ML17215A820

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1983. W/840301 Ltr

ML17215A820
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1983
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-84-52, NUDOCS 8504100287
Download: ML17215A820 (74)

Text

BETS MASTER FILE REGULATORY INFORMATION O'IST t=FF-P'8 8 q Nt3R 85041002>> -- - D"C ~

St. Luci e P lant~ <<Uni t <~ F ori da DATE'ACIL:50-335 1 1 Power L Light Co ~ 05000335 SO SS9 St, -Luoie- P lantq Unit 2jj Florida Power S Light Co, 05000389 AUTH,HARE AUTHOR=AFFILIATION AILLIAMSFJ.W, Florida Power 8 Light Co, RECIP ~ NAME. RECIPIENT AFFILIATION O'REILLY'S J.P, Region 2F Office of Director S UBJECT: "Semi. annual-gadioaotive Effluent Release ReptiJul Oeo 19SS,"

H/84030.1 ltd DIST~~BU~ION CODE: IE2SL COPIES RECEIVED:LTR ENCL SIZE~

TITLE: Periodic EnYiron Monitoring Rept (50 DKT) Annua /Semiannual/Effluent/

NOTES: 05000335 OL;02/01/76 05000389 OL:04/06/83 RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME, LTTR ENCL ID CODE/NAt1E LTTR ENCL NRR OR83 BC 04 7 7 NRR ORB3 BC 04 7 7 INTERNAL: ACRS 11. AEOD 1 1 IE F ILE 01 NRR/DE/EEB 08 1 1 I 9 NRR/DSI/i4IETB 2 2 NRR/DS I / 0 RGN2/DRSS/EPRPB 1

/MIB EXTERNAL: LPDR 1 1 NRC PDR TOTAL" NUMBER OF COPIES REQUIRED'TTR 2& ENCL 26

P. O. BOX 14000, JUNO BEACH, FX 33408 FLORIOA POWER Si LIGHT COMPANY March 1, 1984

">> 5 I,-84-52 Mr. Jaaes P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street NW, Suite 2900 Atl anta, Georgi a 30303

Dear Mr. O'Reilly:

Re: St. Lucie Units 1 and 2 Docket Nos. 50-335, 50-389 Semi-Annual Radi oacti ve Effluent Release Re ort Please find attached the Semi-Annual Radioactive Release Reports for the period of July 1, 1983 through December 31, 1983 as required by Technical Specification 6.9.1.10 for St. Lucie Units 1 8 2.

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

Vice President Nuclear Energy Department JWW/PLP/djc Att achment cc: Document Control Desk (2 copies of attachment)

Harold F. Reis,, Esquire.

P NS-L I-84-65 DESIGNATED ORIGINAL' CB-<ifie4 B r

II

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PEOPLE... SERVING PEOPLE

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FLORIDA POWER & LIGHT COMPANY ST. LUCZE PLANT UNTT NO. I LICENSE NO+ DPR-67 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD S504100287 831231 PDR ADOCN 05000335 R PDR

TABLE OP CONTENTS DESCRIPTION PAGE TECHo SPECo LIMITS AND METHODS OF ANALYSISo ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oooo' I EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATIONo~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 4 LIQUID EPFLUENT SUMMATION OF ALL RELEASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~o ~ ~~~~ 9 LIQUID EPFLUENT NUCLIDE SUMMATION BY QUARTERo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ol0 LIQUID EFFLUENT DOSE SUMMATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~~~~~ ~~~~~~~~~~ 12 GASEOUS EPPLUENT SUMMATION OF ALL RELEASESo ~~~~~~ ~ ~~~~~~~~~ ~ ~~~~~~ 13 GASEOUS EFFLUENT - NUCLIDE SUMMATION BY QUARTERo ~ ~~~~~ ~~~ ~~~ ~~~ ~ ~~~ 14 GASEOUS EPFLUENT DOSE SUMMATIONoo ~ ~~~~~~~~~~~~~ ~~~~~~~~~~~~~ ~~~~~~ 15 SOLID WASTE SHIFMENT SUMMATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~~~~ ~~~~ ~~ ~~~ ~~~ ~ 16

Page 1 EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION 1~ Regulatory Limits are listed by quarter. During Quarter P3, Environmental Technical Specification-B in effect as follows:

l,l For liquid waste effluents (ETS-B) a The concentration of radioactive materials released in liquid waste effluents from all reactors at the= site shall not exceed the value specified in 10 CFR Part 20,, Appendix B, Table II, Column 2,, for unrestricted areas

b. The cumulative. release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/reactor/calendar quarter.

c The cumulative release of radioactive material in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci/reactor in any 12 consecutive months 1,2 For gaseous waste effluents (ETS-B) a (1) The release rate limit of noble gases from the site shall be such that:

2 ' (QT V

K ) < 1 and V

V'33(OT L + 1+i V

N V

l) <1

'(2) The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days,,released to the environs as part of the gaseous wastes from. the site- shall, be such that:

5+5' 10 QV < I' (1) The average release rate of noble gases from the site during any calendar quarter shall be such that:

13 (QT N ) < 1 V'

and 6+3.(QT M ) < 1 V V (2) The average release rate of" gases from the site during any 12 consecutive months shall be:

25 (QT N ) < 1 and V V 13(QT M) <1 V V

Page 2 EFFLUENT AND PASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued 1, Regulatory Limits: (continued) 1 ~2 (b) (continued)

(3) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that:

13 (5 ' X 10 ) < 1 (4) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be such that:

25 (5 5 X 10 g<) < 1 (5) The amount of Iodine -131 released during any calendar quarter shall not exceed 2 Ci/reactor (6) The amount of Iodine 131 released during any period of the 12 consecutive months shall not.exceed 4 Ci/reactors

Page 3 Duxing Quarter 0'4, Standard Technical Specification-A in effect as follows:

1.1 For Liquid Waste Effluents (STS-A) ai The concentration of radioactive material released fxom the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for xadionuclides other than dissolved or entrained noble gases For dissolved or entr~ined 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 r'adioactive 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.

For Gaseous Waste Effluents: (STS-A) 1.2 a The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluentsi fxom the site shall be limited to:

For Noble Gases: ~ < 500 mrems/yr to the total body and Fox'odine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

< 1500 mrems/yr to any organ, b DOSE Limits and Percent of Limits due to Noble Gases to areas at or beyond the SITE BOUNDARY. are not applicable to the Semiannual Report since these limits are related to Historical Meteorological Conditions The Noble Gas Air Doses due to gamma and beta radiations provided in this report were calculated using meteorological conditions concurrent with the time of release~

Ce Dose Limits and Percent o f Limits due to Iodine-131, Iodine-133, Tritium-, and radionuclides. in particulate form to a MEMBER OF THE PUBLIC;at ox'eyond the SITE BOUNDARY are not applicable'o the Semiannual Report since these limits are related to Historical Meteorological Conditions . The DOSE from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greatex'han.8 days provided in this report were calculated using meteorological conditions concurre'nt with the time of release,-

2 Maximum Permissible Concentrations AIR Release concentrations, are limited'o dose'a'te limits as described in 1 2 a of this report WATER 10 CFR Part 20, Appendix B,, Table II, Column 2

Page 4 3, Average energy of fission and activation gases in gaseous effluents is not applicablei 4~ Measurements and Approximations of Total Radioactivity A summary of liquid effluent accounting methods is described iri Table 3.1 (ETS-B) and Table 3.1 (STS-A) ~

A summary of gaseous effluent accounting methods is described in Table 3 2 (ETS-B) and Table 3 2 (STS-A) ~

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 + lOZ b Analytical Error for Nuclides Tg~e ~Avera e Maximum Liquid +9X +30X Gaseous klOX +35X

Page 5 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

~cnntfnued) 4~ Measurements and Approximations of Total Radioactivity (continued) 4,1(b) (continued)

TABLE 3 1 (ETS-B)

RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OP METHOD OP SOURCE PRE UENCY ANALYSIS ANALYSIS Each Batch Principal. Gamma p>>h>>a>>

'onitor Emit ters Tank Monthly H-3 L>>S>>

Releases Com osite. Gross Al ha G>>P>>P>>

Quarterly SR-90 C>>S>>

Co osite SR-89 L S>>

Continuous No continuous activity releases Releases for* this re ortin eriod 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,S - Liquid Scintillation counting C S, Chemical Separation G.P.P. - Gas Plow Proportional Counting TABLE 3 ' (ETS-B)

RADIOACTIVE GASEOUS WASTE SAMPLING'ND ANALYSIS GASEOUS SAMPLING TYPE OP METHOD OF

' ANALYSIS SOURCE PRE UENCY ANALYSIS Waste gas Principal Gamma G, C, P Decay Tank Each, Tank Emitters h a Releases H-3 L>>S ~

Containment ~

Principal Gamma G, C, P Purge Each Purge-- Emitters h a>>

Releases H-3 L>>S>>

Principal Gamma G% C% P Weekly Emitters .h.a.

Monthly Gross P -LG>>F>>P>>

S>>

Plant Composite Alpha Vent (Particulates)

. Quarterly SR-90 C>>ST Composite SR-89 L>>S>>

Particulates G Gaseous Grab SampXe C' detectors' Charcoal Filter Sampl'e Particulate Filter Sample L S~ - Liquid Scintillation counting C>>S>> Chemical Separation pha - Gamma spectrum pulse height analysis using Lithium Germanium

.'ll; peaks're identified G>>F>>P>> - Gas Plow Proportional. Counting.

and, quantified

Page 6 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued 4~ Measurements and + proximations of Total Radioactivity (continued) 4.1(b) (continued)

TABLE 3 1 (STS-A)

RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OF METHOD OF SOURCE FRE UENCY ANALYSIS ANALYSIS Each Batch Principal Gamma pehoao Monitor Emitters Tank Monthly H-3 LES+

Releasesl Com osite Gross Al ha GoFoPe Quart er ly SR-90, FE-55 CATS+

Com osite SR-89 Continuous No continuous activity releases Releases for this re ortin eriod 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 TABLE 3 ' (STS-A)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Waste gas Principal G% C3 P Decay Tank Each Tank Gamma p,h.a, Releases Emitters Containment Principal Gamma G, C, P Purge Each Purge Emitters h.a ~a Releases H-3 LeSi Principal Gamma G. C. P Weekly Emitters ~h a H-3 L+S ~

Monthly Gross P GoF+Po Plant Composite Alpha Vent (Particulates)

Quar ter ly '

SR-90 CiSi &

Composite , SR-89 'L Se (Particulates)

G Gaseous Grab Sample C - Charcoal Filter Sample P - Particulate Filter Sample L,S ~ -'iquid Scintillation counting C S - Chemical Separation.

p,hia - Gamma spectrum pulse height. analysis using Lithium GExmanium detectors. All peaks are identified and quantified GiFiP, Gas Flow Proportional Counting

Page 7 PLORIDA POWER 6 LIGHT COMPANY STi LUCIE UNIT NO+ 1 SEMIANNUAL REPORT Jul I 1983 THROUGH December 31 1983 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued 5 Batch Releases 5>>1 Liquid a Number of batch releases: 34 b, Total time period of batch releases: 15167 MINUTES c .Maximum time period for a batch release: 579 MINUTES d Average time period for a batch release: 446 MINUTES e Minimum time period for a batch release: 314 MINIJTES f Average stream flow during periods of release of effluent into a flowing stream: 529460 USM.

ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5 2 Gaseous a Number of batch releases: I b Total time period for batch releases: 177 MINUTES c . Maximum time period for a batch release:, 177 MINUTES

d. Average time period for batch releases: 177 MINUTES e Minimum time period for a batch release: 177 MINUTES ALL GASEOUS WASTE RELEASES ARE SUMMARIZED IN TABLES 6i Unplanned Releases 6.1 Liquid ai, Number, of releases: 0 b Total activity released: 0 CURIES 6 2 Gaseous a Number of releases:- 0 bi .Total activity released: 0 .

,'"3 See attachments (if applicable) for:

CURZES'o ae A description of the event, and equipment involved b Cause(s) for the unplanned release Actions taken to prevent a recurrence d Consequences of the unplanned release

Page 8 Assessment of radiation dose from effluents to the GENERAL PUBLIC due to their activities inside the site boundary .assume the visitor was on-site, for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, at an average distance of Oi3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St Lucie Site VISITOR DOSE RESULTS:

GASEOUS PARTICULATES AND IODINE EXPOSURE ORGAN DOSE meem e

Bone lm61E-5 Liver 2.4 E-3

'Thyroid 7 ' E-3 Kidney lml E-3 Lung ~

2.4 E-3 GI-LLI 2.4 E-3 Total Body 2.4 E-3 NOBLE GAS EXPOSURE Gamma Air Dose 1.6 E-2 mrads Beta Air Dose 4,0 E-2 mrads Sm .OFFSITE DOSE CALCULATION MANUAL REVISIONS The semiannual report for License No . NPF-16 contains the ODCM C-200 Rev, 04 changes for this reporting interval, The ODCM is a site manual etc.,

and License Nom DPR-67 is affected. the same as License Noi NPF-16 (Unit

2) ~ 3 9 -SOLID WASTE AND IRRADIATED FUEL SHIPMENTS:

No irradiated fuel shipments were made from the site Common solid waste from St~ Lucie Unit 1 and 2'ere shipped )ointly and the quantities of radioactive material are listed in Tabular Form in the back of this report

Page 9 FLORIDA POWER & LIGHT COMPANY ST+ LUCIE UNIT NO+ 1 SEMIANNUAL REPORT TABLE 3 '

LIOUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER 3 UARTER 4 A~ Fission and Activation Products I ~ Total Release (not including .

tritium, gases, alpha) CI 3 09E-1 2 '4E-1 2, Average diluted concentration during period uCI ml 1 58E-8 2+43E-8 3 Percent of A licable Limit Percent 3 '9E-O N/A

)BE Tritium )

1 Total Release . CI 3o 52E+I 2 OOE1

}

2 Average diluted concentration durtn~artad uCI/ml 1 ~ 79E-6. 1.94E-6 C Dissolved and Entrained Gases 1

2 Total release Average diluted concentration j'I 1.54E-2 -7 19E-2 durin eriod uCI/ml 7 '3E-10 6 99E-9 Do Gross Alpha Radioactivity-1~ Total Release 0 0 E>> Volume o Waste Released

( rior to dilution) Liters 96E6 1 45E6 F Volume of Dilution Water Used Durin Period Liters' I 96E10 1 03E10

Page 10 FLORIDA POWER & LIGHT COMPANY ST, LUCIE UNIT NO+ 1 SEMIANNUAL REPORT TABLE 3+4 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 3 UARTER UARTER 3 UARTER 4 I-131 )~CE 1 22E-4 1 56E-2

"" "I--532 I-133 ~C~I 0 5 '5E-4 Ne-24 ~CI 1 1

36E-4 35E-2 1 23E-3 0

CI 3 25E-3 2 28E-3 MN-54 CO-31 C0-58

~CI CI 2 ~ 13E-2 5 95E-3 FE-55 CI 1 ~ 51E-2 1 38E-2

)

FE-59 CI 3 '3E-5 0 CO-60 ) CIJ 9 '8E-2 4 09E-2 ZN-65 CI NB-97 J CI AG-llOM CI SN-113 CI "SS-122 CI 4.39E-3 3 55E-3 SB-124 CI J 2.93E-3 2.44E-3

]

W-187 CI NP-239 CI ZR-95 CI 2 28E>>4 0 MO-99 CI 1 74E-4 0 RU-103 CI

'" ~CI~

CS-134 5.29E-2 6 20E-2 Cs-"134" cx 8.23E-2 03E-1 CS-137 L CI 1 ~

BA-140 CI CE-141' j C'I]

xA-i4o '~cz 0 . 5 '5E-4 8 17E-4 0 ZR-97 J CI L NB-95'I 8 OOE-4 0

Page 11 FLORIDA POWER & LIGHT COMPANY STi -LUCIE UNIT NOD 1 SEMIANNUAL REPORT Jui'i 1983 THROUGH December 31 1983 TABLE 3 '

LIQUID EFFLUENTS (continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER t 3 UARTER 4 UARTER 3 UARTER 4 I 02E-2 07E-2

'z

}

SB-125 CI 1

}

'E-144 CI 3 82E-4 0

}

SR-89 CI 1 '9E-4 1 38E-4 ER-PO O Y-90 CI 0 }

Tc-99M CI 0 Pr-144 CI 5 llE-4 0 TOTAL FOR PERIOD ABOVE CI 3 09E-1 2 64E-l AR-41 KR-85

""XE-131M XE-129

'IJ CI L CI }

1~

8 1

17E-2

'5E-6 79E-3 7 0

0 05E-2

}

J

}

} XE-122E J CEJ 0 4 '7E-4 }

XE-135 CI 5 98E-5 1 01E-3 CIJ }

XE-138 CI 1 91E-3 0 TOTAL ABOVE FOR'ERIOD CI 1~ 54E-2 7 19E-2

.Note:' If no value is1 entered for a r

nuclide, the,,value equals zero Curies

Page 12 FLORIDA POWER & LIGHT COMPANY ST LUCIEUNIT NO+ 1 SEMIANNUAL REPORT Jul 31 1983 THROUGH December 31 1983 TABLE 3+5 LIQUID EFFLUENTS DOSE SUMMATION Age Group: Adult Location: Any Adult Exposure Interval: From October I 1983 through December 31 1983

• FISH & SHELLFISH CALENDAR YEAR PATHWAY TO DOSE ORGAN 'mrem

)

Bone 4 65E-2

)

Liver 1.51E-I Th roid 2.56E-2

)

Kidne 1 '2E-2

)

Lun 1+4 E-l GI-LLI 6 95E-2

) T ~ Bod 5 85E-2 )

• This exposure interval is the effective calendar year due to the implementation of Amendment 59 (Appendix I) to S.T+S. - A on October 31, 1983 for St'ucie Unit 81 The 1984 year will be the first full calendar year'or calculating dose as per SiT~Si

Page 13 FLORIDA POWER & LIGEZ COMPANY STe LUCIE UNIT NOe 1 SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 TABLE 3+6 GASEOUS EFFLUEKZS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER 3 UARTER Ai, Fission and Activation Gases 1~ Total Release } CI 1 86E-2 0

} 2 Average Release Rate for Period } uCI sec 2 34E-3 0 3 Percent of Tech S ec Limit X 6 '4E-6 B~ Iodine s

}

~ Total Iodine-131 } Cr 0 0

2. Average Release Rate for Period } uCI/sec 0 0

3. Percent of Tech. S ec. Limit X 0 C Particulates

} 1 Particulates T-1/2 ) 8 Days } CI 7.34E-5 0 2~ Average Release Rate for Period uCI/sec 9 '3E-6 0 }

3 Percent of Tech..Spec Limit X 6 69E-5 }

4 Gross Al ha Radioactivit CI 0 1 01E-08 D Tritium Total Release CI 3 OOE1 1 85E2 }

2 'vera e Release Rate for Period 'uCI sec 3'7EO 2 '3E1

Page 14 FLORIDA POWER & LIGHT-COMPANY STe LUCIE UNIT NO+ I SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 TABLE 3 '

GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASE UNIT UARTER 3 UARTER 4 UARTER 3 UARTER 4 lo FISSION GASES AR-41" CI KR-85 CI 1+86E-2 0 KR-85M CI KR-87 CI KR-88 CI XE-131M CI XE-133 CI XE-133M CI XE-135 CI XE-135M CI XE-138 CI TOTAL FOR PERIOD ABOVE CI 1 86E-2 0 2~ IODINES I-130 CI I-131 CI I-133 I-135 TOTAL FOR

'I CI PERIOD ABOVE CI 3~ PARTICULATES Co>>58 CI Co-60 CI 7 ' E-5 0 SR-89 CI SR-90 Y-90 CI CI CI CI TOTAL FOR PERIOD ABOVE CI 7~34E-5 0

ST IIJCIE l51T 0 I TABIZ 3a8 GASKUS EH?OJMS DQR SltMHQH gJARIIR 0 N/A AAE IRIIP: IEPAMZ EZKEIEE INB?EVAL: PEIH 1 IXT 83 IIEOIIII 31 188 83A BQR 2MSID T, ME (mxem) (axea)

Gmund Plane A NA 0

}'ss-Ca~1k . B 0 5.868-2 5.868-2 2%57E 2 5.86E-2 5.86E-2 5.86E-2 }

Inhalation A 0 2+9K-2 2 9E-2 I 27E-2 2 9E-2 2.9E-2 }

0 8.768-2 8.76E-2 3.84E-2 8.76E-2 8.76E-2 8 76E-2

} (A) SJPCC: ter RAMZ: 1 78 miles } } B GM KlhT SECHR: MST RAZZ: 4.25 miles }

CAUMM YEN (aaad)

Beta Air Dose N/A 0

} Sector: 1 78 Note: The dose values above ate calculated using actual meteorological data during the specified tiaa interval with MK data neduoed as per Reg, Guide l,ill, Hsrch 1976,

• %is exposure interval is the effective calendar year due to the iaplemntaticn of Aaendaent 59 (Appendix I) to S.T.S -A on October I, 1)83 for St, lacie Mt tl The 1984 year will be the first full calendar year for calculating dose m per S TD

.FXORIDA POWER 6 LIGHT CCMPMY PAGE 16 ST. LUCXZ UNIT ~a. 1 GEE!INUAL REPORT FFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT (1983)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS for ST. LUCIE TRGT NOS. 1 and 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL (Not irradiated fuel)

l. ~of waste Unit theone Period Est. Totlf Error, SS

a. Spent resins, filter sludges, evaporator bottoms etc. 2.00 E 1

b. Dry compressible waste, contaminated m E equip, etc. Ci 2.05E 1 2.00 E 1 c Irradiated components, control m E rods, etc. Ci 9.35 E 4 2.00 61 d Other (describe) E Ci E E

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

. Cobalt 60 9.2 El

~t-

b. Cobalt, 60 Cesium 137 58

.1 6.0 5,8 EO 2.6 El E

El Cesztm- E lr~~ 1.0 EO ci E Cobalt 58 1.9 El Iron- -

Chrcmium 51 23 EO anese - 54 EO Nickel 63 3.3 EO

3. Solid Waste Disposition Destination 41 .

Sole use truck Barni~, SC 5: Sole use txuck Richland, %lash.

Br IRRADIATED FUEL SHIPMENTS (Oispositionl r

Number of Shi ents Mode of Tran rtation Destination Note:- During the above period'here were m.

shi~ts of radioactive waste classified according to ]0 CPR Part 61.

FLORIDA POWER 6 LIGHT COMPANY UT LUCIN PLANT UNIT NO 2 LICENSE NO NPF-16 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Jul 1 1983 I

THROUGH December 31, 1983

TABLE OF CONTENTS DESCRIPTION PAGE DISPOSAL SUPPLEMENTAL INPORMATION OFPSITE DOSE CALCULATION MANUAL REVISIONS. ~ ~

LIQUID EFFLUENT - SUMMATION OP ALL RELEASESe ~ o ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ eoe ~ ~ ~ o ~e ~~7 LIQUID EPFLUENT NUCLIDE SUMMATION BY QUARTERe ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ oo ~ ~~8 LIQUID EPFLUENT DOSE SUMMATION ~~~~ ~~ ~~~ ~~~~~~~~~ ~~o ~~~~~~~~~~o~~ 10 GASEOUS EPPLUENT SUMMATION OP ALL RELEASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~ ll GASEOUS EPPLUENT NUCLIDE SUMMATION BY QUARTERo ~ ~ ~ ~~~~~~~~~~~~~~~~ 12 GASEOUS EFFLUENT DOSE SUMMATIONe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~~~~~ ~~~~~~~~ ol3 SOLID WASTE - SHIPMENT SUMMATION ..'..................................14 ODCM REVISIONS ........,..........................-:.... ATYACHMFNT A

Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1~ Regulatory Limits F 1 For Liquid Waste Effluents ae 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 dissolved or entrained noble genes gor dissolved or entre)ned noble gases, the concentration shall be limited to' 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 and to < 5 mrems to any organ, snd

'. mrems to the total body During any calendar year to < 3 mrems to the total body and to < 10 mrems to any organ 1 ' 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 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 'OSE Limits and Percent of Limits due to Noble Gases to areas at or beyond the SITE BOUNDARY are not applicable to the Semiannual Report since these limits are related to Historical Meteorological Conditions The Noble Gas Air Doses due to gamma and beta radiations provided in this report were calculated using meteorological conditions concurrent with the time of release, c.: Dose Limits and Percent of Limits due to Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY are not applicable to the Semiannual Report since these limits are related to Historical Meteorological Conditionse, The DOSE from Zodine-131, Zodine-133,.

Tritium,'nd radionuclides in particulate form with'alf-lives .

greater'than 8 days provided *in this report weie calculated using e

meteorological, conditions concurrent with the time of release vie, *o., ~~eevsvepvv~n.

"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 I l.-a of this report AIR: Release concentrations are limited to dose rate limits described in I 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 I A summary of gaseous effluent accounting methods is described in Table 3i2~

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 + IOX, b . Analytical Error for Nuclides

~P~ Ave~ra e M&XX&&&

Liquid +30Z

+IOX" AX'aseous

" +35X

Page 3 EPPLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

~

(continued) 4 l Measurements and Approximations of Total Radioactivity {continued) 4 1>>b (continued)

TABLE 3 '

~

RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OP METHOD OP SOURCE PRE UENCY ANALYSIS ANALYSIS Each Batch Princi al Gamma Emitters ~ h.a.

Monitor Monthly H-3 L>>S ~

Tank Co osite Gross Al ha G>>P>>P>>

Releases Quarterly SR 90, SR-89 C>>ST Co osite FE-55 Continuous No continuous activity releases Releases for this re ortia eriod Boric Acid Evaporator condensate is normally recoveied 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 Countiag C.S Chemical Separation G P.P Gas Plow Proportional Counting TABLE 3 '

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING TYPE OP METHOD OP SOURCE PRE UENCY ANALYSIS ANALYSIS'rincipal Waste gas G)

Decay Tank Each Tank Gamma Releases Emit ters ~ h>>a Cont ai ament Principal Gamma G Purge Each Purge Emitters ~ h.a Releases H-3 L>>S>>

Principal Gamma G C>> P Weekly Emitters ~ h a>>

L>>S ~

Monthly Gross P - G>>P>>P>>

Plant: Composite Alpha, Veat (Particulates)

Quarterly SR-90 C>>S ~ .

t ~

Composite SR>>89 (Particuiatee G Gaseous Grab Sample C Charcoal Pilter Sample P: Particulate Filter Sample L>>S ~ Liquid Scintillation Counting C>>S, Chemical Separation p>>h>>a>> Gamma spectrum pulse height- aaalysis using L'ithiCn Germanium detectors>>. All peaks are identified and quantified G>>F,P Gas Plow Proportional Counting...

Page 4 FLORIDA POWER 4 LIGHT COMPANY ST, LUCIE UNIT NO, 2 SEMIANNUAL REPORT Jul 1 1983 THROUGH Decemhei 31 1983 EFPLUEHT AHD WASTE DISPOSAI - SUPPLEMENTAL ZHPORMATZON continued 5 Batch Releases 5 1 Liquid a, Number of batch releases: 14 b Total time period of batch releases: 6365 MINUTES c, Maximum time period for a batch release: 575 MINUTES d , Average time period for a batch .release: 456 MINUTES e Minimum time period for a batch release: 314 MINUTES f Average stream flow during periods of release of effluent into a flowing stream: 544937 UPN ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5 ' Gaseous a Number of batch releases: 42 b, Total time period for batch releases: 13376 MINUTES c, Maximum'time period for a batch release: 660 MINUTES d Average time, period for batch releases: 330 MZNIJTES e Minimum time period for a batch release: 23 MINUTES ALL GASEOUS'ASTE RELEASES ARE SUMMARIZED IN TABLES 6~ Unplanned Releases 6 1 Liquid

a. Number of releases: 0 b,. Total activity releases:. 0 CURIES 6 2 Gaseous.

a Number of releases: 0 b Total activity,released: 0 CURIE S, 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 nf the unplanned release,

Page 5 FLORIDA POWER & LIGHT COMPANY STe LUCIE UNIT NO+ 2 SEMIANNUAL REPORT Jui 1 1983 THROUGH December 31 1983 EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION continued)

7. Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor was on-site for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, at an average distance of 0 3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St, Lucie Site VISITOR DOSE RESULTS:

GASEOUS PARTICULATES & IODINE 'EXPOSURE NOBL'E GAS ESPOSURE ORGAN DOSE mrem Gamma Air Dose 1 6E-2 mrads Bone 1 61E-5 Beta Air Dose 4 OE-2 mrads Liver 2+4 E-3 Thyroid 7 ' E-3 Kidney 1 1 E-3 Lung 2+4 E-3 GI-LLI 2 4 E-3 Total Body 2 4 E-3 8 Offsite Dose Calculation Manual Revisions:

Revision 04 to C-200 was incorporated during the first quarter of 1984 and was used to calculate the doses reported in this Semiannual Report The affected pages are Attachment A to this report with the Revie~ and Approval attached (C-200 Page 1) ~

None of the revisions change the methodology of calculating dose, Most of the revisions fall into four general types These are:

a To correct typographical and grammatical errors bi To add more descriptive instructions where previous revisions assumed the user would be knowledgeable in all areas. These are intended to help the first time user and to avoid interpretation mistakes by being very specific~

c . Previous revisions had been in reference to proposed Technical Specifications (T.S.) ~ Since the T.S. have been finalized for both

. reactor units on site, ODCM revisions were made to correctly reference the L,C 0, numbering system and definitions of certain L,C~O~s in the implemented version of the Plant T ST which occurred in calendar year 1983N d To omit unused columns in the dose factor tables, omit nuclides with zero dose factors for all organs, and to reference nuclide symbols as per ORNL/NUREG/TM-102 'hese revisions are intended to: reduce reading errors with the dose factor tables and to omit unwanted nuclides that had been originally listed with the assumption that a revision to Reg, Guide 1 109 would have dose factor values for them.

Page 6 Three revisions require additional comment as follows:

One revision to .correct an error in.the references to table numbers was made The table numbers were reversed in the text of the ODQf for Cow-and Goat Milk in a few locationsi All dose factor tables are also labeled by title to prevent the inadvertent use of the wrong tablei No milk animals have ever been reported inside a five mile radius of the plant, hence the milk animal pathway has not been applicable to the site to date, All dose calculations are reviewed by the responsible supervisor for accuracy and use of the correct methodology, hence the error that this revision corrects has never affected our calculationsi fi Table M-2 (Selecting the Appropriate Long Term [I/Q]D or [D/Q] etc )

now specifically described in.- note {B),. the appropriate selection of the tritium (I/Q) value with regard to the location of the. milk animal 'his reAsion removes interpretation problems for users g Tabl'e M-3 (Selecting the Appropriate Long Term [D/Q] etc) footnote C now specifies a 4 25 milk animal instead of 4~5 mile Default Milk animal for Semiannual Report purposes This revision is for our convenience due to the fact that our Historical Data Sase and other systems do not list 4i5 mile values>>

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 )ointly,

Page 7 PLORIDA POWER & LIGHT COMPANY ST+ LUCIE UNIT NOe 2 SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 TABLE 3 '

LIQUID EPFLUENTS SUMMATION OP ALL RELEASES NUCLIDES RELEASED UNIT UARTER 3 UARTER 4 A Fission and Activation Products 1~ Total Release (not including tritium, gases, alpha) CI 1 45E-1 2 '4E-1 2, Average diluted concentration durin eriod uCI ml 5 08E-8 2o43E-8 B, Tritium 1~ Total Release ) CI 1 74E1 2 OOE1

/

2, Average diluted concentration durin eriod uCI ml 6 '8E-6 1 94E-6 C. Dissolved and Entrained Gases 1 Total release CI 7 '2E-3 7 '9E-2 2~ Average diluted concentration durin eri'od uCI ml 2e52E-9 6 99E-9 D Gross Alpha Radioactivity 1 Total Release CI 0 0 E Volume of Waste Released

( rior to dilution 2 83E5 1 45E6 PE Volume of Dilution Water Litersiters Used Durin Period 2 '6E9 1 03E10

Page FLORIDA POWER 6 LIGHT COMPANY ST>> LUCIE UNIT NO>> 2 SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 TABLE 3 4 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 3 UARTER UARTER 3 UARTER 4 I-131 CI 9 19E-5 1 56E-2 I-132 CI I-133 CI 1 86E-4 5 '5E-4 NA-24 CI 6 68E-4 1 23E-3 CR-51 CI 2 60E-4 0 l MN-54 CI 1 54E-3 2 28E-3 )

C0-57 CI )

C0-58 CI 1.94E-2 5 '5E-3 FE-55 CI 1 44E-3 1 38E-2 FE-59 CI 3 13E-5 0 l C0<<60 CI 9 '4E-3 4>>09E-2 ZN-65 CI NB-97 CI AG-110M CI SN-113 CI SB-122 CI 4 34E-3 3 55E-3 SB-124 CI 2 '3E-3 2 44E-3 l W-187 CK 2.73E-4 0 NP-239 CI 1 NB-95 CI 1.02E-5 0 I-135 CI 4 '5E-5 0

- RU-103 CI CS-i34 I CIJ 3 '9E-2 6>> 20E-2

'S<<136 CI CS-137 CI 5 73E-'2 1 03E-1 l BA-140 CI I CE-141 CI >>.

l LA-140 CI 5 25E-4 ZR-97 CI 1>>30E-4 0

. >>'>>>>'"<< '<<r .~r, .

". l~~~>>~tF~e<<>> ~ ~i.=

~ = . >>+~i, >>- ~<<~~~>> ~ . ~ >~>> ~ >> ~>>>>>>~r~r~

Page 9 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO 2 SEMIANNUAL REPORT Jul~I 1983 THROUGH December 31 1983 TABLE 3 '

LIQUID EFFLUENTS (continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 3 UARTER 4 UARTER 3 UARTER 4

} SB-125 CI J 9 '7E-3 I 07E-2

• CE-144 CI I ~ 31E-4 0 SR-89 j CI J I ~ 05E-5 I 38E-4 SR-95 CI

)

Y-90 CI J 0 )

TC-99M CI PR-144'NIDENTIFIED CI I 04E04 0 CI 0000EO OmOOEO 0 OOEO 0 OOEO TOTAL FOR PERIOD ABOVE CI I 44E-I 2m64E-I

} AR-41 KR-85 ) CI 5 '7E-3 0 XE-131M CI 8 05E-6 0 XR-133 ~CZ I 78E-3 7 05E-2 }

XE-133M CI 0 4.57E-4 )

XE-135 CI 5 97E-5 I ~ OIE-3 )

}

'R-85M CI XE-138 CI TOTAL FOR PERIOD ABOVE CI 7 '2E-3 7 19E-2

~ NOTE: If no value is entered for a nuclide, the value equals zero Curies .

Page 10 PLORIDA POWER 6 LIGHT COMPANY ST+ LUCIEUNIT NO+ 2 SEMIANNUAL REPORT Jul 31 1 983 THROUGH December 3 1 1 983 TABLE 3 o 5 LIQUID EFFLUENTS - DOSE SUMMATION Age Group: Adult Location: Any Adult Exposure Interval: Prom A r i1 1 1 983 through December 3 1 1 983

• FISH 6 SHELLF ISH CALENDAR YEAR PATHWAY TO DOSE ORGAN mrem Bone 7. 44E-2 Liver 2 ~ 4 1E-1 Th roid 2 65E-2 Kidne 1 95E-2 )

Lun 2 24E-I I G I-LLI 1 ~ 1 3E-1 I T~ Bod 9 39E 2 1

• This exposure interval is the effective ca 1 endar year due to the implementation of Appendi x I with License No. NPF- 1 6 in April, 1 983 ~

The 1984- year wi dose as per S, T~S ll be the first. full. calendar year for calculating

Page 11 FLORIDA POWER & LIGHT COMPANY ST+ LUCIE UNIT NOa 2 SEMIANNUAL REPORT Jul i'i983 THROUGH December 31 1983 3'

GASEOUS EFFLUENTS -TABLE SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER 3 UARTER 4 Ai Fission and Activation Gases 1, Total Release } CI 8.40El 1 17E3 2 Avera e Release Rate for Period uCI sec 1.06E1 1 47E2 B Iodines 1 Total Iodine-131 } CI 9.39E-5 1~ 24E-2 2 Avera e Release Rate for Period uCI/sec 1~ 18E-5 1 '6E-3 Ci Particulates lo Particulates T-1/2 ) 8 Days CI 0 2 05E-4 }.

2 Average, Release Rate for Period uCI/sec 0 2 58E-5 3 Gross Al ha Radioactivit CI 0 1 '8E-8 D~ Tritium

1. Total Release } CI 1.74E1 8 26E1 2 Avera e Release Rate for Period uCI/sec 2 19EOO I 04E1 }

Page 12 FLORIDA POWER 6 LIGHT COMPANY ST+ LUCIE UNIT NO+ 2 SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 TABLE 3e7 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT UARTER 3 UARTER 4 UARTER 3 UARTER 4 le FISSION GASES AR-41 CI 8e77E-1 6 '5E-1 KR-85 CI 9 '5E-2 0 KR-85M CI 0 3e32E-2 KR-87 CI KR-88 CI 0 3 '8E-3 XE-131M CI 6 '3E-2 3 '4E-1 XE-133 CI 5.24E1 1~ 07E3 2m 91El 3o43E1 XE-133M CI 1~ 46E-l 3 '0E-1 XE-135 CI 1 ~ 20EO 6 OOE1 lo49E-1 5 '2E-1 UNIDENTIFIED CI TOTAL FOR PERIOD ABOVE CI 5 36E1 1 ~ 13E3 3 04El 3 62E1 2~ IODINES I-131 CI 9 '9E-5 1~ 22E-2 I-133 CI 0 1.17E-2 I-135 CI TOTAL FOR PERIOD ABOVE CI 9~39E-5 2 39E-2 3 . PARTICULATES.

Co-5 CI Co-60 CI SR-89 CI SR-90 CI Y-90 CI CI CI CI TOTAL FOR PERIOD ABOVE CI'

Si.. IIICIE INIT 0 2 TABrZ 3.8 GASEXS EFPU3ENIS IXSE QMNATION QIARIBt PRANA BZ QEUP: INPAUI IBBBUHU INHUVAL: IUH 1 AK 83 'BUBKU 31 BE 83 To KK IKHS Ground Plane A N/A A 2 678-5 }

' 2.42E-2 5 488-2 5.53K-2 Grass-Cca&filk B) 7.88E-4 5.57PA-2 568-1 Inhalatim 3.71E4 2 71E-2 367E-1 17E-2 2 67E-2 2.67E-2 2.69E-2 }

A) 1 1 1 16E-3 8.288-2 4.938-1 3.59H-2 8 15E-2 8 15E-2 8 228-2 (A axna: mr MZ 1 78 miles } } B KM GRF SECKR: NEST RAMZ: 4 25 miles }

(PAKKR CAIBQhR YEhR (Aim. TIME INIHN%) (mead) mrad 4.09E-1 Beta Air Dose 1.04EO

-Sector: 1 78 r

Note: 'ihe dose values above were calculated usirg actual meteorological data duriqg the speci@ed tiaa interval with MEI.'ata reduoed ss per Reg, Guide 1,111, March 1976

FIORIDA POVKR 6 LICW'CXrPAtiY ST. IGCIE I>liT .',O. 2 PAGE 14

~ZKKGK REPCW July 1, 1983 through Decerkmr 31, 1983 EFFLUENT AND WASTE DISPOSAL SENIIANNUALREPORT {1983)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS for

~T. LUCIE UNZl'GS. 1 anQ 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL Iiitlot Irradiated fuel)

1. ~of~ Unit &month Period Rat. Torei Error, %

a. Spent resins, filter sludges, evaporator 5. 95E bottoms etc. Ci 2. 20E 2 2.00E 1

b. Dry compn:ssible waste, contaminated, m 2. 42E 2 equip, etc. Ci 2. 05E 2.00E 1

c. Irradiated components, control m E.l rods etc. Ci 9.35E 4 2.00E 1

d. Other {descnbe) m E Ci E E

2. Estimate of major nuclide composition {by type of waste)

Cobalt 60 9.2 E E.

b. 6.0 E c'esium 137 2.6 El

~ b E V~ anese 54 .0 EO i.c E Co

'T 50 1.9 El Chra" um 51 2.3 EO p EO Nicl~ 63 3.3- $ 0 3; SoM Waste Disposition e

Destination 41 mc'e use true): Barmn~, eC.

5 Sole use ~ck. Richland, Nash.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Destination Note: the above period there mre no shipments of

- During ra3ioactivemsteclassifiea, accoroing to 10 (XR Part 61..

I s

s e

e

~. 'ttor~rsnl'~~~..~~st:a tettoe~p~ir9%+7~*Mroret~~sts~~ot~

FLORIDA POWER 6 LIGHT COMPANY ST+ LUCIE UNIT 0 2 SEMIANNUAL REPORT Jul 1 1983 THROUGH December 31 1983 ATTACHMENT A C-200 REVISION 04 (AFFECTED PACES ONLY OPFSITE DOSE CALCULATION MANUAL

Page 1 of 80 HCSQDL PQKtt 6 IJGtK QMBAHY SZ IIX'UNT QRHISXtE CKtMCBG PHO(HXhE M), 0-200 HhVISIOM 4 TLtls:

QEfsLte Dose CaIculatha Hanual (QXM) equi <o<y~ ~y Review aad Bavbsadby PeaQity Bmtcar Gmup Appal by Ci M, RevLdcn 4 hmdewafby P RG //-

kypaned by

Page 6 of 80 ST ~ LUG IE PLANT

~

CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OEPSITE DOSE CALCULATION MANUAL (ODCM)

GD3SShRY OP ~KMY USED 'IRONS (continued)

- Far tbe.QXM either the bone, li~, thyzaLd, ktdney, 3nng, (K~, or the T.

Body. Total Body is emshiezed aa organ far ease of wzLtfng the aethodoiogy in tbe QDQC.

- QL - dotted - Denotes a release tate in uCL/sec for nnclfch (i).

QL

- Ihnaces uX of mclide (i) zeleased over a specified aha interval.

Radicdalms - IodLne-131 and Xodfne I-133 far gMeous zelesse parleys Receptor - Tbe individual receiving tb exposuze in a gLven locatLcn or wbo ingests food products from an auiael for exaaple. A zeceptar can zeceLve dose fzaa ace cc coze pat?apso Release Source(s) - A subsystem, taak, ar vent where zadLcactLve aatezial can be mlauwd independently of other zadLosctive zalea pafuts.

SZS

- mLcro CurLm. 1 uCL ~ 1M CuxLes. 'Ihe uCL is the standard unit of xaKoactivLty for all dose calculations in the QXM.

- A ling term QrL o~ Q. It descrLbes the pbysLcal dLspezsica dmaclezistics of a semL~Xnite cloud of, noMe gases m the cloud tzavezses dcaeaege from the zelease paLnt. Since Noble Gases are inert, they- do not tend to settle out cn tbe grid. (See Appendix F),

(~D - A 3cng term Depleted QrL over Q. Itcloud describes the dispersLcn cbazacteristics of a semL~d.te of ve inches and tend to settIe out (faUout af tbe cloud) ca tbe gmund, the (gQ)D zepzesents what physical'eadns of the cloud and its dispersicn qualities .

at a gLven 3ocatLax doemmge fzom tbe zelease patnt. (See appencUx P) ~

r v <<q ), <<~ << ~<<, << ~<<.~, ),<<'<<c:<<P<<<<,-g:~ <<<<q<<<<<<'<<)l qr)

I ic'i << 'l...,<<v 9". ~;I',"v" I'

Page 9 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ . C 200b REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODOM) h 1.2 (ccetfnued)

- I <<

PP<< t),) I L-1. Rc dfssolved or eotz dned noble gms tbe MPC value is 2 X 10 uCL/mI for the. aaa of all gasesa evatuaticn or for purposes of sfayiiffIing the caIaxhaim by a cuzulative actLvity evaluaticn. If the a~luffed aethod is used, the vatue of 3 X 10 uCL/ml (unfdentiffed MPC vatue) should be substituted far QfEIC)i and the cuaulative cco)raarsrfar sbcaIcI bs scbsrf for cf. ss barf )sp cbs dUarsc ccacscrrsdca P).

)h pmvides a PIP) re@dred to dexnstrata coapHLance with the lfX:ER20 MEC liad.t.

stef~tep pmcedoxe fcr detezmfnfng the MPC freya.

~ falhxdng section Calculaxfon Pmcess for Solids '.2.1 1.2 1.1 Obtafu fmm the ~Qaat pmceduxes, the release rata mQua (R) in gpm for th. ze1ease scara 1.2.1.2 (btafn fmm the Replant pmcehxes, the ditutfcn rate (D) in gxu. No credit is taken for any ~Khatfcn beyond tha dfschaega canal Qav.

(~)Ifis 1.2 1D Obtafu (Ci), tha undUuted assay value of muLida (i), in uCL/nil.

tbe siaplified method is used, the cuaulative ccacentxatica useda 1.2 1.4

~/ml

<<<<.* of

'Ihe value -3

~PPPI X 1'CL/ml sbouId be used.

<<)

for the ah~Xied 1DEQlode 1.2.1 5 Divfd Ciby Ofpc)i ~~ ~ ~~ th 1.2 1.6 If the 'sQ~Xfed author 4 used, pmceed to the next step. If repeat steps 1.2.1.3 throu@ lW1.5 for each mclide reported fn the assayb for 83 from pzeviaa arnzb coaposita, and foe SMB/90 and Fe55

. fmm pzwdlaus quarter coapad.te.

'd 1217 each Ci/gPC) quotient from step 1.2.1.5 and salva foe P.

n.

R.

FL ~ D / QQ?C)f.

~fe PL ~ a unit-lees value of FT axQd

~:

be < or >1..The puxpose of the catuculation is to determine the initial value of PL fs for a gLven set of release lf condfticnsa the actual release caxKtbxm for dfhabm dnrfng the actual release, P is called tha fzactfcn af 1CPJ20 MPC

~

PL is<<>1; admfnfstrativa-steps aze taken to ensuze that enaue that PL is <1 because it, should macr be. to be >1 P

, 'It

~ .'.."..: ..;..". ~ .'..:"":.-. -- "----" ....'":., -'"-- ";-'" -

p ph

't p

h C'

-'--'-'--- - """-" '"- ~

Page 10 of 80 ST ~ LUCIE PLANT CHEHISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCH) 1.2 (coatinued) 1D.2 CalaQatian Pzocess for Gases in UquH 1.24,1 Sum the ~/m1 of each aobte Sas activity zepozted in the zelease, 1.2Q.2 the vatues of R aod D faxa 1.2.1 abom sha11 be used in the aQculaChxa belaw-PS' ~ (sum of 1.2.1 1) uCi/ml XR 1.2.2D p shell hs less chen 2 2 10 uCi/el fcr ths sfte for sll mlesses ln progress. pech misuse pcdnt wi21 hs aieirdstrstlucly cmtmlled.

0msult frepleut procechms fcr fnstructlms for Radioactive Efftueat lhoitozs e

liquid efQuents.'Tecbaical SpecLficatizn 3.11,1.1), ThLs sectizn pzesents the Gmss cpa vs. total lhpdd activity ames aze svaQahtie for Lfqufd EfQueot HcaLtors based cn a coapxd.te of zeal zelease data. A dixect corzelatLcn bee+en Smss cpm and estimited 'Ihe 1978 iiqxM zeIease data faxa semi~mal zeports sam used to detezmfne j

ccostaot dihxthn flaw of '121,000 gpn fzoaL 1 cizco mter puanp, Thfs ditnted activLty

~ divLded by tha halide's respective 10CN20 HPC vatue (Table If-1) to obtatn the Hi cahmn m the tabte that foltuws-19 UM)ILUKD Q2

~/ml (ao unLts)

I I-131 4.43 EH 1.22 E-3 I 132 2 23 Ei-7 2.3) E-7 I

I I 133

'-U5>> 1.31' 3 17'62E5 I 271' 24 1.72 E-7 4.74 E-8 l Ct 51 2.51 Ei-5 1.04 E-7

) ~

Co-57 5m E-6 1'll EH 3.69 E-7 4.66 E-7 9 17 7 62 E-ll

&9 Co-58 1.51 &4 1'M &5 I

l Pe 59 2.92 Fr+ '26 8-7

Page 17 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITE DOSE CALCULATION MANUAL (ODCM)

'.1 Gaseous EffLuent Model As tfcns purposes cnly). The St. QmLe Haut is located cn an islaod suxxcnoded m tm sides by tbe Atlautic Ocean and the Todfsn River, an estuazy af the Atlantic Ocean PxLvate pzaperty edgafns che plant site in the mrth sod south dixectfjcns. A mtearalogfcal tower is located mzth of the plsat max'he site pmpexty, line Mme axe 16 sectors, fcr dose caiculaticn puxpases, divided into 2LS each. Tbe nat tower is c Qibrated such that a zem degree bearfng cafzx~ with 25K RRQL A beaxfag of zem chgxees dissects the mrzh sector such that bearfngs af 348.79 aod 11.& define the bandaxfes af tbe north sector. Ihe mszest dfstaoce to prLvate pmpezty occuzs in the ocrth sectar at appzaxhstely 0.97 mLles. Far esse af calculsticn, thfs 0.97 mUe zsdfus is assuaged in sl1 dizectiaas, altkmugx the zeal GuestrLcted Axes Bandaxy is deffned in Fiyae 5.1 of the SIS. Doses calcuLated over w3ter azeas do mt apply to the AS IlS's or the saaual zepozt sad may be listed as O.W, (aver water) in lieu of pezfarmfug calculstfoas. The 0.97 mUe range in the kR sector is O.W., but it was chosen as tbe worst sector far ccnservatLve dose calmlatfms usfng. the historLcal MEZ data Hfstacical MEZ Data -MEZ data, betsaea Septenher 1, 1976 sod August 31, 1978, fmm the St. tucfe MEZ Tcaar ~ analyzed by Ihmes 6 Moore of Wasidngtcn,'A. 'Ibe metfxxhlogy used by Umas Ec Moace was amdstenr with Mthads aug~ted by'eyQstazy Qdde 1.111, Site sad aze tucaxpacated into the hfstacical MEZ tables (TahLes M5, M6, aad M7) in Appeaffx, A af this msaual.

data far this locale.

It wm detexmfoed that these ~ yeazs aze xepxeaacatLve Dose CainQaticns - Bee calculsticns far Techzbml Specfficatfcn dose limLts aze mxaelly cahcubCed using historical MEZ data. sod zeceptar locaebn(s) which yield calculated doses cn lower than the zeal locm~(s) experfeocfng tbe cnst expoeuze.

Accual MEZ data factaxs sxe caIaab~ sod used fn dose calculatfcns for tbe Semf.-

aMlal zepartso LLve MEZ data sod benz"'~mr, dose calaQatiaas axe beycnd the scope af thfs asuual.

Hfstoxfcal tufozmebn aod ccnsexvatfve zeceptar locaeltaas, etc, aze calg tm6 for ease af SXS IlD dose lfmLt caLculaticns. Dose calculaticns far HS dose lfmLts cay be pexfozuacL usfng actual MEZ data, zeal receptor locates, aod sector wfnd frequency dfstxfbuticn if. desfzed. Any'ose calculates pexfccmed with actual data sbatQd nota the sauce af the data in the sanual report Actual MEZ data zeductfon should be pexfaemd in accordsaa with Regulatory Qdde 1.111, Revision 1 aod sbauld incorporate uoes the lang term gxauud zelssse model for all gaseous effhuats. Only those fn.say dose ca]aQsticns, HaKafcxfLues axe de!Rani as Iadfn. 131 aod I-133 for quartered'eca calaQs~ far esse of perfcrmfng calculaticas, but theLr have to be included in the SXS IlD zequfxeaents

~

applfcatfcn to S.TA US's Other mclMes af Xodfue nay be inclxxfed in dose ccntrfbutfon does znt Land Census iufaxmatfon wfll apply to tbe calecxtar year faLLowfng the year that the census was taxen in to avoid splittfng

/RA

Page 18 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM) the Total and Skfn Dose Bares far Noble Gas Releases dc@ Estahlis for Effluent HctMars oobla geese la altboeae talasees to C500 ~yt total body eod C3XO stat/yt-sldn. Technical SpecUKcaeica 3BD.10 xedydzes. that the gaseous zadioactim eQDuera these dose rate limf,ts are mt exceahd Tbe tempts of the samp3~ and analysLs program of Technical Specification Table. 4.11-2 axe used to deaanstrate cocpliance with tbese UmLcs.

rates to, the tatal body and sldn from noble gases in atxbome releases. The alarm/trip apply ro all airborne releases cn the site but all releases aey be treated as if discharged from a shee relearn paine. Only those noble gases appearing in Tahle G-2 ~

will be considered. The cahmlaticn mthods are based ca Secellms 5.1 and 5.2 of HEE&0133, %maiar 1978. '1he equations are:

Par ZEAL MX Ebse Bate n

(QQ)

For ZEAL RUN Dose Rate:

n

[Q+ l,l Mi] (gQ)

Qatar

~ tatal body dose rate from noble gases in airborne releases (mrem/yr) zs

~ atdn dose rare from noble gases in airborne releases (mrem/yr)

~ a tmtrlmatiaL1 syahol.to sigrtfy the operaticns to the right of Fi the synhal aze to be performed far each nome gas nuclide. 0.)

through (n), and the individml nuc1ide doses are sumaed to arrLm at the total dose rate fox'he release source

~ the total body dose factor due to ymua eafs far each noble gas na:lfde zepozted,in the rabat sands. /uCL~)

~ the sldn dose factor doe to beta emtsairns far each gas nuclide (i) zepoxted in the assay af, the zeMee source ( /~~)

~ the air dose factor due to gamta emfssfrns for each mMe gas noel~

(i) xeported in the assay of the release source. 'Qm crastant 1.1 anmrts arad to arem since the usa of Q aze in Q~ /uX~)

~ fcr ground Ill, the hi~t calculated snraal iong term tdstaric ezctusiaa azea boundary (sec/m3)

~ The release rate of nome gas nuclide (i) in uCl/sec fxcm the release scarce-of interest

Page 19 ox 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, ILEVISION 4 OFFSITE DOSE CALCULATION 11ANUAL (ODCM) 2.2 (continued) 2.2.1 Sh~ied Total Body Ihse Bate Calculaticn Para an evatuaticn of past releases, an effective total. body dose factor can be dezived; Ttds dose factor is in effece a wELghted aerage total body

(~f) dose factor, i.e., ~@ted by the radiamclide distzLbuticn typical of past opexaticn. (Befer to Appendix C for a detailed eaplanaticn and evatuatinn of me value of ~~ bas been derLved fmm ehe radioactive noble gas far tbe years l978, 1979, and. 1980. Tbe value is:

6.8 X 10 maoism uX~

'Ihis value any be used in ccnjunction with the total noble gas zelease zate

( QL) to verify that the instaneaaxus dose rate is wittdn the allow QQa limf.ts. To allow for any unexpected variability in the xadicauclide distcituticn, a conservatism factor of 0.8 is intmduced into the calculation.

'lhe sfaqlified equaeica is:

08 '/

To further siaplify the detezadx~tion, the tdstoeLcal annual average aateorologLcaL X/Q of 1.6 X 10 sec/aP (Fmm Table M-1) may be substituted into the equacLon. Also, the dose limf.t of 500 aran/yr any be substituted for Matcing these substitutfcns yields a singLe cuaulative (or gmss) noble gas aQease rate limit. 'Qds value is:

Noble gas zelease rate limLt ~ 3.5 X 105, uX/sec

~

As ~ w the noble gas xelease rates do not exceed this value (3D-X 105 dZ/sec), to additicnal,dose. Zaee callxtlaeicns axe laeded to verify coapliacxe with TechnLcal SpeeUXcaticn 3.11.2.1.

2.2.2 Seepoint Detexmfnaticn To coaply with Tech- Spec. 3BD;10, the alarm/trip setpoints are established to ensuxe that the noble gas xerxes do not exaeed the value of 6.5 X 105 tiX/sec, wtd.ch cozzespmds to a total body dose xate of 500 mxem/yr. The aethod that-foDcaa is a st~~tep pmceduxe for establistdng the setfxdnts. To allow for aultiple smzces of releases xxcaa different or manzn zelease paints, the allcaebla operatic setpcdnes will be conemUed admlhdstratively by allocating a percentage of the, total a11owahle release to each of the xeleme scuxces. /BA 20.2.1 Detenafae (V) the mncLauaf voluaa'release'race potential fmm the in-plane pmceduxes far the zelease sauce under cnnsidexaeicn. The unLts of (V) aze ft3/mfn in uCL/cc that would pmduce the Y dose rate IlD A~3.5X 10 sea,

~X adn

~(U) ft X ft 2.'1 R 1(Ice X 60sec oda uCL/cc.

Page 20 o f 80 ST ~ LUCIE PLANT CHEI<ISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITE 'DOSE CALCULATION MANUAL (ODCIi) 2.2 (coaefmed) 2.2.2 (cannel) 2a2.2.3 Refer to the uCK/cc va. cpa curve for tbe Re1ease Source's Gaseous 2.2.2.4 C is the IOOX setpzdnt, mmufng that there are m other relapse sources ca tbe site 2.2.2.5'btain the cunant X aUocated to tMs zeIease sauce fzaa the gaseous waste aanagxant logs 2.? 2c6 The Operating seg)oint SP SP ~ (C) cpa X X allotted

'Ihe total body dose is uuze Iia~ng thaa the cahxdated atdn chse.

(Refer to Appendix C for a detaQed evatuatha.) 2azefore, the akfn (hse rate calcuI.~> aze not repxLzed if caI(morat~ is used (i.e, use of Hmits)a

~ tbe shyLtQed dose rate to datenaba xelaase rate 2a uCfjsec zeIeases of noble gases ~

caIculati(m pzocess of the foUpwing Section (2.2a3) is to be if actual tbe above Lind.t of 3.5 X 10 te cuapHaxe with the dose rate HuLts of TechCkal 2.2B 'Ibtal ~ aod Sdn Nuclide SpeelIftc Ihse Rate CaIcuIatiaas 2m folIadng autltine provides a a~~tap exphmatioa of hear the total body

~

with Tech Spec,3 11 2 1 %is a)ethod is aalu used the value of 3D X IO ~sec 2.2.3.1 .2ht (z(@ salus sec/a mst if the actual zeIeases ts ths tuse )tsar(ca sector e

ac tla etcluslsc ataa (Sea Xsbla tt.l for cetus aoe( sector.)

2.2BD Eater tbe mIaase zate in ft /min of the sauce aod camas it toz ( )tr X 2.33l7 cc X a(u aim N ssc

~ CC/sec ootLKB x81pA88. rate 2.2 3,3 Solve for Q far nuclide (i) by obtahdag the uC4I'cc assay vah)(e of the release scarce and aultiplyhg it by the product of 2.2D.2 above

'(a~ foal) uCt/sec for nucHde (i)

F 3

r s~

VQ ~

s

Page 22 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFS ITE DOSE CALCULATION MANUAL (ODCH) the Radfaiodixe & P~icLQate Uose IIate to Discus(d(tt - Te(34 Spec. 3.11.2.1 Idtdts d(s dcee tsts ft(ee I-l31, I-l33, ttdtdc(e ecd any'rgm The faUadng ca1culaticn aethod is pmvlded for derezmLning the dose rate Emm ~lalodines (see 2.1) aad particulates and is based aa Sectica 5.2.1 aad 5D.1.1 tbmu@ 5.2.1.3 in NU~L33, Nosed'978. The Infant is tbe caatmlling ay. group in the izkelation, ground pilme, and mar/yet mLlk pat&aye, whLch are the aaly (e((

(D/Q mlles aze based m bistorLcal MEZ data prt/or to iuplaaanting Appendix I. Cbly those mclides that appear cn their respects table wQL be aeELdered. 1be equatiaas ares H-3):

~ISKPI Q ~3 3D%

For Gmuad Plane:

Pi (D/4 Q i

For Grass-~/Goat~ '

'(

Q 8/Q) DI For TrLttua< Masses (IabaIatfca & Gae~/Goat~):

DtSS -  %-3,<3/~D&3

, For Total Dose Race fmm I & 8P and E-3 To An Infant Te E

~RzmLLly shou& be PiT, but'RiT mIues are the sana, thus use RIT tabIes in AppeadLx A.

..C-:,.e,, S ((SC SCCCCS eCSee . e,;, s...,~ee ...: t! '; PCC',

Page 24 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISIVN 4 OFFSITE DOSE CALCULATION MANUAL (ODCH) 2.3 (caarltnued) 28.1 The Zuhalaticn Dose Rate Method Note 'Ihe 8-3 dose is calculated as per 2.3.4

~

2.3.1.1 The ceatral1tug location is asmnad to be an Infant located in the sector at the mUe raage 'Ihe (Xt'(3D for thLt location is sec/at . ThIs balue is coaam to aU.

t . )

2.3.1& Eater the zelatse race in ft /tttfn of the release s{xtrce sad caamtt to cc/sec fe X 2JB17 X 10 cc X efc cc/wc tafn fo eec 2Q.ID Sclce fce ((1 fec ceclids {f.) by cbeeccfcg ebc c{x/cc swaY eabee cf Ibc it relearn source activity- aad ajltiplying by the pmduct of 2.3.1.2 abo%8c (nLx.'lide [iI ) uCi. X (Mue 2.5.1.2) cc

~/sec far saclide (i) 2B.1.4 (btxfa the Q mtue fmm TaMe &5 for the organ T.

2B.1D Salm for ~

212 {Xtgql wwec X ea2 X CL eec tate{a 'Ihe Ihse Rate to organ T fmtaauclide (i) 2&.1A Repeat steps 2B.1D though 2D 1D ffx each mclide Q.) reported in the assay af the aQease scarce is 'athway for all zaclides IR1 except E-3. Ihis dose

+ ~rate+ shall +DR be added to the other pathways as per 2BD Toeal Orle, Ihse.

'ote: Steps 2D.1D thmugh 2D.1.7 need to be coapleted for each argytn T of the IaEau:

Page 25 of 80 ST LUCIE PLANT CHEHISTRY OPERATING"PROCEDURE NO ~ C-200, REVISION 4 OFFSITE DOSE CALCULATION MANUAL (ODCI'I) 2.3 (continued) 2B.2 lhe Note: 'I!zithm dose via the gmuad plane is zem.

2A 2 1 The aatmLLfag location is assuaed to be m Iafaat located in tbe eeccor et tba 'Ue tacee. '1ba (D/Q) for tbfa location is ~

1/m . This value is ammn to all auclides.

(See Table 5-2 for sector, zany ad vatue )

2.3.2Z Barer the zelesse zate in ft /mfn of the zelease sauce aad mavezt to cc/sec fr X 2.8317 10 cc X ttbt cc/aec mal f e0 aec 20.2e3 Salve for Q for auclide (i) by obtaizdug the uCi/cc assay value fmm the xelnlse source it activity aad multiplying by the pmduct of 2DD.2 abovee (auclide i] ) uCi X (Value 2B.2.2) cc uCi/sec for auc1fde (i) 2DDA %tain the Pi value fmm'MQe G-3 2e3DD Salve for DRi

~ PiT (7D4

+~ are2M-sec X 1 X dX le

'Ihe ejr: liF Ibse Bate to organ T fmm 8'rea yr nuclide (i) 2DD.6 Repeat steps 2DDD thmuah 2BDD for each malice (i) reported in the assay of the zelease sauce, 2QM7 2a Zastaaemeous Dose Rate to the Iafaat's Total body fmm the Gmund Eaae Pathway is'11 + 012 + + IE for al1 aocUcIes, This dose, zati shall be added to the other path+ye 4Q per 2e3e5e Gzass~/Goat~ Ihse Rate Method:

Note: E-3 dose is calcul.ued m per 28.4, 2DB 1 The canca~ag aaizjal ms established as a mlles. 'Ihe (~D for this location is Tl 1/m 2,'his value is caaxxa to all auclides.

Page 26 of 80 e

ST ~ . LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 4 OPFSITE DOSE CALCULATION MANUAL (ODCH) 2D (coatltroed) 28c3 (aatinued) 2.3BD Eater the ~pated reIease zate in ft3/min of the zelease sauce and aavezr to cc/sec.

ft X 2.8317 X 10 cc X aan cc/sec mLn lP 2.3RD false far Q far neclfde (2) bf ahhdtdng the a0Van eseep aches or the zelease source activity and anltiplying it by the pmduct of 2DD.2 (nuc1Me [iJ as ) uCL X (value 2.3Dc2) cc

~/sec for nuclide (i)

~,

If

~/Imt, ~).

2.3D.4 Obtain the g valne for fzzmi Table CHi(7) (wtr49mver the limLted analysis appmsch is being used, is the ccatnQling limit the cahularbn to the infant thyroid.

Salva for ~

DOLT ~RiT (D/Q) Q ~ mzearm -sec X 1 X uCi aF sec rR ~ mzem/yr the Ibse Hate- to organ T fmai nuclide (i) 2.3B.6 Repeat steps 2DBB thnagh 2BDS for each mclide (i) zeparted in tbe assay af the ze3aase.scarce Only the zadiatadine> ne'ed to be includefi if the limLted analysLs appmech is befng used 2DD 7

~ pathery fftfn~

is:

-' IR1 + 012 + + Bl far ell nnlfdes.2ds d.ase tete shell he ended to tht other pethsefs es. -

per 2QD Total Organ Dose Nots! Steps 2BDD tha~i 244o7 need to be aoapleted for each argsn of the Infant. Linet the caIaQaticn to tbe infaat thyraLd if the, limited analysis appmsch is being used.

Page 27 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPFSITE DOSE CALCULATION MANUAL (ODCM) 2 3 (aaehaamk) 2D.4 lhe 8-3 Ibse Bate Method:

Tnbalatian (O'Qn

- ~

2.3.4.1 'Ihe controlling locations sad their at sec/aP

(@

range (See Table values in the for each pathway are:

sector ~

5-2 for range, sector and value)

(hmuk Plane - Dace nat apply to 8-3 Gcas~/(hat~- located fn the sector the aalxsdaa ana in tba lo cavan (VeD- sec/aP. (Paxa Table &6 st the rany. m4

.)

2D.4.2 Enter tbe sntiatpated release rate ia aavert it to cc/sec, ft /i'f the release source and 2~3i4i3 .Mie for ~3 for Tr~q release sou:ce, and cultIplylng bF aug it thethe by nQJcc assay value Qf pmduct of 2D.4.2 above.

~(K-3 ~ X (2 3.4.2 @atua) cc 3

mr ~sec activity Qgesse ca M.4 4 rbtaux tbe Tritium dose factor (R ) for. Infant organ T fram.

PAm Xabalatica

)Gras~/Gast ~ Q &6(7)

(ma~) mung am (@'q)D for ma~

. m.4.5 Solve 2

for ~3 3+4ol'nd RR 3 (InI~lstice) ~ ~~4 4~

aaa

-~3 (WeD q 3 h

'r@EL T 2 3i4'6 Solve fof ~3 (Grass-Gcass-

~3 (G -

~ ~) f~)

gama X3.4 1.snd ZZ.4.'4 using tb(~q) 'or Pt m~ ~ - W~

~ ~D4-3

Page 28 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM) 2 3 (ccatiaad)

? 3.4 (cxatinued) 2 3.4.7 Repast steps 2D.4,4 thzm@ 2.3.4.6 far each interest

~ organ T af 2.3.4A 2m indLvidual orgen dose xates fxam K-3 shal1 be added to the other orym paths@ cbse rates as per 2 3.5 2.3.5 Release Souxce(s) 2.3.5,1 'Ihe fatLIawing table dauxibes aQ. the pathways that aust be amnad to arrLve at the total dose zate to m organ T:

Tnbalaticn (I680P)  ? 3.1.7

)

Gz-Ground PL.

~ (XMP),

(ZaaCe)

(T. anl ) 2.3.2 7 2 3.3.7 Gi. ~

Tzdmlat1ca (H-3)

(B-3)

(aua of above) 2 3.4.5 2 3.4.6 2.3.5.2 Repeat the above suction-far each Infaot organ T~

2.3.5.3 'Ihe ~ above shall be added to all other zelease sources ca tbe site that wQ1 be in pxogzess at any instant. Refer to ablaut pzocedozes axl Iogp to detezmfne tbe Total IBT to each ozgan /84 tbe Gama Afr Ibse for RaKoactive Noble Gss ~se Source(s)

IKscussian - Tech Spec, 3.11.2 2 limLts the atr dose due to aoble gases in gaseous efftuents for gama,zactbrtfan to <5 mxsds for the quarter aalu zo '(10 mxads in any calendar year~ The faUc~g eQmQacion mthod is pand.ded for detexmfrzLng the able gas.gmn8, air @me aud is based on section 5B.l of KRE&OI33, Ibueuher 1978.

dose calculatica is id~dent of'any age gzoup 'be equ~icn nay be used for SXS dose calculatltce, the. dose cahxiLaeLcn for the auuuaL report or for pzojecting dose, that the appzoprLste vatue of ezplaaatian that fhUans ~ (~ is used as outlixed in the detaQed equal~ for yeas air dose is:

'xovlded 3 17, X'10 ML.(X/Q) +,

~ gmma air dose in mzad fzcm-zadiaactive aoble gases.

~ A xath.aatical syahol to idgpdfy the apexaticns to the af the symbol.axe to be pexfoaxxk for each,nuclide (1) thzo~

~ side (n),. a@i:sumed'to ardve at- the totaL dose, from all auclides zepoxted duxing, the, interval ; No unLts apply K

t

'.,g>>~>>>N~r,"'~R>jg>> 'A>> g,'i>>p 0, +p>>, i$ir>> ', ~ " >>q'>>>>>>; ~, ~, g g4P~>g:~4, 7~~iPgppkgfi '>>, 3>>.">>, ';"4'>>..ki ' fp<>>wgsw;>c>>>>, t,',',.",.", ...t . >R'">>. i" ~

v Page 32 of 80

'ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION "4 OFFSITE DOSE CALCULATION MANUAL (ODCM) v 2 5 (anil) 2.5.5 Perform steps 2.5.2 tough 2.5.4 for each nuclide (i) zeported during the th)a izzterval in the zelease source 2.5.6 2a total beta each auc1Lide M-D1+D2 air (i) to dose obtain ~

for the pathway Axe

+R is

-~

detezmined hy suamizzg the Di dose of 2 5.7'efer to ~)lant pmceduxes for maparfng the calcLzlated dose to any applicable 2.6 DLscussica - Technical Specification 3.11.2.3 1imits the dose to tbe total body or any pear 2m

%BECr0133, R)md)er 1978.

calculzztion ~

organ zesultiag fmm the zelease of I-131, I-133, triti)(xn, and particulates with half-lims >8 days to <7.5 meaa duxix(g any calendar quarter aud <15 aran during any calendar foll(~g is pmvLded for detezmfxdng the crLtical organ dose due to zel(maes of zadioiodines aod particulates and is based ca Sectica 5.3.1 of

~ equaticn cziz be used for any age gmup pmvLded that the appmprLate dose factors are used aud the total dose zeflscts.only these pathways that aze applicable to the age gmupe 2m (~(Q sydxk xepxesents a lXHK~@g) u)drh ls dlffereur. frau ths )khls Gas (X)0) ln tLt (WQ) takes. hvro sccuunr. the lass of 7&1&Xv sud 8-3 fma tbs Blurs ev the seal~ffntte crave)s aver a g(van distance. 2be (W0) dfspendon faces tepressats rha rare of fallout fma tba e)oud that affects a squaze aeter of gmuod at various distaees fzocL the si.te. 2m IhSP and H-3 m~zs zefer to I-131, I-133 ParticuIates hertng half~ms 08 days, and Td.tium.. For ease of caIculatLomz, dose fzom other Iodine mclides may be izzctuded (sea 2.1). Tththnicalculatlcas are'alsays baserL'cn (Xv0) lbe ffrst seep ls co ealcu1sm ths 7&&LB sud 0-3 due for eadt pac)rvsy chn co a gtvru age gmup.

)be cecal dree co ae vegan cnt then ba deters&nod by sundng cba pschvays that apply to the zeceptor in the sector ~ equations are:

For tuhalaticn Patlaay (exnltuding H-3):,

D~T /

3.17 X 10 Bl (Ã7@0))L For. Gm(md PLaoa or Gee~/Gast~

07&gcpT'

. 3.'l7 X gf (~D I

i, For each patsey abc'exctudix)g,Gmund PLane) For TtLtizxa:

3.17 X 10 Bg.gf (Z)0))t)L

/'v For Total D()se fxaa PartLculate Gaseous effluent to organ T of a specified age gzoup',

f ZggP+~3l'-

~ v ~ v ~ ~ v v

Page 34 of 80 ST ~ LUCIE PLANT CHEMISTRY OPEHATIhlG PROCEDURE NO ~ C-200 ~ REVISION 4 OFPSITE DOSE CALCULATION MANUAL (ODCM) 2.6 (coachaxxl)

'Ihe dose determfned by Secticn 2.6.3 should be divided by a caaservstism factor af 0.8 'Ignis added axeervatism pmvLdes ~suzaace that tbe chse deteradzmd by this. ~

1huited analysis appzoach will be < the dose that would be detezmLaed by evaluating aU.

calculaticzzs for other zadioactive pazticulste astter aud other pathwcrys need aot be pexfozmd Qaly the calculaticas of SectLon 2.6D for the zaRlahdines aza zequized to deazostzate caapULaoce with the Tech. Spec dose limit. ucwever, far. tbe dose assessuent included in SemL&amal Reports, doses wLll.he eeQnated for the infaat age gmu~ aud.all orgBas vLa all d~pated pathways fmm radfoiodtnes aod particulates, aaaaced-in the gaseous effInenzs according to the sapling aad analyses zc pdzed in Tech Spec Table 4.11-2. The foUawing steps provide a deteUed expIaaaticn of how the dose is caiaxIated for the gLven pathaysz 2.6,1 Tbe Ixdalation Dose Method:

Note: Ihe 8-3 dose sbouId be aQculated as per 2.6.4.

2.6 1 1 Detezmtne the applicable (@gD fmm Table H-2 for'ta Iocaticn where the receptor is located. This vaIne is comun to each aucLLde (i) 2.6.1 2 Detezadne the Ri factor of auclide (i) for the organ T aad age gmup fmm Tabie G-5.

2.6.1D obtain zhe mL~3uzfes (Q) of mclide 0.) fmm the zadiosctLve gas during the the inter'.

tl 2.6.1A Salve for Dc Di ~ 3 lf X 10 K(Xlg

. mrea fmm (i)'.6.1.5 Perform steps 2.6.1.2 Uucagn 2.6.1.4 for each nuclide (i) zeported durfng the tine M~ for each organ 2.6.1.6 Ihe tubalsticn dose to organ T of the specified by. anndng tbe Di Dose of each nuclide (i)

~ gmup is chtexmhecL Dj +D2+ +D zrem

)

Refer'to 2.6D to'detezmfne the total chse to a.gsn T fmm racBaiadines

& 89. ParcLculstss

? 6D 'Iha Gmuad Pleas Dose Metbodz Note': Tritium chse via the gmuod plane is zem. 'Jhe Total Body is zhe aaly or'gsn cnasLdezed for the Gmuad Plane pathway chse 2.6i? 1 Detezadne tbe applicable (DDQ fmm Table H-2 foz'ae location where the zeceptor is, Iocated This (D/Q) vatne is coamn to each nuclide (i) 2A.2.2. Detaaafne the M. factor of auclide (i) for the total body fmm Tahie G-4, 2a gmuad plane pachway dose is the saae for al1 age gmups.

J ' / I ~ E / ~

• Page 35 of 80 ST ~ LUG IE PLANT CHEMI STRY OPERATING PROCEDURE NO ~ C ?OU 3 8 EVISION 4 OFF SITE DOSE CALCULATION MANUAL (ODCM) 2.6 (coqdmeI) 2.6e2 (ccatinue(0 e

2.6DB (h'tahe th'e mLcrcKhrtes (Q) of nuclide (i) fram the zaKoactim gas 2.6D.4 Salve for Di 3.17 X 10 ttl (0/0101 D a mzam far axJide (i) 2 6DS Perform steps 2.6DD thzm@ 2.6Q.4 far each nuclide (i) reported durtng the the interval.

2 6.2.6 'lha Gram@ Hans dose to the total body is chaexa5aed by summLng zbe Di Dose of each nuclixh (i)

~ ~ Dl + D2+ +9 mcem er to step 2.6.5 to calculate total dose to the Total Bodya 2e6e3 'Ihe Gzas~/G(mt~ Dose Method:

Note: TrLtium dose is calcuIated as par 2.6e4 2.6e3 1 A mr, ar a Imt, wQl be the axLtzalling anhal; (i ee, dose wQ3. not be tbe aia of each acdual), as tbe bumscL zeceptar is assumed to drb6c mUk fzam caly the anat zestrfctive acdnal, Refer to Table M3 to determLne whfch anfnal is ccatraIling based ca its (D7@,

? 6Q.2 Date'ne.the dose factor Ri for nuc3Lide. (i), far arsscL T, tram 2.6DD.l -Pzom Table &6 far a aw, or, 2e6DDA Paxa TabIe G-7 far. a'SPat K the Iimlted analysis approach is being used, IimLt tha calcul'~

to the infant thy~..

2 6DD ObtaizL the mLcarQsrLes (Q) of nuclide (i) fzom the zadioactive gss the the interval.

2.6BA Salve for DL 3.11 X 10 31(W(301 mcem from nucIide (i) 2.6BD PsrSaaa steps 2.6.3D tbzcugx 2.6D.4 kr each a~~ (i) reported dLztLng the time interval (hly the zaKuta@nes need to be inctuded if the IimLted analysis 'approach is used e

2.6B.6

~

determined by au(naing the IK dose (or ~<) ~ D +++

of each

+Q ~

nuclide(i).

lhe etee te ecch ctNe e(mle he celcclecai la the etta taetat elth steps 2.6e3a2 through 2e6e3e6 mzam Refer to step 2.6.5 to determine the total dose to organ T fzau radfohxHn s &80 Part~lates. If tne limLted analysis approach is Mng used the infant thyr(ztd dose vfa tba detaxndaeda Sectiaa 2.6.5 an=be oaktted

~ ~

Page 36 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCH) 2.6 (caatauad) 2.6.4 lhe Gaseous Tzitiam Dose (Each ) Method:

2.6.4,1 2m antzolLtng IoattLcna for the pathay(s) has already been-detezmtned by: InhQaticn - as per 2 6.1.1 Gmund Hans - not applicable for B-3 Gzaa~/Goat~ - as per 2.6.3il 2.6.4.2 Tciehxa hum calcakatbxe use the depleted (7g)D instead of (WQ Table H-2 describes there the (@'(QD value should be obtained fzom 2.6.4.3 Detennfne-the Pazlaey Trtttum dose factor inzezest fzcm tbe Table spectiKed bhaga

(~3) for tha oem 'C of Infaat &5 &6 G-7 2.6.4.4 (btatn the mt~lurtes ((Q of 'I~a- fzom the zadioactive'gas meta aana~aent loge (for pzo~ doses the mtcaHhefas of nuclide(i)

( )

the time interval. The dose en be aQculazed fzom a sinsle zelease smrce, but the total dose for S.TA. Limits or quazterly zeports shall be fzaa ell Saseew zelease saucesi 2.6.4.5 'Solve for +3

~ 3.17 X 10+

Dtt 3 Btt 3(@Q) mzam fzom in the specked pathway ,

fce aqua T of the spectral a0a gzoup 2.6Q the Tctal Ibse Pzom XocUxms, and 8-3 Pzom Qxmlative Gaseous tteleases Note: SXS IlO dose Ltmtts for X&NP shall axu~r dose fraa all zekaem st+ress fzom St tucte Uakt L 2.6.5.1 The faUrxdng pathways. shall be sucnad to azzive at the total dose to ozSan T fzom a. aQeese aarce,. or if. ~ticahle to SS, fzom a1l zeleme saxzces-SZEP REF Inhalaticn (Z&SP) 261.6

~ ~

)

'Gzass- ~

Gzont Haec (XQKP).

(L&8P)

(T. Body M. ) 2.6W6

?637 Gzasa- ~

Intalaticm (8-3)

Q-3)

Sum of Nave 2.6.4D 2.6 4 5

Page 40 .of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ 0~200, REVISION 4 OFPSITE DOSE CALCULATION MANUAL (ODCH) 4.0 (axainued)

4. (continued)

TAAUt 3. I Hadt.oscttve Ltquid EfQuent S~~g and Analysis TYPE VF ANALYSIS Eh'AKB ~ h.a MKQQZ QRPOSZIE GP Dn S~, S~, ~e-55 CAn 6 LS SIEt3tH NIILIPALQkkK RKXXEES (XHEBAIDR ~KLY AM) DISKLVKO GASES BURIN HEIEASKS TENEZ NEATEST:

lCMHIZ QMBSZK

~, S~, F~5 LDaPa CA. 6 LS Boric held Evaporator axxtensate is maally zecouezed to the Pthsry Mater Storage Tark for rect'~ into the reactor coolant system and mraally does not ~bute to liquid taste sfQuent tota3s.

p.h.a - pena spectrum pulse bmtgbt analysis using Littzfum Gernanixm detectors. All peaks are idaeified and quantified C.S. - Chemi.cal Separatizn GZD. - Gas Flaw Propozthaal Counting tnttUt 3Z Bantnanntan Ganesa Waaaa Saataang aa& Analysts MEMlJ lZ ANaLYSIS G, .h.a

,h a LSn Geaxua ters G,C,P ~. a..

Week1 Monthly Coaposi.ta P - GD&n G

(Partiailates)',

(PartinQates)

Qusrterly Coayosite

- Gasaas Grab Sacple CA ~

LaS

- Filter Sazple P - Qmeoal Parti.culate Filter Satple L8 CA - Separatina pahnan - QmmLcal Gama spectrum pQse beiftht a+lysis using Lithium.Geraanf.mx detectozs. All aze ideneiQed and quantified GZ.P - peaks Ces How Pzoportimal Counting

Page 41 of 80 I

ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-ZOO, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM)

'I 4.0 (conrfuueco

5. 5atch Meases A

1 Narthex of batcn releases:

2 Total time perM of batch releases:

3. Mazhaaa tiaa perM foe a batch release:

4. Average time perM for a.batch release:

5. Ldnhmm tine perM foe a batch release:

6 Average stream flow'urtng pertads of release of efflxusn: into a Qowing streen.

All 1fcpdd releases aze sumarLned in tables B. Gasecus

1. Nuaher of batch releases:

20 Total time perLod for batch releases:

30 tkacLmu tiaa perLod for a batch release.

4. Average tiua perLod for batch releases:

50 Nahum tim perM foe a batch zelease'-

All'aseous waste releases aze suanarized in tables

6. Uaplaared B~~es

. 1 Ãuahee of releases:

2 Total acrLvity releases:

B. Gaseous

1. Nucher of releases:

2 Total acrLvlty released: CurLes C See attachments. (if applicable) for:

1.

2.

A des~eLca of the event and Cause(s) im'im unplanreC release.

~ant involved

3. ActILons take to prevent a reaxnuum

4. Ccnseqoaees of. the unplanted release 7.. DescrLptbn of, dose amssaent of radiarLoa dose from radio.~ve effluenzs to the '.,

,general public due to theLr acrLvLties insLde the size aze reported ca the January semLanmal zeport.

8.

~

Offsi.te dose calculatica,annual revisions inLtiaced durtng ass reporting perLod.

See 6.14 for nquLzed mt'Kaanrs tho the SemLannual Report

Page 43 of 80 ST ~ LUC-IE PLANT

,CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM)

ST+ ?1'e 0 moor - / / ~ma'ammy,

/

FEZ 3 4: E1KllMS (EfhHPfZ ERST)

KMXMXUS ME BhKH QXLEES BELEASED~ ~nz 0 gl!SXIR t gl!RIOR ii I-131 E E E.

I-133 E E F.

F. E E E F E E E F E E E E E F E K E E E K E E'XQHD E E E E E F E

E E I E E E' E

Q-187 E E E NP-239 E .E E E E E E.

E E E E E E Qi-137 E "E E Bk-140 E E E (Z-141 E. E E F K E E E K

Page 44 of 80 ST ~ LUCIE PLANT CHEHISTRT OPERATING PROCEDURE NO C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM),

sr. mm mtrr 0 mCmmlAL am'. / / mmXa / /

TAEZ 3,4: LIQK) EFHIJMS (coaehuxl)

BhKH CjaKIEE d E, E E E E E E E E E E E Xnu. Za amain (mm) Cr E E E E Ct E E E E Ct E E E CZ E E E E Cj E E E E Cj E E E E

~ ZE-Q5 Ct E .

mcIides that tats dstsossd should ha ajdsd to ths psttjat E

ljst of E

Ctt sssspls fottsa.

E ElEIDL PQKR & IZQK QHPAFL SZ, Ill% MT 0 TAEZ. 3a5 LIQGD EPIIlMS - MSE SHHAZEN P@ Gmuy Idun LoaxtM: Jqy kh1t Ezpoaxee XatmaL Pnxa

Page 45'f 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITE DOSE CALCULATION MANUAL (ODCM)

HlRIDA PSKR & IJQK QMPANE Sr. mrs umZ 0" SmuANmr. mar - / / mmXa / . /

TAEZ 3o6z GASEX5 -

EFIIllMS SQMKX OF AU REUASES A Pfsafca ac@ fhtLvattaa Gases 1 Total Release

? Adman Release Rate For Parks B XaBnes 1 Total Tacoma-DI.,

Amzage ReIease Rate for ParM C Parka Qates 1, ParthuL~> T-1/2) 8 Ihys E

? Avazage Release Rate for Ehzhd E 3a, Gzoss Alpha RadioactivLty E D TcUCbxL 1 Total Release

2. kazage Release Rate for PerM HlRIDA PNER & LKHZ QMPALC'Z IIXZE UNIT 0 SmIANmu. mme - /. / AX@ / /

TMZ'3 7 -

@GRUS EFIIllBGS QKSM), INEL HEIZASES (1KkKZ EEL)

(XMBUXS MXE MZ gllllVIR0 glMZL t 1 Hsstaa Gases.

Ak&1 CZ E.

X-133 ZE-034 'Z XE-135 XE-UR E E XE-138 E E UNIDENZZPXED E. K KthL PQR PHGGD QME) E E.

Page 46 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFPSITE DOSE CALCULATION MANUAL (ODCH)

HSHZM PSZR h re EX'MPML'r.

uN1Z t SBKhNMIAL HEPOHT - /. / THEIXK / /

TAHE 3 7: GhSKUS E%uHMH (coadmed)

I-13L E I-133 E I-135 IZ E F

3. PartLoQates (D.-58 E E

E

~ mcUdes tbst, waxa Mulcted sbou1d be added to tbe parttal List af the ca~de fomat /R4

ST ~ LUC IE PLANT CNEMZSTin OIERATrNG PROCEiURE NO. C-ZOO, REVZSZON 4 ORFSXTE DOSE CALCULATIOH MANUAL (ODCM)

Sr. mr@ maT 8 TAHR 3,8 GASMS ERHIINIS - lX5E SlRMXON QINKR f NR QSlP: INFANL EKK68K IMBLUAL! MH 'QMmi HSg LXMM, Ul% T BMf PlQlÃf (mrem) (axes) (mme) (mrem) (mrem) mxem)

) Ground Plane (A)

)Grass- +Oak (B)

~~a (A)

) IIAL

) (A) SECIOL BNZ'dles '

(8) GM / QlhX SRCCg BNR!

tPAEEHL (hBOS TIME MMfAL)

) Beta Air Ibse

) Sector: 0.97 adzes NJIK; 'ibe dose @alum above mre calcLdsbul using actual >uatemolngkcal data @ming the spedf ied tiua interval with NZ data reduced as per Heg. Qdda l,ill,March 1976.

I /ttA

Page 49 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING'ROCEDURE NO ~ C-ZOO, REVISION 4 OFPSITE DOSE CALCULATION MANUAL (ODCM)

N Zdel MPC (~a) ~~1 MPC (m/W) MPC (uQ./mli

~B- 3 E-3 I-K 2 E-5 Te-13 8 &4 St-24 3 E-5 ~hL 3 5-3 '1h-131m 4 E-5 P-32 Z~ T&l 3 EH Te-I31 Ncoe Cr-Sl 2 E-3 ~2 .6 E-5 Te-132 2 E-5 Sr-54. l. Er4 3 EH I-Q) 3 E+

1EW 6.E-5 I-131 ~

3 E-j 8~ 2 Zr5 I-132 8 EW Pe-59 Co-57 5 E-S 4 &4 -

~5

~7 1 &4 9 Pr4 I-133 I-134

'1 Peti 2 E-5 Co-SB 9 E-5 4 E-5 I-I35 4 Eiti 3 &5 3 E-3 Cs-134 9 EW HL~ 1 Er4 ~ 'Ih-101 Nue ~136 6 E-5 2 Er4 Bn-M3 8 &5 Cs-137'h-138 2 E-5 2kHi5 1 EH Rr-105 1 Er4 Nue zaHB 2 E-3 Bu-1%' 1 &5 Ba-139 Ncae E-5 Ag-110 3 E-S Be-140 2 E-5 3~

Nues Sa-113 8~ Be-14l. Ncoe In-113m 1 E.-3 Ba-142 Nue Noae Sb-122. 3 Er5 Ia"140 2~

M@86 2 E-S Sb-124 2 E-5 Ia-142. Nue

.Noae Sb-125 1 &4 Ce-141. 9 E-5 A@69 Nue ~12' 1 &4 (h-143 4 E-S

&6 Te-127jn 5 &5 Ce-144 1 E-5 3 E"7 'Ie-I27'1 2 &4 Br 144 Rae 5 E-5 Te-129a 2 &5 W-187 6 E-5 SMZ 6 E-5 Np-239 1 &4 If a amide is mt listed, refer to 1M?820, ApIeakbc B, and use the aust.

anserwei.ve insotuhIa/sotume MPC.stare. they are @trna in TahLe II, Cotunn 2.,

- (As per Noae Cot listed ebon ~

IK?820, Apperdhc B) "No MPC Emit far aoy sbqga decay Bode other than alpha eclfssicK1 or spcnta fissi.cn axi wUh radioactive half~e less than. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> "

r Pap .> 50 ot 80 ST ~ LUCIE PLANT CHEHISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (OUCH)

TAME h-2 ENVIBQNMM PAGl4lY~ KNNSION FACNS HR UlPID DISQlARKS PAGQAY ShLT QNR FISI AtS SKJHSi -

AX GROUP AIMLT iMGhN lXGE EhCIIR (NREM HM oCiPC)

'QQMOID RKhL MN

0. 3.QR&l 3.QE&l 3.QEl 3.QE1 3.QKr01 3.QR&l 0.

0. 0. 30 1.238HN 7. 2Pil00 1.4IEHI3 5.596HN

0. 1.785HI2 0. 2.268Hl2 0. 5.68HHO 3.17BN1 l,15&05 5.1%H5 0. 0. 6.01N05 2.03$ H5 1.368K5 8.

0. l. 2E~ 0. 0. 3. 2.36SH12

0. 6.055H12 0. 0. 0. 1.35BHO

.026HI2 0. 0. ~ 1

0. 2.155HI2 0. 5. 1EHI2 0. 1 01K~

l. 2005 24 1 1

0. 0. 0. 0. 0. 4.68MO 4.OMN

0. 0. 0. 0. l. Wl ~2

0. 0. 0. 7 9 2Yr02

0. 0. 0, 0. 0. 3.86E~

0. 2.9

0. 1.79E~ 0. 0 0. 0. 9.9R&l

0. l. 1%t00 0. 0. 0. 0, 8.38E&l

.0 1.23K%5 . 0. 0. 0. 1.6%HO 3.0 9.43M)l 0. 0 0. 0. 4.75ea2 4.155HS 1 l. IlHOO Based on 1 dX/sec xeliase xste of each isotoPe in discharge fbi of 1 cc/sec Mlth m sddltionsl dilution

ST ~ LUCIE PLANT Pap '1 of 80 CIIEHISikY OPERATING PROCEDURE NO ~ C-200, Rl5VISION 4 OPPOSITE DOSE CALCULATION HANUAL (ODCH)

TABIZ b-2 PABQAY SQZ WQK FlSi A% SKiZIhli NR GONER MILT (continued) eeW IMSE mCIIR (Hlegm az m/Ni.)

%FAL BODY

0. 0. 1. Xz41

0. 0. l. %1 2.23&N 8.89BI01 0. 0. 0 0. 4.896@4 2.38BHS Y~3 1 6%HS 0 0. 0. 5. ~ 67K~

1 r&1 5.13BOO 0. 8.09BHS 0. 1.59BI04 3.47BHS 8.1 4, 2. 9&02 0. 20 0. l. 1BHS 9. 1 3.76BHS 9.5K&1 0. 1 ~ 11BHS 0. 3.51BHB 3.47K&1

2. 1 1.30E~ 3.67E~ Oi 5.57K&1 1.$ K~ 2.1 1 .67K&1 TG-101 1.338r02 1.93BEQ 0. 3. 7K&1 9.82Er03 0. 1.$ Fr01 O. ~ lBHll 8.%MHS 0. 1 15E 0. 3. 1IBOO 1.59BHB 0. 0. 3.08BKB 0. 1.036H5 2.01BH2 AG-110 0. .9 8. 25I02 20 ~ lE 1 0 2.15BHR 7.85BHB 1.1%SR SS-125 2,2%402 2.37YiHS 1.96El 0. 20 1,95BHB ~ 2BHll

~ E 1 2 9lN01 TE12 i 5. 1.9 0. 1 TFi-12 8. 3.2%Hu 3. 3NOl 0 1.9XWX)

9. 2E

2. 9.65E&1 1.95E~ 1.07BHll 0. 1.92BHS .21E1 1.416l02 6.8wl 1.09IB02 .95BN2 0. 6.81BHB 5. 2BHll 20 1.33BHl2 1.285HB 0. 1.24BNZ

,Based oa 1 uCi/sec telease tate of eaCk isotope in discbargp flaw of 1 cc/sec with xe sdditiamQ. dilotLan

C

~

ST LUCIK PLANT PaI;,.>52 of 80

~

CHKHISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITK DOSE CALCULATION MANUAL (ODCM) wneNNm ~ ~ uew PA'QbÃf SALT RGB FIN M) QÃQFl& NR GNXP AMZ (contiaued) ha8 um FACKR (Nm/IR it@ uCl/Hr.)

GHLX I 1 2.18K%02 3. 1.02BHI5 5. 0. 8.2 I132 1.07BIOl 2.&5BIOl 3.76BHB .55tBOl 0.

1 I 13 ~ 5 1 5.36BHS 1.01BIO1

.57BHS 1.51BH)l 1.96K~ 2. 1BIOl 0. 1~32K~

I135 2.33BIOl 1 8.039 9. 1 0. .88BIO1 5.41BHS 2.25&01 7.17FiIO2 2.83BHB 0. 1.58BHB 2.16BHI2 3+22&02 2.NK 03 8.79BHB 1.ZVifQ 0. .0%HB 1.36BHB 2.31BHI2 7.88B03

5. lEM 0. 3.188r63 1 3%901 2.3ÃrOl 1.65BHB 2.07BHS 0. 1 18BHS 3.39BHB 1.0%HQ 1.N&N i+2%

HA-142 1.73BHS 1.78Fi43 0. 1.5Xr63 1.01Fri8 0. 1.09K&1 1.58BHS 7.95K&1 0. 0. 0. 5.83%34 2.llE&1 9.1 CE-1 1 2.3 1.9K~ 0 .8 ~ Wl CE-143 6.0%r01 4. 7BHQ 1

0. 1.9 Wl 0. 1.67E 04 4.9~

1 9.

1.91Yi42 .RH3 0. 4. 5E~ 0. 2, 3E~ 9.

M 187 9.17BHS 7.68BHS 0 0 0. 2.51BHB 2 696HS Based cn 1 uCi/sec zelease xate of each isotope in dischar~ floe of 1 cc/sec sixth ra sddltiana1 dUutian

.Page 53 of 80 ST ~ LVCIE PLANT CHEMISTRY OPERATIdG PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM)

TENEZ G-1 IN AIR IN QSEli~KD AHnjS Ra1Ifde HK (uX/aa> lbc1bh~ (~ac) 4' HEC

~l 7+1 1 &9 EW ~5 1 &9 1 E-7 3 &9 Ki&6 3 8-7 3'~

2 l&B Ru-1% 2 E-10 2EW ~110 3 8-10 3 EW Sn-113 2 &9 3 EW In-ll3n 2 8-.7 4 E-7 1 E-10 3 E-7 1 8-10 3 E-7 7 8-10 9 E-10 1 8-7 Te-12ch. .1 ~

2 E-7 I-130. 1 8-10 2 &9 I-131 1 8-10 8~ I-'l32 4 8-10 6~

6 Er9 l~

2 EH 4 E-M Cs-136 6 8-9 (h-137 "

5 Be-ll0 8-10E-10 reer Is.-140 3 E-ll Ce-141 3 EH Ce-144 2 E-10 (1) If a mcdade Is not listai, refer to 1K%20, QyexHx B, and use the aast axmeeuatim tusatuhle/saMQe MPC where they are gfvm in Yahle IX, Catuan 1 L

.9V., <<AC, 'o;: Ctp<<i<<+g,,*i% 4 r+ '4 r, 1'<<rt'+ . -W <<..<<<< ii4i>~r '<<'r'r<< f %~rgb<<; t4p!-.<<"~~!', <W ".,<<.Q,V<<g; <<,t: z""'i! <ma L 0

(R 51 4.68MS tS 54 1.38BHJ9'.

5E~

m 57 1.89E~

3.8OWS 2.15Pil-10 7.43E~

9.01E Sly~9 2.1 Fil04 5.35&06 1.086f06 ZRM5 5.01E~

1.36MB MJ-103 1.1(H~

4+19E

- mlat- 3.58E~

5. 16BI-10 S8-12 5.988~

SB-125 2.3%+09 TL'123i 1.55EK6 8.79BH15 3.85BO7 I 130 5.53Q06 I131 1.72EW7 I 132 1.25M6 I D3 2.48E I 13 .5QM5 I135 2.56E+06 6.99E+09 1.49K~

CS-137 1.03&-10 BA-140 1.68K%8 (Z-1 1 l. &7 CE-144 1 ~ 13MS Bawd cn.l uCi/sec ltelease Rate of Each Isotope in and e Value of l. for gg, depleted ){/Q and ttelativa Deposition

/R4

Pag- 57 of UU ST ~ LUC IE PLANT CltEllISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (OUCH)

TAEZ 0-5

- MALATI% I)/K )

PA11 NAY AX GAP MSE PACER QM'YR HR uk'/Ga Mater IN'BQAN KIM '1UZhL MR 0, 1.885N2 MH02 3%HI P 32 2.318105 1.35BN4 0. 0. 0.

~

1.518N4.

~

8,785HB GL 51 0. 0 1AÃd01 3.99EKO 2 52bHB 5.81M@ 1 755Nl 2.068HB 4.86BHS 0 0. 1 785H5 3+2%@4 lo854HB 1.2lFiN2 0. 0. 6. 5.5CBHB 1.18BN2

~1 0. 8.

0. 8.4QBQ2 0. 5.578HS 3.285!04 1 178HB

.6 1.8 0. lo21E 1.53BH5 9. 8.1 4;318N4 0. 0, 0. 2.318HS 6.8QiN4 1.248HH 1.328HJI 0. 0. 0. 1.535N7 1.395H5 8.068H5 Y~l 5.9 0. 0. 0. 2.6 ~1 1.6QiHH

'.%5104 2.73BHH 0. 9.485HB '.818HS lA18N4 1.95BHH 1.285HH 5 755N2 0. 1.35BHH 4 77E~ 1 218N4 3.371802

0. 0. 1.0 5.855HJl 9.31FiHH 0. 0. 2.34FiN4 li5QiN7 1 76BK6 1 148HB 40110 1.89BHB 1.75BHB 0. 3 448HB 8.125H5 5.298N4 1.048HB 0.

2.218l05 5.858HB 1.728HB 0. 1.645HS 2.23Erl04 8.4QB03 1.038KB 1,32E&l 0. ~ 11BN4 2. 178HH

.255N2 1.03BNl 0. 3IU 2.3 3E129f 4.54BN2 1.955N2 1.538102 2.17BHB 4.96BN5 1.36BN4 '.16BI01 TE1281 2.218HH 5.758N2 8.018N3 1 685H5 2.62BN4 2.745N2

'1E1294 1.8%Kb 3 24 I

~

130 8.028N2 ~

2.35BHH 3.05BH5 3.65BHH 1.35BHH 9i258N2 I131 ~ 2 l. 1E 1.0 0 1.0 20 I03 1.34504 1.9%+04 4.66BHS 4.555HB 0. 5.87BHB 1 ~ 13Er$ 2 3.025N2 4.025N4 4.825NR 0. 1 76E&1 1 NBN2 4.8QiN5 0. 5.048N4 1.0l8N5 1 37bHH 7,325N4 CS-136 6.855HB .2.565N4 0. 2.1QiHB 2.048HH 1.955N4 5.7QiHH 4.27EKO 0. 2.93MO 1.64FiHS 3.885HG 2.955N2 2.525N3 1.555HH 0. l. 1%HB 5.24bN5 2.06BN4 1.81IHOZ 1.82FiH5 0. l. 85H5 1.275N la615H5 2.495N4 Based a> 1 uCL/sec Release Mate of Bach Isotope ln and a Mme of l. for Zlg, dayleted Qg and Relative Deposition

ST ~ LllC IE PLANT CllEMISTRY OPERATING PROCEDURE NO C-200 ~ REVISION 4 OPFSITE DOSE CALCUL'ATION MANUAL (ODOM)

TAEZ M BSIBD8%5EA1 PAQMN-DSE GINhIQN PACKtIS R(I)/P(I) HR GAS1%1$ DISIlSNRS PAIlQAY GRIS HQX (OMMHINh'W) EBLIS) AZ QMP 1%atK QEAN IXSE PAf:8R (

' HEIXR - MIIH4/YR Etk ulX/Sec P 32 1.82BI.10 1.14BH8 0. 0.

20 0.

~ 3 2.05BH8 7,05BHS

0. 0. 1.8%I04 6.72BKO 4.04&% 7 66BI06 3.058%4 3.17BN7 7 52EKl 0. 0. 2.09BHP 2.48BHS 2.86'.27IB06

0. 1.38806 0 0. 0. 3.46BHjl

0. 8+73BI07 0. 0. 0. 2.16BHS 2.INBN 1.46BH8 4.65PiK8 0 3 llBH8 0. 2.9%HB 2.1%H8

0. 2e77PiH8 0. 0. 5.45BHS 1,29BH8 1 47BI.10 0. 0. 0. 0. 2.75BHS 1.65Ml 0. 0. 0. 1.61BH8 4,2UB 10 2.12BI05 9.41BI04 0. 1.86BI04 0. 7.47hI07 5 0 56bI04 5.49BH5 2.47BH5 0. 0. 1.98BHS 1 45E~

RU"106 2.01BH5 0. 0. 4.3SI04 0. 1.56M5 2 46BI04 hG IO .21BI0 0. 1, 13BHS . 5BI.10 ~ BIO SS-124 2.75BI07 5.19BI05 6.64BI04 0. 2. 13BI07 7.78BHS 1,0%H)7 3.59LKP 3.2 2.9%K6 3.96BI06 2+83BH8 2.43BHS 6.62BHI6

&12M 5.548%7 1,9XKI7 1 79BI07 2.lXSKS 0. 3.24BHS 7 38BI06 TE 1291 5.8 2.21BHS 2. GB 0. 8.95IB0 I 131 2.59BH8 3.09BH8 9.94E+ll 7.74BHS 0. 1 16BHS 1.81BH8 I132 1.71&01 4 76E&1 6.26BI01 7.58El O. 1.698%1

~ 0 I 134 0. 0. 1.06E~ 0. O.i 0. 0+

I135 .9

'+10 0. 9.

2.78BHS l. 1%H8 O. 6.11BHS 8.37BI07 1 25BKS

+10 .21E+10 0. 3. 8. 1.86BHS ~ 14BH8 2 45BHS 2.47BH5 0. 1.22BI04 1.51BI05 8.136HS 1.27BI0 K-141 2.65BH5 '1.6~ 0. 9.726HB O. 7 87BI07 1.%ht04 8.29BI 8.6 IIased m F1/sec IIelease Bate of Isotope fn and a Value of 1. for X/g, depleted N/Q and Helative Ueyosj.tfan thee: 'Qm 1

units for 0 and 14 Lt Eadem 3 are (MIX~Ver uCI./(h. Heter)

~ '~

I Pay, ~>59 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPOSITE DOSE CALCULATION MANUAL (ODCH)

TABlZ 0-7 K )/K >

PANY GNS MEK (GKEhHINfXHD HNNR) NR GAP USE EhCIIR (Sg. MEHK - MK~HR uQ./Sec) INANI.'BQhN

0. 2.1 32 2 196l.10 378H8 0. 0. 0. 2.46BH8 P

0.

1

0. 2.196HB 0.

8.0 3 2IFiN5 0.

.855HB 9 1~

3.296H5 3.665HB 2.058N5 0.

4.125H5 9 786H5 0. 0. 2.7N5 3,236H5 3.726H5

0. 0. 0, 0. 2.728N5 0.

0.

1.76BHS 0.

3.

1.058N7 5.578HS 3.326HS '. 0 0

0.

0.

0.

0.

2.595Nl 3.51BHS 6.

~ %H5 2,51BN7 2.526HS 1.556HS RU- 03 3.0%+10

9. 45HB 2.548l04 6.595N4 9.

0.

0.

1.136N4 2.9 0.

'. 0.

0.

0.

0.

0 0.

0

.2.235HB 5.815HB 0.

0.

0.

0.

0.

0.

5.77E~

-3. 55H8 8.955H5 2.378N7 8.875HS 8.835l.10 20 6.67N03 1.755N4 2.4 0 0. 5.046HB 0 1.876H5 2.965HB kG110 0. 1.366N7 0. 2.818H8 4.1%HS.

SN-12 2.1 3.39B06 6.2m4 7.97BHB Q. 2.565N6 9 338N7 leXBHS

~ 318 3.9 3.5 2.9

.896N ~ 2 8. 0. 9. 2.5

'IE125 6.648H5 2.31BH5 2.155H5 2 4%N7 0 3.885N7 8.855l05

.056N7 2. 2.668N7 0. lo078N I130 0.

I 131 3,11E409 3.7%H8 1.195l.12 Oi 1,396HS 2,17BH8 I 132 2.13&01 5.71E&l 7.5IBNl 9 1CR&l 0. 1.07Vr41 2.03E1 I 133 ~ 5GBO ~5 1.5 10 1.5 0. 1~1 1 9%N I 134 0. 0. 1.27' 0. 0. 0. 0 I135 l. %l04 4,7'.395l-ll 186H5 2. ZE1 5.296l04 1.3 11 0. 1. 'rl.lO 2. 10 10 8.348HS 3.298H8 0. 1.836H8 2.518HS 3.748HS 2 t 37BH8 1.935l1 1 2.165l.l 1 0. 1.1(& 10 2.61E+10 5.59M8 1.248l-l0 Bk-1 0 2.956N7 2.96M% 0. 1.8 9.766N5 1.5 CE-141 3.1 EKA 1.95@% 0. l. 178HB 0. 9.448N6 2;286HB CE-144 2.526H5 9.958H5 0. 6.MB04 0. 1.045HS 1.365N5 Based cn 1 aCi/aec Release Rate of Esch Isotolm in and a Value of 1. for X/g, depleted gg aod Relative Deposition

$ Qt pa %as ~~ alt r F" > > ~ ~ "'~ ~~ el) uf Ill'il/YI ivy>

Page 61. of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM)

Sele~g the Appropriate Izzzg Tean (@' or (~D(Q for Ense Calculaticns IZNalvtng RadiohxUzzes 6 8 D PartiaQates fort (1) Ixkzslz~ (2) Tritium (All gss Pathzays) (3) Gtoazd Plane LIMZIXHrSEGER (N) sec/nP (E7@ 1/zn )

0+97 B 1.3 X 10 //////

Qarterly for 0 97

/////// 8DX 10 Semfaazneal 0.9 1 days IlX),

Qtr. yearly IlD, 0 97 B

1& X10 //////

12 ccxaenztive math IQ) 0.97 /////// 8.2Xio~

(6) Over land azeas caly (A) To be detezmtzzed by rachcticzz of actual net data occurring during each ~zrter Q) Por Tritium in the MQk Anizazk Pathway, the (g value should be that of the

. respective eatmllizg sector a+i zan0. stere the Azztuel is located aa per .

Table M-3. Ezanplez If a cur benz located at, 4 25 mQes izz % sector, use tbe

%Q)D for 4M mQes tu.

Page 62- of 80 ST LUCIE PLANT CHEMISTR'I OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM)

Selectfng the Appropriate Leg Term (D/Q) for Ibse CalculatLons Involving RaKoieKnes and PartiaQates for Grass~fok or Grass~~:

TYPE OF DOSE LIMITIMr LIMZEING D Q) Value CAIQifAIXCN RAMZ SECKR 1/m A A I I/3i Ihys - GD B B guarterl Yearl - UD B B B 8 B B C C C A ihe mzst car or goat as per locations from land census. If no mUk anfnsl in arty sectce, assuna a cow at 4.25 mQes in the highest (7DQ) sector over land.

B. The historical (D7Q) of all land sectors with the worst cow or goat from each sector as reported in the fand Census. A 4.25 mile mw should be assuned in the worst'sector, when no mUk aniaal is reported.

C. Tbe hi~t (D/(3 at a mLIk arxfaal locaticn of all mQk aniaals reported in the Lnd Census Report.. (If xn mf1k admQs withfn 5 mf1es a 4.25 mLle cow should be assuaged in the sector having the highest (~D at 4.25 mf1es).. Actual Het Ihta shoufd be used fear the selectfon of the erst case mok aninel and for the dose calculattum. If both goat md mUk anirmls are reported inside 5 mf1es, dose calculatioos should be perforned m each anfnal and the higher dose perforsad on each aninal and the hi~ dose anfml contrf,butica'hould be used.-

The hfstorLcal,wind frequency fzacticns foe each sector are listed in Tahle NH.