Text

Offsite Dose Calculation Manual, Revision 17
	ML061220647
Person / Time
Site:	Browns Ferry, Oconee
Issue date:	02/04/2005
From:	Black J, Krueger K; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML061220647 (210)
	v • d • e

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL ODCM REVISION 17 PREPARED BY: Johnnie S. Black PHONE: 2036 RESPONSIBLE ORGANIZATION: RADCHEM, CHEMISTRY APPROVED BY:KURT KRUEGER DATE: 02/04/2005 EFFECTIVE DATE: 03/30/2005 LEVEL OF USE: REFERENCE USE QUALITY-RELATED

REVISION LOG Procedure Number: ODCM Revision Number: 0017 Page Affected: 61 Pagination Pages: None Description of Changes: IC-18.

Revised the definition of OPERABLE - OPERABILITY to be consistent with the Technical Specifications definition. The ODCM currently defines OPERABLE - OPERABILITY as, "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...". The Technical Specification definition states, "...normal or emergency electrical power sources...". , (BF PER 70165-001)

Since only one power supply is required for operability of the instrumentation, this change will maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Revision 0017 Page I of 208 OFFSITE DOSE CALCULATION MANUAL (ODCM)

ODCM Revision 0017 Page 2 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 1 of 10)

Section page INTRODUCTION ........................................................ 12 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS ......................... 14 1/2.) APPLICABILITY ................................................ 15 1/2.1 INSTRUMENTATION ............................................... 17 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 17 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 22 1/2.2 RADIOACTIVE EFFLUENTS .27 1/2.2.1 LIQUID EFFLUENTS . ........................................... 27 1/2.2.1.1 CONCENTRATION . ............................................ 27 1/2.2.1.2 DOSE ................................................... 31 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM ...... .................... 32 1/2.2.2 GASEOUS EFFLUENTS . ........................................... 33 1/2.2.2.1 DOSE RATE ................................................. 33 1/2.2.2.2 DOSE - NOBLE GASES . ....................................... 36 1/2.2.2.3 DOSE - I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS . 37 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ........ ........................ 38 1/2.2.3 TOTAL DOSE .................................................. 39 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ...... ................... 40 1/2.3.1 MONITORING PROGRAM . ......................................... 40 1/2.3.2 LAND USE CENSUS .............................................. 48 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ...... .................... 50

ODCM Revision 0017 Page 3 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page BASE:; .. .............................................................. 51 1/2.:L.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 52 1/2.:L.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 52 1/2.2 RADIOACTIVE EFFLUENTS ......................................... 53 1/2.2.1.1 CONCENTRATION ............................................. 53 1/2.2.1.2 DOSE ...................................................... 53 1/2.2.1.3 LIQUID WASTE TREATMENT .................................... 54 1/2.2.2 GASEOUS EFFLUENTS ........................................... 54 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 WITH HALF-LIVES GREATER THAN EIGHT DAYS... 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 3.0.13. CHANNEL FUNCTIONAL TEST ........... ........................... 60 3.0.0'. GASEOUS WASTE TREATMENT SYSTEM ....... ........................ 60 3.0.]). DOSE EQUIVALENT I-131 . ........................................ 60 3.0.3. MEMBER(S) OF THE PUBLIC ........... ........................... 60 3.0.F. OPERABLE - OPERABILITY . ...................................... 61 3.0.13. PURGE - PURGING ............................................... 61

ODCM Revision 0017 Page 4 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

Section page 3.0.H. RATED POWER ............ ...................................... 61 3.0.1. SITE BOUNDARY ........... ..................................... 61 3.0.1. SOURCE CHECK . ................................................. 61 3.0.K. UNRESTRICTED AREA ............................................ 62 3.0.L. VENTING . ..................................................... 62 3.0.M. CONTROLLED AREA ......... ..................................... 62 3.0.1. RESTRICTED AREA ......... ..................................... 62 3.0.P. MODE . ......................................................... 62 4.0 (NOT USED) . ..................................................... 66 5.0 ADMINISTRATIVE CONTROLS ......................................... 67 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT .... .......... 68 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ...................... 68 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES ......................... 69 5.4 SPECIAL REPORTS . ................................................. 69 5.5 QUALITY ASSURANCE PROCEDURES .................................... 69 6.0 LIQUID EFFLUENTS .......... ...................................... 70 RELEASE POINTS .......................... ............................ 71 6.1 LIQUID RELEASES ........... ...................................... 72 6.1.L Pre-release Analysis/ECL - Sum of the Ratios ........ .......... 72 6.1.2 Release Flow Rate Calculations ............. .. ................. 72 6.1.3 Post-release Analysis ................... ...................... 73 6.2 INSTRUMENT SETPOINTS ............................................ 74 6.2.1 Release Point Monitor Allowable Values ........................ 74 6.2.2 Default Allowable Values ...................................... 75 6.2.2.1 Radwaste Discharge Monitor .............. .. .................. 75 6.2.2.2 Raw Cooling Water and Residual Heat Removal Service Water Monitors

..................................................... 76

ODCM Revision 0017 Page 5 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section page 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ..... ................ 77 6.3.1 Dose Calculation ...................... ........................ 77 6.3.2 Cumulative Doses ...................... ........................ 78 6.3.3 Comparison To Limits .................... ...................... 78 6.4 LIQUID RADWASTE TREATMENT SYSTEM ................................ 79 6.5 DOSE PROJECTIONS . ............................................... 80 6.6 :DOSE CALCULATIONS FOR REPORTING PURPOSES ........................ 81 6.6.1 Water Ingestion ............. .................................. 81 6.6.2 Fish Ingestion . ............................................... 82 6.6.3 Shoreline Recreation .......... ................................ 82 6.6.4 Total Maximum Individual Dose ................................. 83 6.6.5 Population Doses . ............................................. 84 6.7 LIQUID DOSE FACTOR EQUATIONS .................................... 86 6.7.L Water Ingestion Dose Factors .................................. 86 6.7.2 Fish Ingestion Dose Factors ................................... 86 6.7.3 Shoreline Recreation Dose Factors ............................. 86 7.0 GASEOUS EFFLUENTS . ............................................... 106 RELEASE POINTS DESCRIPTION .......... ................................ 107 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS .... ............... 108 7.1.1 Maximum Allowable Value ........ ............................... 108 7.1.2 Default Allowable Values ........ .............................. 109 7.2 Release Rate Limit Methodology .................................. 110

ODCM Revision 0017 Page 6 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section page 7.3 GASEOUS EFFLUENTS - DOSE RATES ............. .. ................... 112 7.3.:L RELEASE SAMPLING ..................... ......................... 112 7.3.2 NOBLE GAS DOSE RATES ................... ....................... 112 7.3.2.1 Total Body Dose Rate ........................................ 112 7.3.2.2 Skin Dose Rate .......... .................................... 113 7.3.3 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS -

ORGAN DOSE RATE .......... .................................... 114 7.4 CUMULATIVE DOSE - NOBLE GASES ................................... 115 7.4.1 Gamma Dose to Air ..................... ........................ 115 7.4.2 Beta Dose to Air .......... .................................... 116 7.4.:3 Cumulative Dose - Noble Gas ................................... 116 7.4.4 Comparison to Limits ........ .................................. 116 7.5 CUMULATIVE DOSE - ORGAN DOSE DUE TO 1-131, I-133, TRITIUM AND PARTICULATES WITH HALF LIVES GREATER THAN 8 DAYS .... ........... 117 7.5..l Organ Dose Calculation .. 117 7.5.2 Cumulative Doses ................ .................. 118 7.5.3 Comparison to Limits ................ .................. 118 7.6 GASEOUS RADWASTE TREATMENT ................................... 119 7.6..L DOSE PROJECTIONS .. 119 7.6.2 SYSTEM DESCRIPTION ............................................ 119 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ..... ................... 120 7.7.L Noble Gas Dose ................................................ 120 7.7.l.1 Gamma Dose to Air ........................................... 121 7.7.1.2 Beta Dose to Air ............................................ 121

ODCM Revision 0017 Page 7 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)

Section page 7.7.2 Radioiodine, Particulate and Tritium - Maximum Organ Dose .... 122 7.7.:3 Population Doses ......... .................................... 124 7.7.4 Reporting of Doses ........................................... 125 7.7..5 Dose to a MEMBER OF THE PUBLIC Inside the SITE BOUNDARY 125 7.8 GASEOUS DOSE FACTOR EQUATIONS .................................. 126 7.8.1 Pasture Grass-Cow/Goat-Milk Ingestion Dose Factors .126 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors .... ......... 127 7.8.3 Pasture Grass-Beef Ingestion Dose Factors .... ................ 128 7.8.4 Stored Feed-Beef Ingestion Dose Factors ...................... 129 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .... ............. 130 7.8.6 Stored Vegetable Ingestion Dose Factors ...................... 131 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor .... .......... 132 7.8.3 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor .... ............ 133 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ....................... 134 7.8.10 Tritium-Stored Feed-Beef Dose Factor ........................ 135 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor .... ............... 136 7.8.12 Tritium-Stored Vegetables Dose Factor ....................... 137 7.8.13 Inhalation Dose Factors ..................................... 138 7.8.14 Ground Plane Dose Factors ................................... 138 7.9 DISPERSION METHODOLOGY ........ ................... .............. 139 7.9.1 Annual Average Air Concentration ................ ... .......... 140 7.9.2 Relative Concentration ....... ................... ............. 141 7.9.3 Relative Deposition .......................................... 141 7.9.4 Effective Release Height ........................ ............. 142

ODCM Revision 0017 Page 8 of 2C8 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8.0 TOTAL DOSE ...................................................... 195 9.0 RWAIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..... .............. 197 9.1 MONITORING PROGRAM DESCRIPTION .................................. 198 9.2 DETECTION CAPABILITIES .......... ................................ 198 9.3 LiAND USE CENSUS . ................................................. 198 9.4 INTERLABORATORY COMPARISON PROGRAM .............................. 198

ODCM Revision 0017 Page 9 of 2C8 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 PROGRAM ................................................. 42 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (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 3.2 MODES ...................................................... 64 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS .................... 87 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA .. ..... 88 Table 6.3 DOSE CALCULATION FACTORS .................................. 91 Table 6.4 INGESTION DOSE FACTORS .................................... 93 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH .. ............. 101 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND.. 102 Table 7.1 BFN - OFFSITE RECEPTOR LOCATION DATA ...................... 143 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN ................................................ 144 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION ................................................. 145 Table 7.4NOBLE GAS DOSE FACTORS .................................... 173

ODCM Revision 0017 Page 10 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 9 of 10)

LIST OF TABLES page Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .......... 174 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT ........ 175 Table 7.7 INHALATION DOSE FACTORS .................................. 176 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............ 199 Table 9.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS ................................................ 204 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS ... ................. 205

ODCM Revision 0017 Page 11 of 208 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 10 of 10)

LIST OF FIGURES page Figu:re 3.1 LAND SITE BOUNDARY ........ ............................... 65 Figu::e 6.1 LIQUID RELEASE POINTS .................................... 104 Figure 6.2 LIQUID RADWASTE SYSTEM ................................... 105 Figucre 7.1 OFFGAS SYSTEM AND STANDBY GAS TREATMENT SYSTEM EFFLUENT MONITORING . .............................................. 184 Figure 7.2 NORMAL BUILDING VENTILATION .............................. 185 Figure 7.3 PLUME DEPLETION EFFECT ................................... 186 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME .... ... 190 Figure 7.5 RELATIVE DEPOSITION ........ .............................. 191 Figure 9.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT ........ .............................. 206 Figure 9.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ................................... 207 Figure 9.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT .............................. 208

ODCM Revision 0037 Page 12 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 Specification 5.5.4; 2) Radiological Environmental Monitoring Controls;

3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by BFN Technical Specifications 5.6.2 and 5.6.3; 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 Radiological Environmental Monitoring Program (REMP).

The I3FN 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.

ODCM Revision 0017 Page 13 of 208 Radioactive waste release levels to UNRESTRICTED AREAS shall be kept "as low as reasonably achievable" and are not to exceed the annual average concentration limits specified in 10 CFR Part 20, Appendix B, Table 2.

At the same time, the requirements specified in this manual permit the flexibility of operation, compatible with considerations of health and safe:y, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the annual average concentration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility and exerting every effort to keep levels of radioactive releases "as low as reasonably achievable" in accordance with criteria established in 10 CFR Part 50, Appendix I, the annual releases will result in a small fraction of the annual average concentration limits specified in 10 CFR Part 20, Appendix B, Table 2.

The surveillance/testing requirements given in this manual provide assu:ance that liquid and gaseous wastes are properly controlled and moni:ored during any release of radioactive materials in the liquid and gaseous effluents. These requirements provide the data for the licensee and -:he Commission to evaluate the station's performance relative to radioactive materials released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 5.0 of this manual.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may require the licensee to take such actions as the Commission deems appropriate.

ODCM Revision 0017 Page 14 of 208 SECTION 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS

ODCM Revision 0017 Page 15 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0) APPLICABILITY CONTROLS 1.0.L Compliance with the Controls contained in the succeeding sections is required during the MODES 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. If the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

11-h-ODCM Revision 0017 Page 16 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.) APPLICABILITY SURVEILLANCE REQUIREMENTS 2.0.:L Surveillance Requirements shall be met during the MODES specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

2.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a Control and associated action statements unless otherwise required by these Controls. Surveillance Requirements do not have to be performed on inoperable equipment.

ODCM Revision 0017 Page 17 of z:08 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 In accordance with BFN Technical Specification 5.5.4.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 Annual Radioactive Effluent Release Report why the in-operability was not corrected in a timely manner.

C. Report all deviations in the Annual Radioactive Release Report.

SURVEILLANCE REQUIREMENTS 2.1.:L Each of the radioactive liquid effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-1.

ODCM Revision 0017 Page 18 of 208 Table 1.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument* OPERABLE Applicability ACTION

1. Liquid Radwaste Effluent Monitor (RM-90-130) 1 ** A/B

2. RHR Service Water Monitor (RM-90-133D, -134D) 1 C

3. Raw Cooling Water Monitor (RM-90-132D) 1 ** D

4. Liquid Radwaste Effluent Flow Rate (77-60 loop) 1 ** E

Alarm/trip setpoints will be calculated in accordance with the guidance given in Section 6.2.

- During Releases via this pathway.

During operation of an RHR loop and associated RHR service water system.

ODCM Revision 0017 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:

(l) 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 specifiec.

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 path-gay without 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. Iif 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 1E-7 pCi/ml (gross) or < applicable ECL ratio (y isotopic) shall be used to monitor the effluent.

ACTIDN 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 lE-7 pCi/:ml (gross) or < applicable ECL 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 be 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.

1 See Table 2.2-1, Table Notation for the definition of LLD.

ODCM Revision 0017 Page 20 of 208 Table 2.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

a. Liquid Radwaste Effluent D4 M 18M 5 Q1 Monitor (RM-90-130)

b. RHR Service Water D4 M 18M 5 Q2 Monitor (RM-90-133D,-134D)

c. Raw Cooling Water D4 M 18M5 Q2 Monitor (RM-90-132D)

d. Liquid Radwaste Effluent D4 N/A 18M Q3 Flow Rate (77-60 loop)

ODCM Revision 0017 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 a maximum allowable extension not to exceed 25% of the interval given.

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.

ODCM Revision 001.7 Page 22 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 In accordance with BFN Technical Specification 5.5.4.a, the radioactive gaseous effluent monitoring instruments listed in Table 1.1-2 shall be OPERABLE with the applicability as shown in Table 1.1-2. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 7.2 to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

a. With a radioactive gaseous 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. Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

c. The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instrument(s) to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

d. Report all deviations in the Annual Radioactive Release Report.

SURVEILLANCE REQUIREMENTS 2.1.2 Each of the radioactive gaseous effluent monitoring instruments shall.

be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-2.

ODCM Revision 0017 Page 23 of 208 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

I:astrument Devices OPERABLE Applicability ACTION

1. STACK (RM-90-147B & -148B)

a. Noble Gas Monitor 1

A/C

b. Iodine Cartridge 1

B/C

c. Particulate Filter 1

B/C

d. Sampler Flow Abnormal 1

C/D

e. Stack Flow (FT, FM, FI-90-271) 1

G

2. R23ACTOR/TURBINE/REFUEL BUILDING VENTILATION ZONE (RM-90-250)

a. Noble Gas Monitor 1

A/C

b. Iodine Sampler 1

B/C

c. Particulate Sampler 1

B/C

d. Sampler Flowmeter 1

C/D

3. TURBINE BUILDING EXHAUST (RM-90-249, -251)

a. Noble Gas Monitor 1 ** A/C

b. Iodine Sampler 1 ** B/C

c. Particulate Sampler 1 ** B/C

d. Sampler Flowmeter 1 ** C/D

4. RPDWASTE BUILDING VENT (RM-90-252)

a. Noble Gas Monitor 1

A/C

b. Iodine Sampler 1

B/C

c. Particulate Sampler 1

B/C

d. Sampler Flowmeter 1

C/D

5. OFFGAS POST TREATMENT

a. Noble Gas Activity Monitor 1 ** F (RM-90-265, -266)

b. Sample Flow Abnormal 1 ** C/D (PA-90-262)

At all times.

- During releases via this pathway.

l4 1 - -

ODCM Revision 0017 Page 24 of 208 Table 1.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION A With the number of channels OPERABLE less than required by the Minimum Chan:nels OPERABLE requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION B With a number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed in accordance with the sampLing and analysis program specified in Table 2.2-2 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system (this includes the flow instrumentation) may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, calibration, or repair without providing, initiating grab sampling, or providing compensatory measures for flow instrumentation.

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 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 .

ACTION F With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Purging during SI perfDrmance is not considered a loss of monitoring capability.

ACTION G With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is recorded from 0-FI-90-348 (WRGERMS, Stack Flow Indicator)[BFPER960961]. If both 0-FI-90-271 and 0-FI-90-348 are inoperable, ACTION D applies.

11-a ODCM Revision 0017 Page 25 of 208 Table 2.1-2 (Page 1 of 2)

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

1. STACK

a. Noble Gas Monitor 4 D M 18M1 Q2

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

c. Particulate Filter W N/A N/A N/A

d. Sampler Flow Abnormal D N/A 18M Q

e. Stack Flowmeter D N/A 18M Q

2. R3ACTOR/TURBINE/REFUEL BUILDING VENTILATION ZONE

a. Noble Gas Monitor5 D M 18M1 Q2

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

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

b. Sampler Flowmeter D N/A 18M Q

3. TURBINE BUILDING EXHAUST

a. Noble Gas Monitor5 D M 18M 1 Q2

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

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

b. Sampler Flowmeter D N/A 18M Q

4. RkDWASTE BUILDING VENT

a. Noble Gas Monitor 5

D M 18M 1 Q2

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

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

b. Sampler Flowmeter D N/A 18M Q

5. OFF GAS POST TREATMENT

a. Noble Gas Activity D M 18M1 Q3 Monitor 4

b. Sample Flow Abnormal D N/A 18M Q2

ODCM Revision 0017 Page 26 of 208 Table 2.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Each requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the interval given.

1 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.

2 The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

L.Instrument indicates measured levels above the alarm/trip setpoint.

2.Instrument indicates an inoperative/downscale failure.

3.Instrument controls not set in operate mode (stack only).

3 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:

L.Instrument indicates measured levels above the alarm/trip setpoint.

2.Instrument indicates an inoperative/downscale failure.

3.Instrument controls not set in operate mode (stack only).

The two channels are arranged in a coincidence logic such that 2 upscale, o:r 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.

4 The noble gas monitor shall have a LLD of 1E-5 pCi/cc (Xe-133 Equivalent).

5 The noble gas monitor shall have a LLD of 1E-6 pCi/cc (Xe-133 Equivalent).

ODCM Revision 003.7 Page 27 of 2:08 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with BFN Technical Specifications 5.5.4.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 ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

a. If the above limits are exceeded, appropriate action shall be initiated without delay to bring the release within limits. Report all deviations in the Annual Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 2.2.:L.l.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.:L.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 once per 24 months.

2.2.L.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.

ODCM Revision 0017 Page 28 of 208 Table 2.2-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD) 3 Type Frequency Frequency Analysis (PCi/ml)

Batch Waste Each Each Batch Principal 5x10-7 Relaasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and 1x10-5 per Month Entrained Gases 5 Monthly Monthly Tritium lx10-5 Proportional Composite 2 Gross Alpha 1x10-7 Quarterly Quarterly Sr-89, Sr-90 5x10-8 Proportional Composite 2 Fe-55 1x10-6

ODCM Revision 003.7 Page 29 of 208 Table 2.2-1 (Page 2 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 A :atch 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.

3 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 95i probability with only a 5% 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 (-Apt)

Where:

LLD = the "a priori" lower limit of detection as defined above (PCi/g or pCi/ml),

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (cpm),

E = the counting efficiency (c/decay),

V = the sample size (g or ml),

2.22E+06 - the number of dpm/pCi Y = the fractional radiochemical yield, when applicable,

= the radioactive decay constant for the particular 1

radionuclide (s- ), and At = the elapsed time between midpoint of sample collection and time of counting (s).

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

ODCM Revision 003.7 Page 30 of 208 Table 2.2-1 (Page 3 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 4 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 liquid releases.

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 as being present..

Nu~lides which are below the LLD for the analysis should not be reported &s being present at the LLD level for that nuclide. I-131 shall have a LLD Of 5 .IE-6 pCi/ml.

5 Gamma Emitters Only.

ODCM Revision 0017 Page 31 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 In accordance with BFN Technical Specifications 5.5.4.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:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding t~he limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, National Primary Drinking Water Regulations.*

SURVEILLANCE REQUIREMENTS 2.2.L.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.

The requirements of (1) and (2) above are applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream only.

ODCM Revision 0017 Page 32 of 20O8 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM CONT:.ROLS 1.2.1.3 In accordance with BFN Technical Specification 5.5.4.f, the Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in liquid discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.20 mrem to any other organ per unit.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to ODCM Adminstrative Control 5.4, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 2.2.1.3 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with ODCM Section 6.5.

ODCM Revision 0017 Page 33 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONT:ROLS 1.2.2.1 In accordance with BFN Technical Specification 5.5.4.g, the dose ra.te 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: a. If the limits above are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits. Report all deviations in the Annual Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 2.2. 2.1. 1 The gross 8/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.

ODCM Revision 0017 Page 34 of 208 Table 2.2-2 (Page 1 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLE)l Type Frequency Frequency Analysis (lICi/ml)

A.Co:atainment Prior to Prior to Principal jx10-4 Purge Each PURGE Each PURGE Gamma Grab Emitters3 Sample5 Monthly 6 H-3 jx10-6 B.1. Stack Monthly Monthly 4 Principal jx10-4 Grab Sample Gamma Emitters 3

2. :3uilding Monthly Monthly 4 H-3 jx10-6 Ventilation Grab Sample

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radwaste C. All Release Continuous Charcoal I-131 lx10- 1 2 2 Points Sampler Sample Listed in Weekly 4 B. Above . . -

11 Continuous Particulate Principal jx10- 2 Sampler Sample Gamma Weekly 4 Emitters 3 I-131 jx10-1 2 2 Continuous Composite Gross Alpha 1x10-1 1 Sampler Particulate Sample Monthly Continuous Composite Sr-89, Sr-90 1X10-1 1 Sampler Particulate Sample Quarterly

ODCM Revision 0017 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 couant above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

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

Where:

LLD the "a priori" lower limit of detection (pCi/g or pCi/ml),

sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (cpm),

E the counting efficiency (c/decay),

V = the sample size (g or ml) 2.22:E+06 the number of dpm/pCi, Y = the fractional radiochemical yield, when applicable, X = 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 At should be used in the calculation It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not arL a p2steriori (after the fact) limit for a particular measurement.

2 When samples are collected 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.

5 A grab sample is not required after deinerting, provided that:

- the reactor has not achieved criticality in the interim, and,

- the reactor coolant temperature has not reached or exceeded 212 0F.

6 The primary coolant H-3 concentration in pCi/ml can be converted to pCi/cc and used to estimate the containment H-3 concentration (R38 960812 943).

ODCM Revision 0017 Page 36 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES CONTROLS 1.2.2.2 In accordance with BFN Technical Specification 5.5.4.h, the air dose to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to noble gases released in gaseous effluents per unit shall be limited to the following:

a. During any calendar quarter, to

5 mrad for gamma radiation and S10 mrad for beta radiation;

b. During any calendar year, to 5 10 mrad for gamma radiation and S 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, c.

Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent.

releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 2.2.2.2 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.3 at least once every 31 days.

ODCM Revision 0017 Page 37 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 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 5.5.4.e and i, 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 S 7.5 mrem;

b. To any organ during any calendar year to < 15 mrem.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 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.

ODCM Revision 0017 Page 38 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 During operation above 25% power, the discharge of the SJAE must be routed through the charcoal adsorbers.

In accordance with BFN Technical Specification 5.5.4.f, the GASEOUS RADWASTE TREATMENT SYSTEM shall be operable and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluents from each unit, to areas at and beyond the SITE BOUNDARY, would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With gaseous radwaste being discharged without treatment for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 2.2.2.4.1 During operation above 25% power, the position of the charcoal bed bypass valve will be verified daily.

2.2.2.4.2 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected in accordance with Section 7.6 at least once per 31 days.

-. 1-ODCM Revision 0017 Page 39 of z.08 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2-2.3 TOTAL DOSE CONT:ROLS 1.2.3 In accordance with BFN Technical Specification 5.5.4.j, the dose or dose commitment to a real individual in an UNRESTRICTED AREA 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:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of Control 1.2.3 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Sections 6.3, 7.4, and 7.5 and the methods in ODCM Section 8.0.

ODCM Revision 001.7 Page 40 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.. The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 2.3-1.

APPLrCABILITY: At all times.

ACTION:

a. With the REMP not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmentp.l Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action pricor to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter a report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted if:

concentration(l) concentration(2)

+ * * . 2 1.0 limit level(l) limit level(2)

When radionuclides other than those in Table 2.3-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annua].

Radiological Environmental Operating Report.

ODCM Revision 0017 Page 41 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS ACTION (CONTINUED):

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 REMP within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Control 1.3.1.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) aind 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 REQUIREMENTS 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.

ODCM Revision 0017 Page 42 of 208 Table 2.3-1 (1 of 3)

MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/Dr and Sample Sampling and Type and Frequency Sample Locationsa Collection Frequency of Analysis

1. AIRBORNE RadiDiodine/ Minimum of 5 Continuous operation Radioiodine canister:

Particulates locations of sampler with Analyze at least once sample collection as per 7 days for I-131.

required by dust loading but at least Particulate sampler:

once per 7 days. Analyze for gross beta radioactivity

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.

2. DERECT At least 40 At least once per Gamma Dose. At least R1,DIATION locations with 92 days. once per 92 days.

> 2 dosimeters at each location.

a Sample locations are given in ODCM Section 9.0.

ODCM Revision 0017 Page 43 of 208 Table 2.3-1 (2 of 3)

MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Path-way Number of Samples and/or and Sample Sampling and Type and Frequency Sample Locationsa Collection Frequency of Analysis

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 clays.

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

water supplies days.blc 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 a Sample locations are given in ODCM Section 9.0.

b 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 .

c Composite samples shall be collected over a period of S 14 days for 1-1:31 if drinking water is obtained within 3 miles downstream of the plant.

d 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, monitoring of ground water is not required.

ODCM Revision 0017 Page 44 of 208 Table 2.3-1 (3 of 3)

MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sample Locationsa Collection Frequency of Analysis

4. INGESTION

a. Milk 3 locations At least once per 15 I-131 analysis of days when animals each sample. Gamma are on pasture; isotopic analysis e.t at least once per least once per 31 clays 31 days at other times.

b. Fish 2 samples One sample in Gamma isotopic season, or at least analysis on edible once per 184 days portions.

if not seasonal.

