 from Table E-15 of RG 1.109;C,4 is the concentration of C-14 in vegetation, in pCi/kg;14" is the concentration of C-14 in milk, in pCi/liter; C I' 4 is the concentration of C-14 in animal flesh, in pCi/kg.Table 3.3-21 Ingestion Dose Factors for Carbon-14 (DFI)(mrem/pCi)
Age Group Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Teenager 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Child 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Infant 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Note: These values are from Regulatory Guide 1.109 Revision 1 Tables E-1 1 through E-1 4.ODCM (BSEP)3-71 Rev. 36 1 INDEX 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...............................
4-3 ODCM (BSEP)4-1 Rev. 25 LIST OF TABLES Table No. Title Paqe SECTION 4 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..............
4-4 ODCM (BSEP)4-2 Rev. 25
 
===4.0 RADIOLOGICAL===
 
ENVIRONMENTAL MONITORING PROGRAM Table 4.0-1 contains the sample point description, sampling and collection frequency analysis, and analysis frequency for various exposure pathways in the vicinity of the BSEP for the radiological monitoring program. Figure 4.0-1 shows the location of various sample points. Figure F-2, Gaseous Radwaste Effluent System, denotes the various release pathways.ODCM (BSEP)4-3 Rev. 26 1 TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency_Frequency
: 1. DIRECT 1 1.1 miles E Q Q Gamma Dose RADIATION 2 0.9 miles ESE Q Q Gamma Dose 3 0.9 miles SE Q Q Gamma Dose 4 1.1 miles SSE Q Q Gamma Dose 5 1.6 milesS Q Q Gamma Dose 6 1.6 miles SSW Q Q Gamma Dose 7 1.1 miles SW Q Q Gamma Dose 8 1.2 miles W Q Q Gamma Dose 9 1.0 miles WNW Q Q Gamma Dose 10 0.8 miles NW Q Q Gamma Dose 11 0.9 miles NNW 0 0 Gamma Dose 12 1.1 miles N Q Q Gamma Dose 13 1.2 miles NNE Q Q Gamma Dose 14 0.5 miles NE Q Q Gamma Dose 15 0.9 miles ENE Q Q Gamma Dose 16 1.0 miles WSW Q Q Gamma Dose 17 1.4 miles ESE Q Q Gamma Dose*Refer to Figure 4.0-1 and Figure F-2.ODCM (BSEP)4-4 Rev. 32 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency 1. DIRECT RADIATION (Cont'd)18 1.7 miles Q Q Gamma Dose 77 5.4 miles S Q Q Gamma Dose 75 4.7 miles S Q Q Gamma Dose 76 4.8 miles SSW Q Q Gamma Dose 22 5.3 miles SW Q Q Gamma Dose 23 4.6 miles WSW Q Q Gamma Dose 24 3.0 miles W Q Q Gamma Dose 25 8.6 miles WNW Q Q Gamma Dose 26 5.9 miles NW Q Q Gamma Dose 27 5.1 miles NNW Q Q Gamma Dose 79 9.5 miles N Q Q Gamma Dose 78 9.9 miles NNE Q Q Gamma Dose 30 2.0 miles NE Q Q Gamma Dose 31 2.5 miles ENE Q Q Gamma Dose 32 5.8 miles ENE Q Q Gamma Dose 33 4.1 miles E Q Q Gamma Dose 34 5.4 miles E Q Q Gamma Dose 81 9.9 miles WNW (c)Q Q Gamma Dose____________________
.1. _______ _____________________________________________
a ODCM (BSEP)4-5 Rev. 30 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency 1. DIRECT 36 8.9 miles NE Q Q Gamma Dose RADIATION (Cont'd) 37 5.5 miles NW Q Q Gamma Dose 38 11.0 miles W Q Q Gamma Dose 39 5.3 miles SW Q Q Gamma Dose 40 6.9 miles WSW Q Q Gamma Dose 20 2.1 miles S Q Q Gamma Dose 21 2.9 miles SSW Q Q Gamma Dose 28 4.2 miles NW Q Q Gamma Dose 29 2.6 miles SSW Q Q Gamma Dose 35 7.3 miles SSE Q Q Gamma Dose 82 0.17 miles NNE Q Q Gamma Dose 83 0.27 miles NE Q Q Gamma Dose 84 0.27 miles NE Q Q Gamma Dose 85 0.09 miles ENE Q Q Gamma Dose ODCM (BSEP)4-6 Rev. 34 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency 2. AIRBORNE Radioiodine and Particulate 200 1.0 miles WSW -Visitors Center C S.ontinuous sampler peration with ample collected ieekly or as equired by dust)ading, whichever 5 more frequent 201 0.5 miles NE -Bio. Lab Road -Projected Maximum Annual Concentration (PMAC)202 1.0 miles S -Substation, Construction Rd.203 2.0 miles SSW -Southport Substation 204 22.4 miles NNE -Sutton Plant -(Historical Control)205 0.6 miles SSE -Spoil Pond W W Q Radioiodine ,anister 1-131 analysis Particulate sampler Gross beta ,adioactivity analysis following filter:hange (b)3amma sotopic analysis of ,omposite by ocation 206 11.3 miles NW -Brunswick County Complex -Control(c)
ODCM (BSEP)4-7 Rev. 35 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis Analysis (a)and/or Sample ID No. Distance, and Direction Collection Frequency Frequency 3. WATERBORNE 400 0.6 miles NE -Intake Canal -Control (c) Composite sample Monthly Gamma (d) Collection-M Isotopic a. Surface 401 4.9 miles SSW -Discharge Canal at OD Q Tritium Pumps 495 Nancy's Creek -WP-52 Grab Sample, Weekly Tritium 496 Nancy's Creek -WP-53 eekly,Monthly Gamma 497 Nancy's Creek -WP-55 Isotopic "g 498 Nancy's Creek -WP-57 499 Cape Fear River (c)-WP-61 Grab Sample, Weekly Tritium 494 Nancy's Creek Marsh Area -WP-106 Weekly Gamma Isotopic from composite 604 Nancy's Creek Marsh Area -WP-92 of WP-106 and IP-92 ODCM (BSEP)4-8 Rev. 35 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis Analysis (a)and/or Sample ID No. Distance, and Direction Collection Frequency Frequency 3. WATERBORNE 605 Nancy's Creek Marsh Area -WP-72 Grab Sample, Weekly Tritium a. Surface Gamma Isotopic (Continued) from composite 606 Nancy's Creek Marsh Area -WP-74 of WP-72, WP-74, and WP-76 607 Nancy's Creek Marsh Area -WP-76 608 Nancy's Creek Marsh Area -WP-82 Grab Sample, Weekly Tritium Weekly Gamma Isotopic from composite 609 Nancy's Creek Marsh Area -oWP-84 f WP-82, WP-84, and WP-88 610 Nancy's Creek Marsh Area -WP-88 ODCM (BSEP)4-9 Rev. 35 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency b. Sediment 500 5.0 miles SSW -Discharge
-Beach near OD Semiannual Semiannual Gamma Pumps Isotopic 501 Nancy's Creek, Adjacent to WP-55, Near Storm Annual Annual Gamma Drain Stabilization Pond Isotopic h c. Groundwater 404 Monitoring Well ESS-IB, 0.16 miles SW Grab Sample, Q Tritium Quarterly, 407 Monitoring Well ESS-13B, 0.06 miles ENE Semiannual Semiannual Gamma 409 Monitoring Well ESS-17A, 0.65 miles NE Isotopic'410 Monitoring Well ESS-17B, 0.65 miles NE 418 Monitoring Well ESS-21B, Near Storm Drain Stabilization Pond Monitoring Well ESS-24A, Near Storm Drain 423 Stabilization Pond Monitoring Well ESS-24B, Near Storm Drain 424 Stabilization Pond Monitoring Well ESS-25B, Near Storm Drain 426 Stabilization Pond Monitoring Well ESS-27A, Near Storm Drain 429 Stabilization Pond 612 Monitoring Well ESS MWPA-1 18B, Near Intake Canal and Plant Stack ODCM (BSEP)4-10 Rev. 35 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency 4. INGESTION 600 To be identified as available With animals on Semi- Gamma a. Milk pasture -monthly isotopic and semi-monthly 1-131 601 At other times -analyses monthly (animals on pasture)602 Monthly Gamma isotopic and 603 1-131 analysis (other times)b. Fish and 700-702 5.5 mile SSW -Atlantic Ocean (e) at Discharge When in Season -Semiannual Gamma Invertebrates (shrimp) Semiannual isotopic on edible portions 703-705 Not Specified
-Atlantic Ocean (c)(e)706-708 Nancy's Creek (e) Annual Annual Gamma isotopic on edible portions ODCM (BSEP)4-11 Rev. 35 1 TABLE 4.0-1 (Cont'd)Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a)and/or Sample ID No. and Direction Collection Frequency Frequency c. Broadleaf Vegetation 800 0.7 miles NE -Intake Canal When available
-Monthly Gamma Monthly Isotopic 801 0.8 miles SW- Discharge Canal Monthly 1-131 802 10.1 miles -Control -Location not Specified (c)803 0.6 miles SSE -Spoil Pond 804 0.7 miles S -Leonard Street plant exit adjacent to RR tracks (a) The LLD for each analysis is specified in Table 7.3.15-3, with the exception of the Nancy's Creek Marsh Area principal gamma isotopic and 1-131. The LLD for the Nancy's Creek Marsh Area gamma isotopic is 5 x 10-7 pCi/ml for Principal Gamma Emitters and 1 x 10-6 pCi/ml for 1-131.(b) Particulate samples will be analyzed for gross beta radiation 24 hours or more following filter change. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic shall be performed on the individual samples.(c) Control Station -These stations are presumed to be outside the influence of plant effluents.(d) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 6 hours.(e) A sample of one free swimmer, one bottom feeder, and one shellfish (shrimp) will be collected if available.
A control sample of each species collected will be obtained if available.(f) Gamma isotopic scan means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.(g) The weekly samples are to be composited for monthly gamma isotopic analyses.
If plant activity is detected, Sr-89, 90 and Fe-55 analysis are to be performed.(h) If plant activity is detected, Sr-89, 90 and Fe-55 analysis are to be performed and frequency will be increased to Semi-Annual.
ODCM (BSEP) 4-12 Rev. 35 FIGURE 4.0-1 Pintelevel PCrliaCampbell
'*I*~ 14 Fisher 133 0sno "s, I Long Behac i Access R d iach --- erort FisherOf-26 S mit " -Isan7 27-"- wla Pdl Caelin Long ~~~~BeachYe",TLNI Boiling ViaeOf Beiac 87 133 21 C/F/ Pln 13r 31he ODCM (BSEP)4-13 Rev. 35 1 INDEX 5.0 INTERLABORATO RY CO M PARISO N STUDIES ........................................................
5-2 5.1 O BJECTIVE ...........................................................................................................
5-2 5.2 PRO G RAM ............................................................................................................
5-2 5.2.1 Environm ental Sam ple Analyses Com parison Program ..............................
5-2 5.2.2 Effluent Release Analyses Program ...........................................................
5-2 5.2.3 Abnorm al Results .......................................................................................
5-2 ODCM (BSEP)5-1 Rev. 25
 
===5.0 INTERLABORATORY===
 
COMPARISON STUDIES 5.1 OBJECTIVE The objective of this program is to evaluate the total laboratory analysis process by comparing results with results obtained by a separate laboratory or laboratories for an equivalent sample.5.2 PROGRAM 5.2.1 Environmental Sample Analyses Comparison Program Environmental samples from the BSEP environs will be analyzed by the Harris Energy & Environmental Center or by a qualified contracting laboratory.
These laboratories will participate at least annually in a interlaboratory comparison study.The results of the laboratories' performances in the study will be provided to BSEP E&RC and will be included in the Annual Radiological Environmental Operating Report. The results will be provided to the NRC upon request.5.2.2 Effluent Release Analyses Program BSEP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases.
The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or equivalent study. The results of these studies will be provided to the NRC upon request.5.2.3 Abnormal Results Progress Energy laboratory or vendor laboratory results shall be compared to the criteria established in the NRC Inspection Manual (Procedure 84750)for Radioactive Waste Treatment, Effluent, and Environmental Monitoring.
The referenced criteria is as follows: a. Divide each standard result by its associated uncertainty to obtain resolution (the uncertainty is defined as the relative standard deviation, or sigma, of the standard result as calculated from counting statistics).
ODCM (BSEP)5-2 Rev. 30 1
: b. Divide each laboratory result by the corresponding standard result to obtain the ratio (laboratory result/standard).
: c. The laboratory measurement is in agreement if the value of the ratio falls within the limits shown below for the corresponding resolution:
Resolution Ratio< 4 0.4-2.5 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51 -200 0.80-1.25> 200 0.85- 1.18 If the Progress Energy laboratory or vendor laboratory results lie outside the ratio criteria, an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors.Complete documentation of the evaluation will be available to BSEP and will be provided to the NRC upon request.ODCM (BSEP)5-3 Rev. 35 INDEX 6.0 TOTAL DO SE (40CFR190 CO NFORMANCE)
.............................................................
6-2 6.1 INTRO DUCTIO N ....................................................................................................
6-2 6.1 G ENERAL ..............................................................................................................
6-2 6.3 CALCULATIO NS O F TOTAL BO DY DOSE ............................................................
6-3 6.3.1 Direct Radiation
...........................................................................................
6-3 6.3.2 Inhalation Dose ...........................................................................................
6-3 6.3.3 Ingestion Pathway .......................................................................................
6-3 6.3.4 Other Uranium Fuel Cycle Sources .............................................................
6-3 6.4 THYRO ID DO SE ....................................................................................................
6-4 ODCM (BSEP)6-1 Rev. 25
 
===6.0 TOTAL===
DOSE (40CFR190 CONFORMANCE)
 
==6.1 INTRODUCTION==
 
Compliance with 40CFR190 as prescribed by ODCM Specification 7.3.14 is to be demonstrated only when one or more of ODCM Specifications 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a, 7.3.9.b is exceeded by a factor of 2. Once this occurs, the Company has 30 days to submit this report.6.2 GENERAL To perform the calculations to evaluate conformance with 40CFR190, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates of dose to a MEMBER OF THE PUBLIC (i.e., calculations for compliance with 10CR50, Appendix I). To accomplish this, the following calculational rules are used: 6.2.1 Doses to a MEMBER OF THE PUBLIC via the liquid release pathway are considered to be <1 mrem/yr. (Ref: NUREG 0543).6.2.2 Doses to a MEMBER OF THE PUBLIC due to a milk pathway will be evaluated only as can be shown to exist. Otherwise, doses via this pathway will be estimated as <1 mrem/yr.6.2.3 Environmental sampling data which demonstrates that no pathway exists may be used to delete a pathway to man from a calculation.
6.2.4 To sum numbers represented as "less than" (<), use the value of the largest number in the group.(i.e., <5 + <1 + <1 + <3 = 5)6.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector.6.2.6 The calculational locations for a MEMBER OF THE PUBLIC will only be at residences or places of employment.
NOTE: Additional assumptions may be used to provide situation-specific parameters, provided they are documented along with their concomitant bases.ODCM (BSEP)6-2 Rev. 25
 
===6.3 CALCULATIONS===
 
OF TOTAL BODY DOSE Estimates will be made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist at a location are considered.
 
====6.3.1 Direct====
Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be determined by: 1. Determining the direct radiation dose at the plant boundary in each sector, D,, 0.2. Extrapolating that dose to the calculational location as follows: D,, = D,,0 (1.49 E + 6)DL, (X2, 0)DL,0 = dose at calculational location in sector 0 1.49E + 6 = square of mean distance to the site boundary (1220 m).XL, 0= distance to calculational locations in sector 0 in meters.6.3.2 Inhalation Dose The inhalation dose will be determined at the calculational locations for each age class at risk according to the methods outlined in Section 3.3 of this manual.6.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as <1 mrem/yr.6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as <1 mrem/yr.ODCM (BSEP)6-3 Rev. 25
 
===6.4 THYROID===
DOSE The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if existing).
The calculational methods will be those identified in Section 3.3 of this manual.6.4.1 Dose projections can incorporate planned plant operations such as power reduction or outages for the projected period.ODCM (BSEP)6-4 Rev. 25 SECTION 7.0 RADIOACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 Brunswick Units 1 and 2 7-0 Rev. 25 INDEX 7.1.0 USE AND APPLICATION
......................................................................................
7.1.1-1 7 .1 .1 D e fin itio n s ............................................................................................
7 .1 .1-1 7.1.2 Logical Connectors
...............................................................................
7.1.2-1 7.1.3 Completion Times ................................................................................
7.1.3-1 7 .1 .4 F re q u e n c y ........................
I ...................................................................
7 .1 .4 -1 7 .2 .0 N o t u s e d ................................................................................................................
7 .2 ,0 -1 7.3 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS
 
====7.3.0 Offsite====
Dose Calculation Manual Specification (ODCMS) Applicability.
7.3.0-1 7.3.0 Test Requirement (TR) Applicability
...................................................
7.3.0-3 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation
........................
7.3.1-1 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation
...................
7.3.2-1 7.3.3 Concentration-Liquid Effluents
.........................................................
7.3.3-1 7.3.4 Dose- Liquid Effluents
.......................................................................
7.3.4-1 7.3.5 Liquid Radwaste Treatment System ...................................................
7.3.5-1 7.3.6 Liquid Holdup Tanks .............................................................................
7.3.6-1 7.3.7 Dose Rate--Gaseous Effluents
............................................................
7.3.7-1 7.3.8 Dose- Noble Gases ............................................................................
7.3.8-1 7.3.9 Dose- l-131, 1-133, Tritium, and Radionuclides in Particulate Form .... 7.3.9-1 7.3.10 Gaseous Radwaste Treatment System ..............................................
7.3.10-1 7.3.11 Ventilation Exhaust Treatment System ...............................................
7.3.11-1 7.3.12 Explosive Gas Mixture ........................................................................
7.3.12-1 7.3.13 Drywell Venting or Purging .................................................................
7.3.13-1 7.3.14 Total Dose (40 CFR Part 190) ............................................................
7.3.14-1 7.3.15 Radiological Environmental Monitoring Program ................................
7.3.15-1 7.3.16 Land Use Census ...............................................................................
7.3.16-1 7.3.17 Interlaboratory Comparison Program .................................................
7.3.17-1 7.4.0 REPORTING REQUIREMENTS
..........................................................................
7.4.0-1 7.4.1 Annual Radiological Environmental Operating Report ..........................
7.4.0-1 7.4.2 Radioactive Effluent Release Report ..................................................
7.4.0-1 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ..........
7.5.0-1 BASES B 7.3.0 Offsite Dose Calculation Manual Specification (ODCMS)A p p lic a b ility .......................................................................................
B 7 .3 .0 -1 (continued)
Brunswick Units 1 and 2 7-i Rev. 25 INDEX (continued)
B 7.3.0 Test Requirement (TR) Applicability
..................................................
B 7.3.0-6 B 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation
.....................
B 7.3.1-1 B 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation
................
B 7.3.2-1 B 7.3.3 Concentration-Liquid Effluents
........................................................
B 7.3.3-1 B 7.3.4 Dose--Liquid Effluents
......................................................................
B 7.3.4-1 B 7.3.5 Liquid Radwaste Treatment System ..................................................
B 7.3.5-1 B 7.3.6 Liquid Holdup Tanks ..........................................................................
B 7.3.6-1 B 7.3.7 Dose Rate- Gaseous Effluents
.........................................................
B 7.3.7-1 B 7.3.8 Dose Rate- Noble Gases .................................................................
B 7.3.8-1 B 7.3.9 Dose- l-131, 1-133, Tritium, and Radionuclides in Particulate F o rm ..................................................................................................
B 7 .3 .9 -1 B 7.3.10 Gaseous Radwaste Treatment System ...........................................
B 7.3.10-1 B 7.3.11 Ventilation Exhaust Treatment System ............................................
B 7.3.11-1 B 7.3.12 Explosive Gas Mixture .....................................................................
B 7.3.12-1 B 7.3.13 Drywell Venting or Purging ..............................................................
B 7.3.13-1 B 7.3.14 Total Dose (40 CFR Part 190) .........................................................
B 7.3.14-1 B 7.3.15 Radiological Environmental Monitoring Program .............................
B 7.3.15-1 B 7.3.16 Land Use Census ............................................................................
B 7.3.16-1 B 7.3.17 Interlaboratory Comparison Program ..............................................
B 7.3.17-1 Brunswick Units 1 and 2 7-ii Rev. 25 LIST OF TABLES Table 7.3.1-1 Table 7.3.2-1 Table 7.3.3-1 Table 7.3.3-2 Table 7.3.7-1 Table 7.3.15-1 Table 7.3.15-2 Table 7.3.15-3 Radioactive Liquid Effluent Monitoring Instrumentation
........................
7.3.1-7 Radioactive Gaseous Effluent Monitoring Instrumentation
.........
7.3.2-9 Radioactive Liquid Waste Sampling and Analysis Program ..................
7.3.3-3 Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels .........
7.3.3-6 Radioactive Gaseous Waste Sampling and Analysis Program .............
7.3.7-2 Radiological Environmental Monitoring Program ................................
7.3.15-6 Limits for the Level of Radioactivity in Environmental Samples ........ 7.3.15-11 Detection Capabilities for Environmental Sample Analysis ...............
7.3.15-12 Brunswick Units 1 and 2 7-iii Rev. 30 LIST OF FIGURES Figure 7.1.1-1 SITE BO UNDARY ................................................................................
7.1.1-5 Brunswick Units 1 and 2 7-iv Rev. 25 Definitions 7.1.1 7.1.0 USE AND APPLICATION ODCMS 7.1.1 Definitions NOTE* The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual Specifications and Bases......................................................................J Term Definition CHANNEL CALIBRATION CHANNELCHECK CHANNEL FUNCTIONAL TEST A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.
A CHANNEL CHECK shall be the qualitative 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.
A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.(continued)
Brunswick Units 1 and 2 7.1.1-1 Rev. 25 Definitions
 
====7.1.1 ODCMS====
7.1.1 Definitions (continued)
GASEOUS RADWASTE TREATMENT SYSTEM LIQUID RADWASTE TREATMENT SYSTEM MEMBER(S)
OF THE PUBLIC MODE OPERABLE-OPERABILITY PURGE-PURGING A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to collect, treat and process radioactive liquid waste streams for reuse or for controlled discharge from the restricted area in compliance with established regulatory requirements.
MEMBER(S)
OF THE PUBLIC shall mean any individual(s) except when that individual is receiving occupational dose.A MODE shall be as required by Technical Specifications.
A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
PURGE or PURGING is the 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 containment.(continued)
Brunswick Units 1 and 2 7.1.1-2 Rev. 30 1 Definitions
 
====7.1.1 ODCMS====
7.1.1 Definitions (continued)
RATED THERMAL POWER (RTP)SITE BOUNDARY SOURCE CHECK THERMAL POWER UNRESTRICTED AREA VENTILATION EXHAUST TREATMENT SYSTEM RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2923 MWt.The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased nor otherwise controlled by the licensee, as defined by Figure 7.1.1-1. For the purpose of effluent release calculations, the boundary for atmospheric releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purpose of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional or recreational purposes.A VENTILATION EXHAUST TREATMENT SYSTEM is 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 Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.(continued)
Brunswick Units 1 and 2 7.1.1-3 Rev. 27 1 Definitions
 
====7.1.1 ODCMS====
7.1.1 Definitions (continued)
VENT-VENTING VENT or VENTING is the 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.
Vent, used in system names, does not imply a VENTING process.Brunswick Units 1 and 2 7.1.1-4 Rev. 25 POWER LINE RIGHT OF WAY'Definitions
 
====7.1.1 INTAKE====
CANAL /i J " I /\CAPEFEAR
/ J' ' \ RIVER Sx- PROPERTY BOUNDARY SITE AREA BOUNDARY/ EXCLUSION AREA Figure 7.1.1-1 (page 1 of 1)SITE BOUNDARY Brunswick Units 1 and 2 7.1.1-5 Rev. 25 Logical Connectors 7.1.2 7.1.0 USE AND APPLICATION ODCMS 7.1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Offsite Dose Calculation Manual Specifications (ODCMS) to discriminate between, and yet connect, discrete Conditions, Required Compensatory Measures, Completion Times, Tests, and Frequencies.
The only logical connectors that appear in ODCMS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.BACKGROUND Several levels of logic may be used to state Required Compensatory Measures.
These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Compensatory Measure. The first level of logic is identified by the first digit of the number assigned to a Required Compensatory Measure and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Compensatory Measure).
The successive levels of logic are identified by additional digits of the Required Compensatory Measure number and by successive indentions of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Test, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Test, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.(continued)
Brunswick Units 1 and 2 7.1.2-1 Rev. 25 Logical Connectors
 
====7.1.2 ODCMS====
7.1.2 Logical Connectors (continued)
EXAMPLES (continued)
EXAMPLE 7.1.2-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Verify...met.AND A.2 Restore...
In this example the logical connector AND is used to indicate that when in Condition A, both Required Compensatory Measures A. 1 and A.2 must be completed.(continued)
Brunswick Units 1 and 2 7.1.2-2 Rev. 25 Logical Connectors
 
