Text

Rev 0 to Odcm.
	ML18036A591
Person / Time
Site:	Browns Ferry
Issue date:	03/25/1992
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML18036A571	List: ML18036A569; ML18036A573; ML18036A591;
References
	PROC-920325, NUDOCS 9203310130
	Download: ML18036A591 (182)
	v • d • e

ODCM Revision 0 Page 1 of 208 OFFSITE DOSE CALCULATION MANUAL (ODCM')

2024o 9203310130 920325 PDR ADQCK 05000259 PDR

ODCM Revision 0 Page 3 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS

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Section page B ASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 51 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 52 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ~ ~ ~ ~ ~ 52 1/2.2 RADIOACTIVE EFFLUENTS ......................................... 52 1/2.2.1.1 CONCENTRATION ............................................. 52 1 /2.2.1.2 DOSE ..............o....................................... 53 1/2.2.1.3 LIQUID WASTE TREATMENT .................................... 53 1 /2.2.2.1 DOSE RATE ................................................. 54 1/2.2.2.2 DOSE NOBLE GASES .................................. ..... ~ 55 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 56 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ................................ 57 1 /2.2.3 TOTAL DOSE .................................................. 57 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 .............................................. 61 2024o

ODCM Revision 0 Page 5 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section page 6 .3.1.2 ~FFishh Ingestion

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I .........................;..'.................. 77 6..3.1.3 Recreation .................................................. 78 6.3.1.4 Monthly Summary .....................;....................... 79 6' LIQUID RADWASTE TREATMENT SYSTEM ~ ~ ~ ~ ~ . ~ .. .................. 80 6.5 DOSE PROJECTIONS -............................................... 81 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES ........................ 82 6..6.1 Water Ingestion ............................................... 82 6..

.6.2 Fish

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I F h 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 ............................. ~ ...... 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 .......................................... 116 2024o

ODCM Revision 0 Page 7 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)

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 ........................... ..............

~ 145 7.9.1 Annual Average Air Concentration .............................. 146 7.9.2 Relative Concentration ........................................ 147 7..9.3 Relative ~Dispersion ...........................................

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147 7.9.4 Effective Release Height ...................................... 148 2024o

ODCM Revision 0 Page 9 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)

LIST OF TABLES 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 P ROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 42 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETFCTION (LLD)

FOR ENVIRONMENTAL SAMPLES ............................... 45 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS 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 UN IT AT BFN ............................................... 150 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND D IRECTION .1....0.......-.................................. 151 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ................ 173 2024o

ODCM Revision 0 Page 11 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS

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LIST OF FIGURES page Figure 3.1 LAND SITE BOUNDARY ... ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ... ~ ...................... 64 Figure 6.1 LIQUID RELEASE POINTS .... .. ~ ~ ~ ~ .... .....................

~ 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 ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ .. ~ ~ ~ ~ . ~ .. ~ ~ ~ 208 2024o

ODCM Revision 0 Page 13 of 208 INTRODUCTION 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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ODCM Revision 0 Page 15 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 Page 17 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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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4 ODCM Revision 0 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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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ODCM Revision 0 Page 23 of 208 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

Instrument Action

1. Stack (RM-90-147A & B)

a. Noble Gas Monitor A/C

b. Iodine Cartridge B/C

c. Particulate Filter B/C

d. Sampler Flow Abnormal D

e. Stack Flow (FT, FM, FI-90-271) D

2. Reactor/Turbine Building Ventilation (RM-90-250)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

d. Sampler Flowmeter D

3. Turbine Building Exhaust (RM-90-249% 251)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

4. Radwaste Building Vent (RM-90-252)

a. Noble Gas Monitor 1 A/C

b. Iodine Sampler 1 B/C

c. Particulate Sampler 1 B/C

e. Sampler Flowmeter 1 D

5. Offgas Post Treatment

a. Noble Gas Activity Monitor (RM-90-265, -266)

b. Sample Flow Abnormal (PA-90-262) 2024o

ODCM Revision 0 Page 25 of 208 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Ins trument CHECK CHECK CALIBRATION TEST

1. STACK

a. Noble Gas Monitor4 M Rl Q2

b. Iodine Cartridge N/A N/A N/A

c. Particulate Filter N/A'/A N/A N/A

d. Sampler Flow Abnormal R Q

e. Stack Flowmeter N/A R

2. REACTOR/TURBINE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

3. TURBINE BUILDING EXHAUST

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

4. RADWASTE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

5. OFF GAS POST TREATMENT4

a. Noble Gas Activity D Rl Monitor

b. Sample Flow Abnormal D N/A Q2 2024o

ODCM Revision 0 Page 27 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 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):

4.66sb LLD =

E V 2.22E+06 Y exp (-Mt)

Where:

LLD = the "a priori" lower limit of detection as defined above (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, X 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

ODCM Revision 0 Page 31 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 Page 33 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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 Specification 6.8.4.l.g, the dose rate at any time to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to radioactivity released in gaseous effluents from the site shall be limited to the 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):

4.66sb LLD E V 2.22E+06 Y exp (-X ht)

Where:

LLD = 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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ODCM Revision 0 Page 37 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 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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ODCM Revision 0 Page 39 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 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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ODCM Revision 0 Page 41 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 Page 43 of 208 Table 2.3-1 (2 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Number of Samples Pathway and/or le and Sample Locationsa Sampling and .

Collection Fre uenc

'ype and of Anal sis Frequency

~Sam

3. WATERBORNE

a. Surface 2 locations Composite sample Gamma isotopic collected over a analysis of each period of < 31 composite sample.

days.b Tritium analysis of composite sample at least once per 92 days.

b.Drinking Minimum of 1 Composite sample Gross beta and gamma downstream collected over a isotopic analysis of location, or all period of < 31 each composite sample.

water supplies days b>c Tritium analysis of within 10 miles composite sample at downstream which least once per 92 are taken from days.

the Tennessee River

c. Sediment Minimum of 1 At least once per Gamma isotopic location. 184 days analysis of each sample.

d.Groundd 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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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ODCM Revision 0 Page 45 of 208 Table 2.3-2 (1 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg, A~nal sis ~Ci/L) ~Ci/m3) wat) ~Ci'/L) wat) dr )

gross beta 4 0.01 N/A N/A N/A N/A H-3 2000 N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58, 60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 15 N/A N/A N/A N/A N/A I-131 lb 0.07 N/A 60 N/A Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 N/A N/A 60 N/A N/A La-140 15 N/A N/A N/A N/A 2024o

ODCM Revision 0 Page 47 of 208 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Milk Food Products

~Anal sis Water

~(Qi/L) n'I or gases

) ( 'IFish ~Ci/L) Ci/I'K wet)

H-3 2 x 104(a) N.A N.A N.A. N.A.

Mn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

s Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 10 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. 2 x 104 N.A. N.A.

Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

I-131 0.9 N.A. 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 N.A.

(a) For drinking water samples. This is 40 CFR Part 141 value.

