Revision as of 12:15, 4 February 2020

Text

Rev 20 to Procedure C-200, Odcm.
	ML17229B036
Person / Time
Site:	Saint Lucie
Issue date:	12/22/1998
From:	West R, Wethy C; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17229B034	List: 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 CALCULATIONMANUAL(ODCM) 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 4/22 1982 Approved by C. M. Weth Plant General Manager 4/27 1982 Revision 20 Reviewed by F R G 12/22 19 98 Approved by R. G. West Plant General Manager 12/22 1998 THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING. /R20 S OPS DATE DOCT PROCEDURE DOCN C-200 SYS 99030VOKBi 'P'F0226 COMP COMPLETED PDR ADOCK 05000335 l,".<I ITM 20 R POR Q

Page 2 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX PAGE INTRODUCTION .... 7 CONTROLS SECTION DEFINITIONS FOR CONTROLS SECTION ... 9 1.1 ACTION .. 9 1.4 CHANNEL CALIBRATION .... .,.... . 9

~

1.5 CHANNEL CHECK ~ .. ... 9 1.6 CHANNEL FUNCTIONAL TEST ~.... ~ . ~ ~ ~ 9 1.10 DOSE EQUIVALENT 1-131 .. 10 1.13 FREQUENCY NOTATION ........... ~ 0 10 1.17 MEMBER(S) OF THE PUBLIC........ 10 1.18 OFFSITE DOSE CALCULATIONMANUAL 10

~ ~ ~ 0 ~ 0 ~

1.19 OPERABLE - OPERABILITY ~ ~ 11 1.20 OPERATIONAL MODE - MODE.......

1.24 PURGE - PURGING ~ ~ 11 1.25 RATED THERMAL POWER.......... 11 1.27 REPORTABLE EVENT ~ ~ 11 1.30 SITE BOUNDARY................. 12 1.31 SOURCE CHECK ~............... ~ ~ ~ 12 1.33 THERMAL POWER................ 12 1.34 UNPLANNED RELEASE ...... ~ . ~... ~ ~ 12 1.35 UNRESTRICTED AREA ~ ~ 13 1.39 VENTILATIONEXHAUST TREATMENT SYSTEM 13

~ ~

1.40 VENTING .. 14 1.41 WASTE GAS HOLDUP SYSTEM .. ~... 14 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS ~......... 16 3/4.0 APPLICABILITY 16 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ~ ~ 17 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ~ ~ 22 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION ~ ~ 32

-- D OSE 36

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

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

LIQUID RADWASTE TREATMENT....... ~ ~ 37

Page 3 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX CONTROLS SECTION PAGE CONTROL AND SURVEILLANCE STATEMENTS FOR CONTROL SECTION-3/4.11 RADIOACTIVE EFFLUENTS (Continued) 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE .............. .. 38 DOSE - NOBLE GAS........ .. 42 DOSE - IODINE-131, IODINE-133, TRITIUMS AND RADIONUCLIDES IN PARTICULATE FORM ..... 43 GASEOUS RADWASTE TREATMENT .......... ~.... ~ ~ ~ 44 3/4.11.3 (NOT USED) 3/4.11.4 TOTAL DOSE ..... ~........ ...... 46 3/4.11.5 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS (ADMINISTRATIVECONTROL) ...... 48 3/4.11.6 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION (ADMINISTRATIVECONTROL) ~ ~ ~ ~ ~ ~ 49 3/4.12 RADIOLOGICALENVIRONMENTALMONITORING 3/4.12.1 MONITORING PROGRAM ...... .. 52 3/4.12.2 LAND USE CENSUS .......... .. 61 3/4.12.3 INTERLABORATORYCOMPARISON PROGRAM ....... .. 63 3/4.12.4 ANNUALRADIOLOGICALENVIRONMENTS,L OPERATING REPORT (ADMINISTRATIVECONTROL) ............. ..... 64 BASES for CONTROLS SECTION 3/4.11 RADIOACTIVE EFFLUENTS 3.3.3.9 INSTRUMENTATION ....... .. 66

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.1 1.1 LIQUID EFFLUENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 67 3/4.11.2 GASEOUS EFFLUENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 69 3/4.11.3 (NOT 72 USED)'OTAL 3/4.11.4 DOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.12 RADIOACTIVE ENVIRONMENTALMONITORING 3/4.12.1 MONITORING PROGRAM ....... ........ 74 3/4.12.2 LAND USE CENSUS . . ~....... 74

~ ~ ~ ~ ~ ~ ~ ~

3/4.12.3.- INTERLABORATORYCOMPARISON PROGRAM ..... ~ 75

Page 4 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM INDEX CONTROLS SECTION PAGE LIST OF FIGURES for CONTROLS SECTION FIGURE 1-1 SITE AREA MAP & ENVIRONMENTALSAMPLE LOCATIONS .... 221 1-2 ENVIRONMENTALSAMPLE LOCATIONS (10 MILES) ~........, 222 LIST OF TABLES for CONTROLS SECTION TABLE 1-1 FREQUENCY NOTATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 5 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .............. ~ ~ ~ ~ ~ ~ ~ 1 8 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ............. ~ . ..

23 27 3.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS 3.12 1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM... .. 54 3.12-2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTALSAMPLES .. 57 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQOIREMENTS .. 20 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .. 29 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.......... ~ ~ ~ ~ ~ ~ ~ ~ 33 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSiS PROGRAM.......... ~ . 39 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTALSAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD) ........ ~ .., ... 58

Page 5 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM INDEX METHODOLOGY SECTION PAGE Glossary for Methodology Section ... ~............. ~........ . 77 1.0 LIQUID RELEASES METHODOLOGY ..... .. . 80

~

1.1 Radioactive Liquid Effluent Model Assumptions 81 1.2 Determining the Fraction (F) of 10 CFR Part 20 Effluent Concentration Limits (ECL) for a Liquid Release Source ........ 82 1.3 Determining Setpoints for Radioactive Liquid Effluent Monitors ...,................, ~ ~ ~ ~ ~ ~ ~ ~ 85 1.4 Determining the Dose for Radioactive Liquid Releases . ~ ~ ~ ~ ~ ~ ~ ~ 89 1.5 Projecting Dose for Radioactive Liquid Effluents..... ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 2.0 .Radioactive Releases of Gaseous Effluents .... 94 2.1 2.2 Gaseous Effluent Model Assumptions ............, .... 95 Determining the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing Setpoints for Effluent Monitors.......................... ~ ~ ~ ~ ~ ~ ~ ~ 96 2.3 Determining the Radioiodine and Particulate Dose Rate to Any Organ From Gaseous Releases ............ .. 110 2.3.1 Inhalation .............. ~............. ~

... 112 2.3.2 Ground Plane . ... 114 2.3.3 Milk 115 2 3 e4 Tntl um

~ e ~ ~ ~ ~ ~ ~ ... 117 2.3.5 Total Dose Rate by Release Source......... 119 2.4 Determining the Gamma Air Dose for Radioactive Noble Gas Releases 119 2.5 Determining the Beta Air Dose for Radioactive

.Noble Gas Releases 'f22 2.6 Determining the Radioiodine and Particulate Dose to Any Age Group's Organ From Cumulative Releases .

DISCUSSION

.....,. 124 2.6.1 Inhalation ...... ~....,..... 'I 26 2.6.2 Ground Plane ............. ... 127 2e6e3 Milk e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

e

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. 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 (continued) 2.6.4 Meat..................... 129 2.6.5 Vegetation ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 31 2.6.6 Tritium (All pathways) 1 33

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2.6.7 Total Organ Dose 1 34

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2.7 Projecting Dose for Radioactive Gaseous 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 ............ 152 Appendix B - Current R.E.M. Sample Point Locations ........... ~ ~ ~ ~ ~ ~ ~ 217 Appendix C - Description of Meteorological Dispersion Formulas Utilized for Historical Data and IVlethodology for Determining Actual MET Data 223 Appendix D - Description of the lnterlaboratory Comparison Program ~ ~ ~ ~ ~ ~ ~ 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 CALCULATIONMANUAL 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 CALIBRATIONshall encompass the entire channel including the sensor and alarm and/or trip functions and shall include the CHANNEL FUNCTIONALTEST. The CHANNEL CALIBRATIONmay 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 FUNCTIONALTEST 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 CALCULATIONMANUAL 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. 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.

3. 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 CALCULATIONMANUAL 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.

VENTILATIONEXHAUST 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 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

4/M* 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.

Q At lease once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not Applicable.

P** Completed prior to each release

For Radioactive Effluent Sampling

- For Radioactive Batch Releases Only St. Lucie Plant ODCM Controls

Page 16 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 3/4 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL(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 MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a) Liquid Radwaste Effluent Line 35 b) Steam Generator Blowdown 1/SG 36 Effluent Line

2. Flow Rate Measurement Devices a) Liquid Radwaste Effluent Line N.A. 38 b) Discharge Canal N.A. 38 c) Steam Generator Blowdown N.A. 38 Effluent Lines 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. 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

b. 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 CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a) Liquid Radwaste Effluent R (2) Q (1)

Line b) Steam Generator R (2) Q (1)

D Blowdown Effluent Line

2. Flow Rate Measurement Devices a) Liquid Radwaste Effluent N.A. Q D (3)

Line b) Discharge Canal D (3) N.A. Q c) Steam Generator N.A. Q D (3)

Blowdown Effluent Line St. Lucie Plant ODCM Controls

Page 21 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 4.3-8 Continued TABLE NOTATIONS (1) The CHANNEL FUNCTIONALTEST 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) CHANNELCHECK 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 CALCULATIONMANUAL 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 CALIBRATIONand CHANNEL FUNCTIONALTEST 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 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Waste Gas Holdup System a) Noble Gas Activity Monitor-Providing Alarm and 1/Rx 45 Automatic Termination of Release

2. Condenser Evacuation System a) Noble Gas Activity Monitor 1/Rx 47

3. Plant Vent System

~

a) Noble Gas Activity Monitor 1/Rx (Low Range) b) Iodine Sampler 1/Rx 51 c) Particulate Sampler 1/Rx 51 d) Flow Rate Monitor N.A. 53 e) Sampler Flow Rate Monitor 1/Rx 46

4. Fuel Storage Area Ventilation System a) Noble Gas Activity Monitor 1/Rx 47 (Low Range) b) Iodine Sampler 1/Rx 51 c) Particulate Sampler 1/Rx 51 d) Flow Rate Monitor N.A. 53 e) Sampler Flow Rate Monitor 1/Rx 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 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

5. Laundry Area Ventilation System a) Noble Gas Activity Monitor 1/Rx 47 (Low Range) b) Iodine Sampler 1/Rx 51 c) Particulate Sampler 1/Rx 51 d) Flow Rate Monitor N.A. 53 e) Sampler Flow Rate Monitor 1/Rx 46

6. Steam Generator Blowdown Building Vent a) Noble Gas Activity Monitor (Low Range) b) Iodine Sampler 51 c) Particulate Sampler 51 d) Flow Rate Monitor 53 e) Sampler Flow Rate Monitor 46 St. 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 CALCULATIONMANUAL 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 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 3.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS CHANNEL BASIS HIGH ODCM Effluent Gas Channels DOCUMENT ID SETPOINT'x SETPOINT'llotted

% Of 1PV LOW RANGE GAS 01%5 Bkg.

Site Limit'llotted

% Of 1FHB LOW RANGE GAS Sx Bkg. Site 2A PV PIG LOW RANGE GAS 423 5x Bkg. Limit'llotted

% Of 2B PV PIG LOW RANGE GAS 433 5x Bkg. Site Limit'or Plant Vent ff2 C-200'-200'-200'-200'-200'-200'-200'-200 2PV WRGM LOW RANGE GAS 621 5x Bkg.

Allotted % Of 2FHB LOW RANGE GAS 413 Sx Bkg. Site Limit'llotted C-200'-200'LERT % Of SGBDB LOW RANGE GAS 45% 5x Bkg. Site Limit~

1 CONDENSER AIR EJECTOR 35 2 x Bkg.' 3x Bkg.

2 CONDENSER AIR EJECTOR 403 C-200 x Bkg.'s 3x Bkg.

1 BATCH GAS EFFLUENT 42 Per C-72 As Per C-72'~

2 BATCH GAS EFFLUENT 203 As Per C-72 As Per C-72'~

CHANNEL BASIS ALERT HIGH ODCM Related Particulate Channels ID DOCUMENT SETPOINT'000 SETPOINT 1PV PARTICULATE 01-01 FUSAR CPM 10,000 PARTICULATE 04-01 FUSAR 5 TS'000 CPM 10,000 CPM'FHB CPM'0,000 2A PV PIG PARTICULATE 421 FUSAR 5000 CPM CPM'0,000 2B PV PIG PARTICULATE . 431 FUSAR 5000 CPM 2FHB PARTICULATE 411 FUSAR 8 TS'000 CPM CPM'0,000

- 5000 CPM CPM'0,000 SGBDB PARTICULATE 45M FUSAR CPM't.

Lucie Plant ODCM Controls

Page 28 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 3.3-14 continued RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS CHANNEL BASIS ALERT HIGH ODCM Related Iodine Channels ID DOCUMENT SETPOINT'000 SETPOINT'0,000 1PV IODINE 01-03 FUSAR CPM CPM'0,000 1FHB IODINE 04-03 FUSAR 5000 CPM CPM'0,000 2A PV PIG IODINE 422 FUSAR 5000 CPM CPM'0,000 2B PV PIG IODINE 432 FUSAR 5000 CPM CPM'0,000 2FHB IODINE 412 FUSAR 5000 CPM 45-5 CPM'0,000 SGBDB IODINE FUSAR 5000 CPM CPM'DCM CHANNEL BASIS ALERT HIGH Related Liquid Channels ID DOCUMENT SETPOINT SETPOINT'.E-04 1A S/G BLOWDOWN C-200 2 x Bkg.

uCi/ml'.E-04 1B S/G BLOWDOWN 45 C-200 2 x Bkg.

uCi/ml'.E-04 2A S/G BLOWDOWN 121 C-200 2x Bkg. uCi/ml 2B S/G BLOWDOWN 122 C-200 2 x Bkg. 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 Modes in CHANNEL which CHANNEL SOURCE CHANNEL FUNCTIONAL surveillance INSTRUMENT CHECK CHECK CALIBRATION TEST required

1. Waste Gas Holdup System a) Noble Gas Activity Monitor - Providing Alarm and p R (3) Q (~)

Automatic Termination of Release

2. Condenser Evacuation System a) Noble Gas Activity R (3) Q (2)

D Monitor

3. Plant Vent System a) Noble Gas Activity R (3) Q (2)

D Monitor b) Iodine Sampler W N.A. N.A.

c) Particulate Sampler W N.A. N.A. N.A.

d) Flow Rate Monitor D N.A. Q e) Sampler Flow Rate N.A.

D N.A. R Monitor

4. Fuel Storage Area Ventilation System a) Noble Gas Activity R (3) Q (2)

D Monitor b) Iodine Sampler W N.A N.A.

c) Particulate Sampler W N.A. N.A. N.A.

d) Flow Rate Monitor D N.A. R Q e) Sampler Flow Rate N.A.

D N.A. R Monitor St. Lucie Plant ODCM Controls

0 Page 30 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 4.3-9 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Modes in CHANNEL which CHANNEL SOURCE CHANNEL FUNCTIONAL surveillance INSTRUMENT CHECK CHECK CALIBRATION TEST required

5. Laundry Area Ventilation System a) Noble Gas Activity R (3) Q (2)

D Monitor b) Iodine Sampler W N.A. N.A.

c) Particulate Sampler W N.A N.A.

d) Flow Rate Monitor Q e) Sampler Flow Rate N.A.

N.A.

Monitor

6. Steam Generator Blowdown Building Vent a) Noble Gas Activity R (3) Q (2)

Monitor b) Iodine Sampler W N.A. N.A.

c) Particulate Sampler W N.A. N.A. N.A.

d) Flow Rate Monitor Q e) Sampler Flow Rate N.A.

N.A.

Monitor 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 FUNCTIONALTEST 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 3/4.11 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 CALCULATIONMANUAL ODCM TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Release Sampling Type of Activity Detection Analysis Type Frequency Analysis LLD (1) (pCi/ml)

Frequency A. Batch Waste P P.G.E. (3) 5.E-07 Each Batch Release Each Batch l-131 1.E-06 Tanks (2) Dissolved and P Entrained 1.E-05 M

One Batch/M Gases (Gamma Emitters)

P M H-3 1.E-05 Each Batch Composite (4) Gross Alpha 1.E-07 P Q Sr-89, Sr-90 5.E-08 Each Batch Composite (4) Fe-55 1.E-06 B. Continuous 4/M P.G.E. (3) 5.E-07 Releases (5, Daily 1.E-06 Composite l-131

6) Dissolved and Daily 4/M Entrained 1.E-05 Grab Sample Composite Gases (Gamma Emitters)

M H-3 1.E-05 Daily 1.E-07 Composite Gross Alpha Q Sr-89, Sr-90 5.E-08 Daily Composite 1.E-06 Fe-55 C. Settling Basin W P.G.E. (3) 5.E-07 W

(7) Grab Sample I-131 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),

the counting efficiency (counts per disintegration),

V the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL ODCM TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING 8 ANALYSIS PROGRAM Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type Frequency Analysis Analysis Detection Frequency (LLD) (1)

(pCi/cc)

Waste Gas P P Noble Gas 1.E-04 Storage Tank Each Tank Each Tank P.G.E. (2)

Grab Sample

2. Containment P P Noble Gas 1.E-04 Purge Each Purge (6) Each Purge (6) P.G.E. (2)

Grab Sample (7) H-3 1.E-06

3. Vents: 4/M 4/M (7) Noble Gas 1.E-04

a. Plant Grab Sample P.G.E. (2)

b. Fuel Bldg (5)

c. Laundry H-3 1.E-06

d. S/G Blowdown Bldg.

4. All Release Continuous (3) 4/M I-131 1.E-12 Types as Charcoal listed in 3. Sample (4) above 4/M P.G.E. 1.E-11 Particulate Sample (4)

M Gross Alpha 1.E-11 Composite Particulate Sample Q Sr-89, Sr-90 1.E-11 Composite Particulate Sample Noble Gas Noble Gases 1.E-06 Monitor Gross Beta or Gamma 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 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),

E the counting efficiency (counts per disintegration),

V the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per 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 CALCULATIONMANUAL 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 THERMALPOWER 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 EQUIVALENTI-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 EQUIVALENT1-131 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 CALCULATIONMANUAL 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 VENTILATIONEXHAUST 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 CALCULATIONMANUAL 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 FUNCTIONALTEST 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) With a Waste Gas Compressor, charge the Gas Decay Tank to at least 150 psi ~

3) Following appropriate holdup decay time, sample and release the Gas Decay Tank with an OPERABLE Waste Gas Holdup System Noble Gas ActivityMonitor (per TABLE 3.3-13).

4) If discrepancies exist, repairs shall be made and the WASTE GAS HOLDUP SYSTEM Administrative FUNCTIONALTEST 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 CALCUIATIONMANUAL 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 CALCULATIONMANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.5 MAJOR CHANGES TO RADIOACTIVELIQUID 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*

ADMINISTRATIVECONTROLS 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 ADMINISTRATIVECONTROLS 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 CALCULATIONMANUAL ODCM RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION Continued ADMINISTRATIVECONTROLS 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 ENVIRONMENTALMONITORING 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 ENVIRONMENTALMONITORING 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 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM'i NUMBER OF EXPOSURE REPRESENTATIVE PATHWAY SAMPLES AND SAMPLING AND TYPE AND and/or SAMPLE COLLECTION FREQUENCY " OF SAMPLE LOCATIONS"" FREQUENCY" ANALYSIS

1. Direct Radiation" 27 Monitoring Continuous Gamma exposure rate-Locations monitoring with quarterly sample collection quarterly "

2. Airborne Continuous sampler Radioiodine filter:

Radioiodine and 5 Locations operation with I-131 analysis weekly Particulates sample collection Particulate Filter:

weekly or more Gross beta radioactivity frequently if analysis >&4 hours required by dust following a filter loading change" Gamma of composite "

isotopic"'nalysis (by location) quarterly

3. Waterborne a) Surface"')

1 Location ' Weekly Gamma isotopic"'

tritium analyses weekly Location"' Monthly Gamma isotopic"'

tritium analyses monthly Sediment from Locations Semiannually Gamma isotopic"'nalyses shoreline semiannually

4. Ingestion a) Fish and Invertebrates

1) Crustacea 2 Locations Semiannually Gamma isotopic"'nalyses semiannually

2) Fish 2 Locations Semiannually Gamma isotopic semiannually "'nalyses b) Food Products

1) Broad leaf 3 Locations" Monthly when Gamma isotopic"'nd vegetation available 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 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.

Gamma isotopic analysis means the identification and quantification of gamma-emitting

~

h. ~

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 RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTALSAMPLES REPORTING LEVELS AIRBORNE FOOD WATER PARTICULATE FISH MILK ANALYSIS PRODUCTS pCi/I OR GASES pCi/kg, wet pCi/I pCi/kg, wet H-3 30,000 Mn-54 1,000, pCI/m'.9 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-400 Nb-95"'-131 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140"* 200 300 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 ENVIRONMENTALSAMPLE ANALYSIS"

~

LOWER LIMITOF DETECTION LLD '

AIRBORNE FOOD WATER PARTICULATE FISH MILK SEDIMENT ANALYSIS PRODUCTS pCi/I OR GASES pCi/kg, wet pci/I pCi/kg, dry pCi/kg, wet pCI/m' Gross Beta 0.01 H-3 3000 Mn-54 15 130 Fe-59 30 260 Co-58, 130 Co-60 Zn-65 30 260 Zr-95, Nb-95~'~ 15 I-131 1** 0.07 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140, 15 La-140~'> 15 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL ODCM RADIOLOGICAL ENVIRONMENTALMONITORING 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 CALCULATIONMANUAL ODCM RADIOLOGICAL ENVIRONMENTALMONITORING 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 CALCULATIONMANUAL ODCM RADIOLOGICAL ENVIRONMENTALMONITORING 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 ENVIRONMENTALMONITORING 3/4.12.4 ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT AREOR ADMINISTRATIVECONTROLS 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OF FSITE DOSE CALCULATION MANUAL ODCM INSTRUMENTATION 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 OPERABILITYand 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 OPERABILITYand 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM 3/4.11 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 flexibilityand 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 3/4.11 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 OPERABILITYof 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 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 CALCULATIONMANUAL 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 flexibilityand 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-'I33 TRITIUMAND RA5lOACTIVEMATERIAL 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 CALCULATIONMANUAL ODCM RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE - NOBLE GASES Continued 3/4.11.2.3 DOSE - IODINE-131 IODINE-133 TRITIUMAND RADIOACTIVEMATERIAL 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 CALCULATIONMANUAL 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 DOSE This 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM RADIOACTIVE EFFLUENTS 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 CALCULATIONMANUAL ODCM 3/4.12 RADIOLOGICALENVIRONMENTALMONITORING 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 ENVIRONMENTALMONITORING 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 Dose from Beta Radiation CC or cc Cubic centimeter Ci Curies - a unit of radioactivity see pCi C, Activity or concentration of a nuclide in the release source. Units 'f pCi, pCi/cc or pCi/ml CFR Code of Federal Regulations Control(s) 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 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 Dose Pathway 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 Dose Rate The dose received per unit time (D/Q) 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).

ECL 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 CALCULATIONMANUAL ODCM METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION (continued)

A gamma photon - The dose from Gammas in air, etc.

Ground Plane 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 Hydrogen-3 or Tritium, a weak Beta emitter I88DP Radioiodines and particulates with half-lives greater than 8 days Cubic Meters Square Meters m'uclide 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.

Organ 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.

pCi 1 pico-Curie = 1.E-12 Curies.

(Q Dot), (Q Dot), - Denotes a release rate in pCI/sec for nuclide (i).

Q, Denotes pCi of nuclide (i) released over a specified time interval.

Radioiodine s 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 CALCULATIONMANUAL 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.

Release Source(s) - A subsystem, tank or vent where radioactive material can be released independently of other radioactive release points.

I TS 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 CALCULATIONMANUAL 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:

F the 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 AWST ¹2 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 225 ST. 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 CALCULATIONMANUAL 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:

n R 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 F is 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 F less 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 CALCULATIONMANUAL 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 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 1.3 (continued)

TABLE 1.3 NUCLIDE SYMBOL 1978 UNDILUTED pCI/ml'.43 M, (no units) l-131 E-5 3.66 EA l-132 2.23 E-7 1.84 E-8 I-133 3.17 EW 3.74 E-6 I-135 1.31 E-6 ~ 3.61 E-7 Na-24 1.72 E-7 2.84 E-8 Cr-51 2.51 E-5 4.15 E-7 Mn-54 5.64 E-6 1.55 E-6 Mn-56 1.11 E-9 1.31 E-'10 Co-57 3.69 E-7 5.08 E-8 Co-58 1.51 EA 6.24 E-5 Fe-59 2.92 E-6 2.41 E-6 Co-60 3.66 E-5 1.01 EA Zn-65 4.55 E-7 7.52 E-7 Ni-65 8.23 E-7 6.8 E-8 Ag-110 1.96 E-6 2.70 E-6 Sn-113 5.75 E-7 1.58 E-7 Sb-122 2.15 E-6 1.78 E-6 Sb-124 8.40 E-6 9.92 E-6 W-1 87 3.51 E-6 9.67 E-7 Np-239 1.57 E-7 6.49 E-8 Br-82 3.64 E-7 7.52 E-8 Zr-95 2.82 E-5 1.17 E-5 Zr-97 4.05 E-6 3.72 E-6 Mo-99 3.24 E-6 1.34 E-6 Ru-103 3.84 E-8 1.06 E-8 Sb-125 2.26 E-6 6.23 E-7 Cs-134 2.14 E-5 E-7

~7 EA E-6 Cs-136 7.82 1.08 Cs-137 4.85 E-5 4.01 E-4 Ba-140 6A4 E-7 6.65 E-7 Ce-141 3.04 E-8 8.38 E-9 Ce-144 2.37 E-6 6.53 E-6 4.01 EA M~~= 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~ ~rot" 4.01 E-4 1.18 E-3 0.34 pCi/ml = ECL Limit Mrot 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 CALCULATIONMANUAL 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 Releases Discussion - 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 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 e 1.4 (continued)

OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION 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, dose commitment in mrem received by organ T of age group (to T 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 the number of hours that the release occurs.

Q,, 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 the total dose commitment to organ T due to all releases during the T desired time interval (mrem)

Page 91 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL 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 Dose Factor Table Infant N/4-Child L-4 Teen L-3 Adult L-2

Page 92 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM METHODOLOGY SECTION 1.4 (continued)

1. (continued)

TABLE 1A FISH AND SHELLFISH PATHWAY TIME/DATE START: /~ TIME/DATE STOP: / / HOURS TOTAL DILUTION VOLUME: mls AGE GROUP: ORGAN: DOSE FACTOR TABLE ¹:

NUCLIDE (i) C,. (p,Ci) Arr DOSE (i) mrem TOTAL DOSE ~ = mrem E. Solve for Dose (i)

(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 Effluents Discussion - 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 CALCULATIONMANUAL 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 225 ST. 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 (Example)

Percent ODCM Release Point Allotment Unit 1 Plant Vent 40 Unit 1 Fuel Bldg. Vent 5 ECCS 1A 1 ECCS 1B 1 Unit 2 Plant Vent 40 Unit 2 Fuel Bldg. Vent 5 ECCS 2A 1 ECCS 2B 1 Blowdown Bldg. Vent + 5 Total Percent Allocated= 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 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 Liver Thyroid Kidney Lung Gl-LLI W.Body mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr 7.4E+00 7.9E+00 O.0E+00 4.2E-01 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 CALCULATIONMANUAL 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:

min

)ft' ft'0.

2.8317 X 10'cc X cc/sec volume release rate min sec 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, Table G-2.

v~ for nuclide (i) from E. Solve for DR~,.

mrem-m' sec X PCI OR, = K(X/Q) (Q DOT), =

p,Ci-yr m'ec DR~ = mrem total body dose from nuclide (i) for yr the specified release source

Page 109 of 225 ST. 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:

n R

DRl&BpP ~ . (X/Q)p (Q DOT)

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

0 s 'h

~

I

Page 111 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL 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:

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 I&8DPT particulates DR~T Dose Rate in mrem/yr to organ T from Tritium DR~ 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 RI The dose factor for nuclide (i) for organ T for the pathway specified (units vary by pathway)

P, 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 CALCULATIONMANUAL 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' ft'0 2.8317 X 10'CC X min 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.

(nuclide I'i] assay) WCi ( Value 2.3. 1 . B) cc (Q DQ7) <

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, mrem-m X sec X Ij I

PR R (X/Q) (Q DQ 7)

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 + + OR for 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.

C.

min ft' ft'0 2.8317 X 10'cc X min sec.

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.

(nuclide fi1 assay) Ij.ci X (Value 2.3.2.B) cc (Q QQ7)

CC sec (Q DOT), = p.CI/sec for nuclide (i)

D. Obtain the P, value from Table G-3 E. Solve for DR, mrem-m' sec X OR, = p. (0/Q) (Q 0073, 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 CALCULATIONMANUAL 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 + + DR for 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.

2.8317 X 10'cc X mi min ft' ft 60 sec.

= cc/s~

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 CALCULATIONMANUAL 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 ~

DR~ = RT (D/Q) (Q DOT),

mrem-m' sec X pCi-yr m X 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- -Milk pathway is:

DRgrms -MilkT = DR, + DR2 + + DR for 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 CALCULATIONMANUAL 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 sector at miles with an Infant at the exclusion area in the sector 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.)

B. Enter the anticipated release rate in ft'/min of the release source and convert it to cc/sec.

min a'X '1'"X 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.

(H 3) p,CI' (2 3 4 B VBIU8) CC (Q ppq CC sec (Q DOT)., = pCi/sec activity release rate D. Obtain the Tritium dose factor (R,) for Infant organ T from:

PATH TABLE ¹ Inhalation G-5 Grass-Cow/Goat-Milk G-6(7)

Page 118 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL 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- -Milk) from 2.3.4.D 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 DOSE RATE STEP 0 REF.

Inhalation (I&8DP) 2.3.1.6 Ground Plane'I&8DP) (Whole Body only) 2.3.2.G Gr- Milk (l&8DP) 2.3.3.G Inhalation (H-3) 2.3.4.E Gr- -Milk (H-3) 2.3.4.F DR~ (sum of above)

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:

D-air =

n Z 3.17 X 10 I

't (XIQ) Q~

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.

J M, the gamma air dose factor for radioactive noble 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. (e.g., month, quarter or year)

Page 121 of 225 ST. 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 CALCULATIONMANUAL 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.

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, 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:

DI 3.17 X 10'r X N, mrad-m'X/Q) sec X

Q, p.Ci 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 CALCULATIONMANUAL 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 17 X 10 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 CALCULATIONMANUAL 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 Dose in mrem to the organ T of a specified age group from Tritium DT 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.

A mathematical symbol to indicate that the total dose D, to Z organ T is the sum of each of the pathway doses of I88DP and H-3 from gaseous particulate effluents.

3.17 X 10 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, The number of micro-Curies of nuclide (i) released (or projected) during the dose calculation exposure period.

QH-3 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 Inhalation Dose Factor Table Number Infant G-5 Child G-S Teen G-13 Adult 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 Cow Milk Dose Goat Milk Dose Factor Table Number Factor Table Number Infant G-6 G-7 Child G-9 G-10 Teen G-14 G-15 Adult G-19 G-20 If 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 225 ST. 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 Meat Dose Factor Table No.

Infant N/A

Child G-11 Teen G-16 Adult 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)

't

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 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 CALCULATIONMANUAL 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 Vegetation Dose Factor Table No.

Infant N/A Child G-12 Teen G-17 Adult 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 CALCULATIONMANUAL 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:

MILK AGE INHALATION COW GOAT Infant G-5 G-6 G-7 Child G-8 G-9 G-10 Teen , G-13 G-14 G-15 Adult G-18 G-1 9 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 BODY PATHWAY DOSE Reference to Remark STEP No.

Inhalation (l&8DP) 2.6.1.F Inhalation (Tritium) 2.6.6.E Ground Plane (!&8DP) 2.6.2.F Grass- -Milk (l&8DP) 2.6.3.F Grass- -Milk (Tritium) 2.6.6.E Grass- -Meat (l&8DP) 2.6.4.G N/A for INFANT Grass- -Meat (Tritium) 2.6,6.E N/A for INFANT Vegetable Garden (l&8DP) 2.6.5.G N/A for INFANT Vegetable Garden (Tritium) 2.6.6.E N/A for INFANT Dose, = (sum of above)

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 225 ST. 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:;

LIQUID GASEOUS Error Topic Avg.% Max.% Avg,% Max.%

Release Point Mixing 2 5 NA NA Sampling 5 2 5 Sample Preparation 1 5 1 5 Sample Analysis 3 10 3 10 Release Volume 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 CALCULATIONMANUAL ODCM METHODOLOGY SECTION 4.0 (continued)

4. (continued)

TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS LIQUID METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS ANALYSIS SOURCE EACH BATCH PRINCIPAL GAMMA EMITTERS p.h.a.

