Text

Rev 20 to Procedure C-200, Odcm.
	ML17229B036
Person / Time
Site:	Saint Lucie
Issue date:	12/22/1998
From:	WEST R G, WETHY C M; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17229B034	List: ML17229B033; ML17229B035; ML17229B036;
References
	C-200, NUDOCS 9903090181
	Download: ML17229B036 (381)
	v • d • e

Page 1 of 225 FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT CHEMISTRY PROCEDURE NO.C-200 REVISION 20 1.0 TITLE: OFFSITE DOSE CALCULATION MANUAL (ODCM)2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group Approved by C.M.Weth Revision 20 Reviewed by F R G Approved by R.G.West Plant General Manager Plant General Manager 4/22 1982 4/27 1982 12/22 19 98 12/22 1998 THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING.

/R20 99030VOKBi

'P'F0226 PDR ADOCK 05000335l,".<I R POR Q S OPS DATE DOCT PROCEDURE DOCN C-200 SYS COMP COMPLETED ITM 20 Page 2 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX INTRODUCTION CONTROLS SECTION PAGE....7 DEFINITIONS FOR CONTROLS SECTION 1.1 ACTION 1.4 CHANNEL CALIBRATION

....~.,....1.5 CHANNEL CHECK.............

~..1.6 CHANNEL FUNCTIONAL TEST~....~.1.10 DOSE EQUIVALENT 1-131 1.13 FREQUENCY NOTATION...........

1.17 MEMBER(S)OF THE PUBLIC........

1.18 OFFSITE DOSE CALCULATION MANUA 1.19 OPERABLE-OPERABILITY

.........1.20 OPERATIONAL MODE-MODE.......

1.24 PURGE-PURGING 1.25 RATED THERMAL POWER..........

1.27 REPORTABLE EVENT 1.30 SITE BOUNDARY.................

1.31 SOURCE CHECK~...............

~1.33 THERMAL POWER................

1.34 UNPLANNED RELEASE......~.~...1.35 UNRESTRICTED AREA 1.39 VENTILATION EXHAUST TREATMENT 1.40 VENTING....................,..1.41 WASTE GAS HOLDUP SYSTEM..~...~~~0~0~L SYSTEM 3/4.0 APPLICABILITY 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS

~.........

10 10 10 11~0~~~~~~~~~~~~~~11 11 11 12 12 12 12 13 13 14 14 16 16...9..9.9...9~~~9..10 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION

~--D OSE~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~LIQUID RADWASTE TREATMENT.......