One sample of commercial and game species.

c. Food 2 locations At least once per Gamma isotopic Productse year at time of analysis on edible harvest portion.

a Sample locations are given in ODCM Section 9.0.

e Since water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

ODCM Revision 00l.7 Page 45 of 208 Table 2.3-2 (1 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)ab FOR ENVIRONMENTAL SAMPLES Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kq, Analysis (pCi/L) (pCi/n3 ) wet) (pCi/L) wet) gross beta 4 0.01 N/A N/7A N/A N/A H-3 2000C 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-5, 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 ld 0.07 N/A 1 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 15 N/A N/A

ODCM Revision 0017 Page 46 of 2:08 Table 2.3-2 (2 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)ab FOR ENVIRONMENTAL SAMPLES TABLE NOTATION a The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 sh -

E V 2.22 Y exp(-X At)

Where:

LLD = the "a priori" lower limit of detection as defined above, (as pCi/g or pCi/L).

3b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, (cpm).

3 = the counting efficiency, (c/decay).

V = the sample size (g or L).

2.22 = the number of dpm/pCi, Y = the fractional radiochemical yield, (when applicable).

t = the radioactive decay constant for the particular radionuclide, (s-1 ) and At = for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples),

seconds.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b Other peaks which are measurable and identifiable shall be identified and reported.

c If no drinking water pathway exists, a value of 3000 pCi/L may be used.

d LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.

ODCM Revision 0017 Page 47 of 208 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or gases Fish Milk Food Products Analysis (pCi/L) (pCi/m3) (pCi/Kg, wet) (pCi/L) (pCi/Kq, wet)

H-3 2 x 1 04(a) N.A N.A N.A. N.A.

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

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

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

CD-60 3 x 102 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 2 (b) 0.9 N.A. 3 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. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.

ODCM Revision 0017 Page 48 of :08 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS CONTROLS 1.3.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest gardenr of greater than 500 square feet producing vegetables in each of the 16 meteorological sectors within a distance of 5 miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

1 Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction sector with the highest D/Q in lieu of the garden census.

APPLICABILITY: At all times.

ACTION:

With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in Section 7.5, identify the new location(s) in the next Annue.l Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Control 1.3.1, add the new location(s) to the REMP within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure s) and table(s) reflecting the new location(s).

SURVEILLANCE REQUIREMENTS (see next page)

IAs _ j ODCM Revision 0017 Page 49 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE REQUIREMENTS 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.

ODCM Revision 0037 Page 50 of 208 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONT:ROLS 1.3.3 Analyses shall be performed on radioactive materials supplied as part.

of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE REQUIREMENTS 2.3.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

ODCM Revision 0017 Page 51 of 208 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS AND 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.

ODCM Revision 0017 Page 52 of 208 BASEFS 1/2.1 EFFLUENT MONITORING INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the limits of 10 CFR Part 20 Appendix B, Tabl.e 2, Column 2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A t:o 10 CFR Part 50.

The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 2.1-1.

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments will be calculated in accordance with Section 7.2.1 to ensure that the alarm/trip will occur prior to exceeding ten times the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The action required when the number of OPERABLE channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 2.1-2.

TwD post treatment off-gas radiation monitors are provided and, when their trip point is reached, cause an isolation of the off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip or both have a downscale trip..

Both instruments are required for trip but the instruments are set so that the instantaneous stack release rate limit given in Control 1.2.2.1 is not exceeded.

The off-gas post treatment monitors are connected in a 2-out-of-2 logic arrangement. Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.

ODCM Revision 003.7 Page 53 of 208 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2-2.1.1 CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials released at any time in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than or equal to ten times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A limits of Appendix I to 10 CFR Part 50, and (2) the limits of 10 CFR Part 20.1301 (a)(1) to a member of the pttolic. The concentration limit for noble gases is based upon the assumption that Xe-135 is the 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. Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301 (a)(1) per 56FR23374.

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 site-:

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 :[

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 methodology 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.

ODCM Revision 0017 Page 54 of 208 BASE:,

1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID 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, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE This requirement is provided to ensure that the external dose rate at anytime at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301 (a)(2) for UNRESTRICTED AREAS. The 500 mrem/yr dose rate will ensure that the instanteous dose rate is well below 2 mrem/hr. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The specified release rate limits restrict, at all times, the corresponding ga~mma and beta dose rates to an individual at or beyond the SITE BOUNDARY to

< 500 mrem/year to the total body or < 3000 mrem/year to the skin. These release rates also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

The action for this requirement requires that appropriate corrective action(s) be taken to reduce gaseous effluent releases if the limits are exceeded.

ODCM Revision 001.7 Page 55 of 208 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES This requirement is provided to implement the requirements 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.

Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301 (a)(1) per 56FR23374.

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 NU'REG/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.

ODCM Revision 003.7 Page 56 of 208 BASE; 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 This requirement is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I. Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301 (a)(1) per 56FR23374.

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 equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for iodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the UNRESTRICTED AREA.

The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

If these limits are exceeded, this section requires that a special reDort be prepared and submitted to explain violations of the limiting doses contained in the section above.

ODCM Revision 0017 Page 57 of 208 BASES 1/2..2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS 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 Ap:pendix I, 10 CFR Part 50, for gaseous effluents.

This action requires that a special report be prepared and submitted to exlain 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.

Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301 (a)(1) per 56FR23374. 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 course 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 REMP 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

ODCM Revision 0017 Page 58 of 208 BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM (continued) radiological effluent monitoring program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The RE1MP satisfies the requirements of 10 CFR 50, Appendix A, Criteria 64 and 10 CFR 50, Appendix I, Section IV.B.2.

1/2.3.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census.

The best survey information from the door-to-door, mail, telephone, aerial or consulting with local authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via the leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

1/2.3.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

ODCM Revision 001.7 Page 59 of 208 SECTION 3.0 DEFINITIONS

ODCM Revision 003.7 Page 60 of 208 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these controls.

3.0.A. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

T:he CHANNEL CALIBRATION shall encompass the entire channel including alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL T:IST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire c:aannel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TEST and SOURCE CHECK.

3.0.:3. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channel - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip function.

3.0.C. GASEOUS WASTE TREATMENT SYSTEM T:he GASEOUS WASTE TREATMENT SYSTEM consists of the charcoal adsorber vessels installed in the discharge of the steam jet air ejector (SJAE) to provide delay to a unit's offgas activity prior to release.

3.0.D. DOSE EQUIVALENT I-131 DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (pCi/g) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

3.0.13. MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.

ODCM Revision 0017 Page 61 of 208 DEFINITIONS 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 or 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 RTED POWER refers to operation at a reactor power of 3,293 MWt (for a licensed thermal power of 3,293 MWt) or 3,458 MWt (for a licensed thermal power of 3,458 M~t); 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 (for a licensed thermal power of 3,293 MWt) applies, corresponds to 3,440 MWt.

3.0.1. SITE BOUNDARY Thae SITE BOUNDARY as defined in 10 CFR 20, shall be that line beyond waich the land or property is not owned, leased, or 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.

ODCM Revision 0017 Page 62 of 208 DEFINITIONS 3.0.::c. UNRESTRICTED AREA Am UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes (see Figure 3.1).

3.0.L. VENTING VENTING is the controlled process of discharging air or gas from primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required. Vent, used in system names, does not imply a VENTING process.

3.0.:M. CONTROLLED AREA A CONTROLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED AREA, but inside the SITE BOUNDARY, access to which can be limited by TVA for any reason, (See Figure 3.1).

3.0.N. RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is limited by the licensee for purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. The permanent RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by BFN Site.

3.0.P. MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 3.2 with fuel in the reactor vessel.

ODCM Revision 001.7 Page 63 of 208 Table 3.1 FREQUENCY NOTATION Notation Frequency S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

18M At least once per 18 months.

N.A. Not Applicable P Completed prior to each release

ODCM Revision 0017 Page 64 of 208 Table 3.2 MODES MODE TITLE REACTOR MODE AVERAGE REACTOR COOLANT SWITCH POSITION TEMPERATURE L l l l (OF) I 1 Power Operation Run NA 2 Startup Refuel J or Startup/Hot NA

__ Standby 3 Hot Shutdown A Shutdown >212 4 Cold Shutdown) Shutdown *212 5 Refueling k Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

ODCM Revision 003.7 Page 65 of 2:08 Figure 3.1 LAND SITE BOUNDARY

ODCM Revision 0017 Page 66 of 208 SECTION 4.0 (NOT USED)

ODCM Revision 0017 Page 67 of 208 SECTION 5.0 ADMINISTRATIVE CONTROLS

ODCM Revision 0017 Page 68 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 pre-operational 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 REMP; 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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Annual 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 liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.

ODCM Revision 0017 Page 69 of 208 5.0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Annual Radioactive Effluent Release Report shall include the information regarding solid waste as specified in the Process Control Program.

5.3 DFFSITE DOSE CALCULATION MANUAL CHANGES As required by BFN TS 5.5.1, changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained as required by process described in TVA-NQA-PLN89-A.

This documentation shall contain:

a. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and

b. A determination that the change will maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the process described in TVA-NQA-PLN89-A.

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.4 SPECIAL REPORTS Special Reports shall be submitted to the NRC in accordance with 10 CFR 50.4.

5.5 QUALITY ASSURANCE PROCEDURES Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, April 1975 or Regulatory Guide 4.15, Dec. 1977.

ODCM Revision 0017 Page 70 of 208 SECTION 6.0 LIQUID EFFLUENTS

ODCM Revision 0017 Page 71 of 208 6.0 - LIQUID EFFLUENTS RELEASE POINTS The minimum flow available for dilution of radwaste are shown below:

--- + open - 2 pumps @ 200,000 gpm/pump------

T1 'V Radwaste ----- > ---- > Discharge T Conduit

--- 4 closed - 50,000 gpm or helper

ODCM Revision 003.7 Page 72 of 208 6.1 LIQUID RELEASES 6.1.1 Pre-release Analysis/ECL - Sum of the Ratios Prior to a batch 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 effluent concentration limit (ECL) fractions (Mi).

Ci Mi = (6.1)

ECLi where:

Mi = ECL fraction of radionuclide i.

Ci = concentration of radionuclide i in the radwaste tank, pCi/ml.

ECLi = ECL 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 = Z Mi (6.2) i where:

R = the sum of the ratios.

Mi = ECL fraction from equation 6.1.

6.1.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be 5 10 due to a liquid release. The following relationship will assure this criterion is met:

R[f/(f+F)]

10 (6.3) 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 ECL limit is not exceeded.

ODCM Revision 0017 Page 73 of 208 6.1.3 Post-release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Control 1.2.1.1 were not exceeded.

A composite list of concentrations (Ci) by isotope, will be used with actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equations 6.1, 6.2 and 6.3 to demonstrate compliance with the limits in Control 1.2.1.1. This data and setpoints will be recorded in auditable records by plant personnel.

ODCM Revision 002.7 Page 74 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 Docuuent.

6.2.1 Release Point Monitor Allowable Values There is only one point through which routine releases are made from BFN, the Liquid Radwaste System. All releases from the Liquid Radwaste System are in a batch mode, and the monitor is looking at an undiluted waste stream as it comes out of a tank. The purpose of the monitor setpoint for these batch releases is to identify any release that would have the potential to exceed ten times the 10 CFR 20 limits after dilution.

Allowable values used to determine the setpoints are calculated as described here.

For each release, a setpoint is calculated based on the monitor response to the activity in the release stream if the release were large enough to exceed ten times the 10 CFR 20 limits after dilution. This maximum calculated setpoint, Smax' is calculated using Equation 6.4 below. A comparison is made between this calculated setpoint and the default setpoint (see Section 6.2.2) to determine which is used. The actual monitor setpoint for the release is set equal to the default setpoint, or to the maximum calculated setpoint, whichever is less.

Calculated Maximum Monitor Setpoint 10* SF (Fw + (FD

Fdil))

Smax = (ER - B) + B (6.4)

Fw R where:

SF = safety factor for the monitor.

Fw = flow of waste stream, gpm.

Fdil = flow of the dilution stream, gpm.

FD = fraction of dilution flow allocated to this release point. For BFN this fraction is equal to one.

B = background, cpm.

R = sum of the ratios for the release point as calculated in Section 6.1.1.

ER = expected monitor response, cpm,

= B + Z Ei

Ci (6.5) i where:

B = monitor background, cpm.

Ei = monitor efficiency for nuclide i, cpm per pCi/cc.

Ci = tank concentration of nuclide i, pCi/cc.

ODCM Revision 0017 Page 75 of 208 6.2.2 Default Allowable Values 6.2.2.1 Radwaste Discharge Monitor The default 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 default 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 90% or less of the trip allowable value.

The default maximum activity concentration1 of liquid radwaste that can be discharged can be calculated as:

A= F + f f

v WFi i

ECLi where:

A = default maximum batch activity concentration, pCi/ml.

ECLi = ECL of radionuclide i as specified in Control 1.2.1.1, pCi/ml.

WFi = weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

F = dilution water flow rate, gpm.

f = maximum discharge flow rate, gpm.

1 The default maximum activity concentration is based on a selected isDtopic mixture so that an allowable value can be calculated. The selected isotopic mixture will be documented in O-TI-45. If ten times the actual batch ECL fraction is less restrictive than ten times the ECL fraction for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maximum activity concentration; this is the case for which the maximum alLowable value defined in Section 6.2.1 would be indicated.

ODCM Revision 0017 Page 76 of 208 The default monitor isolation allowable value, in cps, for releases is calculated using the following equation:

Monitor Isolation Allowable Value = (A

I WFi*Ei) + B i

where:

A = maximum batch activity concentration as calculated above, pCi/ml WFi:= weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i Ei efficiency of the monitor for nuclide i, cps/pCi/ml B monitor background, cps The calculation of these allowable values are documented further in 0-TI-45, including the numerical values for each of the parameters described above.

6.2.2.2 Raw Cooling Water and Residual Heat Removal Service Water Monitors The .allowable value for the Raw Cooling Water (RCW) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RM-90-132 and RM-90-133,134 respectively), shown in Figure 6.1, will be established using the methodology below. The alarm/trip allowable values will be set such that Equation 6.3 is satisfied. The allowable values for these monitors, which will alarm in the control room, are based on ten times the 10 CFR 20 Appendix B concentration limits. These allowable values are also based on a selected isotopic mixture.

The monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation:

Monitor Allowable Values 5 (A

Z WFi*Ei) + B i

where:

A = total activity concentration, pCi/ml.

WFi = weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

Ei = efficiency of the monitor for nuclide i, cpm/pCi/ml.

B = monitor background, cpm.

The calculation of these allowable values are documented further in 0-TI*-45, including the numerical values for each of the parameters described above.

ODCM Revision 0017 Page 77 of 208 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are drinking water ingestion, fish consumption and shoreline recreation. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Wheeler Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e., shoreline recreation), the total body dose will be added to the internal organ dose for all age groups.

6.3.1 Dose Calculation The general equation for the dose calculation for each organ j is:

Dj = EAij T Ci D (6.6) i where:

Aij = the total dose factor to the total body or any organ j for nuclide i, mrem/h per iCi/ml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline recreation, as defined in Section 6.7.

T = the length of time period over which the concentrations and the flows are averaged for the liquid release, h.

Ci = the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, PCi/ml.

D = the near field average dilution factor for ci during any effluent release.

= FLOWW_

0.30 RF where:

FLOWW = maximum undiluted liquid waste flow during the release, cfs.

0.30 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.

RF = default riverflow, cfs. For each release, this value is set to 44,000 cfs (the average monthly riverflow for the period of 1986-1992).

From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group.

ODCM Revision 0017 Page 78 of 208 6.3.2 Cumulative Doses Quarterly and annual sums of all doses are determined for each release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of all the doses for each release in the quarter or year respectively.

6.3.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 prior to and after each liquid release.

ODCM Revision 0017 Page 79 of 208 6.4 LIQUID RADWASTE TREATMENT SYSTEM The Liquid Radwaste Treatment System (LRTS) shall be maintained and operated to keep releases ALARA. A flow diagram for the LRTS is given in Figure 6.2.

ODCM Revision 0017 Page 80 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.

ODCM Revision 0017 Page 81 of 208 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

The average dilution factor, D, used for these calculations is:

1 D =_ _ (for receptors upstream (6.13a)

RF

0.30 of Wheeler Dam) and 1

D = _ (for receptors downstream (6.13b)

RF of Wheeler Dam) where:

RF = the average actual riverflow for the location at which the dose is being determined, cfs.

0.30 = the fraction of the riverflow available for dilution in the near field, dimensionless.

6.6.:L Water Ingestion Wate: ingestion doses are calculated for each Public Water Supply (PWS) identified within a 50 mile radius downstream of BFN (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:

D:j = 106 (9.8E-09) AWij Qi D exp(-8.64E+04 Xi td) (6.14) where:

106 = conversion factor, pCi/Ci.

9.8E*-09 = conversion factor, cfs per ml/h.

AWij = Dose factor for water ingestion for nuclide i, age group j, mrem/h per pCi/ml, as calculated in Section 6.7.1.

Qi = Quantity of nuclide i released during the quarter, Ci.

D = dilution factor, as described above, cfs-1 .

Xi = radiological decay constant of nuclide i, s-1 (Table 6.3).

td = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) to account for the time of processing at the water supply (per Regulatory Guide 1.109), d.

8.64LP+04 = conversion factor, s/d.

ODCM Revision 0017 Page 82 of 208 6.6.2 Fish Ingestion 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:

Dj = 106 (9.8E-09) 0.25 AFij Qi D exp(-8.64E+04 Xi td) (6.15) where:

106 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/h.

0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

AFij = Dose factor for fish ingestion for nuclide i, age group j, mrem/f h per pCi/ml, as calculated in ODCM Section 6.7.2.

Qi = Quantity of nuclide i released during the quarter, Ci.

D = dilution factor, as described above, cfs-1 .

xi = radiological decay constant of nuclide i, s-1 (Table 6.3).

td = 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), d.

8.643+04 = conversion factor, s/d.

6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radias 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:

Dorg = 106 (9.8E-09) rf ARij Qi D exp(-8.64E+04 Xi td) (6.16) where:

106 = conversion factor, uCi/Ci.

9.8E-09 = conversion factor, cfs per ml/h.

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.

ODCM Revision 0017 Page 83 of 208 ARij = Dose factor for shoreline recreation for nuclide i, age group j, mrem/h per pCi/ml, as calculated in ODCM Section 6.7.3.

Qi = Quantity of nuclide i released during the quarter, Ci.

D = dilution factor, as described above, cfs 1.

Xi = radiological decay constant of nuclide i, ;- 1 (Table 6.3).

td = decay time for recreation, equal to the travel time from the plant to the center of the reach, d.

8.64E+04 = conversion factor, s/d.

6.6.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

ODCM Revision 0017 Page 84 of 208 6.6.5 Population 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 person-rem for a given PWS is:

5 4 POPWTRj = 10-3 z POPm X POPa ATMWa TWDOSamj (6.17) m=l a=l where:

POPWTRj = water ingestion population dose to organ j, person-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 5 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 TWDOSamj = total individual water ingestion dose to organ j 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 person-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

3 3 453.6 HVST APRr POPFj = 10-3 10-3 y YE POPa TFDOSarj (6.18) r=l a=l FISHa POPa

ODCM Revision 0017 Page 85 of 208 where:

POPFj = total fish ingestion population dose to organ j, person-rem.

HVST = fish harvest for the Tennessee River, 8.32 lbs/acre/y.

APRr = size of reach r, acres (Table 6.1).

TFDO 3 arj = total fish ingestion dose to organ j for reach r, for the age group a, as described in Section 6.6.2, mrem. Calculated with td in that equation equal to travel time plus 8 days.

POPa = fraction of population in each age group a, as given above.

FISHa = amount of fish ingested by each age group a, kg/y per person.

The average fish ingestion rates (R.G. 1.109 Table E-4) are:

Adult = 6.9 Child = 2.2 Teen = 5.2 453.6 = conversion factor, g/lb.

10-3 = conversion factor, rem/mrem.

10-3 = conversion factor, kg/g.

For shoreline recreation, the general equation used for calculating the population doses, POPR, in person-rem is:

3 PDPRj = REQF1A SHVISr HRSVISr TSHDOSrj (6.19) l03 r=l where:

POPRj = total recreation population dose for all reaches to organ j, person-rem.

REQFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3, year per quarter.

SHVISr = shoreline visits per year at each reach r, (Table 6.1).

HRSVISr = length of shoreline recreation visit at reach r, 5 h.

103 = conversion factor, mrem/rem.

TSHD'DSrj = total shoreline dose rate for organ j, in reach r, mrem-quarter/h per quarter.

Qi exp(-Xitr) Kc M DFGit 1012 24 103 Dr 2.22E11 Xi where:

Qi = total activity released during the quarter, Ci.

Xi = decay constant for nuclide i, d-1.

tr = travel time from the plant to reach r, d.

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

M = mass density of sediment, kg/m 2, (Table 6.3).

DFGit = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/h per pCi/m 2 .

1012 = conversion factor, pCi/Ci.

24 = conversion factor, h/d.

103 = conversion factor, ml/L.

Dr = dilution factor for reach r, cfs-1 . Calculated as described in Equation 6.13.

2.22E11 = conversion factor, ml/quarter per cfs.

ODCM Revision 0017 Page 86 of 208 6.7 LIQUID DOSE FACTOR EQUATIONS 6.7.1 Water Ingestion Dose Factors DFLiaj Uwa 106 103 Awij = 8760 where:

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

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

106 = conversion factor, pCi/pCi.

103 = conversion factor, ml/L.

8760 = conversion factor, h/y.

6.7.2 Fish Ingestion Dose Factors AFij = DFLiaj Ufa Bi 106 103 8760 where:

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

Ufa = fish consumption rate for age group a, kg/y, (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, ml/L.

8760 = conversion factor, h/y.

6.7.3 Shoreline Recreation Dose Factors DFGij Kc M W 103 106 U ARij = _ _ _ __ _ _ _ __ _ _ _ (-exp(-Xi tbl)J 8760

3600 Xi where:

DFGij = dose conversion factor for standing on contaminated ground for nuclide i and organ j (total body and skin), mrem/h per pCi/m 2 ,

(Table 6.6).

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

M = mass density of sediment, kg/m 2, (Table 6.3).

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

103 = conversion factor, ml/L.

106 = conversion factor, pCi/pCi.

3600 = conversion factor, s/h.

Xi = decay constant for nuclide i, s-1, (Table 6.2).

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

U = usage factor, 500 h/y.

8760 = conversion factor, h/y.

ODCM Revision 0017 Page 87 of 208 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Beginning Ending Size Recreation Name TRM* TRM (acres) visits/y Wheeler Lake 294.0 274.9 26076 1,408,600 below BFN Wilson Lake 274.9 259.4 15930 3,816,800 Pickwick Lake 259.4 206.7 15048 705, 500 Public Water Supplies Within 50 Mile Radius Downstream of BFN Name TRM Population West Morgan - East Lawrence, AL 286.5 25, 000 Florence, AL 259.8 36, 000 Muscle Shoals, AL 259.6 10,740 Sheffield, AL 254.3 13, 065 Cherokee, AL 239.3 3, 400

TRM = Tennessee River Mile. Distances in this and other tables are consistent wi:h memo L78 961104 800.

ODCM Revision 0017 Page 88 of 208 Table 6.2 (1 of 3)

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

H-3 6.46E+06 1.79E-09 4.80E+OO l.OOE-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+OO 1.20E-02 1.OOE-O1 3.1OE-02 Na-24 9.OOE+02 1.28E-05 5.2OE-02 4.OOE-02 4.OOE-02 3.OOE-02 P-32 2.06E+04 5.61E-07 l.1OE+OO 2.50E-02 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.OOE-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.0OE-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 l.OOE-03 l.OOE-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.OOE-03 1.OOE-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.OOE-03 1.OOE-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 l.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7. 65E-05 l.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.OOE-O1 3.90E-02 3.90E-02 3.OOE-02 Zn-69m 8.26E+02 1.4OE-05 4.OOE-Ol 3.90E-02 3.90E-02 3.OOE-02 Zn-69 5.56E+01 2.08E-04 4.OOE-Ol 3.90E-02 3.90E-02 3.OOE-02 Br-82 2.12E+03 5.45E-06 7. 60E-O1 5.OOE-02 5.OOE-02 2. 60E-02 Br-83 1.43E+02 8.08E-05 7. 60E-01 5.OOE-02 5.OOE-02 2.60E-02 Br-84 3.18E+01 3.63E-04 7. 60E-01 5.OOE-02 5.OOE-02 2.60E-02 Br-85 2.87E+0O 4.02E-03 7. 60E-01 5.OOE-02 5.OOE-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-O1 3.OOE-02 3.OOE-02 3.1OE-02 Rb-83 1.78E+01 6.49E-04 1.30E-O1 3.OOE-02 3.OOE-02 3.lOE-02 Rb-89 1.54E+0l 7.50E-04 1.30E-Ol 3.OOE-02 3.OOE-02 3.1OE-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.OOE-04 Sr-93 1.50E+07 7.70E-10 1.7OE-02 1.40E-03 1.40E-02 6.OOE-04 Sr-91 5.70E+02 2.03E-05 1.7OE-02 1.40E-03 1.40E-02 6.OOE-04 Sr-92 1.63E+02 7.09E-05 1.7OE-02 1.40E-03 1.40E-02 6.OOE-04 Y-90 3.85E+03 3.OOE-06 2. 60E-03 1. OOE-05 1.OOE-05 4. 60E-03 Y-91lm 4.97E+01 2.32E-04 2.60E-03 1.OOE-05 1.OOE-05 4. 60E-03 Y-91 8.43E+04 1.37E-07 2. 60E-03 1.OOE-05 1.OOE-05 4. 60E-03 Y-92 2.12E+02 5.45E-05 2. 60E-03 l.OOE-05 1.OOE-05 4. 60E-03 Y-93 6.06E+02 l.91E-05 2. 60E-03 1.OOE-05 1.OOE-05 4. 60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.OOE-06 5.OOE-06 3.40E-02 Zr-97 1.O1E+03 1.14E-05 1.7OE-04 5.OOE-06 5.OOE-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 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-93 3.96E+03 2.92E-06 1.20E-Ol 7.50E-03 7.50E-03 1.lOE-03 Tc-99m 3.61E+02 3.20E-05 2.50E-O1 2.50E-02 2.50E-02 4.OOE-01 Tc-101 1.42E+01 8.13E-04 2.50E-O1 2.50E-02 2.50E-02 4.OOE-01 Ru-133 5.67E+04 2.04E-07 5.OOE-02 1.OOE-06 1.OOE-06 4.OOE-01 Ru-105 2.66E+02 4.34E-05 5.OOE-02 l.OOE-06 1.OOE-06 4.OOE-O1 Ru-106 5.30E+05 2.18E-08 5.OOE-02 1.OOE-06 1.OOE-06 4.OOE-01 Ag-ll0m 3.60E+05 3.21E-08 1.50E-O1 5.OOE-02 5.OOE-02 1.70E-02

ODCM Revision 0017 Page 89 of 208 Table 6.2 (2 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Nuclide Half-Life x Biv Fmi Fmi Ffi (minutes) (Ws) (cow) (goat) (beef)

Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.OOE-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.OOE-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.OOE-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.OOE-03 1.OOE-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.OOE-03 1.OOE-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.OOE-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.OOE-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.OOE-03 1.OOE-03 7.70E-02 I-130 7.42E+02 1.56E-05 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9.96E-07 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.OE-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.OOE-02 8.OOE-03 3.OOE-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.OOE-02 8.OOE-03 3.OOE-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.OOE-02 8.OOE-03 3.OOE-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.OOE-02 8.OOE-03 3.OOE-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.OOE-03 4.OOE-04 4.OOE-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.OOE-03 4.OOE-04 4.OOE-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.OOE-03 4.OOE-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.OOE-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.OOE-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.OOE-06 5.OOE-06 2.OOE-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.OOE-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.OOE-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.OOE-04 1.OOE-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.OOE-06 5.OOE-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.OOE-06 5.OOE-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.OOE-06 5.OOE-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.OOE-04 5.OOE-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.OOE-06 5.OOE-06 2.OOE-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A

ODCM Revision 0017 Page 90 of 208 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Nuclide Half-Life X Biv Fmi Fmi Ffi (minutes) (u/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 N/A N/A Xe-135 5.47E+02 2.11E-05 N/A 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+01 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.

