ML17215A820
| 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 ~
DATE'ACIL:50-335 St. Luci e P lant~ <<Uni t 1 <~ F 1 ori da Power L Light Co ~
SO SS9 St, -Luoie-P lantq Unit 2jj Florida Power S Light Co, 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 05000335 05000389 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: OL;02/01/76 OL:04/06/83 05000335 05000389 RECIPIENT ID CODE/NAME, NRR OR83 BC 04 INTERNAL: ACRS 11.
IE F ILE 01 I
9 NRR/DS I/
0
/MIB EXTERNAL: LPDR COPIES LTTR ENCL 7
7 1
1 REC IP IENT ID CODE/NAt1E NRR ORB3 BC 04 AEOD NRR/DE/EEB 08 NRR/DSI/i4IETB RGN2/DRSS/EPRPB NRC PDR COPIES LTTR ENCL 7
7 1
1 1
1 2
2 1
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
- Atlanta, 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 Attachment cc:
Document Control Desk (2 copies of attachment)
Harold F. Reis,, Esquire.
P NS-LI-84-65 DESIGNATED ORIGINAL' r
CB-<ifie4 B II
~ Ea
~L, PEOPLE... SERVING PEOPLE l
+~v+pr<>>rv 0 P>> x'j>>6.
c '@gal'ggnqrrj~g~vr'>>'":>>p>>,. ~", 'p.,~ p,i, ~~ g ww'w'.,,year)w ~), J, J
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
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 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~
GASEOUS EPPLUENT SUMMATION OF ALL RELEASESo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ 12
~ ~ ~ ~ ~ ~ ~ 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 K )
1 and V
V'33(OT L + 1+i N l) <1 V
V V
'(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:
(2) and 13 (QT N )
1 V'
6+3.(QT M )
1 V
V The average release rate of" gases from the site during any 12 consecutive months shall be:
and 25 (QT N ) <
1 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 of 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 Liquid Gaseous
~Avera e
+9X klOX Maximum
+30X
+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 SOURCE
'onitor Tank Releases SAMPLING PRE UENCY Each Batch Monthly Com osite.
Quarterly Co osite TYPE OP ANALYSIS Principal. Gamma Emitters H-3 Gross Al ha SR-90 SR-89 METHOD OP ANALYSIS p>>h>>a>>
L>>S>>
G>>P>>P>>
C>>S>>
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 SOURCE SAMPLING TYPE OP PRE UENCY ANALYSIS METHOD OF ANALYSIS Waste gas Decay Tank Releases Containment Purge Releases Plant Vent Each, Tank Each Purge--
Weekly Monthly Composite (Particulates)
. Quarterly Composite Particulates Principal Gamma Emitters H-3
~ Principal Gamma Emitters H-3 Principal Gamma Emitters Gross Alpha SR-90 SR-89 G, C, P
h a L>>S ~
G, C, P
h a>>
L>>S>>
G%
C%
P
.h.a.
L S>>
P - G>>F>>P>>
C>>ST L>>S>>
G C'
L S ~
C>>S>>
pha G>>F>>P>>
Gaseous Grab SampXe Charcoal Filter Sampl'e Particulate Filter Sample
- Liquid Scintillation counting Chemical Separation
- Gamma spectrum pulse height analysis using Lithium Germanium detectors'
.'ll; peaks're identified and, quantified
- Gas Plow Proportional. Counting.
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 SOURCE Monitor Tank Releasesl SAMPLING FRE UENCY Each Batch Monthly Com osite Quart er ly Com osite TYPE OF ANALYSIS Principal Gamma Emitters H-3 Gross Al ha SR-90, FE-55 SR-89 METHOD OF ANALYSIS pehoao LES+
GoFoPe CATS+
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 SOURCE Waste gas Decay Tank Releases Containment Purge Releases Plant Vent SAMPLING FREQUENCY Each Tank Each Purge Weekly Monthly Composite (Particulates)
Quar terly Composite (Particulates)
TYPE OF ANALYSIS Principal Gamma Emitters Principal Gamma Emitters H-3 Principal Gamma Emitters H-3 Gross Alpha SR-90 SR-89 METHOD OF ANALYSIS G%
C3 P
p,h.a, G, C, P
h.a
~a LeSi G.
C.
P
~h a L+S ~
P GoF+Po CiSi
'L Se G
C P
L,S ~
C S
p,hia
- GiFiP, Gaseous Grab Sample
- Charcoal Filter Sample
- Particulate Filter Sample
-'iquid Scintillation counting
- Chemical Separation.
- Gamma spectrum pulse height. analysis using Lithium GExmanium detectors.
All peaks are identified and quantified 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:
b, Total time period of batch releases:
c
.Maximum time period for a batch release:
d Average time period for a batch release:
e Minimum time period for a batch release:
f Average stream flow during periods of release of effluent into a flowing stream:
ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5 2 Gaseous 34 15167 MINUTES 579 MINUTES 446 MINUTES 314 MINIJTES 529460 USM.
a Number of batch releases:
b Total time period for batch releases:
c Maximum time period for a batch release:,
d.
Average time period for batch releases:
e Minimum time period for a batch release:
ALL GASEOUS WASTE RELEASES ARE SUMMARIZED I
177 MINUTES 177 MINUTES 177 MINUTES 177 MINUTES IN TABLES 6i Unplanned Releases 6.1 Liquid ai, Number, of releases:
b Total activity released:
6 2 Gaseous a
Number of releases:-
bi
,'"3 See ae b
.Total activity released:
attachments (if applicable) for:
A description of the event, and equipment Cause(s) for the unplanned release involved 0
0 CURIES 0
0 CURZES'o d
Actions taken to prevent a recurrence 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 Bone Liver
'Thyroid Kidney Lung
~
GI-LLI Total Body DOSE meem e
lm61E-5 2.4 E-3 7'
E-3 lml E-3 2.4 E-3 2.4 E-3 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 A~
Fission and Activation Products UNIT UARTER 3
UARTER 4
I ~
Total Release (not including tritium, gases, alpha) 2, Average diluted concentration during period 3
Percent of A licable Limit
)BE Tritium
}
1 Total Release 2
Average diluted concentration durtn~artad C
Dissolved and Entrained Gases 1
Total release 2
Average diluted concentration durin eriod Do Gross Alpha Radioactivity-1 ~
Total Release CI 3 09E-1 uCI ml 1 58E-8 Percent 3'9E-O CI 3o 52E+I uCI/ml 1 ~ 79E-6.
