ML20080M488

Rev 15 to Chemistry Procedure C-200, Odcm

ML20080M488
Person / Time
Site:	Saint Lucie
Issue date:	06/14/1994
From:	Burton C, Wethy C FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228B039	List: ML17228B038 ML17228B040 ML20080M479 ML20080M488
References
C-200, NUDOCS 9503030235
Download: ML20080M488 (181)

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FLORIDA POWER & LIGHT COMPANY V~)v ST. LUCIE PLANT

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CHEMISTRY PROCEDURE NO. C-200 REVISION 15

1.0 TITLE

f OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 4/22 1982 Approved by C. M. Wethy Plant General Manager 4/27 1982 Revision 15 Reviewed by F R G 6/14 1994 Approved by C. L. Burton Plant General Manager 6/14 1994 i

FOR INFORMATION ONLY THl$ DMENT IS NOT CONTROLLED. DETCRE USE.

l VER!FY INFORMATION WITH A CONTROLLED DoctrdENT FLORIDA POWER AND LIGHT CO.

(A)

ST.LUCIE PLANT DATE VERITIED ~ If 9 4 INITIALK N DATEVERIFlED INITIAL s_ OPS DATE DOCT PROCEDURE DOCN 0-200 O

SYS COMP COMPLETED ITM 15 9503030235 950224 ADOCK0500g5 DR i

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Pcge 2 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 o

OFFSITE DOSE CALCULATION MANUAL (ODCM) o 3

\\"j INDEX PAGE

. INTRODUCTION

.................................................7 CONTROLS SECTION DEFINITIONS FOR CONTROLS SECTION......................,... 9 1.1 ACTI O N................................................ 9 1.3 CHANNEL FUNCTIONAL TEST.............................. 9 1.5 CH AN N EL C All B RATION... -............................... 9 1.6 CH AN N EL CH ECK....................................... 9 1.10 DOSE EOUIVALENT I-131

................................10 l

l 1.13 FREQUENCY NOTATION.................................

10 1.16 MEMBER (S) OF THE PUBLIC..............................

10 1.17 OFFSITE DOSE CALCULATION MANUAL.....................

10 1.18 OPERABLE - OPERABILITY...............................

11 1.19 OPERATIONAL MODE - MODE.............................

11 1.23 PURG E - PU RGING...................................... 11 1.25 RATED THERMAL POWER................................

11 pQ 1.27 REPORTABLE EVENT....................................

11 1.30 S ITE BOU N DARY............................~...........

12 1.33 SOU RCE CHECK.......................................

12 1.35 TH ERM AL POWER......................................

12 1.38 UN RESTRICTED AREA..................................

12 1.39 VENTILATION EXHAUST TREATMENT SYSTEM...............

12 1.40 V E NTI N G.............................................

13 1.41 WASTE GAS HOLDUP SYSTEM............................

13 3/4 CONTROLS AND SURVElLLANCE REQUIREMENTS............

15 3/4.0 APPLICABI LITY........................................

15 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...

16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.

21 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LtOUID EFFLUENTS t

CONC ENTRATION..................................

28 D O S E............................................

32 O

LIQUID RADWASTE TREATMENT.......................

33

,e Pzge 3 of 181 ST. LUCIE PLANT l

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 V7 OFFSITE DOSE CALCULATION MANUAL (ODCM)

N.)

l lNDEX CONTROLS SECTION

.l PAGE CONTROL AND SURVEILLANCE STATEMENTS FOR CONTROL SECTION 3/4.11 RADIOACTIVE EFFLUENTS (Continued) 3/4.11.2 GASEOUS EFFLUENTS DO S E RATE......................................

34 DO S E - NOBLE G AS.................................

38 DOSE - IODINE-131, IODINE-133, TRITIUMS AND RADIONUCLIDES IN PARTICULATE FORM..............

39 GASEOUS RADWASTE TREATMENT....................

40 3/4.11.3 (NOT USED) 3/4.11.4 TOTAL DOSE......................................

42 -

3/4.11.5 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

_ (ADMINISTRATIVE CONTROL).........................

44 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

'O TO THE COMMISSION (ADMINISTRATIVE CONTROL)....... 45 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.............................

48 3/4.12.2 LAN D USE CENSU S.................................

57 i

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM...........

59 3/4.12.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (ADMINISTRATIVE CONTROL)..................

60 BASES for CONTROLS SECTION 3/4.11 RADIOACTIVE EFFLUENTS 3/4.3.3.9 I N STR UM E NTATION.................................

62 3/4.11.1 LIQUID EFFLUENTS.................................

63 i

3/4.11.2 GASEOUS EFFLUENTS...............

..............65 3/4.11.3 (NOT USED) 3/4.11.4 TOTAL D O S E......................................

68 3/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.............................

70 3/4.12.2 LAN D U S E C EN SU S.................................

70 x

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM,...........

71 b

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P ge 4 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 TN OFFSITE DOSE CALCULATION MANUAL (ODCM) lj INDEX CONTROLS SECTION PAGE LIST OF FIGURES for CONTROLS SECTION FIGURE 1-1 SITE AREA MAP & ENVIRONMENTAL SAMPLE LOCATIONS...

177 1 ENVIRONMENTAL SAMPLE LOCATIONS (10 MILES).........

178 LIST OF TABLES for CONTROLS SECTION TABLE 1-1 FREQUENCY NOTATION...............................

14 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING (3

INSTRU M ENTATION...................................

17 V

3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUM ENTATION....................... !...........

22 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....

50 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES..........................

53 4.3-8 RADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........

19 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........

25 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROG RAM..............................

29 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AN D ANALYSIS PROG RAM..............................

35 3

4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE

.i ANALYSIS LOWER LIMIT OF DETECTION (LLD)..............

54 O

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~ CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 1(^

OFFSITE DOSE CALCULATION MANUAL-(ODCML i

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INDEX

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' METHODOLOGY'SECTION j

i M.

PAGE i

3 Glossary for Methodology Section................................

73 ~

F

-1.0 LIQUID RELEASES METHODOLOGY........................

76

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1.1 Radioactive Liquid Effluent Model' Assumptions.............

77 f

1.2 ' Determining the Fraction (F) of 10 CFR Part 20 1

Effluent Concentration Limits (ECL) for a Liquid Release Source.

78 /R15 1.3 ' Determining Setpoints for Radioactive Liquid Effluent Monitors............ _.......................

81 1

1.4 Determining the Dose for Radioactive Liquid Releases........

83 1.5 Projecting Dose for Radioactive Liquid Effluents.............

87 -

2.0 Radioactive Releases of Gaseous Effluents..................... 88 I

2.1 Gaseous Effluent Model Assumptions....................

89 l

2.2 Determining the Total Body and Skin Dose Rates for-

/R15 i

Noble Gas Releases and Establishing Setpoints j

for Effluent Monitors.................................. 90 j

2.3 Determining the Radiolodine and Particulate Dose Rate j

to Any Organ From Gaseous Releases...................

97 2.3.1 inhalation...................................

99 2.3.2 Ground Plane................................

101 3

2.3.3 M ilk......................................

1 02 2.3.4 Tritium..................................... 104 2.3.5 Total Dose Rate by Release Source................106 2.4 Determining the Gamma Air Dose for Radioactive Noble Gas Releases...............................

106 J

2.5 Determining the Beta Air Dose for Radioactive Noble Gas Releases...............................

110 '

i 2.6 Determining the Radiolodine and Particulate Dose i

to Any Organ From Cumulative Releases.................112 l

DISCUSSION 2.6.1 inhalation..................................

1 15 t

2.6.2 Ground Plane................................ 116 I

2.6.3 M ilk......................................

1 17 2.6.4 Tritium (All pathways).........................

118 2.6.5 Total Organ Dose............................

119 2.7 Projecting Dose for Radioactive Gaseous Effluents.........

120 i

b Page 6 of 181 ST. LUCIE ' PLANT' CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 D-OFFSITE DOSE CALCULATION MANUAL (ODCMF l

,d

INDEX-METHODOLOGY SECTION t

PAGE

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3.0 40 CFR 190 Dose Evaluation..............................

121 4.0 Annual Report Format...................................

122 Appendix A - ECL, Dose Factor and Historical

/R15 Meteorological Tables...................................

138 Appendix B - Limited Analysis Dose Assessment for Liquid Radioactive Effluents...............................

165 Appendix C - Technical Bases for Effective Dose Factors..............

167 Appendix D - Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Storage Tariks......................

171 l

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

173 Appendix F - Description of Meteorological Dispersion Formulas Utilized for Historical Data and Methodology for O

Determining Actual MET Data.............................

179 4

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7. LUCIE PLANT CHEMISTRY OPERE PROCEDURE NO. C-200, REVISION 15

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OFFSITE D:L CALCULATION MANUAL (ODCM)

Q i

INTRODUCTION

]

The ODCM consists of the Controls Section followed by the Methodology Section.

The Controls Section provides the Control Statements, Limits, ACTION Statements, Surveillance Requirements and BASES for ensuring that Radioactive Liquid and Gaseous Effluents released to UNRESTRICTED AREAS and/or the SITE BOUNDARY will be i

maintained within the requirements of 10 CFR Part 20,40 CFR Part 190,10 CFR 50.36.a j

and 10 CFR Part 50 Appendix-1 radioactive release criteria. All Control Statements and j

most Administrative Control Statements in the ODCM are directly tied to and reference the -

l Plant Technical Specification (TS) Administrative Section. The Administrative Control for Major Changes to Radioactive Liquid, Gaseous and Solid Treatment Systems is as per the guidance of NUREG-1301, April 1991, Supplement No.1 to NRC Generic Letter 89-01. The 4

numbering sequences of Control Statements also follow the guidance of NUREG-1301 as i

applicable, to minimize differences.

l The Methodology Section uses the models suggested by NUREG-0133, November,1978 l

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 l

Control requirements. Altemate calculation methods may be used from those presented as O-long as the overall methodology does not change or as long as most up-to-date revisions of the Regulatory Guide 1.109 dose conversion factors and environm' ental transfer factors are substituted for those currently included and used in this document.

RECORDS AND NOTIFICATIONS All records of reviews performed for changes to the ODCM shall be maintained in accordance with Ol 17-PR/PSL-1. All FRG approved changes to the.ODCM, with required documentation of the changes per TS 6.14, shall be submitted to the NRC in the Annual Effluent Release Report. Procedures that directly implement, administer or supplement the l

requirements of the ODCM Controls and Surveillances are:

C-01 Schedule for Periodic Test C-02 Schedule for Test Calibrations C-70 Processing Aerated Liquid Waste f

C-72 Processing Gaseous Wastes i

The Radiological Environmental Monitoring Program is performed by the State of Florida as per FPL Juno Nuclear Operations Corporate l

Environmental Procedures.

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ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 -

7'"y...c OFFSITE DOSE CALCULATION MANUAL (ODCMF y

CONTROLS AND l

SURVEILLANCE REQUIREMENTS -

O l

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O St. Lucie Plant ODCM Controls

P ge 9 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 fl OFFSITE DOSE CALCULATION MANUAL (ODCM)

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.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 CAllBRATION 1.4 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is -

calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the seme parameter.

CHANNEL FUNCTIONAL TEST f

l 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simuhted signal into the l

channel as close to the sensor as practicable to verify OPERABILIW of alarm, interlock and/or trip functions. The CHANNEL FUNCTIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the setpoints are within the required range and accuracy.

St. Lucie Plant ODCM Controls

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. ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 f

OFFSITE DOSE CALCULATION MANUAL (ODCM) -

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i 1.0 DEFINITIONS for CONTROLS SECTION OF ODCM l

DOSE EQUlVALENT l-131 l

l 1.10 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of ~

j 1131,1-132,1-133,1-134 and 1-135 actually present. The thyroid dose conversion factors used for this ' calculation shall be those listed in [ Table ill of TID-14844, Calculation of l

Distance Factors for Power and Test Reactor Sites or Table E-7 of NRC Regulatory i

Guide 1.109, Revision 1, October 1977).

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance l

Requirements shall correspond to the intervals defined in Table 1.1.

j i

MEMBER (S) OF THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area.

However, an individual is not a member of the public during any period in which the 4

individual receives an occupational dose.

/R15 OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from i

radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent l

monitoring Alarm / 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 (2) descriptions of the information that should be included in the Annual Radiological l

Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 6.9.1.7 and 6.9.1.8.

/R15 l

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m Pege 11 of 181-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 6J lOFFSITE DOSE CALCULATION MANUAL (ODCM)

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'3.7d E1.0 DEFINITIONS for CONTROLS SECTION OF ODCM -

OPERABLE - OPERABILITY i

1.19 A system, subsystem, train, component or device shall be OPERABLE or have

'l l.

- OPERABILITY when it is capable of performing-its specified function (s)~ and when all

.necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, a

component or device to perform its function (s) are also capable of performing their related support function (s).

/R15 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.

'/R15 PURGE - PURGING

. O

.24 i

1 PURGE or PURGING shall be any controlled process of discharging air or gas from

. a confinement to maintain temperature, pressure, humidity, concentration or other operating i

condition, in such a manner that replacement air or gas is required to purify the confinement. /R15

- RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the' reactor coolant of 2700 MWt.

f REPORTABLE EVENT 1.27. A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 l

of 10 CFR Part 50.

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St. Lucie Plant ODCM Controls I

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ST. LUCIE PLANT.

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CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 i

74' OFFSIT~ DOSE CALCULATION MANUAL (ODCM)

.1.0 DEFINITIONS for CONTROLS SECTION OF ODCM l

SITE BOUNDARY 1

'1.30 SITE BOUNDARY means that line beyond which the land or property is not owned, leased or otherwise controlled by the licensee.~

l 1

SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when j

the channel sensor is exposed to a radioactive source.

THERMAL POWER l

i 1.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor l

coolant.

l A

UNRESTRICTED AREA l

U 1.35 UNRESTRICTED AREA means an area, access to which is neither limited nor.

l controlled by the licensee.

VENTILATION EXHAUST TREATMENT SYSTEM 1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

/R15 O

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ST. LUCIE PLANT l

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 A

. OFFSITE DOSE CALCULATION MANUAL (ODCM)

Q) 1.0 - DEFINITIONS for CONTROLS SECTION OF ODCM VENTING

- 1.40 VENTING shall be the controlled process of discharging air or gas from a confinement 1

to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

t WASTE GAS HOLDUP SYSTEM 1.41 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to.

reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

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St. Lucie Plant ODCM Controls i

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CHEMISTRY OPERATING PROCEDURE NO. C-200,' REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 1.1 FREQUENCY NOTATION a

NOTATION FREQUENCY S

At least once p.,r 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D.

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

W At least once per 7 days.

At least 4 per month at intervals of no greater 4/M.

than 9 days and minimum of 48 per year.

M

' At least once per 31 days.

O At lease once per 92 days.

j

'l 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 reIease

=i

• For Radioactive Effluent Sampling l

" For Radioactive Batch Releases Only J

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O St. Lucie Plant ODCM Controls

p-P ge 15 cf 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 7]-

OFFSITE DOSE CALCULATION MANUAL (ODCM) 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the Controls contained in the succeeding controls is required during the conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the conditions specified for individual Controls unless otherwise stated in an individual Suweillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with; a.

A maximum allowable extension not to exceed 25% of the surveillance interval.

St. Lucie Plant ODCM Controls

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ST, LUCIE PLANT

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION.15.

OFFSITE DOSE CALCULATION MANUAL (ODCM) l INSTRUMENTATION.

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

CONTROLS 3.3.3.9

In accordance with St. Lucie Plant TS 6.8.4.f.1), the radioactive liquid effluent L l

monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their -

l Alarm / Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The.

Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM),

t

' APPLICABILITY: At all times.

ACTION:

4 With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip a.

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 j

acceptably consentative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful,~ explain in the next Annual Radioactive Effluent' Release!

Report why this inoperability was not corrected in a timely manner..

c.

Report all deviations in the Annual Radioactive Effluent Release Report.

i SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel'shall be I

demonstrated OPERABLE by erformance of the CHANNEL CHECK,' SOURCE CHECK,

.i CHANNEL CAllBRATION ano CHANNEL FUNCTIONAL TEST at the frequencies shown In Table 4.3-8.

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- CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

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OFFSITE DOSE CALCULATION MANUAL (ODCM)

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LTABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION-MINIMUM

{

CHANNELS-

. INSTRUMENT-OPERABLE'

' ACTION.

l

1. Radioactivity Mon?. ors Providing Alarm and Autc.natic Termination of 1

Release i

a) Liquid Radwaste Effluent Line 1

35 l

b) Steam Generator Blowdown 1/SG 36 Effluent Line j

2. Flow Rate Measurement Devices l

a) Liquid Radwaste Effluent Line N.A.

38-b) Discharge Canal N.A.

38 c) Steam Generator Blowdown N.A.

38 i

Effluent Lines O

SG - Denotes Steam Generator

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Pcge 18 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 j7 OFFSITE DOSE CALCULATION MANUAL (ODCM)

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TABLE 3.3-12 (Continued)

I ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with the Surveillance Requirement for concentration limit of Control 4.11.1.1.1. and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 2.E-07 micro-Curie /mi:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is

~

greater than 0.01 micro-Curies / gram DOSE EQUIVALENT l-131 or b.

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

ACTION 38 - Minimum system design flow of required running pumps shall be utilized for ECL calculations for discharge canal flow and maximum system design flow be utilized for ECL calculations for effluent line flow.

/R15 O

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-l CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15-

'OFFSITE DOSE CALCULATION MANUAL (ODCM)

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TABLE'4.3-8 J'

. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

CHANNEL.

CHANNEL-SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CAllBRATION TEST

1. Radioactivity Monitors l

Providing Alarm and Automatic Termination of Release a) Liquid Radwaste Effluent D

P R(2)

O(1) l Line

.b) Steam Generator D

M R(2)

O(1)

Blowdown Effluent Line

2. Flow Rate Measurement i

Devices a) Liquid Radwaste Effluent D(3)

N.A.

R O

Line O

' b)' Discharge Canal D(3)

N.A.

R O

[

c)

Steam Generator -

D(3)

N.A.

it' O-l Blowdown Effluent Line l

l I

l O

St. Lucie Plant ODCM Controls 5

ST. LUCIE PLANT -

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 N'

~ OFFSITE DOSE CALCULATION MANUAL (ODCM) l cd J

TABLE 4.3-8 (Continued)

TABLE NOTATIONS I

1 (1), The CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this i

' pathway and control room alarm annunciation occur if any of the following conditions -

j exist:

j

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

l 2.

Circuit failure or j

3.

Instrument indicates e downscale failure or I

in 1

4.

Instrument controls not set in operate mode.

l

'(2)

The initial CHANNEL CAllBRATION shall be performed using one or more.of the reference standards traceable to the National institute of Standards & Technology.

l (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 O

of energy and rate capabilities that are typical of normal plant operation.

For 1

subsequent CHANNEL CAllBRATION, button sources that have been related to the j

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 hous on days on which l

continuous, periodic or batch releases are made.

l i

l I

.i I

l

o St. Lucie Plant ODCM Controls

n Page 21 of 181 ST) LUCIE PLANT L.

CHEMISTRY. OPERATING PROCEDURE NO. C-200, REVISION 15 -

l

- OFFSITE DOSE CALCULATION MANUAL (ODCM)

-l INSTRUMENTATION -

i

. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l

1

' CONTROLS l

o 3.3.3.10 in accordance with St. Lucie Plant TS 6.8.4.f.1), the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with -

i their Alarm / Trip Setpoints s,et 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.

i q

. APPLICABILITY: As shown in Table 3.3-13 l

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel l

Alarm / Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by I

the affected channel or declare the channel inoperable or change the setpoint

].

so it is acceptably conservative.

~!

b.

With less than the minimum number of radioactive gaseous effluent monitoring i

instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.-

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release i

Report why this inoperability was not corrected in a timely manner.

l i

c.

Report all deviations in the Annual Radioactive Effluent Release Report.

]

I i

l SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be j

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK,

~

CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown i

in Table 4.3-9.

i i

O St. Lucie Plant ODCM Controls

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P ge 22 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 p.,

OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Waste Gas Holdup System a)

Noble Gas Activity Monitor -

Providing Alarm and 1/Rx 45 Automatic Term, nation of i

Release

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

3. Plant Vent System a)

Noble Gas Activity Monitor 1/Rx 47 (Low Range) l b) lodine Sampler 1/Rx 51 g

c)

Particulate Sampler 1/Rx 51 l C/

d) Flow Rate Monitor N.A.

53 e) Sampler Flow Rate Monitor 1/Rx 46

4. Fuel Storage Area Ventilation l

System a)

Noble Gas Activity Monitor 1/Rx 47 (Low Range) b)

lodine Sampler 1/Rx 51 i

c)

Particulate Sampler 1/Rx 51 d)

Flow Rate Monitor N.A.

53 e) Sampler Flow Rate Monitor 1/Rx 46 r

O St. Lucie Plant ODCM Controls

P ge 23 of 181 1

ST. LUCIE PLANT

-CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 6

OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 3,3-13 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY

' ACTION

5. Laundry Area Ventilation System a) Noble Gas Activity Monitor 1/Rx 47 (Low Range) b)

lodine Sampler 1/Rx 51 c)

Particulate Sampler -

1/Rx 51 d) Flow Rate Monitor

-N.A.

53 e) Sampler Flow Rate Monitor 1/Rx 46

6. Steam Generator Blowdown

. Building Vent-a)

Noble Gas Activity Monitor 1

47 (Low Range)

['

b) lodine Sampler 1

51 c)

Particulate Sampler 1

51' d) Flow Rate Monitor N.A.

53 e) Sampler Flow Rate Monitor 1

46

. O St. Lucie Plant ODCM Controls

Pdge 24 of 181 L ST. LUCIE PLANT '

CHEMISTRY OPERATING PROCEDURE NO. C-200,' REVISION 15

~

f OFFSITE DOSE CALCULATION MANUAL (ODCM) i~~ 7

.,/ <

j TABLE 3.3-13 (Ocethygd),

i

. TABLE NOTATIG4S '

- At all times while making releases via this pathway

- At all times wh9n air ejector exhaust is not directed to plant vent.

j.

Rx

- Denotes reactor l

/

ACTION STATEMENTS' LACTION 45 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the:

environment for up to 14 days provided that prior to initiating a release-a.

At least two independent samples of the tank's contents are analyzed and

.i b.

At least two technically qualified membo'rs of the facility staff independently verify the release rate calculations and discharge valve lineup.

j Otherwise, suspend release of radioactive effluents via this pathway, d

i O

ACTION 46 - With the number of channels OPERABLE less than required by the Minimum 1

Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 47 - With the number of channels OPERABLE less than required by the Minimum i

Channels OPERABLE requirement, effluent releases via this pathway may continue for up j

to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling j

equipment as required in Table 4.11-2.

.j ACTION 53 - Maximum system flows shall be utilized in the determination of the instantaneous release monitor alarm setpoint.

i e

O 1

St. Lucie Plant ODCM Controls i

t I

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Pcge 25 of 181 i

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

/

OFFSITE DOSE CALCULATION MANUAL (ODCM) u]--

TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Modes in CHANNEL which CHANNEL SOURCE CHANNEL FUNCTIONAL surveillance INSTRUMENT CHECK CHECK CAllBRATION TEST required -

1. Waste Gas Holdup

~'

System a)

Noble Gas Activity Monitor - Providing Alann and P

P R(3)

Q(1)

Automatic Termination of Release

2. Condenser Evacuation System a)

Noble Gas Activity D

M R(3)

Q(2)

Monitor

3. Plant Vent System a) Noble Gas Activity D

M R(3)

--Q(2)

Monitor b) lodine Sampler W

N.A.

N.A.

N.A.

c) Particulate Sampler W

N.A.

N.A.

N.A.

j d) Flow Rate Monitor D

N.A.

R Q

e) Sampler Flow Rate D

N.A.

R N.A.

Monitor

4. Fuel Storage Area Ventilation System a)

Noble Gas Activity D

M R(3)

Q(2)

Monitor b) lodine Sampler W

N.A.

N.A.

N.A.

c)

Particulate Sampler W

N.A.

N.A.

N.A.

d)

Flow Rate Monitor D

N.A.

R Q

f e)

Sa r Flow Rate D

N.A.

R N.A.

o St. Lucie Plant ODCM Controls P

/- ^-

j

' PAge 26 of 181 l

J

~

v ST. LUCIE PLANT!

CHEMISTRY: OPERATING PROCEDURE NO. C-200, REVISION 15 1

(V'E)-

OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 4.3-9 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING l

INSTRUMENTATION SURVEILLANCE REQUIREMENTS' Modes in :

I CHANNEL which CHANNEL SOURCE

' CHANNEL FUNCTIONAL surveillance

- INSTRUMENT CHECK.

CHECK CAllBRATION TEST required l

S. Laundry Area Ventilation System a)

Noble Gas Activity D

M R(3)-

Q(2)

Monitor b) lodine Sampler W

N.A.

N.A.

N.A.

c)

Particulate Sampler W

N.A.

N.A.

N.A.

d)

Flow Rate Monitor D

N.A.

R Q

e)

Sampler Flow Rate D

N.A.

R N.A.

Monitor

6. Steam Generator Blowdown Building Vent

. a)

Noble Gas Activity.

[

D M-R(3)

Q(2)

Monitor

\\

t b) lodine Sampler W

N.A.

N.A.

- N.A.

c)

Particulate Sampler W

N.A.

N.A.

N.A.

'{

d)

Flow Rate Monitor D

N. A.-

R Q

• )

• p r R w Rate D

N.A.

R N.A.

,.g,

~1 1

O

'St. Lucie Plant ODCM Controls w

n w

a Page 27'of 181;

. ST. LOCIE PLANT

~

j CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION.15 1

[

.OFFSITE DOSE CALCULATION MANUAL (ODCM) j W.

' TABLE 4.3-g (Continued)

[

TABLE NOTATIONS

~

At all times when making releases via this pathway.

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

exist:

]

.(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions-1 1.

Instrument indicates measured levels above the alarm / trip setpoint or

.f 2.

Circuit failure or i

3.

Instrument indicates a downscale failure or f

4.

Instrument controls not set in operate mode.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm I

O (2) annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint or 2.-

Circuit failure or

q 3.

Instrument indicates a downscale failure or l

4.

Instrument controls not set in operate mode.

i (3). The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards traceable to the National Institute of Standards & Technology 1

l :.,

(NIST) or using standards that have been calibrated against standards certified by the 1

NIST. These standards should permit calibrating the system over its intended range j

of energy and rate capebilities that are typical of normal plant operation.

For j

subsequent CHANNEL CAllBRATION, button sources that have been related to the 1

. initial calibration may be used.

l l

"O St. Lucie Plant ODCM Controls t

'Page 28 of 181 l

l ST. LUCIE PLANT-e' CHEMISTRY OPERATING PROCEDURE NO.- C-200, REVISION 15 j

~ OFFSITE DOSE CALCULATION MANUAL (ODCM):

K{y

^ j

/4.11 3

RADIOACTIVE EFFLUENTS 1

!3/4.11.1

- LIQUID EFFLUENTS

]

_, CONCENTRATION CONTROLS ~

i

~

3.11.1.1-In accordance with the St. Lucie Plant TS 6.8.4.f.2) and 3), the concentration '

i of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see TS -

I

. 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 otherthan dissolved'

' or entrained noble gases. - For dissolved or entrained noble gases, the concentration shall be limited to 2.E-04 micro-Curie /ml total activity.

