L-2018-048, Offsite Dose Calculation Manual

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C-2QO ST. LUCIE PLANT INDEX SECTION IN-TRODUCTION .................................................. .' ................. : ..........................................-9 CONTROLS SECTION DEFINITIONS FOR CONTROtS SECTION 1.1 ACTION .................................................................................. -.............................. 12 1-.4 CHANNEL CALIBRATl*ON ...........................- ..................................._ .................. 12 1.5 CHANNEL CHECK ............................................................................................... 12 1.6 C-HANNEL FUNCTIONAL TEST ..............................................~ ......................... 12

--1.10 DOSE EQUIVALENT l-t3'1 ................................................................................... 12 --

1.-13 FREQUENCY NOTATION ..................................................................................... 13 - -

1.17 MEMBER (S) OF THE PUBl:IC .................................................. -*--- ..................... 13 1.t8- OFFSITE DOSE CALCULATION MANUAL ......................................................._.. 13 1.19 OPERABLE - OPERABILITY ................................................................................ 13 1.20 OPERATIONAL MODE - MODE ........................................................................... 13 1.24 PURGE - PURGING ............................................................................................. 14 1.25 RATED THERMAL POWER ................................................................................. 14 1.27 REPORTABLE EVENT ......................................................................................... 14 1.30 SITE B()U-NDARY ................................................................................................. 14 1.31 SOURCE CHECK ................ --............................. - ............................................ 14 1.3B THERMAL POWER .............................................................................................. 14 1.34 UNPLANNED RELEASE ......................................... -.... *......................................... 14 1.35 UI\JRESTRICTED AREA ....................................................................................... 1-5 1.39 VENTILATION EXHAUST TREATMENT-SYSTEM .............................................. 15 1.40- VENTING ....................................................................................................... -...... 16 1.41 WASTE GAS HOLDUP-SYSTEM ....................................................................... -.16.

-3/4 CONTROLS~ND SURVEILLANCE REQUIREMENTS ........................................ 18 3/4-:U- APPLICABILITY .................................................................................................... 18 . -

INSTRUMENTA.FION RADIOACTIVE LIQUID EFFLUENT MONITORI-NG INSTRUMENTAf:ION ..................... 19 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ............... 23

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i----5_0_ _-t OFFSITE DOSE CALCULATION MANUAL (ODCM)

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C-200- ST. LUCIE PLANT INDEX (continued)

SECTION ........... ........ ......................... ...... .... ............................. ...... .... . .... PAGE CONTROL AND SURVEILLANCE STATEMENTS FOR CONTROLS SECTION 3/4.~ 1 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS .................................................................................. CONCENTRATION ......... ~ ..........-....................................................... 34 DOSE .. - .................................................... - ......................................... 39 LIQUID RADWASTE TREATMENT SYSTEM ...................................... 40 3/4.11.2 GASEOUS EFFL:OEN"FS ............................................................................ 4-1 DOSE-RAT£ ............................._.............................................................. 41 DOSE - NOBLE GASES .....................................................-~- ............... 45 DOSE - IODINE-131,JODINE-133, TRITIUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM ............................................. 46 GASEOUS RADWASTE TREATMENT SYSTEM ................................. 47 3/4.11.3 (NOT USED) 3/4.11.4 TO-T-AL DOSE .............................................................................................49-314.11-.5- MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUs-,a.ND SOLID WASTE TREATMENT SYSTEMS ADMINISTRATIVE CGNT--ROLS .......... 51 314.1-1-.6 ANNUAL RADIOACTIVE EFFLUENT-REcLEASE REPORT TO-THE COMMISSION ADMINISTRATIVE CONTROLS ........................................ 52 374.12 -RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORlNG-PROGRAM ........................ _ ............................................... 56 3/4.12.2 LA-ND USE CENSUS .................................................................................. 64 3/4_ 12.3 INTERLABORATORY COMPARIS-ON PROGRAM ................................... 66 3/4.1Z4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) ADMINISTRATIVE CONTROLS ................................................ 67 _

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C-200 ST. LUCIE PLANT INDEX (continued)

J SECTION PAGE BASES FOR CONTROLS SECTION 3/4.11 RADIOACTIVE EFFLUENTS 3_3.3.9 INSTRUMENTATION ................................................................................. 70 3/4.11.1 LIQUID EFFLUENTS ................................... *-***********************************-****** 71 -

3/-4-.11.2 GASEOUS EFFLUENTS ............................................................................ 73

/4.11.3 NOT USED ................................................................................................. 76 3/4.11.4 T-OTAL-DOSE ............................................................................................. 76 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM ......................................................................... 78 3/4.12.2 LAND USE CENSUS .................................................................................. 78

_3/4.12.3 INTERLABORATOHY COMPARISON PROGRAM ................................... 79 --

FIGI.JRES FIGURE"i--1 SFTE AREA MAP & ENVIRONMENTAL-81\MPLE LOCATIONS ........... 226 FIGURE 1-2 ENVIRONMENTAL SAMPLE LOCATIONS (10 MTLES) ........................ 227 FIGURE 1-3 RADIOLOGJCAL ENVIRONMENTAL SAMPLING LOCATIONS IN SUPPORT OF THE GROUNDWAIER-PR-OTECTION INITIATIVE (NEl-07-07) ............................................................................................ 227

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C-200 ST. LUCIE PLANT

-INDEX (continued)

SECTION PAGE CONTROLS SECTION

.l~IST OF TABLES FOR CONTROLS SECTION E~ABLE 1-1 FREQUENCY NOTA~ION ............................................................................ 17 3.3-f2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSrRUMENTA~iON .. 20 3.3--1-3 RADTOACTIVE Gl{SEOtJS EFFLUENT-MONITORING INSTRUMEN'TATION .............................................................................-........ 24 3.3-14 RADIOACTIVE EFFLUENT MONITORING SETPOINT BASIS .................... 27 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ................ 57 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPtES ..................................................................... 60 4.3-8 RADJOACTiVE UQUIB EFFLUENT MONITORING INSTRUMENTAT!QN SURV~ILLANCE REQUIREMENTS ............................................................. 22 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SUR\LEILLANCE REQUIREMENTS .......................... 31 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM. 34 4.11-2 RA910ACTIVE GASEOtlS WASTE SAMPLING AND ANAEYSIS PROGRAM .................................................................................................... 41 4.12-1 DETECTION CAPABILITIES-FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER UMIT OF DETECTION (LLD)****************************-********** 61

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t -_ _ 50_ _---1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

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C-200 ST. LUCIE PLANT INDEX (continued)

SECTION PAGE METHODOLOGY SECTION Glossary for Methodology Section ................................................... - .............................. 80 1.0 UQUIDRELEASES METHODOLOGY .............................................................. 83-1.1 Radioactive Liquid Effluent Model-Assumptions ................................... 83-1.2 Determining the Fraction_(F) of 10 CFR Part 20 Effiuent-Concentration-Limits (~CL) for a Liquia Release Seurce ............. *****- 84 1.3 Determining-Setpoints for Radioactive Liquid Effluer:it Monitors .......... _.-=:87 1.4 Determining the Dose for Radioactive Liquid Releases ........................ 91 1.5 Projecting Dose for Radioactive Liquid Effluents .................................. 94 2.0 GASEOUS RELEASES METHODOLOGY ......................................................... 95 2.1 :Gaseous Effluent Model-Assumptions .................................................. 91 2.2 Deter:mining the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing*Setpoints for Effluent-Monitors ................... 9-6 2.3 Determining the Radioiodir-ie and-Particulate Dose Rate-to Any Organ From Gaseous Releases .......................................................... 110 2.3.1 1n*halation **********m*-****************-**************--*-******************************* 112 2.3.2 Ground Plane ......................................................................... 114 2.3.3

Milk********************************************************-***********************-**** 115 2.3.4 Tritium .................................................................................... 117 2.3.5 Total Dose Rate by Release Source ...................................... 119

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C-200 ST. LUCIE PLANT INDEX (continued)

SECTION RAGE METHODOLOGY SECTION

_Glossary for Methodology Section (cor.itinued) 2.0 RAGIOACTJ.VE RELEASES OF GASEOUS EFFLUENTS (continued)

.4 Determining the Gamma Air-Dose for-Radioactive Noble Gas Release Sourc-e(s) .............................................................................. 119 2.5 Determining the Beta Air Qese for Radioaetive-Noble-Gas

-Releases ............................................................................................. 122 2.6 Determining the Radioiodine and Particulate Dose to Any Age Group's Organ From Cumulative Releases ......................................... 124 2.6.1 Inhalation ............................................................................... 126 2.6.2 Ground Plane ......................................................................... 127 2.6.""3. Mjlk ........................................................................................ 128 2:6.4 Meat. ...................................................................................... 129 2.6.5 Vegetation ............................................................................. 131 2.6.6 Tritium (All pathways) ............................................................ 132 2.6.7 Total-Organ Dose ....~~******************--**********----************************** 134

-2. 7 Projecting Dose for Radioactive Gaseous* Effluents ............................ 135 3.0 40 CFR 1"90 DOSE EVALUATION ................................................................... 135 4.8 ANNUAL RADIOACT~VE EFFLUENT REPORT .............................................. 13-7

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ST. LUCIE PLANT INDEX (continued)

SECTJON PAGE METHODOLOGY SECTION APPENDIXES APPENDIX A ECL, Dose Factor and_ Historical Meteor-ological Tables ..................... 151 APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE ..................... 216 APPEND-IX B-1 ST. LUCTE SUPPLEMENTAL REMP SAMPLING ............................... 220 --

APPENDIX B Radiological Environmental Sampling In Sup13ort oflhe GROUNDWATER PROTECTION INITIATIVE ................................... 223 APPENDIX C Meteorological Dispersion Formulas ................................................... 228 APPENDIX D Description of the lnterlaboratory Comparison Program ..................... 229

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C-200 ST. LUCIE PLANT I_

INTRODlJCTION 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 l::.iq_uid and Gaseot1s

-Effluents released to UNRESTRICTED AREAS and/or the-SITE BOUNDARY will be maintained within the requirements of 10 CFR Part~O. 40 CFR Part 190, -10 CFR Part 72, 10 CFR 50.36.a and 10 CFR Part 50 Appendix-I radioactive release criteria. All 8ontrol Statements and most Administrative Control Statements in the ODCM are directly tied t-o and reference tbe Plant Technical Specification (TS) Administrati\te Section. The Administrative Control for Major Changes to Radioactive Uqu1d, Gaseous amr Solid Treatment Systems is as per the guidance of NUREG-1301, April 1991, Supplement No. 1 to NRC Generic Lettet89-01. T--he numl5ering sequences of Control StatementS:also follow the guidance ef NUREG-1301 as applicable, to minimize differences. R~gulatory Gui.de 4.15, Quality Assurance for Radiological Monitoring*Programs (Normal Operations}-

Effluent Streams arcid the Environment, 6.3.1 and 6.3.2, provide-the-background for the need to maintain Quality Assurance programs for effluent releases and radiological environmental

- monitoring.

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 Controlcrequirements. Alternate calculation methods may be used from those presented as long as the_o_verail---methodology_does not change or as-long as most up-to-date revisions of the Regulatof'1-Guide 1.109 dose conversion factors and environmental transfer factors are substituted for those currently included and used in this document.

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OFFSITE DOSE CALCULATION MANUAL-(ODCM)

C-200 ST. LUCIE PLANT RECORDS AND NO'flFICATIONS All records of reviews performed for changes to the ODCM shall be maintained in accordance with RM-AA-100-10.00, Processing Quality Assurance Records. All ORG approved changes to the ODGM, 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:

CY-SL-102=0104, Processing Aerated Liquid Waste

CY-SL-102-0-105, Processing Gaseous Wastes

O-CPP-28.20, Met Tower Data Processing

COP={)5-:-04, Chemistry-Department Surveillances and-F~.arameters

CY-SL-104-011-2*, Determination of Process Radiation Monitor Setpoints

-=FheJ~adiological Environmental Monitoring Program is performed by the State of Florida as per FPL Juno Nuclear Plant Services Corporate Environmental Procedure Number EV-SR-104-1001.

The licensee also performs environmental monitoring per EV-AA-01, Fleet Groundwater Protection Program, in order to meet the objectives of the Nuclear Energy lnstitute's Industry Initiative fN-El-07-0-7).

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i----5_0_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

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C-200 ST. lUCIE PLANT CONTROLS AND SURVEILLANCE REQUIREMENTS

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1 - -_ _ 5_0_ _-t OFFSITE DOSE CALCULATION MANUAL (ODCM)

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c-200- ST. LUCIE PLANT 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 CAt.lBRATION 1.4 CHANNEL CALIBRATION shall be-the...adjustment, as necessary, of the..channei-output such -that-if-responds with the necessary range and-accuracy to known values of the parameter which th_e channel monitors. Tne CHANNEL CALIBRATION shall e11compass the entire channel including the-sensor and alarm and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5 CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by=observation. This determination shaJLinclude, where possible, comparison of tbe channel indication a.nd/or status with other indicat1ons and/or status derived from independent instrument channels-measuring the same pa-Fameter.

CHANNEL FUNCT'iONAL TEST 1-:6 A CHANNEL FUNCTiONAL TEST shall be the injection of a simulated signal into the chann-elas close fe the primary sensor as practicable*to verify OPERABILITY including alarm andT or trip functions.

DOSE EQUIVALENT 1-131 LHl -DOSE EQUIVAtENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-1"31, 1-132, 1-133, 1-134 and 1-135 actually present. Tfle thyroid dose conversion factors used-for this_ calculation shall be the thyroid dose conversion factors listed in Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion.

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G-200 ST. LUCIE PlANT 1.0 DEFINIT'IONS for CONTROLS SEGTI.ON OF ODCM (continued-)

FREQUENCY NOTATION l.13 The FREQUENCY NOTATION specified-for the performance of Surveillance Requirements shall cor:respond to the intervals defined in-Table 1.1.

INDUSTRY*INITIATIVE 1.14 Nuclear Energy Institute Initiative (NEI 07-07) on Managing Situations Involving lnadvertenrRadiological Releases into Groundwater (The industi:y initiative has-been adopted through FPL Nuclear Policy EV-AA-01, Fleet Groundwater Protection Program).

MEMBER (S) OF THE PUBLIC 1.17 MEMBER OF T'1E PUBLIC means an inruviduarin a controlled or unrestricted area. rlowever, 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 arid-parameters used in the calculation of offsite doses resulting fr-0m radioactive gaseous and liEt-uid effiue.ats, in the calculation of-gaseous and liquid effluent monitoring Ala.rm/Trip Setpoints. and in-the conduct of the Environmental 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 (2r 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.

OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or-have OPERABILITY when it-is capable of perf.orming its specified function(s) and when all -Recessary 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.

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C-20Q ST. LUCIE PLANT 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM (continued)

PURGE - PURGING

-'.1.24- PURGE or PURGING shall be any controlleE! process of discharging air or gas from a confinement to mai.r-1tain temperature, pressure~ humieity ,_concentration or other operating cor-idition, 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 reacter-coolant-of 3020 MWt.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conaitions specified in Section 50.73 of 10-CFR Part 50.

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 q1:1aJitative-assessment of channel respon-se 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 UNeLANNED RELEASE is the unintended discharge of a volume of liq.uid 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.

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C-200 ST. LUCIE PLANT 1.0 DEFINITIONS for CONTB.OLS SEGTION OF ODCM (continued) 1.34 -(continued) 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.

4. For Gas Decay Tunk,-if a Gas Decay Tank loses greater than 2 psig {)er 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for 9 consecutive shifts, or 18 psig in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , AND-the losses were determined to be to the- Reactor Auxiliary Building Atmosphere, then deciare the losses as an UNPLANNED RELEASE (reference CR 00-2039).

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 aetivities to make the system safe for maintenance activities.

UNRESTRICTED AREA 1.35 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

VENTILATle>N EXHAUST TREATMENT S¥'STEM 1.39 A VEN'FILATION EXHAUST TREATMENT SYSTEM shall be any system designed and-installed-to-reduce gaseous radioiodine o.r radioactive material-in particulate form in effluents by passing ventilation or vent exhaust-gases through charcoal assoroers and/or HEPA filters lor the purpose of-removing iodines or particulates from the gaseous exhaust stream prior to-the release to the environment. Such a system-is not considered to have ar1y effect- on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VEN"flLATION EXHAUST TREATMENT SYSTEM components.

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C-200 ST. LUCIE PLANT 1.0 DEFINITIONS for CONTROLS SECTION OF 0D-CM (continued)

VENTING 1.40 VENTING shall be the centrolled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, co!lcentration__or other operating condition, in sucl"l a manner that rep.!acement air or gas is not provided or req1.1ired during VENTING. Vent, used in system names, does not imply a-VENTING process.

WAS:i:E GAS HOLDUP SYSTEM 1.41 A WASTE GAS HOLDtJP SYSTEM shaJ!-be any system designed and-iflstalled to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and-prmtiding for delay or holdup fer the purpese of reducing the total radioactivity prior to release to the environment.

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ST. LUCIE PLANT TABLE 1.1 FREQUENCY NOTATION (Page 1-of 1)

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.

M 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 1/BSC Once per Dry *shielded Canister (DSC) loading and unloading operation when DSC is in-the Cask Hanc;lling Facility (CHF) and DSC is loaded with Spent-Fuel.

For Radioactive Effluent Sampling

- For Radioactive Batch. Releases Only

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C-200 ST. LUCIE PLANT 3/4- CONTROLS AND SURVE-1-LLANCE_REQUIREMENT-S 3/4.0 APPLICABILITY CONTROLS 3*.0-.1 Compliance with the Controls contained in the succeeding controls is required during the coaditions 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 restore-ct-prior to expiration of the-specified time-intervals, completion of the ACTi-ON requirements is-not re-quired.

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-the-specified time inte.rval with:_

a. A maximum allowable extension not to exceed 2-5% of tbe surveillance interval.

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C-200 ST. LUCIE PLANT INSTRUMENTATION RADIOACTIVE t.lQUID EFFLUENT MONITORING INSTRUMENTATION_

CONTROLS 3.3.S-.9- In accerdance-with St. Lucie PlanLTS 6.8.4.f.1 ), the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with tbeir AlarmtTrip Setpoints set to ensure that the limits of Control-3.11.1.1 are not e:Xceeded. The A-larmn:rip Setpoints of these channels shall l:3e determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION;

a. With a radioactive liquid effluent monitoring instrumentation channel AlarmfTrip 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 ohadioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown--in Table 3.3-12.

Restore the rnoperable instrumentation to OPERABLE status-within 30 days and, if ur.-successft.i!, explain in the-next-Annual Radioactive Effluent Release Report why this inoperability was not eorrected in a timely manner.

c. Re1,>ort all-deviations_in the Annual Radioactive Effluent Release Report.

SUR-VEILLANCE REQUIREMENl=S 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 freqaencies shown in Table 4."3-8.

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50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1----------1 PROCEDURE NO.:

C-200 ST. -LUCIE-PLANT TABLE 3.3'"-12 *....

RADIOACTIVE LIQUID EFFLU*ENT MONITORING INSTRUMENTATlo'N (Page 1 of- 2)

MINIMUM CHANNELS INSTRUMENT ACTION OPERABLE

1. Radioactivity .Monitors Providing Alarm and Automatic l=ermination of Release a) Liquid Radwaste Effluent Line 35 b) Steam Generator Slowdown Effluent Line 1/SG 36, 37

2. Flow Rate MeasurementDevices-

"I~ 1---a_)-_L_iq_u_id_R_a_d_w_as_te_Effl_ue_n_t_Li_n_e_ _ _ _ _ _---+-_ _ _ _N_.A_ _ _ _ _ _ _3_8_--i b) Discharge Canal N.A 38 c) Steam Generator Slowdown Effluent Lines N.A 38 SG - Denotes Steam Generator ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:-

a. At least two independent samples are.analyzed-in accordance with the Surveiilance Requirement for concentration limit of Control 4.11.1.1.1.

AND

b. At leasUwo technicatty ~ualified membeTs of the Facility Staff independently verify the release rate calculations and discharge line valv1ng.

Otherwise, suspend release~ef radioactiv.e effluents via-this pathway.

ACTION 36 - With the number of channels -OPERABLE Jess than required by the-Minimum Channels OPERABLE-requirement, effluer.t releases via this pathway may-continue provided g_rab samples are analyzed for gross radioactivity (!;>eta 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 (1) when the specific activity of the s*econdary coolant is greater than 0.01 micro-Curies/gram DOSE EQUIVALENT 1-131 OR

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (1) when the specific activity of the secondary coolant is less than or equal to 0.01 micro-Curies/gram DOSE EQUIVALENT 1-131.

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C-200 ST. LUCIE PLANT T ABL.:E 3.3-12 '""'

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

(Page 2 of 2)

AC-rlON STATEMENTS (continued)

ACTION 37 - V~ith the number of char-mels OPERABLE less than required by the Minimum Channels OPERABLE requirement, isotopic grab samples shalLbe-obtained

-and anafyzed at a bower Limit of Detection for l-13t, Co-58, Co-60, Cs-r34, and Cs-137 to-achieve detection sensitivity capab~e of detecting a primary-to-secondary leak rate of 5 gallons per day, provided that the Reactor Coolant System_has sufficient activity present.

The applicable frequency shall-be:

In-MODES 1, 2, 3, 4

a. At least ence per day<1> for isotopic activity on the affectea Steam Generator, provided that the Air Ejector Gas Activity Mon*itor_ is OPERABLE, OR

b. At least every 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s<1> for isotopic activity on the affected Steam Generator, if the Air Ejector Gas Activity Monitor is INOPERABLE.

This requir:emeat is intended to meet EPRI PWR Primary-to-Secondary Leak Guidelifles (TR-j 04788-R2) per reference PMAI 00-08-1-89.

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.

_ TABLE 3.3-12 Notation

(-1) - -The-initial sample shall be completed prior to-the frequency inter.val specified.

Subsequent.samples (of the same INOPERABLE condition) may be performed per E>DCM surveillance requirement -4:0.2 (a maximum allowable ex-tension not to exceed-25% of the surveillance-interval).

REVISION NO_: PROCEDURE TITLE:

i-----5_0_ _.... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

-C-200 ST.- LUCIE PLANT TABLE 4:3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING-INSTRUMENTATIO SURVEILLANCE REQUIREMENTS (4)

(Page 1 of 1)

CHANNEL CHANNEL SOURCE CHANNEL

-INSTRUMENT FUNCTIONAL-CHECK CHECK CAUSRATION TEST

1. Radioactivit-y Monitors Providing Alarm and Automatic Termination of Release a) Liquid Radwaste Effluent Line D p R-(2) Q (1) b) Steam Generator Slowdown Effluent D M R (2) Q (1)

Line

2. E!ow Rate Measurement Devices a) Liquid Radwaste Effluent Line D (3) N.A. R Q bJ -Discharge Canal- D (3) N.A. R Q c) Steam Generator Slowdown Effluent Q D (3) N.A. R Line TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway and control room alarm annunciation occur if=any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint or

2. Circuit-failure or

3. Instrument indicates a downscale failure or

4. Instrument controls not seLin 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.

l=hese standards should permit calibrating_ the system over its jatended range of energy and rate capabilities that are ty-picai-of normal plant operation. For subsequent CHANNEL _

CALIBRATION, button sources that have-been related to the initial calibration may be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic or batch releases are made.

(4) The requirements to perform the surveillances is not applicable, if Table 3.3-12 list the INSTRUMENT MINIMUM CHANNELS OPERABLE as not applicable (N.A.). (Reference CR 99-0361, PMAI 99-04-106).

REVISION NO.: PROCEDURE TITLE:

t - -_ _ s_o_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

c_-2QO ST. LUGIE PLANT INSTRUMENTATION-RADIOACTIVE GASEOUS EFFLUENT-MONl'.fORING INSTRUMENTATION CONTROLS

r3. 3 .3. 10

In accordance with St, LuciecPlant TS 6. 8 .4 .f. 1), !be radioactive gaseous

-effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip ..s:etpoints 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.

_APPLICA.B1LITY: As.shown in Tabie 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 gacs-e*ous effluent monitoring instrumentation channels OPERA:\Bt.E, take the ACTION-Shownin Table 3.3-'13.-

Restore the inoperable instrumentation to OPERABLE statas within 30 days-and, if unsuccessful, explain in the-next Annual Radioactive Effluent Release Report why this inoperability was not corrected in a tirneiy manner.

-c. Report all deviatiens in the AnnuaLRadioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.3.3~ 10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHAI\INEL 8HECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-13 .. \.>

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIO't-J (Pa§e 1 of=4)

M!NIMUM MEASUREMENT INSTRUMENT *CHANNELS APPLICABILITY ACTION RANGE OPERABLE

1. Waste..GasHoldup System a) Noble Gas Activity Monitor-Providing Alarm 1/ Rx

45 and Automatic Termination of Release

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

3. Plant Vent System Modes 1, 2, 3, 4 48

-I a) Noble Gas Activity 1 o-, - 1o~ uCi/cc (Unit 1)

Monitor (Low 1/ Rx *** 47 10 10-2 uCi/cc Range)

(Unit 2) b) Noble Gas Activity 2 10- - 105 uCi/cc Monitor (Higb.. 1/ Rx *** 47 (Unit 2)

Range) c) Iodine Sampler 1/ Rx

51 d) Particulate-Sampler 1/ Rx

51 e) Flow Rate Monitor N:A. (3)

53 f) Sampler Flow Rate 1/ Rx

46 Monitor

4. Fuel Storage Area VenWation System 1 o-, - 1 O" uCi/cc a) Noble-Gas Activity (Unit 1)-

1/ Rx * -47,54 Monitor 10 10 5 uCi/cc (Unit 2) b) Iodine Sampler 1/ Rx

51 c) Particulate Sampler 1/ Rx

51;54 1-10° cpm d) Flow Rate-Monitor N.A. (3)

53 e) Sampler Flow Rate 1/ Rx

46 Monitor

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-13 .,,;,;,i:;isx RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENT-ATION (Page 2 of 4)

MINIMUM -MEASUREMENT INSTRUMENT CHANNELS APPLICABILITY ACTION

5. Steam Generator Blowdown Building OPERABLE RANGE r

Vent a) Noble Gas Activity Monitor (Low 1 *** 47 Hr1 - 1o:.2 uCi/cc Ranae) b) Iodine Sampler 1

51 c) Particulate Sampler 1

51 d') Flew Rate Monitor -* N.A. (3)

53 e) Sampler Flow Rate-1

46 Monitor

6. Steam Safecy Valve 4/Steam 10 103 uCi/cc Modes 1,2~3,4 -

55 Discharae # Header

7. Atmospheric Steam 1/Steam 10*1 - 103 uCi/cc Dump Valve Modes 1,2,3,4 55 Header Discharae #

8. ECCS Exhaust 1/Train Modes 1,2,3,4 55 10*7 - 10° uCi/cc

- At all-times while making releases via this pathway

- - At all times when air ejector exhaust is not directed to plant vent.

- - - At all times-'Nhile making releases via this pathway or-modes 1-4

- On Unit 2, The steam safeDJ valve discl:1arge monitor ar.EI the atmospheric steam dump valve discharge monitor are the same monitor.

Rx - Denotes reactor ACTION STATEMENTS ACTION 45 - With-the number of ehannels OPERABLE less than required by the Minimum Channels OPERABtE requirement, the contents -of the tank(s) may- be released to-the environment provided that prior to- initiating a release:

a. At least two indepemlent samples of the tanl<'s Gontents 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.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-13 . ** .

RADIOACTIVE GASEOUS-EFFLUENT MONITORING 1NSTRUMENTATI-ON (Page 3 of 4)

ACTION S~ATEMENTS (conUnued}

AC"flON 46 - With the number of-channels OPERABLE less tn*an reqt1ired by the Minimum Channels OPERABLE requireme!'.'lt, effluent rel.eases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47 - With the number-of channels OPERABLE less-than required by the Minimum-Channels OPERABLE, effluent releases via this pathway_may continue provided:

a. !f channel inoperability is due to loss of Control Room alarm annunciation ONLY.

Channel checks are performed once-per forn hours<1> to verJfy normal indication-and current assigned setpoil"lts are NOT exceeded.

OR

Grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months <1> 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 .

b. lf channel inoperability is due to loss of activity indication, Then

Grab samples are taken at least once per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s<1> and these samples are aP.alyzed for isotopic activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The effluent pathway is-continuously monitored using an effluent radiation monitor that meets all the requirements in Table 4.3-'9 and Table 4_11-2.

!f-control room alarm annunciation is not available, Then channel checks are performed once per four hours<1> to verify normal indication and current

__assigned setpoints are NOT exceeded.

ACTION 48 - With the number of channels-OPERABLE less than required by the Minimum Channels OPERABLE-requirement, noble gas isotopic grab samples shall-be obtained and analyzed at a Lower Limit-of Detection for Ar-41, Kr-88.,. Xe-133, Xe-133m, and Xe-135-to achieve detection sensitivity capable of detecting a primary-to.c-secondary leak rate of 5 gallons per day, provided that the Reactor Coolant System has sufficient activity present.

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) t-----------t PROCEDURE NO.:

-C-200 ST. LUCIE PLANT TABLE 3.3-13 "

RADIOACTIVE GASEOUS EFfLUENT MON1TORING INSTRUMENTATION-

{Page 4- of 4)

ACTION STAT-EMENTS (continued)

ACTIGN-48 (continued)

_The applicable frequency shall be:

At least once. per 12-hours'1l;(Zl for noble gas-isotopic activity on the Air Ejector Exnaust provided that each affected Unit's Steam-Generator Slowdown Monitor is OPERABLE, OR-

b. At least oncaper 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (1);(2l for-noble gas isotopic activity on the Air-Ejector Exhaust if either of the affected Unit's Steam Generator Blo.wdown Monitors is INOPERA.81£.

This requirement is intended-to meet EPRI PWR Primary=to-Secondary Leak Guidelines (TR-104788-R2), therefore grab samples-shall be taken regarElless_o.fthe Alignment of the Air Ejector Exhaust while in Modes 1, 2, 3, 4. (Reference PMAI 00-08-109.)

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 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.

ACTION 54 - With the number of channels OPERABLE less than.required-by the Minimum Channels OPERABLE requirement, suspend all-operations involving movemeAt of recently irradiated fuel within the spent f.uel storage pool or crane operations with loads over recently irradiated fuel assemblies in the spent fuel storage.pool.

ACTIONS 55-- With the number of channels OPERABLE less than required by the Minimum

_Channels OPERABLE requirement, either restore the inoperasle Channel(s) to *OPERABLE status within 7.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or initiatathe pr:eplanned alternate method of monitoring the appropriate parameter(s).

TABLE 3.1-3-13 NOTATION (1) - The initial sample shall be completed prior to the frequer.cyinterval specified. Subsequent samples (of the same INOPERABLE condition). may be performed per ODCM-surveillance requirement 4.0.2 (a maximum allowable extension not to exceed 25 percent of the-

-surveillance-interval).

(2) - 1f there is no steam flow to the air ejector nozzles while-the Reactor is in Mode 4, Then the sample may be omitted, but the steam flow condition (status) to the air ejector shall be reverified once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to initiate grab samples if steam flow to the air ejector nozzles is established.

(3) - The flow rate monitors are not functional. Vent flow is based on design engineering documents and values in the UFSAR. EPIP-14 contains the correct flow values.

REVISION NO.: PROCEDURE TITLE: n

- y 50 OFFSITE DOSE CALCULATION MANUAL (ODCM) i 2 PROCEDURE NO.:

C-200 ST. LUCIE PLANT it ;:1:11::

i'::. *;-

1

t TABLE 3.3-14 *ec,>* ,, *,

RADIOACT-IVE EFFLUENT MONITOR SETPOINT BASIS (Page 1 of 4)

CHANNEL .BASIS - ALERT HIGH ODCM Effluent-Gas Channels ID DOCUMENT SETPOIN,e SETPOINr 8

1PV LOW-RANGE GAS RSC26_1L - C-200 5 xBkg.q Allotted % Of Site Limit9 1FHB LOW RANGE GAS RSC26_4L c:.2ooa 5 X Bkg.q Allotted % Qf Site Limit9 2A PV PIG LOW RANGE GAS. 423 C-200'.3 5 x Bkg.q Allotted % Of-Site -

C-20Gi1 Umit9 For Plant 28 P\1- PIG LOW RANGE GAS 433 5 x 8kg.

Vent#2 2FHB LOW RANGE GAS - 413 C-200a 5 x.Bk@. Allotted % Of Site -

Limit9-8 SGBDB LOW RANGE GAS - - 45-6 C-200 5 X 8kg. Allotted % Of Site Limit9 1 CONDENSER AIR EJECTOR 35 C-200 2 X Bkg.b 3 X 8kg.

2 CONDENSER AIR EJECTOR 403 C-200 2 x Bkg.b 3 x 8kg.

8 1 BATCH GAS EFFLUENT 42 C-200 As Per As Per CY-SL-102-0105 CY-SL-102-0105a,h 2 BATCH GAS EFFLUENT 203 C-200a As Per As Per CY-SL-102-0105 CY-SL-102-0105a,h

.. 2PVWRGM Chan Low Range Gas 621 Allotted % Of Site-624P C-200a .5-x Bkg.P uCi/sec _

-- Mid Range Gas 622 Limit uCi/sec High Range Gas 623 -

2AEeCSWRGM Chan Low Range Gas 601 0.75 x HighP Allotted % Of Site 604P C-200a Mid Range Gas 602 uCi/sec Limit uCi/sec High Range Gas 603 - -

28 ECCSWRGM Chan Low Range Gas 61*1- 0.75 x Highp Allotted % Of Site 614P C-200a Mid Range Gas 612 uCi/sec Limit uCf/sec High Range Gas 613 CHANNEL BASIS HIGH ODCM Related Particulate Channels ALERT SETPOINT" ID DOCUMENT SETPOINT""

1FHB PARTICULATE RSC26_4P FUSAR & TSd 5000 CPM 10,000 CPMC 2A-P-V PIG PARTICULATE 421 FUSAR 5000 CPM 10,000 CPMC 2B PV PIG PARTICULATE 431 FUSAR 5000 CPM 10,000 CPMC 2FHB PARTICULATE 411 FUSAR & TSd 5000 GPM 10,000 CPMC SGBDB PARTICULATE 45-4 FUSAR 5000 CPM 10,000 GPMC

REVISION NO.: PROCEDURE TITLE: DA ~ != ""_--~_.;., :,*

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) ',

PROCEDURE NO.:

C-200 ST. LUCIE PLANT tf!:'of231 1

Xr:[,\ ... *****.*. .)

T ABlE 3.3-14 'ii ..*.:,L******}':'.W!!.*.

-RABIOACTIVE EFFLUENT MONITOR SETPOINT BASIS (Page 2 of 4)

CHANNEL BASIS A1-ERT HIGH ODCM Related Iodine Channels ID DOCUMENT SETPOINr SETPOINr l2A PV PIG IODINE 422 FUSAR 5000 CPM 10,000 CPMC 28 PV PIG IODINE 432 FUSAR 5000 CPM 10,000_ CPMC 2FHB IODINE 4.12 FUSAR 5090 CPM 10,000 CPMC ISGBDB IODINE 45-5 FUSAR 5000 CPM 10,000 CPMC CHANNEL BASIS* ALERT HIGH ODCM Related Liquid Channels ID DOCUMENT SETPOINT' SETPOINr 1A S/G SLOWDOWN 44 C-200 2 X 8kg. 2. E-04 uCi/m(m 1

1B S/G BLOWDOWl\l 45- C-200 2 X 8kg. 2. E:="04 uCi/ml 'm 2A S/G SLOWDOWN 121 C-200 2 X 8kg. 2.E-04 uCi/mlm 28 S/G SLOWDOWN 122 C-=200 2 X 8kg. 2.E-04 uCi/mlm 1 BATCH LIQUID EFFLUENT As Per CY-SL-102- As Per CY-SL-102-R6627 C-200 0104 0104n 2 BATCH LIQUID EFFLUENT As Per CY-SL-102- As Per CY-SL-102-301 C-200 0104 0104" Monitor channels not listed are covered _per CY-SL-104-0112, Determination of Process RaBiation-Monitor Setpoints TABLE NOTATIONS I a - ODCM Control 3.11.2.1 a b - ODCM.Table 4.11-1 Note (-7)

C - ODCM Gontroi-3.11.2.1.b ct - TS Table 3.3-6 req(jired instrument 2.a.ii with setpoint per-ODCM e - -setpoints may be rounded for analog and digital displayinput limitations.

f - 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

REVISION NO.: PROCEDURE TITLE:

1----------1 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3-.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS (Page 3 of-4)

TAB.LE NOTATIONS (cor:itinued)-

m - Continuous-Liquid setpoint methodology- per*ODCM 1-.3-.2 n - Batch* liquid setpoint methodology per ODCM 1.3:1

o - Note "oscar" is not used in this table notation p - The individual Channel 621, 622 and 623 {Plant Vent No. 2) 81:lannel 601, 602 an-d-603 (ECCS 2A) and ehannel 611, 612 and 613 (ECCS 28)

Data Base Alert and High Alarm Setpoint Items do not provide activation.,.Qf a-Gon1r-o1 Room Alarm. Only the Skid's Effluent Channel Setpoint provides an alarm function.

After the first Alert and High Effluent Channel Alarms are received they will stay locked in if the release is increasing to higher activity levels. Transfer of Skid internal control to Effluent Channel input from the Mid or High Range Gas Channels will not reset an alarm, nor provide additional alarms. The Effluent Channel on the

-respective-Skid has to be reset to new*setpoints by l&C. References to "Alert Alarm" and "High Alarm" settings for the Low Mid and High C.f:!a-nnels are for display L information only. This is why Table 3.3-14 only list Channel 624, 604 and-614 as the __

Channel-ID for Alarm Setpoints. These are the respective Skid's Alarm Channel.

Channel ID number 604 and 614-are the uCi/sec indication and ALERT/HIGH-Alarm channels for ECC.S 2A and ECCS 28 respectively . ..The ECCS exhaust pathways each have-a single fan. Their Skicl's Monitor Item #059 will be-set per the measured ft3/minute exhaust- rate. Their Skid~s Monitor Item #060 (Accident Flow rate) will be

-set to zero since there is or:tly one flow rate possible for these ECCS pathways. The uCi/sec value indicated-on ECCS sk~ds should be valid regardless of Normal or Accident conditions.

The Channel ID number 624 (generically called the Plant Vent 2 Skid's Channel 4) is-the uCi/sec and Control Room active ALERT/HIGH-Alarm that is Common (shared by) to the Low (621 ), Mici (622), and High (623) Range Gas Channels. The Plant Vent 2~ skid Monitor Item #059 will be set for the maximum ft3/minute flow rate that could occur under all circumstances. The Plant Vent 2 Channel 624's actual uCi/sec is dependent what is set in Monitor Item #059 and Monitor Item #060 as follows:

REVISION NO.: PROCEDURE TITLE:

...,__ _s_o_ _-t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 Sl". LUCIE PLANT TABLE 3.3-1-4 RADIOAC"flVE EFFLUENT MONITOR SETPOINT BASIS (Page 4 of 4)

TABLE NOTATIONS (continue-ct) p- - (continue!)

The NORMAL value for Uie Common Channel 624-uCi/sec indication and

-ALERT/High .Alarms should-be .based on the equivalent uGi/sec of the 5 x Bkg (use CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints) uCi/cc of the Low Ra-nge Channel #621 and-RIM 26-90 Monitcx Item #059-(the MAXIMUM-process ft3/minute flow rate that could occur in the Unit 2 Plant Vent.

The ACCIDENT value -for the Common Channel 624's uCi/sec is based on the Skid switching (at a preset activity va.lue)-iRput from thE Low Range Channel to calculate/

display a uCi/sec value based on receiving activity uCi/cc input from either the Mid

-Range Channel 622 (CJR from the High Range Channel B23) and RIM 26-90 Monitor __

Item #060 o,600 ft3/minute (use CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints) flow rate that is expected during a LOCA Safety Injection sequence.

During an ACCIDENT you have to access the running status of 2-HVE-6A, 2-HVE-6B, 2-HVE-7A, 2-HVE-7B, 2-HVE-8A, 2-HVE-8B, 2-HVE-10A and 2-HVE-10B to determine acti:ial Plant Vent exhaust flow rate ft3/minute. ThisJs the flow rate that should be inserted into Plant Vent #2 Skid's Monitofltem #060 with

_I new Setpoints for Alert and High Alarms in units of uCi/sec calculated-by using the actual Plant Vent exhaust flow during the AccideRt. If fan 013erating status-changes, tbe Effluent Channel 624 uCi/sec indication and existing Alert and High Alarm Setpoints will not be valid for a new flow rate. Thfs is the reason that EPIP-14 does not utilize Chan-net 62"4 indication for calculating -off-site dose.

q - During an outage, the Low Range gas activity ALERT Alarm Setpoint may be set to slightly above outage anticipated activity levels, but.shall always be set to a value less than the High Alarm Setpoint. Examples of outage activities are initiating a Containment Main Purge and ventin~Jhe S/G primary side bowls.

fUSAR - Channel listed FUSAR, but not required by ODCM Control 3.3.10 T-able 3.3-13.

The setpoints are used fo provide alarm well before exceedfng-ODCM Control 3.11.2.1.b Site Dose Kate 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 CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints.