~..............

~~~~~~~~17 22 32 36 37 Page 3 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX CONTROLS SECTION CONTROL AND SURVEILLANCE STATEMENTS FOR CONTROL SECTION-PAGE 3/4.11.3 3/4.11.4 3/4.11.5 3/4.11 RADIOACTIVE EFFLUENTS (Continued) 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE..............

DOSE-NOBLE GAS........

DOSE-IODINE-131, IODINE-133, TRITIUMS AND RADIONUCLIDES IN PARTICULATE FORM GASEOUS RADWASTE TREATMENT..........

~....(NOT USED)TOTAL DOSE.....~........MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS SOLID WASTE TREATMENT SYSTEMS (ADMINISTRATIVE CONTROL)3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION (ADMINISTRATIVE CONTROL)..38..42.....43~~~44......46 AND......48~~~~~~49 3/4.12 3/4.12.1 3/4.12.2 3/4.12.3 3/4.12.4 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM......LAND USE CENSUS..........

INTERLABORATORY COMPARISON PROGRAM.......ANNUAL RADIOLOGICAL ENVIRONMENTS,L OPERATING REPORT (ADMINISTRATIVE CONTROL).............

..52..61..63.....64 BASES for CONTROLS SECTION 3/4.11 3.3.3.9 3/4.1 1.1 3/4.11.2 3/4.11.3 3/4.11.4 RADIOACTIVE EFFLUENTS INSTRUMENTATION

.......~..LIQUID EFFLUENTS..........

GASEOUS EFFLUENTS (NOT USED)'OTAL DOSE~~~~~~~~~~~~~~66~~~~~~~~~~~~~67~~~~~~~~~~~69~~~~~~~~~~~~723/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.......3/4.12.2 LAND USE CENSUS.~.~.......3/4.12.3.-

INTERLABORATORY COMPARISON PROGRAM.............74~~~~~~~74~.......75 Page 4 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX CONTROLS SECTION LIST OF FIGURES for CONTROLS SECTION FIGURE PAGE 1-1 SITE AREA MAP&ENVIRONMENTAL SAMPLE LOCATIONS....221 1-2 ENVIRONMENTAL SAMPLE LOCATIONS (10 MILES)~........, 222 LIST OF TABLES for CONTROLS SECTION TABLE 1-1 3.3-12 3.3-13 3.3-14 3.12 1 3.12-2 4.3-8 4.3-9 4.11-1 4.11-2 4.12-1~~~~~~~~~~~~~1 5~~~~~~~1 8..23..27..54..57..20..29~~~~~~~~33~.39..58 FREQUENCY NOTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

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

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

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

~.RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQOIREMENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM..........

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSiS PROGRAM..........

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)........~..,.

Page 5 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX METHODOLOGY SECTION PAGE Glossary for Methodology Section...~.............

~.........77 1.0 LIQUID RELEASES METHODOLOGY

.....1.1 Radioactive Liquid Effluent Model Assumptions

......1.2 Determining the Fraction (F)of 10 CFR Part 20 Effluent Concentration Limits (ECL)for a Liquid Release Source 1.3 Determining Setpoints for Radioactive Liquid Effluent Monitors...,................, 1.4 Determining the Dose for Radioactive Liquid Releases.1.5 Projecting Dose for Radioactive Liquid Effluents.....

~..~.80........81........82~~~~~~~~85~~~~~~~~89~~~~~~~~93 2.0.Radioactive Releases of Gaseous Effluents 2.1 Gaseous Effluent Model Assumptions

............, 2.2 Determining the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing Setpoints for Effluent Monitors..........................

2.3 Determining

the Radioiodine and Particulate Dose Rate to Any Organ From Gaseous Releases............

2.3.1 Inhalation

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

~.............

2.3.2 Ground

Plane.2.3.3 Milk 2~3 e4 Tntl um e~~~~~~2.3.5 Total Dose Rate by Release Source.........

2.4 Determining

the Gamma Air Dose for Radioactive Noble Gas Releases 2.5 Determining the Beta Air Dose for Radioactive.Noble Gas Releases 2.6 Determining the Radioiodine and Particulate Dose to Any Age Group's Organ From Cumulative Releases.DISCUSSION

2.6.1 Inhalation

......~....,.....

2.6.2 Ground

Plane.............

2e6e3 Milk e~~~~~~~~~~~~~~~~~~~~~~e....94....95~~~~~~~~96~..110...112...114 115...117 119 119'f22.....,.124'I 26...127~..128 Page 6 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULAT)ON MANUAL ODCM INDEX METHODOLOGY SECTION PAGE 2.6 2.7 (continued) 2.6.4 Meat.....................

2.6.5 Vegetation

2.6.6 Tritium (All pathways)2.6.7 Total Organ Dose...........

Projecting Dose for Radioactive Gaseous 129~~~~~~~~~~~~~~~1 31~~~~~~~~~~~~~~~~~1 33~~~~~~~~~~~~~~~~~1 34 Effluents.......~..135 3.0 40 CFR 190 Dose Evaluation

..~.136 4.0 Annual Report Format...........

137 Appendix A-ECL, Dose Factor and Historical Meteorological Tables............

Appendix B-Current R.E.M.Sample Point Locations...........

Appendix C-Description of Meteorological Dispersion Formulas Utilized for Historical Data and IVlethodology for Determining Actual MET Data Appendix D-Description of the lnterlaboratory Comparison Program 152~~~~~~~217 223~~~~~~~225 Page 7 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INTRODUCTION The ODCM consists of the Controls Section followed by the Methodology Section.The Controls Section provides the Control Statements, Limits, ACTION Statements, Surveillance Requirements and BASES for ensuring that Radioactive Liquid and Gaseous Effluents released to UNRESTRICTED AREAS and/or the SITE BOUNDARY will be maintained within the requirements of 10 CFR Part 20, 40 CFR Part 190, 10 CFR 50.36.a and 10 CFR Part 50 Appendix-I radioactive release criteria.All Control Statements and most Administrative Control Statements in the ODCM are directly tied to and reference the Plant Technical Specification (TS)Administrative Section.The Administrative Control for Major Changes to Radioactive, Liquid, Gaseous and Solid Treatment Systems is as per the guidance of NUREG-1301, April 1991, Supplement No.1'o NRC Generic Letter 89-01.The numbering sequences of Control Statements also follow the guidance of NUREG-1301 as applicable, to minimize differences.

The Methodology Section uses the models suggested by NUREG-0133, November, 1978 and Regulatory Guide 1.109 to provide calculation methods and parameters for determining results in compliance with the Controls Section of the ODCM.Simplifying assumptions have been applied where applicable to provide a more workable document for implementing the Control requirements.

Alternate calculation methods may be used from those presented as long as the overall methodology does not change or as long as most up-to-date revisions of the Regulatory Guide 1.109 dose conversion factors and environmental transfer factors are substituted for those currently included and used in this document.RECORDS AND NOTIFICATIONS All records of reviews performed for changes to the ODCM shall be maintained in accordance with QI 17-PSL-1.All FRG approved changes to the ODCM, with required documentation of the changes per TS 6.14, shall be submitted to the NRC in the Annual Effluent Release Report.Procedures that directly implement;administer or supplement the requirements of the ODCM Controls and Surveillances are: C-70 Processing Aerated Liquid Waste C-72 Processing Gaseous Wastes COP-05.04, Chemistry Department Surveillances and Parameters COP-07.05, Process Monitor Setpoints The Radiological Environmental Monitoring Program is performed by the State of Florida as per FPL Juno Nuclear Plant Services Corporate Environmental Procedure Number NBS-NPS-HP-WP-002.

Page 8 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM CONTROLS AND SURVEILLANCE REQUIREMENTS St.Lucie Plant ODCM Controls Page 9 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM The defined terms of this section appear in capitalized type and are applicable throughout these Controls.ACTION 1.1 ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 1.4 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.The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST.The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same, parameter.

CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions.

The CHANNEL FUNCTIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the setpoints are within the required range and accuracy.St.Lucie Plant ODCM Controls Page 10 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM DOSE EQUIVALENT I-1'31 1.10 DOSE EQUIVALENT I-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, l-132, l-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 or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977].FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance.of Surveillance-Requirements shall correspond to the intervals defined in Table 1.1.MEMBER S OF THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area.However, an individual is not a member of the public during any period in which the individual receives an occupational dose.OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL-(ODCM)shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints and in the conduct of the Env~ir ental Radiological Monitoring Program.The ODCM shall also contain (1)the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by TS section 6.8.4 and (2)descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 6.9,1.7 and 6,9.1.8.St.Lucie Plant ODCM Controls Page 11 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM OPERABLE-OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power, 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).

OPERATIONAL MODE-MODE 1.20 An OPERATIONAL MODE (i.e., MODE)shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.2 of the St.Lucie Plant TS.PURGE-PURGING 1.24 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.St.Lucie Plant ODCM Controls Page 12 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM SITE BOUNDARY 1.30 SITE BOUNDARY means that line beyond which the land or property is not owned, leased or otherwise controlled by the licensee.SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.THERMAL POWER 1;33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNPLANNED RELEASE 1.34 UNPLANNED RELEASE is the unintended discharge of a volume of liquid or airborne radioactivity to the environment.

The following guidance is presented to classify differences between unplanned releases and other releases that are not considered as an UNPLANNED RELEASE: Is an UNPLANNED RELEASE if: 1, The wrong waste gas decay tank or liquid radwaste release tank is released off site.2.3.Failure of process system to automatically divert a process stream to a radioactive treatment system upon radioactivity being present in the process at the detection level or at a certain level of activity, and the result is a discharge off site occurs.Large losses from unexpected pipe or valve leaks where the resulting loss of radioactive material to off site such that a 10 CFR Part 50.72 or 10 CFR Part 50.73 report is required.St.Lucie Plant ODCM Controls Page 13 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM UNPLANNED RELEASE (continued) 1.34 (continued)

Is not an UNPLANNED RELEASE if: 1.It cannot be shown that the release went off site, i.e., gas went to another part of the system(s)that contained the loss.2.Normal losses through the Plant Vent due to valve and pipe leakage and purging activities to make the system safe for maintenance activities.

Pressures drops in Gas Decay Tank(s)due to thermal cooling, shifting the Gas Analyzer sampling point, Chemistry Grab Sampling, or planned maintenance activities are not an UNPLANNED RELEASE.UNRESTRICTED AREA 1.35 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.VENTILATION EXHAUST TREATMENT SYSTEM 1,39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactivematerial in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is~considered to have any effect on noble gas effluents.

Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

St.Lucie Plant ODCM Controls Page 14 of 225 ST.LUCIE PLANT CHEMISTRY.

OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM VENTING 1.40 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.Vent, used in system names, does not imply a VENTING process.WASTE GAS HOLDUP SYSTEM 1.41 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

St.Lucie Plant ODCM Controls Page 15 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 1.1 FREQUENCY NOTATION NOTATION S D W 4/M*Q SA R S/U N.A.P**FREQUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .At least once per 7 days.At least 4 per month at intervals of no greater than 9 days and minimum of 48 per year.At least once per 31 days.At lease once per 92 days.At least once per 184 days.At least once per 18 months.Prior to each reactor startup.Not Applicable.

Completed prior to each release*For Radioactive Effluent Sampling**For Radioactive Batch Releases Only St.Lucie Plant ODCM Controls 3/4 Page 16 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the Controls contained in the succeeding controls is required during the conditions specified therein;except that upon failure to meet the Control, the associated ACTION requirements shall be met.3.0,2 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 expiration of the specified time intervals, completion of the ACTION requirements is not required.SURVEILLANCE REQUIREMENTS

4.0.1 Surveillance

Requirements shall be met during the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within th5 specified time interval with: a.A maximum allowable extension not to exceed 25%of the surveillance interval.St.Lucie Plant ODCM Controls Page 17 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-'200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.9 In accordance with St.Lucie Plant TS 6.8.4.f.1), the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded.The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY:

At all times.ACTION:a.With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b.With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected in a timely manner.c.Report all deviations in the Annual Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.St.Lucie Plant ODCM Controls Page 18 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 1.Radioactivity Monitors Providing Alarm and Automatic Termination of Release a)Liquid Radwaste Effluent Line b)Steam Generator Blowdown Effluent Line 2.Flow Rate Measurement Devices a)Liquid Radwaste Effluent Line b)Discharge Canal c)Steam Generator Blowdown Effluent Lines MINIMUM CHANNELS OPERABLE 1/SG N.A.N.A.N.A.ACTION 35 36 38 38 38 SG-Denotes Steam Generator St.Lucie Plant ODCM Controls Page 19 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-12 Continued ACTION STATEMENTS ACTION 35-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release: a.b.At least two independent samples are analyzed in accordance with the Surveillance Requirement for concentration limit of Control 4.11.1.'1.1.

and I At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.Otherwise, suspend release of radioactive effluents via this pathway.ACTION 36-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma)at a limit of detection of at least 2.E-07 micro-Curie/ml:

a.At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 micro-Curies/gram DOSE EQUIVALENT I-131 or b.At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 micro-Curies/gram DOSE EQUIVALENT I-131.ACTION 38-Minimum system design flow of required running pumps shall be utilized for ECL calculations for discharge canal flow and maximum system design flow be utilized for ECL calculations for effluent line flow.St.Lucie Plant ODCM Controls Page 20 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT 1.Radioactivity Monitors Providing Alarm and Automatic Termination of Release a)Liquid Radwaste Effluent Line b)Steam Generator Blowdown Effluent Line 2.Flow Rate Measurement Devices CHANNEL SOURCE CHECK CHECK D CHANNEL CALIBRATION R (2)R (2)CHANNEL FUNCTIONAL TEST Q (1)Q (1)a)Liquid Radwaste Effluent Line b)Discharge Canal c)Steam Generator Blowdown Effluent Line D (3)D (3)D (3)N.A.N.A.N.A.Q Q Q St.Lucie Plant ODCM Controls Page 21 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.3-8 Continued TABLE NOTATIONS (1)The CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist: 1.Instrument indicates measured levels above the alarm/trip setpoint or 2.Circuit failure or 3.Instrument indicates a downscale failure or 4.Instrument controls not set in operate mode.(2)The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Institute of Standards&Technology (NIST)or using standards that have been calibrated against standards certified by the NIST.These standards should permit calibrating the system over its intended range of energy and rate capabilities that are typical of normal plant operation.

For subsequent CHANNEL CALIBRATION, button sources that have been related to the initial calibration may be used.(3)CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL 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 on which continuous, periodic or batch releases are made.St.Lucie Plant ODCM Controls Page 22 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.10 In accordance with St.Lucie Plant TS 6.8.4.f.1), the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.2.1.are not exceeded.The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.APPLICABILITY:

As shown in Table 3.3-13 ACTION:a.With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b.With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected in a timely manner.c.Report all deviations in the Annual Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9.St.Lucie Plant ODCM Controls Page 23 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 1.Waste Gas Holdup System a)Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release 2.Condenser Evacuation System a)Noble Gas Activity Monitor 3.Plant Vent System~a)Noble Gas Activity Monitor (Low Range)b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor 4.Fuel Storage Area Ventilation System a)Noble Gas Activity Monitor (Low Range)b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor MINIMUM CHANNELS OPERABLE 1/Rx 1/Rx 1/Rx 1/Rx 1/Rx N.A.1/Rx 1/Rx 1/Rx 1/Rx N.A.1/Rx APPLICABILITY ACTION 45 47 51 51 53 46 47 51 51 53 46 St.Lucie Plant ODCM Controls Page 24 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-13 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION 5.Laundry Area Ventilation System a)Noble Gas Activity Monitor (Low Range)b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor 6.Steam Generator Blowdown Building Vent a)Noble Gas Activity Monitor (Low Range)b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor 1/Rx 1/Rx 1/Rx N.A.1/Rx 47 51 51 53 46 51 51 53 46St.Lucie Plant ODCM Controls Page 25 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-13 Continued TABLE NOTATIONS-At all times while making releases via this pathway-At all times when air ejector exhaust is not directed to plant vent.Rx-Denotes reactor ACTION STATEMENTS ACTION 45-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s)may be released to the environment for up to 14 days provided that prior to initiating a release: I a.At least two independent samples of the tank's contents are analyzed and b, At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.Otherwise, suspend release of radioactive effluents via this pathway.ACTION 46-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days 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 47-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE, effluent releases via this pathway may continue for up to 30 days provided: a.If channel inoperability is due to loss of activity indication, Then 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 isotopic activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .OR b.If channel inoperability is due to loss of Control Room alarm annunciation discovered during a channel functional test because of any one or more of the following reasons listed, Then channel checks are performed once per hour to verify normal indication and current assigned setpoints are NOT exceeded.1.Failure to annunciate when testing alarm/trip setpoints.

2.Circuit failure.3.Downscale failure.4.Controls NOT set in OPERATE mode.St.Lucie Plant ODCM Controls Page 26 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-13 Continued TABLE NOTATIONS ACTION STATEMENTS (continued)

ACTION 51-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.ACTION 53-Maximum system flows shall be utilized in the determination of the instantaneous release monitor alarm setpoint.St.Lucie Plant ODCM Controls Page 27 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS ODCM Effluent Gas Channels 1PV LOW RANGE GAS 1FHB LOW RANGE GAS 2A PV PIG LOW RANGE GAS 2B PV PIG LOW RANGE GAS 2PV WRGM LOW RANGE GAS 2FHB LOW RANGE GAS SGBDB LOW RANGE GAS 1 CONDENSER AIR EJECTOR 2 CONDENSER AIR EJECTOR 1 BATCH GAS EFFLUENT 2 BATCH GAS EFFLUENT CHANNEL ID 01%5 423 433 621 413 45%35 403 42 203 BASIS DOCUMENT C-200'-200'-200'-200'-200'-200'-200'-200 C-200 C-200'-200'LERT SETPOINT'x Bkg.Sx Bkg.5x Bkg.5x Bkg.5x Bkg.Sx Bkg.5x Bkg.2 x Bkg.'x Bkg.'s Per C-72 As Per C-72 HIGH SETPOINT'llotted

%Of Site Limit'llotted

%Of Site Limit'or Plant Vent ff2 Allotted%Of Site Limit'llotted

%Of Site Limit~3x Bkg.3x Bkg.As Per C-72'~As Per C-72'~ODCM Related Particulate Channels 1PV PARTICULATE CHANNEL ID 01-01 BASIS DOCUMENT FUSAR ALERT SETPOINT'000 CPM HIGH SETPOINT 10,000 CPM'FHB PARTICULATE 2A PV PIG PARTICULATE 2B PV PIG PARTICULATE 2FHB PARTICULATE SGBDB PARTICULATE 04-01 421.431 411 45M FUSAR 5 TS'000 CPM FUSAR 5000 CPM FUSAR 5000 CPM FUSAR 8 TS'000 CPM FUSAR-5000 CPM 10,000 CPM'0,000 CPM'0,000 CPM'0,000 CPM'0,000 CPM't.Lucie Plant ODCM Controls Page 28 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.3-14 continued RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS ODCM Related Iodine Channels 1PV IODINE 1FHB IODINE 2A PV PIG IODINE 2B PV PIG IODINE 2FHB IODINE SGBDB IODINE CHANNEL ID 01-03 04-03 422 432 412 45-5 BASIS DOCUMENT FUSAR FUSAR FUSAR FUSAR FUSAR FUSAR ALERT SETPOINT'000 CPM 5000 CPM 5000 CPM 5000 CPM 5000 CPM 5000 CPM HIGH SETPOINT'0,000 CPM'0,000 CPM'0,000 CPM'0,000 CPM'0,000 CPM'0,000 CPM'DCM Related Liquid Channels 1A S/G BLOWDOWN 1B S/G BLOWDOWN 2A S/G BLOWDOWN 2B S/G BLOWDOWN CHANNEL ID 45 121 122 BASIS DOCUMENT C-200 C-200 C-200 C-200 ALERT SETPOINT 2 x Bkg.2 x Bkg.2x Bkg.2 x Bkg.HIGH SETPOINT'.E-04 uCi/ml'.E-04 uCi/ml'.E-04 uCi/ml 2.E-04 uCVml 1 BATCH LIQUID EFFLUENT R6627 C-200 As Per C-70 As Per C-70" 2 BATCH LIQUID EFFLUENT 301 C-200 As Per C-70 As Per C-70" Table Notations:

a-ODCM Control 3.11.2.1a b-ODCM Table 4.11-1 Note (7)c-ODCM Control 3.11.2.1.b d-TS Table 3.3-6 required instrument 2.a.ii with setpoint per ODCM e-Setpoints may be rounded for analog and digital display input limitations.'

-The channel setpoint to be in cpm equivalent to this activity g-per ODCM Methodology Step 2.2.2 h-Batch Gaseous Release Rate and Maximum activity limits shall be used such that Plant Vent (PV)Release HIGH setpoints should not be exceeded.i, j, k, and I not used in notation for clarity m-Continuous Liquid setpoint methodology per ODCM 1.3.2 n-Batch liquid setpoint methodology per ODCM 1.3.1 FUSAR-Channel listed in fusar, but not required by ODCM Control 3.3.10 Table 3.3-13.The setpoints are used to provide alarm well before exceeding ODCM Control 3.11.2.1.b Site Dose Rate Limit.The inoperability of a fusar channel above does not involve an ACTION statement unless TS (Technical Specification) is noted.2 x Bkg., 3 x Bkg., 5 x Bkg.etc., denotes the number of times the normal channel reading is the appropriate Alarm Setting.These type of setpoints should be periodically evaluated to insure alarm sensitivity is maintained as per COP<7.05.St.Lucie Plant ODCM Controls

Page 29 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION Modes in CHANNEL which FUNCTIONAL surveillance TEST required 1.Waste Gas Holdup System a)Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release 2.Condenser Evacuation System a)Noble Gas Activity Monitor 3.Plant Vent System a)Noble Gas Activity Monitor b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor 4.Fuel Storage Area Ventilation System a)Noble Gas Activity Monitor b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor D D W W D D D W W D D p N.A.N.A.N.A.N.A.N.A N.A.N.A.N.A.R (3)R (3)R (3)N.A.N.A.R R (3)N.A.N.A.R R Q (~)Q (2)Q (2)N.A.Q N.A.Q (2)N.A.Q N.A.St.Lucie Plant ODCM Controls 0

Page 30 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.3-9 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT 5.Laundry Area Ventilation System a)Noble Gas Activity Monitor CHANNEL CHECK D SOURCE CHANNEL CHECK CALIBRATION R (3)CHANNEL FUNCTIONAL TEST Q (2)Modes in which surveillance required b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor 6.Steam Generator Blowdown Building Vent a)Noble Gas Activity Monitor b)Iodine Sampler c)Particulate Sampler d)Flow Rate Monitor e)Sampler Flow Rate Monitor W W W W N.A N.A.N.A.N.A.N.A.N.A.R (3)N.A.N.A.N.A.N.A.Q N.A.Q (2)N.A.Q N.A.e St.Lucie Plant ODCM Controls Page 31 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.3-9 Continued TABLE NOTATIONS At all times when making releases via this pathway.**-At all times when air ejector exhaust is not directed to plant vent.(1)The CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist: 1.Instrument indicates measured levels above the alarm/trip setpoint or 2.Circuit failure or 3, Instrument indicates a downscale failure or 4.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 exist: 1.Instrument indicates measured levels above the alarm/trip setpoint or 2.Circuit failure or 3.Instrument indicates a downscale failure or 4.Instrument controls not set in operate mode.(3)The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Institute of Standards 8 Technology (NIST)or using standards that have been calibrated against standards certified by the NIST.These standards should permit calibrating the system over its intended range of energy and rate capabilities that are typical of normal plant operation.

For subsequent CHANNEL CALIBRATION, button sources that have been related-to the initial calibration may be used.St.Lucie Plant ODCM Controls Page 32 of 225 3/4.11 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with the St.Lucie Plant TS 6.8.4.f.2) and 3), the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see TS Figure 5.1-1)shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, 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 2.E-04 micro-Curie/ml total activity.APPLICABILITY:

At all times.ACTION: a.With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.SURVEILLANCE REQUIREMENTS 4.11.1,1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.4.11.1.1.3 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11-1 and results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 3.11.1.1.St.Lucie Plant ODCM Controls Page 33 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLiquid Release Type A.Batch Waste Release Tanks (2)B.Continuous Releases (5, 6)C.Settling Basin (7)Sampling Frequency P Each Batch P One Batch/M P Each Batch P Each Batch Daily Daily Grab Sample Daily Daily W Grab Sample Minimum Analysis Frequency Each Batch M M Composite (4)Q Composite (4)4/M Composite 4/M Composite M Composite Q Composite W Type of Activity Analysis P.G.E.(3)l-131 Dissolved and Entrained Gases (Gamma Emitters)H-3 Gross Alpha Sr-89, Sr-90 Fe-55 P.G.E.(3)l-131 Dissolved and Entrained Gases (Gamma Emitters)H-3 Gross Alpha Sr-89, Sr-90 Fe-55 P.G.E.(3)I-131 Lower Limit of Detection LLD (1)(pCi/ml)5.E-07 1.E-06 1.E-05 1.E-05 1.E-07 5.E-08 1.E-06 5.E-07 1.E-06 1.E-05 1.E-05 1.E-07 5.E-08 1.E-06 5.E-07 1.E-06 P.G.E.-Denotes Principal Gamma Emitter St.Lucie Plant ODCM Controls Page 34 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-1 Continued TABLE NOTATION (1)The LLD is defined for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%probability with only 5%probability of falsely concluding that a blank observation represents a real signal.For a particular measurement system, which may include radiochemical separation:

4.66 S~LLD-E~V~2.22E+06~Y~exp (-X~d 7)Where: LLD the a priori lower limit of detection (micro-Curie per unit mass or volume), Sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), V the counting efficiency (counts per disintegration), the sample size (units of mass or volume), 2.22E+06=the number of disintegrations per minute per micro-Curie., Y the fractional radiochemical yield, when applicable, the radioactive decay constant for the partic~ul radionuclide (sec')and the elapsed time between the midpoint of sample collection and the time of counting (sec).Typical values of E, V, Y and hT should be used in the calculation.

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

St.Lucie Plant ODCM Controls Page 35 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-1 Continued TABLE NOTATIONS Continued (2)A batch release is the discharge of liquid wastes of a discrete volume.Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.(3)The principal gamma emitters for which the LLD control applies include the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 and Ce-141 and Ce-144.This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 3.11.2.6 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.~(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.(6)If Component Cooling Water activity is>1.E-5 pCI/ml, perform a weekly gross activity on the Intake Cooling Water System outlet to ensure the activity level is less than or equal to 2.E-07 pCI/ml LLD limit.If ICW is>2.E-07 pCI/ml, perform analysis in accordance with a Plant Continuous Release on this Table.(7)Grab samples to be taken when there is confirmed primary to secondary system leakage indicated by the air ejector monitor indicating greater than or equal to 2x background.

St.Lucie Plant ODCM Controls Page 36 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with St.Lucie Plant TS 6.8.4.f.4) and 6.8.4.f.5), the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1)shall be limited: a.During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ and b.During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems 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 Plant TS 6.9.2, 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 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.St.Lucie Plant ODCM Controls Page 37 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1,3 In accordance with St.Lucie Plant TS 6.8.4.f.6), the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1)would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.APPLICABILITY:

At all times.ACTION: a.With radioactive liquid waste being discharged without treatment and 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 Plant TS 6.9.2, 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 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.St.Lucie Plant ODCM Controls Page 38 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 In accordance with St.Lucie Plant TS 6.8.4.f.3) and 7), the dose rate resulting from radioactive materials released in gaseous effluents to areas at or beyond the SITE BOUNDARY (see TS Figure 5.1-1)shall be limited to the following:

a.For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin and b.For Iodine-1 31, for Iodine-133, for tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ APPLICABILITY:

At all times.ACTION: a.With the dose rate(s)exceeding the above limits, immediately restore the release rate to within the above limit(s).SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology~nd parameters in the ODCM.4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.St.Lucie Plant ODCM Controls Page 39 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING 8 ANALYSIS PROGRAM Gaseous Release Type Waste Gas Storage Tank Sampling Frequency P Each Tank Grab Sample Minimum Analysis Frequency P Each Tank Type of Activity Analysis Noble Gas P.G.E.(2)Lower Limit of Detection (LLD)(1)(pCi/cc)1.E-04 2.Containment Purge P P Each Purge (6)Each Purge (6)Grab Sample (7)Noble Gas P.G.E.(2)H-3 1.E-04 1.E-06 3.Vents: a.Plant b.Fuel Bldg (5)c.Laundry d.S/G Blowdown Bldg.4.All Release Types as listed in 3.above 4/M Grab Sample Continuous (3)4/M (7)4/M Charcoal Sample (4)4/M Particulate Sample (4)M Composite Particulate Sample Q Composite Particulate Sample Noble Gas Monitor Noble Gas P.G.E.(2)H-3 I-131 P.G.E.Gross Alpha Sr-89, Sr-90 Noble Gases Gross Beta or Gamma 1.E-04 1.E-06 1.E-12 1.E-11 1.E-11 1.E-11 1.E-06 P.G.E.-Denotes Principal Gamma Emitters St.Lucie Plant ODCM Controls Page 40 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-2 Continued TABLE NOTATIONS (1)The LLD is defined for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%probability with only 5%probability of falsely concluding that a blank observation represents a real signal.For a particular measurement system, which may include radiochemical separation:

4.66 Sb E~V~2.22E+06~Y~exp (-X~b,T)Where: LLD Sb the a priori lower limit of detection (micro-Curie per unit mass or volume), the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E V the counting efficiency (counts per disintegration), the sample size (units of mass or volume), 2.22E+06=the number of disintegrations per minute per micro-Curie., Y the fractional radiochemical yield, when applicable, the radioactive decay constant for the partic~ul radionuclide (sec')and the elapsed time between the midpoint of sample collection and the time of counting (sec).Typical values of E, V, Y and bT 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 tatter the fact)limit for a particular measurement.

St.Lucie Plant ODCM Controls Page 41 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.11-2 Continued TABLE NOTATIONS Continued (2)The principal gamma emitters for which the LLD control applies include the following radionuclides:

Kr-87,Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131;Cs-134, Cs-137, Ce-141 and Ce-144 in Iodine and particulate releases.This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 3.11.2.6 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.(3)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2 and 3.11.2.3.(4)Samples shall be changed at least four times per month and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15%of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of,=10.This requirement does not apply if: (1)analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3;and (2)the noble gas monitor shows that effluent activity has not increased by more than a factor of 3.(5)Tritium grab samples shall be taken at least 4/M from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.(6)Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change exceeding 15%of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1)analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3;and (2)the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.(7)Tritium analysis may be delayed for up to 14 days if the LLD is still attainable at the new counting time.St.Lucie Plant ODCM Controls Page 42 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS DOSE-NOBLE GASES CONTROLS 3.11.2.2 ln accordance with St.Lucie Plant TS 6.8.4.f.5) and 8), the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-1)shall be limited to the following:

a.During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and b.During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads 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 Plant TS 6.9.2, a Special Report that identifies the cause(s)for exceeding the limit(s)and defines the corrective actions that have been taken to assure that subsequent releases will be in compliance with the above limits.SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.St.Lucie Plant ODCM Controls Page 43 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS DOSE-IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with St.Lucie Plant TS 6.8.4.f.5) and 9), the dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-1)shall be limited to the following:

a.During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, b.During any calendar year: Less than or equal to 15 mrems to any organ.APPLICABILITY:

At all times.ACTION'.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 Plant TS 6.9.2, a Special Report that identifies the cause(s)for exceeding the limit(s)and defines the corrective actions that have been taken to assure that subsequent releases will be in compliance with the above limits.SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendhr quarter and current calendar year for Iodine-131, Iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.St.Lucie Plant ODCM Controls Page 44 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.*C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with St.Lucie Plant TS 6.8.4.f.6), the VENTILATION EXHAUST Treatment System and the WASTE GAS HOLDUP 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 effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-1)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.APPLICABILITY:

At all times.ACTION: a.With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that includes the following information:

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.

St.Lucie Plant ODCM Controls Page 45 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM Continued SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM*shall be demonstrated OPERABLE by operating the WASTE GAS HOLDUP SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least.30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.*If the WASTE GAS HOLDUP SYSTEM is not being fully utilized, an Administrative FUNCTIONAL TEST on the WASTE GAS HOLDUP SYSTEM shall also be performed (in addition to the requirements of 4.11.2.4.2's"at least 30 minutes")once per 92 days, by performing the following:

1)Place a Gas Decay Tank (containing less than'30 psi)in service.2)3)With a Waste Gas Compressor, charge the Gas Decay Tank to at least 150 psi~Following appropriate holdup decay time, sample and release the Gas Decay Tank with an OPERABLE Waste Gas Holdup System Noble Gas Activity Monitor (per TABLE 3.3-13).4)If discrepancies exist, repairs shall be made and the WASTE GAS HOLDUP SYSTEM Administrative FUNCTIONAL TEST shall be repeated until completed successfully.

St.Lucie Plant ODCM Controls Page 46 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20" OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with St.Lucie Plant TS 6.8.4.f.10), the annual (calendar year)dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.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 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks etc.)to determine whether the above limits of Control 3.11.4 have been exceeded.If such is the case, prepare and submit to the Commission within 30 days, pursuant to Plant TS 6.9.2, 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 Subpart M of 10 CFR Part 20, shall include an analysis that estimates the radiation exposure (dose)to a MEMBER OF THE PUBLIC 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.

Ifgu.estimated dose(s)exceeds the above limits and if the release condition resulting in violation of 40 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.St.Lucie Plant ODCM Controls

Page 47 of 225 S T.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCUIATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE Continued SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2 and 4.11.2.3 and in accordance with the methodology and parameters in the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks etc.)shall be determined in accordance with the methodology and parameters in the ODCM.This requirement is applicable only under conditions set forth in ACTION a.of Control 3.11.4.St.Lucie Plant ODCM Controls Page 48 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.5 MAJOR CHANGES TO RADIOACTIVE LIQUID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS'DMINISTRATIVE CONTROLS 3.11.2.5 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid): 1)Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period tn which the evaluation was reviewed by the Facility Review Group (FRG).The discussion of each shall contain: a)A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.b)Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c)A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;d)An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;e)An evaluation of the change which shows the expected maximum exposure to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;f)A comparison of the predicted releases of'radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period when the changes are to be made;g)An estimate of the exposure to plant operating personnel as a result of the change;and h)Documentation of the fact that the change was reviewed and found acceptable by the FRG.2)Shall become effective upon review and acceptance by the FRG.Licensees may choose to submit the information called for in this Administrative Control as part of the annual FUSAR update.St.Lucie Plant ODCM Controls Page 49 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION*

ADMINISTRATIVE CONTROLS 3.11.2.6 As per Technical Specification 6.9.1.7, a Annual Radioactive Effluent Release Report covering the operation of each unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year.The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from each unit.The material provided shall be (1)consistent with the objectives outlined in by items a)through f)below, using the example*report format in the ODCM and (2)be in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.a.The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined 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.b.The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.This annual summary may be either in the form of an hour-by-hour listing on magnetic tape df wind speed, wind direction, atmospheric stability and precipitation (if measured),or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.**

This same report shall include an assessment of the radiation doses~e to the radioactive liquid and gaseous effluents released from the unit or station during the A single submittal may be made for a multiple unit station.The submittal should combine.those sections that are common to all units at the station;however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.**-In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.St.Lucie Plant ODCM Controls Page 50 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION Continued ADMINISTRATIVE CONTROLS 3.11.2.6 (Continued) b.(Continued) previous calendar year.This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (see TS Figure 5.1-1)during the report period.All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports.The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM.c.Every 2 years using the previous 6 months release history for isotopes, determine the controlling age group for liquid pathways.Every 2 years using the previous 1 year or longer interval (to include a,refueling outage)and historical meteorological data determine the controlling age group for gaseous pathways.If changed from current submit change to ODCM to reflect new tables for these groups and use the new groups in subsequent dose calculations.

d.The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiationPees to the likely most exposed MEMBER OF THE PUBLIC from reactor releases for the previous calendar year.Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109 March 1976.St.Lucie Plant ODCM Controls Page 51 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION Continued ADMINISTRATIVE CONTROLS 3.11.2.6 (Continued) e.The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61)shipped offsite during the report period: 1.Volume 2.Total Curie quantity (specify whether determined by measurement or estimate)3.Principal radionuclides (specify whether determined by measurement or estimate)4.Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms)5.Type of container (e.g., LSA, Type A, Type B, Large Quantity)and 6.Solidification agent or absorbent (e.g., cement, urea formaldehyde).

f.The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.g.The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP)and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census of ODCM Control 3.12.2.h.The format for an Annual Radioactive Effluent Release Report is provided in ODCM Methodology Section 4.0.The information contained in an annual report shall not apply to any ODCM Control Dose Limit(s)since the methodology for the annual report is based on actual meteorological data, instead of historical conditions that the ODCM Controls and Control required calculations are based on.St.Lucie Plant ODCM Controls Page 52 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 In accordance with St.Lucie Plant TS 6.8.4.g.1), the Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.APPLICABILITY:

At all times.ACTION: a.With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 3.12.4, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.With the confirmed*

level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that 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 limit of Controls 3.11.1.2, 3.11.2.2 or 3.11.2.3.When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: concentration (1)concentration (2)reporting level (1)reporting level (2)When radionuclides other than those in Table 3.12-2 are*A confirmatory reanalysis of the original, a duplicate or a new sample may be desirable, as appropriate.

The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis but in any case within 30 days.**The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.St.Lucie Plant ODCM Controls Page 53 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM Controls (Continued)

Action b.(Continued) detected and are the result of plant effluents, this report shall be submitted if the potential annual dose, to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2 or 3.11.2.3.This report fs 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 Annual Radiological Environmental Operating Report required by Control 3.12.4.c.With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.The specific locations from which samples were unavailable may then be deleted from the monitoring program.Pursuant to Control 3.11.2.6, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s)and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall b5 collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s)in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.St.Lucie Plant ODCM Controls Page 54 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM'i EXPOSURE PATHWAY and/or SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND SAMPLE COLLECTION LOCATIONS"" FREQUENCY" TYPE AND FREQUENCY" OF ANALYSIS 1.Direct Radiation" 2.Airborne Radioiodine and Particulates 3.Waterborne a)Surface"')

Sediment from shoreline 4.Ingestion a)Fish and Invertebrates 1)Crustacea 2)Fish b)Food Products 1)Broad leaf vegetation 27 Monitoring Locations 5 Locations 1 Location'Location"'

Locations 2 Locations 2 Locations 3 Locations" Continuous monitoring with sample collection quarterly" Continuous sampler operation with sample collection weekly or more frequently if required by dust loading Weekly Monthly Semiannually Semiannually Semiannually Monthly when available Gamma exposure rate-quarterly Radioiodine filter: I-131 analysis weekly Particulate Filter: Gross beta radioactivity analysis>&4 hours following a filter change" Gamma isotopic"'nalysis of composite" (by location)quarterly Gamma isotopic"'

tritium analyses weekly Gamma isotopic"'

tritium analyses monthly Gamma isotopic"'nalyses semiannually Gamma isotopic"'nalyses semiannually Gamma isotopic"'nalyses semiannually Gamma isotopic"'nd l-131 analyses monthly St.Lucie Plant ODCM Controls

Page 55 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.12-1 Continued TABLE NOTATIONS a.Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons.If specimens are unobtainable due to sampling equipment malfunction, corrective action shall be taken prior to the end of the next sampling period.All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.b.Specific parameters of distance and direction sector from the centerline of one reactor and additional description where pertinent, shall be provided for each sample location required by Table 3.12-1, in Appendix-E and applicable figures.c.At times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time, In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.d.The following definition of frequencies shall apply to Table 3.12-1 only: Weekly-Not less than once per calendar week, A maximum interval of 11 days is allowed between the collection of any two consecutive samples.Semi-Monthly

-Not less than 2 times per calendar rrionth with an interval of not less than 7 days between sample collections.

A maximum interval of 24 days is allowed between collection of any two consecutive samples.Not less than once per calendar month with an interval of not less than 10 days between sample collections.

Quarterly-Not less than once per calendar quarter.Semiannually

-One sample each between calendar dates (January 1-June 30)and (July 1-December 31).An interval of not less than 30 days will be provided between sample collections.

The frequency of analyses is to be consistent with the sample collection frequency.

St.Lucie Plant ODCM Controls Page 56 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.12-1 Continued TABLE NOTATIONS Continued e.One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of or in addition to, integrating dosimeters.

For purposes of this table, a thermoluminescent dosimeter (TLD)is considered to be one phosphor;two or more phosphors in a packet are considered as two or more dosimeters.

f.Refers to normal collection frequency.

More frequent sample collection is permitted when conditions warrant.g.Airborne particulate sample filters are analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.In addition to the requirement for a gamma isotopic on a composite sample a gamma isotopic is also required for each sample having a gross beta radioactivity which is>1.0 pCi per cubic meters and which is also>10 times that of the most recent control sample.h.Gamma isotopic analysis means the identification and quantification of gamma-emitting

~~radionuclides that may be attributable to the effluents from the facility.k.Discharges from the St.Lucie Plant do not influence drinking water or ground water pathways.m.Atlantic Ocean, in the vicinity of the public beaches along the eastern shore of Hutchinson Island near the St.Lucie Plant (grab sample)n.Atlantic Ocean, at a location beyond influence from plant effluents (grab sample).p.Samples of broad leaf vegetation grown nearest each of two cÃferent offsite locations of highest predicted annual average ground level D/Q and one sample of similar broad leaf vegetation at an available location 15-30 kilometers distant in the least prevalent wind direction based upon historical data in the ODCM.[I, j, I (lower case)and o are not used on notation for clarity reasons]St.Lucie Plant ODCM Controls Page 57 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS ANALYSIS H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95"'-131 Cs-134 Cs-137 Ba-La-140"*WATER pCi/I 30,000 1,000, 400 1,000 300 300 400 30 50 200 AIRBORNE PARTICULATE OR GASES pCI/m'.9 10 20 FISH pCi/kg, wet 30,000 10,000 30,000 10,000 20,000 1,000 2,000 MILK pCi/I 60 70 300 FOOD PRODUCTS pCi/kg, wet 100 1,000 2,000 I-as in pCi/I denotes liter*-Since no drinking water pathway exists, a value of 30,000 pCi/I is used.For drinking water samples, a value of 20,000 pCi/I is used;this is 40 CFR Part 141 value.*-Applies to drinking water pathway exists, 2 pCi/I is the lim~ir drinking water.***-An equilibrium mixture of the parent daughter isotopes which corresponds to the reporting value of the parent isotope, St.Lucie Plant ODCM Controls Page 58 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE'ALCULATION MANUAL ODCM TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS"~LOWER LIMIT OF DETECTION LLD'ANALYSIS Gross Beta H-3 Mn-54 Fe-59 Co-58, Co-60 Zn-65 Zr-95, Nb-95~'~I-131 WATER pCi/I 3000 15 30 30 15 1**AIRBORNE PARTICULATE FISH OR GASES pCi/kg, wet pCI/m'0.01 130 260 130 260 0.07 MILK pci/I FOOD PRODUCTS pCi/kg, wet 60 SEDIMENT pCi/kg, dry Cs-134 Cs-137 Ba-140, La-140~'>15 18 15 0.05 0.06 130 150 15 18 15 60 80 150 180*No drinking water pathway exists, a value of 2000 pCI/f is for drinking water.**LLD for drinking water samples.If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.St.Lucie Plant ODCM Controls Page 59 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.12-1 Continued TABLE NOTATIONS (1)This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.(2)Required detection capabilities for the rmoluminescent dosim etc rs used for environmental measurements are given in Regulatory Guide 4.13.I (3)The LLD is defined for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%probability with only 5%probability of falsely concluding that a blank observation represents a real signal.For a particular measurement system, which may include radiochemical separation:

4.66 Sb E~V~2.22~Y~exp (-X~b,7)Where: LLD=the a priori lower limit of detection (pico-Curie per unit mass or volume), S,=the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E=the counting efficiency (counts per disintegration), V=the sample size (units of mass or volume), 2.22=the number of disintegrations per minute per pico-Curie, Y=the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec')and bT=the elapsed time between the midpoint of sample collection and the time of counting (sec).Typical values of E, V, Y and dT should be used in the calculation.

St.Lucie Plant ODCM Controls Page 60 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 4.12-1 Continued TABLE NOTATIONS Continued 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 gosteriori (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, unavoidable small sample sizes, the presence of interfering nuclides or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.(4)An equilibrium mixture of the parent and daughter isotopes which corresponds to 15 pCi/Liter of the parent isotope.St.Lucie Plant ODCM Controls

Page 61 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS'ONTROLS 3.12.2 In accordance with St.Lucie Plant TS 6.8.4.g.2), a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles)the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden*of greater than 50 square meters (500 square feet)producing broad leaf vegetation.

APPLICABILITY:

At all times.-ACTION: a.With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to Control 3.11.2.6, identify the new location(s) in the next Annual Radioactive Effluent Release Report.b.With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway)20%greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.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.

Pursuant to TS 6.14, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s)and table(s)for the ODCM reflecting the new location(s) with informatioqsupporting the change in sampling locations.

Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.Controls for broad leaf vegetation sampling in Table 3.12-1, Part 4.b., shall be followed, including analysis of control samples.St.Lucie Plant ODCM Controls Page 62 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS Continued SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will'provide the best results, such as by a door-to-door survey, aerial survey or by consulting local agriculture authorities.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 3.12A.St.Lucie, Plant ODCM Controls Page 63 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with St.Lucie Plant TS 6.8.4.g.3), analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.APPLICABILITY:

At all times.I ACTION: '.With analyses not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.SURVEILLANCE REQUIREMENTS 4.12.3 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 pursuant to Control 3.12.4, If the Interlaboratory Comparison Program is other than the program conducted by the EPA, then the Interlaboratory Compeison Program shall be described in the ODCM.*This condition is satisfied by participation in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by the Environmental Protection Agency (EPA).St.Lucie Plant ODCM Controls Page 64 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT AREOR ADMINISTRATIVE CONTROLS 3.12.4 In accordance with St.Lucie Plant TS 6.9.1.8, an Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.The report shall include summaries, interpretations and information based on trend analysis of the results of the Radiological Environmental Monitoring Program for the reporting period.The material provided in the AREOR shall'be consistent with the objectives outlined below and with Sections IV.B,2, IV.B.3 and IV.C of Appendix I to 10 CFR Part 50.The Annual Radiological Environmental Operating Reports shall include summaries, interpretations and information based on trend analysis of the results of the radiological environmental surveillance activities for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls and with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use census required by Control 3.12.2.The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical=-Position, Revision 1, November 1979.In the event that some individual 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 reports shall also include the following:

a summary description of the radiological environmental monitoring program;at least two legible maps*covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor;the results of the Interlaboratory Comparison Program, required by Control 3.12.3;discussion of all deviations from the sampling schedule of Table 3.12-1;and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

A single submittal may be made for multiple unit station.**-One map shall cover stations near the SITE BOUNDARY;a second shall include the more distant stations.St.Lucie Plant ODCM Controls Page 65 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM BASES for the CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.St.Lucie Plant ODCM Controls-Bases Page 66 of 225 OF INSTRUMENTATION ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 FSITE DOSE CALCULATION MANUAL ODCM BASES 3.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITOR)NG INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases of liquid effluents.

The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A.to 10 CFR Part 50.3.3.3.10 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 effluent during actual or potential releases of gaseous effluents.

The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.St.Lucie Plant ODCM Controls-Bases Page 67 of 225 3/4.11 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 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 in UNRESTRICTED AREAS will result in exposures within: (1)the Section II.A design objectives of Appendix I, 10 CFR Part 50,'to a MEMBER OF THE PUBLIC and (2)the limits of 10 CFR Part 20.The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its ECL in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.This control applies to the release of radioactive materials in liquid effluents from all units at the site.The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).Detailed discussion of the LLD and other detection limits can be found in Currie, L.A., Lower Limit of Detection; Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984)and in the HASL Procedures Manual, HAS L-300.3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.The Control implements the guides set forth in Section II.A of Appendix I.The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.

Also, for fresh water sites with drinking water supplies that can be potentially 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 Part 141.The dose calculation St.Lucie Plant ODCM Controls-Bases Page 68 of 225 3/4.11 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS Continued BASES 3/4.11.1 LIQUID EFFLUENTS Continued 3/4.11.1.2 DOSE Continued methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.This control applies to the release of radioactive materials in liquid effluents from each unit at the site.For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system.3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require t<6atment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable.

This control implemqpts-the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective give'n in Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

This control applies to the release of radioactive materials in liquid effluents from each unit at the site.For units with shared Radwaste Treatment Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system.St.Lucie Plant ODCM Controls-Bases Page 69 of 225 OFFSITE RADIOACTIVE EFFLUENTS ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 DOSE CALCULATION MANUAL ODCM BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.The annual dose limits are the doses associated with the concentration of 10 CFR Part 20, Appendix B, Table 2, Column I~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, either within or outside the SITE BOUNDARY, to an annual average concentration exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20 (Subpart D of,10 GFR Part 20).For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

This control applies to the release of radioactive materials in gaseous effluents from all units at the site.The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).Detaile~iscussion of the LLD and other detection limits can be found in Currie, L.A., Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984)and in the HASL Procedures Manual, HAS L-300.St.Lucie Plant ODCM Controls-Bases Page 70 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE-NOBLE GASES This control is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.The control implements the guides set forth in Section I.B.of Appendix I.The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with, the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1, July 1977.The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site.For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are to be proportioned among the units sharing that system.3/4.11.3.3 DOSE-IODINE-131 IODINE-'I 33 TRITIUM AND RA5lOACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.The Controls are the guides set forth in Section II.C of Appendix I.The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV,A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.

The ODCM calculational methods specified in the St.Lucie Plant ODCM Controls-Bases Page 71 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE-NOBLE GASES Continued 3/4.11.2.3 DOSE-IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM Continued Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject material are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases.of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate controls for Iodine-1 31, Iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.The pathways that were examined in the development of the 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 animah 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.This control applies to the release of radioactive materials in gaseous effluents from each unit at the site.For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.St.Lucie Plant ODCM Controls-Bases Page 72 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.

This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in 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 dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents.

This control applies to the release of radioactive materials in gaseous effluents from~~each unit at the site.For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.3/4.11.2.5 NOT USED 3/4.11.2.6 NOT USED 3/4.11.3 NOT USED 3/4.11.4 TOTAL DOSEThis control is provided to meet the dose limitations of 10 C~Part 190 that have been incorporated into.10 CFR Part 20 by 46 FR 18525.The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.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 Part 190 if the individual reactors remain within twice the dose design objectives of Appendix l,and if direct radiation doses from the units (including outside storage tanks, etc.)are kept small.The Special Report will describe a course of action that should result in the limitation St.Lucie Plant ODCM Controls-Bases

Page 73 of 225 OFFSITE RADIOACTIVE EFFLUENTS ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 DOSE CALCULATION MANUAL ODCM BASES 3/4.11.4 TOTAL DOSE Continued of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and Subpart M of 10 CFR Part 20, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1~An individual is not considered a MEMBER OF THE PUBLIC during any~~~period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.St.Lucie Plant ODCM Controls-Bases Page 74 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.The initially specified monitoring program will be effective for at least the first three years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).The LLDs required by Table 4.12-1 are considered optimum 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 oi a measurement system and not as an a gosteiiori (atter the fact)limit for a particular measurement.

Detailed discussion of the LLD and other detection limits can be found in Currie, L.A., Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measu'rements, NUREG/CR-4007 (September 1984)and in the HASL Procedures Manual, HASL-300.3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used.St.Lucie Plant ODCM Controls-Bases Page 75 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS Continued This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 50 square meters provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kilograms/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.To determine this minimum garden size, the following assumptions were made: (1)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 kilograms per square meter.3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This requirement for participation in an approved 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 valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.St.Lucie Plant ODCM Controls-Bases Page 76 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION METHODOLOGY for the CONTROLS AND SURVEILLANCE REQUIREMENTS Page 77 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTiON GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION D8 CC or cc Dose from Beta Radiation Cubic centimeter Ci C, CFR Control(s)

Curies-a unit of radioactivity see pCi Activity or concentration of a nuclide in the release source.Units'f pCi, pCi/cc or pCi/ml Code of Federal Regulations Regulations for operating, controlling, monitoring and reporting radioactive effluent related activity as indicated by the Controls Section of the ODCM.Dose The exposure, in mrem or mrad, the organ or the individual receives from radioactive effluents Dose Factor Dose Pathway Dose Rate (D/Q)ECL Normally, a factor that converts the effect of ingesting radioactive material into the body, to dose to a specific organ.Body elimination, radioactive decay and organ uptake are some of the factors that determine a dose factor for a given nuclide A specific path that radioactive material physically travels through prior to exposing an individual to radiation.

The Grass-Cow-Milk-Infant is a dose pathway The dose received per unit time A long term D over Q-a factor with units of 1/m'hich describes the deposition of particulate matter from a plume at a point downrange from the source.It can be thought of as what part of the cloud is going to fallout and deposit over one square meter of ground.(See Appendix C).Effluent Concentration Limit FUSAR Final Updated Safety Analysis Report.

Page 78 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION (continued)

Ground Plane A gamma photon-The dose from Gammas in air, etc.Radioactive material deposited uniformly over the ground emits radiation that produces an exposure pathway when an individual is standing, sitting, etc., in the area.It is assumed that an adult receives the same exposure as an infant, regardless of the physical height differences.

Only the whole body is considered for the ODCM.H-3 I88DPm'uclide Organ pCi (Q Dot), Q, Radioiodine s Hydrogen-3 or Tritium, a weak Beta emitter Radioiodines and particulates with half-lives greater than 8 days Cubic Meters Square Meters For the purposes of this manual, a radioactive isotope.Nuclide (i)signifies a specific nuclide, the 1st, 2nd, 3rd one under consideration.

If nuclide (i)is l-131, then the Mi (dose factor)under consideration should be M/$3$for example.For the ODCM either the bone, liver.thyroid, kidney, lung, Gl-LLI or the Whole Body.Whole Body is considered an organ for ease of writing the methodology in the ODCM.1 pico-Curie

=1.E-12 Curies.(Q Dot),-Denotes a release rate in pCI/sec for nuclide (i).Denotes pCi of nuclide (i)released over a specified time interval.Iodine-131 and Iodine l-133 for gaseous release pathways.

Page 79 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION (continued)

Receptor The individual receiving the exposure in a given location or who ingests food products from an animal for example.A receptor can receive dose from one or more pathways.TS Release Source(s)-A subsystem, tank or vent where radioactive material can be released independently of other radioactive release points.I The St.Lucie Plant Standard Technical Specifications Total Body Same as Whole Body in Control Statements p,Ci micro Curies.1 p.Ci=10 Curies.The pCi is the standard unit of radioactivity for all dose calculations in the ODCM.(X/Q)A long term Chi over Q.It describes the physical dispersion characteristics of a semi-infinite cloud of noble gases as the cloud traverses downrange from the release point.Since Noble Gases are inert, they do not tend to settle out on the ground.(See Appendix C).(X/Q)~A long term Depleted Chi over Q.It describes the physical dispersion characteristics of a semi-infinite cloud of radioactive iodines and particulates as the cloud travels downrange.

Since lodines and particulates tend to seftle out (fallout of the cloud)on the ground, the (X/Q)0 represents what physically remains of the cloud and its dispersion qualities at a given location downrange from the release point.(See Appendix F).~dt, bt or delta t-A specific delta time interval that corresponds with the release interval data etc.

Page 80 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.0 LIQUID RELEASES METHODOLOGY Page 81 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.1 Radioactive Li uid Effluent Model Assum tions The FUSAR contains the official description of the site characteristics.

The description that follows is a brief summary for dose calculation purposes: The St.Lucie Plant is located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean.Normally, all radioactive liquid releases enter the Atlantic Ocean where the Circulating Water Discharge Pipe terminates on the ocean floor at a point approximately 1200 feet offshore (Figure 1-1 Point"L").No credit is taken for subsequent mixing of the discharge flume with the ocean.The diffusion of radioactive material into the ocean is dependent on the conditions of tide, wind and some eddy currents caused by the Gulf Stream.The conditions are sufficiently random enough to distribute the discharges over a wide area and no concentrating effects are assumed.There are no direct discharge paths for liquid effluents to either of the north or south private property boundary lines.The Big Mud Creek (part of the Indian River)does connect to a normally locked shut dam, that is intended to provide an emergency supply of circulating water to the Intake Cooling Water Canal in the event a Hurricane causes blockage of the Intake Canal.No radioactive water could be discharged directly into the Intake Cooling Water Canal because all plant piping is routed to the discharge canal and no back flow can occur.Consult the FUSAR for a detailed description of characteristics of the water bodies surrounding the plant site.Only those nuclides that appear in the Liquid Dose Factor Tables will be considered for dose calculation.

Page 82 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.2 Determinin the Fraction F of 10 CFR Part 20 ECLs Limits for A Li uid Release Source Discussion

-Control 3.11.1.1 requires that the sampling and analysis results of liquid waste (prior to discharge) be used with calculation methods in the in-plant procedures to assure that the concentration of liquid radioactive material in the unrestricted areas will not exceed ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2.Chemistry Procedure C-70"Processing Aerated Liquid Waste" provides instruction for ensuring batch release tanks will be sampled after adequate mixing.This section presents the calculation method to be used for this determination.

This method only addresses the calculation for a specific release source.The in-plant procedures will provide instructions for determining that the summation of each release source's F values do not exceed the site's 10 CFR Part 20 ECL.The values for release rate, dilution rate, etc., will also have to be obtained from in-plant procedures.

The basic equation is: n C, F~=Z D I 1 (ECL)I Where: Fthe fraction of 10 CFR Part 20 ECL that would result if the release source was discharged under the conditions specified.

R The undiluted release rate in gpm of the release source.Liquid Rad Waste=170 gpm for Waste Monitor Tank Steam Generator=125 gpm/Steam Generator Liquid Rad.Waste=60 gpm for AWST¹2 Liquid Rad Waste=60 gpm for Laundry Drain Pumps 2A/2B D The dilution flow in gpm of Intake Cooling Water or Circulating Water Pumps Intake Cooling flow is 14,500 gpm/pump Circulating Water flow is 121,000 gpm/pump C, The undiluted concentration of nuclide (i)in p.CI/ml from sample assay (ECL), The Effluent Concentration Limit of nuclide (i)in p,CI/ml from Table L-1.For dissolved or entrained noble gases the ECL value is 2 X 10 p,CI/ml for the sum of all gases.-

Page 83 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INETHODOLOGY SECTION 1.2 (continued)

The fraction of the 10 CFR Part 20 ECL limit may be determined by a nuclide-by-nuclide evaluation or for purposes of simplifying the calculation by a cumulative activity evaluation.

If the simplified method is used, the value of 3 X 10~pCI/ml (unidentified ECL value)should be substituted for (ECL),.and the cumulative concentration (sum of all identified radionuclide concentrations) or the gross concentration should be substituted for C,.As long as the diluted concentration (C~R/D)is less than 3 X 10+pCI/ml, the nuclide-by-nuclide calculation is not required to demonstrate compliance with the 10 CFR Part 20 ECL.The following section provides a step-by-step procedure for determining the ECL fraction.1.Calculation Process for Solids A.Obtain from the in-plant procedures, the release rate value (R)in gpm for the release source.B.Obtain from the in-plant procedures, the dilution rate (D)in gpm.No credit is taken for any dilution beyond the discharge canal flow.C.Obtain (C,), the undiluted assay value of nuclide (i), in pCi/ml.If the simplified method is used, the cumulative concentration (Ct t I)is used.D.From Table L-1, obtain the corresponding (ECL)for nuclide (i)in p,Ci/ml.The value of 3 X 10'CI/ml should be used for the simplified method.E.Divide C, by (ECL), and write down the quotient F, If the simplified method is used, proceed to the next step.If determining the ECL fraction by the nuclide-by-nuclide evaluatio~repeat steps 1.2.1.C through 1.2.1.E for each nuclide reported in the assay, for H, from previous month composite and for SR89/90 and Fe55 from previous quarter composite with known results.

Page 84 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.2 (continued) 1.(continued)

G.Add each C/(ECL)quotient from step 1.2.1.E and solve for F, as follows: R n C, F~=Z D I 1 (ECL)i F=a unit-less value where: the value of Fcould be<or>1.The purpose of the calculation is to determine what the initial value of Fis for a given set of release conditions.

H.The Fvalue just obtained is for one release pathway.The TS and ODCM control 3.11.1.1 allow for a site limit of Fless than or equal to 10.Chemistry Procedure C-70 administratively controls each pathway's allocation.

Compare your Fresult with the administrative control for the release pathway in C-70.2.Calculation Process for Gases in Liquid A.Sum the pCI/ml of each noble gas activity reported in the release.B.The values of R and D from 1,2.1 above shall be used in the calculations below: (sum of 1.2.2A)ij,Ci!ml X R 9 1 D C.F, shall be less than 2 X 10 p,CI/ml for the site for all releases in progress.Each release point will be administratively controlled.

Consult C-70 procedure for instructions.

Page 85 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 Determinin Set pints for Radioactive Li uid Effluent Monitors 1.3.1 Setpoints for Batch Liquid Release Monitors channel numbers R6627 and 301 on Table 3.3-14, Radioactive Effluent Monitor Setpoint Basis, are the Batch Liquid Effluent Monitors.Discussion

-Control 3.3.3.9 requires that the liquid effluent monitoring instrumentation alarm/trip setpoints be set to initiate an alarm or trip so that the radioactivity concentration in water in the unrestricted area does not exceed the concentration of 10 CFR Part 20, Appendix B, Table 2 as a result of radioactivity in liquid effluents (Control 3.11.1.1).

Gross cpm vs.total liquid activity curves are available for Batch Liquid Effluent Monitors based on a composite of real release data.A direct correlation between gross cpm and the concentrations that would achieve 10 CFR Part 20 ECL levels in the discharge canal can be estimated.

The 1978 liquid release data from annual reports was used to determine the average undiluted release concentration.

These concentrations were then projected to a diluted concentration in the discharge canal assuming a 1 gpm release rate and a constant dilution flow of 121,000 gpm from 1 circ.water pump.This diluted activity was divided by the nuclide's respective 10 CFR Part 20 ECL value (Table L-1)to obtain the Mi column on the table that follows:

Page 86 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 (continued)

NUCLIDE SYMBOL l-131 l-132 I-133 I-135 Na-24 Cr-51 Mn-54 Mn-56 Co-57 Co-58 Fe-59 Co-60 Zn-65 Ni-65 Ag-110 Sn-113 Sb-122 Sb-124 W-1 87 Np-239 Br-82 Zr-95 Zr-97 Mo-99 Ru-103 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 M~~=TABLE 1.3 1978 UNDILUTED pCI/ml'.43 E-5 2.23 E-7 3.17 EW 1.31 E-6~1.72 E-7 2.51 E-5 5.64 E-6 1.11 E-9 3.69 E-7 1.51 EA 2.92 E-6 3.66 E-5 4.55 E-7 8.23 E-7 1.96 E-6 5.75 E-7 2.15 E-6 8.40 E-6 3.51 E-6 1.57 E-7 3.64 E-7 2.82 E-5 4.05 E-6 3.24 E-6 3.84 E-8 2.26 E-6 2.14 E-5 7.82 E-7 4.85 E-5 6A4 E-7 3.04 E-8 2.37 E-6 4.01 EA M, (no units)3.66 EA 1.84 E-8 3.74 E-6 3.61 E-7 2.84 E-8 4.15 E-7 1.55 E-6 1.31 E-'10 5.08 E-8 6.24 E-5 2.41 E-6 1.01 EA 7.52 E-7 6.8 E-8 2.70 E-6 1.58 E-7 1.78 E-6 9.92 E-6 9.67 E-7 6.49 E-8 7.52 E-8 1.17 E-5 3.72 E-6 1.34 E-6 1.06 E-8 6.23 E-7~7 EA 1.08 E-6 4.01 E-4 6.65 E-7 8.38 E-9 6.53 E-6 1.18 E-3 (1)1978 Undiluted Release Volume=7 E 9 ml~~~~1978 Undil.Act Nuclide (I)<1 gpm (release rate)ECL, (from Table L-1)121000 gpm (dil rate)

Page 87 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 (continued)

A, is the total average pCi/ml concentration of the reference mixture and M,is the fraction of the MPC of all nuclides for the release conditions specified.

Dividing Arby M, yields A~, which is the maximum total activity concentration equivalent to the ECL limit for the nuclide distribution typical of radwaste discharges.

The Technical Specifications allow 10 times the ECL limit where the Site Limit is 10 times A~as follows: A~-"-',-0.34 pCi/ml=ECL Limit~rot 4.01 E-4 Mrot 1.18 E-3 Site Limit=10 x A~=10 x 0.34=3.4 pCi/ml To provtde conservative administrative control, A~of 0.34 pCi/ml should be used as follows: If the effluent monitor requires counts per minute units, a (C)value in cpm should be obtained for the A (0.34 pCi/ml)from the release sources radioactive liquid effluent monitor curve of cpm vs.pCi/ml.NOTE This setpoint is for a specified release of 1 gpm into 121 000 gpm dilution flow.2.For establishing the setpoint prior to liquid radwaste discharges, the A (or C)will be adjusted as needed to account for actual release conditions (i.e., actual design maximum discharge flow rate, dilution flow rate and the contribution of dissolved and entrained Nobles Gas Activity to the Monitor Activity Level).

Page 88 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 (continued)

1.3.2 Setpoints

for Continuous Liquid Release Monitors Discussion

-The activity mixture described in 1.3.1 for Liquid Batch Release Monitors cannot be used for Continuous Liquid Pathways since the Steam Generator (S/G)Blowdown Secondary Side is subject to what the current Reactor Coolant System (RCS)activity and primary-to-secondary leakage exist at any time.Although S/G blowdown is not normally aligned to the Site Liquid Radwaste Release Point (Figure 1-1), the monitor setpoints will be based on the ODCM maximum design S/6 blowdown rate of 125 gpm with 1 Circulating Water Pump (CWP)121,000 gpm in operation.

The ODCM and C-70, Processing Liquid Waste assume that the fraction of solids entering the Discharge Canal to the site release point are controlled less than or equal to 1.0, with batch release using 80%and the remaining 20%allocated to continuous sources on site.The actual site limit for solids is 10 times the concentration specified in 10 CFR Part 20, therefore a conservation factor of 10 is already included in the administrative site limit.Since source in-leakage to a S/6 cannot be controlled, a High alarm monitor setpoint is calculated based on one S/6 releasing to the discharge canal at design blowdown rate while attaining the 20 percent of the site limit (FQ assuming all the gross solid activity is I-131.The contribution from Dissolved and Entrained Gases is assumed to be zero with all of the gaseous activity going to the Steam Condenser and Air Ejector pathway.Fat 20%=0.2=Desi n blowdown rate x I-131 uCi/ml S/6 1 1 CWP Dilution rate I-131 uCi/ml (Table L-1ECL)F t20'/=02=~125 II i*I-13i~i I SIG 121,000 gal/min 1.E-06 uCi/ml (I-131 Table L-1ECL)Solving for the S/G High Alarm Setpoint I-131 Activity, l-131 uCi/ml (S/6)=-2E-04 uCi/ml I-131 is the maximum S/6 activity that could be allowed such that 20 percent of the administrative discharge canal limit would not be exceeded.

Page 89 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 (continued) 1.3.2 (continued)

This S/G Monitor High Alarm Setpoint activity may be converted to cpm using Liquid Monitor uC/ml to cpm conversion constants.

This Setpoint is conservative given that the actual Liquid Site Limit is a factor of ten times higher than the administrative limit used for calculation purposes, that I-131's ECL is conservative vs other isotope mixtures, and that it is unlikely that more than one S/G would be allowed to operate with a 20 gallon per day primary-to-secondary leak rate.1.4 Determinin the Dose for Radioactive Li uid ReleasesDiscussion

-Control 3.11.1,2 requires calculations be performed at least once per 31 days to verify that cumulative radioactive liquid effluents do not cause a dose in excess of 1.5 mrem to the whole body and 5 mrem to any organ during any calendar quarter and not in excess of 3 mrem to the whole body and 10 mrem to any organ during any calendar year.This section presents calculational method to be used for this verification.

This method is based on the methodology suggested by sections 4.3 and 4.3.1 of NUREG-0133 Revision 1, November, 1978.The dose factors are a composite of both the fish and shellfish pathways so that the fish-shellfish pathway is the only pathway for which dose will be calculated.

The dose for adult, child and teenager can also be calculated by this method provided that their appropriate dose factors are available for the organ of interest.An infant is excluded from Liquid Dose Pathway at St, Lucie since they do not eat fish-shellfish.

The effluent supervisor will track which age group is the controlling (most restrictive) age group (see control 3.11.2.6.c).

Only those nuclides that appear in the Tables ops manual will be considered.

Page 90 of 225 e ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.4 (continued)

This method provides for a dose calculation to the whole body or any organ for a given age group based on real release conditions during a specified time interval for radioactive liquid release sources.The equation is: A, dt,Q(oF), Where: D, T dose commitment in mrem received by organ T of age group (to be specified) during the release time interval dt,.AT the composite dose factor for the fish-shellfish pathway for nuclide (i)for organ T of age group (to be specified).

The A~values listed in the Tables in this manual are independent of any site specific information and have the units mrem-ml p,Ci-hr dt Q,, the number of hours that the release occurs.The total quantity of nuclide (i)release during dt, (p,CI)(DF),=The total volume of dilution that occurred during the release time period dt, (i.e., the circulating water flow times time)The doses associated with each release may thence summed to provide the cumulative dose over a desired time period (e.g., sum aliases for release during a 31 day period, calendar quarter or a year).tOt8lg 1q Where: DT T the total dose commitment to organ T due to all releases during the desired time interval (mrem)

Page 91 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.4 (continued) 1.(continued)

NOTE Table 1.4 may be used for compiling the dose accounting.

A.Determine the time interval dt, in hours that the release took place.For once per 31 day dose calculations dt, would be for the entire month's hours.For quarterly dose calculations dt, would be the hours in the quarter, and for annual dose calculations dt, would be the hours in the year.If required, dt, may be hours of duration of a single release to evaluate a batch release.B.Obtain (DF), for the time period dt, from Liquid Waste Management Records for the release source(s)of interest.C.Obtain Q,.l for nuclide (i)for the time period dt, from the Liquid Waste Management Records D.Obtain A~from the appropriate Liquid Dose Factor Table Age Group Infant Child Teen Adult Dose Factor Table N/4-L-4 L-3 L-2 Page 92 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.4 (continued) 1.(continued)

TABLE 1A FISH AND SHELLFISH PATHWAY TIME/DATE START: TOTAL DILUTION VOLUME:/~TIME/DATE STOP: mls//HOURS AGE GROUP: NUCLIDE (i)ORGAN: C,.(p,Ci)Arr DOSE FACTOR TABLE¹: DOSE (i)mrem E.Solve for Dose (i)TOTAL DOSE~=mrem(DF Page 93 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.4 (continued) 1.(continued)

F.For the age group(s)of interest, repeat steps 1.4.1.C through 1.4.1.E for each nuclide reported and each organ required.G.For the age group(s)of interest, sum the Dose (i)values to obtain the total dose to organ T from the fish-shellfish pathway.1.5 Pro'ectin Dose for Radioactive Li uid EffluentsDiscussion

-Control 3.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce radioactive material in liquid effluents when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1)would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.The following calculation method is provided for performing this dose projection.

The method is based on dose as calculated in section 1.4 with the adult as the bases for projecting.

1.For the controlling age group obtain the latest result of the monthly calculation of the whole body dose and the highest organ dose.These doses can be obtained from the in-plant records.2.Divide each dose by the number of days the reactor plant was operational during the month.3.Multiply the quotient of each dose by the number'f days the reactor plant is projected to be operational during the next month.The products are the projected dose for the next month.These values should be adjusted as needed to account for any changes in failed fuel or othe~entifiable operating conditions that could significantly alter the actual releases.4.If the projected dose is greater than 0.06 mrem to the whole body or greater than 0.2 mrem to the adults highest exposed organ, the liquid radwaste system shall be used.

Page 94 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.0 GASEOUS RELEASES METHODOLOGY Page 95 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION Gaseous Effluent Model Assum tions Descri tion of Site-(The FUSAR contains the official description of the site characteristics.

The description that follows is a brief summary for dose calculation purposes only).The St.Lucie Plant is located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean.Private property adjoins the plant site in the north and south directions.

A meteorological tower is located north of the plant near the site property line.There are 16 sectors, for dose calculation purposes, divided into 22.5'ach.The MET tower is calibrated such that a zero degree bearing coincides with TRUE NORTH.A bearing of zero degrees dissects the north sector such that bearings of 348.75 and 11.25'efine the boundaries of the north sector.The nearest distance to private property occurs in the north sector at approximately 0.97 miles.For ease of calculation, this 0.97 mile radius is assumed in all directions, although the real Unrestricted Area Boundary is defined in Figure 5.1-1 of the TS.Doses calculated over water areas do not apply to Controls or the annual report and may be listed as O.W.(over water)in lieu of performing calculations.

The 0.97 mile range in the NW sector is O.W., but it was chosen as the worst sector for conservative, dose calculations using the historical MET data.Historical MET Data-MET data, between September 1, 1976 and August 31, 1978, from the St.Lucie MET Tower was analyzed by Dames&Moore of Washington, D.C.The methodology used by Dames&Moore was consistent with methods suggested by Regulatory Guide 1.111, Revision 1.Recirculation correction factors were also calculated for the St.Lucie Site and are incorporated into the historical MET tables (Tables M5, M6 and M7)in Appendix A of this manual.It was determined that these two years are representative data for this locale.Dose Calculations

-Dose calculations for Control dose limits are normally calculated using historical MET data and receptor location(s) which yield calculated doses no lower than the real location(s) experiencing the most exposure.Actual MET data factors are calculated and used in dose calculations for the annual reports, Live MET data and hour-by-hour dose calculations are beyond the scope of this manual~Historical information and conservative receptor locations, etc., are only used for ease of Control dose limit calculations.

Dose calculations for Control dose limits may be performed using actual MET data and real receptor locations.

Any dose calculations performed with actual data should note the source of the data in the annual report.Actual MET data reduction should be performed in accordance with Regulatory Guide 1.111, Revision 1 and should incorporate Recirculation Correction Factors from Table M-4 of this manual.

Page 96 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.1 (continued)

Dose Calculations

-(continued)

The St.Lucie site uses the long term ground release model for all gaseous effluents.

Only those radionuclides that appear in the gaseous effluent dose factor tables will be considered in any dose calculations.

Radioiodines are defined as Iodine-131 and I-133 for application to Controls.Other nuclides of Iodine may be included in dose calculations for ease of performing calculations, but their dose contribution does not have to be included in the Control requirements.

Land Census information will apply to the calendar year following the year that the census was taken in to avoid splitting quarters, etc.2.2 Determinin the Total Bod and Skin Dose Rates for Noble Gas Releases And Establishin Set pints for Effluent Monitors Discussion

-Control 3.11.2.1 limits the dose rate from noble gases in airborne releases to<500 mrem/yr-total body and<3000 mrem/yr-skin.Control 3.3.3.11 requires that the gaseous radioactive effluent monitoring instrumentation be operable with alarm/trip setpoints set to ensure that these dose rate limits are not exceeded.The results of the sampling and analysis program of Control Table 4.11-2 are used to demonstrate compliance with these limits.The following calculation method is provided for determining the dose rates to the total body and skin from noble gases in airborne releases.The alarm/trip setpoints are based on the dose rate calculations.

The Controls apply to all airborne releases on the site but all releases may be treated as.if discharged from a single release point.Only those noble gases appearing in t'able G-2 will be considered.

The calculation methods are based on Sections 5.1 and 5.2 of NUREG-0133, November 1978.The equations are: For TOTAL BODY Dose Rate: n DR~=Z K, (X!Q)(Q DO+, I For TOTAL SKIN Dose Rate: n DR,~=Z[L,+1.1 M)(XtQ)(Q DOT),

Page 97 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued)

Where: DR~=total body dose rate fromnoble gases in airborne releases (mrem/yr)DR,~=skin dose rate from noble gases in airborne releases (mrem/yr)a mathematical symbol to signify the operations to the right of the symbol are to be performed for each noble gas nuclide (i)through (n)and the individual nuclide doses are summed to arrive at the total dose rate for the release source.the total body dose factor due to gamma emissions for each noble gas nuclide reported in the release source.(mrem-m'/pCi-yr) the skin dose factor due to beta emissions for each noble gas nuclide (i)reported in the assay of the release source.(mrem"-m'/pCi-yr)