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ODCM Revision 0 Page 49 of 208 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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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ODCM Revision 0 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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ODCM Revision 0 Page 53 of 208 BASES 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 flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive 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.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in 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

ODCM Revision 0 Page 55 of 208 BASES 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 flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. 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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ODCM Revision 0 Page 57 of 208 BASES 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

ODCM Revision 0 Page 59 of 208 SECTION 3.0 DEFINITIONS 2024o

ODCM Revision 0 Page 61 of 208 DEFINITIONS 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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ODCM Revision 0 Page 63 of 208 Table 3.1 FRE UENCY NOTATION Notation ~Fre uenc At least once per 12 hours.

At least once per 24 hours.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not Applicable Completed prior to each release 2024o

ODCM Revision 0 Page 65 of 208 SECTION 4.0 (NOT USED) 2024o

ODCM Revision 0 Page 67 of 208 5.0 ADMINISTRATIVE CONTROLS 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 and gaseous effluents and their subsequent dispersion in the river

'iquid and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.

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ODCM Revision 0 Page 69 of 208 SECTION 6.0 LI UID EFFLUENTS 2024o

ODCM Revision 0 Page 71 of 208 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC Sum of the Ratios 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).

Ci Mi MPCi where:

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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ODCM Revision 0 Page 73 of 208 6.2 INSTRUMENT SETPOINTS 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 = g i f where A maximum batch activity concentration, pCi/ml MPCi 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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ODCM Revision 0 Page 75 of 208 6.3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION 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 Fe-59 Sr-90 I-131 Na-24 Co-58 Zr/Nb-95 I-133 Cr-51 Co-60 Mo/Tc-99m Cs-134 Mn-54 Zn-65 Ag-110m Cs-136 Fe-55 Sr-89 Sb-124 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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ODCM Revision 0 Page 77 of 208 6.3.1.2 Fish In estion 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:

3.98E+03 Djk Ai Bi Ufa DFLijk i=1 2024o

ODCM Revision 0 Page 79 of 208 The recreation dose equation then becomes:

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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ODCM Revision 0 Page 81 of 208 6.5 DOSE PROJECTIONS 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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ODCM Revision 0 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 AFi t Qi D exp (-8. 64E+04 Xi td ) (6. 15) where 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 0.139 hours 8.267196e-4 weeks 1.9025e-4 months 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 ARi t Qi D exp (-8. 64E+04 Xi td ) (6. 16) where 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.

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ODCM Revision 0 Page 85 of 208 6.6.5 Po ulation Doses 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 (6.17) m=1 a=1 where:

POPWTRt = water ingestion population dose to organ t, man-rem.

POPa = 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 POPm = population at PWS m. The 3 PWSs and their populations are listed in Table 6.1.

ATMWa = 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 TWDOSamt = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10 3 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

ODCM Revision 0 Page 87 of 208 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiat Uwa 10 10 AWit where:

DFI = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Uw = water consumption rate for age group a, L/year, (Table 6.3).

10~ conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.2 Fish In estion Dose Factors DFLiat Ufa Bi 10 10 AFit where:

DFLi = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Ufa = fish consumption rate for age group a, kg/year, (Table 6.3).

Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).

106 conversion factor, pCi/pCi.

103 conversion factor, pl/L.

8760 = conversion factor, hours per year.

6.7.3 Shoreline Recreation Dose Factors DFG't Kc M W 103 106 U ARit = [1-exp(-X tb)]

where:

DFGit = dose conversion factor for standing on contaminated ground for i

nuclide and organ t (total body and skin), mrem/hr per pCi/m2, (Table 6.6).

Kc = transfer coefficient from water to shoreline sediment, L/kg-hr, (Table 6.3).

M = mass density of sediment, kg/m , (Table 6.3).

W = shoreline width factor, dimensionless, (Table 6.3).

103 conversion factor, ml/L.

106 conversion factor, pCi/pCi.

3600 = conversion factor, seconds/hour.

Xl decay constant for nuclide i, seconds , (Table 6.2).

tb = time shoreline is exposed to the concentration in the water, seconds, (Table 6.3).

U = usage factor, 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year.

8760 = conversion factor, hours/year.

2024o

ODCM Revision 0 Page 89of 208 Table 6.2 (1 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life X Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-.02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-'02'.50E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E<<03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-, 09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.78E+Ol 6.49E-04 1.30E-01. 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m '.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 '.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 2024o

ODCM Revision 0 Page 91 of 208 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat,) (beef)

Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A'/A N/A N/A Xe-135 5.47E+02 2.11E-05 N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+Ol 8.19E-04 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

ODCM Revision 0 Page 93 of 208 Table 6.3 (2 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference Uf(infant) 0 kg/year R. G. 1.109 (Table E-5)

Uf(child) 6.9 kg/year R. G. 1.109 (Table E-5)

Uf(teen) 16 kg/year R. G. 1.109 (Table E-5)

Uf(adult) 21 kg/year R. G. 1.109 (Table E-5)

UFL (infant) 0 kg/year R. G. 1.109 (Table E-5)

UFL (child) 26 kg/year R. G. 1.109 (Table E-5)

UFL (teen) 42 kg/year R. G. 1.109 (Table E-5)

UFL (adult) 64 kg/year R. G. 1.109 (Table E-5)

US (infant) 0 kg/year R. G. 1.109 (Table E-5)

US (child) 520 kg/year R. G. 1.109 (Table E-5)

US (teen) 630 kg/year R. G. 1.109 (Table E-5)

US (adult) 520 kg/year R. G. 1.109 (Table E-5)

U~(infant) 330 L/year R. G. 1.109 (Table E-5)

Uz(child) 510 L/year R. G. 1.109 (Table E-5)

U~(teen) 510 L/year R. G. 1.109 (Table E-5)

U(adult) 730 L/year R. G. 1.109 (Table E-5)

W 0.3 none R. G. 1.109 (Table A-2)

Yf 1.85 kg/m2 NUREG/CR-1004 (Table 3.4) 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Yp Ysf 0.64 kg/m2 NUREG/CR-1004 (Table 3.3)

Ysv 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

X~ (iodines) 7.71E-07 sec 1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

X (particulates) 5.21E-07 sec 1 NUREG/CR-1004 (Table 3.10)

(10.4 d half-life) 2024o

ODCM Revision 0 Page 95 of 208 Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT bone liver t body thyroid. kidney lung gi-lli Sb-124 2.80E-06 5.29E-OS 1.11E-06 .6.79E-09 O.OOE-OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-OS 4.26E-07 1.82E-09 O.OOE-OO 1.38E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-OS 2.38E-OS 8.15E-OS 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-OS 1.18E-OS 7.65E-09 2.41E-OS 1.32E-07 O.OOE+00 2.37E-OS Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1.97E-OS 8.23E-09 6.22E-09 1.62E-OS 8.63E-OS O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+00 7.71E-05 I-130 7.56E-07 2.23E-06 S.SOE-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-OS 1.09E-07 5.40E-OS O.OOE+00 8.01E-OS 7.91E-09 4.65E-13 Ba-139 9.70E-OS 6.91E-11 2.84E-09 O.OOE+00 6.46E-11 3.92E-ll 1.72E-07 Ba-140 2.03E-05 2.55E-OS 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-OS 3.56E-11 1.59E-09 O.OOE+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-OS 2.19E-11 1.34E-09 O.OOE+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+00 O.OOE+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 O.OOE+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+00 2.94E-09 O.OOE+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-OS O.OOE+00 1.21E-07 O.OOE+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 O.OOE+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 O.OOE+00 4.25E-09 O.OOE+00 3.49E-05 W-187 1.03E-07 8.61E-OS 3.01E-OS O.OOE+00 O.OOE+00 O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 O.OOE+00 3.65E-10 O.OOE+00 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 for bone is assumed to be equal to the total body dose factor.