/R15

' APPLICABILITY: At all times.

i

ACTION:

i i

a.

With the concentration of radioactive material released in liquid effluents to Ob UNRESTRICTED AREAS exceeding the above limits, immediately restore the l

concentration to within the above limits.

l

~i

. SURVEILLANCE REQUIREMENTS l

4.11.1.1.1

.adioactive liquid wastes shall be sampled and analyzed according to the-i sampling and analysis program of Table 4.11-1.

l 4.11.1.1.2' The results of the radioactivity analyses shall be used in accordance with the -

methodology and parameters in the ODCM to assure that the concentrations at the point of -

release are maintained within the limits of Control 3.11.1.1.

i

-4.11.1.1.3 Post-release analyses of samples composited from batch' releases shall be performed in accordance with Table 4.11-1 and results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 3.11.1.1.

O St. Lucie Plant ODCM Controls

f5 Prge 29 of 181 j

e ST. LUCIE PLANT

. CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

O-l TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.

f l

M" d

Liquid Release Sampling Type of Actmty

.A i

Type Frequency Analysis p

LLD (1) (pCi/ml) l A.

Batch Waste P'

P.G.E. (3) 5.E-07 j

Ead Bats Release Each Batch -

I131 1.E-06 i

Tank (2)

Dissolved and i

P Entrained 1.E45 One, Batch /M Gases (Gamma Emitters) j P-M H-3 1.E-05 j

Each Batch Composite (4)

Gross Alpha 1.E-07 i

P Q

Sr-89, Sr-90 5.E-08

[

Each Batch Composite (4)

Fe-55 1.E-06 i

B.

Continuous 4/M P.G.E.(3) 5.E-07 f

Releases (5, Daily Composite l-131 1.E 06 l

6)

Dissolved and i

Daily 4/M Entrained 1.E-05 Grab Sample Composite Gases (Gamma O

Emitters) j M

H-3 1.E-05 l

"NY Composite Gross Alpha 1.E-07 i

O Sr-89, Sr-90 5.E-08 DaHy Composite Fe-55 1.E-06 l

C.

Settling Basin W

W (7)

Grab Sample 1-131 1.E-06 l

P.G.E. -

Denotes Principal Gamma Emitter I

l 1

l i

O St. Lucie Plant ODCM Controls i

i l

I t

a w

.---w

-n w.,-----m v

w w,

y Pige 30 of 181-ST. LUCIE PLANT..

- CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 fV OFFSITE DOSE CALCULATION MANUAL (ODCM) w

)

TABLE 4.11-1 (Continued) l TABLE NOTATION t

-(1) - The LLD is defined for purposes of these controls, as the~ smallest concentration of:

,i radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding j

that a blank observation represents a real signal. '

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

l 4.66 S3 LLD =

- E V. 2.22EG. Y. exp (- A. AT) l

' Where:

.l the a priori lower limit of detection (micro-Curie per. unit mass or k

LLD

=

volume),

the standard deviation of the background counting rate or'of the l

S,

=

counting rate of a blank sample as appropriate (counts per minute),

j

~

E the counting efficiency (counts per disintegration),

=

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

=

the number of disintegrations per minute per micro-Curie.,

I 2.22E+06

=

_Y the fractional radiochemical yield, when applicable,.

=

A the radioactive decay constant for the particular radionuclide (sec )

4

=

and AT the elapsed time between the midpoint of sample collection and the

=

time of counting (sec).

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

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

<o St. Lucie Plant ODCM Controls l

l

ST. LUCIE PLANT :

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 2*:

OFFSITE DOSE CALCULATION MANUAL (ODCM) i I

. TABLE 4.11 (Continued) -

TABLE NOTATIONS (Continued)

~(2) _ A batch release is the. discharge of liquid wastes of a discrete volume. ' Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

)

1 (3) The principal gamma emitisrs for which the LLD control applies include the following'.

l radionuclides:

Mn-54, Fe-09, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 and Ce-141 and Ce-144. This list does not mean that only these nuclides are to be -

considered. Other gamma peaks that are identifiable, together with those of the above '

nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 3.11.2.6 in the format outlined in Regulatory Guide l

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.

a (5)' A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,

from a volume of a system that has an input flow during the c6ntinuous release.

(6) If Component Cooling Water activity is > 1.E-5 Ci/ml, perform a weekly gross activity on the Intake Cooling Water System outlet to ensure the activity level is less than or equal to 2.E-07 Cl/mi LLO limit. If ICW is >2.E-07 Ci/ml, perform analysis in accordance with a Plant Conti;.ucus Release on this Table.

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

O St. Lucie Plant ODCM Controls

P:ge 32 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 (5

OFFSITE DOSE CALCULATION MANUAL (ODCM)

RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with St. Lucie Plant TS 6.8.4.f.4) and 6.8.4.f.5), the dose or dose commitment to a MEMBEE < )F THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body 1

and to less than or equal to 5 mrems to any organ and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to theCommission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

l SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

O St. Lucie Plant ODCM Controls

r

]

Pcge 33 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

{J}

OFFSITE DOSE CALCULATION MANUAL (ODCM) b RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM

' CONTROLS 3.11.1.3 in accordance with St. Lucie Plant TS 6.8.4.f.6), the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that includes the following information:

1.

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

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status and 3.

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

l SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

O St. Lucie Plant ODCM Controls

~

f

- '[

~

Prge'34 of 181?

~

+

i

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ST. LUCIE PLANTr

- CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

' RADIOACTIVE EFFLUENTS ~

' ~ ' '

1 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE

' CONTROLS.

)

3.11.2.1:

' in accordance with St. Lucie Plant TS 6.8.4.f.3) and 7), the dose rate resulting; l

from radioactive materials released in gaseous effluents to areas at or beyond the SITE.

BOUNDARY (see_TS Figure 5.1-1) shall be limited to the following:

/R15'

' a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less l

than or equal to 3000 mrems/yr to the skin and

/R15.

1

. b. For lodine-131, for lodine-133, for tritium and for all radionuclides in particulate form -

j

-with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to 'any organ j

APPLICABILITY: At all times.

[

ACTION:

i

a. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

i SURVEILLANCE REQUIREMENTS 4.11.2 1.1. The dose rate due to noble gases in gaseous effluents shall be determined'to L l

be within the above limits in accordance with the methodology and parameters in the ODCM.

'i 1

4.11.2.1.2 The dose rate due to lodine-131, lodine-133, tritium and all radionuclides in l

. particulate form with half-lives greater than 8 days in gaseous effluents shall be determined -

-i 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.

O St. Lucie Plant ODCM Controls j

I i

a Em

.-m,

rs Pcge 35 of 181 ~

l L

ST. LUCIE PLANT i

i CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCMJ TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING & ANALYSIS PROGRAM i

Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type Frequency

. Analysis Analysis Detection

~

Frequency (LLD) (1) -

L!

(kCi/cc)

I

1. - Waste Gas P

P Noble Gas 1.E-04 Storage Tank Each Tank.

Each Tank P.G.E.(2) l Grab Sample i

2.

Containment P

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

Each Purge (6)

P.G.E. (2)

Grab Sample (7)

H-3 1.E-06

/R15 3.

Vents:

4/M 4M (7)

Noble Gas 1.E-04

/R15 i

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

b. Fuel Bidg (5)

c. Laundry H-3 1.E-06

d. S/G j

Blowdown Bldg.

O 4.

All Release Continuous (3) 4/M l-131 1.E-12 Types as Charcoal listed in 3.

Sample (4) above 4/M P.G.E.

1.E-11 l

Particulate i

Sample (4) 1 M

Gross Alpha 1.E-11 Composite.

Particulate -

l Sample O

Sr-89, Sr 90 1.E-11 Composite i

Particulate l

Sample j

Noble Gas Noble Gases 1.E-06

.l Monitor Gross Beta or l

Gamma

-l P.G.E. -

Denotes Principal Gamma Emitters O

D 1

St. Lucie Plant ODCM Controls l

i

+

w

~

'Pige 36'of 181 ST. LUCIE PLANT -

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)-

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1). The LLD'is defined for purposes of these controls, as the smallest concentration of -

radioactive material in a sample that will yield a net count, above system background,1 that will be d' etected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.

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

4.66' S, -

LLD = E. V 2.22E4Xi. Y. exp (- A. A7)

~

Where:

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

=

volume),

S, the standard deviation of the background counting rate or of tha-

=

counting rate of a blank sample as appropriate (counts per minute),

the counting efficiency (counts per disintegradon),

E

=

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 d

the radioactive decay constant for the particular radionuclide (see ) -

=

and j

the elapsed time between the midpoint of sample collection and the AT

=

time of counting (sec).

-l Typical values of E, V, Y and AT should be used in the calculation.

It should be recognized 'that the LLD is defined _as an g oriori (before the fact) limit l

representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

j f

O St. Lucie Plant ODCM Controls I

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P:ge 37 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 f

OFFSITE DOSE CALCULATION MANUAL (ODCM)

'b" TABLE 4.11-1 (Contin.ygd).

J TABLE NOTATIONS (Continued)

(2) The principal gamma emitters for which the LLD control applies include the following radionuclides:

Kr-87,Kr-88, Xe-133, Xe-133m, Xe-135. and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in lodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 3.11.2.6 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the tima 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each O

shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of 3.

(5) Tritium grab samples shall be taken at least 4/M from the ventilation exhaust from the spent fuel ' pool area, whenever spent fuel is in the spent fuel pool.

-(6) Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

(7) Tritium analysis may be delayed for up to 14 days if the LLD is still attainable at the new counting time.

/R15 O

St. Lucie Plant ODCM Controls

t Pcge 38 of 181 l

ST. LUCIE PLANT 4

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

^

-OFFSITE DOSE CALCULATION MANUAL (ODCM)

J RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES -

I CONTROLS I

- 3.11.2.2.

In accordance with St. Lucie Plant TS 6.8.4.f.5) and 8), the air dose due to j

noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE i

BOUNDARY (see TS Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and.less than or equal to 10 mrads for beta radiation and' H

- 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.

i APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the-Commission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to j

assure that subsequent releases will be in compliance with the above limits.

i i

' SURVEILLANCE REQUIREMENTS i

4.11.2.2 Cumulative dose contributions for the current calendar quarter and current l

calendar year for noble gases shall be determined in accordance with the methodology and parameters in the CDCM at least once per 31 days.

y 2

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St. Lucie Plant ODCM Controls

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P:ge 39 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 O

OFFSITE DOSE CALCULATION MANUAL (ODCM)

L RADIOACTIVE EFFLUENTS DOSE - IODINE-131. IODINE-133. TRITlUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 fo accordc.rce with St. Lucie PILnt TS 6.8.4.f.5) and 9), the dose to a MEMBER OF THE PUBLIC fmm !odine-i31, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, I

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

0 with the e ic"i teo 8 e <<em the reie e e'i ei"e-'a, 'eoime-'sa.triti#m #8 radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Plant TS 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to assure that subsequent releases will be in compliance with the above limits.

i SURVE:lLLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions fcr the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined a accordance with the methodology and parameters in the ODCM at least once per 31 days.

1 O

St. Lucie Plant ODCM Controls

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P:ge 40 ef 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 n.,

OFFSITE DOSE CALCULATION MANUAL (ODCM)

-(

/

RADIOACTIVE EFFLUENTS j

GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 in accordance with St. Lucie Plant TS 6.8.4.f.6), the VENTILATION EXHAUST Treatment System and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and i

appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and i

beyond the SITE BOUNDARY (see TS Figure 5.1-1) would exceed:

i a.

0.2 mrad to air from gamma radiation or b.

0.4 mrad to air from beta radiation or c.

0.3 mrem to any organ.

APPLICABILITY: At all times.

(

ACTION:

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

1.

Identification of any inoperable equioment or subsystems and the reason for the inoperability, l

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status and l

3.

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

l O

St. Lucie Plant ODCM Controls

7 P ge 41 of.181 ST. LUCIE PLANT i

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 7'~y OFFSITE DOSE CALCULATION MANUAL (ODCM) v RADIOACT!VE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM (Continued)

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be demonstrated OPERABLE by operating the WASTE GAS HOLDUP SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

4 f

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O St. Lucie Plant ODCM Controls

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_ Pcge 42 of 181 i

ST. LUCIE PLANT l

- CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 -

OFFSITE DOSE CALCULATION MANUAL (ODCML

' RADIOACTIVE EFFLUENTS' f

3/4.11.4- ' TOTAL DOSE i

CONTROLS l

. 3.11.4 in accordance with St. Lucie Plant TS 6.8.4.f.10), the' annual (calendar year) dose-

<i or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and ~

j to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a 3.11.2.2.b,3.11.2.3.a or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks etc.) to i

/

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 l

subsequent releases to prevent recurrence of exceeding the above limits and i

includes the schedule for achieving conformance with the above limits. This Special i

Report, as defined in Subpart M of 10 CFR Part 20, shall include an analysis that l

estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from l

uranium fuel cycle sources, including all effluent pathways and direct radiation, for i

the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive materialinvolved and i

the cause of the exposure levels or concentrations.

If the estimated dose (s) exceeds the above limits and if the release condition resulting in violation of 40 Part -

190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the I

report is considered a timely request and a' variance is granted until staff action on -

l the request is complete.

1 I

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St. Lucie Plant ODCM Controls i

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Page '43 of 181 ST. LUCIE PLANT

)

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 9%

OFFSITE DOSE CALCULATION MANUAL (ODCM)

.t u

- RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE (Continued]

SURVEILLANCE REQUIREMENTS h

4.11.4.1

' Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2,4.11.2.2 and 4.11.2.3 and in accordance with the methodology and parameters in the ODCM.

.i 4.11.4.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks etc.) shall be determined in accordance with the methodology and j

. parameters in the ODCM. This requirement is applicable only under conditions set forth in '

l ACTION a. of Control 3.11.4.

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St. Lucie Plant ODCM Controls i

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Page 44 of 181 3

- ST. LUCIE PLANT

' CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 l

(i N OFFSITE DOSE CALCULATION MANUAL (ODCM) w

RADIOACTIVE EFFLUENTS 3/4.11.5 ~

MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE i

TREATMENT SYSTEMS *

- ADMINISTRATIVE CONTROLS 3.11.2.5

-Licensee initiated major changes to the radioactive waste' systems-(liquid,

' gaseous and solid):

7

1) Shall be' reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluatlon was reviewed by the Facility Review -

Group (FRG). The discussion of each shall contain:

a) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

a b) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

~

i 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 j

materials in liquid and gaseous effluents and/or quantity of solid waste that differ from-those previously predicted in the license application and l

amendments thereto; e) An evaluation of the change which shows the expected maximum exposure to l

individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and i

amendments thereto; f)

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period when the changes are to be made; g) An estimate of the exposure to plant operating personnel as a result of the i

change; and l

h) Documentation of the fact that the change was reviewed and found acceptable i

by the FRG.

j

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

]

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

O

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St. Lucie Plant ODCM Controls l

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c-P:ge 45 of 181 ST. LUCIE PLANT t

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

(

OFFSITE DOSE CALCULATION MANUAL (ODCM)

' RADIOACTIVE EFFLUENTS 3/4.11.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TO THE COMMISSION

• ADMINISTRATIVE CONTROLS 3.11.2.6 As per Technical Specification 6.9.1.7, a Annual Radioactive Effluent Release Report covering the operation of each unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from each unit. The material provided shall be (1) consistent with the objectives outlined in by items a) through f) below, using the example report format in the ODCM and (2) be in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

a. The Radioactive Effluent Release Reports shallinclude 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 O

oe eee erri eete<1.0 pCi per cubic t

meters and which is also >10 times that of the most recent control sample.

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

h radionuclides that may be attributable to the effluents from the facility.

k.

Discharges from the St. Lucie Plant do not influence drinking water or ground water pathways.

m. : Atlantic Ocean, in the vicinity of the public beaches along the eastem shore of l

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/O and one sample of similar broad leaf vegetation at an available location 15-30 kilometers distant in the least prevalent wind direction based upon historical data in the ODCM.

[i, j, I (lower case) and o are not used on notation for clarity reasons) i O

St. Lucie Plant ODCM Controls

Pcge 53 of 181 i

f ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 f)(

QFFSITE DOSE CALCULATION MANUAL (ODCM) -

o, TABLE 3.12-2 1

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS -

1 IN ENVIRONMENTAL SAMPLES l

L REPORTING LEVELS -

L AIRBORNE WATER PARTICULATE FISH MILK ANALYSIS PRODUCTS pCl/l OR GAS,ES pCi/kg, wet pCi/l pCl/kg, wet l-H3 30,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 j

Zn-65 300 20,000 400 N -95".

l-131 2"

0.9 3

100 1

(

Cs-134 30 10 1,000 60 _,

1,000 Cs 137 50 20 2,000 70 2,000 i

Ba-200 300 l

La-140",

l I

I as in pCl/l denotes liter l

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

i Applies to drinking water pathway exists,2 pCi/l is the limit for drinking water.

L An equilibrium mixture of the parent daughter isotopes which corresponds to the l

reporting value of the parent isotope.

l

)

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St. Lucie Plant ODCM Controls H-'

'd.li.

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Pcge 54 of 181 ST. LUCIE PLANT -

/ _

CHEMISTRY OPERATING PROCEDURE NO. C-200,' REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

~' ~

TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 0M4 i

LOWER LIMIT OF DETECTION (LLDf*

AIRBORNE WATER PARTICULATE FISH MILK SEDIMENT ANALYSIS PRO UCTS L

pCi/l OR GAS,ES pCl/kg, wet pCi/l PCl/kg, dry Ci/kg, wet Gross Beta 4

0.01 H-3 3000*

i Mn-54 15 130

.Fe-59 30 260 Co-58, 15 130 Co-60 Zn-65 30 260 Zr-95, 15 Nb-95<y i

l-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-140<y No drinking water pathway exists, a value of 2000 pCi/l is for drinking water.

LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis rnay be used.

I l

t St. Lucie Plant ODCM Controls

[

Prge 55 cf 181 a

ST. LUCIE PLANT

. CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 4.12-1 (Continued) l TABLE NOTATIONS i

i (1): This list does not mean that only these nuclides are to be considered.. Other peaks f

' that are identifiable, together with those of the above nuclides, shall also be analyzedi and reported in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.

i

~(2)

Required detection capabilities for thermoluminescent dosimeters used for l

environmental measurements are given in Regulatory Guide 4.13.

'(3)' The LLD is defined for purposes.of these controls, as the smallest concentration' of

[

radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding i

that a blank observation represents a real signal.

l

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

i l

.4.66 S*

LLD =

O E. V e 2.22. Y. exp (- A. A7) j Where:

i LLD =

the a priori lowor limit of detection (pico-Curie per unit mass or volume),

i S,

the standard deviation of the background counting rate or of the counting.

=

rate of a blank sample as appropriate (counts per minute),

E the counting efficiency (counts per disintegration),

=

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

1

=

2.22 ~ =

the number of disintegrations per minute. per pico-Curie, j

Y the fractional radiochemical yield, when applicable,

=

the radioactive decay constant for the particular radionuclide (sec) and '

l A.

=

AT the elapsed time between the midpoint of sample collection and the time

=

of counting (sec).

/

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

St. Lucie Plant ODCM Controls

i t

V

<y P ge 56 of 181 1

^

ST. LUCIE PLANT-CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

, ]:

OFFSITE DOSE CALCULATION MANUAL (ODCM) -

b

-TABLE 4.12-1 (Continued) -

TABLE NOTATIONS (Continued)'

It 'ahould be recognized that the LLD is dehned as' an a g!jed (before ti.e fact)' limit representing the capability of a measurement system and not as an a posteriori (after.

the fact) limit for a particular measurement. ' Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally.

background fluctuations, 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 pCiApe4 of the parent isotope.

O r

O St. Lucie Platit ODCM Controls J

. ~..

1 Pige 57 cf 181 -

ST. LUCIE PLANT l

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)-

RADIOLOGICAL ENVIRONMENTAL MONITORING j

i 3/4.12.2 LAND USE CENSUS CONTROLS l

3.12.2 in accordance with'St. Lucie Plant TS 6.8.4.g.2), a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each 'of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden

• of greater than 50 square meters (500 square feet) producing broad leaf vegetation.

- APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control ~

-l 4.11.2.3, pursuant to Control 3.11.2.6, identify the new location (s) in the next l

Annual Radioactive Effluent Release Report.

-j 1

b. With a Land Use Census identifying a location (s) that yields a calculated dose or -

dose commitrnent (via the same exposure pathway) 20% greater than at a location j

from which samples are currently being obtained in accordance with Control 3.12.1, j

add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the ' control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant

{

to TS 6.14, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change f

in sampling locations.

j Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Os 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.

-)

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St. Lucie Plant ODCM Controls f

Pcge 58 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

n.,

OFFSITE DOSE CALCULATION MANUAL (ODCM)

L/-

t RADIOLOGICAL ENVIRONMENTAL MONITORING 3!4.12.2 LAND USE CENSUS (Continued)

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 rnonths using that information that will provide the best results, such as by a door-to-door survey, aerial survey or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 3.12.4.

f l

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St. Lucie Plant ODCM Controls

PJge 59 of 181 -

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

- OFFSITE DOSE CALCULATION MANUAL (ODCM) n RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS

/

3.12.3 in accordance with St. Lucie Plant TS 6.8.4.g.3), analyses shall be performed on all radioactive materials, supplied as part of an interiaboratory Comparison Program that has been approved by the Commission *, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective action I

taken to prevent a recurrence to the Commission in the Annual Radiological L

Environmental Operating Report pursuant to Control 3.12.4.

~

1 O

. SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required interlaboratory l

Comparison Program shall be included in the Annual Radiological Environmental Operating

- Report pursuant to Control 3.12.4. If the interiaboratory Comparison Program is other than the program conducted by the EPA, then the Interlaboratory Comparison Program shall be.

described in the ODCM.

I This condition is satisfied by participation in the Environmental Radioactivity Laboratory intercomparison Studies Program conducted by the Environmental Protection Agency (EPA).

o l

St. Lucie Plant ODCM Controls m

-__-_.____:___m_____._.______.--_________.

Page 60 of 181

= ST. LUCIE PLANT '

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

.QEESIIE QQS.E_G&GVLATION MANUAL (ODCM) e RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.4

- ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREORP u

_ ADMINISTRATIVE CONTROLS E

3.12.4 in accordance with St. Lucie Plant TS 6.9.1.8, an Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations and information based on trend analysis of the results of the Radiological Environmental Monitoring Program for the reporting period. The material

- provided in the AREOR shall be consistent with the objectives outlined below and with Sections IV.B.2, IV.B.3 and IV.C of Appendix l to 10 CFR Part 50.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations and information based on trend analysis of the results of the radiological l

environmental surveillance activities for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls and with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use census required by Control 3.12.2.

The Annual n diological Environmental _ Operating Reports shall include the' results of analysis of all radiological environmental samples and of all environmental. radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not l

available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps" covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of the interlaboratory Comparison Program, required by Control 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of -

all analyses in which the LLD required by Table 4.12-1 was not achievable.

t l

A single submittal may be made for multiple unit station.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

St. Lucie Plant ODCM Controls l

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U l-BASES for the CONTROLS AND-SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.

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INSTRUMENTATION BASES i

3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I

The radioactive liquid effluent instrumentation is provided to monitor and control, as i

applicable, the releases of radioactive materials in liquid effluent during actual or potential l

releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM j

to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General i

Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50.

j 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as

[

applicable, the releases of radioactive materials in gaseous effluent during actual or potential j

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 i

to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The

{

OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50.

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• K) 3/4.11 l

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RADIOACTIVE EFFLUENTS-

-BASES 3/4.11.1 LIQUID EFFLUENTS i

J 13/4.11.1.1 CONCENTRATION i

l This control is provided to ensure that the concentration of radioactive _ materials j

released in liquid waste effluents to UNRESTRICTED AREAS will be less than the h

concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section ll.A design 1

objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits l

of 10 CFR Part 20. The concentration limit for dissolved or entrained noble gases is based I

-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 j

described in intomational Commission on Radiological Protection (ICRP) Publication 2.

/R15 l

i This control applies to the release of radioacthre materials in liquid effluents from all l

i units at the site.

e The required detection capabilities for radioactive materials in liquid waste samples are j

tabulated in terms of the lower limits of detection (LLDs).~ Detailed discussion of the LLD-and other detection limits can be found in Currie, LA., Lower Limit of Detection: Definition 1

and Elaboration of a Proposed Position for Rar!hlogical Effluent and Environmental j

Measurements, NUREG/CR-4007 (September 1984) ad in the HASL Procedures Manual, j

4 HASL-300.

l i

e 3/4.11.1.2 DOSE j

This control is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Control implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the

operation of the facility will not result in radionuclide concentrations in the finished drinking l

water that are in excess of the requirements of 40 CFR Part 141. The dose calculation O

St. Lucie Plant ODCM Controls - Bases j

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~ ST. LUCIE PLANT 1 CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 f

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l 3/4.11 RADIOACTIVE EFFLUENTS (Continued)-

. BASES.

i 3/4.11.1' LIQUID EFFLUENTS (Continued)

I l

3/4.11.1.2' DOSE (Continued)'

methodology and parameters in the 'ODCM implement the requirements in Section Ill.A of

. Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational j

procedures based on models and data, such that the actual exposure of a MEMBER OF.

THE PUBLIC through appropriate pathways is.unlikely to be substantially underestimated.

- The equations specified in the ODCM for calculating the doses due to the actual release l

rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of y

Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, l

Appendix 1, Revision 1, October 1977 and Regulatory Guide 1.113, Estimating Aquatic l

Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of

{

. Implementing Appendix 1, April.1977.

3 "O

This control applies to the release of radioactive materials in liquid effluents from each j

V unit at'the site. For units with shared Radwaste Systems, the liquid 'offluents' from the

-l shared system are to be proportioned among the units sharing that system.'

j i

3M.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM l

The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the

.j environment. The requirement that the appropriate portions of this system be used when -

specified provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable'. '. This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix i to 10 CFR Part 50. The specified limits

'goveming the use of appropriate portions of the Liquid Radwaste Treatment System were j

specified as a suitab;e fraction of the dose design objectives' set forth in Section ll.A of i

Appendix I,10 CFR Part 50 for liquid effluents.

_j i

This control applies to the release of radioactive materials in liquid effluents from each

-l unit at the site. For units with shared Radweste Treatment Systems', the liquid effluents from l

the. shared system are to be proportioned among the units sharing that system.

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RADIOACTIVE EFFLUENTS L

BASES 3/4.11.2 GASEOUS EFFLUENTS l

3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose I

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 1. These j

limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to an annual average concentration exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20 (Subpart D of 10 i

CFR Part 20). For MEMBERS OF THE PUBLIC who may at times be within the SITE '

BO'JCARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low w wmpensate 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 l

gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or

~

beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid-dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.

/R15 L

l This control applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984) and in the HASL Procedures Manual, HASL-300.

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Pcge 66 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 O

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-O RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE - NOBLE GASES This control is provided to implement the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The control imp!sments the guides set forth in Section I.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materialin gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.

The Sunreillance Requirements 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.