====7.1.2 ODCMS====
7.1.2 Logical Connectors (continued)
EXAMPLES (continued)
EXAMPLE 7.1.2-2 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Trip...met.OR A.2.1 Verify...AND A.2.2.1 Reduce...OR A.2.2.2 Perform...
OR A.3 Align...This example represents a more complicated use of logical connectors.
Required Compensatory Measures A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement.
Any one of these three Compensatory Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Compensatory Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
Brunswick Units 1 and 2 7.1.2-3 Rev. 25 Completion Times 7.1.3 7.1.0 USE AND APPLICATION ODCMS 7.1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.BACKGROUND Offsite Dose Calculation Manual Specifications (ODCMS) specify minimum requirements for unit systems or variables.
The COMPENSATORY MEASURES associated with an ODCMS state Conditions that typically describe the ways in which the requirements of the ODCMS can fail to be met. Specified with each stated Condition are Required Compensatory Measure(s) and Completion Times(s).DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Compensatory Measure. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering a COMPENSATORY MEASURES Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the ODCMS. Required Compensatory Measures must be completed prior to the expiration of the specified Completion Time. A COMPENSATORY MEASURES Condition remains in effect and the Required Compensatory Measures apply until the Condition no longer exists or the unit is not within the ODCMS Applicability.
If situations are discovered that require entry into more than one Condition at a time within a single ODCMS (multiple Conditions), the Required Compensatory Measures for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.
Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Compensatory Measures of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.(continued)
Brunswick Units 1 and 2 7.1.3-1 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.
To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
: a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.The total Completion Time allowed for completing a Required Compensatory Measure to address the subsequent inoperability shall be limited to the more restrictive of either: a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours; or b. The stated Completion Time as measured from discovery of the subsequent inoperability.
The above Completion Time extension does not apply to those ODCMS that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.
These exceptions are stated in individual ODCMS.The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours," where the Completion Time is referenced from a previous completion of the Required Compensatory Measures versus the time of Condition entry) or as a time modified by the phrase "from discovery..." Example 7.1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 7.1.3-3 may not be extended.(continued)
Brunswick Units 1 and 2 7.1.3-2 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 7.1.3-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours Time not met.Condition B has two Required Compensatory Measures.
Each Required Compensatory Measure has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.The Required Compensatory Measures of Condition B are to be in MODE 3 within 12 hours AND in MODE 4 within 36 hours. A total of 12 hours is allowed for reaching MODE 3 and a total of 36 hours (not 48 hours) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours, the time allowed for reaching MODE 4 is the next 30 hours because the total time allowed for reaching MODE 4 is 36 hours.If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours.(continued)
Brunswick Units 1 and 2 7.1.3-3 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-2 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One pump A.1 Restore pump to 7 days inoperable.
OPERABLE status.B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours Time not met.When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Compensatory Measures B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Compensatory Measures of Condition B may be terminated.(continued)
Brunswick Units 1 and 2 7.1.3-4 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-3 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One Function X A.1 Restore 7 days subsystem Function X inoperable, subsystem to AND OPERABLE status. 10 days from discovery of failure to meet the ODCMS B. One Function Y B.1 Restore 72 hours subsystem Function Y inoperable, subsystem to AND OPERABLE status. 10 days from discovery of failure to meet the ODCMS C. One Function X C.1 Restore 72 hours subsystem Function X inoperable, subsystem to OPERABLE AND status.One Function Y OR subsystem inoperable.
C.2 Restore 72 hours Function Y subsystem to OPERABLE status.(continued)
Brunswick Units 1 and 2 7.1.3-5 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES EXAMPLE 7.1.3-3 (continued)(continued)
When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable.
The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Compensatory Measure C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Compensatory Measure A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the ODCMS was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the ODCMS. The separate Completion Time modified by the phrase "from discovery of failure to meet the ODCMS" is designed to prevent indefinite continued operation while not meeting the ODCMS. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the ODCMS was initially not met, instead of at the time the associated Condition was entered.(continued)
Brunswick Units 1 and 2 7.1.3-6 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-4 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve(s) 4 hours valves to OPERABLE inoperable, status.B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours Time not met.A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable.
The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours provided this does not result in any subsequent valve being inoperable for > 4 hours.If the Completion Time of 4 hours (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.(continued)
Brunswick Units 1 and 2 7.1.3-7 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-5 COMPENSATORY MEASURES NOTE Separate Condition entry is allowed for each inoperable valve.CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve to 4 hours valves OPERABLE inoperable, status.B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours Time not met.The Note above the COMPENSATORY MEASURES Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the COMPENSATORY MEASURES Table.The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.(continued)
Brunswick Units 1 and 2 7.1.3-8 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-5 (continued)
If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.EXAMPLE 7.1.3-6 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One channel A.1 Perform Once per 8 hours inoperable.
TR 7.3.x.x.OR A.2 Reduce 8 hours THERMAL POWER to_< 50% RTP.B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and associated Completion Time not met.(continued)
Brunswick Units 1 and 2 7.1.3-9 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES EXAMPLE 7.1.3-6 (continued)(continued)
Entry into Condition A offers a choice between Required Compensatory Measure A.1 or A.2. Required Compensatory Measure A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per TR 7.3.0.2, to each performance after the initial performance.
The initial 8 hour interval of Required Compensatory Measure A.1 begins when Condition A is entered and the initial performance of Required Compensatory Measure A. 1 must be completed within the first 8 hour interval.
If Required Compensatory Measure A.1 is followed and the Required Compensatory Measure is not met within the Completion Time (plus the extension allowed by TR 7.3.0.2), Condition B is entered. If Required Compensatory Measure A.2 is followed and the Completion Time of 8 hours is not met, Condition B is entered.If after entry into Condition B, Required Compensatory Measure A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.(continued)
Brunswick Units 1 and 2 7.1.3-10 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 7.1.3-7 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One subsystem A.1 Verify affected 1 hour inoperable, subsystem isolated.
AND Once per 8 hours thereafter AND A.2 Restore 72 hours subsystem to OPERABLE status.B. Required B.1 Be in MODE 3. 12 hours Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours Time not met.Required Compensatory Measure A.1 has two Completion Times. The 1 hour Completion Time begins at the time the Condition is entered and each "Once per 8 hours thereafter" interval begins upon performance of Required Compensatory Measure A. 1.If after Condition A is entered, Required Compensatory Measure A. 1 is not met within either the initial 1 hour or any subsequent 8 hour interval from the previous performance (plus the extension allowed by TR 7.3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues (continued)
Brunswick Units 1 and 2 7.1.3-11 Rev. 25 Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)
EXAMPLES EXAMPLE 7.1.3-7 (continued)(continued) from the time Condition A was initially entered. If Required Compensatory Measure A. 1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Compensatory Measure A.2 has not expired.IMMEDIATE When "Immediately" is used as a Completion Time, the Required COMPLETION TIME Compensatory Measure should be pursued without delay and in a controlled manner.Brunswick Units 1 and 2 7.1.3-12 Rev. 25 Frequency 7.1.4 7.1.0 USE AND APPLICATION ODCMS 7.1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
DESCRIPTION Each Test Requirement (TR) of the Offsite Dose Calculation Manual has a specified Frequency in which the Test must be met in order to meet the associated Offsite Dose Calculation Manual Specification (ODCMS). An understanding of the correct application of the specified Frequency is necessary for compliance with the TR.The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 7.3.0, Test Requirement (TR)Applicability.
The "specified Frequency" consists of the requirements of the Frequency column of each TR, as well as certain Notes in the Test column that modify performance requirements.
Sometimes special situations dictate when the requirements of a Test are to be met. They are "otherwise stated" conditions allowed by TR 7.3.0.1.They may be stated as clarifying Notes in the Test, as part of the Test, or both. Example 7.1.4-4 discusses these special situations.
Situations where a Test could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated ODCMS is within its Applicability, represent potential TR 7.3.0.4 conflicts.
To avoid these conflicts, the TR (i.e., the Test or the Frequency) is stated such that it is only "required" when it can be and should be performed.
With a TR satisfied, TR 7.3.0.4 imposes no restriction.
The use of "met or "performed" in these instances conveys specific meanings.
A Test is "met" only when the acceptance criteria are satisfied.
Known failure of the requirements of a Test, even without a Test specifically being "performed," constitutes a Test not "met.""Performance" refers only to the requirement to specifically determine the (continued)
Brunswick Units 1 and 2 7.1.4-1 Rev. 25 Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)
DESCRIPTION ability to meet the acceptance criteria.
TR 7.3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied:
: a. The Test is not required to be performed; and b. The Test is not required to be met or, even if required to be met, is not known to be failed.EXAMPLES The following examples illustrate the various ways that Frequencies are specified.
In these examples, the Applicability of the ODCMS (ODCMS not shown) is MODES 1, 2, and 3.EXAMPLE 7.1.4-1 TEST REQUIREMENTS TEST FREQUENCY Perform CHANNEL CHECK. 12 hours Example 7.1.4-1 contains the type of TR most often encountered in the ODCMS. The Frequency specifies an interval (12 hours) during which the associated Test must be performed at least one time. Performance of the Test initiates the subsequent interval.
Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by TR 7.3.0.2 for operational flexibility.
The measurement of this interval continues at all times, even when the TR is not required to be met per TR 7.3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the ODCMS). If the interval specified by TR 7.3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the ODCMS, and the performance of the Test is not otherwise modified (refer to Examples 7.1.4-3 and 7.1.4-4), then TR 7.3.0.3 becomes applicable.(continued)
Brunswick Units 1 and 2 7.1.4-2 Rev. 25 Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)
EXAMPLES (continued)
EXAMPLE 7.1.4-1 (continued)
If the interval as specified by TR 7.3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the ODCMS for which performance of the TR is required, the Test must be performed within the Frequency requirements of TR 7.3.0.2 prior to entry into the MODE or other specified condition.
Failure to do so would result in a violation of TR 7.3.0.4.EXAMPLE 7.1.4-2 TEST REQUIREMENTS TEST FREQUENCY Verify flow is within limits. Once within 12 hours after! 25% RTP AND 24 hours thereafter Example 7.1.4-2 has two Frequencies.
The first is a one time performance Frequency, and the second is of the type shown in Example 7.1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to_> 25% RTP, the Test must be performed within 12 hours.The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").This type of Frequency does not qualify for the extension allowed by TR 7.3.0.2.(continued)
Brunswick Units 1 and 2 7.1.4-3 Rev. 25 Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)
EXAMPLES EXAMPLE 7.1.4-2 (continued)(continued)"Thereafter" indicates future performances must be established per TR 7.3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example).
If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.EXAMPLE 7.1.4-3 TEST REQUIREMENTS TEST FREQUENCY r---------------------------------------I NOTE:Not required to be performed until 12 hours after;_> 25% RTP.Perform channel adjustment.
7 days The interval continues whether or not the unit operation is < 25% RTP between performances.
As the Note modifies the required performance of the Test, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours after power reaches > 25% RTP to perform the Test. The Test is still considered to be within the "specified Frequency." Therefore, if the Test were not performed within the 7 day interval (plus the extension allowed by TR 7.3.0.2), but operation was < 25% RTP, it would not constitute a failure of the TR or failure to meet the ODCMS. Also, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours with power _> 25% RTP.(continued)
Brunswick Units 1 and 2 7.1.4-4 Rev. 25 Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)
EXAMPLES EXAMPLE 7.1.4-3 (continued)(continued)
Once the unit reaches 25% RTP, 12 hours would be allowed for completing the Test. If the Test were not performed within this 12 hour interval, there would then be a failure to perform a Test within the specified Frequency, and the provisions of TR 7.3.0.3 would apply.EXAMPLE 7.1.4-4 TEST REQUIREMENTS TEST FREQUENCY S-------------------------------------
I NOTE_Only required to be met in MODE 1.Verify leakage rates are within limits. 24 hours Example 7.1.4-4 specifies that the requirements of this Test do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Test continues at all times, as described in Example 7.1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Test. Therefore, if the Test were not performed within the 24 hour (plus the extension allowed by TR 7.3.0.2)interval, but the unit was not in MODE 1, there would be no failure of the TR nor failure to meet the ODCMS. Therefore, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 24 hour Frequency exceeded, provided the MODE change was not made into MODE 1.Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), TR 7.3.0.4 would require satisfying the TR.Brunswick Units 1 and 2 7.1.4-5 Rev. 25 7.2.0 Not used.Brunswick Units 1 and 2 7.2.0-1 Rev. 25 ODCMS Applicability 7.3.0 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)APPLICABILITY ODCMS 7.3.0.1 ODCMSs shall be met during the MODES or other specified conditions in the Applicability, except as provided in ODCMS 7.3.0.2.ODCMS 7.3.0.2 Upon discovery of a failure to meet an ODCMS, the required Compensatory Measures of the associated Conditions shall be met, except as provided in ODCMS 7.3.0.5.If the ODCMS is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Compensatory measure(s) is not required, unless otherwise stated.ODCMS 7.3.0.3 Not used.ODCMS 7.3.0.4 When an ODCMS is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated COMPENSATORY MEASURES to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This ODCMS shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES, or that are part of a shutdown of the unit.Exceptions to this ODCMS are stated in the individual ODCMSs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated COMPENSATORY MEASURES to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.ODCMS 7.3.0.5 Equipment removed from service or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
This is an exception to ODCMS 7.3.0.2 for the system returned to service under administrative control to perform the required testing.(continued)
Brunswick Units 1 and 2 7.3.0-1 Rev. 25 ODCMS Applicability 7.3.0 7.3.0 ODCMS APPLICABILITY (continued)
ODCMS 7.3.0.6 ODCMSs and associated COMPENSATORY MEASURES shall apply to both units except as follows: a. Whenever the ODCMS refers to systems or components which are not shared by both units, the ODCMS and associated Applicability and COMPENSATORY MEASURES shall apply to each unit individually (e.g., in the event of an inoperability in a non-shared system, the appropriate COMPENSATORY MEASURES will apply only to the unit with the inoperable system);b. Whenever the ODCMS only applies to one unit, this will be identified in the Applicability of the ODCMS; and c. Whenever certain portions of the ODCMS, Applicability, or COMPENSATORY MEASURES contain operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.
Brunswick Units 1 and 2 7.3.0-2 Rev. 25 TR Applicability 7.3.0 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY TR 7.3.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability for individual ODCMSs, unless otherwise stated in the TR.Failure to meet a Test whether such failure is experienced during the performance of the Test or between performances of the Test, shall be failure to meet the ODCMS. Failure to perform a Test within the specified Frequency shall be failure to meet the TRMS except as provided in TR 7.3.0.3. Tests do not have to be performed on inoperable equipment or variables outside specified limits.TR 7.3.0.2 The specified Frequency for each TR is met if the Test is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a"once per ..." basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this ODCMS are stated in the individual ODCMSs.TR 7.3.0.3 If it is discovered that a Test was not performed within its specified Frequency, then compliance with the requirement to declare the ODCMS not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Test.If the Test is not performed within the delay period, the ODCMS must immediately be declared not met, and the applicable Condition(s) must be entered.When the Test is performed within the delay period and the Test is not met, the ODCMS must immediately be declared not met, and the applicable Condition(s) must be entered.(continued)
Brunswick Units 1 and 2 7.3.0-3 Rev. 25 TR Applicability 7.3.0 7.3.0 TR APPLICABILITY (continued)
TR 7.3.0.4 TR 7.3.0.5 Entry into a MODE or other specified condition in the Applicability of an ODCMS shall not be made unless the ODCMS's Tests have been met within their specified Frequency.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES or that are part of a shutdown of the unit.TRs shall apply to both units (e.g., a single Test performed at the specified Frequency will satisfy the TR for both units) except as follows: a. Whenever the ODCMS refers to systems or components which are not shared by both units, the associated TR shall apply to each unit individually (e.g., individual tests must be performed on each of the two units' non-shared systems or components; a single Test on a non-shared system of one unit performed at the specified Frequency will not satisfy the TR for the non-shared system of the other unit);b. Whenever a TR only applies to one unit, this will be identified by a note to the TR; and c. Whenever certain portions of the TRs, contain test parameters, acceptance criteria, or frequencies which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.
Brunswick Units 1 and 2 7.3.0-4 Rev. 25 Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.1 The radioactive liquid effluent monitoring instrumentation channels in Table 7.3.1-1 shall be OPERABLE.NOTE The annunciator function may be removed from operation for performance of troubleshooting
!for up to 30 minutes provided the associated function maintains monitoring capability APPLICABILITY:
In accordance with Table 7.3.1-1.COMPENSATORY MEASURES----------------------------------------------------------------------------------NOTE Separate Condition entry is allowed for each required channel.------------------------------------------------------------------------
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A. 1 Enter the Condition Immediately liquid effluent monitoring referenced in instrumentation channels Table 7.3.1-1 for the inoperable.
channel.B. As required by Required B. 1 Perform TR 7.3.3.1 on two Prior to release Compensatory Measure A. 1 independent samples of through the liquid and referenced in the batch to be released.
radwaste effluent Table 7.3.1-1. line AND B.2 Verify the associated Prior to release release rate calculations through the liquid and the discharge valve radwaste effluent lineup using two qualified line members of the technical staff.AND B.3 Restore the channel to 30 days OPERABLE status.(continued)
Brunswick Units 1 and 2 7.3.1-1 Rev. 29 1 Radioactive Liquid Effluent Monitoring Instrumentation
 
====7.3.1 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required C.1 Estimate the flow rate Once per 4 hours Compensatory Measure A.1 through the associated during releases and referenced in pathway using pump through the Table 7.3.1-1. performance curves or associated line tank level indicators.
AND C.2 Restore the channel to 30 days OPERABLE status.D. As required by Required D.1 Collect and analyze a grab Once per 12 hours Compensatory Measure A. 1 sample for gross and referenced in radioactivity (beta or Table 7.3.1-1. gamma) of the associated effluent.
The LLD shall be< 1.0 E-7 pCi/gm.AND D.2 Restore the channel to 30 days OPERABLE status.E. As required by Required E.1 Collect and analyze a grab Once per 24 hours Compensatory Measure A. 1 sample for principal and referenced in gamma emitters per Table 7.3.1-1. Table 7.3.3-1.AND 30 days E.2 Restore the channel to OPERABLE status.(continued)
Brunswick Units 1 and 2 7.3.1-2 Rev. 25 Radioactive Liquid Effluent Monitoring Instrumentation
 
====7.3.1 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME F. As required by F.1 Estimate the flow rate through the Once per 24 hours Required associated pathway using the Compensatory V-notch weir or another acceptable Measure A.1 and method.referenced in Table 7.3.1-1. AND F.2 Restore the channel to OPERABLE status. 30 days G. As required by G.1 Estimate the tank liquid level. Once per 8 hours Required during all liquid Compensatory additions and Measure A.1 and deletions to and from referenced in the tank Table 7.3.1-1.AND G.2 Restore the channel to OPERABLE 30 days status.H. Required H.1 Suspend effluent releases via the Immediately Compensatory associated pathway.Measure B.1, B.2, C.1, D.1, E.1, F.1, AND or G.1 and associated H.2 Completion Time -------------------------------
not met.NOTE nmOnly applicable for Function 6.Suspend liquid additions to the Condensate Storage Tank. Immediately (continued)
Brunswick Units 1 and 2 7.3.1-3 Rev. 25 Radioactive Liquid Effluent Monitoring Instrumentation
 
====7.3.1 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME Required Compensatory
 
===1.1 Prepare===
and submit, in the Upon submittal of Measure B.3, C.2, D.2, E.2, Radioactive Effluent current calendar F.2, G.2, or J.2 and Release Report, the year Radioactive associated Completion Time reason the channel was Effluent Release not met. not restored to Report OPERABLE status within 30 days.J. As required by Required J.1 Estimate the flow rate Once per 24 hours Compensatory Measure A. 1 through the associated and referenced in Table pathway using the 7.3.1-1. Parshall flume or another acceptable method.AND J.2 Restore the channel to 30 days OPERABLE status.TEST REQUIREMENTS NOTE Refer to Table 7.3.1-1 to determine which TRs apply for each Radioactive Liquid Effluent ,Monitoring Instrumentation Function.TEST FREQUENCY TR 7.3.1.1 NOTE For Function 6, only required to be met during liquid additions to the tank.Perform CHANNEL CHECK. 24 hours TR 7.3.1.2 NOTE Only required to be met during continuous, periodic, or batch releases.Verify indication of flow. 24 hours (continued)
Brunswick Units 1 and 2 7.3.1-4 Rev. 35 Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.1.3 Perform SOURCE CHECK. 31 days TR 7.3.1.4 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of automatic isolation of the pathway and control room annunciation in response to any of the following:
: a. Alarm/trip setpoint exceeded.b. Circuit failure.c. Downscale failure.d. Instrument controls not set in "operate" mode.TR 7.3.1.5 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.1.6 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:
: a. Alarm/trip setpoint exceeded.b. Circuit failure.c. Downscale failure.d. Instrument controls not set in "operate" mode.(continued)
Brunswick Units 1 and 2 7.3.1-5 Rev. 26 Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.1.7------------------------NOTE For Functions 1 and 3, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall be used.Perform CHANNEL CALIBRATION.
24 months Brunswick Units 1 and 2 7.3.1-6 Rev. 25 Radioactive Liquid Effluent Monitoring Instrumentation
 
====7.3.1 Table====
7.3.1-1 (page 1 of 1)Radioactive Liquid Effluent Monitoring Instrumentation FUNCTION (a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A. 1 1. Liquid Radwaste Radioactivity At all times 1 B TR 7.3.1.1 (c)Effluent Monitor (b) TR 7.3.1.3 TR 7.3.1.4 TR 7.3.1.7 2. Liquid Radwaste Effluent Flow At all times 1 C TR 7.3.1.2 NA Measurement Device TR 7.3.1.5 TR 7.3.1.7 3. Main Service Water System At all times 1 D TR 7.3.1.1 (c)Effluent Radioactivity Monitor TR 7.3.1.3 TR 7.3.1.6 TR 7.3.1.7 4. Stabilization Pond Effluent (d) 1 E TR 7.3.1.1 NA (e)Composite Sampler TR 7.3.1.5 TR 7.3.1.7 5. Stabilization Pond Effluent (d) 1 F TR 7.3.1.1 NA Flow Measurement Device TR 7.3.1.5 TR 7.3.1.7 6. Condensate Storage Tank At all times 1 G TR 7.3.1.1 NA (0 Level Indicating Device TR 7.3.1.5 TR 7.3.1.7 7. Groundwater Extraction (d) 1 E TR 7.3.1.1 NA (9)Effluent Composite Sampler TR 7.3.1.5 TR 7.3.1.7 8 Groundwater Extraction (d) 1 TR 7.3.1.1 NA Effluent Flow Measurement TR 7.3.1.5 Device TR 7.3.1.7 9. Stabilization Facility Effluent (d) 1 E TR 7.3.1.1 NA (h)Composite Sampler TR 7.3.1.5 TR 7.3.1.7 10. Stabilization Facility Effluent (d) 1 J TR 7.3.1.1 NA Flow Measurement Device TR 7.3.1.5 TR 7.3.1.7 (a)(b)(c)(d)(e)(f)(g)(h)Specific instrumentation identification numbers are provided in Appendix E.Provides alarm and automatic termination of release.Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.3, "Concentration-Liquid Effluents," are not exceeded.At all times other than when the line is valved out and locked.Flow Totalizer 2-DST-FQIS-5026 provides a trip signal to the composite sampler that will initiate sampling.1(2) CO-LIT-1160 provides local level indication and also provides a signal to 1(2) CO-LI-1160A and 1(2) CO-LI-1160B.
Flow Measurement Device 0-GWE-FIT-1 directly triggers the composite sampler.Flow Measurement Device 0-SDSF-FIT-2 directly triggers the composite sampler.Brunswick Units 1 and 2 7.3.1-7 Rev. 35 Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.2 The radioactive gaseous effluent monitoring instrumentation channels in Table 7.3.2-1 shall be OPERABLE.NOTE The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability.
If removing the annunciator for the 1/2-CAC-AT-1264 refer to ODCM Bases 7.3.2.-----------------------------------------------------------------------------------------------------------------------------.APPLICABILITY:
In accordance with Table 7.3.2-1.COMPENSATORY MEASURES NOTE Separate Condition entry is allowed for each required channel.CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A.1 Enter the Condition Immediately gaseous effluent monitoring referenced in instrumentation channels Table 7.3.2-1 for the inoperable, channel.B. As required by Required B.1 Take a grab sample at the Once per 12 hours Compensatory Measure A. 1 associated sample and referenced in location.Table 7.3.2-1.AND 24 hours after B.2 Analyze the grab sample completion of required by Required Required Compensatory Compensatory Measure B. 1 for gross Measure B.1 noble gas activity.AND 30 days B.3 Restore the channel to OPERABLE status.(continued)
Brunswick Units 1 and 2 7.3.2-1 Rev. 29 1 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required Compensatory Measure A. 1 and referenced in Table 7.3.2-1.C.1.1 Initiate actions to establish auxiliary sampling equipment to continuously collect samples from the associated effluent release pathway as required by Table 7.3.7-1.OR C.1.2 S........................, NOTE:Only applicable for ODCM ,test requirements, sample;:analysis, or system;purging.
Reference;ODCMS 7.3.0.5 for post maintenance test requirements.
Initiate continuous sample collection from associated release pathway as required by Table 7.3.7-1 with auxiliary sampling equipment.
Immediately 45 minutes 30 days AND C.2 Restore the channel to OPERABLE status.(continued)
Brunswick Units 1 and 2 7.3.2-2 Rev. 25 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D. As required by Required D.1 Estimate the flow rate Once per 8 hours Compensatory Measure A. 1 through the associated and referenced in pathway.Table 7.3.2-1.AND D.2 Restore the channel to 30 days OPERABLE status.E. Required Compensatory E.1 Suspend effluent releases Immediately Measure B.1, B.2, C.1.1, via the associated C.1.2, and D.1 and pathway.associated Completion Time not met.(continued)
Brunswick Units 1 and 2 7.3.2-3 Rev. 25 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME F. As required by Required Compensatory Measure A. 1 and referenced in Table 7.3.2-1.r--------------------- -I NOTE!Required Compensatory
:Measures F.1 and F.2 are only applicable if two channels are inoperable in the operating! recombiner train.F. 1 AND F.2 AND Take a grab sample from the operating recombiner train.Analyze the grab sample required by Required Compensatory Measure F.1.Verify proper functioning of the operating recombiner train by monitoring recombiner temperature.
Restore the channel(s) to OPERABLE status.Once per 24 hours 4 hours after completion of Required Compensatory Measure F.1 In accordance with approved procedures 30 days F.3 AND F.4 G. Required Compensatory G.1 Suspend operation of the Immediately Measure F.1, F.2, or F.3 associated recombiner and associated Completion train.Time not met.(continued)
Brunswick Units 1 and 2 7.3.2-4 Rev. 25 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME H. Required Compensatory H.1 Prepare and submit in the Upon submittal of Measure B.3, C.2, D.2, Radioactive Effluent current calendar or F.4 and associated Release Report, the year Radioactive Completion Time not met. reason the channel was Effluent Release not restored to Report OPERABLE status within 30 days.As required by Required Compensatory Measure A.1 and referenced in Table 7.3.2-1.I. 1 Verify GASEOUS RADWASTE TREATMENT SYSTEM is not bypassed.AND 1.2 Verify the main stack effluent noble gas monitor is OPERABLE.AND 1.3 -------- NOTE ----------
If the SJAE grab sample cannot be obtained at the normal sample point the sample can be obtained at the inlet to the Gaseous Radwaste Treatment System and the results decay corrected back to normal location to verify the activity level at the SJAE.Take a grab sample and analyze to verify that the noble gas gross gamma activity rate is < 243,600 pCi/second Immediately Immediately Once within 72 hours AND Every 4 hours thereafter 30 days AND 1.4 Restore the channel to OPERABLE status.(continued)
Brunswick Units 1 and 2 7.3.2-5 Rev. 33 1 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 COMPENSATORY====
 
MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME J. Required Compensatory J.1 Be in MODE 2. 12 hours Measure and associated AND AND Completion Time of Condition I not met. J.2 Prepare and submit in the Upon submittal of Radioactive Effluent current calendar Release Report, the year Radioactive reason the channel was Effluent Release not restored to Report OPERABLE status within 30 days.K. As required by Required K.1 Suspend effluent releases Immediately Compensatory Measure A. 1 via the associated and referenced in pathway.Table 7.3.2-1.TEST REQUIREMENTS r -------------------------------------------------------------------
NOTE Refer to Table 7.3.2-1 to determine which TRs apply for each Radioactive Gaseous Effluent:Monitoring Instrumentation Function.TEST FREQUENCY TR 7.3.2.1 Perform CHANNEL CHECK. 24 hours TR 7.3.2.2 Perform CHANNEL CHECK. 7 days TR 7.3.2.3 Perform SOURCE CHECK. 31 days TR 7.3.2.4 Perform CHANNEL FUNCTIONAL TEST. 31 days (continued)
Brunswick Units 1 and 2 7.3.2-6 Rev. 33 1 Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.2.5 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:
: a. Alarm/trip setpoint exceeded.b. Downscale failure.c. Instrument controls not set in "operate" mode.TR 7.3.2.6 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.2.7 Perform CHANNEL FUNCTIONAL TEST; including 92 days demonstration of control room annunciation in response to any of the following:
: a. Alarm/trip setpoint exceeded.b. Downscale failure.TR 7.3.2.8 Perform CHANNEL FUNCTIONAL TEST including 92 days control room annunciation in response to any of the following:
: a. Alarm/trip setpoint exceeded.b. Circuit failure.c. Downscale failure.d. Instrument controls not set in "operate" mode.(continued)
Brunswick Units 1 and 2 7.3.2-7 Rev. 26 1 Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.2.9 Perform CHANNEL CALIBRATION.
The CHANNEL 92 days CALIBRATION shall include the use of standard gas samples containing a nominal: a. Two volume percent hydrogen, balance nitrogen; and b. Four volume percent hydrogen, balance nitrogen.TR 7.3.2.10 r--------------------------------------------
NOTE For Functions 1.a, 2.a, 3.a, 4, and 6, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall be used.Perform CHANNEL CALIBRATION.
24 months Brunswick Units 1 and 2 7.3.2-8 Rev. 25 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 Table====
7.3.2-1 (page 1 of 4)Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION APPLICABLE REQUIRED CONDITIONS TEST ALARM/MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1 1. Main Stack Monitoring System a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)Monitor TR 7.3.2.3 TR 7.3.2.5 TR 7.3.2.10 b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10 e. Low Range Sampler At all limes 1 D TR 7.3.2.1 (c)Flow Rate TR 7.3.2.6 Measurement Device TR 7.3.2.10 f. Mid/High Range (m) -1 D TR 7.3.2.6 N/A Sampler Flow Rate TR 7.3.2.10 Measurement Device 2. Reactor Building Ventilation Monitoring System a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)Monitor TR 7.3.2.3 TR 7.3.2.7 TR 7.3.2.10 b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge c. Particulate Sampler At all limes 1 C TR 7.3.2.2 NA Filter d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10 (continued)(a) Specific instrumentation identification numbers are provided in Appendix E.(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate--Gaseous Effluents," are not exceeded.(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rateaseous Effluents," are not exceeded.(m) During Mid/High Range System operation Brunswick Units 1 and 2 7.3.2-9 Rev. 33 1 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 Table====
7.3.2-1 (page 2 of 4)Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION APPLICABLE REQUIRED CONDITIONS TEST ALARM/TRIP MODES OR CHANNELS REFERENCED REQUIREMENTS SETPOINT OTHER PER FROM REQUIRED VALUE SPECIFIED FUNCTION COMPENSATORY CONDITIONS MEASURES A.1 2. Reactor Building Ventilation Monitoring System (continued)
: e. Sampler Flow Rate At all times 1 D TR 7.3.2.1 (c)Measurement Device TR 7.3.2.6 TR 7.3.2.10 3. Turbine Building Ventilation Monitoring System a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)Monitor TR 7.3.2.3 TR 7.3.2.5 TR 7.3.2.10 b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10 e. Low Range Sampler At all times 1 D TR 7.3.2.1 (c)Flow Rate TR 7.3.2.6 Measurement Device TR 7.3.2.10 f. Mid/High Range (m) 1 D TR 7.3.2.6 NA Sampler Flow Rate TR 7.3.2.10 Measurement Device 4. Main Condenser Off-Gas (e) 1 B TR 7.3.2.1 (b)Treatment System Noble TR 7.3.2.3 Gas Activity Monitor (d) TR 7.3.2.6 (Downstream of AOG TR 7.3.2.10 Treatment System)(continued)(a) Specific instrumentation identification numbers are provided in Appendix E.(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.(c) Alarm/trip selpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rate--Gaseous Effluents," are not exceeded.(d) Provides alarm.(e) During Main Condenser Off-Gas Treatment System operation (m) During Mid/High Range System operation Brunswick Units 1 and 2 7.3.2-10 Rev. 33 1 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 Table====
7.3.2-1 (page 3 of 4)Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION (a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1 5. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System a. Recombiner Train A (I) 2 F TR 7.3.2.1 (c)TR 7.3.2.4 TR 7.3.2.9 b. Recombiner Train B (I) 2 F TR 7.3.2.1 (c)TR 7.3.2.4 TR 7.3.2.9 6. Main Condenser Air Ejector (f) 1 I TR 7.3.2.1 (b)Noble Gas Radioactivity TR 7.3.2.3 Monitor (k) (Prior to input to TR 7.3.2.8 Treatment System) TR 7.3.2.10 7. Hot Shop Ventilation Monitoring System a. Iodine Sampler (j) 1 K TR 7.3.2.2 NA Cartridge b. Particulate Sampler 0) 1 K TR 7.3.2.2 NA Filter c. Sampler Flow Rate () K TR 7.3.2.1 NA Measurement Device TR 7.3.2.2 (continued)(a) Specific instrumentation identification numbers are provided in Appendix E.(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.(f) During operation of the main condenser air ejector () During operation of the Hot Shop Ventilation System (k) Provides Hi and Hi Hi alarm (I) During associated recombiner train operation Brunswick Units 1 and 2 7.3.2-11 Rev. 36 1 Radioactive Gaseous Effluent Monitoring Instrumentation
 