IDA,r.!~ .,.,'\.:.::*

REVISION NO.: PROCEDURE TITLE:

.~7?\Eftn,n; nii'e!iA>'l<:

'**;" nn;-:,,,,-,

PROCEDURE NO.: 231":t:ii:C""'

C-200 ST. l-UCIE PLANT - L,,.,,. __ J~~fo~(:,

',,.... " c,-1.,::.:;;*::D:c.'*

<}{;., ,~./

TABLE 4.3-9 Aiii/'Jlii'!:i:T,'*'

RADJOACTIVE GASEOtJS EFFLUENT MONITORING INSTRUMENTATION

SURVEILLANCE REQUIREMENTS (4J

(-Page 1 of 2)

Modes in CHANNEL CHANNEL SOURCE CHANNEL which INSTRUMENT FUNCTIONAL CHECK CHECK CALIBRATION surveillance TEST required

1. Waste-Gas Holdup System a) Noble Gas Activity Monitor -

Providing Alarm and p p R (3) Q (1)

Automatic Termination of Release

12. C0ndenser Evacuation System aJ Noble Gas Activity Monitor D I _M R (3) Q (2) **

3. Plant Vent System a) ..:.Noble Gas Activity Monitor D -M R (3) Q (2)

b) Iodine Sampler w NA N.A. N.A.

c) Particulate Sampler w N.A. N.A. N.A.

e) Sampler Flow Rate D N.A. R N.A. *

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

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

c) Particulate Sampler: w N.A. N.A. N.A.

e) Sampler Flow Rate Monitor - D -N.A. R N.A. *

.:::5. Steam Generator Slowdown Buildil}Q Vent a) Noble Gas Activity Monitor D -f\11 R (3) Q (2)

b) Iodine Sampler w N.A. NA N.A.

c) Particulate-Sampler w_ N.A. N.A. NA.

e) Sampler Flow Rate-Monitor D N.A-. R N.A. *

6. Cask Handling Facility-(CHF)

Vent a) Sampler Flow Rate Monitor D -NA Ai'mual N.A ***

REVISION NO.: PROCEDURE TITLE:

l - -_ _ so_ _---1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCI-E PLANT TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUEN"f MONITORING INSTRUMENTATION-SURVEILLANSE REQUIREMENTS (4)

(Page 2 of 2)

TABLE NOTATtONS

At all times when making releases via-this pathway.

- At all-times when air-ejector exha1:1st-is noLdirected to plant vent.

- - A.tall times when-Cask Handling Vent (CrlF) is operative.

(1) The CHANNEL FUNCTIONAt"TEST shall also-demonstrate automatic isolation of this-pathway and control room alarm annunciation occurs if any of .tt:ie following sonclitions exist:

1. Instrument indicates measured leveis 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 FtJNCTIONAL TEST shall also demonstrate that contro.Lroom alarm annunciatioft occurs if any of the followil"!_g_ conditions exist:

1. Instrument indiGates 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 & 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.

(4) The requirements to perform the surveillances is not applicable, if Table 3.3-13 list the INSTRUMENT MINIMUM CHANNELS OPERABLE as not applicable (N.A.).

(Reference CR 99-0361, PMAI 99-04-106).

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT 3/4.11 RADIOACTIVE EFFLUENTS I3/4.11.1 LIQUID EFFLUENTS CONCE~TRATION

coNTROLS-3.1-1.1.-1 In accordance with t!~e 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 concentr-ations 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, tha.concentratio.r-1 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.

SURVE!-b.LANCE 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 tharadioactiv1ty_analyses shall be used Jn 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 shaU 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.

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35 of 231 ' ,

I PROCEDURE NO.: '.,,,

-C-200 ST. LUCIE PLAN~ ;.

TABLE 4.11-1 -'*

RADIOACTIVE- LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .

(Page 1 0f 4)

Minimum Lower-Limit of Sampling Type of Activity_

Tiquid Release Type- Analysis Detection Frequency Analysis Frequency Ll.:.D* m (.uCi/ml)

JS.:. Batch Waste Release-Tanks (2) p Each B'atch P.G.E. (3) 5.E-07 Each Batch 1-1-31 1.E-06 p M Dissolved and 1.E-05 One Batch/M Entrained Gases (Gamma Emitters) p M H-3 1.E-05 r Each Batch Composite (4) p Q Gross Alpha Sr-89, Sr-90 Each Batch Composite (4)_ C-14, Fe 55, Ni-63 1.E-07 5.E~o8 Ls. Continuous Releases (5, 6)

Daily 4/M Composite 0

P.G.E.(3) 1-131 1.E-06 5.E-07 1.E=06 Dissolved and Daily 4/M Entrained Gases- 1.E-05 Grab Sample Composite (Gamma Emitters)

M H-3 1.E-05 Daily Composite Gross Alpha 1.E-07 Q Sr-89, Sr-90 5.E-08 Daily Composite C-14, Fe-55, Ni~3 1.E-06 C. EasUWest Settling Basins (7) w w P.G.E. (3) 5.E-07 G~ab-Sample .1-131 1.E-06 D. Settling Basin as a Batch P.G.E. (3) 5.E-07 Release Pathway. (9) p 1-131 1.E-Off (Reference CR 99.=1165 Pi\71AI Each Batch Each Batch Dissolved and 99-08-084 P.MAl-01-04-115 (8) Entrained Gases 1.E~05 (12).CR 2010~296. -(Gamma Emitters)

(13) AR 01967818 H-3 1.E-05 Gross Alpha 1.E-07 Each Batch Each Batch_

Sr-89, Sr-90 5.E-08 C-14, Fe-55, Ni-63 1.E-06 E. Groundwater Dewalering H-3 1E-05 W (11) W (11)

Batch Releases (10) P.G.E. (3)_ 5.E-07 H-3 1E-05 p P.G.E. (3J 5.E-07 Each Batch Gross Alpha 1.E-Q7 -

Each Batch (8)

Sr-89, Sr-90 C-14, Fe-55, Ni-63 5.E.:08

1.E-06 I

P.G.E. - Denotes Principal Gamma Emitter

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1----------1 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-c200 ST. LUCIE PLANT TABLE 4.11-1 '<: >

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS-PROGRAM --**

(Page 2 of 4)-

TABLE NOTATIONS (1) The LLD is deJined-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% probabiHty with only 5% probability of falsely concludin-g-tt:rat a blank -observatio.n represents-a real signal.

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

-:tLD =

E

v~ 2.22E + 06

Y

exp(-A-* LiI)

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, A = the radioactive.decay constant-for the particular radionuclide (sec- 1 )

and LiT = the elapsed time between the midgoint of sample collection and-the time of counting (sec). *1 Typical values of E, V, Y and ~T should be used in the calculation.

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

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1 - -_ _ s_o_ _-t OFFSITE DOSE CALCULATION MANUAL (ODCM)

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C-200_ ST. LUCIE PLANT TABLE 4.11-1 - ,,,

RADIOACTIVE LIQl:JID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 4)

TABLE NOTAI10NS (cor-1tinued)

(2) A Batch release is the -discharge of liquid wastes of a discrete volume. Prior t-0 sampling for analyses, each batch shall be isolated ancf then thoroughly mfxed by a method described-ir1 the ODCM -te assure representative sampling. l

_<<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 r:1ot mean that only-these nuclides are to-5e_considered. Other gamma peaks-that are ideAtifiable, together with th-ose of the abGVe-=nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Contro(3.11.2.6 in the format outlined in Regulator:y 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 sy:stem that has an input flow during the continuous release.

(6) If Component CoolTng-Water activity is > 1.E~S µCi/ml, perform a weekly gmss activity: on tl=te Intake Cooling Water System outlet to ensur-e the activity level is less than or equal to 2-:E-07 µCi/ml LLD limit. If ICW is >2£-07 µCi/m~ perferm analysis in accordance with a Plant Continuous Release on this Table.

(7) Grab samples to be taken wben there is co_nfirmed primary to secondary system leakage indicated by the air ejector monitor indicating greater than or equal to 2x background.

(8) At least two independent samples are analyzed in accorsance with the surveillance requiremennor cencentration limit of control 4.11.1.1.1 and at least two technically qualified-members of the facility staff independently verify the re1ease rate calculations.

(9) The settling basin(s) may receive low level activity per the guidance of CY-SL-102-0104, therefore these samples shall be taken regardless of the absence of a primary-to-secondary leak (note (7) on liquid release type [C] settling basin does not apply to liquid release type [D] settling basin as a batch release pathway). The South Basin (pond) is a permitted outfall (per FDEP Permit FL002208) to the intake canal. An authorized "bypass" is required to pump directly from the East or West Basins.

REVISION NO.: PROCEDURE TITLE:

50 OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 4.11-1 . *<;;,;:s::::

RADIOACTIVE LIQUID-Vlr'ASTE SAMPLING-AND ANAlYSIS PROGRAM

(~age 4 of 4)

TABLE NOTATIONS (contin1a1ed)

(10) Applies to groundwater dewatering-discharges from locations outside the Plant Protected Ar.ea where radiological contamination is not expected at significant levels. This expectation-may be a judgment based on local and peripheral samJa>>es that indicate r-adiological contaminant levels below the LLD from sources in tbe dewatering *j:)ump's zone of influence. These samples may include dewatering pump well samples (taken by small-volume sample pumps), upgradient grOt1ndwater samples_,_and upgradient samples taken from-surface waters (e.g., IW\/V percolation basins) within-the zor:te of influence;- 1=he sampli-ng_protocoL for these releases shall be pr:ecautionary in-nat-l;lre. A conservative value shall be established in the discba.r:ge-p-ermit for the effluent activity;_ however, the-permit shall be reconciled with actual activity concentrations ascertained from sample analysis of the actual effluent.

(11) Each outfall shall be sampled at some point in the discharge header at the frequency described herein. Any outfall that includes a well (or well point) that has not yet achieved its steady state flow rate (indicating that it has not yet reached its steady state zone of influence) shall be sampled weekly~ After the wells of an outfall reaches steady state, the sampling and analysis frequency may be extended to monthly.

(12) CR 2010-296; Radiological Impact Evaluation of Effluent Releases from Catch

-Basins to the East Settling Pond (Dec. 2009). It was determined that potential tritium releases via evaporation from the East Settling Pond alone (i.e. gaseous releases) represents <1.0% of the total activity released-via all gaseous release points ane therefore, does not qualify as significant reiease point.

(13) Id-Ader emergency conditions, the Shift-Manager and Chemistry Manager may waive the requirement to analyze the gamma spectroscopy, tritium, and alpha samples prJ.or to starting the release. Analyses must be completed within a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period following the initiation of a discharge. An "emergency" is a condition where plant floodin§, personnel injury, or damage to plant equipment are likely based on plant conditions. AR 0196701 g, Site Evaluation for Expediting South Pond Releases (May 2014), provides site documentation and justification that the effectiveness of the radioactive effluent control program is not reduced by the change.

REVISION NO.:

50 PROCEDURE NO.:

PROCEDURE TITLE:

_. OFF SITE DOSE CALCULATION MANUAL (ODCM)

C-200 ST. LUCIE PLANT ADIOA-CTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with St. Lucie Plant rs 6.8.4.fA) ano 6.8.4:f.5), the dose or dose- -

commitment.to a MEMB~R OF THE PUBLIC from radioact1ve materials in liquid effluents released,-trom each unit-, to UNRESTRICTED AREAS (see TS Figur.e-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 a!'.ly organ and

b. G>uririg any calendar-year to less than_or equal to 3-mFems to the wnole-body and to less than-m 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 says, 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 tl:!e proposed corrective actions to be-taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.1-1.1.2 Cumulative-dose co.ntributions 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.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RAD10ACT1VE EFFLUENTS LIQUID RADWASTE -TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with St. Lueie 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 rele-ases of radioactivity when the projected d0Ses due t-o the liquid effluent, from each unit, to UNRESTRICTED AREAS (see-TS Frgur:e.5.1-1)_would exceed-0.06 mremto the whole body er 0.2 mrem to any organ in a 31-day period.

~l~PPLICABJUTY: 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 t0- restore the inoperable equipment to_ OPERABLE status_

an.cL

3. Summary _description of action{s) taken Jo prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.1-1.1.3.1 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 Liqu1d 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.

REVISION NO.: PROCEDURE TITLE:

1 PROCEDURE NO.:

C-200 ST. tUCIE PLANT

. 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 Eiose rate_resu!ting from-radioactive materials released in gaseous effluents to areas at or be.yond the SITE BOUNDARY (see TS-Figure 5.1-1-) shall be limited to the-following:

a. For-=i:ioble gases: Less than or equal to 500 mrems/yr-to thelotal body and less than-or equal to 3000 mrems/yr to the skin and

-b. For lodine-131, for lodine-133.,_for tritium and for all radionuciices in particulate form with *half-lives greater than 8 days: Less than or equal to 1509-mrems/yr to any organ APPLICABILITY: At all times.

ACTION:

a. With the-dose rate(s) exceeding the above limits, -1mmediately restore the release rate to within the abeve limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determir:ied to be within the above-limits in accordance with the methoElelogy and parameters-in the-ODCM.

4.11.2. 1.2 The dose rate due ta lodine-131, lodine-133, tritium and all radionuclides in particulate farm 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.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _--t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE-4.11-2 ,.

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANAL Y-SIS PROGRA (Rage 1 of3)

Gaseous Release Type

-Sampling Frequency Minimum Analysis Type of Activity Analysis b;iwer Limit of Detection

[

Frequency LLD 1 Ci/ml -

p p Noble Gas

1. Waste Gas Storage Tank* Each Tank ~0 .E-04 Each Tank P.G.E. (2)

Grab Sam le p p Noble Gas-1.E-04

2. Containment Purge (9) . Each Purge (6) -Each Purge (6) P.G.E. 2)

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

3. Vents:(9) 4/M 4/M (7) Noble Gas Grab Sample P.G.E. 2- 1.E-04

a. -Plant (8)

b. Fuel B-ldg (5) H-3 1.E";.06 C. S/G Blewdown Bldg.

4. All Release Types as listed in- 3. Continuous (3) above-(9) (8) 1-131 1.E-12 P.G.E. 1.E-11 Particulate Gross Alpha 1.E-11 Sam le

_I_ Q Composite Sr-89, Sr-90 1.E-11 Particulate Sam le NobleGas - Noble Gases Gross 1.E-06 Monitor Beta or Gamma

5. Cask Handling Facility Vent (8) w Noble Gas 1-. E-04 Grab Sample P.G.E. 2 (8) w H-3 1_E w Charcoal 1-1-31 1.E-12 Sample w

Particulate P.G.E. 1.E-11 Sam le Continuous (8)- w Particulate Gross Alpha 1.E-11 Sam le Q

Composite Sr-89, Sr-90 1.E..:11 Particulate s-ample P.G.E. - Denotes Prineipal Gamma Emitter

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 4~ n-2 ,*,._;; , , ,.

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM***

(Page 2 of 3).

TABLE NOTATIONS

!1) The LLD is defmed 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 blanR observation-represents a real signal.

i:;:or a particular-measurement system, which may include radiochemical separation:

4.66 Sb LLD = - - - - - - - - - - - - -

E *V* 2.22E + 06 *Y* exp(-k * .L\T}-

Where:

LLD = the a priori lower limit of detection (micro-Curie per unit mass or volume),

Sb = the standard deviation -of the backgrou-Rd counting rate or of the counting_cate of a blank S""c:lillple as approprrate (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, A = the radioactive decay-constant for the particular radionuclide (s.ec-1) and L\T = the elapsed time between the midpoint of sample collect1on and the time of counting (seG).

Typical values ofE, V, Y and ~T should be used in the calculation.

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

- REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 4.11-.2 RADIOACTIVE GASEOUS WASTE SAMP-LING AND-ANALYSIS PROGRAM (Page 3 of 3)

TABLE NOTATIONS-(continued)

(2) The principal gamma emitters for which the LLD-control applies include the following radionuclides: Kr-87, Kr-88, Xe-f33, Xe-133m; Xe-135 and Xe-138 in noble gas releases and Mn-54, Fe-59-, Co-58, Co-60, Zn=-65,_Mo-99, 1-131,-Cs-134-,

Cs-137, Ce-141 and Ce-144 in Iodine and particulate releases. This list does not mean that only these m:1clides 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 Centr:oL3-:-11.2.6 in the format outlined in Regulatory Guide 1.21, ARpenaix B, Revisioo 1, June 1974.

(3) The ratio of the sample flow -rate to the sampled-stream flow rate shall-be known-for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2 and 3.11.2.3.

(4) Samples shall be changed at least four times per month and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change excee.ding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48-hoars of changing. When-samples collecte-d 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 facter of 10. This requirement does r:iot apply if: (1) analysis shows_that the DOS-E EQUIVALENT 1-131 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.

(~) Tritium grab samples shall be taken at least 4/M from the ventilafion 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 ora THERMAL POWER change exceeding 15.% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the-DOSE EQUIVALENT 1-131-concentration in the primary coolant has not incr-eased 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.

(8) Frequencies applicable only when the ventilation system is operating.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT (9) During outages, tbe affected unit's containment equipment hatcl'l* is a poten 1a effluent pathway. Monitoring of the open containment equipment hatch is-performed as per procedural guidance. Any calculated Felease quantity will be:_reported in the annual report. RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES

-coNTROLS 3.11.2.2 In 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 eac;h unit, to areas at and beyond the SITE-SOUNBARY (see TS Figure 5.1-1) shall be limited to-the foUowin_g_:

a. During-any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less thar, or equal to 1-0 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 tt-'le calculated air dose from-Fadioactive nobie gases in gaseous effluents exceediAg any of the above limits, prepare and submit to the Commission within 30

-days, pursuant to Plant TS 6.9.2, a_Specia-1-Report that identifies the cause(s) for exceeding the limit(s) andc:lefines the corrective actions that have been taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIR~MENT'S

4. r1 .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.

REVISION- NO.: PROCEDURE TITLE:

OF-FSITE DOSE CALCULATION MANUAL (ODCM)

50 PROCEDURE NO.:

C-200 ST. LUCJ-E PLANT RADIOACTIVE EFFLUENTS DOSE- IODlNE-131, IODINE-133, TRITIUM-AND RADLOACTIVE MATERIAL IN PARTICU-LATE 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 lodine-131, loaine-133, tritiam-:and all rad1onuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each ur.1t, ta-areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-1) shall be limited to the following:

a. -DuriP.g any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar y_ear: Less than or eqtJal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of lodine-131, lodine-133, tritium and radionuclides in particulate-form with half-lives-§reater than 8 days, in gaseous effluents-axceeding-any-of the above limits, prepare and submit to the Commission within-30 aays, pursuant to Plant TS-6.9.2, a Specia!-R.eporflhat 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.

SURVEltLANCE REQUIREMENTS I 4.11.23 Cumulative dose contFibutions for the current calendar quarter and current calendar year for lodine-131-, lodir.e-133, tritium and radionuclides in particulat,e 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.

REVISION NO.: PROCEDURE TITLE:

1---------t 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE 8lANT RADIOACTIVE EFFLUENTS GASEOUS RAD-WASTE TREATMENT SYSTE~v1 CONTROLS 3.11.2.4 In accordance with St. Lucie Plant TS 6.8.4.f.6), the VENTILATION EXHAUST Treatment System and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of the system shall--=be used to-reduce releases of radioactivity_ when the prnjected doses in 31 days due to gaseous effluent releases, from eacl'l uriJt,lo areas at and- beyondJhe SITE BOUNDARY (see TS Figyre 5.1-1) would exceed:

a. 0.2-mrad-to air from .gamma radiation or

b. 0.4 mrad-to-ainrom beta radiation or

c. 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With radioact-ive gaseous waste-being discharged-without treatment and__:iil excess of the above.limits, prepare and submit to the Commission within 30 days,_

pursuant-to Piant TS 6.9.2, a Special Report tt:iat includes the foilowing information:

1. 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.

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o- - - - 1 OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT ADIOACTIVE EFFLUENTS GASEOUS RADWA-STE TREATMENT SYSTEM (c(:mtinued)

SURVEILLANCE REQUIREMENTS J

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 trre 0DCM when Gaseous Radwaste Treatment Systems are not bein§ fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM*=-shall be demonstrated OPERABLE by l operatingthe-VWtSTE GAS_HOLDUP S'iST-EM equipment and VENTILATION-EXHAUSTTREATMENT SYSTEM equipment for at least JO __

I minutes, at least e:mce per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

If the WAS+E GA.S HOLDUP SYSTEM is not being fully utilized, an Administrative FUNCTIONAL TEST on the WASTE GAS HOLDUP SYSTEM shall also be performed (in addition to the requirements sf 4.11.2.4.2's "arleast 39 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 lhe Gas Decay :rank to at least 150 psi.

3) Following appropriate holdup Eiesaytime, sample and release the Gas Decay Tank with an OPERABLE~Waste Gas HolE11:1p System Noble Gas Activity Monitor (per TABLE 3.3-13).

4) If discrepancies exist, repairs sh-all be made and t!:le WASTE GAS HOLDUP SYSTEM Administrative FUNCTIONAL TEST shall be repeated un-til completed successfully.

REVISION NO.: PROCEDURE TITLE:

50 t----------1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFl:UENTS 3i4.11.4 TOTAL DOSE CONTROLS 3.1-1.4 In accordance.with St-Lucie PlantTS6.8.4.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 sha-ll 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 tnan_or equal to 75 mrems.

APPtlCABILITY: At a!Uimes.

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 limjts. 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 urariium-ftiel cycle sources, incluEling all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered b¥ this report. It shall aJso describe levels of radiation and concentrations of radioactiv.e mater-ial involved and the cause of the exposure levels or coneentrations. If the estimated dose(s) exceeds the above limits and if the release condition res1:1lting in violation of 49-Part 190 has not already been corrected, the Special Report shall include-a- requesnor a v-ariance 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 th*e request is complete.

REVISION NO.:

PROCEDURE TITLE:

50 OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS 3/4.1l.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 4.1-1.2.3 and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contril;>utions from direchadiation from the units (including outside storage tanks etc.) and Independent Spent Fuel Storage Installation (ISFSI) shall be deteFmined in acc0rdance with the methodology_and parameters in the OBCM. This requirement is appHcable only under conditions-set forth in ACTION a. of Control 3-.11.4.-

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ 5_0_ _--t OFFSITE DOSE CAlCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS

~b/4.11.5 MAJOR CHAt\lGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT-SYSTEMS*

ADMINISTRATIVE CONTROLS 3.11.2.5 t.icensee initiated major changes to the radioactive waste_systems (liguid, gaseous and solid):

1) Shall be reported to !he Commission in-lhe Annual Radioactiv.e Effluent Release Report for the period in which the evaluation was reviewed by the On-.:Site Review Group (ORG). 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 TO 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 iR liquid and gaseous effluents and/or quantity orsolid waste that differ from those previously-predicted in the-iicense 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 exposureto plant OR._erating personnel as a result of the change; and h) Documentation of the fact that the change was reviewed and found acceptable by the ORG.

2) Shall become effective upon review and acceptance by the ORG.

Licensees may choose to submit the information called for in this Administrative Control as part of the annual FUSAR update.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _~ OFFSITE DOSE CALCUl:.ATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

- RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL HADIOACTiVE EFFLUENT RELEASE REPORT TO Tl:IE

-COMMISSI-ON*

ADMINlSTRATIVE CONTROLS

]~.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 t2 months--of-operation shall be submitted within 60 day_s after January 1 of each year. The report shall include a summary-of the quantities of radioactive liquie 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 confor-mance with 1O-CFR_50.36a and Section 1-V.B.1 of Appendix I lo to 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 l?ower 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 afteF January 1 of each year shall include-an-annual summary of hol:lfiy meteorological data collected over the previous year. This annual summary may be either iA the for:m of an hour-by-hour listing on-magnetic tape of wind speed, wind direction, atmosj;>heric stability and precipitation (if-measureq) 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 due-to the radioact~ve liquid and gaseous effluents released from the unit or station during the previous calendar year.

- 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.

REVISION NO.: PROCEDURE TIRE:

50 OFF SITE DOSE CALCULAT-ION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE-EFFLUENTS 3/4.11.6 ANNUAL RADIOACTNE EFFLUENT RELEASE REPORT TO THE COMMISSION* (continued)

ADMINISTRATIVE CONTROLS 3 ..11.2.6 (continued)

15. (continued)

This same report shall also include an assessment of the radiation doses from radioactive liquid _ar:id gaseous effluents to..,r?lEMBERS OF THE PUBLIC due to their activities krside 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, or an approximate and conservative method used in lieu of actual meteorological measurements. The assessment of radiation doses shall be performed in accordanee with the methodology and parameters in the ODCM.

c. Every 2 years using the previous 6 months release history for isotopes, determine the controili.11g age group for liquid pathways. Every 2-years using-t!:ie previous 1 year or longer interval (to include a refueling

-0utage) 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 th*e new groups in subsequent dosacalculations.

d. The Radioactive Effluent Release Report to be-submitted 60 days after January 1 of each year-shall also include an ass.essmentufradiation doses 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.

REVISION NO.: PROCEDURE TITLE:

____5_0_ _ _ OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADJ.OACTIVE EFFLUENT RELEASE REPORT T-0 THE COMMISSION* (continuecl)

ADMINISTRATIVE CONTROLS

3.11.2;6 (continued) .

e. The Radioactive Effluent Release Repmts sha~I include-the frnlowing inf0rmation for each class of-soHd waste (as defined by 10 CFR Pa~ 61) shipped offsite during the report period:

1. Volume

2. Total Curie quantity-(-specify whetl'.'!er 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, Tyµe B, Large Quantity) and

6. Solidification agent orabsorbent (e.g., cement, urea formaldehyde).

f. The Radioactive Effluent Release Reports shall include a list and description of unplanned releases fromthe site to UNRESTRICTED AREAS of radioactive mater~als in gaseous and liquid effluents made during the rep_orting period.

g. The Radioactive Effluent Release Reports shall indl:lde any cnanges-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.

REVISION !'JO.: PROCEDURE TITLE:

.,.__ _ 5_0_ _--1 OFF SITE DOS,E CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

. RADIDACTIVE EFFLUENTS 3/4.1-1-.6 ANNUAL RADIOAC"flVE EFFLtJENT RELEASE REPORT TO "FHE CDMMISSION* (continued)

ADMINISTRATIVE CONTROLS 3.11.2.6 {~ontinued) l j__ Beginning with the report due within 60 days after January 1, 2007, the Radioactive Effluent Release Report sflall includeJ:he-following J information for the previous year:

a. A listing with descriptions_of any-leaks or spills that have-been communicated-to State-and Local officials in accor-dance with the Groundwater Prorection 1NITIATIVE (NEI 07-07).

b. Gfeundwater sample results that have been takerr in support of the Groundwater Protection INITIATIVE (NEI 07-07), unless they are from locations that are described in the Radiological Environmental Monitoring Program and will therefore be reported in the Annual Radiological Environmental Operating Report (AREOR).

REVISION NO.: PROCEDURE THLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOLO_GICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING-PROGRAM

.CONTROLS 3.12.1 In accordance with- St. Lucie Plant TS 6.8.4.g.1), the Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1-.

APPLICABILITY: At all times.

ACTION:

a. VVith-the Radiological Environmental Monitorin~J Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the An!'.lual Radiologicai=Environmental Operating Report required by eontrol 3.12.4, a description of the reasons for not conducting the program as required and the pians for preventing a recurrence.

b. With the confirmed* level of radioactivity as the result of plant effluents in an environmental sampling medium at a location specified in Appendix B-1 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 Teduce radioactive effluents so that the potential annual dose** to a MEMBER OF THE PUBLIC is less than the calendar year limit of Controls 3.1 fA .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,-H1is report snall be submitted if:

concentration(1) concentration (2)

+ +>or= 1.01 reporting level ( 1) reporting Ieve~ (2)

A confirmatory reanalysis of fne original, a duplicate or a new sampJe may be desirable, as appropriate. The results of the confirmatory analysis shall se 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.

- - A copy of the 30-day Special Report shall be provided to the Radiation Protection Manager (or designee) so that it can be sent to State and Local Officials in TABLE-1 of HPP-101 concurrent with its submittal to the commission.

REVISION NO.: PROCEDURE TITLE:

1--------f 50 OFFSITE DOSE CALCULATION MANUAL-(ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RAE>IOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM Controls (continued)

ACTION:

b. (continued)

\7Yhen radionuclides other than those in Table 3.12-2.--are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose,

-to a MEMBER OF THE PUBLIC- from alrradionucl-ides 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 is not required if the measuredJevel of radioactivity was not the resulFof plant efflueRts; however, in such an event, the condition shall be reported-and-described in the Annual Radiological Environmental Operating Report required by Control 3. f2.4.

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, su!;>mit in the next Annual Radioactive Effluent--Release Report Eloeumentation for a change in the ODCM including a revised figure(s) and-table for the ODCM reflecting the new location(s) with supporting information identifyinfl the cause__of the unavailability of samples and justifying the selection of-the new Jocation(s) for obtaining samples.

SURVEILLANCE REQtilREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected 131:1rsuant to Table *3.12-1 -from the specific locations given in the table and figure(s) in the ODGM and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection.capabilities required by Table 4.12-i.

REVISION NO.: PROCEDURE TITLE: PAGE: ; _-_ ,}>

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 23 PROCEDURE NO.: 1:1i1li:i:'J; C-200 ST. LUCIE PLANT ){.: . ,..:,..,2 ,:

\.

TABLE 3.12-1 .

RADIOl:.OGISAL ENVIRONMENTAL MONITORING PROGRAMa)

(Page 1 of 3)

NUMBER OF SAMPLING AND TYPE AND EXPOSURE PATHWAY REPRESENTATIVE . -

COLLECTION FREQUENCY dJ anG!/or SAMPLE SAMPLES AND SAMPLE FREQl:JENCY dJ

- OF ANALYSIS LOCATIONSbJcJ

1. Direct RadiationeJ 27 Monitoring Locations Continuous monitoring Gamma exposure rate -

with sam!Jle collection quarterly

- - quarterly fJ

2. AirbornaRadioiodine Continuous sampler Radioiodine filter:

and Particulates 5 Locations operation with sample 1~131 analysis weei<iy collection weekly or more Particulate Filter:

frequently if required by Gross beta radioactivity dust loading analysis ;;::24 hours following a filter change9>-

-Gamma isotopichJ analysis of composite 9>

(by location) quarterly

3. Waterborne

a. Surfacek> 1 Locationm> Weekly Gamma isotopichJ &

tritium analyses weekly 1 Location"> Monthly Gamma isotopichJ &

tritium analyses monthly

b. Sediment from 2 Locations Semiannually Gamma isotopichJ --

shoreline analyses semiannually-

4. Ingestion

a. Fish and Invertebrates

1. Crustacea 2 Locations Semiannually -Gamma isotopichl analyses semiannually

2. Fish 2 Locations Semiannually Gamma isotopic h)

- analyses semiannually

-b. -Food Products

1. Broad le-af 3.LocationsP> ""Monthly when available Gamma isotopich) and vegetation 1-131 analyses monthly

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o_ _-4 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.12-1 RADIOLOGICA[;; ENVIRONMENiAL MONITORING PROGRAMa)

(Page 2 of 3)

TABLE NOTATIONS

a. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailabiHty, malfunction of automatic sampling_ equipment or other 1egitimate reasons. If-specimens are unobtainable due to sampling-equipment malfunction, corrective action shall be taken prior to the end of tt:ie next sampling period. All deviations from the sampling-schedule shall be documented in the Annual Radiolo_gical Environmental Operating Report pursuant to Control 3.12.4.

b. Specific-parameters of distance and direction sector fromihe-centerline of one reactor and additional descriptior:1 wbere pertinen4-shall be provided for each-sample location required by Table 3.12-1, in Appendix-Band appl-icable 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 onoe per calendar week. A maximum interval of 11 days is allowea t::>etween the collection of any two consecutive samples.

Semi-Monthly - Not less th-an 2 times per calendar month-with an interval of not less tnan 7 days between sample coilections. A maximum interval of 24- (fays is allowed between collection of any two consecutive samples.

Monthly - ~ot less than once per calendar month with "an inteNal of not less than 10 days between sample collections.

Quarterly - Not less than once per calendar quarter.

Semiannually - 0Re sample each between calendar .dates (Jan1:1ary 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.

REVISION NO.: PROCEDURE TITLE:

.,___ _s_o_ _~ OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

G-200 ST. LUCIE PLANT TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa>

(Page 3 of 3)

TABLE NOTATIONS-(contim1ed) 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 aadition to,

_integrating dosimeters. For _purposes of this table, a thermoluminescent dosimeter (TLD) is considered to-he one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. r

f. Refers to normal collectfon f-r--equency-. -More frequent sample-collection is permitted-L-when conditjons warrant.

g. Airborne particulate sample-filters are analyzed for gross beta radioact~vity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. In addition to _

the requirement for a gamma isotopic on a composite sample a gamma isotopic is also required for each sample having a gross beta radioactivity which is >1.0 pCi per cubic meters and which is also >10 times that of the most recent control sample.

h. Gamma isotopic analysis means the identificatior:i- and quantification of gamma-emitting-r-adionuclfdes that may be attributable to the effluents from the facmty.

k. Discharges from the -St Lucie Plant do not influence drinkrog 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 different offsite locations of highest predicted annual average ground level D/Q and one sample of - -

sim~arl>road leaf vegetation at an availa9le 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]

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-20Q ST. LUCIE PLANT-

'fABLE- 3-12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES (Page 1- of 1)

REPORTING LEVELS AIRBORNE FOOD WATER =PARTICULATE FISH MILK ANALYSIS PRODUCTS pCi/1 OR GASES pCi/kg, wet pCi/1 pCilhi;i pCi/kg, wet H 30;000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-69 300 10,000 Zn-65 -300 20,000 Zr-400 Nb-95***

1-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-200 3QO La-140*-u

- as in -J;)Ci1i denotes liter

Since no drinking water pathway exists, a value of 30,000 pCi/1 is used. For drinking water samples, a value o.f-20,000.pCi/l is used; this is 40 GFR Part-141 value.

- - Applies to drinking water pathway exists, 2 pCi/1 is the limit for drinking water.

- - An equilibrium-mixture of the parent daughter isotopes which corresJ:?onds to the repor:ting-value of the parent isotope.

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o_ _--t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT LOWER LIMIT OF DETECTION {LLD}-<3>

AIRBORNE FQOQ WATER PARTICULATE FISH MILK SEDIMENT ANALYSIS PRODUCTS pCi/1 OR GASES pCi/kg, wet pCi/1 pCi/kg, dry 3 pCi/kg, wet oCi/m Gross Beta 4 0.01 H-3 3000*

Mn-54 15 130 ..

Fe,,59 30 260 Co-58, 15 130 Co-60 Zn-65 30 260 Zr-95, 15 Nb-s5C4>

1-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0-:-06 150 18 80 180 Ba-140; 15 15 La-14gC4>

No drinking water pathway exists, a value of2000 pCi/1 is for drinking water.

- LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCi/1 may be used.

TABLE- NOTATIONS - -

(1) Thfs list dees Rot mean that on.i'y these-nuclides are to t>e 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 pursuanno Control 3.12.4.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

- <5.).* ,*'<,.'{:0;]:i~:)1~./

TABLE-4.12-1:- ~" .*** .

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYS1s< 1><2r (Page 2 of 2)

TABLE NOTATIONS (continued)

(3) The l=LD 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 concii.Jding that a blank observation represents a real signal.

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

LLD =

E

V

2.22

Y

exp (-A * .lff)

Where:

LLD = the a prior:i l0wer limit of detection (pico-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 (.J.1r:iits of mass or volume),

222 = the number of disintegrations per-minute..per pico-Curie, y = the fractional radiochemical yield, when app!-i£able, A = the radioactive decay constant for the particular radionuclide (sec- 1) and h.T = the elapsed time between-the midpoint of sample collection and the time of counting (sec).

Typical va~ues of E, V, Y and ti T should be- used in the calculation.

It should be re_cognized that the LLB is defined as an g priori (before the fact) limit representing_ the capability of a-measurement system and not as an g posteriorJ (after the fact) limit for a particular measuremenl Analyses shall be performed in such a manRer that the stated Ll.::Ds wilt 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.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

ST. LUCIE PLANT

- RADIOLOGICAL ENVIRONMENTAL MDNITORIN-G 3/4.12.2 LAND USE CENSUS CONTROLS-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 ifl 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£ontrol 3.12.1, ad.crtne new location(s) within 30-days to theRadjological Environmental Monitoring Program given in the ODGM. The samplin~ location(s), excluding the control station locafien, having the lowest calculated dose.or dose commitment(s)_,

via the same exposure pathway, may be deleted fr:om 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 AnnuaLRadioactive Effluent Release Report-documentation for a change.in the 0DCM includ1ng a revised figure(s) and table(s) for the-ODCM reflecting the new location{s-) with information supporting 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.

REVISION NO.: PROCEDURE TITLE:

50 OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST.-LUCIE PLANT RADIOLOGICAL ENVIRONMEN"f-AL MONITORING 3/4.12.2

LAND USE CENSUS (continued~

SURVEILLANCE:: REQUIREMENTS 4-: 12.2 The Land -Use Census shall be_ conducted during the growing season at least once per 12 months-using that information that will provide the best results, such as by a door-to-door survey, aerial survey Oi-by consulting local agriculture-authorities. The results of tbe Lar:1d Use Census shall be- included in the-Annual Radiological Environmental Operating Report pursuant to Control-3.12.4.

REVISION NO.: PROCEDURE TITLE:

l - -_ _ s_o_ _--4 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 *ST. LUCIE PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 IN'fERLABORAl=-ORY 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, suppi*ied as part of an lnterlaboratory Comparison Program that correspond-to samples required by Table 3.12-1.

APPLICABILITY: AraWtimes.

ACTIGN:

a. -with analyses not-being performed as required above, report the correcffve actiorr taken to prevent a recurrence to the Commissior:Lin the Annual RadioJogical 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 ln!erlaboratory Comparison Program shall-be included in the Annual Radiological Environment.a~ Operating Report purSYant to*-control 3.12--A. If the lnterlaboratory Comparison PrQgram is-other than_the program conducted by the DOE-Mixed Analyte-Performance Evaluation Program (MAPEP), then..ihe lnterlaboratory Comparison Program-shall be describee- in the ODCM.

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C-200 ST. LUCIE-PLANT

- RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)*

ADMINIS:t:RATIVE CONTROLS 3.12.4 In accordance witb St. Lucie Plant TS6.9.1.ll, an Annual Radiological Environmental Operating-Report-covering the operation of the unit during the previous calendar _year shall se submitted before May 1 of each year. The report shall incluae summaries, inte~pretatibns and information based on trend analysis of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided in the AREGR shall be cc,nsistent with -

the objectives outlined below and with Sections IV.B.2, IV.B.3 and IV.C of 1_

Appendix I to 1Q-GFR 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-requir..ed by Control 3.12.2.

Tbe Annual Radiological Environmental Operating Be.ports-shall include-the results of

- analysis of all radiological environmental samples and-of all environmental radiation measurements taken d1c1ring the period-pursuantlo the locations specifiea -in-1he 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 submittea noting and

- expJaining the r:easons for the m{ssing results. "Ehe missing data sha-H be submitted as soon as possible-in a supplementary report.

The Annual-Radiological Environmental Operating Report shall also include the r-esults of

_the analyses for all samples that-have been added to the Radiological Environmental Monitoring Program in supportef the-Groundwater Protection INIT1ATIVE (NEI 07-07)-

Appendix B-2.

- A single submittal may be made for multiple unit station.

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50 t----------t OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOLOGICAL ENVIRONMENTAL MONl"fORING 3/4.12.4 ANNUAL RADIOLOGICAL ENVIRONMEN"fAL OPERATING REPORT (AREOR)* (continued)

ADMINISTRArlVE CONTROLS The reports shall also include the following: a summary description of the radiological environmental monitoring program; at- least two legible maps** covering all sampling 1ocationsc-keyed to a table giving-distances and directions from the-centerline of one reactor; the results of the lnterlaboratory 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.

i REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 OFF SITE DOSE CALCULATION MAf\JUAL (ODCM)

ST. LUCIE PLANT SASES FOR "friE CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES conta~ned in s1:1cceeding pages s1:1mmarize the-reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.

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C-200 ST. LUGIE PLANT INSTRUMENTATION-BASES 3.3.3.9 RADJOACTIVE LIQUID-EFFLUENT MONITORING INSTRUMENTATION The radioactive liq11id-effluent -instrume11tation is provided tQ monitor and control, as applicable-, the releases orradioactive materials in liquid effluent during actual or potential eleases of li~uid-effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and .aajusted in accordance with the methodology and parameters in the ODCM to ensure that the- alarm/trip will occur prior to exceeding the limits of 10 CFR Part

_20. The OPERABILITY and use of this instrumentation is consistent with the req.uiremeRts of General Design Criteria 60, 3-and 64 of Appendix A to~1-8 CFR Part 58.

3.3.3. 1-(:)- RADIOACTIVE GASEOldS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided-to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of GeneraJ De=:sign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

. REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

ST. LUCIE PLANT 3/4.11 RADIOACTIVE EFFLUENTS BASES-3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCEN1RATION This control is pr.ovided to ensure that the concentration of radioactive materials released in liquid waste efflue!"lts to UNRESTRICTED AREAS will be less than t!:ie concentration levels specified in 10 CFR Part -20,-.l\ppendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNREfffRICTED AREAS-will result in exposures-within: (1-) the Sectior:i 11.Adesign

_ objectives of-Appendix I, 1-0 CFR Part 5G; to a MEMBER OF THE-13tJBLIC and (2) the

. limits of 1O* CFR=Part 20. The concentrati0n 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 tabulate-d in terms of the lower limits of detection (LLDs). Detailed-discussion of the LLD and other detection limits carrbe found in Currie, L.A., Lower Limit-ef.Detection:.

Definition and* Elaboration of a Proposed Position for RadiolQgical Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984)_ and in the HASL Procedures Manual, HASL-300.

374~11.1.2 _ -oosE his control is 1:>rovided to implement the requirements of Sectioos 11:A, Ill.A and IV.A-of Appendix-I, 10 CFR Part so~ Tbe Control implements the guides set forth in Section II .A

- of Appendix I. The ACTION statements provide the required operating flexibility and a-t-the same time -implement the guides set forth in Sectjon 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 r..easonable 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 methodology and parameters in the ODCM implement the requirements in Section Ill.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.

l

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C-200 ST. LUC!EPLANT 3/4.11 RADIOACTIVE EFFLUENTS* (Continued)

BASES

- 3/4.11.1- LIQUID EFFU:JENTS (Continued) 3/4.11.1.2 DOSE (Continued)

The equatiens specified-in the ODCM fm calculating_the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the metAodology provided in Regulatory Guide 1.1-09, CaJculation 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 A-quatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 197T.

This control applies to the release of radioactive materials in liquid effluents from each unit at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system.

3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be avail-able for use whenever ltquid effluents require treatment~prtor to release to the environment. The requirement that the appropriate portions of this system be-used whe!'.1-specified provides-assurance that the releases of radioactive materials in-liquid effluents I

_will be kept as low as is reasonably achie-vable. This contr-ol implements the requirements of 10 CFR 50.36a, General Design Criter-ion-60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix no 10 CFR Part 50.

The specifiedJimit-s governing the use of appropr~ate portions of the liquid Radwaste Treatment System were specified-as a suitable fraction of the dose design objectives set forth in Section ti.A of Appendix I, 10 CFR Part 50 .for liquid effluents.