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ODCM Revision 0 Page 97 of 208 Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid. kidney lung gi-lli Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 O.OOE-OO 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 O.OOE+00 2.18E-06 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 O.OOE+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 O.OOE+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 O.OOE+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1,22E-05 0.00E+00 9.39E-05 Te-131 2.79E-OS 1.15E-08 8.72E-09 2.15E-08 1.22E-07 O.OOE+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 O.OOE+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 O.OOE+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 O.OOE+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2.72E-06 .

Cs-137 1.12E-04 1.49E-04 5.19E-05 O.OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 O.OOE+00 1.10E-07 1.28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+00 9.22E-11 6.74E-ll 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 O.OOE+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6. 71E-08 5.01E-11 2.24E-09 O.OOE+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-ll 1.84E-09 O.OOE+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 O.OOE+00 O.OOE+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+00 O.OOE+00 O.OOE+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05

'e-143 2.35E-09 1.71E-06 1.91E-10 O.OOE+00 7.67E-10 O.OOE+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E!-08 O.OOE+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 O.OOE+00 5.99E-09 O.OOE+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 O.OOE+00 O.OOE+00 O.OOE+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 O.OOE+00 5.21E-10 O.OOE+00 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 for bone is assumed to be equal to the total body dose factor.

2024o

ODCM Revision 0 Page 99 of 208 Table 6.4 (6 of 8) 'I INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid . kidney lung gi-lli Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-OS O.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-OS 1.50E-06 6.63E-09" O.OOE+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-.06 O.OOE+00 O.OOE+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 O.OOE+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-07 3.74E-OS 3.18E-OS 9.56E-OS 3.92E-07 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 O.OOE+00 1.01E-04 Te-131 8.30E-OS 2.53E-OS 2.47E-OS 6.35E-OS 2.51E-07 O.OOE+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E>>06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-06 I-132 S.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 O.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+00 2.23E-07 2.40E-OS 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-OS O.OOE+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-OS 4.85E-06 O.OOE+00 2.37E-OS 4.34E-OS 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+00 9.69E-ll 6.58E-10 1.14E-07 Ba-142 8.74E-OS 6.29E-11 4.88E-09 O.OOE+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-OS 3.53E-09 1.19E-09 0;OOE+00 O.OOE+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-ll 0.00E+00 O.OOE+00 O.OOE+00 3.31E-05 Ce-141 3.97E-OS 1.98E-OS 2.94E-09 O.OOE+00 8.68E-09 O.OOE+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-,07 O.OOE+00 3.61E-07 O.OOE+00 1.70E-04 Pr-143 3.93E-OS 1.18E-OS 1.95E-09 O.OOE+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+00 2.11E-ll O.OOE+00 8.59E-OS Nd-147 2.79E-OS 2.26E-OS 1.75E-09 O.OOE+00 1.24E-OS O.OOE+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 O.OOE+00 O.OOE+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 O.OOE+00 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 for bone is assumed to be equal to the total body dose factor.

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ODCM Revision 0 Page 101 of 208 Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT bone liver t body thyroid . kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-OS'.84E.-06 O.OOE+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 O.OOE+00 O.OOE+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-OS 6.63E-OS 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-OS 1.57E-07 4.50E-07 O.OOE+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91E-06 Cs>>136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 O.OOE+00 3.90E-07 6.09E-OS 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-OS O.OOE+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 O.OOE+00 4.06E-OS 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-OS 8.32E-09 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.86E-05 Ce-141 7.87E-08 4.80E-OS 5.65E-09 O.OOE+00 1.48E-OS O.OOE+00 2.48E-05 Ce-143 1.48E-OS 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 O.OOEe00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E;07 O.OOE+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-OS 3.04E-OS 4.03E-09 O.OOE+00 1.13E-OS O.OOE+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-OS 5.68E-08 3.48E-09 O.OOE+00 2.19E-OS O.OOE+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.69E-05 Np-239 1.11E-OS 9.93E-10 5.61E-10 O.OOE+00 1.98E-09 O.OOE+00 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 for bone is assumed to be equal to the total body dose factor.

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ODCM Revision 0 Page 103 of 208 Table 6.6 (1 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 2024o

ODCM Revision 0 Page 105 of 208 Figuze 6.1 LI UID RELEASE POINTS BFH Uquld Eff1uan! Monltora 0'yptcat Unit and Common Rahvaata)

Cnndeneer Ceeana Wrier Intake Bay RHR aenrtre We1et RHR Rll $ 0.1 $ $

R11 $ 0.1$ e RaLverre (eenenenf Openrna rer Helper il (t) Turbine Butldlng Equlpmant (2) Reactor But(ding Equlpmant Te Ceeara (3) Condenaar Tewere 2024o

ODCM Revision 0 Page 107 of 208 SECTION 7.0 GASEOUS EFFLUENTS

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ODCM Revision 0 Page 109 of 208 7.1 RELEASE RATE LIMIT METHODOLOGY 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 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.

DFBi 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 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.

DFSi 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.

Dpi dose conversion factor for external gamma for noble gas nuclide i, mrad/year per pCi/m3 (Table 7.4).

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The dose rate limits of interest are.'DCM ill Revision Page 0

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:

Total Body Dose Rate Limit RTB(vent or stack) ven or s ac Skin Dose Rate Limit RS(vent or stack) = ven or s ac )

S Maximum Organ Dose Rate Limit RTH(vent or stack) 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 from building exhaust vents, Ci/s.

Qngs = Total noble gas release rate from main stack, Ci/s.

Qipv Total iodine and particulate release rate from building exhaust vents, Ci/s.

Qips Total iodine and particulate 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:

= RTBv Qngv~

ngv

= RSv Qngv

.whichever is more restrictive, i.e., smaller.

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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 rngs = 1.44E+01 Ci/s rips 3 ~ 57E 05 Ci/s Building Vents rngv 1 50E 01 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 + rngs 0.15 14.4 For iodines and particulates, ripv + rips < 1 2.19E-06 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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ODCM Revision 0 Page 119 of 208 7.4.1.2 Monthl Conservative Model Beta Air Dose (x/Q) 106 Dg = ,

Qi Dpi (7 3) 0.9 3.15E+07 where:

Dg = beta dose to air, mrad.

x/Q = 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).