j'I 1.54E-2 0
uCI/ml 7'3E-10 2'4E-1 2+43E-8 N/A
)
2 OOE1 1.94E-6
E>>
Volume o Waste Released
( rior to dilution)
F Volume of Dilution Water Used Durin Period Liters Liters' 96E6 I 96E10 1 45E6 1 03E10
Page 10 FLORIDA POWER
& LIGHT COMPANY ST, LUCIE UNIT NO+
1 SEMIANNUAL REPORT TABLE 3+4 LIQUID EFFLUENTS CONTINUOUS MODE NUCLIDES RELEASED UNIT UARTER 3
UARTER BATCH MODE UARTER 3
UARTER 4
MN-54 CI CO-31 ~CI C0-58 CI FE-55
) CIJ ZN-65 CI NB-97 J CI AG-llOM SN-113 "SS-122 CI CI CI SB-124
] CI J W-187 CI NP-239 CI ZR-95 CI MO-99 CI RU-103 CI CS-134
~CI~
Cs-"134" '"
cx CS-137 L CI BA-140 CI CE-141' j C'I]
xA-i4o '~cz ZR-97 J CI L NB-95'I I-131
)~CE
"" "I--532 I-133
~C~I Ne-24 ~CI 1 22E-4 0
1 36E-4 1 35E-2 3 25E-3 2 ~ 13E-2 1 ~ 51E-2 3'3E-5 9'8E-2 4.39E-3 2.93E-3 2 28E>>4 1 74E-4 5.29E-2 8.23E-2 0
8 17E-4 8 OOE-4 1 56E-2 5'5E-4 1 23E-3 0
. 5'5E-4 0
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 NUCLIDES RELEASED UNIT UARTER t 3 UARTER 4
BATCH MODE UARTER 3
UARTER 4
}
} 'E-144 CI 3 82E-4 0
}
SR-89 CI 1'9E-4 1 38E-4 ER-PO'z O
Y-90 CI 0
}
Tc-99M Pr-144 TOTAL FOR PERIOD ABOVE CI CI CI 0
5 llE-4 3 09E-1 0
2 64E-l AR-41 J CI KR-85 'I XE-131M L CI
}
J
' "" XE-129
}
XE-122E J
CEJ XE-135 CI CIJ 1 ~ 17E-2 8'5E-6 1 79E-3 0
5 98E-5
}
0 0
7 05E-2
}
4'7E-4
}
1 01E-3
}
XE-138 TOTAL FOR'ERIODABOVE CI CI 1 91E-3 1 ~ 54E-2 0
7 19E-2
.Note:'
If no value is1 entered for a nuclide, the,,value equals zero Curies r
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 PATHWAY TO ORGAN Bone Liver Th roid Kidne Lun GI-LLI T~ Bod CALENDAR YEAR DOSE
'mrem 4 65E-2 1.51E-I 2.56E-2 1 '2E-2 1+4 E-l 6 95E-2 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
}
2 Average Release Rate for Period
} uCI sec 3
Percent of Tech S ec Limit X
B ~
Iodine s
}
~
Total Iodine-131
}
Cr 2.
Average Release Rate for Period
} uCI/sec 3.
Percent of Tech.
S ec. Limit X
0 0
0 0
0 0
C Particulates
}
1 Particulates T-1/2 )
8 Days 2 ~
Average Release Rate for Period 3
Percent of Tech..Spec Limit 4
Gross Al ha Radioactivit
}
CI 7.34E-5 uCI/sec 9'3E-6 X
6 69E-5 CI 0
0 0
1 01E-08
}
}
D Tritium Total Release CI 3
OOE1 2 'vera e Release Rate for Period
'uCI sec 3'7EO 1 85E2
}
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" KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-138 TOTAL FOR PERIOD ABOVE CI CI CI CI CI CI CI CI CI CI CI CI 1+86E-2 1 86E-2 0
0 2 ~
IODINES I-130 I-131 I-133 I-135 TOTAL FOR PERIOD ABOVE CI CI CI'I CI 3 ~
PARTICULATES Co>>58 Co-60 SR-89 SR-90 Y-90 CI CI CI CI CI CI CI 7'
E-5 0
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 Gmund Plane A
}'ss-Ca~1k B
Inhalation A
BQR (mxem) 0 0
0 5.868-2 2+9K-2 8.768-2 2MSID (axea) 5.868-2 2 9E-2 8.76E-2 NA 2%57E 2 I 27E-2 3.84E-2 5.86E-2 2 9E-2 8.76E-2 5.86E-2 8.76E-2 T, ME 0
5.86E-2
}
2.9E-2
}
8 76E-2
} (A)
SJPCC:
ter RAMZ:
1 78 miles
}
}
B GM KlhT SECHR:
MST RAZZ:
4.25 miles
}
CAUMMYEN (aaad)
} Sector:
Beta Air Dose N/A 1 78 0
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 willbe the first full calendar year for calculating dose m per S TD
.FXORIDA POWER 6 LIGHT CCMPMY ST. LUCXZ UNIT ~a.
1 GEE!INUAL REPORT PAGE 16 FFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT (1983)
SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS for ST. LUCIE TRGT NOS.
1 and 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL (Not irradiated fuel) l.~of waste
- a. Spent resins, filter sludges, evaporator bottoms etc.
- b. Dry compressible waste, contaminated equip, etc.
c Irradiated components, control rods, etc.
d Other (describe)
Unit m
Ci m
Ci Ci theone Period E
2.05E 1 E
9.35 E 4 E
E Est. Totlf Error, SS 2.00 E 1 2.00 E 1 2.00 61 E
- 2. Estimate of major nuclide composition (by type of waste)
. Cobalt 60
- b. Cobalt, 60
~t-58 Cesium 137 Cesztm-lr~~
ci Cobalt 58 Iron-Chrcmium - 51 anese - 54 Nickel 63 3.
Solid Waste Disposition 41 Sole use truck 5:
Sole use txuck Br IRRADIATED FUEL SHIPMENTS (Oispositionl r
Number of Shi ents Mode ofTran rtation 9.2 El
.1 E
6.0 El 5,8 EO 2.6 El E
1.0 EO E
1.9 El 23 EO EO 3.3 EO Destination Barni~,
SC
- Richland,
%lash.
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 THROUGH December 31, 1983 I
TABLE OF CONTENTS DESCRIPTION DISPOSAL SUPPLEMENTAL INPORMATION PAGE 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'. mrems to the total body and to < 5 mrems to any organ, snd During any calendar year to < 3 mrems to the total body and to < 10 mrems to any organ 1 '
For Gaseous Waste Effluents:
e 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 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 Liquid AX'aseous+IOX" "
M&XX&&&
+30Z
+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 SOURCE SAMPLING PRE UENCY TYPE OP ANALYSIS METHOD OP ANALYSIS Monitor Tank Releases Continuous Releases Monthly Co osite Quarterly Co osite H-3 Gross Al ha SR 90, SR-89 FE-55 No continuous activity releases for this re ortia eriod Each Batch Princi al Gamma Emitters
~h.a.
L>>S ~
G>>P>>P>>
C>>ST 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 SOURCE Waste gas Decay Tank Releases Cont ai ament Purge Releases Plant:
Veat SAMPLING PRE UENCY Each Tank Each Purge Weekly Monthly Composite (Particulates)
Quarterly Composite (Particuiatee TYPE OP ANALYSIS'rincipal Gamma Emit ters Principal Gamma Emitters H-3 Principal Gamma Emitters Gross
- Alpha, SR-90 SR>>89 METHOD OP ANALYSIS G)
~h>>a G
~h.a L>>S>>
G C>>
P
~h a>>
L>>S ~
P - G>>P>>P>>
C>>S ~.
t
~
G C
P:
L>>S ~
C>>S, p>>h>>a>>
G>>F,P Gaseous Grab Sample Charcoal Pilter Sample Particulate Filter Sample Liquid Scintillation Counting Chemical Separation Gamma spectrum pulse height-aaalysis using L'ithiCn Germanium detectors>>.