TA-is control applies to the-release of radioactive materials in liquid effluents from each unit at the site. FoF _units-with shared Radwaste Treatment Systems, tl:ie liquid effluents from the shared ..system are to be proportioned among the units sharingJhat system.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ ___. OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS BASES

]

3/4-.11.2 GASEous-EFFU:JENTS 3/4.11-2.1 DOSE RATE

+his control is-providedlo e!'.lsure that the dose at any time at and beyond the SITE BOUNDARY from gaseous-effluents from a!I 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 tl:iatradioactive material

- dischar_ged in gaseQUS effluents will not .result irrthe exposure of a MEMBER -OF THE PUBLIC jn an UNRES"FRICTED AREA, either within or outside the SITE BOUNDARY, to an annual average concentration exceeding the limits-specified in Appendix B, Tab1e 2 of 10 CFR Part 20 (Subpart D of 10 CFR Part 20). For MEMBERS OF_THE-J=>UBLIC 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 80 mrems/year to the total sody er 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 U1an or equai-to 1500 mrems/year.

This control applies to the release of radioactive materials in gaseol:ls effluents from alt units at the site.

The required detection capabilities for radioactive materials in gaseous wast-e sampies are tabulated in terms of tne lower limits of detection (l:LDs). Detailed c::iiscussion of the L.:LD and other detection limits canoe-found in Currie, L.A., Lower Limit of Detection~

Definition and Elabor-ation of a Pro13osed Position for Radiological ~ffluent and-Environmental Measurements, Nl::IREG/CR-4007-(September -1984) and irr the-HASL Procedures Manual, HASL-300.

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50 OFF SITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 BOSE - NOBLE GASES rhis control is provided*to implement the requirements of Sections 11.B, Ill.A and IV.A of

~Appendix I, 10 eFR Part-50. The controrimplements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required_operating*flexibility and at the same time implement-the guides set forth in Section IV.A of AppeAdix I to assure tbat the releases of radioactive material in gaseous-effl~ents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. The Surveillance Requirements implement the requirements in Section +1-1-.A of.A1wendix-l that conformance-with the guides of Appendix-I be-shown-by calculatioR*al procedures based on .models and data such-that the actual exposure-of a-MEMBER 0-rTHE PUBLIC through appropriate pathways is unlikely to* be _

substantially underestimated. The dose calculation methodok.lgy and. parameters established in the ODCM for calculating the doses due to the actuaLrelease-r-ates 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 atmospher~c conditions.

This csntrol 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.

3/4.11.2.3 DDSE-JODINE-131, IODH-.JE-1-33, TRITIUM-AND RADIOACTIVE MAT:.ERl"AL IN PARTICULAiE FORM This control is. provided to implement-the requirements of Sections-11.C, Ill.A and IV:A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section 11.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-mat tile

. 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 Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix 1 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.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS BASES 3/4:-11.2.1 DOSE - NOBLE GASES (£ontinued) 3/4.1-1.2.3 DOSE- IODtNE-131 IODTNE-133 TRITIUM AND RADIOACTIVE

.MATERIAL IN-PARTICULATE FORM (Continued)

The ODCM calculafional methodology and parameters for calculating the doses due t0 the actual release rates of the subject material are-consistent with the metnodology 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, Appe...adix.1, Revisio.rr 1, October 1977 and Regulatory Guide 1.111-, Methm:Js-for Estimating Atmospheric T-ransp0rt and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reacters, Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical av.erage atmospheric conditions. The release rate controls for lodine-131, lodine-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 animals and meat producing animals graze with consumption of the milk and meat by man and (4) deposition on the ground with subseEJuent 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 shareci-system are proportioned among the units sharing that system._

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50 OFF SITE DOSE CALCULATION MANUAL (ODCM) t----------t PROCEDURE NO.:

C-200- ST. LUCIE PLANT RADIOACTIVE EFFLUENTS BASES 314.11.2.4 GASEOtJS RADWASTE TREATMENT SY-STEM

-The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMEt~T SYSTEM ensure that tne systems will be available for use wheneve[ §aseous effluents -require treatment prior to release to tbe environment. The requirement that the appropriate portions of these systems be-used, wheA specified,

- provides Feasonable assurance that the releases of ra-eioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This control.implements the requirements of 10 CFR 50.36a,Gener:al Design-Criterion 60 of Appendix A to 10 CFR Part 50 aRd the design-objective given in Section ifD 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 dos-e design objectives set-forth in Section 11.B and 11.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 controris provided to meet the dose limitations of 10 CFR Part 190 that have been Jncorporated tnto 1ff CFR Part-2Q 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 t.o radia11on from uranium-fuel cycle sources exceed 2§-rnrems 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 hi§hly *anlikely that the resultant dose to a MEMBER OF :rHE PUBLIC wiH exceed the dose limits-of 40-CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, 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 of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT RADIOACTIVE EFFLUENTS BASES 3/4.11.4 l=OTAL GOSE (Continued)

For the purposes of the Special Report, it may 5e assumed that the dose commitment to t!:le MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the-exception that dose contributions from ether nuclear fuel cycle facHilies 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 reqµest for a variance (provided the release conditions resulting in

__ viola~i?n of 40 CFR Part 190.have n~t already_ been .corrected)..'. i~ accor~ance witn the 1prov1s1ons of 40 CFR 190.11 and Subpart M of 1Q CFR Pa1:t2u~ 1s considered to be a "timely-request and ftilfills-the requirements of 40 CFR Part 190 until NRG staff action is completed. The variance only relates to the limits-of 40 CFR Part 190 aP.d-does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as..addr:esseEi-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.

L

REVISION NO.: PROCEDURE TITLE:

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C-200 ST LUCIE PLANT 3/4..12 RADIOLOGICAL ENVIRONMENTAL-MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides 0

representative measurements nf radiation and of radioactive materials in those-exposure pathways and for those radioauclides that-lead to the highest potential radiation exposure gf MEMBERS OF THE PUBLIC resulting from~the plant operation. This monitorir.g pro§ram implementsSection IV.B.2 of Appendix I to 1O-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 higfler than expected on -the basis of the effluent measurements and the modeling of the environmental exposure-patriways. 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 optimt1m-for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an ~ priori (before the fact) limit representing the capability of a measurement system and not as.an £!-posteriori (after the

_fact) limit for a particular measurement.

Detailed d~scussion of the LLD and other detection limits can_be found in Currie, L. A.,

Lower Limit of Detection: Definition and Elaboration of a ProQosed Position for Radiotogical Effluer:if and Environmentai*Measuremerits, NUREGICR-4(:)07 (September 1-984) and in-the HASL Procedures Manual, HASL-300.

3/4.12.2 LAND USE CENS1:JS

_[fhis control-is provided to ensure that char:tges in the use of areas at.and be_y0nd the SFTE BOUNDARY are identified and that-modifications to the RadioiogicaLEnvironmental Monitoring Program given in the ODCM are made if required by the results ofthis census.

The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used.

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C-200 ST. UJCIE PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.Z LAND USE CENSl:JS (Continued)

This census satisfies the requirements of-section IV~B.3 of Apper.dix I to- 10 CFR Part 50.

Restrictir:tg the census to gar-dens -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 requireel to produce the- quantity (26 Kilagrams/y_ear) 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-§rowing 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 - lNTERLABORATORY COMPARISON PROGRAM This requirement for participation in an approved lnterlaboratory 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.

REVISlON NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 OFF SITE DOSE CALCULATION MANUAL (ODCM)

ST. LUCIE PLANT METHODOLOGY SECTION METHODOt:OGY for the CONTROLS AND SURVEILLANCE REQUIREMENTS

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION rT

2 GLOSSARY

OF COMMONlY USED TERMS IN METHODOLOGY SECTION (Page 1 of 3)

Ds Dose from Beta Radiation CC or cc Cubic ceAtimeter Ci Curies - a unit of radieactivity see µCi

- Activity or concentration of a nuclide in the release source. Units of µCi, µCi/cc or µCi/ml CFR Code of Federal Regulations Control(s) Regulations for operating, controlling, monitofing and reporti11g radioactive effluent related activity as indicated by the Controls Section of the OG8M.

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 or:gan uptake are some of the fact-ors that determine a dose factor for a given nuclide Dose Patl'lway - A specific path that radioactive material physically* travels through prior k>-exposing an individual to -radiation. The Grass-Cow-Milk-lhfant is a dose pathway Dose Rate - The dose-received per uninime (D/Q) - -A long term D over Q_- a factor with units of 1.fm2 which describes the deposition of particulate matter from_a plume at a point dow11r:ange 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.

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

REVISION NO.: PROCEDURE TITLE:

50 OFF SITE DOSE CALCULATION MANUAL (ODCM)

t.

PROCEDURE NO.:

-C-200 ST. LUCIE PLANT METHODOLOGY SECTION Ti;;,:

GLOSSARY OF COMMONLY USEB TERMS IN METHODOLOGY SECTION (Page 2 of 3)

Ground Plane Radioactive material deposited .uniformly over the ground emits radiation *that pr.oduces -an exposure pathway-when an inciividaal 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 QDCM.

H.,,3 Hydrogen-3 or Tritium, a weak Beta emitter

-IJ&BDP Radioiodines arid particulates with half-lives greater than 8 days

-1~ 3 Cubic Meters m2 - Square Meters

- nuclide For the pur~oses of this manual, a radioactive isotope. Nuclide (i) signifies a specific nuclide, the 1st, 2nd, 3rd one under consideration.

If nuclide (i) is 1-131, then the Mi (dose factor) under consideration should be M1-131 for example.

Organ For the ODCM either the bone, liver, thyroid, kidney, lung, GI-LLI or the Whole Body. Whole Body is considered an organ for ease of wrtting the methodology in the ODCM.

pCi 1-pico-Curie = 1.E-12 C-uries.

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

Qi Denotes µCi 0f nuclide (i) released over a specified time interval.

Radioiodines lodine-131 and Iodine 1-1-33 for.gaseous release pathways.

Receptor - The individual receiving the exposure in a given location or who ingests food products fr:om 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.

TS - The St. Lucie Plant Standard Technical Specifications Total Body - Same as Whole Body in Control Statements

µCi micro Curies. 1 µCi = 10-6 Curies. The µCi is the standard unit of radioactivity for all dose calculations in the ODCM.

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t - -_ _ s_o_ _--1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

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C-=200 ST. LUCIE PLANT METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION-(Page 3 of 3}

(X/Q) - A long term Chi over Q. It descr-ibes the physical dispersion characteristics oJ a sem1-infinite cloud of noble gases as tbe cloud traverses dnwnrange .from-the release-po1nt. Since f'\Joble Gases are-inert, they do not tend* to settle oat on the ground.

-(See Appendix C).

- A long term Depleted Chrover Q. It des.cr:ibes the physical di~persion *characteristics of a-semi-infinite cloud of radioactive iodines and particulates as the cloud travels downrange. Since Iodines and particulates tend to settle out (fallout of the cloud) on the ground, t!:le (X/Q_)D represents-what physically remains otthe cloud and its dispersion qualitie-s-at a~given location -downrange from-the release point. (See Appendix C).

dt, M or delta t - A specific delta time interval that corresponds with the release interval data etc.

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C-200 ST. LUCIE PLANT METHODOLOGY SECTION 1.0 LIQl:.IID RELEASES METHODOLOGY 1-.1 Radioactive L.iquid- Effluent Model Assumptions -.

The FU SAR contains the official descr:iption of the site characteristic~ The description that follows is a brief summary for dose calculation pwrposes:

The-St. Lucie_Plant is located on an islamisurrmmded on two sides by .the Atlantic Ocean and the Indian River, an-estuary of the Atlantic Ocean.

Normatjy, all raeioactive Liquid releases enter the-Atlantic Ocean where the r

Circulating Water Discharge Pipe terminates on the ocean floor at a point approximately 1200 feet offshore (Figure 1.,,.1 Point "L"). No-eredit is taken

-for subsequent mixing of the discharge-flume witf:1 the ocean. The diffusion-of radioactive material into the ocean is deper-1G!en.t0n the conditions of tide, wind and some ed.cly currents caused by the GulfStream. The..conc:litions 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 sup.ply of circulating water to ttie Intake Cooling Water Canal in the event a Hurricane causes blockage of the Intake Canal.

No radioactive water from plant systems could be discharged directly into

-the Intake Cooling Water Canal because all planfpiping is routed-to the discharge canal and no back flow can occur. However, dilute secondary sources from s1;1ch outfalls as the industrial wastewater system and construction dewatering may be pumped to the Intake Canal. These secondary sources would be secured under _tf:le extraordinary conditions that would precede opening the dam. Consult the FUSAR for a detailed description of characteristics of the water bodies surrounding the-plant site.

Only these nuclides that appear in the Liquid Dose Factor Tables will be considered for dose calculation.

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C-200 ST. LUCIE PLANT

-METHODOLOGY SECTION 1.2 Determtning the Fraction F of 10 CFR Part 20 ECLs Limits for A Liquid Release Source Discussion. - Control 3.11.1.-1 requ-ires that the sampling and analysis-results of liquid waste (prior to-discharge) be usedw1th calculation methods in-the in-plant proceaures to assure-that-the concentration of liquid radioactive material in the unrestric;;ted areas will not exceed-ten times the concentrations specified in 10-CFR Part 20, Apperrdix B, Table=2. CY:.SL~102-0104, Precessing 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 th.is determination. This method only addresses the calculation for a specific release sotJrce. The in-plant procedures will provide instructions for-determining that the summation of-each release source's~ values do not exceed the site's 1-0 CFR Part

_T 20 EGL. The values for release rate, dilutior rate, etc., will also have to be obtained from in-plant procedtires. The basic equation is:

n R Ci FL=- r D i= (EGL )i 1

Where:

FL =- the fraction of 10 CFR Part 20 EGL that would result if the release source was_discharged under the conditions specified.

R =- The undiluted release r-ate in gpm of the release source.

Liquid Rad Waste = 170 gpm for Waste Monitor T-ank Steam Generator = 125 gpm/Steam .Generator.

Liquid Rad Waste= 60 gpm for AWST #2 Liquid Rad Waste = 60 gpm for Laundry Drain PumJ>S 2A/2B o- = The dilution flow in gpm of Intake Cooliflg Water or Circulating Water Pumps Intake Cooling flow-is 14,500 gpm/pump Circulating Water flow is 121,000 gpm/pump Ci = The undiluted concentration -of nuclide (i} in µCi/ml from sample assay (ECL)i = The Effluent Concentration Limit of nuclide (i) in µCi/ml from Table L-1.

For dissolved or entrained noble gases the EGL value is 2 X 10-4 µCi/ml for the sum of all gases.

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C-200 ST. LUCIE PLANT METHODOLOGY SECTION 1.2 Determinin§ the Fraction F of 10 CFR Part 20 EC Ls Limits for A Liquid Release Source (continued)

The fraction ofthe 10 CFR Part 20 EGL limit may be-determined by a nuclide-by-nuclide evaluation or for pmposes-of simplifying the calculation by a camulative activity evaluation. If the simplified method is used, the value of 3 X 10-8 µCi/ml (unidentified_ECL value) should be substituted~for (ECL)i and the cumulative concentration (sum-.:of all ident~fled radionuclfde .concentrations) or the gross concentration should be substituted lor Cj. As long as_ the diluted

-Goncentration -(Ctota1 RtD) is-less than 3 X 10-8 µCi/ml, the nuclide-by-nuclide calculation is not required to demonstrate compliance with the 10 CFR Part 20 EGL.

The follewing section provides a step-by-step procedure-for determining the EGL fraction.

1. Calculation Process for SGlids 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-ECi), the undituted assay value of nuelide (i), in µCi/ml. If the

~simplified me!bod is used, the cumulative concentration (Ctota1) is used.

_O. -From Table L-t obtain- the- corresponding (EGL) for nuclide (i) in

µCi/ml. The value of 3 X 10-8 µCi/ml should be used-for the simplified

-method.

E. Divide Ci by (ECL)i and write down tne quotient F. ltihe simplified method is used, pmceed to the next step. -If determining the EGL fraction by the nuclide-by-nuclide evaluation, repeat-steps 1.2.1.C through 1.2A .E for each nuclide reported in the assay, for H3 from previous month composite and for SR89/90 and Fe55 from previous quarter composite with -known results.

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C-200 ST. LUCIE PLANT

-METHODOLOGY SECTION 1.2 Determining the Fraction F of 10 CFR Part 20 EC Ls Limits for A Liquid Release Source (continued)

1. Calculation-Process for-Solids (coRtinued}

G. -Add each C/(ECL) quotient from step 1.2.1.E and solve for FL-as follows:

n R Ci

-FL=- L D i= (EGL) i 1

FL= ,Lunit-less value where:

the value of FL could be:::; or >1. The purpose of the calculation is to determine what the initial value of FL is for a given set of release conditions.

H. The FL value just obtained is for one release pathway. The TS and ODCM control 3.11.1.1 allow for a site limit of FL less than or equal to

10. Chemistry Procedure CY-SL-102-0104 administratively Gontrols each pathway's allocation. Compare your FL result with the

-administrative control for_the release pathway in CY-SL-102-0104.

2. Calculation Process for Gases in Liquid A. Sum the µCi/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:

_ (Sllm of 1.2.2.A) µCi/ml X R-F9 - 1 . D C. F9 shall be less than 2 X 104 pCi/ml for the site for all releases in progress. Each release point will be administratively controlled.

Consult CY-SL-102-0104 procedure for instructions.

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50 OFF SITE DOSE CALCULATION MANUAL (ODCM) t----------f PROCEDURE NO.:

C-200 ST. tUCIE PLANT METHODOLOGY SECTION

-1.3 Determining Setpo-i-nts for Radioactive Liquid Effluent Monitors 1.3.1 Setpoints for Batch Liquid-Release Monitors channel numbers R6627 and 301 on Table 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 Gr trip so that !he radioactivity concentration in water in the unrestricted area does not exceed the concenttatiem of 10 CFR ParL20, 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 fo(Batch Liquid-Effluent Monitors based-on.a composite of-real-release data. A direct corre!ationJJetween gross cpm and the concentrations that would achieve 10 CFR Part 20 ECL levels in the discharg~ 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:

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C-200 ST. LUCIE PLANT METHODOLO~GY SECTION 1.3 Determining Setpoints-for Radioac1ive Liquid Effluent Monitors (continued)

NUCLIDE SYMBOL 197-8 UNDILUTED µCi/ml 1 M? (no units) 1-13=1 4.43 E-5 3.66 E-4 1-132 1-133 2.23 E-7 3*.17 E-6 1.84 E-8 3.74 E I 1-135 1.31- E-6 '3.61 E-7 Na-24 1.72-E-7 2.8zi E-8 Cr-5-1 2.51 E-5 4.15.E-7'.

Mn--54 5.64 E-6 1.55 E-6 Mn-56 1.11 E-9 1.31E-10 eo-57 3--69 E-7 5.0S-E-8 Co-58 1.51 E-4 6.24 E-5 Fe-59 2~92 E-6 2.41 E Co-60 3.66£-5 1.01 E-4 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-187 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 &5 1.17 E-5 Zr-97 4:05 E-6 3.72 E-S 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:"?

Cs-134 2.14 E-5 1.97 E-4 Cs-136 7.82 E::.7 -1.08 E-6 Cs~137 4.85 E-5 4.8"1 E-4 Ba-140 6.44 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 A1a1= 4.01 E-4 :; :*"':\. -'---, ..:,c::\;

_, -c;::;,:i:111::c:]i:1:r::' 0

:/- - :iii>ii:'iWI!li!:~

MTota1= 1.1-8 E-3 (1) 1978 Undiluted Release Volume = 7 E 9 ml.

M = 1978 Undil. Act Nuclide (i) X 1 gpm (release rate)

(2) 1 ECL(fromTableL-1) 121000gpm(dilrate)

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50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 1.3 Determining Setpoints for-Radioactive Liquid Effluent Monitors (continued)

ATot is the total average µCi/ml concentration of the reference-mixture and -MTot is the fraction of tbe MPC of all-nuclldes for the release-conditions specified. Dividing ATot by MTot yields AMax, which is the maximum total activity concentration ee:.iuivaleot to the-ECL limit for the nuclide distribution typical of radwaste discharges. The Technical Specifications allow 10 tTmes the ECL limit where-=the Site Limit is 10 times AMax as -follows:

4 4 AMax = A rot= .(l1 E- = 0.34 µCi/ml= ECL Limit Mrot- 1 . 18 E - 3 Site-Limit =-10 x AMax = 1Q x 0.34 = 34 µCi/ml To provide conservative administrative control, AMax of 0.34 µCi/ml-should be used as follows:

1. If the effluent monitor requires counts per minute units, a (Cmax) value in cpm should be obtained for the Amax (0.34 µCi/ml) from the release sources radioactive liquid effluent monitor curve of cpm vs. µCi/ml.

l'QOTE

]

This setpoint is for a specified release of 1-gpm into 121000* gpm dilution I flow.

2. For establishing the setpoint prior to li<:jt1id radwaste discharges, the Amax (or Cmax) 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-Mor:iit-or Activity Level}.

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C-200 s:r. LUCIE PLANT METHODOLOGY SECTION 1 :3 Determining Setpoints for Radioactive Liquid Effluent Monitors (continued) 1.3.2 SetpoJnts for Continuous Liquid Release Monitors Discussion - The activity mixture described-in 1.3~~ for L:iquid Batch-Release

.Monitors cannot be us.ed for Gol'.'ltinuous Liquid Pathways since the Steam Generator (SIG) Slowdown Secondary Side is-subject to what the current ReaGtor Coolant System (RCS) activity and-primary-to-secondary leakage exist at any time. Although SIG blowdown is not normally aligned to the Site Liq1;Jid Radwaste Release Po~nt (Figure 1-1), the monitor setpoints will be based on the OE>CM-maximum des1gn SIG blowdown rate of 125 gpm with 1 Circulating-Water Pump (CWP) 121,000 gpm in operation"'" The ODCM and CY-SL-~02-0-1-04, Processing Liquid Waste assume--tl:lat the fraction-of soiids ent-ering the Discharg_e Canal to the site reiease point are _

controlled less than or equal-to 1.0, with batch release using 80°/o and the remaining 20% allocated to continuous -sources on site. The aGtual site limit for-solids is 10 times the concentration specified in ~O- CFR Part 20, therefore a conservation factor of 10 is already included in the administrative site limit.

Since source in-leakage to a SIG cannot be controlled, a High alarm monitor setpoint is calculated based on one SIG releasing to the discharge canal at desiq_n blowdown rate while attainir:1g the 2o~percent of the site limit (FL) assuming all the gross solid activity is 1-131. The contribution from Dissolved and Entrained Gases is assumed ts-cbe zero with all of the gaseous activity going to the Steam Condenser and Air Ejector pathway.

FL at 20% = 0:2- = Design blowdown rate x 1-131 uCilml (SIG) 1 1 CWP Dilution rate 1-131 uCilml (Table L-1 ECL)

FL -at 20% = 0.2 = 125 gal/min x 1-1.31 uCi/ml (S/G) 1 121,000 gal/min 1.E-06 uCi/ml (1-131 Table L-1 ECL)_

Solving-for the S/G High Al-arm S_e.tpoint 1-131 Activity, 1-131 uCilml (SIG)= -2E-04-uCi/ml 1-131 is the maximum S1G activity that could be allowed such that 20 percent of the administrative discharge canal limit would not be exceeded.

This SIG Monitor High Alarm Setpoint activity may be converted to cpm using Liquid Monitor uClml 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 1-131 's ECL is conservative vs other isotope mixtures, and that it is unlikely that more than one SIG would be allowed to operate with a 20 gallon per day primary-to-secondary leak rate.

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C-200 ST. LUCIE PLANT METHODOLOGY-S.ECTION 1.4 Determining the Dose for Radioactive Liquid Releases Discussion - Control 3. tt.1.2 requires calculations be performed at least once-per 31 days to verify tha-t-cumulative radioactive liquid effluents do not cause a dose in excess of 1.5 mrem to the whole body and 5 mrem to_any or:gan.duFing any caiendar 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. I-1 This method is based on the methodology suggested by sections 4.3 and 4.3.1 of

-NUREG-0133-Revision 1, Nmrember, 1978. The dose factors are a composite of both the fish and shellfish pathways so that the fish-shellfish pathway is the-only pafnway for which dose will be calcti*lated. The-dose for adult, child and-teenager caP.-also be calculated by this-method provided that their appropriate dose factors are-used for the or.gan ofinterest. An-infant is excluded from Liquid Dose Pathway at St. Lucie since they do not eat fish-shellfish. The-effluent supervisor ,,vill track which age group is the controiling (most restrictive) age group-(see control 3.11.2.6.c). Only those nuclides that appear in the Tables of this manual will be considered. *

1. 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:

Where:

= dose commitment in mrem received by organ T of age 9roup (to be specified) during the release time interval dt1.

Ar. = the composite dose factor for the fish-shellfish pathway for n-uclide-{i) for organ T of age group (to be specified). The:Air values listed in the Tables-in this manual are independent of any site specific information and have-the units mrem-ml

µCi- hr dt1 = the number of hours that the release occurs.

On = The total quantity of nuclide (i) release during dt1 (µCi)

(DF)1 = The total volume of dilution that occurred during the release time period dt1 (i.e., the circulating water flow times time)

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C-200 ST. LUC!E PLANT METHODOLOGY SECTION 1.4 Determining the Dose for Radioactive-Liquid Releases (continued)

1. (continued)

The d-oses associated with each release may then_be summed-to provide the cumulative dose over a desired time period (e.g., sum all doses for releas_e during a 31 day period~ calendar quarter or a year).

Where:

Dn - the total dose commitment to organ T due to alLreleases dur-ing the desireEI time interval ~mrem)

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

A. Determine the time interval dt1in hours that the release took place.

For once per 31 day dose calculations dt1 would be for the entire month's hours.

For quarterly dose calculations dt1 would be the hour-s-in the quarter, and for annual dose calculations dt1wmlld be the hours in the year. If required, dt1may be hours of duration of a single release to evalt.1ate a batch release.

B. Obtain (DF)1for the time period dt1from Liquid Waste Management Records for the release source(s) of ir.iterest.

C. Obtain Qi for nuclide (i) for the time period dt1 from the Liquid Waste Management ReG9rd.s D. -obtain AT from the appropriate Liquid Dose Factor Table Age Group Dose Factor Table Infant N/A Child L-4 Teen L-3 Adult L-2

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C-200 ST. LUCIE 8lANT METHODOLOGY SECTION 1.4 Determining the Dose for Radioactive Liqt1id Release_s (continued)

1. (continued)

TABLE 1.4 FISH AND SHELLFISH PATHWAY TIME/DATE START: _ _:____/ _ / _ TIME/DATE STOP:-_ _ .____/_/_HOURS TOTAL DILUTION VOLUME: _ _ _ _ _ mls AGE GROUP: ORGAN: _ _ _ _ _ _ _ _ DOSE-FACTOR TABLE#: _ __

NUCLIDE (i) Ci (µCi) AiT DOSE (i) mrem TOTAL DOSE T =- mrem E. Solve for Dose (i)

Dose {i) = Oi1 dt1 AiT-(DF)1 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.

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C-200 ST. LUCIE PLA.NT METHODOLOGY SECTION 1.5 Projecting Dose for Radioactive Liquid Effluents Discussion - Control 3.11.1.3 requ1res that appropriate subsystems -of the liquid radwaste treatment system be used to reduce radioactive materia~ in liquid effluents when the pmjected doses due to the liquid effluent, from each un*t,-to UNRESTRTCTED AREAS (_see TS*Figure o.1-1) would exceed*0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day J'.!eriod. The. following calculation method is provided for performing this dose projection. The mettiod is oaseEI on_

dose as calculated in sectien 1.4 with the adult as the bases. for projecting.

1. For the controlling age group obtain the latest result of the monthly calculatio!=I of the whole body dose..-and the highest organ dose. These doses can-be obtained from the in-planLrec0rds.

2. Divide each dose by trre 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 identifiable operating conditions that could significantly alter the actual releases.

4. If the projected dose is greater than 0.06-mrem to the who*le body or greater than-(l.2 mrem to the adults highest exposed organ, t.l:!e liquitrradwaste system shall be used.

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C-200 ST. LUCIE PLANT

-METHODOLOGY SECTION 2.0 GASEOUS-RELEASES METHODOLOGY Z.1 Gaseous Effluent Model Assumptions Description of Site - (The FU SAR confains the official description of the site characteristics. "fhe description that foUows is a brief summary for dose cal_culation purposes on-ly). The St. Lucie Plant is located on an island sarrounded 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, divicled into 22.5° each. The MET tower is calibrated such that a zero degree---:hearirig coincides with TRUE NORTH.

A bearing of zero degrees...:dissects the north sector. such that bearings of 348. 75° and 11.25° define the boLJ-Adaries-of the.north sector. The nearest distance to J private property occurs in tf:'le north sector at approximately 0.97 mile&- For ease of calculation, this 0.97 mile radius is assumecLin 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, f976 and August 31, 1978, fr-om the St. Lucie MET Tower was analyzed by_Dames & Moore-of Washington, D.C. The methodology used by Dames & Moore was consis-tentwifh methods suggested by.Regulatory Guide 1.111, Revision 1. Recir..culation correction factors wer-e also calculated for the St. Lucie Site-and are incorporated inte the historical MET tables (Tables MS, M6 and M7) in Appendix A of this manual. It was determined that these tvvo years. are representative data for this locale.

Dose Calculations - Dose calculations for Control dose limits are normally calculated-using historical MET data and- r:eGeptor location(s) which yield calculated doses no lower than the real location(s) experiencing-me mest exposure. Actual MET data factors are calculated and are normally used in dose calculatiens for the annual reports. Approximate and conservative methods may-be used in !ieu of actual meteorological measurements.

Live MET data and hour-by-hour dose -cafoulations 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.

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C-200 ST. LUCIE PLANT MEi"HODOLOGY- SECTION 2.1 Gaseous Effluent Model Assumptions (continued)

Dose Calculations - (continued)

The St. Lucie site uses the tong 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 lodine-131 and 1-133 for application to Controls. Other-nuclides of loGline may*be included in dose calculations for ease of performing calculations, but their dose contribution does not have Jo 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-avold splitting quarters, -.e:tc.

2.2 Determining me Totai-Body and Skin-.oose Rates-for Noble Gas-Releases And Establishing Setpoints 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 .alar:m/trip setpoints are based on the dose rate calculations. The Controls apply-to all airborne releases on the site but alt releases may be t[eated as if discharged from a singie-release point. Only those noble gases appearing in Table G-2 will be considered.

Tne 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 DRTB = L Ki(X/Q) (Q DOT )i For TOTAL SKIN Dose Rate:

n DRskin = L [L + 1.1 M] (X/Q) (Q DOT )i

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C-200 ST. LUCIE PLANT METHODOLOGY SECTION

_2.2 Determining the TotaT Body and Skin Dose Rates for Noble Gas Releases And Establishing Setpoints for Effll.!ent Monitors (continued)_

Where:

DRrs = total bo-dy dose r:ate from noble-gases in airborne releases Emrem/yr-)

DRskin = skin dose rate from noble gases in airborne-releases (mremLyr)

~L I

= a mathematical symbol to-signify tbe operations to ttre right-of .the symbol-are to be performed for each noble gas nuclide (i) through (n) and the individual nuclide doses ares11mmed to arrive at the total dose rate for_the release source.

K = the total body dose factor-due to gamma emissions for each noble 3

gas nuclide reported in the release source. (mrem-m /µC.i-yr)

Li = the skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source. (mrem-m 3/µCi-yr)

Mi = 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 Mi ar.e in (mrad-m 3/µC-i-yr)

(X/Q) = for ground-level~ the highest calculated annual long-term historic relative conceAtration for any of the 16 sectors, at or beyond the 3

exclusion area boundary (sec/m )

(Q DOT-)i = The release r:ate of nobie gas nuclide (i) in µCi/sec from the release source of interest

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 OFFSITE DOSE CALCUl:.ATION MANUAL (ODCM)

ST. LUCIE PLANT METHODOLOGYSECT~N 2.2 Determining the Total Body and Skin Dose Rates for Noble *Gas Releases And Establishing Setpoints for Effluent-Monitors (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 O 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 be_eP.-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 percer:it 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-ir-1 Percent = 100%

Site Limit in uEi/sec = 3.5E+05 uCi/sec (Example)

Percent OD-CM Release Point Allotment Unit 1 Plant Vent 40

-lJ-nit 1 Fuel Bldg. Vent- 5 ECCS 1A 1 ECCS1B 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 S~te Limit

REVISION NO.: PROCEDURE TIT-LE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body and-Skin Dose Rates for Noble Gas- Releases And EstablishiAg Setpoints for Effluent MGnitors (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. l=he ECCS Reactor Auxiliary Building Exhaust are not ODCM required monitored release points, *but a small R_ercentage should be allotted to each to cover short periodic fan surveillance runs. This allocation is controlled per Chemistry-Procedure CY-SL-104-0:'.l 12, Determination of Proc;;ess-Radiation Monitor Setpoints where-Chemistry Supervisor approval is required. CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints 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. Obtair.1-the release point's maximum expected process flow release rate *(V")-in Cubic-Feet per Minute (cfm) from the Effluent Supervisor.

2. Obtain the release point's percent of_si!e limirallotment (PA)

-from the Chemistry Supervisor.

3-. Substitute the release point's V and PA values into the below equation(s) to obtain the Release Point's Setpoint (SP) in the desired engineering unit (uCi/cc or uCi/sec).

SP = -S.5E+05 uCi x 60 sec x min x ft3 X ...£00~fi1 tiCi/cc sec min V ft3 28317 cc 100%

SP= uCi/cc which is the TABLE 3.3-14 HIGH uCi/cc SETPOINT for ODCM Effluent Gas Channels that have a "Allotted% of Site Limit" declared as their HIGH SETPOINT.

SP = 3.5E+05 uCi x ...fM~~~L uCi/cc sec 100%

SP= uCi/cc uCi/cc

REVISION NO.: PROCEDURE TITLE:

t--_ _ s_o__- - 1 OFFSITE DOSE CALCULATION* MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body and Skin Dose Rates for Noble Gas Releases And Estahlishing Setpoints for Effluent MonitQrs (continued)

1. (continued)

A. (continued)

In the case of Unit 2 Plant Vennhere are 3 ODCM Effluent Gas Ghannels Monitoring the Plant Vent. The wide range-channel 624 HIGH SETPOINT in*

uCi/sec is equivalent to 2A PV PIG LOW RANGE GAS-ood 28 PIG LOW RANGE GAS channel 624 uses the equivalent-uCitsec_based on the l.:lCi/cc at the maximum expected process flow rate. Since they are monitoring the same release point (i.e., eaGh of these cha!"lnels does=not receive their own allotted % of the Site Limit). *

4. The significance of an ODCM Efflt1ent 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 CY-SL-102-0105, Processing Gaseous Waste shall-provide instruction for administratively controlling Batch Releases s1:1ch that the radioact~ve 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 radioactivity is approximately-equal to tbe 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".

setpoint in uCi/cc V or Vmax-ft3/minute vent flow SP= _____ uCi x 28317 cc x Vmax ft3 x minute uCi/sec (equivalent) cc ft3 minute 60 second SP= _____ uCi equivalent to a channel indicating a (uCi/sec) sec uCi/cc concentration assuming a volume release rate of V or Vmax.

SP= _____ uCi x --"""'"1-"-0"""0___ = _ _ _ _ _%

(% of Site Limit) (above) sec 350,000 uCi/sec of Site Limit

REVISION NO.:

50 PROCEDURE NO.:

PROCEDURE TITLE:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body*and Skin Dose Rates for Noble Gas Releases And Establishing Setooints for Effluent Monitors (continued)

1. (continued)

A. (continued)

4. (continued)

C. The receipt of a valid HIGH Alarm on-a release point J where the-ODGM Low Range Gas Channel's-radioactivity is greater than the-HIGH .~.!arm setpoint may quickly be estimated based on:

-FsL = R-Ps1.: + (Sum of-all other Release Point's RPsL on site)

RPsL= Rel Pt's Rel Pt's volume time_

Channel's x Release x conv. X com,. x 1/(site limit) uCi/cc Rate (V) const. const.

RPsL = uCi x V ft 3 X 28317 cc X min X sec cc min ft3 60 sec 3.5E+05 uCi Where:

FsL = Fraction of the Site Limit RPsL = Fraction of a Release Point's contribution to the-site limit (Sum of all other Release Point's RPsL on site) is norm ally less than 0.10 under normal operating conditions.

V = in ft 3/min, the Release Point's actual process Volume flow- release rate

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTIE>N 2.2 Determining the Totai*Body and-Skin Dose Rates for Noble Gas Releases-And Establishing Setpoints for Effluent Monitors (continued)

1. (continued)

A. (continued)

4. (continued)

C. (continued) [

A value of RPsL >1.0 or a FSL >1.0 would be exceeding the Sit-e Limit Based on the above estimate. Off Normal Procedure allow 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to obtain* a grab sample of the Release Roint so that the actual site limit-situation may-be evaiuated.

This methoEl is discussed in the following step.

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 ODGM Step 2.2.2 for Noble Gas Total Body Dase 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 cor:itinuous collection medium(s) and a Tritium Sample canoe pulled and ar:ialyzed to evaluate-compliance with ODCM Control 3.-11.2.1.b.

REVISION NO.: PROCEDURE TITLE:

l - -_ _ s_o__ --4 OFFSITE DOSE CALCULATION MANUAL*(ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Deter:mining the Total Body and Skin Dose Rat-es for Noble Gas Releases And-Establishing Setpoints for- Effluent Monitors {continued)

1. .(continued)

B. No Particulate or Iodine Radioadivity Channels are required by the ODCM. Table 3.3-13 requires Iodine am:! 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 ir:1-2.2.1.C). Tha Unit 2 FU SAR does describe Particulate and Iodine Radioactivity Channels. These Channels are-listed in ODCM Table-3.~-14 and ALERT and-:1:-'!IGH Setpoints*are provided. The intent of-pmviding these setpoinfs is to provide earJy warning that the effluent patl:iway conditions have insreased 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 lodine-131, lodine-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-fypewhere the count rate is not dependent (above thresheld) on the energy of the is0tope -entrained on the collection medium, and that these channels are qualitative trend indicators since the channel Gaunt rate cannot be corrected for tl'le accrued sample collection volume. Plant historical trends have shown that Noble Gas Activity may contribute to the-count r-ate of the Reactor Auxiliary Building (Plant) VeRt Particulate and Iodine Channel(s).

In this event the Noble Gas contribution may be added to the Tabte 3.3-14 Alert and High Setpoints- for Unit 2 Plant Vents-on1y.

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 coa.firm 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.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body and Skin Dose Rates for Noble Gas Releases And Establishing Setpoinis for Effluent Monitors (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 snail require isotopic analysis of particulate an-dfor*iodine channel medium -of the affected channet(s). The-isotopic analysis of the medium shall .be used-to evaluate part-iculate and/oriodine-dose

-rate levels per the methodology of ODCM 2.3.

C. To cemply-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 witl'nhe 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 Building:

The 10,000 cpm High Setpoint is based_on an Infant's Maximum Exposed Organ D0se Rate (Liver) from Inhalation of Cs-137 at the Site-Bounclary. 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 assumptions 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 fiiter), the typical sample volume would yield -3.3E+06 cc's. Greater than 99% sample filter efficiency is assumed.

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

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ 5_0_ _...... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200- ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body and Skin Dose Rates for t,foble Gas Releases And Establishing Setpoints f.o.r Effluent Monitors (continued) 1~ (continued)

C. (continued)

5. The default historical (X/Q)d for the worst sector (NW) at the site *boundar=y is 1.3E-06 meters/sec.

6. The dose rate-Cequivalent to 10;000 cpm) is catculated per ODCM Section-2.3 Inhalation Dose Rate-to an Infant- The resulting dose rates yield.

Bone Liver 'fhyroid Kidney Lung GI-LLI W.Body mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr 7.4E-¥00 7-:-§E+OO O.OE+OO 4.2E-01 1.0E+OO 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-,QQO cpm provides a conservative setpoint §iven that-t!:lis channel analyzes gross activity-on a fixed filter, Cs-137 is a typical long-a..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 Gs-137 activity of -2.3E-06 uCi/cc.

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)

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

G-200 ST. LUCIE PL.ANT MErHOD0LOGY SECTION 2.2 Determining the Total Body and Skin Dose Rates for N-obie Gas- Releases And Establishing Setpoints for Effluent Monitors (continued}-

1. (continued)_

C. (continued)

Unit 2 Fuel Building:

The 10,000 cpm High Setpoint is based on an Infant's Maximum Exposed e>rgan Dose Rate (Liver) from Inhalation of Cs--t37 at the Site Boundary. The value of 10,000 epm is very_ conservative relative-,:::_-

to-the-s-ite dose rate-limit of 1500 mrem/yr. The_methmfology is based on measured particulate channel count-rates when the--

detector was-calibrated with a known source activity of Cs-1-3-7, and on-default assumptions as follows:

r

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 4.08E+06 cc's. Greater than 99% sample filter efficiency rs-assumed.

3. The maximum building process flow exhaust is -31,584 cfm.

4. Q(dot) for Cs-137 uCi/sec release rate is approximately 21 uGi/sec as follows:

7 .59 uCi- x hour x 28317 cc's x 31584 ft3 x min = 27.72 uCi hour 4.08E+86cc.s -ft3 min- 60 sec sec

5. The default bistorical (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 GI-LU W.Body mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr 6.21 E+OO 6.62E+OO OE+OO 3.52E+OO 8.56E+OO 1.2E+OO 3.99E+OO

REVISION NO.: PROCEDURE TITLE:

t - -_ _ s_o- - - t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-20Q ST. LUCIE PLANT METHOOOL0GY SECTION 2.2 Determining the Total-Body and Skin Dose Rates for Noole Gas Releases And Establishing Setpoints for Effluent Monitors (continued)

1. (continued)

C. (continued)

7. The ODCM 3.11.2.1.b dose rate limit to any organ is 1"500 mremlyr_ From the-preceding calculation the Infant's Liver is the maximum exposed organ at 0.34 percent of the site dose rate lim1f.

8. -A .pa-cticulate chaRnel setpoint of 10,000 cpm_provides a conservative setpoint given that this channel analyzes gra:ss activity orra fixed filter, Cs-13 7 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 uCi/cc.

