ML20214X095
| ML20214X095 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/03/1986 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20214X088 | List: |
| References | |
| PROC-861203, NUDOCS 8612100540 | |
| Download: ML20214X095 (17) | |
Text
.
BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)
REVISION 6 DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY 8612100S40 861203 PDR ADOCK 05000324 PDR l
p I
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TABLE OF CONTENTS Section Title Page List of Effective Pages.....................................
i Table of Contents...........................................
iii List of Tables..............................................
iv List of Figures.............................................
ix
1.0 INTRODUCTION
1-1 2-1 2.0 LIQUID EFFLUENTS............................................
2.1 Compliance with 10CFR20 (Liquids)....................
2-1 (Alarm / Trip Setpoint Determination) 2.2 Compliance with 10CFR50 (Liquids)....................
2-11 3.0 GASEOUS EFFLUENTS...........................................
3-1 3.1 Monitor Alarm Setpoint Determination.................
3-1 3.2 Compliance with 10CFR20 (Gaseous)....................
3-15 3.3 Compliance with 10CFR50 (Gaseous)....................
3-34 4.0 RADIOLOGICAL ENVIRONMENTAL........'..........................
4-1
~
MONITORING PROGRAM 5.0 INTERLABORATORY COMPARISON PROGRAM..........................
5-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)...........................
6-1 APPENDIX A - Meteorological Dispersion Factor...............
A-1 Computations APPENDIX B - Calculation of B and V Values................
B-1 f
f for the Elevated Plume APPENDIX C - Dose Parameters for Radioiodines,..............
C-1 Particulates, and Tritium APPENDIX D - Lower Limit of Detection (LLD).................
D-1 E-1 I
APPENDIX E - Radioactive Liquid and Gaseous.................
Effluent Monitoring Instrumentation Numbers F-1 APPENDIX F - Liquid and Gaseous Effluent System............
l Diagrams t
G-1 l
l APPENDIX G - ODCM Software Package..........................
(
LIST OF EFFECTIVE PAGES (Continued)
ODCM Page(s)
Revision A-22 4
A A-28 0
B B-33 0
C C-18 0
D D-2 1
E-1 4
E-2 3
E-3 4
F F-3 0
G-1 1
e i
i l
i i
l LIST OF TABLES No.
Title Py 2.1-1 MPCs for Selected Radionuclides.........................
2-10 2.2-1 A
Values for the Adult................................
2-14 g
3.1-1 Gaseous Source Terms....................................
3-13 3.1-2 Dose Factors and Constants..............................
3-14 1
3.2-1 Releases from Brunswick Steam Electric Plant............
3-29 3.2-2 Distance to Controlling Locations as Measured...........
3-30 from the Brunswick Plant Center 3.2-3 Distance to Site Boundaries Based Upon Brunswick........
3-31 Plant Center and Direction from the Stack 3.2-4 Dose Factors for Noble Cases and Daughters..............
3-32 3-33 3.2-5 P, Values for an Infant for the Brunswick Steam.........
EIectric Plant 3.3-1 thru R Values for the Brunswick Steam Electric Plant.........
3-50 3.3-19 4-2 4.0-1 Radiological Environmental Monitoring Program...........
A-1 X/Q Values at the Special Locations for Releases........
A-5 from the Turbine Buildings A-2 Depleted X/Q Values at the Special Locations for........
A-6 Releases from the Turbine Buildings A-3 D/Q Values at the Special Locations for Releases........
A-7 from the Turbine Buildings A-4 X/Q Values at the Standard Distances for Releases.......
A-8 from the Turbine Buildings A-5 Depleted X/Q Values at the Standard Distances for.......
A-9 Releases from the Turbine Buildings A-6 D/Q Values at the Standard Distances for Releases.......
A-10 from the Turbine Buildings A-7 X/Q Values at the Special Locations for Releases........
A-11 from the Reactor Buildings f
?
LIST OF TABLES (continued)
No.