MONITOR TRITIUM L.S.

TANK 'GROSS ALPHA G.F.P.

MONTHLYCOMPOSITE RELEASES QUARTERLY COMPOSITE Sr-89, Sr-90, Fe-55 C.S.

FOUR PER MONTH PRINCIPAL GAMMA EMITTERS p.h.a.

STEAM AND DISSOLVED GASES GENERATOR TRITIUM L.S.

B LOWDOWN G.F.P.

MONTHLY COMPOSITE GROSS ALPHA RELEASES QUARTERLY COMPOSITE Sr-89, Sr-90, Fe-55 C.S.

TABLE NOTATION:

p.h.a. gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified.

L.S. Liquid Scintillation counting C.S. Chemical Separation G.F.P. 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 RADIOACTIVEGASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS ANALYSIS SOURCE Waste Gas Each Tank Principal Gamma Emitters G, p.h.a.

Decay Tank Releases Containment Each Purge Principal Gamma Emitters G, p.h.a.

Purge H-3 L.S.

Releases Four per Month Principal Gamma Emitters (G, C, P) - p.h.a.

H-3 L.S.

Monthly Composite Gross P-G. F. P.

Plant Vent (Particulates) Alpha Quarterly Composite Sr-90 C.S.

(Particulates) Sr-89 Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample L.S. Liquid Scintillation Counting C.S. Chemical Separation p.h.a. Gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified.

G.F.P. 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: minutes

3. Maximum time period for a batch release: minutes

4. Average time period for a batch release: minute's

5. Minimum time period for a batch release: 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: minutes

3. Maximum time period for a batch releas'e: minutes

4. Average time period for batch releases: minutes

5. Minimum time period for a batch release: 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 CALCULATIONMANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8. LIGHT COMPANY

¹

~~

ST. LUCIE UNIT ANNUAL REPORT -

TABLE 3

~~ THROUGH 3'IQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER ¹ QUARTER ¹ A. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, Alpha) Ci

2. Average Diluted Concentration During Period p,CI/ml B. Tritium Total Release Ci E

2. Average Diluted Concentration During Period p.CI/ml C. Dissolved and Entrained Gases

1. Total Release Ci E

2. Average Diluted Concentration During Period p,CI/ml D. Gross Alpha Radioactivity

1. Total Release Ci

Page 145 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM METHODOLOGY SECTION TABLE 3.3: LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES (continued)

UNIT QUARTER ¹ QUARTER ¹ E. Volume of Waste Released (Prior to Dilution) LITERS F.

Used During Period'ITERS Volume of Dilution Water 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 UNIT ¹ ANNUAL REPORT - ~~ THROUGH TABLE 3.4: LIQUID EFFLUENTS (EXAMPLE FORMAT)

~~

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED'-131 UNIT QUARTER ¹ QUARTER ¹ QUARTER ¹ QUARTER ¹ CI I-133 .'I I-135 CI NA-24 CI CR-51 CI MN-54 CI CO-57 CI CO-58 CI FE-59 CI CO-60 CI ZN-65 CI Nl-65 CI AG-110 CI SN-1 13 CI SB-122 CI SB-124 CI W-1 87 CI NP-239 CI E ZR-95 CI MO-99 CI E RU-103 CI CS-134 CI CS-136 CI CS-137 CI BA-140 CI CE-141 CI BR-82 CI ZR-97 CI SB-125 CI

All that were detected should be added to the partial list of the example nuclides format..

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

(continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER ¹ QUARTER ¹ QUARTER ¹ QUARTER ¹ CE-144 CI SR-89 CI SR-90 CI UNIDENTIFIED CI TOTAL FOR PERIOD (ABOVE) CI AR<1 CI KR-85 CI XE-131M CI XE-133 CI XE-133M CI XE-135 CI

Page 148 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM METHODOLOGY SECTION FLORIDA POWER K LIGHT COMPANY ST. LUCIE UNIT II TABLE 3.5 LIQUID EFFLUENTS - DOSE SUMMATION Age Group: Location:

Exposure Interval: From Through CALENDAR YEAR DOSE Fish 8 Shellfish Pathway to Organ -'(mrem)

BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY

Page 149 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM METHODOLOGY SECTION FLORIDA POWER 8c LIGHT COMPANY

¹

~~

ST. LUCIE UNIT ANNUAL REPORT - ~~ THROUGH TABLE 3.6: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER ¹ QUARTER ¹ A. Fission and Activation Gases

1. Total Release Ci

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 Ci D: Tritium

1. Total Release 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 CALCULATIONMANUAL 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 QUARTER ¹ QUARTER ¹ QUARTER ¹ QUARTER ¹

1. Fission Gases AR-41 CI KR-85 CI KR-85M CI KR-87 CI KR-88 CI XE-131M Cl XE-133 CI XE-133M CI XE-135 CI XE-135M CI XE-138 CI UNIDENTIFIED CI TOTAL FOR PERIOD (ABOVE) CI

2. Iodines I-131 CI I-133 CI I-135 CI TOTAL FOR PERIOD (ABOVE) CI

3. Particulates CO-58 CI SR-89 CI SR-90 CI

All nuclides that were detected should be added to the partial list of the example format.

Page 151 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER L LIGHT COMPANY ST. LUCIE UNIT ¹ TABLE 3.8 GASEOUS EFFLUENTS DOSE SUMMATION - CALENDAR YEAR AGE GROUP: INFANT EXPOSURE INTERVAL: FROM THROUGH BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY PATHWAY (mrem (mrem) (mrem)

(mrem) (mrem) (mrem) (mrem)

Ground Plane (A)

Grass- -Milk(B)

Inhalation (A)

TOTAL (A) SECTOR: RANGE: miles (B) COW/ GOAT SECTOR: RANGE: miles NOBLE GASES CALENDAR YEAR (mrad)

Gamma Air Dose Beta Air Dose Sector: 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 CALCULATIONMANUAL 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 ECL (pCi/ml) Nuclide ECL (p,Ci/ml) Nuclide ECL (pCi/ml)

H-3 1 E-3 Y-90 7 E-6 Te-129 4 E-4 Na-24 5 E-5 Y-91m 2 E-3 Te-131m 8 E-6 P-32 9 E-6 Y-91 8 E-6 Te-131 8 E-5 Cr-51 5 E-4 Y-92 4 E-5 Te-132 9 E-6 Mn-54 3 E-5 Y-93 2 E-5 I-130 2 E-5 Mn-56 7 E-5 Zr-95 2 E-5 l-131 1 E-6 Fe-55 1 E-4 Zr-97 9 E-6 l-132 1 E-4 Fe-59 1 E-5 Nb-95 3 E-5 I-133 7 E-6 Co-57 6 E-5 Nb-97 3 E-4 I-134 4 E-4 Co-58 2 E-5 Mo-99 2 E-5 l-135 3 E-5 Co-60 3 E-6 Tc-99m 1 E-3 Cs-134 9 E-7 Ni-65 1 E-4 Tc-101 2 E-3 Cs-136 6 E-6 Cu-64 2 EA Ru-103 3 E-5 Cs-137 1 E-6 Zn-65 5 E-6 Ru-105 7 E-5 Cs-138 4 E-4 Zn-69 8 E-4 Ru-106 3 E-6 Ba-139 2 E-4 Br-82 4 E-5 Ag-110 6 E-6 Ba-140 8 E-6 Br-83 9 E-4 Sn-113 3 E-5 Ba-141 Br-84 4 E-4 In-113m 7 E-4 Ba-142 7 EA Rb-86 7 E-6 Sb-122 1 E-5 L~O 9 E-6 Rb-88 4 E-4 SI3-124 7 E-6 La-142 Rb-89 9 E-4 Sb-125 3 E-5 Ce-141 3 E-5 Sr-89 8 E-6 Te-125m 2 E-5 Ce-143 2 E-5 Sr-90 5 E-7 Te-127m 9 E-6 Ce-144 3 E-6 Sr-91 2 E-5 Te-127 1 E-4 Pr-144 6 E-4 Sr-92 4 E-5 Te-129m 7 E-6 W-187 3 E-5 Np-239 2 E-5

Page 154 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-2 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)

WHOLE NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI BODY H-3 0. 3.60E-01 3.60E-01 3.60E-01 3.60E-01 3.60E-01 3.60E-01 NA-24 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 P-32 1.67E+07 1.05E+06 0. 0. 0. 1.88E+06 6.47E+05 CR-51 0. 0. 3.34E+00 1.23E+00 7A2E+00 1.41E+03 5.59E+00 MN-54 0. 7.07E+03 0. 2.10E+03 0. 2.17E+04 1.35E+03 MN-56 0. 1.78E+02 0. 2.26E+02 0. 5.68E+03 3.17E+01 FE-55 1.15E+05 5.19E+05 0. 0. 6.01E+05 2.03E+05 1.36E+05 FE-59 8.08E+04 1.92E+05 0. 0. 5.32E+04 6.33E+05 7.29E+04 CO-57 0. 1.42E+02 0. 0. 0. 3.60E+03 2.36E+02 CO-58 0. 6.05E+02 0. 0. 0. 1.22E+04 1.35E+03 CO-60 0. 1.74E+03 0. 0. 3.26E+04 3.83E+03 NI-65 2.02E+02 2.63E+01 0. 0. 6.65E+02 1.20E+01 CU-84 0. 2.15 +02 0. 5.41E+02 0. 1.83E+04 1.01E+02 ZN-65 1.62E+05 5.13E+05 0. 3.43E+05 3.23E+05 2.32E+05 ZN-69 3.43E+02 6.60E+02 0. 4.27E+02 0. 9.87E+01 4.57E+01 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 155 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-2 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

WHOLE NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI BODY BR-82 0. 0. 0. 4.68E+00 4.08E+00 BR-83 0. 0. 0. 0. 0. 1.05E-01 7.26E-02 BR-84 0. 0. 0. 7.38E-07 9A2E-02 BR-85 0. 0. 0. 0. 0. 0. 3.86E-03 RB-86 0. 6.25E+02 0. 0. 1.23E+02 2.91E+02 RB-88 0. 1.79E+00 0. 0. 0. 0. 9.50E-01 RB-89 0. 1.19E+00 0. 0. 0. 0. 8.38E-01 SR-89 5.01E+03 0. 0. 0. 8.01E+02 1.44E+02 SR-90 1.23E+05 0. 0. 0. 0. 1.65E+03 3.02E+04 SR-91 9.43E+01 0. 0. 0. 0. 4.75E+02 4.15E+00 SR-92 3.50E+01 0. 0. 0. 6.91E+02 1.51E+00 Y-90 6.07E+00 0. 0. 0. 6.43E+04 1.63E-01 Y-95M 5.74E-02 0. 0. 0. 0. 1.68E-01 2.23E-03 Y-91 8.89E+01 0. 0. 0. 4.89E+04 2.38E+00 Y-92 5.34E-01 0. 0. 0. 0. 9.33E+03 1.56E-02 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 156 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-2 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY Y-93 1.69E+00 0. 0. 0. 0. 5.36E+04 4.67E-02 ZR-95 1.60E+01 5.13E+00 0. 8.09E+00 0. 1.59E+04 3.47E+00 ZR-97 8.82E-01 1.78E-01 0. 2.69E-01 5.51E+04 8.19E-02 NB-95 4.48E+02 2.49E+02 0. 2.47E+02 1.51E+06 9.79E+01 NB-97 3.76E+00 9.50E-01 0. 1.11E+00 0. 3.51E+03 3.47E-01 MO-99 0. 1.28E+02 0. 2.90E+02 0. 2.97E+02 2.43E+01 TC-99M 1.30E-02 3.67E-02 0. 5.57E-01 1.80E-02 2.17E+01 4.67E-01 TC-101 1.33E-02 1.93E-02 0. 3.47E-01 9.82E-03 0. 1.89E-01 RU-103 1.07E+02 0. 0. 4.09E+02 0. 1.25E+04 4.61E+01 RU-105 8.90E+00 0. 0. 1.15E+02 0. 5A4E+03 3.51E+00 RU-106 1.59E+03 0. 0. 3.08E+03 0. 1.03E+05 2.01E+02 AG-110 1.57E+03 'I.45E+03 0. 2.85E+03 0. 5.92E+05 8.62E+02 SB-124 2.78E+02 5.23 +00 6.71E-01 2.15E+02 7.85E+03 1.10E+02 SB-125 2.20E+02 2.37 00 1.96E-01 0. 2.30E+04 1.95E+03 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

Page 157 of 225 ST, LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-2 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES

. PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY TE-127M 5.50E+02 1.92E+02 1.40E+02 2.23E+03 1.84E+03 6.70E+01 TE-127 8.92E+00 3.20E+00 6.61E+00 3.63E+01 0. 7.04E+02 1.93E+00 TE-129M 9.32E+02 3.49E+02 3.20E+02 3.89E+03 0. 4.69E+03 1.48E+02 TE-129 2.55E+00 9.65E-01 1.95E+00 1.07E+01 0. 1.92E+00 6.21E-01 TE-131M 1.41E+02 6.87E+01 1.09E+02 6.95E+02 6.81E+03 5.72E+01 TE-131 1.60E+00 6.68E-01 1.31E+00 7.00E+00 2.39E-01 5.04E-01 TE-132 2.05E+03 1.33E+02 1.46E+02 1.28E+03 0. 6.25E+03 1.24E+02 I-130 3.98E+01 1.18E+02 1.50E+04 1.83E+02 0. 1.01E+02 4.63E+01 1-131 2.18E+02 3.13E+02 1.02E+05 5.36E+02 0. 8.24E+01 1.79E+02 l-132 1.07E+01 2.85E+01 3.76E+03 4.55E+01 0. 5.36E+00 1.01E+01 I-133 7.51E+01 1.30E+Og ) 2.51E+04 2.27E+02 0. 1.15E+02 3.98E+01 I-134 5.57E+00 1.51E+01 1.96E+03 2.41E+01 0. 1.32E-02 5.41E+00 I-135 2.33E+01 6.14 +01 8.03E+03 9.77E+01 0. 6.88E+01 2.25E+01 CS-134 6.85E+03 1.63 04 0. 5.29E+03 1.75E+03 2.85E+02 1.33E+04 CS-136 7.17E+02 2.83E+03 0. 1.58E+03 2.16E+02 3.22E+02 2.04E+03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 158 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-2 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY CS-137 8.79E+03 1.20E+04 0. 4.09E+03 1.36E+03 2.31E+02 7.88E+03 CS-138 6.08E+00 1.20E+01 0. 8.84E+00 8.73E-01 5.12E-05 5.96E+00 BA-139 7.87E+00 5.61E-03 0. 5.24E-03 3.18E-03 1.39E+01 2.30E-01 BA-140 1.65E+03 2.07E+00 0. 7.04E-01 1.18E+00 3.39E+03 1.09E+02 BA-141 0. 2.89E-03 0. 2.68E-03 1.64E-03 1.80E-09 1.29E-01 BA-142 1.73E+00 1.78E-03 0. 1.50E-03 1.01E-03 0. 1.09E-01 LA-140 1.58E+00 7.95E-01 0. 5.83E+04 2.11E-01 LA-142 8.07E-02 3.67E-02 0. 0. 0. 2.68E+02 9.15E-03 CE-141 3.43E+00 2.32E+00 1.08E+00 0. 8.87E+03 2.63E-01 CE-143 6.05E-01 4.47E+02 0. 1.97E-01 0. 1.67E+04 4.95E-02 CE-144 1.79E+02 7.48E+01 0. 4.43E+01 0. 6.05E+04 9.60E+00 PR-144 1.91E-02 7.88E-03 0. 4.45E-03 0. 2.73E-09 9.65E-04 W-187 9.17E+00 7.68 +00 0. 0. 0. 2.51E+03 2.69E+00 NP-239 3.56E-02 3.50 -03 0. 1.08E-02 0. 7.12E+02 1.92E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 159 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-3 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 2.17E-01 2.17E-01 2.74E-01 2.17E-01 2.17E-01 2.17E-01 NA-24 4.63E-01 4.63E-01 4.63E-01 4.63E-01 4.63E-01 4.63E-01 4.63E-01 P--32 1.27E+07 7.98E+05 0. 0. 0. 1.43E+06 4.93E+05 CR-51 0. 0. 2.54E+00 9.38E-01 5.64E+00 1.07E+03 4.25E+00 MN-54 0. 5.38E+03 0. 1.60E+03 0. 1.65E+04 1.03E+03 MN-56 0. 1.36E+02 0. 1.72E+02 0. 4.32E+03 2.42E+01 FE-55 8.78E+04 3.95E+05 0. 0. 4.57E+05 1.54E+05 1.04E+05 FE-59 6.14E+04 1.46E+05 0. 0. 4.05E+04 4.81E+05 5.55E+04 CO-57 0. 1.08E+02 0. 0. 0. 2.74E+03 1.79E+02 CO-58 0. 6.12E+02 0. 0. 0. 8.26E+03 1.39E+03 CO-60 0. 1.70E+03 0. 0. 0. 2.04E+04 3.88E+03 NI-65 1.54E+02 2.00E+01 0. 0. 5.07E+02 9.11E+00 CU-64 0. 1.64 +02 4.12E+02 0. 1.39E+04 7.69E+01 ZN-65 1.23E+05 3.90 05 2.61E+05 0. 2.46E+05 1.77E+05 ZN-69 2.61E+02 5.02E+02 3.24E+02 0. 7.50E+01 3.47E+01 BR-82 0. 0. 0. 0. 3.55E+00 3.10E+00 BR-83 0. 0. 0. 0. 0. 7.95E-02 5.52E-02 BR-84 0. 0. 5.61E-07 7.16E-02 BR-85 0. 0. 0. 0. 0. 0. 2.94E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 160 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-3 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY RB-86 0. 4.76E+02 0. 0. 9.37E+01 2.22E+02 RB-88 0. 1.37E+00 0. 0. 7.23E-01 RB-89 0. 9.04E-01 0. 0. 0. 0. 6.38E-01 SR-89 5.67E+03 0. 0. 0. 6.15E+02 1.63E+02 SR-90 1,28E+05 0. 0. 0. 0. 2.71E+03 3.17E+04 SR-91 7.18E+01 0. 0. 0. 0. 3.61E+02 3.16E+00 SR-92 2.66E+01 0. 0. 0. 0. 5.25E+02 1.15E+00 Y--90 1.58E+01 0. 0. 0. 1.80E+04 5.23E+04 4.25E-01 Y-91M 4.36E-02 0. 0. 0. 0. 1.28E-01 1.69E-03 Y--91 9.40E+01 0. 0. 0. 3.61E+04 2.51E+00 Y--92 4.06E-01 0. 0. 0. 0. 7.10E+03 1.18E-02 Y--93 1.29E+00 p 0. 0. 4.08E+04 3.55E-02 ZR-95 1.49E+01 4.96 +00 0. 6.16E+00 0. 1.07E+04 3.46E+00 ZR-97 6.72E-01 1.36 01 0. 2.05E-01 0. 4.20E+04 6.24E-02 NB-95 3.97E+02 2.39E+02 0. 1.88E+02 0. 9.76E+05 1.35E+02 NB-97 2.87E+00 7.24E-01 8.45E-01 0. 2.67E+03 2.64E-01 MO-99 0. 9.74E+01 0. 2.21E+02 0. 2.26E+02 1.85+01 TC-99M 9.87E-03 2.79E-02 0. 4.24E-01 1.37E-02 1.65E+01 3.56E-01 TC-101 1.02E-02 1.47E-02 0. 2.64E-01 7.47E-03 0. 1.44E-01 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 161 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-3 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY RU-103 1.04E+02 0. 3.11E+02 0. 8.13E+03 4.66E+01 RU-105 6.77E+00 0. 0. 8.74E+O'I 0. 4.14E+03 2.67E+00 RU-106 1.76E+03 0. 0. 2.34E+03 0. 7.95E+04 2.21E+02 AG110 1.19E+03 1.10E+03 0. 2.17E+03 0. 4.51E+05 6.56E+02 SB-124 2.11E+02 3.99E+00 5.11E-01 0. 1.64E+02 5.98E+03 8.35E+01 SB-125 1.68E+02 1.81E+00 1.49E-01 0. 1.75E+04 1.48E+03 3.37E+01 TE 125M 2.36E+02 8A5E+O'I 6.66E+01 6.72E+02 6.60E+02 3.13E+01 TE 127M 4.18E+02 1.46E+02 1.07E+02 1.70E+03 0. 1.40E+03 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 3.79E+02 3.27E+02 2.96E+03 0. 3.58E+03 1.61E+02 TE-129 1.94E+00 7.34E-01 1A9E+00 8.14E+00 0. 1.46E+00 4.72E-01 TE 131M 1.07E+02 5.22E+01 8.26E+01 5.29E+02 0. 5.18E+03 4.35E+01 TE-131 1.21E+00 5.08 -01 9.99E-01 5.33E+00 0. 1.82E-01 3.83E-01 TE-132 2.19E+02 1.37 02 1A6E+02 9.74E+02 0. 4.93E+03 1.30E+02 I-130 3.03E+01 8.95E+01 1.14E+04 1.39E+02 0. 7.67E+01 3.52E+01 I-131 2.23E+02 3.14E+02 9.07E+04 4.08E+02 0. 5.95E+01 1.87E+02 I-132 8.11E+00 2.17E+01 2.86E+03 3.46E+01 0. 4.08E+00 7.71E+00 I-133 8.11E+01 1.37E+02 2.50E+04 1.73E+02 0. 9.99E+01 4.24E+01 1-134 4.24E+00 1.15E+01 1.49E+03 1.83E+01 0. 1.00E-02 4.12E+00 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 162 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE L-3 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY I-135 1.77E+01 4.68E+01 6.11E+03 7.43E+01 0. 5.23E+01 1.71E+01 CS-134 6.75E+03 1.63E+04 0. 4.03E+03 1.97E+03 1.88E+02 7.60E+03 CS-136 5.46E+02 2.16E+03 0. 1.20E+03 1.65E+02 2.45E+02 1.55E+03 CS-137 8.98E+03 1.21E+04 0. 3.11E+03 1.60E+03 1.61E+02 4.24E+03 CS-138 4.63E+00 9.15E+00 0. 6.73E+00 6.65E-01 3.90E-05 4.54E+00 BA-139 5.99E+00 4.27E-03 0. 3.99E-03 2.42E-03 1.06E+01 1.75E-01 BA-140 1.75E+03 2.15E+00 0. 5.35E-01 1.44E+00 2.55E+02 1.12E+02 BA-141 0. 2.20E-03 0. 2.04E-03 1.25E-03 1.37E-09 9.80E-02 BA-142 1.31E+00 1.35E-03 0. 1.14E-03 7.64E-04 0. 8.26E-02 LA-140 1.67E+00 8.25E-01 0. 0. 0. 4.55E+04 2.18E-01 LA-142 6.14E-02 2.79E-OP, 0. 0. 0. 2.04E+02 6.95E-03 CE-141 3.51E+00 2.36E+00 0. 8.19E-01 0. 6.38E+03 2.70E-01 CE-143 4.60E-01 3.40 +02 1.50E-01 0. 1.27E+04 3.76E-02 CE-144 2.01E+02 8.25E 01 0. 3.37E+01 0. 4.74E+04 1.07E+01 PR-144 1.45E-02 5.99E-03 0. 3.39E-03 0. 2.08E-09 7.34E-04 W-187 6.98E+00 5.85E+00 0. 0. 0. 1.91E+03 2.05E+00 NP-239 2.71E-02 2.67E-03 0. 8.25E-03 0. 5.43E+02 1.46E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 163 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE L-4 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 1.81E-01 1.81E-01 1.19E-01 1.81E-01 1.81E-01 1.81E-01 NA-24 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 P--32 5.53E+06 3.47E+05 0. 0. 0. 6.22E+05 2.14E+05 CR-51 0. 0. 1.12E+00 4.13E-01 2.48E+00 4.70E+02 1.87E+00 MN-54 0. 2.34E+03 0. 6.95E+02 0. 7.15E+03 4.46E+02 MN-56 0. 5.88E+01 0. 7.46E+01 0. 1.88E+03 1.05E+01 FE-55 3.87E+04 1.74E+05 0. 0. 2.02E+05 6.81E+04 4.58E+04 FE-59 2.71E+04 6.43E+04 0. 1.79E+04 2.12E+05 2.45E+04 CO-57 4.78E+01 0. 0. 1.21E+03 7.94E+01 CO-58 5.05E+02 0. 0. 0. 3.00E+03 1.52E+03 CO-60 0. l.41E+03 ) 0. 0. 7.80E+03 4.23E+03 Nl-65 6.73E+01 8.74E+00 0. 0. 0. 2.22E+02 3.98E+00 CU-64 0. 7.15 +01 1.80E+02 0. 6.09E+03 3.36E+01 ZN-65 5.47E+04 1.74 05 1.16E+05 0. 1.09E+05 7.86E+04 ZN-69 1.16E+02 2.23E+02 1.44E+02 3.34E+01 1.55E+01 BR-82 0. 0. 0. 0. 1.59E+00 1.39E+00 BR-83 0. 0. 0. 0. 0. 3.55E-02 2.47E-02 BR-84 0. 0. 0. 2.51E-07 3.20E-02 BR-85 0. 0. 0. 0. 0. 0. 1.31E-03 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 164 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE L-4 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - CHILD ORGAN DOSE FACTOR (MREM/HR PER pCi/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY RB-86 0. 2.08E+02 0. 0. 0. 4.09E+01 9.68E+01 RB-88 5.96E-01 0. 0. 0. 0. 3.16E-01 RB-89 0. 3.95E-01 0. 0. 0. 0. 2.78E-01 SR-89 7.53E+03 0. 0. 0. 0. 2.81E+02 2.16E+02 SR-90 9.39E+04 0. 0. 0. 0. 1.25E+03 2.38E+04 SR-91 3.18E+01 0. 0. 0. 0. 1.60E+02 1.40E+00 SR-92 1.18E+01 0. 0. 0. 0. 2.33E+02 5.08E-01 Y--90 9.00E+00 0. 0. 0. 0. 2.57E+04 2.42E-01 Y-91M 1.95E-02 0. 0. 0. 0. 5.71E-02 7.55E-04 Y--'91 1.25E+02 0. 0. 0. 0. 1.66E+04 3.34E+00 Y--92 1.81E-01 0. 0. 0. 0. 3.16E+03 5.28E-03 Y--93 5.73E-01 0 0. 0. 1.82E+04 1.58E-02 ZR-95 't.80E+01 4.19 +00 0. 2.67E+00 4.33E+03 3.81E+00 ZR-97 2.91E-01 5.87 02 0. 8.86E-02 0. 1.82E+04 2.70E-02 NB-95 4.61E+02 1.97E+02 0. 8.11E+01 0. 3.41E+05 1.45E+02 NB-97 1.24E+00 3.12E-01 0. 3.64E-01 0. 1.15E+03 1.14E-01 MO-99 0. 4.23E+01 0. 9.59E+01 0. 9.81E+01 8.05E+00 TC-99M 4.34E-03 1.23E-02 1.86E-01 6.01E-03 7.26E+00 1.57E-01 TC-101 4.47E-03 6.45E-03 0. 1.16E-01 3.29E-03 0. 6.33E-02 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 165 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM TABLE L-4 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - CHILD ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI. WHOLE BODY RU-103 1.33E+02 0. 1.39E+02 0. 3.50E+03 5.38E+01 RU-105 3.03E+00 0. 0. 3.91E+01 0. 1.85E+03 1.19E+00 RU-106 2.34E+03 0. 1.05E+03 0. 3.63E+04 2.91E+02 AG110 5.18E+02 4.80E+02 0. 9.43E+02 0. 1.96E+05 2.85E+02 SB-124 9.13E+01 1.72E+00 2.21E-01 0. 7.08E+01 2.58E+03 3.61E+01 SB-125 7.24E+01 7.80E-01 6.43E-02 0. 7.57E+03 6.40E+02 1.46E+01 TE 125M 3.11E+02 8.43E+01 8.73E+01 2.97E+02 0. 3.00E+02 4.15E+01 TE 127M 1.85E+02 6.47E+01 4.72E+01 7.50E+02 0. 6.19E+02 2.25E+01 TE-127 1.23E+01 3.27E+00 8.46E+00 1.22E+01 0. 5.24E+02 2.63E+00 TE129M 1.35E+03 3.77E+02 4.31E+02 1.31E+03 0. 1.63E+03 2.09E+02 TE-129 8.59E-01 3.25E-01 6.58E-01 3.60E+00 0. 6.47E-01 2.09E-01 TE131M 4.75E+01 2.31E+01 3.66E+01 2.34E+02 0. 2.29E+03 1.93E+01 TE-131 5.38E-01 2.25 -01 4.42E-01 2.36E+00 0. 8.05E-02 1.70E-01 TE-132 2.78E+02 1.23 02 1.81E+02 4.31E+02 0. 2.15E+03 1.48E+02 I-130 1.33E+01 3.94E+01 5.01E+03 6.12E+01 3.38E+01 1.55E+01 I-131 2.87E+02 2.94E+02 9.55E+04 1.79E+02 0. 2.51E+01 2.22E+02 I-132 3.57E+00 9.55E+00 1.26E+03 1.52E+01 0. 1.79E+00 3.39E+00 I-133 1.05E+02 1.30E+02 3.13E+04 7.61E+01 0. 5.26E+01 5.10E+01 I-134 1.86E+00 5.06E+00 6.58E+02 8.07E+00 0. 4.41E-03 1.81E+00 Based on 1 pCI/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

Page 166 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY I-135 7.79E+00 2.06E+01 2.69E+03 3.27E+01 0. 2.30E+01 7.54E+00 CS-134 8.14E+03 1.37E+04 1.75E+03 1.52E+03 7.42E+01 2.92E+03 CS-136 2.37E+02 9.34E+02 5.20E+02 7.13E+01 1.06E+02 6.73E+02 CS-137 1.13E+04 1.10E+04 0. 1.35E+03 1.29E+03 6.69E+01 1.64E+03 CS-138 2.01E+00 3.96E+00 0. 2.92E+00 2.88E-01 1.69E-05 1.97E+00 BA-139 2.65E+00 1.89E-03 0. 1.77E-03 1.07E-03 4.69E+00 7.75E-02 BA-140 2.25E+03 1.98E+00 0. 2.37E-01 1.18E+00 1.15E+02 1.32E+02 BA-141 0. .

9.71E-04 0. 9.03E-04 5.51E-04 6.06E-10 4.34E-02 BA-142 5.81E-01 5.98E-04 0. 5.05E-04 3.38E-04 0. 3.66E-02 LA-140 2.16E+00 7.52E-01 0. 0. 0. 2.14E+04 2.54E-01 LA-142 2.74E-02 1.24E-OP, 0. 0. 0. 9.09E+01 3.10E-03 CE-141 4.67E+00 2.34E+00 0. 3.66E-01 0. 2.93E+03 3.48E-01 CE-143 2.05E-01 1.52 +02 0. 6.69E-02 0. 5.67E+03 1.68E-02 CE-144 2.66E+02 8.33 01 1.50E+01 0. 2.16E+04 1.42E+01 PR-144 6.46E-03 2.67E-03 1.51E-03 9.26E-10 3.27E-04 W-187 3.03E+00 2.54E+00 0. 0. 0. 8.31E+02 8.90E-01 NP-239 1 18E-02

~ 1.16E-03 0. 3.58E-03 0. 2.36E+02 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 CALCULATlONMANUAL 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 ECL pCi/ml Nuclide ECL pCi/ml Nuclide ECL pCI/ml Ar-41 1 E-8 Co-57 9 E-10 Sb-124 3 E-10 Kr-83m 5 E-5 Co-58 1 E-9 Sb-125 7 E-10 Kr-85m 1 E-7 Fe-59 5 E-10 Te-125m 1 E-9 Kr-85 7 E-7 Co-60 5 E-11 Te-127m 4 E-10 Kr-87 2 E-8 Zn-65 4 E-10 Te-129m 3 E-10 Kr-88 9 E-9 Rb-86 1 E-9 I-130 3 E-9 Kr-89 None Rb-88 9 E-8 I-131 2 E-10 Kr-90 None Sr-89 2 E-10 I-132 2 E-8 Xe-131m 2 E-6 Sr-90 6 E-12 I-133 1 E-9 Xe-133m 6 E-7 Y-91 2 E-10 I-134 6 E-8 Xe-133 5 E-7 Zr-95 4 E-10 I-135 6 E-9 Xe-135m 4 E-8 Nb-95 2 E-9 Cs-134 2 E-10 Xe-135 7 E-8 RU-103 9 E-10 Cs-136 9 E-10 Xe-137 None Ru-106 2 E-11 Cs-137 2 E-10 Xe-138 2 E-8 Ag-110 1 E-10 Ba-140 2 E-9 H-3 1 E-7 Sn-113 8 E-10 La-140 2 E-9 P-32 1 E-9 In-113m 2 E-7 Ce-141 8 E-10 Cr-51 3 E-8 Sn-123 2 E-10 Ce-144 2 E-11 Mn-54 1 E-9 Sn-126 8 E-11

168 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 GASES'age OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 6-2 DOSE FACTORS FOR NOBLE TOTAL BODY SKIN DOSE FACTOR GAMMAAIR BETA AIR DOSE FACTOR L, DOSE FACTOR DOSE FACTOR RADIONUCLIDE N, K, M, (mrem/yr per pCi/m') (mrem/yr per pCi/m') (mrad/yr per pCI/m') (mrad/yr per pCi/m')

Kr-83m 7,56E-02** 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 7.11E+02 3.36E+03 7.39E+02 3.12E+03'.81E+03 Xe-135 1.86E+03 1.92E+03 2.46E+03

~ Xe-137 1.42E 3 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+ 3 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+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 ~

Page 169 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-3 ENVIRONMENTALPATHWAY-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 H-3 0.