M, the air dose factor due to gamma emissions for each noble gas nuclide (i)reported in the assay of the release source.The constant 1.1 converts mrad to mrem since the units of M, are in (mrad-m'/pCI-yr)(X/Q)=for ground level, the highest calculated annual long term historic relative concentration for any of the 16 sectors, at or beyond the exclusion area boundary (sec/m')(Q DOT),=The release rate of noble gas nuclide (i)in pCi/sec from the release source of interest Page 98 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.Setpoint Determination A.To comply with Control 3.3.3.10, the alarm/trip setpoints are established to ensure that all noble gas releases in progress do not exceed the ODCM Control 3.11.2.1 noble gas release rate limit for.the site.Using pre-ODCM Revision 0 data, the total body dose was determined to be more limiting than the calculated skin dose, therefore the site release rate limit of total body dose rate of 500 mrem/yr has been determined to be equivalent to 3.5E+05 uCi/sec being released from the site.Using 3.5E+05 uCi/sec as the equivalent of 100 percent of the site limit, each release point on site may be allotted a portion of the 100 percent, such that the sum of all release point portions allotted shall be less than or equal to 100 percent.The release point's actual monitor setpoint shall take into account the physical release characteristics of maximum expected volume release rate and its percent allotment for a single release point since uCi/sec is proportional to volume rate.The ODCM actual release points and an example of percent allotments is provided: Site Limit in Percent=100%Site Limit in uCi/sec=3.5E+05 uCi/sec ODCM Release Point Unit 1 Plant Vent Unit 1 Fuel Bldg.Vent ECCS 1A ECCS 1B Unit 2 Plant Vent Unit 2 Fuel Bldg.Vent ECCS 2A ECCS 2B Blowdown Bldg.Vent Total Percent Allocated=(Example)Percent Allotment 40 5 1 1 40 5 1 1+5 99 or 1 percent below the Site Limit Page 99 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

A.(continued)

More or less percentage may be used for a release point, but the sum of the total percent allocated to the above Release Points shall never be allowed to exceed 100 percent.The ECCS Reactor Auxiliary Building Exhaust are not ODCM required monitored release points, but a small percentage should be allotted to each to cover short periodic fan'urveillance runs.This allocation is controlled per Chemistry Procedure COP-07.05, Process Monitor Setpoints where Chemistry Supervisor approval is required.COP-07.05 provides calculation steps to calculate a Noble Gas Release Rate Setpoint based on the methodology steps described below.A release point's percent allotment will be converted into the release point's indicating engineering unit of uCi/cc that will be equivalent to the allocated portion of the site limit.1.Obtain the release point's maximum ex ected process flow release rate (V)in Cubic Feet per Minute (cfm)from the Effluent Supervisor.

2.Obtain the release point's percent of site limit allotment (PA)from the Chemistry Supervisor.

3.Substitute the release point's V and PA values into the below equation to obtain the Release Point's Setpoint (SP).SP=3.5E+05 uCi x 60 sec x min x ft x PA sec min V ft3 28317 cc 100%uCi/cc which is the TABLE 3.3-14 HIGH SETPOINT for ODCM Effluent Gas Channels that have a"Allotted%of Site Limit" declared as their HIGH SETPOINT.

Page 100 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

A.(continued)

In the case of Unit 2 Plant Vent there are 3 ODCM Effluent Gas Channels Monitoring the Plant Vent.The HIGH SETPOINT in uCi/cc is the same for 2A PV PIG LOW RANGE GAS, 2B PIG LOW RANGE GAS, and 2PV WRGM LOW RANGE GAS since they are monitoring the same release point (i.e., each of these channels does not receive their own allotted%of the Site Limit).4.The significance of an ODCM Effluent Gas Channel that has a"Allotted%of Site Limit" HIGH Setpoint requires further discussion (Mid and High Noble Gas Accident Channels are not part of this discussion):

a.For Plant Vent Release Points on each reactor unit, the"Allotted%of Site Limit" needs to be high enough to allow for Batch Releases from Gas Decay Tank and Containment Venting Operations, and at the same time C-72, Processing Gaseous Waste shall provide instruction for administratively controlling Batch Releases such that the radioactive concentration and release rate will not be allowed to exceed the site limit at any time.b.The receipt of a valid HIGH Alarm on a release point where the ODCM Low Range Gas Channel's r'adioactivity is approximately equal to the HIGH Alarm setpoint does not mean the site limit has been exceeded, rather it is at a concentration that is equivalent to the"Allotted%of Site Limit".

Wage 101 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1~(continued)

A.(continued) 4.(continued) c.The receipt of a valid HIGH Alarm on a release point where the ODCM Low Range Gas Channel's radioactivity is greater than the HIGH Alarm setpoint may quickly be estimated based on: F<<-RP<<+(Sum of all other Release Point's RP<<on site)RP<<=Rel Pt's Rel Pt's volume time Channel's x Release.x conv.x conv.x 1/(site limit)uCi/cc Rate const.const.RP<<-uCi x V ft'28317 cc x min x sec cc min ft3 60 sec 3.5E+05 uCi Where: F<<=Fraction of the Site Limit RP<<=Fraction of a Release Point's contribution to the site limit (Sum of all other Release Point's RP<<on site)is normally less than 0.10 under normal operating conditions.

V=in ft'/min, the Release Point's actual process Volume flow release rate A value of RP<<>1.0 or a F<<>1.0 would be exceeding the Site Limit Based on the above estimate.Off Normal ProcetfGre allow 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to obtain a grab sample of the Release Point so that the actual site limit situation may be evaluated.

This method is discussed in the following step.

Page 102 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

A.(continued) 5.To quantify the Release Point's actual Noble Gas Dose Rate, the following would need to be performed:

a.A Noble Gas Activity Grab Sample would be obtained and analyzed to determine each Noble Gas Isotopic concentration.

b.The results would be used to perform calculations per ODCM Step 2.2.2 for Noble Gas Total Body Dose Rate and Skin Dose Rate.c.If the Release Point's HIGH Alarms were received on the Table 3.3-14 ODCM Related Particulate and/or Iodine Channel, then ODCM Step 2.3 calculations should be performed as soon as possible after the continuous collection medium(s)and a Tritium Sample can be pulled and analyzed to evaluate compliance with ODCM Control 3.11.2.1.b.

Page 103 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-'200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

B.No Particulate or Iodine Radioactivity Channels are required by the ODCM.Table 3.3-13 requires Iodine and Particulate Samplers only.Technical Specification Table 3.3-6 requires a Fuel Building Vent Particulate Channel (the bases for the setpoint on the Fuel Building Vent Particulate Channel is described in 2,2.1.C).The FUSAR does describe Particulate and Iodine Radioactivity Channels.These Channels are listed in ODCM Table 3.3-14 and ALERT and HIGH Setpoints are provided.The intent of providing these setpoints is to provide early warning that the effluent pathway conditions have increased such that a grab sample should be obtained if a HIGH Alarm Setpoint is reached or exceeded.The Particulate and Iodine HIGH Alarm Setpoint bases is that the collection mediums are fixed filter where continuing deposition of radioactivity would cause a increase in the channel count rate up to the setpoint level(s), the resulting dose rate can be shown to be less than 1 percent of the site limit for ODCM Control 3.11.2.1.b for Iodine-131, Iodine-133, and all radionuclides in particulate from with half-lives greater than 8 days, is that these channel detectors are gross activity monitors of the scintillation type where the count rate is not dependent (above threshold) on the energy of the isotope entrained on the collection medium, and that these channels are qualitative trend indicators since the channel count rate cannot be corrected for the accrued sample collection volume.Plant historical trends have shown that Noble Gas Activity may contribute to the count rate of the Reactor Auxiliary Building (Plant)Vent Particulate and Iodine Channel(s), In this event the Noble Gas contribution may be added to the Table 3.3-14 Alert and High Setpoints for Plant Vents only.The sampling mediums associated with the Particulate and Iodine Channels in Table 3.3-14 are also controlled by the requirements of ODCM Table 4.11-2 which requires 4/M Minimum Analysis Frequency of the sampling mediums.These analysis are used to confirm and quantify the isotopic composition of the radioactivity being monitored by these channels.The presence of Noble Gas on collection medium would be confirmed by these analysis.

Page 104 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

B.(continued)

If an alarm occurs, Channel Check(s).should be performed on these channel(s), an ALERT Alarm should be investigated and a HIGH Alarm shall require isotopic analysis of particulate and/or iodine channel medium of the affected channel(s)

~The Isotopic analysis of the medium shall be used to evaluate particulate and/or iodine dose rate levels per the methodology of ODCM 2.3.C.To comply with Technical Specification 3.3.3.1, Table 3.3-6 Radiation Monitoring Instrumentation,"Instrument 2.a.ii.Particulate Activity", with Alarm/Trip Setpoint determined and set in accordance with the requirements of the Offsite Dose Calculation Manual, the following is the BASES for Fuel Building Particulate Channel High Alarm Setpoints for Unit 1 and Unit 2: Unit 1 Fuel Buildin: The 10,000 cpm High Setpoint is based on an infant's Maximum Exposed Organ Dose Rate (Liver)from Inhalation of Cs-137 at the Site Boundary.The value of 10,000 cpm is very conservative relative to the site dose rate limit of 1500 mrem/yr.The methodology is based on measured particulate channel count rates when the detector was calibrated with a known source activity of Cs-137, and on default assumptiong as follows: 1.The particulate channel read 32,385 ccpm when exposed to a 7.67 uCi source of Cs-137.2.Assuming that 7.67 uCi of Cs-137 were collected during 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of skid sample collection (fixed filter), the typical sample volume would yield-3.3E+06 cc's.Greater than 99%sample filter efficiency is assumed.

Page 105 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

C.(continued) 3.The maximum building process flow exhaust is-24,576 cfm.4.Q(dot)for Cs-137 uCi/sec release rate is approximately 27 uCi/sec as follows: 7.67 uCi x hour x 28317 cc's x 24576 ft3 x min=27 uCi hour 3.3E+06cc.s ft3 min 60 sec sec 5.The default historical (X/Q)d for the worst sector (NW)at the site boundary is 1.3E-06 meters/sec.

6.The dose rate (equivalent to 10,000 cpm)is calculated per ODCM Section 2.3 Inhalation Dose Rate to an Infant.The resulting dose rates yield.Bone mrem/yr 7.4E+00 Liver mrem/yr 7.9E+00 Thyroid mrem/yr O.0E+00 Kidney mrem/yr 4.2E-01 Lung Gl-LLI W.Body mrem/yr mrem/yr mrem/yr 1.0E+00 1.5E-02 4.8E-01 7.The ODCM 3.11.2.1.b dose rate limit to any organ is 1500 mrem/yr.From the preceding calculation the Infant's Liver is the maximum exposed organ at 0.52 percent of the site-dose rate limit.8.A particulate channel setpoint of 10,000 cpm provides a conservative setpoint given that this channel analyzes gross a~c'ty on a fixed filter, Cs-137 is a typical long-lived fission product pre3ent at all times with spent fuel in the pool, and that sample collection intervals shorter than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months would provide adequate warning response if significant particulate activity were being released, i.e., the above assumptions assume a Cs-137 activity of-2.3E-06 uCi/cc.

Page 106 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

C.(continued) 9.The setpoint of 10,000 cpm was administratively chosen to provide early detection/alarm of a problem.The above dose rate calculations are provided to document that the particulate channel is capable of detection sensitivities to insure compliance with the ODCM site limit.Grab samples should be performed to accurately calculate actual releases associated with real high alarm events as per the ODCM methodology for performing dose rate calculations.(End of Unit 1 Fuel Building evaluation)

Unit 2 Fuel Buildin: The 10,000 cpm High Setpoint is based on an Infant's Maximum Exposed Organ Dose Rate (Liver)from Inhalation of Cs-137 at the Site Boundary.The value of 10,00 cpm is very conservative relative to the site dose rate limit of 1500 mrem/yr.The methodology is based on measured particulate channel count rates when the detector was calibrated with a known source activity of Cs-137, and on default assumptions as follows: 1.The particulate channel read 39,782 ccpm when exposed to a 7.59 uCi source of Cs-137 (decayed to June 19, 1996 data).2.Assuming that 7.59 uCi of Cs-137 were collected during 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of skid sample collection (fixed filter), the typical sample volume would yield-5.32E+06 cc's.Greater than 99%sample filter efficiency is assumed.3.The maximum building process flow exhaust is~,584 cfm.4.Q(dot)for Cs-137 uCi/sec release rate is approximately 21 uCi/sec as follows: 7.59 uCi x hour x 28317 cc's x 31584 ft3 x min=21.26 uCi hour 5.32E+06cc.s ft3 min 60 sec sec Page 107 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 1.(continued)

C.(continued) 5.The default historical (X/Q)d for the worst sector (NW)at the site boundary is 1.3E-06 meters/sec.

6.The dose rate (equivalent to 10,000 cpm)is calculated per ODCM Section 2.3 Inhalation Dose Rate to an Infant.The resulting dose rates yield.Bone Liver Thyroid Kidney Lung Gl-LLI W.Body mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr 4.8E+00 5.08E+00 O.OE+00 2.7E-01 7.0E-01 1.0E-02 3.1E-01 7.The ODCM 3.11.2.1.b dose rate limit to any organ is 1500 mrem/yr.From the preceding calculation the Infant's Liver is the maximum exposed organ at 0.34 percent of the site dose rate limit.8.A particulate channel setpoint of 10,000 cpm provides a conservative setpoint given that this channel analyzes gross activity on a fixed filter, Cs-137 is a typical long-lived fission product present at all times with spent fuel in the pool, and that sample collection intervals shorter than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months would provide adequate warning response if significant particulate activity were being released, i.e., the above assumptions

~assume a Cs-137 activity of-1.4E-06 uC'r/cc.9.The setpoint of 10,000 cpm was administratively chosen to provide early detection/alarm of a problem.The above d~rate calculations are provided to document that the particulate channel is capable of detection sensitivities to insure compliance with the ODCM site limit.Grab samples should be performed to accurately calculate actual releases associated with real high alarm events as per the ODCM methodology for performing dose rate calculations.

Page 108 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 2.Total Body and Skin Nuclide Specific Dose Rate Calculations The following outline provides a step-by-step explanation of how the total body dose rate is calculated on a nuclide-by-nuclide basis to evaluate compliance with Control 3.11.2.1.This method is only used if the actual releases exceed the value of 3.5 X 10'Ci/sec.

A.The (X/Q)value=sec/m'nd is the most limiting sector at the exclusion area.(See Table M-1 for value and sector.)B.Enter the release rate in ft'/min of the-release source and convert it to:)ft'2.8317 X 10'cc X min min ft'0.seccc/sec volume release rate C.Solve for(Q DOT), for nuclide (i)by obtaining the pCi/cc assay value of the release source and multiplying it by the product of 2.2.2.B above.(Q DOT),=(nuclide[I])(assay)p,Ci X (2.2.2.B value)cc cc sec (Q DOT),=pCi/sec for nuclide (i)D.To evaluate the total body dose rate obtain the K, v~for nuclide (i)from Table G-2.E.Solve for DR~,.OR,=K(X/Q)(Q DOT),=mrem-m'sec X PCI p,Ci-yr m'ec DR~=mrem total body dose from nuclide (i)for yr the specified release source Page 109 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued) 2.(continued)

F.To evaluate the skin dose rate, obtain the L,-and M, values from Table G-2 for nuclide (i).G.Solve for DR,~, DR~)(j~j[g+<1 M'J (X/Q)(Q DOT)j I DR,.,=mrem skin dose from nuclide (i)for the yr specified release source H.Repeat steps 2.2.2.D through 2.2.2.G for each noble gas nuclide (i)reported in the assay of the release source.I.The Dose Rate to the Total Body from radioactive noble gas gamma radiation from the specified release source is: n DR~=Z DR~I J.The Dose Rate to the skin from noble gas radiation from the specified release source is: n DR,~=Z DR,~, I The dose rate contribution of this release source shall be added to all other gaseous release sources that are in progress at the time of interest.Refer to in-plant procedures and logs to determine the Total Dose Rate to the Total Body and Skin from noble gas effluents.

Page 110 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 Determinin the Radioiodine 8 Particulate Dose Rate to An Or an From Gaseous Releases Discussion

-Control 3.11,2.1 limits the dose rate from 1-131, I-133, tritium and all radionuclides in particulate form with half lives>eight days to<1500 mrem/yr to any organ.The following calculation method is provided for determining the dose rate from radioiodines (see 2.1)and particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in NUREG-0133, November 1978.The Infant is the controlling age group in the inhalation, ground plane and cow/goat milk pathways, which are the only pathways considered for releases.The long term (X/Q), (depleted) and (D/Q)values are based on historical MET data prior to implementing Appendix I.Only those nuclides that appear on their respective table will be considered.

The equations are: For Inhalation Pathwa excludin H-3:DRl&BpP~.(X/Q)p (Q DOT)n R I For Ground Plane: n DRl&8pP Z j (D/Q)(Q DO+)I For Grass-Cow/Goat-Milk:

DR~8pp Z (D/Q)(Q DOT))I For Tritium Releases Inhalation

&Grass-Cow/Goat-Milk:

DRY Rp 3 (XQ)p (Q DOT)g 3 7*Normally should be Pibut Ri~values are the same, thus use Ri~tables in Appendix A.

0 s~'h I Page 111 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued)

For Total Dose Rate from I 8 8DP and H-3 To An infant Or an T: Z DRr Z[DReBDp~DR3)Where: I&8DPT DR~T DR~RI P, The organ of interest for the infant age group The applicable pathways Dose Rate in mrem/yr to the organ T from iodines and 8 day particulates Dose Rate in mrem/yr to organ T from Tritium Total Dose Rate in mrem/yr to organ T from all pathways under consideration A mathematical symbol to signify the operations to the right of the symbol are to be performed for each nuclide (i)through (n)and the individual nuclide dose rates are summed to arrive at the total dose rate from the pathway.A mathematical symbol to indicate that the total dose rate D, to organ T is the sum of each of the pathways dose rates The dose factor for nuclide (i)for organ T for the pathway specified (units vary by pathway)The dose factor for instantaneous ground plane pathway in units of mrem-m'ec p,Ci-yr Page 112 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued)

From an evaluation of the radioactive releases and environmental pathways, the grass-cow/goat-milk pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ.This pathway typically contributes

>90%of the total dose received by the infant's thyroid and the radioiodine contribute essentially all of this dose.Therefore, it is possible to demonstrate compliance with the release rate limit of Control 3.11.2.1 for radioiodines and particulates by only evaluating the infant's thyroid dose for the release of radioiodines via the grass-cow/goat-milk pathway.The calculation method of Section 2.3.3 is used for this determination.

If this limited analysis approach is used, the dose calculations for other radioactive particulate matter and other pathways need not be performed.

Only the calculations of Section 2.3.3 for the radioiodines need be performed to demonstrate compliance with the Control dose rate limit.The calculations of Sections 2.3.1, 2.3.2, 2.3.4 and 2.3.5 may be omitted.The dose rate calculations as specified in these sections are included for completeness and are to be used only for evaluating unusual circumstances where releases of particulate materials other than radioiodines in airborne releases are abnormally high.The calculations of Sections 2.3.1, 2.3.2, 2.3.4 and 2.3.5 will typically be used to demonstrate compliance with the dose rate limit of Control 3.11.2.1 for radioiodines and particulates when the measured releases of particulate material (other than radioiodines and with half lives>8 days)are>10 times the measured releases of gadioiodines.

1.The Inhalation Dose Rate Method: NOTE The H-3 dose ls calculated as per 2.3.4.A.The controlling location is assumed to be an Infant located in the sector at the mile range.The (X/Q)D for this location is sec/m'.This value is common to all nuclides.(See Table M-2 for value, sector and range.)B.Enter the release rate in ft'/min of the release source and convert to cc/sec.min ft'2.8317 X 10'CC X min ft'0 sec.

Page 113 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 1.(continued)

C.Solve for (Q DOT),.for nuclide (i)by obtaining the Ij.CI/cc assay value of the release source activity and multiplying it by the product of 2.3.1.B above.(Q DQ7)(nuclide I'i]assay)WCi<(Value 2.3.1.B)cc cc sec (Q DOT),=: pCI/sec for nuclide (i)D.Obtain the R, value from Table 6-5 for the organ T.E.Solve for DR, PR R (X/Q)(Q DQ 7)mrem-m X sec X Ij I IjCi-yr m'ec DR~=mrem The Dose Rate to organ T from nuclide (i)yr F.Repeat steps 2.3.1.C through 2.3.1.E for each nuclide (i)reported in the assay of the release source.G.The Dose Rate to the Infants organ T from the Inhalation Pathway is: DR,~,,=DR,+DR2++ORfor all nuclides except H-3.This dose rate shall be sQEed to the other pathways as per 2.3.5-Total Organ Dose.NOTE Steps 2.3.1.C through 2.3.1.G need to be completed for each organ T of the Infant.

Page 114 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 2.The Ground Plane Dose Rate Method: NOTE Tritium dose via the ground plane is zero.A.The controlling location is assumed to be an Infant located in the sector at the mile range.The (D/Q)for this location is~1/m'.This value is common to all nuclides.(See Table M-2 for sector, range and value.)B.Enter the release rate in ft'/min of the release source and convert to cc/sec.ft'2.8317 X 10'cc X min min ft'0 sec.C.Solve for (Q DOT),.for nuclide (i)by obtaining the p.Ci/cc assay value from the release source activity and multiplying it by the product of 2.3.2.B above.(Q QQ7)(nuclide fi1 assay)Ij.ci X (Value 2.3.2.B)cc CC sec (Q DOT),=p.CI/sec for nuclide (i)D.Obtain the P, value from Table G-3 E.Solve for DR, OR,=p.(0/Q)(Q 0073,-mrem-m'sec X 1 X J'CI p.Cl-yr m2 sec DR,=mrem The Dose Rate to organ T from nuclide (i)yf Page 115 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 2.(continued)

F.Repeat steps 2.3.2.C through 2.3.2.E for each nuclide (i)reported in the assay of the release source.G.The Dose Rate to the Infant's Whole Body from the Ground Plane Pathway Is: DRar pi=DR~+DR2++DRfor all nuclides.This dose rate shall be added to the other pathways as per 2.3.5.3.The Grass-Cow/Goat-Milk Dose Rate Method: NOTE H-3 dose is calculated as per 2.3.4.A.The controlling animal was established as a'ocated in the sector at miles.The (D/Q)for this location is 1/m'.This value is common to all nuclides.(See Table M-3 for sector, range and value.)B.Enter the anticipated release rate in ft'/min of the release source and convert to cc/sec.ft'2.8317 X 10'cc X mi=cc/s~min ft 60 sec.C.Solve for (Q DOT), for nuclide (i)by obtaining the pCi/cc assay value of the release source activity and multiplying it by the product of 2,3.3.B above.(Q ppg (nuclide[i]assay)p,Ci X (value 2.3.3.B)cc CC sec (Q DOT),=pCi/sec for nuclide (i)

Page 116 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 3.(continued)

D.Obtain the R.,value from Table G-6(7)(whichever is the controlling animal, cow/goat, for infant).If the limited analysis approach is being used, limit the calculation to the infant thyroid.E.Solve for DR,T~mrem-m'sec DR~=RT (D/Q)(Q DOT),-X X-pCi-yr m sec DR~=mrem the Dose Rate to organ T from nuclide (i)yr F.Repeat steps 2.3.3.C through 2.3.3.E for each nuclide (i)reported in the assay of the release source.Only the radioiodines need to be included if the limited analysis approach is being used.G.The Dose Rate to the Infant's organ T from Grass-pathway is:-Milk DRgrms-MilkT=DR,+DR2++DRfor aii nuolides.This dose rate shall be added to the~ot er pathways as per 2.3.5-Total Organ Dose.NOTE Steps 2.3.3.C through 2.3.3.G need to be completed for each organ of the Infant.Limit the calculation to the infant thyroid if the limited analysis approach is being used.

Page 117 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 4.The H-3 Dose Rate Method: A.The controlling locations and their (X/Q)0 values for each pathway are: Inhalation

-Infant at range in the sector.(X/Q)l,=sec/m'See Table M-2 for range, sector and value)Ground Plane-Does not apply to H-3 Grass-Cow/Goat-Milk-located in the miles with an Infant at the exclusion area in the drinking the milk.The (X/Q)c for the location is (X/Q)~=sec/m'.(From Table M-6 at the range and sector corresponding to the location of the Milk Animal above.)sector at sector B.Enter the anticipated release rate in ft'/min of the release source and convert it to cc/sec.a'X'1'"X min ft3 60 sec.cc/sec volume release rate C.Solve for (Q DOT)., for Tritium, by obtaining the pCi/cc assay value of the release source and multiplying it by the product of 2.3.4.B above.(Q ppq (H 3)p,CI'(2 3 4 B VBIU8)CC CC sec (Q DOT).,=pCi/sec activity release rate D.Obtain the Tritium dose factor (R,)for Infant organ T from: PATH Inhalation Grass-Cow/Goat-Milk TABLE¹G-5 G-6(7)

Page 118 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 4.(continued)

E.Solve for D., (Inhalation) using the (X/Q)~for inhalation from 2.3.4.A and R., (Inhalation) from 2.3.4.D.DRg g Rg g (X/Q)p (Q DOT)g 3 DR,=mrem/yr from H-3 Infant Inhalation for organ T F.Solve for D., (Grass--Milk)using the (X/Q)0 for Grass-.-Milk from 2.3.4.A and R., (Grass-from 2.3.4.D-Milk)DR~.>=R<>(XQ)p (Q DOT)/f 3 DR,=mrem/yr from H-3 Infant G.Repeat steps 2.3.4.D through 2.3.4.F for each Infant organ T of interest.H.The individual organ dose rates from H-3 shall be added to the other organ pathway dose rates as per 2.3.5.

Page 119 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.3 (continued) 5.Determinin the Total Or an Dose Rate from lodines 8D-Particulates.

and H-3 from Release Source s A.The following table describes all the pathways that must be summed to arrive at the total dose rate to an organ T: PATHWAY Inhalation (I&8DP)DOSE RATE STEP 0 REF.2.3.1.6 Gr-Milk (l&8DP)Inhalation (H-3)Ground Plane'I&8DP)(Whole Body only)2.3.2.G 2.3.3.G 2.3.4.E Gr--Milk (H-3)DR~(sum of above)2.3.4.F B.Repeat the above summation for each Infant organ T.C.The DR~above shall be added to all other release sources on the site that will be in progress at any instant.Refer to in-plant procedures and logs to determine the Total DR~to each organ.2.4 Determinin the Gamma Air Dose for Radioactive Noble Gas Release Source s Discussion

-Control 3.11.2.2 limits the air dose due to noble gases in gaseous effluents for gamma radiation to<5 mrads for the quarter and to<10 mrads in any calendar year.The following calculation method is provided for determining the noble gas gamma air dose and is based on section 5.3.1 of NUREG-0133, November 1978.The dose calculation is independent of'any age group.The equation may be used for Control dose calculation, the doseMalculation for the annual report or for projecting dose, provided that the appropriate value of (X/Q)is used as outlined in the detailed explanation that follows.The equation for gamma air dose is: n D-air=Z 3.17 X 10't (XIQ)Q~I Page 120 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.4 (continued)

Where: D-air gamma air dose in mrad from radioactive noble gases.Z A mathematical symbol to signify the operations to the right side of the symbol are to be performed for each nuclide (i)through (n)and summed to arrive at the total dose, from all nuclides reported during the interval.No units apply.3.17 X 10+=the inverse of the number of seconds per year with units of year/sec.M, (X/Q)J the gamma air dose factor for radioactive noble gas nuclide (i)in units of mrad-m'Ci-yr the long term atmospheric dispersion factor for ground level releases in units of sec/m', The value of (X/Q)is the same for all nuclides (i)in the dose calculation, but the value of (X/Q)does vary depending on the Limiting Sector the Control is based on, etc.Q, the number of micro-curies of nuclide (i)released (or projected) during the dose calculation exposure period.(e.g., month, quarter or year)

Page 121 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.4 (continued)

The following steps provide a detailed explanation of how the radionuclide specific dose is calculated.

1.To determine the applicable (X/Q)refer to Table M-1 to obtain the value for the type of dose calculation being performed.(i.e., Quarterly Control or Dose Projection for examples).

This value of (X/Q)applies to each nuclide (i).2.Determine (M,)the gamma air dose factor for nuclide (i)from Table G-2.3.Obtain the micro-Curies of nuclide (i)from the in-plant radioactive gaseous waste management logs for the sources under consideration during the time interval.4.Solve for D, as follows: 3.17 X 10-'r M, mrad-m'X/Q) sec X Q(PC'I sec pCi-yr m'D,.=mrad=the dose from nuclide (i)5.Perform steps 2.4,2 through 2.4.4 for each nuclide (i)reported during the time interval in the source.6.The total gamma air dose for the pathway is determined by summing the D, dose of each nuclide (i)to obtain D-air dose.D,=D,+D,++D=mrad 7.Refer to in-plant procedures for comparing the calculated dose to any applicable limits that might apply.

Wage 122 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.5 Determinin the Beta Air Dose for Radioactive Noble Gas Releases Discussion

-Control 3.11.2.2 limits the quarterly air dose due to beta radiation from noble gases in gaseous effluents to<10 mrads in any calendar quarter and<20 mrads in any calendar year.The following calculation method is provided for determining the beta air dose and is based on Section 5.3.1 of NUREG-0133, November 1978.The dose calculation is independent of any age group.The equation may be used for Control dose calculation, dose calculation for annual reports or for projecting dose, provided that the appropriate value of (X/Q)is used as outlined in the detailed explanation that follows.The equation for beta air dose is: n Ds-Z=317 X 10-8N]X/Q)

Q I Where: B-air beta air dose in mrad from radioactive noble gases.3.17 X 10 a mathematical symbol to signify the operations to the right side of the symbol are to be performed for each nuclide (i)through (n)and summed to arrive at the total dose, from all nuclides reported during the interval.No units apply.the inverse of the number of seconds per year with units of year/sec, the beta air dose factor for radioactive nobis gas nuclide (i)in units of mrad-m'.Ci-yr (X/Q)the long term atmospheric dispersion factor for ground level releases in units of sec/m'.The value of (X/Q)is the same for all nuclides (i)in the dose calculation, but the value of (X/Q)does vary depending on the Limiting Sector the Control is based on, etc.Q, the number of micro-Curies of nuclide (i)released (or projected) during the dose calculation exposure period Page 123 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.5 (continued)

The following steps provide a detailed explanation of how the dose is calculated.

To determine the applicable (X/Q)refer to Table M-1 to obtain the value for the type of dose calculation being performed{i.e., quarterly Control or Dose projection for examples).

This value of (X/Q)applies to each nuclide (i).2.Determine (N,)the beta air dose factor for nuclide (i)from Table G-2.3.Obtain the micro-curies of nuclide (i)from the in-plant radioactive gaseous.waste management logs for the source under consideration during the time interval.4.Solve for D, as follows: 3.17 X 10'r X N, mrad-m'X/Q) sec X Q, p.Ci DI sec Ij.Ci-yr M3 1 D,=mrad=the dose from nuclide (i)5.Perform steps 2.5,2 through 2.5.4 for each nuclide (i)reported during the time interval in the release source.6.The total beta air dose for the pathway is determined by summing the D, dose of each nuclide (i)to obtain D~., dose.Dg-air=D>+D2+D=mrad 7.Refer to in-plant procedures for comparing the calculatecLdese to any applicable limits that might apply.

Tage 124 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 Determinin the Radioiodine and Particulate Dose To An A e Grou's Or an From Cumulative Releases Discussion

-Control 3.11.2.3 limits the dose to the whole body or any organ resulting from the release of l-131, I-133, tritium and particulates with half-lives

>8 days to<7.5 mrem during any calendar quarter and<15 mrem during any calendar year.The following calculation method is provided for determining the critical organ dose due to releases of radioiodines and particulates and is based on Section 5.3.1 of NUREG-0133, November 1978.The equations can be used for any age group provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group.The Effluent Supervisor will track which age group is the controlling (most restrictive) age group (see control 3.11.2.6.c).

The (X/Q), symbol represents a DEPLETED-(X/Q) which is different from the Noble Gas (X/Q)in that (X/Q)~takes into account the loss of l&8DP and H-3 from the plume as the semi-infinite cloud travels over a given distance.The (D/Q)dispersion factor represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site.The l88DP and H-3 notations refer to l-131, I-133 Particulates having half-lives

>8 days and Tritium.For ease of calculations, dose from other Iodine nuclides may be included (see 2.1).Tritium calculations are always based on (X/Q)~, The first step is to calculate the l&8DP and H-3 dose for each pathway that applies to a given age group.The total dose to an organ can then be determined by summing the pathways that apply to the receptor in the sector.The infant age group does not apply to Grass-Cow-Meat or Vegetation pathway dose since they are assumed to eat only milk.The equations are: For Inhalation Pathway (excluding H-3): n DI&8DP Z 3 17 X 10 R((X/Q)pQ]For Ground Plane, Grass-Cow/Goat-Milk, Grass-Cow/Goat-Milk, or Vegetation n Dg80p Z 3 1 7 X 1 0 RJ (DIQ)Q(I For each pathway above (excluding Ground Plane)For Tritium: D-3 3.17 X 10-BR'/X/Q)oQ Tage 125 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued)

For Total Dose from Particulate Gaseous effluent to organ T of a specified age group: Z r Z~@BOY+Where: the organ of interest of a specified age group the applicable pathways for the age group of interest DI&BDP Dose in mrem to the organ T of a specified age group from radioiodines and SD Particulates DH-3 DT Dose in mrem to the organ T of a specified age group from Tritium Total Dose in mrem to the organ T of a specified age group from Gaseous particulate Effluents A mathematical symbol to signify the operations to the right of the symbol are to be performed for each nuclide (i)through (n)and the individual nuclide doses are summed to arrive at the total dose from the pathway of interest to organ T.Z 3.17 X 10 A mathematical symbol to indicate that the total dose D, to organ T is the sum of each of the pathway doses of I88DP and H-3 from gaseous particulate effluents.

The inverse of the number of seconds per year with units of year/sec.R, The dose factor for nuclide (i)(or H-3)for pathway Z to organ T of the specified age group.The units are either mrem-m'or pathways<R mrem-m'sec for pathways yr-Pci using (X/Q)yr-Nci using (DIQ)e Page 126 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued)(X/Q)0 The depleted-(X/Q) value for a specific location where the receptor is located (see discussion).

The units are sec/m'D/Q) the deposition value for a specific location where the receptor is located (see discussion).

The units are 1/m'here m=meters.Q, QH-3 The number of micro-Curies of nuclide (i)released (or projected) during the dose calculation exposure period.the number of micro-Curies of H-3 released (or projected) during the dose calculation exposure period.1.The Inhalation Dose Pathwa Method: NOTE The H-3 dose should be calculated as per 2.6.4.A.Determine the applicable (X/Q)0 from Table M-2 for the location where the receptor is located.This value is common to each nuclide (i)B.For the age group(s)of interest, determine the R, factor of nuclide (i)for the organ T and age group from the appropriate table number.Age Group Infant Child Teen Adult Inhalation Dose Factor Table Number G-5 G-S G-13 G-18 C.Obtain the micro-Curies (Q,)of nuclide (i)from the radioactive gas waste management logs for the release source(s)under consideration during the time interval.D.Solve for D, D,=3.17 X 10 Ri(X/Q)QQj D,=mrem from nuclide (i)

Page 127 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 1.(continued)

E.Perform steps 2.6.1.B through 2.6.1.D for each nuclide (i)reported during the time interval for each organ.F.The Inhalation dose to organ T of the specified age group is determined by summing the D, Dose of each nuclide (i)Dtnhatation

!mrem Refer to 2.6.5 to determine the total dose to organ T from radioiodines 8 8D Particulates 2.The Ground Plane Dose Pathwa Method: NOTE Tritium dose via the ground plane is zero.The Whole Body is the only organ considered for the Ground Plane pathway dose.A.Determine the applicable (D/Q)from Table M-2 for the location where the receptor is located.This (D/Q)value is common to each nuclide (i)B.Determine the Ri factor of nuclide (i)for the.whole body from Table G-4.The ground plane pathway dose is the same for all age groups.C.Obtain the micro-Curies (Q,)of nuclide (i)from the radioactive gas waste management logs for the source under consideratioFr.

D.Solve for D,.D(=3 17 X 10 8R, (D/Q)Q(D,=mrem for nuclide (i)

Page 128 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 2.(continued)

E.Perform steps 2.6.2.B through 2.6.2.D for each nuclide (i)reported during the time interval.F.The Ground Plane dose to the whole body is determined by summing the Di Dose of each nuclide (i)Gr.PI.-WBody 1+2++n mrem Refer to step 2.6.5 to calculate total dose to the Whole Body.3.The Grass-Cow/Goat-Milk Dose Pathwa Method: NOTE Tritium dose is calculated as per 2.6.4.A.A cow or a goat, will be the controlling animal;(i.e., dose will not be the sum of each animal), as the human receptor is assumed to drink milk from only the most restrictive animal~Refer to Table M-3 to determine which animal is controlling based on its (D/Q).B.For the age group(s)of interest, determine the dose factor R, for nuclide (i), for organ T, from the appropriate table number for the applicable milk animal.Age Group Infant Child Teen Adult Cow Milk Dose Factor Table Number G-6 G-9 G-14 G-19 Goat Milk Dose Factor Table Number G-7 G-10 G-15 G-20If the limited analysis approach is being used, limit the calculation to the infant thyroid.

Page 129 of 225 ST.LUCIE PLANT=CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 3.(continued)

C.Obtain the micro-Curies (Q,)of nuclide (i)from the radioactive gas waste management logs for the release source under consideration during the time interval.D.Solve for D, D;=3.17 X 10 RI(D/Q)Q, D,=mrem from nuclide (i)E.Perform steps 2.6.3.B through 2.6.3.D for each nuclide (i)reported during the time interval.Only the radioiodines need to be included if the limited analysis approach is used.F, The Grass-Cow-Milk (or Grass-Goat-Milk) pathway dose to organ T is determined by summing the Di dose of each nuclide(i).

Do~(or Doo~)=D,+D,++o=mrem The dose to each organ should be calculated in the same manner with steps 2.6.3.B through 2.6.3.F.Refer to step 2.6.5 to determine the total dose to organ T from radioiodines 88D Particulates.

If the limited analysis approach is being used the infant thyroid dose via the grass-cow(goat)-milk pathway is the only dose that needs to be determined.

Section 2.6.5 can be omitted.4.The Grass-Cow/Goat-Meat Dose Pathway method: NOTE Tritium dose is calculated as per 2.6.6.A.Determine the controlling herd location by: For dose calculations (other than the annual report)the historical herd was determined to be located in Sector at miles.This herd shall be used for all ODCM Control required dose calculations.

Page 130 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM.METHODOLOGY SECTION 2.6 (continued) 4.(continued)

A.(continued) 2.For annual report dose calculations the herd from the Land Use Census having the highest (D/Q)at its location will be the reporting herd.The Land Use Census for 1978 (for example)shall apply to the calendar year 1979 (for example)and will locate the nearest herd in each sector over land.The real (D/Q)will be determined from actual met data that occurred during the reporting period.B.Determine the applicable (D/Q)from Table M-3 for the location(s) of the herd as determined in 2.6.4.A above.C.Determine the dose factor Ri for nuclide (i)for organ tau from the Table specified below: Age Infant Child Teen Adult Meat Dose Factor Table No.N/A*G-11 G-16 G-21*The infant does not eat meat and therefore dose does not apply to this pathway.D.Obtain the micro-Curies (Qi)of nuclide (i)from the radioactive gas waste management logs (for projected doses-the micro-GurIes of nuclide (i)to be projected) for the release source(s)under consideration during the time interval.The dose can be calculated from a single release source, but the total dose for ODCM Control Limits or annual reports shall be from all gaseous release sources.

Page 131 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 4.(continued)

E.Solve for Di Di=3.17 X 10 Ri (D/Q)Qi Di=mrem from nuclide (i)F.Perform Steps 2i6.4.C through 2.8.4.E for each nuclide (i)reported during the time interval.G.The Grass-Cow-Meat pathway dose to organ tau is determined by summing the Di dose of each nuclide (i).Dose=D1+D2+D3+......+Dn=mrem Grass-Cow-Meat Excluding Tritium (Child, Teen, or Adult)5.The Vegetation (Garden)Dose Pathway method: A.Determine the controlling garden location by: 1.For dose calculations (other than annual reports)the historical garden was determined to be located in Sector't miles.This garden shall be used for all ODCM Control dose calculations.

2.For annual report dose calculations the Land Casus Garden having the highest real (D/Q)at its location will be the reporting garden.The Land Use Census for 1978 (for example)shall apply to the calendar year 1979 (for example)and will locate the nearest garden in each sector.The real (D/Q)will be determined from actual met data that occurred during the reporting period.B.Determine the applicable (D/Q)from Table M-3 for the location(s) of the garden(s)as determined above.

Page 132 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 5.(continued)

C.Determine the dose factor Ri for nuclide (i)for organ tau from the Table specified below: Age Infant Child Teen Adult Vegetation Dose Factor Table No.N/A G-12 G-17 G-22*denotes the infant does not eat vegetation and therefore does not apply to this pathway.D.Obtain the micro-Curies (Qi)of nuclide (i)from the radioactive gas waste management logs (for projected doses-the micro-Curies of nuclide (i)to be projected) for the release source(s)under consideration during the time interval.The dose can be calculated from a single release source, but the total dose for ODCM Control Limits or annual reports shall be from all gaseous release sources.E.Solve for Di Di=3.17 X 10 Ri (D/Q)Qi Di=mrem from nuclide (i)F.Perform Steps 2.6.5.C through 2.6.5.E for each nuclkf6 (i)reported during the time interval~G.The Vegetation pathway dose to organ tau is determined by summing the Di dose of each nuclide (i).Dose=D1+D2+D3+......+Dn=mrem Vegetation (Excluding Tritium)(Child, Teen, or Adult)

Page 133 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 6.The Gaseous Tritium Dose Each Pathwa Method: A.The controlling locations for the pathway(s) has already been determined by: Inhalation

-as per 2.6.1.A Ground Plane-not applicable for H-3 Grass-Cow/Goat-Milk

-as per 2.6.3.A Grass-Cow/Goat-Milk

-as per 2,6,4.A Vegetation (Garden)-as per 2.6.5.A B.Tritium dose calculations use the depleted (X/Q)0 instead of (D/Q).Table-M-2 describes where the (X/Q)~value should be obtained from.C.For the age group(s)of interest, determine the Pathway Tritium dose factor (R.g for the organ T of interest from the Table specified below: AGE Infant Child Teen Adult INHALATION G-5 G-8 , G-13 G-18 COW G-6 G-9 G-14 G-1 9 MILK GOAT G-7 G-10 G-15 G-20 D.Obtain the micro-Curies (Q)of Tritium from the radioactive gas waste management logs (for projected doses-the roicro-Curies of nuclide (i)to be projected) for the release source(s)under consideration during the time interval.The dose can be calculated from a single release source, but the total dose for Control limits or quarterly reports shall be from all gaseous release sources.E.Solve for D<<D~=3.17 X 10 R~(X/Q)~Q D~=mrem from Tritium in the specified pathway for organ T of the specified age group 0

Page 134 of 225 ST;LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued) 7.Determinin the Total Or an Dose From lodines SD-Particulates and H-3 From Cumulative Gaseous Releases NOTE Control dose limits for 188DP shall consider dose from all release sources from the reactor unit of interest.A.The following pathways shall be summed to arrive at the total dose to organ T from a release source or if applicable to Control, from all release sources: Age Group: INFANT CHILD TEEN ADULT Organ: BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODYPATHWAY Grass--Meat (Tritium)Vegetable Garden (l&8DP)Vegetable Garden (Tritium)Dose,=Inhalation (l&8DP)Inhalation (Tritium)Ground Plane (!&8DP)Grass--Milk (l&8DP)Grass--Milk (Tritium)Grass--Meat (l&8DP)DOSE (sum of above)Reference to STEP No.2.6.1.F 2.6.6.E 2.6.2.F 2.6.3.F 2.6.6.E 2.6.4.G 2.6,6.E 2.6.5.G 2.6.6.E Remark N/A for INFANT N/A for INFANT N/A for INFANT N/A for INFANT B.The dose to each of the applicable age group's ORGANS shall be calculated:

BONE, LIVER, THYROID, KIDNEY, LUNG, WHOLE BODY,&Gl-LLI The age group organ receiving the highest exposure relative to its Control Limit is the most critical organ for that age group resulting from the radioiodine

&SD Particulates gaseous effluents.

Page 135 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.7 Pro'ectin Dose for Radioactive Gaseous Effluents Discussion

-Control 3.11.2.4 requires that the waste gas holdup system be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY{see TS Figure 5-1-1)would exceed 0.2 mrad for gamma radiation.and 0.4 mrad for beta radiation.

The following calculation method is provided for determining the projected doses.This method is based on using the results of the calculations performed in Sections 2.4 and 2.5.1.Obtain the latest results of the monthly calculations of the gamma air dose{Section 2.4)and the beta air dose if performed{Section 2.5).These doses can be obtained from the in-plant records.2.Divide these doses by the number of days the plant was operational during the month.3.Multiply the quotient by the number of days the plant is projected to be operational during the next month.The product is the projected dose for the next month.The value should be adjusted as needed to account for any changes in failed-fuel or other identifiable operating conditions that could significantly alter the actual releases.4.If the projected doses are>0.2 mrads gamma air dose or>0.4 mrads beta air dose, the appropriate subsystems of the waste gas holdup system shall be used.

Page 136 of 225*ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 3.0 40 CFR 190 Dose Evaluation Discussion

-Dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to<25 mrem to the whole body or any organ (except thyroid, which is limited to<75 mrem)over a period of 12 consecutive months.The following approach should be used to demonstrate compliance with these dose limits.This approach is based on NUREG-0133, Section 3.8.3.1 Evaluation Bases Dose evaluations to demonstrate compliance with the above dose limits need only be performed if the quarterly doses calculated in Sections 1.4, 2.4 and 2.6 exceed twice the dose limits of Controls 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2a, 3.1.2.2b, 3.11.2.3a and 3.11.2.3b respectively; i.e., quarterly doses exceeding 3 mrem to the whole body (liquid releases), 10 mrem to any organ (liquid releases), 10 mrads gamma air dose, 20 mrads,beta air dose or 15 mrem to the thyroid or any organ from radioiodines and particulates (atmospheric releases).

Otherwise, no evaluations are required and the remainder of this section can be omitted.3.2 Doses From Li uid Releases For the evaluation of doses to real individuals from liquid releases, the same calculation method as employed in Section 1.4 will be used.However, more realistic assumptions will be made concerning the dilution and ingestion of fish and shellfish by individuals who live and fish in the area.Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic dose to these real people by providing data on actual measured levels of plant related radionuclides in the environment.

3.3 Doses

From Atmos heric Releases For the evaluation of doses to real individuals from the atmospheric releases, the same calculation methods as employed in Section 2.4 and 2.6 will be used.In Section 2.4, the total body dose factor (K,)should be substituted for the gamma air dose factor (M,)to determine the total body dose.Otherwise the same calculation sequence applies.However, more realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions and the consumption of food (e.g., milk).Data obtained from the latest land use census (Control 3.12.2)should be used to determine locations for evaluating doses.Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic doses to these real people by providing data on actual measured levels of radioactivity and radiation at locations of interest.

Page 137 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 Annual Radioactive Effluent Re ort Discussion

-The information contained in a annual report shall not apply to any Control.The reported values are based on actual release conditions instead of historical conditions that the Control dose calculations are based on.The Control dose limits are therefore included in item 1 of the report, for information only.The ECLs in item 2 of the report shall be those listed in Tables L-1 and G-1 of this manual.The average energy in item 3 of the report is not applicable to the St.Lucie Plant.The format, order of nuclides and any values shown as an example in Tables 3.3 through 3.8 are samples only.Other formats are acceptable if they contain equivalent information.

A table of contents should also accompany the report.The following format should be used: RADIOACTIVE EFFLUENTS-SUPPLEMENTAL INFORMATION 1.Regulatory Limits: 1.1 For Radioactive liquid waste effluents:

a, The concentration of radioactive material released from the site (see TS Figure 5.1-1)shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, 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 2 X 10 p,CI/ml total activity.b.The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each reactor unit to unrestricted areas (See TS Fig.5.1-1)shall be limited during any calendar quarter to<1.5 mrem to the whole body and to<5 mrem to any organ and<3 mrem to the whole body and~mrem to any organ during any calendar year.1.2 For Radioactive Gaseous Waste Effluents:

a.The dose rate resulting from radioactive materials released in gaseous effluents to areas at or beyond the SITE BOUNDARY (See TS Figure 5.1-1)shall be limited to the following values:The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin and Page 138 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 1~(continued) 1.2 (continued) a.(continued)

The dose rate limit from l-131, l-133, Tritium and particulates with half-lives

>8 days shall be<1500 mrem/yr to any organ.I b.The air dose (see TS Figure 5.1-1)due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation and during any calendar year to<10 mrad for gamma radiation and<20 mrad for beta radiation c.The dose to a MEMBER OF THE PUBLIC from l-131, l-133, Tritium and all radionuclide in particulate form, with half-lives

>8 days in gaseous effluents released from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1 in the TS-A)shall be limited to the following:

During any calendar quarter to<7.5 mrem to any organ and during any calendar year to<15 mrem to any organ.2.Effluent Limiting Concentrations:

Air-as per attached Table 6-1 Water-as per attached Table L-1 3.Average energy of fission and activation gases in gaseous effluents is not applicable to the St.Lucie Plant.

Page 139 of 225ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 4.Measurements and Approximations of Total Radioactivity:

A summary of liquid effluent accounting methods is described in Table 3.1.A summary of gaseous effluent accounting methods is described in Table 3.2.Estimate of Errors:;Error Topic Release Point Mixing Sampling Sample Preparation Sample Analysis Release Volume LIQUID GASEOUS Avg.%Max.%Avg,%Max.%2 5 NA NA 5 2 5 1 5 1 5 3 10 3 10 2 5 4 15 Total%9 30 10 35 (above values are examples only)The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.

Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.

Page 140 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 4.(continued)

TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS LIQUID SOURCE MONITOR TANK RELEASES STEAM GENERATOR B LOWDOWN RELEASES SAMPLING FREQUENCY EACH BATCH MONTHLY COMPOSITE QUARTERLY COMPOSITE FOUR PER MONTH MONTHLY COMPOSITE QUARTERLY COMPOSITE TYPE OF ANALYSIS PRINCIPAL GAMMA EMITTERS TRITIUM'GROSS ALPHA Sr-89, Sr-90, Fe-55 PRINCIPAL GAMMA EMITTERS AND DISSOLVED GASES TRITIUM GROSS ALPHA Sr-89, Sr-90, Fe-55 METHOD OF ANALYSIS p.h.a.L.S.G.F.P.C.S.p.h.a.L.S.G.F.P.C.S.TABLE NOTATION: p.h.a.L.S.C.S.G.F.P.gamma spectrum pulse height analysis using Lithium Germanium detectors.

All peaks are identified and quantified.

Liquid Scintillation counting Chemical Separation Gas Flow Proportional Counting Page 141 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 4.(continued)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SOURCE Waste Gas Decay Tank Releases Containment Purge Releases Plant Vent SAMPLING FREQUENCY Each Tank Each Purge Four per Month Monthly Composite (Particulates)

Quarterly Composite (Particulates)

TYPE OF ANALYSIS Principal Gamma Emitters Principal Gamma Emitters H-3 Principal Gamma Emitters H-3 Gross Alpha Sr-90 Sr-89 METHOD OF ANALYSIS G, p.h.a.G, p.h.a.L.S.(G, C, P)-p.h.a.L.S.P-G.F.P.C.S.L.S.C.S.Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample Liquid Scintillation Counting Chemical Separation p.h.a.G.F.P.Gamma spectrum pulse height analysis using Lithium Germanium detectors.

All peaks are identified and quantified.

Gas Flow Proportional Counting Page 142 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 5.Batch Releases A.Liquid 1.Number of batch releases: 2.Total time period of batch releases: 3.Maximum time period for a batch release: 4.Average time period for a batch release: 5.Minimum time period for a batch release: minutes minutes minute's minutes 6.Average dilution stream flow during the period (see Note 1 on Table 3.3): GPM All liquid releases are summarized in tables B.Gaseous 1.Number of batch releases: 2.Total time period for batch releases: 3.Maximum time period for a batch releas'e: 4.Average time period for batch releases: 5.Minimum time period for a batch release: minutes minutes minutes minutes All gaseous waste releases are summarized in tables Page 143 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 (continued) 6.Unplanned Releases A.Liquid Number of releases: 2.Total activity releases: Curies B.Gaseous 1.Number of releases: 2.Total activity released: Curies C.See attachments (if applicable) for;A description of the event and equipment involved.2.Cause(s)for the unplanned release.3.Actions taken to prevent a recurrence 4.Consequences of the unplanned release 7.Description of dose assessment of radiation dose jrom radioactive effluents to the general public due to their activities inside the site are reported on the January annual report.8.Offsite dose calculation manual revisions initiated durinpChis reporting period.See Control 3.11.2.6 for required attachments to the Annual Report.9.Solid waste and irradiated fuel shipments as per requirements of Control 3.11.2.6.10.Process Control Program (PCP)revisions as per requirements of TS 6.13.11.Major changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems as per requirements of Control 3.11.2.5.

Page 144 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8.LIGHT COMPANY ST.LUCIE UNIT¹ANNUAL REPORT-~~THROUGH~~TABLE 3 3'IQUID EFFLUENTS-SUMMATION OF ALL RELEASES A.Fission and Activation Products 1.Total Release-(Not including Tritium, Gases, Alpha)2.Average Diluted Concentration During Period B.Tritium UNIT QUARTER¹QUARTER¹Ci p,CI/ml Total Release 2.Average Diluted Concentration During Period C.Dissolved and Entrained Gases 1.Total Release 2.Average Diluted Concentration During Period D.Gross Alpha Radioactivity 1.Total Release Ci p.CI/ml Ci p,CI/ml Ci E E Page 145 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION TABLE 3.3: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES (continued)

E.Volume of Waste Released (Prior to Dilution)UNIT QUARTER¹QUARTER¹LITERS F.Volume of Dilution Water Used During Period'ITERS E 1-The volume reported should be for the entire interval of the reporting period, not just during release intervals.

This volume should also be used to calculate average dilution stream flow during the period.

Page 146 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8.LIGHT COMPANY ST.LUC(E UNIT¹ANNUAL REPORT-~~THROUGH~~TABLE 3.4: LIQUID EFFLUENTS (EXAMPLE FORMAT)CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED'-131 I-133 I-135 NA-24 CR-51 MN-54 CO-57 CO-58 FE-59 CO-60 ZN-65 Nl-65 AG-110 SN-1 13 SB-122 UNIT QUARTER¹QUARTER¹CI.'I CI CI CI CI CI CI CI CI CI CI CI CI CI QUARTER¹QUARTER¹SB-124 W-1 87 NP-239 ZR-95 MO-99 RU-103 CS-134 CS-136 CS-137 BA-140 CE-141 BR-82 ZR-97 SB-125 CI CI CI CI CI CI CI CI CI CI CI CI CI CI E E*All nuclides that were detected should be added to the partial list of the example format..

Page 147 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION TABLE 3.4: LIQUID EFFLUENTS (EXAMPLE FORMAT)(continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED CE-144 SR-89 SR-90 UNIDENTIFIED UNIT CI CI CI CI QUARTER¹QUARTER¹QUARTER¹QUARTER¹TOTAL FOR PERIOD (ABOVE)CI AR<1 KR-85 XE-131M XE-133 XE-133M XE-135 CI CI CI CI CI CI Page 148 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER K LIGHT COMPANY ST.LUCIE UNIT II TABLE 3.5 LIQUID EFFLUENTS-DOSE SUMMATION Age Group: Exposure Interval: From Location: Through Fish 8 Shellfish Pathway to Organ BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY CALENDAR YEAR DOSE-'(mrem)

Page 149 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8c LIGHT COMPANY ST.LUCIE UNIT¹ANNUAL REPORT-~~THROUGH~~TABLE 3.6: GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES A.Fission and Activation Gases 1.Total Release UNIT QUARTER¹QUARTER¹Ci 2.Average Release Rate For Period pCi/SEC B.Iodines Total Iodine-1 31 Ci 2.Average Release Rate for Period pCI/SEC C.Particulates 1.Particulates T-1/2>8 Days Ci 2.Average Release Rate for Period pCI/SEC 3.Gross Alpha Radioactivity D: Tritium 1.Total Release Ci Ci 2.Average Release Rate for Period pCi/SEC

Page 150 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8c LIGHT COMPANY ST.LUCIE UNIT II ANNUAL REPORT-/~THROUGH~~TABLE 3.7 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES (EXAMPLE FORMAT)CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER¹QUARTER¹QUARTER¹QUARTER¹1.Fission Gases AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-138 UNIDENTIFIED CI CI CI CI CI Cl CI CI CI CI CI CI TOTAL FOR PERIOD (ABOVE)CI 2.Iodines I-131 I-133 I-135 TOTAL FOR PERIOD (ABOVE)3.Particulates CO-58 SR-89 SR-90 CI CI CI CI CI CI CI*All nuclides that were detected should be added to the partial list of the example format.

ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER L LIGHT COMPANY ST.LUCIE UNIT¹TABLE 3.8 GASEOUS EFFLUENTS-DOSE SUMMATION-CALENDAR YEAR AGE GROUP: INFANT EXPOSURE INTERVAL: FROM THROUGH Page 151 of 225 PATHWAY Ground Plane (A)Grass--Milk(B)Inhalation (A)TOTAL BONE (mrem)LIVER (mrem)THYROID (mrem)KIDNEY (mrem)LUNG (mrem Gl-LLI (mrem)WHOLE BODY (mrem)(A)SECTOR: RANGE: miles (B)COW/GOAT SECTOR: RANGE: miles Sector: NOBLE GASES Gamma Air Dose Beta Air Dose CALENDAR YEAR (mrad)Range: 0.97 miles NOTE The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg.Guide 1.111, March 1976.

Page 152 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX A ECL, DOSE FACTOR AND HISTORICAL METEOROLOGICAL TABLES Page 153 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE L-1 EFFLUENT CONCENTRATION LIMITS IN WATER IN UNRESTRICTED AREAS NOTE If a nuclide is not listed below, refer to t0 CPR Part 20, Appendix B, Table 2 Effluent Concentrations Column 2 and use the most conservative ECL listed for the nuclide.Nuclide H-3 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-65 Cu-64 Zn-65 Zn-69 Br-82 Br-83 Br-84 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 ECL (pCi/ml)1 E-3 5 E-5 9 E-6 5 E-4 3 E-5 7 E-5 1 E-4 1 E-5 6 E-5 2 E-5 3 E-6 1 E-4 2 EA 5 E-6 8 E-4 4 E-5 9 E-4 4 E-4 7 E-6 4 E-4 9 E-4 8 E-6 5 E-7 2 E-5 4 E-5 Nuclide Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110 Sn-113 In-113m Sb-122 SI3-124 Sb-125 Te-125m Te-127m Te-127 Te-129m ECL (p,Ci/ml)7 E-6 2 E-3 8 E-6 4 E-5 2 E-5 2 E-5 9 E-6 3 E-5 3 E-4 2 E-5 1 E-3 2 E-3 3 E-5 7 E-5 3 E-6 6 E-6 3 E-5 7 E-4 1 E-5 7 E-6 3 E-5 2 E-5 9 E-6 1 E-4 7 E-6 Nuclide Te-129 Te-131m Te-131 Te-132 I-130 l-131 l-132 I-133 I-134 l-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 L~O La-142 Ce-141 Ce-143 Ce-144 Pr-144 W-187 Np-239 ECL (pCi/ml)4 E-4 8 E-6 8 E-5 9 E-6 2 E-5 1 E-6 1 E-4 7 E-6 4 E-4 3 E-5 9 E-7 6 E-6 1 E-6 4 E-4 2 E-4 8 E-6 7 EA 9 E-6 3 E-5 2 E-5 3 E-6 6 E-4 3 E-5 2 E-5 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 154 of 225 TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)NUCLIDE H-3 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 NI-65 CU-84 ZN-65 ZN-69 0.BONE 6.08E-01 1.67E+07 0.0.0.1.15E+05 8.08E+04 0.0.0.2.02E+02 0.1.62E+05 3.43E+02 LIVER 3.60E-01 6.08E-01 1.05E+06 0.7.07E+03 1.78E+02 5.19E+05 1.92E+05 1.42E+02 6.05E+02 1.74E+03 2.63E+01 2.15+02 5.13E+05 6.60E+02 THYROID 3.60E-01 6.08E-01 0.3.34E+00 0.0.0.0.0.0.0.0.0.0.KIDNEY 3.60E-01 6.08E-01 0.1.23E+00 2.10E+03 2.26E+02 0.0.0.0.0.5.41E+02 3.43E+05 4.27E+02 LUNG 3.60E-01 6.08E-01 0.7A2E+00 0.0.6.01E+05 5.32E+04 0.0.0.0.0.0.GI-LLI 3.60E-01 6.08E-01 1.88E+06 1.41E+03 2.17E+04 5.68E+03 2.03E+05 6.33E+05 3.60E+03 1.22E+04 3.26E+04 6.65E+02 1.83E+04 3.23E+05 9.87E+01 WHOLE BODY 3.60E-01 6.08E-01 6.47E+05 5.59E+00 1.35E+03 3.17E+01 1.36E+05 7.29E+04 2.36E+02 1.35E+03 3.83E+03 1.20E+01 1.01E+02 2.32E+05 4.57E+01 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 155 of 225 TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE BR-82 BR-83 BR-84 BR-85 0.0.BONE 0.0.0.0.LIVER 0.0.0.THYROID 0.0.0.0.KIDNEY 0.0.0.LUNG GI-LLI 4.68E+00 1.05E-01 7.38E-07 0.WHOLE BODY 4.08E+00 7.26E-02 9A2E-02 3.86E-03 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-95M Y-91 Y-92 0.0.0.5.01E+03 1.23E+05 9.43E+01 3.50E+01 6.07E+00 5.74E-02 8.89E+01 5.34E-01 6.25E+02 1.79E+00 1.19E+00 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.23E+02 0.0.8.01E+02 1.65E+03 4.75E+02 6.91E+02 6.43E+04 1.68E-01 4.89E+04 9.33E+03 2.91E+02 9.50E-01 8.38E-01 1.44E+02 3.02E+04 4.15E+00 1.51E+00 1.63E-01 2.23E-03 2.38E+00 1.56E-02 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 156 of 225 TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)NUCLIDE Y-93 BONE 1.69E+00 0.LIVER THYROID 0.0.KIDNEY 0.LUNG Gl-LLI 5.36E+04 WHOLE BODY 4.67E-02 ZR-95 ZR-97 NB-95 NB-97 MO-99 TC-99M TC-101 RU-103 RU-105 RU-106 AG-110 SB-124 SB-125 1.60E+01 8.82E-01 4.48E+02 3.76E+00 0.1.30E-02 1.33E-02 1.07E+02 8.90E+00 1.59E+03 1.57E+03 2.78E+02 2.20E+02 5.13E+00 1.78E-01 2.49E+02 9.50E-01 1.28E+02 3.67E-02 1.93E-02 0.0.0.'I.45E+03 5.23+00 2.37 00 0.0.0.0.0.0.0.0.0.0.0.6.71E-01 1.96E-01 8.09E+00 2.69E-01 2.47E+02 1.11E+00 2.90E+02 5.57E-01 3.47E-01 4.09E+02 1.15E+02 3.08E+03 2.85E+03 0.0.0.0.1.80E-02 9.82E-03 0.0.0.0.2.15E+02 2.30E+04 1.59E+04 5.51E+04 1.51E+06 3.51E+03 2.97E+02 2.17E+01 0.1.25E+04 5A4E+03 1.03E+05 5.92E+05 7.85E+03 1.95E+03 3.47E+00 8.19E-02 9.79E+01 3.47E-01 2.43E+01 4.67E-01 1.89E-01 4.61E+01 3.51E+00 2.01E+02 8.62E+02 1.10E+02 4.42E+01 TE-125M 2.17E+02 7.89E+01 6.54E+01 8.83E+02 0.8.67E+02 2.91E+01 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST, LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 157 of 225 TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES

.PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE TE-127M TE-127 TE-129M TE-129 TE-131M TE-131 TE-132 I-130 1-131 l-132 I-133 BONE 5.50E+02 8.92E+00 9.32E+02 2.55E+00 1.41E+02 1.60E+00 2.05E+03 3.98E+01 2.18E+02 1.07E+01 7.51E+01 LIVER 1.92E+02 3.20E+00 3.49E+02 9.65E-01 6.87E+01 6.68E-01 1.33E+02 1.18E+02 3.13E+02 2.85E+01 1.30E+Og THYROID 1.40E+02 6.61E+00 3.20E+02 1.95E+00 1.09E+02 1.31E+00 1.46E+02 1.50E+04 1.02E+05 3.76E+03)2.51E+04 KIDNEY 2.23E+03 3.63E+01 3.89E+03 1.07E+01 6.95E+02 7.00E+00 1.28E+03 1.83E+02 5.36E+02 4.55E+01 2.27E+02 0.0.0.0.0.0.0.0.LUNG GI-LLI 1.84E+03 7.04E+02 4.69E+03 1.92E+00 6.81E+03 2.39E-01 6.25E+03 1.01E+02 8.24E+01 5.36E+00 1.15E+02 WHOLE BODY 6.70E+01 1.93E+00 1.48E+02 6.21E-01 5.72E+01 5.04E-01 1.24E+02 4.63E+01 1.79E+02 1.01E+01 3.98E+01 I-134 I-135 CS-134 CS-136 5.57E+00 2.33E+01 6.85E+03 7.17E+02 1.51E+01 6.14+01 1.63 04 2.83E+03 1.96E+03 8.03E+03 0.0.2.41E+01 9.77E+01 5.29E+03 1.58E+03 0.0.1.75E+03 2.16E+02 1.32E-02 6.88E+01 2.85E+02 3.22E+02 5.41E+00 2.25E+01 1.33E+04 2.04E+03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 158 of 225 TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 W-187 NP-239 BONE 8.79E+03 6.08E+00 7.87E+00 1.65E+03 0.1.73E+00 1.58E+00 8.07E-02 3.43E+00 6.05E-01 1.79E+02 1.91E-02 9.17E+00 3.56E-02 LIVER 1.20E+04 1.20E+01 5.61E-03 2.07E+00 2.89E-03 1.78E-03 7.95E-01 3.67E-02 2.32E+00 4.47E+02 7.48E+01 7.88E-03 7.68+00 3.50-03 THYROID 0.0.0.0.0.0.0.0.0.0.0.0.KIDNEY 4.09E+03 8.84E+00 5.24E-03 7.04E-01 2.68E-03 1.50E-03 0.1.08E+00 1.97E-01 4.43E+01 4.45E-03 0.1.08E-02 LUNG 1.36E+03 8.73E-01 3.18E-03 1.18E+00 1.64E-03 1.01E-03 0.0.0.0.0.0.0.0.GI-LLI 2.31E+02 5.12E-05 1.39E+01 3.39E+03 1.80E-09 0.5.83E+04 2.68E+02 8.87E+03 1.67E+04 6.05E+04 2.73E-09 2.51E+03 7.12E+02 WHOLE BODY 7.88E+03 5.96E+00 2.30E-01 1.09E+02 1.29E-01 1.09E-01 2.11E-01 9.15E-03 2.63E-01 4.95E-02 9.60E+00 9.65E-04 2.69E+00 1.92E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 159 of 225 TABLE L-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE H--3 NA-24 P--32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 NI-65 CU-64 ZN-65 ZN-69 BR-82 BR-83 BR-84 BR-85 0.BONE 0.4.63E-01 1.27E+07 0.0.0.8.78E+04 6.14E+04 0.0.0.1.54E+02 0.1.23E+05 2.61E+02 0.0.LIVER 2.17E-01 4.63E-01 7.98E+05 0.5.38E+03 1.36E+02 3.95E+05 1.46E+05 1.08E+02 6.12E+02 1.70E+03 2.00E+01 1.64+02 3.90 05 5.02E+02 0.0.THYROID 2.17E-01 4.63E-01 0.2.54E+00 0.0.0.0.0.0.0.0.0.0.0.KIDNEY 2.74E-01 4.63E-01 0.9.38E-01 1.60E+03 1.72E+02 0.0.0.0.0.0.4.12E+02 2.61E+05 3.24E+02 0.0.0.0.LUNG 2.17E-01 4.63E-01 0.5.64E+00 0.0.4.57E+05 4.05E+04 0.0.0.0.0.0.0.0.0.0.GI-LLI 2.17E-01 4.63E-01 1.43E+06 1.07E+03 1.65E+04 4.32E+03 1.54E+05 4.81E+05 2.74E+03 8.26E+03 2.04E+04 5.07E+02 1.39E+04 2.46E+05 7.50E+01 3.55E+00 7.95E-02 5.61E-07 0.WHOLE BODY 2.17E-01 4.63E-01 4.93E+05 4.25E+00 1.03E+03 2.42E+01 1.04E+05 5.55E+04 1.79E+02 1.39E+03 3.88E+03 9.11E+00 7.69E+01 1.77E+05 3.47E+01 3.10E+00 5.52E-02 7.16E-02 2.94E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 160 of 225 TABLE L-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE RB-86 RB-88 0.0.BONE LIVER 4.76E+02 1.37E+00 THYROID 0.0.0.KIDNEY 0.LUNG GI-LLI 9.37E+01 WHOLE BODY 2.22E+02 7.23E-01 RB-89 SR-89 SR-90 SR-91 SR-92 Y--90 Y-91M Y--91 Y--92 Y--93 ZR-95 ZR-97 NB-95 NB-97 MO-99 TC-99M TC-101 0.5.67E+03 1,28E+05 7.18E+01 2.66E+01 1.58E+01 4.36E-02 9.40E+01 4.06E-01 1.29E+00 1.49E+01 6.72E-01 3.97E+02 2.87E+00 0.9.87E-03 1.02E-02 9.04E-01 0.0.0.0.0.0.0.0.p 4.96+00 1.36 01 2.39E+02 7.24E-01 9.74E+01 2.79E-02 1.47E-02 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.6.16E+00 2.05E-01 1.88E+02 8.45E-01 2.21E+02 4.24E-01 2.64E-01 0.0.0.0.1.80E+04 0.0.0.0.0.0.0.0.1.37E-02 7.47E-03 0.6.15E+02 2.71E+03 3.61E+02 5.25E+02 5.23E+04 1.28E-01 3.61E+04 7.10E+03 4.08E+04 1.07E+04 4.20E+04 9.76E+05 2.67E+03 2.26E+02 1.65E+01 0.6.38E-01 1.63E+02 3.17E+04 3.16E+00 1.15E+00 4.25E-01 1.69E-03 2.51E+00 1.18E-02 3.55E-02 3.46E+00 6.24E-02 1.35E+02 2.64E-01 1.85+01 3.56E-01 1.44E-01 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 161 of 225 TABLE L-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE RU-103 RU-105 BONE 1.04E+02 6.77E+00 0.0.LIVER 0.THYROID KIDNEY 3.11E+02 8.74E+O'I 0.0.LUNG GI-LLI 8.13E+03 4.14E+03 WHOLE BODY 4.66E+01 2.67E+00 RU-106 AG110 SB-124 1.76E+03 1.19E+03 2.11E+02 0.1.10E+03 3.99E+00 0.0.5.11E-01 2.34E+03 2.17E+03 0.0.0.1.64E+02 7.95E+04 4.51E+05 5.98E+03 2.21E+02 6.56E+02 8.35E+01 SB-125 1.68E+02 TE 125M 2.36E+02 TE 127M 4.18E+02 1.81E+00 8A5E+O'I 1.46E+02 1.49E-01 6.66E+01 1.07E+02 0.6.72E+02 1.70E+03 1.75E+04 0.1.48E+03 6.60E+02 1.40E+03 3.37E+01 3.13E+01 5.09E+01 TE-.127 9.31E+00 3.28E+00 6.35E+00 2.76E+01 0.7.52E+02 1.99E+00 TE 129M 1.02E+03 1.94E+00 TE-129 TE 131M 1.07E+02 3.79E+02 7.34E-01 5.22E+01 3.27E+02 1A9E+00 8.26E+01 2.96E+03 8.14E+00 5.29E+02 0.0.0.3.58E+03 1.46E+00 5.18E+03 1.61E+02 4.72E-01 4.35E+01 TE-131 TE-132 I-130 I-131 I-132 I-133 1-134 1.21E+00 2.19E+02 3.03E+01 2.23E+02 8.11E+00 8.11E+01 4.24E+00 5.08-01 1.37 02 8.95E+01 3.14E+02 2.17E+01 1.37E+02 1.15E+01 9.99E-01 1A6E+02 1.14E+04 9.07E+04 2.86E+03 2.50E+04 1.49E+03 5.33E+00 9.74E+02 1.39E+02 4.08E+02 3.46E+01 1.73E+02 1.83E+01 0.0.0.0.0.0.0.1.82E-01 4.93E+03 7.67E+01 5.95E+01 4.08E+00 9.99E+01 1.00E-02 3.83E-01 1.30E+02 3.52E+01 1.87E+02 7.71E+00 4.24E+01 4.12E+00 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 162 of 225 TABLE L-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE I-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 W-187 NP-239 BONE 1.77E+01 6.75E+03 5.46E+02 8.98E+03 4.63E+00 5.99E+00 1.75E+03 0.1.31E+00 1.67E+00 6.14E-02 3.51E+00 4.60E-01 2.01E+02 1.45E-02 6.98E+00 2.71E-02 LIVER 4.68E+01 1.63E+04 2.16E+03 1.21E+04 9.15E+00 4.27E-03 2.15E+00 2.20E-03 1.35E-03 8.25E-01 2.79E-OP, 2.36E+00 3.40+02 8.25E 01 5.99E-03 5.85E+00 2.67E-03 THYROID 6.11E+03 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.KIDNEY 7.43E+01 4.03E+03 1.20E+03 3.11E+03 6.73E+00 3.99E-03 5.35E-01 2.04E-03 1.14E-03 0.0.8.19E-01 1.50E-01 3.37E+01 3.39E-03 0.8.25E-03 0.LUNG 1.97E+03 1.65E+02 1.60E+03 6.65E-01 2.42E-03 1.44E+00 1.25E-03 7.64E-04 0.0.0.0.0.0.0.0.Gl-LLI 5.23E+01 1.88E+02 2.45E+02 1.61E+02 3.90E-05 1.06E+01 2.55E+02 1.37E-09 0.4.55E+04 2.04E+02 6.38E+03 1.27E+04 4.74E+04 2.08E-09 1.91E+03 5.43E+02 WHOLE BODY 1.71E+01 7.60E+03 1.55E+03 4.24E+03 4.54E+00 1.75E-01 1.12E+02 9.80E-02 8.26E-02 2.18E-01 6.95E-03 2.70E-01 3.76E-02 1.07E+01 7.34E-04 2.05E+00 1.46E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 163 of 225 TABLE L-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/HR PER p,CI/ML)NUCLIDE H--3 0.BONE LIVER 1.81E-01 THYROID 1.81E-01 KIDNEY 1.19E-01 LUNG 1.81E-01 Gl-LLI 1.81E-01 WHOLE BODY 1.81E-01 NA-24 P--32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 Nl-65 CU-64 ZN-65 ZN-69 BR-82 BR-83 BR-84 BR-85 2.03E-01 5.53E+06 0.0.0.3.87E+04 2.71E+04 0.6.73E+01 0.5.47E+04 1.16E+02 0.0.0.2.03E-01 3.47E+05 0.2.34E+03 5.88E+01 1.74E+05 6.43E+04 4.78E+01 5.05E+02 l.41E+03 8.74E+00 7.15+01 1.74 05 2.23E+02 0.0.0.2.03E-01 0.1.12E+00 0.0.0.0.)0.0.0.0.0.2.03E-01 0.4.13E-01 6.95E+02 7.46E+01 0.0.0.0.0.1.80E+02 1.16E+05 1.44E+02 0.0.0.0.2.03E-01 0.2.48E+00 0.0.2.02E+05 1.79E+04 0.0.0.0.0.0.0.0.0.0.2.03E-01 6.22E+05 4.70E+02 7.15E+03 1.88E+03 6.81E+04 2.12E+05 1.21E+03 3.00E+03 7.80E+03 2.22E+02 6.09E+03 1.09E+05 3.34E+01 1.59E+00 3.55E-02 2.51E-07 0.2.03E-01 2.14E+05 1.87E+00 4.46E+02 1.05E+01 4.58E+04 2.45E+04 7.94E+01 1.52E+03 4.23E+03 3.98E+00 3.36E+01 7.86E+04 1.55E+01 1.39E+00 2.47E-02 3.20E-02 1.31E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 164 of 225 TABLE L-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)NUCLIDE RB-86 RB-88 0.BONE LIVER 2.08E+02 5.96E-01 0.0.THYROID 0.0.KIDNEY 0.0.LUNG Gl-LLI 4.09E+01 0.WHOLE BODY 9.68E+01 3.16E-01 RB-89 SR-89 SR-90 SR-91 SR-92 Y--90 Y-91M Y--'91 Y--92 Y--93 ZR-95 ZR-97 NB-95 NB-97 MO-99 TC-99M TC-101 0.7.53E+03 9.39E+04 3.18E+01 1.18E+01 9.00E+00 1.95E-02 1.25E+02 1.81E-01 5.73E-01't.80E+01 2.91E-01 4.61E+02 1.24E+00 0.4.34E-03 4.47E-03 3.95E-01 0.0.0.0.0.0.0.0.0 4.19+00 5.87 02 1.97E+02 3.12E-01 4.23E+01 1.23E-02 6.45E-03 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.2.67E+00 8.86E-02 8.11E+01 3.64E-01 9.59E+01 1.86E-01 1.16E-01 0.0.0.0.0.0.0.0.0.0.0.0.0.6.01E-03 3.29E-03 0.2.81E+02 1.25E+03 1.60E+02 2.33E+02 2.57E+04 5.71E-02 1.66E+04 3.16E+03 1.82E+04 4.33E+03 1.82E+04 3.41E+05 1.15E+03 9.81E+01 7.26E+00 0.2.78E-01 2.16E+02 2.38E+04 1.40E+00 5.08E-01 2.42E-01 7.55E-04 3.34E+00 5.28E-03 1.58E-02 3.81E+00 2.70E-02 1.45E+02 1.14E-01 8.05E+00 1.57E-01 6.33E-02 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 165 of 225 TABLE L-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)NUCLIDE RU-103 RU-105 RU-106 BONE 1.33E+02 3.03E+00 2.34E+03 0.0.0.LIVER 0.THYROID KIDNEY 1.39E+02 3.91E+01 1.05E+03 0.0.0.LUNG GI-LLI.3.50E+03 1.85E+03 3.63E+04 WHOLE BODY 5.38E+01 1.19E+00 2.91E+02 AG110 SB-124 SB-125 5.18E+02 9.13E+01 7.24E+01 4.80E+02 1.72E+00 7.80E-01 0.2.21E-01 6.43E-02 9.43E+02 0.0.0.7.08E+01 7.57E+03 1.96E+05 2.58E+03 6.40E+02 2.85E+02 3.61E+01 1.46E+01 TE-127 1.23E+01 TE129M 1.35E+03 TE-129 8.59E-01 TE131M 4.75E+01 TE 125M 3.11E+02 TE 127M 1.85E+02 8.43E+01 6.47E+01 3.27E+00 3.77E+02 3.25E-01 2.31E+01 8.73E+01 4.72E+01 8.46E+00 4.31E+02 6.58E-01 3.66E+01 2.97E+02 7.50E+02 1.22E+01 1.31E+03 3.60E+00 2.34E+02 0.0.0.0.0.0.3.00E+02 6.19E+02 5.24E+02 1.63E+03 6.47E-01 2.29E+03 4.15E+01 2.25E+01 2.63E+00 2.09E+02 2.09E-01 1.93E+01 TE-131 TE-132 I-130 I-131 I-132 I-133 I-134 5.38E-01 2.78E+02 1.33E+01 2.87E+02 3.57E+00 1.05E+02 1.86E+00 2.25-01 1.23 02 3.94E+01 2.94E+02 9.55E+00 1.30E+02 5.06E+00 4.42E-01 1.81E+02 5.01E+03 9.55E+04 1.26E+03 3.13E+04 6.58E+02 2.36E+00 4.31E+02 6.12E+01 1.79E+02 1.52E+01 7.61E+01 8.07E+00 0.0.0.0.0.0.8.05E-02 2.15E+03 3.38E+01 2.51E+01 1.79E+00 5.26E+01 4.41E-03 1.70E-01 1.48E+02 1.55E+01 2.22E+02 3.39E+00 5.10E+01 1.81E+00 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 166 of 225 TABLE L-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)NUCLIDE I-135 BONE 7.79E+00 LIVER 2.06E+01 THYROID 2.69E+03 KIDNEY 3.27E+01 0.LUNG GI-LLI 2.30E+01 WHOLE BODY 7.54E+00 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 W-187 NP-239 8.14E+03 2.37E+02 1.13E+04 2.01E+00 2.65E+00 2.25E+03 0.5.81E-01 2.16E+00 2.74E-02 4.67E+00 2.05E-01 2.66E+02 6.46E-03 3.03E+00 1~18E-02 1.37E+04 9.34E+02 1.10E+04 3.96E+00 1.89E-03 1.98E+00.9.71E-04 5.98E-04 7.52E-01 1.24E-OP, 2.34E+00 1.52+02 8.33 01 2.67E-03 2.54E+00 1.16E-03 0.0.0.0.0.0.0.0.0.0.0.0.1.75E+03 5.20E+02 1.35E+03 2.92E+00 1.77E-03 2.37E-01 9.03E-04 5.05E-04 0.0.3.66E-01 6.69E-02 1.50E+01 1.51E-03 0.3.58E-03 1.52E+03 7.13E+01 1.29E+03 2.88E-01 1.07E-03 1.18E+00 5.51E-04 3.38E-04 0.0.0.0.0.0.0.7.42E+01 1.06E+02 6.69E+01 1.69E-05 4.69E+00 1.15E+02 6.06E-10 0.2.14E+04 9.09E+01 2.93E+03 5.67E+03 2.16E+04 9.26E-10 8.31E+02-2.36E+02 2.92E+03 6.73E+02 1.64E+03 1.97E+00 7.75E-02 1.32E+02 4.34E-02 3.66E-02 2.54E-01 3.10E-03 3.48E-01 1.68E-02 1.42E+01 3.27E-04 8.90E-01 6.34E-04 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution Page 167 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATlON MANUAL ODCM TABLE 6-1 EFFLUENT CONCENTRATION LIMITS IN AIR IN UNRESTRICTED AREAS NOTE If a nuclide is not listed below, refer to 10 CFR Part 20, Appendix B, Table 2 Effluent Concentrations Column 1 and use the most conservative ECL listed for the nuclide.Nuclide Ar-41 Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 H-3 P-32 Cr-51 Mn-54 ECL pCi/ml 1 E-8 5 E-5 1 E-7 7 E-7 2 E-8 9 E-9 None None 2 E-6 6 E-7 5 E-7 4 E-8 7 E-8 None 2 E-8 1 E-7 1 E-9 3 E-8 1 E-9 Nuclide Co-57 Co-58 Fe-59 Co-60 Zn-65 Rb-86 Rb-88 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 RU-103 Ru-106 Ag-110 Sn-113 In-113m Sn-123 Sn-126 ECL pCi/ml 9 E-10 1 E-9 5 E-10 5 E-11 4 E-10 1 E-9 9 E-8 2 E-10 6 E-12 2 E-10 4 E-10 2 E-9 9 E-10 2 E-11 1 E-10 8 E-10 2 E-7 2 E-10 8 E-11 Nuclide Sb-124 Sb-125 Te-125m Te-127m Te-129m I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 ECL pCI/ml 3 E-10 7 E-10 1 E-9 4 E-10 3 E-10 3 E-9 2 E-10 2 E-8 1 E-9 6 E-8 6 E-9 2 E-10 9 E-10 2 E-10 2 E-9 2 E-9 8 E-10 2 E-11 ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 6-2 DOSE FACTORS FOR NOBLE GASES'age 168 of 225 RADIONUCLIDE Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135~Xe-137 Xe-138 Ar-41 TOTAL BODY DOSE FACTOR K, (mrem/yr per pCi/m')7,56E-02**

1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02 2.94E+02 3.12E+03'.81E+03 1.42E 3 8.83E+3 8.84E+03 SKIN DOSE FACTOR L, (mrem/yr per pCi/m')1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 GAMMA AIR DOSE FACTOR M, (mrad/yr per pCI/m')1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 9.30E+03 BETA AIR DOSE FACTOR N, (mrad/yr per pCi/m')2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03*The listed dose factors are for radionuclides that may be detected in gaseous effluents.

7.56E-02=7.56 X 10~

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 169 of 225 TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P I FOR GASEOUS DISCHARGES PATHWAY-GROUND PLANE DEPOSITION AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE H-3 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110 WHOLE BODY 0.6.68E+06 1.10E+09 3.92E+08 1.64E+08 5.27E+08 4.40E+09 6.87E+08 1.29E+07 3.07E+04 5.94E+05 1.53E+06 6.94E+08 1.95E+08 1.57E+08 2.99E+08 3.18E+09 Based on 1 pCi/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCMPage 170 of 225 TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P I FOR GASEOUS DISCHARGES PATHWAY-GROUND PLANE DEPOSITION AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE WHOLE BODY SN-126 SB-124 SB-125 4.80E+09 8.42E+08 7.56E+08 TE-125M 2.1 9E+06 TE-127M-1.15E+06 TE-129M I-130 I-131 1-132 l-133 I-134 l-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 5.49E+07 7.90E+06 2.46E+07 1.78E+06 3.54E+06 6.43E+05 3.66E+06 2.82E+09 2.13E+08 1.15E+09 2.39E+08 1.95E+07 9.52E+07 Based on 1 pCi/sec release rate of each isotope in and a Value of 1, for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 171 of 225 TABLE G-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GROUND PLANE DEPOSITION AGE GROUP-CHILD-TEEN-ADULT

&INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE H-3 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-106 AG-110 WHOLE BODY 0.4.68E+06 1.38E+09 2.75E+08 1.89E+08 3.80E+08 2.15E+10 7.43E+08 9.01E+06 2.17E+04 5.35E+06 1.08E+06 5.01E+08 1.36E+08 1.10E+08 4.19E+08 3.58E+09 Based on 1 pCI/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 172 of 225 TABLE G-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GROUND PLANE DEPOSITION AGE GROUP-CHILD-TEEN-ADULT

&INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE SN-126 SB-124 SB-125 TE-125M TE-127M TE-129M I-130 l-131 l-132 I-133 l-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 WHOLE BODY 5.16E+10 5.98E+08 2.30E+09 1.55E+06 8.79E+05 3.85E+07 5.53E+06 1.72E+07 1.25E+06 2.48E+06 4.50E+05 2.56E+06 6.99E+09 1.49E+08 1.03E+10 l.68E+08 1.37E+07 1.13E+08 Based on 1 pCi/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 173 of 225 TABLE 6-5 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-INFANT ORGAN DOSE FACTOR (MREM/YR PER p,CI/Cu Meter)NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H-3 P-32 CR-51 MN-54 0.2.31E+05 0.0.FE-59 2.06E+03 CO-57 CO-58 CO-60 0.0.0.ZN-65 5.67E+03 RB-86 0.Y-91 5.98E+04 ZR-95 1.08E+04 NB-95 1.28E+03 RU-103 1.69E+02 RU-106 9.31E+03 AG-110 1.89E+03 SR-89 4.31E+04 SR-90 1.32E+07 4.30E+02 1.35E+04 0.6.93E+03 4.86E+06 1.21E+02 1.18E+02 8.40E+02 1.81E+04 2.37E+04 0.0.0.2.73E+03 5.E+02 0.0.1.75E+03 4.30E+02 0.1.40E+01 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.88E+02 0.3.99E+00 1.72E+03 0.0.1.21E+04 0.0.0.0.9.48E+03 1.35E+03 1.02E+03 2.34E+04 3.44E+03 4.30E+02 0 2.52E+03 2.45E+05 1.78E+05 6.47E+04 8.79E+05 5.57E+06 1.53E+05 0.2.31E+06 1.53E+07 2.63E+06 1.81E+06 4.77E+05 5.66E+05 1.50E+07 8.12E+05 4.30E+02 1.51E+04 5.81E+02 1.35E+04 3.29E+04 5.50E+03 1.21E+04 3.28E+04 9.35E+03 2.91E+03 6.80E+04 1.39E+05 7.17E+04 1.41E+04 1.21E+04 1.58E+04 1.76E+05 5.29E+04 4.30E+02 8.78E+03 1.75E+01 1.10E+03 1.85E+03 1.18E+02 1.68E+02 1.17E+03 8.15E+03 1.03E+04 1.24E+03 8.06E+05 1.60E+03 1.95E+03 3.37E+02 5.85E+01 1.I4E+03 1.04E+03 Based on 1 p.CI/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM.Page 174 of 225 TABLE G-5 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-INFANT ORGAN DOSE FACTOR (MREM/YR PER pCi/Cu Meter)NUCLIDE SN-123 SN-126 SB-124 SB-125 BONE 3.11E+04 2.21E+05 5.46E+03 1.16E+04 LIVER 6.45E+02 5.85E+03 1.03E+02 1.25E+02 THYROID 6.45E+02 1.72E+03 1.32E+01 1.03E+01 0.0.0.0.KIDNEY LUNG 3.61E+06 1.64E+96 4.34E+05 3.85E+05 GI-LLI 5.99E+04 2.23E+04 7.11E+04 1.76E+04 WHOLE BODY 1.02E+03 8.40E+03 2.17E+03 2.32E+03 TE-125M TE-127M TE-129M I-130 I-131 I-132 I-133 I-134 l-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 4.54E+02 2.21E+03 1.32E+03 8.02E+02 3.63E+04 2.03E+02 1.34E+04 1.13E+02 4.70E+02 4.80E+05 6.85E+03 6.86E+05 5.70E+03.2.52E+03 4.68E+05 1.95E+02 9.83E+02 5.80E+02 2.35E+03 4.27E+04 5.70E+02 1.93E+04 3.02E+02 1.22E+03 8.2 E+05 2.5 E+04 7.31E+05 4.27E+00 1.55E+03.1.82E+05 1.53E+02 5.75E+02 5.08E+02 3.05E+05 1.41E+07 7.67E+04 4.66E+06 4.02E+04 1.64E+05 0.0.0.0.0.0.2.17E+03 8.01E+03 6.40E+03 3.65E+03 1.07E+04 9.09E+02 4.55E+03 4.82E+02 1.95E+03 5.04E+04 1.50E+04 3.89E+04 2.93E+00 1.10E+03 1.48E+05 4.96E+05 1.68E+05 1.83E+06 0.0.0.0.0.0.1.01E+05 2.10E+03 9.45E+04 1.64E+06 5.24E+05 1.27E+07 1,36E+04 2.62E+04 7.32E+04 1.35E+03 1.07E+03 7.11E+01 2.28E+03 1.76E-01 9.18E+02 1.37E+03 2.04E+03 1.32E+03 3.88E+03 2.06E+04 1.61E+05 6.16E+01 2.74E+02 2.06E+02 9.25E+02 2.51E+04 2.03E+02 5.87E+03 1.08E+02 4.51E+02 7.32E+04 1.95E+04 4.41E+04 2.95E+02 1.81E+02 2A9E+04 Based on 1 pCi/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 175 of 225 TABLE G-6 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE H-3 P-32 BONE 0.1.82E+10 LIVER 2.37E+03 1.14E+09 THYROID 2.37E+03 0.KIDNEY 1.04E+03 0.LUNG 2.37E+03 0.GI-LLI 2.37E+03 2.05E+09 WHOLE BODY 2.37E+03 7.05E+08 CR-51 MN-54 0.0.FE-59 3.17E+07 CO-57'.0.8.96E+06 7.52E+07 1.36E+06 1.82E+04 0.0.0.6.72E+03 2.67E+06 0.0.4.04E+04 0.2.09E+07 0.7.66E+06 2.74E+07 2.48E+08 3.46E+07 3.05E+04 1.71E+06 2.86E+07 2.27E+06 CO-58 0.2.55E+07 0.0.0.6.60E+07 6.24E+07 CO-60 0.ZN-65 1.46E+09 RB-86 0.SR-89 I:47E+1 0 SR-90 1.65E+11 8.73E+07 4.65E+09 2.77E+09 0.0.0.0.0.0.0.0.3.11E+09 0.0.0.0.0.0.0.2.16E+08 2.93E+09 5.45E+08 2.75E+08 1.61E+09 2.09E+08 2.'I OE+09 1.29E+09 4.22E+08 4.21E+10 Y-91 8.12E+04 0.0.5.37E+06 2.16E+03 ZR-95 2.12E+05 NB-95 5.49E+05 RU-103 8.30E+03 RU-106 2.01E+05 AG-'I 10 6.21E+07 9.41E+04 2.4 E+05 0.0.5.75E+07 0.0.0.0.0.1.86E+04 4.84E+04 4.16E+03 4.20E+04 1.13E+08 0.0.0.0.0.7.47E+07 1.98E+08 1.04E+05 1.56E+06 2.35E+10 5.56E+04 1.45E+05 2.86E+03 2.46E+04 3.42E+07 Based on 1 pCi/sec release rate of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition Note: The units for C-14 and H-3 are (MREM/YR Per pCi/Cu.Meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM-Page 176 of 225 TABLE G-5 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCi/Sec)NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-126 1.75E+09 SB-124 2.75E+07 SB-125 3.59E+07 TE-125M 1.57E+08 4.54E+05 I-130 TE-127M 5.54E+07 TE-129M 5.87E+08 3.48E+07 5.19E+05 3.27E+06 5.30E+07 1.93E+07 2.02E+08 1.35E+06 1.01E+07 6.64E+04 2.93E+06 5.18E+07 1.79E+07 2.21E+08 1.71E+08 0.0.3.96E+06 7.05E+07 2.00E+08 2.70E+08 2.09E+06 4.97E+06 2.13E+87 2.83E+09 0.0.0.0.1.16E+09 7.78E+08 2.43E+08 7.57E+07 3.24E+08 3.54E+08 1.15E+06 5.25E+07 1.09E+07 6.62E+06 2.10E+07 7.38E+06 8.95E+07 5.29E+05 I-131 1-132 1-133 I-134 2.59E+09 1.78E-01 3.75E+07 0.3.09E+09 4.76E-01 5.48E+07 0.9.94E+11 6.26E+01 1.30E+10 1.06E-09 7.24E+08 7.58E-01 1.29E+07 0.0.0.0.0.1.16E+08 8.93E-02 9.74E+06 0.1.81E+09 1.69E-01 1.66E+07 0.I-135 1.49E+04 CS-134 4.43E+1 0 CS-136 2.78E+08 7.97E+10 1.10E+09 0.0.3.94E+04, 5.15E+06 6.26E+04 4.65E+09 6.11E+08 8.07E-02 9.12E+09 8.37E+07 4.41E+04 1.90E+08 1.25E+08 1.44E+04 6.75E+09 7.90E+08 CS-137 6.44E+10 BA-140 2.45E+08 CE-141 2.65E+05 CE-144 2.10E+07 7.E+10 2.47E+05 1.62E+05 8.29E+06 0.0.0.0.3.66E+09 1.22E+04 9.72E+03 5.67E+05 8.69E+09 1.51E+05 0.0.1.86E+08 8.13E+06 7.87E+07 8.66E+08 4.14E+09 1.27E+07 1.90E+04 1.13E+06 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition.

Note: The units for C-14 and H-3 are (MREM/YR Per pCi/Cu.Meter)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 177 of 225 TABLE G-7 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/Sec)NUCLIDE H-3 P-32 CR-51 MN-54 0.BONE 2.19E+10 0.0.LIVER 4.84E+03 1.37E+09 0.1.08E+06 THYROID 4.84E+03 0.2.19E+03 0.KIDNEY 2.11E+03 0.8.07E+02 3.20E+05 LUNG 4.84E+03 0.4.85E+03 0.Gl-LLI 4.84E+03 2.46E+09 9.19E+05 3.29E+06 WHOLE BODY 4.84E+03 8.46E+08 3.66E+03 2.05E+05 CO-57 0..FE-59 4.12E+05 9.78E+05 1.64E+05 0.0.0.0.2.72E+05 0.3.23E+06 4.15E+06 3.72E+05 2.72E+05 CO-58 0.3.06E+06 0.0.0.7.92E+06 7.49E+06 CO-60 0.Y-91 9.74E+03 ZR-95 2.54E+04 NB-95 6.59E+04 RU-103 9.96E+02 RU-106 2.41E+04 AG-110 7.45E+06 ZN-65 1.76E+08 RB-86 0.SR-89 3.09E+1 0 SR-90 3.46E+11 1.05E+07 5.57E+08 3.32E+08 0.0.1.13E+04 2.E+04 0.0.6.90E+06 0.0.0.0.0.0.0.0.0.0.0.3.73E+08 0.0.0.0.2.23E+03 5.81E+03 4.99E+02 5.04E+03 1.36E+07 0.0.0.0.0.0.0.0.0.0.2.59E+07 3.51E+08 6.54E+07 5.77E+08 3.35E+09 6.45E+05 8.95E+06 2.37E+07 1.24E+04 1.87E+05 2.81E+09 2.51E+07 2.52E+08 1.55E+08 8.87E+08 8.83E+10 2.60E+02 6.67E+03 1.75E+04 3.43E+02 2.96E+03 4.10E+06 Based on 1 pCI/sec release rate.of each isotope in and a Value of 1.for X/Q, depleted X/Q and Relative Deposition Note: The units for C-14 and H-3 are 1MREM/Yr per pCi/Cu meter.

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 178 of 225 TABLE G-7 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I/P I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCi/Sec)NUCLIDE SN-126 SB-124 BONE 2.10E+08 3.30E+06 LIVER 4.17E+06 6.22E+04 THYROID 1.22E+06 7.97E+03 0.0.KIDNEY LUNG 5.97E+05 2.56E+C6 GI-LLI 1.40E+08 9.33E+07 WHOLE BODY 6.30E+06 1.30E+06 SB-125 TE-125M TE-127M TE-129M I-130 1-131 1-132 1-133 I-134 4.31E+06 1.89E+07 6.64E+06 7.05E+07 5.45E+05 3.11E+09 2.13E-01 4.50E+07 0.3.92E+05 6.36E+06 2.31E+06 2.42E+07 1.61E+06 3.70E+09 5.71E-01 6.57E+07 0.3.52E+05 6.21E+06 2.15E+06 2.66E+07 2.05E+08 1.19E+12 7.51E+01'I.55E+1 0 1.27E-09 4.76E+05 8.46E+06 2.40E+07 3.23E+07 2.51E+06 9.28E+08 9.10E-01 1.55E+07 0.3.40E+08 0.0.0.0.0.0.0.0.2.92E+07 9.09E+06 3.88E+07 4.25E+07 1.38E+06 1.39E+08 1.07E-01 1.17E+07 0.7.94E+05 2.52E+06 8.85E+05 1.07E+07 6.35E+05 2.17E+09 2.03E-01 1.99E+07 0.1-135 CS-134 CS-136 CS-137 1.79E+04 1.33E+11 8.34E+08 1.93E+11 2.39E+11 3.29E+09 2.E+11 0.0.4.72E+04, 6.18E+06 7.51E+04 1.39E+10 1.83E+09 1.10E+10 2.42E-01 2.74E+1 0 2.51E+08 2.61E+10 5.29E+04 5.69E+08 3.74E+08 5.59E+08 1.73E+04 2.02E+10 2.37E+09 1.24E+10 BA-140 CE-141 CE-144 2.95E+07 3.17E+04 2.52E+06 2.96E+04 1.95E+04 9.95E+05 0.0.0.1.47E+03 1.17E+03 6.80E+04 1.81E+04 0.0.9.76E+05 9.44+06 1.04E+08 1.52E+06 2.28E+03 1.36E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition.

Note: The units for C-14 and H-3 are 1MREM/Yr per pCi/Cu meter.

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 179 of 225 TABLE G-8 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/YR PER pCI/CU.METER)NUCLIDE H--3 0.BONE LIVER 7.51E+02 THYROID 7.51E+02 KIDNEY 4.96E+02 LUNG 7.51E+02 Gl-LLI 7.51E+02 WHOLE BODY 7.51E+02 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 6.11E+05 0.0.5.44E+03 0.0.0.1.50E+04 0.5.37E+04 1.64E+07 7.44E+04 1.41E+04 1.70E+03 2.16E+02 1.15E+04 5.00E+03 3.57E+04 0.1.83E+04 1.28E+07 3.20E+02 1.52E+02 1.07E+03 4.77E+04 6.25E+04 0.0.0.~3.28E+03.25E+02 0.0.4.63E+03 2.75E+01 0.0.0.0.0.0.0.0.0.0.0.0.1.06E+01 4.55E+03 0.0.0.0.3.19E+04 0.-0.0.0.2.51E+04 3.58E+03 2.70E+03 6.18E+04 9.10E+03 0.6.66E+03 6.48E+05 4.70E+05 1.71E+05 1.13E+06 6.92E+06 4.03E+05 0.2.24E+06 1.48E+07-2.55E+06 2.12E+06 5.85E+05 6.33E+05 1.45E+07 2.15E+06 4.00E+04 1.54E+03 3.58E+04 8.70E+04 1.45E+04 3.62E+04 9.36E+04 2.47E+04 7.70E+03 1.69E+05 3.45E+05 1.78E+05 5.74E+04 3.32E+04 4.22E+04 4.37E+05 1.40E+05 2.32E+04 4.63E+01 2.91E+03 4.88E+03 3.10E+02 2.68E+02 1.88E+03 2.15E+04 2.73E+04 1.54E+03 9.99E+05 1.98E+03 2.98E+03 5.33E+02 8.73E+01 1.44E+03 2.75E+03 Based on 1 pCI/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 180 of 225 TABLE G-8 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY>>INHALATION AGE GROUP-CHILD ORGAN DOSE FACTOR (MREM/YR PER pCI/CU.METER)NUCLIDE SN-123 SN-126 SB-124 BONE 3.85E+04 5.85E+05 1.44E+04 LIVER 6.44E+02 1.55E+04 2.72E+02 THYROID 6.81E+02 4.55E+03 3.49E+01 0.0.0.KIDNEY LUNG 3.50E+06 4.33E+06 1.15E+06 Gl-LLI 1.49E+05 5.88E+04 1.88E+05 WHOLE BODY 1.27E+03 2.22E+04 5.74E+03 SB-125 3.06E+04 TE 125M 5.62E+02 TE 127M 5.85E+03 TE 129M 1.64E+03 3.30E+02 1.94E+02 2.60E+03 5.85E+02 2.72E+01 1.61E+02 1.52E+03 5.40E+02 0.5.74E+03 2.12E+04 1.69E+04 1.02E+06 4.81E+05 4.44E+05 1.80E+06 4.66E+04 3.38E+04 6.92E+04 1.82E+05 6.14E+03 7.62E+01 7.25E+02 2.60E+02 I-130 I-131 I-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 2.12E+03 4.55E+04 5.37E+02 1.68E+04 2.98E+02 1.24E+03 6.22E+05 1.81E+04 8.66E+05 7.14E+03 3.13E+03 5.81E+05 6.22E+03 4.63E+04 1.51E+03 2.05E+04 7.99E+02, 3.23E+03 9.95E+05.77E+04 7.99E+05 4.66E+00 1.57E+03 1.82E+05 8.07E+05 1.54E+07 2.03E+05 5.03E+06 1.06E+05 4.33E+05 0.0.0.0.0.0.9.66E+03 2.84E+04 2.40E+03 1.20E+04 1.27E+03 5.14E+03 1.33E+05 3.96E+04 1.03E+05 7.73E+00 2.90E+03 3.92E+05 0.0.0.0.0.1.19E+05 5.55E+03 1.00E+05 1.74E+06 5.14E+05 1.23E+07 3.56E+03 2.65E+03 1.88E+02 5.55E+03 4.66E-01 2.43E+03 3.77E+03 5.40E+03 3.41E+03 9.92E%03 5.44E+04 4.00E+05 2.45E+03 3.50E+04 5.37E+02 8.03Es 03 2.85E+02 1.19E+03 2.23E+05 5.14E+04 1.25E+05 4.22E+02 2.33E+02 3.10E+04 Based on 1 pCI/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 181 of 225 TABLE G-9 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 0.BONE 1.82E+10 0.0.3.17E+07 0.0.0.1.46E+09 0.6.92E+09 1.13E+11 3.80E+04 1.06E+05 2.75E+05 3.99E+03 9.39E+04 6.21E+07 LIVER 1.57E+03 1.14E+09 0.8.96E+06 7.52E+07 1.36E+06 1.25E+07 4.22E+07 4.65E+09 2.77E+09 0.0.0.4.47E+04 1.18E+05 0.0.5.75E+07 THYROID 1.57E+03 0.1.82E+04 0.0.0.0.0.0.0.0.0.0.0.0.0.KIDNEY 1.04E+03 0.6.72E+03 2.67E+06 0.0.0.0.3.11E+09 0.0.0.0.1.86E+04 4.84E+04 4.16E+03 4.20E+04 1.13E+08 LUNG 1.57E+03 0.4.04E+04 0.2.09E+07 0.0.0.0.0.0.0.0.0.GI-LLI 1.57E+03 2.05E+09 7.66E+06 2.74E+07 2.48E+08 3.46E+07 7.41E+07 2.33E+08 2.93E+09 5.45E+08 2.58E+08 1.52E+09 5.05E+06 7.68E+07 2.03E+08 1.05E+05 1.46E+06 2.35E+10 WHOLE BODY 1.57E+03 7.05E+08 3.05E+04 1.71E+06 2.86E+07 2.27E+06 3.76E+07 1.27E+08 2.10E+09 1.29E+09 1.98E+08 2.87E+10 1.01E+03 3.29E+04 8.63E+04 1.61E+03 1.17E+04 3.42E+07 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 182 of 225 TABLE G-9 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-'HILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 0.BONE 0.LIVER THYROID 0.0.KIDNEY 0.LUNG 0.GI-LLI WHOLE BODY: 0.SN-126 SB-124 SB-125 TE 125M TE 127M TE 129M 1-130 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.75E+09 2.75E+07 3.13E+07 7.38E+07 5.18E+07 2.77E+08 4.54E+05 1.24E+09 1.78E-01 1.78E+07 0.1.49E+04 2.17E+10 2.78E+08 3.08E+10 1.17E+08 1.24E+05 1.00E+07 3.48E+07 5.19E+05 1.41E+06 2.00E+07 1.78E+07 7.73E+07 1.35E+06 1.27E+09 4.76E-01 2.20E+07 0.3.94E+04 3.65E+10 1.10E+09 2.98E+10 1.02E+05 6.22E+04 3.14E+06 1.01E+07 6.64E+04.1.18E+06 2.07E+07 1.46E+07 8.85E+07 1.71E+08 4.12E+11 6.26E+01 5.30E+09 1.06E-09 5.15E+06 0.0.0.0.0.0.0.0.3.96E+06 7.05E+07 2.00E+08 2.70E+08 2.09E+06 7.74E+08 7.58E-01 1.29E+07 0.6.26E+04 4.65E+09 6.11E+08 3.66E+09 1.22E+04 9.72E+03 5.67E+05 4.97E+06 2.13E+07 2.83E+09 0.0.0.0.0.0.0.8.07E-02 4.06E+09 8.37E+07 3.49E+09 6.09E+04 0.0.1.'I 6E+09 7.78E+08 2.43E+08 7.12E+07 2.99E+08 3.33E+08 1.15E+06 1.09E+08 8.93E-02 8.90E+06 0.4.41E+04 1.97E+08 1.25E+08 1.81E+08 7.75E+06 7.80E+07 8.15E+08 5.25E+07 1.09E+07 5.99E+06 9.84E+06 6.60E+06 4.28E+07 5.29E+05 9.56E+08 1.69E-01 8.63E+06 0.1.44E+04 7.76E+09 7.90E+08 4.44E+09 6.84E+06 9.26E+03 5.34E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 183 of 225 TABLE G-10 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 0.BONE LIVER 3.20E+03 THYROID 3.20E+03 KIDNEY 2.11E+03 LUNG 3.20E+03 GI-LLI 3.20E+03 WHOLE BODY 3.20E+03 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-1 03 RU-106 AG110 2.19E+10 0.0.4.12E+05 0.0.0.1.76E+08 0.1.45E+10 2.37E+11 4.56E+03 1.27E+04 3.30E+04 4.79E+02 1.13E+04 7.45E+06 1.37E+09 0.1.08E+06 9.78E+05 1.64E+05 1.50E+06 5.06E+06 5.57E+08 3.32E+08 0.0., 0.5.37E+03 1.41E+04 0.6.90E+06 0.2.19E+03 0.0.0.0.0.0.0.0.0.0.0.8.07E+02 3.20E+05 0.0.0.0.3.73E+08 0.0.0.0.2.23E+03 5.81E+03 4.99E+02 5.04E+03 1.36E+07 0.4.85E+03 0.2.72E+05 0.0.0.0.0.0.0.0.0.2.46E+09 9.19E+05 3.29E+06 3.23E+06 4.15E+06 8.90E+06 2.80E+07 3.51E+08 6.54E+07 5.43E+08 3.16E+09 6.06E+05 9.22E+06 2.44E+07 1.26E+04 1.75E+05 2.81E+09 8.46E+08 3.66E+03 2.05E+05 3.72E+05 2.72E+05 4.51E+06 1.52E+07 2.52E+08 1.55E+08 4.16E+08 6.02E+10 1.22E+02 3.96E+03~1.04E+04 1.94E+02 1.40E+03 4.10E+06 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 184 of 225 TABLE G-10 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 SN-126 SB-124 SB-125 TE 125M TE 127M'E 129M 1-130 I-131 I-132 1-133 I-134 I-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 0.BONE 2.10E+08 3.30E+06 3.75E+06 8.85E+06 6.21E+06 3.32E+07 5.45E+05 1.48E+09 2.13E-01 2.14E+07 0.1.79E+04 6.50E+10 8.34E+08 9.23E+10 1.40E+07 1.49E+04 1.20E+06 0.LIVER 4.17E+06 6.22E+04 1.70E+05 2.40E+06 2.14E+06 9.27E+06 1.61E+06 1.52E+09 5.71E-01 2.64E+07 0.4.72E+04 1.10E+11.29E+09 8.93E+10 1.23E+04 7.46E+03 3.76E+05 0.THYROID 1.22E+06 7.97E+03 1.43E+05 2.49E+06 1.75E+06 1.06E+07 2.05E+08 4.94E+11 7.51E+01 6.36E+09 1.27E-09 6.18E+06 0.0.0.0.0.0.KIDNEY 0.0.4.76E+05 8.46E+06 2.40E+07 3.23E+07 2.51E+06 9.28E+08 9.10E-01 1.55E+07 0.7.51E+04 1.39E+10 1.83E+09 1.10E+10 1.47E+03 1.17E+03 6.80E+04 0.LUNG 5.97E+05 2.56E+06 3.40E+08 0.0.0.0.0.0.0.0.2.42E-01 1.22E+10 2.51E+08 1.05E+10 7.31E+03 0.0.0.Gl-LLI 1.40E+08 9.33E+07 2.92E+07 8.54E+06 3.58E+07 4.00E+07 1.38E+06 1.30E+08 1.07E-01 1.07E+07 0.5.29E+04 5.92E+08 3.74E+08 5.44E+08 9.30E+05 9.36E+06 9.78E+07 WHOLE BODY 0.6.30E+06 1.30E+06 7.19E+05 1.18E+06 7.92E+05 5.15E+06 6.35E+05 1.15E+09 2.03E-01 1.04E+07 0.1.73E+04 2.33E+10 2.37E+09 1.33E+10 8.21E+05 1.11E+03 6.41E+04 Based on 1 pCI/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCI/cu.meter)

