ML17215A774

Forwards Semiannual Radioactive Release Repts for Period Jul-Dec 1984 as Required by Tech Spec 6.9.1.10.W/o Encls

ML17215A774
Person / Time
Site:	Saint Lucie
Issue date:	03/04/1985
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-85-91, NUDOCS 8503190285
Download: ML17215A774 (42)

Text

FLCRIOA PC'VER ~~ I.lGHT cc~i;!Pki'i'4'g 04585

'-85-91 Or. J. Nelson Grace Regional Admini str ator, Region I I U. S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street NW Atlanta, Georgia 30323

Dear Dr. Grace:

Re: St. Luci e Units 1 and 2 Docket Nos. 50-335, 50-389 Semi-Annual Radioactive Effluent Release Report Please find attached the Semi-Annual Radioactive Release Reports for the period of July 1, 1984 through December 31, 1984, as required by Technical Specification 6.9.1.10 for St. Lucie Units 1 and 2.

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/SAV/js Attachment cc: Document Control Desk (2 copies of attachment)

Harold F. Rei s, Esquire P NS-L I-85-87-1

~85 85030+

g503190~8 PDR ADOC} 050pp335 pDR R

REGUL ATi)R Y INF QHb! ATION DISTR I oUT ION SYSTEH (R IDS)

!, FACIL:50-335 St.

ACCESSION NdR:8503190268 50-389 St ~

GuC.DATE: 85/03/04 Lucie Planti Unit 1I Florida Power NOTARIZED: HO Lucie Plant< Unit 2, Flor ida Power a Light Co S Light Co ~

~

DOCKET 05000335 05000389 AUTd, fvANE AUTHOR AFF ILIAT IOiV wILLIAYS~JtW~ Florida Power R, Light Co ~

REC IP ~ NiANE RECIPIENT AFFILIATION GRACEpJ.N ~ Region 2i Office of Dir ector

SUBJECT:

Forwards semiannual radioactive release repts for period Jul-Dec 1984 as required tiy Tech Spec 6.9.1.10,A/o encls.

DISTRIBUTION CODE: IE25L COPIES RECEIVED:LTR ENCL SIZE:

TI TLE: Periodic Environ Honi toring Rept (50 GK ) Annual/Semiannual/Ef fluent/

NOTES: 05000335 OL:02/pi/76 05000389 OL:04/06/83 RECIPIENT COPIES RECIPIENT COPIES Ii) CODE/NAIVE L.TTR ENCL ID CDOE/NAME LTTR ENCL NRR OR&3 BC 04 NRR OR83 BC p4 INTERNAL: ACRS 11 AEOD IE F ILE 01 NRR/DE/EEB 08 NRK RAB 09 NRR/DS I /,'METB NR /DSI R 10 RGN2/DRSS/EPRPe

/f118 EXTERNAL: LPDR 05 NRC PDR 02 TOTAL NLi~laf R OF COPIES HE 'ULRt.D: LTTR 26 ENCL 2

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L Fl-FIETS MASTER FIL FLORIDA POWER & LIGHT COMPANY gS 3 0 1085 L-85-339 Dr. 3. Nelson Grace Regional Administrator, Region II U.S. Nuclear Regulatory Commission Suite 2900 IOI Marietta Street NW Atlanta, Georgia 30323

Dear Dr. Grace:

Re: lSt. Lucie Units and-2~

1 Docket Nos. 50-335 and 50-389 Semi-Annual Radioactive Effluent-Release Re ort Attached is the Radioactive Effluent Release Report for the period of 3a~nuary.

[f, 1985 through Sune 30, i~985 for St. Lucie l and 2; as required by Technical Specification 6.9.1.10.

The data for the'"Volume of Dilution Water Used During Period" on Tables 3.3-l and 3.3-2 are reported, in accordance with plant procedures, to be the volume of dilution water used during periods of release only. The total volume of dilution water used for each unit during the entire period would be as follows:

Ist uar ter (liters) 2nd uar ter (liters)

St. Lucie Unit I 2A6EII 2.06EII St. Lucie Unit 2 2.06E I I 2.06E I I The Plant procedures will be changed so that in the future, we will report the total volume of dilution water used during the period, consistent with the interpretation contained in the NRC letter, on that subject, dated August 8, 1985.

Should you or your staff have any questions on this information, please contact Us ~

Very truly yours, 3.W. Williams, 3r.

Group Vice President Nuclear Energy 3WW/SA V/ms Attachment cc: I Directory Office of Inspection and Enforcement9 USNRC J Document Control Desk, USNRC Harold F. Reis, Esquire

~ PNS 303/I PEOPLE... SERVING PFOPLE

FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE PLANT UNIT 'NO>> 1 & 2 LICENSE NO>> DPR-67 & NPF-16 COMBINED SEMI-ANNUAL RADIOACZIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Janua 1985 THROUGH June 30 1985

TABLE OF CONTENTS DES CRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 OFFSITE DOSE CALCULATION MANUAL REVISIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o6 LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMtfATION BY QUARTER UNIT 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~7 UNIT 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 13 UNIT 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 SOLID WASTE - SHIPMENT SU5fATION~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ol7 OFFS ITE DOSE CALCULATION IfANUAL PAGE REVIS IONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oATTACHMENT A

Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits 1.1 For Liquid Waste Effluents

a. The concentration of radioactive materia'1 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 dissolved or entrained noble gases. For dissolved or entra)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 < 1.5 mrems to the total body and to < 5 mrems to any organ, and During any calendar year to < 3 mrems to the total body and to < 10 mrems to any organ.

1.2 For Gaseous Waste Effluents:

l

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

For Noble Gases: < 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:

< 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 < 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 duri,ng any calendar year to < 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. Maximum 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 l.l.a of this report.

h 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 effluent accounting methods is described in Table 3.1.

A summary of gaseous effluent 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 TvVe ~Aveva e Maximum Liquid +9% +30%

Gaseous +10% +35%

,y II 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 LIQUID SPZPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Each Batch Principal Gamma Emitters .h.a.