CR-51 6.68E+06 MN-54 1.10E+09 FE-59 3.92E+08 CO-57 1.64E+08 CO-58 5.27E+08 CO-60 4.40E+09 ZN-65 6.87E+08 RB-86 1.29E+07 SR-89 3.07E+04 SR-90 5.94E+05 Y-91 1.53E+06 ZR-95 6.94E+08 NB-95 1.95E+08 RU-103 1.57E+08 RU-106 2.99E+08 AG-110 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

Page 170 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 4.80E+09 SB-124 8.42E+08 SB-125 7.56E+08 TE-125M 2.1 9E+06 TE-127M -

1.15E+06 TE-129M 5.49E+07 I-130 7.90E+06 I-131 2.46E+07 1-132 1.78E+06 l-133 3.54E+06 I-134 6.43E+05 l-135 3.66E+06 CS-134 2.82E+09 CS-136 2.13E+08 CS-137 1.15E+09 BA-140 2.39E+08 CE-141 1.95E+07 CE-144 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

Page 171 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM 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 WHOLE BODY H-3 0.

CR-51 4.68E+06 MN-54 1.38E+09 FE-59 2.75E+08 CO-57 1.89E+08 CO-58 3.80E+08 CO-60 2.15E+10 ZN-65 7.43E+08 RB-86 9.01E+06 SR-89 2.17E+04 SR-90 5.35E+06 Y-91 1.08E+06 ZR-95 5.01E+08 NB-95 1.36E+08 RU-103 1.10E+08 RU-106 4.19E+08 AG-110 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

Page 172 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-4 ENVIRONMENTALPATHWAY-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 WHOLE BODY SN-126 5.16E+10 SB-124 5.98E+08 SB-125 2.30E+09 TE-125M 1.55E+06 TE-127M 8.79E+05 TE-129M 3.85E+07 I-130 5.53E+06 l-131 1.72E+07 l-132 1.25E+06 I-133 2.48E+06 l-134 4.50E+05 1-135 2.56E+06 CS-134 6.99E+09 CS-136 1.49E+08 CS-137 1.03E+10 BA-140 l.68E+08 CE-141 1.37E+07 CE-144 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

Page 173 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 6-5 ENVIRONMENTALPATHWAY-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 0. 4.30E+02 4.30E+02 1.88E+02 4.30E+02 4.30E+02 4.30E+02 P-32 2.31E+05 1.35E+04 0. 0. 0 1.51E+04 8.78E+03 CR-51 0. 0. 1.40E+01 3.99E+00 2.52E+03 5.81E+02 1.75E+01 MN-54 0. 6.93E+03 0. 1.72E+03 2.45E+05 1.35E+04 1.10E+03 FE-59 2.06E+03 4.86E+06 0. 1.78E+05 3.29E+04 1.85E+03 CO-57 0. 1.21E+02 0. 6.47E+04 5.50E+03 1.18E+02 CO-58 0. 1.18E+02 0. 0. 8.79E+05 1.21E+04 1.68E+02 CO-60 0. 8.40E+02 0. 0. 5.57E+06 3.28E+04 1.17E+03 ZN-65 5.67E+03 1.81E+04 0. 1.21E+04 1.53E+05 9.35E+03 8.15E+03 RB-86 0. 2.37E+04 0. 0. 0. 2.91E+03 1.03E+04 SR-89 4.31E+04 0. 0. 0. 2.31E+06 6.80E+04 1.24E+03 SR-90 1.32E+07 0. 0. 0. 1.53E+07 1.39E+05 8.06E+05 Y-91 5.98E+04 0. 0. 0. 2.63E+06 7.17E+04 1.60E+03 ZR-95 1.08E+04 2.73E+03 0. 9.48E+03 1.81E+06 1.41E+04 1.95E+03 NB-95 1.28E+03 5. E+02 0. 1.35E+03 4.77E+05 1.21E+04 3.37E+02 RU-103 1.69E+02 0. 0. 1.02E+03 5.66E+05 1.58E+04 5.85E+01 RU-106 9.31E+03 0. 0. 2.34E+04 1.50E+07 1.76E+05 1. I4E+03 AG-110 1.89E+03 1.75E+03 0. 3.44E+03 8.12E+05 5.29E+04 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

. Page 174 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-5 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 3.11E+04 6.45E+02 6.45E+02 0. 3.61E+06 5.99E+04 1.02E+03 SN-126 2.21E+05 5.85E+03 1.72E+03 0. 1.64E+96 2.23E+04 8.40E+03 SB-124 5.46E+03 1.03E+02 1.32E+01 0. 4.34E+05 7.11E+04 2.17E+03 SB-125 1.16E+04 1.25E+02 1.03E+01 0. 3.85E+05 1.76E+04 2.32E+03 TE-125M 4.54E+02 1.95E+02 1.53E+02 2.17E+03 4.96E+05 1,36E+04 6.16E+01 TE-127M 2.21E+03 9.83E+02 5.75E+02 8.01E+03 1.68E+05 2.62E+04 2.74E+02 TE-129M 1.32E+03 5.80E+02 5.08E+02 6.40E+03 1.83E+06 7.32E+04 2.06E+02 I-130 8.02E+02 2.35E+03 3.05E+05 3.65E+03 0. 1.35E+03 9.25E+02 I-131 3.63E+04 4.27E+04 1.41E+07 1.07E+04 0. 1.07E+03 2.51E+04 I-132 2.03E+02 5.70E+02 7.67E+04 9.09E+02 0. 7.11E+01 2.03E+02 I-133 1.34E+04 1.93E+04 4.66E+06 4.55E+03 0. 2.28E+03 5.87E+03 I-134 1.13E+02 3.02E+02 4.02E+04 4.82E+02 0. 1.76E-01 1.08E+02 l-135 4.70E+02 1.22E+03 1.64E+05 1.95E+03 0. 9.18E+02 4.51E+02 CS-134 4.80E+05 8.2 E+05 0. 5.04E+04 1.01E+05 1.37E+03 7.32E+04 CS-136 6.85E+03 2.5 E+04 0. 1.50E+04 2.10E+03 2.04E+03 1.95E+04 CS-137 6.86E+05 7.31E+05 0. 3.89E+04 9.45E+04 1.32E+03 4.41E+04 BA-140 5.70E+03 4.27E+00 0. 2.93E+00 1.64E+06 3.88E+03 2.95E+02 CE-141 .2.52E+03 1.55E+03 0. 1.10E+03 5.24E+05 2.06E+04 1.81E+02 CE-144 4.68E+05 .1.82E+05 0. 1.48E+05 1.27E+07 1.61E+05 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

Page 175 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-6 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE) AGE GROUP - INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER pCI/Sec)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H-3 0. 2.37E+03 2.37E+03 1.04E+03 2.37E+03 2.37E+03 2.37E+03 P-32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 7.05E+08 CR-51 0. 0. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 3.05E+04 MN-54 0. 8.96E+06 0. 2.67E+06 0. 2.74E+07 1.71E+06

0. 2.09E+07 2.48E+08 2.86E+07 FE-59 CO-57 '.

3.17E+07 7.52E+07 1.36E+06 0.

0. 0. 0. 3.46E+07 2.27E+06 6.24E+07 CO-58 0. 2.55E+07 0. 0. 0. 6.60E+07 CO-60 0. 8.73E+07 0. 0. 2.16E+08 2.09E+08 4.65E+09 0. 3.11E+09 0. 2.93E+09 2.'I OE+09 ZN-65 1.46E+09 RB-86 0. 2.77E+09 0. 0. 0. 5.45E+08 1.29E+09 SR-89 I:47E+1 0 0. 0. 0. 0. 2.75E+08 4.22E+08 SR-90 1.65E+11 0. 0. 0. 0. 1.61E+09 4.21E+10 Y-91 8.12E+04 0. 0. 5.37E+06 2.16E+03 ZR-95 2.12E+05 9.41E+04 0. 1.86E+04 0. 7.47E+07 5.56E+04 NB-95 5.49E+05 2.4 E+05 0. 4.84E+04 0. 1.98E+08 1.45E+05 RU-103 8.30E+03 0. 0. 4.16E+03 0. 1.04E+05 2.86E+03 RU-106 2.01E+05 0. 0. 4.20E+04 0. 1.56E+06 2.46E+04 AG-'I 10 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 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)

- Page 176 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-5 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE) 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 3.48E+07 1.01E+07 0. 4.97E+06 1.16E+09 5.25E+07 SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+87 7.78E+08 1.09E+07 SB-125 3.59E+07 3.27E+06 2.93E+06 3.96E+06 2.83E+09 2.43E+08 6.62E+06 TE-125M 1.57E+08 5.30E+07 5.18E+07 7.05E+07 0. 7.57E+07 2.10E+07 TE-127M 5.54E+07 1.93E+07 1.79E+07 2.00E+08 0. 3.24E+08 7.38E+06 TE-129M 5.87E+08 2.02E+08 2.21E+08 2.70E+08 0. 3.54E+08 8.95E+07 I-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 5.29E+05 I-131 2.59E+09 3.09E+09 9.94E+11 7.24E+08 0. 1.16E+08 1.81E+09 1-132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 1.69E-01 1-133 3.75E+07 5.48E+07 1.30E+10 1.29E+07 0. 9.74E+06 1.66E+07 I-134 0. 0. 1.06E-09 0. 0. 0. 0.

I-135 1.49E+04 3.94E+04, 5.15E+06 6.26E+04 8.07E-02 4.41E+04 1.44E+04 CS-134 4.43E+1 0 7.97E+10 0. 4.65E+09 9.12E+09 1.90E+08 6.75E+09 CS-136 2.78E+08 1.10E+09 0. 6.11E+08 8.37E+07 1.25E+08 7.90E+08 CS-137 6.44E+10 7. E+10 0. 3.66E+09 8.69E+09 1.86E+08 4.14E+09 BA-140 2.45E+08 2.47E+05 0. 1.22E+04 1.51E+05 8.13E+06 1.27E+07 CE-141 2.65E+05 1.62E+05 0. 9.72E+03 0. 7.87E+07 1.90E+04 CE-144 2.10E+07 8.29E+06 0. 5.67E+05 0. 8.66E+08 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)

Page 177 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-7 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - GOATS MILK(CONTAMINATEDFORAGE) AGE GROUP - INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER pCI/Sec)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H-3 0. 4.84E+03 4.84E+03 2.11E+03 4.84E+03 4.84E+03 4.84E+03 P-32 2.19E+10 1.37E+09 0. 0. 0. 2.46E+09 8.46E+08 CR-51 0. 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 3.66E+03 MN-54 0. 1.08E+06 0. 3.20E+05 0. 3.29E+06 2.05E+05

. FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 3.72E+05 CO-57 0. 1.64E+05 0. 0. 0. 4.15E+06 2.72E+05 CO-58 0. 3.06E+06 0. 0. 0. 7.92E+06 7.49E+06 CO-60 0. 1.05E+07 0. 0. 0. 2.59E+07 2.51E+07 ZN-65 1.76E+08 5.57E+08 3.73E+08 0. 3.51E+08 2.52E+08 RB-86 0. 3.32E+08 0. 0. 0. 6.54E+07 1.55E+08 SR-89 3.09E+1 0 0. 0. 0. 0. 5.77E+08 8.87E+08 SR-90 3.46E+11 0. 0. 0. 3.35E+09 8.83E+10 Y-91 9.74E+03 0. 0. 0. 6.45E+05 2.60E+02 ZR-95 2.54E+04 1.13E+04 0. 2.23E+03 0. 8.95E+06 6.67E+03 NB-95 6.59E+04 2. E+04 0. 5.81E+03 0. 2.37E+07 1.75E+04 RU-103 9.96E+02 0. 0. 4.99E+02 0. 1.24E+04 3.43E+02 RU-106 2.41E+04 0. 0. 5.04E+03 0. 1.87E+05 2.96E+03 AG-110 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 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.

Page 178 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-7 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - GOATS MILK(CONTAMINATEDFORAGE) 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 2.10E+08 4.17E+06 1.22E+06 0. 5.97E+05 1.40E+08 6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+C6 9.33E+07 1.30E+06 SB-125 4.31E+06 3.92E+05 3.52E+05 4.76E+05 3.40E+08 2.92E+07 7.94E+05 TE-125M 1.89E+07 6.36E+06 6.21E+06 8.46E+06 0. 9.09E+06 2.52E+06 TE-127M 6.64E+06 2.31E+06 2.15E+06 2.40E+07 0. 3.88E+07 8.85E+05 TE-129M 7.05E+07 2.42E+07 2.66E+07 3.23E+07 0. 4.25E+07 1.07E+07 I-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 6.35E+05 1-131 3.11E+09 3.70E+09 1.19E+12 9.28E+08 0. 1.39E+08 2.17E+09 1-132 2.13E-01 5.71E-01 7.51E+01 9.10E-01 0. 1.07E-01 2.03E-01 1-133 4.50E+07 6.57E+07 'I.55E+1 0 1.55E+07 0. 1.17E+07 1.99E+07 I-134 0. 0. 1.27E-09 0. 0. 0. 0.

1-135 1.79E+04 4.72E+04, 6.18E+06 7.51E+04 2.42E-01 5.29E+04 1.73E+04 CS-134 1.33E+11 2.39E+11 0. 1.39E+10 2.74E+1 0 5.69E+08 2.02E+10 CS-136 8.34E+08 3.29E+09 0. 1.83E+09 2.51E+08 3.74E+08 2.37E+09 CS-137 1.93E+11 2. E+11 1.10E+10 2.61E+10 5.59E+08 1.24E+10 BA-140 2.95E+07 2.96E+04 0. 1.47E+03 1.81E+04 9.76E+05 1.52E+06 CE-141 3.17E+04 1.95E+04 0. 1.17E+03 0. 9.44+06 2.28E+03 CE-144 2.52E+06 9.95E+05 0. 6.80E+04 0. 1.04E+08 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.

Page 179 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-8 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - CHILD ORGAN DOSE FACTOR (MREM/YR PER pCI/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 7.51E+02 7.51E+02 4.96E+02 7.51E+02 7.51E+02 7.51E+02 P--32 6.11E+05 3.57E+04 0. 0. 4.00E+04 2.32E+04 CR-51 0. 0. 2.75E+01 1.06E+01 6.66E+03 1.54E+03 4.63E+01 MN-54 0. 1.83E+04 0. 4.55E+03 6.48E+05 3.58E+04 2.91E+03 FE-59 5.44E+03 1.28E+07 0. 0. 4.70E+05 8.70E+04 4.88E+03 CO-57 0. 3.20E+02 0. 0. 1.71E+05 1.45E+04 3.10E+02 CO-58 0. 1.52E+02 0. 0. 1.13E+06 3.62E+04 2.68E+02 CO-60 0. 1.07E+03 0. 0. 6.92E+06 9.36E+04 1.88E+03 ZN-65 1.50E+04 4.77E+04 3.19E+04 4.03E+05 2.47E+04 2.15E+04 RB-86 0. 6.25E+04 0. 0. 7.70E+03 2.73E+04 SR-89 5.37E+04 0. 0. -

0. 2.24E+06 1.69E+05 1.54E+03 SR-90 1.64E+07 0. 0. 0. 1.48E+07 3.45E+05 9.99E+05 Y--91 7.44E+04 0. ~

0.

2.55E+06 1.78E+05 1.98E+03 ZR-95 1.41E+04 3.28E+03 2.51E+04 2.12E+06 5.74E+04 2.98E+03 NB-95 1.70E+03 .25E+02 0. 3.58E+03 5.85E+05 3.32E+04 5.33E+02 RU-103 2.16E+02 0. 0. 2.70E+03 6.33E+05 4.22E+04 8.73E+01 RU-106 1.15E+04 0. 0. 6.18E+04 1.45E+07 4.37E+05 1.44E+03 AG110 5.00E+03 4.63E+03 0. 9.10E+03 2.15E+06 1.40E+05 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

Page 180 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 3.85E+04 6.44E+02 6.81E+02 0. 3.50E+06 1.49E+05 1.27E+03 SN-126 5.85E+05 1.55E+04 4.55E+03 0. 4.33E+06 5.88E+04 2.22E+04 SB-124 1.44E+04 2.72E+02 3.49E+01 0. 1.15E+06 1.88E+05 5.74E+03 SB-125 3.06E+04 3.30E+02 2.72E+01 0. 1.02E+06 4.66E+04 6.14E+03 TE 125M 5.62E+02 1.94E+02 1.61E+02 5.74E+03 4.81E+05 3.38E+04 7.62E+01 TE 127M 5.85E+03 2.60E+03 1.52E+03 2.12E+04 4.44E+05 6.92E+04 7.25E+02 TE 129M 1.64E+03 5.85E+02 5.40E+02 1.69E+04 1.80E+06 1.82E+05 2.60E+02 I-130 2.12E+03 6.22E+03 8.07E+05 9.66E+03 0. 3.56E+03 2.45E+03 I-131 4.55E+04 4.63E+04 1.54E+07 2.84E+04 0. 2.65E+03 3.50E+04 I-132 5.37E+02 1.51E+03 2.03E+05 2.40E+03 1.88E+02 5.37E+02 1-133 1.68E+04 2.05E+04 5.03E+06 1.20E+04 0. 5.55E+03 8.03Es 03 1-134 2.98E+02 7.99E+02, 1.06E+05 1.27E+03 0. 4.66E-01 2.85E+02 1-135 1.24E+03 3.23E+03 4.33E+05 5.14E+03 0. 2.43E+03 1.19E+03 CS-134 6.22E+05 9.95E+05 0. 1.33E+05 1.19E+05 3.77E+03 2.23E+05 CS-136 1.81E+04 .77E+04 0. 3.96E+04 5.55E+03 5.40E+03 5.14E+04 CS-137 8.66E+05 7.99E+05 0. 1.03E+05 1.00E+05 3.41E+03 1.25E+05 BA-140 7.14E+03 4.66E+00 0. 7.73E+00 1.74E+06 9.92E%03 4.22E+02 CE-141 3.13E+03 1.57E+03 0. 2.90E+03 5.14E+05 5.44E+04 2.33E+02 CE-144 5.81E+05 1.82E+05 0. 3.92E+05 1.23E+07 4.00E+05 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

Page 181 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-9 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK (CONTAMINATEDFORAGE) AGE GROUP - CHILD ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 1.57E+03 1.57E+03 1.04E+03 1.57E+03 1.57E+03 1.57E+03 P--32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 7.05E+08 CR-51 0. 0. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 3.05E+04 MN-54 0. 8.96E+06 0. 2.67E+06 0. 2.74E+07 1.71E+06 FE-59 3.17E+07 7.52E+07 0. 2.09E+07 2.48E+08 2.86E+07 CO-57 0. 1.36E+06 0. 0. 3.46E+07 2.27E+06 CO-58 0. 1.25E+07 0. 0. 0. 7.41E+07 3.76E+07 CO-60 0. 4.22E+07 0. 0. 0. 2.33E+08 1.27E+08 ZN-65 1.46E+09 4.65E+09 0. 3.11E+09 0. 2.93E+09 2.10E+09 RB-86 0. 2.77E+09 0. 0. 5.45E+08 1.29E+09 SR-89 6.92E+09 0. 0. 0. 0. 2.58E+08 1.98E+08 SR-90 1.13E+11 0. 0. 0. 0. 1.52E+09 2.87E+10 Y--91 3.80E+04 0. 0. 0. 0. 5.05E+06 1.01E+03 ZR-95 1.06E+05 4.47E+04 1.86E+04 7.68E+07 3.29E+04 NB-95 2.75E+05 1.18E+05 0. 4.84E+04 0. 2.03E+08 8.63E+04 RU-103 3.99E+03 0. 0. 4.16E+03 0. 1.05E+05 1.61E+03 RU-106 9.39E+04 0. 0. 4.20E+04 1.46E+06 1.17E+04 AG110 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 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)

Page 182 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-9 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. : 0.

SN-126 1.75E+09 3.48E+07 1.01E+07 0. 4.97E+06 1.'I 6E+09 5.25E+07 SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.78E+08 1.09E+07 SB-125 3.13E+07 1.41E+06 .1.18E+06 3.96E+06 2.83E+09 2.43E+08 5.99E+06 TE 125M 7.38E+07 2.00E+07 2.07E+07 7.05E+07 7.12E+07 9.84E+06 TE 127M 5.18E+07 1.78E+07 1.46E+07 2.00E+08 0. 2.99E+08 6.60E+06 TE 129M 2.77E+08 7.73E+07 8.85E+07 2.70E+08 0. 3.33E+08 4.28E+07 1-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 5.29E+05 1-131 1.24E+09 1.27E+09 4.12E+11 7.74E+08 0. 1.09E+08 9.56E+08 1-132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 1.69E-01 1-133 1.78E+07 2.20E+07 5.30E+09 1.29E+07 0. 8.90E+06 8.63E+06 1-134 0. 0. 1.06E-09 0. 0. 0. 0.

1-135 1.49E+04 3.94E+04 5.15E+06 6.26E+04 8.07E-02 4.41E+04 1.44E+04 CS-134 2.17E+10 3.65E+10 0. 4.65E+09 4.06E+09 1.97E+08 7.76E+09 CS-136 2.78E+08 1.10E+09 0. 6.11E+08 8.37E+07 1.25E+08 7.90E+08 CS-137 3.08E+10 2.98E+10 0. 3.66E+09 3.49E+09 1.81E+08 4.44E+09 BA-140 1.17E+08 1.02E+05 0. 1.22E+04 6.09E+04 7.75E+06 6.84E+06 CE-141 1.24E+05 6.22E+04 0. 9.72E+03 0. 7.80E+07 9.26E+03 CE-144 1.00E+07 3.14E+06 0. 5.67E+05 0. 8.15E+08 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)

Page 183 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-10 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - GOATS MILK (CONTAMINATEDFORAGE) AGE GROUP - CHILD ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 3.20E+03 3.20E+03 2.11E+03 3.20E+03 3.20E+03 3.20E+03 P-32 2.19E+10 1.37E+09 0. 0. 0. 2.46E+09 8.46E+08 CR-51 0. 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 3.66E+03 MN-54 0. 1.08E+06 0. 3.20E+05 0. 3.29E+06 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 2.72E+05 3.23E+06 3.72E+05 CO-57 0. 1.64E+05 0. 0. 4.15E+06 2.72E+05 CO-58 0. 1.50E+06 0. 0. 0. 8.90E+06 4.51E+06 CO-60 0. 5.06E+06 0. 0. 0. 2.80E+07 1.52E+07 ZN-65 1.76E+08 5.57E+08 0. 3.73E+08 0. 3.51E+08 2.52E+08 RB-86 0. 3.32E+08 0. 0. 6.54E+07 1.55E+08 SR-89 1.45E+10 0. 0. 0. 5.43E+08 4.16E+08 SR-90 2.37E+11 0., 0. 0. 3.16E+09 6.02E+10 Y--91 4.56E+03 0. 0. 0. 0. 6.06E+05 1.22E+02 ZR-95 1.27E+04 5.37E+03 0. 2.23E+03 9.22E+06 3.96E+03 ~

NB-95 3.30E+04 1.41E+04 0. 5.81E+03 0. 2.44E+07 1.04E+04 RU-1 03 4.79E+02 4.99E+02 1.26E+04 1.94E+02 RU-106 1.13E+04 0. 0. 5.04E+03 1.75E+05 1.40E+03 AG110 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 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)

Page 184 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-10 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0.

SN-126 2.10E+08 4.17E+06 1.22E+06 0. 5.97E+05 1.40E+08 6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+06 9.33E+07 1.30E+06 SB-125 3.75E+06 1.70E+05 1.43E+05 4.76E+05 3.40E+08 2.92E+07 7.19E+05 TE 125M 8.85E+06 2.40E+06 2.49E+06 8.46E+06 0. 8.54E+06 1.18E+06 TE 127M 'E 6.21E+06 2.14E+06 1.75E+06 2.40E+07 0. 3.58E+07 7.92E+05 129M 3.32E+07 9.27E+06 1.06E+07 3.23E+07 0. 4.00E+07 5.15E+06 1-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 6.35E+05 I-131 1.48E+09 1.52E+09 4.94E+11 9.28E+08 0. 1.30E+08 1.15E+09 I-132 2.13E-01 5.71E-01 7.51E+01 9.10E-01 0. 1.07E-01 2.03E-01 1-133 2.14E+07 2.64E+07 6.36E+09 1.55E+07 0. 1.07E+07 1.04E+07 I-134 0. 0. 1.27E-09 0. 0. 0. 0.

I-135 1.79E+04 4.72E+04 6.18E+06 7.51E+04 2.42E-01 5.29E+04 1.73E+04 CS-134 6.50E+10 1.10E+11 0. 1.39E+10 1.22E+10 5.92E+08 2.33E+10 CS-136 8.34E+08 .29E+09 0. 1.83E+09 2.51E+08 3.74E+08 2.37E+09 CS-137 9.23E+10 8.93E+10 0. 1.10E+10 1.05E+10 5.44E+08 1.33E+10 BA-140 1.40E+07 1.23E+04 0. 1.47E+03 7.31E+03 9.30E+05 8.21E+05 CE-141 1.49E+04 7.46E+03 0. 1.17E+03 0. 9.36E+06 1.11E+03 CE-144 1.20E+06 3.76E+05 0. 6.80E+04 0. 9.78E+07 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)

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Page 186 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-11 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATEDFORAGE) AGE GROUP - CHILD ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 6.92E+09 1.37E+08 4.02E+07 0. 2 41E+06 2.31E+09 1.98E+08 SB-124 7.40E+06 1.40E+05 1.79E+04 0. 5.74E+06 2.10E+08 2.93E+06 SB-125 7.66E+07 1.84E+07 1.90E+07 6.47E+07 9.26E+08 1.44E+08 1.08E+07 TE 125M 5.69E+08 1.54E+08 1.60E+08 5.44E+08 0. 5.49E+08 7.59E+07 TE 127M 4.40E+08 1.51E+08 1.24E+08 1.70E+09 0. 2.54E+09 5.61E+07 TE 129M 1.84E+09 5.12E+08 5.87E+08 1.78E+09 0. 2.21E+09 2.84E+08 I-130 8.87E-07 2.63E-06 3.34E-04 4.08E-06 0. 2.25E-06 1.03E-06 I-131 1.58E+07 1.62E+07 5.25E+09 9.86E+06 0. 1.38E+06 1.22E+07 I-132 0. 0. 0. 0. 0. 0. 0.

l-133 6.86E-01 8.47E-01 2.04E+02 4.97E-01 0. 3.43E-01 3.33E-01 l-134 0. 0. 0. 0. 0.

I-135 3.21E-02 2.96E-02 1.12E-02 3.37E-03 6.92E-04 1.32E-02 CS-134 8.83E+08 1.49E+09 0. 1.89E+08 1.65E+08 8.04E+06 3.16E+08 CS-136 4.41E+06 1.74E+07 9.69E+06 1.33E+06 1.98E+06 1.25E+07 CS-137 1.27E+09 1.23E+09 0. 1.51E+08 1.44E+08 7.50E+06 1.84E+08 BA-140 4.37E+07 3.84E+04 0. 4.59E+03 2.29E+04 6.03E+06 2.57E+06 CE-141 2.10E+04 1.05E+04 0. 1.65E+03 1.32E+07 1.57E+03 CE-144 2.38E+06 7.46E+05 0. 1.35E+05 0. 1.94E+08 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)

Page 187 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL OUCM TABLE G-12 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 2.47E+02 2.47E+02 1.63E+02 2.47E+02 2.47E+02 2.47E+02 P--32 4.22E+08 2.64E+07 0. 0. 4.74E+07 1.63E+07 CR-51 4.68E+03 1.73E+03 0.'.04E+04

0. 0. 1.97E+06 7.83E+03 MN-54 0. 1.98E+07 0. 5.89E+06 0. 6.07E+07 3.78E+06 FE-59 1.48E+07 3.51E+07 0. 0. 9.75E+06 1.16E+08 1.34E+07 CO-57 0. 7.53E+05 0. 0. 1.91E+07 1.25E+06 CO-58 0. 6.94E+06 0. 0. 0. 4.13E+07 2.09E+07 CO-60 0. 2.33E+07 0. 0. 0. 1.29E+08 6.98E+07 ZN-65 2.08E+07 6.59E+07 0. 4.41E+07 0. 4.15E+07 2.98E+07 RB-86 0. 5.28E+07 0. 1.04E+07 2.46E+07 SR-89 4.84E+09 0. 0. 0. 0. 1.81E+08 1.39E+08 SR-90 7.79E+10 0. 0. 1.52E+09 1.98E+10 Y--91 2.12E+06 0. 0. 0. 0. 2.82E+08 5.65E+04 ZR-95 4.06E+05 9.87E+04 0. 6.07E+04 0. 1.08E+08 8.81E+04

'B-95 6.20E+04 .64E+04 0. 1.09E+04 0. 4.58E+07 1.94E+04 RU-103 2.24E+06 0. 2.34E+06 0. 5.88E+07 9.05E+05 RU-106 5.19E+07 0. 0. 2.32E+07 0. 8.07E+08 6.46E+06 AG110 6.87E+05 6.36E+05 0. 1.25E+06 0. 2.59E+08 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

Page 188 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 BONE LIVER THYROID KIDNEY LUNG GI'-LLI WHOLE BODY SN-123 1.71E-05 2.14E-07 2.26E-07 0. 8.50E-06 4.21E-07 SN-126 3.87E+08 7.68E+06 2.25E+06 0. 1.75E+06 3.44E+08 1.19E+07 SB-124 1.02E+07 1.93E+05 2.47E+04 0. 7.93E+06 2.89E+08 4.04E+06 SB-125 1.22E+07 6.99E+05 6.22E+05 2.09E+06 1.04E+09 9.02E+07 2.29E+06 TE 125M 4.12E+07 1.12E+07 1.16E+07 3.94E+07 3.97E+07 '.49E+06 TE 127M 2.88E+07 9.90E+06 8.09E+06 1.11E+08 0. 1.65E+08 3.67E+06 TE 129M 1.56E+08 4.35E+07 4.99E+07 1.51E+08 0. 1.88E+08 2.41E+07 1-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 1.86E+05 I-131 1.24E+08 1.27E+08 4.13E+10 7.75E+07 0. 1.09E+07 9.58E+07 I-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 2.15E+01 I-133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 0. 1.81E+06 1.75E+06 I-134 . 4.18E-05 1.i 4E-04) 1.47E-02 1.81E-04 0. 9.89E-08 4.06E-05 I-135 1.64E+04 4.33E+04 5.67E+06 6.89E+04 3.51E-03 4.85E+04 1.59E+04 CS-134 9.97E+08 1.68E+09 2.14E+08 1.87E+08 9.08E+06 3.57E+08 CS-136 1.35E+07 .32E+07 0. 2.96E+07 4.06E+06 6.05E+06 3.83E+07 CS-137 1.41E+09 1.37E+09 0. 1.68E+08 1.60E+08 8.34E+06 2.04E+08 BA-140 1.70E+08 1.56E+05 0. 1.78E+04 8.87E+04 2.08E+08 9.96E+06 CE-141 1.17E+05 5.84E+04 0. 9.13E+03 7.33E+07 8.69E+03 CE-144 9.23E+06 2.89E+06 0. 5.22E+05 0. 7.51E+08 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

Page 189 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-13 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/YR PER pCI/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 8.48E+02 8.48E+02 1.07E+03 8.48E+02 8.48E+02 8.48E+02 P--32 1.32E+06 7.72E+04 0. 0. 0 8.64E+04 5.02E+04 CR-51 0. 0. 5.95E+01 2.28E+01 1.44E+04 3.32E+03 1.00E+02 MN-54 0. 3.96E+04 0. 9.84E+03 1.40E+06 7.74E+04 6.30E+03 FE-59 1.18E+04 2.78E+07 0. 0. 1.02E+06 1.88E+05 1.06E+04 CO 57 0. 6.92E+02 0. 3.70E+05 3.14E+04 6.71E+02 CO-58 1.76E+02 0. 0. 1.37E+06 9.52E+04 2.34E+02 CO-60 0. 1.24E+03 0. 0. 8.56E+06 2.35E+05 1.65E+03 ZN-65 3.24E+04 1.03E+05 0. 6.90E+04 8.72E+05 5.34E+04 4.66E+04 RB-86 0. 1.35E+05 0. 0. 0. 1.66E+04 5.90E+04 SR-89 3.87E+04 0. 0. 0. 2.50E+06 3.54E+05 1.11E+03 SR-90 1.18E+07 0. 0. 0. 1.66E+07 7.24E+05 7.23E+05 Y--91 5.38E+04 0. 0. 0. 2.86E+06 3.74E+05 1.44E+03 ZR-95 1.09E+04 3.63E+03 5.42E+04 2.56E+06 1.33E+05 2.54E+03

'B-95 1.36E+03 .24E+02 0. 7.74E+03 7.17E+05 8.80E+04 4.62E+02 RU-103 1.63E+02 0. 5.83E+03 7.51E+05 9.44E+04 7.32E+01 RU-106 8.40E+03 0. 0. 1.34E+05 1.64E+07 9.28E+05 1.06E+03 AG110 1.08E+04 1.00E+04 0. 1.97E+04 4.64E+06 3.02E+05 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 Page 190 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-13 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - TEENAGER ORGAN DOSE FACTOR (MREM/YR PER pCI/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 2.79E+04 6.14E+02 4.92E+02 3.91E+06 3.13E+05 9.20E+02 SN-126 1.26E+06 3.34E+04 9.84E+03 0. 9.36E+06 1.27E+05 4.80E+04 SB-124 3.12E+04 5.89E+02 7.55E+01 0. 2.48E+06 4.06E+05 1.24E+04 SB-125 6.61E+04 7.13E+02 5.87E+01 0. 2.20E+06 1.01E+05 1.33E+04 TE 125M 4.07E+02 1.86E+02 1.17E+02 1.24E+04 5.36E+05 7.08E+04 5.53E+01 TE 127M 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 1.57E+03 TE 129M 1.19E+03 5.64E+02 3.90E+02 3.66E+04 2.03E+06 3.84E+05 1.92E+02 I-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 5.29E+03 l-131 3.37E+04 4.72E+04 1.39E+07 6.14E+04 0. 5.96E+03 2.82E+04 I-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 1.16E+03 I-133 1.23E+04 2.06E+04 3.83E+06 2.60E+04 0. 1.00E+04 6.34E+03 1-134 6.45E+02 1.73E+03, 2.30E+05 2.75E+03 0. 1.01E+00 6.16E+02 1-135 2.69E+03 6.99E+03 9.36E+05 1.11E+04 0. 5.25E+03 2.58E+03 CS-134 4.83E+05 1.10E+06 0. 2.88E+05 1.44E+05 8.96E+03 5.44E+05 CS-136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 1.11E+05 CS-137 6.42E+05 8.24E+05 2.22E+05 1.18E+05 7.68E+03 3.03E+05 BA-140 5.30E+03 4.85E+00 0. 1.67E+01 2.02E+06 2.12E+04 3.42E+02 CE-141 2.27E+03 1.52E+03 0. 6.26E+03 5.83E+05 1.14E+05 1.74E+02 CE-144 4.19E+05 1.74E+05 0. 8.48E+05 1.38E+07 8 40E+05 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

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Page 192 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-14 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE) AGE GROUP - TEENAGER ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 2.12E+09 4.21E+07 1.24E+07 0. 6.03E+06 1.41E+09 6.37E+07 SB-124 3.33E+07 6.29E+05 8.05E+04 0. 2.59E+07 9.43E+08 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 125M 3.00E+07 1.08E+07 8.47E+06 8.55E+07 8.39E+07 3.98E+06 TE 127M 6.02E+07 2.11E+07 1.59E+07 2.43E+08 0. 3.02E+08 7.45E+06 TE 129M 1.13E+08 4.18E+07 3.61E+07 3.27E+08 0. 3.93E+08 1.78E+07 I-130 5.51E+05 1.63E+06 2.07E+08 2.53E+06 0. 1.40E+06 6.41E+05 I-131 5.12E+08 7.24E+08 2.09E+11 9.38E+08 0. 1.37E+08 4.31E+08 I-132 2.16E-01 5.76E-01 7.59E+01 9.19E-01 0. 1.08E-01 2.05E-01 l-133 7.33E+06 1.24E+07 2.26E+09 1.56E+07 9.02E+06 3.83E+06 I-134 0. 0. 1.29E-09 0. 0. 0. 0.