9. The setpoint of 10,000 cpm was administratively chosen to

-provide early detection/alarm of a problem. The above dose rate calct1lations are_prov.ided to document that the particulate chaP.nel is capable of detection sensitivities to insure compliance wfth the ODCM site limit. Grab samples s*hould be performed to accurately calculate actual releases associated

~with real high alarm events as per the ODCM methodology for performing dose rate calculations.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT

.METHODOLOGY-SECTION 2.2 Determining the Total Body-and Skin Dose Rates for Noble Gas Releases And

-Establishing Setpoints for EffiuenLMonitors(continued) 2-: Total Body and Skin Nuclide Specific Dose Rate Calculations The following outline provides a step-by-step explanation- of how tbe total body dose rate-is calculated on a nuclide-by-nuclide basis to evaluate compliance with Control 3.112.1. This method is only used if the actual release_s exceed the va!ue of 3".5 X 1-05 µCi/sec.

A. The (X/QJ value = sec/m 3 and fs the most limitiRg sector at the exclusion area. (See Table M-1 for value and sector.)

B. Enter the release rate-in ff/min of the release source and convert it to:

_ ( )ft 3 X 2.8317 X 10 4 cc X min min ft 3 60 sec

= cc/sec volume release rate C. Salve for(Q DOT)i for nuclide (i) by obtaining the-µCi/cc assay value otthe release-source anci- multipJying it by the product of 2.2.2.B above._

(Q DOT)i = Enuclide [i])

(assay) µCi X {2.2.2.B-value) cc cc sec (Q DOT)i = µCi/sec_for nuclide (i)

D. To evaluate the total body dose rate obtain the~ value for nuclide (i) from Table G:.2.

E. Solve for DRTsi 3

mrem - m X sec X µCi oRTBI_= K,_(X/Q) (Q DOT).=

, c*

µ 1-yr m 3

sec mrem DRTBi=-- total body dose from nuclide (i) for the specified yr release source

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determining the Total Body and-Skin Dose Rates for Noble Gas Releases And Establishing Setpoints for Effluent Moo..itors (continued)

2. (continue-d)

F. To evaluate the skin dose rate, obtain the Li and Mi vaiues from Table G-2 for nuclide (i).

G. Solve for DRskin i DRskin i = [Li + 1 .1 MiJ-(X/Q)(Q DOT) i

_ mrem- skio. dose from -nuclide (i) for lhe specified release DRskin i -

yr source I-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 DRrn = L DRrn; i

J. The_Dose-Rate to the skin from noble gas radiation from the specified

[elease source is:

n DRskin = L DRskini 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.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.3 Determinir:1g the Hadioiodine & -Particulate Dose Rate to Any Organ From Gaseous Releases*

Discussion - Controi 3.11.2.1 limits the dose rate from 1-131, 1-133, tritium and all rad1onucl~des in particulate form with half lives >eight days to ::;1500 mrem/}'r 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-52.1~3 in NUREG-0133, November 1978. The Infant is the controlling_age group-in the in.halation,__ground plane and cow/goat milk pathways, wl:l-ich are the only pathways considered for releases. The long term (X/Q)D (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 Pathway (excluding H-3):

n DR1&BDPT = L R_ (X/0) 0 (Q DOT)i I

T For Ground Plane:

n p

DR1&BDPT = L . (D/Q}(Q DOT )i

I I

T For Grass-Cow/Goat-Milk:

n R

DR1&BDPT: [- . (D/Q)(_Q DOT )i

I I

T For Tritium Releases (Inhalation & GJ:ass-Cow/Goat-Milk):

Normally should be PiT, but Rh values are the same, thus use RiT tables in Appendix A.

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALGULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. "LUCIE PLANT METHODOLOGY SECTION.

2.3 Determining the Rad~oiodine & Particulate Dose Rate to Any Organ From Gaseous Releases (continued)

For Total Dose Rate from I & BOP and H-3 To An Infant Oraan T:

Where:

T = The organ of interest for the infant age group z = The applicable pathways

= Dese Rate in mrem/yr to=the organ T from iodi!'.'!es and 8 day particulates

= Dose Rate in mrem/yr to organ T from Tritium

= Total Dose Rate in mrem/yr to organ T from all pathways under consideration

= A mathematical symbol to signify th:e:=-operations to the right of the symboLare to be pe-1:formeEI for each nuclide (i) through (n) and-the rndividuaLnuclide dose rates are summed to arrive at the total dese rate from the pathway.

A mathematical symbol to indicate that the tetal dose rate OT to organ Tis the s1::1m of. each of the pathways dose rates

= The dose factor for nuclide (i) for organ T for the pathway specified (.units vary l::>y pathway)

= The dose factor for instantaneous ground plane pathway in units of mrem-m 2 sec

µCi-yr

REVISION NO.: PROCEDURE TITLE:

50 t----------1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTl6N 2.3 Determining the Radioiodine & Particulate Dose Rate to Any Orgao From Gaseous Releases (con.tinued)

From an evaluation of the radioactive releases and environmental pathways, the grass-cow/g-oat-rnilk palliway has been identified as the most limiting pathway with the infant's thyroid being the critical organ. This pathway t~rpically contributes

>90°/o of the total dose received by th*e infants thyroid and the radioiodine contribute essentially al1 of this dose. Therefore, it is possible to demonstrate compliance with the release r:ate limit of Contr-ol 3.11".2.1 for radioiodines aAd 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 ferihis determination. If this-limited analysis approach is used, the dose-calctilations 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 pectormed to demonstrate compliance with the Control dose rate Hmit.

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 typieall.y be used to demonstrate compliance with the dose rate limit of Control 3.11.2.1-for radfoiodines and-particulates when the me-asured releases-:of-particulate material (other tban radioiodines and with half lives >8 days) ar-e >10 times the measured releases of radioiodines.

1. The Inhalation Dose Rate Method:

NOTE The H-3 dose is cafculated .as per 2.3.LI-.

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 3. This value is common to all nuclides. (See Table M-2 for value, sector and range.)

B. Enter the release rate in ft37min of the release source and cenvert to cc/sec.

3 4 ft X 2.8317 X 10 cc X min

=- - - - =cc/sec min ft 3 60 sec.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

ST. t.UCIE PLANT METHODOLOGY SECTION 2.3 Determining the Radio iodine & Particulate -Dos*e Rate to Any Organ Fr.om Gaseous Reteases (continued)

1. (continued)

C. _Solve for (Q DOT)i for nuclide (i) by obtaining the-µCiYcc assay value --

of the release source activity and multiplying it by-the product of 2.3.1.B above.

(QDOT).= (nuclide[i]assay) µCi X (Value2.3.1.B)cc 1

cc sec

[

J 0.

(Q-DOT)i = µCi/sec for nuclide (i)

Obtain the-Ri v-a-1-ue from Table G-5 for the organ T.

E. Solve for DRi 3

. = . (X/Q) (Q DOT).= mrem - m X sec X µCi DR,T R,T o , c*

µ 1-yr m 3

sec DRiT = 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 Ffrom the Inhalation Pathway is:

DR1nhalationT =-DR1 + DR2 + _ _ + DRn for all nuclides except H:.3. This dose rate shall be-added to the other p_athways as per 2.3.5 - i:etal Organ Dose.

NOTE Steps 2.3.1.C through 2.3~1-.G need to be completed for each organ T of the Infant.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.3 Determining the Radioiodine & Particulate Dose Rate to Any Organ From Gaseous Releases (continued)

2. The Ground Plane Dose Rate Method:

NOTE Tritium .dose via the ground-plane is zero.

A. The controlUng location-is assumed to b:e an !-nfant located in the

_ _ _ _ _ sector at the mile range. The (D/Q) for this location is 1/m2. This value is common to all nuclides.

(See Table M-2 fur sector, range and value.)-

B. Enter the-mlease rate in ft 3/min of the release source-aP.d convert to cc/sec.

3 4 ft X 2.8317 X10 cc X min

=--- =cc1sec min ft 3 60 sec.

C. Solve for (Q DOT)i for nuclide (i) by obtaining the µCi/cc assay value from the release source activity and multiplying it by the product of 2.3.2.B above.

(Q DOT).= (nuclide [i] assay) µCi X (Value 2.32.B) cc 1

cc sec (Q DOT)i = µCi/sec for nuclide (i)

D. Obtain tne Pi value from Table G-3 E. -Solve for DRi 2

DRi = PiT (D/Q) (Q DOT )i-= mr-em - ~ - sec

µC1 - yr x-;-m X µCi sec DRi = mrem The Dose Rate to organ T from nuclide (i) yr F. Repeat steps 2.3.2.C through 2.3.2.E for each nuclide (i) reported in the assay of the release source.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

-C-200 .ST. LUCIE PLANT METHODOLOGY SECTION 2.3 Determining the Radioiodine-& Particulate Dose Rate to Any Organ From Gaseous Releases {continued)

I 2. (continued)

G.- The Dose Rate to the Infant's Whole Body from the Grou-nd Plane Pathway is:

DRGr Pl = DR1 + DR2 + ____ + DRn for all nuclides. This dose rate shall be adde1:I to the other pathways as per 2.3.5.

3. The-Grass-Cow/Goat-Milk Dose Rate *1v1ethod:

- H-3 dose is calculated as per2.3.4.

----=======N=O=TE===========llll- *.

A. The controlling animal was established as a located in the sector at miles. The (D/Q) for this location is 1/m2. This value is common to all nuclides.

(.See Table M-3 for sector, range and value.)

B. Enter the anticipated release rate in ft3/min of-the release-sour.ce and convert to cc/sec.

3

- - - ft X 2.8317 X 1-()4 cc X min =cc/ sec min ft 3 60 sec.

C. Solve for-(Q DOT)i for .nuclide (i) by obtaining the µCi/cc assay value 0rthe release source activity and multiplyin§]-it by the product of 2.3-:-3.B above.

(QDOT).= (m1clida[i}assay) µCi X (value2-:-3.3.B)-cc 1

cc sec (Q DOT)i = µCi/sec for nuclide (i)

D. Obtain the Ri 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.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

G-2-00 ST. LUGIE PLANT METHODOLOGY SECTION 2.3 Determining the Radioiodine & P.articul-ate Dose Rate-t0 Any Organ From Gaseous

-Releases (continued)

3. (continued)

E. Solve for nRiT 2

. = . (D/Q) (Q DOT). = mrem - m - sec X _1 X _µCi DRir R1r I

µ c*1-_yr m

-2 sec DRiT= mrem the-Oo_se RateJo organ T from nuclide (i) yr F. Repeat steps 2.3.3.C through 2.3-.3.E for each nuelide (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:

DR 9 rass-_ _ _-Milkr = DR1 + DR2 + _ _ + DRn for all nuclides. i::his dose rate shall-be added-to-the other pathways as per 2.3.5 -1otal Organ Dose.

NOTE

-steps 2.3.3.C thro~h 2.3.3.-G need to be completed for each-organ-of the Infant. -Limit-the calculation to the infant thyroid if t!'.le limited analysis

_ -approach is being-used-.

. REVISION NO.: PROCEDURE TITLE:

i-----50 _ _---1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. lUCIE-PLANT METHODOLOGY SECTION 2.3 Determining the Radioiodine & Particulate Qose Rate to Any Organ From Gaseous Releases (continued)

4. The H-3 Dose Rate Method:

A. The controlling locations and their (X/Q)D values for each pathway are:

Inhalation - Infant at _ _ _ _ _ range in the _ _ _ _ _ sector.

(X/Q)D = sec/m3 (See Table M-2 forrange, sector and value)

{3r-ound Plane - Does not apply to H-3 Grass-Cow/Goat-Milk- located in the sector at miles with an Infant at-the e-xclusion area in the - - - - -

sector drinking the milk. The (X/O}o-forihe locatior,:ais (X/Q)D = 3 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 ft3/min of the release source and convert it to cc/sec.

___ fl3 X 2.8317 X 1.a+/-_cc X min 3

min ft 60 sec.

= cc/sec volume release rate

-C. Solve for (Q DOT)1::1-3 for Tritium, by obtaining the µCi/cc assay value of the release source and-multiplying it by the product of-2.-3.4.B above.

(QOOT) = (H-3) µCi X (2.3.4:Hvalue)cc H-3 cc sec (Q DOT)H-3 = µCi/sec activity release rate D. Obtain the Tritium dose factor (Ri) for Infant organ T from:

PATH TABLE#

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

REVJSION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION-2.3 Determining the Radioiodine & Particulate Dose Rate to Any Organ From Gaseous Releases (continued)

-4. (continued)

E. Solve-for DH_3 (Inhalation) using the (X/Q)D for inhalation from 2.3.4.A -

and RH-3 (Inhalation) from 2.3.4.D.

DRH-3tnhT = RH-3 {X/Q ) 0 {Q DOT )H_ 3 DRH- 3 = mrem/yr from H - 3 Infant Inhalation for organ T

~T . .

F. Solve f.or DHa3 (Grass- -Milk) using the (X/Q)D for Grass- -Milk from 2.3.4.A and RH-3 (Grass- -Milk) from 2.3-A.D DRH-3G- -MT= RH-3 8 _ -MT (X/Q )o (Q DOT )H-3 DRH- 38 _ -MT= 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-r:ates as per 2.3.5.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT-METHODOLOGY SECTION 2.3 Determining the Radioiodine & Particulate Dose Rate to Any Organ From Gaseous Releases (continued)

5. Determining the Total Organ Dose-Rate from i-odines, BO-Particulates, and 1-:1-3 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 D-OSE RATE STEP# REF.

Inhalation (1&8DP) 2.3.1.G Gro.und Plane (1&8DPJ (Whole Body only) -2.3.2.G Gr- Milk (1&"'8DP) 2.3.3.G Inhalation (H-3)' 2.3.4.E Gr- -Milk (H-3) 2.3.4.F DRr = (sum of above)

B. Repeat the above summation for each Infant organ T.

C. The ORT above shall be added to all other release sources on the site that will be in progress at af'.ly instant. Refer to=irr-plant procedures and-logs to -determine the Total DRr to each organ.

2.4 Determining the Gamma Air_Dose for-Hadfoactive Nob!e 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 methad is _provided for determining Jhe noble gas gamma air dose and is based on section- 5.-3.1 of Nl:JREG-0133-,

November-1978. The dose-calculation is independent of any age group. The

_equation may be used fer Control dose calcalation, the -.lose calculafion for the annual report or. for projecti-Rg dose, provided that the appropriate valu-e of (X/Q) is used as outlined in the detailed explanation that-follows. The equation fbr gamma air dose is:

n 8

Dv - air= L 3.17 X 1ff M (X/Q) Qi

REVISION NO.~ PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT MET-HODOLOGY SECTION 2.4 Determining- the Gamma Air Dose for Radioactive Noble Gas Release Source(s)

-(continued)

Where:

Dv-air = gamma air-dose in mrad from radioactive noble gases.

L = 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- Ruclides reported during the interval. No units apply.

3.11-x--,-e=e- = tbe inverse-of the number otseconds per year with-units .of yearJs-ec.

= -the gamma air dsse factor for radioactive noble gas- nuclide (i) in units of mrad-m 3

µCi-yr (X/Q) = the long term atmospheric dispersion factor for ground level releases in units of sec/m 3

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~sased on, etc.

= the number of micro~curies of nuclide (i) rele_ased (or projected) durin*g the dose calculation exposure peried. (e.g., month, quarter - -

or year)

REVISION NO.: PROCEDURE TITLE:

i-----5_0_ _--1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHOE>OLOGY SECTION 2.4 Determining the Gamma Air Dose for Radioactive Noble Gas Release Source(s)

(continue!)

The followiP.g steps provide a detailed explanation- of how the radionuclide specific dose-is calculated.

1. To determine ffie applicable (X/QJ 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). Thi$ value of (X/Q) applies to each nuclide (i) ..

2. Determine (Mi) the gamma-air dose factor for nuclicle-(i) from-Table G-2.

3. Obtain the micro-Curies otnuclide (i) from the in-plant radioactive gaseous waste management logs for the sources under consideration during the time-interval.

4. Solve for Di as follows:

8 3 D*= 3.17 X10- yr X Mmrad-m X (X/Q)sec X Qi µCi 1

sec µCi-yr m3 1 Di = 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 Di dose-of each nuclide (i) to obtain Dv-air dose.

Dv-air = D1 + 82 + - - + Dn = mrad

7. Heter to-in-plant proced1Jres for comparing the calculated-dose to any applicable limits that might-apply.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _-1 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOlOGY SECTION 2.5 Determining the Beta Air Dose for Radioactive Noble Gas Re~eases Discussion - Control 3.11.2.2 limits the quarterly air dose due to beta radiation from noble g:ases in-gaseous effluents to <10 mrads in any- calendar quarter and <20 mrads-in-any calendar year. The foHowing calculation-method is provided for determinin_g the beta air-dose and-is based on Section 5.3.1 of NUREG-0133,

-November 1978. The dose calculation is inaependent of any age group. The equation may be used for Gontml dose calculation, dose calculation for annuaJ reports or for projecting dose, p_rnvided that the -appropriate value gf (X/Q) is used as- outlined in the detailed explanation that follows.

The equation for beta air ..dose is:

n_

8 Ds-air L = 3.17 X 1C'.Y Ni (X/Q) Qi j_

Where:

DB-air = beta air dose in mrad from radioactive noble gases.

= a-mathematical symbol to signify the operations to the rigtrt-side of the symbol are to be-performed for each nuclide (i) through (n) and summed to arrive at the lotal dose, from all nuclides reported during the interval. Noc.units apply.

3.17X10-8 = the inverse of the number of seconds per year with units of yearlse-c.

= the beta-air-dose factor-for radioactive noble gas nuclide{i) in

-units-of mrad-m 3

µCi-yr (X/Q) = the long-term atmospheric dispersion factor for ground level

-releases in units of sec/m 3 . The value of (X/Q) is the same for all nuclides (i) in th*e dose calculation, but the-value of (X/Q) does vary depending on the Limiting Sector the Control is based on, etc.

= the number of micro-Curies of nuclide (i) released (or projected) during the dose calculation exposure period

REVISION NO.: PROCEDURE TITLE:

50 1----------t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LlJCIE PLANT METHODOLOGY SECTION 2.5 Determining the Beta A~r Dose for Radioactive Nobie Gas Releases (continued)

The following steps J:)rovide_a detailed explanation of how U1e dose is calculated.

1. "Io-determine the applicable (X/Q) referlo Table M-1 to obtain the value for the type of dose calculation beiP.g performed (i.e., quarterly Control or Dose projection for-examples). Ttiis value of (X/Q) applies to each ouclide (i).

2. Determine (N1) 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 tbe time interval.

4. Solve for D1 as follows:

8 3 D*= 3.17 X10- yr X Nmrad-m X (X/Q)sec X QiµCi 1

sec µCi-yr M3 1 Di = 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 Di dosaof each nuclide (i) to obtain DB-air dose.

DB-air = D1 + D2 - - - - + Dn = mrad

7. Refer to in-plant 13rocedures for comparing the cakulated dose to any applicable limits that might apply.

REVISION NO.: PROCEDURE TITLE: PAGE:_\"

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1---------1 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determining the Radioiodine and Particulate Dose To Any Age Group's Organ From Cumulative Releases Discussion - Control 3.-11.2.3 limits the dose.to th*e whole body or any organ resulting from-the release of 1-1.31, 1-133, 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 cfitical or:gan dose E.lue to releases of raaioiodir.es and particulates and is bas.ed on Section 5.3.1 of NUREG-0133, November 1978. The equations can*be used for any age group provided that the appropriate dose facter:s are used and the total-dose reflects only those pathways that are applicable to the age group. The Effluent Supervisor will track whiGA age group is tbe controlling (mos-t restrictive) age group fsee coP.trol 3.11.2.6as}. The (X/Q~l:l symbol represents a DEPLETEQ-(X/.Q) which is differeAt from the Nonie Gas (X/Q) in that (X/Q)D takes into account the-loss of 1&8DP and H-3 from the plume as the semi-infinite cloud tr.al!els 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 1&8DP and H-3 notations refer to 1-131, 1-133 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)D- The first step is to calculate the 1&8DP and H-3 dose for each pathway that applies to a given age_group. T=he total dose to an organ can then-be determjned by summing the pathways-that apply to the receptor in the sector. The infant ag_e_group does not app!.y- to Grass-Cow-Meat or Vegetation pathway dose s1nGe they are assumed to

-eat only milk.

The equations are:

For Inhalation Pathway (excluding H-3):

n D1&sopT = r 3.17 x 1o-s R1-CXI0-=)0 Qi For Ground Plane, Grass-Cow/Geat-Milk, Grass-Cow/Goat-Milk, or Vegetation n

D1&sopT = r 3.17 x 1o-s Ri (D/Q) Qi For each pathway above (excluding Ground Plane) For Tritium:

3.17 X 1o-S RH-3T (X/Q )o 0;

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1---------1 PROCEDURE NO.:

C-200 ST. UJCIE PLANT METHODOLOGY SEC-TION 2.6 Determining the Radioiodine and Particulate Dose To Any Age Group's Organ From Cumulative Releases (continued)

For Tetal Dase from Particulate Gaseous-efflue.At to organ T of a-specified age group:

\Nhere:

T = the_mggn-of interest o[a specified age group z = the applicable pathways for the age group of-interest

= Dose in mrem to the organ T of a specified age group from radioiodines and 80 Particulates

= Dose in mrem to the organ T of a specified age group from Tritium Dr - Total Dose in mrem to the or§an T of a -specified age group from Gaseous particulate Effluents

~~

I

= A mathematical symbol to signify the operations to the sight of the symbol ar..e to be performed for each nuclide (i) through (n) and the individual -r:iuclide doses are summed to arrive at the total dose from the pathway of interest to organ T.

E = A mathematical symbol to indicate thanhe total dos.e-DT to z organ =F is the sum of each of the pathway doses of 1&8DP and H-3from gaseous particulate effluents.

3.17 X 10-8 = The inverse of th.e number of seconds per year With units of year/sec-:

Ri = 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 - m3 for pathways OR mrem- m 2 - sec for pathways yr- µCi using (X/Q )0 yr- µCi using (D/Q)

REVISION NO.: PROCEDURE TIT.LE:

1 - -_ _ s_o_ _..... OFFSITE DOSE CALCULATION MANUAL(ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determining the Radioiodine and Particulate Dose To Any Age- Group's Organ

Fr-om Cumulative Releases {continued)

(X/Q}D The depleted-(X/Q) value for-a-specific location-where the 3

Teeeptor is located_(see disc1.1ssion). The units are secim (D/Q) = the deposi-tion valu~ for a specific location where the receptor 2

is located (see discussion) .. The units are Hm where m=meters.

= The number of micro-Curies of nuclide (i) released (or projectedJdur::ing the dose calculation exposure period.

= the number of micro-Curies of-rl-3-released-(or Rrojected) during the dose calculation exposure period.

1. The Inhalation Dose Pathway Method:

NOTE The H-3 dose should be calculated as per 2.6.4.

A. Detem:rine the applicable (X/Q)D 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 Ri factor of nuclide (i)_

for the organ T and age group_ from the appropr~ate table number.

Ag~ Group Inhalation Dose Factor Table Numbef -

Infant G-5 Child G-8 Teen G-13--

Adult G-18 C. Obtain tbe micro-Curies (Qi) of nuclide (i) from the radioactive-gas waste management logs for the release source(s) under consideration during the time interval.

D. Solve for D1 mrem from nuclide (i)

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE P~NT METHODOLOGY SECTION Determining the Radioiodine and Particulate Dose To-Any Age Group's Or.qan From-Cumulative Releases (continued)

1. (continued)

E. Perform steps 2.6.1.B through 2.6.1.D for-each nuclide (i) reported durin*g the time interval for each organ.

F. The Inhalation dose to organ T of the specified age group is determined by summing the Di-Dose of each nuclide (i)

D1nhalation

= D1 +-D2 + + D-;;- = _mrem (Age Group) -

-R-efer to 2.6.5 to determine the total dose to-organ T from radioiodines & 8D---Particulates

2. The Ground Plane Dose Pathway Method:

NOTE Tritium dose via the ground plane is zero. The Whole Body is the only organ considered for U1e-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 dosels the same-for all-age groups.

C. Obtain the micro-Curies (Qi)-of nuclide (i) from the radioactive gas waste management logs for tt:1e source under consideration.

D. Solve for D1 mrem for nuclide (i)

E. Perform steps 2.6.2.B through 2.6.2.D for each nuclide (i) reported during the time interval*.

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o__....g OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determining the Radioiodine and Particulate Dose To Any Age Group's Organ From C-umulative Releases (contim1ed)

2. (continued)

F. The Groul"ld Plane dose to the whole body-is determined. by summing the Dr Dose of each nuclkle (i)

DGr.PI.-WBody = E>1 + D2 + _ _ + Dn = mrem Refer to step 2.6.5 to calculate total dose to the Whole Body.

3. The 6rass-Cow/Goat-Milk Dose-Paihway Method:

NOTE Tritium dose is caiculated 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 inter-est, determine the dose-factor R; for nuclide (i), for or.gan T, from the appropriate table-number for the applicable milk animal.

Cow Milk Dose Factor Goat Milk Dose Age Group Table Number Factor Table Number Infant G-6 G-7 Child G-9 G-to Teen G.c_1.4 G-:..15-Adult G-19 G-20 C. Obtain the micro-Curies (Qi) of nuclide (i) from the radioactive gas I_

waste management logs for the release source under consideration-during the time interval.

D. Solve for Di Di = mrem from nuclide (i)

REVISION NO.: PROCEDURE TITLE:

i----50 _ _----1 OFFSITE DOSE CALCULATION MANUAL (ODCM) .

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Qeterminina the Radioiod1ne and Particulate Dose To Any Age Group's Organ Erom Cumulative Releases (continued)

3. (continued)

E Perform steps-2.6.3.B through 2.6.3,D for each-nticlide (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-1\71-ilk) pathway dose.to organ-T is determined by summing the Di dose of each nuclide(i).

mrem The dose to each organ should be calci:ilated in the same manner witlrsteps 2.6.3.B through-2.6.3.F. R-efer to step- 2.6.5-to determine the total dose te organ T from radioiodines &SD 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:

1. Fer dose ca!cu!ations- (other than the annual report) the historical herd was determined to oe located in Sector - - -

at miles. This herd-sha~d-be-used for all ODCM Control required dose calculations.

2. For annual report dose calculations the herd-from the Land Use Census having the highest(D/Q) at its location will be t!:le -i_-

reporting herd. The LaAd-Use Census for 1978 (for example) shall apply to the calendar year 1979 (fer 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.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determining the Radioiodine and Particulate Dose To Any Age Group's Organ From Cumulative-Releases (continued)

4. -(continued)

C. Determine the dose factor Ri for .nuclide-(i) for orga,Q tau from fhe Table specified below:

,A.ge Meat Dose Factor Table N.o. l Infant- NIA*

Child G-1-1 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-Curies of nuclide (i) to be projected) for the release source(s) under consideration durin_glne 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) Q.i Di= mrem from nuclide (i}

F. Perform Steps 2.6.4.C .through 2.8-A.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)

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

-METHODOLOGY SECTION 2.6 Determining the Rac:lioiodine and Particulate Dose To Any Age Group's Organ From C.umulative Releases-(continued) [

5. The Vegetation (Garden) Dose Pathway method:

A. !Jetermine the controlling garden location by:

1. For_do_se calculations (other than annual reports) the historicaJ garden was determined to be located in Sector at

_____ miles. This garden shall be used for all ODCM Control dose calculations.

2. Fer annual report dose caicuiations the-Land-Census Garden

-_,: ha.ving_the highest real (D/Q) at its location will be-the-

_I 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.

C. Determine the dose factor Ri for nuclide (i) for or_gan tau from the Table specified trelow:

Age Vegetation Dose Facto(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 tne 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.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determinin§ the Radioiodine and Particulate Dose To Any Age Group's Organ From CumuJative Releases (continued)

5. (contimied)

E. Solve for Di Qi = 3.17 X 10~8 Ri-(D/Q) Qi Di = _ _ _ _ _ _ _ mrem from nuclide (i)

-F. Perform Steps 2.6.5.C through 2.6.5.E for each nuclide-(i) reported

-during the time interval.

G. The Vegetation pathway dose to organ tau is deter:mined by summing the Bi-dose of each nuclide-(i).

Dose = D1 + D2 + D3 + ...... + Dn = - - - - -mrem Vegetation (Excluding Tritium)

(Child, Teen, or Adult)

6. The Gaseous Tritium Dose (Each-Pathway) Method:

A. The controlling locations for the pathway(s) has already been determined by:

Inhalation - as per 2.6.1.A

-Ground Plar:ie not applica51e for -!=!-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)D-instead of (g1Q).

TableM-2-describes where the (X/Q)D value should be obtained from.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 2.6 Determining the Radioiodin_e and Particulate Dose To Any Age Group's Organ From Cumulative Releases ~continued)

6. (continued)-

C. For the age group(s~ of interest, determine the Patt:iway Tritium dose factor (RH-3) for the organ T of interest from -the Table-=specified-below:

MILK AC3E INHALATION cow GOAT Infant G-5 G-6 -G-7 Child G G-9 G-1-0 Teen G G-14 G-15 Adult G-18 G-19 G-20 D. Obtain the micro-Curies (Q) of Tritium 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 Control limits or quarterly reports shall be from all gaseous release sources.

E. Solve for _QH-3 DH-3 = 3.17 X 1o-s RH-3(X/Q)DQ DH-3 = mrem from Tritium in the specified pathway for organ T of the specified age group

.1r:s<-*

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE D_OSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. tUCIE PLANT

. 01231

. - *\; . f' ;/

METHODOLOGY SECTION ***:*t***--***:.:rrJS

"*'L*L*=*

2.6 Determining the Radioiodine and Particulate Dose-To Any Age Grou12's Organ

- From Cumulative Releases (continued-)

7. Determining the Total Organ Dose From Iodines, BO-Particulates and H-3 From Cumulative Gaseo1;1s Releases NOTE Control dose limits for l&BUP 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 applicabJato Gontrol-;-from a~I release sources: - .

Age Group: INFANT CHILD TEEN ADULT OrgaR: BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY Reference to STEP PATHWAY DOSE Remark No.

Inhalation (l&BDP) 2.6.1.F Inhalation (Tritium) 2.6.6.E Ground Plane (1&8DP) 2.6.2.F Grass- -Milk (1&8DP) 2.6.3.F Grass- -Milk (Tr:itium) Z6.6.E

Grass-Grass-

-Meat (1&8DP)

-Meat (Tritiblm) 2.6.4.G 2~6.6.E N7A for INFANT

-N/A for INFANT I

Vegetable Garden (l&BDP) 2.6.5.G N/A for INFANT Vegetable Garden (Tritium}. 2.6,6.E N/Afor INFANT -

DoseT = (sum of above) -

B. The dose to each of the applicable age group's ORGANS shall be calculated-:-

BONE, LIVER, TH:YROID, KIDNEY, LUNG, WHOLE BODY, & GI-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 & 80 Particulates. gaseous effluents.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION

2. 7 Projecting Dose for Raclioactive 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 .3-1 days due to gaseous effluent releases, from each unit, to areas atcmd beyond the SITE BOUNDARY (see TS-Figure 5-1-1) would exceed-0.2 mrad for gamma radiation and 0.4 mrad for beta r-adiation. The following calculation method is proviEled for determining the projected dos*es. This-method is based on using the resuits..of the calcu~ationS--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 fromJhe in-plant records.

J 2. -Divide-1hese 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 oi the waste gas holdup system shall be used.

3.0 4-0 CFR 190 Dese-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 an_y orgaR (except thyroid, which is ~imited to ~75 mrem) over a period of r2 consecutive months.

The following app.roach should be used to demonstrate compliance With these dose limits. This-approach-is basea on NUREG-0133, Section 3.8.

3.1 Evaluation Bases Dose evaluations to demonstrate compliance with the above dose limits need only be perf.ormed 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.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY-SECTION 3--:-2 Doses From Liquid Releases For the evaluation of doses to real individuals from liquid releases, the same calculation method as employ.ed in Section 1.4 will be used. However, more realistic assumptions wiU be made concerning-the dilution-and ingestion. of fish and sheUfish by individuals wno tive and fish -in the area. Also, the results of the Radiological Environmenta~ Monitoring program wiU-be included in determinin§ more realistic dose to these real people by-praviding data-on actual measured--

levels of plant related ra.c!ionuciides in the-environment.

3.3 Doses From Atmospheric Releases Eor the evaluation of doses to real individuals from the atmospheric releases, the same calcu.iation methods.as employed in-Section 2.4 and 2.6 will be used. In Section 2:4~ the total body dose factor(~) should be substituted for the gamma air dose factor (Mi) to determine the total body-dose. Otherwise the s*ame calculation sequence applies. Hewever, 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.

- REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 S:T. LUCIE PLANT METHODOLOGY SECTION 4.U Annual Radioactive Effluent R-eport 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 aFe based-on. The Control dose l~mits are therefore included in rtem 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 repart is not a13plicable 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

-tt-'re report. The-following=-fermat should be used:

RADIOAGTIVE 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, tl=!e concentration shall be limited to 2 X 1-04 µCi/ml total activity.

b. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents r-eleased 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 whele bogy and to ~5 mrem to any organ and ~3 mrem to-il:ie Whole body and ~1 O~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 effh:1ents 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 The dose rate limit from 1-131, 1-133, Tritium and particulates with half-lives >8 days shall be ~1500 mrem/yr to any organ.

REVISION NO.: PROCEDURE TITLE:

50 1----------t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY-SECTION 4.0 Annual Radioactive Effluent Report (continued)

1. (continued) 1.2 (continued)

b. The air dose {see TS Figure 5.1-1) due-to noble gases T released in gaseous effluents,_fram each reactor unit, to areas __

at and beyond the SITE BOUNDARY shall be limited to the 1

foHowing:

Buring ~-1:1¥ calendar quarter, to ~5 mrad for gamma radiation and ~10 mrad for beta radiation and during any calendar year to ~10 mrad for gamma rad~ation and ~20 mrad for beta radiation

--c. The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, 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:

Du.r-ing any calendar quarter to ~7-.5-mrem to-any organ and during any caleAdar year to ~15 mrem to any organ.

2. Effluent Limiting Concentratior:is:

Air - as per attached Table G-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.-1::uoie Plant.

REVISION NO.: PROCEDURE TITLE:

a-----5_0_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCJE PLANT METHODOLOGY SECTION 4~0 Annual Radioactive Effluent Report (continued)

4. Measurements and Approximations of i:otal Radioactivity:

A summary of liquid effluent accounting methods is descr:ibed-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.% Mme %

Release Point Mixing 2 5 NA NA Sampling 1 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

-nucliEles that are predominant in sample spectrums. Nuclides that are near background relative to the _p_redominant nuclides in a_given-sample could easily have errors greater than the-above listed maximums.

REVISION NO.: PROCEDURE TITLE:

t - -_ _ s_o_ _-4 OFFSffE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 4..0 Annual Radioactive Effluent Report (continued)

4. (continued)

TABLE 3-.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING-AND ANALYSIS LIQUID -METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS SOURCE ANALYSIS EACH BATCH PRINCIPAL GAMMA EMITTERS- p.h.a.

MONITOR TRITIUM L.S.

TANK MONTl=ILY COMPOSITE GROSS JitPHA A.I.C.

RELEASES QUARTERLY COMPOSITE Sr-89, Sr-9(};- Fe-§5 C.S.

PRINCIPAL GAMMA EMFFTERS FOUR PER MONTH p.h.a, STEAM AND DISSOLVED GASES GENERATOR TRITIUM L.S.

SLOWDOWN RELEASES MONTHLY COMPOSITE GROSS ALPHA A.I.C.

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

TABLE NOTATION:

p.h.a. - gamma spectrum palse height analysis11Sing High Purity Germanium (l:IPGE) deteetors. All peaks are identified and quantified.

L:S. - Liquid Scintillation coanting C.S. - Chemical Separation A.I.C. - Air Ion Chamber

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION 4.0 Annual Radioactive* Effluent Report (continued)

4. (continued)

I TABLE 3.2 RADIE>A-cTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING METHOD OF TYPE OF ANALYSIS SOURCE FREQUENCY ANALYSIS Waste Gas Decay Tank Each Tank Principal Gamma Emitters G, p.h.a.

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

Purge Releases -H-3 L.S.

Four per Month Principal Gamma Emitter:s (G, C, P) - p.h.a.

H-3 L.S.

Monthly Composite Gross Plant Vent p - A.I.C.

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

(Particulates) Sr-89 Principal Gamma Emitters (G, C, P.) - p.h.a.

Weekly_

H-3 L.S.

Cask Handling Monthly Composite *Gross p -A.I.C.

FaciJity Vent ( 1)- _(Particulate) Alpha-Quarterly Composite Sr-90 C.S.

_(Particulate) Sr-89 TABLE NOTATiON:

G - Gaseous Grab Sample C - eharcoal Filter Sample P - Particulate Filter Sample L.S. - Liquid Scintillation Counting C.S. - Chemical Separation p.h.a. - Gamma spectrum pulse height analysis using High Purity Germanium(HPGE)detectors. All peaks are identified and quantified.

A.I.C. - Air Ion Chamber (1 )-Only required when operating.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

-METHODOLOGY SECTION 4.0 Anaual Radioactive Effluent Report (continued)

5. Batch Releases A. Liq_uid

1. Number of batch releases:

2. Total time period of batch releases: - - -minutes

3. Maximum-time period- foTa batch release: - - -minutes

4. Averag~ time period for a batch-release: - - -minutes

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 release: - - -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

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _--i OFFSffE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT ME1"H0DOLOGY- SECTION 4.0 AnnuaLRadioactive Effluent Report (continued)

6. Unplanned Releases A. Liquid

1. Number of releases:

2. Total activity releases: - - -Curies B.

Gaseous

1. Nomber of releases:

2. Total activity released: - - -Curies C. See attachments (.if applicable) for:

1. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent a recurrence

4. C-onsequences of the unplanned reiease

7. Description of dose assessment of radiation dose from-radioactive effluents to the general public due to their activities..inside-the site are reported on the January annual report.

8. Offsite dose calcu~ation manual revisions initiated during this reporting period. See Confrol 3.11.2.6 for required attachments to the Annual Report. -

9. Solid waste and irradiated fuel shipments as per requirements of Col'.'ltrol 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.

12. Results of water samples taken in support of the Groundwater Protection INITIATIVE (N El 07-07) during the previous calendar year that have not been incorporated into the Radiological Environmental Monitoring Program.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

ST. LUCIE PLANT METHODOLOGY SECTION FLORI.DA POWER &-LIGHT COMPANY ST. LUCIE UNIT#

ANNUAL REPORT - - -I- -I- - THROUGH - -I- -I- -

TABLE 3.3: UQUIO-E~FLUENTS - SUMMATION DF ALL RELEASES UNIT QUARTER# QUARTER#-

A. Fission and Activation Products

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

2. Average Diluted Concentration During Period µCi/ml E E B. Tritium

1. Total Release Ci E E

2. Average Diluted Concentration During Period µCi/ml E E

-e. DissG-lveci and Entrained Gases

1. Total Release Ci -E E

2. Average Diluted Concentration During Period µCi/ml E E D. Gmss Alpha Radioactivity

1. Total Release Ci E E E. Volume of Waste Released

.(Prior to Dilution) LITERS_ E E F. Volume of Dilution Water Used During Period 1 LITERS E 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.

REVISION NO.: PROCEDURE TITLE: PAGE:

>:,..:'\.,.

} .. *:.: ..

/ ~- *;,<:.:::),;,':: .

F146 of 23'.1*,, . :.,;'

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

);':' /!?

'." .*. J METHOD0LOGYSECT~N };J:~:11:i :>' _

FLORIDA" POWER & LIGHT COMPANY ST. LUCIE UNIT#

ANNUAL REPORT - - -I- -I- - THROUGH - -I- -I- -

TABLE 3.4: LIQUID-EFFLUENTS (EXAMPLE FORMAT)

I

- CONTINUOUS MODE BATCH MODE I

NUCLIQES RELEASED*

1-131 UNIT Cl QUARTER# QUARTER# QUARTER# QUARTER#

-E E E E 1-1"33 -c1 E E E E 1-135 Cl E E E E NA-24 Cl E E E E I

CR-5-1 Cl E E E E MN-54 Cl E E E E C(}-57 Cl E E E E C0-58 Cl E E E E FE-59 Cl E E E E C0-60 Cl E E E E ZN-65 Cl E E E E Nl-65 Cl E E E E AG-110 Cl E E E E SN-1-13 Cl E E E E SB-122 CT E E E E SB-124- Cl E E E E Vt-187 Cl E E E E NP-239 Cl E E E E ZR-95. Cl E E E E M0-99 Cl E E E -E RU-103 Cl E E E E CS_-1.34 Cl E E - E E CS-136 Cl E E E E CS-137 Cl E E E E BA-140 Cl E E E E CE-141 Cl E E E E BR-82 Cl E E E E ZR-97 Cl E E E E SB-125 Cl E E E E

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

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION TABLE 3.4: LIQUfD EFFLUENTS (EXAMPLE FORMAT)

(cor..tinued)

CONTINUOUS MOE>E BATCH MODE NUCLIDES RELEASED UNIT

_Ql::JARTER# QUARTER# QUARTER# QUARTER#

CE-i44 Cl E E E -E SR-89 Cl E E E E SR-90 Cl E E E E UNIDENTIFIED Cl E E E E TOTAL FOR PERIOD Cl E E E E (ABOVE)

CONTINUOUS MODE BATCH MODE NUCLIDES REl::EASED UNIT QUARTER# QUARTER# QUARTER# QUARTER#

AR-41 Cl E E E E KR-85 Cl E E E E XE-131 M Cl E E E E XE-133 Cl E E E E XE-133M er E E E *E XE-135- Cl E E E E

REVISION NO.: PROCEDURE TITLE:

t -_ _ s_o_ _--t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT#- -

TABLE 3.5: LIQUID EFFLUENTS - DOSE-SUMMATION Age Group: _ _ __ -location: - - - - - -

Exposure lnt-erval: From_ _ _ _ _ _ Through _ _ _ _ __

Fish & *shellfish Pathway to Organ CALENDAR YEAR DOSE (mrem)

BONE LIVER .