All peaks are identified and quantified 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:
b Total time period of batch releases:
c, Maximum time period for a batch release:
d
, Average time period for a batch.release:
e Minimum time period for a batch release:
f Average stream flow during periods of release of effluent into a flowing stream:
ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 14 6365 MINUTES 575 MINUTES 456 MINUTES 314 MINUTES 544937 UPN 5'
Gaseous a
Number of batch releases:
b, Total time period for batch releases:
c, Maximum'time period for a batch release:
d Average time, period for batch releases:
e Minimum time period for a batch release:
ALL GASEOUS'ASTE RELEASES ARE SUMMARIZED 42 13376 MINUTES 660 MINUTES 330 MZNIJTES 23 MINUTES IN TABLES 6 ~
Unplanned Releases 6
1 Liquid a.
Number of releases:
b,. Total activity releases:.
6 2 Gaseous.
a Number of releases:
b Total activity,released:
6 3 See attachments (if applicable) for:
a, A description of the event and equipment b
Cause(s) for the unplanned release c,
Actions taken to prevent a recurrence d
Consequences nf the unplanned release,
- involved, 0
0 CURIES 0
0
- CURIES,
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 Bone Liver Thyroid Kidney Lung GI-LLI DOSE mrem 1 61E-5 2+4 E-3 7'
E-3 1
1 E-3 2+4 E-3 2 4 E-3 Gamma Air Dose Beta Air Dose 1 6E-2 mrads 4 OE-2 mrads Total Body 2 4 E-3 bi 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 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 A
Fission and Activation Products UNIT UARTER 3
UARTER 4
1 ~
Total Release (not including tritium, gases, alpha) 2, Average diluted concentration durin eriod B,
Tritium CI uCI ml 1 45E-1 5 08E-8 2'4E-1 2o43E-8 1 ~
Total Release
/
2, Average diluted concentration durin eriod C.
Dissolved and Entrained Gases
)
CI 1 74E1 uCI ml 6'8E-6 2
OOE1 1 94E-6 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 E
Volume of Waste Released
( rior to dilution PE Volume of Dilution Water Used Durin Period CI Litersiters 0
2 83E5 2'6E9 0
1 45E6 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 NUCLIDES RELEASED UNIT UARTER 3
UARTER BATCH MODE UARTER 3
UARTER 4
I-131 I-132 CI CI 9 19E-5 1 56E-2 I-133 CI NA-24 CR-51 MN-54 CI CI CI C0-57 CI C0-58 CI FE-55 FE-59 CI CI C0<<60 CI ZN-65 NB-97 AG-110M SN-113 SB-122 SB-124 W-187 CI CI CI CI CI CI CK NP-239 CI NB-95 CI CS-137 CI BA-140 CI CE-141 LA-140 CI CI ZR-97 CI I-135 CI
- RU-103 CI CS-i34 I CIJ
'S<<136 CI 1 86E-4 6 68E-4 2 60E-4 1 54E-3 1.94E-2 1 44E-3 3 13E-5 9'4E-3 4 34E-3 2'3E-3 2.73E-4 1.02E-5 4'5E-5 3'9E-2 5 73E-'2 1>>30E-4 5'5E-4 1 23E-3 0
0 0
l
)
)
l l
1 l
I l
'<<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
}
SB-125 CI J
- CE-144 CI SR-89 j CIJ UARTER 4
UARTER 3
UARTER 4
)
Y-90 CI J 0
)
TC-99M PR-144'NIDENTIFIED TOTAL FOR PERIOD ABOVE CI CI CI CI 0000EO OmOOEO I 04E04 0
OOEO I 44E-I 0
0 OOEO 2m64E-I
}
AR-41 KR-85
) CI 5'7E-3 0
XE-131M CI 8 05E-6 0
XE-133M XE-135
}
'R-85M XE-138 CI CI CI CI XR-133
~CZ I 78E-3 0
}
4.57E-4
)
I ~ OIE-3
)
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 ri1 1
1 983 through December 3 1 1 983
- FISH 6 SHELLFISH PATHWAY TO ORGAN Bone Liver Th roid Kidne Lun GI-LLI T~ Bod CALENDAR YEAR DOSE mrem
)
2 24E-I I
1 ~ 1 3E-1 I
9 39E 2
1 This exposure interval is the effective ca 1endar year due to the implementation of Appendix I with License No. NPF-1 6 in April, 1 983 ~
The 1984-year will be the first. full. calendar year for calculating dose as per S, T~S
Page 11 FLORIDA POWER
& LIGHT COMPANY ST+ LUCIE UNIT NOa 2
SEMIANNUAL REPORT Jul i'i983 THROUGH December 31 1983 TABLE 3' GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT UARTER 3
UARTER 4
Ai Fission and Activation Gases 1,
Total Release
}
CI 8.40El 2
Avera e Release Rate for Period uCI sec 1.06E1 1
17E3 1 47E2 B
Iodines 1
Total Iodine-131
}
CI 2
Avera e Release Rate for Period uCI/sec 9.39E-5 1 ~ 18E-5 1 ~ 24E-2 1 '6E-3 Ci Particulates lo Particulates T-1/2 ) 8 Days 2
Average, Release Rate for Period 3
Gross Al ha Radioactivit CI 0
uCI/sec 0
CI 0
2 05E-4
}.
Tritium 1.
Total Release
}
CI 1.74E1 2
Avera e Release Rate for Period uCI/sec 2
19EOO 8 26E1 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 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 UNIDENTIFIED TOTAL FOR PERIOD ABOVE CI CI CI CI CI CI CI CI CI CI CI 5.24E1 1 ~ 20EO 5 36E1 1 ~ 07E3 6
OOE1 1 ~ 13E3 8e77E-1 9'5E-2 0
0 6'3E-2 2m 91El 1 ~46E-l lo49E-1 3 04El 6'5E-1 0
3e32E-2 3'8E-3 3'4E-1 3o43E1 3'0E-1 5'2E-1 3 62E1 2 ~
IODINES I-131 I-133 I-135 TOTAL FOR PERIOD ABOVE CI CI CI CI 9'9E-5 0
9~39E-5 1 ~ 22E-2 1.17E-2 2 39E-2 3
PARTICULATES.
Co-5 Co-60 SR-89 SR-90 Y-90 TOTAL FOR PERIOD ABOVE CI CI CI CI CI CI CI CI CI'
Si.. IIICIE INIT 0 2 TABrZ 3.8 GASEXS EFPU3ENIS IXSE QMNATIONQIARIBt PRANA BZ QEUP:
INPAUI IBBBUHU INHUVAL: IUH 1 AK 83
'BUBKU 31 BE 83
, Ground Plane A
N/A Grass-Cca&filk B) 7.88E-4 Inhalatim A) 3.71E4 1 16E-3 5.57PA-2 568-1 2 71E-2 1 367E-1 8.288-2 4.938-1 A
2.42E-2 1 17E-2 3.59H-2 5 488-2 2 67E-2 8 15E-2 2.67E-2 8 15E-2 To KK IKHS 2 678-5
}
5.53K-2 2.69E-2
}
8 228-2 (A
axna:
mr MZ 1 78 miles
} }
B KM GRF SECKR:
NEST RAMZ:
4 25 miles
}
-Sector:
Beta Air Dose (PAKKR (Aim. TIME INIHN%)
mrad CAIBQhR YEhR (mead) 4.09E-1 1.04EO 1 78 Note:
r
'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
~ZKKGK REPCW July 1, 1983 through Decerkmr 31, 1983 EFFLUENT ANDWASTE DISPOSAL SENIIANNUALREPORT
{1983)
SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS for
- ~T. LUCIE UNZl'GS. 1 anQ 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL IiitlotIrradiated fuel)
PAGE 14 1.~of~
- a. Spent resins, filter sludges, evaporator bottoms etc.