I-135 1.81E+04 4.77E+04 6.24E+06 7.58E+04 9.79E-02 5.34E+04 1.75E+04

'CS-134 9.44E+09 2.28E+10 0. 5.63E+09 2.76E+09 2.63E+08 1.06E+10

'CS-136 3.37E+08 .33E+09 7.41E+08 1.02E+08 1.51E+08 9.58E+08 CS-137 1.28E+10 1.72E+10 0. 4.43E+09 2.28E+09 2.29E+08 6.04E+09 BA-140 4.84E+07 5.95E+04 0. 1.48E+04 3.98E+04 9.16E+06 3.11E+06 CE-141 5.05E+04 3.39E+04 0. 1.18E+04 9.18E+07 3.89E+03 CE-144 4.10E+06 1.68E+06 0. 6.87E+05 0. 9.65E+08 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)

Page 193 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-15 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 2.03E+03 2.03E+03 2.56E+03 2.03E+03 2.03E+03 2.03E+03 P--32 2.65E+10 1.66E+09 0. 0. 0. 2.98E+09 1.03E+09 CR-51 0. 0. 2.65E+03 9.78E+02 5.88E+03 1.11E+06 4.43E+03 MN-54 0. 1.30E+06 0. 3.88E+05 0. 3.99E+06 2.49E+05 FE-59 4.99E+05 1 '9E+06 0. 0. 3.29E+05 3.91E+06 4.51E+05 CO-57 0. 1.98E+05 0. 0. 0. 5.03E+06 3.30E+05 CO-58 0. 9.72E+05 0. 0. 0. 1.31E+07 2.22E+06 CO-60 0. 3.28E+06 0. 0. 0. 3.93E+07 7.48E+06 ZN-65 2.13E+08 6.76E+08 0. 4.52E+08 0. 4.26E+08 3.06E+08 RB-86 0. 4.02E+08 0. 0. 7.93E+07 1.88E+08 SR-89 5.87E+09 0. 0. 0. 6.37E+08 1.69E+08 SR-90 1.74E+11 0. 0. 0. 4.05E+05 3.68E+09 4.30E+10 Y--91 1.85E+03 0. 0. 0. 0. 7.11E+05 4.94E+01 ZR-95 5.74E+03 3.41E+03 2.70E+03 0. 1.38E+07 1.93E+03 NB-95 1.49E+04 .96E+03 0. 7.05E+03 0. 3.66E+07 5.05E+03 RU-103 2.03E+02 0. 6.05E+02 0. 1.58E+04 9.08E+01 RU-106 4.59E+03 0. 6.11E+03 0. 2.08E+05 5.78E+02 AG110 9.04E+06 8.36E+06 0. 1.64E+07 0. 3.41E+09 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)

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Page 195 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-16 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATEDFORAGE) AGE GROUP - TEENAGER ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 1.93E+02 1.93E+02 2.44E+02 1.93E+02 1.93E+02 1.93E+02 P--32 2.76E+09 1.73E+08 0. 0. 0. 3.10E+08 1.07E+08 CR-51 0. 0. 2.50E+03 9.22E+02 5.55E+03 1.05E+06 4.18E+03 MN-54 0. 5.42E+06 0. 1.61E+06 0. 1.66E+07 1.04E+06 FE-59 1.58E+08 3.74E+08 0. 0. 1.04E+08 1.24E+09 1.42E+08 CO-57 0. 3.33E+06 0. 0. 0. 8.45E+07 5.54E+06 CO-58 0. 1.44E+07 0. 0. 0. 1.94E+08 3.27E+07 CO-60 0. 5.73E+07 0. 6.87E+08 1.31E+08 ZN-65 2.11E+08 6.69E+08 0. 4.47E+08 0. 4.21E+08 3.03E+08 RB-86 0. 2.89E+08 0. 5.69E+07 1.35E+08 SR-89 2.66E+08 0. 0. 0. 2.89E+07 7.64E+06 SR-90 1.01E+10 0., 0. 0. 2.79E+08 1.02E+09 2.49E+09 Y--91 9.34E+05 0. 0. 0. 0. 3.59E+08 2.49E+04 ZR-95 2.67E+06 1.24E+06 0. 1.18E+06 4.20E+09 7.61E+05 NB-95 1.58E+06 .51E+05 7.48E+05 0. 3.88E+09 5.37E+05 RU-103 8.05E+07 0. 0. 2.40E+08 0. 6.28E+09 3.60E+07 RU-106 2.40E+09 0. 0. 3.20E+09 0. 1.09E+11 3.02E+08 AG110 3.97E+06 3.67E+06 0. 7.21E+06 0. 1.50E+09 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)

Page 196 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-16 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATEDFORAGE) AGE GROUP - TEENAGER ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0.

SN-126 1.10E+10 2.18E+08 6.38E+07 3.82E+06 3.66E+09 3.14E+08 SB-124 1.17E+07 2.21E+05 2.84E+04 0. 9.11E+06 3.32E+08 4.64E+06 SB-125 5.01E+07 1.31E+07 1.02E+07 1.03E+08 1.47E+09 2.25E+08 7.60E+06 TE 125M 3.03E+08 1.08E+08 8.55E+07 8.63E+08 0. 8.47E+08 4.02E+07 TE 127M 6.68E+08 2.34E+08 1.77E+08 2.69E+09 0. 3.35E+09 8.28E+07 TE 129M 9.78E+08 3.63E+08 3.13E+08 2.83E+09 0. 3.41E+09 1.53E+08 I-130 1.41E-06 4.16E-06 5.30E-04 6.47E-06 0. 3.57E-06 1.64E-06 I-131 8.54E+06 1.21E+07 3.48E+09 1.56E+07 0. 2.28E+06 7.19E+06 l-132 0. 0. 0. 0. 0. 0. 0.

I-133 3.69E-01 6.26E-01 1.14E+02 7.88E-01 0. 4.55E-01 1.93E-01 I-134 0. 0. 0. 0. 0. 0. 0.

1-135 5.08E-02 4.69E-02 0. 1.78E-02 5.34E-03 1.10E-03 2.08E-02 CS-134 5.03E+08 1.21E+09 0. 3.00E+08 1.47E+08 1.40E+07 5.66E+08 CS-136 6.99E+06 .76E+07 1.54E+07 2.11E+06 3.14E+06 1.99E+07 CS-137 6.92E+08 9.31E+08 0. 2.40E+08 1.24E+08 1.24E+07 3.27E+08 BA-140 2.37E+07 2.93E+04 7.28E+03 1.95E+04 9.19E+06 1.53E+06 CE-141 1.12E+04 7.51E+03 2.61E+03 0. 2.03E+07 8.61E+02 CE-144 1.28E+06 5.23E+05 . 0. 2.14E+05 0. 3.00E+08 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)

Page 197 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-17 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY H--3 0. 2.09E+02 2.09E+02 2.64E+02 2.09E+02 2.09E+02 2.09E+02 P -32 6.81E+08 4.27E+07 0. 0. 7.66E+07 2.64E+07 CR-51 0. 0. 7.56E+03 2.79E+03 0'.68E+04 3.18E+06 1.27E+04 MN-54 0. 3.20E+07 9.52E+06 0. 9.80E+07 6.11E+06 FE-59 2.39E+07 5.67E+07 0. 0. 1.57E+07 1.87E+08 2.16E+07 CO-57 0. 1.22E+06 0. 0. 3.09E+07 2.02E+06 CO-58 0. 6.01E+06 0. 0. 8.12E+07 1.37E+07 CO-60 0. 2.01E+07 0. 0. 0. 2.41E+08 4.58E+07 ZN-65 3.35E+07 1.06E+08 0. 7.12E+07 I0 6.70E+07 4.82E+07 RB-86 0. 8.52E+07 0. 0. 1.68E+07 3.97E+07 SR-89 2.61E+09 0. 0. 0. 0. 2.83E+08 7.48E+07 SR-90 7.61E+10 0. 0, 0. 2.41E+08 2.31E+09 1.88E+10 Y--91 1.15E+06 0. 0. 0. 0. 4.41E+08 3.06E+04 ZR-95 2.35E+05 8.19E+04 0. 9.81E+04 0. 1.92E+08 5.61E+04 NB-95 3.72E+04 .24E+04 0. 1.76E+04 0. 9.14E+07 1.26E+04 RU-103 1.27E+06 0. 0. 3.77E+06 0. 9.87E+07 5.66E+05 RU-106 2.82E+07 0. 0. 3.75E+07 0. 1.28E+09 3.54E+06 AG110 1.11E+06 1.03E+06 0. 2.02E+06 0. 4.19E+08 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

Page 198 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-17 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 9.25E-06 1.53E-07 1.22E-07 0. 0. 1.33E-05 2.28E-07 SN-126 6.25E+08 1.24E+07 3.64E+06 0. 2.83E+06 5.55E+08 1.94E+07 SB-124 1.65E+07 3.12E+05 3.99E+04 0. 1.28E+07 4.67E+08 6.53E+06 SB-125 1.73E+07 5.97E+05 3.48E+05 3.38E+06 1.68E+09 1.45E+08 3.40E+06 TE 125M 2.23E+07 7.99E+06 6.30E+06 6.36E+07 0. 6.24E+07 2.96E+06 TE 127M 4 46E+07 1.55E+07 1.18E+07 1.80E+08 0. 2.23E+08 5.51E+06 TE 129M 8.46E+07 3.14E+07 2.71E+07 2.45E+08 0. 2.95E+08 1.33E+07 I-130 2.58E+05 7.64E+05 9.72E+07 1.19E+06 0. 6.55E+05 3.00E+05 I-131 6.84E+07 9.66E+07 2.79E+10 1.25E+08 1.83E+07 5.76E+07 I-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 3.47E+01 I-133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 1.04E+06 l-134 6.75E-05 1.83E-04, 2.38E-02 2.92E-04 0. 1.60E-07 6.56E-05 I-135 2.65E+04 7.00E+04 9.15E+06 1.11E+05 5.67E-03 7.84E+04 2.57E+04 CS-134 5.79E+08 1.40E+09 3.45E+08 1.69E+08 1.61E+07 6.52E+08 CS-136 2.18E+07 .60E+07 0. 4.78E+07 6.56E+06 9.77E+06 6.19E+07 CS-137 7.83E+08 1.05E+09 0. 2.72E+08 1.40E+08 1.41E+07 3.70E+08 BA-140 9.38E+07 1.21E+05 0. 2.88E+04 7.73E+04 3.19E+08 6.04E+06 CE-141 6.32E+04 4.24E+04 0. 1.47E+04 1.15E+08 4.86E+03 CE-144 5.03E+06 2.06E+06 0. 8.43E+05 0. 1.19E+09 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

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Page 200 of 225 ST. LUCIE PLANT-CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-18 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/YR PER pCI/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 2.42E+05 5.33E+03 4.53E+03 0. 2.30E+06 3.14E+05 7.86E+03 SN-126 1.26E+06 3.34E+04 9.84E+03 9.36E+06 1.27E+05 4.80E+04 SB-124 3.12E+04 5.89E+02 7.55E+01 2.48E+06 4.06E+05 1.24E+04 SB-125 6.61E+04 7.13E+02 5.87E+01 0. 2.20E+06 1.01E+05 1.33E+04 TE 125M 3.42E+03 1.58E+03 1.05E+03 1.24E+04 3.14E+05 7.06E+04 4.67E+02 TE 12?M 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 1.57E+03 TE 129M 9.76E+03 4.67E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1.58E+03 I-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 5.29E+03 I-131 2.52E+04 3.58E+04 1.19E+07 6.14E+04 0. 6.28E+03 2.05E+04 I-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 1 16E+03

~

I-133 8.64E+03 1.49E+04 2.93E+06 2.60E+04 0. 8.72E+03 4.54E+03 1-134 6.45E+02 1.73E+03, 2.30E+05 2.75E+03 0. , 1.01E+00 6.16E+02 1-135 2.69E+03 6.99E+03 9.36E+05 1.11E+04 0. 5.25E+03 2.58E+03 CS-134 3.74E+05 8.48E+05 0. 2.88E+05 9.?6E+04 1.04E+04 7.29E+05

'S-136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 1.11E+05 CS-137 4.78E+05 6.22E+05 0. 2.22E+05 7.53E+04 8.40E+03 4.29E+05 BA-140 3.90E+04 4.90E+01 0. 1.67E+01 1.27E+06 2.18E+05 2.57E+03 CE-141 1.99E+04 1.35E+04 0. 6.26E+03 3.62E+05 1.20E+05 1.53E+03 CE-144 3.43E+06 1.43E+06 0. 8.48E+05 7.78E+06 8.16E+05 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 CALCULATIONMANUAL ODCM TABLE G-19 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE) AGE GROUP - ADULT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 9.73E+02 9.73E+02 9.73E+02 9.73E+02 9.73E+02 9.73E+02 P--32 1.71E+10 1.07E+09 0. 0. 1.92E+09 6.62E+08 CR-51 0.'.80E+04

0. 1.71E+04 6.32E+03 7.20E+06 2.86E+04 MN-54 0. 8.41E+06 0. 2.50E+06 0. 2.58E+07 1.61E+06 FE-59 2.98E+07 7.06E+07 0. 0. 1.96E+07 2.33E+08 2.69E+07 CO-57 0. 1.28E+06 0. 0. 0. 3.25E+07 2.13E+06 CO-58 0. 4.72E+06 0. 0. 0. 9.56E+07 1.06E+07 CO-60 0. 1.65E+07 0. 0. 3.08E+08 3.62E+07 ZN-65 1.37E+09 4.36E+09 0. 2.92E+09 0. 2.75E+09 1.98E+09 RB-86 0. 2.60E+09 0. 0. 5.12E+08 1.21E+09 SR-89 1.46E+09 0. 0. 0. 0. 2.33E+08 4.17E+07 SR-90 4.70E+10 0., 0. 0. 0. 6.37E+08 1.15E+10 Y--91 8.60E+03 0. 0. 0. 0. 4.73E+06 2.31E+02 ZR-95 3.18E+04 1.75E+04 0. 1.75E+04 0. 1.05E+08 6.95E+03 .

NB-95 8.26E+04 .59E+04 0. 4.55E+04 0. 2.79E+08 1.80E+04 RU-103 1.02E+03 0. 0. 3.91E+03 0. 1.19E+05 4.41E+02 RU-106 2.04E+04 0. 0. 3.95E+04 0. 1.32E+06 2.58E+03 AG110 5.84E+07 5.40E+07 0. 1.06E+08 0. 2.20E+10 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)

Page 202 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-19 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE) AGE GROUP - ADULT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0.

SN-126 1.65E+09 3.27E+07 9.56E+06 0. 4.67E+06 1.09E+09 4.94E+07 SB-124 2.58E+07 4.87E+05 6.24E+04 0. 2.00E+07 7.31E+08 1.02E+07 SB-125 2.64E+07 6.06E+05 2.99E+05 3.72E+06 2.66E+09 2.29E+08 5.23E+06 TE 125M 1.63E+07 5.91E+06 4.91E+06 6.63E+07 6.50E+07 2.18E+06 TE 127M 4.63E+07 1.63E+07 1.21E+07 1.88E+08 0. 2.11E+08 5.72E+06 TE 129M 6.06E+07 2.27E+07 2.09E+07 2.53E+08 0. 3.04E+08 9.61E+06 I-130 4.27E+05 1.26E+06 1.61E+08 1.96E+06 0. 1.08E+06 4.97E+05 1-131 2.96E+08 4.25E+08 1.39E+11 7.27E+08 1.12E+08 2.43E+08 I-132 1.67E-01 4.47E-01 5.88E+01 7.12E-01 0. 8.39E-02 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 0. 0. 9.98E-10 0. 0. 0. 0.

I-135 1.40E+04 3.70E+04 4.84E+06 5.88E+04 7.58E-02 4.14E+04 1.36E+04 CS-134 5.66E+09 1.35E+10 0. 4.36E+09 1.45E+09 2.36E+08 1.10E+10 CS-136 2.61E+08 1.03E+09 0. 5.74E+08 7.87E+07 1.17E+08 7.43E+08 CS-137 7.39E+09 1.01E+10 0. 3.44E+09 1.14E+09 1.95E+08 6.62E+09 BA-140 2.69E+07 3.38E+04 0. 1.15E+04 1.93E+04 5.70E+07 1.78E+06 CE-141 2.91E+04 1.97E+04 0. 9.13E+03 7.52E+07 2.23E+03 CE-144 2.15E+06 8.97E+05 0. 5.32E+05 0. 7.26E+08 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)

Page 203 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-20 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H--3 0. 1.99E+03 1.99E+03 1.99E+03 1.99E+03 1.99E+03 1.99E+03 P--32 2.05E+10 1.29E+09 0. 0. 0. 2.31E+09 7.94E+08 CR-51 0. 0. 2.05E+03 7.58E+02 4.56E+03 8.64E+05 3.43E+03 MN-54 0. 1.01E+06 0. 3.00E+05 0. 3.09E+06 1.93E+05 FE-59 3.87E+05 9.18E+05 0. 2.55E+05 3.03E+06 3.50E+05 CO-57 0. 1.54E+05 0. 0. 3.90E+06 2.55E+05 CO-58 0. 5.67E+05 0. 0. 0. 1.15E+07 1.27E+06 CO-60 0. 1.98E+06 0. 0. 3.70E+07 4.34E+06 ZN-65 1.65E+08 5.24E+08 0. 3.50E+08 0. 3.30E+08 2.37E+08 RB-86 0. 3.12E+08 0. 0. 0. 6.15E+07 1.45E+08 SR-89 3.06E+09 0. 0. 0. 0. 4.89E+08 8.76E+07 SR-90 9.87E+10 0. 1.32E+09 2.41E+10 Y--91 1.03E+03 0. 0. 0. 0. 5.68E+05 2.77E+01 ZR-95 3.82E+03 2.10E+03 0. 2.10E+03 1.26E+07 8.34E+02

'B-95 9.92E+03 .51E+03 0. 5.46E+03 0. 3.34E+07 2.17E+03 RU-103 1.23E+02 0. 0. 4.69E+02 0. 1.43E+04 5.30E+01 RU-106 2.45E+03 0. 4.73E+03 1.58E+05 3.10E+02 AG110 7.00E+06 6.48E+06 0. 1.27E+07 0. 2.64E+09 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)

Page 204 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-20 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - GOATS MILK(CONTAMINATEDFORAGE) AGE GROUP - ADULT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 1.97E+08 3.92E+06 1.15E+06 0. 5.61 E+05 1.31E+08 5.92E+06 SB-124 3.10E+06 5.85E+04 7.49E+03 0. 2.40E+06 8.77E+07 1.22Et06 SB-125 3.16E+06 7.28E+04 3.58E+04 4.47E+05 3.19E+08 2.74E+07 6.29E+05 TE 125M 1.96E+06 7.10E+05 5.89E+05 7.95E+06 0. 7.81E+06 2.62Et05 TE 127M 5.57E+06 1.94E+06 1.47E+06 2.26E+07 0. 2.52E+07 6.86E+05 TE 129M 7.27E+06 2.72E+06 2.51E+06 3.04E+07 0. 3.65E+07 1.15E+06 I-130 5.12E+05 1.52E+06 1.93E+08 2.36E+06 0. 1.30E+06 5.96E+05 l-131 3.56E+08 5.10E+08 1.67E+11 8.72E+08 0. 1.34E+08 2.92E+08 I-132 2.00E-01 5.36E-01 7.06E+01 8.55E-01 0. 1.01E-01 1.91E-01 I-133 4.80E+06 8.32E+06 1.60E+09 1.45E+07 0. 7.32E+06 2.54E+06 I-134 0. 0. 1.20E-09 0. 0.

1-135 1.68E+04 4.44E+04 5.80E+06 7.05E+04 2.28E-01 4.97E+04 1.63E+04 CS-134 1.70E+10 4.04E+10 0. 1.31E+10 4.34E+09 7.06E+08 3.30E+10 CS-136 7.84E+08 .09E+09 0. 1.72E+09 2.36E+08 3.52E+08 2.23E+09 CS-137 2.22E+10 3.03E+10 0. 1.03E+10 3.42E+09 5.83E+08 1.99E+10 BA-140 3.23E+06 4.05E+03 0. 1.38E+03 2.32E+03 6.84E+06 2.13E+05 CE-141 3.49E+03 2.36E+03 0. 1.10E+03 9.02E+06 2.68E+02:

CE-144 2.58E+05 1.08E+05 0. 6.39E+04 0. 8.71E+07 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)

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Page 206 of 225 ST. LUCIE PLANT .

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-21 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATEDFORAGE) AGE GROUP - ADULT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER pCI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 1.86E+10 3.69E+08 1.08E+08 0. 6A6E+06 6.19E+09 5.33E+08 SB-124 1.99E+07 3.75E+05 4.80E+04 0. 1.54E+07 5.62E+08 7.85E+06 SB-125 6.65E+07 1.58E+07 1.29E+07 1.74E+08 2.49E+09 3.80E+08 1.05E+07 TE 125M 3.59E+08 1.30E+08 1.08E+08 1.46E+09 0. 1.43E+09 4.81E+07 TE 127M 1.13E+09 3.93E+08 2.96E+08 4.56E+09 0. 5.11E+09 1.39E+08 TE 129M 1.14E+09 4.29E+08 3.95E+08 4.79E+09 5.76E+09 1.82E+08 I-130 2.38E-06 7.05E-06 8.96E-04 1.10E-05 0. 6.04E-06 2.77E-06 I-131 1.08E+07 1.55E+07 5.06E+09 2.65E+07 0. 4.07E+06 8.85E+06 I-132 0. 0. 0. 0. 0. 0. 0.

I-133 4.40E-01 7.63E-01 1.47E+02 1.33E+00 0. 6.71E-01 2.33E-01 I134 0. 0. 0. 0. 0. 0. 0.

1-135 8.60E-02 7.94E-02 0. 3.01E-02 9.04E-03 1.86E-03 3.53E-02 CS-134 6.58E+08 1.57E+09 0. 5.08E+08 1.68E+08 2.74E+07 1.28E+09

'S-136 1 18E+07

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1.35E+08 2.30E+07 7.82E+08 BA-140 2.88E+07 3.63E+04 0. 1.23E+04 2.07E+04 6.87E+07 1.90E+06 CE-141 1.41E+04 9.52E+03 0. 4.41E+03 0. 3.63E+07 1.08E+03 CE-144 1.46E+06 6.10E+05 0. 3.62E+05 0. 4.93E+08 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)

Page 207 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-22 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY, LUNG Gl-LLI WHOLE BODY H--3 0. 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 P--32 1.04E+09 '.51E+07

0. 0. 1.17E+08 4.02E+07 CR-51 0. 1.15E+04 4.25E+03 0.'.56E+04

0. 4.85E+06 1.93E+04 MN-54 0. 4.87E+07 0. 1.45E+07 0. 1.49E+08 9.31E+06 FE-59 3.64E+07 8.64E+07 0. 0. 2.40E+07 2.85E+08 3.29E+07 CO-57 0. 1.85E+06 0. 0. 0. 4.70E+07 3.08E+06 CO-58 0. 6.89E+06 0. 0. 0. 1.40E+08 1.54E+07 CO-60 0. 2.38E+07 0. 0. 0. 4.46E+08 5.23E+07 ZN-65 5.11E+07 1.62E+08 0. 1.09E+08 0. 1.02E+08 7.34E+07 RB-86 0. 1.30E+08 0. 0. 0. 2.56E+07 6.06E+07 SR-89 2.67E+09 0. 0. 0. 4.26E+08 7.64E+07 SR-90 8.49E+10 0. 0. 0. 0. 2.14E+09 2.07E+10 Y--91 1.26E+06 0.- 0. 0. 0. 6.92E+08 3.37E+04 ZR-95 2.93E+05 9.82E+04 1.49E+05 0. 3.34E+08 6.38E+04.

'B-95 4.87E+04 .71E+04 0. 2.68E+04 0. 1.64E+08 1.06E+04 RU-103 1.50E+06 0. 5.75E+06 0. 1.76E+08 6.49E+05 RU-106 2.95E+07 0. 0. 5.71E+07 0. 1.91E+09 3.74E+06 AG110 1.69E+06 1.56E+06 0. 3.08E+06 0. 6.38E+08 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

Page 208 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20

'HEMISTRY OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-22 ENVIRONMENTALPATHWAY-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 BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-123 1.00E-05 1.66E-07 1.41E-07 0. 0. 2.04E-05 2.45E-07 SN-126 9.52E+08 1.89E+07 5.54E+06 0. 4.3'1 E+06 8.46E+08 2.94E+07 SB-124 2.52E+07 4.75E+05 6.08E+04 0. 1.95E+07 7.12E+08 9.94E+06 SB-125 2.58E+07 7.23E+05 4.03E+05 5.14E+06 2.56E+09 2.22E+08 5.10E+06 TE 125M 2.38E+07 8.65E+06 7.17E+06 9.69E+07 9.51E+07 3.19E+06 TE 127M 6.75E+07 2.36E+07 1.77E+07 2.73E+08 0. 3.06E+08 8.32E+06 TE 129M 8.93E+07 3.34E+07 3.08E+07 3.73E+08 4.49E+08 1.42E+07 I-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 4.58E+05 I-131 7.78E+07 1.12E+08 3.65E+10 1.91E+08 2.94E+07 6.38E+07 I-132 5.57E+01 1.49E+02 1.96E+04 2.38E+02 0. 2.80E+01 5.29E+01 I-133 2.13E+06 3.69E+06 7.10E+08 6.44E+06 0. 3.24E+06 1.13E+06 l-134 1.03E-04 3.63E-02 4.45E-04 0. 2.43E-07 9.99E-05 2.79E-04'.07E+05 l-135 4.04E+04 1.40E+07 1.70E+05 8.65E-03 1.19E+05 3.91E+04 CS-134 6.82E+08 1.62E+09 5.26E+08 1.74E+08 2.84E+07 1.33E+09 CS-136 3.32E+07 1.31E+08 0. 7.29E+07 9.99E+06 1.49E+07 9.43E+07 CS-137 8.90E+08 1.22E+09 4.14E+08 1.37E+08 2.34E+07 7.98E+08 BA-140 1.03E+08 1.35E+05 0. 4.39E+04 7.38E+04 6.65E+08 6.77E+06 CE-141 7.16E+04 4.85E+04 0. 2.25E+04 1.85E+08 5.49E+03 CE-144 5.19E+06 2.17E+06 0. 1.29E+06 0. 1.75E+09 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 LIMITING LIMITING (X/Q) VALUE CALCULATION RANGE (miles) Sector sec/m'.6 Instantaneous 0.97 NW X 10 1/31 days 0.97

1. Normally (X/Q) = 1.6 X 10~ sec/m'.

Quarterly 0.97 Yearly May use option of actual 12 Consecutive 0.97 meteorological data for time of months 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 LIMITING LIMITINGSECTOR (X/Q) sec/m' (D/Q)

CALCULATION RANGE (miles) (OL) 1/m'.2 NW Instantaneous 0.97 1.3 X 10 WNW X 10' 0.97 A,B Annual Report 0.97 1/31 days, B 0.97 NW v Qtr. yearly, 1.3 X 10 v Annual 0.97 WNW 8.2 X 10 Total Dose (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 (D/Q) Value LIMITINGRANGE LIMITINGSECTOR 1/m~

CALCULATION Release Rate

-1/31 Days Quarterly - Yearly Annual (Calendar Year) B Annual Report 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.