Zow-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' transfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.

ODCM Revision 0017 Page 91 of 208 Table 6.3 (1 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference BRa (infant) 1400 m 3 /y ICRP 23 BRa (child) 5500 m3/y ICRP 23 BRa (teen) 8000 m 3 /y ICRP 23 3

BRa (adult) 8100 m /y ICRP 23 fg 1 TVA Assumption fL 1 R. G. 1.109 (Table E-15) fp 1 TVA Assumption fs 0 TVA Assumption H 9 g/m 3 TVA Value Kc 0.072 L/kg-h R. G. 1.109 (Section 2.C.)

M 40 kg/m 2 R. G. 1.109 (Section 2.C.)

P 240 kg/m 2 R. G. 1.109 (Table E-15)

Qf (cow) 64 kg/d NUREG/CR-1004 (Sect. 3.4)

Qf (goat) 08 kg/d NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 S R. G. 1.109 (Table E-15)

(15 y) tbl 4.73E+08 R. G. 1.109 (Table E-15)

(15 y) tcb 7.78E+06 SQN FSAR Section 11.3.9.1 (90 d) tcsf 1.56E+07 SQN FSAR Section 11.3.9.1.

(180 d) S te 5.18E+06 R. G. 1.109 (Table E-15)

(60 d) 5 tep 2.59E+06 R. G. 1.109 (Table E-15)

(30 d) 5 tesf 7. 78E+06 R. G. 1.109 (Table E-15)

(90 d) 5 tfm 8.64E+04 SQN FSAR Section 11.3.9.1 (1 d) the 8. 64E+04 NUREG/CR-1004, Table 3.40 (1 d) S ts 1.12E+06 NUREG/CR-1004, Table 3.40 (13 d) tsv 2.38E+07 SQN FSAR Section 11.3.9.:L (275 d)

UM (infant) 0 kg/y R. G. 1.109 (Table E-5)

UM (child) 41 kg/y R. G. 1.109 (Table E-5)

UM (teen) 65 kg/y R. G. 1.109 (Table E-5)

UM (adult) 110 kg/y R. G. 1.109 (Table E-5)

Up (infant) 330 L/y R. G. 1.109 (Table E-5)

Up (child) 330 L/y R. G. 1.109 (Table E-5)

Up (teen) 400 L/y R. G. 1.109 (Table E-5)

Up (adult) 310 L/y R. G. 1.109 (Table E-5)

ODCM Revision 0017 Page 92 of 208 Table 6.3 (2 of 2)

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

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

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

Uf (aIult) 21 kg/y R. G. 1.109 (Table E-5)

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

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

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

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

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

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

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

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

Uw(infant) 330 L/y R. G. 1.109 (Table E-5)

Uw(child) 510 L/y R. G. 1.109 (Table E-5)

Uw(teen) 510 L/y R. G. 1.109 (Table E-5)

Uw(adult) 730 L/y R. G. 1.109 (Table E-5) w 0.3 none R. G. 1.109 (Table A-2)

Yv 1.85 kg/m 2 NUREG/CR-1004 (Table 3.4)

Yp 1.18 kg/m 2 NUREG/CR-1004 (Table 3.3)

Ys 0.64 kg/m 2 NUREG/CR-1004 (Table 3.3) 0.57 kg/m 2 NUREG/CR-1004 (Table 3.4)

Ysv (value selected is for non-leafy vegetables)

Xwr(:Lodines) 7.71E-07 S-1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

Xw (particulates) 5.21E-07 S-1 NUREG/CR-1004 (Table 3.10)

(10.4 d half-life)

ODCM Revision 003.7 Page 93 of 208 Table 6.4 (1 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT Nuclide bone liver t body thyroid kidney lung gi-lli.

H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E--07 C-14 2.84E-06 5. 68E-07 5. 68E-07 5. 68E-07 5.68E-07 5.68E-07 5.68E-*07 Na-2 4 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.OOE+00 0.OOE+00 0.OOE+00 2.17E-05 Cr-51 0.OOE+00 0.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-*07 Mn-54 0.OOE+00 4.57E-06 8.72E-07 0.OOE+00 1.36E-06 0.OOE+00 1.40E-05 Mn-56 0.OOE+00 1.15E-07 2.04E-08 0.OOE+00 1.46E-07 0.OOE+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.OOE+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.OOE+00 0.OOE+00 2.85E-06 3.40E-*05 Co-57 0.00E+00 1.75E-07 2.91E-07 0.OOE+00 0.OOE+00 0.00E+00 4.44E-06 Co-53 0.OOE+00 7.45E-07 1.67E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.51E-05 Co-6D 0.OOE+00 2.14E-06 4.72E-06 0.OOE+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.OOE+00 0.OOE+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.74E-06 Cu-64 0.OOE+00 8.33E-08 3.91E-08 0.OOE+00 2.1OE-07 0.OOE+00 7.10E-*06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.OOE+00 1.03E-05 0.OOE+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 0.OOE+00 1.28E-08 0.OOE+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.OOE+00 2.47E-07 0.00E+00 2.49E-*05 Br-82 0.OOE+00 0.OOE+00 2.26E-06 0.00E+00 0.OOE+00 0.OOE+00 2.59E-06 Br-83 0.OOE+00 0.OOE+00 4.02E-08 0.OOE+00 0.OOE+00 0.OOE+00 5.79E-*08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.OOE+00 0.OOE+00 4.09E-13 Br-85 0.OOE+00 0.00E+00 2.14E-09 0.OOE+00 0.00E+00 0.OOE+00 0. OOE+00 Rb-86 0.OOE+00 2.11E-05 9.83E-06 0.OOE+00 0.OOE+00 0.OOE+00 4.16E-*06 Rb-88 0.OOE+00 6.05E-08 3.21E-08 0.OOE+00 0.OOE+00 0.OOE+00 8.36E-*19 Rb-8 9 0.OOE+00 4.01E-08 2.82E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.33E-*21 Sr-8 9 3.08E-04 0.00E+00 8.84E-06 0.OOE+00 0.OOE+00 0.OOE+00 4. 94E--05 Sr-9D 7.58E-03 0.OOE+00 1.86E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.19E-04 Sr-91 5.67E-06 0.OOE+00 2.29E-07 0.00E+00 0.OOE+00 0.OOE+00 2.70E-05 Sr-9.2 2.15E-06 0.OOE+00 9.30E-08 0.OOE+00 0.OOE+00 0.OOE+00 4.26E-*05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.OOE+00 0.OOE+00 1.02E-04 Y-91ln 9.09E-11 0.OOE+00 3.52E-12 0.00E+00 0.OOE+00 0.OOE+00 2. 67E-.10 Y-91 1.4lE-07 0.OOE+00 3.77E-09 0.00E+00 0.OOE+00 0.OOE+00 7.76E--05 Y-92 8.45E-10 0.OOE+00 2.47E-l1 0.OOE+00 0.OOE+00 0.OOE+00 1.48E-05 Y-93 2. 68E-09 0.00E+00 7.40E-1l 0.00E+00 0.OOE+00 0.OOE+00 8.50E--05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.OOE+00 3.09E--05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E--04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.OOE+00 3.42E-09 0.OOE+00 2.1OE--05 Nb-97 5.22E-11 1.32E-l1 4.82E-12 0.OOE+00 1.54E-11 0.OOE+00 4.87E--08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.OOE+00 9.99E--06 Tc-99m 2.47E-10 6. 98E-10 8.89E-09 0.OOE+00 1.06E-08 3.42E-10 4.13E--07 Tc-1D1 2.54E-10 3.66E-10 3.59E-09 0.OOE+00 6.59E-09 1.87E-10 1.10E--21 Ru-13 1.85E-07 0.00E+00 7.97E-08 0.OOE+00 7.06E-07 0.OOE+00 2.16E*-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.OOE+00 l.99E-07 0.OOE+00 9.42E--06 Ru-16 2.75E-06 0.OOE+00 3.48E-07 0.00E+00 5.31E-06 0.OOE+00 1.78E-*04 Ag-ll0m 1. 60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.OOE+00 6.04E--05

ODCM Revision 0017 Page 94 of 208 Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 2.8OE-06 5.29E-08 l.1lE-06 6.79E-09 0.OOE-00 2.18E-06 7. 95E-*05 Sb-125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0.OOE-00 1.38E-06 1.97E--05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.OOE+00 1.07E--05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.OOE+00 2.27E--05 Te-127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.OOE+00 8. 68E--06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.OOE+00 5.79E--05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.OOE+00 2.37E--08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.OOE+00 8.40E--05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8. 63E-08 0.OOE+00 2.79E--09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.OOE+00 7.71E--05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.OOE+00 1.92E--06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.OOE+00 1.57E--06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8. 65E-07 0.OOE+00 1.02E--07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4. 31E-06 0.OOE+00 2.22E--06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.OOE+00 2.51E--10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.OOE+00 1.31E--06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.OOE+00 4.79E-05 1.59E-05 2.59E--06 Cs-136 6.51E-06 2. 57E-05 1.85E-05 0.OOE+00 1.43E-05 1.96E-06 2.92E--06 Cs-137 7. 97E-05 1.09E-04 7.14E-05 0.OOE+00 3.70E-05 1.23E-05 2.11E--06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.OOE+00 8.01E-08 7.91E-09 4. 65E--13 Ba-139 9.70E-08 6.91E-l1 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E--07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8. 67E-09 1.46E-08 4.18E--05 Ba-141 4.71E-08 3. 56E-il 1.59E-09 0.OOE+00 3.31E-11 2.02E-11 2.22E--17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.OOE+00 1.85E-11 1.24E-11 3.OOE--26 La-140 2.50E-09 1.26E-09 3.33E-10 0.OOE+00 0.OOE+00 0.OOE+00 9.25E--05 La-142 1.28E-10 5.82E-1l 1.45E-l1 0.00E+00 0.OOE+00 0.OOE+00 4.25E--07 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.OOE+00 2.94E-09 0.OOE+00 2.42E--05 Ce-143 1. 65E-09 1.22E-06 1.35E-10 0.OOE+00 5.37E-10 0.OOE+00 4.56E--05 Ce-144 4.88E-07 2.04E-07 2. 62E-08 0.OOE+00 1. 21E-07 0. OOE+00 1.65E--04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0. OOE+00 2.13E-09 0.OOE+00 4.03E*-05 Pr-144 3.01E-1l 1.25E-11 1.53E-12 0. O0E+00 7.05E-12 0.OOE+00 4.33E*-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.OOE+00 4.25E-09 0.OOE+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.82E-05 Np-239 l.19E-09 1.17E-10 6.45E-ll 0.OOE+00 3.65E-10 0.OOE+00 2.40E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake,, November, 1977, Table 4.

All others:

Regulatory Guide 1.109, Table E-ll.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 95 of 208 Table 6.4 (3 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN Nuclide bone liver t body thyroid kidney lung gi-lli.

H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8. 12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.32E-05 Cr-51 0.00E+00 0.OOE+00 3. 60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-*07 Mn-54 0.OOE+00 5.90E-06 1.17E-06 0.OOE+00 1.76E-06 0.OOE+00 1.21E--05 Mn-56 0.OOE+00 1.58E-07 2.81E-08 0.OOE+00 2.OOE-07 0.OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.OOE+00 0.OOE+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.OOE+00 4.32E-06 3.24E-05 Co-57 0.OOE+00 2.38E-07 3.99E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.44E-06 Co-58 0.OOE+00 9.72E-07 2.24E-06 0.OOE+00 0.OOE+00 0.00E+00 1.34E--05 Co-60 0.OOE+00 2.81E-06 6.33E-06 0.OOE+00 O.OOE+00 0.OOE+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.OOE-06 0.OOE+00 0.OOE+00 0.OOE+00 l.99E-*06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.OOE+00 0.OOE+00 0.OOE+00 5.19E--06 Cu-64 0.0OE+00 1.15E-07 5.41E-08 0.OOE+00 2. 91E-07 0.OOE+00 8. 92E--06 Zn-65 5. 76E-06 2.OOE-05 9.33E-06 0.OOE+00 1.28E-05 0.OOE+00 8.47E--06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.OOE+00 1.83E-08 0.OOE+00 5.16E--08 Zn-69m 2.40E-07 5. 66E-07 5.19E-08 0.OOE+00 3.44E-07 0.OOE+00 3.11E--05 Br-82 0.OOE+00 0.OOE+00 3.04E-06 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE--00 Br-83 0.OOE+00 0.OOE+00 5.74E-08 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Br-84 0.OOE+00 0.OOE+00 7.22E-08 0.OOE+00 0.OOE+00 0.00E+00 0.00E'00 Br-85 0.00E+00 0.OOE+00 3.05E-09 0.OOE+00 0.OOE+00 0.00E+00 0. 00E-00 Rb-86 0.OOE+00 2.98E-05 1.40E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.41E--06 Rb-88 0.OOE+00 8.52E-08 4.54E-08 0.OOE+00 0.OOE+00 0.OOE+00 7.30E--15 Rb-89 0.OOE+00 5.50E-08 3.89E-08 0.OOE+00 0.OOE+00 0.OOE+00 8.43E--17 Sr-89 4.40E-04 0.OOE+00 1.26E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.24E--05 Sr-90 8.30E-03 0.OOE+00 2.05E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.33E--04 Sr-91 8.07E-06 0.0OE+00 3.21E-07 0.OOE+00 0.OOE+00 0.OOE+00 3.66E--05 Sr-92 3.05E-06 0.OOE+00 1. 30E-07 0. OOE+00 0. OOE+00 0. OOE+00 7.77E--0S Y-90 1.37E-08 0.00E+00 3.69E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.13E--04 Y-91m 1.29E-10 0.OOE+00 4.93E-12 0.OOE+00 0.OOE+00 0.OOE+00 6.09E--09 Y-91 2.OlE-07 0.OOE+00 5.39E-09 0.OOE+00 0.OOE+00 0.OOE+00 8.24E-05 Y- 92 1.21E-09 0.OOE+00 3.50E-ll 0.OOE+00 0.OOE+00 0.OOE+00 3.32E-05 Y-93 3.83E-09 0.OOE+00 1.05E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.17E-04 Zr-95 4. 12E-08 1.30E-08 8.94E-09 0.OOE+00 l.91E-08 0.00E+00 3.OOE-05 Zr-97 2.37E-09 4. 69E-10 2.16E-10 0.00E+00 7.11E-10 0.OOE+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.OOE+00 4. 42E-09 0.OOE+00 1.95E*-05 Nb-97 7. 37E-ll 1.83E-l1 6.68E-12 0.OOE+00 2. 14E-ll 0.OOE+00 4.37E-07 Mo-99 0.OOE+00 6.03E-06 1.15E-06 0.OOE+00 1.38E-05 0.OOE+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.OOE+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.OOE+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.OOE+00 1.09E-07 0.OOE+00 8. 99E-07 0.OOE+00 2.13E*-05 Ru-105 2.18E-08 0.OOE+00 8.46E-09 0.OOE+00 2.75E-07 0.00E+00 1.76E--05 Ru-106 3.92E-06 0.OOE+00 4.94E-07 0.OOE+00 7. 56E-06 0.OOE+00 1.88E--04 Ag-llOm 2.05E-07 1. 94E-07 1.18E-07 0.OOE+00 3.70E-07 0.OOE+00 5.45E*-05

ODCM Revision 0017 Page 96 of 208 Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0.OOE-00 3.38E-06 7.80E-*05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.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 0.OOE+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.OOE+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.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 0.OOE+00 2.45E-*07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.OOE+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.OOE+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.OOE+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.OOE+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.OOE+00 1.62E-*06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.OOE+00 3.18E-*07 1-13.3 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.OOE+00 2.58E-*06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.OOE+00 5.10E-09 I-13.5 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.OOE+00 1.74E-*06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.OOE+00 1.84E-05 2.90E-06 2.72E-*06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.OOE+00 1.10E-07 1.28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-11 4.05E-09 0.OOE+00 9.22E-11 6.74E-11 1.24E-*06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.OOE+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.OOE+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.OOE+00 2.53E-1 l.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 0.OOE+00 0.OOE+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+00 0.OOE+00 O.OOE+00 2.42E-06 Ce-ill 1.33E-08 8.88E-09 1.02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 l.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 0.OOE+00 1.72E-07 O.OOE+O0 1.75E-04 Pr-113 1.31E-08 5.23E-09 6.52E-10 0.OOE+00 3.04E-09 0.OOE+00 4.31E-*05 Pr-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+00 1.01E-11 O.OOE+00 4.74E-14 Nd-1417 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 l.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 0.OOE+00 5.21E-10 O.OOE+00 2.67E-05 Refe::ences:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One YeaLr Chronic Intake,, November, 1977, Table 3.

All others:

Regulatory Guide 1.109, Table E-12.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 001.7 Page 97 of 208 Table 6.4 (5 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD Nuclide bone liver t body thyroid kidney lung gi-lli.

H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E--07 C-i4 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-*06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.8OE-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.28E-05 Cr-51 0.OOE+00 0.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-*07 Mn-54 0.OOE+00 1.07E-05 2.85E-06 0.OOE+00 3.OOE-06 0.OOE+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.OOE+00 4.04E-07 0.OOE+00 4.84E-05 Fe-55 1.15E-05 6.IOE-06 1.89E-06 0.OOE+00 0.OOE+00 3.45E-06 1.13E-*06 Fe-59 1.65E-05 2. 67E-05 1.33E-05 0.OOE+00 0.OOE+00 7.74E-06 2.78E--05 Co-57 0.OOE+00 4. 93E-07 9.98E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.04E-06 Co-58 0.OOE+00 1.80E-06 5.51E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.05E-05 Co-6) 0.OOE+00 5.29E-06 1.56E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.93E--05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.OOE+00 0.OOE+00 0.OOE+00 1. 94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.OOE+00 0.OOE+00 0.OOE+00 2.56E--05 Cu-64 0.OOE+00 2.45E-07 1.48E-07 0.OOE+00 5.92E-07 0.OOE+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.OOE+00 2.30E-05 0.OOE+00 6.41E-06 Zn-69 4. 38E-08 6.33E-08 5.85E-09 0.OOE+00 3.84E-08 0.OOE+00 3.99E-06 Zn-63m 7.10E-07 1.2lE-06 1.43E-07 0.OOE+00 7. 03E-07 0.OOE+00 3.94E-05 Br-82 0.OOE+00 0.OOE+00 7.55E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-83 0.00E+00 0.OOE+00 1.71E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-00 Br-8 4 0.OOE+00 0.OOE+00 1. 98E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-00 Br-8 5 0.OOE+00 0.OOE+00 9.12E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-8 S 0.00E+00 6.70E-05 4.12E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.31E-06 Rb-83 0.OOE+00 1.90E-07 1.32E-07 0.OOE+00 0.OOE+00 0.OOE+00 9.32E-09 Rb-8 3 0.OOE+00 1.17E-07 1.04E-07 0.OOE+00 0.OOE+00 0.OOE+00 1.02E-09 Sr-8 3 1.32E-03 0.OOE+00 3.77E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.11E-05 Sr-93 1.70E-02 0.00E+00 4.31E-03 0.OOE+00 O.OOE+00 0.OOE+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.OOE+00 0.OOE+00 0.OOE+00 5.30E-*05 Sr-992 9.03E-06 O.OOE+00 3. 62E-07 0.OOE+O0 O.OOE+00 O.OOE+00 1.71E-04 Y-90 4.11E-08 0.OOE+00 1.10E-09 0.OOE+00 0.OOE+00 0.OOE+00 1.17E-04 Y-91mn 3.82E-10 0.OOE+00 1.39E-ll 0.OOE+00 0.OOE+00 0.OOE+00 7.48E--07 Y-91 6.02E-07 0.OOE+00 1.61E-08 0.OOE+00 0.OOE+00 0.OOE+00 8.02E--05 Y-92 3.60E-09 0.OOE+00 1.03E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.04E--04 Y-93 1.14E-08 0.OOE+00 3.13E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.70E--04 Zr-9. 1.16E-07 2.55E-08 2.27E-08 0.OOE+00 3. 65E-08 O.OOE+00 2. 66E--05 Zr-97 6. 99E-09 1.01E-09 5.96E-10 0.OOE+00 1.45E-09 0.OOE+00 1.53E-*04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.OOE+00 8.23E-09 0.OOE+00 1. 62E--05 Nb-97 2.17E-10 3.92E-11 1.83E-ii 0.OOE+00 4.35E-ll 0.OOE+00 1.21E--05 Mo-93 0.00E+00 1.33E-05 3.29E-06 0.OOE+00 2.84E-05 0.OOE+00 1.10E-05 Tc-93m 9.23E-10 1.81E-09 3.OOE-08 0.OOE+00 2.63E-08 9.19E-10 1.03E--06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.OOE+00 i.91E-08 5.92E-10 3.56E--09 Ru-103 7.31E-07 0.OOE+00 2.81E-07 0.OOE+00 1.84E-06 0.OOE+00 1.89E-05 Ru-105 6.45E-08 0.OOE+00 2.34E-08 0.OOE+00 5. 67E-07 0.OOE+00 4.21E-05 Ru-106 1.17E-05 0.OOE+00 1.46E-06 0.OOE+00 1.58E-05 0.OOE+00 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.OOE+00 6.78E-07 0.OOE+00 4.33E-*05

ODCM Revision 0017 Page 98 of 208 Table 6.4 (6 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD Nuclide bone liver t body thyroid kidney lung gi-lli.

Sb-124 l.l1E-05 1.44E-07 3.89E-06 2.45E-08 0.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.OOE+00 3.99E-06 1.71E-05 Te-1.25m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.OOE+00 0.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-1;27 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.OOE+00 5.94E-05 Te-1:29 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.OOE+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.OOE+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.OOE+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.OOE+00 1.54E-06 I-132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.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 l.19E-06 0.OOE+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.OOE+00 l.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 0.OOE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.OOE+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 0.OOE+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.OOE+00 2.37E-08 4.34E-08 4.21E-05 Ba-1i1 2.OOE-07 1.12E-10 6.51E-09 0.OOE+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.OOE+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 l.19E-09 0.OOE+00 0.OOE+00 0.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.OOE+00 0.OOE+00 0.O0E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.OOE+00 8.68E-09 0.OOE+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.OOE+00 1.59E-09 0.OOE+00 5.55E-05 Ce-124 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-08 1.18E-08 1.95E-09 O.OOE+00 6.39E-09 0.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.OOE+00 2.11E-11 0.OOE+00 8.59E--08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.OOE+00 1.24E-08 0.OOE+00 3.58E--05 W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+00 0.OOE+00 0.OOE+00 3.57E--05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 0.OOE+00 2.79E--05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake,, November, 1977, Table 2.

All others:

Regulatory Guide 1.109, Table E-13.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 99 of 208 Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT Nuclide bone liver t body thyroid kidney lung gi-lli.

H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1. 01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.7OE-03 1.OOE-04 6.59E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.30E-05 Cr-5 0.OOE+00 0.OOE+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E--07 Mn-54 0.OOE+00 1. 99E-05 4.51E-06 0.OOE+00 4.41E-06 0.OOE+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.OOE+00 7.43E-05 Fe-55 1.39E-05 8. 98E-06 2.40E-06 0.OOE+00 0.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 O.OOE+00 0.OOE+00 1.59E-05 2.57E- 05 Co-57 0.00E+00 1.15E-06 1.87E-06 O.00E+00 0.OOE+00 0.OOE+00 3.92E-06 Co-58 0.OOE+00 3.60E-06 8.98E-06 0.OOE+00 O.OOE+00 0.OOE+00 8. 97E-*06 Co-60 0.OOE+00 1.08E-05 2.55E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.95E--06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.OOE+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.OOE+00 5.33E--05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.OOE+00 6. 98E-08 0.OOE+00 1.37E--05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.OOE+00 1.24E-06 0.OOE+00 4.24E--05 Br-82 0.OOE+00 0.OOE+00 1.27E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E--00 Br-83 0.OOE+00 0.OOE+00 3.63E-07 0.00E+00 O.OOE+00 0.OOE+00 0.OOE--00 Br-84 0.OOE+00 0.OOE+00 3.82E-07 0.OOE+00 0.00E+00 0.OOE+00 0.OOE--00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE--00 Rb-86 0.OOE+00 1.70E-04 8.40E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.35E--06 Rb-88 0.OOE+00 4 . 98E-07 2.73E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.85E--07 Rb-89 0.OOE+00 2.86E-07 1.97E-07 0.OOE+00 0.OOE+00 0.OOE+00 9.74E--08 Sr-89 2.51E-03 0.OOE+00 7.20E-05 0.00E+00 0.OOE+00 0.OOE+00 5.16E--05 Sr-90 1. 85E-02 O.OOE+00 4.71E-03 0.OOE+00 0.00E+00 0.OOE+00 2.31E--04 Sr-91 5.00E-05 0.OOE+00 1.81E-06 0.OOE+00 0. OOE+00 O.OOE+00 5.92E--05 Sr-92 1.92E-05 0.OOE+00 7.13E-07 0.OOE+00 0.OOE+00 0.OOE+00 2.07E--04 Y-90 8. 69E-08 0.OOE+00 2.33E-09 0.OOE+00 0.OOE+00 0.OOE+00 1.20E-04 Y-91m 8.10E-10 0.OOE+00 2.76E-11 0.OOE+00 0.OOE+00 0.OOE+00 2.70E-06 Y-91 1.13E-06 0.OOE+00 3.01E-08 0.OOE+00 0.OOE+00 0.OOE+00 8.10E-05 Y-92 7. 65E-09 0.OOE+00 2.15E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.4 6E-04 Y-93 2.43E-08 0.OOE+00 6.62E-10 0.OOE+00 0.00E+00 0.OOE+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.OOE+00 5. 41E-08 0.OOE+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.OOE+00 2.56E-09 0.OOE+00 1. 62E-04 Nb-95 4.20E-08 1.73E-08 1.OOE-08 0.OOE+00 1.24E-08 0.OOE+00 1.46E-05 Nb-97 4. 59E-10 9.79E-11 3.53E-11 0.OOE+00 7. 65E-11 0.OOE+00 3.09E-05 Mo-99 0.OOE+00 3.40E-05 6.63E-06 0.OOE+00 5.08E-05 0.OOE+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.OOE+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2. 86E-09 2.83E-08 0.OOE+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.OOE+00 4.95E-07 0.OOE+00 3.08E-06 0.OOE+00 1.B80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.OOE+00 1.OOE-06 0.OOE+00 5.41E-05 Ru-106 2.41E-05 0.OOE+00 3.01E-06 O.OOE+00 2.85E-05 0.00E+00 1.83E-04 Ag-ll0m 9.96E-07 7.27E-07 4.81E-07 0.OOE+00 1.04E-06 0.OOE+00 3.77E-05

ODCM Revision 0027 Page 100 of 208 Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT Nuclide bone liver t body thyroid kidney lung gi-lli.

Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.OOE+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.OOE+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.OOE+00 0.OOE+00 l.1lE-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.OOE+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.OOE+00 2.10E-05 Te-129m 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.OOE+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.OOE+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.OOE+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.OOE+00 3.81E-05 I-13J 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.OOE+00 1.51E-*06 I-13.2 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.OOE+00 2.73E-*06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.O0E+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.OOE+00 1.84E-*06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.OOE+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.OOE+00 1.81E-04 7.42E-05 l.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.OOE+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.OOE+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.OOE+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.OOE+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.OOE+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-190 2.11E-08 8.32E-09 2.14E-09 0.OOE+00 0.OOE+00 0.OOE+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.OOE+00 0.OOE+00 0.OOE+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.OOE+00 1.48E-08 0.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.OOE+00 2.86E-09 0.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.OOE+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.OOE+00 1.13E-08 0.00E+00 4.29E--05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.OOE+00 3.84E-11 0.OOE+00 4.93E--06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.OOE+00 2.19E-08 0.OOE+00 3.60E--05 W-187 9.03E-07 6.28E-07 2.17E-07 0.OOE+00 0.OOE+00 0.OOE+00 3.69E--05 Np-2.39 l.l1E-08 9.93E-10 5.61E-10 0.OOE+00 1.98E-09 0.OOE+00 2.87E--05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake,, November, 1977, Table 1.

All others:

Regulatory Guide 1.109, Table E-14.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 101 of 208 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCi/kg per pCi/L)

H-3 9.OE-01 Tc-99m 1.5E+01 C-14 4.6E+03 Tc-101 1.5E+Ol Na-24 i.OE+02 Ru-103 1.OE+0O P-32 1.OE+05 Ru-105 l.OE+O1 Cr-51 2.OE+02 Ru-106 l.OE+O1 Mn-54 4.OE+02 Ag-llOm O.OE+00 Mn-56 4.OE+02 Sb-124 l.OE+00 Fe-55 1.OE+02 Sb-125 l.OE+00 Fe-59 1.0OE+02 Te-125m 4.OE+02 Co-57 5. OE+01 Te-127m 4.OE+02 Co-58 5.OE+O1 Te-127 4.OE+02 Co-60 5.OE+01 Te-129m 4.OE+02 Ni-63 1.OE+02 Te-129 4.OE+02 Ni-65 1.OE+02 Te-131m 4.OE+02 Cu-64 5.OE+Ol Te-131 4.OE+02 Zn-65 2. OE+03 Te-132 4.OE+02 Zn-69 2.OE+03 I-130 4.OE+01 Zn-69m 2.OE+03 I-131 4.OE+01 Br-82 4.2E+02 I-132 4.OE+01 Br-83 4.2E+02 I-133 4.OE+01 Br-84 4.2E+02 I-134 4.OE+01 Br-85 4.2E+02 I-135 4.OE+01 Rb-86 2.OE+03 Cs-134 1.9E+03 Rb-88 2.OE+03 Cs-136 1.9E+03 Rb-89 2.OE+03 Cs-137 1.9E+03 Sr-89 5. 6E+01 Cs-138 1.9E+03 Sr-90 5.6E+0O Ba-139 4. OE+00 Sr-91 5. 6E+01 Ba-140 4.OE+00 Sr-92 5. 6E+01 Ba-141 4.OE+00 Y-90 2.SE+01 Ba-142 4. OE+00 Y-9lm 2.5E+0i La-140 2.5E+Ol Y-91 2.5E+01 La-142 2.5E+01 Y-92 2.5E+01 Ce-141 I.OE+00 Y-93 2.5E+01 Ce-143 l.OE+00 Zr-95 3.3E+00 Ce-144 1. OE+00 Zr-97 3.3E+00 Pr-143 2.5E+01 Nb-95 3. OE+04 Pr-144 2.5E+01 Nb-97 3.OE+04 Nd-147 2.5E+01 Mo-99 1.OE+01 W-187 1.2E+03 Np-239 l.OE+O1

References:

Bioaccumulation factors for Antimony nuclides are from ORNL-4992, "A Methodology for calculating Radiation Doses from Radioactivity Released to the Environment, Marcia 1976, Table 4.12A.

Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.

All other nuclides' bioaccumulation factors are from Regulatory Guide 1.109, Table A-1.

ODCM Revision 003.7 Page 102 of 208 Table 6.6 (1 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2

(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.OOE-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70E-08 2.OOE-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.OOE-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-1l 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.OOE-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.OOE-09 1.OOE-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-l1 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.OOE-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.OOE-09 Nb-97 8.11E-09 1.OOE-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.OOE-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-llOm 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08

ODCM Revision 0017 Page 103 of 208 Table 6.6 (2 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m 2 )

Nuclide Total Body Skin Sb-125 5.48E-09 6.80E-09 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.OOE-11 1.1OE-11 Te-129m 7.70E-10 9.OOE-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.OOE-09 I-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.4OE-09 1-132 1.70E-08 2.OOE-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1. 70E-08 Cs-137 4.20E-09 4. 90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4. 90E-09 Ba-142 7.90E-09 9.OOE-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.OOE-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Exposure to Photon and Electron Radiation from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, D. C. Kocher, Health Physics Volume 38, April 1980.

All Others:

Regulatory Guide 1.109, Table E-6.

ODCM Revision 0017 Page 104 of 208 Figure 6.1 LIQUID RELEASE POINTS (1) Turbine Building Equipment (2) Reactor Building Equipment (3)Condenser

ODCM Revision 0017 Page 105 of 208 Figure 6.2 LIQUID RADWASTE SYSTEM Floor Dra ins Fk >or Floor 1- j Dr ain Floor I Drain Colk -.ctor Drain Filter A Sample O-RM-90-13 Taink Tank Thermex 4

11 Laundry Equipment Drain Drains Tank I, _ _

Waste Waste Condensate Waste Waste Collector 4 Filter *0 Demineralizer 7+ Sample Storage Tank Tanks Tanks

ODCM Revision 00:7 Page 106 of 208 SECTION 7.0 GASEOUS EFFLUENTS

ODCM Revision 00:7 Page 107 of 208 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are eleven monitored discharge points at BFN: a Reactor Building Exhaust for each unit, the Radwaste Building Exhaust, two sets of Turbine Deck Roof Fans for each unit, and the Stack. The Reactor and Radwaste Exhausts are located on the roof of the reactor building.

The Reactor Building Exhausts include exhaust from the refuel floor of the reactor buildings, exhaust from the Primary Containment Purge System, and exhaust from the turbine buildings. These discharge points are monitored by radiation monitors 1-,2-,3-RM-90-250.

The Radwaste Building Exhaust includes exhaust from the common radwaste building. This discharge point is monitored by radiation monitor RM-90-252.

There are nine roof fans on the roof of each unit's turbine building to provide building ventilation. These are generally used in the warmer month!

to control building temperature. For each unit, there are two radiation monitors. One of these monitors the exhaust through four of the fans (1-,2-RM-90-249 and 3-RM-90-251). The other monitors the exhaust through the remaining five fans (1-,2-RM-90-251 and 3-RM-90-249).

The common 600 foot plant stack receives the Condenser Offgas exhaust, the Filter Cubicle exhaust, the Steam Packing and Mechanical Vacuum exhaust, an&

the Standby Gas Treatment System (SBGTS) exhaust. The stack effluents are monitored by radiation monitors RM-90-147 and 148.

Figu:-es 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System.

and normal building ventilation with effluent monitor locations.

ODCM Revision 0017 Page 108 of 208 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ODCM Control 1.1.2 requires that gaseous effluent monitors have alarm/trip setpoints to ensure that ODCM dose rate limits are not exceeded. This section of the ODCM describes the methodology that is used to determine the allowable values which are used to calculate the physical settings on the monitors. The monitor setpoints are calculated in the applicable Scaling and Setpoint Docunent. Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with the effluent monitor locations.

All gaseous releases from BFN are continuous, so allowable values are calculated for each of the monitors as a part of a release permit package per sampling requirements of Table 2.2-2. Using the actual radionuclide mix as measured in a sample, a maximum allowable value is calculated (as described below) and compared to a default allowable value assigned to that monitor.

The default allowable values are described in Section 7.1.2. The lower of the two values is the recommended setpoint for that release point. If the release point is one of several leading into a common discharge point, all current releases into that discharge point are used in the calculation of the discharge point monitor allowable value (e.g., the stack).

7.1.1 Maximum Allowable Value An expected monitor response is calculated from the sample results:

R = E; + £ Ei Ci (7.1) i where:

B = monitor background, cpm or cps.

Ei = efficiency factor for the monitor for nuclide i, cpm per pCi/cc or cps per pCi/cc.

Ci = measured concentration of nuclide i, pCi/cc.

The expected response is then used to determine the calculated maximum allowable value, Smax in cpm or cps. This value corresponds to the dose rate limit, for the measured radionuclide mix and is determined using the following equation:

DRlim Smax (A SF ( (R - B))) + B (7.2)

DR where:

A = dose rate allocation factor for the release/discharge point, dimensionless. The dose rate allocation factor for the stack is 0.1, the building vent allocation factors are equal to 0.9 times the fraction of the total building flow assigned to that particular vent.

ODCM Revision 0017 Page 109 of 208 SF = safety factor for the monitor, dimensionless.

DRlixn = the dose rate limit, mrem/y.

= 500 mrem/y to the total body for noble gases,

= 3000 mrem/y to the skin for noble gases, and DR = the calculated dose rate for the release, mrem/y.

= DRTB for total body (as described in Section 7.3.2.1),

= DRs for skin (as described in Section 7.3.2.2), and R = expected monitor response (as calculated above) cpm or cps.

B = the monitor background, cpm or cps.

7.1.2 Default Allowable Values The Methodology for determining the default alarm/trip allowable values is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each release point. The methodology for determining these release rate limits is given in Section 7.2. The second part consists of using the release rate limits to determine default allowable values for the monitors.

The default allowable values are calculated using the following equation.

Allowable Value

r f A + B (7.3)

F E where:

r = release rate limit for stack or ground level, pCi/s. The release rate limits used for the allowable value calculation are 1.44E+07 pCi/s for the stack and 1.50E+05 pCi/s for the building vents.

f = fraction of the limits r which is allowed for the release mode (elevated or ground level).

NOTE: The sum of the f values for elevated and ground levels must be less than or equal to 1. This lowers the limits to ensure that the site dose rate limit will not be exceeded if both the stack and the ground level release rate limits were reached simultaneously.

A = allocation factor. This is the portion of the release rate limit r which is assigned to the release point under consideration. This ensures that the ground level release rate limit will not be exceeded if all building vents were to reach their limit simultaneously. This is equal to 1 for the stack. The building vent release rate limit is divided among the ten vents based on the flow rates.

F = flow rate for the vent, cc/s. Maximum flow rates are used to ensure conservative setpoints.

E = efficiency of the monitor, (pCi/cc)/cpm or (pCi/cc)/cps.

B = background of the monitor, cpm or cps.

The calculation of these setpoints are documented further in 0-TI-15 and the applicable Scaling and Setpoint Document, including the numerical values for each of the parameters described above.

ODCM Revision 0017 Page 110 of 208 7.2 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 U1) noble gases as described in Section 7.3.2 and (2) iodines and particulates as described in Section 7.3.3.

The close rate limits of interest are:

Total Body = 500 mrem/y Skin = 3000 mrem/y Maximum Organ = 1500 mrem/y A release rate limit based on organ dose rates is not considered since iodine and particulate releases are not determined on a real time basis. The total body and skin dose rate limits are divided by the corresponding calculated dose rates described above:

Total Body Dose Rate Limit RTB(vent or stack) =

DTB (vent or stack)

Skin Dose Rate Limit Rs(vent or stack) =

DS (vent or stack)

ThesE: ratios represent how far above or below the guidelines the dose rate calculations were.

A total release rate, Q, for each release level (building vent or stack) is calcv.lated, using the source term data in Table 7.2. Thus, two 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.

To obtain a release rate limit, r, for each release level, the total release rate, Q, for that release level is multiplied by the corresponding ratio, R:

For roble gases released from building vents:

rrgv = RTBv Qngv, or

= RSv Qngv whichever is more restrictive, i.e., smaller.

ODCM Revision 0017 Page 111 of 208 where:

rngv = Calculated release rate limit for noble gases released from building vents.

RTBV = Ratio of total body dose rate limit to total body dose rate for building vent releases, as calculated above.

Qngv = Total Table 7.2 noble gas release rate from building vents.

RSv = Ratio of skin dose rate limit to skin dose rate for building vent releases, as calculated above.

For noble gases released from the stack:

rngs = RTBs Qngs' or

= RSs Qngs whichever is more restrictive, i.e., smaller.

where:

rngs = Calculated release rate limit for noble gases released from the stack.

RTBs = Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.

Qngs = Total Table 7.2 noble gas release rate from stack.

RSS = Ratio of skin dose rate limit to skin dose rate for stack releases, as calculated above.

The release rate limits, r, calculated for BFN using this methodology are:

Noble Gas Stack rngs = 1.44E+01 Ci/s Builcing Vents rngv = l.50E-01 Ci/s

ODCM Revision 0017 Page 112 of 208 7.3 GASEOUS EFFLUENTS - DOSE RATES 7.3.:L RELEASE SAMPLING As required by Table 2.2-2, a grab sample is taken and analyzed to determine the concentration, pCi/cc, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and part:;culates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (e.g., Sr-8s, Sr-90, and alpha emitters).

7.3.2 NOBLE GAS DOSE RATES Dose rates are calculated in order to determine compliance with the requ:.rements of ODCM Control 1.2.2.1. Dose rates are calculated for total body and skin due to noble gases using semi-infinite and finite cloud models as described in NUREG 0133. The release mode will determine the model used:

turbine building releases are treated as ground level and use the semi--infinite model; reactor and radwaste building vents are treated as split:-level (or mixed mode) and use the semi-infinite model; and stack releases are elevated and use the finite cloud model.

7.3.2.1 Total Body Dose Rate The close rate to the total body, DRTB in mrem/y, is calculated using the following equation:

DRTB = v [Vi Qis + DFBi ((X/Q)g Qig) + DFBi ((X/Q)m Qim)] (7.4) i where:

Vi = the constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, in mrem/y per pyi/s, as given in Table 7.4 Qis = the release rate of radionuclide i, in gaseous effluents from the stack, pCi/s.

DFBi = total body submersion dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pci/m 3 (Table 7.4).

X/Qg = for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).

Qig = the release rate of radionuclide i, in the gaseous effluents from all ground level releases, pCi/s.

X/Qm = for split-level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).

Qim = the release rate of radionuclide i, in gaseous effluents from all slit level releases, pCi/s.

ODCM Revision 0017 Page 113 of 208 7.3.2.2 Skin Dose Rate The close rate to the skin, DRS in mrem/y, is calculated using the following equat:ion:

DRS Z [ (DFSi X/Qs + 1.1 Bi) Qis + ((DFSi + 1.1 DFyi) X/Qg Qig)

+ ((DFSi + 1.1 DFyi) X/Qm Qim) ] (7.5) where:

DFSi = the skin dose factor due to beta emissions for each identified noble gas radionuclide, mrem/y per pCi/m 3.

X/Qs = for stack releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/n3 (Table 7.1).

Bi = the constant for long term releases (greater than 500 h/y) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, mrad/y per pCi/s (Table 7.4).

Qis = the release rate of radionuclide i, in gaseous effluents from the stack, pCi/s.

DFyi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, mrad/y per pCi/m 3 (unit conversion factor of 1.1 mrem/mrad converts air dose to skin dose) (Table 7.4).

X/Qg = for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).

Qig = the release rate of radionuclide i, in gaseous effluents from all ground level releases, pCi/s.

X/Qm = for split level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).

Qim = the release rate of radionuclide i, in gaseous effluents from all split level releases, pci/s.

ODCM Revision 0017 Page 114 of 208 7.3.3 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE Organ dose rates due to I-131, I-133, Tritium and all radionuclides in particulate form with half-lives of greater than 8 days, DRj in mrem/y, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

DRj = Z FD [ CTD(X/Q)D[RIT+RCTPJ + E CiD[(X/Q)DRIi+(D/Q)D[RCPi+RGi]J] (7.6)

D i where:

FD = flowrate of effluent stream from discharge point D, cc/s.

CTD = concentration of tritium in effluent stream at discharge point D, pci/cc.

X/QD = the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release mode associated with the discharge point D, s/m3, (Table 7.1).

RIT = inhalation dose factor for tritium, mrem/y per pCi/m 3 . Dose factor is calculated as described in Section 7.8.13 (where: RIi = RIT, i.e., i=T for tritium).

RCTP = grass-cow-milk dose factor for tritium, mrem/y per pCi/m 3 . Dose factor is calculated as described in Section 7.8.7.

CiD = concentration of nuclide i in effluent stream at discharge point D, pci/cc.

Rji = inhalation dose factor for each identified nuclide i, mrem/y per pCi/m 3 . Dose factors are calculated ad described in Section 7.8.13.

D/QD =the highest calculated annual average relative deposition for any area at or beyond the unrestricted area boundary for the release mode associated with discharge point D, m-2 , (Table 7.1).

RCpi = grass-cow-milk dose factor for each identified nuclide i, m2 -mrem/y per pci/s. Dose factors are calculated as described in Section 7.8.1.

RGi = ground plane dose factor for each identified nuclide i, m2 -mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.14.

The organ dose rates for all pathways are summed to find the total site dose rate. The maximum organ dose rate is selected from among the dose rates calculated for all locations, organs, and age groups.

ODCM Revision 0017 Page 115 of 208 7.4 CUMULATIVE DOSE - NOBLE GASES Dose:; to be calculated are gamma and beta air doses due to exposure to noble gases. For elevated releases (stack), a finite cloud model will be used for the gamma dose. All other releases will be calculated using a semi-infinite cloud model. The doses will be calculated at three locations: the land-site boundary locations with the highest annual-average split-level X/Q; the land--site boundary location with the highest ground-level annual-average X/Q; and the offsite location with the highest annual-average elevated-level X/Q.

The joint frequency distributions for the three levels of met data are given in Table 7.3. The locations, and their respective dispersion factors are listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.9.2 No credit is taken for radioactive decay.

7.4.1 Gamma Dose to Air The gamma air dose, Dy in mrad, is calculated for each release permit using one of the following equations:

For ground or split-level release/discharge points:

Dy = 3.17E-08 T Z [ DFyi Qi X/Q 1 (7.7) i For elevated release/discharge points:

Dy = 3.17E-08 T Z [ Bi Qi ] (7.8) i where:

3.17E.-08 = conversion factor, y/s.

T = duration of release, s.

DFyi = dose conversion factor for external gamma for nuclide i (Table 7.4), mrad/y per pCi/m 3.

Qi = the release rate of radionuclide i, pCi/s.

X/Q = the highest calculated annual-average relative concentration for any area at or beyond the unrestricted area boundary for the release type under consideration (Table 7.1), s/m3 .

Bi = the constant for long term releases (greater than 500 h/y) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume (Table 7.4), mrad/y per pCi/s.

The location with the highest dose is selected as the critical receptor for each release. This receptor is used in the determination of the cumulative doses in section 7.4.3.

ODCM Revision 0017 Page 116 of 208 7.4.2 Beta Dose to Air The beta air dose, Dp in mrad, is calculated for each release permit using the following equation:

Df; = 3.17E-08 T Z [ DFpi (Qi X/Q ) ] (7.9) i where:

3.17E-08 = conversion factor, y/s.

T = duration of release, s.

DFpi = dose conversion factor for external beta for nuclide i (Table 7.4), mrad/y per pci/m 3 .

Qi = the release rate of radionclide i from the release/discharge point under consideration, lICi/s.

X/Q = the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release/discharge point under consideration (Table 7.1), s/m3 .

The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.4.3.

7.4._ Cumulative Dose - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.2.

For roble gases, cumulative doses are calculated for gamma and beta air doses.

Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.

7.4.4 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

ODCM Revision 0017 Page 117 of 208 7.5 C:UMULATIVE DOSE - I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS 7.5.1 Organ Dose Calculation Organ dose due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release permit for the critical receptor. The critical receptor is defined as the receptor with the highest calculated dose of all the receptors defined in Table 7.1. Annual average X/Q and D/Q are calculated using the methodology in Sections 7.9.2 and 7.9.3 using the historical 1977-88 meteorological data (Table 7.2). Pathways considered to exist at these locations are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.8. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose is:

Dorg = 3.17E-08 I I T Rpi [ Wp Qi ] (7.10) i P where:

3.17E;-08 = conversion factor, y/s.

T = duration of release from release/discharge point under consideration, s.

Rpi = dose factor for pathway P for each identified nuclide i, m2 -mrem/y per pCi/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrem/y per pCi/m3 for inhalation and tritium ingestion pathways. Equations for calculating these dose factors are given in Section 7.8.

WP = dispersion factor for the release/discharge point under consideration and pathway P (Table 7.1).

= x/Q for the inhalation and tritium ingestion pathways,

= D/Q for the food and ground plane pathways, Qi = release rate for radionuclide i from release/discharge point under consideration, pCi/s.

The receptor with the highest dose of all locations, age groups and organs is selected as the critical receptor. The age group with the highest dose for that receptor is selected as the critical age group. The organ dose for the critical age group will be used in the cumulative doses discussed in Section 7.5.2.

ODCM Revision 0017 Page 118 of 208 7.5.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.

For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.5.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3.

7.5.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

ODCM Revision 0017 Page 119 of 208 7.6 GASEOUS RADWASTE TREATMENT 7.6.1 DOSE PROJECTIONS 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 SYSTEM DESCRIPTION Figure 7.1 shows major elements of the Gaseous Radwaste Treatment System.

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.

ODCM Revision 0017 Page 120 of 208 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described below, using the quarterly release values. For iodine releases, it will be assumed that half the iodines released are organic iodines, which contribute only to the inhalation dose. All real pathways and receptor locations (as identified in the most recent land use survey) are considered. In addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in Section 7.9. Stack releases will be considered elevated releases. Radwaste and reactor building releases will be considered split-level releases. Turbine building releases will be treated as ground level.

7.7.1. Noble Gas Dose All measured radionuclides are used to calculate gamma and beta air doses.

The close is evaluated at the nearest SITE BOUNDARY point in each sector and at other locations expected to be maximum exposure points using a semi-infinite cloud model. The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations usincr the semi-infinite cloud model for BFN.

Radioactive decay is considered in this calculation. The quarterly release is averaged over one year to obtain an average release rate.

ODCM Revision 0017 Page 121 of 208 7.7.:..1 Gamma Dose to Air Dyn = Xni DFyi (7.12) where:

Dyn = gamma dose to air for sector n, mrad.

Xni = air concentration of radionuclide i in sector n, pCi-y/m3 . Air concentrations are calculated as described by Equation 7.16.

DFyi = gamma-to-air dose factor for radionuclide i, mrad/y per lVCi/m3 (Table 7.4).

7.7.1.2 Beta Dose to Air Don = Xni DFBi (7.13) i where:

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

Xni = air concentration of radionuclide i in sector n, pCi-y/m3 . Air concentrations are calculated as described by Equation 7.16.

DFpi = beta-to-air dose factor for radionuclide i, mrad/y per pCi/m3 (Table 7.4).

ODCM Revision 0017 Page 122 of 208 7.7.2 Radioiodine, Particulate and Tritium - Maximum Organ Dose Organ doses due to radioiodine, particulate and tritium releases are calculated using the following equation:

Dorg:= 3.17E-08 (X(D/Q IRpi + D/Q RGi + X/Q Rii)Qi + E(X/Q RPT)QT] (7.14) i P P where:

Dorg = Organ dose, mrem.

3.17}.-08 = conversion factor, y/s.

X/Q = Relative concentration for location under consideration, s/m 3 .

Relative concentrations are calculated as described by Equation 7.17.

Rpi = ingestion dose factor for pathway P for each identified nuclide i (except tritium), m2 -mrem/y per pci/s. Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.8.1 through 7.8.6.

D/Q = Relative deposition for location under consideration, m-2 .

Relative deposition is calculated as described in Equation 7.18.

RGi = Dose factor for standing on contaminated ground, m2 -mrem/y per pCi/s. The equation for calculating the ground plane dose factor is given in Section 7.8.14.

RIi = Inhalation dose factor, mrem/y per pCi/m 3 . The equation for calculating the inhalation dose factor is given in Section 7.8.13.

ODCM Revision 0017 Page 123 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

= QiO Z fj exp(-Xi X/Uj) j=l where:

QiO = initial average release for nuclide i over the period, pCi.

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, s-1.

x = downwind distance, meters.

uj = midpoint value of wind speed class interval j, m/s.

RPT = ingestion dose factor for pathway P for tritium, mrem/y per pCi/m 3 .

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.

ODCM Revision 0017 Page 124 of 208 7.7.3 Population Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.5. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element.

Dispersion factors are calculated for the midpoint of each sector element (see Table 7.5) using the methodology described in Section 7.9. For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population dose in a given sector element is:

Dosepop = Z RATIOp

POPN

AGE

0.001

DOSEp (7.15)

P where:

RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)

= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.

= 1.0 for the inhalation pathway.

= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)

= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh vegetables, only stored vegetables.)

POPN = the population of the sector element, persons (Table 7.6).

AGE = fraction of the population belonging to each age group.

= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).

0.001 = conversion from mrem to rem.

DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as:

ADC = exp(-Xit), for milk and vegetables, where:

Xi = decay constant for nuclide i, s.

t = distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-1).

= 1.21E+06 s (14 d) for vegetables.

= 3.46E+05 s (4 d) for milk.

ODCM Revision 0017 Page 125 of 208 exp(-Xit) %itcb ADC = , for meat, 1 - exp(-Xi tcb) where:

Xi = decay constant for nuclide i, s.

t = additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7d (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 Reporting of Doses The calculated quarterly doses and calculated population doses described in this section are reported in the Annual Radioactive Effluent Release Report as described in ODCM Administrative Control 5.2 7.7.E Dose to a MEMBER OF THE PUBLIC Inside the SITE BOUNDARY The Easis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy factor of that MEMBER.

OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the SITE BOUNDARY.

The highest dose to a MEMBER OF THE PUBLIC will consider the effects of effluent pathways (onsite and offsite) and direct radiation from plant operating activities.

The dose to this hypothetical MEMBER OF THE PUBLIC will be determined on an annual basis (using the methodology above) to ensure that the actual exposure to any individual is less than 100 mrem/year. The results of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.

ODCM Revision 0017 Page 126 of 208 7.8 GASEOUS DOSE FACTOR EQUATIONS 7.8.] Pasture Grass-Cow/Goat-Milk Ingestion Dose Factors (m2 -mrem/y per pCi/s) r(l-exp(-XEtem)) Biv(l-exp(-Xitb))

RCpi = 10 6 DFLiajUapFmiQfexp(-Xitfm)fpc _ + )

YpX E P Xi where:

106 = conversion factor, pCi/pCi.

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

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

Fmi = transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).

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

Xi = decay constant for nuclide i, s-1 (Table 6.2).

tfm = transport time from milking to receptor, s.

fpc = fraction of time animal spends on pasture, dimensionless.

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

XE = the effective decay constant, due to radioactive decay and weathering, s-l, equal to Xi + XW.

Xw = weathering decay constant for leaf and plant surfaces, s- 1 .

tem = time pasture is exposed to deposition, s.

Yp = agricultural productivity by unit area of pasture grass, kg/m 2 .

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, s.

P = effective surface density of soil, kg/m 2 .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 127 of 208 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors (m2 -mrem/y per pCi/s)

(1-exp(-Xitcsf))

RCSi = 106 DFLiaj Uap Fmi Qf fsc exp(-Xitmc) tcsf Xi r(1-exp(-XEtesf)) Biv(l-exp(-Xitb))

Ys XE P Xi where:

106 = conversion factor, pCi/pCi.

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

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

Fmi = transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).

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

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

Xi = decay constant for nuclide i, 5s- (Table 6.2).

tmc = transport time from milking to receptor, s.

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

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

XE = the effective decay constant, due to radioactive decay and weathering, 5-1, equal to Xi + XA.

xW = weathering decay constant for leaf and plant surfaces, s-1.

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

Ys = agricultural productivity by unit area of stored feed, kg/m 2 .

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, s.

P = effective surface density of soil, kg/m 2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 128 of 208 7.8.3 Pasture Grass-Beef Ingestion Dose Factors (m2 -mrem/y per pCi/s)

(1-exp(-Xitcb))

RMpi = 106 DFLiaj Uam Ffi Qf - exp(-Xits) fp Xi tcb r(l-exp(-XEtem)) Biv(l-exp(-Xitb))

+

(.

Yp XE P Xi where:

106 = conversion factor, pCi/pCi.

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

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

Ffi = transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).

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

Xi = decay constant for nuclide i, s51 (Table 6.2).

tcb = time for receptor to consume a whole beef, s.

ts = transport time from slaughter to consumer, s.

fp = fraction of time cow spends on pasture, dimensionless.

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

XE = the effective decay constant, due to radioactive decay and weathering, 5-1, equal to Xi + XW.

Xw = weathering decay constant for leaf and plant surfaces, s-1.

tem = time pasture is exposed to deposition, s.

Yp = agricultural productivity by unit area of pasture grass, kg/m 2.

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, s.

P = effective surface density of soil, kg/m 2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 129 of 208 7.8.4 Stored Feed-Beef Ingestion Dose Factors (m2 -mrem/y per pCi/s)

(l-exp(-Xitcb))

RMSi = 106 DFLiaj Uam Ffi Qf exp(-Xits)

Xi tcb (1-exp(-Xitcsf)) r(1-exp(-XEtesf)) Biv(l-exp(-Xitb))

fs _{ +

Xi tcsf Ysf XE P Xi where:

106 = conversion factor, pCi/pCi.

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

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

Ffi = transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).

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

Xi = decay constant for nuclide i, s-1 (Table 6.2).

tcb = time for receptor to consume a whole beef, s.

ts = transport time from slaughter to consumer, s.

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

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

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

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

Ysf = agricultural productivity by unit area of stored feed, kg/m 2 .

XE = the effective decay constant, due to radioactive decay and weathering, s-l, equal to Xi + XA.

Xw = weathering decay constant for leaf and plant surfaces, s-1.

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, s.

P = effective surface density of soil, kg/m 2 .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 130 of 208 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors (m2 -mrem/y per pci/s) r(l-exp(-XEte)) Biv(I-exp(-Vitb))

RVFi = 106 DFLiaj exp(-Xithc) UFLafL { + }

Yf XE P Xi where:

106 = conversion factor, pCi/pCi.

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

Xi = decay constant for nuclide i, s-1 (Table 6.2).

the = average time between harvest of vegetables and their consumption and/or storage, s.

UFLa = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r =fraction of deposited activity retained on vegetables, dimensionless.

XE = the effective decay constant, due to radioactive decay and weathering, 5-1.

= xi + Xw Xw = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1.

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

Yf = vegetation areal density for fresh leafy vegetables, kg/m 2 .

Biv = 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, s.

P = effective surface density of soil, kg/m 2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 131 of 208 7.8.6 Stored Vegetable Ingestion Dose Factors (m2 -mrem/y per pCi/s)

(l-exp(-Xitsv))

RVsi = 106 DFLiaj exp(-Xithc) Usafg Xi tsv r(1-exp(-XEte)) Biv(1-exp(-Xitb))

_ _ _ _ + _ )__

Ysv XE P Xi where:

106 = conversion factor, pCi/pCi.

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

xi = decay constant for nuclide i, s-1 (Table 6.2).

the = average time between harvest of vegetables and their consumption and/or storage, s.

Usa = consumption rate of stored vegetables by the receptor in age group 3, kg/y.

fg = fraction of stored vegetables grown locally, dimensionless.

tsv = time between storage of vegetables and their consumption, s.

r = fraction of deposited activity retained on vegetables, dimensionless.

XE = the effective decay constant, due to radioactive decay and weathering, s-1.

= Xi + Xw kw = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1.

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

Ysv = vegetation areal density for stored vegetables, kg/m 2 .

Biv = 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, s.

P = effective surface density of soil, kg/m 2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 132 of 208 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor (mrem/y per pCi/rn3 )

RCTP = 103 106 DFLTaj FmT Qf Uap (0.75(0.5/H)] fp exp(-XTtfm) where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/pCi.

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

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

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

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

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 .

fp = fraction of time animal spends on pasture, dimensionless.

XT = decay constant for tritium, s-l (Table 6.2).

tfm = transport time from milking to receptor, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 133 of 208 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor (mrem/y per pCi/m 3)

(l-exp(-XTtcsf))

RCTS = 103 106 DFLTaj FmT Qf Uap [0.75(0.5/H)J f5 exp(-XTtfm)

XT tcsf where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/pCi.

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

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

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

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

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 animal spends on stored feed, dimensionless.

XT = decay constant for tritium, sl (Table 6.2).

tcSf = time between harvest of stored feed and consumption by animal, s.

tfm = transport time from milking to receptor, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 134 of 208 7.8.9 Tritium-Pasture Grass-Beef Dose Factor (mrem/y per pCi/m 3 )

RMT 103 106 DFLTaj FfT Qf Uam [0.75(0.5/H)] fp exp(-XTts)

(1-exp(-XTtep)) (l-exp(-XTtcb))

XT tep XT tcb where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/pCi.

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

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

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

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

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 .

fop = fraction of time cow spends on pasture, dimensionless.

XT = decay constant for tritium, s-1 (Table 6.2).

ts = transport time from slaughter to consumer, s.

tep = time pasture is exposed to deposition, s.

tcb = time for receptor to consume a whole beef, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 135 of 208 7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/y per pCi/m 3)

RMTS = 103 106 DFLTaj FfT Qf Uam (0.75(0.5/H)] fs exp(-XTts)

(l-exp(-XTtCSf)) (1-exp(-XTtcb))

XT tCSf XT tcb where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/pCi.

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

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

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

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

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, s-1 (Table 6.2).

ts = transport time from slaughter to consumer, s.

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

tcb = time for receptor to consume a whole beef, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 136 of 208 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor (mrem/y per pCi/m 3 )

RVTF = 103 106 DFLTaj (0.75(0.5/H)] UFLa fL exp(-XTthc) where:

103 = conversion factor, g/kg.

106 =conversion factor, pCi/pCi.

DFLTEj =ingestion dose conversion factor for tritium for age group a, organ j, 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 vegetables water to the atmospheric water.

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

UFLa =consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

XT = decay constant for tritium, s-I (Table 6.2).

the = time between harvest of vegetables and their consumption and/or storage, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 137 of 208 7.8.:L2 Tritium-Stored Vegetables Dose Factor (mrem/y per pCi/m 3 )

(l-exp(-XTtsv) )

RVTS = 103 106 DFLTaj [0.75(0.5/H)] USafg exp(-XTthc)

XT tsv where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/pCi.

DFLTaj = ingestion dose conversion factor for tritium for age group a, organ j, 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/y.

fg = fraction of stored vegetables grown locally, dimensionless.

XT = decay constant for tritium, s-1 (Table 6.2).

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

thc = time between harvest of vegetables and their storage, s.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

ODCM Revision 0017 Page 138 of 208 7.8.:.3 Inhalation Dose Factors (mrem/y per pCi/m 3)

Rji = DFAiaj BRa 106 where:

DFAijjj = inhalation dose conversion factor for nuclide i, age group a and organ j, mrem/pCi (Table 7.7).

BRa = breathing rate for age group a, m3 /y (Table 6.3).

106 = conversion factor, pCi/pCi.

7.8.14 Ground Plane Dose Factors (m2 -mrem/y per pCi/s)

F:Gi = DFGij (l/Xi) 106 8760 [1 - exp(-Xitb))

where:

DFGi = dose conversion factor for standing on contaminated ground for nuclide i and organ j (total body and skin), mrem/h per pCi/m2 (Table 6.6).

X.i = decay constant of nuclide i, s-1 (Table 6.2).

106 = conversion factor, pCi/pCi.

8760 = conversion factor, h/y.

tb = time period over which the ground accumulation is evaluated, s (Table 6.3).

ODCM Revision 0017 Page 139 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.

Hourly average 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.

Metecrological data are expressed as a joint-frequency distribution of wind speecd, 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 Decenber 1988 are given in Table 7.3.

The wind speed classes that are used are as follows:

Number Range (m/s) Midpoint (m/s) 1 <0.3 0.13 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10 .9 10.95 The stability classes that will be used are the standard Pasquill A through 3 classifications. The stability classes 1-7 will correspond to A=l, B=2, ... ,

G=7.

ODCM Revision 0017 Page 140 of 208 A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.3), and building wake effects. Terrain effects on dispersion are not considered except for reducing the effective height of an elevated release by the terrain height.

7.9.1 Annual Average Air Concentration X (pCi-y/m3J Air concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 fjk Qi P Xi= I E(2/n)1/2 exp(-Xix/uj) exp(-he2 /2azk2 ) 106 3.17E-08 (7.16) j=1 k=l Fzkuj(2nx/n) where:

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

Qi = amount released of radionuclide i, Ci.

p = fraction of radionuclide remaining in plume (Figure 7.3).

Xzk = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (azk2 + cA/n) 1 /2 ,

or = /3 Ozk, whichever is smaller (for ground level releases).

where:

Gyzk 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 m2 .

uj = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

Xi = radioactive decay coefficient of radionuclide i, 5-1 2nx/r = 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.

106 = conversion factor, pCi per Ci.

3.17E;-08 = conversion factor, y/s.

ODCM Revision 0017 Page 141 of 208 7.9.2 Relative Concentration X/Q (s/m3 )

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

9 7 fjk X/Q = Y z (2/n) 1 /2 exp(-he2 /25zk 2 ) (7.17) j=l k=1 Zzk uj (2nx/n) where:

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

Ezk = vertical dispersion coefficient for stability class k which includes a building wake adjustment, 2

= (czk + cA/n)1/2, or = /3 Ezk, whichever is smaller (for ground level releases).

where:

azk 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 2.

uj = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

2nx/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.^ Relative Deposition D/Q (m-2)

Relative deposition of nuclides at downwind locations is calculated using the following equation:

9 7 fjk DR D/Q = E Z (7.18) j=l k=l (2nx/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, mr1 (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.

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

ODCM Revision 0017 Page 142 of 208 7.9.' Effective Release Height For effluents exhausted from release points that are higher than twice the height of adjacent structures (elevated releases) the effective release height is determined by the following equation, consistent with Regulatory GuidE! 1.111 he = hs + hpr - ht -c where:

c = downwash correction factor for low relative exit velocity,

= 3(1.5-Wo/u)d, where:

Wo = the vertical plume exit velocity, m/s.

u = mean wind speed at 93m, m/s.

d = inside diameter of the release point, m.

NOTE: If c is less than zero, it is set equal to zero.

hpr = plume rise above the release point, m.

hs = physical height of release point, m.

ht = maximum terrain height between release point and receptor location, m.

For effluents released from points less than the height of adjacent structures, a ground level release is assumed (he = 0)-

For effluents released from points at the level of or above adjacent structures, but lower than elevated release points, releases are treated as split-level as follows:

Case 1 - elevated if Wo/u 2 5.

Case 2 - ground level (he = 0) if Wo/u

1.

Case 3 - mixed mode if 1 < wo/u < 5.

where:

u = mean wind speed at 46m, m/s.

Under the split-level dispersion approach, a model that requires two JFDs (one for elevated releases and one for ground level releases) is used. The summation of the elevated and ground level JFDs account for the total pericd of record. For Case 3 (mixed-mode), releases are considered to be elevated 100(1-Et) percent of the time and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et = 2.58 - 1.58(WO/u) for 1 < Wo/u

1.5 Et. = 0.3 - 0.06(WO/u) for 1.5 < Wo/u

5

ODCM Revision 0017 Page 143 of 208 Table 7.1 BFN - OFFSITE RECEPTOR LOCATION DATA Elev.

above Dir. / plant Ground Vent Mixed Vent Elevated Vent Dist. grade D/Q X/Q D/Q X/Q D/Q X/Q (Im) (s/m 3 ) (1/m 2 ) (s/m3 ) (1/m 2 )

3 (s/m ) (1/m 2 )

(m)

N 1525 7 l.91E-06 5.77E-09 3.88E-07 2. 19E-09 4.46E-10 4. 99E-10 NNE 1300 4 1.06E-06 2. 69E-09 1. 65E-07 1.12E-09 3.99E-10 3.17E-10 NE 1250 7 7.13E-07 1.89E-09 1.35E-07 8. 90E-10 1.64E-09 3.65E-10 ENE 1450 0 9.08E-07 3.15E-09 1.20E-07 9.36E-10 1.22E-09 3.37E-10 E 1375 0 9.21E-07 3.81E-09 1.50E-07 1.37E-09 8.36E-10 4.25E-10 ESE 1575 0 5.19E-07 3.09E-09 1.25E-07 1.43E-09 4.84E-10 4.78E-10 SE 5600 -6 9.61E-08 3.50E-10 4.30E-08 2. 69E-10 5.15E-09 2.14E-10 SSE 2875 -6 5.20E-07 1.57E-09 9.78E-08 7.40E-10 1.13E-09 3.96E-10 S 2250 -6 1.21E-06 2. 93E-09 1.54E-07 1.14E-09 4.39E-10 5.11E-10 SSW 2425 -6 1.28E-06 2.88E-09 1.74E-07 1.1OE-09 6.10E-10 4.29E-10 SW 2300 -6 8.33E-07 1.71E-09 1.02E-07 5.22E-10 2.55E-10 2.21E-10 WSW 2500 -6 8.17E-07 1.21E-09 7.OOE-08 2. 15E-10 2. 61E-10 1.14E-10 W 2550 -6 8.51E-07 1.43E-09 6.95E-08 2.40E-10 2.63E-10 1.18E-10 WNW 3325 -6 4.14E-07 7.87E-10 1.04E-07 3.33E-10 1.75E-09 2.50E-1D NW 2275 -6 1.90E-06 4.65E-09 3.22E-07 1.53E-09 1.83E-09 6.17E-10 NNW 1650 -6 2.26E-06 5.42E-09 3.63E-07 2.12E-09 8.93E-10 5.54E-10 NW 8500 -6 3.04E-07 4.60E-10 9.90E-08 2.05E-10 8.93E-09 1.37E-10 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.

ODCM Revision 0017 Page 144 of 208 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN Building Vents (Ci/y/Unit) Stack (Ci/y/Unit)

Reactor Radwaste Turbine Gland Complex Building Building Seal and Isotcpe Vent Vent Vent Offgas MVP Kr-8Em 6E+O <1 2E+O 1. 66E+4 0.OE+O Kr-85 6.3E+2 Kr-87 6E+O <1 9.5E+1 7.47E+2 O.OE+O Kr-8E 9E+O <1 1.02E+2 1.35E+4 0.OE+O Kr-8S lE+O 3.4E+1 5.03E+2 4.10E+3 O.OE+O Xe-131m 3.09E+2 0.OE+O Xe-133m OE+O 6.OE+1 OE+O 8.51E+2 0.OE+O Xe-133 1.03E+2 2.94E+2 5.81E+2 9.47E+4 3.OE+2 Xe-135m l.l1E+2 6.67E+2 4. 64E+2 9.17E+2 0.OE+O Xe-135 1.73E+2 3.28E+2 6.72E+2 5. 99E+2 2. OE+2 Xe-137 7.8E+l 1.13E+2 3.86E+2 5.04E+3 0.OE+O Xe-138 1.2E+l 2E+O 1.18E+3 3.15E+3 0. OE+O I-131 I 5.94E-2 5.OE-3 1.56E-2 4.1E-3 8.5E-3 I-132 I 5.94E-1 5.OE-2 1.79E-1 4. 69E-2 9.73E-2 I-133 I 2.97E-1 2.5E-2 1.23E-1 3.23E-2 6.71E-2 I-134 I 1.49E+O 1.25E-1 2. 67E-2 7.OE-3 1.45E-2 I-135 I 5.94E-1 5.OE-2 1.23E-1 3.23E-2 6.71E-2 I-131 0 3.16E-2 2.9E-2 6.5E-3 3. 32E-2 2.74E-1 I-132 0 3.16E-1 2.9E-1 7.44E-2 3.80E-1 3.14E+O I 0 1.58E-1 1.45E-1 5.13E-2 2.62E-1 2.16E+O I-134 0 7.90E-1 7.25E-1 1.1lE-2 5.68E-2 4. 69E-1 I-135 0 3.16E-1 2.90E-1 5.13E-2 2.61E-1 2.16E+O Cr-51 3E-3 9E-4 1E-3 1E-4 0.OE+O Mn-54 3E-3 5E-3 2E-3 4E-5 0.OE+O Co-58 2E-3 4E-4 9E-5 2E-5 0.OE+O Fe-5S 1E-4 8E-4 4E-4 2E-4 0.OE+O Co-6C 3E-2 6E-3 3E-3 1E-5 0.OE+O Zn-6' 3E-3 2E-4 4E-4 9E-5 0.OE+O Sr-89 1E-2 3E-1 *

0. OE+O Sr-90 2E-3 4E-3

0.OE+O Nb-95 3E-4 2E-4 9E-6 8E-5 0.OE+O Zr-95 1E-4 1E-4 8E-6 8E-5 0. OE+O Ru-lC3 3E-5 1E-4 2E-4 1E-4 0.OE+O Ag-lOrm 7E-6 0.OE+O Sb- 124 3E-5 3E-4 6E-5 8E-5 0.OE+O Cs-134 5E-3 3E-4 5E-4 2E-5 0.OE+O Cs-136 2E-3 5E-5 1E-4 9E-8 0.OE+O Cs-137 7E-3 4E-4 2E-3 7E-4 0.OE+O Ba-140 4E-3 5E-4 2E-2 8E-3 0.OE+O Ce-141 4E-4 2E-4 2E-3 2E-5 0.OE+O Ce-144 5E-6 4E-6 0.0OE+O Ar-41 2.5E+l OE+O OE+O OE+O 0.OE+O C-14 OE+O OE+O OE+O 9.5E+O 0.OE+O H-3 OE+O 9.5E+O OE+O OE+O 0. OE+O

Not available.

I denotes nonorganic iodine (elemental, particulate, HIO) 0 denotes organic iodine.

ODCM Revision 0017 Page 145 of 208 Table 7.3 (1 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 > 24.5 TDtal N 0.0 0.0 0.0 0.010 0.026 0.281 0.122 0.005 0.0 0.444 NNE 0.0 0.0 0.001 0.009 0.038 0.284 0. 109 0.001 0.0 0.443 NE 0.0 0.0 0.001 0.007 0.024 0.075 0.015 0.0 0.0 0. 122 ENE 0.0 0.0 0.001 0.003 0.006 0.004 0.0 0.0 0.0 0.014 E 0.0 0.0 0.001 0.004 0.007 0.006 0.0 0.0 0.0 0.018 ESE 0.0 0.0 0.006 0.061 0.093 0.014 0.0 0.0 0.0 0.173 SE 0.0 0.001 0.106 1.205 0.366 0.044 0.0 0.0 0.0 1.721 SSE 0.0 0.0 0.132 0.672 0.115 0.015 0.0 0.0 0.0 0.934 S 0.0 0.0 0.069 0.557 0.112 0.033 0.0 0.0 0.0 0.772 SSW 0.0 0.0 0.018 0.142 0.057 0O.011 0.0 0.0 0.0 0.227 SW 0.0 0.0 0.008 0.097 0.042 0.005 0.0 0.0 0.0 0.152 WSW 0.0 0.0 0.0 0.055 0.084 0.050 0.004 0.0 0.0 0.193 W 0.0 0.0 0.001 0.014 0.046 0.065 0.007 0.001 0.0 0.133 WNW 0.0 0.0 0.0 0.020 0.037 0.115 0.067 0.007 0.0 0.246 NW 0.0 0.0 0.0 0.005 0.032 0.191 0.144 0.004 0.0 0.375 NNW 0.0 0.0 0.0 0.007 0.012 0.107 0.102 0.019 0.0 0.245 Sub total. 0.0 0.001 0.343 2.865 1.098 1.298 0.570 0.036 0.0 6.211 Total hours of valid stability observations - 103468 Total hours of stability class A - 6379 Total hours of valid wind direction-wind speed-stability class A - 6354 Total. hours of valid wind direction-wind speed-stability observations - 102303 Metecorological 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 = 6.81 mph

ODCM Revision 0017 Page 146 of 208 Table 7.3 (2 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class B (-1.9 < Delta-T < -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 > 24.5 Total N 0.0 0.0 0.002 0.021 0.072 0.212 0.044 0.002 0.0 0.353 NNE 0.0 0.0 0.001 0.030 0.093 0.237 0.047 0.0 0.0 0.408 NE 0.0 0.0 0.002 0.024 0.034 0.080 0.007 0.0 0.0 0.148 ENE 0.0 0.0 0.002 0.010 0.008 0.008 0.0 0.0 0.0 0.027 E 0.0 0.0 0.002 0.011 0.007 0.001 0.001 0.0 0.0 0.022 ESE 0.0 0.0 0.013 0.052 0.021 0.011 0.0 0.0 0.0 0.096 SE 0.0 0.0 0.153 0.445 0.053 0.015 0.0 0.0 0.0 0.666 SSE 0.0 0.0 0.130 0.216 0.023 0.012 0.0 0.0 0.0 0.381 S 0.0 0.0 0.072 0.264 0.039 0.012 0.0 0.0 0.0 0.387 SSW 0.0 0.0 0.027 0.104 0.016 0.002 0.002 0.0 0.0 0.151 SW 0.0 0.0 0.013 0.125 0.025 0.007 0.0 0.0 0.0 0.170 WSW 0.0 0.0 0.005 0.088 0.087 0.044 0.008 0.0 0.0 0.232 W 0.0 0.0 0.005 0.024 0. 090 0.082 0.016 0.001 0.0 0.218 WNW 0.0 0.0 0.002 0.044 0.075 0.164 0.071 0.018 0.0 0.374 NW 0.0 0.0 0.001 0.014 0.055 0.236 0.087 0.006 0.0 0.398 NNW 0.0 0.0 0.0 0.007 0.036 0.171 0.058 0.003 0.0 0.275 Sub total. 0.0 0.0 0.430 1.478 0.734 1.292 0.340 0.029 0.0 4.304 Total. hours of valid stability observations - 103468 Total hours of stability class B - 4424 Total hours of valid wind direction-wind speed-stability class B - 4403 Total hours of valid wind direction-wind speed-stability observations - 102303 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 = 7.04 mph

ODCM Revision 0017 Page 147 of 208 Table 7.3 (3 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class C (-1.7 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 _ 24.5 Total N 0.0 0.0 0.011 0.055 0.122 0.231 0.030 0.002 0.0 0.451 NNE 0.0 0.0 0.008 0.062 0.115 0.202 0.027 0.0 0.0 0.414 NE 0.0 0.0 0.002 0.042 0.080 0.086 0.007 0.0 0.0 0.217 ENE 0.0 0.0 0.004 0.021 0O.011 0.011 0.0 0.0 0.0 0.046 E 0.0 0.0 0.004 0.020 0.016 0.003 0.001 0.0 0.0 0.043 ESE 0.0 0.0 0.008 0.048 0.018 0.004 0.0 0.0 0.0 0.077 SE 0.0 0.001 0.213 0.313 0.057 0.013 0.002 0.0 0.0 0.598 SSE 0.0 0.0 0.188 0.166 0.022 0.009 0.0 0.0 0.0 0.385 S 0.0 0.0 0.146 0.232 0.044 0.013 0.0 0.0 0.0 0.434 SSW 0.0 0.0 0.042 0.109 0.014 0.002 0.0 0.0 0.0 0.167 SW 0.0 0.001 0.053 0.143 0.025 0.005 0.001 0.0 0.0 0.228 WSW 0.0 0.0 0.013 0.140 0.079 0.072 0.006 0.001 0.0 0.311 W 0.0 0.0 0.003 0.048 0.103 0.088 0.022 0.004 0.0 0.267 WNW 0.0 0.0 0.009 0.096 0.109 0.197 0.079 0.027 0.0 0.518 NW 0.0 0.0 0.002 0.054 0.108 0.211 0.067 0.004 0.001 0.447 NNW 0.0 0.0 0.003 0.016 0.058 0.182 0.055 0.002 0.0 0.315 Sub total 0.0 0.002 0.707 1.562 0.980 1.328 0.297 0.040 0.001 4.918 Total hours of valid stability observations - 103468 Total hours of stability class C - 5065 Total hours of valid wind direction-wind speed-stability class C - 5031 Total hours of valid wind direction-wind speed-stability observations - 102303 Metecrological 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 = 6.67 mph

ODCM Revision 0017 Page 148 of 208 Table 7.3 (4 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class D (-1.5 < Delta-T < -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 _'24.5 Total N 0.0 0.016 0.212 0.471 0.584 1.151 0.368 0.029 0.001 2.832 NNE 0.0 0.013 0.227 0.519 0.647 1.156 0.190 0.009 0.0 2.761 NE 0.0 0.014 0.195 0.429 0.446 0.461 0.022 0.0 0.0 1.566 ENE 0.001 0.015 0.247 0.346 0.185 0.106 0.004 0.0 0.0 0.903 E 0.001 0.010 0.264 0.435 0.250 0.125 0.008 0.0 0.0 1.092 ESE 0.001 0.013 0.258 0.437 0.241 0.078 0.001 0.0 0.0 1.029 SE 0.003 0.051 1.498 1.203 0.648 0.294 0.005 0.0 0.0 3.702 SSE 0.003 0.031 1.300 0.823 0.228 0.105 0.004 0.0 0.0 2.493 S 0.002 0.029 1.132 1.031 0.290 0.152 0.016 0.001 0.0 2.653 SSW 0.001 0.030 0.624 0.421 0.097 0.053 0.002 0.0 0.0 1.228 SW 0.001 0.018 0.370 0.339 0.065 0.027 0.003 0.001 0.0 0.825 WSW 0.001 0.015 0.456 0.767 0.380 0.331 0.056 0.001 0.0 2. 007 W 0.0 0.006 0.220 0.644 0.697 0.651 0.138 0.016 0.0 2. 372 WNW 0.0 0.007 0.140 0.444 0.518 1.008 0.637 0.152 0.009 2.914 NW 0.0 0.008 0.090 0.316 0.436 0.815 0.617 0.093 0O.011 2.385 NNW 0.0 0.005 0.134 0.363 0.480 1.196 0.568 0.033 0.001 2.780 Sub total. 0.015 0.279 7.365 8.989 6.192 7.710 2.636 0.334 0.022 33.543 Total hours of valid stability observations - 103468 Total hours of stability class D - 34636 Total hours of valid wind direction-wind speed-stability class D - 34315 Total hours of valid wind direction-wind speed-stability observations - 102303 Metecrological 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 = 6.51 mph

ODCM Revision 0017 Page 149 of 208 Table 7.3 (5 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class E (-0.5 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =-24.5 Total N 0.005 0.075 0.430 0.529 0.404 0.371 0.062 0.003 0.0 1. 379 NNE 0.006 0.084 0.506 0.580 0.497 0.413 0.031 0.002 0.0 2. 119 NE 0.006 0.113 0.494 0.491 0.369 0.193 0.009 0.0 0.0 1. 674 ENE 0.007 0.109 0.642 0.417 0.160 0.037 0.005 0.001 0.0 1. 380 E 0.008 0.071 0.744 0.677 0.174 0.065 0.004 0.0 0.0 1. 744 ESE 0.009 0.099 0.821 0.772 0.350 0.121 0.002 0.0 0.0 2.174 SE 0.022 0.2 68 1.942 1.323 0.679 0.328 0.017 0.0 0.0 4.579 SSE 0.013 0.197 1.120 0.695 0.367 0.251 0.030 0.001 0.0 2. 675 S 0.012 0.161 1.016 0.688 0.494 0.559 0.084 0.003 0.0 3.)16 SSW 0.007 0.114 0.547 0.221 0.098 0.101 0.005 0.0 0.0 1.0'93 SW 0.004 0.084 0.2 92 0.082 0.023 0.013 0.0 0.0 0.0 0.498 WSW 0.007 0.060 0.641 0.514 0.109 0.098 0.019 0.0 0.0 1.448 W 0.005 0.044 0.463 0.676 0.299 0.152 0.016 0.0 0.0 1. 656 WNW 0.002 0.025 0.168 0.153 0.133 0.158 0.053 0.004 0.0 0.697 NW 0.002 0.037 0.183 0.259 0.176 0.271 0.080 0.006 0.0 1.0)14 NNW 0.004 0.060 0.392 0.508 0.459 0.530 0.085 0.004 0.001 2.0)44 Sub total 0.119 1.603 10.402 8.586 4.791 3.663 0.500 0.023 0.001 29.689 Total hours of valid stability observations - 103468 Total hours of stability class E - 30806 Total hours of valid wind direction-wind speed-stability class E - 30373 Total hours of valid wind direction-wind speed-stability observations - 1023)3 Metecrological 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 = 4.61 mph

ODCM Revision 0017 Page 150 of .208 Table 7.3 (6 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class F (1.5 < Delta-T < 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 _' 24.5 Total N 0.012 0.113 0.450 0.449 0.240 0.056 0.0 0.0 0.0 1. 319 NNE 0.013 0.144 0.499 0.572 0.324 0.094 0.0 0.0 0.0 1.646 NE 0.009 0.114 0.334 0.238 0.122 0.016 0.0 0.0 0.0 0.333 ENE 0.014 0.121 0.564 0.301 0.038 0.004 0.0 0.0 0.0 1.)42 E 0.018 0.052 0.831 0.499 0.014 0.0 0.0 0.0 0.0 1. 413 ESE 0.012 0.071 0.536 0.119 0.006 0.004 0.0 0.0 0.0 0.749 SE 0.025 0.209 1.021 0.359 0.146 0.066 0.003 0.001 0.0 1.331 SSE 0.014 0.123 0.573 0.309 0.173 0.184 0.018 0.002 0.0 1.395 S 0.008 0.077 0.315 0.218 0.224 0.223 0.013 0.001 0.0 1.0)78 SSW 0.003 0.052 0.108 0.027 0.008 0.007 0.0 0.0 0.0 0.205 SW 0.003 0.030 0.110 0.014 0.003 0.001 0.0 0.0 0.0 0.161 WSW 0.003 0.027 0. 109 0.038 0.001 0.002 0.0 0.0 0.0 0.L81 W 0.003 0.026 0.098 0.062 0.006 0.003 0.0 0.0 0.0 0.197 WNW 0.002 0.028 0.080 0.023 0.007 0.005 0.0 0.0 0.0 0..146 NW 0.003 0.033 0.109 0.042 0.022 0.009 0.0 0.0 0.0 0.:218 NNW 0.008 0.072 0.302 0.276 0.164 0.044 0.0 0.0 0.0 0.8366 Sub total 0.151 1.295 6.040 3.544 1.497 0.716 0.033 0.004 0.0 13.280 Total hours of valid stability observations - 103468 Total hours of stability class F - 13774 Total hours of valid wind direction-wind speed-stability class F - 13586 Total hours of valid wind direction-wind speed-stability observations - 102303 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 = 3.60 mph

ODCM Revision 0017 Page 151 of 208 Table 7.3 (7 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 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 Dir 0.023 0.178 0.699 0.277 0.043 0.002 0.0 0.0 0.0 1.221 N

NNE 0.025 0.190 0.752 0.550 0.166 0.012 0.0 0.0 0.0 1.694 0.118 0.369 0.073 0.021 0.001 0.0 0.0 0.0 0.594 NE 0.013 ENE 0.015 0.084 0.492 0.168 0.013 0.001 0.0 0.0 0.0 0.773 0.013 0.029 0.471 0.280 0.001 0.0 0.0 0.0 0.0 0.794 E

ESE 0.004 0.020 0.121 0.005 0.0 0.0 0.0 0.0 0.0 0.149 0.106 0.373 0.069 0.047 0.010 0.0 0.0 0.0 0.618 SE 0.013 0.095 0.467 0.326 0.120 0.052 0.0 0.0 0.0 1.075 SSE 0.015 0.005 0.068 0 .111 0.128 0.065 0.029 0.0 0.0 0.0 0.407 S

0.002 0.036 0.034 0.002 0.0 0.0 0.0 0.0 0.0 0.074 SSW 0.025 0.015 0.003 0.0 0.0 0.0 0.0 0.0 0.044 SW 0.001 WSW 0. 001 0.012 0.016 0.002 0.0 0.0 0.0 0.0 0.0 0.030 0.012 0.019 0.003 0.0 0.0 0.0 0.0 0.0 0.034 W 0.001 WNW 0.001 0.020 0.028 0.001 0.0 0.0 0.0 0.0 0.0 0.050 NW 0.003 0.039 0.061 0.003 0.0 0.0 0.0 0.0 0.0 0.105 0.007 0.086 0.200 0.075 0.022 0.001 0.0 0.0 0.0 0.392 NNW Sub total 0.140 1.117 4.228 1.966 0.498 0.108 0.0 0.0 0.0 8.055 Total hours of valid stability observations - 103468 Total hours of stability class G - 8384 Total hours of valid wind direction-wind speed-stability class G - 8241 Total hours of valid wind direction-wind speed-stability observations - 102303 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 = 2.95 mph

ODCM Revision 0017 Page 152 of .208 Table 7.3 (8 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 I- 24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.3 NNE 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. )

ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. D E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. D ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. )

SE 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0. 0 0. D0o SSE 0.0 0.0 0.002 0.002 0.0 0.0 0.001 0.0 0.0 0. )05 S 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.D SSW 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0. 301 SW 0.0 0.0 0.0 0.002 0.003 0.002 0.002 0.0 0.0 0.309 WSW 0.0 0.0 0.002 0.001 0.0 0.0 0.002 0.0 0.001 0.306 W 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.302 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0 .301 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.3 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0 . 301 Sub total 0.0 0.0 0.005 0.006 0.004 0.004 0.006 0.0 0.001 0.326 Total hours of valid stability observations - 103166 Total hours of stability class A - 27 Total hours of valid wind direction-wind speed-stability class A - 26 Total hours of valid wind direction-wind speed-stability observations - 101803 Metecrological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 95.63 meter level Mean wind speed = 8.66 mph

ODCM Revision 0017 Page 153 of 208 Table 7.3 (9 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class B (-1.9 < Delta-T _ -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir 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 0.3 NNE 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.0 0.0 0. 002 NE 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.001 0.0 0.0 0.002 0.0 0.0 0.0 0.003 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 0.001 0.003 0.001 0.005 0.004 0.001 0.0 0.015 SE 0.0 0.0 0.008 0.007 0.002 0.002 0.001 0.0 0.0 0.020 SSE 0.0 0.0 0.008 0.005 0.002 0.0 0.0 0.0 0.0 0.015 S 0.0 0.0 0.001 0.002 0.002 0.0 0.0 0.0 0.0 0.305 SSW 0.0 0.0 0.001 0.005 0.001 0.004 0.0 0.0 0.0 0. o11 SW 0.0 0.0 0.003 0.016 0.010 0.013 0.007 0.002 0.0 0.350 WSW 0.0 0.0 0.002 0.009 0.004 0.008 0.003 0.0 0.002 0.028 W 0.0 0.0 0.0 0.0 0.004 0.008 0.013 0.004 0.001 0.329 WNW 0.0 0.0 0.0 0.0 0.002 0.002 0.001 0. 001 0.0 0.006 NW 0.0 0.0 0.0 0.0 0.000 0.001 0.0 0.0 0.0 0 .301 NNW 0 .0 0.0 0.0 0.0 0.000 0.0 0.0 0.0 0.0 0.0 Sub total 0.0 0.0 0.025 0.048 0.028 0.045 0.028 0.008 0.003 0.185 Total hours of valid stability observations - 103166 Total hours of stability class B - 190 Total hours of valid wind direction-wind speed-stability class B - 188 Total. hours of valid wind direction-wind speed-stability observations - 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.57 mph

ODCM Revision 0017 Page 154 of 208 Table 7.3 (10 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class C (-1.7 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >- 24.5 TDtal N 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.002 NNE 0.0 0.0 0.0 0.0 0.002 0.0 0.002 0.001 0.0 0.005 NE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0.003 ENE 0.0 0.0 0.001 0.001 0.0 0.003 0.004 0.0 0.0 0. 009 E 0.0 0.0 0.0 0.002 0.002 0.003 0.0 0.0 0.001 0.008 ESE 0.0 0.0 0.003 0.009 0.008 0.020 0.013 0.003 0. 001 0.056 SE 0.0 0.0 0.018 0.056 0.022 0.015 0.004 0.0 0.0 0.114 SSE 0.0 0.001 0.018 0.027 0.010 0.005 0.0 0.0 0.0 0.060 S 0.0 0.0 0.011 0.013 0.007 0.002 0.0 0.0 0.0 0.032 SSW 0.0 0.0 0.010 0.008 0.004 0.011 0.002 0.0 0.0 0.034 SW 0.0 0.0 0. 019 0.045 0.028 0.038 0.019 0.003 0.0 0.152 WSW 0.0 0.0 0.010 0.037 0.033 0.038 0.021 0.005 0.001 0.145 W 0.0 0.0 0.002 0.014 0.022 0.058 0.034 0.011 0.014 0.154 WNW 0.0 0.0 0.002 0.0 0.011 0.035 0.031 0.010 0.005 0.094 NW 0.0 0.0 0.0 0.001 0.001 0.001 0.017 0.001 0.001 0.022 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.002 Sub total 0.0 0.001 0.092 0.212 0.150 0.232 0.148 0.034 0.023 0.B93 Total hours of valid stability observations - 103166 Total hours of stability class C - 916 Total hours of valid wind direction-wind speed-stability class C - 909 Total hours of valid wind direction-wind speed-stability observations - 1018D3 Metecrological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.90 mph

ODCM Revision 0017 Page 155 of 208 Table 7.3 (11 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class D (-1.5 < Delta-T < 0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 _ 24.5 Total N 0.001 0.010 0.100 0.270 0.468 1.721 1.698 0.468 0.062 4.797 NNE 0.001 0.020 0.098 0.258 0.455 1.685 1.334 0.211 0.020 4.081 NE 0.0 0.010 0.070 0.203 0.364 0.952 0.438 0.035 0.006 2.079 ENE 0.001 0.009 0.088 0.194 0.221 0.396 0.134 0.023 0.009 1.074 E 0.001 0.009 0.122 0.202 0.206 0.339 0.190 0.042 0.013 1.123 ESE 0.001 0.009 0.173 0.336 0.374 0.844 0.691 0.239 0.058 2.724 SE 0.001 0.015 0.265 0.729 0.712 1.364 1.288 0.804 0.337 5.516 SSE 0.002 0.018 0.319 0.581 0.568 1.442 1.293 0.551 0.249 5.021 S 0.001 0.009 0.277 0.491 0.463 1.321 1.336 0.738 0.300 4 .936 SSW 0.001 0.015 0.222 0.348 0.344 0.935 0.914 0.423 0.166 3.368 SW 0.001 0.013 0.254 0.453 0.340 0.760 0.712 0.219 0.091 2.844 WSW 0.001 0.009 0.194 0.556 0.397 0.641 0.541 0.246 0.093 2 .679 W 0.001 0.008 0.129 0.525 0.630 1.103 0.759 0.316 0.173 3.643 WNW 0.001 0.004 0.108 0.262 0.497 1.481 1.124 0.608 0.260 4 .345 NW 0.001 0.012 0.121 0.298 0.458 1.244 1.380 0.842 0.219 4.573 NNW 0.001 0.010 0.098 0.201 0.312 1.184 1.4 67 0.534 0.117 3.924 Sub total 0.015 0.177 2.639 5.907 6.808 17.412 15.297 6.299 2.172 56.727 Total hours of valid stability observations - 103166 Total hours of stability class D - 58662 Total hours of valid wind direction-wind speed-stability class D - 57750 Total hours of valid wind direction-wind speed-stability observations - 1018)3 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.90 mph

ODCM Revision 0017 Page 156 of 208 Table 7.3 (12 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class E (0.5 < Delta-T < 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 > 24.5 Total N 0.001 0.013 0.066 0.099 0.149 0.537 0.735 0.139 0.005 1.744 NNE 0.001 0.007 0.061 0.080 0.134 0.614 0.836 0.202 0.002 1.936 NE 0.002 0O.011 0.075 0.107 0.161 0.640 0.686 0.176 0.001 1.a58 ENE 0.001 0.006 0.063 0.103 0.122 0.443 0.328 0.071 0.005 1.142 E 0.002 0.010 0.097 0.162 0.199 0.461 0.173 0.026 0.003 1.133 ESE 0.003 0.014 0.129 0.179 0.252 0.671 0.696 0.173 0.027 2.143 SE 0.003 0.009 0.152 0.381 0.429 1.259 1.286 0.609 0.282 4.411 SSE 0.003 0.019 0.150 0.369 0.465 1.114 1.080 0.550 0.256 4.006 S 0.003 0.015 0.143 0.293 0.365 0.927 0.975 0.369 0.108 3.199 SSW 0.002 0.014 0.116 0.155 0.188 0.595 0.712 0.215 0.024 2.021 SW 0.002 0.008 0.083 0.139 0.193 0.606 0.631 0.117 0.022 1.799 WSW 0.002 0.006 0.086 0.135 0.169 0.493 0.359 0.047 0.014 1.310 W 0.001 0.007 0.071 0.132 0.190 0.469 0.271 0.041 0.003 1.184 WNW 0.002 0.013 0.079 0.143 0.184 0.474 0.206 0.033 0.002 1.136 NW 0.002 0.012 0.084 0.159 0.162 0.378 0.282 0.089 0.004 1.173 NNW 0.002 0.009 0.079 0.099 0.165 0.372 0.443 0.092 0.001 1.202 Sub total 0.032 0.170 1.533 2.736 3.466 10.055 9.698 2.950 0.757 31.398 Total hours of valid stability observations - 103166 Total hours of stability class E - 32314 Total hours of valid wind direction-wind speed-stability class E - 31964 Total hours of valid wind direction-wind speed-stability observations - 1018D3 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.74 mph

ODCM Revision 0017 Page 157 of 208 Table 7.3 (13 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class F (1.5 < Delta-T < 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 > 24.5 Total N 0.001 0.004 0.010 0.026 0.032 0.099 0.181 0.063 0.0 0.415 NNE 0.001 0.003 0.014 0.024 0.019 0.129 0.342 0.181 0.0 0.711 NE 0.001 0.001 0.024 0.029 0.033 0.173 0.346 0.215 0.001 0.823 ENE 0.001 0.002 0.015 0.031 0.045 0.188 0.277 0.097 0.0 0.656 E 0.002 0.003 0.034 0.051 0.086 0.220 0.116 0.003 0.001 0.516 ESE 0.002 0.003 0.038 0.073 0.121 0.341 0.274 0.030 0.001 0.883 SE 0.001 0.006 0.027 0.059 0.121 0.353 0.357 0.031 0.004 0.958 SSE 0.001 0.0 0.028 0.045 0.078 0.287 0.225 0.022 0.001 0.687 S 0.001 0.003 0.030 0.051 0.075 0.194 0.225 0.028 0.0 0.607 SSW 0.001 0.001 0.021 0.042 0.052 0.168 0.212 0.062 0.0 0.559 SW 0.001 0.004 0.026 0.029 0.046 0.168 0.191 0.033 0.0 0.498 WSW 0.001 0.002 0.016 0.031 0.050 0.139 0.144 0.002 0.0 0.386 W 0. 001 0.009 0.012 0.04 7 0.036 0.096 0.042 0.002 0.0 0.245 WNW 0.001 0.002 0.013 0.033 0.038 0.070 0.033 0.0 0.0 0.190 NW 0.001 0.005 0.024 0.039 0.030 0.052 0.016 0.003 0.0 0.170 NNW 0.001 0.004 0.029 0.021 0.025 0.057 0.053 0.018 0.0 0.208 Sub total 0.017 0.051 0.360 0.633 0.888 2.733 3.033 0.791 0.008 8.513 Total. hours of valid stability observations - 103166 Total. hours of stability class F - 8738 Total hours of valid wind direction-wind speed-stability class F - 8666 Total hours of valid wind direction-wind speed-stability observations - 101803 Metecrological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.66 mph

ODCM Revision 0017 Page 158 of 208 Table 7.3 (14 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >-24.5 Total N 0.0 0.005 0.004 0.003 0.004 0.021 0.038 0.006 0.0 0. 381 NNE 0.0 0.0 0.002 0.002 0.005 0.041 0.087 0.029 0.002 0.169 NE 0.0 0.001 0.010 0.009 0.007 0.062 0.119 0.061 0.003 0.271 ENE 0.0 0.003 0.006 0.009 0.009 0.060 0.088 0.020 0.001 0. 196 E 0.0 0.002 0.011 0.007 0.018 0.089 0.035 0.004 0.0 0.166 ESE 0.0 0.0 0.009 0.024 0.028 0.062 0.055 0.005 0.0 0.183 SE 0.0 0.002 0.013 0.026 0.043 0.118 0.045 0.006 0.0 0.253 SSE 0.0 0.001 0.010 0.020 0.027 0.114 0.082 0.001 0.0 0.254 S 0.0 0.0 0.010 0.019 0.037 0.077 0.038 0.001 0.0 0.182 SSW 0.0 0.0 0.006 0.015 0.021 0.049 0.040 0.005 0.0 0.136 SW 0.0 0.001 0.011 0.013 0.028 0.028 0.052 0.014 0.0 0.148 WSW 0.0 0.001 0.009 0.013 0.008 0.020 0.024 0.002 0.0 0.)076 W 0.0 0.0 0.006 0.Oil 0.008 0.005 0.004 0.0 0.0 0. 034 WNW 0.0 0.001 0.013 0.009 0.008 0.005 0.001 0.0 0.0 0.0)37 NW 0.0 0.001 0.010 0.012 0. 009 0.002 0.0 0.0 0.0 0.034 NNW 0.0 0.003 0.008 0.009 0.006 0.006 0.009 0.001 0.0 0. 042 Sub total 0.0 0.021 0.136 0.197 0.265 0.758 0.718 0.154 0.006 2.259 Total hours of valid stability observations - 103166 Total hours of stability class G - 2319 Total hours of valid wind direction-wind speed-stability class G - 2300 Total hours of valid wind direction-wind speed-stability observations - 101803 Metecrological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 10.93 mph

ODCM Revision 0017 Page 159 of 208 Table 7.3 (15 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class A (Delta-T < -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir 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 0.002 0.045 0.028 0.004 0.0 0.078 NNE 0.0 0.0 0.0 0.0 0.003 0.044 0.025 0.001 0.0 0.073 NE 0.0 0.0 0.0 0.0 0.002 0O.011 0.003 0.0 0.0 0. 016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.001 E 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0.003 0O.011 0.002 0.0 0.0 0.0 0.017 SE 0.0 0.0 0.001 0.053 0.044 0.009 0.0 0.0 0.0 0.107 SSE 0.0 0.0 0.004 0.046 0.021 0.008 0.0 0.0 0.0 0.378 S 0.0 0.0 0.002 0.033 0.021 0.012 0.0 0.0 0.0 0.D68 SSW 0.0 0.0 0.0 0.010 0.009 0.004 0.0 0.0 0.0 0.D23 SW 0.0 0.0 0.0 0.003 0.003 0.001 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.003 0.010 0.010 0.002 0.0 0.0 0.025 W 0.0 0.0 0.0 0.0 0.004 0.010 0.002 0.001 0.0 0.016 WNW 0.0 0.0 0.0 0.0 0.003 0.017 0.016 0.005 0.0 0.040 NW 0.0 0.0 0.0 0.0 0.002 0.028 0.035 0.002 0.0 0.067 NNW 0.0 0.0 0.0 0.0 0.001 0.017 0.027 0.016 0.0 0. 060 Sub total 0.0 0.0 0.008 0.151 0.137 0.218 0.138 0.028 0.0 0.680 Total hours of valid observations - 101961 Total hours of ground level release - 10832.031 Total hours of stability class A - 718.45 Total hours of ground level stability class A - 693.58 Metecrological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured 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

ODCM Revision 0017 Page 160 of 208 Table 7.3 (16 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class B (-1.9 < Delta-T < -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.42 18.4 24.4 > 24.5 7otal N 0.0 0.0 0.0 0.0 0.006 0.030 0.010 0.002 0.0 0.048 NNE 0.0 0.0 0.0 0.0 0.007 0.035 0.011 0.0 0.0 0.053 NE 0.0 0.0 0.0 0.0 0.003 0.011 0.002 0.0 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 E 0.0 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0.002 0.002 0.002 0.0 0.0 0.0 0.006 SE 0.0 0.0 0.001 0.014 0.007 0.003 0.0 0.0 0.0 0.025 SSE 0.0 0.0 0.001 0.012 0.006 0.008 0.0 0.0 0.0 0.026 S 0.0 0.0 0.001 0.012 0.008 0.004 0.0 0.0 0.0 0.025 SSW 0.0 0.0 0.0 0.006 0.003 0.001 0.002 0.0 0.0 0.012 SW 0.0 0.0 0.0 0.002 0.002 0.002 0.0 0.0 0.0 0.005 WSW 0.0 0.0 0.0 0.004 0.009 0.009 0.003 0.0 0.0 0.024 W 0.0 0.0 0.0 0.0 0.007 0.011 0.006 0.001 0.0 0.025 WNW 0.0 0.0 0.0 0.0 0.005 0.023 0.018 0.013 0.0 0.058 NW 0.0 0.0 0.0 0.0 0.004 0.033 0.021 0.004 0.0 0.062 NNW 0.0 0.0 0.0 0.0 0.002 0.026 0.015 0.002 0.0 0.045 Sub total 0.0 0.0 0.003 0.052 0.072 0.198 0.088 0.022 0.0 0.435 Total hours of valid observations - 101961 Total hours of ground level release - 10832.031 Tota.L hours of stability class B - 618.82 Tota.L hours of ground level stability class B - 443.89 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured 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 n/s

ODCM Revision 0017 Page 161 of 208 Table 7.3 (17 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class C (-1.7 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir 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 0.009 0.033 0.007 0.001 0.0 0.050 NNE 0.0 0.0 0.0 0.001 0.008 0.028 0.006 0.0 0.0 0.043 NE 0.0 0.0 0.0 0.0 0.006 0.011 0.001 0.0 0.0 0.019 ENE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0.003 E 0.0 0.0 0.0 0.0 0.001 0.001 0.001 0.0 0.0 0.003 ESE 0.0 0.0 0.0 0.002 0.002 0.001 0.0 0.0 0.0 0.005 SE 0.0 0.0 0.002 0.012 0.009 0.004 0.001 0.0 0.0 0.028 SSE 0.0 0.0 0.003 0.007 0.005 0.006 0.0 0.0 0.0 0.021 S 0.0 0.0 0.001 0.012 0.009 0.004 0.0 0.0 0.0 0.026 SSW 0.0 0.0 0.0 0.007 0.002 0.001 0.0 0.0 0.0 0O.011 SW 0.0 0.0 0.0 0.002 0.002 0.001 0.001 0.0 0.0 0.006 WSW 0.0 0.0 0.0 0.004 0.009 0.013 0.003 0.001 0.0 0.030 W 0.0 0.0 0.0 0.0 0.008 0.013 0.008 0.004 0.0 0.032 WNW 0.0 0.0 0.0 0.0 0.006 0.028 0.018 0.020 0.0 0.072 NW 0.0 0.0 0.0 0.0 0.007 0.02 9 0.017 0.002 0.001 0.056 NNW 0.0 0.0 0.0 0.0 0.004 0.026 0.014 0.002 0.0 0.046 Sub total 0.0 0.0 0.006 0.049 0.089 0.201 0.076 0.030 0.001 0.452 TotaL hours of valid observations - 101961 TotaL hours of ground level release - 10832.031 TotaL hours of stability class C - 1307.02 Total hours of ground level stability class C - 460.54 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured 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

ODCM Revision 0017 Page 162 of 208 Table 7.3 (18 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Release - Ground Level Portion Stability Class D (-1.5 < Delta-T _ -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir 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 0.009 0.050 0.182 0.098 0.023 0.001 0.362 NNE 0.0 0.0 0.0 0.010 0.057 0.178 0.04 6 0.007 0.0 0.297 NE 0.0 0.0 0.0 0.008 0.038 0.068 0.005 0.0 0.0 0.119 ENE 0.0 0.0 0.0 0.011 0.018 0.016 0.001 0.0 0.0 0.047 E 0.0 0.0 0.001 0.022 0.031 0.022 0.003 0.0 0.0 0.078 ESE 0.0 0.0 0.002 0.028 0.032 0.014 0.0 0.0 0.0 0.075 SE 0.0 0.0 0.027 0.117 0.114 0.082 0.004 0.0 0.0 0.344 SSE 0.0 0.0 0.035 0.091 0.052 0.061 0.004 0.0 0.0 0.244 S 0.0 0.0 0.034 0.097 0.059 0.064 0.014 0.001 0.0 0.269 SSW 0.0 0.0 0.014 0.042 0.018 0.026 0.002 0.0 0.0 0.102 SW 0.0 0.0 0.003 0.010 0.005 0.007 0.002 0.001 0.0 0.028 WSW 0.0 0.0 0.004 0.036 0.049 0.065 0.028 0.001 0.0 0.183 W 0.0 0.0 0.001 0.023 0.070 0.103 0.053 0.014 0.0 0.263 WNW 0.0 0.0 0.0 0.003 0.036 0.154 0.164 0.107 0.009 0.472 NW 0.0 0.0 0.0 0.003 0.033 0.126 0.173 0.073 0.011 0.418 NNW 0.0 0.0 0.0 0.007 0.041 0.196 0.157 0.027 0.001 0.428 Sub total 0.0 0.0 0.122 0.517 0.701 1.363 0.753 0.253 0.022 3.732 TotaL hours of valid observations - 101961 Total hours of ground level release - 10832.031 TotaL hours of stability class D - 54573.199 Total hours of ground level stability class D - 3804.72 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity - 12.60 m/s

ODCM Revision 0017 Page 163 of 208 Table 7.3 (19 of 28)

SPLIT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class E (0.5 < Delta-T _ 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 _>-24.5 Total N 0.0 0.0 0.005 0.040 0.054 0.064 0.021 0.002 0.0 0.185 NNE 0.0 0.0 0.008 0.048 0.068 0.071 0.010 0.001 0.0 0.206 NE, 0.0 0.001 0.008 0.044 0.051 0.033 0.003 0.0 0.0 0.140 ENE 0.0 0.001 0.014 0.037 0.023 0.007 0.003 0.001 0.0 0.087 E 0.0 0.0 0.015 0.060 0.024 0.012 0.001 0.0 0.0 0.113 ESE 0.0 0.001 0.021 0.068 0.049 0.022 0.001 0.0 0.0 0.162 SE 0.0 0.004 0.094 0.167 0.122 0.107 0.014 0.0 0.0 0.507 SSE 0.0 0.002 0.070 0 .111 0.106 0.164 0.030 0.001 0.0 0.485 S 0.0 0.003 0.068 0.100 0.112 0.281 0.077 0.003 0.0 0.643 SSW 0.0 0.001 0.027 0.033 0.020 0.050 0.005 0.0 0.0 0.135 SW 0.0 0.0 0.007 0.008 0.004 0.006 0.0 0.0 0.0 0.025 WSW 0.0 0.0 0.016 0.043 0.016 0.023 0.013 0.0 0.0 0.111 W 0.0 0.0 0.009 0.049 0.038 0.027 0.006 0.0 0.0 0.129 WNW 0.0 0.0 0.001 0.008 0.015 0.026 0.015 0.003 0.0 0.069 NW 0.0 0.0 0.001 0.015 0.021 0.046 0.025 0.005 0.0 0.112 NNW 0.0 0.0 0.004 0.035 0.059 0.092 0.024 0.004 0.001 0.219 Sub total 0.0 0.014 0.368 0.865 0.784 1.029 0.248 0.020 0.001 3.328 Tota:L hours of valid observations - 101961 Tota:L hours of ground level release - 10832.031 Tota:L hours of stability class E - 32478.371 Total hours of ground level stability class E - 3393.06 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