THYROID

.. KIDNEY LUNG-GI-LU WHOLE BODY

REVISION NO.: PROCEDURE TITLE:

1 - -_ _ s_o__..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION FLORIDA POWER & UGHT COMPANY ST. LUCIE UNIT#-- -

ANNUAL REPORT - - -/- -/- - THROUGH-- -/- -/- -

-TABLE 3.6: GASEOUS EFFLUEN:rS-- SUMMATION OF ALL RELEASES UNIT QUARTER# QUARTER#

A-. Fission and Activation Gases

1. Total Release. Ci E - - -E

2. Average Release Rate Fur Period- µCi/SEC - - -E- - - -E B. Iodines

1. Total lodine-131 Ci - - -E - - -E

2. Average Release Rate for Period µCi/SEC - - -E - - -E C. Particulates

1. Particulates. T-1/2 > 8 Days Ci - - -E - - -E

2. -Avera§e Release Rate for Period- µCi/SEC - - -E - - -E

3. Gross Alpha Radioactivity Ci - - -E - - -E D. Tritium

1. Total Release Ci - - -E - - -E

2. Average Release Rate for Period µCi/SEC - - -E - - -E.

REVISION NO.: PROCEDURETHLE:

i----5_ff_ _--t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT METHODOLOGY SECTION FlORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT#- -

ANNUALREPORT- - -/- -/- - THROUGH - -/- -/- -

TABLE 3-.7: GASEOUS EFFLl:JENTS_-_GROUND LEVEL RELEASES (EXAMPLE FORMAT)

CONTINUOUS MODE BATCH MODE NUCLIDES-RELEASED* UNIT QUARTER# QUARTER# QUARTER-# QUARTER#

1. Fission Gases AR-41 c,- E E E E-KR-85 Cl E E E E KR-85fvl- Cl E E E E KR-87 Cl E E E E KR-88 Cl E E E E XE-131 M Cl E E E E XE-133 Cl E E E E XE-133M Cl E E E E XE-135 Cl E E E E XE-135M Cl E E E E XE-138 Cl E E E E UNIDENTIFIED e1 E E E E TOTAL FOR PERIOD Cl E E E E (ABOVE)

2. Iodines 1-131 er -E E E E 1-1"33 Cl E E E E 1-135 Cl E E E E TOTA-b. FOR PERIOD L

Cl E E E E (ABOVE)

3. Particulates C0-58 Cl E E E E SR-.89 Cl E E E E SR-90 Cl E E E E

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

I I REVISION NO.: PROCEDURB TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT I

METHODOLOGY SECTION FLORIDA POWER & LIGHT COMPANY ST.

I LUCIE UNIT#- -

TABLE 3.8: GASEOUS EfffLUENTS - DOSE SUMMATION - CALENqAR YEAR AGE GROUP: INFAN 1T EXPdSUfE INTERVAL: FROf'{I-._ _ _ THROUGH _ _

BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY PATHWAY I I (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) (mrem)

I Ground Piane (A)

' I Grass- -Milk (8)

Inhalation {A) ' I '

I TOTAL

!A) !SECTOR: !RANGE: miles !(B) jcow / GOAT !SECTOR: .!RANGE: miles I N0l3LE GASES CALENDAR YEAR (mrad)

I Gamma Air Dose I I Beta Air Dose I I

0.97 miles I I

Sector: Range:

====================.'--'-:.=========;,;==,=*===ii NOTE The dose values above were calculated using actual meteorological data dL,Jring the specified time interval with MET data reduced as per Re . Guide 1.111, March 197(?.

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50 PROCEDURE NO.:

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C-200 ST. LUCIE PLANT TABLE L-1 EFFLUENT CONCENTRATION LIMITS lN WATER IN UNRESTRIC"FED AR NOTE If a !'.luclide is not-listed below, refer to 10 CFR- Part 20, Appendix B, Table 2 Effluent Concentrations Column 2 arrd use the most conservative EGL listed for the nuclide.

Nuclide ECL (µCi/ml) Nuclide ECL (µCi/ml) Nuclide ECL (µCi/ml)

H-3 - 1 E-3 Sr-92 4 E-5 Te,,129 4_E C-14 3 E-5 Y-90 7 E-6 Te-131m 8 E-6

-Na-24 5 E-5 - Y-91m . -

-2 E-3 Te-131 8 E-5 P-32 9 E-6 Y-91 8&6 Te-132 9-E-6 Cr-51 5 E-4 Y-92 4 E-5 1-130 2E-5

-Mn-54 3 E-5 Y-93 2 E-5 1-131 1 E-6 -

Mn 7 E-5 Zr-95 2 E-5 1-132 1 E-4 Fe-55 1 E-4 Zr-97 9 E-6 1-133 7 E-6 Fe-59 1 E-5 Nb-95 3 E-5 1-134 4 E-4 Co-57 6 E-5 Nb-97 3 E-4 1-135 3 E-5 Co-58 2 E-5 Mo-99 2 E-5 Cs-134 9 E-7 Co-60 _3 E-6 Tc-99m 1 E--3 Cs-136 6 E-6

- Ni-63 1 E-4 Tc-Hl1 2 E-3 -Cs-137 1 E-6 Ni-65 1 E-4 Ru-103 3 E-5 Cs-138 4 E-4 Cu-64 2 E-4 Ru-105 7 E-5 Ba-139 2 E-4 Zn-65 5 E-6 Ru-1-06 3 E-6 Ba-140 8 E-e-Zn-69 8 E-4 Ag-110 6 E-6 Ba-141 3 E-4 Br-82 4 E-5 Sn-113 3 E-5 Ba-142 . - 7 E-4 Br-83 9E-4 ln-113m 7 E-4 La-140 9 E-6 Br-84 4 E-4 Sb-122 1 E-5 La-142 1 E-4 Re 7 E..:6 Sb-124_ 7 E-6 Ce-141 3 E-5 Rb-88 4-E-4 Sb-125 3 E-5 Ce-1-43 2 E-5 Rb-89 9 E-4 Te-125m 2 E-5 Ce-144 3-E-6 Sr-89 8 E-6 Te-127m 9 E-6 Pr-144 6 E-4 Sr-90 5 E-7 Te-127 1 E-4 W-187 3 E-5 Sr-91 2 E-5 - Te-129m 7 E~6 Np-239 2 E-5

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50 OFFSITE DOSE CALCULATION MANUAL (ODCM) of 23 PROCEDURE NO.: \*

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' I I' I TABLE L-2 1liit ,

ENVIRbNMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISGHARGE§ PATHWAY -SALT WATl;:R FISH AND SHELLFISli AGE GROUP - ADUL1' I ORGAN DOSE FACTOR (MR~M/HR PER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDt~EY 1

LUNG GI-LLI WHOLE BODY H-3 0. 3.60E-01 3.60E-01 3.60E-01 3.(;>0E-01 3.60E-01 3.60E-01 C-14 1.45E+04 2,91E+O~ 2.91E+03 2.91,E+03 2.91E+03 2.!;)1E+03 2.91 E+03 NA-24 6.0BE-01 6.0BE-01 ~.OBE-01 6.0BE-01 6.0BE-01 6.0BE-01 6.0BE-01 P-32 1i67Et97 1.05E+06 0. 0. 0. 1.88E+Oq 6;47E+05 CR-51 0. 0. 3.34E+OO 1.23E+Op 7.42E+OO 1.41E+03 5.59E+OO MN-54 0. 7.07E+03 d. 2.10E+03 0. 2.17E+04 1.35E+03 MN-56 0. 1.~8E+02 0. 2.26E+O? 0. 5.68E+03 3.17E+01 FE-55 1.15E+05 5.19E+05 0. 0. 6.01 E+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 C0-57 0. 1.42E+02 b. 0. 0. 3.(30E+03 2.36E+02 C0-58 0. 6.05E+02 b. 0. 0. 1.22E+04 1.35E+03 C0-60 0. 1.74E+03 0. 0. 0. 3.26E+04 3.83E+03 Ni-63 4.97E+04 3.45E+03 0. 0. 0. 7.19E+02 1.67E+03 Nl-65 2.02!=+02 2.63E+01 0. 0. 0. 6.65E+o2 1.20E+01 CU-64 0. 2.15E+02 0. 5.41 E+02 0. 1.83E+04 1.01 E+02 ZN-65 1.62E+05 5.13E+05 0. 3.43E+05 0. 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 µCi/sec releas,e rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

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I TABLE L-2 I I I

,, . <t.

ENVIRONMENTAL RATHWAY-DO§E CONVERSION FACTORS FOR LIQUID DISCHARGES

'PATHWAY -SALT WATER FISH AND SHELLFISH I I A(3E GRQL)P - ADULT ORGA~ DOSE FACTOR (MREMl!-lR PER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDI\JEY I

LUNG GI-LLI WHOLE BODY BR-82 0. 0. 0. 0. 0. 4.68E+OO 4.0BE+OO BR-83 0. 0. 0. 0. 0. 1.05E-01 7i.26E-02 BR-84 0. 0. 0. 0. 0. 7.38E-07 9.42E-02 BR-85 0. 0. q. 0. 0. 0. 3.86E-03 RB-86 0. 6.25E+02 0. 0. 0. 1.23E+02 2.91E+02 RB-88 0. 1.79E+OO 0. 0. 0. 0. 9.5pE-01 RB-89 0. 1.19E+OO 0. 0. 0. 0. 8.3~E-01 SR-89 5.01E+Q3 0. Q. 0. 0. 8.01 E+02 1.44E+02 SR-90 1.23E+05 0. 0. 0. 0. 1.65E+b3 3.02E+04 SR-91 9.43E+01 0. p. 0. 0. 4.75E+02 4.15E+OO SR-92 3.50E+01 0. b. 0. 0. 6.91 (;+02 1.51 E+OO Y-90 6.07E+OO 0. 0. 0. 0. 6.43E+04 1.63E-01 Y-91M 5.74E-02 0. 0. 0. 0. 1.68E-01 2.23E-03 Y-91 8.89E+01 0. 0. 0. 0. 4,89E+04 2.38E+OO Y-92 5.34E-01 0. 0. 0. 0. 9.33E'.+03 1.56E-02 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/f$eC with no a,dditional dilution I ' I

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, 156 of C-200 ST. LUCIE PLANT I TABLE L-2 '.

ENVIRO~MENTAL PATHWAY-DOSE CONVERSION FACTORS 170RUQUID DIS.CHARGES PATHWAY -SALT I I WATER FISH AND SHELLFISH AGE G~OUP -'ADULT '

ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

NUCLIDE BdNE LIVER THYROID KIDNE'Y LUNG Gl-:LLI WHOLE BODY Y-93 1.69E+OO 0. 0. 0. 0. 5.36E+04 4.67E-02 ZR-95 1.60E+01 5.13E+OO 0. 8.09E+OO 0. 1.59E+04 3.47E+OO ZR-97 8.82E-01 1.78E-01 0. 2.69E-01 0. 5.51E+04 ~.19E-02 NB-95 4.48E+02 2.49E+O~ 0. 2.4'i'.E+02 0. 1.51 E+06 9.79E+01 NB-97 3.76E+Op 9.50E-01 q. 1.11 f-+00 0. 3.51E+03 3.47E-01 M0-99 0. *1.28E+02 d. 2.90E+02 0. 2.976+02 4.43E+01 TC-99M 1.30E-02 3.67E,02 0. 5.57E-01 1.8pE,:Q2 2.17E+Q1 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. 1.25F+04 4.61E+01 RU-105 8.90E+OO 0. 6. 1.15E+02 0. 5.44E+03 3.5;1E+OO RU-106 1.59E+03 0. 0. 3.08!=+03 0. 1.03E+09 2.01E+02 AG-110 I

1.57E+03 1.45E+03 q. 2.asl::+03 0. 5.92E+05 8.62E+02 SB-124 2.78E+02 5.2BE+OO 6.71 E-01 0. 2.15E+02 7.85E+03 1.1 OE+02 SB-125 2.20E+02 2.37E+OO 1.96E-01 0. 2.30E+04 1.95E+03 4.42E+01 TE-125M 2.17E+O~ 7.89E+01 6.54E+01 8.83E+Q2 p. 8.67E+02 2.91 E+01 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution I I I I

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50 OFFSITE DOSE CALCULATION MANUAL I (ODCM)

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C-200 ST. LUCIE PLANT TABLE L-2 ENVIRONMENTAL PATHWA'f-DOSE CONVERSION FACTORS FOR LIQUID DISCHAB,GES PATHWAY-SALT WATER.FISH AND SHELLFISH AGE GROUP-ADULT ORGAN DOSE FACTOR (MREM/HR PER µCi/M~)

NUCLIDE BOl,\JE LIVER THYROID KIDNEY LUNG ~1-LLI WHOLE BODY TE-1271\/1 5.5QE+02 1.92E+02 1.40E+02 2.23E+p3 0. 1.84E+O~ q.70E+01 TE-127 8.92E+QO 3.20E+OO 6.61 E+OO 3.63E+01 0. 7.04E+02 1.93E+OO TE-129M 9.32E+02 3.49E+02 $.2QE+02 3.89E+03 0. 4.69E+03 1.48E:,+02 TE-129 2.55E+OO 9.65E-01 1.95E+OO 1.01F+o1 0. 1.92E+OO ~.21 E-01 TE-131M 1.41E+02 6.87E+0,1 1.091;:+02 6.9qE+02 0. 6.81E+03 5.72E+01 TE-131 1.60E+OO 6.98E-01 1.31 (::+00 7.00f=+OO 0. 2.39E-01 5.04E-01 TE-132 2.05E+03 1.33E+02 1.46E+02 1.2s1::+03 0. 6.25E+03 1.24E+02 1-130 1.18E+02 1.50E+04 1.83E+02 0. 1.01E+02 4.93E+01 1-131 2.18E+02 3.13E+02 1.02E+05 5.36E+Q2 0. 8.24E+01 1.79E+02 1-132 1.07E+01 2.85E+01 3.76E+03 4.55E+01 0. 5.36E+OO 1.01 E+01 1-133 7.51 E+d1 1.30[;+02 2.51 E+04 2.27E+02 0. 1.15E+o2 3.98E+01 1-134 5.51E+OO 1.51 E+01 1.96E+03 2.41 E+01 0. 1.32E-02 5.41 E+OO 1-135 2.33E+01 6.14E+01 ~.03E+03 9.77E+01 0. 2.25E+01 CS-134 6.85E+03 1.6~E+04 d. 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 2.04~+03 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

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PROCEDURE NO.:

C-200 ST. LUCIE PLAN~ ..

TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGE~

1 PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT 1

ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

I NUCLIDE BONE LIVFR THYROID KIDNEY LUNG GI-LLI WHOLE BODY CS-137 8.79E+03 1.20E+04 0. 4.09E+03 1.36E+03 2.31 E+02 7.$8E+03 t - - - - - - - - - - + - - - ~ - - - - - - - - - - + - - - - - - - - + - - - - - - - - - - - - ' ' -~*- + - - - - - - - - + - - -

CS-138 6.0~E+00 1.20E+01 0. 8.84E+p0 8. 73E-01 5.12E-05 5.96E+OO BA-139 7.87E+Ob 5.61 E-03 0. 5.24E-03 3.18E-03 1.39E+b1 2.30E-01 BA-140 1.65E+63 2.07E+OO O. 7.04E-p1 1.18E+OO 3.39E:+03 1.09E+02 BA-141 0. 2.89E-03 0. 2.68!=-03 1.64E;-03 1.80E-09 , 1.29E-01 BA-142 1.73E+OO 1.78E-03 0. 1.50E-03 1.01E-03 0. 1.09E-01 LA-140 1.58E+OO 7.95E-01 0. 0. 0. 5.83E+04 2.11 E.-01 LA-142 8.07~-02 t----------+--------+------+--

3.67E-02 Q. 0. 0. 2.68E+02 9.15E-03 C E-141 3.43E+OO 2.32E+OO 0. 1.08E+OO 0. 8.87E+03 2.63E-01 f---C-E---14_3_-------!--6-.05E-O~ 4.47E4-02 0. 1.97E-01 0. 1.67E+04 4.9!?E-02 CE-144 1.79E+02 7.18E+01 0. 4.43E+01 0. 6.05E+0,4 9.6QE+OO PR-144 1.91E-O?- 7.8?E-03 Q. 4.45E-03 0. 2.73E-09 9.65E-04 W-187 9.17E+OO 7.68E+OO 0. 0. 0. 2.51E+b3 2.69E+OO NP-239 3.f?6E-02 3.50E-03 0. 1.08!=-02 0. 7.12E+02 1.92E-03 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

- - - - - - - - - - - - - - - , - - - - - - - - - - - - - - , , - . - - - - - - - : - ,- - ~ - - - - - - - - - - i

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J\..'159 l

of 231 PROCEDURE NO.:

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TABLE L-3 ENVIRONMENiTAL PATHWAY-DOSE.CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY' - SALT WATER FISH AND SHELLFISH AGE GROUP - T~ENAGER ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

NUCLIDE BONF LIVER THYROID KIDNEY LUt\)G Gl-,LLI WHOL_E BODY H----3 0. 2.17E-01 2.17E-01 2.74E-01 2.17q-01 2.17E-01 2.17E-01 C-14 4.94E+03 2.94E+03 2.94E+03 2.22E+d3 2.94E+03 2.94E+03 2.94E+03 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 1.2iE+07 7.98E+05 0. 0. 0. 1.43E+06 4.93E+05 CR--51 0. 0. 2.54E+OO 9.38E-01 5.64E+OO 1.07E;+03 4.25E+OO 1------1------+--------+-----+----*~--------+--

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. 4.3,2E+03 2,.42E+01 FE--55 8.78E+04 3.95E+Op 0. 0. 4.57E+05 1.54E+05 1.04E+05 FE--59 6.14E+0,;4 1.46E+05 Q. 0. 4.05E+04 4.81 E+05 5.55E+04 C0--57 0. '1.08E+02 d. 0. 0. 2. 74E+03 1. 79E+02 C0--58 0. 6.12E+02 0. 0. 0. 8.26E+Q3 1.39E+03 C0--60 Q. 1. 70E+03 0. 0. 0. 2.04E+0 4 1 3.88E+Q3 Ni-63 3.78E+04 2.63E+03 0. 0. 0. 5.47~+02 1.27E+03 Nl--65 1.54E+02 2.00E+01 6. 0. 0. 5.07E+02 9.11 E+OO CU--64 0. 1.64E+02 0. 4.12E+02 0. 1.39E+04 7.69E+01 ZN--65 1.23E+05 3.90E+05 q. 2.61 E+05 0. 2.46E+05 1.77E+05 ZN--69 2.61 E+02 5.0:2E+02 0. 3.24E+02 0. 7.50E+01 3.47E+01 BR--82 0. 0. 0. 0. 0. 3.55E+OO 3.1 OE+OO BR--83 o. o. 0. 0. p. 7.95E-02 5.52E-02 BR--84 0. 0. 0. 0. 0. !?.615,-07 7.16E-02 BR--85 0. 0. 0. 0. b. 0. 2.94E-03 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dih.1tion

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50 pFFSITE DOSE CALCULATION MANUAL (ODCM) .*t,(

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PROCEDURE NO.: It

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TABLE L-3 <l:\*;i ENVIRONt'i15NTAL PATHWA~-DOSE GONVERSION FACTO~S FOR LIQUID DISCHARGES PATHWAY*. ~Al_T'WATI; FISH AND SHELLFISH . . A~E GROUP* TEENAGER 1

1 ORGAN DQSE FACTOR (MREM/HR PER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY RB--86 0. 4.76E+02 0. 0. 0. 9.37E+01 2.22E+02 RB--88 0. 1.37E+OO o. 0. 0. 0. 7.231;-01 RB--89 0. 9.04E-01 0. 0. 0. 0. 6.38E-01 SR--89 5.67f:+03 o. 0. 0. 0. 6.15E+02 1.~l3f-+02 SR--90 1.2~E+05 6. 0. 0. 0. 2.71E+03 3.17E+04 SR--91 7.18E+Q1 0. 0. 0. 0. 3.61 E+02 3.16E+OO SR--92 2.66E+01 0. b. 0. 0. 5.25E+o2 1.15~+00 Y---90 1.58E+01 0. 0. 0. 1.80.E+04 5.23E+04 4.25E-01 Y--91M 4.36E-02 6. 0. 0. 0. 1.28E-01 1.69E-03 Y---91 9.40E+01 0. 0. 0. 0. 3.61E+04 2.51 E+OO Y---92 4.06E-01 0. d. 0. 0. 7.10E+03 1.18E-02 Y---93 1.29E+OO 0. 0. 0. 0. 4.08E+04 3.95E-02 ZR--95 1.49E+01 4.96E+OO 0. 6.16E+QO 0. 1.07E+04 3.46E+OO ZR--97 6.72E-01 1.36E-01 0. 2.05E-01 0. '4.20E+04 6.24E-02 NB--95 3.97E+d2 2.39E+02 0. 1.88E+02 0. 9.76E+05 1.35E+02 NB--97 2.87E+OO 7.24E-01 0. 8.45E-01 0. 2.67E+Q3 2.64E-01 M0--99 0. 9.74E+01 _Q. 2.21 E+02 0. 2.26E+02 1.85+01 TC-99M 9.87E-03 2.7~E-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. 1.441:;-01 Based on 1 µCi/sec release rate of each isotope in discharge flow of *1 cc/sec with no additional dilution I

- I

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,f" 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

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$1 of 2i31 C-200 ST. LUCIE PLANT '\* ... *; i-**,

I I

- \ .,,:\?

TABLE L-3 *':I*,::i;'::\.

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID D.l§CHARGES I AGE GROUP - TEENA GER 1

PATHWAY -SALT WATER FISH AND SHELLFISH '

OR.GAN GOSE FACTOR (MREM/I-IR E'ER ~tCi/ML)

NUCLIDE [30NE LIVER THYROID KIDNEY LUNG Gl-~LI WHOLE BODY RU-103 1.04E+02 0. 0. 3.11 E+02 0. 8.13E+03 4.66E+01 RU-105 6.77E+OO 0. 0. 8.74E+01 0. 4.14E+03 2.67E+OO RU-106 1.76E*rQ3 0. 0. 2.34E+03 o. 7.95E+04 2.21 E+02 AG110 1.19E+03 1.10f=+03 0. 2.17E+Q3 0. 4.51 E+05 6.56E+02 SB-124 2.11 f-+02 3.99E+OO 5.11E-01 0. 1.64E+02I ,

5.98E+03 8.35E+01 SB-125 1.6~E+02 1.81 E+OO 1.49E-01 0. 1.75E+04 1.48E+03 3.37E+o1 TE 125M 2.36E+02 8.45E+01 6.66E+01 6.72E+02 0. 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+OO 3.28E+OO 6.35E+OO 2.761=+01 0. 7.52E+02 1.99E+OO TE 129M 1.02E+03 3.79E+02 3.27E+02 2.96E+03 0. 3.58E+03 1.61 E+02 TE-129 1.94E+OO 7.34E-01 1.49E+OO 8.14f-+OO 0. 1.46E+OO 4.72E-01 TE 131M 1.07E+02 5:22E+01 ~.26E+01 5.29E+o2 0. 5.18E+03 4.35E+01 TE-131 1.21 E+OO 5.08E-01 9.99E-01 5.33E+OO 0. 1.82E-01 3.83E-01 TE-132 2.19E+02 1.3YE+02 1.46E+02 9.74E+02 0. 4.93E+03 1.30E+02 1--130 3.03E+01 8.~5E+01 1.14E+04 1.39E+02 0. 7.67E+01 3.52,E+01 1--131 2.23E+Q2 3.11E+02 ~.07E+04 4.08E+02 0. 5.95E+01 1.87E+02 1--132 8.11E+OO 2.17E+01 2.86E+03 3.46E+01 0. 4.08E+b0 7.71E+OO 1--133 8.11 E+01 1.37E+02 ~.EiOE+04 1.731=+02 0. 9.99E+0*1 4.24E+01 1--134 4.24E+OO 1.15E'+-01 1.49E+03 1.83E+01 0. 1.00E-02 4.12E+OO Bas~d 011 1 µCi/sec release rate d'F each isotope in discharge flow of 1 cc/sec with no additional dilution

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50 OFFSITE DOSE CALCULATION MANl)AL (ODCM) of 23*

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I

' I I I' TABLE L-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTOR§ FOR LIQUID DISCHARGES PATHWAY -SALT WATER FISH AND SHELLFISH AG'r: GRdUP ,.. TEENAGER ORGAN DOSE FACTOR (MREM/HR F/ER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDN8Y LUNG GI-LLI WHOLE BODY 1--135 1,77E+01 4.68E+01 6.11 E+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 2A5E+02 1.55E+03 CS-137 8.98E+Q3 1.21 E+04 0. 3.11 E+03 1.60E/03 1.61 E*r02 4.24E+03 CS-138 4.63E+dO 9.15E+OO 0. 6.73E+OO 6.65~-01 3.90E-05 4.54E+OO BA-139 q.99E+OO 4.27E-03 0. 3.99E-03 2.42E-03 1.06E+01 1.75E-01 BA-140 1.75E+03 2.15E+OO 0. 5.35E-01 ;l.44E+OO 2.55E+02' 1.12[;:+02 BA-141 0. 2.20E-03 0. 2.04E-03 1.25E-03 1.37E-09 9.80E-02 BA-142 1.31 E+OO 1.35E-03 0. 1.14E-03 7.64E-04 0. 8.26E-02 LA-140 1.67E+OO 8.25E-01 0. 0. 0. 4.55E+04 2.18E-01 I

LA-142 6.14E-02 2.79E-02 0. 0. 0. 2.04E+02 6.95E-03 CE-141 3.51E+OO 2.36E+Op 0. 8.1~E-01 0. 6.38E+03 2.?0E-01 CE-143 4.60E-01, 3.40E+02 0. 1.50f--01 0. 1.27E+04 . 3.76E-02 CE-144 2.01E+02 8.25E+01 d. 3.37E+01 0. 4.746+04 1.07E+01 PR-144 1.45E-02 5.9~E-03 0. 3.39E-03 0. 2.08E-O~ 7.34E-04 W--187 6.98E+OO 5.85E+OO 0. 0. 0. 1.91 E+03 2.05E+QO NP-239 2.71E-02 2.67E-03 0. 8.25E-03 0. 5.43!=+02 1.46E-03 Based on 1 µCi/sec release rate of each Isotope in discharge flow of 1 cc/sec with nd additional dilution I

REVISION NO.: PRO(;EDURE TITLE:

IPA<i~r~: .*.,

50 PROCEDURE NO.:

(:)FFSITE DOSE.CALCULATION MA['JUAL (ODCM) t! .,13 of 'i' C-200 ST. LUCIE PLANT .c ....

I ' '

II ' \; /a,,,

TABLE L-4 1

}/ii\j:

ENVIR0~MENTAL PATH~Y-dosE CONVERSION,FACtORS FOR LIQUID Dl§CHARGES PATHWAY ,;-SALT ATER FISH AND SHELLFISH I AGE GROUP - CHILD ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG qi-LLI WHO~E BODY H----3 0. 1.81 E-01 1.81 E:.01 1.19E-01 1.81E-01 1.81 E-01 1.81 E-01 C-14 3.82E+03 3.82E+03 3.82!=+03 9.61E+02 3.82E+03 3.82E+03 3.82E+03 NA--24 2.03E-01 2.03Ei01 2.03E-01 2.03E-01 2.03,E-01 2.036:-01 2.03E-01 I

P---32 5.53E+06 3.47E+05 0. 0. 0. 6.22E+05 2.14E+05 CR--51 0. 0. 1.12E+OO 4.13E-01 2.48E+OO 4.70E+02 1.87E+OO MN--54 0. 2.34E+03 o. 6.95E+02 0. 7.15E+03 4.46f+02 MN--56 0. 5.88E+01 0. 7.46E+01 0. 1.88E+03 1.Q5E+01 FE--55 3.87[;:+04 1.74E+05 0. 0. 2.02E+05 6.81 E+04 4.t)8f-+04 FE--59 2.71E+04 6.43E+04 0. 0. 1.79E+04 2.12E+05 4.45E+04 C0--57 0. 4.78E+01 0. 0. 0. 1.21 E+03 7.94E+01 C0--58 0. 5.05E+02 b. 0. 0. 3.00E+03 1.52~+03 C0--60 0. 1.41E+03 0. 0. 0. 7.80E+03 4.23E+03 Ni-63 1.66E+04 1.15E+O~ 0. 0. 0. 2.39E+02 5.55E+02 Nl--65 6.73E+01 8.74E+Ob 0. 0. 0. 2.2,2E+02 3.98E+OO CU--64 0. 7.15E+01 d. 1.80E+02 0. 6.09E+03 3.36E+01 ZN--65 5.47E+0 41 1.74E+05 0. 1.16E+05 0. 1.09E+05 7.~6E+04 ZN--69 1.16E+02 2.23E+02 0. 1.44E+Q2 0. 3.34E+01 1.55E+01 BR--82 b. 0. 0. 0. 0. 1.59E+OO 1.39E+OO BR--83 0. 0. 0. 0. 0. 3.55E-02 2.47E-02 BR--84 0. 0. 0. 0. 0. 2.51E-07 3.20E-02 BR--85 0. 0. p. 0. 0. 0. 1.31 E-03 Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional diluti1:m I

~ - - - - - - - -

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of ;{11 '

PROCEDURE NO.: r fj1 64 I : '

C-200 I ST. LUCIE PLANT "' '

'i .. ,

I , I TABLEL4

\ ,. ;:'::

1 ENVIRONMEWfAb,PATHWAY-DOSE CONVERSION FACTbRS FOR LIQUID DISCHARGES I

PATHWAY -'SALT WATE~ FISH AND SHELLFISH AGE GROUP - CHILD ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY RB--86 0. 2.08E+02 0. 0. 0. 4.09E+01 9.68E+01 RB--88 0. 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 153E+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+OO SR--92 1.18Et01 0. 0. 0. p. 4.33E+02 5.08E-01 Y---90 9.00E+OO 0. 0. 0. 0. 2.57E+04 2.42E-01 Y--91M 1.95E;:-02 0. 0. 0. 0. 5.71 E-02 7.$5E-04 Y---91 1.2qE+02 0. 0. 0. 0. 1.66E+04 3.34E+OO Y---92 1.81,E-01 0. 0. 0. 0. 3.16E+b3 5.28E-03 Y---93 5.73E-01 0. o. 0. 0. 1.82E+04 1.58E-02 ZR--95 1.80E+01 4.19E+OO b. 2.67f-+OO 0. 4.33E+03 ~.81E+OO ZR--97 2.91 E-01 f5.87E-02 0. 8.86E-02 0. 1.82E+04 2.70E-02 NB--95 4.61E+02 1.976+02 0. 8.11 f-+01 0. 3.41 E+05 1.45E+02 NB--97 1.24q:+Ob 3.12E-01 q. 3.64E-01 0. 1.15E+03 1.14E-01 M0--99 0. 4.23E+01 ci. 9.59E+01 0. 9.81 E+01 8.05E+OO TC-99M 4.34E-03 1.23E-02 0. 1.86E-01 6.01 E-03 7.26E+OO 1.57E-01 TC-101 4.47E-03 6.15E-03 0. 1.16E-0'1 3.29E-03 0. 6.3~E-02 Based on 1 µCi/sec releaseI rate of each isotope in discharge flow of 1 cc/sec with no additional dilution I'

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50 OFFSITE DOSB CALCULATION MANUAL (ODCM)

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C-200 ST. LUCIE PLA~T 1-----------------------------:,*-".'--.---------:i~~~~~

TABLE L-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY-SALT WATER FISH AND SHELLFISH AG!;: GROUP,. CHILD ORGAN DOSE FACTOR (MREM/HR PER µCi/ML)

I NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY RU-103 1.33E+02 0. 0. 1.39E+02 b. 3.50E+03 5.38E+01 RU-105 3.03E+OO 0. 0. 3.91 E+01 0. 1.85E+Oq 1.19E+OO RU-106 2.34E+O~ 0. 0. 1.05E+Q3 0. 3.63E+04 2.91 E+02 AG110 5.18E+02 4.~0E+02 0. 9.43E-t,-02 0. 1.96E+05 2.85Et02 SB-124 9.13E+01 1.72E+OO 2.21 E-01 0. 1.oaE+o1 2.58E+03 3.61 E+01 SB-125 7.24E+01 7.80E~01 6.43E-02 0. 7.57E+P3 6.40E+02 1.46E+01 TE 125M 3.11 E+02 8.43E+01 8.73E+01 2.97E+02 0. 3.00E+.02 4.15E+01 TE 127M 1.85EtQ2 6.47E+01 4.72E+01 7.50E+02 o. 9.19E+02 2.25E+01 TE-127 1.23E+01 3.271;:+00 8.46E+OO 1.22E+01 0. 5.24E*H)2 2.63E+OO TE129M 1.35E+03 3.77E+02 4.31E+02 1.31 E+03 0. 1.63E+03 2.09E+62 TE-129 a.59E-01 ~.25E-01 6.58E-01 3.60E+po 6. 6.47E-01 2.09E-01 TE131M '

4.75E+01 2.31 E+01 3.66E+01 2.34E+b2 0. 2.29E+03 1.93E+01 TE-131 5.38E-01 2.25E-01 4.42E-01 2.36E+OO 0. 8.05E;:-,02 1.70E-01 TE-132 2.78E+02 1.23E+02 1.81E+02 4.31E+02 0. 2.15E+03 1.48E+02 1--130 1.33E+01 ~.94E+01 5.01E+03 6.121::+01 0. 3.3,8E+01 ~ .55E+01 1--131 2.87E+02 2.94E;+02 9.55~+04 1.7QE1*02 0. 2.51E+01 2.22E+02 1--132 3.57~+00 9.55E+OO 1.261=+03 1.52~+01 0. 1.79E+OO 3.39E+OO 1--133 1.05E+o2 1.30E+02 3.13E+04 7.61 E+01 0. 5.26E+01 q.10E+01 1--134 1.86E+OO 5.0~E;+-00 6.58E+02 8.07E+OO 0. 4.41 E-06 1.81 E+OO Based on 1 µCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additiqnal dilution

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50 PROCEDURE NO.:

C-200 OFFSIT'= DO~E CALCULATION MANUAL (ODCM)

ST. LUCIE PLANT I(ft ~~11, 0

TABLE L-4 I

.?'it}J[;r ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTOR~ FOR LIQUl!J DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH - ~GE GROUP - CHILD ORGAN DOSE FACTOR (MREM/HR PER ~tCi/ML)

NUCLIDE BONE LIVER . THYROID KIDN!;Y LUNG GI-LU WHOLE BODY 1--135 7.79E+OO ?.06E+01 2.69E+03 3.27E+01 0. 2.30E+01 7.54E+OO CS-134 8.14E+03 1.37E+04 0. 1.75E+03 1.52E+,03 7.42E+01 2.92E+03 CS-136 2.37E+02 9.34E+02 0. 5.20E+02 7.13E+01 1.0pE+02 6.73E+o2 CS-137 1.13E+0:<1,- , 1.10E+04 0. 1.35E+03 1.29E+03 6.69E+01 1,64E+03 CS-138 2.01 E+Od 3.96E+OO 0. 2.92E+OO 2.8~E-01 1.69E-05 1.97E+OO BA-139 2.65E+OO 1.89E-03 0. 1.77E-03 1.07E-O~ 4.69~+00 7.75E-02 BA-140 2.25E+03 1.98E+OO 0. 2.37E-01 1.18,E+OO 1.15E+02 1.32E+02 BA-141 0. 9.71E-04 0. 9.03E-04 5.51'E-04 6,06E-10 4.34E-02 BA-142 5.81 E-01 5.98E-04 0. 5.05E-04 3.38E-04 0. 3.66E-02 LA-140 2.16E+OO 7.52E-01 0. 0. 0. 2.14E+04 2.54E-01 LA-142 4.74E-Q2 1.24E-02 0. 0. 0. 9.09E+01 3.10E-Q3 CE-141 4.67~+00 2.34E+OO 0. 3.66E-01 0. 2.93E+03 3.48~-01 CE-143 2.0$E-01 1.52E+02 0. 6.69E-02 0. 5.67E+03 1.68E-02 CE-144 2.66E+Q2 8.33E+01 0. 1.50E+01 0. 2.16E+04 1.42E+01 PR-144 6.46E-03 2.67E-03 b. 1.51 E-93 0. 9.26E-10 3.276-04 W--187 3.03E+OO 2.54E+OO 0. 0. 0. 8.31 E+02 8.90E-b1 NP-239 1.18E-02 1.16E-O~ 0. 3.58E-03 0. 2.36E+02 6.34E-04 I I Based on ;I µCi/sec release rate of each isotope in discharge flow 01' 1 cc/sec with no additional dilution I

' 'I '

I

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i----5_0_ _--i OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT-

.\;;':7;:: .3;:Jjji)i.;JJt TABL*E G-1 :,*:," .;,;,',,,~,;~(5/:;:

EFFLUENT CONCENTRATION LIMITS IN AIR IN UNRESTRICTED AREA!f=" .

NOTE If-a nuclide-is not listed below, refer to 10 CFR Part 20, Appendix B, Table 2 Effluent Concentrations Golumr:1 1 and use the most conservative i=CL listed for the nuclide.

Nuclide- ECL (µCi/ml) Nuclide ECL (µCi/ml) Nuclide EGL (µCi/ml)

Ar-41 1 E-8 Co-5:Z -9 E:.10 Sb-1-24 ~ E-10 Kr-83m 5 E-5 Co-58 1 E-9 Sb-125 7 E-10 Kr-85m 1_F-7 Fe-59 5 E-10 Te=125m 1 E-R Kr.,,,85 E-7 I Co 5 E-11 Te~127m 4 E-10 Kr-87

2 E Zn-65 --4 E-10 Te-129m 3 E-10 Kr-88 Kr-89 9 E-9 None Hb-86 Rb-:S8 1 E.c9 9 E-8 J-130 1-1-3-1 3 E-9 2 E-10 J Kr-90 None Sr-89 2 E-10 1-132 2 E-8 Xe-131 m 2 E-6 Sr-90 6 E-12 1-133 1 E-9 Xe-133m 6 E-7 Y-91 2 E-10 1-134 6 E-8 Xe-133 5 E-7 Zr-95 4 E-10 1-135 6 E-9

- . Xe-135m 4 E-8 Nb-95 2 E-9 Cs-134 2 E-10 Xe-135 7 E-8 Ru-rD3 9 E-10 -Cs-136 9 E-10 Xe-137 None- Ru-106 2 E-11 Cs-137 2 E-10 T Xe-138 2 E-8 Ag-11.0 1 E-10 Ba--1.40 2-E-9 H-3 1 E-7 S-n-113 8 E-10 La-140 2 E-9 P-32 1 E,.9- ln,-113m- 2 E-7 Ce-'141 8 E-10 Cr-5-1 3E-8 Sn-123 2 E-10 Ce-144 2 E-11

,Mn-54 1 E-9 Sn-126 8-E-11

50 OFFSITE DOSE CALCULATION fv1ANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-2 odsE FACTORS FOR NOBLE GASES*

TOTAL BODY SKIN GAMMA'AIR BETA AIR ElOSE FACTOR DOSE FACTOR DOSE FACTOR DQSE FACTOR RADldNUCLIDE Ki Li Mi N, (mremtyr per µCi/m 3) (mrem/yr per µCi/m 3) :J!!lrad/yr per µCi/m 3) . (mrad/y,r per µOi/m 3 )

I Kr-83m 7.56E!02** -------- '

1.9BE+01 . 2.88E+02 I ' 1

Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 I

Kr-85 1.61E+01 1.34E+03 ' 1.72E+01, 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+o3 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+Q4 2.93Eto~

' 0 I

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 2.511;:+02 9.94E+02 3°.27E+02 1.481=+03 I

Xe-133 I . 2.94E+02 3.06E+02 3.53E+02 1,.05~+0;3 Xe-135m 3.121;+03 7.11E+02 3.~~E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 I ' 1.92E+03 2.46E+b3 Xe-137 I ' 1.42E+03 I 1.22E+04

' I 1.51 E+03 1.27E+04 I I I

Xe-138 8,83E+03 ' 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+o3 l28f=+03

The listed dose factors are for radionuclides that may be detected i1 gaseolls effluents.

7 .56E-02 = 7 .56 X 10-2

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50 OFFSITE DOSE CALCULATION ¥ANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P {I) FOR GASEOU§ p1SCHARGBS PATHWAY-GROUt,~D Pl.JANE DEPOSITION AGE GROUP -INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER µCi/Sec) I NUCLIDE WHOLE BODY H-3 0.

CR-51 6.68~+06 MN-54 1.10E+Q9 FE-59 3.92E+08 C0-57 1.64E+08 C0-58 5.27E+08 C0-60 4.40E+09 ZN-65 6.871;+08 RB-8(? 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 1.95Et08

~U-103 1.57E+08 RU-106 2.99E+08 AG-110 3.18E+09 Based on 1 µCi/sec release rate of e9ch isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Depo$ition

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P (I) FOR GASEOUS DISCHARGES

' PATHWAY - GROU'NO PLAN~ DEPOSITION AGE GROUP - INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER µCi/Sec)

NUCLIDE WHOLE BbDY SN-126 4.80E+09 SB-124 8.42E+08 SB-125 7.56E+O~

TE-125M 2.19E+06 TE-"127M 1.15E+O~

TE-129M 5.49E+07 1-130 7.90E+06 1-131 2.46E+07 1-132 1.78E+06 1-133 3.54E+O(?

1-134 6.43E+05 1-135 3.66E+06 CS-134 2.82E+09 CS-136 2.13E+08 CS-.-137 1.15(=:+09 BA~140 2.39E+08 CE-141 1.95['.:+07 CE-144 9.52E+07 Based on 1 µCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition I [

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50 OFFSll"E DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT I TABLE G-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R Cl) FOR GASEdUS DISCHARGES PATHWAY-GROUND.PLANE DEPOSITION AGE GROUP-CHILD-TEEN1.ADULT & INFANT I ORGAN DOSE FACTOij (SQ. METER - MRErv,NR PER µCi/Sec)

NUCLIDE WHOLE BCDQY H-3 0.

C-14 0 CR-51 4.68E+06 MN-54 1.38E+09 FE-59 2.75E+08 CQ-57 1.891:i+dB C0-58 3.80E+08 C0-60 2.15E+10 ZN-65 7.43E+08 RB-86 9.01E+06 SR-89 2.171+/-+04 SR-90 5.35E+06 Y-91 1.08E+06 ZR-95 5.01E+08 N!3-95 1.36E+08, RU-103 1.10E+08 RU-106 4.19E+08 AG-110 3.58E+09 Based on 1 µCi/sea rel~ase rate of each isot?pe in and a Value 9f 1. for X/Q, depleted X/Q anq Re;lative D~po,sition

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE bOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 $T. LUCIE PLANT I

TABLE G-4 .