====7.3.2 Table====
7.3.2-1 (page 4 of 4)Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION ( APPLICABLE REQUIRED CONDITIONS TEST ALARM/MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1 8. Radioactive Materials Container and Storage Building Decontamination Facility a. Iodine Sampler (g) 1 K TR 7.3.2.1 NA Cartridge b. Particulate Sampler (g) 1 K TR 7.3.2.1 NA Filter c. Sampler Flow Rate (g) 1 K TR 7.3.2.1 NA Measurement Device 9. Low Level Warehouse a. Particulate Sampler Filter (h) 1 K TR 7.3.2.2 NA (i (a)(g)(h)(i)Specific instrumentation identification numbers are provided in Appendix E.During operation of the Radioactive Materials Container and Storage Building Decontamination Facility.During operation of the Low Level Warehouse ventilation system.Local alarm.Brunswick Units 1 and 2 7.3.2-12 Rev. 32 1 Concentration
-Liquid Effluents 7.3.3 7.3.3 CONCENTRATION-LIQUID EFFLUENTS ODCMS 7.3.3 The concentration of radioactive material released to UNRESTRICTED AREAS after dilution in the discharge canal shall be limited to: a. 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 for radionuclides other than dissolved or entrained noble gases; and b. 2 x 10-4piCi/ml total activity concentration for all dissolved or entrained noble gases.APPLICABILITY:
At all times.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Concentration of radioactive A.1 Initiate action to restore Immediately material released to concentration to within UNRESTRICTED AREAS limits.not within limits.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.3.1 Verify the concentration of radioactive material In accordance with released to UNRESTRICTED AREAS is within limits. Table 7.3.3-1 (continued)
Brunswick Units 1 and 2 7.3.3-1 Rev. 25 Concentration
-Liquid Effluents 7.3.3 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.3.2 NOTE O nly required to be performed if service water samples analyzed in accordance with Table 7.3.3-1 indicate concentrations of any gamma-emitting radionuclides greater than the trigger level of 5 x ,10'-6O Ci/mI.Verify concentration of radioactive material released to In accordance with UNRESTRICTED AREAS is within limits. Table 7.3.3-2 for liquid wastes exceeding the trigger level Brunswick Units 1 and 2 7.3.3-2 Rev. 35 Concentration
-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 1 of 3)Radioactive Liquid Waste Sampling and Analysis Program LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD) (a)(e)Sample Tanks, Prior to release of Prior to release of each Principal Gamma 5 x 1 0-7(b) pCi/ml Detergent Drain each batch batch Emitters g Tank, and Salt Water 1-131 1 x 106pCi/ml Release Tanks (Batch Release), (h)Prior to release of one 31 days Dissolved and 1 x 10-5pCi/ml batch once per entrained gases AND 31 days (Gamma Emitters)Circulating Water Pit Prior to release of 31 days Gross Alpha 1 x 10-7 pCi/ml each batch Composile(c)
H-3 1 x 10-5pCi/ml Prior to release of 92 days Sr-89, Sr-90 5 x 1081PCi/mI each batch Composite(c)
Fe-55 1 x 106pCi/ml 2. Stabilization Pond Prior 1o each release Prior to each release Principal Gamma 5 x 1 0-7(b) pCi/mI Emitters (H-3 1 x 10.5 pCi/ml AND AND 24 hours during 24 hours during periods of release M periods of release (After completion of After completion of Sr-89, Sr-90 5 x 10"8 pCi/ml each release (i each release (i) Fe-55 1 x 10, pCi/ml Gross Alpha 1 x 10-7 pCi/ml Principal Gamma 5 x 10.7 pCi/mI Emitters (g)H-3 1 x 10-5 pCi/ml 3. Service Water (d) 7 days during system 7 days during system Principal Gamma 5 x 10-i pCi/ml(')(Potential operation operation Emitters )Continuous Release)4. Groundwater Prior to each releaseo)
Grab Sample Principal Gamma 5 x 10.7 pCi/ml Extraction System 7 day Composite(c)
Emitters(g)(Continuous 1-131 1 x 106 pCi/mI Release) AND H-3 1 x 10-5 pCi/ml 7 days during system operation(c(t) 31 day Composite(c)
Gross Alpha 1 x 10-7 pCi/ml 92 day Sr-89, Sr-90 5 x 10-8 pCi/ml Composite(c)
Fe-55 1 X 106 pCi/ml 5. Stabilization Facility Prior to each release Prior to each release Principal Gamma 5 x 10.71() pCi/ml Emitters (g)H-3 1 x 10.5 pCi/ml AND AND 24 hours during 24 hours during periods of release(f) periods of release(f After completion of After completion of Sr-89, Sr-90 5 x 10.8 pCi/ml each release(,)
each release(')
Fe-55 1 x 106 pCi/ml Gross Alpha 1 x 10-7 pCi/ml Principal Gamma 5 x 10,7 pCi/ml Emitters (g)H-3 1 x 10.5 pCi/ml Brunswick Units 1 and 2 7.3.3-3 Rev. 35 Concentration
-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 2 of 3)Radioactive Liquid Waste Sampling and Analysis Program (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released.
For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.(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 in a specimen that is representative of the liquids released.(d) The service water liquid release type represent potential release pathways and not an actual release pathway. Test of this pathway is intended to alert the plant to a potential problem; analysis for principal gamma emitters should be sufficient to meet this intent.If analysis for principal gamma emitters indicates a problem (i.e., exceeds the trigger level of 5x10-6 liCi/ml), then complete sampling and analyses shall be performed as per Table 7.3.3-2.(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 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 yb E-V-2.22 x 10 6
* Y. e-( &#xfd;t e)Where: LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume)b = (N/tb)/'= standard deviation of background (cpm)Brunswick Units 1 and 2 7.3.3-4 Rev. 31 Concentration
-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 3 of 3)Radioactive Liquid Waste Sampling and Analysis Program N = background count rate (cpm)tb = time background counted for (min)E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)
Y = fractional radiochemical yield S = radioactive decay constant of ith nuclide (sec')te = elapsed time between sample collection and counting (sec)Typical values of E, V, Y, and te should be used in the calculation.
It should be recognized that the LLD is defined as an "a orio" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.(f) The stabilization pond and stabilization facility are typically released over a several-day period. The pond and facility are to be sampled and analyzed prior to commencing a release. When composite sampling instrumentation is OPERABLE, daily grab sampling of the stabilization pond or stabilization facility effluent will not be required during release and the composite sample will be analyzed at the end of the release.(g) The principal gamma emitters for which the LLD specifications apply exclusively are 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.(h) 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.(i) Sr-89, Sr-90, Fe-55 and Gross Alpha analyses are to be performed on the composite sample at the end of the release period.(j) These requirements only apply if the Groundwater Extraction (GWE) System is being released directly to the intake canal. During periods when the GWE System is directed to the Stabilization Pond or Stabilization Facility sampling of the GWE System is not required.Brunswick Units 1 and 2 7.3.3-5 Rev. 35 Concentration
-Liquid Effluents 7.3.3 Table 7-3.3-2 (page 1 of 3)Radioactive Liquid Waste Sampling and Analysis Program for Potenlial Release Pathways Which Have Exceeded Trigger Levels LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD) (a)(e)Service Waler 24 hours (d) 7 days Principal Gamma 5 x 10-7 (b)pCi/ml (Continuous Composite(c)
Emilters (10 Release) (g)1-131 1 X 10,6Ci/ml 31 days 31 days Dissolved and 1 x 10-5 1pCi/ml Grab Sample entrained gases (Gamma Emitters)24 hours (d) 31 days Gross Alpha 1 x 10-7pCi/ml Composite(c)
H-3 1 x 10-.Ci/ml 24 hours (d) 92 days Sr-89, Sr-90 5 x 101Ci/ml Composile(c)
Fe-55 1 x 10 pCi/ml Brunswick Units 1 and 2 7.3.3-6 Rev. 35 Concentration
-Liquid Effluents 7.3.3 Table 7.3.3-2 (page 2 of 3)Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released.
For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.(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 in a specimen that is representative of the liquids released.(d) Until such time as continuous proportional composite samplers are installed on the service water discharge line, daily grab sampling of the service water effluent will be required for use in making up the composite.(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 5%probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
LLD= 4.66ab E. V-2.22 x 106
* Y. e-(?'t e)Where: LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume)cGb = (N/tb)'= standard deviation of background (cpm)N = background count rate (cpm)Brunswick Units 1 and 2 7.3.3-7 Rev. 25 1 Concentration
-Liquid Effluents 7.3.3 Table 7.3.3-2 (page 3 of 3)Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels tb = time background counted for (min)E= counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 10 6  = conversion factor (dpm/microcurie)
Y = fractional radiochemical yield ki = radioactive decay constant of ith nuclide (sec-1)te = elapsed time between sample collection and counting (sec)Typical values of E, V, Y, and te should be used in the calculation.
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.(f) The principal gamma emitters for which the LLD specifications apply exclusively are 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.(g) A continuous release is the discharge of liquid waste of a nondiscrete volume, e.g., from a volume or a system that has an input flow during the continuous release.Brunswick Units 1 and 2 7.3.3-8 Rev. 31 1 Dose-Liquid Effluents 7.3.4 7.3.4 DOSE--LIQUID EFFLUENTS ODCMS 7.3.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to: a. _< 3 mrem to the total body and _ 10 mrem to any organ during any calendar quarter; and b. < 6 mrem to the total body and  20 mrem to any organ during any calendar year.APPLICABILITY:
At all times.COMPENSATORY MEASURES NOTE;Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total.Dose (40 CFR_1_90)_," when liquid effluent dose-results in exceeding an annual total dose -imit_.CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report 30 days r -to the NRC that identifies NOTE causes for exceeding i Required Compensatory limits, corrective actions ,Measure A. 1 shall be lmtcretv cin Mtaken to reduce releases, completed if this Condition and corrective actions to is entered.------------------------
assure that subsequent releases will be in Calculated dose from the compliance with the release of radioactive required limits.materials in liquid effluents to UNRESTRICTED AREAS not within limits.Brunswick Units 1 and 2 7.3.4-1 Rev. 25 Dose-Liquid Effluents 7.3.4 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.4.1 Verify the cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.4-2 Rev. 25 Liquid Radwaste Treatment System 7.3.5 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM ODCMS 7.3.5 APPLICABILITY:
The Liquid Radwaste Treatment System shall be used to reduce radioactive materials in liquid wastes prior to their discharge.
During release of liquid radioactive water when the projected doses due to the liquid effluent, from the site to UNRESTRICTED AREAS, would exceed 0.12 mrem to the total body or 0.4 mrem to any organ in a 31 day period.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report 30 days , -to the NRC that includes SNOTE explanation of why liquid Required Compensatory radwaste was being Measure A. 1 shall be discharged without completed if this Condition dshre ihu ,ompetditis etreatment, identification of ,is entered, --any required inoperable equipment or subsystem Liquid waste being and the reasons for the discharged without inoperability, the corrective treatment.
actions taken to restore the required inoperable equipment to OPERABLE status, and a summary description of the corrective actions taken to prevent recurrence.
Brunswick Units 1 and 2 7.3.5-1 Rev. 25 Liquid Radwaste Treatment System 7.3.5 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.5.1 Verify required valve alignments to ensure Liquid Prior to release of Radwaste Treatment System is in use to reduce liquid effluents radioactive materials in liquid waste.TR 7.3.5.2 Determine the projected doses due to liquid releases 31 days from the site to UNRESTRICTED AREAS in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.5-2 Rev. 25 Liquid Holdup Tanks 7.3.6 7.3.6 LIQUID HOLDUP TANKS ODCMS 7.3.6 APPLICABILITY:
The quantity of radioactive material, excluding tritium and dissolved or entrained gases, suspended in solution in the condensate storage tank, auxiliary surge tank and outdoor temporary tank shall be maintained within limits.At all times.COMPENSATORY MEASURES r--------------------------------------------------------------------
I NOTE'Separate Condition entry is allowed for each tank.CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Quantity of radioactive A.1 Suspend addition of Immediately material in one or more of radioactive materials to the specified liquid holdup the associated tank.tanks not within limit.AND A.2 Restore quantity of 48 hours radioactive material in the tank to within limit.AND A.3 Prepare and submit in the Upon submittal of Radioactive Effluent the current Release Report, a calendar year description of the events Radioactive leading to the Effluent Release non-compliance.
Report Brunswick Units 1 and 2 7.3.6-1 Rev. 25 Liquid Holdup Tanks 7.3.6 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.6.1-----------------------------------------------
NOTE Only required to be performed when radioactive
'materials are being added to the tank.Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the condensate storage tank is < 10 Ci by analyzing a representative sample of the tank's contents.TR 7.3.6.2 NOTE'Only required to be performed when radioactive
; materials are being added to the tank.Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the auxiliary surge tank is < 10 Ci by calculation using dose measurement(s) of the tank area.TR 7.3.6.3 NOTE Only required to be performed when radioactive
'materials are being added to the tank.Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the outdoor temporary tank is _< 10 Ci by analyzing a representative sample of the tank's contents.Brunswick Units 1 and 2 7.3.6-2 Rev. 25 Dose Rate-Gaseous Effluents 7.3.7 7.3.7 DOSE RATE-GASEOUS EFFLUENTS ODCMS 7.3.7 The dose rate at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
: a. For nobles gases, _< 500 mrem per year to the total body and_< 3000 mrem per year to the skin; and b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, _< 1500 mrem per year to any organ.APPLICABILITY:
At all times.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Dose rate from the release A.1 Initiate action to restore Immediately of radioactive materials in dose rate to within limits.gaseous effluents from the site at or beyond the SITE BOUNDARY not within limits.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.7.1 Verify the dose rate due to noble gases in gaseous In accordance with effluents is within limits in accordance with the ODCM methodology and parameters in the ODCM.TR 7.3.7.2 Verify dose rate due to iodine-131, iodine-133, tritium, In accordance with and all radionuclides in particulate form with half lives Table 7.3.7-1> 8 days in gaseous effluents is within limits in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.7-1 Rev. 25 Dose Rate--Gaseous Effluents 7.3.7 Table 7-3.7-1 (page 1 of 3)Radioactive Gaseous Waste Sampling and Analysis Program GASEOUS RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS SAMPLE LOWER TYPE FREQUENCY FREQUENCY TYPE LIMIT OF DETECTION (LLD) (a)1. Drywell Purge Prior to each purge Prior to each Principal Gamma 1 x 10-4 pCi/ml Grab Sample purge Emitters (b)2. Environmental Release 31 days 31 days Principal Gamma 1 x 10-4 PCi/mI Points Grab Sample Emitters(b) (c)a. Continuous Release: H-3 (d) 1 x 10-6 pCi/ml Main Stack Reactor Building Continuous (e) 7 days (f) (g) 1-131 1 x 10-12 pCi/ml Vents Charcoal Sample Turbine Building Continuous (e) 7 days (f) (g) Principal Gamma 1 x 10-11 [iCi/ml Hot Shop h Particulate Emitters (b) (1-131, Building Vents Sample others)Continuous (e) 31 days Gross Alpha 1 x 10-11 pCi/ml Composite Particulate Sample Continuous (e) 92 days Sr-89, Sr-90 1 x 10-11 pCi/ml Composite Particulate Sample Continuous (e) Noble Gas Noble Gases, 1 x 10-6 pCi/ml Monitor Gross Beta or Gamma b. Batch Release: During RMCSB (e) Each batch 1-131 1 x 10-12 pCi/ml Radioactive operation only release: Charcoal Materials Sample Container and Storage Building During facility (e) Each batch Principle Gamma 1 x 10-11 pCi/ml Decontamination operation release: Emitters(b)
(1-131, Particulate others)Sample Facility (RMCSB)Low Level During facility (e) 31 days Gross Alpha 1 x 10-11 pCi/ml operation Composite Particulate Sample Warehouse During facility (e) 92 days Sr-89, Sr-90 1 x 10-11 pCi/ml operation Composite Particulate Sample Brunswick Units 1 and 2 7.3.7-2 Rev. 30 1 Dose Rate--Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 2 of 3)Radioactive Gaseous Waste Sampling and Analysis Program (a) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 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 c b E- V- 2.22 x 106
* Y. e Where: LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume)yb- (N/tb)"'standard deviation of background (cpm)N = background count rate (cpm)tb = time background counted for (min)E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)
Y = fractional radiochemical yield&#xfd;I= radioactive decay constant of ith nuclide (sec 1)te = elapsed time between sample collection and counting (sec)Typical values of E, V, Y, and te should be used in the calculation.
It should be recognized that the LLD is defined as an "a orio" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
Brunswick Units 1 and 2 7.3.7-3 Rev. 25 Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 3 of 3)Radioactive Gaseous Waste Sampling and Analysis Program (b) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-137, Ce-141, and Ce-144 for particulate emissions.
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.(c) With a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, or following shutdown or start-up, sampling and analyses shall also be performed unless (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2)the applicable noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.(d) If during refueling, the tritium concentration in the spent fuel pool water exceeds 2 x 10-4 piCi/ml, tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. Spent fuel pool water will be sampled at least once per 7 days during refueling.(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 ODCMS 7.3.7, 7.3.8, and 7.3.9.(f) Sample cartridges/filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).(g) Sampling shall be performed at least once per 24 hours for at least 7 days following each shutdown, start-up, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour, 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 primary coolant has not increased more than a factor of 3; and (2) the applicable noble gas monitor shows that effluent activity has not increased more than a factor of 3. This footnote does not apply to the Hot Shop environmental release point.(h) Monthly grab samples to be analyzed for principal gamma emitters and tritium are not applicable for the Hot Shop environmental release point. In addition, the Hot Shop release point does not have a noble gas monitor and, therefore, the noble gas activity analysis requirements of Table 7.3.7-1 are not applicable.
Brunswick Units 1 and 2 7.3.7-4 Rev. 30 Dose-Noble Gases 7.3.8 7.3.8 DOSE--NOBLE GASES ODCMS 7.3.8 The air dose at and beyond the SITE BOUNDARY due to noble gases in gaseous effluents from the site shall be limited to the following:
: a. < 10 mrads gamma radiation and < 20 mrads beta radiation during any calendar quarter; and b. < 20 mrads gamma radiation and _ 40 mrads beta radiation during any calendar year.APPLICABILITY:
At all times.COMPENSATORY MEASURES NOTE Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total Dose (40 CFR 190)," when gaseous effluent (noble gases) dose results in exceeding an annual total dose limit.-. .---------------------------------------------------------------------------. ..CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report 30 days r-- to the NRC that identifies NOTE causes for exceeding the SRequired Compensatory limits, corrective actions ,Measure A. 1 shall be Mtaken to reduce releases, completed if this Condition and corrective actions to Ii andcotetiercton.t is assure that subsequent releases are within limits.Calculated air dose from radioactive noble gases in gaseous effluents at or beyond the SITE BOUNDARY not within limits.Brunswick Units 1 and 2 7.3.8-1 Rev. 25 Dose-Noble Gases 7.3.8 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.8.1 Verify the cumulative dose contributions from noble 31 days gases in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.8-2 Rev. 25 Dose--I-131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 7.3.9 DOSE-l-131, 1-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM ODCMS 7.3.9 The dose to a MEMBER OF THE PUBLIC at and beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, in gaseous effluents released from the site shall be limited to the following:
: a. _ 15 mrems to any organ during any calendar quarter;b. _ 30 mrems to any organ during any calendar year; and APPLICABILITY:
At all times.COMPENSATORY MEASURES NOTE Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total[Dose (40 CFR 190)," when gaseous effluent (1-131, 1-133, tritium, radionuclides in particulate form) dose results in exceeding an annual total dose limit.CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A. 1 Submit a Special Report 30 days to the NRC that identifies NOTE causes for exceeding the i Required Compensatory Rlimits, corrective actions ,Measure A. 1 shall be Mtaken to reduce releases, completed if this Condition and corrective actions to;is entered.is-entered
.-.--------------
assure subsequent releases are within limits.Calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives
> 8 days, in gaseous effluents at or beyond the SITE BOUNDARY not within limits.Brunswick Units 1 and 2 7.3.9-1 Rev. 31 Dose--I-131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.9.1 Verify the cumulative dose contributions from 31 days iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days, in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.9-2 Rev. 25 GASEOUS RADWASTE TREATMENT SYSTEM 7.3.10 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM ODCMS 7.3.10 APPLICABILITY:
The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.
Whenever the Main Condenser Air Ejector (evacuation)
System is in operation.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. GASEOUS RADWASTE A.1 Place GASEOUS 7 days TREATMENT SYSTEM not RADWASTE in operation.
TREATMENT SYSTEM in operation.
B. B.1 Submit a Special Report 30 days r -to the NRC that identifies NOTE the required inoperable Required Compensatory equipment and the Measure B. 1 shall be reasons for the completed if this Condition inoperability, corrective is enteredactions taken to restore the required inoperable Required Compensatory equipment to OPERABLE measure and associated status, and a summary Completion Time not met. description of the corrective actions taken to prevent recurrence.
TEST REQUIREMENTS TEST FREQUENCY TR 7.3.10.1 Verify GASEOUS RADWASTE TREATMENT 12 hours SYSTEM in operation by checking the readings of the relevant instruments.
Brunswick Units 1 and 2 7.3.10-1 Rev. 25 VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM ODCMS 7.3.11 APPLICABILITY:
The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge.
During release of gaseous radioactive wastes when the projected doses due to gaseous effluent, from the site to areas at or beyond the SITE BOUNDARY, when averaged over 31 days, would exceed 0.6 mrem to any organ in a 31 day period.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report 30 days to the NRC that identifies NOTE the inoperable equipment Required Compensatory or subsystems and the o subsystem and 1tsaheb Measure A. 1 shall be reason for inoperability, completed if this Condition the corrective actions is entered.; ----- ----- ---taken to restore the inoperable equipment to Gaseous waste being OPERABLE status, and a discharged without summary description of treatment.
the corrective actions taken to prevent recurrence.
TEST REQUIREMENTS TEST FREQUENCY TR 7.3.11.1 Verify required valve alignment to ensure Prior to release of VENTILATION EXHAUST TREATMENT SYSTEM is gaseous effluents in use to reduce radioactive materials in gaseous waste.(continued)
Brunswick Units 1 and 2 7.3.11-1 Rev. 25 VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 7.3.11.2 I. .....................NOTE Only required to be performed when the!VENTILATION EXHAUST TREATMENT SYSTEM is not in use.Determine the projected doses due to gaseous 31 days releases from the site to areas at or beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.Brunswick Units 1 and 2 7.3.11-2 Rev. 25 Explosive Gas Mixture 7.3.12 7.3.12 EXPLOSIVE GAS MIXTURE ODCMS 7.3.12 APPLICABILITY:
The concentration of hydrogen in the Main Condenser Offgas Treatment System shall be _ 4% by volume.When the Main Condenser Air Ejector System is in operation.
COMPENSATORY MEASURES NOTE ODCMS 7.3.0.4 is not applicable.
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CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Hydrogen concentration in A.1 Restore hydrogen 48 hours the Main Condenser Offgas concentration to within Treatment System > 4% by limit.volume.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.12.1 Verify the concentration of hydrogen in the Main Continuously Condenser Offgas Treatment System is _< 4% by volume by monitoring waste gases with the required hydrogen monitors of ODCMS 7.3.2, "Radioactive Gaseous Effluent Monitoring Instrumentation." Brunswick Units 1 and 2 7.3.12-1 Rev. 25 Drywell VENTING or PURGING 7.3.13 7.3.13 DRYWELL VENTING OR PURGING ODCMS 7.3.13 APPLICABILITY:
The drywell shall be purged to the environment at a rate in conformance with ODCMS 7.3.7, "Dose Rate-Gaseous Effluents." When the drywell is being vented or purged.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of ODCMS A.1 Suspend VENTING and Immediately not met. PURGING of the drywell.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.13.1 Perform a sample analysis in accordance with Prior to each Table 7.3.7-1. drywell PURGE Brunswick Units 1 and 2 7.3.13-1 Rev. 25 Total Dose (40 CFR Part 190)7.3.14 7.3.14 TOTAL DOSE (40 CFR PART 190)ODCMS 7.3.14 The dose or dose commitment to any MEMBER OF THE PUBLIC over the calendar year due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to: a. <_ 25 mrems to the total body or any organ (except the thyroid);and b. _< 75 mrem to the thyroid.APPLICABILITY:
At all times.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A.NOTE Required Compensatory
:Measures A.1 and A.2 shall be completed if this Condition is entered.Calculated dose for uranium fuel cycle sources to any MEMBER OF THE PUBLIC not within limits.A.1----- -----------------------------
I; NOTE Estimates of radiation exposure from uranium fuel cycle sources shall include the effects of all effluent pathways and direct'radiation, including releases covered by this Special Report.Submit a Special Report to the NRC that includes corrective actions taken to prevent recurrence, the schedule for achieving conformance with required limits, an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC from uranium fuel cycle sources for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
30 days AND (continued)
Brunswick Units 1 and 2 7.3.14-1 Rev. 25 Total Dose (40 CFR Part 190)7.3.14 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. (continued)
A.2 NOTES 1. Only applicable if the release condition resulting in violation of 40 CFR 190 has not been corrected.