~~~~0 0~0 0 00~~~II~~a~a a~~~I 0 a~~~~0 0~~~0 0~~I~~0~~0~~0~0~~a~0 0 0 0~~~~~~~I~I'~'I~~~~~I~~~I~~I~I I~~'~I I I~~~I I I~I~II I~I~~r~r~~~~~I I~I I I~I~I~I~~~I~I~0 0~0~~I~~I 0~~o I~~o I I I~I~I~~~~~I~I I~0 0~~~~I~I I~I~I~I~~~I~I I I~~~I~I~0~~~~~0~i~~~--~~-.~-~~~r~

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 186 of 225 TABLE G-11 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-MEAT (CONTAMINATED FORAGE)AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 0.BONE 0.LIVER THYROID 0.0.KIDNEY 0.LUNG 0.GI-LLI WHOLE BODY 0.SN-126 SB-124 SB-125 6.92E+09 7.40E+06 7.66E+07 1.37E+08 1.40E+05 1.84E+07 4.02E+07 1.79E+04 1.90E+07 0.0.6.47E+07 2 41E+06 5.74E+06 9.26E+08 2.31E+09 2.10E+08 1.44E+08 1.98E+08 2.93E+06 1.08E+07 TE 125M 5.69E+08 TE 127M 4.40E+08 TE 129M 1.84E+09 1.54E+08 1.51E+08 5.12E+08 1.60E+08 1.24E+08 5.87E+08 5.44E+08 1.70E+09 1.78E+09 0.0.0.5.49E+08 2.54E+09 2.21E+09 7.59E+07 5.61E+07 2.84E+08 I-130 I-131 I-132 l-133 l-134 I-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 8.87E-07 1.58E+07 0.6.86E-01 0.3.21E-02 8.83E+08 4.41E+06 1.27E+09 4.37E+07 2.10E+04 2.38E+06 2.63E-06 1.62E+07 0.8.47E-01 0.2.96E-02 1.49E+09 1.74E+07 1.23E+09 3.84E+04 1.05E+04 7.46E+05 3.34E-04 5.25E+09 0.2.04E+02 0.0.0.0.0.0.4.08E-06 9.86E+06 0.4.97E-01 0.1.12E-02 1.89E+08 9.69E+06 1.51E+08 4.59E+03 1.65E+03 1.35E+05 0.0.0.0.3.37E-03 1.65E+08 1.33E+06 1.44E+08 2.29E+04 0.2.25E-06 1.38E+06 0.3.43E-01 6.92E-04 8.04E+06 1.98E+06 7.50E+06 6.03E+06 1.32E+07 1.94E+08 1.03E-06 1.22E+07 0.3.33E-01 0.1.32E-02 3.16E+08 1.25E+07 1.84E+08 2.57E+06 1.57E+03 1.27E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL OUCM Page 187 of 225 TABLE G-12 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 0.BONE LIVER 2.47E+02 THYROID 2.47E+02 KIDNEY 1.63E+02 LUNG 2.47E+02 GI-LLI 2.47E+02 WHOLE BODY 2.47E+02 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95'B-95 RU-103 RU-106 AG110 4.22E+08 0.0.1.48E+07 0.0.0.2.08E+07 0.4.84E+09 7.79E+10 2.12E+06 4.06E+05 6.20E+04 2.24E+06 5.19E+07 6.87E+05 2.64E+07 0.1.98E+07 3.51E+07 7.53E+05 6.94E+06 2.33E+07 6.59E+07 5.28E+07 0.0.0.9.87E+04.64E+04 0.6.36E+05 0.4.68E+03 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.73E+03 5.89E+06 0.0.0.4.41E+07 0.0.6.07E+04 1.09E+04 2.34E+06 2.32E+07 1.25E+06 0.'.04E+04 0.9.75E+06 0.0.0.0.0.0.0.0.0.0.0.0.4.74E+07 1.97E+06 6.07E+07 1.16E+08 1.91E+07 4.13E+07 1.29E+08 4.15E+07 1.04E+07 1.81E+08 1.52E+09 2.82E+08 1.08E+08 4.58E+07 5.88E+07 8.07E+08 2.59E+08 1.63E+07 7.83E+03 3.78E+06 1.34E+07 1.25E+06 2.09E+07 6.98E+07 2.98E+07 2.46E+07 1.39E+08 1.98E+10 5.65E+04 8.81E+04 1.94E+04 9.05E+05 6.46E+06 3.78E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 188 of 225 TABLE G-12 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-CHILD ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 BONE 1.71E-05 LIVER 2.14E-07 THYROID 2.26E-07 KIDNEY 0.LUNG GI'-LLI 8.50E-06 WHOLE BODY 4.21E-07 SN-126 SB-124 SB-125 TE 125M TE 127M TE 129M 1-130 I-131 I-132 I-133 I-134 I-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 3.87E+08 1.02E+07 1.22E+07 4.12E+07 2.88E+07 1.56E+08 1.60E+05 1.24E+08 2.26E+01 3.61E+06.4.18E-05 1.64E+04 9.97E+08 1.35E+07 1.41E+09 1.70E+08 1.17E+05 9.23E+06 7.68E+06 1.93E+05 6.99E+05 1.12E+07 9.90E+06 4.35E+07 4.73E+05 1.27E+08 6.05E+01 4.46E+06 1.i 4E-04)4.33E+04 1.68E+09.32E+07 1.37E+09 1.56E+05 5.84E+04 2.89E+06 2.25E+06 2.47E+04 6.22E+05 1.16E+07 8.09E+06 4.99E+07 6.02E+07 4.13E+10 7.97E+03 1.08E+09 1.47E-02 5.67E+06 0.0.0.0.0.0.0.2.09E+06 3.94E+07 1.11E+08 1.51E+08 7.35E+05 7.75E+07 9.65E+01 2.62E+06 1.81E-04 6.89E+04 2.14E+08 2.96E+07 1.68E+08 1.78E+04 9.13E+03 5.22E+05 1.75E+06 7.93E+06 1.04E+09 0.0.0.0.0.0.0.3.51E-03 1.87E+08 4.06E+06 1.60E+08 8.87E+04 0.3.44E+08 2.89E+08 9.02E+07 3.97E+07 1.65E+08 1.88E+08 4.05E+05 1.09E+07 1.14E+01 1.81E+06 9.89E-08 4.85E+04 9.08E+06 6.05E+06 8.34E+06 2.08E+08 7.33E+07 7.51E+08 1.19E+07 4.04E+06 2.29E+06'.49E+06 3.67E+06 2.41E+07 1.86E+05 9.58E+07 2.15E+01 1.75E+06 4.06E-05 1.59E+04 3.57E+08 3.83E+07 2.04E+08 9.96E+06 8.69E+03 4.92E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 189 of 225 TABLE G-13 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/YR PER pCI/CU.METER)NUCLIDE H--3 0.BONE LIVER 8.48E+02 THYROID 8.48E+02 KIDNEY 1.07E+03 LUNG 8.48E+02 Gl-LLI 8.48E+02 WHOLE BODY 8.48E+02 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95'B-95 RU-103 RU-106 AG110 1.32E+06 0.0.1.18E+04 0.0.3.24E+04 0.3.87E+04 1.18E+07 5.38E+04 1.09E+04 1.36E+03 1.63E+02 8.40E+03 1.08E+04 7.72E+04 0.3.96E+04 2.78E+07 6.92E+02 1.76E+02 1.24E+03 1.03E+05 1.35E+05 0.0.0.3.63E+03.24E+02 0.1.00E+04 0.5.95E+01 0.0.0.0.0.0.0.0.0.0.0.0.0.0.2.28E+01 9.84E+03 0.0.0.0.6.90E+04 0.0.0.0.5.42E+04 7.74E+03 5.83E+03 1.34E+05 1.97E+04 0 1.44E+04 1.40E+06 1.02E+06 3.70E+05 1.37E+06 8.56E+06 8.72E+05 0.2.50E+06 1.66E+07 2.86E+06 2.56E+06 7.17E+05 7.51E+05 1.64E+07 4.64E+06 8.64E+04 3.32E+03 7.74E+04 1.88E+05 3.14E+04 9.52E+04 2.35E+05 5.34E+04 1.66E+04 3.54E+05 7.24E+05 3.74E+05 1.33E+05 8.80E+04 9.44E+04 9.28E+05 3.02E+05 5.02E+04 1.00E+02 6.30E+03 1.06E+04 6.71E+02 2.34E+02 1.65E+03 4.66E+04 5.90E+04 1.11E+03 7.23E+05 1.44E+03 2.54E+03 4.62E+02 7.32E+01 1.06E+03 5.94E+03 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition l