Monitor Monthly H-3 L.S.

Tank Com osite Gross Al ha G.F.P ~

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

Com osite FE-55 Continuous Daily Gamma Em

'rincipal tters Releases Grab & I-131 4/M Composite Samples p.h.a.

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

Gross Alpha Com osite Monthl G.F.PE Sr-89, Sr-90, & Fe-55 Com osite uarterl C.S ~

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 effluent totals.

p.h.a. gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are .identified and quantified L.ST Liquid Scintillation Counting C.S ~

Chemical Separation G.F.P. Gas Flow Proportional Counting 4/M four per month

Page 4 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

4. Measurements and Approximations of Total Radioactivity (continued) 4 .1 (continued)

b. (continued)

TABLE 3,2 RADIOACZIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING TYPE OF METHOD OF SOURCE FRE UENCY ANALYSIS ANALYSIS Waste gas Principal (G)

Decay Tank Each Tank Gamma Releases Emit ters ~ h.a.

Containment ,Principal Gamma Purge Each Purge Emi t ters ~ h,a.

Releases H-3 L+S ~

Principal Gamma (G~ C~ P)

Weekly Emitters ~ h.a.

H-3 L S ~

Monthly Gross P G.F ~ P ~

Plant Composite Alpha Vent (Particulates)

Quarterly SR-90 C ~S ~

Composite SR-89 (Particulates)

Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample L.S ~ Liquid Scintillation Counting C+S ~ Chemical Separation p.h.ao Gamma spectrum pulse height analysis using -Lithium Germanium detectors. All peaks are identified and quant ified GoF ~ PE Gas Flow Proportional Counting

Page 5 FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE UNIT NO ~ 1 & 2 SEMIANNUAL REPORT Januar 1 1985 THROUGH June 30 1985 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORHATION (continued)

5. Batch Releases F 1 Liquid UNIT 1 UNIT 2

a. Number of batch releases: 22 22

b. Total time period of batch releases: 1.06E04 1.06E04 MINUTES

c. Haximum time period for a batch release: 660 660 MINUTES

d. Average time period for a batch release: 482 482 t f1 NUTES

e. Hinimum time period for a batch release: 322 322 MINUTES

f. Average stream flow during periods of release of effluent into a'lowing stream: 1.02E06 1.02E06 GPH 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 HINUTES

c. Maximum time period for a batch release: 1592 1920 MINUTES

d. Average time period for batch releases: 570 291 HINUTES

e. Minimum time period for a batch release: 164 35 MINUTES ALL GASEOUS WASTE RELEASES ARE SUMMARIZED IN TABLES

6. Unplanned Releases 6.1 Liquid

a. Number of releases:

b. Total activity releases: , 0 CURIES 6.2 Gaseous

a. Number of releases:

b. Total activity released: 0 CURIES 6.3 See attachments (if applicable) for:

a. A description of the event and equipment involved.

b. Cause(s) for 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 Januar 1 1985 THROUGH June 30 1985 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

7. Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC is reported on the January Report.

8~ Offsite Dose Calculation Manual (ODCM) Revisions:

Seven pages were revised. Pages 19, 25, 66, and 72 correct typographical errors. Page 53 changes Ag-110m to Ag-110 to be consistent with ORNL/NUREG/TM-102 Reference. Pages 80 and 81 identifies the H15 Sample Distance (< < 1 mile instead of 1 mile. Page 81 also had a comment added to identify the agency actually conducting the sampling program and their interaction with Florida Power & Light Company.

None of the above changes affected the methodology of dose calculations of the ODCM.

9. Solid Waste and Irradiated Fuel Shi ments No irradiated fuel shipments were made from the site. Common solid waste from St. Lucie Units 1 and 2 were shipped jointly. A summation of these shipments is given in Table 3.8 of this report.

10. Process Control Pro ram Revisions No revisions were made during the reporting period.

Page 7 FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE UNIT NO ~

SEMIANNUAL REPORT Januar 1 1985 THROUGH June 30 1985 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER f/ 1 UARTER fI 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) CI 5.4 2E-01 2.19E-01

2. Average diluted concentration durin eriod uCI/ml 1.17E-08 6.12E-09 B. Tritium '.

Total Release CI 1.01 E02 7.75 E01 I

2. Average diluted concentration durin eriod uC I /ml 7 ~ 27E-06 2. 16E-06 C. Dissolved and Entrained Gases

1. Total release CI 1.58E "00 2.38E-01

2. Average diluted concentration durin eriod uCI/ml 3.42E-08 6.66E-09 D. Gross Alpha Radioactivity

1. Total Release CI E ~ Volume of Waste Released

( rior to dilution) Liters 1.59 E06 1.27 E06 F. Volume of Dilution Water Used Durin Period Liters 4.62 E10 3 ~ 58 E10

I It

Page FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT Januar 1 1985 THROUGH June 30 1985 TABLE 3 '-1 LIQUID EFFLUENIS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER /i' UARTER /7 2 UARTER /k 1 UARTER /h 2 Na-24 CI 0 0. 0 5.25 E&5 CR-51 CI 0 0 2 '3 E-04 7.55 E-03

~m-54 CI 0 0 5.85 E-03 1 ~ 12 E-03 MN-56 CI 0 0 0 0 Co-57 CI 0 0 0 0 Co-58 CI 0 0 8 '5 E-02 4,42 E-02 Co-60 CI 0 0 3 ~ 48 E-02 3.47 E-02 Fe-59 CI 0 0 3.32 E-03 6.55 E-04 Fe-55 CI 0 0 2 ~ 94 E-02 8 ~ 90 E-02 A -110 CI 0 0 0 1 ~ 11 E-05 SN-113 CI 0 ID 0 2.45 EW5 0 S