i2. Special Report submitted is considered a timely request and a variance is granted until NRC action on the request is complete.Submit a request for a 30 days variance in accordance with 40 CFR 190 in the Special Report to the NRC.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.14.1 Determine cumulative dose contributions from liquid In accordance with and gaseous effluents in accordance with TR 7.3.4.1, ODCM TR 7.3.8.1 and TR 7.3.9.1, and the methodology and parameters in the ODCM.(continued)
Brunswick Units 1 and 2 7.3.14-2 Rev. 25 Total Dose (40 CFR Part 190)7.3.14 TEST REQUIREMENTS (continued)
TEST FREQUENCY 4 TR 7.3.14.2 NOTE Only required to be performed when calculated doses from the release of radioactive materials in liquid or gaseous effluents exceed twice the limits of ODCMSs 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a., or 7.3.9.b.Determine cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks in accordance with methodology and parameters in the ODCM.In accordance with ODCM Brunswick Units 1 and 2 7.3.14-3 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ODCMS 7.3.15 The Radiological Monitoring Program shall be as follows: a. Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 7.3.15-1.b. Each sample location specified in Table 7.3.15-1 shall contain required milk or leafy vegetable samples c. The level of radioactivity as the result of plant effluents for each radionuclide in each environmental sampling medium at a required location shall be less than the limits specified in Table 7.3.15-2, when averaged over the calendar quarter;d. The total level of radioactivity as the result of plant effluents in each environmental sampling medium at a required location shall be less than the limit specified in Table 7.3.15-2, when averaged over the calendar quarter; and e. The potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides other than those in Table 7.3.15-2 in each environmental sampling medium at a required location shall be less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.APPLICABILITY:
At all times.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of--- Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, a description for Radiological Measure A.1 shall be not conducting the Environmental completed if this Condition Radiological Operating Report!is entered. Environmental Monitoring sampling and analysis One or more samples not requirements as required collected or analyzed as and the corrective actions specified in Table 7.3.15-1.
to prevent recurrence.(continued)
Brunswick Units 1 and 2 7.3.15-1 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. B. 1 Identify locations for 30 days-- obtaining replacement
* NOTES-- -- -- -- -- -- -- -- -samples and replace, in---- --- --- ---- --- ---the Radiological
: 1. Separate Condition entryhenvionmental is alowe foreachEnvironmental Monitoring Program, the location(s) sample location.
from which samples are unavailable with the new 2. Required Compensatory location(s).
Measure B.2 shall be completed if this Condition is entered. AND L -- ---- --- ---- ---- ---Upon subm ittal of B.2 Prepare and submit, in the current calendar One or more sample Radioactive Effluent year Radioactive locations required by Release Report, the cause Effluent Release Table 7.3.15-1 with required of the unavailability of Report milk or fresh leafy vegetable samples, the new samples unavailable, locations for obtaining replacement samples, and the revised figure(s) and table for the ODCM reflecting the new locations.(continued)
Brunswick Units 1 and 2 7.3.15-2 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C.* NOTES 1. Separate Condition entry* is allowed for each sample location.2. Required Compensatory Measure C.1 shall be; completed if this Condition is entered.-------------------------
One or more sample locations with the level of radioactivity for one or more radionuclides as the result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.OR One or more sample locations with the total level of radioactivity as a result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.C. 1 Submit a Special Report to the NRC which includes the cause(s) for exceeding the limit(s) and the corrective actions to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.30 days (continued)
Brunswick Units 1 and 2 7.3.15-3 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D.* NOTES 1. Separate Condition entry is allowed for each sample location.2. Required Compensatory Measures D. 1 and D.2; shall be completed if this Condition is entered.One or more sample locations with the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides other than those in Table 7.3.15-2 not within limits.D. 1 NOTE Only required if the radionuclides are the result of plant effluents.
Submit a Special Report to the NRC which includes the methodology and parameters used for estimating the potential annual dose, the cause(s)for exceeding the limit(s)and the corrective actions to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.AND D.2 NOTE Only required if the radionuclides are not the result of plant effluents.
Describe the condition in the Annual Radiological Environmental Operating Report.30 days Upon submittal of the current calendar year Annual Radiological Environmental Operating Report Brunswick Units 1 and 2 7.3.15-4 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.15.1 Verify radiological environmental monitoring samples In accordance with collected at the locations given in the table and Table 7.3.15-1 figure(s) in the ODCM and analyzed as specified in Table 7.3.15-1 are within limits. Detection capabilities for the analyses are specified in Table 7.3.15-3.Brunswick Units 1 and 2 7.3.15-5 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 1 of 5)Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a)
COLLECTION FREQUENCY FREQUENCY OF ANALYSIS Direct Radiation(b)
Forty-nine locations, either with two or 92 days Gamma dose: more dosimeters or with one or more 92 days instruments for measuring and recording dose rate continuously to be placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY as is reasonably accessible and practical.
An outer ring of stations, one in each of the meteorological sectors at distances of 8 km or greater from the site as is reasonably accessible and practical.
The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and one or two areas to serve as control stations.2. Airborne-Samples from the following locations:
Continuous sampler operation 1-131 analysis of Radioiodine and Sample collection:
7 days or radioiodine canisters:
Particulate Three samples from different as required by dust loading, 7 days sectors as close to the SITE whichever is more frequent.BOUNDARY as is reasonably AND accessible, one of which being at the highest calculated Gross beta radioactivity annual average ground level analysis of particulate D/Q. sampler: following filter change(d)One sample from the vicinity of a nearby community.
AND One sample from a control Gamma isotopic location, as for example analysis(e) of composite greater than 15 km distant (by location):
92 days and in a less prevalent wind direction(c).(continued)
Brunswick Units 1 and 2 7.3.15-6 Rev. 35 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 2 of 5)Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a)
COLLECTION FREQUENCY OF FREQUENCY ANALYSIS 3. Waterborne
: a. Surface(f)
Two locations:
Composite(')
Gamma isotopic One sample upstream.
sample collection:
31 days analysis(e):
31 days One sample downstream.
AND Tritium analysis: 92 days Four locations from Nancy's Creek Grab Samples Tritium Weekly 7 Days Composite samples for monthly gamma isotopic analysis, if gamma activity detected from plant, Sr- 89, Sr-90, Fe-55 analysis required.Eight locations from Nancy's Creek Grab Samples Tritium Weekly Marsh Areas 7 Days Composite samples for weekly gamma isotopic analysis, if gamma activity detected from plant, Sr- 89, Sr-90, Fe-55 analysis required.b. Sediment from One sample from downstream 184 days Gamma isotopic Shoreline area with existing or potential analysis(e):
184 days recreational value.One sample from Nancy's 365 days Gamma isotopic (e), Creek Area analysis 365 days c. Groundwater One sample from 10 184 days Gamma isotopic (e): Monitoring wells: 184 days 92 days Tritium: 92 days 4. Ingestion Samples from the following four With animals on pasture: Gamma isotopicie) and locations:
14 days 1-131 analyses:
14 days a. Milk One sample from milking when animals are on animals in each of three At other times: 31 days pasture locations within 8 km of the site having the highest dose AND potential (when available).(h)
Gamma isotopicie) and One sample from milking 1-131 analyses:
31 days animals at a control location at other times greater than 15 km distance from the site and in a less prevalent wind direction.(continued)
Brunswick Units 1 and 2 7.3.15-7 Rev. 35 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 3 of 5)Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a)
COLLECTION FREQUENCY OF FREQUENCY ANALYSIS 4. (continued)
: b. Fish and Samples from the following When in season: 184 days Gamma isotopic Invertebrates locations:
analysis(e) on edible portion: 184 days One sample of each of three recreationally important species in vicinity of plant discharge area (one free swimming species, one bottom feeding species, and one shellfish species).One sample of each similarly edible species from an area not influenced by plant discharge to serve as control samples.One sample of each of 365 days Gamma isotopic three recreationally analysis(e) on edible important species in portion: 365 days Nancy's Creek (one free swimming species, one bottom feeding species, and one shellfish species.)c. Broadleaf Samples from the following three When available:
31 days Gamma isotopic(e) and Vegetation locations:
1-131 analyses: 31 days when available Samples of broadleaf vegetation grown in two sectors of historically high D/Q values at the SITE BOUNDARY if milk sampling is not performed.
One sample of similar broadleaf vegetation grown at a distance of greater than 15 km from the site in a less prevalent wind direction if milk sampling is not performed.
Brunswick Units 1 and 2 7.3.15-8 Rev. 35 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 4 of 5)Radiological Environmental Monitoring Program (a) Specific parameters of distance and direction sector from the site, and additional description where pertinent, shall be provided for each and every sample location in Table 7.3.15-1 in a table and figure(s) in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).(b) 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 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.(c) The purpose of this sample is to obtain background information.
If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.(d) 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 ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.(e) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.Brunswick Units 1 and 2 7.3.15-9 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 5 of 5)Radiological Environmental Monitoring Program (f) The "upstream" sample shall be taken at a distance beyond significant influence of the discharge.
The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
Salt water shall be sampled only when the receiving water is utilized for recreational activities.(g) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. Composite samples shall be collected with equipment that is capable of collecting an aliquot at time intervals that are short (e.g., once per 6 hours) relative to compositing period (e.g., monthly) in order to assure obtaining a representative sample.(h) When less than three (3) milking animal locations are available for testing within an 8-km distance, sampling of broadleaf vegetation shall be performed as indicated in Table 7.3.15-1, 4.c, in lieu of milk sampling.Brunswick Units 1 and 2 7.3.15-10 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 ANALYSIS Table 7.3.15-2 (page 1 of 1)Limits for the Level of Radioactivity in Environmental Samples (a)WATER AIRBORNE FISH MILK (pCi/I) PARTICULATE (pCi/kg, wet) (pci/I)AND GASES (pCi/m 3)BROADLEAF VEGETATION (pCi/kg)H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 30,000 1,000 400 1,000 300 300 400 30,000 10,000 30,000 10,000 20.000 2 30 50 200 0.9 10 20 1,000 2,000 3 60 70 300 100 1,000 2,000 (a) The Limits are for samples that have only one radionuclide detected.
When a sample contains more than one radionuclide, the total level of radioactivity limit is concentration(1) limit (1)+ concentration(2)
+ .... < 1.0.limit (2)Brunswick Units 1 and 2 7.3.15-11 Rev. 26 1 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 1 of 3)Detection Capabilities for Environmental Sample Analysis (a)Lower Limit of detection (LLD) b)ANALYSIS WATER AIRBORNE FISH MILK BROADLEAF SEDIMENT (pCi/I) PARTICULATE (pCi/Kg, wet) (pCi/I) VEGETATION (pCi/kg, dry)OR GASES (pCi/m 3) (pCi/kg, wet)Gross Beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1(c) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Brunswick Units 1 and 2 7.3.15-12 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 2 of 3)Detection Capabilities for Environmental Sample Analysis (a) This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radiological Environmental Operating Report.(b) The LLD is defined for purposes of the specifications, as the smallest concentration of radioactive material in an unknown sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
LLD = 4.66yb E. V. 2.22- Y. e (Xt)Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.Cy = (N/tb)"'= ~standard deviatinn nf h-rknrnri IrnrI N tb E V 2.22 Y te= background count rate (cpm)= time background counted for (min)= counting efficiency, as counts per disintegration
= volume or mass of sample= conversion factor (dpm/pCi)= fractional radiochemical yield= radioactive decay constant of ith nuclide (sec-')= elapsed time between sampling collection and counting (sec)Brunswick Units 1 and 2 7.3.15-13 Rev. 25 Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 3 of 3)Detection Capabilities for Environmental Sample Analysis Typical values of E, V, Y, and te should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs shall 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.(c) LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCi/L may be used.Brunswick Units 1 and 2 7.3.15-14 Rev. 36 1 Land Use Census 7.3.16 7.3.16 LAND USE CENSUS ODCMS 7.3.16 A land use census shall be conducted and: a. Shall identify the location of the nearest milk animal, residence, and garden of greater than 50m 2 (500 ft 2) producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles);b. Shall identify (for elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977) the location of all milk animals and all gardens of greater than 50m 2 producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 5 km (3 miles);c. The calculated dose and dose commitment at each identified location shall be less than the most recent values calculated by TR 7.3.9.1; and d. The calculated dose and dose commitment at each identified location, via the same exposure pathways, shall be _ 120% of the actual dose and dose commitment from the current sample location identified in Table 7.3.15-1, excluding the central station location.------------------------------------------------
NOTE In lieu of the garden census of ODCMS 7.3.16.a, broadleaf vegetable sampling of at least 3 different kinds of vegetation may be performed at the SITE BOUNDARY in each of 2 different direction sectors with the highest D/Qs. Specifications for broadleaf vegetation sampling of Table 7.3.15-1 (item 4.c) shall be followed, including analysis of control samples.APPLICABILITY:
At all times.0Brunswick Units 1 and 2 7.3.16-1 Rev. 30 1 Land Use Census 7.3.16 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of--------------------------
Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, a description for Radiological Measure A.1 shall be not conducting the land Environmental completed if this Condition use census and the Operating Report is entered.,,is --- ----- ---corrective actions to prevent recurrence.
Land use census not conducted.
OR All required locations not identified.
B. B.1 Identify new location(s) in Upon submittal of-------------------------.
the Radioactive Effluent the current NOTE Release Report. calendar year Required Compensatory Radioactive Measure B.1 shall be Effluent Release completed if this Condition ,. Report , is entered.One or more identified locations with the calculated dose or dose commitment greater than the values calculated by TR 7.3.9.1.(continued)
Brunswick Units 1 and 2 7.3.16-2 Rev. 25 Land Use Census 7.3.16 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. C. 1 Add the new location to 30 days--------------------------
the R adiological NOTE Environmental Monitoring Required Compensatory Program.Measure C.1 shall be completed if this Condition AND is entered. After October 31 of C.2 Delete the sampling the year in which One or more identified location having the lowest land use census locations with the calculated calculated dose or dose was conducted dose or dose commitment, commitment, via the same via the same exposure exposure pathway, from pathway, > 120% of the the Radiological actual dose or dose Monitoring program.commitment from the current location identified in AND Table 7.3.15-1.
Upon submittal of C.3 Identify the new the current location(s) in the calendar year Radioactive Effluent Radioactive Release Report, and the Effluent Release revised figure(s) and table Report for the ODCM reflecting the new location.Brunswick Units 1 and 2 7.3.16-3 Rev. 25 Land Use Census 7.3.16 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.16.1 Conduct a land use census during the growing season 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; identify all required locations, and verify the calculated dose and dose commitments at each identified location is within limits.Brunswick Units 1 and 2 7.3.16-4 Rev. 25 Interlaboratory Comparison Program 7.3.17 7.3.17 INTERLABORATORY COMPARISON PROGRAM ODCMS 7.3.17 APPLICABILITY:
Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program approved by the NRC.At all times.COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of r Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, corrective actions Radiological Measure A.1 shall be to prevent recurrence.
Environmental completed if this Condition Operating Report is entered.Requirements of ODCMS 7.3.17 not met.TEST REQUIREMENTS TEST FREQUENCY TR 7.3.17.1 Perform the analyses required by the Interlaboratory In accordance with Comparison Program. the ODCM Brunswick Units 1 and 2 7.3.17-1 Rev. 25 Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS ODCMS 7.4.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include: a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impact of the plant operation on the environment;
: b. Results of the land use census required by ODCMS 7.3.16;c. A summary description of the radiological environmental monitoring program;d. At least two legible maps of all sampling locations keyed to a table giving distances and directions from the centerline of one reactor (one map shall cover stations near the SITE BOUNDARY and the second map shall include more distant stations);
: e. Results of the Interlaboratory Comparison Program required by ODCMS 7.3.17;f. Discussion of all deviations from the sampling schedule of Table 7.3.15-1; and g. Discussion of all analyses in which the LLD required by Table 7.3.15-3 was not achievable.
ODCMS 7.4.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the Radioactive Effluent Release Report shall include: (continued)
Brunswick Units 1 and 2 7.4.0-1 Rev. 25 Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)
ODCMS 7.4.2 Radioactive Effluent Release Report (continued)
: a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released for the facility as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis similar to the format of Appendix B thereof.b. Information specified below for each class of solid waste (as defined by 10 CFR Part 61, when implemented) shipped offsite during the report period: 1. Container volume;2. Total curie quantity (specify whether determined by measurement or estimate);
: 3. Principal radionuclides (specify whether determined by measurement or estimate);
: 4. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms);5. Type of container (e.g., LSA, Type A, Type B, Large Quantity);
and 6. Solidification agent or absorbent (e.g., cement, urea formaldehyde).
: c. A list and description of unplanned releases from the site to the UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.d. Any changes made during the reporting period to the Process Control Program (PCP) or the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to ODCMS 7.3.16.(continued)
Brunswick Units 1 and 2 7.4.0-2 Rev. 25 Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)
ODCMS 7.4.2 Radioactive Effluent Release Report (continued)
: e. An annual summary of hourly meteorological data collected over the previous calendar 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 of this summary of required meteorological data with the Radioactive Effluent Release Report, the summary of required meteorological data may be retained in a file that shall be provided to the NRC upon request.f. An assessment of radiation doses due to radioactive liquid and gaseous effluents released from the station during the previous calendar year.g. The Radioactive Effluent Release Report shall include results from any groundwater samples obtained in accordance with the Radiological Environmental Monitoring Program during the reporting period that are not described in the ODCM.h. The Radioactive Effluent Release Report shall include any assigned doses that were performed as a result of a spill or leak from the site that occurred during the reporting period.The Radioactive Effluent Release Report shall include a summary of any on-site spills and leaks that occurred during the reporting period that were communicated to offsite agencies.Brunswick Units 1 and 2 7.4.0-3 Rev. 30 1 Major Changes to Radioactive Waste Treatment Systems 7.5.0 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ODCMS 7.5.1 Licensee initiated major changes to the liquid, gaseous, and solid Radioactive Waste Treatment Systems shall be reported to the NRC as part of the Radioactive Effluent Release Report or as part of the annual UFSAR update. 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 10 CFR Part 50.59;b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
: c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;d. An evaluation of the change that shows the predicted release of radioactive materials in the liquid and gaseous effluents and quantity of solid waste differ from those previously predicted in the license application and amendments thereto;e. An evaluation of the change that shows the expected maximum exposure to an individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid wastes, to the actual releases for the period prior to when the changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change; and h. Documentation of the fact that the change was reviewed and found acceptable by the PNSC.ODCMS 7.5.2 The change shall become effective upon review and acceptance by the PNSC.Brunswick Units 1 and 2 7.5.0-1 Rev. 25 ODCMS Applicability B 7.3.0 B 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)APPLICABILITY BASES ODCMSs ODCMS 7.3.0.1 through ODCMS 7.3.0.6 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.ODCMS 7.3.0.1 ODCMS 7.3.0.1 establishes the Applicability statement within each individual ODCMS as the requirement for when the ODCMS is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each ODCMS).ODCMS 7.3.0.2 ODCMS 7.3.0.2 establishes that upon discovery of a failure to meet an ODCMS, the associated COMPENSATORY MEASURES shall be met.The Completion Time of each Required Compensatory Measure for a COMPENSATORY MEASURES Condition is applicable from the point in time that a COMPENSATORY MEASURES Condition is entered. The Required Compensatory Measures establish those remedial measures that must be taken within specified Completion Times when the requirements of an ODCMS are not met. This ODCMS establishes that: a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with an ODCMS; and b. Completion of the Required Compensatory Measures is not required when an ODCMS is met within the specified Completion Time, unless otherwise specified.
There are two basic types of Required Compensatory Measures.
The first type of Required Compensatory Measure specifies a time limit in which the ODCMS must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Compensatory Measure is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the ODCMS is not applicable. (Whether stated as a Required Compensatory Measure or not, correction of the entered (continued)
Brunswick Units 1 and 2 B 7.3.0-1 Rev. 25 ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Condition is a compensatory measure that may always be considered (continued) upon entering COMPENSATORY MEASURES.)
The second type of Required Compensatory Measure specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Compensatory Measures provides an acceptable level of safety for continued operation.
Completing the Required Compensatory Measures is not required when an ODCMS is met or is no longer applicable, unless otherwise stated in the individual ODCMSs.The nature of some Required Compensatory Measures of some Conditions necessitates that, once the Condition is entered, the Required Compensatory Measures must be completed even though the associated Condition no longer exists. The individual ODCMS's COMPENSATORY MEASURES specify the Required Compensatory Measures where this is the case.The Completion Times of the Required Compensatory Measures are also applicable when a system or component is removed from service intentionally.
The reasons for intentionally relying on the COMPENSATORY MEASURES include, but are not limited to, performance of Tests, preventive maintenance, corrective maintenance, or investigation of operational problems.
Entering COMPENSATORY MEASURES for these reasons must be done in a manner that does not compromise safety. Intentional entry into COMPENSATORY MEASURES should not be made for operational convenience.
Alternatives that would not result in redundant equipment being inoperable should be used instead. Doing so limits the time both subsystems/
divisions of a safety function are inoperable.
Individual ODCMSs may specify a time limit for performing a TR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Compensatory Measures are applicable when this time limit expires, if the equipment remains removed from service or bypassed.When a change in MODE or other specified condition is required to comply with Required Compensatory Measures, the unit may enter a MODE or other specified condition in which another ODCMS becomes applicable.
In this case, the Completion Times of the associated (continued)
Brunswick Units 1 and 2 B 7.3.0-2 Rev. 25 ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Required Compensatory Measures would apply from the point in time (continued) that the new ODCMS becomes applicable and the COMPENSATORY MEASURES Condition(s) are entered.ODCMS 7.3.0.3 Not used.ODCMS 7.3.0.4 ODCMS 7.3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an ODCMS is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist: a. Unit conditions are such that the requirements of the ODCMS would not be met in the Applicability desired to be entered; and b. Continued noncompliance with the ODCMS requirements, if the Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the Required Compensatory Measures.Compliance with Required Compensatory Measures that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation.
This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Compensatory Measures.The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before unit startup.The provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES.
In addition, the provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.(continued)
Brunswick Units 1 and 2 B 7.3.0-3 Rev. 25 ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.4 (continued)