- b. Dry compn:ssible waste, contaminated, equip, etc.
- c. Irradiated components, control rods etc.
- d. Other {descnbe)
Unit Ci m
Ci m
Ci m
Ci
&month Period
- 5. 95E
- 2. 20E 2
- 2. 42E 2
- 2. 05EE.l 9.35E 4 E
E Rat. Torei Error, %
2.00E 1 2.00E 1 2.00E 1 E
- 2. Estimate of major nuclide composition {bytype of waste)
Cobalt 60 b.
9.2 E
E.
6.0 E
c'esium 137 V~ anese 54 2.6 El
~ b E
.0 EO i.c E
Co 50
'T Chra" um 51 pNicl~ 63 3;
SoM Waste Disposition e
41 mc'e use true):
5 Sole use ~ck.
B. IRRADIATED FUEL SHIPMENTS (Disposition) 1.9 El 2.3 EO EO 3.3- $ 0 Destination Barmn~,
eC.
Richland, Nash.
Destination Note:
During the above period there mre no shipments of
- 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)
Review aad equi <o<y~ ~y 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.
- Aling 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. It describes the dispersLcn cbazacteristics of a semL~d.te cloud 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 I
v
<<q
),
<<~
<< ~<<,
<< ~<<.~, ),<<'<<c:<<P<<<<,-g:~
<<<<q<<<<<<'<<)l qr) 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 sfayiiffIingthe 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
)h PIP)
P).
re@dred to dexnstrata coapHLance with the lfX:ER20 MEC liad.t. ~ falhxdng section pmvides a stef~tep pmcedoxe fcr detezmfnfng the MPC freya.
'.2.1 Calculaxfon Pmcess for Solids 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.
1.2 1D Obtafu (Ci), tha undUuted assay value of muLida (i), in uCL/nil. If tbe siaplified method is used, the cuaulative ccacentxatica (~) is useda 1.2 1.4
~PPPI
<<)
~/ml
'Ihe value of-3 X1'CL/ml sbouId be used. for the ah~Xied 1DEQlode Divfd Ciby Ofpc)i~~~ th ~~
1.2.1 5 1.2 1.6 1217 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 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 condfticnsa lfPL is<<>1; admfnfstrativa-steps aze taken to ensuze that the actual release caxKtbxm for dfhabm~ enaue that PL is <1 dnrfng the actual release, P is called tha fzactfcn af 1CPJ20 MPC because it, should macr be.
to be >1 P
, 'It h
p ph
't p
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-P
. ~ (sum of 1.2.1 1) uCi/ml XR S'
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-I I-131 19 UM)ILUKD
~/ml 4.43 EH Q2 (ao unLts) 1.22 E-3 I
I 132 2 23 Ei-7 2.3) E-7 I I 133 3 17'62E5 I '-U5>>
1.31' 271' 24 1.72 E-7 4.74 E-8 l
Ct 51 2.51 Ei-5 1.04 E-7 5m E-6 4.66 E-7
) ~
1'll EH 9 17 E-ll Co-57 3.69 E-7 7 62 &9 I
Co-58 1.51 &4 1'M &5 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. It wm detexmfoed that these ~ yeazs aze xepxeaacatLve data far this locale.
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 applfcatfcn to S.TA US's Other mclMes af Xodfue nay be inclxxfed in dose calaQs~ far esse of perfcrmfng calculaticas, but theLr~ ccntrfbutfon does znt have to be included in the SXS IlD zequfxeaents Land Census iufaxmatfon wfllapply to tbe calecxtar year faLLowfng the year that the census was taxen in to avoid splittfng quartered'eca
/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
~
willbe considered.
The cahmlaticn mthods are based ca Secellms 5.1 and 5.2 of HEE&0133, %maiar 1978.
'1he equations are:
Par ZEALMX Ebse Bate n
(QQ)
For ZEAL RUN Dose Rate:
n
[Q+ l,lMi] (gQ)
Qatar zs Fi
~ tatal body dose rate from noble gases in airborne releases (mrem/yr)
~ atdn dose rare from noble gases in airborne releases (mrem/yr)
~ a tmtrlmatiaL1 syahol.to sigrtfy the operaticns to the right of 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 ofQ 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 (~f) can be dezived; Ttds dose factor is in effece a wELghted aerage total body 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 ~ X adn X
ft X 60sec
- sea,
~(U) ft 2.'1 R 1(Ice 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 tbe shyLtQed dose rate caI(morat~ is used (i.e, use of~ to datenaba xelaase rate Hmits)a 2a caIculati(m pzocess of the foUpwing Section (2.2a3) is to be if actual zeIeases of noble gases~ tbe above Lind.t of 3.5 X 10 uCfjsec 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 if the actual zeIeases
~ the value of 3D X IO ~sec 2.2.3.1.2ht (z(@ salus sec/a mst ts ths tuse )tsar(ca sector ac tla etcluslsc ataa (Sea Xsbla tt.l for cetus aoe( sector.)
e 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 fornucHde (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 fmmI & 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 Note 2.3.1.1 Zuhalaticn Dose Rate Method
'Ihe 8-3 dose is calculated as per 2.3.4 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 relearn source activity-aad ajltiplyingit 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
'athway is IR1 + ~ +
+DR for all zaclides except E-3.
Ihis dose rate shall 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:
2A 2 1
'I!zithm dose via the gmuad plane is zem.
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 activity aad multiplyingit 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 ejr:
liF 8'rea
'Ihe Ibse Bate to organ T fmm 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:
2DB 1 E-3 dose is calcul.ued m per 28.4, The canca~ag aaizjal ms established as a mlles.
'Ihe
(~D for this location is 2,
1/m 'his value is caaxxa to all auclides.
Tl
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 anltiplyingit by the pmduct of 2DD.2 (nuc1Me [iJ as
) uCL X
(value 2.3Dc2) cc 2.3D.4
~/sec for nuclide (i)
Obtain the g valne fzzmi Table CHi(7) (wtr49mver is the ccatnQling
~, ~/Imt, for~).
If the limLted analysis appmsch is being used, limit the cahularbn to the infant thyroid.
Salva for~
DOLT ~RiT (D/Q) Q ~
mzearm -sec X
1 X
uCi aF sec 2.3B.6 2DD 7 rR
~
mzem/yr the Ibse Hate-to organ T fmai nuclide (i)
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
~ pathery is:
fftfn~
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:
2.3.4.1
'Ihe controlling locations sad their (@
values for each pathway are:
Tnbalatian -~ at range in the sector ~
(O'Qn sec/aP (See Table 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 ft/i'fthe release source and aavert it to cc/sec, 2~3i4i3.Mie for ~3 for Tr~q bF aug the nQJcc assay value Qf release sou:ce, and cultIplylngit by the 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 Q )Gras~/Gast ~
&6(7)
. m.4.5 Solve for ~3 (ma~) mung am (@'q)D forma~ aaa 2 3+4ol'nd RR 3 (InI~lstice)~ ~~4 4~
-~3 (WeD q 3 h
'r@EL T 2 3i4'6 Solve fof~3 (Grass-
~) using tb(~q)'or Gcass-
~ gama X3.4 1.snd
~3 (G
~) f ZZ.4.'4 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~ organ T af interest 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)
Ground PL. (XMP),
(T.
anl )
)
Gz- ~ (ZaaCe)
Tzdmlat1ca (H-3)
Gi. ~ (B-3)
(aua of above)
? 3.1.7 2.3.2 7 2 3.3.7 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,
'xovlded that the appzoprLste vatue of (~ is used as outlixed in the detaQed ezplaaatian that fhUans ~ equal~ for yeas air dose is:
3 17, X'10 ML.(X/Q) +,
~ gmma air dose in mzad fzcm-zadiaactive aoble gases.
~ Axath.aatical syahol to idgpdfy the apexaticns to the~ side af the symbol.axe to be pexfoaxxk for each,nuclide (1) thzo~
(n),. a@i:sumed'to ardve at-the totaL dose, fromall auclides zepoxted duxing, the, interval ; No unLts apply K
t
'.,g>>~>>>N~r,"'~R>jg>> 'A>>g,'i>>p 0, +p>>, i$ir>> ',
~
>>q'>>>>>>; ~,
~,
gg4P~>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) 2 5 (anil) v 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 air dose for the pathway is detezmined hy suamizzg the Di dose of each auc1Lide (i) to obtain~ Axe M-D1+D2
+R -~
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 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 pear 2m foll(~g calculzztion~ 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
%BECr0133, R)md)er 1978. ~ 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&&LBsud 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~
3.17 X 10 Bl (Ã7@0))L T
/
For. Gm(md PLaoa or Gee~/Gast~
07&gcp 3.'l7 X gf
(~D T'
I i,
For each patsey abc'exctudix)g,Gmund PLane) For TtLtizxa:
3.17 X 10 Bg.gf (Z)0))t)L For Total D()se fxaa PartLculate Gaseous effluent to organ T of a specified age gzoup',
- f ZggP+~3l'-
/'v
~
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 willbe < 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 tl during the the inter'.
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 ~ gmup is chtexmhecL by. anndng tbe Di Dose of each nuclide (i)
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 ~
LUGIE PLANT CHEMISTRY 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:
2.6e3 1
? 6Q.2 2 6DD TrLtium dose is calcuIated as par 2.6e4 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@,
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~..
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 2.6B.6 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
determined by au(naing the IK dose of each nuclide(i).
~ (or ~<)
~
D +++
+Q
~
mzam lhe etee te ecch ctNe e(mle he celcclecai la the etta taetat elth steps 2.6e3a2 through 2e6e3e6 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 (~3) for tha oem 'C of inzezest fzcm tbe Table spectiKed bhaga 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 Dtt 3 ~ 3.17 X 10+ 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-
~
~
Inhalaticn (Z&SP)
Gzont Haec (XQKP).
) 'Gzass-
~ (L&8P)
Intalaticm (8-3)
Gzasa-
~ Q-3)
SZEP REF 261.6 (T. Body M. )
2.6W6
?637 2.6.4D 2.6 4 5 Sum of Nave
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 SIEt3tH (XHEBAIDR BURIN HEIEASKS Eh'AKB MKQQZ QRPOSZIE
~KLY lCMHIZQMBSZK TYPE VF ANALYSIS S~, S~, ~e-55 NIILIPALQkkK RKXXEES AM) DISKLVKOGASES
~, S~, F~5
~h.a GP Dn CAn 6 LS LDaPa CA. 6 LS TENEZ NEATEST:
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 Week1 Monthly Coaposi.ta (PartinQates)
Qusrterly Coayosite (Partiailates)',
,h a LSn Geaxua ters G,C,P ~.
a..
P - GD&n CA~ &
LaS G
P L8 CA pahnan GZ.P
- Gasaas Grab Sacple
- Qmeoal Filter Sazple
- Parti.culate Filter Satple
- QmmLcal Separatina
- Gama spectrum pQse beiftht a+lysis using Lithium.Geraanf.mx detectozs.
All peaks aze ideneiQed and quantified
- 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.
All1fcpdd releases aze sumarLned in tables B.
Gasecus 1.
Nuaher of batch releases:
20 30 4.
50 Total time perLod for batch releases:
tkacLmu tiaa perLod for a batch release.
Average tiua perLod for batch releases:
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.
A des~eLca of the event and ~ant involved 2.
Cause(s) im'im unplanreC release.
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
'ammy, moor -
/
/
~ma
/
QXLEES BELEASED~
I-131 I-133 Q-187 NP-239 Qi-137 Bk-140 (Z-141 FEZ 3 4:
KMXMXU
~nz 0 E
E F.
E E
E F
E E
E E
E EI E
E E
E E
E E
E E
E E
E.
F E
K S ME gl!SXIR t E
E E
F E
E E
E E
E F
E E
E' E
.E E
E.
E E
E "E
E E
K E
E'XQHD E1KllMS (EfhHPfZ ERST)
BhKH gl!RIOR ii E.
F.
E E
F E
K K
E E
E E
E E
E E
E E
Page 44 of 80 ST ~
LUCIE PLANT CHEHISTRT OPERATING PROCEDURE NO C-200, REVISION 4 OPPSITE DOSE CALCULATION MANUAL (ODCM),
sr. mm mtrr 0 mCmmlALam'.
/
/
mmXa
/
/
TAEZ 3,4:
LIQK)EFHIJMS (coaehuxl)
E, E
E E
E E
E E
BhKH CjaKIEE d E
E E
E Xnu. Za amain (mm)
Cr E
E E
E ZE-Q5
~ mcIides Ct E
E Ct E
CZ E
E Cj E
E Cj E
E Ct E
E that tats dstsossd should ha ajdsd to ths psttjat ljst ElEIDLPQKR & IZQK QHPAFL SZ, Ill%MT 0 TAEZ.3a5 LIQGD EPIIlMS-MSE SHHAZEN E
E E
E E
E E
E E
E E
E of Ctt sssspls fottsa.
P@ Gmuy Idun Ezpoaxee XatmaL Pnxa LoaxtM:
Jqy kh1t
Page 45'f 80
, ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITE DOSE CALCULATION MANUAL (ODCM)
HlRIDAPSKR & 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
?
Avazage Release Rate for Ehzhd 3a, Gzoss Alpha RadioactivLty D
TcUCbxL 1
Total Release 2.
kazage Release Rate for PerM E
E E
HlRIDA PNER & LKHZ QMPALC'Z IIXZE UNIT 0 SmIANmu. mme -
/.
/
AX@
/
/
TMZ'3 7 @GRUS EFIIllBGS - QKSM),INEL HEIZASES (1KkKZEEL)
(XMBUXSMXE MZ gllllVIR0 glMZLt 1
Hsstaa Gases.
Ak&1 CZ E.
X-133 ZE-034 XE-135 XE-UR XE-138 UNIDENZZPXED KthL PQR PHGGD QME)
'Z E
E E.
E E.
E E
K
Page 46 of 80 ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFPSITE DOSE CALCULATION MANUAL (ODCH)
HSHZM PSZR h EX'MPML'r.
re uN1Z t SBKhNMIALHEPOHT -
/.
/
THEIXK
/
/
TAHE 3 7:
GhSKUS E%uHMH (coadmed)
I-13L I-133 I-135 E
E 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 ~
LUCIE PLANT CNEMZSTin OIERATrNG PROCEiURE NO.