ENVIRONMENTAL f:>ATHWAY ..DOSE CONVERSION FACTORS R (I) FOR GAS.EOUS DISCHARGES PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - CHILD -TEEN-,ADULT & INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER µCi/Sec)

NUCLIDE WHOLE BODY SN-126 5.16E+10 SB-124 5.98,E+QS SB-125 2.30E+09 TE-125M 1.55E+06 TE-127M 8.79E+05 TE-129M 3.85E+07 1-130 5~53E+bf?

1-131 1.72E+07 1-132 1.25E+06 1-133 2.48E+06 1-134 4.50E+05 1-1 (35 2.56E+06 CS-134 6.99E+09 CS-136 1.49E+08

~S-137 1.03E+10 BA-140 1.68E+08 CE-141 1.37E+07 CE--144 1.13E+08 1

Based on 1 µCi/sec release rate of each ii:,otope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition

......_------------,------------,--------.-1,-------......------ .

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J73 of 2;31 C-200 ST. LUCIE PLANT I I ' ' (

TABLE G-5 I ENVIRONMENTAL PATHWAY-DOSE t~)NVERSION FACTQ~S R{l}/P{I) FOR GASEOUS DISCHARGE.$

PATHWAY - INHALATION AGE' GROUP - INFANT .

ORGAN DOSE FACTOR (MREM/YR PER µCi/Cu Meter)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY H-3 0. 4.3QE+02 4.30[;+02 1.88E+02 4.30E+02 4.30E+02 4.3QE+Q2

+------+-----.,------t--------+-----~~-1 C-14 5.04E+03 4.28E+03 4.28E+03 5.98E+02 4.28E+03 4.48E+03 4.28~+03 P-32 2.31 E+05 1°.35E+04 0. 0. 0. 1.51 E+04 8.78E+03 CR-51 0. 0. 1.40E+01 3.99E+OO 2.52E+03 5.81 E,+02 1.75E+01

-.,-----+--------;

MN-54 0. 6.936+03 0. 1. 72E+03 :e.45E+05 1.3~E+04 1.1 OE+03*-----<

FE-59 2.06E+03 4.86E+06 0. 0. 1.78E+05 3.29E+04 1.85E+03 C0-57 0. 1.21 F+o2 0. 0. 6.47E+04 5.50E+03 1.18E+02 C0-58 0. 1.18E+o2 0. 0. 8. 79E+05 1.21 E+04 1.68E+02 C0-60 0. 8.40E+02 0. 0. 5.578+06 3.28E+04 1.17E:+03 ZN-65 5.67E+03 1.81 E+04 0. 1.21 E+04 1.53E+05 9.35E+03 8.15E+03 RB-86 0. 2.37E+04 0. 0. 0. 2.91 E+03 1.03E+04 SR-89 4.31 E+04 0. 0. 0. 2.31 E+06 6.80E+04 1.24E+03 SR-90 1.32E+07 0. 0. 0. 1.53E+07 1.~9E+05 8.06E+05 Y-91 5.98E+04 0. 0. 0. 2.6~E+06 7.17E+04 1.60E+03 ZR-95 1.08E+04 2.73E+03 0. 9.48E+03 1.81 F+06 1.41 E;+04 1.95E+03 NB-95 1i28E+03 5.75E+O~ 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 9.31 E+03 0. 0. 2.34E+04 1.50E+07 1.76E+05 1.14E+03 AG-110 1.89E+03 1.7pE+03 q. 3.44E+03 8.12E+05 5.29E+Q4 1.04E+03 Based on 1 µCi/$ec release rate of each isotope in and a Value of 1. for X/Q, 9epleteq X/Q and Relative Deposition

REVISION NO.: PROCEDURE TITLE: i' Dllr:\F*'*. ,.

I . r~t :' ?':;

11 *.*

50 OFFSITE qosE CALCULATION MANUAL (ODCrvl)

PROCEDURE NO.: {f~p 4 of L,3 *.

C-200 I ST. LUCIE PLANT I ':::,,., ' "

1 TABLE G-5 . *::,:tr':,(/:r** "'

ENVIRONMENTAL PATHWAY-DOSE CO~VERSION FACTORS R{l}/P{I} FOR GASEOUS DISCHABGE:S I PATHWAY- IMHIALATION AGE GRpUP-INfANT I 1

ORGAN QOSE FACTOR (MREMNR. PER µCi/Cu Meter)

NUCLIDE BONE LIVER JHYROID KIDNEY LUNG GI-LU WHOLE BODY SN-123 3.11 E+04 6.45E+02 6.45E+02 0. 3.61E+06 5,99E+04 1.02E+03 SN-126 2.21 E+05 5.85E+03 1.7gE+03 0. 1.64E+06 2.23E+04 8.40E+03 SB-124 5.46E+03 1.03E+02 1.32~+01 0. 4.34E+05 7i11E+04 2.17E+03 SB-125 1.16E+04 1.25E+02 1.03E+01 0. 3.85E+05 1.76E+04 2.32E+Q3 TE-125M 4.q4E+02 1.95E+02 1.53E+02 2.17E+03 4.96E+05 1.36E+04 6.16E+01 TE-127M 2.21 E+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 1-130 8.02E+02 2.~5E+03 3.051::+05 3.65E+03 0. 1.35E+03 9.25E+02 1-131 3.63E+04 4.27E+04 1.41 E+07 1.07E+04 0. 1.07E+03 2.51 E+04 1-132 2.03E+02 5.70[;:+02 7.67E+04 9.09E-+*02 --~*

0. 7.11 E+01 ~.03(;.:+02 1-133 1.34E+Q4 1.93E+0~i1 4.66E+06 4.55E+,03 0. 2.28E+03 5.87E+03 1-134 1.13E+02 3.02E+02 4.02E+04 4.82E+02 0. 1.76E-01 1.08E+02 1-135 4.7QE+02 1.22E+03 1.64E:l-05 1.95E+03 0. ~.1.8E+02 4.51 (:;+02 CS-134 4.80E+05 8.25E+05 0. 5.04E+04 1.01 E+05 1.37E+Oq 7.32E+04 CS-136 6.85E+O~ 2.56(:;+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 4.41 E+04 BA-140 5.70E+03 4.27E+OO 0. 2.93E+OO 1.64E+06 3.88E+03 2.95E+02 CE-141 2.52E+03 1 155E+03 0. 1.10E+03 5.24E+05 2,06E+04 1.81 E+02 CE-144 4.68E+05 1.82E+05 0. 1.48E+05 1.27E+07 1.61 E+05 2.49E+04 Based on 1 µCi/sec release rate of each isotope in and a Value of 1. for X/Q, depl~ted X/Q and Relative Depositior, I I I

I ' >:=~*-

REVISION NO.: PROCEDURE TITLE: PAGE:<,?\

.... /_,:,;\>!--

50 OFFplTE DOSE CALCULATl9N MANUALi (ODCM) :-; <

,, 17;5 of 231 PROCEDURE NO.:

I

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C-200 I I ST. LUCIE PLANT j *.

I I

I I l I '..

TABLE G-6 . ,*,: ,:*\<'*

ENVIRONMENTAL PATHWAY-DOSE CONY:ERSION FACTORS R{l}/P{I} FOR GASEOUS Dl§CHARGES PATHW~Y-COWS MILK (CpNT,AMINATED FORAGE) AGE GROUP - INFANT ORGAN DOSE FACTOR (SQ. METER - MREM/YR PER µi/Sec)

NUCLIDE BONE LIVER THYROID KIDNEY LlJNG GI-LLI WHOLE BODY H-3 0. 2.37E+03 2.37f-+03 1.04E+d3 2.37E+03 2.37E+03 2.37E+03 C-14 6.55E+05 6.95E+05 6.55E+05 7.55E+04. 6.55E+05 6.55E+05 6.55E+05 P-32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 7.05E+08 CR-51 0. 0. 1.82q+04 6.72E+03 4.04E+04 1;66E+06 3.p5E+04 MN-54 0. 8.96E+06 0. 2.67E+06 0. 2.7i4E+07 1.71E+06 FE-59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2.48E+O~ 2.~6E+07 C0-57 0. 1.36E'+06 0. 0. 0. 3.466.+07 2.27E+06 C0-58 0. 2.55E+07 0. 0. b. 6.60E+07 6.24E+Q7 C0-60 0. 8.73E+07 0. 0. 0. 2.16E+08 2.09E+08 ZN-65 1.46E+09 4.651::+09 0. 3.11 E+09 0. 2.93E+09 2.10E+09 RB-86 0. 2.77~+09 0. 0. o. 5.45E+08 1.29E+09 SR-89 1.47E+10 0. 0. 0. 0. 2.75E+08 4.22E+oa SR-90 1.65E+11 0. 0. 0. 0. 1.61 E+09 4.21E+10 Y-91 8.12E+04 0. 0. 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+Oq 2.47E+05 0. 4.84E+04 0. 1.98E+08 1A5E+05 RU-103 8.30E+03 0. 0. 4.16E+03 0. 1,04E+05 2.86E+03 RU-106 2.01 E+05 0. 0. 4.20E+04 0. 1.566+06 2.46E+04 AG-110 6.21 E+07 5.75E+07i 0. 1.13E+08 0. 2,35E+10 3.42E+07 Based on 1 µCi/sec release rate of each isotope in and a Value of 1. tor X/Q, depleted X/Q and Relative Deposition 1

Note: The unit~ for C-1, 4 and H-3 are (MREM/YR Per µCi/Cu. Meter)

I I I

REVISION NO.: PROCEDURE TITLE:

I 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT I TABLE G-6 ENVIRONMENTALPATHWAY-DOSE CONVERSION FACTORS R{l)/P(I} FOR GA~EOUS DISCHARGES PATHWAY-COWS MILK (CONTAMINATED FORAGE) AGE GROUP- INFANT ORGAN DOSE F)\CTOR (SQ. METER - MREMNR PER µCi/Sec)

NUCLIDE BONE LIVER Tr-1YROID KIDNEY LUNG Gl,LLI WHOLE BODY .

1-------+------+---------j SN-126 1.75E+09 3.48E+07 1.01 E+07 0. 4.97E+06 1.16E+09 q.25E+07 f---------+------+--------+------!---------+--* ---+*-----"--------<

SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 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 2.1 OE+07 TE-127M 5.54E+07 1.93E+07 1.79~+07 2.00E+08 0. 3.24E+08 7.38E+06 f--------+------+--------+--~---l---------+-------+---'-----l---

TE-129M 5.87E+08 2.02E+08 2.21 E+08 2.70E+08 0. 3.54E+08 8.95E+07 1-130 4.54E+05 1.35E+06 1. 71 E+08 2.09E+06 0. 1.15E+06 5.29E+05 1-131 2.59E+09 ~.09E+09 9.94E+11 7.24E+08 0. 1.16E+08 1.81 E+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 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 4.416+04 1.44E+04 CS-134 4.43 E;+ 1p 7 .97E+ 10 0. 4.65E+_0~~----1f---9._1_2E_:*+_0~9-,___1_.9_0_E+_0_8_-+-_6_.7_5_E_+_09_----l CS-136 2.78E+08 1.1 OE+09 0. 6.11 E+08 8.37E+07 1.25E+08 7.90E+08 CS-137 6.44E+10 7.21E+10 0. 3.66E+09 ~.69E+09 1.86E+08 4.14E+09 BA-140 2.45E+08 2.47E+05 0. 1.22E+04 1.51 E+05 8."13E+Oq 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+0~1 8.29E+06 0. 5.67E+05 0. 8.66E+08 1.13E+06 Based on 1 µCi/sec release rate of e~ch isotope in and a Value of 1. for X/Q, depleted X/Q and R~lative Deposition Note: The units for C-14 qnd H-3 are (MREMNR Per µCi/Cu. Meter)

REVISION NO.:

50 PROCEDURE T\TLE: I OFFSITE DOSE CALCULATION MANUAL (ODCM)

IPAqS?:~1[

PROCEDURE NO.:

l);:1t:r of '

"1 C-200 I ST. LUCIE PLANT >

Y,i ' '1 I ' I I I I i", '\'

TABLE G-7 ')i/.-:'!i:i'~f/[i:,

ENVIRONMENTAL PAT!::!WAY-DQSE CONVERSION FACTORS R{l)LP{I} nOR GASEOU§ DISCHARGES PATHWAY-GOATS Milk (CONTAMINATED FORAGE) ' 1 1

AGE GROUP- INFANT bRGAN DOSE FACTOR (SQ. METER - MR EMNR PER µCi/Sec)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI \NHOLE BODY H-3 0. 4.84E+03 4.84E+03 2.11 E+03 4.84Et03 4.84E-f*03 4.84E+03 C-14 6.55E+05 6.55E+05 6.55E+05 7.75E+04 6.55E+05 6.55E+05 6.55E+05 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. 3.2~E+Oq 2.09E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+09 3.72E+05 C0-57 0. 1.64(2+05 0. 0. 0. 4.15E+06 2.721:;+05 C0-58 0. 3.Q61;:+06 d. 0. 0. 1.92E+06 7.49E+06 C0-60 0. 1.05E+07 0. 0. 0. 2.59E+07 2.51E+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. 0. 6.54E+07 1.55E+08 SR-89 3,09E+10 0. 0. 0. 0. 5.77E+os 8.87E+08 SR-90 3.46E+11 0. 0. 0. 0. 3.35E;.+09 8.83E+10 Y-91 9.74~+03 d. 0. 0. 0. 6.45E+05 2.60~+02 ZR-95 2.54E+04 1.13E+0;4 Q. 2.23E+03 0. 8.95E+06 6.67E+03 NB-95 6.59E+04 2.97E+04 0. 5.81E+03 0. 2.37E+07 1.75E+04 RU-103 ~.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+Ol,5 2.96E+03 AG-110 7.45E+065 6.90E+06 0. 1.36E+G7 0. 2.81 E+09 4.10E+06 Based on 1 µCi/sec releas~ rate of each isotope in and a Value of 1. for X/Q, depleted X/d. find Relative Deposition Note: The units for 0-14 qnd H-3 are (MREMNR Per µCi/Cu. Meter)

I

' I

I REVISION NO.: PROCEDURE TITLE: PAGE::**; .,,...:; > \:::;

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 78., of PROCEDURE NO.:

C-200 ST. LUCIE PLANT r

I

){. ,.'/,*

<,;;:('\. cs TABLE G-7 ii ENVIRONMENTAL PATHWAY-DOSE C.ONVERSION FACTORS R(l}/P(I} FOE! GASEOYS DISCHARG!;S PA;THWAY - GOATS MILK (CONTAMINATED FORAGE) AGE; GROUP~ INFANT ORGAN DOSE FACTOR (SQ. METER - MREM~R PER µCi/Sec)

NUCLIDE BON~ LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY SN-126 2.10E+0~3 4.17E+06 1.22E+06 0. 5.97~+05 1.40E+Q8 6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+06 9.33F+o7 1.30E+06 SB-125 4.31 E+06 3.92E+05 3.52E+05 4.766+05 3.40E+08 2.92E+07 7.94E+05 TE-125M 1.89E+07 6.36E+06 6.~1 E+06 8.46E+06 0. 9.p9E+06 2.52E+06 TE-127M 6.64E+06 2.31E+06 2.15E+06 2.40E+Q7 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 1-130 5.45E+05 1.61 E+06 2.05E+08 2.51E+06 0. 1.38E+06 6.35E+05 1-131 3.11 E+09 3.70E+09 1.19~+12 9.28E+08 0. 1.39E+08 2.17E+09 1-132 2.13E-01 £).71 E-01 1.51 E+01 9.10E-01 0. 1.07E-01 2.03E-01 1-133 4.50E+07 6.57E+07 1.55E+10 1.55E+07 0. 1.17E+Q7 1.99E+07 1-134 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+10 5.69Et08 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 2.16E;+11 0. 1.10E*r10 2.61E+10 5.59E+oa 1.246+10 BA-140 2.95E+Q7 2.96E+0,4 0. 1.47Et03 1.a1 E+o4 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 µCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative D1ppositiqn Nbte: The units for C-14 and H-3 are (MREM/YR Per µCi/Cu. Meter)

I I REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION IVJANUAL (ODCM)

I PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-8 ENVIRONMENTAU. PATHWAY~DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES I ' PATHWAV - INHALATION AGE GIROl,l'P - CHILD I ORGAN DOSE FACTOR (MREM/YR PER µCi/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY H----3 0. 7.51 E+02 7.51 E+02 4.96E+02 7.51 E+02 7.51 E+02 7.51 E+02 C-14 6.25E+O~~ - - - t 6.25E+03 6.25E+03 1.58E+03 6.2!;iq+03

t---------t-------t--~"---+------f-----------1 6.25E+03 6.25E+03 P---32 6.!11 E+05 3.57E+04 0. 0. 0. 4.00E+04 2.32E+04 CR--51 0. 0. ?.75E+01 1.06q-r01 6.66E+03 1.54E+03 4.63E+01 MN--54 0. 1.83E+04 0. 4.55E+03 6.48E+05 ~.58E+04 2,.91 Et03 FE--59 5.44E+03 1.28E+07 0. 0. 4. 70E+05 8.'7bE+04 4.88E+03 C0--57 0. ~.20E+02 0. 0. 1.71 E+05 1.45E+04 3.10E+02 C0--58 0. 1.52E+02 0. 0. 1.13E+06 3.62E+04 2.68E+02 C0--60 0. 1.07E+03 0. 0. 6.92E+06 9.36E+04 1.8~E;+03 ZN--65 1.50E+04 4.77E+04 Q. 3.19E+04 4.03E+05 2.47E+04 2.151;:+04 RB--86 0. 6.25E+04 0. 0. 0. 7.70E+03 2.73E+04 SR--89 5.37E+04 Q. 0. 0. 2.24E+06 1.691;:+0p 1.54E+03 SR--90 1.64E+b7 0. 0. 0. 1.48E+07 3.45E+05 9.9~E+05 Y---91 7.44E+04 0. 0. 0. 2.55E+06 1.78E+05 1.98E+03 ZR--95 1.41 E+04 3.2eE+03 0. 2.51 E+04 2.12E+06 5.74E+04 2.98E+03 NB--95 1.70E+03 7.25E+02 0. 3.58E+03 5.85E+05 3.328+04 5.33E+02 RU-103 2.16q+Q~ 0. 0. 2.70E+03 6.331+/-+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. 9.1 OE+03 2.15E-'1-09 1.40E+05 2.75E+03 Based on 1 µCi/sey release rate of each isotope in and a value of 1. for X/Q, depleted X/Q and relative deposition

REVISION NO.: PROCEDURE TITLE: ' I '

P~q;'"}

PROCEDURE NO.: I/ 1a,o of C-200 ST. LUCIE PLANT .. :: : .

' I I ' /

TABLE G-8 ENVIRONMENTAL PATHWAY-DOSE CO~VERSION FACTORS R{I} FOR GASEOUS blSO:HARGES o~~:HNWtJs*~~~~~~ON(MREM/Yt~:RG:C~/~)~.-~~ti°R)

I NUCLIDE BONE LIVER THYROID KIDNEY qJNG GI-LU WHOLE BODY SN-123 3.85E+04 6.44E+o2 6.81E+02 0. 3.50E+06 1A~E+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. 1.15~+06 1.88E+05 5.74E+03 SB-125 3.06E+04 3.30E+02 2.72E+01 0. 1.028+06 4.66E+04 6.14E+03 TE 125M 5.62E+02 1.94E+02 1,61 E+02 5.74E+03 4.81 Et05 3.38E-f*04 7.62E+01 TE 127M 5.85E+03 2.6QE+03 :I .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+Q4 1.80E+06 1.82E+05 2.60E+02 1--130 2.12E+03 6.22E+03 8.07E+05 9.66E+03 0. 3.56E+03 2.45E+03 1--131 4.55E+04 4.63E+04 1.54E+07 2.84E+04 0. 2.(;>pE+03 3.5QE+04 1--132 5.37E+02 1.51 E+03 2.03E+05 2.40E+03 0. 1.88E+O? 5.37E+02 1--133 1.68E+04 2.05E+04 5.03E+06 1.20E+04 0. 5.55E+03 8.03E+03 1--134 2.98E+02 7.Q91;:+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 1.81 E+04 6.77E+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 3.41 E+03 1.25E+05 BA-140 7.14E+03 4.66E+OO 0. 7.73E+OO 1.74Et06 9.92E+-03 4.22E+02 CE-141 3.13~+03 1.57!:E+03 0. 2.90E+O~ 5.14q:+05 5.44E+04 2.33~+02 CE-144 5.81E+05 1.82E+05 Q. 3.92E+05 1.23E+O"i:' 4.00E+05 3.10E+04 Based on 1 µCi/sec release rate of each isotope in and a value of 1. for X/0., depleted X/Q and relative deposition I !

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

OFFSITE QQSB CALCULATION MANUAL (ODCM) p:lJtt:;1J;

C-200 ST. LUCIE PLANTI I

[:illil i } :, '

, ,,,, *)';;;.,,..,//' *_,;?'

TABLE G-9 1

'i;,;) ,,,,

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DIS~HARGES PAT~WAY -COWS MILK (CONTAMINATED FORAGE) 1 J\G~ GROUP ,. CHILD ORGAN DOSE FACTOR (SQ. METER-MRE;M/YR PER µCl/SEC)

I NUCLIDE BONE Ll,VER 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 C-14 3.08E+05 3.08E+05 3.08E+05 7.75E+04 3.d8E+05 3.0,8E+05 3.oaF+05 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. 2.741;:+07 1.71 E+06 FE--59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2.48F+oa 2.86E+07 C0--57 0. 1.36E+06 0. 0. 0. 3.46E+07 2.27E+06 C0.,-58 0. 1.25E+07 0. 0. 0. 7.41E+07 3.76E+07 C0--60 0. 4.22E+07 0. 0. 0. 2.33E+08 1.27E+08 ZN--65 1.46E+09 4.65E+09 0. 3.11 E+09 0. 2.93E+09 2.10E+09 RB--86 0. 2.776+09 0. 0. 0. 5.45E+08 1.29E+09 SR--89 6.92E+*og 0. 0. 0. 0. 2.58E+08 1.986+08 SR--90 1.13E+11 Q. d. 0. 0. 1.!52E+O~ 2.87E+10 Y---91 3.80E+04 0. 0. 0. 0. 5.05E+Q6 1.01 E+03 ZR--95 1.06E+05 4.476+04 0. 1.86E+04 0. 7.681i:+Q7 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. 1.05Et05 1.61 E+03 RU-106 9.39E+04 0. 0. 4.20E+04 0. 1.46E+06 1.17E+04 AG110 6.21E+07 5.75~+07 0. 1.13E*r08 0. 2.35E+10 3.426+07 Based on 1 µCi/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 µCi/cu. meter)

I

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200 I

OFFSITEI DOSE CALCULATION MANUAL (ODCM)

ST. LUCIE PLANT

!({2!:;~l:

I TABLE G-9 \('.y ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS ~ISCl::!ARGES PATHWAY~ COWS MILK (CONTAMINATED FORAGE) AGE GROUP - CHILD

@RGAN DOSE FACTOR (SQ. METER-MREM/YR PER f-LCI/SEC)

WHOLE NUCLIDE BONE LIVER THYROID KIDNEY LUf\JG GI-LU BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 1.75E+09 3.48E+07 1.01 E+07 0. 4.97E+06 1.16E+ci9 5.25E+07 SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.7aE+08 1.0~E+07 SB-125 3.13E+07 1.41 E+06 1.18E+06 3.96E+06 2.83E+09 2.43E+08 5.99E+06 TE125M 7.38E+07 2.00E+07 2.07E+07 7.05E+07 0. 7.12E+07 9.84E+06 TE 127M 5. i18E,+0"'1 1.78E+07 1.46E+07 2.00E+08 0. 4.99E+08 6.60E+06 TE129M 2.77E+08 7.73E+07 ~.85E+07 2.70E+08 0. 3.3~E+08 4.28E+07 1--130 4.54E+05 1.35E+06 1.71 E+08 2.09E+06 0. 1.15E+06 5.29E+05 1--131 1.24E+09 1.27E+09 4.12E+11 7.74E+Q8 0. 1.b9E+os 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.~0E+06 8.63E+06 1--134 0. 0. 1.06E-09 0. 0. 0. 0.

1--135 1.49E+04 3.94E+04 q.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 1.10(;+09 0. 6.11 E+08 8.37E+07 1.25E+08 7.90E+08 CS-137 3.08E+10 2.981:;:+10 0. 3.66E+09 3.491;+0~ 1.81 E+ba 4.44E+09 BA-140 1.17E+08 1.02E+05 0. 1.22E+04 6.09E+04 7.75E+06 6.84E+b6 CE-141 1.2,4E+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. 8.156,+08 5.34E+05 Based on 1 ~tCi/sec release rate of eaqh isok:>pe in and a value bf 1. for X/Q, depleted X/Q and relative deposition

~ate - the units for C---14 and H----3 are (mrem/yr per µCi/cu. meter~

I . ' I

REVISION NO.: PROCEDURE TITLE:

p~?~:,

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 83 of 23 PROCEDURE NO.:

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' I ST. LUCIE PLANT I ' /'ti TABLE G-10 ENVIRONMENTAL PA"{HWAY*DOSE CONVERSION FACTORS R(I} FOR GASEOUS DISCHARGES

. PATHWAY-GOATS MILK (CONTAMINATED FORAGE) AGE GROUP -CHILD ORGAN DOSE FACTOR (SQ. METER-MR\=f'.1NR PER 11CI/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI Wt,OLE BODY H--~-3 0. 3.20E+03 3.20E+03 2.11 E+03 3.20E.+03 3.20E+03 3.20E+03 C-14 3.08E+05 3.08E+05 3.08E+05 7.75E+04 3.0~E+os 3.08E+06 3.08E+05 I

P---32 2.19E+10 1.37E+09 0. 0. 0. 2.46E+Q9 8.46E+08 CR--51 0. 0. 2.19E+03 8.07E+02 4.~5E+03 9.19E+05 3.66E+03 MN--54 0. 1.08E+06 0. 3.20E+05 0. 3.29E+06 4.0tiE+05 FE--59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 3.72E+05 C0--57 0. 1.64E+05 0. 0. 0. 4.15E+06 2.72E+05 C0--58 0. 1.50E+06 0. 0. 0. 8.90E+06 4.51E+06 C0--60 0. 5.06E+06 Q. 0. 0. 2.80E+07 1.52E+07 ZN--65 1.76E+08 5.57E+08 6. 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 1.45E+10 0. 0. 0. 0. 5.43E+08 4.16E+08 SR--90 2.37E+11 0. 0. 0. 0. 3.1(3E+09 6.0~E+10 Y---91 4.56E+03 0. 0. 0. 0. 6.06E+09 1.22E+02 ZR--95 1.27E+04 5.37E+03 0. 2.23E+03 0. 9.22E+06 3.96E+03 NB--95 3.30E+04 1.41 l;:+04 d. 5.81E+03 0. 2.44E+07 1.04E+04 RU-103 4.79E+02 0. 0. 4.99E+02 0. 1.26E+04 1.94E+02 RU-106 1.13E+04 0. 0. 5.04E+03 0. 1.75E+05 1.40E+03 AG110 7.49E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 4.10E+06 Based on 1 µCi/sec rele1:1se rate of each isotope in and a value of 1. tor XIQ, d~pleted X/Q 1rnd relptive deposition Note - the uni.ts for C---14 and H----3 are (mremtyr per µCi/cu. meter)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT

\-!

TABLE G-10 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS Rm l=oR GASEOUS DISCHARGES, PATHWAY-GOATS MILK (CONTAMINATED FORAGE) . I AGE GROUP -CHILD .

ORGAN DOSE FACTOR (SQ. METER-MPffM/YR PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY SN-123 0. 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.?5E+06 1.70E+05 1.43E+05 4.76E+05 3.4bEt08 2.92E+07 7.19E+05 TE 125M 8.8~E+06 2.40E+06 2.49E+06 8.46E+06 0. 8.54E+Q6 1.18E+06 TE127M 6.21E+Q6 2.14E+06 1.75E+06 2.40E+07 0. 3.5.8E+07 7.92F+o5 TE129M 3.32E+07 9.27E+06 1.06E+07 3.23E+07 0. 4.00E+07 5.15E+06 1--130 5.45Et05 1.61 E+06 2.05E+08 2.51E+06 0. 1.38E+06 6.35E+05 1--131 1.48E+O~ 1.52E+09 4.94E+11 9.28E+08 0. 1.30E+08 1.15E+09 1--132 2.13E-01 5.71E-01 7.51 E+01 9.10E-01 0. 1.07!=-0;1 2.03E-01 1--133 2.14E+07 2.64E+07 6.36E+09 1.55E-lj07 0. 1.07E+07 'l.04E/07 1--134 0. 0. 1.~?E-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 6.50E+10 1.10E+11 0. 1.39E+10 1.22E+10 5.92E+08 2.33E+10 CS-136 8.34E+08 3.296+09 0. 1.8~E+09 2.51E+O~ 3.'74E+08 2.37E+09 CS-137 9.23E+10 8.9iE+10 0. 1.10E+10 1.05E+10 5.44E+08 1.336+-10 BA-140 1.40E+07 1.23E+04 ci. 1.47E+03 7.31 E+03 9.30E+05 8.21 E+05 CE-141 1.49E+04 7.46E+03 0. 1.17E+03 0. 9.36E+0.6 1.11 E+03 CE-144 1.20E+06 3.76E:+05 0. 6.80E*.+-04 0. 9.78\;:+Q7 6.41E+04 Based on 1 µCi/sec release rate of each isotope in and a value of 1. for X/Q, depleted X/Q and relative peposition Note - the units for C---14 and H----3 are (mrem/yr per µCi/cu. meter)

,__________. . . _____,,-,;------------------------------:--------1

I I '.,

REVISION NO.: PROCEDURE TITLE: jPAGE:'

50 OFFSITE DOSE CALCULATION MANUA~ (ODCM)

185 of 2;31 :,1' PROCEDURE NO.: *. \

C-200

! ;: ;:;:*:J I

ST. LUCIE PLANT :/*<t?I/

I TABLE G-11 I ';:tHJ; ENVIRONMENTAL PATHWAY-DOSE OO~VERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATED FORAGE) ' AGE GROUP - CHILD

' I ORGAN DOSE Fr'ACTOR (SQ. METER-MREMNR PER µCl/SEC)

WHOLE NUCLIDE BONE L.IVER THYROID KIDNEY LUNG GI-LLI BODY H----3 0. 2.33E+02 2.33E+02 1.54E+02 2.33E+02 2.33E+02 2.33E+02 I '

C-14 9.87E+04 9.87E+04 9.87E+04 2.49E+04 9.87E+04 9.87E*+-04 9.87E+04 P---32 1.74E+09 1.09E+08 0. 0. 0. 1.96E+08 6.73E+07 CR--51 0. 0. 1.58E+03 5.82E+02 3.5pE+03 6.63E+05 2.64E+03 MN--54 0. ' 3.42E+06 0. 1.02E*.t-06 0. 1.05E+07 6.54E+05 FE--59 9.95E+07 2.36(;:+08 0. 0. 6.55E+07 7.79E+08 8.98E+07 C0--57 0. 2.10E+06 0. 0. 0. 5.33E+07 3.50E+06 C0--58 0. 1.69E+07 0. 0. 0. 1.00E+08 5.10E+07 C0--60 0. I 6.77E+07 0. 0. 0. 3.75E+,08 2.03E+08 ZN--65 1.33q+08 4.22E+08 0. 2.82E+08 0. 2.66E+08 1.91 E+08 RB--86 0. 1.82E+08 0. 0. 0. 3.59E+07 ~.50E+07 SR--89 5.04E+08 0. 0. 0. 0. 1.88E+07 - 1.44E+07 SR--90 1.05E+10 0. 0. 0. 0. 7.b2E+08 2.67E+09 Y---91 1.76E+06 0. 0. 0. 0. 2.33E+08 4.69E+04 ZR--95 4.62E+06 1.51 E+06 0. 7.47E+05 0. 2.22E+09 1.20E+06 NB--95 2.68E+06 1.15E+06 0. 4.72E+05 0. 1.98E+09 8.41 E+05 RU-103 1.45E+08 0. o. 1.51 E+OB 0. 3.~1E+09 5.87E+07 RU-106 4.51 E+09 6. 0. 2.02E+09 0. 7.01E+10 5.61E+08 AG110 2.50E+06 ~.311;+06 0. 4.55E+06 0. 9.44E+08 1.38E+06 Based on 1 ~tQi/sec relypse 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 µGi/cu. meter)

I

REVISION NO.: PROCEDURE TITL.'.E: I I I PAGE: ',e:c'*,,, ,,, ...

50 PROCEDURE NO.:

C-200 OFFSITE DDSE CALCULATION MANUAL (ODCM)

$T. LUCIE PLANT

le: fi{:f of I

'H'" ( .,

'q:i(.Y .

I TABLE G-11 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATHWAY -MEAT (CON"fAMINATED FORAGE) AGE GROUP -tHILD .

ORGAN QOSE FACTOR (SQ. METER-MREMN'R PER µCl/SEC)

WHOLE NUCLIDE BONE l-lVER THYROID KIDNEY LUNG GI-LU BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 6.92E+09 1.37E+08 4.02E+07 0. 2.41E+96 2.31E+09 1.98E+08 SB-1i4 7.40~+06 1.40E+05 1.79E+04 0. 5.74E-t,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 TE127M 4.40E+08 1.51 E+08 1.24E+08 1.70E+09 0. 2.54E+09 5.61E+07 TE 129M 1.8~ff+09 5.12E+08 5.87E+08 1.78E+09 0. 2.21E+09 2.84E+08 1--130 8.87E-Q7 2.63E-06 3.34E-04 4.08E-06 0. 2.25E-06 1.031=-06 1--131 1.58E+07 1.62E+07 5.25E+09 9.86E+06 0. 1.38E+06 1.22E+07 1--132 0. 0. 0. 0. 0. 0. 0.

1--133 6.(36E-01 8.47E-01 2.04E+02 4.97E-01 0. 3.43E-01 3.33E-01 1--134 0. 0. 0. 0. 0. 0. 0.

1--135 3.21 E-02 2.99E-02 6. 1.12E-P2 3.37E-03 6.92E-04 1.32E-02 CS-134 8.83E+08 1.49E+09 0. 1.89E+Q8 1.65E+08 8.P1E+06 3.16E+08 CS-136 4.41E+06 1.74E+07 0. 9.69E+06 1.33E+06 1.98E+06 1.25E+07 CS-137 1.27E+09 1.23E+09 0. 1.51 E+08 1.44E+08 7.5pE+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 0. 1.32E+07 1.57E+03 CE-144 2.38E+06 7.46E+05 d. 1.35E+05 0. 1.94E+08 1.27E+05 Based on 1 µCi/sec release rate of each- isotope in and a value of 1. f~r x/p., depleted X/Q and relative deposition Note - the units for C---14 and H----3 are (mrem/yr ~er µCi/cu. meter)

I

' I I

REVISION NO.: PROCEDURE TITLE: n, " :.:, ::- __

~~;~;}

50 OFFSIT\= QQSE CALCULATIOI\J MANUAL (ODCM)

PROCEDURE NO.: of 2r~i(ift';!

C-200 I

ST. LUCIE PLANT h'<ii{ i >I

'\rt '

TABLE G-12 ENVIRONMENTAL PATHWAY-DOSE CCINVERSION FACTORS R{I} FOR GASEOUS DISCHARGES I

PATHWAY - FRESH FRUITS ANp VEGETABLES AGE GROUP - CHILD ORGAN DOSE FA~TQR (SQ. METER-MR~f\1/Yf1 PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG ~1-LLI WhlOLE BODY H----3 0. 2.47E+02 2.47E+02 1.63E+02 2.47E+02 2.47E+02 , 2.47E+02 C-14 4.04E+04 4.04E+04 4.04E+04 1.02E+04 4.04E+04 4.04E+04 4.04E+04 P---32 4.22E+08 2.!31E+07 0. 0. I

0. 4.74E-1,07 1.63E+07 CR--51 Q. 0. 4.68E+03 1.73E+03 1.046+04 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 C0--57 0. 7.53E+05 0. 0. 0. 1.91 E+07 1.25E+06 C0--58 0. 6.94E+06 0. 0. 0. 4.13E+07 2.09E+07 C0--60 0. 2.33E+07 0. 0. 0. 1.29E+0,8 6.98E+07 ZN--65 2.08E+07 6.59E+07 0. 4.41E+07 0. 4.15E+07 2.98F+o7 RB--86 0. 5.28E+07 0. 0. 0. 1.04E+07 2.46E+07 SR--89 4.84Et09 0. 0. 0. 0. 1.81 E+08 1.39E+08 SR--90 7.79E+1(.) 0. 0. 0. 0. 1.52E+09 1.98E+10 Y---91 2.12E+06 0. 0. 0. 0. 2.821::+08 5.65E+04 ZR--95 4.06E+05 9.87E+04 0. 6.07E+,-04 0. 1.08E+08 8.81 ~+04 NB--95 6.20E+04 2.64E+04 0. 1.09E+04 0. 4.p8E+07 1.94E+04 RU-103 2.24E+06 0. 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 6.366+05 0. 1.25E+06 0. 2.59E+08 3.78E+05 Based on 1 µCi/sec release rate of each isot0pe in and a value of 1. for X/Q, depleted X/Q andI relative deposition I

i-1 ;-

,-R-EV-IS-IO_N_N_O-.:---..-P-RO_C_E-DU-.R-E'-T-ITL_E_:- - * , ---*--1-:*---------------------~P=AGT1-"':"::,.-,.,,.,~.~ *:,:---:*,--,

50 OFFSITE D<;)pE CALCULATION MA!'JUAL (ODCM)

.;'::?~:q~!0' PROCEDURE NO.:

,190 of C-200 ST. LUCIE PLANT ' :1::::,::1 I

TABLE G-12 I ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I) FOR GASEOUS DISCHARGES PATHWAY - FRESH FRUITS AND VEGETABLES ' AGE GROUP - CHILD I '

ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER µCl/SEC)

NUCLIDE BONE LIVER THY~OID KIDNEY L~JNG GI-LU WHOLE BODY SN-123 1.71 E-05 2.14E-07 2.26E-07 0. 0. 8.50E-09 fL21 E-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 6.9~E+05 6.Q2E+05 2.09E+06 1.04E+09 9.02E+07 2.29E+06 TE 125M 4.12E+O~ 1.12E+07 1.16E+07 3.94E+07 0. 3.97E+07 5.49E+06 TE 127M 2.88E+07 9.90E+06 8.09E+06 1.11 E+08 0. 1.65E+08 3.67E+06 TE 129M 1.56E+08 4.35E+07 4.99E+07 1.51 E+08 0. 1.88Et08 2.41 E+07 1--130 1.qOE+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 1.86E+05 1--131 1.24E+08 1.27E+08 4.13E+10 7.75E+07 0. 1.09E+07 9.58E+07 1--132 2.29E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 2.15E+01

----+-------l 1--133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 ' 0. 1.81 E+06 1.75E+06 1--134 4.18E-05 1.14E-04 1.47E-02 1.81 E-04 0. 9.89E-08 4.06E-05 1--135 1.64Et04 4.33E+04 5.67E+06 6.89E+04 3.51 E-03 4.85E+04 1.59E+04 CS-134 9.97E+O~ 1.68E+09 0. 2.14E+08 1.87q+08 9.08E+p6 - t - - -3.57E+08 CS-136 1.356+07 5.32E+07 0. 2.96E+07 - . - + -

4.06E+06 6.05E+06

+----------+-----------<

3.83E+07 CS-137 1.41E+09 1.37E+09 (,). 1.681:;+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 Q.96E+06

--+--~----.-----~---+-------,

CE-141 1.17E+05 5.841:;+04 0. 9.13E+G3 0. 7.33E+07 8.69E+03 CE-144 9.23E+06 2.89E+06 0. 5.22E+05 0. 7.51 E+08 4.92E+05

~----~-----~-----~------+------~-----~-

Based on 1 µCi/sec release ratr of each isotope in and a value of 1. for X/Q, depleted X/Q and relative deppsition

I I

' I PAGE:':**/.,

REVISION NO.: ' ' PROCEDURE TITLE: I 1,1~9' of 231Ii~

50 OFF811TE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200

' I '

ST. LUCIE PL,4.NT I

. ).....