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 190 of 225 TABLE G-13 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-TEENAGER ORGAN DOSE FACTOR (MREM/YR PER pCI/CU.METER)NUCLIDE SN-123 SN-126 SB-124 SB-125 BONE 2.79E+04 1.26E+06 3.12E+04 6.61E+04 LIVER 6.14E+02 3.34E+04 5.89E+02 7.13E+02 THYROID 4.92E+02 9.84E+03 7.55E+01 5.87E+01 0.0.0.KIDNEY LUNG 3.91E+06 9.36E+06 2.48E+06 2.20E+06 Gl-LLI 3.13E+05 1.27E+05 4.06E+05 1.01E+05 WHOLE BODY 9.20E+02 4.80E+04 1.24E+04 1.33E+04 TE 125M TE 127M TE 129M I-130 l-131 I-132 I-133 1-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 4.07E+02 1.26E+04 1.19E+03 4.58E+03 3.37E+04 1.16E+03 1.23E+04 6.45E+02 2.69E+03 4.83E+05 3.91E+04 6.42E+05 5.30E+03 2.27E+03 4.19E+05 1.86E+02 5.62E+03 5.64E+02 1.34E+04 4.72E+04 3.26E+03 2.06E+04 1.73E+03, 6.99E+03 1.10E+06 1.46E+05 8.24E+05 4.85E+00 1.52E+03 1.74E+05 1.17E+02 3.29E+03 3.90E+02 1.74E+06 1.39E+07 4.38E+05 3.83E+06 2.30E+05 9.36E+05 0.0.0.0.0.1.24E+04 4.58E+04 3.66E+04 2.09E+04 6.14E+04 5.19E+03 2.60E+04 2.75E+03 1.11E+04 2.88E+05 8.56E+04 2.22E+05 1.67E+01 6.26E+03 8.48E+05 5.36E+05 9.60E+05 2.03E+06 0.0.0.0.0.0.1.44E+05 1.20E+04 1.18E+05 2.02E+06 5.83E+05 1.38E+07 7.08E+04 1.50E+05 3.84E+05 7.69E+03 5.96E+03 4.06E+02 1.00E+04 1.01E+00 5.25E+03 8.96E+03 1.17E+04 7.68E+03 2.12E+04 1.14E+05 8 40E+05 5.53E+01 1.57E+03 1.92E+02 5.29E+03 2.82E+04 1.16E+03 6.34E+03 6.16E+02 2.58E+03 5.44E+05 1.11E+05 3.03E+05 3.42E+02 1.74E+02 2.24E+04 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition

~~~0 0~~0~~0~~0~II a~a~~~I P 0~~~I~~~~~~a~~0 a~0 0~~~0~~~0~0~~'0 0 0 0~~~~~~~~~I~~'I'~~~I~~~~~~~I~~o~~I~~I lo I I~I o~I I~I~I I~~I I I~I~I~I~0 O~0~~0~~I~~I I'~~I~~I'~~I~I~~~I~I I~~I'~~I I~0~0 0 I~I~~'~I~~I~~o I I~~I~l~I'~I~I lo I~~I~~0 0~~~~~~~~~o~~I~-~--~O.~-.-~-~~~

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 192 of 225 TABLE G-14 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 SN-126 SB-124 0.BONE 2.12E+09 3.33E+07 0.LIVER 4.21E+07 6.29E+05 THYROID 0.1.24E+07 8.05E+04 0.0.0.KIDNEY 0.LUNG 6.03E+06 2.59E+07 0.Gl-LLI 1.41E+09 9.43E+08 WHOLE BODY 0.6.37E+07 1.32E+07 SB-125 3.45E+07 9.58E+05 5.05E+05 4.80E+06 3.43E+09 2.95E+08 6.82E+06 TE 127M 6.02E+07 TE 129M 1.13E+08 I-130 I-131 5.51E+05 5.12E+08 TE 125M 3.00E+07 1.08E+07 2.11E+07 4.18E+07 1.63E+06 7.24E+08 8.47E+06 1.59E+07 3.61E+07 2.07E+08 2.09E+11 8.55E+07 2.43E+08 3.27E+08 2.53E+06 9.38E+08 0.0.0.0.8.39E+07 3.02E+08 3.93E+08 1.40E+06 1.37E+08 3.98E+06 7.45E+06 1.78E+07 6.41E+05 4.31E+08 I-132 l-133 I-134 I-135'CS-134'CS-136 CS-137 BA-140 CE-141 CE-144 2.16E-01 7.33E+06 0.1.81E+04 9.44E+09 3.37E+08 1.28E+10 4.84E+07 5.05E+04 4.10E+06 5.76E-01 1.24E+07 0.4.77E+04 2.28E+10.33E+09 1.72E+10 5.95E+04 3.39E+04 1.68E+06 7.59E+01 2.26E+09 1.29E-09 6.24E+06 0.0.0.0.0.9.19E-01 1.56E+07 0.7.58E+04 5.63E+09 7.41E+08 4.43E+09 1.48E+04 1.18E+04 6.87E+05 0.0.9.79E-02 2.76E+09 1.02E+08 2.28E+09 3.98E+04 0.1.08E-01 9.02E+06 0.5.34E+04 2.63E+08 1.51E+08 2.29E+08 9.16E+06 9.18E+07 9.65E+08 2.05E-01 3.83E+06 0.1.75E+04 1.06E+10 9.58E+08 6.04E+09 3.11E+06 3.89E+03 2.17E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 193 of 225 TABLE G-15 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 0.BONE 2.65E+10 0.0.4.99E+05 0.0.0.2.13E+08 0.5.87E+09 1.74E+11 1.85E+03 5.74E+03 1.49E+04 2.03E+02 4.59E+03 9.04E+06 LIVER 2.03E+03 1.66E+09 0.1.30E+06 1'9E+06 1.98E+05 9.72E+05 3.28E+06 6.76E+08 4.02E+08 0.0.0.3.41E+03.96E+03 0.0.8.36E+06 THYROID 2.03E+03 0.2.65E+03 0.0.0.0.0.0.0.0.0.0.0.KIDNEY 2.56E+03 0.9.78E+02 3.88E+05 0.0.0.0.4.52E+08 0.0.0.2.70E+03 7.05E+03 6.05E+02 6.11E+03 1.64E+07 LUNG 2.03E+03 0.5.88E+03 0.3.29E+05 0.0.0.0.0.0.4.05E+05 0.0.0.0.0.0.Gl-LLI 2.03E+03 2.98E+09 1.11E+06 3.99E+06 3.91E+06 5.03E+06 1.31E+07 3.93E+07 4.26E+08 7.93E+07 6.37E+08 3.68E+09 7.11E+05 1.38E+07 3.66E+07 1.58E+04 2.08E+05 3.41E+09 WHOLE BODY 2.03E+03 1.03E+09 4.43E+03 2.49E+05 4.51E+05 3.30E+05 2.22E+06 7.48E+06 3.06E+08 1.88E+08 1.69E+08 4.30E+10 4.94E+01 1.93E+03 5.05E+03 9.08E+01 5.78E+02 4.97E+06 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

~-'a~as~as as 0 as~~as~II~~a a~a a~~~I a~~e~a~~~~I~~~~~a a J~o~~o o~~~~0~~~ss~~'0~o~~~I~~II I~~~I~~I~I~~~I I~I I~I r I~I~I I~'o I~~~~I~'I~~~I~I~I~I I~I~~I~~~I~I I II~ls~'~I I~I~~I~~~I~~lo s I~~I~~'I~~I~~'~~I~I II~~I I~I~I~'~I~o~I~I I I'~I~~~QCI>>~I I ir~'~I I~I I~~~I'~~I~~I Is~r~~o I~~~I I~I I I~I~I~I~I I I I I~~I~~~~I~I'~~~~~o~~~~-~--~o~~~~~~r~

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 195 of 225 TABLE G-16 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-MEAT (CONTAMINATED FORAGE)AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 0.BONE LIVER 1.93E+02 THYROID 1.93E+02 KIDNEY 2.44E+02 LUNG 1.93E+02 Gl-LLI 1.93E+02 WHOLE BODY 1.93E+02 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 2.76E+09 0.0.1.58E+08 0.0.0.2.11E+08 0.2.66E+08 1.01E+10 9.34E+05 2.67E+06 1.58E+06 8.05E+07 2.40E+09 3.97E+06 1.73E+08 0.5.42E+06 3.74E+08 3.33E+06 1.44E+07 5.73E+07 6.69E+08 2.89E+08 0.0., 0.1.24E+06.51E+05 0.0.3.67E+06 0.2.50E+03 0.0.0.0.0.0.0.0.0.0.0.0.0.9.22E+02 1.61E+06 0.0.0.0.4.47E+08 0.0.1.18E+06 7.48E+05 2.40E+08 3.20E+09 7.21E+06 0.5.55E+03 0.1.04E+08 0.0.0.0.0.2.79E+08 0.0.0.0.0.3.10E+08 1.05E+06 1.66E+07 1.24E+09 8.45E+07 1.94E+08 6.87E+08 4.21E+08 5.69E+07 2.89E+07 1.02E+09 3.59E+08 4.20E+09 3.88E+09 6.28E+09 1.09E+11 1.50E+09 1.07E+08 4.18E+03 1.04E+06 1.42E+08 5.54E+06 3.27E+07 1.31E+08 3.03E+08 1.35E+08 7.64E+06 2.49E+09 2.49E+04 7.61E+05 5.37E+05 3.60E+07 3.02E+08 2.18E+06 Based on 1 pCI/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 196 of 225 TABLE G-16 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-MEAT (CONTAMINATED FORAGE)AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 0.BONE 0.LIVER THYROID 0.KIDNEY 0.LUNG 0.Gl-LLI WHOLE BODY 0.SN-126 1.10E+10 2.18E+08 6.38E+07 3.82E+06 3.66E+09 3.14E+08 SB-124 SB-125 1.17E+07 5.01E+07 TE 127M 6.68E+08 TE 129M 9.78E+08 I-130 1.41E-06 TE 125M 3.03E+08 2.21E+05 1.31E+07 1.08E+08 2.34E+08 3.63E+08 4.16E-06 2.84E+04 1.02E+07 8.55E+07 1.77E+08 3.13E+08 5.30E-04 0.1.03E+08 8.63E+08 2.69E+09 2.83E+09 6.47E-06 9.11E+06 1.47E+09 0.0.0.0.3.32E+08 2.25E+08 8.47E+08 3.35E+09 3.41E+09 3.57E-06 4.64E+06 7.60E+06 4.02E+07 8.28E+07 1.53E+08 1.64E-06 I-131 l-132 I-133 I-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 8.54E+06 0.3.69E-01 0.5.08E-02 5.03E+08 6.99E+06 6.92E+08 2.37E+07 1.12E+04 1.28E+06 1.21E+07 0.6.26E-01 0.4.69E-02 1.21E+09.76E+07 9.31E+08 2.93E+04 7.51E+03 5.23E+05.3.48E+09 0.1.14E+02 0.0.0.0.0.1.56E+07 0.7.88E-01 0.1.78E-02 3.00E+08 1.54E+07 2.40E+08 7.28E+03 2.61E+03 2.14E+05 0.0.0.0.5.34E-03 1.47E+08 2.11E+06 1.24E+08 1.95E+04 0.0.2.28E+06 0.4.55E-01 0.1.10E-03 1.40E+07 3.14E+06 1.24E+07 9.19E+06 2.03E+07 3.00E+08 7.19E+06 0.1.93E-01 0.2.08E-02 5.66E+08 1.99E+07 3.27E+08 1.53E+06 8.61E+02 6.76E+04 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted YJQ and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 197 of 225 TABLE G-17 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 0.BONE LIVER 2.09E+02 THYROID 2.09E+02 KIDNEY 2.64E+02 LUNG 2.09E+02 Gl-LLI 2.09E+02 WHOLE BODY 2.09E+02 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 6.81E+08 0.0.2.39E+07 0.0.0.3.35E+07 0.2.61E+09 7.61E+10 1.15E+06 2.35E+05 3.72E+04 1.27E+06 2.82E+07 1.11E+06 4.27E+07 0.3.20E+07 5.67E+07 1.22E+06 6.01E+06 2.01E+07 1.06E+08 8.52E+07 0.0.0.8.19E+04.24E+04 0.0.1.03E+06 0.7.56E+03 0.0.0.0.0.0.0.0, 0.0.0.0.0.0.0.2.79E+03 9.52E+06 0.0.0.7.12E+07 0.0.0.9.81E+04 1.76E+04 3.77E+06 3.75E+07 2.02E+06 0'.68E+04 0.1.57E+07 0.0.I0 0.0.2.41E+08 0.0.0.0.0.0.7.66E+07 3.18E+06 9.80E+07 1.87E+08 3.09E+07 8.12E+07 2.41E+08 6.70E+07 1.68E+07 2.83E+08 2.31E+09 4.41E+08 1.92E+08 9.14E+07 9.87E+07 1.28E+09 4.19E+08 2.64E+07 1.27E+04 6.11E+06 2.16E+07 2.02E+06 1.37E+07 4.58E+07 4.82E+07 3.97E+07 7.48E+07 1.88E+10 3.06E+04 5.61E+04 1.26E+04 5.66E+05 3.54E+06 6.10E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 198 of 225 TABLE G-17 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 BONE 9.25E-06 LIVER 1.53E-07 THYROID 1.22E-07 0.KIDNEY 0.LUNG Gl-LLI 1.33E-05 WHOLE BODY 2.28E-07 SN-126 SB-124 6.25E+08 1.65E+07 1.24E+07 3.12E+05 3.64E+06 3.99E+04 0.0.2.83E+06 1.28E+07 5.55E+08 4.67E+08 1.94E+07 6.53E+06 SB-125 1.73E+07 TE 125M 2.23E+07 TE 127M 4 46E+07 TE 129M 8.46E+07 5.97E+05 7.99E+06 1.55E+07 3.14E+07 3.48E+05 6.30E+06 1.18E+07 2.71E+07 3.38E+06 6.36E+07 1.80E+08 2.45E+08 1.68E+09 0.0.0.1.45E+08 6.24E+07 2.23E+08 2.95E+08 3.40E+06 2.96E+06 5.51E+06 1.33E+07 I-130 I-131 I-132 I-133 l-134 I-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 2.58E+05 6.84E+07 3.65E+01 1.98E+06 6.75E-05 2.65E+04 5.79E+08 2.18E+07 7.83E+08 9.38E+07 6.32E+04 5.03E+06 7.64E+05 9.66E+07 9.77E+01 3.36E+06 1.83E-04, 7.00E+04 1.40E+09.60E+07 1.05E+09 1.21E+05 4.24E+04 2.06E+06 9.72E+07 2.79E+10 1.29E+04 6.10E+08 2.38E-02 9.15E+06 0.0.0.0.0.1.19E+06 1.25E+08 1.56E+02 4.23E+06 2.92E-04 1.11E+05 3.45E+08 4.78E+07 2.72E+08 2.88E+04 1.47E+04 8.43E+05 0.0.0.0.5.67E-03 1.69E+08 6.56E+06 1.40E+08 7.73E+04 0.6.55E+05 1.83E+07 1.84E+01 2.44E+06 1.60E-07 7.84E+04 1.61E+07 9.77E+06 1.41E+07 3.19E+08 1.15E+08 1.19E+09 3.00E+05 5.76E+07 3.47E+01 1.04E+06 6.56E-05 2.57E+04 6.52E+08 6.19E+07 3.70E+08 6.04E+06 4.86E+03 2.67E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition

~4'E 0~0 5~~0~rs~~~I I s~<<~~~I~a~~~~~~~0 s~~~s s~~g~~s~~~0 8~0 s~I~I I I I~~I I I I I I~~~~~e~~I 0 s~s~~a~~0~s~~I~~I~~~I~'I'I~'~I I I ar: II I~~I~~~<<I I~~I~I~~~I~'I I~I le I I~~'I~~I I~~I I~I I~~I~I~I I~I~~~I~~r I~~~I r I~I~I~I~~~I'I~I I I I~I I I I I II I~I I I~I I~~~~I~~I I~~~~I I~~~~~~~~~~0~-~~0~-~-I~~

ST.LUCIE PLANT-CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 200 of 225 TABLE G-18 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-INHALATION AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/YR PER pCI/CU.METER)NUCLIDE SN-123 SN-126 SB-124 BONE 2.42E+05 1.26E+06 3.12E+04 LIVER 5.33E+03 3.34E+04 5.89E+02 THYROID 4.53E+03 9.84E+03 7.55E+01 0.KIDNEY LUNG 2.30E+06 9.36E+06 2.48E+06 GI-LLI 3.14E+05 1.27E+05 4.06E+05 WHOLE BODY 7.86E+03 4.80E+04 1.24E+04 SB-125 6.61E+04 TE 125M 3.42E+03 TE 12?M 1.26E+04 TE 129M 9.76E+03 7.13E+02 1.58E+03 5.62E+03 4.67E+03 5.87E+01 1.05E+03 3.29E+03 3.44E+03 0.1.24E+04 4.58E+04 3.66E+04 2.20E+06 3.14E+05 9.60E+05 1.16E+06 1.01E+05 7.06E+04 1.50E+05 3.83E+05 1.33E+04 4.67E+02 1.57E+03 1.58E+03 I-130 I-131 I-132 I-133 1-134 1-135 CS-134'S-136 CS-137 BA-140 CE-141 CE-144 4.58E+03 2.52E+04 1.16E+03 8.64E+03 6.45E+02 2.69E+03 3.74E+05 3.91E+04 4.78E+05 3.90E+04 1.99E+04 3.43E+06 1.34E+04 3.58E+04 3.26E+03 1.49E+04 1.73E+03, 6.99E+03 8.48E+05 1.46E+05 6.22E+05 4.90E+01 1.35E+04 1.43E+06 1.74E+06 1.19E+07 4.38E+05 2.93E+06 2.30E+05 9.36E+05 0.0.0.0.0.0.2.09E+04 6.14E+04 5.19E+03 2.60E+04 2.75E+03 1.11E+04 2.88E+05 8.56E+04 2.22E+05 1.67E+01 6.26E+03 8.48E+05 0.0.0.0.0.0.9.?6E+04 1.20E+04 7.53E+04 1.27E+06 3.62E+05 7.78E+06 7.69E+03 6.28E+03 4.06E+02 8.72E+03 , 1.01E+00 5.25E+03 1.04E+04 1.17E+04 8.40E+03 2.18E+05 1.20E+05 8.16E+05 5.29E+03 2.05E+04 1~16E+03 4.54E+03 6.16E+02 2.58E+03 7.29E+05 1.11E+05 4.29E+05 2.57E+03 1.53E+03 1.84E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Page 201 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE G-19 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95 NB-95 RU-103 RU-106 AG110 0.BONE 1.71E+10 0.2.98E+07 0.0.0.1.37E+09 0.1.46E+09 4.70E+10 8.60E+03 3.18E+04 8.26E+04 1.02E+03 2.04E+04 5.84E+07 LIVER 9.73E+02 1.07E+09 0.8.41E+06 7.06E+07 1.28E+06 4.72E+06 1.65E+07 4.36E+09 2.60E+09 0.0., 0.1.75E+04.59E+04 0.0.5.40E+07 THYROID 9.73E+02 0.1.71E+04 0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.KIDNEY 9.73E+02 0.6.32E+03 2.50E+06 0.0.0.0.2.92E+09 0.0.0.0.1.75E+04 4.55E+04 3.91E+03 3.95E+04 1.06E+08 LUNG 9.73E+02 0.'.80E+04 0.1.96E+07 0.0.0.0.0.0.0.0.0.0.0.GI-LLI 9.73E+02 1.92E+09 7.20E+06 2.58E+07 2.33E+08 3.25E+07 9.56E+07 3.08E+08 2.75E+09 5.12E+08 2.33E+08 6.37E+08 4.73E+06 1.05E+08 2.79E+08 1.19E+05 1.32E+06 2.20E+10 WHOLE BODY 9.73E+02 6.62E+08 2.86E+04 1.61E+06 2.69E+07 2.13E+06 1.06E+07 3.62E+07 1.98E+09 1.21E+09 4.17E+07 1.15E+10 2.31E+02 6.95E+03.1.80E+04 4.41E+02 2.58E+03 3.21E+07 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 202 of 225 TABLE G-19 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE)AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 SN-126 SB-124 0.BONE 1.65E+09 2.58E+07 0.LIVER 3.27E+07 4.87E+05 THYROID 0.9.56E+06 6.24E+04 0.0.KIDNEY 0.LUNG 4.67E+06 2.00E+07 0.GI-LLI 1.09E+09 7.31E+08 WHOLE BODY 0.4.94E+07 1.02E+07 SB-125 TE 125M TE 127M TE 129M I-130 1-131 I-132 2.64E+07 1.63E+07 4.63E+07 6.06E+07 4.27E+05 2.96E+08 1.67E-01 6.06E+05 5.91E+06 1.63E+07 2.27E+07 1.26E+06 4.25E+08 4.47E-01 2.99E+05 4.91E+06 1.21E+07 2.09E+07 1.61E+08 1.39E+11 5.88E+01 3.72E+06 6.63E+07 1.88E+08 2.53E+08 1.96E+06 7.27E+08 7.12E-01 2.66E+09 0.0.0.0.2.29E+08 6.50E+07 2.11E+08 3.04E+08 1.08E+06 1.12E+08 8.39E-02 5.23E+06 2.18E+06 5.72E+06 9.61E+06 4.97E+05 2.43E+08 1.59E-01 I-133 4.00E+06 6.94E+06 1.33E+09 1.21E+07 0.6.10E+06'.12E+06 I-134 I-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 0.1.40E+04 5.66E+09 2.61E+08 7.39E+09 2.69E+07 2.91E+04 2.15E+06 0.3.70E+04 1.35E+10 1.03E+09 1.01E+10 3.38E+04 1.97E+04 8.97E+05 9.98E-10 4.84E+06 0.0.0.0.0.0.0.5.88E+04 4.36E+09 5.74E+08 3.44E+09 1.15E+04 9.13E+03 5.32E+05 0.7.58E-02 1.45E+09 7.87E+07 1.14E+09 1.93E+04 0.0.4.14E+04 2.36E+08 1.17E+08 1.95E+08 5.70E+07 7.52E+07 7.26E+08 0.1.36E+04 1.10E+10 7.43E+08 6.62E+09 1.78E+06 2.23E+03 1.15E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 203 of 225 TABLE G-20 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 0.BONE LIVER 1.99E+03 THYROID 1.99E+03 KIDNEY 1.99E+03 LUNG 1.99E+03 GI-LLI 1.99E+03 WHOLE BODY 1.99E+03 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95'B-95 RU-103 RU-106 AG110 2.05E+10 0.0.3.87E+05 0.0.0.1.65E+08 0.3.06E+09 9.87E+10 1.03E+03 3.82E+03 9.92E+03 1.23E+02 2.45E+03 7.00E+06 1.29E+09 0.1.01E+06 9.18E+05 1.54E+05 5.67E+05 1.98E+06 5.24E+08 3.12E+08 0.0.0.2.10E+03.51E+03 0.0.6.48E+06 0.2.05E+03 0.0.0.0.0.0.0.0.0.0.0.0.0.0.7.58E+02 3.00E+05 0.0.3.50E+08 0.0.0.2.10E+03 5.46E+03 4.69E+02 4.73E+03 1.27E+07 0.4.56E+03 0.2.55E+05 0.0.0.0.0.0.0.0.0.2.31E+09 8.64E+05 3.09E+06 3.03E+06 3.90E+06 1.15E+07 3.70E+07 3.30E+08 6.15E+07 4.89E+08 1.32E+09 5.68E+05 1.26E+07 3.34E+07 1.43E+04 1.58E+05 2.64E+09 7.94E+08 3.43E+03 1.93E+05 3.50E+05 2.55E+05 1.27E+06 4.34E+06 2.37E+08 1.45E+08 8.76E+07 2.41E+10 2.77E+01 8.34E+02 2.17E+03 5.30E+01 3.10E+02 3.85E+06 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 204 of 225 TABLE G-20 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (CONTAMINATED FORAGE)AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 0.BONE 0.LIVER THYROID 0.0.KIDNEY 0.LUNG 0.GI-LLI WHOLE BODY 0.SN-126 SB-124 SB-125 TE 125M TE 127M TE 129M I-130 l-131 I-132 I-133 I-134 1-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 1.97E+08 3.10E+06 3.16E+06 1.96E+06 5.57E+06 7.27E+06 5.12E+05 3.56E+08 2.00E-01 4.80E+06 0.1.68E+04 1.70E+10 7.84E+08 2.22E+10 3.23E+06 3.49E+03 2.58E+05 3.92E+06 5.85E+04 7.28E+04 7.10E+05 1.94E+06 2.72E+06 1.52E+06 5.10E+08 5.36E-01 8.32E+06 0.4.44E+04 4.04E+10.09E+09 3.03E+10 4.05E+03 2.36E+03 1.08E+05 1.15E+06 7.49E+03 3.58E+04 5.89E+05 1.47E+06 2.51E+06 1.93E+08 1.67E+11 7.06E+01 1.60E+09 1.20E-09 5.80E+06 0.0.0.0.0.0.0.0.4.47E+05 7.95E+06 2.26E+07 3.04E+07 2.36E+06 8.72E+08 8.55E-01 1.45E+07 7.05E+04 1.31E+10 1.72E+09 1.03E+10 1.38E+03 1.10E+03 6.39E+04 5.61 E+05 2.40E+06 3.19E+08 0.0.0.0.0.0.0.0.2.28E-01 4.34E+09 2.36E+08 3.42E+09 2.32E+03 0.1.31E+08 8.77E+07 2.74E+07 7.81E+06 2.52E+07 3.65E+07 1.30E+06 1.34E+08 1.01E-01 7.32E+06 0.4.97E+04 7.06E+08 3.52E+08 5.83E+08 6.84E+06 9.02E+06 8.71E+07 5.92E+06 1.22Et06 6.29E+05 2.62Et05 6.86E+05 1.15E+06 5.96E+05 2.92E+08 1.91E-01 2.54E+06 1.63E+04 3.30E+10 2.23E+09 1.99E+10 2.13E+05 2.68E+02: 1.38Et04 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter) 0 4"~

P~P P~~~P P~~P a~0 II a r~~~I~~~~~~~~0 0~P~~~~)~P~~o~1 P~P~~~a~~r~~l~l~l~~o~~I~l~I~l~~I~I I~~~~l~I~o~l~l~l l~l~l~~~I~~l~~~l~I I~I~l~l~l~p o~P~~P~~P~P~o~e l P I l~~I~~I~I I~I'o~I l'~~~l~~I~I I~l I~l~~l~ll l~~~I~l~~~l~o I I'~~~~~~~l~I~l~I~I~P~~~~~~~~-~--~0~--~-~~~

ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 206 of 225 TABLE G-21 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-MEAT (CONTAMINATED FORAGE)AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE SN-123 0.BONE 0.LIVER THYROID 0.0.KIDNEY 0.LUNG 0.GI-LLI WHOLE BODY 0.SN-126 SB-124 SB-125 1.86E+10 1.99E+07 6.65E+07 TE 125M 3.59E+08 TE 127M 1.13E+09 3.69E+08 3.75E+05 1.58E+07 1.30E+08 3.93E+08 1.08E+08 4.80E+04 1.29E+07 1.08E+08 2.96E+08 0.0.1.74E+08 1.46E+09 4.56E+09 6A6E+06 1.54E+07 2.49E+09 0.0.6.19E+09 5.62E+08 3.80E+08 1.43E+09 5.11E+09 5.33E+08 7.85E+06 1.05E+07 4.81E+07 1.39E+08 TE 129M I-130 I-131 I-132 I-133 I-134 1-135 CS-134'S-136 CS-137 BA-140 CE-141 CE-144 1.14E+09 2.38E-06 1.08E+07 0.4.40E-01 0.8.60E-02 6.58E+08 1~18E+07 8.73E+08 2.88E+07 1.41E+04 1.46E+06 4.29E+08 7.05E-06 1.55E+07 0.7.63E-01 0.7.94E-02 1.57E+09.67E+07 1.19E+09 3.63E+04 9.52E+03 6.10E+05 3.95E+08 8.96E-04 5.06E+09 0.1.47E+02 0.0.0.0.0.0.0.0.4.79E+09 1.10E-05 2.65E+07 0.1.33E+00 0.3.01E-02 5.08E+08 2.60E+07 4.06E+08 1.23E+04 4.41E+03 3.62E+05 0.0.0.0.0.9.04E-03 1.68E+08 3.56E+06~1.35E+08 2.07E+04 0.0.5.76E+09 6.04E-06 4.07E+06 0.6.71E-01 0.1.86E-03 2.74E+07 5.31E+06 2.30E+07 6.87E+07 3.63E+07 4.93E+08 1.82E+08 2.77E-06 8.85E+06 0.2.33E-01 0.3.53E-02 1.28E+09 3.36E+07 7.82E+08 1.90E+06 1.08E+03 7.83E+04 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Note-the units for C--14 and H--3 are (mrem/yr per pCi/cu.meter)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 207 of 225 TABLE G-22 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCI/SEC)NUCLIDE H--3 P--32 CR-51 MN-54 FE-59 CO-57 CO-58 CO-60 ZN-65 RB-86 SR-89 SR-90 Y--91 ZR-95'B-95 RU-103 RU-106 AG110 0.BONE 1.04E+09 0.0.3.64E+07 0.0.0.5.11E+07 0.2.67E+09 8.49E+10 1.26E+06 2.93E+05 4.87E+04 1.50E+06 2.95E+07 1.69E+06 LIVER 4.02E+02'.51E+07 0.4.87E+07 8.64E+07 1.85E+06 6.89E+06 2.38E+07 1.62E+08 1.30E+08 0.0.0.-9.82E+04.71E+04 0.0.1.56E+06 THYROID 4.02E+02 0.1.15E+04 0.0.0.0.0.0.0.0.0.0.0.0.0.KIDNEY, 4.02E+02 0.4.25E+03 1.45E+07 0.0.0.0.1.09E+08 0.0.0.1.49E+05 2.68E+04 5.75E+06 5.71E+07 3.08E+06 LUNG 4.02E+02 0.'.56E+04 0.2.40E+07 0.0.0.0.0.0.0.0.0.0.0.0.0.Gl-LLI 4.02E+02 1.17E+08 4.85E+06 1.49E+08 2.85E+08 4.70E+07 1.40E+08 4.46E+08 1.02E+08 2.56E+07 4.26E+08 2.14E+09 6.92E+08 3.34E+08 1.64E+08 1.76E+08 1.91E+09 6.38E+08 WHOLE BODY 4.02E+02 4.02E+07 1.93E+04 9.31E+06 3.29E+07 3.08E+06 1.54E+07 5.23E+07 7.34E+07 6.06E+07 7.64E+07 2.07E+10 3.37E+04 6.38E+04.1.06E+04 6.49E+05 3.74E+06 9.30E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition ST.LUCIE PLANT'HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 208 of 225 TABLE G-22 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY-FRESH FRUITS AND VEGETABLES AGE GROUP-ADULT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER.pCI/SEC)NUCLIDE SN-123 SN-126 BONE 1.00E-05 9.52E+08 LIVER 1.66E-07 1.89E+07 THYROID 1.41E-07 5.54E+06 0.0.KIDNEY LUNG 0.4.3'1 E+06 Gl-LLI 2.04E-05 8.46E+08 WHOLE BODY 2.45E-07 2.94E+07 SB-124 SB-125 TE 125M TE 127M TE 129M I-130 I-131 I-132 I-133 l-134 l-135 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 2.52E+07 2.58E+07 2.38E+07 6.75E+07 8.93E+07 3.93E+05 7.78E+07 5.57E+01 2.13E+06 1.03E-04 4.04E+04 6.82E+08 3.32E+07 8.90E+08 1.03E+08 7.16E+04 5.19E+06 4.75E+05 7.23E+05 8.65E+06 2.36E+07 3.34E+07 1.16E+06 1.12E+08 1.49E+02 3.69E+06 2.79E-04'.07E+05 1.62E+09 1.31E+08 1.22E+09 1.35E+05 4.85E+04 2.17E+06 6.08E+04 4.03E+05 7.17E+06 1.77E+07 3.08E+07 1.48E+08 3.65E+10 1.96E+04 7.10E+08 3.63E-02 1.40E+07 0.0.0.0.0.5.14E+06 9.69E+07 2.73E+08 3.73E+08 1.81E+06 1.91E+08 2.38E+02 6.44E+06 4.45E-04 1.70E+05 5.26E+08 7.29E+07 4.14E+08 4.39E+04 2.25E+04 1.29E+06 1.95E+07 2.56E+09 0.0.0.0.0.8.65E-03 1.74E+08 9.99E+06 1.37E+08 7.38E+04 0.7.12E+08 2.22E+08 9.51E+07 3.06E+08 4.49E+08 9.98E+05 2.94E+07 2.80E+01 3.24E+06 2.43E-07 1.19E+05 2.84E+07 1.49E+07 2.34E+07 6.65E+08 1.85E+08 1.75E+09 9.94E+06 5.10E+06 3.19E+06 8.32E+06 1.42E+07 4.58E+05 6.38E+07 5.29E+01 1.13E+06 9.99E-05 3.91E+04 1.33E+09 9.43E+07 7.98E+08 6.77E+06 5.49E+03 2.78E+05 Based on 1 pCi/sec release rate of each isotope in and a value of 1.for X/Q, depleted X/Q and relative deposition Page 209 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM'TABLE M-1 Selecting the Appropriate Long Term (X/Q)for Dose Calculations Involving Noble Gases for: (1)Total Body dose from instantaneous releases (2)Skin dose from instantaneous releases (3)Gamma air dose (cumulative)

(4)Beta air dose (cumulative)

TYPE OF DOSE CALCULATION Instantaneous 1/31 days LIMITING RANGE (miles)0.97 0.97 LIMITING Sector NW (X/Q)VALUE sec/m'.6 X 10 Quarterly Yearly 12 Consecutive months 0.97 0.97 1.Normally (X/Q)=1.6 X 10~sec/m'.May use option of actual meteorological data for time of concern.Annual Report 0.97 N/A Note-1 NOTE 1 The (X/Q)has to be calculated based on actual meteorological data that occurred during the period of interest.The sectoF of interest is N/A because the limiting (X/Q)will be determined from the actual meteorological data and may occur in any sector.0.97 miles Corresponds to the minimum site boundary distance in the north direction and 0.97 miles was chosen for all other sectors for ease of calculations-when the averaging is done for quarterly reports.

Page 210 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE M-2 Selecting the Appropriate Long Term (X/Q)o or (D/Q)for Dose Calculations Involving Radioiodines

&8 D Particulates for: (1)Inhalation (2)Tritium (All gas pathways)(3)Ground Plane TYPE OF DOSE CALCULATION Instantaneous Annual Report 1/31 days, Qtr.yearly, Annual Total Dose LIMITING RANGE (miles)0.97 0.97 0.97 0.97 0.97 LIMITING SECTOR (OL)NW WNW NW WNW (X/Q)sec/m'1.3 X 10 A,B B 1.3 X 10 (D/Q)1/m'.2 X 10'v v 8.2 X 10 (OL)Over land areas only (A)To be determined by reduction of actual met data occurring during each quarter (B)For Tritium in the Milk Animal Pathway, the (X/Q)o value should be that of the respective controlling sector and range where the Milk Animal is located as per Table M-3.Example: If a cow was located at 4.25 miles in NW sector, use the (X/Q)o for 4.25 miles NW.

Page 211 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE M-3 Selecting the Appropriate Long Term (D/Q)for Dose Calculations Involving Radioiodines and SD Particulates for Grass-Cow-Milk or Grass-Goat-Milk:

TYPE OF DOSE CALCULATION Release Rate-1/31 Days Quarterly-Yearly Annual (Calendar Year)Annual Report LIMITING RANGE B LIMITING SECTOR (D/Q)Value 1/m~A.The worst cow or goat as per locations from land census.If no milk animal in any sector, assume a cow at 4.25 miles in the highest (D/Q)sector over land.B.The historical (D/Q)of all land sectors with the worst cow or goat from each sector as reported in the Land Census.A 4.25 mile cow should be assumed in the worst sector over land when no milk animal is reported.C.The highest (D/Q)at a milk animal location of all milk animals reported in the Land Census Report.(If no milk animals within 5 miles a 4.25 mile cow should be assumed in the sector having the highest (D/Q)at 4.25 miles over land).Actual Met Data should be used for the selection of the worst case milk animal and for the dose calculations.

If both goat and milk animals are reported inside 5 miles, dose calculations should be performed on each animal and the higher dose animal contribution should be used.The historical wind frequency fractions for each sector are listed in Table M-8.

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE M-4 TERRAIN CORRECTION FACTORS Page 212 of 225 Florida Power 8 Light Company St.Lucie Unit 1 Hutchinson Island, Florida Dames and Moore Job No: 4598-112 Terrain Correction Factors (PUFF/STRAIGHT LINE)Period of Record: 8/29/77 to 8/31/78 Base Distance in Miles/Kilometers AFFECTED SECTOR DESIGN DISTANCE MILES.25.40.75 1.21 1.25 2.01 1.75 2.82 2.25 3.62 2.75 4.42 3.25 5.23 3.75 6.03 4.25 4.75 6.84 7.64 NNE NE ENE ESE SE SSE SSW SW WSW W WNW NW NNW 0.0.0.0.0.0.0.0.0.0.0.1.906 1.576 1.887 1.581 1.452 1.230 1.662 1.425 1.690 1.483 1.818 1.691 1.812 1.586 1.398 1.321 1.534'.411 1.685 1.492 1.0 1.333 1.6 1 1.415 1.720 1.430 1.681 1.407 1.739 1.488 1.816 1.524 1.465 1.404 1.338 1 461 1.391 1.310 1.122 1.081 1.047 1.277 1.193 1.151 1.328 1.260 1.246 1.470 1.427 1.435 , 1.370 1.302 1.270 1.125 1.083 1.108 1.296 1.192 1.205 1.294 1.233 1.200 1.210 1.173 1.082 1.290 1.218 1.154 1.267 1.185 1.150 1.257 1.173 1.119 1.316 1.212 1.172 1.389 1.285 1.257 1.318 1.334 1.259 1.164 1.033.941 1.123 1.097 1.190 1.134 1.36 I 1.366 1.263 1.229 1.127 1.073 1.132 1.135 1.222 1.160 1.091 1.099 1.099 1.081 1.133 1.125 1.078 1.063 1.122 1.135 1.263 1.285.941.906.902 1.121 1.123 1.122 1.094 1.032.968 1.331 1.279 1.239 1.193 1.171 1;151 1.063 1.047 1.024 1.116 1.077 1.060 1.160 1.198 1.196 1.056 1.034 1.004 1.067 1.093 1.083 1.085 1.033 1.045.995.998.978 1.080 1.099 1.091 1.267 1.231 1.213 1.386 1.346 1.338 1.128 1.101 1.116 Note 1: Any interpolations between stated mileages will be done by Iog-log ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 213 of 225 TABLE M-5 HISTORICAL LONG TERM-X/Q Fre uenc corrected Terrain/Recirculation Adjusted Program ANNXOQ9 Version-11/18/76 Florida Power 8 Light Company St.Lucie Unit 1 Hutchinson Island, Florida Dames and Moore Job No: 1.4598-112 Average Annual Relative Concentration (sec/cubic meter)Period of Record: 9/1/76 to 8/31/78 Base Distance in Miles/Kilometers AFFECTED SECTOR DESIGN DISTANCE MILES.25.40.75 1.21 1.25 2.01 1.75 2.82 2.25 3.62 2.75 4.42 3.25 5.23 3.75 6.03 4.25 6.84 4.75 7.64 NE ENE ESE SE SSE SSW'SW Wsw W WNW Nw NNW 0.0.0.0.0.0.0.0.1.1E-05 1.7E-06 1.3E-05 2.1E-06 9.3E-06 1AE-06 9.8E-06 1.6E-06 1.2E-05 1.9E-06 1.4E-OS 2.4E-06 1.1E-05 1.?E-06 6.2E-06 1.0E-06 5.7E-06 9.0E-07 6.1E-06 9.4E-07 7.3E-06 1.1E-06 7.6E-06 1.2E-06 1.4E-05 2.1E-06 1.6E-05 2.4E-06 1.5E-OS 2.2E-06 9.1E-06 1.4E-06 7.8E-07 8.9E-07 6.2E-07 6.5E-07 8.1E-07 9.7E-07 i 7.3E-07 4.2E-07 4.0E-07 3.9E-07 4.6E-07 5.2E-07 9.1E-07 1.0E-06 9.6E-07 6.3E-07 4.5E-07 5.1E-07 3.7E-07 3.7E-07 4.8E-07 5.7E-07 4.3E-07 2.5E-07 2.3E-07 2.2E-07 2.7E-07 2.9E-07 5.2E-07 5.9E-07 5.5E-07 3.6E-07 3.1E-07 3.4E-07 2.5E-07 2.5E-07 3.2E-07 4.0E-07 2.9E-07 1.8E-07 1.6E-07 1.6E-07 1.7E-07 2.0E-07 3.4E-07 3.9E-07 3.6E-07 2.4E-07 2.2E-07 1.7E-07 2.4E-07 1.7E-07 1.9E-07 1.3E-07 1.8E-07 1.4E-07 2.4E-07 1.8E-07 2.9E-07 2.3E-07 2.1E-07 1.6E-07 1.4E-07 1.0E-07 1.1E-07 8.9E-OB 1.1E-07 8.6E-OB 1.3E-07 1.0E-07 1.3E-07 1.0E-07 2.6E-07 2.0E-07 2.8E-07 2.1E-07 2.6E-07 2.0E-07 1.8E-07 1.4E-07 1.5E-07 1.2E-07 1.4E-07 1.1E-07 1.1E.07 B.BE-OB 1.2E-07 9.9E-OB 1.4E-07 1.1E-07 1.9E-07 1.4E-07 1.3E-07 1.1E-07 B.OE-OB 6.6E-OB 7.0E-OB 5.7E-OB 7.0E-OB 6.0E-OB B.OE-OB 6.5E.OB 8.4E.OB 7.2E-OB 1.5E-07 1.2E-07 1.7E-07 1 AE-07 1.6E-07 1.3E-07 1.2E-07 9.4E-OB 1.0E.07 9.8E-OB 7.5E-OB BAE-08 9.0E.OB 1.2E-07 9.1E-OB 5.5E-OB 4.8E.OB 5.1E-OB 5AE-08 6.1E-OB 1.0E-07 1.2E.07 1.2E.07 7.9E-OB Number of Valid Observations

=17135 Number of Calms Lower Level=95 Number of Invalid Observations

=385 Number of Calms Upper Level=0 Note 1-Any interpolations between stated mileages will be done by log-log

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 214 of 225 TABLE M-6 HISTORICAL LONG TERM DEPLETED-X/Q Fre uenc corrected Terrain/Recirculation Adjusted Program ANNXOQ9 Version-11/18/76 Florida Power 8 Light Company St.Lucie Unit 1 meter)Hutchinson Island, Florida Dames and Moore Job No: 4598-112 Average Annual Relative Concentration Depleted (sec/cubic Period of Record: 9/1/76 to 8/31/78 Base Distance in Miles/Kilometers AFFECTED SECTOR DESIGN DISTANCE MILES.25.40.75 1.21 1.25 2.01 1.75 2.82 2.25 3.62 2.75 4.42 3.25 5.23 3.75 6.03 4.25 6.84 4.75 7.64 ENE ESE SE SSE Ssw'Sw WSW W WNW NW NNW 0.0.0.0.0.0.0.0.0.0.0.1.1E-05 1.6E-06 6.6E-07 1.2E-05 1.7E-06 7.6E-07 8.9E-06 1.2E-06 5.3E-07 9.1E-06 1.3E-06 5.6E-07 1.2E-05 1.6E-OB 6.9E-07 1.3E-05 2.0E-06 8.2E-07 1.1E-05 1,6E-06 I 6.3E-07 5.9E-06 9.1E-07 3.6E-07 5.4E-06 B.OE-07 3.4E-07 5.7E-06 8.4E-07 3.4E-07 7.0E-06 9.6E-07 4.0E-07 7.3E-06 1.1E-06 4.4E-07 1.3E-OS 1.9E-06 7.9E-07 1.5E-05 2.1E-06 8.9E-07 1.4E-05 2.1E-OB 8.3E-07 8.7E-06 1.3E-06 5.4E-07 3.8E-07 4.3E-07 3.0E-07 3.1E-07 3.9E-07 4.7E-07 3.5E-07 2.1E-07 1.9E-07 1.8E-07 2.2E-07 2.4E-07 4.4E-07 4.9E-07 4.5E-07 3.0E-07 2.4E-07 2.8E-07 2.0E-07 2.1E-07 2.6E-07 3.3E-07 2.4E-07 1.4E-07 1.3E-07 1.2E-07 1.4E-07 1.6E-07 2.9E-07 3.1E-07 2.9E-07 2.0E-07 1.4E-07 1.0E-07 1.5E-07 1.1E-07 1.9E-07 1.4E-07 2.3E-07 1.8E-07 1.8E-07 1.4E-07 1.1E-07 7.7E-OB 8.9E-OB 6.9E-OB 9.2E-OB 6.7E-OB 1.0E-07 B.OE-OB 1.1E-07 8.2E-OB 2.0E-07 1.6E-07 2.3E-07 1.7E-07 2.0E-07 1.6E-07 1 4E-07 1.1E-07 1.7E-07 1.3E-07 1.9E-07 1.4E-07 1.1E-07 9.2E-OB 1.1E-07 8.6E-OB 8.4E-OB 6.6E-OB 9.1E-OB 7.5E-OB 1.1E-07 8.5E-OB 1.3E-07 1.1E-07 1.0E-07 8.2E-OB 6.2E-OB 5.0E-OB 5.5E-OB 4.3E-OB 5.3E-OB 4.6E-OB 6.1E-OB 5.0E-OB 6.4E-OB 5.5E-OB 1.2E-07 9.3E-OB 1.3E-07 1.0E-07 1.2E.07 1.0E-07 8.9E.OB 7.0E-OB 7.6E-OB 7.4E-OB 5.6E-OB 6.3E.OB 6.7E-OB 9.0E.OB 6.8E-OB 4.1E-OB 3.6E-OB 3.8E-OB 4.0E-OB 4.4E.OB 7.8E-OB 8.5E-OB 8.6E.OB 5.8E-OB Number of Valid Observations

=17135 Number of Calms Lower Level=95 Number of Invalid Observations

=385 Number of Calms Upper Level=0 Note 1-Any interpolations between stated mileages will be done by Iog-log ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 215 of 225 TABLE M-7 HISTORICAL LONG TERM-D/Q Fre uenc corrected TERRAIN/RECIRCULATION ADJUSTED PROGRAM ANNXOQ9 VERSION-11/1 8/76 Florida Power&Light Company St.Lucie Unit 1 Hutchinson Island, Florida Dames and Moore Job No: 4598-112 Average Annual Relative Deposition Rate (square meter-1)Period of Record: 9/1/76 to 8/31/78 Base Distance in Miles/Kilometers.

AFFECTED SECTOR DESIGN DISTANCE MILES.25 AO.75 1.21 1.25 2.01 1.75 2.82 2.25 3.62 2.75 4A2 3.25 5.23 3.75 6.03 4.25 6.84 4.75 7.64 NNE NE ENE ESE SE SSE SSW Sw Wsw W WNW NNW 0.0.0.0.0.0.0.0.0.0.0.6.5E-OB 6.0E-OB 3.2E-OB 3.0E-OB 3.7E-OB 6.4E-OB 6.2E-OB 4.2E-OB 3.4E-OB 4.5E-OB 5.3E-OB 5.0E-OB B.BE-OB 8.2E-OB 8.2E-OB 5.1E-OB 9.3E-09 8.9E-09 4.8E-09 4.6E-09 5.8E-09 1.0E-OB 9.5E-09 7.0E-09 5.4E-09 7.0E-09 7.7E-09 7.5E-09 1.3E-OB 1.2E-OB 1.2E-OB 7.3E-09 3.7E-09 3.5E-09 1.9E-09 1.8E-09 2.3E-09 4.0E-09 3.6E-09 i 2.6E-09 2.2E-09 2.6E-09 3.0E-09 3.0E-09 4.9E-09 4.7E-09 4.6E-09 2.9E-09 2.1E-09 1.9E-09 1.0E-09 9.5E-10 1.2E-09 2.1E-09 2.0E-09 1AE-09 1.1E-09 1.5E-09 1.6E-09 1.6E-09 2.6E-09 2.5E-09 2.4E-09 1.5E-09 1.3E-09 9.0E-10 1.2E-09 8.1E-10 6.6E-10 4.6E-10 6.0E-10 4.2E-10 B.OE-10 5AE-10 1.4E-09 9.7E-10 1.2E-09 8.7E-10 9.5E-10 6.9E-10 7.5E-10 5.0E-10 9.0E-10 6.6E-10 1.0E-09 7.3E-10 9.8E-10 6.7E-10 1.7E-09 1.1E-09 1.6E-09 1.1E-09 1.5E-09 1.1E-09 9.8E-10 7.1E-10 6.8E-10 5.5E-10 5.6E-10 4.3E-10 3.2E-10 2.4E-10 3.1E-10 2.5E-10 3.9E-10 3.0E-10 7.2E-10 5.6E-10 6.4E-10 4.9E-10 4.9E-10 3.8E-10 3.7E-10 2.9E-10 4.6E-10 3.6E-10 5.5E-10 4.1E-10 5.0E-10 3.8E-10 8.7E-10 6.6E-10 7.9E-10 5.8E-10 8.1E-10 5.9E-10 5AE-10 4.2E-10 4.3E-10 3.5E-10 3.3E-10 2.8E-10 1.9E-10 1.5E-10 2.0E-10 1.6E-10 2.2E-10 1.7E-10 4.3E-10 3.5E-10 3.9E-10 3.1E-10 3.0E-10 2.5E-10 2.3E-10 1.8E-10 3.0E-10 2.5E-10 3.3E-10 2.6E-10 3.2E-10'.6E-10 5.1E-10 4.2E-10 4.7E-10 3.8E-10 4.8E-10 4.0E-10 3.2E-10 2.7E-10 4 Number of Valid Observations

=17135 Number of Calms Lower Level=95 Number of Invalid Observations

=385 Number of Calms Upper Level=0 Note 1-Any interpolations between stated mileages will be done by log-log

Page 216 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION'20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE M-8 Joint Wind Frequency Distribution Data Period: September 1, 1976-August 31, 1978 All Winds St.Lucie Unit 2 Data Source: On-Site Hutchinson Island, Florida Wind Sensor Height 10.00 Meters Florida Power&Light Co.Table Generated:

12/05/78.07.42.18.Dames and Moore Job No: 4598-112-27 Wind Speed Categories (Meters per Second)WIND SECTOR NNE ENE ESE SE SSE SSW SW WSW W WNW NW NNW CALM TOTAL 0.0-1.5 71.43 62 38 60.36 69.42 115.70 183 1.11 129.78 72 84.51 129.78 155.94 174 1.05 203 1.23 143.87 85.51 91.55 95.57 1920 11.62 1.5-3.0 206 1.25 292 1.77 334 2.02 355 2.15 684 4.14 660 3.99 579 3.50 310 1.88 372 2.25 440 2.66 320 1.94 267 1.62 304 1.84 518 3.14 379 2.29 194 1.17 6214 37.61 3.0-5.0$18 1.92 385 2.33 505 3.06 510 3.09 744 4.50 749 4.53 656 3.97 407 2.46 446 2.70 336 2.03 186 1.13 119.72 172 1.04 424 2.57 535 3.24 531 3.21 7023 42.51 5.0-7.5 71.43 128 158.96 76.46 72 28.17 93.56 99.60 105 106.64 29.18 37 17 10 50.30 70.42 148.90 1287 7.79 7.5-10.0 3 02 0 0.00 0 0.00 0 0.00 1 01 0 0.00 1 01 8 05 33.20 14 08 5 03 2 01 0 0.00 0 0.00 1 01 5.03 73)10.0 0 0.00 0 0.00 0 0.00 0 0.00 0 0.00 0 0.00 0 0.00 1.01 4 02 0 0.00 0~600 0 0.00 0 0.00 0 0.00 0 0.00 0 0.00 5.03 TOTAL'69 4.05 867 5.25 1057 6.40 1010 6.11 1616 9.78 1620 9.81 1458 8.82 897 5.43 1044 6.32 1025 6.20 695 4.21 599 3.63 696 4.21 1135 6.87 1070 6.46 969 5.86 95.57 16522 100.00 MEAN SPEED 3.32 3.43 3.51 3.25 2.88 3.10 3.36 3.48 3.10 2.59 2.43 3.69 CALM 3.10 NUMBER OF VALID OBSERVATIONS 16522 94.30 PCT.Key NUMBER OF INVALID OBSERVATIONS 988 5.70 PCT.TOTAL NUMBER-OF OBSERVATIONS 17520 100.00 PCT.'Totals below are given in hours 8 percent for wind frequency by sectors XXX Number of Occurrences XXX Percent Occurrences ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 217 of 225 APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE ST.LUCIE PLANT Key to Sample Locations PATHWAY Direct Radiation LOCATION N-1 DESCRIPTION North of Blind Creek SAMPLES COLLECTED TLD SAMPLE APPROXIMATE COLLECTION DISTANCE FREQUENCY (miles)<Quarterly DIRECTION SECTOR Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation NNW-5 South of Pete Stone Creek NNW-10 C.G.Station NW-5 Indian River Drive at Rio Vista Drive NW-10 Intersection of SR 68 and SR 607 WNW-2 Cemetery South of 7107 Indian River Drive WNW-5 US-1 at SR 712 WNW-10 SR 70, West of Turnpike TLD TLD TLD TLD TLD TLD TLD Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 10 10 NNW NNW NW NW WNW WNW WNW Direct Radiation W-2 7609 Indian River Drive TLD Quarterly W Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation W-5 Oleander and Sager Streets W-10 l-95 and SR 709 WSW-2 8503 Indian River, Drive WSW-5 Prima Vista Blvd.at Yacht Club WSW-10 Del Rlo and Davis Streets SW-2 9207 dian River Drive SW-5 US 1 a d Village Green Drive SW-10 Port St.Lucie Blvd.and Cairo Road SSW-2 10307 indian River Drive TLD TLD TLD TLD TLD TLD TLD TLD TLD Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 10 10 W W WSW WSW WSW SW SW SW SSW ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 218 of 225 APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (continued)

ST.LUCIE PLANT Key to Sample Locations PATHWAY Direct Radiation Direct Radiation Direct Radiation LOCATION SSW-5 SSW-10 S-5 DESCRIPTION Port St.Lucie Blvd.and US 1 Pine Valley and Westmoreland Roads 13179 Indian River Drive SAMPLES COLLECTED TLD TLD TLD SAMPLE COLLECTION FREQUENCY Quarterly Quarterly Quarterly APPROXIMATE DIRECTION DISTANCE SECTOR (miles)SSW SSW Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiation Airborne Airborne Airborne Airborne S-10 S/SSE-10 SSE-5 SSE-10 SE-1 H-32 H08'H12 H14 H30 US 1 and SR 714 Indian River Drive and Quail Run Lane Entrance of Nettles Island Elllot Museum South of Cooling Canal U.of Florida-1FAS Entomology Lab Vero Beach FPL Substation

-~Weatherby Road FPL Substation

-SR 76, Stuart Onsite-near south property line Power Line-7609 Indian River Drive TLD TLD TLD TLD TLD TLD Radioiodine 8 Particulates Radioiodine

&Particulates Radioiodine

&Particulates Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Weekly Weekly Weekly Weekly 10 10 10 19 12 SSE SSE SSE SE NNW WNW SE W'Denotes Control Sample ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM Page 219 of 225 APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (continued)

ST.LUCIE PLANT Key to Sample Locations PATHWAY LOCATION DESCRIPTION SAMPLES COLLECTED SAMPLE APPROXIMAT COLLECTION E DISTANCE FREQUENCY (miles)DIRECTION SECTOR Airborne Waterborne H34 H15 Onsite-At Meteorological Tower Radioiodine 8 Particulates Surface Water Atlantic Ocean vicinity of public beaches east side (ocean)of Route A1A Sediment from shoreline Weekly Weekly Semi-Annually 0.5 ENE/E/ESE Waterborne

'H59 Near south end of Hutchinson Island Surface Water (ocean)Sediment from shoreline Monthly Semi-Annually 10-20 S/SSE Food Products H15 Ocean side vicinity of St.Lucie Plant (NOTE 1)Crustacea Fish Semi-Annually Semi-Annually ENE/E/ESE Food Products H51 Offsite near north property line Broad Leaf vegetation (mangrove)

Monthly (when available)

N/NNW'Denotes control sample ST.LUCIE PLANT.CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (continued)

ST.LUCIE PLANT Key to Sample Locations Page 220 of 225 PATHWAY LOCATION DESCRIPTION SAMPLES COLLECTED SAMPLE APPROXIMAT COLLECTION E DISTANCE ,FREQUENCY (miles)DIRECTION SECTOR Food Products Food Products H52'H59 Offsite near south property line Near south end of Hutchinson Island Broad leaf vegetation (mangrove)

Crustacea Fish Broad leaf vegetation (mangrove)

Monthly (when available)

Semi-Annually Semi-Annually Monthly$0-20 S/SSE S/SSE'Denotes control sample It is the policy of Florida Power&Light Company (FPL)that the St.Lucie 1&2 Radiological Environmental Monitoring Programs are conducted by the State of Flqrida Department of Health and Rehabilitative Services (DHRS), pursuant to an Agreement between FPL and DHRS and;that coordination of the Radiological Environmental Monitoring Programs with DHRS and compliance with the Radiological Environmental Monitoring Program Controls are the responsibility of the Nuclear Energy Services Depart nt.NOTE 1 These samples may be collected from or supplemented by samples collected from the plant intake canal if the required analyses are unable to be performed due to unavailability or inadequate quantity of sample from the ocean side location.

Page 221 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM FIGuRE 1-1 SITE AREA MAP Bc ENVIRONMENTAL SAMPLE LOCATIONS C5 4 O~N-1 H51 CC LLI 0 IZ WNW-2 Z z'R o.e,+~O CREE~i~-EXCLUSION AREA (0.97 mi)ANO LOW W.2 POPULATION ZONE (1 mi)+NOTES: 1)L-Uquid Radwaste Release Poi nt 2)Due to the scale of the Figure the Exclusion Area Radius (0.97 mile)and the Low Population Zone (1 mile)area shown as being tho same size.UNIT 1 UNIT 2+e Al SE-H15....L FPL's Property~Une H14 O z.'SW-2 H52 SCALE IN MILES (C-ZOOA.WPG)

Page 222 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCUIATION MANUAL ODCM FIGURE 1-2 ENVIRONMENTAL SAMPLE LOCATIONS 10 MILES NW 10-H32 Veto Beach (Control)10 rrtrlea NNW-1 0 WNW.10 EOF W-1 SW-WSW 5 W~.10)SSW SSE S10 SW.10 S/SSE-1 0 SSE-1 0 H59 SSW-10 H12 fC.200B.WPC)

Page 223 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX C METEOROLOGICAL DISPERSION FORMULAS'or X/Q: X/Q-(u)D 2.032 (a~)2 cV~z 1t EQ (1)2.032 z (u)D EQ (2)Where: C V (u)=.5=207.5 ft.(63.2 meters)=a name for one term X/Q was calculated using each of the above EQs for each hour.The highest X/Q from EQ (1)or EQ (2)was selected.The total integrated relative concentration at each sector and distance was then divided by the total number of hours tn the data base.Terrain correction factors given by Table M-4 were also applied to Dispersion Formulas Page 224 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX C METEOROLOGICAL DISPERSION FORMULAS'continued)

For De leted X/Q: (X/Q)~=(X/Q)X (Depletion factor of Figure 2 of R.G.1.111-R1)~FO DIQ: D/Q=RDep/(2 sin[11.25]X)X (Freq.distribution)

Where: D/Q Ground deposition rate Calculation distance RDep=Relative ground deposition rate from Figure 6 of R.G.1.111, R1

Page 225 of 225 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX D DESCRIPTION OF THE INTERLABORATORY COMPARISON PROGRAM ICP The State of Florida, Department of Health-Bureau of Radiation Control (BRC)Laboratory shall participate in an INTERLABORATORY COMPARISON PROGRAM.1.The sample matrices an analytical methods shall be: A.Gamma isotopic on a filter sample simulating airborne radioiodine and particulate collection.

B.Gamma isotopic on a water sample simulating a surface water grab sample.C.Gamma isotopic on either sediment (or soil)or broad leaf vegetation.

2.The source of samples for this program: A.A Federal Government Laboratory Program (e.g., DOE-LAP, EPA Safe Drinking Water Program)B.A State, Federal, or private (commercial) laboratory capable of providing NIST traceable samples.To be eligible, a Commercial Laboratory shall meet the FPL Quality Assurance criteria of"Quality Related".C.For Gamma Analysis only, a FPL Nuclear Site Laboratory may prepare sample matrices using known quantities of radioactivity from isotopes provided by a FPL Contract Laboratory currently approved as PC-1 Level vendor.These prepared matrices may be prepared by the vendor, or by FPL personnel, but shall not exceed the participant(s) form and/or license quantities for allowed radioactivity.

3.Analysis of Matrix samples shall be capable of achieving ODCQ Table 4.12-1 prescribed LLDs on a blank sample.4.Results within 20%of expected shall be considered acceptable.

Results exceeding 20%but within 35%require a description of probable cause and actions performed to bring the analysis into conformance.

Results exceeding 35%are considered Not Acceptable; the Matrix shall be replaced and reanalyzed.

5.The frequency for performing the interlaboratory comparison program shall be annually with a maximum of 15 months between comparisons of similar matrices.

St.Lucie Units I and 2 Docket Nos.50-335 and 50-389 L-99-046 EncIosure 3 Marked Up Copy of ODCM Revision 19 Page 6 or 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION PAGE 3.0 40 CFR 190 Dose Evaluation......................,........

135 4.0 Annual Report Format....................................

136 Appendix A-ECL, Dose Factor and Historical Meteorological Tabtes~~~~~e~~~~~~~~~~a i~e i~pendlx 8-Limit Dose ssment for a ctlve u~~~~~~~~~~~~~~t~d for Eff~~~~~~~~~~~~~i 152~~~~~~~~~~~~~~~~~~~-Current R,E.M.Sample Point Locattons........-Descrlptlon of Meteorological Dlsperslon Formulas Utilized for Hlstorlcat Data and Methodology for Determlnlng Actual MET Data.'..........,........

Qp4'I'l" c gpnAi v.-$4~o~o4 Wt X,>~<L~+<~~/

pen N.ccMAl~oQr Ro~>~-'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~V II i'i~~i i~"~\

e 0 I Page 7 ot 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAI ODCM INTRODUCTION The ODCM consists of the Controls Section followed by the Methodology Section.The Controls Section provides the Control Statements, Limits, ACTION Statements, Surveillance Requirements and BASES for ensuring that Radioactive Liquid and Gaseous Effluents released to UNRESTRICTED AREAS and/nr the SITE BOUNDARY will be maintained within the requirements of 10 CFR Part 20, 40 CFR Part 190, 10 CFR 50.36.a and 10 CFR Part 50 Appendix-I radioactive release criteria.All Control Statements and most Administrative Control Statements In the ODCM are directly tied to and reference the Plant Technical Specification (TS)Administrative Section, The Administrative Control for Major Changes to Radioactive Liquid, Gaseous and Solid Treatment Systems is as per the guidance of NUREG-1301, April 1991, Supplement No, 1 to NRC Generic Letter 891.The numbering sequences of Control Statements also follow the guidance of NUREG-1301 as applicable, to minimize differences.

The Methodology Section uses the models suggested by NUREG4133, November, 1978 and Regulatory Guide 1.109 to provide calculation methods and parameters for determining results ln compliance with the Controls Section of the ODCM.Simplifying assumptions have been applied where applicable to provide a more workable document for Implementing the Control requirements.

Alternate calculation methods may be used from those presented as long as the overall methodology does not change or as Iong as most up-t~ate revisions of the Regulatory Guide 1.109 dose conversion factors and environmental transfer factors are substituted for those currently Included and used in this document.RECORDS AND NOTIFICATIONS All records of reviews performed for changes to the ODCM shall be maintained ln accordance with Ql 17-PRIPSL-1.

All FRG approved changes to the ODCM, with required documentation of the changes per TS 6.14, shall be submitted to the NRC in the Annual ENuent Release Report.Procedures that directly implement, administer or supplement the requirements of the ODCM Controls and Surveillances are: 0 C-70 Processing Aerated Liquid Waste C-72 Processing Gaseous Wastes COP%5.04, Chemistry Department Surveillances and Parameters C i'-i EASMNSiP M i S lp i I The Radiological Environmental Monitoring Program is performed by the State of Florida as per FPL Juno'Nuclear Plant Servfces Corporate Environmental Procedure Number NBS-NPS-HP-WP~2.

IR19 IR19 IR19 Page 28 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODOM TABLE 3.3-14 continued RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS ODCM Related Iodine Channels 1PV IODINE 1FHB IODINE 2A PV PIG IODINE 2B PV PIG IODINE 2FHB IODINE SGBDB IODINE ODCM Related Uquld Channels 1A SlG BLOWDOWN 1B SIG BLOWDOWN 2A SlG BLOWDOWN 2B S/G BLOWDOWN 1 BATCH LIQUID EFFLUENT 2 BATCH LIQUID EFFLUENT CHANNEL ID 01%3 412 45-5 CHANNEL ID 121 R6627 BASIS DOCUMENT FUSAR FUSAR FUSAR FUSAR FUSAR FUSAR BASIS DOCUMENT C-200 ALERT SETPOINT'000 CPM 5000 CPM 5000 CPM 5000 CPM 5000 CPM 5000 CPM ALERT SETPOINT'x Bkg.2x Bkp.2 x Bkp.2x Bkp.As Per C-70 As Per C-70 HIGH SETPOINT 10,000 CPM'0,000 CPM'0,000 GPM'0,000 CPM'0,000 CPM'0,000 CPM'IGH SETPOINT'.E~

uCI/ml 2.EM uCVml 2,E~uCVml 2.E~uCVmi" As Per G-70" As Per C-70" t Table Notations:

a-ODCM Control 3.11.2.1a b-ODCM Table 4.11-1 Nota P)c-ODCM Control 3.112,1.b d-TS Table 3.34 required instrument 2.a.ii vAth sotpolnt por ODCM e-Satpolnts may bo rounded for analog and digital cRaplay Input limitations.

f-The channel setpoint to be kt'cpm equivalent to thh activity g-per ODCM Methodology Step 222 h-Batch Gaseous Release Rate and Maxknum actMty limits shall ba used such that Plant Ven!(PV)Release HIGH satpolnts shoukf not be exoeedad.I, I, k, and l not used ln notation for clarity m-Conthuous Uqukf eetpolnt methoctoiogy per ODCM 1.32 n-Batch llqukf satpoht methodology per ODCM 1.3.1 FUSAR-Channel Ilstodin fusar, but notrequlrad by ODCM Control 8810Table 33-18.The setpoints are used to provide alarm weibefore exceeding ODCM Control 8.110.1,b Site Dose Rate Umlt.The inoperablity of a fusar channel above does not lnvoNe an ACTION statement unless TS Pechnical Specification)

Is noted.2 x Bkg3 x Bkg., 5 x Bkg.atc., denotes the number of Smes the normal channel reading ls the appropriate Alarm SoNng.These typo ol setpotnts shoukf be perkxfhalty evaluated to Insure alarm sensitivity ls maintained as per COP-0 T.o~,'t St.Lucle Plant ODCNI Controls IR19 Page 51 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTiVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION Continued ADMINISTRATIVE CONTROLS 3.11.2.6 (Continued) e.The Radioactive ENuent Release Reports shall include the followIng Information for each class of solid waste (as defined by 10 CFR Part 61)shipped offslte during the report period!1.Volume 2.Total Curie quantity (specify whether determined by measurement or estimate)3.Principal radionuclides (specify whether determined by measurement or estimate)4.~of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms)6.Type of container (e.gLSA, Type A, Type 8, Large Quantity)and 6.Solldicatlon agent or absorbent (e.g., cement, urea formaldehyde).

f, The Radioactive ENuent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials In gaseous and liquid effluents made during the reporting period.g.The Radioactive Effluent Release Reports shall Include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP)and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monltorlng identied by the Land Use Census of ODCM Control 3.12.2.L h.The format for an Annual Radioactive Effluent Release Report Is provided in ODCM~g~<g<(++ection 4.0.The information contained in an annual report shall not apply to any'DCM Control Dose Limit(s)since the methodology for the annual report Is based on actual meteorological data, Instead of hlstortcai conditions that the ODCM Controls and Control required calculations are based on.St.Lucie Plant ODCM Controls Page 77 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERM IN METHODOLOGY SECTION CC or cc Cl CI CFR Control(s)

Dose from Beta Radiation Cubic centimeter Curies-a unit of radioactivity see pCI Activity or concentration of a nuclide in the release source.Units of pCI, pCVcc or pCVml Code of Federal Regulations Regulations for operating, controlling, monitoring and reporting radioactive eNuent related activity as indicated by the Controls Section of the ODCM.The exposure, ln mrem or mrad, the organ or the Individual receives from radioactive eNuents Dose Factor Dose Pathway Dose Rate (D/Q)ECL FUSAR Normally, a factor that converts the effect of Ingesting radioactive material into the body, to dose to a specific organ.Body elimination, radioactive decay and organ uptake are some of the factors that determine a dose factor for a given nuclide A specific path that radioactive'material physicaIIy travels through prior to exposing an'individual to radiation.

The Grassow-MIIk-lnfant Is a dose pathway The dose received per unit time A long term D over Q-a factor with units of 1lm'hich describes the deposition of particulate matter from a plume at a point downrange from the source.It can be thought of as what part of the cloud is going to fallout and deposit over one square meter of ground.(See Append~.C.ENuent Concentration Limit Final Updated Safety Analysis Report.

I 0 0 Page 79 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLO Y SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION (continued)

Receptor The individual receiving the exposure In a given location or who Ingests food products from an animal for example.A receptor can receive dose from one or more pathways.~Retsase Source(s)-A subsystem, tank or vent where radloactlve material can be released Independently of other radioactive release points.TS Total Body pCI (X/Q)(X/Q)~dt, at or delta t The St.Lucle Plant Standard Technical Specifications Same as Whole Body In Control Statements micro Curies.1 pCI~10~Curies.The pCI is the standard unit of radioactivity for all dose calculations ln the ODCM.A long term Chl over Q.It describes the physical dispersion characterhstics of a semi-Infinite cloud of noble gases as the cloud travetees downrange from the release point.Since Noble Gases are inert, they do not tend to settle out on the ground.(See Appendix F).A long term Depleted Chl over Q.It describec the physical dispersion characteristics of a semi-Infinite cloud of radioactive lodines and particulates as the cloud travels downrange.

Since lodines and particulates tend to settle out (fallout of the cloud)on the ground, the (X/Q)~represents what physically remains of the cloud and Its dispersion qualities at a given location downrange from the release point.(See Appendix+.

A specie delta time interval that corresponds with the release Interval data etc.

Page 81 of 194 ST.LUClf=PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALC LATION MANUAL ODCM METHODOI OGY SECTlON 1.1 Radioactive Li uid Effluent Model Assum tions The FUSAR contains the official description of the site characteristics, The description that follows is a brief summary for dose calculation purposes: (Figiiie l-l Po'iii4'I-" The St.Lucie Plant ls locat d on an island surrounded on two sides by the At(antic Ocean and the Indi River, an estuary of the Atlantic Ocean.Normally, all radioactive llqul leases enter the Atlantic Ocean where the Circulating Water Discharge Pi terminates on the ocean floor at a point approximately 1200 feet offshomg No credit Is taken for subsequent mixing of.the discharge flume with the oce%.The dNusion of radioactive material into the ocean ls dependent on the condwons of tide, wind and some eddy currents caused by the Gulf Stream.The condsons are suNciently random enough to distribute the discharges over a wide area and no concentrating effects are assumed.There are no direct discharge paths for liquid eNuents to either of the north or south private property boundary lines.The Blg Mud Creek (part of the Indian River)does connect to a normally locked shut dam, that is intended to provide an emergency supply of clmulatlng water to the intake Cooling Water Canal In the event a Hurricane causes blockage of the intake Canal.No radioactive water could be discharged directly into the Intake Cooling Water Canal because all plant piping h routed to the discharge canal and no back flow can occur.Consult the FUSAR for a detailed description of characteristics of the water bodies surrounding the plant site.Only those nuclides that appear ln the Uquid Dose Factor Tables will be considered for dose calculation.,i"'~~'I p/

Page 82 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCUIATION MANUAL ODCM METHODOLOGY SECTION 1.2 Determinln the Fraction F of 10 CFR Part 20 ECLs Limits for A Li uid Release Source Discussion

-Control 3.11.1.1 requires that the sampling and analysis results of liquid waste (prior to discharge) be used with calculation methods In the in-plant procedures to assure that the concentration of llqutd radioactive material in the unrestricted areas will not exceed ten times the concentrations specmed in 10 CFR Part 20, Appendix B, Table 2.Chemistry Procedure C-70'Processing Aerated Liquid Waste'rovides instruction for ensuring batch release tanks wIII be sampled after adequate mixing.This section presents the calculation method to be used for this determination.

This method only addresses the calculation for a spec5c release source.The ln-plant procedures will provide instructions for determining that the summation of each release source's F values do not exceed the site's 10 CFR Part 20 ECL.The values for release rate, dilution rate, etcwill also have to be obtained from in-plant procedures.

The basic equation is: n C, F,-Z 0/1 (ECL)Where:=~the fraction of 10 CFR Part 20 ECL that would result If the release source was discharged under the conditions specled.R The undiluted release rate ln gpm of the release source.Uquid Rad Waste~170 gpm 4'~~as&Mov+e Th<I Ste 8 erator~.126 gpm/St am Generator a.<to~<Nathan=toogg~r Re we@=6o Xerrr r Mlle rr ueere~ererr 6+Ar S)D~Ine" mon ow in gpm of'take Cooling hter or Clrcuihting Water Pumps.'.:..'*Intake Cooling flow Is 14,600 gpm/pump Circulating Water flow h 121,000 gpm/pump C,~The undiluted concentration of nuclide (i)ln pCI/ml from sample assay (ECL),~The Effluent Concentration Limit of nuclide (I)in pCi/mi from Table L-1.For dissolved or entrained noble gases the ECL value is 2 X 10 p,CVml for the sum'o'i all gases.

Page S3 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE D SE ALC TION MANUAL OD M METHODOLOGY SECTION 1.2 (continued)

The fraction of the 10 CFR Part 20 ECL limit may be determined by a nuclide-by-nuclide evaluation or for purposes of simplifying the calculation by a cumulative activity evaluation.

If the simplified method is used, the value of 3 X 10~p.CI/ml (unldentNed ECL value)should be substituted for (ECI), and the cumulative concentration (sum of all identified radionuclide concentrations) or the gross concentration should be substituted for C,.As long as the diluted concentration (C~R/D)Is less than 3 X 10~pCI/m1, the nucllde4y~ucllde calculation h not required to demonstrate compliance with the 10 CFR Part 20 ECL.The following section provides a step-by-step procedure for determining the ECL fraction.1.Calculation Process for Solids A.Obtain from the Ingiant procedures, the release rate value (R)in gpm for the release source.B.Obtain free the I~lant procedures, the dilution rate (D)in gpm.No credit Is taken for any dilution beyond the discharge canal flow.~<C.'btain (Q, the undiluted assay value of nuclide (I), In pCI/ml.If the.simplNed method is used, the cumulative concentration (Ct~l)ls used.C D..From Table L-1, obtain the corresponding (ECL)for nuclide (I)In pCI/ml.The value of 3 X 10~'pCI/mI should be used for the slmplNed method.1 4~~E.Divide C, by (ECL), and write down the quotient F.If the simplNed method Is used, proceed to the next step.If determining the ECL fraction by the nuctkh4ywuciide evaluation, repeat steps 1.2.1.C through 1.2.1.E for each nuclide spotted in the assay, for H, from previous month composite and for SR89/90 and Fe55 from previous quarter composites,'~~-Fh k~ae~resu I4,'1 I'I'~~.%), k II-1 k 41k SV IO 7 d gllgl k%)1'4 4~t Page 88 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CAL LATION MANUAL ODCM METHODOLOGY SECTION 1,3 (continued) t.3.2 Setpoints for Continuous Liquid Release Monitors Liqutl M~ah4~Discussion

-The activity ixture described in 1.1 for Liquid Batch Release Monitors cannot be used for Contlnu us Liquid Pathways since the Steam Generator (Sl)Blowdown Seco dary Side is subject to what the current Reactor Cool t System (RCS)ctivlty and primary-to-secondary leakage exist at y time.Alth gh SIG blowdown Is not normally aligned to the Site Release Poln the monitor setpoints will be based on the ODCM maximum design S/G blowdown rate of 125 gpm with 1 Circulating Water Pump (CWP)121,000 gpm ln operation.

The ODCM and C-70, Processing Liquid Waste assume that the fraction of solids entering the Discharge Canal to the site release point are controlled less than or equal to 1.0, with batch release using 80%and the remaining 20%allocated to continuous sources on site.The actual site limit for solids ls 10 times the concentration specIed in 10 CFR Part 20, therefore a conservation factor of 10 Is already Included in the administrative site limit.Since source in-leakage to a S/G cannot be controlled, a High alarm monitor setpolnt Is calculated based on one S/G releasing to the discharge canal at design blowdown rate white attaining the 20 percent of the site limit (Q assuming all the gross solid activity Is I-131.The contribution from DIssolved and Entrained Gases Is assumed to be zero with all of the gaseous activity going to the Steam Condenser and Air Ejector pathway.F, t2D%sR.X I 1 CWP Dllutlon rate l-131 uCVml (Table L-1ECL)F, at 20%a~2m"X 121,000 gaVmln..1.BS uCVrnl (I-131 Table L-1ECL)I Solving for the S/8 High Alaim Setpoint l-131 Actlvtty, I-131 uCI/ml (S/G)~-2E44&I/ml H31 Is the maximum S/G activity that could be aihwed such that 20 percent of the administrative discharge canal limit would not be'xceeded.

J~,~~

Page S9 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCVLATI N MAN AL OD M METHODOLQ Y SERMON 1.3 (continued) 1.3.2 (continued)

This S/G Monitor High Alarm Setpolnt activity may be converted to cpm using Liquid Monitor uC/ml to cpm convenlon constants.

/R19 This Setpolnt is conservative given that the actual Liquid Site Limit is a factor of ten times higher than the administrative limit used for calculation purposes, that I-131's ECL Is conseIvative vs other isotope mixtures, and that it is unlikely that more than one S/8 would be allowed to operate with a 20 gallon per day primary-to-secondary leak rate.1.4~igg+gn-Control 3.11.1.2 aquires calculations be performed at hast once per 31 days to vetlfy that cumulative radioactive liquid eNuents do not cause a dose ln excess of 1.6 mrem to the whole body and 5 mrem to any organ during any calendar quarter and not ln excess of 3 mrem to the whole body and 10 rnrem to any organ during any calendar year.This section presents caiculationaI method to be used for this verwcatlon.

This method Is based on the methodology suggested by sections 4.3 and 4.3.1 of NUREGA133 Revision 1, November,'878, The dose factors are a composite of both the fish and sheINsh pathways so that the fish-shellfish pathway is the only pathway for which dose will be cal lggt.': e dose for l8,bid teenager can g4so be calculated by this meth rovlded that.their approprhte dose factors are available for the organ of interest.gO ly those nuciides that appear ln the Tables of this manual will be considered.

~~~y I~~,i~geg 4,~Lijuil go gyf.eQ 4lsh-$AallgQIii.c,ggg~~f'~p~~v~pr wtlk+acW~high g P is Wa c~W i(ig (~os'id'"~)

+~+(~~~I 3.(l~~.~),v.~

Page 91 of 194 1A (continued) 1.(continued)

METHODOLOGY SECTION g6.6 QogI cHL<ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDLIRE C-200, REYISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM posE Fhc TER rl A Based the radionuclide distribution typical in ra active effluents, the calculate oses to individuals are dominat~d the radionuclides Fe-59, Co-58, Co-6 Zn45, Nb-95, Cs-134 and C 37.These nuclides typically contribute over 5%of the whole body d e and over 90%of the Gl-LLI dose, which is the criti organ.Therefore e dose commitment due to radioactivity in liquid effluents ma reasona evaluated by limiting the dose calculation process to these radion lldes the adult whole body and adult 61-LLI.To allow for any unexpected v llity ln the radlonucllde distribution, a conservatism factor of 0.6 I uced into the equation.After calculating the dose based on these 7 uclides, cumulative dose should be divided by 0,6, the conservatism fa.(l.e., D,~.6).Refer to Appendix B for a detailed evaluation and exp nation of this limit nalysis approach.The methodology th follows is a step-by-step breakd o calculate doses based on the above e ation.Refer to the tn-pl rocedures to determine the applicable organs, a groups and path factors, If the limited analysis approach is used, the calc tlon shoul limited to the Adult whole body dose and Adult Gl-LLI dose fr sh and shellfish pathways.Only the 7 previously specied radionucli should be evaluated.

For the dose calculations to be included annu reports, the doses to the adult groups and all organs should be e ated for all dlonuclides identified in the liquid effluents.

Table 1.4 Pi~TE for compiling the dose accounting.

in hourg A.Ot t 1 tl tt tk,lh Ih i kpt on<~Per 31+~><<o~<<~ohon~

d.I woulh b<o~Wa ew+J'rp wow+4z koHI" B.Obtain (DF), for the time period g from Liquid Waste Management Records for the release source(s)of Interest.C.Obtain Q,I for nuclide (i)for the time period dt, from the Liquid Waste Management Records D.Obtain A from the appropriate Liquid Dose Factor Table~r/gy5g CalCKlgtt>~>

Q y~~aeL(4ofe<olculakioM

~aug.I,a+~~0>rgl~Wa year-, W P luis~<~i,e40~.'P Au~a4ion oY a-sln~4~Ieese~"+"~~4.

Page 92 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCLILATION MANUAL ODCM METHODOLOGY SECTlON 1.4 (continued) 1.(continued)

TABLE 1.4 FISH AND SHELLFISH PATHWAY~TIME/DATE START::~~TIMEIDATE STOP::~~HOURS TOTAL DILUTION VOLUME: mls AGE GROUP'RGAN:

DOSE FACTOR TABLE 8: NUCLIDE (I)Ci (SCI)DOSE (I)mrem s-1 s-1 7 TOTAL DOSE g~mrem E.Solve for Dose (I)ooae (I)Q~-A (DF),

Pago 93 of 194 ST.LUCtE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.4 (continued) 1.(continued) gge QouPS)aQ modems'I>>F.g Repeat steps 1 4.1.C through 1.4.1.E for each nuclide reported and each<G.QSum the Dose (i)values to obtain the total dose to organ T from the fish-shellfish pathway.WKeelmlted ana s 1.5 Pro ectln Dose for Radioactive LI uld ENuents Discussion

-Control 3.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce radioactive material in liquid eNuents when the projected doses due to the liquid eNuent, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1)would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.The following calculation method Is provided for performing this dose projection.

The method Is based on dose as calculated In section 1.4 with the adult as the bases for projecting.

F()<4hz co~+roll(nq Pge,~up 1, p Obtain the latest result of the monthly calculation of the~whole body dose and the hack~highest organ dose.These doses can be obtained from the in-plant~rds.2.Divide each dose by the number of days the reactor plant was operational during the month.3.Multiply the quotient of each dose by the number of days the reactor plant is proJected to be operational during the next month.The products are the projected dose for the next month.These values should be adjusted as needed to account for any changes In failed fuel or other ldentmable operating conditions that could significantl atter the actual releases.4.If the projected dose ls greater than 0.06 mrem to the whole body or greater than 0.2 mrem to the adults highest exposed organ, the liquid radwaste system shall be used.

~P,'

Page 97 ot 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 2.2 (continued)

Where;DR~=total body dose rate from noble gases in airborne releases (mrem/yr)D~=skin dose rate from noble gases in airborne releases (mrem/yr)a mathematical symbol to signify the operations to the right of the symbol are to be performed for each noble gas nuclide (i)through (n)and the Individual nuclide doses are summed to arrive at the total dose rate for the release source.=the total body dose factor due to gamma emlssions for each noble gas nuclide reported ln the release source.(mrem-m'/pCi-yr}

~the skin dose factor due to beta emlssions for each noble gas nuclide (I)reported in the assay of the release source.(mrem-m'/pCi-yr)

~the air dose factor due to gamma emlsslons for each noble gas nuclide (i)reported in the assay of the release source.The constant 1.1 converts mrad to mrem since the units of M, are ln (mrad-m'/pCI-yr)(X/Q}~for ground level, the highest calculated annual long term historic relative concentration for any of the 16 sectors, at or beyond the exclusion area boundary (sec/m')(Q DOT),=The release rate of noble gas nuclide (i)ln pCI/sec from the release source of Interest 1.Implmed Total Body Dose Rate cula on F an evaluation of past rele ses, an e ive total body dose fact (K can derived.This dose fa r ls in eff a weighted average tot body dose ctor, l.e., weighted by e radlonuclld distribution typical o st operatl.(Refer to Append C for a detail explanation and aluatlon of K).Th value of K has n derived from e radioactive le gas eNuents r the years 197, 1979 and 1980.e value is: 6 8 (p m18m-yr 0 0 1'I>I Page 98 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CAL LATI N MANUAL ODCM METHODOI OGY SECTlON 2.2 (continued)

This valu ay be used ln conjunction with the t al noble gas release rate (Q DOT), to erify that the dose rate is within t allowable limits.To allow for any unexpect variability in the radionuclid distribution, a conservatism factor of 0.8 ls introdu d into the calculation.

e simplified equation Is: DR Q DO7)0.8 To further simplify the dete I tion, the historical annual average meteorological X/Q of 1.6 X~sec/m'From Table M-1)may be substituted into the equation..

Also,'th d Ilmlt of 500 mrem/yr may be substituted for D~, Making these su on sids a single cumulative (or gross)noble gas release rate limit.Is value Noble gas release e limit~3.6 X 10 I/sec As long as the e gas release rates do n t exceed this value (3.6 X 10'CI/sec), no a Itional dose rate calculations re needed to verify compliance with Control.11.2.1.'~*~4'I.a~

Page 99 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATI N MANUAL DCM METHODOLOGY SECTION 2.2 (continued) llswct t'~oocsh tt.ao t s<o~p+%a Setpoint Determination

~la5 c4Xermiwhh No b R.To comply with Control 3.3.3.10, the alarm/trip setpoln are established to ensure that all noble gas releases In progress do not e ed the ODCM Control 3.11.2.1 noble gas release rate limit for the site, e total body osefjiamore timing than the oatcutated skin dose~,lh t tt Il I II lt tt t lady dose rate of 500 mrem/yr has been determined to be equivalent to 3.5E+05 uCVsec being released from the site.Using 3.5E+05 uCVsec as the equivalent of 100 percent of the site limit, each release point on site may be allotted a portion of the 100 percent, such that the sum of all release point portions allotted shall be less than or equal to 100 percent.The release point's actual monitor setpolnt shall take into account the physical release characteffstlcs of maximum expected volume release rate and Its percent allotment for a single release point since uCI/sec Is proportional to'olume rate.The ODCM actual release points and an example of percent allotments ls provided;Site Limit In Percent~100%-Site Limit in uCl/sec~3.6E+05 uCVsec~Milt Pt Unit 1 Plant Vent Unit 1 Fuel Bldg.Vent EGGS 1A EGGS 1B.Unit 2 Plant Vent Unit 2 Fuel Bldg.Vent ECCS 2A-"~ECCS 28'>>Blowdown Bldg.Vent'otal Percent Allocated~(Example)Percent~II mmi 40 5 1 1 5 1+6 99 or 1 percent below the Site Limit Page 100 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE ALCULATION MANUAL ODCM METHODOLOGY SECTION 2,2 (continued) j g.(continued) 07,c5 A.(continued)

O'7,O+1.Obit tt t pll'P II rate (Yj In Cubic Feet per Minute (cfm)from the ENuent Supervisor.

2.Obtain the release point's percent of site limit allotment (PA)from the Chemistry Supervisor., 3..Substitute the release point's V~PA values Into the below equation to obtain the Release Point's Setpolnt (SP).W~~"Ilkala"~II-*~"~k-sec, min,, Y ft3 28317 cc 100%1 uCVcc'hich ls the TABLE 3.3-14 HIGH SETPOINT for-ODCM ENuent Gas Channels that have a'Allotted%of Site Umlt'eclared as their HIGH SETPOINT.SP~+ot~H~~o0 t-"e More or less percentage may be used fr a retease potnt, but thgtotat percent allocated to the above Release)Pelnt shall never be allows d to exceed 100 percent.The ECCS Reactor Auxiliary Building Exhaust are not ODCM required monitored release points, but a small percentage should be allotted to each to cover short periodic fan surveillance ru allocation h controlled per Chemistty Procedure COP, Process Monitor Setpoints where Chemistty Supetvisor approval Is required.OP provides calculation steps to calculate a Noble Gas Release Rate Setpolnt based on the methodology steps described below.A release point's percent allotment wilt be converted into the release point's indhatlng engineering unit of uCVcc that will be equivalent to the allocated portion of the site limit.e 4 Page 101 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE SE CAL LATION MAN AL ODCM M ODOLO SE ON 2.2 (continued}(continued}

A.(continued)

In the case of Unit 2 Plan Monitoring the Plant Vent 2A PV PIG LOW RANG Vent there are 3 ODCM ENuent Gas Channels The HIGH SETPOINT In uCl/cc is the same for GAS, 28 PIG LOW RANGE GAS, and 2PY WRGM LOW RANGE GAS since they are monitoring the same release point (l.e., each of these channels does not receive their own allotted%of the Site Llmlt), 4., The slgnicanoe of an OOGM ENuent Gas Channel that has a'Allotted%of Site Limit'IGH Setpolnt requires further dlscusslon (Mld and High Noble Gas Accident Channels are not part of this discussion):

-,"+~I a.For Plant Vent Release Points on each reactor unit, the'Allotted%of Site Limit'eeds to be high enough to allow for Batch'eleases,from Gas Decay Tank and Containment Venting Operations, ind at the same,'time C-72, Processing Gaseous.Wiste shall provide,in'structlon for admlnlstratlvely controlling

'atch Releasco such that the radioactive con'centratlon and ,,release rate will'not be'allowed o exceed the site limit at any time.I"~'..The receipt'of;a valid Alarm on a release point where the , ODCM Low'Ri'n'ge,Gas,',Ghanriel's radioactMty.

Is approximately

'.equal to,the HIGH'Alarm setpoint does not mean the site, limit has'.been"exceeded, mthe'r, It ls'at.a coricentiitlon that Is'equivalent to'the"Allotted 5 of'Site Umlt",'"'.,"..".;,:,,'I I~~, 4\)~I~'I I/R19 ,I~,~l~I~,l I~~I~ail Page 102 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 1S OFFSITE DO E CAL LA N NUAL OD M METHODOlOGY E ON 2.2 (continued)(continued}

A.(continued) 4.(continued) c.The receipt of a valid HIGH Alarm on a release point where the ODOM Low Range Gas Channel's radioactivity ls greater than the HIGH Alarm setpolnt may quickly be yg~gycf based on;F~RP+(Sum*of y+f~Release Point's.RP8, on site)RP~~, Rei Pt's: '-Rel Pt's" volume time Channel's.x..Release x conv.x conv.x 1/(site limit)uCI/cc-'.'.'Rate const.const.~.\I~RP",Jgl.-:V.IP-'Rl I1II'-mlle co"-': min....:.-.:-.'t, 60 sec 3.5E+05 uCI I 1~Where: ', F~Fraction of the Site,LImit

", RP~~Fractiori of a'Releaie Point's contrlbuthn to the site limit."(Sum'of,g~f~,Releaie';Point's RP~on site)Is notmaliy less"';'.than,0.10'under,nomial

',o'perating'condlthns.,.'.V.~'iri ft'/min, the'Releaie'Point's actual process Volume flow..A'value of,RP~'~1.0'or a F~~1.0 would be exceeding the Site LImit',Based'on the above'jgggjgg

~'Off Normal Procedure allow 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to'..';obtain'a grab sample of<the, Release Point so that the actual site limit':;.':, situation,may be;evaIuited.";,This method Is'lscusied in the following I/R~'I' Page 103 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE D E CALCULAT 0 ANUAL ODCM METHODOL GY E ON.2.2 (continued)(continued)

A, (continued) 5.To quantify the Release Point's a ai obie s D Rate the followinp would need to be performed:

a.A Noble Gas ActMty Grab Sample would be obtained and analyzed to ermine each Noble Gas Isotopic concentration.

<,'L,M-..b.We re would'u'sed to perform calculations per ODCM.for N le Gas Total Body Dose Rate and Skin Dose Rate', F c.lf the Release Point's HIGH Alarms were received on the.Table:3.3-14 ODCM Related Particulate and/or iodine Channel,'hen ODCM Step 2.3.cahulatlons should be performed as soon as~.,'," ttoeetble after the conttnuoui collection medium(e)and a Trltlum",;, Sample can be pulled.'ind analyzed to evaluate compliance with~,',...'.":ODCM'Control 3;11.'2.1'.b

',';., F'I'I'I ,~F I r If/R)9 I I II~~~~II F~*~I I F~'I I'*

Page 104 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE ALCULATION MANUAL ODCM METHODOLOGY

~iECTION 2.2 (continued)

I g.'continued) 7y~B.No Particulate or Iodine Radioactivity Channels are required by the ODCM.Table 3.3-13 requires Iodine and Particulate Samplers only.Technical Specication Table 3.3-6 requires a Fuel Bulldtng Vent Particutate Channel (the bases for the setpolnt on the Fuel Building Vent Particulate Channel Is esc n~~).The FUSAR does describe Particulate and Iodine Radioactivity Channels.These Channels are listed In ODCM Table 3.3-14 and ALERT and HIGH Setpolnts are provided.The Intent of providing these setpoints Is to pravkle early warning that the eNuent pathway ndtttons have increased such that a grab sample should be obtained if a Hlg Alarm Setpolnt Is reached or exceeded.The Particulate and Iodine Alarm Setpolnt bases is that the collection mediums are fixed filter where continuing deposion of radioactMty would cause a Increase in the channel count rate up'to the setpolnt Ievet(s), the resulting dose rate can be shown to be less than 1 percent of the site limit for ODCM Control 3.11.2.1.b for Iodine-131, iodine-133, and all radionuclides ln particulate from with half-lives greater than 8 days, Is that these channel detectors are gross actMty monitors of the scintillation type where the count rate Is not dependent (above threshold) on the energy of the Isotope entrained on the collection medium" ,and that these'channels are qualitative trend Indicators since the channel count rate cannot be corrected for the accrued sample collection volume.Plant historical trends have shown that Noble Gas ActMty may contribute to the count rate of the Reactor Auxiliary Building (Plant)Vent Particulate and iodine Channel(s), In this event the Noble Gas contribution may be added to the Table 3.3-14 Alert and High Setpolnts for Plant Vents only.~t I The sampling mediums associated'with,the Particulate and Iodine Channels ln Table 3.3-14 are also oontrolled by the requirements of ODCM Table;4.11-2 which equires 4M Minimum Analysts Frequency of the sampttng mediums.'hese analysts are used to confirm and quantify the Isotopic co'mposion of, the radioactivity being monitored by these channels.The presence of Noble Gas on collection medium would be confirmed by these,anatysts;.

"':.'4 Page 105 of 194 ST.LUCIE PLANT CHEMtSTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALC TION MANUAL ODGM METHODOLOGY SECTION 2.2 (continued)(continued)

B.(continued) tf an alarm occurs, Channel Check(s)should be performed on these channel(s), an ALERT Alarm should be investigated and a HIGH Alarm shall require isotopic analysis of paittcutate and/or Iodine channet medium of the affected channel(s).

The isotopic analysis of the medium shall be used to evaluate particulate and/or Iodine dose rate tevels per the methodology of OOCM 2.3.C.To comply with Technical Specification 3.3.3,1, Table 3.34 Radiation Monitoring lnstrumentatlon,"instrument 2.a.ll.Particulate Activity', wtth Alarm/Trip Setpolnt determined and set ln accordance with the requirements of the Offstte Dose Calculation Manual, the following ls the BASES for Fuel Building Parttcutite Channel High Alarm Setpolnts for Unit 1 and Unit 2:.I The 10,000 cpm High Setpolnt is based on an infant's Maximum Exposed Organ Dose Rate'(Uver) from Inhalation of Cs-137 at the Site Boundary, The value of 10,000 cpm is very conservative relative to the stte dose rate ,limit of 1600 mrem/yr., The methodology ts based on measured particulate channel count rates when the detector was calibrated with a known source activity of Gs-137, and on default assumptions as follows: The particulate channel read 32,386 ccpm when exposed to a 7.67 uCI soutee of Cs-137.2.Assuming that 7.67 uCl of Cs-137 were collected during 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of stdd sample collection (fixed fitter), the typical sample volume would yield-3.3E+OB cc's.Greater than 99%sample fitter efficienc ls assumed.C~,," 4/R19 1'~~

Page 106 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19~~SISS G G SIS I~GS 2.2 (continued)(continued)

C, (continued) 3.The maximum building process flow exhaust is-24,676 cfm.4, Q(dot)for Cs-137 uGllsec release rate ls approximately 27 uCl/sec as follows: Z4&g~x x R~RUt xRMEQ x~~gj'Vg~hour 3,3E+06cc.s ft3 min 60 sec sec 5.The default historical (XtQ)d for the worst sector (NW)at the site boundaty ls 1.3E4B ll1eterslsec.

6.The dose rate (equivalent to 10,000 cpm)h calculated per ODCM Section 2.3 Inhalatlon Dose Rate to an infant.The resuing dose rates yield.Bone LIver ThyroId KIdney Lung Glkll Vl.Body mtamhp mremPp mremtyr memtyr mremtyr mremtyr mre~7AE~7.9E+00 O.OE~, 42E41 1.0E+00 1.&E~4.8E%1 S.fl.<.I.b 7.The ODCMQA+~(ose rate limit to any organ Is 1600 mrem/yr.From the preceding calculation the Infant's Liver Is the maximum exposed organ at 0.62 percent of the site dose rate limit.I I 61 A partfculate channel setpolnt of 10,000 cpm provides a conservative setpolnt given that this channel analyzes gross activity on a fixed filter, Cs-187 Is a typical lon+Ived fission pmluct present at all times with spent fuel tn the pool;and that sample collection Intervals shorter than.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months would provide adequate warning response lf significant particulate activity were being released;I.e., the above assumptions assume a Cs-187 activity of'-'2.3E~

uCI/cc.1 Page 107 of 194 ST.LUG'IE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE CALCULATION MANUA ODCM METHODOLOGY SECTlON 2.2 (continued)

}P (continued)

C.(continued) 9.The setpoint of 10,000 cpm was,administratively chosen to provide early detection/alarm of a problem.The above dose rate calculations are provided to document that the patticulate channel ls capable of detection sensitivities to insure compliance with the ODCM site limit.Grab samples should be perfotmed to accurately caicuIate actual releases associated with real high alarm events as per the ODCM methodology for performing dose rate calculations.(End of Unit 1 Fuel Building evaluation)

The 10,000 cpm High Setpolnt is based on an infant's Maximum Exposed Otgan Dose Rate (Uver)from lnhalatlon of Cs-137 at the Site Boundary.The value of 10,00 cpm Is very conservative relative to the site dose rate limit of 1500 mrem/yr.The methodology Is based on measured particulate channel count rates when the detector was calibrated with a known source activity of Cs-137, and on default assumptions as follows: 1.The particulate channel read 39,782 ccpm when exposed to a 7.59 uCI source of Cs-137 (decayed to June 19, 1996 data).2, Assuming that 7.69 uCI of Cs-137 were collected during 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of skid sample collection (fixed filter), the typical sample volume would yield-5.32E+OB cc's.Greater than 99%sample filter efficiency Is assumed.3.The maximum building process flow exhaust h-31,584 cfm.4.Q(dot)for Cs-137 uCI/sec release rate Is approximately 21 uCI/sec as , follows:-aaaaal'"~

" aeoiaa aleue~s-eaaae hour 6.32E+06cc.s ft3.'min 60 sec sec/R19 Page 108 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E CAL LATION MAN AL OD M METHODOLOGY SECTION 2.2 (continued) t, g (oontinved)

C.(continued) 6.The default hlstoricai (X/Q)d for the worst sector (NW}at the site boundary ls 1.3E~meters/sec.

6.The dose rate (equivalent to 10,000 cpm)Is calculated per ODCM Section 2.3 Inhatatlon Dose Rate to an Infant.The resulting dose rates yield.Bone Liver Thyroid Ndney Lung Gl-LLI W.Body mrem/yr mrem/yr mrem/yr mremtyr mre~mrem/yr mremrtyr 4,8E~5.08E+00 0.0E~2.7E%1 7.0E%1 1.0ECR 8,1M)1 3 IIt'K.'l, Q 7.The ODCM~dace rate limit to any organ ta 1 500 mrem/yr.From the preceding calculation the Infant's Liver Is the maximum exposed organ at 0.34 percent of the site dose rate limB.t a~'rr a 8.A particulate channel setpolnt of 10,000 cpm provides a conservative setpolnt given that this channel analyzes gross activity on a fixed filter, Cs-137 Is'a typical longlved fission pnxiuct present at all times with spent fuel In the pool, and that sample collection Intervals shorter than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months would provide adequate warning response lf significant particulate activity were being released, l.e., the above assumptions assume a Cs-137 activity'f

-1.4E~uCI/cc.-~e~~9, The setpolnt of 10,000 cpm,was administratively chosen to provide early detection/alarm of a problem..The above dose rate calculations are provided to document that the particulate channel ls capable of detection sensitivities to insure compliance with the ODCM site limit.Grab samples should be performed to accurately calculate actual releases associated with real high alarm events as per the ODCM methodology for performing dose rate calculations.

'R19 I P Page 109 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE AL LATION MANUAL DCM METHODOLOGY SECTION 2.2 (continued}

Total Body and Skin Nuclide Specific Dose Rate Calculations I The following outline provides a step-by-step explanation of how the total body dose rate is caiculated on a nuclide-by-nuclide basis to evaluate compliance with Control 3,11.2,1.This method is only used lf the actual releases exceed the value of 3.5 X 10'CI/sec, A.The (X/Q)value i sec/m'nd ls the most limiting sector at the exclusion area, (See Table M-1 for value and sector.)B.Enter the release rate in ft'/mtn of the release source and convert It to: (}0'2.8217 X10'cc X min min gP 60 sec cc/sec volume release rate C.Solve for(Q DOT), for nuclide (I)by obtaining the pCl/cc assay value of the release source and muiplying lt by the product of...above.4.'LA.c 8 (Q DOT),~(nuclide fg)i.~.~.>~(assag pCl<(&0&8 va/ue)cccc.'ec (Q DOT),~pCI/sec for nuclide (I)D.To evaluate the total body dose rate obtain the K}value for nuclide (0 from Table 6-2.E.Solve for DR'Rm'KgÃQ}(Q DDTJ, X-X-"}c-m'ec DR~ggygj.total body dose from nuclide (I)for yr the specmed release source s t.-~~'"~~%'i\-~\J 9 r~I.~'~~/gag~S I,p Page 110 of 194 ST.LVCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE D E CAL LATION MAN AL DCM METHODOLOGY SE N 2.2 (continued)(continued)

I F.To evaluate the skin dose rate, obtain the L, and M, values from Table G-2 for nuclide (i).G.Solve for D~, D~(~Q+1~1 MJ (X/Q)(Q DOT))D~,~~skin dose from nuclide (I)for the yr specied release source~,i,~.O.~.~,~6-H.Repeat steps 2.~through 2 MAR for each noble gas nuclide (I)reported ln the assay of the release source.~~I.The Dose Rate to the Total Body from radioactive noble gas gamma radiation from the specied release soulce ls: n.DR~Z DR~I r J.The Dose Rate to the skin from noble gas radiation from the specified~release soutce ls: I'r'0~DR~~Z DR~, i'~1 r II The dose rate contribution of this release source shall be added to all other gaseous release sources that are'ln progress at the time of Interest.Refer to I~ant procedu es and logs to'determine the Total Dose Rate to the Total Body and Sdn from noble gas effluents.

',~,', r I I I 1~I ll r r 1~~r,~r r I=~,r r~r~wr r~rrqrr rv y~g~~I l rr i'%h.~rupia'j)~gm<$w~%qr q~~r'e w;r'W~+"W, s r cger pW yl

Page 122 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALC LATION MANUAL ODCM METHODOLOGY SECTION 2.4 (continued)

From an evalu tion of past releases, a single effective gamm ir dose factor (M,)has been derive, which is representative of the radionuclid abundances and corresponding do e contributions typical of past operation, (Refer to Appendix C for a detailed expl ation and evaluation of M~).The v e of M~has been derived from the ra'ctive noble gas effluents for the ears 1978, 1979 and 1980.The value is M,-7.4X10 m~+pCk'm'his value may be used ln njunctlon with total noble gas releases (Q,)to simplify the dose evaluation a d to verify th the cumulative gamma air dose Is within the limits of Control 3.1.2.To al w for any unexpected variability in the radlonuclide distribution, a con rvatlsm actor of 0.8 ts introduced into the calculation.

The simplified equat n ls 3.17 X 10 M~g E 08 For purposes of calculations, appro ate meteorological dispersion (X/Q)from Table NI-1 should be used.ntrol 3.11..2 requires that the doses be evaluated once per 31 days, (l.e., m ly).The qu erly dose limit ls 5 mrads, which corresponds to a monthly lotment of 1.7 ds.If the 1.7 mrads is substituted for D~a cumulative noble as monthly release objective can be calculated.

This value Is 36,000 CVmon, noble gases.As long as this value not exceeded in any mon, no additional calculations are needed to verify pllance with the quarterly nob gas release limits of Control 3.11.2.2.Also, the gamma air dose is more limiting han the beta air dose.Therefore, the be air dose does not need to be cal lated per Section 2.5 if the M~dose factor used to determine the gamma air d.Refer to Appendix C for a detailed eval tlon and explanation.

The calculati ns of Section 2.5 may be omitted when this lmlted analysIs approach is used, b should be performed lf the radionuciide specI dose analysis ls performed Also, the radlonucllde specie calculations will performed for inclusion n annual reports.

0 0 I Page 123 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E GAL ULATION MANUAL ODGM METHODOLOGY SECTlON 2A (continued)

The following steps provide a detailed explanation of how the radionuclide specific dose is calculated.

~1.To determine the applicable (X/Q)refer to Table M-1 to obtain the value for the type of dose calculation being performed, (l.e., Quarterly Control or Dose Projection for examples).

This value of (X/Q)applies to each nuclide (I).2.Determine (M)the gamma air dose factor for nuclide (I)from Table G-2.3.Obtain the micro-Curles of nuclide (I)from the in-plant radioactive gaseous waste management logs for the sources under consideration during the time Interval, 4.Solve for D, as follows: 3.'f7 X 10~yr Mi mrsd m'XQj ssc sec y.Ci yr-m'D,~mrad~the dose fromnucllde (i)5.Perform steps 2.4.2 through 2.4A for each nuclide (i)reported during the time interval ln the source.6.The total gamma air dose for the pathway is determined by summing the D, dose of each nuclide (I)to obtain D-air dose.Oy~=C,+O,+

+D,=mrsd.4, 0.8, liance a 1/31 day ontro uarterly ntrol, arly or 1 utlve onths Control n be demonst ted by the limited alysls ach sing M~.Using thi method onl requires th t steps.4.2 th gh be rformed one time, re emberln at the dos must dMd by conservatism factor.7.Refer to ln-plant procedures for comparing the calculated.

dose to any applicable limits that might apply.

Page 125 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL OD M METHODOLOGY SECTION 2.5 (continued) not hav sga..The following steps provide a detai e exp anation of how the dose Is calculated.

1.To determine the applicable (X/Q)refer to Table M-1 to obtain the value for the type of dose calculation being performed (l,e., quatterty Control or Dose projection for examples).

This value of (X/Q)applies to each nuclide (i).2, Determine (N)the beta air dose factor for nuclide (I)from Table 6-2.3.Obtain the mic~urles of nuclide (I)from the ln-plant radioactive gaseous waste management togs for the source under consideration during the time Interval.4.Solve for D, as follows: p.t7 g tp<yI Ni mrad m3 p-gpss Stm Qi ILCI sec pCI yI'M'D,~mrad~the dose from nuclide (I)\~I'I I 5.Perform steps 2.5.2 through 2.5.4 for each nuclide (I)reported during the time interval in the release souse.'6.The total beta air dose for the pathway ls determined by summing the D, dose of each nuclide (I)to obtain D~dose..r D~D,+D,'Dmrad 7.Refer to lnglant procedures for comparing the calculated dose to any applicable limits that might apply.'\

Page 126 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION.Q fI Q.(r l ONP S 2.6 Determinin the Radioiodine and Particulate Dose To An 0 an From Cumulative Releases Lv.m'r S~ervtS0 Wit(+T-GCg cV ht'c I P ge~uP~Illho fwceI~~Lc+iv+)~e.QrGuQ(s~co~(E.u.<4 Discussion

-Control 3.11.2.3 limKS'the dose to the whole body or ahy organ resulting from the release of l-131, l-133, tritium and particulates with half-lives

>8 days to<7.5 mrem during any calendar quarter and<15 mrem during any calendar year.The following calculation method is provided for determining the critical organ dose due to releases of radlolodines and particulates and Is based on Section 5.3.1 of NUREG-0188, November 1978, The equatlorIoan be used for any age group provided that the appropriate dose factors are used a dose reflects onl those pathways that are applicable to the age group.~e (X/Q), symbol represents a DEPLETED-(X/Q) which Is different from the Noble Gas (X/Q)In that (X/Q)~takes into account the hss of I&8DP and H from the plume as the semi-Infinite cloud travels aver a given distance.The (D/Q)dispersion factor represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site.The t&8DP and H-3 notatIons refer to I-131, I-133 Particulates having half-lives

<<8 days and TrIum.For ease of calculations, dose from other Iodine nucildes may be included (see 2.1).Tritium calculations are always based on (X/Q)~.The first step Is to calculate the l&8DP and H-3 dose for each pathway that applies to a given age group.The total dose to an organ can then be determined by summing the pathways that to the rece or ln the sector.Ol,tIg g r o~p OeS AO+App,g The equations are: g~g~~~/~I/~+pfyp4 5'I~QK~)(Q~4$$tVAfr 5.hy e~4~lp'i pC~For lnhalatlon Pathway (excluding H-3): n D, Z 3 17 X 10~Ri (X/Q)oQ l ,(g~cia<]o~For Ground PlanearfGrass&owlGoat-Milk, Gr<<s-<'j)I7 O~~sa Z 3.17 X10~RI (NQ)Q, i For each pathway above (excluding Graund Plane)For Tritium: P~~3.17 X 10~R~~QX/Q}r Q(HN W~e~n<<if~sv~<<p rk~u~s',,svsv rr/p'"~'I Page 128 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MAN AL ODCM METHODOLOGY SECTION 2.6 (continued)(X/Q)~=The depleted-(X/Q) value for a specific location where the receptor Is located (see discussion).

The units are sec/m'D/Q)

Q, the deposion value for a specific location where the receptor ls located (see discussion).

The units are 1/m'here m=meters.The number of mic~uries of nuclide (I)released (or proJected) during the dose calculation exposure period.the number of mlc~uries of H4 released (or projected) during the dose calculation exposure period.~~~~r~t',p,~~~,'L~I+l~W%~e,g~,~~~,

Page 129 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E CALCULATION MANVAL OD M METHODOLOGY SECTI N 2.6 (continued}

1.The Inhalation Dose Pathwa Method;~N/E The H-3 dose should be calculated as per 2,6.4.A, Determine the applicable (X/Q)~from Table M-2 for the location where the receptor ls located.This value is common to each nuclide (I)R~wa Age.~roy.pQ')o~x-~~est B.g Determine the R, factor of npqltde (I)for the organ T and age group from o,ppc'o~ae.~~~/(~hJum+r C.Obtain the micro-Curles (CQ of nuclide (I}from the radioactive gas waste management logs for the release source(s)under consideration during the time interval.'D.SolveforD, Di~3 17 X 10 Rl(X/Q)oQ D,~mrem from nuclide (I)T E.Perform steps 2,6.1,B through 2.6.1.0 for each nuclide (I)reported during the time Interval for each organ..F.The lnhalatlon dose to organ T of the specified age group ls determined by summing the D, Dose of each nuclide (I)4\"~~lnhelatlon (Age Gmup)\Refer to 2.6.5 to deteimlne the, total doie to organ 7&m radlolodlnes

&8D Particulates.

-.Xwha4hoa~p~" P~~--+58M.gcivhbt<r g Page 131 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALC LATION MANUAL ODCM METHODOLOG SECTION 2.6 (continued) 3.The Grass-Cow/Goat-Milk Dose Pat wa Method: KQX Tritium dose ls calculated as per 2.6,4.A, A cow or a goat, will be the controlling animal;(l.e., dose will not be the sum of each animal), as the human receptor Is assumed to drink milk from only the most restrictive animal.Refer to Table M-3 to determine which animal ls controlitng based on its (D/Q).P,lng GroaP(s'jj c)0")n~d B.p Determtne the, dose factor Q for nuclide (I), fo)organ 7, fram appnepAa@Mttta ttuw ben+ac me appt{eeet<mi Ik<<~al r t I heW If the limited analysis approach ls being used, limit the calculation to the infant thyroid.C.Obtain the m~urles (Q)of nuclide (I)from the radioactive gas waste management logs for the release source under consideration during the time.Interval;D.Solve for D, 0(~3.17 X 10 R,(D/Q)Q D,~.mrern from nuclide (I)'t E.Perform ste ps 2.6.3.B through 2.6.3.D for each nuclide (I)reported during the time Interval.Only the rad1olodines need to be Included lf the limited analysis appfaach ls used.-.':" t" oat Ht k CowŽ,.Do'Mt',Ml'x.NFL~,i EE-8'AC HI-W~c-9-'-7 G.IO~~~~q~~~~~

Page 132 of 194 ST.LUCl" PLANT CHEMISTRY OPERATING PROCEOURE C-200, REVISION 19 OFFSITE OOSE CALCULATION MANUAL ODCM METHODOLOGY SECTfON 2.6 (continued) 3.(continued)

F.The GrassCow-Milk (or Grass-Goat-Milk) pathway dose to organ T is determined by summing the Dl dose of each nuclide(i).

Deee (or D~)~D,+D,++D=mrem The dose to each organ should be catculated in the same manner with steps 2.6.3.8 through 2.6.3.F.Refer to step 2.6.5 to determine the total dose to organ T from radlolodtnes

&BD Patttcutates.

If the limited analysis approach ls being used the infant thyroid dose via the grassy(goat}mttk pathway ts the only dose that needs to be determined.

Section 2.6.5 can be omitted.O I A.The controlling locations for the pathway(s) has already been determined by: lnhalatlon

-as per 2.6.1A Ground Plane-not appltcabte for H4 Grassy/Qoat-Mtlg

-as per 2.6 SA,>B.Tritium close catcutat ons use thb depte ed (X/Q), instead of (0/Q).Table M-2 describes where the (X/Q)>value should be obtained from.r We P Se.m~~>oP]nMes+C.Jt Determine the Pathway Tritium dose favor (~for the organ T of interest from the Table specied below AGE.INHALATION COW MILK GOAT Infant 8%6-7 65 OC D.Obtain the mlc~urtes (Q)of Tritium from the radioactive gas waste management logs (for projected doses-the mtcreCurtes of nuclide (i)to be projected) for the release source(s)under conslderatlon during the time Interval.The dose can be calculated from a single release source, but the total dose for Control Iimtts or quarterly reports shall be from all gaseous release sources..0 m P<P~erey Melhe$~Mals Og Illa r 40k L.os/13~

2.6.4.The Grass-Cow/Goat-Meat Dose Pathway method: NOTE Tritium dose is calculated as per 2.6.6.A Determine the controlling herd location by: 1.For dose calculations(other than the annual report)the historical herd was determined to be located in Sector at miles.This herd shall be used f'r all ODCM Control required dose calculations.

2.For annual rcport dose calculations the herd from the Land Use Census having the highest (D/Q)at it's location will bc the reporting herd.The Land Use Census for 1978(for example)shall apply to the calendar year 1979(for example)and will locate thc nearest herd in each sector over land.The real (D/Q)will be determined from actual met data that occur?cd during the reporting period.B.Determine thc applicable (D/Q)from Table M-3 for the location(s) of thc herd as tt..tcrmined in 2.6.4.A above.C.Determine the dose factor Ri for nuclide (i)for organ tau from thc Table specified below: Agc Infant Child Teen Adult Meat Dose Factor Table No.N,A.i G-11 G-16 G-21~-The Infant does not cat meat and therefore dose does not apply to this pathway D.Obtain the micro-Curies(Qi) of nuclide(i) from the radioactive gas waste management logs(for projected doses-the micro-Curics of nuclide(i) to bc projected) for the release source(s)under condidcration during thc time interval.The dose can be calculated from a single release source, but the'otal dose for ODCM Control Limits or annual reports shall be from all gaseous rcleasc sources, E.SolveforDi Di 3.17 X 10 Rl (D/Q)Qi t ,~Di mrem from nuclide (i)~F.Perform steps 2,6.4.C through 2.8.4.E for each nuclide(i) reported during the time inteval.G.The Grass-Cow-Meat pathway dose to organ tau is determined by summing thc Di dose of each nuclide(i)

Dose.-Dl D2 tt D3 t....;tDn nnesn Grass-Cow-Meat Excluding Tritium'(Child, Teen, or Adult)s s s J sl~n~~

z~~P~2.6.5.The Vegetation(Garden)

Dose Pathway method: A.Determine the controlling garden location by: 1.For dose calculations(other than annual reports)the historical garden was dctennined to be located in g ctor at miles.'ibis garden shall be used for sii ODCM Consol dose eaicuiations.

2.For annual report dose calculations the Land Census Garden having thc highest real (D/Q)at it's location will be the reporting garden.The Land Use Census for 1978(for example)shall apply to the calendar year 1979(for example)and will locate the nearest garden in each sector.Thc real (D/Q)will be detemuned from actual met data that occurred during thc reporting period.B.Determine the applicable (D/Q)from Table M-3 for thc location(s) of the garden(s)as determined above C.Determine the dose factor Ri for nuclide(i) for organ tau from the Table specified below: Vcgctation Dose Factor Agc Table No.Infant NAP Child G-12~Teen G-17 Adult G-22~-denotes thc infant docs not eat vcgctation and therefore does not apply to this pathway D.Obtain thc micro-Curies(Qi) of nuclide(i) from thc radioactive gas waste management logs(for projected doses-the micro-Curics of nuclide(i) to bc projected) for the release source(s)under consideration during thc time intervah Thc dose can bc calculated

'rom a single release source, but thc total dose for ODCM Control limits or annual reports ahaH be 6am all gaseous release sources.r E.SolvcforDi

-8 Di 3.17 x 10 Ri(D/Q)Qi Di mrem from nuclide(i)

F.Perform steps 2,6.$.C through 2.6.5,B for each nuclide(i) reported during the time interval.I G.Thc Uegetation pathway dose to organ tau is determined by summing the Di dose of each nuclide(i).

r'Dose""~Dl+D2+D3+."......

+Dn~Uegetation...(Excluding Tritium), (Child, Teen, or Adult)-~~~~~P~~s s 1~~*

e Page 133 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CAlCULATION MANUAL ODCM METHODOLOGY SECTION 2.6 (continued}

4, (continued}

E.Solve for D<<D<<~3.17 X 10 R<<(XIQ}t,Q D<<~mrem from Tritium In the speclfled pathway for organ T of the specified age group D l um d-Fro QQTE Control dose limits for I&8DP shall consider dose from all release sources from the reactor unit of interest.A.The following pathways shall be summed to arrive at the total dose to organ T from a release source or If applicable to Control, from all release sourcesl PATH Inhalatlon (l&8D Ground Plane (l&8DP)Grass-Milk (I&8DP Inhaiatlon (H<)Grass--Mll H4)DOSE rem)ole Body only)STEP 0 REF.2.6.1.F 2.6.2.F 2.6.3.F 2.6.4.E 2.6,4.E Doser (sum of abave)~t WuP's B.The dose toNch o)ttreftttPANPB ORGANS shall be calculated:

BONE, LIVER, THYROID, KIDNEY, 1.UNG, WHOLE BODY,&Gl-LLI Al'.C&gP The$NPANT-organ receiving the highest exposure relative to its Control Limit ls ths most critical orgarrjrtsi'ths radtotodloe tt SD particulates gaseous eNuents.p~'p~<~~~r.+~rt zM,)pi~4'Ov Page 13>g r treed rice 2nsek Q4la<<

p~Issue op l9Q T v spry~~%4 F'IEE 4'9q.S4~~.t.~Age Group: INFANT CHILD TEEN ADULT Organ: BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY PATHWAY Inhalation (I&8DP)Inhalation (Tritium)Ground Plane (I&8DP)Grass--Milk (l&8DP)Grass--Milk (Tritium)Grass--Meat (I&8DP)Grass--Meat (Witium)Vegetable Garden (1&8DP)Vcgctablc Garden (Tritium)Do~.DOSE rs>>>>,>>p a4wl)erenee to STEP No.2.6.1.F.2.6.2.F.2.6,3.F.36KB.%.4C E.Remark N.A.for INFANT N.A.for INFANT N.A.for INFANT N.A.for INFANT Page 136 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 4.0 Annual Radioactive Effiuent Re ort Discussion

-The information contained In a annual report shall not apply to any Control.The reported values are based an actual release conditions instead of historical candltions that the Control dose calculations are based on.The Control dose limits are therefore included ln item 1 of the report, for information only, The ECLs in Item 2 of the report shall be those listed in Tables L-1 and 6-1 of this manual, The average energy in item 3 of the report Is not applicable to the St.Lucie Plant.The format, order of nuclldes and any values shown as an example In Tables 3.3 through 3.8 are samples only.Other formats are acceptable if they contain equivalent Information.

A table of contents should also accompany the report, The following format should be used: TL FO 1.Regulatory Llmlts: 1.1 For Radioactive liquid waste effiuents:

a.The concentration af radioactive material released from the site (see<5 Rgure 6.1-1¹F8 A)shall be limited to ten times the concentrations specified In 10 CFR Part 20.1001-20.2401, Appendix 8, Table 2, Column 2 for radlonuclldes other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10~, pCllml total activity,'TS b.The dose or dose corn Itment to a MEMBER OF THE PUBLIC from radioactive materials In uld effiuents released from each reactor unit to unrestrIcted areas (SeetIFlg, 5.1-1~&A)shall be limited during any calendar quarter to<<1.6 mrem to the whole body and to<<6 mrem to any organ and<<3 mrem to the whole body and<<10 mrem to any organ during any calendar year.1.2 For Radioactive Gaseous Waste Effiuents:

a.The dose rate resulting from radioactive materials released in gaseous effiuents to areas at or beyond the SITE BOUNDARY (See TS Figure 6.1-1)shall be limited to the following values: The dose rate limit for noble gases shall be<<500 mremlyr to the total body and<<3000 mrem/yr to the sMn and~~

0 1 Page 137 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE D A N AL ODCM sKoeor~4.0 (continued) 1.(continued) 1.2 (continued) a, (continued)

I: The dose rate limit from l-t3t, l-t33, Trltlum and parttoutates with half-lives

~8 days shall be g$600 mrem/yr to any organ.b: 'll t 1 (tRg~'I1lR+rl&AI d t dhg released In gaseous effluenti, from each reactor unit, to areas at and beyond the SITE BOUNDARY.shall be limited to the following:

During any calendar quarter, to+mrad for gamma radiation and<10 mrad for beta radlatlon and during any calendar year to<10 mrad for gamma radiation and c20 mrad for beta radiation c.The dose to a MEMBER OF THE PUBLIC from I-131, I-133, Tritium and all radlonucllde'n particulate form, with half-lives

&days In gaseous effluents released from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1 In the TS-A)shall be limited to the following:

During any calendar quarter to c7.6 mrem to any organ and during any calendar year to c16 mrem to any organ.2.Effluen Limiting Concentrations:

Air-as per attached Table 6-1 Water-as per attached Table L-1 3.Average energy of,fission and activation gases ln gaseous effluents ls not applicable to the St.Lucis'Plant.

~~4 r~~,~r=rsrr'r',>~r~'~~ts4>

Page 139 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E CALCU Tl N MANUAL OD M METHODOLOGY SECTKl 4,0 (continued) 4.(continued)

~TA L~E R lOACTIVE LIQUID EFFI.VENT SAMPLING AND ANALYSIS LIQUID SOURCE MONITO TANK/RELEASEte STEAM GENERATOR 8 LOWDOWN RELEASES SAMPLING FREQUENCY EACH BATCH MONTHLY COMPOSITE QUARTERL OUR PER MONTH MONTHLY COMPOSITE QUARTERLY ITE TYPE OF ANALYSIS PR IP MrITERs Sr%9, r-QO,@45 PR IPAL MfTTERS AND DISSOLVED GASES re&, r-90, Fe-65 METHOD OF ANALYSIS P.h.a.LS.,F.P.C.S.~P.h.a, LS.,F.P.C.S,~S.TABLE NOTATION: Boric d Eva tor condensate is normally recove to the ary at r Tank fo cling into r coolant an no I does not contrl e llqu waste e uent tota.N N, I~p.h.a.".-gamma spectrum pulse height analysis using Lithium Germanium detectors.

All peaks are ldentNed and quantNed.L,S,-Uquld Scintillation counting I I I'C,S.-Chemical Separation,.I'.F.P.~-Gas Flow Proportional Counting I'I I~Nt~~~~~~II~~'~

Page 140 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALC LATION AN L M ODOL GY E 4.0 (continued) 4.(continued) 339~~MR RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSlS GASEOUS SOURCE Waste Gae Decay Tank Releaeee Containment Purge Releasee SAMPLING FREQUENCY Each Tank Purge our per Month TYPE OF ANALYSIS Prlnclpal Gamma Emltlere rlnclpal Gamma Emlttere Prlnclpal Gamma Emlttere METHOD OF ANALYSIS G, p,h.a.G, p.h,a.S., C, P)-p.h.a.L, Plant Vent tParticulatee)

Quarte e (Partloulatee)

Sr%0 Sr%9 Cg,.F.C L.S.C.S.p.h.a.G.F.P.Gaseous Grab Sample Charcoal Fitter Sample Particulate Filter Sample Uquld Scintillation Counting Chemical Separation.'

Gamma spectrum pulse height analysis'using Uthlum Germanium detectois..'All peaks are identNed and quantNed.C'as Flow Proportional.Counttng 0

Page 144 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION t9 OFFSITE DOSE ALC LATON MAN AL DCM METHODOLOGY SECTION FLORIDA POWER 6 LIGHT COMPANY ST.LUCIE UNIT tt ANNUAL REPORT-~~THROUGH~~TABLE 3,3: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES IcMMl aaiiiaijt clSR TB~A.Fission and Activation Products 1.Total Release-(Not including Tritium, Gases, Alpha)Ci E 2.Average Diluted Concentration During Period 8.Tritium Total Release.~L~lttttlt'E CI~ttttt E E pci/il CI 2.Average Diluted Concentration During Period.C.Dissolved and Entrained Gases Total Release'l 2..Average Diluted Concentration:,,c,~'~f During Period..1 D.Gtoaa Alpha Radloactlvtty 1.Total Release-'I c Il~~4 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E ALCULATION MANUAI ODCM METHODOLOGY E ON FLORIDA POWER 8 LIGHT COMPANY ST.LUCIE UNIT ff TABLE 3.5 LIQUID EFFLUENTS-DOSE SUMMATION Ago Group: Adelt-Exposure Interval: From Fish 8 Shellfish Pathway to Organ BONE LIVER THYROID KID L N Gl-I WHOLE BODY Location:*wpAttott Through CALENDAR YEAR DOSE (mrem)

ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATI MANUAL ODCM Page 158 of 194 TASLE I=2 IIRONINENTAL PATHWAY~SE CDNVERSION FACTORS FOR UQUID DISCHARGES PATHWAY-SAI.T WATER RSH AND SHELLRSH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)G8-137..8.79E4$GS-138-6.08EAS BA-139-.'JPEAN.BA-140..-1.65E+03-.-=LIVER'=.120E+04

-12DEW1--,5.61HS 0.0.0.0., 8~+00 5%4E~.7.04E<1~LUNG 8.73E&1 3.18E~1.18E+00 Gl-Lu 2.31E+02 5.12E~1 ME+01 3.39E+03 WHOLE BODY 7.88E+K 5.96E+00 2.30E41 1.09E+02 BA-141;~0.0.1.64E~f29E<1-BA-142'-.1.73E+00',.=;-1.78E~-0.1.01E~0.1.09Et: LA-140'-.:.158E+00

-=LA>>142-"=-8.0?E42 735E41 3.6?EH)2 0.0.0.0.0.0.583&04 2.68E+02 2.11F%1 9.15E43--GE-141"-.343E~0.0.8.87E+03 GE-143 6.05E%1 W-187-9.17E4$35SE42 NP-239 GE-144.1.79EA2 PR-144.191M2 4.47E+02.7ASE+01 7$8E~7.68E+00 350E~0.Q.0.0.0.1$7E+1 4A3E+01 4.45E~0.1.08E~0.0.0.0.Q.1.67E+04 6.05E+04 2.73E49 251 E+03 7.12E+02 4.95'.60E+00 9.65&)4 2.69E+00 1.92E~Based on 1 pCI/sec telease tate of each hotope in dhcharge flow of 1 cc/sec with no additional dilution

=NVIRONHENTAL PATHMAY COSc CONVERSIOH FACTORS FOR LIOUIO DISCHARGES PATHVAY SALT HATER FISH ANO SHELLFISH ACE CROUP Tii NACER NUCLIOE Neeee3 0~BONE ZeiTE 01 zeiTE 01 ORGAN DOSE LIVER THYROIO FACTO KIDNEY Zel4c 01 TH%EH/HR LUNG 2e17E 01 PEP.UCI/HL l CI LLI 2 irE'i N TOT)~17'/H~

Z>>ll E-a 1 NA Peee32 CR 51 Hgee54 HNe-56 Fc 55 FE-59 CO-57 CO 58 co-&a NI 65 CU 64 ZN-65 ZH-69 BR 82 BR-83 8%-84 BR 85%8e 86 RB bd FB 89 SR-89 SR 90 cR 91 SR 9Z Y-90 Y--91H Y-e 91 Y-9Z Yeee93 2%95 ZR 97 NB 95 NB 97 HO-99 TC 99H 4e63E 01 ie 27c+Ol 0~5e Oe be 78E+04&e ivEc<<04 a.Ee Oe 1~54E+OZ Oe ie23E+05 Z~61E+0 2 Oe ae a.ae Oe 0~ae 5e6lc+D3 ieZOE+05 7eidi+01 Ze66E+01 1'88+01 4'6Ee02 9e40i+Di 4'6E 01 ieZ9E+OD 1~49E<<ai 6~72E 01 3e97E<<02 2~blE+OD 0~9eblE 03 4e&3E 01 le98E+05 Oe Se38E+03 ie3&E+02 3e95E+05 le4&E+05 ieadc+02 be 1ZE+02 ieTOE+03-, 2e DOE+01 ie&4E+OZ 3o 90E+05 Seazf+02 0~Oe 0~0~4e 76 E+0 2 1.37E<<00 9ea4E 01 0~Oe 0~0~0~0~0~0~D~4e96E+00 le36E 01 2o39E+02 7e24E 01 9o 74E+01 Ze79E 02 4~63E 01 4~63E Oi 0~a.D~0~0~F 0'~0~Oe 0~0~0~0~0~0~0~0~0~0~0~0~0~0~0~0~0~0~Oe 0~D~0~Oe 0~1 6aE+03 ieTZE+02 0~0~0~0~0~a 4~12E+DZ 2e&1E+DS 3e24E<<02 0~Oe 0~0~0~Oe 0~Oe Oe 4~Oe Oe 0~0~Oe D~6.1&E<<aa Ze05E-01 1~88E<<02 8 F 456 01 ZeZic+02 4eZ4f.01 D~0~Ze54E+OQ 9e38Eeai 4e63Eeai Oe 5.64E<<aa Oe 0~4e57E+05 4eQSE<<04 0~0~0~0~De Oe 0~Oo Oe Oe 0~Oo 0~a.de ao 0~0~iebOE<<04 0~0~0~Oe 0~0 0~0~go 1~37E-02 4~63E 01 ie43E+06 iealE+03 1e&SE+04 4e3ZE+03 ie54E+05 4ebiE+05 Ze74E+03 8~26E+03 Ze04E+44 5~QTE+02 1~39E+04 Ze46E+05 7~50E+01 3'5E+00 le95Eeaz 5e61E OT a.9'TE<<01 0~Qe 6e15E+OZ 2 liE+D3 3'1E+OZ 5e25E+OZ S.Z3E+a4 1~ZSE 01 3~61E+04 lelaE.+03~08E+04 1~Ol'6+04 4~ZOE+04 9'&E<<05 Z~&lE<<03 Ze26E+OZ 1~65E<<81 Oe Oe Oe 0~0 4>>Oe e 0 0 Oe 0~Oe Oe 0~0 0 4~63f.Dl 4o93&i05 4'SE<<00 le 03c<<03 2.4ZE<<01 lea4E<<05 5.55t<<04 1~746<<OZ le39Eea3 3'8E<<03 88 9e ill<<00 7~69c<<01 ioTTE<<05 3~47E<<01 3e 10ic<<00 5'2E-02 le 16E-OZ Ze94E 03 2~2ZE<<02 Te Z3E-al 6438E 41 1~63ioaz 3 alii<<04 3e 16c<<00 1.15ioaa 4~ZSE Dl 1~69E-03 2'li<<00 lotbc 02 3155E-02 3.4&ieaa 6~Z4E 02 lo 35f e OZ 2~64E 01 1~85E<<01 3e 5&i-01 BASER nN i Hnf/CCI CCI CeeC~ee 0

cNVIRONNENTAL FATHttAY OOSE COHVERSION FACTORS FOR PATHMAY SALT HATER FISH AHO SHELLFISH LIGUIO OISCHARGES AGE GROUP-TEE HAGER HUQ.IOE ORGAN 0GS FACTO R I NAf.N/HR PER UCIIHL1 at'-t I q',.cJ i to t"~r.TC 101 Ruo103 RU 105 FU 106 AGjjaP SS iZ4=SS 125 Tf 125N Tc jZTN TE 127 Tc 129N TE 129 TE 131N TE 131 TE 132.130 I--131 I 132 I 133 I 134 I 135 CS 134 CS 136 CS 137 CS 138 BA 139 BA-140 BA 141 BA 142 LAoj40 LA 142 CE 141 CE 143 Cc 144 PR 144 N 187 NP 239 BCNE 1~42E-02 1~04E+02 6o77E+00 1~76E+03.io 19E+03 Ze iif>02 1~68E+02-Zo36E+02 4oldf+02 9o 31E+00 1~QZE+03 io94E+00 1~OTE+DZ 1~21E+00.2ei9E+OZ-3e QSE+Oi 2e 23c+OZ , 8~1 jf>00 8~iiE+Qi 4e24E+aa 1~77E+Oi 6o75E+03 5e46E+02 8~9dE+03 4'3E+00 5'9E+00 1~TSE+03 0~1~31E+0 0 1~67E+00 6 14E 02 3~51E+40 4.eaE-ai 2~Oic+02 io45f OZ.6~98E+00 2elif 02 LIVER io47E 02 Oo 0~0~ioiaf+G3 air Soggf+00 1e diE+00 do45E+Oi.io46c402 3oZdf+00 3e79E+02 le34fea j 5o 2ZE+01 5oadfea j 1~3lE+02 do 95E+01 3ei46+02 ZeilE+Oi ioSTE+02 iei5E+Cj 4eebftai 1~63E+04 Zoi6E+03 1~21E+04 9.jsfioo 4o 27fe 03 Zojsftaa 2oZOEo03 io35E OS do25E 01 Zelgfe02 2o36E+00 Se40ft02 do 25E+0 1 5o99E 03 5ob5f+00 Zo67E 03 THYROIO 0~0~0~a.0~5oiiEooi 1 o49E 01 6'6c+Oi 1 alf+QZ 6e35E+00 3oZTE+02 je49E+00 boZ6E+bi 9o99E 01 1 4ef+02 ioj4E+04 gooTE+04 2'eftaS 2~SQE+04 io49E+03 ee jif+03 a.0~0~0~a 0~0~0~0~0~0~0~0~0~0~0~KIONEY 2e64E ai 3e iiE+02 do74fiaj Ze34f+03 ZoilE+G3 0~0~eoTZE+CZ irlof+OS Ze 76E+01 Zo96E+03 be14f+00 5e29E+OZ 5e33E+08 9ol4E+OZ io39E+02 4oadE+OZ 3o46E+0 1 ie 73E+OZ iod3E+ai le43f>0 j 4~OSE+03 jeZQE+03 SeiiE+03 6ol3E+04 3o99E 03 5o35E 01 Zeaafo03 io 14f 03 0~0~bo jgfea1 jo50E Qi 3e3TE+Qi 3o39fe03 0~beZ5E 03 LUNG 7 4lc OS 4~0~0~4~1 64E+02 io lsf+04 0~ao 0~0~0~0~0~0~0~0~4~a.a 0~1~9lE+03 io65E+OZ ie60E+03 e.eSf-ai Z~42c 03 1.44E+00 1~Z5E-03 7.64E-04 0~S~0~0~0~0~0~0~GI-LLI Oe do 13E+03 4oi4E+03 le 9SE+04 4'if+45 5.98E+aS io48E+43 6'aft02 ie40f+Q3 7'ZE+8Z Sesdf+03 1 46E+aa idc+43 1~82E bi 4'3E+03 Teelf tai 5e95E+41 4'8E+44 9'9E+Qi ie04E-02 5 ZSE+aj 1~88E+42 2'5E<OZ 1~61E+02 3~94E 05 io06E+01 2e5SE+aZ 1.37E-ag 0~4.55E~04 2'4E+02 6'8E+03 ieZTE+04 74E+O4 Zoodf-09 io9ifo03 5~43EIQZ Oe Oo a.0 a.4o 4o a.a a a.0~Qo oe 0~RCT5t~&tY~~wt}0LE 1~44E 01 4~eef+oj z~elf+00 ZeZjf+02 6o56f+OZ 8~35E+Oj 3o3Tcoai So 13fiai soagfiaj 1~99E+Qa 1~ejf+Gz 4~TZE-01 4~SSE+41 3~83E 41 io 30f.<4Z 3~SZE+01 joblfioZ 7~Tjf<00 4~24E+Oi 4o iZE<00 1~71E oai T~eof<03 1~55E+43 4e24E<43 4o54E<00 1~Tsf-Qi ioiZfiaZ gobaE-OZ 8~26f OZ Z~idE 41 6~95E 03 ZoTOE-41 3'6E QZ 1~OTE+01 To 34E 04 2~Ost+40 1.4ef-oj o RASED ON 1 UCI/SEC PELEASE RATE OF EACH ISOTOPc YM hYCl'Hoocc o I~u

ENVIRDNHcHTAL FATHKAY DOSE CDHVERSION FACTORS FOR LIQUIO OISCHARCES PATHKAY SALT HATER FISH AHO SHELLFISH AGE GROUP CHILO HUG LIOE Herr>>3 KA>>r24 32 CR 51~N 54 KH 56 Fc 55 Ff 59 C0-57 Ca-55 CO 60 , HI-65=CU or 64 ZH 65 ZH 69 BR-52 BR 53 BR 54 8%55 RB 56 RB 85 RB 59 SR 59 SR 90 SR 91 SR 9Z Y r 90'r>>91H Y-91 Yrr>>92'Yrrr93 ZR 95 ZR 97 NB>>-95 NB 97 HO 99 TC 99H BCNE 2>>03fr01 5'3E+06 Oe 0~De 3~57Et04-2>>71E+44 0~Do 0.6>>73Etoi Oe 5>>47E+04 1~16c+0 2 Oe De 0>>4~De De 0~Te53Et03 9>>39E+04 3>>idE+01 leidE+01 9>>DOEtDO 1~95E 02 1~25E+02 i>>die 41 5~73E 01 1~dof+01 2>>91E 01 4~61E+02 1~24Et00 Oo 4'4E 03 LIVER 1~51Er01 2>>03Ero 1 3>>47ft05 0~2e34E+03 5 85Etoi 1~T4ft05 6>>43Et04 4>>78Et01 5>>05Et02 1>>4l,f+03 be74Et00 7>>15ct01 74E+05 Ze 23 E+02 0-0~0~0~2>>08Et02 5>>96E 01 3>>95E 01 a.a.0 0~0~0.0~0~0.4>>19E+00 5>>87E 02 1~97c+02 3>>1ZE 01 4>>Z3E+01 i>>23E 02 A H DOS THYROID f~61E 01 2~03E 01 Oe 1~1Zctoo 0~0>>0>>0~0~0~oe D~Oe 0~0.0~0~0~0.0~0~D~0~a.0~0~0~0~0~4~0~4~0~0~0~0~0~i FACTOR KIDNEY 1~19i 01 2>>03E 01 Qe 4>>13E 01 6>>95Ftoz 7>>46E+01 0.0~0~0~8~0>>ieboi+02 ief&ft05 ie44E+02 0~0~0~0~8~be 0~0~0~0~0~0~oe 0~a.oo 2>>&TE+00 6~56E 02 8~iii+01 3>>64E 01 9'9ctoi 1>>56E 01 (NREH/HR PER UCI/HL)r r'UNG GI-LLI~1>>51E-41 1>>51E-01 2>>d3E bi a.Ze48E+~0 0~0~Z.0Zi+05 1~79E>>04 0~0~4~0~0~0~0~0~0~4~0.0~0~Oo Qo 0~0~0~~o 4~0~0~0~4~0~0~4~0~6>>oif r03 Z>>03E 01 6e2ZE+05 4>>TOE+02 7 15Et43 1~bdct03 6>>dec+04 2e 12Et05 1>>Z1E+03 3 OQF+43 le 80E+03 2>>22E+QZ 6>>09E+03 1>>49c+45 3>>34E+01 1~59f+08 3>>55E-OZ 2e5if 07 0>>4~09E+01 Oe 0.Z>>51Et42 le 2SE+03 ie60E+QZ 2'3i+OZ Z>>STE+44 5'1c 4Z 1~66E+04 3>>1&f+03 1>>bzc+04 4>>33&+03 iodzf>>44 3>>41E+05 1 o 15E+03 9>>bif+01 Tez&ftoo Oe 0~0>>0 0>>0>>4>>0 0>>0~0>>4>>Oo 0~0 Oo Oe Oo Oo Oo 0~0 4>>~~POT W~Sy'~bii-01 2~D3E-01 2'4ft05 1~57E+00 4'6E>>OZ 1~05E eoi 4e55E t DC 2-45ftoc 7~94E+Dl 1'2ft03 4~23f t03 55E'3'5E+40 3>>36ftoi 7'6E+04 f>>SSEtof 1~39E+OO Z 4TE-DZ 3>>ZOE-02 1>>3ff-03 9e65Etbf 3'6f-oi 2>>7bfr01 Ze16ftoz Z>>3bft04 1'0E>>00 5>>Odf-Of 2~CZE of 7'5E-04 3~34E>>OO 5'bf.03 1~Sbf 02 3.bfcftOO 2~Tof DZ 1~45ftoz iofCE 01&~OSE<00 f~STE 01 BASED OH 1 UCI/Scc RELEASE RATE OF EACH ISOTOPE IH OISCHAROE FLOK OF CC/SEC KITH NO APOTTIttetl ntc<it tnt

t.
cNVIRGNNEHTAL PATKMAY DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHMAY SAlT HATER FISH AND SHELLFISH AGE GROUP CHILD NUCLIDE ORGA'N DOSE FACTO R (NREN/HR PER UCI/HL1 TC>>101 RU>>103 RU 145 RU>>106 AG1 igt SB 124 SB 125 TE 125H Tf 12TH Ti-izl TE129N Tc 129 TE131N TE 131 TE 132 I 134 I 131 I 132 I 133 I 134 I 135 CS 134 CS 136 CS 137 CS 138 BA 139 BA 140 BA 141 BA 142 LA 140 LA 142 CE-141 Cc 143 CE 144 PR>>144 N>>187 HP 239 BCNE 4>>47E 03 io 33E+02-3o 03E+00 2~34Et43 5oidftOZ 9o 13E+Oi lo 24E+41 3o iiE+OZ iob5E+42 1~Z3E+Oi 1~35E+03 de59E 01 4o75E+Oi.'5e38E 01'2~lbft02 1e33Et01 2eblE+42~3>>57E+00 io05Et02 io86E+00 lo79E+00 8 e14E+03 2e37E+OZ fe 13ft04 Zo 01E+40 Zo 65E+00 2o25f+03 0~5obif 01 2>>16Et00 2~74E DZ 67E+GO z.05E-01 Z.66E tOZ 6o46E 03 3'3E+DO 1~ibf 02 LIVER 6o45E 03 0~4~0~4obdf+02 1,~72E+00 7o DOE>>01 bo43E+Oi 6.47E+01 3o ZTE+00 3o 77 f+02 3e25E Oi Ze31E+41-Z>>25E>>01 ie23E+02 3o94f+Oi 2o94E+02 9o55E+00 ie30E+02 5o 06E+00 2o 46E+Oi fo37Ft04 9o34ft42 Ceidft44 3o 96E+04 1 ob9E 43 1098Et 00 9eT1E 04 5e98E 04 T>>52E 01 ie24E>>02 2o34E+04 fo52E+02 be33Et01 Ze 67E>>43 2>>54Ftoo 1 o f 6E>>03 THYROID Oo 4o 4~de 4~2>>21E>>01 6>>43E OZ de73Et01 4'ZE+41 de46ft00 4>>31E+02 6>>58E 01 3>>66Et01 4>>42E bi iebiE+OZ 5~01Et03 9o55Et04 1e26E+03 3>>13E+04 6e5dEtOZ Z~69Et43 4~0~0~4~0.0~0~0~0~0~0~0~0~0~0~0~KIDNEY ioi6E>>01 io39Et42 3o9ift01 1005E+03 9e43F+02 0~0~Ze9lE+02 le 50E+02 ie 22C+Oi ie 31E+03 3>>60E+00 2>>34E+02 Zo36E+04 4o3f E+02 6oiZE+Oi fe79Et02 ie52E+Di 7e61E+01 boDTE+DO 3o27E+Oi io75E+03 5ezDftDZ 1o 35f+03 Z>>9ZE+00 ioTTE 43 Zo3TE Oi 9>>03E 44 5'5E 04 0~e-3o66E Oi 6o69E OZ 1~50E+Oi 1~Sif 03 0~3'8E 03 LUNG 3ozgf 03 0~0~4~Oe le48E+41 To57E+03 0.)~0~8~0~0~0~0~0~0~0~do 0~0~1.52Et03 lo13E+81 ie29E+03 2obbE Oi 1~OTE-83 ioibft00 5o5if-04 3o 38f 04 0.0~0.0~0~0~0.GI LLI 0~3'0E+D3 io85E+03 3.63E+04 io96E+05 2 58E+03 6o40E+82 3.00E+OZ 6~19E+02 5 24E+02 1>>63Et03 6>>4lE 01 2'9E+03 8~05E OZ 2>>15ct03 3'8E+01 2~51E+Oi 1>>79Etbb 5.26E+01 4~41E 03 Zo 30E+Oi 7.42E+01 1~46f t02 6~69E+Di 1~69E 45 4~69f+DO 1 ei5ft02 6~06'E 10 0~Z~14E+04 9~49E+01 Zo 93E+03 5'7E+03 2e 16f+04 9~Z6E 10 8~31f+02 Z~36'6+02 D~de 0~0~0 Oo 0.0~0 0 0~Oo Oo Oo 0~0 0~Oo 4fR4lr-DOOV UIHCiG S40y'~33E OZ 5'bftOf 1 fgft00 2o91C+OZ Ze 85f tOZ 3~61'E+01 1~46f t Oi 4o 15f tOf Zo 256 t01 2o 636 t 00 2o 09C.t 02 Zo 49E-41 1 e 93E+41 1 o TOE 01 fe48Et4Z 1~55Et01 Ze Zzft02 3'9ft00 5~iOE+01 febift44 To 54Et 00 Zo9ZCt03 6o73ftdz io 64Ct 03 fe9TE+00 7o75f-OZ 1~3zf tOZ 4o 34C 02 3o 66E-OZ 2~54f D1 3~106>>43 3o48E 01 io 68E-OZ fe4zftbf 3~Zl f 04 bo90f-41 6'4E 44 BASED OH 1 UCI/SEC RELBASE RATE OF'EACH JSOYO>f 0 0 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE G-7 ENVIRONMENTAL PATHWAY~SE COXVERSIOX FACTORS R FOR GASEOUS DISCHARGES PATHNAY-GOATS NLK (CONTNINATED fORAGE)AGE GROUP-INFANT ORGAN DOSE FACTOR (SQ.METER-MREM/YR PER pCi/Sec)NUCUDE SN-126 2.10E+08 SB-124 390E~4.17E+06 THYROID 7.9?E~0.0.KIDNEY LUNG 256 E+06 Gl-LLI 1.40E+08 9.33E+07 WHOLE BODY 6.30E+06 SB-125 4.31&06 TE-125M 1.89E+07 TE-127M 6.64E+06 TE-129M 7.05E+07, I-130.5A5EAS I-131 3.11E+09 I-132'.13E%1-I-133 450E~0.I-135 CS-134 1.33E+11 CS-136 894E~CS-137 1.93E+11 BA-140 2.95E+07 CE-141 3.17E+Q4 3.92E+05 6ME+06 231 E+06 2.42E+07 1.61E+06 3.70E+09 5.71E%1 6$7E+07 0.4.72E+04 239E+11 32SE+09 2.1 BE+11 2.96E+04 1.95E+04 621 E+QB 2.15E+OB 2.66E+07 2.05E+08 1.19E+12 7$1E+01 1$5E+10 6.1 BE+06 0.0.0.0.0.4.76E+05 8ABE+06 2AOE+07 323E+07 K51E+06 9.10E%1 1$5E~0.7$1E~1ME+10 1.83E+09 1.10E+10 1.47E+03 1.1?E+03 3AOE+08 0.0.0.0.0.0.0.0.2.42E<1 2.74E+10&51 E+08 2.61E+10 181 E+04 0.2.92E+07 9.09E+06 3.88E+07 425 E+Q7 1.38E+08 1.39EAN 1.0?E<1 1.17E+07 0.5ME+04 5.69E+08 3.74E+08 589 E+08 9.76E+05?.94E+05 2.52E+06 8.85E+05 1.0?E+07 6.35E+05 2.17E+09 2.03E-01 1.99E+07 1.?3E+04 2.02E+10 2.3?E+09 1.24E+10 1.52E+06 2.28E+03 CE-144 2$2E+06 9.95E+05 I 0.0.1.36E+05 Based on 1 pCtrsec release rate of each isotope ln and a value of 1.for XIQ, depleted XlQ and relative deposition.
Note: The units for C-14 and H-3 are 1MREM/Yr per pCI/Cu meter.
%~LE.G--8 EHVIROHHENTAL PATHIIAY DOSE COHVERSIOH FACTORS Rlil FOR GASEOUS DISCHARGES PATHMAY INHALATION AGE GROUP CHILO NUC IOE~0 R G A N 0 0 S E F A C T 0 R S<HREH/YR PElt UCI/CU<<HETER)
>>\>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>><<>>>>>>>>>>>>>>>><<>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>
<<>>>>>>>>3 BGHE De LIVER THYRCIO KIOHEY LUNG GI LLI~~R wing~gpgg 7 51E+DZ 7 51E+02 4 96EtDZ 7 51E+OZ l 51E+02 0 7~51EtOZ P 32" 6<<11Et 05 CR 51 DE HN>>54 0~FE 59 5'CEt03 CO>>>>57 DE CO 50 0~CO 60 Do ttf ZN 65'50E+04 RB<<06 Do SR>>d9.5<<37E+04,=
SR>>90~1<<64E+07." Y 91.7<<44Et04.: ZR 95 1<<41Et04..-
, HB 95-:1<<7DE+03
.FU<<103, 2<<16E+02 RU<<106 1~15E+04 AGi1 DP'~0 DE+03 3<<57E+04 Do ieb3E+04 i<<ZDE+D7 3<<20E+D2 1<<52E+02 1.07E+03 Ce77E+DC 6<<25i+04 De D~0~3<<Zb E+03 l<<25E+02 0~0~4<<63E+03 0.2<<75E t01 D~D~Do 0~0~Do 0~0~0~De 0~0~Do 0~Do 0~1~06E+01 Ce55E+03 0~0~0~D~3>>19E+04 D~0~0~0~Z>>51E+04 3<<50E+03 ZolDE+03 6~idE+DC 9<<10E+03 0~6<<66E+03 6<<40E+DS 4<<70E+05 1~71Et 05 1<<13E+46 6>>92E+06 C<<03E+05 0~2<<24E+06 1<<40E+07 Ze55E+06 Ze 1ZE+06 5>>05E+05 6<<33Et05 1>>45E+Dl Z<<15E+06 CeDDE+04 1~5CE+03 3<<50E+04 0 elOE+04 1.45Eta4 3'2E+44 9'6E+OC 2eC7E+04 7.70E+03 1 69E+05 3 CSEt05 1<<ldE+05 5<<74Et04 3~3ZE+DC 4 ZZEt44 4'7E+05 1~CDE+45 4<<0 Ze 3ZEt 04 4'3Et41 2<<91Et03 4~bbit03 3<<10E t02 2'4EtOZ 1'dft03 Z<<15EtDC 0 2<<73Et04 1<<54E+03 9<<99ft05 1<<9DEt03 2'4Ee03 5<<33EtDZ 0 73Et41 1'4Et03 2.75Et03 BASED OM 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AHO A VALUE OF 1 FOR X/O~OEPLETEO X/0 AHO RELATIVE DEPOSITION
=hVIROHHENTAL FATHHAY DOSE COHVERSION FACTORS R(il FOR GASEOUS OISCHARG'ES PATHMAY o IHHALATIOH ACE CROUP CHILO r j~~r r J.~rjj tj.':~II j NUCLIOE SH 123 SH 126 SBoize','B 125 TE125H TE 127H=TE 129H I 130 I 131~'132 I 133.I 134'=I 135 CS o134.~CS 136'.CS 137-'-BA 140 CE-141 CE 144~-~j~~BONE 3'5E+04 5'5E+05 1~44E<04 3o06E+04 5o 62E+02 5'5E+03 1~64E+03 Zo 12E+0 3 Co55E+0>>5o37E+02 io68E+04 Zo98E+02 ioZ4E+03 6o22E+05 1odic+04 bo66E+05 7 o 14E>>03 3e 13E+03 5~81E+05 LIVER 6o44iP02 1.55E+OC ZorZEt02 3o38Etaz io94Eiaz Zo60Et03 So85fPGZ 6ozzEt03'.-Co63E+04'51E~03 2o05E+04 lo99E+02 3e23E103:." 9.95E+05 6.77&04 le99ct05"Co66E+00 1o57E+03 iebZEta5 THY RCIO 6~biE<02 Ce55E+03 3~49Etai 2o7ZE+01 ie6iE<02 io52E+03 So40E+OZ doarE+05 1~54E>07 Ze 03i>05 5o03E+06 io06E>>05 4e33E+05 a.0~0~0~0~8~ORGAH OOS 0~0~0~ao 5erCE+03 2oizE+04 ie69E+04 9e66E+03 2ebCE+04 2o48E+03 io20E+OC iozlc+03 5oiCE+03 io33E>>05 3o96E+84 io03E+05 7073E+00 Zo98E+03 3o9ZE+05 3eSOE+06 4o33E+06 io 15E+06 1.OZE+06 4ediE+05 CoCCE+05 iobOE+06 Oe 0~Oo 0~bo 8~ie19E+05 So55E+83 iodaE+85 ielCE+06 5oiCE+85 ie23E+Ol 1~49E405 5'dE+bC 1~88E+05 Co66E+04 3'bE+04 6e92E+04 iod2E+05 3e56E+03 Ze6SE+03 iodbE+OZ 5o55E+03 Ce66f 01 Ze43E+03 3orrE+03 5eCOE+03 3e41E+03 9e92E+03 5oCCE+04 aaE+aS 0~ao 0 0 E F A C T 0 R S tHREH/YR PER UCI/CUo HETER)o e&&e o o e e e e rr e%&oo e o o e oe e W XIONEY LUNC OI LLI WACS BOG+1~2TE+03 2~ZZE<04 5.74Et03 6o 14E+03 ro 62Eiai ro 25EIOZ Z~60E+OZ Zo45Eta3 3o50E+04 5'7E+02 boa3E+03 2obSE>02 io 19E>03 2o 23E+05 So 14E+04 25E+05 C.ZZEt 02 Zo33E~CZ 3olOEI04 BASEO ON 1 UCI/ScC RELEASE RATE OF EACH ISOTOPE IH AHD A VALUE OF 1 FOR X/Q OEPLETEO X/O ANO RELATIVE OEPOSITION
-bme5779 ENVIRONNENTAL FATHNAY OOSE CONVERSION FACTORS R(I)FOR GASEOUS OISCHAPGES PATHllAY CONS HILK (COHTAHINATEO FORAGE)AGE GROUP-CHILO Ha>>a>>3 0~~~r P 32 1>>b2E+10 CR 51 0~tlH a>>54 Oo FE>>59 3>>1?E+07 CO 57 0~CO 5b 0~CO 60 0>>ZH 65'>>46E+09 RS b6.0>>SR b9.6>>9ZE+09 SR 90 1>>13'E+11 91.'-3>>SOE404 ZR 95 io 06E+05 HS>>95'>>75E+05 RU 103-3e99E+03 RU>>106.9>>39E+04 AG110PC 6>>21E+07 1>>57E+03 io 14E+09 0~S>>96E>06 7>>52Et07 i>>36E4'06 ie 25E+Dl 4>>22E+07 4e65E+09 2>>77 E+09 0~0~0>>4'7E+04 i>>ibE+05 0~0~5e 75E+07 1~5?6 103 1~04E+03 ie 57E+03 1>>57 E+03 0~iobZE<04 0~0~0.0>>0>>0>>0~0~0>>0~0~0~0~0~0~0~6>>TZE+03 2>>67E+06 Oo bo 0~0~3>>116+09 0>>0~0~0~iob6E404 4>>b4E404 4>>16E+03 4.20E+04 1>>13E+OS 0~4'4E+04 de Z>>09Et07 0>>0~0>>0>>0>>0~0~0>>0~0~0.Oo 0~Zo 05E+09 T>>66E+06 2>>T4E+OT 2>>4SE+Db 3>>46E+07 l>>41F+OT 2'33E+Ob 2e 93E+09 5>>45E+Ob Z>>5SE+Ob i>>52E+09 5>>05E+06 7>>6SEiBT 2>>03E+Ob i>>05f+05 1>>46'E+06 2>>35E+10" HUCLIOE 0 R 6 A N 0 0 S E F A C T 0 R S lSO HETER tlREH/YR aaa>>aaaaaaaaaaaaaaaaaaa>>aa SORE LIV ER THYROI 0 KIDNEY LUHG GI LLI PER UCI/SEC)4 HO+S<Oy i>>5?E>>035E>>OS 3e 05E+04 7)E>>06 2>>S6E>>07 2>>2?E<06 3'66>>07 1~2?E>>OS Zo 10E+09 io 29E+09 i>>9dE>>0b Ze b?E+10 io 0)E+03 3>>29E>>04 be 63%+04 1'iE>03 io i?Et 04 3.42Eio?k4I SASEO OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE Itl AHD A VALUE OF 1~FOR X/0>>OEPLETEO X/0 AHO RELATIVE OEPOSITION NOTE'HE UNITS FOR C 14 AHO H 3 ARE lHREH/YR PER UCI/CU>>tlETER) h 0
~a5LF c.-9 EhVIROHKEHTAL PATHMAY OOSE CONVERSION FACTORS Rlil FOR GASEOUS OISCHARGES oATHMAY-CONS HILK CCOHTAHINATEO FORAGE)AGE GROUP-CHILO NUCLIOE 0 R G A H 0 0 S E F A C T 0 R S CSQ HETERMREH/YR PER UCI/SECl ceo'\eeeeeeew e>>eweeeee\eeeeeeeeeewe SN 123 SH 1Z6 SB 1Z4 SB 125 TE 1ZSH TE127H TE 129H I 134 I->>131 I--132 Ie>>133 I 134 I 135 CS 134 CS 136 CS 137 BA 140 Cc 141 CE 144-lect BONE 0>>ie 75E+09 2>>75E+DT 3.13E+al T>>38E+07 5~ibE+07 2>>TTE+0 8 4>>54E+05 1~24E+09 ielbE ai 1>>78E+07 0~1>>49004 Ze 17E+10 2 TDE+ad 3>>08E+iD-1>>17E+08 i>>24E+05 i.Dad+el LIVER D>>3.486+07 5>>19E+05 1>>41E+06 2 DDE+07 i>>lbE+07 Te 73E+07 1~35E+06 1>>ZTE+09 4>>76E 41 2 ZOEi07 D~3e94E+04 3>>65E+10 1>>14E+49 2 9bf+ia 1.02E+05-6>>ZZE+04 3>>14E+06 THYROID 0~1~01E<07 6>>64E+04 ieibE+06 Z~OTE+DT 1~46E407 8 85Et07 1~71E+08 4>>12E+ii 6>>26E401 5>>3DEt09 i>>06E 09 5~15E+06 0~0 0 8~0~D~KIDNEY 8~D~0~3>>96E<06 7>>85EiDT Z>>4DE+08 2>>lDE+ab 2>>09Et06 7>>74E+08 7>>5dE>>01 1>>29E+DT 0~6 26E+04 4>>65E+D9 6>>iiE+Db 3>>66'E+09 1>>ZZE+04 9.72E+03 5>>6TE+05 LUNG 4>>4>>97E+46 2e13E+07 Z>>83E+89 0>>0~0>>a.0~0~0~8-8>>87E DZ 4>>06E+09 de37E+Dl 3e49'E+09 6'9E+04 0~0~GI-LLI Oe 1~16E+09 7>>78 E+ad 2>>43E+Db 7>>iZE+Dl 2>>99E+08 3 33E+Dd s 1~15E+06'.09E+ab d>>93E 02 b>>90Et46 e.4e 41E+04 1 97E+ad 1'5E+eb 1.81Eiab T>>75E+06 T~DDE+07 b>>15Eiad 4~0>>0 AOVk~~&W50~60Dy'~5>>25E+07 i>>09E+07 5>>99E+06 9>>d4E~06 6>>60Eia6 4'8E+07 5 29E+05 9.56Eiab 1>>69E-01 b>>63E+06 D>>1>>%46<04 7~76E409 7~90Etad 4.44Ei09 6>>84Ei06 9'6E+03 5'4E+05 M04 BASEO O'H 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH ANO A VALVE OF ie FOR X/0~OEPLETEO X/0 ANO RELATIVE OEPOSITION NOTE THE UNITS FOR C 14 ANO H 3 APE fKREK/YR PER UCI/CU~HETER) 01/25!79 ihVIRCNHcNTAL FATHMAY COSE COHVERSIOH FACTORS g(il FOR GASEOUS OISCHARGES PATHMAV GOATS HILK (CONTAHIhATEO FORAGE)AGE GROUP-CHILO He e3 P-32 CQ--51 HH 5>>Fi 59 CO-57 CO-58 CO 60 a.Ze 19E+10 a.Oe 4e12i+05 0~Oe 0~3,20F+03 3~20i+03 1.37E+09 0~ie06E+06 9e76E+05 ie64E+05 fe50E+06 5.06E+06 0~Ze19E+03 Or 0~Oe 0~0~NU LIDE ORGAN 0 OS BCNE LIVER THVRCIO 0~6~07E+02 3rZOE+05 0~0~Oe 0~0~4e85E+03 0~2elZE+05 0~Oe 0~Ze46E+09 9~19E+05 3e29E+06 3e 23E+06 4~15E+06 6~90E+06 2e60E+07 Oe 0 E F A C T 0 R S (SQ~HETER-HREH/YR Pf R UCI/SEC)KIOHEY LUNG GI-LLI Zeiif+03 3eZOE+03 3~20E+03+6+l~}OOV.
w~~py 3~20E~03 8.46f+06 3e66Ei03 2.05fia5 3'ZE+05 2~7Zf+05 4e51E e06 1'ZEe07 ZN 65 Fc8 86 SR 89 SR-90 Ver>>91 ZR-95 NB 95 KU 103 RU 1G6 AGiigtc('8++5i4 ie76E+06 Oe ie45E+10 2'7i+ii 4'6E+03'e ZTE+04 3e 30E+04 4'9E+OZ iri3c+0 le SSE+06 5e 57 E+08 3e 3ZE+08 0~Oe Oe 5e 37c+03 te41E+04 0~Oe 6e90E+06 0~Oe 0~0~0~Oe Oe 0.0~0~3~73E<06 0~0~0~Or 2e23E+03 , SediE>03 4r99E<02 Se04ft03 ie36E+07 Oe 0~0~0-0~0~]e 0~0~0.3.51E+08 6e54E+07 5e43c+06 3e16E+09 6'6E+05 9'2E+06 Z~44E t 07 1~266+04 ie75i+05 Zedif e09 Oe 2'2i+08 1 55fc06 4e 16E e08 6 OZEei0 1~ZZE>02 3e 96E>03 1~04f~04 1'4E+02 1 e 40'Ee 03 4.10E e 06 BASEO GN 1 UCI/SEC R LEASE RATE OF cACH ISOTOPE IN AHG A VALUE OF 1~FOR X/0~OEPLETEO X/0 AHO RELATIVE OEPOSITION VCT-THE UNITS FOR C 14 ANO H 3 AGE (HREH/TR PER UCI/CU HET'ER) 01/25/T 9 g--lO ENVIRONNENTAL FATHMAY-OOSc CONVERSION FACTORS R(I)FOR GASEOUS DISCHARGES PATHNAY GOATS HILK (CONTAHI)IATiO FORAGE)AGE GROUP-CHILD NIJCLIOE 0 R G A N 0 0 S c F A C T 0 R S (SQ~HETER HhiH/YR PER UCI/SEC)SN 123 SH 126 S8 1Z4 SB 125 T 125H Tc 12TH Ti 129H I 130 I<<131 I-132 I-133 I 134 I 135 CS 134 CS-136 CS 137 BA 140'E 141 CE-144 80NE 0~Ze jaftab 3e3DE+06 3o 75E+06 8.SSc+i6 6o Z1E+06 3o 3ZE+07 5'58+05 1.4ef+09 2~13E-01 Zej4ftar ao ie79c+04 6o 506+10 8~34E+08 9'3c+10 1.40E+ar j.c 9E+04 ieZOE+06 LIVER 0~4e il f+06 6<<22E+04 ie70E+05 2e40E+06 Ze14 i+06 9eZTE+06 ie 61E+06 1<<52E+09 5<<71E 01 Ze64E+Ol 0~~4<<72E+04 ieiaE+11 3<<29E+D9 be93E+10 ie23E+04 T<<46E+03 3e76E+05 THYROID 0~jeZZE>06 leglf 103 je43E+05 2'9E+06 jeTSE+06 i.a6E+ar 2'5i+08 4'4E+11 Te51E+01 6<<36E+09 ie2l f 09 6~ibf+06 0~0~0~0~Oe 0~KIDNEY 0~0~0~4el6E+05 be46E+06 Ze4DE+07 3e23E+OT Ze51E+06 9<<286+08 9<<10E-01'1<<55c+07 Oe l<<51E+04 ie39E+10 ie83E+09 1 1DE+10 ie47E+03 ie 17E+03 6edOE+04 LUNG 0~5'TE+05 2'6E+06 3<<40foab Qe Qo 0~0~0~ae Qe 0~Z<<42E Dt jeZZE+ja 2<<51E+Ob ie DSE+10 le31E+03 Oe Oo GI LLI 0~je40E+08 9'3E+Dl 2~92E+Dl 8 e54E+06 3'8E+07~aacyar ie 3dE+06 1~30E+08 ical f 01 1 e OTE+Ol 0~5.29E+04 5e92E+08 3'4E+08 5'4E+08 9'0E405 9e 36 i+06 9erbital SK'IN Oo 0~a.0~Oe 0~0~a.Oe 0~a.0~a.Oe 0~Oe ae 0~0~COFA~OOY wHoM 5oOg 0~6.30E+06 1~30E<06 7~19Eea5 1~i bi+06 TogZE+05 So 15E+06 6 35fe05 1~15E+09 2~03E<<01 1~04E+OT 0~ioT3foa4 Z~33E tia Z~37 f t 09 1o 33E+10 bo21E+05 io 11Eoa3 6~4)f104 ASc ON 1 UCI/SEC RELEASi RA~E OF EACN ISOTOFE IN AHO A VALUE OF 1~FOR X/0~OfPLETEO X/0 AHO RELATIVE OEPOSI)ION NGTE TH UNITS FGF.C 14 AHO H<<<<3 AFE{HFEH/Y4 FER UCI/CU~'HETEP) p'I h,v ocr~EHVIRONNEHtAL PATHNAT OOSc CONVERSIOH FACTORS RI Il FOR GASEOUS OISCHARGES PATNVAY NEAt (COHTANIHATEO FORAGE I AGE GPOUP CNILO KUCLIOc H--3 ae BONE ORGAN OOS LIVER THYRQIO 2e33E+02 Ze33E F42 E F A C T 0 R 5 ISO HETER-HREH/TR eAoweoow KIOHET LUNG GI LLI ie54E+02 Ze33E~DZ 2'3E+42 PER UCI/SECl N TOTA~OOY wEQM/ply'~33EIDZ~'L~~P 32 ie 74c+09 CR 51 0~NK 54 De FE 59 9~95E+Dl CO 57 De CO 5d ae CO 60, ae ie09E+ad ae 3o42E4 06 Ze36E+08 ZeiDE+06 1e 69E+a?6e77E+07 0~1~5d E+03 0~0~0~0~0~0~5ebZE+02 1eaZE+46 0~0~0~0~0~3~50Ee03 4~6e55E~07 4e a.a.1~96E+Db 6e63f+05 iobSE+07 le79E+08 5~33E+07 ieaOE+06 3~75f+06 0~0~0~De 6e?3E+0?2'4E+03 6o54E+05 8~98E>0?3e SDE o06 Soiaf>0?2'3E>08~or-ZK 65 RB 86 SR 89 SR 90 Y 91 ZR 95-.*HB 95 RU 103 RU 106 AG110/=~+5H ie 33E 408 ao 5e04E+08 1~DSE+10 1.76c+a6 4'ZE+06 2e68E+D6 ie45E+ad 4e 51E+09 2e SDE+D6 4e 22 E+ad 1~8 2E+06 4~0~-~0~ie 51E+06 iei5E+06 0~0~Ze31f+06 0~0~ao D~0~De 0~0~0~4~2 82E+46 0~4.0~0~le47E+45 4e72E+05 ie Sif 406 2eOZE+09 4e55E406 0~De 0~0~ae D~4~0~De 0~Z~66E+46 3 59E+al iobdE+47 l.a2E+08 Zo33fiad ZeZZE+49 ie98E+09 3~61f+09 le 41E+ia 9'4E+06 ao 0 ae a 1~91 E+08 bo SDE+0?I~44E>0?Ze6?f449 4~69E~D4 io20fi46 6~4if<05 Sob?f ia?5~61f+08 I~386<06 46obC o BASEO OK 1 UCI/ScC RELEASE RATc OF EACH ISOTOPE IH AHO A VALUE OF 1~FOR X/1 OE~LETEO X/0 ANO RELATIVE OE POSITION HOtc THE UNITS FOR C~14 AKO K 3 ARE INRcN/YR PER UCI/CUeNETERI TA8)F C-lt EHVIRDHNEHTAL PATHMAY DOSE CONVERSION FACtORS Rill FOR GASEOUS DISCHARGES PATHMAY Hf AT (COHTAHIHATED FORAGE)AGE GROUP-CHILD)UCLIOE ORGAN DOSE e&o rr e e e e e e o e e O o e e e w w e e e o e e\e\&DONE LIVER THTRCID KIDNEY LUHG GI-LLI F A C T 0 R S[SOeNETER-NREN/YR PER UCI/SEC)r r l I er~o'o'7 ,~r r SH 123 Oe SHe126 6~92E+09 SB 124 lo40E+46 SS 125?eSSE+07 tf 125K 5o69E>ad Tc 12?N 4e40E<08 TE129H ie84E+ag I--130 5~dlf 07 I 131 ie 55f+07 I 132 ae 133 6ed6ioai I 134 0~I 135 3eZ1E"DZ CS 134=de53E>08 CS 136 4e41E+06 CS 137.ie2?E+09 8A 14D 4'?fta?CE 141 Z~1DE+04 Cc 144 Z~38E+06 0~ie37E+08 1'0E+45 ie 84E+Ol ie54c+08 ie5if+48 5eiZE+05 Ze63fe06 ie62E+Dl e.de4?E 01 De 2e96E 02 ie49E+09'e?4E+Ol ie23E+09 3e84E+04 ie05E+04 7e4SE+D5 0~4ea2E+47 1 e?9E+04 ie94E+07 ieSDE+05 ie24E+05 5~blf+05 3'4E 04 5e25E+09 0~Ze04E+02 a.0~0~0~0~D~0~0~a.a.4e 6e 4?f+4?5e44E+ad ie70E+09 ieldf+09 4eadfe06 9.56f+06 0~4e9?f 01 0~ieiZE 02 1 59E+05 9e69E+06 ie 51E+05 4e59E+03 1~65E+03 ie35E+05 ae 2e41E+06 5 74E+06 9o26E+08 0~4~0~Oe 0.0~0~Oe 3e3?f-53 ie65E+ad ie33E+06 ie44E+Od 2e29E+04 0~0~0~2e 31E+09 Ze iaf+05 1~44E+05 5e49E+08 2o54E+09 2'1F+49 2'5E-06 1~38E+06 ae 3e43E 01 0~6'ZE 04 de04E+06 1 e 98E+06 le50E+06 6e03E+06 1~32E<07 1~94E+08 0~ao a De wNe-E fepg 0~le95Eiab Zo93Ee06 1~05E~O?7~59E+07 5o Sif+07 2~64E+05 ioa3E-06 1'2E+07 0~-3o 33f-ai 0~1~32E-02 3 16Eoab ie 25E ia?ie84fi48 Zo 57Ei06 io 5?E+03 1~2?E>05 OZ-OZ 8ASEO OH 1 UCI/ScC RELEASE RATE OF EACH ISOTOPE IH AHD A VALUE OF 1~FOR X/0~DEPLETED X/0 AM RELATIVc DEPOSITION NOTE THE UHITS FOR G 14 ANO H 3 ARE (HRcN/YR PER UCI/CUeHETER)
A ENVIRONHENTAL FATHHAY BOSE CONVERSION FACTORS RC I)FOR GASEOUS OISCHARGES PATHMAT FRESH FRUITS AHO VE::ETABLES AGE GROUP-CHILO NUCL IOE N 3 Oo BONE 0 R G A N 0 0 S E F A C T 0 R S tSQoHETER HREH/YR PER UCI/SEC)eaeoeeo LIVER THYROIO KIOHEY LUHG GI LLI S 4EAAt-QOLUf.
ut&M BcOp'o4lfodZ 2>7E+02 2~47E+02 1~63E+OZ 2 47E+OZ 2~47E+02 P-32 CR 51 HK 54 FE 59 CO 57 CO 58 Co-ed Vt%ZH 65 RB-8&SR 89 SR 90'Yaoegi ZR-95 HB-95 RU 103 RU.o106 AGiiOP'~ZZfi08 Oo Oo 1~48E+07 0~0~do 2 Obf+07 0.4od4E+09 lo79f+10 2 12f+06 4o06E+d5 6o20E+04 Zo24E406 5o19EI07 6o 87f 405 2 64E+OT Oo io9bf+07 3o51E+07 To 53E+05 6o94E+06 2o33E+07 6o59E+07 5o25 E+OT 0~0~0~9o blE+04 2o64E+04 0~0~6o36E+05 0~4.68E~03 0~0~0~0~.0~0~0~0~0~0~0~0~0~0~0~0~io73E+03 5o89E+06 0~0~0~0~4o41E+07 Oo 0~0~0~6odlf+04 1'9E+04 Zo34E+06 2o32E+07 io25E+06 0~io04E+OC 0~9.75E+06 Oo 0~0~0~0~0~Oo 0~0~0~0~0~0~4o74E+OT io97E+06 6eOTE+OT 1oi6E+05 io 9if+07 4oi3E+07 io29E+Ob 4o 15E+07 1o 04E+07 io biE+05 1~52E+09 2'ZE+Ob 1~08E+Ob 4'8E+07 5~bbft07 8~OTE+0 8 2'9E+Od 0~0~Oo 0 0 0.Oo 1'3Etdl 7od3f 103 3~7bf>06 io34E+DT io Z5E+06 Zo09E+07 6o 98E+07 Zo9df idl Zo46f<07 io39fodd 1~9bf+10 5 65fi04 bobif<04 io94E~04 9o05f+05 6-46E F06 3olbf+05~45-BASEO OK 1 UCI/SEC RELEASE RATf OF fACH ISOTOPE IH AKO A VALUE OF 1 FOR X/Q OEPLETEO X/0 AHO RELATIVE OE POSITION cNVIRONHENTAL FATHNAY DOSE CONVERSIOH FACTORS R(II FOR GAS'EOUS OISCHARGES PATHMAY FRESH FRUITS ANO VEGETABLcS AGE GROUP CHILD NUCLIOE 0 R G A N 0 0 S E F A C T 0 R S (54>>HETERWREH/YR PER UCI/SEC)SN 123 SN 126 Sd 124 SB"125 TE 125K tE 127K Tf 129K I-130 I>>131, I oi32 I 133 I 134 I 135 CS 134 CS 136 CS 137 BA-140.Cf 141 CE-14~KOeof~BCNE 1~lif-05 3>>dlf+08 1>>OZE+07 1~2Zc+07 4~12f+07 Ze bbE+07 1~5&f+08 1~60E+05 1~24E+Dd 2>>2&E<df 3>>61E+06 4>>idE 05 1.64E+04 9>>97f+Dd i>>35E+07 1>>41E+09 ie 70E+08 1>>ilf+05 9'3E+06 2>>14E 07 7>>6bf+06 1>>93E+05 6>>99E+05 1~iZE+07 9>>90E+06%>>35E+07 4>>73E+05 1'7E+05 6.05E+01 4>>46E+06 1>>14E 04 4>>33E+04'>>68E+09 5>>32E+07 1>>37E+09 i>>5&E+05 5>>84E+04 2'bgE+06 2>>2&E 07 2>>25E+06 2'7E404 6~ZZE+05 1>>16E F07 8>>09E406 4'9E>07 6~DZE+07 4>>fdf+10 7'7E~03 ioddf+09 i>>47f-OZ 5'le+06 0~0~0~0~Oe 0~LIVER THYROID KIDNEY 0~0~0~2>>09E+06 3>>94E+07 1>>iif+Od 1~5if+08 l>>35f+05 7.75E+07 9>>&5E+Oi Z>>6ZE+06 febiE 04 6.89E+04 Zo 14E+08 2 9&E+07 1>>68F+08 ioldf+04 9>>13E t03 5>>ZZE+05 LUNG Oe 1>>75E+06 l>>93E+d6 f>>04E+09 0~0~0~4>>0~0>>0~De 3>>51'E 03 iobtfedb v>>0&fed&1&DE+05 d 87Ee04 0~0>>GI LLI do 50E 06 3>>44E+Ob 2>>89E+05 9~OZE+07 3~97E+07 1 o 65E+05 iobbf+05 4>>OSE+05 ie89E+07 i>>14E+Oi iebiE+06 9>>59E 05 4~85E+84 9edbf+06 6eb5E+06 be34E+06 2~ODE+Dd 7~33E+Dl 7>>51c+85 0~0 0~0>>%RA~DOY w5~5OO/4~21E 07 1>>19'f o 07 4~04EID&2>>29E>06 5'9fed&3'7E>06 2~4if edl 1~b&E>05 9'8E>07 2'5fedl 1~75E e 06 4'&E-05 1~59E+04 3>>57E+08 3>>536 e 07 2>>04E>08 9>>96E+06 d>>69E+03 4~92f>05 4P-BASED OH 1 UCI/SEC RELEASE RATE CF EACH ISOTOPE IK ANO A VALUE OF 1 FOR X/0 OEPLETEO X/0 AHO RELATIVE OEPOSITION
~ha,iE.C-~E EHVIROHHENTAL PATHHAY"BOSE COHVERSION FACTORS R(I)FOR GASEOUS OISCHARGES PATHMAY INHALATION AGE GROUP-TEENAGER 0 R G A N 0 G S E F A C T 0 R S fHREH/YR PER UCI/CUeHETEP.l Ha a a3 Oe BONE LIVEr de48E+02 THYROIO KIOHEY LUNG GI" LLI H ROTAL~OY W81m grPf 8 48Et02 1 OlE+03 8 48E+OZ 8 4bE+02 be48Et02 Paaa32 CR 51 HHa-54 FEa 59 CO 57 CO 58 CO 60 Wt%ZN 65 RB 86 SR 89 SR 90 Yaaagf ZR 95 HB 95 RU f03 RU 106 AGf f DP'~K 1~32E+06 0e 4e 1eidFt 04 Oe Oe Oe 3e Z4E+04 Oe 3edlEt04 ie ibE+07 5e3dEt04 1e09Et04 ie36Et03 1'3Et02 8~40'E+03 le08E+04 7.72Et04 0~3,96Et 04 2 lbi+07 6e92E+02 1e76E+02 ie24E+03 ie03E+05 fe35Et05 Oe Oe 0~3e63E+03 de24Et02.0~0~feOOE+04 0~5e95Et 01 0~0~0~Oe 0~0~0~Oo 0~0~0~do 0~0~Oo 0~Ze28E+Di 9eb4E+03 0~Oe 0~0~6o90Et04 0.Oe 0~0~5e42E+04 7ellE t03 5eb3E+03 ie34E+05 ie97E+04 0~fe44E+04 ie40E+06 fe02E+06 3elOE+05 ie3lct06 8~56E+06 belZE+05 Oe Ze58E+06 fe66E+87 Ze86E+06 2e56E+06 le ilE+05 le 51E+05 1~64E+07 4'4Et06 be64E+04 3'ZEt03 7'4E+04 febbE+05 3~14E+04 9e5ZE+04 Z 35E+05 5'4E+04 1 66Et04 3'4E+05 7~24E+05 3'4E+05 1~33E+05 8~dOEt04 9e44Et04 9e28E+05 3eOZE+05 5e OZE>04 iebbbt02 6e306t03 1~06Et04 6e71Et 02 2~34Et 02 1~65Et03 SEt84 4'6Et04 5e90Et04 io 11Et03 23Et05 io44Eo03 Ze 54Et03 4'2EtOZ le32Et41 1 06Et03 5'4Et03 BASEO ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1~FOR X/Oe DEPLETEO X/0 AMD RELATIVE OEPOSIT ION t
ENVIROHHEHTAL PATHWAY DOSE CONVERSION FACTORS R(1)FOR GASEOUS DISCHARGES PATHWAY IHHALATIOH AGE GROUP-TEENAGER NUCLIDE ORGAN DOS'E oeo ao\ooeeeoeoo eea&e\&o BONE.LIVER THYROID KIDNEY LUNG GI LLI F A C T 0 R S IHREH/YR PER UCI/CUeHETER}
SH iZ3 SH 126 SB 124 SB 125 TE 125H TE127H TE129H I 130 I 131 Iooi32 I 133 I 134 I 135 CS 134 CS 136 CS 137~BA 140 CE 141 CE 144 2'9E+04 1~26E+06 3~12f+04 6~61E+04 Ce 076+02 io 26E+04 io 19fi03 Co5bf+03 3'7E+04 ioe6E+03 io23E+0%6o45E+02 Zo 69f+03 Cob3B05 3ogifqb 6o42E+05 5o30E+03 Zo27E+03 19fo05 6 14E+02 3r 34E+04 5ob9E+02 lo13E+02 1 86E+02 5o62E+03 5o64E+02 io3Cf+04 Co72E+04 3o26E+03 2o06E+04 jr73E+03 6r99E+03 ioiOE+06 io46FP05 bo24c+05 Cob5E+00 io5ZE+03 1.74E+05 Ce9ZE+02 9 84E+03 7 55E+01 5 odlE+01 ioilf+02 3r29c+03 3o90ft02 1~TCE+06 ir39E+0T 4~3$E+05 3'3ft06 Zo30E+05 9o36f+05 Oo 0~0~0~0~0~0~0~be 0~ioZCE+04 4'8E+04 3e66E+bC Zo09E+04 6o 14E+04 Ee 196+03 2o 68E>04 2o l5E+03 io 11E+04 2rbbE+05 dr56E+04 ZrZZE+05 1~6TE+01 6r26f+03 br48E+05 3o91fo06 9'6E+06 2~4 bE+06 ZoZOE+06 5036E+05 9o60f+05 Zob3E+06 0 0.0~0~0~0~io44f+05 ioZ4E+84 ioibf+85 Zo02E+06 5ob3E+45 ir38E+07 3~13E+05 1~ZTE+05 4'6E+05 1~01E+45 T~Odf+04 io 50E+05 3obCE+05 To69E+03 5'6E+03 Co06E+02 io 00E+44 io01f+00 5e25E+03 8~96fo03 1 o ilE+04 lo6dE+03 ZoiZE+44 1 o 14E+05 bo48E+05 0 0 0 0 de be wBOM+O/9r206402 4r 80E o04 io24E o04 ir33E<04 5o53E+Oi 1'7E>03 1'2EoDZ 5'9ft03 2'2E+04 1~16E<03 6'4E>03 6e 16Eo02 ZeSbf+03 5r44fo05 1riif+05 3'3E+05 3eCZE+02 ieTCE>82 Ze24E+04 BASED OH 1 UCI/SEC RELEASE RATE GF EACH ISOTOP IN ANO A VALUE OF 1~FOR X/0~DEPLETED X/0 AHO RELATIVE DEPOSITION ENVIROHNENTAL FATNWAT-DOSE COHVERSION FACTORS RCI)FOR GASEOUS OISCKARGES PATH))AY CONS HILK (CONTANIsiATEO FORAGE)AGE GROUP Tf f HAGE R HU LIOE H 3 Ma Peoo32 CR-51 HNe-54 Ffeo59~CO 57 Coe 58 COe 60 7He-65 RB 86 SR" 89 SR 90 Y-91'=.ZR 95-NB 95 RU 103 RU 106 AG iilP{0~BONE 2o 21E+10 Do a.3o84E+07 0~0~ao 1 e 776+C.9 Do Zobaf+09 de29E+10 ie54E<04 4'8E+04 1.24E+D5'o 69E+03 3'3E+04 lo53E+07 1e38E+09 De io09c+07 9oiZE+al 1e65E+06 doiaE+06 2e 73c+Ol 5o 63E+09 3o35E+09 D~De De 2ed4E+04 7e46E+04 0~0~6o97E+07 0~2~Z1E>04 0~a.0~0~Oe 0~0~Do 0~a.0~Oe 0~0~a.0~be15E+03 3o23E+D6 0~4e De De 3ellE+09 0~0~a.Oe Ze ZSE+04 5oblE+04 5o04E+03 5 09ft44 ie37E+08 0~4'0E+04 0~Zo53E+07 a.a.0 D~0~0~3o38E+06 0~0~0~0~0~0~2e48E+09 9 29E+06 3e33E+07 3eaiE+08 4e 19'E+Dl ie14E+08 3e27E+08 3e55E+49 6e61Etad 3e03E+08 1e76E+49 5e93E+06 1e 15E+08 3'5ftab ie3ZE+05 ie73E+06 Zedlf+10 0 0 0~D ORGAN DOSE F A CTO RS)SQ HETER HREH/YR PER eo ceo oee e LIVER THYROID KIOHEY LUNG GI LLI 9o93f+02 9e93E+02 ie26E+03 9o93fo02 9'3E+02 UCI/SE C)H%9+At~)OOT wB~gopy'o93f+02 OQ-8~54E>08 3of9f<ai Zo al f1 06 3o47f+al Zo75f+06 io 85f+07 6o23fi07 Zo 55f i 09 1~56E+09 be 03E+Dl Pe 05E+10 4o 12E>42 1'0E+04 4'if+04 7~56f+02 4 biE+43 4e 14E>07 9ASEO ON 1 UCI/SEC RELcASE RATE OF EACH ISOTOPE IH ANO A VALUf, OF 1 FOR X/O~OEPL'ETEO X/0 AHO RELATIVE OEPOSITION NOTE THE UHITS FOR C-14 AHO H 3 ARE (HREH/TR PER UCI/CUobfTFR)
-W itZDt~ping,~<C.-l 9 ENVIRONHEHTAL PATHMAY DOSE CONVcRSION FACtORS R(il FOR GASEOUS DISCHARGES PATHVAY-CONS MILK (COHTAHIHATEO FORAGE)ACE C'ROUP T EE MACE R HUCLIOE 0 R G A H 0 0 S f F A C I 0 R S (SQeHETER HRfH/YR PER UCI/SEC1 SH 123 SN-126 SB iZ4 SB 125 tf 125H Tf 1ZTH TE129H I 134 Io 131 I 132 I 133 Io-134 I i35 CS 134 CS-136 CS 137 BAoi40 CE 141 Cc 144 BGHE De Ze 12E+09 3 33E+07 3e45ft07 3eDDE<07 6eOZE+07 ie13E+08 5>>5 if+05 5 iZE+08 2.16f-ai 7e33E+06 Do ied if+04 9e44E+09 3e37E+Dd ieZDE+10 4ebhf+Dl 5e45E+04 heibf+06 LIVER 0~heZjf+07 6eZ9E+05 9e55'E+05 ieDDE+07 ZeiiE+07 4eibf+07 1,~63E+06 leZ4E+08.5e76E Di ieZ4E+07 0~4e77E+04 ZezdE+10 ie33E+09 ie72E+10 5e 95&04 3e39ft04 ie65E+06 TH'YR0 I 0 0~io24E+07 8~05E+04 5'5E+05 8 ohlE+06 io59E+07 3e61'E+07 Zeblfibb Zo09E+11 7e59E<01 2e26E+09 ie29E 09 6e24E+46 4~0~0~0~0~0~KIDNEY~e 0~0~4~80E+06 be55f 407 2e43E+Db 3e27E+05 2 53E+06 9e38E+08 9e19E 01 jo56E+07 De le58E+04 5e63E+09 lehiE+08 he43E+09 iehbf+04 ieibf+04 6edlf+05 LUNG 0~6e03E+46 Ze59E+07 3e43E+09 0~Oe 0~0~De 0~0~0~9e79E 02 Z 76E+49 ieOZE+05 ZeZbfi09 3e9bf+04 be 0~GI LLI 0~iohiE+09 9.43E+ad 2~95f+05 be 39E+Dl 3'2E+05 3'3E+08 1 48E+06 1~37E+05 1~Odf-01 9eDZE+06 0~5o34E+04 2'3'E+05 ie5if+Dd 2'9E+45 9ei6E+06 9e 18E+47 9'5E+45 0~0~Do 0 N R~~Y mBoM+pp'.6~37Eo 07 1~32E i 07 6'2E+06 3e9bf+06 7e45E+06 1 75E+Dl 6~4if+05 4'ifi08 2 05E-01 3e 83Eo06 n e 1e75'Eo 04 jo56fi10 9e55E>08 6e04E+09 3e iif>06 3e59E+03 2~17E+05 BASEO OM 1 UCI/ScC RcLEASE RATE OF flCH ISOTOPE IH AHO A VALUE OF 1~FOR X/0~OEPLETEO X/0 AMO RELATIVE DEPOSITION NOTE TH UHITS FOR Co 14 AHO H 3 ARE (HREH/YR PER UCI/CUoHETERl I f~
cNVIRONKENTAL PATHVhT OOSE COHVERSIOH FACTORS RCI1 FOR GASEOUS OISCHARGES PATHMAY GOATS NILK (CONTAKINATEO FORAGE)AGE GRoup TEENAGER NUCLIOE ORGAN OOSE F A C T 0 R S (SoeNETER NREN/YR PER UCI/SEC)BCYE LIVER THTROIO KIONEY LUHG GI LLI t~~f;~C e 1 e J r'r+-V P-Hoeee3 Poee32 Ce-Si NN 54 FE 59 Co 57 Co%54 Co-60 M 44'N 65 RB 46 SR b9 SR 90 Toe gi.ZR 95 NS 95 RU 103.RU 106 A611DP 0~2e65E+10 Oe 0e 99E+05 Oe, 0~Oe~l46.2e 13E+Ob Oe 5eblf+09 ie 74c+i i.ieb5E+03 5e l4E+43 1'9E>44~Ze03E402 4e5gf+03 9e04c+06 2e 03 E+03~ie 66E+09 0~1 30&06 iei9E+06 ie94E+05 ge72E+05 3eZOE+06 6e76E+Od 4e42E+Ob Oe.Oe Oe 3e41E+03 de96E+03 Oe Oe be36E+06 Ze03ft03 4~2'5E+03 0~0.0~0~0.0~0~0~0~0~0~0 0-0~0~2 56E+03 4~gelbf+02 3 bbE+05 0~0~4~0~4e52ftbb Oe 4~be Oe ZelOE+03 lo45E+03 6~45E 102 6eiiE+03 ie64E+Ol Oe 5ebbE+03~e 3e29E+05 0~0.0~0~4~0-4eb5f+45 be 0~0~be Oe 4e 2 e90E+09 iei1E+06 3eggE+06 3e91'E+06 5 03E+06 1 31E+b7 3e93E+bl 4e26E+Ob 7 e93f F07 6e37E+Ob 3ebbf tbg le 11E+05 1 e 30'E+07 3e66E+07 ie5bE+04 2.00E+05 3e41E+09 0~0~Ze03f+03 2~03E+03 0~Wt}OM~p3Et03 1'3E+09 4'3E+03 Zo49E+05 4~51E+05 3e30E+05 2e ZZE+06 7e40E+06 3e06ftbb 1'bE+Ob 1~69E+bb 4 30Eoib 4'4E+bi 1~93E+03 5 05E+03 9obbf+01 5elbfi02 4.97Eo06 SASEO ON 1 VCI/Scc RELEASE RATE OF EACH ISCTOFE IN ANO A VALUE OF 1 FOR X/O, OEPLETEO X/O AHO RELATIVE OEPOSITIOH NOTc THE UNITS FCR C 14 ANO H e3 ARE UNPEN/TR PER UCICCUeKE TER)
~p Q ENVIRONHENTAL PATHNAY GOSE CONVERSION FACTORS R\Il FOR GASEOUS DISCHARGES PATHMAZ GOATS HILK (COHTAHIHATEO FORAGE1 AGE GROUP TEENAGER NUCLIDE SH 123 SH<<126 SB 124 SB 125 TE 125H TE 12TH<TE iZ9H I 130 I 131 I 13Z I 133 I-<<134 I 135 CS 134 cs-13e.CS 137 BA-14a CE 141 CE 144 BONE ae 2<<54E+08 4~aaE<06 4.14E+ae 3<<61E+4&Te 23E+06 1<<35E+07 6<<61E+05 6<<15E+48 Z<<59E ai 8<<l9-'+06 0.Ze LTE+04 2<<83E+1 0 io 01E+D9 3<<84E+10'<<81&a&6<<06E+03 4<<92E+45 LIVER 4~5 05Epae Te 54E+04 i<<15E+05 1<<Z9E+46 2 52E+06 5<<DZE+06 i<<96E+06 d<<68E+Ob 6<<9ZE 01 1<<49E+47 a 5<<T3E+04 eob3E+10 3<<99E+49 5<<16E+10 7<<14E+03 4~OTE+03 2<<02E+05 THYROI0 0~1<<48E406 9.6&Ei03 6'6E+04 ie42E+06 1 e91E+06 4<<34E+06 2'9E+08 Z<<54E+li 9<<iiE+Di Z<<TiE+09 1<<55E 09 7<<496+06 0~Oo 0~D~0~0~KIDNEY 0~0~Oo 5<<TTE+05 1<<03E+07 Z<<92E+Dl 3<<92Et07 3<<04E+06 i<<13E+09 1eiaE+40 1<<88E+07 0~9<<iaE+44 1 69E+10 2<<22E+09 1<<33E+10 1<<78E+03 1<<41C+D3 8<<24Et04 LUHG 0~T<<23E F05 3<<10E+06 4<<12F+08 0~ao 0~0~0~0~do 0~2<<94Eeai 8<<ZTEie9 3 05E>08 6ed5E+09 4<<78Ei03 0<<0~GI LLI 0~1~69E+08 1<<13Etab 3'4C+07 1<<01E+07 3'3E+87 4e72E+47 i<<68E+06 io&4E+08 ie30E Oi ieabE+el a.6e41E+04 lebbE44d 4'4Etab 6<<bbE+48 1~10E+06 leiOE+al ie16E+08 Oe 0~0 0~8 0~0~0 R G A H 0 O S E F A C T 0 R S tSQ HETER HREH/ZR PER UCI/SEC1~~1OY w+m~y 0~7'4E+06 1~58E+06 8~19E<<05 4~78E+45 8<<94E<<45 2<<13E+06 7<<69E+05 5'7E+08 2<<46E-01 4'9E+06 M~Z<<10E+04 3<<19F+10 2<<87E+09 1 bfE<10 3<<73E+45 4~66E+DZ 2'1E+44 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AHO A VALUE OF 1~FOR X/O~OCPLETEO X/0 AHO RELATIVE DEPOSITION NOTE THE UHITS FOR C 14 ANO H-3 ARE tHREH/YR PER UCI/CU HETER1 EHVIROHNENTAL PATHMAVaOOSE COHVERSIOH FACTORS RII)FOR GASEOUS OISCHARGES PATNMAY HEAT ICOHTAHIHATEO FORAGE)ACE CROUP TEENAGER J'M~<1 4v A+<<(~~fi rg.,-..<-.b'o 4b)(C<-5,"<)</<~J<<Sii gt-<S,<~C.HUCLIDE Heeee3 Paee32 CR 51 HHaa5l FE 59 CO a57 CO 5$COe 60 W~H 0 R G A N 0 0 S E F A C T 0 R S CsaoNETERaHREH/rR PER UCI/SEC)eeaeageeaeaaaea
\aeeeeaeaeeaeeeeeeeeeeaeeeeeeeeeeaeeae'eeaaeea ceo e aee e BONE LIVER YHV ROIO XIOHEr LUHG GI LLI S+fR~DOY N~gy)/Qe Ze%%c+DZ ie93E+02 e 1~93Et 02 ie93E+42 ie93E+QZ 1~93E+02 2 e 76E+09 De Ce 1e5dE+Ob De 0~0~iel3E+00 D~5e42E+06 3el4E+00 3e33E+06 ie%4BDl 5el3E+07 0~2'DE+43 0~0~0~0~0~0~9e2ZE+OZ ie61E+06 0~0~Oe 0~Qe 5e55E+43 0~ie04E+Qd 0~Qe 0~3e iQE+00 ie05E+06.1 e 66 E+07 ie24E+09 be45E+Ql 1~90E+Db 6e blE+Db 0~1 QTE<00 4~)DE+03 1'4E+06 1~42E+Qd 5'4E+06 3e27E+OT ie 31E ebb ZH 65 RB 06'R 09 SR 90.Veaagi ZR.95 HBe 95 RU 103 RU 106 AG110y'W&lt-2eiiE+Qb De 2 66E+Qb<ie01E+10.-.9e34E+05 2'7E>06 ie 50B06 be05Ee07 Ze40E+09 3 97E+06 6e69BDd 2 d9E400 4~De De ie24EI06 9e 51E+05 4~0~3o67E+06 4~0~0~0~0~0~4~0~0~0~4e47E+Dd Oo Oe 0~D~ieidE+06 le4dE+05 Ze40E+Qb 3eZOEt09 7o21E+06 0~4~0~Ze79E+Od 0~Qe 0~Oe Qe 0~4e 21E+Dd 5e69E+Ql 2 09E+07 ie 4ZE+09 3 59Eebb 4e20E+09 3ebbE409 6e20E+09 ie09E+ii ie50E+09 3e03E+Qd io35EtQb le64E+06 Z~49Ei09 Zo49EtQls 7~6IE+05 5e 37E+05 3e 60E+Dl 3~026i00 2e idE+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AND A VALUE OF io FOR X/Oe OEPLETEO X/0 ANO RELATIVE OEPQSITIQH NOTE THE UNITS FOR C 14 ANO N e 3 ARE (HfcEHIYR PER UCI/CUoHETER)
ENVIRONNENTAL PATKKAraOOSE CONVERSION FACTORS R(I)FOR GASEOUS DISCHARGES PAl'HNAY NEAT (CONTANINATE9 FORAGE)AGE GROUP-TEENAGER ORGAN OOSE FACTO a aaaa'a aaaa\aaaa\aaaaaaaa a aaaaaaaaa BONE LIVER THYROIO KIDNEY!.UNG GI LLI R S ESQ~Nil'ER BREN/YR PER UCI/SECl~t-88ER'H 123 SN 126 SBa124 SB 125 TE125H T E 127H TE129H I a130 I 131 I a132 I 133 I 134.I 135 CS 134 CS 136 CSa137 BA 140 CE 141 Ci 144 Do 1~10E+10 fo 176+07 5o 01E+07 3e03C+08 6e68E+08 9e78E+Dd 1.41E-oe be54E+06 De 3o69Ea01 Do 5oDDEaDZ'o03E+Db 6'9E+06 6e92E+08 2e37E+07 io 12E+04 1 o 28 i+06 0~ZoibE+08 Zo21E+05 io 31E+07 ieDDE+Dd 2o34E+08 3e63E+08 4o16E, 06 ie 21E+07 0~6eZSEaD1 0~.4e69E 02 ie21E+09 Ze76E+07 9e31E+08 Zo93E+04 7e51&03 5e23E+05 0~6'dE+07 2ob4E+04 fo02E+07 be55E+dl iollE+0d 3o13E+Db 5e30E 04 3o48E+09 0~f o14E+02 0~0~0~De 4~0~Oo 0~0~0~0~1~03Etod be63E+08 2o69E+09 2ob3E+09 6e4lE 06 1~56C+07 Do 7odbEabi De folbE 02 3oDDEIDb ie 54E+4 7 Ze44Etbd leZDE 403 Ze61E+03 ZoiCE+05 0~3eb2E+06 9o 11E+06 ie4lE+Dg 0~0~bo to 0~0.0~4~5o34E 43 fo47E+Od Zo iiE+06 io Z4E+Db io95E+04 4~0~Do 3.eeE+Dg 3'2E+08 2'5E+08 be47E+08 3'5E+49 3e41E>09 3e57Ea06 2'8E+06 Do 4~55E 01 Do io 10E 03 fo44Et07 3o 14E+DS 1 24E+07 9~19E+06 2'3E+07 3obbE+08 o De 0 0 0~0~0<NocE Sop/De 3~14E+08 4'4E+Ds 7eeDEi06 4~DZE<07 8~ZDE+07 1~53E>0d 1'4E-06 7o 19Ee 06 0~1 936a01 0~2~08E D2 5oeeE+Db 1'9E+07 3'7E>08 1'36>06 beefEi02 ee76Ei04 BASED ON 1 UCI/SEC RELEASE RATE CF EACH ISOTOPE IN ANO A VALUE OF 1 FOR X/0~OEPLETEO X/0 ANO RELATIVE DEPOSITION NOTE THE UNITS FOR C" 14 ANO N 3 ARE INREH/YR PER UCI/CUeNETERl ENVIRGNNEHTAL PATHMAY BOSE CONVERSIOH FACTORS R<I)FOR GASEOUS DISCHARGES
~r PATHMAY FRESH FRUITS ANO YEGETABLES AGE GROUP-TEENAGER 0~J'UCLIDE Nor r3 ORGAN DOSE rrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrr BONE LIVER THYROID Oo 2 09E+02 2 09E+02 2 64E+42 2>>09f+02 2'9E+02 F A C T 0 R S (SQ HETER HREH/ZR PER UCI/SEC)oe re r r KIDNEY LUNG GI-LLI~~QOl~HoM BdOf 2>>09Eo 42~0~r~~rl(Prr>>32 CR 51 HN 54 FE 59 CO 57 CO 58 CO 6D A6 ZN 65 RB 86 SR 89 SR 90 Y 91 ZR 95 NB 95 RU 103" RU 106~AG110)t'L$
45I4 6>>81E+Ob 0~Do 2>>39E+OF 0>>0~Oo 3>>35E+07 Qe Ze 61E+09 le 61E+14 i>>15E+06 2>>35E405 3>>72ft04 1>>ZFE406 2 SZE+07 1 iif+06 Co 27E+07 D~3>>20E+07 5>>67E+07 i>>22E+06 6>>01E+06 2>>81E+Ol i>>06E+08 8>>52E+07 De Oo 0~8>>19E+04 2>>24E+04 0.Or i>>03E+06 0~7>>56ft03 0~0~0~0~0~0~0~0~0~Oe 4~0~0~Oo 4~0~2>>79E+03 9 52E+06 0.0>>4~0>>7eiZE+07 0~Oo 0>>0~9ebiE+04 i>>76E+04 3e77E+D6 3 75F+07 Z>>QZE+06 4~1>>68E+04 0>>i>>57E+07 4>>0~0~4~0~0~2~41E+Ob 4 00 0>>De 4~De l>>66E+Ol 3>>ibf+46 9~SOE+07 1>>SFE+48 3'9E+07 8 0 12E+47 2>>41E+Ob 6>>74E+47 i>>68E+Ol 2'3E+08 2>>31E+49 4'1E+48 i>>92E+08 9~14'E+Ol 9>>87E+07 i>>ZSE489 4~19E+DS 0 0 0 2~64EIDF 1~27E 004 6>>iif4 06 Zo 16E+DF 2 DZfi06 1'FE+87 4'8E+OF F 4>>82E007 3>>9lfiOF 7>>Cbf+07 iobbfo14 3>>46E404 5>>eifr04 1'6E+04 5>>eefr05 3 54E<46 er SOEi05 g'BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AHO A VALUE OF ie FOR X/O~OEPLFTEO X/0 AKO RELATIV'f DEPOSITION 0 1~
ENVIRONHENTAL PATH@AY DOSE CONVFRSIOH FACTORS R{il FOR GASEOUS DISCHARGES PATHHAY-FRESH FRUITS AHO V":9ETABLES AGE GROUP-TcEHAGER NUCLIDE BONE LIVER THYROID ORGAH DOSE F A C I 0 R S CSO HETFR-HREH/YR PER UCI/SEC)KIDNEY LUNG GI LLI SN 123 SH 126-SB 124 58-125 TE 125H TE 1ZTH TE 129H I 130 I 131 Ie 132 I 133 I 134 I 135 CS 134 CS 136 CS 13T BA 140 C" 141 CE 144 9e25E 06 So25Eted ie65E+07 ie73Et07 2e23E+07 4.46E+07 be46E+07 2e5dE+05 6~84Etdl 3e65E+01 1e9dEt06 6e75E 45 Ze65Et04 5e79Etdb 2e idE+Dl 7 83Etdd 9e38Etdl 6e3ZE+04.5e03E+66 1~53Eo07 fo24EtOT 3o12Et05 5o97Et05 7e99E+06 ie55E+07 3e 14E+07 le64E+D5 9eSSEtdl 9e77Et01 3e3SEt06.1e63E 04 TeOOE+04 ie40Et09 e.60E+07 ie05E+09 ieZ1Et05 4.24E+04 Ze06E+06 1eZZE Dl 3e64E+06 3e99Et04 3ehbE+05 6e30E+06 ie ihE+Ol 2e71E tel 9eTZE+07 2o79Et10 ie29E+Dh Se1DEtDO Ze38E 02 9~15E+0 6 D~Oe 0~0~8~De 0~0~D~3e38E+06 6e36F+07 iedOE+08 2e45E+Od 1ei9Et06 ie25E+08 ie56E+OZ 4e23Et06 Ze92Ee04 ioit'E+05 3o45E+O8 he78Et07 2o7ZE+08 ZebbEt04 iehlE+Dh be43E+05 0~Ze83E+06 ie ZDE+Ol 1'6E+09 0~0~D~0~Oe Oe 0~e.5e67E 03 1~69E+Od Se56EtOS iehOEtDb le73E+Dh D.0~ie33E 05 5'5E+08 he6TE+08 ie45E+08 6'4E+07 2e23E+db 2'5E+08 6e55E+85 ie83E+Ol iedhE+Oi Ze44E+06 ie60E Dl le 64E+44 ie61E+OT 9ellE+06 1 41E+Dl 3e19E+Ob ie 15E+Ob io 19'E+09 0 0~VO~eOOy 2'6E OT ie 94E t 07 6o 53Ft 06 3.40EtOS Ze96EtOS 5'1E+06 ie33EtOT 3oDDEt05 5oTSEtOT 3ohTEt01 1 04Et06 6e56E-05 2'7E+04 6o52Et06 6e 19Et OT 3e 70E+Od 6o04Et06 hodSE+O3 2oSTEt05 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1 FOR X/O~OEPLcTED X/O AHD RELATIVE DEPOSITION iNVIRDNHCNTAL FATHNAY DOSf CONVERSION FACTORS R(I)FOR GASEOUS OISCHAPGES PATHNAY INHALATION AGE GROUP-ADULT NUCLIOc H 4 Mr 0>>BONE 0 R G A N 0 0 S E F A C T 0 R S lHREH/YR PER UCI/CU>>HETER)
LIVER THYROID KIDNEY LUNG GI LLI N 1>>07E+03 1~07E403 1>>07ft03 1>>07ft03 1>>07E+03~~mTT lo FROM 6OPP'~DTEo03 Poaa32 CR 51 HN o54 Fi 59 CO 57 COoo58 CO 60 M~3 ZN-65 RB 86 SR 89 SR 90'Ywoo91 ZR 95 NB 95 RU 103 RU 106 AG110 1>>32ft06 Oo Oe ie 1 DE+04 0.0~0~3>>24E+DC 0~3e04f+05 9'ZE+07 4'2E+05 1>>07E+05 1~Cif+04 io 53E+03 6~91E+04 1~DOE+D4 l>>72E+04.0~3>>96f 104 2oldf+Ol 6>>92E+02 1>>5bf+03 1>>15 f104 1>>03E+05 1>>35E+05 0~0~De 3>>44E+04 le 82E+03 0~0~1~DDE+DC 0~5>>95E<01 0~0~0~0~0~0~0~0~De 0~0~0~0~0~De 0~Z>>28E+01 9 84E+03 0~0~De 0~6>>90E+04 0~0~0~0~5.42E+04 7>>74ft03 5>>d3E+03 1~34i+05 1>>97E+04 Oe 1>>ACE+04 1>>COE+06 1>>OZE>06 3>>70E+05 9>>ZOE+05 5>>98E+06 8>>72E+05 a.i>>COE+06'9>>60i+06 le lbf+06 ielbE+06 5>>06E+05 5.06E+05 9eCCE+06 4>>64E+06 8~64E+04 3'ZE+03 lelCE+04 1~bbf+05 3'4E+04 1>>06E+05 Ze85f i05 5>>34E+04 1'6E+04 3'0E+05 l>>ZZE+05 3>>85E+05 i>>5bfi05 ieDCE+05 1~10E+05 9>>12E+05 3.02f+a5 0~0~0~0~0 D~0~0 5>>02Eo04 1>>DOE+02 6>>30E+D3 1>>06E~DC 6~Tic+02 Z>>07E+03 1'8E+04 4'6E+04 5>>90f<04 b>>72E+03 6~10E+06 1~24E+04 2>>33E404 4'1E>03 6'8E+02 8>>TZE+03 5'4E<03 BASiO ON 1 UCI/SEC llELEASE RATE OF EACH ISGTOFE Ill AND A VALUE OF 1 FOR X/0 DEPLETED X/0 AND RELATIVE DEPOSITION EHVIROHHEHTAL FATHMAYoOOSE CONVERSION FACTORS fc(I)FOR GASEOUS OISCHARGES PATHHAY INHALATION AGE GROUP-AOULT r.;1 J'o" r r~t*~'~t~I SN 123 SH 126 SB 124 SB 125 TE 125H TE 127H TE 129H I 130 I 131 I-o132 I 133 I 134 I 135 CS 134 CS 136 Csoi37 BAo140 CEo141 CE-144 Ze CZE405 1~26E+06 3~12E104 6o 61Ei04 3 CZEia3 ie 26E+04 9e 76E+03 Co58E+03 2'2E>04 ioiSE403 8.64E+63 6.45E+aZ 2o69E+03 3elCE+05 3e 91E+04 4o78&05 3e90E404 1~99E+04 3o 43E+06 HUCLIOE BONE LIVER 5e33E+03 3o34E+04 5o89E>02 7o13E+02 io58FP03 5e62E+03 Ce67E+03 io34E+04 3o58FPD4'o26&03 1e49E+04 io73E+03 6e99E+03 bo48E+05 1e46E+05 6oZZE+05 Ce90E+ai io35E+04 1e43E+06 THYROID 4'3E+03 9obCE>03 7e55E401 5'7E+Oi i.a5F+a3 3'9E+03 3oCCE+03 ie74E406 ie19E+07 Ce3bE+05 Zo93E+06 2o30E+05 9o36E+05 00 0~0~a.0~0~KIOHET 0~0~0~0~1eZCE+04 4 58F+04 3e66E+04 Ze09E+04 6eiCE+04 5e19E+03 2eSOE+04 Ze75E+03 ieiiE+OC 2ebbE+05 bo56E+04 Ze22E+05 ioSTEiai 6oZ6E+03 beCbE+05 LUNG Ze30E+06 9o36E+06 Ze48E>06 Zo20Ei06 3e 14E+05 9eSOEib5 I~166+06 0~0~0~0~0~0~9o76E+04 ie20E+04 lo53E+04 io27E+86 3e62E+05 7 78E+06 GI LLI 3e 14E+05 1~27E+05 4'6E+05 ie 01E+05 leaSE+0C io50E+05 3'3E+05 lo69E+03 6o26E+03 4'6E+02 6elZE+03 io 01E+ab 5'5E+03 V OCE+04 1.17E+04 bo4OE+03 2 oibE+05 1020E+05 do16E+05 ae ao 0 0~Oe 0 R G A H 0 0 S E F A C T 0 R S (HREH/YR PER UCI/Cvo METER)~HOYLE:~y 7 6SE+03 4'0E+04 1~ZCE+04 io33E+04 4~67E+02 1'7E<03 1'8E+03 5o29E+03 Zo 05E+04 1~ISE+03 4'4E+03 6o ISE+OZ 2o 58E>03 lo29E<05 1~11E+05 4'9Eo05 Ze 57E+03 1~53E+03 1~84Eo05 SASEO OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AHO A VALUE OF 1 FOR X/Qo OEPLETEO X/0 AHO RELATIVE OEPOSITIOH
~~5r EHVIRONHENTAL FATHNAY OOSE COHVcRSIOH FACTORS Rll)FOR GASEOUS OISCHARGES PATHNAY CONS HILK (CONTAHIuATEO FORAGE)AGE GROUP-ADULT~>I I's~I~\g 0~LI>>>>c e>>NUCLIDE Heeee3 W&r Peee32 CR 51 HHe-54 F" 59 CO 57 CO 58~.-CO 60.'ZN 65 RS 86...SR 89 SR 90.'"~Ye 91 ZR-95 HS 95 RU 103 RU 106 AG 11 le 80NE Do 1>>7 iE+10 0>>0>>2>>98E+07 De 0>>D~1>>37E+09 0>>1~46E+09 4.70E+10 8~60E+03 3>>ibE+04 8'6E+04 1>>02E+03 2>>04E+04 5>>84E+07 f>>07E+09 0~8>>41E+06 7>>DSE+Dl 1>>28E+06 4>>72E106 i>>65E+07 4>>36E+09 2e60E+09 0~0~0~1>>75E+04 4>>59E+04 0~0~5eCOE+07 0~ie71E+04 0~0~0~0~0~0~0~0~0~0~0 0~0~0.De ORGAN OOSE LIVER TH'YROID 9 73E+02 9 73E+DZ 0~6>>32E+03 2>>5PE+06 Oe 0~0~be 2>>92E+09 0~0~0~0~1>>75E+04 4>>55E+04 3>>91E+03 3>>95E+04 i>>06E+Qb 0~3ebDE+04 D~1>>96E+07 0.0~0~0~8~D.a.0>>0~0~0~0~0~i>>92c+09 l>>ZDE+06 Ze58E+07 2'3E408 3>>25E+Pl 9>>56E+07 3>>08E+08 Ze 75E+09 5>>iZE+Db 2>>33E+88 6~37E+Pb 4'3E+06 i>>05E488 2'9E+bb i>>19E+QS 1>>32E+PS 2>>ZDE+10 0 0 0~0~0 6>>SZEibd 2'SE+84 1~6iE+06 Z>>69E+Dl Z>>13E+06 X.DSE+07 3>>62c+07 1'86+09 1~21E+09 4~17E+Dl i>>15coib 2>>31E+02 6>>95E>03 1~bDE+04 4>>41E+02 2>>58E>03 3>>2)E+07 F A C T 0 R S lSR>>HETER HREH/YR PER UCI/SEC)e e e e e e e e e e e e ee'e e e e e ee XIOHEY LUNG GI LLI N)ego~gypy'>>73E+02 9e73E+02 9>>73E+D2 0~9>>73E+DZ BASEO ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IH AHO A VALUE OF 1 FOR X/Oo OEPLETEO X/O ANO RE)ATIVE DEPOSITION NOTc THE UNITS FOR C 14 ANO H e3 ARE{HPEH/YR PER UCI/CU>>HETER)
ENVIRONNENtAL FAtHMAY OOSE CONVERSION FACtORS Rll)FOR GASEOUS OISCHARGES PATHMAY COMS MILK ECOMTANJ.(ATEO FORAGE)AGE GROUP-AOULT NU LIOE'CME 0 R G A N 0 0 S E F A C't 0 R S TSO~'HETER NREN/YR Pf R UCI/SEC)LIVER THYROIO KIONEY LUNG GI LLI H M%k~~SN 123 0>>SM,126"~,1>>65E409 SB,124'.;,'>>58E+07
-S 8 125,'>>64E+07 Tf 125N,-" i>>63f+Ol Tf 1Z7N.'.':~4>>63E<07 Tf 129M-.;" 6>>06E407'130.'4>>2?f405 I131~--2>>96f+Db I.132'-.1'>>67f ai I,133;".4>>00E+06 I 134~'0~I 135"'!:1>>45E404'S, 134:-;"5>>66E+09
-.CS 136-2'61f+08: CS 137,=i" l>>39E+09 BA>>140,rr'>>69BO?,.
', Cf 141")'>>91f>04 CE, 144 i'-'2 15E+06 0~3>>27E+a?4>>57 E+05 6>>0 6E+05 5>>91E+06 i>>63E+al 2>>2?f+07 X~26E+06 4>>25&08 4>>4?E ai 6>>94E+06 ae 3 70f+04 i>>35E+10 1 03E+a9 io aif+10 3>>38E+04 1>>97&04 d>>9?E+05 0~9>>5&f10&6'4E+04 Z>>99E+05 4~9if<06 i>>Zif<07 2.09E+07 1~&if 408 1~39E>11 5 bbE+01 1~33E+09 9>>98E 10 4'4E+06 0~0~a.0~a 0~~e Oe Oe 3>>72E+06 6>>63E+07 1085E+Dd 2>>53E+05 1096E+06 7>>2?E+08 7>>12E 01 i>>21E+07 0~5>>bdE+44 4>>36E+09 5>>74E+Od 3>>44E+09 1>>15E+04 9>>13E+43 5>>32E+05 5>>4e6?f+06 Ze OOE+Ol Z>>66E+09 0~0>>0~0~0~0~ae 0~7>>55F.-OZ 1>>45E+09 led?f+07 1>>14E+09 l>>93E+04 0~0~5~1~09f+09 7>>31E+ab 2>>29E+ab 6.50foo?2 11E+05 3'4E+05 1~abfo06 1>>12E+05 5>>39E 02 6>>10E+06 0~4e 1WE+04 2>>36E+05 1 e i?E+05 l>>95E iab 5>>70'E+57 7>>52E+07 7'&f>ab NH~Sary'~4~94f ta?i>>OZE+07 5>>23E ta&Ze ibf+06 5 72foo&9>>&if+06 4>>9?f405 2>>43foab 1~59f ai 2>>12E<06 0>>1>>3&f>>04 ie 10f+10 7>>43f+Ob 6>>62f 109 1~?bf<05 Z>>23f 4 03 1>>15f oa5 BASEO ON 1 UCI/SEC RELEASE RATE OF EACH ISOtOPE IN ANO A VALUE OF 1.FOR X/Oe OEPLETEO X/O ANO RELATIVE OEPOSITIOH NOTE THE UNITS FOR C 14 AMO H 3 ARE (NREM/YR PER UCI/CU HETER)
III~, r.~j ENVIROHHENTAL PATKHAY OOSE CONVERSIOH FACTORS R(11 FOR GASEOUS OISCKARGES PATH@AY GOATS HILr (COHTAH[HATEO FORAGE)AGE GROUP-AOULT NU LIOE 0 R G A K O C S E F A C T G R S tSQ HETER HREN/YR coo ooeooo\BONE LIVER THYRCIO rIOHEY LUHG GI LLI PER UCI/SECI 1<<99E+03 1~99F+03 1<<99E+03 1~99E+03 1<<996+03 wHoM goo)1'9E>03 CRo<<51 r NHoo54 4""~:-: Ff 59"-CO 57 co-ea A~LGJ ZH 65)-':,...RB 86~,-SR<<<<89's'..-"-SR 90:.: RU 103'-.RU 106 A 611+~2<<45E+10 0~0~3~8?f+05 0~0~a.t<<65E+08 a..3.aeE+09..9ebrf+14 1 03E+43 3<<82E+03 9<<9ZE+03.1<<23E+42 Z<<45E+03?<<OOE+06 io Z9E i 09 0~Iobiftae 9<<idf+05~1<<5CE+05 5<<67E+05 1<<98E+06 5<<ZCE+08 3<<12E+Od 0<<0<<0<<2e 10 E+03 5<<51E403 0<<0~=6<<48E+06 4~2<<05E403 0~0~ai 0~0~0~0~0~0-0~a.0~0<<0~0~0~7<<58E+OZ 3<<Oaf<05 0~Oo 0~0<<3<<50E+08 Oo 0~0~0~2<<14E+43 5<<46E+43 C<<69E+42 Co?3E+03 1<<2?f+07 0~C<<56E+03 0~2<<55E+05 0~0~0~4<<8~4<<~e 0~00 0<<0~0~0~2e31E+09 d o 64E+05 3<<09E+46 3<<03E+06 3'4c+06 i<<15E+07 3<<?OE+al 3<<30E+08 6<<15E+Ol C<<89fiab io 32E+09 5<<68E+~5 1<<26E+07 3<<3CE+07 1<<43E+44 1<<58E<<45 2'CE+09 0~0~0~4<<Oe 0~4 l<<9CE<<08 3'3E<03 1~93f<05 3 50E+05 2<<55E<05 1~2?E+46 4<<3CE+06 2<<37E<<bd 1~45E+ad d 76E<<al 2.41E+10 2.?rf<<01 b<<3CE+02 Z<<lrf>03 5<<30E>01 3<<10E<<02 3<<85E<<06~BASEO OH 1 UCI/SEC RELEASE RATf OF EACH ISGTOP E IN ANO A VALUE OF ie FOR X/Qo Of PLETE 0 X/0 ANO RELATIVE DEPOSITION HOTE TKE UHITS FOR C 14 AHO K 3 ARE (HREH/YR PER UCI/CU<<HETER) 0 IN aha-E&-~~EHVIRONHEHTAL FATH@AY BOSE COHVERSIOH FACTORS Rt I)FOR GASEOUS OISCHARGE'ATHWAY
-GOATS BILK (CONT':)IHATEO FORAGE)AGE GROUP AOULT NU LIOE ORGAN OOS ooo oooooofoooeooooooooooooooo LIVER-THZRCIO BONE E F A C T 0 R S (SOe HETER HREH/YR o o&oo w o o o KIONET LUNG GI LLI PER UCI/SEC)SH 123 SH 126 SBo124 SB 125 Ti 125H Tci27H TE 129H I 130 I 131 I 13Z I 133 I 134 135 CS 134 CS 136 CS 137 BAoi40 CE 141 CE 144 Qe 1~97EtQS 3eiQF+06 3e 16 E+06 1~96E+06 5'7Et06 le 27E+06 5~12E+05 3e56EtQS 2~QQE 01 4edbf<06.0.1~68 E+04 1~70Etid led4E+Qb Ze2ZE+10 3e23c+06 3e49E+03 2e58E+05 0~3e 92E+0&5e d5E+04 lo ZSE+04 le 1 0E+05 ie94E+06 2e72E+06 1~52E+06 5'0E+Qb 5e36Eo01 Se32E+06 0~4~44E+04 4e 04E+10 3o 09E+09 3e 03c+10 4e05E+03 2e36E+03 ioQSE+05 0~1~15E+06 lo49Ee03 3e5SE+04 5eb9Ei05 ie47E+06 Ze51E106 1~93c+bb io67E>ii le066+Ci 1 e60E+09 ieZQF-09 5 SQE+06 0~0~Qe 0~0~0~0~0~0~4e47E+05 le95E+06 ZeZ6E+Ql 3e04E+07 Ze36E+06 be7ZE+Ob 8~55E 01 ie45E+07 0~leQSE+04 ie 31F+10 ielZE+09 1~03E+10 ie3SE+03 ie 10 E+03 6e39E+04 0~5e61E+05 Ze40E+06 3e 19i+Qb Qe 0~0~Qe 0~Qe Qe 0~2e28E 01 4e34E+09 Ze36c+Qb 3e42E>09 2e322+03 Qe 0~0~1~31E+Qb b 77E+07 2el4E+Ol le diE+06 2e52E+Ql 3~65E+Ql 1~3QE+06 1~34E+Qb ie 01E 01 7o32Eib6 Qe 4e97E+04 7~06E+Qb 3'2E+Qb 5 d3E+08 6'4E+06 9'ZEt06 be liE+Ql 0.Qe 0 a.0~0~0~0 HHQL)=Q0Of 00 5e9ZE+06 1~Z2Ee06 6e 29E>05 Z~6ZE<05 6'6E~05 1~15E>06 5e96E>05 2'ZE+Qb 1~9)E 01 Z~54E<06 0~1~636+04 3e30E+10 2'3E+09 1~99Ee 10 Ze 13f.e 05 2'8E+02 1~3SE+04 BASEO OH 1 UCI/SEC RELEASE RATE CF EACH ISOTOPE IN ANO A VALUE OF io FOR X/Oe OEPLETEO X/0 AHO RELATIVE OEPQSITIQH NOTE THc UNITS FOR C 14 AHO H 3 ARE (HREH/TR PER UCI/CUeHETiR)
Ff>..'I<cir':
whSM G--W)ENVIRONHENTAL PATHWAY OOSE CONVERSION FACTORS Rlil FOR GASEOUS OISCHARCES PATHWAY HEAT (CONTAHINATE<.'ORAGE)
ACE CROUP AOULT>>'l l'UCLIOc'0 R G A N 0 C S E F A C T 0 R S tso HETER HREH/YR eeeeeeeee\eeeeeeee'eeeeeeeeeeeeeeeeeee\eeeeee\e eeeeeeeeeeeeeeeeee BONE LIVER THYROIO KIDNEY LUNG GI LLI PER UCI/SEC)e I,.~i>>,t r~~o l-~I'~I r>>*Heeeed Peee32 CRe 51 HNee54.FE 59 Co 57: CO 56 Coee60~3 ZN 65 RB e66~SR 69 SRee90 Yee 91 ZRee95 NB 95 RU>>103 PU 106 AG110+4>>67E+09 Oe Oe Ze 67E+08 Oo De Oe 3>>56E+08 Oe 3>>03E+08 i>>25E+10 i>>14E+06 3 lbf+06 2>>30BOS 1>>06E+06'ZedOE+09 6>>liE+06 2>>93E>06 0~r 9i 18 E+06--6>>33E+06 5>>SCE+06 ied3E+07.7>>55E+07 1>>13E+09'4>>69f+08-Oe.Oe.;0..1>>67E+06 1>>Zd&06 0~Oe S>>21E+06 0~4>>23ft03 0 0~.0~0~0-0~Oe De 0~0~0~0~0~0~0~'~ir56E+03 2>>73E+06 0~0~0~0~l 57E+06 0~0~0~0~Ze 01E+DS 1>>27E+D6 4>>OSE+08 5>>41E+09 1e22E+07 0~9>>38E+03 D~1>>76E+Od 0~0~0~0~0~0 0~0~0~0~Oo 0~0~5>>25E+Dd 1>>76E+06 2>>61c+0 2>>09E+09 1>>43E+08 3>>70E+bb i>>4if+09 7>>13E+06 9>>SCE+07 4'CE+07 1>>45Er89 6>>26E+Dd b>>30E+09 7 el5E+09 1~2CE+10 iebif+11 2'3E+09 C>>13E+02 4>>136402 4>>13f+02 4>>13E 102 4>>13E+02 De 0.0 0~0~II e De De 0 0 WHDLC 800+4~13EI 05~ck4l 1>>diE+08 7~07E<03 i>>75E r06 2'ifr06 9>>38frDS 4'9Er07 i>>66Erbd 5>>iZEr06 Zr Zdf+08 6>>67E+06 3>>05fr09 3>>05E+04 8'6E+05 5~DZEr05 4'9fr07 3>>5CEr06 3>>69E+06 BASSO ON 1 UCI/SEC RELEASE RATE CF EACH ISOTOPE IN ANO A VALUE OF i.FOR X/a, OEPLETEO X/O AHO RELATIVE OEPOSITIOH NOTE THE UNITS FOR C 14 AHO H 3 ARE (WREN/YR PER UCI/Cu>>NETERl
+I 1 P 0
+~a~~~-~~ENVIROHHENTAL FATHHAY DOSE CONVERSION FACTORS R(I)FOR GASEOUS OISCHARGES PATHWAY HEAT (CONTAHIHATEO FORAGE)AGE CROUP-AOULT NU LIOE 0 R 6 A H 0 0 S E F A C T 0 R S (SOeHETER HREH/YR PER UCI/SEC)teeeeoeeeeeeeeeeewo\eeeeeeeeeeeeeeoweeeeeeeeeeeeee BONE L I V ER THYROIO KIDNEY LUNG GI LLI SH 123 SHe126 SB 124 SBY125 TE 125H TE127H TE129H I ei30 I-131 I 132 I, 133 I 134 I 135 CS 134 CS 136 CS 137-BA 140 CEe141 CEei44 Oe.1 e 86E+10 1.99E+07 6e65E407 3'9E+Dd 1~13E+09 1~14E+09 Ze38E 06 1~08E+07 ae 4e40E Di 0~8.6aE-az 6e5dE+08 ieibE+07 8 73E+08 ZedbEt07 ie41E+04 1~46E+06 D~3e69E+08 3e75BD5 io58E+07 ie30E+08 3e93E+08 4o29E+08 leD5E 06 ie556+07 0~7.63E-01 0~le94E 02 ie57E+09 4'7E+07.1ei9E+09 3e63E+04 9e52E+03 6e10E+05 0~1'dE+Db 4ebDE+D4 1 29E407 1.adE~ad Ze96E+Od 3'5Etab 8~96Ee04 5~06E409 0~ie47E+02 0~Or 0~0~0~0~0~0~D~Oe 0~ie 746+08 ie46E409 4e56E+09 4e79E+09 iefDE 05 2e65E+07 0~ie33E+00 D~3eaiEe02 SeabE+08 Ze60E+07 4e06E408 ie23E+D4 4e41E+03 3e62E+05 0~6e 46E+06.ie54E+07 Ze49E+09 0~0~0~0~Oe Oe 0~0~9e04E 03 ie68E+08 3e56E+06 ie35E+08 Ze07E+04 0~0>>0~6e 19E+09 5 62E+Ob 3ebOEtab ie43E+09 5eiiE+09 5e76E+09 6e04E 06 4'7E+06 de 6e71E-01 0~1~86E 03 Ze74Etal 5e 31E+06 2'0E+07 6eblE+07 3e63E+07 4e93E+Ob ao 0~0~0 0~0~De De 0 a'tU HO~$(()P'~5'3E+08 leb5E+D6 1~05E+07 4ebiE+07 fe39E+08 iebZE+ad 2'7E 06 d 85Ei06 0~Ze 33E-D(0~3e 53E-OZ ieZBE+09 3e36E+07 7obZE+58 ie90E+06 ieabE+03 7ed3E+OC BASEO OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1~FOR X/O OEPLETEO X/0 AHD RELATIVE OEPOSITION NOTE THE UNITS FOR C 14 ANO H 3 ARE (t%EH/YR PER UCI/CUeHETER)
<<e ENVIRONNENT'AL FATHWAT DOSE CONVERSION FACTORS R(il FOR GASEOUS OISCHARCES PATHWAY FRESH FRUITS ANO VEGETABLES AGE CROUP-ADULT HU t.IOE Ho>>>>>>3~~a De ORGA\>>>>>>>>>>>>>>o>>>>>>>>
80HE LIVER N OCS THYROIO 4e02E+02 4eaZE+DZ E F A C'T 0 R S (SOo HETER HREN/YR PER KIOHET LUHG GI LLI 4o02E+02 4ea2E+02 4eDZE+02 UCI/SEC)~~DOY-urtto~Qgy'~DZE+DZ~o-P>>>>32 CR>>-51 HH>>54 FE 59 CO 57 CO 58 CO 60 ZN 65 RO 86 SR>>-89 SR-90'Y>>>>>>9 1 ZR 95 H8>>-95 RU>>103 f U>>106 AG11IPf t 1.04E+09 Go Do 3'4E+07 0~Do Do 5e iiE+07 0~2e 67E+09 8'9E+ia ie26E+DS 2>>93E+G5 4 87Et04 ie 50E406 2e95E+07 ie 69E<GS 6e5ic+07 0~4e blE+Ol bo64E+07 1'5E+06 6o89EtD6 Ze386+Ol ioSZE+08 ie30E+08 De.ae De 9od2E+04 2eliE+04 0~0~ie56E+06 0~ie15E+04 0~0~0~0~0~a.Oe 0~0~0~0~0~0~0~0~Oe 4e25E+03 ie45E+07 0~0~0~0~1 09E+08 0~0~0~0~1>>49E+05 Z>>68E+04 5e75E+06 5eliE+07 3eabE+GS Oe 2>>56f+04 0~2>>40E+07 0~0~De 0~0~de 0~a.0~0~0~0~0~1 ilE+08 4eb5E+06 1>>49E+ab 2'5E+Od 4elaE+07 1~4DE+Db 4>>46E+Db 1~02E+Db 2'6Et07 4>>26E+48 2>>14E+49 6'2E+Ob 3'4E+Od 1>>64E+Db 1~76E+ab 1>>91E+09 6e38E+Dd Do a.0 0~Oe 0~De Oe a ae 0~0~D 4'Zc+07 1~93E+04 9o31E+06 3o29f+07 3oadEoDS 1~54E+07 5e 23f+Dl le 34E+Dl 6~DSE+07 lo64Eoal Zo 07E+10 3o 37Et 04 6'8E+04 ioa6E+04 So49E+05 3'4E+06 9o 30E+05 BASSO ON 1 UCI/ScC REt.EASE RATE OF'EACH ISOTOPE IH AHO A VALUE OF ie FOR X/O~OEPLETEO X/0 AHO RELATIVE DEPOSITION EHVIRCHHEHTAL PATHHAY DOSE COXVERSIOH FACTORS Rtil FOR GASEOUS DISCHARGES PATHMAY FRESH FRUITS AHO VEGE'TA9LES AGE GROUP ADULT*>>t SH 123 SH 126.SBaiZ4 SBa125 TE 125H TE 127K Ti 129K I 130 Ia"131 I 132'I a133 I 134 I a135~CSa134 CS 136 CS>>137 BA 140 CEa141 Ci 144 1~OOE.05 9>>526+08 2,5ZE+07 2'>>58E>07 2>>38E+07 6>>75E+07 S 93E+07 3'3E<05~7>>78E+07 5>>57E+01~2>>13E+06 1~03Ea04.4'4E+04 6'2E+08 3>>32E+07 8>>90E+OS 1>>03E+08 l>>16E+44 5'9E+06 1.66Ea07 1>>89E+07 4>>75E+05 l>>23E<05'>>65E>06.2>>36E+07 3>>34E+07 1>>16E>06 1>>12E>08-1>>49E+42 3>>69E>06 Ze79E 04 1~07 E+05"'.1>>62E+09 1 31E+08 1~22&09 1>>35B05 4>>85E+04 Z>>17E+06 1>>416 47 5'4E+06 6'dE+04 4>>03E+05 l>>17E+06 1~77E407 3.0SE+07 1>>4CE+08 3 6>E<10 1>>96E+04 7>>10E>08 3>>63E OZ 1>>40E+Ol 0~8>>0~0~Oo Oo 0~0~0~5>>14E+06 9>>69E+07 2>>73E+08 3el3E+Ob 1>>81E+06 1>>91E+08 2>>38E+02 6>>44E<06 4>>45E 04 1>>70E>05 5>>26E+08 7>>29E<07 4>>146+08 4>>39E+04 2>>25E+04 1~29E>06 0~31E+06 1>>95E+Ol 2>>56E+09 Oo I~0~Oo 0.0~Ie Oo 8>>65E 03 1>>74E+08 9>>99E+06 iedlE+Od 7>>38E+04 0~I 2~04E 05 8>>46E+48 lei2E+08 2>>2ZE+48 9>>51E+07 3>>06E+88 4>>49E+08 9>>98E+05 Z~94E+47 Zedoi+41 3e 24E+86 2>>43E Il 1>>19E+45 2>>84Eo Ol 1>>49E+Il 2>>34E+Il 6>>65E+08 1.85E+08 1 e75E+09 HUCLIOE ORGAH DOSE FACTORS lSOHETERHREH/YR aaaaaaaaaaaaaaaaaaaa a\a BDHE LIVER THYROID KIDHEY LUHG GI LLI PER U 0 0.0 0~0~0~Oo Oo 0.0 CI/SEC)aaaa'a'>>aa Retest-9OOr wB~P~oy 2>>45Ea Ol 2~94E+07 9>>94E+06 5~iOE+06 3>>19E<06 8~3ZE+06 1~42Et Ol 4>>5SEt05 6e3SEo07 5~29E+01 1~13E>06 9>>99E 05 1~33E+09 9 43Eo07 7>>9SE+08 6>>77E+06 5>>49Eo03 2>>78E+05 sasEO oH 1 UCI/SEC RELEASE RAtE cF EACH ISOTOPE IH AHO A VALUE OF 1 FoR x/a, OEPLEtED x/a AHo RELAtIVE oEPDSITIOX 1
Page 172 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE M-2 Selecting the Appropriate Long Term (X/Q)o or (D/Q)for Dose Calculations Involving Radiolodlnes 8 8 D Particulates for.(1)lnhalatlon (2)Tritium (All gas pathways)(3)Ground Plane TYPE OF DOSE CALCULATION Instantaneous AoHQ Annual Runny 1i31 days,.Qtr.yearly, Annual Total Dose LIMITING RANGE (miles)0.97 0.97 0.97 0.97 0.97..LIM ING SECTOR (OL)WNW WNW,,'.~B;.;14X10 (DIG)1/m'2X10 82 X 1C.(OL}Over land areas only (A)To be determined by reduction of actual met data occurring during each quarter (8)For Tritium ln the Milk Ar.!mal Pathway, the (X/Q)o value should be that of the respective controlling sector and range where the Milk Animal h located as per Table M4.Example: If a cow was located at 4.25 mlles in NW sector, use the (X/Q), for 4.25 mlles NW.~~~"aa
'4g~4 Page 179 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 0 OFFSITE DOSE CALCULATION MANUAL ODOM APPENDIX B UMITED A LYSIS DOSE ASSESSMENT FOR LIQUID RADIOAC E EFFLUENTS The radioactive li id effluents for the years 1978, 1979 and 1980 ere evaluated to determine the dose ontribution of the radionuclide distribution.
Is analysis was performed to evaluat the use of a limited dose analysis for de rmlning environmental doses.Umiting the d e calculation to a few selected radion clides that contribute the majority of the dose p ides a simplified method of determ ing compliance with the dose limits of Control 3..1.2.Tables B-1 and B-2 presen the results of this evaluatl.Table B-1 presents the fraction of the adult whole dose contributed by t e maJor radionuclides.
Table B-2 presents the same data for th adult Gl-LLI dose.e adult whole body and adult Gl-LLI were determined to be the Iim g doses based o n evaluation of all age groups (adult, teenager, child and Infant)and I organs (bone, er, kidney, lung and Gl-LLI).As the data In the tables show, the radio uclides Fe-5, Co-58, Co-60, Znw5, Cs-134 and Cs-137 dominate the whole body se;the ra onuclldes, Fe-58, Co-58, Co-60, Zn<5 and Nb-95 dominate the Gl-LLI do.In all one case (1878-fish, Gl-LLI dose)these radionuclldes contribute 90%or mo of th total dose.If for 1878 the fish and shellfish pathways are combined as ls done to et ine the total dose, the contribution from these nuclides is 84%" of the total Gl-dose.Therefore, the dose commitment due dioactlve material In liquid eNuents can be reasonably estimated by limiting the ose Iculation to the radionuclldes, Fe-59, Co-58, Co-60, Zn45, Nb-95, Cs-134 and s-137, Ich cumulatively contribute the majority of the total dose calculated by using ll radionu Ides detected.This limited analysis dose assessment method is a slmpllfl't.alculation at provides a reasonable evaluation of doses due to liquid radioactive Nuents and all ws for an estimate of Fe-55 contribution to dose.Tritium is not included In tk limited analysis dose ssessment for liquid releases because the potential do resulting from normal re ctor releases is negligible and ls essentially Independent radwaste system operatlo.The amount of tritium releases annually ls ahcut 300 c ries.At St.Lucia, 300 Cl/p leased tc the Atlantic Ocean produces a calculated ole body dose of 5 X 10 m r via the fish and shellfish pathways.This amo ts to less than 0.001%of the de n objective dose of 3 mrem/yr.Furthermore, th'e rel ase of tritium Is a function of operat g time and power level and is essentially unrelat to radwaste system operation.
The se due to Iron-55 made lt necessary to change the cons atlsm factor from 0.8 0.6, which was done on Revision 7 to the ODCM, based on eaQ 1986 data.
age 180 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, R ISION 19 OFFSITE DOSE CALCULATION MANUAL 0 M TABLE B-1 ADULT HOLE BODY DOSE CONTRIBUTIONS F CTION OF TOTAL RAOIONUCLIDE 1978 SHELLFISH FISH 1979 SHE ISH FISH SHELLFISH Fe-59 Gs-134 Cs-137 TOTAL 0.08 0.10 0.01 0.31 0.42 0,97 027 0.19 025 0.10 0.07 ,10 0, 0.08 0.03 0.04 0.02 048 0 0 048 0.15 0.13 0.19 0.14 0,11 1.00 0.02 0.15 0.04 027 0.30 0,9&0.05 0.44 0.22 0.20 0,04 0.04 0.99 RADIONUCUDE TABLE 2 B l, q~~l~>~i'a~E\FISH=, SHELLFISH FISH ELLFIS FISH~SHELLFISH Fe+9 TOTAL 0.03 0.0.0.98 OM OM 0.31 0.02 0.01 0.92 026 0.12 0.18 0.01 041 0.76 044 19 0.0,0 0.90 0.01 0,05 0.04 0.01 0.88 0.97 0.07 047 OM 0.04 0.01 0,97~i 1Q))If'%IIW k lpy p'+C~l'E~I Page 181 of 194 ST.LVCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISI 19 OFFSITE DOSE CALCULATION MANUAL DCM APPENDIX C CHNICAL 8ASES FOR EFFECTIVE DOSE F TORS Overview The evaluation of dose due to releases of radioactive m erial to the atmosphere can be simplified by the use of e ective dose transfer factors I tead of using dose factors which are radionuclide specie.ese effective factors, wh are based on the typical radionuclide distribution in t e releases, can be ap ed to the total radioactivity released to approximate the dose in t environment, l,e., stead of having to sum the Isotopic distribution multiplied by the is tope specie do factor only a single multiplication (K, M~or N~)times the total quan of radloact e material released would be needed.This approach provides a reason ble estlm of the actual dose while eliminating the need for a detailed caiculational t hnlque Dee In ti E iv The effective dose trinsfer factors a ased on past operating data.The radioactive effluen distribution for the past yea ca be used to derive single effective factors by~the followtng equations:
K,>>]Kr f, X (C-1)Where: t effectlvetotalbodydo factordueto gamma lssfons fram all noble g s released the total body dose factor du to gamma emlssions from each noble gas radionuc de i released I the fractiorial abundance of nob gas radlonucllde i is of the total noble gas radlonuc des I
Page 182 of 194 ST.LUCIE PLANT CHEM TRY OPERATING PROCEDURE NO.C-200, REVISION 19 FFSITE DOSE CALCULATION MANUAL ODCM APPENDIX C TECHNI L BASES FOR EFFECTIVE DOSE FACTORS (continued)(L+1.1 M)~~((L(+.1 M)f, Z (C-2)Where:{L+1.1 M)~=the effective dose factor due beta and gamma emlsslons from I noble gases eased{L,+1.1 M)=the skin dose fact due to a and gamma emlssions from each noble ga radlon elide l released M~]M,~f, Z (G4)Where: M'ff the effective al dose factor ue to gamma emlsslons from all noble ases rel~'~,-the air do factor due to gam a emlsslons from each noble gas dlonucllde l rele N~~].Nj~f(X (~)Where: Neff e effectiv air dose factor due to beta II noble gases released the air dose factor, due to beta emlsslons gas radlonucllde I lssions from each noble Page 183 of 194 ST.LUCIE PLANT CHEMIS Y OPERATING PROCEDURE NO.C-200, REYISION 9 0 SITE DOSE CALCULATION MANUAL DCM APPENDIX C TECHNIC L BASES FOR EFFECTIVE DOSE FACT RS (continued)
To determine the appropriate ective factors to be used an o evaluate the degree of variability, the atmospheric radi ctlve effiuents for the past years have been evaluated, Tables C-1 and C-2 sent the results of this valuation.
~As can be seen fram Tabtes C-t a t', the siisctiv dose transfer factors varies iittie from year to year.The maximum ob rved variabil from the average value ls 18%.This variability is minor considering o er areas of certainty and conservatism Inherent in the environmental dose calculation odels.To provide an additional degree of conse atl, a factor of 0.8 ls Introduced into the dose calculation process when the effectlv ose transfer factor ls used.This added conservatism provides addional assu that the evaluation of doses by the use of a single effective factor wIll not slgnicantly n restlmate any actual doses In the environment.
~IhBLllll The doses due to the gaseous e ents are evalu ted by the more detailed calculation methods (l.e., use of nuclide c dose factors)n a yearly basis.At this time a comparison can be made betw the slmplied me od and the detailed method to assure the overall reasonabl ess of this limited ana ls approach.If this comparison Indicates that the radlonuci distribution has chan gnicantly causing the slmplied method to underestimate doses by more than 20%, e value of the effective factors will need to be reexaml to assu;~the overall a llty of this approach.However, this reexamlnatlon will be needed lf the doses as ca lated by the detailed analysis exceed 50%of the des n bases doses (l.e., greater than mrads gamma air dose or 10 t mrads beta air dose).In any case, the ropriateness of the A value will be peri lly evaluated to assume the applicability o a single effective dose factor for evaluating vironmental doses.'~~~1 r'\~rr r r r~r Pag 184 of 194 ST.LUCIE PLANT CHE TRY OPERATING PROCEDURE NO.C-200, REVIS N 19 FFSITE'DOSE CALCULATION MANUAL ODCM I TABLE C-I EFFECTlYE DOSE FACTORS NOBL GASES-TOTAL BODY AND SKIN OSES YEAR 1978 1979 1980 AVERA E TO L BODY EFFECTIVE OSE FAGTOR rem-m'i-r 7, X1 7A 1 5.6 X 6.8 X1 S EFFECTIVE OSE FACTOR (L+1.1M),
mrem-m'i-r 1.4 X 1 1.4 X 1 1.2X 1 1.3 X 1 TABLE C-2 BLE GASES-'AIR D SES YEAR 1978 1979 1980 AVERAG 8AM AIR EFFECTIVE SE FACTOR M~'B&QL'i<<r 8.0X1 8.0X1 6.2X1 7.4X1 ETA AIR EFFECTIVE DOSE FACTOR N~mrmBa'I-1.2 X 1 2 X 1 1.X1 1.2 1 0 e.twas r~
Page 185 of 194 ST.LUCIE PLANT HEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 1 OFFSITE DOSE CALCULATION MAN AL M APPENDIX D TEC ICAL BASES FOR ELIMINATING CURIE INVENTO LIMIT FOR GASEOUS VtASTE STORAGE TANKS The NRC Standard hnlcal Specmcations include a limit for e amount of radioactivity that can be stored In single waste gas storage tank.This rie inventory limit is established to assure at In the event of a tank failure rele ing the radloactMty to the t environment the resulti total body dose at the site boun ary would not exceed 0,5 rem.For St.Lucie, the Invento limit In the waste gas sto e tank has been determined to be approximately 285,000 ries (Xe-133, equivalen.An allowable primaty coolant radioactMty concentration established by the Ap ix A Technical Specifications which limits the primary cool t radioactivity co ntratlons to 100!E with E being the average energy of the radloa vlty In Mev.Thl equation yields an upper primary coolant gross actMty limit of ut 160 pCVml By applying this actMty concentration limit to the total liquid volume o the primary em, a total actMty limit can be determined.
For St.Lucie the p any syst volume Is about 70,000 gallons, which yields a limiting total Inventory of proxl tely 43,000 Ci, By assuming a typical radionucllde 1st utlon an equivalent Xe-133 Inventory can be determined.
Table 0-1 provides the ical radlonucllde (noble gases)distribution and the Xe-133 equivalent concentration.
e equivalent concentration ls determined by multiplying the radionuciide concen tl n by the ratio of the nuclide total body dose factor to the Xe-133 total body fa r.Summing all the Individual radlonuciide equivalent concentrations provid the o rail reactor coolant Xe-133 equivalent concentration.
The data show at the eq lvalent concentration Is a factor of 2 larger than the gross concentration (i., 24 pCVg total versus 47 pCVgm equivalent).
The resulting Xe-133 equivalent rle inventory f the reactor coolant system Is approximately 86,000 Cl.Therefore, even lf the to primary system at maximum Tech.Spec.allowable~concentration was to a slnttto waste as decay tank, the tank curie tnventory would be well below th 285,000 Cl limit.on this evaluation, the curie Inventory limit on a single wast gas storage tank cannot ceed the Technical Specification requirement.
'~0~l Page 186 of 194 ST.LUCIE PLANT EMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CAL/LA N MAN AL OD M TABLE 0-1 REAC OR COOLANT-XE-1 3 EFFECT1VE CONCENTRA N REACTOR OO LANT'ONC TION RADIONUCLIDE (gCVgm REG.GUIDE 1.109 TOTAL BODY DF~mret~(pGVml)RATI X 33DF Xe-133 EFFECTIVE CONCENTRATION (pCVgm)Kr45m Kr<?Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 T TAL 0,19 0,83 0.18 0,31 8.8 0.11 0,02 0;12 24.12X10 1.6 X 10 5.9 X1 1'1 QZ 1 2.5 X 10.Q 1 10 1.1 4.1 0.06 0.32 0.86 1.0 4.8 0.78 0.05 16.2.8 0.17 12.7.4 0.1 3.6 47.~'Data adapted trom the NRG GALE'a~<<*1<<g<<+%*AD t ps<<p q<<'~
ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODGM'APPEND RADIOLOGICAL ENVIRONMENT L SURVEILLANCE ST.LUCIE PLANT Key to SamPIe LocatIoos Page 187 of 194" PATHWAY DESCRIPTION SAMPLES COLLECTED SAMPLE APPROXIMATE COLLECTION DISTANCE FREQUENCY (miles)DIRECTION SECTOR*DfrectRadlatfon
.=N-1" Northof BffndCreek
Direct Radiation NNWN.South ot Pete Stone Creek Dhect Radfa5an.NNW-10" C.G.Station NNW Dhect Radiation~NW-10.Intersectke ol SR 68 and SR 607-., Direct Radfatfon, WNW-2.