C-ZOO, REVZSZON 4
ORFSXTE DOSE CALCULATIOH MANUAL (ODCM)
NR QSlP:
Sr. mr@ maT 8 TAHR 3,8 GASMS ERHIINIS-lX5E SlRMXON QINKRf INFANL EKK68K IMBLUAL! MH
'QMmi PlQlÃf
) Ground Plane (A)
)Grass-
+Oak (B)
~~a (A)
)
IIAL HSg (mrem)
- LXMM, (axes)
(mme)
(mrem)
Ul%
(mrem)
T BMf mxem)
) (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)
Te-13
'1h-131m Te-I31 Te-132 I-Q)
~
I-132 I-133 I-134 I-I35 Cs-134
~136 Cs-137'h-138 Ba-139 Be-140 Be-14l.
Ba-142 Ia"140 Ia-142.
Ce-141.
(h-143 Ce-144 Br 144 W-187 Np-239 2 E-5 3 5-3 3 EH
.6 E-5 3 EH 6.E-5 2 Zr5 1 &4 9 Pr4 4 E-5 3 E-3 Nue 8 &5 1 Er4 1 &5 3 E-S 8~
1 E.-3 3 Er5 2 E-5 1 &4 1 &4 5 &5 2 &4 use the aust.
TahLe II, Cotunn 2.,
N Zdel MPC (~a)
~~1 MPC (m/W)
~B-3 E-3 I-K St-24 3 E-5
~hL P-32 Z~
T&l Cr-Sl 2 E-3
~2 Sr-54.
- l. Er4 1EW 8~
Pe-59 5 E-S
~5 Co-57 4 &4
- ~7 Co-SB 9 E-5 3 &5 HL~
1 Er4
~
'Ih-101 2 Er4 Bn-M3 2kHi5 1 EH Rr-105 zaHB 2 E-3 Bu-1%'
E-5 Ag-110 3~
Sa-113 Nues In-113m Noae Sb-122.
M@86 2 E-S Sb-124
.Noae Sb-125 A@69 Nue
~12'
&6 Te-127jn 3 E"7
'Ie-I27'1 5 E-5 Te-129a 2 &5 SMZ 6 E-5 If a amide is mt listed, refer to 1M?820, ApIeakbc B, and anserwei.ve insotuhIa/sotume MPC.stare. they are @trna in Noae - (As per IK?820, Apperdhc B) "No MPC Emit far aoy sbqga Cot listed ebon~ 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 /> "
MPC (uQ./mli 8 &4 4 E-5 Ncoe 2 E-5 3 E+
3 E-j 8 EW
'1 Peti 2 E-5 4 Eiti 9 EW 6 E-5 2 E-5 Nue Ncae 2 E-5 Ncoe Nue 2~
Nue 9 E-5 4 E-S 1 E-5 Rae 6 E-5 1 &4
r 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)
Pap
.> 50 ot 80 0.
0.
0.
l,15&05 8.
0.
0.
3.QR&l 0.
1.785HI2 5.1%H5
- l. 2E~
6.055H12
'QQMOID 3.QE&l 30 0.
0.
0.
0.
3.QEl 0.
1.238HN 2.268Hl2 0.
0.
0.
3.QE1
- 7. 2Pil00 0.
6.01N05 0.
3.QKr01 1.4IEHI3 5.68HHO 2.03$ H5 3.
RKhL MN 3.QR&l 5.596HN 3.17BN1 1.368K5 2.36SH12 1.35BHO
.026HI2 0.l. 2005 0.
0.
0.
0.
0.
0.
0.
.0 1.23K%5 9.43M)l 1
2.155HI2 0.
0.
0.
1.79E~
l.1%t00 0.
0.
0.
0.
0.
0.
0, 0.
0.
0.
0
- 5. 1EHI2 0.
0.
0.
0 0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
1 4.68MO l.
Wl 7
0.
0.
0, 1.6%HO 4.75ea2
~
1 1 01K~
24 1
4.OMN
~2 9
2Yr02 3.86E~
2.9 9.9R&l 8.38E&l 3.0 4.155HS
- l. IlHOO Based on 1 dX/sec xeliase xste of each isotoPe in discharge fbiof 1 cc/sec Mlth m sddltionsl dilution
ST ~
LUCIE PLANT CIIEHISikY OPERATING PROCEDURE NO ~ C-200, Rl5VISION 4 OPPOSITE DOSE CALCULATION HANUAL (ODCH)
Pap '1 of 80 TABIZ b-2 PABQAY SQZ WQK FlSi A% SKiZIhli NR GONER MILT (continued) eeW IMSE mCIIR (Hlegm az m/Ni.)
Y~3 TG-101 AG-110 SS-125 TE12 i TFi-12 8.89BI01 1 6%HS 1
r&1 4,
3.76BHS 1.30E~
1.338r02 8.%MHS 1.59BHB 20 2,2%402 5.
8.
9.
2E 2.
1.416l02 20 0.
0 5.13BOO
- 2. 9&02 9.5K&1 3.67E~
1.93BEQ O.
0.
2.37YiHS
~
E 1
1.9 3.2%Hu 9.65E&1 6.8wl 1.33BHl2 0.
0.
0.
0.
0.
Oi 0.
0.
0.
0.
~ lE 1
1.96El 1.95E~
1.09IB02 0.
0 0.
8.09BHS 20 1 ~ 11BHS 5.57K&1
- 3. 7K&1 1 15E 3.08BKB 0
0.
- 3. 3NOl 1.07BHll
.95BN2 1.285HB 0.
0.
0.
0.
0.
0.
0.
1.$K~
9.82Er03 0.
0.
2.15BHR 20 0.
0 0.
0.
0.
l.
%1 4.896@4 5.
1.59BI04
- l. 1BHS 3.51BHB 2.1 1
0.
1.036H5
.9 7.85BHB 1,95BHB 1.92BHS 6.81BHB
%FAL BODY
- 1. Xz41 2.23&N 2.38BHS
~67K~
3.47BHS 8.1 9.
1 3.47K&1 2.
1
.67K&1 1.$Fr01
~ lBHll 3.
1IBOO 2.01BH2
- 8. 25I02 1.1%SR
~ 2BHll 2 9lN01 1
1.9XWX)
.21E1
- 5. 2BHll 1.24BNZ
,Based oa 1 uCi/sec telease tate of eaCk isotope in discbargp flaw of 1 cc/sec with xe sdditiamQ. dilotLan
ST ~ LUCIK PLANT CHKHISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITK DOSE CALCULATION MANUAL (ODCM)
C
, ~
PaI;,.>52 of 80 wneNNm ~
~
uew PA'QbÃf SALT RGB FIN M) QÃQFl&
NR GNXP AMZ (contiaued) ha8 um FACKR (Nm/IR it@ uCl/Hr.)
GHLX I1 I
132 I
13 2.18K%02 1.07BIOl
~5 1
.57BHS 1.65BHB I
135 2.33BIOl 7.17FiIO2 8.79BHB 3.
2.&5BIOl 1.51BH)l 1
2.83BHB 1.ZVifQ
- 5. lEM 2.07BHS 1.02BHI5 3.76BHB 1.96K~
8.039 0.
0.
0.
0.
5.
.55tBOl
- 2. 1BIOl 9.
1 1.58BHB
.0%HB 0.
0.
0.
0.
2.16BHI2 1.36BHB 3.188r63 1 18BHS 8.2 1
5.36BHS 1~32K~
.88BIO1 3+22&02 2.31BHI2 1 3%901 3.39BHB 1.N&N 1.01BIO1 5.41BHS 2.25&01 2.NK 03 7.88B03 2.3ÃrOl 1.0%HQ i+2%
HA-142 1.73BHS 1.78Fi43 1.58BHS 7.95K&1 0.