0.9 = fraction of total beta dose expected to be contributed by the assumed nuclides.

106 pCi/Ci conversion factor.

3.15E+07 = s/yr conversion factor.

Qi = monthly release of radionuclide i, Ci.

DF8i = 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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ODCM Revision 0 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 where 0.9 (3.15E+07)

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.

D/Q = 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 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).

DFT = 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).

D/Q = 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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ODOM Revision 0 Page 125 of 208 7.6 GASEOUS RADWASTE TREATMENT 7.6.1 Dose Pro 'ections 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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ODCM Revision 0 Page 127 of 208 7.7.1.1 Gamma Dose to Air D~ 7 Xni DF~i (7.7) 1 where:

gamma dose to air for sector n, mrad.

air concentration of radionuclide i in sector n, Dyn Xni pCi-year/m . Air concentrations are calculated as described by Equation 7.11.

DFyi 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:

= beta dose 'to air for sector n, mrad.

air concentration of radionuclide i in sector Dan Xni n, pCi-year/m . Air concentrations are calculated as described by Equation 7.11.

Dpi = 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 j=l fj exp(-Xi x/uj) 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 RPT 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.

QT 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 for meat, 1 - exp(-X itch) where 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

ODCM Revision 0 Page 133 of 208 7.8.2 Stored Feed-Cow/Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Xitcsf))

CSi = 0 DF iao Uap mi Qf s exP( Xitfm) csf i r(1-exP(-XEtesf)) Biv(1-exP(-Xitb))

~sf >E P Ai where:

106 conversion factor, pCi/pCi.

DFLiao = 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 Uap Fmi =

(Table 6.2).

Qf = animal's consumption rate, kg/day.

fs = fraction of time animal spends on stored feed, dimensionless.

Xi decay constant for nuclide i, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

r = fraction of activity retained on pasture grass, dimensionless.

XE 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 tesf = time stored feed is exposed to deposition, seconds.

>sf = agricultural productivity by unit area of stored feed, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = 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.

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ODCM Revision 0 Page 135 of 208 7.8.4 Stored Feed-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

~

(1-exp(-'hit b) )

RMSi = 10 DFLiao Uam Ffi Qf i cb exP( Kits)

(1-exp (-'Ait f) ) r(l-exP(-XEtesf)) Biv(1-exP(-Xitb))

fs Xi tcsf Ysf XE P Xi where:

106 factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Ua = meat ingestion rate for age group a, kg/year.

transfer factor for nuclide i from cow's feed to meat, days/kg Ffi =

(Table 6.2).

Qf = cow's consumption rate, kg/day.

Xi decay constant for nuclide i, seconds (Table 6.2).

tcb = time NOTE'onversion for receptor to consume a whole beef, seconds.

ts = transport time from slaughter to consumer, seconds.

fs = fraction of time cow spends on stored feed, dimensionless.

tcsf = time between harvest of stored feed and consumption by cow, seconds.

r = fraction of activity retained on pasture grass, dimensionless.

tesf = time stored feed is exposed to deposition, seconds.

>sf = agricultural productivity by unit area of stored feed, kg/m2.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + Q.

Xw weathering decay constant for leaf and plant surfaces, seconds Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = 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.

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ODCH Revision 0 Page 137 of 208 7.8.6 Stored Ve etable In estion Dose Factors m -mrem/year per pCi/second)

(1-e(-X t ))

RgSi = 10 "iao exp( Xi hc) Sa g i sv r(1-e(-%Etc) ) Biv(1-e(-Xitb))

( }

~sv >E P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

'Ai decay constant for nuclide i, seconds (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

tsv = 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 te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.

lsv = vegetation areal density for stored vegetables, kg/m .

>iv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = 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.

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ODCM Revision 0 Page 139 of 208 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )

(1-exP(-XTtcsf))

RCTS 10 10 DFLTao FmT pf Uap [0 '5(0 '/H)] fs exp(-'ATtfm)

T csf where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

o.15 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fs = fraction of time animal spends on stored feed, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tfm = 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.

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ODCM Revision 0 Page 141 of 208 7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )

RMTS = 10 10 DFLTao FfT Qf'Uam [0.75(0.5/H)] fs exP(-its)

(1-exP( XTtcsf)) (1-exP( XTtcb))

XT tcsf XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fs = fraction of time cow spends on stored feed, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tcb = 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.

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ODCM Revision 0 Page 143 of 208 7.8.12 Tritium-Stored Ve etables Dose Factor (mrem/year per pCi/m )

(1-exP(-XTtsv))

RATS = 10 10 DFLTao [0.75(0.5/H)) USa g exP(-XTthc)

T sv where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0. 75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

tsv = time between harvest of stored vegetables and their consumption and/or storage, seconds.

thc = 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.

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ODCM Revision 0 Page 145 of 208 7.9 DISPERSION METHODOLOGY 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 0.45 0.7-1.5 1.10 1.6-2.4 1.99 2.5-3.3 2.88 3.4-5.5 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.

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~ I ODCM Revision 0 Page 147 of 208 7.9.2 Relative Concentration X/q (sec/m )

Relative concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 X/q = E 7. (2/~)'/2 3 exP( .h 2/2azk2) (7.12) j=l k=1 Ezk uj (21ac/n) where:

fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, expressed as a fraction.

blowing toward this exposure point, Ezk vertical dispersion coefficient for stability class k which includes a building wake adjustment, (ozk2 + cA/e)1/2~

or = l3 crzk, whichever is smaller (for ground level releases).

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 ).

x uj midpoint value of wind speed class interval

= downwind distance, m.

j, m/s.

n = number of sectors, 16.

2m/n sector. width at point of interest, m.

he 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/~ = E (7.13) j=l k=1 (2m/n) where:

fk joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.

DR = 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.

x = downwind distance, m.

n "-number of sectors, 16.

2m/n sector width at point of interest, m.

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ODCM Revision 0 Page 149 of 208 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA 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 1525 N 7 1.60E-06 5.64E-09 N/A N/A Site Boundary 1300 NNE 4 7.88E-07 1.97E-09 N/A N/A Site Boundary 1250 NE 7 4.52E-07 1.56E-09 N/A N/A Site Boundary 1450 ENE 0 7.30E-07 2.92E-09 N/A N/A Site Boundary 1375 E 0 8.24E-07 4.04E-09 N/A N/A Site Boundary 1575 ESE 0 4.56E-07 3.28E-09 N/A N/A Site Boundary 5600 SE -6 7.61E-08 3.63E-10 N/A N/A Site Boundary 2875 SSE -6 4.86E-07 f.77E-09 N/A N/A Site Boundary 2550 S -6 8.27E-07 2.24E-09 N/A N/A Site Boundary 2425 SSW -6 1.08E-06 2.92E-09 N/A N/A Site Boundary 2300 SW -6 6.87E-07 1.75E-09 N/A N/A Site Boundary 2500 WSW -6 6.38E-07 1.14E-09 N/A N/A Site Boundary 2550 W -6 6.70E-07 1.25E-09 N/A N/A Site Boundary 3325 WNW -6 3.69E-07 9.07E-10 N/A N/A Site Boundary 2275 NW -6 1.69E-06 4.92E-09 N/A N/A Site Boundary 1650 NNW -6 1.84E-06 5.29E-09 N/A N/A Air Dose Point 6100 NW -6 N/A N/A 2.08E-08 4.75E-10 Garden 1830 NNW 34 1.57E-06 4.46E-09 N/A 1.13E-09 Garden 4437 E 19 N/A N/A 9.50E-09 N/A Milk Cow 8045 N 34 1.47E-07 3.16E-10 N/A 2.30E-10 Milk Cow 10975 NNW 34 N/A N/A 1.69E-08 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.