Page 212 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE M-4 TERRAIN CORRECTION FACTORS Florida Power 8 Light Company St. Lucie Unit 1 Terrain Correction Factors (PUFF / STRAIGHT LINE)

Hutchinson Island, Florida Period of Record: 8/29/77 to 8/31/78 Dames and Moore Job No: 4598-112 Base Distance in Miles/Kilometers DESIGN AFFECTED DISTANCE .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SECTOR MILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 1.906 1.576 1.465 1.404 1.338 1.318 1.334 1.386 1.346 1.338 NE 1.887 1.581 1 461 1.391 1.310 1.259 1.164 1.128 1.101 1.116 ENE 1.452 1.230 1.122 1.081 1.047 1.033 .941 .941 .906 .902

0. 1.662 1.425 1.277 1.193 1.151 1.123 1.097 1.121 1.123 1.122 ESE 0. 1.690 1.483 1.328 1.260 1.246 1.190 1.134 1.094 1.032 .968 SE 0. 1.818 1.691 1.470 1.427 1.435 1.36 I 1.366 1.331 1.279 1.239 SSE 0. 1.812 1.586 , 1.370 1.302 1.270 1.263 1.229 1.193 1.171 1;151 1.398 1.321 1.125 1.083 1.108 1.127 1.073 1.063 1.047 1.024 SSW 0. 1.534'.411 1.296 1.192 1.205 1.132 1.135 1.116 1.077 1.060 SW 1.685 1.492 1.294 1.233 1.200 1.222 1.160 1.160 1.198 1.196 WSW 0. 1. 0 1.333 1.210 1.173 1.082 1.091 1.099 1.056 1.034 1.004 W 0. 1.6 1 1.415 1.290 1.218 1.154 1.099 1.081 1.067 1.093 1.083 WNW 0. 1.720 1.430 1.267 1.185 1.150 1.133 1.125 1.085 1.033 1.045 NW 0. 1.681 1.407 1.257 1.173 1.119 1.078 1.063 .995 .998 .978 NNW 0. 1.739 1.488 1.316 1.212 1.172 1.122 1.135 1.080 1.099 1.091

0. 1.816 1.524 1.389 1.285 1.257 1.263 1.285 1.267 1.231 1.213 Note 1: Any interpolations between stated mileages will be done by Iog-log

Page 213 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 Average Annual Relative Concentration (sec/cubic meter)

Hutchinson Island, Florida Period of Record: 9/1/76 to 8/31/78 Dames and Moore Job No: 1.4598-112 Base Distance in Miles/Kilometers DESIGN AFFECTED DISTANCE .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SECTOR MILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64

0. 1.1E-05 1.7E-06 7.8E-07 4.5E-07 3.1E-07 2.2E-07 1.7E-07 1.5E-07 1.2E-07 1.0E.07 NE 1.3E-05 2.1E-06 8.9E-07 5.1E-07 3.4E-07 2.4E-07 1.7E-07 1.4E-07 1.1E-07 9.8E-OB ENE 0. 9.3E-06 1AE-06 6.2E-07 3.7E-07 2.5E-07 1.9E-07 1.3E-07 1.1E.07 B.BE-OB 7.5E-OB 9.8E-06 1.6E-06 6.5E-07 3.7E-07 2.5E-07 1.8E-07 1.4E-07 1.2E-07 9.9E-OB BAE-08 ESE 0. 1.2E-05 1.9E-06 8.1E-07 4.8E-07 3.2E-07 2.4E-07 1.8E-07 1.4E-07 1.1E-07 9.0E.OB SE 1.4E-OS 2.4E-06 9.7E-07 5.7E-07 4.0E-07 2.9E-07 2.3E-07 1.9E-07 1.4E-07 1.2E-07 SSE 0. 1.1E-05 1.? E-06 i 7.3E-07 4.3E-07 2.9E-07 2.1E-07 1.6E-07 1.3E-07 1.1E-07 9.1E-OB 6.2E-06 1.0E-06 4.2E-07 2.5E-07 1.8E-07 1.4E-07 1.0E-07 B.OE-OB 6.6E-OB 5.5E-OB SSW 0. 5.7E-06 9.0E-07 4.0E-07 2.3E-07 1.6E-07 1.1E-07 8.9E-OB 7.0E-OB 5.7E-OB 4.8E.OB

'SW 6.1E-06 9.4E-07 3.9E-07 2.2E-07 1.6E-07 1.1E-07 8.6E-OB 7.0E-OB 6.0E-OB 5.1E-OB Wsw 0. 7.3E-06 1.1E-06 4.6E-07 2.7E-07 1.7E-07 1.3E-07 1.0E-07 B.OE-OB 6.5E.OB 5AE-08 W 7.6E-06 1.2E-06 5.2E-07 2.9E-07 2.0E-07 1.3E-07 1.0E-07 8.4E.OB 7.2E-OB 6.1E-OB WNW 0. 1.4E-05 2.1E-06 9.1E-07 5.2E-07 3.4E-07 2.6E-07 2.0E-07 1.5E-07 1.2E-07 1.0E-07 Nw 1.6E-05 2.4E-06 1.0E-06 5.9E-07 3.9E-07 2.8E-07 2.1E-07 1.7E-07 1 AE-07 1.2E.07 NNW 1.5E-OS 2.2E-06 9.6E-07 5.5E-07 3.6E-07 2.6E-07 2.0E-07 1.6E-07 1.3E-07 1.2E.07

0. 9.1E-06 1.4E-06 6.3E-07 3.6E-07 2.4E-07 1.8E-07 1.4E-07 1.2E-07 9.4E-OB 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

Page 214 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 Average Annual Relative Concentration Depleted (sec/cubic meter)

Hutchinson Island, Florida Period of Record: 9/1/76 to 8/31/78 Dames and Moore Job No: 4598 - 112 Base Distance in Miles/Kilometers DESIGN AFFECTED DISTANCE .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SECTOR MILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64

0. 1.1E-05 1.6E-06 6.6E-07 3.8E-07 2.4E-07 1.7E-07 1.3E-07 1.1E-07 9.2E-OB 7.6E-OB

0. 1.2E-05 1.7E-06 7.6E-07 4.3E-07 2.8E-07 1.9E-07 1.4E-07 1.1E-07 8.6E-OB 7.4E-OB ENE 0. 8.9E-06 1.2E-06 5.3E-07 3.0E-07 2.0E-07 1.4E-07 1.0E-07 8.4E-OB 6.6E-OB 5.6E-OB

0. 9.1E-06 1.3E-06 5.6E-07 3.1E-07 2.1E-07 1.5E-07 1.1E-07 9.1E-OB 7.5E-OB 6.3E.OB ESE 0. 1.2E-05 1.6E-OB 6.9E-07 3.9E-07 2.6E-07 1.9E-07 1.4E-07 1.1E-07 8.5E-OB 6.7E-OB SE 1.3E-05 2.0E-06 8.2E-07 4.7E-07 3.3E-07 2.3E-07 1.8E-07 1.3E-07 1.1E-07 9.0E.OB SSE 0. 1.1E-05 1,6E-06 I 6.3E-07 3.5E-07 2.4E-07 1.8E-07 1.4E-07 1.0E-07 8.2E-OB 6.8E-OB

0. 5.9E-06 9.1E-07 3.6E-07 2.1E-07 1.4E-07 1.1E-07 7.7E-OB 6.2E-OB 5.0E-OB 4.1E-OB Ssw 0. 5.4E-06 B.OE-07 3.4E-07 1.9E-07 1.3E-07 8.9E-OB 6.9E-OB 5.5E-OB 4.3E-OB 3.6E-OB

'Sw 5.7E-06 8.4E-07 3.4E-07 1.8E-07 1.2E-07 9.2E-OB 6.7E-OB 5.3E-OB 4.6E-OB 3.8E-OB WSW 0. 7.0E-06 9.6E-07 4.0E-07 2.2E-07 1.4E-07 1.0E-07 B.OE-OB 6.1E-OB 5.0E-OB 4.0E-OB W 7.3E-06 1.1E-06 4.4E-07 2.4E-07 1.6E-07 1.1E-07 8.2E-OB 6.4E-OB 5.5E-OB 4.4E.OB WNW 0. 1.3E-OS 1.9E-06 7.9E-07 4.4E-07 2.9E-07 2.0E-07 1.6E-07 1.2E-07 9.3E-OB 7.8E-OB NW 1.5E-05 2.1E-06 8.9E-07 4.9E-07 3.1E-07 2.3E-07 1.7E-07 1.3E-07 1.0E-07 8.5E-OB NNW 1.4E-05 2.1E-OB 8.3E-07 4.5E-07 2.9E-07 2.0E-07 1.6E-07 1.2E.07 1.0E-07 8.6E.OB

0. 8.7E-06 1.3E-06 5.4E-07 3.0E-07 2.0E-07 1 4E-07 1.1E-07 8.9E.OB 7.0E-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

Page 215 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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 Average Annual Relative Deposition Rate (square meter - 1)

Hutchinson Island, Florida Period of Record: 9/1/76 to 8/31/78 Dames and Moore Job No: 4598-112 Base Distance in Miles/Kilometers.

DESIGN AFFECTED DISTANCE .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SECTOR MILES AO 1.21 2.01 2.82 3.62 4A2 5.23 6.03 6.84 7.64 NNE 0. 6.5E-OB 9.3E-09 3.7E-09 2.1E-09 1.3E-09 9.0E-10 6.8E-10 5.5E-10 4.3E-10 3.5E-10 NE 6.0E-OB 8.9E-09 3.5E-09 1.9E-09 1.2E-09 8.1E-10 5.6E-10 4.3E-10 3.3E-10 2.8E-10 ENE 0. 3.2E-OB 4.8E-09 1.9E-09 1.0E-09 6.6E-10 4.6E-10 3.2E-10 2.4E-10 1.9E-10 1.5E-10 3.0E-OB 4.6E-09 1.8E-09 9.5E-10 6.0E-10 4.2E-10 3.1E-10 2.5E-10 2.0E-10 1.6E-10 ESE 0. 3.7E-OB 5.8E-09 2.3E-09 1.2E-09 B.OE-10 5AE-10 3.9E-10 3.0E-10 2.2E-10 1.7E-10 SE 6.4E-OB 1.0E-OB 4.0E-09 2.1E-09 1.4E-09 9.7E-10 7.2E-10 5.6E-10 4.3E-10 3.5E-10 SSE 0. 6.2E-OB 9.5E-09 3.6E-09 2.0E-09 1.2E-09 8.7E-10 6.4E-10 4.9E-10 3.9E-10 3.1E-10 4.2E-OB 7.0E-09 i 2.6E-09 1AE-09 9.5E-10 6.9E-10 4.9E-10 3.8E-10 3.0E-10 2.5E-10 SSW 0. 3.4E-OB 5.4E-09 2.2E-09 1.1E-09 7.5E-10 5.0E-10 3.7E-10 2.9E-10 2.3E-10 1.8E-10 Sw 4.5E-OB 7.0E-09 2.6E-09 1.5E-09 9.0E-10 6.6E-10 4.6E-10 3.6E-10 3.0E-10 2.5E-10 Wsw 0. 5.3E-OB 7.7E-09 3.0E-09 1.6E-09 1.0E-09 7.3E-10 5.5E-10 4.1E-10 3.3E-10 2.6E-10 W 0. 5.0E-OB 7.5E-09 3.0E-09 1.6E-09 9.8E-10 6.7E-10 5.0E-10 3.8E-10 3.2E-10 '.6E-10 WNW 0. B.BE-OB 1.3E-OB 4.9E-09 2.6E-09 1.7E-09 1.1E-09 8.7E-10 6.6E-10 5.1E-10 4.2E-10

0. 8.2E-OB 1.2E-OB 4.7E-09 2.5E-09 1.6E-09 1.1E-09 7.9E-10 5.8E-10 4.7E-10 3.8E-10 NNW 0. 8.2E-OB 1.2E-OB 4.6E-09 2.4E-09 1.5E-09 1.1E-09 8.1E-10 5.9E-10 4.8E-10 4.0E-10

0. 5.1E-OB 7.3E-09 2.9E-09 1.5E-09 9.8E-10 7.1E-10 5AE-10 4.2E-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 0.0- 1.5- 3.0- 5.0- 7.5- MEAN SECTOR 1.5 3.0 5.0 7.5 10.0 )10.0 TOTAL'69 SPEED 71 206 $ 18 71 3 0 3.32 NNE 1.92 .43 02 0.00 4.05

.43 1.25 62 292 385 128 0 0 867 3.43 38 1.77 2.33 0.00 0.00 5.25 60 334 505 158 0 0 1057 ENE 3.51

.36 2.02 3.06 .96 0.00 0.00 6.40 69 355 510 76 0 0 1010 3.25

.42 2.15 3.09 .46 0.00 0.00 6.11 115 684 744 72 1 0 1616 ESE 4.14 4.50 01 0.00 9.78

.70 183 660 749 28 0 0 1620 2.88 SE 4.53 .17 0.00 0.00 9.81 1.11 3.99 129 579 656 93 1 0 1458 SSE 3.10

.78 3.50 3.97 .56 01 0.00 8.82 72 310 407 99 8 1 897 3.36 1.88 2.46 .60 05 .01 5.43 84 372 446 105 33 4 1044 3.48 SSW 2.25 2.70 .20 02 6.32

.51 129 440 336 106 14 0 1025 SW 3.10

.78 2.66 2.03 .64 08 0.00 6.20 155 320 186 29 5 0 695 2.59 WSW 1.94 1.13 .18 03 600 4.21

.94 ~

174 267 119 37 2 0 599 2.43 W 1.62 .72 01 0.00 3.63 1.05 203 304 172 17 0 0 696 WNW 1.84 1.04 10 0.00 0.00 4.21 1.23 143 518 424 50 0 0 1135 NW 3.14 2.57 .30 0.00 0.00 6.87

.87 85 379 535 70 1 0 1070 NNW 0.00 6.46

.51 2.29 3.24 .42 01 91 194 531 148 5 0 969 3.69

.55 1.17 3.21 .90 .03 0.00 5.86 95 95 CALM CALM .57

.57 1920 6214 7023 1287 73 5 16522 3.10 TOTAL 37.61 42.51 7.79 .03 100.00 11.62 NUMBER OF VALIDOBSERVATIONS 16522 94.30 PCT. Key XXX Number of Occurrences NUMBER OF INVALIDOBSERVATIONS 988 5.70 PCT. XXX Percent Occurrences TOTAL NUMBER-OF OBSERVATIONS 17520 100.00 PCT.

' Totals below are given in hours 8 percent for wind frequency by sectors

Page 217 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX B RADIOLOGICALENVIRONMENTALSURVEILLANCE ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMATE SAMPLES DIRECTION PATHWAY LOCATION DESCRIPTION COLLECTION DISTANCE COLLECTED SECTOR FREQUENCY (miles)

Direct Radiation N-1 North of Blind Creek TLD <Quarterly Direct Radiation NNW-5 South of Pete Stone Creek TLD Quarterly NNW Direct Radiation NNW-10 C. G. Station TLD Quarterly NNW Direct Radiation NW-5 Indian River Drive at Rio Vista Drive TLD Quarterly NW Direct Radiation NW-10 Intersection of SR 68 and SR 607 TLD Quarterly 10 NW Direct Radiation WNW-2 Cemetery South of 7107 Indian River Drive TLD Quarterly WNW Direct Radiation WNW-5 US-1 at SR 712 TLD Quarterly WNW Direct Radiation WNW-10 SR 70, West of Turnpike TLD Quarterly 10 WNW Direct Radiation W-2 7609 Indian River Drive TLD Quarterly W Direct Radiation W-5 Oleander and Sager Streets TLD Quarterly W Direct Radiation W-10 l-95 and SR 709 TLD Quarterly W Direct Radiation WSW-2 8503 Indian River, Drive TLD Quarterly WSW Direct Radiation WSW-5 Prima Vista Blvd. at Yacht Club TLD Quarterly WSW Direct Radiation WSW-10 Del Rlo and Davis Streets TLD Quarterly 10 WSW Direct Radiation SW-2 9207 dian River Drive TLD Quarterly SW Direct Radiation SW-5 US 1 a d Village Green Drive TLD Quarterly SW Direct Radiation SW-10 Port St. Lucie Blvd. and Cairo Road TLD Quarterly 10 SW Direct Radiation SSW-2 10307 indian River Drive TLD Quarterly SSW

Page 218 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX B RADIOLOGICAL ENVIRONMENTALSURVEILLANCE (continued)

ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMATE SAMPLES DIRECTION PATHWAY LOCATION DESCRIPTION COLLECTION DISTANCE COLLECTED SECTOR FREQUENCY (miles)

Direct Radiation SSW-5 Port St. Lucie Blvd. and US 1 TLD Quarterly SSW Direct Radiation SSW-10 Pine Valley and Westmoreland Roads TLD Quarterly SSW Direct Radiation S-5 13179 Indian River Drive TLD Quarterly Direct Radiation S-10 US 1 and SR 714 TLD Quarterly 10 Direct Radiation S/SSE-10 Indian River Drive and Quail Run Lane TLD Quarterly 10 SSE Direct Radiation SSE-5 Entrance of Nettles Island TLD Quarterly SSE Direct Radiation SSE-10 Elllot Museum TLD Quarterly 10 SSE Direct Radiation SE-1 South of Cooling Canal TLD Quarterly SE U. of Florida - 1FAS Entomology Lab Vero Direct Radiation H-32 TLD Quarterly 19 NNW Beach Radioiodine 8 Airborne H08 FPL Substation -~Weatherby Road Weekly WNW Particulates Radioiodine &

Airborne 'H12 FPL Substation - SR 76, Stuart Weekly 12 Particulates Radioiodine &

Airborne H14 Onsite - near south property line Weekly SE Particulates Radioiodine &

Airborne H30 Power Line - 7609 Indian River Drive Weekly W Particulates

'Denotes Control Sample

Page 219 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX B RADIOLOGICALENVIRONMENTALSURVEILLANCE (continued)

ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMAT SAMPLES DIRECTION Airborne PATHWAY LOCATION DESCRIPTION COLLECTION E DISTANCE COLLECTED SECTOR FREQUENCY (miles)

Radioiodine 8 H34 Onsite - At Meteorological Tower Weekly 0.5 Particulates Surface Water Weekly Atlantic Ocean vicinity of public beaches east side (ocean) ENE/E/ESE Waterborne H15 of Route A1A Sediment from Semi-Annually shoreline Surface Water Monthly

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

(mangrove)

'Denotes control sample

Page 220 of 225 ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX B RADIOLOGICALENVIRONMENTALSURVEILLANCE (continued)

ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMAT SAMPLES DIRECTION PATHWAY LOCATION DESCRIPTION COLLECTION E DISTANCE COLLECTED SECTOR

,FREQUENCY (miles)

Broad leaf Monthly Food Products H52 Offsite near south property line vegetation S/SSE (when available)

(mangrove)

Crustacea Fish Semi-Annually Broad leaf Semi-Annually Food Products 'H59 Near south end of Hutchinson Island $ 0-20 S/SSE vegetation Monthly (mangrove)

'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 ENVIRONMENTALSAMPLE LOCATIONS

~ N-1 C5 4 H51 O

CC LLI R 0

IZ WNW-2 Z o.

e, z' +~

O CREE~

H15 .... L i

~ - EXCLUSION AREA (0.97 mi)

ANO LOW UNIT 1 Al W.2 POPULATION ZONE (1 mi)

NOTES:

+ UNIT 2

1) L-Uquid Radwaste Release Poi nt

2) Due to the scale of the SE-Figure the Exclusion Area Radius (0.97 mile) and the +e Low Population Zone (1 mile) area shown as being tho same size.

O FPL's Property Une

~ H14 z.'SW

-2 H52 (C-ZOOA. WPG)

SCALE IN MILES

Page 222 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCUIATIONMANUAL ODCM FIGURE 1-2 ENVIRONMENTALSAMPLE LOCATIONS 10 MILES NW 10 H32 Veto Beach (Control) 10 rrtrlea NNW-1 0 WNW.10 EOF W-1 SW-WSW 5 SSW W~.10 )

SSE S10 SW.10 S/SSE-1 0 SSE-1 0 H59 SSW-10 fC.200B.WPC)

H12

Page 223 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX C METEOROLOGICAL DISPERSION FORMULAS'or X/Q:

2.032 X/Q EQ (1) 2 cV~

(u)D (a z ~

1t

)

2.032 EQ (2) z (u)D Where:

C =.5 V = 207.5 ft. (63.2 meters)

(u) = 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 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i 152 pendlx 8 - Limit Dose ssment for a ctlve u ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

d for Eff

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

- 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. II ccMAl~oQr Ro~>~ -' V 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 IR19 C i'- i EASMNSiP M i S lp i I IR19 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

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 CHANNEL BASIS ALERT HIGH ODCM Related Iodine Channels ID DOCUMENT SETPOINT'000 SETPOINT 1PV IODINE 01%3 FUSAR CPM 10,000 CPM'0,000 1FHB IODINE FUSAR 5000 CPM CPM'0,000 2A PV PIG IODINE FUSAR 5000 CPM GPM'0,000 2B PV PIG IODINE FUSAR 5000 CPM CPM'0,000 2FHB IODINE 412 FUSAR 5000 CPM CPM'0,000 SGBDB IODINE 45-5 FUSAR 5000 CPM CPM'IGH CHANNEL BASIS ALERT ODCM Related Uquld Channels ID DOCUMENT SETPOINT' SETPOINT'.E~

1A SlG BLOWDOWN x Bkg. uCI/ml 1B SIG BLOWDOWN 2x Bkp. 2.EM uCVml 2A SlG BLOWDOWN 121 2 x Bkp. 2,E~ uCVml 2B S/G BLOWDOWN 2x Bkp. 2.E~ uCVmi" 1 BATCH LIQUID EFFLUENT R6627 As Per C-70 As Per G-70" t 2 BATCH LIQUID EFFLUENT Table Notations:

a - ODCM Control 3.11.2.1a b- ODCM Table 4.11-1 Nota P)

C-200 As Per C-70 As Per C-70" 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.

't 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~,

IR19 St. Lucle Plant ODCNI Controls

Page 51 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM RADIOACTiVEEFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION Continued ADMINISTRATIVECONTROLS 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

4. ~

estimate) 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 Dose from Beta Radiation CC or cc Cubic centimeter Cl Curies - a unit of radioactivity see pCI CI Activity or concentration of a nuclide in the release source. Units of pCI, pCVcc or pCVml CFR Code of Federal Regulations Control(s) 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 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 Dose Pathway A specific path that radioactive'material physicaIIy travels through prior to exposing an'individual to radiation. The Grassow-MIIk-lnfant Is a dose pathway Dose Rate The dose received per unit time (D/Q) 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.

ECL ENuent Concentration Limit FUSAR Final Updated Safety Analysis Report.

I 0

0

Page 79 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL 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 The St. Lucle Plant Standard Technical Specifications Total Body Same as Whole Body In Control Statements pCI micro Curies. 1 pCI ~ 10~ Curies. The pCI is the standard unit of radioactivity for all dose calculations ln the ODCM.

(X/Q) 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).

(X/Q)~ 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+.

dt, at or delta t 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 CALCUIATIONMANUAL 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 F, Z C,

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~ < =

we@ = toogg~ rr Mlle rr ueere ~ererr 6 +Ar S)

D ~

Water Pumps. '.:..'*

Re Nathan 6o Xerrr Ine" mon ow in gpm of'take Cooling hter or Clrcuihting 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 I

121,000 gaVmln .. 1.BS uCVrnl (I-131 Table L-1ECL)

Solving for the S/8 High Alaim Setpoint l-131 Actlvtty, I-131 uCI/ml (S/G) ~ -2E44 &I/mlH31 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

(~os'id'"~) + ~+ (~ ~~ I P

is Wa c~W i(ig 3.(l ~ ~.~)

,v . ~

Page 91 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDLIRE C-200, REYISION 19 OFFSITE DOSE CALCULATION MANUAL ODCM posE METHODOLOGY SECTION g6.6 Fhc TER QogI 1A (continued) rl A cHL<

1. (continued)

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.

Pi~TE Table 1.4 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>rg l~ 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 CALCLILATIONMANUAL 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)

Q ~-A ooae (I)

(DF),

Pago 93 of 194 ST. LUCtE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM METHODOLOGY SECTION 1.4 (continued)

1. (continued) gge QouPS) aQ modems'I> >

i d. 'UU!