0.
1.5Xr63 0.
1.01Fri8 0.
0.
5.83%34 1.09K&1 2.llE&1 9.1 CE-1 1
CE-143 M
187 6.0%r01 1.91Yi42 9.17BHS 2.3
- 4. 7BHQ 1
.RH3 7.68BHS 0.
0.
0 1.9K~
1.9 Wl 1
- 4. 5E~
0 0
0.
0.
0.
.8 1.67E 04 2, 3E~
2.51BHB
~
Wl 4.9~
9.
9.
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)
Ra1Ifde HK (uX/aa>
~l 4'
EW 1 E-7 Ki&6 3 8-7 2 l&B 2EW 3 EW 3 EW 4 E-7 3 E-7 3 E-7 1 8-7 Ru-1%
~110 Sn-113 In-ll3n 2 E-10 3 8-10 2 &9 2 8-.7 1 E-10 1 8-10 7 8-10 9 E-10 TENEZ G-1 IN AIR IN QSEli~KD AHnjS lbc1bh~
HEC (~ac) 7+1 1 &9
~5 1 &9 3 &9 3'~
2 E-7 2 &9 8~
6 Er9 2 EH Te-12ch.
I-130.
I-131 I-'l32
.1 ~
1 8-10 1 8-10 4 8-10 6~l~
4 E-M Cs-136 6 8-9 (h-137 5
8-10E-10 3 E-ll 3 EH Be-ll0 Is.-140 Ce-141 Ce-144 2 E-10 (1) If a mcdade axmeeuatim Is not listai, refer tusatuhle/saMQe to 1K%20, QyexHx B, and use the aast MPC where they are gfvm in Yahle IX, Catuan 1
L
.9V.,
<<AC,
'o;: Ctp<<i<<+g,,*i% 4 r+ '4 r, reer 1'<<rt'+. -W <<..<<<< ii4i>~r '<<'r'r<< f %~rgb<<;
t4p!-.<<"~~!', <W ".,<<.Q,V<<g; <<,t: z""'i! <<i.
l 0-3 1 FACJMS P (I)
'MiZ 65%tCSIS IXIQl
(
. HEAR HR GhSSNS DLi(BARQ'S AGV GAP INFANT@
YR Hm uC1/SN:)
PAINTY QSIMl KA%NS QSAN IQR HCBR ST ~
LUCIE PLANT CllEHISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OFFSITK DOSE CALCULATION MANUAL (ODCM)
Pa~~ 55 of 80
.51 (0-57 6.68N06 1 199 3.925HS 1.64BHS 5.27BHS 5
6.875HS 1.296N7
~0 5.94BN5
- l. 3BN6 hQ-110.
SS-12
'%12%
1.955HS 1.57BHS 2.995HS 3.185HS
~NBH8 7.56BHS 2 15VjH36 1 155HS 5.4%807 I
1 1
I 132 I
133 I
135 (S-137 HA-1 0 lX-1 1 CK-144 20 1.785H5 30
. 35N5 3.66E~
2.82BH8 2.1 1.15BH8 2.39BHS 9 525Nl Based on 1 uCi/sec Release Bate of Each Isotope & and a Value of 1. for X/Q, depleted gg and Relative Deposition
/R4
ST ~
LUCIE PLANT CttENISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4
OF1'SITE DOSE CALCULATIOH ttANUAL (ODCH)
Pagi 6.o f 80 Q-4
'1QLS R (I)
GHOUP 0 L HIKE/
'MlJ.
GWtSIDH M.
ITIUH i'sq. >ma HR GASEQJS DISQhlth tlU) ~AMZ& INFANl Yk HR uCi./Sec) 0 MNQY GSUM) PMK DEPC8 QCAH IXSE PACHA (R
51 tS54 m
57 Sly~9 ZRM5 MJ-103
- mlat-S8-12 SB-125 TL'123i I
130 I
131 I
132 ID3 I
13 I
135 CS-137 BA-140 (Z-1 1
CE-144 4.68MS 1.38BHJ9'. 5E~
1.89E~
3.8OWS 2.15Pil-10 7.43E~
9.01E 2.1 Fil04 5.35&06 1.086f06 5.01E~
1.36MB 1.1(H~
4+19E 3.58E~
- 5. 16BI-10 5.988~
2.3%+09 1.55EK6 8.79BH15 3.85BO7 5.53Q06 1.72EW7 1.25M6 2.48E
.5QM5 2.56E+06 6.99E+09 1.49K~
1.03&-10 1.68K%8 l.
&7 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
ST ~
LUCIE PLANT CltEllISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4
OPPSITE DOSE CALCULATION MANUAL (OUCH)
TAEZ 0-5 I)/K )
PA11NAY-MALATI%
AXGAP IN'BQAN MSE PACER QM'YR HR uk'/Ga Mater Pag-57 of UU P
32 GL 51 Y~l 40110 3E129f TE1281
'1E1294 I
130 I
131 I03 CS-136 0,
2.318105 0.
2.068HB 0.
.6 4;318N4 1.328HJI 5.9
'.%5104 1.285HH 9.31FiHH 1.89BHB 2.218l05 4.54BN2 2.218HH 8.028N2
~
1.34504 1 ~ 13Er$2 4.8QiN5 6.855HB 5.7QiHH 2.525N3 1.35BN4 0
4.86BHS 1.2lFiN2
~ 1 8.4QBQ2 1.8 0.
0.
0.
2.73BHH 5 755N2 0.
0.
1.75BHB 5.858HB 1.038KB
.255N2 1.955N2 2.35BHH
~2 1.9%+04 3.025N2
.2.565N4 4.27EKO 1.555HH 1.82FiH5 0.
1AÃd01 0
0.
0.
0.
0.
0, 0.
0.
0.
0.
0.
0.
0.
1.728HB 1,32E&l 1.03BNl 1.538102 5.758N2 3.05BH5
- l. 1E 4.66BHS 4.025N4 0.
0.
0.
0.
0.
KIM 1.885N2 0.
3.99EKO 0.
0.
lo21E 0.
0.
0.
9.485HB 1.35BHH 1.0 2.34FiN4 3 448HB 0.
0.
0.
0.
2.17BHB 8.018N3 3.65BHH 1.0 4.555HB 4.825NR 5.048N4 2.93MO l.1%HB
- l. 85H5 0.
2 52bHB 1 785H5 6.
8.
5.578HS 1.53BH5 2.318HS 1.535N7 2.6
'.818HS 4 77E~
li5QiN7 8.125H5 1.645HS 3IU 4.96BN5 1 685H5 1.8%Kb 0
0.
0.
1.0l8N5 2.1QiHB 1.64FiHS 5.24bN5 1.275N
~MH02 1.518N4.
5.81M@
3+2%@4 5.5CBHB 3.285!04 9.