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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 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 0.0 0.0 0.0 0.04 0.12 0.05 0.0 0.0 0.21 NNE 0.0 0.0 0.0 0.05 0.19 0.10 0.0 0.0 0.34 NE 0.0 0.0 0.0 0.04 0.06 0.0 0.0 0.0 0.10 ENE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 E 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 ESE 0.0 0.01 0.11 0.17 0.02 0.0 0.0 0.0 0.31 SE 0.0 0.03 1.11 0.40 0.02 0.0 0.0 0.0 1.56 SSE 0.0 0.04 0.52 0.10 0.02 0.0 0.0 0.0 0.68 S 0.0 0.01 0.38 0.11 0.04 0.0 0.0 0.0 0.54 SSW 0.0 0.0 0.04 0.05 0.01 0.0 0.0 0.0 0.10 SW 0.0 0.0 0.05 0.04 0.0 0.0 0.0 0.0 0.09 WSW 0.0 0.0 0.04 0.07 0.04 0.0 0.0 0.0 0.15 W 0.0 0.0 0.01 0.05 0.05 0.01 0.0 0.0 0.12 WNW 0.0 0.0 0.02 0.03 0.09 0.06 0.0 0.0 0.20 NW 0.0 0.0 0.0 0.02 0.17 0.11 0.0 0.0 0.30 NNW 0.0 0.0 0.01 0.01 0.06 0.09 0.02 0.0 0.19 Sub-total 0.0 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- 1259 Total hours calm 0 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 0.0 0.01 0.08 0.11 0.21 0.02 0.0 0.0 0.43 NNE 0.0 0.01 0.07 0.09 0.17 0.20 0.0 0.0 0.36 NE 0.0 0.0 0.03 0.08 0.05 0.0 0.0 0.0 0.16 ENE 0.0 0.0 0.02 0.02 0.0 0.0 0.0 0.0 0.04 E 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.05 ESE 0.0 0.01 0.05 0.02 0.0 0.0 0.0 0.0 0.08 SE 0.0 0.17 0.29 0.09 0.01 0.0 0.0 0.0 0.56 SSE 0.0 0.12 0.17 0.04 0.01 0.0 0.0 0.0 0.34 S 0.0 0.11 0.25 0.04 0.02 0.0 0.0 0.0 0.42 SSW 0.0 0.03 0.06 0.01 0.0 0.0 0.0 0.0 0.10 SW 0.0 0.03 0.12 0.03 0.01 0.0 0.0 0.0 0.19 WSW 0.0 0.0 0.11 0.07 0.07 0.0 0.0 0.0 0.25 W 0.0 0.0 0.05 0.12 0.10 0.02 0.01 0.0 0.30 WNW 0.0 0.01 0.12 0.13 0.17 0.07 0.04 0.0 0.54 NW 0.0 0.0 0.05 0.09 0.22 0.10 0.01 0.0 0.47 NNW 0.0 0.0 0.02 0.08 0.18 0.10 0.0 0.0 0.38 Sub-total 0.0 0.50 1.52 1.04 1.22 0.33 0.06 0.0 4.67 Total hours of valid stability observations 25935 Total hours of Stability Class C 1202 Total hours of valid wind direction-wind speed-Stability Class C 1197 Total hours calm 0 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 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 0.04 0.47 0.54 0.43 0.41 0.05 0.01 0.0 1.95 NNE 0.05 0.61 0.74 0.55 0.47 0.04 0.0 0.0 2.46 NE 0.05 0.57 0.63 0.42 0.27 0.02 0.0 0.0 1.96 ENE 0.05 0.71 0.45 0.17 0.08 0.02 0.0 0.0 1.48 E 0.04 0.61 0.74 0.16 0.07 0.0 0.0 0.0 1.62 ESE 0.03 0.76 1.01 0.53 0.16 0.01 0.0 0.0 2.50 SE 0.11 2.04 1.75 0.92 0.55 0.02 0.0 0.0 5.39 SSE 0.07 1.16 0.78 0.48 0.33 0.04 0.0 0.0 2.86 S 0.05 1.03 0.74 0.44 0.63 0.14 0.01 0.0 3.04 SSW 0.02 0.52 0.14 0.08 0.06 0.01 0.0 0.0 0.83 SW 0.04 0.30 0.07 0.02 0.03 0.0 0.0 0.0 0.46 WSW 0.01 0.53 0.60 0.14 0.11 0.04 0.0 0.0 1.43 W 0.02 0.37 0.77 0.42 0.27 0.04 0.0 0.0 1.89 WNW 0.03 0.15 0.13 0.11 0.22 0.09 0.02 0.0 0.75 NW 0.02 0.17 0.20 0.14 0.25 0.09 0.02 0.0 0.89 NNW 0.05 0.41 0.48 0.54 0.59 0.09 0.01 0.0 2.17 Sub-total 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- 8098 Total hours calm 3 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 0.07 0.76 0.32 0.02 0.0 0.0 0.0 0.0 1.17 NNE 0.05 0.83 0.51 0.18 0.02 0.0 0.0 0.0 1.59 NE 0.04 0.34 0.12 0.02 0.0 0.0 0.0 0.0 0.52 ENE 0.04 0.48 0.18 0.02 0.0 0.0 0.0 0.0 0.72 E 0.02 0.52 0.34 0.0 0.0 0.0 0.0 0.0 0.88 ESE 0.01 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.08 0.43 0.09 0.04 0.03 0.0 0.0 0.0 0.67 SSE 0.03 0.44 0.31 0.16 0.08 0.0 0.0 0.0 1.02 S 0.05 0.09 0.12 0.10 0.04 0.0 0.0 0.0 0.40 SSW 0.05 0.05 0.01 0.0 0.0 0.0 0.0 0.0 0.11 SW 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 WSW 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.04 W 0.01 0.01 0.0 0-0 0.0 0.0 0.0 0.0 0.02 WNW 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.03 NW 0.04'.04 0.0 0.0 0.0 0.0 0.0 0.0 0.08 NNW 0.05 0.23 0.12 0.03 0.0 0.0 0.0 0.0 0.43 Sub-total 0.57 4.45 2.13 0.57 0.17 0.0 0.0 0.0 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- 2019 Total hours calm 4 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 0.0 0.0 0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.03 NNE 0.0 0.0 0.0 0.0 0.0 0.03 0.02 0.0 0.0 0.05 NE 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.0 0.05 0.04 0.01 0.0 0.0 0.0 0.10 SSE 0.0 0.0 0.0 0.03 0.02 0.01 0.0 0.0 0.0 0.06 S 0.0 0.0 0.0 0.02 0.02 0.01 0.0 0.0 0.0 0.05 SSW 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 WNW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 0.0 0.0 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.04 NNW 0.0 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.0 0.05 Sub-total 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 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 0.0 0.0 0.0 0.0 0.01 0.03 0.0 0.0 0.0 0.04 NNE 0.0 0.0 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.03 NE 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 S 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.01 0.01 0.01 0.01 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.03 0.0 0.08 NW 0.0 0.0 0.0 0.0 0.01 0.03 0.02 0.01 0.0 0.07 NNW 0.0 0.0 0.0 0.0 0.01 0.02 0.03 '.0 0.0 0.06 Sub-total 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 0.0 0.0 0.0 0.04 0.06 0.07 0.02 0.01 0.0 0.20 NNE 0.0 0.0 0.01 0.06 0.07 0.08 0.02 0.0 0.0 0.24 NE 0.0 0.0 0.01 0.06 0.06 0.05 0.01 0.0 0.0 0.19 ENE 0.0 0.0 0.02 0.04 0.03 0.01 0.01 0.0 0.0 0.11 E 0.0 0.0 0.02 0.07 0.02 0.01 0.0 0.0 0.0 0.12 ESE 0.0 0.0 0.02 0.08 0.07 0.03 0.0 0.0 0.0 0.20 SE 0.0 0.0 0.08 0.22 0.16 0.18 0.02 0.0 0.0 0.66 SSE 0.0 0.0 0.05 0.12 0.12 0.19 0.04 0.0 0.0 0.52 S 0.0 0.0 0.06 0.10 0.09 0.27 0.13 0.01 0.0 0.66 SSM 0.0 0.0 0.02 0.02 0.02 0.02 0.01 0.0 0.0 0.09 SM 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.0 0.02 MSW 0.0 0.0 0.01 0.05 0.02 0.03 0.02 0.0 0.0 0.13 W 0.0 0.0 0.01 0.06 0.05 0.05 0.01 0.0 0.0 0.18 WNM 0.0 0.0 0.0 0.01 0.01 0.04 0.02 0.01 0.0 0.09 NW 0.0 0.0 0.0 0.01 0.02 0.04 0.03 0.01 0.0 0.11 NNW 0.0 0.0 0.0 0.03 0.07 0.10 0.02 0.01 0.0 0.23 Sub-total 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