ODCM Revision 0017 Page 164 of 208 Table 7.3 (20 of 28)

SPLINT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class F (1.5 < Delta-T < 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Total N 0.0 0.0 0.014 0.051 0.038 0.010 0.0 0.0 0.0 0.112 NNE 0.0 0.001 0.016 0.068 0.051 0.017 0.0 0.0 0.0 0.152 NE 0.0 0.002 0.012 0.030 0.020 0.003 0.0 0.0 0.0 0.066 ENE 0.0 0.004 0.018 0.031 0.006 0.001 0.0 0.0 0.0 0.061 E 0.0 0.001 0.017 0.034 0.002 0.0 0.0 0.0 0.0 0.054 ESE 0.0 0.002 0.019 0.010 0.001 0.001 0.0 0.0 0.0 0.032 SE 0.0 0.005 0.064 0.052 0.030 0.036 0.002 0.001 0.0 0.191 SSE 0.0 0.005 0.050 0.056 0.060 0.138 0.017 0.002 0.0 0.328 S 0.0 0.003 0.028 0.035 0.054 0.121 0.013 0.001 0.0 0.255 SSW 0.0 0.002 0.007 0.005 0.002 0.003 0.0 0.0 0.0 0.019 SW 0.0 0.001 0.004 0.001 0.001 0.0 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.004 0.003 0.0 0.0 0.0 0.0 0.0 0.008 W 0.0 0.0 0.003 0.006 0.001 0.001 0.0 0.0 0.0 0.010 WNW 0.0 0.0 0.002 0.002 0.001 0.001 0.0 0.0 0.0 0.006 NW 0.0 0.0 0.002 0.004 0.003 0.002 0.0 0.0 0.0 0.010 NNW 0.0 0.0 0.007 0.031 0.025 0.008 0.0 0.0 0.0 0.071 Sub total 0.0 0.027 0.265 0.418 0.296 0.340 0.032 0.004 0.0 1.383 TotaL hours of valid observations - 101961 TotaL hours of ground level release - 10832.031 TotaL hours of stability class F - 9482 Tota:L hours of ground level stability class F - 1410.51 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s

ODCM Revision 0017 Page 165 of 208 Table 7.3 (21 of 28)

SPLIT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Total N 0.0 0.0 0.020 0.034 0.007 0.0 0.0 0.0 0.0 0.062 NNE 0.0 0.001 0.022 0.071 0.028 0.002 0.0 0.0 0.0 0.123 NE 0.0 0.001 0.009 0.010 0.004 0.0 0.0 0.0 0.0 0.023 ENE 0.0 0.002 0.008 0.011 0.002 0.0 0.0 0.0 0.0 0.024 E 0.0 0.0 0.009 0.007 0.0 0.0 0.0 0.0 0.0 0.016 ESE 0.0 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.0 0.006 SE 0.0 0.004 0.027 0.012 0.013 0.007 0.0 0.0 0.0 0.062 SSE 0.0 0.003 0.053 0.065 0.044 0.041 0.0 0.0 0.0 0.206 S 0.0 0.002 0.011 0.022 0.016 0.016 0.0 0.0 0.0 0.067 SSW 0.0 0.001 0 .001 0.0 0.0 0.0 0.0 0.0 0.0 0.002 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. 001 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. 001 W 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 WNW 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 NW 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 NNW 0.0 0.0 0.005 0.009 0.003 0.0 0.0 0.0 0.0 0.017 Sub total 0.0 0.014 0.174 0.242 0.116 0.066 0.0 0.0 0.0 0.614 Total hours of valid observations - 101961 TotaL hours of ground level release - 10832.031 TotaL hours of stability class G - 2783.14 Total hours of ground level stability class G - 625.73 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

ODCM Revision 0017 Page 166 of 208 Table 7.3 (22 of 28)

SPLIT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class A (Delta-T _ -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Tctal 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 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSE 0.0 0.0 0.003 0.002 0.0 0.0 0.001 0.0 0.0 0.006 S 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 SSW 0.0 0.0 0.002 0.001 0.002 0.0 0.0 0.0 0.0 0.005 SW 0.0 0.0 0.0 0.003 0.002 0.002 0.001 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.001 0.001 0.002 0.0 0.0 0.0 0.004 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 0.001 0.0 0.0 0..0 0.001 Sub total 0.0 0.0 0.007 0.007 0.005 0.004 0.002 0.0 0.0 0.024 Total hours of valid observations - 101961 Total hours of elevated releases - 91128.969 Total hours of stability class A - 718.45 TotaL hours of elevated stability class A - 24.87 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

ODCM Revision 0017 Page 167 of 208 Table 7.3 (23 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class B (-1.9 < Delta-T < -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 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 0.001 0.0 0.2 0.0 0.0 0.0 0.001 NE 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 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 0.001 0.002 0.004 0.001 0.0 0.0 0.008 SE 0.0 0.0 0.010 0.008 0.0 0.004 0.0 0.0 0.0 0.021 SSE 0.0 0.0 0.007 0.009 0.001 0.0 0.0 0.0 0.0 0.017 S 0.0 0.0 0.005 0.008 0.004 0.0 0.0 0.0 0.0 0.017 SSW 0.0 0.0 0.004 0.010 0.005 0.009 0.001 0.0 0.0 0.028 SW 0.0 0.0 0.0 0.022 0.007 0.007 0.001 0.0 0.0 0.036 WSW 0.0 0.0 0.0 0.002 0.006 0. 009 0.001 0.0 0.0 0.018 W 0.0 0.0 0.0 0.0 0.006 0.007 0.006 0.002 0.0 0.020 WNW 0.0 0.0 0.0 0.001 0.0 0.002 0.002 0.0 0.0 0.004 NW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 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 0.025 0.062 0.029 0.042 0.010 0.002 0.0 0.172 Tota:L hours of valid observations - 101961 TotaL hours of elevated releases - 91128.969 TotaL hours of stability class B - 618.82 TotaL hours of elevated stability class B - 174.930 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

ODCM Revision 0017 Page 168 of 208 Table 7.3 (24 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class C (-1.7 < Delta-T c -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Total N 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 NNE 0.0 0.0 0.0 0.0 0.003 0.003 0.001 0.001 0.0 0.007 NE 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.0 0.0 0.0 0.003 0.002 0.0 0.0 0.005 E 0.0 0.0 0.0 0.002 0.004 0.003 0.0 0.0 0.0 0.008 ESE 0.0 0.0 0.0 0.007 0.008 0.012 0.002 0.0 0.0 0.029 SE 0.0 0.0 0.030 0.063 0.010 0 .011 0.001 0.0 0.0 0.116 SSE 0.0 0.0 0.020 0.054 0.007 0.004 0.0 0.0 0.0 0.084 S 0.0 0.0 0.027 0.025 0.010 0.001 0.0 0.0 0.0 0.063 SSW 0.0 0.0 0.010 0.030 0.021 0.009 0.001 0.0 0.0 0.071 SW 0.0 0.0 0.011 0.063 0.040 0.022 0.003 0.0 0.0 0.139 WSW 0. 0 0.0 0.002 0.025 0.028 0.046 0.006 0.0 0.0 0.108 W 0.0 0.0 0.001 0.004 0.031 0.057 0.015 0.008 0.0 0.117 WNW 0.0 0.0 0.0 0.003 0.003 0.030 0.025 0.003 0.0 0.064 NW 0.0 0.0 0.0 0.002 0.002 0.002 0.010 0.0 0.0 0.015 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.002 Sub total 0.0 0.0 0.101 0.278 0.166 0.206 0.066 0.013 0.0 0.830 TotaL hours of valid observations - 101961 TotaL hours of elevated releases - 91128.969 Total hours of stability class C - 1307.02 Total hours of elevated stability class C - 846.48 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 and direction measured at 45.67 meter level Effluent velocity = 12.60 m/s

ODCM Revision 0017 Page 169 of 208 Table 7.3 (25 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class D (-1.5 < Delta-T _ -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Total N 0.0 0.005 0.120 0.359 0.577 1.660 1.059 0.135 0.003 3.919 NNE 0.0 0.017 0.129 0.416 0.719 1.926 0.915 0.070 0.001 4.193 NE 0.0 0.016 0.124 0.358 0.469 0.904 0.153 0.008 0.0 2.032 ENE 0.0 0.012 0.122 0.245 0.244 0.260 0.034 0.003 0.0 0.920 E 0.0 0.018 0.124 0.219 0.245 0.298 0.088 0.008 0.0 0.999 ESE 0.001 0.010 0.224 0.499 0.561 0.822 0.138 0.005 0.0 2.260 SE 0.002 0.025 0.753 1.509 0.945 1.586 0.834 0.143 0.006 5.803 SSE 0.002 0.036 0.520 0.8 67 0.705 1.411 0.981 0.277 0.013 4.811 S 0.001 0.012 0.417 0.769 0.603 1.197 1.036 0.320 0.022 4.376 SSW 0.001 0.017 0.240 0.524 0.409 0.792 0.479 0.119 0.006 2.586 SW 0.001 0.016 0.322 0.749 0.425 0.620 0.297 0.053 0.002 2.484 WSW 0.001 0.010 0.178 0.604 0.505 0.575 0.279 0.053 0.001 2.204 W 0.0 0.008 0.111 0.482 0.701 1.163 0.432 0.086 0.004 2.985 WNW 0.0 0.008 0.107 0.330 0.481 1.140 0.823 0.246 0.009 3.145 NW 0.0 0.007 0.110 0.382 0.535 1.281 1.115 0.289 0.007 3.726 NNW 0.0 0.013 0.117 0.277 0.400 1.264 1.092 0.181 0.005 3.348 Sub total 0.012 0.227 3.715 8.588 8.524 16.899 9.754 1.994 0.080 4S'.792 TotaL hours of valid observations - 101961 Total hours of elevated release - 91128.969 Total hours of stability class D - 54573.199 Total hours of elevated stability class D - 50768.48 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

ODCM Revision 0017 Page 170 of 208 Table 7.3 (26 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class E (-0.5 < Delta-T _ 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Tctal N 0.001 0.019 0.146 0.239 0.369 0.794 0.160 0.001 0.0 1.729 NNE 0.001 0.019 0.159 0.273 0.374 0.935 0.228 0.003 0.0 1.992 NE 0.001 0.021 0.138 0.271 0.320 0.713 0.133 0.002 0.0 1.598 ENE 0.002 0.018 0.179 0.260 0.298 0.407 0.057 0.0 0.0 1.221 E 0.001 0.007 0.111 0.283 0.338 0.558 0.046 0.003 0.0 1.347 ESE 0.003 0.019 0.299 0.587 0.719 0.866 0.069 0.004 0.0 2.566 SE 0.005 0.034 0.558 1.105 1.027 1.327 0.446 0.064 0.004 4.570 SSE 0.003 0.021 0.293 0.612 0.522 0.938 0.659 0.156 0.010 3.214 S 0.002 0.018 0.207 0.453 0.335 0.779 0.437 0.075 0.003 2.309 SSW 0.001 0.014 0.167 0.304 0.277 0.519 0.212 0.020 0.001 1.514 SW 0.002 0.013 0.213 0.331 0.321 0.342 0.102 0.014 0.001 1.337 WSW 0.001 0.015 0.162 0.290 0.256 0.291 0.040 0.005 0.0 1.061 W 0.001 0.007 0.113 0.280 0.316 0.347 0.051 0.001 0.0 1.114 WNW 0.001 0.015 0.082 0.183 0.205 0.243 0.038 0.003 0.0 0.771 NW 0.001 0.012 0.107 0.179 0.183 0.294 0.111 0.003 0.0 0.890 NNW 0.001 0.014 0.109 0.192 0.256 0.563 0.154 0.004 0.0 1.293 Sub total 0.026 0.262 3.043 5.843 6.115 9.916 2.942 0.359 0.018 28.526 Total hours of valid observations - 101961 Total hours of elevated release - 91128.969 Total hours of stability class E - 32478.371 Total hours of elevated stability class E - 29085.311 MeteDrological 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

ODCM Revision 0017 Page 171 of 208 Table 7.3 (27 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class F (1.5 < Delta-T _ 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Ž24.5 Total N 0.001 0.002 0.035 0.082 0.066 0.306 0.038 0.0 0.0 0.530 NNE 0.001 0.002 0.038 0.088 0.097 0.438 0.144 0.0 0.0 0.808 NE 0.001 0.005 0.041 0.115 0.135 0.349 0.102 0.0 0.0 0.748 ENE 0.001 0. 009 0.037 0.103 0.149 0.255 0.057 0.0 0.0 0.612 E 0.001 0.003 0.031 0.084 0.133 0.269 0.023 0.001 0.0 0.545 ESE 0.003 0.008 0.115 0.243 0.294 0.183 0.002 0.0 0.0 0.848 SE 0.004 0.009 0.162 0.410 0.274 0.177 0.005 0.001 0.0 1.041 SSE 0.002 0.011 0.088 0.147 0.127 0.161 0.022 0.001 0.0 0.559 S 0.002 0.008 0.079 0.120 0.122 0.171 0.023 0.0 0.0 0.525 SSW 0.001 0.013 0.057 0.119 0.121 0.140 0.010 0.0 0.0 0.461 SW 0.001 0.008 0.061 0.101 0.093 0.063 0.0 0.0 0.0 0.327 WSW 0.001 0.004 0.043 0.072 0.080 0.047 0.001 0.0 0.0 0.248 W 0.001 0.007 0.037 0.063 0.063 0.047 0.001 0.0 0.0 0.219 WNW 0.001 0.005 0.026 0.047 0.029 0.024 0.0 0.0 0.0 0.133 NW 0.001 0.005 0.033 0.047 0.029 0.016 0.002 0.0 0.0 0.132 NNW 0.001 0.006 0.025 0.032 0.043 0.068 0.005 0.0 0.0 0.179 Sub total 0.022 0.103 0.910 1.873 1.855 2.717 0.434 0.003 0.0 7.916 Total hours of valid observations - 101961 TotaL hours of elevated release - 91128.969 TotaL hours of stability class F - 9482 TotaL hours of elevated stability class F - 8071.49 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

ODCM Revision 0017 Page 172 of 208 Table 7.3 (28 of 28)

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 224.5 Total N 0.0 0.0 0.007 0.023 0.022 0.064 0.002 0.0 0.0 0.118 NNE 0.0 0.001 0.013 0.025 0.045 0.130 0.051 0.0 0.0 0.264 NE 0.0 0.002 0.018 0.021 0.051 0.122 0.021 0.0 0.0 0.234 ENE 0.0 0.003 0.005 0.017 0.027 0.071 0.010 0.0 0.0 0.133 E 0.0 0.001 0.003 0.019 0.013 0.043 0.002 0.0 0.0 0.082 ESE 0.001 0.006 0.048 0.103 0.054 0.016 0.0 0.0 0.0 0.229 SE 0.003 0.005 0.107 0.219 0.107 0.035 0.0 0.0 0.0 0.475 SSE 0.001 0.005 0.045 0.064 0.038 0.025 0.0 0.0 0.0 0.177 S 0.001 0.002 0.026 0.040 0.035 0.011 0.0 0.0 0.0 0.116 SSW 0.0 0.003 0.012 0.014 0.030 0.023 0.001 0.0 0.0 0.083 SW 0.0 0.006 0.009 0.008 0.028 0.012 0.0 0.0 0.0 0.063 WSW 0.0 0.001 0.013 0.008 0.0 0.001 0.0 0.0 0.0 0.023 W 0.0 0.0 0.014 0.011 0.005 0.004 0.0 0.0 0.0 0.033 WNW 0.0 0.002 0.009 0.004 0.005 0.002 0.0 0.0 0.0 0.022 NW 0.0 0.006 0.005 0.010 0.008 0.003 0.0 0.0 0.0 0.031 NNW 0.0 0.0 0.012 0.010 0.005 0.007 0.0 0.0 0.0 0.034 Sub total 0.006 0.042 0.344 0.592 0.471 0.568 0.087 0.0 0.0 2.116 Total hours of valid observations - 101961 Tota:L hours of elevated release - 91128.969 TotaL hours of stability class G - 2783.14 TotaL hours of elevated stability class G - 2157.41 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

ODCM Revision 0017 Page 173 of 208 Table 7.4 NOBLE GAS DOSE FACTORS Submersion dose Air dose mrem/y per pCi/m3 mrad/y per pCi/m 3 DFBi DFSi DFyi DFj~i Ar-4L 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Kr-8:3m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-885 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-8!3 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-1:31m 9.15E+01 4.76E+02 1.56E+02 1.llE+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-1:35 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-1:38 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Refe:^ence:

Regulatory Guide 1.109, Table B-1.

Finite Cloud Dose Factors mrad/y per pCi/s (Bi) or mrem/y per pCi/s (Vi)

Highest Site Boundary Highest Site Boundary Highest Offsite Location Ground Vent Releases Split Level Vent Elevated Vent Releases NNW Sector at 1650 m Releases N Sector NW Sector at 8500 m at 1525 m Bi vi Bi Vi Bi vi Ar-41 1.30E-03 1.50E-03 1.63E-03 1.87E-03 2.71E-04 3.12E-04 Kr-83m 1.08E-05 1.23E-05 1.31E-05 1.48E-05 2.25E-06 2.55E-016 Kr-85m 7.29E-05 8.57E-05 9.38E-05 1.10E-04 1.52E-05 1.78E-C15 Kr-85 2.68E-04 3.11E-04 3.34E-04 3.88E-04 5.56E-05 6.46E-0'5 Kr- 87 8.46E-04 9.72E-04 1.11E-03 1.28E-03 1.76E-04 2.02E-04 Kr- 8:3 1.84E-03 2.09E-03 2.42E-03 2.75E-03 3.82E-04 4.34E-04 Kr-89 1.89E-03 2.17E-03 2.49E-03 2.86E-03 3.94E-04 4.51E-04 Kr-90 1.17E-03 1.36E-03 1.54E-03 1.78E-03 2.44E-04 2.83E-014 Xe-1:31m 5.87E-05 6.67E-05 7.10E-05 8.08E-05 1.22E-05 1.39E-05 Xe-133m 9.91E-05 1.14E-04 1.22E-04 1.41E-04 2.06E-05 2.37E-05 Xe-133 1.34E-04 1.52E-04 1.61E-04 1.83E-04 2.78E-05 3.15E-05 Xe-1:35m 7.20E-04 8.4 3E-04 9.31E-04 1.09E-03 1.50E-04 1.75E-04 Xe-135 4.73E-04 5.54E-04 6.01E-04 7.05E-04 9.83E-05 1.15E-04 Xe-137 6.74E-04 7.68E-04 8.87E-04 1.01E-03 1.40E-04 1.60E-04 Xe-1.38 1.24E-03 1.43E-03 1.63E-03 1.87E-03 2.59E-04 2. 97E-04

Reference:

TVA generated values.

ODCM Revision 0017 Page 174 of 208 Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1 - 2 miles 1.5 miles 2 - 3 miles 2.5 miles 3 - 4 miles 3.5 miles 4 - 5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 miles

ODCM Revision 0017 Page 175 of 208 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT Distance Range 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 38 0 0 82 133 1338 2887 3172 11844 4190 NNE 0 12 23 155 54 1516 2756 4551 3827 4236 NE 0 3 23 44 123 4560 13356 7431 7554 13S72 ENE 0 38 86 102 44 1750 9232 30963 18076 7866 E 0 0 23 7 32 1586 15764 48934 90006 6'83 ESE 0 0 12 0 0 123 2466 5115 26482 11164 SE 0 0 0 0 0 8435 22086 7344 8313 21440 SSE 0 0 0 0 0 2483 30555 13272 21617 202:44 S 0 0 10 12 46 1525 4758 2533 6218 5550 SSW 0 0 33 40 188 1345 6369 1160 2570 4703 SW 0 0 0 15 111 847 5719 2470 3460 131.38 WSW 0 0 10 19 73 244 3461 2895 13472 4772 W 0 84 15 8 17 79 3761 10877 29784 5845 WNW 0 0 4 8 27 36 1970 7936 49335 5307 NW 0 0 76 9 60 826 4145 7270 6059 4242 NNW 0 189 183 63 79 1381 2332 2958 15381 10031

ODCM Revision 0017 Page 176 of 208 Table 7.7 (1 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT Nucl:ide bone liver t body thyroid kidney lung gi-lli H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-21 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.OOE+00 0.OOE+00 0.00E+00 1.08E-05 Cr-5l 0.OOE+00 0.OOE+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.OOE+00 4.95E-06 7.87E-07 0.OOE+00 1.23E-06 1.75E-04 9.67E-06 Mn-565 0.OOE+00 1.55E-10 2.29E-11 0.OOE+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.OOE+00 0.OOE+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.OOE+00 0.OOE+00 1.27E-04 2.35E-05 Co-57 O.OOE+00 8.65E-08 8.39E-08 0.OOE+00 0.OOE+00 4.62E-05 3.93E-06 Co-5:3 0.OOE+00 1.98E-07 2.59E-07 0.OOE+00 0.OOE+00 1.16E-04 1.33E-05 Co-60 0.OOE+00 1.44E-06 1.85E-06 0.OOE+00 0.OOE+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.OOE+00 0.OOE+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.OOE+00 O.OOE+00 7.00E-07 1.54E-06 Cu-6l 0.OOE+00 1.83E-10 7.69E-11 0.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.OOE+00 8.62E-06 1.08E-04 6.68E-06 Zn-63 4.23E-12 8.14E-12 5.65E-13 0.OOE+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.OOE+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.OOE+00 0.OOE+00 1.69E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.30E-06 Br-83 0.OOE+00 0.OOE+00 3.01E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.90E-08 Br-84 0.OOE+00 0.OOE+00 3.91E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.05E-13 Br-85 0.OOE+00 0.OOE+00 1.60E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Rb-86 0.OOE+00 1.69E-05 7.37E-06 0.OOE+00 0.OOE+00 0.OOE+00 2.08E-*06 Rb-83 0.OOE+00 4.84E-08 2.41E-08 0.OOE+00 0.OOE+00 0.OOE+00 4.18E-*19 Rb-89 0.OOE+00 3.20E-08 2.12E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.16E--21 Sr-89 3.80E-05 0.OOE+00 1.09E-06 0.OOE+00 0.OOE+00 1.75E-04 4.37E--05 Sr-90 1.24E-02 0.OOE+00 7.62E-04 0.OOE+00 0.OOE+00 1.20E-03 9.02E--05 Sr-91 7.74E-09 0.OOE+00 3.13E-10 0.OOE+00 0.OOE+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.OOE+00 0.OOE+00 2.06E-06 5.38E--06 Y-90 2.61E-07 O.OOE+00 7.01E-09 0.OOE+00 0.OOE+00 2.12E-05 6.32E--05 Y-91n 3.26E-11 0.OOE+00 1.27E-12 0.OOE+00 0.OOE+00 2.40E-07 1.66E--10 Y-91 5.78E-05 0.OOE+00 1.55E-06 0.OOE+00 0.OOE+00 2.13E-04 4.81E--05 Y-92 1.29E-09 O.OOE+00 3.77E-11 O.OOE+00 0.00E+00 1.96E-06 9.19E--06 Y-93 1.18E-08 0.OOE+00 3.26E-10 0.OOE+00 0.OOE+00 6.06E-06 5.27E--05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.OOE+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.OOE+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.OOE+00 9.67E-07 6.31E-05 1.30E--05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.OOE+00 8.18E-12 3.OOE-07 3.02E*-08 Mo-99 0.OOE+00 1.51E-08 2.87E-09 0.OOE+00 3.64E-08 1.14E-05 3.10E--05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.OOE+00 1.35E-13 4.99E-08 1.36E--21 Ru-103 l.91E-07 0.OOE+00 8.23E-08 0.OOE+00 7.29E-07 6.31E-05 1.38E--05 Ru-105 9.88E-11 0.OOE+00 3.89E-11 0.OOE+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.OOE+00 1.09E-06 0.OOE+00 1.67E-05 1.17E-03 1.14E-04 Ag-llOm 1.35E-06 1.25E-06 7.43E-07 0.OOE+00 2.46E-06 5.79E-04 3.78E*-05

ODCM Revision 0017 Page 177 of 208 Table 7.7 (2 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.OOE+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.OOE+00 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 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-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-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-08 2.69E-08 2.02E-08 2.37E-08 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 0.OOE+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.OOE+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.OOE+00 5.08E-08 I-13:3 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.OOE+00 1.l1E-06 1-131 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.OOE+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.OOE+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.OOE+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.OOE+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.OOE+00 6.OOE-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.OOE+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.OOE+00 0.OOE+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.OOE+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.OOE+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.OOE+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.OOE+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.OOE+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.OOE+00 0.OOE+00 3.63E-06 1.94E-05 Np-2 3 9 2.87E-08 2.82E-09 1.55E-09 0.OOE+00 8.75E-09 4.70E-06 1.49E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 8.