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

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

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

3/4.11.2.3 DOSE -IOG,hE-131. LODINE-133. TRITIUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections 11.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive materialin gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. The ODCM calculational methods specified in the O

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. BASES 3/4.' 1.2.1 DOSE - NOBLE GASES (Continued) 1

'I 3/4.11.2.3' DOSE -IODINE-131. IODINE-133. TRITIUM AND RADIOACTIVE MATERIAL 1

IN PARTICULATE FORM (Continued) i Surveillance Requirements implement the requirements in Section Ill.A of Appendix l 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 j

appropriate pathways-is unlikely to be substantially underestimated.

The ODCM 1

calculational methodology and parameters for calculating the doses due to the actual release i

rates of the subject material are consistent with the methodology provided in Regulatory l

Guide 1.100, Calculation of Annual Doses to Man from Routine Releases of Reactor j

Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, j

Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric i

Transport and Dispersion of Gaseous Effluents in. Routine Releases' from Light-Water l

O Cooled Reactors, Revision 1, July 1977. These equations also provide for determining the l

actual doses based upon the historical average atmospheric conditions.. The release rate

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

j 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 1

effluents from the shared system are proportioned among the units sharing that system.

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Ptge 68 cf 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

RADIOACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM I

The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous o

effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix l to 10 CFR Part

50. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10 CFR Part 50 for gaseous effluents.

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

3/4.11.2.5 NOT USED 3/4.11.2.6 NOT USED 3/4.11.3 NOT USED 3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 10 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1,and if direct radiation doses from the units (it.cluding outside storage tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation O

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RADIOACTIVE EFFLUENTS

' BASES' 3/4.11.4 TOTAL DOSE (Continued) l of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

i For the purposes of the Special Report, it may be assumed that the dose commitment to the i

MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered. If the dose to any MEMBER OF THE i

PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report l

with a request for a variance (provided the release conditions resulting in violation of l

40 CFR Part 190 have not already been corrected), in accordance with the provisions of l

40 CFR 190.11 and Subpart M of 10 CFR Part 20, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 -

and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any j

period in which he/she is engaged in carrying out any operation that is part of the nuclear i

fuel cycle.

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"3/4.12

' RADIOLOGICAL ENVIRONMENTAL MONITORING 1

' BASES

.h F

3/4.12.1 MONITORING PROGRAM i

The Radiological Environmental Monitoring Program required by this control provides~

i representative measurements of radiation and of radioactive materials in those exposure.

pathways and for those radionuclides that lead to the highest potential radiation exposure

~

of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program

.j implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations i

of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

7 Guidance for this monitoring program is provided by the Radiological Assessment Branch l

Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially.

j specified monitoring program will be effective for at least the first three years of commercial '

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

O The required detection capabilities for envir nmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required-by Table 4.12-1 are.

Li considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an g oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after tha fact) limit for a particular measurement.

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

i Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological i

Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984) and in the HASL Proceduros Manual, HASL-300.

t 3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in th' use of areas at and beyond the l

SITE BOUNDARY are identified and that modifications ta the Radiological Environmental

~

Monitoring Program given in the ODCM are made if required by the results of this census.

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

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BASES i

3/4.12.2 LAND USE CENSUS (Continued) j This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.'

. Restricting the census to gardens of greater than 50 square meters provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a t

garden of this size is the minimum required to produce the quantity (26 kilograms / year) of '

leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To j

' determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and (2) a vegetation yield of 2 kilograms per square meter.

.i 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This requirement for participation in an approved interlaboratory Comparison Program j

'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 I

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.

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METHODOLOGY SECTION l

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h METHODOLOGY l

for the f

CONTROLS AND-SURVEILLANCE REQUIREMENTS I

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METHODOLOGY SECTION a

~ GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION 1

i l

Dose from Beta' Radiation 10.

CC or oc

- Cubic centimeter l

Cl

- Curies - a unit of radioactivity see Ci.

j Activity or concentration of a nuclide in the release source." Units -

C, of Cl, pCi/cc or Ci/mi j

Code of Federal Regulations CFR Regulations for operating, controlling, monitoring and reporting l

Control (s) radioactive effluent related activity as indicated by the Controls j

Section of the ODCM. -

i I

The exposure, in mrem or mrad, the organ or the individual

{

Dose-

- receives from radioactive effluents j

O.

i Normally, a factor that converts the effect of ingesting radioactive Dose Factor material into the body, to dose to a specific organ. Body j

elimination, radioactive decay and organ uptake are some of the l

factors that determine a dose factor for a given nuclide A specific path that radioactive material physically travels through' Dose Pathway prior to exposing an individual to radiation. The Grass-Cow-Milk-Infant is a dose pathway The dose received per unit time Dose Rate A long term D over O - a factor.with units of 1/m" which describes.

(D/O) the deposition of particulate' matter from a plume at a point -

downrange from the source. It can be thought of as what part of the cloud is going to fallout and deposit over one square meter of ground. (See Appendix F).

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Effluent Concentration Limit

/R15 ECL

'FUSAR Final Updated Safety Analysis Report, O

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Q METHODOLOGY SECTION.

GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION j

(continued).

j 1

Ye

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

i Radioactive material deposited uniformly over the ground emits

[

Ground Plane radiation that produces an exposure pathway when an individual is standing, sitting, etc., in the area.- it is assumed that an adult j

receives the same exposure as an infant, regardless of the l

physical height differences. Only the whole body is considered for the ODCM..

(

H-3 Hydrogen-3 or Tritium, a weak Beta emitter Radiolodines and particulates with half-lives greater than 8 days l&BDP 8

' Cubic Meters m

-i Square Meters m

~/R15 For the purposes of this manual, a radioactive isotope. Nuclide nuclide (i) signifies a specific nuclide, the 1st, 2nd, 3rd one under -

l consideration. If nuclide (i) is 1-131, then the Mi (dose factor) 1 under consideration should be M,.,3, for example.

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

of writing the methodology in the ODCM.

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

l pCl (O Dot), - Denotes a release rate in pCi/sec for nuclide (i).

l (O Dot),

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

Q, lodine-131 and lodine I-133 for gaseous release pathways.

)

Radiolodines i

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Page 75 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 O

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b METHODOLOGY SECTION GLOSSARY OF COMMONLY USED TERMS IN METHODOLOGY SECTION-(continued) r

' Receptor The individual receiving the exposure in a given location or who ingests food products from an animal for example. A receptor can receive dose from one or more pathways.

Release Sou :e(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 4

Ci micro Curies.1 Cl = 10 Curies. The Ci is the standard unit of radioactivity for all dose calculations in the ODCM.

(X/O)

A long term Chi over O. It describes the physical dispersion pd characteristics of a semi-infinite cloud of noble gases as the cloud traverses downrange from the release point.,Since Noble Gases are inert, they do not tend to settle out on the ground. (See Appendix F).

(X/O)o A long term Depleted Chi over O. It describes the physical dispersion characteristics of a semi-infinite cloud of radioactive iodines and particulates as the cloud travels downrange. Since lodines and particulates tend to settle out (fallout of the cloud) on the ground, the (X/O)o represents what physically remains of the cloud and its dispersion qualities at a given location downrange from the release point. (See Appendix F).

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

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METHODOLOGY SECTION 3

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JQ METHODOLOGY SECTION u

1.1! Radioactive Liould Effluent Model Assumptions

' The FUSAR contains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes:

The St. Lucie Plant is located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean.

Normally, all radioactive liquid releases enter the Atlantic Ocean where the Circulating Water Discharge Pipe terminates on the ocean floor at a pcint I

approximately 1200 feet offshore. No credit is taken for subsequent mixing of the discharge fiume with the ocean. The diffusion of radioactive material into -

the ocean is dependent on the conditions of tide, wind and some eddy currents caused by the Gulf Stream. The conditions are sufficiently random l

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 p

an emergency supply of circulating. water to the intake Cooling Water Canal in

?

d the event a Hurricane causes blockage of the Intake Car;al. No radioactive j

water could be discharged directly into the intake Cooling Water Canal j

because all plant piping is routed to the discharge canal and no back flow can occur. Consult the FUSAR for a detailed description of characteristics of the water bodies surrounding the plant site.

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

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OFFSITE DOSE CALCULATION MANUAL (ODCM)

METHODOLOGY SECTION L1.2 Determinina the Fraction F of 10 CFR Part 20 ECLs Umits for A Liould Relee==

q Source _

1 Discussion - Control 3.11.1.1 requires that the sampling and analysis results 'of j

liquid waste (prior to discharge) be used with calculation methods in the in-plant j

procedures to assure that the concentration of liquid radioactive material in the i

unrestricted areas will not exceed ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2. Chemistry Procedure C-70 " Processing Aerated Liquid Waste" provides instruction for ensuring batch release tanks will be sampled after adequate mixing. This section presents the calculation method to be used for i

this determination. This method only addresses the calculation for a specific release source. The in-plant procedures will provide instructions for determining l

that the summation of each release source's F values do not exceed the site's 10 CFR Part 20 ECL. The values for release rate, dilution rate, etc., will also have to l

be obtained from in-plant procedures. The basic equation is, i

n C'

i F,, = _R

E i

D f1 (ECL),

Where:

F the fraction of 10 CFR Part 20 ECL that would result if the

=

t release source was discharged under the conditions specified.

j R

The undiluted release rate in gpm of the release source.

=

Liquid Rad Waste = 170 gpm j

Steam Generator = 125 gpm/ Steam Generator i

The dilution flow in gpm of Intake Cooling Water or Circulating i

D

=

Water Pumps l

Intake Cooling flow is 14,500 gpm/ pump j

Circulating Water flow is 121,000 gpm/ pump j

C, The undiluted concentration of nuclide (i) in pCi/mi from sample

=

assay (ECL),

The Effluent Concentration Limit of nuclide (i) in Ci/mi from

=

i Table L-1. For dissolved or entrained noble gases the ECL value is 2 X 10" pCi/ml for the sum of all gases.

/R15 l

i

\\

I

i PIge 79 of 181.

j ST. LUCIE PLANT:

' CHEMISTRY OPERATING PROCEDURE.C-200, REVISION 15 j

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METHODOLOGY SECTION 1.2'. (continued)

The fraction of the 10 CFR Part 20 ECL limit may be determined by a nuclide-by-nuclide' evaluation or for purposes of simplifying the calculation by a cumulative activity evaluation. if the simplified method is used, the value of 3 X 10* Ci/ml (unidentified ECL value) should be substituted for (ECL), and the -

1 cumulative concentration (sum of.all identified radionuclide concentrations) or the gross concentration should be substituted for C,. As long as the diluted l

concentration (C. R/D) is less than 3 X 10* Ci/ml, the nuclide-by-nuclide calculation is not required to demonstrate compliance with the 10 CFR Part 20 ECL.

The following section provides a step-by-step procedure for determining the ECL fraction.

3 1.

Calculation Process for Solids A. Obtain from the in-plant procedures, the release rate value (R) in gpm for the release source.

j t

B.

Obtain from the in-plant procedures, the dilution rate (D) in gpm. No credit is taken for any dilution beyond the discharge canal flow.

C. Obtain (C,), the undiluted assay value of nuclide (i),16 Ci/mi. If the t

simplified method is used, the cumulative concentration (Ctotal) is used.

D.

From Table L-1, obtain the corresponding (ECL) for nuclide (i) in pCl/ml.

The value of 3 X 10* Ci/mi should be used for the simplified method.

l E.

Divide C; by (ECL), and write down the quotient F.

If the simplified method is used, proceed to the next step. If determining the ECL fraction by the nuclide-by-nuclide evaluation, repeat steps 1.2.1.C through 1.2.1.E for each nuclide reported in the assay, for H from previous l

3 month composite and for SRB 9/90 and Fe55 from previous quarter composite.

/R15 O

4 l

t I

t

Pcge 80 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 T.

_OFFSITE DOSE CALCULATION MANUAL (ODCM)

(Q METHODOLOGY SECTION (1.2 (continued) 1.

(continued)

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

t R

C, F=R E

t D f.1 (ECL) /

F = a unit-less value where:

t the value of F could be s or >1. The purpose of the calculation is to e

determine what the initial value of F is for a given set of release t

conditions.

H. The F value just obtained is for one release pathway. The TS and ODCM t

control 3.11.1.1 allow for a site limit of F less than or equal to 10.

o Chemistry Procedure C-70 administrativly controls each pathway's m

allocation. Compare your F result with the administrative control for the o

release pathway in C-70.

2.

Calculation Process for Gases in Liquid 4

A.

Sum the Cl/mi 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:

y*, (sum of 1.2.2.A) pCilml y _R 1

D C.

F, shall be less than 2 X 10" Ci/mi for the site for all releases in progress.

Each release point will be administratively controlled. Consult C-70 procedure for instructions.

/R15 l

I J

j

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P;ge 81 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 M-OFFSITE DOSE CALCULATION MANUAL (ODCM)

(

METHODOLOGY SECTION

.1.3 Determinina Setpoints for Radioactive Liouid Effluent Monitors Discussion - Control 3.3.3.10 requires that the liquid effluent monitoring instrumentation alarm / trip setpoints be set to initiate an alarm or trip so that the radioactivity concentration in water in the unrestricted area does not exceed the concentration of 10 CFR Part 20, Appendix B, Table 2 as a result of radioactivity in liquid effluents (Control 3.11.1.1). This section presents the method to be used for determining the instrumentation setpoints.

Gross epm vs. total liquid activity curves are available for Liquid Effluent Monitors i

l based on a composite of real release data. A direct correlation between gross epm I

and the concentrations that would achieve 10 CFR Part 20 ECL levels in the discharge canal can be estimated. The 1978 liquid release data from annual reports was used to determine the average undiluted release concentration. These concentrations were then projected to a diluted concentration in the discharge canal assuming a 1 gpm release rate and a constant dilution flow of 121,000 gpm from 1 circ. water pump. This diluted activity was divided by the nuclide's respective 10 CFR Part 20 ECL value (Table L-1) to obtain the Mi column on the table that i

follows:

' O

/R15 l

l

P:ge 82 of 181'

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METHODOLOGY SECTION q

'1.3 (continued)

TABLE 1.3 NUCLIDE SYMBOL 1978 UNDILUTED pCi/mi' M,'(no units) l l-131 4.43 E-5 3.66 E-4 l

1-132

. 2.23 E-7 1.84 E4

,l

- l-133 3.17 E 3.74 E-6 l'

1-135.

1.31 E-6 3.61 E-7 l

l Na-24 1.72 E 2.84 E-8 l

Cr-51 2.51 E 5 4.15 E-7

.l Mn-54 5.64 E-6

.1.55 E-6 l

Mn-56 1.11 E-9 1.31 E-10

.l Co-57 3.69 E-7 5.08 E-8 l

l Co-58 1.51 E-4 6.24 E-5 l

i Fe-59 2.92 E 2.41 E-6 l

f Co-60 3.66 E-5 1.01 E-4 l

[

Zn 4.55 E 7 7.52 E-7 l

Ni-65 8.23 E-7 6.8 E l Ag-110 1.96 E-6 2.70 E-6 l

Sn-113 5.75 E-7 1.58 E-7,

l l

Sb-122 2.15 E-6 1.78 E-6 l

Sb-124 8.40 E-6

-9.92 E-6..

l l

W 187 3.51 E-6 9.67 E-7 l

Np-239 1.57 E 7 6.49 E-8 l

t Br-82 3.64 E-7 7.52 E-8 l

'l' Zr-95 2.82 E-5 1.17 E-5 l

Zr-97 4.05 E-6 3.72 E-6 l

t Mo-99 3.24 E-6 1.34 E-6 l

l Ru 103 3.84 E-8 1.06 E-8 l

Sb-125 2.26 E-6 6.23 E l Cs 134 2.14 E-5 1.97 E-4 l

Cs 136 7.82 E-7 1.08 E-6 l

l Cs-137 4.85 E-5 4.01 E-4 l

Ba 140 6.44 E-7 6.65 E-7 l

Ce 141 3.04 E 8 8.38 E-9 l

Ce-144 2.37 E-6 6.53 E-6 A.=

4.01 E-4 Mg 1.18 E-3 (1) 1978 Undiluted Release Volume = 7 E 9 ml.

O g,1978 Undil. Act Nuclide (i) y 1 gptn (release rate)

%5 ECL, (from 7able L-1) 121000 gpm (dil rate) i

Pcge 83 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 r

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(q).

METHODOLOGY SECTION 1.3 (continued)

Am is the total average Cl/mi concentration of the reference mixture and M is a

the fraction of the MPC of all nuclides for the release conditions specified. Dividing Am by Mm yields A, which is the maximum total activity concentration equivalent to the ECL limit for the nuclide distribution typical of radwaste discharges. The Technical Specifications allow 10 times the ECL limit where the Site Limit is 10 times A% as follows:

m, 4.01 E-4 = 0.34 yCUml = ECL Limit Au,M 1.18 E-3 m

Site Limit = 10 x A% = 10 x 0.34 = 3.4 pCi/mi To provide conservative administrativ ontrol, A of 0.34 Ci/mi should be used m

as follows:

1.

If the effluent monitor requires counts per minute units, a (C.) value in cpm

. should be obtained for the A, (0.34 Ci/ml) from the release sources m

radioactive liquid effluent monitor curve of cpm vs. pCi/ml.

.N_OTE This setpoint is for a specified release of 1 gprn into 121000 gpm dilution flow.

2.

For establishing the setpoint prior to liquid radwaste discharges, the A,

m (orOm) will be adjusted as needed to account for actual release conditions (i.e., actual design maximum discharge flow rate, dilution flow rate and the contribution of dissolved and entrained Nobles Gas Activity to the Monitor Activity Level).

j i

1.4 Determinina the Dose for Radioactive Liauid Releases Discussion - Control 3.11.1.2 requires calculations be performed at least once per 31 days to verify that cumulative radioactive liquid effluents do not cause a dose in excess of 1.5 mrem to the whole body and 5 mrem to any organ during any calendar quarter and not in excess of 3 mrem to the whole body and 10 mrem to any organ during any calendar year. This section presents calculational method to be used for this verification.

/R15

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~ 1.4 (continued)

This method is based on the methodology suggested by sections 4.3 and 4.3.1 of

t NUREG-0133 Revision 1, November,1978. The dose factors are a composite of both the fish and shellfish pathways so that the fish-shellfish pathway is the only pathway for which dose will be calculated. For St. Lucie Plant, the adult is the most limiting age group, but the dose for child and teenager can also be calculated by.

c

. this method provided that their appropriate dose factors are available for the organ of interest. Only those nuclides that appear in the Tables of this manual will be

(

considered.

i L

1.

This method provides for a dose' calculation to the whole body or any organ for-h:

a give,n age group based on real release conditions during a specified time '

interval for radioactive hquid release sources. The equation is:

D,' = A dt, O ir n

(DF),

Where:

D, dose commitment in mrem received by c. gan T of age group (to

=

T be specified) during the release time interal dt,.

the composite dose factor for the fish-shellfish pathway for nuclide Ay

=

(i) for organ T of age group (to be specified). The Ay values listed in the Tables in this manual are independent of any site specific information and have the units mrem-ml Cl-hr the number of hours that the release occurs.

dt,

=

Q, The total quantity of nuclide (i) release during dt, ( Ci)

=

(DF),

The total volume of dilution that occurred during the release time

=

period dt, (i.e., the circulating water flow times time)

)

i i

O l

- Pcge 85 of 181 1

. ST. LUCIE PLANT '

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b' CHEMISTRY, OPERATING PROCEDURE C-200, REVISION 15 I

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OFFSITE DOSE CALCULATION MANUAL (ODCM) 1 3

METHODOLOGY SECTION f

1.4..(continued) 1.-

(continued)-

The doses associated with each release may then be summed to provide the l

~

_ cumulative dose over a desired time period (e.g., sum all doses for release i

during a 31 day period, calendar quarter or a year).

1 D., = I D,,

Where:

1 the total dose commitment to organ 7 due to all releases during the Dr

=

T desired time interval (mrem) i Based on the radionuclide distribution typical in radioactive effluents, the ~

i calculated doses to individuals are dominated by the radionuclides Fe-59, Co-58, Co-60, Zn-65, Nb-95, Cs-134 and Os-137. These nuclides typically j

contribute over 95% of the.whole body dose and over 90% of the GI-LLI dose, _

j which is the critical organ. Therefore, the dose commitment due to radioactivity

-j in liquid effluents may be reasonably evaluated by lindting_the dose calculation j

process to these radionuclides for the adult whole body and adult GI-LLI. To 1

allow for any unexpected variability in the radionuclide distribution, a.

i conservatism factor of 0.6 is introduced into the equation. - After calculating the j

dose based on these 7 nuclides, the cumulative dose should be divided by 0.6, l

the conservatism factor. (i.e., Di= D/0.6)._ Refer to Appendix B for a detailed j

evaluation' and explanation of this limited analysis approach.

. The methodology that follows is a step-by-step breakdown to calculate doses

(

based on the above equation.' Refer to the in-plant procedures to determine the applicable organs, age groups and pathway factors._ If the limited analysis -

approach is used, the calculation should be limited to the Adult whole body i

dose and Adult GI-LLI dose from the, fish and shellfish pathways. - Only the 7 previously specified radionuclides should be evaluated. For the dose i

calculations to be included in annual reports, the doses to the adult groups and j

all organs should be evaluated for all radionuclides identified in the liquid effluents.

l l

O 1

P ge 86 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 y

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_ f'f

\\_

METHODOLOGY SECTION j

1.4 (continued) 1.

(continued)

NOTE Table 1.4 provides a convenient form for compiling the dose accounting.

A.

Determine the time interval dt, that the release took place. The in-plant procedures shall describe the procedure for calculating dt, for offcial release purposes.

B.

Obtain (DF), for the time period dt, from Liquid Waste Management Records for the release source (s) of interest.

C. Obtain Q,i for nuclide (i) for the time period dt, from the Liquid Waste Management Records D. Obtain A from the appropriate Liquid Dose Factor Table i

y O

1 h

r I

' O

P*ge 87 of 181 1

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

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^

q s

(f METHODOLOGY SECTION 1.

i 1.4 (continued) i 1.

(continued)

TABLE 1.4 FISH AND SHELLFISH PATHWAY TIME /DATE START:

. __]

/

TIME /DATE STOP:

/

/

HOURS

. TOTAL DILUTION VOLUME:

mis AGE GROUP:

ORGAN:

DOSE FACTOR TABLE #:

NUCLIDE (i)

C, ( Ci)

An DOSE (i) mrem Fe-59 Co-58 I

Co-60 Zn-65 i

Nb-95 Cs-134 Cs-137 OTHERS j

i 6

i l

i TOTAL DOSE 7=

mrem if based on limited analysis, divide by 0.6 mrem -

E.

Solve for Dose (i)

Dose (1) =

(DF),

t l

h,,

~

P ge 88 of 181'-

~

ST. LUCIE PLANT-

- CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 Ny>

OFFSITE DOSE CALCULATION MANUAL (ODCMF "Q

METHODOLOGY SECTION f

I1.4 (continued)

I$~

1.

{ continued)

^

p

?'

F.

Repeat steps 1.4.1.C through 1.4.1.E for each nuclide reported and each h

organ required. If the limited analysis method is used, limit the -

1 tV radionuclides to Fe-59, Co-58, Co-60,2n-65, Nb-95, Cs-134 and Cs-137.

and determine the adult whole body dose and the adult GI-LLI dose.

h G.-

Sum the Dose (i) values to obtain the total dose to organ T from the fish-'

shellfish pathway. If the limited analysis method is being used, divide the

. cumulative dose by a conservatism factor of 0.6 to account for any unexpected variability in radionuclide distribution y

f.-

L 1.5 Projectina Dose for Radioactive Liauid Effluents Discussion - Control 3.11.1.3 requires.that appropriate subsystems of the liquid.

l radwaste treatment system be used to reduce radioactive material in liquid effluents when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see TS Figure 5.1-1) would exceed 0.06 mrom to the O

whole body or 0.2 mrem to any organ in a 31 day period. The following calculation method is provided for performing this dose projection. The rhethod is based on a

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

j 1.

Obtain the latest result of the monthly calculation of the adult whole body dose and the adult's highest organ dose. These doses can be obtained from the i

in-plant records.

1 2.

Divide each dose by the number of days the reactor plant was operational p

during the month, i

3.

Multiply the quotient of each dose by the number of days the reactor plant is 1

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.

I 4.

If the projected dose is greater than 0.06 mrem to the whole body or greater than 0.2 mrom to the adults highest exposed organ, the liquid radwaste system shall be used.

O

Page.89 of 181-4

' ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 3r OFFSITE DOSE CALCULATION MANUAL (ODCM) t k,j-METHODOLOGY SECTION -

I t

I 2.0 GASEOUS RELEASES METHODOLOGY 1

~

O 9

Il I

l O

l o

Pzgo 90'of'181 -

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM).

METHODOLOGY SECTION

~ 2.1 Gaseous Effluent Model Assumptions Description of Site - (The FUSAR contains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes only). The St. Lucie Plant is located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean.

L Private property adjoins the plant site in the north and south directions. A p

meteorological tower is located north of the plant near the site property line. There are 16 sectors, for dose calculation purposes, divided into 22.5* each. The MET u

tower is calibrated such that a zero degree bearing coincides with TRUE NORTH.

A bearing of zero degrees dissects the north sector such that bearings of 348.75*

and 11.25 define the boundaries of the north sector. The nearest distance to private property occurs in the north sector at approximately 0.97 miles. For ease of calculation, this 0.97 mile radius is assumed in all directions, although the real Unrestricted Area Boundary is defined in Figure 5.1-1 of the TS. Doses calculated over water areas do not apply to Controls or the annual report and may be listed as O.W. (over water) in lieu of performing calculations. The 0.97 mile range in the NW sector is O.W., but it was chosen as the worst sector for conservative dose calculations using the historical MET data.

Historical MET Data - MET data, between September 1,1976 and August 31,1978, from the St. Lucie MET Tower was analyzed by Dames & Moore of Washington, D.C. The methodology used by Dames & Moore was consistent with methods suggested by Regulatory Guide 1.111, Revision 1. Recirculation correction factors were also calculated for the St. Lucie Site and are incorporated into the historical MET tables (Tables M5, M6 and M7) in Appendix A of this manual. It was determined that these two years are representative data for this locale.

Dose Calculations - Dose calculations for Control dose limits are normally calculated using historical MET data and receptor location (s) which yield calculated doses no lower than the real location (s) experiencing the most exposure. Actual MET data factors are calculated and used in dose calculations for the annual reports.

l-Live MET data and hour-by-hour dose calculations are beyond the scope of this manual. Historical information and conservative receptor locations, etc., are only used for ease of Control dose limit calculations. Dose calculations for Control dose limits may be performed using actual MET data and real receptor locations. Any dose calculations performed with actual data should note the source of the data in the annual report. Actual MET data reduction should be performed in accordance with Regulatory Guide 1.111, Revision 1 and should incorporate Recirculation Conection Factors from Table M-4 of this manual.

t

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CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

E METHODOLOGY SECTION

. 2.1 (continued)

Dose Calculations - (continued)

The St. Lucie site uses the long term ground release model for all gaseous effluents. Only those radionuclides that appear in the gaseous effluent dose factor

tables will be considered in any dose calculations. Radioiodines are defined as lodine-131 and 1-133 for application to Controls. Other nuclides of lodine may be.

included in dose calculations for ease of performing calculations, but their dose contribution does not have to be included in the Control requirements. Land

{

Census information will apply to the calendar year following the year that ttie -

l census was taken in to avoid splitting quarters, etc.

2.2 Determinina the Total Body and Skin Dose Rates for Noble Gas Releases And Establishina Setooints for Effluent Monitors Discussion - Control 3.11.2.1 limits the dose rate from noble gases in airbome '

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 l

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 theselimits.

The following calculation method is provided for determining the dose rates to the total body and skin from noble gases in airbome releases. The alarm / trip setpoints are based on the dose rate calculations. The Controls apply to all airbome releases on the site but all releases may be treated as if discharged from a single release point. Only those noble gases appearing in Table G-2 will be considered.

The calculation methods are based on Sections 5.1 and 5.2 of NUREG-0133,-

November 1978. The equations are:

For TOTAL BODY Dose Rate:

n

'DRni " E K (MO) (O DO7),

i i

For TOTAL SKIN Dose Rate:

n DR,, = E \\L, + 1.1 M) (XIO) (Q DOT),

a O

/R15

Pag 3 92 of 181 l

l ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) 9 METHODOLOGY SECTION 2.2 (continued)

Where:

DRrs

= total body dose rate from noble gases in airbome releases (mrem /yr) /R15 DR.

= skin dose rate from noble gases in airbome releases (mrem /yr) 3;

= a mathematical symboi to signify the operations to the right of I

the symbol are to be performed for each noble gas nuclide (i) through (n) and the individual nuclide doses are summed to arrive at the total dose rate for the release source.

K,

= the total body dose factor due to gamma emissions for each noble l

8 gas nuclide reported in the release source. (mrem-m /pCi-yr)

/R15 4

L,

= the skin dose factor due to beta emissions for each noble gas nuclide

~

8 (i) reported in the assay of the release source. (mrem-m /pCi-yr) g M,

= the air dose factor due to gamma emissior's for each noble gas nuclide (i) reported in the assay of the release source. The constant 1.1 converts mrad to mrem since the units of M, are in 8

(mrad-m / Ci-yr)

(X/Q)

= for ground level, the highest calculated annual long term historic relative concentration for any of the 16 sectors, at or beyond the 8

exclusion area boundary (sec/m )

(O DOT), = The release rate of noble gas nuclide (i) in Ci/sec from the release source of interest 1.

Simplified Total Body Dose Rate Calculation

/R15 From an evaluation of past releases, an effective total body dose factor (K,n) can be derived. This dose factor is in effect a weighted average total body dose factor, i.e., weighted by the radionuclide distribution typical of past operation. (Refer to Appendix C for a detailed explanation and evaluation of K,n). The value of K,, has been derived from the radioactive noble gas erffluents for the years 1978,1979 and 1980. The value is:

/R15 8

mem-m 9

K*, = 6.8 X 102 pCi-yr

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?.2-(continued) ~

2 1.

(continued) '

This value may be used in conjunction with the total noble gas. release rate

- (O DOT), to verify that the dose rate is within the allowable limits. To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:

DR, =

I (Q DOT),

0.8

/R15 1

To further simplify the determination, the historical annual average 4

8 meteorological X/Q of 1.6 X 10 sec/m (From Table M-1) may be substituted into the equation. Also, the dose limit of 500 mrem /yr may be substituted for DRa. Making these substitutions yields a single cumulative (or gross) noble -

. gas release rate limit. This value is:

/R15 l

Noble gas release rate limit = 3.5 X 10 Ci/sec I

5 O

5 As long as the noble gas release rates do 'not exceed this value (3.5 X 10 Ci/sec), no additional dose rate calculations are needed to verify compliance with Control 3.11.2.1.

j.

1 1

u l

P ge 94 of 181 ST. LUCIE PLANT t..

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

[p OFFSITE DOSE CALCULATION MANUAL (ODC M)

,V METHODOLOGY SECTION 2.2' (continued)

L 2.

Setpoint Detem1ination To comply with Control 3.3.3.11, the alarm / trip setpoints are established to 5

4

' ensure that the noble gas releases do not exceed the value of 3.5 X 10 Ci/sec, which corresponds to a total body dose rate of 500 mrom/yr. The method that follows is a step-by-step procedure for establishing the setpoints.-

To allow for multiple sources of releases from different or common release points, the allowable operating setpoints will be controlled administratively by.

allocating a percentage of the total allowable release to each of the release l

sources.

/R15 h

A.

Determine (V) the maximum volume release rate potential from the in-plant I

procedures for the release source under consideration. The units of (V) j are ft'/ min.

B.'

Solve for A, the activity concentration in pCl/cc that would produce the '

l Y control dose rate Limit.

j p, 3.5 X 10' Cl min M sec y

y y

sec (V) It' 2.8317 X 10*cc min I

A = pCl/cc C.

Refer to the pCi/cc vs. cpm curve for the Release Source's Gaseous Effluent Monitor epm value (C), corresponding to the value of A above.

L

_ D. O is the 100% setpoint, assuming that there are no other release sources -

on the site.

E.

Obtain the current % allocated to this release source'from the gaseous waste management logs.

I.

uO I

}-

Prge 95 cf 181 '

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 -

YN OFFSITE DOSE CALCULATION MANUAL'(ODCM)

, (M METHODOLOGY SECTION j

T2.2 (continued)

2. -(continued)

]

F.

The Operating setpoint SP 1

% allotted by in-plant procedures SP = (C) cpm X 100 % -

The total body dose is more limiting than the calculated skin dose. (Refer p

to Appendix C for a detailed evaluation.) Therefore, the skin dose rate j

calculations are not required if the simplified dose rate calculation is used l

F (i.e., use of K, to determine release rate limits).

/R15 l

1 The calculation process of the following Section (2.2.3) is to be used if -

5 actual releases of noble gases exceed the above limit of 3.5 X 10 pCi/sec.

Under these conditions,'a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Control 3.11.2.1.

1 l

3.

Total Body and Skin Nuclide Specific Dose Rate Calculations'

/R15:

{

1 The following outline provides a step-by-step explanation of how the total body dose rate is calculated on a nuclide-by-nuclide basis to evaluate compliance l

with Control 3.11.2.1. This method is only used if the actual releases exceed

j 5

the value of 3.5 X 10 Ci/sec.

/R15 8

A.

The (X/O) value = -

sec/m and is the most limiting sector at the exclusion area. (See Table M-1 for value and sector.)

i i

8 B.

Enter the release rate in ft / min of the release source and convert it to:

-i

,(

)ft

- 2.8317 X 10'cc min j

8 y y

min ft*

60 sec i

cc/sec volume release rate

=

l o

l

.1

['

Page 96 of.181 ST. LUCIE PLANT -

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 f~X OFFSITE DOSE CALCULATION MANUAL (ODCM)

~U METHODOLOGY SECTION 2.2 (continued) 3.

(continued)

C. Solve for(Q DOT), for nuclide (i) by obtaining the Ci/cc assay value of the release source and multiplying it by the product of 2.2.3.B above.

(Q DOT), = (nuclide [i])

(assay)

Cl y (2.2.3.B value) cc cc sec (O DOT), =

Ci/sec for nuclide (i).

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

E.

Solve for DRr, ra = KjXIQ) (Q DO7), = M'**~*' X *** X Ci DR pCi-yr m

sec a

DRrs =

mrem total body dose from nuclide (i) for yr the specified release source F.

To evaluate the skin dose rate, obtain the L, and M, values from Table G-2 for nuclide (i).

G. Solve for DR.,,

DR

= [L + 1.1 MJ (X/O)(Q DOT),

i oni i

DR,n, = mrem skin dose from nuclide (i) for the yr specified release source

)

/R15 b

Prge 97 of 181 ST. LUCIE PLANT--

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 (W).

OFFSITE DOSE CALCULATION MANUAL (ODCM)

METHODOLOGY SECTION 2.2. (continued)

. 3.

(continued)

. H. Repeat steps 2.2.3.D through 2.2.3.G for each noble gas nuclide (i)-

reported in the assay of the release source.

1.

The Dose Rate to the Total Body from radioactive noble gas gamma t

radiation from the specified release source is:

n DR,=EDR,

7 rs I

J.

The Dose Rate to the skin from noble gas radiation from the specified release source is:

n DR, = E DRa, j

n The dose rate contribution of this release source shall be a'dded 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.

/R15 i

-l 4

I

Page 98 cf 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

' p OFFSITE DOSE CALCULATION MANUAL (ODCM)-

L()-

METHODOLOGY SECTION 2.3 Determinina the Radioiodine & Particulate Dose Rate to Any Oraan From Gaseous Releases Discussion - Control 3.11.2.1 limits the dose rate from I-131,1-133, tritium and all radionuclides in particulate form with half lives >eight days to s1500 mrom/yr to any

^

organ. The following calculation method is provided for determining the dose rate from radioiodines (see 2.1) and particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in NUREG-0133, November 1978. The Infant is the controlling age group in tha inhalation, ground plane and cow / goat milk pathways,

)

which are the only pathways considered for releases. The long term (X/O)o (depleted) and (D/O) values are based on historical MET data prior to implementing Appendix 1. Only those nuclides that appear on their respective table will be considered. ' The equations are:

For Inhalation Pathway (excludina H-3):

R DR,y,,

, {X/O)o (O DOT),

a O

For Ground Plane:

P DR,,,, = I f (D/0)(O D07),

I T

j For Grass-Cow / Goat-Milk:

n N

DR,.y, = I f (D/0)(O DO7),

r For Tritium Releases (Inhalation & Grass-Cow / Goat-Milk):

DR, = R[4_3, Mo (O DODu.,

m Normally should be Pi, but Ri values are the same, thus use Ri tables in 7

r r

Appendix A.

F Pzgo 99 of 181 l

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 :

OFFSITE DOSE CALCULATION MANUAL-(ODCM)

,O METHODOLOGY SECTION-2.3 (continued) 7 1

L For Total Dose Rate from I & 8DP and H-3 To An infant Oroan T:

DR *'z(DR,,? DRu) r

'Where-1 The organ of interest for the infant age group T

=

The applicable pathways z

=

I&8DPr Dose Rate in mrem /yr to the organ T from iodines and 8 day

'DR

=

particulates Dose Rate in mrem /yr to organ T from Tritium DR

=

g Total Dose Rate in mrem /yr to organ T from all pathways under DR

=

7 consideration A mathematical symbol to signify the operations to the right '

I

=

of the symbol are to be performed for each nuclide (i) through (n).

and the individual nuclide dose rates are summed to arrive at the total dose rate from the pathway.

A mathematical symbol to indicate that the total dose rate D I

=

7 Z

to organ T is the sum of each of the pathways dose rates-The dose factor for nuclide (i) for organ T for the pathway R,

=

specified (units vary by pathway)

I The dose factor for instantaneous ground plane pathway in units of P,

=

mrem-m' see Cl-yr O

i i

ll

~ ST. LUCIE PLANT '

l

' CHEMISTPY OPERATING PROCEDURE C-200, REVsSION 15 A. '.

OFFSITE DOSE CALCULATION MANUAL 10DCM) l L/ !,

METHODOLOGY SECTION 12.3. '(continued).

l

. From an evaluation of the radioactive releases and environmental pathways, the.

grass-cow / goat-milk pathway has been identified as the most limitir;g pathway with

. the infant's thyroid being the critical organ. This pathway typically contributes >90%

- of the total dose received by the infant's thyroid and the radioiodine contribute essentially all of this dose.-- Therefore, it is possible to demonstrate compliance with -

i

' the release rate limit of Control 3.11.2.1 for radioiodines and particulates by only evaluating the infant's thyroid dose for the release of radiolodines via the grass-

-l cow / goat-milk pathway. The calculation method of Section 2.3.3 is used for this

determination. If this limited analysis approach is used, the dose' calculations for h

other radioactive paniculate matter and other pathways need not be performed.

i Only the calculations of Section 2.3.3 for the radioiodines need be performed to l

demonstrate compliance with the Control dose rate limit.-

-l 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 airbome releases are abnormally _

high. The calculations of Sections 2.3.1,2.3.2,2.3.4 and 2.3.5 will typically be used l

O to demonstrate compliance with the dose rate limit of Control 3.11.2.1 for radiolodines and particulates when the measured releases of pkrticulate material

i (other than radiolodines and with half lives >8 days) are >10 times the measured I

-releases of radioiodines.

1.

The Inhalation Dose Rate Method:

'f l

NOTE i

The H-3 dose is calculated as per 2.3.4.

A.

The controlling location is assumed to be'an Infant located in the i

sector at the mile range. The (X/O)o i

for this location is sec/m*. This value is common to all i

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

j B.

Enter the release rate in ft*/ min of the release source and convert to cc/sec.

ft8 2.8317 X 10'cc min l

y y

= cdsec min ft 8 60 sec.

O i

L

Pzge 101 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 G

OFFSITE DOSE CALCULATION MANUAL (ODCM)

U METHODOLOGY SECTION

. 2.3 (continued)

+

1.

(continued) r C. Solve for (O DOT), for nuclide (i) by obtaining the Ci/cc assay value of the release source activity'and multiplying it by the product of 2.3.1.B above.

(Q D01),, (nuclik (1] assan pCi y Walue 2.3.1.B) cc CC Sec (O DOT), =

Ci/sec for nuclide (i)

D. Obtain the R, value from Table G-5 for the organ T.

E.

Solve for DR, g = R (X/Q)o (Q DOT), = "'**~** X sec gCI DR y

a pCi-yr m

sec O

os =

-<em The oe e sete ie eroem T <<e- ##ciiee ci) m 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.

i G. The Dose Rate to the Infants organ T from the Inhalation Pathway is:

'l DRm, = DR, + DR, +

+ D R,,

for all nuclides except H-3. This dose rate shall be added to the other pathways as per 2.3.5 - Total Organ Dose.

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

v e

Page 102 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

METHODOLOGY SECTION 2.3 (continued) 2.

The Ground Plane Dose Rate Method:

NOTE Tritium dose via the ground plane is zero.

..a A.

The controlling location is assumed to be an Infant located in the I

sector at the mile range. The (D/Q) for this 2

location is 1/m. This value is common to all nuclides. (See Table M-2 for sector, range and value.)

l B.

Enter the release rate in ft*/ min of the release source and convert to

\\

cc/sec.

N* X 2.8317 X 10dec min y

= cdsec

=

min It8 60 sec.

~'

O C.

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

(Q DOT),, (nuclide (1) assan Ci y Walue 2.3.2.B) cc oc sec (O DOT), =

pCi/sec for nuclide (i)

D.

Obtain the P, value from Table G-3 E.

Solve for DR,

~

DR, = P (DIO) (O DOT), = "'**~*' ~ *** X '

Ci X

g pCl-yr m*

sec D R, =

mrem The Dose Rate to organ T from nuclide (i) yr r

O

P ge 103 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-20b, REVISION 15 f]

OFFSITE DOSE CALCULATION MANUAL (ODCM)

C/

METHODOLOGY SECTION

2.3 (continued) 2.

(continued)

F.

Repeat steps 2.3.2.C through 2.3.2.E for each nuclide (i) reported in the assay of the release source.

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

1 D Ro, p, = D R, + DR +

+ DR, 2

for all nuclides. This dose rate shall be added to the other pathways as per 2.3.5.

3.

The Grass-Cow / Goat-Milk Dose Rate Method:

NOTE H-3 dose is calculated as per 2.3.4.

A. The controlling animal was established as a

-~ located in the sector at miles. The (D/Q) for this location is 2

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

B.

Entar the anticipated release rate in ft*/ min of the release source and convert to cc/sec.

4 8

2.8317 X 10 cc min ft X y

= cdsec

=

min it 60 sec.

s C. Solve for (O DOT), for nuclide (i) by obtaining the Cl/cc assay value of the release source activity and multiplying it by the product of 2.3.3.B above.

(Q DO7),, (nuclik M assap Ci y (value 2.3.3.@ cc cc sec (O DOT), =

Cl/sec for nuclide (i)

Page 104 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 y%

OFFSITE DOSE CALCULATION MANUAL (ODCM).

d METHODOL.OGY SECTION

2.3 (continued)

3. :(continued).

D. Obtain the R, value from Table G-6(7) (whichever is the controlling animal.

l

. cow / goat, for infant).

If the limited analysis approach is being used, limit the calculation to the l

infant thyroid.

i E. Solve for DRiT DR, = R (DVQ) (Q DOT), = ***~*' ~ *** X ' X pCI a

t-Ci-yr,

m sec 2

1 dry = mrom the Dose Rate to organ T from nuclide (i) j yr

'l F.

Repeat steps 2.3.3.C through 2.3.3 E for each nuclide (i) reported in the -

assay of the release source.

~

~'

Only the radioiodines need to be included if the limited analysis approach is being used.

G. The Dose Rate to the Infant's organ T from Grass-

-Milk pathway is:

i DR,-

-Milkr = DR, + DR +

+ DR.

2 n

for all nuclides. This dose rate shall be added to the other pathways as l

per 2.3.5 - Total Organ Dose.

i 1

NQTE Steps 2.3.3.C through 2.3.3.G need to be completed for each organ of the Infant. Limit the calculation to the infant thyroid if the limited analysis i

approach is being used.'

T i

O 9

i

c

- Page 105 of 181 }

F ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 M

OFFSITE DOSE CALCULATION MANUAL (ODCM)

U METHODOLOGY SECTION 2.3 (continued) 4.

The H-3 Dose Rate Method:

{

' A. The controlling locations and their (X/O), values for each pathway are:

Inhalattion - Infant at range in the sector.

~i 8

(X/O)o =

sec/m '(See Table M-2 for range, sector and value).

Ground Plane - Does not apply to H-3 t-Grass-Cow / Goat-Milk-located in the sector at miles with an Infant at the exclusion area in the sector for the location is '

drinking the milk. The (X/0)p (From Table M-6 at the range and sec]

(X/O)o =

sec/m.

corresponding to the location of the Milk Animal above.)

8 B.

Enter the anticipated release rate in ft / min of the release source and.

convert it to cc/sec.

]

2.8317 X 10' cc rnin 8

ft X y

-=

min It*

60 sec.

.'i l

cc/sec volume release rate

=

O. Solve for (O DOT)u for Tritium, by obtaining the pCl/cc assay value of the release source and multiplying it Ly the product of 2.3.4.B above.

(O DOT)y = (H-3) pCI y (2.3.4.B value) cc cc sec (O DOT)u =

Ci/sec activity release rate D.

Obtain the Tritium dose factor (R) for Infant organ T from:

PATH

-TABLE #

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

Pcge 106 of 181

n 1.

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

.ji OFFSITE DOSE CALCULATION MANUAL (ODCM)

A,0 METHODOLOGY SECTION 12.3 (continued) 4.'-

(continued).

+

1 E.. Solve for Dg3 (Inhalation) using the (X/Q)o for inhalation from 2.3.4.A and R, (Inhalation) from 2.3.4.D..

3 DRu.,, = Rua (XIQ)o (Q DOT)g,.

m}_

DR.,,, = miendyr from H-3 Infant Inhalation for organ T n

F.

Solve for D, (Grass-

-Milk) using the (X/Q)o for S

Grass-

-Milk from 2.3.4.A.and R, (Grass-

-Milk) l S

from 2.3.4.D D R.3,,, = Rya,,, (X/0), (O DO7)y.3 y

i i

DRu4,,, = mrentyr from H-3 Infant O

G. Repeat steps 2.3.4.D through 2.3.4.F for each Infant organ T of interest.

H. The individual organ dose rates.from H-3 shall be added to the other organ pathway dose rates as per 2.3.5.

1 1

a i

i O

m

7.

Pzge'107 of 181 -

ST. LUCIE PLANT '

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 f

OFFSITE DOSE CALCULATION MANUAL (ODCM)

METHODOLOGY SECTION 2.3 '(continued) 5.

Determinina the Total Oraan Dose Rate from lodines. 8D-Particulates. and H-3 from Release Source (s)

A. The following table describes all the pathways that must be summed to.

' arrive at the total dose rate to an organ T:

PATHWAY DOSE RATE STEP # REF.

Inhalation (l&8DP).

2.3.1.G Ground Plane (l&BDP)-

(Whole Body only) 2.3.2.G Gr-Milk (l&BDP) 2.3.3.G Inhalation (H-3) 2.3.4.E Gr-

-Milk (H-3) 2.3.4.F DR =

(sum of above) 7 B.

Repeat the above summation for each Infant organ T.

j

'f C. The.DR above shall be added to all other release sources on the site that 1

I will be in progress at any instant.: Refer to in-plant ptocedures'and logs to determine the Total DR to each organ.

7 2.4 Determinina the Gamma Air Dose for Radioactive Noble Gas Release Source (s)

Discussion - Control 3.11.2.2 limits the air dose due to noble gases in gaseous effluents for gamma radiation to <5 mrads for the quarter and to <10 mrads in any.

calendar year. The following calculation method is provided for determining the noble gas gamma air dose and is based on section 5.3.1 of NUREG-0133, November 1978. The dose calculation is independent of any age group. The equation may be used for Control dose calculation, the dose calculation for the annual report or for projecting dose, provided that the appropriate value of (X/Q) is -

used as outlined in the detailed explanation that follows. - The equation for gamma -

air dose is:

e D -air = I 3.17 X 104 M, (X/0) O, y

i O

1 X

]

- Page 108 of 181 -

']

I ST. i.UCIE PLANT -

' CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 f/'\\-

OFFSITE DOSE CALCULATION MANUAL (ODCM) j M

METHODOLOGY SECTION

2.4 ? (continued)-

i Where:

Dy-air gamma' air dose in mrad from radioactive noble gases.

=

1 A mathematical symbol to signify the operations to the right side of '

-I

=

the symbol are to be performed for each nuclide'(i) through (n) :

.j

' and summed to arrive at the total dose, from all nuclides reported during the interval. No units apply.

4 3.17 X 10 the inverse of the number of seconds per year with units of

=

year /sec.

the gamma air dose factor for radioactive noble gas nuclide (i) in

)

M,

=

8 units of mrad-m Cl-yr -

(X/Q) the long term atmospheric dispersion factor for ground level i

=

8 releases in units of sec/m. The value of (X/Q) is the same for all nuclides (i) in the dose calculation, but the value of (X/Q) does vary depending on the Limiting Sector the C~oritrol is based on, etc.

O, the number of micro-curies of nuclide (i) released (or projected)

=

during the dose calculation exposure period. (e.g., month, quarter or year) 1 1:

t O

i i

-1 Pcge 109 of 181 f

i ST. LUCIE PLANT j

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 tr]

OFFSITE DOSE CALCULATION MANUAL (ODCM)

(./

METHODOLOGY SECTION

. 2.'4. (continued) -

From an evaluation of past releases, a single effective gamma air dose factor (M,)

has been derived, which is representative of the radionuclide abundances'and corresponding dose contributions typical of past operation. (Refer to Appendix C for a detailed explanation and evaluation of M,). The value of M, has been derived from the radioactive noble gas effluents for the years 1978,1979 and 1980.

The value is M,, = 7.4 X 10' "*W' CFm8 This value may be used in conjunction with the total noble gas releases (

Q,) to simplify the dose evaluation and to verify that the cumulative gamma air dose is within the limits of Control 3.11.2.2. To allow for any unexpected variability in the l

radionuclide distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is i

D,,,

0* y, y,g g,

.7 For purposes of calculations, the appropriate meteorological dispersion (X/Q) from Table M-1 should be used. Control 3.11.2.2 requires that the doses be evaluated l

once per 31 days, (i.e., monthly). ~ The quarterly dose limit is 5 mrads, which i

corresponds to a monthly allotment of 1.7 mrads. If the 1.7 mrads is substituted for 1

Dg,, a cumulative noble gas monthly release objective can be calculated. This value is 36,000 Ci/ month, noble gases.

As long as this value is not exceeded in any month, no additional calculations are needed to verify cornpliance with the quarterly noble gas release limits of Control 3.11.2.2. Also, the gamma air dose is more limiting than the beta air dose.

Therefore, the beta air dose does not need to be calculated per Section 2.5 if the J

M, dose factor is used to determine the gamma air dose. Refer to Appendix C for a detailed evaluation and explanation.

i The calculations of Section 2.5 may be omitted when this limited analysis approach:

)

is used, but should be performed if the radionuclide specific dose analysis is performed. Also, the radionuclide specific calculations will be performed for inclusion in annual reports.

O

~

s

(

X, Pcge 110 of 181 -

'ST. LUC'IE PLANT i

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 W

- OFFSITE DOSE CALCULATION MANUAL (ODCM)

-l

- Nx METHODOLOGY SECTION j

1 1

2.4 (continued) q The following ' steps provide a detailed explanation of how the radionuclide specific i

dose is calculated.. This method is used to evaluate quarterly doses in accordance

- with Control 3.11.2.2 if the releases of noble gases during any month of the; quarter -

exceed 36,000 Cl.

j 1.

To determine the applicable (X/Q) refer.to Table M-1 to obtain the value for the.

l type of dose calculation being performed. -(i.e., Quarterly Control or Dose Projection for examples). This value of (X/Q) applies to each nuclide (1).

l

2. ' Determine (M) the gamma air dose factor for nuclide (i) from Table G-2.

3.

Obtain the micro-Curies of nuclide (i) from the in-plant radioactive gaseous-l waste management logs for the sources under consideration duhng the time interval.

I 4.

Solve for D, as follows:

j M mdm* y M sec Q, yCi g,,. 3.17 X 104 yr y I

i

_y see C/-yr m'

-1 D, = mrad = the dose from nuclide (i) 5.

Perform steps 2.4.2 through 2.4.4 for each nuclido (i) reported during the time j

interval in the source.

6.

The total gamma air dose for the pathway is determined by summing the D,

,1 dose of each nuclide (i) to obtain Dy-air dose.

Dy, = D, + D, +

+ D, = mrad i

NOTE Compliance with a _1/31 day Control, Quarterly Control, yearly or 12 l

consecutive months Control can be demonstrated by the limited analysis j

approach using M,. Using this method only requires that steps 2.4.2 through 2.4.5 be performed one time, remembering that the dosa must be divided by l

0.8, the conservatism factor.

.j i

7.

Refer to in-plant procedures for comparing the calculated dose to any O

applicable limits that might apply.

{

r

..w.

Page 111 of 181.

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 hW OFFSITE DOSE CALCULATION MANUAL (ODCM)

U METHODOLOGY SECTION 2.5 l Determinina the Beta Air Dose for Radioactive Noble Gas Releases Discussion - Control 3.11.2.2 limits the quarterly air dose due to beta radiation from noble gases in gaseous effluents to <10 mrads in any calendar. quarter and <20 rnrads in any calendar year. The following calculation method is provided.for determining the beta air dose and is based on Section 5.3.1 of NUREG-0133, November 1978. The dose calculation is independent of any age group. The equation may be used for Control dose calculation, dose calculation for annual reports or for projecting dose, provided that the appropriate value of (X/Q) is used as outlined in the' detailed explanation that follows.

The equation for beta air dose is:

n~

D,., I = 3.17 X 10*N/X/0) Q,

/

Where:

UB-air beta air dose in mrad from radioactive ncble gases.

=

S a mathematical symbol to signify the operations to the right

=

side of the symbol are to be performed for each nuclide (i) through (n) and summed to arrive at the total dose, from all nuclides reported during the interval. No units apply.

3.' 7 X 10* =

the inverse of the number of seconds per year with units of 1

year /sec.

N, the beta air dose factor for radioactive noble gas nuclide (i) in units

=

of mrad-m*

Cl-yr (X/O) the long term atmospheric dispersion factor for ground level

=

8 releases in units of sec/m. The value of (X/O) is the same for all.

nuclides (i) in the dose calculation, but the value of (X/O) does vary depending on the Limiting Sector the Control is based on, etc.

the number of micro-Curies of nuclide (i) nileased (or projected)

O,

=

during the dose calculation exposure period O

E P ge 112 cl181 b

(

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 f

n --

OFFSITE DOSE CALCULATION MANUAL (ODCM)

()

METHODOLOGY SECTION

. 2.5 (continued)

The beta air dose does not have to be evaluated if the noble gas gamma air dose is evaluated by the use of the effective gamma air dose factor (M,). However, if j

l the nuclide specific dose calculation is used to evaluate compliance with the quarterly gamma air dose limits (Section 2.4), the beta air dose should also be evaluated as outlined below for the purpose of evaluating compliance with the quarterly beta air dose limits of Control 3.11.2.2. The following steps provide a detailed explanation of how the dose is calculated.

1.

To determine the applicable (X/Q) refer to Table M-1 to obtain the value for the i

type of dose calculation being performed (i.e., quarterly Control or Dose l

projection for examples). This value of (X/Q) applies to each nuclide (i).

2.

Determine (N,) the beta air dose factor for nuclide (i) from Table G-2.

3.

Obtain the micro-curies of nuclide (i) from the in-plant radioactive gaceous waste management logs for the source under consideration during the time interval.

4.

Solve for D, as follows:

D, =

• '0* Y' X X 5 0)*** X

'1 sec pCi-yr M

1 D, = mrad = the dose from nuclide (i) 5.

Perform steps 2.5.2 through 2.5.4 for each nuclide (i) reported during the time interval in the release source.

6.

The total beta air dose for the pathway is determined by summing the D, dose of each nuclide (i) to obbin Du, dose.

D%, = D + D,

+ D, = mrad i

7.

Refer to in-plant procedures for comparing the calculated dose to any applicable lim'ts that might apply.

I h_

P ge 113 of 181' ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 o

OFFSITE DOSE CALCULATION MANUAL (ODCMI C

METHODOLOGY SECTION 2.6 Determinina the Radiciodine and Particulate Dose To Any Oraan From Cumulative Releases Discussion - Control 3.11.2.3 limits the dose to the whole body or any organ resulting from the release of I-131,1-133, tritium and particulates with half-lives >8 days to 57.5 mrem during any calendar quarter and $15 mrem during any calendar year. The following calculation method is provided for determining the critical organ dose due to releases of radioiodines and particulates and is based on Section 5.3.1 of NUREG-0133, November 1978. The equation can be used for any age group i

provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group. The (X/Q)o symbol represents a DEPLETED-(X/O) which is different from the Noble Gas (X/Q) in that (X/O)o takes into account the loss of I&8DP and H-3 from the plume as the semi-infinite cloud travels over a given distance. The (D/Q) dispersion factor represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site. The I&BDP and H-3 notations refer to I-131,1-133 Particulates having half-lives >8 days and T '+ium. For ease of calculations, dose from other lodine nuclides may be included (see 2.1). Triwm calculations are always based on 7

(X/Q)o. The first step is to calculate the l&BDP and H-3 dose for each pathway that l

applies to a given age group. The total dose to an organ can then be determined pd by summing the pathways that apply to the receptor in the sect,or, j

l The equations are:

For Inhalation Pathway (excluding H-3):

n l

Duoe, = I 3.17 X 10-eR, (X/0),O,

)

l l

l i;or Ground Plane or Grass-Cow / Goat-Milk i

t l

i n

Duog, = I 3.17 X 104R, (D/0)O, j

i i

l For each pathway above (excluding Ground Plane) For Tritium:

l D.3,

=

3.17 X 104Ry4fX/0)o,

O y

L i

l i

I

^

l, P;ge 114 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

. (V~'y OFFSITE DOSE CALCULATION MANUAL (ODCM)-

l METHODOLOGY SECTION 2.6 (continued)

For Total Dose from Particulate Gaseous effluent to organ T of a specified age group:

D

• 2 (D og + D j r

u t

Where:

the organ of interest of a specified age group T

=

the applicable pathways for the age group of inte, 't z

=

Dose in mrem to the organ T of a specified age group from D op

=

radiolodines and 8D Particulates Dose in mrem to the organ T of a specified age group from Tritium D

=

H-3 Total Dose in mrem to the organ T of a specified age group from Dr

=

Gaseous particulate Effluents l

s 1

A mathematical symbol to signify the operations to the right

=

of the symbol are to be performed for each nuclide (i) through (n) and the individual nuclide doses are summed to arrive at the total dose from the pathway of interest to organ T.

A mathematical symbol to indicate that the total dose Dr to I

=

Z organ T is the sum of each of the pathway doses of I&BDP and H-3 from gaseous particulate effluents.

3.17 X 10-8 The inverse of the number of seconds per year with units of

=

year /sec.

t The dose factor for nuclide (i) (or H-3) for pathway Z to organ T of R,

=

the specified age group. The units are either mrem-m for pathways mrem-m' - sec for pathways s

og yr-- pCi usmg (NO)o yr-pCi using (DIQ)

O

'l g

}p' Pzgo 115 of 181 -

i ST. LUCIE PLANTL e

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 -

T

' OFFSITE DOSE CALCULATION MANUAL (ODCM) l METHODOLOGY SECTION 2.6 (continued) j i

Tho' depleted-(X/Q) value for a specific location where the receptor

]

(X/Q)o:

=

' is located (see discussion). - The units are sec/m' j

.th feposition value for a specific location where the receptor is l

.(D/Q)

=

kcated (see discussion).- The units are 1/m" where m= meters.

i The number of micro-Curies of nuclide (i) released (or projected)

-l Q,'

=-

during the dose calculation exposure penod.

'l l

QH-3 the number of micro-Curies of H-3 released (or projected) during l

=

the dose calculation exposure period.

As discussed'in Section 2.3, the grass-cow / goat-milk pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ, This pathway typically contributos >90% of the total dose received by the ir.fant's thyroid and the radioiodine cc aibutes essentially all of this dose. Therefore, it is possible to demonstrate compliance with the dose limit of Control 3.11.2.3 for radioiodines and particulates by only evaluating the infant's thyroid dose due to the release of j

O Section 2.6.3 is used for this determination. ~

~~

j radiolodines via the grass-cow / goat-milk pathway. The calculation method of '

The dose determined by Section'2.6.3 should be' divided by 'a conservatism factor-l of 0.8. This added conservatism provides assurance that the dose determined by l

this limited analysis approach will not be < the dose that would be determined by l

evaluating all radionu::lides and all pathways. If this limited analysis approach is used, the dose calculations for other radioactive particulate matter and other' j

pathways need not be performed. Only the calculations of Section 2.6.3 for the radiolodines are required to denionstrate compliance with the Control dose limit.

1 However, for the dose assessment included in Annual Reports, doses will be j

evaluated for the infant age groups and all organs via all designated pathways from j

radiolodines and particulates measured in the gaseous effluents according to the j

sampling and analyses required in Control Table 4.11-2. The following steps l

provide a detailed explanation of how the dose is calculated for the~given pathways:

l i

I 1

O i

I

..J.,

I

- ~. - -

A

Page 116.of 181 1

ST. LUCIE PLANT '

L..

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 -

f' OFFSn E DOSE CALCULATION MANUAL (ODCM)

< A.

METHODOLOGY SECTION g-

'2.6' - (continued) 1.

The inhalation Dose' Pathway Meth_qd:

NOTE ~

i The H-3 dose should be calculated as per 2.6.4.

A.

Determine the applicable (X/Q)o from Table M-2 for the location where the receptor is located. This value is common to each nuclide (i)

B.

Determine the R, factor of nuclide (i) for the organ T and age group from l

. Table G-5.

C. Obtain the micro-Curies (Q,) of nuclide (i) from the radioactive gas waste management logs for the release source (s) under consideration during the -

time interval.

D. Solve for D,.

D, = 3.17 X 10*Ri(X/Q)oQ, D, =

mrem from nuclide (i)

E.

Perform steps 2.6.1.B through 2.6.1.D for each nuclide (i) reported during the time interval for each organ.

F.

The lahalation dose to organ T of the specified age group is determined by summing the D, Dose of each nuclide (i) g py = D, + D, +

+ D,, =

miem i

Refer to 2.6.5 to determine the total dose to organ T from radiolodines &

8D Particulates L

l0 W-

n Page 117 of 181

~

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 fN OFFSITE DOSE CALCULATION MANUAL (ODCM)

[ U, METHODOLOGY SECTION

2.6 (continued) 1 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 the Ground Plane pathway dose.

A.

Determine the applicable (D/0) from Table M-2 for the location where the receptor is located. This (D/O) value is common to each nuclide (i)

B. Determine the Ri factor of nuclide (i) for the whole body from Table G-4.

The ground plane pathway dose is the same for all age groups.

C. Obtain the micro-Curies (0,) of nuclide (i) from the radioactive gas waste i

management logs for the source under consideration.

D. Solve for D, r~

t.

D, = 3.17 X 104R, (O'O)O, D, =

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.

F.

The Ground Pldne dose to the whole body is determined by summing the Di Dose of each nuclide (i)

Do,n.w, = D, + D, +

+D, mrem n

Refer to step 2.6.5 to calculate total dose to tho Whole Body'.

Page 118 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 75.

OFFSITE DOSE CALCULAYlON MANUAL (ODCMJ

(/

METHODOLOGY SECTION.

i L

~ 2.6 (continued) 3.

The Grass-Cow / Goat-Milk Dose Pathway Method:

l.

NOTE Tritium dose is calculated as per 2.6.4.

i A. A cow or a goat, will be the controlling animal; (i.e., dose will not be the i

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).

l B.

Determine the dose factor R, for nuclide (i), for organ T, from 1.

From Table G-6 for a cow, or;

)

2.

From Table G-7 for a goat.

' p(,f)

If the limited analysis approach is being used, limit the calculation to the infant thyroid.

C. Obtain the micro-Curies (0,) of nuclide (i) from the radioactive gas waste management logs for the release source under consideration during the time interval.

i D. Solve for D, D, = 3.17 X 10*R,(D/Q)O, D, =

mrem from nuclide (i)

E.

Perform steps 2.6.3.B through 2.6.3.D for each nuclide (i) reported during the time interval. Only the radioiodines need to be included if the limited analysis approach is used.

5 O

P ge 119 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 75 OFFSITE DOSE CALCULATION MANUAL (ODCM)'.

(,) '

METHODOLOGY SECTION 2.6 (continued) 3.

(continued)

F.

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

Dwu (or Do.a.u) = D, + D, +

+ D, =

mrem The dose to each organ should be calculated in the same manner with steps 2.6.3.B through 2.6.3.F. Refer to step 2.6.5 to determine the total dose to organ T from radiolodines &8D Particulates. If the limited analysis i

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 Gaseous Tritium Dose (Each Pathway) Method:

A. The controlling locations for the pathway (s) has already been determined p

by: Inhalation

- as per 2.6.1.A

()

Ground Plane

- not applicable for H-3

~~

Grass-Cow / Goat-Milk - as per 2.6.3.A B. Tritium dose calculations use the depleted (X/O)o instead of (D/Q). Table M-2 describes where the (X/Q)o value should be obtained from.

C.

Determine the Pathway Tritium dose factor (Ru) for the organ T of interest from the Table specified below:

AGE INHALATION COW GOAT Infant G-5 G-6 G-7 D. Obtain the micro-Curies (O) 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.

O

Page 120 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODOM)

Os METHODOLOGY SECTION 2.6 (continued) 4.

(continued)

E.

Solve for Dg3 4

Dg3 = 3.17 X 10 Rg3(X/Q)oO Dg3 =

mrem from Tritium in the specified pathway for organ T of the specified age group 5.

Determinina the Total Oraan Dose From lodines. 8D-Particulates and H-3 From Cumulative Gaseous Releases NOTE Control dose limits for I&8DP shall consider dose from all release sources from the reactor unit of interest.

A.

The following pathways shall be summed to arrive at the total dose to organ T from a release source or if applicable to Control, from all release sources:

PATHWAY DOSE (mrem)

STEP # REF.

Inhalation (l&8DP) 2.6.1.F Ground Plane (l&8DP)

(Whole Body only) 2.6.2.F Grass-Milk (l&BDP) 2.6.3.F Inhalation (H-3) 2.C.4.E Grass-

-Milk (H-3) 2.6.4.E Dose =

(sum of above) r B.

The dose to each of the INFANT'S ORGANS shall be calculated:

BONE, LIVER, THYROID, KIDNEY, LUNG, WHOLE BODY, & GI-LLI The INFANT organ receiving the highest exposure relative to its Control Limit is the most critical organ for the radiciodine & 8D Particulates gaseous effluents.

O

P ge 121 cf 181 ST. LUCIE PLANT 4

J CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 fr^(

OFFSITE DOSE CALCULATION MANUAL (ODCM)

U METHODOLOGY SECTION 2.7 ' Proiectina Dose for Radioactive Gaseous Effluents g

Discussion - Control 3.11.2.4 requires that the waste gas holdup system be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each und, to areas at and beyond the SITE BOUNDARY (see TS Figure 5-1-1) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The following calculation method is provided for determining the projected doses. This method is based on using the results of the calculations performed in Sections 2.4 and 2.5.

1.

Obtain the latest results of the monthly calculations of the gamma air dose (Section 2.4) and the beta air dose if performed (Section 2.5). These doses p

can be obtained from the in-plant records.

2.

Divide these doses by the number of days the plant was operational during the -

month.

)

3.

Multiply the quotient by the number of days the plant is projected to be operational during the next month. The product is the projected dose for the l

next month. The value should be adjusted as needed to account for any -

changes in failed-fuel or other identifiablo operating conditions that could -

significantly alter the actual releases.

J 4.

If the projected doses are >0.2 mrads gamma air dose or > 0.4 mrads beta air doso, the appropriate subsystems of the waste gas holdup system shall be i

used.

L l

l O

1 l

I h.

P;ge 122 of 181 ST. LUCIE PLANT CHEMISTRY OPERAT!NG PROCEDURE C-200, REVISION 15 A-OFFSITE DOSE CALCULATION MANUAL (ODCM)

{

J METHODOLOGY SECTION 3.0 40 CFR 190 Dose Evaluation Discussion - Dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to $25 mrem to the whole body or any organ (except thyroid, which is limited to s75 mrem) over a period of 12 consecutive months. The following approach should be used to demonstrate compliance with these dose limits. This approach is based on NUREG-0133, Section 3.8.

3.1 Evaluation Bases I

Dose evaluations to demonstrate compliance with the above dose limits need i

only be performed if the quarterly doses calculated in Sections 1.4,2.4 and 2.6 exceed twice the dose lindts 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 i

the thyroid or any organ from radiciodines and particulates (atmospheric l

releases). Otherwise, no evaluations are required and the remainder of this section can be omitted.

l 3.2 Doses From Llauid Releases For the evaluation of doses to real individuals from liquid releases, the same calculation method as employed in Section 1.4 will be used. However, more realistic assumptions will be made conceming the dilution and ingestion of fish and shellfish by individuals who live and fish in the area. Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic dose to these real people by providing data on actual measured levels of plant related radionuclides in the environment.

3.3 Doses From Atmospheric Releases For the evaluation of doses to real individuals from the atmospheric releases, the same calculation methods as employed in Section 2.4 and 2.6 will be used.

in Section 2.4, the total body dose factor (K,) should be substituted for the gamma air dose factor (M,) to determine the total body dose. Otherwise the same calculation sequence applies. However, more realistic assumptions will be made conceming 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 Eavironmental 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.

/R15

P ge 123 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 q

OFFSITE.QDSE CALCULATION MANUAL (ODCM) luf Ee*THODOLOGY SECTION 4.0 Annual Radioactive Effluent Report 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 condition; that the Control dose calculations are based on. The Control dose limits are therefore included in item 1 of the report, for information only. The ECLs in item 2 of the report shall be those listed in Tables L-1 and G-1 of this manual. The average energy in item 3 of the report is not applicable to the i

St. Lucie Plant. The format, erder of nuclides and any values shown as.an example in Tables 3.3 through 3.8 are samples only. Other formats are acceptable i

if they contain equivalent infomat'on. A table of contents should also accompany the report. The following format should be used:

RADIOACTIVE EFFLUENTS - SUPPLEMENTAL INFORMATION

1. Regulatory Limits:

1.1 For Radioactive liquid waste effluents:

a.

The concentration of radioactive material released from the site (see

~ (

Figure 5.1-1 in TS-A) shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appehdix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10" Ci/mi total activity, b.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each reactor unit j

to unrestricted areas (See Fig. 5.1-1 in TS-A) shall be limited during any calendar quarter to 51.5 mrem to the whole body and to 5 mrem

)

5 to any organ and 3 mrem to the whole body and $10 mrem to any 5

organ during any calendar year.

1.2 For Radioactive Gaseous Waste Effluents-a.

The dose rate resulting from radioactive materials released in gaseous efflueno 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 5500 mrem /yr to the total body and 3000 mrem /yr to the skin and 5

o I

/R15

p P ge 124 of 181 i

'1 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C 200, REVISION-15 f}

OFFSITE DOSE CALCULATION MANUAL (ODCM)

V METHODOLOGY SECTION.

4.0 (continued) 1.

(continued) l 1.2 (continued) a.

(continued)

The dose rete limit from I-131,1-133, Tritium and particulates with '

half-lives >8 days shall be $1500 mrem /yr to any organ.

b.

The air dose (see Figure 5.1-1 in the TS-A) due'to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following e

During any calendar quarter, to s5 mrad for gamma radiation and 510 I

mrad for beta radiation and during any calendar year to s10 mrad for gamma radiation and 20 mrad for beta radiation c.

The dose to a MEMBER OF THE PUBLIC from I-131,1-133, Tritium 1

and all radionuclide in particulate form, with half-lives >8 days in gaseous effluents released from each reactor unii to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1 in the TS-A) shall be limited to the following:

During any calendar quarter to s7.5 mrem to any organ and during any calendar year to s15 mrem to any organ.

2.

Effluent Limiting Concentrations:

/R15 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. Lucie Plant.

i l

t P ge 125 of 181 ST. 'LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 A

OFFSITE DOSE CALCULATION MANUAL (ODCM)

.L,h METHODOLOGY SECTION -

4.0 (continued) 4.

Measurements and Approximations of Total Radioactivity:

A summary of liquid effluent accounting methods is described in Table 3.1.

A summary of gaseous efiluent accounting methods is described in Table 3.2.

Estimate of Errors:

LIQUID GASEOUS Error Topic Avg. % Max. %

Avg. % Max. %

Release Point Mixing 2

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

e 4

O.

4

y V:

Pcge 126 of 181 ~

7 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

/

OFFSITE DOSE CALCULATION MANUAL (ODCM) a]f METHODOLOGY SECTION 4.0 (continued)

4. (continued)~

TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SAMPLING FREQUENCY TYPE OF ANALYSIS S URCE A

YSIS

)

EACH BATCH PRINCIPAL GAMMA EMITTERS p.h.a.

l MONITOR TRITIUM L.S.

MONTHLY COMPOSITE GROSS ALPHA G.F.P.

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

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

STEAM AND DISSOLVED GASES l

GENERATOR TRITIUM LS.

MONTHLY COMPOSITE GROSS ALPHA G.F.P.

RE F E QUARTERLY COMPOSITE Sr-89, Sr-90, Fe-55 C.S. & L.S.

TABLE NOTATION:

j i

Boric Acid Evaporator condensate is normally recovered to the Primary Water l

Storage Tank for recycling into the reactor coolant system and normally does l-not contribute to liquid waste effluent totals.

j gamma spectrum pulse, height analysis using Lithium Germanium p.h.a.

detectors. All peaks are identified and quantified.

Liquid Scintillation counting L.S.

C.S.

Chemical Separation G.F.P.

Gas Flow Proportional Counting O

Pcge 127 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

- (3)l METHODOLOGY SECTION

.f 4.0 ' (continued) 4.

(continued)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GA METHOD OF SAMPLING FREQUENCY TYPE OF ANALYSIS.

gOURCE Waste Gas Each Tank Principal Gamma Emitters G,p.h.a.

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

Purge H-3 L.S-Releases Four per Month Principal Gamma Emitters (G, C, P) - p.h.a.

H-3 L.S.

Plant Vent Monthly Composite Gross P - G. F. P.

(Particulates)

Alpha j

Quarterly Composite Sr-90 C.S. &

(Particulates)

Sr-89 L.S.

4 Gaseous Grab Sample G

Charcoal Filter Sample C

Particulate Filter Sample P

Liquid Scintillation Counting L.S.

Chemical Separation C.S.

Gamma spectrum pulse height analysis using Lithium p.h.a.

Germanium detectors. All peaks are identified and quantified.

Gas Flow Proportional Counting G.F.P.

t

(

4:g ]

r. :N

'Page.128 of 18'1 0

y n:

s

'899

ST. LUCIE PLANT

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15-

,yMg OFFSITE DOSE CALCULATION MANUAL (ODCM) l T

4. j,.

METHODOLOGY SECTION J

4.0l1(continued) -

L51 : Batch Releases

~

e J

.A. ~ Liquid 1

l 1.

Number of batch releases:

2.

Total time period of batch releases:.

minutest 3.

Maximum time period for a batch release:

minutes

~4.

Average time period for a batch release:

minutes l

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 O

B.

Gaseous 1.

Number of batch releases:

I 2.

Total time period for batch releases:

minutes 3.

Maximum time period for a batch release:

minutes

-i 4.

Average time period for batch releases:

minutes' 5.

Minimura time period for a batch release:

minutes j

- All gaseous waste releases are summarized in tables a

i d

'i L

4

(ffm-P:ge 129 of.181 m

4

ST. LUCIE PLANT

(.,,.

CHEMISTRY OPERATING PROCEDURE C' 200, REVISION 15 cj s f"'

. OFFSITE DOSE CALCULATION MANUAL 10DCM) l i

METHODOLOGY SECTION -

04.0 (continued) _

r I

6.

Unplanned Releases i

,s

^

' A.

Liquid 1.

Number of releases:

4.

2.

Total activity releases:

Curies B.

Gaseous 1.

Number of releases:

2.

Total activity released:

Curies l

C. See attachments (if applicable) for.

t 1.

A description of the event and equipment involved.

]

' 2.

Cause(s) for the unplanned release.

3.

Actions taken to prevent a recurrence

. 4.. Consequences of the unplanned release 7.

Description of dose assessment of radiation dose from radioactive effluents to j

the general public due to their activities inside the' site are reported on the' January annual report.

j 8.

Offsite dose calculation manual revisions initiated during this reporting period.

' See Control 3.11.2.6 for required attachments to the Annual Report.

q 9.

Solid waste and irradiated fuel shipments as per requirements of Control 3.11.2.6.

~

y 1

Page 130 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

O METHODOLOGY SECTION 4.0 (continued)

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.

I

'I O

b O

P ge 131 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

/N OFFSITE DOSE CALCULATION MANUAL-(ODCM)

()

METHODOLOGY SECTION FLORIDA POWER & LIGHT COMPANY ~

s ST. LUCITi UNIT #

ANNUAL REPORT -

/

/

THROUGH

/

/

TABLE 3.3: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER # QUARTER #

A.

Fission and Activation Products -

1.

Total Release - (Not including Tritium, Gases, Alpha)

Ci E

E 2.

Average Diluted Concentration Dunng Penod CUML E

E B.

Tritium

'1.

Total Release Ci E-E 2.

Average Diluted Concentration During Period Ci/ML E

E C.

Dissolved and Entrained Gases 1.

Total Release Ci E

E 2.

Average Diluted Concentration During Period Cl/ML-E E

. D.

Gross Alpha Radioactivity 1.

Total Release Ci E

E J

'. i j

E,

=.

' Prge 132 of 181 -

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

' VN -

OFFSITE DOSE CALCl)LATION MANUAL (ODCM1 Af

- METHODOLOGY SECTION TABLE 3.3: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (continued)

UNIT.

QUARTER # QUARTER #

E.

-Volume of Waste Released (Prior to Dilution)

LITERS E

E F.

Volume of Dilution Water Used During Period' LITERS E

'E l

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.

1

a g'~

0

..l

• <""1

,W$

Pige 133 of 181 j

{_ ;;7;tR, W #

ST. LUCIE PLANT M

Y ~ _

CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 -

OFFSITE DOSE CALCULATION MANUAL'(ODCM)

METH6 I

1

~ FLORIDA POWER & LIGHT COMPANY ST, LUCIE UNIT # ~

ANNUAL REPORT '-

/

/

THROUGH-

/

/

i TABLE 3.4:. LIQUID EFFLUENTS (EXAMPLE FORMAT)

-CONTINUOUS MODE BATCH MODE.

NUCLIDES RELEASED

• UNIT QUARTER #

QUARTER #

QUARTER #

QUARTER #

1-131 Cl E

E E

E-c; l133

- Cl E

E E

E l

l135 Cl E

E

.E-E NA-24 Cl

-E E

E E

i CR-51 Cl E

E E

E

.[

MN-54 Cl E

E E

E CO-57 Cl E

E E

.E CO-58 Cl E

E E

E-I FE-59 Cl E

E E

E CO-60 Cl E

E E

E 4

O ZN-65 Cl E-E E

E j

Ni-65 Cl E

E

-.. E E

AG-110 Cl E

E E.

E J

SN-113 Cl E

E E

E-SB 122 -

Cl E

E' E-E, lj SB 124 Cl E

E E

E W-187 Cl E

E E

E NP-239

.Cl E.

E E.

E l

ZR-95 Cl E

E E

E MO-99 Cl E

E E

E

'i RU-103 Cl E

E E

E-CS 134 Cl E

E E

E-l CS-136 Cl E

E E

E i

CS-137 -

Cl E

E E

E BA 140 Cl E

E E

E' CE-141 Cl E

E E

E-3 BR-82 Cl E

E E

E

-l ZR-97

. Cl E

E E

E l

SB 125 -

Cl E

E E-E-

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

- O lf l

-: c,

Prge 134 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 cr~N OFFSITE DOSE CALCULATION MANUAL (ODCM)

L,i METHODOLOGY SECTION

- TABLE 3.4: LIQUID EFFLUENTS (EXAMPLE FORMAT)

(continued) -

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER #

QUARTER #

QUARTER #

QUARTER #

r CE 144 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 (ABOVE)

Cl E

E E

E AR41 Cl E

E E

E KR-85 Cl E

E E

E XE-131M 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

/V a

.m

Pcge 135 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15

.,q

- OFFSITE DOSE CALCULATION MANUAL (ODCM)

.( f METHODOLOGY SECTION FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #

TABLE 3.5 LIQUID EFFLUENTS - DOSE SUMMATION I'

Age Group: Adult Location: Any Adult h

Exposure Interval:

From Through l

CALENDAR YEAR DOSE Fish & Shellfish Pathway to Organ (mrem) i BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY i

l i

i O

n i

I L

Pcge 136 of 181

. ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C-200, REVISION 15 ~

-/~i OFFSITE DOSE CALCULATION MANUAL (ODCM) if METHODOLOGY SECTION

' FLORIDA POWER & LIGHT COMPANY

' ST. LUCIE UNIT #

! ANNUAL REPORT -

/

/

THROUGH

/

/

~ TABLE 3.6: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT.

QUARTER # QUARTER #

A.

Fission and Activation Gases 1.

Total Release Cl E

E 2.

Average Release Rate For Period C1/SEC E

E B.

lodines 1.

Total lodine-131 Ci E

E 2.

Average Release Rate for Period Ci/SEC

~'E_

E i

C. Particulates i

1.

Particulates T-1/2 > 8 Days Ci E

E i

2, Average Release Rate for Period Cl/SEC E

E 3.

Gross Alpha Radioactivity Ci E

E D. Tritiurn 1.

Total Release Ci E

E 2.

Average Release Rate for Period Cl/SEC E

E i

i

pp ff P ge 137 of 181

[

ST. LUCIE PLANT' CHEM:STRY OPERATING PROCEDURE C-200, REVISION 15

^p

' OFFSITE DOSE CALCULATION MANUAL (ODCM) l

'af E.WODOLOGY SECTION i

(,

FLORIDA POWER & LIGHT COMPANY L

ST. LUCIE UNIT #

t ANNUAL REPORT -

/

/

-THROUGH

/

/

i TABLE 3.7 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (EXAMPLE FORMAT) i r

CONTINUOUS MODE BATCH MODE

- NUCLIDES RELEASED

• UNIT QUARTER # l QUARTER #

QUARTER # l QUARTER #

1.

Fission Gaws AR41 Cl E

E E

E KR-85 Cl E

E E

E n

KR45M Cl E

E E

E KR47 Cl E

E E

E i

KR-88 Cl E

E E

E i

XE-131M Cl E

E E

E l

XE-133 Cl E

E E

E

'p XE-133M Cl '

E E

E E

XE-135 Cl E

E

_.E E

i XE-135M Cl E

E E

E XE iT Cl E

E E

E l

UNIDENTIFIED Cl E

E E

E TOTAL FOR PERIOD (ABOVE)

Cl E

E E

E I~' nodines l131 Cl E

E E

E l133 Cl E

E E

E l-135 Cl E

E E

E TOTAL FOR PERIOD (ABOVE)

Cl E

E E

E 3.

Particulates l

l l

CO-58 Cl E

E E

E SR-89 Cl E

E E

E SR-90 Cl E

E E

E I

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

i o

e-Page 1 81

( )3 ST.L PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

METHODOLOGY SECTION FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #

TABLE 3.8 GASEOUS EFFLUENTS - DOSE SUMMATION - CALENDAR YEAR AGE GROUP: INFANT EXPOSURE INTERVAL: FROM THROUGH BONE LIVER THYROID KIDNEY LUNG ul-LLI WHOLE BODY PATHWAY (mrem)

(mrom)

(mrem)

(mrem)

(mrem (mrem)

(mrem)

Ground Plane (A)

Grass-

-Milk (B)

Inhalation (A)

TOTAL (A)

SECTOR:

RANGE:

miles (B) COW / GOAT SECTOR:

RANGE:

miles NOBLE GASES CALENDAR YEAR (mrad)

Gamma Air Dose Beta Air Dose Sector:

Range:

0.97 miles NOTE The dose values above were calcula'ted using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.

t Page 139 of 181

.r ST. LUCIE PLANT e

I CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 7(-)

- OFFSITE DOSE CALCULATION MANUAL (ODCM) i-NJ

[

S

?

i r

APPENDIX A ECL, DOSE FACTOR

/R15 I

AND l

HISTORICAL METEOROLOGICAL TABLES

.l l

i t

I l

o

P;ge 140 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

,c3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE L-1 EFFLUENT CONCENTRATION LIMITS IN WATER

/R15 IN UNRESTRICTFD AREAS NOT E If a nuclide is not listed below, refer to 1C CFR Part 20, Appendix B, Table 2 Effluent Concentrations Column 2 and use the most conservative ECL listed for the nuclide,

/R15

~

Nuclide ECL ( Ci/ml)

Nuclide ECL (pCi/ml)

Nuclide ECL (pCl/ml)

/R15 H-3 1 E-3 Y-90 7 E-6 Te-129 4 E-4

)

Na-24 5 E-5 Y 91m 2 E-3 Te-131m 8 E-6 P-32 9 E-6 Y-91 8 E-6 Te-131 8 E-5 Cr-51 5 E-4 Y-92 4 E-5 Te-132 9 E-6

)

Mn-54 3 E-5 Y-93 2 E-5 l-130 2 E-5 Mn-56 7 E-5 Zr-95 2 E-5 l-131 1 E-6 Fe-55 1 E-4 Zr-97 9 E-6 l-132 1 E-4 Fe-59 1 E-5 Nb-95 3 E-5 l-133 7 E-6 Co-57 6 E-5 Nb-97 3 E-4 1-134 4 E-4 fg C/

Co-58 2 E-5 Mo-99 2 E-5 l-135 3 E-5 Co-60 3 E-6 Tc-99m 1 E-3 Cs-134 9 E-7 Ni-65 1 E-4 Tc-101 2 E-3 Cs-136 6 E-6 Cu-64 2 E-4 Ru-103 3 E-5 Cs-137 1 E-6 Zn-65 5 E-6 Ru-105 7 E-5 Cs-138 4 E-4 Zn-69 8 E-4 Ru-106 3 E-6 Ba-139 2 E-4 Br-82 4 E-5 Ag-110 6 E-6 Ba-140 8 E-6 j

Br-83 9 E-4 Sn-113 3 E-5 B&-141 3 E-4 Br-84 4 E-4 in-113m 7 E-4 Ba-142 7 E-4

]

Rb-86 7 E-6 Sb-122 1 E-5 La-140 9 E-6 j

Rb-88 4 E-4 Sb-124 7 E-6 La-142 1 E-4 Rb-89 9 E-4 Sb-125 3 E-5 Ce-141 3 E-5 Sr-89 8 E-6 Te-125m 2 E-5 Ce-143 2 E-5 i

Sr-90 5 E-7 Te-127m 9 E-6 Ce-144 3 E-6 Sr-91 2 E-5 Te-127 1 E-4 Pr-144 6 E-4 Sr-92 4 E-5 Te-129m 7 E-6 W-187 3 E-5 Np-239 2 E-5 O

.W O

O O

Page 141 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM /HR PER pCi/ML)

NUCLlDE BONE LIVER THYROID KIDNEY LUNG GI-LLI BODY H-3 0.

3.60E-01 3.60E-01 3.60E-01 3.60E-01 3.60E-01 3.60E-01 NA-24 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 6.08E-01 P-32 1.67E+07 1.05E+06 0.

O.

O.

1.88E+06 6.47E+05 CR-51 0.

O.

3.34E+00 1.23E+00 7.42E+00 1.41 E+03

- 5.59E+00 MN-54 0.

7.07E+03 0.

2.10E+03 0.

2.17E+04 1.35E+03

~

MN-56 0.

1.78E+02 0.

2.26E+02 0.

5.68E+03 3.17E+01 FE-55 1.15E+05 5.19E+05 0.

O.

6.01 E+05 2.03E+05 1.36E+05 FE-59 8.08E+04 1.92E+05 0.

O.

5.32E+04

- 6.33E+05 7.29E+04 CO-57 0.

1.42E+02 0.

O.

O.

3.60E+03 2.36E+02 CO-58 0.

6.05E+02 0.

O.

O.

1.22E+04 1.35E+03 CO-60 0.

1.74E+03 0.

O.

O.

3.26E+04 3.83E+03 NI-65 2.02E+02 2.63E+01 0.

O.

O.

6.65E+02 1.20E+01 CU-64 0.

2.15E+02 0.

5.41E+02 0.

1.83E+04 1.01 E+02 ZN-65 1.62E+05 5.13E+05 O.

3.43E+05 O.

3.23E+05 2.32E+05 ZN-69 3.43E+02 6.60E+02 O.

4.27E+02 0.

9.87E+01 4.57E+01 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution'

- _ - _ _ _ _ _..,__... _.. _ _. _. _ - _. _ _. _ - _. _ _ _ _ _ - _ _ _ _. _.. _. _ _ _ _. _. _ _ _ ~ _ - _. _...

G Y)

Page 142 of 181' ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) s TABLE L-2 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR (MREM /HR PER pCi/ML)

NUCLIDE BONE LIVER THYROID !

KlDNEY LUNG GI-LLI OD BR-82 0.

O.

O.

O.

O.

4.68E+00 4.08E+00 BR-83 0.

O.

O.

O.

O.

1.05E-01 7.26E-02 BR-84 0.

O.

O.

O.

O.

7.38E-07 9.42E-02 BR-85 O.

O.

O.

O.

O.

O.

3.86E-03 RB-86 0.

6.25E+02 0.

O.

O.

1.23E+02 2.91 E+02 RB-88 0.

1.79E+00 0.

O.

O.

O.

9.50E-01 RB-89 0.

1.19E+00 0.

O.

O.

O.

8.38E-01 SR-89 5.01 E+03 0.

O.

O.

O.

8.01 E+02 1.44E+02 SR-90 1.23E+05 0.

O.

O.

O.

1.65E+03 3.02E+04 SR-91 9.43E+01 0.

O.

O.

O.

4.75E+02 4.15E+00 SR-92 3.50E+01 0.

O.

O.

O.

6.91 E+02 1.51 E+00 Y-90 6.07E+00 0.

O.

O.

O.

6.43E+04 1.63E-01 Y-91M 5.74E-02 0.

O.

O.

O.

1.68E-01 2.23E-03 Y-91 8.89E+01 0.

O.

O.

O.

4.89E+04 2.38E+00 Y-92 5.34E-01 0.

O.

O.

O.

9.33E+03 1.56E-02 Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

o o

x.d. y%

m' c.

Page'143 ofl181' ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15.-

l OFFSITE DOSE CALCULATION MANUAL (ODCM)

^

TABLE L-2 l

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES PATHWAY - SALT WATER RSH AND SHELLFISH AGE GROUP - ADULT l

ORGAN DOSE FACTOR -

(MREM /HR PER pCi/ML).

v t

NUCLIDE BONE LIVER l

THYROID KIDNEY LUNG GI-LLI WHOLE BODYs Y-93 1.69E+00 0.

O.

O.

O.

5.36E+04

.4.67E-02 l

ZR-95 1.60E+01 5.13E+00 0,

8.09E+00 -

- 0. -

1.59E+04.

- 3.47E+00 -

~

ZR-97 8.82E-01 1.78E-01 0.

2.69E-01 0.

5.51 E+04 -

. 8.19E-02 -:

NB-95 4.48E+02 2.49E+02 0.

2.47E+02 0.

1.51E+06

. 9.79E+01 -.

~

l NB-97 3.76E+00 9.50E-01 0.

- 1.11 E+00 0.

3.51E+03

- 3.47E-01 l

MO-99 0.

1.28E+02 0.

2.90E+02 0.

. 2.97E+02 2.43E+01 TC-99M 1.30E-02 3.67E-02 0.

5.57E-01 1.80E-02 2.17E+01.

,4.67E TC-101 1.33E-02 1.93E O.

3.47E-01 9.82E O.

1.89E-01 RU-103 1.07E+02 0.

- 0.

4.09E+02 0.

1.25E+04

' 4.61E+01 RU-105 8.90E+00 0.

O.

1.15E+02 0.

5.44E+03 3.51E+00 RU-106 1.59E+03 0.

O.

3.08E+03 0.

1.03E+05.

.2.01E+02 AG-110 1.57E+03

~ 1.45E+03 0.

2.85E+03 -

O.

5.92E+05=

- 8.62E+02 SB-124 2.78E+02 5.23E+00 6.71E-01 0.

2.15E+02

- 7.85E+03 1.10E+02 -

SB-125 2.20E+02 217E+00 1.96E-01 0.

2.30E+04 -

1.95E+03 4.42E+01 -

TE-125M 2.17E+02

-7.89E+01 6.54E+01 8.83E+02 0.

- 8.67E+02

- 2.91E+01 :

Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional ddution i

?

d % v-edi--wa._swww W =aeeawwrWe*ses erWp Puwe

• M he M-hvV+%%=18-witT-us

'mWseSW---o-

'tW'e - et e W + w4'rY war "9-W' mwt WW'W W W 4'At -W rr's-*WerE**WNW

-'D-W-9 44p *4lr e* wew*e -e D Meer twee'em

-e st es'w e D-4-eetdw1" W um hwtuisesee eur t-e w a'e*esee -e 4T ea e.-w' w s a

w-.%m+ch m-m lhe tw ep-M w

a +eir9mr

+

.0019 O

O ~

V

' fy (7

Page_144 of 181?

- ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) l xTABLE L _ <

L ENVIRONMENTAL PATHWAY-DOSE CCK4Z ;3 ION FACTORS FOR LIQUID DISCHARGES '

l PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT j

ORGAN DOSE FACTOR (MREM /HR PER pCi/ML) j l

NUCLIDE BONE LIVER THYROID.

KIDNEY LUNG

- GI-LLI WHOLE BODY TE-127M 5.50E+02 1.92E+02

- 1.40E+02 2.23E+03 0.

1.84E+03 6.70E+01 -

1-TE-127 8.92E+00 320E+00

- 6.61 E+00 3.63E+01 0.

.7.04E+02 -

1.93E+00.

TE-129M 9.32E+02 3.49E+02 3.20E+02 -

3.89E+03 0.

- 4.69E+03 1.48E+02 TE-129 2.55E+00 9.d5E-01 1.95E+00 1.07E+01 -

O.

1.92E+00 8.21E-01 TE-131M 1.41E+02 -

6.87E+01 1.09E+02 -

6.95E+02 0.

6.81 E+03 5.72E+01 TE-131 1.60E+00 6.68E-01

- 1.31 E+00 7.00E+00 0.

2.39E-01 5.04E-01 TE-132 2.05E+03 1.33E+02

- 1.46E+02

.1.28E+03

- O.

- 6.25E+03 1.24E+02 -

i 1130 3.98E+01 -

1.18E+02 1.50E+04 1.83E+02 0.

1.01E+02 4.63E+01.

i 1-131 2.18E+02

- 3.13E+02 1.02E+05 5.36E+02-O.

824E+01 1.79E+02 1-132 1.07E+01 :

2.85E+01 r 3.76E+03 4.55E+01 0.

5.36E+00 -

1.01E+01 l-133 7.51 E+01

-1.30E+02 2.51 E+04 227E+02 0.

1.15E+02 3.98E+01 1-134 5.57E+00 1.51E+01 1.96E+03 2.41E+01 0.

1.32E 5.41E+00-

~

1-135 2.33E401

6.14E+01 8.03E+03

$.77E+01 0.

6.88E+01 225E+01 -

CS-134 6 D.+03 1.63E+04 -

O.

529E+03 1.75E+03 2.85E+02 1.33E+04 '

3 CS-136 7.17E+02 2.83E+03 0.

1.58E+03 2.16E+02 3.22E+02 -

2.04E+03 4

Based on 1 Ci/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

~

F

, _w--Te-Pmy ee %.a w-t

• h e-=-e ew 4pe'w e -e m-e'semew

• W er eiew m._

wi.

h we.ez er o.es nr._mmmq.4-4timeer Wem_h w m-eg.3et+ s twg sywmiy eew mgge 6hwwglyiuse e M131m c& m-hue ? py a-w'M.1 m

tryr' e r='A4N'@= sw W" d2

+h-,kr

.m*mr-u-e-rv tww-ret teee w uu -m

---

m*

e surawwe-e mf %

9mmew eem.tr eenen

-gg g.

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_,>..s y

[.

~

Pagef145 ofI181i ST. LUCIE PLANT-

~

g CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15.

OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE L,

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS FOR UQUKs :MS PATHWAY - SALT WATER FISH AND SHELLFISH AGE GROUP - ADULT ORGAN DOSE FACTOR.

-(MREM /HR PER pCi/ML) i NUCLIDE BONE LIVER.

THYROID -

KlDNEY LUNG GI-LLl-WHOLE BODY CS-137 8.79E+03

- 1.20E+04 0.

4.09E+03 1.36E+03 2.31E+02 7.88E+03 -

CS-138 6.08E+00 1.20E+01 0.

- 8.84E+00 8.73E-01 5.12E-05 5.96E+00 --

BA-139 7.87E+00 5.61 E-03 0.

5.24E-03 3.18E-03 1.39E+01

2.30E-01 BA-140 1.65E+03 -

2.07E+00 0.

7.04E 1.18E+00 -

.3.39E+03 :

1.09E+02 BA-141 0.

2.89E O.

2.68E-03 1.64E-03 1.80E-09

.1.29E-01 --

BA-142 1.73E+00 1.78E-03 0.

1.50E 1.01 E-03.

0.-

1.09E-01 LA-140 1.58E+00 7.95E-01

. O.

O.

O.

5.83E+04-2.11E-011 LA-142 8.07E-02 3.67E-02 0.

O.

O.

- 2.68E+02 9.15E !

CE-141 3.43E+00 2.32E+00 0.-

1.08E+00 0.

8.87E+03 2.83E-01:

CE-143

. 6.05E-01 4.47E+02.

' O.

1.97E O.

1.67E+04

. 4.95E-02.

1 CE-144

.1.79E+02

- 7.48E+01 0.

4.43E+01 -

O.

6.05E+04 -

9.80E+00 PR-144 1.91E-02

'- 7.88E-03 0.

4.45E-03 0.

2.73E 9.85E i W-187 9.17E+00

' 7.68E+00 0.

O.

O.

2.51E+03

- 2.89E+00 l

NP-239 3.56E-02 3.50E-03 ~

0.

1.08E-02.

0.-

7.12E+02 1.92E-03 l

Based on 1 pCi/sec release rate of each isotope in discharge flow of 1 cc/sec with no additional dilution

=

I l

l l

..-_ __. _ _ _ _ __ _ ___. _. _ _ _ _,. _ _ _ _ _ _ _ _ _ _ _ _ _ _... _ _ _ _ _ -. _. - _. _ _ _ _ _ _... _ _ _ _..... _ _ ~ _.. - ~,. _... _. ~, _... _ _ _

Page 146 of 181 y

ST. LUCIE PLANT I

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 gm, OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-1 EFFLUENT CONCENTRATION UMITS IN AIR IN UNRESTRICTED AREAS-

/R15 NOTE If a nuclide is not listed below, refer to 10 CFR Part 20, Appendix B, Table 2 Effluent Concentrations Column 1 and use the most conservative ECL listed for the nuclide.

/R15 Nuclide -

ECL pCi/mi Nuclide ECL Ci/mi Nuclide ECL Ci/ml

/R15 Ar-41 1 E-8 Co-57 9 E-10 Sb-124 3 E-10

/R15~

Kr-83m 5 E-5 Co-58 1 E-9 Sb-125 7 E-10 Kr-85m 1 E-7 Fe-59 5 E-10 Te-125m 1 E-9 I

Kr-85 7 E-7 Co-60 5 E-11 Te-127m 4 E-10 Kr-87 2 E-8 Zn-65 4 E-10 Te-129m 3 E-10 Kr-88 9 E-9 Rb-86 1 E-9 l-130 3 E-9 Kr-89 None Rb-88 9 E-8 l-131 2 E-10 Kr-90 None Sr-89 2 E-10 1-132 2 E-8 i

Xe-131m 2 E-6 Sr-90 6 E-12 1-133 1 E-9 O

Xe-133m 6 E-7 Y-91 2 E-10 1-134 6 E-8 V

Xe-133 5 E-7 Zr-95 4 E-10 1-135_

6 E-9 i

Xe-135m 4E3 Nb-95 2 E-9 Cs-134 2 E-10 Xe-135 7 E-8 Ru-103 9 E-10 Cs-136 9 E-10 Xe-137 None Ru-106 2 E-11 Cs-137 2 E-10 Xe-138 2 E-8 Ag-110 1 E-10 Ba-140 2 E-9 H-3 1 E-7 Sn-113 8 E-10 La-140 2 E-9 P-32 1 E-9 in-113m 2 E-7 Ce-141 8 E-10 Cr-51 3 E-8 Sn-123 2 E-10 Ce-144 2 E-11 Mn-54 1 E-9 Sn-126 8 E-11 O

,. m p

_/

Page 147 of 181 -

ST. LUCIE PLANT

~

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-2 DOSE FACTORS FOR NOBLE GASES

• TOTAL BODY SKIN DOSE FACTOR GAMMA AIR BETA AIR

/R15 OSE FACTOR

(

DOSE FACTOR DOSE FACTOR RADIONUCLIDE K,

M, N,

(mrem /yr per pCi/m )

(mrem /yr per Ci/m')

(mradlyr per pCi/m )

(mrad /yr per pCi/m')

Kr-83m 7.56E-02**

1.93E+01 2.88E+ 02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xo-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xo-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94 E+02 3.06E+02 3.53E+02 1.05E+03 -

Xo-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 122E+04 i

1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents.

4 7.56E-02 = 7.56 X 10

O O

O' Page~ 148 of 181-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P (1) FOR GASEOUS DISCHARGES PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - INFANT ORGAN DOSE FACTOR (SO. METER - MREM /YR PER pCi/Sec)

NUCLIDE WHOLE BODY H-3 0.

CR-51 6.68E+06 MN-54 1.10E+09 FE-59 3.92E+08 CO-57 1.64E+08 CO-58 527E+08 CO-60 4.40E+09 ZN-65 6.87E+08 RB-86 1.29E+07 SR-89 3.07E+04 SR-90 5.94E+05 Y-91 1.53E+06 ZR-95 6.94E+08 NB-95 l 1.95E+08 RU-103 1.57E+08 RU-106 2.99E+08 AG-110 3.18E+09 Based on 1 Cl/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition

.w v.,,,,-,,

~-

..n..n

.--,..--n

,...,,.., - ~

e

,n,-.

Page 149 of 181T ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-3 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS P (I) FOR GASEOUS DISCHARGES PATHWAY - GROUND PLANE DEPOSITION AGE GROUP -INFANT ORGAN DOSE FACTOR (SO. METER - MREM /YR PER pCi/Sec) l NUCLIDE WHOLE BODY SN-126 4.80E+09 SB-124 8.42E+08 SB-125 7.56E+08 i

TE-125M 2.19E+06 TE-127M 1.15E+06 TE-129M 5.49E+07 l-130 7.90E+06

.l-1-131 2.46E+07 l-132 1.78E+06 1-133 3.54E+06 l-134 6.43E+05 l-135 3.66E+06 CS-134 2.82E+09 CS-136 2.13E+08 CS-137 1.15E+09 l

BA-140.

2.39E+08 CE-141 1.95E+07 -

CE-144 9.52E+07 Based on 1 pCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/O and Relative Deposition

--mm_--_m-__.

--mm_-_._

-__m...m___.__m-__.m__m.-___._m.m

.--_.__m

_.m.mm-___

.mm.m-_--__.._ _ _

____m____

_m.-.---____.__._..~.m.

__.____._.mm_..

{

' ?]

Page 150 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-4 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R ft) FOR GASEOUS DISCHARGES PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - CHILD - TEEN-ADULT & INFANT ORGAN DOSE FACTOR.

(SO. METER - MREM /YR PER pCi/Sec)

NUCLIDE WHOLE BODY H-3 0.

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

1.36E+08 RU-103 1.10E+08 RU-106 4.19E+08 -

l AG-110 3.58E+09 i

Based on 1 pCi/sec release rate of each isotope in and a Value of 1. for X/O, depleted X/Q and Relative Deposition

O O

O Page 151 of 181-. '

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-4 s

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R (1) FOR GASEOUS DISCHARGES -

PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - CHILD - TEEN-ADULT & INFANT ORGAN DOSE FACTOR (SO. METER - MREM /YR PER pCi/Sec)

NUCLIDE WHOLE BODY SN-126 5.16E+10 SB-124 5.98E+0B SB-125 2.30E+09 -

TE-125M 1.55E+06 TE-127M 8.79E+05 TE-129M 3.85E+07 l-130 5.53E+06 l-131 1.72E+07

~

I-132 1.25E+06 l-133 2.48E+06 l-134 4.50E+05 1-135 2.56E+06 CS-134 6.99E+09 CS-136 1.49E+08 CS-137 1.03E+10 i

BA-140 1.68E+08 CE-141 -

1.37E+07 CE-144 1.13E+08 Ci/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition Based on 1 l

. ~..

O O

U1

. ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-5 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS RGWPG) FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - INFANT.

ORGAN DOSE FACTOR (MREM /YR PER pCi/Cu Meter)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H-3 0.

4.30E+02 4.30E+02 1.88E+02 4.30E+02 4.30E+02 4.30E+02 P-32 2.31 E+05 1.35E+04 0.

O.

O.

1.51E+04

- 8.78E+03.

CR-51 0.

O.

1.40E+01 -

3.99E+00 2.52E+03 5.81 E+02 1.75E+01 MN-54 0.

6.93E+03 0.

1.72E403 2.45E+05 1.35E+04 1.10E+03 FE-59 2.06E+03 4.86E+06 0.

O.

1.78E+05 3.29E+04 1.85E+03 CO-57 0.

1.21E+02 0.

O.

6.47E+04-

. 5.50E+03 1.18E+02 CO-58 0.

1.18E+02 0.

O.

8.79E+05 1.21 E+04 1.6F, N CO-60 0.

8.40E+0E 0.

O.

5.57E+06 3.28E+04

- 1.17E+03 ZN-65 5.67E+03

- 1.81 E+04 0.

1.21E+04 1.53E+05 9.35E+03 8.15E+03 RB-86 0.

2.37E+04 0.

O.

O.

2.91 E+03 1.03E+04.

SR-89 4.31 E+04 0.

0. -

O.

2.31 E+06 6.80E+04 1.24E+03 SR-90 1.32E+07

- O.

O.

O.

1.53E+07 1.39E+05 8.06E+05 Y-91 5.98E+04 0.

O.

O.

2.63E+06 7.17E+04 -

1.60E+03 ZR-95 1.08E+04

- 2.73E+03 0.

9.48E+03 1.81 E+06 1.41 E+04 1.95E+03 NB-95 128E+03

- 5.75E+02-O.

1.35E+03 4.77E+05

- 1.21 E+04 3.37E+02 -

RU-103 1.69E+02 0.

. O.

1.02E+03.

5.66E+05 1.58E+04 -

5.85E+01

~

RU-106 9.31 E+03 0.

O.

2.34E+04

-1.50E+07 1.76E+05

-1.14E+03 AG-110 1.89E+03 1.75E+03 0.

3.44E+03 8.12E+05

. 5.29E+04-1.04E+03 Based on 1 Ci/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition I

i s

w,a=s,-+ww+

--e w w-w.-,vns,v==w4<-w, vw n y

,w, v e uw,

's--

w me-- e r

-'e--

m c---eme.',

w= = ew w e i e' w-aaw +- e

==t, w+-re-

.s-*

no-*

-e**=

-w-w+=*,e-++,v------+-,

s -m+e-*un se%w=.,

we ~

-*wm* - - - = =-v--+--

m-e e - en-

-

=---m-a --

u*-+

~

^ ~ ~

w=m7 p g x'

l' 11.. %

Page1153 of=181i :

ST. LUCIE PLANT

-* l CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL 10DCM)

T TABLE G-5 i

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS RGWPm FOR GASEOUS DISCH.^"**

PATHWSY - INHALATION

' AGE GROUP -INFANT ORGAN DOSE FACTOR

. (MREM /YR PER pCi/Cu Meter) i NUCLIDE BONE LIVER TMYROID KIDNEY LUNG-

. GI-LLI WHOLE BODY l

^

SN-123 3.11E+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 1.72E+03 0.

1.64E+06 2.23E+04 8.40E+C1 SB-124 5.46E+03 1.03E+02 1.32E+01 0.

4.34E+05

.7.11 E+04.

2.17E+03 SB-125 1.16E+04 1.25E+02 1.03E+01

- O.

3.85E+05 -

1.76E+04 2.32E+03 -

l TE-125M 4.54E+02 1.95E+02 1.53E+02 2.17E+03 4.96E+05

.1.36E+04

' 6.16E+01 -

z; TE-127M 2.21E+03 9.83E+02 5.75E+02 8.01E+03 1.68E+05

- 2.62E+04

. 2.74E+02 -

~ "

TE-129M 1.32E+03 5.80E+02 5.08E+02 6.40E+03 1.83E+06 7.32E+04 2.06E+02 -

l l-130

- 8.02E+02 2.35E+03

- 3.05E+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 -

2.51E+04 l-132

. 2.03E+02

- 5.70E+02 7.67E+04 9.09E+02 0.

7.11 E+01 2.03E+02 l-133 1.34E+04 1.93E+04

-4.66E+06.

4.55E+03 0.

2.28E+03 x 5.87E+03 i

l l-134 1.13E+02 3.02E+02 4.02E+04 4.82E+02 0.

1.76E-01 1.08E+02 1-135 4.70E+02 1.22E+03 1.64E+05 1.95E+03 0.

9.18E+02.

. 4.51E+02 -

CS-134 4.80E+05 8.25E+05 O.

5.04E+04 1.01 E+05 1.37E+03 -

7.32E+04 i

}

CS-136 6.85E+03

- 2.56E+04 O.

1.50E+04 2.10E+03 2.04E+03 1.95E+04 -

CS-137 -

6.86E+05 7.31E+05

0. -

' 3.89E+04.

9.45E+04 1.32E+03 4.41E+04

]

BA-140 5.70E+03 4.27E+00 O.

2.93E+00 1.64E+06 3.88E+03 -

- 2.95E+02 l

CE-141 2.52E+03 1.55E+03 0.

1.10E+03 5.24E+05.

2.06E+04

.1.81E+02 1

CE-144 4.68E+05 -

1.82E+05

- O.

1.48E+05

' 1.27E+07-1.61E+05 2.49E+04 :

4 Based on 1 pCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition l

1 9

4

,,.,,-----em

-ir.+-,-

i.e

-ie.....e.-m-am.-.--.w-a-_-.a..-,w.ena.

-,.mumerw.w--,m=ce-,rer-,-w.-e-e.u+e-e.-wewe...-si.,,,em.wge..,rr-.-e,-.--ermw-,a--er..i-.ver=s.mm-----e.,%-,s.w-~rn,-...,c_

w.__c,,_m_-_=..s%.s-wae-m_m w-a..t.mm

' Page'.154 of '181l ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE G-6 ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R0l!PM FOR GASEOUS DISCHARGES PATHWAY - COWS MILK (CONTAMINATED FORAGE)

AGE GROUP - INFANT ORGAN DOSE FACTOR (SO. METER - MREM /YR PER pCi/Sec)

NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY H-3 0.

2.37E+03 2.37E+03 1.04E+03 2.37E+03 2.37E+03 2.37E+03 P-32 1.82E+10 1.14E+09 0.

O.

O.

2.05E+09 7.05E+08 CR-51 0.

- O.

1.82E+04 6.72E+03 4.04E+04 7.66E+06 3.05E+04 MN-54 0.

8.96E+06 0.

2.67E+06 0.

2.74E+07 1.71 E+06 FE-59 3.17E+07 7.52E+07 0.

O.

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

1.36E+06 0.

O.

O.

3.46E+07 -

2.27E+06 CO-58 0.

2.55E+07 0.

O.

O.

6.60E+07 6.24E+07-CO-60 0.

8.73E+07 0.

O.

O.

2.16E+08 2.09E+08 ZN-65 1.46E+09 4.65E+09 0.

3.11 E+09 0.

2.93E+09 2.10E+09 RB-86 0.

2.77E+09 0.

O.

O.

5.45E+08 1.29E+09 SR-89 1.47E+10 0.

0. -

O.

O.

2.75E+08 4.22E+08 SR-90 1.65E+11 0.

0.

O.

O.

1.61 E+09 4.21 E+10 Y-91 8.12E+04 0.

O.

O.

O.

5.37E+06 2.16E+03 -

i ZR-95 2.12E+05 9.41 E+04 0.

1.86E+04

0. -

7.47E+07 5.56E+04 NB-95 5.49E+05 2.47E+05 O.

4.84E+04 0.

1.98E+08 1.45E+05 RU-103 8.30E+03 0.

O.

4.16E+03 0.

1.04E+05 2.86E+03 RU-106 2.01 E+05 O.

O.

4.20E+04 0.

1.56E+06 2.46E+04 AG-110 6.21 E+07 5.75E+07 0.

1.13E+08 0.

2.35E+10 3.42E+07 Based on 1 pCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/O and Relative Deposition -

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

,, yy

_g g',. s

[3 n..

U$g*

c s 'l c

.-r W9

.... Wg f y Page1155lof 181 ST. LUCIE PLANT

, y CHEMISTRY OPERATING PROCEDURE-NO. C-200, REVISION 15

+

OFFSITE DOSE CALCULATION MANUAL (ODCM)

J TABLE G-6

~.

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS RmRI) FOR GASEOUS DISCI"L"mt PATHWAY - COWS MILK (CONTAMINATED FORAGE)

AGE GROUP -INFANT ORGAN DOSE FACTOR

' (SO. METER - MREM /YR PER pCi/Sec) ;

NUCLlDE BONE LIVER -

THYROlO KIDNEY LUNG GI-LLI WHOLE BODY-SN-126 1.75E+09

. 3.48E+07 1.01 E+07 0.

4.97E+06 1.16E+09 5.25E+07 j

7.78E408

' 1.09E+07 --

SB-124

. 2.75E+07

- 5.19E+05

- 6.64E+04 0.

2.13E+07-

~

SB-125 3.59E+07 3.27E+06 2.93E+06 3.96E+06 2.83E+09 2.43E+08

' 6.62E+06 TE-125M 1.57E+08 5.30E+07 5.18E+07 7.05E+07 0.

7.57E+07--

2.10E+07 -

~

TE-127M 5.54E+07 1.93E+07 1.79E+07

- 2.00E+08 0.

-3.24E+08 7.38E+06 TE-129M 5.87E+08 2.02E+08

.- 2.21E+08 -

2.70E+08 0.

3.54E+08.

8.95E+07.

I-130 4.54E+05 1.35E+06 1.71E+08

2.09E+06 0.

1.15E+06 5.29E+05 l-131 2.59E+09 3.09E+09 9.94E+11 7.24E+08 0.

1.16E+08

- 1.81E+09 -

I-132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0.

- 8.93E-02 1.69E l-133 3.75E+07 5.48E+07-1.30E+10 1.29E+07 O.

9.74E+06 1.66E+07 -

1-134 0.

O.

1.06E-09 0.

O.

0.

O.

1-135 1.49E+04 3.94E+04

~ 5.15E+06 6.26E+04 -

8.07E-02 4.41E+04 :

1.44E+04.

CS-134 4.43E+10 7.97E+10

, 0. -

4.65E+09 9.12E+09 1.90E+08 6.75E+09 CS-136 2.78E+08 1.10E+09 -

O.

6.11E+08 8.37E+07 s 1.25E+08 7.90E+08 -

CS-137 6.44E+10 7.21 E+10

- O.

3.66E+09 8.69E+09 z 1.86E+08 4.14E+09 BA-140 2.45E+08.

. 2.47E+05 -

O.

1.22E+04 1.51E+05

~ 8.13E+06.

1.27E+07:

- CE-141 2.65E+05

' 1.62E+05 O.

9.72E+03 0.

- 7.87E+07 -

1.90E+04 CE-144 2.10E+07 8.29E+06 -

O.

5.67E+05 O.

8.06E+08 1.13E+06.-

Based on 1 pCi/sec release rate of each isotope in and a value of 1. for X/Q, depleted X/Q and relative deposition.

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

f m

f-j pgym

.m O

O fxya;$gi) p:% g 7

by ya w

,c.

p

.~

r

Page 156a1811 ST. LUCIE PLANT

~

~ ~. ~

"i CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) w y

TABLE G-7 ENVIRONMENTAL PATHWAY-DOSE CONversiNON FACTORS RGilPG) FOR GNnUS DISCH^.Fm '

l PATHWAY - GOATS MILK (CONTAMINATED FORAGE)

AGE GROUP -INFANT i

ORGAN DOSE FACTOR (SO. METER - MREM /YR PER pCi/Sec)

NUCLIDE BONE LIVER THYROlD KIDNEY LUNG GI-LLI WHOLE BODY H-3 0.

4.84E+03 4.84E+03

- 2.11 E+03 4.84E+03 4.84E+03.

4.84E+03 '

P-32 2.19E+10 1.37E+09 0.

O.

O.

2.46E+09

- 8.46E+08 -

_~

~ CR-51 0.

O.

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 O.

3.29E+06 2.05E+05.

FE-59 4.12E+05 9.78E+05 O.

O.

2.72E+05 3.23E+06 -

3.72E+05 l

CO-57 0.

- 1.64E+05 O.

- O.

O.

4.15E+06 2.72E+05 CO-58 0.

3.06E+06 0.

O.

O.

7.92E+06

- 7.49E+06 -

i CO-60 0.

1.05E+07 0.

O.

O.

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

. O.

-O.

O.

6.54E+07 -

1.55E+08 -

SR-89 3.09E+10 -

O.

O.

O.

O.

-- 5.77E+08 -

8.87E+08 =

i SR-90 3.46E+11 -

O.

O.

- O.

O.

3.35E+09 8.83E+10 Y-91 9.74E+03

. O.

O.

O.

O.

6.45E+05 2.80E+02 ZR-95 2.54E+04 1.13E+04

0. -

2.23E+03 0.

8.95E+06 -

- 6.67E+03 NB-95 6.59E+04 2.97E+04.

0. -

. 5.81E+03 0.

2.37E+07 -

1.75E+04.

RU-103 9.96E+02 0.

O.

4.99E+02 0.

1.24E+04 3.43E+02 -

I RU-106 2.41 E+04 0.

O.

5.04E+03 =

O.

1.87E+05 2.96E+03 -

AG-110

- 7.45E+06 6.90E+06 0.

1.36E+07 0.

- 2.81 E+09 4.10E+06 3.

l; Based on'1 pCi/sec release rate of each isotope in and a Value of 1. for X/Q, depleted X/Q and Relative Deposition Note: The units for C-14 and H-3 are 1 MREM /Yr per pCi/Cu rneter.

- -. i n -., -

n..

a---

n,-... n _,, -.+.

-n a- >-.-.,i: ~

e-.

4 -

.---.------.,-----.-L-~.-..w---:.~i-..---~-LL'2

w

?,

3 <

..[^

7

/

4

Page 157 of 181/3

x ST. LUCIE PLANT

- CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 '

OFFSITE DOSE CALCULATION MANUAL (ODCM)

. TABLE G-7; a

ENVIRONMENTAL PATHWAY-DOSE CONVERSION FAsivR5 RGWPm FOR GASEOUS MW'?.RGES -

PATHWAY - GOATS MILK (CONTAMINATED FORAGE)

AGE GROUP -INFANT l

ORGAN DOSE FACTOR (SQ. METER - MREM /YR PER pCi/Sec).

NUCLIDE BONE LIVER THYROID

- KIDNEY -

LUNG-GI-LLI WHOLE BODY SN-126 2.10E+08 4.17E+06 1.22E+06 0.

5.97E+05 1.40E+08 -

6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0.

2.56E+06 9.33E+07

- - 1.30E+06

- a SB-125 -

4.31 E+06 3.92E+05 3.52E+05 4.76E+05 3.40E+08

- 2.92E+07 -

- 7.94E+05 -

TE-125M 1.89E+07 6.36E+06 6.21E+06 8.46E+06

- O.

9.09E+06 2.52E+06 TE-127M 6.64E+W 2.31 E+06 2.15E+06

. 2.40E+07 0.

3.88E+07

- 8.85E+05 TE-129M 7.05E+07 2.42E+07 2.66E+07 3.23E+07

- O.

. 4.25E+07 1.07E+07 1-130 5.45E+05 1.61E+06 -

2.05E+08 2.51E+06 0.

1.38E+06 6.35E+05 -

1-131 3.11 E+09 3.70E+09 1.19E+12 9.28E+08 0.

1.39E+08 -

- 2.17E+09 :

1-132 2.13E-01

- 5.71 E-01 7.51 E+01_

9.10E-01

- 0. -

1.07E - 2.03E-01 1-133 4.50E+07 6.57E+07 1.55E+10 1.55E+07 0.

1.17E+07 1.99E+07 1-134 0.

O.

1.27E-09 0.

O.

. O.

- O.

1.73E+04 -

1-135 1.79E+04 4.72E+04 6.18E+06 7.51 E+04 -

2.42E-01

• 5.29E+04 CS-134 1.33E+11 2.39E+11 0.

1.39E+10 2.74E+10 -

5.69E+08 2.0PE+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+10 2.61E+10 5.59E+08

-- 1.24E+10 4

BA-140 2.95E+07 2.96E+04 0.

1.4h.+03 1.81E+04 9.76E+05

- 1.52E+06 CE-141 3.17E+04 1.95E+04 0.

1.17E+03 0.

.9.44+06 2.28E+03 i

CE-144 2.52E+06 9.95E+05 O.

6.80E+04 -

0. -

~1.04E+08 -

1.36E+05 -

Based on 1 pCi/sec release rate of each isotope in and a value of 1. for X/Q,' depleted X/Q and relative deposition.,

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

~

%ew_am.s.--,

i.-*-n=-%.r*res-=+=ewwme -wis, we e e===+e-3-=--.ea=e-use.wwe ar* -

-am, e n *.4 - e +. wai&.a w mw*c'e wesre 'm

'm -wee w owemw -

._r--we,--se-*w-sm.-

an===ee vee **ar e =*

mmm anse ensim e m < - e + es we +ic = ae w

-r-su - u--ww

• • m+ tw e a w emi uma==.,mu -eva a vwin

• m p;g,~158 of 181 f<

. 'ST. LUClE PLANT l

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

/h OFFSITE DOSE CALCULATION MANUAL (ODCM)

() ~,

i TABLE M-1 l

._ Selecting the Appropriate Long Term (X/Q) for Dose Calculations involving Noble Gases for:1 (1)

Total Body dose from instantaneous releases

/R15 j

i (2) _ Skin dose from instantaneous releases (3)

Gamma air. dose (cumulative) y (4)

Beta air dose (cumulative) l TYPE OF DOSE LIMITING LIMITING (X/Q) VALUE 8

CALCULATION RANGE (miles)

Sector sec/m.

Instantaneous 0.97

-NW 1.6 X 10' i

1/31 days 0.97 l

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

j 4

Quarter 1y -

0.97 l

Yearty

2. May use option of actual l

O

'2 c c ' -

o.a7

- ' ' ' aic ' d * ' "'-

l months concem.

Annual Report 0.97 N/A Note-1 NOTE 1 The (X/Q) has to be calculated based on actual meteorological data that i

occurred during the period of interest. The sector'of interest is N/A because j

the limiting (X/Q) will be determined from the actual meteorological data'and 1

may occur in any sector.

0.97 miles Corresponds to the minimum site boundary distance in the north direction and 0.97 miles was chosen for all other sectors for' ease of calculations when the averaging is donc for quarterly reports.

l l

l l

l l

O

, _ _ _.I

f Pcge 159 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 73 OFFSITE DOSE CALCULATION MANUAL (ODCM)

.\\J U

. TABLE M-2

Selecting the Appropriate Long Term (X/Q)o or (D/Q) for Dose I

i

' Calculations involving Radioiodines & 8 D Particulates for:

1

'(1) Inhalation (2) Tritium (All gas pathways)

(3) Ground Plane TYPE OF DOSE LIMITING LIMITING SECTOR l

)o W rn' (DC) 1M

.(

s CALCULATION RANGE (miles)

(OL) 4 instantaneous 0.97 1.3 X 10 WNW 8.2 X 10 Ouarterly for 0.97 A

A, B Annual Reports 0.97 A

A 1/31 days' B

O.97 NW Otr. yearly, 1.3 X 10 _

0.97 WNW 8.2 X 10-'

l To al ose O'-

(OL) Over land areas only i

(A) To be determined by reduction of actual met data occurring during each quarter

.(B) For Tritium in the Milk Animal Pathway, the (X/Q)o value should be that of the respective controlling sector and range where the Milk Animal is located as per Table M-3. Example: If a cow was located at 4.25 miles in NW sector, use the (X/Q)o for 4.25 miles NW.

i 0

3 i

J

^'%

Pcge 160 of 181 j

, i e@

f JST. LUCIE PLANT w

CHEMISTRY OPERATING PROCEDURE'NO. C-200, REVISION 15.

~ ' ~

M :^

e 1)

' OFFSITE DOSE CALCULATION MANUAL (ODCM)

.i

~

TABLE M-3 l

Selecting the Appropriate Long Term (D/Q) for Dose Calculations involving

,1 Radioiodines and 8D Particulates for Grass-Cow-Milk or Grass-Goat-Milk:

l w

-(D ah LIMITING RANGE LIMITING SECTOR C

Reisese Rate -

.A A

A:

i l

1/31 Days

-B-B

-B Quarterly - Yearly B

B B

Annual (Calendar Year)

B.

B B

.j Annual Report C

C C

L A.

The worst cow or goat as per locations from land census. If no milk' animal in l

any sector, assume a cow at 4.25 miles in the highest (D/Q) sector over land.

.j l

B.

The historical (D/Q) of all land sectors with the worst cow or goat from each.

i sector as reported in the Land Census. A 4.25 mile cow should be assumed in the worst sector over land when no milk animal is reported.

C.

The highest (D/Q) at a milk animal location of all milk animals reported in the Land Census Report. (if no mllk 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 -

l land). Actual Met Data should be used for the selection of the worst case milk I

animal and for the dose calculations. If both goat and milk animals are reported inside 5 miles, dose calculations shou ld be performed on each animal j.

and the higher dose animal contribution should be used.

i The historical wind frequency fractions for each sector are listed in Table M-8.

.j

'l I

i O

1 i

i

. ~

gy

[.

5'

~

~

LPageL161 Af[181~ '

ST. LUCIE PLANT

'1 CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE M-4

~

TERRAIN CORRECTION FACTORS Florida Power & Light Company St. Lucie Unit 1 Terrain' Correction Factors (PUFF / STRAIGHT LINE)-

Hutchinson Island, Florida Period of Record: 8/29/77 to 8/31/78 Dames and Moore Job No: 4598 - 112 Base Distance in Miles / Kilometers DESIGN AFFECTED DISTANCE

.25

.75 125 1.75 2.25 2.75 325 3.75 425 4.75 SECTOR MILES

.40 1.21 2.01-P.82 3.62 4.42 523 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 1259 1.164 1.128 1.101 1.116 f"

^

ENE 0.

1.452

'1230

-1.122 1.081 1.047 1.033

.941

.941

.906

.902 E

0.

1.662 1.425 1.277 1.193 1.151 1.123 1.097 1.121 1.123 1.122 ESE 0.

1.690 1.483 1.328 1.260 1246 1.190 1.134 1.094 1.032

.968 SE 0.

1.818

-1.691 1.470 1.427 1.435 1.361 1.366 1.331 1.279

-1.239 SSE 0.

1.812 1.586 1.370 1.302 1.270 1.263 1.229 1.193 1.171 1.151 S

0.

1.396 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 1.000

~

SW 0.

1.685 1.492 1.294 1233 1.200 1222 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 1.290 1218 1.154 1.099 1.081

-1.067 1.093

-1.083 L

WNW 0.

1.720

-1.430 1267 1.185 1.150 1.133

.1.125 1.085 1.033 11.045 NW 0.

1.681 1.407 1.257 1.173 1.119 i1.078 1.063

.995

.998

.978 NNW 0.

1.739

1.488 1.316

~ 1.212

-1.172 1.122 1.135 1.080 1.099 1.091 N

. O.

1.816 1.524 1.389 1.285 1.257 1.263 1.285

1267 1231

'1.213 l

l Note 1:

Any interpolations between stated mileages will be done by log-log; l'

i-l u

L

- OM O

O g

p ST. LUCIE PLANT

~'

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15' OFFSITE DOSE CALCULATION MANUAL (ODCM) h TABLE M-5 HISTORICAL LONG TERM - 000) (Frequency corrected)

Terrain / Recirculation Adjusted Program ANNXOQ9 -Version '11/18/76 Florida Power & Light Company H

SL Lucie Unit 1 Average Annual Relative Concadiation (sec/ cubic meter) _

Hutchinson Island, Florida Period of Record: 9/1/76 to 8/31/78 Dames and Moore Job No: 1.4598 112 Base Distance in Miles / Kilometers DESIGN AFFECTED DISTANCE

.25

.75 1.25 -:

1.75 2.25 2.75 3.25 3.75 -

4.25 i L 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.

1.1 E-05 1.7E-06 7.8E-07 4.5E-07 3.1 E-07

- 2.2E-07 1.7E-07 1.5E-07 1.2E-07 1.0E-07 y

NE 0.

1.3E-05 2.1E-06

> 8.9E-07 5.1 E-07 3.4E-07 2.4E-07 1.7E-07 1.4E-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 1.1E-07 8.8E-08

'7.5E-08 E-O.

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 3.2E-07 2.4E-07 1.8E-07 1 1.4E-07 1.1E-07

- 9.0E-06 ESE 0.

1.2E-05 1.9E-06 8.1E-07 4.8E-07 1.4E-07 1.2E-07 SE 0.

1.4E-05 2.4E-06 9.7E-07 5.7E-07 4.0E-07

- 2.9E-07

- 2.3E-07 1.9E-07 SSE 0.

1.1 E-05

1.7E-06 7.3E-07 4.3E-07 2.9E-07 2.1 E-07 1.6E-07 1.3E-07

. 1.1E-07 9.1E-08 1.8E-07

- 1.4E-07 1.0E-07 8.0E-08

- 6.6E-08 5.5E-08 S

. O.

6.25-06 1.0E-06 4.2E-07 2.5E-07 SSW 0.

5.7E-06 9.0E-07 4.0E-07 2.3E-07 1.6E-07 1.1E-07 8.9E-08 7.0E-08

~ 5.7E-08 4.8E 06 SW 0.

' 6.1E-06 9.4E-07 3.9E-07 2.2E-07

- 1.6E-07 1.1 E-07

- 8.6E-08 7.0E-08 6.0E-08 5.1E-08 WSW 0.

7.3E-06 1.1E-06 4.6E-07 2.7E-07 1.7E-07 1.3E-07 1.0E-07 8.0E-08

, 6.5E-08

- 5.4E-08 b

W

' O.

7.6E-06 1.2E-06 5.2E-07 2.9E-07

- 2.0E-07 1.3E-07 1.0E-07

- 8.4E-08 7.2E-08 6.1E-08 WNW 0.

1.4E-05 2.1E 06 9.1E-07 5.2E-07

-3.4E-07

- 2.6E-07 2.0E-07 1.5E-07 1.2E-07

'1.0E-07 NW 0.

1.6E-05 2.4E-06 1.0E-06 5.9E-07

-3.9E-07 2.8E-07 2.1E-07 1.7E-07 1.4E-07 1.2E-07 NNW 0.

1.5E-05

- 2.2E-06 9.6E-07

< 5.5E-07

- 3.6E-07 2.6E-07

' 2.0E-07 1.6E-07 1.3E-07 1.2E-07 N

. O.

9.1 E-06 1.4E-06 6.3E-07 3.6E-07 2.4E-07 1.8E-07 1.4E-07 1.2E-07 9.4E-08

- 7.9E-08 Number of Valid Observations = 17135

- Number of Calms Lower Level = 95

' 7-Number of invalid Observations = 385 :

Number of Calms Upper Level = 0 -

Note 1 - Any interpolations between stated mileages.will be done by log-log :

___.-.m._

m.s.___m-.__a..i___..

-__,__a.__.a.__m_

_____m__

a-

_a__.e-.A

-..m__m____-_____._mm.._

a__-___..

i____._-___

__..m.-_m__-__.____.__-

______-_m MJan

-maa2.

O O

7 wg cs

, Q; w;.cq Pagel163 ofL1811; -[

ST. LUCIE PLANT

~

4 N

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 W

OFFSITE DOSE CALCULATION MANUAL (ODCM)

- TABLE M 6 HISTORICAL LONG TERM DEPLETED -(X/QL (Frecuency corrected).

Terrain / Recirculation Adjusted Program ANNXOQ9 Version '11/18/76 -

Florida Power & Light Company St. Lucie Unit 1 Average Annual Relative Concentration Depleted (sec/ cubic meter);

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

- 3 O

DESIGN AFFECTED DISTANCE

.25

.75 1.25 1.75 2.25 2.75 3.25 3.75

-425I 4.75 J 1

SECTOR MILES

.40 1.21 2.01 2.82 3.62:

4.42 523 6.03 6.84

7.64 79 NNE 0.

1.1 E-05 1.6E-06 6.6E-07

- 3.8E-07 2.4E-07 1.7E-07 1.3E-07 1.1E-07 9.2E-08 7.6E-08 NE 0.

12E-05 1.7E-06 7.6E-07 4.3E-07 2.8E-07 1.9E-07 1.4E-07 1.1 E-07 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-08 6.6E-08

' 5.6E-08 E

0.

- 9.1E-06 1.3E-06

' 5.6E-07 3.1 E-07 2.1 E-07 1.5E-07 1.1 E-07 9.1 E-08 7.5E-08 6,3E-08 ESE 0.

12E-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 82E-07 4.7E-07 3.3E-07 2.3E-07 1.8E-07 1.3E-07 1.1E-07 9.0E-08 SSE O.

1.1 E-05

- 1.6E-06 6.3E-07 3.5E-07 2.4E-07 1.8E-07 1.4E-07 1.0E-07 82E-08 6.dE-08 9

S 0.

5.9E-06

- 9.1E-07 3.6E-07 2.1E-07 1.4E-07 1.1E-07

- 7.7E-08 62E-08

- 5.0E-08 4.1E-08 SSW 0.

5.4E-06 8.0E-07 3.4E-07 1.9E-07 1.3E-07 8.9E-08 6.9E-08

- 5.5E-08

- 4.3E-08 3.6E-08 SW 0.

5.7E-06 8.4E-07 3.4E 07

1.88-07 12E-07

. 9.2E-08 6.7E-08 5.3E-08 4.6E-08 3.8E-08 a

WSW 0.

7.0E-06 9.6E-07 4.0E-07 22E-07

- 1.4E-07 1.0E-07 8.0E-08 6.1E-08 5.0E-08

4.0E-08 W

0.

7.3E-06 1.1 E-06

- 4.4E 07 2.4E-07 1.6E-07 1.1 E-07 8.2E 08 6.4E-08 5.5E-OS 4.4E-08 WNW 0.

1.3E-05

- 1.9E-06 7.9E-07 4.4E-07

- 2.9E-07 2.0E-07 1.6E-07 1.2E-07 9.3E-08 7.8E-08 NW 0.

1.5E-05 2.1 E-06 8.9E-07 4.9E-07 3.1 E-07 2.3E-07 1.7E-07 1.3E-07

-1.0E-07

- 8.5E-08 NNW 0.

1.4E-05 2.1E-06

- 8.3E-07 4.5E-07

- 2.9E-07 2.0E-07 1.6E-07

- 12E-07 1.0E-07 8.6E-08 N

0.

8.7E-06 1.3E-06 5.4E-07 3.0E-07 2.0E-07 1.4E-07 1.1 E-07 8.9E-08 7.0E-08 5.8E-08 Number of Valid Observations = 17135

. Number of Calms Lower Level =' 95 Number of Invalid Observations = 385 Number of Calms Upper Levei ='O

- Note 1 - Any interpolations between stated mileages will be done by log-log

,,,s

.s.:

?

-~~.~-%

.. m

,b,

.m,_,,_m

((

1

,m

,a NIff M

%-/ %

.y-:

... 1 Page1164 of 81L '

^

- ST. LUCIE PLANT m

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

- ~

_ m.

OFFSITE DOSE CALCULATION MANUAL (ODCM) '

I

. TABLE M-7 HISTORICAL LONG TERM - (DMM (Freauency correctedF 4

TERRAIN / RECIRCULATION ADJUSTED PROGRAM ANNXOQ9 VERSION - 11/18/76 1m Florida Power & Light Company St. Lucie Unit 1

. Average Annual Relative Deposition Rate (square meter - 1) -

~

Hutchinson Island, Florida Period of Record: 9/1/76 to 8/31/78

~

Dames and Moore Job No: 4598.112 Base Distance in Miles / Kilometers cm DESIGN AFFECTED DISTANCE

.25

'.75.

'125 1.75 2.25 2.75 3.25 3.75 425 4.75 l 4

SECTOR MILES

.40 1.21

- 2.01 2.82 -

3.62 4.42 5.23 6.03 6.84 7.64 NNE 0.

6.5E-08

-9.3E-09 3.7E-09 2.1 E-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 12E-09 8.1 E-10 5.6E-10 4.3E-10 3.3E-10

' 2.8E-10 ENE 0.

32E-08 4.8E-09 1.9E-09 1.0E-09 6.6E-10 4.6E-10 3.2E-10 2.4E-10 1.9E-10

- 1.5E-10 E

0.

3.0E-08 4.6E-09 1.8E-09 9.5E-10 6.0E-10 42E-10 3.1E-10 2.5E-10

-2.0E-10 1R-10 ESE 0.

- 3.7E-08

- 5.8E-09

- 2.3E-09 12E-09 8.0E-10 5.4E-10

- 3.9E-10 3.0E-10 22E-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 SK-10 4.3E-10 3.5E-10 1.2E-09 8.7E-10 6.4E-10 4K-10 3.9E-10 3.1E-10 SSE 0.

6.2E-08 9.5E-09 3.6E-09 2.0E-09 S

0.

- 42E-08 7.0E-09

= 2.6E-09 1.4E-09 9.5E-10

- 6.9E-10 4.9E-10 3.8E-10 3.0E-10

- 2.5E-10

- j SSW 0.

3.4E-08 5.4E-09 22E-09 1.1 E-09 7.5E-10

- 5.0E-10 3.7E-10 2.9E-10

' 2.3E-10 1K-10 y

SW O.

4.5E-08 7.0E-09 2E-09 1.5$-09 9.0E-10 6.6E-10 4M-10

-3K-10

-3.0E-10 2.5E-10 WSW 0.

5.3E-08

- 7.7E-09 3.0E-09 1.6E-09 1.0E-09 7.3E-10 5.5E-10 4.1E-10 3.3E-10 2.6E-10 W

0.

5.0E-08

. 7.5E-09 3.0E-09 1.6E-09 9.8E-10 6.7E-10 5.0E-10 3.8E-10

'3.2E-10

- 2.6E-10 4

WNW 0.-

- 8.8E-08 1.3E-08 4.9E-09 2.6E-09 1.7E-09 1.1 E-09 8.7E-10 6M-10 5.1E-10 42E-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 SK-10 4.7E-10 3.8E-19 NNW 0.

8.2E-08 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.1 E-09 8.1 E-10 5.9E-10 4.8E-10 4.0E-10 N.

O.

- 5.1 E-08

-7.3E-09 2.9E-09 1.5E-09 9.8E-10 7.1 E-10 5.4E-10 4.2E-10 32E-10 2.7E-10 Number of Valid Observations = 17135 Number of Calms Lower Level = 95 '

. Number of Invalid Observations = 385 Number of Calms Upper Level = 0

- Note 1 - Any interpolations between stated mileages will be done by log-log -

.e-ie....m

-x

.mm-

. +

u,W,

.. -m ne36 1

. m.L2.

a + e -

e m

m m m.

<* fr.-.i

~

L PIge 165 of 181 l

ST. LUCIE PLANT:

~

m _

. CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION.15 OFFSITE DOSR$4LCULATION MANUAL (ODCM)

. TABLE M-8.

' Joint Wind Frequency Distribution Data Period: September 1,1976 - August 31,1978

~ All Winds St. Lucie Unit 2

' Data Source: On-Site Hutchinson Island. Florida Wind Sensor Height 10.00 Meters Florida Power & Light Co.

i

. Table Generated: 12/05/78. 07.42.18._

Dames and Moore Job No: 4598 - 112 - 27 l

Wind Speed Categories (Meters per Second) -

WIND 0.0-1.5-3.0-5.0-7.5-MEAN

~f SECTOR 1.5 3.0 5.0 -

7.5 10.0

>10.0 ~

TOTAL'

~ SPEED 71 206 318 71 3

0 689 -

l NNE 3.32

.43 1.25 1.92

.43

.02 0.00 4.05 62 292 385 128 0

.0 867

'?

NE 3.43

.38 1.77 2.33

.77 0.00 0.00' 5.25 j

60 334 505 158 0

0 1057 ENE 3.51

.36 2.02 3.06

.96 0.00 0.00 6.40 l

69 355 510 76 0

0

~iO10 E

3.25

,4p 2.15

'3.09

.46 0.00 0.00 6.11 j

115 684 744 72 1

0 1616 ESE 3.04

.70 4.14 4.50

.44

.01 0.00 9.78 183 660 749 28 0

0 1620 8

2.88 l

1.11 3.99 4.53

.17 0.00 0.00 9.81 b

129 579 656 93 1

0 1458 I

.Q SSE 3.10

.78 3.50 3.97

.56

.01 0.00 8.82

}

72 310 407 99 8

1 897 g

3'36

.44 1.88 2.46

.60

.05 -

.01 5.43 i

84 372 446 105 33 4

1044 SSW 34

.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.(:

l 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 i

2.43 l

1.05 1.62

.72

.22

.01 0.00 3.63 203 304 172 17 0

0 696 WNW 2.34 l

1.23 1.84 1.04

.10 0.00 0.00 4.21 43 518 424 50 0

0 si35 NW 2.85

.87 3.14 2.57

.30 0.00 0.00 6.87 i

85 379 535 70 1

0 1070 NNW 3.22

)

.51 2.29 3.24

.42

.01 0.00 6.46 91 194 531 148 5

0 969 I

N 3.69

.55 1.17 3.21

.90

.03 0.00 5.86

, 77

. 77 CALu CALM 1920 6214 7023 1287 73 5

16522 TOM 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 O

TOTAL NUMBER OF OBSERVATIONS 17520 100.00 PCT.

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

7 Pcge 166 of 181 e

ST. LUCIE PLANT -

. CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

APPENDIX B 2

LIMITED ANALYSIS DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS l

I The radioactive liquid effluents for the years 1978,1979 and 1980 were evaluated to determine the dose contribution of the radionuclide distribution. This at:alysis was l

perfoimed to evaluate the use of a limited dose analysis for determining environmental j

doses. Limiting the dose calculation to a few selected radionuclides that contribute the

^

majority of the dose provides a simplified method of determining compliance with the i

dose limits of Control 3.11.1.2.

j l

Tables B-1 and B-2 present the results of this evaluation. Table B-1 presents the i

fraction of the adult whole body dose contributed by the major radionuclides. Table B-2 i

presents the same data for the adult GI-LLI dose. The adult whole body and adult GI-LLI l

were determined to be the limiting doses based on an evaluation of all age groups (adult, j

teenager, child and infant) and all organs (bone, liver, kidney, lung and GI-LLI). As the data in the tables show, the radionuclides Fe-59, Co-58, Co-60, Zn-65, Cs-134 and j

Cs-137 dominate the whole body dose; the radionuclides, Fe-59, Co-58, Co-60, Zn-65 and Nb-95 dominate the GI-LLI dose. In all but one case (1979-fish, GI-LLI dose) these l

radionuclides contribute 90% or more of the total dose. If for 1979 the fish and shellfish O

these nuclides is 84%^ of the total GI LLI dose. pathways are combined as is done to Therefore, the dose commitment due to radioactive material in liquid effluents can be l

reasonably estimated by limiting the dose calculatiors to the radionuclides, Fe-59, Co-58, j

Co-60, Zn-65, Nb-95, Cs-134 and Cs-137, which cumulatively contribute the majority of

{

the total dose calculated by using all radionuclides deter:ted. This limited analysis dose i

assessment method is a simplified calculation that provides a reasonable evaluation of I

doses due to liquid radioactive effluents and allows for an estimate of Fe-55 contribution l

to dose.

i i

Tritium is not included in the limited analysis ' dose assessment for liquid releases l

because the potential dose resulting from normal reactor releases is negligible and is l

essentially independent of radwaste system operation. The amount of tritium releases annually is about 300 curies. At St. Lucie,300 Ci/ r released to the Atlantic Ocean produces a calculated whole body dose of 5 X 10'7 mrem /yr via the fish and shellfish

. pathways. This amounts to less than 0.001% of the design objectivo dose of 3 mremlyr.

j Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation.

s O

~

^ Tr.e dose due to Iron -55 made it necessary to change the conservatism factor from 0.8 to 0.6, which was done on Revision 7 to the ODCM, based on early 1986 data.

u

Pega 167 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) p V

TABLE B-1 ADULT WHOLE BODY DOSE CONTRIBUTIONS FRACTION OF TOTAL RADIONUCLICE FISH SHELLFISH FISH SHELLFISH FISH SHELLFISH Co-58 0.08 0.27 0.06 0.28 0.02 0.05 Co-60 0.05 0.19 0.03 0.15 0.20 0.44 Fe-59 0.10 0.25 0.04 0.13 0.15 0.22 Zn-65 0.01 0.10 0.02 0.19 0.04 0.20 Cs-134 0.31 0.07 0.46 0.14 0.27 0.04 Cs-137 0.42 0.10 0.38 0.11 0.30 0.04 I

TOTAL 0.97 0.98 0.99 1.00 0.98 0.99 O

TABLE B-2 ADULT GI-LLI DOSE CONTRIBUTION FRACTION OF TOTAL RADIONUCLIDE FISH SHELLFISH FISH SHELLFISH FISH SHELLFISH Co-58 0.03 0.36 0.25 0.44 0.01 0.07 Co-60 0.02 0.23 0.12 0.22 0.05 0.57 Fe-59 0.03 0.31 0.16 0.19 0.04 0.29 Zn-65 0.01 0.02 0.01 0.05 0.01 0.04 t

Nb-95 0.89 0.01 0.21 0.01 0.88 0.01 TOTAL 0.98 0.92 0.75 0.90 0.97 0.97

?

Prge 168 of 181

+-

ST. LUCIE PLANT

' CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

[

cr" OFFSITE DOSE CALCULATION MANUAL (ODCM) l A

APPENDIX C l

TECHNICAL BASES FOR EFFECTIVE DOSE FACTOR 1

.i i

Overview t

l The evaluation of doses due to releases of radioactive material to the atmosphere can' be i

simplified by the' use of eflective dose transfer factors instead of using dose. factors which j

are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released -

l to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope' specific dose factor only a single multiplication (K,,

M, or N,)' times the total quantity of radioactive material released would be needed.

-This approach provides a reasonable estimate of the actual dose while eliminating the -

l need for a detailed calculational technique.

i Determination of Effective Dose Factors l

The effective dose transfer factors are based on past operatQ data. The radioactive I

effluent distribution for the past years can be used to derive egle effective factors by j

O the following equations:

j i

K,,=fK,ef, (C-1)

Where:

l K,

the effective total body' dose factor due to gamma

'l

=

emissions from all noble gases released

/R15 K,

the total body dose factor due to gamma emissions j

=

from each noble gas radionuclide i released

/R15

)

f, the fractional abundance of noble gas radionuclide i

=

is of the total noble gas radionuclides 1

0 I

,,, -,,+

- -... - ~, - -.,. - - -.

P ge 169 of 181-ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 p

- OFFSITE DOSE CALCULATION MANUAL (ODCM) xj APPENDIX C TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (continued)

(L + 1.1 M),, = f (L, + 1.1 M). f, (C-2).

~

i Where:

(L+1.1 M),

the effective skin dose factor due to beta and gamma

=

emissions from all noble gases released (L, + 1.1 M) the skin dose factor due to beta and gamma emissions

=

i from each noble pas radionuclide i released M,, = f M, 1,

(C-3) i Where:

M,g the effective air dose factor due to gamma emissions j

=

from all noble gases released M,

the air dose factor due to gamma emissions from each

=

noble gas radionuclide i released N,, = f N,. f, (C-4) f Where:

N,g the effective air dose factor due to beta emissions from

=

all noble gases released the air dose factor due to beta emissions from each noble I

N,

=

gas radionuclide i i

O

)

Pcge 170 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

V( 3.

APPENDIX C TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (continued)

To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the past 3 years have been evaluated. Tables C-1 and C-2 present the results of this evaluation.

As can be seen from Tables C-1 and C-2, the effective dose transfer factors varies little from year to year. The maximum observed variability from the average value is 18%.

This variability is minor considering other areas of uncertainty and conservatism inherent in the environmental dose calculation models.

To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculation process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

Reevaluation The doses due to the gaseous effluents are evaluated by the more~ detailed calculation methods (i.e., use of nuclide specific dose factors) on a yearly basis. At this time a comparison can be made between the simplified method and the detailed method to assure the overall reasonableness of this limited analysis approach. If this comparison indicates that the radionuclide distribution has changed significantly causing the simpl!'ied method to underestimate the doses by more than 20%, the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach. However, this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses (i.e., greater inan 6 mrads gamma air dose or 10 mrads beta air dose).

)

in any case, the appropriateness of the A.,, value will be periodically evaluated to assume the applicability of a single effective dose factor for evaluating environmental doses.

O u

i

i f_

P ge 171.of 181i i

m q

ST. LUCIE PLANT -

a

" CHEMISTRY OPERATING PROCEDURE NO.' C-200, REVISION 15'-

OFFSITE DOSE CALCULATION MANUAL (ODCM)-

1

TABLE C-1:

j EFFECTIVE DOSE FACTORS l

NOBLE GASES-TOTAL BODY AND SKIN DOSES

/R15 l

TOTAL BODY EFFECTIVE SKIN EFFECTIVE

/R15-

)

DOSE FACTOR DOSE FACTOR

'l YEAR

.K, (L+1.1 M),

j mrom-m'~

mrom-m' nCi-yr pCi-yr

-i 1978 7.3 X 10' 1.4 X 10"

'i 1979

-7.4 X 10" 1.4 X.10'

.I 1980 5.6 X 10' 1.2 X 10' AVERAGE 6.8 X 10' 1.3 X 10' Li

.j 1

.j O

1

~'

TABLE C-2 EFFECTIVE DOSE FACTORS I

NOBLE GASES - AIR DOSES j

GAMMA AIR EFFECTIVE BETA AIR EFFECTIVE l

- DOSE FACTOR DOSE FACTOR YEAR M,.

'N,

}

8 8

mrad-m mrad-m '

l gCi-yr nCi-yr i

1978 8.0 X 10'.

1.2 X 103 j

1979 8.0 X 10' 1.2 X 10'.

i 1980 6.2 X 10' 1.2 X 10' AVERAGE 7.4 X 10' 1.2 X 10' l

I 1

IO i

[

Page 172 of 181' i

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 l

q OFFSITE DOSE CALCULATION MANUAL (ODCM)

V 1'

APPENDIX D :

TECHNICAL BASES FOR ELIMINATING CURIE INVENTORY LIMIT FOR GASEOUS WASTE STORAGE TANKS l

The NRC Standard Technical Specifcations include a limit for the amount of radioactivity.

that can be stored in a single waste gas storage tank. This curie inventory limit is established to assure that in the event of a tank failure releasing the radioactivity to the i

environment the resulting total body dose at the site boundary would not exceed 0.5 rem. /R15 1

i For St. Lucie; the inventory limit in the waste gas storage tank has been determined to be approximately 285,000 curies (Xe-133, equivalent). An allowable primary coolant radioactivity concentration is established by the Appendix A Techn~ mal Specifications

'which limits the primary coolant radioactivity concentrations to 100/E with E being the average energy of the radioactivity in Mev. This equation yields an upper primary coolant gross activity limit of about 160 Ci/ml. By applying this activity concentration limit to the total liquid volume of the primary system, a total activity limit can be l determined. For St. Lucie the primary system volume is about 70,000 gallons, which yields a limiting total inventory of approximately 43,000 Cl.

By assuming a typical radionuclide distribution an equivalent Xe-133 inventory can be O..

. determined. Table D-1 provides the typical radionuclide (noble gases) distribution and the Xe-133 equivalent concentration. The equivalent concentratioriis determined by multiplying the radionuclide concentration by the ratio of the nuclide total body dose factor to the Xe-133 total body dose factor. Summing all the individual radionuclide j

equivalent concentrations provides the overall reactor coolant Xe-133 equivalent i

concentration. - The data show that the equivalent concentration is a factor of 2 larger i

than the gross concentration (i.e., 24 pCi/gm total versus 47 Ci/gm equivalent). The i

resulting Xe-133 equivalent curie inventory of the reactor coolant system is.approximately j

86,000 Cl.

/R15 l

Therefore, even if the total primary system at the maximum Tech. Spec. allowable l

concentration was degassed to a single waste gas decay tank, the tank curie inventory would be weil below the 285,000 Ci limit. Based on this evaluation, the curie inventory limit on a single waste gas storage tank cannot exceed the Technical Specification i

requirement.

i l

ll r

i o

i i

u,

Page 173 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

/m OFFSITE DOSE CALCULATION MANUAL (ODCM)

)

TABLE D-1 REACTOR COOLANT - XE-133 EFFECTIVE CONCENTRATION REG. GUIDE 1.109 Xe-133 -

REACTOR COOLANT

• TOTAL BODY DF RATIO EFFECTIVE

/R15 CONCENTRATION (mremNr)

TB DF CONCENTRATION RADIONUCLIDE (pCl/gm)

(pCl/ml)

Xe-133 DF

( Ci/gm)

Kr-85m 0.19 1.2 X 10'*

4.1 0.78 Kr-85 0.83 1.6 X 10'*

0.06 0.05 Kr-87 0.16 5.9 X 10*

20.

3.2 Kr-88 0.31 1.5 X 10'*

52.

16.

Xe-131m 8.8 9.2 X 10

O.32 2.8 Xe-133m 0.20 2.5 X 10*

0.86 0.17 Xe-133 12.

2.9 X 10*

1.0 12.

Xe-135m 0.11 3.1 X 10-*

11.

1.2 Xe-135 1.2 1.8 X 10'*

6.2 7.4 Xe-137 0.02 1.4 X 10'*

4.8 0.1 Xe-138 0.12 8.8 X 10'*

30.

3.6 i

TOTALS 24 47.

• Data adapted from the NRC GALE Code

[

i O

m

~

~

' Page 174 of 181:

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) i APPEND!X E -

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE ST. LUCIE PLANT Key to Sample Locations SAMPLE APPROXIMATE R

PATHWAY LOCATION DESCRIPTION CMEN DIS M E COL ECTED gECTOR l

FREQUENCY (miles).

Direct Radiation N-1 North of Blind Creek TLD.

Quarterly 1

~N l

Direct Radiation NNW-5 South of Pete Stone Creek TLD Quarterly 5

NNW i

Direct Radiation NNW-10 C. G. Station TLD Quarterly 9-NNW i

Direct Radiation NW-5 Indian River Dnve at Rio Vista Drive TLD-Quartedy 6

NW Direct Radiation NW-10 livioioectioii of SR 68 and SR 607 TLD Quarterty 10

-NW Direct Radiation WNW-2 Cemetery South of 7107 Indian River Drive TLD Quartetty 3

WNW i

Direct Radiation WNW-5 US-1 at SR 7'12 TLD Quarterly 5

WNW l.

Direct Radiation WNW-10 SR 70, West of Tumpike

-TLD Quartetty 10 WNW l

Direct Radiation W-2 7609 indian River Dnve TLD-Quarterly 2:

W-Direct Radiation W Oleander and Sager Streets TLD

. Quarterly 5

W Direct Radiation W-10 1-95 and SR 709 TLD Quarterly 9

W g

l Direct Radiation WSW-2 8503 Indian River Drive TLD

. Quarterly 2

WSW Direct Radiation WSW-5 Prima Vista Blvd. at Yacht Club TLD Quarterly

.5 WSW Direct Radiation

. WSW-10 Del Rio and Davis Streets TLD Quarterly

10 WSW.

Direct Radiation SW-2 9207 Indian River Dnve TLD Quarterly 2

SW l

Direct Radiation SW-5 US 1 and Village Green Drive TLD-Quarterly 5

SW Direct Radiation SW-10 Port St. Lucie Blvd. and Cairo Road TLD Quarterly 10 SW Direct Radiation SSW-2 10307 Indian River Drive TLD-Quarterty 3

.SSW.

f

= -

.- - -.u.-:

+

O O

D, f a

~

Page 175 of 181.

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION -15 OFFSITE DOSE CALCULATION MANUAL (ODCML l

APPENDIXE i

RADIOLOGICAL ENVIRONRRENTAL SURVEILLANCE l

(continued)

ST. LUClE PLANT Key to Sample Locations SAMPLE APPROXIMATE t

l PATHWAY LOCATION DESCRIPTION O

C E

D SECT FREQUENCY (miles) -

l Direct Radiation SSW-5 Port St. Lucie Blvd. and US 1 TLD; Quartetty 6.

SSW i

Direct Radiation SSW Pine Valley and Westmoreland Roads TLD-Quartetty

.8-SSW

~

Direct Radetion S-5 13179 Indan River Drive TLD Quartetty 5

-S l-Direct Radiation

-S-10 US 1 and SR 714 TLD Quarterly

-10 S,

u L

Direct Radetion S/SSE-10 ' indian River Drio and Quail Run Lane TLD Quartetty 10

SSE-3

[

Direct Radiation SSE-5 Entrance of Nettles Island TLD Quartetty 5

-SSE-Direct Radiat6on SSE-10 Elliot Museum TLD Quarterly 10 SSE.

Direct Radiation SE-1 South of Cooling Canal TLD Quarterly 1

SE-i Direct Radiation

• H-32 U. of Florida - 1FAS Entomology Lab Vero Beach TLD Quartetty 19 NNW A

Airbome

- H06 FPL Substation - Weatherby Road Weekly 6-WNW Airbome

• H12 FPL Substation - SR 76, Stuart l

"* O

'Weeldy

12-S:

1 Airborne

-H14 Onsite - near south property line Weeldy 1_

'SE^

j Airbome H30 Power Line -7609 Indian Rever Drive Wesidy

2-W--

L L

• Denotes Control Sample l

l l

i

g

. y'

2; y,

O O

O..

l Page -.176 of 181..

ST. LUCIE PLANT.

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM) :

' APPENDIX E RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE (contmuod)

ST. LUCIE PLANTE Key to Sample Locations =

SAMPLE APPROXIMATE GSTK):

PATHWAY LOCATION DESCRIPTION CMECM E'

C E TED CT FREQUENCY

.(mGes E

Airborne H34 Onsite - At Meteorological Tower Weekly 0.5 '

N-Surface Water Ahnk hn % d @ h east 2

( m.)

Waterborne H15

<1 ENE/E/ESE of Route A1A Sediment from shoreline Surface Water Waterborne

• H59 Near south end of Hutchinson Island 10-20 S/SSE -

Semi-Annua #y C

Ocean side vicinity of ' t. Lucie Plant (NOTE 1)

<1 ENE/E/ESE S

Food Products HIS Broad Leaf.

MontNy Food Products HS1 Offsite near north property line vegetation (when.

'1-N/NNW (mangrove) -

available)

• Denotes control sample

't x

-__._..m

--_m___.-_-____m___.m__._

O O

Q-

- Page 177 of 181; ST. LUCIE PLANT--

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

- =

OFFSITE DOSE CALCULATION MANUAL (ODCM)

APPENDIX E

~

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE l

(continued) l ST. LUCIE PLANT

. Key to Sample Locations A

SAMPLES DIRECTION PATHWAY LOCATION DESCRIPTION CMCM

. DISTANCE COLLECTED SECTOR-FREQUENCY

- (miles)-

Broad leaf Monthly l

Food Products H52 Offsite near south property line vegetation.

(when 1

S/SSE j

(mangrove).

available)

Crustacea Semi-Annually i

Fish Semi-Annually l

Food Products

• H59 Near south end of Hutchinson Island Broad leaf Monthly 10-20 S/SSE ~

vegetation '

(mangrove) i

• Denotes control sample It is the policy of Florida Power &. Light Company (FPL) that the St. Lucie 1 & 2 Radiological Environmental Monitoring Programs are j

conducted by the State of Florida Department of Health and Reipabilitative Services (DHRS), pursuant to an Agreement between FPL i

and DHRS and; that coordination of the Radiological Environmental Monitoring Programs with DHRS and compliance with the Radiological Environmental Monitoring Program Controls are the responsibility of the Nuclear Energy Services Department.

i NOTE 1 These samples may be collected fmm or supplemented by samples collected from the plant intake canal if the required analyses are unable to be -

l performed due to unavailability or inadequate quantity of sample from the -

ocean side location.

1 i

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- m--

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Page 178 of 181 -

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

FIGURE 1-1 SITE AREA MAP & ENVIRONMENTAL SAMPLE LOCATIONS

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Page 179 of 181 i

ST. LUCIE PLANT r

. CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 OFFSITE DOSE CALCULATION MANUAL (ODCM).

FIGURE 1-2 ENVIRONMENTAL SAMPLE LOCATIONS (10 MILES)

H32 Vero Beach (Conto 0 y

N s y' a

a)

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Pzge 180 of 181 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15

/~s.

OFFSITE DOSE CALCULATION MANUAL (ODCM)

~

APPENDIX F l

METEOROLOGICAL DISPERSION FORMULAS

• For X/Q:

EQ (1) i-m i

'2.032 gg,

[3' o EQ(2) z (u)D l

i Where:

C

=.5 V

= 207.5 ft. (63.2 meters)

(u)

= a name for one term X/O was calculated using each of the above EOs for each hour. The highest X/O from.

EO (1) or EQ (2) was selected. The total integrated relative concentration at each sector and distance was then divided by the total number of hours in the data base.

Terrain correction factors given by Table M-4 were also applied to Dispersion Formulas l')

b

L age 181 of 181 P

~

ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 15 l

~ 7~t OFFSITE DOSE CALCULATION MANUAL (ODCM) i

-L.L);

APPENDIX F -

METEOROLOGICAL DISPERSION FORMULAS *

(continued) l f

For Deoleted X/Q:

(X/Q)o = (X/O) X ' Depletion factor of Figure 2 of R.G.1.111-R1)

(

lI For Deposition (D/Q):

j 3

D/O = RDep/(2 sin [11.25] X) X (Freq. distribution)

Where:

Ground deposition rate D/O i

=

Calculation distance X

=

Relative ground deposition rate from Figure 6 of R.G.1.111, R1 RDep

=

O i

t 9

6 P

O I

l L.

._