ODCM Revision 0 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 0.0 0.0 0.02 0.04 0.0 0.0 0.0 0.0 0.0 0.06 NNE 0.0 0.0 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.11 NE 0.0 0.0 0.01 0.01 0.0 o.o 0.0 o.o 0.0 0.02 ENE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 E 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE SE '.0 0.0 0.03 0.01 0.01 0.02 0.0 0.0 0.0 0.07 SSE 0.0 0.0 0.04 0.05 0.03 0.06 0.0 0.0 0.0 0.18 S 0.0 0.0 0.01 0.02 0.02 0.01 0.0 0.0 0.0 0.06 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.01 0.01 0.08 0.0 0.0 0.0 0.0 0.02 Sub-total 0.0 0.0 0.17 0.22 0.09 0.09 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0" 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE E 0.0 0.0 0.0 '.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE'SE 0.0 0.0 0.01 0.01 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 S 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSW 0.0 0'.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 WSW 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0..0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub-total 0.0 0.0 0.01 0.01 0.01 0.03 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 0.0 0.0 0.12 0.40 0.62 1.49 0.87 0.12 0.0 3.62 NNE 0.0 0.01 0.13 0.46 0.72 1.88 0.91 0.05 0.0 4.16 NE 0.0 0.0 0.09 0.36 0.48 1.04 0.14 0.02 0.0 2.)3 ENE 0.0 0.01 0.11 0.24 0.23 0.23 0.04 0.01 0.0 0.87 E 0.0 0.01 0.10 0.20 0.28 0.25 0.05 0.01 0.0 0.80 ESE 0.0 0.01 0.22 0.52 0.68 1.07 0.16 0.0 0.0 2.66 SE 0.0 0.01 0.67 1.66 0.89 1.75 ~

0.84 0.16 0.01 5.99 SSE 0.0 0.01 0.48 0.90 0.63 1.49 1.08 0.26 0.02 4.871 S 0.0 0.0 0.34 0.99 0.67 0.99 0.93 0.33 0.02 4.27 SSW 0.0 0.01 0.20 0.52 0.37 0.69 0.34 0.11 0.0 2.24 SW 0.0 0.01 0.24 0.79 0.43 0.49 0.32 0.05 0.0 2.33 WSW 0.0 0.02 0.16 0.51 0.57 0.57 0.27 0.08 0.0 2.18 W 0.0 0.0 0.07 0.36 0".80 1.34 0.55 0.16 0.01 3.29 WNW 0.0 0.0 0.09 0.33 0.48 1.25 0.94 0.32 0.01 3.42 NW 0.0 0.0 0.07 0.36 0.55 1.40 1.44 0.37 0.01 4.20 NNW 0.0 0.0 0.09 0.29 0.53 1.36 1.15 0.19 0.0 3.61 Sub-total 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 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 0.0 0.0 0.03 0.08 0.06 0.34 0.05 0.0 0.0 0.56 NNE 0.0 0.0 0.04 0.06 0.11 0.42 0.21 0.0 0.0 0.54 NE 0.0 0.0 0.04 0.10 0.15 0.40 0.12 0.0 0.0 0.81 ENE 0.0 0.0 0.04 0.11 0.11 0.29 0.07 0.0 0.0 0.62 E 0.0 0.0 0.03 0.07 0.11 0.32 0.02 0.0 0.0 0.55 ESE 0.0 0.0 0.13 0.26 0.24 0.24 0.0 0.0 0.0 0.87 SE 0.0 0.0 0.13 0.38 0.30 0.19 0.0 0.0 0.0 1.00 SSE 0.0 0.0 0.09 0.11 0.12 0.14 0.03 0.0 0.0 0.49 S 0.0 0.0 0.08 0.11 0.13 0.21 0.03 0.0 0.0 0.56 SSW 0.0 0.0 0.04 0.12 0.14 0.24 0.01 0.0 0.0 0.55 SW 0.0 0.0 0.04 0.09 0.10 0.06 0.0 0.0 0.0 0.29 WSW 0.0 0.0 0.03 0.07 0.06 0.05 0.0 0.0 0.0 0.21 W 0.0 0.01 0.04 0.04 0.05 0.04 0.0 '0.0 0.0 0.18 WNW 0.0 0.0 0.02 0.04 0.01 0.01 0.0 0.0 0.0 0.08 NW 0.0 0.0 0.03 0.04 0.03 0.02 0.0 0.0 0.0 0.12 NNW 0.0 0.0 0.02 0.02 0.04 0.10 0.0 0.0 0.0 0.18 Sub-total 0.0 0.01 0.83 1.70 1.76 3.07 0.54 0.0 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

ODCM Revision 0 Page 173 of 208 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose mrem/yr per pCi/m3 mrad/yr per pCi/m3 DFBi DFSi DFYi Dpi Kr-83m 7.56E-02 " 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-l.