W-18 N

7'I b-122 S b-124

-239 CI CI CI 0

0 0

0 0

0 1.04 E-03 5.45 E&4 0

0 8 ~ 30 0

0 E-05 5.65 E&4 I-131 CI 0 0 3.17 E-02 1.39 E-02 I-132 CI 0 0 0 0 I-13 3 CI 0 0 1.90 E-04 7.00 E-4 CI 0 0 0 0 I-135 CI 0 0 0 0 Zr-95 CI 0 0 8 ~ 90 E-04 1.30 E-03 Nb-95 CI 0 0 0 0 ZR-97 CI 0 0 0 0 Nb-97 CI 0 0 0 4.04 E-05 Mo-99 CI 0 0 0 0 Tc-99M CI -

0 0 1.46 E-04 2 '2 E-04 RU-103 CI 0 0 1.82 E&4 2.69 E&4 S b-125 CI 0 0 7.50 E-03 4 64 E-03 Cs-134 CI 0 0 1 ~ 15 E-Ol 6 ~ 50 E-03

Page 9 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO ~ 1 SEMIANNUAL REPORT Januar 1 1985 THROUGH June 30 1985 TABLE 3.4-1 LIQUID EFFLUENZS (continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 01 UARTER //2 UARTER f31 UARTER //2 Cs-136 CI 0 0 6.40 E-03 1.27 E-04 I Cs-137 CI 0 0 2.17 E-01 9.85 E-03 I Ba-140 CI 0 0 . 0 La-140 CI 0 0 1.18 E-03 2.41 E-03 I Ce-141 CI 0 0 5.60 E-5 3 ~ 11 E&4 I Ce-14 4 CI 0 0 0 5.40 E-04 Sr-89 CI 0 0 4 ~ 77 E&4 8 ~ 90 05 I Sr-90 CI 5.55 E-05 2.54 E-05 Y-90 CI 5.55 E-05 2 '4 E-05 UNIDENTIFIED CI TOTAL FOR PERIOD ABOVE CI 5.42 E-1 2.19 E-1 AR-41 CI 0 0 KR-85 CI 0 0 0 XE-13 1M CI 0 3.76 E-03 0 XE-133 CI 0 1.56 EWO 2.33 E-01 XE-133M CI 0 1.28 E-02 2.16 E-03 XE-135 CI 0 3 ~ 14 E-03 3.21 E-03 KR-85M CI 0 0 0 XE-138 CI TOTAL FOR PERIOD ABOVE CI 1.58 E 00 2.38 E-01 NOTE: If no value is entered for a nuclide, the value equals zero Curies.

Page 10'LORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT J anuar 1 1985 THROUGH June 30 1985 TABLE 3 ~ 3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER /7 1 UARTER /f 2 A. Fis sion and Activation P roducts 1 ~ Total Release (not including tritium, gases, alpha) CI 5.73 E-01 2.19 E-01

2. Average diluted concentration durin eriod uCI/ml 9 '9 E-09 5.03 E-09 B~ Tritium

1. Tot'al Release CI 1 ~ 01' 02 1 ~ 55 E 02

2. Average diluted concentration durin eriod uCI/ml 1.45 E-05 3.56 E-06 C. Dissolved and Entrained Gases

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

2. Average di.luted concentration

, durin eriod uCI/ml 3.44 E-08 5.47 E-09 D. Gross Alpha Radioactivity

1. Total Release CI E . Volume of Waste Released

( rior to dilution) Liters 5.50 E 06 3 ~ 53 E 06 F. Volume of Dilution Water Used Durin Period Liters 6 ~ 17E 10 4 ~ 35E 10

Page FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE UNIT NO ~ 2 SEMIANNUAL REPORT J anuar 1 1985 THROUGH June 30 1985 TABLE 3 4-1 LIQUID EFFLUEN1'S CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 0 1 UARTER fi' UARTER fP 1 UARTER /k 2 Na-24 CI 1 +40 E-03 0 0 5 ~ 25 E-05 CR-51 CI 0 0 2.53 E-04 7.55 E-03 MN-54 CI 1 ~ 11 E-04 0 5.85 E-03 1 ~ 12 E-03 MN-56 CI 0 0 0 0 Co-57 CI 0 0 0 0 Co-58 CI 0 0 8.55 E-02 4.42 E-02 Co-60 CI 0 0 '.48 E-02 .3.47 E-02 Fe-59 CI 0. 3.32 E-03 6.55 E-04 Fe-55 CI 1 ~ 56 E-03 3.98 E&4 2 ~ 94 E-02 8' 90 E-02 A -110 CI 0 0 0 1 '1 E-05 SN-113 CIA 0 0 2.45 E&5 0 S b-122 CI 0 0 1.04 E-03 8.30 E-05 S b-124 CI 0 5.45 E&4 5 ~ 65 E-04 W-187 CI 0- 0 0 0 N -239 CI 0 0 0 0 I-131 CI 5.71 E-03 2.43 E-04 3.17 E-02 1.39 E-02 I-132 CI 4 ~ 24 E-03 0 0 0 I-133 CI 9.95 E-03 0 1.90 E-04 7.00 E-4 I-134 CI 0 0 0 0 I-135 CI 0 0 0 0 Zr95 . CI 0 0 8.90 E&4 1.30 E-03 Nb-95 CI '-

0 0 0 0 ZR-97 -

CI 0 0 0 0 Nb-97 CI 0 0 0 4.04 E-05 Mo-99 CI 0 0 0 0 Tc-99M CI 0 0 1.46 E-04 2.22 E-04 RU-103 CI 0 0 1 ~ 82 E&4 2 ~ 69 E-04 Sb-125 CI 0 0 7.50 E-03 4 ~ 64 E-03 Cs-134 CI 1 ~ 51 E-03 1 ~ 52 E-05 1.15 E-01 6.50 E-03

Page 12 FfORIDA POWER & LIGHT COMPAiH ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT J anuar 1 1985 THROUGH June 30 1985 TABLE 3.4-1 LIQUID EFFLUENZS (continued)