Exceptions to ODCMS 7.3.0.4 are stated in the individual Tests.Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of an ODCMS.Tests do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by TR 7.3.0.1. Therefore, changing MODES or other specified conditions while in a COMPENSATORY MEASURES Condition, either in compliance with ODCMS 7.3.0.4 or where an exception to ODCMS 7.3.0.4 is stated, is not a violation of TR 7.3.0.1 or TR 7.3.0.4 for those Tests that do not have to be performed due to the associated inoperable equipment.
However, TRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected ODCMS.ODCMS 7.3.0.5 ODCMS 7.3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with COMPENSATORY MEASURES.
The sole purpose of this ODCMS is to provide an exception to ODCMS 7.3.0.2 (e.g., to not comply with the applicable Required Compensatory Measure(s))
to allow the performance of TRs to demonstrate:
: a. The OPERABILITY of the equipment being returned to service; or b. The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the COMPENSATORY MEASURES is limited to the time absolutely necessary to perform the allowed TRs. This ODCMS does not provide time to perform any other preventive or corrective maintenance.
An example of demonstrating the OPERABILITY of the equipment being returned to service is taking an inoperable channel or trip system out of the tripped condition after it has been tripped to comply with Required Compensatory Measures since it must be untripped to perform the TRs.(continued)
Brunswick Units 1 and 2 B 7.3.0-4 Rev. 25 ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.5 (continued)
An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of a TR on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a TR on another channel in the same trip system.ODCMS 7.3.0.6 ODCM 7.3.0.6 delineates the applicability of each ODCMS and associated COMPENSATORY MEASURE to Brunswick Unit 1 and Brunswick Unit 2 operations.
Brunswick Units 1 and 2 B 7.3.0-5 Rev. 25 TR Applicability B 7.3.0 B 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY BASES TRs TR 7.3.0.1 through TR 7.3.0.5 establish the general requirements applicable to all ODCMSs and apply at all times, unless otherwise stated.TR 7.3.0.1 TR 7.3.0.1 establishes the requirement that TRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the ODCMS apply, unless otherwise specified in the individual TRs. This ODCMS is to ensure that Tests are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Test within the specified Frequency, in accordance with TR 7.3.0.2, constitutes a failure to meet an ODCMS.Systems and components are assumed to be OPERABLE when the associated TRs have been met. Nothing in this ODCMS, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the TRs; or b. The requirements of the Test(s) are known to be not met between required Test performances.
Tests do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated ODCMS are not applicable, unless otherwise specified.
Tests, including Tests invoked by Required Compensatory Measures, do not have to be performed on inoperable equipment because the COMPENSATORY MEASURES define the remedial measures that apply. Tests have to be met and performed in accordance with TR 7.3.0.2, prior to returning equipment to OPERABLE status.Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE.
This includes ensuring applicable Tests are not failed and their most recent performance is in accordance with TR 7.3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the (continued)
Brunswick Units 1 and 2 B 7.3.0-6 Rev. 25 TR Applicability B 7.3.0 BASES TR 7.3.0.1 (continued)
Applicability due to the necessary unit parameters not having been established.
In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function.
This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
TR 7.3.0.2 TR 7.3.0.2 establishes the requirements for meeting the specified Frequency for Tests and any Required Compensatory Measure with a Completion Time that requires the periodic performance of the Required Compensatory Measure on a "once per..." interval.TR 7.3.0.2 permits a 25% extension of the interval specified in the Frequency.
This extension facilitates Test scheduling and considers plant operating conditions that may not be suitable for conducting the Test (e.g., transient conditions or other ongoing Test or maintenance activities).
The 25% extension does not significantly degrade the reliability that results from performing the Test at its specified Frequency.
This is based on the recognition that the most probable result of any particular Test being performed is the verification of conformance with the TRs.As stated in TR 7.3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance.
The initial performance of the Required Compensatory Measure, whether it is a particular Test or some other remedial action, is considered a single compensatory measure with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such a compensatory measure may verify that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.(continued)
Brunswick Units 1 and 2 B 7.3.0-7 Rev. 25 TR Applicability B 7.3.0 BASES TR 7.3.0.2 The provisions of TR 7.3.0.2 are not intended to be used repeatedly (continued) merely as an operational convenience to extend Test intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.
TR 7.3.0.3 TR 7.3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Test has not been completed within the specified Frequency.
A delay period of up to 24 hours or up to the limit of the specified Frequency, whichever is less, applies from the point in time that it is discovered that the Test has not been performed in accordance with TR 7.3.0.2, and not at the time that the specified Frequency was not met.This delay period provides adequate time to complete Tests that have been missed. This delay period permits the completion of a Test before complying with Required Compensatory Measures or other remedial measures that might preclude completion of the Test.The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Test, the safety significance of the delay in completing the required Test, and the recognition that the most probable result of any particular Test being performed is the verification of conformance with the requirements.
When a Test with a Frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, TR 7.3.0.3 allows the full delay period of 24 hours to perform the Test.TR 7.3.0.3 also provides a time limit for completion of Tests that become applicable as a consequence of MODE changes imposed by Required Compensatory Measures.(continued)
Brunswick Units 1 and 2 B 7.3.0-8 Rev. 25 TR Applicability B 7.3.0 BASES TR 7.3.0.3 (continued)
Failure to comply with specified Frequencies for TRs is expected to be an infrequent occurrence.
Use of the delay period established by TR 7.3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Test intervals.
If a Test is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon expiration of the delay period. If a Test is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon the failure of the Test.Completion of the Test within the delay period allowed by this ODCMS, or within the Completion Time of the COMPENSATORY MEASURES, restores compliance with TR 7.3.0.1.TR 7.3.0.4 TR 7.3.0.4 establishes the requirement that all applicable TRs must be met before entry into a MODE or other specified condition in the Applicability.
This ODCMS ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.However, in certain circumstances failing to meet a TR will not result in TR 7.3.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated TR(s)are not required to be performed, per TR 7.3.0.1, which states that Tests do not have to be performed on inoperable equipment.
When equipment is inoperable, TR 7.3.0.4 does not apply to the associated TR(s) since the requirement for the TR(s) to be performed is removed. Therefore, failing to perform the Test(s) within the specified Frequency does not result in a (continued)
Brunswick Units 1 and 2 B 7.3.0-9 Rev. 25 TR Applicability B 7.3.0 BASES TR 7.3.0.4 TR 7.3.0.4 restriction to changing MODES or other specified conditions of (continued) the Applicability.
However, since the ODCMS is not met in this instance, ODCMS 7.3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.The provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES.
In addition, the provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.The precise requirements for performance of TRs are specified such that exceptions to TR 7.3.0.4 are not necessary.
The specific time frames and conditions necessary for meeting the TRs are specified in the Frequency, in the Test, or both. This allows performance of Tests when the prerequisite condition(s) specified in a Test procedure require entry into the MODE or other specified condition in the Applicability of the associated ODCMS prior to the performance or completion of a Test. A Test that could not be performed until after entering the ODCMS Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Test may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of TRs' annotation is found in ODCMS Section 7.1.4, Frequency.
TR 7.3.0.5 TR 7.3.0.5 delineates the applicability of the test activities to Brunswick Unit 1 and Brunswick Unit 2 operations.
Brunswick Units 1 and 2 B 7.3. 0-10 Rev. 25 Radioactive Liquid Effluent Monitoring Instrumentation B 7.3.1 B 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that, if not controlled, could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.The initial CHANNEL CALIBRATION for the Table 7.3.1-1, Functions 1 and 3, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for the initial requirement.
Subsequent to CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.
The ODCMS are modified by a Note to indicate that the annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability.
Upon completion of troubleshooting, or expiration of the 30 minute allowance, the annunciator must be returned to operation or the applicable condition entered and required Compensatory Measures taken. Appropriate compensatory actions should be determined an implemented during the loss of annunciator function.
This note is based on the availability of the associated monitor and appropriate compensatory actions to identify changes in the liquid effluent for the monitored location.
The monitor availability and compensatory actions ensure that the 30 minute trouble shooting allowance does not significantly reduce the probability of identifying the changing radiological conditions to allow appropriate response.Brunswick Units 1 and 2 B 7.3. 1-1 Rev. 29 1 Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 B 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.The main condenser air ejector monitoring instrumentation, the main condenser offgas treatment system monitor, and the explosive gas monitoring instrumentation shown in Table 7.3.2-1 are not considered effluent monitoring instrumentation in the same sense as the other instrumentation listed in the table. Therefore, their alarm/trip setpoints are not necessarily set to ensure that the limits of ODCMS 7.3.7 are not exceeded.The main condenser air ejector monitoring instrumentation channels 1(2)-D12-RM-K601A and 1(2)-D12-RM-K601B are provided to monitor and control gross radioactivity removed from the main condenser.
The alarm/trip setpoints for the main condenser air ejector monitors are set to ensure that the limits of Technical Specification 3.7.5 are not exceeded.
The alarms alert the operator that an abnormal condition exists. Operability of the Hi and Hi Hi alarms are required for satisfying the main condenser air ejector monitoring instrumentation channel function.
The trip function associated with the monitors, initiates when any combination of HI-HI, downscale, or INOP is received on both monitors.
The trip function associated with the monitors initiates the off-gas timer which, after 15 minutes, initiates closure of 1(2)-AOG-HCV-102 and the Loop Seal Reservoir Drain Valve. Operability of the 1(2)-AOG-HCV-102 and Loop Seal Reservoir Drain Valve are not required for operability of the main condenser air ejector monitoring instrumentation.
The alarm/trip setpoint for this monitor shall be calculated in accordance with NRC approved methods to provide reasonable assurance that the potential total body accident dose will not exceed a fraction of the limits specified in 10 CFR Part 100.This specification also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the offgas treatment system (hydrogen monitors).
The initial CHANNEL CALIBRATION for the Table 7.3.2-1, Functions 1.a, 2.a, 3.a, 4 and 6, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for the initial requirement.
Subsequent CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.(continued)
Brunswick Units 1 and 2 B 7.3.2-1 Rev. 33 1 Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 BASES Regulatory Guide 1.21 requires continuous sampling of iodine and particulate in gaseous effluents and subsequent analysis at least weekly. However, a short downtime period of the sample devices is necessary to accomplish applicable ODCM test requirements, sample analysis, or system purging. This time will be accounted for in sample volume calculations.
As such, 45 minutes is provided to initiate the auxiliary sampling system or restore the normal sampling devices to OPERABLE status.Reference ODCMS 7.3.0.5 and B 7.3.0.5 for the performance of post maintenance testing.Upon identification of a loss of radioactive gaseous effluent monitoring instrumentation, steps shall be taken immediately to install auxiliary sampling.
If this cannot be accomplished, releases via the associated effluent pathway shall be secured. Any monitor downtime will be accounted for in sample volume calculations.
The ODCMS are modified by a note to indicate that the annunciator function may be removed from operation for performance of trouble shooting for up to 30 minutes provided the associated function maintains monitoring capability.
Upon completion of the troubleshooting, or expiration of the 30 minute allowance, the annunciator must be returned to operation or the applicable condition entered and Required Compensatory Measures taken. Appropriate compensatory actions should be determined and implemented during the loss of annunciator function.
Since the 1/2-CAC-AT-1264 alarm is used as an EAL entry condition, removal of the 1/2-CAC-AT-1264 annunciator for 30 minutes for troubleshooting is prohibited when there are any fuel handling activities on the refuel floor or activities where there is the potential to cause a decrease in spent fuel pool water level. This Note is based on the availability of the associated monitor and appropriate compensatory actions to identify changes in the gaseous effluent for the monitored location.
The monitor availability and compensatory actions ensure that the 30 minute troubleshooting allowance does not significantly reduce the probability of identifying the hanging radiological conditions to allow appropriate response.Brunswick Units 1 and 2 B 7.3.2-2 Rev. 33 1 Concentration-Liquid Effluents B 7.3.3 8 7.3.3 CONCENTRATION-LIQUID EFFLUENTS BASES This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS after dilution in the discharge canal will be less than or equal to 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 for radionuclides other than dissolved and entrained noble gases. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will not result in exposures within (1) the Section II.A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1302(b)(2)(i) to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP), Publication 2.The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the Lower Limits of Detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manuals, HASL-300 (revised annually), Currie, L. A. "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).Note that for batch releases, recirculation of at least two tank volumes shall be considered adequate for thorough mixing.The service water liquid release represents a potential release pathway and not an actual release pathway. Test of this pathway is intended to alert the plant to a potential problem;analysis for principal gamma emitters is sufficient to meet this intent. If analysis for principal gamnma emitters indicates a problem (i.e., exceeds the trigger level of 5x10-6 ACi/ml), then complete sampling and analyses shall be performed as per Table 7.3.3-2. The trigger level of 5x1 0-6 lCi/ml was chosen as being sufficient to provide reasonable assurance of accountability of all nuclides released based upon lower limits of detection and expected concentrations.
Brunswick Units 1 and 2 B 7.3.3-1 Rev. 35 Dose-Liquid Effluents B 7.3.4 B 7.3.4 DOSE-LIQUID EFFLUENTS BASES This specification is provided to implement the requirements of Sections IL.A, lIl.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.4 implements the guides set forth in Section II.A of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of 10 CFR Part 50 to assure that releases of radioactive material in liquid effluents to UNRESTRICTED AREAS 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 a MEMBER OF THE PUBLIC 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.The dose or dose commitment to a MEMBER OF THE PUBLIC is based on the 10 CFR Part 50, Appendix I, guideline of: a. 1.5 mrem to the total body and 5.0 mrem to any organ during any calendar quarter, and b. 3 mrem to the total body and 10 mrem to any organ during any calendar year, from radioactive material in liquid effluents from each reactor unit to UNRESTRICTED AREAS.This specification is written for a two unit site.Brunswick Units 1 and 2 B 7.3.4-1 Rev. 25 Liquid Radwaste Treatment System B 7.3.5 B 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM BASES The requirement that 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 Criteria 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1, 10 CFR Part 50, for liquid effluents.
Mechanical filtration as per system design is considered to be an appropriate component of the Liquid Radwaste Treatment System.The requirements of 0.12 mrem total body or 0.4 mrem to any organ in a 31-day period is based on two reactor units having a shared Liquid Radwaste Treatment System.Brunswick Units 1 and 2 B 7.3.5-1 Rev. 25 Liquid Holdup Tanks B 7.3.6 B 7.3.6 LIQUID HOLDUP TANKS BASES The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.Since the condensate storage tanks have continuous influent and effluent, stratification should not occur. Samples taken from the operating condensate transfer pump(s) vent or drain shall be deemed representative of this system.Appropriate alternatives to the COMPENSATORY MEASURES and TEST REQUIREMENTS are acceptable if they provide reasonable assurance that in the event of an uncontrolled release of the tank's content, the resulting concentrations would be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.Brunswick Units 1 and 2 B 7.3.6-1 Rev. 25 Dose Rate--Gaseous Effluents B 7.3.7 B 7.3.7 DOSE RATE-GASEOUS EFFLUENTS BASES This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of Appendix I to 10 CFR part 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.
It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR part 50.For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
This specification does not affect the requirements to comply with the annual limitations of 10 CFR 20.1301.This specification applies to the release of gaseous effluents from all reactors at the site.With regard to footnotes (c) and (g) of Table 7.3.7-1: 1. The sampling is only required following transients when the primary coolant DEI and the applicable noble gas monitor increase by a factor of 3.2. To determine whether the Dose Equivalent 1-131 concentration in the primary coolant has increased by more than a factor of 3, the iodine-131 analysis performed after the transient will be compared to the most recent routine analysis for Dose Equivalent 1-131 concentration performed before the transient.
: 3. To determine whether the effluent noble gas monitor has increased by more than a factor of 3, the activity indicated on the monitor's chart recorder after the transient will be compared to the activity indicated on the recorder just before the transient occurred.4. The intent of footnote (c) is to determine the impact of the transient on the isotopic mix release for the applicable effluent pathway.5. Sampling described in footnote (g) shall be performed on the applicable effluent pathways.
For example, a Unit 1 transient could potentially result in sampling the Stack, Unit 1 Reactor Vent, and the Unit 1 Turbine Building Vent. Each of these pathways should be included in the evaluation.
Actual sampling will only be performed on the path or pathways that meet the factor of 3 increase criteria.6. The intent of the sampling is to evaluate the impact on particulate and iodine releases during the transient.
The sampling can be exited when both entry conditions (DEI and noble gas monitor) have returned to steady-state levels below a factor of 3 change or after 7 days, whichever condition comes first.The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the Lower Limits of Detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "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).Brunswick Units 1 and 2 B 7.3.7-1 Rev. 30 1 Dose Rate-Noble Gases B 7.3.8 B 7.3.8 DOSE -NOBLE GASES BASES This specification is provided to implement the requirements of Sections II.B, IlIl.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.8 implements the guides set forth in Section 11.B of Appendix I. The COMPENSATORY MEASURES 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 to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The TEST 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 a MEMBER OF THE PUBLIC 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 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 provided for determining the air doses at and beyond the SITE BOUNDARY will be based upon the historical annual average atmospheric conditions.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.Brunswick Units 1 and 2 B 7.3.8-1 Rev. 30 1 Dose -Iodine-1 31, Iodine-1 33, Tritium, and Radionuclides in Particulate Form B 7.3.9 B 7.3.9 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM BASES This specification is provided to implement the requirements of Section II.C, Ilil.A, and IV.A of Appendix 1, 10 CFR Part 50. ODCMS 7.3.9 implements the guides set forth in Section II.C of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the TEST REQUIREMENTS 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 a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods 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,"Calculating 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 specification for iodine-131, iodine-133, tritium, and radioactive material in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.
The pathways which are examined in the development of these calculations are: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.* The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.Brunswick Units 1 and 2 B 7.3.9-1 Rev. 31 GASEOUS RADWASTE TREATMENT SYSTEM B 7.3.10 B 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM BASES This requirement 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 the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The GASEOUS RADWASTE TREATMENT SYSTEM refers to the 30-minute offgas holdup line, stack filter house filtration, and the Augmented Off-Gas-Treatment System.Brunswick Units 1 and 2 B 7.3. 10-1 Rev. 25 VENTILATION EXHAUST TREATMENT SYSTEM B 7.3.11 B 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM BASES This requirement 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 the design objectives given in Section IL.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.
At the Brunswick Steam Electric Plant, the only VENTILATION EXHAUST TREATMENT SYSTEMS shall be those installed for the Turbine Buildings' ventilation.
Brunswick Units 1 and 2 B 7.3.11-1 Rev. 25 Explosive Gas Mixture B 7.3.12 B 7.3.12 EXPLOSIVE GAS MIXTURE BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen.
Maintaining the concentration of hydrogen below the flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.Brunswick Units 1 and 2 B 7.3.12-1 Rev. 25 Drywell VENTING or PURGING B 7.3.13 B 7.3.13 DRYWELL VENTING or PURGING BASES This specification provides reasonable assurance that releases from drywell VENTING or PURGING operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.Brunswick Units 1 and 2 B 7.3.13-1 Rev. 25 Total Dose (40 CFR Part 190)B 7.3.14 B 7.3.14 TOTAL DOSE (40 CFR PART 190)BASES This specification is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 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 if the individual reactors remain within the reporting requirement level. 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.
If the 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 Part 190.11 and 10 CFR Part 20.2203(a)(4) 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 ODCMSs 7.3.3 through 7.3.14. 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.Brunswick Units 1 and 2 B 7.3.14-1 Rev. 25 Radiological Environmental Monitoring Program B 7.3.15 B 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES The radiological environmental monitoring program required by this specification provides 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 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 are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways.The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limits of Detection (LLDs). The LLDs required by Table 7.3.15-3 are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD and other detection limits can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry" Anal. Chem 40, 586-93 (1968), and Hartwell, L. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).Groundwater is not monitored by this specification because plant liquid effluents are not tapped as a source for drinking or irrigation purposes.In the absence of the availability of leafy vegetables intended for human consumption, sampling of indigenous broadleaf vegetation may be performed since the objective of sampling broadleaf vegetation (i.e., to approximate fallout from plant operation) is satisfied in either case.Brunswick Units 1 and 2 B 7.3.15-1 Rev. 25 Land Use Census B 7.3.16 B 7.3.16 LAND USE CENSUS BASES This specification is provided to ensure that changes in the use of the area at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made, if required, as a result of the census. The best information from door-to-door surveys, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine the minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broadleaf vegetation (i.e., similar to lettuce and cabbage; and (2) a vegetation yield of 2 kg/m 2 Brunswick Units 1 and 2 B 7.3.16-1 Rev. 25 Interlaboratory Comparison Program B 7.3.17 B 7.3.17 INTERLABORATORY COMPARISON PROGRAM BASES The requirement for participation in the Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.Brunswick Units 1 and 2 B 7.3.17-1 Rev. 25 LIST OF TABLES Title Table No.APPENDIX A A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 A-i 1 A-12 A-13 A-14 PaQe X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE T U R B IN E B U ILD IN G S ...............................................................................
A -5 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FRO M THE TURBINE BUILDING S ............................................................
A-6 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE T U R B IN E B U ILD IN G S ...............................................................................
A -7 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM T H E T U R BIN E BU ILD IN G S .......................................................................
A -8 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS
........................................
A-9 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDING S ................................................................