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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 0 10 55 35 85 670 15'15 2615 10660 3690 0 5 15 65 55 915 2990 2230 3125 3420 NE 0 5 25 45 88 4180 14180 6625 5385 12625 ENE 0 15 50 40 70 1310 4990 9615 13860 5425 0 30 10 40 945 1910 73405 75125 4610 ESE 0 5 0 0 165 1880 2535 7465 9575 SE 0 0 0 20 10390 30945 4660 6230 13850 SSE 0 0 0 50 1630 6250 11630 15175 18945 0 20 35 90 1250 3805 1800 4475 3730 SSW 0 60 75 175 845 5895 1270 1490 2535 SW 0 20 35 90 685 2970 2280 2725 10675 WSW 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

ODCM Revision 0 Page 177 of 208 Table 7.7 (2 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 3.90E-06 7.36E-OS 1.55E-06 9.44E-09 O.OOE+00 3.10E-'4 5.08E-05 Sb-125 6.67E-06 7.44E-OS 1.58E-06 6 '5E-09 O.OOE+00 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-OS 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-ll 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-OS 1.82E-05 6 '5E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-OS 2.69E-08 2.02E-OS 2.37E-OS 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 O.OOE+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 O.OOE+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 O.OOE+00 5.08E-OS I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 O.OOE+00 1.11E-06 I-134 8.05E-OS 2.16E-07 7.69E-OS 3.73E-06 3.44E-07 O.OOE+00 1.26E-10 I-135 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+00 6.56E-07 3.35E-07'.66E-05 Cs-134 1.06E-04 9.10E-05 O.OOE+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 O.OOE+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 O.OOE+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-OS 7.76E-08 4.05E-OS O.OOE+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 O.OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-OS 5.73E-09 O.OOE+00 O.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 O.OOE+00 O.OOE+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 O.OOE+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-OS 1.72E-08 1.91E-09 O.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 O.OOE+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 O.OOE+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3. 76E-12 1.56E-12 1.91E-13 O.OOE+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 O.OOE+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 O.OOE+00 O.OOE+00 3.63E-06 1.94E-05 Np-239 2.87E-OS 2.82E-09 1.55E-09 O.OOE+00 8.75E-09 4.70E-06 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 for bone is assumed to be equal to the total body dose factor.

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ODCM Revision 0 Page 179 of 208 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS .

(mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney lung gi-lli Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E O.OOE+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 O.OOE+00 6 '0E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.'t2E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 O.OOE+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 O.OOE+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 O.OOE+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 O.OOE+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 O.OOE+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 O.OOE+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 O.OOE+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 O.OOE+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 O.OOE+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 O.OOE+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 O.OOE+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 O.OOE+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 O.OOE+00 O.OOE+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 O.OOE+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 O.OOE+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 O.OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 O.OOE+00 1.26E-12 2.19E-07 2. 94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 O.OOE+00 6.28E-07 4.65E-05 2. 28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 O.OOE+00 O.OOE+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 O.OOE+00 1.25E-08 8.11E-06 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 for bone is assumed to be equal to the total body dose factor.

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0 ODCM Revision 0 Page 181 of 208 Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD bone liver t body thyroid kidney lung gi-lli Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-OS O.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-OS O.OOE+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 O.OOE+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-OS 1.37E-OS 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-ll 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-OS 7.12E-OS 8.58E-OS 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 O.OOE+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0 ~ OOE+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+00 1.48E-06 I>>134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 O.OOE+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 O.OOE+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 O.OOE+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+00 7.63E-, 05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 O.OOE+00 1.68E-07 1.84E-08 7.29E-OS Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-OS 1.17E-06 O.OOE+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 O.OOE+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 O.OOE+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-OS O.OOE+00 O.OOE+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 O.OOE+00 O.OOE+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 O.OOE+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-OS 5.37E-OS 7.77E-09 O.OOE+00 2.26E-OS 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 O.OOE+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 O.OOE+00 2.64E-12 4.23E-07 5.32E-OS Nd-147 2.92E-06 2.36E-06 1.84E-07 O.OOE+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 O.OOE+00 O.OOE+00 1.11E-05 2.46E-05 Np-239 1 ~ 26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-OS 1.57E-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 for bone is assumed to be equal to the total body dose factor.

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ODCM Revision 0 Page 183 of 208 Table 7.7 (8 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.71E-05 3.97E-07 8.56E>>06 7.18E-08 O.OOE+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 O.OOE+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-ll 5.87E-12 3.57E-12 1.13E-ll 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 O.OOE+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E>>06 2.54E-03 1.60E-05 O.OOE+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 O.OOE+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 O.OOE+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 O.OOE+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 O.OOE+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 O.OOE+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 O.OOE+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 O.OOE+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-ll 2.36E-14 1.40E-12 O.OOE+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 O.OOE+00 O.OOE+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 O.OOE+00 O.OOE+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 O.OOE+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 O.OOE+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 O.OOE+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 O.OOE+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-ll 1.32E-ll 1.72E-12 O.OOE+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 O.OOE+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 O.OOE+00 O.OOE+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 O.OOE+00 4.73E-08 4.25E-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 for bone is assumed to be equal to the total body dose factor.

2024o

ODCM Revision 0 Page 185 of 208 Figure 7.2 NORMAL BUILDING VENTILATION ROOF FANS

~ ~

~

I

~ e r ~ i r

~ ~ ~ ~ ~~

+i ~ te ~ z Refuel, Turbine Deck Floor RM 90-249 RM 90-261 RM 90-262 Flem PAnay Oertebmem Puye Oyelem Turbine Building Control Reactor Building 9 yplcal for each unit) Bay (typical for each vnlt)

Te OCTO (emeepeney eemieeeq)

Used seasonally to control temperature 2024o

ODCM Reviaion 0 Page 187 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page 2 of 4) 1.0 'E ST kEIITRAL ICT

)'u OP

~ 0.T K

Q STALL 0.0 )AIIP) g

> 0S Z

0 g OA 03 02 0.1 1Al 10AI 'f 00.0'%00>.

tlUME TRAvEL DlsTAkcE IKILOMETERs) ~

Flume Dtptetfon Effect for 30m Relesses, )Letters denote Pesrtulll Stab)0ty Chss).

2024o

ODCM Revision 0 Page 189 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4)

NEUTRAl. (D) tu 0$

UNSTABLE (APS)

$ 0.2 STABLE (E,F,O)

Ig O.e NO DEPL ION (FRACTION REMAININO 3 os Z

O g o.i OD 0.2 0.1 0.1 1AI 10AI 100.0 200AI FLUME TRAYEL DlsTANcE (KILDMETERs)

Flun>> Depletion'EIIeet Ioe 100en Releeeet (Lettete denote Aequlll Steblllty Cteet) 2024o

ODCM Revision 0 Page 191 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 1 of 4) 10-4 LLJ I-sU UJ cr, o 1W I

O 0

O LLI I-

LU tt:

10-6 10 7 0.1 1.0 10.0 '100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Relative Deposition for Ground-Level Reieases (Ail Atmospheric Stability Classes) 2024o

ODCM Revision 0 Page 193 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4)

UNSTABLE (A,B 10 B NEUTRAL(D)

UJ I-UJ UNSTABLE tU N EUTRAL I-CC 0 1W rIJ 0

UJ O

, UJ STABL (E,F,G) 10-8 0.1 1.0 10.0> 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

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

ODCM Revision 0 Page 199 of 208 Table 9.1 (1 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis AIRBORNE Particulates 6 samples from Continuous sampler Particulate sampler.

locations (in operation with sam- Analyze for gross different sectors) ple collection as beta radioactivity at or near the required by dust >24 hrs following site boundary loading but at least filter change.

(LM<<l, LM-2, once per 7 days. Perform gamma isotopic LM-3, LM-4, analysis on each LM-6, and LM-7) sample when gross beta activity is >10 2 samples from times the average of control locations control samples.

greater than 10 Perform gamma miles from isotopic analysis the plant on composite (by (RM-1 and RM-6) location) sample at least once per 3 samples from 31 days.

locations in communities approx-imately 10 miles from the plant (PM-l, PM-2 and PM-3)

Radioiodine Same locations as Continuous sampler I-131 every 7 days air particulates operation with charcoal canister collection at least once per 7 days SOIL Samples from same Once every year Gamma scan, Sr-89, locations as air Sr-90 once per year particulates DIRECT 2 or more dosi- At least once per Gamma dose once per meters placed at 92 days 92 days locations (in dif-ferent sectors) at or near the site boundary in each of the 16 sectors 2024o

ODCM Revision 0 Page 201 of 208 Table 9.1 (3 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Drinking 2 additional sam- Grab sample taken Gross beta and gamma (continued) ples of potable at least once per scan at least once surface water 31 days. per 31 days.

downstream from Composite for Sr-89 the plant and Sr-90 and tritium (TRM 274.9 and at least once per TRM 259.5) 92 days 1 sample at a control location (TRM 306) 1 additional Collected by auto-sample at a con- matic sequential-trol location type sampler with (TRM 305) composite sample taken at least once per 31 daysa GROUND 1 sample adjacent Collected by auto- Composite for gamma to the plant matic sequential- scan, Sr-89, Sr-90, (well N6) type sampler with and tritium at least composite sample once per 92 days.

taken at least once per 31 days.

1 sample at a Grab sample taken Composite for gamma control location at least once per scan, Sr-89, Sr-90, upgradient from 31 days. and tritium at least the plant once per 92 days.

(Farm Bn)

AQUATIC Sediment 2 samples At least once per Gamma scan, Sr-89, upstream from 184 days and Sr-90 analyses discharge point (TRM 297.0 and TRM 307.52)

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

c The surface water control sample shall be considered a control for the drinking water sample.

2024o

ODCM Revision 0 Page 203 of 208 Table 9.1 (5 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locations Collection Fre uenc of Anal sis Clams 1 sample down- At least once per Gamma scan on flesh stream from the 184 days. only discharge 1 sample upstream from the plant.

(No permanent stations established; depends on avail-ability of clams).

Fruits & Samples of food At least once per Gamma scan on edible Vegetables crops such as year at time of portion corn, green beans, harvest tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from Once per 31 days I-131, gamma scan (pasturage) farms producing once per 31 days.

milk but not Sr-89 and Sr-90 providing a milk analysis on the last sample (Farm T). monthly sample of each quarter.

Control sample from 1 control dairy farm (Farm Gl) 2024o

ODCM Revision 0 Page 205 of 208 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Number Station Sector Miles) Offsite Off) 1 NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.3 Off 6 E-3 E 24.2 Off 7 N-1 N 1.0 On 8 NNE-1 NNE 0.9 On 9 ENE-1 ENE 0.9 On 10 NNW-2 NNW 1.7 On 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 On 40 NNE-3 NNE 5.2 Off 41 NE-1 NE 0.8 On 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-1 E 0.8 On 45 E-2 E 5.2 Off 46 ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 On 49 SE-2 SE 5,4 Off 50 SSE-1 SSE 5.1 Off 51 S-l S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-2 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-1 SW 1.9 On 56

'W-2 SW 4,7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-1 W 1.9 On 62 W-2 W 4,7 Off 63 W-4 W 32. 1 Off 64 WNW-1 WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 66 NW-1 NW 2.2 Off 67 NW-2 ~

NW 5.3 Off 68 NNW-1 NNW 1.0 On 69 NNW-3 NNW 5.2 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

ODCM Revision 0 Page 207 of 208 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT H 11.25

$ 45,Td I 3 ~ >

HHE I't3 SS.TS 225.25 42 55.25 502.75 WHW Q ~T C~ 8 85 ~ 10 TS.Td 25 IA 36,84 81 40 SROWHS FERI1T

~ 101.2S 25S.T 0 s 4 65 P ~

<+4,3T SSK

<e Cs.

WSW 123.TS sse25 61 SE SW 68

~ 54 'I 5 5.25 2 IS.T5 SSK SCALE SSW o os ISS.T5 MLS 5 I ~ 1.25 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

PCP Manual Revision 0 Page 5 of 19 3.8 Vendor To ical Re orts 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.

2023o

PCP Manual Revision 0 Page 9 of 19 ATTACHMENT 1 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 TRUCK CHEM-5 18 NUCLEAR ft.

29 ft. 3 in. SYSTEM r

Shielding F~.

io'5" -I 2023o

PCP Manual Revision 0 Page 13,of 19 ATTACHMENT 2 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).

2023o

PCP Manual Revision 0 Page 15 of 19 ATTACHMENT 3 (Continued)

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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P(. nua1 Revision 0 Page 17 of 19 ATTACHMENT 3 (Continued)

FiGURE 2 Waste Packaging Room Layout For Chem Nuclear System Radwaste Bldg.

565'04 ft. 3 in.

Crane Operator Hatform TRUCK CHEM-18 NUCLEAR 29 ft. 3 in. ft.

SYSTEM I

>o'5" -I Shielding

PCP Manual Revision 0 Page 19 of 19 ATTACHMENT 4 (Continued)

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.

LAST PAGE 2023o

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ML18036A591

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