CONTINUOUS MODE BATCH MODE I NUCLIDES RELEASED UNIT UARTER /Pl UARTER /$ 2 UARTER // 1 UARTER // 2i I

Cs-136 CI 0 0 6.40 E-03 1.27 E-04 I I

Cs-137 CI 2.10 E-03 3.54 E-05 2.17 E-01 9.85 E-03 Cs-138 CI 4 .82 E-02 0 0 I Ba-140 CI 0 8 ~ 14 E-06 0 0 I

La- 140 CI 0 0 1.18 E-03 2.41 E-03 I I

Ce-141 CI 0 0 5.60 E-5 3.11 E-04 I

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

Sr-89 . CI 0 0 4.77 E-4 8.90 E 05 I Sr-90 CI 0 0 5.55 E&5 2 ~ 54 E-05 V-90 CI 0 0 5 ~ 55 E-05 2 ~ 54 E-05 UNIDENTIFIED CI TOTAL FOR PERIOD ABOVE CI 3 ~ 14 E-02 7.00 E-04 5042 E-01 2.19 E-01 I

AR-41 CI .0 0 0 0 I

KR-85 CI 0 0 0 I

XE-131M CI 0 0 3 ~ 76 E-03 0 I I

XE-13 3 CI 0 2 50 E-05 1 '6 E 00 2.33 E-01 I

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

XE-135M C 8 '5 E-03 0 0 0 XE-138 CI 0 0 0 TOTAL FOR PERIOD ABOVE CI 9.39 E-03 .2.'50 E-05 1.58 E 00 2.38 E-01 NOTE: If no value is entered for a nuclide, the value equals zero Curies ~

Page 13 FLORIDA POLAR & LIGHT COMPANY ST. LUCIE UNIT, NO. 1 SEMIANNUAL REPORT J anuar 1 1985 THROUGH June 30 1985 TABLE 3 ~ 6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UAKTER 6' UARTER fi' A. Fission and Activation Gases

1. Total Release CI 1.89 E 04 9 '3 E 03 2.. Avera e Release Rate for Period uCI/sec 2.40 E 03 1.26 E 03 B. Iodines

1. Total Iodine-131 CI 1.31 E-01 5 '6 E-01

2. Avera e Release Rate for Period uCI/sec 1.66 E-02 6.67 E-02 C. Particulates

1. Particulates T-1/2 > 8 Days J CI 3.75 E&5 1.43 E&5 2~ Average Release Rate for Period )

uCI/sec 4.82 E-06 1.82 E-06

3. Gross Al ha Radioactivit CI 1 '2 E-07 5.44 E-08 D. Tritium

1. Total Release CI 2.43 E 02 1.08 E 02 2 Avera e Release Rate for Period uCI/sec 3.08 E 01 1.37 E 01

Page 14 FLORIDA PO'i<ER 6 LIGHT COMPAiVE ST ~ LUCIE UNIT NO 1 SEMIANiVUAL REPORT Januar 1 1985 THROUGH June 30 1985 TABLE 3 '-1 GASEOUS EFFLUENZS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER // 1 UARTER tk 2 UARTER /t 1 UARTER /J' 1 ~ FISSION GASES AR-41 CI 2.55 EOO KR-85 CI 2 ~ 71 EOO 2 41 EOO KR-85M CI 1 ~ 20 E02 1 ~ 52 E02 2.06 E01 2.73 E-1 KR-87 CI 1.67 Eol 5.9b EOI 3 ~ 11 EOO KR-8 8 CI 4.03 Eo1 1 ~ 85 E02 1.74 Eol 1 ~ 63 E-1 XE-131M CI 4 ~ 15 EOO 3.45 EOO 4.55 EOO XE-13 3 CI 8 ~ 38 E03 6.27 E03 8.93 E03 1 ~ 96 E03 XE-133M CI 3 '2 Eol 6 '8 E01 7 ~ 12 E01 1.43 Eol XE-135 CI 9.32 E02 1.18 E03 2 ~ 98 E02 1.37 Eol XE-135M CI 2+55 EOl XE-138 CI TOTA[ FOR PERIOD ABOVE CI 9 ~ 53 E03 7 ~ 93 E03 9 ~ 35 E03 2+00 E03 2 ~ IODINES I-130 CI I-131 CI 2 '5 E-02 1.95 E-02 I-132 CI 2 ~ 19 E-01 I-13 3 CI 1.02 E-01 9.07 E-02 I-135 CI 1 97 E-01 TOTAL FOR PERIOD ABOVE CI 1 ~ 31 E-01 5 '6 E-01 3 ~ PARTICULATES Co-58 CI Co-60 CI S R-89 CI SR-90 CI Y-90 CI I-131 CI 3 ~ 75 EW5 1.43 E&5 CI TOTAL FOR PERIOD ABOVE CI 3.75 E-05 1.43 E-05

Page 15 FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE UNIT NO ~ 2 SEMIANNUAL REPORT Januar 1 1985 THROUGH June 30 1985 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCL IDES RELEASED UNIT UARTER f 1 UARTER /2 A. Fission and Activation Gases

1. Total Release I CI 2.96 E 03 1.62 E 03

2. Avera e Release Rate for Period uCI/sec 3.75 E 02 2.05 E 02 BE Iodines 1~ Total Iodine-131 CI 5.23 E-02 1.16 E-01

2. Avera e Release Rate for Period uCI/sec 6.63 E-03 1.47 E-02 CD Particulates

1. Particulates T-1/2 ) 8 Days . CI 1.76 EW5 2.82 EW5 2~ Average Release Rate for Period uCI/sec 2.26 E-06 3.59 E-06

3. Gross Al ha Radioactivit CI 2.65 E-07 1.41 E-09 D. Trit ium

1. Total Release I CI 3.83 E 01 6.79 E 01 I

2. Avera e Release Rate for Period uCI/sec 4.86 E 00 8.61 E 00

Page 16 FLORIDA POWER 6 LIGHT COi~lPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT Januar . 1 1985 THROUGH June 30 1985 TABLE 3 '-2 GASEOUS EFFLUENZS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER /f 1 UARTER /t 2 UARTER // 1 UARTFR 13 2 1 ~ 'ISSION GASES AR-41 CI 2.89 E 00 3002 E 00 KR-85 CI 1.38 E-01 KR-85M CI 1 ~ 38 E 01 8.34 E 00 6085 E-01 1 ~ 60 E 00 KR-87 CI 6.52 E-02 1 51 E-01 KR-88 CI 1.81 E 00 9.47 E-01 1 ~ 64 E 00 XE-131M CI 2.49 E 00 1 83 E 00 XE-133 CI 2 ~ 19 E 03 1.20 E 03 4 ~ 94 E 02 2 ~ 22E 02 XE-133M CI 4 ~ 90 E 00 2 ~ ll EOO XE-135 CI 2.40 E 02 1.57 E 02 1 ~ 10 E 01 1 ~ 31 E 01 XE-135M CI 0 XE-138 CI TOTAL FOR PERIOD ABOVE CI 2.44 E 03 1.37 E 03 5.17 E 02 2.46 E 02 2 ~ IODINES I-130 CI I-131 CI .2 ~ 71 E-02 5.54 E-02 I-132 CI 3.43 E-02 I-133 I-135 CI 2 '2 E-02 2 '2 E-02 CI TOTAL FOR PERIOD ABOVE CI ' 23 E-2 1.16 E-1 3 ~ PARTICULATES Co-58 CI Co-60 CI SR-89 CI S R-90 CI Y-90 CI I-131 CI 1 76 E-05 2 ~ 82 E&5 CI CI TOTAL FOR PERIOD ABOVE CI 1 ~ 76 E-5 2 '2 E-05

Page 17 TABLE 3.8 Y

EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1-June. 30, 1985 St. Lucie Unit Nos. 1 6 2 A. SOLID '@PASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL (Not irradiated fuel)

&month Eet. To tel I. Type of waste .Unit

. Period Error, SS

a. Spent resins, filter sludges, evaporator m 4.5 El bottoms, etc. Ci 62 E220 El

b. Dry cotnpressible waste, contaminated 2.0 E2 equip, etc. Cl 2. 0 El 2.0 El

c. Irradiated components, control m E rods, etc. Ci E E d Other (describe) E E

2. Estimate of major nuclide composition (by type of waste) r

a. Cs-137 4. 2 E.l Cs-134 2.1 E 1 Co-60 5.6 EO Co-58 1.3 E 1 Fe-55 8.4 EO E

b ~ Cs-1 7 1.6 El Cs-134 8.0 EO Co-60 2.2 El 0 1.1 E 1 Fe-55 1.8 El 1.5 E

3. Solid Waste Disposition Mode of Trans ortation Destination 12 Sole Use Truck Barnwell, S.C.

2 Sole Use Truck Richland, Wash.

L IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi ments Mode of Trans ortation Destination

,; ~ .~ . ~ ~

4 l1

~

'FLORIDA POMER & LIGHT COMPANY UT. LUCIE UNIT NOE. I AIIO 2 EEIIIANNUAL REPORT JANUARY I 1995 TEROUCN JUNE 39 1995 TABLE 3.9 (C I.)

solid waste suPPle333enc Total Total Note 1 Type Note 3 R.G. 1.21 T eNOte 4 Solidification Maste Volune Curie principal NOteS 1.2 of of Agenc Classification Cu-Pc ~EI I Radionuclides Waste ~COUP Container (or Absorbent 6798 3.687 None PWR Trash l.b Non-Specification None Strong Tight Pkg.

966 195 0.686

16. 449 'i,63 63 90 90 Sr, Hone 137 137 Cs PWR PMR Ion-Exchange Resin Trash l.a l.b Hon-Specification Strong Tight Pkg.

NRC Certified LSA > Type A None None 390 227.530 Ni, Sr, Cs PMR Ion- l.a NRC Certified None Exchange Resin LSA > Type A 121 364.338 129 63 90 60 137 PWR Ion- l.a NRC Certified None I ~ NiE Sr ~ Co ~ Cs Exchange Resin Type B 134 58 131 54 95 55 Cs, Co, I, Hn, Nb, Fe 14 99 129 60 63 90 PMR Filters l,a HRC Certified Hone 121 26.670 C, Tc, I, Co, Ni, Sr, Type B 137 54 57 58 59 95 Cs, Mn, Co, Co, Fe, Hb, 95 113 Zr, Sn TOTAL VOLUME: 8591 FT TOTAL ACTIVITYc 639.360 Curies

Page 17B FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE UNIT NOS. I AND 2 SEMIANNUAL REPOSER January l, 1985 THROUGH June 30, 1985 TABLE 3.8 (Cont.)

Solid Waste Supplement Note 1: The total curie quantity and radfonuclfde composition of solid waste shipped from the St. Lucfe Plant are determined using a combination of qualitative and quantitative techniques. In general, the St.

Lucie Plant follows the guidelines outlined fn the Low-Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Class)ffcatfon (5/11/83) for these determinations.

The most frequently used techniques for determining the total curie quantity fn a package are the dose-to-curie methods and the (Concentration) X (Volume or Mass) calculations. Where appropriate, engfneerf ng type actfvatfon analyses may be applied. Since each of the above methodologies involves to some extent qualitative

'arameters, the total curie quantity fs c'onsidered to be an estimate.

The composition of radionuclfdes in the waste fs determined by bath on-site analyses for principal gamma emftters, and periodic offsfte analyses for other radfonuclides. The onsfte analyses are performed either on a batch basis or on a routine basis using reasonably.

representative samples as appropriate for the waste type. Offsfte analyses are used to e~tabIfsh scaling factors or other estimates for radionuclides such as H, C 99Tc, 129I, TRU, 241Pu, 242Cm 63Nf, and 55Fe.

Note 2: "Principal Radionuclfdes" refers to those radfonuclides contained 'in the waste in concentrations greater than .01 times the concentration of that nuclide listed fn 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, 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.

Page 18 FLORIDA POWER R LIGHT COMPANY ST. LUCIE UNIT NO 1 2 2 SEMIANNUALREPORT Januar 1 1985 THROUGH June 30 1985 ATTACHMENT A G

CHANGES TO OFFSITE DOSE CALCULATION MANUAL DURING PERIOD JANUARY 1, 1985 THROUGH JUNE 30, 1985 PAGE REVISIONS ATTACHED

4 Page I of 8 FLOREA K4KR & LEQK CMPNY STo LUCIE OKRAIL~G PR3QDURE Ã)e C-200 FLAN'KQSTRY M~SEPl 5 TITLE nws.i~

Offsite Dose Calculation ihrual (ODOM) JL Reviewed by Facility Revim Group Anrii 22 I982 Approved by C. M. Vethv Plant Manager ril 27 1982 Revision 5 RevieM by P R G / - / I9/$

Approved by Plant ~ir S -19' rect cf J'lc if l outer P <~Pg<<'va(

Page 19 of 84 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.2 (continued) 1.'implified Total Body Dose Rate Calculation Fran an evaluation of past releases, an effective total body dose factor (Keff) can be derived. This dose factor is in effect a weighted average total body dcse factor, i.e., mighted by tbe radionuclide distributfan typical of past operation. (Refer to Appmx1hc C for a detailed explanation and evaluation of Keff)~ The vatue of K pf has been derived from tbe radioactive noble gas ef flints for the years 1978, 1979, ani 19o The value is:

6.8 K 3 K<f 18 Sresrve This value nay be used in conjunction with the total noble gas release rate

( Qi) to verify that the instantaneous dase rate is within the allowable lind.tso 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 88 -K 0.8 To further sfoogfT the deteualuatiou, tha historical arcual average seteorolcgfcsl X/Q of 1.6 X 10 sec/aP (Fran Table 8-1) may be suQtituted into the equation.

Also,,the dose lind.t of 500 mrem/yr may be substituted for tIT . Making these substitutions yields a single cunulative (or grass) noble gas release rate lind.t.

This value is'oMe gas release rate limit ~ 3.5 X 10 uCi/sec As long ay the noble gas release rates do not exceed this value (3.5 X 10 uCi/sec), no additional dose rate calculations are needed to verify canpliance with Tednical Specification 3.11.2.1.

2. Setpoint Detezmdnation To canply with Tech Spec. 3.3.3.10, the alarm/trip setpoints are eshglished to ensure that tbe noble gas re1eases do not exceed the value of 3.5 X 10 uCi/sec, which corresponds to a total body dose rate of 500 mrem/yr. The aathxl that follows is a st~~tep ~cedure for establishing the setpoints. To allow for multiple sources of releases frcm different or camnn release points, tbe alliable operating setpoints wiil be controlled admbdstratively by allocating a p rcentage of the total allowable release to each of the release sources.

A Deteradne (V) the maxilann voluaa release rate potential fran the i~lant pr es for the release source under consideration. The units of (V) are f /non.

'age 25 df 84 ST 'UCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)

The calculations of Sections 2.3;1, 2.3.2, 2.3.4, ard 2.3.5 msy be md.tted. The dose rate calcuLrtions as specified in these sections are inctuded for ccmpleteness and are to be used only for eraluatizg unusual ~cunstances ~re releases of particulate asterials other than raKoiodines: in airborne releases are ahmrmally high. The calculations of Sections 2.3.1, 2'.3.2, 2.3.4, ard 2.3.5 wi11 typically be used to demonstrate ccmpliance with the dose rate limit of Tech. Spec. 3.11.2.1 for raiioiadines ard particulates when the aaasurel releases of particulate material (other than radioiodines and with half lives 08 days) are )10 times the aaasured re1errses of radioiodines.

1. The Instantaneous Inhalation Dose Rate Method:

NZE The H-3 dcse is calculated as r 2.3.4 A The controllirg location is asamed to be an Infant located in the sector at the mile range. The (X/Q)D for this location is sec/az . This value is ccrrrmm to all nuclides. (See Table M-2'or valm, sector and rang..)

B. Enter the telesse r~te ln ft / annof tIn release source and convert to crjssc ft X 2.8317 X 10 cc X mtn crjsec min f 60 sec.

C.'olve for gi for nrclide (i) by obtainimg the uCi/cc assay value of the release source activity and aultiplying it by the przxbrct of 2.3.1.B above.

(nrclide i as ) uCi X (Value 2.3.1.B) cc uCi/sec for nuclide (i)

D. Obtain the Ri value frcm Table G-5 for the organ T.

E. Solve for DR DRiT ~ RiT (X/Q)D Qi ~ {~~

uCi~

X sec aP X uCi sec mean The Dose Rate to organ T frcm nuclide (i) r~

F. Repeat steps 2.3.1.C through 2.3.1.E of the source.

for each mclide (i) reported in the assay

Page 53 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 5 OFFSITE DOSE CALCULATION MANUAL (ODCN)

TABLE L-1 NAXMM KRGSSIBLE G)iV(ZNIRATIONS LV WAKR LV UMESTRICTH) AREAS Nuelidel ~C (uC;./ml) Nuclide mC (uCi/ml) duelldei mC (uCi/ml)-

H-3 3 E-3~' Y-90 2 E-5~ Te-I 29 8 EH >

Na-24 L.-S J Y-91m 3 E-3~ Te-131m 4 E-S ~

P-32 2 E-5 ~ Y-91 3 E-5> Te-131 None Cz Sl 2 E-3 ~ Y~ 6 E-S~ Te-132 E-S~

~54 Y-93 3 E-5> I-130 3 E-6

~56 Zr-95 6 E-5'+ I-131 3 E-7 ~

Fe-55 8 E4~ Zz 9I I-132 8 E-6>~

Fe-59 5 E-5~ idler 95 I-133 1 EW Co-57 4 E-4 ~ Vb-97 9E~J I-134 2 E-5 >

Co-58 9 E-s~ i>9-99 4 E-5 I-135 4 E-6 >

Ccr60 .3 E-5~ Tc-99m 3 E-3~ Cs-134 9 E-6>

iVims 1 EH" Tc"101 None Cs-136 6 E-5>

Gra4 2 E-4~ R 103 8 E-5 Cs-137 2 E-S~

~5 1E-4> Ru-105 1 EA~ Cs-138 iVone Zrr69 2 E-3'/ Ru-106 1 E-S > Ba-139 None Bz-'82 4 E-5 ~ Ag-1 10 3 E-.;~ Ba-140 2 E-5>

Bz-83 3 EW Sn-113 8 E-S~ Ba-141 Nme Bz-84 None2 In-113m Ba-142 None BM5 None Sb-122 La-140 2 E-5>

Rb-86 2 E-5 > Sb-124 2 E-5> Ia-142 None 8 None Sb-125 1 E~J Ce-141 9 E-5~

Rb-89 None Te-l~~ rQ v Ce-143 4 E-S~

SM9 3 E+~ Te-127m 5 i-5" Ce-144 1 E-5~

Sz-.O 3 t'-7 w Te-127 Pr 144 None Sr-91 5 E-5 Te-129m ~ -;5> V-187 6 E-5 S K 6 E-5 Np-239 1 E-4 ~

If a -.u"Lide is r.oc usted, refer co 10CKO, .-'~pnZc B, a~3 use che xsc conse.":ative inso~ble/soluble WC ihere ch,i e given in Table II, Colunn 2.

None (As p r 1~0, Appendix B) "Vo M'C 1'Mc for any single radionuclide noc 3~seed above with decay zode och.r than alph- emission or sponcanecus

'ission and with radioactive half-life less dan 2 ~i

~ I ~e~

~k IXII e S 1

tt C.Fh" C'

C'...i

Page 66 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C 200 ~ REVI SION 5 OFFSITE DOSE CALCULATION MANUAL (ODCM)

LZQE M-3 Selecting the Appropriate Long Term (D/Q) for Dose Calcu1ations Involving Radioiodines and SD Particulates for Gras~~03k or GrasrGoaMiilk:

UMETLG LLGTIl6 (D/Q) Ualue

! SECm 1/8 Release Rate - LCD I A A A

(

. 1/31 Davs Lm I B I B I B I rterl Yearlv UD ~

B B B 12 Consecutive Months L(D l B I B B C C l'I C

A 'Ihe worst cow or goat as per locations frcm 1and ce~. If no mL1k animal in any sector, assum a cow at 4.25 milch in the highest (D/Q) sector over'a&.

B. The historical (D/Q) of all land sectors with th,worst cow or goat frcm each sector as reported in the Land Census. A 4.25 mile cow should be asamed in the erst sector when no mLlk animal is r~rted.

C. Tne highest (D/Q) at a mQk an'~ location of all milk animQs reported in the land Census Re~rt. (If no mi1k animals within 5 ad.les a 4.25 mile ccats shxQd be asmaad in th sector having the highest (D/Q) at 4.~D miles). A~ Yet Data shoed be used for the selection of the worst ~~ arLk animal ard for the dme mlcu1ations. If both goat ard

, milk aralu~ are reported imide 5 miles, dose calculations shculd be perforned on each animal ard the ~er dose aninal contribution skuld be used.

The historical wind frequency frac=ions for each sector are listed in Table ~.

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

APPENDIX B Limited Analysis Dose Assessment for Liquid Radioactive Efflu nts Ihe radioactive liquid effluents for t?e years 1978, 1979, arri 1980 were evaluatal to determine the dose contribution of the radionuclide diswibution. 3ds analysis was p rformed to evaluate the use of a limited dose analys's for detenni&rg erNironnental doses. Limitirg the dose calculation to a few selected radioru" lido'hat contribute the maj)rity of the dose provides a simplified tret?od of detennin'~ ccnpiiance Cth the dose Limits of Technical Specif icaiton 3.11.1.2.

Tables B-1 a+i B-2 present the results of t~ evaluation. TabIe B-1 presents the fraction of the adult total body "dose contributed by the ma~r radionuclides. Table B-2 prea.nts the sana data for t?a adult GI-LLI dose. The adult total bcdy ard adult GI-LLI were determined to be the limiting doses based on an evaluation of all age g reps (adult, teenager, child, and irdant) and all organs (bone, liver, kidney, lung, ard GI-LLI). As the data in the tables show, the radionuclides Fe-59, Co-58, Ccr60, Ztr65, Cs-'34, and Cs-l.37 dcminate the tctal body dose the radioruclides, Fe-59, Co-58, Ccn60, Zrr65, aM Nb-95 dcminate the GI-LLI dose. In all but one case (1979-fish, GI-LLI dose) these radionuclides contribute 98'r nore aE the total dose. If for 1979 t?e fish ard s?ellfish ~t?ways are canbined as is done to determine the total dose,'he contribution fran these nucL'des is 84% of the tccal GL-LLI dose.

Therefore, the dose crnrzi~nt due to radioactive material in liquid effluents can be reasorahly es ~ted by ~ting the dose calcuiation to the radiornx'.1'ides, Fe 59~ Co 58, Ccr60,

~~t'~~~y cor ribute the majority of the total dose Pl Z~5, .'".o-95, Cs-134, aM Cs-137, which calculated by using all radionuclides detected. ~is limited analysi.s dose assessnent net?nd is a simplified calaxlation that provides a rmsorabw evaluation of doses du'o liquid radioactive ef r luents.

Tritium is nct included in th lated analysis dose assesaranx for liquLd re1esses because the potential dose resulting from normal reactor releases is negligible and is esxntially irdependent of radiate systen operation. Th anoint of tritium releases anrually is abcut 3GO curies. At St. LucLe, 300 Ci/yr released to the At3antic Ocean produces a calcu1ated w?ale body dose of 5 X 10 nomen/yr via the fish arri s'.all ish pathways. 'Ihis anuunts to less than 0.001X of the design objective dose of 3 mrem/yr. Furthernore, the release of trLtiumis a fmction of operati~ time aM pomr level ard is essen ially corelated to radwaste system operation.

~

Page 80 of 84 ST, LUCI'LANT L1IEMISTRY OPERATING PROCEDbad NO ~ C-200 'EVISION 5 OPPSITE DOSE CAI.CULATION MANUAL ODCM

'PPIM)IX E

(continued)

IUOI(Xl)GICALENVIIK)QRNl'AL SURVEf LLAMZ ST. LUCIE P~r Key to Sample locations SAHPIZ APPROXIM<<GE QHKRS 03USCf I(N DISXhNX DIMTKN awLEcfa) (<nf les) SECKR Direct Luflation S"10 US I anti SR 714 'le) I iarterl 10 S Direct Radfati<m S/SSE-10 Indian River Drive aixl <ail Run lane rterl 10 SSE Df rect Radfatio<t SSE-5 Entra<)ce of Nettles Island rterl SSE'0 Direct kadfatftu< SSE-10 Llliot ~aN< tartar l SSE Direct Radf ation Sl:;I South of Coolf < C<uu<1 uirterl SE I) frect R<<dfat lon lt-32 O. ot'l<<rlda-IP'hS 6<Limni ~

Iab Vero Beach ( rturl IKS FVI. Sufr.tat foil W<u<tliu<'by Roid Radfof<ull>>L< 6 Weddy Part. 1(w<l<<t us Airborne WI12 Fl'L Soll'tatI<u< hR 76, Stiurt Radiof<uUnL' WLefdy 12 p

Part lc<<lat es Airborne lll4 Omfte ne<<r south 1<rol<erty line R<<dfofo<lfn & WL< de SE P;irt lr<< latLs Airbor<ie I'~r I.lne 7609 I>>dlnii Rt vut'rtvu R<<diof<xlf<<L 6 Waddy I'<it't.

0<<sf te At MLtoorob<tlf<.al T<~r Ilail.it<a'ulfolodf<u.

Airborne 104 & WL<tkly 0.5 Parti ciil;iten Waterborne Atlantic Ocean vfcfnity of. puhflc Iieaclies Surface Water Weekly ENE ESI:

Last sly'f Route AIA (OCL<i<n)

Sediment Frun Semi-A<natal ly sir<reline Waterborne WI59 Near s<x<th L<<d of Ilutchfnson Island Surface Water M<ulth ly 10-20 S/SSE (ou"<n)

SedfnL<<t Prun Son<I A<urn<I Iy i<h)re I lite

• Dunotes Colltrol San@le

V Page Hl of 84 ST. LUCI 'LANT LREHISTRY OPERATING PROCEDt,atl NO ~ C-200, REVISION 5 OPPSITE DOSE CALCULATION MANUAl. ODCH APPENHX E fVDI(XlSICALENVIK%%?ÃI'AL SURVEMJAZ ST ~ LUCIE PI%K Key to Saraple Locations ShHPIZ APPHOXMGR (DllECI'ICH DISTAN(Z DIRECEICH (nriles) SECKR Food Products l65 Ocean side vicinity of St. Lucie Plant . Czustacea Semi-AnnraIly Fish Semi-A>>nuall Food Products Offsite near north property line Broad leaf Honthly vega tat ion (wlen available)

(rrlll il ove)

Food Products ll52 Offsite near south pr'operty line Brurd leaf Ho>>thly S SE ve~eatat b>>> (wlierr uvai.lable)

(rnrrr arrvu)

Food Products Nerrr south errd uf Uutchlnson Islaal Cnrst.>>c<<n 'Sw<<l-Amoral ly l0-20 S SSE Flair Seward-Ar>>aud ly Bru<<l leal Holltlrly vugr ta t loll (nrrr 'ruvu)

• DLAote8 control saint)le It is tie policy of Florida t'~~r & Llglit Curquny (FPL) tlrat the St. Lucie l & 2 Radlolnglcal Ellvlrr)lwlelltnlHrxlltorlllg PrograrlU are corducted by tire State of Florid;r Ik;partra:nt of Uealtli ard Relrabilitative Servi~ (ASS), lxrnirant to an Ay.cern.nt betwrwri FPL arrd lXNS aal; that cirerdlnatiori of the Rarliol~~iM Enviroarental Honiturir g Progr>>re wit.h IWMS arxl cunplla>>ce with the Radiolcgical Envirrxaa.rital Hrxil turing Prugraa Teclvtical Speci ficat low are the resporaibillty ot tlru Nuclear lilergy Services Departrrent.

P Too Distribution

Subject:

L 85 339 August 30, 1985 From: J.W. Williams, Jr.

NRC CORRESPONDENCE ST. LUCIE UNITS I &2 GO: D.A. Chancy (3) PSL I: L.L. McLaughlin J.W. Dickey Vault Custodian (4)

J.H. Francis R. V. Crlenjak (NRC)

D.C. Poteralski JB: G.J. Boissy PSL 2: C.T. Hamilton S.G. Brain N.T. Weems R.F. Englrneier G.E. Crowel I (ISEG)

B.J. Escue F.G. Flugger F.P. Green PTP 3!4: Document Control (K. York)

J.B. Harper C.S. Kent H.D. Mantz F.A. Panzani J.L. Parker OTHER: W.J. Harris (Combustion)

Harold Reis, Esq. (Newman)

M. Horrel I (Ebasco)

L 85 55O No, of coploaI 28 OO/05/85 SOISSV DRAIN CH4NCY CRLCHJAK CRONCLL<ISCO) DANCK DICKCY CNOLHCICR CSCUL PLUOOCR CRANCIQ ORCCN H4NILTON HARPLR H4RR IS HORRCLL KCNT HANTI HAL4UOHLIN PANZ4NI PARKCR POTCRALSK! ROIS SCLLQ VAULT CUSTODIAN NCCNS If ILI IANS ~ Or YORK

l 1

IP