A-10 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTO R BUILDING S .......................................................................
A-11 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS
....................................................
A-12 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTO R BUILDING S .......................................................................
A-13 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
...............................................................
A-14 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
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A-15 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS
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A-16 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE S T A C K ..............................................................................................
..A -17 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FR O M TH E STA C K .............................................................................
A-18 ODCM (BSEP)A-1 Rev. 30 LIST OF TABLES (Cont'd)Title Table No.APPENDIX A A-15 A-16 A-17 A-18 A-19 A-20 Paqe D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE S T A C K .....................................................................................................
A -1 9 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM T H E S T A C K .............................................................................................
A -2 0 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FRO M THE STACK ..............................................................
A-21 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM T H E S T A C K .............................................................................................
A -2 2 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ" PROGRAM .................
A-23 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC "XOQDOQ" PROGRAM ...........
A-26 ODCM (BSEP)A-2 Rev. 30 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) engaged the services of Dames and Moore to assess the transport and dispersion of the effluent in the atmosphere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide (RG) 1.111, Revision 1 (USNRC, 1977). The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted)based on numerical models acceptable for use in Appendix I evaluations.
Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations.
These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach).
It was resolved that for operational efficiency, the straight line described in XOQDOQ Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (Draft), NUREG 0324 (USNRC, September 1977)would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant site, terrain/ recirculation correction factors (TCF) were to be determined from a combined puff-advection/straight-line scheme for a one-year meteorological data base.In 2005, Murray and Trettel utilized a five-year record of meteorological data from the on-site meteorological program at the Brunswick Steam Electric Plant. This data consisted of all collected parameters at both the 10-meter and 103-meter tower levels for the years 2000 through 2004.Tables A-1 through A-6 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground-level release for both standard distances and special locations.
Tables A-7 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for mixed-mode release for both standard distances and special locations.
ODCM (BSEP)A-3 Rev. 30 1 Tables A-13 through A-18 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for elevated release for both standard distances and special locations.
Values for y/Q, depleted X/Q, and D/Q for releases to special locations are from the standard distance tables. The values used are from the distance nearest the special location in the appropriate sector.Operation Computations The NRC "XOQDOQ" Program (Revision
: 1) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest without a terrain/recirculation factor. The input to"XOQDOQ" for ground-level releases are presented in Table A-19 and for elevated releases in Table A-20. The resulting computations will have applied the TCFs to produce a final atmospheric diffusion estimate for the site.In general, it is concluded that the straight-line model is as reasonable a projection of concentrations as the puff-advection model. By inclusion of the terrain correction factors developed by a combination of the puff-advection/straight-line scheme with the results of the XOQDOQ Program, ready evaluation of on-site meteorological data may be made.Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Specifications:
Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Brunswick Facility, Dames and Moore, January 18, 1979.ODCM (BSEP)A-4 Rev. 30 1 TABLE A-1 X/Q Values at the Special Locations for Releases From the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Concentration (Sec./Cubic Meter)Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Site Boundary Dairy* Meat* Resident*
Garden*Sector NNE 1.7E-06 0. 7.9E-07 7.9E-07 7.9E-07 4.3E-06 3.2E-07 0. 0. 0.ENE 6.OE-06 0. 0. 0. 0.E 6.OE-06 0. 2.8E-06 2.8E-06 0.ESE 6.3E-06 0. 6.3E-06 1.8E-06 1.8E-06 SE 8.9E-06 0. 8.9E-06 8.9E-06 0.SSE 1.5E-05 0. 1.5E-05 1.5E-05 1.5E-05 S 9.4E-06 0. 0. 4.4E-06 2.8E-06 SSW 4.4E-06 0. 2.1 E-06 2.1 E-06 2.1 E-06 SW 2.8E-06 0. 2.8E-06 2.8E-06 2.8E-06 WSW 1.9E-06 0. 5.5E-07 8.9E-07 8.9E-07 W 1.3E-06 0. 0. 1.3E-06 1.3E-06 WNW 1.2E-06 0. 0. 1.2E-06 1.2E-06 NW 1.3E-06 0. 0. 1.3E-06 1.3E-06 NNW 1.7E-06 0. 0. 1.7E-06 1.7E-06 N 1.5E-06 0. 0. 1.5E-06 1.5E-06*A zero indicates that this point was not calculated.
ODCM (BSEP) A-5 Rev. 30 TABLE A-2 Depleted X/Q Values at the Special Locations for Releases From the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Depleted Concentration (Sec./Cubic Meter)Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Site Dairy* Meat* Resident*
Garden*Sector Boundary NNE 1.5E-06 0. 6.7E-07 6.7E-07 6.7E-07 NE 3.8E-06 2.3E-07 0. 0. 0.ENE 5.3E-06 0. 0. 0. 0.E 5.3E-06 0. 2.4E-06 2.4E-06 0.ESE 5.6E-06 0. 5.6E-06 1.5E-06 1.5E-06 SE 7.9E-06 0. 7.9E-06 7.9E-06 0.SSE 1.3E-05 0. 1.3E-05 1.3E-05 1.3E-05 S 8.3E-06 0. 0. 3.8E-06 2.3E-06 SSW 3.9E-06 0. 1.8E-06 1.8E-06 1.8E-06 SW 2.5E-06 0. 2.5E-06 2.5E-06 2.5E-06 WSW 1.7E-06 0. 4.6E-07 7.6E-07 7.6E-07 W 1.2E-06 0. 0. 1.2E-06 1.2E-06 WNW 1.1E-06 0. 0. 1.1 E-06 1.1 E-06 NW 1.1E-06 0. 0. 1.1E-06 1.1E-06 NNW 1.5E-06 0. 0. 1.5E-06 1.5E-06 N 1.3E-06 0. 0. 1.3E-06 1.3E-06*A zero indicates that this point was not calculated.
ODCM (BSEP) A-6 Rev. 30 TABLE A-3 D/Q Values at the Special Locations for Releases From the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Deposition (Meter**-2)
Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Sector Site Boundary Dairy* Meat* Resident*
Garden*NNE 7.2E-09 0. 3.0E-09 3.OE-09 3.OE-09 NE 1.8E-08 7.2E-10 0. 0. 0.ENE 7.6E-09 0. 0. 0. 0.E 4.3E-09 0. 1.8E-09 1.8E-09 0.ESE 4.5E-09 0. 4.5E-09 1.OE-09 1.OE-09 SE 6.3E-09 0. 6.3E-09 6.3E-09 0.SSE 8.6E-09 0. 8.6E-09 8.6E-09 8.6E-09 S 9.2E-09 0. 0. 3.8E-09 2.1E-09 SSW 7.5E-09 0. 3.1E-09 3.1E-09 3.1E-09 SW 7.1 E-09 0. 7.1 E-09 7.1E-09 7.1 E-09 WSW 5.1E-09 0. 1.2E-09 2.1E-09 2.1E-09 W 3.2E-09 0. 3.2E-09 3.2E-09 3.2E-09 WNW 2.5E-09 0. 2.5E-09 2.5E-09 2.5E-09 NW 2.7E-09 0. 2.7E-09 2.7E-09 2.7E-09 NNW 3.OE-09 0. 3.OE-09 3.OE-09 3.OE-09 N 3.9E-09 0. 3.9E-09 3.9E-09 3.9E-09*A zero indicates that this point was not calculated.
ODCM (BSEP)A-7 Rev. 30 1 -
TABLE A-4 7/Q Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Concentration (Sec./Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.OE-05 3.2E-06 1.7E-06 1.1E-06 7.9E-07 6.OE-07 4.9E-07 4.1E-07 3.OE-07 2.3E-07 1.9E-07 1.6E-07 1.3E-07 1.2E-07 NE 0. 2,6E-05 8.2E-06 4,3E-06 2,8E-06 2,OE-06 1.5E-06 1I2E-06 1,OE-06 7.6E-07 6,0E-07 4.8E-07 4.OE-07 3.4E-07 3.2E-07 ENE 0. 4.OE-05 1.2E-05 6.OE-06 3.9E-06 2.8E-06 2.2E-06 1.8E-06 1.5E-06 1.1E-06 9.OE-07 7.4E-07 6.2E-07 5.3E-07 5.OE-07 E 0. 4.1E-05 1.2E-05 6.OE-06 3.9E-06 2.8E-06 2.1E-06 1.8E-06 1.5E-06 1.1E-06 9.OE-07 7.4E-07 6.2E-07 5.4E-07 5.OE-07 ESE 0. 4,3E-05 1.3E-05 6.3E-06 4.0E-06 2.9E-06 2.2E-06 1.8E-06 1.6E-06 1.2E-06 9.4E-07 7.7E-07 6.5E-07 5.7E-07 5.3E-07 SE 0. 6.1E-05 1.8E-05 8.9E-06 5.7E-06 4.1E-06 3.1E-06 2.6E-06 2.2E-06 1.7E-06 1.3E-06 1.1E-06 9.2E-07 8.0E-07 7.5E-07 SSE 0. 1.2E-04 3.1E-05 1.5E-05 9.6E-06 6.9E-06 5.2E-06 4.3E-06 3.7E-06 2.8E-06 2.2E-06 1.9E-06 1.6E-06 1.4E-06 1.3E-07 S 0. 6.3E-05 1.9E-05 9.4E-06 6.1E-06 4.4E-06 3.4E-06 2.8E-06 2.4E-06 1.8E-06 1.4E-06 1.2E-06 9.7E-07 8.4E-07 7.8E-07 SSW 0. 2.8E-05 8.6E-06 4,4E-06 2.9E-06 2.1E-06 1.6E-06 1.3E-06 1.1E-06 8.1E-07 6.4E-07 5.2E-07 4.4E-07 3.8E-07 3.5E-07 SW 0. 1.7E-05 5,4E-06 2.8E-06 1.8E-06 1.3E-06 1.OE-06 8.2E-07 6.8E-07 5.1E-07 4.OE-07 3.2E-07 2.7E-07 2.3E-07 2.2E-07 WSW 0. 1.1E-05 3.5E-06 1.9E-06 1.2E-06 8.9E-07 6.9E-07 5.5E-07 4.6E-07 3.4E-07 2.6E-07 2.1E-07 1.8E-07 1.5E-07 1.4E-07 W 0. 7.9E-06 2.5E-06 1.3E-06 8.8E-07 6.4E-07 4.9E-07 3.9E-07 3.3E-07 2.4E-07 1.9E-07 1.5E-07 1.2E-07 1.1E-07 9.8E-08 WNW 0. 7.4E-06 2.3E-06 1.2E-06 8.OE-07 5.8E-07 4.5E-07 3.6E-07 3.OE-07 2.2E-07 1.7E-07 1.4E-07 1.2E-07 9.9E-08 9.2E-08 NW 0. 7.6E-06 2.4E-06 1.3E-06 8.3E-07 6.OE-07 4.6E-07 3.7E-07 3.1E-07 2.3E-07 1.8E-07 1.4E-07 1.2E-07 1.OE-07 9.4E-08 NNW 0. 1.OE-05 3.2E-06 1.7E-06 1.1E-06 8.1E-07 6.2E-07 5.OE-07 4.2E-07 3.1E-07 2.4E-07 2.OE-07 1.6E-07 1,4E-07 1.3E-07 N 0. 8.6E-06 2.7E-06 1.5E-06 9.7E-07 7.1E-07 5.4E-07 4.4E-07 3.7E-07 2.7E-07 2.1E-07 1.7E-07 1.4E-07 1.2E-07 1.1E-07 ODCM (BSEP)A-8 Rev. 30 TABLE A-5 Depleted yIQ Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Concentration (Sec,/Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000 -2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1,25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 9.6E-06 2.9E-06 1.5E-06 9.5E-07 6.7E-07 5.1E-07 4.OE-07 3.3E-07 2.4E-07 1.8E-07 1.4E-07 1.2E-07 9.9E-08 9.1E-08 NE 0. 2.4E-05 7.5E-06 3.8E-06 2.4E-06 1.7E-06 1.3E-06 1.OE-06 8.5E-07 6.1E-07 4.7E-07 3.7E-07 3.0E-07 2.5E-07 2.3E-07 ENE 0. 3.8E-05 1.1E-05 5.3E-06 3.4E-06 2.4E-06 1.8E-06 1.5E-06 1.2E-06 9.OE-07 7.OE-07 5.6E-07 4.6E-07 3.9E-07 3.6E-07 E 0. 3.9E-05 1.1E-05 5.3E-06 3.4E-06 2.4E-06 1.8E-06 1.4E-06 1.2E-06 8.9E-07 6.9E-07 5.6E-07 4.6E-07 3.9E-07 3.6E-07 ESE 0. 4.1E-05 1.2E-05 5.6E-06 3.5E-06 2.5E-06 1.9E-06 1.5E-06 1.3E-06 9.3E-07 7.3E-07 5.9E-07 4.9E-07 4.1E-07 3.8E-07 SE 0. 5.8E-05 1.6E-05 7.9E-06 4.9E-06 3.5E-06 2.6E-06 2.1E-06 1.8E-06 1.3E-06 1.OE-06 8.2E-07 6.9E-07 5.8E-07 5.4E-07 SSE 0. 1.OE-04 2.8E-05 1.3E-05 8.3E-06 5.8E-06 4.4E-06 3.6E-06 3.OE-06 2.2E-06 1.7E-06 1,4E-06 1.2E-06 9.9E-07 9.2E-07 S 0. 6.0E-05 1.7E-05 8.3E-06 5.3E-06 3.8E-06 2.9E-06 2.3E-06 1.9E-06 1.4E-06 1.1E-06 8.8E-07 7.3E-07 6.1E-07 5.7E-07 SSW 0. 2.7E-05 7.9E-06 3.9E-06 2.5E-06 1.8E-06 1.3E-06 1.1E-06 8.9E-07 6.5E-07 5.OE-07 4.OE-07 3.3E-07 2.8E-07 2.5E-07 SW 0. 1.6E-05 4.9E-06 2.5E-06 1.6E-06 1.1E-06 8.5E-07 6.8E-07 5.6E-07 4.OE-07 3.OE-07 2.5E-07 2.OE-07 1.7E-07 1.6E-07 WSW 0. 1.1E-05 3.2E-06 1.7E-06 1.1E-06 7.6E-07 5.8E-07 4.6E-07 3.8E-07 2.7E-07 2.1E-07 1.6E-07 1.3E-07 1.1E-07 1.OE-07 W 0. 7.4E-06 2.3E-06 1.2E-06 7.6E-07 5.4E-07 4.1E-07 3.3E-07 2.7E-07 1.9E-07 1.4E-07 1.1E-07 9.4E-08 7.8E-08 7.2E-08 WNW 0. 7.OE-06 2.1E-06 1.1E-06 7.OE-07 5.OE-07 3.8E-07 3.OE-07 2.5E-07 1.8E-07 1.3E-07 1.1E-07 8.7E-08 7.3E-08 6.7E-08 NW 0. 7.1E-06 2.2E-06 1.1E-06 7.2E-07 5.2E-07 3.9E-07 3.1E-07 2.5E-07 1.8E-07 1.4E-07 1.1E-07 8.9E-08 7.5E-08 6.9E-08 NNW 0. 9.6E-06 2.9E-06 1.5E-06 9.7E-07 6.9E-07 5.2E-07 4.2E-07 3.4E-07 2.5E-07 1.9E-07 1.5E-07 1.2E-07 1.OE-07 9.5E-08 N 0. 8.1E-06 2.5E-06 1.3E-06 8.4E-07 6.OE-07 4.6E-07 3.6E-07 3.OE-07 2.1E-07 1.6E-07 1.3E-07 1.1E-07 8.8E-08 8.1E-08 ODCM (BSEP)A-9 Rev. 30 TABLE A-6 D/Q Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Deposition (Meter**-2)
Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.1E-08 1.4E-08 7.2E-09 4.4E-09 3.0E-09 2.2E-09 1.7E-09 1.3E-09 9.0E-10 6.5E-10 5.0E-10 3.9E-10 3.2E-10 2.9E-10 NE 0. 1.0E-07 3.5E-08 1.8E-08 1.1E-08 7.5E-09 5.5E-09 4.2E-09 3.3E-09 2.3E-09 1.6E-09 1.2E-09 9.8E-10 7.9E-10 7.2E-10 ENE 0. 4.4E-08 1.5E-08 7.6E-09 4.7E-09 3.2E-09 2.3E-09 1.8E-09 1,4E-09 9.6E-10 6.9E-10 5.3E-10 4,1E-10 3.4E-10 3.0E-10 E 0. 2.5E-08 8.3E-09 4.3E-09 2.6E-09 1.8E-09 1.3E-09 1.0E-09 7.9E-10 5.4E-10 3.9E-10 3.0E-10 2.3E-10 1.9E-10 1.7E-10 ESE 0. 2.6E-08 8.7E-09 4.5E-09 2.8E-09 1.9E-09 1.4E-09 1.OE-09 8.3E-10 5.6E-10 4.1E-10 3.1E-10 2.4.E-10 2.OE-10 1.8E-10 SE 0. 3.6E-08 1.2E-08 6.3E-09 3.9E-09 2.6E-09 1.9E-09 1.5E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.4E-10 2.8E-10 2.5E-10 SSE 0. 5.OE-08 1.7E-08 8.6E-09 5.3E-09 3.6E-09 2.6E-09 2.0E-09 1.6E-09 1.1E-09 7.8E-10 5.9E-10 4.7E-10 3.8E-10 3.4E-10 S 0. 5.3E-08 1.8E-08 9.2E-09 5.6E-09 3.8E-09 2.8E-09 2.1E-09 1.7E-09 1.1E-09 8.3E-10 6.3E-10 5.0E-10 4.OE-10 3.7E-10 SSW 0. 4.3E-08 1.5E-08 7.5E-09 4.6E-09 3.1E-09 2.3E-09 1.8E-09 1.4E-09 9.4E-10 6.8E-10 5.2E-10 4.1E-10 3.3E-10 3.OE-10 SW 0. 4.1E-08 1.4E-08 7.1E-09 4.4E-09 3.OE-09 2.2E-09 1.7E-09 1.3E-09 8.9E-10 6.5E-10 4.9E-10 3.9E-10 3.1E-10 2.8E-10 WSW 0. 2.9E-08 9.8E-09 5.1E-09 3.1E-09 2.1E-09 1.5E-09 1.2E-09 9.4E-10 6.3E-10 4.6E-10 3.5E-10 2.8E-10 2.2E-10 2.OE-10 W 0. 1.8E-08 6.2E-09 3.2E-09 2.OE-09 1.3E-09 9.7E-10 7,4E-10 5.9E-10 4.OE-10 2.9E-10 2.2E-10 1.7E-10 1.4E-10 1.3E-10 WNW 0. 1.5E-08 4.9E-09 2.5E-09 1.6E-09 1.1E-09 7.7E-10 5.9E-10 4.7E-10 3.2E-10 2.3E-10 1.7E-10 1.4E-10 1.1E-10 1.OE-10 NW 0. 1.6E-08 5.2E-09 2.7E-09 1.7E-09 1.1E-09 8.2E-10 6.3E-10 5.0E-10 3.4E-10 2.4E-10 1.9E-10 1.5E-10 1.2E-10 1.1E-10 NNW 0. 1.7E-08 5.9E-09 3.OE-09 1.9E-09 1.3E-09 9.2E-10 7.OE-10 5.6E-10 3.8E-10 2.7E-10 2.1E-10 1.6E-10 1.3E-10 1.2E-10 N 0. 2.3E-08 7.7E-09 3.9E-09 2.4E-09 1.7E-09 1.2E-09 9.2E-10 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 1.7E-10 1.6E-10 ODCM (BSEP)A-10 Rev. 30 TABLE A-7 x/Q Values at the Special Locations for Releases From the Reactor Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Concentration (Sec./Cubic Meter) -Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Site Boundary Dairy* Meat* Resident*
Garden*Sector NNE 9.1E-07 0. 4.4E-07 4.4E-07 4.4E-07 NE 2.3E-06 1.9E-07 0. 0. 0.ENE 1.9E-06 0. 0. 0. 0.E 1.3E-06 0. 6.8E-07 6.8E-07 0.ESE 1.3E-06 0. 1.3E-06 4.4E-07 4.4E-07 SE 1.8E-06 0. 1.8E-06 1.8E-06 0.SSE 2.5E-06 0. 2.5E-06 2.5E-06 2.5E-06 S 2.5E-06 0. 0. 1.3E-06 8.6E-07 SSW 1.6E-06 0. 8.2E-07 8.2E-07 8.2E-07 SW 1.2E-06 0. 1.2E-06 1.2E-06 1.2E-06 WSW 9.6E-07 0. 3.1 E-07 4.8E-07 4.8E-07 W 6.7E-07 0. 0. 6.7E-07 6.7E-07 WNW 5.8E-07 0. 0. 5.8E-07 5.8E-07 NW 6.3E-07 0. 0. 6.3E-07 6.3E-07 NNW 7.7E-07 0. 0. 7.7E-07 7.7E-07 N 7.9E-07 0. 0. 7.9E-07 7.9E-07*A zero indicates that this point was not calculated.
ODCM (BSEP) A-11 Rev. 30 TABLE A-8 Depleted x/Q Values at the Special Locations for Releases From the Reactor Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Depleted Concentration (Sec./Cubic Meter)Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Site Dairy* Meat* Resident*
Garden*Sector Boundary NNE 8.1E-07 0. 3.8E-07 3.8E-07 3.8E-0 NE 2.1 E-06 1.5E-07 0. 0. 0.ENE 1.7E-06 0. 0. 0.E 1.2E-06 0. 5.9E-07 5.9E-07 ESE 1.2E-06 0. 1.2E-06 3.8E-07 3.8E-07 SE 1.6E-06 0. 1.6E-06 1.6E-06 0.SSE 2.2E-06 0. 2.2E-06 2.2E-06 2.2E-06 S 2.2E-06 0. 0. 1.1 E-06 7.4E-0 SSW 1.5E-06 0. 7.1E-07 7.1E-07 7.1E-0 SW 1.1 E-06 0. 1.1 E-06 1.1 E-06 1.1E-0 WSW 8.5E-07 0. 2.7E-07 4.2E-07 4.2E-07 W 6.OE-07 0. 0. 6.OE-07 6.OE-07 WNW 5.2E-07 0. 0. 5.2E-07 5.2E-07 NW 5.6E-07 0. 0. 5.6E-07 5.6E-07 NNW 6.9E-07 0. 0. 6.9E-07 6.9E-07 N 7.1 E-07 0. 0. 7.1 E-07 7.1 E-07*A zero indicates that this point was not calculated.
ODCM (BSEP) A-12 Rev. 30 I TABLE A-9 D/Q Values at the Special Locations for Releases From the Reactor Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Deposition (Meter**-2)
Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Affected Site Boundary Dairy* Meat* Resident*
Garden*Sector NNE 7.0E-09 0. 2.9E-09 2.9E-09 2.9E-09 NE 1.7E-08 7.OE-10 0. 0. 0.ENE 6.6E-09 0. 0. 0. 0.E 3.1 E-09 0. 1.3E-09 1.3E-09 0.ESE 3.3E-09 0. 3.3E-09 7.8E-10 7.8E-10 SE 4.7E-09 0. 4.7E-09 4.7E-09 0.SSE 5.8E-09 0. 5.8E-09 5.8E-09 5.8E-09 S 7.4E-09 0. 0. 3.1E-09 1.7E-09 SSW 6.8E-09 0. 2.8E-09 2.8E-09 2.8E-09 SW 6.7E-09 0. 6.7 E-09 6.7E-09 6.7E-09 WSW 4.8E-09 0. 1.1 E-09 2.OE-09 2.OE-09 W 3.OE-09 0. 0. 3.OE-09 3.OE-09 WNW 2.3E-09 0. 0. 2.3E-09 2.3E-09 NW 2.5E-09 0. 0. 2.5E-09 2.5E-09 NNW 2.7E-09 0. 0. 2.7E-09 2.7E-09 N 3.7E-09 0. 0. 3.7E-09 3.7E-09*A zero indicates that this point was not calculated.
ODCM (BSEP)A-1 3 Rev. 301 TABLE A-10 X/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Concentration (Sec./Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.9E-06 1.7E-06 9.OE-07 6.OE-07 4.4E-07 3.4E-07 2.8E-07 2.3E-07 1.7E-07 1.4E-07 1.1 E-07 9.3E-08 8.OE-08 7.5E-08 NE 0. 1.3E-05 4.3E-06 2.3E-06 1.6E-06 1.1E-06 8.8E-07 7.1E-07 6.OE-07 4.5E-07 3.5E-07 2.9E-07 2.4E-07 2.1E-07 1.9E-07 ENE 0. 1.1 E-05 3.5E-06 1.9E-06 1.3E-06 9.6E-07 7.6E-07 6.4E-07 5.5E-07 4.3E-07 3.5E-07 3.OE-07 2.6E-07 2.3E-07 2.2E-07 E 0. 7.8E-06 2.5E-06 1.3E-06 9.OE-07 6.8E-07 5.5E-07 4.5E-07 4.OE-07 3.2E-07 2.7E-07 2.3E-07 2.OE-07 1.8E-07 1.7E-07 ESE 0. 7.8E-06 2.5E-06 1.3E-06 8.8E-07 6.6E-07 5.3E-07 4.4E-07 3.9E-07 3.1 E-07 2.6E-07 2.2E-07 1.9E-07 1.7E-07 1.7E-07 SE 0. 1.1 E-05 3.4E-06 1.8E-06 1.2E-06 8.9E-07 7.1 E-07 6.OE-07 5.2E-07 4.2E-07 3.5E-07 3.OE-07 2.7E-07 2.4E-07 2.3E-07 SSE 0. 1.6E-05 4.8E-06 2.5E-06 1.6E-06 1.2E-06 9.8E-07 8.3E-07 7.2E-07 5.9E-07 5.OE-07 4.3E-07 3.9E-07 3.5E-07 3.4E-07 S 0. 1.4E-05 4.6E-06 2.5E-06 1.7E-06 1.3E-06 1.OE-06 8.6E-07 7.4E-07 5.9E-07 4.9E-07 4.2E-07 3.6E-07 3.2E-07 3.1 E-07 SSW 0. 8.9E-06 3.OE-06 1.6E-06 1.1 E-06 8.2E-07 6.5E-07 5.3E-07 4.5E-07 3.5E-07 2.8E-07 2.4E-07 2.OE-07 1.8E-07 1.7E-07 SW 0. 6.7E-06 2.3E-06 1.2E-06 8.3E-07 6.1 E-07 4.8E-07 3.9E-07 3.3E-07 2.5E-07 2.OE-07 1.7E-07 1.4E-07 1.2E-07 1.2E-07 WSW 0. 5.2E-06 1.7E-06 9.8E-07 6.5E-07 4.8E-07 3.8E-07 3.1E-07 2.7E-07 2.OE-07 1.6E-07 1.3E-07 1.1E-07 9.7E-08 9.1E-08 W 0. 3.6E-06 1.2E-06 6.7E-07 4.6E-07 3.5E-07 2.7E-07 2.3E-07 1.9E-07 1.5E-07 1.2E-07 9.6E-08 8.1 E-08 7.0E-08 6.6E-08 WNW 0. 3.1 E-06 1.OE-06 5.8E-07 3.9E-07 2.9E-07 2.3E-07 1.9E-07 1.6E-07 1.2E-07 1.OE-07 8.2E-08 7.0E-08 6.1 E-08 5.7E-08 NW 0. 3.4E-06 1.1E-06 6.3E-07 4.3E-07 3.2E-07 2.5E-07 2.1E-07 1.8E-07 1.3E-07 1.1E-07 8.8E-08 7.5E-08 6.4E-08 6.OE-08 NNW 0. 4.1 E-06 1.4E-06 7.8E-07 5.3E-07 4.OE-07 3.2E-07 2.6E-07 2.3E-07 1.7E-07 1.4E-07 1.2E-07 9.8E-08 8.5E-08 8.OE-08 N 0. 4.2E-06 1.4E-06 7.9E-07 5.4E-07 4.0E-07 3.2E-07 2.6E-07 2.2E-07 1.7E-07 1.4E-07 1.1 E-07 9.5E-08 8.2E-08 7.7E-08 ODCM (BSEP)A-14 Rev. 30 TABLE A-11 Depleted x/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy -Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Depleted Concentration (Sec./Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.6E-06 1.5E-06 8.1E-07 5.3E-07 3.8E-07 2.9E-07 2.3E-07 1.9E-07 1.4E-07 1.1E-07 9.OE-08 7.5E-08 6.4E-08 6.0E-08 NE 0. 1.2E-05 3.9E-06 2.1 E-06 1.4E-06 9.8E-07 7.6E-07 6.1 E-07 5.OE-07 3.7E-07 2.9E-07 2.3E-07 1.9E-07 1.7E-07 1.5E-07 ENE 0. 1.OE-05 3.2E-06 1.7E-06 1.1 E-06 8.3E-07 6.6E-07 5.5E-07 4.7E-07 3.6E-07 3.OE-07 2.5E-07 2.2E-07 1.9E-07 1.8E-07 E 0. 7.4E-06 2.2E-06 1.2E-06 7.9E-07 5.9E-07 4.7E-07 4.OE-07 3.5E-07 2.7E-07 2.3E-07 1.9E-07 1.7E-07 1.5E-07 1.4E-07 ESE 0. 7.4E-06 2.2E-06 1.2E-06 7.7E-07 5.8E-07 4.6E-07 3.8E-07 3.3E-07 2.6E-07 2.2E-07 1.8E-07 1.6E-07 1.4E-07 1.4E-07 SE 0. 1.OE-05 3.1 E-06 1.6E-06 1.OE-06 7.7E-07 6.1 E-07 5.1 E-07 4.4E-07 3.5E-07 2.9E-07 2.5E-07 2.2E-07 2.OE-07 1.9E-07 SSE 0. 1.5E-05 4.4E-06 2.2E-06 1.4E-06 1.1 E-06 8.4E-07 7.1 E-07 6.2E-07 5.OE-07 4.2E-07 3.7E-07 3.3E-07 3.OE-07 2.8E-07 S 0. 1.4E-05 4.2E-06 2.2E-06 1.5E-06 1.1 E-06 8.8E-07 7.4E-07 6.3E-07 5.OE-07 4.1 E-07 3.5E-07 3.OE-07 2.7E-07 2.6E-07 SSW 0. 8.4E-06 2.7E-06 1.5E-06 9.6E-07 7.1 E-07 5.6E-07 4.6E-07 3.9E-07 2.9E-07 2.3E-07 1.9E-07 1.7E-07 1.4E-07 1.4E-07 SW 0. 6.4E-06 2.1E-06 1.1E-06 7.3E-07 5.3E-07 4.1E-07 3.4E-07 2.8E-07 2.1E-07 1.7E-07 1.4E-07 1.2E-07 1.OE-07 9.3E-08 WSW 0. 4.9E-06 1.6E-06 8.5E-07 5.7E-07 4.2E-07 3.3E-07 2.7E-07 2.3E-07 1.7E-07 1.3E-07 1.1 E-07 9.2E-08 7.9E-08 7.4E-08 W 0. 3.4E-06 1.1 E-06 6.OE-07 4.1 E-07 3.OE-07 2.4E-07 1.9E-07 1.6E-07 1.2E-07 9.8E-08 8.OE-08 6.7E-08 5.8E-08 5.4E-08 WNW 0. 2.9E-06 9.5E-06 5.2E-07 3.5E-07 2.6E-07 2.OE-07 1.7E-07 1.4E-07 1.1E-07 8.3E-08 6.9E-08 5.8E-08 5.OE-08 4.6E-08 NW 0. 3.2E-06 1.OE-06 5.6E-07 3.8E-07 2.8E-07 2.2E-07 1.8E-07 1.5E-07 1.1E-07 8.9E-08 7.3E-08 6.1E-08 5.3E-08 4.9E-08 NNW 0. 3.9E-06 1.2E-06 6.9E-07 4.7E-07 3.5E-07 2.8E-07 2.3E-07 1.9E-07 1.5E-07 1.2E-07 9.6E-08 8.1E-08 7.OE-08 6.5E-08 N 0. 4.OE-06 1.3E-06 7.1E-07 4.7E-07 3.5E-07 2.8E-07 2.3E-07 1.9E-07 1.4E-07 1.1E-07 9.2E-08 7.8E-08 6.7E-08 6.2E-08 ODCM (BSEP)A-15 Rev. 30 TABLE A-1 2 D/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy- Brunswick Release Type: Annual Release Mode: Mixed Mode Variable:
Relative Deposition (Meter**-2)
Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.OE-08 1.4E-08 7.0E-09 4.3E-09 2.9E-09 2.1E-09 1.6E-09 1.3E-09 8.8E-10 6.4E-10 4.8E-10 3.8E-10 3.1E-10 2.8E-10 NE 0. 1.OE-07 3.4E-08 1.7E-08 1.1E-08 7.3E-09 5.3E-09 4.1E-09 3.2E-09 2.2E-09 1.6E-09 1.2E-09 9.5E-10 7.7E-10 7.OE-10 ENE 0. 3.8E-08 1.3E-08 6.5E-09 4.0E-09 2.8E-09 2.OE-09 1.5E-09 1.2E-09 8.2E-10 6.OE-10 4.5E-10 3.6E-10 2.9E-10 2.6E-10 E 0. 1.8E-08 6.1E-09 3.1E-09 1.9E-09 1.3E-09 9.6E-09 7.4E-10 5.9E-10 4.OE-10 2.9E-10 2.2E-10 1.7E-10 1.4E-10 1.3E-10 ESE 0. 1.9E-08 6.5E-09 3.3E-09 2.0E-09 1.4E-09 1.0E-09 7.8E-10 6.2E-10 4.2E-10 3.OE-10 2.3E-10 1.8E-10 1.5E-10 1.3E-10 SE 0. 2.7E-08 9.OE-09 4.7E-09 2.9E-09 2.OE-09 1.4E-09 1.1E-09 8.7E-10 5.9E-10 4.2E-10 3.2E-10 2.5E-10 2.1E-10 1.9E-10 SSE 0. 3.3E-08 1.1E-08 5.8E-09 3.6E-09 2.5E-09 1.8E-09 1.4E-09 1.1E-09 7.3E-10 5.3E-10 4.OE-10 3.2E-10 2.6E-10 2.3E-10 S 0. 4.3E-08 1.4E-08 7.4E-09 4.6E-09 3.1E-09 2.3E-09 1.7E-09 1.4E-09 9.3E-10 6.8E-10 5.1E-10 4.OE-10 3.3E-10 3.OE-10 SSW 0. 3.9E-08 1.3E-08 6.8E-09 4.2E-09 2.8E-09 2.1E-09 1.6E-09 1.3E-09 8.5E-10 6.2E-10 4.7E-10 3.7E-10 3.OE-10 2.7E-10 SW 0. 3.8E-08 1.3E-08 6.7E-09 4.1E-09 2.8E-09 2.1E-09 1.6E-09 1.2E-09 8.4E-10 6.1E-10 4.6E-10 3.7E-10 3.OE-10 2.7E-10 WSW 0. 2.7E-08 9.3E-09 4.8E-09 2.9E-09 2.OE-09 1.5E-09 1.1E-09 8.9E-10 6.OE-10 4.3E-10 3.3E-10 2.6E-10 2.1E-10 1.9E-10 W 0. 1.7E-08 5.7E-09 3.OE-09 1.8E-09 1.2E-09 9.1E-10 6.9E-10 5.5E-10 3.7E-10 2.7E-10 2.OE-10 1.6E-10 1.3E-10 1.2E-10 WNW 0. 1.3E-08 4.5E-09 2.3E-09 1.4E-09 9.7E-10 7.1E-10 5.4E-10 4.3E-10 2.9E-10 2.1E-10 1.6E-10 1.3E-10 1.0E-10 9.3E-11 NW 0. 1.4E-08 4.8E-09 2.5E-09 1.5E-09 1.OE-09 7.6E-10 5.8E-10 4.6E-10 3.1E-10 2.3E-10 1.7E-10 1.4E-10 1.1E-10 1.OE-10 NNW 0. 1.6E-08 5.3E-09 2.7E-09 1.7E-09 1.1E-09 8.3E-10 6.4E-10 5.1E-10 3.4E-10 2.5E-10 1.9E-10 1.5E-10 1.2E-10 1.1E-10 N 0. 2.1E-08 7.2E-09 3.7E-09 2.3E-09 1.6E-09 1.1E-09 8.7E-10 6.9E-10 4.7E-10 3.4E-10 2.6E-10 2.OE-10 1.6E-10 1.5E-10 ODCM (BSEP)A-16 Rev. 30 TABLE A-13 x/Q Values at the Special Locations for Releases From the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Concentration Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Accountinq for Stack Center Offset Affected Site Dairy* Meat* Resident*
Garden*Sector Boundary NNE 1.9E-08 0. 2.3E-08 2.3E-08 2.3E-08 NE 4.6E-08 2.4E-08 0. 0. 0.ENE 3.2E-08 0. 0. 0. 0.E 8.4E-09 0. 1.3E-08 1.3E-08 0.ESE 9.3E-09 0. 9.3E-09 1.1 E-08 1.1E-08 SE 1.OE-08 0. 1.OE-08 1.OE-08 0.SSE 1.5E-08 0. 1.5E-08 1.5E-08 1.5E-08 S 1.6E-08 0. 0. 2.0E-08 2.1 E-08 SSW 1.5E-08 0. 2.4E-08 2.4E-08 2.4E-08 SW 1.6E-08 0. 1.6E-08 1.6E-08 1.6E-08 WSW 2.4E-08 0. 2.5E-08 2.5E-08 2.5E-08 W 1.9E-08 0. 0. 1.9E-08 1.9E-08 WNW 1.4E-08 0. 0. 1.4E-08 1.4E-08 NW 1.4E-08 0. 0. 1A4E-08 1.4E-08 NNW 1.OE-08 0. 0. 1.OE-08 1.OE-08 N 9.8E-09 0. 0. 9.8E-09 9.8E-0*A zero indicates that this point was not calculated.
ODCM (BSEP) A-17 Rev. 30 I TABLE A-14 Depleted X/Q Values at the Special Locations for Releases From the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Depleted Concentrations Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Accounting for Stack Center Offset Affected Site Dairy* Meat* Resident*
Garden*Sector Boundary NNE 1.9E-08 0. 2.3E-08 2.3E-08 2.3E-08 NE 4.5E-08 2.2E-08 0. 0. 0.ENE 3.1E-08 0. 0. 0. 0 E 8.3E-09 0. 1.2E-08 1.2E-08 ESE 9.1E-09 0. 9.1E-09 1.1E-08 1.1E-08 SE 9.8E-09 0. 9.8E-09 9.8E-09 0.SSE 1.5E-08 0. 1.5E-08 1.5E-08 1.5E-0 S 1.6E-08 0. 0. 2.OE-08 2.OE-08 SSW 1.5E-08 0. 2.3E-08 2.3E-08 2.3E-08 SW 1.6E-08 0. 1.6E-08 1.6E-08 1.6E-08 WSW 2.3E-08 0. 2.4E-08 2.5E-08 2.5E-08 W 1.9E-08 0. 0. 1.9E-08 1.9E-08 WNW 1.4E-08 0. 0. 1.4E-08 1.4E-08 NW 1.3E-08 0. 0. 1.3E-08 1.3E-08 NNW 1.OE-08 0. 0. 1.OE-08 1.OE-08 N 9.6E-09 0. 0. 9.6E-09 9.6E-09*A zero indicates that this point was not calculated.
ODCM (BSEP) A-18 Rev. 30 1 TABLE A-15 D/Q Values at the Special Locations for Releases from the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Deposition (Meter**-2)
Calculation Points: Special Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Accounting for Stack Center Offset Affected Site Boundary Dairy* Meat* Resident*
Garden*Sector NNE 1.0E-09 0. 6.7E-10 6.7E-10 6.7E-10 NE 2.7E-09 2.9E-10 0. 0. 0.ENE 1.8E-09 0. 0. 0. 0.E 3.7E-10 0. 2.8E-10 2.8E-10 0.ESE 4.4E-10 0. 4.4E-10 1.9E-10 1.9E-10 SE 5.5E-10 0. 5.5E-10 5.5E-10 0 SSE 8.OE-10 0. 8.OE-10 8.OE-10 8.OE-10 S 8.5E-10 0. 0. 5.9E-10 4.1E-10 SSW 7.9E-10 0. 6.6E-10 6.6E-10 6.6E-10 SW 8.5E-10 0. 8.5E-10 8.5E-10 8.5E-10 WSW 1.3E-09 0. 5.3E-10 8.OE-10 8.OE-10 W 8.9E-10 0. 0. 8.9E-10 8.9E-10 WNW 5.9E-10 0. 0. 5.9E-10 5.9E-10 NW 5.6E-10 0. 0. 5.6E-10 5.6E-10 NNW 4.6E-10 0. 0. 4.6E-10 4.6E-10 N 4.7E-10 0. 0. 4.7E-10 4.7E-10*A zero indicates that this point was not calculated.
ODCM (BSEP)A-1 9 Rev. 30 TABLE A-16 X/Q Values at the Standard Distances for Releases from the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Concentration (Sec./Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.1 E-08 1.7E-08 1.9E-08 2.1 E-08 2.3E-08 2.3E-08 2.3E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.6E-08 1.4E-08 1.4E-08 NE 0. 4.1 E-08 4.7E-08 4.6E-08 4.7E-08 4.8E-08 4.7E-08 4.6E-08 4.4E-08 3.9E-08 3.5E-08 3.1E-08 2.8E-08 2.5E-08 2.4E-08 ENE 0. 2.3E-08 2.9E-08 3.2E-08 3.7E-08 4.OE-08 4.2E-08 4.3E-08 4.2E-08 4.OE-08 3.6E-08 3.3E-08 3.OE-08 2.7E-08 2.6E-08 E 0. 3.OE-09 5.7E-09 8.4E-09 1.1 E-08 1.3E-08 1.4E-08 1.5E-08 1.5E-08 1.5E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 ESE 0. 5.4E-09 8.0E-09 9.3E-09 1.OE-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 1.OE-08 9.7E-09 9.OE-09 8.3E-09 7.7E-09 7.4E-09 SE 0. 8.9E-09 9.8E-09 1.OE-08 1.1 E-08 1.1 E-08 1.2E-08 1.2E-08 1.2E-08 1.1 E-08 1.OE-08 9.3E-09 8.6E-09 7.9E-09 7.6E-09 SSE 0. 1.7E-08 1.6E-08 1.5E-08 1.6E-08 1.6E-08 1.6E-08 1.6E-08 1.5E-08 1.4E-08 1.2E-08 1.1E-08 1.OE-08 9.2E-09 8.8E-09 S 0. 1.4E-08 1.4E-08 1.6E-08 1.8E-08 2.OE-08 2.1E-08 2.1E-08 2.OE-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 SSW 0. 8.2E-09 1.1 E-08 1.5E-08 2.0E-08 2.4E-08 2.5E-08 2.6E-08 2.6E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.5E-08 SW 0. 6.5E-09 1.2E-08 1.6E-08 2.OE-08 2.3E-08 2.4E-08 2.5E-08 2.4E-08 2.3E-08 2.OE-08 1.8E-08 1.7E-08 1.5E-08 1.4E-08 WS 0. 2.2E-08 2.4E-08 2.4E-08 2.5E-08 2.5E-08 2.5E-08 2.5E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 W W 0. 2.2E-08 2.2E-08 1.9E-08 1.7E-08 1.7E-08 1.7E-08 1.6E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.1E-08 9.8E-09 9.4E-09 WN 0. 1.4E-08 1.6E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1 E-08 1.0E-08 9.2E-09 8.4E-09 7.7E-09 7.1 E-09 6.8E-09 W NW 0. 1.4E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1E-08 1.OE-08 9.1E-09 8.3E-09 7.5E-09 6.9E-09 6.6E-09 NN 0. 1.2E-08 1.1E-08 1.OE-08 1.OE-08 1.OE-08 1.1E-08 1.1E-08 1.OE-08 9.9E-09 9.2E-09 8.5E-09 7.8E-09 7.2E-09 6.9E-09 W N 0. 7.7E-09 8.9E-09 9.8E-09 1.1E-08 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.1E-08 1.OE-08 9.6E-09 8.9E-09 8.6E-09 ODCM (BSEP)A-20 Rev. 30 TABLE A-17 Depleted x/Q Values at the Standard Distances for Releases from the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Depleted Concentration (Sec./Cubic Meter)Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.1E-08 1.7E-08 1.9E-08 2.1E-08 2.2E-08 2.3E-08 2.3E-08 2.2E-08 2.OE-08 1.8E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 NE 0. 4.1E-08 4.7E-08 4.5E-08 4.6E-08 4.6E-08 4.6E-08 4.4E-08 4.2E-08 3.8E-08 3.3E-08 2.9E-08 2.6E-08 2.3E-08 2.2E-08 ENE 0. 2.3E-08 2.8E-08 3.1 E-08 3.6E-08 4.OE-08 4.2E-08 4.2E-08 4.1 E-08 3.8E-08 3.5E-08 3.2E-08 2.9E-08 2.6E-08 2.5E-08 E 0. 3.OE-09 5.6E-09 8.3E-09 1.1E-08 1.2E-08 1.4E-08 1.4E-08 1.5E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.1E-08 1.1E-08 ESE 0. 5.8E-09 7.9E-09 9.1E-09 9.8E-09 1.OE-08 1.1 E-08 1.1E-08 1.1 E-08 1.OE-08 9.4E-09 8.7E-09 8.OE-09 7.5E-09 7.1E-09 SE 0. 8.9E-09 9.7E-09 9.8E-09 1.OE-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 9.8E-09 9.OE-09 8.2E-09 7.5E-09 7.2E-09 SSE 0. 1.7E-08 1.6E-08 1.5E-08 1.5E-08 1.6E-08 1.6E-08 1.5E-08 1.5E-08 1.3E-08 1.2E-08 1.1 E-08 9.6E-09 8.7E-09 8.3E-09 S 0. 1.4E-08 1.4E-08 1.6E-08 1.8E-08 2.OE-08 2.0E-08 2.OE-08 2.OE-08 1.8E-08 1.6E-08 1.5E-08 1.3E-08 1.2E-08 1.1 E-08 SSW 0. 8.2E-09 1.1E-08 1.5E-08 2.OE-08 2.3E-08 2.5E-08 2.5E-08 2.5E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 SW 0. 6.5E-09 1.2E-08 1.6E-08 2.OE-08 2.3E-08 2.4E-08 2.4E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 WSW 0. 2.2E-08 2.4E-08 2.3E-08 2.4E-08 2.5E-08 2.5E-08 2.4E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 W 0. 2.2E-08 2.2E-08 1.9E-08 1.7E-08 1.6E-08 1.6E-08 1.5E-08 1.5E-08 1.4E-08 1.2E-08 1.1 E-08 1.OE-08 9.3E-09 8.9E-09 WNW 0. 1.4E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1 E-08 1.1 E-08 9.7E-09 8.8E-09 8.OE-09 7.3E-09 6.7E-09 6.4E-09 NW 0. 1.4E-08 1.5E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1 E-08 1.OE-08 9.6E-09 8.7E-09 7.9E-09 7.1 E-09 6.5E-09 6.2E-09 NNW 0. 1.2E-08 1.1 E-08 1.OE-08 1.OE-08 1.OE-08 1.OE-08 1.OE-08 1.OE-08 9.5E-09 8.8E-09 8.1E-09 7.4E-09 6.8E-09 6.6E-09 N 0. 7.5E-09 8.8E-09 9.6E-09 1.1E-08 1.1E-08 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.1E-08 1.OE-08 9.2E-09 8.5E-09 8.2E-09 ODCM (BSEP)A-21 Rev. 30 TABLE A-18 D/Q Values at the Standard Distances for Releases from the Stack Progress Energy -Brunswick Release Type: Annual Release Mode: Elevated Variable:
Relative Deposition (Meter**-2)
Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations:
42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.6E-09 1.3E-09 1.OE-09 8.4E-10 6.7E-10 5.5E-10 4.5E-10 4.OE-10 3.1E-10 2.4E-10 2.OE-10 1.6E-10 1.3E-10 1.2E-10 NE 0. 4.5E-09 3.5E-09 2.7E-09 2.2E-09 1.7E-10 1.3E-09 1.1E-09 9.6E-10 7.3E-10 5.7E-10 4.6E-10 3.8E-10 3.1E-10 2.9E-10 ENE 0. 2.7E-09 2.1E-09 1.8E-09 1.5E-09 1.2E-10 1.OE-09 8.4E-10 7.4E-10 5.7E-10 4.5E-10 3.7E-10 3.0E-10 2.5E-10 2.3E-10 E 0. 5.1E-10 4.2E-10 3.7E-10 3.4E-10 2.8E-10 2.3E-10 2.0E-10 1.8E-10 1.4E-10 1.1E-10 8.9E-11 7.3E-11 6.1E-11 5.6E-11 ESE 0. 7.2E-10 5.6E-10 4.4E-10 3.6E-10 2.8E-10 2.3E-10 1.9E-10 1.7E-10 1.3E-10 1.OE-10 8.1E-11 6.6E-11 5.5E-11 5.1E-11 SE 0. 9.2E-10 7.1E-10 5.5E-10 4.6E-10 3.5E-10 2.8E-10 2.3E-10 2.OE-10 1.5E-10 1.2E-10 9.7E-11 7.9E-11 6.6E-11 6.1E-11 SSE 0. 1.4E-09 1.1E-09 8.OE-10 6.4E-10 4.9E-10 3.9E-10 3.2E-10 2.8E-10 2.1E-10 1.7E-10 1.3E-10 1.1E-10 9.1E-11 8.3E-11 S 0. 1.3E-09 1.OE-09 8.5E-10 7.3E-10 5.9E-10 4.9E-10 4.1E-10 3.6E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.2E-10 1.E-10 SSW 0. 9.3E-10 8.2E-10 7.9E-10 7.7E-10 6.6E-10 5.6E-10 4.9E-10 4.4E-10 3.4E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.4E-10 SW 0. 1.1E-09 9.5E-10 8.5E-10 7.9E-10 6.6E-10 5.6E-10 4.8E-10 4.2E-10 3.3E-10 2.7E-10 2.2E-10 1.8E-10 1.5E-10 1.3E-10 WSW 0. 2.1E-09 1.6E-09 1.3E-09 1.OE-09 8.OE-10 6.4E-10 5.3E-10 4.7E-10 3.5E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.4E-10 W 0. 1.6E-09 1.2E-09 8.9E-10 6.8E-10 5.1E-10 4.OE-10 3.2E-10 2.8E-10 2.1E-10 1.6E-10 1.3E-10 1.1E-10 8.9E-11 8.1E-11 WNW 0. 1.1E-09 8.2E-10 5.9E-10 4.4E-10 3.3E-10 2.5E-10 2.OE-10 1.7E-10 1.3E-10 1.0E-10 8.OE-11 6.6E-11 5.5E-11 5.OE-11 NW 0. 1.OE-09 7.8E-10 5.6E-10 4.3E-10 2.2E-10 2.5E-10 2.OE-10 1.7E-10 1.3E-10 1.0E-10 8.OE-11 6.5E-11 5.4E-11 5.OE-11 NNW 0. 8.2E-10 6.2E-10 4.6E-10 3.6E-10 2.8E-10 2.2E-10 1.7E-10 1.5E-10 1.2E-10 9.OE-11 7.3E-11 6.0E-11 5.OE-11 4.5E-11 N 0. 7.7E-10 6.OE-10 4.7E-10 3.9E-10 3.1E-10 2.4E-10 2.OE-10 1.8E-10 1.4E-10 1.1E-10 8.8E-11 7.2E-11 6.OE-11 5.5E-11 ODCM (BSEP)A-22 Rev. 30 TABLE A-19 Brunswick Plant Site Information To Be Used for Ground Level Calculations with NRC "XOQDOQ" Program Card Columns Description Value to be Used in Type XOQDOQ 1 1 Print input data 1 38 Calculate annual ,/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs 1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted ,/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution
*21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 11 6-20 Half-life (days) used in the XlQ calculations 101.00 2.26 8.00*Appropriate data to be supplied.ODCM (BSEP)A-23 Rev. 25 TABLE A-19 (Cont'd)Card Columns Description Value to be Used in Type XOQDOQ 5 N/A N/A 6 1-80 Joint wind frequency distribution 7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond to distances in All are 0 Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site Boundary 16 Dairy 1 Meat 8 Residence 14 Garden 12 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence*Appropriate data to be supplied.ODCM (BSEP)A-24 Rev. 30 TABLE A-19 (Cont'd)Card Columns Description Value to be Used in Type XOQDOQ 1-16 Cont'd Title of receptor type for receptor locations (Cont'd) Garden 12 1-80 Receptor direction and distance (See Table 1)13 1-80 Title for release point whose characteristics are described on Card *Type 14 14 1-5 Vent average velocity (m/sec) 1.0 6-10 Vent inside diameter (m) 1.0 11-15 Height of vent release point (m) 0.000 16-20 Height of the vent's building (m) 56.9 21-25 Minimum cross-sectional area for the vent's building (M 2) 2120.0 26-30 Wind height used for vent elevated release 11.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0*Appropriate data to be supplied.ODCM (BSEP)A-25 Rev. 25 TABLE A-20 Brunswick Plant Site Information To Be Used for Elevated Release Calculations with NRC "XOQDOQ" Program Card Columns Description Value to Be Used in Type XOQDOQ 1 1 Print input data 1 4 Release to be elevated 100% of the time 1 38 Calculate annual X/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs 1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted X/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours injoint wind frequency distribution
*21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 5 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 104 6-20 Half-life (days) used in the X/Q calculations 101.00 2.26*Appropriate data to be supplied.ODCM (BSEP)A-26 Rev. 25 TABLE A-20 (Cont'd)Card Columns Description Value to Be Used in Type XOQDOQ 6-20 Half-life (days) used in the x/Q calculations (Cont'd) 8.00 (Cont'd)5 N/A N/A 6 1-80 Joint wind frequency distribution
*7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond to distances in All are 0 Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site Boundary 16 Dairy 1 Meat 8 Residence 14 Garden 12*Appropriate data to be supplied.ODCM (BSEP)A-27 Rev. 30 TABLE A-20 (Cont'd)Card Columns Description Value to Be Used in Type XOQDOQ 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Garden 12 1-80 Receptor direction and distance (See Table 1)13 1-80 Title for release point whose characteristics are described on Card Type *14 14 1-5 Vent average velocity (m/sec) 4.66 6-10 Vent inside diameter (m) 3.58 11-15 Height of vent release point (m) 100.9 16-20 Height of the vent's building (m) 0.0 21-25 Minimum cross-sectional area for the vent's building (Mi) 0.00 26-30 Wind height used for vent elevated release 104.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0*Appropriate data to be supplied.ODCM (BSEP)A-28 Rev. 25 Table No.APPENDIX B B-1 B-2 B-3 B-4 B-5 B-6 B-7 B-8 B-9 B-10 B-11 B-12 LIST OF TABLES Title Paqe DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE B O U N D A R Y ...............................................................................................
B -5 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ... B-6 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE B O U N D A R Y ...............................................................................................
B -7 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ...............
B-8 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE B O U N D A R Y ...............................................................................................
B -9 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA N T .............................................................................................
..B -10 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE B O U N D A R Y ........................................................................................
B -11 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA N T .............................................................................................
..B -12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE B O U N D A R Y ........................................................................................
B -13 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ...... B-14 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BO U N D A R Y ........................................................................................
B -15 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA N T .....................................................................................................
B -1 6 ODCM (BSEP)B-1 Rev. 30 LIST OF TABLES (Cont'd)Table No. Title Page APPENDIX B (continued)
B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE B O U N D A R Y .............................................................................................
B -17 B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT .............
B-18 B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE B O U N D A R Y .............................................................................................
B -19 B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P L A N T .....................................................................................................
B -2 0 B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE B O U N D A R Y .............................................................................................
B -2 1 B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT .............
B-22 B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE B O U N D A R Y .............................................................................................
B -2 3 B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P L A N T .....................................................................................................
B -2 4 B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE B O U N D A R Y .............................................................................................
B -2 5 B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P L A N T .....................................................................................................
B -2 6 B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE B O U N D A R Y .............................................................................................
B -27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P L A N T ....................................................................................................
B -2 8 ODCM (BSEP)B-2 Rev. 30 LIST OF TABLES (Cont'd)Table No. Title Page APPENDIX B (continued)
B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE B O U N D A R Y .............................................................................................
B -29 B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ...... B-30 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE B O U N D A R Y .............................................................................................
B -3 1 B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA N T .....................................................................................................
B -3 2 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE B O U N D A R Y .............................................................................................
B -33 B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA N T .....................................................................................................
B -3 4 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE B O U N D A R Y .............................................................................................
B -35 B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P L A N T .....................................................................................................
B -3 6 ODCM (BSEP)B-3 Rev. 30 APPENDIX B Calculation of Vi and Bi Values for the Elevated Plume Values of Vi and Bi were calculated for the elevated plume release from the Brunswick stack using the NRC computer program RABFIN. This program was used to determine the controlling location based upon the releases of Table 3.2-1. In addition it was used to develop the Vi and Bi values for the various noble gas radionuclides at the site boundary at each of the 16 sectors.Table B-7 presents the Vi and Bi values for the NE sector which is the controlling location for noble gases for showing compliance with 1OCFR20 and 1OCFR50. Table B-8 presents thejoint frequency distribution for the NE sector. Tables B-1 through B-6 and B-9 through B-32 present the Vi and Bi values and the joint frequency distribution for the remaining sectors. The inputs which were utilized in the RABFIN code are presented below.1. Height of Stack -100.9 (m)2. Stack Diameter -3.6 (m)3. Exit Velocity -5.0 m/sec 4. Wind Height -104.6 (m)ODCM (BSEP)B-4 Rev. 25 TABLE B-I DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY*Noble Gas Radionuclides Vi Total Body Bi Gamma Air/mremyr Imrad, r" IiCi/ sec ) Ci/ sec Kr-83m 2.70E-09 7.46E-07 Kr-85m 1.14E-04 1.69E-04 Kr-85 1.69E-06 2.56E-06 Kr-87 5.12E-04 7.71E-04 Kr-88 1.35E-03 2.02E-03 Kr-89 7.59E-04 1.14E-03 Xe-131m 2.78E-05 4.44E-05 Xe-133m 2.12E-05 3.51E-05 Xe-1 33 2.22E-05 3.52E-05 Xe-135m 2.62E-04 3.97E-04 Xe-135 1.82E-04 2.74E-04 Xe-1 37 6.42E-05 9.70E-05 Xe-138 8.09E-04 1.21 E-03 Xe-139 1.89E-05 2.83E-05 Ar-41 9.71 E-04 1.46E-03*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-5 Rev. 30 I TABLE B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.39 0.00 0.00 0.01 0.10 0.21 0.06 0.01 2 0.55 0.00 0.00 0.02 0.13 0.32 0.08 0.00 3 0.95 0.00 0.00 0.05 0.33 0.44 0.12 0.01 4 5.71 0.00 0.06 0.45 1.58 2.33 1.06 0.22 5 3.69 0.00 0.02 0.24 1.17' 1.58 0.58 0.09 6 0.96 0.00 0.03 0.19 0.39 0.28 0.06 0.00 7 0.77 0.01 0.06 0.22 0.32 0.16 0.00 0.00 Total 13.02 0.02 0.16 1.18 4.01 5.32 1.98 0.34 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity ___ __ 3.10 Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I I AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.16 6.16 Harmonic 0.00 4.85 4.85 ODCM (BSEP)B-6 Rev. 301 TABLE B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY*Noble Gas Radionuclides Vi Total Body Bi Gamma Air mrem/yr mrad/yr jiCi/sec) iCi/ sec)Kr-83m 9.02E-10 2.46E-07 Kr-85m 4.25E-05 6.29E-05 Kr-85 6.50E-07 9.85E-07 Kr-87 1.91 E-04 2.88E-04 Kr-88 5.24E-04 7.86E-04 Kr-89 2.49E-04 3.74E-04 Xe-131m 1.03E-05 1.64E-05 Xe-133m 7.88E-06 1.30E-05 Xe-133 8.13E-06 1.28E-05 Xe-135m 9.13E-05 1.39E-04 Xe-135 6.88E-05 1.03E-04 Xe-137 2.01 E-05 3.03E-05 Xe-138 2.98E-04 4.47E-04 Xe-139 5.74E-06 8.62E-06 Ar-41 3.67E-04 5.50E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-7 Rev. 30 I TABLE B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (misec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.11 0.00 0.00 0.01 0.06 0.04 0.00 0.00 2 0.12 0.00 0.00 0.01 0.08 0.02 0.00 0.00 3 0.31 0.00 0.00 0.05 0.17 0.06 0.02 0.00 4 1.27 0.00 0.04 0.23 0.44 0.31 0.16 0.08 5 1.52 0.00 0.02 0.11 0.42 0.49 0.33 0.14 6 0.48 0.00 0.03 0.09 0.17 0.12 0.04 0.02 7 0.43 0.00 0.04 0.16 0.16 0.06 0.01 0.00 Total 4.23 0.02 0.14 0.66 1.50 1.09 0.57 0.25 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 5.78 5.78 Harmonic 0.00 3.87 3.87 ODCM (BSEP)B-8 Rev. 30 1 TABLE B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY*Noble Gas Vi Total Body B, Gamma Air Radionuclides (mrem/yr rmrad/yr'(gCi/sec) ,pCi/sec)Kr-83m 1.55E-09 4.62E-07 Kr-85m 6.42E-05 9.54E-05 Kr-85 9.59E-07 1.45E-06 Kr-87 2.88E-04 4.34E-04 Kr-88 7.66E-04 1.15E-03 Kr-89 4.14E-04 6.22E-04 Xe-131m 1.58E-05 2.52E-05 Xe-133m 1.20E-05 2.OOE-05 Xe-133 1.26E-05 2.OOE-05 Xe-135m 1.45E-04 2.20E-04 Xe-135 1.03E-04 1.55E-04 Xe-137 3.47E-05 5.25E-05 Xe-138 4.54E-04 6.81 E-04 Xe-139 1.05E-05 1.58E-05 Ar-41 5.48E-04 8.22E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-9 Rev. 30 I TABLE B-6 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.00 0.06 0.09 0.01 0.00 2 0.33 0.00 0.00 0.00 0.13 0.16 0.03 0.00 3 0.62 0.00 0.00 0.02 0.27 0.23 0.08 0.01 4 2.93 0.00 0.04 0.25 0.86 1.04 0.58 0.15 5 1.86 0.00 0.02 0.18 0.48 0.52 0.41 0.24 6 0.62 0.00 0.02 0.11 0.22 0.20 0.06 0.00 7 0.57 0.00 0.04 0.16 0.22 0.13 0.02 0.00 Total 7.11 0.01 0.13 0.74 2.24 2.38 1.19 0.41 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.29 6.29 Harmonic 0.00 4.62 4.62 ODCM (BSEP)B-1 0 Rev. 30 1 TABLE B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr rmrad/yr"_, jCi/sec) (,Ci/sec)Kr-83m 3.11 E-09 1.10E-06 Kr-85m 1.07E-04 1.59E-04 Kr-85 1.55E-06 2.35E-06 Kr-87 4.73E-04 7.11 E-04 Kr-88 1.23E-03 1.84E-03 Kr-89 7.51E-04 1.13E-03 Xe-131m 2.69E-05 4.35E-05 Xe-133m 2.05E-05 3.46E-05 Xe-133 2.19E-05 3.51E-05 Xe-135m 2.48E-04 3.77E-04 Xe-135 1.70E-04 2.55E-04 Xe-1 37 6.53E-05 9.87E-05 Xe-138 7.49E-04 1.12E-03 Xe-139 2.22E-05 3.33E-05 Ar-41 8.91 E-04 1.34E-03*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-11 Rev. 30 1 TABLE B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%)PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.00 0.01 2 0.21 0.00 0.00 0.00 0.05 0.10 0.06 3 1.13 0.00 0.00 0.03 0.28 0.50 0.32 4 7.30 0.01 0.15 0.63 2.50 2.51 1.50 5 5.15 0.03 0.09 0.30 1.21 1.99 1.53 6 1.04 0.01 0.06 0.32 0.33 0.24 0.08 7 0.41 0.01 0.12 0.10 0.13 0.03 0.02 Total 15.26 0.06 0.42 1.38 4.51 5.37 3.52 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity I AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 7.81 7.81 Harmonic 0.00 6.63 6.63 ODCM (BSEP)B-1 2 Rev. 30 1 TABLE B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr I mrad/yr (pLCiIsec) ptC iI sec)Kr-83m 1.05E-09 2.15E-07 Kr-85m 5.81 E-05 8.63E-05 Kr-85 9.08E-07 1.38E-06 Kr-87 2.66E-04 4.OOE-04 Kr-88 7.39E-04 1.11 E-03 Kr-89 3.12E-04 4.69E-04 Xe-131m 1.39E-05 2.19E-05 Xe-133m 1.06E-05 1.73E-05 Xe-133 1.08E-05 1.69E-05 Xe-135m 1.23E-04 1.86E-04 Xe-135 9.52E-05 1.43E-04 Xe-1 37 2.40E-05 3.62E-05 Xe-138 4.13E-04 6.19E-04 Xe-139 5.31 E-06 7.98E-06 Ar-41 5.12E-04 7.69E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-13 Rev. 30 1 TABLE B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.04 0.00 0.00 0.01 0.02 0.01 0.00 0.00.2 0.06 0.00 0.00 0.02 0.03 0.01 0.00 0.00 3 0.26 0.00 0.01 0.12 0.10 0.03 0.00 0.00 4 1.50 0.00 0.06 0.39 0.68 0.31 0.04 0.01 5 1.67 0.00 0.04 0.28 0.96 0.39 0.00 0.00 6 0.72 0.00 0.03 0.16 0.35 0.16 0.00 0.00 7 0.67 0.01 0.07 0.25 0.24 0.10 0.00 0.00 Total 4.91 0.02 0.21 1.23 2.38 1.01 0.05 0.01 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity FT .MAXIMUM WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 4.31 4.31 Harmonic 0.00 3.15 3.15 ODCM (BSEP)B-1 4 Rev. 30 TABLE B-11 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr mrti/emly (gi Isec)Kr-83m 8.29E-10 2.29E-07 Kr-85m 3.88E-05 5.76E-05 Kr-85 5.93E-07 8.99E-07 Kr-87 1.76E-04 2.65E-04 Kr-88 4.77E-04 7.17E-04 Kr-89 2.42E-04 3.64E-04 Xe-131 m 9.43E-06 1.50E-05 Xe-133m 7.20E-06 1.19E-05 Xe-133 7.43E-06 1.17E-05 Xe-1 35m 8.55E-05 1.30E-04 Xe-1 35 6.29E-05 9.46E-05 Xe-137 2.OOE-05 3.02E-05 Xe-1 38 2.75E-04 4.12E-04 Xe-139 6.19E-06 9.30E-06 Ar-41 3.37E-04 5.05E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-15 Rev. 30 I TABLE B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.09 0.00 0.00 0.01 0.03 0.03 0.02 0.00 2 0.14 0.00 0.00 0.01 0.05 0.05 0.02 0.00 3 0.29 0.00 0.01 0.06 0.12 0.08 0.02 0.00 4 1.15 0.00 0.06 0.13 0.30 0.41 0.19 0.05 5 1.23 0.00 0.01 0.13 0.24 0.50 0.34 0.01 6 0.70 0.00 0.02 0.05 0.16 0.24 0.21 0.02 7 0.69 0.00 0.04 0.09 0.16 0.23 0.14 0.03 Total 4.28 0.01 0.14 0.48 1.05 1.54 0.95 0.11 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.27 6.27 Harmonic 0.00 4.29 4.29 ODCM (BSEP)B-1 6 Rev. 30 TABLE B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides I mrem/yr mrad/yr Kr-83m 8.52E-10 2.44E-07 Kr-85m 3.84E-05 5.70E-05 Kr-85 5.86E-07 8.88E-07 Kr-87 1.73E-04 2.61 E-04 Kr-88 4.71 E-04 7.07E-04 Kr-89 2.41 E-04 3.62E-04 Xe-131m 9.38E-06 1.49E-05 Xe-133m 7.17E-06 1.18E-05 Xe-133 7.42E-06 1.17E-05 Xe-135m 8.42E-05 1.28E-04 Xe-135 6.23E-05 9.36E-05 Xe-137 2.OOE-05 3.02E-05 Xe-138 2.70E-04 4.06E-04 Xe-139 6.45E-06 9.68E-06 Ar-41 3.32E-04 4.98E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-17 Rev. 30 I TABLE B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.01 0.03 0.06 0.04 0.02 2 0.20 0.00 0.00 0.02 0.04 0.06 0.06 0.01 3 0.29 0.00 0.00 0.04 0.08 0.09 0.06 0.01 4 1.34 0.00 0.06 0.17 0.34 0.44 0.25 0.07 5 1.13 0.00 0.02 0.04 0.20 0.44 0.41 0.01 6 0.62 0.00 0.04 0.06 0.15 0.19 0.15 0.02 7 0.60 0.00 0.02 0.06 0.17 0.24 0.09 0.02 Total 4.33 0.02 0.15 0.42 1.02 1.51 1.07 0.16 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.49 6.49 Harmonic 0.00 4.38 4.38 ODCM (BSEP)B-1 8 Rev. 30 TABLE B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yrj jpCi/sec ,/sec)Kr-83m 1.15E-09 3.88E-07 Kr-85m 4.49E-05 6.67E-05 Kr-85 6.69E-07 1.01 E-06 Kr-87 2.01 E-04 3.02E-04 Kr-88 5.35E-04 8.04E-04 Kr-89 2.86E-04 4.30E-04 Xe-131m 1.11E-05 1.79E-05 Xe-133m 8.49E-06 1.42E-05 Xe-133 8.92E-06 1.42E-05 Xe-135m 1.OOE-04 1.52E-04 Xe-135 7.20E-05 1.08E-04 Xe-137 2.39E-05 3.61 E-05 Xe-138 3.16E-04 4.75E-04 Xe-139 7.36E-06 1.10E-05 Ar-41 3.82E-04 5.74E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-19 Rev. 30 I TABLE B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.28 0.00 0.00 0.02 0.09 0.13 0.04 0.00 2 0.27 0.00 0.00 0.02 0.10 0.09 0.04 0.01 3 0.43 0.00 0.00 0.11 0.17 0.10 0.05 0.00 4 1.74 0.00 0.05 0.22 0.53 0.57 0.29 0.08 5 0.98 0.00 0.01 0.05 0.20 0.36 0.34 0.02 6 0.70 0.00 0.02 0.08 0.08 0.26 0.27 0.00 7 0.66 0.00 0.03 0.10 0.15 0.22 0.14 0.02 Total 5.06 0.01 0.11 0.59 1.32 1.72 1.18 0.13 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I I I I AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.31 6.31 Harmonic 0.00 4.58 4.58 ODCM (BSEP)B-20 Rev. 30 TABLE B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr Kr-83m 1.31 E-09 3.79E-07 Kr-85m 5.42E-05 8.06E-05 Kr-85 8.09E-07 1.22E-06 Kr-87 2.44E-04 3.68E-04 Kr-88 6.46E-04 9.70E-04 Kr-89 3.57E-04 5.37E-04 Xe-131 m 1.33E-05 2.13E-05 Xe-133m 1.01 E-05 1.69E-05 Xe-133 1.06E-05 1.69E-05 Xe-135m 1.23E-04 1.87E-04 Xe-135 8.71E-05 1.31E-04 Xe-137 3.01 E-05 4.55E-05 Xe-138 3.85E-04 5.79E-04 Xe-139 9.15E-06 1.37E-05 Ar-41 4.64E-04 6.96E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-21 Rev. 30 1 TABLE B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.24 0.00 0.00 0.03 0.08 0.08 0.05 0.01 2 0.24 0.00 0.00 0.02 0.09 0.10 0.03 0.01 3 0.42 0.00 0.01 0.09 0.14 0.14 0.05 0.00 4 2.81 0.00 0.06 0.25 0.69 1.07 0.69 0.06 5 1.21 0.00 0.01 0.07 0.30 0.56 0.26 0.00 6 0.62 0.00 0.01 0.05 0.12 0.29 0.14 0.00 7 0.72 0.00 0.03 0.11 0.23 0.26 0.08 0.01 Total 6.27 0.01 0.12 0.61 1.64 2.50 1.30 0.09 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.28 6.28 Harmonic 0.00 4.75 4.75 ODCM (BSEP)B-22 Rev. 30 1 TABLE B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY*Noble Gas Vi Total Body B, Gamma Air Radionuclides I m re m/yr (mrad/yrJ&#xfd;t, pCi/ sec ) (gCi/ sec)Kr-83m 1.45E-09 3.36E-07 Kr-85m 6.52E-05 9.96E-05 Kr-85 9.75E-07 1.48E-06 Kr-87 2.95E-04 4.45E-04 Kr-88 7.77E-04 1.17E-03 Kr-89 4.48E-04 6.73E-04 Xe-131 m 1.58E-05 2.52E-05 Xe-133m 1.20E-05 1.99E-05 Xe-133 1.26E-05 1.99E-05 Xe-135m 1.51 E-04 2.30E-04 Xe-135 1.05E-04 1.58E-04 Xe-137 3.81 E-05 5.76E-05 Xe-1 38 4.66E-04 7.OOE-04 Xe-139 1.16E-05 1.74E-05 Ar-41 5.61 E-04 8.41 E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-23 Rev. 30 I TABLE B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT F- MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.12 0.00 0.00 0.02 0.04 0.06 0.00 0.00 2 0.19 0.00 0.00 0.02 0.08 0.07 0.02 0.00 3 0.33 0.00 0.00 0.05 0.14 0.10 0.04 0.00 4 4.02 0.00 0.05 0.24 0.88 2.03 0.78 0.03 5 1.53 0.00 0.02 0.06 0.29 0.90 0.26 0.00 6 0.81 0.00 0.01 0.06 0.17 0.34 0.23 0.00 7 0.82 0.00 0.03 0.12 0.24 0.31 0.13 0.00 Total 7.84 0.01 0.12 0.56 1.83 3.81 1.46 0.04 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.37 6.37 Harmonic 0.00 5.01 5.01 ODCM (BSEP)B-24 Rev. 30 TABLE B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr (l, Ci/sec,) (,iCi/ sec)Kr-83m 1.45E-09 3.61 E-07 Kr-85m 6.40E-05 9.51 E-05 Kr-85 9.58E-07 1.45E-06 Kr-87 2.89E-04 4.36E-04 Kr-88 7.63E-04 1.15E-03 Kr-89 4.38E-04 6.57E-04 Xe-131m 1.56E-05 2.48E-05 Xe-133m 1.19E-05 1.96E-05 Xe-133 1.24E-05 1.96E-05 Xe-135m 1.48E-04 2.24E-04 Xe-135 1.03E-04 1.55E-04 Xe-1 37 3.73E-05 5.63E-05 Xe-1 38 4.56E-04 6.85E-04 Xe-139 1.13E-05 1.69E-05 Ar-41 5.49E-04 8.24E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-25 Rev. 30 I TABLE B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.10 0.00 0.00 0.00 0.02 0.04 0.03 0.00 2 0.21 0.00 0.00 0.01 0.06 0.11 0.02 0.00 3 0.48 0.00 0.00 0.04 0.14 0.22 0.08 0.00 4 3.69 0.00 0.05 0.23 0.77 1.83 0.69 0.10 5 1.55 0.00 0.01 0.08 0.36 0.94 0.16 0.00 6 0.68 0.00 0.02 0.04 0.15 0.36 0.10 0.00 7 0.90 0.01 0.05 0.08 0.30 0.38 0.07 0.00 Total 7.60 0.01 0.13 0.50 1.80 3.89 1.17 0.10 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity ____AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.34 6.34 Harmonic 0.00 4.96 4.96 ODCM (BSEP)B-26 Rev. 30 TABLE B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr (g, ifsec),(&#xfd;Ci/