TABLE G-13 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUR -' TEENAGER ORGAN DOSE FACTOR (MREM/YR PER µCl/OU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H----3 0. 8.48E+02 8,48E+02 1.07E+03 8.48E+02 8.48E+02 8.48E+02 C-14 4.58E+03 4.53E+03 4.53E+03 3.42E+03 4.53E+03 4.58E+03 4.53E+03 P---32 1.32E+O(? 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+O~ 2.78E+07 0. 0. 1.02E;+06 1.88E+05 1.06E+04 C0--57 0. 6.92E+02 0. 0. 3.70E+os 3.14E+04 6.71 E+02 C0--58 0. 1.76E+02 0. 0. 1.3iF-+06 9.52E*t04 2.34E+02 C0--60 0. 1.24E+03 0. 0. a.56F+o6 2.35E+05 1.65E+03 ZN--65 3.24E+04 1.03E+05 0. 6.Q0~+04 8.7~E+os 5.34E+04 4.66E+04 I

RB--86 0. 1.35E+05 0. 0. 0. 1.66E+Q4 5.90E+04 SR--89 3.8'7E+04 0. 0. 0. 2.qOE+06 3.54E+05 1.11 E+03 SR--90 1.18E+07 0. 0. 0. 1.66E+07 7.24:E+05 7.2qE+05 Y---91 5.q8E+04 0. 0. 0. 2.86E+06 3.74E+05 1.44E+03 ZR--95 1.09E+04 3.63E+03 0. 5.42E+04 2.56E+06 1.33E+05 2.54E+03 NB--95 1.36E+03 8.24E+02 0. 7.74E+03 7.178+05 ~.80E+04 4.62E+02 RU-103 1.63E+02 0. 0. 5.83E+03 7.51Et05 9.44E-t*04 7.32E+01 RU-106 8.40E+03 0. 6. 1.34E+os 1.641;+07 9.28E+05 1.06E+03 AG110 1.08E+04 1.00E+04 0. 1.97E+Q4 4.64E+06 3.02E+05 5.94E+03 Based on 1 µCi/sec release rate of each isotope in and a value of 1. for X/Q, depleted X/Q and r~lative deposition

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-13 ENVIRONMENTAL PATHWAY-DC:>SE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP' - TEENAGER. ,

ORGAN DOSE FACTOR (MREM/YR PER µCl/CU. METER)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY SN-123 2.79E+04 6.14E+02 4.92E+02 0. 3.Q1E+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.~9E+02 7.55~+01 0. 2.48E+06 4.06E+05 1.24E+04 SB-125 q.61 E+04 7.13E+o2 5.87E+01 0. 2.2QE+06 1,01 E+05 ~ .33E+04 TE 125M 4.07~+02 1.86E+02 1.17E+02 1.24E+04 5.361:;+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 TE129M 1.19E+03 5.64E+02 3.90E+02 3.66E+04 2.03E+06 3.84E-t,*05 1.92E+02 1--130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.6~E+03 5.29E+03 1--131 3.37~+04 4.72E+04 1.39E+07 6.14E+04 0. 5.96E+03 2.82E+04 1--132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 1.16E+03 1--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. 1.01 E+OO 6.16E+02 1--135 2.6~E+03 6.99E+03 9.36E+05 1.11 E+04 0. 5.25E+Q3 2.58E+03 CS-134 4.83E+Q5 1.10E+06 0. 2.88E+05 1.44E+05 8.9.~E+03 5.44F+o5 CS-136 3.91 E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 1.11 E+05 CS-137 6.42Et05 8.24E+05 0. 2.22E+05 1.18~+05 7.68E+03 3.03E+05 BA-140 5.~0E+O$ 4.85E+OO 0. 1.67E+01 2.02g+o6 2.12E+04 3.42E+02 CE-141 2.27E+03 1.52E+03 0. 6.26E+03 5.83E+05 1.14F+05 1.74E+02 CE-144 4.19E+05 1.74E+05 0. 8.486~05 1.38E+07 8.40E+05 2.24E/04 Based on 1 µCi/sec release rate of each isotope in and a value of 1, for X/Q, depleted X/Q. and relative deposition

~---------'-------'-------.,--,,------------------,,_,_ ______________ __.

REVISION NO.: PROCEDURE TITLE: ' I I PA~E: ;(> -

~.,.: ,i 50 OFFSITE DOSE CALCULATION MANUAL (OIDCM) -'){'"

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!?~)(

C-200 I I ST. LUCIE PLANT ' ,--

I I

' ' )Ji' TABLE G-14 ENVIRONMENTJ~L PATHWAY-DOS~ ~ONVERSION FAC:TORS R{l},FOB GASEOUS DISCHARGES 1

PATHWAY-COWS MILK (CQNTAMINATED FORAGE) AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ. METER7MREM/YR PER µCl/SEC)

NUCLIDE BONE LIVER THYR©ID KIDNEY LUNG GI-L,.LI WHOLE BODY H----3 0. 9.93E+02 9.93EE+02 1.26E+03 9.93E+02 9.93F+o2 9.93E+02 C-14 1.25E+05 1.25E+05 1.25E+05 9.39E+04 1.25E+05 1.25E+05 1.25E+05 P---32 2.21 E+10 1.38E+09 0. 0. 0. 2.48E+09 8.54E+08 CR--51 0. q. 2.21 F-+04 8.15E+03 4.90E+04 9.29E+06 3.69E+04 MN--54 0. 1.09E+07 0. 3.23E+06 0. 3.:33E+07 2.07E+06 FE--59 3.84E+07 9.12E+07 0. 0. 2.53E+07 3:01E+08 3.47E+07 C0--57 0. 1.65E+06 0. 0. 0. 4.19E+07 2.75E+06 C0--58 0. 8.1QE+06 0. 0. 0. 1.10E+08 1.85E+07 C0--60 0. 2.73E+07 0. 0. 0. 3.27E+08 6.23E+07 ZN--65 1.77E+09 5.63E+09 0. 3.77E+09 0. 3.55E+09 2.55E+09 RB--86 0. 3.35E+09 0. 0. 0. 6.61Et08 1.56E+09 SR--89 2.~0E+09 0. 0. 0. 0. 3.03E+08 8.03E+07 SR--90 8.29E+10 0. 0. 0. 3.3aE+06 1.76E+09 2.05E+10 Y---91 1.51E+04 0. 0. 0. 0. 5.93E+06 4.12E+02 ZR--95 4.78E+04 2.84F-+04 0. 2.25E+04 0. 1.15E+08 1.60E+04 NB--95 1.24E+05 7.46E+04 0. 5.87E+04 0. 3.05E+08 4.21 E+04 RU-103 1.69E+03 0. 0. 5.04E+03 0. 1.32E+05 7.56E+02 RU-106 3.83E+04 0. 0. 5.09E+04 0. 1.73E+p6 4.81E+03 AG-110 7.53E+07 6.97E+07 0. 1.37E+08 0. 2.84E+10 4.14E+07 Based on 1 µCi/sec releas.e rate of each isotope in and a value of ~. for X/Q, depleted X/Q and relativ~ deposition Note - the units for C---14 and H----3 are (mre)ni/yr per µCi/cu. meter)

I

REVISION NO.: f ROCEDURE TITLE: ' I '

50 PROCEDURE NO.:

C-200 OFFSlTE DOSE CALCULATION MANUAL (ODCM)

ST. LUCIE PLANT

~*;g~;, r:;11ii 2

I I

' 1 \ ('

TABLE G-14 ,, ,,*:...*,

/

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I} FOR GASEOUS DISCHARGES PATHWAY - COWS MILK (CONT~IVIINATED FORAGE) AGE GROUP -TEENAGER ORGAN, DOSE FACTOR (SQ. METER~MREM/YR PER µCl/SEC)

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

SN-126 2.12E;:+09 4.21 E+07 1.24E;:+07 0. 6.03E+06 1.41 E+og 6.37E+07 SB-124 3.33E+07 6.29E+05 8.0$E+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 TE125M 3.00E+07 1.08E+07 8.47E+06 8.55E+07 0. 8.39E+07 3.98E+06 TE 127M 6.02E+07 2.11 f,+07 1'.59E+07 2.43E+08 0. 3.02E+08 7.45E+06 TE 129M 1.13E+O~ 4.18E+07 3.61E+07 3.27E+08 0. 3.93E+08 1.78E+07 1--130 5.51E+05 1.63E+06 2.07E+08 2.53E+06 0. 1.40E+06 6.41 E+05 1--131 5.12E+08 7.24E+08 2.p9E+11 9.38E+08 0. 1.37E+08 4.31E+08 1--132 2.16E-01 5.76E-01 7.59E+01 9.19E-01 0. 1.0BE-01 2.05E-01 1--133 7.33E+06 1.24E+07 2.26E+09 1.56E+07 0. 9.02E+06 3.83E+06 1--134 0. 0. 1.29,E-09 0. 0. 0. 0.

1--135 1.81 E+04 4.77E+04 6.24E+06 7.58E+04 9.?~p-02 5.34E+04 1.75E+04 CS-134 9.44E+09 2.28E+10 0. 5.63~+09 2.76E+09 2.63E+08 1.06E+10 CS-136 3.37E+08 1.33E+09 0. 7.41 E+OB 1.02E+OB 1.51 E+QB 9.58E+08 CS-137 1.2~E+10 1.72E+10 0. 4.43E+09 2.~8E+09 2.29E+d8 6.Q4E+09 BA-140 4.84E+07 5.95E+04 0. 1.48E+04 3.98E+04 9.1qE+06 3.11 E+06 CE-141 5.Q5E+04 3.39E+04 0. 1.18E+04 0. 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 µCi/sec release rate of each is,otppe in and a value of 1. for X/Q, deRleted X/Q and relative deposition Note - the unit$ for C---14 and H----3 are (mrem/yr per µCi/cu. rr1eter)

REVISION NO.: PROCEDURE TITLE: ' PAGE:,::,::"' ** *.

50 PROCEDURE NO.:

OFFSITE DOS~~ CALCULATION MANUAL (ODCM)

/::j'gf of 23.f'>

C-200 ST. LUCIE PLANT I t::*.**:;A*.******

I I

TABLE G-15 *.,_\"'

ENVIRONMENTAL PATHWAY-DOSE .CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATHWAY-GOATS MILK (tONTAMINATED FORAGE) ' AGE GROUP - TEENAGER ORGAN DOS~c FACTOR (SQ. METER-,-MREM/YR PER µGI/SEC)

NUCLIDE BONE LIVER Tt-lYROID KIDNEY LUNG GI-LLI WHOLE BODY H----3 0. 2.03E+03 2.03E+03 2.56E+03 2.03E+03 2.03E+03 2.03E+03 C-14 1.25E+05 1.25E+os 1.25E+05 9.39E+04 1.25E+05 1.25E+05 1.25E+05 P---32 2.651:;+10 1.66E+09 0. 0. Q. 2.98E+09 1.03E+09 CR--51 0. 0. 2.6$E+03 9.78E+02 5.88E+03 1.11 E+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 1.19E+06 0. 0. 3.29E+05 ~.91 E+06 4.51 E+05 C0--57 0. 1.98E:+05 0. 0. Q. 5.03E+Op 3.30E+05 C0--58 0. 9.72E+05 0. 0. 0.

.. 1.31 E+O? 2.22E+06 C0--60 0. 3.28~+06 0. 0. 0. 3.93E+o7 7.48E+06 ZN--65 2.13E+08 6.76,E+OB 0. 4.52E+08 0. 4.26E+08 3.06E+08 RB--86 0. 4.02E+08 0. 0. 0. 7.93E+07 1.88E+08 SR--89 5.87E;+09 0. 0. 0. d. 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. .Q. 7.11E+05 4.94E+01 ZR--95 5.74E+03 3.41 E+03 Q. 2.70E+03 6. 1.38E+Q7 1.93E+03 NB--95 1.49E+04 8.96E+03 6. 7.05E+03 0. 3.66E+07 5.05E+03 I

RU-103 2.0~E+02 0. 0. 6.05E+02 0. 1.58j=+04 9.08E+01 RU-106 4.59E+03 0. 0. 6.11 E+03 0. 2.08E+05 5.78E+02 AG110 9.04E+06 8.36E+06 0. 1.64E+07 0. 3.41 E+09 4.97E+06 Based on 1 µCi/sec release rate of each is.otppe in and a value of 1. for x.tb., depleted X/Q and relative deposition Note - the units for C---14 and H----3 are (mrem/yr per µCi/cu. meter)

I

REVISION NO.: PROCEDURE TITLE: : I PAGE:f; ..*

I I 50 PROCEDURE NO.:

OFFSITE DOSE CALCULATION MANUAL (ODCM) .* t9~ of ;;3J C-200 ST. LUCIE PLANT '

i.

I I I I I

. ii;;;:,,Jt?/

I TABLE G-15 , I I ./,0fl)';jij. ,, *..

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATMWAY - GbATS' MILK (CONTAMINATED,, FORAGE) AGE GROUP-TEENAGER ORGAN DOSE FACTOR (SQ. METER-MREMNR PER µCl/SEC)

NUCLIDE BONE LIVER Tr,YROID KIDNEY Ll)NG GI-LU WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 0.

SN-126 2.54E+08 5.05E+06 1.48E+06 0. 7.23E+05 1.69E+08 7.64E+06 SB-124 4.00E+06 7.54E+04 9.66E+03 0. ~.10E+06 1.13E+08 1.58E+06 SB-125 4.14E+06 1.15E+05 6.06E+04 5.77E+05 4.12E+08 3.54E+07 8.19E+05 TE125M 3.61E+06 1.29E+06 1.02E+06 1.03E+07 0. 1.01E+07 4.78E+05 TE127M 7.23E+06 2.52E+06 1.91 E+06 2.92E+07 0. 3.63E+07 8.94E+05 TE 129M 1.35E+07 5.02E+06 4.34E+06 3.92E+07 0. 4.72E+07 2.13E+06 1--130 6.61E+05 1.96E+06 2.L~9E+08 3.04E+06 0. 1.68E+06 7.69E+05 1--131 6.15E+08 8.68E+08 2.50E+11 1.13E+09 0. 1.64E+08 5.17E+08 1--132 2.59E-01 6.92E-01 9.11 E+01 1.10E+OO 0. 1.30E-01 2.46E-01 1--133 8.79E+06 1.49E+07 2.71 E+09 1.88E+07 0. 1.oaE+07 4.59E+06 1--134 0. 0. 1.55E-09 0. 0. 0. 0.

1--135 2.17E+04 5.73E+04 7.49E+06 9.10E+04 2.94E-01 6.41 E+04 2.10E+04 CS-134 2.83E+10 6.83E+10 0. 1.69E+10 8.27(;:+09 7.88E+oa 3.19E+10 CS-136 1.01 E+09 3.99E+09 0. 2.22E+09 3.osE+oa 4.54E+08 2.87E+09 CS-137 3.84E+10 5.16E+10 0. 1.33~+10 9.85Bt09 6.88E+08 1.81E+10 BA-140 5.81E+06 7.14E+03 0. 1.78E+03 ,t78E+03 1.10E+06 3.73E+05 CE-141 6.06E+03 4.07E+03 G. 1.41 E+03 0. 1.1 OE+0;7 4.66E+02 CE-144 4.92E+05 2.02E+05 0. 8.24E+04 0. 1:1~E+08 2.6*1~+04 Based on 1 µCi/stpc 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 µCi/au. meter)

REVISION NO.: PROCEDURE TITLE:

i I 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 . ST. LUCIE Pq'.\NT TABLE G-16 ENVIRONMENTAL F?ATt:M{AY-DOSE CONVERSION FACTORS R{I) FOB....@ASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATED FORAGE) AGE GROUP -TEENAGER ORGAr~ DOSE FACTOR (SQ. METER-MREMNR PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU WHOLE BODY H----3 0. 1.93E+02 1.93E+02 2.44E+02 1.93E+02 1.93E+02 1.93E+02 C-14 5.23E+04 5.2,3E+04 5.23E+04 3.94E+04 5.23E+04 5.23E+04 P---32 2.76E+09 1.73E+08 0. 0. 0. 3.10E+Q8 1.07E+08 CR--51 0. 0. 2.50E+03 9.22E+02 5.55E+03 1.05E+Oq 4.18E+03 MN--54 0. 5.42E+06 0. 1.61 E+06 0. 1.66E+07 1.04E+06 FE--59 1.58~+08 3.74E+08 0. 0. 1.04E+08 1.24E+09 1.42E+08 C0--57 0. 3.33E+06 0. 0. 0. 8.45E+07 5.54E+06 C0--58 0. 1.44E+07 0. 0. 0. 1.94E+08 3.27E+07 C0--60 0. 5.73E+07 0, 0. 0. 6.87E+08 1.31 E+08 ZN--65 2.11 E+08 6.69t=+08 0. 4.47E+08 0. 4.21 E+08 3,.03E+08 RB--86 0. 2.89E+08 0. 0. 0. 5.69E+07 1.35E+08 SR--89 2.66E+08 0. 0. 0. 0. 2.89E+07 7.64E+06 SR--90 1.01 E+10 0. 0. 0. 2. 79E+08 1.02E+09 2.49E+09 Y---91 9.34E+Oq 0. 0. 0. 0. 3.59E+08 2.49E+04 ZR--95 2.67E+06 1.24E+06 0. 1.18E+06 0. 4.20E+09 7.61 E+05 NB--95 1.58E+06 9.51E+05 0. 7.48E+05 0. 3.88E-.+-09 5.371::+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. 3.20~+09 0. 1.09E+11 3.02E+08 AG110 3.97E+06 3.67E+06 0. 7.21E*,+-06 0. 1.!)0E+09 2.18E+06 Based on 1 µGi/sec re,ease rate of each isotobe in and a value of 1. fpr X/Q, depleted X/Q and re_!lative deposition Note - the units for C---14 and H----3 are (mrem/yr per µCi/cu. IT)eter)

REVISION NO.:

50 PROCEDURE TITLE:

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1iit PAGE'" ::1; of c PROCEDURE NO.:

1~ . :.

C-200 ST. LUCIE PU~~NT \'

.J

" ~( ::.i TABLE G-16 :Jt,;* t**

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS Rll} FOR GASEOUS DISCHAR~

PAT'"'WAY - MEAT (CONTAMINATED FORAGE) AGE GRqUP .. TEE;NAGER ORG.AN DOSE FA~TOR (SQ. METER-MREMNR PER µ81/SEC)

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

SN-126 1.10E+10 2.18E+08 q.:38E+07 0. 3.82E+06 3.66E+09 3.14E+08 SB-124 1.17E+07 2.21E+05 2.84E+04 0. 9.11 E+06 3.32E+08 4.64E+06 SB-125 5.01 E+07 1.31 E+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. 3.41 E+09 1.53E+08 1--130 1.41 E-06 4.16E-06 5.3PE-04 6.47E-06 0. 3.57E-06 1.64E-06 1--131 8.54E+06 1.21 E+07 3.48E+09 1.56E+07 0. 2.28E+06 7.19E+06 1--132 0. 0. 0. 0. 0. 0. 0.

1--133 3.69E-01 6.26E-01 1:14B:+02 7.88E-01 0. 4.55E-01 1.93E-01 1--134 0. 0. 0. 0. 0. 0, b.

1--135 5.0BE-02 4.69E-02 0. 1.78E-02 5.34~-03 1.10E-03 2.0~E-02 CS-134 5.03E+08 1.21 E+09 0. 3.00E+08 1.47E+08 1.40E+07 5.66E+08 CS-136 6.99E+06 2.7@E+07 0. 1.54E+O(' 2.11 E+06 3.14E+p6 1.99E+07 CS-137 6.92E+08 9.31E+08 0. 2.40E+08 1.24E+os 1.24E+07 3.27E+08 BA-140 2.37f:i:+07 2.93E+04 0. 7.28E+03 1.95E-+:04 9.19E+06 1.53E+06 CE-141 1.12E+04 7.51E+03 0. 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 µC,i/sec release rate of each isotope in and a value of 1. for X/Q, depl~ted X/Q and relative depqsition Note - the units for C---*.14 and H----3 are (mrem/yr p:er µCi/cu. rrieter)

I I I I I '

'a\)

I I , I REVISION NO.: PR9CEDURE TITLE:

50 I

I PA1\¥J PROCEDURE NO.: Ji 197 of C-200 I ST. LUCIE PL~,NT ' ',, :* '* ,' ,,

TABLE G-17

';\/ ' .'.'/

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES

'PATHWAY - FRESH FRUITS AND I VEGETABLES AGE GROUP - TEENAGER '

ORGAN DOSE FAqTOR (SQ. METER-MREMtyR PER µCI/SqC)

NUCL!DE 1;30NE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H----3 0. 2.09E+02 2.09E+02 2.64E+02 2.09E+02 2.09E+02 2.09E+02 C-14 2.181;:+04 2.18E+04 2.18E+04 1.64E+04 2.18E+04 2.18E+04 2.18E+04 P---32 6.81E+08 4.27E+07 0. 0. 0. 7.66E+07 2.64E+07 CR--51 0. 0. 7.56E+03 2.7QE+03 1.68E+04 3.18E+06 1.27E+04 MN--54 0. 3.20E+07 q. 9.52E+06 0. 9.80E+07 6.11 E+06 FE--59 2.39E+07 5.67E+07 0. 0. 1.57E+07 1.87E+08 2.16E+07 C0--57 0. 1.22E+06 0. 0. 0. 3.09E+07 2.02E+06 C0--58 0. 6.01E+06 0. 0. 0. 8.12~+07 1.37E+07 C0--60 0. 2.01E+07 0. 0. 0. 2.41 F+08 4.58E+07 ZN--65 3.35E+07 1.06E+08 0. 7.12E+07 0. 6.70E+07 4.82E+07 RB--86 0. 8.52E+07 0. 0. 0. 1.68E+07 3.97E+07 SR--89 2.61 E+09 Q. 0. 0. 0. 2.83E+08 7.48E+07 SR--90 7.61E+10 0. 0. 0. 2.41 E+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+Q4 0. 1.92E+08 5.61 E+04 NB--95 3.72E+04 2.24E+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 1.11 E+06 1.03E+06 0. 2.02E+06 0. 4.19Et08 6.10E+05 I

Based on 1 µCi/sec release rate of each isotope in and a value df 1. for X/Q, depleted X/9, and relative deposition

REVISION NO.: PROCEDURE TITLE: I I '

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50 OFFSITE DOSE CALCULATION MANUAL (ODCM) of 231 PROCEDURE NO.:

i C-200 ST. LUCIE PLANT '

I I '

TABLE G-17 ENVIRONMENTAL PATHWAY~DOiE CONVERSION FACTORS R{I} FOR.GASEOUS DISCHARGES PATHWAY- FRESH FRUITS AND VEGETABLES I

AGE I

GROUP-TEENAGER I

ORGAN DOS!= FACTOR (SQ. METER-MREMNR PER µCl/SEC)

NUCLIDE ~ON6 LIVER THYROID KIDNEY LUN~ GI-LU WHQLE 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.J24E+07 3:64E+06 0. 2.83E+06 5.55E+d8 1.94E+07 SB-124 1.65E+07 3.12~+05 B.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 6.3qE+07 0. 6.24E+07 2.96E+06 TE 127M 4.46E+07 1.55E+07 1.18E+07 1.80E+08 0. 2.43E+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 1--130 2.58E+05 7.64E+O~ 9.72E+07 1.19E+06 0. 6.55E+05 3.00E+05 1--131 6.84E+07 9.66E+07 2.79E+10 1.25E+08 0. 1.83E+07 5.76E+07 1--132 3.651;+01 9.77E+01 1.29~+04 1.56E+02 0. 1.84E+o1 3.47E+01 1--133 1.98E+06 3.36E+06 6.1i)E+08 4.23E+06 0. 2.44E+06 1.04E+06 1--134 6.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1.60E-07 6.56E-05 1--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 1.401=+09 0. 3.45E+08 1.69E+08 1.61 E+07 6,.52E+08 CS-136 2.18E+07 8.60E+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 f21E+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+01 0. 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 µCi/sec relea~e rate of e;,:1ch isotope in and a value of 1. for X/Q, depleted X/Q and relative deposition I I

REVISION NO.: PROCEDURE TITLE: I p~~~:. ;}';, *, .***

50 OFFSITE DPSE CALCULATION MA~~UAL (ODCM)

PROCEDURE NO.: {' 1~9 of 2!t C-200 ST. LUCIE PLANT j ; .,

I I TABLE G-18 *'*

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FA<J:TORS R{I} FOR GASEOUS DISCHARGES PATHWAY- INHALATION tGE GROUP-ADULT ,

ORGAN DOSE ~ACTOR (MREM/YR PER µCl/CU. METER)

NUCLIDE BONE l,_IVER TrJYROID KIDNEY LUNG GI-LLI WHOLE BODY H----3 0. 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 C-14 1.82E~d4 3.4eE+04 3.42E+03 3.42E+03 3.42E+03 3.42E+03. 3.42E+03 P---32 1.32E+06 7.72E+04 0. 0. 0. 8.64E+Q4 5.0?E+04 CR--51 0. 0. p.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 'l.18E+04 2.78E+07 q. 0. 1.02E+06 1.88E+05 1.06E+04 C0--57 0. 6.92E+02 0. 0. 3.70E+05 3.14!=+04 6.71E+02 C0--58 0. 1.58E+03 q. 0. 9.28E+05 1.06E+05 2.07E+03 C0--60 0. 1.15E+04 0. 0. 5.98E+06 2.85E+05 1.48E+04 ZN--65 3.24E+04 1.03E+05 0. 6.90E+04 8.72E+05 5.34E+04 4.66E+04 RB--86 0. 1.39E+05 0. 0. 0. 1.66E+04 5.90E+04 SR--89 3.04E+05 0. 0. 0. 1.40E+06 3.50E+05 8.72E+03 SR--90 9.92E+07 0. 0. 0. 9.60E+06 7.22E+05 6.10E+06 Y---91 4.62E+05 0. 0. 0. 1.70E+06 3.85E+05 1.24E+04 ZR--95 1.07E+05 3.44E+04 o. 5.42E+04 1.78E+06 1.50E+05 2.33E+04 NB--95 1.41E+04 7.82E+03 0. 7.74E+03 5.06E+05 1,04E+05 ll-.21E+03 RU-103 1.53E+03 0. 0. 5.83E+03 5.06E:;+05 1.10E+05 6.5~E+02 RU-106 6.91E+04 0. 0. 1.34E+05 9.44E+06 9.12E+05 8.72E+03 AG110 1.08E+04 1.00E+04 0. 1.97E+04 4.64E+06 3.02E+p5 5.94E+03 Based on 1 µCi/pee release rate of each isotope in and a value of 1. for 'f,./Q, der:1leted X/Q and relative deposition

REVISION NO.: PROCEDURE TITLE: PAGE:'*

I <.**

50 PROCEDURE NO.:

OFFSITE DOS~ CALCULATION MANUAL (ODCM)

!. 200 of ~\;,rx, C-200 ST. LUCIE PLANT TABLE G-18 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY- INHALATION ,~GE GROUP -ADULT 1

ORGAN DOSE FACTbR (MREMNR F>ER µCl/CU. METER)

.____N_U_C_L_ID_E_-+--__B_O_N_E_--+_ _ LI_V_E_R_---+-_T_H_Y~~~O_ID_--+-__

K_ID_N._E-'Y_----+--__

1 -- L_U_N_G_ _.____G_I_-L_L_I-*--+-_W_H_O_L_,E__B_O_D_Y-----i 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 0. 9.36E+06 1.27E+05 4.80E+04 SB-124 s.*:12E+Q4 5.89E+02 7.55E+01 0. 2.4,8E+06 4.06E+05 1.24E+04 SB-125 6.61 E+04 7.13E+02 5.87E+01 0. 2.20E+06 1.01 E+Q5 1.33E+04 TE 125M 3.42E+Q3 1.58E+03 1.05E+03 1.24E+04 3.14E+05 7 .06E+d4 4.67E+02 TE 127M 1.261;:+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+Q6 3.83E+05 1.58E+03 1--130 4.58E+03 1.34E+04 1.74E+06 2.0~E+04 0. 7.69E+03 5.29E+03 1--131 2.52E+04 3.58E+04 1.19E+07 6.14E+04 0. 6.28E+03 2.05E+04 1--132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 1.16Et03 1--133 8.64E+O~ 1.49E+04 2.93E+06 2.60E+Q4 0. 8. 72E+03 4.54E+03 1--134 6.45E+02 1.73E+03 2.30E+05 2.75E+03 0. 1.011;:+00 6.16E+02 1--135 2.69E+03 6.99E+03 9.36E+05 1.11 E+04 0. 5.25!=+03 2.58E+03 CS-134 3.74E+05 8.48E+05 0. 2.88E+05 9.76E+04 1.04E+04 7.29E+05 CS-136 3.91 E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 1.11 E+05 CS-137 4.78E+05 q.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 1.431;:+06 0. 8.4~E+Q5 7.78E+06 8.16E+05 1.84E+05 Based or1 1 µCi/sec release rate of each isotope in and a value bf 1. for Xtq, depl~ted X/Q and relative deposition

, I

' - - - - - - - - - - - - - - - - - - - - - * - - - - - - - - - - - - : , ' -- - - - , , - ~ - - - - - - - - - - - - - - - - - J

REVISION NO.: PROCEDURE TITLE: I 50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 201 of 2.3t PROCEDURE NO.: !

C-200 ST. LUCIE PLANT ,!

I' TABLE G-19 ENVIRONMENTAL PATHWAY-DOSH CONVERSION FACTORS R{I) FOR GASEOUS IDISCHARGES PAlHWAY-COWS I

MILK (CONTAMINATED FORAGE) AGE GROUP

-ADULT I

ORGAN DOSE FACTOR (SQ. METE~-MREMNR PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDt~EY 1

LU~JG GI-LLI WHOLE BODY H----3 0. 9.73E+02 9.73.E+02 9.7~E+02 9.73E+02 9.73E+02 9.73E+02 C-14 3.63E+05 7.28~+04 7.281=+04 7.28E+04 7.~.8E+04 7.28E+04 1

P---32 1.71E+1o 1.07E+09 0. 0. 0. 1.92E+09 6.62E+08 CR--51 0. 0. 1.71 E+04 6.32E+03 3.80E+i04 7.20E+06 2.86E+04 I

MN--54 0. 8.41 E+06 2.50E+Q6- + - -0.- - - - - - + -2.58E+07

---s--+-------j 1.61 E+06 FE--59 2.98E+07 7.06E+07 0. 0. 1.96E+07 2.33E+d8 2.69E+07 C0--57 0. 1.2~1;:+06 o. 0. 0. 3.25E+07 2.13E+06 C0--58 0. 4.72E+06 0. 0. 0. 9.56E+07 1.06E+07 C0--60 0. 1.65E+07 CJ. 0. 0. 3.08E+08 3.62E+07 ZN--65 1.37E+09 4.~6E+09 0. 2.92E+09 0. 2. 75E+09 1.98E+09 RB--86 0. 2.60E+09 0. 0. 0. 5.12E+08 1.211;:+09 SR--89 1.46E+09 0. 0. 0. o. 2.33E+oa 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 2.31 E+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 4.59E+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 4.41 E+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 3.21 E+07 Based on 1 µCi/sec release rate of each isotope in and a value of 1. for X/Q, depleted X/Q and relative depoi;ition Note - the units for C---14 and H----3 are (mrem/yr per µCi/cu.

I meter) '

REVISION NO.: PROCEOURE lllTLE:

I I I PAGE::: ::::i::liI~i.

50 OFFSITE DOSE CALCULATION MANUAL (00(:M) of 2p111/j PROCEOURE NO.:

C-200 ST. LUCIE PLANT V.... ,.,,

I TAB LE G-19 \fi { );;1:i:jij!)ii[{i ENVIRONMENTAL PATt;IWAY-DOSE CONVERSION FACTORS R(l} FOR GASEOUS DISCHARGES f>AtHWAY- ~0WS MILK (CONTAMINATED FORAGE) AGE GROUP - ADULT ORGAN DOS~ FACTOR (SQ. METER-MfEMNR PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDI\JEY LUNG GI-LLI WHOLE BODY SN-123 0. 0. 0. 0. 0. 0. 9.

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 6.24~+04 0. I 2.dOE+07 7.31E+08 1.02E+07 SB-125 2.641=+07 6.06E+05 ?.99E+05 3.72E+06 2.66E+09 2.29E+08 5.23E+06 TE125M 1.63E+07 5.91E+06 4.91E+06 6.63E+07 0. 6.50E+07 2.18E+06 TE127M 4.63E+d7 1.6GE+07 1.21 E+07 1.BBE+08 0. 2.11 E+(:)8 5.:72E+06 TE129M 6.06E+07 2.27E+07 2.09E+07 2.53E+08 0. 3.04E+QB 9.61E+06 1--130 4.27E+Q5 1.26E+06 1.61E+OB 1.96E+06 0. 1.0BE+06 4.97E+05 1--131 2.96E+08 4.25E+OB 1.39E+11 7.27E+08 0. 1.12E+08 2.43E+OB 1--132 1.67E-01 4.47E-01 q.138E+01 7.12E-01 0. 8.39E-02 1.59E-01 1--133 4.00E+06 6.94E+06 1.33E+09 1.21 E+07 0. 6.10!=+06 2.12E+06 1--134 0. 0. ~.98E-10 0. 0. 0. 0.

1--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+1 b 0. 4.36E+09 1.45E+09 2.36E+OB 1.10E+10 CS-136 2.61 E+OB 1.0~E+09 0. 5.74E+OB 7.87E+Q7 1.17E+OB 7.43E+OB 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.Q3E+04 5.70E+07 1.7BE+06 CE-141 2.91E+04 1.97E+04 0. 9.13E+03 0. 7.52E+07 2.23E+03 CE-144 2.15E+06 8.97E+05 0: 5.32E+05 0. 7.26E+OB 1.15E+05 Based on 1 µCi/sec release rate of each isotope in and a value of 1. for ),C/Q, depl~ted X/Q and r~lative deposition Note - the units for C---14 and H----3 are (mr~m/yr per µGi/cu. meter)

I

REVISION NO.: PROCEDURE TITLE: ' ' ' I PA~§:,'* i&f \;,

50 OFFSITE DOSE CALCULATION MANµAL (ODCM)

PROCEDURE NO.:

/'/2~3 of 231

,*:;:. ::*:*l ' ..

'J o~*

C-200 I ST. LUCIE PLANT I I

TABLE G-20 ,*':_

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEO!JS1DISCHARGES PATHWAY i~ GOATS I MILK (CONTAMINATED FORAGE) ,

, A~E GROUP -ADULT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER µCl/SEC)

NUCLIDE BdNE LIVER THYROID KIDNE'.Y LUNG Gl-:LLI WHOLE BODY H----3 0. 1.99E+03 1.99E+03 1.9~E+03 1.99E+03 1.99E+03 1.99E+03 C-14 3.63E+05 7.28E+04 7.28E+04 7.28E+04 7.28E+04 7.28E+04 7.28E+04 P---32 2.05E+10 1.29E+09 0. 0. 0. 2.q1E+09 (94E+08 CR--51 0. 0. 2.0q,E+03 7.51~E+02 4.56E+03 8.64E+05 3.43E+03 MN--54 0. 1.01 E+06 Q. 3.oo:E+05 0. 3.09E+06 1.93E+05 FE--59 3.87E+05 9.18E+05 6. 0. 2.55E+05 3.03E+06 3.50E+05 C0--57 0. 1.54E+05 0. 0. 0. 3.90E+06 2.55E+05 CO--q8 0. 5.67E+05 0. 0. 0. 1.15E+Q7 1.47E+()6 C0--60 0. 1.98E+06 0. 0. 0. 3.7QE+07 4.34E+06 ZN--65 1.65E+D8 5.24E+08 b. 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. d. 0. 0. 4.89E+08 8.76E+07 SR--90 9.87E+10 0. 0. 0. 0. 1.32E+09 2.41E+10 Y---91 1.03E+03 0. 0. 0. 0. 5.68E+05 2.77Et01 ZR--95 3.82E+O~ 2.10E+03 0. 2.10E+Q3 0. 1.26E+07 8.34E+02 NB--95 9.92E+03 5.51E+03 0. 5.46E+03 0. 3.34E+07 2.17E+03 RU-103 1.23E+02 Q. 0. 4.69E+02 0. 1.43E+04 5.30E+01 RU-106 2.45E+03 0. 0. 4.73E+03 0. 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 µCi/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 µCi/cu. meter)

I I

' I I

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION MANUAL I (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE G-20 ENVIRONMENTAL PAtHWAY-DQSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY - GOATS MILK (CONTAMINATED FORAGE) I AGE GROUP - ADµL*r ORGAN DOSE FACTbR (SQ. METER-MREl\'1/YR PER µCl/SEC)

I NUCLIDE BOl~E LIVER THYROID KIDNEY LUNG ~1-LLI WHOLE BODY I '

SN-123 0. b. 0. 0. 0. 0. 0.

SN-126 1.97E+Q8 3.92E+06 1.15E+06 0. 5.q1E+05 1.31 E+08 5.92E+06 SB-124 3.10E+06 5.85E+04 7.4~E+03 0. 2.40E+06 s.77E+07 1.22!:;:+06 SB-125 3.16E+06 7.28E+04 3.58E+04 4.47E+05 3.1QE+08 2.74E+07 13.29E+05 TE 125M 1.96E+06 7.10E+05 5.89E+05 7.99E+06 0. 7.81 E+06 2.62E+05 TE 127M 5.57E+06 1.~4E+06 1.41t+06 2.26E+07 0. 2.q2E+67 6.86E+05 TE 129M 7.27E+06 2.72E+06 2.51E+06 3.04E+07 0. 3.65E+07 1.15E+06 1--130 5.12E+Q5 1.52E+06 1.93E+08 2.36E+06 0. 1.30E+06 5.~6E+05 1--131 3.56E+08 5.1bE+08 1;67E+11 8.72E+Q8 0. 1.34E+08 2.92E+08 1

1--132 2.00E-01 5.t36E-01 7.06E+01 8.55E-o'1 0. 1.01 E-01 1.9*1 E-01 1--133 4.80E+06 8.3~E+06 1.60E+09 1.45E+07 0. 7.32E+06 2.54E+06 1--134 0. 0. 1.;20E-09 0. 0. 0. 0.

1--135 1.68E+04 4.44E+04 5.B0E+06 7.0qE+04 2.28E-01 4.97E+04 1.63E+04 CS-134 1.70E+10 4.Q4E+10 b. 1.31E+10 4.34E+09 7.Q6E+08 3.30E+10 CS-136 7.84E+08 3.09E+09 0. 1.72E+09 2.36E+08 3.52E+08 2.231;:+09 CS-137 2.22E+10 3.03,E+10 0. 1.03E+1 O 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 0. 9.02E+06 2.68E+02 CE-144 2.58E+05 1.08E+05 0. 6.39E+04 0. 8.71E+07 1.38E+04 Based on 1 µCi/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 µCJ/cu. meter)

REVISION NO.: PROCEDURE TITLE: I ' ' ' '

50 PROCEDURE NO.:

OFFSITE DOSE CALCULATION MANUAL (ODCr~) ?{bs /f of~:3 C-200 ST. LUCIE PLAN~ F .

I

' I

' ' ,'\.*,.*;,"

I TABLE G-21 I E~VIRQNMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES I

PATHWAY - MEAT (CO~TAMINATED FORAGE). AGE: GROUP -'AD~JLT ORGAN DOSE FACTOR (SQ. METER-MREMtyR PER µCl/SEC)

NUCLIDE BONE LIVl=R THYROID KIDNEY LUNG GI-LU WHOLE BODY H----3 CO. I 4.13E+02 4.13E+02 4.13E+02 4.13E+02I 4.13E+02 4.13E+b2 C-14 3.3~E+05 6.p7E+04 6.67E+04 6.67E+04 6.67E+04 6.67q+04 6.67E+04 P---32 4.67E+09 2.93E+08 0. 0. 0. 5.25E+08 1.81 E+08 CR--51 0. 0. 4.23E+03 1.56.E+03 9.38E+03 1.78f-+06 7.07E+03 I

MN--54 0. 9.18E+06 0. 2.73E-¥06 0. 2.81 E+07 ~ .75E+06 FE--59 2.67E+08 (3.33E+08 0. 0. 1.76E+08 2.09E+09 4.41 E+08 C0--57 0. 5.64E;+0,6 0. 0. 0. 1.43E+Q8 9.38E+06 C0--58 0. 1.83E+07 0. 0. 0. 3.70E+08 4.09E+07 C0--60 0. 7.55E+07 d.' 0. 0. 1.416+09 1.66E+08 ZN--65 3.56E+Q8 1.13E+09 0. 7.57E+08 0. 7.13E+Q8 5.*.t2E+08 RB--86 Qt 4.89E+08 0. 0. 0. 9.64E+07 2.28E+08 SR--89 3.03E+08 0. 0. 0. 0. 4.84E+07 8.67E+06 SR--90 1.25E+10 0. b. 0. 0. 1.45E+09 3.05E+09 Y---91 1.14E+06 0. 0. 0. 0. 6.26E+08 3.05E+04 ZR--95 3.78E+06 1.67E+06 q. 2.01E+06 0. 8.30E+09 8.26E+05 NB--95 2.30Et06 1.28E+06 d. 1.27E+06 0. 7.75E+09 5.02E+05 RU-103 1.06E+08 0. d. 4.06E+08 0. 1.24E+10 4.59f;+07 RU-106 2.80E+09 0. 0. 5.41 E+09 0. 1.81E+11 3.54E+08 AG110 6.71E+06 6.21E+06 0. 1.22E-1;Q? 0. 2.53E+09 3.69E+06 Based on 1 µCi/sec relea?e i*ate of each isotop~ in and a value of 1. fbr X/Q, depleted X/Q and relative deposition Note - the units for Q---14 and H----3 are (mrem/yr per µCi/cu. meter)

-------~-~

REVISION NO.: PROCEDURE TITLE: PAGE:/'

._-~:*:' .. :\\:'

~,:\,{

50 OFFS!TE DQSE CALCULATION MAl\,UAL (ODCM)

, 206 of 231 PROCEDURE NO.:

i I i C-200 ST. LUCIE PLANT .

TABLE G-21 I '

ENVIRONMENTAL. PATHWAY-DOSE CONVERSION FACTORS R{I) FOR GASEOUS DISCHARGES PATHWAY - MEAT (CONTAMINATED FORAGE) , AGE GROUP -ADULT .

ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER µCl/$EC)

NUCLIDE BON!= LIVER THYROID KIDNEY LUl\)G Gl-,-LLI WHOL.. E BODY SN-123 0. 0. b. 0. 0. 0. 0.

SN-126 3.69E+08 1.08E+08 0. 6.46E+06 6.19E+09 5.B3E+b8 SB-124 1.99E+p7 3.75E+05 4.80E+04 0. 1.54E+07 5.62E+08 7.85E+06 SB-125 6.65E+Q7 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 1.4(qE+09 0. 1.43!=+09 4.81 E+07 TE 127M 1.13E+09 3.93E+08 2.96E+08 4.56E-1*09 0. 5.11 E+09 1.39E+08 TE129M 1.14E+09 4.29E+08 3.95E+08 4.79E+09 0. 5.76E+09 1--130 2.38E-06 7.05E-O~ 8.96)::-04 1.1QE,05 0. 6.04E-06 2.77E-06 1--131 1.08E+07 1.55E+07 2.65~+07 0. 4.07E+06 8.85E+06 I

1--132 0. 0. 6. 0. 0. 0. Q.

1--133 4.40E-b1 7.6~E-01 1.47E+02 1.33E+OO 0. 6.71E-0,1 2.l33E-01 1--134 0. 0. 0. 0. 0. 0. 0.