Title Page A-8 Depleted X/Q Values at the Special Locations for........
A-12 Releases from the Reactor Buildings A-9 D/Q Values at the Special Locations for Releases........
A-13 from the Reactor Buildings A-10 X/Q Values at the Standard Distances for Releases.......
A-14 from the Reactor Buildings A-11 Depleted X/Q Values at the Standard Distances for.......
A-15 Releases from the Reactor Buildings A-12 D/Q Values at the Standard Distances for Releases.......
A-16 from the Reactor Buildings A-13 X/Q Values at the Special Locations for Releases........
A-17 from the Stack A-14 Depleted X/Q Values at the Special Locations for........
A-18 Releases from the Stack A-15 D/Q Values at the Special Locations for Releases........
A-19 from the Stack A-16 X/Q Values at the Standard Distances for Releases.......
A-20 from the Stack A-17 Depleted X/Q Values at the Standard Distances for.......
A-21 Releases from the Stack A-18 D/Q Values at the Standard Distances for Releases.......
A-22 from the Stack A-19 Brunswick Plant Site Information to be Used for.........
A-23 Ground Level Calculations with NRC "X0QD0Q" Program A-20 Brunswick Plant Site Information to be Used for.........
A-26 Elevated Release Calculations with NAC "XOQD0Q" Program B-1 Dose Parameters for Finite Elevated Plumes ENE..........
B-2 Site Boundary B-2 Joint Frequency Distribution for ENE Sector
(%).........
B-3 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-3 Dose Parameters for Finite Elevated Plumes N Site.......
B-4 Boundary Rev. 6 l
LIST OF TABLES (continued)
No.
Title Page B-4 Joint Frequency Distribution for N Sector (%)...........
B-5 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-5 Dose Parameters for Finite Elevated Plumes NNE..........
B-6 Site Boundary B-6 Joint Frequency Distribution for the NNE Sector (%).....
B-7 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-7 Dose Parameters for Finite Elevated Plumes NE Site......
B-8 Boundary B-8 Joint Frequency Distribution for NE Sector (%).........
B-9 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-9 Dose Parameters for Finite Elevated Plumes E Site.......
B-10 Boundary B-10 Joint Frequency Distribut' ion for E Sector (%)...........
B-11 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-11 Dose Parameters for Finite Elevated Plumes ESE..........
B-12 Site Boundary B-12 Joint Frequency Distribution f or ESE Sector (%).........
B-13 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-13 Dose Parametert for Finite Elevated Plumes SE Site......
B-14 Boundary B-14 Joint Frequency Distribution for SE Sector (%)..........
B-15 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-15 Dose Parameters for Finite Elevated Plumes SSE Site.....
B-16 Boundary B-16 Joint Frequency Distribution for SSE Sector (%).........
B-17 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-17 Dose Parameters for Finite Elevated Plumes S Site.......
B-18 Boundary ODCM (BSEP) vi Rev. 6 l
LIST OF TABLES (continued)
No.
Title g
B-18 Joint Frequency Distribution for S Sector
(%)...........
B-19 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-19 Dose Parameters for Finite Elevated Plumes SSW..........
B-20 S(te Boundary B-20 Joint Frequency Distribution for SSW Sector
(%).........
B-21 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-21 Dose Parameters for Finite Elevated Plumes SW...........
B-22 Site Boundary B-22 Joint Frequency Distribution for SW Sector
(%)..........
B-23 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-23 Dose Parameters for Finite Elevated Plumes WSW..........
B-24 Site Boundary B-24 Joint Frequency Distribution for WSW Sector (%).........
B-25 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-25 Dose Parameters for Finite Elevated Plumes W Site.......
B-26 Boundary B-26 Joint Frequency Distribution for W Sector
(%)...........
B-27 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-27 Dose Parameters for Finite Elevated Plumes WNW..........
B-28 Site Boundary B-28 Joint Frequency Distribution for WNW Sector
(%).........
B-29 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-29 Dose Parameters for Finite Elevated Plumes NW Site......
B-30 Boundary B-30 Joint Frequency Distribution for NW Sector
(%)..........
B-31 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-31 Dose Parameters for Finite Elevated Plumes NNW..........
B-32 Site Boundary ODCM (BSEP) vii Rev. 6 l
LIST OF TABLES (continued)
No.
Title g
B-32 Joint Frequency Distribution for NNW Sector
(%).........
B-33 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant
.C-1 Parameters for Cow and Goat Milk Pathways...............
C-16 C-2 Parameters for the Meat Pathway.........................
C-17 C-3 Parameters for Vegetable Pathway........................
C-18 ODCM (BSEP) viii Rev. 6 l
LIST OF FIGURES No.
Title Page 4.0-1a BSEP Sample Point Locations................................
4-5 4.0-ib BSEP Sample Point Locations................................
4-6 4.0-Ic BSEP Sample Point Locations................................
4-7 4.0-Id BSEP Sample Point Locations................................
4-8 F-1 Liquid Radwaste Effluent System............................
F-2 F-2 Gaseous Radwaste Effluent System...........................
[
L
Long-term annual (X/Q) values for the stack, Reactor Building, and Turbine 1
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.
X/Q values at the limiting site boundary for releases from the Turbine Building, Reactor Building, and stack were obtained from Tables A-1, A-7, and A-13, 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 highest X/0 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 dorinates 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 1
controlling location is at the ENE at the site boundary due to its higher V 1 values.
l I
j Values for K, L, and M, which were used in the determination of the g
g g
controlling locations and which are to be used by BSEP in Expressions 3.2-5 and 3.2-6 to show compliance with 10CFR20, 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 0
multiplied by 10 to convert picoeuries to microcuries for use in Expressions 3.2-5 and 3.2-6.
1 Values for V and B for the finite plume model can be expressed as shown in f
g 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 V an'd B for each of g
the 16 sectors are presented in Appendix B.
The V factor is computed with conversion from air dose to tissue depth dose, g
thus; E1 e "T d
~
f A
u, g
jk g
1.1 K/r EZZ (3. 2-7)
V
=
d jk1 "j
where:
The tissue energy absorption coefficient for photons of energy p
=
T E, em /gm g
The tissue density thickness taken to represent the total body T
=
d dose (5 gm/cm )
The ratio of the tissue to air absorption coefficients over the 1.1
=
energy range of photons of interest, mrem / mrad 3.2.2 I-131, I-133, Particulates, and Tritium
- l The dose rate in unrestricted areas resulting from the release of radio-iodines 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 10CFR20.
h) s 1500 mrem /yr (3.2-9)
(W,h
+ W I P y g s
v where:
Dose parameter for radioiodines and particulates with P
=
g half-lives greater than 8 days based upon the critical organ and the most restrictive age group mrem / year per uCi/m for inhalation pathways and for tritium
=
- I-133 values used in ODCM calculations are determined by actual analysis.
For tritium, at the limiting site boundary, Equation 3.2-13 becomes:
For tritium:
b = 3.0 x 10s (2.5 x 10 8 b
+ 2.0 x 10 7 Q,
+ 2.9 x 10 6 b
)
(3.2-16)
T T
g s
rb tb At the " hypothetical" limiting real pathway location. Equation 3.2-13 becomes:
For tritium:
D = 3.0 x 10s (2.4 x 10 8 Q
+ 4*I
- ig_a q
+ t,4 x ig_7 O
)
(3.2-17)
T T
g g
s rb tb The determination of controlling location,for implementation of 10CFR20 for radiciodines 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 l
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 l
stack. The higher values for X/Q and D/Q for the NE sector at the site boundary make it the dominant meterological 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 Bui1 ding and Turbine Buildings.
TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASlfRED FROM THE BRITSWICK PLANT CENTER (Mi)
Site Milk Milk Meat Nearest Nearest Sector Boundary Cow Coat Animal Resident Garden 1.3 1.2 1.2 l
NNE 0.7 NE 0.7 4.75*
ENE 0.7 l
0.7 E
0.7 0.6 1.6 1.5 l
ESE 0.7 l
0.6 0.9 SE 0.7 l
0.7 2.3 SSE 0.7 1.1 1.5 1.7 l
S 0.8 1.4 1.4 1.4 l
SSW 0.8 1.0 1.0 l
SW 0.7 2.0 1.1 1.0 l
WSW 0.7 0.8 0.9 l
W 0.7 0.9 0.9 WNW 0.6 0.9 1.1 l
NW 0.6 0.9 0.4 NNW O.6 l
N 0.7 c
- A " hypothetical" cow milk pathway is located at this point in accordance with 5.3.1 of NtfREG 0133.
and elevated releases occur from BSEP and their maximum X/Q values may not decrease with distance (i.e., the site boundary may not have the highest X/Q values); X/0 values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest X/O 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/0 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-1, A-7, and A-13, respectively, of Appendix A.
A description of the derivation of X/Q values is also presented in Appendix A.
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 B values. The ENE sector at the site boundary is the control g
location because of its higher B values.
g ValuesforM[andN,whichwereusedinthedeterminationofthecontrolling g
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 0
Regulatory Guide 1.109, Revision 1.
The values have been multiplied by 10 to convert from picoeuries to microcuries.
The following relationship should hold for BSEP to show compliance with Radiological Effluent Technical Specification 3.11.2.2.
For the calendar quarter Dy s 10 mrad (3.3-9)
D8 s 20 mrad (3.3-10)
For the calendar year:-
Dy 5 20 mrad (3.3-11)
DS s 40 mrad
( 3. 3-12) where:
The air dose from gamma radiation, mrad Dy The air dose from beta radiation, mrad D8
=
The quarterly limits given above represent one-half the annual design objective of Section II.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.
3.3.2 1-131, I-133, Particulates, and Tritium
- 3.3.2.1 Cumulation of DosesSection 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:
-8
+w
+W 0
+w qi) 3.17 x 10 I Rg (W, Qg
,qt y 1 y
s a
v v
s 7.5 mrem per quarter or 15 mrem per calendar year (3.3-13) t
- I-133 values used in ODCM calculations are determined by actual analysis.
l i
0DCM (BSEP) 3-40 Rev. 6 i
)
Og TABLE 4.0-1 (Cont'd)
- c Exposure Pattmay Sample Sample Point Description, Approximate Sampling and Analysis and/or Sample ID No.
Distance, and Direction Collection Frequency Frequency Analysis (a)
INCESTION
- a. Milk 600 To be identified as available, r - Isotopic (animals on 601 pasture) 1-131 analyses 602 (animals on pasture) 603 Camma isotopic (other times) 1-131 analysis (other times)
- b. Fish and 700 S.S mile SSW Atlantic Ocean (e)
When in Season -
Semiannual Casuna isotopic Inverte-at Discharge Sealannual on edible brates 701 portions d
(shrimp) 1 702 703-705 Not Specified - Atlantic Ocean (c)(e)
- c. Broadleaf 800 0.7 alles NE Intake Canal When available -
Monthly Camma isotopic Vegetation Monthly 801 0.6 miles SW Discharge Canal Monthly 1-131 802 10 miles - Control - Location not Specified (c)
(a) The LID for each analysis is specified in Table 4.12.1-1 of the Technical Specifications for the Brunswick Steam Electric Plant.
(b) Particulate samples will be analyzed for gross beta radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change. Perform gasuna scan on each sample uhen gross beta activity is 10 times the mean of the control station.
(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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
,e<
(e) A sample of one free swinumer, one bottom feeder, and one shellfish (shrimp) will be collected if available. A control sample of each species collected will be obtained if available.
m