6.8QiN4 1.395H5
~ 1 lA18N4 1 218N4 1 76BK6 5.298N4 2.23Erl04
~11BN4 1.36BN4 2.62BN4
~3 1.35BHH 1.0 1 76E&1 1 37bHH 2.048HH 3.885HG 2.06BN4 la615H5
'1UZhL MR
~3%HI 8,785HB 1 755Nl lo854HB 1.18BN2 1 178HB 8.1 1.248HH 8.068H5 1.6QiHH 1.95BHH 3.371802 5.855HJl 1 148HB 1.048HB 8.4QB03
- 2. 178HH 2.3
'.16BI01 2.745N2 24 9i258N2 20 5.87BHB 1 NBN2 7,325N4 1.955N4 2.955N2 1.81IHOZ 2.495N4 Based a> 1 uCL/sec Release Mate of Bach Isotope ln and a Mme of l. for Zlg, dayleted Qg and Relative Deposition
ST ~ LllC IE PLANT CllEMISTRY OPERATING PROCEDURE NO C-200
~ REVISION 4 OPFSITE DOSE CALCUL'ATION MANUAL (ODOM)
TAEZM BSIBD8%5EA1 PAQMN-DSE GINhIQN PACKtIS R(I)/P(I) HR GAS1%1$ DISIlSNRS PAIlQAY-GRIS HQX (OMMHINh'W)EBLIS)
AZ QMP 1%atK QEAN IXSE PAf:8R
( '
HEIXR - MIIH4/YREtk ulX/Sec P
32 RU"106 hG IO SS-124
&12M TE1291 I
131 I
132 I
134 I
135 K-141 1.82BI.10 0.
3.17BN7 0.
0.
1.46BH8 0.
1 47BI.10 1.65Ml 2.12BI05 5.49BH5 2.01BH5
.21BI0 2.75BI07 3.59LKP 5.548%7 5.8 2.59BH8 1.71&01 0.
2.78BHS
+10 2 45BHS 2.65BH5 1.14BH8 0.
7 52EKl 1.38806 8+73BI07 4.65PiK8 2e77PiH8 0.
9.41BI04 2.47BH5 0.
5.19BI05 3.2 1,9XKI7 3.09BH8 4 76E&1 0.
.9
'+10 l.1%H8
.21E+10 2.47BH5
'1.6~
8.29BI 0.
1.8%I04 0.
0 0.
0 0.
0.
0.
0.
0.
0.
0.
6.64BI04 2.9%K6 1 79BI07 2.21BHS 9.94E+ll 6.26BI01
~
0 1.06E~
0.
O.
0.
0.
0.
0.
6.72BKO 0.
0.
0.
3 llBH8 0.
0.
0.
1.86BI04 4.3SI04 1, 13BHS 0.
3.96BI06 2.lXSKS
- 2. GB 7.74BHS 7.58El 0.
6.11BHS 3.
1.22BI04 9.726HB 20 0.
4.04&%
2.09BHP 0.
0.
0.
0.
0.
0.
0.
0.
- 2. 13BI07 2+83BH8 0.
0.
0.
O.
O.i 9.
8.37BI07 8.
1.51BI05 O.
~3 2.05BH8 7 66BI06 2.48BHS 3.46BHjl 2.16BHS 2.9%HB 5.45BHS 2.75BHS 1.61BH8 7.47hI07 1.98BHS 1.56M5
. 5BI.10 7.78BHS 2.43BHS 3.24BHS 1 16BHS 0.
1 25BKS 1.86BHS 8.136HS 7 87BI07 8.6 7,05BHS 3.058%4 2.86'.27IB06 2.INBN 2.1%H8 1,29BH8 4,2UB 10 5 056bI04 1 45E~
2 46BI04
~ BIO 1,0%H)7 6.62BHI6 7 38BI06 8.95IB0 1.81BH8 1.698%1 0+
~ 14BH8 1.27BI0 1.%ht04 IIased m 1 F1/sec IIelease Bate of Eadem Isotope fn and a Value of 1. for X/g, depleted N/Q and Helative Ueyosj.tfan thee:
'Qm units for 0 14 and Lt 3 are (MIX~Ver uCI./(h. Heter)
0.
I ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 4 OPPOSITE DOSE CALCULATION MANUAL (ODCH)
TABlZ 0-7 K )/K >
PANY GNS MEK (GKEhHINfXHDHNNR)
NR GAP INANI.'BQhN USE EhCIIR (Sg. MEHK -MK~HR uQ./Sec) 2.1
~'~
- Pay,
~>59 of 80 P
32 2 196l.10 0.
0.
4.125H5 0.
0.
1 378H8 0.
9 786H5 3.
0.
2.196HB 0.
0.
0.
0.
8.0 3 2IFiN5 0.
0, 0
0.
.855HB 0.
2.7N5 0.
2.46BH8 9 1~
3.296H5 3,236H5 3.665HB 2.058N5 3.726H5 2.728N5
~ %H5 RU- 03 kG110 0.
1.76BHS 0.
3.0%+10
- 9. 45HB 2.548l04 6.595N4 9.
2.4 1.058N7 5.578HS 0
0.
0.
0.
0.
1.136N4'.
2.9 0.
0 0.
0.
0.
0.
3.326HS '.
0.
0 0.
0
.2.235HB 5.815HB 5.046HB 1.366N7 0.
0.
0.
0.
0.
0.
0.
0.
0.
0 0.
2.595Nl 3.51BHS 6.
5.77E~
-3. 55H8 8.955H5 2.378N7 1.876H5 2.818H8 2,51BN7 2.526HS 1.556HS 8.875HS 8.835l.10 20 6.67N03 1.755N4 2.965HB 4.1%HS.
SN-12
'IE125 I
130 I
131 I
132 I
133 I
134 I
135 Bk-1 0 CE-141 CE-144 2.1 3.39B06
~318
.896N 6.648H5
.056N7 3,11E409 2.13&01
~5GBO 0.l. %l04 1.3 11 8.348HS 1.935l1 1 2.956N7 3.1 EKA 2.526H5 6.2m4 3.9 2.31BH5 2.
3.7%H8 5.71E&l
~ 5 0.
4,7'.395l-ll 3.298H8 2.165l.l 1 2.96M%
1.95@%
9.958H5 7.97BHB 3.5
~2 2.155H5 2.668N7 1.195l.12 7.5IBNl 1.5 10 1.27' 186H5 0.
0.
0.
0.
0.
0.
Q.
8.
2 4%N7 9 1CR&l 1.5 0.
1.
'rl.lO 1.836H8 1.1(&10 l.178HB 6.MB04 2.565N6 0.
0 0.
0.
Oi 0.
0.
0.
- 2. ZE1 2.
10 2.518HS 2.61E+10 1.8 0.
0.
9 338N7 2.9 9.
3.885N7 1,396HS 1.07Vr41 1 ~ 1 0.
5.296l04 3.748HS 5.59M8 9.766N5 9.448N6 1.045HS leXBHS 2.5 8.855l05 lo078N 2,17BH8 2.03E1 1 9%N 0
10 2t37BH8 1.248l-l0 1.5 2;286HB 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 (Allgss Pathzays)
(3)
Gtoazd Plane LIMZIXHrSEGER (N) sec/nP (E7@
1/zn )
0+97 B
1.3 X 10
/ / / / / /
Qarterly for Semfaazneal 1 days IlX),
Qtr. yearly IlD, 12 ccxaenztive math IQ) 0 97 0.9 0 97 0.97
///////
8DX 10 B
1& X10
//////
/////// 8.2Xio~
(6)
(A)
Q)
Over land azeas caly To be detezmtzzed by rachcticzz of actual net data occurring during each ~zrter Por Tritiumin 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 CAIQifAIXCN I
I/3i Ihys - GD LIMITIMr LIMZEING D Q) Value RAMZ SECKR 1/m A
A B
B guarterl Yearl - UD B
B 8
B B
B C
C C
A ihe mzst car or goat as per locations from land census. Ifno 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.. (Ifxn 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. Ifboth 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.