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 CALCULATIONMANUAL 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:
m18m 68 (p
-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 no a Itional dose rate calculations re needed to verify compliance 10'CI/sec),
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
~,lh ensure that all noble gas releases In progress do not e Control 3.11.2.1 noble gas release rate limit for the site, osefjiamore timing than the t
oatcutated tt Il skin I
dose dose rate of 500 mrem/yr has been determined to be equivalent to II 3.5E+05 uCVsec being released from the site. Using 3.5E+05 uCVsec as lt ed the ODCM e total body tt t lady 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 (Example)
Percent
~Milt Unit Plant Vent 1
Pt ~II mmi 40 Unit 1 Fuel Bldg. Vent 5 EGGS 1A 1 EGGS 1B. 1 Unit 2 Plant Vent Unit 2 Fuel Bldg. Vent 5 ECCS 2A -" ~ 1 ECCS 28'>>
Blowdown Bldg. + 6 Vent'otal Percent Allocated~ 99 or 1 percent below the Site Limit
Page 100 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE ALCULATIONMANUAL ODCM METHODOLOGY SECTION 2,2 (continued) j g. (continued)
A. (continued)
+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 O'7,O+
allocation h controlled per Chemistty Procedure COP, Process Monitor Setpoints where Chemistty Supetvisor approval Is required.
07,c5 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 the site limit.
1.
2.
Obit tt t pll'P engineering unit of uCVcc that will be equivalent to the allocated portion of II rate (Yj In Cubic Feet per Minute (cfm) from the ENuent Supervisor.
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 ~~
sec, "Ilkala"~II min,, Y ft3
~"~k-1 28317 cc 100%
SP~ 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.
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 Vent there are 3 ODCM ENuent Gas Channels Monitoring the Plant Vent The HIGH SETPOINT In uCl/cc is the same for 2A PV PIG LOW RANG 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 ~
~ ~
ail I
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.
RP ",Jgl. "- '::V.IP-'RlI1II' -mlle co min....:. .:-.'t, 60 sec 3.5E+05 uCI I 1 ~
Where:
~ Fraction of the Site,LImit F
", 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 
~ .
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 to'..';
I
/R
~ '
\I ~
I'
Page 103 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE D E CALCULAT0 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 ,
~ F I
'I r If
/R)9 I
I II II F
~
~
~ ~ * ~ I F ~
I I'
'I
Page 104 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE ALCULATIONMANUAL ODCM METHODOLOGY ~iECTION 2.2 (continued) g.'continued)
I 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 7y ~ (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
~~SISSI CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 SIS ~GS G G 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 hour 3,3E+06cc.s x R~RUt xRMEQ ft3 min x ~~
60 sec gj'Vg~
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'"~
hour 6.32E+06cc.s
" aeoiaa ft3 .
aleue min
~s 60 sec
- eaaae 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.
8.
a ~ 'rr 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 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 sector at the exclusion area, (See Table sec/m'nd M-1 ls the most limiting 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'ec va/ue) cc cc.
(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 X X "
'KgÃQ} (Q DDTJ,
}c -m'ec DR ~ ggygj .total body dose from nuclide (I) for yr the specmed release source t.- '"
s
~ % '
~ ~
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 yr specied release source (I) for the
~,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:
'r I
0 ~
DR~ ~ Z i'DR~, ~ 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
I ll r r 1 1 ~
~ ~
r I
= ~
r,
,r
~
r r
~ r ~ wr r
~ rrqrr rv y~g ~ ~ Il 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 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
.4, be rformed one time, re emberln at the dos must dMd by 0.8, 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 sec pCI yI'M' Ni mrad m3 p-gpss Stm Qi ILCI 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..
D,+D, 'Dmrad r
D~
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 fIQ. (r l ONP S 2.6 Determinin the Radioiodine and Particulate Dose To An 0 an From Cumulative Releases
~Illho Lv.m'r S~ervtS0 Wit( +T-GCg cV ht'c I P ge fwceI ~~Lc+iv+) ~e. QrGuQ(s~ co~( E.u.<4
~uP 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.
OeS AO+ App,g Ol,tIg g r o~p 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
For Ground PlanearfGrass&owlGoat-Milk, Gr<<s -<'j ,(g~ cia<]o~
)
I7 O~~ sa Z 3.17 X10~RI (NQ)Q, i
For each pathway above (excluding Graund Plane) For Tritium:
P ~ ~
HN 3.17 X 10~R~~QX/Q}r Q(
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) the deposion value for a specific location where the receptor ls located (see discussion). The units are 1/m'here m=meters.
Q, 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
~ae.~ hJum+r o,ppc'o ~~/(~
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 8D Particulates. -. '
7 &m radlolodlnes &
Xwha4hoa ~
~
p~" P~gcivhbt<
-- +58M.
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. ':" -.
Cow' '
t" oat Ht k
,.Do x.NFL~
Mt',Ml'
'-7 c G. IO
,i EE-8 AC HI-W ~
~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 O steps 2.6.3.8 through 2.6.3.F. Refer to step 2.6.5 to determine the total I 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.
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 from the Table specied below
(~ for the organ T of interest MILK AGE . INHALATION COW GOAT Infant 65 8% 6-7 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.
~ Mals 0 m P<P~erey Melhe$
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 willbc 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) willbe 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:
Meat Dose Factor Agc Table No.
Infant N,A.i Child G-11 Teen G-16 Adult 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
~ ~
2.6.5.
z~ ~P~
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) willbe 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 CAlCULATIONMANUAL 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 d - Fro um 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 DOSE rem) STEP 0 REF.
Inhalatlon (l&8D 2.6.1.F Ground Plane (l&8DP) ole Body only) 2.6.2.F Grass- Milk (I&8DP 2.6.3.F Inhaiatlon (H<) 2.6.4.E Grass- -Mll H4) 2.6,4.E B. The dose Doser toNch
~ t (sum of abave)
WuP's 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 Q4 la<<
T v spry p~ Issue op l9Q
~~% 4 F' IEE 4'9q. S4~ ~. t .~
Age Group: INFANT CHILD TEEN ADULT Organ: BONE LIVER THYROID KIDNEY LUNG Gl-LLI WHOLE BODY erenee PATHWAY DOSE to STEP No. Remark Inhalation (I&8DP) 2.6.1.F.
Inhalation (Tritium)
Ground Plane (I&8DP) 2.6.2.F.
Grass - - Milk(l&8DP) 2.6,3.F.
Grass - - Milk(Tritium) 36KB.
Grass - - Meat (I&8DP)
N.A. for INFANT Grass - - Meat (Witium)
N.A. for INFANT Vegetable Garden (1&8DP)
N.A. for INFANT Vcgctablc Garden (Tritium) %.4C E.
N.A. for INFANT rs>>>>, >>p a4wl)
Do~ .
Page 136 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL 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 6.1-1 ¹F8 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 sKoeor~ A N AL ODCM 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&AId 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= rsr r'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 METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS SOURCE ANALYSIS EACH BATCH PR IP MrITERs P.h.a.
MONITO LS.
TANK RELEASEte
/ MONTHLYCOMPOSITE ,F.P.
QUARTERL Sr%9, r-QO, @45 C.S.~
OUR PER MONTH PR IPAL MfTTERS P.h.a, STEAM AND DISSOLVED GASES GENERATOR LS.
8 LOWDOWN MONTHLYCOMPOSITE ,F.P.
RELEASES QUARTERLY ITE re&, r-90, Fe-65 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, .
~ - Gas Flow Proportional Counting I'.F.P.
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 METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS SOURCE ANALYSIS Waste Gae Each Tank Prlnclpal Gamma Emltlere G, p,h.a.
Decay Tank Releaeee Containment Purge rlnclpal Gamma Emlttere G, p.h,a.
Purge Releasee S.
our per Month Prlnclpal Gamma Emlttere , C, P) - p.h.a.
L, Plant Vent . F.
tParticulatee)
Quarte e Sr%0 (Partloulatee) Sr%9 Cg, Gaseous Grab Sample C Charcoal Fitter Sample Particulate Filter Sample L.S. Uquld Scintillation Counting C.S. Chemical Separation.'
p.h.a. Gamma spectrum pulse height analysis'using Uthlum Germanium detectois..'All peaks are identNed and quantNed.
'as C
G.F.P. 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
'l IcMMl aaiiiaijt clSR TB ~
A. Fission and Activation Products
1. Total Release - (Not including Tritium, Gases, Alpha) Ci E
2. Average Diluted Concentration ~L During Period ~lttttlt' E
8. Tritium Total Release . CI
2. Average Diluted Concentration During Period . ~ttttt E E pci/il C. Dissolved and Entrained Gases Total Release 2.. Average Diluted Concentration:,, c,~'~f During Period.. 1 D. Gtoaa Alpha Radloactlvtty
1. Total Release-' CI I
c Il
~ ~
4
ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 19 OFFSITE DO E ALCULATIONMANUAI ODCM METHODOLOGY E ON FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE UNIT ff TABLE 3.5 LIQUID EFFLUENTS - DOSE SUMMATION Ago Group: Adelt- Location: *wpAttott Exposure Interval: From Through CALENDAR YEAR DOSE Fish 8 Shellfish Pathway to Organ (mrem)
BONE LIVER THYROID KID L N Gl- I WHOLE BODY
Page 158 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATI MANUAL ODCM TASLE I=2 IIRONINENTALPATHWAY~SE CDNVERSION FACTORS FOR UQUID DISCHARGES PATHWAY- SAI.T WATER RSH AND SHELLRSH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM/HR PER pCI/ML)
= LIVER LUNG Gl-Lu WHOLE BODY G8-137 .. 8.79E4$ '=.120E+04 0. 2.31E+02 7.88E+K GS-138 6.08EAS -
12DEW1 0. , 8~+00 8.73E&1 5.12E~ 5.96E+00 BA-139 -. 'JPEAN. --,5.61HS 0. 5%4E~. 3.18E~ 1 ME+01 2.30E41 BA-140.. - 1.65E+03- .-
0. 7.04E<1 ~ 1.18E+00 3.39E+03 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 -=
735E41 0. 0. 0. 583&04 2.11F%1 LA>>142 -" =-8.0?E42 3.6?EH)2 0. 0. 0. 2.68E+02 9.15E43
-- GE-141 "-.
343E~ 0. 0. 8.87E+03 GE-143 6.05E%1 4.47E+02 0. 1$ 7E+1 0. 1.67E+04 4.95'.60E+00 GE-144 . 1.79EA2 .7ASE+01 Q. 4A3E+01 0. 6.05E+04 PR-144 . 191M2 7$ 8E~ 0. 4.45E~ 0. 2.73E49 9.65&)4 W-187 - 9.17E4$ 7.68E+00 0. 0. 0. 251 E+03 2.69E+00 NP-239 35SE42 350E~ 0. 1.08E~ Q. 7.12E+02 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 ORGAN DOSE FACTO TH%EH/HR PEP. UCI/HL l BONE LIVER THYROIO KIDNEY LUNG CI LLI N TOT)~17'/H~
Neeee3 0~ ZeiTE 01 zeiTE 01 Zel4c 01 2e17E 01 2 irE'i Z>> llE-a 1 NA 4e63E 01 4e&3E 01 4 ~ 63E 01 4 ~ 63E Oi 4e63Eeai 4 ~ 63E 01 Oe 4 ~ 63f. Dl Peee32 ie 27c+Ol le98E+05 D~ 0~ Oe ie43E+06 Oe 4o93&i05 CR 51 0~ Oe Ze54E+OQ 9e38Eeai 5.64E<<aa iealE+03 4 'SE<<00 Hgee54 5e Se38E+03 0~ 1 6aE+03 Oe 1e&SE+04 Oe le 03c<<03 HNe-56 Oe ie3&E+02 a. ieTZE+02 0~ 4e3ZE+03 0~ 2.4ZE<<01 Fc 55 be 78E+ 04 3e95E+05 D~ 0~ 4e57E+05 ie54E+05 0 lea4E<<05 FE- 59 &e ivEc<<04 le4&E+05 0~ 0~ 4eQSE<<04 4ebiE+05 5.55t<<04 CO -57 a. ieadc+02 0~ 0~ Ze74E+03 746<<OZ CO co-&a 58 Ee Oe be 1ZE+02 ieTOE+03 F
0~
0 '
~
0~
0~
0~
0~
8 ~ 26E+03 Ze04E+44 4>>
Oe 1~
le39Eea3 3 '8E<<03 88 NI 65 1 ~ 54E+OZ -, 2e DOE+01 0~ a 0~ 5 ~ QTE+02 9e ill<<00 CU 64 Oe ie&4E+OZ Oe 4 ~ 12E+DZ De 1 ~ 39E+ 04 7 ~ 69c<<01 ZN-65 ie23E+05 3o 90E+ 05 0~ 2e&1E+DS Oe Ze46E+05 ioTTE<<05 ZH-69 Z~ 61E+0 2 Seazf+02 0~ 3e24E<<02 0~ 7 ~ 50E+01 3 ~ 47E<<01 BR 82 Oe 0~ 0~ 0~ Oo 3 '5E+00 3e 10ic<<00 BR -83 ae Oe 0~ Oe Oe le95Eeaz e 5 '2E-02 8% -84 a. 0~ 0~ 0~ Oe 5e61E OT 0 le 16E-OZ BR 85 ae 0~ 0~ 0~ 0~ a. 0 Ze94E 03
%8e 86 Oe 4e 76 E+0 2 0~ 0~ Oo 9 'TE<<01 2 ~ 2ZE<<02 RB bd 0~ 1.37E<<00 0~ Oe 0~ 0~ Oe Te Z3E-al FB 89 ae 9ea4E 01 0~ 0~ a. Qe 0 ~ 6438E 41 SR -89 5e6lc+D3 0~ 0~ Oe de 6e15E+OZ Oe 1 ~ 63ioaz SR 90 ieZOE+05 Oe 0~ Oe ao 2 liE+D3 3 alii<<04 cR 91 7eidi+01 0~ 0~ 4 ~ 0~ 3 '1E+OZ 3e 16c << 00 SR 9Z Ze66E+01 0~ 0~ Oe 0~ 5e25E+OZ 1.15ioaa Y -90 1 '88+01 0~ 0~ Oe iebOE<<04 S.Z3E+a4 4 ~ ZSE Dl Y--91H 4 '6Ee02 0~ 0~ 0~ 0~ 1 ~ ZSE 01 1~ 69E-03 Y-e 91 9e40i+Di 0~ 0~ 0~ 0~ 3 ~ 61E+04 Oe 2 'li<<00 Y -9Z 4 '6E 01 0~ 0~ Oe 0~ lelaE.+03 lotbc 02 Yeee93 ieZ9E+OD D~ 0~ D~ Oe ~ 08E+04 0 ~ 3155E-02 2% 95 1 ~ 49E<<ai 4e96E+00 Oe 6.1&E<<aa 0~ 1 ~ Ol'6+04 0 3.4&ieaa ZR 97 6 ~ 72E 01 le36E 01 0~ Ze05E-01 0 4 ~ ZOE+ 04 6 ~ Z4E 02 NB 95 3e97E<<02 2o39E+02 D~ 1 ~ 88E<<02 0~ 9 '&E<<05 lo 35f e OZ NB 97 2 ~ blE+OD 7e24E 01 0~ 8 F 456 01 0~ Z~ &lE<<03 0 2 ~ 64E 01 HO-99 0~ 9o 74E+01 Oe ZeZic+02 go Ze26E+OZ 1~ 85E<<01 TC 99H 9eblE 03 Ze79E 02 0~ 4eZ4f. 01 1~ 37E-02 1 ~ 65E<<81 3e 5&i-01 BASER nN i Hnf/CCI CCI CeeC ~ ee
0 cNVIRONNENTAL FATHttAY OOSE COHVERSION FACTORS FOR LIGUIO OISCHARGES PATHMAY SALT HATER FISH AHO SHELLFISH AGE GROUP - TEE HAGER HUQ.IOE ORGAN 0GS FACTO R I NAf.N/HR PER UCIIHL1 TC 101 1~
BCNE 42E-02 LIVER io47E 02 0~
THYROIO KIONEY 2e64E ai 7 LUNG 4lc OS Oe GI-LLI
~~
RCT5t~&tY 1 ~ 44E 01 wt}0LE Ruo103 1~ 04E+02 Oo 0~ 3e iiE+02 4~ do 13E+03 4 ~ eef+oj RU 105 6o77E+00 0~ 0~ do74fiaj 0~ 4oi4E+03 z ~ elf+ 00 FU 106 1~ 76E+03. 0~ a. Ze34f+03 0~ le 9SE+04 ZeZjf+02 AGjjaP io 19E+03 ioiaf+G3 0~ ZoilE+G3 4~ 4 'if+45 Oe 6o56f+OZ air SS iZ4 = Ze iif >02 Soggf+00 5oiiEooi 0~ 1 64E+02 5.98E+aS 8 ~ 35E+Oj SS 125 1 ~ 68E+02- 1e diE+00 1 o49E 01 0~ io lsf +04 io48E+43 Oo 3o3Tcoai Tf 125N Zo36E+02 do45E+Oi 6 '6c+Oi eoTZE+CZ 0~ 6 'aft02 a. So 13fiai at'- Tc jZTN 4oldf+02 . io46c402 1 alf+QZ irlof+OS ao ie40f+Q3 0 soagfiaj TE 127 9o 31E+00 3oZdf+00 6e35E+00 Ze 76E+01 0~ 7 'ZE+8Z 1 ~ 99E+Qa Tc 129N 1 ~ QZE+03 3e79E+02 3oZTE+02 Zo96E +03 0~ Sesdf+03 a. 1 ~ ejf+Gz TE 129 io94E+00 le34fea 5o 2ZE+ 01 j je49E+00 boZ6E+bi be14f+00 5e29E+OZ 0~ 1 46E+aa idc+43 4o 4o 4 ~ TZE-01 4 ~ SSE+41 TE 131N 1 ~ OTE+DZ 0~
tI TE 131 1 ~ 21E+00 . 5oadfea j 9o99E 01 5e33E+08 0~ 1 ~ 82E bi 3 ~ 83E 41 TE 132 . 2ei9E+OZ- 1~ 3lE+02 1 4ef+02 9ol4E+OZ 0~ 4 '3E+03 a. io 30f.< 4Z q',. c
J 130 3e QSE+Oi do 95E+01 ioj4E+04 io39E+02 0~ Teelf tai a 3 ~ SZE+01 I--131 2e 23c+ OZ 3ei46+02 gooTE+04 4oadE+OZ 0~ 5e95E+41 a joblfioZ I 132 , 8~ 1 jf>00 ZeilE+Oi 2 'eftaS 3o46E+0 1 4~ 4 '8E+44 7 ~ Tjf<00 I 133 8 ~ iiE+Qi ioSTE+02 2 ~ SQE+04 ie 73E+OZ a. 9 '9E+Qi 4 ~ 24E+Oi I 134 4e24E+aa iei5E+Cj io49E+03 iod3E+ai a ie04E-02 4o iZE< 00 I 135 CS 134 1 ~ 77E+Oi 6o75E+03 4eebftai 1 ~ 63E+04 ee a.
jif+03 le43f >0 4~ OSE+03 j 0~
1 ~ 9lE+03 5 ZSE+aj 1~ 88E+42 1 ~ 71E oai T~ eof <03 CS 136 5e46E+02 Zoi6E+03 0~ jeZQE +03 io65E+OZ 2 '5E<OZ a. 1 ~ 55E+43 i CS 137 8 ~ 9dE+03 1 ~ 21E+04 0~ SeiiE+03 ie60E+03 1~ 61E+ 02 0~ 4e24E<43 to t CS 138 4 '3E+00 9.jsfioo 0~ 6ol3E+04 e.eSf-ai 3 ~ 94E 05 Qo 4o54E<00 BA 139 5 '9E+00 4o 27fe 03 a 3o99E 03 Z ~ 42c 03 io06E+01 1~ Tsf-Qi BA-140 1~ TSE+03 Zojsftaa 0~ 5o35E 01 1.44E+00 2e5SE+aZ ioiZfiaZ BA 141 0~ 2oZOEo03 0~ Zeaafo03 1 ~ Z5E-03 1.37E-ag gobaE-OZ BA 142 1 ~ 31E+0 0 io35E OS 0~ io 14f 03 7.64E-04 0~ 8~ 26f OZ LAoj40 1 ~ 67E+00 do25E 01 0~ 0~ 0~ 4.55E~04 Z~ idE 41 LA 142 6 14E 02 Zelgfe02 0~ 0~ S~ 2 '4E+02 oe 6 ~ 95E 03 CE 141 3 ~ 51E+40 2o36E+00 0~ bo jgfea1 0~ 6 '8E+03 0 ~ ZoTOE-41
"~
CE 143 4. eaE-ai Se40ft02 0 ~ jo50E Qi 0~ ieZTE+04 3 '6E QZ Cc 144 2~ Oic+02 do 25E+ 0 1 0~ 3e3TE+Qi 0~ 74E+O4 1~ OTE+01 r.
PR 144 io45f OZ . 5o99E 03 0 ~ 3o39fe03 0~ Zoodf-09 To 34E 04 N 187 6 ~ 98E+00 5ob5f+00 0~ 0~ 0~ io9ifo03 2~ Ost+40 NP 239 2elif 02 Zo67E 03 0~ beZ5E 03 0~ 5 ~ 43EIQZ 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 A H DOS i FACTOR (NREH/HR PER UCI/HL) r LIVER GI-LLI ~~POT THYROID KIDNEY W~
r'UNG BCNE ~
Sy' Herr>>3 1 ~ 51Er01 f ~ 61E 01 1~ 19i 01 1>>51E-41 1>> 51E-01 ~ bii-01 KA>>r24 2>> 03fr01 2>> 03Ero 1 2 ~ 03E 01 2>>03E 01 2>> d3E bi Z>>03E 01 Oe 2 ~ D3E-01 32 5 '3E+06 3>>47ft05 Oe Qe a. 6e2ZE+05 0 ~ 2 '4ft05 CR 51 Oe 0~ 1 ~ 1Zctoo 4>>13E 01 Ze48E+ ~0 4>>TOE+02 0>> 1~ 57E+ 00
~N 54 0~ 2e34E+03 0~ 6>>95Ftoz 0~ 7 15Et43 0 4 '6E>>OZ KH 56 De 5 85Etoi 0>> 7>>46E+01 0~ 1 ~ bdct03 1 ~ 05E eoi Fc 55 3 ~ 57Et04- 1~ T4ft05 0>> 0. Z.0Zi+05 6>>dec+04 4e55E t DC Ff 59 2>> 71E+44 6>>43Et04 0~ 0~ 1 ~ 79E>>04 2e 12Et05 2-45ftoc C0-57 0~ 4>>78Et01 0~ 0~ 0~ 1>> Z1E+03 7 ~ 94E+Dl Ca-55 Do 5>>05Et02 0~ 0~ 0~ 3 OQF+43 0>> 1 '2ft03 CO 60 0. 1>>4l,f+03 oe 8~ 4~ le 80E+03 0>> 4 ~ 23f t03 55E'
, HI-65= 6>>73Etoi be74Et00 D~ 0>> 0~ 2>>22E+QZ 4>> 3 '5E+40 CU or 64 Oe 7>>15ct01 Oe ieboi+02 0~ 6>> 09E+03 0 3>>36ftoi ZH 65 5>>47E+04 74E+05 0~ ief&ft05 0~ 1>>49c+45 7 '6E+04 ZH 69 1 ~ 16c+0 2 Ze 23 E+ 02 0. ie44E+02 0~ 3>> 34E+ 01 0>> f>>SSEtof BR -52 Oe 0- 0~ 0~ 0~ 1 ~ 59f+08 0~ 1 ~ 39E+OO BR 53 De 0~ 0~ 0~ 0~ 3>>55E-OZ Z 4TE-DZ BR 54 0>> 0~ 0~ 0~ 4~ 2e5if 07 0>> 3>>ZOE-02 8% 55 4~ 0~ 0. 0~ 0. 0>> 4>> 1>>3ff-03 RB 56 De 2>>08Et02 0~ 8~ 0~ 4 ~ 09E+01 Oo 9e65Etbf RB 85 De 5>>96E 01 0~ be 0~ Oe 0~ 3 '6f-oi RB 59 0~ 3>>95E 01 D~ 0~ Oo 0. 0 2>>7bfr01 SR 59 Te53Et03 a. 0~ 0~ Qo Z>>51Et42 Ze16ftoz SR 90 9>>39E+04 a. a. 0~ 0~ le 2SE+03 Oo Z>>3bft04 SR 91 3>>idE+01 0 0~ 0~ 0~ ie60E+QZ Oe 1 '0E>>00 SR 9Z leidE+01 0~ 0~ 0~ 0~ 2 '3i+OZ Oo 5>>Odf-Of Y r 9>>DOEtDO 0~ 0~ 0~ ~o Z>>STE+44 Oo 2 ~ CZE of 90'r>>91H 1 ~ 95E 02 0. 0~ oe 4~ 5 '1c 4Z 7 '5E-04 Y -91 1~ 25E+02 0~ 0~ 0~ 0~ 1~ 66E+04 Oo 3 ~ 34E>>OO Yrr>>92 i>>die 41 0~ 4 ~ a. 0~ 3>>1&f+03 0~ 5 'bf. 03
'Yrrr93 5 ~ 73E 01 0. 0~ oo 0~ 1>>bzc+04 0 1~ Sbf 02 ZR 95 1~ dof+01 4>>19E+00 4~ 2>>&TE+00 4~ 4>>33&+03 3.bfcftOO ZR 97 2>>91E 01 5>>87E 02 0~ 6 ~ 56E 02 0~ iodzf>>44 2 ~ Tof DZ NB>>-95 4 ~ 61E+02 1 ~ 97c+02 0~ 8~ iii+01 0~ 3>>41E+05 1~ 45ftoz NB 97 1 ~ 24Et00 3>>1ZE 01 0~ 3>>64E 01 4~ 1 o 15E+03 iofCE 01 HO 99 Oo 4>>Z3E+01 0~ 9 '9ctoi 0~ 9>>bif+01 &~ OSE<00 TC 99H 4 '4E 03 i>>23E 02 0~ 1>>56E 01 6>>oif r03 Tez&ftoo 4>> 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 BCNE LIVER THYROID KIDNEY LUNG GI LLI 4fR4lr -DOOV UIHCiG S40y' TC>>101 4>>47E 03 6o45E 03 Oo ioi6E>>01 3ozgf 03 0~ ~ 33E OZ RU>>103 io 33E+02 0~ 4o io39Et42 0~ 3 '0E+D3 D~ 5 'bftOf RU 145 3o 03E+00 4~ 4~ 3o9ift01 0~ io85E+03 de 1 fgft00 RU>>106 2 ~ 34Et43 0~ de 1005E+03 4~ 3.63E+04 2o91C+OZ AG1 igt 5oidftOZ 4obdf+02 4~ 9e43F+02 Oe io96E+05 0~ Ze 85f tOZ SB 124 9o 13E+ Oi 1, ~ 72E+00 2>>21E>>01 0~ le48E+41 2 58E+03 3 ~ 61'E+ 01 SB 125 lo 24E+41 7o DOE>>01 6>>43E OZ 0~ To57E+03 6o40E+82 0 ~ 1~ 46f t Oi TE 125H 3o iiE+OZ bo43E+Oi de73Et01 Ze9lE+02 0. 3.00E+OZ 0 4o 15f tOf Tf 12TH iob5E+42 6.47E+01 4 'ZE+41 le 50E+02 )~ 6 ~ 19E+02 Zo 256 t01 Ti-izl 1 ~ Z3E+ Oi 3o ZTE+00 de46ft00 ie 22C+Oi 0~ 5 24E+02 t 2o 636 00 t
TE129N 1 ~ 35E+03 3o 77 f+02 4>>31E+02 ie 31E+03 8~ 1>>63Et03 Oo 2o 09C. 02 Tc 129 de59E 01 3e25E Oi 6>>58E 01 3>>60E+00 0~ 6>>4lE 01 0. Zo 49E-41 TE131N 4o75E+Oi .' Ze31E+41- 3>>66Et01 2>>34E+02 0~ 2 '9E+03 0~ 1e 93E+41 TE 131 5e38E 01' Z>>25E>>01 4>>42E bi Zo36E+04 0~ 8 ~ 05E OZ 1o TOE 01 TE 132 2 ~ lbft02 ie23E+02 iebiE+OZ 4o3f E+02 0~ 2>>15ct03 0 fe48Et4Z I 134 1e33Et01 3o94f+Oi 5 ~ 01Et03 6oiZE+Oi 0~ 3 '8E+01 0 1~ 55Et01 I 131 2eblE+42 ~ 2o94E+02 9o55Et04 fe79Et02 0~ 2 ~ 51E+Oi Ze Zzft02 I 132 3>>57E+00 9o55E+00 1e26E+03 ie52E+Di 0~ 1>>79Etbb 3 '9ft00 I 133 io05Et02 ie30E+02 3>>13E+04 7e61E+01 do 5. 26E+01 0~ 5 ~ iOE+01 I 134 io86E+00 5o 06E+ 00 6e5dEtOZ boDTE+DO 0~ 4 ~ 41E 03 febift44 I 135 lo79E+00 2o 46E+Oi Z ~ 69Et43 3o27E+Oi 0~ Zo 30E+Oi Oo To 54Et 00 CS 134 8 e14E+03 fo37Ft04 4~ io75E+03 1.52Et03 7.42E+01 Zo9ZCt03 CS 136 2e37E+OZ 9o34ft42 0~ 5ezDftDZ lo13E+81 1~ 46f t02 Oo 6o73ftdz CS 137 fe 13ft04 Ceidft44 0~ 1o 35f+03 ie29E+03 6 ~ 69E+Di Oo io 64Ct 03 CS 138 Zo 01E+40 3o 96E+ 04 4~ Z>>9ZE+00 2obbE Oi 1 ~ 69E 45 0~ fe9TE+00 BA 139 Zo 65E+ 00 1 ob9E 43 0. ioTTE 43 1 ~ OTE-83 4 ~ 69f+DO 7o75f-OZ BA 140 2o25f+03 1098Et 00 0~ Zo3TE Oi ioibft00 1 ei5ft02 0 1 ~ 3zf tOZ BA 141 0~ 9eT1E 04 0~ 9>>03E 44 5o5if-04 6 ~ 06'E 10 4o 34C 02 BA 142 5obif 01 5e98E 04 0~ 5 '5E 04 3o 38f 04 0~ 3o 66E-OZ LA 140 2>>16Et00 T>>52E 01 0~ 0~ 0. Z~ 14E+04 0~ 2~ 54f D1 LA 142 2 ~ 74E DZ ie24E>>02 0~ e- 0~ 9 ~ 49E+01 Oo 3~ 106>>43 CE-141 67E+GO 2o34E+04 0~ 3o66E Oi 0. Zo 93E+03 3o48E 01 Cc 143 z. 05E-01 fo52E+02 0~ 6o69E OZ 0~ 5 '7E+03 io 68E-OZ CE 144 Z. 66E tOZ be33Et01 0~ 1 ~ 50E+Oi 0~ 2e 16f +04 fe4zftbf PR>>144 6o46E 03 Ze 67E>>43 0~ 1 ~ Sif 03 9 ~ Z6E 10 3 ~ Zl f 04 N>> 187 3 '3E+DO 2>>54Ftoo 0~ 0~ 0~ 8 ~ 31f+02 bo90f-41 HP 239 1~ ibf 02 f 1 o 6E>>03 0~ 3 '8E 03 0. Z ~ 36'6 + 02 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 CALCULATIONMANUAL ODCM TABLE G-7 ENVIRONMENTALPATHWAY~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 THYROID KIDNEY LUNG Gl-LLI WHOLE BODY SN-126 2.10E+08 4.17E+06 0. 1.40E+08 6.30E+06 SB-124 390E~ 7.9?E~ 0. 256 E+06 9.33E+07 SB-125 4.31 &06 3.92E+05 4.76E+05 3AOE+08 2.92E+07 ?.94E+05 TE-125M 1.89E+07 6ME+06 621 E+QB 8ABE+06 0. 9.09E+06 2.52E+06 TE-127M 6.64E+06 231 E+06 2.15E+OB 2AOE+07 0. 3.88E+07 8.85E+05 TE-129M 7.05E+07, 2.42E+07 2.66E+07 323E+07 0. 425 E+Q7 1.0?E+07 I-130 . 5A5EAS 1.61E+06 2.05E+08 K51E+06 0. 1.38E+08 6.35E+05 I-131 3.11E+09 3.70E+09 1.19E+12 0. 1.39EAN 2.17E+09 I-132'.13E%1- 5.71E%1 7$ 1E+01 9.10E%1 0. 1.0?E<1 2.03E-01 I-133 450E~ 6$ 7E+07 1$ 5E+10 1$ 5E~ 0. 1.17E+07 1.99E+07
0. 0. 0. 0. 0.
I-135 4.72E+04 6.1 BE+06 7$ 1E~ 2.42E<1 5ME+04 1.?3E+04 CS-134 1.33E+11 239E+11 0. 1ME+10 2.74E+10 5.69E+08 2.02E+10 CS-136 894E~ 32SE+09 0. 1.83E+09 &51 E+08 3.74E+08 2.3?E+09 CS-137 1.93E+11 2.1 BE+11 0. 1.10E+10 2.61E+10 589 E+08 1.24E+10 BA-140 2.95E+07 2.96E+04 0. 1.47E+03 181 E+04 9.76E+05 1.52E+06 CE-141 3.17E+Q4 1.95E+04 0. 1.1?E+03 0. 2.28E+03 CE-144 2$ 2E+06 9.95E+05 0. 0. 1.36E+05 I
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)
>>\>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>><<>>>>>>>>>>>>>>>><<>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>
BGHE LIVER THYRCIO KIOHEY LUNG GI LLI
~~R wing~ gpgg
>>>>>>3 De 7 51E+DZ 7 51E+02 4 96EtDZ 7 51E+OZ l 51E+02 0 7~ 51EtOZ P 32 "
6<< 11Et 05 3<<57E+04 0. 0~ 0~ CeDDE+04 Ze 3ZEt 04 CR 51 DE Do 2<<75E t01 1 ~ 06E+01 6<<66E+03 1 ~ 5CE+03 4 '3Et41 HN>> 54 0~ ieb3E+04 D~ Ce55E+03 6<<40E+DS 3<<50E+04 2<<91Et03 FE 59 5 'CEt03 i<<ZDE+D7 D~ 0~ 4<<70E+05 0 elOE+04 4 ~ bbit03 CO>>>>57 DE 3<<20E+D2 Do 0~ 1 ~ 71Et 05 1.45Eta4 3<< 10E t02 CO 50 0~ 1<<52E+02 0~ 0~ 1<<13E+46 3 '2E+44 2 '4EtOZ CO 60 Do 1.07E+03 0~ D~ 6>>92E+06 9 '6E+OC 1 'dft03 ttf ZN 65
' 50E+04 Ce77E+DC Do 3>>19E+04 C<<03E+05 2eC7E+04 Z<<15EtDC 0 RB<<06 Do 6<<25i+04 0~ D~ 0~ 7.70E+03 2<<73Et04 SR>> d9 . 5<<37E+04,= De 0~ 0~ 2<<24E+06 1 69E+05 1<<54E+03 SR>> 90 ~ 1<<64E+07 ." D~ 0~ 0~ 1<<40E+07 3 CSEt05 9<<99ft05 Y 91 . 7<<44Et04 .: 0~ De 0~ Ze55E+06 1<<ldE+05 1<<9DEt03 ZR 95 1<<41Et04..- 3<< Zb E+ 03 0~ Z>>51E+04 Ze 1ZE+ 06 5<<74Et04 4<< 2 '4Ee03
, HB 95 -:1<<7DE+03 . l<<25E+02 0~ 3<<50E+03 5>> 05E+05 3 ~ 3ZE+DC 0 5<<33EtDZ FU<<103, 2<<16E+02 0~ Do ZolDE+03 6<<33Et05 4 ZZEt44 0 73Et41 RU <<106 1 ~ 15E+04 0~ 0~ 6 ~ idE+DC 1>>45E+Dl 4 '7E+05 1 '4Et03 AGi1 DP' ~ 0 DE+03 4<<63E+03 Do 9<<10E+03 Z<<15E+06 1 ~ CDE+45 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 NUCLIOE ORGAH OOS 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 BONE LIVER THYRCIO XIONEY LUNC OI LLI WACS BOG+
SH 123 3 '5E+04 6o44iP02 6 ~ biE<02 0~ 3eSOE+06 1 ~ 49E405 0~ 1~ 2TE+03 j r SH 126 5 '5E+05 1.55E+OC Ce55E+03 0~ 4o33E+06 5 'dE+bC 2 ~ ZZE<04 SBoize ','B 1 ~ 44E<04 ZorZEt02 3 ~ 49Etai 0~ io 15E+06 1 ~ 88E+05 5.74Et03 125 3o06E+04 3o38Etaz 2o7ZE+01 ao 1.OZE+06 Co66E+04 6o 14E+ 03 TE125H 5o 62E+02 io94Eiaz ie6iE<02 5erCE+03 4ediE+05 3 'bE+04 ro 62Eiai rr ~ ~ TE 127H 5 '5E+03 Zo60Et03 io52E+03 2oizE+04 CoCCE+05 6e92E+04 ro 25EIOZ
=
TE 129H 1 ~ 64E+03 So85fPGZ So40E+OZ ie69E+04 iobOE+06 iod2E+05 Z ~ 60E+OZ I 130 Zo 12E+ 0 3
'. 6ozzEt03 doarE+05 9e66E+03 Oe 3e56E+03 Zo45Eta3 J
I 131 Co55E+0>> -
Co63E+04 1 ~ 54E>07 2ebCE+04 0~ Ze6SE+03 3o50E+04
.~ ~ 132 5o37E+02 51E~03 Ze 03i >05 2o48E+03 Oo iodbE+OZ 5 '7E+02 I 133 . io68E+04 2o05E+04 5o03E+06 io20E+OC 0~ 5o55E+03 boa3E+03
'= I I 134 Zo98E+02 lo99E+02 io06E>>05 iozlc+03 bo Ce66f 01 2obSE>02 rjj 135 ioZ4E+03 3e23E103 4e33E+05 5oiCE+03 8~ Ze43E+03 io 19E > 03 CS o134. 6o22E+05 :. " 9.95E+05 a. io33E>>05 ie19E+05 3orrE+03 2o 23E+05
~
CS 136 1odic+04 6.77&04 0~ 3o96E+84 So55E+83 5eCOE+03 ao So 14E+04 CS 137-'- bo66E+05 le99ct05 0 ~ io03E+05 iodaE+85 3e41E+03 25E+05 II tj j .': ~
BA 140 7 o 14E>>03 "Co66E+00 0 ~ 7073E+00 ielCE+06 9e92E+03 0 C.ZZEt 02 CE-141 3e 13E+03 1o57E+03 0 ~ Zo98E+03 5oiCE+85 5oCCE+04 0 Zo33E~CZ CE 144 ~ 5 ~ 81E+05 iebZEta5 8 ~ 3o9ZE+05 ie23E+Ol aaE+aS 3olOEI04
~
j~~
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
" HUCLIOE 0 R 6 A N 0 0 S E F A C T 0 R S lSO HETER tlREH/YR PER UCI/SEC) aaa>>aaaaaaaaaaaaaaaaaaa>>aa SORE LIVER THYROI 0 KIDNEY LUHG GI LLI 4 HO+ S<Oy
~~rHa>>a>>3 P 32 0~
1>> b2E+10 1>>57E+03 io 14E+09 1 ~ 5?6 0~
103 1 ~ 04E+03 0~
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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) 80NE LIVER THYROID KIDNEY LUNG GI LLI SK'IN COFA~OOY wHoM 5oOg SN 123 SH 126 S8 1Z4 0~
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EHVIROHHEHTAL FATHMAYoOOSE CONVERSION FACTORS fc(I) FOR GASEOUS OISCHARGES PATHHAY INHALATION AGE GROUP - AOULT HUCLIOE 0 R G A H 0 0 S E F A C T 0 R S (HREH/YR PER UCI/Cvo METER) r.
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~~a P>>>> 32 De 1.04E+09 6e5ic+07 0~ Oe Oe 1 ilE+08 Do
~
~o DZE+DZ 4 'Zc+07 CR>>-51 Go 0~ ie15E+04 4e25E+03 2>>56f+04 4eb5E+06 a. 1~ 93E+04 HH>> 54 Do 4e blE+Ol 0~ ie45E+07 0~ 1>>49E+ab 0 9o31E+06 FE 59 3 '4E+07 bo64E+07 0 ~ 0~ 2>>40E+07 2 '5E+Od 3o29f+07 CO 57 0~ 1 '5E+06 0~ 0~ 0~ 4elaE+07 0~ 3oadEoDS CO 58 Do 6o89EtD6 0~ 0~ 0~ 1 ~ 4DE+Db Oe 1 ~ 54E+07 CO 60 Do Ze386+Ol 0~ 0~ De 4>>46E+Db 0 ~ 5e 23f+ Dl ZN 65 5e iiE+07 ioSZE+08 a. 1 09E+08 0~ 1 ~ 02E+Db De le 34E+Dl RO 86 0~ ie30E+08 Oe 0~ 0~ 2 '6Et07 Oe 6 ~ DSE+07 SR>>-89 2e 67E+09 De. 0~ 0~ de 4>>26E+48 a lo64Eoal SR -90 8 '9E+ia ae 0~ 0~ 0~ 2>> 14E+49 Zo 07E+10
'Y>>>>>> 9 1 ie26E+DS De 0~ 0~ a. 6 '2E+Ob ae 3o 37Et 04 ZR 95 2>>93E+G5 9od2E+04 0~ 1>>49E+05 0~ 3 '4E+Od 0~ 6 '8E+04 H8>>-95 4 87Et04 2eliE+ 04 0~ Z>>68E+04 0~ 1>>64E+Db ioa6E+04 RU>>103 ie 50E406 0~ 0~ 5e75E+06 0~ 1 ~ 76E+ab 0 ~ So49E+05 f U>>106 2e95E+07 0~ 0~ 5eliE+07 0~ 1>>91E+09 D 3 '4E+06 AG11IPf ie 69E<GS ie56E+06 0~ 3eabE+GS 0~ 6e38E+Dd 9o 30E+05 t
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 Retest HUCLIOE ORGAH DOSE FACTORS lSOHETERHREH/YR PER U CI/SEC) aaaaaaaaaaaaaaaaaaaa a \ a aaaa'a '>>aa 9OOr BDHE LIVER THYROID KIDHEY LUHG GI LLI wB~ P~oy SH 123 1 ~ OOE.05 1.66Ea07 1>>416 47 0~ 0 ~ 2 ~ 04E 05 2>> 45Ea Ol SH 126 . 9>>526+08 1>>89E+07 5 '4E+06 0~ 31E+06 8>>46E+48 2 ~ 94E+ 07 SBaiZ4 2,5ZE+07 4>>75E+05 6 'dE+04 0~ 1>>95E+Ol lei2E+08 0 9>>94E+ 06 t *>> SBa125 2'>>58E>07 l>>23E<05 4>>03E+05 5>> 14E+06 2>>56E+09 2>>2ZE+48 0. 5 ~ iOE+06 TE 125H 2>>38E+07 '>>65E>06 l>>17E+06 9>>69E+07 Oo 9>>51E+07 0 3>>19E<06 TE 127K 6>>75E+07 .2>>36E+07 1 ~ 77E407 2>>73E+08 I~ 3>>06E+88 8 ~ 3ZE+06 Ti 129K S 93E+07 3>> 34E+ 07 3.0SE+07 3el3E+Ob 0~ 4>>49E+08 0~ 1 ~ 42Et Ol I 130 3 '3E<05 1>>16E>06 1>>4CE+08 1>>81E+06 Oo 9>>98E+05 0~ 4>> 5SEt05 Ia"131 ~
7>>78E+07 1>>12E>08 3 6>E<10 1>>91E+08 0. Z ~ 94E+47 6e3SEo07
'II 132 5>>57E+01 - 1>>49E+42 1>>96E+04 2>>38E+02 0~ Zedoi+41 5 ~ 29E+ 01 a133 2>> 13E+06 3>>69E>06 7>>10E>08 6>>44E<06 Ie 3e 24E+86 1~ 13E>06 Il
~
I 134 1 ~ 03Ea04 Ze79E 04 3>>63E OZ 4>>45E 04 Oo 2>>43E 9>>99E 05 I a135 ~ . 4 '4E+04
"'. 1 ~ 07 E+05 1>>40E+Ol 1>>70E>05 8>>65E 03 1>>19E+45 0~
CSa134 6 '2E+08 1>>62E+09 0~ 5>>26E+08 1>>74E+08 2>> 84Eo Ol Oo 1 ~ 33E+ 09 CS 136 3>>32E+07 1 31E+08 8>> 7>>29E<07 9>>99E+06 1>>49E+Il Oo 9 43Eo07 CS >>137 8>>90E+OS 1 ~ 22&09 0~ 4>>146+08 iedlE+Od 2>>34E+Il 7>> 9SE+08 BA 140 1>>03E+08 1>>35B05 0~ 4>>39E+04 7>>38E+04 6>>65E+08 0. 6>>77E+06 CEa141 l>>16E+44 4>> 85E+04 Oo 2>>25E+04 0~ 1.85E+08 0 5>>49Eo03 Ci 144 5 '9E+06 Z>>17E+06 Oo 1 ~ 29E>06 I 1 e75E+09 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 LIMITING LIM ING SECTOR (DIG)
CALCULATION RANGE (miles) (OL) 1/m'2X10 Instantaneous 0.97 WNW AoHQ 0.97 Annual Runny 0.97 1i31 days,. ~ B 0.97 Qtr. yearly, ;.; 14X10 Annual Total Dose 0.97 .. WNW,,'. 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 CALCULATIONMANUAL 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 CALCULATIONMANUAL 0 M TABLE B-1 ADULT HOLE BODY DOSE CONTRIBUTIONS F CTION OF TOTAL 1978 1979 RAOIONUCLIDE SHELLFISH FISH SHE ISH FISH SHELLFISH 0.08 027 0.08 048 0.02 0.05 0.19 0.03 0.15 0.44 Fe-59 0.10 025 0.04 0.13 0.15 0.22 0.01 0.10 0.02 0.19 0.04 0.20 Gs-134 0.31 0.07 048 0.14 027 0,04 Cs-137 0.42 ,10 0 0,11 0.30 0.04 TOTAL 0,97 0, 0 1.00 0,9& 0.99 TABLE 2 B
l
~ > ~ i 'a l, q ~ ~
~ E\
RADIONUCUDE FISH =, SHELLFISH FISH ELLFIS FISH ~
SHELLFISH 0.03 OM 026 044 0.01 0.07
0. OM 0.12 0,05 047 Fe+9 0. 0.31 0.18 19 0.04 OM 0.02 0.01 0. 0.01 0.04 0.01 041 0,0 0.88 0.01 TOTAL 0.98 0.92 0.76 0.90 0.97 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 CALCULATIONMANUAL 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:
X (C-1)
K,>> ] Kr f, 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)
Z (C-2)
(L + 1.1 M)~ ~
( (L(+ .1 M) f, 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 Z (G4)
M~ ] M,~f, 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~ ~ X.
] Nj ~ f( (~)
Where:
Neff e effectiv air dose factor due to beta lssions from II noble gases released the air dose factor, due to beta emlsslons each noble gas radlonucllde I
Page 183 of 194 ST. LUCIE PLANT CHEMIS Y OPERATING PROCEDURE NO. C-200, REYISION 9 0 SITE DOSE CALCULATIONMANUAL 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 t
exceed 50% of the des n bases doses (l.e., greater than mrads gamma air dose or 10 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
\ rr
~ r ~ r
Pag 184 of 194 ST. LUCIE PLANT CHE TRY OPERATING PROCEDURE NO. C-200, REVIS N 19 FFSITE'DOSE CALCULATIONMANUAL ODCM I
TABLE C-I EFFECTlYE DOSE FACTORS NOBL GASES-TOTAL BODY AND SKIN OSES TO L BODY EFFECTIVE S EFFECTIVE OSE FAGTOR OSE FACTOR YEAR (L+1.1M),
rem-m'i- mrem-m'i-r r 1978 7, X1 1.4 X 1 1979 7A 1 1.4 X 1 1980 5.6 X 1.2X 1 AVERA E 6.8 X1 1.3 X 1 TABLE C-2 BLE GASES -'AIR D SES 8AM AIR EFFECTIVE ETA AIR EFFECTIVE SE FACTOR DOSE FACTOR YEAR M~ N~
'B&QL mrmBa'I-
'i<<r 1978 8.0X1 1.2 X 1 1979 8.0X1 2X1 1980 6.2X1 1. X1 AVERAG 7.4X1 1.2 1
0
e. twas r ~
Page 185 of 194 ST. LUCIE PLANT HEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 1 OFFSITE DOSE CALCULATIONMAN AL M APPENDIX D TEC ICAL BASES FOR ELIMINATINGCURIE 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 t
established to assure at In the event of a tank failure rele ing the radloactMty to the 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 REG. GUIDE 1.109 Xe-133 REACTOR OO LANT'ONC TOTAL BODY DF RATI EFFECTIVE TION ~mret~ CONCENTRATION RADIONUCLIDE (gCVgm (pGVml) X 33DF (pCVgm)
Kr45m 0,19 12X10 4.1 0.78 0,83 1.6 X 10 0.06 0.05 Kr<? 0.18 5.9 X1 0,31 1'1 16.
Xe-131m 8.8 QZ 1 0.32 2.8 Xe-133m 2.5 X 10 0.86 0.17 Xe-133 .Q 1 1.0 12.
Xe-135m 0.11 Xe-135 10 7.4 Xe-137 0,02 1. 1 4.8 0.1 0;12 3.6 T TAL 24. 47.
~ 'Data adapted trom the NRG GALE a ~
1<<
g <<
+%*AD t ps<<p q<<' ~
Page 187 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODGM APPEND RADIOLOGICALENVIRONMENT L SURVEILLANCE ST. LUCIE PLANT Key to SamPIe LocatIoos SAMPLE APPROXIMATE
" PATHWAY DESCRIPTION SAMPLES COLLECTED COLLECTION DISTANCE DIRECTION SECTOR FREQUENCY (miles)
DfrectRadlatfon . = N-1" Northof BffndCreek
Direct Radiation NNWN. South ot Pete Stone Creek NNW Dhect Radfa5an . NNW-10 " C. G. Station Dhect Radiation ~ NW-10 . Intersectke ol SR 68 and SR 607- . 10
, Direct Radfatfon, WNW-2.: Cemeteqr South of 7107 frxSan River Drfve DhectRadfatke -: WNWN: USr1atSR712 .. - -.
WNW
. Dfrect Radfalkl- WNW-10 SR 70, West of Tumplke 10 Dhect Radiation, - W-2,. 7609 lnrNan River Drive .
Dhect Radfalkl . W+ Oleander and Sager Streets Dfrect Rarlatkrn . W-10 M5 and SR 709 W
. Dhect Ra@ation . WSW-2 8503 hxian River Drive WSW DfrectRadfatfon .WSWW PrfmaVfstaSIvd.atYachtQub WSW Dfrect Radiation ~ WSW-10 Del Rfo and Davis Streets 10 WSW Direct Radiation SW-2 9207 indian River Drive SW Direct Radhrtfon SWW US 1 and Viage Green Drive SW Direct Radfaffon =
SW-10 Port SL Lucfe Sfvd. and Caha P~ 10 SW DfrectRadfa5on SSW-2 10307INianRIverDrfve SSW
Page 188 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFF ITE SE AL LATlON MANUAL ODCM APPEN RADIOLOGICALENVlRONIIENY SURVEILLANCE (conttnued)