1--135 8.60E-02 7.94E-02 0. 3.01 E-02 9.04E-OB 1.86,E-03 3.53E-02 CS-134 6.58E+08 1.5'7E+09 b. 5.08E+08 1.68E+08 2.74E+07 1.28E+09 CS-136 1.18E+07 4.67E+07 0. 2.60E+07 3.56E+Q6 5.31 E+Op 3.36E+07 CS-137 8.73E+08 1.19E+09 CJ. 4.0qE+OB 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 1.41 E+04 9.52E+03 0. 4.41 E+03 0. 3.63E+07 1.08E-t03 CE-144 1.46E+09 6.10E+05 0. 3.62E+05 0. 4.93E+08 7.83E+04 Based on 1 µCi/sec release rate of each isotop'r in and a value of 1. f?r X/Q, depleted X/Q and relative deposition Not'e - the units f9r C---14 ~md H----3 are (mrem/yr per µCi/cu. meter)

REVISION NO.: PROCEDURE TITLE: PAGE:

,:0,:

50 pFFSITE DOSE CALCULATION MANUAL. (ODCM)

PROCEDURE NO.: ! 2()7 of 2~1 1

1 C-200 ST. LUCIE PLANT :

TABLE G-22 }~!!ii !1!i1;;[;

ENVIRONME~TALPATHWAY-DOSE CONVERSION FACTORS J~{I} FOR GASEOUS DISCHARGES PATHWAY i FRESH FRUITS AND VEGETABLES . . 1 AGE GROUP -AOU.LT ORGAN DOSE FACTOR (SQ. METER-MREM/YR PER µCl/SEC)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H----3 0. 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 C-14 1.25E+05 2.50E+04 2.50E+04 2.50E+04 2.50E+04 2.50E+04 2.50E+04 P---32 ~-01E+09 6.51E+07 0. 0. 0. 1.17E+08 4.P2E+07 CR--51 b. 0. 1.15E+04 4.25E+03 2.56E+04 4,85E+06 1.!~3!=+04 MN--54 0. 4.87E+07 0. 1.45E+07 0. 1.4~E+os 9.31 E+06 FE--59 3.64E+p7 8.64E+07 0. 0. 2.40E+07 2.85E+08 3.29E+07 C0--57 0. 1.85E+06 0. 0. 0. 4.70E+07 3.08E+06 C0--58 0. 6.89E+06 0. 0. 0. 1.40E+08 1.54E+07 C0--60 0. 2.38E+07 0. 0. 0. 4.46E+08 5.23E+07 ZN--65 5.11 E+07 1.62E+oa 0. 1.09;E+08 0. 1.Q2E+08 7.34E+07 RB--86 0. 1.30E+08 0. 0. 0. 2.56E+07 6.06E+07 SR--89 2.67E+Q9 0. 0. 0. 0. 4.26E+Q8 7.(34E+07 SR--90 8.49E+10 b. 0: 0. 0. 2.14E+Q9 2.07E+10 Y---91 1.26E+06 0. 0. 0. 0. 6.92E+d8 3.3"1E+04 ZR--95 2.93E+05 9.8~E+04 b. 1.49E+Oq 0. 3.34E+08 6.38E+04 NB--95 4.87E+04 2.71E+04 0. 2.68E+04 0. 1,64E+08 1.06E+04 RU-103 1.50E+06 0. q. 5.7qE+06 0. 1.76E+08 6.49E+05 RU-106 2.95E+07 0. 6. 571E+07 0. 1.81 E+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 µCi/sec release rate of each isotope ih and a value of *1. for X/Q, depleted X/Q and relative deposition I I

REVISION NO.: PROCEDURE TITLE: I I PAGE/ ' ..... ***

,j~'.i:)/t"'.* ,'

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) *:,:

PROCEDURE NO.: ' :;gqa of 2~1 f_:{/= *.,.,...*' ;

C-200 I ST. LUCIE PLANT I

}:.:

\

TABLE G-22

\:jrJ::** ..*

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R{I} FOR GASEOUS DISCHARGES PATHWAY- FRESH FRUITS AND VEGETABLES I

AGE GROUP - ADULT ORGAN GOSE FACTOR I (SQ. METER-MREM/YR PE~ µCl/SEC)

NUCLIDE BC>NE LIVE.R THYROID KIDNEY LUNG Ql-~LI WHOLE BODY SN-123 1.00E-05 1.66E-07 1.41 E-07 0. 0. 2.04E-05 2.45E-07 SN-126 9.52E+08 1.89E+07 5.54E+06 0. 4.31 E+06 8.46E+Q~ 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 2.561+/-+09 2.22E+08 5.10E+06 TE 125M 2.38E-1'.07 8.65E+06 7.17E+06 9.69E+07 0. 9.51 E+07 3.19E+06 TE 127M 6.79E+b7 2.36E+07 1.77E+07 2.73E+08 0. 3.066:+08 8.32E+06 TE 129M 8.93E+d7 3.34E+07 3.08E+07 3.73E+08 0. 4.49E+08 1.42E+07 1--130 3.93E+b5 1.16E+06 1.48E+08 1.81 E+06 0. 9.98E+05 4.58E+05 1--131 7.78E+07 1.12E+08 3.65E+10 1.91 E+08 0. 2.94E+07 ~.38E+07 1--132 5.57E+01 ~ .49E+02 1.96E+04 2.3~E+02 0. 2.80E+01 5.29E+01 1--133 2.13E+06 3.69E+06 7.1d~+08 6.4l+l=+06 0. 3.24E+06 1.136+06 1--134 1.03E-04 2.79E-04 ~r63E-02 4.45E-04 0. 2.43E-07 9.99E-05 1--135 4.04E+Q4 1.07E+05 1.40E+07 1.70E+05 8.65E-p3 1.19E+05 3.91E+04 CS-134 6.82E+d8 1.6QE+09 0, 5.26E+08 1.74E+08 2.84E+07 1.33E+09 CS-136 3.32E+07 1.p1 E+08 o: 7.29E+07 9.99E+06 1.49E+d7 9.4~E+07 CS-137 8.90E+Q8 1.2.2E+09 p. 4.14E+08 1.37E+08 2.34E+07 7.98E+08 BA-140 1.03E+08 1.35E+os 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 0. 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 µCi/sec release rate of each isotope in and a value df 1. for X/Q, depleted X/Q and relative deposition

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1----------1 PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABi:E M-1 Selecting the Appropriate Long Jerm (X/Q) for Dose Calculations Involving Noble Gases -

-for:

(1) Tota!-Bodydose from-instantaneous releases (2) SkiP.- dose from instantaneous releases (3r Gamma air dose (cumulative)-

(4) l3eta air dose (cumulativ~

TYPE OF DOSE LIMITING RANGE LIMITING (X/Q~ VALUE CALCtJLATION (miles) Sector sec/m 3 Instantaneous 0.97 NW 1.6 X 10*5 1/31 days 0:97

1. Normally (X/Q) = 1.6 X 10*5 sec/m 3 Quarterly 0.97 Yearly 2. May use option of actual meteorological 12 Consecutive 0.97 data for time of concern.

months Annual Report 0.97 N/A Note-1 NOTE 1 The (X/Q) nas to be calct1lated based-on actual meteorological data--that-occurred during the period of interest. The-sector of interest is- N/A because

_the limiting (X/Q) wiU-be determined-from the actual meteorological data and ma occur in an sector.

- 0.97 miles Corresponds to-the minimum site boundary distance inlhe north direction and 0.97 miles was chosen for all other sectors for ease of calculations when-the averaging is done for quarterly reports.

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _- t OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

-C-200 ST, LUCIE F'LANT TABLE fv1-2 Selecting the Appropriate Long Term (X/Q~D or (D/Q) for Dose

Ca~culations Involving Radioiodines & 8 D Particulates for:

(1) Inhalation (21 Tritiam (All gas. pathways)

(3) Ground Plane TYPE OF DOSE LIMITING LIMITING SECTOR (X/O)o sec/m 3 (D/Q) 1/m2 CALCULATION RANGE (miles) (OL)

NW Instantaneous 0.97 WNW 0.97 Annual Report 0.97 A 1/31 days, Qtr. yearly, 0.97 NW Annual Total Dose 0.97 WNW 8.2 X 10-9 (OL) Over land areas only (A) To be determined by reduction of actua1 met data occurring during each E1,Uarter (B) For Tritium in the Milk Animal Pathway, the (X7Q)D value should be that of the respective controlling sectm 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)D for 4.25 miles NW.

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

c_-200 ST. LUGIE PLANT TABLE M-3 Selecting the Appropriate Long Term (D/Q) for Dose Calculations Involving Radioiodines and 8Q Particulates for Grass-Cow-Milk or Grass-Goat-Milk:

TYPE OF DOSE LIMiTING LIMITING (D/Q) Value-CALCULATION -RANGE SECTOR 1/m2 Release Rate A A.. A 1/31* Days B B B Quarterly - Yearly B B 8-Anr:1ual (Calendar Year} - B B B Annual Report c_ C C A. Th-e war-St cow..ur goat as f')er locatfons from land-census. If no milk animal in any sector, assume a cow at 4.25 miles in the highest (D/Q) sector ewer land.

B. The historical (D/Q) of all land sectors with the.werst caw or goat from eacl:i-sectof 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 th-e worst case milk animaJ and for the dose calculations. If both goat and milk animals are reported inside--5 miles, dose calculations should be performed on each animal-cand the higher dose animal..

_contribution should be used.

The historical wind frequency fractions for each sector are listed in Table M-8.

REVISION NO.: PROCEDURE TITLE: I PAG.E:

\Jii1.-<;; /.\::::.:,~;:*,

50 OFFSITE DOSH CALULATION MANUAL (ODCM)

<212 of PROCEDURE NO.:

j i C-200 ST. LUCIE PLANT I J I

' ' I I

.\ ;'}

TABLE M-4 TERRAIN CORRECTION FACTORS Florida Power & Light Company St. Lucie Unit 1 Terrain Corre~tion 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 DESIClN AFFECTED DISTANCE I

.25 .75 I

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 0. 1.906 1.576 1.465 1.404 1.338 1.318 1'.334 1.386 1.346 1.338 NE 0. 1.887 1.581 1.461 1.391 1.310 1.259 1.164 1.148 1.101 1.116 ENE 0. 1.452 1.230 1.122 1.081 1.047 1.033 .941 .941 .906 .902 E o. 1.662 1.425 1.277 1.193 1.151 1.1?3 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 !). 1.818 1.691 1.470 1.427 1.435 1.361 1.~66 1.331 1.279 1.239

$SE 0. 1.812 1.586 1.370 1.302 1.270 1.~63 1.229 1.193 1.171 1.151 s 0. 1.398 1.321 1.125 1.083 1.108 1.127 1.073 1.063 1.047 1.024 SSW 0. 1.534 1.411 1.296 1.192 1.205 1.132 1.135 1.116 1.077 1.060 SW 0. 1.685 1.492 1.294 1.233 1.400 1.222 1.160 1.160 1.198 1.196 WSW 0. 1.620 1.333 1.210 1.173 1.082 1.091 1.099 1.056 1.034 1.004 w 0. 1.651 1.415 1.~90 1.218 1.154 1.099 1.081 1.067 1.093 1.083 WNW 0. 1.720 1.430 1.2,67 1.185 1.150 1.133 1.125 1.085 1.033 1.045 NW 0. 1.p81 1.407 1.257 1.173 1.119 1.078 1.063 .995 .9~~ .978 NNW q. 1.739 1.488 1.316 1.212 1.172 1.122 1.13~ 1.080 1.099 1.091 N 0. 1.816 1.524 1.389 1.285 1.257 1.263 1.285 1.267 1.231 1.213 Note 1: Any interpolatjons between stated niileqges will be done by log-log I

nJ\r.,i:;., .. ,

REVISION NO.: PROCEDUREITITLE:

s; ....,.

50 OFF!plTE DOSE CALULATION MANUAL (ODOM)

PROCEDURE NO.: I ~~01 C-200 ST. LUCIE PLANT (., :/, J ...

TABLE M-5 ,, :J.Jli?t~: r*:1~L *.*.

,,, '/

HISTORICAL LONG TERM - {X/Q} {Freguenc¥ correct~a}

Terrain / Recirculation Adjusted Program ANNXOQ9 Version - 11/18/76 Florida Power & Light Company St. Lucie Unit 1 Average An~ual R1~lative Concer1tration (sec/cubic meter)

Hutchinson Island, Florida Period of Hec0rd: 9/1/76 to 8/q1/78 Dames and Moore Job No: 1.4598 - 112 Base Distance in Miles/Kil:Ometers I

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.q2 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.1E-05 1.7E-06 7.8E-07 4.5E-07 3.1E-07 2.2E-07 1.7E-07 1.5E~p7 1.2E-07 1.0E-07 NE o. 1.3E~05 2.1E~06 8.9E-07 5.1E-07 3.4E-07 2.4E-07 1:7E-07 1.~E-07 1.1E-07 9.8E-08 ENE 0. 9.3E-06 1.4E-06 6.2E-07 3.7E-07 2.5E-07 1.9E-07 1.3E-07 1.1 E-07 8.8E-08 7.5E-08 E 0. 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-08 8.4E-08 ESE 0. 1.2E-05 1.9E-06 8.1 E-07 4.8E-07 3.2E-07 2.4E-07 1.8E-07 1.4E-07 1.1E-07 9.0E-08 SE 0. 1!4E-05 2.4E-06 9.7~-07 5.7E-07 4.0E-07 ~.9E-07 2.3E-07 1.9E-0'7 1.4E-07 1.2E-07 SSE 0. 1.1E-Q5 1.7E-06 7.3E-07 4.3E-07 2.9E-07 2.1E-07 1.9E-07 1.3E-07 1.1 E-07 9.1E-08 s 0. 6.2E-06 1.0E-06 4.2E-07 2.5E-07 1.8E-07 1.4\;:-07 1.0E-07 8.0E-08 6.6E-08 5.5E-08 SSW 0. 9.7E-06 9.0E-d7 4.0E-07 2.3E-07 1.6E-07 1.1 E-07 8.9E-08 7.0E-08 5.7E-08 4.8E-08 SW 0. E}.1E-06 9.4E-07 3.9E-07 2.2E-07 1.6E-07 1.1 E-07 8.6E-08 ~.OE-q8 6.0E-08 5.1E-08 WSW 0. 7.3E-06 1.1 E-06 4.GE-~)7 2.7E-07 1.7E~07 1.3E-07 1.0E-07 8.0E-08 6.5E-08 5.4E-08 w 0. 7.6E-06 1.2E-P6 5.2E-07 2.9E-07 2.pE-07 1.3E-07 1.0E-07 8.4E-08 7.2E-08 6.1E-08 WNW 0. 1.4E-05 2.1 E-06 9.1 E-07 5.2E-07 3.4E-07 2.6E-07 2.0E-07 1.5E-07 1.2E-07 1.0E-07 NW 0. 1.6E-05 2.4E-06 1.0E-0$ 5.9E-07 3.QE-07 2.8E-07 2.1E-07 1.7E-07 1.4E-p7 1.2E-07 NNW 0. 1.5E-05 2.2E-06 9.8,E-07 5.5E-07 3.6E-07 2.6E-07 2.0E-07 1.6E-07 1.3E-07 1.2E-07 N 0. 9.1E-06 1.4E-06 6.3E-07 3.6E-07 2.4E-07 *1.8E-07 1.4Er07 1.2E-b7 9.4E-08 7.9E-08 Number of Valid Observations = 17135 Number of Calms Lower Level I

=95 Number of Invalid Obs~rvations 385 = Number of Calms Upper Level =0 Note 1 - Any interpQlations between stated mil~ages will be done by log-ldg I

I

R-Ev-,s-,o-N_N_O......:_ _ _ _

PR_O_C_ED_U_R_E-TI-TL_E_:- - - - - - -...........- - - - - - - - , * . , -_ _ _ _ _ _ _ ,_ _ _,,-,.-----';:-.-.,--.-P-AG-.E-:,;-:,-\\'t-/.-:aa:"-*.".*- - - ,

PROCEDURE NO.:

50 C-200 I

OFFSITE DOSE CALULATION MANUAL (ODCM) pT. LUCIE PLANT i .21~ of ~r1 TABLE M-6 HISTORICAL. LONG TERM DEPLETED * (X/Q}Q_(Freguenc~ corrected}

I ' I Terrain I Recirculation Adjusted Program ANNX0~9 Version - 11 /18/76 Florida Power & hight Company St. Lucie Unit 1 Average Annual Rel~tive Concentration Deplete9 (sec/cubic meter)

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

DESIGN AFFECTED DIStANCE .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.~5 4.75 SECTOR MILES .40 1.21 2.01 2.82 3.62 4.'fl,2 5.23 6.03 6.84 7.64 NNE 0. 1.1 E-05 1.6E-06 6.6E-07 3.8E-07 2.4E-07 1.7E-07 1.3E-07 1.1 E-07 9.2E-08 7.6E-08 NE 0. 1.~E-05 1.7E-06 7.6E-07 4.3E-07 2.8E-07 1.~E-07 1.4E-07 1.1 E-Q7 8.6E-08 7.4E-08 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-D8 6.6E-08 5.6E-08 E 0. 9.1E-06 1.3E-06 5.6E-07 3.1E-07 2.16-07 1.5E-07 1.1E-07 9.1 E-08 7.5E-08 6.3E-08 ESE 0. 1.2E-05 1.6E-06 6,9E-07 3.9E-07 2.6E-07 1.9E-07 1.4E-07 1.1 E-07 8.5E-08 6.7E-08 SE 0. 1.3E-05 2.0E-06 8.2E-07 4.7E-07 3.3E-07 2.3E-07 1.8E-07 1.3f--Q7 1.1 E-07 9.0E-08 SSE p. 1, 1E-05 1.6E-06 6.36-07 3.5E-07 2.4E-07 1.8E-07 1.4E-07 1.0E-07 8.2E-08 6.8E-08 s 0. 5:9E-06 9.1 E-07 3.6E-07 2.1E-07 1.4E-07 1.1E-07 7.7E-08 6.2E-08 5.0E-08 4.1E-08 SSW 0. 5.4E-09 8.0E-07 3.4E-07 1.9E-07 1.3E-07 8.9fa08 6.9E-08 5,5E-08 4.3E-08 3.6E-08 SW 0. 5.7E-06 8.4E-Q7 3.4E-07 1.8E-07 1.2E--07 9.2i=-08 6.7E-08 5'.3E-08 4.6E-O~ 3.8E-08 WSW 0. 7.QE-06 9.6E-07 4.0E-07 2.2E-07 1.4E-07 1.0E-07 8.0~-08 6.1E-08 5.0E-08 4.0E-08 w 0. 7.3E-06 1.1 E-06 4.4E-Q7 2.4E-07 1.6E-07 1.1E-07 8.2E-08 6.4E~d8 5.pE-08 4.4E-08 WNW 0. 1.3E-05 1.9E-06 7.9E-07 4.4E-07 2.~E-07 2.0~-07 1.6E-07 1.2E-07 9.3E~O~ 7.8E-08 NW 0. 1.5E-05 2.1E-06 8.9E-07 4.9E-07 3. ~ E-07 2.3E-07 1.7E-07 1.3E-07 1.0E-07 8.5E-08 NNW 0. 1.4E-05 2.1 g-06 8.3E-O{' 4.5E-07 2.~6-07 ~.OE-07 1.6E-07 1.2E-07 1.0E-07 8.6E-08 N 0. 8.7E-06 1.3E-06 5.4E-07 3.0E-07 iiJE-07 1.4E-07 1.1E-07 8.9E-08 7.0E-'08 5.8E-08 Number of Valid ObseNations = 171 ;35 Number of Calms Lower Level = $5 Number of Invalid Observations= 385 Number of Calms ypper Level= 0 Note 1 - Any interpolations between stated mileages will be done by log-log

REVISION NO.: PROCEDURE TITLE: ' I I I PAG,f\\tif:f ,

50 OFFSITE DOSE CALULATION Mf.t~UAL (ODCM)

PROCEDURE NO.: t1i/1s 01 ,,,

C-200 I ST. LUCIE PLANT ':';

t(, ;,'},,,,,,x:,f ' .

I TABLE M-7 HISTORICAL LONG TERM - {D/Q} {Freguenc~ corrected}

TERRAIN/ RECIRGULATION ADJUSTED PROGRAM ANNXOQ9 VERSION - 11/18/76 I '

Florida Power & Light Company St. Lucie Unit 1 Average Annual Reilative Deposition Rate (squi;lre meter - 1)

Hutchinson Island, Florida I Period of Record: 9/1/76 to a/31/78 Dames and Moore Job No: 4598 - 112 Base Distpnce 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 M'LES .40 1.21 2.01 2.82 3.62 4.42 5.23 (;,.03 6.84 7.64 NNE 0. 6.5E-08 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 0. 6.0E-08 8.9E-09 3.5E-09 1.9E-09 1.2E-Q9 s.1E-10 5.6E-10 4.BE-10 3.~E-10 2.BE-10 ENE 0. 3.2E'-Q8 4.BE-09 1.912-09 1.0E-09 6.61:;-10 4.pE-10 3.2E-10 ~.41:;-10 1.9E-10 1.5E-10 E 0. 3.dE-08 4.6E-09 1.BE-09 9.5E-10 6.0E-10 4.2E-10 3.1E-1Q 2.5E-:IO 2.0E-10 1.6E-10 ESE 0. 3.7E-08 5.8Et09 2.3E-09 1.2E-09 8.0E-10 5.4E-10 3.9E-10 3.0E~10 2..2E-10 1.7E-10 SE 0. 6.4E-08 1.0E-08 4.0E-09 2.1E-09 1.4E-09 9.7E-10 7.2E-10 q.6E-10 4.3E-10 3.5E-10 SSE 0. 6.2E-08 9.5E-09 3.6E-09 2.0E-09 1.2E-09 ~.?E-10 6.4E-10 4.9E-10 3.9E-10 3.1E-10 s 0. 4.2E-08 7.0E-09 2.~E-09 1.4E-09 9.5E-10 6.9E-10 4.9E-10 B.BE-10 3.0E-10 2.5E-10 SSW b. 3.4E-08 5.4E-09 2.21:;-09 1.1 E-09 7.5E-10 5.0E-10 3.7E-10 2.9E-10 2.3E-10 1.BE-10 SW 0. 4.5(;:-08 7.0E-09 2.6E-09 1.5E-09 9.0E-10 6.6E-10 4.f?E-10 3.6E-10 3.0E-10 2.5E-10 WS\fl/ 0. 5.3E-oi3 7.7E-09 3.0E-09 1.6E-09 1.0E--09 7.3f-~10 5.9E-10 4.1 E-10 B.3E-10 2.6E-10 w 0. 9.0E-08 7.5E-09 3.0E-09 1.6E-09 9.BE-10 6.7E-10 5.0E-1. 0 3.BE-10 3.2E-10 2.6E-10 WNW 0. 8.8E-08 1.3E-08 4.9E-09 2.6E-09 1.?E-09 1.1E-09 8.7E-10 q.6E-10 5.1f--10 4.2E-10 NW 0. 8.2E-08 1.2E-08 4.7E-09 2.5E-09 1.6E~09 1.1 E-09 7.9E-10 5.BE-10 4.7E~10 3.BE-10 NNW 0. 8.2E-08 1.2E-08 4.6E-09 2.4E-09 1.6E-09 1.1 E-09 8.1E-10 5.~E-10 4.8E-1 CJ 4.0E-10 N 0. 5.1E-Q8 7.3E-09 2.9E-O~ 1.5E-09 9.8~-10 7.1E-10 5.4E-10 4.2E-10 3.2E-10 2.?E-10 I

Number of Valid Observations = 17135 Number of Calms Lower Level= 95 Numb~r of Invalid Observat1onr = 385 Number of Calms Upper ~evel = 0 Note 1 - Any interpolations betweerl stated mileagTs will be done by log-lqg

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1---------1 PROCEDURE NO.:

C-200 ST. LUCIE PLANT

=J"ABLE M-8 Joint Wind Frequency Distribution Data Period: September 1, 1976 - August 31, 1978 All \,'\finds St. Lucie Unit 2 Data- Source: On--Site Hutchinson -Island, Florida Wind Sensor Height 10.00 l111eters Florida Power & Light Co.

Tal:51e Generated: t2/05/78. 07.42.18. Dames and Moore Job No: 4598 - 112 - 27 V\11nd Speed Categories {Meters per Second)

WIND 0.0- 1 :5- 3.0- 5.0- 7.5- 1 MEAN

>10.0 TOTAt SECTOR 1.5 3.0 5.0- 7.5 10.0 SPEED 71 206 31:S 71 3 8 669 *-

NNE- 3.32..

.43 1.25 1.9-2 .43 .02 0.00 4.05 62 292 385 1 . - 0 0 867 NE 3.43-

.38 1.77 2.33 .77 0.00 0.00 5.25 60 334 505 - 158 0 0- ~057 ENE 3.5-1

~35- 2.02 3.0"6 .96 0.00 0.00 6.40 69 355 10 76 0 0 1010 E -

I- 3.25

.42 2.15 3.09 .46 0.00 0.00 6.11 ESE 115 684 744 72 1 0- 1616 3.04

.70 4.14 4.50 .44 .01 0.00 .9..78 183 660 749 28 0 0 1620 SE 2.88 1.11 3.99 4.53 .17 0.00 0.00 9.81 129 579 656 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 s .44 1.88 2.46 .60 .05 .01 5.43 3.36 84 372 446 105 33 4 1044 -

SSW 3.48

.51 2.25 2.70 .64 .20 .02 6.32 129 440 336 106 14 0 1025 SW 3.10

.78_ 2.66 2.03 .64 .08 0.00 6.20 155 320 186 29 5 0 695 WSW 2.59

.94 1:94 1.13 .18 .03 0.00 4.21 174 267 119 37 2 0 599 w 1.05 1.62 .72 .22 - .01 0.00 3.63 2.43

. a 203 304 172 17 0 . 0 696 WNW -

- 2.34 123 1.84 1.04 .10 o:oo 0.00 4.21 143 518 -424 50 0 0 1135 NW 2.85"

.87 - "3-:-t4 2.57 .3Q- 0.00 0.00 6.87 85 379 535 70 1 0 1070 NNW 3..22

.51 2.29 - . 3.2..4 .42 .01 0.00 6.46 91 194 531 148 5 0 969 N - .

3.69

.55 -- 1.17 3.21 .90 .03 -o.oo 5.86 95 95 CALM CALM

.57 .57 1920 6214 7023 1287 73 5 16522 - ..

TOTAL 3.10 11.62 37.61 42.51 7.79 .44 .03 100.00 NUMBER OF VALID OBSERVATIONS 16522 94.30 PCT. Key XXX Number of Occurrences NUMBER OF INVALID OBSERVATIONS 988 5.70 PCT. XXX Percent Occurrences TOTAL NUMBER OF OBSERVATIONS 17520 100.00 PCT.

1

- Totals below are given in hours & percent for wind frequency by sectors END OF APPENDIX A

PROCEDURE NO.:

C-200 ST. LUCIE PLANT I

APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE 1

(Page 1 of 4)'

ST. LUCIE PLANT Key to Sample Locations SAMPL!= APPROXIMATE SAMPLES DIRECTION PATHWAY LOCATION DESCRIPTIQN COL~ECTION DISTANCE COLLECTED SECTOR I F~.EQUENCY (mile~)

Direct Radiation N-1 North, qf Blind Creek TLD Q\jarterly 1 N Direct Radiation NNVV-5 Frederic~ Douglas Beac~ Entrance TL~ Quart~rly 4.8 NNW Direct Radiation NNW-10 Coast Guard Station TLD Qufirterly 8.7 NNW I I Direct Radiation NW-5 lndian,River Drive at Rio Vista Drive TLD Quarterly 5.4 NW I

Direct Radiation NW-10 Intersection of SR 68 and 33rd St TLD. ' Quarterly 9.6 NV\(

I Direct Radiation WNW-2 Cerpetery South of 7107 lndi~n River Drive TLQ Quarterly 2.3 WNW Direct Radiation WNW-5 Up~1 at SR 712 TLP 'quarterly 9.1 WNW I

Direct Radiation WNW-10 SR 70, J1,Jst W~st of 1-95 TLD Quarterly '10 WNW Direct Radiation W-2 Power Line' - 7760Q Indian River Drive TLD, (Quarterly I

2 w Direct Radiation W-5 Oleander and Sager Streets TLD Quarterly 5.4 w Direct Radiation W-10 1,-95 and SR 709 ' TLD Quarterly 1Q.3 ' w Direct Radiati9n WfJW,-2 8503 lnqian River Drive TU) Quarterly 1.8 WSW Direct Radiation WSW-5 Prima Vista Blvd. at Yc;icht Club TLD Quart(erly 5.6 'f'I_.SW Direct Radiation WSW-10 I I Del Rio and Da~is ~treets TLD Quarterly 1p wsw Direct Radiation SW-4 9205 Indian River !Drive TLD Quc,irterly 2 SW Direct Radiation SW-5 'FPL Walton Svc Ctr I TLD Quarte,rly 4.5 I

sw Direct Radiation SW-10 Port St. Lucie Blvd. ~md Cairo Road TLD Q,llarterly 10.2 SW Direct Radiation TLD '

SSW-2 103Q7 Indian River Drive ,. '

Quarterly 2.6 SSW I I I.

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- J 50 OFFSffE DOSE CALCULATION MANUAL (ODCM) . */ '.,= .. }*\,

. 218 .:

of 231\,

PROCEDURE NO.: :

i. \

C-200 ,,.-

ST. LUCIE PLANT I : .

' I :*:.,:

APPENDIX B RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (Page 2 of 4)

I SJ. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMATEI SAMPLESI DIRECTION PATHWAY LOCATION DESCRIPTION COLLECTION DISTANCE COLLECTE£D SECTOR FREQUENCY (mi,les)

Direct Radiation SSW-5 Port St. Lucie Blvd. and US 1 TLD Quarterly 6 SSW Direct Radiation SSW-10 Pine Yplley and Westmoreland Roads TLD Quarterly 8 SSW Direct Radiation S-5 13189 Indian River Dr)ve TLp Quarterly 5.2 s Direct Radiation S-10 US 1 pnd Palm City Ave TLb Quarterly 10.8 s Direct Radiation S/SSE-10 Indian River Drive and Quail Run Lane TLD Quartwly 9.9 SSE Direct Radiation SSE-5 North of Entrance to Miramar TLD Quarterly 5.1 SSE Direct Radiation SSE-10 Elliot Museum TLD Quarterly 10.2 SSE Direct Radiation SE-1 Smith of Cooling Canal TLD Quarterly 1 SE U( of Florida - 1FAS Entomqlogy Lab Vero Direct Radiation *H-32 TLD Quarterly 18.1 NNW Beach I Radioiodir,e &

I '

Airborne HOB FPL Substation - VVeatt,erbee Road Weekly Q WNW Particulat~s Radioiodine &

Airborne *H12 FPL Substation - SR 76, Stuart Particula~es Weekly 12 s Radioiodine &

Airborne H14 Orisite - near south property line Weekly 1 SE Particulates I Radioiodine &

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

2 w

Denotes Control Sample I

REVISION NO.: PROCEDURE TITLE: I 50 OFFSITE bOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 $T. LUCIE PLANT APPENDIX 8 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (Page 3 of 4) 1 1

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

Radioior:Jirle &

Airborne H34 Onsite -At Meteorological Tower We;ekly 0.5 N Particulates I

Surfac~ '{\later Weekly Atlantic Ocea11 vicinity of public beaches east (qcean)

Waterborne H15 I I < 1 ENE/E/ESE side of Route A 1A

Sedir'nent from Semi-Annually sho~eline Surface Water Monthly (ocean)

Waterborne *H59 Near south end of Hutchinson Island 10..20 S/SSE Sediment from Semi-Annually

,shore~line I, I

I Crustacea $emi-Ann~ally Food Products H15 Ocean side vicinity of St Lucie Plant (NOTE 1) <1 ENE/E/ESE Fish Semi-Annually Broad Leaf Mohthly Food Products H51 Offsite near north prop~rty line 1 N/NNW vegetatjon (when available)

Denotes Control Sample

,__------------------------------------,-,.------------...1

REVISION NO.: PROCEDURE TITLE:

50 OFFSITE DO.SE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT I I APPENDIX 8 t RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (Page 4 of 4)

I ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMATE SAMPLES DIRECTION PATHWAY LOCATION DES8RIPTION COLLECTION DIStANCE COLLECTED SECTOR FREQUENCY (miles)

Broad leM Monthly Food Products H52 Offsite near sou~h property line I I 1 S/SSE vegetatiqn (wher availal:lle)

Crustace~

SE;!mi-Annually Fish Food Products *H59 Near sbuth enq of Hutchinson Island Semi-Annually 10-20 S/SSE Broad teaf Monthly vegeta ior, I

Denotes control sample It is the policy of Florida Power & Light Company (FPL) that the St. Lucie 1 & 2 Ratjiological EnvironmJntal Monitoring Programs are 1

conducted by the State of Flori9~ Department of Health (DOH) and Bureau of ~adiation Control (BRC), p4rsuant to ar, Agree:ment between FPL and DOH and; that coor~ination of the Radiological Environmental Monitoring Programs with QOH and compliance with the Radiological Environmental Monitoring Program Controls I are the responsibility of the Nuclear Plant Suppqrt Services Department.

NOTE 1 These samples may be collected from or supplemented by samples collected from the plant intake canal if the required anal ses r;1re unable to be , erform~d due to Lina ailabilit or inade uate quantit of sal!) le from the oc.ean i;ide location.

END OF APPENDIX J3

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT APPEND1X B-1 ST. LUCIE SUPPLEMENTAL REMP S..~MPLING (Page 1 of 3)

The sam13ling and analysis progr-am=outlined in this appendix is performed- in addition to the St. Lucie REMP sample and analysis program required by Contrcl 3.. 12.1. These samples

are not required_to satisfy the REMP-Program nor required-to be reported in the Annual Radiological Environmental-Operating Report. Su;pplemeRtal samples are performed to provide a-broader _data base for -the Radiological Environmental Monitoring Program.

NOTE

_* Approximate Distance from plant in miles Pathway: Direct Exposure via TLD Sampling and Collection Frequency: Quarterly Collection-Name -Sector Distance* Desc.ciption -

H-08 WNW 6 FPL Substation (White City Sub), Weatherbee Rd H-09 SSW 7 FPL Substation (Jensen Sub), US-1 South of St.

Lucie County Line H-12 s 12 FPL Substation (Stuart Sub), SR-76, West of Stuart by High School H-14 SE 1 South Site Property Line H-33 ESE- <1 On-site, North of Intake Canal, West-of Dunes H-34 N 0.5 On-site, Meteoroloav Tower H NE <1 Utility PoJe;-A 1A, East of TAB H~61 & SW <1 Canal Dredging Spoils fv1-ound H-62 Pathway: Airborne Radioiodines and Particulates Sampling and CollectionFrequency: Samples Collected Weekly;

1. Iodine - Gamma-Spec Analysis

2. Particulate - Gross-Beta and Composite Gamma-Spec Analysis Name Sector Distance* Description H-09 SSW 7 FPL Substation (Jensen Sub), US-1 South of St.

Lucie County Line H-32 NNW 19 HRS Entomoloav Lab., East of US-1, Vero Beach H-33 ESE <1 On-site, North of Intake Canal, West of Dunes

REVISION NO.: PROCEDURE TITLE:

i----5_0_ _..... OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE Pl:.ANT APPENDIX B-1 r ST. LUCIE SUPPL:.EMENTAl REMP SAM!?LING (Page 2 of 3)

NOTE

Approximate Distance from plant-in miles.

Pathway: Waterborne, Surface Water Sampling and Collection Frequency: Monthly Colle-ction~ Gamma-Spec and Tritium-Analysis Name Sector Distance* Descri tion H-13 N:NW/N <1 Gn~~te, North Bank of-Big Mud*Creek, Between

-Pum Station and Meteemlo- Tower H-36 NE/ENE <1 On-site, Discharge Canal, West Side A1A 5/6/96 On-site, Discl'large Canal, Near Bridge Pathway: Waterborne, Sediment Sampling and Collection Frequency: Semi-Annual Collection and Gamma-Spec Analysis Name Sector Distance* Descri tion H-13 N-MW/N <1 On-site, North Bank of Big Mud Creek, Between Pump Station and Meteorolo

Tower H-16=- N 1 Ocean Covered Sand, Beach Opposite Blind ']_

Creek, North of Dischar e Canal H-19 SE 1 Ocean Covered Sand, Beach South of Intake Canal H-36 NE/ENE <1 -On-site~ Discharg_e Canal, West Side A1 A Pathway:-vvaterborne, Beach Sand

_Sampling and Collection Frequency: Semi-Annual Collection and Gamma-Spec Anal¥5is Name Sector Distance* Description H-15 NE/ENE/E <1 On-site, Beach Near Discharqe Structure H-16 N 1 Ocean Covered Sand, Beach Opposite Blind Creek, North of Discharge Canal H-19 SE 1 Ocean Covered Sand, Beach South of Intake Canal

REVISION NO.: PROCEDURE TITLE:

PROCEDURE NO.:

C-200 ST. LUCIE PLANT APPENDIX B-1 S:f. LtJCIE SUPPLEMENTAL REMP SAMPLING (Page 3 ef 3)

-NOTE

Approximate Distanee from plant *in miles.

Although the -Name remains the same, the locatior:1s can vary with sample availability. l

-rathway: Ingestion, Garden Crop

-1~ampiing and Collection Frequency: Anm:ial-Collection and G-amma..:spec AnaJysis Name# Sector _Distance* Description H-41 w 2 Priva1e Residence, Indian River Dr.

Pathway: Ingestion, Citrus Sampling and Collection Frequency: Annual Collection and Gamma-Spec Analysis Name# Sector Distance* Description

-H-23 w 5 Vicinity of US-1 and Easy St.

END=OF APPENOIX B-1

REVISION NO.: PROCEDURE TITLE:

I 50 OFFSITE DOSE CALCULATION MANUAL (ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT t----------'----:-------.-------------1:-,,.+:-----------,...---;....&.~~-

APPENDIX B-2 , .

RADIOLOGICAL ENVIRONMENTAL SAMPLING IN SUPPORT OF THE GROUNDWATER PROTECTION INITIATl\i 1

1 (Page 1 of 2) I * '

ST. LUCIE PLANT Key to Sample Locations L

STATE PSLID SAMPLES SAMPLE LOCATION DESCRIPTION ID COLLECTED FREQUENCY H70 GIS-MW-ES Tritium / Gamma Quart~rly West of A1A; between the dischprge canal and Gate "B" H71 GIS-MW-EI Tritium / Gamma duarterly West of A1A; between the discharge canal and G.ate "B" H72 GIS-MW:-SI Tritium / G'amma Quarterly South. of Intake canal ar,d tl:,e 'adjace'nt access road H73 GIS-MW-SWS Tritium / Gan,ma Quarterly S/W corner of Intake canal qnd the adjacent acce~s r9ad H74 GIS-MW1SWI Tritium / Gamma Quarterly S/W corner of Intake canal and the adjqcent access road H75 GIS-MW-VVI Tritium / Gamma Quarterly West of plant site and intake canal; South of switchyard H76 H76 Tritium I Oamrna Quarterly North of $irnulatqr; South of Big Mud Cr~ek H77 H77 Tritiurn / Gamma Quarterly East of Barge SHp; By LU bldg H78 H7~ Triti1,1m 't Gamma Quarterly South of North VV~rehouse .

H79 H79 Tritiu111 / Gamma Quarterly West of A 1A and East of Parking Lot I

It is the policy of Florida Po"Yer & Light Company (FPL) that the St. Lucie 1 & 2 R,a,diol~gical ~nvircmmental Monitoring Programs are conducted by the State of Florida Department df Health (DOH) and Bureau of Radjation Control (BRC), pursuant to an Agreement between FPL and DOH and; that coordination of the Radiological Environmental M0ni\oring Programs with DOH and compliance with the Radiological Environmental Monitoring Program Controls are the responsibility of \he Nuclear Rlant Sµppbrt ServiGes Depprtment.

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.:

C-200_ ST. LUCIE PLANT APPENDIX B-2 . ,. , .

RADIOLOGICAL ENYIRONMENTA~ SAMPLING IN SUPPORT OF THE*_,,

-GROUNDWATER PROTECTION INITIATIVE (Page 2 of:2)

Until further notice, sample collection points, sampling pe6od1city; and ar.alyses to be performed in-support of the Groundwater Protection INITIATIVE (NEI 07-07) shall*be at the discretion of the Chemistry-Manager~

l END OF APPENDJX B-2

REVISION NO.: PROCEDURE TITLE: PAGE:

t PROCEDURE NO.:

226 of 231 C-200 ST. LUCIE PLANT FIGURE 1-1

~SITE AREA MAP & -ENVIRONMENT AL SAMPLE LOCATIONS (Page 1 of 1)

INSET DETAIL

REVISION NO.: PROCEDURE TITLE: PAGE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) t,-----------t 227 of 231 PROCEDURE NO.:

C-200 ST. LUCIE PLANT FIGURE 1-2 ENVIRONMENTAL-SAMPLE LOCATIONS (10 Ml-LES)

(Page 1 of 1)

SSW-10 H12 (P! Chem!C-200/Frg 1-2/Rev.2/png)

REVISION NO.: PROCEDURE TITLE: PAGE:

50 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1------------1 PROCEDURE NO.:

228 of 231 C-200 ST. LUCIE PLANT FIGURE 1-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIE>NS IN SUPPORT OFTHE GROUNDWATER .PROTECTION INITIATIVE (Page 1 of l) r INDIAN RIVER BIG MUD CREEK ATLANTIC OCEAN (PtcnemlC-200/Fig 1-3/Rev.O/png/

REVISION NO.: PROCEDURE TITLE:

i-----5_0_ _--1 OFFSITE DOSE CALCULATION MANUAL .(ODCM)

PROCEDURE NO.:

C-200 ST. LUCIE PLANT APPENDIXC METEOROLOGICAL DISPERSION FORMULAS*

(Page 1 of 1)

For X/Q:

EQ (1)

EQ (2)

Where:

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

(u) = a name for one term X/Q was calculated usin_g_each of the above EQs for each hour. The highest X/Q from EQ (1) or EQ (2) was selected. The totarintegrated relative concentration at each sector and distance was then divided by-tiie total number of hours-in the data base.

Terrain correction factors given by Table M-4 were also applied to Dispersion Formulas For Depleted X/Q:

(X/Q)o-= (X/Q) X (Depletiofriacto_[_Of Figure 2 of R.G. 1.1 t-1-R1)

For Deposition (D/Q):

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 from Figure 6 of R.G. 1.111, R1

REVISION NO.: PROCEDURE TITLE:

50 PROCEDURE NO.: