ML20137P549

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Combined Semiannual Radioactive Effluent Release Rept, Jan-June 1985
ML20137P549
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/30/1985
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20137P542 List:
References
NUDOCS 8509190700
Download: ML20137P549 (30)
v • d • e


Text

.

FIDRIDA POWER & LIGHT COMPANY Sr. LUCIE PLANT UNIT NO. 1&2 LIM NSE NO. DPR-67 & NPF-16 COMBIED SEMI-ANPRJAL RADI0 ACTIVE EFFLUENT HELEASE REPORT FOR THE PERIOD January 1. 1985 THROUGH June 30, 1985 1

8509190700 850830 PDR ADOCK 05000335 R pop

TABLE OF CONTENTS DESCRIPTION PAGE EF FLUENT AND WASTE DISPOS AL SUP PLEMENTAL INFORMATION . . . . . . . . . . . . . . . . . . . . . . I 0FFS ITE DOSE CALCULATION MANUAL REV IS IONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 SOL ID WAST E AND IRRADI ATED FUEL SHI PMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT 1......................................................... 7 UNIT 2........................................................10 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT 1........................................................13 UNIT 2........................................................15 S OL ID WASTE - S H I PME NT S UMMATIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 0FP3 ITE DOSE CALCULATION MANU AL PAGE REV IS IONS . . . . . . . . . . . . . . . . . ATTACHMENT A

Page 1 l

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regdlatory Limits 1.1 For Liquid Waste Effluents
a. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolvedorentrainednoblegases.Fordissolvedorentra{ned noble gases, the concentration shall be limited to 2 X 10- micro curies /ml total activity.
b. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:

During any calendar quarter to j[ 1.5 mrems to the total body and to j[ 5 mrems to any organ, and During any calendar year to j[ 3 mrems to the total body and to j( 10 mrems to any organ.

1.2_ For Gaseous Waste Effluents:

a. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:

For Noble Cases: j[ 500 mrems/yr to the total body and

[ 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days

j[ 1500 mrems/yr to any organ.

  • b. The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

During any calendar quarter, to j( 5 mrad for gamma radiation and

< 10 mrad for beta radiation and, during any calendar year to

][ 10 mrad for gamma radiation and ;[ 20 mrad for beta radiation.

  • c. The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives > 8 days in gaseous effluents released, from each reactor unit to areas at and beyond the SITE BOUNDARY, shall be limited to the following:

During any calendar quarter to ;[ 7.5 mrem to any organ, and during any calendar year to j[ 15 mrem to any organ.

  • The calculated doses contained in a semi-annual report shall not apply to any STS LCO. The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calculations are based on. The STS LCO dose limits are therefore included in Item 1 of the report, for information only.

. Page 2 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

2. -Maxinum Permissible Concentrations WATER: As per 10 CFR Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in 1.1.a of this

, report.

AIR: Release concentrations are limited to dose rate limits described in 1.2.a of this report.

3. Average energy of fission and activation gases in gaseous effluents is not applicable.

4 Measurements and Approximations of Total Radioactivity A summary of liquid ef fluent accounting methods is described in Table 3.1.

A summary of gaseous ef fluent accounting methods is described in Table 3.2.

4.1 Estimate of Errors

a. Sampling Error The error associated with volume measurement devices, flow measuring devices, etc. based on calibration data and design

~ tolerances has been conservatively estimated collectively to be less than + 10%.

b. Analytical Error for Nuclides Type Average ' Maximum Liquid +9% +30%

Gaseous +10% +35%

I

. Page 3 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

4. Measurements and Approximations of Total Radioactivity (continued) 4.1 (continued)
b. (continued)

TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS l LIQUID '

SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Each Batch Principal Gamma Emitters p.h.a.

Monitor Monthly H-3 L.S.

Tank Composite Gross Alpha G.F.P.

Releases 1 Quarterly SR-90, SR-89 C.S.

Composite FE-55 l Continuous Daily Principal Gamma Emitters Releases Grab & I-131 4/M Composite Samples p.h.a.

Dissolved & Entrained l Gases one batch / month l H-3 Composite Monthly L.S.

Gross Alpha Composite Monthly G.F.P.

Sr-89, Sr-90, & Fe-55 l Composite Quarterly C.S.

1 Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to liquid waste ef fluent totals.

p.h.a. gamma spectrum pulse height analysis using Lithium Ge rmanium detectors. All peaks are identified and quantified L.S. - Liquid Scintillation Counting C.S. - Chemical Separation G.F.P. - Gas Flow Proportional Counting 4/M - four per month l

Page-4 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

4. Measurements and Approximations of Total Radioactivity (continued) 4.1 (continued) i
b. (continued)

, TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS r

GASEOUS SAMPLING TYPE OF METHOD OF a SOURCE FREQUENCY ANALYSIS ANALYSIS 4

Waste gas Principal (G)

Decay Tank Each Tank Gamma -

Releases Emit te rs p.h.a.

i Containment Principal Gamma (G) -

Purge Each Purge Emitters p.h.a.

Releases H-3 L .S .

Principal Gamma (G, C, P) -

Weekly l Emitters p.h.a.

H-3 L.S .

Monthly Gross P - G.F.P.

Plant Composite Alpha l

Vent (Part iculat es )

Quarterly SR-90 C.S. ,

j Composite S R-89 j (Particulates)  ;

j G - Gaseous Grab Sample i C - Charcoal Filter Sample 1

P - Particulate Filter Sample j L .S . - Liquid ~ Scintillation Counting -

l C .S . - Chemical Separation -

p.h.a. - Gamen spectrum pulse height analysis using Lithium

Germanium detectors. All peaks are identified and
quant ified i G.F.P. - Gas Flow Proportional Counting l

4 i

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-,w. , - - - , em-. . - - . . , , ,-,,r n,-_,,,,,. , ,

Page 5 FLORIDA POWER & LIGitT COMPANY ST. LUCIE UNIT NO. 1&2 SEMI ANNUAL REPORT Januarv ' , 1985_ THROUGil June 30, 1985 EFFLUEMr AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases 5.1 Liquid UNIT I UNIT 2
a. Number of batch releases: 22 22
b. Total time period of batch releases: 1.06E04 1.06E04 MINUTES
c. Maximum time period for a batch release: 6 60 660 MINUTES
d. Average time period for a batch release: 482 482 MI NUTES
e. Minimum time period for a batch . release: 322 322 MINUIES
f. Average stream flow during periods of release of effluent into a flowing stream: 1.02E06 1.02E06 GPM ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5.2 Gaseous
a. Number of batch releases: 27 46
b. Total time period for batch releases: 15389 13385 MINUIES
c. Haximum time period f or a batch release: 1592 1920 MI NUTES
d. Average time period for batch releases: 570 291 MINUTES
e. Minimum time period for a batch release: 164 35 MINUTES ALL GASEOUS WASTE RELEASES ARE SUMMARIZED IN TABIES
6. Unplanned Releases 6.1 Liquid
a. Number of releases: 0 0
b. Total activity releases: 0 0 CURIES 6.2 Gaseous
a. Number of releases: 0 0
b. Total activity released: 0 0 CURIES 6.3 See at tachments (if applicable) for:
a. A description of the event and equipment involved.
b. Cause(s) f or the unplanned release.
c. Actions taken to prevent a recurrence.
d. Consequences of the unplanned release.

Page 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO.1 & 2 SEMIANNUAL REPORT January 1, 1985 THROUGH June 30, 1985

, EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (continued)

7. Assessment of radiation dose f rom radioactive ef fluents to the GENERAL PUBLIC is reported on the January Report.
8. Of fsite Dose Calculation Manual (ODCM) Revisions:

Seven pages were revised. Pages 19, 25, 66, and 72 correct typographical e rrors. Page 53 changes Ag-110m to Ag-110 to be consistent with '

ORNL/NUREG/TM-102 Reference. Pages 80 and 81 identifies the HIS Sample Distance 6 < 1 mile instead of 1 mile. Page 81 also had a comment added to identify the agency actually conducting the sampling program and their i interaction with Florida Power & Light Company.

, None of the above changes af fected the methodology of dose calculations s

of the ODCM.

4 9. Solid Waste and Irradiated Fuel Shipments 1

No irradiated fuel shipments were made f rom the site. Common solid waste from St. Lucie Units 1 and 2 were shipped jointly. A summation of these ,

3 shipments is given in Table 3.8 of this report.

l

10. Process Control Program Revisions -

I No revisions were made during the reporting period.

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.- - . _ , , . , - - --._~,_,.-....,_..,,,,% ..#-,,,..,.,-.,,-w. ,-,,,,,-,,,.-n, , ---,,- -,,. . -

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Page 7 FLORIDA POWER 6 LIGilT COMPANY ST. LUCIE UNIT NO. I SEMIANNUAL REPORT J anuary 1, 1985 TilROUGli June 30, 1985 TABLE 3.3-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED l UNIT l QUAKTER # ll QUARTER # 2:

A. Fission and Activation Products l

1. Total Release (not including tritium, gases, alpha) CI 5.42E-01 2.19E-01
2. Average diluted concentration during period uCI/ml 1.17E-08 6.12E-09 B. T ritium l 1. Total Release l CI l 1.01 E02 l 7.75 E01 l
2. Average diluted concentration during period uCI/ml 7.27E-06 2.16E-06 C. Dissolved and Entrained Cases l 1. Total release l CI l 1.58E 00 l 2.38E-01 l
2. Average diluted concentration during period uCI/ml 3.42E-08 6.66E-09 D. - - Gross Alpha Radioactivity
1. Total Release CI l 0 1 0

E. Volume of Waste Released

-(prior to dilution) Liters 1.59 E06 1.27 E06 F. Volume of Dilution Water Used During Period Liters 4.62 E10 1 3.58 E10

. - . - . . . .-. ~- . . ,- - - . -- - - - -.

l Page 8 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 ,

SEMIANNUAL REPORT January 1, 1985 THROUGH June 30, 1985 2 TABLE 3.4-1 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED UNIT QUARTER F l l QUARTER # 2 QUARTER # 1l QUARTER # 2  ;

l Na-24 l CI l 0 l 0 l 0 l 5.25 E-05 l  :

l CR-51 l CI l 0 l 0 l 2.53 E-04 l 7.55 E-03 l f l MN-54 l CI l 0 l 0 l 5.85 E-03 l 1.12 E-03 l l MN-56 l CI l 0 l 0 l 0 l 0 l

( l Co-57 l CI l 0 l 0 l 0 l 0 l i l Co-58 l CI l 0 l 0 l 8.55 E-02 l 4.42 E-02 l l Co-60 l CI l 0 l 0 l 3.48 E-02 l 3.47 E-02 l i l Fe-59 l CI l 0 l 0 l 3.32 E-03 l 6.55 E-04 l i

l Fe-55 l CI l 0 l 0 l 2.94 E-02 l 8.90 E-02 l l l Ag-110 l CI l 0 l 0 l 0 l 1.11 E-05 l l SN-ll3 l CI l 0 l 0 l 2.45 E-05 l 0 l

l Sb-122 l CI l 0 l 0 l 1.04 E-03 l 8.30 E-05 l l S b-124 l CI l 0 l 0 l 5.45 E-04 l 5.65 E-04 l l l W-187 l CI l 0 l 0 l 0 l 0 l ,

j l Np-239 l CI l 0 l 0 l 0 l 0 l l

l I-131 l CI l 0 l 0 l 3.17 E-02 l 1.39 E-02 l j l I-132 l CI l 0 l 0 l 0 l 0 l l I-133 l CI l 0 l 0 l 1.90 E-04 l 7.00 E-4 l l I-134 l CI l 0 l 0 l 0 l 0 l

! l I-135 l CI l 0 l 0 l 0 l 0 l  :

l Zr-95 l CI l 0 l 0 l 8.90 E-04 l 1.30 E-03 l l l Nb-95 l CI l 0 l 0- l 0 l 0 l l ZR-97 l CI l 0 l 0 l 0- l 0 -l l Nb-97 l CI l 0 l 0 l 0 l 4.04 E-05 l l Mo-99 l CI l 0 l 0 l 0 l 0 l

l Tc-99M l CI l 0 l 0 l 1.46 E-04 l 2.22 E-04 l l Ru-103 l CI l 0 l 0 l 1.82 E-04 l 2.69 E-04 l l Sb-125 l CI l 0 l 0 l 7.50 E-03 l 4.64 E-03 l l l Cs-134 l CI l 0 l 0 l 1.15 E-01 l 6.50 E-03 l l

! .. _ _ . _ __ _ _ . _ _ _ _ _ . _ _ _a

_. . . .- . . ~.. . - . ~ - -- .- . . .- . . - - .