"- ST. LUCIE PLANT Key to SampIe LocatIoos APPROXIMATE
' PATHWAY;;,* LOCATION DESCRIPTION SJVAPLES COLLECTION DISTANCE DIRER N FREQUENCY (mlles)
Sf CTOR Dhect Radiation - SSW4: ' Port St. Luckr Svd. and US 1 SSW Pine Yaiey and Westrnoreland Roads
~
~,
. DIrect Rariatlon SSW-10
~5
~ > s ~
- Dkect Rarlatlon ":;:$5 ~
13178 le%an River Drfve,- S
.'kect Rarlatlcn ::":.S.10 ~. '-. US1 and SR 754 50 S
-'SSSE-50: hxRan River Drive and Qual Run Lane 50 5 ~ '.. SS&5...-. Entrance of NeNes hrhrnd . - - "--
Dhect RaNation .: SSE-10". Eiot Muserin'" *'- - -. 50
Direct Radiation South of GooNng Canal SE U. of Florida -1FAS Entomology Lab Yero
'irect Radlaticn .; %42 Beach Redlolodlne 8 Ahbome- '. H08 FPL Substatlon - Weatherby Road Particulates Radlolodlne 8 AIrbome, FPL Substatlon - SR 76, Stuart Partlcutates Ahbome Onslte - near south property line Ahbome Power une - 7609 Indhrn RIver Drive
'Denotes Control SampIe
I Page 189 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX~
RADIOLOGICALENVIRONIJIENT SURVEILLANCE (aetlnued)
ST. LUCIE PUBS Key to Sample Locations SAMPLES APPROX'T DIRECTION
'ATHWAY LOCATION DESCRIPTION E DISTANCE sE~TOR COLLECTED r (mmes)
AIrbome, H34;; Onstta '-'.
At Meteorofoglcat Tower 0.5 P
~,
Surface Water AttantIc Ocean vtcInIty of pubIIc beaches east sR5e (ocean)
.Waterborne H15 ENE/E/ESE Waterborne of Route A1A- Sedfment from shoreine Surface Water
.'H59 (ocean)
Near south end of Hutchlnson Ishnd S/SSE SedIment fmm stroreIIne Food products H15 Ocean sate vtcIntty of SL LucIe Rant (NOTE 1) Crustacea Rsh ENE/E/ESE (mangrove)
Denotes control sampIe
Page 190 of 194 ST. LUClE PLANT CHEMlSTRY OPERATlNG PROCEDURE NO. C-200, REVlSION 19 OFFSlTE DOSE CALCULATlONMANUAL ODCM
, APPENDIX~+
RADfOLOGlCALENVNONNENTALStJRVHLLANGE (continued)
ST. LUCfE PLANT Key to Sample Locations SAMPlE APPROXIMAT SAMPlES DIRECTION PATHWAY. LOCATION COLLECTION E DISTANCE COLLBCTED SECTOR 0 ~
FREQUENCY (mIIes)
Broad ket Monthly Food Products H52 vegetatIon 8/SSE (when avaIIable)
~
(mangrove)
Crustacea FIsh See%-Annually
\
Broad leaf Near south end d HutchInson island veg@atlon Monthly
'sC-20 4
(mangrove)
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:
2.032 EQ (1}
(u)o (g2 + cV't
)
2o032 g/Q EQ (2}
z (u)D Where:
~ c =.5
~ 207.5 ft. (63,2 meters)
(u) 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.
N l
~ ~
~ 5 ~
-.Terrain correction factors given by Table MA were also applied to Dispersion Formulas n
\I I~
1
~ ~ ~ ~ 'L ~
1 h
0
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.ABORATORYCOMPARISON 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 FPL personnel, but shall not radioactivity.
~
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 the participant(s) form aaVor license quantitics for allowed
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. REV.
ADDENDUM SHEET 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 be'eplaced with legible, reproducible prints
'ust I
Proofread by: 'ept. I Date~~~
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 Page 2 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX PAGE INTRODUCTION                                                                                                 .... 7 CONTROLS SECTION DEFINITIONS FOR CONTROLS SECTION                                                                          ... 9 1.1    ACTION                                                                                               .. 9 1.4    CHANNEL CALIBRATION                .... .,....                                                         . 9
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 .5    CHANNEL CHECK                                      ~ ..                                            ... 9 1.6    CHANNEL FUNCTIONAL TEST                    ~....     ~ .                                           ~ ~ ~  9 1.10 DOSE EQUIVALENT 1-131                                                                                .. 10 1.13 FREQUENCY NOTATION                   ...........                                                     ~ 0   10 1.17 MEMBER(S) OF THE PUBLIC........                                                                            10 1.18 OFFSITE DOSE CALCULATIONMANUAL                                                                             10
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 .19 OPERABLE - OPERABILITY                                                                               ~ ~   11 1.20 OPERATIONAL MODE - MODE.......
 .24 PURGE - PURGING                                                                                      ~ ~   11 1.25 RATED THERMAL POWER..........                                                                              11 1.27 REPORTABLE EVENT                                                                                     ~ ~   11 1.30 SITE BOUNDARY.................                                                                             12 1.31 SOURCE CHECK             ~...............                ~                                           ~ ~   12 1.33 THERMAL       POWER................                                                                        12 1.34 UNPLANNED RELEASE                  ......      ~ . ~...                                              ~ ~   12 1.35   UNRESTRICTED         AREA                                                                          ~ ~   13 1.39 VENTILATIONEXHAUST TREATMENT SYSTEM                                                                        13
-                      ....................,
                                                                                                               ~ ~
 .40 VENTING                                                ..                                                  14 1.41 WASTE GAS HOLDUP SYSTEM .. ~...                                                                            14 3/4    CONTROLS AND SURVEILLANCE REQUIREMENTS                                     ~.........                    16 3/4.0 APPLICABILITY                                                                                             16 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION                                                    ~ ~   17 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION                                                   ~ ~   22 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1     LIQUID EFFLUENTS CONCENTRATION                                                                                ~ ~   32
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 Page 3 of 225 ST. LUCIE PLANT CHEMISTRY            OPERATING   PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATION MANUAL ODCM INDEX CONTROLS SECTION PAGE CONTROL AND SURVEILLANCE STATEMENTS FOR CONTROL SECTION-3/4.11    RADIOACTIVE EFFLUENTS (Continued) 3/4.11.2    GASEOUS EFFLUENTS DOSE RATE            ..............                                        .. 38 DOSE - NOBLE           GAS........                                         .. 42 DOSE - IODINE-131, IODINE-133, TRITIUMS AND RADIONUCLIDES IN PARTICULATE FORM                                  ..... 43 GASEOUS RADWASTE TREATMENT                ..........     ~....       ~ ~ ~     44 3/4.11.3    (NOT USED) 3/4.11.4    TOTAL DOSE            ..... ~........                              ......      46 3/4.11.5    MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS (ADMINISTRATIVECONTROL)                                            ......      48 3/4.11.6    ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION (ADMINISTRATIVECONTROL)                          ~ ~ ~ ~ ~ ~ 49 3/4.12      RADIOLOGICALENVIRONMENTALMONITORING 3/4.12.1    MONITORING PROGRAM                ......                                   .. 52 3/4.12.2    LAND USE CENSUS              ..........                                    .. 61 3/4.12.3    INTERLABORATORYCOMPARISON PROGRAM                    .......               .. 63 3/4.12.4    ANNUALRADIOLOGICALENVIRONMENTS,L OPERATING REPORT (ADMINISTRATIVECONTROL)              ............. .....                64 BASES for CONTROLS SECTION 3/4.11      RADIOACTIVE EFFLUENTS 3.3.3.9     INSTRUMENTATION              ....... ..                                        66
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 /4.1 1.1   LIQUID EFFLUENTS                                     ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 67 3/4.11.2    GASEOUS EFFLUENTS                                      ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   69 3/4.11.3    (NOT 72 USED)'OTAL 3/4.11.4                    DOSE                                 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
 /4.12      RADIOACTIVE ENVIRONMENTALMONITORING 3/4.12.1    MONITORING PROGRAM                .......                      ........        74 3/4.12.2    LAND USE CENSUS . .              ~.......                                      74
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 /4.12.3.-  INTERLABORATORYCOMPARISON PROGRAM .....                        ~               75
 Page 4 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM INDEX CONTROLS SECTION PAGE LIST OF FIGURES for CONTROLS SECTION FIGURE 1-1      SITE AREA MAP & ENVIRONMENTALSAMPLE LOCATIONS             ....      221 1-2      ENVIRONMENTALSAMPLE LOCATIONS (10 MILES)      ~........,            222 LIST OF TABLES for CONTROLS SECTION TABLE 1-1      FREQUENCY NOTATION                        ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~  1 5 3.3-12   RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION   ..............                      ~ ~ ~ ~ ~ ~ ~  1 8 3.3-13   RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION   .............  ~ .                            ..
-                                                                            ..
 27 3.3-14   RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS 3.12 1   RADIOLOGICALENVIRONMENTALMONITORING PROGRAM...                  .. 54 3.12-2   REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTALSAMPLES                                         .. 57 4.3-8    RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQOIREMENTS                       .. 20 4.3-9    RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS                       .. 29 4.11-1   RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM..........                      ~ ~ ~ ~ ~ ~ ~ ~  33 4.11-2   RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSiS PROGRAM..........                                  ~ . 39 4.12-1   DETECTION CAPABILITIES FOR ENVIRONMENTALSAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD) ........      ~ .., ...      58
 Page 5 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM INDEX METHODOLOGY SECTION PAGE Glossary for Methodology Section               ... ~............. ~........                                                  . 77 1.0    LIQUID RELEASES METHODOLOGY                                   .....                                         ..       . 80
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                                                                                                                              ~
 .1    Radioactive Liquid Effluent Model Assumptions                                                                     81 1.2    Determining the Fraction (F) of 10 CFR Part 20 Effluent Concentration Limits (ECL) for a Liquid Release Source                                ........                    82 1.3    Determining Setpoints for Radioactive Liquid Effluent Monitors      ...,................,                                          ~  ~  ~  ~    ~   ~  ~  ~   85 1.4    Determining the Dose for Radioactive Liquid Releases .                               ~  ~   ~  ~    ~   ~ ~  ~    89 1.5    Projecting Dose for Radioactive Liquid Effluents.....                              ~ ~  ~  ~  ~     ~  ~  ~  ~    93 2.0    .Radioactive Releases of Gaseous Effluents                                                                 ....           94 2.1 2.2 Gaseous Effluent Model Assumptions                              ............,                      ....           95 Determining the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing Setpoints for Effluent Monitors..........................                                       ~  ~  ~  ~    ~   ~  ~  ~   96 2.3     Determining the Radioiodine and Particulate Dose Rate to Any Organ From Gaseous Releases                                  ............                        ..       110 2.3.1 Inhalation      .............. ~.............                                                 ~
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 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    (continued) 2.6.4    Meat.....................                                                           129 2.6.5 Vegetation                            ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   ~   ~   ~   ~            1 31 2.6.6 Tritium (All pathways)                                                                 1 33
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                                                            ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   ~   ~   ~   ~   ~   ~
 .6.7 Total Organ Dose                                                                       1 34
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                                                            ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   ~   ~   ~   ~   ~   ~
 .7    Projecting Dose for Radioactive Gaseous 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     ............                                                             152 Appendix B - Current R.E.M. Sample Point Locations      ...........           ~   ~   ~   ~   ~   ~   ~ 217 Appendix C - Description of Meteorological Dispersion Formulas Utilized for Historical Data and IVlethodology for Determining Actual MET Data                                                                        223 Appendix D - Description of the lnterlaboratory Comparison Program            ~   ~   ~   ~   ~   ~   ~ 225
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 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
+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.
-                                                             -
-.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
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 St. Lucie Plant ODCM Controls
-Page 46 of 225 ST. LUCIE PLANT
+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.
-                                                                                      "
-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:
@@ Line 564: / Line 551: @@
                                                                                        ~
 LOWER LIMITOF DETECTION LLD '
-AIRBORNE                                     FOOD WATER      PARTICULATE         FISH        MILK                      SEDIMENT ANALYSIS                                                            PRODUCTS pCi/I     OR GASES        pCi/kg, wet    pci/I                     pCi/kg, dry pCi/kg, wet pCI/m' Gross Beta                   0.01 H-3        3000 Mn-54          15                           130 Fe-59          30                           260 Co-58,                                      130 Co-60 Zn-65          30                           260 Zr-95, Nb-95~'~        15 I-131         1**         0.07                                        60 Cs-134         15          0.05             130         15             60           150 Cs-137         18          0.06             150         18             80           180 Ba-140,                                                  15 La-140~'>       15
+AIRBORNE                                     FOOD WATER      PARTICULATE         FISH        MILK                      SEDIMENT ANALYSIS                                                            PRODUCTS pCi/I     OR GASES        pCi/kg, wet    pci/I                     pCi/kg, dry pCi/kg, wet pCI/m' Gross Beta                   0.01 H-3        3000 Mn-54          15                           130 Fe-59          30                           260 Co-58,                                      130 Co-60 Zn-65          30                           260 Zr-95, Nb-95~'~        15 I-131         1**         0.07                                        60 Cs-134         15          0.05             130         15             60           150 Cs-137         18          0.06             150         18             80           180 Ba-140,                                                  15 La-140~'>       15 No drinking water pathway exists, a value of 2000 pCI/f is for drinking water.
-* 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
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 Page 63 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM RADIOLOGICAL ENVIRONMENTALMONITORING 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.
@@ Line 691: / Line 676: @@
 Ground Plane         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                  Hydrogen-3 or Tritium, a weak Beta emitter I88DP                Radioiodines and particulates with half-lives greater than 8 days Cubic Meters Square Meters m'uclide 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.
-                                                           $
 Organ                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.
 pCi                  1  pico-Curie = 1.E-12 Curies.
@@ Line 755: / Line 739: @@
 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
+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:
-                         ',
-Technical Specifications allow 10 times the ECL limit where the Site Limit is 10 times A~ as follows:
 A~  ~rot"       4.01 E-4 1.18 E-3 0.34 pCi/ml = ECL Limit Mrot 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.
@@ Line 990: / Line 972: @@
 DR~8pp       Z        (D/Q)(Q DOT))
 I For Tritium Releases    Inhalation & Grass-Cow/Goat-Milk:
-DRY       Rp 3 7 (XQ)p (Q DOT)g 3
+DRY       Rp 3 7 (XQ)p (Q DOT)g 3 Normally should be   Pibut    Ri~ values are the same, thus use Ri~ tables in Appendix A.
-* Normally should be   Pibut    Ri~ values are the same, thus use Ri~ tables in Appendix A.
 s   'h
@@ Line 1,083: / Line 1,064: @@
 : 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-             -Milk) from 2.3.4.D DR~.>      = R<       (XQ)p (Q DOT)/f 3
+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-             -Milk) from 2.3.4.D 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.
-                               >
-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.
@@ Line 1,429: / Line 1,408: @@
 Page 151 of 225 ST. LUCIE PLANT OPERATING PROCEDURE NO. C-200, REVISION 20
-                                                                         'HEMISTRY OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER L LIGHT COMPANY ST. LUCIE UNIT  &#xb9; TABLE 3.8 GASEOUS EFFLUENTS DOSE SUMMATION - CALENDAR YEAR
+                                                                         'HEMISTRY OFFSITE DOSE CALCULATION MANUAL ODCM METHODOLOGY SECTION FLORIDA POWER L LIGHT COMPANY ST. LUCIE UNIT  &#xb9; TABLE 3.8 GASEOUS EFFLUENTS DOSE SUMMATION - CALENDAR YEAR AGE GROUP: INFANT              EXPOSURE INTERVAL: FROM                      THROUGH BONE         LIVER      THYROID      KIDNEY           LUNG     Gl-LLI   WHOLE BODY PATHWAY                                                                      (mrem   (mrem)         (mrem)
-                                                      -
-AGE GROUP: INFANT              EXPOSURE INTERVAL: FROM                      THROUGH BONE         LIVER      THYROID      KIDNEY           LUNG     Gl-LLI   WHOLE BODY PATHWAY                                                                      (mrem   (mrem)         (mrem)
 (mrem)       (mrem)       (mrem)      (mrem)
 Ground Plane (A)
@@ Line 1,490: / Line 1,467: @@
 Nuclide       ECL pCi/ml         Nuclide     ECL pCi/ml     Nuclide      ECL pCI/ml Ar-41           1 E-8           Co-57         9 E-10       Sb-124         3 E-10 Kr-83m           5 E-5           Co-58           1 E-9      Sb-125         7 E-10 Kr-85m           1 E-7            Fe-59        5 E-10      Te-125m          1 E-9 Kr-85           7 E-7           Co-60         5 E-11      Te-127m         4 E-10 Kr-87           2 E-8            Zn-65        4 E-10      Te-129m         3 E-10 Kr-88           9 E-9            Rb-86          1 E-9        I-130         3 E-9 Kr-89           None             Rb-88          9 E-8        I-131        2 E-10 Kr-90           None             Sr-89        2 E-10         I-132         2 E-8 Xe-131m           2 E-6            Sr-90        6 E-12         I-133         1 E-9 Xe-133m           6 E-7            Y-91         2 E-10         I-134         6 E-8 Xe-133           5 E-7            Zr-95        4 E-10         I-135         6 E-9 Xe-135m           4 E-8            Nb-95          2 E-9      Cs-134         2 E-10 Xe-135           7 E-8           RU-103        9 E-10       Cs-136         9 E-10 Xe-137           None            Ru-106        2 E-11       Cs-137         2 E-10 Xe-138           2 E-8          Ag-110          1 E-10      Ba-140          2 E-9 H-3            1 E-7           Sn-113        8 E-10        La-140         2 E-9 P-32            1 E-9          In-113m          2 E-7      Ce-141         8 E-10 Cr-51            3 E-8           Sn-123        2 E-10       Ce-144         2 E-11 Mn-54            1 E-9           Sn-126        8 E-11
-of 225
+of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 GASES'age OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 6-2 DOSE FACTORS FOR NOBLE TOTAL BODY               SKIN DOSE FACTOR          GAMMAAIR              BETA AIR DOSE FACTOR                         L,            DOSE FACTOR          DOSE FACTOR RADIONUCLIDE                                                                                          N, K,                                             M, (mrem/yr per pCi/m')          (mrem/yr per pCi/m') (mrad/yr per pCI/m') (mrad/yr per pCi/m')
-                                                                           .
-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 GASES'age OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE 6-2 DOSE FACTORS FOR NOBLE TOTAL BODY               SKIN DOSE FACTOR          GAMMAAIR              BETA AIR DOSE FACTOR                         L,            DOSE FACTOR          DOSE FACTOR RADIONUCLIDE                                                                                          N, K,                                             M, (mrem/yr per pCi/m')          (mrem/yr per pCi/m') (mrad/yr per pCI/m') (mrad/yr per pCi/m')
 Kr-83m              7,56E-02**                                        1.93E+01             2.88E+02 Kr-85m               1.17E+03                    1.46E+03             1.23E+03             1.97E+03 Kr-85               1.61E+01                    1.34E+03             1.72E+01             1.95E+03 Kr-87               5.92E+03                    9.73E+03             6.17E+03             1.03E+04 Kr-88               1.47E+04                    2.37E+03             1.52E+04             2.93E+03 Kr-89               1.66E+04                    1.01E+04             1.73E+04             1.06E+04 Kr-90               1.56E+04                    7.29E+03             1.63E+04             7.83E+03 Xe-131m               9.15E+01                    4.76E+02             1.56E+02             1.11E+03 Xe-133m               2.51E+02                    9.94E+02             3.27E+02             1.48E+03 Xe-133               2.94E+02                    3.06E+02             3.53E+02             1.05E+03 Xe-135m                                           7.11E+02             3.36E+03             7.39E+02 3.12E+03'.81E+03 Xe-135                                           1.86E+03             1.92E+03             2.46E+03
      ~   Xe-137               1.42E 3                     1.22E+04             1.51E+03              1.27E+04 Xe-138               8.83E+ 3                    4.13E+03             9.21E+03             4.75E+03 Ar-41               8.84E+03                    2.69E+03             9.30E+03             3.28E+03
@@ Line 1,503: / Line 1,478: @@
 Page 170 of 225 ST. LUCIE PLANT.
-CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-3 ENVIRONMENTAL       PATHWAY-DOSE       CONVERSION       FACTORS P I FOR GASEOUS DISCHARGES
+CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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)
-                             -
-PATHWAY GROUND PLANE DEPOSITION                        AGE GROUP - INFANT ORGAN DOSE FACTOR             (SQ. METER - MREM/YR PER pCI/Sec)
 NUCLIDE         WHOLE BODY SN-126        4.80E+09 SB-124        8.42E+08 SB-125        7.56E+08 TE-125M        2.1 9E+06 TE-127M      -
 .15E+06 TE-129M        5.49E+07 I-130        7.90E+06 I-131        2.46E+07 1-132        1.78E+06 l-133        3.54E+06 I-134        6.43E+05 l-135        3.66E+06 CS-134        2.82E+09 CS-136        2.13E+08 CS-137        1.15E+09 BA-140        2.39E+08 CE-141        1.95E+07 CE-144        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
@@ Line 1,531: / Line 1,504: @@
 : 0.             0.               0.             3.46E+07         2.27E+06 6.24E+07 CO-58     0.               2.55E+07        0.             0.               0.             6.60E+07 CO-60     0.               8.73E+07        0.             0.                              2.16E+08         2.09E+08 4.65E+09        0.             3.11E+09         0.             2.93E+09         2.'I OE+09 ZN-65     1.46E+09 RB-86    0.               2.77E+09        0.             0.               0.             5.45E+08         1.29E+09 SR-89     I:47E+1 0       0.              0.             0.               0.             2.75E+08         4.22E+08 SR-90     1.65E+11        0.              0.              0.              0.              1.61E+09        4.21E+10 Y-91    8.12E+04         0.                              0.                             5.37E+06         2.16E+03 ZR-95     2.12E+05        9.41E+04        0.              1.86E+04        0.             7.47E+07         5.56E+04 NB-95     5.49E+05        2.4 E+05        0.              4.84E+04        0.              1.98E+08         1.45E+05 RU-103     8.30E+03        0.              0.              4.16E+03        0.              1.04E+05        2.86E+03 RU-106     2.01E+05        0.              0.              4.20E+04        0.              1.56E+06        2.46E+04 AG-'I 10   6.21E+07        5.75E+07        0.              1.13E+08        0.              2.35E+10        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)
-                                                                                                      - Page 176 of 225
+                                                                                                      - Page 176 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-5 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE)                           AGE GROUP - INFANT ORGAN DOSE FACTOR             (SQ. METER - MREM/YR PER pCi/Sec)
-                                                                    .
-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-5 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R I /P I FOR GASEOUS DISCHARGES PATHWAY - COWS MILK(CONTAMINATEDFORAGE)                           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         3.48E+07        1.01E+07       0.               4.97E+06        1.16E+09        5.25E+07 SB-124    2.75E+07         5.19E+05       6.64E+04        0.               2.13E+87       7.78E+08         1.09E+07 SB-125    3.59E+07         3.27E+06       2.93E+06        3.96E+06         2.83E+09       2.43E+08         6.62E+06 TE-125M    1.57E+08         5.30E+07       5.18E+07        7.05E+07         0.             7.57E+07         2.10E+07 TE-127M    5.54E+07         1.93E+07        1.79E+07       2.00E+08         0.             3.24E+08         7.38E+06 TE-129M    5.87E+08         2.02E+08       2.21E+08        2.70E+08         0.             3.54E+08         8.95E+07 I-130    4.54E+05         1.35E+06        1.71E+08       2.09E+06         0.              1.15E+06        5.29E+05 I-131    2.59E+09         3.09E+09       9.94E+11        7.24E+08         0.              1.16E+08        1.81E+09 1-132    1.78E-01         4.76E-01       6.26E+01        7.58E-01         0.             8.93E-02         1.69E-01 1-133    3.75E+07         5.48E+07        1.30E+10       1.29E+07         0.             9.74E+06         1.66E+07 I-134    0.               0.              1.06E-09       0.               0.              0.              0.
 I-135    1.49E+04         3.94E+04,      5.15E+06        6.26E+04         8.07E-02       4.41E+04         1.44E+04 CS-134    4.43E+1 0        7.97E+10       0.              4.65E+09         9.12E+09        1.90E+08        6.75E+09 CS-136    2.78E+08         1.10E+09       0.              6.11E+08         8.37E+07        1.25E+08        7.90E+08 CS-137    6.44E+10         7. E+10         0.             3.66E+09         8.69E+09        1.86E+08        4.14E+09 BA-140    2.45E+08         2.47E+05        0.             1.22E+04         1.51E+05        8.13E+06        1.27E+07 CE-141    2.65E+05         1.62E+05        0.             9.72E+03         0.              7.87E+07        1.90E+04 CE-144    2.10E+07         8.29E+06        0.             5.67E+05         0.              8.66E+08        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.
@@ Line 1,554: / Line 1,525: @@
 .55E+06      1.78E+05         1.98E+03 ZR-95       1.41E+04        3.28E+03                         2.51E+04          2.12E+06      5.74E+04         2.98E+03 NB-95       1.70E+03          .25E+02        0.              3.58E+03          5.85E+05      3.32E+04         5.33E+02 RU-103      2.16E+02        0.               0.              2.70E+03          6.33E+05      4.22E+04         8.73E+01 RU-106      1.15E+04        0.               0.              6.18E+04          1.45E+07      4.37E+05         1.44E+03 AG110       5.00E+03        4.63E+03         0.              9.10E+03          2.15E+06      1.40E+05         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
-Page 180 of 225
+Page 180 of 225 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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)
-                                                                   .