All others:

Regulatory Guide 1.109, Table E-7.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 178 of 208 Table 7.7 (3 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN Nucl:ide bone liver t body thyroid kidney lung gi-lli H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-241 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.16E-05 Cr-51 0.OOE+00 0.OOE+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.OOE+00 6.39E-06 1.05E-06 0.OOE+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.OOE+00 2.12E-10 3.15E-11 0.OOE+00 2.24E-10 1.90E-06 7.18E-06 Fe-5-5 4.18E-06 2. 98E-06 6.93E-07 0.OOE+00 0.OOE+00 1.55E-05 7.99E-07 Fe-59 l.99E-06 4. 62E-06 1.79E-06 0.OOE+00 0.OOE+00 l.91E-04 2.23E-05 Co-57 0.OOE+00 1.18E-07 1.15E-07 0.OOE+00 0.OOE+00 7.33E-05 3.93E-06 Co-5:3 0.OOE+00 2.59E-07 3.47E-07 0.OOE+00 0.OOE+00 1.68E-04 1.19E-05 Co-6E) O.OOE+00 1.89E-06 2.48E-06 0.OOE+00 0.OOE+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.OOE+00 0.OOE+00 3.84E-05 1.77E-06 Ni-6;5 2.73E-10 3.66E-11 1.59E-11 0.OOE+00 0.OOE+00 1.17E-06 4.59E-06 Cu-64 0.OOE+00 2.54E-10 1.06E-10 0.OOE+00 8.01E-10 1.39E-06 7. 68E-06 Zn-6.; 4.82E-06 1.67E-05 7.80E-06 0.OOE+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.OOE+00 7.53E-12 1.98E-07 3.56E-08 Zn-63m 1.44E-09 3.39E-09 3.11E-10 0.OOE+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.OOE+00 0.OOE+00 2.28E-06 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE400 Br-8:3 0.OOE+00 0.OOE+00 4.30E-08 0.OOE+00 0.OOE+00 0.OOE+00 O.0OE400 Br-84 0.OOE+00 0.OOE+00 5.41E-08 O.OOE+00 0.OOE+00 0.OOE+00 0.00E400 Br-85 0.00E+00 0.OOE+00 2.29E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E400 Rb-8,; 0.OOE+00 2.38E-05 1.05E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.21E-06 Rb-8:3 O.OOE+00 6.82E-08 3.40E-08 0.OOE+00 0.OOE+00 0.OOE+00 3.65E-15 Rb-89 O.00E+00 4.40E-08 2.91E-08 0.OOE+00 0.OOE+00 0.OOE+00 4.22E-17 Sr-89 5.43E-05 0.OOE+00 1.56E-06 0.OOE+00 0.OOE+00 3.02E-04 4. 64E-05 Sr-90 1.35E-02 0.OOE+00 8.35E-04 0.OOE+00 0.OOE+00 2.06E-03 9.56E-05 Sr-9L 1.10E-08 0.OOE+00 4.39E-10 0.OOE+00 0.OOE+00 7.59E-06 3.24E-05 Sr-992 1.19E-09 0.OOE+00 5.08E-11 0.OOE+00 0.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.OOE+00 1. OOE-08 0.OOE+00 0.OOE+00 3.66E-05 6.99E-OS Y-91in 4. 63E-11 0.OOE+00 1.77E-12 0.OOE+00 0.OOE+00 4.OOE-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.OOE+00 0.OOE+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.OOE+00 0.OOE+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4. 65E-10 0.OOE+00 0.OOE+00 1.04E-05 7.24E-05 Zr-9!5 1.82E-05 5.73E-06 3.94E-06 0.OOE+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.OOE+00 5.15E-09 1.62E-05 7.88E-*05 Nb- 95 2.32E-06 1.29E-06 7.08E-07 0.OOE+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.OOE+00 1.14E-11 4.91E-07 2.71E-07 Mo- 99 0.OOE+00 2.11E-08 4.03E-09 0.OOE+00 5.14E-08 1.92E-05 3.36E--05 Tc-99m 1.73E-13 4. 83E-13 6.24E-12 0.OOE+00 7.20E-12 1.44E-07 7. 66E--07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.OOE+00 1.90E-13 8.34E-08 1.09E--16 Ru-103 2.63E-07 0.OOE+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E--05 Ru-105 1.40E-10 0.OOE+00 5.42E-11 0.OOE+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.OOE+00 1.55E-06 0.OOE+00 2.38E-05 2.01E-03 1.20E-*04 Ag-llOm 1.73E-06 1.64E-06 9.99E-07 0.OOE+00 3.13E-06 8.44E-04 3.41E-05

ODCM Revision 0017 Page 179 of 208 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN Nucl:ide bone liver t body thyroid kidney lung gi-lli Sb-12:4 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.OOE+00 3.42E-04 1.24E-05 Te-125m 6.1OE-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-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 9.1OE-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-11 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-1:31 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2. 92E-07 1.89E-09 Te-1:32 4.50E-08 3. 63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8. 65E-07 0.OOE+00 1.59E-07 I-13:3 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.4 9E-06 0.OOE+00 1.29E-06 I-134 l.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.OOE+00 2.55E-09 I-135 4. 62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.OOE+00 8.69E-07 Cs-1i34 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-1i36 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-1:37 8.38E-05 1.06E-04 3.89E-05 0.OOE+00 3.80E-05 1.51E-05 1.06E-06 Cs-1:38 5.82E-08 1.07E-07 5.58E-08 0.OOE+00 8.28E-08 9.84E-09 3.38E-l1 Ba-1:39 1.67E-10 1.18E-13 4.87E-12 0.OOE+00 1.llE-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.OOE+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.OOE+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4. 62E-12 4. 63E-15 2.84E-13 0.OOE+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2. 95E-08 7.82E-09 0.00E+00 0.OOEE+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.OOE+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2. 37E-06 2.71E-07 0.00E+00 1.1E-06 7. 67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.OOE+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2. 53E-04 3.28E-05 0. OOE+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6. 64E-07 8.28E-08 0. OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.OOE+00 1.26E-12 2.19E-07 2.94E-*14 Nd-1i47 9.83E-07 1.07E-06 6.41E-08 0.OOE+00 6.28E-07 4. 65E-05 2.28E-05 W- 187 1.50E-09 1.22E-09 4.29E-10 0.OOE+00 0.OOE+00 5.92E-06 2.21E-05 Np-2:39 4.23E-08 3. 99E-09 2.21E-09 0.OOE+00 1.25E-08 8.11E-06 1.65E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Yezr Chronic Intake, November 1977, Table 7.

All others:

Regulatory Guide 1.109, Table E-8.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 180 of 208 Table 7.7 (5 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD Nucl:ide bone liver t body thyroid kidney lung gi-lli H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-291 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.OOE+00 O.OOE+00 0.OOE+00 1.14E-05 Cr-5L 0.OOE+00 0.OOE+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.OOE+00 1.16E-05 2.57E-06 0.OOE+00 2.71E-06 4.26E-04 6.19E-06 Mn-5-5 0.OOE+00 4.48E-10 8.43E-11 0.OOE+00 4.52E-10 3.55E-06 3.33E-05 Fe-5.5 1.28E-05 6.80E-06 2.10E-06 0.OOE+00 0.OOE+00 3.OOE-05 7.75E-07 Fe-53 5. 59E-06 9.04E-06 4.51E-06 0.OOE+00 0.OOE+00 3.43E-04 l.91E-05 Co-57 0.OOE+00 2.44E-07 2.88E-07 0.OOE+00 0.OOE+00 1.37E-04 3.58E-06 Co-53 0.OOE+00 4.79E-07 8.55E-07 0.0OE+00 0.OOE+00 2.99E-04 9.29E-06 Co-60 0.OOE+00 3.55E-06 6.12E-06 0.OOE+00 0.OOE+00 1.91E-03 2. 60E- 05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.OOE+00 0. O0E+00 7.43E-05 1.71E-06 Ni-6;5 8.08E-10 7. 99E-11 4.44E-1l 0.OOE+00 0.OOE+00 2.21E-06 2.27E- 05 Cu-61 0.OOE+00 5.39E-10 2.90E-10 0.OOE+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.OOE+00 1.93E-05 2. 69E-04 4.41E-06 Zn-63 1.81E-11 2.61E-l1 2.41E-12 0.OOE+00 1.58E-11 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.OOE+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.OOE+00 0.OOE+00 5.66E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Br-83 0.OOE+00 0.OOE+00 1.28E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Br-84 0.OOE+00 0.OOE+00 1.48E-07 0.OOE+00 0.OOEE+00 0.OOE+00 0.OOE-00 Br-8.5 0.OOE+00 0.OOE+00 6.84E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-00 Rb-86 0.OOE+00 5.36E-05 3.09E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.16E-06 Rb-83 0.OOE+00 1.52E-07 9. 90E-08 0.OOE+00 0.OOE+00 0.OOE+00 4. 66E-*09 Rb-83 0.OOE+00 9.33E-08 7.83E-08 0.OOE+00 0.OOE+00 0.OOE+00 5.11E-10 Sr-83 1.62E-04 0.OOE+00 4. 66E-06 0.OOE+00 0.OOE+00 5.83E-04 4.52E-05 Sr-93 2.73E-02 0.OOE+00 1.74E-03 0.OOE+00 0.OOE+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.OOE+00 1.24E-09 0.OOE+00 0.OOE+00 1.44E-05 4.70E-05 Sr-9.2 3.54E-09 0.OOE+00 1.42E-10 0.OOE+00 0.OOE+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.OOE+00 2.99E-08 0.OOE+00 0.OOE+00 7.07E-05 7.24E--05 Y-91:n 1.37E-10 0.OOE+00 4.98E-12 0.OOE+00 0.OOE+00 7.60E-07 4. 64E--07 Y-91 2.47E-04 0.OOE+00 6.59E-06 0.OOE+00 0.OOE+00 7.10E-04 4.97E--05 Y-92 5.50E-09 0.OOE+00 1.57E-10 0.OOE+00 0.OOE+00 6.46E-06 6.46E--05 Y-93 5.04E-08 0.OOE+00 1.38E-09 0.OOE+00 0.OOE+00 2. 01E-05 1.05E--04 Zr-95 5.13E-05 1.13E-05 1.OOE-05 0.OOE+00 1.61E-05 6.03E-04 1.65E--05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.OOE+00 1.05E-08 3.06E-05 9.49E--05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.OOE+00 2.33E-06 1.66E-04 1.OOE--05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.OOE+00 2.31E-ll 9.23E-07 7.52E-06 Mo-99 0.OOE+00 4. 66E-08 1.15E-08 0.OOE+00 1.06E-07 3.66E-05 3.42E--05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.OOE+00 1.37E-l1 2.57E-07 1.30E*-06 Tc-101 2.19E-14 2.30E-14 2. 91E-13 0.OOE+00 3.92E-13 1.58E-07 4.41E--09 Ru-103 7.55E-07 0.OOE+00 2. 90E-07 0.OOE+00 1.90E-06 1.79E-04 1.21E*-05 Ru-105 4.13E-10 0.OOE+00 1.50E-10 0.OOE+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.OOE+00 4.57E-06 0.OOE+00 4.97E-05 3.87E-03 1.16E--04 Ag-lOrm 4.56E-06 3.08E-06 2.47E-06 O.OOE+00 5.74E-06 1.48E-03 2.71E--05

ODCM Revision 0017 Page 181 of 208 Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD Nucl:Lde bone liver t body thyroid kidney lung gi-lli Sb-124 1.55E-05 2.OOE-07 5.41E-06 3.41E-08 0.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.OOE+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.OOE+00 1.29E-04 9.13E-06 Te-1127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 l.91E-09 2.71E-06 1.52E-05 Te-1:29m 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-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 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-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-131) 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.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 0.OOE+00 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.OOE+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.OOE+00 1.20E-06 Cs-1;34 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 0.OOE+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.OOE+00 7.63E-05 2.81E-05 9.78E-07 Cs-1:38 1.71E-07 2.27E-07 1.50E-07 0.OOE+00 1.68E-07 1.84E-08 7.29E-08 Ba-1:39 4.98E-10 2.66E-13 1.45E-11 0.OOE+00 2.33E-13 1.56E-06 1.56E-*05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 0.OOE+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.OOE+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.OOE+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.OOE+00 0.OOE+00 4.94E-05 6.10E-05 La-1Q2 3.50E-10 1.11E-10 3.49E-11 0.OOE+00 0.OOE+00 2.35E-06 2.05E--05 Ce-ill 1.06E-05 5.28E-06 7.83E-07 0.OOE+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 O.OOE+00 2.26E-08 3.12E-05 3.44E--05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.OOE+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.OOE+00 8.11E-07 1.17E-04 2.63E--05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.OOE+00 2.64E-12 4.23E-07 5.32E--08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.OOE+00 1.30E-06 8.87E-05 2.22E--05 W-187 4.41E-09 2.61E-09 1.17E-09 0.OOE+00 0.OOE+00 1.11E-05 2.46E--05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.OOE+00 2.63E-08 1.57E-05 1.73E--05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 6.

All others:

Regulatory Guide 1.109, Table E-9.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 182 of 208 Table 7.7 (7 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT Nucl:Lde bone liver t body thyroid kidney lung gi-lli H-3 4. 62E-07 4. 62E-07 4. 62E-07 4.62E-07 4. 62E-07 4. 62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3. 79E-06 Na-21 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.OOE+00 0.00E+00 0.OOE+00 l.1SE-05 Cr-51 0.OOE+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.OOE+00 1.81E-05 3.56E-06 0.OOE+00 3.56E-06 7.14E-04 5.04E-06 Mn-5, 0.00E+00 1.10E-09 1.58E-10 0.OOE+00 7.86E-10 8. 95E-06 5.12E-05 Fe -55 1.41E-05 8.39E-06 2.38E-06 0.OOE+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9. 69E-06 1.68E-05 6.77E-06 0.OOE+00 0.OOE+00 7.25E-04 1.77E-05 Co-557 0.OOE+00 4. 65E-07 4.58E-07 0.OOE+00 0.OOE+00 2.71E-04 3.47E-06 Co-53 0.OOE+00 8.71E-07 1.30E-06 0.OOE+00 0.OOE+00 5.55E-04 7.95E-06 Co-60) 0.OOE+00 5.73E-06 8.41E-06 0.OOE+00 0.OOE+00 3.22E-03 2.28E-05 Ni-63 2. 42E-04 1.46E-05 8.29E-06 0.OOE+00 0.OOE+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-ll 0.OOE+00 0.OOE+00 5.80E-06 3.58E-05 Cu-61 0.00E+00 1.34E-09 5.53E-10 0.OOE+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.OOE+00 2.32E-05 4. 62E-04 3.67E-05 Zn-63 3.85E-ll 6.91E-ll 5.13E-12 0.OOE+00 2.87E-ll 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.OOE+00 7.45E-09 l.91E-05 2.92E-05 Br-82 0.OOE+00 0.OOE+00 9.49E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.00E400 Br-8:3 0.OOE+00 0.OOE+00 2.72E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.00EI00 Br-84 0.00E+00 0.OOE+00 2.86E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.00E4-00 Br-8 5 0.OOE+00 0.00E+00 1.46E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.00E400 Rb-85 0.OOE+00 1.36E-04 6.30E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.17E-06 Rb-83 0.OOE+00 3.98E-07 2.05E-07 0.OOE+00 0.OOE+00 0.00E+00 2.42E-07 Rb-89 0.OOE+00 2.29E-07 1.47E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.87E-08 Sr-8,3 2.84E-04 0.OOE+00 8.15E-06 0.OOE+00 0.OOE+00 1.45E-03 4.57E-05 Sr-9') 2.92E-02 0.OOE+00 1.85E-03 0.OOE+00 0.OOE+00 8.03E-03 9.36E-05 Sr-9L 6.83E-08 0.OOE+00 2.47E-09 0.OOE+00 0.OOE+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.OOE+00 2.79E-10 0.OOE+00 0. OOE+00 1.70E-0S 1. OOE- 04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.OOE+00 0.OOE+00 1.92E-04 7.43E-05 Y-91in 2.91E-10 0.OOE+00 9.90E-12 0.OOE+00 0.OOE+00 l.99E-06 1.68E-06 Y-91 4.20E-04 0.OOE+00 1.12E-05 0.OOE+00 0.OOE+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.OOE+00 0.OOE+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.OOE+00 2. 91E-09 0.OOE+00 0.OOE+00 5.46E-05 l.19E-04 Zr-95 8.24E-05 l.99E-05 1.45E-05 0.OOE+00 2.22E-05 1.25E-03 1.55E-'05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.OOE+00 1.85E-08 7.88E-05 1.00E--04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.OOE+00 3.37E-06 3.42E-04 9.05E--06 Nb-97 2.44E-10 5.21E-ll 1.88E-ll 0.OOE+00 4.07E-ll 2.37E-06 1.92E--05 Mo-93 0.OOE+00 1.18E-07 2.31E-08 0.OOE+00 1.89E-07 9.63E-05 3.48E--05 Tc-99m 9.98E-13 2.06E-12 2.66E-ll 0.OOE+00 2.22E-ll 5.79E-07 1.45E--06 Tc-101 4. 65E-14 5.88E-14 5.80E-13 0.OOE+00 6.99E-13 4.17E-07 6.03E-.07 Ru-103 1.44E-06 0.OOE+00 4.85E-07 0.OOE+00 3.03E-06 3.94E-04 1.15E--05 Ru-105 8.74E-10 0.OOE+00 2.93E-10 0.OOE+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.OOE+00 7.77E-06 0.OOE+00 7.61E-05 8.26E-03 1.17E--04 Ag-lOrm 7.13E-06 5.16E-06 3.57E-06 O.OOE+00 7.80E-06 2.62E-03 2.36E-*05

ODCM Revision 0017 Page 183 of 208 Table 7.7 (8 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.OOE+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-1:31m 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-11 5.87E-12 3.57E-12 1.13E-11 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 0.OOE+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.OOE+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.OOE+00 1.36E-06 I-13:3 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 0.OOE+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.OOE+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.OOE+00 1.31E-06 Cs-1:34 2.83E-04 5.02E-04 5.32E-05 0.OOE+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.OOE+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+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 0.OOE+00 4.23E-13 4.25E-06 3.64E-05 Ba-1410 4.OOE-05 4.OOE-08 2.07E-06 0.OOE+00 9.59E-09 1.14E-03 2.74E-05 Ba-1411 1.12E-10 7.70E-14 3.55E-12 0.OOE+00 4.64E-14 2.12E-06 3.39E-06 Ba-1412 2.84E-11 2.36E-14 1.40E-12 0.OOE+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.OOE+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.OOE+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.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-1.34 2.28E-03 8.65E-04 1.26E-04 O.OOE+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.OOE-05 3.74E-06 4.99E-07 0.OOE+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.OOE+00 4.80E-12 1.15E-06 3.06E--06 Nd-117 5.67E-06 5.81E-06 3.57E-07 0.OOE+00 2.25E-06 2.30E-04 2.23E--05 W-187 9.26E-09 6.44E-09 2.23E-09 0.OOE+00 0.00E+00 2.83E-05 2.54E--05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.OOE+00 4.73E-08 4.25E-05 1.78E--05 Refecence:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 5.

All others:

Regulatory Guide 1.109, Table E-10.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

ODCM Revision 0017 Page 184 of 208 Figure 7.1 OFFGAS SYSTEM AND STANDBY GAS TREATMENT SYSTEM EFFLUENT MONITORING Elevated Release (600 feet) t from common stack Steam Packing Exhauster Mechnaical Vacuum Pump Charcoal Adsorber Vessels

ODCM Revision 0017 Page 185 of 208 Figure 7.2 NORMAL BUILDING VENTILATION ROOF FANS I A I I I I I II II ..... I I

q Turbine Dock l 90-9 l RMX9-251 R,-

RM025 RM 90-22l A5 I1 Fro Prnr Contain=en From Purge System Redwaste Building Turbine Building Control Reactor Building to SGTS (Typical for each unit) Bay (typical for each unit) (emergency ventilaton) r Used seasonally to control temperature

ODCM Revision 0017 Page 186 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page I of 4)

Ili ft i:

j 52 II IL 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Plume Doepltion Effect for Ground-Level Releases (Al Stability Classes)

ODCM Revision 0017 Page 187 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page 2 of 4) m N

9 a.

4.

2.

CL.

0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Plume DepIeton Effect t 30 meter Releases (Letters danote Pasqull StabUy aCS)

ODCM Revision 0017 Page 188 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page 3 of 4)

1. __LSTABL W e =e = _i3 NEPTFM 1 0.7 2 0 _____

0.4 CL 0.2 0.1 1.0 10.0 10C).0 200.0 PLUME TRAVEL DISTANCE (kilomneters)

Plume Depletion Effect for 60 meter Releaeas (Letters denote Pasquill Stabi ty Class)

ODCM Revision 0017 Page 189 of 208 Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4) 0.8

-Ii 0.7 f.

tJ.

0.5 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

P[Lkne Deplton Effect for 100 meter Refases (Letters denote Pasquil Stabity Class)

ODCM Revision 0017 Page 190 of 208 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME LU I-LU

{).1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)

Vertical Standard Deviation of Material in a Plume (Letters denote Pasquill Stability Class)

ODCM Revision 0017 Page 191 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 1 of 4)

. cow I 1-I I

,IE-O' IEl0 1E-7 0.

1.0 FI~

.1 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Rebave Deposton fo Grotnd-Level Relases (A Atmcwphbec Stabllfty Classes)

ODCM Revision 001.7 Page 192 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 2 of 4)

'U.

w

= 10, gtO 0

'U w

io0 -L 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Plume Deplefion Effec fo 30 metr Releaw (Lettzrs donate PlugW Stabdty aas)

ODCM Revision 0017 Page 193 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4) 1.-3 Ew I&

II To Ea Ui c)

C).I 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Plm Doploebtn Etotd for 60 meter ReoIsxs (Letters dmowt PequiM Stbehy Clas)

ODCM Revision 0017 Page 194 of 208 Figure 7.5 RELATIVE DEPOSITION (Page 4 of 4) 16.3 le 09

.o5 10-5 w

t 9-J 10

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

Plume Deplbion Effed 1o 00 me*r Releasd (Letter derste Paquill SIb)t Clae)

. I

ODCM Revision 0017 Page 195 of 208 SECTION 8.0 TOTAL DOSE

ODCM Revision 0017 Page 196 of 208 8.0 TOTAL DOSE To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by: first, summing the total body air submersion dose, and the maximum (critical) organ dose (except thyroid) from gaseous effluents; the total body dose, and maximum organ dose (except thyroid) from liquid effluents for each quarter calculated in accordance with Sections 6.6 and 7.7. Then to this sum for each quarter is added any identifiable increase in direct radiation dose leveLs attributable to the plant as determined by the REMP outlined in SectLon 9.0. These quarterly sums are then conservatively summed for the four calendar quarters to estimate the maximum individual dose for the year.

This dose is compared to the limit in Control 1.2.3, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.

The :otal annual thyroid dose to the maximum individual will be conservatively estimated in the following manner. For each calendar quarter, a total dose will be obtained by summing the total body gaseous submersion dose, the gaseous thyroid dose, the liquid total body dose, and the :Liquid thyroid dose. To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the REMP outlined in Section 9.0. These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year. This dose is compared to the limit in Control 1.2.3, i.e., 75 mrem per year to determine compliance.

ODCM Revision 001.7 Page 197 of 208 SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

ODCM Revision 0017 Page 198 of 208 9.1 MONITORING PROGRAM DESCRIPTION A Radiological Environmental Monitoring Program (REMP) as described in Tables 9.1, 9.2, and 9.3 and in Figures 9.1, 9.2, and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric REMP shall consist of 11 monitoring stations from which samples of air particulates and radioiodine shall be collected.

The terrestrial monitoring program shall consist of the collection of milk, soil, drinking water, and food crops as provided in Tables 9.1 and 9.2. In addition, direct gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.

9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-2 are achieved.

9.3 'AND USE CENSUS A land use survey shall be conducted in accordance with the requirements in Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC.

A sunmary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report.

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

ODCM Revision 0017 Page 199 of 208 Table 9.1 (1 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sample Locations Collection Frequency of Analysis AIRBORNE Part:-culates 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 224 hrs following site boundary loading but at least filter change.

(LM-1, 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 cf 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-1, 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

ODCM Revision 003.7 Page 200 of 208 Table 9.1 (2 of 5)

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

.sample Locations Collection Frequency of Analysis DIRECT (con- 2 or more dosi- At least once per Gamma dose once per tinued) meters placed at 92 days. 92 days.

stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosi-meters in at least 8 additional locations of special interest WATERBORNE Su::face 1 sample upstream Collected by auto- Gamma scan at (TRM 306.0) matic sequential- least once per 31 1 sample im- type sampler with days. Composite fcr mediately down- composite sample tritium at least orce stream of dis- taken at least once per 92 days charge (TEM 293.5) per 31 daysa.

Drinking 1 sample at the Collected by auto- Gross beta and gamma first potable matic sequential- scan at least once surface water type sampler with per 31 days. Compo-supply downstream composite sample site for from the plant taken at least once tritium at least (TRM 286.5) per 31 daysarb once per 92 days.

a 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 .

b Th:.s assumes that the nearest drinking water intake is >3.0 mile downstream of the plant discharge. If a drinking water intake is constructed with:n 3.0 miles downstream of the plant discharge, sampling and analysis sh.all be every 2 weeks.

ODCM Revision 00'.7 Page 201 of 208 Table 9.1 (3 of 5)

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

_-Sample Locations Collection Frequency of Analysis Drinking 4 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 the plant(TRM 282.A tritium at least once TRM 274.9, per 92 days TRM 259.8, and TRM 259.6) 1 sample Collected by auto-at a control matic sequential-locationc type sampler with (TRM 306) 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 and tritium (well #6) type sampler with at least once per composite sample 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 and tritium upgradient from 31 days. at least once per the plant 92 days.

(Farm B) I AQUAT'IC Shoreline 1 sample At least once per Gamma scan of each Sediment upstream from 184 days sample a recreational area (TRM 305) a 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 .

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

ODCM Revision 0017 Page 202 of 208 Table 9.1 (4 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sample Locations Collection Frequency of Analysis Shoreline 1 sample from At least once per Gamma scan of each Sediment each of at least 184 days sample (c ontinued) two downstream locations with with recreational use. (TRM 293 and 279.5)

INGESTION Milk At least once per Gamma scan and I-1ll 15 days when animals on each sample.

are on pasture; at Sr-89 and Sr-90 at least once per 31 least once per 92 clays days at other times.

- - Samples from milking animals in three locations within 5 km distance having the highest dose potential as identified in the annual land use survey. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. Milk samples will be collected as required by FSAR Section 2.6.2.2. There are currently no locations meeting this criteria; however, a dairy farm between 9 and 15 km is being sampled.

- - - One sample from milking at a control location 15 to 30 km distant and in the least prevalent wind direction. Samples are not required from the control location if no indicator locations are sampled.

Fish 2 samples repre- At least once per Gamma scan at least senting commercial 184 days once per 184 days on and game species edible portions.

in Guntersville Reservoir above the plant 2 samples repres-enting commercial and game species in Wheeler Reservoir near the plant

ODCM Revision 0017 Page 203 of 208 Table 9.1 (5 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sample Locations Collection Frequency of Analysis 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 providing a milk sample.

Control sample from 1 control dairy farm.

Vegetation sampled only if milk is produced but not sampled.

ODCM Revision 001.7 Page 204 of 208 Table 9.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Ma ? Approximate Indicator (I)

Locatio n Distance or Sample.3 Number a Station Sector (Miles) Control (C) Collect(~db 1 PM-1 NW 13.8 I AP, CF, S 2 PM-2 NE 10.9 I AP, CF, S 3 PM-3 SSE 7.5 I AP, CF, S 4 LM-7 W 2.1 I AP, CF, S 5 RM-1 W 31.0 C AP, CF, S 6 RM-6 E 23.4 C AP, CF, S 7 LM-1 NNW 1.0 I AP, CF, S 8 LM-2 NNE 0.9 I AP, CF, S 9 LM-3 ENE 0.9 I AP, CF, S 13 LM-4 NNW 1.7 I AP, CF, S 11 LM-6 SSW 3.0 I AP, CF, S 12 Farm B NNW 6.8 I W 139 Farm R SW 12.5 C M I 22 Well #6 NW 0.02 I W 23 TRMc 282.6 - 1 1 .4 d I PW 24 TRM 306.0 - 1 2 .0 d C PW, SW 25 TRM 259.6 - 3 4 .4 d I PW 2D TRM 274.9 - 19 .1 d I PW 2:3 TRM 293.5 - 0 .5 d I SW 34 Farm Be NW 28.8 C M 7') TRM 259.8 - 34 2. d I PW 7L TRM 286.5 _ .

7 5 d I PW

.72 TRM 305 11 0. d C SS 7.3 TRM 293 1 .0 d I SS 74 TRM 279.5 1 4 .5 d I SS Wheeler Reservoir I/C F (TRM 275-349)

Guntersville Reservoir C F (TFM 349-424) a See Figures 9.1, 9.2, and 9.3 b Sample codes:

AP = Air particulate filter S = Soil SS = Shoreline Sediment CF = Charcoal Filter SW = Surface Water M = Milk

? = Fish V = Vegetation PW = Public Water W = Well Water c TRM = Tennessee River Mile d Miles from plant discharge (TFRM 294)

ODCM Revision 0017 Page 205 of 208 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS Ma ? Approximate Onsite (On)a Location Distance or Numnoer 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 31.0 Off 6 E-3 E 23.1 Off 7 N-1 NNW 1.0 On 8 NNE-1 NNE 0.9 On 9 ENE-1 ENE 0.9 On 13 NNW-2 NNW 1.7 On 33 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 4D ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 4:3 SE-1 SE 0.5 On 49 SE-2 SE 5.4 Off 5') SSE-1 SSE 5.1 Off 51 S-1 S 3.1 Off 5:2 S-2 S 4.8 Off 53 SSW-1 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 5.5 SW-1 SW 1.9 On 5,5 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 513 WSW-1 WSW 2.7 Off 5'3 WSW-2 WSW 5.1 Off

61) WSW-3 WSW 10.5 Off 61 W-1 W 1.9 On 62 W-2 W 4.7 Off 6:3 W-4 W 31.7 Off 641 WNW-1 WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 615 NW-i NW 2.2 Off 67 NW-2 NW 5.3 Off 6:3 NNW-1 NNW 1.0 On 693 NNW-3 NNW 5.2 Off 75 N-1A N 1.0 ON aTLD:5 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.

ODCM Revision 0017 Page 206 of 208 Figure 9.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT 5

1 0

O Mile Mile II

ODCM Revision 001.7 Page 207 of 208 Figure 9.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT

ODCM Revision 0017 Page 208 of 208 Figure 9.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT LASTPAGE

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