Page 9 d '

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 1 SEMIANNUAL REPORT

! January 1, 1985 THROUGH June 30, 1985

't TABLE 3.4-1

? LIQUID EFFLUENTS i (continued) i CONTINUOUS MODE l BATCll MODE l NUCLIDES RELEASED l UNIT l QUARTER #1 l QUARTER #2 l QUARTER #1 l QUARTER I/2 l

i. l Cs-136 l CI l 0 l 0 l 6.40 E-03 l 1.27 E-04 l s

l Cs-137 -l CI l 0 l' O l 2.17 E-01 l 9.85 E-03 l l Ba-140 l CI l 0 l 0 l 0 l 0 l i

] l La-140 l CI l 0 l 0 l 1.18 E-03 l 2.41 E-03 l l Ce-141 l CI l 0 l 0 l 5.60 E-5 l 3.11 E-04 l l Ce-14 4 l CI l 0 l O' l 0 l 5.40 E-04 l l l Sr-89 l CI l 0 l 0 l 4.77 E-04 l 8.90 E-05 l j l Sr-90 l CI l 0 l 0 l 5.55 E-05 l 2.54 E-05 l Y-90 CI O O 5.55 E-05 2.54 E-05 UNIDENTIFIED CI O O O O TOTAL FOR , l PERIOD ABOVE l CI O l 0 1 5.42 E-1 ,1 2.19 E-1 l 1

0 4

l AR-41 l CI l 0 l 0 l 0 l 0 l l KR-85 l CI l 0 l -0 l 0 l 0 l l XE-131M l CI l 0 l 0 l 3.76 E-03 l 0 l l XE-133 l CI l 0 l 0 l 1.56 E-00 l 2.33 E-01 l

} l XE-133M l CI l 0 l 0 l 1.28 E-02 l 2.16 E-03 l 4

l XE-135 l CI l 0 l 0 l 3.14 E-03 l 3.21 E-03 l l l KR-85M l CI'l 0 l 0 l 0 l 0 l l XE-138 CI l 0 l 0 l 0 l 0 l j TOTAL FOR l PERIOD ABOVE CI O 'O 1.58 E 00 2.38 E-01 NUIE: If' no value is entered for a nuclide, the value equals zero Curies.

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l Page 10 FLORIDA POWER & LIGilT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT

January 1, 1985 THROUGil June 30, 1985 _

TABLE 3.3-2 i

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

~

NUCLIDES RELE ASE3 l UNIT l QUARTER F ll QUARTER F 2 A. Fission and Activation Products -

1

1. Total Release (not including l t ri t ium, gases, alpha) CI l 5.73 E-01 2.19 E-01 l
2. Average diluted concentration  !

l during period uCI/ml 9.29 E-09 l 5.03 E-09 B. T ritium 4 l 1. Total Release l CI l 1.01 E 02 l 1.55 E 02 l

2. Average diluted concentration during period uCI/ml 1.45 E-05 3.56 E-06

, C. Dissolved and Entrained Gases I

l 1. Total release l CI l 1.59 E 00 l 2.38 E-01 l *

2. Average diluted concentration l l l l

] during period uCI/ml 3.44 E-08 l 5.47 E-09 D. Gross Alpha Radioactivity l 1. Total Release l CI l 0 l 0 E. Volume of Waste Released .

(prior to dilution) Li te rs 5.50 E 06 3.53 E 06 4

F. Volume of Dilution Water j Used During Period Liters 6.17 E 10 4.35 E 10 i

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Page 11 FLORIDA POWER & LIGilT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT January 1, 1985 TilROUGil June 30, 1985 TABLE 3.4-1 LIQUID EFFLUENTS CONTINUUUS MODE l HATCll MODE NUCLIDES RELEASED UNIT ' QUARTER # l l QU ART ER # 2 l QU ART ER # ll QUARTER # 2 l Na-24 l CI l 1.40 E-03 l 0 l 0 l 5.25 E-0 5 l l CR-51 l CI l 0 l 0 l 2.53 E-04 l 7.55 E-03 l l MN-54 l CI j 1.11 E-04 l 0 l 5.85 E-03 l 1.12 E-03 l l MN-56 l CI l 0 l 0 l 0 l 0 l l Co-57 l CI l 0 l 0 l 0 l 0 l l Co-58 l CI l 0 l 0 l 8.5 5 E-02 l 4.42 E-02 l l Co-60 l CI l 0 l 0 l 3.48 E-02 l 3.47 E-02 l l Fe-59 l CI l 0 l 0 l 3.32 E-03 l 6.55 E-04 l l Fe-55 l CI l 1.56 E-03 l 3.98 E-04 l 2.94 E-02 l 8.90 E-02 l l Ag-110 l CI l 0 l 0 l 0 l 1.11 E-05 l l SN-ll3 l CI l 0 l 0 l 2.4 5 E-05 l 0 l l Sb-122 l CI l 0 l 0 l 1.04 E-03 l 8.30 E-05 l l S b-124 l CI l 0 l 0 l 5.45 E-04 l 5.65 E-04 l l W-187 l CI l 0 l 0 l 0 l 0 l l Np-239 l CI l 0 l 0 l 0 l 0 l l I-131 l CI l 5.71 E-03 l 2.4 3 E-04 l 3.17 E-02 l 1.39 E-02 l l I-132 l CI l 4.24 E-03 l 0 l 0 l 0 l l I-133 l CI l 9.95 E-03 l 0 l 1.90 E-04 l 7.00 E-4 l l I-134 l CI l 0 l 0 l 0 l 0 l l I-135 l CI l 0 l 0 l 0 l 0 l l 7. r-95 l CI l 0 l 0 l 8.90 E-04 l 1.30 E-03 l l Nb-95 l CI l 0 l 0 l 0 l 0 l l ZR-97 l CI l 0 l 0 l 0 l 0 l l Nb-97 l CI l 0 l 0 l 0 l 4.04 E-05 l l Mo-99 l CI l 0 l 0 l 0 l 0 l l Tc-99S l CI ~l 0 l 0 l 1.46 E-04 l 2.22 E-04 l l Ru-103 l CI l 0 l 0 l 1,82 E-04 l 2.69 E-04 l l Sb-125 l CI l 0 l 0 l 7.50 E-03 l 4.64 E-03 l l Cs-134 l CI l 1.51 E-03 l 1.52 E-0 5 l 1.15 E-01 l 6.50E-03l

v'  !

,- ' Page 12 l FLORIDA POWER & LIGitT COMPANY ST. LUCIE UNIT NO. 2 l l SEMIANNUAL REPORT l

' January 1, 1985 June 30, 1985 THROUGH  !

(

TABLE 3.4-1 f LIQUID EFFLUENTS j (continued) [

i i I

CONTINUOUS MODE l BATCll MODE l NUCLIDES RELEASED l UNIT QUARTER #1 l QUARTER #2 l QUARTER # ll QU ARTER # 2l f l Cs-136 l CI l 0 l 0 l 6.40 E-03 l- 1.27 E-04 l

); l Cs-137 l CI l 2.10 E-03 l 3.54 E-05 l 2.17 E-01 l 9.85 E-03 l f l Cs-138 l CI l 4.82 E-02 l 0 l 0 l 0 l f l Ba-140 l CI l 0 l 8.14 E-06 l 0 l 0 l l La-140 l CI l 0 l 0 l 1.18 E-03 l 2.41 E-03 l

l Ce-141 l CI l 0 l 0 l 5.60 E-5 l 3.11 E-04 l  !

I l- Ce-144 l CI l 0 l 0 l 0 l 5.40 E-04 l [

l Sr-89 l CI l 0 l 0 l 4.77 E-4 l 8.90 E-05 l f

, l S r-90 l CI l 0 l 0 l 5.55 E-05 l 2.54 E-05 l  !

I Y-90 l CI l j

r l 0 l 0 l 5.55 E-05 l 2.54 E-05 l i L

q j UNIDENTIFIED CI l 0 l 0 l 0 l 0 j

< TOTAL FOR ~

r

! PERIOD ABOVE CI 3.14 E-02 7.00 E-04 5.42 E-01 2.19 E-01  !

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! l AR-41 l CI l 0 l 0 l 0 l 0 l l l l KR-85 l CI l 0 l 0 l 0 l 0 l l l XE-131M l CI l 0 l 0 l 3.76 E-03 l 0 l [

4 l XE-133 l CI l 0 l 2.50 E-05 l 1.56 E 00 l 2. 3 3 E 'll_l  ;

l XE-133M l CI l 0 l 0 l 1.28 E-02 l 2.16 E- I j l XE-135 l CI l 6.43 E-04 l 0 l 3.14 E-03 l 3.21 E-03 [

j l XE-135M lC l 8.75 E-03 l 0 l 0 1 0 l f XE-138 l CI I O l 0 0 I O  !

$ TOIAL FOR ,

l PERIOD ABOVE l CI 9.39 E-03 2.50 E-05 1.58 E 00 2.38 E-01 )

i NUIE: If no value is entered for a nuclide, the value equals zero Curies. i

+

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_ .. -- _ _ _ . _. _ - . ._ ~ _ . _ >_. . . _ . . .

Page 13 FLORIDA POWER & LIGilT COMPANY ST. LUCIE UNIT NO. I SEMIANNUAL REPORT January 1, 1985 TiiROUGH June 30, 1985 1

! TABLE 3.6-1 {

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELE ASED l UNIT l QUARTER # ll QUARTER # 2 A. Fission and Activation Gases l 1. Total. Release l CI l 1.89 E 04 l 9.93 E 03 l

2. Average Release Rate for Period I uCI/secl 2.40 E 03 l 1.26 E 03 B. Iodines ,

l 1. . Total Iodine-131 l CI l 1.31 E-01 l 5.26 E-01 l

~

2. Average Release Rate for Period l uCI/secl 1.66 E-02 l 6.67 E-02 C. Particulates l 1. Particulates T-1/2 > 8 Days l CI l 3.75 E-05 l 1.43 E-05 l ,

l 2. Average Release Rate f or Period l uCI/secl 4.82 E-06 l 1.82 E-06 l

3. Gross Alpha Radioactivity l CI l 1.62 E-07 l 5.44 E-08 D. T rit iun l 1. Total Release l CI l 2.43 E 02 l 1.08 E 02 l l 2. Average Release Rate for Period l uCI/seci 3.08 E 01 l 1.37 E 01 l r

's

i Page 14 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEM1 ANNUAL REPORT January 1, 1985 THROUGH June 30, 1985 TABLE 3.7-1 G ASEOUS EFFLUENTS l CONTINUOUS MODE HATCH MODE {

NUCLIDES RELEASED UNIT l QUARTER F ll QUARTER # 2 QUARTER # ll QUARTER # 2

1. FISSION GASES AR-41 CI l 0 l 0 l 2.55 EOO O KR-85 CI l 0 l 0 l 2.71 EOO 2.41 EOO KR-85M CI l 1.20 E02 1.52 E02 2,06 E01 2.73 E-1 KR-67 CI l 1.67 EOl 5.90 EOl 3.11 -EOO O

.KR-88 CI } 4.03 EDI 1.85 E02 1.74 EOl 1.63 E-1 XE-131M CI 4.15 E00 0 3.45 E00 4.55 E00 XE-133 CI 8.38 E03 6.27 E03 8.93 E03 1.96 E03 XE-133M CI 3.62 EOl 6.18 E01 7.12 E01 1.43 EDI XE-135 CI 9.32 E02 1.18 E03 2.98 E02 1.37 E01 XE-135M CI O 2.55 E01 0 0

- XE-138 Cl 0 0 1 0 1 0 TOTAL FOR l ,

PERIOD ABOVE l CI 9.53 E03 7.93 E03 9.35 E03 2.00 E03 l 2. 10 DINES I- 1 30 CI O O I-131 CI 2.85 E-02 1.95 E-02 I-132 CI O 2.19 E-01 1-133 CI 1.02 E-01 9.07 E-02 I-135 CI O 1.97 E-Ol TOTAL FOR PERIOD ABOVE CI 1.31 E-01 5.26 E-01 1 3. PARTICULAIES l Co-58 CI O l 0 (

. Co-60 CI O I O S R-89 CI O O S R-90 CI O 0 .

Y-90 CI O O I-131 CI 3.75 E-05 1.43 E-05 CI TOTAL FOR PERIOD ABOVE l CI 3.7 5 E-05 1.4 3 E-05 l 2

--m - - , . - - - . ,

, _m ., -

Page 15 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT January 1, 1985 THROUGH June 30, 1985 TABLE 3.6-2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

! NUCLIDES RELEASED l UN IT l QUARTER #1 l QUARTER #2 A. Fission and Activation Gases l 1. Total Release l CI l 2.96 E 03 l 1,62 E 03 l

2. Average Release Rate for Period l uCI/secl 3.75 E 02 l 2.05 E 02 B. Iodines f l 1. Total Iodine-131 l CI l 5.23 E-02 l 1.16 E-01 l l 2. Average Release Rate for Period l uCI/secl 6.63 E-03 l 1.47 E-02 C. Particulates l 1. Particulates T-1/2 > 8 Days l CI l 1.76 E-05 l 2.82 E-05 l

! l 2. Average Release Rate for Period luCI/secl 2.26 E-06 l 3.59 E-06 l

,  ?. Gross Alpha Radioactivity l CI l 2.65 E-07 l 1.41 E-09 D. i rit iun l 1. Total Release l CI l 3.83 E 01 l 6.79 E 01 l l 2. Average Release Rate for Period l uCI/secl 4.86 E 00 l 8.61 E 00 l l

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d i Page 16 l FLORIDA POWER & LIGHT COMPANY

ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT i

January 1, 1985 TilROUGli June 30, 1985 TABLE 3.7-2 GASEOUS EFFLUENTS j CONTINUOUS MODE HATCil MODE I NUCLIDES RELEASED UNIT ,l QUARTER # 1 l QUARTER # 2 QUARTER # ll QUARTER # 2 e 1. FISSION GASES

! AR-41 CI O j 0 l 2.89 E 00 3.02 E 00 KR-85 CI O O O 1.38 E-01 KR-85M CI 1.38 E 01 8.34 E 00 6.85 E-01 1.60 E 00 KR-87 CI O O 6.52 E-02 1.51 E-01 KR-8 8 CI O 1.81 E 00 9.47 E-01 1.64 E 00 XE-131M CI O O 2.49 E 00 1.83 E 00 XE-133 CI 2.19 E 03 1.20 E 03 4.94 E 02 2.22 E O2 XE-133M CI O O 4.90 E 00 2.11 E 00 XE-135 CI 2.40 E 02 1.57 E O2 1.10 E 01 1.31 E 01 XE-135M CI O O O O XE-138 CI O O O O

. TOTAL FOR PERIOD ABOVE I CI I 2.44 E 03 i 1.37 E 03 5.17 E 02 2.46 E 02 l

2. 10 DINES I-130 CI l O O

, 1-131 CI 2.71 E-02 5.54 E-02 I-132 CI O 3.43 E-02 I-133 C1 2.52 E-02 2.62 E-02 I-135 CI O O TOTAL FOR PERIOD ABOVE CI 5.23 E-2 1.16 E-1

3. PARTICULAIES l Co-58 CI I O I O Co-60 CI O O S R-89 CI O j O i S R-90 CI O O Y-90 CI O o I-131 CI 1.76 E-05 2.82 E-05 CI CI '

I f TOTAL FOR PERIOD ABOVE CI 1.76 E-5 2.82 E-05 i

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,_ - , _ _ . . _ _ . , - - . . _ _ . - _ ~---s,- ...,m_ _ - - . . . .,_-,_,m.. , _ . - - ,

Page 17

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TABLE 3.8 >

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1-June.30, 1985 -

St. Lucie Unit Nos. 1& 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DiSbSAL (Not irradiated fuel) t

~ '

6 month Est. To tal

1. Type of waste .. .unii Period Error. %

, s. Spent resins, filter sludges, evaporator tr/ 45E1 bottoms. etc. Ci 6. 2 E 2 2 .0 El

b. Dry compressible waste, contaminated m3 2. 0 E 2 equip. etc.- Ci 2.0 El 2 .0 El i c. Irradiated components, control m' . E rods, etc. Ci . E . E
d. Other (describe) m' . E Ci . E . E
2. Estimate of major nuclide composition (by type of waste) . .
a. Cs-137  % 4.2 E 1 -

Cs-134  % 2.1 E 1 Co-60  % 5.6 E O Co-58  % 1, 3 E 1 Fe-55  % 8. 4 E 0

% . E b, Cs-137  % 1. 6 E1 Cs-134  % 8. 0 E O Co-60  %

2.2 E 1 Co-55  % 1.1 E 1 Fe-55  % 1. 8 E 1 H-3  % 1. 5 E1

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3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 12 Sole Use Truck Barnwell, S.C. l 2 Sole Use Truck Richland, Wash.

B. IRRADIATED FUEL SH:PMENTS (Disposition) 1 Number of Shipments Mode of Transportation Destination

. 9 l

FLORIDA POWER & LICHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SEMIANNUAL REPORT JANUARY 1. 1985 THROUCH JUNE 30, 1985 TABLE 3.8 (Cont.)

Note 1 8" I ' d "'s t .> Supplement Total Total Type Note 3 R.C.1.21 Type Note 4 Solidification Waste Volume Curie Principal Notes 1,2 of of Agent Classification Cu-Ft Quantity Radionuclides Waste Category Container (or Absorbent)

A 6798 3.687 None PWR Trash 1.b Non-Specification :k>ne Strong Tight Pkg.

A 966 0.686 None PWR Ion- 1.a Non-Specification None Exchange Resin Strong Tight Pkg.

63 90 137 B 195 16.449 Ni, Sr. Cs PWR Trash 1.b NRC Certified None LSA > Type A 63 90 137 8 390 227.530 Ni, Sr. Cs PWR Ion- 1.a NRC Certified None Exchange Resin LSA > Type A C 121 364.338 129 63 90 60 137 PWR Ion- 1.a NRC Certified None I, N1, Sr. Co, Cs Exchange Resin Type B 134 58 131 54 95 55 Cs, Co. I, Mn, Nb, Fe 14 99 129 60 63 90 PWR Filters 1.a NRC Certified None C 121 26.670 C. Tc, I, Co, N1, Sr. Type B 137 54 57 58 59 95 Cs, Mn, Co, Co, Fe, Nb, 95 113 ad Zr, Sn (D

1DTAL VOLUME: 8591 FT TOTAL ACTIVITY: 639.360 Curies >

i b _ _ _ _

Paga 17B l

i FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SEMIANNUAL REPORT

' January 1,1985 THROUGH June 30, 1985 4 TABLE 3.8 (Cont'.)

Solid Waste Supplement Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant are determined using a combination

! of qualitative and quantitative techniques. In general, the St.

Lucie Plant follows the guidelines outlined in the Low-level Waste

~

j g

Licensing Branch Technical Position (BTP) on Radioactive Waste i Classification (5/11/83) for these determinations.

i The most frequently used techniques for determining the total curie

. quantity in a package are the dose-to-curie methods and the I (Concentration) X (Volume or Mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to some extent qualitative _

- parameters, the total curie quantity is considered to be an estimate.

The composition of radionuclides in the waste is detennined by both  ;

on-site analyses for principal gamma emitters, and periodic offsite  ;

i analyses for other radionuclides. The onsite analyses are perfonned l either on a batch basis or on a routine basis using reasonab!y I representative samples as appropriate for the waste type. Offsite analyses are used to egtabysh scaling factors or other estimates for

- radionuclides such as H, C, 99 Tc, 129 1, TRU, 241Pu, 242Cm, 63Ni, and 55p ,,

Note 2: " Principal Radionuclides" refers to those radionuclides contained 'in

, the waste in concentrations greater than .01 times the concentration

  • of that nuclide listed in Table 1 or .01 times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.

Note 3: " Type of Waste" is generally specified as described in NUREG 0782, l

Draft Environmental Impact Statement on 10 CFR 61 " Licensing Requirements for Land Disposal of Radioactive Waste".

Note 4: " Type of Container" refers to the transport package.

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Page 18 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO 1 & 2 SEMIANNUAL REPORT 3anuary 1,1985 THROUGH June 30,1985 ATTACHMENT A CHANGES TO OFFSITE DOSE CALCULATION MANUAL

- DURING PERIOD JANUARY 1,1985 THROUGH JUNE 30,1985 PAGE REVISIONS ATTACHED 1

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E10RIDA IUER & LIGII (INPANY  !

f sr. wCIE PLWI OC'J5rRY OIERAIllU PROQIXRE NO. C-200  ;

REVISION 5 i forinherntbc'v\ o y1 TIHE: / ,

L Co'n 1 Offsite Dose Calculation Marual (CD01) 2

/ x REVIBl AND APPRLTAL: ,

i i

Reviewn! by Frility Revice Grcup April 22,19g Approval by C. M. Wehv Plant Mmager April 27,1918 i

Revision 5 P s ic ui by F R G /d -d / 19 8 Approved by hM/[2./M[

Plant Managr .F- 2 A - 19fo~ I Preef of flari Manger Ogreva( i l

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Pega 19 of 84 ST. LUCIE PLANT  !

CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 )

0FFSITE DOSE CALCULATION MANUAL (ODCM) l 2.2 (maria-a)

1. R4=nlified Total Body Dese Rate Calo11ation Fras an ev=1'=rian of past rala , an effective total body dose factor (Kdf) can be derived. This dose factor is in effect a weighted average total body dose factor, i.e., weighted by the radiornelida distribution typical of past operation. (Refer to Appemiix C for a deraflad explanacim and ev=1narian of Kgg). The value of K f has been derived from the radioactive noble gas effitants for the years 1978,19e , armi 1980 The value is:

a~

Kdf = 6.8 X 10 2 ,,,,,,3 uCiyr This value may be used in conjunction with the total noble gas ralamaa rate

( Qi) to verify that the instantaneous dose rate is within the allowable lidts.

To allme for any unexpected vnriah414 t y in the radionelida distribution, a conservatism factor of 0.8 is intrna ead into the calt-*1arinn. The singlified eqi=rfan is:

g = Ko b) i 0.8 O 1 To further simpgfy the detaminarina, the historical arrual average meteorological X/Q of 1.6 X 10 sec/m3 (From Table M-1) may be substituted into the equation.

Also, the dose limit of 500 nrea/yr may be substituted for %. Makirs these substitutions yields a sirgle n=>1ative (or gross) noble gas release rate lidt.

This value is:

Noble gas ralamaa rate lintit = 3.5 X 105 uci/see As long ag the noble gas release rates do not exceed this value (3.5 X 10' uC1/sec), no additional dose rate calculations are needed to wrify compliance with Tecirtical Specification 3.11.2.1.

2. Setpoint Detecnination To cmply with Tech. .pec. 3.3.3.10, the alarm / trip setpoints are estaglished to ensure that the noble gas ralamaaa do not exmed the value of 3.5 X 10' uCi/sec, which co swds to a total body dose race of 500 nren/yr. The metind that -

follous is a step-brstep grocedure for establishing the setpoints. To allow for m21tip14 saarces of relamaan from different or cannon ralamaa points, the allowable operating setpoints will be controlled administratively by allomeing a percentage of the total allouable ralaaan to each of the release sources. /R5 A. Determine (V) the maxima whine ralamaa rate potential fran the irr plant es for the ralaaaa saura under consideration. The tztits of (V) are a

. Pags 25 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5

.- 0FFSITE DOSE CALCULATION MANUAL (ODCM)

< i 2.3 (continued)

The calmiatiana of Sectiorm 2.3.1, 2.3.2, 2.3.4, ard 2.3.5 may be anitted. The dose rate calculations as specified in these sections are inelmiai for completeness and are to be used only for evaluatirg trusual ciremstances tJere releases of particulate meterials other than r=44af~44_nas in airborne ralaaaae are almonnally high. The calmlations of heefana 2.3.1, 2.3.2, 2.3.4, and 2.3.5 will typically be used to demonstrate coglimce with the dose rate limit of Tech. Spec. 3.11.2.1 for raiininriinaa and particulates then the measured releases of partimlate material (other thm r=44aiaiinaa and with half lives >8 days) are >10 times the measured ralamaaa of radiofodines.

,- 1

1. The Instantaneous Inhalation Dose Rate Method:

NOTE The H-3 dose is calmlated as per 2.3.4 A. The controllirg lacattan is assmed to be an Infant located in the sector at the mile range. The(5)D f#

this location is sec/m3 . This value is common to all

~1 h. (See Table M-2 for value, sector ard rang.)

B. Enter the ralamaa rgte in ft 3/udn of tp release source and convert to cc/sec.

f") = fe' X 2.8317 X_10'cc X ndn = cc/see min ft" 60 sec.

C. Solve for Og for ruclide (i) by obtainiry the uC1/cc assay value of the ralaaae source activity and nultiplyug it by the proince of 2.3.1.B above.

41 = (ruelide liVasy) uCi X (Value 2.3.1.B) cc /RS cc see O

d=

i dsec for nelfria (1)

, , D. Obtain the Rt value from Table G-5 for the organ T.

E. Solve for IR 1 DaiT = RiT ( }D i" EEE -

X sec X uCi uCi yr d see DRIT = nren The Dose Rate to organ T from nelinia (i) yr F. Repeat steps 2.3.1.C through 2.3.1.E for each ruclide (1) reported in the assay of the rataaaa sourm.

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l Page 53 of 84 ST. LUCIE PLANT l CHEMISTRY OPERATING PROCEDURE No. C-200, REVISION 5 0FFSITE DOSE CALCULATION MANUAL (ODCM)

TABIE L-1 MA' GEM IERiISSIBLE ON VIRATIONS IN RUER IN LMESTRICI'ED AREAS i

Nuclide l SPC (uci/ml) Nuclide l MPC ( 4 /ml) Nuclide l MPC (uCi/ml)

H-3 3 E-3 / Y-90 2 E Te-129 8 E-4 / <

3 E-5 / 3 E-3 / 4 E-5 #

Na-24 Y-91m Te-131m l 4 P-32 2 E-5 /, Y-91 3 E-5d Te-131 None -

I 'Cr-51 2 E-3 / Y-92 6 E-5 # Te-132 2 E-5/

! Mtr-54 1 E-4 ' Y-93 3 E-5 / I-130 3 E-6

. M:r-56 1 E-4 # Zr-95 6 E-5 J I-131 3 E-7 -

Fe-55 8 E-4 # Zr-97 2 E-5 / I-132 8 E-6/  :

Fe-59 5 E-5/ N'.r95 1 E4 / I-133 1 E-6 Ccr-57 4 E-4 # Ntr97 9 E-4 / I-134 2 E-5 /

Co-58 9 E-5 / Mo-99 4 E-5 I-135 4 E-6 I C:re0 3E-Si Tc-99m 3 E-3/ Cs-134 9 E-6 d 1

Ni-65 1 E-4# Te-101 ' Cs-136 6 E-5 /

None 8 E-5 # 2 E-5 /

) Ctr M 2 E-4 / . Re-103 Cs-137 j Zrr-65 1 E-4 / Ra-105 1 E-4/ Ca-138 None j Zrr49 2 E-3# Ru-106 1 E-5 / Ba-139 None l Br-82 4 E-5 / Ag-110 3 E-5 I Ba-140 2 E-5 / /R4 8 E-3 I l Br-83 3 E-6 Sn-ll3 Ba-141 None Br-% 2 l None In-ll3m 1 E-3 J Ba-142 None .

Br-35 tbne Sb-122 3 E-5 / ta-140 2 E-5/

Rb-86 2 E-5 / Sb-124 2 E-5 / la-142 None ,

FJre8 !bne Sb-125 1 E-4/ Ce-141 9 E-5 # '

Rb-89 None Te-125m 1 E-4 s Ce-143 4 E-5 J i Sr-69 3 E-6# Te-127m 5 E-5 # Ce-144 1 E-5 #  ;

Sr-90 3 E-7/ Te-127 2 E-4 / Pr-144  ;

} Sr-91 5 E-5/ Te-129m 2 E-5 / W-187 None 6 E-5 #

i Sr-92 6 E-5 Np-239 1 E-4 #

I If a mclide is not listed, ' refer to 10CFR20, Appendix B, and use the erst i corservative insoluble / soluble MPC eere tky are given in Table II, Colten 2.

' 2 None - (As per 10CFR20, Appendix B) 7b MPC limit for any single radiomelide f not listed above with decay :: ode otMr than alpha e=ission or spontaneous

  • fission and with radioactive half-life less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />." .

E i

@Mk MPC 5 I y

  • tocegzc7 ewinkgsg 1985~

an o. tc. #N -!

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Page 66 of 84 ST. LUCIE PLANT CilEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 0FFSITE DOSE CALCULATION MANUAL (ODCM)

TAKE M-3 Selecting the Appropriate long Term (D/Q) for Dose Calculations Inwiving Radioiodines ad 8D Particulates for Grass-CcvMilk or Grass-Coat 6:

IYPE OF D W E  ! LIMITIE LIMITIE (D/Q) Value I CAUL'LATION RA'KE SECIDR 1/m2 r l Release Rate - 1/D I A l A l A l l 1/31 Davs - t/D I B l B l B l l Omrteriv-Yearly - IID l B l B B l l l 12 Consecutive ?bnths - lid l B l B l B l l Se:d-Anmal Report l C  ! C l C l 4

i A. The worst ccu or goat as per locations frcn land census. If no dik antm_l in any sector, assum a ecu at 4.25 dles in the highest (D/Q) sector over land.

B.

The historical (D5 of all land sectors with the worst cow or 4

, goat frcn each sector as reported in the land Census. A 4.25 die cru shld be assumed in the worst sector sten no dik animi is reprted.

C. The highest (D/Q) at a cd.lk animi lomtion of all dlk animls reprted in the land Cemus Report. (If no milk animla within 5 mih a 4.25 die cow shld be assmed in the sector hwing the highest (D/Q) at 4.25 miles). Actual Met Ihta shld be used for the selection of the worst case = ilk animi and for tic dme calculations. If both goat ad milk nients are reported imide 5 dies, dose calculations ahid be -

perforud on each animi a:d the higher dose animl contribution shld be used. /RS The historical wind frequency fractions for each sector are listed in Table M-8.

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, Page 72 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 0FFSITE DOSE CALCULATION MANUAL (ODCM)

APPE' DIX 3 Limital Analysis Dose Asses::ent for Liquid RaMnaaive Effheits The radioactive liquid effluents for tie years 1978,1979, ani 1980 were evalmtai to

- deter:nine the dose contribution of tN radiortclide distribution. This analysis ms perfonned to evalmte tre use of a limital dose analysis for &tec:inirs enviromental doses. Limitirg the dose calculation to a few selecta! radionclids tMt contribute the maprity d the dose provides a simplifiel cetlud of detersinirg cospliance with the dose limits of Tednical Specifica1 ton 3.11.1.2.

Tables 3-1 ard B-2 present tie results of this evalmtion. Table B-1 preserts the fraction

'of tle adult total body dose contributal by the cupr radforuelides. Table B-2 tresents the sane data for tie adult GI-LLI dose. The adult total body and adult GI-ILI were detenninal to be the limiting doses ksai on an evalmtion of all age g oups (adult, teenagr, diild, ani infant) and all orgam (bone, liver, kidney, lung, and GI-ILI). As tle data in the tables slow, the radioruelides Fe-59, Co-58, CHO, Zrr-65, Cs-134, ani Cs-137 daninate the tcral body dose; the ratio:uclides, Fe-59, co-58, ccr 60, 2n-65, ani Nb-95 dasinate the GI-LLI dose. In all but one case (1979-fish, GI-LLI dose) these radiortclides contribute 90: or note d the total done. If for 1979 the fish ani stellfish pattways are casbinal as is done to deternine the total dose,' the contribution from these nuclides is 8!.% of the total GI-LLI dose.

Therdore, the dose corait::ent due to ralicactive material in liquid effluents can be reasonably esti:nted by limiting the dose calculation to the radioruelides, Fe-59, Co-58, Co-60, Err 65, i:b-95, Cs-134, an! Cs-137, thich cmulatively cortribute the enjority of the total dose calculated by using all radfortclides detectal. This limited analysis dose assessnent metted is -

a simplifiel calculation that provides a reasonable evaluation of doses due to liquid ratioactive effluents.

Tritfu:n is not included in tie li:nited analysis dose assessaent for liquid releases beamise the potential dose resulting fran normal reactnr releases is ng;11gible ani is essentially iniepenient of radaste syste, operation. The a:ount of tritium releases anrually is about 300 -

curies. At St. Lucie, 300 Ci/yr released to the Atlantic Ocean produces a calmistal wtule body dose of 5 X 10-7 =rea/yr via the fish ani shellfish pat! ways. This anounts to less than 0.001%

of tre design objective dose of 3 2reci/yr. Furtheruore, the release of tritium is a function of operating tire an! powr level ani is essertially unrelatal to radaste systen operation. , /RS

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Pegs 80 of 84 fj ST. LUCl* 'LANT .",

dtEMISTRY OPERATING PROCEDisad No. C-200, REVISION 5 ,s.

OPFSITE DOSE CALCilLATION MANUAL (ODCN) r-APITN)IX E (contimani)

IUDlulI]GICAL ENVIILMe!NTE StRVEILIJM2, ST. LDCIE PLET Key to Sample locations SMP!E APPEXIMAIE SMPLES (DIlffrItN DISTMFE DIRECit(N pan 850f I ILCATION IES(3tIPTION OitlECIID FRFIllFNIX (iniles) SEC!I]R 11D Qiarterly 10 S l Direct h!!ation l S-10 l IS I ami SR 714 l l l l l l 11J) l Smitterly l 10 l SSE l 1

l Direct Raitiattan l S/SSE-10 l Infian Rtwr Drive an! Simil Rm lane l IMrect Raitation l N-5 l Entrance of Nettles Islant l *ni) l Qurterly l 5 l SSE l j

l Dirvet Mattarion l SSE-10 l Elliot hiessu l 11J1 l 46erterly l 10 l SSE l l LMrect httation l SE-l l Smith of Crnliry C,mul l 11D l Qiart erly l 1 l SE l l Ilirect hilarinni l 98-32 l U. of Flortila-IFAS Entianl<gy lab Vero Beach] 11D l Saarterly l 19 l teu l Airborne 15M R1, Solutation - Weatla a by hal Raitotaline & Weekly I 6 MM l Particulatt*;

Airtume 9112 nt Sutstation - SR 16, Stturt I htfota=11ru & Weily 12 l S 4 Part ioilat es I l Airtorne 1114 Disite near south progerty line hilotodine & l Wetkly I SE I Pa rt iculat e.i l

. Airtorne IG) Powr Line - 7609 Indlein Rlwr Detw h ilotallne & Wetkly 2 W l PastInilat s Airtome ILM Oiuite - At &tanroirgical Taaer .

bilotatine & Wetkly j O.$ N  ; ,

l Part in:lates l l l

! l Waterturne l 111 5 l Atlantic <icean vicinity of pinhLic tu acties l Siirface Water l Weekly l <l l DE/E/ESli l /iPs cast sitk= of hate AI A (ocean)

Sn!Iwnt Fron Soni-Anntal ly

- storeline l

Waterturne 9159 Near suth en! of flutchiedon Islant Surface Water Mothly 10-20 ( S/SSE (otwin) l Sedient Frun , Soni-Aiu aul ly l l l l l sturelt ne l. l l

  • Deswtes Control Simple i

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Pega 81 of 84 ST. LUCI 'La3rc 3gy3 OlEMisfitY OPERATING PROCEDbad NO. C-200, REVISION 5

  • OPPSITE DOSE CALCULATION MANUAL. (ODCM)- MI,b" "t APftM11X E RM)IDIR;ICAL I!NVIIDHWTAL RRtVE!IlWG Sr. IECIE PIAff Key to Saiq>1e lomtions j SN1PLE APPIGUMAIE i S#fLES QNJECTRN DISTANT DIRECTIGl PAIM&Y IIICATimi TES0t! Primi G11.1EcrTD FHFQlEN0f (rat les ) SECIUt Foat Prakects 111 5 Ocean side vicinity of St. Incie Plant Crustacea Semi-Annially <! DE/B/kSE /It5 Fish Sont-hnially l Font Prnlucts  !!51 Offsite near north property line Brami leaf Hmthly 1 N/NMi wwetation (wlen available)

(=u grew)

Ftxml Products 1l52 Offstte near eruth progerty line Bram! leaf H mthly 1 S/SSE w wetation (wl.m available) i (nuntyow)

Fon! Products 81159 Near smith en! of flutchla;on IsLint Crust.mxa Smil-hu ai,il if 10-20 S/SSE i Fish & sat-Awahilly l l

Brant teat Hmthly weitation  !

(nnigr w ) I  !

  • Denotes crmtrol sasaple it is tir p>1 icy of Florida Power & Light Gvpiny (FPL) tlut tie St. tocle 1 & 2 Raltoingical Envinumental Muitoring Prograins are cosaluctal ty tie State of Florists Ikgurtnent of 11ealth an!

hhabilitative Services (ltES), pumtunnt to an Agreement tetute 171. ant fliRS ant; tlut ctronlination of tie ILellological Environmental Hutturlig Progr.ses with l#WS anal compthmice with tie Italiolq;1 cal Envirtmeiental Kwitortig Prtgr.se Technical Spet.ificatirwu are the resp >nsibility or tie t&m: lear lhergy Services Depirinent. /R5 t

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