Cemeteqr South of 7107 frxSan River DrfveDhectRadfatke
-: WNWN: USr1atSR712
..--.:.Dfrect Radfalkl-WNW-10 SR 70, West of Tumplke Dhect Radiation,-W-2,.7609 lnrNan River Drive.Dhect Radfalkl.W+Oleander and Sager Streets Dfrect Rarlatkrn.W-10 M5 and SR 709.Dhect Ra@ation.WSW-2 8503 hxian River Drive DfrectRadfatfon.WSWW PrfmaVfstaSIvd.atYachtQub Dfrect Radiation~WSW-10 Del Rfo and Davis Streets Direct Radiation SW-2 9207 indian River Drive Direct Radhrtfon SWW US 1 and Viage Green Drive Direct Radfaffon=SW-10 Port SL Lucfe Sfvd.and Caha P~DfrectRadfa5on SSW-2 10307INianRIverDrfve 10 10 10 10 WNW W WSW WSW WSW SW SW SW SSW ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFF ITE SE AL LATlON MANUAL ODCM APPEN RADIOLOGICAL ENVlRONIIENY SURVEILLANCE (conttnued)
"-ST.LUCIE PLANT Key to SampIe LocatIoos Page 188 of 194'PATHWAY;;,*
LOCATION DESCRIPTION SJVAPLES COLLECTION FREQUENCY APPROXIMATE DIRER N DISTANCE Sf CTOR (mlles)-~~,~5~>s~5 Dhect Radiation.DIrect Rariatlon-Dkect Rarlatlon.'kect Rarlatlcn: Dhect RaNation: Direct Radiation'irect Radlaticn Ahbome-AIrbome, Ahbome Ahbome-SSW4: 'SSW-10":;:$5~::":.S.10~.'-.-'SSSE-50:
~'..SS&5...-..: SSE-10"..;%42'.H08 Port St.Luckr Svd.and US 1 Pine Yaiey and Westrnoreland Roads 13178 le%an River Drfve,-US1 and SR 754 hxRan River Drive and Qual Run Lane Entrance of NeNes hrhrnd.--"--Eiot Muserin'"*'---.South of GooNng Canal U.of Florida-1FAS Entomology Lab Yero Beach FPL Substatlon
-Weatherby Road FPL Substatlon
-SR 76, Stuart Onslte-near south property line Power une-7609 Indhrn RIver Drive Redlolodlne 8 Particulates Radlolodlne 8 Partlcutates 50 50 50 SSW S S SE'Denotes Control SampIe I
ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19-OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX~RADIOLOGICAL ENVIRONIJIENT SURVEILLANCE (aetlnued)
ST.LUCIE PUBS Key to Sample Locations Page 189 of 194'ATHWAY LOCATION r DESCRIPTION SAMPLES COLLECTED APPROXŽT DIRECTION E DISTANCE sE~TOR (mmes)AIrbome, H34;;Onstta'-'.At Meteorofoglcat Tower 0.5~, P.Waterborne H15 Surface Water AttantIc Ocean vtcInIty of pubIIc beaches east sR5e (ocean)of Route A1A-Sedfment from shoreine ENE/E/ESE Waterborne
.'H59 Near south end of Hutchlnson Ishnd Surface Water (ocean)SedIment fmm stroreIIne S/SSE Food products H15 Ocean sate vtcIntty of SL LucIe Rant (NOTE 1)Crustacea Rsh ENE/E/ESE Denotes control sampIe (mangrove)
ST.LUClE PLANT CHEMlSTRY OPERATlNG PROCEDURE NO.C-200, REVlSION 19 OFFSlTE DOSE CALCULATlON MANUAL ODCM , APPENDIX~+
RADfOLOGlCAL ENVNONNENTAL StJRVHLLANGE (continued)
ST.LUCfE PLANT Key to Sample Locations Page 190 of 194 0~\4 PATHWAY.Food Products LOCATION H52 Near south end d HutchInson island SAMPlES COLLBCTED Broad ket vegetatIon
~(mangrove)
Crustacea FIsh Broad leaf veg@atlon (mangrove)
SAMPlE COLLECTION FREQUENCY Monthly (when avaIIable)
See%-Annually Monthly APPROXIMAT E DISTANCE (mIIes)'sC-20 DIRECTION SECTOR 8/SSE II'C~~Denotes cofltlol salnple ft is the policy of Florida Power 8 Ught Company (FPL)that the St.Lucie 1 8 2 Radiofogical Environmental Monitoring Programs are conducted by the State of Florid Department of Health and Rehabltatfve Services (DHRS), pursuant to an Agreement between FPL and DHRS and;that coordination of the Radiological Environmental Monitoring Programs with DHRS and compliance with the Radiological Environmental Monitoring Program Controls are the responsibility of the Nucfear Energy Services Department NOTE 0 These samples may be coffected from or supphmented by samples collected fIom the plant fntake canal if the required analyses are unable to be performed due to unavailability or inadequate quantity of sample from the ocean side location'.
Page 193 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CAI CULATION MANUAL ODCM APPENDIX'ETEOROLOGICAL DISPERSION FORMULAS'or xrQ: (u)o 2.032 (g+)2 cV't EQ (1}g/Q 2o032 z (u)D EQ (2}Where:~c (u)=.5~207.5 ft.(63,2 meters)a name for one term X/Q was calculated using each of the above EQs for each hour.The highest X/Q from EQ (1)or EQ (2)was selected.The total integrated relative concentration at each sector.and distance was then dlvkied by the total'number of hours in the data base.l~~N~5~-.Terrain correction factors given by Table MA were also applied to Dispersion Formulas n\I I~1~~~~'L~
1 h0 Page 194 of 194 ST.LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM APPENDIX'METEOROLOGICAL DISPERSION FORMULAS'continued)
~P~I dXI (NQ)~=(NQ)X (Depletion factor of Figure 2 of R.G.1,111-R1)~~Fi D D/Q=RDep/(2 sin[11.25]X)X (Freq, distribution)
Where: D/Q~Ground deposition rate X=Calculation distance RDep=Relative ground deposition rate fram Figure 6 of R.G.1.111, R1~ew p~e~~S\~I~'I
i~t.199A ST.LUCK PLANT CHEMISTRY OPERATING PROCEDURE C-200.REVlSION 20 AI N METHODOLOGY SECTION APPENDIX D DESCRIPTI N f he IN RLAB NP I The State of Florida, Department of Health-Bureau of Radiation Control(BRC)
Laboratory shall participate in an INfEIU.ABORATORY COMPARISON PROGRAM.1.Thc sample matrices and analytical methods shall bc: A.Gamma isotopic on a filter sample sirmthttlng airborne radioiodine and particulate collection.
B.Gamma isotopic on a water sample simulating a surface water grab sample.C.Gamma isotopic on either scdimcnt(or soil)or broad leaf vegetation.
2.Thc source of samples for this prograttt:
A.A Federal Govenmtent Laboratoty Program (c.g., DOE-LAP, EPA Safe Drinking Water Program)B.A State, Federal, or private (commercial) laboratoty capable of providing NIST traceable samples.To be eligiHe, a Commercial Laboratory shall meet thc FPL Quality Assurance criteri of"Quality Related".'I C.For Gamma Analysis only, a FPL Nuclear Site Laboratory may prepare sample matrices using known quantities of radioactivity from isotopes provided by a FPL Contract Laboratory currently approved as PC-1 Level vendor.'Ihcsc pre pttred matrices may bc prqered by thc vendor, or by FPL personnel, but shall not~the participant(s) form aaVor license quantitics for allowed radioactivity.
3.Analysis of Matrix samples shall be capable of achict~ODCM TaHe 4.12-1 prescribed LLD's on a bhmk sample.4.Results within 20%%d of expected shall be considered acceptable.
Results exceeding 20%but within 35N requite a description of probaHe cause and actions performed to bring tbe analysis into conformance.
Results excectling 35%%d arc considered Not Acceptable'he Matrix shall b replaced and reanalyzed.
5.Thc frequency for performing the interittboratoty comparison program shall bc annually with a nulinnnn of 1$months between comparisons of ahnilar matrices.I, C'UU U ,4 I'I I I I\'I I DOCUMENT NO.ADDENDUM SHEET REV.FOR DOCUMENT PROOFREADING Verify the following on the cover sheet or 1st page:~The FRG date(s)correspond to the FRG date on the PCR(s).~The Plant General Mgr.name Is correct and the PGM Approval date corresponds to the PGM Approval date of the latest PCR.~The revision number In the header In Secttort 2 and tn the~HOPS'h d p tth Verify the following on each page of the procedure:
~The correct revlslon number on~e~a~e.~The page count Is correct.PLEASE make sure every page has the correct number.~Only current revlslon marks are present In the procedure and all changes are Identified by current revlslon marks (/R)or a complete rewrite statement Is written In bold on the first page, prior to section 3.~Verify the changes made via the PCR have been processed accurately.
~Verify the step sequence ls corre.t.~All DRAFT marks have been removed from each page.This document has been pmnfread and veNIed to have Incorporated the changes as Indicated on the enclosed PCR Form(s)..All special matMnjs have been incorporated except those which are Incvoiporated by the Vault Custodian.
CHARTSJ GRAPHICS~AND FIGURES'ust be'eplaced with legible, reproducible prints Proofread by: I'ept.I 1 sic~Date~~~
0=

ML17229B036

Contents

Text

2.3 Determining

2.3.1 Inhalation

2.3.2 Ground

2.4 Determining

2.6.1 Inhalation

2.6.2 Ground

2.6.5 Vegetation

4.0.1 Surveillance

1.3.2 Setpoints

3.3 Doses

Navigation menu

ML17229B036

Text

2.3 Determining

2.3.1 Inhalation

2.3.2 Ground

2.4 Determining

2.6.1 Inhalation

2.6.2 Ground

2.6.5 Vegetation

4.0.1 Surveillance

1.3.2 Setpoints

3.3 Doses

Navigation menu

Search