sec,)Kr-83m 1.75E-09 5.79E-07 Kr-85m 6.69E-05 9.93E-05 Kr-85 9.93E-07 1.50E-06 Kr-87 2.98E-04 4.49E-04 Kr-88 7.92E-04 1.19E-03 Kr-89 4.32E-04 6.50E-04 Xe-131m 1.66E-05 2.67E-05 Xe-133m 1.27E-05 2.12E-05 Xe-133 1.33E-05 2.13E-05 Xe-135m 1.51 E-04 2.29E-04 Xe-135 1.07E-04 1.61 E-04 Xe-137 3.64E-05 5.51 E-05 Xe-138 4.70E-04 7.06E-04 Xe-139 1.05E-05 1.58E-05 Ar-41 5.67E-04 8.51 E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-27 Rev. 30 I TABLE B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT F- MAXIMUM WIND SPEED (m/sec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.37 0.00 0.00 0.01 0.12 0.20 0.04 0.00 2 0.45 0.00 0.00 0.02 0.15 0.24 0.05 0.00 3 0.68 0.00 0.01 0.08 0.25 0.28 0.07 0.00 4 3.10 0.00 0.06 0.26 0.69 1.32 0.68 0.10 5 1.51 0.00 0.01 0.10 0.44 0.84 0.11 0.00 6 0.56 0.00 0.03 0.09 0.23 0.20 0.01 0.00 7 0.74 0.00 0.04 0.13 0.34 0.21 0.01 0.00 Total 7.41 0.01 0.14 0.67 2.21 3.29 0.98 0.11 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity I Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 6.02 6.02 Harmonic 0.00 4.61 4.61 ODCM (BSEP)B-28 Rev. 30 TABLE B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY*Noble Gas V1 Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr[, tiCi/sec ) (, Ci/ sec)Kr-83m 1.34E-09 4.89E-07 Kr-85m 5.04E-05 7.49E-05 Kr-85 7.56E-07 1.15E-06 Kr-87 2.24E-04 3.37E-04 Kr-88 6.07E-04 9.11 E-04 Kr-89 2.93E-04 4.41 E-04 Xe-131 m 1.26E-05 2.03E-05 Xe-133m 9.63E-06 1.61 E-05 Xe-133 1.01 E-05 1.61 E-05 Xe-135m 1.09E-04 1.65E-04 Xe-135 8.11 E-05 1.22E-04 Xe-137 2.38E-05 3.60E-05 Xe-138 3.52E-04 5.28E-04 Xe-1 39 5.78E-06 8.68E-06 Ar-41 4.28E-04 6.42E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-29 Rev. 30 I TABLE B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.31 0.00 0.00 0.04 0.19 0.08 0.01 0.00 2 0.40 0.00 0.00 0.02 0.26 0.11 0.00 0.00 3 0.44 0.00 0.00 0.06 0.25 0.13 0.00 0.00 4 1.50 0.00 0.04 0.26 0.54 0.49 0.16 0.01 5 1.14 0.00 0.03 0.11 0.44 0.47 0.08 0.01 6 0.47 0.00 0.03 0.11 0.25 0.06 0.00 0.00 7 0.53 0.00 0.02 0.11 0.30 0.09 0.00 0.00 Total 4.79 0.01 0.14 0.71 2.22 1.43 0.25 0.02 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 5.02 5.02 Harmonic 0.00 3.80 3.80 ODCM (BSEP)B-30 Rev. 30 1 TABLE B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr 1' mrad/yrhjpCi/sec ) (, Ci/ sec,)Kr-83m 1.01 E-09 3.71 E-07 Kr-85m 3.96E-05 5.89E-05 Kr-85 6.01E-07 9.11E-07 Kr-87 1.76E-04 2.65E-04 Kr-88 4.86E-04 7.29E-04 Kr-89 2.10E-04 3.15E-04 Xe-131 m 9.88E-06 1.59E-05 Xe-133m 7.57E-06 1.26E-05 Xe-133 7.89E-06 1.26E-05 Xe-135m 8.24E-05 1.25E-04 Xe-135 6.41 E-05 9.63E-05 Xe-137 1.63E-05 2.47E-05 Xe-138 2.75E-04 4.12E-04 Xe-139 3.71 E-06 5.57E-06 Ar-41 3.38E-04 5.07E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-31 Rev. 30 I TABLE B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.21 0.00 0.00 0.02 0.13 0.05 0.00 0.00 2 0.25 0.00 0.00 0.04 0.18 0.02 0.00 0.00 3 0.32 0.00 0.01 0.11 0.18 0.02 0.00 0.00 4 0.85 0.00 0.03 0.25 0.34 0.20 0.04 0.00 5 0.88 0.00 0.02 0.14 0.32 0.33 0.06 0.01 6 0.39 0.00 0.03 0.10 0.19 -0.06 0.00 0.00 7 0.43 0.00 0.04 0.14 0.21 0.03 0.00 0.00 Total 3.33 0.01 0.13 0.81 1.55 0.71 0.11 0.01 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 .4.49 4.49 Harmonic 0.00 3.29 3.29 ODCM (BSEP)B-32 Rev. 30 TABLE B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY*Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr" (, ICi/sec ) (&#xfd;[, sc Kr-83m 9.83E-10' 3.64E-07 Kr-85m 3.83E-05 5.69E-05 Kr-85 5.83E-07 8.83E-07 Kr-87 1.70E-04 2.55E-04 Kr-88 4.72E-04 7.08E-04 Kr-89 1.95E-04 2.93E-04 Xe-131m 9.58E-06 1.54E-05 Xe-133m 7.34E-06 1.23E-05 Xe-133 7.64E-06 1.22E-05 Xe-135m 7.85E-05 1.19E-04 Xe-135 6.21 E-05 9.33E-05 Xe-137 1.50E-05 2.27E-05 Xe-138 2.64E-04 3.97E-04 Xe-139 3.48E-06 5.23E-06 Ar-41 3.26E-04 4.90E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-33 Rev. 30 1 TABLE B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (misec)Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.19 0.00 0.00 0.04 0.14 0.01 0.00 0.00 2 0.25 0.00 0.00 0.05 0.18 0.02 0.00 0.00 3 0.30 0.00 0.00 0.13 0.13 0.04 0.00 0.00 4 0.88 0.00 0.02 0.36 0.29 0.14 0.05 0.02 5 0.72 0.00 0.02 0.12 0.29 0.18 0.08 0.03 6 0.31 0.00 0.03 0.09 0.09 0.09 0.01 0.00 7 0.43 0.01 0.05 0.15 0.18 0.05 0.00 0.00 Total 3.09 0.01 0.12 0.94 1.30 0.52 0.14 0.05 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0 0.95 2.42 14.40 6.83 9.47 13.10 Velocity ___ ___ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 4.42 4.42 Harmonic 0.00 3.13 3.13 ODCM (BSEP)B-34 Rev. 30 1 TABLE B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY*Noble Gas Radionuclides Vi Total Body Bi Gamma Air mrem/yr" (mrad/yr jiC i/ sec ) iCi/ sec)Kr-83m 8.53E-10 2.74E-07 Kr-85m 3.71E-05 5.52E-05 Kr-85 5.69E-07 8.62E-07 Kr-87 1.67E-04 2.51 E-04 Kr-88 4.61 E-04 6.92E-04 Kr-89 1.97E-04 2.96E-04 Xe-131m 9.13E-06 1.46E-05 Xe-133m 6.99E-06 1.16E-05 Xe-133 7.23E-06 1.14E-05 Xe-135m 7.75E-05 1.18E-04 Xe-135 6.03E-05 9.06E-05 Xe-137 1.53E-05 2.31 E-05 Xe-138 2.59E-04 3.89E-04 Xe-1 39 3.77E-06 5.66E-06 Ar-41 3.20E-04 4.80E-04*The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM (BSEP) B-35 Rev. 30 I TABLE B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%)PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec) 1 Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.04 0.12 0.01 0.00 0.00 2 0.16 0.00 0.00 0.03 0.11 0.02 0.00 0.00 3 0.25 0.00 0.00 0.10 0.12 0.02 0.00 0.00 4 0.91 0.00 0.03 0.29 0.36 0.16 0.05 0.01 5 0.94 0.00 0.02 0.12 0.34 0.22 0.14 0.09 6 0.42 0.00 0.03 0.12 0.16 0.05 0.04 0.02 7 0.36 0.00 0.03 0.16 0.13 0.03 0.00 0.00 Total 3.21 0.01 0.12 0.86 1.34 0.52 0.23 0.12 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I I _AVERAGE WIND SPEED (m/sec)Mean Ground Elevated Combined Arithmetic 0.00 4.80 4.80 Harmonic 0.00 3.28 3.28 ODCM (BSEP)B-36 Rev. 30 LIST OF TABLES Title Table No.APPENDIX C C-1 C-2 C-3 P~qe PARAMETERS FOR COW AND GOAT MILK PATHWAYS .....................
C-14 PARAMETERS FOR THE MEAT PATHWAY ...........................................
C-15 PARAMETERS FOR VEGETABLE PATHWAY ........................................
C-16 ODCM (BSEP)C-1 Rev. 25 APPENDIX C DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with 1OCFR 20 and Appendix I of 10CFR50 for gaseous effluents.
These dose parameters Pi and R 1 were calculated using the methodology outlined in NUREG 0133, Regulatory Guide 1.109 Revision 1, and letter to J. W.Davis, "Dose Factors for Hf-181 and SN-113", BSEP File: B10-10530, May 24, 1988. The following sections provide the specific methodology which was utilized in calculating the Pi and R, values for the various exposure pathways.C.1 CALCULATION OF Pi The parameter Pi contained in the radioiodine and particulate portion of Section 3.2, includes pathway transport parameters of the ith radionuclide, the receptor's usage of the pathway media and the dosimetry of the exposure.
Pathway usage rates and the internal dosimetry are functions of the receptor's age; however, the youngest age group, the infant, will always receive the maximum dose under the exposure conditions for ODCM, Section 1, 3.11.2.1 (b). For the infant exposure, separate values of Pi may be calculated for the inhalation pathway which is combined with a W parameter based on (X/Q), and the food (milk) and ground pathway which is combined with a W parameter normally based on (D/Q), except for tritium. The following sections provide in detail the methodology which was used in calculating the Pi values for inclusion into this ODCM.C.1.1 Inhalation Pathway P, K' (BR) DFAj (C.1-1)where: P , dose parameter for radionuclide i for the inhalation pathway, mrem/yr per P.Ci/m 3 K' = a constant of unit conversion 106 pCi/ICi BR the breathing rate of the infant age group, m 3/yr DFA the maximum organ inhalation dose factor for the infant age group for radionuclide i, mrem/pCi ODCM (BSEP) C-2 Rev. 25 The age group considered is the infant group. The infant's breathing rate is taken as 1400 m 3/yr from Table E-5 of Regulatory Guide 1.109 Revision 1.The inhalation dose factors for the infant, DFAi, are presented in Table E-10 of Regulatory Guide 1.109, BSEP File: B10-10530, Letter to J. W.Davis "Dose Factors for Hf-181 and Sn-113, "May 24, 1988, and NUREG CR4653 for Am-241, in units of mrem/pCi.
The total body is considered as an organ in the selection of DFA 1.The incorporation of breathing rate of an infant and the unit conversion factor results in the following:
P = 1.4 x 10 9 DFAi (C.1-2)C.1.2 Ground Plane Pathway P= K' K"DFGi(1-e--)/X, (C.1-3)where: PiG = Dose parameter for radionuclide i for the ground plane pathway, mrem/yr per &#xfd;iCi/sec per m 2 K' = A constant of unit conversion
= 10 6 pCi/jCi K" = A constant of unit conversion
= 8760 hr/yr i = The radiological decay constant for radionuclide i, sec 1 t = The exposure period= 3.15 x 107 sec (1 year)DFGI = The ground plane dose conversion factor for radionuclide i, mrem/hr per pCi/m 2 The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide.
The ground plane dose conversion factors for radionuclide i, DFGi, are presented in Table E-6 of Regulatory Guide 1.109, Revision 1. BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for Am-241.ODCM (BSEP)C-3 Rev. 25 Resolution of the units yields: P = 8.76 x 109 DFGj (1 -ext)/ Xj (C.1 -4)C.1.3 Milk pP K'r QF (Uap) Fm DEL e t , (C.1-5)YP (Xi, +2.) DL C15 where: P = Dose parameter for radionuclide i for the cow milk or goat milk pathway, mrem/yr per [tCi/sec per mz K' = A constant of unit conversion
= 106 pCi/OCi QF -The cow's or goat's consumption rate of feed, kg/day (wet weight)Uap = The infant's milk consumption rate, liters/yr YP = The agricultural productivity by unit area, kg/m 2 Fm = The stable element transfer coefficient, pCi/liter per pCi/day r = Fraction of deposited activity retained on cow's or goat's feed grass DFL = The maximum organ ingestion dose factor for radionuclide i, mrem/pCi X = The radiological decay constant for radionuclide i sec 1 X = The decay constant for removal of activity on leaf and plant surfaces by weathering, sec'= 5.73 x 10-7 sec 1 (corresponding to a 14 day half-time) tf = The transport time from pasture to cow or goat to milk to infant, sec A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering processes.
ODCM (BSEP)C-4 Rev. 25 Various parameters which were utilized to determine the Pi values for the cow and goat milk pathways are provided in Table C-1. Table E-1 of Regulatory Guide 1. 109, Revision 1, provides the stable element transfer coefficients, Fm, and Table E-1 4 of the same regulatory guide provides the ingestion dose factors, DFL 1 , BSEP File: B10-10530, Letter to J. W. Davis"Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241, for the infant's organs. The organ with the maximum value of DFLi was used in the determination of Pi for this pathway. The incorporation of the various constants of Table C-1 into Equation C. 1-5 results in the following:
For cow's milk for radioiodines and particulates:
rFm PiM 2.14 x11 0 0  -- DFL e"'Xrf (C.1-6)For the goat milk pathway for radioiodines and particulates:
rFm PiM = 2.8 x1l0 9 -DFL e?, t f (C.1-7)Xi + X,.For tritium, the concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.PT = K'K"'FmQFUapDFLT
[0.75 (0.5/H)] (C.1-8)where: PTM Dose parameter for tritium for the cow milk and goat milk pathways, mrem/yr per &#xfd;iCi/m 3 K"' = A constant of unit conversion 101 gm/kg H = Absolute humidity of the atmosphere, gm/m 3 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water DFLT = Maximum organ ingestion dose factor for tritium, mrem/pCi ODCM (BSEP)C-5 Rev. 25 C.2 CALCULATION OF Ri The Radioiodine and Particulate ODCM Specification 7.3.9 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations.
The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations.
R 1 values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways.
The methodology which was utilized to calculate these values is presented below.C.2.1 Inhalation Pathway R = K' (BR)a (DFA,)a (C.2-1)where: Ri, Dose factor for each identified radionuclide i of the organ of interest, mrem/yr per [LCi/m 3 K' A constant of unit conversion 106 pCi/PLCi (BR)a Breathing rate of the receptor of age group a, m 3/yr (DFAi)a Organ inhalation dose factor for radionuclide i for the receptor of age group a, mrem/pCi ODCM (BSEP)C-6 Rev. 25 The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109, Revision 1.Age Group (a) Breathing Rate (m 3/yr)Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.C.2.2 Ground Plane Pathway R1G = I K'K"(SF) DFGI (1-e--i t)/IX (C.2-2)where: RIG = Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest, mrem/yr per pCi/sec per m 2 K' = A constant of unit conversion 106 pCi/&#xfd;ICi K" = A constant of unit conversion 8760 hr/year i = The radiological decay constant for radionuclide i, sec1 t = The exposure time, sec 4.73 x 108 sec (15 years)DFGj The ground plane dose conversion factor for radionuclide i; mrem/hr per pCi/m 2 ODCM (BSEP)C-7 Rev. 25 SF The shielding factor (dimensionless)
Ii = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor lI is equal to one. For radioiodines, the value of li may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2.A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.C.2.3 Grass-Cow or Goat Milk Pathway Rim =IK'QFUaPF (DFL )a e-i" f,-r(1_- eB-NEe (1 -Jr(l- e4 1E+e ) + B v(1-e ).eb  YpX,, P ,i J (1- Pfi (C.2-3)where: RiM Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, mrem/yr per iLCi/sec per Mz K' = A constant of unit conversion 106 pCi/jICi QF = The cow's or goat's feed consumption rate. kg/day (wet weight)Uap = The receptor's milk consumption rate for age group a, liters/yr Yp = The agricultural productivity by unit area of pasture feed grass, kg/m 2 Y = The agricultural productivity by unit area of stored feed, kg/m 2 Fm = The stable element transfer coefficients, pCi/liter per pCi/day ODCM (BSEP)C-8 Rev. 25 r = Fraction of deposited activity retained on cow's feed grass (DFLi)a = The organ ingestion dose factor for radionuclide i for the receptor in age group a, mrem/pCi E, = ki + kW X = The radiological decay constant for radionuclide i, sec 1 k = The decay constant for removal of activity on leaf and plant surfaces by weathering sec1 5.73x10 7 sec" (corresponding to a 14 day half-life) tf = The transport time from feed to cow or goat to milk, to receptor, sec th = The transport time from harvest to cow or goat consumption, sec tb = Period of time that soil is exposed to gaseous effluents, sec BR, = Concentration factor for uptake of radionuclide i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil)P = Effective surface density for soil, Kg (dry soil)/m 2 fp = Fraction of the year that the cow or goat is on pasture fS = Fraction of the cow feed that is pasture grass while the cow is on pasture te = Period of pasture grass and crop exposure during the growing season, sec II = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of lI may vary. However, a value of 1.0 was used in calculating the R values Tables 3.3-9 through 3.3-16.Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information.
The value of fp was 0.667 based upon an 8-month grazing period.ODCM (BSEP)C-9 Rev. 25 Table C-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.The concentration of tritium in milk is based on the airborne concentration rather than the deposition.
Therefore, the R 1 is based on X/Q: RT. K'Km'FMQFUaP(DFLi)B[0.75( 0.5J (C.2-4)where: RTM = Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per jiCi/m 3 K' = A constant unit of conversion, 106 pCi/&#xfd;Ci K'" = A constant unit of conversion
= 103gm/kg H = Absolute humidity of the atmosphere, gm/m 3 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water Other parameters and values as defined previously.
A value for H of 8 grams/meter 3 , was used in lieu of site-specific information.
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
R E =IiK'QFUapFf (DFL),)a e--s fpfS r(1 -e-Ee + B ,(1 -e- ). + (1- fPfS) r(1 -e-"te +
e ,t}Yp--E, Px-i Ys?,E, Pki (C.2-5)where: RiB = Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, mrem/yr per iCi/sec per M2 ODCM (BSEP)C-10 Rev. 25 Ff = The stable element transfer coefficients, pCi/Kg per pCi/day UP = The receptor's meat consumption rate for age group a, kg/yr t = The transport time from slaughter to consumption, sec th The transport time from harvest to animal consumption, sec te Period of pasture grass and crop exposure during the growing season, sec I, Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor I, is equal to one. For radioiodines, the value of lI may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8.All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used in calculating Ri for the meat pathway.The concentration of tritium in meat is based on its airborne concentration rather than the deposition.
Therefore, R 1 is based on X/Q.RTB K'KfFfQFUab(DFLI)aL0.75( 0.5)] (C.2-6)where: RTB Dose factor for the meat ingestion pathway for tritium for any organ of interest, mrem/yr per jCi/m 3 All other terms are as defined in Equation C.2-4 and C.2-5, above.C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
ODCM (BSEP)C-11 Rev. 25 Riv =IiK'(DFLi).
u L fL e [ r(1 -e -'E tie ) BB iv (1 -e--Xitb I f h [r -'eX 'i'e ) 1)aLe [ YVXE + P+i .v:(E t P )1i (C.2-7)where: Riv Dose factor for vegetable pathway for radio nuclide i for the organ of interest mrem/yr per pCi/sec per m-2 K' a constant of unit conversion 106 pCi/PCi L The consumption rate of fresh leafy vegetation by the receptor age group a, kg/yr s The consumption rate of stored vegetation by the receptor in age group a, kg/yr fg The fraction of the annual intake of stored vegetation grown locally fL The fraction of annual intake of fresh, leafy vegetables grown locally tL The average time between harvest of leafy vegetation and its consumption, sec th The average time between harvest of stored vegetation and its consumption, sec Yv The vegetation area density, kg/M 2 te Period of leafy vegetable exposure during growing season, sec Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5.All other factors were defined above.ODCM (BSEP)C-12 Rev. 25 Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculation of R 1.These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.
Therefore, the R 1 is bases on X/Q: RTv K'K- [uL fL +u fg](DFLi)a L.0750.51 (C.2-8)where: RTv Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per jiCi/m 3 All other terms remain the same as those in Equations C.2-4 and C.2-7.ODCM (BSEP)C-13 Rev. 25 QF (kg/i Yp (kg/n tf (seco r (DFLi)a Fm (pCi tb (seco Y, (kg/n Yp (kg/n th (seco Uap (lite TABLE C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS Parameter Value Reference (Reg. Guide 1.109, Rev. 1)day) 50 (cow) Table E-3 6 (goat) Table E-3 n 2) 0.7 Table E-15 nds) 1.73 x 10 5 (2 days) Table E-15 1.0 (radioiodines)
Table E-15 0.2 (particulates)
Table E-15 (mrem/pCi)
Each radionuclide Tables E-1 1 to E-1 4-/1 per pCi/day) Each stable element Table E-1 (cow)*Table E-2 (goat)**inds) 4.73 x 108 (15 yr) Table E-15 n 2) 2.0 Table E-15 n 2) 0.7 Table E-15 inds) 7.78 x 106 (90 days) Table E-15 rs/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 inds) 2.59 x 106 (pasture)
Table E-15 te (seco B,v pCi/Kg (wet weight)per pCi/Kg (dry soil)P Kg (dry soil)/m 2 5.18 x 106 (stored feed)Each stable element 240 Table E-1 Table E-15*Reference 1, BSEP File: B130-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.**Where goat data was not available, cow value Fm was assumed.ODCM (BSEP) C-14 Rev. 25 TABLE C-2 PARAMETERS FOR THE MEAT PATHWAY Parameter r Ff (pCi/Kg per pCi/day)Uap (Kg/yr)(DFLi)a (mrem/pCi)
Yp (kg/m 2)Y, (kg/mr 2)tb (seconds)t, (seconds)th (seconds)te (seconds)QF (kg/day)Biv pCi/Kg (wet weight)per pCi/Kg (dry soil)P kg (dry soil)/m 2 Value 1.0 (radioiodines) 0.2 (particulates)
Each stable element 0 infant 41 child 65 teen 110 adult Each radionuclide 0.7 2.0 4.73 x 108 (15 yr)1.73 x 106 (20 days)7.78 x 106 (90 days)2.59 x 106 (pasture)5.18 x 106 (stored feed)50 Each stable element 240 Reference (Reg. Guide 1.109, Rev. 1)Table E-15 Table E-15 Table E-1 *Table E-5 Table E-5 Table E-5 Table E-5 Tables E-11 to E-14 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-3 Table E-1 *Table E-15*Reference 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.ODCM (BSEP) C-15 Rev. 25 TABLE C-3 PARAMETERS FOR THE VEGETABLE PATHWAY Parameter r (dimensionless)(DFLi)a (mrem/Ci)U' (kg/yr) -Infant-Child-Teen-Adult Us (kg/yr) -Infant-Child-Teen-Adult tL (seconds)th (seconds)Yv (kg/M 2)te (seconds)tb (seconds)P (Kg[dry soil]/m 2)B j (pCi/Kg[wet weight]per pCi/kg [dry soil])Value 1.0 (radioiodines) 0.2 (particulates)
Each radionuclide 0 26 42 64 0 520 630 520 8.6 x 104 (1 day)5.18 x 106 (60 days)2.0 5.18 x 106 (60 days)4.73 x 108 (15 yr)240 Each stable element Reference (Reg. Guide 1.109, Rev. 1)Table E-1 Table E-1 Tables E-11 to E-14" Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-1**Reference 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.ODCM (BSEP)C-16 Rev. 25 APPENDIX D LOWER LIMIT OF DETECTION (LLD)The following discussion of LLD is taken from NUREG-0473, Rev. 2, February 1, 1980. It represents the bases for LLD footnotes (e) in Table 7.3.3-1, (e) in Table 7.3.3-2, (a) in Table 7.3.7-1, and (b) in Table 7.3.15-3 of the BSEP ODCM Specifications.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system (which may include radiochemical separation):
LLD = 4.66sb E-V. 2.22 x 10'. Y. exp(-,At)LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plants effluents, not environmental samples).The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
Typical values of E, V, Y, and At shall be used in the calculation.
ODCM (BSEP)D-1 Rev. 25 APPENDIX E RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Liquid Effluent Monitoring Instruments A. Liquid Radwaste Radioactivity Monitor 2-D12-RM-K60 B. Liquid Radwaste Effluent Flow Measurement 2-G16-FIT-N05 Device C. Main Service Water Effluent Radioactivity 1(2)-D12-RM-I4 Monitor D. Stabilization Pond Effluent Composite Sampler 2-DST-XE-502 E. Stabilization Pond Effluent Flow Measurement 2-DST-FIT-502 Device F. Condensate Storage Tank Level Indicating 1(2)-CO-LIT-i 1 Device G. Groundwater Extraction Effluent Composite 0-GWE-COMP Sampler 1 H. Groundwater Extraction Effluent Flow 0-GWE-FIT-1 Measurement Device 1. Stabilization Facility Effluent Composite 0-SDSF-COMF Sampler 2 J. Stabilization Facility Effluent Flow Measurement O-SDSF-FIT-2 Device II. Gaseous Effluent Monitoring Instruments
: 1. Main Stack Monitoring System a. Noble Gas Activity Monitor 2-D12-RM-23S (2-D1i2-RE-498
: b. Iodine Sampler Cartridge IRSH35 c. Particulate Sampler Filter IRSH35 Prefilt d. System Effluent Flow Rate 2-VA-FIQ-5902 Measurement Device e. Low Range Sampler Flow Rate 2-D12-FE-459 Measurement Device f. Mid/High Range Sampler Flow Rate 2-D12-FE-459(Measurement Device)4 57.605 7.6 160-SAMPLER->-SAMPLER-32)&#xfd;rs A or B&#xfd;rs A or B_-1 OR -2 7 ODCM (BSEP)E-1 Rev. 35 1 APPENDIX E (Cont'd)RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont'd)2. Reactor Building Ventilation Monitoring System a. Noble Gas Activity Monitor b. Iodine Sampler Cartridge c. Particulate Sampler Filter d. System Effluent Flow Rate Measurement Device e. Sampler Flow Rate Measurement Device 1 (2)-CAC-AQH-1264-3 1 (2)-CAC-AQH-1264-2 (collection cartridge only)1 (2)-CAC-AQH-1264-1 (collection filter only)1 (2)-VA-FIQ-3356 1 (2)-CAC-FI-1264
: 3. Turbine Building Ventilation Monitoring System a. Noble Gas Activity Monitor b. Iodine Sampler Cartridge (Recirculation Mode)Iodine Sampler Cartridge for Once Through Ventilation (Unit 2 only)c. Particulate Sampler Filter (Recirculation Mode)Particulate Sampler Filter Once Through Ventilation (Unit 2 only)d. System Effluent Flow Rate Measurement Device (Recirculation Mode)System Effluent Flow Rate Measurement Device for Once Through Ventilation (Unit 2 only)e. Low Range Sampler Flow Rate Measurement Device Sampler Flow Rate Measurement Device for Once Through Ventilation (Unit 2 only)f. Mid/High Range Sampler Flow Rate Measurement Device 1(2)-D12-RM-23 (1 (2)-D1 2-RE-4563) 1 (2)-IRTB32 Prefilters A or B 2-D1 2-OTV-FLT-03(04) 1 (2)-IRTB32 Prefilters A or B 2-D12-OTV-FLT-03(04) 1(2)-VA-FIQ-3358 2-VA-FIQ-7554 1 (2)-D 12-FE-4542 2-D12-FE-7559 1 (2)- D12-FE-4543 ODCM (BSEP)E-2 Rev. 351 APPENDIX E (Cont'd)RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont'd)4. Main Condenser Off-Gas Treatment System (AOG) Monitor a. Noble Gas Activity Monitor 1(2)-AOG-RM-103
: 5. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System a. Recombiner Train A 1. First Hydrogen Monitor 1 (2)-OG-AIT-4284
-Stream 1 2. Second Hydrogen Monitor 1 (2)-OG-AIT-4324
-Stream 2 b. Recombiner Train B 1. First Hydrogen Monitor 1 (2)-OG-AIT-4324
-Stream 1 2. Second Hydrogen Monitor 1 (2)-OG-AIT-4284
-Stream 2 6. Main Condenser Air Ejector Radioactivity Monitor a. Noble Gas Activity Monitor 1(2)-D12-RM-K601A 1 (2)-D12-RM-K601 B 7. Hot Shop Ventilation Monitoring System a. Iodine Sampler Cartridge b. Particulate Sampler Filter c. Sampler Flow Rate Measurement 2-D12-FI-6094 Device 8. Radioactive Materials Container and Storage Building Decontamination Facility a. Iodine Sampler Cartridge b. Particulate Sampler Filter c. Sampler Flow Rate Measurement Device ODCM (BSEP)E-3 Rev. 35 1 APPENDIX F LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS ODCM (BSEP)F-1 Rev. 25 FIGURE F-i Liquid Radwaste Effluent System HIGHWASTE WASTE WASTE PE HQUID WASTES COLLECTOR FILTER DEMINERALIZER LIQUD WATES ANK ANK REGENERATIONI MEDI LOW PURITY FLOORDRAN AUXILIARY F FLOOR DRAIN LIQUID WASTES COLLECTOR D DEMINERALIZER MONITORADIATION TANK FILTE R I H ! H TANKS / MONITORING BLOCK STATION VALVE LIQUID 44 I ADWUASpTEN IDETERGENT DETERGENT TO ET)ETERGENT
----- DRAIN DRAIN 10CFR0 VASTES TANKS FRFILTERS 42 SEC 10CF50 OI&deg;L LIMITS OILY WASTE SEPARATOR OIL DRUM ALTER SALT WATER SALT WATER IATER -ITANKS -- FILTER" POTENTIAL LIQUID RELEASE PATHWAYS LOW PURITY LOW ACTIVITY 0 MAIN SERVICE WATER DISCHARGE LIQUID WASTES LINES HAVE CONTINUOUS RADIOACTIVITY MONITORS.FLOOR DRAIN THE STABILIZATION POND EFFLUENT SYSTEM TO THE INTAKE CANAL HAS A PROPORTIONAL COMPOSITE SAMPLER FUEL CASK AND A FLOW MEASURING DEVICE.WASHDOWN K -CONCENTRATED RESIN PROCESSING 0 THE REACTOR BUILDING COMPONENT IWASTETANK AREA COOLING WATER (SERVICE WATER)LINE HAS CONTINUOUS RADIOACTIVITY MONITORS.LOW PURITY HIGH ACTIVITY LIQUID WASTES NOTES* SOLID RADWASTE SYSTEM -NOT USED LIQUID PROCESS HIGH INTEGRITY MEDIA CONTAINER STORAGE/BURIAL ODCM (BSEP)F-2 Rev. 26 FIGURE F-2 Gaseous Radwaste Effluent System 02 MONITORS 30 CONDENSER AIR EJECTION RAD MONITOR 02 MONITORS CONDENSER M2 MONITORS AIR EJECTION RAD MONITOR SJ E RECOMBINER A SUNIT, 2 -'-- 02N MONITORS ICONDENSERF1 H2 MONITOR'S
-- F I I I I tSWJAME 5 '' l II TRM 8 J -30 MINDELAY LIE CONDENSER AMR EJECTION RDMONITOR SECONDARY CONTAINMENT ISOLATION RAD MONITOR UNIT I TURBINE BUILDING IT1ALAROHEPg1 MONITORING VENTILATION EXHAUST F YTEMEY M UNIT ~ ~ FITE SYSTEMN BULDN 1- CHROARD ETIULATIO FOITORIN]VENTILATION EXHAUST FILTER SYSTEM SYSTEM VENT ON FILTER SY STEM ] P NE CARTRID OE A ND VEN~tAOTONFX&#xfd;USJ ILTRS""".................
i SAMPLER VENTILATION EXHAUST HEPAIFILTERSYTEM PARTICULATE FILTER MONITOR 'LW -LEVEL WAREH&#xfd;OUSE HER FLTER SYSTE j MT7TLATEFI L...SECONDARY CONTAINMENT ISOLATION RAD MONITOR UNIT 2 REACTOR BUILDING .. ......J- .... .VENTILATION MONITORN VENTIlLATION EXHAUST ISS M" UNIT 2 TURBINE BUILDING CHARCOAL AND HEPA VENTILATION MONITORING VENTILATION EXHAUST FILTER SYSTEM SYSTEM ONCE THROUGH VENTILATION EXHAUST (OPTIONAL)
GASEOUS GRADWASTE TOMEET I (AN.1 OCFRSS (EFFLUENT)
LIMITS NOTATIONS o OTHER PATHWAYS MONITORED FOR RELEASE-BUILDING EXFILTRATION
-CIRC WATER PIPING VENTILATION THE HCV-102 VALVE AUTOMATICALLY ISOLATES 15 MIN AFTER HIGH READING ON THE CORESPONDING CONDENSER AIR EJECTOR RAD MONITOR EACH VENTILATION MONITORING SYSTEM CONTAINS: NOBLE GAS ACTIVITY MONITOR-IODINE SAMPLER CARTRIDGE-PARTICULATE SAMPLER FILTER o SYSTEM FLOW MONITOR SAMPLER FLOW MONITOR ODCM (BSEP)F-3 Rev. 32 1 APPENDIX G ODCM SOFTWARE PACKAGE In order to minimize calculational errors and to facilitate the use of the ODCM, BSEP has developed an ODCM software package. All applicable calculations listed in the ODCM have been included in this software.During periods when the ODCM software is not available, the following alternate method may be used to assess dose or dose rates to the public from liquid or gaseous effluents:
Dt = (Dh x Ct)/Ch where: Dt = the unknown dose/dose rate for the time period Dh = the known dose/dose rate from historical data Ct = the total curies released for the time period Ch = the total curies used to calculate the known dose/dose rate When the ODCM software becomes available again, all doses to the public will be reassessed using the software package.ODCM (BSEP)G-1 Rev. 25 LIST OF TABLES Title Table No.APPENDIX H Pagie H-1 X/Q Values at the Standard Distances for Releases from the Stabilization Facility ....................................................................................
H-2 ODCM (BSEP)H-1 Rev. 35 TABLE H-1 x/Q Values at the Standard Distances for Releases from the Stabilization Facility Progress Energy -Brunswick Release Type: Annual Release Mode: Ground Level Variable:
Relative Concentration Sec./Cubic Meter)Calculated Points: Standard Model: Straight Line Gaussian Diffusion Period: 2006-2010 Number of Observations:
43738 Base Distance in Miles Sector 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 NNE 5.78E-05 1.69E-05 8.21 E-06 3.92E-06 1.48E-06 7.79E-07 4.86E-07 3.36E-07 2.48E-07 1.93E-07 1.55E-07 NE 1.10E-04 3.20E-05 1.56E-05 7.46E-06 2.80E-06 1.47E-06 9.12E-07 6.28E-07 4.64E-07 3.59E-07 2.88E-07 ENE 2.04E-04 5.97E-05 2.91 E-05 1.39E-05 5.26E-06 2.77E-06 1.73E-06 1.20E-06 8.86E-07 6.88E-07 5.54E-07 E 2.36E-04 6.88E-05 3.33E-05 1.60E-05 6.08E-06 3.23E-06 2.03E-06 1.41 E-06 1.05E-06 8.20E-07 6.63E-07 ESE 2.77E-04 8.04E-05 3.87E-05 1.86E-05 7.10E-06 3.78E-06 2.38E-06 1.66E-06 1.24E-06 9.70E-07 7.85E-07 SE 3.47E-04 1.01 E-04 4.85E-05 2.32E-05 8.88E-06 4.73E-06 2.98E-06 2.08E-06 1.55E-06 1.21 E-06 9.84E-07 SSE 6.69E-04 1.94E-04 9.29E-05 4.46E-05 1.71 E-05 9.13E-06 5.77E-06 4.03E-06 3.01 E-06 2.36E-06 1.91 E-06 S 6.39E-04 1.85E-04 8.91 E-05 4.27E-05 1.64E-05 8.73E-06 5.51 E-06 3.85E-06 2.87E-06 2.25E-06 1.82E-06 SSW 2.38E-04 6.95E-05 3.38E-05 1.62E-05 6.14E-06 3.25E-06 2.04E-06 1.41E-06 1.05E-06 8.18E-07 6.60E-07 SW 8.73E-05 2.55E-05 1.24E-05 5.94E-06 2.24E-06 1.18E-06 7.34E-07 5.06E-07 3.74E-07 2.90E-07 2.33E-07 WSW 5.67E-05 1.65E-05 8.08E-06 3.85E-06 1.44E-06 7.54E-07 4.67E-07 3.21 E-07 2.36E-07 1.82E-07 1.46E-07 W 5.40E-05 1.58E-05 7.70E-06 3.67E-06 1.38E-06 7.22E-07 4.49E-07 3.09E-07 2.28E-07 1.77E-07 1.42E-07 WNW 4.83E-05 1.41 E-05 6.88E-06 3.28E-06 1.23E-06 6.47E-07 4.03E-07 2.78E-07 2.05E-07 1.59E-07 1.28E-07 NW 4.80E-05 1.40E-05 6.85E-06 3.27E-06 1.23E-06 6.45E-07 4.01 E-07 2.76E-07 2.04E-07 1.58E-07 1.27E-07 NNW 5.48E-05 1.60E-05 7.82E-06 3.73E-06 1.41E-06 7.40E-07 4.61E-07 3.19E-07 2.36E-07 1.83E-07 1.47E-07 N 6.23E-05 1.82E-05 8.91E-06 4.26E-06 1.61E-06 8.47E-07 5.29E-07 3.65E-07 2.70E-07 2.10E-07 1.69E-07 ODCM (BSEP)H-2 Rev. 35}}

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