ML18036A591
| ML18036A591 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/25/1992 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18036A571 | List: |
| References | |
| PROC-920325, NUDOCS 9203310130 | |
| Download: ML18036A591 (182) | |
Text
ODCM Revision 0
Page 1 of 208 OFFSITE DOSE CALCULATION MANUAL (ODCM')
2024o 9203310130 920325 PDR ADQCK 05000259 PDR
Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS
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Page 3 of 208 Section page ASES
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1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION......
52 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
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52 1/2.2 RADIOACTIVE EFFLUENTS.........................................
52 1/2.2.1.1 CONCENTRATION.............................................
52
/2.2.1.2 DOSE..............o.......................................
53 1
1/2.2.1.3 LIQUID WASTE TREATMENT....................................
53
/2.2.2.1 DOSE RATE.................................................
54 1
1/2.2.2.2 DOSE NOBLE GASES..................................
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55 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES PARTICULATE FORM
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56 1/2.2.2.4 GASEOUS RADWASTE TREATMENT................................
57
/2.2.3 TOTAL DOSE..................................................
57 1
1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING........................
57 1/2.3.1 MONITORING PROGRAM........,..................................
57 1/2.3.2 LAND USE CENSUS.............................................
58 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM..........................
58 3.0 DEFINITIONS.....................................................
59 3.0.A.
CHANNEL CALIBRATION..........................................
60 3.0.B.
CHANNEL FUNCTIONAL TEST......................................
60 3.0.C.
GASEOUS WASTE TREATMENT SYSTEM...............................
60 3.0.D.
DOSE EQUIVALENT I-131........................................
60 3.0.E.
MEMBER(S) OF THE PUBLIC......................................
60 3.0.F.
OPERABLE - OPERABILITY.......................................
61 3.0.G.
PURGE PURGING..............................................
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Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)
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Page 5 of 208 Section page 6 ~
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.3.1.2 Fish Ingestion.........................;..'..................
77 6..3.1.3 Recreation..................................................
78 6.3.1.4 Monthly Summary.....................;.......................
79 6 '
LIQUID RADWASTE TREATMENT SYSTEM
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80 6.5 DOSE PROJECTIONS -...............................................
81 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES........................
82 6..6.1 Water Ingestion...............................................
82 6..
F h I
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.6.2 Fish Ingestion................................................
83 6..6.3 Shoreline Recreation..........................................
83 6.6.4 Total Maximum Individual Dose.................................
84 6..6.5 Population Doses..............................................
85 6.7 LIQUID DOSE FACTOR EQUATIONS.............................
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87 6.7.1 Water Ingestion Dose Factors..................................
87 6.7.2 Fi.sh Ingestion Dose Factors...................................
87 6.7.3 Shoreline Recreation Dose Factors.............................
87 7.0 GASEOUS EFFLUENTS...............................................
107 RELEASE POINTS DESCRIPTION..........................................
108 7.1 RELEASE RATE LIMIT METHODOLOGY..................................
109 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS...................
114 7..2.1 Alarm/Trip Setpoints..........................................
114 7.2.2 Allowable Values..............................................
114 7.3 GASEOUS EFFLUENTS DOSE RATES..................................
116 7.3.1 Noble Gas Dose Rates..........................................
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Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)
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Page 7 of 208 Section page 7.7.2 Radioiodine, Particulate and Tritium Naximum Organ Dose.....
128 7.7.3 Population Doses..............................................
130 7..7.4 Reporting of Doses...................;........................
131 7.8 GASEOUS DOSE FACTOR E(UATIONS.-...........-...................
132 7.8.1 Pasture Grass-Cow-Goat-Milk Ingestion Dose Factors............
132 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors..............
133 7.8.3 Pasture Grass-Beef Ingestion Dose Factors.....................
134 7.8.4 Stored Feed-Beef Ingestion Dose Factors.......................
135 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors..................
136 7.8.6 Stored Vegetable Ingestion Dose Factors.......................
137 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor...............
138 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor.................
139 7.8.9 Tritium-Pasture Grass-Beef Dose Factor........................
140 7.8.10 Tritium-Stored Feed-Beef Dose Facto'r.........................
141 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor....................
142 7.8.12 Tritium-Stored Vegetables Dose Factor........................
143 7.8.13 Inhalation Dose Factors......................................
144 7.8.14 Ground Plane Dose Factors....................................
144 7.9 DlSPERSION METHODOLOGY...........................
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145 7.9.1 Annual Average Air Concentration..............................
146 7.9.2 Relative Concentration........................................
147 7.
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.9.3 Relative Dispersion...........................................
147 7.9.4 Effective Release Height......................................
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Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)
LIST OF TABLES ODCM Revision 0
Page 9 of 208 page Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..
18 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......'.......................
20 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING. INSTRUMENTATION.
23 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
25 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM..
28 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM........................................
34 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING ROGRAM
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Table 2.3-2 MAXIMUMVALUES FOR THE LOWER LIMIT OF DETFCTION (LLD)
FOR ENVIRONMENTAL SAMPLES...............................
45 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES...................................
47 Table 3.1 FREQUENCY NOTATION........................................
63 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS....................
88 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA.......
89 Table 6.3 DOSE CALCULATION FACTORS..................................
92 Table 6.4 INGESTION DOSE FACTORS....................................
94 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH...............
102 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND..
103 Table 7.1 BFN - OFFSITE RECEPTOR LOCATION DATA......................
149 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN...............................................
150 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND IRECTION.1....0.......-..................................
151 D
Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES................
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LIST OF FIGURES ODCM Revision 0
Page 11 of 208 page Figure 3.1 LAND SITE BOUNDARY...
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64 Figure 6.1 LIQUID RELEASE POINTS....
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105 Figure 6.2 LIQUID RADWASTE SYSTEM...................................
106 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING........,...,..
184 Figure 7.2 NORMAL BUILDING VENTILATION..............................
185 Figure 7.3 PLUME DEPLETION EFFECT.......................,....,,....,
Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME.......
190 Figure 7.5 RELATIVE DEPOSITION......................................
191 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT......................................
206 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1
TO 5 MILES FROM THE PLANT...................................
207 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT
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INTRODUCTION ODCM Revision 0
Page 13 of 208 The Browns Ferry Nuclear Plant
{BFN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the BFN Technical Specifications.
The ODCM is divided into two major parts.
The first part of the ODCM contains:
- 1) Radioactive Effluent Controls specified by the BFN Technical Specifications;
- 2) Radiological Environmental Monitoring Controls required by the BFN Technical Specifications;
- 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by BFN Technical Specifications; and, 4) Administrative Controls for the ODCM requirements.
The second part of the ODCM contains the methodologies used to: 1) calculate offsite doses resulting from radioactive gaseous and liquid effluents;
- 2) calculate gaseous and liquid effluent monitor Alarm/Trip setpoints;
- and,
- 3) conduct the Environmental Radiological Monitoring Program.
The BFN ODCM is maintained for use as a reference guide on accepted methodologies and calculations.
Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas.
Any licensee initiated ODCM changes will be implemented in accordance with BFN Technical Specifications.
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1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS ODCM Revision 0
Page 15 of 208 1/2.0 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls contained in'the succeeding sections is required during the conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.
1.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals'f the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.
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Page 17 of 208 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 In accordance with BFN Technical Specification 6.8.4.l.a, the radioactive liquid effluent monitoring instrumentation listed in Table 1.1-1 shall be OPERABLE with the applicability as shown in Tables 1.1-1 and 2.1-1.
Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 6.2 to ensure that the limits of Control 1.2.1.1 are not exceeded.
APPLICABILITY: This requirement is applicable as shown in Table 1.1-1.
ACTION:
a.
With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.
b.
The action required when the number of OPERABLE channels is less than the minimum channels OPERABLE requirement is specified in the notes for Table 1.1-1.
Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
SURVEILLANCE RE UIREMENTS 2.1.1 Each of the radioactive liquid effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-1.
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Page 19 of 208 Table 1.1-1 (Page 2 of 2)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION A During release of radioactive wastes from the radwaste processing
- system, the following shall be met:
(1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before'exceeding the limits specified in Control 1.2.1.1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in Table 2.2.1 and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge.
Otherwise, suspend releases via this pathway.
ACTION B With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend release via this pathway witho'ut delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.
ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored.
If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis with at least an LLD1 of lE-7 pCi/ml (gross) or ( applicable MPC ratio (y isotopic) shall be used to monitor the effluent.
ACTION D With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLD1 of 1E-7 pCi/ml (gross) or
< applicable MPC ratio (y isotopic).
ACTION E With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves may be used to estimate flow.
See Table 2.2-1, Table Notation for the definition of LLD.
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Page 21 of 208 Table 2.1-1 (Page 2 of 2)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION NOTE: Each requirement shall be performed within the specified time interval with: (1) a maximum allowable extension'not to exceed 25K of the interval given, but (2) the combined time entered for any 3 consecutive intervals shall not exceed 3.25 times the specified interval.
1 The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicates measured levels above the alarm/trip setpoint.
b.
Instrument indicates an inoperative/downscale failure.
c.
Instrument controls not set in operate mode.
2 The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicates measured levels above the alarm/trip setpoint.
b.
Instrument indicates an inoperative/downscale failure.
c.
Instrument controls not set in operate mode.
3 This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.
4 INSTRUMENT CHECK shall consist of verifying indication during periods of release.
INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.
5 The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))
radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.
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Page 23 of 208 Table 1.1-2 (Page 1 of 2)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels/
Action
- 1. Stack (RM-90-147A & B)
- a. Noble Gas Monitor
- b. Iodine Cartridge
- c. Particulate Filter
- d. Sampler Flow Abnormal e.
Stack Flow (FT, FM, FI-90-271)
- 2. Reactor/Turbine Building Ventilation (RM-90-250)
A/C B/C B/C D
D
- a. Noble Gas Monitor
- b. Iodine Sampler
- c. Particulate Sampler
- d. Sampler Flowmeter
- 3. Turbine Building Exhaust (RM-90-249%
251)
- a. Noble Gas Monitor
- b. Iodine Sampler
- c. Particulate Sampler e.
Sampler Flowmeter 4.
Radwaste Building Vent (RM-90-252)
A/C B/C B/C D
A/C B/C B/C D
- a. Noble Gas Monitor
- b. Iodine Sampler
- c. Particulate Sampler e.
Sampler Flowmeter
- 5. Offgas Post Treatment
- a. Noble Gas Activity Monitor (RM-90-265, -266) b.
Sample Flow Abnormal (PA-90-262) 1 1
1 1
A/C B/C B/C D
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Page 25 of 208 Table 2.1-2 (Page 1 of 2)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ins trument INSTRUMENT SOURCE CHECK CHECK CHANNEL CALIBRATION FUNCTIONAL TEST 1.
STACK
- a. Noble Gas Monitor4
- b. Iodine Cartridge
- c. Particulate Filter
- d. Sampler Flow Abnormal
- e. Stack Flowmeter M
N/A N/A'/A N/A Rl N/A N/A R
R Q2 N/A N/A Q
2.
REACTOR/TURBINE BUILDING VENT
- a. Noble Gas Monitor5
- b. Iodine Sampler
- c. Particulate Sampler
- b. Sampler Flowmeter 3.
TURBINE BUILDING EXHAUST
- a. Noble Gas Monitor5
- b. Iodine Sampler
- c. Particulate Sampler
- b. Sampler Flowmeter 4.
RADWASTE BUILDING VENT
- a. Noble Gas Monitor5
- b. Iodine Sampler
- c. Particulate Sampler
- b. Sampler Flowmeter 5.
OFF GAS POST TREATMENT4
- a. Noble Gas Activity D
Monitor
- b. Sample Flow Abnormal D
M N/A N/A N/A M
N/A N/A N/A M
N/A N/A N/A N/A Rl N/A N/A R
Rl N/A N/A R
Rl N/A N/A R
Rl Q2 N/A N/A Q
Q2 N/A N/A Q
Q2 N/A N/A Q
Q2 2024o
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Page 27 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with BFN Technical Specifications 6.8.4.1.b and c, the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.
APPLICABILITY: At all times.
ACTION'f the above limits are exceeded, appropriate action shall be initiated without delay to bring the release within limits.
Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.
SURVEILLANCE RE UIREMENTS 2.2.1.1.1 Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released~
and of the average dilution flow and the length of time over which each discharge occurred.
2.2.1.1.2 Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in Table 2.2-1.
2.2.1.1.3 The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.
2.2.1.1.4 The results of the analysis of samples collected from release points shall be used with the calculational methodology in ODCM Section 6.1 to assure that the concentrations at the point of discharge are maintained within the above limits.
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Page 29 of 208 Table 2.2-1 (Page 2 of 3)
RADIOACTIVE LlgVID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION A batch release is the discharge of liquid waste of a discrete volume.
The discharge shall be thoroughly mixed prior to sampling.
2 A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.
The LLD is defined for the purpose of these requirements as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95'X probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD =
Where:
4.66sb E
V 2.22E+06 Y
exp (-Mt)
LLD sb E
V 2.22E+06 Y
X
= the "a priori" lower limit of detection as defined above (microcurie per unit mass or volume) the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
= the counting efficiency (counts per disintegration)
= the sample size (units of mass or volume)
= the number of disintegrations per minute per microcurie,
= the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (s-1) and the elapsed time between midpoint of sample collection and time of counting (s).
Typical values of E, V, Y, and ht should be used in the calculation.
It should be recognized that the LLD is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Zn-65, Co-60, Cs-137, Mn-54, Co-58, Cs-134, Ce-141, Ce-144, Mo-99 and Fe-59 for 2024o
1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS ODCM Revision 0
Page 31 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 In accordance with BFN Technical Specifications 6.8.4.1.d and e, the doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS shall be limited:
a.
During any calendar quarter to
< 1.5 mrem to the total body and to
< 5 mrem to any organ, and b.
During any calendar year to
< 3 mrem to the total body and to
< 10 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
If the limits specified above are exceeded, prepare and submit a Special Report pursuant to ODCM Administrative Control 5.4.
SURVEILLANCE RE UIREMENTS 2.2.1.2 Cumulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in ODCM Section 6.3 at least once every 31 days.
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Page 33 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 In accordance with BFN Technical rate at any time to areas at and Figure 3.1) due to radioactivity the site shall be limited to the Specification 6.8.4.l.g, the dose beyond the SITE BOUNDARY (see released in gaseous effluents from following values:
a.
The dose rate limit for noble gases shall be
<500 mrem/yr to the total body and
<3000 mrem/yr to the skin, and b.
The dose rate limit for I-131, I-133, H-3 and particulates with greater than eight day half-lives shall be
<1500 mrem/yr to any organ.
APPLICABILITY: At all times.
ACTION: If the limits above are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.
Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.
SURVEILLANCE RE UIREMENTS 2.2.2.1.1 The gross 9/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.
a.
For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in Table 1.1-2.
b.
For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified above.
2.2.2.1.2 Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in Table 2.2-2.
Dose rates shall be determined to be within the above limits using methods contained in ODCM Section 7.3.
2.2.2.1.3 Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.
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l
ODCM Revision 0 Page 35 of 208 Table 2.2-2 (Page 2 of 2)
RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 The LLD is defined, for the purpose of this requirement, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely concluding'hat a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD 4.66sb E
V 2.22E+06 Y
exp (-X ht)
Where:
= the "a priori" lower limit of detection (microcurie per unit mass or volume) sb
= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
E
= the counting efficiency (counts per disintegration)
V
= the sample size (units of mass or volume) 2.22E+06
= the number of disintegrations per minute per microcurie, Y
= the fractional radiochemical yield, when applicable,
'h
= the radioactive decay constant for the particular radionuclide (s 1),
and At
= the elapsed time between midpoint of sample collection and time of counting (s).
Typical values of E, V, Y, and Dt should be used 'in the calculation It should be recognized that the LID is defined as an
~a riori (before the fact) limit representing the capqbility of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.
3 The principal gamma emitters for which the LLD specification will apply are exclusively 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-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.
4 Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.
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1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS ODCM Revision 0
Page 37 of 208 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 In accordance with BFN Technical Specification 6.8.4.1.j, the dose to a MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:
a.
To any organ during any calendar quarter to
< 7.5 mrem; b.
To any organ during any calendar year to ( 15 mrem.
APPLICABILITY: At all times.
ACTION:
If the calculated doses exceed the limits specified above, prepare and submit a special report pursuant to ODCM Administrative Control 5.4.
SURVEILLANCE RE UIREMENTS 2.2.2.3 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.4 at least once every 31 days.
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1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS ODCM Revision 0
Page 39 of 208 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 In accordance with BFN Technical Specification 6.8.4.1.j, the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to
< 25 mrem to the. total body or any organ (except the thyroid, which is limited to (
75 mrem) over a period of one calendar year.
APPLICABILITY: At all times.
ACTION With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, prepare and submit a Special Report to the Commission pursuant to ODCM Administrative Control 5.4 and limit the subsequent releases such that the above limits are not exceeded.
SURVEILLANCE RE UIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Sections 6.3, 7.3, and 7.4 and the methods in ODCM Section 8.0.
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1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS ODCM Revision 0
Page 41 of 208 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Control 1.3.l.b, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).
The detection capabilities required by Table 2.3-2 are state-of-the art for routine environmental measurements in industrial laboratories.
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 a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a
manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.
SURVEILLANCE RE UIREMENTS 2.3.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures listed below and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-2.
2.3.1.2 If measured levels of radioactivity in a environmental sampling medium are determined to exceed the reporting level values of Table 2.3-3 when averaged over any calendar quarter sampling
- period, a report shall be submitted to the Commission pursuant to Control 1.3.1.b.
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Page 43 of 208 Table 2.3-1 (2 of 3)
MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or
~Sam le Number of Samples and Sample Locationsa Sampling and
'ype and Frequency Collection Fre uenc of Anal sis 3.
WATERBORNE
- a. Surface 2 locations Composite sample collected over a period of
< 31 days.b Gamma isotopic analysis of each composite sample.
Tritium analysis of composite sample at least once per 92 days.
b.Drinking Minimum of 1
downstream location, or all water supplies within 10 miles downstream which are taken from the Tennessee River Composite sample collected over a period of
< 31 days b>c Gross beta and gamma isotopic analysis of each composite sample.
Tritium analysis of composite sample at least once per 92 days.
- c. Sediment d.Groundd Minimum of 1
location.
At least once per 184 days Gamma isotopic analysis of each sample.
Sample locations are given in ODCM Section 9.0.
Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Composite samples shall be collected over a period of
< 14 days for I-131 if drinking water is obtained within 3 miles downstream of the plant.
Ground water movement in the area has been determined to be from the plant site toward the Tennessee River.
Since no drinking water wells exist between the plant and the river, ground water will not be monitored.
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Page 45 of 208 Table 2.3-2 (1 of 2)
MAXIMUMVALUES FOR THE LOWER LIMIT OF DETECTION (LLD)
FOR ENVIRONMENTAL SAMPLES Water A~nal sis
~Ci/L)
Airborne Particulate Fish or Gases (pCi/kg,
~Ci/m3) wat)
Food Products Milk (pCi/kg,
~Ci'/L) wat)
Sediment (pCi/kg, dr )
gross beta 4
H-3 2000 Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 0.01 N/A N/A N/A N/A N/A N/A N/A 130 260 130 260 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 60 15 N/A N/A 30 N/A 15 N/A lb 0.07 15 0.05 18 0.06 N/A N/A N/A 130 150 N/A N/A N/A N/A 15 18 60 N/A N/A 60 60 80 N/A N/A N/A N/A N/A 150 180 N/A N/A 2024o
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Page 47 of 208 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES
~Anal sis Water
~(Qi/L)
Airborne Particulate or gases Fish n'I
)
( 'I Milk
~Ci/L)
Food Products Ci/I'K wet)
H-3 2 x 104(a)
N.A N.A N.A.
N.A.
Mn-54 Fe-59 1 x 103 s
4 x 102 Co-58 1 x 103 Co-60 3 x 10 Zn-65 3 x 102 Zr-Nb-95 4 x 102 I-131 Cs-134 30 Cs-137 50 Ba-La-140 2 x 102 N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
0.9 10 20 N.A.
3 x 104 1 x 104 3 x 104 1 x 104 2 x 104 N.A.
N.A.
1 x 103 2 x 103 N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
60 70 3 x 102 N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
1 x 102 1 x 103 2 x 103 N.A.
(a)
For drinking water samples.
This is 40 CFR Part 141 value.
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1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS ODCM Revision 0
Page 49 of 208 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE RE UIREMENTS 2.3.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:
1.
Within a 2-mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.
2.
Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.
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Page 51 of 208 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.
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BASES ODCM Revision 0
Page 53 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION (continued) controlling radioisotope and its Maximum Permissible Concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission of Radiological Protection (ICRP) Publication 2.
1/2.2.1.2 DOSE This requirement is provided to implement the dose requirements of Section II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.
The requirement implements the guides set forth in Section II.A of Appendix I.
This action provides the required operating flexibilityand at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable".
Also, for fresh water sites with drinking water supplies which can potentially be affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.
The dose calculations in Section 6.0 implement the requirements in Section III.Aof Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in Section 6.0 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the...ethodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" April 1977.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
1/2.2.1.3 LI UID WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified.
This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."
This requirement implements the requirements of 10 CFR Part 50.36a, 2024o
BASES ODCM Revision 0
Page 55 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.2 DOSE NOBLE GASES This requirement is provided to implement the re'quirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50.
The limits are the guides set forth in Section II.C of Appendix I.
The action to be taken for exceeding these limits provides the required operating flexibilityand at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable."
Section 7.0 calculational methods implement the requirements in Section III.Aof Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides."
October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes 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 ODCM equations also provide for determining the air doses at the exclusion area boundary are based upon the historical average atmospheric conditions.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.
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BASES ODCM Revision 0
Page 57 of 208 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT This requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior their release to the environment.
This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable".
This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective,Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a
suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
This action requires that a special report be prepared and submitted to explain reasons for any failure to comply with the above requirements.
1/2.2.3 TOTAL DOSE This requirement is provided to meet the dose limitations of 40 CFR 190.
This requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.
The Special Report will describe a coprse of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 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 fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of five miles must be considered.
1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring 2024o
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Page 59 of 208 SECTION 3.0 DEFINITIONS 2024o
DEFINITIONS ODCM Revision 0
Page 61 of 208 This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.
This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter RESTRICTED AREAS.
3.0.F.
OPERABLE OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation,
- controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
3.0.G.
PURGE PURGING PURGE or PURGING is the controlled process of discharging air or gas from the primary containment 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.
3.0.H.
RATED POWER RATED POWER refers to operation at a reactor power of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.
Design power, the power to which the safety analysis applies, corresponds to 3,440 NWt.
3.0.I.
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased,'r otherwise controlled by TVA (see Figure 3.1).
3.0.J.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.
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Page 63 of 208 Table 3.1 FRE UENCY NOTATION Notation
~Fre uenc At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SA S/U N.A.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
At least once per 7 days.
At least once per 31 days.
At least once per 92 days.
At least once per 184 days.
At least once per 18 months.
Prior to each reactor startup.
Not Applicable Completed prior to each release 2024o
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Page 65 of 208 SECTION 4.0 (NOT USED) 2024o
5.0 ADMINISTRATIVECONTROLS ODCM Revision 0
Page 67 of 208 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Annual Radiological Environmental Operating, Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational
- studies, operational controls (as appropriate),
and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The report shall also include the results of land use censuses required by Control 1.3.2.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The report shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by Control 1.3.3.
5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B
thereof.
The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly bases following the format of Appendix B thereof.
Calculated offsite dose to members of the public resulting from the release of
'iquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.
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Page 69 of 208 SECTION 6.0 LI UID EFFLUENTS 2024o
6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC Sum of the Ratios ODCM Revision 0
Page 71 of 208 Prior to release, a grab sample will be analyzed to determine the concentration (Ci) of each gamma emitting radionuclide i in the radwaste tank.
The following equation is used to calculate MPC fractions (Mi).
where:
Mi Ci MPCi Mi
= MPC fraction of radionuclide i.
Ci
= concentration of radionuclide i in the radwaste tank, pCi/ml.
MPCi = MPC of radionuclide i as specified in Control 1.2.1.1, pCi/ml.
The sum of the ratios (R) will be calculated by the following relationship:
R=
E Mi (6. 2) where
= the sum of the ratios.
Mi = MPC fraction from equation 6.1.
6.1.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be 1 due to the releases from the above source.
The following relationship will assure this criterion is met:
f (R 1)
< F where:
f
= the effluent flow rate (gallons/minute) before dilution.
R
= the sum of the ratios as determined by Equation 6.2.
F
= minimum dilution flow rate for prerelease analysis.
The allowable release rate is calculated before each release and the release rate is continuously monitored during the release so that the MPC limit is not exceeded.
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6.2 INSTRUMENT SETPOINTS ODCM Revision 0
Page 73 of 208 Alarm/trip setpoints for each liquid monitor will be established and set such that Equation 6.3 is satisfied.
The locations and identification numbers for each liquid effluent radiation detector are shown in Figures 6.1 and 6.2.
This section of the ODCM describes the methodology that will be used to determine allowable values.
The allowable values are then used to determine the physical settings" on the monitors.
The physical settings are calculated in the applicable Scaling and Setpoint Document.
6.2.1 Radwaste Dischar e Monitor The allowable value for the radwaste discharge monitor (RM-90-130),
shown in Figures 6.1 and 6.2, will be established using the methodology below.
The alarm/trip allowable value will be set such that Equation 6.3 is satisfied.
The trip allowable value for the monitor, which will automatically isolate the release, is set at less than or equal to the limit in Control 1.2.1.1.
The alarm allowable value is set at 50K of the trip allowable value.
The maximum activity concentrationl of liquid radwaste that can be discharged into a Condenser Cooling Water (CCW) conduit can be calculated as:
( MPCi WFi ) F A = gi f
where A
MPCi maximum batch activity concentration, pCi/ml Maximum Permissible Concentration, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.
weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.
CCW dilution water flow rate, gpm.
maximum discharge flow rate, gpm 1 The maximum activity concentration is based on a selected isotopic mixture so that an allowable value can be calculated.
The selected isotopic mixture will be documented in TI 45. If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maximum activity concentration.
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6.3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION ODCM Revision 0
Page 75 of 208 6.3.1 Monthl Anal sis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose.
If the projected dose calculated by this monthly method exceeds the monthly fraction of the annual limits in Control 1.2.1.2, then the methodology in Section 6.6 will be implemented.
The 20 nuclides listed below, based on operational source
- terms, contribute more than 95 percent of the total estimated dose to the total body and the most critical organ for both the water and fish ingestion pathways.
The organs considered for both water ingestion and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver.
H-3 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Zr/Nb-95 Mo/Tc-99m Ag-110m Sb-124 I-131 I-133 Cs-134 Cs-136 Cs-137 A conservative calculation of the monthly dose will be done according to the following procedure.
First, the monthly operating report containing the release data will be obtained and the activities reported (if any) for each of the above 20 radionuclides will be noted.
This information will then be used in the following calculations.
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6.3.1.2 Fish In estion ODCM Revision 0
Page 77 of 208 The dose to an individual. from the consumption of fish is described by Equation 6.4.
In this case, the activity ingested of the ith radionuclide due to eating fish (Iik) is described by 103 Ai Bi Ufa (1/12) where:
103
= conversion factor, g/kg.
Ai
= activity released of the ith radionuclide during the month, Ci Bi
= bioaccumulation factor of ith radionuclide,. pCi/g per pCi/ml.
(Table 6.5)
Ufa
= amount of fish eaten yearly by the kth age group (Table 6.3),
kg/yr.
1/12
= conversion factor, yr/month.
F
= average river flow rate for the month, cubic feet per second.
d
= fraction of river flow available for dilution, 0.30.
7.34E+10
= conversion from cubic feet per second to milliliters per month.
Inserting this for Iik in equation 6.4, the dose equation for fish ingestion then becomes:
Djk 3.98E+03 Ai Bi Ufa DFLijk i=1 2024o
The recreation dose equation then becomes:
ODCM Revision 0
Page 79 of 208 1
Dr =
(29.8 Al + 1690 A2 + 539 A3 + 812 A4)
(6.11) where:
Al, A2, A3, Ag = the activities of Co-58, Co-60, Cs-134, and Cs-137, respectively, pCi.
6.3.1.4 Monthl Summar To obtain the total monthly dose to the total body, sum the total body dose from water ingestion, the total body dose from fish 'ingestion, and the recreation dose.
This value will be compared to the limit for total body dose.
To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from fish ingestion, and the recreation dose.
This value will be compared to the limit for maximum organ dose.
Calendar quarter and calendar year doses are first estimated by summing the doses calculated for each month in that year.
However, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters with the methodology of ODCM Section 6.6 will be used instead of those quarterly doses estimated by summing monthly results.
An annual check will be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in ODCM Section 6.6.
If less than 95 percent of the dose has been estimated, either a new list of principal isotopes will be prepared or a new correction factor will be used.
The latter option will not be used if less than 90 percent of the total dose is predicted.
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6.5 DOSE PROJECTIONS ODCM Revision 0
Page 81 of 208 Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
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Page 83 of 208 Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1).
Individual fish ingestion doses are calculated for the total body and each internal organ as described below:
Doz g 10 9 ~ 8E 09 0 ~ 25 AFit Qi D exp (-8. 64E+04 Xi td )
where (6. 15) 10
='onversion factor, pCi/Ci.
9.8E-09
= conversion factor, cfs per ml/hour.
0.25
= fraction of the yearly fish consumption eaten in one quarter, dimensionless.
AFit
= Dose factor for fish ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in ODCM Section 6.7.2.
= Quantity of nuclide i released during the quarter, Curies.
= dilution factor, as described above, cfs
= radiological decay constant of nuclide i, seconds (Table 6.3).
= decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109),
days.
8.64E+04
= conversion factor, seconds per day.
6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1).
It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers.
Individual recreation shoreline doses are calculated for the total body and skin as described below:
Doz g 10 9 8E 09 rf ARit Qi D exp (-8. 64E+04 Xi td )
where (6. 16) 106
= conversion factor, pCi/Ci.
9.8E-09
= conversion factor, cfs per ml/hour.
rf
= recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter.
Recreation factors used are:
1st quarter 0.1 2nd quarter 0.3 3rd quarter 0.4 4th quarter 0.2.
2024o
6.6.5 Po ulation Doses ODCM Revision 0
Page 85 of 208 For determining population doses to the 50-mile population around the
- plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.
For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:
3 4
POPWTRt
= 10 g POPm g POPa ATMWa TWDOSamt m=1 a=1 (6.17) where:
POPWTRt POPa POPm ATMWa TWDOSamt 10 3
= water ingestion population dose to organ t, man-rem.
= fraction of population in each age group a (from NUREG CR-1004, Table 3.39).
= 0.665 for adult
= 0.168 for child
= 0.015 for infant
= 0.153 for teen
= population at PWS m.
The 3
PWSs and their populations are listed in Table 6.1.
= ratio of average to maximum water ingestion rates for each age group a.
Maximum water ingestion rates are given in Table 6.3.
Average water ingestion rates 'are obtained from R.G.
1.109 Table E-4).
The ratios are:
= 0.5069 for adult
= 0.5098 for child
= 0.7879 for infant
= 0.5098 for teen
= total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.
conversion factor for rem/mrem.
For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BFN are consumed by local population.
An additional 7-days decay is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:
3 3
453.6 HVST APRr POPFt
= 10 10 El El POPa TFDOSart r=l a=1 a
a 2024o
6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors ODCM Revision 0
Page 87 of 208 AWit DFLiat Uwa 10 10 where:
DFI Uw 10~
103 8760
= ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).
= water consumption rate for age group a, L/year, (Table 6.3).
conversion factor, pCi/pCi.
conversion factor, ml/L.
= conversion factor, hours per year.
6.7.2 Fish In estion Dose Factors AFit DFLiat Ufa Bi 10 10 where:
DFLi Ufa Bi 106 103 8760
= ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).
= fish consumption rate for age group a, kg/year, (Table 6.3).
= bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).
conversion factor, pCi/pCi.
conversion factor, pl/L.
= conversion factor, hours per year.
6.7.3 Shoreline Recreation Dose Factors ARit =
DFG't Kc M W 103 106 U
[1-exp(-X tb)]
where:
DFGit Kc M
W 103 106 3600 Xl tb U
8760
= dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m2, (Table 6.6).
= transfer coefficient from water to shoreline
- sediment, L/kg-hr, (Table 6.3).
= mass density of sediment, kg/m, (Table 6.3).
= shoreline width factor, dimensionless, (Table 6.3).
conversion factor, ml/L.
conversion factor, pCi/pCi.
= conversion factor, seconds/hour.
decay constant for nuclide i, seconds
, (Table 6.2).
= time shoreline is exposed to the concentration in the water,
- seconds, (Table 6.3).
= usage factor, 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year.
= conversion factor, hours/year.
2024o
ODCM Revision 0
Page 89of 208 Table 6.2 (1 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69m Zn-69 Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Half-Life (minutes) 6.46E+06 3.01E+09 9.00E+02 2.06E+04 3.99E+04 4.50E+05 1.55E+02 1.42E+06 6.43E+04 3.90E+05 1.02E+05 2.77E+06 5.27E+07 1.51E+02 7.62E+02 3.52E+05 8.26E+02 5.56E+01 2.12E+03 1.43E+02 3.18E+01 2.87E+00 2.69E+04 1.78E+Ol 1.54E+01 7.28E+04 1.50E+07 5.70E+02 1.63E+02 3.85E+03
'.97E+01 8.43E+04 2.12E+02 6.06E+02 9.22E+04 1.01E+03 5.05E+04
'.21E+01 3.96E+03 3.61E+02 1.42E+01 5.67E+04 2.66E+02 5.30E+05 3.60E+05 X
(1/s) 1.79E-09 3.84E-12 1.28E-05 5.61E-07 2.90E-07 2.57E-08 7.45E-05 8.13E-09 1.80E-07 2.96E-08 1.13E-07 4.17E-, 09 2.19E-10 7.65E-05 1.52E-05 3.28E-08 1.40E-05 2.08E-04 5.45E-06 8.08E-05 3.63E-04 4.02E-03 4.29E-07 6.49E-04 7.50E-04 1.59E-07 7.70E-10 2.03E-05 7.09E-05 3.00E-06 2.32E-04 1.37E-07 5.45E-05 1.91E-05 1.25E-07 1.14E-05 2.29E-07 1.60E-04 2.92E-06 3.20E-05 8.13E-04 2.04E-07 4.34E-05 2.18E-08 3.21E-08 Biv 4.80E+00 5.50E+00 5.20E-02 1.10E+00 2.50E-04 2.90E-02 2.90E-02 6.60E-04 6.60E-04 9.40E-03 9.40E-03 9.40E-03 1.90E-02 1.90E-02 1.20E-01 4.00E-01 4.00E-01 4.00E-01 7.60E-01 7.60E-01 7.60E-01 7.60E-01 1.30E-01 1.30E-01.
1.30E-01 1.70E-02 1.70E-02 1.70E-02 1.70E-02 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.60E-03 1.70E-04 1.70E-04 9.40E-03 9.40E-03 1.20E-01 2.50E-01 2.50E-01 5.00E-02 5.00E-02 5.00E-02 1.50E-01 Fmi (cow) 1.00E-.02 1.20E-02 4.00E-'02'.50E-02 2.20E-03 2.50E-04 2.50E-04 1.20E-03 1.20E-03 1.00E<<03 1.00E-03 1.00E-03 6.70E-03 6.70E-03 1.40E-02 3.90E-02 3.90E-02 3.90E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 3.00E-02 3.00E-02 3.00E-02 1.40E-03 1.40E-03 1.40E-03 1.40E-03 1.00E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 5.00E-06 5.00E-06 2.50E-03 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1.00E-06 1.00E-06 5.00E-02 Fmi (goat) 1.70E-01 1.00E-01 4.00E-02 2.50E-01 2.20E-03 2.50E-04 2.50E-04 1.30E-04 1.30E-04 1.00E-03 1.00E-03 1.00E-03 6.70E-03 6.70E-03 1.30E-02 3.90E-02 3.90E-02 3.90E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 3.00E-02 3.00E-02 3.00E-02 1.40E-02 1.40E-02 1.40E-02 1.40E-02 1.00E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 5.00E-06 5.00E-06 2.50E-03 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1.00E-06 1.00E-06 5.00E-02 Ffi (beef) 1.20E-02 3.10E-02 3.00E-02 4.60E-02 2.40E-03 8.00E-04 8.00E-04 1.20E-02 1.20E-02 1.30E-02 1.30E-02 1.30E-02 5.30E-02 5.30E-02 9.70E-04 3.00E-02 3.00E-02 3.00E-02 2.60E-02 2.60E-02 2.60E-02 2.60E-02 3.10E-02 3.10E-02 3.10E-02 6.00E-04 6.00E-04 6.00E-04 6.00E-04 4.60E-03 4.60E-03 4.60E-03 4.60E-03 4.60E-03 3.40E-02 3.40E-02 2.80E-01 2.80E-01 1.10E-03 4.00E-01 4.00E-01 4.00E-01 4.00E-01 4.00E-01 1.70E-02 2024o
Table 6.2 (3 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA ODCM Revision 0
Page 91 of 208 Half-Life (minutes)
Biv Fmi Fmi Ffi (1/s)
(cow)
(goat,)
(beef)
Xe-133 7.55E+03 Xe-135m 1.54E+01 Xe-135 5.47E+02 Xe-137 3.83E+00 Xe-138 1.41E+Ol 1.53E-06 7.50E-04 2.11E-05 3.02E-03 8.19E-04 N/A N/A N/A N/A N/A N/A N/A'/A N/A N/A-N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
References:
Half lives for all nuclides:
DOE-TIC-11026, "Radioactive Decay Data Tables A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment,"
D. C. Kocher, 1981.
Transfer factors for Sb-isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.
Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.
Goat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.
Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.
All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.
2024o
Table 6.3 (2 of 2)
DOSE CALCULATION FACTORS ODCM Revision 0
Page 93 of 208 Factor Value Units Reference Uf(infant)
Uf(child)
Uf(teen)
Uf(adult)
UFL (infant)
UFL (child)
UFL (teen)
UFL (adult)
US (infant)
US (child)
US (teen)
US (adult)
U~(infant)
Uz(child)
U~(teen)
U(adult)
W Yf Yp Ysf Ysv X~ (iodines)
X (particulates) 0 6.9 16 21 0
26 42 64 0
520 630 520 330 510 510 730 0.3 1.85 1.18 0.64 0.57 kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year L/year L/year L/year L/year none kg/m2 kg/m2 kg/m2 kg/m2 7.71E-07 sec 1
(15.4 d half-life) 5.21E-07 sec 1
(10.4 d half-life)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table A-2)
NUREG/CR-1004 (Table 3.4)
NUREG/CR-1004 (Table 3.3)
NUREG/CR-1004 (Table 3.3)
NUREG/CR-1004 (Table 3.4)
(value selected is for non-leafy vegetables)
NUREG/CR-1004 (Table 3.10)
NUREG/CR-1004 (Table 3.10) 2024o
Table 6.4 (2 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
ODCM Revision 0
Page 95 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 2.80E-06 1.79E-06 2.68E-06 6.77E-06 1.10E-07 1.15E-05 3.14E-OS 1.73E-06 1.97E-OS 2.52E-06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1.06E-07 4.43E-07 6.22E-05 6.51E-06 7.97E-05 5.52E-OS 9.70E-OS 2.03E-05 4.71E-OS 2.13E-OS 2.50E-09 1.28E-10 9.36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-11 6.29E-09 1.03E-07 1.19E-09 liver 5.29E-OS 2.00E-OS 9.71E-07 2.42E-06 3.95E-OS 4.29E-06 1.18E-OS 8.46E-07 8.23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.47E-06 2.88E-07 1.16E-06 1.48E-04 2.57E-05 1.09E-04 1.09E-07 6.91E-11 2.55E-OS 3.56E-11 2.19E-11 1.26E-09 5.82E-11 6.33E-09 1.22E-06 2.04E-07 3.69E-09 1.25E-11 7.27E-09 8.61E-OS 1.17E-10 t body 1.11E-06 4.26E-07 3.59E-07 8.25E-07 2.38E-OS 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06 S.SOE-07 3.41E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21E-04 1.85E-05 7.14E-05 5.40E-OS 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-11 7.18E-10 1.35E-10 2.62E-OS 4.56E-10 1.53E-12 4.35E-10 3.01E-OS 6.45E-11 ADULT thyroid.
.6.79E-09 1.82E-09 8.06E-07 1.73E-06 8.15E-OS 3.95E-06 2.41E-OS 1.34E-06 1.62E-OS 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE-OO O.OOE-OO 1.09E-05 2.75E-05 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-OS 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E-05 8.01E-OS 6.46E-11 8.67E-09 3.31E-11 1.85E-11 O.OOE+00 O.OOE+00 2.94E-09 5.37E-10 1.21E-07 2.13E-09 7.05E-12 4.25E-09 O.OOE+00 3.65E-10 lung 2.18E-06 1.38E-06 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.59E-05 1.96E-06 1.23E-05 7.91E-09 3.92E-ll 1.46E-08 2.02E-11 1.24E-11 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 7.95E-05 1.97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-OS 8.40E-05 2.79E-09 7.71E-05 1.92E-06 1.57E-06 1.02E-07 2.22E-06 2.51E-10 1.31E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1.72E-07 4.18E-05 2.22E-17 3.00E-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1.65E-04 4.03E-05 4.33E-18 3.49E-05 2.82E-05 2.40E-05
References:
Regulatory Guide 1.109, Table E-ll.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake
, November,
- 1977, Table 4.
NOTE: The tritium dose factor total body dose factor.
for bone is assumed to be equal to the 2024o
Table 6.4 (4 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
ODCM Revision 0
Page 97 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141
'e-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 3.87E-06 2.48E-06 3.83E-06 9.67E-06 1.58E-07 1.63E-05 4.48E-08 2.44E-06 2.79E-OS 3.49E-06 1.03E-06 5.85E-06 2.79E-07 2.01E-06 1.46E-07 6.10E-07 8.37E-05 8.59E-06 1.12E-04 7.76E-08 1.39E-07 2.84E-05
- 6. 71E-08 2.99E-08 3.48E-09 1.79E-10 1.33E-08 2.35E-09 6.96E-07 1.31E-08 4.30E-11 9.38E-09 1.46E-07 1.76E-09 liver 7.13E-08 2.71E-08 1.38E-06 3.43E-06 5.60E-08 6.05E-06 1.67E-08 1.17E-06 1.15E-08 2.21E-06 2.98E-06 8.19E-06 7.30E-07 3.41E-06 3.87E-07 1.57E-06 1.97E-04 3.38E-05 1.49E-04 1.49E-07 9.78E-11 3.48E-08 5.01E-11 2.99E-ll 1.71E-09 7.95E-11 8.88E-09 1.71E-06 2.88E-07 5.23E-09 1.76E-11 1.02E-08 1.19E-07 1.66E-10 t body 1.51E-06 5.80E-07 5.12E-07 1.15E-06 3.40E-08 2.58E-06 1.09E-08 9.76E-07 8.72E-09 2.08E-06 1.19E-06 4.40E-06 2.62E-07 1.04E-06 1.39E-07 5.82E-07 9.14E-05 2.27E-05 5.19E-05 7.45E-08 4.05E-09 1.83E-06 2.24E-09 1.84E-09 4.55E-10 1.98E-11 1.02E-09 1.91E-10 3.74E!-08 6.52E-10 2.18E-12 6.11E-10 4.17E-08 9.22E-11 TEEN thyroid.
8.78E-09 2.37E-09 1.07E-06 2.30E-06 1.09E-07 5.26E-06 3.20E-08 1.76E-06 2.15E-08 2.33E-06 2.43E-04 2.39E-03 2.46E-05 4.76E-04 6.45E-06 1.01E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE-OO O.OOE+00 O.OOE+00 3.92E-05 6.40E-07 6.82E-05 1.88E-07 1,22E-05 1.22E-07 2.12E-05 4.59E-06 1.41E-05 1.15E-06 5.98E-06 6.10E-07 2.48E-06 6.26E-05 1.84E-05 5.07E-05 1.10E-07 9.22E-11 1.18E-08 4.65E-11 2.53E-11 O.OOE+00 O.OOE+00 4.18E-09 7.67E-10 1.72E-07 3.04E-09 1.01E-11 5.99E-09 O.OOE+00 5.21E-10 lung 3.38E-06 2.18E-06 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 2.39E-05 2.90E-06 1.97E-05 1.28E-08 6.74E-ll 2.34E-08 3.43E-11 1.99E-11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 7.80E-05 1.93E-05 1.13E-05 2.41E-05 1.22E-05 6.12E-05 2.45E-07 9.39E-05 2.29E-09 7.00E-05 2.29E-06 1.62E-06 3.18E-07 2.58E-06 5.10E-09 1.74E-06 2.45E-06 2.72E-06 2.12E-06 6.76E-ll 1.24E-06 4.38E-05 1.43E-13 9.18E-20 9.82E-05 2.42E-06 2.54E-05 5.14E-05 1.75E-04 4.31E-05 4.74E-14 3.68E-05 3.22E-05 2.67E-05
References:
Regulatory Guide 1.109, Table E-12.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake
, November, 1977, Table 3.
NOTE: The tritium dose factor total body dose factor.
for bone is assumed to be equal to the 2024o
Table 6.4 (6 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
ODCM Revision 0
Page 99 of 208
'I Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.11E-05 7.16E-06 1.14E-05 2.89E-05 4.71E-07 4.87E-05 1.34E-07 7.20E-06 8.30E-OS 1.01E-05 2.92E-06 1.72E-05 S.OOE-07 5.92E-06 4.19E-07 1.75E-06 2.34E-04 2.35E-05 3.27E-04 2.28E-07 4.14E-07 8.31E-05 2.00E-07 8.74E-OS 1.01E-OS 5.24E-10 3.97E-OS 6.99E-09 2.08E-06 3.93E-OS 1.29E-10 2.79E-OS 4.29E-07 5.25E-09 liver 1.44E-07 5.52E-OS 3.09E-06 7.78E-06 1.27E-07 1.36E-05 3.74E-OS 2.49E-06 2.53E-OS 4.47E-06 5.90E-06 1.73E-05 1.47E-06 7.32E-06 7.78E-07 3.15E-06 3.84E-04 6.46E-05 3.13E-04 3.17E-07 2.21E-10 7.28E-OS 1.12E-10 6.29E-11 3.53E-09 1.67E-10 1.98E-OS 3.79E-06 6.52E-07 1.18E-OS 3.99E-11 2.26E-OS 2.54E-07 3.77E-10 t body 3.89E-06 1.50E-06 1.52E-06 3.43E-06 1.01E-07 7.56E-06 3.18E-OS 2.65E-06 2.47E-OS 5.40E-06 3.04E>>06 9.83E-06 6.76E-07 2.77E-06 3.58E-07 1.49E-06 8.10E-05 4.18E-05 4.62E-05 2.01E-07 1.20E-OS 4.85E-06 6.51E-09 4.88E-09 1.19E-09 5.23E-ll 2.94E-09 5.49E-10 1.11E-,07 1.95E-09 6.49E-12 1.75E-09 1.14E-07 2.65E-10 CHILD thyroid.
2.45E-OS 6.63E-09" 3.20E-.06 6.91E-06 3.26E-07 1.57E-05 9.56E-OS 5.12E-06 6.35E-OS 6.51E-06 6.50E-04 5.72E-03 6.82E-05 1.36E-03 1.79E-05 2.79E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0;OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 1.34E-06 1.43E-04 3.92E-07 2.41E-05 2.51E-07 4.15E-05 8.82E-06 2.84E-05 2.25E-06 1.22E-05 1.19E-06 4.83E-06 1.19E-04 3.44E-05 1.02E-04 2.23E-07 1.93E-10 2.37E-OS 9.69E-ll 5.09E-11 O.OOE+00 O.OOE+00 8.68E-09 1.59E-09 3.61E-07 6.39E-09 2.11E-ll 1.24E-OS O.OOE+00 1.09E-09 lung 6.16E-06 3.99E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.27E-05 5.13E-06 3.67E-05 2.40E-OS 1.30E-10 4.34E-OS 6.58E-10 3.70E-11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 6.94E-05 1.71E-05 1.10E-05 2.34E-05 1.84E-05 5.94E-05 8.34E-06 1.01E-04 4.36E-07 4.50E-05 2.76E-06 1.54E-06 1.73E-06 2.95E-06 5.16E-07 2.40E-06 2.07E-06 2.27E-06 1.96E-06 1.46E-07 2.39E-05 4.21E-05 1.14E-07 1.14E-09 9.84E-05 3.31E-05 2.47E-05 5.55E-05 1.70E-04 4.24E-05 8.59E-OS 3.58E-05 3.57E-05 2.79E-05
References:
Regulatory Guide 1.109, Table E-13.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake
, November, 1977, Table 2.
NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the 2024o
Table 6.4 (8 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
ODCM Revision 0
Page 101 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs>>136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 2.14E-05 1.23E-05 2.33E-05 5.85E-05 1.00E-06 1.00E-04 2.84E-07 1.52E-05 1.76E-07 2.08E-05 6.00E-06 3.59E-05 1.66E-06 1.25E-05 8.69E-07 3.64E-06 3.77E-04 4.59E-05 5.22E-04 4.81E-07 8.81E-07 1.71E-04 4.25E-07 1.84E-07 2.11E-OS 1.10E-09 7.87E-08 1.48E-OS 2.98E-06 8.13E-OS 2.74E-10 5.53E-OS 9.03E-07 1.11E-OS liver 3.15E-07 1.19E-07 7.79E-06 1.94E-05 3.35E-07 3.43E-05 9.79E-OS 6.12E-06 6.50E-08 1.03E-05 1.32E-05 4.23E-05 3.37E-06 1.82E-05 1.78E-06 7.24E-06 7.03E-04 1.35E-04 6.11E-04 7.82E-07 5.84E-10 1.71E-07 2.91E-10 1.53E-10 8.32E-09 4.04E-10 4.80E-OS 9.82E-06 1.22E-06 3.04E-OS 1.06E-10 5.68E-08 6.28E-07 9.93E-10 t body 6.63E-06 2.53E-06 3.15E-06 7.08E-06 2.15E-07 1.54E-05 6.63E-OS 5.05E-06 4.94E-OS 9.61E-06 5.30E-06 1.86E-05 1.20E-06 5.33E-06 6.33E-07 2.64E-06 7.10E-05 5.04E-05 4.33E-05 3.79E-07 2.55E-OS 8.81E-06 1.34E-08 9.06E-09 2.14E-09 9.67E-11 5.65E-09 1.12E-09 1.67E;07 4.03E-09 1.38E-11 3.48E-09 2.17E-07 5.61E-10 INFANT thyroid 5.68E-08 1.54E-OS'.84E.-06 1.69E-05 8.14E-07 3.84E-05 2.38E-07 1.24E-05 1.57E-07 1.52E-05 1.48E-03 1.39E-02 1.58E-04 3.31E-03 4.15E-05 6.49E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 1.44E-04 2.44E-06 2.50E-04 7.07E-07 4.21E-05 4.50E-07 6.44E-05 1.45E-05 4.94E-05 3.76E-06 2.14E-05 1.99E-06 8.07E-06 1.81E-04 5.38E-05 1.64E-04 3.90E-07 3.51E-10 4.06E-OS 1.75E-10 8.81E-11 O.OOE+00 O.OOE+00 1.48E-OS 2.86E-09 4.93E-07 1.13E-OS 3.84E-11 2.19E-OS O.OOE+00 1.98E-09 lung 1.34E-05 7.72E-06 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.42E-05 1.10E-05 6.64E-05 6.09E-OS 3.54E-10 1.05E-07 1.77E-10 9.26E-11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEe00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 6.60E-05 1.64E-05 1.11E-05 2.36E-05 2.10E-05 5.97E-05 2.27E-05 1.03E-04 7.11E-06 3.81E-05 2.83E-06 1.51E-06 2.73E-06 3.08E-06 1.84E-06 2.62E-06 1.91E-06 2.05E-06 1.91E-06 1.25E-06 5.58E-05 4.20E-05 5.19E-06 7.59E-07 9.77E-05 6.86E-05 2.48E-05 5.73E-05 1.71E-04 4.29E-05 4.93E-06 3.60E-05 3.69E-05 2.87E-05
References:
Regulatory Guide 1.109, Table E-14.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake
, November,
- 1977, Table 1.
NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the 2024o
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Page 103 of 208 Table 6.6 (1 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )
Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-124 Total Body 0.0 0.0 2.50E-08 0.0 2.20E-10 5.80E-09 1.10E-08 0.0 8.00E-09 1.77E-09 7.00E-09 1.70E-08 0.0 3.70E-09 1.50E-09 4.00E-09 0.0 5.50E-09 3.18E-08 6.40E-11 1.20E-08 0.0 6.30E-10 3.50E-09 1.50E-08 5.60E-13 7.10E-09 9.00E-09 2.20E-12 3.80E-09 2.40E-11 1.60E-09 5.70E-10 5.00E-09 5.50E-09 5.10E-09 8.11E-09 1.90E-09 9.60E-10 2.70E-09 3.60E-09 4.50E-09 1.50E-09 1.80E-08 2.17E-08 Skin 0.0 0.0 2.90E-08 0.0 2.60E-10 6.80E-09 1.30E-08 0.0 9.40E-09 2.21E-09 8.20E-09 2.00E-08 0.0 4.30E-09 1.70E-09 4.60E-09 0.0 6.59E-09 3.90E-08 9.30E-11 1.40E-08 0.0 7.20E-10 4.00E-09 1.80E-08 6.50E-13 8.30E-09 1.00E-08 2.60E-12 4.40E-09 2.70E-11 1.90E-09 7.80E-10 5.80E-09 6.40E-09 6.00E-09 1.00E-08 2.20E-09 1.10E-09 3.00E-09 4.20E-09 5.10E-09 1.80E-09 2.10E-08 2.57E-08 2024o
Figuze 6.1 LI UID RELEASE POINTS ODCM Revision 0 Page 105 of 208 BFH Uquld Eff1uan! Monltora 0'yptcat Unit and Common Rahvaata)
Cnndeneer Ceeana Wrier RHR aenrtre We1et Intake Bay RHR Rll $0.1 $$
R11 $0.1$ e RaLverre (eenenenf Openrna rer Helper il (t) Turbine Butldlng Equlpmant (2) Reactor But(ding Equlpmant (3) Condenaar Te Ceeara Tewere 2024o
ODCM Revision 0
Page 107 of 208 SECTION 7.0 GASEOUS EFFLUENTS
- 2024o
7.1 RELEASE RATE LIMIT METHODOLOGY ODCM Revision 0
Page 109 of 208 A dose rate (DTB, DS, or DTH) is calculated based on the design objective source term mix used in the licensing of the plant.
Dose rates are determined for (1) noble gases and (2) iodines and particulates as described below.
Total Bod Dose Rate The dose rate to the total body from nuclide i, DTBi in mrem/year, is calculated using the following equation:
DTBi = (X/Q) Qi DFBi where X/Q DFBi relative concentration, s/m Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.
release rate of noble gas nuclide i, pCi/sec.
total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m (Table 7.4).
Skin Dose Rate The dose rate to the skin for nuclide i, Dsi in mrem/year, is calculated using the following equation:
Dsi = (X/Q) Qi(DFSi + 1.11 Dpi) where X/Q DFSi Dpi relative concentration, s/m3.
Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.
release rate of noble gas nuclide i, pCi/sec.
skin dose factor due to beta radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).
the average ratio of tissue to air energy absorption coefficients, mrem/mrad.
dose conversion factor for external gamma for noble gas nuclide i, mrad/year per pCi/m3 (Table 7.4).
2024o
The dose rate limits of interest are.'DCM Revision 0
Page ill of 208 Total Body = 500 mrem/yr Skin = 3000 mrem/yr Maximum Organ
= 1500 mrem/yr These limits are divided by the corresponding calculated dose rates described above:
RTB(vent or stack)
Total Body Dose Rate Limit ven or s ac RS(vent or stack)
=
Skin Dose Rate Limit
)
S ven or s ac RTH(vent or stack)
Maximum Organ Dose Rate Limit ven or s ac These ratios represent how far above or below the guidelines the dose rate calculations were.
A total release
- rate, Q, for each nuclide type (noble gas or iodine/particulate) and release point (building vent or stack) is calculated, using the source term data in Table 7.2.
Thus, four total release rates are calculated:
Qngv = Total noble gas release rate Qngs
= Total noble gas release rate Qipv Total iodine and particulate vents, Ci/s.
Qips Total iodine and particulate from building exhaust vents, Ci/s.
from main stack, Ci/s.
release rate from building exhaust release rate from main stack, Ci/s.
To obtain a release rate limit, r, For each nuclide type and release point, the total release
- rate, Q, for that nuclide type and release point is multiplied by the corresponding ratio, R:
For noble gases released from building vents:
ngv
= RTBv Qngv~
= RSv Qngv
.whichever is more restrictive, i.e., smaller.
2024o
ODCM Revision 0
Page 113 of 208 The release rate limits, r, calculated for BFN using this methodology are.'
Noble Gas Iodine and Particulate Stack Building Vents rngs
= 1.44E+01 Ci/s rngv 1 50E 01 Ci/s rips 3 ~ 57E 05 Ci/s ripv = 2 19E-06 Ci/s The values listed are used as administrative guidelines for operation.
The instantaneous release rates, r in Ci/sec~ for each nuclide type and release point are limited by the following equations:
For noble gases, rngv
+
0.15 rngs 14.4 For iodines and particulates, ripv 2.19E-06
+
rips 1
3.57E-05 2024o
ODCM Revision 0
Page 115 of 208
= flow rate for the vent, cc/sec.
Maximum flow rates are used to ensure conservative setpoints.
= efficiency of the monitor, (pCi/cc)/cpm (or (pCi/cc)/cps for the stack monitor)
= background of the monitor, cpm (cps for the stack monitor)
The calculation of these setpoints are documented further in Technical Instruction (TI) 15 and the applicable Scaling and Setpoint
- Document, including the numerical values for each of the parameters described above.
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ODCM Revision 0
Page 117 of 208 7.3.2 I-131 I-133 Tritium and all Radionuclides in Particulate Form wi,th Half-lives of Greater than 8 da s Or an Dose Rate Dose rates are calculated for the critical organ, thyroid, of the critical age group, infant.
Pathways considered are inhalatjon, ground contamination and milk ingestion.
The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e.,
the nearest SITE BOUNDARY points in each of the 16 sectors (from Table 7.1) and at other locations expected to be the maximum exposure points.
This calculation assumes that a (hypothetical) cow is at each of these locations.
These cows are assumed, conservatively, to obtain 100 percent of their food from pasture grass.
The inhalation, ground contamination, and milk ingestion dose rates (in mrem/year) for the selected organ (thyroid) and age group (infant) are calculated using Equation 7.9 as described in Section 7.6.2.
For determining the total thyroid dose rate from iodines and particulates:
DTH = DTHI + DTBG + DTH where.'TH
= total thyroid dose rate, mrem/yr.
DTHI = thyroid dose rate due to inhalation, mrem/yr.
DTBG = total body dose rate due to ground contamination, mrem/yr.
The thyroid dose rate is assumed to be equal to the total body dose rate for this pathway.
DTHg = thyroid dose rate due to pasture grass-cow-milk ingestion, mrem/yr.
The iodine and particulate dose rates are calculated for the design objective source term given in Table 7.2.
The above dose rate calculation is repeated for each release point.
Dose rates for releases from all building vents are summed.
The maximum stack and building vent thyroid dose rates will be used to determine release rate limits.
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7.4.1.2 Monthl Conservative Model Beta Air Dose ODCM Revision 0
Page 119 of 208 (x/Q)
Dg =
0.9 where
106 Qi Dpi 3.15E+07 (7 3)
Dg x/Q 0.9 106 3.15E+07 Qi DF8i
= beta dose to air, mrad.
= highest annual-average relative concentration at or beyond the SITE BOUNDARY, s/m3 (from Table 7.1).
= 1.84E-06 for ground level releases,
= 2.08E-08 for elevated releases (stack).
= fraction of total beta dose expected to be contributed by the assumed nuclides.
pCi/Ci conversion factor.
= s/yr conversion factor.
= monthly release of radionuclide i, Ci.
= beta-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).
7.4.1.3 Cumulative Dose Noble Gas Cumulative calendar quarter doses are estimated by summing the doses calculated for each month i.n that quarter.
Cumulative calendar year doses are estimated by summing the doses calculated for each month in that year.
7.4.1.4 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits to determine compliance.
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Page 121 of 208 7.5.1 Monthl Conservative Model Infant Th roid Dose from Milk
~in cation The monthly thyroid dose from milk ingestion is calculated using the following equation:
[ E(Qi RCPi) D/Q + (QT RCPT) X/Q ] 106 DTH -
i 0.9 (3.15E+07) where D/Q Qi
= monthly release of iodine nuclide i, Ci.
QT
= monthly release of H-3, Ci.
RCPi
= I-131 or I-133 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m -s.
Dose factors are calculated as described in Section 7.8.1.
RCPT
= H-3 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m The dose factor is calculated as described in Section 7.8.7.
= highest relative deposition rate for a location with an identified milk cow, m
(from Table 7.1).
= 3.16E-10 for ground level releases,
= 2.30E-10 for elevated releases (stack).
X/Q
= highest relative air concentration for a location with an identified milk cow, s/m3 (from Table 7.1).
= 1.47E-07 for ground level releases,
= 1.69E-08 for elevated releases (stack).
0.9
= fraction of dose expected to be contributed by I-131, I-133 and H-3.
3.15E+07
= s/yr.
106
= pCi/Ci.
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ODCM Revision 0 Page 123 of 208 7.5.3 Monthl Conservative Model Teen Gastrointestinal Tract GIT)
Dose from Ve etable In estion The monthly teen GIT dose from vegetable ingestion is calculated using the following equation:
[ Z(Q'F ) D/Q + QT DFT X/Q ] 10 DGT i
~
+
where D/Q Qi
= monthly release of cobalt nuclide i~ Ci.
QT
= monthly release of H-3, Ci.
DFi
= Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem/yr per pCi/m -s.
= RVFi + RVSi~ where RVFi is the dose factor for fresh leafy vegetables (as calculated in Section 7.8.5) and RVSi is the dose factor for stored vegetables (as calculated in Section 7.8.6).
= Total vegetable ingestion dose factor to the teen GIT for H-3, mrem/yr per pCi/m3.
= RVFT + RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 7.8.11) and RVST is the tritium dose factor for stored vegetables (as calculated in Section 7.8.12).
= highest relative deposition rate for a location with an identified home use garden, m
(from Table 7.1).
= 4.46E-09 for ground level releases,
= 1.13E-09 for elevated releases (stack).
X/Q
= highest relative air concentration for a location with an identified home use garden, s/m (from Table 7.1).
= 1.57E-06 for ground level releases,
= 9.50E-09 for elevated releases (stack).
3.15E+07
= s/yr.
106
= pCi/Ci.
0.9
= fraction of total teen CIT dose expected to be contributed by H-3, Co-58, and Co-60.
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7.6 GASEOUS RADWASTE TREATMENT 7.6.1 Dose Pro 'ections ODOM Revision 0
Page 125 of 208 Dose projections will be performed by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
If the results of the dose projection indicate potential doses in excess of the monthly fraction of the annual dose limit, efforts will be made to minimize future releases.
7.6.2 S stem Descri tion A flow diagram for the GRTS is given in Figure 7.1.
The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers.
One gaseous radwaste treatment system is provided for each unit.
The processed gases from each unit are routed to the plant stack for dilution and elevated release to the atmosphere.
The air-ejector off-gas line of each unit and the stack are continuously monitored by radiation monitors.
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7.7.1.1 Gamma Dose to Air ODCM Revision 0
Page 127 of 208 D~
7 Xni DF~i 1
(7.7) where:
Dyn Xni DFyi gamma dose to air for sector n, mrad.
air concentration of radionuclide i in sector n, pCi-year/m Air concentrations are calculated as described by Equation 7.11.
gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).
7.7.1.2 Beta Dose to Air Dan = E Xni DFOi where:
Dan Xni Dpi
= beta dose 'to air for sector n, mrad.
air concentration of radionuclide i in sector n, pCi-year/m Air concentrations are calculated as described by Equation 7.11.
= beta to air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).
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ODCM Revision 0
Page 129 of 208 Qi
= adjusted release for nuclide i for location under consideration, pCi.
The initial release is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector.
- Hence, the adjusted release is equal to the actual release decayed for an average travel time during the period.
9
= Qi0 E fj exp(-Xi x/uj) j=l RPT QT where Qi0
= initial average release for nuclide i over the period,
@Cia fj
= joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.
Xi
= radiological decay constant for nuclide i, sec l.
x
= downwind distance, meters.
uj
= midpoint value of wind speed class interval j, m/st ingestion dose factor for pathway P for tritium, mrem/year per pCi/m3.
Ingestion pathways available for consideration are the same as those listed above for Rpi.
Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through 7.8.12.
adjusted release for tritium for location under consideration, pCi.
Calculated in the same manner as Qi above.
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ODCM Revision 0
Page 131 of 208 ADC = exp(-Kit),
for milk and vegetables, where decay constant for nuclide i, seconds.
= distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-l).
= 1.21E+06 seconds (14 days) for vegetables.
= 3.46E+05 seconds (4 days) for milk.
exp(-Kit) Kitch ADC 1 - exp(-X itch) where for meat, Xi
= decay constant for nuclide i, seconds.
t
= additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7 days (from Regulatory Guide 1.109, Table D-2).
tcb
= time to consume a whole beef, as described in Section 7.8.3.
For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose.
This assumes that the maximum individual freezes and eats a whole beef, but the average individual buys smaller portions at a time.
Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.
7.7.4 Re ortin of Doses The calculated quarterly doses and calculated population doses described in this section are reported in the Semiannual Radioactive Effluent Release Report as described in ODCM Administrative Control 5.2 2024o
7.8.2 Stored Feed-Cow/Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/second)
ODCM Revision 0
Page 133 of 208 (1-exP(-Xitcsf))
CSi =
0 DF iao Uap mi Qf s exP( Xitfm) csf i where:
r(1-exP(-XEtesf))
Biv(1-exP(-Xitb))
~sf >E P Ai 106 DFLiao Uap Fmi Qffs Xi tfm tcsf r
XE tesf
>sf Biv tb NOTE conversion factor, pCi/pCi.
= ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).
= milk ingestion rate for age group a, L/year.
= transfer factor for nuclide i from animal's feed to milk, days/L (Table 6.2).
= animal's consumption rate, kg/day.
= fraction of time animal spends on stored feed, dimensionless.
decay constant for nuclide i, seconds (Table 6.2).
= transport time from milking to receptor, seconds.
= time between harvest of stored feed and consumption by animal, seconds.
= fraction of activity retained on pasture
- grass, dimensionless.
the effective decay constant, due to radioactive decay and weathering, seconds 1, equal to 'Ai + Xw.
weathering decay constant for leaf and plant surfaces, seconds
= time stored feed is exposed to deposition, seconds.
= agricultural productivity by unit area of stored feed, kg/m2.
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
= time period over which accumulation on the ground is evaluated, seconds.
= effective surface density of soil, kg/m Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.8.4 Stored Feed-Beef In estion Dose Factors (m2-mrem/year per pCi/second)
ODCM Revision 0
Page 135 of 208
~
(1-exp(-'hit b) )
RMSi = 10 DFLiao Uam Ffi Qf exP( Kits) i cb where:
(1-exp (-'Ait f) )
fs Xi tcsf r(l-exP(-XEtesf))
Biv(1-exP(-Xitb))
Ysf XE P Xi 106 DFLiao UaFfi Qf Xi tcb ts fs tcsf r
tesf
>sf XE Xw Biv tb P
NOTE'onversion factor, pCi/pCi.
= ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).
= meat ingestion rate for age group a, kg/year.
= transfer factor for nuclide i from cow's feed to meat, days/kg (Table 6.2).
= cow's consumption rate, kg/day.
decay constant for nuclide i, seconds (Table 6.2).
= time for receptor to consume a whole beef, seconds.
= transport time from slaughter to consumer, seconds.
= fraction of time cow spends on stored feed, dimensionless.
= time between harvest of stored feed and consumption by cow, seconds.
= fraction of activity retained on pasture
- grass, dimensionless.
= time stored feed is exposed to deposition, seconds.
= agricultural productivity by unit area of stored feed, kg/m2.
the effective decay constant, due to radioactive decay and weathering, seconds
, equal to Xi + Q.
weathering decay constant for leaf and plant surfaces, seconds
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
= time over which accumulation on the ground is evaluated, seconds.
= effective surface density of soil, kg/m2.
Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.8.6 Stored Ve etable In estion Dose Factors m -mrem/year per pCi/second)
ODCH Revision 0
Page 137 of 208 (1-e(-X t
))
RgSi = 10 "iao exp( Xi hc)
Sa g i
sv where:
r(1-e(-%Etc) )
Biv(1-e(-Xitb))
(
}
~sv >E P Xi 106 DFLiao
'Ai thc USa fgtsv te lsv
>iv tb conversion factor, pCi/pCi.
= ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).
decay constant for nuclide i, seconds (Table 6.2).
= average time between harvest of vegetables and their consumption and/or storage, seconds.
= consumption rate of stored vegetables by the receptor in age group a, kg/year.
= fraction of stored vegetables grown locally, dimensionless.
= time between storage of vegetables and their consumption, seconds.
= fraction of deposited activity retained on vegetables, dimensionless.
the effective decay constant, due to radioactive decay and weathering, seconds
+tw decay constant for removal of activity on leaf and plant surfaces by weathering, seconds
= exposure time in garden for fresh leafy and/or stored vegetables, seconds.
= vegetation areal density for stored vegetables, kg/m
= transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
= time period over which accumulation on the ground is evaluated, seconds.
= effective surface density of soil, kg/m.
NOTE:
Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )
ODCM Revision 0
Page 139 of 208 (1-exP(-XTtcsf))
RCTS 10 10 DFLTao FmT pf Uap [0'5(0 '/H)] fs exp(-'ATtfm)
T csf where:
103 106 DFLTao FmT Qf o.15 0.5 H
fs XT tcsf tfm conversion factor, g/kg.
conversion factor, pCi/pCi.
= ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).
= transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).
= animal's consumption rate, kg/day.
= milk ingestion rate for age group a, L/year.
= the fraction of total feed that is water.
= the ratio of the specific activity of the feed grass water to the atmospheric water.
= absolute humidity of the atmosphere, g/m3.
= fraction of time animal spends on stored feed, dimensionless.
decay constant for tritium, seconds 1 (Table 6.2).
= time between harvest of stored feed and consumption by animal, seconds.
= transport time from milking to receptor, seconds.
NOTE:
Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )
ODCM Revision 0
Page 141 of 208 RMTS = 10 10 DFLTao FfT Qf'Uam [0.75(0.5/H)] fs exP(-its)
(1-exP( XTtcsf))
(1-exP( XTtcb))
where:
XT tcsf XT tcb 103 106 DFLTao FfT Qf Uam
- 0. 75 0.5 H
fs XT ts tcsf tcb conversion factor, g/kg.
conversion factor, pCi/pCi.
= ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).
= transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).
= cow's consumption rate, kg/day.
= meat ingestion rate for age group a, kg/year.
= the fraction of total feed that is water.
= the ratio of the specific activity of the feed grass water to the atmospheric water.
= absolute humidity of the atmosphere, g/m3.
= fraction of time cow spends on stored feed, dimensionless.
decay constant for tritium, seconds (Table 6.2).
= transport time from slaughter to consumer, seconds.
= time between harvest of stored feed and consumption by animal, seconds.
= time for receptor to consume a whole beef, seconds.
NOTE:
Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.8.12 Tritium-Stored Ve etables Dose Factor (mrem/year per pCi/m )
ODCM Revision 0
Page 143 of 208 (1-exP(-XTtsv))
RATS = 10 10 DFLTao [0.75(0.5/H))
USa g
exP(-XTthc)
T sv where:
103 106 DFLTao
- 0. 75 0.5 H
USa fg XT tsv thc conversion factor, g/kg.
conversion factor, pCi/pCi.
= ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).
= the fraction of total vegetation that is water.
= the ratio of the specific activity of the vegetation water to the atmospheric water.
= absolute humidity of the atmosphere, g/m3.
= consumption rate of stored vegetables by the receptor in age group a, kg/year.
= fraction of stored vegetables grown locally, dimensionless.
decay constant for tritium, seconds 1 (Table 6.2).
= time between harvest of stored vegetables and their consumption and/or storage, seconds.
= time between harvest of vegetables and their storage, seconds.
NOTE:
Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
2024o
7.9 DISPERSION METHODOLOGY ODCM Revision 0
Page 145 of 208 Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.
Meteorological data for ground level releases consist of windspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.
Hourly average meteorological data for the ground level portion of a split level release consist of wind speeds and directions measured at the 10m level and temperature measurements at 10m and 45m.
The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.
Raw meteorological data for the elevated releases consist of windspeed and directions measured at 93m.
Stability class D is assumed to persist during the entire period for elevated
- releases, except for the dose calculations described in Section 7.7 when all stability classes will be used to evaluate the elevated results.
Meteorological data are expressed as a joint-frequency distribution of wind
- speed, wind direction, and atmospheric stability for each release level (ground, split and elevated).
The joint-frequency distributions which represent the historical meteorological data for the period January 1977 to December 1979 are given in Table 7.3.
The wind speed classes that are used are as follows:
Number
//)
(//
(0.3 0.13 0.3-0.6 0.7-1.5 0.45 1.10 1.6-2.4 1.99 2.5-3.3 3.4-5.5 2.88 4.45 5.6-8.2 6.91 8.3-10.9 9.59 9
)10.9 10.95 The stability classes that will be used are the standard A through G
classifications.
The stability classes 1-7 will correspond to A=1, B=2,...,
G=7.
2024o
~ I
7.9.2 Relative Concentration X/q (sec/m
)
ODCM Revision 0
Page 147 of 208 Relative concentrations of nuclides at downwind locations are calculated using the following equation:
9 7
X/q
= E 7.
(2/~)'/2 j=l k=1 3
exP(.h 2/2azk2)
Ezk uj (21ac/n)
(7.12) where:
fjk Ezk or
= joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
vertical dispersion coefficient for stability class k which includes a building wake adjustment, (ozk2 + cA/e)1/2~
= l3 crzk, whichever is smaller (for ground level releases).
uj x
n 2m/n he where crzk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4),
c is a building shape factor (c=0.5),
A is the minimum building cross-sectional area (2400 m ).
midpoint value of wind speed class interval j, m/s.
= downwind distance, m.
= number of sectors, 16.
sector. width at point of interest, m.
effective release
- height, m.
The effective release height is calculated as described in Section 7.9.4.
7.9.3 Relative Dis ersion D/q (m-
)
Relative deposition of nuclides at downwind locations is calculated using the following equation:
f kDR D/~ =
Ej=l k=1 (2m/n)
(7.13) where:
fk DR x
n 2m/n joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.
= relative deposition rate, m
(from Figure 7.5).
The choice of figures is governed by the effective release height calculation described in Section 7.9.4.
A linear interpolation is used for effluent release heights that fall in between the given curves.
= downwind distance, m.
"-number of sectors, 16.
sector width at point of interest, m.
2024o
Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA ODCM Revision 0
Page 149 of 208 GROUND LEVEL ELEVATED DISTANCE Elev above X/Q D/Q X/Q D/Q POINT from plant plant grade (s/m )
(1/m )
(s/m
)
(1/m2)
(m (m)
Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Air Dose Point Garden Garden Milk Cow Milk Cow 1525 N
7 1300 NNE 4
1250 NE 7
1450 ENE 0
1375 E
0 1575 ESE 0
5600 SE
-6 2875 SSE
-6 2550 S
-6 2425 SSW
-6 2300 SW
-6 2500 WSW
-6 2550 W
-6 3325 WNW
-6 2275 NW
-6 1650 NNW
-6 6100 NW
-6 1830 NNW 34 4437 E
19 8045 N
34 10975 NNW 34 1.60E-06 7.88E-07 4.52E-07 7.30E-07 8.24E-07 4.56E-07 7.61E-08 4.86E-07 8.27E-07 1.08E-06 6.87E-07 6.38E-07 6.70E-07 3.69E-07 1.69E-06 1.84E-06 N/A 1.57E-06 N/A 1.47E-07 N/A 5.64E-09 1.97E-09 1.56E-09 2.92E-09 4.04E-09 3.28E-09 3.63E-10 f.77E-09 2.24E-09 2.92E-09 1.75E-09 1.14E-09 1.25E-09 9.07E-10 4.92E-09 5.29E-09 N/A 4.46E-09 N/A 3.16E-10 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2.08E-08 N/A 9.50E-09 N/A 1.69E-08 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4.75E-10 1.13E-09 N/A 2.30E-10 N/A NOTE: For quarterly dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.
2024o
ODCM Revision 0
Page 151 of 208 Table 7.3 (1 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T( -1.9 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT January 1,
1977 December 31, 1979
- 0. 6-1.4 Wind Speed (mph) 1.5-3.5-5.5-7.5-12.5-18.5-3,4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.04 0.12 0.0 0.0 0.05 0.19 0.0 0.0 0.04 0.06 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 0.01 0.11 0.17 0.02 0.03 1.11 0.40 0.02 0.04 0.52 0.10 0.02 0.01 0.38 0.11 0.04 0.0 0.04 0.05 0.01 0.0 0.05 0.04 0.0 0.0 0.04 0.07 0.04 0.0 0.01 0.05 0.05 0.0 0.02 0.03 0.09 0.0 0.0 0.02 0.17 0.0 0.01 0.01 0.06 0.05 0.10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.06 0.11 0.09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.21 0.34 0.10 0.01 0.01 0.31 1.56 0.68 0.54 0.10 0.09 0.15 0.12 0.20 0.30 0.19 0.09 2.29 1.19
~ 0.90 0.42 0.02 0.0 4.91 Total hours of valid stability observations 25935 Total hours of Stability Class A 1262 Total hours of valid wind direction-wind speed-Stability Class A-Total hours calm 0
1259 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed
= 6.8 mph 2024o
ODCM Revision 0
Page 153 of 208 Table 7.3 (3 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class C
(-1.7
< Delta-T( -1.5 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4
)24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.01 0.17 0.12 0.11 0.03 0.03 0.0 0.0 0.01 0.0 0.0 0.08 0.11 0.07 0.09 0.03 0.08 0.02 0.02 0.03 0.02 0.05 0.02 0.29 0.09 0.17 0.04 0.25 0.04 0.06 0.01 0.12 0.03 0.11 0.07 0.05 0.12 0.12 0.13 0.05 0.09 0.02 0.08 0.21 0.17 0.05 0.0 0.0 0.0 0.01 0.01 0.02 0.0 0.01 0.07 0.10 0.17 0.22 0.18 0.02 0.20 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.07 0.10 0.10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.04 0.01 0.0 0.50 1.52 1.04 1.22 0.33 0.06 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.43 0.36 0.16 0.04 0.05 0.08 0.56 0.34 0.42 0.10 0.19 0.25 0.30 0.54 0.47 0.38 0.0 4.67 Total hours Total hours Total hours Total hours of valid stability observations 25935 of Stability Class C
1202 of valid wind direction-wind speed-Stability Class calm 0
C 1197 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed
=
7.0 mph 2024o
ODCM Revision 0
Page 155 of 208 Table 7.3 (5 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class E
(-0.5
< Delta-T( 1.5 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT January 1,
1977 December 31, 1979 0.6-1.4
- 1. 5-3.4
- 3. 5-5,4 Wind Speed (mph) 5.5-7.5-12.5-7.4 12.4 18.4 18.5-24.4
)24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.04 0.47 0.54 0.05 0.61 0.74 0.05 0.57 0.63 0.05 0.71 0.45 0.04 0.61 0.74 0.03 0.76 1.01 0.11 2.04 1.75 0.07 1.16 0.78 0.05 1.03 0.74 0.02 0.52 0.14 0.04 0.30 0.07 0.01 0.53 0.60 0.02 0.37 0.77 0.03 0.15 0.13 0.02 0.17 0.20 0.05 0.41 0.48 0.43 0.55 0.42 0.17 0.16 0.53 0.92 0.48 0.44 0.08 0.02 0.14 0.42 0.11 0.14 0.54 0.41 0.47 0.27 0.08 0.07 0.16 0.55 0.33 0.63 0.06 0.03 0.11 0.27 0.22 0.25 0.59 0.05 0.04 0.02 0.02 0.0 0.01 0.02 0.04 0.14 0.01 0.0 0.04 0.04 0.09 0.09 0.09 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.02 0.0 0.01 0.0 1.95 2.46 1.96 1.48 1.62 2.50 5.39 2.86 3.04 0.83 0.46 1.43 1.89 0.75 0.89 2.17 0.68 10.41 9.77 5.55 4.50 0.70 0.07 0.0 31-68 Total hours of valid stability observations 25935 Total hours of Stability Class E 8264 Total hours of valid wind direction-wind speed-Stability Class E-Total hours calm 3
8098 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed
=
5.0 mph 2024o
ODCM Revision 0 Page 157 of 208 Table 7.3 (7 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G
(Delta-T> 4.0 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-1,4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.07 0.76 0.32 0.05 0.83 0.51 0.04 0.34 0.12 0.04 0.48 0.18 0.02 0.52 0.34 0.01 0.18 0.01 0.08 0.43 0.09 0.03 0.44 0.31 0.05 0.09 0.12 0.05 0.05 0.01 0.0 0.01 0.0 0.02 0.02 0.0 0.01 0.01 0.0 0.01 0.02 0.0 0.04'.04 0.0 0.05 0.23 0.12 0.02 0.0 0.18 0.02 0.02 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.04 0.03 0.16 0.08 0.10 0.04 0.0 0.0 0.0 0.0 0.0 0.0 0-0 0.0 0.0 0.0 0.0 0.0 0.03 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.57 4.45 2.13 0.57 0.17 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.17 1.59 0.52 0.72 0.88 0.20 0.67 1.02 0.40 0.11 0.01 0.04 0.02 0.03 0.08 0.43 7.89 Total hours of valid stability observations 25935 Total hours of Stability Class G 2056 Total hours of valid wind direction-wind speed-Stability Class G-Total hours calm 4
2019 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed
=
3.2 mph 2024o
" ODCM Revision 0 Page 159 of 208 Table 7.3 (9 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T( -1.9 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.05 0.0 0.0 0.0 0.03 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.03 0.02 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.04 0.01 0.0 0.0 0.02 0.01 0.0 0.0 0.02 0.01 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 0.02 0.0 0.0 0.01 0.02 0.02 0.0 0.03 0.0 0.05 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.10 0.0 0.06 0.0 0.05 0.0 0.01 0.0 0.0 0.0 0.02 0.0 0.01 0.0 0.02 0.0 0.04 0.0 0.05 0.0 0.0 0.0 0.10 0.12 0.15 0.08 0.02 0.0 0.47 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class A -
133.1 Total hours of ground level Stability Class A 127.5 Meteorological facility:
located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 2024o
ODCM Revision 0
Page 161 of 208 Table 7.3 (11 of 22)
SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class C (-1.7
< Delta-T( -1.5 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1,
1977 December 31, 1979 0.6-Calm 1.4 Wind Speed (mph) 1.5-3.5-5.5-7.5-12.5-18.5-3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.03 0.0 0.01 0.02 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.01 0.01 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.01 0.01 0.01 0.01 0.02 0.02 0.01 0.03 0.02 0.01 0.02 0.03 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.03 0.01
'.0 0.0 0.04 0.0 0.03 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.03 0.0 0.03 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.04 0.0 0.08 0.0 0.07 0.0 0.06 0.0 0.0 0.0 0.03 0.11 0.17 0.08 0.05 0.0 0.44 Total hours of valid observations 25482.0 Total hours of ground level release -
2832.4 Total hours of Stability Class C
259.0 Total hours of,ground level Stability Class C 106.3 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03, and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity = 12.60 m/s 2024o
ODCM Revision 0
Page 163 of 208 Table 7.3 (13 of 22)
SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class E (-0.5<Delta-T< 1.5 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
)24.5 Total N
NNE NE ENE E
SSM SM MSW W
WNM NW NNW Sub-total 0.0 0.0 0.0 0.04 0.0 0.0 0.01 0.06 0.0 0.0 0.01 0.06 0.0 0.0 0.02 0.04 0.0 0.0 0.02 0.07 0.0 0.0 0.02 0.08 0.0 0.0 0.08 0.22 0.0 0.0 0.05 0.12 0.0 0.0 0.06 0.10 0.0 0.0 0.02 0.02 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.01 0.06 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.03 0.06 0.07 0.02 0.01 0.07 0.08 0.02 0.0 0.06 0.05 0.01 0.0 0.03 0.01 0.01 0.0 0.02 0.01 0.0 0.0 0.07 0.03 0.0 0.0 0.16 0.18 0.02 0.0 0.12 0.19 0.04 0.0 0.09 0.27 0.13 0.01 0.02 0.02 0.01 0.0 0.0 0.01 0.0 0.0 0.02 0.03 0.02 0.0 0.05 0.05 0.01 0.0 0.01 0.04 0.02 0.01 0.02 0.04 0.03 0.01 0.07 0.10 0.02 0.01 0.0 0.20 0.0 0.24 0.0 0.19 0.0 0.11 0.0 0.12 0.0 0.20 0.0 0.66 0.0 0.52 0.0 0.66 0.0 0.09 0.0 0.02 0.0 0.13 0.0 0.18 0.0 0.09 0.0 0.11 0.0 0.23 0.0 0.0 0.32 0.97 0.87 1.18 0.36 0.05 0.0 3.75 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class E 7920.6 Total hours of ground level Stability Class E 957.9 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Mind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 2024o
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Page 165 of 208 Table 7.3 (15 of 22)
SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)
Part 1 of 2 ground level release mode BROWNS FERRY NUCLEAR PLANT January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0
'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.04 0.0 0.0 0.02 0.06 0.03 0.0 0.01 0.01 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.0 0.03 0.01 0.01 0.0 0.04 0.05 0.03 0.0 0.01 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.08 0.0 0.0 0.0 0.0 0.0 0.0 o.o 0.0 o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.06 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.17 0.22 0.09 0.09 0.0 0.0 0.0 0.06 0.0 0.11 0.0 0.02 0.0 0.02 0.0 0.02 0.0 0.01 0.0 0.07 0.0 0.18 0.0 0.06 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.57 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class G
694.7 Total hours of ground level Stability Class G 151.7 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Effluent velocity = 12.60 m/s 2024o
ODCM Revision 0 Page 167 of 208 Table 7.3 (17 of 22)
SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class B (-1.9
< Delta-T< -1.7 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph)
- 0. 6-
- 1. 5-
- 3. 5-
- 5. 5-
- 7. 5-
- 12. 5-
- 18. 5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
ESE SE'SE S
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
'.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0" 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.01 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0..0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.01 0.03 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.01 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.06 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class B
185.1 Total hours of elevated stability class B 21.8 Meteorological facility:
located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 2024o
ODCM Revision 0
Page 169 of 208 Table 7.3 (19 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5
< Delta-T< -0.5 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1,
1977 December 31, 1979 Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.12 0.01 0.13 0.0 0.09 0.01 0.11 0.01 0.10 0.01 0.22 0.01 0.67 0.01 0.48 0.0 0.34 0.01 0.20 0.01 0.24 0.02 0.16 0.0 0.07 0.0 0.09 0.0 0.07 0.0 0.09 0.40 0.46 0.36 0.24 0.20 0.52 1.66 0.90 0.99 0.52 0.79 0.51 0.36 0.33 0.36 0.29 0.62 1.49 0.72 1.88 0.48 1.04 0.23 0.23 0.28 0.25 0.68 1.07 0.89 1.75 0.63 1.49 0.67 0.99 0.37 0.69 0.43 0.49 0.57 0.57 0".80 1.34 0.48 1.25 0.55 1.40 0.53 1.36 0.87 0.91 0.14 0.04 0.05 0.16
~ 0.84 1.08 0.93 0.34 0.32 0.27 0.55 0.94 1.44 1.15 0.12 0.05 0.02 0.01 0.01 0.0 0.16 0.26 0.33 0.11 0.05 0.08 0.16 0.32 0.37 0.19 0.0 3.62 0.0 4.16 0.0 2.)3 0.0 0.87 0.0 0.80 0.0 2.66 0.01 5.99 0.02 4.871 0.02 4.27 0.0 2.24 0.0 2.33 0.0 2.18 0.01 3.29 0.01 3.42 0.01 4.20 0.0 3.61 0.0 0.10 3.18 8.89 8.93 17.29 10.03 2.24 0.08 50.74 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class D - 13904.1 Total hours of elevated Stability Class D 12935.5 Neteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 2024o
ODCM Revision 0
Page 171 of 208 Table 7.3 (21 of 22)
JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class F ( 1.5
< Delta-T( 4.0 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1,
1977 December 31, 1979 0.6-Calm 1.4 Wind Speed (mph) 1.5-3.5-5.5-7.5-12.5-18.5-3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
NNE NE ENE E
WNW NW NNW Sub-total 0.0 0.0 0.03 0.08 0.0 0.0 0.04 0.06 0.0 0.0 0.04 0.10 0.0 0.0 0.04 0.11 0.0 0.0 0.03 0.07 0.0 0.0 0.13 0.26 0.0 0.0 0.13 0.38 0.0 0.0 0.09 0.11 0.0 0.0 0.08 0.11 0.0 0.0 0.04 0.12 0.0 0.0 0.04 0.09 0.0 0.0 0.03 0.07 0.0 0.01 0.04 0.04 0.0 0.0 0.02 0.04 0.0 0.0 0.03 0.04 0.0 0.0 0.02 0.02 0.06 0.34 0.05 0.0 0.11 0.42 0.21 0.0 0.15 0.40 0.12 0.0 0.11 0.29 0.07 0.0 0.11 0.32 0.02 0.0 0.24 0.24 0.0 0.0 0.30 0.19 0.0 0.0 0.12 0.14 0.03 0.0 0.13 0.21 0.03 0.0 0.14 0.24 0.01 0.0 0.10 0.06 0.0 0.0 0.06 0.05 0.0 0.0 0.05 0.04 0.0
'0.0 0.01 0.01 0.0 0.0 0.03 0.02 0.0 0.0 0.04 0.10 0.0 0.0 0.0 0.01 0.83 1.70 1.76 3.07 0.54 0.0 0.0 0.56 0.0 0.54 0.0 0.81 0.0 0.62 0.0 0.55 0.0 0.87 0.0 1.00 0.0 0.49 0.0 0.56 0.0 0.55 0.0 0.29 0.0 0.21 0.0 0.18 0.0 0.08 0.0 0.12 0.0 0.18 0.0 7.91 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class F 2385.0 Total hours of elevated Stability Class F 2028.0 Meteorological facility:
located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 2024o
Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ODCM Revision 0 Page 173 of 208 Submersion dose mrem/yr per pCi/m3 DFBi DFSi Air dose mrad/yr per pCi/m3 DFYi Dpi Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02 2.94E+02 3.12E+03 1.81E+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03
" 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 9.30E+03 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03
Reference:
Regulatory Guide 1.109, Table B-l.
2024o
ODCM Revision 0
Page 175 of 208 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT Distance to Midpoint of Sector Element 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 NE ENE ESE SE SSE SSW SW WSW 0
10 55 35 85 670 15'15 2615 10660 3690 0
5 15 65 55 915 2990 2230 3125 3420 0
5 25 45 88 4180 14180 6625 5385 12625 0
15 50 40 70 1310 4990 9615 13860 5425 0
30 10 40 945 1910 73405 75125 4610 0
5 0
0 165 1880 2535 7465 9575 0
0 0
20 10390 30945 4660 6230 13850 0
0 0
50 1630 6250 11630 15175 18945 0
20 35 90 1250 3805 1800 4475 3730 0
60 75 175 845 5895 1270 1490 2535 0
20 35 90 685 2970 2280 2725 10675 0
35 15 135 295 3060 3005 11545 3755 0
25 5
30 625 2960 6830 35070 4785 0
0 25 55 50 885 9300 39875 5545 0
0 0
5 345 4345 5215 5485 3260 5
35 25 20 625 2090 2440 12350 7360 2024o
Table 7.7 (2 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
ODCM Revision 0
Page 177 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 3.90E-06 6.67E-06 4.27E-07 1.58E-06 1.75E-10 1.22E-06 6.22E-12 8.74E-09 1.39E-12 3.25E-OS 5.72E-07 3.15E-06 1.45E-07 1.08E-06 8.05E-OS 3.35E-07'.66E-05 4.88E-06 5.98E-05 4.14E-OS 1.17E-10 4.88E-06 1.25E-11 3.29E-12 4.30E-08 8.54E-11 2.49E-06 2.33E-OS 4.29E-04 1.17E-06
- 3. 76E-12 6.59E-07 1.06E-09 2.87E-OS liver 7.36E-OS 7.44E-OS 1.98E-07 7.21E-07 8.03E-11 5.84E-07 2.99E-12 5.45E-09 7.44E-13 2.69E-08 1.68E-06 4.47E-06 4.07E-07 1.85E-06 2.16E-07 8.73E-07 1.06E-04 1.83E-05 7.76E-05 7.76E-08 8.32E-14 6.13E-09 9.41E-15 3.38E-15 2.17E-OS 3.88E-11 1.69E-06 1.72E-08 1.79E-04 4.69E-07 1.56E-12 7.62E-07 8.85E-10 2.82E-09 t body 1.55E-06 1.58E-06 5.84E-OS 1.96E-07 3.87E-11 1.98E-07 1.55E-12 3.63E-09 4.49E-13 2.02E-OS 6.60E-07 2.56E-06 1.45E-07 5.65E-07 7.69E-OS 3.21E-07 9.10E-05 1.38E-05 5.35E-05 4.05E-OS 3.42E-12 3.21E-07 4.20E-13 2.07E-13 5.73E-09 9.65E-12 1.91E-07 1.91E-09 2.30E-05 5.80E-08 1.91E-13 4.56E-08 3.10E-10 1.55E-09 ADULT thyroid 9.44E-09 6 '5E-09 1.31E-07 4.11E-07 1.32E-10 4.30E-07 4.87E-12 6.88E-09 1.17E-12 2.37E-OS 1.42E-04 1.49E-03 1.43E-05 2.69E-04 3.73E-06 5.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 1.55E-06 5.72E-06 6.37E-10 4.57E-06 2.34E-ll 3.86E-OS 5.46E-12 1.82E-07 2.61E-06 7.66E-06 6.48E-07 3.23E-06 3.44E-07 1.39E-06 3.59E-05 1.07E-05 2.78E-05 6.00E-08 7.78E-14 2.09E-09 8.75E-15 2.86E-15 O.OOE+00 O.OOE+00 7.83E-07 7.60E-09 1.06E-04 2.70E-07 8.81E-13 4.45E-07 O.OOE+00 8.75E-09 lung 3.10E-'4 2.18E-04 3.92E-05 1.20E-04 8.14E-07 1.45E-04 2.42E-07 1.82E-05 1.74E-07 3.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.22E-05 1.50E-06 9.40E-06 6.07E-09 4.70E-07 1.59E-04 2.42E-07 1.49E-07 1.70E-05 7.91E-07 4.52E-05 9.97E-06 9.72E-04 3.51E-05 1.27E-07 2.76E-05 3.63E-06 4.70E-06 gi-lli 5.08E-05 1.26E-05 8.83E-06 1.87E-05 7.17E-06 4.79E-05 1.96E-08 6 '5E-05 2.30E-09 6.37E-05 9.61E-07 7.85E-07 5.08E-OS 1.11E-06 1.26E-10 6.56E-07 1.30E-06 1.46E-06 1.05E-06 2.33E-13 1.12E-07 2.73E-05 1.45E-17 1.96E-26 5.73E-05 2.64E-07 1.50E-05 2.83E-05 1.02E-04 2.50E-05 2.69E-18 2.16E-05 1.94E-05 1.49E-05
Reference:
Regulatory Guide 1.109, Table E-7.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 8.
NOTE: The tritium dose factor total body dose factor.
for bone is assumed to be equal to the 2024o
Table 7.7 (4 of 8)
INHALATIONDOSE FACTORS (mrem/pCi inhaled)
ODCM Revision 0
Page 179 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 5.38E-06 9.23E-06 6.10E-07 2.25E-06 2.51E-10 1.74E-06 8.87E-12 1.23E-08 1.97E-12 4.50E-08 7.80E-07 4.43E-06 1.99E-07 1.52E-06 1.11E-07 4.62E-07 6.28E-05 6.44E-06 8.38E-05 5.82E-08 1.67E-10 6.84E-06 1.78E-11 4.62E-12 5.99E-08 1.20E-10 3.55E-06 3.32E-08 6.11E-04 1.67E-06 5.37E-12 9.83E-07 1.50E-09 4.23E-08 liver 9.92E-08 1.01E-07 2.80E-07 1.02E-06 1.14E-10 8.23E-07 4.22E-12 7.51E-09 1.04E-12 3.63E-08 2.24E-06 6.14E-06 5.47E-07 2.56E-06 2.90E-07 1.18E-06 1.41E-04 2.42E-05 1.06E-04 1.07E-07 1.18E-13 8.38E-09 1.32E-14 4.63E-15 2.95E-08 5.31E-11 2.37E-06 2.42E-08 2.53E-04 6.64E-07 2.20E-12 1.07E-06 1.22E-09 3.99E-09 t body 2.10E-06 2.15E-06 8.34E-08 2.73E-07 5.52E-11 2.81E-07 2.20E-12 5.03E-09 6.30E-13 2.74E-08 8.96E-07 3.30E-06 1.97E-07 7.78E-07 1.05E-07 4.36E-07 6.86E-05 1.71E-05 3.89E-05 5.58E-08 4.87E-12 4.40E-07 5.93E-13 2.84E-13 7.82E-09 1.32E-11 2.71E-07 2.70E-09 3.28E-05 8.28E-08 2.72E-13 6.41E-08 4.29E-10 2.21E-09 TEEN thyroid 1.22E-08 8.80E 1.75E-07 5.48E-07 1.77E-10 5.72E-07 6.48E-12 9.06E-09 1.55E-12 3.07E-08 1.86E-04 1.83E-03 1.89E-05 3.65E-04 4.94E-06 7.76E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 8.17E-06 9.10E-10 6.49E-06 3.32E-ll 5.49E-08 7.'t2E-12 2.44E-07 3.44E-06 1.05E-05 8.65E-07 4.49E-06 4.58E-07 1.86E-06 4.69E-05 1.38E-05 3.80E-05 8.28E-08 1.11E-13 2.85E-09 1.23E-14 3.92E-15 0.00E+00 O.OOE+00 1.11E-06 1.08E-08 1.51E-04 3.86E-07 1.26E-12 6.28E-07 O.OOE+00 1.25E-08 lung 4.81E-04 3.42E-04 6 '0E-05 2.07E-04 1.40E-06 2.47E-04 4.12E-07 2.97E-05 2.92E-07 5.61E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.83E-05 2.22E-06 1.51E-05 9.84E-09 8.08E-07 2.54E-04 4.11E-07 2.39E-07 2.68E-05 1.27E-06 7.67E-05 1.63E-05 1.67E-03 6.04E-05 2.19E-07 4.65E-05 5.92E-06 8.11E-06 gi-lli 4.98E-05 1.24E-05 9.38E-06 1.99E-05 1.01E-05 5.06E-05 2.02E-07 7.76E-05 1.89E-09 5.79E-05 1.14E-06 8.11E-07 1.59E-07 1.29E-06 2.55E-09 8.69E-07 1.22E-06 1.36E-06 1.06E-06 3.38E-11 8.06E-07 2.86E-05 9.33E-14 5.99E-20 6.09E-05 1.50E-06 1.58E-05 3.19E-05 1.08E-04 2.67E-05
- 2. 94E-14
- 2. 28E-05 2.21E-05 1.65E-05
Reference:
Regulatory Guide 1.109, Table E-8.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.
NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the 2024o
0
Table 7.7 (6 of 8)
INHALATIONDOSE FACTORS (mrem/pCi inhaled)
ODCM Revision 0
Page 181 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I>>134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.55E-05 2.66E-05 1.82E-06 6.72E-06 7.49E-10 5.19E-06 2.64E-11 3.63E-08 5.87E-12 1.30E-07 2.21E-06 1.30E-05 5.72E-07 4.48E-06 3.17E-07 1.33E-06 1.76E-04 1.76E-05 2.45E-04 1.71E-07 4.98E-10 2.00E-05 5.29E-11 1.35E-11 1.74E-07 3.50E-10 1.06E-05 9.89E-OS 1.83E-03 4.99E-06 1.61E-11 2.92E-06 4.41E-09 1 ~ 26E-07 liver 2.00E-07 2.05E-07 6.29E-07 2.31E-06 2.57E-10 1.85E-06 9.45E-12 1.60E-OS 2.28E-12 7.36E-OS 4.43E-06 1.30E-05 1.10E-06 5.49E-06 5.84E-07 2.36E-06 2.74E-04 4.62E-05 2.23E-04 2.27E-07 2.66E-13 1.75E-OS 2.95E-14 9.73E-15 6.08E-08 1.11E-10 5.28E-06 5.37E-OS 5.72E-04 1.50E-06 4.99E-12 2.36E-06 2.61E-09 9.04E-09 t body 5.41E-06 5.59E-06 2.47E-07 8.16E-07 1.65E-10 8.22E-07 6.44E-12 1.37E-OS 1.78E-12 7.12E-OS 2.28E-06 7.37E-06 5.07E-07 2.08E-06 2.69E-07 1.12E-06 6.07E-05 3.14E-05 3.47E-05 1.50E-07 1.45E-11 1.17E-06 1.72E-12 7.54E-13 2.04E-OS 3.49E-11 7.83E-07 7.77E-09 9.77E-05 2.47E-07 8.10E-13 1.84E-07 1.17E-09 6.35E-09 CHILD thyroid 3.41E-OS 2.46E-OS 5.20E-07 1.64E-06 5.30E-10 1.71E-06 1.93E-ll 2.64E-08 4.59E-12 8.58E-OS 4.99E-04 4.39E-03 5.23E-05 1.04E-03 1.37E-05 2.14E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 1.72E-05 1.91E-09 1.36E-05 6.94E-ll 1.08E-07 1.59E-ll 4.79E-07 6.61E-06 2.13E-05 1.69E-06 9.13E-06 8.92E-07 3.62E-06 8.93E-05 2.58E-05 7.63E-, 05 1.68E-07 2.33E-13 5.71E-09 2.56E-14 7.87E-15 O.OOE+00 O.OOE+00 2.31E-06 2.26E-OS 3.17E-04 8.11E-07 2.64E-12 1.30E-06 O.OOE+00 2.63E-OS lung 8.76E-04 6.27E-04 1.29E-04 4.00E-04 2.71E-06 4.76E-04 7.93E-07 5.56E-05 5.55E-07 1.02E-04 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.27E-05 3.93E-06 2.81E-05 1.84E-08 1.56E-06 4.71E-04 7.89E-07 4.44E-07 4.94E-05 2.35E-06 1.47E-04 3.12E-05 3.23E-03 1.17E-04 4.23E-07 8.87E-05 1.11E-05 1.57E-05 gi-lli 4.43E-05 1.09E-05 9.13E-06 1.93E-05 1.52E-05 4.91E-05 6.89E-06 8.32E-05 3.60E-07 3.72E-05 1.38E-06 7.68E-07 8.65E-07 1.48E-06 2.58E-07 1.20E-06 1.04E-06 1.13E-06 9.78E-07 7.29E-OS 1.56E-05 2.75E-05 7.44E-08 7.41E-10 6.10E-05 2.05E-05 1.53E-05 3.44E-05 1.05E-04 2.63E-05 5.32E-OS 2.22E-05 2.46E-05 1.73E-05
Reference:
Regulatory Guide 1.109, Table E-9.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November
- 1977, Table 6.
NOTE: The tritium dose factor total body dose factor.
for bone is assumed to be equal to the 2024o
Table 7.7 (8 of 8)
INHALATIONDOSE FACTORS (mrem/pCi inhaled)
ODCM Revision 0
Page 183 of 208 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 2.71E-05 3.69E-05 3.40E-06 1.19E-05 1.59E-09 1.01E-05 5.63E-11 7.62E-08 1.24E-ll 2.66E-07 4.54E-06 2.71E-05 1.21E-06 9.46E-06 6.58E-07 2.76E-06 2.83E-04 3.45E-05 3.92E-04 3.61E-07 1.06E-09 4.00E-05 1.12E-10 2.84E-ll 3.61E-07 7.36E-10 1.98E-05 2.09E-07 2.28E-03 1.00E-05 3.42E-ll 5.67E-06 9.26E-09 2.65E-07 liver 3.97E-07 3.41E-07 1.42E-06 4.93E-06 6.81E-10 4.35E-06 2.48E-11 3.93E-08 5.87E-12 1.69E-07 9.91E-06 3.17E-05 2.53E-06 1.37E-05 1.34E-06 5.43E-06 5.02E-04 9.61E-05 4.37E-04 5.58E-07 7.03E-13 4.00E-08 7.70E-14 2.36E-14 1.43E-07 2.69E-10 1.19E-05 1.38E-07 8.65E-04 3.74E-06 1.32E-ll 5.81E-06 6.44E-09 2.37E-08 t body 8.56E>>06 7.78E-06 4.70E-07 1.48E-06 3.49E-10 1.59E-06 1.34E-11 2.59E-08 3.57E-12 1.26E-07 3.98E-06 1.40E-05 8.99E-07 4.00E>>06 4.75E-07 1.98E-06 5.32E-05 3.78E-05 3.25E-05 2.84E-07 3.07E-11 2.07E-06 3.55E-12 1.40E-12 3.68E-08 6.46E-11 1.42E-06 1.58E-08 1.26E-04 4.99E-07 1.72E-12 3.57E-07 2.23E-09 1.34E-08 INFANT thyroid 7.18E-08 4.45E-08 1.16E-06 3.48E-06 1.32E-09 3.91E-06 4.82E-11 6.38E-08 1.13E-ll 1.99E-07 1.14E-03 1.06E-02 1.21E-04 2.54E-03 3.18E-05 4.97E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 0.00E+00 2.68E-05 3.47E-09 2.27E-05 1.25E-10 1.89E-07 2.85E-11 7.39E-07 1.09E-05 3.70E-05 2.82E-06 1.60E-05 1.49E-06 6.05E-06 1.36E-04 4.03E-05 1.23E-04 2.93E-07 4.23E-13 9.59E-09 4.64E-14 1.36E-14 O.OOE+00 O.OOE+00 3.75E-06 4.03E-08 3.84E-04 1.41E-06 4.80E-12 2.25E-06 O.OOE+00 4.73E-08 lung 1.89E-03 1.17E-03 3.19E-04 9.37E-04 7.39E-06 1.20E-03 2.14E-06 1.42E-04 1.47E-06 2.43E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 5.69E-05 8.40E-06 5.09E-05 4.67E-08 4.25E-06 1.14E-03 2.12E-06 1.11E-06 1.20E-04 5.87E-06 3.69E-04 8.30E-05 7.03E-03 3.09E-04 1.15E-06 2.30E-04 2.83E-05 4.25E-05 gi-lli 4.22E-05 1.05E-05 9.22E-06 1.95E-05 1.74E-05 4.93E-05 1.88E-05 8.51E-05 5.87E-06 3.15E-05 1.42E-06 7.56E-07 1.36E-06 1.54E-06 9.21E-07 1.31E-06 9.53E-07 1.02E-06 9.53E-07 6.26E-07 3.64E-05 2.74E-05 3.39E-06 4.95E-07 6.06E-05 4.25E-05 1.54E-05 3.55E-05 1.06E-04 2.66E-05 3.06E-06 2.23E-05 2.54E-05 1.78E-05
Reference:
Regulatory Guide 1.109, Table E-10.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.
NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the 2024o
Figure 7.2 NORMAL BUILDING VENTILATION ODCM Revision 0
Page 185 of 208 ROOF FANS
~
~
~
~I
~
e r
~
~
~
+i ~ te Turbine RM 90-249
~
~
~
i r
~
~
~
~ z Deck RM 90-261
- Refuel, Floor RM 90-262 Flem PAnay Oertebmem Puye Oyelem Turbine Building 9 yplcal for each unit)
- Used seasonally to control temperature Control Bay Reactor Building (typical for each vnlt)
Te OCTO (emeepeney eemieeeq) 2024o
Figure 7.3 PLUME DEPLETION EFFECT (Page 2 of 4)
ODCM Reviaion 0 Page 187 of 208 1.0 kEIITRAL ST
'E ICT
)'u OP K
~
0.T Q
g 0.0
> 0S Z0 g
OA 03 STALL
)AIIP) 02 0.1 1Al 10AI tlUMETRAvELDlsTAkcE IKILOMETERs) ~
'f00.0'%00>.
Flume Dtptetfon Effect for 30m Relesses, )Letters denote Pesrtulll Stab)0ty Chss).
2024o
Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4)
ODCM Revision 0
Page 189 of 208 NEUTRAl. (D) tu 0$
0.2 Ig O.e 3 os ZO g o.i OD STABLE (E,F,O)
NO DEPL ION INO (FRACTION REMAIN UN (A
STABLE PS) 0.2 0.1 0.1 1AI 10AI FLUMETRAYELDlsTANcE (KILDMETERs)
Flun>> Depletion'EIIeet Ioe 100en Releeeet (Lettete denote AequlllSteblllty Cteet) 100.0 200AI 2024o
Figure 7.5 RELATIVE DEPOSITION (Page 1 of 4)
ODCM Revision 0
Page 191 of 208 10-4 LLJI-sU UJ cr, o
1W I
0 O
O LLII-
LU tt:
10-6 10 7 0.1 1.0 10.0
'100.0 200.0 PLUME TRAVELDISTANCE (KILOMETERS)
Relative Deposition for Ground-Level Reieases (AilAtmospheric Stability Classes) 2024o
Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4)
ODCM Revision 0 Page 193 of 208 UNSTABLE (A,B 10 B NEUTRAL(D)
UJI-UJ tUI-CC 0 1W rIJ0 UJO
, UJ NEUTRAL UNSTABLE STABL (E,F,G) 10-8 0.1 1.0 10.0>
PLUME TRAVELDISTANCE (KILOMETERS) 100.0 200.0 Relative Deposition for 60m Releases (Letters denote Pasquill Stability Class) 2024o
ODCM Revision 0
Page 195 of 208 SECTION 8.0 TOTAL DOSE 2024o
ODCM Revision 0
Page 197 of 208 SECTION 9.0 ENVIRONMENTAL MONITORING PROGRAM 2024o
Table 9.1 (1 of 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ODCM Revision 0
Page 199 of 208 Exposure Pathway and/or Sam le Number of Samples and Sample Locations Sampling and Collection Fre uenc Type and Frequency of Anal sis AIRBORNE Particulates 6 samples from locations (in different sectors) at or near the site boundary (LM<<l, LM-2, LM-3, LM-4, LM-6, and LM-7)
Continuous sampler operation with sam-ple collection as required by dust loading but at least once per 7 days.
2 samples from control locations greater than 10 miles from the plant (RM-1 and RM-6) 3 samples from locations in communities approx-imately 10 miles from the plant (PM-l, PM-2 and PM-3)
Particulate sampler.
Analyze for gross beta radioactivity
>24 hrs following filter change.
Perform gamma isotopic analysis on each sample when gross beta activity is
>10 times the average of control samples.
Perform gamma isotopic analysis on composite (by location) sample at least once per 31 days.
Radioiodine Same locations as air particulates Continuous sampler operation with charcoal canister collection at least once per 7 days I-131 every 7 days SOIL Samples from same locations as air particulates Once every year Gamma scan, Sr-89, Sr-90 once per year DIRECT 2 or more dosi-meters placed at locations (in dif-ferent sectors) at or near the site boundary in each of the 16 sectors At least once per 92 days Gamma dose once per 92 days 2024o
Table 9.1 (3 of 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ODCM Revision 0
Page 201 of 208 Exposure Pathway and/or Sam le Number of Samples and Sample Locations Sampling and Collection Fre uenc Type and Frequency of Anal sis Drinking (continued) 2 additional sam-ples of potable surface water downstream from the plant (TRM 274.9 and TRM 259.5) 1 sample at a control location (TRM 306)
Grab sample taken at least once per 31 days.
Gross beta and gamma scan at least once per 31 days.
Composite for Sr-89 and Sr-90 and tritium at least once per 92 days 1 additional sample at a con-trol location (TRM 305)
Collected by auto-matic sequential-type sampler with composite sample taken at least once per 31 daysa GROUND 1 sample adjacent to the plant (well N6)
Collected by auto-matic sequential-type sampler with composite sample taken at least once per 31 days.
Composite for gamma
1 sample at a control location upgradient from the plant (Farm Bn)
Grab sample taken at least once per 31 days.
Composite for gamma
AQUATIC Sediment 2 samples upstream from discharge point (TRM 297.0 and TRM 307.52)
At least once per Gamma scan, Sr-89, 184 days and Sr-90 analyses Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c The surface water control sample shall be considered a control for the drinking water sample.
2024o
Table 9.1 (5 of 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ODCM Revision 0
Page 203 of 208 Exposure Pathway and/or
~Sam le Number of Samples and Sample Sampling and Locations Collection Fre uenc Type and Frequency of Anal sis Clams 1 sample down-At least once per stream from the 184 days.
discharge Gamma scan on flesh only 1 sample upstream from the plant.
(No permanent stations established; depends on avail-ability of clams).
Fruits Vegetables Samples of food At least once per crops such as year at time of corn, green beans, harvest
- tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant Gamma scan on edible portion 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation (pasturage)
Samples from farms producing milk but not providing a milk sample (Farm T).
Once per 31 days I-131, gamma scan once per 31 days.
Sr-89 and Sr-90 analysis on the last monthly sample of each quarter.
Control sample from 1 control dairy farm (Farm Gl) 2024o
Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS ODCM Revision 0
Page 205 of 208 Map Location Number Station Sector Approximate Distance Miles)
Onsite (On)a or Offsite Off) 1 2
3 5
6 7
8 9
10 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 NW-3 NE-3 SSE-2 W-3 E-3 N-1 NNE-1 ENE-1 NNW-2 N-2 NNE-2 NNE-3 NE-1 NE-2 ENE-2 E-1 E-2 ESE-1 ESE-2 SE-1 SE-2 SSE-1 S-l S-2 SSW-2 SSW-2 SW-1
'W-2 SW-3 WSW-1 WSW-2 WSW-3 W-1 W-2 W-4 WNW-1 WNW-2 NW-1 NW-2
~
NNW-1 NNW-3 NW NE SSE W
E N
NNE ENE NNW N
NNE NNE NE NE ENE E
S SSW SSW SW SW SW WSW WSW WSW W
W W
WNW WNW NW NW NNW NNW 13.8 10.9 7.5 31.3 24.2 1.0 0.9 0.9 1.7 5.0 0.7 5.2 0.8 5.0 6.2 0.8 5.2 0.9 3.0 0.5 5,4 5.1 3.1 4.8 3.0 4.4 1.9 4,7 6.0 2.7 5.1 10.5 1.9 4,7
- 32. 1 3.3 4.4 2.2 5.3 1.0 5.2 Off Off Off Off Off On On On On Off On Off On Off Off On Off On Off On Off Off Off Off Off Off On Off Off Off Off Off On Off Off Off Off Off Off On Off aTLDs designated onsite are those located two miles or less from the plant.
TLDs designated offsite are those located more than two miles from the plant.
2024o
Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ODCM Revision 0
Page 207 of 208 225.25
$45,Td H
3 I't3 11.25
~ > I HHE SS.TS 502.75 42 55.25 WHW Q ~T 85 25 IA 36,84 C~
8
~ 10 TS.Td 81 40 SROWHS FERI1T 25S.T WSW 0
65 P
~
<+4,3T
<eCs.
s 4
~101.2S SSK sse25 61 123.TS SW 68 2 IS.T5
~ 54
'I5 5.25 SE SSW I~ 1.25 ISS.T5 SSK SCALE o
os MLS5 2024o
PCP Manual Revision 0
Page 1 of 19 PROCESS CONTROL PROGRAM MANUAL (PCP) 2023o
PCP Manual Revision 0
Page 3 of 19
1.0 INTRODUCTION
1.1
~Sco e
This Process Control Program (PCP) is applicable to radioactive waste solidification and dewatering of wet solid radioactive wastes generated as a result of the operation and maintenance of Browns Ferry Nuclear Plant.
This PCP is not applicable to the treatment of mixed wastes.
1.2
~Pur ose The PCP provides those controls necessary to ensure that disposal criteria are met by BFN processing techniques, or by vendor supplied systems, if used for dewatering or solidification.
2.0 DEFINITIONS 2.1 Absorb To take liquid in through pores, or as if through pores or interstices of a material.
2.2 Absorbent Media or material used to absorb liquid.
2.3 Batch An isolated quantity of waste to be processed having constant physical and chemical characteristics.
2.4 Container The primary receptacle in which processed wastes (dewatered, solidified or absorbed) are packaged for disposal.
2.5 Dewatered - Wet solid wastes which have had excess water removed.
2.6 Free Liquid Uncombined liquid not bound by the solid matrix of the solid waste mass; capable of flowing.
2.7 Homogeneous Of uniform composition; the waste is uniformly distributed throughout the container.
2.8 Liquid waste For the purposes of this
- PCP, any aqueous or non-aqueous radioactive liquid which requires solidification or absorption before disposal.
This may include oils, chemicals, water or other liquids unsuitable for in-plant clean-up or treatment.
2023o
3.8 Vendor To ical Re orts PCP Manual Revision 0
Page 5 of 19 3.8.1 Chem Nuclear Systems, Inc. (CNSI), DM-11118-01-P-A 3.8.2 CNSI, RDS-25506-01-P 3.8.3 Nuclear Packaging, Inc., TP-02-NP-A 3.9 Letter from U.S.
NRC to S.A. White dated 5/6/83 (Docket Nos.
50-259/260/296) 3.10 Letter from R. L. Gridley to NRC dated 2/11/87 (L44870211808) 3.11 Letter from R. L. Gridley to NRC dated 10/16/87
{L44871016807) 4.0 WASTE CHARACTERISTICS 4.1 Waste Streams Three general waste streams applicable to this PCP'ave been identified for Browns Ferry.
These are the Condensate Waste Phase Separator (CMPS), Reactor Water Cleanup Phase Separator (RWCU), and Dry Active waste (DAW).
Other waste streams may be established based upon plant operational needs.
CWPS is fed by several waste sub-streams, including the Equipment Drain, Chemical Waste, Floor Drain, Fuel Pool Cooling, and Condensate systems.
RWCU is fed by Reactor Mater Cleanup only.
DAW is used for wastes generated within the regulated areas of the reactor buildings and turbine buildings which cannot be appropriately attributed to either RWCU or CMPS.
DAW normally includes paper, plastic, wood, metal and other such material generated as a result of the operation and maintenance of the plant.
4.2 Waste Form Wet solid radioactive wastes consist of bead resins, filter aids (such as activated charcoals or carbons),
powdered resins, and slurries or sludges.
Wastes which may require solidification may include, but are not limited to, liquids which cannot be processed using installed plant systems, oils, chemicals, aqueous filter media, and decontamination wastes.
Wastes are processed as appropriate to ensure that the minimum physical characteristics required by 10 CFR and disposal site criteria are met.
All Class B and Class C waste is stabilized.
On
- occasion, Class A waste
{such as aqueous filter media with a concentration 1 pCi/cc of isotopes with half-lives 5 years) 2023o
PCP Manual Revision 0
Page 7 of 19 5.2 Manifest Trackin Acknowledgment of receipt for each shipment to a disposal site is sent to BFN Radwaste Group by the disposal site.
Shipments for which acknowledgment is not received. within the time limits allowed in 10 CFR 20.311 are traced by Corporate Radcon/Radwaste.
6.0 ADMINISTRATIVE CONTROLS 6.1 Procedures and Surveillance Detailed procedures are written and maintained by BFN which cover plant process
- systems, waste packaging, and shipment requirements.
Surveillance Instructions are used to ver'ify that plant Technical Specifications for waste processing are met.
Programmatic guidance is provided through Corporate Radcon/Radwaste.
Corporate Radcon/Radwaste maintains the Radioactive Material Shipment Manual and the Package Quality Assurance Program (for packages licensed under 10 CFR 71).
6.2 ualit Assurance/ ualit Control Quality assurance audits are conducted by the BFN site Quality Assurance organization, and by Nuclear Quality Assurance (NQA),.
Audit findings are reviewed by BFN management, ensuring prompt corrective actions when needed.
Quality control measures include quarterly tests of the resin dewatering system performed by BFN personnel upon actual dewatered High Integrity Containers (HICs) or liners, site review of all radwaste vendor procedures before use, and second party verification by BFN personnel of end points or acceptance criteria in vendor procedures.
Quality control of solidification methods is
,performed through controlled testing of a minimum of three samples from each batch to be solidified.
Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria.
6.3
~Tra in in Personnel involved in processing radioactive waste for shipment are trained in site procedures, regulatory requirements, and disposal site criteria.
Training and retraining sessions are held when needed to support operations.
Retraining is required on an annual basis to maintain qualification.
Personnel found not complying with procedures may have their qualifications revoked by the Radwaste Group Supervisor, if deemed necessary.
Qualifications may be reestablished through completion of retraining, and approval of the Radwaste Group Supervisor.
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ATTACHMENT 1 PCP Manual Revision 0
Page 9 of 19 Dewatering is conducted at BFN using plant equipment and plant personnel.
Chem-Nuclear
- Systems, Inc.,
(CNSI) high-integrity containers and the CNSI dewatering procedures are used.
l.
EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT NO. DW-11118-Ol-P-A DATED DECEMBER 1983.
BFN dewaters powdered resin, filter media, and mixtures of powdered resin with small quantities of bead resin (normally less than 10 percent bead resin) using a plant specific version of Chem-Nuclear Procedure FO-OP-022, "Ecodex Precoat/Powdex/Solka-Floe/Diatomaceous Earth Dewatering Procedure for CNSI 14-195 or Small Liners."
The dewatering system was fabricated by TVA to meet the equipment specifications in FO-OP-022.
The TVA dewatering system differs from the Chem-Nuclear system in that:
(a)
TVA's system has no off-gas collector.
The high integrity containers are open to the waste packaging room air during filling and dewatering.
Air from this room is normally discharged through the Radwaste Building ventilation system.
This air then flows through a HEPA filter and is released through a monitored release point on the Reactor Building roof.
(b)
The valves on the pump suction manifold are manually operated.
The system is not operated remotely.
However, the high integrity containers are enclosed behind a shielded wall or inside a shielded cask during filling and dewatering to keep radiation levels in the vicinity of the system near background.
(c)
There are no vacuum gauges at each inlet connection.
A single vacuum gauge is provided at the flush inlet connection to the manifold.
This vacuum gauge will indicate a break in vacuum in any active (not isolated) filter set.
Loss of vacuum normally occurs in sequence from the top to the bottom set of filters.
When vacuum breaks at a given filter level, that level is isolated.
Therefore, vacuum is monitored continually for all active filter sets.
(d)
There is no automatic level control or level indicating instrument in the TVA dewatering system.
Level is determined by visual observations.
TVA has conducted tests which conclude that mixtures of bead and powdered resin, in proportions of up to 50-percent
- bead, can be adequately dewatered using a modified procedure for dewatering powdered resin.
These tests were conducted using TVA-fabricated steel liners with dewatering internals similar to those found in the Chem-Nuclear high-integrity containers and a dewatering pump which is inferior to that 2023o
P ual Rev ion 0 Page 12 of 19 ATTACHMENT 1 (Continued)
FIGURE 1
Waste Packaging Room Layout For Chem Nuclear System Radwaste Bldg.
565'04 ft. 3 in.
Crane Operator Platform 29 ft. 3 in.
r Shielding 5
F~.
io'5" -I CHEM-NUCLEAR SYSTEM TRUCK 18 ft.
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ATTACHMENT 2 PCP Manual Revision 0
Page 13,of 19 Dewatering is conducted at BFN using Chem-Nuclear
- System, Inc (CNSI) supplied portable air driven pumps.
Dewatering will be performed on CNSI 24 inch diameter pressure vessels.
1.
EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT None.
Plant specific versions of CNSI Procedure FO-OP-025 and vendor supplied equipment will be used to dewater vessels.
2.
INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a)
The dewatering pump discharges, through a flexible to a plant floor drain.
This water will be processed through Radwaste.
(b)
Compressed air is supplied from the plant air system through a flexible hose with Chicago connections to the air driven pump.
(c)
The dewatering system will be located in a permanent plant building.
Any leaks or spills will be contained inside this building and collected in floor drains.
Failure of any of the components will not provide a pathway for radioactive releases to the environment or to a portable water supply.
3.
LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT The dewatering will be performed in a permanent plant building.
The dewatering pump will be located in the immediate vicinity of the pressure vessels and as close as possible to a floor drain.
4.
WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement.
Samples or smears, as appropriate, of standard waste streams are sent off site for analysis.
An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured.
Scaling factors are developed on a waste stream specific basis.
Scaling factors are periodically reconfirmed through sampling and analysis.
A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.
5.
DESCRIPTION OF WASTE CONTAINER The waste containers are the CNSI 24 inch diameter carbon steel and fiberglass re-inforced plastic pressure vessels.
6.
CAPABILITY TO MEET 10 CFR 50 Appendix I This dewatering process does not cause any direct releases to the environment (see note 2C above).
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ATTACHMENT 3 (Continued)
PCP Manual Revision 0
Page 15 of 19 C.
Radwaste building service water (demineralized) will be provided to the PCS at approximately 25 gpm at 80 psig
(+20 psig) through a flexible hose.
Both connection points.(plant and PCS) are equipped with quick-disconnect fittings.
D.
The dewatering pump discharge is provided by a 1.5 inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank.
The connection to the drain header is made by a 1-inch Kamlock quick-disconnect fitting.
The dewatering pump connection is a 1.5 inch Kamlock quick-disconnect fitting.
A 1 to 1.5-inch Kamlock adaptor will be used at the drain header.
E.
The connection to the plant waste media line will be made either by a 1.5-inch 150 ANSI flat faced flange connection or by a flange connection to Kamlock quick-disconnect adaptor utilizing existing flexible hose.
A waste isolation valve will be installed downstream of this connection, providing local control by the CNSI operator over the flow of waste to the liners being filled.
The waste isolation is controlled remotely, and is interlocked to close on high waste level, high-high level, decreasing air pressure, or loss of electrical power.
3.
LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1
The RDS-1000 system will be located inside the radwaste packaging
- room, elevation 565 Any leaks or spills will be contained inside this room by exterior doors, which are closed during liner filling and dewatering operations.
Any spillage will be collected in the radwaste floor drains.
Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or potable water supply.
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ATTACHMENT 3 (Continued)
FiGURE 2 P(.
nua1 Revision 0
Page 17 of 19 Waste Packaging Room Layout For Chem Nuclear System Radwaste Bldg.
565'04 ft. 3 in.
Crane Operator Hatform 29 ft. 3 in.
CHEM-NUCLEAR SYSTEM TRUCK 18 ft.
Shielding I>o'5" -I
ATTACHMENT 4 (Continued)
PCP Manual Revision 0
Page 19 of 19 4.
WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement.
Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis.
An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured.
Scaling factors are developed on a waste stream specific basis.
Scaling factors are periodically reconfirmed through sampling and analysis.
Computerized calculation of individual container isotopic contents is performed.
Maintenance,
- testing, and independent verification of this program ascertain correct data manipulation.
TVA gA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.
Procedural controls, corporate assessments of the Radwaste
- program, periodic QC audits of the program, and management evaluation of audit finding ensure qualify in the plant program.
5., DESCRIPTION OF WASTE CONTAINERS High-integrity containers manufactured by Pacific Nuclear Systems, inc.
are used for packaging resin.
6.
CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment.
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