-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 20 OFFSITE DOSE CALCULATIONMANUAL ODCM 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          BONE             LIVER          THYROID         KIDNEY            LUNG           Gl-LLI        WHOLE BODY SN-123      3.85E+04        6.44E+02         6.81E+02       0.               3.50E+06        1.49E+05        1.27E+03 SN-126      5.85E+05        1.55E+04         4.55E+03       0.               4.33E+06       5.88E+04         2.22E+04 SB-124      1.44E+04        2.72E+02         3.49E+01       0.                1.15E+06       1.88E+05        5.74E+03 SB-125      3.06E+04        3.30E+02         2.72E+01       0.                1.02E+06      4.66E+04         6.14E+03 TE 125M      5.62E+02        1.94E+02         1.61E+02       5.74E+03         4.81E+05       3.38E+04         7.62E+01 TE 127M      5.85E+03        2.60E+03         1.52E+03       2.12E+04         4.44E+05       6.92E+04         7.25E+02 TE 129M      1.64E+03        5.85E+02         5.40E+02        1.69E+04         1.80E+06       1.82E+05         2.60E+02 I-130      2.12E+03        6.22E+03         8.07E+05        9.66E+03         0.             3.56E+03         2.45E+03 I-131      4.55E+04        4.63E+04         1.54E+07       2.84E+04          0.             2.65E+03         3.50E+04 I-132      5.37E+02         1.51E+03        2.03E+05        2.40E+03                        1.88E+02         5.37E+02 1-133      1.68E+04        2.05E+04         5.03E+06        1.20E+04         0.             5.55E+03         8.03Es 03 1-134      2.98E+02        7.99E+02,        1.06E+05        1.27E+03         0.             4.66E-01         2.85E+02 1-135      1.24E+03        3.23E+03         4.33E+05        5.14E+03         0.             2.43E+03         1.19E+03 CS-134      6.22E+05        9.95E+05         0.              1.33E+05         1.19E+05       3.77E+03         2.23E+05 CS-136      1.81E+04          .77E+04        0.              3.96E+04         5.55E+03       5.40E+03         5.14E+04 CS-137      8.66E+05        7.99E+05         0.              1.03E+05         1.00E+05       3.41E+03         1.25E+05 BA-140      7.14E+03        4.66E+00         0.              7.73E+00         1.74E+06       9.92E%03         4.22E+02 CE-141      3.13E+03         1.57E+03        0.              2.90E+03         5.14E+05       5.44E+04         2.33E+02 CE-144      5.81E+05         1.82E+05        0.              3.92E+05         1.23E+07       4.00E+05         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
@@ Line 1,748: / Line 1,717: @@
 Ir
                                                                     ~
-                                                                     '
                                                                       ~ ~
 I ~
@@ Line 1,767: / Line 1,735: @@
 I   ~
                                                                                                                                                        ~ ~   I ~                ~
-                                                                                                                                                                                  '
 I~                ~  ~ ~  I~                                                                                                    ~ ~
 I~                         I~
@@ Line 1,813: / Line 1,780: @@
 NUCLIDE           BONE             LIVER          THYROID         KIDNEY             LUNG          Gl-LLI        WHOLE BODY SN-123       9.25E-06         1.53E-07        1.22E-07        0.                0.            1.33E-05        2.28E-07 SN-126       6.25E+08         1.24E+07        3.64E+06        0.                2.83E+06      5.55E+08         1.94E+07 SB-124       1.65E+07        3.12E+05         3.99E+04        0.                1.28E+07      4.67E+08         6.53E+06 SB-125       1.73E+07        5.97E+05         3.48E+05        3.38E+06          1.68E+09      1.45E+08         3.40E+06 TE 125M       2.23E+07        7.99E+06         6.30E+06        6.36E+07          0.            6.24E+07         2.96E+06 TE 127M       4 46E+07         1.55E+07        1.18E+07        1.80E+08          0.            2.23E+08         5.51E+06 TE 129M       8.46E+07        3.14E+07         2.71E+07        2.45E+08          0.            2.95E+08         1.33E+07 I-130       2.58E+05        7.64E+05         9.72E+07        1.19E+06          0.            6.55E+05         3.00E+05 I-131       6.84E+07        9.66E+07         2.79E+10        1.25E+08                        1.83E+07         5.76E+07 I-132       3.65E+01        9.77E+01         1.29E+04        1.56E+02          0.            1.84E+01         3.47E+01 I-133       1.98E+06        3.36E+06         6.10E+08        4.23E+06          0.            2.44E+06         1.04E+06 l-134       6.75E-05         1.83E-04,       2.38E-02        2.92E-04          0.            1.60E-07         6.56E-05 I-135       2.65E+04        7.00E+04         9.15E+06        1.11E+05          5.67E-03      7.84E+04         2.57E+04 CS-134       5.79E+08         1.40E+09                        3.45E+08          1.69E+08      1.61E+07         6.52E+08 CS-136       2.18E+07          .60E+07        0.              4.78E+07          6.56E+06      9.77E+06         6.19E+07 CS-137       7.83E+08         1.05E+09        0.              2.72E+08          1.40E+08      1.41E+07         3.70E+08 BA-140       9.38E+07         1.21E+05        0.              2.88E+04          7.73E+04      3.19E+08         6.04E+06 CE-141       6.32E+04        4.24E+04         0.              1.47E+04                        1.15E+08         4.86E+03 CE-144       5.03E+06        2.06E+06         0.              8.43E+05          0.            1.19E+09         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
+~ 4 ' E 0   ~
-                                                                                                 <<
-   ~
       ~    0   5                   rs
                                                                               ~    ~               ~        II                  ~      I
@@ Line 1,920: / Line 1,885: @@
 I                      ~
 I~               I      I
-                                     ''
                                                                                                      ~
                                                                               ~
@@ Line 2,149: / Line 2,113: @@
 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 ~ ~ ~ ~ ~ ~ ~ ~ ~  ~ ~ ~ ~  ~ i 152 pendlx 8 - Limit                Dose                ssment for a    ctlve     u         ~ ~ ~   ~      ~   ~      ~ ~ ~ ~   ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~  ~ ~ ~ ~  ~ ~
 d                            for Eff
-                                                                                   ........
                                                                                           ~ ~ ~ ~ ~   ~ ~ ~  ~ ~ ~ ~  ~ ~
                 - Current R,E.M. Sample Point Locattons                                             ~ ~ ~  ~ ~ ~ ~ ~  ~ ~
@@ Line 2,309: / Line 2,272: @@
 : 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,
@@ Line 2,331: / Line 2,293: @@
 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 no a Itional dose rate calculations re needed to verify compliance      10'CI/sec),
 with Control .11.2.1.
-                            '     *
                                ~
                                                    ~ 4   'I.
@@ Line 2,385: / Line 2,346: @@
                                       ,     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
+                                          '.been"exceeded, mthe'r, It ls'at.a coricentiitlon that Is'equivalent to the "Allotted 5 of'Site Umlt",'"'.,"..".;,:,, '
-                                   '
-the "Allotted 5 of'Site Umlt",'"'.,"..".;,:,, '
 I I
                                                         ~,
@@ Line 2,411: / Line 2,370: @@
 RP     ",Jgl. "- '::V.IP-'RlI1II'                     -mlle co          min....:.      .:-.'t,         60 sec      3.5E+05 uCI I      1 ~
 Where:
-                                         ~ Fraction of the Site,LImit
+                                         ~ Fraction of the Site,LImit F
-                                          ',
-F
                                  ", 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.
@@ Line 2,459: / Line 2,415: @@
 I I'
    'I
-* Page 104 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE ALCULATIONMANUAL ODCM METHODOLOGY ~iECTION 2.2   (continued) g.'continued)
+Page 104 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REYISION 19 OFFSITE DOSE ALCULATIONMANUAL ODCM METHODOLOGY ~iECTION 2.2   (continued) g.'continued)
 I 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 7y ~              (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.
@@ Line 2,516: / Line 2,473: @@
 hour        6.32E+06cc.s
                                         " aeoiaa ft3    .
-                                                        '
 aleue min
                                                                         ~s 60 sec
@@ Line 2,547: / Line 2,503: @@
 (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
+E. Solve for DR'Rm X      X "
-DR'Rm X      X "
                             'Kg&#xc3;Q} (Q DDTJ,
                                                                        }c       -m'ec DR       ~         ggygj .total body dose from nuclide                 (I)  for yr       the specmed release source t.- '"
@@ Line 2,561: / Line 2,515: @@
 r
                                                                      ~  I
-                         '
                                          \
                                          - ~
                                                                                                                   .~
                                                                                                                     ~
-                                                                                                                     '
                                                                                                                         / gag
                                                                                                                               ~
@@ Line 2,588: / Line 2,540: @@
 release soutce ls:
                                                                                         'r I
-                                    '
      ~
 DR~            ~    Z i'DR~, ~        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. ', ~,',
@@ Line 2,639: / Line 2,590: @@
 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..
 D,+D, 'Dmrad r
@@ Line 2,695: / Line 2,645: @@
                   ~lnhelatlon (Age Gmup)
                                               \
-                                     ''
 Refer to 2.6.5 to deteimlne the, total doie to organ 8D Particulates. -.          '
 &m radlolodlnes &
@@ Line 2,716: / Line 2,665: @@
 Mt',Ml'
                                                                      '-7 c                 G. IO
-                                       '
                              ,i EE-8 AC  HI-W     ~
                                                                ~q
@@ Line 2,733: / Line 2,681: @@
 C. Jt Determine the Pathway Tritium dose favor from the Table specied below
 (~    for the organ T of interest MILK AGE         . INHALATION COW               GOAT Infant             65                 8%                6-7                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.
-            ~        Mals
+            ~        Mals 0 m     P<P~erey       Melhe$
-                                               .
-m     P<P~erey       Melhe$
 Og Illa r 40k         L.os/
 ~
@@ Line 2,749: / Line 2,695: @@
 Infant                  N,A.i Child                  G-11 Teen                   G-16 Adult                  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
+Dose         .   -             Dl D2 tt D3    t ....; tDn            nnesn Grass-Cow-Meat Excluding Tritium (Child, Teen, or Adult)                                     s s
-                                            '
-(Child, Teen, or Adult)                                     s s
 s J      sl
                                          ~     n
@@ Line 2,771: / Line 2,714: @@
 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
+                  ~- 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
-                                             -
-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
@@ Line 2,783: / Line 2,724: @@
 Uegetation...
 (Excluding Tritium)
-                   ,
 (Child, Teen, or Adult)-
                                                               ~~
@@ Line 2,950: / Line 2,890: @@
 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 BCNE              LIVER     THYROID       KIDNEY          LUNG         GI LLI                  4fR4lr -DOOV UIHCiG S40y' TC>>101    4>>47E 03         6o45E 03     Oo            ioi6E>>01      3ozgf 03       0~                          ~ 33E OZ RU>>103    io 33E+02        0~           4o            io39Et42      0~             3 '0E+D3        D~        5 'bftOf RU 145   3o 03E+00        4~           4~            3o9ift01      0~             io85E+03        de        1   fgft00 RU>>106    2 ~ 34Et43       0~           de            1005E+03      4~             3.63E+04                  2o91C+OZ AG1 igt   5oidftOZ         4obdf+02     4~            9e43F+02      Oe             io96E+05        0~        Ze 85f tOZ SB 124    9o 13E+ Oi       1, ~ 72E+00  2>>21E>>01      0~            le48E+41       2 58E+03                  3 ~ 61'E+ 01 SB 125    lo 24E+41        7o DOE>>01    6>>43E OZ      0~            To57E+03       6o40E+82        0 ~       1~  46f t Oi TE 125H   3o iiE+OZ        bo43E+Oi     de73Et01      Ze9lE+02      0.             3.00E+OZ        0         4o  15f tOf Tf 12TH   iob5E+42         6.47E+01     4 'ZE+41      le 50E+02     )~             6 ~ 19E+02                Zo 256 t01 Ti-izl    1 ~ Z3E+ Oi      3o ZTE+00    de46ft00      ie 22C+Oi     0~             5 24E+02                          t 2o 636 00 t
@@ Line 2,957: / Line 2,896: @@
 0
-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-7 ENVIRONMENTALPATHWAY~SE COXVERSIOX FACTORS R                                FOR GASEOUS DISCHARGES
+ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM TABLE G-7 ENVIRONMENTALPATHWAY~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)
-                            -
-PATHNAY GOATS NLK (CONTNINATED fORAGE)                            AGE GROUP - INFANT ORGAN DOSE FACTOR             (SQ. METER - MREM/YR PER pCi/Sec)
 NUCUDE                                          THYROID        KIDNEY            LUNG           Gl-LLI        WHOLE BODY SN-126     2.10E+08         4.17E+06                       0.                              1.40E+08         6.30E+06 SB-124     390E~                            7.9?E~         0.               256 E+06       9.33E+07 SB-125     4.31 &06         3.92E+05                       4.76E+05         3AOE+08        2.92E+07         ?.94E+05 TE-125M     1.89E+07         6ME+06          621 E+QB       8ABE+06          0.             9.09E+06         2.52E+06 TE-127M     6.64E+06         231 E+06        2.15E+OB       2AOE+07          0.             3.88E+07         8.85E+05 TE-129M     7.05E+07,        2.42E+07        2.66E+07       323E+07          0.             425 E+Q7         1.0?E+07 I-130 . 5A5EAS           1.61E+06        2.05E+08       K51E+06          0.             1.38E+08         6.35E+05 I-131     3.11E+09         3.70E+09        1.19E+12                        0.             1.39EAN          2.17E+09 I-132'.13E%1-              5.71E%1         7$ 1E+01       9.10E%1          0.             1.0?E<1          2.03E-01 I-133     450E~            6$ 7E+07        1$ 5E+10       1$ 5E~           0.             1.17E+07         1.99E+07
 : 0.               0.                             0.               0.             0.
@@ Line 2,969: / Line 2,906: @@
                             >>\>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>><<>>>>>>>>>><<>>>>>>>>>>>>>>>><<>>>>>>>>>>>><<>>>>>>>>>>>>>>>>>>>>
 BGHE            LIVER          THYRCIO      KIOHEY          LUNG         GI LLI
-                                                                                                                      <<>>
                                                                                                                            ~~R wing~ gpgg
             >>>>>>3       De               7 51E+DZ        7  51E+02    4 96EtDZ      7 51E+OZ       l 51E+02     0            7~  51EtOZ P     32    "
@@ Line 2,981: / Line 2,917: @@
 TE 129H        1 ~ 64E+03        So85fPGZ    So40E+OZ       ie69E+04             iobOE+06              iod2E+05                 Z ~ 60E+OZ I    130       Zo 12E+ 0 3
                                                      '. 6ozzEt03    doarE+05       9e66E+03             Oe                    3e56E+03                  Zo45Eta3 J
-                    '
 I   131       Co55E+0>>       -
-                                                       '
 Co63E+04    1 ~ 54E>07     2ebCE+04             0~                    Ze6SE+03                  3o50E+04
   .~               ~           132       5o37E+02             51E~03   Ze 03i >05     2o48E+03             Oo                    iodbE+OZ                  5 '7E+02 I    133 . io68E+04          2o05E+04    5o03E+06       io20E+OC             0~                    5o55E+03                  boa3E+03
                        '= I I   134       Zo98E+02          lo99E+02    io06E>>05       iozlc+03             bo                    Ce66f 01                  2obSE>02 rjj                        135       ioZ4E+03          3e23E103    4e33E+05       5oiCE+03             8~                    Ze43E+03                  io 19E > 03 CS o134.       6o22E+05 :. " 9.95E+05        a.             io33E>>05             ie19E+05              3orrE+03                  2o 23E+05
-                    '.
                                       ~
 CS 136         1odic+04          6.77&04     0~             3o96E+84             So55E+83              5eCOE+03      ao          So 14E+04 CS 137-'-      bo66E+05          le99ct05    0 ~            io03E+05             iodaE+85              3e41E+03                      25E+05 II tj j      .': ~
@@ Line 3,149: / Line 3,082: @@
 SH<<126     2<<54E+08         5 05Epae        1<<48E406       0~           T<<23E F05    1 ~ 69E+08               7  '4E+06 SB 124     4 ~ aaE<06        Te 54E+04      9.6&Ei03       Oo           3<<10E+06     1<<13Etab                  1~  58E+ 06 SB 125     4.14E+ae          i<<15E+05       6 '6E+04       5<<TTE+05     4<<12F+08     3 '4C+07                 8 ~ 19E<< 05 TE 125H    3<<61E+4&          1<<Z9E+46       ie42E+06       1<<03E+07     0~           1<< 01E+07                4 ~ 78E+45 TE 12TH    Te 23E+06         2 52E+06       1 e91E+ 06     Z<<92E+Dl     ao           3 '3E+87     Oe          8<<94E<<45
      < TE iZ9H    1<<35E+07          5<<DZE+06       4<<34E+06       3<<92Et07     0~           4e72E+47                  2<< 13E+06 I   130    6<<61E+05          i<<96E+06       2 '9E+08       3<<04E+06     0~           i<<68E+06                  7<<69E+05 I   131    6<<15E+48          d<<68E+Ob       Z<<54E+li       i<<13E+09     0~           io&4E+08     0~           5 '7E+08 I   13Z    Z<<59E ai          6<<9ZE 01       9<<iiE+Di       1eiaE+40     0~           ie30E Oi     0            2<<46E-01 I   133    8<<l9-'+06         1<<49E+47       Z<<TiE+09       1<<88E+07     do           ieabE+el                  4 '9E+06 I-<<134     0.                a              1<<55E 09       0~           0~           a.                        M~
-I   135    Ze LTE+04         5<<T3E+04 eob3E+10 7<<496+06       9<<iaE+44     2<<94Eeai 8<<ZTEie9 6e41E+04 lebbE44d 0~           Z<<10E+04 CS  134    2<< 83E+ 1 0                      0~             1 69E+10                               8            3<< 19F+10 cs-13e. io 01E+ D9        3<<99E+49       Oo             2<<22E+09     3 05E>08     4 '4Etab                 2<<87E+09 CS 137     3<<84E+10          5<<16E+10       0~             1<<33E+10     6ed5E+09     6<<bbE+48     0 ~          1 bfE<10 81&a&                                       1<<78E+03     4<<78Ei03
+I   135    Ze LTE+04         5<<T3E+04 eob3E+10 7<<496+06       9<<iaE+44     2<<94Eeai 8<<ZTEie9 6e41E+04 lebbE44d 0~           Z<<10E+04 CS  134    2<< 83E+ 1 0                      0~             1 69E+10                               8            3<< 19F+10 cs-13e. io 01E+ D9        3<<99E+49       Oo             2<<22E+09     3 05E>08     4 '4Etab                 2<<87E+09 CS 137     3<<84E+10          5<<16E+10       0~             1<<33E+10     6ed5E+09     6<<bbE+48     0 ~          1 bfE<10 81&a&                                       1<<78E+03     4<<78Ei03 BA-14a                       7<<14E+03       D~                                        1 ~ 10E+06               3<<73E+45 CE 141     6<<06E+03          4 ~ OTE+03     0~             1<<41C+D3     0<<            leiOE+al                 4 ~ 66E+ DZ CE  144    4<<92E+45          2<<02E+05       0 ~            8<<24Et04     0~            ie16E+08    0~           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
-                             '<<
-BA-14a                       7<<14E+03       D~                                        1 ~ 10E+06               3<<73E+45 CE 141     6<<06E+03          4 ~ OTE+03     0~             1<<41C+D3     0<<            leiOE+al                 4 ~ 66E+ DZ CE  144    4<<92E+45          2<<02E+05       0 ~            8<<24Et04     0~            ie16E+08    0~           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 J'
@@ Line 3,236: / Line 3,167: @@
 NH~       Sary' SN   123                      0>>              0~              0~              ~e                           5~                           ~
 SM,126 "~,1>>65E409                            3>> 27E+ a?      9>>5&f10&        Oe           4e6?f+06        1 ~ 09f +09                4~  94f ta?
-SB,124'.;,'>>58E+07                            4>> 57 E+ 05     6 '4E+04                     Ze OOE+Ol       7>> 31E+ab                  i>>OZE+07
+SB,124'.;,'>>58E+07                            4>> 57 E+ 05     6 '4E+04                     Ze OOE+Ol       7>> 31E+ab                  i>>OZE+07 S8   125,                   '>> 64E+07         6>> 0 6E+05      Z>>99E+05 Oe 3>>72E+06     Z>>66E+09        2>>29E+ab                   5>> 23E ta&
-S8   125,                   '>> 64E+07         6>> 0 6E+05      Z>>99E+05 Oe 3>>72E+06     Z>>66E+09        2>>29E+ab                   5>> 23E ta&
 Tf 125N, -" i>>63f+Ol                          5>>91E+06        4~  9if< 06     6>>63E+07     0~              6.50foo?                   Ze  ibf+06 Tf 1Z7N.'.': 4>> 63E<07      ~                 i>>63E+al        i>>Zif<07        1085E+Dd     0>>              2 11E+05                   5   72foo&
-Tf 129M .;" 6>> 06E407                        2>>2?f+07        2.09E+07        2>>53E+05     0~              3 '4E+05                   9>>&if+06
+Tf 129M .;" 6>> 06E407                        2>>2?f+07        2.09E+07        2>>53E+05     0~              3 '4E+05                   9>>&if+06 130 .'4>>2?f405                           X ~ 26E+06      1~  &if408      1096E+06     0~              1 ~ abfo06                 4>>  9?f405 I131     ~ --2>>96f+Db                       4>>25&08         1 ~ 39E >11     7>>2?E+08     0~               1>>12E+05                  2>>43foab I   .132'-
-      '
-.'4>>2?f405                           X ~ 26E+06      1~  &if408      1096E+06     0~              1 ~ abfo06                 4>>  9?f405 I131     ~ --2>>96f+Db                       4>>25&08         1 ~ 39E >11     7>>2?E+08     0~               1>>12E+05                  2>>43foab I   .132'-
 I,133;"
                                    . 1'>>67f  ai      4>>4? E ai 6>>94E+06 5 bbE+01 1 ~ 33E+09 7>>12E 01 i>>21E+07 0~
@@ Line 3,272: / Line 3,199: @@
 <<37E<<bd 1~
 d 45E+ ad 76E<<al s'..-
-                     '
+SR   90    9ebrf+14           0<<               0-             0~          ~e            io 32E+09                  2.41E+10 1 03E+43           0<<               0~             0~          0~            5<<68E+ ~ 5    Oe           2.?rf<<01 3<<82E+03           2e 10 E+03       a.             2<<14E+43    00            1<<26E+07                   b<<3CE+02 Z<<lrf>03 RU  103 9<<9ZE+03 .
-                       "  -
-SR   90    9ebrf+14           0<<               0-             0~          ~e            io 32E+09                  2.41E+10 1 03E+43           0<<               0~             0~          0~            5<<68E+ ~ 5    Oe           2.?rf<<01 3<<82E+03           2e 10 E+03       a.             2<<14E+43    00            1<<26E+07                   b<<3CE+02 Z<<lrf>03
-               '':.:'-
-RU  103 9<<9ZE+03 .
 <<23E+42 Z<<45E+03 5<<51E403 0<<
 ~
@@ Line 3,303: / Line 3,226: @@
 whSM G--W)
 ENVIRONHENTAL PATHWAY OOSE CONVERSION FACTORS                 Rlil FOR GASEOUS OISCHARCES PATHWAY      HEAT (CONTAHINATE<.'ORAGE)                                                      ACE CROUP      AOULT
-  'l   l'UCLIOc
+  'l   l'UCLIOc 0 R   G A N      0 C S  E eeeeeeeee\eeeeeeee'eeeeeeeeeeeeeeeeeee\eeeeee\e BONE             LIVER          THYROIO F A C T 0 R S KIDNEY tso HETER HREH/YR PER eeeeeeeeeeeeeeeeee LUNG         GI LLI UCI/SEC) e WHDLC 800+
-          >>
-                  '
-R   G A N      0 C S  E eeeeeeeee\eeeeeeee'eeeeeeeeeeeeeeeeeee\eeeeee\e BONE             LIVER          THYROIO F A C T 0 R S KIDNEY tso HETER HREH/YR PER eeeeeeeeeeeeeeeeee LUNG         GI LLI UCI/SEC) e WHDLC 800+
 Heeeed                        C>>13E+02        4>>136402         4>>13f+02     4>>13E 102      4>>13E+02                      4 ~ 13EI 05 I,. ~
-                                                                               '
                                                                                                                                                ~ck4l i>>                 Peee32      4>>67E+09          2>>93E>06        0~                 ~          0~             5>>25E+Dd       De             1>>  diE+08
   ,t                CRe 51      Oe                0~      r       4>>23ft03         ir56E+03     9>>38E+03       1>>76E+06       0.             7 ~ 07E< 03 HNee54   . Oe                9i 18 E+06      0                2>>73E+06     D~             2>>61c+0        0              i>>75E r06 FE    59    Ze  67E+08   -- 6>>33E+06          0 ~.             0~           1>>76E+Od       2>>09E+09                      2 'ifr06 r                Co    57:    Oo               5>>SCE+06        0~               0~           0~             1>>43E+08       0~             9>>38frDS 4 '9Er07
@@ Line 3,322: / Line 3,241: @@
 ~   o Yee 91     i>> 14E+06    .;0..                0~               0~           0~              6>>26E+Dd      De             3>>05E+04 l
 ZRee95     3   lbf+06        1>>67E+06        0~               Ze 01E+DS    0~              b>>30E+09      De             8 '6E+05 NB   95    2>>30BOS           1>>Zd& 06        0~               1>>27E+D6     0~              7 el5E+09                    5 ~ DZEr05 RU>>103     1>>06E+06          0~              0~               4>>OSE+08      Oo             1 ~ 2CE+10    0              4 '9fr07
-  ~    I'           PU 106     'ZedOE+09         Oe              0~               5>>41E+09     0~              iebif+11      0              3>>5CEr06 r   ~ I          AG110+     6>> liE+06         S>>21E+ 06       0~                1e22E+07     0~             2 '3E+09                     3>>69E+06
+  ~    I'           PU 106     'ZedOE+09         Oe              0~               5>>41E+09     0~              iebif+11      0              3>>5CEr06 r   ~ I          AG110+     6>> liE+06         S>>21E+ 06       0~                1e22E+07     0~             2 '3E+09                     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
-       >>*
-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
@@ Line 3,410: / Line 3,327: @@
 M 'ff                  the effective al dose factor ue to gamma emlsslons from all noble ases rel      '
                                                    ~
-                 ~, the air do
+                 ~, the air do factor due to gam a emlsslons from each noble gas        dlonucllde l rele N~   ~   X.
-                     -
-factor due to gam a emlsslons from each noble gas        dlonucllde l rele N~   ~   X.
            ]  Nj ~ f(                                                                      (~)
 Where:
@@ Line 3,427: / Line 3,342: @@
 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
-                                                                                           '
                                                                                               \   rr
                                                                                                 ~    r             ~ r
@@ Line 3,454: / Line 3,367: @@
 Xe-131m              8.8                    QZ 1            0.32          2.8 Xe-133m                                     2.5 X 10        0.86         0.17 Xe-133                                      .Q   1          1.0          12.
 Xe-135m             0.11 Xe-135                                           10                      7.4 Xe-137             0,02                    1. 1          4.8          0.1 0;12                                                  3.6 T TAL                24.                                                  47.
-~ 'Data adapted trom the NRG GALE
+~ 'Data adapted trom the NRG GALE a ~
-                                           '
-a ~
 <<
 g <<
                                                                                              +%*AD t ps<<p    q<<' ~
-                         <<*
-Page 187 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODGM
+Page 187 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODGM APPEND RADIOLOGICALENVIRONMENT L SURVEILLANCE ST. LUCIE PLANT Key to SamPIe LocatIoos SAMPLE   APPROXIMATE
-                                                                   '
-APPEND RADIOLOGICALENVIRONMENT L SURVEILLANCE ST. LUCIE PLANT Key to SamPIe LocatIoos SAMPLE   APPROXIMATE
    " PATHWAY                                           DESCRIPTION SAMPLES COLLECTED COLLECTION   DISTANCE DIRECTION SECTOR FREQUENCY      (miles)
-* DfrectRadlatfon  .       =    N-1"   Northof BffndCreek
+DfrectRadlatfon  .       =    N-1"   Northof BffndCreek
 ; Direct Radiation            NNWN. South ot Pete Stone Creek                                                         NNW Dhect Radfa5an       . NNW-10 " C. G. Station Dhect Radiation  ~          NW-10 . Intersectke ol SR 68 and SR 607- .                                    10
 ,  Direct Radfatfon, WNW-2.: Cemeteqr South of 7107 frxSan River Drfve DhectRadfatke         -:   WNWN: USr1atSR712            .. - -.
@@ Line 3,478: / Line 3,386: @@
                                                                                "- ST. LUCIE PLANT Key to SampIe LocatIoos APPROXIMATE
                    '  PATHWAY;;,* LOCATION                           DESCRIPTION SJVAPLES COLLECTION   DISTANCE DIRER    N FREQUENCY      (mlles)
-Sf CTOR Dhect Radiation    -   SSW4: ' Port St. Luckr Svd. and US      1                                                           SSW
+Sf CTOR Dhect Radiation    -   SSW4: ' Port St. Luckr Svd. and US      1                                                           SSW Pine Yaiey and Westrnoreland Roads
--
-Pine Yaiey and Westrnoreland Roads
    ~
        ~,
@@ Line 3,495: / Line 3,401: @@
                 'Denotes Control SampIe
-I Page 189 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19
+I Page 189 of 194 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 19 OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX~
-OFFSITE DOSE CALCULATIONMANUAL ODCM APPENDIX~
 RADIOLOGICALENVIRONIJIENT                 SURVEILLANCE (aetlnued)
 ST. LUCIE PUBS Key to Sample Locations SAMPLES APPROX'T DIRECTION
@@ Line 3,540: / Line 3,444: @@
                                                          ~                    ~
                              ~ 5                              ~
-                        '
-                      '
           -.Terrain correction factors given by Table                           MA were also applied to Dispersion Formulas n
                                                                              \I I~
@@ Line 3,577: / Line 3,479: @@
 : 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
+I,       C UU U
-                         '
-UU U
                                                       ,4                     I              '
 I I

ML17229B036: Difference between revisions

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